IR 05000518/1980008
| ML19321A880 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 05/30/1980 |
| From: | Cantrell F, Contrell F, Swan W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19321A839 | List: |
| References | |
| 50-518-80-08, 50-518-80-8, 50-519-80-08, 50-519-80-8, 50-520-80-08, 50-521-80-08, NUDOCS 8007240329 | |
| Download: ML19321A880 (6) | |
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UNITED STATES
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,, NUCLEAR REGULATOHY COMMISSION.
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101 MARIETTA ST., N.W., SUITE 3100 ATLANTA. G EORGI A 30303
MAY 3 01980
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Report Nos. 50-518/80-08, 50-519/80-08, 50-520/80-08 and 50-521/80-08 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name: Hartsville Docket Nos. 50-510, 50-519, 50-520 and 50-521 License Nos. CPPR-150, CPPR-151, CPPR-152 and CPPR-153
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Inspection at Hartsville site near Hartsville, Tennessee Inspector:
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W. 'B.' Swan
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Approved by:
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F. S. Cantrell, Sect ief, RCES Branch Dste Signed
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SUMMARY Inspection on March 31 - April 25, 1980 Areas Inspected This routine resident inspection involved 163 inspector-hours on site in the areas of: quality assurance program review; structural concrete; Unit A-2 RPV storage; steel structures and supports in Unit A-1 and A-2 containments; and outstanding items.
Results l
Of the five areas inspected, no items of noncompliance or deviations were identi-fled in four areas; one item of noncompliance with procedural requirements was found in the area of RPV storage. This noncompliance is detailed in paragraph 7 of the report details.
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DETAILS
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Persons Contacted Licensee Employees J. C. Killian, Assistant Manager, Division of Engineering Construction
- R. T. Hathcote, Site Project Manager L. H. Jacks _
cting Construction Engineer, STRIDE
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W. T. Quinn, Construction Engineer, BOP H. S. Sheppard, Assistance Construction Engineer, STRIDE QC B. E. Huffaker, Acting Asst. Const. Engineer, B0P QC G. A. Gonzalves, QA Unit Supervisor A. G. Debbage, QA Audit Supervisor
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J. W. Davenport, Materials Engineering Supervisor, STRIDE S. P. Stagnolia, Supervisor, Welding QC, STRIDE F. E. Laurent, Principal Mechanical Engineer, STRIDE
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D. L. Widner, Mech. Project Engineer T. O. Wilkinson, Supervisor, B0P, haterials Services W. R. Brown, DEC, Coordinator for Hartsville, Yellow Creek & Phipps Bend Other licensee employees contacted included 8 construction craftsmen, 9 technicians, and 12 office personnel.
Other Organizations W. E. Widner, General Electric Co., N. E. D., Site Manager J. E. Nichols, General Electric Co., Site representative, Mechanical
- Attended exit interview on April 25, 1980 2.
Management Interviews Monthly inspection scope and findings were summarized on April 25, 1980 with the site project manager.
Weekly resident inspector's findings were discussed with the site project
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manager on April 7,14, and 22,1980.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 50-519, 521/80-06-01 Extended Construction Delay -
Plant B Procedures The licensee has issued Standard Operation Procedure No. 58 " Periodic Inspection of the Delayed Portion of Plant B".
This procedure references existing procedures for functions involved in maintanence inspections. It is supplemented by an extensive ' memorandum detailing those portions of plant B in " Mothball" status and existing QCIR's and NCRs which are to be held in abeyance.
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Unresolved Items Unresolved items were not identified during this inspection.
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5.
Follow on Mid Term Construction Permit QA Inspections During this report period the inspector made an interim assessment of the impact of QA-QC related charges which the licensee has made since January 1980. These changes involved personnel, personnel assignments, training, assignment scopes and availability of vehicles.
No noncompliances or deviations were identified.
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Licensee Identified 50.55(e) Items New Items Reported by Licensee (Open) 518/80-08-01 Cracks in RPV Shield Wall (NCR HNP-A-091) Ihree cracks in the base metal in the inner shell plates of the RPV shield wall were found. A section of base metal with a crack in it is under metallurgical evaluation by Singleton Materials Engineering Laboratory. The questioned areas were examined by the inspector on April 1,1980.
(0 pen) 518, 519, 520, 521/80-08-02 Incorrect Root Face on Skewed Cadweld Sleeves (NCR CEB 80-11). The adequacy of welds on slanted Cadweld sleeves is in question due to incorrect root face. The Cadweld sleeves in question i
are welded to drywell - framed embedments and main steam tunnel embedments i
at an angle of 45 degrees. Testing and evaluation arc under way. Results are to be reported by licensee by June 20, 1980.
(0 pen) 518, 519, 520, 521/80-08-03 Wiriag Discrepancies in High Pressure Core Spray Metal - Clad Switchgear (NCR HNP-A-090). On six GE SB-12 auxil-iary switches checked, the date code was either missing or erroneous.
Wiring checks by Hartsville site personnel disclosed wiring discrepancies in the HPCS metal-clad switchgear.
These discrepancies involve wiring terminations which do not match the wiring diagrams, errors on the wiring diagrams, missing wires, mislabeling or nonlabeling of parts or terminations, and examples of discrepancies between bill of materials and installed components. TVA is to transmit a final report on this deficiency on or
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before August 29, 1980.
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Reactor Vessel Installation - Unit A-2 - Observation of Work and Work Activities During Interim Field Storage of Vessel Receiving inspection, storage and periodic inspections for the RPV were subject to the requirements of RIS&PM Interim Procedure Mechanical H-650, Rev. O dated 10-24-79 and entitled Reactor Pressure Vessel (NSSS) - QA ASME Section III MPL No. B13-D001. Preparation of this procedure was based on the requirements of GE-NED Document 22A4645 entitled " Site Receiving and Storage of Reactor Pressure Vessel with Shop Installed Internals - BWR Requirements".
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s-3-The RPV, initial 17
_goated for installation in Unit B-1, was unloaded
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and placed on cribbug under Work Package D528-CI through Addenda No. 2.
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Procedure M-650, Rev. 1, Section B, Storage, Paragraph 1.
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Position - Storage Yard, sub paragraph i, states "The item shall not be stored in areas adjacent to:
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Unpaved roads heavily traveled by site vehicles or other dust making operations - - -."
Subsequent to storage of the vessel, a frequently travelled haul road was-opened to the east and the area has become showered with dust, contrary to the intent of section B, par,1, sub paragraph i. This failure to.
Iow procedure is a deficiency designated as Deficiency: 520/80-08-04 Section C - Preventive Maintenance 3 states:
"For heated vessels, the
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temperature of the heated surfaces shall be checked at three equally-spaced locations at least once a day. This may be done remotely by temperature recorders".
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i Temperatures have not been checked as required by the procedure. This i
failure to implement the procedure is another example of Deficiency 520/80-08-04.
i Hot, filtered air is being blown into the vessel.
The surface areas, volume and mass of the vessel and its contents are so large that, without monitoring equipment, a determination of adequacy of the heating and air movement cannot be made. The direction and volumes of air flows appear to be dependent on leakage through flanges and nozzle caps. The licensee has stated that when the vessel has been entered, no deposits of water have been noted.
The inspector has determined that there is no potential nuclear safety significance discernable from these procedural discrepancies.
8.
Containment (Structural Concrete II) - Observation of Work and Work Acti-vities - Unit A-2 The inspector observed preparations for placement A2R-Db for part of the fourth wall lift in the A-2 containment shield building. The completed pour card authorizing the placement was inspected. Placement of the concrete,
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185 cubic yards, was inspected and proper provisions for curing were verified.
The operations iuspected we te controlled by C. F. Braun specification TVA STRIDE 300-01, which impler ents the PSAR criteria and incorporates TVA General Construction Specification G-2 R2 Plain and Reinforced Concrete, and by Procedures QCI-C-201 to 218, 401, 402 and C. E. P. 's 9.02, 12.01, 15.01 and 17.01.
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No noncompliance or deviation was identified.
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Units A-1 and A-2 - Steel Structures and Supports - Observation of Work and Work Activities - (Except welding other than fitup tacking)
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Two work packages were examined for the Unit A-1 Weir wall stainless steel liner:
W. P. D-022-CI Assemble and Set W. W. Liner Plates controlled shop fabrication of liner sections and their placement in the containment.
W. P.
D0-24-CI Installation of W. W. Liner Plate, will carry through finish welding.
The complete ring, tacked into place, was inspected. The installed vertical reinforcing bars were inspected. The A-1 vent wall internal bracing was obse rved. The wall'is ready for installation of concrete.
The fourth course of the A-1 steel containment wall was inspected during placement and tack welding into place.
Installation welding is now under way.
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The inspector inspected the first ring of the A-2 steel containment wall.
The sections had been placed and tack welded into position in accordance
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with the contruction drawings.
A follow on inspection found that the personnel hatch casing had been tacked into position on the A-1 vent wall in accordance with the instal-
lation drawing; that finish welding is in progress on the vent walls of both A-1 and A-2 and that the top section of the A-2 RPV pedestal has been positioned and is being tack welded to the lower section in accordance with the assembly drt. ings.
Work package D-256-M1 Reactor Pressure Vessel j
Pedestal - Prepare and Pour Pedestal, Plant A, Unit 2, thrcugh Addendum No.
17, and Work Package No. D-260-C1 with Addendum No. 1 Plant A-2 "P/P (Pre-l pare and Place) Drywell Vent Structure" were referred to during the inspections.
No noncompliances or deviations from the requirements of the controlling documents were identified.
10.
Status of OI&E Bulletins j
(Closed) 518, 519, 520, 521/79-B U-25 Failures of Westinghouse BFD Relays In Safety-Related System.
The licensee's letter of January 4,1980, states that "none of the Westing-house BFD or NBFD relays are in use or are planned for use in safety-related systems at Hartsville".
(Closed) 518, 519, 520, 521/80-B U-03 Loss of Charcoal From Standard Type II, 2 Inch, Tray Adsorber Cells The licensee's supplemental letter of April 25, 1980 described a finding of broken spot welds attaching the filter retaining screen to the frame.
Corrective actions are insured through NCR HIN-ED-80-02.
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Status of IE Circulars
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The inspector has determined that the licensee has received and assigned for review the following circulars, which are closed for record:
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(Closed) 518, 519, 520, 521/80-C I-01; 80-C I-04; 83-C I-05; 80-C I-06; 80-C I-07; 80-C I-08; 80-C I-09; and 80-C I-10 (Closed) 521/80-C I-02
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