IR 05000518/1981009
| ML20009D848 | |
| Person / Time | |
|---|---|
| Site: | Hartsville  |
| Issue date: | 06/21/1981 |
| From: | Cantrell F, Cartrell F, Swan W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20009D840 | List: |
| References | |
| 50-518-81-09, 50-518-81-9, 50-519-81-09, 50-519-81-9, 50-520-81-09, 50-520-81-9, 50-521-81-09, 50-521-81-9, NUDOCS 8107240414 | |
| Download: ML20009D848 (6) | |
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L NITED STATES
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"h NUCLEAR REGULATORY CUMMISSION U
E REGION 11
101 MARIETTA ST., N.W.. SUITE 3100 e,g
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ATLANTA, GEORGIA 30303
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Report Nos. '50-518/81-09, 50-519/81-09, 50-520/81-09, and 50-521/81-09 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 3740'
Facility Name: Hartsville Nuclear Plant Docket Hos. 50-518, 50-519, 50-520, and 50-521 License Nos. CPPR-150, CPPR-151, CPPR-152, and CPPR-153 Inspector:
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W. B. Swan / SeniopResiderit Inspector Date Signed Approved by:
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F. S', Cantrell, SecWo6fhief, Division of Date S'igned Resident and Reactor Project Inspection SUMKARY Inspection on May 1-31, 1981
/.reas Inspected This routine inspection involved 101 resident inspector-hours on site in the areas of safety-related piping; plant B extended shutdown; A-1 steel containment; A-1 biologic shield wall around RPV; A-1 drywell wall; A-1 fuel building shipping cask storage pit; open items and independent inspection effort.
Results Of the eight areas inspected, no violations or deviations were identified.
I G107240414 810624 PDR ADOCK 05000518 G
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DETAILS 1.
Persons Contacted Licensee Employees
- R. T. Hathcote, Site Project Manager W.-T. 'Quinn, Construction Engineer; Acting Project Manager R. E. Young, Assistant Construction Engineer, Project Engineering J. T. Dorman, Assistant Construction Engineer, Quality Control H. S. Sheppard, Assistant Construction Engineer, Quality Control P. F. Gillespie, Suparvisor, 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
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R. E. McClure, Unit Supervisor, Mechanical Quality Control Other licensee employees contacted included document contr>l personnel craftsmen, QC technicians, and project engineers.
- Attended exit interview 2.
Exit Interviews The inspection scope.
"r. dings were summarized with the Site Project Manager on May 8,15, 29, 1981.
3.
Licensee Action on Previous Inspection Findings (0 pen) Infraction 518, 519, 520, 521/80-18-01 Failure to Take Timely Corrective Action on Drawing Control Findings (Reference 50.55(e), Item 518, 519, 520, 521/81-03-03 Deficient Drawing and Document Control). On May 12, 1981, the site QA unit reported a sampling audit of drawing - control had been completed. Of 200 prints checked, one discrepant print was found. The licensee plans to perform a 100% audit in June 1981.
This item remains open until adequate drawing control is verified by follow up on QA units audits and this inspector's confirming observations.
4.
Unresolved Items
. Unresolved items were not identified during this inspectio, _ -_
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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 u.-d facilities.
The inspection was concentrated on Plant A power block structures, but included outlying structures such as the Plant A essential service water pump stations and earthfill for the spray ponds.
Opan Site Items Control: Nonconformance Reports (NCRs), significant Quality Control Inspection Reports (QCIRs) and QA Unit audit findi'ig were reviewed for pertinence to the inspection program and for adequacy of corrective actions.
Fontainment Erection: The inspector inspected fit-up of the eighth ster.1 ring of the A-1 containment cylinder wall. Joint talerances were being assured by the steel strap inserts, and preheating was established for welding and weld repair. During this inspection period, installation of the vendor fabricated equipment hatch frame assembly into the A-1 steel containment was performed.
The inspector inspected the fit-up operations and inspected the welding of stainless cladding on the horizontal seam below the hatch. This work was controlled by a sketch,page 5 of Work Pack r DC-MI, Welding Procedure SM 11-B-9, C.
F.
Braun Drawing S-089, and Specification 300-13, and ASME Section III Subsection NE.
In the areas inspected, no violations or deviations were ider:tified A-1 Biologic Shield Wall: The inspector found that concrete fi?llng of the annular space in the radiation shield arcund the reactor pressurt vessel had been completed. The inspector inspected the welding of the s+ el capping plate at the top of the shield wall (elevation 50' 4") and vi fied that the shielded metal arc procedure SM-U-8, dated 5/7/81 was bei.1g used, and that the correct 1/8" electrode was being used on joints one inch wide, beveled 10 degrees, as shown on Industrial Enginearing Works Drawing 820 117-00-021, Rev. 6,Section F.
No violations or deviations were identified in the areas inspected.
A-1 Drywell Wall:
The inspector made Mspections of rebar placement, cadwelding of rebar joints and the placement of steel penetration frames in the A-1 drywell. ' The inspector inspected the installation of the concrete forming for placement of concrete in a 210 degree segment of the drywell to elevation 12' 6"; and also observed the checking operations to verify the pas,itioning of embedments tnd the cleanup prior to coner M z pouring.
Progressive signoff of the pour authorization was verified.
(Refer to paragraph 8 for controlling documents).
In the areas inspected, no violations or deviations were identified.
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A-1 Fuel Building Shipping Cask Storage Pit: For the placement of concrete for this pit, *he stainless steel liner was preplaced and used as the inner form.
During concrete placement, the displacement of temporary caulking permitted grout ta enter the vertical leak chases behind liner welds.
The bettom horizontal. leak chase was plugged effectively blocking gravity flow of any future leaking liquid to a sump.
A Nonconforming Condition Report (NCR) was prepared under which the stainless liner was removed to expose the blocked leakage channels near the bottom of the pit.
The inspector inspected the exposed blocked channels and the start tif clearance operations. The inspector had reviewed the NCR, discussed the matter with the project engineers and found the proposed corr.ective actions acceptable.
The Construction Engineer had referred this problem to General Electric.
This problem was judged nonsignificant and determinea to be nonreportable under 10.CF,R 50.55(e). Additional inspections will be made as the work progresses.
In the areas inspected, no violations or deviations were identified.
Trenching for the installation of piping south of the A-2 essential service water pumphouse involved rock removal by blasting. Tne inspector inspected blasting operations and timing, and verified that ad;quate meatures were taken to protect newly placed concrete in the pump house, the nearest structure, as stipulated in Specification N6C-875, Earth and Rock Foundations and Fills, Section 4.2.1.3, Blasting During and After Placement of Concrete, and PSAR Section 2.5.
The inspector inspected the placement of a fill concrete pad, over the rock excavation which will serve as the base for the foundation of the valve
" vault" ctructure for the A-2 spray pond, under the provis;ons of sub-section 4.2.2, Foundation Treatment, Specification N6C-875.
The inspector verified compliance with QCI C-102, Foundation and Fill, Earthfill Control Testing and with Section 4.2.2 of Construction Specification N60-875, Earth ar.d Rock Foundations and Fills.
In the areas inspected, no violations or deviations were identified.
Review of Revised Procedures:
The inspector reviewed revisions to the following construction engineering proceoures:
Revision 1 to CEP 3.02, Configuration Control for Drawings Revision 13 to CEP 4.01, Procurement Document Control Revision 7 to CEP 15.03, Control of Nonconformance Reports Revision 4 to CEP 17.01, Quality Assurance Records The revisions addressed the system configuration control drawing lists (SCCDL). and drawings; quality control of field procured items; clarifies the determinations of "significant" conditions adverse to quality and imposes
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detailed responsibility on the Documentation Control Unit to insure completeness of stored quality assurance records.
Revisions to these procedures ' are governed by CEP 5.01, which established the method and responsibilities for review, approval and revisions of CEPs.
In the areas inspected, no violations or deviations were identified.
6.
Licensee Identified 50.55(e) Items a.
Previou21y Identified Items -
(0 pen) 518, 519, 520, 521/80-10-02, Design Deficiency of T-Head Section of Anchor / Darling Gate Valves (NCR-6). TVA's Architect Engineer, C. F.
Braun Co., rejected the vendor's proposed modification to the valves.
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Deficient valve disks are to be replaced by new disks and cast to the proper configuration. The NRC inspector was informed that seven valves were returned to the vendor and that the other seven are being held in the Hartsville warehouse, pending final resolution.
(Closed) 518/520/80-27-02) Inadequate Wedge Bolt F.xpansion Anchors by Rawlplug (NCR HTM-COB-8002). The licensee has determined that one-inch anchors are adequate for STRIDE supports already installed. Rawlplug anchors are inadequate for certain STRIDE pipe systems and for TVA
- designed systems in balance of plant (B0P) structures. The inspector has desermined thtt one-in.ch Rawiplug anchors have been removed from stock.and are isolated pending a resolution to scrap or ship them off site.
7.
Plant B Construction The inspector inspected preparations for placement of concrete to protect rebars and containment anchor bolts at the base of Unit B-1 containment during the_ indefinite suspension of construction. The completed placement and curing operations were inspected. The inspector made an inspection of concrete flaw removals throughout the B-1 complex and the preparations for patch repairs.
The controliing documents are C. F. Braun Specification 300-01 Concrete-TVA STRIDE, and TVA quality control instructions C-201 Concrete - Concrete Placement and C-208 Sampling and Testing of Plastic Concrete which appear to be adequate to protect the rebar, chair welds and
.and anchor bolts from corrosion.
In the areas inspected, no violations or deviations were identified.
The inspector has determined that equipment being received is stored and provided preventive maintenance under e:.isting requirements and p ocedures.
ENDES personnel have been reviewing existing procedures and requiraments for long-term storage. A number of new procedures are being developed.
At present, Standard Operating Procedare SOP-58, R2, dated 10/14/80, Periodic Inspection of Delayed Portion of Plent B is used as a base for cortrol and
.pi:nning of site protective meausres. These measures are being periodically
- audited by the site QA Unit.
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The inspector inspected reactor pressure vessel X-21 for Unit B-2.
It had been placed on rollers by CB&I preparatory to inspection of its exterior by GE-ISI. The inert gas blanket in the RPV has been maintained. A memorandum to the senior resident inspector dated May 21, 1981, from the assistant construction engineer, site project engineering, stated in part:
"During actual ISI, GE has verified that there will be no need for entry inside the RPV.
GE is also preparing a letter allowir.g us to deviate from their storage requirements until completion of ISI inspection and removal of the rollers. Adehumidifier will be installed to maintain the proper internal atmosphere.
There are,o plans at this time to store Plant B vessels vertically. GE has deteimined that hurizontal storage for an extended period of time is acceptable and that no excessive internal distortion will occur".
In the areas inspected, no violations or deviations were identified.
8.
Siesmic 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 bu' icings, and essential service water pump nouses. Specific placements inspected included pour A2KESWPS 85 and 86, consisting of 340 cubic yards for the main floor slab on the A-2 ESW pump station; curing of pour A-1-A 59 and 60 for the floor slab on the east side of A-1 auxiliary building at elevation 28';
preparations for placement of the A-1 control building decking at the same elevation; and forming for placement of the steam tunnel walls to 50'
elevation. Additional inspections were made of installations of rebar for the foundations and sump areas of emergency diesel generator buildings at the. south sides of Units A-1 and A-2.
During inspection of activities'for structural concrete in these areas, the conformance with the equirements of C.
F. Braun Specification 300-01, Revision 8
" Concrete, TVA Construction Specification G-2, QCI C-201, d
Rev. 4, and CEP 9.02, Revision 5, was verified.
In the areas inspected, ao violations or dev':tions were identified.
9.
Safety-Reiated Piping - Observation of Work anu Work Activities During surveillance tours in the Plant A fuel buildings, auxiliary buildings
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and radwaste building, the inspector made inspections of the fit up and
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tupporting of safety-related piping. For a more htailed inspection of the ccnstruction and quality control of a specific sy: tem, the inspector chose the Unit A-1 main steam line which was under installation to the reactor core isolation cooling (RCIC) tu"bine in the low pressure core spray (LPCS) pump. room in the bottom of the auxiliary building.
Installation of the main steam line in various sizes and elevation 6' in the pipe chase in back or the pump room.
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The principal controlling specification of this line and other STRIDE systems is C. F. Braun Specification 400-15, Rev. 3 Field Fabrication and Erection, ASME Section III Piring, TVA STRIDE, supplemented by TVA HNP Standard Operating Procedures 50P-27 HNP ASME III Piping Program and SOP-31 Control of Weld Maps and Fabrication / Installation Sketches; and by Quality Control Instructions QCI M-230 Piping and Pipe Sleeve Inspection and M-305 Surface Cleaning of Fluid Handling Systems.
The installation and control of the section of the main steam line was initiated by site mechanical project engineering and Work Package No. MA 06-M6 which defines the scope of the work, lists material status, prerequisites, instructions / precautions, control documents including weld procedures, isometrics, C. F. Braun drawings and specifications, pipe spool numbers, and supplemental instructions.
The work package provides the necessary instructions and details for the craft and QC personnel to perform their respective jobs.
50P-27, paragraph 5.0, requires that Sequence Control Charts (SCC's) be initir red by project engineering and that QC is responsible for approving the SCC, coordinating the SCC with the ANI and s'.pplying the SCC to craft personnel.
The inspector reviewed SOP-27, sections of Specification 400-15, and the referenced construction drawings, isometrics and weld map. Their uses and implementation were discussed with the responsible project engineer, QC inspector and his supervisor, and the craft foreman.
The SCC sheets for this portion of the main steam system were inspected and discussed with QC and craft foreman at the job site.
Pipe spools 17AB-MS 203-2, 3, 4, and 6 wera found to have been installed, and spool 17AB-MS-203-1, field modified, was being readied for welding to the assembled sections.
In the areas inspected, no violations or deviations were identified.
10.
Status of IE Circulars (Closed) 81-07, Cont.o1 of Radioactively Contaminated Material.
This circular is closed for the Hartrville record since no radioactive material-is on site other than in instruments and shield radiographing sources.
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