IR 05000518/1982007

From kanterella
Jump to navigation Jump to search
IE Insp Repts 50-518/82-07,50-519/82-07,50-520/82-07 & 50-521/82-07 on 820503-14 & 21-28.No Noncompliance Noted. Major Areas Inspected:Seismic Category 1 Concrete,Open Items,Independent Insp Effort & Site Deferral Preparation
ML20055A116
Person / Time
Site: Hartsville  Tennessee Valley Authority icon.png
Issue date: 06/17/1982
From: Cantrell F, Schapker J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20055A107 List:
References
50-518-82-07, 50-518-82-7, 50-519-82-07, 50-519-82-7, 50-520-82-07, 50-520-82-7, 50-521-82-07, 50-521-82-7, NUDOCS 8207150491
Download: ML20055A116 (5)


Text

- - . . . - = - - _ _ . . - - . - . . - . . - ... _ - - - - _ _ . ~

-

- . _ - . .

.

.

, . .

c9 #o, UNITED STATES

,

8' o NUCLEAR REGULATORY COMMISSION g e '

REGION il

! 101 MARIETTA ST., N.W., SUITE 3100

{

o, f[ ATLANTA, GEO9GIA 30303

%*****o'

i a Report Nos. 50-518/82-07, 50-519/82-07, 50-520/82-07 and 50-521/82-07

! Licensee: Tennessee Valley Authority

500A Chestnut Street Chattanooga, Tennessee 37401-s Fi. cili tk_Name: Hartsville Nuclear Plant

!

ilocketNhs. 50-518, 50-519, 50-520 and 50-521

,

e License Nos. CPPR-150, CPPR-151, CPPR-152 and CPPR-153 Inspection at Hartsville site near Hartsville, Tennessee

~ Inspector: N

_J. F. Schapker N 0 . 6//7[N Date Signed j ~

/

.

Approved by: W[Ad[

F. S.~Cantrell, Sect Kn p fef, Division of d (, 7[V 2.-

Dyts S.fgned Resident and Reactor Inspection r

SUMMARY Inspection on May 3-14, 21-28, 1982

Areas Inspected This routine, announced inspection involved 74 inspector-hours on site in the 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 i

and A-2).

I ReSJlts Of the 4 areas inspected, no violations or deviations were identified.

t

i I

l

!

l l

l l

i DO Fo!$0g$[g PDR

. . . _ _ _ L _ ___ ._- ._ _ - - _

.

.

DETAILS Persons Contacted Licensee Employees

  • 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 J. T. McGehee, Engineering Management Assistant R. E. Young, Assistant Construction Engineer 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 May 7,14, and 28,198 . Licensee Action On Previous Inspection Findings (Closed) IFI 82-06-01 "Ametek After Cocler Tube Sheet Clad Discrepancies."

Ametek after cooler het.c exchangers referenced in investigative report 99900059/81-02 (Region I), in which allegations that the heat exchangers, which were fabricated with cooper-nickel clad tube sheets and copper-nickel tube to tube sheet welds, "were observed 5y the allegator leaving the shop l with holes in the cladding that could be seen with the naked eye." Two of l the referenced after coolers were opened by the licensee for inspectio '

The inspector with his Section Chief, observed the tube sheet area of the after coolers. Large amounts of corrosion was evident, of which some pitted the tube sheet. No tube to tube sheet welds were present on the two units I observed.

l Further investigation by the licensee as requested by the inspector, revealed the.t the after coolers are designed to the requirements of TEMA Class 3 per C. F. Braun Specification 133-04. The design does not require copper-nickel cladding on the tube sheet, nor does it require tube to tube sheet welds. The corrosion allowance is 1/16 of an inch. The corrosion observed was well within these requirements. The licensee removed the loose corrosion and closed up the af ter coolers for storage. A copy of this report will be forwarded to Region I for informatio . Unresolved Items Unresolved items were not identified during this inspectio . . .

5. Independent Inspection Effort The inspector made 3 surveillance tours during which the status of project work was noted, and construction activities were inspected on nuclear safety-related structures, systems and component The inspections included: E'rth Fill for Plant A Conduit Runs and Conduit Vaults. Placement and

'

compaction of earth fill for conduit run and conduit vault was observed in progress. The inspector verified compliance with specification N6C-875 and with quality control procedure QCI-102, Foundation and Fill, Earth Fill Control Testin Open Items Control: Newly issued Nonconformance Reports (NCR's),

significant Quality Control Inspection Reports (QCIR's) and QA Unit audit findings were reviewed for pertinence to the inspection program

.

!

and for adequacy of corrective action NCR-HNPA-178 was initiated for mislocated holes in high density fuel rack support assemblies. The corrective action taken was to plug the misaligned holes, using compatible material and qualified weld procedures, and redrill in proper locations. The inspector reviewed weld procedures, plug material identification and tracability, welders' qualifications and reviewed the radiographs of the completed weld Review of NCR's and QCIR's did not disclose any violations or unresolved item Within the areas inspected no violations or deviations were identifie . Licensee Identified 50.55(e) Items Previously Identified Items t

( (Closed) CDR-518/82-12 Incorrect Orifice Size In RHR Discharge Line '

Indicated On Fabrication Specification.

'

i The deficiency was a typographical error and was corrected prior to the hardware being fabricated. Specification writers and reviewers were alerted to be more thorough in their review of specification The following interim reports were received on previously identified items. The inspector reviewed these reports and found that none contained information that would permit closure. Follow on reports are I scheduled at later dates.

,

(0 pen) COR-518, 520/82-05; 519, 521/82-04 Failure Of Transamerica Delaval to Promptly Correct Deficiencie Corrective action to be completed by June 30, 198 l

. .

(0 pen) CDR-518/81-27, 519/81-21, 520/81-26, 521/81-22 Receiving, Checking, and Controlling Record Corrective action to be completed byJuly 30, 1982 (0 pen) CDR-518/81-29, 519/82-22, 520/82-28, 521/81-23 Atlas QA Docu-mentation for Auxiliary and Fuel Buildings Structural Stee Indefinite Final report due to deferral of sit . Seismic Category 1 Concrete Forming, installation of rebar, cadwelding, prepouring inspection, place-ments and post placement curing were inspected as work continued in the A plant reactor building, and fuel building Specific placements inspected included: A1F-111 and AIF-69, 70, 210 cubic yards in the A-2 fuel building; and AIR-11E and 11F, 60 cubic yards in the A-1 reactor buildin Preplacement inspection was indicated by the properly signed pour car Placement of reinforcing steel conformed to drawing and procedure require-ment Placement activities pertaining to delivery time, free fall, flow distance, layer thickness and consolidation conformed to specification Activities were continuously monitored by QC personne Samples for temperature, slump, air content, unit weight and test cylinders were made in accordance with procedure requirement Examination of the batch plant and stockpiles showed materials were being controlled and that accurate batch plant records were being generated. Post placement inspection showed proper curing was in progres During inspection 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 No deviations or violations were identifie . Review of Deferral Activities.

!

The inspector toured the site to observe activities for preservation of material and equipment during deferral. Structural steel exposed to the elements is being sand blasted and painted in areas of deterioration or lack of protection. Concrete slurry on rebar is being applied 12 to 24 inches extending from concrete. A containment cover is in the process of being fabricated to be installed over the containment to keep moisture and contaminates to a minimum. Protective measures for preservation of materials are progressing slowly due to construction activities still in progress, and manpower reduction.

<

!

. .

9. Status of Inspection and Enforcement Bulletin (0 pen) 82-01 Revision 1 Alteration of Radiographs of Welds in Piping Assemblie This item will be dispositioned upon reactivation of construction or transfer, sale or other consignment of the subject piping subassemblies to another nuclear plant site.