IR 05000413/1980036

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IE Insp Repts 50-413/80-36 & 50-414/80-36 on 801202-05.No Noncompliance Noted.Major Areas Inspected:Observation of Nondestructive Exam Activities & Followup of Licensee & NRC Identified Items
ML19341C740
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 01/20/1981
From: Bryant J, Vandoorn P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19341C736 List:
References
50-413-80-36, 50-414-80-36, NUDOCS 8103040056
Download: ML19341C740 (5)


Text

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  • o UNITED STATES

' NUCLEAR REGULATORY COMMISSION i O! ~ n ' s a E oio ~ ii [[ 101 MARlETTA ST., N.W., SulTE 3100 o ATLANTA, GEORGIA 30303 9q Report Nos. 50-413/80-36 and 50-414/80-36 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility: Catawba Docket Nos. 50-413 and 50-414 License Nos. CPPR-116 and CPPR-l'17 Inspection at Catawba site near Rock Hill, South Carolina Inspector:h.

. ., b /!2e F/ - P.~K. Van orn* Date/ Signed Approved by:_ e,ar[ /- 20 - // - . Br ant, etion Ch#ef, RC&ES Branch Date Signed SUMMARY Inspection on December 2-5, 1980 Areas Inspected This routine, unannounced inspection involved 26 inspector-hours on site in the areas of observation of nondestructive examination activities; followup of licensee identified items; and followup of NRC identified items.

Results Of the three areas inspected, no items of noncompliance or deviations were identified.

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. - . DETAILS 1.

Persons Contacted Licensee Employees

  • D. G. Beam, Project Manager
  • D. L. Freeze, Project Engineer
  • S. W. Dressler, Senior Construction Engineer R. A. Morgan, Senior QA Engineer
  • L. R. Davison, Senior QC Engineer
  • J. C. Shropshire, QA Engineer H. L. Adkins, QAE Mechanical D. Gadd, Welding Engineer R. G. Rouse, QA Technician V. H. Shellhorse, Design Engineer R. L. Oakley, Design Engineer Other licensee employees contacted included three construction craftsmen, and seven inspectors.

Other Organizations Hartford Steam Boiler Inspection and Insurance Company

  • C. F. Toegel, Authorized Nuclear Inspector J. W. Kosko, Authorized Nuclear Inspector
  • Attended exit interview 2.

Exit Interview The inspec;1on scope and findings were summai hed on December 5,1980 with those persons indicated in Paragraph 1 above.

3.

Licensee Action on Previous Inspection Findings a.

(Closed) Infraction 413/80-10-01 - Undersize Fillet Weld.

This item concerned the fact that a pipe support weld was smaller in - one area than the required 5/16-inch size.

Duke actions have i included reinspection of 396 support fillet welds, included all fillets required to be greater or equal to 5/16-inch.

Seven welds ' were undersize to code (AWS D1.1) requirements.

Design analysis showed these welds to be acceptable "as is" for the intended service. Duke also retrained inspectors concerning measurement of fillet welds.

The inspector reviewed documentation of the above actions and considers the actions acceptable.

l b.

(Closed) Infraction 413/414/80-24-01 - Inadequate Measures for l Storage. This item concerned the fact that valves were allowed to t l be stored temporarily outdoors which is not in accordance with . - -,,

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ANSI N45.2.2 requirements.

Duke has issued Revision 4 to proce-dure CP-371 requiring proper valve storage.

In addition, the responsible craft foreman have been trained in the requirements for valve storage.

The inspector reviewed documentation of the above actions and verified by observation that valves were now being properly stored.

c.

(0 pen) Unresolved Item 413/414/80-24-03 - Chloride Control. This concerned whether ASME Code requirements were being met for control of thread cutting fluid.

Duke has performed a chemical evaluation and determined that material used to date will not be damaging to safety related systems.

Use of an improved material has been impimented via procedure CP-479 for any new threading operations.

It was not determined during the inspection if Duke has addressed the requirement for removal of fluid prior to seal welding per Code paragraph NX-4713.

Therefore this item remains open.

d.

(Closed) Unresolved Item 414/80-29-02 - Mechanical Undercut. This item concerned acceptability of undercut caused by grinding of containment plate to stiffiner welds.

Duke has provided guidance for evaluation and documentation for this condition via procedure CP-64. The areas previously questioned were inspected by Duke and found to be acceptable.

The inspector reviewed documentation of the above inspection, reviewed procedure CP-64 and reviewed documentation of similar conditions to verify that inspectors were aware of requirements.

e.

(0 pen) Unresolved Item 413/414/80-29-05 - Omitted Rinse After Bending. This item concerned control of fluid used during bending of stainless steel pipe. Duke has included control of the questioned material (Triton X-100) in procedure CP-479. However the procedure is not clear as to whether rinsing is required. Also Duke has not performed a safety evaluation of material used to date without rinsing. Until the procedure is clarified and a safety evaluation is performed this item will remain open.

No violations or deviations were identified.

4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Independent Inspection Effort (Unit 2) (Closed) Inspector Followup Item 414/80-29-06 - Unavailable CMTR. This item concerned availability of a Certified Material Test Report for Reactor Coolant system elbow Heat No. 2588-2.

The inspector reviewed the requirements of Specification 1201.00-1 for this material and determined that only a quality release (QR) was required for the elbo _.

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3 The inspector reviewed QR-29384 for the subject elbow and determined it to be acceptable.

No violation's or-deviations were identified.

6.

Licensee Identified Items (50.55(e)) (Units 1 & 2) a.

(Closed) Item 413/414/77-14-02 - Valve operator Nature Frequency.

This item concerned the fact that valves supplied by Fisher Control Valve Co. and Kerotest Valve Co. actually had lower natural frequencies than initially determined by analysis. Action concerning this item have included revising analytical modeling programs to predict frequencies which will correspond to actual test results, redesign of Fisher supplied containment isolation valves, reanalysis of affected systems to determine modification of supports / restraints where necessary.

The inspector held discussions with responsible licensee personnel and reviewed documentation of the above actions.

These actions are considered acceptable.

b.

(Closed) Item 413/414/80-22-01 - Diesel Generator Heat Exchanger.

This item concerned incorrectly installed baffling in two heat exchangers for diesel generators.

Actions included return of the heat exchangers to the manufacturer, correction of the condition and subsequent return to the site. The inspector reviewed documentation of the above actions and considers the actions to be acceptable.

No violations or deviations were identified.

7.

Observation of Nondestructive Examination Activities (!' nits 1& 2) The inspector observed nondestructive examination (NDE) surface inspections of various welds to determined if code and procedure requirements were being met in the areas of use of certified materials, qualification of inspectors, use of calibrated equipment, suitability of surface being inspected, use of proper inspection ?.echnique and evaluation of indications.

The following inspections were observed: Weld No.

Unit Inspection Procedure Code Containment

MT of repair NDE 22, App. N ASME III, NE, Weld D-5-4B excavations 71S72 Fuel Pool

PT of Final NDE 30, App. O ASME VIII, Liner Weld 24 Weld 74S74 Class C Pipe

PT of Final NDE 30, App. J ASME III, 74S74 Weld 1WL1261-19 Weld

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Class C Pipe

PT of Final NDE 30, App. J A.SME III, 74S74 Weld 1WL1261-Weld

Class A Pipe

PT of 25% of NDE 30, App. J ASME III, 74S74 Weld 2NC15-3 final external weld surface No violations or deviations were identified.

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