IR 05000414/1985019

Insp Rept 50-414/85-19 on 850528-31.No Violation or Deviation Noted.Major Areas Inspected:Spent Fuel Storage Racks,Observation of Work Activities,Defects in Girth Weld of Accumulator Tank 20 & Previously Identified Findings

ML20128L535
Person / Time
Site:	Catawba
Issue date:	06/12/1985
From:	Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20128L524	List: IR 05000414/1985019 ML20128L519
References
50-414-85-19, NUDOCS 8507110355
Download: ML20128L535 (5)

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,= UNITED STATES ojks Kioug'e NUCLEAR REGULATORY COMMISSION d

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$ ,j 101 MARIETTA STREET. * '* ATLANTA, GEORGI A 30323

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Report No.: 50-414/85-19

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Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket No.: 50-414 License No.: CPPR-117 Facility Name: Catawba 2 Inspection Cond : Ma 8 - 31, Inspector: ///f '

_ [/ W fod Date Si ned

' Approved by: -/ < - NI p J. f. JWaW 3ectio Enfin 6ering Bran Date Signed Division of ctor Safety SUMMARY Scope: This routine, unannounced inspection involved 30 inspector-hours on site in the areas of Spent Fuel Storage Racks Observation of Work Activities; Over-pressurization and Rupture of Volume Control Tank (SD 414/85-06); Defects in Girth Weld of Accumulator Tank 2D (SD 414/86-C2); Previously Identified Inspection Finding Results: No violations or deviations were identifie "

PDR ADOCK 05000414 G PDR

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REPORT DETAILS Persons Contacted Licensee Employees

• E. M. Couch, Project Manager - Construction

• L. R. Davison, Project QA Manager

• H. L. Atkins, Quality Assurance Engineer

• J. E. Cherry, Quality Assurance Specialist (ISI) Inservice Inspection B. Gillespie, QA Welding /NDE (Nondestructive ' xanination)

J. W. Peace, Weld Technical Support Technicie Other licensee employees contacted included construction craftsmen, technicians, and office personne NRC Resident Inspector

• P. K. Van Doorn, Senior Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were summarized on May 31,1985, with those persons indicated in paragraph 1 above. The inspector described the scope of the inspection and discussed inspection findings identified belo Inspector Followup 414/85-19-01, Volume Control Tank RT Film Sensitivity, paragraph The licensee did not identify as proprietary any of the materials providect to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during this inspectio . Licensee Identified Items 50.55(e) (92700) (Closed) Significant Deficiency ('SD) No. 414/85-02, Defects in Girth Weld of Safety Injection Accumulator Tank 2D. On January 25, 1985, the licensee notified Region II of a 50.55(e) item concerning the discovery of t ultiple rejectable indications in the Safety Injection Accumulator Tank 2D (Tank) during preservice inspection. The indications were located in the shell to upper-head weld of the tank. During a previous

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inspection, documented under Report No. 50-414/85-01, the inspector reviewed in detail the licensee's findings and proposed corrective actions outlined in nonconformance item report S/N 19227, also during that inspection, the inspector raised a concern over acceptability of the vendor welds and recommended that the review of radiographs be expanded to assure that weld integrity meets construction code require-ments, (Inspector Followup Item 414/85-01-01 Accumulator Tank 2D defects). At the end of this inspection, weld examination on the SIS Accumulator Tanks in both Units was completed and the evaluation concluded that except for the aforementioned weld, no other repairs would be required. The tank manufacturer, Southwest Fabricating and Welding (Southwest), had repaired the entire length of the weld in question except for a short length of approximately 5/8 inches which was repaired and radiographed on May 29, 1985. Welding was performed per ASME Code Section III (74S74) and Section IX. Radio performed by the licensee per ASME Code Section V (80W82) and radio-graphy was graphic procedure NDE-1 Within these areas the inspector reviewed process control, qualification of welders / weld procedure (s), filler metal quality records H-3B rod issue tickets, and radiographs for compliance with code and procedural requirements. Following the inspection the licensee's representative informed the inspector that preservice/ ultrasonic inspection of the upper and lower shell to head welds had identified some linear indications in the repaired weld that were confirmed by radiography and may require weld repai b. (0 pen) SD No. 414/85-06 Overpressurizing and Rupture of Volume Control Tank. On April 22, 1985, the licensee notified Region II of a 50.55(e)

item concerning the overpressurization and rupture of Unit 2 volume control tank during cold hydrostatic testin The licensee issued nonconforming item report S/N 1963 dated April 23, 1985 to provide a brief description of the event and to outline the actions required to l remove the damaged component (s) e.g. tanks, valve and associated l piping, and install replacements. At the time of this inspection, the replacement tank had been fabricated and steps were underway to weld and secure the supports to the anchor bolt assembly. The replacement tank was furnished by Richmond Engineering Company (RECO) on Requisition No. 8337 1201.04-00-0023-00 under requirements of ASME Code,Section III, Class 2 (74S74). The inspector observed selected completed welds on the outside and inside of the tank and reviewed radiographs for welds numbered 151, 152, 154, 165, 169, 170, 195 and 196. This radiographic film review disclosed that the code required 4T l

hole sensitivity had not been attained on certain weld locations l

(stations) and thereby the 4T penetrameter hole was not readily discernible. This matter was discussed with the DPC, Level III examiner who agreed to review and evaluate' radiographs and to report back his findings. The inspector identified this matter as Inspector Followup Item 414/85-19-01 " Volume Control Tank Radiograph Sensitivity", until

! the evaluations can be reviewed on a future inspectio .

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6. Spent Fuel Storage Racks Observation of Work and Work Activities (50095)

At the time of this inspecticn work on the spent fuel storage racks was complete and the rack assemblies were in plac Section 9.1.2.1 of the Catawba Final Safety Analysis Report (FSAR)

identifies the spent fuel storage structure as seismic Category I and the racks as free standing, self-supporting, independent modules. It invokes Regulatory Guide 1.13, Spent Fuel Storage Facility Design Basis and the American Institute of Steel Construction (AISC) for design requirement Materials were procured to the ASTM Standards A-666 Gr.A, A-240 and A-276 requirement The following DPC design drawings and specifications were reviewed to ascertain whether requirements and commitments set forth in the FSAR were implemente CNS 1121.00-1, Rev. 17, Specification for Field Fabrication and Erection of Steel Structures....for Nuclear Safety Related Structures CN 1210-5, Rev. 8, Auxiliary Building Spent Fuel Racks CN 1210-13, Rev. 6, Module Location & Orientation Details for Perimeter Cover CNS 1140.00-1 Specification for Furnishing & Fabricating the Spent Fuel Storage Racks The letter specification (CNS1140.00-1) invokes ANSI N45.2 requirements and provides for certified material test reports, deviations, nondestructive examination reports, dimensional checks and bill of materials and drag test results to be furnished by the vendor (Selamco Inc.).

Within these areas, the inspector reviewed receiving inspection reports documented on Form P-1A Rev. 10 and the Quality Records for the following:

5 X 8 All Fuel Storage Module PO# Part # Item # Drawing # Traveler S/N C-66740 CN-1210-5 05 LM-7202-04 Rev. C 100669 C-66740 CN-1210-5 05 LM-7202-04 Rev. C 100670 5 X 9 All Fuel Storage Module C-66740 CN-1213-5 07 ~ LM-7202-05 Rev. C 100673 6 X 8 All Fuel Storage Module C-66740 CN-1210-5 03 LM-7202-03 Rev. C 100651

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t 6 X 6 All Fuel Storage Module C-66740 CN-1210-5 01 LM-7202-02 Rev. C 100239 Within the areas inspected / reviewed, no violations or deviations were identifie . Inspector Followup Items (IFI) (92701) (Closed)IFI 414/85-01-01 Accumulator Tank 2D Weld Defects This item was discussed in paragraph 5 of the repor (Closed)IFI 414/85-01-02, S/G "B" Stub Barrel The supplemental ultrasonic examination of one circumferential weld in each of the four S/Gs was complete. Welds inspected as part of this expanded preservice inspection effort were as follows:

S/G "A" - Tube Sheet to Stub-barrel C1. S/G "B" - Stub-Barrel to Lower Shell C1. S/G "C" - Lower Shell to Transition Core C1. S/G "D" - Transition Core to Upper Shell C1. Upper Shell to Upper head C1. Following this inspection the licensee informed the inspector by telephone that the tube sheet to channel-head weld inspection from the primary side had been completed. In all cases reportable indications were documented and evaluated by a Level III U/T examiner. A review of these evaluations disclosed that in most cases the indications were root condition and/or geometrical indications that were confirmed by review of construction radiographs, others were located in the base metal away from the area of interest as verified by plottin .

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