ML20147C729

IE Inspec Repts#50-413/78-8,#50-414/78-7 on 780815-18 During Which No Items of Noncompliance Were Noted.Major Areas Inspected Included:Reactor Coolant,Piping Work & Quality Records of Unit 1, & All safety-related Structures

ML20147C729
Person / Time
Site:	Catawba
Issue date:	09/20/1978
From:	Blake J, Conlon T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20147C713	List: IR 05000413/1978008 ML20147C709 ML20147C729
References
50-413-78-08, 50-413-78-8, 50-414-78-7, NUDOCS 7810130101
Download: ML20147C729 (5)

Text

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Report Nos.: 50-413/78-8 and 50-414/78-7 Docket Nos.: 50-413 and 50-414 License Nos.: CPPR-116 and CPPR-117 Categories: A2 and A2 Licensee: Duke Power Company Power Building 422 South Church Street Charlotte, North Carolina 28242 Facility Name: Catawba Nuclear Power Station, Units 1 and 2 Inspection at: Clover, South Carolina Inspection conducted: August 15-18, 1978 Inspector: J. b.ake Reviewed by:

T. E. Conlon, Chief t/

/f 9/2r/] f 7 Dat'e Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Inspection Summary Inspection on August 15-18, 1978 (Report Nos. 50-413/78-8; 50-414/78-7)

Areas Inspected: Routine, unannounced inspection of reactor coolant pressure boundary piping work activities and quality records (Unit 1);

safety-related piping work activities and quality records (Unit 1) safety-related structures (Units 1 and 2). This inspection involved 25 inspector hours on site by one NRC inspector. There were no 50.55(e) or Part 21 items in this inspection.

Results: There were no items of noncompliance or deviations identified.

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RII Report Nos. 50-413/78-8 and 50-414/78-7 I-1 Prepared by: 4/

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Details I

{ /A<4 lM t J. J. IhaYe, Metallurgical Engitieer 'Date Engineering Support Section No. 2 Reactor Construction and Engineering Sepoort Branch Dates of Inspection: August 15-18, 1978 Reviewed by:

T. E. Conlon, Unief' M

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' Date Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch

1. Persons Contacted

a. Duke Power Company (DPC)

D. G. Beam, Project Manager

• R. A. Morgan, Senior QA Engineer

• R. P. Ruth, QA Engineer

• D. L. Freeze, Project Engineer

• L. R. Davison, Senior QC Engineer

b. Contractor Organization Richmond Engineering Company (RECO)

J. S. Antill, QC Engineer The inspector also talked with an interviewed several other licensee and contractor personnel during this inspection.

• Denotes those participating in the exit interview.

2. Licensee Actions on Previous Inspection Findings There were no previous inspection findings reviewed during this inspection.

1

3. Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during the inspection is discussed in paragraph 8.

RII Report Nos. 50-413/78-8 and 50-414/78-7 I-2

4. Independent Inspection The inspector conducted a walk-through inspection of the reactor building, auxiliary building, and storage areas to observe status of construction; handling and storage of materials; and safety-related work activities. Work activities observed included the following:

a. Storage Areas The inspector observed the handling of materials in piping storage yard. The piping was being handled with nylon slings and in a manner which would minimize the chance of damage.

b. Reactor Buildings and Auxiliary Building The inspector observed the condition of installed equipment, and precautions which were being taken to protect the equipment frco damage.

There were no items of noncompliance or deviations in this area of inspection.

! 5 Safety-Related Structures (Units 1 and 2)

The Richmond Engineering Company (RECO) has been contracted to fabricate and erect the 400,000 gallon stainless steel refueling water storage tanks for Units 1 and 2. These tanks are designed and being fabricated and erected in accordance with the ASME B&PV Code,Section III Class 2 (1974 Edition with Summer 1975 Addenda) requirements.

At the time of this inspection the Unit I tank was being erected.

The inspector reviewed REC 0's QA manual, and the following welding and quality control procedures.

Welding Procedure PS/TIG-1, Rev. 2 Welding Procedure P8/MMA, Rev. 1 Welding Procedure P1/P8/MMA/ PIPE Welding Procedure P1/MMA/DBW/ PIPE ES-116 Vacuum Box Testing Method

, ES-118 Procedure for Cleaning Weld Scars on Tank Surfaces ES-134 Visual Inspection Procedure ES-107NC Liquid Penetrant Examination Procedure for Nuclear Components ES-123 Weld Repair Procedure t - - - - - _

RII Report Nos. 50-413/78-8 and 50-414/78-7 I-3 The inspector also reviewed certifications for the plate materials, welding materials and liquid penetrant inspection materials being

. used.

There were no items of noncompliance or deviations in this area of inspection.

6. Reactor Coolant Pressure Boundary (RCPB) Piping - Observation of Work and Work Activities The inspector observed the handling and protection of the three main coolant pump casings and the tenporary support and protection of the hot and cold leg piping spools. The methods used to support and protect other piping components such as 10" MOV No. 9J-209 and 12" Valve No. INI-249 in the Unit I pipe chase were also reviewed.

There were no items of noncompl:ance or deviations in this area of inspection.

7. RCPB Piping - Review of Quality Records The inspector reviewed the material certifications and receipt inspec-tion records for the following p; ping components:

10" SCH 140 Elbow H41371 (QA?-123-4) 10" SCH 140 Pipe H2598-6-1 ((AP-120-5) 10" SCH 140 Pipe H2598-4-2 (QAP-120-5) 10" Motor Operated Gate Valve 9J-209 (V-437) 12" SCH 140 Fire H535397 (QAP-120-6) 12" Swing Check Valve INI-249 (V04)

There were no items of noncomplianca or deviations in this area of inspection.

8. Safety-Related Piping - Review of Quality Records The inspector selected the following piping materials for a review of material certifications and receipt inspection records.

l 6-inch SCH 160 Stainless Pipe HT 6743424 (QAP-119-1) 6-inch Swing Check Valve 9J-212 (V-79) 20-inch Diameter Carbon Steel Pipe HT LO4057 (QAP-126-19) 14-inch Diameter Carbon Steel Pipe HT 273345 (QAP-327-14) 20-inch Diameter Carbon Steel Elbow Code #YS3X (QAP-128-8)

During the review of the certifications for the 20-inch diameter elbow the inspector noted that the mechanical property test values for yield

RII Report Nos. 50-413/78-8 and 50-414/78-7 I-4 strength, tensile strength and clongation were exactly the same as the raw material mechanical properties for seven out of ten of the fittings supplied on the same order. The certifications were not clear for the following fittings:

Control Description Stock YS3D 3" 90 EL 2 5/8" HT260928 YJ3D 16" 90 EL 11 3/4" HT153725 YS3X 20" 90'EL 14" HTL20961 XR3C 10" 90 EL 8 5/8" HTL01245 YS3D 3" 45 EL 2 5/8" HT260928 YJ3H 16" 45 EL 11 3/4" HT153725 UL3H 10" 45 EL 8 5/8" HT232704 The inspector informed the licensee that these certifications would be considered to be an unresolved item No. 413/78-08-01; 414/78-07-01; pending clarification by the vendor.

9. Exit Interview The inspector met with licensee and contractor representatives (denoted l in paragraph 1) at the conclusion of the inspection on August 18, 1978. The inspector summarized the scope and findings of the inspection.

l The licensee stated that the QA Personnel would follow up on the material certifications which resulted in the unresolved item.

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