IR 05000250/1979022

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IE Insp Repts 50-250/79-22 & 50-251/79-22 on 790627.No Noncompliance Noted.Major Areas Inspected:Steam Generator Feedwater Line Radiography
ML17338B066
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 07/12/1979
From: Crowley B, Herdt A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17338B065 List:
References
50-250-79-22, NUDOCS 7909180538
Download: ML17338B066 (6)


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UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-250/79-22 and 50-251/79-22 Licensee:

Florida Power and Light Company 9250 West Flagler Street Miami, Florida 33101 Facility Name:

Turkey Point Units 3 and

Docket Nos. 50-250 and 50-251 License Nos.

DPR-31 and DPR-41 Inspection at Tu k y Point Site near Homestead, Florida Inspecto

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B. R.

rowle Approved by:

" A. R. Herdt, Section Chief, RC&ES Branch t

SIMARY 7/

ate Signed ate igned Inspection on June 27, 1979 Areas Inspected This special, announced inspection involved 9 inspector-hours onsite in the area of steam generator feedwater line radiography (RT).

Results No apparent items of noncompliance or deviations were identified.

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DETAILS 1.

Persons Contacted Licensee Employees

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H. E. Yaeger, Plant Manager R. J.

Spooner, QA Supervisor G. Gotch, GO PRN Staff Specialist

+K. V. Smart, Construction Coordinator -

QC

+Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on June 27, 1979 included review of original construction requirements, loop configurations, and recently taken radiographs for the steam generator feedwater piping.

3.

Licensee Action on Previous Inspection Findings Not inspected.

4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Independent Inspection Effort Due to recently reported cracking in steam generator feedwater lines in several PWR plants, Florida Power and Light Company radiographically (RT)

inspected certain feedwater line welds and adjacent base material on Turkey Point, Units 3 and 4.

This radiography did not reveal any feedwater line cracking as experienced in other plants.

The purpose of this inspection was to review radiographs and obtain information relative to the configura-tion and original construction aspects of the feedwater loops.

The following is a

summary of observation/reviews made-by the inspector and information obtained.

a.

Configuration of Feedwater Lines The three feedwater loops are 14-inch diameter schedule 60 carbon steel pipe connected to 18-inch diameter steam generator nozzles using a 18-inch x 14 inch carbon steel reducer.

A horizontal section of pipe, approximately 3-feet long for loops "A" and "B" and 7-feet for loop "C", is welded to the 14-inch end of the reducer.

The lines then run vertical down 5 to 16 feet dependant upon loop and uni 'I 1 j

-2-The first restraint (snubber)

is located in the second vertical run for loop "A", the second horizontal run for loop "B", arid the first vertical run for loop "C".

b.

Review of RT Film (1)

Unit 4 Ioop A-Loop B-Ioop C-Nozzle to Reducer Reducer to Pipe Nozzle to Reducer Reducer to Pipe Nozzle to Reducer Reducer"to Pipe Weld Weld Weld Meld Weld Weld A-1 A"2 B-1 B-2 C-1 C-2 These radiographs were made on a rush basis prior to development of RT requirements as specified in IE Bulletin 79-13 and in cases do not meet code requirements because of missing penetrameters, density problems, location of penetrameters, weld coverage, etc

.

However, the film can be interpreted for the presence of cracks as found in other plants.

The RT revealed no cracks.

Reradiography will be performed later as required to meet IE Bulletin 79-13.

(2)

Unit 3 Loop A-Weld A-1 Meld A-2 Weld A-3 Weld A-4 Weld A-5 Weld A-6 Weld A-7 Weld A-8 Weld A-9 Weld A-10 Loop B-Weld B-1 Weld B-2 Weld B-3 Weld B-4 Weld B-5 Weld B-6 Loop C-Weld C-1 Weld C-2 Weld C-3 Weld C-4

The above list includes all weld joints between the steam generators and the first restraint in each line.

The radiographs were made using a

2 shot technique recommended by Westinghouse where the source is placed on one side of the weld 1/2-inch from the centerline of the weld for one shot and then moved to the other side of the weld 1/2-inch from the centerline of the weld for the record shot.

A number 12 and number 15 penetrameter was used for each shot.

Although the film showed no evidence of cracking, several of the radiographs contained weld defects which were not noted on the film reader sheets.

It was not clear whether the radiographs had been reviewed for cracks only or for cracks plus code acceptability.

The inspector pointed out to the licensee that since the issue of IE Bulletin 79-13, the film would need to be reviewed for code acceptabiliy.

Note:

The weld numbers listed in (1)

and (2)

above do not agree with original ISO Weld Numbers.

The numbers were selected for this RT exercise and are made up of the loop alphabetic identification and consecutive number running upstream starting at the nozzle to reducer weld.

C.

Materials Based on a review of available drawings, the following material specifi-cations are applicable:

Steam Generator Nozzle - SA 336 Cl.2 Reducer - SA 234 Gr.

WPB Pipe - SA 106 Gr.

B d.

Welding and Heat Treatment The inspector reviewed the applicable construction welding procedure and the construction weld records for nozzle to reducer welds to obtain the following information:

Joint Type - Backing Ring Filler Material - E7018 Preheat - 200 degrees Fahrenheit PWHT - 1150 degrees Fahrenheit Within the areas inspected, no items of noncompliance or deviations were identified.