IR 05000280/1979037
| ML18130A636 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/13/1979 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18130A635 | List: |
| References | |
| 50-280-79-37, 50-281-79-56, NUDOCS 7909210038 | |
| Download: ML18130A636 (4) | |
Text
e e
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-280/79-37 and 50-281/79-56 Licensee:
Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name:
Surry Nuclear Facility, Unit 1 and 2 Docket No and 50-281 License No DPR-32 and DPR-37 Inspectof]=-'~--L....,-~---=-~~r~~~t_y_* ~~~~~~~~~~~~
(JJJ B. R.~y~".
Approved by :--,--....... (dlt'="""".-~~-~~//£.~,:(/;--;1--,--~.,.--,,,--------
A. R. Herdt, Section Chief SUMMARY Inspection on June 28-29, 197 Areas Inspected DAte Signed D?<<{~
This special, announced inspection involved 6 inspector-hours onsite in the area of steam generator feedwater line radiography (RT).
Results No apparent items of noncompliance or deviations were identifie ?:lf, _
e Persons Contacted Licensee Employees DETAILS W. L. Stewart, Station Manager
- G. E. Kane, Operating Supervisor T. Peebles, Superintendent of Technical Services J. P. Maciejewski, Engineering Supervisor T. W. Brombach, NDE Foreman
- F. L. Rentz, Resident QC Engineer
- Attended exit interview Exit Interview The inspection scope and findings were summarized on June 29, 1979 with those persons indicated in Paragraph 1 abov This inspection included review of original construction requirements, loop configurations, and recently taken radiographs for the steam generator feedwater pipin.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
Independent Inspection Effort Due to recently reported cracking in steam generator feedwater lines in several PWR plants, Virginia Electric and Power Company (VEPCO) radio-graphically (RT) inspected certain feedwater line welds and adjacent base material on Surry, Unit The RT inspection revealed cracks near the nozzle to reducer welds located in the reducer base material for all three loops and in the nozzle base material for loops "B" and "C".
The purpose of this inspection was to review the radiographs and obtain information relative to the configuration and original construction aspects of the feedwater loop The following is a summary of obser-vations/reviews made by the inspector and information obtained: Configuration of Feedwater Lines The three feedwater loops are 14-inch diameter schedule 80 pipe connected to 16-inch diameter steam generator nozzles using 16-inch x 14-inch carbon steel reducer The horizontal sections of pipe
" 9 21 ('
e-2-leaving the steam generators are from 11 to 15-feet long and contain an inverted "U" or flex-loo The lines then make 90 to 120-degree turns with the first restraint being 4 to 9-feet upstream from the bend or elbo Observation/Review of Inspection Results (1)
The inspector reviewed the following Unit 1 film:
Loop A Nozzle to Reducer:
FW-18, Line WFPD-17-601 Reducer to Pipe:
Line WFPD-17-601 Loop B Nozzle to Reduce:
Reducer to Pipe:
Loop C FW7, Line WFPD-13-601 Line WFPD-13-601 Nozzle to Reducer:
FWB, Line WFPD-9-601 Reducer to Pipe:
Line WFPD-9-601 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 weld for one shot and then moved to the other side of weld 1/2-lnch from the centerline of the weld for the second sho Number 12, 15 and 17 penetrameters were used for each sho The 2T hole was visible in all radio-graph Review of the radiographs revealed circumferential cracking in the reducer and nozzle base materials as previously reported by the license Most of the cracks are in the reducer base materia However, Nozzles "B" and "C" do have some indications of crack Also, in "A" loop there is an indication in the edge of the weld on the reducer side parallel to an indication in the reducer base materia In two of the reducer to pipe welds, there are questionable indications which the licensee plans to investiga.te further after the reducers are remove In addition to the film listed above, the inspector also reviewed the original construction film for the nozzle to reducer weld These film did not show the cracking observed in the above recent fil (2)
The inspector visually inspected the Unit 2 reducers which had been cut out previously as part of the steam generator replacement projec The inside surface of the reducers had not been cleaned up and i
-
-3-therefore a meaningful visual inspection could not be performe The licensee was in process of RT inspection of the reducer welds and adjacent base materia At the conclusion of the inspection, RT results had not been obtaine Materials Based on a review of available drawings, the following material specifications are applicable:
Steam Generator Nozzle - SA508, C Reducer - SA234, Gr.WPB Pipe - SA106, Gr. B Welding and Heat Treatment The inspector reviewed a sample of the construction weld records to obtain the following information:
(1)
Nozzle to Reducer Weld -
(2)
Joint Type - Consummable Insert Filler Material - Root:
MS-1 Insert, Remainder:E7018 Preheat - 200 F PWHT - 1150 F I
14-Inch Pipe Welds Joint Type - Open Butt Filler Material - Root:
MIG A681, Remainder:
E7018 Preheat - 200 F PWHT - N/A Within the areas inspected, no items of noncompliance or deviations were identified.