IR 05000281/1980002
| ML18139A044 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/24/1980 |
| From: | Herdt A, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18139A043 | List: |
| References | |
| 50-281-80-02, 50-281-80-2, NUDOCS 8003190752 | |
| Download: ML18139A044 (6) | |
Text
Report No. 50-281/80-02 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Licensee:
Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name:
Surry Nuclear Station Docket No. 50-281 License No. DPR-37 Inspection Williamsburg, Virginia
~, ;'_
l/2(/~0 Approved SUMMARY Inspection on January 14-17, 1980 Areas Inspected Dat'eSigned zbr/r:o RCES Branch DJte Signed This routine, unannounced inspection involved 28 inspector-hours onsite in the areas of welding filler material control, and nondestructive examinatio Results Of the two areas inspected, no apparent items of noncompliance or deviations were identified.
,,
DETAILS Persons Contacted Licensee Employees
- J. L. Wilson, Superintendent Operations
- T. A. Peebles, Superintendent, Technical Sv *J. Maciejewski, Engineering Supervisor (NDT)
- F. L. Rentz, Resident QC Engineer
- C. Rhodes, Resident Engineer Construction
- W.R. Skelley, Jr., SGRP Staff Assistant
- J. Goodson, SGRPResident QC Engineer
- C. Embler, SGRP Staff Engineer - Welding
- E,* 0. DeWandel, Station Staff Assistant
- D. Hahn, Maintenance Coordinator Other licensee employees contacted included thre,e construction craftsmen, four technicians, seven security force members, and two office personne NRC Resident Inspector D. J. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on January 17, 1980, with those persons indicated in Paragraph 1 abov.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
Independent Inspection Effort Construction Activiti~s The inspector conducted a general inspection of the turbine and polishing buildings to observe construction progress and construction activities such as welding, pipe fitting, material handling and control, hou~ekeep-ing and storag * *
- Welding Filler Material Control The inspector observed activities at the weld material issue station in the polishing building to determine adequacy of:
weld material storage/segregation, oven temperatures, issue records and return of unused weld materia The inspector also observed work areas for uncontrolled weld materia Within the areas inspected, no items of noncompliance or deviations were identifie Steam.Generator Replacement - Non Destructive Examination The applicable code as required by VEPCO's licensee submittal (Steam Genera-tor Project Surry Power Station Unit Nos. 1 and 2, Revision 9), is ASME Section XI, 1974 Edition with addenda through the winter of 197 Based on paragraph IWA-7000 of Section XI, VEPCO is using the original construction code. (USAS B31. l. 0 1967) for pipe weldin Welding qualifications and procedure qualifications are being performed in accordance with the latest edition and addenda of ASME Section IX in effect at the time of the quali-ficatio All welding materials were purchased and certified in accordance with Class *1 requirements of the ASME co.d Nondestructive testing is being performed in accordance with ASME code,Section III and V, 1974 Edition with Addenda through the Winter of 197 Review of Procedures The inspector reviewed the below listed procedures to determine whether the procedures were consistent with regulatory requirements and licensee commitment (1)
Chicago Bridge and Iron (a) MTll, Rev. 2, "Magnetic Particle Examination Procedure, Continuous Yoke, Dry, Visible Particles" (b)
RT-1, Rev. 3, "Radiographic Examination.Procedure" (c)
UTIX, Rev. 4, "Ultrasonic Examination Procedure for Low Alloy Welds" (2)
VEPCO (a)
NDT-14.1, Rev. 1 "Eddy Current Testing.of Steam Generator Tubing"
_J
- . - :._ -
(3)
-3-Westinghouse (a)
ISI-8, Rev. 7, Amendment 01 "Visual Examination Procedure" (b)
ISI-205, :Re.v. 2, Amendment 3 "Manual Ultrasonic Examination of Full Penetration Circumferential and Longitudinal Butt Welds" Observation of Work On the date of this inspection nondestructive examination for the steam generator replacemnt project in the below listed areas had been completed, therefore the inspector reviewed VEPCO Engineering Task Assignment (ETA) 40006 "Steam Generator Girth Weld", VEPCO ETA 40004
"Installation of Reactor Coolant Piping", four Westinghouse Ultrasonic Examination reports and two VEPCO Audit reports for the nondestructive examination activities described below to determine whether these activities were being performed in accordance with regulatory requfre-ments and licensee approved procedure (1)
Volumetric examination using ultrasonic technique was reviewed for the following welds:
PIPE TO PIPE/ELBOW/NOZZLE Size Weld N System and Loop Drawing N (Dia)
Material SDM Reactor Coolant "B" VIR-1-4200 29" Stainless Steel 6DM Reactor Coolant "B" VIR-1-4200 31" Stainless Steel
Reactor Coolant "B" VIR-1-4200 29" Stainless Steel
Reactor Coolant "A" VIR-1-4100 29" Stainless Steel
Reactor Coolant "A" VIR-1-4100 31" Stainless Steel
Reactor Coolant "A" VIR-1-4100 31" Stainless Steel
Reactor Coolant "A" VIR-1-4100 31" Stainless Steel
Main Steam "A" VIR-2-2100 30" Carbon.Steel
Main Steam "C" VIR-2-2300 30" Carbon Steel
Main Steam "A" VIR-2-2100 30" Carbon Steel
Feed Water "B" VIR-2-2201 14" Carbon Steel
Feed Water "B" VIR-2-2201 14" Carbon Steel
Feed Water."C" VIR-2-2301 14" Carbon Steel SHELL TO SHELL
"B" Generator Girth Weld
"C" Generator Girth Weld
- ~: -..
-4-The above examinations were compared with the applicable proce-.
dures in the following areas:
Type of apparatus used Extent of coverage Calibration method Size and frequency of search units Beam angle Method of distance compensation Reference level for monitoring discontinuities Methods of demonstrating penetration Method of recording significant indications Levels or limits for evaluations Acceptance limits are determined (2)
Volumetric examination using the radiographic technique was reviewed for the following welds:*
PIPE TO PIPE/ELBOW/NOZZLE Size Weld N.System and Loop Reactor Coolant "C" Reactor Coolant "C" Drawing N (dia)
Material
,5
- SHELL TO SHELL
"B" Generator Girth Weld
"C" Generator Girth Welds 31" Stainless Steel 31" Stainless Steel The above examinations were compared with the applicable proce-dures in the following areas:
Type of material Material and weld surface condition Material thickness Type of radiation source Film brand, type Minimum source to film distance Type and thickness of screens and filters
.
.
--.~.
...
. '
.
.. - - -- ---.
- - -:--*-
~
- ..
..
.
-
-5-(3)
Surface examination using magnetic particle technique was reviewed for the following welds:
SHELL TO SHELL
"B" Generator Girth weld
"C" Generator Girth Weld The above examinations were compared with the applicable proce-dures in the following areas:
Examination by the continuous method Particle color/contrast Reuults are consistent with acceptance criteria Data Review and Evaluation The inspector reviewed the records for the joints listed in paragra1h 6b above, the eddy current base line records for steam generator tubes, and the applicable procedures to determine whether the selected records contained or provided reference to the following documents:
(1)
Examination results and data sheets (2)
Examination equipment data (3)
Calibration data sheets (4)
Records on program deviations, if any (5)
Identification of N.D.E. Material such as penetrant, cleaner, couplant, films, tape, et (6)
The recording, evaluation and disposition of findings are in compliance with the applicable N.D.E. procedures and code requirement (7)
Evaluation of data complies with the criteria of the N. procedur (8)
Evaluation of data performed by a level II or level III examine In the areas inspected, no items of noncompliance or deviations were identified.
- -- *-**-***-**-- ------**-