IR 05000281/1979023
| ML18114A736 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/25/1979 |
| From: | Conlon T, Crowley B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18114A735 | List: |
| References | |
| 50-281-79-23, NUDOCS 7906260603 | |
| Download: ML18114A736 (5) | |
Text
I
-*
- -* : -. -.,. __
' -.
Report No. 50-281/79-23 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Licensee: Virginia Electric and Power Company P. 0. Box 26666 Richmond, Virginia 23261 Facility Name: Surry Power Station, Unit 2 Docket No. 50-281 License No. DPR-37 r. Williamsburg,_,ginia SUMMARY Inspection on April 2-5, 1979 Areas Inspected This routine unannounced inspection involved 46 inspector hours onsite in the area of steam generator replacement welding activitie Results Of the one area inspected, no apparent items of noncompliance or deviations were identified.
?906 2 60<.;03
-- ---*-* -- -*--~~-..- ---~*
- ---
!_ -
,:
1,'
DETAILS Persons Contacted Licensee Employees
- W. L. Stewart, Station Manager
- A. L. Parrish, III, Project Manager, SGRP
- J.B. Goodson, Resident QC Engineer W. L. Byrd, Supervisor Welding Construction C. W. Embler, Staff Engineer Welding
- C. W. Rhodes, Resident Engineer Construction Q. A. Vogtsberger, Jr., Nuclear Training Coordinator Other licensee and Contractor employees contacted included Engineering, security force members, and office personne Other Organizations Daniels Construction Company (DCC)
J. Latimer, Project Welding Engineer NRC Resident Inspector
- D. J. Burke
- Attneded exit intervie.
Exit Interview The inspection scope and findings were summarized on April 5, 1979 with those persons indicated in Paragraph 1 abov The inspection included steam generation replacement welding activitie.
Unresolved Items Unresolved items were not identified during this inspectio Independent Inspection Effort.
The inspector spent approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> obtaining the required security and radiation control clearances and orientatio After obtaining the ~equired clearances, the following areas were observed during a general plant 'tour:
. ~:,
/* Six DCC welding operators were observed during mockup training for reactor coolant loop welding. The automatic gas tungsten arc (GTA) process will be used for this weldin The training was being accomplished on 16 inch diameter heavy wall pip The licensee indicated that 29 welders have qualified and the plans are to have a total of 32 by the time the work starts. In addition, one welding operator was observed in the process of qualifying for the buildups on the ends of the reactor coolant loop pipin The sumerged arc (SAW) process will be used for this weldin A Chicago Bridge and Iron (CB&I) welder was observed during mockup training for the steam generator feed water nozzle wel Also, the mockups to be used for training steam generator shel to shell welders were observe The shell to shell weld and nozzle to shell weld will be accomplished using the shielded metal arc (SMA) proces The licensee indicated that 4 welders have qualified for this weldin The inspector toured the rerurbishment building and observed preparations in process for welding and machining the ends of reactor coolant loop pipin The inspector toured the mockup training building. At the time of the tour, no training was in process., DCC weld material issue station in the auxiliary building was inspected for temperature control and material issue requirement General work activities in the steam generator cubicles in the containment were observe Within the areas inspected, no items of noncompliance or deviations were identifie Steam Generator Replacement - Observation of Welding and Associated Activities The inspector observed/reviewed the welding and cutting activities and procedures described below to determine whether these activities relative to steam generator replacement are being accomplished in accordance with regulatory requirements, applicable codes, standards, and licensee commitments. The applicable code, as required in "VEPCO's licensee submittal (Steam Generator 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 plans to use the original construction code (USAS B31.1.0-1967) for pipe welding and ASME Section III, 1974 edition
- ,
.
-;" __ -~:. -.....
-*
-3-including addenda through the winter of 1976 for steam generator shell welding. Welder 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 qualification. All welding materials were purchased and certified in accordance with class 1 requirements of the ASME cod The inspector reviewed applicable specifications and procedures to assure that appropriate code classes have been determined and specified for each weld. Each Engineering Task Assignment (ETA)
specifies the applicable cod ETAS 30005 (Cutting Reactor Coolant Piping), 30006 (Cutting Main Steam Piping), and 30007 (Cutting Feedwater Piping) were reviewed to determine if appropriate cutting procedures were availabl In order to determine that procedures and equipment were in place to protect cutting and welding personnel, the inspectors observed/
reviewed the following:
(1)
"Vepco Steam Generator Replacement Project, Surry Power Station Health Physics Manual" had been issued and was in use. Each ETA requires that Radiation Work Permits (RWP) be issued for all work to be performed in radiation area (2)
The inspector.. observed that for cutting EP-3 and EP-4 (loop Piping), RWP-SGRP-79-82 had been issued and posted. At the time of observation, temporary lead shielding was in place on the loop piping and a tent, which *apparently had been intact for the cutting operation, was open for removal of a piece of loop pipin The inspector reviewed the following DCC welding procedures to determine compliance with applicable codes:
(1)
(2)
(3)
WP-500, Revision O, "General Welding Requirements".
WP-501~ Revision 2, "Qualification of Welding Procedures and Welders".
WPS 8-8, Revision 2, "Welding of Stainless Steel" including technique sheets 8-8-D-13, Revision O; 8-8-B-22, Revision 1; and 8-8-B-21, Revision 1. The applicable procedure qualifica-tion record (PQR) for each Technique Sheet was also reviewe During review of 'Technique Sheet 8-8-D-13, the inspector noted that one of the nonessential variables (contact tip to work distance) had not been covered as required by ASME
- -- --. -------. -*******-*
- -.
--*-*---**,.. -*-*- - *.,... --~*.,,....,.. -..-~-~--,,........... ~--. r--*
- - *. (.......-
~ :. *-:*.f ___......... ~- --* *.*.*..*.,.........,.
....
.
..
-4-Section I When this was brought to the attention of the DCC Welding Engineer, it was evident that this problem has been recognized and correction was in process.; This will be identified as inspector followup item No. 281/79-23-0 Within the areas inspected, no items of noncompliance or deviations were identified.