ML20138M934
| ML20138M934 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/11/1985 |
| From: | Rogge J, Schepens R, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20138M914 | List: |
| References | |
| 50-424-85-43, 50-425-85-32, NUDOCS 8511040483 | |
| Download: ML20138M934 (16) | |
See also: IR 05000424/1985043
Text
.
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UNITED STATES
MUCLEAR REGULATORY COMMISSION
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REGION il
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101 MARIETTA STRE ET.N.W.
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ATLANTA. GEORGI A 30323
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Report Nos..
50-424/85-43 and 50-425.'d5-32
Licensee: Georgia Power Company
P. O. Box 4545
Atlanta, GA 30302
Docket Nos.
50-424 and 50-425
License Nos.
CPPR-108 and CPPR-109
Facility Name: 'dogtle 1 and 2
Inspection Conducted: September 3-September 26, 1985
Inspectors: d "[>(
/0/_/f/f5
p J. F. 'Rogge, Senior Resicent
Date Signed
Inspector, Operations
Y~
T
-.&/H/]S
.$m R. J. Schepens, Resident
Date Signed
Inspector, Construction
Approved By: Md $(.
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M. V. Sinkule, Section Chief
Oate Signed
Division of Reactor Projects
SUMMARY
Scope:
This routine, unannounced inspection entailed 242 resident inspector-
hours on site (32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> were on backshif ts) inspecting: containment and safety-
related structures, piping systems and supports, safety _ related components,
auxiliary syste,s, electrical equipment and cables, and quality programs and
administrative controls affecting quality.
Results: One violation was identified
" Failure to Provide Adequate Protection
to Safety-Related Components During In-Plant Storage" - Paragraph 15.
8511040403 051017
ADOCK 05000424
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REPORT DETAILS
1.
Persons Contacted
Licensee Employees
D. O. Foster, Vice President and Project General Manager
P. D. Rice, Vice President and General Manager, Q.A.
W. T. Nickerson, Deputy Project General Manager
- D. G. Smith. Assistant Deputy Project General Manager
W. C. Ramsey, Readiness Review Manager
H. H. Gregory III, General Manager Nuclear Construction
- M. H. Googe, Project Construction Manager
G. Bockhold, Jr., General Manager Nuclear Operations
0. Batum, General Manager Engineering and Licensing
C. W. Hayes, Vogtle Quality Assurance Manager
- C. E. Belflower, Quality Assurance Site Manager - Operations
E. D. Groover, Quality Assurance Site Manager - Construction
S. D. Haltom, Quality Assurance Engineering Support Supervisor
- W. E. Mundy, Quality Assurance Audit Supervisor
J. E. Sanders, Project Construction Manager - Unit 1
- D. M. Fiquett, Project Construction Manager - Unit 2
,
- B. C. Harbin, Manager Quality Control
C. R. Brewer, Assistant Quality Control Manager
T. L. Weatherspoon, Assistant Quality Control Manager
- G. A. McCarley, Project Compliance Coordinator
W. C. Gabbard, Assistant Project Compliance Coordinator
J. O. Dorough, Administrative Manager
W. F. Kitchens, Operations Superintendent
- P. T. Ciccanesi, Regulatory Compliance
M. Stone, Engineering Supervisor
T. Dannemiller, Senior QA Engineer
- R. C. Walker, Quality Assurance Field Representative
- G. C. Lapsley, Quality Control - Mechanical
- J. F. D'Amico, Regulatory Compliance Superintendent
Other licensee employees contacted included craftsmen,
technicians,
supervision, engineers, inspectors, and office personnel.
Other Organizations
- J. Mamon, Quality Engineer - Bechtel
R. Bends, NSCW Flushing Engineer
M. L. Bagale, Surveillance Specialist - Bechtel
J. R. Baleicki, Lead HVAC Equipment / Maintenance Engineer -
Pullman /Kenith-Fortson Co., Inc.
" Attended Exit Interview
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2.
Exit Interview (30703C)
The inspection scope and findings were summarized on September 26, 1985 with
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those persons indicated in paragraph 1 above.
The inspector described the
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areas inspected and discussed in detail the inspection finding listed below.
No dissenting comments were received from the licensee. The licensee did
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not identify as proprietary any of the raterials provided to or reviewed by
the inspector during this inspection.
3
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(0 pen) Violation, 50-424/85-43-01 & 50-425/85-32-01 " Failure to provide
adequate protection to safety related components during in plant storage" -
paragraph 15.
The following NRC exit interviews were attended during the inspection period
1
by a resident inspector:
September 6,1985
L. H. Jackson & R. W. Wright
September 6,1985
S. J. Vias
September 13, 1985
R. M. Latta
3.
Licensee Action on Previous Enforcement Matters (92702)
Not inspected.
4.
Unresolved Items (92701)
Unresolved items are matters about which more information is required to
determine whether they are acceptable or may involve violations or
deviations. Unresolved items were not identified during this inspection.
5.
Construction Inspection - Units 1 & 2
4
Periodic inspections were made throughout this reporting period in the form
of general type inspections in different areas of both facilities.
The
areas were selected on the basis of the scheduled activities and were varied
j
to provide wide coverage. Observations were made of activities in progress
i
to note defective items or items of noncompliance with the required codes
and regulatory requirements. On these inspections, particular note was made
of the presence of quality control inspectors, supervisors, and quality
control evidence in the form of available process sheets, drawings, material
identification, material protection, performance of tests, and housekeeping.
Interviews were made with craft personnel, supervisors, coordinators,
quality control inspectors, and others as they were available in the work
areas.
i
Independent inspection encompassed but was not limited to the following
areas:
Unit No.1 Condensate Storage Tank (CST) Level Instrumentation Piping
-
Installation
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3
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Unit No. 1 Main Condenser, Associated Connections, and Feedwater
Heaters
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Unit No. 2 Main Condenser and Feedwater Heaters
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Unit No. 2 Backfilling West of Containment Near Tower Crane No. 1
No violations or deviations were identified.
6.
Fire Prevention / Protection and Housekeeping Measures - Units 1 & 2 (42051C)
The inspector observed fire prevention / protection measures throughout the
inspection period. Welders were using welding permits with fire watches and
extinguishers.
Post indicator valves were being maintained in the open
position. Fire fighting equipment is in its designated areas throughout the
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plant.
!
The inspector reviewed and examined implementation portions of the following
procedures pertaining to the placement of concrete to determine whether they
comply with applicable codes, standards, NRC Regulatory Guides and licensee
commitments.
-
SD-T-05, Rev. 6 Fire-Protection Equipment Inspection and Testing
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GD-T-15, Rev. 5 Welding and Cutting
-
GD-T-17, Rev. 3 Housekeeping
The inspector observed fire prevention / protection measures in work areas
containing safety-related equipment during the inspection period to verify
the following:
Combustible waste material and rubbish was removed from the work areas
-
as rapidly as practicable to avoid unnecessary accumulation of
combustibles
Flammable liquids are stored in appropriate containers and in
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designated areas throughout the plant
Cutting and welding operations in progress have been authorized by an
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appropriate permit, combustibles have been moved away or safety
,
covered, and a fire watch and extinguisher was posted as required
Fire protection / suppression equipment was provided and controlled in
-
accordance with applicable requirements
No violations or deviations were identified.
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7.
Containment (Structural Concrete) - Unit 2 (47053C)
a.
Procedure and Document Review
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The inspector reviewed and examined implementation portions of the
following procedures pertaining to the placement of concrete to
determine whether they comply with applicable codes, standards, NRC
-
Regulatory Guides and license commitments.
CD-T-02, Rev. 15
Concrete Quality Control
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$
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CD-T-06, Rev. 9
Rebar and Cadwela Quality Control
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CO-T-07, Rev. 8
Embed Installation and Inspection
CD-T-20, Rev. 6
Installation and Inspection of Trumpets,
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Rigid Extensions, and Duct Sneathing
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2X2001A002, Rev. 11
Containment Concrete Forming and Placing
Plan and Section
1
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2X2048A003, Rev. 5
Containment Internals Concrete Forming
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Plan at El 220'-0"
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2X2044008, 010 &011,
Outside Area Tunnels Forming Plan-
Rev. 1
Bottom & Top 2T3A & 2T3B
b.
Installation Activities
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The inspector witnessed portions of concrete placement indicated below
to verify the following:
(1) Forms, En.bedment, and Reinforcing Steel Installation
!
Forms were properly placed, secure, leak tight and clean.
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Rebar and other embedment installation was installed in
accordance with construction specifications and drawings,
secured, free of concrete and excessive rust, specified
distance from forms, proper on-site rebar bending (where
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applicable) and clearances consistent with aggregate size.
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(2) Delivery, Placement and Curing
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Preplacement inspection was completed and approved prior to
placement utilizing a Pour Card (Exhibit CD-T-02*18).
Construction joints were prepared as specified.
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Proper mix was specified and delivered.
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Temperature control of the mix, mating surfaces, and ambient
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were monitored.
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1
1
Testing at placement location was properly performed in
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accordance with the acceptance criteria and recorded on a
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Concrete Placement Pour Log (Exhibit CD-T-02*20).
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Adequate crew, equipment and techniques were utilized.
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Inspections during the placement were conducted by qualified
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personnel.
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Curing temperature was monitored.
(3)
Installation of Trumpets, Tendon Sheaths and Anchurage Components
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for Containment Pours Only
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Trumpets, sheaths and anchorage component.s were uriented
!
properly, installed within specified tolerances clear and
free of damage.
(4) Fabrication of Dome Tendon Sheathing Vent Connections
pour No.
Location
Inspection Activity
2-010-040
Containment Dome El
Curing
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363' 1-1/4 - 369' 4-3/4"
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2-010-041
Containment Dome El
Preplacement,
369' 4-3/4" - 375' 3-1/8"
Placement & Curing
2-01C-151,157
Pressurizer Wall
Preplacement and
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Curing
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2-44A-053,056
2T3A&B Tunnels-Walls
Preplacement and
Slab
2-44A-051,052,063
2T3A&B Tunnels-Walls
Preplacement
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N/A
Auxiliary Building
Reinforcing Steel
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Level II-Roof
Installation
No violations or deviations were identified.
]
8.
Containment (Prestressing) - Observation of Work Activities
Unit 1
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(47063C)
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a.
Procedure and Document Review
The inspector reviewed and examined implementation portions of the
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following specification, procedure, and quality assurance manual
pertaining to the installation of horizontal tendons, to determine
whether they comply with applicable codes, standards, NRC Regulatory
Guides and licensee commitments.
!
AX2AF04-100-12
Field Instruction Manual for Installation
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of VSL E5-55 Post-Tensioning System Within
Nuclear Containment Structures, Rev. 9
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- X2AF04-50-5
Horizontal Tendon Elevation-Unit 1 Buttress
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- 1 to #2
IX2AF04-51-4
Horizontal Tendon Elevation-Unit 1
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Buttress #3 to #1
"
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IX2AF04-52-3
Horizontal Tendon Elevation-Unit 1
Buttress #2 to #3
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AX2AF04-78-4
Horizontal Tendon Stressing Data
AX2AF04-79-4
Horizontal Tendon Stressing Data
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b.
Installation Activities
1
The insoector witnessed portions of the installation activities
indicated below to verify the following:
The latest issue (revision) of applicable drawings or procedures
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are available to the installers and were being used.
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Tendons were free of nicks, kinks, corrosion; were installed in
designated locations; and that the installation sequence and
technique was per specified requirements.
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Installation crew was properly trained and qualified.
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QC inspection was properly performed by qualified personnel in
accordance with applicable requirements.'
Adequate protective measures were being taken to ensure mechanical
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and corrosion protection during storage, handling, installation,
,
and post installation.
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)
The following tendons were observed:
t
From Buttress
'
Horizontal Tendon No.
to Buttress
Seq. No.
Activity
69
2 North-3 West
12
Installation
68
1 South-2 East
12
Installation
67
1 North-3 East
12
Installation
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No violations or deviations were identified.
9.
Containment (Steel Structures and Supports) - Units 1 & 2 (48053C)
Periodic inspections were conducted to observe containment steel and support
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installation activities in progress, to verify the following:
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Components were being
properly handled
(included bending
or
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straightening).
Specified clearances were being maintained.
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Edge finishes and hole sizes were within tolerances.
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Control, marking, protection and segregation were maintained during
"
storage.
Fit-up/ alignment meets the tolerances in the specifications and
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drawings.
No violations or deviations were identified.
,
10.
Safety-Related Structures (Structural Steel and Supports) - Units 1 & 2
(48063C)
Periodic inspections were conducted to observe construction activities of
safety-related structures / equipment supports for major equipment outside the
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containment to verify that:
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Materials and components were being properly handled to prevent damage.
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Fit-up/ alignment were within tolerances in specifications and drawing
requirements.
,
Specified clearances from adjacent components were being met.
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Welding Activity Unit 1
The inspector observed in process welding activities and reviewed records
4'
for supports as described below to determ'ne whether applicable codes and
procedure requirements were being met.
Support No.
WPS
Process
Applicable Code
I
1206-003-H005 R/2
IT8-III/I-1-BR-2
SMAW*
AISC & Section III NA NF
VI-1407-094-
IT12-III/1-08-12
SMAW/GTAW**
4
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H601 R/0
1418-042-H613,
IT8-III/I-1-/BR-2
SMAW*
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R/0
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- Shielded Metal Arc Welding
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- GAS Tungsten Arc Welding
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No violations or deviations were identified,
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11.
Safety-Related Piping - Observation of Work and Work Activities - Unit 1
(49063C)(337301)
,
During the inspection period, pipe run walkdowns were performed where piping
installation is near completion to determine whether the piping run is
installed as shown on current, approved drawings and in accordance with
,
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applicable construction specifications. Specific pipe run walkdowns of ASME
B&PVC,Section III, Class II piping are listed below:
1
DWG. No./ Revision
Title
pipe Run Inspected
}
1X4DB133-1, Rev. 15
P&I Diagram
Line No's. 023-18", 004-24",
Nuclear Service
031-18", 390-18", 181-20",
4
Cooling Water System
181-24"
(NSCW) Train "A"
1X4DB135-1, Rev. 16
P&I Diagram-NSCW
Line No's. 174-18", 174-14",
Train "A"
179-14", 180-14", 181-14",
181-16
1X4DB133-2, Rev. 16
P&I Diagram-NSCW
Line No's. 024-18", 032-18",
-
)
Train "B"
034-18", 006-24", 084-18",
086-18", 086-16", 086-14",
,
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087-14", 088-14", 089-14",
)
088-16", 088-24"
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Specific areas examined during the pipe run walkdown for compliance with the
applicable isometric drawings and the Plant Design and Instrumentation
!
Construction Specification No. X4AZ01, Revision 19 were as follows:
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Vent and Drain Connections and Locations
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Instrumentation Connections and Locations
Valve Installation and Orientation
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Line Size and Location
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Fittings Type and Size
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Pipe / Valve / Fitting /End Connections
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Hanger Locations and Types
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During the inspection period the following flushes were observed:
.
- 1-1EF-04, Rev. O, Flow Path 4.7-NSCW Supply & Return to Diesel Train "A"
{
- 1-1EF-04, Rev. O, Flow Path 4.20-NSCW Supply & Return to RHR Train "A"
Pump
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- NSCW Train 8 operation of circulating water from the basis thru the NSCW
tunnel supply header piping bypassing the ACCW and CCW heat exchangers back
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thru the NSCW tunnel return header piping and discharging out into the top
of the basin via a temporary strainer. The purpose of this flow path is to
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circulate the water in the basin thereby cleaning it and the supply and
return header piping prior to starting the NSCW flush.
No violations or deviations were identified,
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12. Reactor Vessel Protection - Unit 1 & 2 (50053C)
The Unit No. 1 inspection consisted of examination of the Reactor Vessel
installed in Containment to determine that proper storage protection
practices were in place and that entry of foreign objects and debris was
prevented.
The Unit No. 2 inspection consisted of examination of the Reactor Vessel
installed in containment to determine that proper storage protection
practices were in place and that entry of foreign objects and debris was
prevented.
No violations or deviations were identified.
13. Reactor Vessel Integrated Head Package - Unit 1 & 2 (50053C)
The Unit No. 1 inspection consisted of examination of the integrated head
package stored on the refueling floor in its designated laydown area to
determine that proper storage protection practices were in place, entry of
foreign objects and debris was prevented, and that access was controlled.
The Unit No. 2 inspection consisted of examinatien of the Reactor Vessel
head with the installed control rod drive mechanisms on the refueling floor
in its designated laydown area. During the assembly of the integrated head
package, proper storage protection practices were observed to be in place
and maintained during the performance of this work.
No violations or deviations were identified.
14.
Reactor Vessel Internals - Unit 1 (50063C)
Periodic inspections were conducted during the inspection period when the
upper and lower internals were stored in their designated storage area to
determine that proper storage protection practices were in place, entry of
foreign objects and debris was prevented and that access was controlled.
No violations or deviations were identified.
15.
Safety-Related Components - Units 1 & 2 (50073C)
a.
The inspector reviewed and examined implementation portions of the
following procedures pertaining to the storage and maintenance
requirements for safety related components to determine whether they
comply with applicable codes, standards, NRC Regulatory Guides and
licensee commitments.
GD-T-09, Rev. 8, Inspection and Maintenance of Items In Storage
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MI-A-13, Rev.
4, Mechanical Equipment Maintenance and Storage
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Program
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10
00851-C, Rev. O, Storage, Handling and Shipping Requirements
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<
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PKF No. JP-518, Rev. O, Instorage Maintenance
AX4AJ06-55-0, Receiving, Installation & Maintenance Manual for
,
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Model "N" Air Handling Units
b.
Observation of Storage Activities
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The inspection consisted of plant tours to observe protection of
installed components to determine that adequate protection f rom dirt,
dust, debris, water, or adjacent construction activities were in place.
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Unit 1 equipment examined included:
Residual Heat Removal Pumps
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Diesel Generators Train A & B
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Containment Spray Pumps
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Auxiliary Feed Water Motor & Turbine Driven Pumps
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NSCW Train A & B Pumps
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Auxiliary Component Cooling Water (ACCW) Heat Exchangers
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Component Cooling Water (CCW) Heat Exchangers
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Battery & Charger Rooms Train A & 0
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Train A Remote Shutdown Panel 1-1605-P5-SDA
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Cable Spreading Room Train A & B
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4160 V Train A Switchgear (1AA02)
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Main Control Board Termination Cabinets Nos. 1-1601-U3-T02, 04,
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06, 08, 10, 12, 14, 16, 18, 20, 22, 24, 26 & 28
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Unit 2 equipment examined included:
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ACCW Heat Exchangers
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CCW Heat Exchangers
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CCW Surge Tank
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Reactor Coolant Pump Casings
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CCW Pump Room Cooler (2-155-A7-012)
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Safety Injection (SI) Pump Room Coolers (2-1555-A7-015 & 016)
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Train A Remote Shutdown Panel (2-1605-P5-SDA)
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During an inspection of the CCW & SI Pump Room Coolers the inspector
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reviewed the following preventative maintenance work orders.
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2-1555-A7-012 CCW Pump Room Cooler
2-1555-A7-015 S1 Train A Pump Room Cooler
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2-1555-A7-016 S1 Train B Pump Room Cooler
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The inspector observed the inplant storage condition of the above
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equipment after review of the above preventative maintenance work
orders.
The inspector noted that the preventative maintenance work
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order for the SI Train B Pump Room Cooler had been signed as being
complete and the chiller portion of cooler had not been cleaned.
The
licensee advised the inspector that this was in error and that what
happened is that the preventative maintenance work order was
accidentally signed off based on the electrical portion of the
inspection being complete and not the mechanical.
The licensee took
immediate action to clean the chiller portion of the cooler, thereby
completing the mechanical portion of the preventative maintenance work
order.
During an inspection of the storage of safety related components in
Units 1 & 2 on September 3, 5, 19, & 20 the following components were
found not being properly protected in accordance with the requirements
,
!
of Paragraph 7.4 contained in GD-T-09, Rev.
8,
Paragraph VI.B.3. f
contained in MI-A-13. Rev.
4,
and Paragraph 7.4.4.g contained in
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00851-C, Rev. O.
Component Identification
As Found Condition
Valve No. 2HY-212B
Valve was lying on floor on the limit
{
switch without cribbing for protection.
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Herculite draped over the valve did not
provide adequate protection from the sand
,
blasting activities in the general area
as
evidenced by grit being on the
exterior valve surfaces.
,
Valve No. 2HY-212C
The air pressure regulator supply line
,
solenoid electric connection junction
!
box, solenoid valve port to atmosphere,
and end connections were not capped.
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Herculite draped over the valve did not
,
provide adequate protection from the sand
!
blasting activities in the general area
as evidenced by grit being on the
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exterior valve surfaces.
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Valve No. 2HY-2168
The solenoid electrical connection
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junction box limit switch electrical
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connection box was not capped. Herculite
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draped over the valve did not provide
adequate
protection
from
the
sand
,
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blasting activities in the general area
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as evidenced by grit being on the
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exterior valve surfaces.
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Valve No. 2HY-216C
Valve was lying on the Air Pressure
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regulator evidenced by a bent bracket.
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Two limit switch electrical connections
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and
solenoid
electrical
connection
junction box were not capped. Valve was
located in middle of walkway with two
pipe support tripods over the top of the
valve where fitters were working on pipe.
Herculite draped over the valve did not
provide adequate protection from the sand
,
blasting activities in the general area
i
as evidenced by grit being on the
exterior valve surfaces.
.
Valve No. HV 8812A
Valve was found disassembled with
!
RWST Suction Inlet
the bonnet portion removed from the
body witnout protection provided to
a
!
the gate.
Train "A" Remote Shutdown
Panel was found with door open with
Panel 1-1605-P5-SDA
no work in progress.
In addition
welding of a support was in progress
,
overhead.
l
The above conditions are -?xamples of failure to provide adequate protection
,
"
to safety related con) con sts during in plant storage in accordance with
existing procedures. This is considered to be in violation of 10 CFR Part 50, Appendix
B,
Criterion V and will be identified as Violation
50-424/85-43-01 & 50-425/85-32-01 " Failure to Provide Adequate Protection to
4
j
Safety Related Components During Inplant Storage".
1
j
16. Electrical (Components and Systems) - Units 1 & 2 (51053C)
Periodic inspections were conducted during the inspection period to observe
safety-related electrical equipment to verify that the installation and
stcrage were accomplished in accordance with applicable requirements. The
following areas were examined at during the inspections:
4
Location and alignment
-
)
Type and size of anchor bolts
-
j
Identification
-
Segregation and identification of nonconforming items
!
-
Equipment space heating
.
-
'
Rotation of motor shafts
-
Lubrication and fluid levels
-
i
Protective coatings, preservations, desiccants, inert gas blanket, etc.
-
The inspector observed in process anchor bolt installation and reviewed
records for an electrical panel as described below to determine whether
applicable code and procedure requirements were being met.
1
)
j
-
!
)
_ __
.
.. _
. .
_
.
.
13
4
Concrete Expansion Anchor
'
Location and Hole Report
Panel Identification
Control Building
1-1623-D5-006A
Display Processing
,
Unit (DPU) Train "A" -Post
Accident Sampling Unit
t
No violations or deviations were identified.
17.
Electrical (Cables and Terminations) - Unit 1 (51063C)
1
Periodic inspections were conducted during the inspection period to
determine whether the raceway installation and protection of installed cable
is in accordance with applicable codes, standards, and NRC Regulatory
,
t
Guides.
In reference to the raceway installation, the following areas were inspected
to verify compliance with the applicable requirements:
Identification
-
Alignment
I
-
Bushings (Conduit)
-
Grounding
-
Supports and Anchorages
-
In reference to the installed cable, the following areas were inspected to
3'
verify compliance with the applicable requirements:
protection from adjacent construction activities (welding, etc.)
-
Coiled cable ends properly secured
-
Unterminated cable ends taped
-
Cable trays, junction boxes, etc., reasonably free of debris
4
-
Conduit capped, if no cable installed
-
Cable supported
-
.
The inspector observed in process cable lugging preparation of the A Train
'
Calvert Bus to the Diesel. Cable cutback of the "W" run cables A-1 and C-1
was witnessed.
Train A and B RHR Pump power terminations were also
witnessed.
'
No violations or deviations were identified.
<
18.
Safety Related Piping (Welding) - Unit 2 (55083C)
Periodic inspections were conducted on Reactor Coolant System Primary Loop
pipe welds at various stages of weld completion.
The purpose of the
inspection was to determine whether the requirements of applicable
specifications, codes, standards, work performance procedures and (QC)
procedures were being met as follows:
1
!
..
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.
-
-
O
~
14
Work was conducted in accordance with a process sheet which identifies
-
the weld and its location by system, references procedures or
instructions, and provides for production and QC signoffs.
-
Welding procedures, detailed drawings and instructions, were readily
available and technically adequate for the welds being made.
-
Welding procedure specification (WPS) were in accordance with the
applicable ASME Code requirements and that a Procedure Qualification
Record (PQR) is referenced and exists for the type of weld boing made.
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That the base metals, welding filler materials, fluxes, gases, and
insert materials were of the specified type and grade, have been
properly inspected, tested and were traceable to test reports or
certifications.
-
That the purge and/or shielding gas flow and composition were as
specified in the welding procedure specification and that protection
was provided to shield the welding operation from adverse environmental
conditions.
-
That the weld joint geometry including pipe wall thickness was
j
specified and that surfaces to be welded have been prepared, cleaned
i
and inspected in accordance with applicable procedures or instructions.
-
That the pipe to be welded to the component was assembled and held in
place within specified gap and alignment tolerances allowed by the ASME
Code.
i
That a sufficient number of adequately qualified QA and QC inspection
-
personnel were present at the work site, commensurate with the work in
progress.
!
That disbursement of welding materials was controlled in accordance
-
with approved procedures.
Installation Activities
The inspector observed the above criteria on the following Reactor Coolant
i
.
System primary pipe welds at various stages of weld out during the
'
inspection period.
Procedure
Joint Con
Weld Out Stage
ISO No.
Weld No's.
No.
Figuration
Code
Inspected
2K4-
106-W-02
IT1-III/I
Capped, grinding
!
1217-067-
Steel K-
CL II,
for Visual
01,R/2
Insert
III
Inspection
i
!
_ . . . . _ _
_-
___ _
_
___.-.._-_ _ _ ___ _ _ ___ -_ _ _ ,,__ _ ______,__
____
._
-
.
-
15
Procedure
Joint Con
Weld Out Stage
ISO No.
Weld No's.
No.
Figuration
Code
Inspected
2K4-
216-W-105, 24-III/I
1" Stainless ASME
Fit-up, Observed
1202-216-
106,107,
Socket
III,
Marking for
01,R/4
108
CL II Socket Enlargement
2K4-
24-III/I
8" Stainless ASME
Root
1206-008-
Steel K-
III,
10
Insert
CL II
2K4-
216-W-05
24-III/I
8" Stainless ASME
Fit-up, K-Insert
1202-216-
Steel K-
III,
01,R/4
Insert
CL II
2K4-
007-W-24
24-III/I
10" Stainless ASME
Final Tacked -
1206-007-
Steel K-
III,
Repair Grind
08,R/3
Insert
CL II Thru Wall
No violations or deviations were identified.
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- - -
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