ML20137A936
| ML20137A936 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/31/1985 |
| From: | Constable G, Garrison D, Clay Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20137A817 | List: |
| References | |
| 50-498-85-13, 50-499-85-13, IEB-83-06, IEB-83-6, IEIN-83-07, IEIN-83-7, IEN-83-7, NUDOCS 8511260142 | |
| Download: ML20137A936 (17) | |
See also: IR 05000498/1985013
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APPENDIX B
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-498/85-13
CP: CPPR-128 and.129
50-499/85-13
Docket:
50-498 and 50-499
Licensee: Houston Lighting & Power Company (HL&P)
P. O. Box 1700
Houston, Texas 77001
Facility Name: South Texas Project, Units 1 and 2
Inspection At: . South Texas Project, Matagorda County, Texas
.-Inspection Conducted: August 5 - September 27, 1985
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Inspectors:
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C. E. Johnson, Senior Resident Inspector
.Date
Project Section C, Reactor Projects Branch
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D. L. Garrison, Resident inspector
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Project Section C, Reactor Projects Branch
Approved:
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G.'L. Constable, Chief, Project Section C
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Reactor Projects Branch
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Inspection Summary .
Inspection Conducted August 5 - September 27, 1985 (Rer:,rt 50-498/85-13;
50-499/85-13
Areas Inspected:
Routine, unannounced inspection of licensee action on
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previous inspection findings, IE Information Notices and IE Bulletins,
protective coatings, spent fuel storage racks, reactor vessel internals,
post-tensioning system, and pipe supports. The inspection involved
384 inspection-hours onsite by two NRC inspectors.
Results: Within the scope of this inspection, one violation was identified and
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is discussed in paragraph 10.
8511260142 851112
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DETAILS
1.
Persons Contacted
Principal Licensee Employees
E. Hill - Project Compliance Engineer
'*F. White, Lead Project Compliance Engineer
K. O'Gara, Project Compliance Engineer
- R. R.'Hernandez, Supervisor, Project Compliance
F. Alkov, Material Control Supervisor
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- L.'Dolan, Project Compliance Engineer
M. McDaniels, QA
- R. Daly, Startup Manager
- A. G. Peterson, Startup
- T. J. Jordan, Project QA Manager
- D. R. Keating, Operations QA General Supervisor
- J. T. Westermeier, Project Manager
- R. C. Arthurs, Project QA General Supervisor
- M. S. Whittaker, Metrology Lab Supervisor
- W. H. Kinsey, Plant Manager
- S. M. Dew, Deputy Project Manager
Other Personnel
Bechtel Power Corporation (Bechtel)
B. Bittner, Design Engineer
- N. A. Joonejo, Engineering Group Supervisor
F. W. Joyce, Quality Assurance Engineer
Al Dansman, Civil Engineer
G. A. Koch, Contract Administrator
L. Vaupel, Site Coatings Engineer
B. Fultz, Coatings Engineer
M. Peters, Coatings Engineer
8. Nilius, QA
- L. W. Hurst, Project QA Manager
- R. D. Bryan, Deputy Project Manager, Construction
- R. Schulman, Site Civil Engineer
- J. B. Gatewood, Project QA Engineer
- J. T. Minor, Deputy Site. Engineering Manager
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Ebasco Services, Inc. (Ebasco)
D. Calsyn, Mechanical Supervisor
C. Murray, Lead QC, Pipe Supports
C. Sist, Supervisor Pipe Supports
J. Tucker, QC, Pipe Supports
- A. M. Cutrona, QA Manager
- R. M. Zaist, Construction Manager
Prescon Corporation (Prescon)
W. Schneider, Quality Control Supervisor
G. Jewel, Project Manager
H. Williams, Corporate Quality Manager
D. Berthier, Director of Engineering
C. Hahn, Welding Engineer
- Denotes those individuals attending the exit interview conducted on
October 3, 1985.
2.
Site Tour
The NRC inspectors made several site tours in order to assess the general
cleanliness and housekeeping activities, condition of equipment, and plant
status.
The following parts of the plants were inspected:
containment
buildings, mechanical / electrical auxiliary buildings, fire protection
diesel pumphouse, and fuel building Unit II.
No violations or deviations were identified.
3.
Licensee Action on Previous Inspection Findings
(Closed) Unresolved Item 8412-01:
This item concerns the purchasing of nonconforming material from Tube-Line.
An evaluation was performed by the NRC inspector and it was detennined
that none of the items of concern were supplied to the project. This item
was determined not to be a violation of NRC requirements. See para.10 below.
'(Closed) Open Item 8506-02:
This item concerns the material test report traceability of the
Units 1 and 2 6 X 6 spent fuel storage racks. Thisitem(8506-02)
is closed.
It has now been escalated to a violation (8513-01).
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(Closed) Unresolved Item 8209-09:
This item concerned lack of supporting documentation for (120) 1 1/2"
and (32) 2" ASTM A540 Grade B23 class 3 nuts. The required documentation
has been received by HL&P and is acceptable to the NRC inspector. A
supplemental requirement of the purchase order for MT or PT testing has
been deleted and documented in a nonconformance report. The item is
considered closed and was determined not to be a violation.
(Closed) Violation 8324-02:
This item concerned the testing of soils, in which a scoop was used in
lieu of a funnel device.
Prefiled testimony given to the Atomic Safety
and Licensing Board indicates that all affected relative soil density
tests were recalculated after incorporating the reduction in relative
density and were found to be within the specified criteria. Testing is now
in full accordance with the procedures.
4.
Licensee Action on IE Bulletins
(Closed) IE Bulletin 83-06:
This item pertained to Tube-Line (see also URI 8412-01 above). HL&P
action on this IEB was reviewed by the NRC inspector and found to be
acceptable.
5.
Licensee Action on IE Infonnation Notices
(Closed) IE Information Notice 83-07:
This item pertained to Tube-line (see URI 8412-01 andIEB83-06above).
HL&P action on this Information Notice was reviewed by the NRC inspector
and found to be acceptable.
6.
Protective Coatings
The NRC inspector reviewed the protective coatings system applied to
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Units 1 and 2 containment steel liner plate. The purpose of this
review was to determine if the system was DBA (Design Basis Accident)
qualified and if the procedures and specifications were in accordance
with: NRC regulations, FSAR, ANSI coc'es and manufacturer's application
instructions.
Unit l's initial coating system was removed down to the steel substrate
from all surfaces except those inaccessible areas such as behind installed
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HVAC ducts. The containment liner was then coated with a two-coat epoxy
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system (Amercoat 90/Amercoat 90). The initial coating system for lfnit I
was Dimetcote 6 primer with Amercoat 90 topcoat. This system is still
applicable for Unit 2.
The NRC inspector was informed by the Bechtel
coatings engineer that the Unit 1 initial coating system was removed
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because Brown & Root (B&R) had problems with the application of Amercoat
90 over the Dimetcote 6 primer, and that PDM, the steel liner fabricator,
had lost the documentation for the primer that they had applied. B&R then
elected to remove the Dimetcote 6/Amercoat 90 system and replace it with
the two coat epoxy system.
The NRC inspector reviewed the DBA test results on the
Dimetcote 6/Amercoat 90 and the Amercoat 90/Amercoat 90 protective coatings
system. The test rest.lts were acceptable for the required mil thickness
utilized at STP.
The NRC inspector compared DBA test results for the two systems
described in the specification. The specification requirement was in
accordance with the required mil thickness as used in the DBA test.
Review of the QC procedures and specification appear to be adequate.
Documents Reviewed
DBA Documents (Amercoat 90/Amercoat 90)
. LSR 2206
(12/17/75)
. LSR 2408 A-1 (1/20/77)
. ORNL Log Book No. A7562; 1-12-6 (3/9/76)
. ORNL Log Book No. A7562; 2-28-7 (3/28/77)
. ORNL Log Book No. A9675; A9-22-2 (9/30/82)
DBA Documents (Dimetcote 6/Amercoat 90)
. Test Report No. 2585 (7/2/79)
. ORNL Log Book No. A7562; A7-9-9 (7/24/79)
. ORNL Log Book No. A7562; A7-16-9 (7/24/79)
Test Report LSR 2206, 2207 (5/27/76)
Procedures / Specification
. QCP-10.8, " Protective Coatings Inspection," Revision 5, dated 4/26/85
. TPNS SA819A1001, " Painting and Coating," Revision 2, dated 1/25/83
. Specification #3C080AS1007, " Technical Specification for Field
Coating of Surfaces Inside the Reactor Containment Building,"
Revision 11, dated 5/9/85.
No violations or deviations were identified.
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7.
Reactor' Vessel Internals
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- The NRC inspectors reviewed procedures for the rigging and setting of
.the Unit 2 reactor vessel lower and upper internals.
The procedures
were adequate.
.The NRC inspectors observed the craftsmen attaching the rigging to
the upper internals storage frame in the storage yard.
The NRC
inspector did not observe the upper or lower internals being lifted
on to the trailer.
The NRC inspector observed that protection requirements for the Units 1
and 2, unit reactor pressure vessel and internals were met.
Units I and 2 reactor vessel and internals were properly covered to
prevent entry of foreign objects and debris.
Platforms and
scaffolding around the vessel were nonflammable or treated to prevent
spread of accidental fire.
Documents Reviewed
. CSP-63, " Rigging for Setting the Reactor Head," Revision 0, dated 9/14/84
(Unit II)
. CSP-64, " Rigging for Setting Unit II Reactor Internals," Revision 0,
dated 2/5/85
. ICP-Nos. 3 and 4, '" Rigging for Setting Unit II Reactor Internals,"
Revision 0, dated 2/5/85
No violations or deviations were identified.
8.
Post-Tensioning System Unit 1
The containment is a post-tensioned, reinforced concrete structure in
the shape of a vertical cylinder with a hemispherical dome and flat base.
The cylindrical portion and half of the dome are prestressed with tendons
in the horizontal direction utilizing three buttresses equally spaced at
120 degrees. The dome is prestressed with tendons in the vertical direc-
tion; these tendons extend over the dome and are anchored in the tendon
gallery beneath the base mat. The installation is basically as follows:
~ hop fabricate and ship the tendons to the site, place the tendons into
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the preinstalled sheathing, prepare the tendon ends for stressing, stress,
install a corrosion inhibitor and cover.
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The purpose of the inspection was to assure that the design and regulatory
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requirements are carried out in fabrication, installation and stressing
operations,
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a.
Procedures Review
(1)
FSAR/ Specification
The FSAR in Section 3.8 outlines the requirements for the
materials to be used in construction, installation, stressing
and greasing.
The NRC inspector has verified that these items
are addressed in the engineers specification (Bechtel) 2C239CS003
and are further defined in the fabricator / constructors (Prescon)
Quality Assurance and Quality Control procedures.
The FSAR also
detailed the program for in service surveillance.
(2) Specification / Quality Procedures
The specification noted above was compared to the Quality
Control-Quality Assurance procedures for inclusion of require-
ments.
The engineering design requirements as previously noted,
were included in the Prescon procedures.
The specification was
noted to address deflection of tendons around the hatches or
The fabricator / constructors' programs were observed to include
the requirements in detailed written procedures addressing each
area'of fabrication, Quality Assurance and Quality Control.
The
areas 'specifically reviewed were fabrication of washers, shop
buttonheading, corrosion protection and shipping, installation
of the tendon into sheathing, protection, field buttonheading,
stressing and sequencing, greasing, capping and QC records.
(3)
Audit Programs
The licensee was noted to have an audit plan that included
a major audit of Prescon.
Audit S12-501 of Bechtel and Prescon
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is scheduled for September 30, 1985, by the licensee.on-site QA
group.
The construction manager (Bechtel) is required by contract
to perform frequent surveillances of the fabricator's shop.
Quality Surveillance Reports QSR 11 and 19 were reviewed by the
NRC inspector and were found to be detailed, including hold
points and type of inspection or examination, with references to
the inspection requirement document.
A programmatic audit of Prescon, on site, by Bechtel QA was
reviewed and it was noted that the auditor had issued five
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site deficiency reports. At this writing, Prescon had responded
to each_ item, however, the implementation of corrective action
had not been verified.
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.Bechtel has an ongoing surveillance of on-site work
,d QC
activities.- The.NRC inspector reviewed the survei.(_nces by.
Bechtel site QC for adequacy and effectiveness.
(4)
Documents Reviewed
. South' Texas Project FSAR through Amendment 50
Concerning Tendons
.'Bechtel Specification 2C239CS003 Revision 4,
" Containment Post-Tensioning System"
. Prescon " Quality Assurance-Manual," Revision 9
. Prescon " Shop Fabrication Procedures," Revision 4A
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. Prescon " Field Quality Control Procedures," Revision ~3
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. Prescon ." Vertical and Horizontal Tendon Installation
Procedures"
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. Prescon "Q.C. Procedure for Cleaning and Checking
Post Tension Embedded Items," Revision 1
. ASTM-A421 " Uncoated Stress-Relieved Wire for
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Prestressed Concrete,"_1965
. ASME Section III Division 2 Essential Variables in
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Prestressing Element Materials
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. Construction drawings and plans for the system and
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other documents relating to the work.
. Qualification tests for the tendon system
b.
Engineering / Tests
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(1)
Wire Relaxation Test
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A minimum of three relaxation test of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> duration
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are required in accordance with the requirements of ASTM
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E-328, " Standard Recommended Practice for Stress-Relaxation
Tests for Materials and Structures." -The package which
included mill test reports, stress-strain curve, and
relaxation curves was complete.
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(2)
Dynamic Tests-Tendons
Dynamic tests are required to be performed on the anchorage units
and tendon and shall duplicate the behavior of the full size
tendon.
The testing is required to be performed on specimens
having at least 10% of the full size prestressing steel area of
the proposed production tendon.
One test is to be 50 cycles of
stress varying from 40% to 80% of the unit's ultimate tensile
strength.
The second test, is 500,000 cycles of stress from
60% to 66% of the unit's ultimato tensile strength.
The test
report reviewed was atlequate for methods, calculations, set-up
and supporting documentation.
(3)
Static Test - Stressing Washer
In this test, the specification requires a test assembly con-
sisting of standard manufacture anchorage units and a full size
tendon not less that 10 feet long.
All items are to be identical
in material and manufacture as those proposed to be supplied in
this work.
In lieu of special test programs of static and
dynamic tests on tendon units, the contractor may supply certi-
fied data from previous tests on like units.
(4)
Static Test-Tendon
The specifications require that a test assembly, consisting of
standard manufactured anchorages and tendons of full size and
not less that 10 feet long, be tested to destruction in order to
prove the materials and system design.
Certified data from pre-
vious like tests are acceptable.
The NRC inspector reviewed
three reports of tests performed at Prescon in 1974.
The testing
was witnessed by a third party as required in addition to
Prescon and Bechtel representatives.
The reports reviewed were:
(a) Test #1100H186-ll, Revision 1, test date 7/19/74
Static Test - Tendon
(b) Test #1100H186-3, test date 8/19 - 20/69
Static Test - Stressing Washer
(c) Test #1100H186-3, test date 8/19 - 20/69
Static Test - Bearing Plate
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(5)
Static Test - Bearing Plates
The specification requires that the material for bearing
-plates be tested with the tendon in a series of static
tests. The material is required to be manufactured to ASTM
A633 grade E or equivalent.
Review of the test data for
the bearing plates indicate that the test material meets
the ASTM requirements; also the test data, method and
recording appear to be adequate.
(6)
Grease Test
The specification requires that test data for the sheathing
filler grease meet specific requirements.
The NRC
inspector reviewed a report from Viscosity 011 Company and
a grease test report and determined that the requirements
for the compound used (Visconorust 2090P-4) meets the
requirements of the specification.
c.
Work Observation
(1)
Receiving
The NRC inspector observed the receipt of tendons on two
occasions in August and September and it was found that the
tendons were adequately wrapped and coated with preservative
grease. The unloading was performed with adequate assurance
against damage.
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(2) Storage
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The laydown storage of the tendons from receipt until install-
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ation was found to be adequate during several inspections.
(3)
Installation
The complete installation of two tendons was observed during the
inspection, additionally, partial inspectio'ns were made of
others. The two installations inspected were 1-H-094 and
2-H-087.
The documentation was reviewed and was complete.
(Tendon Installation Card)
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Buttonheading
The work process of buttonheading was observed on the field
-made end on 1-H-028 and 1-H-022.
This is a process of
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upsetting or deforming the wire end so as it cannot go through
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the hole in the stressing washer.
The Prescon QC inspector
examined 100% of the buttonheads for splits or defects and
checked each for size with a go-no go gauge.
The tendon ends
were greased and tne wire was pulled up to the washer face and
the entire unit was pulled into the trumplate.
It was noted that the wire used by Prescon makes unusually
good quality buttonheads with near zero defects.
The temporary
cover and weatherproof gasket was installed and work proceeded
to the next station.
The documentation (Tendon Buttonheading
Card) was examined and found to be complete.
(5)
Tendon Stressing
Tendon stressing was performed on approximately one-third of the
horizontal tendons from the number two buttress during the
inspection.
One-half of the verticals have previously been
stressed.
A review of the process and records was made and it
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was noted that the stressing cards are completed and include the
required data which reflected the actual work effort.
On
completion of the stressing the protective can and gaskets were
affixed and tightened.
(6)
Greasing
The-greasing operation was observed on several occasions and in
detail'on two tendons (2-H-063 and 2-H-045).
The grease was
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pumped from the tank at 40 PSI (150 max) at 210 F (250 F max),
the air was bled off and the casing was filled and sealed off.
No spills have been or were observed and the records (Tendon
Greasing Cards) were reviewed and were found to be complete.
(7)
Calibration
During the reporting period, many instruments were checked
for reading and calibration interval and due date.
No discre-
pancies were noted concerning this item.
(8)
Cans
The tendon cans were inspected and found to be fabricated as
required.
(9)
Inspectors
Prescon provides an adequate number of inspectors (4) to the
job.
In conversation with inspectors, and also review of
inspector qualifications and training records, it was observed
that the inspection process is being accomplished by adequately
trained and knowledgeable personnel.
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d.
Records
(1)
Procedures / Records
A review of the procedures by the NRC inspector revealed that
there are an adequate number of forms to be completed into
records covering all aspects of the program from receipt to
greasing.
(2)
Vendor Surveillance Records
Two packages of Bechtel vendor surveillance reports (QRS 11 and
19) were reviewed for adequacy and it was noted that the inspec-
tor was descriptive of the items inspected, including reference
requirements, type of inspection and results, and the identifica-
tion of the hardware; i.e., tendons, shims, washers, and grease
caps.
Also included was Prescon's certificate of conformance
and shipping documents.
(3)
Shipping / Receiving Records
The basic shipping and receiving records in seven record packages
were reviewed for materials shipped to the site.
The records
included stressing washer mill test reports Nos. H-917 and H-918;
-these two reports were for AISI.4330 modified steel. The required
elements, including mechanical and chemical properties, heat
treating, hardness and impact test were reviewed. Wire mill test
reports for Shinko Wire Co., specifically mill test
reports KA0490, KB7023, KB7473, KC2585, KA1419, and KC2920, were
reviewed for process, chemistry,. narking, grade, physical
properties and stress / strain curves.
The reviewed reports were
adequate and meet the specification requirements.
(4)
Receiving Records - Grease
The records for the grease were compared to the FSAR, Bechtel
specification, Prescon procedures, and ASME Code and it was noted
that the required tests were performed and properly documented
for Visconorust 2090-P-4 lot 5-6894.
(5)
Training Records
The training records for a level II inspector for Prescon
was examined.
The attributes covered were:
(a) Testing - which included assignments and tests covering
receiving, cleaning and checking, installation, button-
heading, greasing and stressing and protection.
All of
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the documents reviewed indicated that the test was of
significant depth to assure that a person was qualified to
inspect the work if he had a satisfactory score on the test.
(b) On the job training - records were available to indicate
and record on the job training in the area of cleaning,
receiving, installation, buttonheadings, stressing,
greasing and calibration.
Also, ample records were on file
to record past work experience on resumes.
(6)
Calibration Records
For the records examined, each point on the inspection forms
would have an annotation for the measuring and test equipment
used.
There are approximately nine items in the calibration
program and are buttonhead and eccentricity gauges, torque
wrenches, pressure gauges, micrometers, calipers, stressing
jack / gauges, and thermometers.
The units are required to be
checked against national standards.
No discrepancies were
noted.
(7)
Completed Records Packages-Tendons V109, V127, V207, V223,
V235, V247
Completed record packages for six vertical dome tendons were
examined for completeness.
These packages include the fabri-
cation record, mill tests for the washer and wire including back
up data.
Hold points are noted throughout the fabrication
process traveler and all applicable hold / inspection points were
signed off.
Prescon deficiency and disposition report and supplier deviation
disposition requests were included in the package under the
appropriate heading and were completed and in order.
The
following reports are required by the procedures and follow the
order of the work process.
These records are:
Tendon Receiving Card - Nine attributes are recorded, checked
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and signed off; an attachment is the quality verification
documents requirements sheet.
Tendon Void Check - This document records the check for
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obstructions, clearance and cleanliness; each of which was
signed off as completed except for three columns that were
not applicable.
Trumplate Assembly Check - Cleanliness, bolt holes, sealing
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and protection are completed for this item.
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Vent and Drain Check - Form properly filled out--vent
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only applies here.
Tendon Installation Card - This checklist records the
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results of installing the tendon into the sheathing and
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spacing it on each end.
All attributes were indicated
acceptable and checked.
Temporary Tendon End protection - After the tendon is
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inserted there is a time interval before stressing,
therefore the protruding ends must be covered; this form
indicated that the work was performed.
Tendon Buttonheading Cord Field End - The 186 buttonheads
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are made and checked with a go-no go gauge for concentricity
and splits. This form provides for 10 inspection attributes,
each of which was satisfactory.
_ Tendon Stressing Card - These cards contain dimensional
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data on slack pressure, gauge pressure, elcr.gation,
shimming and actual lift off or actual load. The cards
were noted to be ccn.pleted.
Grease Can Installation Card - This card indicates that
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the can, "0" rings, and bolting is satisfactory.
Tendon Greasing Card - This card contains 10 items of
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inspection in greasing; mainly, the grease, its
temperature, pressure and cycle through the tendon void and
capping.
In this and previous cards, measuring and test
equipment used was noted on the cards.
e.
Summary
During the review of the engineering test and qualification data and
the comparison of the specification /FSAR/ procedure requirements, scre
minor concerns were noted and are included in the body of this report.
The items of concern were promptly responded to and the corrective
actions were acceptable to the NRC inspector.
The Prescon program for tendon installation appears to be functioning
as required as no items of significance were observed in the
fabrication, work process, Quality Control or records.
No violations or deviations were identified.
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9.
Safety-Related Pipe Supports / Restraint Systems
The purpose of this inspection was to determine the following:
Whether technical requirements are detailed or referenced in the
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FSAR with safety-related pipe supports / restraints, and have been
adequately addressed in construction specifications, drawings
and work procedures.
Whether QA plans, instructions, and procedures for
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safety-related pipe supports have been established in the QA
Manual.
Through direct observation and independent evaluation of work,
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whether the licensee's work control system is functioning
properly and whether the installation of safety-related pipe
supports /restrair.ts are in compliance with licensee
specification and procedures.
a.
Procedures / Specification
The NRC inspector reviewed procedures and specifications to
determine whether technical requirements were detailed and
adequately addressed.
The procedures reviewed contained some
technical requirements but mainly referenced the pipe support
specification and manufacturer's instruction.
The specification
did contain adequate inspection criteria for purposes of
inspection and installation.
The FSAR contained technical
requirements mainly for the design and stress analysis for
safety-related piping and pipe supports. Work procedures and
specifications were determined to incorporate controls to ensure
that: type and classification of pipe supports / restraints
systems comply with approved drawings, preinstallation and
in process inspections are performed at the appropriate time,
means to ensure that bolts, nuts, and washers are of the proper
type and correctly installed, and minimum bolt embedment and
thread engagement criteria are imposed.
The procedures / specifications that were reviewed are adequate.
Documents Reviewed
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QCP 10.12 " Component Support Fabrication & Installation
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Inspection," Revision 4, dated 6/17/85
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Specification 4L360JS1000 " Specification for Pipe Supports
for ASME III Piping," Revision 4, dated 4/4/85
Specification SL340JS1002 " Pipe Stress and Support
.
Construction Specification," Revision 7, dated 7-1-85
b.
Observation of Work and Work Activities
The NRC inspector visually examined 21 pipe supports of the Essential
'
Cooling Water (EW) system.
These supports had previously been
QC-accepted.
The purpose of this inspection was to determine if the
pipe supports installed were installed per the current design
drawings, procedures and specifications.
Review and examination of these supports by the NRC inspector
indicated correct configuration, alignment and installation, with
one exception.
Pipe support #EW-9129-HL5003 contained two
discrepancies.
(1) NF welds shown on the drawing indicated 3/8" fillet
welds, the actual field weld was 1/4".
(2) The design drawing indicated a UH9 strap; actual field
installation indicated a UH9 A strap which is larger.
Investigation by the NRC inspector indicated that, shortly before
the final acceptance by QC, a new revision was issued.
It
appears that the field revision list (FRL) possibly did not get
into the hands of the QC inspector.
There was an NCR issued on
this support.
The NRC inspector has determined that this
discrepancy was an isolated case.
Documents Reviewed
EW-9114-HF5007
EW-9229-HL5005
.
.
EW-9113-HF5006
EW-9229-HL5003
.
.
EW-9114-HF5005
EW-9129-HL5001
.
.
EW-9114-HF5006
EW-9130-HL5003
.
.
EW-9114-HF5002
EW-9107-HL5008
.
.
EW-9113-HL5003
EW-9129-HL5003
.
.
EW-9130-HL5002
EW-9114-HL5001
.
.
EW-9114-HL5003
EW-9130-HL5001
.
.
EW-9329-HL5003
EW-9130-HL5006
.
.
EW-9107-HL5003
EW-9113-HL5001
.
.
EW-9330-HL5003
.
No violations or deviations were identified.
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10. Spent Fuel Storage Racks
A follow up on open item 8506-02 was performed by the flRC inspector.
Westinghouse was requested to provide traceable material test records
for the STP spent fuel storage racks to ensure proper fabrication and
use of materials. Certified material test records (CMTRs) for requested
shop orders were reviewed by the NRC inspector with the referenced
Westinghouse drawings.
It was determined that the STP spent fuel racks
could not be directly tied to the provided CMTRs.
Documentation was obtained from Westinghouses' Pensacola Operations by
Westinghouse personnel.
However, it was determined that material trace-
ability for eight (8) components used in the fabrication of the
6 X 6 fuel rack for Units 1 and 2 could not be determined.
It appears
that the eight components were surplus materials obtained from other
purchase orders and were not properly identified on travelers for those
components. Open item 8506-02 will be closed and escalated to a violation.
This is an apparent violation.
(8513-01)
11.
Exit Interview
An exit interview was conducted on October 3, 1985, with those
personnel denoted in paragraph 1 of this report. During the exit
interview, the NRC inspectors summarized the scope and findings of
this inspection.
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