ML20151A521
| ML20151A521 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 07/05/1988 |
| From: | Barnes I, Gilbert L, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20151A512 | List: |
| References | |
| 50-498-88-36, 50-499-88-36, NUDOCS 8807200025 | |
| Download: ML20151A521 (8) | |
See also: IR 05000498/1988036
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APPENDIX B
U.S.-NUCLEAR REGULATORY COMMISSION
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REGION IV
NRC Inspection Report:
50-498/88-36
Operating License:
HPF-76
50-499/88-36:
Construction Permit:
CPPR-129
Dockets:
50-498
50-499
Licensee:
Houston Lighting & Power Company (HL&P)
P.O. Box 1700
Houston, Texas 77001
Facility Name:
South Texas Project (STP), Units 1 and 2
Inspection At:
Inspection Conducted: May 16 through June 17, 1988
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Inspectors:
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g@< L. D. Gilbert, Reactor Inspector, Materials
Date
and Quality Programs Section, Division of
Reactor Safety
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(. L )W \\lll
,/rks
W. M. McNdill, Reactor Inspector, Materials
Date '
and Quality Programs Section, Division of
Reactor Safety
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7-I-FF
Approved:
es
1. Barnes, Chief, Materials and Quality
Date
Programs Section, Division of Reactor
Safety
Inspection Summary
Inspection Conducted May 16 through June 17, 1988 (Report 50-498/88-36)
Areas Inspected: No inspection of Unit I was conducted.
Inspection Conducted May 16 through June 17, 1988 (Report 50-499/88-36)
8807200025 88070s
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! Areas I.ispected:
Routine, unannounced inspection of preservice inspection'of
- comprnents and component supports.-
.Results:-.Within the area inspected, one violation was identified ~-(failure to
promptly identify nonconformances, paragraph 2.d)~.
Two unresolved items are
identified in paragraphs 2.c and 2.d.
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DETAILS
1.
Persons Contacted'
HL&P
- J. T. Westermeier, Project Manager
- J. E. Geiger, General Manager, Nuclear Assurance
- L. Giles, Operations Manager', Unit 2
- D.- R. Keating, Quality Engineering Manager
- M. A. McBurnett, Operations Support Licensing Manager
- R. L. Beverly, PSI /ISI Supervising Engineer
- J. Haning, Systems Engineering Group, Senior _ Engineer
M. Stewart, PSI Coordinator-Supports
W. Isereau, Operations Quality Assurance Supervisor
D. Murdock, ISI Coordinator-Piping-
Bechtel Engineering Corporation (BEC)
- R. W. Miller, Project Quality Assurance Manager
- R. H. Medina, Quality Assurance Supervisor
F. Almeida, Engineering ABR Group Supervisor
Southwest Research Institute (SwRI)
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R. A. Fougerousse, PSI Project Engineer
J. C. Younger, Research Engineer
Kemper Group
B. R. Russell, Authorized Nuclear Inservice Inspector (ANII)
The NRC inspectors also interviewed other contractor personnel during
the inspection.
- Indicates the personnel that attended the exit meeting.
2.
Preservice Inspection.
a.
Review of Program (73051)
The NRC inspectors reviewed the licensee's program pertaining to the
preserviceinspection(PSI). The following documents were reviewed
for conformance with the requirements of 10 CFR Part 50.55a(g) and
Section XI of the ASME Boiler and Pressure Vessel Code.
Interdepartmental Procedure No. 3.04Q, Revision 0, "Preservice
and Inservice Inspection Program."
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Operations Engineering Procedure No. 9.04Q, Revision 0,
"Personnel Certification Procedure for Visual Examination per
ASME B&PV Code,Section XI."
Unit 2 PSI Weld Examination Plan, ST-HL-AE-2178, dated May_14,
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1987, with changes 1 through 14.
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PSI Examination Plan for Component Supports-Unit 2,
ST-HL-AE-2514, dated March 9, 1988.
PSI Examination Plar, for Steam Generator Tubes (Unit 2),
ST-HL-AE-2020, dated April 13, 1987.
Mechanized Scan Plan for PSI of Unit 2 RPV, ST-HL-AE-2274, dated
June 23, 1987.
SwRI Plan 84-HLP-STP-1-1-0, Revision 0 Change 5, "Project Plan
for the Preservice Examination of South Texas Project Electrical
Generating Station, Units 1 and 2."
SwRI Project 17-1480, "Examination _ Plan for the Preservice
Inspection of Selected Class 1 and Class 2 Components of the
South Texas Project Electric Generating Station, Unit 2."
SwRI Nuclear Quality Assurance Program Manual, Revision 2,
Change 13.
Interdepartmental Procedure No. 3.07Q, Revision 3, "ASME
Section XI Repair / Replacement Program."
Specification No. SUO36JS0002, Revision 0, "Specification for
Preservice Inspection of Component Supports of South Texas
Project Electric Generating Station-Unit 2."
Records of licensee Quality Assurance (QA) audit and surveillance of
PSI activities were reviewed by the NRC inspectors.
From this
review, the NRC inspectors found that the vendor (Conam) for eddy
current testing of steam generators had been audited (Audit Report
No.88-122) and the vendor (SwRI) for PSI of vessels and piping had
been subjected to QA surveillance (Surveillance Report No. 87-08).
The NRC inspectors also ascertained that com)onent supports PSI for
Unit 2, which is performed by the licensee, lad not been the subject
of audits or surveillances. Licensee personnel informed the NRC
inspectors that it was planned to perform such after hot functional
testing.
The NRC inspectors observed that approximately 75 percent
of the component supports had been already inspected and that the
post hot functional testing inspection would be limited to
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observation for damage. The licensee agree 6 to review this
information and assure itself that PSI of component supports would
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indeed be the tubject of surveillance or audit.
No violations or deviations were identified.
'b.
Review of Procedures
(73052)
The NRC inspectors reviewed the following procedures:
Mechanized Ultrasonic Inside Surface Examination of Ferritic
Vessels Greater Than 2.0 Inches In Thickness. SwRI-NDT-800-120
Revision 0.
Manual Ultrasonic Examination of Austenitic Thin Wall Pioing
Welds, SwRI-NDT-800-36, Revision 37.
Dry Powder Magnetic Particle Examination, SwRI-NDT-300-1,
Revision 33.
Solvent-Removable Liquid Penetrant Color Contrast Examination,
SwRI-NDT-200, Revision 69.
Visual Examination of Nuclear Plant Components, SwRI-NDT-900-7,
Revision 11.
VT-3 Visual Examination of Component Supports, OEP-9.05Q,
Revision 1.
VT-4 Visual Examination of Component Supports, OEP-9.06Q,
Revision 1.
Multifrequency Eddy Current Drocedure Westinghouse Series E2
Steam Generator Tubing MIZ-18 Digital Eddy Current System South
Texas Project, Conam-42-EC-153, Revision 0.
Motorized Rotating Probe Procedure for Westinghouse Series E2
Steam Generator Tubing Expansion MIZ-18 Digital Eddy Current
System South Texas Project, Conam-42-EC-156, Revision 0.
Guidelines for Data Analysis of MIZ-18 Data Utilizing DDA-4
Digital Data Analysis System Bobbin Coil Examination Sot.th Texas
Project, Conam-42-DA-011, Revision 2.
Guidelines for Data Analysis of MIZ-18 Data Utilizing DDA-4
Digital Data Analysis System Motorized Rotational Probe Exam of
Support Plate Expansions South Texas Project, Conam-42-DA-014,
Revision 0.
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The procedures were reviewed for their conformance to the
requirements of ASME Code and the established plans. The ANII log
was inspected to verify his review of the procedures.
-No violations or deviations were identified,
c.
Observation of Work Activities
(73053)
The NRC inspectors reviewed the PSI plans to ascertain whether the
licensee's PSI program met the Safety Analysis Report for number of
items to be inspected, methods of examination, and extent of
examination <
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The qualifications and certifications of 2 Level I, 21 Level II, and
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1 Level III examination personnel were reviewed by the NRC inspectors
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which included personnel for visual, liquid penetrant, ultrasonic,
and eddy current examinations.
The NRC inspectors observed the following examinations that were
performed as required by the Unit 2 PSI examination plans for
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components and component supports.
Liquid penetrant examination of Weld Exam 28 on Line 16-SI-2101,
a reactor containment sump suction line for the safety injection
piping system.
Visual examination, augmented PSI VT-3 and VT-4, of component
support SI-2301-SS05 for the safety injection piping system.
Visual examination, augmented PSI VT-3, of component support
SI-2306-HL5012 for the safety injection piping system.
Visual examination, PSI VT-3, of component supports SGCIA.
SGC2A, SGC3A, and SGC4A for steam generator "A."
Visual examination, PSI and augumented PSI VT-3 and VT-4, of
component support CC-2105-HL5004 for the component cooling
piping system.
In the areas inspected, the examinations were performed in accordarca
with the examination procedure by certified Level 11 examiners.
However, the NRC inspectors determined that the visual examiners were
not consistent in interpreting the examination boundary where the
support selected for examination was part of a multiple support and
the building connection was not shown on the support drawing but
reference was made to another support for the connection.
The visual
examiners were reinstructed to clarify that the examination boundary
for performing a VT-3 examination, as stated in Procedure OEP-9.050,
is from the component to the building structure.
The licensee
initiated a review of the supports which had been completed to assure
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that all supports with this type of design included examination of
the. building connection. This subject is an unresolved item pending
the licensee's review of completed examinations for drawings that
reference other support drawings for the building connection
(4s9/8836-01).
No violations or deviations were identified.
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Review of Records (73055)
(1) Component Supports
The following records for completed examinations on seven
component supports were reviewed:
Exam Number
Method
CS-2303-HL5001
VT-3
AF-2012-HL5018
VT-3 and VT-4
CC-2106-RH12
VT-3
CV-2121-HS5008
VT-3
RC-2125-HL5003
VT-3
RH-2204-HL5002
VT-3
SI-2102-HL5016
VT-3
(2) Components
The following records for completed examinations on components
were reviewed:
Exam Number
Method
SG-28-TR12
SG-28-FW10-IR
6-SI-2108-BB1-3
10-RH-2108-BB1-3A
(3) Pechanized Examinations
The NRL inspectors reviewed the "Eddy Current Examination
Houston Lighting & Power Co. South Texas Electrical Generating
Station Unit 2 Steam Generators A, B, C, and D April, May, and
September 1987." NonconformanceReport(NCR)Nos.AN-03389,
3365, 3366, and 3388 were examined which documented
nonconformances identified during the inspection by Conam.
It
was noted that three tubes were reworked and one tube was
plugged as a result of the PSI inspection.
The NRC review
verified the use of qualified personnel and properly calibrated
equipment as well as compliance to the ASME Code and the
approved procedures. The eddy current testing records of Steam
Generator No. A were reviewed in detail.
During the NRC review,
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one' nonconforming condition (i.e., bulge) was found in the
initial inspection by Conam; this. nonconforming condition had
not been identified on an NCR for Westinghouse evaluatier.. The
licensee initiated an NCR (No. SN-03778) and reviewed the Conam
data in detail. The licensee's review found four additional
nonconforming tubes (i.e., overexpansions) which had not been
previously identified in NCRs. Again the licensee initiated an
NCR (No. SN-03780) for these additional tubes. Unit I data
which was collected by a different vendor is also under review
presently. The failure to appropriately document nonconforming
conditionsisanapparentviolation(499/6836-02).
The records of mechanized ultrasonic examination of the reactor
vessel were reviewed by the NRC inspe, tors. Only very minor
rework, blending gouges, was perforrad as a result of the PSI.
One intermediate shell longitudina". weld (2-101-124) was
reviewed in detail.
From the rev',ew, the NRC inspectors found
that Examination Sheet No. 05001 dated June 24, 1987, referenced
a Resolution Record No. 31034 in regard to a reportable
indication. This resolution record was not available.
There
was, however, on the weld's Examination Sumary Record Sheet
No. 001300 a reference to another resolution record which was in
the data and appeared _to address the indication in question.
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SwRI contended that Resolution Record No. 310154 had been
voided, replaced by the one which was in the package, and the
examination sheet had not been updated to reflect the
replacement record.
This subject is considered an unresolved
item pending SwRI furnishing a basis for whid is the correct
resolutionsheet(499/8836-03).
3.
Unresolved Item
Unresolved items are matters about which more information is required in
order to ascertain whether or not the items are acceptable, violations,
or deviations. The following two unresolved items were discussed in
this report:
Paragraph
Item
Subject
2.c
499/8836-01
Review drawings of multiple supports
to assure PSI examination completed
2.d
499/8836-03
Missing PSI examination resolution
sheet
4.
_E_xj_t Interview
The NRC inspectors reet with the licensee representatives denoted in
paragraph 1 on June 17, 1988, and summarized the inspection scope and
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findings.
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