ML19351E777
| ML19351E777 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/17/1980 |
| From: | Bryant J, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19351E770 | List: |
| References | |
| 50-413-80-32, 50-414-80-32, NUDOCS 8012190222 | |
| Download: ML19351E777 (5) | |
See also: IR 05000413/1980032
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA ST., N.W., sulTE 3100
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ATLANTA, GEORGI A 30303
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Report Nos. 50-413/80-32 and 50-414/80-32
Licensee: Duke Power Company
422 South Church Street
Charlotte, NC 28242
Facility Name: Catawba Nuclear Station, Units 1 and 2
Docket Nos. 50-413 and 50-414
License Nos. CPPR-116 and CPPR-117
Inspection at Catasha site
r Lake Wylie, South Carolina
Inspector
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Date Signed
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Approved by:
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ryant,SectionChief[RCESBranch
Date Signed
SUMMARY
Inspection on October 20-22, 1980
Areas Inspected
This routine resident inspection involved 18 inspector-hours on site in the
review of QA procedures and training records, inspector followup items, and IE
Bulletins, response to 10 CFR 50.55(e) items and observing work related to the
corrective action program for 10 CFR 50.55(e) items.
Results
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Of the areas inspected, no apparer.'. Items of noncompliance or deviations were
identified.
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DETAILS
1.
Persons Contacted
Licensee Employees
D. G. Beam, Project Manager
- D. L. Freeze, Project Engineer
- S. W. Dressler, Senior Construction Engineer
- L. R. Davison, Senior QC Engineer
- R. A. Morgan, Senior QA En;ineer (QAE)
- J. C. Shropshire, QAE Mechanical, Welding
H. D. Mason, QAE Civil Electrical
J. Glenn, QAE Instrumentation
D. A. Jenkins, QA Technician, Instrumentation
S. Atkinson, Construction Engineer, Instrumentation
G. W. Greer, III, Planning Manager
R. Gist, Technical Specialist
T. Sappenfield, NCI Clerh
Other licensee employees contacted included various construction craftsmen,
technicians and office personnel.
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on October 22, 1980, with
those persons indicated in Paragraph 1 above. No new items of noncompliance
or unresolved items were identified in the areas inspected.
3.
Licensee Action on Previous Inspection Findings
Not inspected.
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4.
Unresolved Items
There were no new unresolved items identified during this inspection.
5.
Independent Inspection
a
The inspector observed work inside the Unit 2 reactor building and the
auxiliary building, talked to various craft personnel, and discussed construc-
tion status with the project engineer.
6.
IE Bulletins
a.
(Closed) IEB 78-12, 12A and 12B (50-413 only), Atypical Weld Material
in Reactor Pressure Vessel Welds. The NRC has completed the review of
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documentation submitted by L'estinghouse for the subject bulletin for
the Catawba 1 reactor pressure vessel (RPV). The weld material used in
the Catawba 1 RPV met the applicable acceptance criteria. No atypical
weld material was found.
b.
(Closed) IEB 79-03, 03A, Longitudinal Defects in ASME SA-312 Type 304
Stainless Steel Pipe Spools Manufactured by Youngstown Welding and
Engineering Company. Region II reviewed the Duke Power Company (DPC)
response dated August 5, 1980. DPC has not used, and does not plan to
use, the subject pipe at greater than 85 percent of Code allowable
pressure stresses.
(Closed) IEB 80-16, Potential Misapplication of Rosemount Inc. , Models
c.
1151 and 1152 Pressure Transmitters with either an "A" or "D" Output
Code.
Region II has reviewed the licensee's response dated August 6,
1980.
None of the subject pressure transmitters are installed in any
safety related applications and there are no plans to install any of
these transmitters in safety related applications.
7.
Inspector Followup Items (IFI)
a.
(Closed) IFI 413/414/79-05-01 Nonconforming Item (NCI) System. The
inspector reviewed the implementation of the NCI system with DPC staff
responsible for scheduling the work required to correct the problems
identified in the NCI's and the QA staff that monitors the resolutions
of the NCI's. A significant increase in management effort and manpower
devoted to expeditiously correcting the NCI's has been developed and
maintained since the inspector's previous efforts on this subject were
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reported (reference NRC reports 50-413/414/79-14, 79-15 and 79-20.)
Computer printouts of NCI's are routinely sent to each group responsible
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for closing the NCI's.
Design Engineering routinely monitors the
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completion work and timeliness. Site planning expedites the completion
of the NCI work.
QA monitors the effectiveness of the corrective
action work on each NCI.
b.
(Closed) IFI 413/79-16-01, Pull Box Installation Not Covered By Procedure.
The inspector reviewed the revised installation specification number
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CNS-1390.01-00-0048, revision 6 dated March 18, 1980, design drawing
CN1214-5, Revision 7 dated August 5,
1980, installation drawing
CN-2892-01, revision 11, dated October 10, 1980, and NCI 6339 as
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referenced in NRC reports 50-413/79-16 and 79-19.
The inspector
confirmed that the pull boxes have been reinstalled per a seismically
qualified design drawing detail and the above specification and drawings.
The electrical craft foremen have been trained and reinstructed to
contact the technical support engineers if any information is unclear
or unavailable.
8.
Licensee Identified Items,10 CFR 50.55(e)
a.
(Closed) LII 413/414/79-15-01, Safety Related Instrumentation and
Controls. The inspector reviewed the corrective action program (CAP)
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as stated in the licensee's responses to Region II dated September 10,
1979 and October 17, 1979. The inspector discussed the subject with
the responsible design engineer to confirm the CAP taken relative to
the main steam power operated relief valves as shown on drawing CN
1593-10. The CAP has provided for two safety grade valves to evacuate
(depressurize) the actuator. The two valves are powered from separate
power trains. The inspector discussed the CAP with the responsible
technical support engineer and the QA staff and reviewed representative
valves affected by the CAP for the component cooling system (flow
diagram CN 1573-1.1) the chemical and volume control system (flow
diagram CN 1554-1.0) and the auxiliary feedwater system (flow diagram
1592-1.1).
The inspector verified that the solenoid valves are class
IE by reviewing the mechanical instrumentation and control list for
representative valves as noted on the above flow diagrams.
The
inspector's previous review of the study of the subject by the design
engineering department was reported in NRC report 50-413/414/79-20 in
an LII erroneously identified as 413/414/ 79-20-01 rather than 413/414/
79-15-01.
The current inspection work closes the concerns expressed in both
reports 50-413/414/7915 and 79-20.
9.
QA Procedure Review, Design and Construction
The inspector reviewed the recent revisions to the QA procedures noted
below and discussed the implementation of the revised procedures with the
senior QA engineer.
Procedure No.
Revision
Title
1
PR-100
2
Application of QA Program
PR-360
4
Transfer of Items
PR-840
9
Internal Audits
PR-860
5
QA Training
PR-901
14
Document Control
PR-130
5
Electrical Division Special
Drawings
PR-130
5
Mechanical System Support /
Restraint Design Drawings,
and Change Orders
A-1
10
Preparation and Issue of QA
Procedures
F-10
3
Process Control for Alteration
or Repair of Code Stamped Items
F-14
0
Control of Onsite Vendor Work
12
Identification and Control of
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Welding Material Inspection of
Design Concrete
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21
Visual Inspection and NDE of
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M-10
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Process Control and Inspection
of the Application of Torque
to Bolts and Studs
M-14
5
Cadweld Splice Inspection and
Testing
M-23
12
Visual and NDE of Nuclear
Safety Related Pipe Welds
(ASI B31.7)
M-26
3
Laboratory Soil Testing
M-41
7
Electrical Equipment Installation
Inspection
M-51
1
Component Supports
M-61
4
Instrumentation Process Control
and Inspection
M-71
3
Process Control and Inspection
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of Containment Systems and
Liner Plate (ASME III)
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4
Requirements for Applying the
NA Stamp to Code Systems
6
General Specification for
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Heat Treatment of Weldments
Control of Hoisting Equipment
No items of noncompliance were identified.
10.
QA Training
The inspector reviewed the following QA department procedures and discussed
the inplementation of the procedures with the senior QA engineer and staff.
Procedure No.
Revision
Title
QA-112
1
Certification of QA Analysts
QA-131
1
QA Training
QA-140
0
QC Inspector Training
The inspector inspected the QA training records as required by QA-112 for
L. R. Davison, H. D. Mason, R. A. Morgan, and C. S. Shropshire. The inspector
also inspected the QA training roster records (form QA-131B) for training
meetings conducted between January 18, 1980 and October 15, 1980.
No items of noncompliance were identified.
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