ML20051A097
| ML20051A097 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/27/1982 |
| From: | Gilbert L, Randy Hall, Hunnicutt D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20051A115 | List: |
| References | |
| 50-482-82-06, 50-482-82-6, NUDOCS 8205140478 | |
| Download: ML20051A097 (6) | |
See also: IR 05000482/1982006
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. APPENDIX
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U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
This Report Contains Results of an Investigation
Report:
STN 50-482/82-06
Docket:
STN 50-482
Category A2
Licensee:
Kansas Gas and Electric Company
P. O. Box 208
Wichita, Xansas 67201
Facility Name:
Wolf Creek, Unit 1
Inspection at:
Wolf Creek Site, Coffey County, Burlington, Kansas
Inspection Conducted:
March 29 - April 2, 1982
1'd6/8A
Inspector:
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L. D. Gilbert, Reactor Inspector, Engineering Section
'Date
Reviewed:
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R. E. Hall, Chief, Reactor Project Section C
Date'
Approved:
/97/l
d#
7/.27/84
D. M. Hunnicutt, Chief, Engineering Section
Date '
Inspection Summary
Inspection during March 29 - April 2, 1982 (Report STN 50-482/82-06)
Areas Inspected: Routine, unannounced inspection of construction activities
including an allegation item and observation of work and review of records
for welding and nondestructive examination (NDE) of Reactor Coolant Pressure
Boundary piping.
The inspection involved 30 inspector-hours onsite by
one NRC inspector.
Results: No violations or deviations were identified.
The allegation dis-
cussed in paragraph 2 was not substantiated.
8205140478 820427
PDR ADOCK 05000482
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DETAILS
1.
Persons Contacted
Principal Licensee Personnel
,
- D. W. Prigel, Manager QA, Site
- G. W. Reeves, Assistant Manager QA, Site
- 0. L. Thero, Supervisor, QA Surveillance
- C. E. Parry, Supervisor, QA Systems
- D. A. Colwell, QA Technologist
- J. L. Stokes, Project Support Supervisor
Other Personnel
J. Johnson, Project Piping Engineer, Daniel International Corporation
(Daniel)
J. Linsome, Mechanical Superintendent, Daniel
G. Robertson, NDE Level III, GE0 Construction Testing
The NRC inspector also interviewed other licensee and contractor employees
during the course of the inspection.
- Denotes those attending the exit interview.
2.
Allegation Regarding Improper Welding Techniques
An allegation regarding improper welding techniques, received by the NRC
Resident Reactor Inspector on March 4, 1982, was reviewed by the NRC
inspector during the inspection.
A welder claimed that while taking a
test on Performance Test No. N-8-8-B-3 he was told to run the root pass
and " wash" the remainder which he believed to be contrary to the procedure.
He refused to complete the weld by " washing" and was fired.
The welder
also stated that he believed this practice was common onsite for weld-out
of small bore extra strong pipe, but that it is not in accordance with
the procedure.
The following information was obtained by the NRC inspector:
Performance Test No. N-8-8-B-3 is specified in Daniel Procedure
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CWP-502, Revision 16 for qualification of welders.
The test requires
that a welder complete four consecutive open root butt joints con-
sisting of 1/2-inch NPS pipe with a 0.294-inch nominal wall thickness
in the "6G" position using the gas tungsten-arc welding process and
type ER 308 filler metal.
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Instructions for welding stainless steel small bore extra strong
pipe are contained in Daniel Procedure CWP-507, Revision 14 under
Weld Procedure Specification (WPS) N-8-8 and Welding Technique
(WT) N-8-8-B-3.
Paragraph 4.18.4 of WPS N-8-8 specifies that a
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minimum of three layers of weld metal shall be deposited for wall
thicknesses 1/4-inch and greater.
Therefore, at least three
layers of wald metal should be used to complete the Performance
Test No. N-8-8-B-3.
The welder qualification supervisor informed the NRC inspector
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that he had been assigned the position on March 29, 1982, since
the previous welder qualification supervisor terminated employ-
ment at the site en March 26, 1982.
'-
The NRC inspector interviewed all eight of the welders listed as
currently qualified to WT N-8-8-B-3.
Each of the eight welders
stated to the NRC inspector that:
a.
He had taken the Performance Test No. N-8-8-B-3, consisting
of four consecutive test welds, which he completed using
between four and seven layers of weld metal.
b.
He had never been requested or instructed to weld the test
weldments nor aly production welds (1/4-inch or greater in
wall thickness) using only two layers of weld metal (root
pass and " wash" remainder),
c.
He could not recall depositing less than four layers of weld
metal on any safety-related weld having a pipe wall thickness
of 1/4-inch or greater.
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This allegation could not be substantiated and the NRC inspector indicated
that he had no further questions regarding this matter.
3.
Reactor Coolant Pressure Boundary Pipe Welding Activities
a.
Observation of Work
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The NRC inspector selected eleven completed welds in the Reactor
Coolant Pressure Boundary piping to inspect the final weld surface.
The following welds were inspected and found to be consistent with
the ASME B&PV Code,Section III NB for weld reinforcement limitations,
transition requirements between different wall thickness pipe, and
weld quality.
Drawing
System
I-M13BB02(Q)
F010
I-M13BB02(Q)
F017
I-M03BB14(Q)
F005
I-M03BB14(Q)
F004
I-M03EP02(Q)
F007
Accumulator Safety Injection
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Drawing
System
I-M03HB24(Q)
F500
Liquid Radwaste
I-M03BB05(Q)
F001
I-M038G24(Q)
F552
Chemical and Volume Control
I-M03BG24(Q)
F553A
Chemical and Volume Control
P-M03BB14(Q)
W534A
P-M03BB15(Q)
W566
The NRC inspector observed the following repair activities on the
Reactor Coolant Pressure Boundary Class 1 piping:
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Cutting defective Weld F021 in Reactor Coolant System of
of Drawing I-M13BB04(Q) for rewelding.
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Excavation of a radiographic defect and liquid penetrant
inspection of completed weld repair on Weld F304R-1 in
Reactor Coolant System of Drawing I Loop 3(Q).
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Wcid repair of counterbore on Weld F905A in Accumulator Safety
Injection System of Drawing I-M03EJ04(Q) for violating minimum
wall thickness requirements. The NRC inspector reviewed the
Weld Repair Instruction WRI 2-FW905-1 and Veld Repair Procedure
CWP-504, Revision 10 and requested that CWP-504 be clarified to
comply with ASME Code Interpretation III-1-79-14, issued
January 25, 1979, in that, weld buildup of pipe counterbores
shall be treated as a weld repair of material under ASME B&PV
Code,Section III NB/NC/ND-4214 and nondestructively examined
accordingly.
This item is considered unresolved pending completion of actions
required in KG&E Surveillance Report S-478 for clarification of
CWP-504 and evaluation of past weld repairs to pipe inside diameter
surfaces.
b.
Review of Records
,
The NRC inspector selected five coraleted welds in the Reactor
Coolant Pressure Boundary piping to review.
The following weld
records were reviewed for adequate wel,d and inspection history
documentation:
Drawing
System
I-M13BB02(Q)
F010
I-M13BB02(Q)
F017
4
,
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Drawing
System
I-M03BB05(Q)
F001
I-M038G24(Q)
FW552
Chemical and Volume Control
I-M038G24(Q)
FW553A
Chemical and Volume Control
No violations or deviations were identified.
4.
Reactor Coolant Pressure Boundary Piping NDE Activities
a.
Observation of Work
The NRC inspector selected two welds in the Reactor Coolant piping
system where the welding and surface preparation were complete and
liquid penetrant examinations were in progress.
The two welds
inspected were Weld W534A of Drawing P-M03BB14(Q) and Weld W566 of
,
Drawing P-M03BB15(Q).
Each weld was liquid penetrant inspected con-
sistent with the requirements of GEO Procedure IPPT-340, Revision 1701-3
for liquid penetrant examination techniques, materials, and acceptance
criteria,
b.
Review of Records
The NRC inspector selected six completed welds in the Reactor Coolant
Pressure Boundary piping to review the NDE records covering evaluation
of weld quality.
lhe following NDE reports were reviewed:
,
NDE Report
Drawing
System
I-M13BB02(Q)
F010
PT-4476
I-M13BB02(Q)
F010
I-M13BB02(Q)
F017
PT-4476
I-M13BB02(Q)
F017
I-M03BB05(Q)
F001
PT-4122
I-M03BB05(Q)
F001
I-M03EP02(Q)
F007
Accumulator Safety
Injection
PT-3288
I-M03EP02(Q)
F007
Accumulator Safety
Injection
I-M03BG24(Q)
FW552
Chemical and Volume
Control
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...
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NDE Report
Drawing
System
PT-69922
I-M03BG24(Q)
FW552
Chemical and Volume
Control
I-M038G24(Q)
FW553A
Chemical and Volume
Control
PT-69930
I-M03BG24(Q)
FW553A
Chemical and Volume
Control
No violations or deviations were identified.
5.
Unresolved Items
Unresolved items are matters about which more information is required
in order to ascertain whether they are acceptable items, violations, or
deviations.
One unresolved item disclosed during the inspection is
discussed in paragraph 3.a.
6.
Exit Interview
The NRC inspector met with licensee representatives (denoted in para-
graph 1) and T. E. Vandel (NRC Senior Resident Reactor Inspector) on
April 2, 1982, and summarized the scope and findings of the inspection.
6