ML19225B469
| ML19225B469 | |
| Person / Time | |
|---|---|
| Site: | Callaway |
| Issue date: | 05/25/1979 |
| From: | Hansen W, Knop R, Schweibinz E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19225B467 | List: |
| References | |
| 50-483-79-04, 50-483-79-4, NUDOCS 7907250216 | |
| Download: ML19225B469 (7) | |
See also: IR 05000483/1979004
Text
.
.
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-483/79-04
Docket No. 50-483
License No. CPPR-139
Licensee:
Laion Electric Company
Post Office Box 149
St. Louis, Missouri
63166
Facility Name:
Callaway, Unit 1
Inspection At: Callaway Site, Callaway County, Missouri
Inspection Conduct d: Ap il 24-26, 1979
b
'
Inspectors:
weibinz
lf-
'
'
S c 4L .
L[pf/79
5
Approved By:
R. C. Knop, Ch ef
Projects Section
Inspection Summary
Inspection on April 24-26, 1979 (Report No. 50-483/79-04)
Areas Inspected:
Licensee action on previous inspection findings;
radiographic examination procedures for containment liner plate; and
site tour.
The inspection involved a total of 28 inspector-hours
onsite by two h7C inspectors.
Results:
Of the three areas inspected, no items of noncompliance or
deviations were found in two areas; one apparent deviation was
identified in one area (Deviation - failure to use proper penetrameter
for radiography of containment liner plate - Paragraph 1).
79072 5 oE6
e5
., o c,
S
'O
MzN
.
.
~,
DETAILS
Persons Contacted
Union _ Electric Company (UE)
- W. H. Weber, Manager, Nuclear Construction
M. 1. Doyne, General Superintendent, Callaway Construction
- R. L. Powers, Site Quality Assurance Group Leader
- W.
Stahl, Quality Assurance Engineer
'
Daniel International (Daniel)
xH. J. Starr, Project Manager
- W. L. Sykora, Assistant Project Manager
- J. R. Cook, Quality Manager
- E. D. McFarland, Construction Engineering Manager
- J. N. Kaelin, Project NRC Coordinator
- M. K. Smith, Audit Response Coordinator
- h'. L. Petrie, Quality Assurance Engineer
The inspectors also contacted and interviewed other licensee and
contractor personnel, including craf tsman, QA/QC, technical and
engineering staff members.
- Denotes those attending the exit meeting.
Licensee Action on Previous Inspection Findings
(Closed) Noncompliance (50-483/79-02-02):
Failure to control
nonconforming safety-related equipmeat.
The following documentation
was reviewed and the corrective actions taken were found to be
acceptable:
telecon report, March 14, 1979, between the Site QA
Grcup Leader and SKUPPS QA Manal,er; memorandum dated April 5,1979,
from the Site QA Group Leader tc Manager Nuclear Construction;
letter from the Daniel Project Manager to the Manager Nuclear
Construction dated April 20, 1979 and the attached interoffice
communication SQCE-ll36 April 19, 1979; memo to file AB23.02
(79-02) March 19, 1979; memo fron T. H. McFarland to R. L. Powers,
March 15, 1979; Union Electric memo from the Manager of Nuclear
Engineer 2ng to the Manager of Quality Assurance, March 12, 1979;
letter from the Daniel Project Manager to the Manager Nuclear
Lou;truction, March 19, 1979; Paniel letter from the Project Manager
to the Manager Nuclear Construction, March 23, 1979; SNUPPS letter,
SLW79-11, March 20, 1979 from the Quality Assurance Manager to
-2-
39 b>
9 5 :t
M
M
-
i3 4 9
.
9
Manager SNUPPS Projects PWR C, stems Division, Vestinghouse Electric
Corporation; and nontatiformance report No. 2SN-9239-M, Februa ry 13,
1979. This item was further reviewed with the SNUPPS Quality Assurance
Manager, during an audit of activities at their Gaithersburg, Maryland,
office on April 30, 1979. This item is closed.
(Closed) Noncompliance (50-483/78-10-02; 50-483/79 03):
Failure
to follos procedures for weld rod control. The R7;I inspectors
reviewed the corrective action taken by the licersee and the training
prossam including training records to date, end Jeter.nined that they
were acceptable. During the site tour no uncon'. rolled weld rod
stubs were observed. This item is clor-d.
(Clcsed) Unresolved item (50-483/78-1405):
Cvnflicting require-
menti for determining delta ferrite content in stainless steel
welding consumables and welds in the appropriate procedures. The
inspectors reviewed the revised procedure QCP-509, Rev.
1, and the
inspection records completed to date and determined them to be
acceptable. This item is closed.
Fuactional or Program Areas Inspected
Details of functional or program areas iuspected are documented as
follows.
1.
Radiographic Exami:igtion Procedures for Containment Liner Plate
The following Jocumentation was reviewed:
a.
(1) SKUPPS PSAR Section 3.12, Regulatory Guide 1.19 -
Nondestructive Examination of Primary Containment
Liner Welds, which states, in ? art, "All nondestruc-
tive examination methods and techniques are in cccor-
dance with Section V cf the AShE Boiler and Pressure
Vessel Code, except for radiography which is in
accordance with Appendix X of ASME Section III."
(2) Appendix X to Section III of the 1971 addition of the
ASME Boiler and Pressure Vessel Code, Nondestructi'e
Examination Methods for Metal Containment Vessels.
(a) Paragraph X-3325, Penetrameters, subparagraph
X-3325.1, Material, Size and Shape, states, in
part, "The maximum thickness of the penetrameter
shall be as shown in Table X-3325.1-1"
'
-3-
t
.
2V11
y 52_ - 3sf4
-3 @ F F R
.
.
(b) Table X-3325.1-1, Standard Per etrameter Sizes,
indicates that "For a weld Th ckness between the
range of over 1/4" through 3/3" t'
thickness of
the p?netrameter on the Fource side shall be
0.0073" and the designatisn on the penetrameter
shall be No.
7."
(c) Subsubarticle X-3330, Technique for Radiographic
Examination of Welded Joints, Paragraph X-3332,
Required Sensitivity of Radiographic Technique,
states " Radiography shall be performed with a
technique which will have sufficient sensitivity
to indicate the features in X-3334.5
o.'
a pene-
trameter of the thickness specified for the
thicx-ness of the weld being examined, as shown
in Table X-3325.1-1."
(d) Subparagraph X-3334.5, Images Which Shall Appear
on Radiographs, (a) "The images of the identifying
numbers of the penetrameter outline and of the
2T hole are all essential indexes of image
quality :,n the radiograph and they shall appear
on the radiograph, except that far penetrameters
5, 7, and 10, the slit shall appear clearly, and
hole need not appear."
(3) Bechtel Specification !'
10466-C151(Q), Furnishing,
Fabricating and Delivering Reactor Building Liner
Plate:
(a) Paragraph 7.5.1.a, requires that liner seam
welds be examined radiographically in accordance
with the requirements of Article 3 of Section V
of the ASHE Code.
(b) Paragraph 7.5.7, requires that Type 1 or 2 film
be used and that fluorescent screens shall not
be used.
(4) Chicago Bridge and Iron (CB&I) Procedure No. RTP-
(74-3730/59), Rev. 2, approved by Bechtel by a letter
dated November 22, 1977, titled " Radiographic
Examination Procedure for Welds, SNUPPS Containment
Liners."
.
-4-
3W
NZ
3:::3-- 35
.
.
(a) Section 3.0, References;
1974 ASME Boiler and Pressure Vessel Code,
Section III, Division I, and Section V, and wi 'h
the following Addenda:
None
'o Terenced Parts:
Section V, Article 3 Section
111, NE 5300
(b) Section 4.5, Type of Film:
Only film types
equivalent to Class 1 and Class 2 .
will be
.
used for radiography.
(c) Section 4.7, Type of Screen: Nc fluorescent
screens will be used.
(d) Section 4.9, Penetrameter:
The type, size and
shape of penetrameter shall be in accordance
with T-320 (e) of Section V.
(e) Section 8.1.A, "The images of the identifying
n umbe rs , the penetrameter outline, and of the
essential hole as required by Table T-320 are
all essential indexes of image quality, and they
shall appear on the radiograph."
(5) ASME Boiler and Pressure Vessel Code,Section V,
Article 3, Radiographic Examination:
(a) T-320(e) states in part "Penetrameter thickness
shall be as specified in Table T-320..."
(b) Table T-320, "ii ness, Penetrameter Designations,
and Essential
res, requires that for a single
wall material thickness of the range of over
1/4" through 3/8" that the source side pene-
trameter chall be a size no. 12.
Note:
A size no. 12 penetrameter
has a thickness of 0.012"
b.
Evaluation of the Above Documents
The RIII inspector equested the 11 ensee to explain the
apparent deviation between: (1) The commitment in the PSAR
to have radiographic examination procedures for containment
-5-
349
45'2
3W
$nes -
aars
.
liner welds accordance with Appendix X to Section III of
the ASME Boiler and Pressure Vessel Code, which requires
the use of a 0.0075" thick penetrameter for a weld thick-
ness over 1/4" through 3/8" (the liner plate is 1/4"
thick) and; (2) The requirement of CB&I Procedure No.
RTP-(74-3750/59) to determine the thickness of the pene-
trameter in accordance with Table T-320 which requires a
penetrameter 0.012" thick for the same material thickness.
The RIII inspector explained that he had identified an
identical deviation at Wolf Creek during the previous
week. The licensee was aware of this deviation at Wolf
Creek.
Bechtel Specification No. 10466-C151(Q) references
Article 3 of Section V instead of Appendix X to Section
III of the ASME Boiler and Pressure Vessel Code.
It
should be noted at this time that the No. 12 penetrameter
called for in Article 3 of Section V is 60% thicker than
the No. 7 penetrameter as called for in Appendix X to
Secticn III.
The licensee indicated that it woulo contact Bechtel to
explain why the thicker penetrameter was allowed to be
used in lieu of the commitment in the PSAR.
This item is a deviation from a commitment in the PSAR
(483/71-04-01).
Note: The RIII inspector recognizes that Section III of
the ASME Boiler and Pressure Vessel Code does not require
that the containment liner plate seam welds be radiographed.
However, Regulatory Guide 1.19 does require that these
seam welds be spot radiographed.
SKUPPS PSAR Section 3.12 commits to Regulatory Guide 1.19,
August 11, 1972, Nondestructive Examination of Primary
Containment Liner Welds.
Regulatory Gaide 1.19: Paragraph C.1, Nondestructive
Exaraination of Liner Seam Welds, Subparagraph C.1.a requires
that welds be examined radiographically in accordance with
the techniques prescribed in Section V.
Subparagraph 7.a, Containment Liner Seam Welds Examined by
Radiography, states, "Where a spot in the seam weld is
judged acceptable in accordance with the referenced stand-
ards of NE-5120 of Section III of the ASME P&PV Code, the
eatire weld test unit represented by this spot
sdiograph
is considered acceptable."
-6-
30
H SV3SE>
m - ws
.
Subarticle NE-61, ' , Exaraination Requirements of Welded
Joints for Vessels, of Section III of the 1971 Edition of
the ASMI B&PV Code states, " Examination in accordance with
the requirements of Section VIII, Division 1 of this Code
chall be made of welded joints for vessels as follows:
(a) Welded joints of Categories A and B as defined in
NB-3351 shall be radiographed in accordance with UW-51."
Subparagrar~ NB-3351.1 defines Category A welded joints as
longitudin 1 welded joints within the main shell.
Subpara-
graph NB-3351.2 defines Category B welded joints as circum-
ferential welded joints within the main shell.
UW-51 to Section VIII, Division 1 of the ASME Boiler and
Pressure Vessel Code, Table UV-51, Standard Penetrameter
Sizes, requires that a penetrameter for weld thickness
range of over 1/4" through 3/8" be of a thickness of
0.0075" and designated a No. 7 penetrameter. The liner
plate is 1/4" thick.
The commitment in the PSAR Section
3.12 requires that radiographic examination procedures for
containment liner welds will be in accordance with Appendix X
to Section III of the ASMI Boiler and Pressure Vessel
Code.
(Appendix X to fection III and Article 2 of Section
V are acceptable methods of meeting the requirements of
Regulatory Guide 1.19, since their examination requirements
are equivalent.)
2.
Site Tours
An extensive site tour was conducted to further inform the new
p roj ect inspector of previous activities at the site.
Entrance / Exit Meeting
The inspectors informed the licensee on April 24, 1979, that
Mr. W. ,A. Hansen has been selected as the resident inspector
for the Callaway site.
The inspector met with the site staff representatives (denoted
in the Persons Contacted paragraph) at the conclusion of the
inspection on April 26, 1979.
The inspector cummarized the
scope and findings of the inspection.
It was noted that work
area housekeeping has improved since the last inspection.
-7-
.
aG\\
_
2EBSS