ML20151N913
| ML20151N913 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak |
| Issue date: | 10/09/1985 |
| From: | Harris R, Kerch H, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20151N849 | List: |
| References | |
| 50-445-85-13, 50-446-85-09, 50-446-85-9, NUDOCS 8601030219 | |
| Download: ML20151N913 (22) | |
See also: IR 05000445/1985013
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A_PDENDIX F
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
50-445/85-13
Report No.
50-446/85-09
50-445
Docket No.
50-446
CPPR-126
License No.
CPPR-127
Priority
-
Category
C
Licensee:
Texas Utilities Electric Company
2001 Bryan Tower
Dallas, Texas 75201
Facility Name:
Comanche Peak, I and 2
Inspection At:
Glen Rose, Texas
Inspection Conducted:
September 9-19, 1985
Inspectors
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W. Kerc'h', L a~d 'eactoi Engineer
/
date
n$e
A/9/fC=~
,
-< u ,
chard HJrris, Engineering Technician
/ date
l
Approved by:
Ad'$
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'
Ja s WYgging/faterials and Processes
daf e' *
t
ction, DRS
Inspection Summary: Areas Inspected: A special announced NRC independent
measurement inspection was conducted at the utility's construction site using_
NRC nondestructive examination (NDE) personnel.
The inspection included visual
inspection of welds on electrical raceway supports, and ultrasonic inspection
of the bolting on the steam generator upper lateral supports. Also, an inspec-
tion of concrete expansion anchor bolt installation, visual inspections of
skewed welding and configuration of large bore pipe supports were conducted.
Two Region I based inspectors were assisted by two NRC contract personnel. The
inspection involved 384 onsite hours and 72 offsite hrurs (236 hours0.00273 days <br />0.0656 hours <br />3.902116e-4 weeks <br />8.9798e-5 months <br /> for Unit
1; 220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br /> for Unit 2).
Results: One violation was identified related to failure to follow a quality
control instruction (Paragraph 5).
1030219 851224
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ADOCK 05000445
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1.0 Persons Contacted
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Licensee
R. Hooton, Texas Utilities Generating Company
]
F. Powers, Texas Utilities Generating Company
1
T. Wright, Texas Utilities Generating Company
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R. Muldoon, EBASCO
NRC
T. F. Westerman, NRC Region IV
I. Barnes, NRC Region IV
2.0 Purpose
The purpose of this special inspection was to provide technical' assistance
to Region IV using the NRC Mobile Nondestructive Examination Van resources.
Background
Since 1981, the NRC has issued several Safety Evaluation Reports (SER)
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related to Comanche Peak Units 1 and 2.
Technical concerns and allega-
tions were a part of the regulatory issues that remained outstanding
,
toward the completion of construction of the Comanche Peak facility.
To address these outstanding concerns, the licensee has developed and
4
implemented the Comanche Peak Response Team Program Plan to identify any
design or construction deficiencies.
This inspection, using the NDE Van personnel and equipment, was designed
.
to verify, on a sampling basis, the adequacy of previous licensee efforts
under its Plan.
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3.0 Electrical Cable Tray Supports, Unit 2
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The selected sample of cable tray supports consisted of sixty-three supports.
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The attributes inspected included selected as-built dimensions and weld
,
characteristics. All welded joints in this selected sample were examined
after primer and epoxy coating.had been applied. Therefore, the attributes
of the fillet welds that could be evaluated were:
1.
Fillet size
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2.
Location
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3.
Leg and throat size
4.
Concavity and convexity
5.
Length of weld
6.
Gross undercut and large porosity
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7.
Overall workmanship.
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The inspection was performed and an evaluation made in accordance with
the as-built drawings and considered the visual weld acceptance criteria
contained in the Nuclear Construction Issues Group acceptance standard
(NCIG-01). Cable tray supports sampled during this inspection were in the
Safeguard and Reactor buildings.
Table I lists the supports inspected.
Results of Inspection
On support 11730, torquing of support bolting appeared inadequate.
However, a review of the quality records indicated that this support had
not yet been reinspected by the licensee (licensee is committed to 100%
reinspection). Welding aad as-built dimensional configuration of Unit 2
electrical cable tray supparts met construction requirements. No viola-
tions were identified.
4.0 Electrical Cable Tray Supports, Unit 1
The licensee reinspected a sample of 451 cable tray supports in Unit 1.
The NRC independently selected a sample of 61 supports, 24 were part of
the licensee's 451 and 37 were selected out of the total remaining
population. Attributes and acceptance standards were the same as for the
sample inspection performed in Unit 2.
Cable tray supports sampled during
this inspection were selected in the Fuel and Reactor buildings.
Table II
lists the supports inspected.
Results of inspection disclosed that the welding and ~ssle'cted dimensional
configuration of the cable tray supports met construction requirements.
However, the inspector identified a generic concern with Richmond insert
bolting.
De'iciencies existed such as gaps between the head of the bolt
and the base angle of the hanger; procedure QI-QP-11-10-2 requires contact
between faying surfaces. Other gaps existed between the base angle and
concrete. Drawing CTH-1, note 18, has specific engineering angle to con-
crete bearing requirements that have not been met.
These conditions,
although in some instances were understated, were reported on the as-built
drawings for the cable tray supports.
Supports 6057, 6058, 5995 and 1973
revealed gap deficiencies between the head of the bolt and angle. Also the
supports had gaps between the angle and the concrete.
The generic bolting concern is considered unresolved pending the comple-
tion of the licensee's engineering evaluation and NRC review.
(445/8513-U-01)
5.0 Pipe Supports
A selected sample of pipe supports and hangers were inspected per site
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Quality Instruction Procedure QI-QAP-11-1-26 and the as-built drawings. A
total of eleven were inspected in Unit I and eight in Unit 2.
Supports
were inspected for overall dimensions, location and material size.
In
addition to the dimensional inspection, weldments were visually inspected
for size, surface condition and overall wczkmanship.
Table III lists the
specific items inspected.
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Results: Drawing AF-2-SB-10, mark No. AF-2-006-412-S33A, indicated the
as-built dimensions from centerline of the pipe to the wall at line 14S
to be 11 ". This dimension when measured by NRC was shown to be 13 ".
In order to verify if this difference was recorded by the licensee, the
inspector compared NRC inspection data with the site quality dimensional
records for support AF-2-006-412-S33A, dated 4/27/85.
This review revealed
that the quality control inspector did not assign a number to the 11 "
dimension and did not record the measurement.
Procedu're QI-QAP-11.1-28
requires that each dimensional attribute be assigned a number and measure-
ments made.
Because, in this particular case, the as-built dimension had
not been recorded, as required, the inspector considered this item to be a
violation (446/8509-V-01)
Skewed Welds
A selected sample of type 2 skewed weldments, previously inrpected and
accepted by the utility, was reinspected by the NRC to verify the method
and validity of the licensee's inspection.
Skewed welds inspected included stanchion-to-stanchion, stanchion-to pipe
saddle and tube steel-to pipe or pipe saddle weldments. Nineteen pipe
supports in Unit I were inspected; approximately thirteen hundred linear
inches of weldment were inspected by NRC using fillet weld gages,
Cambridge gages and a contour gage. Areas that could not be inspected
with a fillet or Cambridge gage were inspected using the contour gage per
site Procedure QI-006, Revision 1.
Results:
No violations were identified.
No instances of undersized welds were observed when the as-built conditions
were compared to the applicable drawing requirements. Additionally, those
measurements taken by the NRC were compared to those measurements taken
and documented by site personnel.
There were no significant differences
noted.
Hilti Bolt Inspection
One hundred and twenty-four Hilti Kwik anchor bolts were inspected per
site Quality Instruction Procedures QI-QP-11-2-1, Revision 18, and
QI-QP-11.18-4, Revision 0, in conjunction with NRC Procedure NDE-18,
Revision 0.
The inspection consisted of ascertaining embedment depth,
bolt spacing and length and diameter of individual bolts as identified by
code stamp.
Table IV lists the specific items inspected.
Results: No violations were identified.
As of 9/19/85, the inspectors
had identified ore bolt on a concrete base plate which appeared to be
underlength. On 9/25/85, telephone communications from Region IV
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personnel indicated that the bolt had been verified to be the correct
length by both the licensee and NRC persennel. The inspectors had no
further questions.
6.0 Steam Generator Upper Lateral Support Bolting
Steam Generator upper lateral support bolts had been reported as
improperly shortened by the licensee. The licensee had replaced several
of the reported shortened bolts and was awaiting engineering disposition
as to the course of follow-on action. The NRC selected one hundred and
four bolts for independent ultrasonic inspection to determine their length.
Ninety-eight wert measured from the top of the bolt head to the concrete
wall (see sketch on Attachment A for dimension "A").
A calculation was
performed to determine embedment engagement.
The NRC compared its data
to the site's and there were some differences.
In order to resolve the
differences, the NRC requested bolt 1E15 be removed and a dimensional
measurement be made.
This_ revealed that the embedment plate was not flush
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with the wall, but stuck out 5/8" (see Attachment A, dimension "C").
This
accounted for the difference between NRC data and the licensee's.
Results:
No violations were identified.
7.
Unresolved Items
An unresolved item is a matter for which more information is necessary to
determine whether the item is acceptable, a violation or deviation.
Unresolved items are contained in paragraph 4.
8.
Tables and Attachments
Table I is a tabulation of specific Electrical Cable Tray Supports
inspected in Unit 2.
Table II is a tabulation of specific Electrical Cable Tray Supports
inspected in Unit 1.
2
Table III is a tabulation of specific Hanger / Supports and skewed welds
inspected.
Table IV is a tabulation of specific Hilti Bolts that were ultrasonically
tested for length.
Attachment A is a tabulation of specific Steam Generator lateral support
bolts that were dimensionally checked for length.
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9.
Exit
A formal exit interview was not held.
However, members of the licensee's
staff and NRC Region IV personnel were informed of progress and findings
during the course of the inspection.
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ELECTRICAL CA8LE TRAY SUPPORTS
UNIT 2
TABLE I
11600
9768
9801
11603
11733
9802
11604
11825
9803
11607
11826
- -9804
11608
9850
9805
11519
9851
9806
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11520
9852
9807
11522
9853
9808
11523
9854
9809
11524
9855
9810
11526
9836
9811
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11527
9837
9812
11528
9839
9813
10094
9840
9814
10095
9841
9815
11924
9918
9816
11933
9919
9817
10136
9920
9818
9765
9921
9819
9766
9922
9820
9767
9800
11730
Results: The above cable tray supports reinspected by the NRC for welding
and selected as-built dimensional configuration met construction
requirements.
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TABLE II
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The NRC selected a total of 61 supports to be inspected. Asterisked supports
were selected from the 451 previously reinspected by the licensee. The remain-
der were selected from the remaining population. The Unit I supports that were
inspected are the following:
CTH-1- 236
CTH-1-1970
- CTH-1-5918
1181
1973
5919
1184
1974
5920
1186
1975
5921
1719
1978
5922
1720
5226
5986
1722
5765
5994
1723
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5766
5995
1724
5767
6017
1725
5769
6057
1726
5771
6058
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1727
5772
6938
1728
5773
6939
1741
5876
6940
1742
5886
6941
1743
5912
6942
1746
5914
6943
1842
5915
6944
1852
5916
6945
1862
5917
6946
6947
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Results: The above cable tray supports reinspected by the NRC for welding
and selected as-built dimensional configuration met construction
requirements. However, a bolt torquing concern was identified
on some of these supports.
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TABLE III
LISTING 0F HANGER / SUPPORTS INSPECTED AS-BUILT AND SKEWED WELDS
Unit 1
Drawing
Building
Comments
1.
CC-1-202-001-S53A
Safeguards
Welds and Dim. Acc.
2.
BR-X-106-059-S43A
"
"
"
"
"
3.
CC-1-065-003-S33A
"
"
"
"
"
4.
CC-1-019-012-A43K
Auxiliary
"
"
"
"
5.
CC-X-079-006-A43A
"
"
"
"
"
6.
CC-1-035-018-A33A
"
"
"
"
"
7.
RH-1-001-001-C41S
Containment
"
"
"
"
8.
CC-1-110-007-A43S
Auxiliary
"
"
"
"
-9.
CC-1-235-006-C53R
Containment
"
"
"
"
10. RC-1-135-008-C41K
"
"
"
"
"
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11.
RC-1-135-004-C51K
"-
"
"
"
"
Unit 2
Drawing
Building
Comments
1.
SI-2-071-405-S33K
Safeguards
Welds and Dim. Acc.
2.
AF-2-004-405-S33A
"
"
"
"
"
3.
CT-2-005-403-S22K
"
"
"
"
"
4.
CC-2-116-006-F43A
Fuel
"
"
"
"
5.
AF-2-101-431-S33A
Safeguards
Welds and Dim. Acc.
(CMC 87004)R3
6.
CS-2-597-403-C42A
Containment
Welds and Dim. Acc.
7.
RH-2-064-406-S22R
Safeguards
"
"
"
"
8.
AF-2-006-412-S33A
"
See Report
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TABLE IV
HILTI BOLT UT
Unit 1
Drawing
Building
Code
Total
Comments
CC-1-AB-044
Auxiliary
T
8
Acceptable
"
"
0
4
"
CC-X-AB-003A
"
R
8
"
"
"
0
4
"
CC-X-AB-002
"
0
8
"
CC-1-AB-19-11
R
4
"
"
CC-1-AB-19-12
"
R
3
"
CC-1-AB-19-13
"
R
8
"
CC-1-AB-19-12
T
1
"
"
CC-X-041-004-F43
Fuel
R
4
"
SF-X-067-002-F35R
L
8
"
"
SF-X-067-700-F35R
"
T
4
"
SF-X-066-007-F33R
"
L
4
"
SF-X-01-F51-R-3
"
R
4
"
CT-1-105-003-C62R
Containment
R
8
"
CT-1-RB-057-001
T
4
"
"
SI-1-RB-058-002
"
L
4
"
"
"
P
4
"
SI-1-RB-058-001
"
R
4
"
CC-1-242-004-C53R
"
0
4
"
SF-X-068-006-F33R
Fuel
0
4
"
CC-X-024-001-A43
Auxiliary
T
4
"
CC-X-211-010-F43
Fuel
P
4
"
CC-2-116-008-F43
T
10
"
"
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P
2
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