ML19344D779
| ML19344D779 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/03/1980 |
| From: | Dodds R, Narbut P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19344D773 | List: |
| References | |
| 50-312-80-05, 50-312-80-5, IEB-79-02, IEB-79-2, NUDOCS 8004280180 | |
| Download: ML19344D779 (7) | |
See also: IR 05000312/1980005
Text
O
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
=
REGION V
50-312/80-05
Report No.
50-312
Docket No.
License No.
Safeguards Group
Licensee:
Sacramento Municipal Utility District
P. O. Box 15830
Sacramento, California 95813
Rancho Seco
Facility Name:
Rancho Seco Site
Inspection at:
Inspection conducted:
Jan 30-Feb 1, Feb 12-15, Feb 17-18,1980
Inspectors:
tw M
3/3/DO
P. P. Narbut, Reactor Inspector
Date Signed
Date Signed
Date Signed
Approved By:
N
'
R. T. Dodds, Chief, Reactor Engineering Support Branch, Vate/ Signed
ReactorConstructfonandEngineeringSupportBranch
Suenary:
Inspection on January 30-February 1, February 12-15, February 17-18, 1980
(Report No. 50-312/80-05)
Areas Inspected:
Routine, unannounced inspection by regional based
,
inspectors of % 11censee's activities performed in response to IE
Bulletin /OL'
" Pipe Support Base Plate Design Using Concrete Expansion
Anchor Bolts" and of licensee's activities performed for the inservice
inspection for the 1980 refueling outage. The inspection involved 67
inspector-hours onsite by one NRC inspectors.
Results: ~ No items of noncompliance or deviations were identified as a
result of the inspections.
RV Form 219 (2)
800428o
WO;
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DETAILS
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1.
Persons Contacted
a.
Sacramento Municipal Utility District (SMUD)
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- R. J. Rodriguez, Manager, Nuclear Operations
- P. Oubre, Plant Superintendent
- R. Columbo, Technical Assistant
- B. Stiver, Mechanical Engineer
- J. Sullivan, Quality Assurance
- G. A. Coward, Maintenance Supervisor
- W. Ford, Supervisor of Nuclear Operations
- R. Medina, Quality Assurance Engineer
- H. Heckert, Nuclear Engineer Technician
'
- N. C. Brock, Electrical Supervisor
W. Garrett, Mechanical Engineer
- Denotes those attending the exit interview on February 1,1980
'thich was attenCed by R. T. Dodds, H. L. Cantor and J. O'Brien
.
of the NRC.
- Denotes those attending the exit interview of February 15,1o80
which was attended by H. L. Cantor and G. Zwetzig of the NRC.
b.
Babcock & Wilcox (B&W)
Howard Stoppelman, Supervisor
J. Uhl, ISI Coordinator
M. Gallagher, NDE Examinor
c.
Hartford Steam Boiler
P. Miller, ANI
2.
Licensee Action on orevious Inspection Findings
a.
(Closed) Open Item: Pipe support welding does not meet
AWS D.1.1 acceptance criteria (Item 50-312/79-17/06)
,
The inspector examined supports 60-32120-1 and 4A-26020-1 and
found that they met the AWS D.1.1 criteria. The inspector
further examined recently acccmplished support welds on
nuclear raw water support NRW 10G 47350-1 and found they met
AWS D.1.1 requirements. The inspector had no further questions.
This item is closed.
. _ _ _ _ - - _
__ ________
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b.
(0 pen) Open Item: Acceptance criteria for concrete expansion
anchor expansion was not established and inspection data
had not been evaluated.
(Item 50-312/79-17/01)
The inspector examined the wedge placement data for 16 supports
and determined the 12 of the 16 supports may have one or more
anchors with insufficient expansion. At the time of inspection
the licensee had not finalized the acceptance criteria to be
used and had not evaluated the data in hand.
At the exit
interview of 2/1/80 the results of the inspectors data review
were explanied to licensee management and the potential for
significant additional work was discussed.
c.
(0 pen) Unresolved Item:
Sliding supports had been modified
by the addition of non-sliding bracing (Item 50-312/79-17/07)
The inspector examined decay heat system support DHS 40 26021-
1 and observed it had been remodified to restore sliding
capability in accordance with modified engineering instructions
on Bechtel drawing M-485 Sheet 4-56 DCN 1E. The inspector had
no further questions on the design of the sliding supports
which had been changed by addition of bracing.
The inspector
examined the following sliding supports which had not been
modified, that is no bracing was added by design modifications,
but had been worked on, in that the grout under the slide
plate had been removed for bolt testing and replaced with
Concresive (epoxy type compound):
^
SU 23803-9
4U 26020-4
4U-26020-6
The Concresive was observed to be built up in such a manner as
to lap over between the slide platas and would apparently
interfere with the slide function of the plates.
Four additional supports were examined which had not been
modified or tested.
4G-26122-1
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SU-23820-2
The edges of the slide plates were observed to be encrusted
with debris and, in some cases, borate crystals. There was no
visual evidence of the supports having moved in recent times.
The installation drawings for these sliding supports required
that upon original installation, the bottom of the slide plate
be greased and that the support be free to slide after installatir-
Through discussions with the cognizant engineer it was determined
that there are no maintenance requirements, which require the
periodic reapplication of grease nor a visual verification of
sliding functionability on heat up or cool down.
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,
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.
.
At the February 1,1980 exit interview licensee management
comitted to inspect for and remove excess Concresive which
would interfere with the sliding function. The licensee
management further committed to evaluate the need for periodic
lubrication of sliding supports and the need for visual evidence
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of movement.
!
3.
Concrete Expansion Anchors in Pipe Supports.
l
I
The inspector examined the testing of concrete expansion anchors by
two of the testing crews to verify conformance to the requirements
'
No items of noncompliance or deviations were observed.
During the testing of support SU-23620-2 (SIM) which is a grouted
coltimn support, it was noted, with the grout chipped away for
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inspection, that one of the anchor bolt sleeves protruded above
the face of the concrete floor by approximately one inch. The
anchor inspector noted the condition as a coment on the inspection
data sheet. The inspector noted that tne procedure MT.017 Revision
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2
" Inspection of Concrete Fasteners" does not prohibit a concrete
anchor sleeve projecting from the concrete surface nor does the
procedure require reporting of the condition. At the exit in
terview of February 1,1980 licensee management comitted to
determine if other involved inspectors have consistently reported
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anchor standout and to make a procedure change to specify anchor
standout criteria. This item will be inspected further on a future
inspection (Item 50-312/80-05/01.)
_
4.
Inservice Inspection
The licensee is performing the third refueling outage inservice
inspection in accordance with ASME B&PV Code Section XI 1971
Edition through Sumer of 1973 Addenda for Class 1 and 1974 Edition
through Sumer of 1975 for Class 2 and 3.
i
a.
Eddy Current Testing of Steam Generator Tubing
i
The inspector examined the eddy current testing of steam
'
generators A and B during the outage for conformance to
Technical Specification 4.17. and Procedure ISI-401 Rev.10
of 8-8-79.
,
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,
The inspector (1) examined the acquistion of eddy current
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data on generators A and B, (2) reviewed calibration data
sheets,(3) checked qualification records of selected eddy
current operators, and (4) reviewed the B&W computerized
method of data analysis.
No items of noncompliance or deviations were observed.
It was noted by the inspector that a two channel method
of recording was not used as is recommended by Regulatory
Guide 1.83.
However the licensee has not committed to
b.
Visual Inspection of the Space Below the Reactor Core
In the course of preparation for the inservice inspection a
question arose as to whether visual inspection of the space
below the reactor core was required at this time by ASME B&PV
Code Section XI Table IS 251 Category N examination.
The licensees inspection program regards the space below the
core as inaccessible for visual examination when components
are removed during normal refueling outages.
The licensee
stated that a visual examination will be performed under the
core at the end of the inspection internal (currently estimated
to be 1985) as is allowed by the requirements of Examination
Category N.
The inspector had no further questions.
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c.
Automated Ultrasonic Examination of Reactor Vessel Nozzle to
Pipe Welds
,,
The inspector examined the preparations for and partial
4
calibration of the equipment for the ultrasonic examination
of the nozzle to pipe weld (Inspection B.4.5.1 of SMUD's
inspection plan) for compliance to procedure ISI-131
Revision 5 and the requirements of ASME B&PV Code 1971 Edition
through Summer of 1973 Addenda.
No items of noncompliance or deviations were observed,
d.
Ultrasonic Examination of Steam Generator Secondary Manway
Studs and Nuts
The inspector examined the calibration of equipment for the
ultrasonic examination of the Steam Generator B Secondary
manway studs and nuts, inspections C.1.4.5 and C.1.4.6.
The
actual inspection was not performed at that time because the
studs and nuts had not been sufficiently cleaned for examination.
No items of noncompliance or deviations were observed.
(
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.
The examiners performed calibration for straight beam scan of
the ends of the nuts by establishing a reference level on the
scope using a 3/4" thick calibration block with a 1/2 t
reference reflector hole. The nut being scanned was approximately
2 1/2 inches thick. The applicable procedure, ISI 105, can be
'
read to allow calibration by the back reflection method or a
calibration block. The intent of the procedure, as established
by subsequent discussions with the examiners supervisor,
was to use the calibration block to establish a reference
level for straight beam scan from the nut flats and to use the
back reflection method for the straight beam axial scan from
the nut ends.
At the exit interview of February 15, 1980 licensee management
committed to resolve the proper method of calibration prior to
acceptance of data for the examination of the nuts and to
resolve whether a procedure clarification is required. This
item will be inspected further on a future inspection (Item
50-312/80-05/02)
e.
Ultrasonic Examination of the Pressurizer Power Operated
Relief Valve Nozzle to Head Weld and Pressurizer Spray line
To Head Weld
The inspector examined the calibration and examination of the
nozzle to head welds of the power operated relief valve and
the spray line nozzles for conformance to the requirements the
ASME B&PV Code and procedures ISI 130 and 124. These inspections
are licensee inspection numbers B.2.2.1 and B.2.2.2.
No items of noncompliance or deviations were noted.
..
f.
Qualifications of Nondestructive Examiners
The inspector examined the qualification records of three
Level II examiners and one Level III examiner for compliance
to the requirements of SNT-TC-1A of Summer 1973.
No items of noncompliance or deviations were observed.
9
Review of Quality Records
,
The inspector examined nondestructive examination records
including data sheets, calibration records and expendable
material certifications for the following examinations.
1)
Inspection B.4.5.90 Pressurizer spray elbow to pipe
weld, ultrasonic examination.
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2)
Inspection B.4.5.139 High Pressure Injection elbow to
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pipe weld, ultrasonic examination.
No items of noncompliance or deviations were observed.
5.
Exit Interview
The inspector met with the licensee representative denoted in
paragraph 1 on the dates indicated. The scope of inspections and
the inspectors findings as noted in this report were discussed.
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$