ML19323A592
| ML19323A592 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/20/1980 |
| From: | Dodds R, Narbut P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19323A587 | List: |
| References | |
| 50-312-80-08, 50-312-80-8, IEB-79-02, IEB-79-2, NUDOCS 8004210428 | |
| Download: ML19323A592 (5) | |
See also: IR 05000312/1980008
Text
MAR t ir 1990
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U. S. NUCLEAR REGUIATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Re ort No. 50-312/80-08
Docket No. 50-312
License No.
Safeguards Group
Licensee:
Sacramento Municipal Utility District
P. 0. Box 15830
Sacramento, California 95813
Facility Name: Rancho Seco
Rancho Seco Site
Inspection at:
Inspection conducted:
March 4-5, 1980
Inspectors:
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P. P. Narbut, Reactor Inspector
Date Signed
Date Signed
Date Signed
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Approved By:
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R. T. Dodds, Chief, Reactor Engineering Support Branch,[Date/ Signed
Reactor Construction and Engineering Support Branch
Su:::: nary :
Inspection on March 4-5, 1980 (Report No. 50-312/80-08)
Areas inspected:
Routine, unannounced inspection by. regional based inspectors
of the licensee's activities performed in response to IE Bulletin 79-02,
" Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts". The
ir.spection involved 16 inspector-hours onsite by one NRC inspector.
Results:
No items of noncompliance or deviations were identified as a
result of the inspections.
RV Form 219 (2)
soods2eLLM
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DETAILS
1.
Persons Contacted
a.
Sacramento Municipal Utility District (SMUD)
- R. Columbo, Technical Assistant
- J. Sullivan, Quality Assurance
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- G. A. Coward, Maintenance Suoervisor
- H. Heckert, Nuclear Engineer Technician
J. Dowson, QC Coordinator
D. Raasch, Generation Engineering
- L. Schwieger, QA Director
- Denotes those attending the exit interview on March 5, 1980
which was attended by H. L. Cantor, J. O'Brien and G. Zwetzig
of the NRC.
b.
Bechtel
R. Benson, Civil Engineer
2.
Licensee Action on previous Inspection Findings
a.
(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 acceptance criteria established by
the licensee for the acceptable degree of anchor expansion.
The acceptance criteria were derived from a University of
Tennessee study and appeared to be reasonable.
The inspector
had no further questions regarding the acceptance criteria.
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The acceptance criteria had not been applied to all the anchor
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inspection data, at the time of the inspection.
At the exit'
interview on March 5, 1980, the inspector discussed the potential
for additional' work that might-be identified as a result of
the remaining data review. Licensee management restated their
intention to complete the data review and take appropriate
actions in accordance with the bulletin requirements prior to.
the end of the current refueling outage. The item will
be inspected further on a future inspection.
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b.
'(0 pen) Unresolved Item:
Sliding supports had been modified by
the addition of non-sliding bracing (item 50-312/79-17/07)
The cognizant engineer stated that the commitment to remove
Concresive buildup from the faying surfaces of sliding supports
would be accomplished during a planned support by support
walkdown.
This aspect will be inspected further on a future inspection.
In regards to the need to provide periodic lubrication for
sliding supports, the cognizant licensee engineer provided a
letter BSL-978 of February 5,1980 which stated periodic
lubrication was not required since the design accounted for
friction coefficients for metal to metal contact surfaces.
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The inspector had no.further questions on this aspect of the
item.
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Based on the fact that the support design was based on metal ~
to metal friction factors, the fact that the supports observed
did not experience large thermal differentials between operation
and shutdown, the fact that the supports observed did not have
long pipe runs from fixed points, and the consideration that
the supports may have been installed for seismic movements
rather than thermal growth, the inspector had no further
questions. This aspect of the item is considered closed,
c.
(Closed) Unresolved Item: The effectiveness of Quality Assurance
in Maintenance / Modification work was questioned (Item 50-
312/79-17/08)
The question of quality assurance effectiveness, as it is
related to the control of maintenance and modification work,
was discussed with several supervisory licensee personnel
including quality assurance, quality control and engineering.
The licensee personnel stated that several actions were underway
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which included a. planned increase in the staffing of the
quality assurance group and the quality control group.
Other
actions included the hiring of engineering assistance for the
purpose of reviewing maintenance procedures for current-technical
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requirements and for the adequacy of' inspection callouts. An
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additional' action underway is the rewriting of standard inspection
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instructions. This item will be inspected further in the
normal course of future inspections.
Therefore this item is
closed.
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d.
(Closed) Open Item:
Anchor shell standout is not limited in
the procedure for inspection grouted supports.
Revision 3 to Procedure MT.017 Inspection of Concrete Fasteners
of 2/1/80 added a requirement to verify that the anchor shell
does not stand out above the concrete.
In addition it was determined by discussion with the Quality
Control Coordinator that the inspectors involved with anchor
bolt inspection had been specifically trained to inspect for
sleeve standout. Therefore this item is closed.
3.
IE Bulletin 79-02 " Pipe Support Base Plate Designs Using Concrete
Expansion Anchor Bolts".
,
The inspector examined the licensees activities in the area of
insuring that all seismic category 1 pipe supports using concrete
anchor bolts had been identified for test and analysis. The question
arose as a result of the licensees analytical activities in response
to IE Bulletin 79-14 " Seismic Analyses for As-Built Safety-Related
Piping Systems" wherein 89 additional supports were identified as
applicable to Bulletin 79-02 and required analysis to the requirements
of Bulletin 79-02. Cognizant licensee personnel stated that a list
of applicable supports had been generated during the system walk
downs done for Bulletin 79-14. This complete list of pipe supports
generated for Bulletin 79-14 was being used as a source document to
generate a complete list of those particular pipe supports which
used concrete anchor bolts (Bulletin 79-02). This list of supports,
which used anchor bolts, will be used to verify that the lists of
supports which had been:
(1) tested and, (2) analyzed for Bulletin 79-02 was, in fact, complete. The cognizant licensee personnel
stated this review and any consequently identified actions would be
completed prior to the end of the current refueling outage. This
item will be inspected further during a future inspection (Item 50-
,
312/80-08/01).
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The inspector examined. supports SG 29120-1 (CBS Aux Bldg) and
10-29122-4 (CBS Containment) which were two'of approximately 20
supports identified as having inaccessible anchor bolts. The
Region V imediate action letter of January 14, 1980 recorded the
agreement reached between the NRC and the licensee.
The letter
stated, in part that the licensee would perform inspections to the
extent possible on those anchors determined to be inaccessible.
The concrete anchors listed as inaccessible on support 10-29122-4
were accessible for inspection. -Further questioning of cognizant
licensee personnel ~ determined that the instructions given to anchor
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bolt inspection personnel were that anchors which were not accessible
for repair should not be tested, even if there was sufficient
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accessibility for testing.
It was further determined that'all the
supports with anchor bolts listed as inaccessible were being reanalyzed
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without taking credit for the inaccessible anchor bolts to determine
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if the. remaining ancnor bolts were capable of carring the design
' load within the bulletin required factors of safety. At the time
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of inspection, all supports :s'o analyzed met the factor of safety
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requirements.
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At the exit interview of March 5, 1980, the licensee management
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committed that the above approach would continue.to be used and any
instance where bulletin requirements were not met would be identified
to the NRC with appropriate justification prior to the end of the
current refueling outage. This item will be-inspected further in a
futureinspection(Item 50-312/80-08/02).
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4.
< Exit Interview
The inspector met with the licensee representatives denoted'in
paragraph 1 on the date indicated. 'The scope of inspections and
the inspectors findings as noted in this report were discussed.
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