ML19312E758
| ML19312E758 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/23/1980 |
| From: | Dodds R, Narbut P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19312E753 | List: |
| References | |
| 50-312-80-14, IEB-79-02, IEB-79-13, IEB-79-2, NUDOCS 8006090503 | |
| Download: ML19312E758 (5) | |
See also: IR 05000312/1980014
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0FFICE OF INSPECTION AND ENFORCEME!.~f
REGION V
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Report No.
50-312/80-14
Docket No.
50-312
License No.
Safeguards Group
I.icensee:
Sacramento flunicipal Utility District
P. O. Box 15830
Sacramento, California 95813
Facility Nace:
Rancho Seco
Inspection at:
Rancho Seco Site
Inspection Conducted: lla'rch 25-27, 1980
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Inspectors:
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F.
narcut, Keactor Inspector
date 41gned
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Date Signed
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Date Signed
Approved By:_ _
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W
n. i. voces, tnier, xeactor tngineering dupport branch
Ifatc 41gned
Reactor Construction a.nd Engineering Supprot Branch
S u =a ry :
Inspection on flarch 25-27, 1980 (Report No. 50-312/80-14)
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Areas Inspected: Routine, unannounced inspection by regional based inspec-
tors of the licensee's activities performed in response to IE Bulletin 79-02,
" Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts",
IE Bulletin 79-13 " Cracking in Feedwater System Piping" and an examination
of a reported weld cracking problem during valve installation.
The inspec-
tion involved 24 inspector-hours onsite by one NRC inspector.
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Results:
No items of noncompliance or deviations were identified as a re-
sult of the inspections.
av Form 219 (2)
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DETAILS
1.
Persons Contacted
a.
Sacramento Municioal Utility District (SMUD)
- P. Oubre, Plant Superintendent
- R. Colombo, Technical Assistant
- J. Sullivan, Quality Assurance
- G. A. Coward, Maintenance Supervisor
- H. Heckert, Nuclear Engineer Technician
- J. Dowson, QC Coordinator
- W. Ford, Supervisor Nuclear Operations
- D. C. Blachly, Mechanical Engineer
- ti. Carter, Outage Coordinator
- J. Field, Mechanical Engineer
- B. Stiver, Plant Mechanical Engineer
- Denotes those attending the exit interview on March 27, 1980
which was attended by H. L. Canter, NRC Resident Inspector,
and C.* Kammerer, Director, Office of Congressional Affairs, NRC.
b.
Bechtel
R. Benson, Civil Engineer
2 .,
Licensee Action on orevious inspection findings
a.
(Closed) Open Item: Acceptance criteria for concrete exoansion
anchor exoansion was not established and inspection data had not
been evaluated (Item 50-312/79-17/01)
The inspector examined a sampling of the support documentation and
determined that all the anchor wedge position data in that sample
had been properly evaluated and appropriate action taken, that is
either by analysis or repair. Exceptions to the above were data
on four supports from the initial data sheets of July 1979. Al -
though these data sheets had unacceptable anchor wedge position
data they hadn't been identified by the engineering personnel
performing the data review. A 100% rereview was done by the en-
gineering personnel and nu additional data sheets were identified.
The licensee coninitted to evaluate the data for the four supports
and take appropriate action prior to the resumption of power op-
erations. The inspector had no further questions.
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b.
(0 pen) Open Item: Sliding supports had been modified by the addition
of non-sliding bracing (item 50-312/79-17/07)
The remaining action on this item was completion of the commit-
ment to remove concresive buildup from the faying surfaces of sliding
supports which would be accomplished durina a planned support by
support walkdown.
This action had not been completed at the time of this inspection.
The inspector examined the preplanning for the walkdown and the
walkdown packages being assembled by Quality Control personnel.
The planning actions appeared to be well organized.
The results of the walkdowr. will be examined on a future inspection.
c.
(0 pen) Open Item: List of oipe supports for IE Bulletin 79-02
has not been verified comolete.
(Item 50-312/80-08/01)
The cognizant licensee engineering personnel stated that the ver-
ification that the list of pipe supports field tested at Rancho
Seco was complete.
The verification that all those supports were
analyzed in accordance with the Bulletin requirements had not been
completed but at the exit interview licensee management personnel
committed to ensure that the review to ensure all supports had been
analyzed would be completed prior to the end of the current refuel-
ing outage.
d.
(Ocen) Open Item: Anchors inaccessible for possible repair were
considered inaccessible for testing even if testing was possible.
(Item 50-312/80-08/02)
At the time of inspection all supports except two had been analyzed
for the effect of treating anchors as inaccessible. One support
NSW SG 48401-11 was determined to be totally inaccessible for
inspection, or testing.
At the exit interview licensee management personnel committed
to complete the analysis and any necessary actions on the two
unanalyzed supports. Additionally, management committed to resolve
the inaccessible support NSW SG 48401-11 from a system operability
standpoint.
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e.
(Closed) Noncompliance Item: Data on anchor bolt expansion signed
off as acceptable by engineer an6 quality control oersonnel with-
out evaluation to quantitative acceptance criteria.
(Item 50-312/
79-17/09)
This item was closed based on the licensee's response of February
27, 1980.
3.
IE Bulletin 79-02 " Pipe Support Base Plate Desions Using Concrete Ex-
pansion Anchor Bolts."
The inspector examined previous open items as reported in
paragraph 2 of this report. One new item was brought up however.
The bulletin requires that for piping 21s inches and smaller testing
need not be done if the licensee can demonstrate that the degree of
conservatism used in supporting the small bore pipe is sufficient to
account for the expected installation deficiency rates, that is to
justify not performing testing from a system operability standpoint
for small bore piping. The licensee is not testing small bore pipe
support and has not justified this from a system operability standpoint.
At the exit interview licensee management comitted to resolve this
issue from a system operability standpoint prior to resumption of power
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operations .
This item will be inspected further on a future inspection (Item 50-
312/80-14/01).
4.
IE Bulletin 79-13 " Cracking in Feedwater System Pipino"
The inspector examined licensee actions in response to Bulletin 79-13.
SMUD has perfonned the visual inspection of piping supports in the
.eedwater system.
However volumetric examination of the flanged nozzle
to piping and outboard piping welds was not performed on the basis that
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Rancho Seco has constant feedwater level within the steam generator
and no intermittent cold auxiliary feedwater injection and, under those
conditions, the bulletin does not require volumetric cxamination.
At the exit interview, licensee management committed to address in
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their response to the bulletin the operational details which alleviate
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the need for Rancho Seco to perform volunetric examinations per the
bulletin.
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5.
Welding, Letdown Orifice flanual By- 'ss Valve
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The inspector examined selected aspects of the welding of valve PLS-036,
the Letdown Grifice Manual By-pass Valve. A replacement valve was being
welded in the piping system.
It was reported that initially four attempts
had been nade to weld the valve and each had resulted in cracking either
in the root or cover pass.
The inspector examined the Maintenance Inspection Data Report f1M-187-R1,
and the chemical and physical certifications aoplicable to the weld rod,
valve body and reducers. No items of noncompliance or deviations were observed.
At the exit interview licensee management committed to have the cut
out weld examined metallagraphically to determine the cause of crack-
ing. Licensee management further committed to notify the NRC s'ould
they make the decision not to examine the cut out weld prior to dis-
carding the cut out weld.
This item will be inspected further on a future inspection.
(Item
50-312/80-14/02)
6.
Exit Interview
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The inspector met with the licensee representatives denoted in para-
graph 1 on the date indicated. The scope of inspections and the in-
spectors findings as noted in this report were discussed.
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