ML19337A745
| ML19337A745 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/26/1980 |
| From: | Dodds R, Narbut P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19337A744 | List: |
| References | |
| 50-312-80-25, NUDOCS 8009300054 | |
| Download: ML19337A745 (6) | |
See also: IR 05000312/1980025
Text
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U. S. NUCLEAR REGUIATORY C0!ciISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Rzport No.
50 312/An_9t;
Docket No.
50-319
License No.
no n_ c;a
Safeguards Group
Licensee:
Sacramento Municinal litilitv Dietrict
P. O. Box 15830
Sacramento. California 95813
Facility Name:
Rancho Seco
Inspection at:
Rancho Seco Site
Inspection conducted:
Aunust 11-15. 1980
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Inspectors:
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Da(e Signed
P. P. flarbut, Reactor Inspector
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Date Signed
Date Signed
Approved By:
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R.'T. Dod'ds, Chief, Reactor Engineering Supoort Branch
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Reactor Construction & Engineering Support Branch
Inspection on Auaust 11-15,1980 (Recort flo. 50-312/80-25)
Areas Inspected: Routine, unannounced inspection by regional based inspector
of the licensee's activities performed in response to open items from previous
inspections and inservice inspection data review. The inspection involved
40 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance or deviations were identified as a result
of the inspection.
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RV Form 219 (2)
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' DETAILS
1.
Persons Contacted
a.
Sacramento Municinal Utility District (SMUD)
- R. Colombo, Technical Assistant
- R. Miller, Chem. Rad. Supervisor ~
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- T. Tucker, Acting Operations Supervisor
- G. L. Coleman, QA Engineer
'D. Blachley, Mechanical Engineer
- J. McCulligan, Engr. & QC Supervisor
- H. Heckert, Nuclear Engineer Tech.
L. Smith, Generation Engineering
8. Stiver, Plant Mechanical Engineer
J. Parman, QC Inspector
J. Dowson, OC Coordinator
G. A. Coward, Maintenance Supervisor
J. Uhl, Plant Mechanical Engineer
- Denotes those attending the exit interview on August 15, 1980 which
was attended by J. O'Brien, NRC Resident Unit Inspector.
2.
Licensee Action on Previous Inspection Findinas
a.
(Closed) Open Item: Main Steam and Main Feed System containment
penetration radiographs were not in comoliance with the radiographic
procedure (Item 50-312/79-03/01).
The inspector examined the configuration of the main steam and main
feed system containment penetrations as depicted on drawing M-119.
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The configuration prohibited including one wall thickness on each
side of the weld and would not permit penetrameter placement on the
The licensee representative stated that the
Level III nondestructive examiner who reviewed the radiographic
films did not believe the ima
film (in the area of interest)ge of the aluminum film holder on the
interfered with the interpretability
of the film. The inspector had no further questions.
b.
(Closed) Open Item:
Licensee actions required subsequent to a water
hamer event on December 15, 1978 (Item 50-312/79-03/02).
The inspector's concerns were resolved through the licensee's actions
taken as a result of IE Bulletin 79-02, " Pipe Support Base Plate
Design Using Concrete Expansion Anchor Bolts", and the consequent
comitted actions which included 100% inspection of anchors and
commitments to increased detail in procedures and increased
Q //QC involvement. This item is considered closed on the basis
of the IE Bulletin 79-02 actions.
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c.
(Closed) Open Item: The final report on IE Bulletin 79-02 had not
been submitted to the NRC (Item 50-312/79-17/03).
Tne licensee submitted a final repo.rt dated June 26, 1980. This
item is considered closed.
d.
(Closed) Open Item: Several sliding; supports had lost their sliding
function due to support modification work (Item 50-312/79-17/07).
The remaining action for this item was to complete a system walkdown
to identify and remove "Concressive" compound from sliding surfaces.
The inspector examined the walkdown records and verified each support
had been inspected for Concressive compound and, if applicable, the
comoound removed and the support subsequently verified to be free of
compound. This item is considered closed.
e.
(Closed) Open item: Resolution required for method of ultrasonic
calibration for axial scan of steam generator secondary manway nuts
(Item 50-312/80-05/02).
The inspector examined the records of the ultrasonic examination
of the steam generator manway nuts (Examination C.l.4.6).
The records
showed that the calibration performed for the axial scan of the
steam generator nuts was the proper back reflection method. The
licensee representative stated that procedure clarification was
determined not to be requ Sed. The inspector had no further questions.
f.
(Closed) Open Item: The lists of supports analyzed and tested for
IE Bulletin 79-02 should be verified complete.
The-remaining action for this item, identified in Report 50-312/80-08,
was to compare the Bechtel list of analyzed supports and the SMUD
list of tested supports and ensure the lists were in agreement.
Bechtel Letter BSL-1057 of April 9, 1980 comoletes the comparison.
The letter identified a discrepancy of eight supports.
The eight
supports were reviewed with licensee personnel and determined to
be quality class 2 reactor building purge air supply supports outside
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the containment. The bulletin requirements do not apply to these
-supports.
This item is considered closed.
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g.
(Closed)OpenItem: Pipe support is inaccessible for inspection
(Item 50-312/80-08/02).
Support NSW SG-48401-11 identified in Report 50-312/80-14 as inaccess-
ible for inspection was resolved by not taking credit for the support
and adding a new support NSW-5G-48401-13 in an accessible area.
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This item is considered closed.
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h.
(Closed);0 pen _ Item: Justification for not testing small bore oiping
support had not been provided as required by IE Bulletin 79-02 (Item
50-312/80-14/01).
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The licensee provided justification 'in the final report submitted
June 26, 1980. This iten is considered closed.
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(Closed)OpenItem:
Licensee committed to perform metallographic
analysis on the cracked weld on valve'PLS-036.
The inspector examined the report on PLS-036 weld cracking provided
by the licensee. The report is by Anamet Laboratories Inc., dated
April 30, 1980 and is entitled " Analysis of Weld Cracking". The
report concluded that cracking of the weld was due to the use of a nickel
base alloy insert ring; probably ER NI Cr-3 (Inconel). The wye ring was
supposed to have been 308L (stainless steel) material. The material
came from the supply of wye inserts the licensee had maintained from
original construction.
Licensee representative stated that to the best
of their knowledge no otner wye insert welds had been made since initial
operc' ion. The PLS-036 weld was a unique case because of restricted work
space ed high radiation levels. As a subsequent action licensee
personnel discarded the remaining supply of wye insert wings.
The PLS-036 valve problem had been bypassed by removal of the valve
and capping of the pipe. The pipe caps were welded with normal weld
rod, not wye inserts. The inspector had no further questions.
3.
Review of Inservice Examination Data
The inspector examined the inservice inspection (ISI) report for the
1980 refueling outage. A sampling of the ASME Section XI categories
of examination was examined to detemine if the non destructive
examination (flDE) data covered the scope of examination as described
in the AStE Code and the licensees ISI program. A list of comments requiring
resolution was provided to licensee personnel.
Subsequent to further discussion
with licensee personnel by telephone after the exit interview all items
were resolved except for the reactor vessel skirt inspection (Category
H Table 15-251 of the ASME Code) which was not performed this outage due
to high radiation levels.
The examination was rescheduled to the fourth
refueling outage by Field Change 599-0481-12-01-0031. Hcwever, the re-
quirements of table 15-242 were not met. Table IS-242 requires a percentage
of the examination to be completed by the first one third of a ten year
inspection interval.
The first one third of the interval was completed
in the 1980 outage. The licensee representative comitted to consider
initiating a relief request to flRC (Licensing) which is currently reviewing
tht previously submitted revised SMUD ISI program. Therefore this item
will be inspected further in a future inspection (Item 50-312/80-25/01).
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The inspector examined the records of evaluations of reportable indications:
B.1.18.4, Peripheral CRDM motor tube to extension weld.
B.4.5.6.1, Pressurizer surge line pipe to elbow weld.
C.I.1, Stean generator A upper tube sheet to shell weld.
For examination C.I.1 the evaluation record listed three indications whereas
the data record listed five reportable:in'dications.
Subsequent discussion
with the licensee representative indicated that all five reportable indications
had been evaluated satisfactorily but two had not been listed on the
evaluation record because their layouts duplicated the listed conditions.
The inspector had no further questions.
The insoector examined the following leakage test records:
L.0.1, Reactor Coolant System
L.0.2.3, Make Up Pump
L.0.2.8, Building Spray B
L.0.3.5, Condensate Storage
L.03.12.1, Auxiliary Feed Pump A (including bearing and seals)
L.0.3.13.1, Auxiliary Feed Pump B (including bearing and seals)
No items of noncompliance or deviations were observed.
The inspector examined the data records for recordable indications on
the following support examinations:
C.2.6.5, Feedwater A Spring hanger
C.26.119, Make up suction Spring hanger
C.2.6.124, Decay Heat Removal A Spring hanger
The records indicate the cold spring setting on the hangers were properly
reset.
It was established by discussion with the licensee representative
that the two supports with loose fasteners were not in an inoperable
condition as a result of the conditions found. The inspector had no
further questions.
The inspector examined the following data records for examinations:
B.1.3.1, Reactor Vessel circle seam weld flange to upper shell
B.2.11.1, Pressurizer manway studs and nuts
C.2.3.11, Decay Heat Removal B Piping 6 inch Branch Connection
B.1.3.2, Reactor Vessel Closure Head Flange to Head
No items of noncompliance or deviations were observed.
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Exit Interview
At the conclusion of the inspection a meeting was held with the licensee
At the request of the i. cope and findings of the inspectionnspec
personnel denoted in paragraph 1.
The s
were discussed.
agreed to forward a copy of the detailed inservice inspection report to
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the llRC. :The insoector informed the licensee representatives-that, with
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the closecut of the open items 'related:to' IE Bulletin 79-02, the licensee's
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actions for the bulletin were considered' complete.
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