ML19225A306
| ML19225A306 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/04/1979 |
| From: | Blake J, Conlon T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19225A200 | List: |
| References | |
| 50-395-79-10, NUDOCS 7907180801 | |
| Download: ML19225A306 (7) | |
See also: IR 05000395/1979010
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LINITED STATES
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NUCLEAR REGULATORY COMMISSION
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Report No. 50-395/79-10
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South Carolina Electric and Gas Company
Licensee:
Columbia, South Carolina 29218
Facility Name: Virgil C. Summer
License No. CPPR-94
Inspection at 9 -
Site near Columbia, South Carolina
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Inspector:
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Date Signed
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~ 7j, Conlon , ' Won Chief, RC&ES Branch
<I)4te Signed
Approved by:
T.'EN
Inspection on March 20-23, 1979
Areas Inspected
This routine, unannounced inspection involved 28 inspector-hours onsite in
the areas of Licensee Action on Frevious Inspection Findings, RCPB Piping-
Work and Work Activities; RCPB Piping-Quality Records;
RCPB piping Welding-
Work and Work Activities; RCPB Piping Welding-Review of Quality Records;
Licensee Identified Item - Potential 50.55(e), Cable Tray Support, unauthor-
ized weld.
Results
Of the 6 areas inspected, no apparent items of noncompliance or deviations
were identified in 5 areas; an apparent item of noncompliance was found in
one area (Infraction - No requirements on weld profile
paragraph 7).
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DETAILS
1.
Persons Contacted
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Licensee Employees
- D. Moore, Director Surveillance Systems
- A. A. Smith, Site QA Coordinator
- H. Radin, Senior Engineer
- J.
Algar, Site Manager
- 0. S. Bradham, Manager - Operations
- T. A. McAlister, QA Surveillance Specialist
- C.
C. Turrett, QC Supervisor
- E. Evans, QA Supervisor
J. Gypin, QA Surveillance Specialist
Other licensee and contractor employees contacted included several
construction craftsmen and inspectors.
Other Organizations
Daniels Construction Company (DCC)
- J. Harvey, Construction Manager
- G. Curtis, Mechanical QC Supervisor
M. Pierce, QC Supervisor
K. Heaton, QC Engineer
Gilbert Associates, Inc. (GAI)
R. H. Fleming
- Attended exit interview.
2.
Exit Interview
The inspection scope and findings were summarized on March 23, 1979,
with those persons indicated in paragraph I above. The inspector
reviewed the scope and findings of the inspection. The details of how
the item of noncompliance evolved from the unresolved item No. 79-03-02
a
was discussed.
3.
Licensee Action on Previous Findings
,
a.
(Closed) Unresolved Item 50-395/78-04-02: Welds to be radiographed.
The inspector reviewed the additional radiographs taken of weld
FW-3 on ISO SP-09 and FW-14 on ISO CS-04.
These reshots were
com,,ared to the original radiographs for differences in technique
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and resolution of the questions raised during the initial radio-
graph review.
The apparent questionable indications noted during
the original review have been resolved. This item is closed.
b.
(Closed) Unresolved Item 50-395/78-15-01, Cold Spring Requirements.
,
The inspector verified that the licensee's cold spring requirements
are described in specification SP-220-044461-000 Revision 3, Work
Procedure WP-VII-09 Revision 7, and Quality Control Procedure
QCP-VII-09 Revision 5.
This item is closed.
c.
(Closed) Noncompliance 50-395/79-03-01, Failure to Follow Tape
Procedures. The inspector held discussions with licensee and
Contractor personnel concerning the corrective actions stated in
the letter of response. The inspector concluded that SCE&G had
determined the full extent of the subject noncompliance, performed
the necessary survey and follow-up actions to correct the present
conditions and developed the necessary corrective actions to preclude
recurrence of similiar circumstances. The corrective actions
identified in the letter of response have been implemented.
d.
(Closed) Unresolved Item 50-395/79-03-02:
No Requirements on Weld
Profile.
The inspector reviewed results (records) of the visual
inspection performed on velds subject to the " flush" requirements
described in Table NB-3683.2-1 of ASME Section III (71S73). This
review disclosed that one of the field welds (FW-3), had not met
the " flush weld" profile requirement. The inspector stated that he
would close this matter as an unresolved item and would identify it
as a noncompliance. This matter is discussed under paragraph 7 of
this report.
4.
Unresolved Items
Uuresolved items were not identified during this inspection.
5.
Inspector Follow-Up Items
(Closed) Inspector Follow-up Item 50-395/78-16-03:
Surveillance Reports
Show Unacceptable Welds Accepted. The GAI Resident Engineer submitted
the final engineering evaluation on the welding of the electrical conduit
hangers and supports it accepts the welds "as - is".
The inspector
reviewed the inspection data and discussed the methods used to evaluate
the conditions noted with the resident engineer and the licensee. These
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data vill be filed with the final resolution to the Corrective Action
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Request CAR-39.
Note: The close-out of CAR-39 apparently resolves the
question of the acceptability of the we~lds which are supposed to be in
these hanger and support systsms. Arather problem with apparent
unauthorized welding in these same 'aanger and support systems has been
discovered by the licensee and is discussed in paragraph 6 of this
report.
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052
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6.
Licensee Identified Items
On March 23, 1979, the licensee informed the inspector that IE:II had
been notified of a possible 50.55(e) item concerning unauthorized weld
splicing of cable tray supports.
The licensee reported that information concerning unauthorized weldit e
of cable tray support No. 256 had been received from an anonymous worker
"ia a QC inspector intermediary.
Nondestructive Examination (NDE) of
1.he support revealed a spli e weld with apparent internal defects such
as lack of fusion and slag inclusions (the surface area was ground
smooth which made the weld very hard to locate).
Destructive testing
(i.e.
Tensile and Bend Tests) confirmed the lack of complete fusion and
the presence of lag in the weld. These test data were being forwarded
to the licen ne's A&E resident engineer for evaluation.
The licer.see stated that the anonymous worker had now volunteered to
come f orward this weekend (March 24-25, 1979) and lead SCE&G personnel
to the_ location of many more unauthorized splices.
The licensee stated that thej will keep the IE:II project inspector
informed of the status of the investigation.
The inspector reviewed the test data and inspected the samples used for
the destructive tests. There were no questions concerning the tests.
The inspector informed the licensee that this item would be assigned
inspector followup item number 50-395/79-10-02 for tracking purposes.
7.
Reactor Coolant Pressure Boundary Pipint (Welding I) - Observation of
Work and Work Activities
The inspector observed field welding of reactor coolant pressure boundary
(RCPB) piping at various stages of weld completion.
The applicable Code
for reactor Coolant pressure boundary piping is the ASME Foiler and
Pressure Vessel Code,Section III, 1971 Edition with Summer 1973 addenda
(71 & 73) as implemented by DCC QA Program for ASME work.
The inspector examined weld joint fitup prior to welding to deter-
a.
mine whether weld identification / location, joint preparation and
alignment, evidence of QC verification meet applicable procedures.
The following veld joints were examined:
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Joint Number
Isometric
Svstem
Pine Size
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FW-3 Repair
Residuai lleat Removal (RIIR)
12-inch
b.
The inspector examined weld joints of pipe to pipe fitting (PPF)
and pipe to component (PC) where welding was beyond the root pass
to determiae weld / welder identification, qualified welder / weld
procedure, periodic checks of welding variables, use of specified
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weld material, proper interpass temperature, pre-heat, post-weld
heat treatment where applicable and, physical appearance of weld
starts, stops, undercut and surface inperfections).
(e.
g.
Joint Number
Size
Isometric No.
System
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FW-2
3.5-inch
Feactor Coolant
FW-3
3.5-inch
Reactor Coalant
As stated in paragraph 3.d above, the record review disclosed that
field weld FW-3 (piping to pressurizer veld) had not met the " flush
weld" profile requirements, as described in Table NB'3683.2-1 of
ASME Section III (71, S73) and engineering specification
SP-220-044461-000 Revision 3, because tne internal pipe surface
(root of the weld) was inaccessible for grinding and/or inspection.
The inspector stated that since Table NB 3683.2-1 provides stress
indices for the analysis of piping systems with welds furnished in
the " flush" and "as-welded" conditions, it appears that FW-3 of the
pressurizer surge line should have been nonconformed and the design
engineers notified that the more conservative "as-welded" stress
indices be used for the analysis of this pipe section.
In addition, the inspector stated that the contractor's failure to
include special weld contour requirements in a written procedure
had resulted in a weld condition which was less conservative than
specified in the licensee's engineering specification SP-220-044461-
000 Revision 3.
The licensee agreed with the inspector's interpre-
tation of Table NB 3683.2-1 requirements and stated that a noncon-
formance report would be generated to inform the stress analysts
that the more conservative stress indices be used for that weld.
Failure to include acceptance criteria in written form is in This
noncompliance with Criterion V of Appendix B, to 10 CFR 50.
is considered to be an infraction and identified as item number
395/79-10-01: No requirements on veld profile.
8.
Reactor Coolant Pressure Boundary Piping (Welding II) Review of Quality
Records
The inspector reviewed the quality records described below relative to
RCPB pipe welding to determine whether these records reflected work
accomplishment consistent with NRC requirements and FSAR commitments.
The applicable code for this' welding is the ASME Boiler and Pressure
Vessel Code,Section III, Subsection NB, 1971 Edition with Addenda
through the summer cf 1973 as implemented by the DCC ASME QA Program.
Weld records for the. listed welds were reviewed in the areas of;
a.
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visual and dimensiodal inspections, weld history, preheat and
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interpass temperature, NDE . weld repair, velder qualification and
inspector qualification, as opplicable to each weld:
Weld Number
ISO /Dwg. Number
Pipe Size
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FW-7R4
12-inch
FW-2R1
12-inch
ew-6
3.5-inch
FW-7
3.5-inch
FW-3R1
6-inch
FW-6
6-inch
FW-6
3.5-inch
FW-6R1
12-inch
b.
The following velding material records relative to;
receipt inspec-
tion, weld material certification, issue and storage control, and
disposition of unused materials were reviewed:
(1) Welding material field requisitions No. 160837, No. 107774,
No. 146666, No. 162463.
(2) Certifications and receipt inspection records for:
E-308L-16, Lot No. 308LB22
E-308L-16, Lot No. 308LB43
ER-308L, Heat No. 01554
The inspector reviewed the following nonconformance reports (NCR)
c.
relative to RCPB pipe welding to determine whether records were
complete, legible, retrievable and properly closed out:
NRC Number
Subject
0570
Reactor Coolant - Base Metal Defect Adjacent
ts FW-6 on C-Loop Cold leg.
0557
Reactor Coolant - Grinding of Tacks on Thermal
Shield of Surge Line Nozzle.
0542
Reactor Coolant FW-6R1, Craft Bypassed QC&AI
Hold Points.
0538
Valve 1-8346 Check - Class II Valve Installed in
Class 1 System.
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0517
Incore Instrumentation - Piping Dropped.
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0516
Reactor Coolant FW-6R4, Porosity Ground Out
Without Authority
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Within the areas examined, there were no items of noncompliance or
deviations identified.
9.
Reactor Coolant Pressure Boundary Piping (I) - Observation of Work and
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Work Activities
The inspector observed non-welding work activities for RCPB piping. The
applicable code for installation of RCPL piping is as shown in paragraph
7 of this report.
The following piping " runs" were inspected for compliance with instal-
lation specifications or plans:
From
To
Plan
Viive B702B
Valve 87elB
C.ld Leg Loop B
Valve 89,sB
Within the areas examined, there were no items of noncompliance or
deviations identified.
10.
Reactor Coolent Pressure Boundary Piping _ 'TI) - Review of Quality Records
The insprctor selected various RCPR piping components (e.g., pipe,
fittings and welded-in compone.cs) for review of pertinent records to
dete mine conformance with procurement, storage and installation speci-
fications and, QA/QC site procedures. A plicable requirements are
contained zu; I.icensee and contractor QA programs for ASME work.
Records of
t'- fol owing items were selected for review to ascertain
whether they (recards) were in conformance with applicable requirements
relative to the follocing areas: material test reports / certifications;
tendor supplied NDE reports; NSSS quality releases; site receipt
inspection; storage; installation; vendor nonconformance reports.
Item
System
Spool Piece 1-RC-04-01
12" Reactor Crolant
Valve 1-8702A
12" RHR
Spool Piece 1-51-22-02
6" Safety Inspection
Valve 1-h973B
6" Safety Inspect
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Spool Piece 1-RH-09-05
12" RHR
Spool Piece 1-RC-14-03
3.5" Reactor Coolant
Spool Piece 1-RC-14-04 '
3.5" Reactor Coolant
Valve 1-8074C
3.5" Reactor Coolant
Within the areas examined, there were no noncompliances or deviations
identified.
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