ML20199E808
| ML20199E808 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/06/1986 |
| From: | Ireland R, Norman D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20199E801 | List: |
| References | |
| 50-458-86-19, IEIN-86-003, IEIN-86-3, NUDOCS 8606240088 | |
| Download: ML20199E808 (7) | |
See also: IR 05000458/1986019
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APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-458/86-19
License:
Docket:
50-458
Licensee: Gulf States Utilities
P. O. Box 220
St. Francisville, Louisiana 70775
Facility Name:
River Bend Station (RBS), Unit 1
Inspection At:
St. Francisville, Louisiana
Inspection Conducted:
April 28 through May 2, 1986
Inspector:
I. M
4/z/c//
D. E. Norman, Reactor Inspector, Engineering
Date' ~ ^
Section, Reactor Safety Branch
Approved:
e[. M
4//,/d
R. E. Ireland, Chief, Engirteering Section,
Ddte"
Reactor Safety Branch
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Inspection Summary
Inspection Conducted April 28 through May 2, 1986 (Report 50-458/86-19)
Areas Inspected:
Special, announced inspection to determine what wiring is
installed in Limitorque valve operators and to review licensee's environmental
qualification documentation to ensure that qualification of wiring is
adequately established.
The inspection also included a review of licensee's
actions relative to IE Information Notice (IN) 86-03.
Results:
The inspection determined that Limitorque had qualified valve
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operators without internal wiring being in place and that some wiring later
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installed by Limitorque did not have documentation to show qualification in
accordance with requirements of 10 CFR 50.49.
The licensee previously had
taken corrective action regarding unqualified wiring and determined that no
further action was required with respect to IN 86-03; however, the NRC
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inspector found:
(1) two operators with apparently unqualified wiring,
(2) test reports for wiring in several operators were not available at the
site.
P606240088 860620
{DR
ADOCK 05000458
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DETAILS
1.
Persons Contacted
Gulf States Utilities (GSU)
- W. J. Cahill, Senior Vice President
- P. F. Tomlinson, Director, Quality Services
- I. M. Malik, Supervisor, Quality Engineering
- T. L. Crowe, Quality Assurance Manager
- D. M. Rynnerson, Director, Nuclear Plant Engineering
- R. E. Bailey, Supervisor, Quality Control
- G. K. Henry, Supervisor, Electrical Engineering
- R. B. Stafford, Director, Operations Quality Assurance
- H. M. McClellan, Senior Compliance Analyst
- J. C. Deddens, Vice President, River Bend
- E. R. Grant, Supervisor, Nuclear Licensing
- T. O. Moffitt, Quality Engineer
- J. L. Frick, Supervisor, Electrical Maintenance
- L. Schell, Senior Electrical Engineer
- D. R. Gipson, Assistant Plant Manager, Operations
R. King, Licensing Engineer
J. H. McQuirter, Licensing Engineer
H. S. Garcha, Senior Quality Assurance Engineer
J. E. Spivey, Operations Quality Assurance Engineer
R. Eddings, Electrician
B. Johnson, Electrician
F. Boyle, Quality Control
D. Derbonne, Supervisor, General Maintenance
Stone and Webster (S&W)
A. Abella, Senior Field Engineer
Nuclear Regulatory Commission (NRC)
- D. D. Chamberlain, Senior Resident Inspector
W. B. Jones, Resident Inspector
- D. E. Norman, Reactor Inspector
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- Denotes those present during exit interview on May 2, 1986.
2.
Purpose:
The purpose of this inspection was to identify wiring used in Limitorque
valve operators installed in harsh environment, to review licensee's
environmental qualification documentation to ensure that qualification of
wiring was adequately established, and to review licensee's actions
relative to IN 86-03.
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3.
Inspection Summary
a.
Review of Previous Licensee Actions
During the disassembly of a spare Limitorque operator, which was
originally intended for use at RBS, Unit 2, the licensee disco"ered
that the control wiring was apparently unqualified.
It was
subsequently verified by Limitorque that no qualification
documentation was available for the wiring.
Since the operator
(2E22-F011) was of the same vintage as the remaining operators
provided by General Electric, those operators were also inspected and
found to have unqualified wiring.
The wiring was later replaced
according to Modification Request (MR) 86-0037 and the condition was
reported by LER 86-008.
The following operator numbers, with
corresponding Limitorque serial numbers, were included in the
modification:
(1) 1E22*M0VF001
(S/N 219152)
(2) 1E22*MOVF004
(S/N 232682)
+(3) 1E22*MOVF010
(S/N 220882)
(4) 1E22*MOVF011
(S/N 220881)
(5) 1E22*MOVF012
(S/N 223864)
(6) 1E22*MOVF015
(S/N 223875)
(7) 1E22*M0VF023
(S/N 223009)
+(8) 1DFR*MOV146
(S/N 223969)
+0riginally provided for Unit 2.
Five additional valves (S/N 219153, 220880, 222394, 223970, and
230642) manufactured during the same time period, and provided for
Unit 2, by General Electric, have not been modified since their
future application is unknown. Their status has been documented by
Condition Report 86-052, and they have been tagged to prevent use
without prior approval.
Condition Report 86-038 reported that an inspection was performed
during 1985 on all 62 Limitorque operators in the reactor building
and identified that only Rockbestos or Raychem wiring was used.
Either wiring was acceptable to Revision 5 of the Installation
Specification 228.160.
An additional inspection was reportedly
performed on January 12, 1986, of five randomly selected operators
outside containment.
This inspection verified all acceptable wiring
except for one unidentified jumper wire connecting terminal 3C to 7C,
on operator S/N 275572 which was reported on CR 86-049.
The wire was
subsequently dispositioned as acceptable per the installation
specification.
Based on the previous inspection activity related to
Limitorque wiring, the licensee concluded that no further action was
considered necessary in respect to IN 86-03.
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b.
Hardware Inspection
(1) Sample Selection
The Master List of safety related equipment located in a harsh
environment was reviewed and a sample of 22 operators, of the
216 listed, was selected to be inspected.
This sample was later
reduced to 10 after reviewing results of the licensee
inspections of operator wiring.
Selection of the final sample
was based on the following criteria:
(a) operators from several
safety systems, (b) range of Limitorque serial numbers, (c) at
least one operator previously inspected by licensee, and
(d) operators located outside high radiation areas.
The
following operators were included in the sample:
(1) 1CCP*MOV129
(S/N 330879)
(2) 1CNS*MOV125
(S/N 316310)
(3) 1C11*MOVF083 (S/N 277282)
(4) 1E12*M0VF0038 (S/N L376337)
(5) 1E12*M0VF105 (S/N 328286)
(6) 1E33*MOVF005 (S/N 329986)
(7) 1FPW*MOV121
(S/N 321186)
(8) 1HVN*MOV130
(S/N 325731)
(9) ISWP*MOV5078 (S/N 318079)
+(10) 1LSV*MOV19A
(S/N 275572)
+Previously inspected by licensee.
(2) Findings
Each operator was inspected to establish the type of internal
wiring.
Most long wires could be identified by wiring
manufacturer markings; however, many short wires did not have
markings and were identified by visual comparison to wires with
markings.
All wires in eight of the operators were identified
as Raychem or Rockbestos Firewall III.
Operator S/N 275572 had
one short jumper wire which did not have markings and did not
appear similar to the identified wires.
Most wires inside
operator S/N 277282 were red and had markings of "Phalon AMW
105 C FR-1 CSA TEW."
Field wiring which interfaced with the operators was also
inspected.
All wires appeared to be the same type; however,
specific identification could not be made at this point since
the jacket material, which contained the markings was not
visible.
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c.
Documentation Review
(1) System Component Evaluation Work (SCEW) Sheets
SCEW sheets for the sample operators were reviewed to determine
specified and qualified environmental conditions, method of
qualification, qualified life, and reports used to establish
qualification. The following discrepancies were identified
during this review:
(a) SCEW sheets indicated that several unqualified model SMC
operators were installed in harsh environment. The
operators have been replaced; however, the SCEW sheets have
not been updated to reflect this change.
(b) SCEW sheets reference the qualification report of the
Limitorque operator which was qualified without internal
wiring.
The wiring qualification report, therefore, should
be part of the qualification documentation and should be
referenced on the SCEW sheets.
The failure to update SCEW sheets and to reference all
applicable qualification documentation therein are apparent
deviations from the River Bend Station Environmental Qualifica-
tion Document, Revision 1, March 1985.
(458/8619-01)
(2) Cable Pull Tickets
Cable pull tickets for field cable interfacing with the
following operators were reviewed to establish cable identity.
(a)
ICCP*M0V129
(b)
ICNS*MOV125
(c)
1E33*M0VF005
(d)
1HVN*MOV130
The cables were identified as Okonite-FMR insulated cables whose
qualification was reported in Okonite Reports SWGS-1282-1 and 2.
(3) Vendor Qualification Reports
The following manufacturer or test laboratory qualification
reports were reviewed:
(a) Limitorque Report B0058, Valve Actuator Qualification,
dated January 11, 1980.
(b) Rockbestos Report QR 5805, AWG Power Cable, dated
November 18, 1985.
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(c) Okonite Reports SWGS-1282-1 and -2, Okonite Insulated Cable
Nuclear Qualification Report, dated December 15, 1982.
(d) S&W Calculation Nos. 12210-EQS-4, -5 and -10, Calculations
to Support Qualified Life of Limitorque actuators.
(e) Franklin Institute Research Laboratories Report F-C4033-1,
Tests of Raychem Flamtrol Insulated and Jacketed Electrical
cables, dated January 1975.
It was mentioned previously in this report that wiring
qualification reports were not referenced on the SCEW sheets;
however, the licensee provided "Rockbestos Report QR 5805 which
appears to establish qualification of Rockbestos wiring used in
the operators.
The licensee presented Franklin Report F-C4033-1
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as the basis for establishing qualification of Raychem wiring,
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but this report does not appear to provide that basis for a
single conductor, nonjacketed wire as used in the operators.
While the wire does appear to be qualified it currently lacks
qualification documentation.
This is considered to be an
unresolved item pending verification that qualification
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documentation exists.
(458/8619-02)
A test report for the Phalon wiring, used in operator S/N 277282
was not reviewed by the NRC inspector; however, a summary of a
telephone conversation between the licensee and Limitorque
stated that the test report did not include aging and that mild
to moderate PVC insulation damage resulted at about 2 x 107
Rads, which is the specified radiation environment for the
operator.
Phalon wiring does not appear to be properly
qualified. This is a potential violation of 10 CFR 50.49.
(458/8619-03)
In paragraph 3.b(2) it was reported that one short jumper wire
in operator S/N 275572 had no identification markings and did
not appear similar to identified wires.
This same wire has been
identified during two independent inspections, once by a
licensee QC inspector and once by the NRC inspector.
Since
qualification documentation could not be provided for the wire,
this is considered a potential violation of 10 CFR 50.49.
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(458/8619-04)
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4.
Licensee Corrective Action
Shortly after discovery of the apparent unqualified wire in operator
S/N 277282, the plant experienced a SCRAM because of an unrelated problem.
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Prior to restarting, the licensee replaced the questionable wires with
qualified wires and conducted an inspection of the following operators:
a.
1E33*MOVF008 (S/N 275562)
b.
1E12*MOVF073A (S/N 275566)
c.
1E112*MOVF073B (S/N 275567)
d.
1E112*MOVF074A (S/N 275569)
e.
1E112*M0VF074B (S/N 275568)
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1LSV*MOV19A (S/N 275572)
g.
1LSV*MOV19B (S/N 275573)
h.
1E33*MOVF006 (S/N 275574)
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1E33*MOVF026 (S/N 275575)
j.
1E51*M0VF077 (S/N 275862)
+k.
1C11*MOVF083 (S/N 277282)
+Previously inspected.
No additional unqualified wires were found.
Limitorque stated in a memorandum to S&W, dated February 3,1983, that
they provide two types of a<',uators for nuclear service.
Units for inside
containment had Rockbestos rirewall III or Raychem Flamtrol control
wiring.
Units for outside containment with serial numbers greater than
283870 also had Firewall III or Flamtrol wiring, but earlier unit' had TEW
wire.
After the inspection of the above operators, all operators with
serial numbers below 283870 located in a harsh environment have beer
inspected at RBS.
Approximately 140 valve operators in a harsh
environment outside containment with serial numbers greater than 283870
have not been inspected.
5.
Exit Interview
An exit inverview was conducted on May 2, 1986, during which time results
of the inspection were reviewed with members of the GSU staff.