ML20199F193
| ML20199F193 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/17/1986 |
| From: | Ireland R, Norman D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20199F177 | List: |
| References | |
| 50-285-86-16, IEIN-83-72, IEIN-86-003, IEIN-86-3, NUDOCS 8606240220 | |
| Download: ML20199F193 (4) | |
See also: IR 05000285/1986016
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APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-285/86-16
Operating License:
Docket: 50-285
Licensee: Omaha Public Power District
1623 Harney Street
Omaha, Nebraska 68102
Facility Name:
Fort Calhoun Station, Unit 1
Inspection At: Omaha and Fort Calhoun, Nebraska
Inspection Conducted: May 27-29, 1986
Inspector:
[ 78mo~
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D. E. Norman, Reactor Inspector, Engineering
Date
Section, Reactor Safety Branch
Approved:
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R. E. Ireland, Chief Engineering Section,
Ddte '
Reactor Safety Branch
Inspection Summary
Inspection Conducted May 27-29, 1986 (Report 50-485/86-16)
Areas Inspected:
Special, announced inspection to determine what wiring was
installed in Limitorque valve operators and to review licensee's environmental
equipment documentation to ensure that qualification of wiring was adequately
established. The inspection also included a review of licensee's actions
relative to Information Notices (IN) 83-72 and 86-03.
Results: The inspection determined that the licensee had replaced wiring in
Limitorque valve operators with wiring which was qualified to the requirements
of 10 CFR 50.49; however, the NRC inspector found that the licensee had
accepted safety-related wiring with a material test report which did not
document results of all required tests.
8606240220 860620
ADOCK 05000285
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DETAILS
1.
Persons Contacted
Omaha Public Power District (0 PPD)
J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs
- D. J. Munderloh, Sr. Engineer, Nuclear Regulatory and Industry Affairs
- M. R. Core, Supervisor, Maintenance FCS
A. W. Richard, Manager, Quality Assurance
- T. L. Patterson, Manager, Technical Support
R. Ronning, Co-op Engineer
- J. Tucker, Senior Electrical Engineer, GSE
- R. L. Jaworski, Section Manager, Technical Services
- J. K. Gasper, Manager, Administrative Services
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- R. L. Andrews, Division Manager, Nuclear Production
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- H. Faulhaber, Manager, Electrical Engineering, GSE
- S. K. Gambhir, Section Manager, GSE
R. Conner, Electrical Engineer, Maintenance
1
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NRC
- D. E. Norman, Reactor Inspector
- Denotes those present at the exit interview.
2.
Purpose
The purpose of this inspection was to identify wiring used in Limitorque
valve operators installed in a 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 ins 83-72 and 86-03.
3.
Inspection Summary
a.
Review of Previous Licensee Actions
As a result of notices from industry and the NRC, the licensee had
performed various inspections and in some instances modifications to
Limitorque valve operators located in a harsh environment. During
the last outage, internal wiring in each operator was removed and
replaced with Rockbestos Firewall III wiring.
During this same
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inspection, terminal blocks and splices were inspected and modified
as required to be upgraded to a qualified status.
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b.
Hardware' Inspection
The EQ master list contained 28 Limitorque operators, with 21 inside
containment and 7 outside. The following three operators, located
outside containment were inspected by the NRC inspector for proper
wiring, terminal blocks, splices, and switches.
o
HCV-308 (S/N - N/A)
o
HCV-347 (S/N 100847)
o
HCV-1384 (S/N 130436)
Gray and tan wires were found during the inspection, but none of the
wires had manufacturer identification markings.
It was explained by
the licensee that the wires had been removed from a reel of
3-conductor jacketed Firewall III cable which had the identification
on the jacket; therefore, the insulation had not been marked,
c.
Documentation Review
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Supporting qualification documentation for Limitorque operators was
included in Operations Support Analysis Report (0SAR) 85-17. The
following items from the OSAR were reviewed by the NRC inspector:
(1) System Component Evaluation Work (SCEW) Sheets: SCEW sheets for
all operators were reviewed to determine specified and
qualified environmental conditions, method of qualification,
qualified life, and reports used to support qualification.
No
questions were identified with the SCEW sheets.
(2) Vendor / Consultant Qualification and Analysis Reports: The NRC
inspector verified qualification of Limitorque operators by
reviewing Limitorque test report B0058 dated January 11, 1980,
and supporting analyses conducted by Di Benedetto Associates as
reported in Document Number OPD03-07-06 dated April 19, 1985.
These documents support a 40-year life for the operators when
certain qualified age sensitive materials (i.e., motor coil
insulation, switch base and rotor material, terminal blocks, and
wire insulation) are installed as tested.
(3) Limitorque Operator Modification Documentation: The following
documentation which addressed the inspection and modification of
operators was reviewed by the NRC inspector:
o
Engineering Evaluation and Assistance Request (EEAR) dated
December 23, 1985
o
Safety-Related Design Change Order (SRDCO) 85-17, dated
December 28, 1986
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Work Instruction MR-FC-85-220
Instructions.in MR-FC-85-220 were used by the licensee for the
inspection and modification of operator wiring, terminal blocks,
and splices. Records showed that splices and terminal blocks
were modified as required and all internal wiring was replaced
with Firewall III wiring purchased under Purchase Order 526016,
dated April 21, 1982, to OPPD Specification GSEE-0504. Quality
Control verified that the designated wire was installed in each
operator.
(4) Wire Purchase Order and Certified Test Report
Purchase Order 526016 was reviewed and appeared to adequately
describe requirements for wire to be used in a harsh
environment. The Rockbestos material test report for the cable,
however, neither described the cable as Firewall III nor
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reported radiation aging of the cable as required by the
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purchase order. The cable was subsequently accepted by 0 PPD
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receiving and placed in CQE stores where it could be used in a
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harsh environment. The failure to adequately control purchase
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material is a violation of 10 CFR 50, Appendix B (285/8616-01).
Based on available documentation tne NRC inspector was unable to
verify that the cable had been radiation aged and was Firewall
cable which had been qualified by Rockbestos Report
Number QR-4802. On May 29, 1986, a telephone call by the
licensee confirmed that the cable (Product Code C07-3133) was
Firewall III with irradiated XLP insulation.
It was, therefore,
qualified for use in the operators.
4.
Exit Meeting
An exit meeting was conducted on May 29 with the persons identified in
paragraph 1 at which time results of the inspection were discussed.
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