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{{Adams
#REDIRECT [[IR 05000285/1986016]]
| number = ML20199F193
| issue date = 06/17/1986
| title = Insp Rept 50-285/86-16 on 860527-29.Violation Noted:Failure to Establish Measures to Prevent Acceptance of Electrical Cable W/Insufficient Matl Test Rept
| author name = Ireland R, Norman D
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee name =
| addressee affiliation =
| docket = 05000285
| license number =
| contact person =
| document report number = 50-285-86-16, IEIN-83-72, IEIN-86-003, IEIN-86-3, NUDOCS 8606240220
| package number = ML20199F177
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 4
}}
See also: [[see also::IR 05000285/1986016]]
 
=Text=
{{#Wiki_filter:.
    .
                                          APPENDIX B
                              U.S. NUCLEAR REGULATORY COMMISSION
                                            REGION IV
      NRC Inspection Report:    50-285/86-16              Operating License:  DPR-40
      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~
                      D. E. Norman, Reactor Inspector, Engineering
                                                                        64;/B6
                                                                        Date
                        Section, Reactor Safety Branch
      Approved:          [ [.                                            t,// 7 /r/6
                      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
PDR    ADOCK 05000285
c                    PDR
 
  -    _                    _                                          __ __
k
        .
  e
                                                -2-
                                            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
1      *R. L. Andrews, Division Manager, Nuclear Production
!      *H. Faulhaber, Manager, Electrical Engineering, GSE
        *S. K. Gambhir, Section Manager, GSE
1          R. Conner, Electrical Engineer, Maintenance
                                                                    '
          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
i                replaced with Rockbestos Firewall III wiring. During this same
                inspection, terminal blocks and splices were inspected and modified
                as required to be upgraded to a qualified status.
.
                            .                -                      _        .  _ - -
                                                                                        . _ , ,
 
                                                                                N
    ..
  .
                                        -3-
      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
.
          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
 
  .                                    -_                        . -
          ,-
    .
                                                        -4-
                      o    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
l                    reported radiation aging of the cable as required by the
i                    purchase order. The cable was subsequently accepted by 0 PPD
!                      receiving and placed in CQE stores where it could be used in a
i
                      harsh environment. The failure to adequately control purchase
j                      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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