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#REDIRECT [[IR 05000458/1987021]]
{{Adams
| number = ML20151R716
| issue date = 04/05/1988
| title = Insp Rept 50-458/87-21 on 871102-26 & 1218.Violations Noted. Major Areas Inspected:Licensee Implementation of Program for Establishing & Maintaining Qualification of Electric Equipment within Scope of 10CFR50.49
| author name = Johnson A
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee name =
| addressee affiliation =
| docket = 05000458
| license number =
| contact person =
| document report number = 50-458-87-21, NUDOCS 8804280071
| package number = ML20151R676
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 35
}}
See also: [[see also::IR 05000458/1987021]]
 
=Text=
{{#Wiki_filter:_ _ _ _ _ _ _ _ - _ - _ _ _ _ _
  .
                                            APPENDIX B
  .
                              U.S. NUCLEAR REGULATORY COMMISSION
                                            REGION IV
      NRC Inspection Report:    50-458/87-21          Operating License: NPF-47
      Docket:  50-458
      Licensee: Gulf States Utilities (GSU)
                  P.O. Box 220
                  St. Francisville, Louisiana 70775
      Facility Name:    River Bend Station (RBS)
      Inspection At:    St. Francisville, Louisiana 70775
      Inspection Conducted:    November 2-26, 1987 (onsite) to December 18, 1987
                                (NRC Region IV office)
      Inspector:      __j.          M        DM&                                                              '
                                                                                                                86
                      A. R. Jofinson ' Reactor Inspector, Division of        Date
                        Reactd        ty
      Accompanying
        Personnel:    J. L. Milhoan, Director, Division of Reactor
                        Safety (DRS), Region IV (RIV)
,                      R. Maist, Equipment Qualification and Test
!                        Engineer, DRIS, NRR
l                    M. Trojovsky, Consultant Engineer, Idaho
                        National Laboratory (INEL)
;                    Q. Decker, Consultant Engineer, INEL
,                    V. Nicolette, Member of Technical Staff,
                        Sandia National Laboratories
                      R. E. Irelana, Acting Chief, Plant Systems
                        Section (PSS), DRS, RIV
                      D. E. Norman, Reactor Inspector, PSS, DRS, RIV
{
                      R. Evans, Reactor Inspector, PSS, DRS, RIV
l
      Approved:              [ N /b/
                      R. E. Ireland,' Acting Chieft Plant Systems          ~~Date '
                                                                                            f/[[
                        Section, Division of Reactor Safety
      Inspection Summary
      Inspection Conducted November 2-6,1987, (onsite) to December 18, 1987 (NRC
:    Region IV Office) (Report 50-458/87-21)
j    Areas Inspected:    Special, announced inspection to review the licensee's
      implementation of a program for establishing and maintaining the qualifict. tion
l
                        ~
    ~~8804'280071'880419
    PDR    ADOCK 05000458
    g                    DCD
 
                                                                        .  _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _
              .                                                            .
  .
                                                                      2
  .
    of electric equipment within the scope of 10 CFR 50.49. In preparation for
    this inspection, the NRC team included a review of GSU's implementation of
    equipment qualification (EQ) corrective action commitments, identified in
    Safety Evaluation Report, NUREG-0989, May 1984 (SER), SER Supplements 3 and 5
    (August and May 1985). These documents provide the NRC staff acceptance with
    regard to equipment for which justification for interim operation (JI0s), were
    provided prior to the November 30, 1985, deadline.
    The NRC inspection team reviewed a sample of 45 EQ binders (job books and
    packages) in the EQ file (EQF) out of a total of 89, and walked down 38
    components / equipment.
    Results: The inspection determined that the licensee has implemented a program
    to meet the requirements of 10 CFR 50.49, however, four violations of NRC
    requirements and five unresolved items about which more information is
    required, were identified.
l
l    The licensee's submittals (GSU Walkdown Question / Response Identification Forms)
i
    to the NRC Region IV during and subsequent to the onsite inspection period,
    provided additional information and addressed the inspection findings presented
    in the exit interview by the NRC on November 6, 1987. The licensee's
    information and proposed methods of resolution of the inspection findings have
    been reviewed and were considered in preparation and issuance of this report.
    The deficiencies identified by the NRC inspection team involve documentation
    files which could not establish that this equipment was qualified. These
,
    components were identified during onsite review of the EQ documentation files
    and a corresponding plant walkdown inspection. The licensee was urged to
    resolve these concerns and place the necessary justifications for continued
    operation (JCOs) in place as soon as possible in accordance with the NRC
    Generic Letter 86-15.
                                        _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
 
    _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                    ._  _                                              -_
  .
                                                                                      3
  .
                                                                                  DETAILS
                                            1.  Persons Contacted
                                                V. Bacanskas, Coordinator, Equipment Qualification Coordinator
                                                A. Soni, Supervisor, EQ
                                                T. F.- Punkett, Plant Manager
                                                J. E. Booker, Manager, RBS Oversight
                                              *R. R. Smith, Engineer, Nuclear Licensing
                                                M. E. Walton, Technical Assistant
                                              - T. C. Crouse, Manager, Quality Assurance (QA)
                                                D. L. Andrews, Director, Nuclear Training
                                                T. P. Anthony, Field Engineering
                                                I. M. Malik, Supervisor, Quality Systems
                                                J. E. Spivey, QA Engineer
                                                D. R. Shah, Senior EQ Engineer
                                                D. R. Derbonne, Assistant Plant Manager
                                                G. R. Kimmell. Director. Quality Service
                                              *W.  H. Odell, Manager, Administration
                                              *K. Suhrke, Manager, Project Management
                                                J. R. Hamilton, Director, Design Engineering
                                                C. L. Miller, Compliance Analyst
                                                P. D.. Graham, Assistant Plant Manager, Operations
                                                T. L. Weir, Director, RBS Materials
                                                R. J. King, Supervisor, Nuclear Licensing
                                                M. F. Sankovich, Manager, Engineering
                                                D. N. Lorfing, Senior Engineer, Nuclear Licensing
                                                R. B. Stafford, Director, Operations, QA
                                                A. D. Kowalczuk, Director, RBS Oversight
                                              *H. Roach, Electrical Maintenance Supervisor
                                              *C. B. Graham, Supervisor, EQ Maintenance
                                              *R. Horn, Nuclear Training Coordinator
                                              *S. V. Desai, Senior Instrumentation Engineer
                                                Other
t
l                                              A. Athelu, Senior EQ Engineer, Consultant
j                                              G. McGee, Manager, Engineering, General Electric Corporation (GE)
                                                A. K. Wadhwa, Supervisor, Engineer, Stone & Webster Engineering
l                                                  Corporation (SWEC)
i                                                L. Johnson, Site Representative, Consultant
i                                              N. Luria, Manager, Qualification Engineer, GE
l                                              A. Blum, Assistant Section Manager, SWEC
'                                                L. Illy, Lead EQ Engineer, SWEC
                                                A. S. Abella, Field Engineering, SWEC
                                                NRC
                                                W. H. Paulson, NRR Project Manager
l
i
i
 
  .
                                              4
  ..
        D. D. Chamberlain, Senior Resident Inspector, RIV
        *G.  L. Madsen, Region IV, Project Inspector, RIV
        * Denotes attendance at the exit interview only.
    2.  Purpose
        The purpose of this_ inspection was to review the licensee's implementation
        of the requirements of 10 CFR 50.49.
    3.  Background
        NUREG-0588 was issued in December 1979 to promote an orderly and
        systematic implementation of equipment qualification programs by industry
        and to provide guidance to the NRC for its use in ongoing licensing
        reviews.    The positions contained in NUREG-0588 provided guidance on
        (a) how to establish environmental service conditions, (b) how to select
        methods that are considered appropriate for qualifying equipment in areas
        of nuclear plants, and (c) other areas such as margin, aging, and
        documentation.
        A final rule on environmental qualification of electrical equipment
        important to safety for nuclear power plants became effective on
        February 22, 1983. This rule, Section 50.49, of 10 CFR Part 50, specified
        the requirements to be met for demonstrating the environmental
<
        qualification of electrical equipment important to safety located in a
        harsh environmer.t    In conformance with 10 CFR 50.49, electrical equipment
        for the RBS is qualified according to the criteria specified in Category I
        of NUREG-0588.
        To document the degree to which the environmental qualification program
        complies with the NRC environmental qualification requirements and
        criteria, the licensee provided equipment qualification information by
        letters dated March 1, October 19, and December 14, 1984; and February 15,
        March 12, 15, and 29; April 26 and 29; May 10, 13, and 15; June 10, 19,
        24, and 26; July 19 and 23; August 13, 22, and 26; September 12 and 30;
        October 10, 18, and 25, 1985; and July 23, 1986, to supplement the
        information in FSAR Section 3.11 and Appendix A and B.
        The GSU SER, NUREG-0989 (May 1984), stated that the NRC had reviewed the
        adequacy of the RBS environmental qualification program for electrical
        equipment important to safety as defined in 10 CFR 50.49. The scope of
        this report included an evaluation of (a) the completeness of the list of
        systems and equipment to be qualified, (b) the criteria they must meet,
        (c) the environments in which they must function, and (d) the
        qualification documentation for the equipment.
        On January 26-28, 1985, the NRC, with assistance from EG&G Idaho, Inc.,
        conducted an audit of GSU's qualification documentation and equipment
        installed at the plant. Equipment items were reviewed to determine if the
        documents in the qualification files supported the qualification status
 
                                                                                __ __
                                                                                        ,
  .
                                        5
  .
,
'
    determined by the licensee.    Several deficiencies were noted and discussed
    with GSU at the time of the audit. These deficiencies were also provided
    to'the applicant in June 1985 and transmitted to the applicant by letter
    dated July 17, 1985. The applicant responded by letters dated June 19 and        ,
    July 19, 1985, The NRC reviewed the responses and concluded that the
    deficiencies had been adequately resolved.
    By letter dated March 29, 1985, GSU in response to Generic Letter 84-24,
    certified it was in compliance to 10 CFR 50.49 in that all equipment was
    either fully qualified or a justification for interim operation (JIO) had
    been submitted pending full qualification, and 10 CFR 50.49(1) was
    applicable based on their plant schedule.
    By letter dated June 26, 1985, GSU submitted to NRC drywell and
    containment pressure and temperature results for limiting large break and
    for various small breaks. These curves showed the corresconding
    environmental design criteria used for the equipment qualification. SER
    NUREG-0989, Supplement No. 3, was issued in August 1985.
    For safety-related items not having complete qualification documentation,
    GSU provided commitments for corrective action and schedules for
    completion. For items identified that would not have full qualification
    before an cperating license was issued, analyses had been performed in
    accordance with 10 CFR 50.49(i) to ensure that the plant could be operated
    safely pending completion of environmental qualification. These analyses
    were submitted to the NRC. The NRC reviewed the JI0's and concluded that
    reasonable assurance has been provided that the River Bend plant could be
    operated safely pending completion of environmental qualification.
    RBS initial criticality occurred October 31, 1985.    SER NUREG-0989,
    Supplement No. 5, was issued in November 1985. By letters dated July 19;
    August 13, 14, 22, and 26; September 12 and 30; October 10, 18, and 25;
    and November 4, 1985, GSU provided information stating that environmental
    qualification has been completed on all equipment having outstanding
    JIO's.
    The aging program requirements for electrical equipment at River Bend are
    defined in Category I of NUREG-0588. All degrading influences are
    considered and included in the aging program. Justification for excluding
    pre-aging of equipment in type testing is to be established on the basis
    of equipment design and application, or on state-of-the-art aging
    techniques. A qualified life is to be established for each equipment
    item. A maintenance / surveillance program is required to be implemented to
    identify and prevent significant age-related degradation of electrical
    equipment. GSU committed to follow the recommendations in Regulatory
    Guide 1.33, Revision 2, which defines the scope and content of a
    maintenance / surveillance program for safety-related equipment. Provisions
    for preventing or detecting age-related degradation in safety grade
    equipment are specified and include (a) utilizing experience with similar
    equioment, (b) revising and updating the program as experience is gained
    with the equipment during the life of the plant, (c) reviewing and
 
                ..          .  .      _ _ -    _
                                                      .                                      -
  .
                                                    6
  .
          evaluating malfunctiening equipment and obtaining adequate replacement
          components, and (d) establishing surveillance tests and inspections based            .
          on reliability analyses, frequency and type of service, or age of the
          items, as appropriate. This maintenance / surveillance program is to be in
i
          effect at River Bend.
          The above identified documents were reviewed by the NRC inspection team
"
          members and used in preparation for this inspection. The inspection
          involved an onsite and subsequent NRC Region IV in-office inspection of
          records furnished by the licensee.
      4. Findings                                                                            6
          a.    EQ program Compliance With 10 CFR 50.49
              The NRC inspectors examined the licensee's program for establishing
                the qualification of electric equipment within the scope of 10 CFR
                50.49. The program was evaluated by examination of the licensee's
                qualification documentation files, review of procedures for
              controlling the licensee's EQ efforts, and verification of adequacy
                and accuracy of the licensee's program for maintaining the status of
              electrical equipment. Based on the inspection findings, which are
              discussed in more detail below, the inspection team determined that
i
                the licensee has implemented a program to meet the requirements of
                10 CFR 50.49 for the RBS although some deficiencies were identified
                (refer to Sections 4.f and 4.h).
          b.    EQ Program procedures
,
              The inspection team examined the implementation and adequacy of site
              policies and procedures for establishing and maintaining the
              qualification of electrical equipment in compliance with the
                requirements of 10 CFR 50.49. The licensee's methods for
              establishing and maintaining the qualification of electric equipment
j              were reviewed in the following documents:
I              Engineering Department procedures Manual
                procedure No.                  Title
                EDP-EE-01                      Processing of Equipment Qualification Related
                                              Documents, Revision 1
                EDP-EE-02                      Evaluation of Change Documents for Impact on
                                              Equipment Qualification, Revision 1
'
                EDP-EE-04                      Control and Maintenance of the River Bend
                                              Equipment Qualification Master Lists,
                                              Revision 1
;
    A
 
  _ _ _ _ _ _ _ _ _ - _ _ _ _ .__    ._,
  .
i-                                                            7
    ..
                              EDP-EE-05                Preparation and/or Revision of Equipment
                                                        Qualification Maintenance and Surveillance
                                                        Requirements (EQMSR), Revision 1
                              EOF-EE-07                Ccmpilation, Maintenance, and Updat!ng of the
                                                        Equipment Qualification Job Books, Revision 0
                              EDP-EE-09                Control and Maintenance of System Component
                                                        Evaluation Worksheet (SCEW), Revision 1
                              EDP-AA-30                Processing Condition Reports within
                                                        Engineering, Revision 1
                              EDP-AA-54                Engineering Department Guidelines and
                                                        Instructions for Processing Modification
                                                        Requests, Revision 8
                              EDP-AA-64                Control and Approval of Field Change
                                                        Notices (FCNs), Revision 6
                              EDP-AA-65                Review and Processing of Vendor Technical
                                                        Information, Revision 3
                              E0 Maintenance procedures
                              Procedure No.            Title
                              MSP-0003                  Preventive Maintenance Program, Revision 10
                              GMP-0093                  Equipment Qualification Special Requirements,
                                                        Revision 1
                              GMP-0015                  Lubrication Procedure, Revision 3
                              PMP-1205                  Motor Operated Valve Routine Maintenance,
                                                        Revision 4
                              Training procedures
                              Procedure No.            Titie
                              TPP-7-013                Mechanical Maintenance Training, Revision 1
                              MSP-0009                  Qualification of Maintenance Personnel,
                                                        Revision 8
                              EDP-AA-10                Training Requirements for Engineering
                                                        Department Personnel, Revision 6
                              TPP-7-025                Staff and Management Training Technical
                                                        Program
                                                                                                      1
 
  .
                                    8
  4
    TAP-5-007                  Training Records and Documentation,
                              Revision 2
    TPP-7-027                  Quality Assurance Personnel Training,
                              Revision 1
    GAP-1.3                    Quality Assurance Indoctrination and Training
                              Program Procedure, Revision 6
    Station Operating Procedures
    Procedure No.              Title
    E0P-0101                  Emergency Procedure - RPV Control, Revision 0
    Qualification Engineering Procedure
    Procedure No.              Title
    QUAL-85-001                On Site FDDR Oualification Review, Revision 4
    QUAL-85-002                River Bend FDDR Qualification Review Check
                              List, Revision 5
    Station Support Manual Procedures
    Procedure No.              Title
    ENG-3-006                  River Bend Station Design and Modification
                              Request Control Plan, Revision 3
    Operations Quality Procedures and Instructions
    Procedure No.              Title
    QAI-2.1                  Audit Performance, Reporting tnd Followup,
                              Revision 4
    QAI-2.6                    QA Review of Design Changes and Plant
                              Modifications, Revision 1
    The inspection team reviewed the above licensee's procedures for
    meeting the requirements of 10 CFR 50,49 including: (1) qualified
    life; (2) servict conditions; (3) periodic testing; and
2
    (4) maintenance and surveillance. The licensee's EQ program was also
    reviewed with regarc to establishment of an auditable documentation
    file, including such documents as EQ audit reports, maintenance and
    surveillance records, supporting documents which establish EQ
    training of personnel, and supporting documents which control plant
i  modifications, and installation of replacement equipment to the
    requirements of 10 CFR 50.49.
 
  . - _ - _ _ _ - _ _ _ _ _ _                  _ _ _ _ _                                                  . _ _ _ _ _ _ _ _ _ _ _    _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ _ _
            .
            .
                                                                                              9
                                                                                                                                                                                                            '
                                                          The licensee's EQ program procedures and policies are established and
                                                          are being adequately implemented to control and maintain the
                                                          environmental qualification of electrical equipment at RBS for
                                                          compliance with the requirements of 10 CFR 50.49.
                                                          The following programs were effectively in place at RBS:
                                                          (1) EQ Maintenance / Preventive Maintenance Program
                                                              (a) The RBS EQ maintenance program has been integrated into the
                                                                        licensee's overall maintenance program through the
                                                                        following procedures which were reviewed by the NRC                                                                                ,
                                                                        inspection team:                                                                                                                  ,
                                                                        MSP-0003 establishes and implements a preventive
                                                                        maintenance (PM) program, establishes equipment to be
                                                                        included in the program, monitors and adjusts maintenance
                                                                        activities, and establishes the EQ requirements for
                                                                        parts / component replacement and special maintenance                                                                              ,
                                                                        requirements. Primary features of the program, as related
                                                                        to EQ maintenance, include the Equipment Qualification
                                                                        Maintenance and Surveillance Requirements (EQMSR), issued
                                                                        by engineering to maintenance departments and PM task
                                                                        approvals (PMTA) which are initiated to comply with the
                                                                        EQMSRs. The program is managed by means of a computerized                                                                          '
                                                                        PM data base which tracks and schedules the PM activities.
                                                                        GMP-0093, defines EQ maintenance requirements that have not
                                                                        been defined with a specified frequency, but are required
                                                                        anytime a maintenance activity is performed.
                                                                        EDP-EE-05 establishes the guidelines for preparing and
                                                                        revising requirements identified in the equipment
                                                                        qualification documentation that are necessary to maintain
                                                                        the equipment in a qualified status.
                                                                        EDP-EE-07 provides guidelines and instructions for
                                                                        compiling, reviewing, maintaining, and updating EQ Job
                                                                        Books.
                                                                                                                                                                                                            >
                                                                        EDP-EE-01 establishes guidelines and instructions for the
                                                                        control, processing, review, and maintenance of EQ-related
                                                                        documentation.
                                                                        GMP-0015 provides general instructions for lubrication of
                                                                        plant components, including EQ items,
i                                                                        PMP-1205 provides instructions for the periodic maintenance
                                                                        of motor operated valves.
'
!
i
                                                                                                                                                                                                            i
                                                                                                                                                                                                            t
                              - ,_
                                  -,--..,-..,n                  -,..n_.    _ - - ..  -_,.n_-  -  _ , , . . , _                - - , . , _ . . . _ - - . - _ - _ - - - -                          - - -
 
.
                                  10
.
              No violations or deviations were identified by the NRC
              inspection team during the procedural review.
          (b)  In addition to procedural reviews, the NRC inspection team
              reviewed the EQ maintenance program implementation by
              selecting a sample of 11 components from the EQ master list
              and comparing the required PM from the applicable EOMSRs to
              that scheduled to be performed by the PM data base. All
              required maintenance for the sample appeared to be
              adequately scheduled for 10 of these items; however, vendor
              recommended maintenance shown on the EQMSR for the
              Gould-Brown Boveri switchgear (mark number 1 ENS *SWG3A),
              even though included on the maintenance data base, had not
              been scheduled for completion during this outage, as
              required. The following maintenance had not been scheduled
              to be performed:
              *    -Servicing circuit breakers,
              *
                    Exercising circuit breakers,
              *    Inspection of primary interface connectors.
              *    Inspection of primary cables,
              *
                    Exercising racking mechanism,
              *
                    Cleaning contamination from all primary insulation,
              *    Inspection of control wiring bundles, and
              *
                    Cleaning stationary breaker connection stubs.
              Prior to the completion of the NRC inspection, the licensee
              scheduled the maintenance to be completed during the
              outage. The PM requirement for the equipment had been
              addressed in Task Approval EC01113 which was added to the
              required PM tasks on July 27, 1987. Prior to the outage,
              PM tasks placed on the master outage schedule were placed
              on "Hold" on May 1, 1987. Since the PM for the subject
              item was added subsequent to the master schedule "Hold"
              date, it was inadvertently omitted from the schedule. The
              PM was due on July 27, 1987, and performed on November 11,
              1987, within the 25 percent grace period permitted by
              MSP-0003, after being identified during the NRC inspection.
              GSU electrical maintenance group performed a 100 percent
              review of all task approvals from the "Hold" date to the
              present and no other missed PM tasks were identified.
              No violations or deviations were identified by the NRC
              inspection team.
    (2) Control of Plant EQ Modifications
          RBS procedures were reviewed by the NRC inspection team to
          ensure proper maintencnce of documentation for EQ components
          during plant modifications as follows:
  .
 
!
  .
                              11
  .
    (a) Procedure EDP-EE-01 provides guidelines and instructions to
          maintain control, processing, review, updating, and
          maintenance of documentation for EQ components. An EQ
          reviewer reviews assigned documents (including vendor
          technical information, modification requests (MR),
          nonconformance reports (NR), condition reports (CR), EQ
          maintenance / surveillance requirements, NRC or INPO          i
          correspondence and IE notices / bulletins), and determines if
          the document is applicable to, or affects EQ. If there is
          an impact, the impact is tracked on an EQ documentation      ,
          log.
    (b) Procedure E0P-EE-02 specifically describes the requirements
          for evaluation of MRs, NRs, and CRs for impact on EQ
          components. A copy of the attached EQ Impact
          Summary (EQIS) sheet, and tb EQ Impact Review
          Checklist (EQ1RC), are then included in the MR/CR packages.
          Any EQ documentation requiring revision and/or initiation
          of action as well as EQ evaluations are identified on the
          EQIS.
    (c) Procedure EDP-AA-54 establishes guidelines and instructions
          for processing MRs by engineering personnel. Most MR
          packages include an EQIRC (EDP-AA-54, Attachment G) to
          ensure that qualification is maintained if modifications to
          the plant are required. A checklist is required for all
          emergency and Q Class 1 MRs.
    (d) Procedure ENG-3-006 provides overall instructions on
          controlling design and modification actions at RBS. This
          procedure is used in conjunction with EDP-AA-54 when
          processing MRs. The modification completion checklist
          (ENG-3-006, Attachment 5) includes instructions to ensure
          that EQ documentation has been updated prior to final
          closeout of an MR.
    (e) procedure EDP-AA-64 provides directions on the control and
          approval of field change notices (FCNs). The FCN provides
          a method of incorporating a change into an existing MR
          design, and the FCN becomes a part of the MR package. The
          FCN is reviewed to determine if any previous review or
          evaluation is affected by the change, with regards to
          qualification of components.
    (f) Procedure EDP-AA-30 provides instructions for processing
          CRs within the RBS engineering department. The Condition
          Report One Time Deviation Design Review (EDP-AA-30,
          Attachment B) ensures that a qualification review is
          performed.
 
        .-
  j(
                                      12
    .
            (g) Procedure QAl-2.6 defines and establishes QA
                  responsibilities for the review of design change activities
                  including MRs, FCNs, and NRs. QA checklists (QAI-2.6,
                  Attachment 2 and 3) are used in the review of MRs and FCNs
                  to ensure they are in accordance with applicable procedures
                  and requirements, including EQ engineering reviews.
            No violations or deviations were identified by the NRC
            inspection team during review of procedures.
            In addition to the procedure review and interviews with
            personnel, the NRC inspection team reviewed the implementation
            of the EQ modification program by selecting one MR (No. 86-1778)
            to ensure the licensee was following approved procedures.
            Controls for the EQ Modification Program appear to be adequately
            implemented based on the selection of this one MR.
            Further verification of the GSU EQ Modification Program, using a
            larger sample, will be accomplished during a subsequent NRC
            - inspection.
      (3) Procurement of Materials and Services Including Replacement
            Parts
            The RBS EQ Procurement Program is an integral part of the
            licensee's overall EQ Program and is controlled by the following
            procedures:
            Procedure No.              Title
            RBNP-003                    Material Management System
            NuPE-AA-42                  Evaluation and Justification of
                                        Commercial Grade Items
            EDP-AA-43                  Technical Quality Documents for
                                        Procurement
            The RBS EQ Replacement Parts Program is integrated with the EQ
,
            Maintenance Program (refer to paragraph 4.b(1)(a) above) which
            establishes the requirements for part/ component replacement.
            Also, the EQ Replacement Parts Program is governed by those
            procedures listed above.
            Further review of the controls and implementation of the EQ
            Replacement Parts Program at RBS will be accomplished during a
            subsequent NRC inspection,
i
i
 
      __ _                    _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ __                              _ _ _ _ _              _ ___  . _ _ _ _ _ _ _ _ _ _ _ _ _ _
                                                                                                                                                                    l
  .
                                                                                                                                                                    i
                                                                                                                                                                    I
                                                                                                                  13
    .
                                                                          c. Training Program
                                                                                                                                                                    !
                                                                            A review was conducted by the NRC inspection team to determine if a
^
                                                                            training program was in place to provide necessary training to
                                                                            personnel involved in implementing all phases of the EQ program at
                                                                            RBS as follows:
                                                                            (1) Technical Staff and Management - This program consists of a
                                                                                    series of formal training courses and mandatory reading lists
                                                                                  which are specified in Procedures TPP-7-025, EDP-AA-10, and
                                                                                  TAP-5-007. Procedure TAF-5-007 is applicable to all RBS
                                                                                  disciplines.
                                                                                  The program for training of technical staff and management
                                                                                  appears adequate; however, review of implementation of the
                                                                                  program could not be completed because of an inadequate sample
                                                                                  of training records available at the time of the onsite
                                                                                  inspection.
                                                                            (2) Quality Assurance - The Ouality Assurance and Quality Control
                                                                                  training programs consist of formal training, on-the-job
                                                                                  training, and mandatory reading lists which are specified in
                                                                                  Procedures QAP-1.3 and TPP-7-027. No specific EQ training or
                                                                                  mandatory reading could be identified in this program review.
                                                                                  Also, review of the program implementation could not be
                                                                                  completed because of an inadequate sample of training records
                                                                                  available at the time of the onsite inspection.
<                                                                            (3) Maintenance Program - The RBS maintenance program reportedly
                                                                                  meets INP0 accreditation standards in the areas of mechanical,
                                                                                  electrical, and instrumentation and control (I6C). The
                                                                                  objectives of this inspection were to review procedures which
                                                                                  establish the program and to review the program implementation
                                                                                  by reviewing a sample of employee training records.
                                                                                  Procedures MSP-0009 and TPP-7-013 were reviewed during the
,
                                                                                  inspection.
,                                                                            Items identified in paragraphs 4.c(1), 4.c(2), and 4.c(3) above are
l                                                                            considered an Unresolved Item pending review of electrical and I&C
j                                                                            procedures and training records which were not available during the
'
                                                                            NRC onsite inspection (458/8721-07).
.
                                                                          d. 0A Audits of EO Activities
)
l
                                                                            A review of RBS QA audits of EQ activities was performed, including
                                                                            interviews with key QA personnel.
,
                                                                            (1) Procedure QAI-2.1 defines the responsibilities and the methods
;                                                                                  to be used by the GSU QA organization for planning, performing,
,
                                                                                  reporting, and followup of QA audits of RBS site activities.
!                                                                                  Prior to an actual audit, a "Master Audit Schedule" and "Master
1
          _ _ - _ _ _ _ _ , _ _ _ _ _ . . _ _ _ . _
 
    __. _ _ - _ _ _ _ _ _
          .
                                                              14
      ..
                                    Audit Plan" are developed, followed by a "Notification of Audit"
                                    letter to the specific department to be audited. The audit is
                                    performed in accordance with a GSU audit plan. Audit finding
'
                                    reports are issued within 5 working days and the formal report
                                    is issued within 30 days.
                                    The NRC inspection team reviewed GSU Audit No. 87-01-I-EQAL
                                    regarding an audit of the GSU EQ program, performed during
  '
                                    January 1987. The audit was conducted to provide an overall
                                    assessment of the adequacy and effectiveness of the EQ program
                                    implementation. Emphasis was placed on the capability of the
                                    program to maintain designated equipment in a qualified status
                                    in accordance with the acceptance criteria of 10 CFR 50
                                    Appendix B, 10 CFR 50.49, and RBS procedures. A previous audit
                                    by DiBenedetto Associates (Audit Report No. GSU-01-08-01,
                                    Revision A, dated October 22,1986) focused on the adequacy of
                                    the original qualification data. The NRC inspection
                                    concentrated mainly on the maintenance of EQ qualification
                                    equipment.
                                    The NRC inspection team concluded that QA audits of EQ
                                    activities were effectively being implemented at GSU.
                                    No violations or deviations were identified.
                            e. 10 CFR 50.49 Equipment Qualification Master List (EQML)
]
                              The EQML and suoporting procedures were reviewed to determine if a
,                              program has been implemented to generate, maintain, and distribute
                              the EQML in accordance with 10 CFR 50.49 requirements .
'
                              Procedure EDP-EE-04 is used to provide control and maintenance of the
                              RBS EQML. All documents having impact on EQ activities at RBS are
                              processed through an EQ reviewer, who determines if the documents
                              warrant an EQML change.    If an update is required, changes to the
,
                              EQML are made using EQML revision control sheets.
                              The EQML was reviewed against emergency operating procedures (EOPs)
                              and procedure No. E0P-0101 to ensure postaccident monitoring (PAM)
,                              components listed as part of the RG 1.97 program were included on the
;                              E0ML.  Eight PAM parameters were selected and all components were
l                              found on the EQML.
I
                              No violations or deviations were identified.
!                          f. EQ Documentation Files
i
9
                              The licensee's environmental qualification file (EQF) at RBS has been
l'                            established and is being maintained to meet the requirements of
                              10 CFR 50.49. The requirements are contained primarily in
                              Procedures EDP-EE-07, EDP-AA-65, and QUAL-85-001,
t
                          +
 
                                15
.
  The NRC inspection team examined files for 45 selected equipment
  items (E0JBs) to verify the qualified status of equipment within the
  scope of 10 CFR 50,49.    In addition to comparing plant service
  conditions with qualification test conditions and verifying the bases
  for these conditions, the NRC inspectors selectively reviewed areas
  such as: (1) required post-accident operating time compared to the
  duration of time the equipment has been demonstrated to be qualified;
  (2) similarity of tested equipment to that installed in the plant;
  (3) evaluation of adequacy of test conditions; (4) aging calculations
  for qualified life; (5) replacement part schedules; (6) the effects
  of decreases of insulation resistance on equipment performance;
  (7) adequacy of demonstrated accuracy; (8) evaluation of test
  anomalies; and (9) applicability of EQ problems as reported in IE
  Information Notices (IN) and IE Bulletins (IEB) and their resolution.
  During this review of the EQF, the inspection team identified the
  concerns described below:
  (1) EOF Auditability and Organization of Documentation
        During the NRC inspection, a concern was raised with regards to
        the organization of documentation in that it was not readily
        understandable and traceable to permit independent verification
        of interfaces or conclusions. The auditability concerns
        pertained primarily to the EQJBs in the EQF having provided
        incomplete information in establishing qualification of
        equipment, as identified by the NRC inspection team as follows:
        (a) E0JBs 211.161 and 241.232: Hydrogen Ignitor Assemblies,
            Bisco Sealing Compound, Conax Electrical Conductor Seal
            Assembly, Raychem Heat Shrink Splices, Marathon Terminal
            Blocks, Okonite Tape Splices, Anaconda Power Cable, and
            Rockbestos Instrument Cable: File Auditability Problems
            Many RBS files were difficult to audit.    For example, in
            most files reviewed a similarity analysis and an evaluation
            of performance characteristics were not part of the file.
            Similarity questions arose frequently and required tracing
            down the trecification and purchase order,    Licensee
            personnel often gave conflicting verbal answers to
            questions, and significant time was required to obtain the
            correct answers in writing.
        (b) E0JBs BOP Limitorque Motor Opetator, File Auditability
            Problems
            It was not apparent in the file that cycle testing of motor
            operators required for RBS had been enveloped by the cycle
            tests contained in the file used to support qualification
            of the actuators installed. Discussions with licensee
            personnel revealed that the approach used to address this
 
  -__
                                                                                                          !
e
                                            16
            concern had been incorporated into the specified cycle
            testing of similar actuators in the GE phase III testing
            program. No specific references or auditable trail was                                        -
            contained in the EQF.
            When questioned whether or not the proper orientation of
            the motor actuators had been considered in regard to
            greases, which are found to migrate from the main gearbox
            to the motor or switch compartment, the licensee supplied
            the NRC inspection team with installation procedures. The
            procedures clearly showed that this concern had been
            addressed in the actuator installation and during
            subsequent inspections of the Limitorque actuators at RBS.
            However, no specific references or auditable trail to the
            SWEC installation procedures were contained in the EQF.
            It was not evident in the EQF that either Raychem Flamtrol
            or Rockbestos Firewall III was used as replacement wire for
            internal wiring of SMB Limitorque motor operators. The HRC
            inspection team identified only Reckbestos Firewall III in
            motor operators inspected during the NRC walkdown.
      (c) E0JB SRN 503, Limitorque SMB Motor Operators, High pressura
            Core Spray, Outside Containment, File Auditability Problems
            The basis of qualification of. these valve operators is                                      .
            NUREG-0588, Category I.                            Qualification was supported by            l
            Limitorque Report B0058, dated January 11, 1980, for SMB
            model actuators. Wyle Report 57675, dated April 30, 1986,
            extended the qualification to additional models by
            providing a similarity analysis for the other models.
            Qualification of the operators was adequately established;
            however, audit of the qualification documentation was
            difficult since changes to the tested configuration had not
            been adequately documented in the EQJB documentation
            packages. This became apparent during the walkdown
            inspection and is discussed in greater detail in
            paragraph 4.h of this report. Examples of auditability
            problems are:
            1)  Taped splices made onsite, and not a part of the
                  tested configuration, were not identified in the EQJB
                  oualification documentation of the EQF.
            2)    Terminal blocks, which were not in the tested                                          ,
                  configuration, had been installed and were not
                  identified in the E0JB qualification documentation of
                  the EQF.
!
!
                                                                                                          I
                    y . - -  , - - - . _ , , - - - , . - - - -              - , ,    - - - - - - -
                                                                                                ..
                                                                                                      - -
 
                  _ _ _ _ - _ _ _ _ _ _ _ .    _ _ _ _ - . _          ___        ._                ____                          _ _ _ _ _
  .
                                                                                          17
                                                                                                                                              ,
  *
                                                                                                                                              ,
                                                                                                                                              t
                                                                          GSU responded to the above NRC concerns by letter
                                                                                                                                              '
,
                                                                          No. RBG-27213 to the NRC Region IV on December 28,                "
                                                                          1987, as follows:                                                  L
                                                                          "The puroose of the EQJB is provided in Design        .
                                                                          Engineering Procedure EDP-EE-07, of which Section 6.2
                                                                                                                                              '
                                                                          states that the EQJBs contain copies of the controlled            ,
                                                                          documents that are compiled to provide the EQ auditors
                                                                          with readily accessible cross-reference information.
                                                                          The information contained within the EQJB job book is
                                                                          intended to demonstrate tFe environmental
                                                                          qualification of the equipment used at RBS.    During an
                                                                          audit of-the EQ program at RBS performed by an
                                                                          independent third party consulting firm, similar
                                                                          questions with respect to EQJB content were raised.                :
                                                                          Since the completion of the independent audit, RBS had
                                                                          initiated steps to resolve the questions previously
                                                                          identified; however, these actions were not completed
                                                                          prior to the NRC inspection. GSU recognizes that the
                                                                          concerns raised by the NRC inspection team, with
                                                                          respect to auditability, were similar to those
                                                                          identified during the independent audit. The concerns              >
                                                                          are being addressed on a generic basis with the files
                                                                          being reviewed against a checklist which requires EQ
                                                                          auditors to verify that the information discussed
                                                                          above is included in the EQJB documentation packages.              ,
                                                                          Specific action areas identified for RBS to upgrade
                                                                          the EQJBs include:    (1) identification of installed
i                                                                        equipment interfaces, (2) addition of documentation to
                                                                          the EQJBs for design changes, (3) analysis of
                                                                          functional performance requirements, and (4) reference            ;
                                                                          to associated calculations (i.e., instrument accuracy
                                                                                                                                              '
                                                                          calculations, MVA reduced voltage calculations, etc.).
                                                                          These actions are in progress and will be completed by
                                                                          GSU on June 30, 1988."                                            ;
.                                                                                                                                            ,
                                                              Items identified in paragraphs 4.f(1)(a) 4.f(1)(b), and                        i
                                                              4.f(1)(c) above are considered an Unresolved Item (458/8721-06).
                                                                                                                                              .
                                            (2) EQJBs 228.212, 228.214. 228.216. 228.241, 228.243 and SRN 503:
                                                              BOP and NSSS Supplied Limitorque SMB/SB Motor Operators (Inside
                                                              and Outside Containment)
                                                              (a) BOP Supplied Limitorque Motor Operators. Models SMB and SB                  f
                                                                    (SPEC. 228.212)                                                            t
!,                                                                                                                                            !
                                                                    This EQJB file contained documentation to support                        !
!                                                                  qualification of the BOP-supplied Limitorque motor                        ,
;                                                                  operators installed at RBS. Valve actuator                                '
'
                                                                    Nos. 1G33*MOVF001, 1821*MOVF016, and IE51*MOVF064
                                                                    documentation was reviewed by the NRC inspection team.
.
                                                                                                                                              i
                                                                                                                                              I
                                                                                                                                              i
                                                                                                                                              '
    . _ _ _ _ _ _
 
  .
                                18
                                                                        ,
          Actuator IG33*M0VF001 is located inside the drywell and is
          used to operate the containment isolation valve for the
          reactor water cleanup system. Actuator 1821*MOVF016 is
          also located inside the drywell and is used to operate the
          containment isolation valve for the drain system.
        ~ Actuator 1E51*MOVF064 is located in Zone AB-114-2 (main
          steam tunnel) and is used to position the reactor core
          isolation cooling (RCIC) turbine steam supply containment
          isolation valve.
          1)    The licensee was asked to supply data which would
                indicate that the motor operators used in dual voltage
                application were properly sized for reduced voltage
                application at RBS. The licensee supplied motor
                operator calculations which showed that reduced
                voltage considerations were factored into the
                selection of these valve actuator motor operators.
          2)    A full inspection was performed by the NRC inspection
                team on JB21*MOVF016 which included verifying that
                proper components and materials internal to the limit
                switch compartment were installed. In addition, an
                external inspection was performed, with only one minor
                deficiency identified in that the model depicted on
                the EQML was SMB, whereas SB was found on the actuator
                nameplate. It was determined that this was a
                transcription error and to correct this error, the
                licensee committed to initiate a master list revision
                control (HLRC) and system compo,ent evaluation
                                            ~
                worksheet (SCEW) revision form to indicate the correct
                model and to verify the accuracy of nameplate
                transcriptions for other valves.
        No violaticns or deviations were identified.
    (b) Okonite T95 and 35 Sp_1_ ice,hp_e Applicatiens on 80P-Supplied
        Motor Operators
        Not all of the types of splices used in Limitorque motor
        operators at RBS were identified in the EQJB (Limitorque)
          files; nor was any reference to the documentation used in
        establishing the qualification of these splices f0und in
          the files.
        During the walkdown, the NRC identified Okonite T95 and
!
        35 splice tape incorporated as the motor lead / field cable
          splice material. An evaluation of the EQJBs that establish
        qualification of the B0P-supplied motor operators revealed
        that the motor lead / field cable interface had not been
          identified (also refer to paragraph 4.h(1) of this report).
l
                                  ___ _ _ -
 
  i
  i
    .
                          19
    .
      The licensee supplied reference to the documentation file
      used to establish qualification of the Okonite T95 and
      35 splice tape as EQJB 211.161 (fer application of motor
      leads and control circuits for motcr operators). This file
      is part of SWEC specification for nonengineered field
      purchased items. There were two concerns with this file as
      follows:
      1)  During the NRC walkdown, a V-shaped splice
          configuration was observed to be installed as well as
          an in-line configuration. The observed V-shaped
            splice configuration was not qualified by
          documentation contained in EQJB 211.161.    By the end
          of the inspection, the licensee was able to
          demonstrate that the V-shaped configuration could be
          qualified, thus resolving this concern. However,
          documentation was not present in the EQJB during the
          NRC inspection, indicating that the licensee had not
          adequately assessed the similarity of tested and
            installed splices. NUREG-0588, Category I, Section 5,
          paragraph 1 states that the basis of qualification
            shall be explained to show the relationship of all
            facets of proof needed to support adequacy of the
          complete equipment. The EQJB for Okonite tape did not
          contain sufficient information to establish that the
          tested and installed specimens were identical or
            similar.
      2)  The NRC inspection team identified another concern
          regarding insulation resistance data taken during the
          type test for the in-line splice configuration w' ich
'
          were not included in the EQJB. Since these splices
          are used in harsh environments (including steam) in
          coatrol circuits, the insulation resistance data was
          requested. The licensee obtained this data from
          Okonite on November 6, 1987, during the NRC inspection
          ar.d presented it to the NRC. The data indicated
          several insulation resistance measurements which were
            so low that they were off the instrument scale. The
          vendor test laboratory attributed the low values to
            improper sealing (equipment apparatus) where cables
          entered the test chamber. Because of the timing in which
          measurements were taken of the low insulation
          resistance values (af ter the most severe temperature
          and moisture conditions), the NRC inspection team
          agreed with this explanation of the test anomalies.
          While this observation was resolved concerning
            insulation resistance data, it indicated that the
            licensee did not have this data prior to the
            inspection and obviously had not reviewed it for its
 
    _ _ _ _ _ _ _ _ _ ._            _              ___  - _ _
  .
                                                  20
  .
                                    impact on the specified functional performance
                                    requiremcnts of control circuits at RBS.
                              3)    The NRC inspection team identified another concern
                                    regarding unidentified tape splices to motor operator
                                    replacements from Class B to RH insulation. Refer to
                                    paragraph 4.h(1) of this report.
                                    Along with the analysis that provided established
                                    similarity of the V-type tape configuration (as found
                                    in ICCP*M0V144) to the in-line shaped tape
                                    configuration, the in-line type tape splices were also
                                    the configuration found in the remaining four motor
                                    operators inspected by the NRC inspection team.
                              The above concerns in paragraphs 4.f(2)(b)1), 4.f(2)(b)2)
                              above, and 4.h(1) are considered an apparent violation of
                              10 CFR 50.49 (458/8721-01).
                        (c) Qualification of Terminal Blocks (tbs) used in NSSS and B0P
                              Supplied Limitorque Motor Operators
                              1)    B0P Limitorque Motor Operators
                                    At the time of the NRC inspection, the licensee had
                                    yet to identify all of the tbs incorporated in the
                                    power and control circuits internal to the switch
                                    compartment of these Limitorque actuators installed at
                                    RBS.  The types of tbs that may have been used were
                                    not identified in the docementation for all the above
                                    80P-supplied actuators; nor was the methodology
                                    incorporated in the EQJBs to establish qualification
                                    of the tbs found in motor operators at RBS. The only
                                    interface described was found in the documentation of
                                    the GE Phase III testing where Marathon 300 tbs were
                                    incorporated in the tested Limitorque actuators.
                              2)    EQJB SRN S03, Limitorque Motor Operator, Outside
                                    Containment, Unidentified Terminal Blocks
                                    During the walkdown inspection, Buchanan tbs (no
                                    visible model number) were identified in Limitorque
                                    motor operators for valve actuators 1E22*MOVF001,
                                    1E22*MOVF004, 10FR*MOV146, and no TB identification
                                    could be found on ISWP*MOV5703. The tbs were
                                    apparently not oriented in the type test
                                    configuration, or the operator and had not been
                                    addressed in the documentation file for the operators.
                                    Therefore, the qualification status for these motor
                                    operators was indeterminate.    The licensee had no
                                    documentation at the time of the NRC inspection to
[
 
  .
                                    21
  .
                      identify tbs which had been installed in these
                      operators.
                      The licensee performed a walkdown~ inspection, at the
                      time of the NRC inspection, of all safety-related
                      Limitorque operators on November 23, 1987, at which
                      time tbs were identified and summarized. The summary
                      presented to the NRC did not include Buchanan tbs
                      blocks which had previously been identified during the
                      NRC inspection; therefore, the licensee's inspection
                      results appear to be inconclusive. It was also stated
                      by the licensee, concerning TB qualification, that
                      Corporate Consulting Limited Report A-686-85 (SDDF
                      No. 6211.161.997-138A and -139A) demonstrates
                      qualification of tbs used at RBS.
              The above concerns in paragraphs 4.f(2)(c)1) and
              4.f(2)(c)2) regarding the identification and qualification
              of tbs incorporated in the Limitorque motor operators at
              RBS is considered an apparent violation of 10 CFR 50.49
              (458/8721-04).
    (3) EQJB 213.161, Marathon Terminal Blocks
        The NRC inspection team reviewed this file on Marathon NUC 1500,
        1600, and 142ST tbs. These blocks are part of the SWEC
        specification for nonengineered field purchased items. At RBS,
        these tbs are not used inside contai.nment, but can be found in
        harsh environments (including steam). The file contained
        confusing statements as to whether or not these tbs are in
'
        completely sealed junction boxes. Some junction boxes are
        completely sealed and some have 1/4-inch weep holes drilled in
        the bottom. A referenced talculation in the file successfully
        demonstrated th? abiliP,y of the completely sealed junction boxes
        to withstand postulated accident pressure differentials.      The
I        licensee showed the NRC inspection team installation drawings
        and specifications indicating that top entry conduits were
        sealed.    The identification of the sealant could not be
        confirmed during the inspection: however, after the inspection,
        the utility identified the sealant as Promatec Low Density
        Elastomer (PLDE). This sealant had been qualified as part of
        the mechanical equipment qualification program at RBS. Its use
        to protect electrical components was not addressed in the EQJB.
        This raised a concern on the part of the NRC inspection team
        that the installed sealant may not be qualified for LOCA/HELB
        environments and may allow moisture to reach the Marathon 1600
        tbs housed in junction boxes. Since these tbs are used in
        instrumentation and control circuits at RBS, the effects of
        moisture may be leakage currents in these circuits large enough
        to give misleading indications to the plant operator.      There
                                        _-  _  - _ .
                                                                    __
                                                              ._
 
______. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _          . _ .    _ _ _    _  __        _ _ _ _ _              _ _ _ _ _ _ _ _      ___ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _
        .
                                                                                22
        .
                                                  were no functional performance calculations in ene EQJB since
                                                  RBS assumed the blocks would not be used in a steam environment.
                                                  Since qualification of the Marathon 1600 tbs is dependent on the
                                                  integrity of the seal, the licensee must oemonstrate that PLDE
                                                  is an acceptable sealant for the junction boxes housing tbs. A
                                                  functional performance evaluation of Marathon 1600s will be
                                                  necessary if the terminal blocks are determined to be
                                                  susceptible to a steam / condensate environment.
                                                  This item is considered an Unresolved Item (458/8721-08).
                                          (4) EQJB 211.161, Bisco Scaling Compound
                                                  The NRC inspection team reviewed the file on the Bisco LOCA-Seal
                                                  sealing compound. This compound is part of a SWEC specification
                                                  for nonengineered items, field purchased. The file contained
                                                  Wyle Test Report 17607, Revision A. A qualified life of greater
                                                  than 40 years at 150 F was established. The type test
                                                  environment enveloped the reautred RBS environment. The
                                                  compound was tested in a fitting which was subjected to
                                                  187 Mrads of gamma radiation. The only concern raised with this
                                                  file is that the licensee was not sure exactly where this
                                                  sealing compound is used. The file contained a note that the
                                                  sealant was typically used in fittings (*.d sometimes in junction
                                                  boxes. RBS was able to identify, by the end of the NRC onsite
                                                  inspection, that the sealant observed between cables and conduit
                                                  on the NRC walkdown was not Bisco LOCA-Seal. This file was
                                                  initially reviewed for qualification assuming that the sealant
                      *
                                                  was housed in a fitting.        The NRC inspection team concluded that
                                                  if the sealant is actually installed unrestrained, the
                                                  qualification file would need further data to establish
                                                  qualification of all the additional configurations for which the
                                                  Bisco LOCA-Seal is used.
                                                  GSU responded to the NRC concern by letter No. RBG-27213 to the
                                                  NRC Region IV on December 28, 1987. The Sisco LOCA-Seal used at
                                                  RBS was procured under Specification 211.161, Nonengineered
                                                  Items. Data Sheet No. 1144, Section D, includes a product
                                                  technical description which states that the conduit entrance
                                                  sealing compound is to be used for ASCO solenoid valves
                                                  (Class IE located in a harsh environment) to seal out moisture.
                                                  Also a Babcock and Wilcox basic ceramic fiber is to be used as a
                                                  damming material. The installation drawings which identify the
                                                  devices sealed with BISCO LOCA-Seal are also included in the
                                                  BISCO LOCA-Seal EQJ3. Review of these drawings identified the
                                                  use of the BISCO LOCA-Seal on ASCO solenoid valves and
                                                  thermocouples only. The additional information supplied by GSU
                                                  resolved the NRC inspectors concerns for solenoid valves and
                                                  thermocouples only. Data to establish qualification of
                                              .-.        _ -      ,-      .--              - _ _ - , . -                - . .-                                                    -
 
.
                                23
      other component applications using Bisco LOCA-Seal will be
      reviewed during a subsequent NRC inspection.
      This item is considered an Unresolved Item (458/8721-09).
  (5) EQJB 211.161, Conax Electrical Conductor Seal Assembly
      The NRC inspection team reviewed the file on the Conax
      electrical conductor seal assembly (ECSA). The ECSAs are part
      of SWEC specification for nonengineered items which are field
      purchased. Conax Reports IPS-409 and -411 in the file were used
      to document qualification. The NRC inspection team had
      difficulty with the similarity analysis but was directed to the
      necessary information which verified that the tested and
      installed ECSAs are identical. There was a concern that the
      test profile (14 days) did not envelope the 100-day postaccident
      operating time, and an arrhenius calculation was performed and
      submitted to the NRC inspection team. This calculation was not
      present in the file prior to the inspection, indicating the
      licensee had not adequately addressed the test data for RBS
      application. The calculation indicated the test profile
      enveloped the required profile, only by using an activation
      energy of 3.916 eV for Kapton and polysulfone materials used in
      the construction of the ECSA. When questioned about the use of
      such a high activation energy as 3.916 eV in the calculation,
      the licensee referred to a letter from Conax to SWEC which
      referenced Conax Report IPS-325 from which the data using this
      high activation energy was apparently derived. Data which
      indicates the use of an activation energy of 3.916 eV for an
      ECSA containing materials which have been known to have lower
      activation energies, as documented in prominent test laboratory
      data banks (1.299 eV and 0.84 eV), will require the licensee to
      further review the bases for qualification.
      NUREG-0588, Category I, Section 5, paragraph 1, states that the
      qualification documentation shall verify that c.ach type of
      electrical equipment is qualified for its application and meets
      its seccified performance requirements. The RBS Conax ECSA test
      data had not been evaluated to verify that the ECSA met the
      necessary performance requirements beyond the November 30, 1985,
      deadline.
      This item is considered an apparent violation of 10 CFR 50.49
      (458/8721-03).
  (6) EQJB 241.242, Rockbestos Instrument Cable 300 Volt Firewall III
      (FWIII)
      The inspection team reviewed this file for Rockbestos
      instrumentation cable at RBS. The file contained several of the
                                                                        f
 
.
                            24
.
  latest Rockbestos reports including QR5804, QR5805, and QR6802.
  There were two concerns with this file.
  (a) RBS did not appear to know which formulations of Rockbestos
        they had installed in their plant. The licensee stated
        initially that they had chemically cross-linked as well as
        irradiation cross-linked cables, and they were in the
        process of confirming this. Thus similarity could not be
        conclusively established. After the inspection, the
        licensee was able to provide the NRC inspector with
        information indicating they had Rockbestos KXL760G
        (irradiation XLPE). However, this information was not
        present in the file and required a letter from Rockbestos
        (November 13,1987) to clarify the question.
  (b) A concern arose when the NRC inspection team could not find
        an analysis, regarding functional performance requirements
        for instrumentation circuits involving cable connections to
        components addressed in the file.    The licensee then
        provided a worst case calculation for irradiation
        cross-linked Rockbestos FWIII and Brand Rex Special
        Instrument cable for a typical pressure transmitter and RTD
        circuit at RBS. There were two problems with this
        submittal. First, it didn't account for any chemically
        cross-linked FWIII which may be in instrumentation circuits
        and has lower insulation resistances than the irradiation
        cross-linked FWIII. This concern was resolved when the
        licensee was able to show they.hao no chemically
        cross-linked polyethleyne cables at RBS. Second, the
        calculations were dated October 22, 1987, indicating they
        had been performed the week prior to the NRC inspection.
        The NRC inspection team asked to see any calculations which
        the licensee had in place before this date.    The utility
        responded that no such calculations existed, but
        engineering judgement had been exercised 'n assessing
        applicability of the Rockoestos and Brand Rex cable for
        instrumentation circuits.
        NUREG-0588, Category I, Section 5, paragraph 1, states that
        the qualification documentation shall verify that each type
        of electrical equipment is qualified for its application
        and meets its specified performance requirements. The RBS
        instrumentation cable circuits had not been evaluated to
        verify that they meet the necessary performance
        requirements until after October 22, 1987, beyond the
        November 30, 1985, deadline. Also thu Rockbestos
        Firewall III EQJB files did not contain sufficient
        information to establish that the tested and installed
        specimens were identical or similar.
 
                                                                          . _ _ ______ _ -___ ____ __ _
  *
(
                                        25
  .
            The concerns of paragraph 4.i(6)(a) and 4.f(6)(b) above are
            considered an apparent violation of 10 CFR 50.49 (458/8721-02).
      (7) EQJB 242.491, GE Terminal Boards, Model EB-25
            The GE tbs, Component ID IRO*TCA08, documented in this file are
            located in the auxiliary building in environmental
            zone AB-114-5.    The tbs are in the Reactor Core Protection
            system. The test report referenced to demonstrate qualification
            is Southwest Research Institute Report No SWRI-6772-317.
            (a) During the review of the file, it was noted that GE TB
                  qualification for humidity was not established.        The SCEW
                  sheet indicated that tbs were qualified to 98 percent
                  relative humidity.      In reviewing this test report no
                  testing for relative humidity was established.
                  GSU personnel stated that qualification documentation was
                  available to establish qualification of the EB-25 tbs to
                  the specified values per NUREG-0588, Category I and they
                  would be included in the EQJB.
            (b) During the equipment walkdown, it was determined that
                  Marathon tbs are also installed in the terminal cabinet
                  referenced in this EQJB. When GSU was questioned
                  concerning qualification of the Marathon tbs, they stated
                  the tbs were qualified using Wyle Test Report
                  No. NEQ-45603-1 and traceability to their qualification
                  will be included in the EQJB by E&DCR No. C-23.135.
            Pending update of EQJB 242.491, as described in
            paragraphs 4.f(7)(a) and 4.f(7)(b) above, this is considered an
            Open Item (458/8721-11).
    g. Review of IE Information Notices (IN) and Bulletins (IEB)
      The NRC inspector reviewed Nuclear Licensing Procedure NLP-10-006,
      Revision 1, dated October 30, 1986, titled, "Processing and Tracking
      of Regulatory and Industry Correspondence." The purpose of this
      procedure is to provide a systematic method of processing and
      tracking licensing correspondence from the Nuclear Regulatory
      Commission such as IEBs, ins, inspection reports, generic letters,
      and requests for additional information.
      In order to assess the effectiveness of RBS program, the inspector
      selected ins relating to EQ issues and reviewed responses and actions
      for each IN. The inspector determined that appropriate actions were
      taken by RBS for each IN and that the implementation of their program
      as stated in the above procedure was followed.
      No violations or deviations were identified.
 
    _ . _ .    __ ._                                      ._.      __.  _ ._.  _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ -_
  .
                                                    26
  '
                                                                                                                    I
                                                                                                                    l
            h.      Plant Physical Inspection
                    The NRC inspection team, with the rcquired tagging out of operation                            i
                    selected equipment and components by the licensee, walked down and
                    physically inspected 38 EQ components / equipment at RBS. The
                    inspection team examined attributes and characteristics such as
                    mounting configurations, orientation, interfaces, ambient
                    environment, and physical condition; the team also verified
                    traceability of equipment identified in the EQJBs in the EQF by model
                    and serial numbers.
                    During the NRC walkdown inspection, the NRC inspection team
                    identified the concerns described below:
                    (1) EQJB SRN S03, Limitorque Motor Operators, Outside Containment,
                          Unidentified Taped Splice
                          During the NRC walkdown inspection, Limitorque valve operator
                          IE22*MOVF001 was found to have taped in-line butt splices in the
                          motor leads. Since there was no record of the splices in the EQ
                          documentation defining a change to the tested configuration, the
                          splice type and qualification status were indeterminate.
                          The NRC inspectors were provided Procedure CMP-1277, dated
                          December 17, 1984, entitled "Low, Medium, and High Voltage Power
i                        Cable Splicing, and Termination." It was the NRC inspection
                          teams' understanding that splices were to be installed to the
                          requirements of this procedure after the initial startup of RBS.
(                        Okonite Report NGRN-3, dated June 23, 1980, was used as a basis
l                        of qualification for splices included in CMP-1277. The test
l                        report was documented under SDDF 6221.161-997-009. Neither of
'
                          these documents was in the EQF during the time of the NRC
                          inspection.
                          It was found that CMP-1277 had not been released for use by QA
l                        because of procedural inadequacies; alternately, splices were
!                        made in accordance with Specification 248, Revision 9,
                          Appendix J.    The qualification status of the identified splices
                          remained indeterminate since it was not known if the splices
                          were identical or similar to CMP-1277 splices.
l
                          Prior to the end of the NRC inspection, the licensee performed
!                        an analysis which showed similarity between the tested splices
                          and those identified during the NRC inspection, for V-shaped
l                        splices which were identified by the NRC inspection team in
l                        operator ICCP*MOV144 (refer to paragraph 4.f(2)(b) of this
                          report). The analysis was added to the Okonite tape splice
l                        EQJB 211.161. A note was also added to the Limitorque operator
l                        SCEW sheets, referencing the appropriate EQJB for electrical
                          interfaces. A 100 percent walkdown was also performed by the
                          licensee to verify splice acceptability.
l
1
i
 
  .
                                    27
  .
          Also, Modification Report (MR) 86-0395 was included in a
          supplemental EQJB to the Limitorque operator EQJB SRN S03 in the
          EQF. This supplement had not been provided for review by the
<
          NRC inspection team. The MR, initiated on March 7, 1987, was
          not approved at the time of the NRC inspection.    Its purpose was
          to replace operator motors that had Class B insulation with
          equivalent motors that have RH insulation in order to extend the
          operator life. The replacement motor leads were spliced with
          the Okonite splices qualified by Okonite Report NGRM-3. The MR
          required splices to be made in accordance with
          Specification 248, Revision 9, Appendix J.
          .The concerns described above are considered part of the apparent
          violation of 10 CFR 50.49 identified in paragraph 4.f(2) of this
          report.  (482/8721-01)
    (2) SNR 224150 and 228212, Limitorque Motor Operators, Outside
          Containment, Blind Barrel Crimped Connector Splices for Dual
          Voltage Application
          During the walkdown inspection, Limitorque valve operators
          IDFR*MOV146 and ISWP*MOV510 were found to have blind barrel
          crimped connector splices in the motor leads. The operators
          were equipped with 230/460 volt Reliance motors with Class B
          insulation. These splices are factory installed during assembly
          of the Limitorque motor operator valve actuator and provide a
          dual voltage motor application which are procured for 460 Vac
          service. This is the manufacturers. generic configuration for
          all operators equipped with dual voltage motors supplied by
          Limitorque. Qualification test reports contained in the EQJBs
          for the operators did not inc1Me documentation to support
          qualification of these splices.
          GSU responded to the above NRC concerns by letter No. RBG-27213
          to the NRC Region IV un Decuoer 28, 1987. Limitorque has
          subjected the dual voltage motor design to environmental
          qualification testing on four separate occasions.      Limitorque
          has tested dual voltage motors with Reliance Class H, Type RH
          insulation (Test Report No. 600376A), and with Reliance Class B
          insulation (Test Report No. B0003). Limotorque has also tested
          dual voltage moters with Reliance Class B insulation (Test
          Report No. F-C3271); and with Class H, Type Rad H insulation
          (Test Report No. 600198). A quality assurance audit of
          Limotorque's facilities in Lynchburg, Virginia, which was
          conducted by another licensee, included within its scope a
          review of purchase order records for these crimp connector type
          splices used by Limitorque. The purchase records at Limitorque
          indicated a purchase of 112,000 Thomas & Betts RC-6 splices
          between April 1967 and May 1979; 240,000 Thomas & Betts RB-4
          splices between January 1971 and June 1973; and 30,000 Thomas &
          Betts RB-44 splices between June 1984 and June 1987. GSU
 
  .
  '
                                            28
                  believes the tests cited above included these crimp connector
                  splices manufactured by Thomas-& Betts, even though
                  documentation to verify this conclusion is not available.
    .
                  A qualification test for Thomas & Betts RB-4 and RB-6 nylon
                  crimp connector splices used in dual voltage Limitorque
                  operators was being performed by Wyle Laboratories. An 8 year
                  screen qualification test was completed successfully in late
                  October 1987 with a completed test summary. A 40 year
                  qualification test is being conducted and completion and
                  issuance of a final test report is scheduled for early 1988.
                  The results of the test program will be required to be
                  incorporated in the EQJBs to document the qualification when the
                  final test report is issued. At this time the type test results
                  are preliminary and supporting analysis to show similarity to
                  the equipment tested and environment installed at RBS has not
                  been established.
                  NUREG-0588, Revision 1, Category 1, paragraph 5, requires that
                  cualification documentation shall verify that each type of
                  electrical equipment is qualified for its application and meets
                  its specified performance requirements. The basis of
                  qualification is required to be explained to show the
                  relationship of all facets of proof needed to support adequacy
                  of the complete equipment. Data used to demonstrate the
a
                  qualification of the equipment shall be pertinent to the
                  application and organized in an auditable form. The
                  documentation is required to include sufficient information to
                  address those items identified in NUREG-0588, Appendix E, which
                  includes splices (item 16).
I
                  The NRC item described above is co151dered an Unresolved Item
                  (458/8721-05).
    5. Unresolved Items
      Unresolved items are matters about which more information is required in
      order to ascertain whether they are acceptable items, items of
      noncompliance, or deviations. Unresolved items identified during the
      inspection are discussed in paragraphs 4.b(1)(b), 4.c, 4.f(1)(a),
      4.f(1)(b), 4.f(1)(c), 4.f(3), 4.f(4) and 4.h(2).
    6. Exit Interview
      An exit interview was conducteo on December 12, 1987, at the conclusion of
      the onsite inspection, with GSU in which the scope of the inspection and
      findings were summarized.
 
                                                                                    U.S. NUCLE AR REGULATORY COMMISSION                                      sv sC + At *Nsac cm N 4 v w <m ov ~n % ,
    Mc sCav 766
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      20                        25  26                  31
                                                                                                                              T1PE 05 ACTtvif v CONDUCTED echece one tms orevi
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                    wo0VLE NUW8Ea s%5P                Qg e                            MODULE #EQ 50tLOwvP                  eh
                                                                                                                                                                                8
                                                                      ao                                                                            r                                                                                r
            -
                                  .                                                                        r                                                                              ie
                                                        qn':@$g                                                                                                            h$5435 E. r.
            -
            -          :          i:
                                  _.
                                                      c              i~            e.  _
                                                                                              2    !.    !:.      .        :.    .  i> s,      2.5          .
                                                                                                                                                                    . :
                                                                                                                                                                r e 6r o,pr    - , 0, vgg
                                                                                                                                                                                            -              s- .,        !,!.        !.          .
                                              . .                                                                                  .
                                                                                                                                                    Lt
                  .                                                  _,,                ,                                                                                                                        .
        r    s    :    ,:
                        ,          8,          2 , 5    mas,cd,      r>o          :    : :a v: 81                s E t,          ;        ;                                                            s    ;      <;          8g
:      :          : sa            : ;        en e    s-            ese          a    -                  : .    : -              -  > e          4        :  -
                                                                                                                                                                            a a:.< re                -      -    -      >v          r,        =
        .  9      53id%1$                        ^
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                                                                                                                                                                                i i            i i                        i    Iiil
                                                                                                        liil                                                      *                                                            li,1
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                                                                                                                                                                                                                          i
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            w %,                                          i i
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                                                                                                                                                                                , i            , ,                        ,    ii,I
        dd24%71d                          /      ^
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                                                                                                '      I''I                                                      '
                                                                                                                                                                                ' '            ' '                        '    l''l
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                                  g (g n,,j p                                                  1              1
            Eo A Iuse                                      i ,          , ,                    ,      1,,1                                                      o
                                                                                                                                                                    '
                                                                                                                                                                                , ,            , ,                        ,    I,,l
        6    l          t          1 i    I
                                                  '
                                                            I i          i i                    i          i I            9  i          !    II      I
                                                                                                                                                              I
                                                                                                                                                                                i l            i i                        I    Iil l
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                                                  '
                                                            i 1          , i                    1      II    I  i                                                            l 1            i l                        i !l i l
                                                            1 i          i ,                      i        t i                                                                i 1            I i                        1 l1          1  l
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            ' ' 9'. ' l'.V f,',1                    -
                                                        ],,                , ,                    ,      l,,l                                                      L
                                                                                                                                                                                g ,            , ,                        , l,y l
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                                                                                                                                                                                                      ..      9  3      ,,                      2E
 
                                                                                                                                                          I
                                                                                                              EipO41          WODULE Nuwet p
    NRCforma798A                                                  DCCatt NO is osasi om uCE NS!
    ("[g                                                              NO t87 6 ROOuCT H13 6 9'toi            NO      SEQ    (lkjhlhj7l[gl
                  lNSPECTOR'S REPORT                        O6OOO4Se                                  A'7 29            -    ----.~.i .g
                                                                                                                        e    ,                    p-
                                                                                                                                                g
                                                                                                                                  ,          ,
                        (Continuation)                                                                                  c
                                                                                                                                    3  ,  ,
                                                                                                                                                    eo-
          Office of Inspection and Enforcement                                                                                        K-          .
          vetuon om ot u ren w.< eo no suc envuove w eun e n ose " r uce*** une ww "-* o* uns u, ro o* non<a** i,~r n, es ro w ena.ur.,, un >
    $1
      '
                  Contrary to paragraphs (f) and (k) of 10 CFR 50.49, and Section 5(1) of
      a          NUREG-0588, Category I, E0JB 241.242 intheJQFforRockbestos              ar :x'e, did not adequately
      *
                  Firewall III 300-volt instrument cable a:.
                  support qualification (1) in that similari[y between the tested
        5        irradiation cross-linked insulation cable and the cable installed at RBS
                  was not established (originally chemically cross-linked insulation cables
        ,
                  were ordered at RBS and no information was available in the EQF to clarify
        7          what was installed); and (2) in that no functional performance
        ,
                  requirements on instrumentation circuits W 7e'rYormed and documented in                                                              i
                  the EQF in consideration of cable insulation resistances. The EOF did not
        '        verify that these cable types had been evaluated to meet the necessary
      ,,
                  functicnal performance requicements specified [ Appendix B,
                  paragraphs 4.f(6)(a) and 4.f(6)(b)].
        11-
      11
      13
        14
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        is
        17
                                                                                                                                                --
        is
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    -                                                                                                              U.S. NUCLE AR REGULATORY COMMISSK
  ,            -
                                              -                                                      -- - --              --.
 
                                                                                                                                                                                      _
                                                                                                                    n ,,o,,        . 3 % , ,, ,,
                                                                                              , ng , ,,,,
  ",ac,soeu ns A                                                        m,=o, ,,iso,,aoovc
                                                                                      ,,,,t i n s . .. .          ,,        ,
  , ,j,                                                                                                                              - r . . .n
                                                                O600045&
                                                                                                                                                s . ., . v . . . . . ,.. , , , , ,
,
                                                                                                              a>7 gij          .
                                                                                                                                                                                  ':-
                INSPECTOR'S REPORT                                                                                            e  ,    ,    ,  ,  ,    ,
                      (Continuation)
        Of fice of Inspection and Enforcement
                                                                                                                                c
                                                                                                                                D                    z'
                                                                                                                                                                g            ,o-
                                                                                                                                                                              a
                                                                                                                                                                                    ~
                                                                        .. . .< ,, , ,, a . , . . .< . ,,,,, ,. ,,,,,,,,,, ,,, ,,, ,, , ,,,,,,,,, ,,,, ,
      v ota t e oa oe v ia r e= re,., ,, un ca. .e,. , =, ea n.. n ,a.
                                                                                                .
  1
    2
    3
                  Contrary to paragraphs (f) and (k) of 10 CFR 50.49, and Section 5(1) of
                  NUREG-0588. Category 1, E0JB 211.161 in the EOF for Conax electrical
    ,
                  conductor seal assembly (ECSA), did not adequately support qualification
      5
                  in that similarity between the tested ECSA and those installed was not
                  established at RBS. The test profile, contained in the                                        EQF, did not
                                                                                                          The EOF did not verify
      ,
                  envelope the 100-day postaccident operating time.
      >          that the installed ECSAs had been evaluated to meet the necessary
      ,
                  functional performance requirements specified [ Appendix B,
                  paragraph 4.f(5)].
      e
    to
      11.
    12.
    13
      14
      1%
        4
      17
      18
      19
                                                              -
      21
      22
      23
      te
      n
        D
l
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        2e
!      En
        %
l
        31
        .
        33
          M
l
          *
          h
            2
                                                                                                                            U.S. NUCLE AR REGULATORY COMMIS5K
 
~
                                                                                                    REPORT              WODULENuwBf9
  IvRC 80aM 796 A                                          DCC111 NO t8 at's> OR UCE NSE
  ill      -                                                NO (87 PRODUCis tt3 0ttse              NO              $M  h[h          h
                                                      O 6 O O O 45 e                          a*7                      *  ~ ' ~ . ~      ' ~ ~ *                $
                INSPECTOR'S REPORT
                    (Continuation)
                                                                                                      pli
                                                                                                                      e ,  , 3    . . .                      y.'tc
                                                                                                                                                                  ao-
        Office of Inspection and Enforcement
                                                                                                                      c
                                                                                                                                K ..                        Q      .
      votarc, on oevsa to, wn*< *o w sm enewes w eun ~~ m "a *"***n~* "****'    " ~" ** """"," ***"'"* L~ "*n w u c"vwe= =un s
    1
                                                                                              ___
    3                                              __
      3
                  Contrary to paragraphs (f) and (k) of 10 CFR 50.49, and Section 5(1) of
                  NUREG-0588, Category I, the EQJB B0P-Limitorque and EQJB SRN 503 for
    *            Limitorque motor operators, did not adequately support qualification
      3          (1) in that the terminal block (TB) types used within the operators were
                  not identified in the documentation file: (2) no methodology to establish
      *          qualification of these TB's were in the documentation file; and (3) a
      ,
                  similarity analysis, to demonstrate qualification of tbs used in operators
                  represented by the EQJB SRN 503 file, was not available [ Appendix B,
      '
                  paragraphs 4.f(2)(c)l) and 4.f(2)(c)2)].
      s
      to
      it.
      12
      13
      14
      15
      16
      17
      18
      tt
                                                                                                                                                            --
      30                              _
      21
      22
        23
        SS
        2s
        26
        27
        A
        n
        w
        31
        st
        as
        se
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        d
        as
              *                                                                                                  U.S. NUCLE AR REGULATORY COMMISSK
                                  ._          _      ._
                                                                                          .      _    . . _ . _ _ ..          __.      . . _ . _ _ . _ .
 
                                                                                                                          _
~                                                                                            cu oar      woovai,uucta
                                                        ocem ,,o . . ..., on t,co.si
      c eom 7ee A
  1' 8
                                                          NO 18v Dmoovctatt36. gds)        NO      5tQ  hlkj5jhl7l[gl
                INSPECTOR'S REPORT                O 5 0 0 0 45&                        87    71 1
                                                                                                      e
                                                                                                      -  ~'*4" ~ ^ ~ ~a ,, g
                                                                                                          , ,    ,  ,    ,      ,c
                                                                                                                3
                    (Continuation)
      Office of Inspection and Enforcement
                                                                                                      c
                                                                                                                  K  11
                                                                                                                                g  eo
                                                                                                                                    m
                                                                                                                                        -
    tans,o on onvaron wnw ,.o ro sa cwuws w enn m o w*=t =um* *~* ~~~'. " * " nu*m, *o o*'no~~ L~ ~m ro w envuws *un s
  i
                                                                                                                                      _
  a
                Contrary to paragraphs (f) and (k) of 10 CFR 50.49, and Section 5(1) of                                              -
    '
                NUREG-0588, Category 1, EQ Job Book (E0JB) 211.161 in the equipment
  4            qualification file (EQF) for T95 and 35 tape splices, used in Limitorque
          ~~
                SMB/SB motor operators inside and outside containment, did not adequately
    * {-
                                                                                                                                      -
                support qualification (1) in that similarity between the tested in-line
                splice and the installed V-shape splice configurations was not
                                                                                                                        *    -
                                                                                                                                ,y  _
                                                                                                                  -T
    e
                established; and (2) the insulation resistance data take.n._dur.i m the                                              -
                  in-line splice type test were not availa Mbe'EQT and consequently
                                                                            '
    '                                                                          . ,
    af-        not reviewed for impact with regards toVfunctional performance
                                                                        -
                                                                                                                                      -
    , {          requirements of control circuits at RBS.
    10
    11
    11.
    11
    14
    Il
    ,.
    17
    ''
    1
      )
    ,.
          E
  ~D  ,
      4
      4                    _
                                                              -
                                                                                                -
      }4
      1s
      O
      s1
      O
      O
        so
      31
        12
        31
        M
        O
        h
              2                                                                                    U.S. NUCLE AR REGULATORY COMMISSR
 
                                                          .                    -
    In Reply Refer To:
    Docket: 50-458/87-21
    Gulf States Utilities
    ATTN: Mr. James C. Deddens
                Senior Vice President, (RBNG)
    P.O. Box 220
    St. Francisv111e, Louisiana 70775
    Gentlemen:
    SUBJECT:        EQUIPMENT QUALIFICATION INSPECTION - RIVER BEND STATION
    This refers to the first round special team inspection to review compliance
    with 10 CFR 50.49, of activities authorized by License No. NPF-47, conducted by
    Mr. A. R. Johnson and other NRC representatives, onsite during the period of
    November 2-6, 1987, and subsequently at the NRC Region IV office until
    December 18, 1987, concerning the River Bend Station (RBS). The team's
    findings were discussed with members of your staff at the conclusion of the
    onsite inspection on November 6,1987.
    Areas examined during the inspection included your implementation of a program
    for establishing and maintaining the qualification of electric equipment within
    the scope of 10 CFR 50.49. In preparation for this inspection, the NRC team
    included reviews and evaluations of your implementation of equipment
    qualification (EQ) corrective action commitments identified in Safety
    Evaluation Report (SER) NUREG-0989 (May 1984) and SER Supplements 3 and 5
    (August and Novcmber 1965). These documents provide the NRC staff acceptance
    of justifications for irterim operation (J10s) which you provided prior to the
    Novan.ber 30, 1985, deadiine for the completion of EQ as defined by
    10 CFR 50.49.
    Within these areas, the inspection consisted of the examination of selected
    procedtres and records, interviews with personnel, and observations by the NRC
    inspectors. The inspectior. firdings are documented in the enclosed inspection
    report.
    During this inspection, it was found that certain of your activities were in
    violation of hRC requirements.          Consequently, you are required to respond to
    these violations, in writing, in accordance with provisions of Section 2.201 of
    the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations.
    Your response should be based on the specifics contained in the Notice of
    Violation enclosed with this letter.
    Five unresolved items are identified in paragraphs 4.c, 4.f(1)(a),
    t..f(1)(b), 4.f(1)(c), 4.f(3), 4.f(4), and 4.h(2) of the enclosed inspection
    report.                                                                      7
                                                                                  D
    DRS/PSS            AC:PSS          0/DRS              C:0RP/                D:DRP            Reconcur
    ARJohnson;dp        REIreland      JLMilhoan          00Chrber..fr LJCallan REIreland
        / /88              / /88            / /88              / /88                  / /88          / /88
                                                            grg o cc v72.
    NRR:0RIS:SPS/C
    UPotapovs
    4/6/88
    By tel call with R. Wilson NRR:0RIS:SPS
-. _        , _ . -            -
                                    ___ _          . . _ _        - _ - _ _ . .      -    . . _ _ _    . , - _. .
 
  In Reply Refer To:
  Docket:  50-458/87-21
  Gulf States Utilities
  ATTN: Mr. James C. Deddens
          Senior Vice President, (RBNG)
  P.O. Box 220
  St. Francisville, Louisiana 70775
  Gentlemen:
  SUBJECT:  EQUIDMENT QUALIFICATION INSPECTION - RIVER BEND STATION
  This refers to the first round special team inspection to review compliance
  with 10 CFR 50.49, of activities authorized by License No. NPF-47, conducted by
  Mr. A. R. Johnson and other NRC representatives, onsite during the period of
  November 2-6, 1987, and subsequently at the NRC Region IV office until
  Decemt,e r 18, 1987, cont -ning the River Bend Station (RBS). The team's
  findings were discussed with members of your staff at the conclusion of the
  onsite inspection on November 6, 1987.
  Areas examined during the inspection included your implementation of a program
  for establishing and maintaining the qualification of electric equipment within
  the scope of 10 CFR 50.49. In preparation for this inspection, the      NRC team
  included reviews and evaluations of your implementation of equipment
  qualification (EQ) corrective action commitments identified in Safety
  Evaluation Report (SER) NUREG-0989 (May 1984) and SER Supplements 3 and 5
  (August and November 1985). These documents provide the NRC staff acceptance
  of justifications for interim operation (JI0s) which you provided prior to th:
  November 30, 1985, deadline for the completion of EQ as defined by
  10 CFR 50.49.
  Within these areas, the inspection consisted of the examination of selected
  procedures and records, interviews with personnel, and observations by the NRC
  inspectors.    The inspection fIrdings are documented in the enclosed inspection
  report.
  During this inspectior., it was found that certain of your activities were in
  violation of NRC requirements. Consequently, :ou are required to respond to
  these violations, in yriting, in accordance with provisions of Section 2.201 of
  the NRC's "Rules of Practice," Part 2, Title 10 Code of Federal Regulations.
  Your response should be based on the specifics contained in the Notice of
  Violation enclosed with this letter.
  Six unresolved items are identified in paragraphs 4.b(1)(b), 4.c, 4.f(1)(a),
  4.f(1)(b), 4.f(1)(c), 4.f(3), 4.f(4), and 4.h(2) of the enclosed inspecticn
  report.
                                  '
  DRS/PSS          AC:P5S                        C:DRP/A        D:DRP      Reconcur
  ARJohnson p      REIreland      MJL lhoan      DDChamberlain LJCallan RElreland
  A /5/88          j/,f/88          1/ /88          / /88            / /88      / /88
      a , 3 2 n s n/c,
      Q , Toto p o %
      4/u/%
g    gq      mu d lvfb mo wt'54
}}

Latest revision as of 21:49, 14 June 2022

Insp Rept 50-458/87-21 on 871102-26 & 1218.Violations Noted. Major Areas Inspected:Licensee Implementation of Program for Establishing & Maintaining Qualification of Electric Equipment within Scope of 10CFR50.49
ML20151R716
Person / Time
Site: River Bend Entergy icon.png
Issue date: 04/05/1988
From: Andrea Johnson
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151R676 List:
References
50-458-87-21, NUDOCS 8804280071
Download: ML20151R716 (35)
v • d • e


See also: IR 05000458/1987021

Text

{{#Wiki_filter:_ _ _ _ _ _ _ _ - _ - _ _ _ _ _ 

 .
                                           APPENDIX B
 .
                              U.S. NUCLEAR REGULATORY COMMISSION
                                            REGION IV
     NRC Inspection Report:     50-458/87-21           Operating License: NPF-47
     Docket:   50-458
     Licensee: Gulf States Utilities (GSU)
                 P.O. Box 220
                 St. Francisville, Louisiana 70775
     Facility Name:    River Bend Station (RBS)
     Inspection At:    St. Francisville, Louisiana 70775
     Inspection Conducted:     November 2-26, 1987 (onsite) to December 18, 1987
                               (NRC Region IV office)
     Inspector:      __j.          M        DM&                                                               '
                                                                                                                86
                     A. R. Jofinson ' Reactor Inspector, Division of        Date
                        Reactd        ty
     Accompanying
       Personnel:    J. L. Milhoan, Director, Division of Reactor
                        Safety (DRS), Region IV (RIV)

, R. Maist, Equipment Qualification and Test ! Engineer, DRIS, NRR l M. Trojovsky, Consultant Engineer, Idaho 

                        National Laboratory (INEL)
Q. Decker, Consultant Engineer, INEL

, V. Nicolette, Member of Technical Staff, 

                        Sandia National Laboratories
                      R. E. Irelana, Acting Chief, Plant Systems
                        Section (PSS), DRS, RIV
                     D. E. Norman, Reactor Inspector, PSS, DRS, RIV

{ 

                      R. Evans, Reactor Inspector, PSS, DRS, RIV

l 

     Approved:               [ N /b/
                      R. E. Ireland,' Acting Chieft Plant Systems          ~~Date '
                                                                                            f/[[
                        Section, Division of Reactor Safety
     Inspection Summary
     Inspection Conducted November 2-6,1987, (onsite) to December 18, 1987 (NRC
Region IV Office) (Report 50-458/87-21)

j Areas Inspected: Special, announced inspection to review the licensee's 

     implementation of a program for establishing and maintaining the qualifict. tion

l 

                        ~
   ~~8804'280071'880419
    PDR     ADOCK 05000458
    g                     DCD

                                                                        .   _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _
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                                                                      2
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    of electric equipment within the scope of 10 CFR 50.49. In preparation for
    this inspection, the NRC team included a review of GSU's implementation of
    equipment qualification (EQ) corrective action commitments, identified in
    Safety Evaluation Report, NUREG-0989, May 1984 (SER), SER Supplements 3 and 5
    (August and May 1985). These documents provide the NRC staff acceptance with
    regard to equipment for which justification for interim operation (JI0s), were
    provided prior to the November 30, 1985, deadline.
    The NRC inspection team reviewed a sample of 45 EQ binders (job books and
    packages) in the EQ file (EQF) out of a total of 89, and walked down 38
    components / equipment.
    Results: The inspection determined that the licensee has implemented a program
    to meet the requirements of 10 CFR 50.49, however, four violations of NRC
    requirements and five unresolved items about which more information is
    required, were identified.

l l The licensee's submittals (GSU Walkdown Question / Response Identification Forms) i 

    to the NRC Region IV during and subsequent to the onsite inspection period,
    provided additional information and addressed the inspection findings presented
    in the exit interview by the NRC on November 6, 1987. The licensee's
    information and proposed methods of resolution of the inspection findings have
    been reviewed and were considered in preparation and issuance of this report.
    The deficiencies identified by the NRC inspection team involve documentation
    files which could not establish that this equipment was qualified. These

, 

    components were identified during onsite review of the EQ documentation files
    and a corresponding plant walkdown inspection. The licensee was urged to
    resolve these concerns and place the necessary justifications for continued
    operation (JCOs) in place as soon as possible in accordance with the NRC
    Generic Letter 86-15.
                                        _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

   _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                    ._  _                                              -_
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                                                                                     3
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                                                                                  DETAILS
                                           1.   Persons Contacted
                                               V. Bacanskas, Coordinator, Equipment Qualification Coordinator
                                               A. Soni, Supervisor, EQ
                                               T. F.- Punkett, Plant Manager
                                               J. E. Booker, Manager, RBS Oversight
                                              *R. R. Smith, Engineer, Nuclear Licensing
                                               M. E. Walton, Technical Assistant
                                              - T. C. Crouse, Manager, Quality Assurance (QA)
                                               D. L. Andrews, Director, Nuclear Training
                                               T. P. Anthony, Field Engineering
                                                I. M. Malik, Supervisor, Quality Systems
                                               J. E. Spivey, QA Engineer
                                               D. R. Shah, Senior EQ Engineer
                                               D. R. Derbonne, Assistant Plant Manager
                                               G. R. Kimmell. Director. Quality Service
                                              *W.   H. Odell, Manager, Administration
                                              *K. Suhrke, Manager, Project Management
                                               J. R. Hamilton, Director, Design Engineering
                                               C. L. Miller, Compliance Analyst
                                               P. D.. Graham, Assistant Plant Manager, Operations
                                               T. L. Weir, Director, RBS Materials
                                               R. J. King, Supervisor, Nuclear Licensing
                                               M. F. Sankovich, Manager, Engineering
                                               D. N. Lorfing, Senior Engineer, Nuclear Licensing
                                               R. B. Stafford, Director, Operations, QA
                                               A. D. Kowalczuk, Director, RBS Oversight
                                              *H. Roach, Electrical Maintenance Supervisor
                                              *C. B. Graham, Supervisor, EQ Maintenance
                                              *R. Horn, Nuclear Training Coordinator
                                              *S. V. Desai, Senior Instrumentation Engineer
                                               Other

t l A. Athelu, Senior EQ Engineer, Consultant j G. McGee, Manager, Engineering, General Electric Corporation (GE) 

                                               A. K. Wadhwa, Supervisor, Engineer, Stone & Webster Engineering

l Corporation (SWEC) i L. Johnson, Site Representative, Consultant i N. Luria, Manager, Qualification Engineer, GE l A. Blum, Assistant Section Manager, SWEC ' L. Illy, Lead EQ Engineer, SWEC 

                                               A. S. Abella, Field Engineering, SWEC
                                               NRC
                                               W. H. Paulson, NRR Project Manager

l i i 

  .
                                              4
 ..
        D. D. Chamberlain, Senior Resident Inspector, RIV
       *G.  L. Madsen, Region IV, Project Inspector, RIV
       * Denotes attendance at the exit interview only.
    2.  Purpose
        The purpose of this_ inspection was to review the licensee's implementation
        of the requirements of 10 CFR 50.49.
    3.  Background
        NUREG-0588 was issued in December 1979 to promote an orderly and
        systematic implementation of equipment qualification programs by industry
        and to provide guidance to the NRC for its use in ongoing licensing
        reviews.    The positions contained in NUREG-0588 provided guidance on
        (a) how to establish environmental service conditions, (b) how to select
        methods that are considered appropriate for qualifying equipment in areas
        of nuclear plants, and (c) other areas such as margin, aging, and
        documentation.
        A final rule on environmental qualification of electrical equipment
        important to safety for nuclear power plants became effective on
        February 22, 1983. This rule, Section 50.49, of 10 CFR Part 50, specified
        the requirements to be met for demonstrating the environmental

< 

        qualification of electrical equipment important to safety located in a
        harsh environmer.t     In conformance with 10 CFR 50.49, electrical equipment
        for the RBS is qualified according to the criteria specified in Category I
        of NUREG-0588.
        To document the degree to which the environmental qualification program
        complies with the NRC environmental qualification requirements and
        criteria, the licensee provided equipment qualification information by
        letters dated March 1, October 19, and December 14, 1984; and February 15,
        March 12, 15, and 29; April 26 and 29; May 10, 13, and 15; June 10, 19,
        24, and 26; July 19 and 23; August 13, 22, and 26; September 12 and 30;
        October 10, 18, and 25, 1985; and July 23, 1986, to supplement the
        information in FSAR Section 3.11 and Appendix A and B.
        The GSU SER, NUREG-0989 (May 1984), stated that the NRC had reviewed the
        adequacy of the RBS environmental qualification program for electrical
        equipment important to safety as defined in 10 CFR 50.49. The scope of
        this report included an evaluation of (a) the completeness of the list of
        systems and equipment to be qualified, (b) the criteria they must meet,
        (c) the environments in which they must function, and (d) the
        qualification documentation for the equipment.
        On January 26-28, 1985, the NRC, with assistance from EG&G Idaho, Inc.,
        conducted an audit of GSU's qualification documentation and equipment
        installed at the plant. Equipment items were reviewed to determine if the
        documents in the qualification files supported the qualification status

                                                                               __ __
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                                        5
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   determined by the licensee.    Several deficiencies were noted and discussed
   with GSU at the time of the audit. These deficiencies were also provided
   to'the applicant in June 1985 and transmitted to the applicant by letter
   dated July 17, 1985. The applicant responded by letters dated June 19 and         ,
   July 19, 1985, The NRC reviewed the responses and concluded that the
   deficiencies had been adequately resolved.
   By letter dated March 29, 1985, GSU in response to Generic Letter 84-24,
   certified it was in compliance to 10 CFR 50.49 in that all equipment was
   either fully qualified or a justification for interim operation (JIO) had
   been submitted pending full qualification, and 10 CFR 50.49(1) was
   applicable based on their plant schedule.
   By letter dated June 26, 1985, GSU submitted to NRC drywell and
   containment pressure and temperature results for limiting large break and
   for various small breaks. These curves showed the corresconding
   environmental design criteria used for the equipment qualification. SER
   NUREG-0989, Supplement No. 3, was issued in August 1985.
   For safety-related items not having complete qualification documentation,
   GSU provided commitments for corrective action and schedules for
   completion. For items identified that would not have full qualification
   before an cperating license was issued, analyses had been performed in
   accordance with 10 CFR 50.49(i) to ensure that the plant could be operated
   safely pending completion of environmental qualification. These analyses
   were submitted to the NRC. The NRC reviewed the JI0's and concluded that
   reasonable assurance has been provided that the River Bend plant could be
   operated safely pending completion of environmental qualification.
   RBS initial criticality occurred October 31, 1985.     SER NUREG-0989,
   Supplement No. 5, was issued in November 1985. By letters dated July 19;
   August 13, 14, 22, and 26; September 12 and 30; October 10, 18, and 25;
   and November 4, 1985, GSU provided information stating that environmental
   qualification has been completed on all equipment having outstanding
   JIO's.
   The aging program requirements for electrical equipment at River Bend are
   defined in Category I of NUREG-0588. All degrading influences are
   considered and included in the aging program. Justification for excluding
   pre-aging of equipment in type testing is to be established on the basis
   of equipment design and application, or on state-of-the-art aging
   techniques. A qualified life is to be established for each equipment
   item. A maintenance / surveillance program is required to be implemented to
   identify and prevent significant age-related degradation of electrical
   equipment. GSU committed to follow the recommendations in Regulatory
   Guide 1.33, Revision 2, which defines the scope and content of a
   maintenance / surveillance program for safety-related equipment. Provisions
   for preventing or detecting age-related degradation in safety grade
   equipment are specified and include (a) utilizing experience with similar
   equioment, (b) revising and updating the program as experience is gained
   with the equipment during the life of the plant, (c) reviewing and

                ..          .   .       _ _ -    _
                                                     .                                      -
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                                                   6
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         evaluating malfunctiening equipment and obtaining adequate replacement
         components, and (d) establishing surveillance tests and inspections based            .
         on reliability analyses, frequency and type of service, or age of the
         items, as appropriate. This maintenance / surveillance program is to be in

i 

         effect at River Bend.
         The above identified documents were reviewed by the NRC inspection team

" 

         members and used in preparation for this inspection. The inspection
         involved an onsite and subsequent NRC Region IV in-office inspection of
         records furnished by the licensee.
      4. Findings                                                                             6
         a.    EQ program Compliance With 10 CFR 50.49
              The NRC inspectors examined the licensee's program for establishing
               the qualification of electric equipment within the scope of 10 CFR
               50.49. The program was evaluated by examination of the licensee's
               qualification documentation files, review of procedures for
              controlling the licensee's EQ efforts, and verification of adequacy
               and accuracy of the licensee's program for maintaining the status of
              electrical equipment. Based on the inspection findings, which are
              discussed in more detail below, the inspection team determined that

i 

               the licensee has implemented a program to meet the requirements of
               10 CFR 50.49 for the RBS although some deficiencies were identified
               (refer to Sections 4.f and 4.h).
         b.    EQ Program procedures
,
              The inspection team examined the implementation and adequacy of site
              policies and procedures for establishing and maintaining the
              qualification of electrical equipment in compliance with the
               requirements of 10 CFR 50.49. The licensee's methods for
              establishing and maintaining the qualification of electric equipment

j were reviewed in the following documents: I Engineering Department procedures Manual 

               procedure No.                  Title
               EDP-EE-01                      Processing of Equipment Qualification Related
                                              Documents, Revision 1
               EDP-EE-02                      Evaluation of Change Documents for Impact on
                                              Equipment Qualification, Revision 1

' 

               EDP-EE-04                      Control and Maintenance of the River Bend
                                              Equipment Qualification Master Lists,
                                              Revision 1

    A

  _ _ _ _ _ _ _ _ _ - _ _ _ _ .__    ._,
  .

i- 7 

   ..
                              EDP-EE-05                 Preparation and/or Revision of Equipment
                                                        Qualification Maintenance and Surveillance
                                                        Requirements (EQMSR), Revision 1
                              EOF-EE-07                 Ccmpilation, Maintenance, and Updat!ng of the
                                                        Equipment Qualification Job Books, Revision 0
                              EDP-EE-09                 Control and Maintenance of System Component
                                                        Evaluation Worksheet (SCEW), Revision 1
                              EDP-AA-30                 Processing Condition Reports within
                                                        Engineering, Revision 1
                              EDP-AA-54                 Engineering Department Guidelines and
                                                        Instructions for Processing Modification
                                                        Requests, Revision 8
                              EDP-AA-64                 Control and Approval of Field Change
                                                        Notices (FCNs), Revision 6
                              EDP-AA-65                 Review and Processing of Vendor Technical
                                                        Information, Revision 3
                              E0 Maintenance procedures
                              Procedure No.             Title
                              MSP-0003                  Preventive Maintenance Program, Revision 10
                              GMP-0093                  Equipment Qualification Special Requirements,
                                                        Revision 1
                              GMP-0015                  Lubrication Procedure, Revision 3
                              PMP-1205                  Motor Operated Valve Routine Maintenance,
                                                        Revision 4
                              Training procedures
                              Procedure No.             Titie
                              TPP-7-013                 Mechanical Maintenance Training, Revision 1
                              MSP-0009                  Qualification of Maintenance Personnel,
                                                        Revision 8
                              EDP-AA-10                 Training Requirements for Engineering
                                                        Department Personnel, Revision 6
                              TPP-7-025                 Staff and Management Training Technical
                                                        Program
                                                                                                      1

 .
                                   8
 4
   TAP-5-007                  Training Records and Documentation,
                              Revision 2
   TPP-7-027                  Quality Assurance Personnel Training,
                              Revision 1
   GAP-1.3                    Quality Assurance Indoctrination and Training
                              Program Procedure, Revision 6
   Station Operating Procedures
   Procedure No.              Title
   E0P-0101                   Emergency Procedure - RPV Control, Revision 0
   Qualification Engineering Procedure
   Procedure No.              Title
   QUAL-85-001                On Site FDDR Oualification Review, Revision 4
   QUAL-85-002                River Bend FDDR Qualification Review Check
                              List, Revision 5
   Station Support Manual Procedures
   Procedure No.              Title
   ENG-3-006                  River Bend Station Design and Modification
                              Request Control Plan, Revision 3
   Operations Quality Procedures and Instructions
   Procedure No.              Title
   QAI-2.1                   Audit Performance, Reporting tnd Followup,
                              Revision 4
   QAI-2.6                    QA Review of Design Changes and Plant
                             Modifications, Revision 1
   The inspection team reviewed the above licensee's procedures for
   meeting the requirements of 10 CFR 50,49 including: (1) qualified
   life; (2) servict conditions; (3) periodic testing; and

2 

   (4) maintenance and surveillance. The licensee's EQ program was also
   reviewed with regarc to establishment of an auditable documentation
   file, including such documents as EQ audit reports, maintenance and
   surveillance records, supporting documents which establish EQ
   training of personnel, and supporting documents which control plant

i modifications, and installation of replacement equipment to the 

   requirements of 10 CFR 50.49.

 . - _ - _ _ _ - _ _ _ _ _ _                   _ _ _ _ _                                                  . _ _ _ _ _ _ _ _ _ _ _    _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ _ _
           .
            .
                                                                                              9
                                                                                                                                                                                                           '
                                                         The licensee's EQ program procedures and policies are established and
                                                         are being adequately implemented to control and maintain the
                                                         environmental qualification of electrical equipment at RBS for
                                                         compliance with the requirements of 10 CFR 50.49.
                                                         The following programs were effectively in place at RBS:
                                                         (1) EQ Maintenance / Preventive Maintenance Program
                                                              (a) The RBS EQ maintenance program has been integrated into the
                                                                        licensee's overall maintenance program through the
                                                                        following procedures which were reviewed by the NRC                                                                                ,
                                                                        inspection team:                                                                                                                   ,
                                                                        MSP-0003 establishes and implements a preventive
                                                                        maintenance (PM) program, establishes equipment to be
                                                                        included in the program, monitors and adjusts maintenance
                                                                        activities, and establishes the EQ requirements for
                                                                        parts / component replacement and special maintenance                                                                              ,
                                                                        requirements. Primary features of the program, as related
                                                                        to EQ maintenance, include the Equipment Qualification
                                                                        Maintenance and Surveillance Requirements (EQMSR), issued
                                                                        by engineering to maintenance departments and PM task
                                                                        approvals (PMTA) which are initiated to comply with the
                                                                        EQMSRs. The program is managed by means of a computerized                                                                          '
                                                                        PM data base which tracks and schedules the PM activities.
                                                                        GMP-0093, defines EQ maintenance requirements that have not
                                                                        been defined with a specified frequency, but are required
                                                                        anytime a maintenance activity is performed.
                                                                        EDP-EE-05 establishes the guidelines for preparing and
                                                                        revising requirements identified in the equipment
                                                                        qualification documentation that are necessary to maintain
                                                                        the equipment in a qualified status.
                                                                        EDP-EE-07 provides guidelines and instructions for
                                                                        compiling, reviewing, maintaining, and updating EQ Job
                                                                        Books.
                                                                                                                                                                                                           >
                                                                        EDP-EE-01 establishes guidelines and instructions for the
                                                                        control, processing, review, and maintenance of EQ-related
                                                                        documentation.
                                                                        GMP-0015 provides general instructions for lubrication of
                                                                        plant components, including EQ items,

i PMP-1205 provides instructions for the periodic maintenance 

                                                                        of motor operated valves.

' ! i 

                                                                                                                                                                                                           i
                                                                                                                                                                                                           t
                             - ,_
                                  -,--..,-..,n                  -,..n_.    _ - - ..   -_,.n_-   -   _ , , . . , _                 - - , . , _ . . . _ - - . - _ - _ - - - -                          - - -

. 

                                  10
.
              No violations or deviations were identified by the NRC
              inspection team during the procedural review.
         (b)  In addition to procedural reviews, the NRC inspection team
              reviewed the EQ maintenance program implementation by
              selecting a sample of 11 components from the EQ master list
              and comparing the required PM from the applicable EOMSRs to
              that scheduled to be performed by the PM data base. All
              required maintenance for the sample appeared to be
              adequately scheduled for 10 of these items; however, vendor
              recommended maintenance shown on the EQMSR for the
              Gould-Brown Boveri switchgear (mark number 1 ENS *SWG3A),
              even though included on the maintenance data base, had not
              been scheduled for completion during this outage, as
              required. The following maintenance had not been scheduled
              to be performed:
              *    -Servicing circuit breakers,
              *
                    Exercising circuit breakers,
              *     Inspection of primary interface connectors.
              *     Inspection of primary cables,
              *
                    Exercising racking mechanism,
              *
                    Cleaning contamination from all primary insulation,
              *     Inspection of control wiring bundles, and
              *
                    Cleaning stationary breaker connection stubs.
              Prior to the completion of the NRC inspection, the licensee
              scheduled the maintenance to be completed during the
              outage. The PM requirement for the equipment had been
              addressed in Task Approval EC01113 which was added to the
              required PM tasks on July 27, 1987. Prior to the outage,
              PM tasks placed on the master outage schedule were placed
              on "Hold" on May 1, 1987. Since the PM for the subject
              item was added subsequent to the master schedule "Hold"
              date, it was inadvertently omitted from the schedule. The
              PM was due on July 27, 1987, and performed on November 11,
              1987, within the 25 percent grace period permitted by
              MSP-0003, after being identified during the NRC inspection.
              GSU electrical maintenance group performed a 100 percent
              review of all task approvals from the "Hold" date to the
              present and no other missed PM tasks were identified.
              No violations or deviations were identified by the NRC
              inspection team.
    (2) Control of Plant EQ Modifications
         RBS procedures were reviewed by the NRC inspection team to
         ensure proper maintencnce of documentation for EQ components
         during plant modifications as follows:
  .

! 

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                             11
 .
   (a) Procedure EDP-EE-01 provides guidelines and instructions to
         maintain control, processing, review, updating, and
         maintenance of documentation for EQ components. An EQ
         reviewer reviews assigned documents (including vendor
         technical information, modification requests (MR),
         nonconformance reports (NR), condition reports (CR), EQ
         maintenance / surveillance requirements, NRC or INPO          i
         correspondence and IE notices / bulletins), and determines if
         the document is applicable to, or affects EQ. If there is
         an impact, the impact is tracked on an EQ documentation       ,
         log.
   (b) Procedure E0P-EE-02 specifically describes the requirements
         for evaluation of MRs, NRs, and CRs for impact on EQ
         components. A copy of the attached EQ Impact
         Summary (EQIS) sheet, and tb EQ Impact Review
         Checklist (EQ1RC), are then included in the MR/CR packages.
         Any EQ documentation requiring revision and/or initiation
         of action as well as EQ evaluations are identified on the
         EQIS.
   (c) Procedure EDP-AA-54 establishes guidelines and instructions
         for processing MRs by engineering personnel. Most MR
         packages include an EQIRC (EDP-AA-54, Attachment G) to
         ensure that qualification is maintained if modifications to
         the plant are required. A checklist is required for all
         emergency and Q Class 1 MRs.
   (d) Procedure ENG-3-006 provides overall instructions on
         controlling design and modification actions at RBS. This
         procedure is used in conjunction with EDP-AA-54 when
         processing MRs. The modification completion checklist
         (ENG-3-006, Attachment 5) includes instructions to ensure
         that EQ documentation has been updated prior to final
         closeout of an MR.
   (e) procedure EDP-AA-64 provides directions on the control and
         approval of field change notices (FCNs). The FCN provides
         a method of incorporating a change into an existing MR
         design, and the FCN becomes a part of the MR package. The
         FCN is reviewed to determine if any previous review or
         evaluation is affected by the change, with regards to
         qualification of components.
   (f) Procedure EDP-AA-30 provides instructions for processing
         CRs within the RBS engineering department. The Condition
         Report One Time Deviation Design Review (EDP-AA-30,
         Attachment B) ensures that a qualification review is
         performed.

        .-
 j(
                                      12
   .
            (g) Procedure QAl-2.6 defines and establishes QA
                  responsibilities for the review of design change activities
                  including MRs, FCNs, and NRs. QA checklists (QAI-2.6,
                  Attachment 2 and 3) are used in the review of MRs and FCNs
                  to ensure they are in accordance with applicable procedures
                  and requirements, including EQ engineering reviews.
            No violations or deviations were identified by the NRC
            inspection team during review of procedures.
            In addition to the procedure review and interviews with
            personnel, the NRC inspection team reviewed the implementation
            of the EQ modification program by selecting one MR (No. 86-1778)
            to ensure the licensee was following approved procedures.
            Controls for the EQ Modification Program appear to be adequately
            implemented based on the selection of this one MR.
            Further verification of the GSU EQ Modification Program, using a
            larger sample, will be accomplished during a subsequent NRC
           - inspection.
     (3) Procurement of Materials and Services Including Replacement
            Parts
            The RBS EQ Procurement Program is an integral part of the
            licensee's overall EQ Program and is controlled by the following
            procedures:
            Procedure No.               Title
            RBNP-003                    Material Management System
            NuPE-AA-42                  Evaluation and Justification of
                                        Commercial Grade Items
            EDP-AA-43                   Technical Quality Documents for
                                        Procurement
            The RBS EQ Replacement Parts Program is integrated with the EQ

, 

            Maintenance Program (refer to paragraph 4.b(1)(a) above) which
            establishes the requirements for part/ component replacement.
            Also, the EQ Replacement Parts Program is governed by those
            procedures listed above.
            Further review of the controls and implementation of the EQ
            Replacement Parts Program at RBS will be accomplished during a
            subsequent NRC inspection,

i i 

     __ _                     _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ __                               _ _ _ _ _              _ ___   . _ _ _ _ _ _ _ _ _ _ _ _ _ _
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                                                                                                                 13
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                                                                         c. Training Program
                                                                                                                                                                    !
                                                                            A review was conducted by the NRC inspection team to determine if a

^ 

                                                                            training program was in place to provide necessary training to
                                                                            personnel involved in implementing all phases of the EQ program at
                                                                            RBS as follows:
                                                                            (1) Technical Staff and Management - This program consists of a
                                                                                   series of formal training courses and mandatory reading lists
                                                                                  which are specified in Procedures TPP-7-025, EDP-AA-10, and
                                                                                  TAP-5-007. Procedure TAF-5-007 is applicable to all RBS
                                                                                  disciplines.
                                                                                  The program for training of technical staff and management
                                                                                  appears adequate; however, review of implementation of the
                                                                                  program could not be completed because of an inadequate sample
                                                                                  of training records available at the time of the onsite
                                                                                  inspection.
                                                                            (2) Quality Assurance - The Ouality Assurance and Quality Control
                                                                                  training programs consist of formal training, on-the-job
                                                                                  training, and mandatory reading lists which are specified in
                                                                                  Procedures QAP-1.3 and TPP-7-027. No specific EQ training or
                                                                                  mandatory reading could be identified in this program review.
                                                                                  Also, review of the program implementation could not be
                                                                                  completed because of an inadequate sample of training records
                                                                                  available at the time of the onsite inspection.

< (3) Maintenance Program - The RBS maintenance program reportedly 

                                                                                  meets INP0 accreditation standards in the areas of mechanical,
                                                                                  electrical, and instrumentation and control (I6C). The
                                                                                  objectives of this inspection were to review procedures which
                                                                                  establish the program and to review the program implementation
                                                                                  by reviewing a sample of employee training records.
                                                                                  Procedures MSP-0009 and TPP-7-013 were reviewed during the

, 

                                                                                  inspection.

, Items identified in paragraphs 4.c(1), 4.c(2), and 4.c(3) above are l considered an Unresolved Item pending review of electrical and I&C j procedures and training records which were not available during the ' 

                                                                            NRC onsite inspection (458/8721-07).

. 

                                                                         d. 0A Audits of EO Activities

) l 

                                                                            A review of RBS QA audits of EQ activities was performed, including
                                                                            interviews with key QA personnel.
,
                                                                            (1) Procedure QAI-2.1 defines the responsibilities and the methods
to be used by the GSU QA organization for planning, performing,

, 

                                                                                  reporting, and followup of QA audits of RBS site activities.

! Prior to an actual audit, a "Master Audit Schedule" and "Master 1 

         _ _ - _ _ _ _ _ , _ _ _ _ _ . . _ _ _ . _

   __. _ _ - _ _ _ _ _ _
          .
                                                              14
     ..
                                    Audit Plan" are developed, followed by a "Notification of Audit"
                                    letter to the specific department to be audited. The audit is
                                    performed in accordance with a GSU audit plan. Audit finding
'
                                    reports are issued within 5 working days and the formal report
                                    is issued within 30 days.
                                    The NRC inspection team reviewed GSU Audit No. 87-01-I-EQAL
                                    regarding an audit of the GSU EQ program, performed during
 '
                                    January 1987. The audit was conducted to provide an overall
                                    assessment of the adequacy and effectiveness of the EQ program
                                    implementation. Emphasis was placed on the capability of the
                                    program to maintain designated equipment in a qualified status
                                    in accordance with the acceptance criteria of 10 CFR 50
                                    Appendix B, 10 CFR 50.49, and RBS procedures. A previous audit
                                    by DiBenedetto Associates (Audit Report No. GSU-01-08-01,
                                    Revision A, dated October 22,1986) focused on the adequacy of
                                    the original qualification data. The NRC inspection
                                    concentrated mainly on the maintenance of EQ qualification
                                    equipment.
                                    The NRC inspection team concluded that QA audits of EQ
                                    activities were effectively being implemented at GSU.
                                    No violations or deviations were identified.
                           e. 10 CFR 50.49 Equipment Qualification Master List (EQML)

] 

                              The EQML and suoporting procedures were reviewed to determine if a

, program has been implemented to generate, maintain, and distribute 

                              the EQML in accordance with 10 CFR 50.49 requirements .

' 

                              Procedure EDP-EE-04 is used to provide control and maintenance of the
                              RBS EQML. All documents having impact on EQ activities at RBS are
                              processed through an EQ reviewer, who determines if the documents
                              warrant an EQML change.     If an update is required, changes to the

, 

                              EQML are made using EQML revision control sheets.
                              The EQML was reviewed against emergency operating procedures (EOPs)
                              and procedure No. E0P-0101 to ensure postaccident monitoring (PAM)

, components listed as part of the RG 1.97 program were included on the

E0ML. Eight PAM parameters were selected and all components were

l found on the EQML. I 

                              No violations or deviations were identified.

! f. EQ Documentation Files i 9 

                              The licensee's environmental qualification file (EQF) at RBS has been

l' established and is being maintained to meet the requirements of 

                              10 CFR 50.49. The requirements are contained primarily in
                              Procedures EDP-EE-07, EDP-AA-65, and QUAL-85-001,
t
                         +

                                15

. 

 The NRC inspection team examined files for 45 selected equipment
 items (E0JBs) to verify the qualified status of equipment within the
 scope of 10 CFR 50,49.     In addition to comparing plant service
 conditions with qualification test conditions and verifying the bases
 for these conditions, the NRC inspectors selectively reviewed areas
 such as: (1) required post-accident operating time compared to the
 duration of time the equipment has been demonstrated to be qualified;
 (2) similarity of tested equipment to that installed in the plant;
 (3) evaluation of adequacy of test conditions; (4) aging calculations
 for qualified life; (5) replacement part schedules; (6) the effects
 of decreases of insulation resistance on equipment performance;
 (7) adequacy of demonstrated accuracy; (8) evaluation of test
 anomalies; and (9) applicability of EQ problems as reported in IE
 Information Notices (IN) and IE Bulletins (IEB) and their resolution.
 During this review of the EQF, the inspection team identified the
 concerns described below:
 (1) EOF Auditability and Organization of Documentation
       During the NRC inspection, a concern was raised with regards to
       the organization of documentation in that it was not readily
       understandable and traceable to permit independent verification
       of interfaces or conclusions. The auditability concerns
       pertained primarily to the EQJBs in the EQF having provided
       incomplete information in establishing qualification of
       equipment, as identified by the NRC inspection team as follows:
       (a) E0JBs 211.161 and 241.232: Hydrogen Ignitor Assemblies,
            Bisco Sealing Compound, Conax Electrical Conductor Seal
            Assembly, Raychem Heat Shrink Splices, Marathon Terminal
            Blocks, Okonite Tape Splices, Anaconda Power Cable, and
            Rockbestos Instrument Cable: File Auditability Problems
            Many RBS files were difficult to audit.    For example, in
            most files reviewed a similarity analysis and an evaluation
            of performance characteristics were not part of the file.
            Similarity questions arose frequently and required tracing
            down the trecification and purchase order,    Licensee
            personnel often gave conflicting verbal answers to
            questions, and significant time was required to obtain the
            correct answers in writing.
       (b) E0JBs BOP Limitorque Motor Opetator, File Auditability
            Problems
            It was not apparent in the file that cycle testing of motor
            operators required for RBS had been enveloped by the cycle
            tests contained in the file used to support qualification
            of the actuators installed. Discussions with licensee
            personnel revealed that the approach used to address this

  -__
                                                                                                         !
e
                                           16
           concern had been incorporated into the specified cycle
            testing of similar actuators in the GE phase III testing
           program. No specific references or auditable trail was                                        -
           contained in the EQF.
           When questioned whether or not the proper orientation of
            the motor actuators had been considered in regard to
           greases, which are found to migrate from the main gearbox
           to the motor or switch compartment, the licensee supplied
           the NRC inspection team with installation procedures. The
           procedures clearly showed that this concern had been
           addressed in the actuator installation and during
            subsequent inspections of the Limitorque actuators at RBS.
           However, no specific references or auditable trail to the
           SWEC installation procedures were contained in the EQF.
            It was not evident in the EQF that either Raychem Flamtrol
           or Rockbestos Firewall III was used as replacement wire for
            internal wiring of SMB Limitorque motor operators. The HRC
            inspection team identified only Reckbestos Firewall III in
           motor operators inspected during the NRC walkdown.
      (c) E0JB SRN 503, Limitorque SMB Motor Operators, High pressura
           Core Spray, Outside Containment, File Auditability Problems
           The basis of qualification of. these valve operators is                                       .
           NUREG-0588, Category I.                             Qualification was supported by            l
           Limitorque Report B0058, dated January 11, 1980, for SMB
           model actuators. Wyle Report 57675, dated April 30, 1986,
           extended the qualification to additional models by
           providing a similarity analysis for the other models.
           Qualification of the operators was adequately established;
           however, audit of the qualification documentation was
           difficult since changes to the tested configuration had not
           been adequately documented in the EQJB documentation
           packages. This became apparent during the walkdown
            inspection and is discussed in greater detail in
           paragraph 4.h of this report. Examples of auditability
           problems are:
            1)   Taped splices made onsite, and not a part of the
                  tested configuration, were not identified in the EQJB
                 oualification documentation of the EQF.
           2)    Terminal blocks, which were not in the tested                                           ,
                 configuration, had been installed and were not
                  identified in the E0JB qualification documentation of
                  the EQF.

! ! 

                                                                                                         I
                   y . - -   , - - - . _ , , - - - , . - - - -               - , ,     - - - - - - -
                                                                                                ..
                                                                                                     - -

                  _ _ _ _ - _ _ _ _ _ _ _ .    _ _ _ _ - . _          ___         ._                ____                           _ _ _ _ _
  .
                                                                                         17
                                                                                                                                             ,
  *
                                                                                                                                             ,
                                                                                                                                             t
                                                                          GSU responded to the above NRC concerns by letter
                                                                                                                                             '
,
                                                                          No. RBG-27213 to the NRC Region IV on December 28,                 "
                                                                          1987, as follows:                                                  L
                                                                          "The puroose of the EQJB is provided in Design        .
                                                                          Engineering Procedure EDP-EE-07, of which Section 6.2
                                                                                                                                             '
                                                                          states that the EQJBs contain copies of the controlled             ,
                                                                          documents that are compiled to provide the EQ auditors
                                                                          with readily accessible cross-reference information.
                                                                          The information contained within the EQJB job book is
                                                                          intended to demonstrate tFe environmental
                                                                          qualification of the equipment used at RBS.    During an
                                                                          audit of-the EQ program at RBS performed by an
                                                                          independent third party consulting firm, similar
                                                                          questions with respect to EQJB content were raised.                :
                                                                          Since the completion of the independent audit, RBS had
                                                                          initiated steps to resolve the questions previously
                                                                          identified; however, these actions were not completed
                                                                          prior to the NRC inspection. GSU recognizes that the
                                                                          concerns raised by the NRC inspection team, with
                                                                          respect to auditability, were similar to those
                                                                          identified during the independent audit. The concerns              >
                                                                          are being addressed on a generic basis with the files
                                                                          being reviewed against a checklist which requires EQ
                                                                          auditors to verify that the information discussed
                                                                          above is included in the EQJB documentation packages.              ,
                                                                          Specific action areas identified for RBS to upgrade
                                                                          the EQJBs include:    (1) identification of installed
i                                                                         equipment interfaces, (2) addition of documentation to
                                                                          the EQJBs for design changes, (3) analysis of
                                                                          functional performance requirements, and (4) reference             ;
                                                                          to associated calculations (i.e., instrument accuracy
                                                                                                                                             '
                                                                          calculations, MVA reduced voltage calculations, etc.).
                                                                          These actions are in progress and will be completed by
                                                                          GSU on June 30, 1988."                                             ;

. , 

                                                             Items identified in paragraphs 4.f(1)(a) 4.f(1)(b), and                         i
                                                             4.f(1)(c) above are considered an Unresolved Item (458/8721-06).
                                                                                                                                             .
                                            (2) EQJBs 228.212, 228.214. 228.216. 228.241, 228.243 and SRN 503:
                                                             BOP and NSSS Supplied Limitorque SMB/SB Motor Operators (Inside
                                                             and Outside Containment)
                                                             (a) BOP Supplied Limitorque Motor Operators. Models SMB and SB                  f
                                                                   (SPEC. 228.212)                                                            t

!,  ! 

                                                                   This EQJB file contained documentation to support                         !

! qualification of the BOP-supplied Limitorque motor ,

operators installed at RBS. Valve actuator '

' 

                                                                   Nos. 1G33*MOVF001, 1821*MOVF016, and IE51*MOVF064
                                                                   documentation was reviewed by the NRC inspection team.

. 

                                                                                                                                              i
                                                                                                                                              I
                                                                                                                                              i
                                                                                                                                              '
    . _ _ _ _ _ _

 .
                               18
                                                                       ,
         Actuator IG33*M0VF001 is located inside the drywell and is
         used to operate the containment isolation valve for the
         reactor water cleanup system. Actuator 1821*MOVF016 is
         also located inside the drywell and is used to operate the
         containment isolation valve for the drain system.
        ~ Actuator 1E51*MOVF064 is located in Zone AB-114-2 (main
         steam tunnel) and is used to position the reactor core
         isolation cooling (RCIC) turbine steam supply containment
         isolation valve.
         1)     The licensee was asked to supply data which would
                indicate that the motor operators used in dual voltage
                application were properly sized for reduced voltage
                application at RBS. The licensee supplied motor
                operator calculations which showed that reduced
                voltage considerations were factored into the
                selection of these valve actuator motor operators.
         2)     A full inspection was performed by the NRC inspection
                team on JB21*MOVF016 which included verifying that
                proper components and materials internal to the limit
                switch compartment were installed. In addition, an
                external inspection was performed, with only one minor
                deficiency identified in that the model depicted on
                the EQML was SMB, whereas SB was found on the actuator
                nameplate. It was determined that this was a
                transcription error and to correct this error, the
                licensee committed to initiate a master list revision
                control (HLRC) and system compo,ent evaluation
                                            ~
                worksheet (SCEW) revision form to indicate the correct
                model and to verify the accuracy of nameplate
                transcriptions for other valves.
        No violaticns or deviations were identified.
   (b) Okonite T95 and 35 Sp_1_ ice,hp_e Applicatiens on 80P-Supplied
        Motor Operators
        Not all of the types of splices used in Limitorque motor
        operators at RBS were identified in the EQJB (Limitorque)
         files; nor was any reference to the documentation used in
        establishing the qualification of these splices f0und in
         the files.
        During the walkdown, the NRC identified Okonite T95 and

! 

        35 splice tape incorporated as the motor lead / field cable
         splice material. An evaluation of the EQJBs that establish
        qualification of the B0P-supplied motor operators revealed
        that the motor lead / field cable interface had not been
         identified (also refer to paragraph 4.h(1) of this report).

l 

                                  ___ _ _ -

 i
 i
   .
                          19
   .
     The licensee supplied reference to the documentation file
     used to establish qualification of the Okonite T95 and
     35 splice tape as EQJB 211.161 (fer application of motor
     leads and control circuits for motcr operators). This file
     is part of SWEC specification for nonengineered field
     purchased items. There were two concerns with this file as
     follows:
     1)   During the NRC walkdown, a V-shaped splice
          configuration was observed to be installed as well as
          an in-line configuration. The observed V-shaped
           splice configuration was not qualified by
          documentation contained in EQJB 211.161.     By the end
          of the inspection, the licensee was able to
          demonstrate that the V-shaped configuration could be
          qualified, thus resolving this concern. However,
          documentation was not present in the EQJB during the
          NRC inspection, indicating that the licensee had not
          adequately assessed the similarity of tested and
           installed splices. NUREG-0588, Category I, Section 5,
          paragraph 1 states that the basis of qualification
           shall be explained to show the relationship of all
           facets of proof needed to support adequacy of the
          complete equipment. The EQJB for Okonite tape did not
          contain sufficient information to establish that the
          tested and installed specimens were identical or
           similar.
     2)   The NRC inspection team identified another concern
          regarding insulation resistance data taken during the
          type test for the in-line splice configuration w' ich

' 

          were not included in the EQJB. Since these splices
          are used in harsh environments (including steam) in
          coatrol circuits, the insulation resistance data was
          requested. The licensee obtained this data from
          Okonite on November 6, 1987, during the NRC inspection
          ar.d presented it to the NRC. The data indicated
          several insulation resistance measurements which were
           so low that they were off the instrument scale. The
          vendor test laboratory attributed the low values to
           improper sealing (equipment apparatus) where cables
          entered the test chamber. Because of the timing in which
          measurements were taken of the low insulation
          resistance values (af ter the most severe temperature
          and moisture conditions), the NRC inspection team
          agreed with this explanation of the test anomalies.
          While this observation was resolved concerning
           insulation resistance data, it indicated that the
           licensee did not have this data prior to the
           inspection and obviously had not reviewed it for its

   _ _ _ _ _ _ _ _ _ ._            _              ___   - _ _
 .
                                                  20
 .
                                   impact on the specified functional performance
                                   requiremcnts of control circuits at RBS.
                             3)    The NRC inspection team identified another concern
                                   regarding unidentified tape splices to motor operator
                                   replacements from Class B to RH insulation. Refer to
                                   paragraph 4.h(1) of this report.
                                   Along with the analysis that provided established
                                   similarity of the V-type tape configuration (as found
                                   in ICCP*M0V144) to the in-line shaped tape
                                   configuration, the in-line type tape splices were also
                                   the configuration found in the remaining four motor
                                   operators inspected by the NRC inspection team.
                             The above concerns in paragraphs 4.f(2)(b)1), 4.f(2)(b)2)
                             above, and 4.h(1) are considered an apparent violation of
                             10 CFR 50.49 (458/8721-01).
                        (c) Qualification of Terminal Blocks (tbs) used in NSSS and B0P
                             Supplied Limitorque Motor Operators
                             1)    B0P Limitorque Motor Operators
                                   At the time of the NRC inspection, the licensee had
                                   yet to identify all of the tbs incorporated in the
                                   power and control circuits internal to the switch
                                   compartment of these Limitorque actuators installed at
                                   RBS.   The types of tbs that may have been used were
                                   not identified in the docementation for all the above
                                   80P-supplied actuators; nor was the methodology
                                   incorporated in the EQJBs to establish qualification
                                   of the tbs found in motor operators at RBS. The only
                                   interface described was found in the documentation of
                                   the GE Phase III testing where Marathon 300 tbs were
                                   incorporated in the tested Limitorque actuators.
                             2)    EQJB SRN S03, Limitorque Motor Operator, Outside
                                   Containment, Unidentified Terminal Blocks
                                   During the walkdown inspection, Buchanan tbs (no
                                   visible model number) were identified in Limitorque
                                   motor operators for valve actuators 1E22*MOVF001,
                                   1E22*MOVF004, 10FR*MOV146, and no TB identification
                                   could be found on ISWP*MOV5703. The tbs were
                                   apparently not oriented in the type test
                                   configuration, or the operator and had not been
                                   addressed in the documentation file for the operators.
                                   Therefore, the qualification status for these motor
                                   operators was indeterminate.     The licensee had no
                                   documentation at the time of the NRC inspection to

[ 

 .
                                    21
 .
                     identify tbs which had been installed in these
                     operators.
                     The licensee performed a walkdown~ inspection, at the
                     time of the NRC inspection, of all safety-related
                     Limitorque operators on November 23, 1987, at which
                     time tbs were identified and summarized. The summary
                     presented to the NRC did not include Buchanan tbs
                     blocks which had previously been identified during the
                     NRC inspection; therefore, the licensee's inspection
                     results appear to be inconclusive. It was also stated
                     by the licensee, concerning TB qualification, that
                     Corporate Consulting Limited Report A-686-85 (SDDF
                     No. 6211.161.997-138A and -139A) demonstrates
                     qualification of tbs used at RBS.
              The above concerns in paragraphs 4.f(2)(c)1) and
              4.f(2)(c)2) regarding the identification and qualification
              of tbs incorporated in the Limitorque motor operators at
              RBS is considered an apparent violation of 10 CFR 50.49
              (458/8721-04).
   (3) EQJB 213.161, Marathon Terminal Blocks
        The NRC inspection team reviewed this file on Marathon NUC 1500,
        1600, and 142ST tbs. These blocks are part of the SWEC
        specification for nonengineered field purchased items. At RBS,
        these tbs are not used inside contai.nment, but can be found in
        harsh environments (including steam). The file contained
        confusing statements as to whether or not these tbs are in

' 

        completely sealed junction boxes. Some junction boxes are
        completely sealed and some have 1/4-inch weep holes drilled in
        the bottom. A referenced talculation in the file successfully
        demonstrated th? abiliP,y of the completely sealed junction boxes
        to withstand postulated accident pressure differentials.       The

I licensee showed the NRC inspection team installation drawings 

        and specifications indicating that top entry conduits were
        sealed.    The identification of the sealant could not be
        confirmed during the inspection: however, after the inspection,
        the utility identified the sealant as Promatec Low Density
        Elastomer (PLDE). This sealant had been qualified as part of
        the mechanical equipment qualification program at RBS. Its use
        to protect electrical components was not addressed in the EQJB.
        This raised a concern on the part of the NRC inspection team
        that the installed sealant may not be qualified for LOCA/HELB
        environments and may allow moisture to reach the Marathon 1600
        tbs housed in junction boxes. Since these tbs are used in
        instrumentation and control circuits at RBS, the effects of
        moisture may be leakage currents in these circuits large enough
        to give misleading indications to the plant operator.      There
                                       _-  _   - _ .
                                                                    __
                                                             ._

______. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ 

       .
                                                                               22
        .
                                                 were no functional performance calculations in ene EQJB since
                                                 RBS assumed the blocks would not be used in a steam environment.
                                                 Since qualification of the Marathon 1600 tbs is dependent on the
                                                 integrity of the seal, the licensee must oemonstrate that PLDE
                                                 is an acceptable sealant for the junction boxes housing tbs. A
                                                 functional performance evaluation of Marathon 1600s will be
                                                 necessary if the terminal blocks are determined to be
                                                 susceptible to a steam / condensate environment.
                                                 This item is considered an Unresolved Item (458/8721-08).
                                         (4) EQJB 211.161, Bisco Scaling Compound
                                                 The NRC inspection team reviewed the file on the Bisco LOCA-Seal
                                                 sealing compound. This compound is part of a SWEC specification
                                                 for nonengineered items, field purchased. The file contained
                                                 Wyle Test Report 17607, Revision A. A qualified life of greater
                                                 than 40 years at 150 F was established. The type test
                                                 environment enveloped the reautred RBS environment. The
                                                 compound was tested in a fitting which was subjected to
                                                 187 Mrads of gamma radiation. The only concern raised with this
                                                 file is that the licensee was not sure exactly where this
                                                 sealing compound is used. The file contained a note that the
                                                 sealant was typically used in fittings (*.d sometimes in junction
                                                 boxes. RBS was able to identify, by the end of the NRC onsite
                                                 inspection, that the sealant observed between cables and conduit
                                                 on the NRC walkdown was not Bisco LOCA-Seal. This file was
                                                 initially reviewed for qualification assuming that the sealant
                     *
                                                 was housed in a fitting.         The NRC inspection team concluded that
                                                 if the sealant is actually installed unrestrained, the
                                                 qualification file would need further data to establish
                                                 qualification of all the additional configurations for which the
                                                 Bisco LOCA-Seal is used.
                                                 GSU responded to the NRC concern by letter No. RBG-27213 to the
                                                 NRC Region IV on December 28, 1987. The Sisco LOCA-Seal used at
                                                 RBS was procured under Specification 211.161, Nonengineered
                                                 Items. Data Sheet No. 1144, Section D, includes a product
                                                 technical description which states that the conduit entrance
                                                 sealing compound is to be used for ASCO solenoid valves
                                                 (Class IE located in a harsh environment) to seal out moisture.
                                                 Also a Babcock and Wilcox basic ceramic fiber is to be used as a
                                                 damming material. The installation drawings which identify the
                                                 devices sealed with BISCO LOCA-Seal are also included in the
                                                 BISCO LOCA-Seal EQJ3. Review of these drawings identified the
                                                 use of the BISCO LOCA-Seal on ASCO solenoid valves and
                                                 thermocouples only. The additional information supplied by GSU
                                                 resolved the NRC inspectors concerns for solenoid valves and
                                                 thermocouples only. Data to establish qualification of
                                             .-.        _ -       ,-       .--              - _ _ - , . -                 - . .-                                                     -

. 

                               23
      other component applications using Bisco LOCA-Seal will be
      reviewed during a subsequent NRC inspection.
      This item is considered an Unresolved Item (458/8721-09).
 (5) EQJB 211.161, Conax Electrical Conductor Seal Assembly
      The NRC inspection team reviewed the file on the Conax
      electrical conductor seal assembly (ECSA). The ECSAs are part
      of SWEC specification for nonengineered items which are field
      purchased. Conax Reports IPS-409 and -411 in the file were used
      to document qualification. The NRC inspection team had
      difficulty with the similarity analysis but was directed to the
      necessary information which verified that the tested and
      installed ECSAs are identical. There was a concern that the
      test profile (14 days) did not envelope the 100-day postaccident
      operating time, and an arrhenius calculation was performed and
      submitted to the NRC inspection team. This calculation was not
      present in the file prior to the inspection, indicating the
      licensee had not adequately addressed the test data for RBS
      application. The calculation indicated the test profile
      enveloped the required profile, only by using an activation
      energy of 3.916 eV for Kapton and polysulfone materials used in
      the construction of the ECSA. When questioned about the use of
      such a high activation energy as 3.916 eV in the calculation,
      the licensee referred to a letter from Conax to SWEC which
      referenced Conax Report IPS-325 from which the data using this
      high activation energy was apparently derived. Data which
      indicates the use of an activation energy of 3.916 eV for an
      ECSA containing materials which have been known to have lower
      activation energies, as documented in prominent test laboratory
      data banks (1.299 eV and 0.84 eV), will require the licensee to
      further review the bases for qualification.
      NUREG-0588, Category I, Section 5, paragraph 1, states that the
      qualification documentation shall verify that c.ach type of
      electrical equipment is qualified for its application and meets
      its seccified performance requirements. The RBS Conax ECSA test
      data had not been evaluated to verify that the ECSA met the
      necessary performance requirements beyond the November 30, 1985,
      deadline.
      This item is considered an apparent violation of 10 CFR 50.49
      (458/8721-03).
 (6) EQJB 241.242, Rockbestos Instrument Cable 300 Volt Firewall III
      (FWIII)
      The inspection team reviewed this file for Rockbestos
      instrumentation cable at RBS. The file contained several of the
                                                                       f

. 

                            24

. 

 latest Rockbestos reports including QR5804, QR5805, and QR6802.
 There were two concerns with this file.
 (a) RBS did not appear to know which formulations of Rockbestos
       they had installed in their plant. The licensee stated
       initially that they had chemically cross-linked as well as
       irradiation cross-linked cables, and they were in the
       process of confirming this. Thus similarity could not be
       conclusively established. After the inspection, the
       licensee was able to provide the NRC inspector with
       information indicating they had Rockbestos KXL760G
       (irradiation XLPE). However, this information was not
       present in the file and required a letter from Rockbestos
       (November 13,1987) to clarify the question.
 (b) A concern arose when the NRC inspection team could not find
       an analysis, regarding functional performance requirements
       for instrumentation circuits involving cable connections to
       components addressed in the file.     The licensee then
       provided a worst case calculation for irradiation
       cross-linked Rockbestos FWIII and Brand Rex Special
       Instrument cable for a typical pressure transmitter and RTD
       circuit at RBS. There were two problems with this
       submittal. First, it didn't account for any chemically
       cross-linked FWIII which may be in instrumentation circuits
       and has lower insulation resistances than the irradiation
       cross-linked FWIII. This concern was resolved when the
       licensee was able to show they.hao no chemically
       cross-linked polyethleyne cables at RBS. Second, the
       calculations were dated October 22, 1987, indicating they
       had been performed the week prior to the NRC inspection.
       The NRC inspection team asked to see any calculations which
       the licensee had in place before this date.     The utility
       responded that no such calculations existed, but
       engineering judgement had been exercised 'n assessing
       applicability of the Rockoestos and Brand Rex cable for
       instrumentation circuits.
       NUREG-0588, Category I, Section 5, paragraph 1, states that
       the qualification documentation shall verify that each type
       of electrical equipment is qualified for its application
       and meets its specified performance requirements. The RBS
       instrumentation cable circuits had not been evaluated to
       verify that they meet the necessary performance
       requirements until after October 22, 1987, beyond the
       November 30, 1985, deadline. Also thu Rockbestos
       Firewall III EQJB files did not contain sufficient
       information to establish that the tested and installed
       specimens were identical or similar.

                                                                          . _ _ ______ _ -___ ____ __ _
 *

( 

                                       25
 .
            The concerns of paragraph 4.i(6)(a) and 4.f(6)(b) above are
            considered an apparent violation of 10 CFR 50.49 (458/8721-02).
      (7) EQJB 242.491, GE Terminal Boards, Model EB-25
            The GE tbs, Component ID IRO*TCA08, documented in this file are
            located in the auxiliary building in environmental
            zone AB-114-5.     The tbs are in the Reactor Core Protection
            system. The test report referenced to demonstrate qualification
            is Southwest Research Institute Report No SWRI-6772-317.
            (a) During the review of the file, it was noted that GE TB
                  qualification for humidity was not established.        The SCEW
                  sheet indicated that tbs were qualified to 98 percent
                  relative humidity.      In reviewing this test report no
                  testing for relative humidity was established.
                  GSU personnel stated that qualification documentation was
                  available to establish qualification of the EB-25 tbs to
                  the specified values per NUREG-0588, Category I and they
                  would be included in the EQJB.
            (b) During the equipment walkdown, it was determined that
                  Marathon tbs are also installed in the terminal cabinet
                  referenced in this EQJB. When GSU was questioned
                  concerning qualification of the Marathon tbs, they stated
                  the tbs were qualified using Wyle Test Report
                  No. NEQ-45603-1 and traceability to their qualification
                  will be included in the EQJB by E&DCR No. C-23.135.
            Pending update of EQJB 242.491, as described in
            paragraphs 4.f(7)(a) and 4.f(7)(b) above, this is considered an
           Open Item (458/8721-11).
   g. Review of IE Information Notices (IN) and Bulletins (IEB)
      The NRC inspector reviewed Nuclear Licensing Procedure NLP-10-006,
      Revision 1, dated October 30, 1986, titled, "Processing and Tracking
      of Regulatory and Industry Correspondence." The purpose of this
      procedure is to provide a systematic method of processing and
      tracking licensing correspondence from the Nuclear Regulatory
      Commission such as IEBs, ins, inspection reports, generic letters,
      and requests for additional information.
      In order to assess the effectiveness of RBS program, the inspector
      selected ins relating to EQ issues and reviewed responses and actions
      for each IN. The inspector determined that appropriate actions were
      taken by RBS for each IN and that the implementation of their program
      as stated in the above procedure was followed.
      No violations or deviations were identified.

   _ . _ .    __ ._                                       ._.      __.   _ ._.  _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ -_
 .
                                                   26
 '
                                                                                                                   I
                                                                                                                   l
           h.       Plant Physical Inspection
                    The NRC inspection team, with the rcquired tagging out of operation                            i
                    selected equipment and components by the licensee, walked down and
                    physically inspected 38 EQ components / equipment at RBS. The
                    inspection team examined attributes and characteristics such as
                    mounting configurations, orientation, interfaces, ambient
                    environment, and physical condition; the team also verified
                    traceability of equipment identified in the EQJBs in the EQF by model
                    and serial numbers.
                    During the NRC walkdown inspection, the NRC inspection team
                    identified the concerns described below:
                    (1) EQJB SRN S03, Limitorque Motor Operators, Outside Containment,
                         Unidentified Taped Splice
                         During the NRC walkdown inspection, Limitorque valve operator
                         IE22*MOVF001 was found to have taped in-line butt splices in the
                         motor leads. Since there was no record of the splices in the EQ
                         documentation defining a change to the tested configuration, the
                         splice type and qualification status were indeterminate.
                         The NRC inspectors were provided Procedure CMP-1277, dated
                         December 17, 1984, entitled "Low, Medium, and High Voltage Power

i Cable Splicing, and Termination." It was the NRC inspection 

                         teams' understanding that splices were to be installed to the
                         requirements of this procedure after the initial startup of RBS.

( Okonite Report NGRN-3, dated June 23, 1980, was used as a basis l of qualification for splices included in CMP-1277. The test l report was documented under SDDF 6221.161-997-009. Neither of ' 

                         these documents was in the EQF during the time of the NRC
                         inspection.
                         It was found that CMP-1277 had not been released for use by QA

l because of procedural inadequacies; alternately, splices were ! made in accordance with Specification 248, Revision 9, 

                         Appendix J.    The qualification status of the identified splices
                         remained indeterminate since it was not known if the splices
                         were identical or similar to CMP-1277 splices.

l 

                         Prior to the end of the NRC inspection, the licensee performed

! an analysis which showed similarity between the tested splices 

                         and those identified during the NRC inspection, for V-shaped

l splices which were identified by the NRC inspection team in l operator ICCP*MOV144 (refer to paragraph 4.f(2)(b) of this 

                         report). The analysis was added to the Okonite tape splice

l EQJB 211.161. A note was also added to the Limitorque operator l SCEW sheets, referencing the appropriate EQJB for electrical 

                         interfaces. A 100 percent walkdown was also performed by the
                         licensee to verify splice acceptability.

l 1 i 

 .
                                   27
  .
          Also, Modification Report (MR) 86-0395 was included in a
          supplemental EQJB to the Limitorque operator EQJB SRN S03 in the
          EQF. This supplement had not been provided for review by the

< 

          NRC inspection team. The MR, initiated on March 7, 1987, was
          not approved at the time of the NRC inspection.     Its purpose was
          to replace operator motors that had Class B insulation with
          equivalent motors that have RH insulation in order to extend the
          operator life. The replacement motor leads were spliced with
          the Okonite splices qualified by Okonite Report NGRM-3. The MR
          required splices to be made in accordance with
          Specification 248, Revision 9, Appendix J.
         .The concerns described above are considered part of the apparent
          violation of 10 CFR 50.49 identified in paragraph 4.f(2) of this
          report.   (482/8721-01)
    (2) SNR 224150 and 228212, Limitorque Motor Operators, Outside
          Containment, Blind Barrel Crimped Connector Splices for Dual
          Voltage Application
          During the walkdown inspection, Limitorque valve operators
          IDFR*MOV146 and ISWP*MOV510 were found to have blind barrel
          crimped connector splices in the motor leads. The operators
          were equipped with 230/460 volt Reliance motors with Class B
          insulation. These splices are factory installed during assembly
          of the Limitorque motor operator valve actuator and provide a
          dual voltage motor application which are procured for 460 Vac
          service. This is the manufacturers. generic configuration for
          all operators equipped with dual voltage motors supplied by
          Limitorque. Qualification test reports contained in the EQJBs
          for the operators did not inc1Me documentation to support
          qualification of these splices.
          GSU responded to the above NRC concerns by letter No. RBG-27213
          to the NRC Region IV un Decuoer 28, 1987. Limitorque has
          subjected the dual voltage motor design to environmental
          qualification testing on four separate occasions.      Limitorque
          has tested dual voltage motors with Reliance Class H, Type RH
          insulation (Test Report No. 600376A), and with Reliance Class B
          insulation (Test Report No. B0003). Limotorque has also tested
          dual voltage moters with Reliance Class B insulation (Test
          Report No. F-C3271); and with Class H, Type Rad H insulation
          (Test Report No. 600198). A quality assurance audit of
          Limotorque's facilities in Lynchburg, Virginia, which was
          conducted by another licensee, included within its scope a
          review of purchase order records for these crimp connector type
          splices used by Limitorque. The purchase records at Limitorque
          indicated a purchase of 112,000 Thomas & Betts RC-6 splices
          between April 1967 and May 1979; 240,000 Thomas & Betts RB-4
          splices between January 1971 and June 1973; and 30,000 Thomas &
          Betts RB-44 splices between June 1984 and June 1987. GSU

 .
 '
                                            28
                  believes the tests cited above included these crimp connector
                  splices manufactured by Thomas-& Betts, even though
                  documentation to verify this conclusion is not available.
    .
                  A qualification test for Thomas & Betts RB-4 and RB-6 nylon
                  crimp connector splices used in dual voltage Limitorque
                  operators was being performed by Wyle Laboratories. An 8 year
                  screen qualification test was completed successfully in late
                  October 1987 with a completed test summary. A 40 year
                  qualification test is being conducted and completion and
                  issuance of a final test report is scheduled for early 1988.
                  The results of the test program will be required to be
                  incorporated in the EQJBs to document the qualification when the
                  final test report is issued. At this time the type test results
                  are preliminary and supporting analysis to show similarity to
                  the equipment tested and environment installed at RBS has not
                  been established.
                  NUREG-0588, Revision 1, Category 1, paragraph 5, requires that
                  cualification documentation shall verify that each type of
                  electrical equipment is qualified for its application and meets
                  its specified performance requirements. The basis of
                  qualification is required to be explained to show the
                  relationship of all facets of proof needed to support adequacy
                  of the complete equipment. Data used to demonstrate the

a 

                  qualification of the equipment shall be pertinent to the
                  application and organized in an auditable form. The
                 documentation is required to include sufficient information to
                  address those items identified in NUREG-0588, Appendix E, which
                  includes splices (item 16).

I 

                 The NRC item described above is co151dered an Unresolved Item
                  (458/8721-05).
   5. Unresolved Items
      Unresolved items are matters about which more information is required in
      order to ascertain whether they are acceptable items, items of
      noncompliance, or deviations. Unresolved items identified during the
      inspection are discussed in paragraphs 4.b(1)(b), 4.c, 4.f(1)(a),
      4.f(1)(b), 4.f(1)(c), 4.f(3), 4.f(4) and 4.h(2).
   6. Exit Interview
      An exit interview was conducteo on December 12, 1987, at the conclusion of
      the onsite inspection, with GSU in which the scope of the inspection and
      findings were summarized.

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      a           NUREG-0588, Category I, E0JB 241.242 intheJQFforRockbestos               ar :x'e, did not adequately
      *
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       ,
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        ,
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   ,
                 conductor seal assembly (ECSA), did not adequately support qualification
     5
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                                                                                                         The EOF did not verify
     ,
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                 NUREG-0588, Category I, the EQJB B0P-Limitorque and EQJB SRN 503 for
    *            Limitorque motor operators, did not adequately support qualification
     3           (1) in that the terminal block (TB) types used within the operators were
                 not identified in the documentation file: (2) no methodology to establish
     *           qualification of these TB's were in the documentation file; and (3) a
     ,
                 similarity analysis, to demonstrate qualification of tbs used in operators
                 represented by the EQJB SRN 503 file, was not available [ Appendix B,
      '
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   '
                NUREG-0588, Category 1, EQ Job Book (E0JB) 211.161 in the equipment
  4             qualification file (EQF) for T95 and 35 tape splices, used in Limitorque
          ~~
                SMB/SB motor operators inside and outside containment, did not adequately
    * {-
                                                                                                                                     -
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                splice and the installed V-shape splice configurations was not
                                                                                                                        *     -
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                established; and (2) the insulation resistance data take.n._dur.i m the                                              -
                 in-line splice type test were not availa Mbe'EQT and consequently
                                                                            '
   '                                                                           . ,
    af-         not reviewed for impact with regards toVfunctional performance
                                                                        -
                                                                                                                                     -
    , {          requirements of control circuits at RBS.
   10
    11
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    14
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     4                    _
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             2                                                                                     U.S. NUCLE AR REGULATORY COMMISSR

                                                         .                     -
    In Reply Refer To:
    Docket: 50-458/87-21
    Gulf States Utilities
    ATTN: Mr. James C. Deddens
               Senior Vice President, (RBNG)
    P.O. Box 220
    St. Francisv111e, Louisiana 70775
    Gentlemen:
    SUBJECT:        EQUIPMENT QUALIFICATION INSPECTION - RIVER BEND STATION
    This refers to the first round special team inspection to review compliance
    with 10 CFR 50.49, of activities authorized by License No. NPF-47, conducted by
    Mr. A. R. Johnson and other NRC representatives, onsite during the period of
    November 2-6, 1987, and subsequently at the NRC Region IV office until
    December 18, 1987, concerning the River Bend Station (RBS). The team's
    findings were discussed with members of your staff at the conclusion of the
    onsite inspection on November 6,1987.
    Areas examined during the inspection included your implementation of a program
    for establishing and maintaining the qualification of electric equipment within
    the scope of 10 CFR 50.49. In preparation for this inspection, the NRC team
    included reviews and evaluations of your implementation of equipment
    qualification (EQ) corrective action commitments identified in Safety
    Evaluation Report (SER) NUREG-0989 (May 1984) and SER Supplements 3 and 5
    (August and Novcmber 1965). These documents provide the NRC staff acceptance
    of justifications for irterim operation (J10s) which you provided prior to the
    Novan.ber 30, 1985, deadiine for the completion of EQ as defined by
    10 CFR 50.49.
    Within these areas, the inspection consisted of the examination of selected
    procedtres and records, interviews with personnel, and observations by the NRC
    inspectors. The inspectior. firdings are documented in the enclosed inspection
    report.
    During this inspection, it was found that certain of your activities were in
    violation of hRC requirements.          Consequently, you are required to respond to
    these violations, in writing, in accordance with provisions of Section 2.201 of
    the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations.
    Your response should be based on the specifics contained in the Notice of
    Violation enclosed with this letter.
    Five unresolved items are identified in paragraphs 4.c, 4.f(1)(a),
    t..f(1)(b), 4.f(1)(c), 4.f(3), 4.f(4), and 4.h(2) of the enclosed inspection
    report.                                                                      7
                                                                                 D
    DRS/PSS             AC:PSS           0/DRS               C:0RP/                D:DRP             Reconcur
    ARJohnson;dp         REIreland       JLMilhoan           00Chrber..fr LJCallan REIreland
       / /88              / /88             / /88              / /88                   / /88           / /88
                                                           grg o cc v72.
    NRR:0RIS:SPS/C
    UPotapovs
    4/6/88
    By tel call with R. Wilson NRR:0RIS:SPS

-. _ , _ . - - 

                                   ___ _          . . _ _        - _ - _ _ . .       -     . . _ _ _     . , - _. .

  In Reply Refer To:
  Docket:   50-458/87-21
  Gulf States Utilities
  ATTN: Mr. James C. Deddens
          Senior Vice President, (RBNG)
  P.O. Box 220
  St. Francisville, Louisiana 70775
  Gentlemen:
  SUBJECT:   EQUIDMENT QUALIFICATION INSPECTION - RIVER BEND STATION
  This refers to the first round special team inspection to review compliance
  with 10 CFR 50.49, of activities authorized by License No. NPF-47, conducted by
  Mr. A. R. Johnson and other NRC representatives, onsite during the period of
  November 2-6, 1987, and subsequently at the NRC Region IV office until
  Decemt,e r 18, 1987, cont -ning the River Bend Station (RBS). The team's
  findings were discussed with members of your staff at the conclusion of the
  onsite inspection on November 6, 1987.
  Areas examined during the inspection included your implementation of a program
  for establishing and maintaining the qualification of electric equipment within
  the scope of 10 CFR 50.49. In preparation for this inspection, the       NRC team
  included reviews and evaluations of your implementation of equipment
  qualification (EQ) corrective action commitments identified in Safety
  Evaluation Report (SER) NUREG-0989 (May 1984) and SER Supplements 3 and 5
  (August and November 1985). These documents provide the NRC staff acceptance
  of justifications for interim operation (JI0s) which you provided prior to th:
  November 30, 1985, deadline for the completion of EQ as defined by
  10 CFR 50.49.
  Within these areas, the inspection consisted of the examination of selected
  procedures and records, interviews with personnel, and observations by the NRC
  inspectors.    The inspection fIrdings are documented in the enclosed inspection
  report.
  During this inspectior., it was found that certain of your activities were in
  violation of NRC requirements. Consequently, :ou are required to respond to
  these violations, in yriting, in accordance with provisions of Section 2.201 of
  the NRC's "Rules of Practice," Part 2, Title 10 Code of Federal Regulations.
  Your response should be based on the specifics contained in the Notice of
  Violation enclosed with this letter.
  Six unresolved items are identified in paragraphs 4.b(1)(b), 4.c, 4.f(1)(a),
  4.f(1)(b), 4.f(1)(c), 4.f(3), 4.f(4), and 4.h(2) of the enclosed inspecticn
  report.
                                  '
  DRS/PSS          AC:P5S                         C:DRP/A         D:DRP      Reconcur
  ARJohnson p      REIreland      MJL lhoan       DDChamberlain LJCallan RElreland
 A /5/88           j/,f/88          1/ /88          / /88            / /88      / /88
     a , 3 2 n s n/c,
     Q , Toto p o %
      4/u/%

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