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{{Adams
#REDIRECT [[IR 05000530/1985020]]
| number = ML20137M835
| issue date = 08/28/1985
| title = Insp Rept 50-530/85-20 on 850729-0802 & 12-16.No Violation or Deviation Noted.Major Areas Inspected:Activities Re Instrument Components & Sys
| author name = Miller L, Wagner W, Young T
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
| addressee name =
| addressee affiliation =
| docket = 05000530
| license number =
| contact person =
| document report number = 50-530-85-20, NUDOCS 8509130384
| package number = ML20137M833
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 6
}}
See also: [[see also::IR 05000729/2008002]]
 
=Text=
{{#Wiki_filter:7
            .
      .
                                                      U. S. NUCLEAR REGULATORY COMMISSION
                                                                        REGION V
              Report No.                          50-530/85-20
              Docket No.                          50-530
              Construction Permit No.                      CPPR-143
              Licensee:                          Arizona Nuclear Power Project
                                                    P. 0. Box 52034
                                        '
                                                    Phoenix, Arizona 85072-2034
              Facility Name:                      Pal"o' Verde Nuclear Generating Station - Unit 3
              Inspection at:                      . Pal'o' Verde' Site, Wintersburg, Arizona
              Inspection conducted:                              July 29.- August 2 and August 12-16, 1985
              Inspectori                                                      .
                                                                                      .
                                                    Qagner,' Reptor Ins      fee    r
                                                                                        /            Date Signed
              Approved By:                              ~^
                                                                                t
                                                                                      .              M
                                          T. Young, Jr.', Chyf                                      Date Signed
                                          Engineering Section
                                                                                        .
                                                                                                              #
                                                                                                                $
                                            . F.      iller, 'Jr. // Chief .                '
                                                                                                      Date Signed
                                          Reactor Projects Fection 2              '
              Summary:
              Inspection on July 29 - August 2 and August 12-16, 1985
              (Report No. 50-530/85-20)
              Areas Inspected: Routine unannounced inspection by a regional based inspector
              of activities associated with instrument components and systems. The
              inspection involved 75 inspector-hours by one NRC inspector. During this
              inspection, Inspection Procedure 52053 was covered.
              Results: No violations of NRC. requirements or deviations were identified.
                  8509130384 850820
                    PDR                ADOCK 0 % y0
                    O
L_________-_____        _ _ _ _ - - _ _      __ .          __    -                            - -
 
                                                                                          l
    ..
  %
                                                    DETAILS
      1.  Persons Contacted
          a.      Arizona Nuclear Power Project (ANPP)
s
                *D.    B.' Karner, Assistant Vice President, Nuclear Production
                *W.    E. Ide, Director,' Corporate QA/QC'
                *C. N. Russo, Manager, Quality Audits and Monitoring
                *S. G. Penick, Quality Monitoring Supervisor
                *R. M. Butlar, Director, Technical Services
                *J. R. Bynum, Plant Manager
                    J. D. Bayless, Quality Assurance Engineer
                    W. Montefour, Quality Assurance Engineer
          b.      Bechtel Power Corporation (Bechtel).                                  ,
                *G. A. Hierzer, Field Construction Manager
                *T.    L. Horst, Project Field Engineer
                *H. A. Hear, Assistant Project QC Engineer-
                *R. E. Vote, Assistant Project QA Manager
                    K. N. Bethell, Instrument Area Field Engineer
                    R. L. Treaster, Shipping and Receiving Supervisor
                    L. R. Eton,. Calibration Lab Engineer-                                .
                                                                                          ,
                    J. Yoshida, Mechanical Engineer
                    R. Kumbla, Lead F,ield. Engineer
                                                                                          '
                  iT.. Weber, Lead-Mechanical'Engi,neer
          * Denotes those attendin'gethe exit interview on August 15, 1985.
      2.  Ins'trument Component      t
                                          and Systems      Work Observation
                                                              '
          a.    ' Receiving Inspection                _
                                            '
                    No safety-related iastrument components were received during this
                                                                          -
                    inspection'. . The. inspector conducted a' detailed inspectica of
                    receiving and storage activities during March 1981; this is
                                              ~
                  -documented in NRC Report Nos. 50-529/85-13 and 50-530/85-06.~ To
                    assure that~the administrative controls were currently being
                    affectively implemente'd the; inspector observed receiving inspection
                    activities. . Components were'being properly identified,
                    nonconforming components ccutrolled, and an adequate number of
                    qualified personnel were available- to perform the receiving
                    inspection functicn. The inspector-reviewed the quality records for.
                                                                        -
                    evidence that receiving inspection was performed for the installed
                    instrument components identified in.Section 2.c of this report. The    '
                    folle.ing Material' Receiving Reports (MRRs) were reviewed.
                                                                            -
                    MRR No.                  Instrument Component
                  '183566                    LT-1124B
                                                                                          '
                  .161785                    PT-352C
                    166567                    Instrument Racks SBA-A01 and SBB-A01
                    168416                    Instrument Racks SBC-A01 and SBD-A01
                                                          .
                                                                w
 
                                                                                    1
                                                    2
  .
.
                Receiving inspections was performed for damage, storage
                classification, identification and marking, and documents received.
                A nonconformance report was written on MRRs 116567 and 168416 (NCR
                No. 1203) for documentation not received. This NCR was subsequently
                closed upon receipt of the documentation.
        b.    Storage
                None of the type of instrumentation selected for this inspe tion
                were located in storage. However, observation and evaluation of
                storage activities for. Other safety-related instrument components
                revealed the-following:
                (1) Instruments are stored in proper storage level designations.
                (2) Components are properly identified.
                (3) Storage conditions (temperature, humidity, cleanliness, etc.)
                      are controlled and monitored.
                (4) Nonconforming items are identified and segregated.
                (5) An adequate number of qualified personnel are available to
                      perform.the; required storage function.
        c.    Completed Work
                The following installed instruments were selected for inspection:
                Instrument                Transmitter
                  System        ^
                                            Number        Description    Channel
          -
                            ,
                                    n '
              i Reactor Trip ;
                                          J-RCN-PT-101A    Pressurizer        A
      ,,        (SCRAM)''~              ,J-RCB-PT-101B    Pressure          B
                Initiai.iori . i"
                                      '
                                          J-RCA-PT-102A                      A
        c!                                J-RCD-PT-102D
                        '          '
                ,
                      '
                                                                              D
                              ,,
                                          J-RCD-PT-101D                      D
              , Engineered                J-HCA-PT-352A    Containment        A
            . Safety-Featurese            J-HCB-PT-352B    Pressure          B
              . Actuation _      ~
                                          J-HCC-PT-352C                      C
          -
                                        . J-HCD-PT,-352D                      D
      ^
    "
                Display                    J-SGB-LT-1124B  Steam Generator    B
                Instrumentation                            No.2 Level
                              1-
 
                  ,                                                                          ,
                    *f
                    .
  .
                                                  ,
                                                        3
.                          ,
                                    <
                                                      s
                                        ,
      '
            Th$-location, configuration.'and installation of these instruments
            were in accordance with the following approved design drawings
            utilized during this inspection:
            Combustion
            Engineering                          Revision
            Drawing No.                            No.            Title
            E-14272-510-006                          3        Transmitter Configuration
                                                              for Mounting Bracket
            E-14273-510-011                        5        Instrument Rack Assembly
                                                              and Details
            Bechtel
            Drawing No.
            13-J-ZZS-167                            6        Instrument Mounting Assembly
                                                              Rosemount TransmittLr
            13-J-01D-105                            5        Auxiliary Building Isometric
            13-J-01D-106                            4        Sensing Lines
            13-J-03D-117                            5        Containment Building
            13-J-01D-133                            4        Isometric Sensing
            13-J-01D-138                            4        Lines
            13-J-01D-140                            4
            13-J-01D-116                            4
            13-J-01D-103                            3        Auxiliary Building
            13-J-01D-104                            3        Isometric Sensing Lines
            13-J-ZAF-013                            6        Auxiliary Building
            13-J-ZAF-013                            5=        Instrument Location Plan
            13-J-ZCF-004                            8        Containment Building
            13-J-ZCF-007                            6        Instrument Location Plan
            13-J-ZCF-008                            7
            Inspection of the installed instruments' revealed the following:
            (1) A11' instruments were as specified on the design drawings.
                                                                                        s
            (2) Instruments were correctly and permanently identified.
            (3) Instruments were not exposed to potential hazards such as high-
                    pressure piping or flammable material.
            (4)= Physical and electrical independence between redundant parts
                    were properly maintained.
            Two of the instruments selected for this inspection were recently
            removed. Pressure transmitter number RCA-PT-101A was removed for
            rework in accordance with NCR No. JC-1065. Review of this NCR
                                            *
            ,(    -
                                ,                                                          r
                      .
                                      , ,            9 '
                                          .                o
    ,, -                ,        ' 4 i #.
                                \    *          #
                                                      %
                                              ~
    . ; l__                  *n  .* A >          '
                                                        l  *
 
                                            .                                    _ _
                          ,
                                                      g.
      .
    "
  o
              revealed that the instrument was returned to the vendor for
              recertification in response to a 10 CFR Part 21 report. Pressure
              transmitter RCD-PT-101D was removed as a result of a Material Change
              Notice (MCN) No. 60196-J. The MCN is the controlling mechanism
              utilized to transfer material and equipment from one unit to
              another.      In this instance MCN-60196-J was issued to obtain a
              replacement pressure transmitter from Unit 3 for use in Unit 2.
        d.    Construction Testing and Calibration
              This activity is no longer being performed by construction. All
              testing and calibration activities are done by the startup group.
        e.    Instrument Air System
              The instrument air system is not safety-related; however, it is
              important to safety because instrument air is used for
              safety-related control components. The major component of the
              instrument air system selected for inspection was an air compressor
              identified as IAN-COIC, R2T. The inspector utilized the following
              design / installation drawings to verify proper location and
'
              installation of the air compressor:
              (1) Drawing No. 13-M-IAP-001 Revision 13, "P&ID Diagram Instrument
                    and Service Air System"
              (2) Drawing No. 13-P-ZTL-401 Revision 5, " Equipment Locations
                    Turbine Building Plan"
                                                                                      ,
              (3) Drawing No. 13-C-ZTS-101 Revision 22, " Turbine Building
                    Foundation Mat Plan Area TIA, B&C"
              The inspector observed that the air compressor was correctly and
              permanently identified. In addition, the inspector was able to
              verify correct location and configuration of the air compressor,
              including anchor bolt locations, by performing physical measurements
              within the Turbine Building. The air compressor was correctly and
              permanently identified.
'
              The inspector reviewed the inspection reports, called CIPs
              (Construction Inspection Planning) associated with installation of
              the air compressor. The CIP of May 21, 1981, was for inspection of
              equipment installation which covered installation of anchor bolts,
              and equipment location and orientation. Angular alignment and
i            offset (parallel) alignment was performed and documented on CIP of
              August 25, 1981. An additional CIP was initiated on May 17, 1984,
              for equipment inspection as a result of internal corrosion being
              discovered in the Unit.2 air compressors. CIP No. 156.0-301 was
              written for. inspection of Unit 3 air compressors for evidence of
              corrosion; no' corrosion was. discovered.
              In addition ~to the above equipment inspection, the inspector            !
              performed a lwalkdown inspection of approximately 45 feet of              .
            : instrument air; tubing. This activity was conducted from header          '
          .                          ,
                    *
                                      a
                                                        4
                                                  &
                                          4    *
2
.                                                  v
t
                                        .I    .
                        ,
 
                                                                                        ,
                                                5
    *
  .
..
                (Root) valve V-872 to safety-related valves UY648 (Solenoid) and
                UV648 (Control) located in the safety injection system. The
                following drawings and specifications were utilized for verification
                of the valves and associated air lines:
                (4) Drawing No. 13-M-SIP-002 Revision 11, " Safety Injection and
                      Shutdown Cooling System"
                                        ~
                (5) Drawing No. 13-P-SIF-103 Revision 17, " Containment Building
                      Isometric-Safety Injection System"
                (6) Drawing No. 13-P-IAF-177 Revision 2, " Containment Building
                      . Isometric-Service Air System Instrument Air"
                                              ,
                (7) Drawing No. 13-J-100.099 Revision 7, " Instrument Installation
                      Notes - Pneumatic"
              '(8)-DrawingNo.13'-J-ZZS-092 Revision 10,"Instrumentsand
                      Controls,' General Installation Notes"
                (9) Specification'No. 13-JM-702 Revision 7, " Installation
                -
                      Specification for~ Instrumentation and Controls"
                . Instrument air tubing is' field routed which means that the tubing is
                installed from' support to-support at the discretion of the field
                engineer as long as the' installation is in accordance with the
                requirements contained in the above drawings and specifications.
                Attributes verified were minimum length of the unistrut supports,
                embedment. length, minimum weld length, and where applicable, the
                anchor bolt spacing distance. The safety-related valves were
                correctly identified and located in accordance with the construction
                drawings.
                No violations of NRC requirements or deviations were identified.
      3. Exit Meeting
          The inspector met with licensee management representatives denoted in
          paragraph 1 on August 15, 1985. The scope of the inspection and the
          inspector's findings as noted in this report. were discussed.
          ,
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