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{{Adams
#REDIRECT [[IR 05000458/1985066]]
| number = ML20137A279
| issue date = 11/13/1985
| title = Insp Rept 50-458/85-66 on 850930-1004.Violations Noted: Failure to Update Procedures After Issuance of Temporary Change Notices & Issuance of Temporary Change Notice After Final Approval
| author name = Bennett W, Jaudon J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee name =
| addressee affiliation =
| docket = 05000458
| license number =
| contact person =
| document report number = 50-458-85-66, IEB-82-03, IEB-82-3, NUDOCS 8511250453
| package number = ML20137A234
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 4
}}
See also: [[see also::IR 05000930/2010004]]
 
=Text=
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: ) -.
                                '
                                                                    APPENDIX B
                                                    U.S. NUCLEAR REGULATORY C0f71ISSION
                                                                      REGION IV
                          NRC Inspection Report: 50-458/85-66                  License: NPF-40
                          Docket: 50-458
          '
>
                ,
                          Licensee:      -Gulf States Utilites
;                                          P.-0. Box 2951
        '
                                            Beaumont, Texas 77704
        '
                          Facility Na'me: ' diver Bend Station -
  '
                        ' Inspection At: River Bend Site, St. Francisville, Louisiana
                          Inspection Conducted: September 30-October 4,1985
                          , Inspector:                      A            M                      /
                                        WW./R. Aenn9(t, Project Engineer, Project              Date
                                        ,
                                              Section A, Reactor Projects Branch
                                      ,
                          . Approved:                      o2      .      h                    a        O
                                            J.p. /auc) tin, Chief, Project Section A          Date              ,
          >
                                            LReac' tor [ Projects Branch
                                                                                          ,
                          . Inspection Sumary
            >            . Inspection Conducted September 30-October 4,1985 [ Report 50-458/8566)
x
                          Areas Inspected:    Routine, unan'nounced inspection of licensee identified'
                          deficiency reports, 10 CFR 50.55(e), IE Bulletin followup,-and operating.              ..
                          procedures. The inspection involved 37_ inspector-hours onsite by'one.NRC        >
n                        inspector.
        ,          ,      Results: Within the three areas inspected, three. violations were identified
                          (failure to update procedures after issuance of'three TCNs, issuance of a TCN
                        - after final approtal and failure to properly prepare TCNs, paragraph 5).
                                                                                                        ,
                                      -
                      0511250h53 851114                                                                        -
                      PDR      ADOCK 05000458
                      O                      PDR
                                  -,.
 
  .
                                                  2
                                              DETAILS
        1.  Personnel Contacted
          *T. L. Crouse, Manager - Quality Assurance (QA)
                    .
          *J. C. Deddens, Vice President
          *A.,O. Fredieu, Assistant Operations Supervisor
          *D. R. Gipson, Assistant Plant Manager
          *P. D. Graham, Assistant Plant Manager
          *B. E. Hey, . Engineer-Licensing
            G. R. Kimmell, Supervisor, Operations QA
          *G.  V. King, Plant Services Supervisor
          *
            J. Miller, Senior Nuclear Engineer, Nuclear Plant Engineering (NUPE)
            J. E. Spivey, Operations QA Engineer
          *R.  B. Stafford, Director Quality Services
          *P. F. Tomlinson, Director Operations QA
            W. Trudell, Senior Reactor Operator
          *J. A. Wright, NUPE Supervisor
            The~NRC inspector also contacted other site personnel including
            administrative, clerical, operations, and testing personnel.
          * Denotes those attending the exit interview conducted on October 4, 1985.
        2.  Licensee Action on Previous Inspection Findings
            a.    (Closed) Violation (458/8542-01).  Control of Temporary Alterations.
                  Corrective action included deleting the option of not hanging
                  temporary alteration tags if they were required for less than one
                  work shift.    The NRC inspector reviewed the temporary alterations log
'                  and determined that the procedure for temporary alterations is being
                  implemented properly.
                -This item is considered closed,
            b.    (Closed) Open Item (458/8542-02) Implementation of a Spare-Lead
                  Identification System.
                  All spare leads in panels in the main control' room have been wrapped
                  and tied back. Maintenance work requests have been initiated to wrap
                  and tie back spare leads in the rest of the plant.
                  This item is considered closed.
            c.    (Closed) Open Item (458/8432-03) Filling ana Venting Procedures
                  The NRC inspector reviewed a sample of the syctem operating
                  procedures and determined that instructions fm filling and venting
b  ___
 
                                                                  ,
                                                                    !
        .
          <                                        .
      ,
                                                      3-      ,
                                                                                -
                                                                                              '
    {
                                                                '
                                                                              ~
                      of systems related to safety.have been incorporated into,the system
                      operating procedures.
                      This item is considered closed.
                Licensee Identified Deficiency Reports (DRs), 10 CFR 50.55(e)
                                              ~
            3 .'
                                                                                              >
                The purpose of this portion of the inspection was to determine the
                adequacy of corrective actions taken by the licensee on construction
                deficiencies identified to the NRC pursuant to the requirements of
                10 CFR'50.55(e).
                The NRC inspector reviewed the following " Reportable" DR and it is
                considered closed:
                      DR        SHORT TITLE                INITIAL        GSU FINAL
                    NUMBER        OR SUBJECT            NOTIFICATION    REPORT LETTER
                    280      Loss of Torque of            07/23/85        RBG 21683-07/24/85
                              Reliance Rotors in
                              Motor-0perated Valves
                              (MOVs)
                The NRC inspector determined that the deficiency was properly determined
                to be reportable and that all required reports were made within the
                appropriate time and contained all required information. The licensee
                performed an evaluation of the deficiency. Corrective action consisted of
                making changes to emergency operating procedures relative to these MOVs.
                These changes are specified in the operating license for River Bend as
                License Condition 2.b of Attachment 1. The NRC inspector reviewed the
                changes to the emergency operating procedures and License Condition 2.b is
                considered to be completed satisfactorily.
                No violations or deviations were identified in this portion of the
                inspection.
            4.  IE Bulletin Followup
                The purpose of this portion of the inspection was to determine the status
                of IE Bulletins.
                a.  IE Bulletin 82-03 and Revision 1 - Stress Corrosion Cracking in
                      Thick-Wall, Large Diameter, St.'.inless Steel, Recirculation System
                      Piping at BWR Plants.
                      Item - A plant reported. visually detectable leakage during
''
                      hydrostatic testing of recirculation system piping.    Visual
                      examination revealed pin-hole leaks and cracks in piping which had
                      been successfully ultrasonically tested 9 months previously. A
                      modified ultrasonic test verified these defects and revealed
                      additional defects in that piping.
L.,.
 
  , , .
      , ..n
  '
                                                    4
h
r-
"
                    Findings - The licensee identified that the only coolant pressure
                    boundary piping which does not conform to NUREG 0313 Revision 1 is
                    small diameter instrument piping. Analysis shows that the
                    nonconforming piping will not be exposed to temperatures above 200*F,
                    which is the threshold for intergranular stress corrosion cracking as
                    stated in Reg. Guide 1.44, for more than 1% of expected plant life.
                    This bulletin is considered closed.
            5. Operating Procedures
              The objective of this portion of the inspection was to confirm that the
              plant operating procedures are prepared to control safety-related
              operations within the applicable regulatory requirements.
              The NRC inspector sampled system operating procedures specifically to
              determine if filling and venting instructions were incorporated in the
              procedures. River Bend Procedure ADM-0003 requires that a procedure
              revision be initiated when three TCNs are outstanding against a procedure.
              Eight of the system operating procedures reviewed (50Ps-2, -16, -18, -41,
              -42, -48, -53, and -90) had more than 3 TCNs, which required a permanent
              procedure change, outstanding. S0P-90, " Reactor Water Cleanup System,"
              Revision 1, dated May'13, 1985, had 12 outstanding TCNS. Six of the eight
              S0Ps, were in various stages of procedure revision, however, the revision
              to S0P-90 only. incorporated 6 of the 12 outstanding TCNs. This is an
              apparent violation (458/8566-01). The NRC inspector found several
              instances (50Ps-35, -42, -48,- and -49) wherein TCNs were issued which did
t              not incorporate previously approved TCNs to the same pages. This resulted
.
'
              in two different approved changes to the same page. This is an apparent
              violation (458/8566-02). The NRC inspector found one instance
              (TCN 85-1550 to S0P-0035) where two pages of a TCH were removed and the
              numbers of thez remaining pa'ges changed after the TCN was approved. This
              change was apparently accomplished without the knowledge of the originator
              or any of the approving personnel. 'This is also an apparent violation
                                                      .
              (458/8566-03).
              No other violations or deviations were identified in this portion of the
              inspection.
              Exit Interview
                                                                          ~
            6.
!
              An exit interview was held on October 4, 1985, with the personnel denoted
              in paragraph 1 of this report. The NRC senior resident inspector also
              attended this meeting. At this meeting, the scope of the inspection and
              the findings were summarized.
,
}}

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