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{{Adams
#REDIRECT [[IR 05000336/1985018]]
| number = ML20127E524
| issue date = 05/29/1985
| title = Insp Rept 50-336/85-18 on 850429-0503.No Violation Noted. Major Areas Inspected:Areas of Inservice Insp Program Activities,Including Ultrasonic Exam of Piping & Eddy Current Test of Steam Generator Tubes & Sleeves
| author name = Gray E, Wiggins J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| addressee name =
| addressee affiliation =
| docket = 05000336
| license number =
| contact person =
| document report number = 50-336-85-18, NUDOCS 8506240575
| package number = ML20127E492
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 5
}}
See also: [[see also::IR 05000429/2005003]]
 
=Text=
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                                                U.S. NUCLEAR REGULATORY COMMISSION
                                                                      REGION I
              Report No.        50-336/85-18
              Docket No.        50-336
              License No. DPR-65
              Licensee:          Northeast Nuclear Energy Company
                                  P.O. Box 270
                                  Hartford, Connecticut
              Facility Name: Millstone Nuclear Power Station, Unit 2
              Inspection At: Waterford, Connecticut
              Inspection Conducted: April 29, - May 3, 1985
            Inspectors:
                                    E. H. Gray, LeacVReactor Engineer
                                                                                        h3 date
                                                                                                /8
          Approved by:
                                              -
                                                  M
                                                                                            dats
                                                                                                                    7d
                                    y.pWiggins, pff      rf, Materials
                                    Uand ProcesW          Section, DRS
            Inspection Summary:              Inspection during April 29 - May 3, 1985 (Report No.
          50-336/85-18).
          Areas Inspected:                Routine, unannounced inspection by one region based inspec-
          tor.      The inspection included the areas of Inservice Inspection (ISI) program
          activities including ultrasonic examination of piping and eddy current examina-
          tion of steam generator tubes and steam generator sleeves. Work in progress
            including sleeve installation on steam generator tubes and disassembly of the
          service water pump "A" were observed. The control and status of the reactor
          vessel material surveillance test coupons were reviewed.                    The inspection in-
          cluded 35 hours on site and an additional 4 hours at the regional office.
          Results: No violations were identified.
                                                        ~
                  8506240575 850618
                  PDR          ADOCK 05000336
                  G                          PDR
                                          __
 
  F  ,                                                                                    .i
  .
      1.0 Persons Contacted
            Northeast Nuclear Energy Company (NNECo)
            J. Bergin, Engineer (Sleeving)
            *T. Blanchard, ISI Coordinator - MS #2
            S. Brinkman, Engineer (S.W. Pumps)
            G. Closius, QC/QA Manager - MS#2
            *J. Kelley, Superintendent, Millstone #2
            *W.  Romberg, Station Superintendent
            *J. Smith, Engineering Supervisor
            Northeast Utilities Service Company (NUSCO)
            L. Baird, ISI Coordinator
            H. Cote, Construction QC Supervisor
            R. Fuller, UT, Level III
            R. Michaud, Construction QC Manager
            *Present at exit meeting on 5/3/85.
            Combustion Engineering (CE)
            C. Ashman, EC, Level III
            ZETEC
            R. Miranda, EC Data Analyst
      2.0 Steam Generator (SG) Tube Eddy Current Examination
            By the time of this inspection the eddy current (EC) steam generator tube
            examinations were complete although EC data analysis was still in progress.
            The inspector observed a portion of the eddy current analysis in progress
            and reviewed the applicable procedure number STD-ISI-004, Revision 0.
            Comparisons were made to the ASME Code Section XI, IWB 2413 and IWB2420
            requirements and the intent of the NRC Regulatory Guide 1.83. The primary
            defect identified is pitting on the tube secondary (outside) side at a
            location within several inches above the upper surface of the tube sheet.
            All of the accessible tubes in both steam generators were examined in this
            area, to the first tube support plate, for pitting.  Those with pits in ex-
            cess of 39% through wall were scheduled for sleeving prior to continued
            service.
            The secondary side of the tubes in both steam generators were chemical
            cleaned as an assist in removal of the secondary side copper bearing
;            sludge.    In the opinion of this inspector, this cleaning operation has
'
            enhanced the EC response from existing pits or made their detection easier
            by removal of superfluous copper indications.
'
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                                                                                        1
.
                                              3
          In the sequence of eddy current data review, data is reviewed separately
          by two groups. The results are then compared with differences being
          reviewed and reevaluated. The licensee provided an independent third
          party review of selected portions of the eddy current evaluation.
          No violations were identified.
    3.0 Steam Generator Tube Sleeving
          The detection of pits greater than 39's throughwall just above the tube
          sheet surface resulted in the decision to prepare those tubes for further
          service by the insertion of sleeves and hard rolling them to the tube in-
          side surface. The inspector reviewed the basic procedure for tube sheet
          sleeving and portions of procedures applicable to specific steps in the
          sleeving process. The training and mockup area for practice in both
          robotic and manual sleeving was observed. Sleeving operations in progress
          during the inspection including eddy current examinations to confirm that
          sleeving was successfully completed were observed to determine the confor-
          mance to applicable procedures, the level personnel training and control
          over the sleeving process.
          No violations were identified.
    4.0 Ultrasonic Examination (UT) For Inservice Inspection (ISI)
          The plant outage in progress during this inspection is the Final Examina-
          tion period of the first ten year ISI interval.        In continuation of in-
          spection 50-336/84-17, the progress toward meeting the 10 year interval
          ISI plant requirements was reviewed. The inspector noted the status of
          completion of examinations, schedule to meet examinations yet required and
          the documentation system in place to achieve the 10 year interval ISI
          program plan.
          In the UT area the inspector observed examination of welds MSA-CG-16 and
          MSA-CG-14 as shown on drawing 25203-201-67.      This UT was done in accor-
          dance with procedures NU UT-1 Revision 4 and NU UT-3 Revision 2 as re-
          viewed by the inspector. The UT observed and related activities were
          compared to the requirements of the ASME Code Section V, Articles 4 and
          5, the ASME Code Section XI and ASNT-TC-1A. The UT test blocks for speci-
          fic UT data sheets were examined and data sheets, personnel qualifica-
          tions, the procedure of indication evaluation, significance of data sheet
          signoffs and the above mentioned UT procedures were reviewed.
          No violations were identified.
    5.0 Reactor Vessel Irradiation Material Surveillance Specimens
          The plant Technical Specification paragraph 4.4.9.1(c) requires that:
                "The reactor vessel material irradiation surveillance specimens
                shall be removed and examined, to determine changes in material
                properties, at the intervals shown in Table 4.4-3."
 
r  ,
.
                                                4
          Table 4.4.-3 requires capsule W-97 be removed and examined after 3.0 ef-
          fective full power years (EFPY), with the next capsule (W104) scheduled
          for removal after 10 EFPY.
          The inspector determined that surveillance specimen removal and examina-
          tion is under control of the plant ISI coordinator. The first surveil-
          lance capsule (W-97) was removed from the Millstone Unit 2 reactor vessel
          in August -1980 after 3.0 EFPY. Mechanical test specimens of base metal,
          weld metal and weld heat affected zone provided for determination of ra-
          diation induced changes of both tension and impact properties.
          Temperature monitors, alloys with specific melting properties, indicated
          the irradiation temperature to be between 536F and 558 F.
          The inspector reviewed the report of evaluation of irradiated capsule
          W-97 dated April 1982 by Combustion Engineering, Inc., and noted that
          provision was made by the ISI coordinator for removal of capsule W-104 in
          1988.
          No violations were identified.
    6.0 Service Water Intake Pump Columns - Independent Measurements
          The original material of the service water intake pump columns was cast
          iron. The cast iron was replaced with carbon steel on a temporary basis
          until stainless steel could be obtained. The last replacement design as
          installed in 1983 included type 316L flanges welded to type 316L plate
          rolled and welded to form cylinders with welding per the ASME Code
          Section IX.
          Pumps    "A" and "C" operate continuously during normal conditions, which
          pump    "B" is reserved for backup. During the 1985 outage scheduled
          inspection found the internal column welding of pump "C" circumferential
          velds had significant weld metal voids partially filled with a powder with
          a chemistry of 24.4% Cr, 5.4% Ni, 60.9% Fe. Pump columns "B" and "A" were
          removed and examined. Pump "B" had one area of one weld with a condition
          similar to pump "C".      Pump "A" columns had no visible areas with the
          defective condition of pump "C".
          The inspector saw a photograph of the defective condition of pump "C"
          columns and examined visually the column section welds of pump "A", in-
          cluding both the inside and outside surfaces of the longitudinal welds and
          the six circumferential flange to pipe welds. The longitudinal welds were
          noted to be nonmagnetic while the circumferential welds were slightly
          magnetic as typical for austenitic stainless steel weld with at least 10%
          ferrite.    The Northeast Utilities Engineering / Materials Laboratory report
 
    o                                                                                              }
  O
                                                                                                    i
                                              5
          dated March 29, 1985, by M. Galler and the purchase order for the columns                I
          were reviewed. The pump 'B" and "C" columns have been repaired, "C" by the
          manufacturer and "B" at the site and examined both visually and ultra-                  !
          sonically.  The pump "A"  column flange to pipe welds are scheduled for                l
          ultrasonic and formal visual examination. The pump manufacturer is con-                  l
          ducting an analysis of the weld problem.
          No violations were identified.
      7.0 QA/QC Involvement in Areas Inspected
          The inspector observed QA/QC personnel to be present and involved in
          areas covered by this inspection.        Procedures used in ultrasonic
          examination, eddy current examination, and sleeving were noted to be
          reviewed by QA as part of the plant operating review committee activity
          in advance of performance of the actual work activities.            During
          sleeving and eddy current sleeved tube area examination, QC personnel
          were present and actively involved in documentation of work steps and
          sequences. Level III nondestructive examination personnel were involved
          in both ultrasonic and eddy current examination activity.
          No violations were identified.
      8.  Exit Meeting
          The inspector met with licensee representatives, listed in paragraph 1,
          at the conclusion of the inspection to summarize the scope and findings
          of the inspection.    At no time during this inspection was written
          material provided to the licm see by the inspector.
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