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#REDIRECT [[IR 05000397/1983029]]
{{Adams
| number = ML17277A773
| issue date = 08/15/1983
| title = Forwards Info Describing Actions Taken to Resolve Const Issues Identified in IE Insp Rept 50-397/83-29,per 830715 Submittal.Schedules for Completion & Status of Programs Addressing Broad Issues Also Encl
| author name = Carlisle C
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| addressee name = Martin J
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
| docket = 05000397
| license number =
| contact person =
| document report number = GO2-83-732, NUDOCS 8308300762
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 97
}}
 
=Text=
{{#Wiki_filter:BEDE!VEO Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington Qp35Z, +09@7(-5/90 830825 8308300762 05000397 PDR ADOCK 8
XE HQ, 'PILE COPY Docket No. 50-397 August 15, 1983 G02-83-732 Mr. J. B. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA      94596
 
==Dear Mr. Martin:==
 
Subject          NUCLEAR PROJECT 2 CONSTRUCTION APPRAISAL TEAM ISSUES
 
==References:==
: 1)  Construction Appraisal Inspection Report 50-397/
83-29, NRC letter, DeYoung to Mazur, dated July 26,
                    . 1983
: 2)  WPPSS letter to  Region V, G02-83-622, dated    July 15, 1983 The purpose  of this letter is to provide information relating to issues and concerns  reported by the NRC Construction Appraisal Team incident to their May-June, 1983, inspection of WNP-2.
Reference 1) transmitted    to the Supply    System the report of inspection of WNP-2 by the NRC Construction Appraisal Team (CAT). Reference 2) transmitted to Region V a preliminary report of activity by the Supply System to resolve CAT concerns.      Reference 2) stated that seven programs
 
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Mr. J. B. Martin Page 2 August 15, 1983 G02-83-732 had been  established to address the broad issues raised by the CAT. A review of Ref'erence 1) has indicated that the programs established by the Supply System before receipt of the'inspection report do in fact address the major issues.      The attachments to this letter contain descriptions, schedules for completion, and status of each program as of this date.
o  As-Builting o  Non-Destructive Examination o  Bolts, Fasteners and Torquing o  Welding o  Concrete o  Engineering Disposition of Deficiencies o  Review of Site guality Programs Against      CAT Issues Our general  approach to the  resolution of these issues is:
o  Grouping and assessment    of related specific issues and  consideration of generic implications (for each grouping);
o  Formulation of  investigative  and  corrective action programs; o  Formulation of detailed schedules    for tracking progress on each program; o  Consultation with off-site experts on the concrete issue, and with Bechtel's engineering and materials 5 services organizations on as-builting, welding, bolts, fasteners and torquing, and NDE; o  Contracting with Stone and Webster to do an independent "third-par ty" assessment of the project as-builting program, and Westinghouse to do a general third-party review of project resolution of the CAT issues; and o  Tracking of each specific item in the CAT report to ensure, closure.    (This process will be discussed with the NRC resident representative as      it is implemented.}
These programs are being given    priority attention to ensure successful resolution of the. Construction Appraisal Team issues within our. licensing/
fuel load schedules. We reaffirm our request for an early meeting between Supply System and NRC Region V representatives to discuss these programs and our findings to date. We suggest that this meeting take
 
l Mr. J. B. Martin Page 3 August 15, 1983, G02-83-732 place at WNP-2 so that those persons responsible for implementation of each program will be available'to provide the details of their investi-gations  and  findings.
A  copy  of this letter and the enclosed package is being sent to Mr. R.
F. Heishman for information.
C.  . ar  ss e - 901A Program  Director, WNP-2 HAC/fl Attachments:    As Stated cc:    Mr. R. C. DeYoung, NRC I&E Mr. R. F. Heishman, NRC QASIP IE Mr. A. D. Toth, NRC Resident, WNP-2
 
0 TABLE OF CONTENTS MANAGEMENT
 
==SUMMARY==
 
AS-BU ILTING NDE BOLTS, FASTENERS AND TORQUING WELDING ENGINEERING DISPOSITION OF DEFICIENCIES CONCRETE REVIEW OF SITE QUALITY PROGRAMS AGAINST CAT ISSUES
 
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MANAGEMENT
 
==SUMMARY==
 
Programs were initiated based on NRC CAT exit briefing and subsequently adjusted based on the Final CAT Report received July 29, 1983. The current programs are described in this submittal. These programs address guality Class I work except where Seismic Category I, guality Class            II is specifically identified.
Programs are scoped      to address all CAT-specific concerns as well as generic implications of CAT-identified deficiencies. These programs will address the root cause of programmatic deficiencies.
Program completions are scheduled with expectations that resolution and corrective actions will be implemented to prevent delays in system sequences necessary to support the WNP-2 fuel load and power ascension testing schedule.
(WNP-2 CAT Program Summary Schedule is provided on the last page of this Management Summary Section.)
Third-party participation        has been  incorporated into these programs through a Westinghouse overview, the        Stone  and  Webster assignment on as-builting, and independent Bechtel Engineering        actions  on elements such as the fastener acceptance    criteria  and assessment  of  structural  concrete. Attachment 1 to this Summary provides a description of the Westinghouse/Stone and Webster work scopes.
The  following    summaries provide a brief    description and status of WNP-2    CAT programs.      These programs are described      in greater detail following this summary.
H Pro ram  I - As-Builtin Stone and Webster will perform a third-party review          of the project as-built    program including physical inspection of a        significant sample of the hangers.
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: 2. Project specifications have      been. revised to clarify as-builting require-ments, including measurement      tolerances, and to disposition variances from design requirements.
: 3. Bechtel will retrain personnel, re-review the as-built drawings against the new construction tolerances, and submit all out-of-tolerance dis-crepancies to Burns and Roe for evaluation. This process will be independently audited by Bechtel (SFHO) engineering personnel.
Page    1 of 5 -  MANAGEMENT
 
==SUMMARY==
 
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: 4. CAT  concerns on the need to finalize as-built guality Class II, Seismic Category I supports are not supported by evaluations performed to date.      The previous status as-built program in conjunction with the design    margins  for these supports being maintained at the level of guality    Class  I  requirements provides substantial assurance that the installations will not fall during a postulated design basis earthquake.
This was further demonstrated for each discrepancy identified by CAT on guality Class II, Seismic Category I supports and the results will be included in the final response to the CAT report.
: 5. ASME/AISC code      jurisdictional boundaries for gC I supports are consistent with code requirements and industry practice at several other nuclear projects. Implementation of this boundary does not degrade the support in performing the required design function.
: 6. Significant as-builting errors will be made subject to reinspection on a generic basis through use of one or more of the existing project walkdown inspection programs.
Pro ram  II - NDE
: 1. Welds questioned      (by  CAT review of RT film) meet all code and specifi-cation requirements.        This was demonstrated by direct visual examination, macrographic examination and etching of laboratory weld sections or re-radiography. Laboratory work was performed by Bechtel in San Francisco
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with surveillance by NRC personnel.
,2. The radiographs      for all Bechtel weld repairs have been re-reviewed (317 welds). Thirteen    additional instances were discovered where inadequate weld repairs were caused by failure to compare original radiograph with repair radiographs.
: 3. The ongoing Phase      II film review activity  from the HBG radiography reverification program has been completed. One hundred        six welds with film quality deviations have been identified.
: 4. Seven welds    with  PT  indications have been found in an expanded sample covering the work of the same technician questioned by CAT. Six of the seven have been evaluated and found to be nonrelevant/insignificant.
The seventh is still under investigation.
Page 2  of  5 - MANAGEMENT
 
==SUMMARY==
 
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Pro ram  III -  Bolts, Fasteners,  and Tor  uin
: 1. This program addresses      four quality attributes    on 18 fastener types:
o      Material.
o      Tightness/torque.
o      Locking device/washer.
o      Thread engagement.
: 2. An  extensive program is being implemented as indicated by the matrix in the detailed section of this submittal.
: 3. Field inspections and torque tests 'are being performed        on  nine cate-gories of fasteners.
: 4. Acceptance guidelines are being developed where torquing          is not required and range of acceptability where torquing is required.
: 5. Field inspections are in progress in several major categories of fasteners including flange bolting, pipe support fasteners, valve bolting and equipment anchors on non-rotating equipment.
: 6. Conclusions to date:
o      Acceptable As Installed - structural steel bolting, cable tray splices, cable termination screws, blowout panel fasteners.
o    100K  Inspections Required - ECCS pump couplings, instrument mounting, warehouse storage segregation of fasteners, and rotating equipment anchor bolts.
Pro ram IV  - Weldin
: l. The types    of weld surface (contour) irregularities identified by        CAT at  WNP-2  are within code and specification requirements and are enveloped by the code stress analysis.
: 2. One hundred percent of olet welds within the scope of contracts 215 and 220 are being inspected for sufficient weld reinforcement.'ll cases that do not meet design requirements will be reworked.
: 3. Availability of    weld procedure requirements is currently adequately addressed by Bechtel procedures and instructions. Bechtel welders are trained to the Bechtel weld procedures and attest in writing to their understanding of the "Bechtel Welder 's Guidelines" which identify the location of weld procedures.        There is a large sign located in the welding  engineers'rea      with the  words,  "Bechtel welding procedures located here. .    .". Actual  welding  observed  by CAT concluded that weld parameters were being properly implemented.
Page    3 of  5 -  MANAGEMENT
 
==SUMMARY==
 
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: 4. In response to CAT concerns on the visual acceptance criteria implemented during reverification inspections of structural steel welds, the degree of individual weld characteristics accepted which occur simulataneously on the same joint, will be identified and evaluated (for select critical structural connections). This will demonstrate acceptability on a more conservative basis than previously analyzed.
: 5. All containment penetration stiffener welds made by PDM under Contract 213 were reinspected. Eight of the eleven have welds slightly undersized or with unequal legs, usually of a 1/8" magnitude. The welds have been technically evaluated and are structurally adequate and acceptable for the application. Additional penetration stiffener welds performed by PDM under contracts  213A and 213B  will be inspected.
Pro ram V -  En ineerin  Dis  osition of Deficiencies
: 1. CAT concerns for an adequately-documented,      technical basis for NCR dispositions are being addressed by evaluating for trends the CAT-identified NCRs and NCR dispositions reviewed by the guality Verifi-cation Program.
: 2. Generic CAT concerns for adequacy of engineering dispositions are being addressed by individually evaluating each identified item for adequacy, assessing any deficiencies against the required Burns and Roe design control procedures, and trending deficiencies for a common cause.
Pro ram YI  - Concrete
: l. Additional excavations have    been performed and  variations identified.
: 2. Design margins exceed    all identified construction variations.
: 3. Third-party reviews are being performed to confirm the adequacy of concrete/structures to perform design basis functions.
: 4. Excavations will be repaired and analysis of adequacy finalized and submitted in our final CAT report.
Pro ram  VII - Review  of Site ualit    Pro rams A  ainst  CAT Issues 1
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: 1. CAT  findings are being reviewed against previous guality Verification Program (gVP) results to determine      if  CAT identified deficiencies which gVP should have identified on work completed prior to June 1980.
Page 4  of  5 -  MANAGEMENT
 
==SUMMARY==
: 2. CAT  findings    on work performed under  the Operational Quality Assurance Program are being individually reviewed for corrective action, including generic implications (if any), and the need for program changes to pre-clude recurrence.      Inspections performed by Test and Startup engineers are described in approved Startup Program Manuals submitted to the NRC prior to initiation of Startup activities.
: 3. A  comparison    of CAT findings on work performed after June 1980 and findings    of the ongoing Construction QA program in the same areas is being performed to assess any weaknesses in the current QA programs.
: 4. Engineering walkdowns are being performed in select areas of completed Quality Class I construction based upon an overview of the areas that QVP and other special programs have previously addressed.        The purpose of this t
effor is to identify areas not previously addressed and to increase the level of confidence in the quality of construction in these select areas.
Walkdowns described in the detailed sections of this report are complete and have identified no new generic issues.        From this overview,  it was evident that incr eased attention should be directed to primary containment work performed by the 213 contractor; this work is currently being addressed by QVP under the PPIA portion of that Program.
From  this overview,    it is evident that with the multitude of programs being    implemented  on  WNP-2, there are programs redundant to the original construction programs which verify most of the quality attributes that are measurable on completed work.
Page  5  of  5  -  MANAGEMENT
 
==SUMMARY==
 
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MANAGEMENT
 
==SUMMARY==
    -  ATTACHMENT 1 PROGRAM OVERVIEW BY WESTINGHOUSE The Supply System      contracted with Westinghouse Electric Corporation to provide    a technical  and licensing overview of the response program. This overview includes a detailed review of the CAT findings, monitoring of the Supply System response program, and evaluation of the results and conclusions of the program. Westinghouse has personnel on site experienced in design, construction and startup activities of nuclear power plants with specific expertise in each of the areas identified in the CAT findings. These personnel are monitoring the work performed under the response program and will ensure that the implementation of the program is adequate and techni-cally sound to assure safe and reliable operation of the plant. At the conclusion of the response program, Westinghouse will submit a report docu-menting the findings of this overview.
AS-BUILT REVIEW      BY STONE AND WEBSTER Stone and Webster will perform a third-party review of the project as-built program. The Stone and Webster review consists of four activities:
: l. A  review of the existing as-built program and      it s implementation.
: 2. A  review of the  CAT  findings in relation to Project    and Bechtel gA findings.
: 3.      Physical inspection of    a  significant  sample of the hanger population.
: 4. An  assessment  of the as-built    program  with respect to:
a)    Meeting the needs    of the project.
    . b)    Meeting the requirements    of NRC  IE Bulletin 79-14.
Page  1  of  1  - ATTACHMENT  1 -  MANAGEMENT
 
==SUMMARY==
 
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I. AS-BUILTING A. DEVELOP 79-14 GUIDELINES FOR AS-BUILTING B. DEVELOP ATTRIBUTES RE UIRING FURTHER INSPECTION C. WALKDOWN/AS-BUILT D. AS-BUILT TOLLERANCE DISCREPAN IES E. SEISMIC  II I CONCERN F. PIPE WHIP RESTRAINT CONCERN G. FINAL REPORT II  NDE EVALUATION A. WELD CUTOUT B. M S EXAHINATION C. LI UID PENETRANT RE-EXAM D. NDE FILH UALITY REVIElt
: 1. 'LEVEL III EVALUATION
: 2. RADIOGRAPHIC RE-EXAH E. FINAL REPORT V  W  DING TETLIl                                    PROBLEH AREA SUt%QRY SCHEDULE QCONST.
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PROGRAM  I AS-BUILTING DESCRIPTION OF CONCERNS AND          UESTIONS The  NRC CAT  concerns with the project as-built program for large and small bore pipe supports and piping isometrics cover five general areas:
A. Errors in Field Engineering identification 'of hardware dis-crepancies and dimensions on the redline drawings.
B. Errors in Field Engineering dispositioning of hardware dis-crepancies and dimensions by interpretation of. allowable construction tolerances in Burns and Roe,(BRI) drawing H-501.
C. Exclusion of Quality. Class      II, Seismic Category I supports from the. project as-built program.
D. The  issues regarding ASME/AISC code jurisdictional bound-aries  (i.e., the NF boundary descriptions provided on BRI's H-501 drawing) for the design and construction of QCI pipe supports.
E. The pipe whip restraints may not be        in the location assumed in the pipe whip analysis.
In addition to these        five  main concerns, two outstanding questions remain to be answered        from  the CAT inspection. They are: .(1) Is the direction of snubber safety wiring important?; and (2). Is the orienta-tion of lubrite.plates important?
PROGRAM TO RESOLYE CONCERNS o      Develop  'as-builting guidelines    based upon 79-14 requirements.
o      Review as-builting errors identified by CAT, BQA and        PQA expanded sample and rate them as to significance        (i.e., effect of the error    on  the design).
o      Based upon    significance ratings, identify attributes for necessary additional inspection.
o      BRI has added    as-builting tolerances to the specii'ication  and
            .clarified construction tolerances for the      H-501 drawing.
Page  1 of  5  -  PROGRAM  I - AS-BUILTING
 
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o      The  project will adjust program, perform necessary inspections and  re-review dispositions of past redline discrepancies.
o      A  third-party review of the total as-builting      program has been initiated.
STATUS OF ACTIONS TAKEN A. Concern A Bechtel Engineering has developed a set of guidelines, based upon IE Bulletin 79-14 requirements, with necessary measure-ment tolerances and critical dimensions needed for as-builting large and small bore pipe supports and piping isometrics.
: 2. Bechtel Engineering and BRI have reviewed.all of the errors identified to date by CAT, BQA, and PQA expanded sample and rated them as to their significance.        The signifi-cance ratings, which are a function of the effect of the error on the design, were determined by using the guidelines from Step 1 above.
: 3. Bechtel Engineering, with BRI concurrence, will determine if  there are any attributes which, based upon the signifi-cance ratings from Step 2 above, warrant additional inspection. If there are, they will be covered either by repeating the Bechtel as-built walkdown process for those particular attributes or by using one of the other existing project walkdown inspection programs for piping and pipe supports (e.g., hanger balancing) as appropriate for the particular attributes.
It should be noted that several of the as-builting errors identified by CAT (e.g., snubber cold set, clearances, staking, etc.) are covered and would have been picked up by other project programs which were in, place but not completed at the time of the CAT inspection.
B. Concern    B Bechtel and BRI have developed    a  set of as-builting measurement  tolerances for large and small bore pipe and hangers.
: 2. BRI has prepared    a.215 specification revision for as-builting which incorporates the following:
(a)    Consolidation  of,all as-builting  requirements    into a single specification section.
(b)    As-builting  measurement  tolerances from Step    1 above.
Page 2  of  5  -  PROGRAM  I'S-BUILTING
 
(c)            A  statement describing      how the as-builting measure-ment tolerances      relate to the H-501 construction tolerances and how each are to be applied by Bechtel in the preparation of as-built drawings, as  well  as both  Bechtel and others (during the performance of a subsequent gA audit) checking for accuracy of the as-built drawings.
(d)            A  definitive requirement that Bechtel must submit actual large bore isometric as-built drawings with IRRs  regardless of whether or not discrepancies      are within H-501 construction tolerances.
(e)            A definitive requirement that Bechtel shall evaluate
                          .all as-built discrepancies from the design drawings against the H-501 construction tolerances and submit, on  RFIs, only those discrepancies which are outside the K-501 tolerances.        The specification revision also states that small bore isometric and large bore hanger as-built drawings need not be submitted to BRI with IRRs/PRRs.
: 3.      Bechtel has provided comments to BRI for                    clarification changes              to the  H-501  construction tolerances.
: 4.      BRI has              revised and reissued the H-501 drawing.
: 5.      Bechtel will revise their as-builting procedure SWP/P-6 to conform to the.215 specification and H-501 drawing changes.                Items that were required by procedure to be as-built but are covered by other more appropriate existing walkdown inspection programs will be deleted from the SWP/P-6 procedure.
: 6.      Bechtel              will review    PMI  6-6 against the.215 specification and H-501 drawing changes                  and provide comments to Supply System Engineering.
: 7.    -
Supply System Engineering                  will, if necessary,  revise PMI  6-6 for reconciliation with the                  215  specification  and SWP/P-6
    ~ -    changes.'.
Bechtel will conduct a documented training session to cover the.215 specification and SWP/P-6 changes.
: 9.      For those cases where the new.215 specification does not require Bechtel to submit as-built drawings to BRI with IRRs/PRRs, Bechtel will re-review the as-built drawings against the new H-501 construction tolerances and submit all out-of-tolerance discrepancies to BRI on RFIs.
Page 3  of            5 -  PROGRAM    I  AS-BUILTING
 
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: 10. Bechtel Engineering (SFHO) will audit Bechtel Field Engineering dispositioning of as-built discrepancies            from Step 9 above.
C. Concern      C The CAT concern          is essentially the    same as NRC unresolved  Item 83-05/05.        Letter G02-83-622 to NRC Region V, dated July 15, 1983,    transmitted      a paper stating the Supply System's position with respect to as-builting guality.Class II, Seismic Category I hangers and the rationale supporting that position.
D. Concern      D The CAT concern          is essentially the same as that described in the  NRC Notice      of  Deviation 83-22 ( Item 82-18/02). The response to this concern is contained in the Supply System's letter G02-83-701 to NRC Region V, dated August 5; 1983.
E. Concern      E BRI will measure the actual location of pipe whip restraints on the piping run and perform evaluations to determine the acceptability of the as-constructed location. The measurements and evaluations will be included as part of the pipe break/
missile protection walkdown and study to be performed by BRI.
F.  . uestions.      1  and    2 Although not mentioned in the attachments to this letter, the question concerning the direction of snubber safety wiring is being addressed by Program III - "Bolts, Fasteners and Torquing".
Supports with lubrite plates, where orientation            is critical, will be inspected to assure proper orientation.
G. Third-Part          Review Stone and Webster, acting entirely independent of the above-described program, is performing a third-party review of the project as-built program        The Stone and Webster program consists of four activities:
o      A  review of the existing as-built program and        its implementation.
o      A  review of the      CAT  findings in relation to previous  PgA and B(A      findings.
o      Physical inspection of        a significant  sample  of the hanger population.
Page 4    of  5  -  PROGRAM    I AS-BUILTING
 
o    An assessment  of the as-built program with respect to:
Meeting the needs of the  project.
Meeting the requirements  of NRC IE Bulletin 79-14.
Page 5 of 5 -  PROGRAM I  AS-BUILTING
 
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PROGRAM  II NDE DESCRIPTION OF CONCERNS AND          UESTION The NRC CAT concerns        with the project nondestructive examination are identified below, referenced to CAT Report 50-397/83-29.
A. Radio ra hic Film Review - Ref. CAT IV-B-4 Wel d    ual i t The    following welds      were  identified  as having weld  quality defects:
(a)    RHR  882-1.4, 'FW-6Rl - Root Linear Indication (b)    RHR  854-12.16, FW-14Rl - Root Linear Indication (c)    LPCS 756-1.4, FW Linear Indication (d)    RHR 851-18.19, FW-12ARl - Wrong Repair Area Film (e)    LPCS 756-5.7, FW-17R2 - Linear Indication (f)    RFW 438-3, FW-1Rl - Linear Indication
: 2. Film      ualit From the review of WBG Phase II radiographic film for film quality, rejectable densities were identified on the radiographs for RRC-1819-2, FW4; RRC-1819-2, FW7; and RRC-3083-1, FW1.
: 3. Film    Artifacts Radiographs        for two welds were    identified  as having  film artifacts:
(a)    CAC  088-1,  FW6 (b)    CIA 4131-1,    FW10 B. NDE  Personnel      Interviews  and Methods  Evaluation  IVB5 Bestco    NDE    procedures were considered to provide inadequate direction for evaluation of weld surface conditions prior to performance of nondestructive examination.
: 2. NRC CAT      identified    two welds  that were re-examined  by  liquid penetrant      and found  to  have  rejectable indications.
Page  1 of  4  -  PROGRAM    II  NDE
: 3. Bestco radiographic procedures were considered to provide insufficient direction in the following areas:
(a)  Selection of radiographic techniques by        NDE  operators.
(b)  Application  and use  of film markers    on  repair areas.
(c)  Lack  of specific instruction regarding film orientation and  technique.
(d)  The use  of more than two    film per cassette.
PROGRAM TO RESOLVE CONCERNS o    Examine welds thought to have rejectable indications by destructive or nondestructive examination to resolve inter-pretation differences.
o    Review radiographs      of all repair welds    made by  Bechtel; resolve additional questions.
o    Review remaining Phase      II radiographs for film quality.
o    Re-radiograph films considered by        CAT to  have  film artifacts.
o    Review  liquid penetrant procedures.
0    Review Bestco procedures      for radiography    and  other  NDE.
STATUS OF ACTIONS TAKEN A. Radio ra  hic Film Review Weld  ualit Welds previously identified as items (a), (b), (e) and (f) have been evaluated by Bechtel's Materials and guality Services Department. The evaluation included direct visual examination, laboratory weld sectioning, macrographic examination, etching, and photographic preservation.        A detailed description of this activity is being prepared and will include supportive laboratory reports and photographs. Item (c) was investigated while the CAT was on site and found to be satisfactory. See Program IV, point 4 under STATUS OF ACTIONS TAKEN, for a complete discussion of item (c).
The  evaluation activities are complete for items (a), (b),
(c), (e)  and (f). The results of this evaluation indicate weld items (a), (b), (c), (e) and (f) meet.all specification and code requirements.
Item (d) involved    a  weld repair error  caused  by  failure to Page 2  of 4  - PROGRAM  II  NDE
 
l review the original weld radiographs in conjunction with the repair weld radiographs. A commitment to review all radiographs of Bechtel repaired welds has been completed.
A total of 317 weld repairs were reviewed.      Fourteen repair welds were  identified for further evaluation.
Nonconformance reports have been prepared for the 14 weld repairs. Two welds were found with the wrong area repaired.
The remaining 12 welds had inadequate film coverage.(l),
defect identification discrepancies,(10),    and incorrect interpretation.(1). With the exception of the one incorrect interpretation, all errors are directly related to not com-paring the original radiograph with the repair radiograph when performing the repair evaluation.
Additional actions taken are:
: l. Written instructions are being prepared to assure that original radiographs are compared with repair radiographs to provide corrective action to prevent recurrence.
: 2. The item has been identified as a potentially reportable 10CFR50.55(e). The undiscovered defects in each of the 14 welds have been analyzed by fracture mechanic' techniques described in Section XI of the Code. The results indicate that the stress intensity factors for the defects are lower than the    critical  values for the materials involved.
: 3. Because of the one incorrect interpretation, an additional sample review of 61 production r adiographs, originally interpreted by the same NDE technician, was performed.
This resulted in finding one additional radiograph with a marginal porosity condition. This condition is      still under evaluation by Level III NDE personnel.
The remaining WBG Phase    II radiographs have been reviewed and 106 welds identified with minor film quality deviations.      The guality.Class I welds are identified by nonconformance reports for resolution of the discrepancy.
: 3. Film Artifacts Three radiographic views covering two welds have artifacts from film processing. Despite the film artifacts, the film  is interpretable when    the two films for each view are compared one  against the other. This is a code-permitted and industry-accepted practice and is the primary reason for using Page 3  of 4  - PROGRAM  II  NDE
 
I two  films in each cassette for industrial radiography. Never-theless, to dispel any lingering doubt it was agreed to reshoot the three views    for  welds CAC-088-1, FW6, and CIA-4131-1, FW10. However, CAC-088-1 was  cut out prior to the      CAT inspection.
CIA-.4131-1 was re-radiographed    and the film accepted.      No further corrective action    is necessary as there    was  no code nor specification violation.
B. NDE  Personnel  Interviews  and Methods  Evaluation
: 1. The Bestco    procedural practices (Items Bl and B3) are within specification and code requirements. Level III personnel are reviewing current NDE procedures and practices to identify any areas that may need strengthening, and/or to verify procedure and practice acceptability. References to Bestco RT procedure, RT194A, Rev. 4, in the CAT Report, appear to be in error. This procedure has not been implemented on  this site.
: 2. The two-weld PT sample described      by  CAT was  increased to five welds to cover.all PT examinations made by the same technician on the same day on the same isometric.        PT indications similar to those found by CAT were discovered on all five welds. The sample was then increased again to 39 welds (34 additional),
all originally examined by the same technician but over an extended time period on different isometrics. Seven welds with PT indications were found; the five original ones. plus two more from the additional 34-weld sample.        Six of the seven welds with PT indications were. blended by filing to remove the indications and determine their cause. .All six indications were found to be nonrelevant or insignificant. No weld repairs were necessary.
Access problems have delayed removal and investigation of the PT indications on the one remaining weld.        This weld will be investigated in a manner similar to the other six as soon as possible.
Page 4  of 4  -  PROGRAM  II  NDE
 
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PROGRAM  III BOLTS, FASTENERS AND TOR(jUING DESCRIPTION OF CONCERNS AND        UESTIONS The  NRC CAT found discrepancies    in bolting material on equipment and piping systems. In addition, they raised questions as to the adequacy of specified torquing requirements and the results apparent in the installation of several types of fasteners.
PROGRAM TO RESOLVE CONCERNS
~Pur  ose Provide assurance that Ouality Class I and guality Class      II, Seismic Category I fasteners installed on WNP-2 are:
The proper  material Adequately tightened/torqued    for their intended function Installed with  an adequate  locking provision or  flat washer as required Installed with the proper thread    engagement
~Sco  e Implement a deficiency trending program to review types of fasteners provided by suppliers, installed by contractors on site, and disassembled/reassembled    by Test 8 Startup to assure that verification exists that the final fastener installation is adequate. If no verification exists, sample inspection programs will be established to provide this verification.
o    Re-evaluate and document the technical basis for existing specification requirements on tightening/torquing and material of, fasteners.
Pro ram Descri    tion A.      The  Bolts, Fasteners and Torquing Deficiency Trending Program is described in the attached matrix (Attachment 1). This matrix identifies 18 fastener types which represent the major guality
      ,Class I and guality Class II, Seismic Category I fasteners used on WNP-2. For each fastener type, four critical attributes are considered: material, tightness/torque, locking device/washer, and thread engagement. The matrix also identifies the major installers Page  1  of 3  - PROGRAM  III BOLTS,  FASTENERS AND TOR(UING
 
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of  each type    of fastener including suppliers, site contractors, and Test  5  Startup. (Note the matrix indicates information developed to date.)
For each major    installer of a particular fastener type, a checklist is prepared. This checklist covers the installer's scope of work, specification requirements, installer's procedures, previous in-spections of this work conducted in addition to normal installa-tion, and the CAT findings. This checklist forms the basis'for deciding if additional inspections are required. Previous in-spection programs, NRC audit findings, and additional inspection programs needed are summarized in the        matrix.
The  results of the identified sample programs, plus the CAT findings will  be analyzed for trends to see    if  further inspections are required.
B. The A/E, Burns and Roe,      will re-evaluate the technical basis for existing specification requirements for fasteners, including an assessment of a small percentage of randomly scattered variations in tightness and materials, justification for the use of flat washers on slotted holes, and an assessment of bolt relaxation with use. Included in this evaluation will be guidelines for evaluating torque data on bolting for acceptability, considering both passive boundary and structural loading performance.
C. An  independent organization, Bechtel, will provide an assessment of the effect of randomly scattered variations in tightness and materials for flange bolting, use of flat washers on slotted holes, and an assessment      of bolt relaxation.
D. The sample    inspection of final in-.place hardware will be the verifica-tion of material adequacy. In the case of Bechtel and the Supply System, additional documented audits, of warehousing will be performed to assure adequate material control.
STATUS OF ACTIONS TAKEN A. Overall program schedule is      shown on Attachment  II.
              -t As  indicated in the matrix (Attachment I), the major fastener types have been    identified along with the major fastener installers. In addition, checklists have been completed to identify the areas where additional sampling is needed.
Sample programs have been      established in the areas indicated. These programs include a procedure      for performing the inspections, train-ing of personnel involved in making the inspections, and initiation of field inspections.
Of the 18 major fastener types, conclusions have been reached on Page 2  of  3    - PROGRAM  III - BOLTS, FASTENERS AND TORQUING
 
six types      as  indicated below:
          .81      Structural steel bolting - Acceptable b7      Instrument mounting - Test 8 Startup to add      100 percent bolt inspection to System Lineup Test-I-4 89      Rotating equipment coupling installation A. Test 5 Startup to reinspect.all ECCS pumps with    a follow-on maintenance surveillance program.
B. Test  & Startup to check torque  and material on 12 additional pump groups.
            ,812    Cable tray splices - Acceptable
            ,5'14  .Electrical cable termination screws - Acceptable 816    Blow-out panel fasteners - Acceptable Tornado siding fasteners - Acceptable B. The  Architect/Engineer, Burns and Roe, has prepared a technical memo  which addresses the technical issues on bolts, fasteners, and torquing. In addition, they have established guidelines for re-viewing    field    sample data.
C. Bechtel provided an assessment of the technical issues concerning fasteners. This assessment supports the basic A/E positions.
D. Bechtel warehousing reinspected          their fastener storage facilities in total      and  this effort  has been  audited by Bechtel gA.
Page 3  of  3    -  PROGRAM  III  BOLTS, FASTENERS AND TORgUING
 
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1983 AU IEL  SAM LES  EGIN ING    /21 R  G  RA BPE    O. ILS R P  R  F  D E. REVIEM BY FASTENER TYPE fl STRUCTURAL STEEL    BOLTING PREPARE
 
==SUMMARY==
 
f32 CONCRETE EXPANSION ANCHORS PREPARE SUGARY
            ~:    CAT PROGRN
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STATUS DATUN i
I ATTACHNENT    II
 
PROGRAM    IV WEL DING DESCRIPTION OF CONCERNS AND        UESTIONS The  NRC CAT  concerns with the project welding program cover        five  general topics:
A. Improper weld surface appearance/contour.
B. Insufficient    weld reinforcement on weldolets.
C. Lack of knowledge of welding parameters        by some welders;  availability of welding procedures to the welders.
D. The general  use of gVI-09 for reverification inspection of structural steel welds.
E. Undersized  fillet welds  on  containment penetration  stiffener
          . plates.
There are no outstanding questions        to  be answered  other than those pertaining to the above concerns.
PROGRAM TO RESOLVE CONCERNS A. Improper weld surface appearance/contour
: l. A detailed study has been made of the actual welds examined by the  NRC CAT to determine their acceptability under the requirements of the ASME Code and project specificiations..
: 2. The  acceptability of the "toe-to-toe"      fillet welds  on LPCS-7591,  FW4 and  FW5  has been determined.
: 3. Inspection requirements and training for accepting weld contours (surface appearance) has been reviewed.
B,    Insufficient    weld reinforcement on weldolets
: l. All Supply  System  guality Class I weldolets and other olet fittings within      the scope of Contracts 215 and 220 have been identified by review of applicable drawings.
: 2. An  inspection program, including inspection criteria and inspector training has been developed to inspect olet welds.
Page  1  of  9 -  PROGRAM  IV -  WELDING
: 3. One hundred      percent of olet welds within the scope of Contracts 215 and 220 are being inspected        for weld reinforcement.
: 4. All  nonconformances identified during step        3 are being documented on  appropriate nonconformance reports.
C. Lack  of  Knowledge    of welding parameters  and availaibility of welding procedures.
: 1. The    existing site program    has been reviewed.
: 2. The    results of this review are presented in the Status of Action Taken in this report.
D. The general      use of QVI-09 for reverification inspection of structural steel welds:
: 1. The BRI    technical basis for the criteria contained in QVI-09 has been provided to the        NRC.
: 2. Determine the degree to which welded structural connections contain multiple attributes not meeting AWS D.l.l but meeting QVI-09.
: 3. Several critical structural connections will be selected and evaluated against QVI-09 to determine          if mulitple attribute deficiencies are acceptable.
E. Undersized      fillet welds    on containment  penetration stiffener plates:
: l. All containment penetrations with stiffener plate fillet welds made by PDM under Contract 213 have been identified.
: 2. All the      above welds have been inspected    and nonconformances have been documented.
: 3. All    nonconformances    have been dispositioned by Burns    and Roe as  "accept as is" based on an engineering evaluation.
: 4. Identify all other containment penetrations with stiffener plate    fillet welds    made by PDM  under subsequent  contracts with augmented    QA  programs.
: 5. Inspect    all the  above welds and document any nonconformances.
Page 2  of  9  -  PROGRAM  IY -  WELDING
 
STATUS OF ACTIONS TAKEN A. Improper weld surface appearance/contour The NRC CAT    report states that their concerns for weld contour are based upon:
: 1. Two welds (actually      3  welds) exhibited improper  fillet weld contour.
: 2. Numerous    other welds examined by the NRC CAT inspectors exhibited marginally acceptable contour and surface appearance.
: 3. Two  welds  failed  PT examination; possibly due to surface conditions.
: 4. For one weld,    it was  necessary  to grind the weld surface to obtain    an acceptable radiograph.
Based upon    the above four points, the NRC CAT questioned the adequacy    of  training for weld engineering and inspection personnel, and concluded that a review of the procedures and training (re-training) program of BPC field engineers and gC inspectors is warranted.
A  detailed study of    each  of the  above four points reveals the following:
Point 1:
The  three welds referred to in 1) above are:
a)      NS-522-3.4 pipe-stanchion-to-pipe      fillet weld  for support NSRV-4C-8 b)      LPCS-759-1,    FW4  (fillet weld) c)      LPCS-759-1,    FW5  (fillet weld)
Weld a)  did not require nondestructive examination other than visual inspection. Therefore, the Code requirements of NB4424 were met in that the weld was sufficiently free from coarse ripples, grooves, overlaps, abrupt ridges and valleys to make        it suitable for interpretation by      visual  examination.
Page 3  of  9 -  PROGRAM  IV -  WELDING
 
Other than the requirement that weld surfaces be suitable for NDE interpretation,    fillet weld bead contour is not addressed in the code or specifications because    it is not a technical concern. The WNP-2 design assumes that welded joints are in the as-welded condition unless specifically designated to be otherwise. The code-specified stress indices, or stress intensification factors, for  as-welded surfaces were used in the design. These stress indices take into account the "ropey" appearance which is inherent in stringer bead fillet welds, similar to weld a). Although weld a) was not aesthetically appealing, the weld contour surface appearance was nevertheless completely acceptable from design, code specification and structural integrity points of view. The weld was, nevertheless, reported on a NCR and reworked to help expedite resolution of the NRC CAT's concern. Further discussions with the NRC CAT reached agreement that all other specific welds identified by the NRC CAT as questionable met all code and specification requirements.
The welds b) and c)    did require PT examination. Both welds wer e  so examined during    construction and again during the CAT inspection.
The surface condition of the welds was such that there was no difficulty in interpreting the results of the PT examination.
Therefore, the requirements of NB4424 were met.,
A  second "weld contour" question concerning welds b) and c) was raised by NRC CAT. This question had to do with the included angle at the intersecting toes of the two adjacent      fillet welds, see attached photograph.
Welds b) and c) are both socket welds between 3/4" schedule 160 SA-106B pipe and 3/4" 6000 4 SA181 GR    II socket weld fittings. The welds are such that the toe of weld b) and the toe of weld c) touch. As we understand      it, the Inspector's concern is the existence of an unaccounted for structural discontinuity. The existence of this type of condition is not precluded by any project procedure or specification, and is not in violation of any code requirements. The existing condition is within construction tolerances.      The WNP-2 A/E (Burns and Roe) has reviewed    this specific application and determined that the close proximity of the welds is acceptable.      Further, the A/E has determined that the condition is very limited, possibly one of a kind, and that any other similar conditions are likewise acceptable.
Page 4 of  9  - PROGRAM  IV - WELDING
 
hk Point 2:
All of these welds were judged acceptable by the CAT. See above discussion of weld a) for additional information.
Point 3:
The two welds which failed PT are the same two identified as welds a) and b) under Point 1 above. The PT failures are discussed    in a separate report covering the resolution of CAT  concerns:with JJDE. As pointed out in the discussion above, and as shown in the attached photograph, the surface appearance of these two welds is totally acceptable.
Point 4:
At the time of construction completion,      it was not necessary to grind the surface of this weld (LPCS7561.4, Weld 6) to obtain a satisfactory radiograph. Reader sheets are available at the site to show that the film was reviewed and accepted by Bechtel under the WBG radiography reverification program on April 7, 1982.      During the CAT inspection, the NRC consultant for NDE interpreted the radiograph as showing evidence of incomplete fusion. The code rules of NB4424 state:
          "In those cases where there is a question regar'ding the surface condition on the interpretation of radiographic film, the film shall be compared to the actual weld surface for interpretation and determination of acceptability."
The  film and weld comparisons were made and project personnel were satisfied with the comparisons.      However, agreement could not be reached with the NRC CAT and accordingly the weld was ground and re-radiographed. The grinding and reshooting were done to prove clarity    and that  the original film interpretation made under the WBG radiograph      reverification  program was done correctly. This re-radiograph clearly      confirms  that the weld was acceptable and that the previous radiograph was acceptable and  interpreted correctly.
In summary, weld surface appearance is acceptable provided that proper nondestructive examinations are achievable.
Bechtel's welding engineers and gC inspectors are trained specifically to inspect weld surface characteristics and        it is a specific inspection step in the Project guality Control Instructions. The types of weld surface irregularities identified at WNP-2 are within code and specification requirements, Page 5  of  9 -  PROGRAM  IV - WELDING
 
and enveloped    by the code  stress analysis.      detailed study of the four points made by CAT regarding weld contour shows that weld surface appearance is not an issue of concern at WNP-.2.
B. Insufficient    weld reinforcement on weldolets The  HRC CAT    identified cases of insufficient weldout on the branch fitting to    run pipe weld on olet-type (weldolet, sockolet, elbolet, etc.) weld-on branch connection fittings. With the exception of one case, all such welds identified were on stainless steel piping systems where the run pipe was relatively thin-walled and the olet-type branch connection fitting was standard or heavy (extra or double extra strong) wall. These types of applications can result in excessive distortion in the run pipe in the weld zone. This potential problem was identified by a previous contractor and the A/E was requested in 1979 to allow for lesser weldout in these instances (reference: RFI 4563W). The A/E's response to this request was that generic approval could not be given, and the contractor was required to identify any applications receiving limited welding on a case-by-case basis to the A/E.
Weld-on    olet-type branch connection fittings are widely        used in the nuclear industry and at      WNP-2. The    fittings  have been  available in a wide variety of sizes      and schedules    (thicknesses). Although fittings for thin-walled      (schedule  5S and 10S)  stainless were not commercially available      until recently, fittings for virtually all other applications were available.        At WNP-2, the O'E designed many branch connections utilizing olet-type fittings with a greater wall thickness than required      f'r  pressure integrity. This practice resulted from the fact that schedule 5S and 10S fittings were not available, the requirement for a specific inside diameter on the branch to accommodate a specific thermowell or sample probe, and for reasons of design conservatism.
Although numerous cases were identified to the A/E, documentation does not exist to substantiate many of the known cases that have less than full weldout.
A corrective action program, as descr ibed below, was implemented to correct this deficiency. The existing welds are such that the design drawings do not specify a weld size, but the specification requires that the fittings be installed to the manufactuer's instructions.
Although the manufacturer's instructions are clear that the welds should be made fully to the weld line, this point is often difficult to locate on a fitting with a completed weld and in the case of some Page 6  of  9 - PROGRAM  IV - WELDIflG
 
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applications, impossible to achieve      due to excessive weld distortion and/or geometrical limitation.      With due consideration of these facts,    it is believed that the existence of conditions precedent to this problem do not exist. With due consideration of these facts, it  is believed that the existence of undersized welds on olet type fittings is no indication of weld or weld documentation problems on other types of welds where the unique conditions precedent to this problem do not exist.
The  corrective action program for weldolet concerns consists of  an  isometric/drawing review, inspector training, in situ walkdown, A/E evaluation of deficiencies, and rework necessary.
if The  isometric drawing review consisted of a 100 percent review of    all Supply System Quality Class I large bore and  all small bore piping within the scope of contract 215  and all Supply System Quality Class I piping within the scope of'ontract 220. Approximately 970 olet-type branch connection fittings were identified. This review identified the location, type and size of the olet-type fitting.
The inspector training program consisted of instruction by Bechtel construction field welding engineers to the quality control inspectors in identification of      fitting type and manufacturer, manufacturer's welding requirements (using both pictorial references and actual as-welded hardware samples), and evaluation techniques.      Subsequent weld inspection is being performed and documented in accordance with Quality Control Instruction QCI 14631/Pl.ll.
All deficiencies indentified by the quality control inspectors are being documented on a proper nonconformance document and forwarded to the appropriate design organization.
All cases found to not meet the requirements of the design and/or manufacturer will be identified to construction to be reworked to an acceptable condition.
C. Weld    rocedure  availabilit  knowled e During their site visit, the NRC CAT witnessed in sj,tu welding.
During specific in-process weld inspection, the CAT members questioned welders as to the requirements for that specific weld (weld procedure, weld size, travel speed, amperage, etc.). Although, in each case the weld was made to the correct procedure (size, speed, amperage, etc.), the actual welder did not, when questioned, state knowledge of the Page 7  of  9  - PROGRAM  IV - WELDING
 
weld procedure number, did not have a copy of the weld procedure, and did not profess knowledge of procedure ava i 1 abi 1 i ty.
The WNP-2      project program for welding procedure availability is that all required procedures for performance of the actual work are made available to the welders. The weld procedure is not required to be present at the work station.        Welding procedures are made available to welders at the welding material issuance stations.
Each    welder at WNP-2 is instructed in and given a copy of the document, "Bechtel Welder's Guidelines". This document, among other things, instructs the welder that welding procedures are available from the welding engineer. There is a large sign located in the welding engineers'rea with the words "Bechtel Welding Procedures Located Here...". All welders at WNP-2 have signed a statement attesting to the fact that they have read and understand the Bechtel Welding Guidelines. The signed statements are retained on file with the Bechtel Lead Melding Engineer.
Specifically, with regard to the NRC CAT concern regarding fillet weld size requirements for socket welds, all welders have been instructed to weld the fittings fully to the edge of the hub, even though the project specifications require that the weld leg be a minimum of 1.09 x t of the connecting piping (which is equal to or less than the full hub thickness).
The actual welding witnessed by the NRC CAT confirms this welder    instruction.
The  fact that all welding witnessed by the CAT members was  to the requirements of the applicable procedures shows that the welders are knowledgeable of the requirements. Craft personnel, when questioned by non-manual personnel, are apt to make a wide variety of statements, depending upon the manner and wording of the questioning and the attitude of the particular craftsman. Me believe that the training of welders is best reflected in both the results of their performance qualification tests and the actual quality of workmanship in the completed welds.        Me continue to train each welder to the Bechtel Welding Procedures and Guidelines and while doing so impress upon each craftsman the necessity for understanding and following the procedures. Each welder is firmly instructed that deviations from the procedures and guidelines will result in disciplinary action.
Page 8  of  9  -  PROGRAM  IV - MELDING
 
D. The general  use  of (VI-09 for the reverification of structural steel The  NRC CAT  identified that  some structural steel beams do not meet the visual acceptance criteria of AWS Dl.l. This led to a general concern regarding the use of (VI-09. Specifically, CAT appears to be concerned that the use of gVI-09 may not be adequately justified in that conclusions reached in the structural steel reverification program should reflect the consideration of all allowed weld deviations, and a detailed review of the more critical connections. The program for resolving this concern is still in the data gathering stage..
Page 9  of 9-  PROGRAM  IV -  WELDING
 
I 51
 
A  WEI.D SURFACE APPEARANCE WRITE POSITION PAPER BRI REVIEW/COMMENTS FINALIZE PROJECT POSITION PAPER 8  WELD PROCEDURE    AVAILABILITY CONFIRM ACCEPTABILITY OF EXISTiNG  PROGRAM  KITH A. TOTrl DEVELOP PROJECT POSITION PAPER C  OLET YELDOUT EVALUATION PROGRAM ISOMETRIC REVIEW O.C. WALKDOWN INSPECTION                                                                        BQC      T        ON C. INSPECTOR TRAINING                                                                        BOC      T  FAL ON ENGINEERiNG EVALUATION CONSTRUCTION FALLOUT IF RE 'D FINAL REPORT D  CONTAINMENT STIFFENER WELD EVALUATION PROGRAM INSPECT WELDS DRYWELL GENERATE NCR'S(DRYWELL ENGiNeERING EVALUATION DRYWELL                    RENDU RESl  ETW  LL A CESS WETWELL INSPFCTION ENGINEERING EVALUATION IF RE WRITE REPORT E  OVI  QVI-09 BRI REVIEW OF RB444                                                                            BRI      L OUANTIFY DEGReE OF MULTI-DISCREPANCY WELDS BRI CRITICAL CONNECTION REVIEW                                                                  BRI WRITE REPORT                                                                    BR    BPE        h      T  8  S SUBMIT FINAL REPORT ANSWERING CAT                                                                    BPE              OM WELDING FINDINGS IH PECT  ON S 952 OTA 952 HIT            K    NCP PPR VED CAT WELDING ISSUES            2 RJS 8/08/83/    0  ENG.      P  PROBLEM AREA    STATUS  >
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PROGRAM V ENGINEERING DISPOSITION OF DEFICIENCIES DESCRIPTION OF CONCERN AND      UESTION The CAT Report questioned    NCR  dispositions    and the adequacy of the design drawings to properly reflect      design calculation requirements with respect to concrete structures.
PROGRAM TO RESOLYE CONCERNS
: l. Analyze NCRs questioned by CAT during inspection; compare gVP Report on NCR dispositions with CAT NCR sample; draw conclusions; and,    if  analysis indicates action to be taken, strengthen procedure/program.
: 2. Analyze  CAT Report and develop a matrix of the items related to concrete and reinforcing steel identified by the CAT or by the project during the study of the CAT concrete issue.
: 3. Prepare a response    to  each item from the    matrix.
(a)  Identify item (b)  Provide  an assessment    of adequacy (c)  Establish a position (d)  Propose actions to be taken,      if warranted
: 4. Evaluate items and responses      related to the concrete issues for possible trends.
a)  Draw  conclusions as to adequacy of engineering position b)  For items found deficient, categorize as to type
{c)  Assess deficiencies for trends 5:  Prepare a paper defining Burns and Roe's process for approving contractor submittals. Evaluate deficient items from 4 above against design approval process (i.e.,
followed or not followed)
: 6. Propose action necessary      from the analyses of 4 and    5 above.
STATUS OF ACTIONS TAKEN Action Item  1-      755  complete..All      NCRs  have been analyzed.
Page  l of 2  - PROGRAM Y  ENGINEERING DISPOSITION OF DEFICIENCIES
 
,I One NCR requires disposition. Results to date contained in attachment.
Action Item 2-6      Work is underway. Matrix is being developed.
Page 2 of 2 -  PROGRAM Y. ENGINEERING DISPOSITION OF DEFICIENCIES
 
ATTACHMENT PROGRAM V
                . ENGINEERING DISPOSITION OF DEFICIENCIES NCR    DISPOSITIONS Twenty-seven    NCRs were identified in the CAT synopsis.          Twenty-six NCRs have been evaluated and one NCR has not been dispositioned as of this date. The results of this evaluation are as follows:
: 1. Statistical Information:
(a)    Disposition Use as  is -. 17 Rework      -    3 Repair      -    3 Void        -    3 (b)    Disciplines Making Disposition Mechanical -      1 Electrical - 2 Ci vi 1        -17 Hangers        - 2
                                  - 5  (3 voids; 2 IRs, no A/E involvement)
(c)    NCR  Initiation    Dates 1976        -. 1 1978        -, 1 1980        -. 1 1982        -    7 1983        -. 17
: 2. Evaluati on:
This evaluation concurred          fully with 24  of 26  dispositions provided.
Two NCR    dispositions were not considered totally adequate and are discussed        below:
NCR.218-8034
 
==Subject:==
ASTM  A-307 bolts not  marked  with  manu-facturers'dentification.
Page  1 of  3  -  ATTACHMENT      PROGRAM V
 
Disposition:  Use as  is.
Justification: Concurred with proposed technical    justi-fication provided by the contractor which stated the bolts were certified to ASTM A-307, IFI standards do not require any marking, and.all commercially avail-able bolts are ASTM A-307.
Analysi s:    The proposed    disposition provided by the contractor should have been rejected and a revised disposition provided by the A/E.
: l. The statement    made in the NCR, ",All commercially available bolts are A-307 steel" is not accurate and does not represent the statement made by Mr. H. Houten of Fasteners, Inc.
(telecom attached to NCR).
: 2. The  IFI Standard identified as being attached to the NCR was not attached. The IFI Standard intended to be referenced (checked with con-tractor to identify the IFI Standard) only identifies that no grade marking is required. It should be noted that ASTM A'-307 also does not require grade marking.
 
== Conclusion:==
The  use-as-is disposition of NCR.218-8034 is acceptable    based upon the fact that the contr actor had, from the supplier, certification that the bolts were ASTM A-307 bolts (even though they had no manufacturers'dentification), that ASTM  A-307 bolts are the lowest strength level (60,000 ultimate tensile) carbon steel commercially produced, and that ASTM A-307 does not require mechanical testing on a lot basis. Testing is ac-complished based upon mass production from stock which provides the assurance      of quality, material, and manufacturing pr acti ce.
Even though    the unmarked bolts are structurally adequate, the NCR disposi-tion should have required the contractor Page 2 of 3 - ATTACHMENT. PROGRAM V
 
to purge his stock of unmarked bolts to prevent the administration problems associated with continuing usage.          It should be noted that per the contractor, Mr. Hollenbach, the stock was purged even though not specifically required by the  NCR  disposition.
Subsequent    to the  CAT  identification of this  NCR, a sample    of  unmarked  bolts were removed from    field installations    and mechanically tested.      .All met the require-ments  of  ASTM  A-307.
NCR  500-021376
 
==Subject:==
Meld  defect (Lack of Fusion).
Disposition:    Use as  is.
Justification: Existing    weld adequate    for the load.
Analysis:        The  existing weld is structurally accept-able although the disposition to accept the lack of fusion in the weld is in violation of AHS.Dl.l and should have been repaired (weld defect ground out).
 
== Conclusion:==
The  use-as-is disposition of      NCR 500-021376  is acceptable. Further evaluation has indicated that the entire weld could be
                                .eliminated without affecting the structure and that the weld is in compression and would not be expected to propagate into the base material.
The  results of this evaluation confirm the findings of the QVP review of A/E NCR dispositions.          The QVP review concluded that: "It can therefore be stated with a 95K confidence that in-.,exces's-of 99K of all documents dispositioned by BRI are technically adequate."
Page 3 of 3  -  ATTACHMENT- PROGRAM V
 
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19 INK ACTIVIlY 14 R's I  NT F    BY CAT NCR  EQUI ES C HPL  ION OF A  LYS R"
TULE:
ENGINEERING DISPOSITION  CI ENG. P  PROBLEN AREA  STAUS V
OF DEFICIENCIES        0 CONST.    ~CTIVITY          DATtw i    ~a~~
 
PROGRAM  VI CONCRETE DESCRIPTION OF CONCERNS AND        UESTIONS From  the  CAT  Report:
      "(1) Rebar.placement deficiencies with respect to ACI.318-71 Code and design specification requirements have been identified in 10 of 12 examined locations. These will have varying degrees of adverse impact on the .strength of concrete structural, elements, ranging from significant to insignificant. (The issue of grout patch integrity had been identified previously and is being pursued by Region V personnel  (see Inspection Report    =  50-397/83-14)).
(2) The  ability of  the  initial HNP-2 gC  inspection records, RFIs and  NCR  dispositions to establish overall conformance with the design specifications is questionable.
(3) The accuracy with which the design drawings reflect confor-mance with the design calculation requirements is question-able.
(4) The visual inspections and documentation reviews .proposed by the applicant are of insufficient depth and scope to address the issue of rebar placement adequacy.        In addi tion, the destructive examinations discussed above are insufficient to completely characterize the extent of the rebar placement deviations at these locations and to provide a sufficient data base to infer the extent of deviations throughout the facility.
Therefore, there is not reasonable assurance that the reinforced concrete members and structures at HNP-2 were constructed to provide sufficient strength to adequately conform to the FSAR design requirements."
PROGRAMS TO RESOLVE CONCERNS o      Perform additional excavations and increase the scope of existing excavations    sufficiently to define the spectrum of possible reinforcing bar placement problems.
o      Record the    "as-constructed" condition at each excavation, paying particular attention to bond between concrete and steel; the existence of voids in the concrete; and the location of re-infor cing steel.
Page  1  of  3 -  PROGRAM  VI  CONCRETE
 
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o    Review    all existing pour records for engineering direction      given relative to the excavated structures.
o    Analyze the structure as-constructed        at each excavation and compare this analysis with the original design objectives to determine the significance of the deviations observed.
o    Review the process      for control of engineering approval on contractor submittal of steel details and compare NCRs, RFIs and steel details with sample excavations.        This will be done in conjunction with CAT Program V - Engineering Disposition of Def i ci enci es.
o    Draw    conclusions with respect to the adequacy of the structure to meet    its intended function based on the sam'pling done.
o    Assessment of off-site experts        with respect to condition of bond between steel and concrete      at each excavation and the existence of voids.
o      Review concrete documentation for all contracts.        Identii'y trends for further investigation. This will be done in con junction with the guality Verification Program review of concrete.
Third-party review of conclusions.
STATUS OF ACTIONS TAKEN o      Six additional excavations have been made at various locations in the plant. Included was an excavation to expose all tension steel in    Beam 2B5.
o      All excavations      have been photographed and as-builts prepared of the location      and size of the reinforcing bar exposed.
Photographs and    as-builts  were transmitted to Region V with letter    G02-83-622,  dated July 15, 1983.
o      The new    excavations have been viewed by NRC representatives Hessrs. Herring and Albert. The NRC representatives raised the following questions relative to two of the new excavations.
These items will be addressed in the final report.
SK-12:
As-built condition sketch called out      a.Ill bar when  a.tl0  was actually exposed.
One  layer of bars  was not exposed at the surface;  a  bar  may be  missing.
Page 2  of  3  -  PROGRAM  VI  CONCRETE
 
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Design drawing does not appear      to  have been  translated correctly to the. placement drawing.
SK-17:
Excavation is not    sufficient to confirm that splices    are staggered.
An RFI  exists permitting the use of additional bars but not clearly specifying when they are to be used.
The  following general    comments were made by the NRC during the exit discussion      and  will.also  be addressed in the final report:
Beam 4B30 and 6B9    appear  to contain  a mix substitution without  RFI  approval.    (See also Table V-2  of the CAT report.)
Beams  2Bll and 2B25:    Excavate  to sound concrete before patching.
Beam 2B5:    Noted that one location appeared to have been patched and questioned whether patch had been checked for soundness.
Base Mat at Pum    Pit: Still believe, placement contains an extra.k'll bar  not called  for in design.
Actions are underway to recheck the as-built drawing of each excavation, rephotograph selected excavations, resolve where possible by additional excavation questions regarding reinforcing bar.placement.
o    Final response to Region V on inspection report 50-397/83-14 has been submitted; letter G02-83-678, dated July 29; 1983.
o    Analyses are underway to determine the significance of the deviations observed in each excavation.
o    Nonresident experts have been consulted. They have offered conclusions that the honeycombing in beams 2Bll and 2B25 can be repaired so that the adequacy of these structures is not impaired. Further, one con-sultant has viewed the excavations made, in addition to the honey-combed beams, and concluded ".All concrete'made visible since my visit May 9    is perfectly sound and without imperfection. It is well--
consolidated    and therefore well-bonded around the reinforcing bars.".
Page 3  of  3  - PROGRAM  VI  CONCRETE
 
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1983 LNK 4QIVITY SUBMI T RE ORT  0
      ~: BT RMNr1        8/09/83 0  ENG. PROBLEM AREA  STATUS >
VI CONCRETE CONCERNS 0 CONST. ACTI V ITY    OATUM amrlor3 A
 
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PROGRAM  VII REVIEW OF SITE      UALITY PROGRAMS AGAINST CAT ISSUES DESCRIPTION OF CONCERNS AND            UESTIONS This program      will compare the issues identified by the CAT with site quality programs to assure that the site quality programs have been effective in identifying and correcting quality issues. The program will include      the following tasks.
o      Determine, by analyzing        CAT findings, the extent to which quality programs    identified similar concerns.
o      Analyze the effectiveness of corrective action programs          resulting from such previous identification.
o      Determine      if there are areas other than those    identified  by CAT which should be reviewed.
o      Identify remedial actions to        be taken.
PROGRAMS TO RESOLVE CONCERNS A. Comparison      of CAT  findings  and QVP program (Pre-June  1980  construction)
Perform a comparison of the CAT findings against the pre-June 1980 work scope of QVP. Determine          if QVP and CAT inspected the same hardware to similar or identical attributes.          The analysis will include an assessment of each specific item and an assessment of the trend where similar deficiencies permit trending. The analysis will draw a conclusion as to whether CAT has identified deficiencies which should have been identified by QVP. After completion of the overall analysis of the specifics, the data accumulated will be reviewed to determine        if the CAT inspection has identified weaknesses
            .in the QYP. Appropriate corrective actions will be established for any weakness thus identified.
C B. Comparison      of CAT  findings  and  operational quality assurance  program A  comparison of CAT findings as related to the Test and Startup program will be performed to substantiate or mitigate the findings. The CAT report will be reviewed to identify each specific CAT item related to the operational quality assurance program. Each item will be reviewed to establish specific corrective actions, generic implications            (if any) and a conclusion will be developed as to whether remedial program actions will be taken or not.
Page    1  of 4  -  PROGRAM  VII  REVIEW OF SITE QUALITY PROGRAMS AGAINST CAT ISSUES
 
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A  report will be developed containing the results of the comparison of the specific review, the quality program actions,and corrective action recommendations.            The general  CAT  issues are:
o      Weaknesses in the        Quality Control Program in    use  during Test and Startup.
o      Concerns      related to the adequacy of the bolt torquing.
o      Concerns      related to the control of materials; specifically, bolts, nuts      and washers.
o      Concern      related to Test and Startup closeout of Contract 218 Inspection Reports.
C. Comparison        of  CAT  findings  and construction quality program (Post-June        1980)
A  comparison of CAT findings against the post-June 1980 work scope will    be performed to identify similarities or differences between the CAT issues and the findings of the ongoing construction QA program. The method employed will be identical to the analysis described in Item A.
D. Plant quality attributes not addressed            by  site quality programs This program was initiated to identify and review project cons'truction activities to determine            if site quality programs have adequately verified critical attributes.
Inspection modules, not specific to WNP-2, were reviewed to establish critical attributes. Included were the NRC IEE inspection modules, the attributes for which there were CAT findings at Texas Utilities, and the inspection plans implemented by Bechtel at Palo Verde.
Based on      review of these sources      for critical attributes, the following areas have been          identified for further evaluation of physical installations:
t o    Equipment/raceway grounding.
o    Raceway    instal=lations (assembly attributes).
o    Use  of flex conduit connections to equipment        and panels.
Page 2  of  4  -  PROGRAM    VII REVIEW OF SITE QUALITY PROGRAMS AGAINST CAT ISSUES
 
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Areas  for further evaluation of        h  sical installations: (continued) o  Heat    tracing (Class I).
o    Instrument setpoints (set within ranges and accuracies).
o    Functional interfaces, functional orientation, and special clearances of equipment because of their uniqueness and the potential lack of familiarization by construction of some particular component installation requirements and interactions.
      . STATUS OF ACTIONS TAKEN Activit    A and    C The  specific      CAT items have been  identified    on a computer  listing and  actions initiated to address each.          This analysis is scheduled for completion      September  2, 1983. A  schedule for each activity is attached..
Activit      B An  assessment of the inspection activities performed by Test and Startup personnel has been performed. This assessment has resulted in identifying needed changes to the Startup Deficiency Report (SDR) system. Additionally, operational gA is performing a sample re-inspection of SDR'st Test and Startup personnel are re-reviewing all inspection reports issued by Fischbach/Lord to determine that each has been dispositioned adequately; each will be signed off by the cognizant engineer and contractor reports will be closed accordingly.
Other activities listed under Activity B are ongoing with scheduled Completion of September 2, 1983.
Activit      0 o    Grounding, Flex Connections,        Raceway Assembly, Heat  Tracing.
An  engineering walkdown of    field installations is    being performed    by a  Burns and Roe/Bechtel    engineering team.
o    Instrument Setpoints Walkdowns are being performed to assure setpoints are properly implemented by Startup within the prescribed instrument accuracies, instrument ranges and with correct
                    .elevation compensation.
Page 3  of  4  -  PROGRAM  VII REVIEW OF SITE EQUALITY PROGRAMS AGAINST CAT ISSUES
 
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    ~Ail      D(C      i    d) o    Equipment    Orientation/Interfaces Walkdowns are being performed on        select equipment by Engineering personnel to assess the adequacy of'mplementa-tion of vendor requirements for orientation and AE/NSSS design requirements for functional interface and spatial clearances.
o  Equipment      Orientation/Interface  Walkdown Summary To  date  this task    has selected nine areas to survey with each area having      generally unique attributes. The areas include the following: RCIC turbine skid, hydrogen re-combiner skid,,vacuum breaker valves, excess flow check valves, SW equipment and pump house, expansion joints, rupture discs, concrete block walls and batteries. Attri-butes such as equipment orientation, interferences, and special vendor requirements were observed in each of the areas to ascertain the adequacy of construction for these unique    attributes.
For the sample data collected to date,          it appears that only minor discrepancies exist between the installation attributes and the physical conditions which presently exist in the plant.
One  additional walkdown will      be performed  in the area of flexible connections to      Seismic  1  electrical  equipment such as switchgear and control panels.
Results from the completed walkdowns as well as the additional area  of review are being evaluated and compiled.
Page 4 of 4  - PROGRAM    VII  REVIEW OF SITE QUALITY PROGRAMS AGAINST CAT ISSUES
 
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A~CTIV TY M    R    VP  vs  CAT B    CMP FF C          V    P RT  N    VP TY 2 A) ASSESS TESTESTARTUP                        C B    RESOLVE    IR   CONCERN y  e        i      p D
D TIVITY 3 MPAR      PEST          PR              Mv
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P    T          T F      N PR GRAM-LEO ENO:                            SCf KDVLE IKL SITE QUALITY                      8/09/83  0 ENG. I PROBLEM AREA STATUS i      VII REVIEW'GAINST CAT FINDINGS                    0 CONST. ACTIV ITY    DATUM emrlor3 N        AINT
 
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Latest revision as of 07:52, 4 February 2020

Forwards Info Describing Actions Taken to Resolve Const Issues Identified in IE Insp Rept 50-397/83-29,per 830715 Submittal.Schedules for Completion & Status of Programs Addressing Broad Issues Also Encl
ML17277A773
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 08/15/1983
From: Carlisle C
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
GO2-83-732, NUDOCS 8308300762
Download: ML17277A773 (97)


Text

BEDE!VEO Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington Qp35Z, +09@7(-5/90 830825 8308300762 05000397 PDR ADOCK 8

XE HQ, 'PILE COPY Docket No. 50-397 August 15, 1983 G02-83-732 Mr. J. B. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596

Dear Mr. Martin:

Subject NUCLEAR PROJECT 2 CONSTRUCTION APPRAISAL TEAM ISSUES

References:

1) Construction Appraisal Inspection Report 50-397/

83-29, NRC letter, DeYoung to Mazur, dated July 26,

. 1983

2) WPPSS letter to Region V, G02-83-622, dated July 15, 1983 The purpose of this letter is to provide information relating to issues and concerns reported by the NRC Construction Appraisal Team incident to their May-June, 1983, inspection of WNP-2.

Reference 1) transmitted to the Supply System the report of inspection of WNP-2 by the NRC Construction Appraisal Team (CAT). Reference 2) transmitted to Region V a preliminary report of activity by the Supply System to resolve CAT concerns. Reference 2) stated that seven programs

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Mr. J. B. Martin Page 2 August 15, 1983 G02-83-732 had been established to address the broad issues raised by the CAT. A review of Ref'erence 1) has indicated that the programs established by the Supply System before receipt of the'inspection report do in fact address the major issues. The attachments to this letter contain descriptions, schedules for completion, and status of each program as of this date.

o As-Builting o Non-Destructive Examination o Bolts, Fasteners and Torquing o Welding o Concrete o Engineering Disposition of Deficiencies o Review of Site guality Programs Against CAT Issues Our general approach to the resolution of these issues is:

o Grouping and assessment of related specific issues and consideration of generic implications (for each grouping);

o Formulation of investigative and corrective action programs; o Formulation of detailed schedules for tracking progress on each program; o Consultation with off-site experts on the concrete issue, and with Bechtel's engineering and materials 5 services organizations on as-builting, welding, bolts, fasteners and torquing, and NDE; o Contracting with Stone and Webster to do an independent "third-par ty" assessment of the project as-builting program, and Westinghouse to do a general third-party review of project resolution of the CAT issues; and o Tracking of each specific item in the CAT report to ensure, closure. (This process will be discussed with the NRC resident representative as it is implemented.}

These programs are being given priority attention to ensure successful resolution of the. Construction Appraisal Team issues within our. licensing/

fuel load schedules. We reaffirm our request for an early meeting between Supply System and NRC Region V representatives to discuss these programs and our findings to date. We suggest that this meeting take

l Mr. J. B. Martin Page 3 August 15, 1983, G02-83-732 place at WNP-2 so that those persons responsible for implementation of each program will be available'to provide the details of their investi-gations and findings.

A copy of this letter and the enclosed package is being sent to Mr. R.

F. Heishman for information.

C. . ar ss e - 901A Program Director, WNP-2 HAC/fl Attachments: As Stated cc: Mr. R. C. DeYoung, NRC I&E Mr. R. F. Heishman, NRC QASIP IE Mr. A. D. Toth, NRC Resident, WNP-2

0 TABLE OF CONTENTS MANAGEMENT

SUMMARY

AS-BU ILTING NDE BOLTS, FASTENERS AND TORQUING WELDING ENGINEERING DISPOSITION OF DEFICIENCIES CONCRETE REVIEW OF SITE QUALITY PROGRAMS AGAINST CAT ISSUES

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MANAGEMENT

SUMMARY

Programs were initiated based on NRC CAT exit briefing and subsequently adjusted based on the Final CAT Report received July 29, 1983. The current programs are described in this submittal. These programs address guality Class I work except where Seismic Category I, guality Class II is specifically identified.

Programs are scoped to address all CAT-specific concerns as well as generic implications of CAT-identified deficiencies. These programs will address the root cause of programmatic deficiencies.

Program completions are scheduled with expectations that resolution and corrective actions will be implemented to prevent delays in system sequences necessary to support the WNP-2 fuel load and power ascension testing schedule.

(WNP-2 CAT Program Summary Schedule is provided on the last page of this Management Summary Section.)

Third-party participation has been incorporated into these programs through a Westinghouse overview, the Stone and Webster assignment on as-builting, and independent Bechtel Engineering actions on elements such as the fastener acceptance criteria and assessment of structural concrete. Attachment 1 to this Summary provides a description of the Westinghouse/Stone and Webster work scopes.

The following summaries provide a brief description and status of WNP-2 CAT programs. These programs are described in greater detail following this summary.

H Pro ram I - As-Builtin Stone and Webster will perform a third-party review of the project as-built program including physical inspection of a significant sample of the hangers.

C

2. Project specifications have been. revised to clarify as-builting require-ments, including measurement tolerances, and to disposition variances from design requirements.
3. Bechtel will retrain personnel, re-review the as-built drawings against the new construction tolerances, and submit all out-of-tolerance dis-crepancies to Burns and Roe for evaluation. This process will be independently audited by Bechtel (SFHO) engineering personnel.

Page 1 of 5 - MANAGEMENT

SUMMARY

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4. CAT concerns on the need to finalize as-built guality Class II, Seismic Category I supports are not supported by evaluations performed to date. The previous status as-built program in conjunction with the design margins for these supports being maintained at the level of guality Class I requirements provides substantial assurance that the installations will not fall during a postulated design basis earthquake.

This was further demonstrated for each discrepancy identified by CAT on guality Class II, Seismic Category I supports and the results will be included in the final response to the CAT report.

5. ASME/AISC code jurisdictional boundaries for gC I supports are consistent with code requirements and industry practice at several other nuclear projects. Implementation of this boundary does not degrade the support in performing the required design function.
6. Significant as-builting errors will be made subject to reinspection on a generic basis through use of one or more of the existing project walkdown inspection programs.

Pro ram II - NDE

1. Welds questioned (by CAT review of RT film) meet all code and specifi-cation requirements. This was demonstrated by direct visual examination, macrographic examination and etching of laboratory weld sections or re-radiography. Laboratory work was performed by Bechtel in San Francisco

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with surveillance by NRC personnel.

,2. The radiographs for all Bechtel weld repairs have been re-reviewed (317 welds). Thirteen additional instances were discovered where inadequate weld repairs were caused by failure to compare original radiograph with repair radiographs.

3. The ongoing Phase II film review activity from the HBG radiography reverification program has been completed. One hundred six welds with film quality deviations have been identified.
4. Seven welds with PT indications have been found in an expanded sample covering the work of the same technician questioned by CAT. Six of the seven have been evaluated and found to be nonrelevant/insignificant.

The seventh is still under investigation.

Page 2 of 5 - MANAGEMENT

SUMMARY

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Pro ram III - Bolts, Fasteners, and Tor uin

1. This program addresses four quality attributes on 18 fastener types:

o Material.

o Tightness/torque.

o Locking device/washer.

o Thread engagement.

2. An extensive program is being implemented as indicated by the matrix in the detailed section of this submittal.
3. Field inspections and torque tests 'are being performed on nine cate-gories of fasteners.
4. Acceptance guidelines are being developed where torquing is not required and range of acceptability where torquing is required.
5. Field inspections are in progress in several major categories of fasteners including flange bolting, pipe support fasteners, valve bolting and equipment anchors on non-rotating equipment.
6. Conclusions to date:

o Acceptable As Installed - structural steel bolting, cable tray splices, cable termination screws, blowout panel fasteners.

o 100K Inspections Required - ECCS pump couplings, instrument mounting, warehouse storage segregation of fasteners, and rotating equipment anchor bolts.

Pro ram IV - Weldin

l. The types of weld surface (contour) irregularities identified by CAT at WNP-2 are within code and specification requirements and are enveloped by the code stress analysis.
2. One hundred percent of olet welds within the scope of contracts 215 and 220 are being inspected for sufficient weld reinforcement.'ll cases that do not meet design requirements will be reworked.
3. Availability of weld procedure requirements is currently adequately addressed by Bechtel procedures and instructions. Bechtel welders are trained to the Bechtel weld procedures and attest in writing to their understanding of the "Bechtel Welder 's Guidelines" which identify the location of weld procedures. There is a large sign located in the welding engineers'rea with the words, "Bechtel welding procedures located here. . .". Actual welding observed by CAT concluded that weld parameters were being properly implemented.

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SUMMARY

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4. In response to CAT concerns on the visual acceptance criteria implemented during reverification inspections of structural steel welds, the degree of individual weld characteristics accepted which occur simulataneously on the same joint, will be identified and evaluated (for select critical structural connections). This will demonstrate acceptability on a more conservative basis than previously analyzed.
5. All containment penetration stiffener welds made by PDM under Contract 213 were reinspected. Eight of the eleven have welds slightly undersized or with unequal legs, usually of a 1/8" magnitude. The welds have been technically evaluated and are structurally adequate and acceptable for the application. Additional penetration stiffener welds performed by PDM under contracts 213A and 213B will be inspected.

Pro ram V - En ineerin Dis osition of Deficiencies

1. CAT concerns for an adequately-documented, technical basis for NCR dispositions are being addressed by evaluating for trends the CAT-identified NCRs and NCR dispositions reviewed by the guality Verifi-cation Program.
2. Generic CAT concerns for adequacy of engineering dispositions are being addressed by individually evaluating each identified item for adequacy, assessing any deficiencies against the required Burns and Roe design control procedures, and trending deficiencies for a common cause.

Pro ram YI - Concrete

l. Additional excavations have been performed and variations identified.
2. Design margins exceed all identified construction variations.
3. Third-party reviews are being performed to confirm the adequacy of concrete/structures to perform design basis functions.
4. Excavations will be repaired and analysis of adequacy finalized and submitted in our final CAT report.

Pro ram VII - Review of Site ualit Pro rams A ainst CAT Issues 1

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1. CAT findings are being reviewed against previous guality Verification Program (gVP) results to determine if CAT identified deficiencies which gVP should have identified on work completed prior to June 1980.

Page 4 of 5 - MANAGEMENT

SUMMARY

2. CAT findings on work performed under the Operational Quality Assurance Program are being individually reviewed for corrective action, including generic implications (if any), and the need for program changes to pre-clude recurrence. Inspections performed by Test and Startup engineers are described in approved Startup Program Manuals submitted to the NRC prior to initiation of Startup activities.
3. A comparison of CAT findings on work performed after June 1980 and findings of the ongoing Construction QA program in the same areas is being performed to assess any weaknesses in the current QA programs.
4. Engineering walkdowns are being performed in select areas of completed Quality Class I construction based upon an overview of the areas that QVP and other special programs have previously addressed. The purpose of this t

effor is to identify areas not previously addressed and to increase the level of confidence in the quality of construction in these select areas.

Walkdowns described in the detailed sections of this report are complete and have identified no new generic issues. From this overview, it was evident that incr eased attention should be directed to primary containment work performed by the 213 contractor; this work is currently being addressed by QVP under the PPIA portion of that Program.

From this overview, it is evident that with the multitude of programs being implemented on WNP-2, there are programs redundant to the original construction programs which verify most of the quality attributes that are measurable on completed work.

Page 5 of 5 - MANAGEMENT

SUMMARY

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MANAGEMENT

SUMMARY

- ATTACHMENT 1 PROGRAM OVERVIEW BY WESTINGHOUSE The Supply System contracted with Westinghouse Electric Corporation to provide a technical and licensing overview of the response program. This overview includes a detailed review of the CAT findings, monitoring of the Supply System response program, and evaluation of the results and conclusions of the program. Westinghouse has personnel on site experienced in design, construction and startup activities of nuclear power plants with specific expertise in each of the areas identified in the CAT findings. These personnel are monitoring the work performed under the response program and will ensure that the implementation of the program is adequate and techni-cally sound to assure safe and reliable operation of the plant. At the conclusion of the response program, Westinghouse will submit a report docu-menting the findings of this overview.

AS-BUILT REVIEW BY STONE AND WEBSTER Stone and Webster will perform a third-party review of the project as-built program. The Stone and Webster review consists of four activities:

l. A review of the existing as-built program and it s implementation.
2. A review of the CAT findings in relation to Project and Bechtel gA findings.
3. Physical inspection of a significant sample of the hanger population.
4. An assessment of the as-built program with respect to:

a) Meeting the needs of the project.

. b) Meeting the requirements of NRC IE Bulletin 79-14.

Page 1 of 1 - ATTACHMENT 1 - MANAGEMENT

SUMMARY

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I. AS-BUILTING A. DEVELOP 79-14 GUIDELINES FOR AS-BUILTING B. DEVELOP ATTRIBUTES RE UIRING FURTHER INSPECTION C. WALKDOWN/AS-BUILT D. AS-BUILT TOLLERANCE DISCREPAN IES E. SEISMIC II I CONCERN F. PIPE WHIP RESTRAINT CONCERN G. FINAL REPORT II NDE EVALUATION A. WELD CUTOUT B. M S EXAHINATION C. LI UID PENETRANT RE-EXAM D. NDE FILH UALITY REVIElt

1. 'LEVEL III EVALUATION
2. RADIOGRAPHIC RE-EXAH E. FINAL REPORT V W DING TETLIl PROBLEH AREA SUt%QRY SCHEDULE QCONST.

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PROGRAM I AS-BUILTING DESCRIPTION OF CONCERNS AND UESTIONS The NRC CAT concerns with the project as-built program for large and small bore pipe supports and piping isometrics cover five general areas:

A. Errors in Field Engineering identification 'of hardware dis-crepancies and dimensions on the redline drawings.

B. Errors in Field Engineering dispositioning of hardware dis-crepancies and dimensions by interpretation of. allowable construction tolerances in Burns and Roe,(BRI) drawing H-501.

C. Exclusion of Quality. Class II, Seismic Category I supports from the. project as-built program.

D. The issues regarding ASME/AISC code jurisdictional bound-aries (i.e., the NF boundary descriptions provided on BRI's H-501 drawing) for the design and construction of QCI pipe supports.

E. The pipe whip restraints may not be in the location assumed in the pipe whip analysis.

In addition to these five main concerns, two outstanding questions remain to be answered from the CAT inspection. They are: .(1) Is the direction of snubber safety wiring important?; and (2). Is the orienta-tion of lubrite.plates important?

PROGRAM TO RESOLYE CONCERNS o Develop 'as-builting guidelines based upon 79-14 requirements.

o Review as-builting errors identified by CAT, BQA and PQA expanded sample and rate them as to significance (i.e., effect of the error on the design).

o Based upon significance ratings, identify attributes for necessary additional inspection.

o BRI has added as-builting tolerances to the specii'ication and

.clarified construction tolerances for the H-501 drawing.

Page 1 of 5 - PROGRAM I - AS-BUILTING

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o The project will adjust program, perform necessary inspections and re-review dispositions of past redline discrepancies.

o A third-party review of the total as-builting program has been initiated.

STATUS OF ACTIONS TAKEN A. Concern A Bechtel Engineering has developed a set of guidelines, based upon IE Bulletin 79-14 requirements, with necessary measure-ment tolerances and critical dimensions needed for as-builting large and small bore pipe supports and piping isometrics.

2. Bechtel Engineering and BRI have reviewed.all of the errors identified to date by CAT, BQA, and PQA expanded sample and rated them as to their significance. The signifi-cance ratings, which are a function of the effect of the error on the design, were determined by using the guidelines from Step 1 above.
3. Bechtel Engineering, with BRI concurrence, will determine if there are any attributes which, based upon the signifi-cance ratings from Step 2 above, warrant additional inspection. If there are, they will be covered either by repeating the Bechtel as-built walkdown process for those particular attributes or by using one of the other existing project walkdown inspection programs for piping and pipe supports (e.g., hanger balancing) as appropriate for the particular attributes.

It should be noted that several of the as-builting errors identified by CAT (e.g., snubber cold set, clearances, staking, etc.) are covered and would have been picked up by other project programs which were in, place but not completed at the time of the CAT inspection.

B. Concern B Bechtel and BRI have developed a set of as-builting measurement tolerances for large and small bore pipe and hangers.

2. BRI has prepared a.215 specification revision for as-builting which incorporates the following:

(a) Consolidation of,all as-builting requirements into a single specification section.

(b) As-builting measurement tolerances from Step 1 above.

Page 2 of 5 - PROGRAM I'S-BUILTING

(c) A statement describing how the as-builting measure-ment tolerances relate to the H-501 construction tolerances and how each are to be applied by Bechtel in the preparation of as-built drawings, as well as both Bechtel and others (during the performance of a subsequent gA audit) checking for accuracy of the as-built drawings.

(d) A definitive requirement that Bechtel must submit actual large bore isometric as-built drawings with IRRs regardless of whether or not discrepancies are within H-501 construction tolerances.

(e) A definitive requirement that Bechtel shall evaluate

.all as-built discrepancies from the design drawings against the H-501 construction tolerances and submit, on RFIs, only those discrepancies which are outside the K-501 tolerances. The specification revision also states that small bore isometric and large bore hanger as-built drawings need not be submitted to BRI with IRRs/PRRs.

3. Bechtel has provided comments to BRI for clarification changes to the H-501 construction tolerances.
4. BRI has revised and reissued the H-501 drawing.
5. Bechtel will revise their as-builting procedure SWP/P-6 to conform to the.215 specification and H-501 drawing changes. Items that were required by procedure to be as-built but are covered by other more appropriate existing walkdown inspection programs will be deleted from the SWP/P-6 procedure.
6. Bechtel will review PMI 6-6 against the.215 specification and H-501 drawing changes and provide comments to Supply System Engineering.
7. -

Supply System Engineering will, if necessary, revise PMI 6-6 for reconciliation with the 215 specification and SWP/P-6

~ - changes.'.

Bechtel will conduct a documented training session to cover the.215 specification and SWP/P-6 changes.

9. For those cases where the new.215 specification does not require Bechtel to submit as-built drawings to BRI with IRRs/PRRs, Bechtel will re-review the as-built drawings against the new H-501 construction tolerances and submit all out-of-tolerance discrepancies to BRI on RFIs.

Page 3 of 5 - PROGRAM I AS-BUILTING

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10. Bechtel Engineering (SFHO) will audit Bechtel Field Engineering dispositioning of as-built discrepancies from Step 9 above.

C. Concern C The CAT concern is essentially the same as NRC unresolved Item 83-05/05. Letter G02-83-622 to NRC Region V, dated July 15, 1983, transmitted a paper stating the Supply System's position with respect to as-builting guality.Class II, Seismic Category I hangers and the rationale supporting that position.

D. Concern D The CAT concern is essentially the same as that described in the NRC Notice of Deviation 83-22 ( Item 82-18/02). The response to this concern is contained in the Supply System's letter G02-83-701 to NRC Region V, dated August 5; 1983.

E. Concern E BRI will measure the actual location of pipe whip restraints on the piping run and perform evaluations to determine the acceptability of the as-constructed location. The measurements and evaluations will be included as part of the pipe break/

missile protection walkdown and study to be performed by BRI.

F. . uestions. 1 and 2 Although not mentioned in the attachments to this letter, the question concerning the direction of snubber safety wiring is being addressed by Program III - "Bolts, Fasteners and Torquing".

Supports with lubrite plates, where orientation is critical, will be inspected to assure proper orientation.

G. Third-Part Review Stone and Webster, acting entirely independent of the above-described program, is performing a third-party review of the project as-built program The Stone and Webster program consists of four activities:

o A review of the existing as-built program and its implementation.

o A review of the CAT findings in relation to previous PgA and B(A findings.

o Physical inspection of a significant sample of the hanger population.

Page 4 of 5 - PROGRAM I AS-BUILTING

o An assessment of the as-built program with respect to:

Meeting the needs of the project.

Meeting the requirements of NRC IE Bulletin 79-14.

Page 5 of 5 - PROGRAM I AS-BUILTING

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PROGRAM II NDE DESCRIPTION OF CONCERNS AND UESTION The NRC CAT concerns with the project nondestructive examination are identified below, referenced to CAT Report 50-397/83-29.

A. Radio ra hic Film Review - Ref. CAT IV-B-4 Wel d ual i t The following welds were identified as having weld quality defects:

(a) RHR 882-1.4, 'FW-6Rl - Root Linear Indication (b) RHR 854-12.16, FW-14Rl - Root Linear Indication (c) LPCS 756-1.4, FW Linear Indication (d) RHR 851-18.19, FW-12ARl - Wrong Repair Area Film (e) LPCS 756-5.7, FW-17R2 - Linear Indication (f) RFW 438-3, FW-1Rl - Linear Indication

2. Film ualit From the review of WBG Phase II radiographic film for film quality, rejectable densities were identified on the radiographs for RRC-1819-2, FW4; RRC-1819-2, FW7; and RRC-3083-1, FW1.
3. Film Artifacts Radiographs for two welds were identified as having film artifacts:

(a) CAC 088-1, FW6 (b) CIA 4131-1, FW10 B. NDE Personnel Interviews and Methods Evaluation IVB5 Bestco NDE procedures were considered to provide inadequate direction for evaluation of weld surface conditions prior to performance of nondestructive examination.

2. NRC CAT identified two welds that were re-examined by liquid penetrant and found to have rejectable indications.

Page 1 of 4 - PROGRAM II NDE

3. Bestco radiographic procedures were considered to provide insufficient direction in the following areas:

(a) Selection of radiographic techniques by NDE operators.

(b) Application and use of film markers on repair areas.

(c) Lack of specific instruction regarding film orientation and technique.

(d) The use of more than two film per cassette.

PROGRAM TO RESOLVE CONCERNS o Examine welds thought to have rejectable indications by destructive or nondestructive examination to resolve inter-pretation differences.

o Review radiographs of all repair welds made by Bechtel; resolve additional questions.

o Review remaining Phase II radiographs for film quality.

o Re-radiograph films considered by CAT to have film artifacts.

o Review liquid penetrant procedures.

0 Review Bestco procedures for radiography and other NDE.

STATUS OF ACTIONS TAKEN A. Radio ra hic Film Review Weld ualit Welds previously identified as items (a), (b), (e) and (f) have been evaluated by Bechtel's Materials and guality Services Department. The evaluation included direct visual examination, laboratory weld sectioning, macrographic examination, etching, and photographic preservation. A detailed description of this activity is being prepared and will include supportive laboratory reports and photographs. Item (c) was investigated while the CAT was on site and found to be satisfactory. See Program IV, point 4 under STATUS OF ACTIONS TAKEN, for a complete discussion of item (c).

The evaluation activities are complete for items (a), (b),

(c), (e) and (f). The results of this evaluation indicate weld items (a), (b), (c), (e) and (f) meet.all specification and code requirements.

Item (d) involved a weld repair error caused by failure to Page 2 of 4 - PROGRAM II NDE

l review the original weld radiographs in conjunction with the repair weld radiographs. A commitment to review all radiographs of Bechtel repaired welds has been completed.

A total of 317 weld repairs were reviewed. Fourteen repair welds were identified for further evaluation.

Nonconformance reports have been prepared for the 14 weld repairs. Two welds were found with the wrong area repaired.

The remaining 12 welds had inadequate film coverage.(l),

defect identification discrepancies,(10), and incorrect interpretation.(1). With the exception of the one incorrect interpretation, all errors are directly related to not com-paring the original radiograph with the repair radiograph when performing the repair evaluation.

Additional actions taken are:

l. Written instructions are being prepared to assure that original radiographs are compared with repair radiographs to provide corrective action to prevent recurrence.
2. The item has been identified as a potentially reportable 10CFR50.55(e). The undiscovered defects in each of the 14 welds have been analyzed by fracture mechanic' techniques described in Section XI of the Code. The results indicate that the stress intensity factors for the defects are lower than the critical values for the materials involved.
3. Because of the one incorrect interpretation, an additional sample review of 61 production r adiographs, originally interpreted by the same NDE technician, was performed.

This resulted in finding one additional radiograph with a marginal porosity condition. This condition is still under evaluation by Level III NDE personnel.

The remaining WBG Phase II radiographs have been reviewed and 106 welds identified with minor film quality deviations. The guality.Class I welds are identified by nonconformance reports for resolution of the discrepancy.

3. Film Artifacts Three radiographic views covering two welds have artifacts from film processing. Despite the film artifacts, the film is interpretable when the two films for each view are compared one against the other. This is a code-permitted and industry-accepted practice and is the primary reason for using Page 3 of 4 - PROGRAM II NDE

I two films in each cassette for industrial radiography. Never-theless, to dispel any lingering doubt it was agreed to reshoot the three views for welds CAC-088-1, FW6, and CIA-4131-1, FW10. However, CAC-088-1 was cut out prior to the CAT inspection.

CIA-.4131-1 was re-radiographed and the film accepted. No further corrective action is necessary as there was no code nor specification violation.

B. NDE Personnel Interviews and Methods Evaluation

1. The Bestco procedural practices (Items Bl and B3) are within specification and code requirements. Level III personnel are reviewing current NDE procedures and practices to identify any areas that may need strengthening, and/or to verify procedure and practice acceptability. References to Bestco RT procedure, RT194A, Rev. 4, in the CAT Report, appear to be in error. This procedure has not been implemented on this site.
2. The two-weld PT sample described by CAT was increased to five welds to cover.all PT examinations made by the same technician on the same day on the same isometric. PT indications similar to those found by CAT were discovered on all five welds. The sample was then increased again to 39 welds (34 additional),

all originally examined by the same technician but over an extended time period on different isometrics. Seven welds with PT indications were found; the five original ones. plus two more from the additional 34-weld sample. Six of the seven welds with PT indications were. blended by filing to remove the indications and determine their cause. .All six indications were found to be nonrelevant or insignificant. No weld repairs were necessary.

Access problems have delayed removal and investigation of the PT indications on the one remaining weld. This weld will be investigated in a manner similar to the other six as soon as possible.

Page 4 of 4 - PROGRAM II NDE

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PROGRAM III BOLTS, FASTENERS AND TOR(jUING DESCRIPTION OF CONCERNS AND UESTIONS The NRC CAT found discrepancies in bolting material on equipment and piping systems. In addition, they raised questions as to the adequacy of specified torquing requirements and the results apparent in the installation of several types of fasteners.

PROGRAM TO RESOLVE CONCERNS

~Pur ose Provide assurance that Ouality Class I and guality Class II, Seismic Category I fasteners installed on WNP-2 are:

The proper material Adequately tightened/torqued for their intended function Installed with an adequate locking provision or flat washer as required Installed with the proper thread engagement

~Sco e Implement a deficiency trending program to review types of fasteners provided by suppliers, installed by contractors on site, and disassembled/reassembled by Test 8 Startup to assure that verification exists that the final fastener installation is adequate. If no verification exists, sample inspection programs will be established to provide this verification.

o Re-evaluate and document the technical basis for existing specification requirements on tightening/torquing and material of, fasteners.

Pro ram Descri tion A. The Bolts, Fasteners and Torquing Deficiency Trending Program is described in the attached matrix (Attachment 1). This matrix identifies 18 fastener types which represent the major guality

,Class I and guality Class II, Seismic Category I fasteners used on WNP-2. For each fastener type, four critical attributes are considered: material, tightness/torque, locking device/washer, and thread engagement. The matrix also identifies the major installers Page 1 of 3 - PROGRAM III BOLTS, FASTENERS AND TOR(UING

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of each type of fastener including suppliers, site contractors, and Test 5 Startup. (Note the matrix indicates information developed to date.)

For each major installer of a particular fastener type, a checklist is prepared. This checklist covers the installer's scope of work, specification requirements, installer's procedures, previous in-spections of this work conducted in addition to normal installa-tion, and the CAT findings. This checklist forms the basis'for deciding if additional inspections are required. Previous in-spection programs, NRC audit findings, and additional inspection programs needed are summarized in the matrix.

The results of the identified sample programs, plus the CAT findings will be analyzed for trends to see if further inspections are required.

B. The A/E, Burns and Roe, will re-evaluate the technical basis for existing specification requirements for fasteners, including an assessment of a small percentage of randomly scattered variations in tightness and materials, justification for the use of flat washers on slotted holes, and an assessment of bolt relaxation with use. Included in this evaluation will be guidelines for evaluating torque data on bolting for acceptability, considering both passive boundary and structural loading performance.

C. An independent organization, Bechtel, will provide an assessment of the effect of randomly scattered variations in tightness and materials for flange bolting, use of flat washers on slotted holes, and an assessment of bolt relaxation.

D. The sample inspection of final in-.place hardware will be the verifica-tion of material adequacy. In the case of Bechtel and the Supply System, additional documented audits, of warehousing will be performed to assure adequate material control.

STATUS OF ACTIONS TAKEN A. Overall program schedule is shown on Attachment II.

-t As indicated in the matrix (Attachment I), the major fastener types have been identified along with the major fastener installers. In addition, checklists have been completed to identify the areas where additional sampling is needed.

Sample programs have been established in the areas indicated. These programs include a procedure for performing the inspections, train-ing of personnel involved in making the inspections, and initiation of field inspections.

Of the 18 major fastener types, conclusions have been reached on Page 2 of 3 - PROGRAM III - BOLTS, FASTENERS AND TORQUING

six types as indicated below:

.81 Structural steel bolting - Acceptable b7 Instrument mounting - Test 8 Startup to add 100 percent bolt inspection to System Lineup Test-I-4 89 Rotating equipment coupling installation A. Test 5 Startup to reinspect.all ECCS pumps with a follow-on maintenance surveillance program.

B. Test & Startup to check torque and material on 12 additional pump groups.

,812 Cable tray splices - Acceptable

,5'14 .Electrical cable termination screws - Acceptable 816 Blow-out panel fasteners - Acceptable Tornado siding fasteners - Acceptable B. The Architect/Engineer, Burns and Roe, has prepared a technical memo which addresses the technical issues on bolts, fasteners, and torquing. In addition, they have established guidelines for re-viewing field sample data.

C. Bechtel provided an assessment of the technical issues concerning fasteners. This assessment supports the basic A/E positions.

D. Bechtel warehousing reinspected their fastener storage facilities in total and this effort has been audited by Bechtel gA.

Page 3 of 3 - PROGRAM III BOLTS, FASTENERS AND TORgUING

0 WNP LP BOLTS, FASTENERS AND TORQUING DEFICIENCY TRENDING MATRIX ATTACWCNT I

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1983 AU IEL SAM LES EGIN ING /21 R G RA BPE O. ILS R P R F D E. REVIEM BY FASTENER TYPE fl STRUCTURAL STEEL BOLTING PREPARE

SUMMARY

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STATUS DATUN i

I ATTACHNENT II

PROGRAM IV WEL DING DESCRIPTION OF CONCERNS AND UESTIONS The NRC CAT concerns with the project welding program cover five general topics:

A. Improper weld surface appearance/contour.

B. Insufficient weld reinforcement on weldolets.

C. Lack of knowledge of welding parameters by some welders; availability of welding procedures to the welders.

D. The general use of gVI-09 for reverification inspection of structural steel welds.

E. Undersized fillet welds on containment penetration stiffener

. plates.

There are no outstanding questions to be answered other than those pertaining to the above concerns.

PROGRAM TO RESOLVE CONCERNS A. Improper weld surface appearance/contour

l. A detailed study has been made of the actual welds examined by the NRC CAT to determine their acceptability under the requirements of the ASME Code and project specificiations..
2. The acceptability of the "toe-to-toe" fillet welds on LPCS-7591, FW4 and FW5 has been determined.
3. Inspection requirements and training for accepting weld contours (surface appearance) has been reviewed.

B, Insufficient weld reinforcement on weldolets

l. All Supply System guality Class I weldolets and other olet fittings within the scope of Contracts 215 and 220 have been identified by review of applicable drawings.
2. An inspection program, including inspection criteria and inspector training has been developed to inspect olet welds.

Page 1 of 9 - PROGRAM IV - WELDING

3. One hundred percent of olet welds within the scope of Contracts 215 and 220 are being inspected for weld reinforcement.
4. All nonconformances identified during step 3 are being documented on appropriate nonconformance reports.

C. Lack of Knowledge of welding parameters and availaibility of welding procedures.

1. The existing site program has been reviewed.
2. The results of this review are presented in the Status of Action Taken in this report.

D. The general use of QVI-09 for reverification inspection of structural steel welds:

1. The BRI technical basis for the criteria contained in QVI-09 has been provided to the NRC.
2. Determine the degree to which welded structural connections contain multiple attributes not meeting AWS D.l.l but meeting QVI-09.
3. Several critical structural connections will be selected and evaluated against QVI-09 to determine if mulitple attribute deficiencies are acceptable.

E. Undersized fillet welds on containment penetration stiffener plates:

l. All containment penetrations with stiffener plate fillet welds made by PDM under Contract 213 have been identified.
2. All the above welds have been inspected and nonconformances have been documented.
3. All nonconformances have been dispositioned by Burns and Roe as "accept as is" based on an engineering evaluation.
4. Identify all other containment penetrations with stiffener plate fillet welds made by PDM under subsequent contracts with augmented QA programs.
5. Inspect all the above welds and document any nonconformances.

Page 2 of 9 - PROGRAM IY - WELDING

STATUS OF ACTIONS TAKEN A. Improper weld surface appearance/contour The NRC CAT report states that their concerns for weld contour are based upon:

1. Two welds (actually 3 welds) exhibited improper fillet weld contour.
2. Numerous other welds examined by the NRC CAT inspectors exhibited marginally acceptable contour and surface appearance.
3. Two welds failed PT examination; possibly due to surface conditions.
4. For one weld, it was necessary to grind the weld surface to obtain an acceptable radiograph.

Based upon the above four points, the NRC CAT questioned the adequacy of training for weld engineering and inspection personnel, and concluded that a review of the procedures and training (re-training) program of BPC field engineers and gC inspectors is warranted.

A detailed study of each of the above four points reveals the following:

Point 1:

The three welds referred to in 1) above are:

a) NS-522-3.4 pipe-stanchion-to-pipe fillet weld for support NSRV-4C-8 b) LPCS-759-1, FW4 (fillet weld) c) LPCS-759-1, FW5 (fillet weld)

Weld a) did not require nondestructive examination other than visual inspection. Therefore, the Code requirements of NB4424 were met in that the weld was sufficiently free from coarse ripples, grooves, overlaps, abrupt ridges and valleys to make it suitable for interpretation by visual examination.

Page 3 of 9 - PROGRAM IV - WELDING

Other than the requirement that weld surfaces be suitable for NDE interpretation, fillet weld bead contour is not addressed in the code or specifications because it is not a technical concern. The WNP-2 design assumes that welded joints are in the as-welded condition unless specifically designated to be otherwise. The code-specified stress indices, or stress intensification factors, for as-welded surfaces were used in the design. These stress indices take into account the "ropey" appearance which is inherent in stringer bead fillet welds, similar to weld a). Although weld a) was not aesthetically appealing, the weld contour surface appearance was nevertheless completely acceptable from design, code specification and structural integrity points of view. The weld was, nevertheless, reported on a NCR and reworked to help expedite resolution of the NRC CAT's concern. Further discussions with the NRC CAT reached agreement that all other specific welds identified by the NRC CAT as questionable met all code and specification requirements.

The welds b) and c) did require PT examination. Both welds wer e so examined during construction and again during the CAT inspection.

The surface condition of the welds was such that there was no difficulty in interpreting the results of the PT examination.

Therefore, the requirements of NB4424 were met.,

A second "weld contour" question concerning welds b) and c) was raised by NRC CAT. This question had to do with the included angle at the intersecting toes of the two adjacent fillet welds, see attached photograph.

Welds b) and c) are both socket welds between 3/4" schedule 160 SA-106B pipe and 3/4" 6000 4 SA181 GR II socket weld fittings. The welds are such that the toe of weld b) and the toe of weld c) touch. As we understand it, the Inspector's concern is the existence of an unaccounted for structural discontinuity. The existence of this type of condition is not precluded by any project procedure or specification, and is not in violation of any code requirements. The existing condition is within construction tolerances. The WNP-2 A/E (Burns and Roe) has reviewed this specific application and determined that the close proximity of the welds is acceptable. Further, the A/E has determined that the condition is very limited, possibly one of a kind, and that any other similar conditions are likewise acceptable.

Page 4 of 9 - PROGRAM IV - WELDING

hk Point 2:

All of these welds were judged acceptable by the CAT. See above discussion of weld a) for additional information.

Point 3:

The two welds which failed PT are the same two identified as welds a) and b) under Point 1 above. The PT failures are discussed in a separate report covering the resolution of CAT concerns:with JJDE. As pointed out in the discussion above, and as shown in the attached photograph, the surface appearance of these two welds is totally acceptable.

Point 4:

At the time of construction completion, it was not necessary to grind the surface of this weld (LPCS7561.4, Weld 6) to obtain a satisfactory radiograph. Reader sheets are available at the site to show that the film was reviewed and accepted by Bechtel under the WBG radiography reverification program on April 7, 1982. During the CAT inspection, the NRC consultant for NDE interpreted the radiograph as showing evidence of incomplete fusion. The code rules of NB4424 state:

"In those cases where there is a question regar'ding the surface condition on the interpretation of radiographic film, the film shall be compared to the actual weld surface for interpretation and determination of acceptability."

The film and weld comparisons were made and project personnel were satisfied with the comparisons. However, agreement could not be reached with the NRC CAT and accordingly the weld was ground and re-radiographed. The grinding and reshooting were done to prove clarity and that the original film interpretation made under the WBG radiograph reverification program was done correctly. This re-radiograph clearly confirms that the weld was acceptable and that the previous radiograph was acceptable and interpreted correctly.

In summary, weld surface appearance is acceptable provided that proper nondestructive examinations are achievable.

Bechtel's welding engineers and gC inspectors are trained specifically to inspect weld surface characteristics and it is a specific inspection step in the Project guality Control Instructions. The types of weld surface irregularities identified at WNP-2 are within code and specification requirements, Page 5 of 9 - PROGRAM IV - WELDING

and enveloped by the code stress analysis. detailed study of the four points made by CAT regarding weld contour shows that weld surface appearance is not an issue of concern at WNP-.2.

B. Insufficient weld reinforcement on weldolets The HRC CAT identified cases of insufficient weldout on the branch fitting to run pipe weld on olet-type (weldolet, sockolet, elbolet, etc.) weld-on branch connection fittings. With the exception of one case, all such welds identified were on stainless steel piping systems where the run pipe was relatively thin-walled and the olet-type branch connection fitting was standard or heavy (extra or double extra strong) wall. These types of applications can result in excessive distortion in the run pipe in the weld zone. This potential problem was identified by a previous contractor and the A/E was requested in 1979 to allow for lesser weldout in these instances (reference: RFI 4563W). The A/E's response to this request was that generic approval could not be given, and the contractor was required to identify any applications receiving limited welding on a case-by-case basis to the A/E.

Weld-on olet-type branch connection fittings are widely used in the nuclear industry and at WNP-2. The fittings have been available in a wide variety of sizes and schedules (thicknesses). Although fittings for thin-walled (schedule 5S and 10S) stainless were not commercially available until recently, fittings for virtually all other applications were available. At WNP-2, the O'E designed many branch connections utilizing olet-type fittings with a greater wall thickness than required f'r pressure integrity. This practice resulted from the fact that schedule 5S and 10S fittings were not available, the requirement for a specific inside diameter on the branch to accommodate a specific thermowell or sample probe, and for reasons of design conservatism.

Although numerous cases were identified to the A/E, documentation does not exist to substantiate many of the known cases that have less than full weldout.

A corrective action program, as descr ibed below, was implemented to correct this deficiency. The existing welds are such that the design drawings do not specify a weld size, but the specification requires that the fittings be installed to the manufactuer's instructions.

Although the manufacturer's instructions are clear that the welds should be made fully to the weld line, this point is often difficult to locate on a fitting with a completed weld and in the case of some Page 6 of 9 - PROGRAM IV - WELDIflG

't P

applications, impossible to achieve due to excessive weld distortion and/or geometrical limitation. With due consideration of these facts, it is believed that the existence of conditions precedent to this problem do not exist. With due consideration of these facts, it is believed that the existence of undersized welds on olet type fittings is no indication of weld or weld documentation problems on other types of welds where the unique conditions precedent to this problem do not exist.

The corrective action program for weldolet concerns consists of an isometric/drawing review, inspector training, in situ walkdown, A/E evaluation of deficiencies, and rework necessary.

if The isometric drawing review consisted of a 100 percent review of all Supply System Quality Class I large bore and all small bore piping within the scope of contract 215 and all Supply System Quality Class I piping within the scope of'ontract 220. Approximately 970 olet-type branch connection fittings were identified. This review identified the location, type and size of the olet-type fitting.

The inspector training program consisted of instruction by Bechtel construction field welding engineers to the quality control inspectors in identification of fitting type and manufacturer, manufacturer's welding requirements (using both pictorial references and actual as-welded hardware samples), and evaluation techniques. Subsequent weld inspection is being performed and documented in accordance with Quality Control Instruction QCI 14631/Pl.ll.

All deficiencies indentified by the quality control inspectors are being documented on a proper nonconformance document and forwarded to the appropriate design organization.

All cases found to not meet the requirements of the design and/or manufacturer will be identified to construction to be reworked to an acceptable condition.

C. Weld rocedure availabilit knowled e During their site visit, the NRC CAT witnessed in sj,tu welding.

During specific in-process weld inspection, the CAT members questioned welders as to the requirements for that specific weld (weld procedure, weld size, travel speed, amperage, etc.). Although, in each case the weld was made to the correct procedure (size, speed, amperage, etc.), the actual welder did not, when questioned, state knowledge of the Page 7 of 9 - PROGRAM IV - WELDING

weld procedure number, did not have a copy of the weld procedure, and did not profess knowledge of procedure ava i 1 abi 1 i ty.

The WNP-2 project program for welding procedure availability is that all required procedures for performance of the actual work are made available to the welders. The weld procedure is not required to be present at the work station. Welding procedures are made available to welders at the welding material issuance stations.

Each welder at WNP-2 is instructed in and given a copy of the document, "Bechtel Welder's Guidelines". This document, among other things, instructs the welder that welding procedures are available from the welding engineer. There is a large sign located in the welding engineers'rea with the words "Bechtel Welding Procedures Located Here...". All welders at WNP-2 have signed a statement attesting to the fact that they have read and understand the Bechtel Welding Guidelines. The signed statements are retained on file with the Bechtel Lead Melding Engineer.

Specifically, with regard to the NRC CAT concern regarding fillet weld size requirements for socket welds, all welders have been instructed to weld the fittings fully to the edge of the hub, even though the project specifications require that the weld leg be a minimum of 1.09 x t of the connecting piping (which is equal to or less than the full hub thickness).

The actual welding witnessed by the NRC CAT confirms this welder instruction.

The fact that all welding witnessed by the CAT members was to the requirements of the applicable procedures shows that the welders are knowledgeable of the requirements. Craft personnel, when questioned by non-manual personnel, are apt to make a wide variety of statements, depending upon the manner and wording of the questioning and the attitude of the particular craftsman. Me believe that the training of welders is best reflected in both the results of their performance qualification tests and the actual quality of workmanship in the completed welds. Me continue to train each welder to the Bechtel Welding Procedures and Guidelines and while doing so impress upon each craftsman the necessity for understanding and following the procedures. Each welder is firmly instructed that deviations from the procedures and guidelines will result in disciplinary action.

Page 8 of 9 - PROGRAM IV - MELDING

D. The general use of (VI-09 for the reverification of structural steel The NRC CAT identified that some structural steel beams do not meet the visual acceptance criteria of AWS Dl.l. This led to a general concern regarding the use of (VI-09. Specifically, CAT appears to be concerned that the use of gVI-09 may not be adequately justified in that conclusions reached in the structural steel reverification program should reflect the consideration of all allowed weld deviations, and a detailed review of the more critical connections. The program for resolving this concern is still in the data gathering stage..

Page 9 of 9- PROGRAM IV - WELDING

I 51

A WEI.D SURFACE APPEARANCE WRITE POSITION PAPER BRI REVIEW/COMMENTS FINALIZE PROJECT POSITION PAPER 8 WELD PROCEDURE AVAILABILITY CONFIRM ACCEPTABILITY OF EXISTiNG PROGRAM KITH A. TOTrl DEVELOP PROJECT POSITION PAPER C OLET YELDOUT EVALUATION PROGRAM ISOMETRIC REVIEW O.C. WALKDOWN INSPECTION BQC T ON C. INSPECTOR TRAINING BOC T FAL ON ENGINEERiNG EVALUATION CONSTRUCTION FALLOUT IF RE 'D FINAL REPORT D CONTAINMENT STIFFENER WELD EVALUATION PROGRAM INSPECT WELDS DRYWELL GENERATE NCR'S(DRYWELL ENGiNeERING EVALUATION DRYWELL RENDU RESl ETW LL A CESS WETWELL INSPFCTION ENGINEERING EVALUATION IF RE WRITE REPORT E OVI QVI-09 BRI REVIEW OF RB444 BRI L OUANTIFY DEGReE OF MULTI-DISCREPANCY WELDS BRI CRITICAL CONNECTION REVIEW BRI WRITE REPORT BR BPE h T 8 S SUBMIT FINAL REPORT ANSWERING CAT BPE OM WELDING FINDINGS IH PECT ON S 952 OTA 952 HIT K NCP PPR VED CAT WELDING ISSUES 2 RJS 8/08/83/ 0 ENG. P PROBLEM AREA STATUS >

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pi J 7 I f F, ' i ~ I l'l l <> qao->> (E4, C PROGRAM V ENGINEERING DISPOSITION OF DEFICIENCIES DESCRIPTION OF CONCERN AND UESTION The CAT Report questioned NCR dispositions and the adequacy of the design drawings to properly reflect design calculation requirements with respect to concrete structures. PROGRAM TO RESOLYE CONCERNS

l. Analyze NCRs questioned by CAT during inspection; compare gVP Report on NCR dispositions with CAT NCR sample; draw conclusions; and, if analysis indicates action to be taken, strengthen procedure/program.
2. Analyze CAT Report and develop a matrix of the items related to concrete and reinforcing steel identified by the CAT or by the project during the study of the CAT concrete issue.
3. Prepare a response to each item from the matrix.

(a) Identify item (b) Provide an assessment of adequacy (c) Establish a position (d) Propose actions to be taken, if warranted

4. Evaluate items and responses related to the concrete issues for possible trends.

a) Draw conclusions as to adequacy of engineering position b) For items found deficient, categorize as to type {c) Assess deficiencies for trends 5: Prepare a paper defining Burns and Roe's process for approving contractor submittals. Evaluate deficient items from 4 above against design approval process (i.e., followed or not followed)

6. Propose action necessary from the analyses of 4 and 5 above.

STATUS OF ACTIONS TAKEN Action Item 1- 755 complete..All NCRs have been analyzed. Page l of 2 - PROGRAM Y ENGINEERING DISPOSITION OF DEFICIENCIES ,I One NCR requires disposition. Results to date contained in attachment. Action Item 2-6 Work is underway. Matrix is being developed. Page 2 of 2 - PROGRAM Y. ENGINEERING DISPOSITION OF DEFICIENCIES ATTACHMENT PROGRAM V . ENGINEERING DISPOSITION OF DEFICIENCIES NCR DISPOSITIONS Twenty-seven NCRs were identified in the CAT synopsis. Twenty-six NCRs have been evaluated and one NCR has not been dispositioned as of this date. The results of this evaluation are as follows:

1. Statistical Information:

(a) Disposition Use as is -. 17 Rework - 3 Repair - 3 Void - 3 (b) Disciplines Making Disposition Mechanical - 1 Electrical - 2 Ci vi 1 -17 Hangers - 2 - 5 (3 voids; 2 IRs, no A/E involvement) (c) NCR Initiation Dates 1976 -. 1 1978 -, 1 1980 -. 1 1982 - 7 1983 -. 17

2. Evaluati on:

This evaluation concurred fully with 24 of 26 dispositions provided. Two NCR dispositions were not considered totally adequate and are discussed below: NCR.218-8034

Subject:

ASTM A-307 bolts not marked with manu-facturers'dentification.

Page 1 of 3 - ATTACHMENT PROGRAM V

Disposition: Use as is.

Justification: Concurred with proposed technical justi-fication provided by the contractor which stated the bolts were certified to ASTM A-307, IFI standards do not require any marking, and.all commercially avail-able bolts are ASTM A-307.

Analysi s: The proposed disposition provided by the contractor should have been rejected and a revised disposition provided by the A/E.

l. The statement made in the NCR, ",All commercially available bolts are A-307 steel" is not accurate and does not represent the statement made by Mr. H. Houten of Fasteners, Inc.

(telecom attached to NCR).

2. The IFI Standard identified as being attached to the NCR was not attached. The IFI Standard intended to be referenced (checked with con-tractor to identify the IFI Standard) only identifies that no grade marking is required. It should be noted that ASTM A'-307 also does not require grade marking.

Conclusion:

The use-as-is disposition of NCR.218-8034 is acceptable based upon the fact that the contr actor had, from the supplier, certification that the bolts were ASTM A-307 bolts (even though they had no manufacturers'dentification), that ASTM A-307 bolts are the lowest strength level (60,000 ultimate tensile) carbon steel commercially produced, and that ASTM A-307 does not require mechanical testing on a lot basis. Testing is ac-complished based upon mass production from stock which provides the assurance of quality, material, and manufacturing pr acti ce.

Even though the unmarked bolts are structurally adequate, the NCR disposi-tion should have required the contractor Page 2 of 3 - ATTACHMENT. PROGRAM V

to purge his stock of unmarked bolts to prevent the administration problems associated with continuing usage. It should be noted that per the contractor, Mr. Hollenbach, the stock was purged even though not specifically required by the NCR disposition.

Subsequent to the CAT identification of this NCR, a sample of unmarked bolts were removed from field installations and mechanically tested. .All met the require-ments of ASTM A-307.

NCR 500-021376

Subject:

Meld defect (Lack of Fusion).

Disposition: Use as is.

Justification: Existing weld adequate for the load.

Analysis: The existing weld is structurally accept-able although the disposition to accept the lack of fusion in the weld is in violation of AHS.Dl.l and should have been repaired (weld defect ground out).

Conclusion:

The use-as-is disposition of NCR 500-021376 is acceptable. Further evaluation has indicated that the entire weld could be

.eliminated without affecting the structure and that the weld is in compression and would not be expected to propagate into the base material.

The results of this evaluation confirm the findings of the QVP review of A/E NCR dispositions. The QVP review concluded that: "It can therefore be stated with a 95K confidence that in-.,exces's-of 99K of all documents dispositioned by BRI are technically adequate."

Page 3 of 3 - ATTACHMENT- PROGRAM V

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19 INK ACTIVIlY 14 R's I NT F BY CAT NCR EQUI ES C HPL ION OF A LYS R"

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ENGINEERING DISPOSITION CI ENG. P PROBLEN AREA STAUS V

OF DEFICIENCIES 0 CONST. ~CTIVITY DATtw i ~a~~

PROGRAM VI CONCRETE DESCRIPTION OF CONCERNS AND UESTIONS From the CAT Report:

"(1) Rebar.placement deficiencies with respect to ACI.318-71 Code and design specification requirements have been identified in 10 of 12 examined locations. These will have varying degrees of adverse impact on the .strength of concrete structural, elements, ranging from significant to insignificant. (The issue of grout patch integrity had been identified previously and is being pursued by Region V personnel (see Inspection Report = 50-397/83-14)).

(2) The ability of the initial HNP-2 gC inspection records, RFIs and NCR dispositions to establish overall conformance with the design specifications is questionable.

(3) The accuracy with which the design drawings reflect confor-mance with the design calculation requirements is question-able.

(4) The visual inspections and documentation reviews .proposed by the applicant are of insufficient depth and scope to address the issue of rebar placement adequacy. In addi tion, the destructive examinations discussed above are insufficient to completely characterize the extent of the rebar placement deviations at these locations and to provide a sufficient data base to infer the extent of deviations throughout the facility.

Therefore, there is not reasonable assurance that the reinforced concrete members and structures at HNP-2 were constructed to provide sufficient strength to adequately conform to the FSAR design requirements."

PROGRAMS TO RESOLVE CONCERNS o Perform additional excavations and increase the scope of existing excavations sufficiently to define the spectrum of possible reinforcing bar placement problems.

o Record the "as-constructed" condition at each excavation, paying particular attention to bond between concrete and steel; the existence of voids in the concrete; and the location of re-infor cing steel.

Page 1 of 3 - PROGRAM VI CONCRETE

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o Review all existing pour records for engineering direction given relative to the excavated structures.

o Analyze the structure as-constructed at each excavation and compare this analysis with the original design objectives to determine the significance of the deviations observed.

o Review the process for control of engineering approval on contractor submittal of steel details and compare NCRs, RFIs and steel details with sample excavations. This will be done in conjunction with CAT Program V - Engineering Disposition of Def i ci enci es.

o Draw conclusions with respect to the adequacy of the structure to meet its intended function based on the sam'pling done.

o Assessment of off-site experts with respect to condition of bond between steel and concrete at each excavation and the existence of voids.

o Review concrete documentation for all contracts. Identii'y trends for further investigation. This will be done in con junction with the guality Verification Program review of concrete.

Third-party review of conclusions.

STATUS OF ACTIONS TAKEN o Six additional excavations have been made at various locations in the plant. Included was an excavation to expose all tension steel in Beam 2B5.

o All excavations have been photographed and as-builts prepared of the location and size of the reinforcing bar exposed.

Photographs and as-builts were transmitted to Region V with letter G02-83-622, dated July 15, 1983.

o The new excavations have been viewed by NRC representatives Hessrs. Herring and Albert. The NRC representatives raised the following questions relative to two of the new excavations.

These items will be addressed in the final report.

SK-12:

As-built condition sketch called out a.Ill bar when a.tl0 was actually exposed.

One layer of bars was not exposed at the surface; a bar may be missing.

Page 2 of 3 - PROGRAM VI CONCRETE

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Design drawing does not appear to have been translated correctly to the. placement drawing.

SK-17:

Excavation is not sufficient to confirm that splices are staggered.

An RFI exists permitting the use of additional bars but not clearly specifying when they are to be used.

The following general comments were made by the NRC during the exit discussion and will.also be addressed in the final report:

Beam 4B30 and 6B9 appear to contain a mix substitution without RFI approval. (See also Table V-2 of the CAT report.)

Beams 2Bll and 2B25: Excavate to sound concrete before patching.

Beam 2B5: Noted that one location appeared to have been patched and questioned whether patch had been checked for soundness.

Base Mat at Pum Pit: Still believe, placement contains an extra.k'll bar not called for in design.

Actions are underway to recheck the as-built drawing of each excavation, rephotograph selected excavations, resolve where possible by additional excavation questions regarding reinforcing bar.placement.

o Final response to Region V on inspection report 50-397/83-14 has been submitted; letter G02-83-678, dated July 29; 1983.

o Analyses are underway to determine the significance of the deviations observed in each excavation.

o Nonresident experts have been consulted. They have offered conclusions that the honeycombing in beams 2Bll and 2B25 can be repaired so that the adequacy of these structures is not impaired. Further, one con-sultant has viewed the excavations made, in addition to the honey-combed beams, and concluded ".All concrete'made visible since my visit May 9 is perfectly sound and without imperfection. It is well--

consolidated and therefore well-bonded around the reinforcing bars.".

Page 3 of 3 - PROGRAM VI CONCRETE

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1983 LNK 4QIVITY SUBMI T RE ORT 0

~: BT RMNr1 8/09/83 0 ENG. PROBLEM AREA STATUS >

VI CONCRETE CONCERNS 0 CONST. ACTI V ITY OATUM amrlor3 A

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PROGRAM VII REVIEW OF SITE UALITY PROGRAMS AGAINST CAT ISSUES DESCRIPTION OF CONCERNS AND UESTIONS This program will compare the issues identified by the CAT with site quality programs to assure that the site quality programs have been effective in identifying and correcting quality issues. The program will include the following tasks.

o Determine, by analyzing CAT findings, the extent to which quality programs identified similar concerns.

o Analyze the effectiveness of corrective action programs resulting from such previous identification.

o Determine if there are areas other than those identified by CAT which should be reviewed.

o Identify remedial actions to be taken.

PROGRAMS TO RESOLVE CONCERNS A. Comparison of CAT findings and QVP program (Pre-June 1980 construction)

Perform a comparison of the CAT findings against the pre-June 1980 work scope of QVP. Determine if QVP and CAT inspected the same hardware to similar or identical attributes. The analysis will include an assessment of each specific item and an assessment of the trend where similar deficiencies permit trending. The analysis will draw a conclusion as to whether CAT has identified deficiencies which should have been identified by QVP. After completion of the overall analysis of the specifics, the data accumulated will be reviewed to determine if the CAT inspection has identified weaknesses

.in the QYP. Appropriate corrective actions will be established for any weakness thus identified.

C B. Comparison of CAT findings and operational quality assurance program A comparison of CAT findings as related to the Test and Startup program will be performed to substantiate or mitigate the findings. The CAT report will be reviewed to identify each specific CAT item related to the operational quality assurance program. Each item will be reviewed to establish specific corrective actions, generic implications (if any) and a conclusion will be developed as to whether remedial program actions will be taken or not.

Page 1 of 4 - PROGRAM VII REVIEW OF SITE QUALITY PROGRAMS AGAINST CAT ISSUES

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A report will be developed containing the results of the comparison of the specific review, the quality program actions,and corrective action recommendations. The general CAT issues are:

o Weaknesses in the Quality Control Program in use during Test and Startup.

o Concerns related to the adequacy of the bolt torquing.

o Concerns related to the control of materials; specifically, bolts, nuts and washers.

o Concern related to Test and Startup closeout of Contract 218 Inspection Reports.

C. Comparison of CAT findings and construction quality program (Post-June 1980)

A comparison of CAT findings against the post-June 1980 work scope will be performed to identify similarities or differences between the CAT issues and the findings of the ongoing construction QA program. The method employed will be identical to the analysis described in Item A.

D. Plant quality attributes not addressed by site quality programs This program was initiated to identify and review project cons'truction activities to determine if site quality programs have adequately verified critical attributes.

Inspection modules, not specific to WNP-2, were reviewed to establish critical attributes. Included were the NRC IEE inspection modules, the attributes for which there were CAT findings at Texas Utilities, and the inspection plans implemented by Bechtel at Palo Verde.

Based on review of these sources for critical attributes, the following areas have been identified for further evaluation of physical installations:

t o Equipment/raceway grounding.

o Raceway instal=lations (assembly attributes).

o Use of flex conduit connections to equipment and panels.

Page 2 of 4 - PROGRAM VII REVIEW OF SITE QUALITY PROGRAMS AGAINST CAT ISSUES

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Areas for further evaluation of h sical installations: (continued) o Heat tracing (Class I).

o Instrument setpoints (set within ranges and accuracies).

o Functional interfaces, functional orientation, and special clearances of equipment because of their uniqueness and the potential lack of familiarization by construction of some particular component installation requirements and interactions.

. STATUS OF ACTIONS TAKEN Activit A and C The specific CAT items have been identified on a computer listing and actions initiated to address each. This analysis is scheduled for completion September 2, 1983. A schedule for each activity is attached..

Activit B An assessment of the inspection activities performed by Test and Startup personnel has been performed. This assessment has resulted in identifying needed changes to the Startup Deficiency Report (SDR) system. Additionally, operational gA is performing a sample re-inspection of SDR'st Test and Startup personnel are re-reviewing all inspection reports issued by Fischbach/Lord to determine that each has been dispositioned adequately; each will be signed off by the cognizant engineer and contractor reports will be closed accordingly.

Other activities listed under Activity B are ongoing with scheduled Completion of September 2, 1983.

Activit 0 o Grounding, Flex Connections, Raceway Assembly, Heat Tracing.

An engineering walkdown of field installations is being performed by a Burns and Roe/Bechtel engineering team.

o Instrument Setpoints Walkdowns are being performed to assure setpoints are properly implemented by Startup within the prescribed instrument accuracies, instrument ranges and with correct

.elevation compensation.

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~Ail D(C i d) o Equipment Orientation/Interfaces Walkdowns are being performed on select equipment by Engineering personnel to assess the adequacy of'mplementa-tion of vendor requirements for orientation and AE/NSSS design requirements for functional interface and spatial clearances.

o Equipment Orientation/Interface Walkdown Summary To date this task has selected nine areas to survey with each area having generally unique attributes. The areas include the following: RCIC turbine skid, hydrogen re-combiner skid,,vacuum breaker valves, excess flow check valves, SW equipment and pump house, expansion joints, rupture discs, concrete block walls and batteries. Attri-butes such as equipment orientation, interferences, and special vendor requirements were observed in each of the areas to ascertain the adequacy of construction for these unique attributes.

For the sample data collected to date, it appears that only minor discrepancies exist between the installation attributes and the physical conditions which presently exist in the plant.

One additional walkdown will be performed in the area of flexible connections to Seismic 1 electrical equipment such as switchgear and control panels.

Results from the completed walkdowns as well as the additional area of review are being evaluated and compiled.

Page 4 of 4 - PROGRAM VII REVIEW OF SITE QUALITY PROGRAMS AGAINST CAT ISSUES

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A~CTIV TY M R VP vs CAT B CMP FF C V P RT N VP TY 2 A) ASSESS TESTESTARTUP C B RESOLVE IR CONCERN y e i p D

D TIVITY 3 MPAR PEST PR Mv

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P T T F N PR GRAM-LEO ENO: SCf KDVLE IKL SITE QUALITY 8/09/83 0 ENG. I PROBLEM AREA STATUS i VII REVIEW'GAINST CAT FINDINGS 0 CONST. ACTIV ITY DATUM emrlor3 N AINT

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