IR 05000423/1985004
| ML20151K960 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Seabrook, 05000000 |
| Issue date: | 06/19/1985 |
| From: | Partlow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20151J031 | List: |
| References | |
| FOIA-87-866 NUDOCS 8506260612 | |
| Download: ML20151K960 (33) | |
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JUN i v 1985 MEMORANDUH FOR:
R. W. Starosteckt, Director Olvision of Reactor Projects, Region 1 FR0H:
J. G. Partlow, Director Division of Inspection Programs Office of Inspection and Enforcement SUBJECI:
ASSESSHENT OF IMPLEMENTAi!0N OF THE NRC INSPECTION PROGRAM BY REGION I AT HitLSTONE NUCLEAR POWER STAi!0N UNii 3 The Office of Inspection and Enforcement described to the Commission in SECY 82 150A the assessment of the implementation of the NRC inspection program in conjunction with Construction Appraisal Team (CAT) inspections.
Accord-Ingly, we have examined Region l's implementation of the construction inspec-tion program based on the February March 1985 CA1 Inspection at Mllistone Unit 3.
The results of the inspection were documented in inspection Report 50 423/85 04 dated May 21, 1985.
The enclosure to this memorandum documents the results of our assessment of the construction inspeCLlon program implemen*
tation.
In acidition, we have reviewed the region's followup to the CAT inspection performed at Seabrook Station. We noted that the region has been thorough, conscientious, and timely in the closure and documentation of the CA1 findings.
The resident inspectors were knowledgeable of the current status of the corrective actions.
J. G. Partlow. Olrector Olvision of Inspection Programs Office of Inspection and Enforcement inclosure-Auessment cc:
J. Taylor, it Ulstribution
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REGIONAL CONSTRUCTION IStrPICTION PROGRAM ASSESSMENT OUTLINE
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FOR HILLSTONE UNIT 3 i
1.
Objective 11.
Assessment Activities 111. Assessment findings A.
Discipline Areas 1.
CAT Findings g
2.
Assessment 3.
Recommendations IV.
Review of Inspection Reports A.
Scope
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B.
Assessment
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C.
Recommendations V.
SAlP Reports VI.
Overall Assessment Conclusions
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REGIONAL CONSTRUCTION INSPECTION PROGRAM
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ASSESSMENT - HILLSTONE UNIT 3 (R 1)
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OBJECTIVE The objective of this assessment is to evaluate Region l's implementation l
of the Construction Inspection Program and to make an overall assessment of the adequacy of Region l's oversight of construction activities at the
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Hillstone Unit 3 site.
The Construction Appraisal Team (CAT) of the Division of Inspection Programs conducted an announced construction inspection at the Hillstone Nuclear Power Station Unit 3 of the Northeast Nuclear Energy Company during the period of February 19 March 1 and March 11 22, 1985. While the predominant offort of the inspection team was devoted to hardware inspection, the team also evaluated the control of design changes and corrective actions.
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11.
Assessment Activities A review was made of Region I inspection reports of Hillstone Unit 3, j
SAtP reports and construction deficiency reports to identify those
deficiencies that were previously identified by Region 1 inspectors or the licensee.
The inspectioh reports of 1979 1984, SAtP reports for the period ending 1982, 1983, and 1984, open items and violations were reviewed.
To determine the inspection ef fort at Hillstone Unit 3, the inspection reports l
for 1979 1984 and the 766 systen inspection data were analyzed, it was
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determined that Region i performed approximately 1870 manhours in 1983 and 2130 manhours in 1984 of direct inspection effort at the Hl)lstone Unit 3 site. The inspection hours for 1983 and 1984 were compared to single unit sites in a stellar state of construction and the manhours were found compar-able thus indicating a satisf actory level of inspection ef fort at the site.
The analysis of the inspection reports and 766 computer data indicated that the Construction inspect {on program was approx {mately 90 percent Corplete at the start of the CAT inspection.
The Executive Summary and Potential Enforcement Actions of the Hillstone Unit 3 CAT inspection report (50 423/85 04) are provided as Appendix A and Appendix 8, respectively.
l l
111. Asuspent Findinos A.
Electrical and Instrumentation Construction 1.
CA1 Findinos The CAT inspectors identified terstnations that were not in accord-
ance with current design drawings.
These discrepancies were caused by incoeplete teptementation of design changes and inadequate
docuSentation of post turnover wiring changes.
5eparation def tetencies were identified in the Main Control Board
wiring installed by the vendor or as modifled by design and
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construction activities.
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Although electrical separation criteria of the FSAR had not been
met in ra:eway and cable installations, recent tests were conducted to determine whether the lesser separation criteria could be used.
2.
Assessment it appears that regional inspections in the area of electrical terminations in the construction and testing phases had not identified the deficiencies found by the CAT inspectors.
Based on discussions with Region I and NRR personnel it was evident that the parties involved were aware of the difference between the FSAR and installation cr ueria for electrical
separation, in f act, rieasures were taken to ensure that the reduced separation criteria were properly justified by testing and that the test report would be reviewed by NRC personnel.
3.
Recomendation The Construction Inspection Procedures in the area of electrical terminations are adequate if properly implemented.
Since the
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Ifcensee is now progressing into the startup and testing phases.
the regional office should place more attention in the area of the
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control of work on components and systems subsequent to turnover from construction.
B.
Mechanical Construction 1,
CAT Finding The CAT inspectors identified several areas which showed a lack of
attention to detail by QC inspectors.
These were in the areas of
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installation of pipe supports / restraints, equipment foundation anchorages, and as built drawings.
The CAT inspectors determined that complete engineering had not
always been performed in that def tetencies were identified in the inspection criteria and engineering Interf ace for pipe support / restraint attachment locations, the review of attachment lug contact criteria, and a number of draf ting errors.
the CAT inspectors determined that corrective actions for
deficiencies in the NNECO maintenance program were not ef fective or timely.
2.
Assesloent
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The Region 1 SAtP report number 50 423/84 19 identifled a
declining trend in the area of piping systers and supports.
The CAT findings regarding lack of attention to details, though Individually not significant, also reflect the declining trend.
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The lack of engineering thoroughness was highlighted to a
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degree in SALP report number 50-423/84-19.
Although the SALP
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rating in the newly addressed area of Engineering Construction Interfaces was Category 1 (consistent), the SALP Board did recom-mend increased HRC attention to address the increasing engineering work during the closecut of the construction phase, it does not appear that the regional office has focused upon comunications between engineering and construction in the form of procedures or criteria.
Based on the CAT findings it seems that engineering activities should receive additional attention.
The deficiencies in the NHECO maintenance program was identified
in a December 1984 audit by the licensee.
There had not been suf fletent time prior to the CAT inspection for the regional office to assess the effectiveness of the corrective actions.
The CAT inspectors reviewed this area as a normal part of their inspection scope.
3.
Recomendations_
The Region 1 of fice has shown an awareness of the programatic weaknesses in the areas of pipe supports and engineering activities.
Continuation of increased attention in these areas is warranted.
C.
Weldina NDE 1.
CAT Findings The CAT inspectors identified deficiencies in completed structural
welds in pipe supports for skewed connections and pipe straps.
Undersized welds were identified by the CAT inspectors in the area
of vendor supplied tanks and heat exchangers in nottles, aanways, and supports.
2.
Asse s sment l
Previous Region I inspections had not identified the deficiencies
in the skewed connections and pipe straps.
The Construction Inspection Procedures are adequate in this area if properly implemented.
- 10 vendor deficiencies in tanks and heat enchangers are recurring on-at nuclear construction sites.
3.
b omendations The welding deficiencies in pipe supports / straps sees to be related
to the declining trend in pipe and pipe supports in general.
This area marrants additional attention.
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The Construction Inspection Procedures for this area are adequate.
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An IE Information Notice has been issued and discusses the vendor
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tank and heat exchanger problems.
D.
Civil and Structural Construction 1.
CAT Findings The CAT inspectors identified deficiencies in a number of struc-
tural steel connections in the Main Steam Valve Building.
The deficiencies were in welded connections and bolts too tight to allow for thermal expansion.
Unauthorited material was found by t e CAT inspectors in the
seismic isolation joints between buildings.
2.
Assessment The structural steel deficiencie. in the Main Steen Valve Building
(MSVB) had not been previously identified by the regional office.
The Region I team inspection conducted in March 1984 (Inspection Riport 50 423/84 04) reviewed the connections in the MSVB and had found incor.plete bearing on beta seats, but had not identified the
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welding or bolting discrepancies.
Cleanliness of butiding isolation joints has not been emphasized
in the Construction Inspection Procedures.
3.
Recoseendations
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In the area of structural steel, the Construction Inspection
Procedures are adequate if properly implemented.
An evaluation will be made to determine whether isolation joint
cleanliness should be made a part of the Construction Inspection Procedures.
l.
Material Traceability and Control 1.
CAT Findinos j
three areas were identified in which there was a lack of traceability for vendor supplied f asteners mounting bolts for large pump motors, battery rack bolts, and interconnecting bolts
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l for adjacent motor control center cabinets,
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2.
As sessment
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It does not appear that either the regional of fice or the licensee has previously identified this problem.
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3.
Recorreendations
Problems in the traceability of fasteners has been identified by the NRC CAT program at several sites.
At the present time, lE
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Inspection procedures address material traceability only in each i
technical discipline.
Current procedures do not exist to cover the programmatic control for material traceability.
IE will evaluate the need for additional inspection guidance in this area.
F.
Design Change Control j
1.
CAT Findings j
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In the area of design change control, an increasing number of druings were found which were overdue for updating to include the latest design changes.
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In the area of design document control, a llgolflCant number of
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document contro) errors were identified by the CAT inspectors at drawing stations used by construction and inspection personnel.
Veaknessen were identified in the use of yellow (uncontrolled)
drawings and in document control audits.
2.
As s e s t mi,nt Region I had previously identified a lack of timely incorporation
of design changes in Inspection Report 50 423/84 04, this iten was identified as a weabest in the licensee's program.
Region I had also reviewed the area of document contros in Inspec-
tion Report 50 423/84 04, only one deficiency was identified in a drawing out of date for revillon number.
5tallar parameters
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were reviewed by both the Region I and CAT inspect. tons.
A possible
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esplanation of the difference in findings in that a change had j
occurred in the licensee's programs in the approximately one year Interval between the Region I and CAT lanpections.
3.
Recoemendations The Construction Inspection Procedures are adequate in the dellgn
change control area.
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G.
Corrective Action Systeen l
1.
CA1 Findtnen the CAT inspectors identified weaknesses in the corrective actions programs in the following areas:
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preventive maintenance after turnover from construction
design change control and document control
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unresolved nonconformances after turnover from construction.
2.
Assessment The areas of design change control and document control, and unresolved nonconformances after turnover had been previously identified by Region I.
However, Improved performance by the licensee in these areas is still warranted.
The preventative nalntenance issue is too recent to have gotten mech regional attention.
Generally lewedfromthequalityassurancestandpointandreviewed the area of corrective action systems 15 programmatt-cally rev
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in detall in the technical disciplines.
3.
Recomendations Additional regional attention is warranted to ensure that th(-
11,censee's corrective actions are ef fective and timely.
The Con-
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struction Inspection Procedures are adequate in this area.
For additional details see the previous discussion in the discipline
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iv.
R[vl[W OF M!ttSTONE UNIT 3 CONSTRUCTION INSP[CTION REPORTS A.
Scope the inspection procedures itselXed in 1[ Manual Chapter (MC) 2512 were reviewed as to which were applicable to the Millstone Unit 3 construc-tion site. A 766 systes computer printout was obtained for the entire construction period which identified report numbers, inspection proce*
dures, inspection dates Staff hours, percent Complete and completion status, the inspection history for Millstone Unit 3 was tabulated as indicated in Attachment 1.
A review was conducted for which procedures were laplemented against the inspection procedure requirements, in addition, Attachments ll ly present a suonary of inspection aan hours in each functional area, as defined by the inspection procedures shown below.
Functional Area Inspection Procedures Management (MMT)
30XXX Quality Assurance P'ogram (QA)
35xxx
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As Bullt/ Design ( AS 8UIL1)
37XXX
$lte Preparation / Foundation 45KXX/46KXX (51T( PR(P)
Concrete (CONC)
47XXX
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Structural Steel ($1R $tt)
48XXX Piping (PIPING)
49XXX e
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Mechanical (M(CH)
50XXX (lectrical ([L(CT)
$1XXX ltC blXXX
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l Penetrations (Plhlf R)
$3XXX
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welding /HDE (wet 0lHG)
55XXX/56xxx/57xxx/58XXX
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In service Inspection (151)
73XXX Hiscellaneous (H150)
92XXX Independent inspections 92706 (IND INSP)
Inspection data for 1984 is presented in Attachment V.
The 1984 data represents information in the 766 systen an of January 22, 1985.
The inspection reports prepared by the regional inspectors were evaluated to determine whether they:
included the required information, were tuffi-ciently corprehensive, were issued in a timely f anhlon and were prepared in accordance with HC 0610.
8.
Assettment the review of the HC 2512 inspection procedures required to be laple-mented al Priority 1 as compared to those actually laplemented indicated basically full implementation except for a few where plant construction was still in progrelt.
It appearn that in two areas inspection proce-duren have not been laplemented based on the data available an of January 1985 (not all 1984 inspection procedure completion information was available).
The two areas are instrumentation and welding of steel structures and supports.
Those inspection proceduren without inspection
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time astigned to them are categorized as Priority 1 in MC 2512 (dated 9/15/81) and are listed below.
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Welding (Steel Structures Instrumentation and Supports)
520548 551514 520568 551528 520618 551538 52063B 551548 520648 551568 520658 551578 520668 551568 lt is noted that gone regional inspections were performed in late 1984 in the area of electrical and instrumentation construction which may not be reflected in the data base, in the area of welding steel structures and supports, seven inspection proceduren appear not to have been implemented.
The only previous inspection performed in this area was performed as part of the NOl van inspection in 1983 (dliculled in inspection Report 8314).
In light of the deficiencien identified in
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the welded Connectionl of the Main 5 teas Valve Bullding, laplementation of these inspection procedures thould have identitled these deficiencies.
Recent changen in the Construction Inspection Proceduren in thlt area thould clarify and Staplify the inspection requirteents.
In addition to the two arean highlighted above, it was also noted that the inspection procedures in the area of preservice/intervice inspec-tions have not been reviewed by the regional of fice in much detall.
the latest inspection was perforstd in late 1983 and only a total of 12 i
inspectlen aan hourt have been spent in this area.
The latent regional procedure statun in noted to be 10% complete.
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A random sample of 10 Inspections reports (Indicated below) shows that they were essentially being prepared in conformance with ![ Hanual Chapter 0610.
The reports included pertinent information such as report number, docket no., inspectors, inspection summary, results, details of inspection, persons interviewed, and individuals present at entrance and emit meetings.
The inspection reports provided suf ficient detall to understand the issues and showed evidence of adequate technical content and review.
One area for leprovement involves the issuance of inspection reports.
MC 0010 luggests that inspection reports be issued 20 days after the last day of inspection or 20 days af ter the inspection period ends as in the case of monthly relldent's reports, the following IIsts the reports reviewed and the total time elapsed from the end inspection to issuance of report.
Inspection Report Days
Inspection Report
Performed
Ending
1ssue
To
Number
8y
Date
Date
lisue
81 07
$r. Res. Insp.
6/12
9/9
Bl08
Region !
6/9
7/5
83 12
Region 1
6/24
8/3
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83 13
Region 1
7/22
8/18
83 20
$r Res. Insp.
12/10
1/27
83 21
Region 1
12/2
2/1
84 02
$r. Res. insp.
3/4
4/10
84 03
$r. Res. Insp.
4/14
5/29
and Region 1
84 06
$r. Res. Insp.
5/19
6/26
84 11
Region 1
5/18
6/20
Ave.
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(Note
Inspection Report 84 23 issued on March 20, 1985 pertains
to an inspection which ended on October 26,1984
A total of 157
days were required to illue the inspection report.)
the average time required to issue reports is auch longer than recoa-
eended in MC 0610 and a recent inspection report (64 2J) thcvs an
inordinate delay in issuing the report.
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Rece m ndatte.n
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Overall, the Region I of fice has performed satisf a:tority in the laple-
pentation of the construction procedures, except in the area of welding
steel structures and supports.
An allessment of the lecteeentation of
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the instrumentation and in service / pre service inspecuon preceduren
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should be done to ensure that this area t 46 been or will te adequately
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Inspected.
Regional management should accress the timely \\ttuance of
inspection reports.
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SALP Reports
An analynit was made of the two mont recent $ ALP reports 1982 1983 and
1983 1984 for those areal that were Connon to both $ ALP and the CAT inspec-
tion.
Generally the $ ALP reports reflect a high level of licensu per-
formance with mostly Category I ratings and only a few Category 2 ratingt
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(in the last $ ALP period
piping nylless and supports. and licenning
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activitien were Category 2).
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Int CAI intpettion identifled weaknennen in the licenlee's programl in the
areas of:
pont turnover work control; communicationn betwun the engineer-
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ing. construction, and inspection groupn; document control errors; and
Quality Control Innpection of fectivenent.
The SALP report 6 deal directly
.Itn three of the four program weakness arean,
in two arean (pre opera *
tional testing and engineering construction interf aces) the CAT and regional
findings are in general agreement.
The regional atletsment in preoperational
testing shows the increating need to aggrennively review the implementation
cf the testing progras,
ine regional findings in the area of engineering-
construction interf acen also recognized the need to increase NRC inspection
efforts,
in the area of document cont.rol, the regional of fice nad eliminated thin an
a f unctional area as it was no longer considered to be a lignificant progran-
ratic concern.
At the CAT findings indicate, thlt elimination may have been
done too loon.
Continued attention in thlt area in warranted,
in the area of contairment and other safety related structuren, the CAI and
regional findings were nialler for concrete and reinforcing steel activitten.
However, in Structural steel CDnnections, the deflClencles in welding and
bolting were not identified in regional inspectionn for the name building
structuren al reviewed by the CAT Inspectorn.
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the 19831984 $ ALP report dentribed a potential trend of "lent foresight.
thoroughnett, and aggrennive retolution of iteel" in the area of piping
systems and supportn.
This trend in niallar to that found by the CA1
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inspection In the area of engineering thoroughnent, particularly regarding
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pipe supports,
in the other areal allested in the $ ALP reports (nafety related components,
support lystern, and electrical power, instrumentation, and controll), the
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regional findingt were generally in agreteent with the CA1 firedings.
VI
Ov,e,rall Assessewnt Conclustent
A review of the Millstone Unit 3 inspections reports $ ALP reports, and 766
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spies data indicaten that generally the conntr6ction inspection modulen had
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been adequately leptemented.
The inspection reports were written with the
necessary scope, depth and technical content. However, a few inspection
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rodulen require additional attentlen.
An annellment by regional management
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should be made to ensure that intpection modulen in the areal of Instruments.
tlon. welding of steel structuren and supportl. and in service / pre tervice
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Inspect.lon are toolemented.
An of fort by regional sanagement thould
lie rade to ensure more timely innvence of Inspection toports,
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A review of the CAT and regional findings shows general agreement and the
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CAI findings particularly reinforce the region's impression of potentially
decilning trends in the areas of pipe supports, engineering construction
interfaces, post turnover work control including maintenance activities, and
design change control.
The significant area which requires additional
regional attention (previously judged to be no longer a concern) is the area
of document control, particularly drawings and associated design changes.
A review of the latest $ ALP reports indicates that the licensee's performance
has apparently declined in several areas from the high levels previously
achieved, based on the CAT findings.
This 16 significant in that regional
attention will be necessary in order to allure that the declining trends do
not progress into unsatisfactory program perfotrance.
Overall, the regional efforts to oversee the construction activities at
Millstone Unit 3 appear to.4 ' u t s f act';ry.
The implerentation of the
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Construction Inspection Prt
'rocedures was adequate.
Regional management
attention will be necessar;
b.
.1,ure completion of the constrection inspec-
tion program in a few remat,>. areas and as the project moves into the
testing phase.
The declinte; trends in several areas should also be given
additional (ttention.
The regional office has demonstrated perceptiveness in
identifying these trends at an early stage.
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APPEH0!X A
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. EXECUTIVE SUMMARY
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An annou id NRC Construction Appraisal Team (CAT) inspection was conducted
at Northe
.t Nuclear Energy Company's Hillstone Unit 3 during the period
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february
, March 1 and March 11 22, 1985.,
Overall Conclusions
Hardware and documentation for construction activities were generally in
accordance with requirements and licenses commitments.
However, the NRC
CAT did identify a number of construction program weaknesses that require
additional eianagement attention.
These include:
1.
Controi of work on systems and componeints subsequent to turnover from
Construction to the testing organization requires leprovement.
This is
indicated by the deficiencies found in the control of wiring changes, and
preventive maintenance deficiencies found in the mechanical end electrical
areas subsequent to turnover to the startup organization.
Additional
attention is needed to ensure that missed maintenance activities are
evaluated as to the potential damaging effects on the components.
These
findings indicate the need to reevaluate the controls applied to activi -
ties subsequent to systcm turnover from Construction to Operations.
2.
A number of hardware deficiencies were identified which appear to have
been caused by a lack of effective coreunications between the design,
construction, and inspection groups.
Design parameters w'ere in some
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cases not properly translated into inspection criteria. For example, pipe
supports had been installed and accepted by 0
not in accordance with the design cafet.14 tion.C with dimensional. tolerances
s.
In addition, a lack of
thoroughness on the part of the design orgsntration was identified.
Exa.tples identified include:
omission of the Residual Heat Aemoval Systes
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from the pipe support "lugn={n= contact" review; wiring termination changes
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.made to drawings without the issuance of the necessary documents to
contro' the actual construction work; inadequate technical justification'.
for the acceptance of unEUked fasteners in certain actor control centers;
and conflicting details for a structural steel end connection.
3.
A significant number of document control errors were found at both the
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Quality Cont,rol and Construction drawings stations.
This is of particular
concern in that the defletenctet iti document control had been identified
previously, and the number of audits increased to monitor the situation.
In fact, a 100% audit of all drawing stations had been performed just
prior to the s' art of the Ntc CAT inspection.
The corrective actions
taken had not uten of fective, however.
A1
__
__.._._.
..
.
-
_.,_,,_ _.__.
- --.-- - - - - --
'
lr
.
.
..
.. -
,...
.... -.. -... -. ~........ ~.
,
i
t
,
,..
,
,
a.
A number of findings indicate that the ef fectiveness of Quality Control
!'
inspection activities needs to be improved.
These findings IN1ude the
'
,
area of pipinq as built drawings, mechanical aquipment foundation anchorage,
-
'
structural steel connections (welded and bolted), piping support welding
Il,
(pipe straps and skewed fillet welds), and pipe support miscellaneous
'
hardware (lock nut tightness, cotter pin installations, etc.).
Also,
vendor deficiencies were identified in the areas of tank and heat
exchanger fillet welds (pressure boundary and supports), performance
of load indicating washers, and marking of fasteners.
The foregoing identified weaknesses require additional managemen; attention
to assure tl.at completed installations eeet design requirements.
AREAS IHiPECTED AND RESULT 5
'
Electrical and instrumentation Construction
The electrical and instrumentation samplos inspected
design requirements and installation specifications. generally met the applicable
Several discrepancies
were identified including some that will require additional management attentlen.
Humerous electrical separation discrepancies were identified in the Main
Control Board wiring installed by the vendor and as modified by design and
construction activities.
Several areas were noted in which redundant electrical
-
division wires were in contact with each other.
Electrical separation criteria detailed in the Hillstone Unit 3 FSAR had not
i
been met in many raceway and cable installat.f ons.
However, lesser separation
'
may be acceptable based en recent tests,
This matter is considered open
pending NRR review and evaluation.
During examination of Class 1E cable ends, a number of terminations were
identified that were not in accordance With Current design drawings.
One
group of discrepancies pertains to incomplete implementation of design changes.
The second group relatos to inadequate documentation of post turnover wiring
changes.
!'echanical Construction
s.
HVAC restraints, concrete expansion anchor installaticns, pipe wall thickness
and piping hydrostatic test records were found to be in general conformance
to design and procedural requirements.
Numerous discrepancies were identified le pipe support / restraints and rechant-
cal equipment foundation installations.
A nue.ber of discrepancies were
cbserved bebeen as built drawings and piping configurations.
Greater atun-
tion to detail during QC inspect 1rns appears necessary.
,
A need for more thorough engineering review activitle.l. and additional
reinspection and/or reanalysis was observed.
This nee 6 was indicated by:
unclear inspection criteria and inadequate engineering interface for pipe
support / restraint attachment locations; inadequate review of attachment lug
contact criterla; and a number of draf tirig errors,
kt
-.w
.- wrymarwegaeww
.
.....
~
^
.-...-.~........-.....:..:.'~...;....-~....~.-
.
.
.
.
j
-
-
.
>
,'
,..
.
..
l
The HNECO maintenance program and maintenance activitte; performed after
.
equipment turnover from Construction were considered to be inadequate.
This
i
,
item had been previously identified, but corrective actions taken had not been
effective or timely.
Weldina and Hondestructive Examination
'
Welding and nondestructive examination activities were generally found to be
conducted in accordance with the governing codes and specifications.
However,
a number of examples were identified where completed structural welds in pipe
supports involving skewed welded connections did not have the weld sizes
specified by ths Architect-Engineer.
These undersized welds in skewed
connections should have been identified during the weld inspection process,
and their existence indicates a program weakness.
The licensee has performed
an engineering evaluation concerning this problem and concluded that most of
these welds are adequate for the intended application.
In the area of vendor
supplied tanks and heat exchangers a number of tanks were found to have
.
undersized weld reinforcements in nozzle and manway welded joints.
In addition,
some tank supports were found to have deficient welds.
,
-
,
Civil and Structural Construction
In general, concreto quality, cadwelding ;nd concrete material certification
were found to be acceptable.
Robar appeared to be placed in accordance with
.
the design drawings.
However, the NRC CAT inspectors identified unauthorized
eaterialinthecuildingisolationjoints(rattlespaces).
Structuralsteelmemb'ersizeandconfturationwereknSteamYalveBuildin
acceptable. AnumberofsteelconnectkonsintheMa enerally found to be
were found to be not in accordance with the design drawings.
Based on testing
by the NRC CAT, problems were identified in the performance of load indicating
washers.
)
-
Hateris) Traceability and Control
l
The licensce's material traceability and control program was found to be
-
acceptable, except for certain fastener hardware.
Si
tratability was found for vendor fastener materials,gnificant lack of
,
including bolts for
s
mounting large pump motors, bolts for battery racks and bolts for inter-
connecting adjacent motor control center cabinets.
Oosten Chance Control
,,
Design change control was deterstned to ' e in accordance with site procedures
b
with the exceptica of timely updating of dealgn documents with the latest
change information.
A number of drawings were found to be overdue for updating
to include the latest design change requirements,
in the trea of design
document control, a significant number of docusent control errors were founo at
i
site drawing stations used for construction work and QC acceptance.
Weaknesses
were also identified in the 'Jse of yellow drawings and document control audits.
In addition, four cases of apparent inadequate corrective actions were noted
in both the document control and design change control areas.
A3
- _.. -
-
.-
.-.
-. - - -
.
- -.
. - -..
-
~
. -..
....
.. - _........... _.,..,,,,
-
r
,
..
,
p
,
,
'
.
/
-
Corrective Action Systems
-
l
A weakness was found in the corrective actions tak'en to control preventive
'
maintenance after components had been turned over for testing / operation.
In
addition, corrective actions applied to design change controls and document
control d:ficiencies had not been effective.
Also, an increasing number of
i
unresolved nonconformances was found after turnover of system packages for
testing /coeration.
These matters require additional management attention,
'
b
,
e
%
e
\\
.
.
-.
,
e
.
g
I
p
',.
..
'
,
.
.
.
A4
.
..
_ _ _.. _ _ _,
.,...,, - - _,
- _ _ _ _ -. _. _... _. _. _ _ -.. _ _,, _ _.. _ _,
_-,-,,,,.,_.,_,_._y._ /
.,_.,.
.........
.. -.....
,
L..
.,.
-
,-
.
,
,
I
i
'
.
.
,.
APPEN0!X 8
POTEllTI At. EftFORCEMENT ACT!0fis
'
As a result of the 11RC CAT inspection of February 19. March I and March !! 22,
1985 at the Hillstone Unit 3 site, the following items are being referred to
Region I as Pottattal Enforcement Actions.
Section references are to the detailed i
portion of the inspection report.
10 CFR 50, Appendix 8, Criterton !!!,)as implemented by Northeast U
1.
ties Quality A'surance Program (NUQAP, QAP 3.0, requires that masures
shall be estabitshed to assure that applicable regulatory requirements are
'
correctly translated into spectf tcations, drawings, procedures and
instructions.
,
.
Contrary to the above, at the time of this inspection, the licensee's
program for design control has not been adequate to assure that Class It
wiring configurations are in accordance with applicable design. As a
result of incomplete control of electrical termination changes, a number
.
of existing)) installations may not perform their intended function (Section
!!.B.2.b.(6
.
.
..
2,
10 CFR 50 Appendix 8. Criterton V, as implemented by NVQAP, QAP 5.0,
requires that activities affecting quality shall be prescribed by
documented instrvctions, procedures or drawinfit which include appropriate
quantitative or qualitative acceptance criter's.
.
Contrary to the above, the NRC CAT inspectors found, at the time of this
inspection, that the licensee's programs were not effectively implemented
in that theyt
a.
Failed to adequately implement their post turnover test and
-
inspection program to assure that wirin chenftes were documented in
.
accordance w1th appltcable procedures. g(Sect'on !!.8.2.b.(6)).
,
i '\\
b,
failed to identify conflicting allowable acceptance criteria between
the design organtration and the inspection organitation for pipe
supports / restraints (Section !!!.I.2).
3,
10 CFR 50, Appendix 8. Criterton VI,"as implemented by NVQAP, QAP 6.0,
requires in part that swasures be established to control issue and
distributton of document changes to the prescribed locations.
'
Contrary to the above, during this inspection, 'he $WEC design documnt
control proceduros were not adequately implemnted in that numerous errors
,
In distributton, filinfi and updattafl of document record cards, design
change docuMnts, draw'ngs and spec' fications were found to exist in site
drawin station) used for plant construction and Quality Control inspec.
,
tion ( ection VII.8.1).
.
4,
10 CFR 50. Appendix 8. Criterton Vll, as impleNnted by NVQAP, QAP 1.0,
requires that measures be established to assure that purchased Ntdrial,
'
equipment and services confona to the procureMnt documents.
,
.
,_______ _ ______.__
m
,
_._,_,_-___,_..__,_,,_,m.,,__m.._
.,_,.y__,,
,,,,.._y_,,,_._m
., _,., -,..,. - - _,,
.
.... - -
.
..
-
...
.
....
.....:.-............_......~......-....-......~..
.
,.
,
j
,
.
Contrary to the above, at the time of this inspection, the implementation
of SWCC's procedures were found to be ineffective in that vendor procured
,
tanks and heat exchangers were accepted and installed with deficient
welds ($ection IV.S.1).
5.
10 CFR 50, Appendix 8. Criterion Vill, as 1. plemented by NVQAP, QAP 8.0,
requires that measures be established for the control of materials, parts
and components to prevent the use of incorrtet or defective ittms.
Contrary to the above, at the time of this inspection the material
traceability and control of some fasteners, including bolts for mounting
large pump motors, have not been adequate to assure the use of ';orrect
materials.
L
6.
10 CFA 50, Appendix 8. Criterton X, as implemented by NUQAP, QAP 10.0,
requires that a program for inspection of activities affecting quality be
established and executed to verify conformance with design documents.
Contrary to the above, at the time of this inspection, it was found that
.
the Itcensee's peograms were not effectively implemented in that theyi
a.
failed to ensure that safety related pipe supports / restraints were
constructed in accordance with design requirtments in that support
'ttachment locations were not installed as shown on design drawin1s
(Section!!!.B.2).
b.
Old not assure that equipment foundation bolting connections were
installed in accordance wtth s
requirements (Section !!!.8.5)pec1fied acceptance criterta and
.
,
c.
Have not assured that the spectffed weld sizes in skewed structural
pipe support connections have the required weld sizes ($ection
lY.8.1).
7.
10 CFR 50 Appendix 8. Criterton XV!, as implemented by NUQAP, QAP 16.0,
requires that measures be estabitshed to assure that conditions adverse
.
to quality are promptly identified and corrected, including action to
av'otd repetition.
's
'
Contrary to the above, at the time of this inspection, the licenste's
program of Qualit{s in that there wastControl Inspection had not provided adeq
procedural controi
p
4.
Failure to promptly identtfy and correct numerous separation
deffetencies in vendor or modified vendor wiring installations
withinthemaincontrolboards(Section!!.8.2.b(2)).
'
b.
Failure to promptly perform effective corrective action to prevent
recurrence of nonconformances (Section Yllt.B.I.b(1)).
c.
Inadequato control of preventtve maintenance af ter turnover for
testing / operating (Section Yllt.8.1.b.(2)).
d.
Failure to ap ly effective corrective actions for document control
deffetencies
SectionYll!.8.1.b.(4)).
'
.
.
.
'
._
_ _,.,
_ _ _ _,
--.e-
,,
-
--
- - ' " " - ' - - " ' ' ^ ' "
'
.
L
.
,
'
,
,
l
.
.
.
,
,
l
.
'
ATTACHMENT I
!HSPECTION PROGRAM HISTORY FOR MILLSTONE UNIT 3
A.
Civil and Structural Procedures
1.
Program Recuirements
a.
IP 45051B, 450538, 45055B
Site Preparation - Procedures review
to be completed before site work started and records reviewed
during site work,
b.
IP-46051B, 460558 - Foundations - Procedures to be done before work
is 10% complete and review of quality records before work is 60%
complete,
c.
IP 46153B
Site Preparation and Foundations
To be done before
work is 60% complete.
d.
IP 470518, 47053B, 47054B, 470558, 470568 - Containment (Structural
Concrete) - Procedure review before start of work, observation of
work af ter 10% and 50% and review of records af ter 10% and 50%.
e.
IP 48051B, 48053B, 480558 - Containment (Steel Structures and
Supports) - Procedure review before start of work, observation of
work and record review before work is 50% complete,
f.
IP 48061B, 48063B, 480648, 48065B, 480668, - Safety-Related Struc-
tures (Structural Steel and Supports) - Procedure review before
start of work, observation of work at 10% and 50%, and record review
at 20% ani 50%.
2.
Inspections Conducted at Hillstone Unit 3
'
Proc.
Total
Latest
No.
Report
Staff
Percent
latest
("Priority I) Humber
Hours
Complete
Status
I
a.
IP-450518, 450538, 450448 - Site Preparation
450518
75 05
100
C
450538
75 05
100
C
79 10
45055B
75 05
100
C
79 10
b.
IP 460518, 460558 - Foundation
460518
75 05
100
C
-
"
46053B
75 05
100
C
A1
.
_ _ _.
__
_
.
.
.
..
...
... - -
.
.
....
l
.. _..
-. _........ i
-
'
t
.
.
,
.-
l
.
.
-
,,
'
84-06
-
46053*
j
46055B
75-05
100
C
t
c.
IP-46153B - Site Preparation and Foundations - Module not in
effect of time of activity.
Earlier site preparation and
foundations modules completed,
d.
IP-47051B, 47053B, 47054B, 470558, 47056B - Contairment
(Structural Concrete)
47051B*
75-05
100
C
47053B*
75-09
N
100
C
77-03
82-09
47053C
81-04
81-06
81-12
47054B*
76-05
81-02 123
100
C
'
78 03
81-09
78-04
83-12
'
79-06
83-20
79 10
83-21
-
80-
83-22
'
47055B*
76 vi
100
C
77-03
47056B
78-03
81-02
90
78 06
81-09
79 06
82 09
79-10
e.
IP-48051B, 48053B, 48055B, - Containment (Steel Structures and
Supports)
48051B*
75-07
100
C
76-04
'
84 04
48053B*
76 04
77 06
100
C
76-06
77 08
,
76-07
77-11
77-01
80 05
77 02
80 05
77-04
81 02
.
77 05
84 04
48053C
81-08
,
48055B*
76-04.
77-04
70
76 06
77 05
'
76-07
77-06
'
77 01
77 08
77-02
f.
IP 48061B, 48063B, 48064B, 48066B
Safety Related Structures
(Structural Steel and Supports)
A-2
- _.
-.
.
-- -
.
---
__ _-
-. -.
. _. _.
._
.
..:-
.
.
.
.
.
l
48061B"
75-07
77 09
50
.
77 02
79 09
'
l
48063B"
79 09
100
C
81-02
84 04
48063C
81 12
82 11
82 04
83 02
48064B
83 16
100
C
82 21
48065B"
83 21
100
C
48066B
83 21
100
C
B.
Mechanical Construction Procedures
1.
Program Requirements
a.
IP 490518, 490538, 490548, 490558, 490568 - Reactor Coolant
Procedure review before start of work,
.
Pressure Boundary Piping % and 60% and record review after 20% and
observation of work at 20
60%.
b.
IP-490618, 490638, 490658 - Safety-Related Piping - Procedure
review before start of work, observation of work at 40% and record
review at 50%.
j
c.
IP 50051B, 500538, 500558 - Reactor Vessel Installation -
l
observation of work at
Frocedure review before start of work,ffffM.-
l
'
IRtilllllf99 OM fifH$ (Nfft M $@f
d.
IP-50061B, 500638, 50065 - Reactor Vessel Internals
Procedure
review before start of work observation of work during
installationandrecordrevlewafterinstallation,
e.
IP-50071B, 500738, 500748, 500758, 500768 - Safety Related
Components - Procedure review before start of work, observation of
'
work at 10% and 50% and record review af ter 20% and 50% work
completion.
f.
IP 50090B
Safety Related Pipe Support and Restraint Systens
To
be implemented before work is 20% complete,
g.
IP 500958, Spent Fuel Storage Racks
Observation of work before
work is 50% complete,
h.
IP 500100 - Safety Related Heating, Ventilating, and Air
Conditioning (HVAC)Systens(newprocedureinitiated10/83)
-
2.
Inspections Conducted at Millstone Unit 3
Proc.
Total
latest
No.
Report
Staff
Percent
latest
(* Priority 1) Number
Hours
Complete
Status
A3
-
-_.
.
--
-_
_
.
-
_
-..-
.. - - - -
-.
-
.
.
.
.
.
...
>
.
'.
.-
,
a.
IP-490518, 490538, 490548, 490558, 490568 - Reactor Coolant
'
.
.
Pressure Boundary Piping
49051B"
77 04
10
77 06
49053B"
82 12
49053C"
81-04
81 15
81-11
82 04
81-12
82 08
'
81-14
IP 490548, 490558, and 490568 do not appear to have been implemen-
,
ted, however the related IPs (4906180 490638, and 490658) have been
performed for safety related piping,
b.
IP 490618, 49063B, 490658 - Safety Related Piping
49061B*
77 04
10
77 06
49063B"
77 11
100
C
83 21
'
84-04
49063
83 07
83 22
90
.
83 10
84 0*
49063C
81 04
81 14
81 08
82 04
49065B'
83 21
100
C
84 04
49065
83 16
10
c.
IP 50051B, 500536, 500558 - Reactor Vessel Installation
50051B'
77 04
80 05
100
C
77 05
'
50053B'
77 03
80 02
60
77 04
80 05
77 05
80 06
50053C
82 06
82 08
50055B'
77 05
100
C
80 06
d.
IP 500618, 50063B, 500658 - Reactor Vessel Internals
50061B'
77 05
15
82 12
50063B'
77 05
80 02
40
80 02
81 02
50063C
81 04
82-12
82 06
83 05
82 11
50065B'
77 05
10
,
e.
IP 500718, 50073B, 500748, 500758, 500768 - Safety Related
Components
!
A4
l
- -.. -.. -.,,..
.,-..--,---. ---
.-..,-.-,,.-,,..,,.,-,..n,..n-...
,
. -...' " ' ' " ' ^ *
. - ~. - -
1
.
-
l
,-..
.
.
.
.
50071B"
77 05
100
C
-
84 04
50073B'
77 05
81 02
100
C
77 09
83 10
80 02
84 04
50073C
81 04
82 04
129
81 06
82 06
81 14
82 11
50074B"
82 15
83 12
10
83 07
50075B'
77 05
81 02
30
l
77 09
f.
IP 500908 - Pipe Support and Restraint Systems
50090B"
62 10
84 04
100
C
83 10
84 18
50090
83 10
10
500900
82 12 82 04
82 02 82 08
g.
IP 500958 - Spent Fuel Storage Racks
50095B
83 22
50
h.
50100
84 08
80
,
84 11
C.
Electrieel and Instrumentation Construction Procedures
'
1.
Program Requirements
a.
IP 510518, 510538, 510548, 510558, 51056B - Electrical
Components and Systems - Procedure review before start of
work, observation of work at 30% and 60% complete and record
review before 70%.
b.
IP 510618, 510638, 510648, 510658, 510668 - tiectrical Cables
and Terminations
Procedure review before start of work, work
observation at 10% and 50% completion and record review at 20%
and 50%.
c.
IP 520518, 520538, 520548, 520558, 520568 - Instrumentation -
Components and Systems - Procedure review before start of work,
'
work observation at 10% and 50% and record review at 20% and
50%.
d.
IP 520618, 520638, $20648, 520658, 520668 - Instrumentation -
Cables and Teretnations
Procedure review before start of
work, work observation of 10% and 50% and record review at 20%
and 50%.
A5
. -.
.
. -
-...
-... - - - -.. -..
,. - _ -.
- -
- _ - _ -
L
l
l
.
.
-
-
s..
.
2.
Inspection Conducted at Millstone Unit 3
Proc.
Total
latest
No.
Report
Staff
Parcent
latest
(* Priority I) Number
Hours
Complete
Status
a.
IP 510518, 51053B, 510548, 510558, 510568 - Electrical
Components and Systems
510518*
81 02 83 04
100
C
82 05 83 09
82 13 83 15
L
51053B'
81 02 83 11
100
C
82 13 83 15
82 06
51053C
81 14 83 05
82 03
51054B'
83 04 83 18
100
C
83 09 64 04
83 11
51055B'
83 11 84 04
100
C
83 18
.
510568*
83 18
100
C
84 04
b.
IP 510618, 510638, 510648, 510658, 510668 - Electrical Cables
and Terminations
510618'
82 05 83 15
100
C
82 12 44 04
82 13
51063B'
82 13 83 20
80
83 06 83 22
83 13 84 04
83 15 84 08
83 19
51063C
81 06 82 03
102
81 08 82 11
81 11 82 15
81 15 83 05
51064B'
83 11 83 18
90
83 17 84 02
510658'
83 13
100
C
,
83 15
5106688
83 18
100
C
,
c.
IP 510518, 52053B, 520548, 52055, 520568 - Instrumentation -
Components and Systems
52051B"
83 13
100
C
84 11
52053
84 20
30
52053B'
83 13
50
C
52054B"
84 11
A6
-
. _. - _ _ _ _ _. -
.
-
. -. -
-
-
_
.
.
-
.
l
-
!
520558'
83 13
50
C
.
520558'
04-11
d.
IP 520618, 520638, 520648, 520658, 520668 - Instrumentation -
!'
Cables and Terminations
52063C
82 08
.
(Note
IP 520618, 520638, 520648, 520658, 520668 do not appear to
navebeenlaplemented.)
e.
IP 530518, 530558, 530558 - Containment Penetrat.lons
$3051B'
77 11
100
C
53053B'
79 08
10
81 02
53053C'
81 04 82 04
82 02 82 08
82 03 82 11
53055B'
79 08
30
O.
Weldino and N0( Procedur31
'
1.
Program Requirements
a.
IP 550518, 55053B, 550558 - Containment
Structural Steel
Welding
Procedure review before start of work, work
observation af ter 20% and record review af ter 30%,
b.
IP 550618, 550638 550648, 550658, 550668 = Safety Related
Structures
Weld lng
Procedure review before start of work,
work observation at 10% and 50% and record review at 20% and
50%.
c.
IP 550716. 550738, 550748, 550758, 55076B
Pressure Boundary Piping Welding
Procedure 6 review before
start of work, work observation at 10% and 40% and record
review at 20% and 50%.
d.
IP 550818, 550838, 550858 - Safety Related Piping Welding -
Procedure review before start of work, work observation at
20% and record review at 30%.
e.
IP 550938 - Reactor Vessel Internals Welding
Observation of
work during installation,
f.
IP 551518, 551528, 551536, 551548, 551568, 551578, 551588 -
Steel structures and Supports
Welding during various stages
of construction.
g.
IP 551718, 551728, 551738, 551758, 551768, 551778. 551788 -
Reactor Coolant 1.oop Piping
Welding Activities
To be
performed at various stages of construction.
A-7
.
---
,, - - -
---
n-----,.
-,,-,-----------..,<----,--.-.,-,n-...
.. -. - - -. _ - -, ~ - - - - - -, - - - - - - - - - - - - - - - - - -
-
..
_
....
.
.
...
......,.............
.
.
.
-
.
,
-
,,
i
h.
IP 551818, 551828, 551838, 551858, 551868, 55187B, 55188B -
.
Other Safety-Related Piping
Welding Activities
To be
performed at vario u sti,ges of construction.
i.
IP 55900B, 559018, 570948 - Welding /HDE
Procedure review,
material control, RT.
i
j.
IP 730518, 730528, 730f'B, 730558 - Inservice /Preservice
inspection
Pro ran r.';lew, work observations at 30% and
data review at 5
.
2.
Inspections Conducted at Millstone _ Unit 3
-
Proc.
Total
Latest
Ho.
Report
Staff
Percent
latest
'
("Priority l) Hvaber
Hours
Complete
Statys
j
a.
IP 550518, 55053B, 550558 - Containment Structural Steel
i
Welding
55051B'
75 07 76 06
90
76 04 79 08
.
76 05
550538'
76 05 77 04
50
76 06 77 05
76 07 77 08
77 01 77 12
17 02 19 04
5505)C
41 04
55055B'
76 04 77 02
30
16'05 11 04
76 06 77 04
76 07 77 12
77 01
.
b.
IP 550618, 550638, 550648, 550658, 550668 - Safety Related
Structures
Welding
55061B'
77 02
10
77 09
55063B'
77 01 78 05
20
77 08
55063C
82 04
82 06
'
55065B'
77 01
10
77 08
550668a
83 14
10
c.
IP 550718, 55073B, 550748, 550758, 55076B - Reactor Coolant
Pressure Boundary Piping
Welding
A4
_ _ _ _ _ _ _ _ _ _
.
.
. -
...
.
..
..
.
.
.....
.
.
.
.
...
..
l
.
.
I
l
55071B'
77 06 81 02
30
-
..
79 02
55073B'
79 02
C
55073C
81 11 82 06
-
81 14 82 08
81-15 82 11
82 03 83 02
'l
82 04 83 05
550748
79 02
C
55075B*
79 02
C
55076B
79 02
10
83 14
d.
IP 550818, 550838, 550858 - Safety Related Piping
Welding
55081B'
77 06
10
C
79 02
55083B'
77 09 83 14
90
79 02 64 02
81 02
55083C
81 04 82 02
112
81 12 82 04
81 14 82 06
81 15 82 11
550858'
77 09 83 14
10
79 02
e.
IP 550938 - Reactor Vessel Internals - Weldin9
550938'
82 15
10
83 01
f.
IP 551518, 551528, 551538, 551548, 551568, 551578, 551588 -
Steel Structures and Supports
Welding Activities
55155B'
83 14
10
(Note
IP 551518, 551528, 551538, 551548, $51568, and 551578 do not
appear to have been lapiteented.)
IP 551718, 551728, 551738, 551758, 551768 551778, 551788 -
g.
Reactor Coolant Loop Piping
Welding Activities
$5171B*
79 05
20
81 10
55172B'
79 05
10
81 02
55173B'
81 02 82 15
20
81 10
55175B'
81 10 83 14
82 10
106
55176B*
55177B*
82 10
50
551788*
81 10
30
A9
- - _.
-
_ _.
.
.
..
- r
.
-
..
--
,...
..
.
.
...
.
_....
... _ _. _........._,
.......,
.7
'
'
.'
,'
'
.
/
-
.
,
h.
IP 551818, 551828, 55183B, 551858, 551868, 551878, 551888 -
Other Safety Related Piping
Welding Activities
$5181B'
81 10
40
55182B'
80 05
90
81 10
551838'
80 05 83 08
90
82 10 83 21
83 01 84 06
55185B'
80 05 83 01
125
81 10 83 08
82 10 83 14
551868*
L
55187B'
82 10 83 08
90
83 01
551888*
81 10
50
82 10
t.
IP 559008, 559016, 570945 - Wolotng/ HOE
$59008
84 06
90
559018'
84 06
100
C
57904B
83 14
100
C
.
84 04
j.
IP 730518, 730528, 730538, 73055B
In service / Pre tervice Inspection
73051B'
83 21
10
72051'
R3 16
10
73053B'
83 21
10
(Note
IP 730528 and 730558 do not appear to have been implemented and
the last inspection was performed in 1983.]
(,
Miscellaneout Inspection Procedurei
1.
Program Requirements
a.
IP 30702B, 30703C, 350608, 350618, 350658, 351008, 361008,
370516, 370558, 802208, 920518, 920538, 920558, 92700, 927008,
927000, 927018, 92702, 927028,12702C, 92703, 927038, 92703C,
927048, 927058, 92706, 927068, 92706C
Various inspections
during construction phase.
2.
Inspection Conducted at Ml11 stone Unit 3
Proc.
Total
Latest
No.
Report
Staff
Percent
latest
'(' Priority 1) Number
Hours
Complete
5tatus
307028*
77 07
81 07
30703B*
Perforsed as Required
.
A - 10
-
-
. -. - - - - -.. - -..
.. -. -
. -
. -. -
.... -.
- - - - - - -
.
- - -. -.-.
.
.
.,.
..
.
.
.
.
.
-
.
30703C'
Performed as Required
-
350608
81 02 84 04
81 11
350618
81 02
50
84 04
35065B
81 02
60
351008
84 04
100
C
361005
78 01
30
37055B
81 02 83 16
115
83 12 84 04
80220B
75 01 81 03
100
76 08 43 03
77 10 83 17
79 01
l
'
920518
76 01
77 11
100
C
76 02 77 12
76 04
78 01
92053B
76 01
76 05
76 02 76 07
76 04
78 02
920558
76 04
1*)
76 05
92700
Performed as Required
927008
Performed as Required
92700C
Performed as Required
927018'
Perforved as Required
92702"
Performed 46 Required
927026'
Performed as Required
92702C'
Performed as Required
92703*
Performed as Required
927038'
Performed as Required
92703C"
Performed as Required
927046'
Performed as Required
92705B'
Performed as Required
92706*
Performed as Required
927068*
Performed as Required
92706C"
Performed as Required
.
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