ML20114G098

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Summary Rept for Regional Evaluation of Louisiana Power & Light Co,Waterford 3
ML20114G098
Person / Time
Site: 05000000, Waterford
Issue date: 04/01/1983
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML082170562 List: ... further results
References
FOIA-84-143 NUDOCS 8310050441
Download: ML20114G098 (32)
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SINmitY ItEPORT FOR ItEGIONAL EVALUATION OF LOUISIAllA POWDt AND LIGHT COMPANY IRTDtFWt0 3 000ET 50-382 PltEPAltED BY U. 5. IRfCLEAR ItEGULATORY COP 9t!SSION ItEGION IV APRIL 1, 1983 w

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PROECT HISTORY 1.

Chronological Project Milestones The application for a construction permit for Waterford 3 was submitted in December 1970. Due to the length of time required te mselve the antitrust issue. which became effective in August 1970, the permit was not issued until 463: months later en Noved er 14. 1974.

Site activity began in July 1871 with excavation bepinning on March 31. 1972. Excavatten was halted on July 15, 972.

Activity resumed on January 24,1975. Concrete placement tegen Deca d er 8. 1975.

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Louisiana power and Light (LP&L) credits delay of their engineering effort on the promulgation of new NRC safety i

requirements as requimd ty revised General Design Criteria of 10 CFR 50. Appendix A exagles of which include:

a.

Redesign of reactor vessel and primary coolant system supports.

b.

Redesign and rerouting of electrical and ISC cable trays.

l control boards and cabinets.

Modifica'tten to the fire y,e^.ection system.

c.

d.

Criteria change regarding the %namic effects of pipe l

repture.

1 Other major delays are credited to lower than anticipated sub-centre': tor productivity coupled with high personnel turnover; delays in start of construction activities due to establishment of centractor quality assurance (OA) programs; reduction in construction mort force due to difficulties in obtaining rate imrease free Louisiana Pelic Service Caunission; and the 41ementation of post-TMI requirements.

There has been no change in principal contractor. The plant is in the process of preoperational testing. Precore het functional testing bepen in February 1983 and was completed during April 1983.

The current scheduled fuel load is July 1983. LP&L was granted a 11aense to receive and store fuel on February 19.1983, ar.d received all shipments of fuel asse611es during the subsequent 8 east perted. The fuel and associated control element asse211es are presently stored in the fuel handling building.

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Principal Contractors Ebasco Services, Inc. (Ebasco) is the constructor / constructionThe manager, as well as the architect-engineer for Waterford 3.

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nuclear staan supply system vendor is Coeustion Engineering (C-E).

Major subcontrectors include:

J. A. Jones Soils /Coment Gulf Engineering Mechanical Engineering i

MISCO NS55 Installation Coe usion Engineering Alignment Sline Coatings Tompkins-Seckwith Piping / Fittings Mercury Instrumentation

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S&B Insulations American Bridge Structural Steel

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Rooter Pools / Liners Peabody Non-Destructive Examinations /

Civil Testing La. Industries Concrete Supply Feegles Shield Wall & Dome F&M Electrical Maldinger HVAC

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"L* ITY M98ANCE ORGANIZATIONAL STRUCTURE At the time the construction permit was granted for Waterford 3, the 0A organisation consisted of an engineering supervisor and a staff of seven engineers and technicians. "he engineering supervisor reported to the manager of power production. In 1976 the organization was changed to delineste the separation of office (corporate) and Water-ford 3 site staff. The onsite QA organization consisted of five engineers and technicians, while the staff had four positions. The supervisor of each of these tuo groups reported to the QA engineering mSnager.

In Septader 1981, the QA organization was enlarged and separated into four areas - nuclear operations, nuclear construction, general office, and fossil. This change was made in order to more clearly define the areas of reportability and the areas of responsibility. The organization consisted of 20 engineers and technicians.

On Secoder 1.1981, a new organization chart was approved which provided for the 0A manager to report directly to the senior vice president, operations.

A 0A organization chart which is current as of February 28,1983, is attached as Exhibit 1.

The total Lp4L QA organization has grown to include 28 LP&L personnel with support from 19 contract persons.

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SALP REVIEWS SALP reviews were conducted to evaluate LP&L's performance during the periods of. July 1, Ig80. through June 30,1981, (NRC Inspection Report 81-32) and July 1, 1g81, through June 30, 1982 (NRC Inspection Amport 82-20).

During the period of July 1. Ig80, through June 30, 1981, this facility was evaluated in the following functional areas:

Constrvction Functional Area Rating Containment and Other Safety-Related 1

Structures Piping Systems and Supports 2

Safety-Related Components 2

Electrical Power Supply and Distribution 2

Instrumentation and Control Systaus 2

Licensing Activities 3

Corrective Actions and Reporting 1

Pyeoperational Functional Artes

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Plant theretions Preparation 3

Security and 2

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Surve111anos and tional Testing 2

Audits. Review and Coeurittee Activities 3

The SALP Board concluded that negative characteristics substantiated an overall rating of Category 3 for this period. Two of the three areas evaluated la the preoperational functions; preparation for operation, and review and audit activities, were rated Category 3.

The third area, preoperational testing, was rated Category 2.

Preparation for operation was rated Category 3 principally because of a lack of nuclear utility esperianos, staff turnover problems, and insufficient involvement of permanent plant staff in the prepara-tien of plant oparating and testing iaCm. Review and audit activities were rated category 3 due to a lack of onsite preoperational QA function and difficulties it: implementing an effective document centrol program capable of %tely supporting plant activities.

Preopers.tional testing was nted Category 2 based on an observed problem of interfacing and coordinating activities with the operating orpization. It was noted that the startup group's activities wert we 1 planned and offenized and were being implemented by an experienced staff of consultants.

In the functional area of licensing review, the applicant was

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cooperative; however, their management and staffing problems required i

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+i a Category 3 rating. Staffing fell far behind showing a lack of management fj attention which reflected poorly on management capabilities.

?j The SALP review for the period of July 1,1981. through June 30, 1982, I

evaluated licensee's performance in the following areas:

Construction Functional Areas Rating

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Containment and Other Safety-Related 2

Y Structures N

Piping Systems and Supports 3

td Safety-Related Components 3

b Fire Protection 2

j Electrical Power Supply and Distribution 2

g Instrumentation and Control Systems 3

Licensing Activities 2

Precoeretional Functional Areas Plant Operations Preparation 2

Security and Safeguards 1

i Prooperational Testing 2

Surveillance 3

Audits. Reviews, and Committee Activities 3

Initial Fuel Load Preparations 2

Chemistry / Radiochemistry 1

Radiation Protection 2

Effluent Control and Monitoring 3

Transportation of Radioactive Waste 3

Radioactive Weste Management 3

Of the 18 areas evaluated. 8 areas were. rated Category 3.

Since this evaluation was based on a full year of observation, some corrective actions were already in progress; however. it was felt that l

management attention was warranted to ensure that corrective actions were adequately implemented. Although it was noted that this report was prepared during a particularly difficult time, system turnover l

and testing phase, it appeared that LP&L had been slower than most in establishing needed management controls. This was due in part

s to the late start in establishing operational QA activities. This area

'w had significantly improved during the last half of the assessment period, however, much work still needed to be done.. Significant g

improvement was noted in the areas of plant staffing and implementing

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of a training program.

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. y D. ESCALATED INGENHf MISTWlf t

One sipificant violation of Istc requimments for which LPE was assessed a Severity Level III Violetten uns identified during an f

toepection eenducted Illy 16 through July 15,1982. This violation

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uns assessed as a reemit of numerous deficiencies and discrepancies noted by LPOL's startep and QA ergantastions in both the as-built eenditten of systems effered for startup testing and deficiencies and in the sgperting quality documentation.

LPE uns notified on Decaster 6.1982. of the violetten and proposed tapositten of a civil penalty in the amount of $20,000 for failure to comply with requirments of 10 CFR 50. Appendix 8. Criterion !!.

which requires that. "The 11ty assuren e progra shall provide control over activities ing the quality of the identified structures, systems, and c p to an extent consistent.with their layertence to safety. Activities affecting acceplished under suitably centre 11ed conditions. yea 11ty shall be Enfereement centereness uere held en August 20. and November 23,1982.

Si January 4.1983. applicast's annagement requested a review and reconsideretten of the propened civil penalty. LPE requested complete sitigatten of the penalty on the that: (1) civil penalties are not norusily assessed for a 1 III~violetten in accordance with 47 FR 9g3 3 and (t) because the deficiency was identified by LPE. it ses reported ty LPE to IRC. prompt corrective action had been acknowledged by anc and because the deficiency had not been the subject of aqr prior notice of violation (47 FR 9991).

After consideration of the sequest for additional mitigation, the order 1 ing the civil monstery penalty was issued by certified asil en 16 1983 to be peld within 30 days of the date of the order. See dahibit 2.

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IIEEPDRENT MIISI EllIN Terrmy Ptees Technology (TPT), a Divisten of General Atomic i

Techselegies. Inc., conducted an independent design review of the feeduster (EFW) system for Waterford 3.

The report, dated 1983, eencluded that an adequate design control system existed i

and uns iglemented with flew exceptions. Four valid findings were i

identified as a result of their review.

t The technical review resulted in three physical design endifications.

ene to reduce the piping load imposed on an equipment.inte-face.

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to eliminate a potentia for waterhauser and to prevent pipe l

freezing for a specific section of the EFW system. Carrective action plans in response to the four findings were generated by LPR and j

uere judged by TFT to adeguately resolve the findings.

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K DEEPHEEN MARIEMN1 IISPECTIR 3 RS.1983 the MC Mobile WE Laboratory During the ported ord 3 site to conduct independent examinations wastrempettothe to 1ertfy the adequesy of applicant's solding, quality control, and A.

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^=?tve sample of safety-related welds were IEE so) in the felleslag spec 1Ne areas to be inspected:

Omality Reeeres Review _

Material TWeseshtitty.

nondestsective taamtsette Redi L1 penetreet -

Th cemens Messerements Visual Enaminett e F

Mereness feet perrtte last

,8 Retorial WertMeetten ultresente Inst tertMeetten of tesite M personnel Qualifications E K Site Bursetilance RevertMeetten of todtegraphs Enemination i

movertfleetten of Pr;eservies Ultresenic Enamination t

p Re vietettens more temattfled eartog tis taspection.

All areas i

esamleed were feued to be agespeek b'.

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LPGL has este11sted precedures providing specific instructions to the nuclear prefect support group personnel uhe are responsible for coortlestia and review of IE Circulars. Bulletins, and emneric Latters. le eesti sese, an LPK-appointed MC requests coordinator is given roepensiblitty,for assigni,gg the cognizant responsible to review and tresit all actwas and provide documentation.

required te seerttemer abs 11 draft a response to the NRC uhtch ul11 he reviamed ty plant annesse nuclear. licensing l

engtesertag ser=eesleer, and predoct support manager-nuclear.

i The sospense 11 te stened ty the vice president-nuclear eserettens and shall teclude an affidevit. A permanent record of actions takes is estatstead.

a To date. 144 1E Outlettes teve been received by LP E and 143 have been addressed. It Bullette 35 05 is still outstanding. Of the 144 bulletins received. St require response by LPE and they have responded to 51 (83-05 encepted). Of tN total telletins received.102 are not applicable (10 required reaperee). Of the 42 telletins applicable to LPAL.19 have

.been coupleted and 23 are in progress.

A total of 108 ft Circulars have boon veceived by the Nuclear Pro.fect Supacrt l

l Grew. Of the total,) response uns required and made to 3; 62 wer I

Of the 62 applicable stremiers. g_ response and 41 unre not applicable.15 have been es (3requirta l

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States of IWt Generic Latters received by applicant is as follmes. To dete. 67 generic letters have been determined to be applicable. The work en 14 has been completed and eart is in pr g ress on 53. Seventy-five have been evaluated and determined not to be app.icable. One hundred and three are being evaluated for applicability.

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LIGISEE. NIO CEURACTOR INITIATED STOp 40RK ACTION There have been a total of S stop mort artiers issued by applicant and Ms contracters, see tahtbit 3 for a summary of stop work orders.

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CtN57RUCTTW EUCIDICY REPW5_(10.CFR 50.55e)

LP&L has reported a total of 73 significant construction deficier.es.

See Exhibit 4 for a tabulatten of these reports. Nineteen of t'.se reports remain unresolved.

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pART El IIUf1FICATIGIS

' f, Fourteen Part 21 nettf1catiens were issued luy applicant. See Exh1 bit 5 1

i for a tabulatten of these notifications. Only one rareins open.

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M; INIPECTIM ACTIVNIES j

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Constrectfen Inspectice i

um samPae+1em Program IE 512 ts predsminately applicable to r

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. site constrectlan, ilsterfor113.is 935 couplete and inspection activttles for the construction phase are asentf ally complete.

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Prosperettemel lissting med Derettenal Properabioss IE 513 ts directed temord inspection of activities involved in prosperettamal testing and operettenal preparedness. These inspection activities any be summerized as follows:

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Prosperettenal Test Precedere Asvier 100 prosperational Test lHtnessing 80 prosperstianal Test Result Evalustian 0*

D erettenal staffteg 95 Omattty Asserence 95 Inspecties of D erating staff Training 90 Tecsuitest Specification Review 30 Derettenal Precedures Review 40 Radietten Protectlen 90 Ae6 mate 80 Radio Chemis 85 Environmental itoring 85 Emergency Planning 25 security as

  • Prosperational test results have only recently been received from applicant, therefore these inspection activities have justbegun.

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Startup Testing f

Inspection estivities required by MC 2514 establish the inspection program for the startup testing phase. Waterford 3 1s just entering this phase, therefore inspection in this area has just begun. These activities include:

04/OC Technicet specification aeview Initial Ruel Lead procrttical Checks peuer Ascensten Testing Initial Cetticality/ Law power Testing Data Review 4.

TNIOpenItems(T! 2514/01, Revision 1) i nost of the 1MI lessens-learsed issues were specifically addressed during the F5AR review process. LpAL has completed approximately 50%

of the TRI heresere items. Administrative and procedural items are in various stages of development and will be itamized and updated in the nest report. Duries the startup testing phase (MC 2514) each of these span itens will be individually inspected and closed out in accordance with the tagerary instruction.

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Allegettees -

h A total of 10 allopettens fic to the Waterford 3 SES or its principal centracters have received by the NRC since i

Aprt1~15EE. Eight of these have been closed out. The remaining tus allegations do not appear to represent safety issues of such si ificance as to affsict license issuance. These items are he folleued y en as a reutine part of the inspection process.

Addi ene11y. verteus vender related allegations are under review uhtch could affect a breed category of plants, including Water-ferd 3.

Retification and correction of any prob 12ns uncovered to this aanmer will be handled via IE Bulletins or other motificettens.

4.

IRR Confitentory items (To be verified by Region IV program) i jLRh Description of item 6.3 Review ECCS test program and results 7.1.2 Arrisw procedures for IES 79-27 11.2.2 Test HEpA and charcoal absorters 11.2.28 Verify testing of RAB ventilation system in accordance with ANS! M510-1980 2.2.2 II.A.I.3 Verify that all instructors have complette SR0 examination prior to fuel loading e-

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SER Section Description of Item

!!.8.1 Review operating procedures and test procedures for RCS vent systeso prior to operating above 51 power

!!.8.4 Verify training program before fuel load; verify training prior to operation above Si poder

!!.E.4.1 Reviou plant procedures for hydrogen recas6iner use

!!.F.1 Verify installation of systems

!!.K.1 Review procedures concerning ECCS valve operations II.K.3.17 Review program for reporting ECCS outages II.O.1.1 Review leakage monitoring program

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CSISMCTlWI STATU5

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j Those structures systems, and components for uhich construction is not-essentially cogIete and thich could affect the safe startup and operation of the plant are as fellous:.

Itydrogen Recombiner Conta1 ament Vessel Polar Crane Sttssile Shield Contefament Building Lighting teacter Auxiliary Building L' ghting 90evable Incere Nuclear Instrumentation Centstament Vocean Relief These items have not been released to LP&L by the contra: tor. Each of these systems has been selked down to determine their completion. Punch-l lists have toen generated. There are essentially 13.129 open items on the systems required for fuel load. Of these open items, approximately 4.606 l

could affect the safe startup and operation of the plant. These open items can be classified into the following six categories:

Pipe Mengers.18tip Restraints. Snubber work or Rework Document Verification and Review Environmental Qualifications Replacement Design Changes Delayed Construction Completion Weld Repairs Instrument Tubing Repairs e

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U Constrection is 935 complete with many items scheduled for completion I

after het functional testing. All items required for safe operation l

of the plant will be completed and tested before fuel load.

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MEOPEMTIOML TEST RESULTS 7 i

LfGL starte peup has determined that the plant will be safe for fluel lead when the fis11 ewing systems have been prerequisite /preopere-tional tested. Net all systems 'ere required to be prosperational tested my at angelatory bien 1.m. novision 2; homever. LP&L will preregetsite/preservlee test.these systems (not listed) before they' are declared operational.

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Prooperational

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100 4-S/U TvensfIsraers -

30 SA S. R. Inverters 100 10 Communications 11 Lighting -

13A Most Tracing Sailety-Related '

18 Radiation Manitoring 35 21 Fire Detectism

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22 Fire protection

[ 23 Instrument Air.

. 25 Nitrogen

'1 36 Component Coottog IInter - Cooling Tauers 36-2 Component Cooling tinter - RCS

. 35-3 Component Coeling IInter - Salance 39 fuergency Diesel eenerator 40-7 Polar Crane 4 43A RCS Contaissent Coeling 90 (33 IICS Shield Butiding Ventilation 43c RCS Annulus Itegative pressure 43E RCS Vacusa Relief 43F RCS Centrolled Atmosphere helease

. 43G RCS Airborn Radietten Asmoval 43H RCS W Recediner Analyser 43J RCS Centrol Clement Drive Mechanism 40 Coeling 46A 948 Cable Vault & Switchgear Area IIVAC 468 RAB Centrol Asem MVAC 40C 4AS floreal Ventilation Area HVAC 480 RAB Centre 11ed Ventilation Area HVAC 46E RA8 Chilled Water -

stb Pressuriser and Quench Tank 10 53A Charging and Latdoun 75

i Preoperational

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Distr 1Dt1on

  • % Cowleto 538 Soric Acid Makeup and Chemical Feed 80 54-g Primary Sampling,

56A Beren Menegament,

SEB toric Acid Concentator 58 Refueltag Water 90 Containment Spray 100 804 Nigh Pressure Safety Injection 100 g5 Lar Pressure Safety Injection 100 00C Safety Injection Tanks 100 41 Fuel Hand 11 and Storage 14 63 amering fety Features 50 44 Centrol E1anent Drive 55 NA Encore Maclear Instrumentation M Incere lheclear Instrumentation GEC 4tevehle Incere lheclear Instroentation,

85 Plant Protection 10 88 Reacter Angulating S V1tretten and Lesee Parts Monitoring 80 73 tuergency meetsetse 66 M

Steam Generator (M51Vs) 30 l

6 indicates that pIqysteel bting is complete with the menining 105 elleued for review and asseptance of test results.

The prosperations) test progeen is 245 complete and will be 265 esoplete with the conclusten of het functional testing. It is the intention of the Meterford 3 startup group to have all deficiencies uhich could prevent safe system operation corrected and tested by feel 1eed.

1here are at prosperational and system integrated test procedums that are in the draft stage. They are listed belou along with scheduled completion dates.

5F8 48 001 Reactor Regulating System 3/22/83(StartTest)

SIT-TP-300 Integretos Engineered Safety 4/11/83 (Start Test) l Featurge SIT-TP-400 Initis1 Fuel Lead 7/17/83 SIT-TP-503 EDM Performance 7/17/83 SIT-TP-50g Postcore MFT RCS Expansion 7/17/83

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Measumments STT-TP-513 Postcore Vibration and Loose 7/17/83 L

Parts Monitoring System SIT-TP-600 Initial Criticality 7/17/83 SIT-TP-650 Law Power Physics Test 7/17/83 r

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$!T-TP-700 Power Ascension Test Contmiling 7/17/83 Doceent

$!T-TP-708 Initial Turbine Startup 7/17/83

$!T-TP-715 81ological Shield Effectiveness 7/17/83 Surver 517 T7-718 Variable Tavg Test 7/17/83 SIT-TP-727 805 Total Loss of Flou Trip-7/17/83 Natum1 Circulation Test SIT-TP-738 Less of Offsite Feuer Trip 7/17/83 517-TP-734 M10C5 Detector Checks.

7/17/83 SIT-TP-738 Feeduster Control System 7/17/83 Post Trip 5etting SIT-TP-743 Pouer Ascension Testing 7/17/85 i

Ventilation capability SIT-TP-747 PLCEA Xenon Cont al 7/17/83 SIT-TP-74g RPCS 505 Power Loss-of-Lead 7/17/83

$!T-TP-750 RPC5 708 Peuer Lass-of-Feed 7/17/83 SIT-TP-751 RFCS 805 Peuer Loss-of-Lead 7/17/83 SIT-TP-752 RPCS 1005 Power Loss-of-Load 7/17/83 SIT TP-753 RPCS 1005 Power Loss-of-Feed 7/17/83 i

$1T-TP-754 Turtline Generator' Perforemace 7/17/83 geogre r.

SPD 538 40t

. Seric Acid Mahoup and Chemical 7/17/83 poed i

w SPO-888-001 Liquid Weste Management System 5/"3/83(StartTest)

SPO-EEE-001 Laundry unste Renagement $ysten 5/23/83(StartTest)

SPD GS 808 Pp5 toepense Time Test w 4/15/83 SPD 88 001 Seester RegWlettag tem 5/17/83(StartTest)

$P0n70 801 Reester Pomer System 7/17/83

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Status of major system prosperational testing as of March 24,1983 is a fellems:

l Estimated Actual Desadation Start 5 tart complete Power Distribution System 02/07/83 70 Diesel Generators 03/23/83 Pressuriser and Quench Tank 02/15/83 90 Chemical and Volume Centrol System 11/26/82 75 03/22/83 Seren 03/27/83 ~

Safety ten 08/05/82 100 r

Eaglesered Safety Features Actuation 12/06/82 50 Plant Protection 03/11/83 15 Emergency Feceseter 01/10/83 80 Cantainment Cooling 01/17/83 90 Control Red Drive Mechanism 01/05/83 75 O

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Estimated Actual Description Start Start Complete CEDM Cooling 02/25/83 50 Cold Hydro 10/02/82 100

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Secondary Hydro 10/08/82 100 Pre-Core Het Functional Testing 02/28/83 70 Less of Offsite Peuer Test 06/04/83 ILRT' 04/15/83...

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  • 905 indicates that physical testing is complete with ramaining los alleued for review and acceptance of test results.

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CWCUBIE 7

l LPSL historically has published overly aptimistic fuel load dates thich have met been est. Actual fuel load date will depend a

deal.en the time it takes to complete the systems and on si ficent testing and evaleetten of test results that still a to be completed. An W Case Load and Fomcast Meeting, which will assess the status of eenstruction completten schedules, is i

I scheduled for June 1 3. 1003. :

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LPSL sosier senegment enh1Mts a high level of interest L

l and support for the Waterford 3 project and has been responsive to W esseems. Lp6L has feend difTieult economic and staffing pnhiens te part ese to the temp learning process that a non-nuclear utility must underge een bef1 ding their first nuclear plant.

Due to e philesephical approach that placed heavy reliance on Ebasco as construction anneser. LPE maintained a small 0A steff until early 1982 uhen quality problems started appearing during tne tuvasver preessa. Since that time, LPE significantly expantied their 04 staff from 7 to 90 peepia and have become a strong lefhence en site activities..

Prior to CL. additional NRC reviews of staffing, training, and overall operational readiness att planned. These reviews, along with atter planned inspection activities, will be used as a basis for a secommendation regarding a Waterford 3 OL.

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_ r J mu EXHIBIT 1 AL CHART QUALITY ASSUMNE ORGAlIZAT 28, 1983 Fat,ruary OPERATINIS Sr. Vice President-I QUALIFY A55WtANCE I

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GDERAL OFFIM I

LPSL 7 -

IRICLEAR CSISTRUCTim Consultants 2

LPSL 7

Censultants 0

F055!L LPAL 2

consultants 0

WICLE M GPERAT! W5 1

LPSL 11Cnnsultants 12 STARTUP LPAL 4

Consultants 5

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EXHit!T 2 ESCALATED DtFORCEMENT ACTION Escalated Enforcement Action-neeson for Action corrective Measures Civil Penalty Issued 3/16/83 Severity Level III Violation Increased ausreness en.

por IRC lampaction Report of 44 voquirements e,f part of LPSL menessment.

50-M2/82-14 dated 12/6/82.

10 CFR 50. Appendix 3 Increased sine of QA staff.

Criterien !!.

Improved audit program.

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STOP KWK ACT!ON EXHIBIT 3 heesen for Star: Wort Corrective Measures Year Orsenization period of Stas We d Concrete Placement Activities Provided more stringent controls for placement 1975 J.A. Jones 12/14/75-12/14/75 and inspection.

l 1975 J.A. Jones Cenerete plassment 15 had Core sogles taken. All surface defects:end uns betas cylinders exceeded spec.

covered with testft11.

requirements. Repairs made 2/12/M 4/14/76 per J.A. Jones precedure I

W-SP-5.

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- Concente uns a11 sued to stead All guestieueble conwete for extended pod ed. suspicien uns chipped and unter jetted 1975 J.A. Jones af cold joist. 4n/55/10nl to sound concrete. proper repairs made by J.A. Jones.

1976 J.A. Jones Concrete Placaneet Activities Established edittional centrols to essere lack of 5/7/54/M/M J

cold joint cemettiens la concrete plassenets.

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Precedure corrected.

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19N CS&1 reviewed and tased teing esed.

acceptable.

Review of backft11 layers 19N J.A.Jenes Spanged scales used to test deterudmod backfill te be cegacted backft11.

of proper elevation and IC/12/510/12/N compacted te acceptable Itaits.

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-landegusta toeperature control 04 inspecter put on third shift.

en concrete curing.

1/25/77-1/31/77 Cowrote pleessant been Ned Liquid peneteent testing tesofficieet ME se fillet of males was perfereed and f

19U J.A. Jones all welds were witnessed meld en pipe speels.

eat scapted by QA.

5/5/77-5/8/77 Concrete placement in need of Repairs mere casoleted per repstre en mes. 502-12 6 502-14.

disposition of NCR.

1977 J.A. Jones 7/26/77-9/30/77 l

Evaluation showed 11 of the 12 1977 Peabody Co. crete had les_s then the batches were within acceptable I

(

Testing required 4000 pl1 9 28-day

)

beesks. 9/1/77-9/3/77 Itatts.

/

_. _ _ _.. ~

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p.m e

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v m

. n 7_-ammxwnm. an ::

a e

g i

e Reason for Stop Work Year Organi:ation Period of Stoo Work Corrective Measures 19U Gulf Engr.

No approved pmcedum for Gulf Engineering procedure placing fleuable grout under approved.

equipment. 9/19/n-9/11/77 19U J.A.Jenes Backfill being placed without J.A. Jones provided 100%

quality verification personnel

'nspection for~each area bei 1005 ef the time, being backfilled.

9/

-3/3/7Fc.

e i
t. _

. tT L.

19U Fischbeth &

Laminatten deflects appeared Perfomed HDE for Mesm. Inc.

after meldt uns complete en acceptability.

Clip #0 M1

..172.

9/21/M-9 1

19U Temekins-Meld prec. Qualification-Wald procedum revised.

esckwith 9/27/n-10/5/n 19U Gulf Engr.

Fies time for great encoeded Greuting specification procedure limits revised by Ebasce

, 10/28/77-11/2/F7 1977 FiscMech &

Re documentatten entsts showing IIenufacturer's representative i

Moore. Inc.

tratulag of pereennel for conducted tratalog.

Insta11atten of ancher helts.

11/2/ M-11/3/FF.

y i

1978 Fischbach &

Class A (Seismic) beckf111 has precedure approved and all l

Moore. Inc.

heen put in place without an A Sockf111 arewteusly

~

engineer approved precedure.

placed has been replaced.

1/27/78-3/7/80 1978 Maldinger Phillips expansion anchors have All Phillips anchors were been found to lessen after checked for torque and toeg eing.

accepted er rejected. phillips 1

l l

3/1/78-7/17/78 brand expansion anchors were l

suspended from further use.

'i978 Tompkins-Unspproved asterial IICR TS-30 issued and closed.

Beckwith insta11ed. Post. #25.

6/9/75 l/9/78 1978 Tompkins-Inspection requirements for Inspection requirements Bockwith Penden Steel. 5/8/ 5 6/1/78 issued.

1978

$1ine Coating peri-e for inspection. Audit performed showing painter erslifications, and

$11ne had an acceptable application not approved by QA program.

Ebasco for use.

5/3/78-5/5/78 w-

__y

.,,_,,_,y.

__,,,,__.m

e n -- ; _- -

c

.ag a m m, n. m. y.

. ~.

Reason for Stop Work

(

Year Organization Period of Stop Wort Corrective Meawre 1978 Ebasco To determine if specific Cabinets determined to be procedure uns required to unload category "c" recuiring no instrument cabinets.

specific handling, i

6/2/78-4/2/78 1978 Waldinger E-40XX electrodes were Supports were audited and i

taproperly used to weld accepted or rujected and i

structure 1 to fined reworked per Ebasco I

plates..

r.

requirements.

[

x.-

g,.

y

[

1978 All Westing-Evaluate stysical. chemical and Vendor furnished satisfactory l

house moisture test en Mestinghouse CNTR. Meets NS-2400 t

electrodes E-7018 electrodes.

requirements.

9/25/78-10/9/79 _.

t t

1978 International No precedure approved'for Procedure twiemut and Rigging assedly and lead testing of approved for implementation, j

outside trestle end asso. lifting and hand 11 equipment.

10/24/ 5 1 i

1975 thesco Microfl1 ming of 04 Records Procedures approved and l

10/16/78-10/16/79 1ssueds evaluation of prwvious wort completed.

1978 Theepktas.

Unautherland personnel Procedure 13P-4 r wined.

Sockwith signature.

11/15/78 1978 Tompkins-Meterial defects.

NCR TS-48 1ssued. Material Sectarith Meterial Ht. No. GBC returned to Ebasco and NCR 12/15/78-12/19/78 closed.

1979 All Wald Wald red was manufactured Aud!t performed to detemine Rod Users and supplied by unapproved location of material. All source. 1/5/79-1/10/79 locate.e. None issued to cont

  • actors doing code work.

1979 NISCO Repairs on Pressuriser Support Supplement to NCR issued 1/25/79-2/2/79 providing adequate direction on repairs.

1979 Tompkins-Weldt operation Pent. #42.

NCR TS-42 issued and closed.

Seclarith 2/26/

3/27/79 1979 Nooter Corp.

Contractor not fulfilling a11 Procedure approved and requirveents of 10 CFR 21.

issued.

3/15/79-3/15/79

m.

)

Reason for Stop Work Year roanization Period of Stop Wort Corrective Measuret 1979 511ne Insb111ty to surface prep. RCS Perfomed power tool preo.

bridge crene properly.

3/20/79-3/21/M.

1979 sline Blast without inventory Inventory performed.

3/30/79-3/30/M 19M American Leeding of +45 strecturel Cervective action completed

{

Briden steel to M B'goles en without and verified by site 04.

cowletten of C/A en previously i

addressed repairs. '*

3/30/79-7/XVW.T 1

1er

' Additional test performed.

Tg f 19 3 1979 Tangkins-

.' Ilsacenfaming enterial - 4" 458 Dispositten uns to cut out Seclarith I

redius ells and 4' 90 long nonconfo ming asterial.

j 8

us std. ells.-

4/6/79-7/12/79f 19M F&W IIsiding activtth en 4:18 KV F 4 N Instructed by Basco

~

(Sf)MS A. 383-5 7 MS-S has to pressed with IICR C/$

r as acespted evolustion provided as precedure.-

I 4/9 7ht/79 t

y 1979 theseo etwt going en shove tendequately Tempemry setorials removed protected h1We pressure safety and adequate protective A and B.

covers installed.

1979 F&M Pailure to follow procedures for Training requirements placed prep. of cable ends for applica-en personnel to gustify to tien of stress cones for Calverts perfom activity.

Bus. 6/s/79-4/s/M 1979 511ae Shop discrepency in mort descrip. Production in cose11ance tien and held point bypassed.

with program requirements.

7/27/79-3/14/83 1979 Tanskies.

Material treceability question.

Material traceability Becserith able. 8/10/79-8/13/79 established.

1979 Fea91es Inspection and control of Corrective action require-concrete placement operations.

monts (14) imposed to 8/17/79-9/17/79 address control & inspection.

19h9 511ae Loss of contal of traceability.

Ebasco imposition of 8/21/79-10/1/79 stasping requirements.

I

_ __ m m.

~

Feason for Stop Work tere Omanization Feriod of Step Work Corrective Mee w-1979 Ebasco Overhead work by HVAC construc-Protective coverin; inua' lec tion personnel above unprotected to prevent damage.

diesel generator control panels.

8/31/79-9/10/79 1979 Fischbach &

Cables pulled from reel on QA Cables meggered and coroleted Moore

hold, final disposition of MOR.

9/14/79-3/8/80 1979 Tompkins-Failum to install fiberglass Additional quality controls Sachwith piping in accordence with Ebesco imposed to assure speci-specifications. 12/4/79-12/6/7*

fication requirements are addressed.

1980 Tosekins-Walder Qualification Qualifications established.

Sochwith 1/16/80-1/16/80 1980 Tompkins-Two inch and under non-safety Guideline deficiency 1

Seckwith ses11 hore piping not being resolved. Two additional installed to Ebasco guidelines.

pipe engineering support 1/28/80-1/30/80 persons added to staff.

1980 511ne Damage by others to elevetor See NCR 5-17 8 Ebasco shaft "D".

2/12/80-3/16/83 letter F-4695 E 1980 511ne Damage to coating wort by other Demoged areas repaired.

crafts while costing in progress. Sespective contractors warned 1

2/12/W-2/24/81 they could be charged for future damage.

j 1980 LP&L Document control (Startup 5AP-03 revised to provide Group) 3/6/80-4/23/80 adequate controls.

1980 NISCO Noncampliance with test NCR's issued delineating precedure and contract spec. on requirements and procedures hydrostatic testing of contal revised accordingly.

element drive sechanism.

3/24/80-4/23/ 5 1980 Gulf Grouting had started without an An FCR was iniu sted by approved traveler on chlorinator Ebasco defining 1'.sta11ation unit. 4/15/80 5/13/80 procedures. An approved traveler was generated from these instructions.

1980 NISCO Inadequate program for training Program upgraded to provide and quellfication of OC acceptable program.

personnel. 5/7/80

+

v --.

- -.m % a c..,,..;.,..

Ij.

l i

i Reason for Stop Wort i

Year Oreanization Period of $too Work Corrective Measum 19W Basco MVAC Force Account was instal-All ASE Class 2 code work ling ASE Class 2 or 3 MVAC turned over to Tompkins-butterfly velves, f1 Beckwith for rework and fittings, etc. 9/15/

11/17/80 completion.

4 1980 Tempkins-Precedum does not provide Procedure mvised and l

s tecturtth inspectlen steck11st isr verify-approved.

ing and desusenttog the essential t

attributes et festelletten and l

[ pi Inspeetten steel i

i 2*

be1ts.:

?:u

@ y%gnmy W

)

i l

l19W Itercury Seisele supports W installed Design review performed in assert nee with drastags and approved for seismic

?

.c y ;. m it :i w 1981 Fischbach 4 Interes1 separetten of associated OCN-E-4021soned to correct finere cireutts saanet he entstelnad deficiency.

l ras 451'. elevitten to ICC's.:

1/x8/813/18/88 '/:

a;+ ; m u w;7 "b,'

1981 Fischtesh &

Internal esperetten~ef asecciated BCN4-401 issued to cermet Itsere ctsgetts esmet to estetstead deficienqF. '

in IEC's FIS +1' elevetten.:,

1/23/SI-4/1GISI.s q "i~s '

i

  1. C.,dh O'>Q

~

1981 Fissthoek &

Internal esperetten safety and Condition is acceptable and i

i IIsore non eefety and assectated will be documented in an circuits cannet te metatsined in FSAR amanement.

l CP's. 2/17/81 3/12/81 1981 Gulf Tie in of pipes per'Ehesco IIC-1 specification was segervisten to sendenser water revised by Ebasco to allow and C was in viola-construction to continue.

pengs A. B.1 and PC-1 specifi-tien of IIC-cettens. 5/27/81-5/29/s1 l

1981 Gulf theses renewed fire retardent Basco wrote a memo allowing plyused from met cesling teuer Gulf to weld in area with aves and laced with non-certain restrictions without.

retardent fire retardant plywood.

5/29/81 1981 LP&L plechine Shop A5P-IV-78 1ssued to control 4/30/81-7/9/81 activities performed by j

machine shop, i

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__,,,-.---__._m m

J Reason for Stop Work tear Omantastion Period of Stos Work corrective Nawes j

1981 Topekins-procurement of aschining by Gulf qualif te'd, P.O.

I teckwith Gulf Engineering supplemented stating quality 7/14/81-7/15/81 requirements. Directives issued rw9erding use of Gulf l

shop.

I 1981 N!SCO performing cort en items under S W generated to document QA j

a held tog. 10/3/81-10/13/81 nanuel violatten. Upon clostne of NCS's 147, 152. &

138 SWB uns 11 feed.

{

f 4

. Jg s.

i l

1981 All All centreeters wors' testructed that use of ISC Dimetcote i

Centracters EZ-II sprey to eenfleed to touch op en conduit throeds and EZ-Zinc costing te eens.stell be used en melds or touch up of galventand surfhese facInding conde1t threads.

10/5/81 untti flerther esties.-

.,7 wn gen.

l l

1982 50 Sand did not meet ftcetion Test results show sand to be requirements.;.1

-2/12/82 within acceptable limits.

)

,. y 1982 N!SCO Dt to meld ved les en precedures were revised.

contre e' CS and SS filler Training implemented en

'l motorial and hand 19eg of same.

storege and handitag of 2/3/M 12/tt/ Wf j,, jy filler motortel.

l

. 3.s...w.

m..

i j

1982 Bases ne precedere for the og. AW-N-E and A$p-N-5. -

[.

evelaatten of issued to provide i

I Pipe tangers.3 engineering evaleetten.

t

- n y.. av f

51tne meesthis predett ftflere of Vender representatives and i

1982 Cartes 1ec 11/phens11ae 35 en thesco engineer evaluation j

SCS Itser. 4/30/St-5/10/St acceptable.

1982 Self Tie-in of pipes to sendensate Pipe tie-ins were corrected l

pumps were te violetten of MC-1 to comp 1; with MC-1 and pc-1 i

and pC-1 specificottens.

specifications.

3/6/32-3/8/82 1982 LP&L Damage to cogenents during CIMA issued requiring inspec-l reassently of reacter coolant tien and repair.

l pump ester S. 7/2/82-7/13/82 l

1982 Ehesco Service fieras de not specifically Service focus revised to delineets mort performed in satisfy audit.

disasseely. inspection and reasses61y of cesponent cooling j

fan. 9/3/82-9/17/82 1982 Ebasco 0A/0C F e: t.; not being Anchors were accepted or follemed in installation of reworked after inspection.

expensten anchers.

Craft instructed to follow l

9/3/82-10/20/82 installation procedures.

l l

4

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,,.,.--wen

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. ~.

Reason for Stop Work Year Organization Period of Stoo Wort Corrective Measures

_. erforming installations without Procedures were instituted.

p 1982 Ebesco following procedures nor using proper interface according to procedum. 9/22/82-10/18/82 1982 511ne Isomper defects in cured film New product delivered for use.

of Cartoline #191 primer.

10/28/m-11/tt/02 isst sa8 Procedums landsomete.

num procedura t oi m ented.

11/18/m-1/3/s3-1982 LPSL Continued nonesspliance with Engineering evaluation made F14t and failure to comply with as to acceptability, program co'vective action stated in instituted to control future response to LP8L construction purcheses.

GA's survey moort W35 82-785 12/3/82-12/20/82 1983 Mercury Lack of guelifted melding-Cormctive seasums not yet precedures for melding cowleted.-

on toestreck umiding.

3/22/83-St111 in effect.

l l

l l

i

i CONSTWCTION DEFICith;Y FirMT5

[XHIBIT 4 CDR ko.

Brief Descrip!1on Corrective Measums 1

Cassion Foundation Mat - Block 19 Mat was resurfaced. F epai rs inspected and documented.

j 2

Reactor Auxiliary Building Interior Documentation for Wall '1B was Wall 518 reviewed and found to be accurate.

3 Common Foundation Structuru Mall nepairs to affected area Worwed Placement 4995 M-11A4 in accordance with J.A. Jones precedums. Sutsequent verification and inspection revealed no irmgularities.

4 HPSI Target Rock Valves - Escessive HPSI valves redesigned, disassee61ed pressum Drep and new design incorporated. All other valves in safety-related systems were not supplied by this manufacturer.

5 I-4 8 20 W LP5I Puses 8 Impeller Shaft Manufactemr developed modification Astaining Mech. Failure kits for pump impeller locking devices for more positive locking.

Installation en pimps completed.

5 Part 21 Report - See Eshibit 5 7

Less Centsw1 Element Drive Mechanism C-E completed corrective repairs.

Repairs were visually inspected and verified to meet pmcedure requirements.

8 Contatament Electrical Penetration -

Weld repairs were performed, flanges Solting Failure were sandblasted and primed in accordance with procedures.

9 noncompliance with Welding Requirements All repairs made for hanger to for MVAC Seiseric Support Hanger to embedded plate welds by Waldinger Esbedded Plates or Ebasco. Repairs inspected and documented by 0A/0C.

10 Part 21 Aspert See Est.ibit 5

.11 Switchgeer treaker Position Switch All 33 breaker position switch Operater Defect operators have been replaced with newly designed switch operator assemblies. Reinspection coreleted.

D 0

}

i CDo km B-icf ;esertption Corrective Measures t

18 Part 21 Report - See Exhibit 5 13 Reactor Containment Building Dome Repairs were made to the concrete.

Concrete Cores were taken of the repairs and tested. Corrections were found to j

be acceptable. Corrective measures implemented to prevent recurrence l

of this problen.

14 Unsatisfactory Ispect Tests en Pipe Penetration asse elies returned to penetration Asseelies 3 and 4 menefacterer for romert. Assort 5

produced acceptable process pipe for Assedly No. 4 and Asseele No. 3 mes replaced. Increased scope and training to provide more emphasis on revice of preparetten of 04/0C t

records.

15 Procederst and Performance Deficiencies Condition inspected and docusented in Ultresenic Testing of Structural as item of noncompliance. Follow-Welds performed by Industrial Engineering up inspections performed and this usets item uns closed in IMC Nyt. 81-07.

16 Centrol Element Drim Mechanism Golds C-E completed servective repairs.

Cenes Off-Set;

~

17 Base Metal Defects in Main Steam and Cracks have been repaired. Design Fondater Centeineent penetration Anchers has been reeveleted and modifications '

made. All mort has been tested, approved and documented.

18 part 21 Report - See Emhibit 5 19 Target Rect Meter Operated Valves All valves modified to prevent Sushing Not Staked threaded bushings from rotating.

Wert has been reinspected.

i 20 Inadogmate Design / Design Review of Review and analysis completed.

Instruosntation Seismic Support necessary rework completed, reviewed Drawings and doc uented.

21 Lineer Indications in Electrieel Cable Meck-up lead tests performed under Tray Seismic Seppert Clips most critical lead conditions on most susceptible seterial. Clips were found to be atructurally sound and adquate for their use.

22 Inadequate Elec. Insulation on Ex-core Repairs completed 7/20/81 in i

Neutron Flux Detectors accordance with C-E procedures.

Repairs inspected and documented i

by C E.

1 w

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--wt-

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4 Coc fe.

Brief Description Corrective Maasures 23 Fart 21 Report - See Exhibit ~5 24 Part 21 Report - See Exhibit 5 25 Defective E Circuit Breakers Bearing and associated assectly en (AKR-30andAKR-50) 86 breakers replaced by Ebasco N

Feeduster Isolation Valves Tag.

To insure cold weather operation of Maintenance of Actuators Ancher the actestors, bones have been Berling built ever the actuators and i

hosters installed to keep actuators i

i above miniese tageratums.

27 Switchgoer Breaker pesitien Switch All 33 posttien' switch opereter g91 des i

Operator Defect have been aligned with appropriate 4

breakers in accordance with E drawings and under E techniul direct <en.

\\

28 2* and telen Schedule 140 Socket Socket welds reinspected. Additional Melds understae (T88) unid metal applied where required.

Corrective actions verified by Ebasco.

2g landequate Clearnese beteen Process theses performed stress analysis on piptog Systens and ten-TM Suppects/

the supports and submitted results Asstraints to TSB for romerk. Centract require-nests en restraint gap clearances f

sere changed to preest recurrence 7

of this deficiency.

30 Chanda A51H A 193 Stainless Steel Repairs completed 12/18/81. Repairs Bolts en 80 ster Centrol Center Bus Bars inspected and documented by LP&L.

31 Incorrect Friction Facter Used in Open Design of Pipe Seppert Mengers 32 Stress Analysis for Molded Pipe Open Sepport Attachments Mas not perfomed Prior to Fabrication 33 Ch111ed Water Piping Supports Open N

Part 21 Asport - See Exhibit 5 35 Meterial properties of Time Track Open and Molded Fittings 36 Short Circuit Bracing in E Vertical Field modifications submitted to and Lift Metal-Clad Switchgear Equip.

approved by GE. GE furnished kits of parts and instructions. Modifications were completed and documented.

--ny.

wa-

-,,,, _, _ _,_n_,,_,,

i pc h-8-tef Nseripten Corrective %sur s 37 Teeperature Detectors' (RTS's)

Open Failurt 38 Startup Test Control; Flooding of Panels were replaced with new pancis Emergency Diesel Generator Control from Cooper Energy Services and Relay Panel 39 Fire Demoge in RCS to Main Steam Area was secured and inspected. No and Safety-Related Cables mechanical properties were damaged.

Area was cleaned and necessary repairs completed. All wood will be replaced with fin retardent meterial through-out plant island wherever possible.

40 Port 21 Report - See Exhibit 5 41 Unepproved Welding Unapproved welding was identified, disposittened and corrected.

42 GE MA Aand11ary Reitys Open 43 Main / Emergency Feed Water System homoved internals of check velves and Panel added two check valves deumstream of each EFW flow transmitter. Design changed and corrective action was reviewed, accepted and closed.

44 LPSI Pump Section Va?r s Two new check valves added; deleted proposed enter operators and required that the valves be locked open.

l 45 AKR 50 Relay tell Suitch Mounting Failed components were replaced. All Failure others were modified to correct problem.

46 C:;:r "::semer Emergewy Diesel Relays removed and returned to Genereters Agostat Relay Defect manufacturer. They were mpaired and replaced. Repairs were reviewed and docuented.

47 General Electric AKR-30/50 Circuit Field inspection performed. Screws treakers Closing Spring Screw reinstalled er replaced as necessary.

Docuentation reviewed and verified by 04.

48 Dest @ Application of Break Flanges All flanges were analyzed by Ebasco.

at E' evated Temperatures Flanges which did not meet the code roovirements were replaced. All flanges now meet ASME Section 111 code requirements.

i

^

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=

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m. n '. c *e r. u-r.

49 Part 21 ReNr - Sec Exhibit 5 50 Part 21 Report - See Exhibit 5 51 Singham willia==tte Energency Feed Determined to be non-reportaM e Water Pops (hdHT) 52 Bi-Metallic penetration hids - No New penetration assert 11es were Stmss Relief obtained from vendor with correct l

ptMT perfomed by vendor ard these have been installed.

53 Part 21 Report - See F.shibit 5 i

54 Tube Steel (NT #16600) Laminations Open 55 tield up and Boric Acid Make up Tanks Open Incorrect Structural Calculatten 56 KB Liner Plate Maclear Coatings Open Failure I

57 Inadeguate 14C Installation and Open Turnover Doceasestation C3 Cable Trey Fire. RAS at +35' Level Damaged cables identified and molaced.

Ramsining cable was tested by cable manufactc..r. All cable found to be acceptable.

59 Reacter Coolant Pimp Supports A490 Golts were evaluated and found to be Selts satisfactory when properly insta'iled.

Reverification program was conducted.

Any bolt that failed tests was replaced.

60 Turnover Oscamentation & Inadequate Open Manger Meld Problems 61 Linear Cesck in $5 Tubing Defective material subjected to metallurgical analysis. All tubing with heat he. 466023 has been identified and hydrostatically tested.

Corrective action has been completed and documented.

62 undersire Melds on 1/2" Schedule All socket welds in question have been 160 Piping inspected. hids nut in compliance have been reworked and reinspected.

QA welding inspection program has been upgraded to prevent further recurrences.

\\

CD0 ko.

B-tef Description Corrective Measum 63 Procurweent of Spa m/ Replacement Open i

Parts 64 Safety Injection Tanks Discharge Rate Open 65 Orifice Plate Gasket Failures in HPSI Gaskets were replaced with flexi-System tallic style CG-0-175" gaskets as originally specified.

I;.

86 Deflective GE Type Act Smokers.

Open l

C-Clips Fall Off l

. 'N Port 21 Report - See EaMbit 5 68 Sportees Actuation of ESEA$-J3109 open i

Ceanector SS Crosby Stellite Velve Discs Open

\\

70 Deficiency in Centrol Circuits of Open 400 Volt Switchgoer Breehors t

[

71 Fetiere to Properly Asvlow Conditten Open i

Identification and Mort Authorisation 1

Fems(CIM's) y F2 Seficiencies la Rettetten Nemitoring Open System 55 23 Redetes.

g 1

i l

l h

l i

4 e

0 i.

-..-- - 1

6..

PART 21 NOTIFICATIONS 00t! SIT 5 Year Organization Brief Description corrective Measures 1978 Cooper-Bessemer Emergency Diesel Gen.

New governor drive shafts Defective Shafts & Springs fabricated from a now material f

and installed.

[

y 1978 Ceeper EnergF Detecti n Emergency Replaced inlet and ashaust

[

5ervices Genomter, teller.Me-vol w crosshead assemblies

-.7.. c..

with som design.

1979 ncJunkin Corp.

Material Fa11ere. pipe Three ells'already installed Fittings 4*-48 ELL & 4' were removed. Sin ells in f

90 ELL

.,.A -

warehsese unre placed en hold.

~

Remaining one uns determined to have been scrapped.

1979 Nemos Defective Top Cover Gaskets. The 88 breakers have been Remco EA-18 Limit Switches repaired.-

1980 ITT General N1111 ampere IWdremeter Springs replaced and adjusted.

t Centrols Activaters N.,";

Others determined to be

. i%

adequate. All will be tested..

i 1980 Anecende Flesitie Ligold Tight -

Electrical penetrettens.

8 Wiring Ceedelt Covering Prwesetive Failure ers installed. 0A surveillance increased.

l 1900 Fisher Defective Vat e All ten actuators replaced.

Controls Actuators 1900 Fisher Defective Valve Manus)

Replaced worm gear sector l

Controls Operators and pin between input shaft and wem gear.

l 1981 Suffale NVAC Fan Sweeds inadequate All nine fan shreves were Forge design to serve as fan blade modified.

sisstle horriers.

l 1982 6-E Possible Fallere of Type OPEN NFA Reitys 1981 ITE Gould Starter Coil Failurt All colls replaced in these l

in Containment Cooling Fans starters.

l

,[

k 9.

t ver-

..e.i

. - :r Brtef Desertption C.o r c, t' o V -.

1982 Aw ' a c e Fossible malfunction ir Eighteen relar-r Co rp.

Agastat E7000 series Time-Delay Relay 1982 Time-Trol Heat Trace Panel Temporary medvies, senu-Malfunctions anglifier boards, volte::e regulators & temperature sensors for all 3 panels replaced.

1982 Pressure Vessel Failure of A500 Grade B Pipe supports retested with i

Muclear Steels, Tube Steel to meet actual loadings. Decrease Inc.

Chemical / Physical in elongation found to be Properties witnin elastic limits of material.

)

1 l

1

.

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