ML17195A908

Summary of 850723 Meeting W/Util & Impell Re Details of RCS Piping Replacement Program to Be Performed During Oct 1985 Refueling Outage.List of Attendees & Comm Ed Viewgraphs Encl

ML17195A908
Person / Time
Site:	Dresden
Issue date:	08/05/1985
From:	Gilbert R Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
LSO5-85-08-004, LSO5-85-8-4, NUDOCS 8508090291
Download: ML17195A908 (64)

Text

W1\\SHINGTON, 0; C. 20555 August 5, 1985

• ~

Docket*No. 50-249 LS05-85-08-004 LICENSEE:

Commonwealth Edison Company (CECo)

FACILITY:

DRESDEN NUCLE'.A.R POWER STATION,. UNIT NO. 3

SUMMARY

OF MEETING HELD ON JULY 23, 19£>5 The NPC held a meeting with CECo and their design contractor, Impell, to df~cuss the details of the reactor coolant system piping replaceme"t program for Dresden Unit 3 scheduled to be done during the* next refuelinq outage planned to start. in lat~ October 1985.

A list of attendees is provided in Enclosure 1 and copies of the viewgraphs used by CECo during the ~eeting are presented in Enclosure 2.

With the viewgraphs as a guide, the speakers presented: the proposed replace-*

ment program and deta i 1 ed the fo 11 owing i terns:

1. Total scope of the outage

2.

Major* contractors 3~ Saving some removed piping and we.lds for research and training

4.

Type of piptng to be installed 5.. Reduction in total system welds

6.

Use of hydrogen water chemistry (HWC)

7. Codes and standards P.

Interferences

9.

ALARA

10.

Quality Assurance (QA) program

11. Station Activities Durin~ and fo11nwinq the presentaticm, discussions between CECo and the staff occurred.

Specific staff concerns were in the areas of QA (who esta~lishPs hnld ooints), HWC (evaluate total system), codes and standards interfaces and jet-pump alignment problems during replacement.

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850809029-t 850805

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• The staff, in summary, requested that CECo document the qualifications of the personnel involved with the replacement program and furnish more detailed documentation of some of the presentation areas, e.g., the jet pump alignment problem.

After this information is furnished, the staff will evaluate it and respond in writing.

Enclosures:

1.

List of*Attende~s

2.

Viewgraph ~opies**

cc w/enclosures:

• see next page DISTRIBUTION Docket NRC PDR.. _

Local PDR

- ORB* #5 Reading JZwolinski RGilbert CJamerson OELD

'.EJordan -

BGrimes

• ACRS ( 10)

- NRC Par~ i ci-_pa!1tS.,

DL:ORB#5~

CJamerso

$15 /_85 DL~~

RGil~rt:jb

<j I 5 /85 Robert A. Gilbert, Project Manager Operating Reactors Branch #5 Division of Licensi~g X'

DL:ORB#5 J,..fWOl inski "6 /'l -/85

cc:

Robert G. Fitzqibbons Jr.

Isham, Lincoln & Beale Three First Nation~l Plaza Suite 5200 Chicago,. Illinois 60602 Mr. Doug Scott Plant Superintpndent Dresden Nuclear Power Station Rural Route #1 Morris. Illinois 60450 U. S. Nuclear Requlatory Commission Resident Inspectors Office Dresden Station Rural Route #1 Morris, Illinois 60450 Chairman Board-of Supervisors of Grundy County Grundy.County Courthous~

Morris, Jllinois 60450 Regional Administrator Nuclear Regulatory Conunission~ Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Gary N. Wright, Mana~er Nuclear Facility Safety

. Illinois Department of Nuclear SafP.ty 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 Mr. Dennis L. Farrar Director of Nuclear Licensing Cmnrnonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690

ENCLOSURE 1 ATIENDANCE LIST DRESDEN NUCLEAR POWER STATION, UNIT NO. 3 MEETING OF JULY 23, 1985 Nar.ie C. Reed D. Farrar B. Rybak E. Zebus D. Brown J. Bitel W. Pietrvaa T. Gilman~

J. Abel J-. Famiglietti J. Gavula J. Renwick J. Wojnarowski A. Dromerick J. l<onklin D. Daniel son J. Barker S. Swartz P.. L1 oyd A. Saunders.

H. Shaw F. Cherny W. Koo N. Edwards W. Johnston R. Bosnak B. Liaw D. Crutchfield J. Zwolinski W. Collins W. Hazelton R. Gilbert AFFILIATION

. Commonwealth Edi son C~mm~nwealth Edison Commonwealth Edison Commonwealth Erlison Corrmonwealth Edison Commonwealth Edison Commonweatlh Ediscn Commonwealth Edison Commown.Palth Edison*

Impell lmpell Cormnn~wealth Edison Corrmonwealth Edison NRC

~PC NRC, Region III NRC Ill. Dept. of Nucl. Safety NRC*

NRC NRC NRC NRC Nu tech NRC NRC NRC NRC NRC NRC NRC MRC

I..

~*

ENCLOSURE 2 e

~,'*'PWESEN.TATION TO THE NUCLEAR REGULATORY COMMIS-SION FOR REPLACEMENT OFJGSCC SUSCEPTIBLE PIPING.

AT DRESDEN NUCLEAR' GENERATING STATION-UNIT 3,

~

Commonwealth Edison e

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,9 AGENDA 0

INTRODUCTION & ORGANIZATION E.ZEBUS 0

• ENGINEERING J.GAVULA

• o A LARA T.GILMAN 0

QUALITY ASSURANCE.

D.* BROWN 0

STATION ACTIVITIES W.PIETRYGA 0

SUMMARY

E.ZEBUS

~

INTRODUCTION & ORGANIZATION PROJECT PLANNING ORGAN I ZA T*ION MAJOR CONTRACTS,

PROJECT PLANNING 0 -

PLANN INC PARAMETERS 0

DETAILED PROJECT FLAN 0

SEQUENCE OF EVEN.TS ESTABLISHED a--..:_-_;

0 OWNER/DESICN£R/INSTALLER INTERFACE 0 -

DELIVERABLES LIST DEVELOPED

t.

ORGANIZATION MANAGEMENT.

0 RPR RESPONSIBILITIES 0

PROJECT PLAN 0

MONITORING (IMPELL)

DESIGN 0

SNED 0

IMPELL OPERATIONS 0

STATION OPERATING ENGINEER-SITE COORDINATOR

- MAINTENANCE

- TECH STAFF

- RADWASTE

.A LARA 0

DEDICATED RPR ALARA COORDINATOR 0

RADIATION PROTECTION PLAN CONTRACT SUPERVISION 0

STATION CONSTRUCTION DEPARTMENT 0

DEDICATED RPR SITE COORDINATOR QUALITY ASSURANCE 0

RPR COORDINATOR & STAFF 0

NOE AND QC RESPONSIBILITIES

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JU!'ELL J. A.

f"AUIGL.IF.TTI ilRESDEN

~TATIOU L!ANAOlm L). J. ':iCOTT

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£iNED 0/0 PROJECT a.IOltEEA J.E. tWJSUAN DA~t Jll..Y IWJ 4'

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- MAJOR' CONTRACTS DESIGN INS,TALLA TION PIPE MFGR.

DECON (LOMI)

PIPE DISPOSAL

. HP TECHS*.

INSULATION NOE - QC IMPELL CB&I' MANNESMANN LONDON NUCLEAR QUADREX.

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.ENGINEERING*

SCOPE OF REPLACEMENT ANALVS IS /~RECT ION INTERFERENCES r-L ---

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0 SCOPE OF REPLACEMEN,T SYSTEMS AFFECTED MATERIAL SELECTION AND CONTROL INDUSTRY PROBLEMS/SOLUTIONS ENHANCED DESIGN WELD DESIGN ALTERNATE REMEDIES

. ~*

. SYSTEMS AFFECTED

SUMMARY

0

. RECIRCULATION SYSTEM O*

LOW PRESSURE COOLANT INJECTION 0

SHUT DOWN CQOLING 0

CORE SPRAY 0

ISOLATION CONDENSER RETURN 0

• CONTROL ROD DRIVE RETURN 0

JET PUMP INSTRUMENT SAFE:--END 0

REACTOR WATER CLEAN'-UP

e.

SYSTEMS AFFECTED - DETAIL 0

RECIRCULATION SYSTEM REPLACE ALL STAINLESS STEEL

- REPLACE SAFE-ENDS

- ELIMINATE CROSS-TIE.

a

- ELIMINATE 411 BY-PASS

- RE;..USE PUMP AND PUMP SUCTION ELBOW

).-

- RE-USE VALVES i -~ -

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O*. LOW. PRESSURE. COOLANT INJECTION.

REPLACE. ALL STAINLESS STEEL

- REPLACE TO OUTBOARD ISOLATION VALVES REPLACE FLUED HEAD REPLACE BELLOWS RE-USE VALVES

~ ::-.

0 SHUT DOWN COOLING REPLACE ALL STAINLESS STEEL

. - REPLACE TO INBOARD ISOLATION VALVE

• ° CORE SPRAY

~

REPLACE SAFE'."' EN OS REPLACE TO INBOARD ISOLATION CHECK VALVE

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SYS:rEMS AFFECTED - DETAIL 0

ISOLATION CONDENSER RETURN

• - REPLACE ALL STAINLESS STEEL

- REPLACE TO OUTBOARD ISOLATION. VALVE

- RE-USE VALVES-

- REPLACE FLUED HEAD AND BELLOWS*

0

• CONTROL ROD. DRIVE RETURN

- REPLACE SAFE-ENDS

- CUT AND CAP SYSTEM 0 '

JET PUMP INSTRUMENT SAFE-ENOS.

o.

REACTOR WATER.CL*EAN UP

- REPLACE TO OUTBOARD ISOLATION VALVES

- REPLACE VALVE BODIES

- REPLACE FLUED HEAD

- REPLACE BELLOWS

• ...:~

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MATERIAL SELECTION AND CONTROL o*

TYPE 3*1& NC 0

EXTENSIVE USE OF* EPRI MATERIAL GUIDELINES 0

CHEMISTRY CONTROL (WEICHT %)

- CARBON.

0.020 MAX I..

- PHOSPHORus*

0.025 MAX I --

- SULPHUR 0.005 MAX

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- BORON 10 PPM MAX

- UNSPECIFIED ELEMENTS o.ol MAX EACH f

o.os MAX COMBINED

o.

2% FERRITE BY CHEMICAL COMPOSITION 0

LIMITS ON ALUMINUM, LEAD, TIN, AND OTHERS f.

• I'

MATERIAL SELECTION AND CONTROL 0

MANUFACTURINC CHECKS

- PHYSICAL. PROPERTIES AT ROOM TEMP AND 550°F

~ INCLUSION CONTENT

.~ CRAIN SIZE

):

-* INTERCRANULAR ATTACK l

- CLEEBLE TEST

- FISSURE BEND TEST

- PICKLINC PROCEDURE QUALIFICATION,

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SOLUTION ANNEALINC OF SHOP WELDS

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° FOUR-DIRECTIO.NAL UT + CHECK ENDS FOR LAMINIATIONS 0

ELECTROPOLISH AND PASSIVATION.

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INDUSTRY PROBLEMS /SOLUTIONS PROBLEMS 0 HOT CRACKING 0

• MICRO FISSURING..

NEAR WELDS SOLUTION

° FERRITE CONTENT

° CONTROL OF TRAMP ELEMENTS 0 GLEEBLE TESTING 0 B*ENDING QUALIFICATIONS 0 BENDING TEMPERATURE CONTRO~

0

• TIGHT COPPER CON.TROLS

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ENHANCED DESIGN - WELD REDUCTION 0

• ALL SYSTEMS USE PIPE BENDS WHERE POSSIBLE 00

• LONG TANGENT FLUED HEADS. (LPCI & ISCOJ 0

50% DESIGN REDUCTION IN NUMBER OF WELDS

• • -~

0 ACCESSIBILITY CRITERIA FOR AUTOMATIC UT 0

TUNING FORK SAFE-END DESIGN 0

PROLONGATION CRITERIA FOR ISi

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BG _.U----s' CAP '------.a..

LOOP B

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CURRENT CONF' I GURA r 1 ON.

101. TOTAL W~LDS LOOP ~

NEW CONf'JOURATIOlll

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82 TOTAL Wf;LD$

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• '~e.xl~TING SAfE~~.~i:>/THERMAL SLEEVE

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NEW SAFE-END/THERMAL SLEEVE

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60° UT CRYSTAL*

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* 'I INSPECTI.ON VOLUME

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• WELD DESIGN 0 '

2T COUNTERBORE FOR UT 0

20° /10° J-BEVEL

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SIMILAR TO BYRON/BRAIDWOOD 0

REDUCED SHRINKAGE PER EPRI TESTS 0

ENERGY PER VOLUME OF WELD METAL CONTROL 0

MULTIPLE PASS LAYERS - STRINGER BEADS

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GROOVE WELD END PREPARATION FOR Pf PING, PIPE BENDS, AND LONG TANGENT AND SPECIAL FITTINGS

0. 125" R MIN.

10* MAX.

NOTES:

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.. T" JS NOMINAL THICKNESS CORNERS MAY BE ROUNDED 1.-

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PIPE Co.065".. 0.030 3/32" R ~OI /~irz" O OSS" tO. 030" A'TYP.

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MACH I NE BLEND OR POL I SH I. '. I

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. i ALTERNATE REMEDIES 0

• STRESS IMPROVEMENT

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JiYDROGEN WATER* CHEMISTRY*

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ANALYSIS/ERECTION 0

ORIGINAL CODES.

0 *

• DESIGN: CODES 0

PROCUREMENT CODES 0.

ERECTION CODES.

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ORIGINAL CODES OF CONSTRUCTION 0

PIPING

-*USAS 83.1.1.0 -

1967

- ASME SECTION I (65W66)

. - NUCLEAR CODE CASES 0

SAFE-ENDS

- ASME SECT ION 111 ( 1963) 0 SUPPORTS

- USAS B3l. 1. 0. -

1967

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• DESIGN CODES

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PIPING

- ASME SECTION IH ANALYSIS (80S82)

- RECONCILED TO USAS B.31.1.0 -

1967 0

SAFE~ENDS

- ASME SECTION 111 ANALYSIS (80S82) 0 SUPPORTS

- ANSl/ASME 631. l (80S81)

9

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[*

l PROCUREMENT CODES 0

PIPING' MATERIAL *

- ASME SECTION XI IWA-7()00 (77 S 79)

ANSl/ASME 831. l (80S80 AND ASME SECTION. I. (83W83l *

- AUGMENTED BY ASME SECTION Ill (80S82) 0 SAFE-ENDS ASME 111 (80S82) 0 VALVES

- ORIGINAL CODES

- ANSI.8'31. l AND* ORIGINAL SPECIFICATION REQUIREMENTS*

0 SUPPORTS AND RUPTURE RESTRAINTS

- ANSI 831.1/AISC (8TH ED.)

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L ERECTION CODES 0

ASME SECTION XI IWA-7000

• 0 LATEST EDlTION OF ORIGINAL CONSTRUCTION CODES 0

AUGMENTED B.V ASME SECTION 111 (80S82) 0 EXAMINATIONS TO ASME SECTION 111 NB-5000 (80582) 0 NO "N" STAMPING 0

WELDING TO ASME IX (83W83)

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INTERFEltENCE REMOVAL/INSTALLATION

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INTERFERENCES *

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.,. 200 MECHANICAL/STRUCTURAL 100 ELECTRICAL MINOR INTERFERENCES

... DOCUMENT.AS-BUILT CONDITION

- HAND CALCULATIONS FOR MINOR CHANGES MAJOR.INTERFERENCES

- REANALYZE NEW CONDITION

- GENERATE NEW DESIGN, DRAWING 0

INTERFERENCE INSTALLATION

- HANDLED AS MAINTENANCE REPAIR INSTALLED TO ORIGINAL CODE

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0 10CFRS0.59 EVALUATIONS PIPE REPLACEMENT PROJECT MODIFICATIONS EVALUATED TO REQUIREMENTS OF 10CFRS0.59 EVALUATION PERFORMED IN* ACCORDANCE WITH COMMONWEALTH* EDISON: COMPANY'S SAFETY EVALUATION GUIDELINES>>

0 NO UNREVIEWED SAFETY QUESTIONS WERE I DENT I.Fl ED 0

NO-SAFETY MARGINS AFFECTING TECHNICAL SPECIFICATIONS WERE REDUCED 0

.INTERFERENCES

- MINOR:

COVERED BY PROJECT SAFETY EVALUATION

- MAJOR:

NEW SAFETY.EVALUATION.

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CLEANLINESS PROGRAM

- MINIMIZE USE OF NON-REMOVABLE PURGE DAMS

- 'WALK' PIPE BEFORE FINAL WELDS 0

FLUSH AWAY FROM VESSEL

e -.

RADWASTE_PROCESSING DRYWELL

~. IN!ERFERENCES

--..:..:*TO BE RE-USED-------..:

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METALLICS

/

OFFSITE DECONTAMINATION CAW PROCESSING AREA COMBUSTIBLE TO COMPACTOR TO INCINERATOR TO BURIAL SITE INSULATION.

TO COMPACTOR

..,_ _ __. INSULATION TO SUPER COMPACTOR (LATER)

• TO BURIAL SITE NON-COMBUSTIBLE TO COMPACTOR

~

TO BURIAL SITE

f-l ___ :.-.;

O*

TESTING PREREQUISITE/COMPONENT TESTING

.... *PROVES COMPONENT OPERABILITY FOLLOWING INSTALLATION, OR PREPARES THIS SYSTEM FOR FURTt:IER TESTING AND/OR OPERATION

- HYDROSTATIC PRESSURE TEST

- MEGGER/CONTINUITY /LOGIC TESTING INSTRUMENT CALIBRATIONS

- VALVE OPERABILITY, TIMING

- PUMP OPERAS ILITY, MOTOR ROTATION AND CLEARANCES

- JET PUMP INSTRUMENTATION LINE VERIFICATION 0

PREOP TESTING INTEGRATED SYSTEM TESTING PRIOR TO PLACING SYSTEM INTO OPERATION

- PERFORMED* BY USE OF EXISTING SURVEILLANCE.

PROCEDURES OR USE OF SPECIFIC PREOP TEST PROCEDURES

- PREOP TEST ON REACTOR RECIRC SYSTEM IS COM-PARABLE TO NEW CONSTRUCTION PREOP TEST 0

STARTUP TESTING INTEGRATED WITHIN THE NORMAL POST-REFUEL STARTUP TESTING

- ACCEPTANCE CRITERIA BASED ON UNIT BASELINE DATA

.~

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i PREOP TESTING.

o*

• SYS.TEMS DIRECTLY AFFECTED BY PIPING REPLACEMENT

. - LPCI

- CORE SPRAY

- REACTOR RECIRC.

-* SHUTDOWN COOLING

- REACTOR WATER CLEANUP 0

SYSTEMS INDIRECTLY AFFECTED DUE TO BEING INTERFERENCES

. 0

- DRYWELL COOLING SYSTEM (HVAC)

- RPIS PREOP TESTING INCLUDES:

- VALVE OPERABILITY

- V.ALVE STROKE. TIME

-*LOGIC TESTS*

- FLOW VERIFICATIONS

- PIPE VIBRATION TESTING

- LOCAL LEAK RATE TESTING

- PRIMARY CONTAINMENT INTEGRATED LEAK RATE TEST

• • ..:~

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STARTUP TESTING.

0 SYSTEMS WHICH REQUIRE UNl*T. OPERATION ISOLATION CONDENSER

- REACTOR RECIRC 0

THERMAL EXPANSION OF NEW PIPE 0

HOT VIBRATION TESTING OF NEW PIPE 0 '" NORMAL POST-REFUEL STARTUP TESTING

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SCHEDULE 0

PIPING REPLACEMENT

- OUTAGE DURATION 10J29/8S - 7/1/8&

-*FIRST CUT 12'/ l3/85

- LAST WELD 3/13/86

-* DRYWELL RESTORED' 4:/13/86

- RETEST I REFUEL.

6/13/86

,_--.r

-* RETURN TO SERVICE 7/1/86 0

TORUS RECOAT o*

LOW PRESSURE TURBINE ROTOR REPLACEMENT 0

DETAILED INTEGRATED OUTAGE SCHEDULE

ALARA RADIATION PROTECT.ION PLAN DECONTAMINATION.

PERSON-REM ESTIMATE f

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• RAD PROTECTION ORGANIZATION

• 0 RECORDS-0

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INSTALLER ALARA COORDINATOR

RPR ASSISTANT SUPERINTENDENT

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• RADIOLOGICAL PROTECTION ORGANIZATION ASSISTANT V.P:

NUCLEAR SERVICES ASSISTANT SUPERINTENDENT TECH.. SERVICES STATJoN PROJECl CECO NUCLEAR SERVICES

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HEALTH t----- ~

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STATION SUPPORT PHYSICIST I

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CBI ALA RA STAFF CBI PROJECT ENGINEER

CBI, ALARA COORDINATOR ALAR A SUPERVISOR (IMPELL)

ALAR A

. STAFF (IMPELL)

...... PROJECT...

RADIOLOGICAL PROTECTION 1

1uor11 1RECORDS...,

SUPERVISOR

{JMPELL)

RECORDS STAFF" (CONTRACTOR)

~, ",I OTHl;R OPERATIONS HEALTH PHYSICS SYrnG ~.*~YR HEALTH PHYSICS FOREMAN (CONTRACTOR)

HEALTH PHYSICS TECHNICAL STAf"F (CONTRACTOR)

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PLANNER i '.

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. -.* CEco: ALARA'COMMITMENT LESSONS LEARNED 7 PROJECT SPECIFIC ALARA COMMITMENT*

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PERSON-REM CRITERIA P'.

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0 RADIATION EXPOSURE MONITORING & CONTROL

- EXTERNAL.

DOSIMETRY.

RADIATION WORK PERMIT DRYWELL ACCESS CON-TROL SHIELDING WORKER SURVEILLANCE RADIOLOGICAL SURVEY /AREA POSTING-INTERNAL FIXED VENTILATION SYSTEMS PORTABLE VENTILATION SYSTEMS SPECIAL CONTAINMENTS/GLOVE BAGS CONTAMINATION CONTROL RESPIRATORY PROTECTION B IOASSA Y PROGRAM EXPOSURE TRACKING PER TASK/JOB TRACKING PER INDIVIDUAL/WORK GROUP TRACKING REPORT GENERATION DOCUMENTATION

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- DOCUMENTATION.

HEALTH PHYSICS EQUIPMENT

- HEALTH PHYSICS INSTRUMENTATION

. - CLOSED-CIRCUIT TV MONITORING

- PERSONNEL DECONTAMINATION

PERSON-REM ESTIMATE 0

INSTALLER DESCRIPTION PERSON-REM GENERAL TASKS 340 PHASE I-INTERFERENCE

. & PIPE REMOVAL 469 PHASE I I-REMOVAL &

REINSTALLATION OF SAFE-ENDS & FLUED HEADS.

295

• PHASE: II.I-PIPE INSTALLATION 195 '

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PHASE IV-RESTO RAT ION 223 ELECTRICAL WORK 89 L---

SUB TOTAL 1611 0

OTHER ORGANIZATIONS CECO QA/QC/NOE 140 L

IMPELL (A/E)

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STARTUP/ADDITIONAL TESTING 21 1:~

DECONTAMINATION 10 SUB TOTAL 295 I~

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APR QA SUPERVISOR QA SUPERVISOR I

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FROM APRIL 11, 1985 THROUGH FINAL DOCUMENT TURNOVER FOR OUTAGE RPR QA SHALL BE RESPONSIBLE FOR:

0 REVIEW AND* ACCEPTANCE OF CONTRACTOR'S PROCEDURES 0

. ESTABLISHMENT OF WITNESS AND HOLD POINTS 0

REVIEW AND ACCEPTANCE OF CONTRACTOR'S N-CR'S 0

. VERIFICATION OF PROPER COMPLETION OF FIELD:

CHANGE REQUESTS 0

• SURVEILLANCE AND AUDIT OF ALL PARTIES INVOLVED 0

ADMINIS:TRATION OF NOE/QC CONTRACT 0

RECEIPT. INSPECTION OVERVIEWS OF OUTAGE RELATED MATERIALS 0

WITNESSING OF WELDER QUALIFICATION TESTING 0

SURVEILLANCE OF OUTGOING RADWASTE SHIPMENTS 0

TRENDING OF RPR RELATED DEFICIENCIES 0

REVIEW AND ACCEPTANCE OF _QC INSPECTOR QUALIFICATIONS 0

ASSURING THAT ALL CONSTRUCTION TESTING IS COMPLETE.

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DRESDEN OPERATIONS QA SHALL BE RESPONSIBLE FOR:

0 AUDIT & SURVEILLANCE OF ALL NON-OUTAGE RELATED OPERATING ACTIVITIES 0

QA FO.R ALL OUTAGE ACTIVITIES PERFORMED BY THE STATION MAINTENANCE STAFF 0

REVIEW OF ALL WORK REQUESTS IN ORDER TO DELEGATE CONSTRUCTION RELATED PACKAGES TO THE RPR GROUP 0

ASSURING ALL PRE-OPERATIONAL AND STARTUP TESTING THAT MAY BE REQUIRED IS COMPLETE

ENGINEER/

INSPECTOR EDUCATION SUPERVISOR BSEE BSME BSED BSME INSPECTOR (H.S.)

BS TECH ENG.

INSPECTOR BS BUS.

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REPRESENTATIVE QA EXPERIENCE WORK EXPERIENCE (NUCLEAR)

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( 11 NUCLEAR) 4 Y~S.

(4 ~UCLEAR) 6 YRS.

NAVY NUCLEAR 11 YRS.

(6 NUCLEAR) 1.5 YRS.

(1.5 NUCLEAR) 8.5 YRS.

( 1 W /CECO) 37 YRS.

(9 NUCLEAR) 14 YRS.

(7 NUCLEAR) 1.5 YRS.

QA EXPERIENCE.

5 YRS.

4 YRS.

Q YRS~

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(1 W/CECO) 9 YRS.

7 YRS.

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-OTHt=R SRO CERT-PWR ANSI Nq5. 2. 6 - LEVEL 111 LEAD AUDITOR - ANSI ~45.2.:u ANSI N45. 2. 6 LEVEL II LEAD AUDITOR -

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FINAL NOE/QC ACCEPTANCE BY IN.DEPENDENT TESTING AGENCY

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- REDUCE NUMBER OF WELDS, IN DRYWELL

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INSTALLED FIRE PROTECTION

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• 0 RAD OFFICES 0

PERSONNEL CONTAMINATION MONITORS

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