ML17157B847

Summary of 920528 Meeting W/Representatives of Util to Discuss Status of Current Licensing Issue Re Feedwater Weld build-up.List of Attendees & Presentation Encl

ML17157B847
Person / Time
Site:	Susquehanna
Issue date:	06/12/1992
From:	Raleigh J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9206240300
Download: ML17157B847 (37)

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Docket Nos.

50-387 and 50-388 UNITED STATES

, NUCLEAR REGULATORY COMIVIISSION WASHINGTON, D.C. 20555 June 12, 1992 Mg~;.~gli'f.-g( g++(~hei LICENSEE:

Pennsylvania Power and Light Company FACILITY: 'Susquehanna Steam Electric Station, Units 1 and 2

SUMMARY

OF MEETING WITH PENNSYLVANIA POWER AND LIGHT COMPANY (PP&L)

ON THE FEEDWATER "TEE" WELD OVERLAY REPAIR A meeting was held on May 28, 1992, at NRC Headquarters, between members of the NRC staff and representatives of the licensee.

The purpose of this meeting was to discuss the status of the current licensing issue regarding the feedwater weld build-up.

This meeting gave the licensee the opportunity to present this issue and clarify any interpretations between the NRC and the licensee.

Enclosure 1 orovides a list of attendees.

In the licensee's presentation (Enclosure 2), they stated that they took a

conservative approach in sizing the defect and code qualified methods for the repair.

The repair was valid because it was a weld buildup according to ASME

Code,Section III.

However, the staff takes exception to the conclusions that the licensee drew in its presentation:

1.

Eroded area is not considered a "flaw".

2.

The reinforcement repair conducted by the licensee meets the ASME Code.

The repair conducted by the licensee is not in accordance with the repair/replacement rules of ASME Code Section XI and therefore, 10 CFR 50.55a(g)(4) is not fully satisfied.

The staff believes that a weld reinforcement of the base metal pursuit to ASME Code Section II'. could only occur if the licensee removed the affected component, removed the defect, reinforced the component, performed the required Non-Destructive Examination (NDE) and re-installed the repaired component in accordance with ASME Code,Section XI requirement.

The repair as performed i5 considered a weld overlay repair.

Such a repair method for Carbon Steels has been specifically excluded,

however, the method for Stainless Steels is currently being processed as an ASME Code Section XI case.

If the repair could be conducted in accordahce with PSME Code Section III rules, there would be no need for the overlay code case being developed by ASME Code Section XI.

The staff believes that the licensee was conservative in evaluating the erosion rate for the component.

The component itself may have been suitable for service'for the balance of +he cycle without the repair.

Further, the

- staff believes that the weld overlay performed did not degrade the component 920b240300 '920612 PDR ADDCK'05000387 P

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since the welding itself was performed to ASHE requirements.

Therefore, this temporary measure, although not satisfying the repair/replacement rules of ASHE Code Section XI, does not constitute a significant safety concern and full compliance with ASHE Code Section XI could be deferred to the next refueling outage.

This issue is being addressed as part of inspection report number 387/388 92-05 as an unresolved item.

The licensee is expected to provide their basis for the code interpretation, additional info'rmation on the projected erosion/corrosion wear rate over the operating cycle and an analysis of the structural integrity of the component through the cycle considering expected wear.

If there are any questions, please call me at (301) 504-1447.

/S/

'James J. Raleigh, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1.

List of Attendees 2.

Licensee's Presentation cc w/enclosures:

See next page DISTRIBUTION f-- '-'Docket. Fi 1 e

",Q'NRC-5 L'ocal PDRs PDI-2/Reading THurley/FHiraglia, 12G18

JPartlow, 12G-18 SVarga JCalvo CHiller JRaleigh HO'Brien DGarcia I

OGC

• Previously Concurred

EJordan, 3701

RHermann, 7D-4

JHedoff, 7D-4 GGeorgiev, 7D-4

ATaboada, NS217C GHornseth, 7D-4

KBattige, 14D-2

LBanic, 7D-4

HModes, RGN-I ACRS(10)

RLobel, RGN-I EWenzinger, RGN-I

JWhite, RGN-I OFFICE PPI L

PDI-2/

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PDI-2 P

JRalei h

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RHermann PDI-2 PD CH'ATE OFFICIAL

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since the welding itself was performed to ASME requirements.

Therefore, this temporary measure, although not satisfying the repair/replacement rules of ASME Code Section XI, does not constitute a significant safety concern and full compliance with ASME Code Section XI could be deferred to the next refueling outage.

I This issue is being addressed as part of inspection report number 387/388 92-05 as an unresolved item.

The licensee is expected to provide their basis

'or the code interpretation, additional information on the projected erosion/corrosion wear rate over the operating cycle and an analysis of the structural integrity of the component through the cycle considering expected wear.

If there are any, questions, please call me at (301) 504-1447.

Enclosures:

1.

List of Attendees 2.

Licensee's Presentation mes J. Raleigh, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc w/enclosures:

See next page

Pennsylvania Power 8 Light Company Susquehanna Steam Electric Station, Units 1

E 2

CC:

Jay Silberg, Esq.

Shaw, Pittman, Potts 5 Trowbridge 2300 N Street N.W.

Washington, D.C.

20037 Bryan A. Snapp, Esq.

Assistant Corporate Counsel Pennsylvania Power 3 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. J.

M. Kenny Licensing Group Supervisor Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr, Scott Barber Senior Resident Inspector U.

S. Nuclear Regulatory Commission P.O.

Box 35 Berwick, Pennsylvania 18603-0035 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0.

Box 2063 Harrisburg, Pennsylvania 17120 Mr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.

212 Locust Street P.O.

Box 1266 Harrisburg, Pennsylvania 17108-1266 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company 1009 Fowles Avenue Berwick, Pennsylvania 18603 Mr. Robert G.

Byram Vice President-Nuclear Operations Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. Harold W. Keiser Senior Vice President - Nuclear

'ennsylvania Power and Light Company

, 2 North Ninth Street Al.lentown, Pennsylvania 18101

ENCLOSURE 1

WELD OVERLAY MEETING Hay 28, 1992 NAME Charles L. Hiller James J. Raleigh Denise Garcia Ken Battige Robert A. Hermann James Hedoff George Georgiev Alfred Taboada Geoff Hornseth Lee Banic Michael C.

Modes Ed Gerlach John T. Lindberg James E. O'ullivan Hathew A. Hober Thomas A. Gorman Robert A. Saccone Chuck Dvorscak James H. Kenny James B. Wesner ORGAN IZATION NRC/NRR/PDI-2 NRC/NRR/PDI-2 NRC/NRR/PD I-2 NRC/NRR/PDI-3 NRC/NRR/DET/EHCB NRC/NRR/DET/EHCB NRC/NRR/DET NRC/RES/HEB NRC/NRR/EMCB NRC/NRR/EHCB NRC/RGN-I PP&L PP&L PP&L PP&L PP&L

PP&L PP&L PP&L PP&L

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ENCLOSURE 2

SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 - 6 RIO FEEDWATER WELD BUILD-UP MEETING WITH THE NRC MAY28, 1992 GENDA Introduction and Overview Initial Inspections Design - NB 3000 Construction - NB 4000 T. A. Gorman J. T. Lindberg C. L. Dvorscak J. O'ullivan Implementation and Pre-Service Inspection - NB 5000 -',

E. B. Gerlach Future ISI/E.C. Inspections Conclusions J. T; Lindberg T. A. Gorman

Introduction Overview:

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Erosion/Corrosion Methods - Feedwater

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Feedwater Tee - X-175 - Wall Thinning

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Conservative Assumptions Require Action

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Weld Build-up is The Best Option

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Discussed Plans with NRC and ANII

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All Code Requirements Were Satisfied

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Finished Condition > Original Construction

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Finished Condition will be Monitored.

.688"

.482"

.206" TOC (TOP DEAD CENTER)

I2 FEED VATER LINE (DLA-/02)

VALL THICKNESS.68 VELD BUILD-UP 20 REDUCING TEE

. 482 BLOh'P OF AFFECTEO AREA

Wear Rate A sum tions:

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Counterbore Area

[.657" - A82"]/6 =.029"

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Nominal Wall

[.688" - A82"]/6 =.034"

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Nominal Wall and Manufacturer's Tolerance

[.774" - A82"]/6 =.048"

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Delta U1-6 RIO/U1-5 RIO

-.098 X 1.5 =.1470

'EEDWATER "TEE" ISI AND EROSION/CORROSION SYNOPSIS I I HI T RY - DI A-1 2-1-F

-1 PSI - CODE CATEGORY B-J, B4.5; VOLUMETRIC-5/80, NO RECORDABLES ISI - CODE CATEGORY B-J, B9.11; VOLU)dETRIC A SURFACE-5/89 (U1PRIO), NO RECORDABLES ER SI N RR I NHI T RY-X-175

~1-iR~I MFOIUIIMWALLTHICIOIFFAFFAZIFIG OF.616" ALLOWABLEMl¹ WALLTHICKMKSOF.438" LOCATION-DOWNSTREAM SIDE OF TEE TO PIPE BRANCH WELD NO FURI'HIER ISI OR ENGINEERING ACTIONREQUIRED Q11jIUO INH'IALWALLTHICKNXBSREADING OF.521" ALLOWABLEMIN. WALLTHICKNESS OF.438" LOCATION-SAINTE AS OF U1-5RIO (LONGER 326) DEEPER)

FURTHER ISI/ENGINEERING ACTIONREQUIjRED

.688"

.482"

.206" TDC (TOP DEAD CENTER)

/2 FEED WA TER LINE (DLA-l02)

WALL THICKNESS.6h WELD BUILD-UP ZONE ZB:

UI-5RIO.6/9 Ul-6RIO.482

~ZONE ZA:

UI-5RIO -.656 UI-6RIO.62/

20 REDUCING TEE

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.5PJ I EXPAI'6)ED MANUALEXAMINATIONOF AREA W/ 1" GRID SPACING REVEALEDLOWEST READING OF.482" WALL-CONFORMED BY GE LEVELIII t AUTOMATEDUT (0 DEG.) EXQHINATIONOF AREA USING GE SMART 20M (.I" INCREMENTSI CONPIRMS MANUALTRICI<NESS PROP/LE DATASHOWING LOCALIZEDWALLTIHNMNG 1 PAL AND GE LEVELIIIM'VIEWOF MANUAL&6)

AUTOMATEDDATAEVALUATESAIBAAS "TYPICAL" EROSION/CORROSION WALLTIHNMNGIN COUNT/UIRORE REGION t ISI ENGINEHGNG STATISTICALANALYSISOF MAKUAL THICZNMS DATAVER/PISS VALIDITYOP EROSION/CORROSION DATA t MABUALAl'6) AUTOMATEDEXAMINATIONOF "SISTER" LOCATIONVERWIES EROSION/CORROSION, ZUT NOT AS SIGNIFICANTAS X-175. NO ACTIONREQUIRED 0 "THXNNED"AE&A~IllA FLAWAS DEFINED BY ASME SECTION Xt. LOCALIZEDWALLTHINNINGAPPROXU//ATELYI" WIDE BY 4" LONG - DOWNSTREAM OF WELD

FEEDWATER WELD BUILD-UP MODIFICATION FOR SUSQUEHANNA SES

. UNIT I

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System Design Data

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Engineering Evaluation of E/C Inspection Results

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Design of Feedwater Weld Build-up

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Post-Modification Evaluations

SYSTEM DESIGN DATA ASME NUCLEAR CLASS I PIPE

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ASME SECTION III, 197 I EDITION Wl ADDENDA THRU WINTER 1972

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MATERIAL CARBON STEEL SA-333, GRADE 6 (SEAMLESS)

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PIPE O.D.

= 12.76";

SCH 80; T(NQQINAL)= 0.688"

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T(g~N)

OA38"

{CALCULATED}

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DESIGN PRESSURE

= 1260 PSI

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DESIGN TEMPERATURE = 575 F

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LOW STRESS LOCATION

EVALUATIONOF EiC INSPECTION RESULTS

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PIPE HOOP STRESS (PRESSURE)

MINIMUMMEASURED WALL THICKNESS ~ 0.482" WALL THICKNESS MARGIN ~ 0.044" (0.482" " 0.438")

PREDICTED E/C WEAR RATE ~ 0.170"/CYCLE CONCLUSIONS AN E/C WEAR RATE OF 0.044"/CYCLE OR LESS WOULD BE ACCEPTABLE A MIN WALL VIOLATIONPOSSIBLE DURING NEXT CYCLE, IF E/C WEAR RATE IS GREATER THAN 0.044"

EVALUATIONOF E/C INSPECTION RESULTS

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PIPE AXIALSTRESS

{MECH LOADINGS}

ALL DEFINED MECHANICALLOADINGS USED ASSUMED MINIMUMWALL THICKNESS ~ 0.312" (0.482" - 0.170")

CONCLUSIONS ALL ASME CODE EQUATIONS WOULD BE SATISFIED WITH AN E/C WEAR RATE ~

0.170" /CYCLE MECHANICALLOADINGS ARE NOT CONTROLLING STRESSES AT THIS LOCATION

DESIGN OF FEEDWATER WELD BUILD-UP

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ASME CLASS I ANALYSIS PERFORMED

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ASME SECTION III, NB-3641 AND NB-3650, l977 ED. THRU SUMMER l979 ADDENDA

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ALL ORIGINAL DESIGN BASIS LOADINGS/COMBINATIONSUSED

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ANALYSIS INCLUDED PRIMARY STRESSES (EQN. 9)

PRlMARY PLUS SECONDARY STRESSES (EQN. 10)

PEAK STRESSES (EQN. 11)

CUMMULATIVEFATlGUE DAMAGE

DESIGN OF FEEDWATER WELD BUILD-UP

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COMPONENT MODELING TNPMI~AL (0.688") USED TO DETERMINE P RESSURE/MOMENT STRESSES TMAXIMuM(1.250") USED TO CALCULATE NEW THERMAL GRADIENT STRESSES TTJ STRESS INDICES USED

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RESULTS ALL CODE EQUATIONS SATISFIED USAGE FACTOR 1.0

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FEEDWATER CLASS I STRESS REPORT REVISED/RECERTIFIED

POST MODIFICATION EVALUATIONS f

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WELD SHRINKAGE AFFECTS

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PIPE STRESSES NOZZLE LOADS

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OVALITYCHECK

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RESULTS NO SIGNIFICANT IMPACT ON DESIGN MARGINS

1fy lg o

)I 9 (use Shoo(.

DL+ 202-I.D) co

ASNE SECTION III NB4336 QUALIFICATION REQUIREMENTS FOR BUILT-UP MELD DEPOSITS BUXLT-UP MELD DEPOSXTS FOR BASK METAL COMPENSATXON (RKXNFORCEMENT) SHALL BE QUALZFZ ED ZN ACCORDANCE MZYH THE REQUXREMENTS OF NB4331 THROUGH NB4335.

ASME SECTION III CLASS I QUALIFICATION REQUIREMENTS (NB4331 - NB4335)

ASME SECTION IX (SUPPLKMKNTARY EssKNTZAL VARZABLKs)

CHARPY V-NOTCH IMPACT TESTS BasK MKTAL WKLn MKTAL HKAT-AFFKGTKn Z0NK LATERAL EXPANSION & PERCENT DUCTILE FRACTURE

SUPPLEMENTAL PPRL-IMPOSED REQUIREMENTS MATER-BACKED MELDING MACHINE GTAW PROCESS ONLY POSITXON 66 SIMULATED WATER COOLZNG SAME EXLLER METAL HEAT FOR QUALIFICATION 8t PRODUCTXON FULL-SCALE MOCK-UP SHRINKAGE VERIFICATION NO PREHEAT REGUIRED IMPACT SPECIMEN LOCATIONS

= ACTUAL CONDXTXONS

I

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See Groove Detail Voà Pily

MATER-BACKED DRY-BACKED CHARPY V-NOTCH (FT.LSS.)

BASE METAL HEAT-AFFECTED ZONE MELO METAL 267 281 87 267 289 294 LATERAL EXPANSION (MrLs)

BASE METAL 88 HEAT-AFFECTED ZONE 82 MELD METAL 55 PERCENT DUCTILE/SHEAR BASE METAL 100 HEAT-AFFECTED ZONE 100 MELD METAL 30 100 97 100

INSPECTIONS PRIOR TO WELD BUILDUP EXISTING MELD PROFILES MAGNETIC PARTICLE EXAMINATION ULTRASONXC EXAMINATION BENCHNARKXNG FOR MELD CENTERLINE PIPE OYALITY PIPE LOCATION

WELD BUILD-UP LAYERS OF MACHINQ GTAg FXNAL SURFACE PREPA~TJ0g C.CX]ST)Nt v +;<g

~ai'O W~r.

JA" ~w.

"INo WELD BUILDUP GROUND FLATFOR ISI UT EXAM 1/4'1/16' 0'o xio"x)i>>sat 1X". OlA-iOR-S

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INSPECTIONS AFTER WELD BUILD-UP ASME SECTION III VISUAL EXAM

$ URFACE EXAM (MAGNETIC PARTICLE)

VOLUMETRIC EXAM (RADIOGRAPHIC)

ALTERNATIVE EXAM (ULTRASONIC) WAS USED BASEMETAL BUILD-UP THICKNESS MEASUREMENT

INSPECTIONS AFTER MELD BUILD-UP ASME SECTION XI - PRE-SERVICE INSPECTIONS SURFACE EXAM (MAGNETIC PARTICLE)

VOLUMETRIC EXAM (ULTRASONXC)

ADDITIONAL INSPECTIONS PIPE OYALXTY PIPE MOYEMENT ULTRASONIC THICKNESS FOR EROSION CORROSION PROGRAM

FUTURE EROSION/CORROSION AND ISI INSPECTIONS ER I N RR I

X-175 M6) "SISTER" LOCATIONS - SCHEDULED FOR E/C INSPECTION XWXZYOUTAGE URINALENGINEERING D~ ALTSENA1TPE INSPECTION PEIIQUENCT DLA-102-1-FW INSPECTION SCHEDULED FOR TEE U1-11RIO, SURFACE ANDVOLUMETRIC-CODE CATEGORY B-J, B9.11.'

- ASSULWS WELD SELEC11ON CR1TZBM USED IIOE SECOND TEN YEAR ISI IN'XXRVALIS SIMIILARTO HEST ISI IXI'ERVAL SELEC11ON CSITESIA.

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Conclusions:==

Took a Conservative Approach

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Implemented the Best Option

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Satisfied All Code Requirements

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Condition will be monitored.

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