JPN-88-062, Forwards Addendum to Summary of IGSCC Insps During Reload 8/Cycle 9 Outage & Weld Overlay Design Info,Per Generic Ltr 88-01

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Forwards Addendum to Summary of IGSCC Insps During Reload 8/Cycle 9 Outage & Weld Overlay Design Info,Per Generic Ltr 88-01
ML20206F032
Person / Time
Site: FitzPatrick 
Issue date: 11/10/1988
From: Brons J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GL-88-01, GL-88-1, JPN-88-062, JPN-88-62, NUDOCS 8811180305
Download: ML20206F032 (20)
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Text

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>~co-4ff Authority " nirli"E " l JPN-88-062 November 10, 1988 , j U.S. Nuclear Regulatory Commission ATTN Document Control Desk Mail Stop Pl-137 Washington, D.C. 20555

Subject:

J ames A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Intergranular Stress Corrosion Cracking ( Inspection Results for the Reload 8/ Cycle 9 Refuel Outage Refereheest

1. NRC Generic Letter 88-01, dated January 25, 1988, which transmitted NUREG-0313, Rev.

2, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping."

2. NYPA letter, J.C.

Brons to NRC, dated Pr ust 16, 1988 (J PN-8 8-0 41), provided a= plans relating to piping replacement, inspection, repair, and laakage detection. N

3. NYPA letter, J.C.

B1'ons to NRC, dated November 10, 1988 Summarized results of 'aB Reload 8/ Cycle 9 Deidel Outage.

Dear Sirs:

Reference i requeste5 that the Authority provide current plans for piping repla;ettent, inspettion, repair, and leakago detection. Reference 2 transmitted the Authority's plans for intergranular stress co. erosion cracking (IG8CC) inspections during the Fall 1988 outage. Refersuce 3 summarized the results of those inspections and provided repair data. Bem:.wa several evaluations were still in progress, data on some weict. Mas not included in that tra1 mittal. This letter addresses '.ftsse items. provides an evaluation of weld 28-37, which concludes that the veld contains no IG8CC. details tho weld overlay design information for velds 28-48 and 28-116. e.311180305 GS11.0 FDR ADOCK 0S000333 ) p FDC \\

. s. We request your prompt review in time for scheduled start-up. 5 If you or your staff have any questions on this matter, please contact J.A. Gray, of my staff. Very truly yourr, L d,ohn C. Brons yacutive Vice President Nuclear Generation ( cc Office of the Resident Inspector I-U.S. Nuclear Regulatory Commission Post Office Box 136 e Lycoming, New York 13093 Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19400 David LaBarge Project Directorate I-l Division of Reactor Projects I/II Us8. Nuclear Regulatory Commission [ Nail Stop 14 B2 Washington, D.C. 20555 I R. NcBrear&,y U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19400 l i l I f l

g ._J / N' [h DATE:= M# V E I CONTROL NUMBER: DOCUMENT CONTROL DESK:

        • PLEASE RETURN THIS DOCUMENT TO SENDER ****

DC"UMENT INCOMPLETE / MISSING PAGES AVAILABILITY UNCLEAR /NOT MARKED DOCUMENT NOT NORMALLY PROCESSED BY NUDOCS PER MANUAL CHAPTER 0232 INCONSISTENT DATA (i.e. DOCKETS. DATES) THROUGHOUT PACKAGE DOCUMENT CONTAINS TRIVACY ACJ OPYRIG UNMARKED PROPRIETARY INFORMATION S et W., y e r t-A p i NO DOCKET OR UTILITY IDENTIFIED FORWARDING LETTER AND ENGLOURES UNRELATED MISSING / INCORRECT DISTRIBUTION CODE NO CF/RES/WM SUBJECT FILE ASSIGNED DOCKET DATE ILLEGIBLE /NO DOCKET DATE OTHER k A. k St.44// PHONE: 2-T N O NAME:

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  • TO NUDOCS, C DOCUMENT NRC NOTES:

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  • NAME:

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REVISION 1, 7/13/88 ~

ATDOMENF 1 'IO JPW-SS-062 SUGOGW_Or.DFIEltRMUIAR N CORIO6IN C30GING DSPECTIC05 DUKQG3 REFML 8 CYCIE 9 OUDu28 4 NDt YORK POWER AUDORITY JAMES A. FITZPA2 RICK NUCIZAR POWER PIANF DOCIGT W. 50-333 i i t W m.,_

1.0 Introduction As described in Reference 1, the Authority has implemented an Intergranular stress corrosion Cracking (IGBOC) inspection program for stainless steel piping welds at the FitsPetrick plant. his program conforms to the requirunents of MUREG-0313, Rev. 2. Fifty-four welds were in the original inspection plan as detailed in Reference 2. hirty eight additional welds were examined as part of NUREG 0313 Rev. 2 requiImments. Mis report details the three welds which were tmdar wvaluation and were discussed in Reference 2. 2.0 Wald Overlavs Installed on Welds 28-48 and 28-116 Wald overlayd installed on these welds during the 1988 refueling cutage were designed in accordance with NUptBt>0313 Rev. 2. Wald overlays designs are discussed in Att h t 2. A designed overlay on weld 28-48 will be installed as allowed by NUptBG 0313 Rev. 2. mis weld may be tygraded to a standard overlay if the outage scheele is not ispected. A standard overlay will be installed on weld 28-116. Weld overlays installed on wolds 24-4s and 28-116 t ring this refueling outage take credit for the first layer as allowed by NUREG-0313 Rev. 2, pars.p@ 2.1.1 and 4.4 if the following is truet 1. S e ferrite readings are greater than 7.5 FW upon ocepletion of the first lagw. 2. The pipe surface has been found acceptable via a dye-penetrant exuaination prior to overlay welding. 3. No 'blowthroughs" ooour kring the first layer of ceerlay welding. Prior to installation of the weld overlays, a 'W weld repair *' is installed over the areas of the deepest known IGBOC indications j to prevent 'blowthrough." h e veld area is 30aL weld metal i containing high ferrite and is installed using the shielded Natal l Arc Process. l i I e 1 I b t l I t t i i

Wald 23-48 EBhSCO first identified this Imoc indication in 1984 during a pre-IISI===4mation as having a length of 1" (50% to 50% recording level). De JhF Isvel III amminar evaluated the indication and foted a length of 3.1" (0% to 0% zw@ 1evel) with a merium depth of 18%. ENU discriminated and sised the indication during a post-235I===4mation and foted it to be Imac rith a length of 1.2" and a through-wall idamnsion of less then 10%. In 1901 EBhSCX) re-enemined this indication and found it to have a L length of 1.37" (20% to 20% zwalag level) and a maximm depth of [ 20%. ENU inspected this wald for discrimination and sising and i determined the indication to be oeused by root geometry. In 1947 ITL inspected this weld by P-coon and noted the indication f in the eene area. No independm* sising===4mations were l performed by EEh300 and 3, and an 10B00 _adication was dotaminad to exist in the same area as noted in 1944. Se length was detamined to be 1.5" (0% to 0% zweing level) with a maw 4mm j depth of 20%. S e differences in sising length were attributable to j difforences in amplitude recording levels; there was no growth of [ the Iosoc indication since the indication was first identified in 1984. I l his weld was reinspected &aring this refueling outage and the indication was noted in the same area with a length of 4". The j depth was noted as 0.5" or 48% through wall. De wald was eramissed by Esh800 and M. S e change is attributed to crack growth. I i l M is weld will be repaired by installation of a designed overlay as l l discussed in Attachment 2. Mis overlay any be W to a l standard overlay if outage length is not LW. j l Wold 28-11g } i r nis wald (NUREG category c-1) was first inspected in 1984 with no ( l IGeoc noted. 1 l { Mis weld was asuudnad &aring this refunling outage and was noted as l containing IGeoc. D e most - arvative - ination results were j used in flaw sising as several mammination tactmiques were used. l Se final flaw size detamissed was a depth of 42% with a 2" length. [ i l his wold will be repaired by installation of a standard overlay as ( discussed in Attaclement 2. i i \\

Wald 24-37 Mis weld (NUREG Category C-1) weJ first inspected in 1984 with no IGeoc noted. The pay casing side of the weld was not ammined &as to the cast stainless steel material. No indications were identified &aring an Iasoc emaninstin on the samp casing side of the weld &aring the 1988 refueling outagJ. mese indications were identified by the e Inval nI and sised as having a through-wall depth of grrester than 70% for both indications. a did not perfom am tesce===ination to verify that the indication originated frun the pipe internal diameter (ID). A 60 degree shear wave===4mation was used for sising, although this taremique would not confirst ID creak opening. NURBS-0313, Sanr. 2 considers cast mustatitio exagonente with delta ferrite cositent greater than 7.5 Fa and anstum content less than .035% to be resistant to I m ac. Delta ferrite erAsurements were performed using a severn gauge and revealed several locations of low ferrite. S e measurements are detailed in Table 1-1. The areas of low delta ferrite in the A recirculation pay casting weld prey area may be traceable to discrepancies in the solution heat treatment of the ocupnnents, to nenhanical working of the casting &aring fabrication, to weld repairs of the casting, or to thamm1 outting or welding &aring original fa' cication. S o weld a metal used in the repair was 316 which had between.045% to.06% carbon content and 5.5% to 8.0% ferrite by Magna Gage datamination. To determine the eartant of this low ferrite, all cast ocuponents in the 28" section of the recirculation system piping were ammined for esita ferrite using a Severn gauge. His enemination included both recirculation pay suction and dianharge walds {4 total), and welds i to valve bodies. on).y recirculation pap A==hihited the icw delta l ferrite. De other ocuponents have ferrite readings greater than 7.5 Fa and thus the materials are considered to be resistant to IGeoc. S e delta ferrite results for each location are contalmad in Table 1-1. I During a review of the construction records, it was noted that major I repairs were perforund in both areas in which indications were noted &aring original fabrication of the casting. Mis was confirmed by acid etching with Aqua magia solution (nitrio aci$7.r^=whlorio acid). A visual amaninktion was also performed on the ID surface of the pipe weld (with boroscope) with no creaking detected. l

During preliminary preparations for the repair of this weld (i.e., identifying the flaw location by tJr inspection), the EBA900 level III determined that this area did not contain I0000 but was a weld repair. Additional examinations were performed to detect the flaw including examination techniques to detect Ir. cracking by the EBAsco i Imval III. No IG800 cracking was detected fran the ID surface. Additionally, delta ferrite measurements were taken in the area of weld repairs to confirm the presence of weld metal residual delta ferrite. One re. pair contained ferrite greater than 10 Fn. 'Ihe other repair ountained ferrite on the order of 2.5 to 5 Fn. It was noted that durity fabrication 316 weld metal was allowed for repairs. The certified Material Test Reports show that the ferrite ranged from 5% to 8.5% dependirq on the heat of material used as measured by the Delong method. The JAF Imvel III confirmed the the examination results by perfornirs several examinations to detect ID cracking with no IG800 noted. The indications noted during the original examinations are due to the weld metal / base metal interface and casting imperfections. The original acceptance standard for radiography was ASIM E-71, E-186, E-280 severity level 2, except that no category D,E,F, or G defects were allowed. Minor defacts such as shrink, gas porosity and sand / slag inclusions were allowed in the casting. R.1diographs taken this outage showed ntnarous castirn imperfections as noted by an EnAscn Invel II radiographic inspector. Based on these inspections, this weld is detamined to have no IGSCE. It will be inspected in the future as part of NURD3 0313 Rev. 2 requirenents. 3.0 Belief frun NUREG-0313 Rev. 2 Requhuunent_s Relief is requested fran the Ivguirenants for surface finishing and inspection of the two veld overlays: 28-48 and 28-116 as surface l finishirq and inspection of these welds would lernthen the 1988 refueling outage by about 3 days. In lieu of surface finishing and ultrasonic inspections, a bonding inspection of the overlays will be performed. The two weld overlays will be surface finished (field criteria of 250FHS-Flatness of 1/32" per inch) to unhence inspectability durity the 1990 refuelity outage. The welds will be inspected by ultrasonic examination durirn the 1990 refueliry outage by inspectors qualified in act ardance with the EmI-IMHOG cvarlay inspection trainiry program. If the 1988 refueling outage schedule allows, the above welds will be alrface finished and inspected in accordance with EPRI-DRBOG requirenants prior to starttp.

j ~ 4.0 Summary In accordance with NUREG 0313 Rev. 2 a "Designed" overlay will be installed on weld 24-48. If cutage length is not inpacted, a "Stardard" cuerlay will be installed. A "Standart!" overlay will be installed on weld 28-116. Relief frtan surface finishirq is requested. A bonding examination will be perfonned in the a.s-welded condition. Wald 28-37, after further examination and a review of construct.m records, was found not to contain IGSOC. 'Ihis weld was inspected ?7y l the EBMCO and JAF Imvel II7 examiners. 'Ihe original indications [ found are due to a weld tipair/ base material interface. t i i l l 5.0 References I 1. NYPA letter, J. C. Brons to NRC, dated Augustl6,1988 (JIH-88-043). 2. NYPA letter, J. C. Brt:ns to }EC, dated Novater 10, 1988 l (JIN-88161). i l l I i i t i b i f l 1 l t

TABIE 1-1 Ferrite Realims for Rrn/ Valves "A" Dischargo Valvo Suction Side - >7.5 Fn Dischugo Sido - >7.5 Fn "A" Suction Valvo Suction Sido - >7.5 Fn Dicdurgo Sido - >7.5 Pn "A" Brp C4sciurgo Sidt - <7.5 Fn Includirg Weld M2tal Weld >5.0 Fn Purp Iard - Safe Areas <5.0 Fn All >2.5 Fn Area of IGSCC on nrp lard 10" 04 indication #1 i REPAIR AREA #1-Ferrite > 10 Eh OLIISIDE AREA OR REFAIR > 5 Fn tut less thsn 7.5 Fn 21" Of inlication #2 REPAIR AREA #2-Ferrito 2.5 to 3.5 Fn Ol1ISIDE AREA OF REPAIR > 5 Fn Scro Arnis 3.5 to 5.0 Fn IKTIT: Material is cast stainless steel (CF8M) for all,, cu Tonents. 9 l l i 1

7 TABIE 1-1 (Continued), "B" Discharge Valve Soction Side - >7.5 Fn Discharge Sido - >7.5 Fn "B" Suction Valve Suctico Side - >7.5 Fn Discharge Side - >7.5 Fn ngo g Discharge Side ->7.5 Fn Iand Weld >5.0 Fn <7.5 Fn Suction Side - >7.5 Fn lud 1

o (g l I ATTAONDfr 2 TO JEN 88-062 h'UD CNERIAY DESIGi INFDFMATI' tf l 1 l l l l l l l l NDi YORK 1%IR AUIlORITI l JAMES A. FITZPATRICK bVCIEAR FChTR PIRTP [OCITT 10. 50-333

Wold overlay Pepairs in the Recirculation Systm. 'two additioml welds, 28-48 ard 28-116, required weld overlays to be installed. 'Iho design dinensions for eacb seld overlay repair are su:Turized in Table 1. 'Ihe affected locations are in stainless steel pipirn with measured wall thicknesses shown in Table 2. 'Ihc applied stresses for each of the locations were taken frun the origimi General Electric design stress report, and are su:marized in Table 2. Wold overlay repairs for the affected locations were designed based on the guidance of IURD3-0313 Pav. 2. 'Iho repairs for recirullation systm wolds were designed to meet the zu juirments of the "standartl wld overlay" or the "designed weld overlay" r.s defined in paragraph 4.4 of the IURD3. For the "standarti overlay" no credit sus taked for the runining unflawd origimi pipe. For the "designed overlay" credit was taken for the origiml pipe wld, L tho therral expansion stress ard a shrinkago stress of 1000 pi sus used in tho aalyses for ack11tional conservatirm in ackiition to pressure, doadmight arxi OBE Icads. 'Iho IGSOC crack is assumcd to be acrpletely through-sull for the length of the crack involved as required by IURD3 0313 Rev. :., paragraph 4.4.2 for the "designed overlay". Wold overlays sero designcd in accortlance with the criteria of ASME Coction XI, Article IWD-3641,1986 Edition. 'Iho primry stresses listed in Table 2 (pressure + deadweight + seismic) wre uscd. In ack11 tion, to acki ccnservatisms for using a designed overlay the therral stress arri a shrinkage stress are incitried in the evaluation. 'Iho allowable stress frun A!GI-ASME B31.1 (15.9 ksi) was used in the overlay design process rather than the Section III allowable Sm (16.95 ksi), for additiomi concervatism. Wold overlay lergth was detemined for all repairs by two irdependent factors. 'Iho first of these sus that the repair cust te lorg enough to provide adeqtute structural reinforcanent of the flawed location. For this pnpore, the mininra full thickness lcrgth of the repair vu taken as L=1.5 % 'Iho soccrd consideration sus that the overlay rust be lorg erneh to allow adcquato ultrasonic inspection through the sold o m lay. 'Ihc noewy leryth to support inspection was detmined in dm field.

Attadunent 2-Table 1 WFID OVERIAY DEBIGi DIMDEIOG(2) WEID MJMBER I-Bi%L DESIGI 'n{ICNUES DESIQi 1DUni A B 28-48 1.25" 0.42" 3.2" 3.2" 28-116 1.41" 0.4S" 3.4"(1) 3.4" Notes: 1. 'Ihe inlicated wid is a 28" pipe to prp suction wld. Sitco the pmp taper increases sharply, the repair is to be blenkd into that taper. ResultinJ lcrgth may, therefore, be,R ss than the design lergth on this sido. i i i

.o... Attadment 2-Table 2 64E2D OVERIAY IDCfLTICMS 1TNSIIE AXIAL SIRESS IUE 10 WE2D NLMBER MtESSurt DENNEIGff 1H DOGLL SEISMIC rui) (nsi) fesi) 28-48 5674 198 1280 4133 i k 28-116 4936 835 224 853 l 1 1. A ahrinkagu stress of 1000 psi is a===a4 ard the themal stress is 4 used in the analyses for a&iltional ocmaervatima for weld 28-48 which is a "Designed" cNerlay. 4 1 a o 9 4 Y 4 i i

tm pc-CRACK (' ) (C) COPYRIGHT 1984, 1987 STRUCTURAL INTEGRITY ASSOCIATES, INC. SAN JOSE CA (408)978-8200 VERSION 1.2 STRUCTURAL REINFORCEMENT SIZIllG EVALUATION STRUCTURAL REINFORCEMENT SI3ING FOR CIRCUHF. CRACK. WROUGHT / CAST STAINLESS NYPA-19Q, WELD 28-48. DESIGN OVERLAY WALL THICKNESS: 1.2500 MEMBRANE STRESS: 5674.0000 BENDING STRESS: 6611.0000 STRESS RATIO: 0.7726 ALLOWABLE STRESS =15900.0000 FLOW STEISS:47700.0000 L/ CIRCUM 0.00 0.10 0.20 0.30 0.40 0.50 FINAL A/T 0.7500 0.7500 0.7500 0.7500 0.7500 0.6704 REINFORCEMENT THICK. 0.4167 0.4167 0.4167 0.4167 0.4167 0.6145 O s"o or ac-ca^ck k u n y. a s % d,,,, ( chme: cy _)}-f 4,, 4 ~, O Frittia /t/ X P,s)-/ y _ L_Page _ /C __ y _ fx

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tm pc-CRACK ( (C) COPYRIGHT 1984. 1987 'j STRUCTURAL INTEGRITY ASSOCIATES. INC. SAN JOSE. CA (408)978-8200 VERSION 1.2 STRUCTURAL REINFORCEMENT SIZING EVALUATION l STRUCTURAL REINFORCEMENT SIZING FOR CIRCUMF. CRACK, WROUGHT / CAST STAINLESS NYPA-19Q, WELD 28-48. STANDARD OVERLAY WALL THICKNESS: 1.2500 MEMBRANE STRESS: 5674.0000 BENDING STRESS: 4?31.0000 STRESS RATIO: 0.6292 ALLOWABLE STRESS:15900.0000 FLOW STRESS-47700.0000 L/ CIRCUM 0.00 0.10 0.20 0.30 0.40 0.50 FINAL A/T 0.7500 0.7500 0.7500 0.7500 0.7500 0.7070 REINFORCEMENT THICK. O.4167 0.4167 0.4167 0.4167 0.4167 0,5180 (v) END OF pc-CRACK Pre;3re: ty on A d-ggg. Checkea by: )Y k & ri-V-tt 'q F4 No. &b-{7tQ -] c.R Pc gs ___ 9_ ct _ f L

k ic. FLOW 8 A = =

== = I 45* MIN j TYP i i ? f k...,. I i 1 g .A / / Pipe Pipe t C WELD WELD DVERLAY RE. AIR DETAILS l l .rLAV , DESIGN DIMENSIGNS 1 WE' O NUF'*c..,-s COMMEN._ i- ~ CHARACTERIZATION t l A l 8 28-48 Circumferential: 'O.4:a 3.2a 3.2" Design veld i \\ 4a x 4 8f. 31 overlay repair per NUREG-0313, Rev. 2 PREPARE IT: [, [. h f/,s y([ OAIE OE50A!PIION: J.F. Copeland 11-4-88 Design veld overlay design for chEc<t3 Br. M M OAft recirculation system veld 28-48. H.L. Gustin 11-4-38 .;3 sc. U.n r / a t t i REV NYPA-19Q J..l. Fit::Pa t riC!< o , jjy gey,. L. , g 'h 3hI F:LE NC. O'.G @ 4 g 1 n- 'f NYPA-19-302 NYPA-19 010 l

tm pc-CRACK g (C) COPYRIGHT 1984, 1987 STRUCTURAL INTEGRITY ASSOCIATES, INC. SAtt JOSE. CA (408)978-8200 VERSION 1.2 STRUCTURAL REItlFORCEMEtiT SIZIl1G EVALUATIOt1 STRUCTURAL REI!1FORCEME!1T SIZI!1G FOR CIRCUMF. CRACK, WROUGHT / CAST STAINLESS tiYPA-19Q, WELD 28-116, STA*1DARD OVERLAY WALL THICKNESS: 1.4100 MEMBRA!1E STRESS: 4936.0000 BENDIhG STRESS: 1688.0000 STRESS RATIO: 0.4166 ALLOWABLE STRESS:15900.0000 FLOW STRESS:47700.0000 L/ CIRCUM 0.00 0.10 0.00 0.30 0.40 0.50 FINAL A/T 0.7500 0.7500 0.7500 0.7500 0.7500 0.7471 REIt1FORCEMENT THICK. O.4700 0.4700 0.4700 0,4700 0.4700 0.4774 Et3D OF pc-CRACK g r,,; m m u. ma a bl SW I> 7-tV C~e:v.a ry rile No /W/'/Y-l ?0 - 702-Pagt 9 cf l! ~"

~ n'. FLOW A 8 ' = (~) '\\,,i l 45' MIN j TYP l I f I'['['d$,ce$$$3,$$$$$$$.$$$$$,$$$$$'.-. t N / / l PtJMP ttsc*a qWELD Repared by: L'I E 2 + 7 9 /.,A Checked by: NW II -;.gy WELD OVCRLAY '"' N

  1. # # Y ? c' C -

race u ce v REPAIR DETAILS SI Calculation O' hTPA-19-011 FLAV lCESIGN DIMENSIGNSI WELD NUF~C:3 C"""MENis. CHARACTERIZATIONl t l A l 3*l 28-116 circusferential: 0.48" 3.4" 3.4" Standard weld overlay 2" x 42: T4 repair per SVREG-0313, Revision ' l

  • Note: ou pump side, blend into pump taper to ppecifigd thickness if overlay is less than 3.4".

Length on "B" side say be l less than 3.4". l l l l PtEput: sta y CATE ESCA!PTICO J. F. Copeland 11-7-48 Standard weld overlay design for recircula-tion syrtes veld 28-116. 3 CFECXE0SYiQu / h -( ) 04fE A. Y. Kuo 11-7-58 .03 sc. 7'. ANT / u !Ti REV i 57PA-19Q J.A. Fit: Patrick NA bub 4 WMAI. o i hg SHI 4 FILE sai 7.G 13 sTPA-19-Jo2 NYPA-19-o11 1 CF 1 - -}}

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