JPN-89-012, Forwards Addl Info Re IGSCC Insps During Reload 8/Cycle 9 Operation.Crack Depth Noted by IGSCC Inspectors Determined to Be Extremely Conservative W/Respect to Crack Depth Sizing

Forwards Addl Info Re IGSCC Insps During Reload 8/Cycle 9 Operation.Crack Depth Noted by IGSCC Inspectors Determined to Be Extremely Conservative W/Respect to Crack Depth Sizing

ML20247D619
Person / Time
Site:	FitzPatrick
Issue date:	03/24/1989
From:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JPN-89-012, JPN-89-12, NUDOCS 8903310142
Download: ML20247D619 (20)

Text

m yy ,

o' }

.- 123 Mdn Street White Plains, NewYbrk 10301 914 f61.6240 ,

e- s.

k:

A Nebrkbr soncao-

& Authority Rf'e^a7E$e* tN "'

March 24,1989 JPN-89-012 -

U.S. Nuclear Regulatory Commission Mail Station F1-137 Washington,D.C. 20555 o

Attn.: Document Control Desk

Subject:

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

References:

1. NYPA letter, J. C. Brons to NRC, dated November 10,1988 (JPN 88-061) provided results ofIGSCCinspections.

2. NYPA letter, J. C. Brons to NRC, dated November 10,1988 (JPN 88-062) provided additional information on results of IGSCC inspections.

3. NRC letter, R. A. Capra to J. C. Brons, dated November 18,1988 concluded that JAF could be safely returned to service.

Dear Sir:

e In Reference 1 the Authority provided information on the results ofintergranular stress corrosion cracking (IGSCC) inspections performed during the Reload 8/ Cycle 9 refuel outage. These inspections complied with the requirements of NRC Generic Letter 88-01. In Reference 2 the Authority presided additional information on welds still under evaluation when Reference 1 was being prepared. The NRC approved of the IGSCC inspection results in Reference 3. In that letter, the NRC also confirmed that the Authority's inspections and analyses met Generic Letter 88-01 guidelines. The purpose of this submittal is to provide additional information relating to the inspections performed during the outage.

In Reference 3 the NRC states that weld 28-37 will be inspected during the mid-cycle maintenance outage scheduled for Fall 1989. This is an apparent error. The Authority has inspected weld 28-37 using numerous techniques and found no IGSCC. This weld is discussed in detail in Reference 2. Relevant portions of that submittal are included as Attachment 1 to this letter. The Authority committed to inspect welds 28-33 and 28-112 during the maintenance outage (Reference 1). Relevant portions of Reference 1 are included as Attachment 2 to this letter.

Ao'll I

n I 8903310142 890324 (a PDR ADOCK 05000333 g PDC

_ _ _ _ - _ _ _ _ = _ _ _ _

m Because of a possible impact on the 1988 outage schedule, the Authority had requested relief from surface finishing in Reference 1 and 2. However, due to an outage delay, all weld '

overlays installed during the 1988 refueling outage were surface finished in accordance with -

Electric Power Research Institute - Boiling Water Reactor Owners Group (EPRI BWROG) requirements. The welds were then inspected by inspectors qualified in accordance with the EPRI-BWROG weld overlay inspection program.

In addition, the Authority removed two " boat" samples from weld 28-113 to examine the - l area of the IGSCC indications. Ultrasonic testing inspections indicated that welds 28-92 and i 28-113 potentially entained IGSCC at a depth greater than 50%.. This is unlikely in welds in 28" diameter, heavy wall pipe, because large diameter piping is subject to relatively low welding residual stress and not typically susceptible to deep IGSCC. Because of time constraints, the Authority elected to overlay these welds rather than wait for the results of the sample evaluations. The weld samples were taken from the pipe outer diameter and represented approximately 70% of the through-wall depth of the weld. The samples were evaluated by two independent laboratories, Lucius Pitkin, Inc. and Battelle. Both vendors determined that the samples did not contain IGSCC. The crack depth noted by the IGSCC inspectors was determined to be extremely conservative with respect to the crack depth sizing.

The reports are included as Attachment 3 and Attachment 4.

During a telephone conversation, the NRC staffinquired about three residual heat removal bimetallic welds. These welds were inspected as described in Reference 1. Unique calibration blocks were used for each weld configuration. No IGSCC was found.

Should you or your staff have any questions regarding this matter, please contact Mr. J.- A. Gray, Jr. of my staff.

Very truly yours,

/ )

(

p

. ilohn C. Brons

/ Executive Vice President

( ' Nuclear Generation Attachments (4) cc: U. S. Nuclear Regulatory Commission Region 1 475 Allendale Road

. King of Prussia, PA 19406 Office of the Resident inspector U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, New York 13093 Mr. David E. LaBarge Project Directorate I-1 Division of Reactor Projects -1/11 U. S. N clear Regulatory CommUsion Mail S*op 14 B2 Washington, D.C. 20555 m____ _ _ . _ __ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ . _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ____-.._m._ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

n-a s. .

l Ei p .

j.;. ,# '. n.

! ATTACH. MENTI TO JPN-89-012 -

INTERGRANULAR STRESS CORROSION CRACKING -

- INSPECTI i\' RESULTS FOR THE RELOAD 8/ CYCLE 9 REFUEL OUTAGE -

i l

.i l

)

l 1

1 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59 l

'" , , ~,~

1. > NewWrkPbwer tv Authority JPN-88-061-November 10, 1988 o

U. 8. Nuclear Regulatory Commission ATTN Document Control Desk Nail Stop.P1-137 i : ' Washington, D.C. 20555 J

Subject James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Intergranular stress Corrosion Cracking Inspection Results for the Reload 8/ Cycle 9 Refuel Outaae.

Referencess 1. NRC Generic Letter 88-01, dated January 25, 1988, which transmitted NUREG-0313 Rev. 2 -

" Technical Report on Naterial Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping".

2. NYPA letter, J.C. Brons to NRC, dated August 16, 1988 (JPN-88-041), provided plans relating to piping replacement, inspection, repair, end leakage detection.

l Dear Sirst Reference 1 requested that the Authority provide our current plans relating to piping replacement, inspection, repair, and leakage detection. Reference 2 included the Authority's plans for intergranular stress corrosion cracking (IGSCC) inspections during the Pall 1988 outage. This letter summarizes the results

~of'these IG8CC inspections. This letter does not address the cracking found in the internal core spray piping during this outage,-since this'is addressed in a separate submittal.

The Authority inspected a total of 92 welds. Eight new IG8CC indications have beenThe found. These included two previously uninspected welds. affected welds are 28-33,28-116, 12-15, 22-63, 2s-92, 4-118, 28-52, and N-SA-8E-2. In addition, weld 28-37 is still being evaluated. It will be discussed further in -

a' separate submittal.

Q 'y (f]~Q~D~

w - _ - - - _ - - _

4 previously detected indications.Wald overlays have been applied to seven this outage are 28-113, 22-63, 28-52, The welds repaired with overlay 12-15, 4-118, and N-8A-SE-2. 28-48,28-116, 28-92, The overlays for velds 28-48 and 28-116 a suparatearesubmittal.

not described in this letter, but will be included in (

Because of the cracking found, inspected was extended beyond that originally planned. theThe sample original sample and sample expansion are in accordance with Reference 2 and are detailed in Table 1-2 of Attachment 1 .

IGSCC detection was performed by EBASCO using manual techniques and Independent Testing Labs (ITL) using P-Scan.

IGSCC indications were sized by two independent EPRI-qualifiedAll inspectors (EBASCO, NYPA, and General Electric personnel).

not including field supervision and craft support. Exposure to i ,

I Attachment 1 summarizes the results of the IGSCC inspection program.

Attachment 2 summarizes crack growth analyses.

new Attachment weld overlays. 3 details the weld overlay design information for For repairs which include removal of material samples and metallographic submittal. evaluation, results will be provided in a future The Crack Arrest Verification System (CAV) was installed in mid 1987.

It is discussed in Attachment 1 Section 12. Since this period, the electro-chemical potentialthe hydrogen addition system hydrogen water chemistry (EWC) (ECP) data for rate was continually adjusted. drifted, and the hydrogen flow state ECP data for KWC. Therefore, there is no steady during Based this on the results of the IGSCC inspections performed outage, the crack growth analyses, and the veld overlay repairs, safe to operate. the Authority considers the FitzPatrick plant scheduled start-up on November 19,We request your prompt review in time for 1989.

l

If you please or your contact J.A.staff have any questions on this matter, Gray, of my staff.

Very truly yours, John c. brons tracutive vice President uclear Generation ces Office of the Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 135 Lycoming, New York 13093 Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19400 David LaBarge Project Directorate I-1 r

Division of Reactor Projects I/II U.S. Nuclear Regulatory Commission Mail stop 14 B2 L washington, D.C. 20555 R. McBrearty U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pa. 19400

i I 8.0 M

.A rwienr of the IEBI Records for flaws identifA 12 1988 was

<w=Aneted.

The process records for Tnanetion Beating 8 trees Impropenset (IEBI) of the above welds in which flaws were identified in 1988 were zwieued. The IBBI of these walds was parformed in the  ;

Fall of of 1984, annept for weld 12-15, which was treated in the spring 1984.

}

The treatment records confirai that the minf== EPRI criteria for effective IkBI were met on each of the evaluated welds, although in a fant cases a single thermocouple recordad less then mini == j acceptable temperature.

The effects of these isolated Icar readings were evaluated as acceptable by the IIBI vendor. Of the 14 flawed locations identified in 1988, six are 28" walds involving a besvy sector camponent (valve er ptap). IIBI practice in the treataset of 3 these configurations has historically involved offset of the coil muey frist the valve or pump, Glas to the gecastric constraints of the ocuponent.

The czambinatice of the oczqmnant and pipe wall thir*na==, and the offset heated scos may have affected the poet -

treatment resiotaal strees distriMice at the flawed locations.

finame EPRI sponsorship, an ISOC Damage Model was developed and was used at Fitsfatrick. This undel could be av=hinnd with plant specific operational and fabrication information to predict the nLmber of welds espected to develop IeIOC cracking, en a statistical basis, as a fluction of time of plant operaticut and the various mitigation opticas availmhle. This approach was used to evaluate the welds in the recirculation system at FitsPatrick. A detailed reviour 1986. of construction records was conetacted in 1983 and tylated in The damage inder results for those locations with identified naus prenant outage.

in the .7AF recirculation systen were zwiewed during the In ganarel, these locations have higher damage inder results, consistant with predictions of IGeoc susceptibility.

As a result of the i -5+11cas conducted in the 1988 refria14try cutage, welds 12-61 and 24-56, which had prwious IGBOC indications noted were iva and found not to contain Ioscr. The two walds will Reference 1.

be monitored in the future under exaelinations required by Mine welds,28-113, 28-92, 28-52, 22-63, 4-118, IRA-85-2, 28-48,28-116 and 12-15 required wald overlays to be perfonned. Overlays were installed in accordance with Reference 1. This is discussed in detail in at+=<4= ant 3.

Feur welds28-112, 28-33,12-4, and 28-53 were evaluated by fracture mechmiics and found to be acomptable. This is d4=cenamed in detail in At+mr*mant 2. Evaluations for the 28" welds were performed with no credit taken for IEBI or hydrogen water eWstry. As-welded resietaal stress distributions for the 28" welds were used in the evaluations.

Two unlos,28-112 and 28-33, will be enemined during a mid-cycle inspection mehadtiled for Sephenhe 1989.

O

.. L ;. :. - '

L . ..

ATTACHMENTII TO -  ;

l o JPN-89-012 .j g INTERGRANULAR STRESS CORROSION CRACKING INSPECTION RESULTS FOR THE RELOAD 8/ CYCLE 9 REFUEL OUTAGE

'l l

-l

.l 1

1

-i F

ap L

I i

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT  ;

DOCKET NO. 50-333  ;

DPR-59 l

l l

l.-

1 l? _

. .- Y

7 m.__., ij r.

-(j hMhh [ mn c Brons 9

gaff hthori14

. i JPN-SS-062-November 10, 1988

.j'

'UE8. Nuclear Regulatory Commission ,f ATTN Document Control Desk il

. Nail stop P1-117 '

Washington, D.C. 20555 Subject James ~A. FitsPatrick Nuclear Power Plant Docket No. 50-333. {

Intergranular Stress Corrosion Cracking l Inspection Results for the Reload S/ Cycle 9 Refuel Outaae Referencess 1. NRC Generic Letter 88~01, dated January 25, 1988, which transmitted NUREG-0313, Rev. 2, " Technical Report on Naterial.

Selection and.Procesping Guidelines for BWR Coolant Pressure Boundary Piping."

2. NYPA letter,'J.C. Brons to NRC, dated August 16, 1988 (JPN-88-041), provided plans relating to piping replacement, inspection, repair, and leakage detection.

3. NYPA letter, J.C. Brons to NRC, dated November 10, 1988, summarised results of Reload S/ Cycle 9 Refuel Outage.

Dear Sirst

. Reference 1-requested that the Authority provide current plans for piping replacement, inspection, repair, and leakage detection. Reference 2 transmitted the Authority's plans-for intergranular stress corrosion cracking (IGsCC) inspections during.the Fall 1988 outage. Reference 3 summarised the results Because several of those inspections and provided repair data.

evaluations were still in progress,' data on some welds was not

-included in that transmittal. This letter addresses'these items.

Attachment 1 provides an evaluation of weld 28-37, which

-concludes that the weld contains no IGSCC.

Attachment 2 details the weld overlay design information for welds 28-48 and 28-116.

l

e e we request your prompt review in time for scheduled start-up.

'If you or your staff have any questions on this' matter, please contact J.A. Gray, of my staff.

Very truly yours,

v. s dohn C. Brons Ekecutive Vice President N2 clear Generation ces Office of the Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 136 Lycoming, New York 13093 Regional Administrator U.s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19400 David LaBarge Project Directorate I-1 Division of Reactor Projects I/II U.S. Nuclear Regulatory Commission Mail stop 14 B2 Washington, D.C. 20555 R. McBrearty U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19400 I

'~~

. r Wald 28-37 This weld (NUREG Category C-1) was first inspected in 1984 with no IGBOC noted. The ptamp casing side of the veld was not examined due

• to the cast s+minless steal material. ,

Two indications were identified diaring an IGBOC examination on the ,

puup casing side of the weld during the 1988 refueling cutage. ,.

T' These indications were identified by the 3 Isvol III and sized as having a through-wall depth of greater than 70% for both ll i

indications. G5 did not perfom an IGIOC examination to verify that '

the indication originated frtza the pipe intenal diameter (ID). A 60 degree shaar wave emanination was used for sizing, although this taehnique would not confirm ID crack opening.

NURBG-0313, Rev. 2 considers cast austenitic cxmponents with delta l.

I ferrite content greater than 7.5 Fn and tur+rm ocatant less than

.035% to be resistant to IGIOC. Delta ferrite measurements were performed using a severn gauge and revealed several locations of low I ferrite. The measurenants are detailed in Table 1-1.

he areas of low delta ferrite in the A recirculation ptmp casting weld prep area may be trar==hle to dihWes in the solution heat treatment of the ocuponents, to amehanical working of the castirq during fabrication, to weld repairs of the casting, or to tbamm1 cutting or welding during original fabrication. The weld metal used ir. the repair was 316 which had between .045% to .06%

car +rm content and 5.5% to E.0% ferrite by Magna Gage de& amination.

'Ib datamirm the extent of this icw ferrite, all cast ocuponents in the 28" section of the recirculation system piping were examined for '

delta ferrite using a Severn gauge. This armnination included both recirculation pump suction and Aimeharge yelds (4 total), and welds to valve bodies. Only recirculation plup A exhibited the low delta ferrite. The other couponents have ferrite readings greater than 7.5 Fn and thus the materials are considered to be resistant to IGB00. The delta ferrite results for each location are contained in Table 1-1.

During a review of the construction records, it was noted that major repairs were performed in both areas in which indications were noted l during original fabrication of the casting. Mis was conf 4med by acid strhing with Aqua Regia solution (nitric aciFaydwddoric acid). A visual examination was also performed on the ID surface of the pipe weld (with boroscope) with no cr= eking detected.

... F 6

During pr=H=4aavy preparations for the repair of this wald (i.e., U identifying the flaw location by Ur inspection), the FRamm. level t III datamined that this area did not **in IGICO but was a wald I repair. Additional examinations were performed to detect the flar p including examination taehnitytaa to detect ID cracking by the EBh800 'g Impel III. 3b IGBOO credking was detected fremt the ID surface. l Additionally, delta ferrita measurements were takan in the area of L wald repairs to confizzi the presence of wald metal residual The delta [,

ferrita. One repair ocatained ferrite greater then 10 Fn. It was r other repair contained ferrite on the order of 2.5 to 5 Pn. [-

noted that during fabrication 316 vald metal was allowed for L repairs. The certified Material ' Inst Esports show that the ferrita [

ranged fremt 5% to 8.5% depending en the heat of material used as t measured by the Delong method.

The JAF Imval III confirmed the the summination results by perfozzing several amantinations to detect ID cracking with no IGB00 noted. The indications noted enring the original summinations are due to the wald metal / base metal interface and casting imperfections. The original maaa=*=aan standard for redivy..y:ri was ABD( B-71, E-186, E-280 asvarity level 2, defects Minor except that suchno ascategory shrink, gas D,E,F, or G defects were allowed. ,

porosity and sanyslag inclusicos were allowed in the castin j as noted by an tlBhBCO Imvel II radiographic 4===+ar.

Based on these inspections, this wald is estaminaa to have no IGB00. It will be inspected in the future as part of MmtB3 0313 Rev. 2 requirements.

3.0 Relief fa *mn-0313 Rev. 2 *-=iivements M and Relief is requestad front the requirements for surface f4=i=h4 inspection of the two weld overlays: 28-48 and 28-116 as surface i

f4=4=h4 M and inspection of these welds would lengthen the 1988 refueling outage by about 3 days.

5 In lieu of surface f_4a4=h45 and ultrasonic inspections, a haad4 inspection of the overlays will be perfc:ned.

The tuo wald overlays will be surfeos finished (field critaria of 25CIOS-Flatname of 1/32"The perwalds inch) will to anhanan inspectah411ty atring be inspected by the 1990 refueling outage.

ultrasonic examinatica during the 1990 refueling cutage by inspectors qualified in accordance with the EPRI-BEROG overlayIf the inspection train {ng progrant. allows, the above welds will be surface finished accordanan with EPRI-BNROG requirements prict to startup.

- . O '.

.h.

U . , - e f

1 ATTACHMENTIII TO JPN-89-012 INTERGRANULAR STRESS CORROSION CRACKING INSPECTION RESULTS FOR THE RELOAD 8/ CYCLE 9 REFUEL OUTAGE I

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59 1.

LUCIUS: VILKin

. .~ ,

'~co""o"^,eo Aletallurgical and Gltentical Gmultants -

[ UCS/EMg dabordfor/CS-)YOMiffSilltfliVC 8K

• w too, (212) 233 2737 50 HUDSON STREET, NEW YORK, N.Y.10013 CABLE NIKTIP (212)233-2558 TE LEX 124615 TECHNICAL ~ REPORT December 9, 1988 Report No. M - 9977 Technical Report No. 7857 New York Power Authority 123 Main Street White Plains, NY i

Attention: Mr. Joseph Lafferty I

Subject:

EXAMINATION OF STAINLESS STEEL BOAT SAMPLE .

INTRODUCTION:

A stainless steel boat sample from a reactor weld, adjacent water heat-affected recirculation circumferential pipe to Lucius Pitkin, Inc., for submitted zone and base metal was examination.

The boat sample had been cut from a weld which j- reportedly exhibited an ultrasonic crack indication in the weld fusion line. The location

l l

heat-affected zone close to cl. eof the weld deposit had been marke OBJ ECT to determine if

( The object of this investigation was heat-affected possible, the nature and extent of cracking in the

) i zone, or other cause of the observed ultrasonic crack indicat f the on, and to examine the microstructure and chemical composition o weld and base metal.

f.

l l

f i ther purposes over our signature 1his report is renderedorupon the condition in connection thatwithout with our name it is special not topermission be reproduced in writing. who!!y or in part fo

^ ~ ~ "

I I rnRlwLs2 7/01 l

~ _ . -. ,

-~~^--"----_m _ _ _ _ _ _ _ _ _

o.

l .

Incorporated l -

e

' December 9, 1988

(

New York Power Authority Attention: Mr. J . Laf ferty M 9977 - T.R. No. 7857 2

l' PROCEDURE AND OBSERVATIONS A. Visual Examination The submitted boat sample, which was approximately 5 in, long and 1-3/8 in, wide, is shov i in the as-received the condition in Fig. 1. . Visual examination of the surfaces of sample at magnifications of up. to 40 X did not reveal the presence of any cracks.

B. Liould Dve Penetrant InspectiqD The boat sample was degreased and subjectedpenetrant to liquid Results of the dye dye penetrant examination. the presence of any crack-like examination did reveal indications.

C. Meta 11onraphic Examination ,

~__ _

weld The sample was sectioned transversely through the

.Seven specimens, 1/4 in, apart and and suspected crack location. -in extending on either side of the weld fusion line weremetallographic mounted Bakelite, carefully ground and An polished forspecimen was also additional s

examination, as shown in Fig. 2. the other side of the weld, prepared through the fusion line at also shown in Fig. 2.

In the as-polished condition, the specimens did not j exhibit any cracks when examined at magnifications as high as (

700 X. Two specimens exhibited linear non-metallic inclusions (0.080 in, long), oriented parallel to the pipe outer surface, as A perpendicular section through one shown of theseinsamples, Figs. 3 through 5. intersecting the linear non-metallic inclusions indicating the inclusions not exhibited 'only globular inclusions,The orientation of the inclusions, and to be planar in nature. as

__.s their linear nature preclude the inclusions as acting I

ultraconic reflectors.

material f Etching the specimens revealed the pipe microstructure to consist of twinned austenite grains (grain size 5 to 6), as shown in Fig. 6. Adj acent to the weld fusion line to l normal grain growth (to grain size 3) had occurred also developed, as shown in Fig. 7.

and light moderate sensitization had l No significant differences in microstructure were observed in the (

_two_ fusion line zones. - . _ . - _ _

'*a-e,

1. , '4 '

Ug. s[ . 7

. < i f1 C O'I p 0 f a t 6 (i .

' ~

Aga Decembe r -- 9, ' 1988' r

-N'ev. York' Power Authority.

79P[1, e Attention: Mr.. ' J . ' Lafiarty - M-9977 T.R. No. 7857 c

t 3-f The ferrite content of. the weld metal, shown in Fig. 8',;

was estimated to be 21 percent, usin5 the point intercept method of ' phase volume percent estimation.

D. Chemical Analysis

, 'l Drillings from the base metal and weld, as determinedly Sh4 from the specimen markings and confirmed by light etching of the-

"*r boat sample, were submitted for qualitative spectrographic and quantitative chemical analyses. The results of qualitative' and

.g a quantitative analyses of drillings from the base metal, given in-

' Table I. and JII indicated the- pipe material to- be Type .304-stainless steel. Qualitative spectrographic analysis the of

.s' drillings from .the weld- metal -was consistent' with identification of the weld metal as. Type 308 stainless steel

. filler metal, as given in Table II.

DISCUSSION AND CONCLUSIONS p ?pr F' Results of our examination-indicate the submitted boat 'The sample to be : free of any macro or -any microcracks.

microstructure of the weld deposit,. heat-affected zone and base metal were considered normal and satisfactory.

y.

No discontinuities or other anomalous features were:

observed in the specimens examined.

Respectfully submitted,

c,- LUCIUS PITKIN,-INC.

4 C.S. Walker Metal urgist

A. . Vecchio, P.E.

V ce President j,

, y.

4 CSW:AJV/ksk/2 1

I

.s : l

• ^

Lucius Pitkin iNCOR PORAT CO (fffflll'gl((jf(ffff ffffffff"[gf jfgfjllgg{g R

w im Ccsting Laboratories-Nondestructive Erawination Screiccs 50 HUDSON STREET, NEW YORK, N.Y.10013 (212) 233 2737 TELEX 12-6615 CABLE NIKTIP (212) 233 2558 SPECTRO GR APHIC ESTIM ATES Date December 9,1988 Report No, M-9977 - T.R. No. 7857 l The following is our analysis of 1 sample (s) of stainless steel pipe base metal l

i TABLE I BY QUANTITATIVE CHEMICAL AND QUALITATIVE SPECTROGRAPHIC ANALYSES 1

l Chromium, % 18.57 l Nickel 9.41 Manganese 1.04 Silicon 0.71 Phosphorous 0.019 Carbon 0.06 Sulfur 0.004 Iron Maj or Molybdenum 0.0X high Vanadium 0.0X Copper 0.0X Aluminum 0.00X Magnesium 0.00X low ELEMENTS CHECKED FOR BUT NOT FOUND:

Titanium, Zirconium, Zinc, Bismuth, Lead, Tin, Antimony, Beryllium, Gallium, Germanium, Boron, Cobalt, Columbium, Tungsten LUCIUS PITKIN, INC.

NOTF.:

Major = above 57 estimated. Minor = 1.57 estimated. .X=.ON.

• = less than. NI' .OOX etc. = concentration of th not found.

to the nearest decimal place - c.g. .OX = .01.09') estimated.

The numbers m parenthesis indicate the estimated relatne concentration of the element among th

[)etectabihty varie considerable > among the clernents and also depends upon the amount and na therefore. "Not i ound" or NF means not detected in the particular sample by the technique employed. _

FORM 104-7/81 _

l'

o i f .(

t f

f a .

Lucius Pitkin

,~co"eo" ,eo hietallurgical ami Circwical Gwisultants i

R u , ,,,, Ccsting Laboratories-Mondestructice Erawination Screiccs 50 HUDSON STREET, NEW YORK, N.Y.10013 (212) 233-2737 TELEX 124615

• CABLE NIKTIP (212)233 2558 SPECTROGRAPHIC ESTIM ATES Date December 9, 1988 Report No. M-977 - T.R. No. 7857 The following is our analysis of I sample (s) of stainless steel weld -

TABLE II BY QUALITATIVE SPECTR0 GRAPHIC ANALYSIS Iron Maj or Nickel Maj or Chromium Major Manganese Minor low Silicon 0.X Molybdenum 0.0X high Vanadium 0.0X Copper 0.0X low ,

Aluminum 0.00X Magnesium 0.00X low l

ELEMENTS CHECKED FOR BUT NOT FOUND:

Titanium, Zirconium, Zinc, Bismuth, Lead, Tin,' Antimony, Beryllium, Gallium, Germanium, Phosphorous, Boron, Cobalt, Columbium, Tungsten LUCIUS PITKIN, INC.

Minor = 1.5'; estimated. ,X, ,0X, .OOX etc. = concentration ut the elements estimated NOTE: Major = above 50 estimated.

to the nearest decimal place - c.g. .OX = .01. 097; estimated. *= less than.NI = not found The numbers m parenthesis indicate the estimated relative concentration of the element arnong the sarious samp Detectabihty varies conuderably among the elements and also depends upon the amount and nature of the samp therefore, "Not i ound" or Ni means not detected in the particular sampic by the techmque emplo)cd.

d

/

/

~ e 2

' E

~

m s

s

~ ,

w. '9%,

e W.,"

- I

1 '

t.ucius PRkin-Inc0tp0f at8d

.[, . .., f ., .

December 9, 1988-

- New York Power Authority M-9977 T.R. No. 7857

_ Attentit>n: Mr . J , ' Lafferty '

u ree. u f

• Fusson LINE Fusion '.

N.- WC g

s f s 4 WELD

% 3

' 2 4

BASE HerAL y-

%~ N 5US PEc.TEb max LotA TIO M m

\

MICR0 SPECIMEN LOCATIONS pgg, 2 4

Sketch showing locations of microspecimens through weld fusion line'and suspected crack location.

.(

. j .:

_ _.m___ __ _ __________._i._____________.________________ . . . . .

!?J; os .~ , . ..,

.9 e . m.

.,.,y_- > - - . . --

'*( ; e , . . 1.ucius Pitkin-i n c o 'r p o ~r a t e 'd :

New York Power Authority ~ December 9' 1988

At tention: Mr. J Lafferty M-9977 - T.R. No. 7857 I

1 w.

.: J s j

,. j e.

'l i

l 4

I

. i i

l

. a.. , .

l~. !

Fig.'4 EIDNGATED INCLUSION IN BASE METAL 50 X '

(MICR0 SPECIMEN 6) ]

- 1 Photomicrograph showing elongated inclusions in the i

. pipe base metal, close to the weld fusion line, in microspecimen

" ~

6. .

1

.I

. A perpendicular section through the microspecimen i exhibited only globular inclusions, indicating that the observed inclusions were linear rather than planar in-form.

1

+.

9"" N **PM j M ,, ,-.Z t'p4f'O9'WIW'4T**'MT*'M W'f ' MF T$)W M9 M W ' > FN W. ' '# b f 4 .fm + + - A v' _ - .

?*We*7 # 2 + ~mmm

.s a

' ' - Lucius Pitkin incorporated New York Power Authority December 9, 1988 Attention: Mr. J . Laf ferty M-9977 - T.R. No. 7857 l

{

r'

~

, g ,

\

'  : p.

• /

i j 1, .

5 6 ,

INCLUSION IDCATIONS, MICROSPECIMENS 5 & 6 50 X Fig. 5 Photomicrograph showing the locations of the elongated inclusions observed in microspecimens 5 and 6, after etching to reveal the weld.

);' . .

l : , .. ,

L. ... . . .

ATTACHMENTIV TO JPN-89-012 :

r.

INTERGRANULAR STRESS CORROSION CRACKING INSPECTION RESULTS FOR THE RELOAD 8/ CYCLE 9 REFUEL OUTAGE t

4 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59

jl} ,

e

.c. .

.OBattelle Columbus Division lui king Awnue Columtaus Ohiu 43201-2tal Telephone 1614) 424M24 Teles 24 5454 l

November 18, 1988 New York Power Authority James A. Fitzpatrick Nuclear Power Plant 4 P. O. Box 41 Lake Road East

- - - Town of Scriba Oswegt, New York 13126 Attention Mr. Joseph Lafferty, ISI Trailer

Dear Mr. Lafferty:

ANALYSIS OF CRACKS IN CLIENT'S BOAT SAMPLE (NYPA P. O. No. 88-0861)

Introduction This report constitutes Batte11e's final report of our examination of a-boat sample that reportedly contained cracks. The objective of this study was to verify the presence of cracks and to determine the most probable cause of the cracks.

The boat sample was removed from Weld No. 113 at a location where indications of a circumferential crack at the inside surface of the pipe near' a girth weld had been obtained by New York Power Authority personnel. Weld No. 113 was in a Type 304 stainless steel pipe from the Recirculation Piping System'at NYPA's James A. Fitzpatrick Nuclear Power Plant.-~The pipe was reported.to be 28 inches in diameter with a wall thickness of 1.3 inches. The boat sample provided by NYPA extended to a maximum depth of about 0.8 inch through the pipe wall from the outside surface and contained weld metal at one end and pipe base metal at the other end.

This report describes the procedures and results of the examinations of the boat sample._ _.

-- - ~~

l 1 i m A---_.-.-______.._-__._- _ . - _ - _ _ . _ - - - _ - . - _ _ _ _ _ _ _ _ _ _ _ _ _ - - . _ - - - __ _ _ - . _ _ _ . _ _ _ _ _ _ - - - . - . _ . _ _ _ _ _ _ _ _ _ _ . . . _ . _ - _ - _ _ _ _ . - _ _ _ _ _ _ _ . _ _ - - - . - - - _ _ _ _ _ - _ - _ . _ _ - _ _ _ - -

a

'e;1 I

t S. .

.-- .~ _-

m,_,,,,_

Pipe i

l I

I l = Toe of the Weld' I

I i

l I

i.

Weld 1

. Actual Size

(

L FIGURE 1. OUTLINE OF THE TOP SURFACE OF THE BOAT SAMPLE i The pipe, weld, and toe of the weld were I identified, as shown, by'NYPA on the top  ;

surface of the boat sample.  ;

1 The dashed lines indicate the locations of cuts made in the laboratory using an abrasive cutoff wheel.

l

+

a e

New York Power Authority James A. Fitzpatrick Nuclear Power Plant November 18, 1988 Attention Mr. Joseph Lafferty 4 an abrasive cutoff wheel at the locations indicated by the dashed lines in Figure 1. The vertical cat indicated in Figure 1 provided the plane of the metallographic cross section, which intersected the thickest partion,of the boat sample, that is, the maximum thickness of the pipe wall that was available from the boat sample, in a direction that was parallel to its length. That cross section was the most likely section that would intersect a circumferential crack contained in the boat sample, if the crack had started at the inside surface of the pipe and propagated sufficiently far (about 0.5 inch or more) toward the outside pipe surface to be included in the boat sample.

No cracks were observed microscopically in the metallographic specimen at magnifications up to 1000X. The microstructure of the pipeNo consisted of equiaxed austenite grains containing annealing twins.

precipitation of carbides was observed in the austenite grain boundaries in the weld heat-affected zone. The absence of precipitated carbides in the grain boundaries indicated that the heat-affected zone was not sensitized and, consequently, was not likely to be susceptible to intergranular stress-corrosion cracking.

A photomicrograph of the metallographic specimen showing a portion of the weld and the adjacent pipe material is presented in Figure 2.

Figure 3 is a photomicrograph of the microstructure in the weld heat-affected zone of the lype 304 stainless steel pipe material.

Conclusions The results of the examinations of the boat sample led to the conclusion that no circumferential crack that initiated at the inside Intergranular surface of stress-the pipe was contained in the boat sample. corrosion cracking of the s absence of sensitization of the weld heat-affected zone.

By mutual agreement with NYPA, no further search for a crack in the boat sample was made.

l l

I 1

f' l' '

)

s

. ; ;f , *

~ -, ,,

1 New York Power Authority James A. Fitzpatrick Nuclear Power Plant November 18, 1988 Attention Mr. Joseph Lafferty 5 Top surface of the boat sample

;' ' ' , ,1 ,', y

[ .

t, -

,i ',

h $+'

e ' ~' ' ,, " J:

4 t

, ' .' v

. . . 6. . .

.; s,

'.*i.g:p,_.

)1

(

,> Ga h., vv.

e i-i 5N962 3X FIGURE 2. METALL0 GRAPH)C CROSS SECTION OF THE BOAT SAMPLE THAT WAS EXAMINED FOR THE PRESENCE OF CRACKS i

/ .s.

/]$0Q Q l

f 3 Q' " 0/ ,

c' xy t

g q

t

\3 s ,

w1 ~ 41 x J [D s I

l. k ) 5N959 100X Glyceregia Etch FIGURE 3. TYPICAL MICROSTRUCTURE IN THE WELD HEAT-AFFECTED ZONE OF THE TYPE 304 STAINLESS STEEL PIPE

e i

^

.f

t I

"^ .c lc; v. "

.. y v.

New York Power Authority James A. Fitzpatrick Nuclear Power P1 ant. November 18, 1988' ..,-

M. Attention Mr. Joseph Lafferty 6 ,

l The examination of the ' boat sample for cracks ~were interesting and . i j challenging. Please contact me if you have any questions or comments concerning the'results of our investigation.

Very truly yours, R. D. Buchheit Principal Research Metallurgist

~ Physical Metallurgy Section  !

RDB:cp Enclosures (3)

L

,e r s'7 1 "'-s .

1. ii 4

Y

, A

. Q')

3,p- . . . .