1:.PatriciJ Buckley - 1.tif

DISTRIBUTION:

* Barberton

F.W. ArmstrongL.M. FavretH.L. HelmbrechtP.J. KovachT.M. 4oskoD.E. YoungLibrary - Van Buren

Akron

L.E. Spry

Lynchburg

A.H. LazarD.F. Levstek

Alliance

P.S. AyresS.A. CoughlinLibrary - Research

INVESTIGATION OF SIX WIRECLADDING DEFECTS IN B&W

REACTOR VESSEL620-0014-51-

REPORT No. 14BY: I. BARNES

AUGUST 15, 1973

APPRDVED BY:.

G.N. EMMANUEL

Mt. Vernon

R.N.E.K.T.L.G.K.A.L.V.L.C.D.S.N.P.A.G.A.W.L.

BottorfCarlsonElliottJeffersMacKinneyO'NealSomersSt. DenisWalkerWaltonWilcox

, his rec,v[ s i "4eds .drve vjl.hjj, eFree om O IOni ator

cr' ejemnptiOnSAF.O1A-

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1.0 INTRODUCTION

The internal surfaces of the NSS14 reactor vessel were overlayclad with a single layer of stainless steel using the BW six wireprocess. The consumables were prior tested to a minimum chemistryrequirement of 19% chromium and 9% nickel. The contractual analysisrequirements for the production overlay were 0.087. carbon max., 17%chromium min., and 7 nickel min., with a minimum ferrite contentin the deposit of 5%. Initial cladding of the I.D. surfaces of thevessel was performed in December 1970 with the overlay of the A181Lower Head Dome to Dutchman Transition Forging Assembly. The A170Shell Assembly was clad in February 1971 and the A169 VesselFlange to Nozzle Belt Assembly was completed in April 1971. Eachassembly was liquid penetrant inspected after performance of anintermediate post weld heat treatment with no significant defectcondition detected.

As a result of the Oconee incident, it was decided to remove theflow vanes installed in the lower head of the vessel. After removalof the vanes a liquid penetrant inspection was performed of the locallyground areas to verify the integrity of the newly exposed claddingsurfaces. Rejectable indications were obtained in these areas whichinitiated a comprehensive repeat inspection of the entire six wirecladding in the vessel. This inspection revealed a general claddingproblem with rejectable penetrant indications being discovered ineach clad component.

An investigation of the defect condition and the conclusionsreached are described below.

2.0 CLADDING HISTORY AND INSPECTION RESULTS

2.1 Consumables

Three consumable combinations were used for six wire cladding ofthe NSS14 reactor vessel., The qualification records for theseconsumables are shown in Attachment A. The area of application ofeach consumable combination is as shown below.

QUALIFICATION WIRE FLUX LOCATION OF USE

WF 173-1 Sandvik 308L Arcos 642CDG A181Heat #7-OB381 Lot #9N8F

WF 190 Sandvik 308L Arcos 642CDG A170Heat #4-95192 Lot 9E3F

WF 192 Sandvik 308L Arcos 642CDG A169Heat #4-95171 Lot 9E1F

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Each of the combinations produced a six wire deposit that compliedwith the internal qualification requirement of 19% chromium and 9Znickel minimum. The combinations were thus tolerant of a maximumdilution condition in production overlay operations, consistent withmeeting a required 0.08% max. carbon content.

2.2 Penetrant Inspection History After Discovery Of Problem

The initial rejectable penetrant indications in the areas whereflow vanes had been removed were rounded in appearance. Furthergrinding and re-inspection of these areas revealed numerous smallrandomly oriented linear defects. As a result of this discovery, acomplete inspection was performed of the cladding on the dutchmantransition forging. Linear indications were detected over 90%of the cladding surface, the condition becoming more apparent aftergrinding of the as-deposited surface. Two areas located 900 apartwere then probed to determine the cladding thickness on thedutchman forging. The values obtained established the thickness tobe in the vicinity of 0.230", which is slightly below the normalexpected thickness for this process. A complete inspection was thenperformed of the lower head dome, after buffing of the surface toachieve a clean condition. Linear indications were detected inareas occupying approximately 3. of the dome surface.

Four bands located 900 apart were subsequently inspected alongthe length of the vessel i.e. from the vessel flange to.the dutchmantransition forging. iNumerous rejectable linear indications werediscovered at this time in the core region shell cladding. Thisdiscovery initiated a 100% inspection of the six wire cladding inthe core region and nozzle belt resulting in the detection oflinear indications in both components. It should be noted thatinspection of the nozzle belt cladding showed mainly acceptablerounded indications. Grinding of the surface then revealed a linearcondition on repeat penetrant inspection.

2.3 Production Cladding Chemistry

The laboratory records for the vessel cladding are shown inAttachment B. Review of this data shows acceptable chemistry valuesfor each of the clad assemblies. The data also indicates valueswhich are generally in excess of 18% chromium and 8% nickel. It wouldthus appear from this data that dilution was not excessive duringcladding of the vessel.

2.4 Ferrite Survey Of Dutchman Transition Forging

On discovery of linear penetrant indications over 90% of thecladding surface in:the dutchman transition forging it was decided toestablish whether hot cracking was the operative mechanism for thecondition detected. A ferrite survey was therefore made at 6" incrementsof the six wire cladding deposited on the dutchman transition forgingand immediate adjacent beads on the lower head dome. Ten beads inall were inspected, the results of the survey being shown in AttachmentC. Included in the sketches are the areas which showed the worst

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penetrant indications. It is apparent from these records that thedefect condition was equally prevalent in areas containing 10% ferriteas in other areas with lower measured values.

2.5 Check Analysis Of Cladding In Defective Areas

Four samples were removed for analysis from defective regions inthe dutchman cladding. The results obtained and the locations of thesamples are shown below.

BEAD # LOCATION %C %Cr 70Ni 7.JIn 70S

4 Z Axis 0.061 18.97 8.63 1.70 0.0118 Y Axis 0.064 19.09 8.67 1.53 0.0088 Z Axis 0.077 17.78 8.10 1.50 0.017

10 W Axis 0.073 17.59 8.14 1.85 0.008

Respective ferrite predictions of 8%, 9%, 6% and 6% wereobtained for the four samples. The latter two values do indicate areasonably high dilution condition. It is therefore possible thatsome of the linear penetrant indications in the dutchman claddingwere fissures associated with boundary regions locally denuded inferrite phase. Values of 8% and 9% ferrite are too high to suggesta hot cracking mechanism and may be indicative of similar defectsto those observed in the nozzle belt cladding. Since no sampleswere removed for metallographic examination, however, it is impossibleto define the exact nature and type of defects present in this assembly.

2.6 Defect Removal

Local probe grinding indicated that the defects were confinedto the surface region of the cladding and could be removed with aremnant cladding thickness in excess of the minimum requirement of1/8". Grinding was performed until an acceptable penetrant conditionwas established throughout the vessel. The maximum defect conditionoccurred in the lower head assembly where 0.060 inches had to beremoved to achieve an acceptable penetrant inspection. Defect depthsin the core region and nozzle belt cladding were found to be somewhatshallower, an acceptable penetrant condition being achieved afterremoval of 0.030 - 0.040".

3.0 TEST PROGRAM

3.1 Examination Of SS14 And Other Production Six Wire Cladding

3.1.1 Two nozzle cutouts from the NSS14 reactor vesselwere removed from bonded storage and penetrant inspected afterperformance of a buffing operation. Linear indications were discoveredin the cladding deposited on these cutouts, which was similar inappearance to indications observed in the reactor vessel. Ametallographic examination was performed of areas showing penetrantindications in order to establish the nature and type of defectspresent in the cladding.

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examinedsix wireand thusselected

3.1.2 Four nozzle cutouts from other contracts wereto establish whether similar defects were present in thecladding. Penetrant inspection revealed very few indicationsmetallography was performed at random with specimens beingfrom locations showing different ferrite values.

3.2 Evaluation Of Effects Of Variations In Cladding Parameters

I t dI

4.0 TEST RESULTS

4.1.1 NSS14 Cladding Results

Figure 1 shows a view of a cross-section of NSS14 claddingcontaining surface defects. Figures 2 and 3 show higher magnification

, ,Patricia Buckley -1.-tit..

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views of the defects and indicate that the defects are interdendriticwith entrapped slag also present. The defects are not associated withregions locally dnuded in ferrite phase. Work done at the AllianceResearch Center Ci on samples from the same cutouts also confirmsthe presence of slag in the defects and a completely normal distributionof ferrite phase in the vicinity of the defects.

The failure to det'ect the presence of these surface defectsduring the inspection cycle performed after an intermediate post weldheat treatment is disturbing. It has been the experience of Mt. VernonWorks that defects in six wire cladding (including fissuring createdby high dilution) are rarely detected at this stage of fabrication.Problems are normally detected only after multiple heat treatment cycles.The extent of a defect condition is also rarely established until asurface grinding operation has been performed to remove the as-depositedsurface. It was therefore decided to thermally cycle samples of NSS14cladding in a similar manner to that which occurs during production heattreatment, in order to establish whether the heat treatment cycles alterthe defect size or appearance. Figures 5 and 6 show defects that weredetected by dye penetrant inspection after performance of the heattreatment. Significant scale buildup has occurred but it would appearthat no growth or major alteration has occurred as a result of heattreatment.

4.1.2 Production Cladding Samples

Metallographic examination of the four production nozzle beltcutouts failed to reveal any evidence of defects similar to thosedetected in the NSS14 reactor vessel cladding. Extensive samplingwas performed of each cutout with special emphabis being placedon specimen removal from locations with varying ferrite contents.Isolated instances of surface fissures were observed with the majority -of the defects falling in a depth range of 0.001 to b.04". Figure10 shows the worst case defect condition observed, which was removedfrom NSS 9 cutout material that Dad been subjected to a 40 hour postweld heat treatment at 1100-1150 F.

4.2 Cladding Trial Results

DeposiTravel Speed inch/minute Cladding Thickness Ferrite Content

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5.0 DISCUSSION

Examination of production cladding from the NSS14 nozzle belt hasrevealed surface defects, which from location and appearance can be

categorized as interdendritic shrinkage. The present of entrappedslag further indicates that the defects formed during the weld metal

solidification process. Measurement of the ferrite content in the

samples and metallographic examination of the structure. show" an

adequate quality of ferrite phase adjacent to the suiface of thedefects. It would thus appear that this type of defect is no 'related

to hot cracking or fissuring commonly observed in austenitic-stainlessweld metals containing low quantities of low ferrite phase.

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It is postulated that this type of defect would be expected tooccur most readily in a situation where heat input was at a maxim-mand very high weld pool tem peratures were created. Such conditionswould be conducive to rowth of a coarse dendritic structure and hencemaximu= chance of development of interdendritic shrinkage. The claddingthickness of the nozzle belt component was established to be in therange of 0.375 to 0,400", which would indicate that a deviation occurredfrom the prescribed process parameters during production cladding. Themost rational explanation for the observed thickness would be that thewelding head was not correctlyas timed and that a speed some whatslower than the requ ired lso have been used. Positioningof the head behind center postTron th respect to direction of rotationcan result in a significant increase iliclAding thickness, even withtravel speeds close to the required Location of the headpast center will also result in a stuat on where molten claddingwould tend to be concentrated under the arc, thereby reducing dilutionfrom the base material and increasing weld pool temperatures. It isthus believed that the most rational explanation for the defects inthe nozzle belt cladding is incorrect set up of the welding headdurin production welding. An attempt estae

a~E"!Qta1Zjvluate this cgt._

Examination of the ferrite records for the lower head assemblyshows defects have occurred equally in cladding containing eithermoderate or high ferrite contents. The chip samples removed fromdefective regions in the six wire beads show Schaeffler predictionsof 6 to 97. ferrite. The 6% ferrite values would not rule out thepresence of a limited fissuring condition in certain areas of thelower head assembly, but the equal prevalence of penetrant indicationsin regions of high ferrite content suggests similar defects to thoselocated in the nozzle belt cladding may also have been present. Twocladding thickness.measurements were made in the lower head assmbly,which only indiat a hic es.i the vici 0_230

Small interdendritic shrinkage defects with entrapped slagwere detected in experimental deposits made with low travel speedsand increased voltages above the range prescribed for the proqess.The use of marginal increases in voltage above the rangecannot be ruled out as never occurring in production, especially ifsupervision is faced with a high dilution c4j_tio In a difficultcomoonemnt trn c a il c n dome nsebl h6hMh OMiil

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These defects are not readily explained on the basis of the lowferrite content of the deposit, since they are not characteristic ofthe fissuring condition that would be normally expected. Thesefactors coupled with the detection of small shrinkage defects containingentrapped slag in cladding made with correct parameters raise thequestion of whether the six wire process is inherently susceptible toshrinkage type defects.

Review of the work done in the present study does indicate thatshrinkage defects of a size detectable by penetrant inspection canoccur in six wire cladding deposited with cnsiderable variations ofparameters. It is considered that the high heat input of this processmakes it particularly susceptible to solidification defects, whichmay prove impossible to totally eliminate during production claddingoperations. Further work is required, however, if it is desired toconclusively establish whether defect occurrence and magnitude show apositive correlation with welding parameters and practices used.

6.0 CONCLUSIONS

(1) Metallographic examination of NSS14 nozzle cutouts revealedthe presence of solidification defects at the surface of the cladding.It is believed that these defects are characteristic of interdendriticshrinkage and occurred in the latter stages of the weld metalsolidification process.

(2) The failure of penetrant inspection to detect these claddingdefects after an initial intermediate post weld heat treatment is notfully understood. The ability of penetrant inspection to reveal thecondition after grinding of te as-deposited surface in the nozzlecutouts, suggests that the problem is related to some surfacecharacteristic of the cladding. Penetrant inspection has also failedto reveal fissuring type defects in the past when the inspection wasperformed on the as-deposited surface after an initial heat treatment.Grinding of the surface also facilitates detection of this type ofdefect. It would therefore appear probable that a surface filmcondition must exist, which prevents entry of dye into a surface defect.

(3) It is believed that the type of defect observed duringmetallographic examination is most readily explained on the basis ofthe use of a practice leading to extremely high weld pool temperaturep.Experimentation to date is not complete, but does indicate that thesix wire process may be inherently susceptible to some extent to thistype of problem.

7.0 RECON-rENDATIONS

linear type detects in six wire cladding cannot be properly etecteduntil after removal of the as-deposited surface.

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(3) A reviewq should be made by Welding Development personnel ofwhat data exists on the amperage values obtained with different lotsof 642CDG and.642CDK fluxes. Consideration should be given toevaluation of the effect of this variation on incidence of defect.

(4) The six wire process deposits cladding with thicknessconsiderably in excess of.minimum Equipment Specification requirements.An increase in travel speed to reduce this thickness is not possible ,because of a resultant deterioration in deposit quality. It is believedthat an evaluation should now be made to establish whether a red. jonin thickness can be achieved by usine reduced wire feed rates. lgi|

(5)to be notthis type

If further refinement of the six wire process is determinedfeasible, serious consideration should be given to use ofof process with a reduced number of wires.

(1). Reference - I.R. Sprung: LR:73:6509-01:1Metallurgical investigation of NSS14 wix ire cladding.

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ATTACMEZNT A

REC0RD Of F ILLER WI RE UALIFICATION TESTc -,CT R tLtts^trff. rrsP "'UN II Crt I*rJrcsc CO RCG sRC HE 4 ..

12E4-156-20 Sandvik 308L Sn. Stl.1/.16". 16 Arc C 1ST 642 CDG Lot 98F 7-08381

;P. ODER UMBER |TYPE OF CURRENT AMPERES

WET BATCH EOUIVALENCY CHENIICAL ANALYSIS TESTS.' 8. NO. PAD C. MN. P. S. S1. CR. N I . r.0. OTHR|

= 9071 5 Wire -U67 = 1.1 9.23 _

___ 90Y7 _6 Wire Zl.{l ___9_ Y.49 _

' I 9069 aseii[et. - _ = = _ - - 3- -. , _ ___ _j 1 ____1

i I TEST rEPORT ANALYSIS _ _ _ ITENSILE PROPERTIES

TEST ~~~~ ~ ~~~~~~~~~ULT. YI ELD E-LON FED o| TES. HEAT TREAthIENT TEN. sTR. POINT IN | AREA

4 ___________________________ N . R . ___ . _ _ __ _ __ ____N .

; _ _ _ _ _ _ _ _ _ __ __ _ _ _ _ t _ _

:I.IPACT TEST S--OF - T/L8. ENERGY LOAD i

HEAT TREATMENT TEST NO. FT/LB. TEST NO. FT. L. I

N .__

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rACE IROOT SDE

AcceptableN. R. N.R. Acceptable

| II CRO CR MACRDrISSURZE kALYSIS. Acceptable

t.E HiEREBY CERTIFY THAT THE ABOVE MATERIAL HAS BEENTESTED It ACCORDANCE WITH THE ABOVE LISTED SPECIFICA-

TION AND IS IN CONFORMANCE WITH ALL REQUIREMENTS.

DATE 10/13/70

SIGNED Babcock & Wilcox Company

INSPECTION AGENCY - i

INSPECTOR i i - I

Page 11 A

lEST NO. WF-173-1

MATERIAL APPROVAL JAPPROVEDIPEJ EC.-

NAVSHIPS 250/1500-1 |NIAO

ASME * COM'L NUCLEAR

STEsA GENERATORS N/A

GROOVE WELD TESTRADIOGRAPHIC EXAMINATION

IRE FOLIO NO. 508-579

IX rL O NO. 499-004

ORKS rt.- Verno|

CONTRACT NO. _

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,!ON ,D :5 IN MIFOMM.;'.CE ';:!THl .LL EOUIRENZNTS.

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r"RD OF

ATTACflMENT ATHE BASCOCK & WILCOX CfPANY

POWER GENERATION DIVISIONBARDiRTON, OHIO

FILLER 11I RE OUALIFICATION TESTI ELtCrllt~npf r * IFICA110M fILLER WIRE IOENTIF IC110N

II ..: 7' C.N .RC5 I_ I -K1. FLLUX

- I R R.

I CORE WI1RE tHEA7 NO0.

I 2E4-156-20 ISANDVTY 308T. C71I TT.I Arc. Clad. (SST) 1b42 CDG Lot 9F i -'Qc 71

?, ORDER N*UPISER TYPE OF CURRENT AMPERES

_ ________ _WET BATCH EOUIVALENCY CHEMICAL ANALYSIS TESTSft'.lAII LA^t JO. ] PAD C. UN. P. S S. Si. CR. NJ. MO. Vm-.r

_____ 9731 5 wire .075 1 9.0 963 __ n

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I _ mITT' u__3 ase Mate 7 _ n _

____ ____ rial _ _ ___ _ ___.

TEST REPORT ANALYSIS ,

_____________________TENSILE PROPERTIES ______________ ______________ ________________

TEST ~~~~~~ ~~~~~~~UT. 1 YIELD E.LONG 1 RED OFR7o. HEAT TREATMENT TEN. STR. | POINT IN LOrG | AREA NO. ;SI PSI

. .-~- ____ _ _ _ . _ _ _ _ _ _ _ t _ _ I. _ _

_ py -RIMPACT TEST °F _ FT/LB. ENERGY LOAD |

HEAT TREATMENT | TEST NO. | FT/LB. TEST No. FT. L.

N~ ~ i________________________________ ______ I_____ ~~~~~~~I

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ . _ _ _ _ _ _ _

GJIDED END TESTSFACE ROOT SIDE

I. AcceptableIAcceptable

:41 O OR M.ACRO;ISURE ANALYSS. AC PTABLE

-WE HEREBY CERTIFY THAT THE ABOVE MATERIAL HAS BEENTESTED IN ACCORDANCE WITH THE ABOVE LISTED SPECIFICA-TION AND IS LN CONFORMANCE WITH ALL REQUIREMENTS.

"IRE FOLIO NO.

.- L!X FOLIO NO.

."ORKS

C.;TPIXT .:L).

508-577

499-004

Mt. Vernon

MATERIAL APPROVAL jAPPROVEREJCTE

NAYSHIPS - 50/1500-t /AASME - COM.ML NUCLEAR

STEAM GENERATORS [ N/A | II

I I j~~~~~~~~~~~~I I

G.ROOVE WELD TESTRADIOGRAPHIC EXAI.1INATION l

. ' l ~~~~~~~~~~~~~~... .

DATE ½U;. 19.~~~~~~~~~~~~

| ~DATE January 19,

SIGNED Babcoc & W4il

INSPECTION AGENCY

INSPECTOR _ -

, 1971

.cox Co.

Paoe 13

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- 1/16

TrT ur/ WF 192

-13-

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ATTACTENT B

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f>r V. e,.ro > rs,, C C r N i Co_ VI

START3/10/71 10-15% 1ST 10084 .067 18.92 9.34 .046

II _ i ., 1+900 10085 .067 18.44

1+1800 10086 066 18.47

1+2700 10087 .064 18.73

,. ., 2 10088 .055 1 [3/11/71 . 3 10101 .072 19.72

4 10102 .066 20.73

.. _ 5 10103 .070 20.33 _ _

6 10104 .071 19.97 FLANGE & NOZZL BELT

.. .s 7 10105 .068 19.91

It . 8 10110 .072 19.79

3/12/71 9 10111 .069 20.31 WIRE HT 4951 1 & D9 70T

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19 10125 .061 20.08

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3/16/71 21 10128 .062 18.18_ __

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1+900 9866' .063 18.94 __

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10-15% 2 9872 .057 19.53 _

ol 0l 3 9875 .056 20.07

1/29/7 " 4 9879 .060 19.62 _.

5 9881 .054 20.07

6 9882 .057 19.49 _

7 9883 4 057 20.13

8 9887 .057 20.38

9 9889 .062 20.12

10 9894 .062 19.82 _

11 9898 .062 20.21 -

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14 9905 .066 20.06

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2/2/71 " 17 9921 .063 20.14

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ATTACHMENT B

5/FJ A_70-2014-51-1 SHEE T

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2/2/71 10-15% 23 9938 .058 20.00 . _

24 9939 .057 20.11-

zL3LZI . .2i.......25 9945 .053 20.55

26 9947 .056 20.36

2/4/71 . 27 9956 .055 20.56

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29 9958 .062 19.82 __ __=

30. 9963 .063 20.41

2/5/71 31 9966 .067 19.66

32 9967 .065 19.83 _ _

33 9968 .065 20.04

_______ 34 9969 .062 20.17 .

35 9970 .064 20.17

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2/6/71 7.5-10% _39 9983 .074 19.45 .__

2/8/71 10-157 40 9985 .067 19.90

.,____ .______ 41 9956 .069 19.78

2/9/71 " 42 9987 .069 19.65

LAST B,. _____ 43 9988 .063 20.33 l

ACCEP1 #20863-

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ATTACHMENT B

sEjl A181-2014-1 - HEET 1 of 1.COt.JVFsCV 620-0014-51

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12/917 7.5-10 START 9573 ,063 17.76 8.31 .040

1+90 9574 .063 18.22

1+180° 9576 .067 18.01 _

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10-15%, 2 9579 .058 18.86

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6 9590 .060 19.11

12/10/73 " 7 9594 .053 19.61

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9 9596 .052 19.39 FLUX - 9N8F

10 9598 .063 18.38 WF- 1 3-1

11 9602 .055 19.58

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12/11/ 0 " __ 15 9608 .053 19.46

16 9609 .050 19.96

17 9610 .057 19.15

18 9611L22.9 18.99

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23 9614 .056 19.44 _

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Fig 1 (x5O) Unetched. Showing solidification defectspresent at surface of NSS 14-6-wire cladding.

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a (xlOO) Etchant - Kallings Reagent

b (xlOO) Etchant Kallings Reagent

Fig 2 Showing interdendritic solidificationdefects at surface of NSS 14 6-wire cladding.

Page 23 1

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Fig 3 (x500) Higher magnification view of

solidification defect shown in Fig 2a.

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Fig 4 (x5 0 0 ) Higher magnification viewof solidification defect shown in Fig 2b.

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Fig 5 (x500) Showing structure ofsolidification defect in NSS 14 claddingafter exposure to simulated productionheat treatment cycles.

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Fig 6 (x500) Showing structure of solidifiation defect

in NSS 14 cladding after exposure to simulated productionheat treatment cycles.

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Fig. 7 (x500) Defect observed inexperimental six wire claddingdeposited using correct parameters.Etchant - Kallings Reagent

Fig. 8 (x500) Defect observed inexperimental six wire cladding depositedusing 3/minute Travel Speed and 35Volts. Electrolytic Etch - 1oxalic.

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Fig. 9 Defects observed in experimental six wire claddingdeposited using 3½"/minute Travel Speed and 33'Volts.

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Fig. 10 (xlOO) Unetched.NSS 9 production cladding.

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Fig. 11 Defects served in experimental cladding deposited in 28"'I D[. pipe with welding head positioned 1" ahead of center.

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