ML20083R483

From kanterella
Jump to navigation Jump to search
Rept of Stud Failure,Ginna Station
ML20083R483
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/10/1970
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML20083R487 List:
References
NUDOCS 8304040273
Download: ML20083R483 (37)


Text

S6-n%

% g/A Aflu/zi/10 O

1 REPORT OF STUD FAILURE I

GINNA STATION i

l I.

i

!o i

I ROCHESTER GAS AND ELECTRIC CORPORAT' ION I

i ROCHESTER, NEW YORK i

DECEMBER 10, 1970 4

9A j

//

4 Q

481 g 79,I= 2

}

g.

ut.;

c.,

,.%7 4

s

\\,rp Ni e

1 i

I

/s U

-i 8304040273 701210 DRADOCK05000g

/dT76; a

s

TABLE' OF CONTENTS O

Section 1. 0 Scope Section 2. O General Section 3. O Conclusion i

l Section 4. O Audit Board Section 5. O Observation During Heatup i

Appendices:

A-Westinghouse Electric Corporation Report Anchor Bolt Failures R. E. Gizma Nuclear Power Plant i

j B

Burke Steel Company, Inc.

Heat Treating Certification C

Pittsburgh Testing Laboratory s

Certification Report l

D Richard F. Eisenberg Material Certification Report I

E

' Revised Design of Broken Anchor Bolt t

]

F Joseph T. Ryerson Certified Test Report i

G-Pittsburgh Testing Laboratory Certification Report l

Ultrasonic Inspection of Bolts i

s 1

Drawings:

GAI-D-521-049 - Reactor Containment Vessel

]

Miscellaneous Steel: Steam Generator & Reactor Coolant

- Pump - Lower Supports i

{

GAI-D-421- 014 Reactor Containment Vessel i

Interior Walls - Reactor Pit Plans, Sections k-Details i

O a

1

+

{

Section 1. 0 - Scope This report covers those activities related to the investigation

~

of the failure of primary system components anchor bolts and the review of other embedded restraints of like material.

. 1 Section 2. 0 - Genera 1 The primary system steam generators and reactor coolant i

pumps at the Ginna Nuclear Station are supported on four and three legs, respectively, in such a manner that no lateral support is provided from the legs. Flexible connections are provided at both top and bottom of each leg. Each leg is provided with four anchor bolts heat treated to ASTM Specification A490 to prevent uplifting of these components in accordance with seismic and pipe rupture criteria. These anchor bolts, O

or studs, are connected to beams embedded in the concrete floor of the containment structure. Details of these supports are shown on GAI

^

Drawing D-521-049 attached.

I During a scheduled shutdown from September 30 to October 15, 1970, a stud on the "B" loop reactor coolant pump was observed to have fractared in the upper thread. The upper portion of the broken stud was visually examined by a special RGLE consultant and the remaining studs 4

i were ultrasonically inspected by Southwest Research Institute. The in-spection indicated two additional bolts to be "short" by several inches 4

and two others to be suspicious. Preliminary oral reports from the RG8cE consultant indicated that the mechanism of failure did not appear to be

'O-4 initiated by a flaw in the material but rather indicated points of crack e

+

w

initiation around the circumference.. The remaining portion of the broken stud was successfully removed. It appeared to be partially greased and was protected from the concrete by a PVC tube that 'vas placed prior to pouring the concrete. It was then confirmed that both "short" bolts and one of the suspicious bolts were truly broken in the lower thread and the other suspicious bolt had a large crack.

The failed studs were analyzed by the Westinghouse Metals 1

Application Research Lab and an evaluation of the failures was made by the Plant Materials Engineering Section of the Westinghouse Electric Corporation. These reports are contained herein as Appendix A to this report.

g f.l,

The heat treating certification records, Appendix B, for the O

stude certify that they were heat treated to a hardness of 45/8 R.C.

Final mechanical properties were determined by Pittsburgh Testing Laboratory and were reported in their certification sheet dated May 24, 1967, included as Appendix C to this report. Following failure, these i

properties were re-confirmed by Richard F. Eisenberg, metallurgical consultant, to the Rochester Gas and Electric Corporation. This re-

' certification is included herein as Appendix D.

It should be noted, the total lot for heat treating consisted of 57 - 13/8" diameter studs (56 for steam generator and pump anchor bolt installation and 1 for test) and 24 - 13/8" diameter studs for in-sta11ation in the LOCA restraints on the primary coolant pumps. The I

configuration and location of these anchorage systems is shown on

-GAI Drawing D-421-014 attached to this report.

1 I

J

An evaluation of conditions resulted in the decision to replace all of the 56 anchor bolts for the steam generators and coolant pumps.

This replacement was possible because of the PVC sleeves that were installed prior to concrete placement. All studs that were not broken in the lower threads were successfully removed. We were unable to remove the lower portion of those three studs that failed in the lower thread. For these, a redesign of the embedded beam was made, in order to minimize concrete excavation. This revised design including calculations are included herein as Appendix E.

The reibcement stud material was obtained from Ryerson and is described in a certified test report contained herein as Appendix F.

1 The mechanical properties of this material were confirmed by Richard O

F. Eisenberg, metallurgical consultant, using test specimens from each bar used in the manufacture of the new studs. Results of his examination are contained in Appendix D.

Each stud was examined ultrasonically by Pittsburgh Testing Laboratory to assure soundness.

A certification of this examination is contained herein as Appendix G.

i This material meets the requirements of ASTM A490 mechanical properties as to ultimate tensile, yield and hardness. Elongation is 12%, however, instead of 14% as per ASTM A490. RG&E and the de-7-

signers of the primary system supports consider the 12% acceptable j in that the studs are not preloaded.

The original anchor bolts were tightened in accordance with accepted code practices for structural bolts. It has been calculated that the resulting stress in the studs was approximately 160,000 psi.

1 i

Cc,nsultation with the original design engineers, Gilbert Associates, i

confirmed our contention that it was not essential that these anchor studs i

be preloaded but rather be installed with a very nominal loading as might l

be obtained by a single person using a standard stud wrench. Under these new conditions we believe the continued integrity of the presently installed system is reasonably assured.

I l

The 20 atude used in providing the anchorage system for the pump restraints ald not be removed from the concrete as sleeves were not used during installation.. Ultrasonic inspection was performed on these bolts by Pittsburgh Testing Laboratory and they were found 1

6 1

to be sound. Certification of this test is included in Pittsburgh Testing Laboratory report #1 dated November 6,1970 and included herein as O

e rt er ^erendix o west i-rere tiv. newever it w s cenft med durins testing that these 20 studs were not pre-tightened to produce a high stress y.

level in the stud.

q Mgy s

'/(Cy/[f.

Based on these conditions of minimal stress and the improved 4

j environment that would exist around these studs bectuse' of their location approximately ten feet above floor level, a reasonable level of confidence j

can be obtained to assure that these anchorage systems.will perform as required.

t Section 3. 0 - Conclusion Based on the analysis as presented herein, there is reasonable assurance that the failure of the anchor studs was caused by either t

/

l-hydrogen embrittlement o stress corrosion. The less probable cause is hydrogen embrittlem nt since the bolts or studs were not torqued until

.- c 4

,a.

}

t r i t

}

a considerable length of time after installation, thus allowing time for Q,

any hydror-n picked up in the heat treatment to diffuse out before being v

stressed. The PVC tubes surrounding each bolt make it very unlikely that any stray currents could have contributed to the failure.

[ g/

)m V -

Stress-corrosion cracking appears to be the more likely M

The bolts were " slugged up" resulting in a high,I p) mechanism of failure.

prestress and in fact it could be conjectured that some might have been overstressed.

On several occasions borated water has been spilled on the floor and washing and hosing down of the floor has taken place. Some water was observed in some of the holes during the replacement of the studs.

This water was tested and found to contain boric acid.

O

~

rae st as in the tOCA restraints fer the grimarv ceotant pumps have never been highly stressed and have not seen the wet boric

'I

~1 acid environment common to the floor anchor bolts. We can therefore establish a reasonably high degree of confidence that the bolts in the LOCA restraints are not susceptible to stress corrosion within the conditions as they exist.

As described in this report both the initial failure and those found subsequent to it, have been investigated and the probable cause of failure identified. Similar bolts used for support and restraint of primary system components have either been replaced or inspected and adjusted to assure that similar failures will not occur.

Section 4. 0 - Safety Review The Nuclear Safety Audit and Review Board met on October 9, I

m,.

,s

t 1970 and approved the investigation and replacement program that O

has been detailed in this report.

i-Section 5.0 - Observation During Heatup During the heatup to normal operating conditions after re-placement of the anchor bolts, the anchorage was checked for vibration and growth. No vibration or displacement was observed at the anchor bolt plates at any time during heatup. Expansion of the primary system during heatup was confirmed to be as designed and similar to that measured on several occasions in the past.

i 1

O i

i i

5 l

1 e

i i

1 l

4 0 4

s

I I

O I

i l

l APPENDIX A i

l WESTINGHOUSE ELECTRIC CORPORATION REPORT ANCHOR BOLT FAILURES R. E. GINNA NUCLEAR POWER PLANT O

1

{

i 1

mV 1

PA-PME-1675 k

s EVALUATION OF GINNA PLANT - ANCHOR BOLT FAILURES i

An evaluation of the Ginna Plant - anchor bolt failures has been conducted.

I The bolts failed either from hydrogen embrittlement (sometimes referred to as static fatigue), or by stress corrosion. The type of failure is very similar in both cases. As a result of the metallurgical investigation performed, Appendix A, it is concluded that the bolt failures most probably were caused by stress corrosion cracking.

l Hydrogen embrittlement failures occur after loading to high stresses in a progressive manner. Time to failure depends on the hydrogen concentration and the stress levels. This alloy, 4140, is extremely susceptable to hydrogen embrittlement at the hardness level (45-48 Rockwell C) used.

If failure does not occur fairly soon after loading, the hydrogen will be able to diffuse out, and cause no future problem. Therefore, if the cause of failure was hydrogen embrittlement, no further cracking would be expected.

This alloy, at this hardness level, is also very sensitive to stress corrosion.

The type of fracture will be almost identical to hydrogen embrittlement - in fact many authorities consider stress corrosion in high strength steels to be

a. form of hydrogen embrittlement in which the source of hydrogen is the corrosion Os reaction. Chloride, boric acid, and many other contaminants will cause this type l

of stress corrosion cracking on highly stressed hi'gh hardness steel.

All of the stressed, high hardness 4140 bolts were replaced.

The replacement material would not be expected to be subject to either mode of failure, so there should be no cause for concern with respect to these bolts.

h p r'j The remaining bolts of high hardness 4140 are not stressed, and are much lese i,/f subject to contaminants that could cause stress corrosion. The fact that they are not stressed means that they could not fail from either hydrogen embrittlement or stress corrosion. In addition, if hydrogen embrittlement were the cause of the bolt failures, the hydrogen would have diffused away shortly after installation, so no problems vould be expected at this date.

Background Information Heat Treatment The heat treatment, procedure for the anchor bolts was as follows:

1550*F to 1600*F - Austenitizing temperature (in Endothermic City-gas; heated to 1950*F with a catalyst; moisture controlled by dew point) 850*F Temper (in air) s O

M

PA-PME-1675 0

Ultrasonic Testing 1.

The failed bolts were from a lot' of 56 bolts used to attack the reactor component supports to the containment floor slab. These bolcs were ultrasonically inspected by Southwest Research Institute as described in Appendix B. - The partially cracked bolt #2, as identified in Appendix A, was detected by this method.

2.

The remaining bolts (lateral supports) were ultrasonically tested by Pittsburgh Testing Laboratory as described in Appendix C.

No indication of cracking was observed.

1 l

E. Landerman PLANT MATERIALS ENGINEERING l

O O

i I

__ j

j sf)[

AppIndix A l O I

Investigation of Failed High Strength Steel Bolts I

l Four of the 1-3/8 inch dia by 23 inches long high strength

~

steel bolta securing the main coolant pump at Rochester Electric and l

l Cas Corporation's nuclear installation against earthquake damage failed in servf.ce. Part of a fractured bolt still with the nut attached (bolt #1) and two bolts, one suspected of containing a crack in one of its threaded end, (bolt #2), and one only 20-3/8 inchas long with a portion of one of the thceaded ends missing (bolt f3) were submitted by the Pressurized Water Reactor Division for determination of the cause of failure. The investigation of the bolts included magnaflux inspection, visual examination, determination of the mechanical properties, chemical analysis and a fracto;;raphic analysis.

Magnaflux inspection of bolt #2 confirmed the pres,ence of a crack approximately 3.5 inches from one end in the threaded section of the bolt. This appeared clean and showed only minor signs of corrosion.

In contrast, both pitting and genersi corrosion was observed on bolt #3 7

and the fracture in one end of this bolt wai, oxidized and mutilated' v y-to such an extent that the macroscopic fracture features were barely O

recognizable.

The tensile properties of bolts #2 and #3 were determined l

using standard 0.50 inch dia tensile specimens as follows:

T.S.

0.2% Y.S.

Elongation R.A.

psi psi 221,900 206,200' 11,4 46.3 B lt #2 223,150 203,200

'10.9 41.6 220,650 199,200 10.5 42.2 Bolt #3 11.1 44.3 219,650 198,450 The hardness was found to be almost constant from the surface-to the center of both bolts indicating that the bolts had been uniformly heat treated. Bolts #2 and #3 had a hardness of~48 and 46 4t

  1. 4 H.

Rockwell C, respectively.

4 The bolts were reportedly made of AISI 4140 alloy steel.

This was confirmed by a chemical _ analysis, which.gave the following results:

O l

. C Mn P

S Si Ni Cr Ho Cu Bolt #2 0.43 0.95 0.009 0.020 0.2 0.22 0.84 0.14 0.18 Bolt #3 0.43 0.93 0.009 0.021 0.2 0.23 0.80 0.14 0.18 The crack found in bolt #2 was broken open in the lab and subjected to a fractographic analysis together with the fracture of bolt #1.

Both fractures were examined visually by means of a low power microscope and replicated using the carbon-replica method for examination in the electron microscope. The fracture of bolt #1 is shown in Fig. 1 and the fracture features found in the various locations indicated on

[g Fig. 1 are shown in Figs. 2-5.

The fracture had multiple origins and

/

.$ { y ', P initiated and propagated in fully intergranular rupture (locations A, B, and E).

Location C shows the transition from intergranular rupture p' to the dimple rupture characteristic of the area within the dotted line.

M In this area,.some_cleavageg as found intermixed with_the dimple rupture # g'

~

as se'en 1n_ location F.

The bolt finally failed in a brittle fracturgg showing a_ mixture of_cleavagerdimple; rupture _and some_intergranul_ar I

fracture (locations G,_li,_and_I).

The fracture surface of the crack

/I foudd~iii'61t #23s s_hown in Fig. 6.

Again the fracture had a fully intergranular appearance (locations K, M, and P, Figs. 7 and 8).

Location Q shows the transition from intergranular fracture _to_the mixed 4

cleavage, dimpled.and_intergranular. rupture characteristic of that portiond my;w of'the fracture, which was generated,_when the crackiTas opened in tTe b

A

~

lab (location S).

~ ~~~~~ ~ ~

4%

-[

Although the fractures in bolt #1 and bolt #2 differed idl macroscopic appearance, it is believed, based on the fractographicl.

analysis, that they were caused _by..the_same mechanismF Fdlly inter-granular rupture at ambient temperature in alloy steel bolts quenched and tempered to a high strength can result from the following causes:

quench cracking, hydrogen embrittlement, stress corrosion, and fatigue (in a high humidity environment). Fatigue fractures in high strength steel in a high humidity atmosphere, although intergranular at the origin, will normally show some transgranular fracture exhibiting g

fatigue striations. No transgranular features were observed in the slow8 [f I

growing portions of the fractures in the present case, and,in addition, A

it was reported that the. bolts had been subjected to static loads only. ba Fatigue is, therefore, not considered to be the cause of failure. It T) isalsohighlyunlikelythatthefailureswerecausedbyquenchcracking,[#gg d

since the fracture surfaces were only faintly discolored from oxidation.

Many of the intergranular facets exhibited hairline cracks and partially formed dimples. Both of these features are commonly regarded as evidence of hydrogen embrittlement, but can sometimes also be seen on fractures caused by stress-corrosion cracking. The bolts were reportedly not stressed until a considerable time had elapsed after they were heat treated. Any hydrogen picked up in the heat treatment would, therefore, be expected to have diffused out of the bolts by the time they were stressed. Hydrogen

=

e embrittlement was, therefore, probably not the cause of failure, although this possibility can not be completely eliminated. It is concluded that the bolt failures most probably were caused by stress-corrosion cracking.

C. H. Neergaard Metals Application Research Westinghouse Res. Labs pgh Attachs.

4 4

l l

1 o i

i I

~

,..,f '

9'. 'r.f

.Y....

1,,

~

y,,.., g, f;),

a

f.. 7.-

._,,4

[, f.

+,e.

,,)

I g-5 / )f, l. '

I G l. [

7'

.,e r

l I

5 :., <

<. < ' >)

. i s'

~

ll g

.~

!/ pf

<s 4,-

c.

U

'... ',)y ;O,,.

r

. ((.

(:

s.

'I

.., T '

p.

t, 8 '

I $_

f.rfs ' a:'..g ' l

~

y*

e

.t p

e.

. z 5 N*y

')

.x '

s ',.,. ' ',, toq

,f'

~

. k, cj n.

l l

l t

Figure 1

e r

. = = ** wvs ic. es

% =w 2,e g a =. 9.

+.. + - - *

~%

e x,

.g O

d l

/

/

e 1

/

/

/

/

j

/

/

/

/

/

Up

g, m,gm_ < - m----

7._.

_Lg.;,.m._;;i7_;;;

~ - ~ -

l 3-4 g -/ %.- A.,,. g,

j

~ l f

h

w e.2: p:.#v. e.y u

l c

w. u..a v...

.. ;- :4;... j.- - %. ' '. '5 _.. :t k, M

)

Q " j '. *. ' ' ' '

  • C.S+y.;;+' :;;

' s

.T-.'

l

t

, ;1gp.- b c_.

' '...' i f y, :

j

- Wf ?.y ;_ 2..

'. s;4 t -.

~

,, : yl...'[

l

_ i. :: s'-

.,.. > a r.

'. #.k h g'b ( ' M.~" *..

j h

?M.

'd".'

..e

f.'..

w t'

m a : y' t':. 'y' _

t.ft

=, - e..

g...'-.

n

    • s

.- wn.. m' ' 4

.N,. ;.

I :.... i l

-[

,; j

. o Location B

.- 'r-

-s..-

J-

~

g ih

~

{h

'. '.-, h.h.7 j. aryp-h f

3: hb. k.w ' --

w

k. :

. y g;.!

.?

r l

3 r

g 4400X l

i A,

O 1

l l

4 f

4400X 4

l r

I Location C l

t g

i i

s h

i h-4400X Figure 3

Y...:

-I f* ', 3 [h '(

yg

).]. ~; _ ].(. '" ' __

. ',. [ ' '

',d

',..'[,,4I,-

.. " /, :..

it; -.. y

.O-

?.. _ ;.

'a

.4 gy:..

ry,3 9,.

,. # g, g,..'. :,.

+

. g.

.,s.....

n e e

. g ' ? n.

. n.H

. '::. '. ~. -T,c :...'

\\

h.gy.

_ : ;V. _

y-s s.

<Qe'y*' M :..< :< '... ;- 7.

. %sY '. _ '.

C y,* g q.%.'..c ~ ;.

4.,

j. -:

4

.Q w..
. ',: 3, N*.f,..Q.. _. %... - > %.%c.a -

.; e. p ;.

.x.

an... ;

p' " % --

<. ^..;

.p

. gt F,. - ;

4 C-

?.j.

...: m.,.-[n.,1.W,,.

o.-

.:.go...c. n.

y

' *M.

.K

'., ' '... i, ]_ g

_....y

, g 2080X

.-s e

R.y,,;g,.

./%"4.a;p.'j;,?_~j.: Q "..

'& z9, n)

%_ c..%$.p. q~.

. -74

... - O..n [ L.:

.? { [

m j?? 7A

.. y.

- " r.c ~

yy.8 y

.A p....cy % %o :;,.*, -

4.js' R.$'.$,i.

y# A..[. V _p 4 - M y..y t, y:[ r J

f f,

.g.

.T{:^ d.'q "7,i g g g

, 'g g

  • ) @,yf+e, f n.M.. t A-

,, r. C.g 3. y,

1.. n t;.s w r -;;.

+ >.

o.

,. y a..

u g~,,.Mi' ',; '

l g,' t.

^'i.+

4

..f c,

s 4

Location F L '".'

N

'D C

h g

'.(:'p. ;; & Q. f _ y.k f,, ~

?

...y,,

w q

2700X 9 %:y Ay4

%,%,w - jA 6 eg.. t.

n,*

. key f..x;,:.f4y Y 'm 5.

- Q.v V:...

_.C:,:,]p*j,p,)..

t

). i.;.~.'

p.

~

,, _. 5,,.w u.., 3::.r4.;.+......

..e\\ p. r..,. w..

-y

c. y

.p 4

.. t.. -

t

~ Ws, ',.%.4

.f..*.

l * 'l '- R;

"\\

. f.y

. *%e. 3

,,q....

.c.

c.

J.
tl; *~

c.,..,. 4.e,,6 A[.

7*-p j c

m,

  • g

. *. _ j+z.

e.

..? 4 a c L., -;-,.

y.-.

. +

1..

....a l,9 WW,;.

. Wllq.h.'L.?y.$N-.-.Y..

y ek.m *..;,'

l 9;.<

gg

  • 3*

e. y n ;4. [ ',4 g 1..

5f, y ' - -

v'g;:;.,.- ;

- gt

.Y,,,,.

e

..:.. %,.q:.pw,;j

...r...

  • f

. ;g/pa..,..

- ;-?,:. h. 4 k"$'l..s

,...m

- L. f.-.

Location G

-s$f Q ',' w.il %;

b '. _ -

. l' G,

  • x

..6:a

we 1

nnny

?

s' f'

L s

+

n

,r. m,,,a:

~

3 '"...

~ s

?.;'gj ;lg,

.R

.$ u&,.

?

L'

,/ ).', '

b it Y,, ; s

=,, ~

y.

r s m~ -

v

- s s

s yds l '

.e

4. s -

s y

\\

,(

,e Location H l'q.

' T {...e

p.
'.?

2

)

= * $N w

.:.s

,, :; P

' ', s, g

. Ji'

(,

l

>, ;j % r

' 3 3 *, '.

2700X j

,.4. 1,.

.(;,.{' 'I

.i

',~.Q, f vft g

I s

. p

'g ' - ',,.

t y,,

43

  • 4,s

' \\ W!

e

" X f W

,(

>c h i g..)

. qi

, 'g..

1

.\\,(

i

,,4 g

v -

a 3 7. k'd 7 b;y,. ' d%%.I yA

^

jj /

d

%t s

n: 1 j

t, s b.

w 4, g

...y*

e

,y v,

l Y ' 4 4 '..

..,q.

R*s t

,1

{

6400X

l h f a

f

~'

s s

[ '-

~

4, s

p s

ig 0

,.V**,.

',.=e.

.4i

1. -

. 's.

e

~ ~

em h~

'4,

' d, f.s l

Location I

.=

. $. '. '..yQ

}.

s 3.....

- xs.

e a

.gn

,2 2700X Figure S 1

=. --.,--,.~,-,,_ -,

c c g _ _,,_

___1.

l e

i I

i i

f

.+.,,,~i, 3i..

Cd

. M'iWd Beeteer e'n i - :h.;)'>{%'.*;f?/N;".,s.q t t g jl4 y'

/a 6.

,e 2

s

~3* s..>. a e. _

~

-s z

f, j

! ' ' 21 -

)

I I

't.:i,.

P U.

t. y,;

1 0."1 M

c:y;

.-gy~

.x

uu K

l Figure 6

... - - - - ~

i,

, s.

l

. ~~~ C: 1.4.' >.: nwemManh9pt=see.eame e -a.,-

-' 4 - ~. W ' k

".***'N C ' '

j i

,;.;_.. ;j..

} g g,__:

. ~ : 5 = : a *:;,..

.:'i% $..

3.K : _

_j.

~..

~

J. _ -

- 4A w c..

.. -- w s..
q. :y.....,
. a.k :;-

- :', s. ? < *.*y.

y, -.

-..;. _. - ' s p' 9.1 a,

n y_, - -

._P.-

..'f.*,

_ 4 n,,

s

.1-.

. - 4:

  1. . ~**.e-Q

..a

.s

.m.-

s _

i 9

[

. k j

t** h. x.-

b :-..g

.,......-

  • sd -

v.:. ?_.. <

.~h - :; ;,; : :

s V,

. ;:;. q; *
R, so.

~

5, N.' :2$.:.%..'

' gg t,4

,g

.,~

l

?

??> Y _

. ' '...f.1

.,,....#* $*p.-

.h. +

l

-rs..... -Q =.'. 4

- e-4

.p.

L,*

...:... :. 1 g,- '..

, ;'... ' s,,y - <;

y, 5..%_

r.. c[. ;.. -

,ng.. -- c..%' g'.': A.e.mt p.: c e.--

\\

2. v. :

' g;;.

%.s.;.y,n.

s.

3

=

% ', s ' :. W

s ?.i l
n..

ib.y p;.,,..,. a.,

..v..

~::^'.f $.>.. s...Q

.K L &

  • g"-:*X q:
  • s l

' %K ' '"b. +,

V:" ~."

' 'a J.

  • 'Nfg.7y/Fy..cn.}."f.g, z.<g h'-

j Location K 2700X

)

- a ; c.?^ '

~ w". ;. 2.; ' M*. '.

y..,'

. \\

r

. /. m,

f.

kN. ;,

e/.c,),. k,..,f> ; - -- 7'j.f

' ).

g.

.;:........ m u,,

A

.m

,, s:. g..4 3 s,...:

l 1.6.;.

g ;.. :.

m 4-

.' - T. ?;- f. '.

V4 v.

Z. ',.

w

v...

l$ fi:M }j..,&.%..k[

h.n'.,._

'.. ' - y? i 4,7N

.'y - ' y OW ' ;

.y.y -

.i,.,.

.. A.c 1..

'q,

.pyw

.. v m...,.,yf. t..-..., -

y 3

s C~Q '

. '.; 'y "' :l?-[ k

' -.i. ', '. ! * *

'o' sj V

. q.l_ ~ _. f lu +:...

b.-

Ti;V.

?-

T_?,

.-s a.

. sd;a.....

..._.:,.v.

n..

J.

'r

. gj,

....'.;, [},

s. 'W '. ; ?. 7,A,,,.

, (,p ;[. t -

y t il, g' ',; C t, '. 4 A -

u,.,f.,. : '.*.

f'

. j C s,

.., gg-.y+3

., w Y g

y

(

,.,.:,_ :./_

1 v.,

a y, x ; y q..

7'yr.V:p ' ;

s.

4..

4..j..~a. -,.

...; Location M l

e c,1.

1 v.

F -

j v. /.,

g i., f. -

.f y'.

^

I

..,8

3.y w,.

ee.'..m.,..,

,n;

- **)

+

.,t' n

c.,.; e...yf, o V.

2700X i

J

,g

.4

,,y" g '..

n.

%g

_..~~a.

l

. )6 ^ ? y;;5 K".

O.h.4hf, ; ' ~'(g., &..-(

L.

.- p : V : y m yl w gew.,

, 4f,., '1 % - lu.%G-DAD,Y. (_i?R.:,Qf. '. O.f

?

l

. e.

n w

x.. g7;......~ i g h..

2.F F.t v.n.w.

' #, f J.

4 ti

^ -:

.p.

.' e;M ;. '-:; 2 W

h f

k f.

  • r., *

" " =

i 4

vA,M ug i

A m

f. u m;n mm z f,b..,

j' -

,1>k n O r [ 9 y' n.-

l Location P a.t m.

g.s e-< y- ~

. m..

m

(

f.

I

[

4, 2700X i

l i

Figure 7

-- "-..,; ;- :g _ ;,61_-

._ o 1. 2

-u;.A J gga..

e

.c O

v kocag,y

, 7..

N400g 4

p W.

/

_*y t

5 004

/

f

/

/

/

  1. 8Ur,

O

)

i APPENDIX B i

BURKE STEEL COMPANY, INC, HEAT TREATING CERTIFICATION 4

i 4

O 1

l 4

i I

e i

'I i

O 4

.7..f: S:", 'b.U d. t.i Q\\.').i..i.!.M %...V ic d. I.2 /d id * /....U li d..,.D. '. [.

I

~

's a L..,,

'.[:.. { - W'*

' P. O. : J? M4' - :.

~ ~. - :',...

'...L..

f.

4

?.:~

' b."..h;p. s... $.$.. *O,elc..':-.$...,.N' C.0 C)'UOT.III'?.:.N.Ii

~~ ~

.:. C:i

..Q:

\\ v..

. a

"< u i..

..,..... ~.... C. Est.cMb.in. d.w.. 3. 0.0.:

7. Scco.m Cent.u.r>* of. ScM.:m..
'
9 %..,+ %-\\ '*: n........
7. 7....
;r, ',y..Y,y,.... &. %.u. -Q '. f.: '.. + N w....

s,,....,

.. v,.

.. i.

..c,. o

-'.'y. ?.fW. '...

n;5;: ?e. :.N

.'.... ' ). ?'....

s..

9

.~.

c g.

,..,).

.y

e.,..

v..

s b, a.

-.,,1. 0;ue.

,,.....s.

............ *g......

,,..* ggyg cmma...e.

.' s.

..~::

. v... *.

9 te

, Y,.,9.

u..

".,. i. w....N,..., %.

s,;;

go..She t. Me..ha.l..Uorke. s. Inc. 6......+/.s e

~ : ~. m n " es.". W,..:-.

.-n,' e " - N'

..y...,. g..: '"

s

..g w,

k ;4 4 ~ Hall,13oad

......,;.w..[.

.c.

y fP;

'v.

joapego, Key Yovk..13120

, '..L

(.:.4 ' :.:..a : s a.

. *... 'd

..,c :* h.G& "h.fEC.* Gc.,, -

'% jf,

c g

.-M & ~

-Q ~ h.. p\\*'

8.'.Y...

r.

y<. 4. e... 9, : i.,. y

t. -
a..*.,;.. -....

. ;4...,

..a.

u

.. n.

. ~: <.: :

r..

,c 3.,..,..,..

..v......~....r..

.s t.,.,

x.

,'- l.G'*::v :q n,.., :..-.

W.

5 a.

d '. -

. 4.

.,. l., * '.... :.,.... *..r.J...

.. c. PAC.W.NG L. IGT.. ~.

g L.

..b f.fr,m II:.# T E T -..

    • .g..-.,* *! c ?3t.? 3:"? t 1 P Wf FPJ.?..."1

.. *g !m: tut.t.

.

  • tWp3fp.

,V.

friiff

  • t
m. ; % -

=8.---..

m

.:-'...au.

~2-

. i..

... r......

?*-

c..

.,,.... f.-

f..

,p s.

4

., ?:.,.

f,...,.: 3;,

~;..s y \\. -:

..t..

p..,

~

N..

.,.3-

.,;T,

llx. 25.109.,,...,:...;..Ro6,. :,.',...J.. _,. s... d1h.0,,.

Sr..

.. a.n+

"., r+'.%- :w04993. ?. R..

r. ~..s..c.

s

.i,..

.. ~......,...

..... n n

n 2g c.....,:,

..,. a....,. n,,..:.~.... a_

..,. %.c:.

4...

c.

...., u...e. '.e

.u. o:t

,.T <.:

-s

. :. ~,..

.n. :. v.

... +....

.v.:-.

s.

-r.*

" ' U. i.1,.,..,.,

. ~.

.,N....

.y '.

..a J

s.'Q.,. a. M';.,7..'...ll...: % p..."l.

.=

. ; 1. <. ',. ~\\i.*:

  • 9. l.

.,: '..U.f.p & ' -

. ?,c.::4.:.i

.y

.... ~. :, :

...s.

... a

?..,% v....

,.,,:.. n. ~,.

y, e

...c..

8.

.t......

...s n.

r v>.

.. CEF.:TIF.I CATION -

.... e

... : s

..,i

... :e._. W.".J _. C,....--.. Man. -

Le.t y.

Phca.

. Sul -:. Si.

.LNi

. Cr :

'.'. Vc., ;

"M *. Cu '."

  • 7fo

-n

' ?. w '- :

.' n..., c..c..:).

2

  • .. c. ?...

n, u..

t.

.~. -

~..:....

.::c

. y:..

.h

,A.:'.'.'..

- ::l '*/. Q.,

^~-

t.,

e.l;; ;:

. :. L.d, " +. '.. :. '

n

~...,

.. s

, a.3..~ ;.,.,...

.,p :.:.. m. ~,..- ;.v:.,....

..,..a...:

a;....

s.

.:-i:.

?

a'... - -

^

.1

~.

. ~.

7...

c

.. ~

%+ ' ^*,,L-t

.PHYDICAL PT;OPERTIES:

r.

_. s.:7. - -

. s 7

2

, %ce s.w,.-3.y2

, yst

.y' rM*"" Y*' ~,*=m'm' ar%,'g,g%,

.t

~[Ek.nytta

. :...We. certify that the above parts hav$c

. syimqid Ps1 i

'been Heat' Treated to c hardness or ntaxau eu.m

.45/8 n.c.

EHN RC

. Gr. S'ze

..e..'

y. $: tr5' 6
  • k g

Q.}vh.d E 6.&.c.T

=. -

so.d. i'it?t.rm ms

-I-g 31gyc? nan, 1g(7,

' '. to -. p. /rr, a t

Y*

.s

. Y73:llET:*.M'CEtt11rYTPATTIM ?";Lt. /.?;.g t.W O;'Tr;; ??AT;.

I

/ -.

F.I AL DI.33F.ESD AIN:i', li TO iiN; I TJ i O CC.

j

/ g,y),T.,.4 ' C,,,.,

~ix At.0 1. p..%..._

c.' ~., -

tr.OMCISG.ThUL /.ND TtlAT*.;2 4.1 T.'; 11Mr't KNGY:.'.'DC.j P

L..

AND L El.l'M'

/- J ny.

.%.'..u.,.

TU S Qw:.it.

%;A t.@ g

./

3

.,,. : EURIUI SIT.rL CO., I"C.

. J ' 'JOHX Q:,::00'.*LR,1& ui Pd'h

... i O..

c.

,z.

-, -.J. Y. : g '. #..., ? W' N'.T..

.:.Y.

.r..,

c-

.~,,a-~

.c.... c *..... h ^. C ~..c..a2't.*

,."..i.

y

..J.' ' _' W.:.s c. y! a I ~.Ut II 68,... '. b. ',..

..,. j. 3 '. Cp/.6.)..bS+ 1., 'pa s.

6..,3... m.M.' - l.

. y.

_, \\

n^

W

.s t

.~ _..

........ ~.

6:.f ;. ',

.. '. ' ' ;. g... '. ;..

.l,..,.<-.,s.

it.**.t:. $. ~~?* **l;');. 'R. a - y. ' '.

  • E'

. ' ' %A..., k. ' 5 '

f' 1

..1..*.

.. ~,

s

.s.

w.

e

^

m

4 0

4 APPENDIX C PITTSBURGH TESTING LABORATORY CERTIFICATION REPORT 4

t O

]

O

i,

o 6

7ala 209 REY.

PITTSBURGH TESTING LABORATORY miae,g j.+.-

+..,

..,a.us..,....

.' c-q' \\,v PITTSBURGH, PENNA.

,, i

' '. k,

,1-as A Mutual enovectio e to cututs. vnc rusue ano ovest6was att naronts "E i iN ans suomesteco as vns conceocassas enortarv or cLarnum, amo autnon.rarion 5,

,. Iv.m /

rom ruotecareow or suavcweests. couctuseons on savnacts anone on nasaroemo eve arecats as atstavto esmosso own wnervsm arenowat.,

,. I

  • .;... 3,. f 8

1 g-

.s

,,,,. g h

  • J i

CRDER No.

t 3A 0 s..r-r <,,r' r. -

. L ABO R ATO RY NO. ' ~ ~' " " *

  • f

.s.

b' CUSTOMER NO.

b,*~-

D.y 2[h 196 7

'N"ON b*E E

  • b'-

'IRT CF TENSILE TEST OF 2e F0R ? :h': 9. C.. s. c.':i.:.n. : i._ _' m::_ _ _.T.?. w & _c & '.: 3la '- 1.4:Y. D.

m omicemat flELO Max:mun 73tLO trasitt stoucaTson atouction j

so. IN.

pouweg POUNDS (s.pga soTIN.

Lt.PERSO.lN.

IM

  • .lN..

or anca Paacrunt toao statscTN DESCRIPTION

  • ansa.

PER CENT PER CENT j

Jtz t sww c.

.:. 2...

loc. G=u,

(=: *, e....: e. %

e m,

.n i

F 3

.D s

.cc4-199'T 43 M 47/cc Zl?drol 239irej,. /$ - 9.gg 32,5 g N/3 Hf7 q

j ik.A L 4't.4 "r-CtAkw _

.,l346

. -. c.

. : :,.~~ :

27. of9 set

. (:.; e r :(. - W.:. J.r:'- !.

m ill. J +- Q { x~

1 l

i, o,y d i

.N9 4

Gk.6 b

' A s.! &&/

V

/ MN:w -

A >* 'n.

lrc* b1.. m b.bju

/C. O -

/

//

8 h

(3

. f.,

b 6 #

@,4 c.

w.

n o

PITT RGH rS P!G LAB 'ATORY k

1

l i

l O

t i

i APPENDIX D i

e i

i l.

RICHARD F. EISENBERG 1

MATERIAL CERTIFICATION REPORT i

i 4

4 I

O 1

J i

4 I

I I

f

!O l

l l

l

k RICHARD F. EISENBERG 26 summit Drive-1 Rochester, New York 14620 e

( ).

october 30, 1970 l

Mr. John Arthur j

Hoqhester oas & Electric Corp.

89 East Avenue Rochester, N.Y.

14604 l

Lear Mr. Arthur:

~

I In confirmation of my telephone conversations with j

you and. Fred Lupi concernin6 the broken studs from the Brookwood j

Plant, I am reporting the results of my examination and tests.

Initial examination of the fractured" surface of a i

broken stud revealed characteristics of a hard, brittle material that exhibited little ductility.

The fracture had the appearance of havin6 occurred progressively over a period of time, althou6h it was not typical of the characteristic fatique type of failure.

There were at least three points spaced around the circumference of the stud.that indicated points of crack initiation.

As i

the respective cracks progressed distinctive facets were formed from each of the sources.

1 l

Although I did not have'the opportunity of examinin6 i

the installation, it appears that the cause of failure can be O

'" "2*"'** *

'h* * "" "*'2 "

' 'h* 2" '2*2 hi h **"*** *"*

S i

to the tightenin6 of the nut on the stud and the vibrations in i

the installation caQain6 initiation and propa6ation of cracks in the brittle material.

Laboratory tests of a broken stud confirmed that the stud was too hard and with insufficient ductility and i

tou6hness for the application.

A comparison of test results of the broken stud, replacement studs and the specified j

properties for the studs ( ASTM A 490) are tabulated belows 1

Hard.

Yiald strength Tensile Elon6 Red. Area l

R

(.2 % Perm. Set)

Stren6th %/2 in.

i C

Psi.

Psi.

o l

Broken Stud i

1

)

2 3 45 -46 [5

> 159,000 249,000 11.6 45 5 217,000 Est.. 223,000 12.o' 49.o Replacement stud 1 39 (Surface) 145,800 158,000 11 7 49.2 2

35 (core)

.152,000 161,000 13. 2 46.2 l

3j 146,600 159 800 11 7 48.2 ASTM A 49D 32 -38

>130,000 150,000- lag, con 4o,o j

(])

Speo.

14,o l

It appears that the replacement bolts should be such more satisfact'ory for the application.

Very truly yours, i

s'l O)U YI**"

/ fi

.-,. -- - - - - L --

1 O

i I

.i l

APPENDIX E i.

1 I

REVISED DESIGN OF i

i BROIIN ANCHOR BOLT 1

i i

I 1

1 1

l!O I

I.

t t

+9 q

1 2

j i

2 O

4 1

I t

C.0CHESTE3 GAS AND ELECTCic C;RPORATl'N

=

43 33

[

g PAGE OF OATE:

ENG. OEPT.

STATION:

fg,/

q g

b DE BYs N

JOB:

p,wna m

s;

> F ( g u y, h

f AT b

m n

l._<

~<

9 e

w

_<u

, W S

1

/

)

f

[

g"h weiJsJ})

a 1

AN l

FAr%i

~

w%

ac;g % eIJs unm n o.s t s'y Z4 "p/pte s W

d w

.?IWFl'/2%

?

&w z",l.d<

r

/\\

3 " (fof Pj"h weld er.sid< af h t w lg "jo/ir !c)

~ Ex.jg" plate t

e

Ri HESTER CAS AND ELECTRIC C'RPORATION 42 33

/g-[_ %

PAGE OF ENG. DEPT.

STATION:

DATE:

E

~ Al,,, &&

k.e +- S.G 's

~cc ":

"=

l%"(1) 8%4/,c4 j'/fo As/t m in. ult., dc

/sa d tes wo*

desip Asea l

,7 X /P-5000 =

/.A C 500'*

F = l2e sus *

~

direc t /cis' o n we /d'

_F V = EM:(ruid,

_ /pg 5oo __ gggggg.g

~

ay Loeat-e C. 6 c. ( W.cf

(* C 8 ha qf we$

O n : k A n ('tX5%2.5)+ (91ss) 7a~

3'O, G //

p.y ay NN wiL tbic bl0 =. Sa95" e=

M =

f~ e

=

{p t 5osy. 3p.rs) = st2,70o z. isc.

f fIc/ _ (9270U34

~

3~

  • I

<-- /*sla r /%. o f Toe rtia y =.2~x +ry

~(#155l5)*(Y&?+fp?-(sjf/X)

(ig'(sy..sfggp,5)'

4 J= 29,5 + J/ O.0,'_- l o. %2 1-q/, G7 + go +- 3 f.25

' ~ '

3 = /50 E1

CODIESTER CAS AND ELECTQlc CORPERATION 4

/

gj

[ j - f.,

g ENG. DEPT.

STATION:

DATE:

PAGE F

/,s ( d~f d

S

,h

,8 T= bO 7ll'f )= g 5o*/.;,J.g a y G G w.J L t

=

7t

/

ewo -e 5320 = 6 250%f

=

an lf " h w eed vi!e t te tA< umfshss?

fi x.767 x fr, =6Aso

~

~

~

bv =

l 7 6 S D p <'

andAm 4

> AbaWe Ws r h, n, Stress O4E M < c>,

1bb7c 1.s 3 4 /sc spe 7 At / cast

/Vodopsi l* f h W L lclS c7 o'-e o u c? $c /s y $cciE!en l' c7 y-c c._,,M ue_

&s ea e f,.cic/e o f nc w Jf "(4, t'z-on m us t d'ualsp 'f ne w J{"ph h-sh ess in

& "b we/c! Le t ween

//a nye

+tep6 T= fa'=' @fyo C, 7o7yg f = V 1-T= yoe + sa eo.- s osg%)

t

};"/h

'/" ys e 7 vie to w" o f 4 " L\\

y x s ose :: a (.vsX Goed

/*

9 :=- 5: 3 'f A c A:, -- =p usc d

,3 " C D.. S I cl<

f I

L i

a 1

i i

APPENDIX F ii 1

4 JOSEPH T. RYERSON 1

CERTIFIED TEST REPORT i

f

.i 5j!O 1

1 4

r d

e 1

i d

j f

1 4

i f

a f

.g._

RYMRS'ON CBRTEFERD YBSY REPORT B

~

,,.c, m

y r

a It uuaEt CgwS ORDaI.uMau;Q

'^

Ett x

  • DOUs.D.T:3 0.'$ L FT.CO2 0'.HPCT.T. Tai r.;L mmmm d:.d b' q'+

~

09 UffR [P.CC 72 DOIC&fu DU YDIC 1hM 10/22/70 O'M3?h2 d d kCO3

}$

1 DESCntPTIOM OF IRfEntAL /.l4D spi 41WCATIO!4S t

~

  1. J/E ch' N3 3301-3/G".Es!0 lo/m

- @y t.

c g

CHEMICAL AIJALYSIS bq s.

HEAT NO.

CAttON MANO.

PHOS.

SULPflut ILICO NICKEL CHROME MOLY.

COPPER it.

ALUM,

, LEAD

'OTHER

'T'531

. k~t.

.07

.012

.05 97

.17 l

~

,3 w

1

[4 i

H MECilAtllCAl. PROPERTIES Al'D TESTS

~

HARDENAllLITY TEN 5fLE YlELD

% ELONGAilON REDUCilON HARDNESS SEND GRAIN EMS.! cot.

g -

PSI r$1._

Or AtEA v.

3 b,.g-

[.

ff&-

- fl4 -

9l_1910^O 11 Coo 19 bl,.6 311/ ire

, l-g MANUFACTU ttt OTHER MECHANICAL PROPERIBES AND TE5TS s.

6y i

IA S V m ETE 3I. d0:3 D N 1 ".

s.

.A.

-Y b'

t p

q DESCluPTIOff op MATERIAL At4D TPTciFICATIOU5 f3

~

![5 N.

r

.c w

m*f, CHEMICAL Al!ALYSIS

)

(

HEAT NO.

CAtlON MANG.

PHOS.

5UtPHut t'LICOP( NICKEL CHROME MOLY.

COPPER 13 ALUM.

LEAD,.. l' OTHER k.

y f, A m

I j,5 i '.

lD q

MECHANICAL PROPERTIES AI'D TESTS b

R.i EMS. con, HARDENAllLITY

. ' ltt YlELD

% ELONGATION t EDUC110N HARDNESS BEND

. GRAIN i1 y

P5i OF AttA v.

6p

(,d x

r.,

r.o

j fis-fis.

M ex

h MANUFACiuttt o

, ;}

OTHER MFCHANICAL PROP [ tiles AND TE5T5 t g r

).Q

~

i$

d' DESCRil TIOil OF MATERIAL Al4D SPECIF!CATIOl45 4*

R

, y, L,

0,1 CHEMICAL. A!4ALY51S CAtlON MANG.

PHOS.

$ULPH'Ut SittCON N'CKEL CHROME MotY.

COPPER 78.

ALUM.

LEAD OTHEt

,g

' gj HEAT NO.

u M:.s i@

MECilAI41 CAL PROPERTIES AI4D TESTS f7 D

TEN 5fLE YlELD

% ELONGAtlON R EDUCTION HARDNESS SEND GRAIN EMS.

COR.

HAtDENAtillfY h

i h{

D d

PSI P58 OF AREA %

p?

fis _

fis. -

&'q

  • c.

4 MANt'FACTUREt OTHER MECHANICAL PROPEtilES AND TE515 6

og cq h.

.d

=

+

v:

. THE ABOVE TESTS CONFORM TO THE REQUIREMENTS OF THE SPECIFICATIONS LISTED y

n.e n. vu.s.t., d.t. i.. er....,,.e n.F y'j THIS CERTIFICATE NOTARIZED ONLY WHEN REQUIRED

w. nu.6y.ui:fr

. '. l..-

, a Notary Public do hereby certify that d.e. vas:4 4 n or n. cr suing ni., n. d.i.,u.sei.y '

,T Nihis affidavit was subscribed and sworn to before rne by a duly authorized

'" '" '"f.wd la n. trona L.bustur.

l f.!cge of Joseph T. Ryerson & Son. Inc., this day Of JostPn' Y. aVS$ ort t. sor:.

It3 Nc.

I

,, <' d./ xLd. '/i./

Og <., /

!h A

Y COMu15510N EXPitES NOTARY PUBLIC AZ~.'aud Agent WV -

[$

'd /k h e.i n st r u.

..a.

u..,..s.............

,,,no., u,n,,o..

.n,...... /

e

,u....

(J ijuBL'PH l. IlYE.RSON & SON, INC.

. l f.,9, g.'.

. i,. terss..s s

i,f ca..suws a.i an.uss. saa rea*:sse.e p

. eines.un. M u.et +. wewavra smca.o e g.

j. *,

tout 220.29 3 nt at corrticHT test

.vii

. susiana,ms.

. suvise aius f

l..Y lp.,....' U. a...

.,. -..... :... r., s o. y.. +.usy..a~>

..7s

.,a...v..-.

,....sr a

+.;,. ;,. a, 6,y. u s,+ ; my, ;.. an g w.s s % v 'g +; p.: '49.;.

,.,.,.q, q.,~@. ;

e. x,w. m.,.. u

,_~,-.

l h

a O

I APPENDIX G PITTSBURGH TESTING LABORATORY a

CERTIFICATION REPORT-i ULTRASONIC INSPECTION OF BOLTS a

i O

i 1

(

i f

i r

O O

p 5

l i

l

[

---r,---.,,,,,__,_,,,,,,n..,,

-...,.-,,-n,.

,,n,,,,.

,-.n..,-,

-.... _,n

. --n-

. - - +-,,an..__,-,-,w

.-4..

,.m..,.E.....

[!@T"g%, PITTSBURGH TESTING LABOf4ATORY u.

..TA.m..NE.

5,

,f 850 POPLAR STREET, PITTSBURGH, PA.15220

p. o. so x...
  • UID AS A MUTUAL PROTECTION TO CLIENTS. THE PUBLIC AND OURSELVES. ALL REPORT.

f.

=.:. :,:,:=~.' N:::=:::=::,a:: ::R==

Oult REPORTS Is RESERVEO PENDING OUR W RITT E N APPROVAL. L*.DoRAToRY No.

ARE A CODE 4 52 TELEPHONE 92b4000

~

CUENT'3 No. Verbal REPORT Mr. Bob Koprowski

  1. 1 November 6, 1970 Report of a Ultrasonic Inspection of Bolts At Rochester Gas & E1ectric Company

~

Onterio Center Reported to 3 Rochester Gas & Electric Company Onterio-Center i

New York, New York On October 10, 1970 our inspector visited the maintenance shop of the Rochester Gas & Electric Company, Rochester, New York, New York to perform Ultrasonic Inspection of fifty.seven (57) 1 1/2" dia, bolts. These bolts were inspected from end to end and through the axis of the bolt where there were no threads.

Results:

No indications were found An Ultrasonic Inspection was also parformed on twenty (20) bolts in the Reactor Area at the Stabilizer Arms. Access could only be made from the end of these bolts.

Results: No Indiciations were found Calibration was made by using a full screen back reflection.

s Bquipment used was a Branson SOlA with a 2.25 MH longitudinal z

beam 1" dia., a light Oil Couplant was also used.

INSPBCIOR:

G.B. Maksin i

i PITTSBURGH TESTING LABORATORY p

W. H. Carnec, Manager O

Nondestructive Tests Department ec:3. Client,Attb: Mr. Koprowski I

maC

Pittsburgh Testing Laboratory Examination of Bolts on Pump Restraint l

O gy l'

d The installed bolts / studs were examined ft om.the exposed l

. e.urface at 2'l/4 and 5. 0 Mhz reference to a(200% of full scree g//

height end or back reflection and a reporting levebequivalen to 5% of the BR amplitude. The 5% of BR level, which represents

'f

! )e ' / y '

a 1/8 inch diameter (0. 0123 square inch) detection level near the far end of the bolt, was reported to be approximately 2 times the noise (threads) level noted.'

O m

O

_ _ _ _ _ _ _. _ _ _ _ _