ML20133B013

Requests Temporary Relief from ASME Boiler & Pressure Vessel Code Section XI Requirement IWA-5250,to Delay Repair of Weld on Safety Injection Recirculation Piping Until Next Outage of Sufficient Duration

ML20133B013
Person / Time
Site:	Calvert Cliffs
Issue date:	12/19/1996
From:	Cruse C BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20133B014	List: ML20133B013 ML20133B541
References
NUDOCS 9701020230
Download: ML20133B013 (17)

Text

TDQ

^

f2 4

CHAOLES H. CRtJSE Baltimore Gas and Electric Company Vice President Calven Cliffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410 495-4455 December 19,1996 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No.1; Docket No. 50-317 Request for Temporary Relief from ASME Boiler & Pressure Vessel Code Section XI Requirement 1WA-5250 Baltimore Gas and Electric Company requests temporary relief from American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI (1983 Edition), requirement IWA 5250, as allowed under 10 CFR 50.55a(a)(3)(i). We specifically request permission to delay the repair of a weld on the safety injection recirculation piping until the next outage of sufficient duration. The proposed alternative actions provide an acceptable level of quality and safety. In addition, compliance with this Code requirement would require the shutdown of Unit I to repair the piping. This results in hardship without compensatory quality or safety improvement.

I.

Campanent for Which ReliefIs Requested Temporary relief is requested for pipe segment 4"HC-231005. This section of safety injection piping is the common minimum flow recirculation piping for the Unit I high pressure safety injection pumps, low pressure safety injection pumps, and containment spray pumps. The recirculation piping provides a minimum flow from the pumps to the Refueling Water Tank to prevent pump overheating.

Under post-accident conditions, the line is isolated during containment sump recirculation to prevent radioactive contamination of the Refueling Water Tank. A small leak has been discovered in the vicinity of a piping support attachment weld in the Unit 1 Component Cooling Pump Room. The leak is occurring at the location of an original construction weld defect. The affected pipe segment is Class 2 and subject to the requirements of Section XI and Regulatory Guide 1.26.

A M' [ (

k l

n,mm~

9701020230 961219 PDR ADOCK 05000317 P

PDR'

f

1

' 4, Documpnt Control Desk December 19,1996 l

Page 2 i

II.

- Code Reauirements for Which ReliefIs Reauested ASME Boiler and Pressure Vessel Code Section XI (1983 Edition), requirement IWA-5250, states:

4.

"(a) The source ofleakages detected during the conduct of a system pressure test shall be located and evaluated by the Owner for corrective measures as follows:

... (2) repairs -or replacements of components shall be ' performed in accordance with IWA -4000 or IWA -7000, respectively."

c III.

Pronosed Alternative j

Instead of conducting a repair at this time, we propose to perform weekly visual examinations and trending to ensure that the leakage from the affected pipe segment weld does not

. significantly increase. We will also perform quarterly non-destructive examination of the defect to ensure no degradation of the weld or piping material in the vicinity of the defect. This

' provides appropriate safety assurance until Unit l's next outage of sufficient duration, at which time a Code repair will be made. These. compensatory actions are consistent with the recommendations contained in Generic Letter 90-05 (Guidance for Performing Temporary Non--

Code Repair of ASME Code Class 1,2, and 3 Piping).

IV.

Sunnartine Information i

A.

Sequence of Esents During housekeeping rounds on December 11,1996, evidence of a leak from the Unit I safety injection common recirculation piping was found. This evidence consisted of crystallized boric acid at the bottom of a horizontal pipe support, approximately three inches off of the floor (see Attachment I for the location of the leak). No active leakage (drops or stream of water) was found.

The affected pipe segment was initially determined to be operable based on the rate of j

leakage from the weld being imineasurably small, low stress levels at this location, nrobable flaw characteristics, and the location of the leak. The lack of significant leakage provides reasonable assurance that the weld is not substantially degraded.

Further degradation of this pipe segment will not prevent the safety injection pumps and containment spray pumps from accomplishing their design safety functions under post-accident conditions.

Additionally, the affected pipe segment is isolated during containment sump recirculation.

The flaw was examined by liquid penetrant and ultrasonic testing and determined to be a pin-hole weld defect. Liquid coming from the leak appears to evaporate faster than a single droplet can form. The defect was observed with a high pressure safety injection i

pump running and again with all pumps secured. No change in leakage was observed.

The pipe stresses at this location were evaluated by Design Engineering and determined to be well below the Code allowable.

e

i I-

• i.\\

t 1=D Docum:nt Control Desk '

December 19,1996 l

Page 3 i-Based on these observations, a determination was made that pipe segment 4"HC '

1005_ is able to perform its safety function. Therefore, the system was determined to be operable.

However, because of the identified leakage in the weld, Technical Specification Action Statement 3/4.4.10.b, " Structural Integrity of ASME Code Class 1, 2 & 3 Components," was entered. This Action Statement does not restrict continued power operation; however, should Unit I be shut down to Mode 5, this Action Statement j

would prevent restart until repair was made.

B.

Analysis The defect was examined using ultrasonic and liquid penetrant techniques. The penetrant examination revealed one rounded indication and no'other indications on the weld around the pipe support. Ultrasonic examination revealed an indication with no circumferential or axial dimension. We have determined that the leak was caused by a through-wall weld defect. The results of the analysis are contained in Attachments (2) and (3), respectively. Attachment (4) provides the flaw evaluation calculation and a summary of the pipe stress levels at the defect location. Our evaluation followed the guidelines and recommendations contained in Generic Letter 90-05. Based on the results of non-destructive examination and engineering analysis, we have determined that the defect is unlikely to grow under any circumstances. Therefore, it is concluded that the pin-hole size defect will have no effect on the ability of the pipe pressure boundary to i

fulfill its safety function. We intend to further evaluate this defect once the affected pipe segment is removed.

C.

Safety Sienificance The operability of the safety injection pump minimum flow recirculation piping ensures the high pressure safety injection, low pressure safety injection, and containment spray pumps have a minimum flow path to remove excessive pump heat. The pin hole in the affected pipe segment is currently leaking at an immeasurably small rate. Thus,-

flooding, spray, or loss of safety injection pump recirculation flow are not current concerns. Additionally, as shown in Attachment (1), the pipe segment is restrained above the defect by the pipe anchor and three inches below the defect by the floor grouting.

This provides restraint against pipe movement resulting in a stable configuration should degradation of the wcld or pipe occur.

He proposed compensatory actions include weekly visual examination trending, and quarterly non-destructive examination. The operability of the pipe segment will be re-evaluated in the event an increasing leakage trend is noted. The piping at the location of the defect remains structurally sound, and the calculated stresses at this location are low.

Additionally, we have concluded that there are no mechanisms which indicate the possibility for significant degradation of the weld. As described above, the pipe segment is restrained in such a manner that substantial cracking of the pipe would not result in pipe separation. Therefore, catastrophic failure of this line is not credible.

.'tio g

A Docum;nt Control Desk December 19,1996 Page 4 Even though failure of this line is not credible, the impact of such a failure has been reviewed. If this pipe were to catastrophically fail, the maximum expected flow out of the break is approximately 400 gpm. This flooding rate is well within the currently evaluated rate for this room (2852 gpm). A break at this location would result in some loss ofinventory from the Refueling Water Tank (capacity 400,000 gallons); however, at this flooding rate, this loss does not appear excessive.

In conclusion, the Safety Injection System remains capable of performing its design safety functions. Delaying the repair of this minor leak until as ' ate as the next Unit 1 refueling outage has no safety significance.

D.

Code-Reautrement Perf' rs===ca Im_ net o

n The repair of the weld requires that the safety injection pump recirculation line be isolated and drained. Therefore, Unit I would have to be shut down into Mode 5 while.

the repair is made. Currently, we expect the repair to require removal of the pipe segment and possible relocation of the pipe support.

We b:lieve the below compensatory actions provide an acceptable alternative until Unit 1 is in an outage of sufficient duration to accomplish the repair.

V.

Comne== tory Actia==

We will perform ultrasonic and liquid penetrant testing on a quarterly basis to verify no further degradation of the weld has occurred. Visual examination of the affected pipe segment will be performed weekly. The boric acid buildup will also be measured, cleaned, and trended weekly.

In the event of an increasing trend, the non-destructive examination frequency will be increased, and the operability of the pipe segment will be re-evaluated.

VI.

Implementation Schedule A.

Boric acid buildup measurement, trending, and visual examination - Weekly B.

Ultrasonic and liquid penetrant examination -Quarterly j

C.

Repair of the weld-Next Unit I shutdown of sufficient duration to Mode 5 (no later than spring 1998 outage) j SAFETY COMMITTEE REVIEW The proposed relief request has been reviewed by our Plant Operations and Safety Review Committee, and they have concluded that the proposed compensatory actions provide an acceptable level of quality and safety for the non-conforming pipe segment. In addition, they have concluded that compliance with the Code at this time would result in a hardship (plant shutdown) with no compensatory increase in the l

level of quality and safety.

... - = -.....

8-QA g

D Document Control Desk December 19,1996 Page5 In order to prevent any restart delay in the event Uni 1 is unexpectedly shut down, reliefis requested as soon as possible. Should you have questions regarding this matter, we will be pleased to discuss them with you.

Very truly yours, l/

gre -

&n P CllC/JPW/ dim Attachments: (1)

Simplified Drawing Showing Location of Weld Defect (2)

Ultrasonic Examination Results (3)

Liquid Penetrant Examination Results (4)

Flaw Evaluation Calculation ec:

D. A. Brune, Esquire H. J. Miller, NRC l

J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R.1. McLean, DNR 1

A. W. Dromerick, NRC J. II. Walter, PSC 7

i i

l l

x 1

ATTACHMENT (1) l SIMPLIFIED DRAWING SHOWING LOCATING OF WELD DEFECT Baltimore Gas and Electric Company i

December 19,1996

DHIAJHEttNa YdfH-30td

.c

..s u.

Y l(6 21-/0 W A3'l

~

Fl0M AlbER a

/.

/

i V

e R oo/L Pearorr/w

% is..nsn

/t

-r/ abed /Aff-B1ifbn7DEdrhao /9tssx. 3 g"faygosecyc

?

is

. Su ATTACHMENT (2)

+

i 4

4 1

ULTRASONIC EXAMINATION RESULTS i

}

i 1

1 Baltimore Gas and Electric Company December 19,1996

Iff+A h + t prety f,'

COLOR CONTRAST SECTION XI LIQUID PENETRANT NDE-5210-CC REV.O EXAMINATION LIQUID PENETRANT EXAMINATION RECORD NDE Numbcr:

96 - PT 301 LTP No.: NA Exam Date:

12/13/96 MWO No: 1199606554 R & R No: NA IR No: NA FCR No: NA Ex: miner:

EDDIE HOUSTON Level: II Initials:

Ex: miner:

NA Level: NA Initials: NA Campoutnt/ Weld ID 4-IIC-23-1005 A37 Weld Lg: 16" WO:.125" 4

Loc;tlIn:

5' AUX BLDG COMPONENTCOOLING ROOM Sys No: 052 LO: 11.8125" Extent of Exam: WELD & BASE MATERIAL 1" ON EITHER SIDE OF WELD Miterial: STAINLESS STEEL MaterialTemp:

83 Degrees F Surface Condition Acceptalile i

VT Examination Acceptable: NA Initials: NA Date:

NA Procedure No: NA Rev: NA Color Contrast Pentetrant Type:

Solvent Removable Pre-Cleaner:

Penetrant:

Remover:

Developer:

Type DR60 DP51 DR60 D100 Bitch No.

524-G4 217F47 524-04 517-H6 Step Times Completed: 2315 Time Applied: 2320 Time Removal 2335 Time Applied: 2340 Completed:

Time Rem 2330 Time Read: 2350 No Indications Found unless Noted Below Indication No.

L W

Location Type Size Notes 1

1/16" 1/16" ROUNDED 1/16" SEE REMARKS 2

Serial Number:

Cal Due Date:

Model:

DigitalThermometer:

873F 20Y05068 12/16/96 Remarks: A LEAK WAS IDENTIFIED IN Tile AREA OF TiiE BOX ANCllOR A37 TilAT IS ATTACIIED TO 4"-IIC 23-1005. A PT EXAMINATION OF ALL WELDS ASSOCIATED WITilTilE ANCllOR WAS PERFORMED AFTER REMOVAL OF GROUT AND PAINT. TliE RESULTS OF Tile EXAMINATION WAS AS FOLLOWS: (1). A 1/16" DIAMETER INDICATION WAS DETECTED (BLEED OUT 1/8*) IN Tile LOWER PLATE TO PIPE WELD (TOE). SEE DATA SilEET NO.96-PT-t-301-C FOR LOCATION. Tills EXAMINATION WAS SUPPLEMENTED WITil A VOLUMETRIC (UT) FLAW EXAMINATION FOR INDICATION CONFIRMATION AND PROFILE. REPORT NO. 96-UT 1585.

Number of Attached Data Sheets: 3 Examination Attachment No: NA Prepared By:

[gj Certification Level:

gy' Date: g,/g'-g Reviewed By:

/.

g Certification Level:

Date:

Date:

Received By:(Print)

Signature:

p j

k bd

)

• , t' g

_m w

q s

t I. ' : -

.s s., -

s[O

",, a a, y

a g

6 a

g-

.2 e s so

'. z g',$

f y : '>l

.h

. E. '.

\\\\'\\

00

%%4

\\

z 8

a JL y 3.A i

\\\\

\\

o l-W

?

D./

\\,

/.s-

@., l/-pt' i

s., x,.

2

~%

g

,j

,5 m

s r

s, a

N

(

w m

.JE-;o R,, *9 %

A 3

er ac./-sois a

g

.g'

?

h

?

a b

U V

u i

ii i E !

i i

d

//

F.' fi/

~ &,f,'<

5 4

g< f':.'r '*

b.

l R

C E

3

)

.r-o*

r.fi 9

r y

y>

0 v

3 F

SE '

a W

$ f

p A

.3 s sc-i-ioir c

?*

s'p g

y*

a\\

y I

G g y, g

"Ei.$, t e

,P i

d k @t.5 E

N x.I

\\

l' $s;6 Y.

H N

E- :

.,f s

• p.

.e' s ha s

4

-e-o

.s ro 4\\

S', @

o

/i O!

~

_ a%

E_

i-.

I P

o

.) g

< <c-r roef

%' g-3

?\\ v 3

i 0a-s y

i l

=

o 4

T

~

~~~N.

hS k.

./

f =, f.4 Y W

I 9 /_,

I 5*

{fQ

'5

• • "c r'-soor @

@ *n;y%

• Q" f,f.;'

~

rn f I

/.+ 8 @_4 II

'>/

s.1 sd I

0>

f y'

%V

• i

')

89-'

't %

• t b.-

s

• H g

.s&)

L

,s

(

I a 2

~

s

_p..

o

~

g

?

f.gV.~,s,e, A?

&r,

• • "C-23-/003 C

i g

4 e,

t

'3

._, e

.y p

.e p~;

O M

s;t s i 6

?

ea 18 S

Q~ B t'

/=

c c

4

'EE i 4

+3 qE m

~=

M.,

., h>

.y p

s o

s g

e V

w n

a:

8 e

eP

<l cf.

w

's sN,..

61

+

a c

0

~ c t y

,)

E 5$

[jgW i

4 N

. x

,1 t

w...-

l

, i,:s: i. s i..

e h

h Nh h

UO9 hlf 853 s%jf3 p<

,a

.a a

~,

O g s EE9

-- ~

y i

i,;

9~

1 E5A" A5:5 116 35ER = ped 8 s.=:.5pe3=5 dijm

==g b

s,

! Th. -

• 5 5 N ~s E w

- =~

4 -~

i 3

E f, * " $. s

~k 55' 4

er $$g e-8 u

-n sum p,

_a lo a

o 8

$8 ' i! 1 $ $ ' E i ' [

-::.K EIS 1

00

-r.

8E Ugg e ;p g

,g p Ds 25 ;s

< w-s ;g x

e

h. -

=

J gP a

on

• g p-z i s 2

n m a

v{

ge.

ia

. lag jg o z A

4;-

iN A

t 7"

/

r is_

p n%

Em n

y p8 ot

/

pf<,

g n

2,C o

ta pI to Rn 2

E O

a?

Ag

/

R ag i$

Ot

• ~

'f

?

/

M*Re KR W*-

M En

-< o2

$ ' gbt 6

p m a 5

,a g

M m

,0 aa g 33{E E

4 uMC w

l l

j a3Tioungga da50 j

-c.

o n

k

1. f 3$ h

\\

/

4 '..

l GlT2MZ 317 DnrySWWA61G'&nt;.x><iz

'!!. ET.LLXG C.'l.

care nuwose orPARTMENT cusvowen

~~

O 8D20-501

, gD * 'f*,',,y f,

//r epoen on cour, u,,

Joo NAwe

_,C.}L'v'EP.T CLIF.?S ITJIT_jg, _

,gg,,,

h)O

'f

%z),Y

. i.z:,.

(

p.,

Nj d[#M7,2.,)g z 4ci.77. son)

N y------

'y k

a, rn

\\

. _ L J

g ~,e.

\\

\\

l

.

• 4 % A W*

~

QD

\\

s sa m ma

95. m y g g kf

&_CWAttfy cogi.

v

@ ' W r,",::-~~

'm; muw

'A J. -- - -/r, enoccoune p e rMn *.

1 i

w.

t WELD R0D CftA l

.g.

E' PH_ @ PW HT l

C, l

l

-[-~,

,)

'=c:>--- fd E--

IN

'd, y i M h \\.

l i

n.

(

INSP.

No h:

y

<h N $'I class

'.g Q j

j i

j i

.N t

q, r

. ou e._

y.:.

W b

\\

\\

{.

gN..

u u

3 isai X

/

N

.(

N w!"LbtNo & QUALITY cont.

I v

azo e.c o.n-j (f.'.

f

%--yygy,w.__

pgnegaggg gq.gp y {

)

^ 4 G5 ? *KY g

c.s. -

M-y i

~

.o

~

o '-I4 6 TtGO 2CF l

No rd":

WELD RO3 f.h s

f s r 1s,c.+- 7.e,v r r.s 5.%

p::

S-?-$f h tw Mt L"'

l GIDT @

3 I.

.

• LOCAT&ON Pl.AN-We r ew A-A.

m, s _,,o q,

(

MATERIAL.S AND OPERAT! OMS g,7 g ggg;s.. 3M "1" -

PIPE ANCJ40R CONSISTIMG' OF 6M~

Abficated S.S. r MSTM A' 204 TP 304) tube as detai?ed chovo 1

1 g

TM-lO4 shon weld tot

'7 rabricated S.S. -(ASTM A 204 TP 304) ttWo uer detai.1 *A" TU-19 7.

_phoa wold-to -

_2 3

Pinte as det. above " TW-2iv WMDWE DR AWW9 Drut*\\.#

1 1

i18.p,, % -

• L sundlo &Jari-

!%rk: 4" HC-23-10CS-A3'1 M

a

' U "" "N-NE l

Eb "#42 WP' 1 *PI I ut L

i peu ase um

[

4 1======== = -a i

J V E'. ]O MUTE'4,Qiff.C.WM.

EJ -\\st I _I I-w I LJ '1 1 praimenTa m:1n

_ _7__

7 API'LYfG567

~'

- gy. s.J Os. E,..

J-~.,~., g_yf. m

=

a rau r. a r. rw%#9e A L'AEM-T '

/

-r -r r,

_y _

m

. pre.qq }f*VJ'

- JW_1

" M J2"!S'N'*H

_ _.f,:

al. Anm.V%!%#Rv w-

-ten *=P maga rh Eu

_ r f r -- _ - --

t

"..co - u m.= ep.

&w. _

( \\00 p,pe M T'92 *

.

• 1 ".h Q.E.5,, M QfE*.'.$ ?

~

sketc.4 wo. g[g ricv.'

r mar. onwo. nos.

,.,,.yo,

. *Anx no.--,,

siact

,....m.

DOCUMENT NO. 12600-7089 hggLj$

l 9

h,M N S N R' '

l:.?',,i'7,r*.c

.@ N"

'l,

.. A:

g.

MrWWFP3erra

'b

,.u V-/(6 ?J-/00f A39 E

t I

l Ae>De i

/, =

J

/

i J

n 3.-

ll.tt gg

.\\

Pereresria

% a ns~

1kbid /Aff- &iTbH1dddF&&'D AHbA. dl/4"RetWdQ/A u

f.

,y

. r.

4 ',-

NrTACHMENT (3)

LIQUID PENETRANT EXAMINATION RESULTS i

Baltimore Gas and Electric Company December 19,1996

_.. _.,..... ~,

mg 3

(,

DATA COVER SHEET p ~,, i a y CALVERT CLIFFS UNIT //1 PROCEDURE NO. P34co15 REV.

4-PAGE OF 4-COMPONENT / SYSTEM + - # c - 2 3 - e o,3 e.3,/sz M.O. NO. i119 c o c 5 5 4 ISO / DRAWING NO. z 51 - 21 REV. o NDE NO. 9 c-ur-/-575 COUPLANT BATCII SONOTRACE 40 # o9 si o 4 EXAM. ITEM _ f - u c - 2 5 - / o o 5 A 5y THERMOMETER S/N 7-i 3 c 7 y c LTP NO.

ev /M COMPONENT TEMPERATURE - 7o

• F SCAN V 5

• 9-7 /

EXAMINATION GEOMETRIC RECORDABLE EVALUATION SCAN dB c ?

COMPLETE INDICATIONS INDICATIONS

"/g YES NO YES NO YES NO ACCEPT REJECT O'

1

=

XX;X%XXXX5-s' X

>C REMARKS:

4S*E xMn P t r<

F o nas e A7 full V

w I r s, io y, io tz e i. L

/V o

c. vt or c sc.

/

cr s <. x vi e wt

,sL' o Y r a E x n m inor 3co*

,4 es o s. o s-S e f t' o et r SCAN

1. - S

• EXAMINATION GEOMETRIC RECORDABLE EVALUATION SCAN dIl 5 7. 6 COMPLETE INDICATIONS INDICATIONS O'

1 YES NO YES NO YES NO ACCEPT REJECT

=

XXX/* X XX

~<'X X

REMARKS:

YS" E * * **'

/* ! '* ' " * * *

/1 Y VN k"Y'*

5 l'

• T / " O " ' ' ' "

/"

At is e n or L c w/t

,,v o e t ><. e ve r r n c *~ rix e L / ~ s rs, 7o7 r1 o c.

1 SCAN 7o EXAMINATION GEOMETRIC RECORDABLE EVALUATION h CAN dB C 1. C S

COMPLETE INDICATIONS INDICATIONS 1*

1 YES NO YES NO YES NO ACLEPT REJECT

=

zi/%/' '><' M X:A' X

%' J r

REMARNS:

V t d ' F.

S !' 'r

' " " ' ' *r r s, ~

ga v Esnniweg A n r,,

fcm As o

c. n. s/ e lc

/w u s e erio~)

w o r r e, r rt n e ic,,

a SCAN EXAMINATION GEOMETRIC RECvKDABI.E EVALUATION SCAN dll COMPLETE INDICATIONS INDICATIONS YES NO YES NO YES NO ACCEPT REJE [

O' 1

=

REMARKS:

/

A

./

EXA 11NERS:

1 /3 #/ FA.

LEVEL rr(- DATE / 2 - / F -7 c 2

LEVEL -h DATE

~/e 1

I LEVEL T DATE //// M 2

LEVEL DATE

P n E 'i ~2"d F 4-

• g

'..t.

4 t.

NDE NUMBER 96-UT-1-585 MO NUMBER I199606554 COMPONENT 4-IIC-23-1005 A37 UT EXAMINATION liAS BEEN PERFORMED ON TIIE REPORTED LEAK ON TIIE ATTACIIMENT WELD. THIS INDICATION ON TIIE SURFACE IS APPROXIMATELY 1/16 INCH DIAMETER AND IS LOCATT D ON TIIE BOTTOM TOE OF TIIE WELD.

UT EXAMINATION WAS PERFORMED TO DETERMINE IF THIS LEAK IS CAUSED BY A CRACKING.

A 45 AND A 70 DEGREE EXAM WAS PERFORMED. THESE EXAMS WERE PERFORMED BY VARIOUS TECIINIQUES. THREE SEPARATE EXAMINATIONS WERE PERFORMED AND ALL EXAMS DID NOT DETECT ANY CRACK INDICATIONS.

i TilERE IS A UT SPOT INDICATION IN TIIE AREA OF TIIE LEAK. TlilS INDICATION IIAS NO CIRCUMFERENTIAL LENGTH AS DETERMINED BY UT. Tills INDICATION COULD BE CAUSED l' A PIT ClN TIIE ID, BUT TIIERE IS NO REASON TO CLASSIFY THIS AS A CRACK.

I IT IS VERY DIFFICULT TO DETECT, BUT IT IS REPEATABLE. THIS INDICATION IS MOST DETECTABLE ON TIIE T111RD LEG WITH A 45 DEG VEE AND ONE HALF CALIBRATION..

O F-BILL DOWNS 1

LTT lli 12-14-96

a -> = M ~ M 4 L M,1 p A g 5 o I 4 A

DATA SHEET

.. t ILVERT CLIFFS. UNIT # I

? AGE J

OF 4

PROCEDURE NO.

P5aco/S REV.

f-ME 140.

'1 C - u 7 S VS INSTRUMENT SETTINGS SEARCH UNIT CALIBRATION BLOCK MANUFACTURE 5 o wec ANGLE 4-5

• MODE 5 N e a n CALIBRATION BLOCK NO.

,MODEL i3G FIXTURING L o c o r a v s e s-a C cU - /o SERIAL NO. / oo P t-SIZE & SHAPE //e * / /t e * - o BLOCK TEMP. 7 e'. 5

• F VEL, / 2 : In/ps DELAY.2 3 7 in FREQUENCY S MHz THERM. S/N T/3c?rc

. RANGE. F in REP. RATE 2 /<#c SERIAL NO.

c++o7 CAL BLK. "T". / e. 2 INCHES

!PUIEER/ DAMPING / o * / r *

• BRAND /4 bA CRT CALIBRATED IN M E rse FREQ. 6 MHz FILTER /

MEASURED ANGLE P5 e

p g r4

.M!D'4

(* E REJECT o r r-CABLE LENGTH & TYPE C '

EACH MAJOR SCREEN DIVISION GAU'v4n. /, 7. / b rt. 4 4 gyc-mo EQUAIE =

OS COUPLANT BRANDS o-, re..e e, REMARKS c #z. is t,, A COUPLANT BATCH o i 3 i o 4-o<ta e-T*

v s e s's Y i i " s a n-e a r.

INSTR. LINEARTIY CAL, CALIBRATION AMPLITUDE 0'

AXIAL CIRC HIGH LOW HIGH LOW d

! 1 100 to 6

50 25 2

90 45 7

40 2e DAC PLOT 3

80 40 8

30 s5 1 4 70 35 9

20 to loo y 5

60 3e \\\\

\\

99 3 t*

SV 4 x

x AMPL. CONTROL 7o w LINEARITY 60 %

' INTIAL dB RESULTS 80

-6 3f 50 %

80

-12 2o a.3 40

+6 yo 20

+12 7p 30 %

20*4 10 %

CAL. CIIECKS TIME

.I t

~~

i INITIAL CAL o 3i o o

1 2

3

',4 5

6

,-[

8 9

to INTERMEDIATE

/

INTERMEDIATE T/a REMARKS

/ o

/t o e <- A o ru 5 rro 7o 2 i o y, p 5 INTERMEDIATE /

FINAL CAL.

o s' c o E. o r E E w n ou AsSe u$ts y**

w e rg,

$ $ o.r t s e s r y e, 50 7 "o'/. c 'J",, - s r,c,,, t - r S r r r /w,

W EXAMINERS:

43 h V-m_

LEVEL IE DATE / z - / 4 - 9 6 ev / M LEVEL -/e DATE

- /e LEVEL SL' DATE MIM/E LEVEL DATE,_

- -winnwer www2 y

DATA SHEET NA44

lbXLVERT, CLIFFS UNIT # 2

[lPAGE F

OF t

PROCEDURE NO. 65A/ool5 REV. #

iNDE NO.

'1 c - u r - t-T T S INSTRUMENT SETTINGS SEARCH UNIT CALIBRATION BLOCK MANUFACJURE SbraleV ANGLE

• MODE CALIBRATIO BLOCK NO.

MODEL Oc, Hic 136 FIXTUR G

/uc$ e V OO #

SERIALNO. /008/-

SIZE & SHAPE.26" Reg BLOCK TEMP. 77

• F j I VEL,/22-in/ s DELAY. /50 in FREQUENCY

.5 MHz THERM. S/N % 3 L 49/.

l RANGE /. 00 in REP. RATE 2k SERIAL NO.

l.4/4'o *7 CAL BLK. "T"

./34 INCHES l1 PUIEER/ DAMPING /00mM BRAND A'AA CRIC LIlIRA DNLeIes oi 7 REQ. 4 M Iz FILTER JL e'll d MEASURED ANGLE #/A MODE PdisnEcmo REJECT CABIf LENGTH & TYPE

(,

EACH MAJOR SCREEN DIVISION

)1 GAIN W851.4 / ',b' d I.6 K/, f 74/L)

EQUALS =

, /d "

COUPLANT B'RANIlbub e 40 REMARKS COUPLANT BATCH 4

INSTR. LINEARITY CAL.

CALIBRATION l

AMPLITUDE o.

axial CIRC IBGli LOW IBGH LOW

^

1 100 So 6

50 2*

2 90 er 7

40 2*

DAC PLOT E

3 80 40 8

30 i 5 j

4 70 35 9

20 ta 100 Y 5

60 3e \\\\\\

90 %

J 1

s/

rn 80 %

4 y

AMPL. CONTROL 70 %

j LINEARITY

\\

60 %

\\

INTIAL dB RESULTS 80

-6 3?

50 */.

j 80

-12 2*

40 %

40

+6 f.

N 20

+12 77 30 %

20 %

1h 1

CAL. CIIECKS TIME 30 %

g 45' 1

INITIAL CAL

// 24 I

o I

2 4

f 6

7 8

9 to l

INTERMEDIATE

^>/A xb eb

_Ib INTERMEDIATE M'A REMARKS

/

INTERMEDIATE N/A Fxam t r s f an m e e

-r e o r rea mier l k FINAL CAL.

/2/5

- If irna

• ~

AT w #ME#V Whe To e caus so e, y enocx

~o 4

4 j EXAMINERS:

[ 1 ' A J4P-~O-.<._

LEVEL 771-DATE

/ 2 - / 7 'r e 2

1. /A LEVEL

'e DATE e/w

/2//'/b L EVEL _22I' DATE 2

LEVEL DATE

.