Text

J. M. Farley Unit 2, Inservice Inspection Report, Refueling 15, Interval 3, Period 1, Outage 1, Td Certs
	ML030640647
Person / Time
Site:	Farley
Issue date:	01/21/2003
From:	; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	NL-03-0167
	Download: ML030640647 (160)
	v • d • e

TD Certs.

J. M. FARLEY UNIT 2 RF-15 ULTRASONIC EQUIPMENT (TRANSDUCERS)

SERIAL NO.

SIZE FREQUENCY MANUFACTURER 00-1158 2(8x14) 2.00 MHz RTD 00-1159 2(8x14) 2.00 MHz RTD 008NXR 1.000" 1.00 MHz KRAUTKRAMER 008NXV 1.000" 1.00 MHz KRAUTKRAMER 0094KWV 1.000" 2.25 MHz AEROTECH 009TNR 0.500" 2.25 MHz AEROTECH 0OB6PH 0.250" 5.00 MHz AEROTECH OODRRJ 1.000" 2.25 MHz KRAUTKRAMER OODRRP 1.000" 2.25 MHz KRAUTKRAMER OOTD6F 0.375" 2.25 MHz KRAUTKRAMER OOTD6H 0.375" 2.25 MHz KRAUTKRAMER OOTKAMN 1.000" 2.25 MHz KRAUTKRAMER 239864 0.500" 10.0 MHz PANAMETRICS 267694 0.5"xl.0" 2.25 MHz PANAMETRICS 267701 0.5"xl.0" 2.25 MHz PANAMETRICS 276054 0.5"xl.0" 2.25 MHz PANAMETRICS E10606 0.500" 5.00 MHz KRAUTKRAMER F14920SP 0.750" 2.25 MHz AEROTECH G03136 1.000" 2.25 MHz AEROTECH G19804(SP) 1.000" 2.25 MHz AEROTECH L30469 0.500" 2.25 MHz KRAUTKRAMER 1

4-4

-t 1-4 4

4-4 4

4-4 J

4-4 4

4-4 I

1-4 4

4-4 4

4-1

.1-4

Equipment Probe

1. Spectrum Analyser Make : Hewlett Packard Type: HP 4195A

2. Oscilloscoop Make: Hewlett Packard Type: HP 54501A

3. Ultrasonic Analyser Make : Panametrics Type: PA 5052UA Energy: Z/ ; RcvrAtten',il+ e dB; Gain 40 dB; Damping: 50 Q Cable 2 meter Coax RG 174/U 50,

I Wave form i

Measurement with flat probe shoe 8: REF 03 (non o MKR MA r 2 067 500.000 F

-35 169 IRwlz t

f = 11/t Spectrum (dB)

Spectrum (Volt)

!,rz da I

MAG,,

STM DiV START 500 000.000 Hz

-- !0.0 10.00 STOP 10 000 000.000 Hz RBAt:

3 KH-z ST: 8.20 sac RANGE" R-10. T-Odcrm 00-115, SPECTRUM Math A: REF B REF J MKR 532 500.000 Hz 3.994m 0.000 AMAG 13.5300P V

(10 08MM 00 0 000 DMI t Dm)I5-m--ADa DIV CENTER 2 051 464.545 Hz i0.00 SPAN 3 000 000.000 HZ KHz ST:2.53 sec RANGE:R-IC.T-OdBm Centre Frequency :4f/MHz Band Width at -3dB

//*, S.1 MHz

.J-OSu s -9 23 x

x mm (LxWxH)

Style 1 Manual LI Mechanised Conn. M] Lemo-00 IP L7/lLmm on R=.5W' mm WD i*mm Reference Block Z]1 Aust, -5750 m/s Long

. 3150 mls Trans LI Steel. -5950 mrs Long

-3230 m/s Trans El CD Radius Block L

-IP.

-/

0]25rnrn

[

50 mm Radius LI GO rnm Z) Bac* Wall 0° L

r

~

H T

Thickness mm rI Notch Notch Depth 1 mm Rontgen Technische Dienst bv Probe Department Frequency Spectrum Data Sheet

-7Wter-a-NL - Te Ne.,,erfancs Measured by D

Date SPECTRUý A: REF 3

100 4

BTH 0.000 RBW:

3 00-1158 I

RTD 00-1158 Long Wave 450 TRL 2-A ust 2(8x 14)

SA 30 FS-30

-1L.00 0.000 I

dHm I f

-35.3731

-damF Si VAi

.,+/-k I

I I

i Spectrum (dB)

I I

O:V START 500

!O.00 STOP iO 000 KHZ ST: 5.20 sac RANGESR-000.000 Hz 000.00o Hz 10, T-Odgm Spectrum (Volt)

MI Radius Block

--- L p

1Pe Thickness mm 0 Notch L

Cr J-33 Notch Depth I rmm Notch Depth 1 mm

-Rontgen Technische Dienst bv Probe Department Frequency Spectrum Data Sheet S=:~'-cam. NL - -"

Netre,lancs MAS MAG BTM

-1!0.0 RBa:

3 00-1!59 BTM

0. ý00 RBN:

3 00-1159 Equipment Probe RTD

1. Spectrum Analyser Make: Hewlett Packard Type: HP 4195A 00-Ln59 Long. Wave

2. Oscilloscoop Make : Hewlett Packard Type: HP 54501A 600 TRL 2-Autvt

3. Ultrasonic Analyser Make : Panametrics Type: PA 5052UA 2(Iv14)

Energy-RcvrAtten:/le+ 4 dB; Gain 40 dB; Damping: 50.D SA 20 FS-30 Cable 2 meter Coax RG 174/U 50Dq

' **6*Wave form-Lus r-23 x

x mm (LxWxH)

Style A Manual Cl Mechanised i~g lll

~

l it Conn. X) Lemo-00 1=

ilt iP i/iron on R=,*,d mm MEMO_

i l=

t WD..,2*mm inEEi i Reference Block

'*--"--'='--"*""*

"..ii.

[]

Aust,-70 rn/s Long 20.5O US25.5150 us30-066 US A st.-3150 m/s Trans Measurement with flat probe shoe

[iSteel, -5950 m/s Long SPECTRUM A:REF B:REF c MKR 2 043 750.000 Hz, leasured o%,

C ate'J/*

DIV CENTER 2 0.46 304.377 Hz 1O.OO SPAN 3 000 000.000 Hz KHz ST: 2.53 sec RANGE: R-10.T-OdBm Centre Freouency A.,( 'S-MHz Band Width at -3dB *.ý,,

1'!MHz I

II I

I ni'

)L*.

LI

ýýV r_ I I ar I t I IUN Transducer Description *W, B IOtIL/i S/N 008oN).,

NoilF Nominal Freq {-'O MHz Element Size 1.0" Test Setup (JU--A-q I I"IP tsý-J' Relative Sensitivity Energy Setting Impedance Setting Inspector ajD dB Date 3"_3_"_-)?

Cr 4

E e

nu3I r-UL;U*e U[r A

B II:

Ill The real time waveform shown in the photo above-is the first return echo from a reflector selected with respect to transducer type. All contact (wearplate and dual) transducers are tested on a flat steel (4340) plate while epoxy-faced qr wave transducers are tested on a flat polymer block. Delay fingertip removable (Style DFR) transducers are tested the tip of the delay line. Nonfocused immersion transducers are tested in water over a flat stainless steel plate using a water path as specified above Focused immersion transducers are tested the same as nonfocused transducers except that the water path used is equal to the actual focal length.

Using an AEROTECH Ultrasonic Transducer Analyzer, Model UTA-4, and Tektronix 7L12 Frequency Spectrum Analyzer in a 7704A Mainframe, the real time waveform, UTA-4 gate signal, and the frequency spectrum of the gated signal are simultaneously displayed and photographed Using the linear attenuator in the UTA-4 receiver, the amplitude of the real time waveform is adjusted to six centimeter amplitude (+/- 1 dB) on the CRT. With the vertical calibration of Trace II fixed 100 Millivolts per division, the amount of attenuation used provides a relative sensitivity rating for all transducers certified by Krautkramer Branson.

Real Time Waveform - Trace II Screen writing figures A and F provide the vertical and horizontal screen calibration respectively for Trace II.

Gate Marker - Trace I Screen wnting figure C provides the vertical amplitude of the gate marker and is an inconsequential figure The honzontal calibration for Trace I is the same as that for Trace I1. The portion of Trace I1 that falls within the gate time period is the signal fed to the frequency spectrum analyzer.

Frequency Spectrum - Trace Ill Screen writing figure E provides the horizontal calibration for Trace I1l.

Figures B and D show the spectrum

'zer's attenuator and resolution settings respectively.

Krautkramer Branson P.O. Box 350 Lewistown, PA 17044 r

""' X,2_ 1 - 03B.7 01 C

D E

F (S

%'J-

' -- r- % % -' -C I Ir I i

L, - I I U l1'4 Transducer Description -SWS* 6

.OMHZ./ '

A

"'N 2~9io§~. c~ S/N_

I'- Nominal Freq 1,O MHz Element Size I.d I

Test Setup LU1T -A 4 I "PLý_

Relative Sensitivity

__________d13 Energy Setting Impedance Setting

~,..~

Inspector

a.

Date 3-31*

ll C

D E

F Testing Procedure The real time waveform shown in the photo above is the first return echo from a reflector selected with respect to transducer type. All contact (wearplate and dual) transducers are tested on a flat steel (4340) plate while epoxy-faced

.ar wave transducers are tested on a flat polymer block. Delay fingertip removable (Style DFR) transducers are tested f the tip of the delay line Nonfocused immersion transducers are tested in water over a flat stainless steel plate using ater path as specified above. Focused immersion transducers are tested the same as nonfocused transducers except that the water path used is equal to the actual focal length Using an AEROTECH Ultrasonic Transducer Analyzer, Model UTA-4, and Tektronix 7L12 Frequency Spectrum Analyzer in a 7704A Mainframe, the real time waveform, UTA-4 gate signal, and the frequency spectrum of the gated signal are simultaneously displayed and photographed. Using the linear attenuator in the UTA-4 receiver, the amplitude of the real time waveform is adjusted to six centimeter amplitude (+/- 1 dB) on the CRT. With the vertical calibration of Trace II fixed 100 Millivolts per division, tne amount of attenuation used provides a relative sensitivity rating for all transducers certified by Krautkramer Branson.

Real Time Waveform - Trace II Screen writing figures A and F provide the vertical and horizontal screen calibration respectively for Trace II.

Gate Marker-Trace I Screen writing figure C provides the vertical amplitude of the gate marker and is an inconsequential figure. The horizontal calibration for Trace I is the same as that for Trace I1. The portion of Trace II that falls within the gate time period is the signal fed to the frequency spectrum analyzer.

Frequency Spectrum - Trace IIl Screen writing figure E provides the horizontal calibration for Trace Ill.

Figures B and D show the spectrum

'yzer's attenuator and resolution settings respectively.

Krautkramer Branson P.O. Box 350 Lewistown, PA 17044

SAE ROT E C H TRANSDUCER CERTIFICATION DATE: 06-08-1998 MODEL 113-862-600 SERIAL 0094KW SERIES: BENCHMARK STYLE:

SWS ELE.

SIZE: 1.0 NOMINAL FREQUENCY: 2.25 MHz Test Setup-Test Block :

.75" Plexi Glass Energy Setting: 2 Impedance Setting: 100 ohms Test Data-r Center Frequency: 2.1 MHz Peak Frequency: 2.0625 MHz Absolute Sensitivlty:-17 db Inspector: 3t 2

Equipment Used:

db/div UT-A:

SN Mý100113 UTA Cal Due Date: 07/15/98 O-Scope SN:B010804 Cal Due Date:10/17/98 Software: FNT0040 Rev.

C Procedure:

Waveform shown is the first Return Echo from the indicated target.

o I

I I

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1-I-

I I

I J

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I 1

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I

.4 usec/div L - -

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I

. 75 M/qz/div The accuracy of the instrument described above has been confirmed by factory standard test equipment and laboratory reference standards traceable to the National Institute of Standards and Technology.

a This fac:lity's Quality System is registered to ISO 9001 -

DNV Certificate No 96-FOU-AQ-1095, and is Compliant to MIL-STD-45662A Krautkramer Branson P.O. Box 350, Lewistown, PA; 17044 M(717)242-0327 Fax: (717)242-2606

TTV.AHS=U:'e AEROTECH TRANSDUCER CERTIFICATION DATE: 08-18-1998 MODEL 113-242-043 SERIAL 009TNR SERIES: GAMMA STYLE: CR-RHP ELE.

SIZE:

.50 NOMINAL FREQUENCY: 2.25 MHz Test Setup-Test Block :

1.0" 303 Steel Energy Setting: 4 Impedance Setting: 250 ohms Test Data-Center Frequency: 2.275 MHz Peak Frequency: 2.225 MHz Absolute Sensltivity:-33.6 db Inspector: jt Equipment Used:

UTA: SN MMD0113 UTA Cal Due Date: 07/06/99 O-Scope SN:B010804 Cal Due Date:10/17/98 Software: FNT0040 Rev. C 100 mV/div 2

db/div Procedure:

Waveform shown is the first Return Echo from the indicated target.

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I I I I

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t'

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I a

II I

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I-I1_

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4usec/div I

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.75 MHz/div The accuracy of the instrument described above has been confirmed by factcry standard test equipment and laboratory reference standards traceable to the National Institute of Standards and Technology.

This facility's Quality System is registered to ISO 9001 -

DNV Certificate No 96-HOU-AQ-1095.

and is compliant to MIL-STD-45662A.

Krautkramer Branson P.O. Box 350, Lewistown, PA; 17044 M(717)242-0327 Fax:(717)242-2606

AEROTECH TRANSDUCER CERTIFICATION DATE: 10-12-1998 MODEL 113-224-000 SERIAL 00BGPH a

a a.

I I

I SERIES: GAMMA STYLE: F-HP a

a I

II I

I a

ELE. SIZE:.25

-LLL--

I I

a a

I a

NOMINAL FREQUENCY:

5 MHz 100 "a

mV/div aa-------

Test Setup--

a a Test Block :

1.01 303 STEEL a

a a

a Energy Setting: 4 7

a-- a a

a Impedance Setting: 250 ohms

-T

-r-r--r--

.2 usec/div Test Data, I

I I

a a

I i

I I

Center Frequency: 4.85 MHz I - -

a a

Peak Frequency:

S

.M, a

Relative Sensitivity: 68 db a

a

, a Inspector: s.diven a

a a

I a

a a

a I

I r

2 a

, a

- - - L 1_-I

- L -

-L Equipment Used:

db/div I

I I

a I

UTA-4: SN 0305 a

UTA-4 Cal Due Date: 06/26/99 O-Scope SN:B010804 a

I a

a I

Cal Due Date:l0/17/98

, a a

a Software: FNT-0040 Rev.

C a

a a

a Procedure:

Waveform shown is the first 1.5 MHz/div Return Echo from the indicated target.

The accuracy of the instrument described above has been confirmed by factory standard test ecaipment and laboratory reference standards traceable to the National Institute of Standards and Technology.

This facility's Quality System is registered to ISO 9001 - DNV Certificate No. 96-HOU-AQ-1095.

and is compliant to MIL-STD-45662A.

Krautkramer Branson P.O. Box 350, Lewistown, PA; 17044

%(717)242-0327 Fax:(717)242-2606

Krautkramer Transducer Certification DATE: 06-16-1999 MODEL 113-862-600 SERIAL OODRRJ SERIES: BENCHMARvK STYLE:

SWS ELE. SIZE: 1.0 NOMINAL FREQUENCY: 2.25 MHz Test Setup-Test Block :

.75" Plexi Glass Energy Setting: 2 Impedance Setting: 100 ohms Test Data--

Center Frequency: 2.0875 MHz Peak Frequency: 2.025 MHz Absolute Sensitivity:-18.8 db Inspector: jt 2

Eauipment Used:

db/div UTA: SN t2I00113 UTA Cal Due Date: 07/06/99 O-Scope SN:B010804 Cal Due Date:lO/15/ 9 9 Software: FNT0040 Rev.

C Procedure:

Waveform sholr is the first Return Echo from the indicated target.

A

-i 100 mV/div4 ue, I

r A.

I I _

.4 u

I i

d I

4 r-----I

.7 f-i z/

The accuracy of the 1nstrument described above has been ccnfirmed by factory standard test equipment and laboratory reference standards traceable to the National Institute of Standards ard Technology.

This facility's Quality System is registered to ISO 9001 DcV Certificate No.

99-HOU-AQ-1095, and is compliant to MIL-STD-45662A Krautkramer Branson Inc.

50 Industrial Park Rd.

Lewistown, PA 17044 (717)242-0327 Fax: (717)242-2606 http ://www. krautkramer com

J Krautkramer STransducer Certification DATE: 07-08-1999 MODEL 113-862-600 SERIAL OODRRP SERIES: BENCHMARK STYLE:

SWS ELE.

SIZE: 1.0 L

NOMINAL FREQUENCY: 2.25 MHz 100 Test Setup-Test Block :

.75" Plexi Glass Energy Setting: 2 Impedance Setting: 100 ohms S

I I

I i

a I

a a

.4 usec/div Test Data-Center Fi-equency: 2.1 MHz I

a I

I a

a Peak Frequency: 2.05 MHz Absolute Sensitivity:-19 db iI

- - - 4i 1

i JI*-----------------------IL----I----J---I I

L--_

Inspector: jt 2

Equipment Used:

db/dIv UTA:

SN IýZ100113

-- a-a a

a-a--,------

UTA Cal Due Date: 07/06/99 I,

a a

a O-Scope SN :B010804 a-a a-a-a----

a Cal Due Date:10/15/99 a

a a

a Software: FNT0040 Rev.

C a

a a

Procedure:

Waveform shown is the first

.75 MHz/div Return Echo from the indicated target.

The accuracy cf the instrument described above has been confirmed by factory standard test equipment and laboratory reference standards traceable to the National Institute of Standards and Technology.

This facility's Quality System is registtred to ISO 9001 -

DNV Certificate No 99-HOU-AQ-1095, and is compliant to MIL-STD-4S662A.

Krautkramer Branson Inc.

50 Industrial Park Rd.

Lewistown, PA 17044 (717)242-0327 Fax:(717)242-2606 http://www.krautkramer.coM

K;rautlkramer An AGFA Company Transducer Certification Compliant to ASTM E-1065 Guidelines Date:

Product Code:

Serial Number:

==

Description:==

Test Setup Test Target:

Energy:

Impedance:

Equipment Used UTA Pulser:

UTA vN:

UTA Cal Date:

O-scope SN:

0-scope Cal Date:

Software:

3/1/02 113-232-591 OOTD6F FABP-XDCR MSWQC 2 25X 38

.375" Plexiglass 3

250 Ohms UTA5 NM001 13 6/13/02 B010804 10/17/02 FNTO040 Rev D Real Time 10 m V/div i i

I I

-I I-I i r -

-r t

T - -

'- - r-r T

T -,-

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It I-I I '

liI" I,

as 00r~S/div i Waveform the first Return Echo from the indicated target Spectrum 2

FdBOdvM....

S...

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~

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_ 7- !

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-I/

/-- --

Test Data Sensitivity(Abs db):

Pulse Duration@-20dB:

Peak Frequency:

Center Frequency:

% Bandwidth@-6dB:

Inspector:

-32.00 9.83E-07 2.20E+06 2 26E+06 70.0 dB Sec Hz Hz JPT The accuracy of the instrument described above has been confirmed by factory standard test equipment and laboratory reference standards traceable to the National Institute of Standards and Technology. This facilitys Quality System is registered to ISO 9001 - DNV Certificate No 99-HOU AQ-1095, and is compliant to MIL-STD45662A Krautkramer Inc.

50 Industrial Park Rd.

Lewistown, PA 17044 MO NTH Tel.: 717.242.0327

\\\\

sdmer Fax: 717.242.2606

[w,,-,

)

http://www.krautkramer.com

E Krautlkramer An AGFA <1 Company Transducer Certification Compliant to ASTM E-1065 Guidelines Date:

Product Code:

Serial Number:

==

Description:==

Test Setup-Test Target:

Energy:

Impedance:

Equipment Used UTA Pulser:

UTA '/N:

UTA Cal Date:

O-scope SN:

O-scope Cal Date:

Software:

3/1/02 113-232-591 O0TD6H FABP-XDCR MSWQC 2 25X 38

.375" Plexiglass 3

250 Ohms UTA5 MM00113 6/13/02 B010804 10/17/02 FNT0040 Rev D Real Time 1I0 mVldiv i d

I I

r-

, - '--- --- F-- -......

7 I

400 hS/div i Waveform is the first Return Echo from the indicated target Spectrum Sd8/rjiv A

/',0

,o6 5 M hzd iv

/

7

- -S- - -,- - - --..

L -- -

/

Test Data-Sensitivity(Abs db):

Pulse Duration@-20dB:

Peak Frequency:

Center Frequency:

% Bandwidth@-6dB:

Inspector:

-31.40 1.04E-06 2.08E+06 2.29E+06 77.0 dB Sec Hz Hz

'PT The accuracy ofthe instrument descnbed above has been confirmed by factory standard test equipment and laboratory reference standards traceable to the National Institute of Standards and Technology. This facilhtys Quality System is rmgistered to ISO 9001 - DNV Certbficate No 99-HOU AQ-1095, and is compliant to MIL-STD-45662A.

Krautkramer Inc.

50 Industrial Park Rd.

Lewistown, PA 17044 Tel.: 717.242.0327 Fax: 717.242.2606 h ttp://www.krautkramer.com

f Krautksramer An AGFA 8 Company Transducer Certification Compliant to ASTM E-1065 Guidelines Date:

Product Code:

Serial Number:

==

Description:==

Test Setup-Test Target:

Energy:

Impedance:

Equipment Used UTA Pulser:

b UTA*S/N:

UTA Cal Date:

O-scope SN:

O-scope Cal Date:

Software:

3/12/02 113-262-600 OOTKMN FABP-XDCR SWS 2 25XIGMA 1.0" PLEXI GLASS 2

100 Ohms UTA5 MIMI00113 6/13/02 B010804 10/17/02 FNT0040 Rev D Real Time 1O MV/div; I

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-- *---r T- -

T..

-4 4

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400 S/ddiv!

Waveform is the first Return Echo from the indicated targeL Spectrum IV 0 65 Mht/divi

/

7I' '

1------

--i - - - - - - - - - - - - -

j

,~-

--i..

t.......

-I-K 2- - - :2 Test Data-Sensitivity(Abs db):

Pulse Duration@-2OdB:

Peak Frequency:

Center Frequency:

% Bandwidth@-6dB:

Inspector:

-680 1.49E-06 2.44E+06 2.20E+06 55.0 dB Sec Hz Hz JPT The accuracy of the instrument descnbed above has been confirmed by factory standard test equipment and laboratory reference standards traceable to the National Institute of Standards and Technology. This facility's Quality System is registered to ISO 9001 - DNV Certificate No 99-HOU.

AQ-1095, and is compliant to MIL-STD-45662A.

Krautkramer Inc.

50 Industrial Park Rd.

Lewistown, PA 17044 Tel.: 717.242.0327 Fax: 717.242.2606 http://www.krautkramer.com

SIGNAL WAVEFORM S221 Crescent St Waltham MA 021 54 Tel: 800-225-8330, 617-899-2719 PANAMETRICS FaI= 617-899-1552 0.8 0.4 TRANSDUCER DESCRIPTION R!

0 03 0

FREQUENCY:

10 00 MHz ELEMENT SIZE:

.5 in. DIA.

0.0 TEST INSTRUMENTATION PULSER/RECEIVER:

PANAETRICS 505Z UAA 6F4 DIGITAL OSCILLOSCOPE:

LECROY 9400 -

V Z06FT 3E0322 TEST PROGRAM: TP103-1 VER. 973H5 SETUP:

OWG. #5979.

-CABLE:

RG--174/U LENGTH:

4 FT.

TEST CONDITIONS PULSER ENERGY:

1 PULSER DAMPING.

50 ohm RECEVER SETTING:

40 dB GAIN / 54dS ATTENUATION TARGET: BACK WALL OF 1.0 in SIUCA

-0.4-

-0.8 MEASUREMENTS PER ASTM E1065 WAVEFORM DURATION:

-14D0 LEVEL ---.

212US

-20DB LEVEL -

.307US

-40DE LEVEL

.485US COMMENTS:

F 8.6 SPECTRUM MEASURANDS:

CENTER FREQ.

8.60MHz PEAK FREQUENCY--- 8.45MHz

-60D BANDWIDTH --

60.47 5 I RECO0R D C 0 pI TECHNICIAN: (6)

DATE: 09-03-97 FREQUENCY SPECTRUM 1.0 0.8 0.6 0.4 0.2.

0.0 0

10 20 (MHz)

(

PART NO.:

Al11S SERIAL NO.:

239864 DESIGNATION: -

CONTACT C

( 2

-J 0

(.1 USEC / DMSION )

u Z:

I-.

0 En IL)

A

,D CD U)

LC 221 Crescent St Waltham MA 02453-3497 Tel: 800-225-8330, 781-899-2719 PANAMETRICS Fax: 781-899-1552 TRANSDUCER DESCRIPTION PART NO.

A403S SERIAL NO..

267694 DESIGNATION:

CONTACT TEST INSTRUMENTATIO1 C

0.8 04 FREQUENCY:

2 25 MHz ELEMENT SIZE.

500X1.000 (in.)

0.0 PULSER/RECEIVER.

PANAMETRICS 5052 UA #4 DIGITAL OSCILLOSCOPE-LECROY 9400 -

V 2 08FT 3E0446 TEST PROGRAM. TP103-1 VER. 987TE SETUP DWG. #5979 CABLE RG-58/U LENGTH.

4 FT TEST CONDITIONS PULSER ENERGY-1 PULSER DAMPING 50 ohm RECEIVER SETTING 40 dB GAIN / 40dB AT[ENUATION TAR1GET: BACK WALL OF 1 0 in LUCITE MEASUREMENTS PER ASTM E1065 SPECTRUM MEASURANDS:

CENTER FREQ.

2.22MHz PEAK FREQUENCY --

2.35MHz

-6DB BANDWIDTH 46 85

-04

-08 1.0 08 06 04 K

1*

SIGNAL WAVEFORM

--...T..........................

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

(.5 USEC / DI.,

FREQUENCY SPECTRUM.

/

tI a.... S......

S....T...

-6

['ATE 03-

,v'- E-Z,=

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I 221 Crescent St Waltham MA 02453-3497 Tel: 800-225-8330, 781-899-2719 PANAMETRICS Fax: 781-899-1552 TRANSDUCER DESCRIPTION PART NO..

A403S SERIAL NO..

267701 DESIGNATION-CONTACT FREQUENCY 2 25 MHz ELEMENT SIZE-50OX1 000 (m) 0.0 TEST INSTRUMENTATION PULSER/RECEIVER PANAMETRICS 5052 UA #4 DIGITAL OSCILLOSCOPE.

LECROY 9400 -

V 2.08FT 3E0446 TEST PPOGRAM. TP103-1 VER 987TE SETUP DWG. #5979

,APLE RG-58/U LENGTH.

4 FT TEST CONDITIONS

-04

-08 (7

SIGNAL 08 04

(

WAVEFORM 0

ý'.'LPEP EN"ERG'

-L'L$EP DAMPING.

RECEiVE0 SETTING TAý__ET BACK WALL

(.5 USEC /

DIVISION )

1 50 ohm 40 dB GAIN / 40dB ATTENUATION OF 1 0 in. LUCITE MEASUREMENTS PER ASTM E1065 WAVEFORM DURATION.

-14DB LEVEL 1.37US

-20DB LEVEL --

1.78US

-40DB LEVEL 350US SPECTRUM MEASURANDS:

CENTER FREQ.

2.23MHz PEAK FREQUENCY 2.33MHz

-6DB BANDWIDTH 45.74 %

COMMENTS:

- ACCEPTED DATE 03-22-99 FREQUENCY SPECTRUM 1.0 08 0.6 04 L 02 O00 0.00 2 50 (MHz) 501

(7

'221 Crescent St Waltham MA 02453-3497

[]

Tel: 800-225-8330, 781-899-2719 PANAMETRICS Fax 781-899-1552 TRANSDUCER DESCRIPTION PART NO A403S FREOUENCY 2 25 MHz SERIAL NO 276054 ELEMENT SIZE 50OX1 000 (in DESIGNATION CONTACT TEST INSTRUMENTATION

'UL:EP 'PE-EIVER PArIAMETRICS 5052 UA #7

[1"-ITiAL OSCILLOSCOPE.

LECROY 9400 -

V 2.08FT 3EO321 TEST PFROGAM TP103-1 VER 995R2 SETUP DWG. #5979 A

.BLE F,'-58,U LENGTH.

4 FT.

TEST CONDITIONS PULSER ENERGY I

PI'LSER DAMPING.

50 ohm RECEIVEP SETTING 40 dB GAIN / 40dB ATTENUATION TAPGET. BACK WALL OF 1 0 in LUCITE MEASUREMENTS PER ASTM E1065 WAVEFORM DURATION-SPECTRUM MEASURANDS.

-14DB LEVEL I 20LiS CENTER FREO.

2.19MHz

-20DB LEVEL 160LIS PEAK FREQUENCY 2.35MHz

-40DB LEVEL 4 32US

-6DB BANDWIDTH 52 05 %

COMMENTS:

. ACCEPTED TECHfI1CIAN(I

1) 10-06-99 7)

SIGNAL WA'./EFORM 08 0 -...

O 4....... I................

TA -

4

..... i........ *...

0

-083

(.5. USEC / DIVISION FREQUENCY SPECTRUM 10

0.

i.... /.....

i.....

i.......

0o.

......................... !?

16?

2,76

~dB 04 02r 2 50, (MI Iz

'K

(

TRANSDUCER CERTIFICATION Transducer Description SeriesC-)tf\\r( Y' 1 1 P, S/N ~/)(,"&

luency 2*'.

!.{MHz Size Style Connector TRACE 27 contact

~ImmuersionDMNonfocused TIC Water Path __

Spherical Target

.]

S\\

i'.

LCylindrical TRACE!

Relative Sensitivity Y...-

dB Energy Setting.Cf Impedance TRACE WPeak or M Center Frequency

..5 flaMHz III Inspector

.(lW Date.-

2'-

Testing Procedure The real time waveform shown in the'.photo above is the first return echo from a reflector selected with respect to transducer type.

All contact (wearplate) transducers are tested on a flat steel (4340) plate while epoxy-faced shear wave transducers are tested on a flat polymer b'-ak.

D-Zl contact transducers are tested on a flat polymer block unless otherwise ified. Delay fingertip removable (Style DFR) transducers are tested off of the tip of the Qay line.

Nonfocused irmersion transducers are tested in water over a flat steel plate using a water path as specified above.

Focused immersion transducers are tested the same as nonfocused transducers except that the water path used is equal to the actual focal length.

- ng an AEROTECH Ultrasonic Transducer Analyzer, Model UTA-4, and a Tektronix 7L12 frequency spectrum analyzer in a 7704A Mainframe, the real time waveform, UTA-4 gate signal, and the frequency spectrum of the gated signal are simultaneously displayed and photographed.

Using the linear attenuator in the UTA-4 receiver, the amplitude of the real time waveform is adjusted to a six centimeter amplitude (+/- 1 dB) on the CRT.

With the vertical calibration of Trace II fixed at 100 millivolts per division, the amount of attenuation used provides a relative sensitivity rating for all transducers certified by Krautkramer Branson.

ea+/- lime waveform - Trace II Screen writing figures A and F provide the vertical and horizontal screen calibration respectively for Trace II.

Gate Marker -

Trace I Screen writing figure C provides the vertical amplitude of the gate marker and is an inconsequential figure.

The horizontal calibration for Trace I is the same as that for Trace II.

The portion of Trace II that falls within the gate time period is the signal fed to the frequency spectrum analyzer.

Frecuency Spectrum - Trace III Screen writing figure E provides the horizontal calibration for Trace 11I.

1"1w the spectrum analyzer's attenuator and resolution settings respectively.

KRAUTKRAMER BRANSON P. 0. Box 350 Lewistown, PA 17044 Figures B and A

B

\\

C D

EF P

)

Aerotech Transducer Certification DATE: 06-16-1989 MODEL 113-252-043 SERIES:

GAMMA STYLE: CR SERIAL F114920SP DIAMETER:

.75 ii. CONNECTOR:

BNC NOMINAL FREQUENCY:

2.25 MHz TEST SETUP-TEST BLOCK THICKNESS:

2.0 ENERGY SETTING: 4 IMPEDANCE SETTING: 250 OHMS

-;T DATA-K..PEAr FREQUENCY:

2.05 MHz RELATIVE SENSITIVITY:

74 dB INSPECTOR:

B.BENNETT EQUIPMENT USED:

UTA-4 (S/N 103 CAL THRU 10-90)

TEE 2430 SCOPE (S/N B012909 CAL THRU TEX PEP301 CONTROLLER PROCEDURE:

WAVEFORM SHOWN IS THE FIRST RETURN ECHO FROM THE INDICATED TARGET 100 "mu/div MATERIAL: STEEL S......----i...i...i...i.....i....i....i.

4.....

1.0 usec/diuv dB/

i v

S...;.

r..

4.....

)

dB/di 0.5

M THE ACCraRCy, Or TI-E !L'STRU'MENT DEF,.R..EED ABOV H_[AS BEEN F-'r-,*iE BYFATY STANDARD TESTý EOLIP'!.ET AND LABORATORY P.rE---F*XCE S7TANDAXDS TRA*CEABLE TO0 THE N*ATION*--,!

BUREAU*L OF STANDARDS.

f*I*rautleramer Branson P.O. Box 350. Lewistown, PA 17044

' (717) 24.2-0327 Fax: 717-242-2606

Aerotech Transducer Certification DATE: 07-85-1991 MODEL 113-262-600 SERIES:

GAMMA STYLE: SwS SERIAL #G83136 DIAMETER:

1.0 in.

CONNECTOR: BNC NOMINAL FREQUENCY:

2.25 MHz TEST SETUP-TEST BLOCK T1ICINESS: 1.006 ENERGY SETTING: 2 EDANCE SETTING: 186 OHMS r%.,

DATA-3EAX FREQUENCY:

2.15 MHz IELATIVE SENSITIVITY:

47 dB

[NSPECTOR: S.DIVEN 168 mv/div MATERIAL: PLEX 2

JQUIPMENT USED:

dB/d2i UTA-4 (S/N 183 CAL THRU 16-91)

TER 2438 SCOPE (S/N B012909 CAL THRU 10-91)

TEE PEP301 CONTROLLER

'ROCEDURE:

UAVEFORM SHOWN IS THE FIRST RETURN ECHO FROM THE INDICATED TARGET THE ACCURACY OF THE INSTRUMENT DESCRIBED ABOVE FACTORY STANDARD TEST EQUIPMENT AND LABORATORY TRACEABLE TO THE NATIONAL INSTITUTE OF STANDAR

........i..i.... i..... i.... i..-

I.........

J

0 S

1. 4-r 1.6 usec/diV I......

i.....

...*:... *....i i

6 8.56 MHz/div HAS BEEN CONFIRMED BY REFE PE NCE S TA11DARDS LDS AND TECHNOLOGY.

Kirautkramer Branson RO. Box 350, Lewistown, PA 17044 (717) 242-0327 Fax: 717-242.2606

Aerotech Transducer Certification DATE: 08-05-1988 MODEL 113=-262-043 SERIES: GAMMA STYLE: CR SERIAL UG19804(SP)

DIAMETER: 1.0 in.

CONNECTOR:

BNC NOMINAL FREQUENCY:

2.25 MHz TEST SETUP-TEST BLOCH<

T1ICENESS:

3.0 MATERIAL

ENERGY SETTING: 4 IMPEDANCE SETTING: 250 OHMS

\\,,-cT DATA-PEAI< FREQUENCY:

2.29 MHz RELATIVE SENSITIVITY:

72 dB INSPECTOR: S.DIVEN EQUIPMENT USED: UTA-4, TEX 2430 SCOPE, TEX PEP301 CONTROLLER PROCEDURE:

WAVEFORM SHOWNM IS THE FIRST RETURN ECHO FROM THE INDICATED TARGET 100 mv/div STEEL 2

dB/div 0

I S.........

J o

I S.... *....

4...

L.8 Sec/di V 7-s z !.. - -*

....i....

S......

0.5 MHz/div 0

01-me Krautlrrarner Branson PO. Box 350, Lewistown, PA 17044 (717) 242-01327 Fax: 717-242-2606

No. 85 6 P. 1/1

~ ~

~4t11 5CUTHirRN NuCL~EAR style connector 020c otaet QIn marsiiQI 11onifocuse1 Water Path A )-4...

Spherical Target..JLIQL&......

Cylindrcal TMJCR eula~t4ve Senaltivity

=2

-4 Energy Setting U

~~edance TunC Inspector Date The real time waveform shown in t~he photo above is the first return echo fromi a rtflector ad with respect to transducer type, All contuat (wearplate) transducers are te~gtod On a it~eel, (4340) plate while epoxy-faced shear wave t~ransducers ame tested on a flat polymier Dual contact tranou4Cars are tested an Zz flat polyme~r block,- unless otherwise

<'.;Mfed.

Delay fin~artip reo~vable (style DIR) transducers are tooted off of the tip of the Salay line, Wonfocused 1=suraion transducers ares tested in water over a f lot steal plate using t wat~er path as specifi.ed above.

Focused i or lon-traxiudu is eam tasted the twmoas tonfocuoee transducers except that the water path ubad is equal to the aetual focal legh

'Using an ASROTECH U~ltrasoni~c ?re~naduaer Artalyzer, Model UTAI-4, ind a Toletronix 7LU2 vaquency spectruft 9nalyzer ini a 7704A HainErwmpe the real tims waveform, tWTA-4 sate signal,*

nd the frequency spectrum of the gated signial are slwitauneouly displayed and plhoto~raphed.

sing th. linear attenuator in the VTA-4 receiver, the uaplitude of the real time waveform is Ijusted to a sLic centimeter w*pltude C+/- I 4B) on the CRT.

WAth the vertical calibration of rate 11 fixed at 100 mIllivolts per divinaion, the smnounk of attenuation used provides 4 ilative sensitivity rating for all. transducers certlif £4 'y 2Xcautkvramer Druneon.

~~~I1jc TieWvfr racis 1 Screen. writ~ng fig~ures A and P provide the verticeal anid borizontal Berson calibration ispettively for Trace 1U.

toIa ur~cor, -

Tracti I Screen writing figure C provides the vertical. wiqitiido of the CutsO marker and is an monsequential figure..

The horizontal ;alibz' iou for Trace I Lo the same an tbat for Trace

..The portion of Traco 11 that falls Within the Za0A time period iu the signal f ed to the iquency spectrum analyzer.

M-gOne snatm-Trace IUI N

I1,een vqrlitn; figure E provides the horizontal calibration for Trace T11.

F'igures 2 and b,-

%be spectrum suAl.yzer's attenuator and resoluiiton settints reopectively.

IMLUTEcRMM BRUiS0R P. 0, Box 350 Lodstown, PA. 1044

Material Certs.

J. M. FARLEY UNIT 2 RF-15 EXAMINATION MATERIALS ULTRASONIC COUPLANT MANUFACTURER TYPE BATCH NO SONOTECH, INC.

ULTRAGEL II 01125 SONOTECH, INC.

ULTRAGEL II 01225 DYE PENETRANT PRODU CT MANUFACTURER TYPE BATCH NO.

CLEANER/REMOVER MAGNAFLUX SKC-S 02E05K 99J01K PENETRANT MAGNAFLUX SKL-SP 96J02K DEVELOPER MAGNAFLUX SKD-S2 02G07K 96J08K MAGNETIC MATERIALS MANUFACTURER TYPE BATCH NO.

MAGNAFLUX RED 8A 95H062 SURFACE THERMOMETER MANUFACTURER IDENTIFICATION NO.

PACIFIC TRANSDUCER CORP.

48647 PACIFIC TRANSDUCER CORP.

48881 PACIFIC TRANSDUCER CORP.

48890

LABORATORY TESTING INC.

SI1006-01-04-08650 2331 Topaz Drive, Hatfield, PA 19440 TEL: 800-219-9095 a FAX: 800-219-9096 SOLD TO Sonotech, Incorporated P.O. Box 2189 Bellingham, WA 98227-2189 SHIP TO Sonotech, Incorporated P.O. Box 2189 Bellingham, WA 98227-2189 ATTN: John Rutter CUSTOMER P.O.

5621 CERTIFICATION DATE 04/27/01 SHIP VIA FAX AND MAIL DESCRIPTION 1 pc. Test Sample, Identified as 011-U, Covering: Ultragel II - 01125 Sonotrace 20 - 01141, Sonotrace 30 - 01142, Sonotrace 40 - 01143 The submitted sample was analyzed in accordance with ASTM D-512, ASTM D-808 and ASTM D 129 with the following results:

ELEMENT Total Chlorides Total Fluorides Total Sulfur ACTUAL

26. ppm

7. ppm

29. ppm The services performed above were done in accordance with LTI's Quality System Program Manual Revision 15 dated 12/4/00 These results relate only to the items tested and this report shall not be reproduced, except in full, without the written approval of Laboratory Testing Inc L T I. is accredited by A2.LA in the Chemical. Mechanical and Nondestructive Fields of Testing L T I is accredited by NADCAP in the Material's Testing and NDT, MT, PT. RT and UT MERCURY CONTAMINATION: During the testing and inspection, the product did not come in direct contact with mercury or any of its compounds nor with any mercury containing devices employing a single boundary of containment By:

Sherri L. Lengyel Ato inator Authorized Signature Page 1 of 1 hDT IPT MT AT U1

SLABORATORY TESTING INC.

S11006-01-10-24075 2331 Topaz Drive, Hatfield, PA 19440 i

TEL: 800-219-9095

FAX: 800-219-9096 Certm 0117-01.02 03 Materials Testing L.boratory NDT (PT. MT RT. UT}

SOLD TO Sonotech, Incorporated P.O. Box 2189 Bellingham, WA 98227-2189 SHIP TO Sonotech, Incorporated P.O. Box 2189 Bellingham, WA 98227-2189 ATTN: John Rutter CUSTOMER P.O.

5773 CERTIFICATION DATE 11/2/01 SHIP VIA FAX AND MAIL DESCRIPTION 1 pc.

Test Sample, Sample No. 012-U, Covering Ultragel II - 01225, Sonotrace 20 - 01241, Sonotrace 30 - 01242 and Sonotrace 40-01243 The referenced sample was analyzed in accordance with ASTM D-808, ASTM D-129, ASTM D-512 and Customer's Instructions with the following results:

ELEMENT Total Fluorides Total Halogens as CI Total Sulfur SAMPLE 012-U

8. ppm

6. ppm

3. ppm The services perfocmed above were done in accordance witn LTI's Quality System Program Manual Revision 16 dated 9/1/01. These results relate only to the items tested and this report shall not be reproduced, except in full, without the written approval of Laboratory Testing, Inc. L T.I. is accredited by A2.LA in the Chemical, Mechanical and Nondestructive Fields of Testing. L.T.I. is accredited by NADCAP in the Material's Testing and NDT. MT. PT, RT and UT.

MERCURY CONTAMINATION: During the testing and inspection, the product did not come in direct contact with mercury or any of its compounds nor with any mercury containing devices employing a single boundary of containment Sherri L. Lengyel QA Coordinator By:

Authorized Signafure Page 1 of 1

Dal*DIV~VnIO,IUgJ*TooI Works Inc.

<> urchase Order No:

Subject:

SPOTCHECK CLEANER/REMOVER Type: SKC-S Batch No. 02EO5K We hereby certify that when tested at time of manufacture, the above material:

1.

Meets the requirements of and has been tested for sulfur and halogens according to A. ASME Boiler and Pressure Vessel Code, 1983 Edition,Section V, Nondestructive Examination, including all Addenda through Winter 1983 Addendum, Article 6 Paragraph T-625 and Article 24 as applicable.

B.

ASME Boiler and Pressure Vessel Code, 1986, 1989, and 1992 Edition,Section V Nondestructive Examination, Article 6 including 1992 Addenda, Paragraph T-625, 1993 Addenda Paragraph T-640 and Article 24 as applicable.

C. ASME Boiler and Pressure Vessel Code, 1995 Edition & 1998 Edition,Section V, Nondestructive Examination, including 1999 & 2000 Addenda, Article 6 Paragraph T640 and Article 24 as applicable.

D ASTM E-165-92, ASTM E-165-94, ASTM E-165-95, and ASTM E-165-02, Paragraph 7. 1.

E.

MIL-STD-271F(SH), 27 June 1986, Paragraphs 5.3 and 5.3.1., including Notice I Paragraph 5.6.1(21, June 1993).

F. NAVSEA T9074-AS-GIB-010!271, 30 April 1997, Paragraph 5.3.1.

G.

NAVSEA 250-1500-1 (Rev. 10 June 1979, Rev. 11 May 1983, Rev 12 December 1987 Including ACN 2 Nov. 15, 1990, Rev. 13 October including ACN 4 June 30, 1995)

Paragraphs 12.5.1.1 and 12.5.1.1.1.

H MIL-STD-2132C (SH), 1 February 1996, Paragraph 7.1,7.1.2.,7.1.3, and Appendix C, Paragraph 40.

The following test results were obtained:

Sulfur:

NA wt, % of residue. CL + F:

NA wt, % of residue Cleaner residue (see not.e 3) 0.0049 g/100g 0 0037 g/100ml

2.

We further certify that this material does not contain mercury as a basic element and no mercury bearing equipment was used in its manufacture.

MAGNAFLUX For and on behalf of Q. A. Manager Mary Kay McGlynn - Lab Tech Mathew Plamoottil - Quality Assurance Manager Notes:

1. Our batch number appears on the bottom of all aerosol cans and on the label of all bulk containers.

2. Most specifications require test results stated in percent but some require parts per million(ppm). To convert "percent" figures to "parts per million" move the decimal four places to the right.

3.The above certification gives the results obtained at the time of manufacture.

Age and use may alter the properties of any material.

Form No. 1569 R-4/02 3624 WEST LAKE AVENUE 1" GLENVIEW, ILLINOIS 60025 ff TEL (847] 657-5300 r-FAX (847) 657-5388 www.mognaflux.com

A Division of Illinois Tool Works Inc.

Date: May 16, 2002 Purchase Order No.

We hereby certify that the SPOTCHECK CLEANER/REMOVER

, Type SKC-S Batch No. 02EO5K

, supplied meets the requirements of AMS 2644B, and is approved by the U.S. Air Force.

When tested according to paragraph 4.3.2., Sampling Plan A, the following results were obtained.

4.2.2.1 Penetrant Tests:

Flash Point(PMCC), 3.3.3 Viscosity, 3.3.4(

cs. Nominal)

Fluorescent Brightness,3.3.8.3.2.(

Standard)

Water Tolerance(Method A only),3.3.8.5 Removability, 3.3.8.6 4.2.2.1 Emulsifier Tests:

Flash Point(PMCC), 3.3.3 Viscosity, 3.3.4(

cs. Nominal)

Water Content(Method D only), 3.3.9.6 4.2.2.3. Developer Tests:

Developer Fluorescence, 3.3.10.2 Developer Removability, 3.3.10.4 Redispersibility, 3.3.10.5 3.3.11.5 Remover Tests Penetrant Removal, 4.4.11.3.2 NA OF NA cs @ I 00*F NA NA NA NA OF NA cs @ I001F NA NA NA NA PASS We further certify that this material meets the requirements of ASTM E 1417, Paragraph 5. 1.

Certification is issued under the auspices of the Quality Assurance Manager.

MAGNAFLUX Form 1579C R-09/01 For and on behalf of Q. A. Manager Mary Kay McGlynn - Lab Tech Mathew Plamoottil - Quality Assurance Manager 3624 WEST LAKE AVENUE ff GLENVIEW, ILLINOIS 60025 li TEL (847) 657-5300 M FAX (847) 657-5388 www.mognatlux.com

3624 WEST LAKE AVE GLENVIEW, ILLINOIS 60025 DATE:-

ocTOgg, 71, locoPHONE 847 657.5300 FAX 847 657.S388 P U R C HA S E O R D E R N O.

SUBJECT:

SPOTCHECK CLEANER/REM-OVFR TYPE:

SKC-S BATCH NO:

99J01K We hereby certify that when tested at time of manufacture, the above material:

1. Meets the requirements of and has been tested for sulfur and halogens according to:

AASME Boiler and Pressure Vessel Code, 1983 Edition,Section V, Nondestructive Examination, including all Addenda through Winter 1983 Addendum, Article 6 Paragraph T-625 and Article 24 as applicable.

BASME Boiler and Pressure Vessel Code, 1986,1989, and 1992 Editon,Section V, Nondestructive Examination, Article 6 including 1992 Addenda, Paragraph T-625, 1993 Addenda Paragraph T-640 and Article 24 as applicable.

CASME Boiler and Pressure Vessel Code, 1995 Echdon & 1998 Edition,Section V, Nondestructive Examination, Article 6 Paragraph T640 and Article 24 as applicable.

D.ASTM E-165-92, ASTM E-165-94, and ASTM E-165-95, Paragraph 7.1.

E.MIL-STD-271 F(SH), 27 June 1986, Paragraphs 5.3 and 5.3.1., including Notice 1 Paragraph 5.6.1(21, June 1993).

F.NAVSEA T9074-AS-GIB-01 0/271,30 April 1997, Paragraph 5.3.1.

G.NAVSEA 25D-1500-1 (Rev. 10 June 1979. Rev. 11 May 1983, Rev 12 December 1987 including ACN 2 Nov. 15, 1990, rev. 13 September 1993) Paragraphs 12.5.1.1. and 12.5.1.1.1.

H.MIL-STD-2132B(SH), 31 August 1993, Paragraph 7.1,7.1.2, 7.1.3, and Appendix C, Paragraph 40.

The following test results were obtained.

Sulfur:

NA wt, % of residue. CL + F:

NA wt, % of residue Cleaner residue (see note 3) 0.0041

.o9/100g 0.0011

.o/100ml

2. We further certify that this material does not contain mercury as a basic element and no mercury beanng equipment was used in its manufacture.

MAGNAFLUX Mary Kay McGlynn - Document Clerk NOTES: 1. Our batch number appears on the bottom of all aerosol cans and on the label of all bulk containers.

2. Most specifications require test results stated in percent but some require parts per miUion(ppm). To convert "percent" figures to "parts per milbon" move the decimal four places to the nght.

3.The above certification gives the results obtained at the time of manufacture.

Age and use may alter the properties of any matenal.

Form No. 1569 R-10199

3624 WEST LAKE AVE GLENVIEW ILLINOIS 60025 PHONE 847.657.5300 DATE:

OCTOBER 13, 1999 FAX 847.657.5388 PURCHASE ORDER NO.

We hereby certify that the SPOTCHECK CLEANER/REMOVER, TYPE SKC-S Batch No.

99J01K

, supplied meets the requirements of MIL-;-25135, and is approved by the U.S. Air Force When tested according to paragraph 4.4.1.2., Sampling Plan A, the following results were obtained:.

(a) Flash Point (PMCC), 4.5.3 NA or (b) Viscosity, (

cs Nominal), 4.5.4 NA CS@100°F (c) Developer Fluorescence, 4.5.14 NA (d) Water Content, 4.5.21 NA (e) Penetrant Removability, 4.5.17(

Standard)

PASS (f) Water Tolerance, 4.5.12 NA (g) Fluorescent Bnghtness of Penetrants, 4.5.7(

Standard)

NA (h) Surface Wetting, 4.5.6 NA (i) Thermal Stability, 4.5.9 NA (j) Redispersibility, 4.5.13 NA (k) Valve Leakage, 4.5.20 PASS

-(I) Net Content, 4.5.19 227-245 GM.

We further certify that this material meets the requirements of ASTM E 1417, Paragraph 5.1.

MAGNAFLUX (

M. Par io( "u tv,surance Mary Kay 1cGlvnn fl-..........

fI,.

Form No. 1579B R-1197

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A Division of Illinois Tool Works In jate:

07/26/02 Purchase Order No.

We hereby certify that the Spotcheck Developer

, Type SKD - S2 Batch No.

02G07K

, supplied meets the requirements of AMS 2644C, and is approved by the U.S. Air Force.

When tested according to paragraph 4.3.2., Sampling Plan A, the following results were obtained.

4.2.2.1. Penetrant Tests:

Flash Point (PMCC), 3.3.3 NA

F Viscosity, 3.3.4(

cs. Nominal)

NA cs@100"F Fluorescent Brightness, 3.3.8.3.2.(FP-4PE Standard)

NA Water Tolerance (Method A only), 3.3.8.5 NA Removability, 3.3.8.6 NA 4.2.2.1 Emulsifier Tests:

Flash Point (PMCC), 3.3.3 Viscosity, 3.3.4(

cs. Nominal)

Water Content (Method D only), 3.3.9.6 4.2.2.3. Developer Tests:

Developer Fluorescence, 3.3.10.2 Developer Removability, 3.3.10.4 Redispersibility, 3.3.10.5 3.3.11.5 Remover Tests:

Penetrant Removal, 4.4.11.3.2 NA

F NA cs@100"F NA PASS PASS PASS NA We further certify that this material meets the requirements of ASTM E 1417, Paragraph 5.1.

MAGNAFLUX Mathew Plamoottil - Quality Assurance Mgr.

Mary Kay McGlynn - Lab Technician.

Form No F-1 579C R-7/02

,24 WEST LAKE AVENUE 5 GLENVIEW, ILLINOIS 60025 &E TEL (847) 657-5300 E FAX (847) 657-5388 Ww.magnaflux.com

A Division of Illinois Tool Works Inc.

rlate:

07/26/02 Purchase Order No:

Subject:

Spotcheck Developer Type:

SKD - S2 Batch No.

02G07K We hereby certify that when tested at time of manufacture, the above material:

1. Meets the requirements of and has been tested for sulfur and halogens according to.

A. ASME Boiler and Pressure Vessel Code, 1983 Edition,Section V, Nondestructive Examination, includ ing all Addenda through Winter 1983 Addendum, Article 6 Paragraph T-625 and Article 24 as apphcatle B. ASME Boiler and Pressure Vessel Code, 1986, 1989 and 1992 Edition,Section V Nondestructive Examination, Artcle 6 including 1992 Addenda, Paragraph T-625, 1993 Addenda Paragraph T-640 and Article 24 as applicable.

C. ASME Boiler and Pressure Vessel Code, 1995 Edition & 1998 Edition,Section V, Nondestructive Examination, including 1999 & 2000 Addenda, Article 6 Paragraph T640 and Article 24 as applicable.

D. ASTM E-1 65-92, ASTM E-1 65-94, ASTM E-1 65-95, and ASTM E-1 65-02, Paragraph 7.1.

E. MIL-STD-271F(SH), 27 June 1986, Paragraphs 5.3 and 5.3.1., including Notice 1 Paragraph 5.6.1 (21, June 1993).

F. NAVSEAT9074-AS-GIB-010/271, 30April 1997, Paragraph 5.3.1.

G. NAVSEA 250-1500-1 (Rev. 10 June 1979, Rev. 11 May 1983, Rev 12 December 1987 Including ACN 2 Nov. 15, 1990, Rev. 13 October 1993 including ACN 4 June 30, 1995) Paragraphs 12.5.1.1 and 12.5.1.1.1.

H. MIL-STD-2132C(SH), 1 February 1996, Paragraph 7.1, 7.1.2., 7.1.3, and Appendix C, Paragraph 40 The following test results were obtained:

Sulfur:

0.0057 wt, % of residue. CL+F:

0.0232 wt, % of residue Cleaner residue (see note 3)

NA g/loog NA g/looml

2. We further certify that this material does not contain mercury as a basic element and no mercury bearing equip ment was used in its manufacture.

MAGNAFLUX Mathew Plamoottil - Quality Assurance Mgr.

Mary Kay McGlynn - Lab Technician.

Notes:

1.

Our batch number appears on the bottom of all aerosol cans and on the label of all bulk containers.

2.

Most specifications require test results stated in percent but some require parts per million (ppm). To convert "per cent' figures to "parts per million" move the decimal four places to the right.

3.

The above certification gives the results obtained at the time of manufacture.

Age and use may alter the properties of any material Form No. F-1569 R-4/02

./3624 WEST LAKE AVENUE &.. GLENVIEW, ILLINOIS 60025 L. TEL (847) 657-5300 z FAX (847) 657-5388 www.magnaflux.com

GLENVIEW, ILLINOIS 60025 PHONE 847.657.5300 DATE:

OCTOBER 6, 1996 FAX 847.657.5388 JJURCHASE ORDER NO.

We hereby certify that the SPOTCHECK DEVELOPER, TYPE SKD-S2 Batch No.

96J08K

, supplied mees the requrements of MIL-;-25i.SE and is approvea by the U.S. Air Force When tested according to paragraph 4.4.1.2., Sampling Plan A, Ine fcllowing resuts were obtained:.

(a) Fiash Point (PMCC), 4.5.3 (b) Viscosity, (,.,cs Nominal), 4 5.4 NA (c) Developer Fluorescence, 4.5.14 PASS (d) Water Content, 4.5.21 (e) Penetrant Removability, 4.5.17(-Standard)

NA (f) Water Tolerance, 4.5.12 NA

.g) Fluorescent Brightness of Penetrants, 4.5. 7 __Standard)

NA (h) Surface Wetting. ".5.6 NA (i) Thermal Stablity, 0-.5.9 NA (J) Redispersibility, 4.5.13 PASS (k) Valve Leakage, 4.5.20 PASS (I) Net Content, 4.5.19 256-280 GM.

We fur'ther certify that this material meets the requirements of MIL-STD-6865 (29 November 1985), Paragraph 4.4.1 and where applicable, 5.8._S,,nclucing Amendment 1(10/4/89).

MAGNAFLUX

)

M. Plamootil - Manager, Quality Assurance "Kim Maschmann - Documents Clerk Form No. 15798 R-SIS6 A DIVISION OF ILLINOIS TOOL WORKS INC

DATE:

October 6, 1996 PURCHASE ORDER NO.

SUBJECT:

Spotcheck Developer TYF BATCH No.

96JO8K" GLENVIEW, ILLINOIS 60025 PHONE 847.657-5300 FAX 847.657.5388 "E:

SKD-S2 We hereby certify that when tested at the time of manufacture, the above material:

1. Meets the requirements of and has been tested for sulfur and halogens according to:

(a). ASME Boiler and Pressure Vessel Code. 1983 Edition Section V, Nondestructive Examination, including all Addenda though Winter 1983 Adoendum, Article 6 Paracraph T-625 and Article 24 as applicable.

(b). ASME Boiler and Pressure Vessel Code, 1986, 1939.& 1992 Edition,Section V.

Nondestructive Examination, Article 6, including 1992 Adoenda, Paragraph T-625, 1993 Addenda Paragraph T-640 and Article 24 as applicable (c). ASME Boiler and Pressure Vessel Code, 1995 Edition,Section V. Nonoestructive Examination, Article 6, Paragraph T-640 and Aritcle 24 as applicable.

(d). ASTM E-165-92 and ASTM E-165-94, Paragraph 7.1.

(e). NAVSEA 250-150 0 -1 (Rev. 10 June 1979, Rev. 11 May 1983. Rev. 12 December 1957 including ACN 2 Nov. 15, 1990,Rev. 13 September 1993) Paragraphs 12 5.1.1 and 12.5 1.1.1.

(f). MIL-STD-271F(SH), 27 June 1986, Paragraphs 5.3 and 5.3.1 including Notice 1, Para. 5.6.1 (6/21193).

(g). MIL-STD-2132B(SH), 31 August 1993, Paragraph 7.1.1, 7.1.2. and 7.1.3 and Appendix C, Paragraph 40.

The following test results were obtained:

Sulfur. 0.0065 wt, % of residue. CL+F-F

-0066 wt, % of residue.

Cleaner residue (see Note 3)

NA g/100g.

NA g/100 ml.

2. We further certify that this material does not contain mercury as a basic element, and no mercury bearing equipment was used in its manufacture.

MAGNAFLUX (D NOTES:

M. Plamoottil - Manager, Quality Assurance Kim Maschmann.- Documents Clerk

" 1. Our batch number appears on the bottom of all aerosol cans and on the label of all bulk containers.

2. Most specifications require test results stated in percent but some reouire parts per million (ppm). To convert "percent" figures to "parts per million" move the decimal four places to the right.

3. The above certification gives the results obtained at the time of manufacture.

Age and use may alter the properties of any material.

A DIVISION OF IIt.NOIS TOOl WORKS INC le, Form No. 1569 R-5196

3624 WMST LAKE AVE GLENWEW. IINOUS 60025 P<ONE W.465*5300 FAX 817.63

- Au st 29 PURCHASE ORDER NO.

We hereby c=rty that the Magnetic Particle Inspection Material type 8,

Red Powder..

Batch No.

95H062 meets the requirements of the following specifications:

A. ASME Boiler and Pressure Vessel Code,Section V, 1989 & 1992 Edition, Nondestructive Examination, including 1992 Addenda, Paragraphs T-723, T-726(A) and Article 25 as applicable.

S. ASTM E-709-g5, Paragraphs 8.1, 8.2, and 8.3.

i. NAVSEA 250-1500-1, (Rev. 10 June 1979, Rev. 11 May 1983, and Rev. 12 December 1987 including ACN 2 Nov. 15, 1990 & Rev. 13 September 1993)

Paragraph 12.4.1.6.

D. ASTM E 1444-93, Paragraph 5.8.1.

E. MIL-STD-271F(SH). 27 June 1986, Paragraphs 4.2.7, 4.3.2.3, and 4.3.3.1,including Notice 1,21,June 1993.

F. MIL.STD-2132B(SH), 31 August 1993, Paragraph 6.1.3.

We further certify that this material does not contain mercury as a basic element and no mercury bearing equipment was used in its manufacture.

Batch numbers appear on labels of bulk containers.

MAGNAFLUX G M. Plamoottil - Manager, Quality Assurance Kim Maschmann-Documents Cleak Form No. 1565A RP-15 A DVrAONH OF K12

?O.

=WCI.S, tC.-

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'I r strmmSPN.102570 Date:

2-();.112 K>

~CERTIFICATE OF CALIBRATION4

1.

cum1,mcr WVcdvne lat.

k. ason to., Submijsm:oii___

ULczeaikr, I3!17 Mill C.alibranonN I

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14, 3.11-.-20,1 2 TrEM PERATURE INI)ICATO R COMlPARISON 1'eiiuperalure I

Teniperaturc Tempejtratuire 25OF to 55"F b0T to 900F 10031' to I 50c F Control Temperature Indicator S!lN SAP 101753 44 I

72

1211____"

Field Tempera ture Indicator S.N SAP 102570 46 OF I72 al.

120 )

CALIBRtATION TEST RESUJLTS ACCEPTABLE X

UNACCEIPTABI.E Calibrated by:

Barry L Hlughey

6 61RO499q6 Instrument SAP No.

102578 Date:

2-05-02 CERTIFICATE OF CALIBRATION Cw~znlarv Locaion I

IrL'.rufliew CIibrazion

fliermnimeter Manu!.idurcr NlodcI Number V,...dini. In?.

Valtz NOi Surf~2ce Temperature~

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C.11 I lat 3.I6.201)i c

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3-1t, 20):I TEMP[ERATU RE INDIC'ATO R COM)PA~RIN0)N Temperature Teniperuture Temlperaturt:

250F to 55OF I

60'F to 90)T 100'~F to 15017 S "N ISAP 102578 CALIBRATION TEST RESULTS ACCEPIYARLE

-x UN 3&CEPTABLL Calibrated bN.

Barz-vL Hug'hey

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CALIBRATION TEST REsuir ACCEPTABLE X

UNACCEITlABLE Calibrated 1):

Barrv 1, Hugdiev Signature:

71

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Cal. Block Certs.

J. M. FARLEY UNIT 2 RF-15 CALIBRATION BLOCKS BLOCK NO SIZE OR MATERIAL HEAT NO.

SCHEDULE ALA-5 0.906" SA-376(A)

M9217 ALA-32 0.880" SA-240(A)

HT25814 ALA-36 N/A SA-540(F) 84080 ALA-38 6"

SA-508(F)/CLAD 31-3212 612034 309-16 ALA-53 4.76" SA-336 CL F316LN 800397 ALA-RV2 14" SA-508(F)/CLAD 4952 E308-309 ALA-RV6 14.75" SA-508(F)/CLAD 123X303 2349 70985 2480 APR-6 5.5" SA-336(F)/CLAD 123PI18 06804/2506511 C3260/2589686 19944/2986601 APR-7 3.5" SA-533(F)

D8366-5 06804/2506511 C3260/2589686 19944/2986601 Cal block drawings and material certifications are included in FNP-0-M-076

J. M. FARLEY UNIT 2 RF-15 ADDITIONAL CALIBRATION BLOCKS BLOCK NO SIZE OR MATERIAL HEAT NO.

SCHEDULE_______

4846 Angle beam SS N/A

SAP# 102268 PO800

- Lz 3S o*L A 1%17,6A 47-7124 2-032 1

& rautkramer Branson CERTIFICATE OF coMpLIAgCE Customer: WESTINGHOUSE DYNACON

SYSTEMS, INC.

1061 MAIN STREET NORTH HUNTINGDON, PA 15642 P.

0. 0:

MA37277D

==

Description:==

Type:

Miniature Angle Beam Block Angle Beam Calibration and Verification Material: Stainless Steel to BS 1501 Cast Number 15247 S/N: 4846 Krautkramer Branson hereby certifies that the subject block has been manufactured in accordance with AWS specif ication D1.1-90 (section.6.16.1) and ASTM E164.

This test block has been checked and found to be dimensionally accurate using labratory reference standards supported by valid certificates traceable to the National Institute of Standards and Technology The reference standards used in the performance of the calibration procedure OCP 1037 REP are of ten (10) times greater accuracy than the standard being calibrated.

The calibration system procedures utilized at this faci lity conform to the requirements set forth in M!L-STD-45662 Instrument: Deltronic DH14-612RE Instrument: Mitutoyo optical Comparator (IOX Lens) 0-6" Dial Calipers SINra!

Da9:121 S/N: 7001032 Calibrat-ion Date:

12-13-90 Calibration 05-13-91 Due Date:

12-13-91 Due Date: 07-13-91 D.A. BOHN Quality Control Technician Date: 05-24-91

PROCEDURE LIST The following procedures were used in the performance of Inservice Examinations at the Farley Nuclear Plant - Unit 2 during the 15th refueling outage. Copies of the procedures are available in the FNP Document Control.

PROCEDURE TITLE REVISION/TCN NUMBER FNP-ISI-54 MANUAL ULTRASONIC EXAMINATION for the 0

REACTOR VESSEL UPPER SHELL to FLANGE WELD for FARLEY UNIT 1 and 2 FNP-ISI-55 MANUAL ULTRASONIC EXAMINATION of the REACTOR 0

VESSEL THREADS in FLANGE for FARLEY UNIT I and 2 FNP-ISI-88 UNDERWATER REMOTE VISUAL EXAMINATION for 1

FARLEY UNIT I and 2 NUCLEAR POWER PLANT FNP-0-NDE-100.5 LIQUID PENETRANT EXAMINATION (COLOR 6

CONTRAST AND FLUORESCENT)

FNP-0-NDE-100.11 MAGNETIC PARTICLE EXAMINATION 4

FNP-0-NDE-100.21 VISUAL EXAMINATION VT-I I

FNP-0-NDE-100.22 VISUAL EXAMINATION VT-2 5

FNP-0-NDE-100.23 VISUAL EXAMINATION VT-3 5

FNP-0-NDE-100.31 MANUAL ULTRASONIC EXAMINATION OF FULL-8 PENETRATION WELDS (0.200 TO 6.0 INCHES)

FNP-0-NDE-100.34 MANUAL ULTRASONIC EXAMINATION OF WELDS IN 6

VESSELS FNP-0-NDE-100.38 MANUAL ULTRASONIC EXAMINATION OF NOZZLE 2

INNER RADIUS FNP-0-NDE-100.39 MANUAL ULTRASONIC EXAMINATION OF BOLTS AND 4

STUDS GREATER THAN 2 INCHES IN DIAMETER

I

NO EXAMINATIONS SCHEDULED THIS OUTAGE

i

Class 1

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT.pe: L1.52 Owner Southern Nuclear Operating Company 40 Inverness Center Parkway Birmingham, Alabama 35242 (as agent for Alabama Power Company)

Job Number E21 - W002001650 U

2.

Plant Farley Nuclear Plant Highway 95 South Columbia, Al. 36319 Sheet I of 2 Unit FNP 2 Date September 26, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Chemical and Volume Control System

5.

(a) Applicable Construction Code.

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section Xl Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Mech Snubber Pacific Scientific 37864 N/A PO QP1470 1987 Replaced No Hyd Snubber Lisega 02615240 / 041 N/A P 0 QP020295 2002 Replacement No

7.

Description Of Work Snubber SS-12648 was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02041207 1.

.8.

Test Conducted D

Hydrostatic 1-'

Pneumatic Ej Normal Operating Pressure Z None [

Other Pressure PSI Temperature OF

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT~pe: LI.52

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Job Number I E21 - WOO2Of! 6*0l E -. W02015 of 2

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate We certify that the statements made in this report are correct and this ASME Code,Section XI of Compliance replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp t,4 ZA Certificate of Authorization Number V1, A, Signed Owner or Owner's Designee, Title Expiration Date lf,-l_

Date I P I /

Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by 4,

/,7AA..

4a c, '

of 0

XA-have inspected the components described in this Owner's Report during the period

.__to

,eZX4!/,: 7"

, and state that to the best of my knowledge and belief, the Ownef has performed examinations and takeni corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report Furthermore, neither the Inspector not his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising fiom or connected with this inspection.

Commissions

~

tor's Signature

,,.Z15 National Board, State, Province, and Endorsements

/

Dte_

1 ISheet 2

of 2

'":Date

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E21 -VW'002001653 RType: LI.52 Sheet I of 2

1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

September 26, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name: Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Chemical and Volume Control System

5.

(a) Applicable Construction Code:

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped No. __Replacement_(Yes

/ No)

Mech Snubber Pacific Scientific 37891 N/A PO QP1470 1987 Replaced No Hyd Snubber Ltsega 02615240 / 043 N/A P 0 QP020295 2002 Replacement No

7.

Description Ofl Work Snubber SS-12677 was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref. MIF 02041211

8.

Test Conducted D

Hydrostatic

[

Pneumatic E Normal Operating Pressure 0 None

]

Other Pressure PSI Temperature OF

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RTTpe: L1.52 Job Number E21 - W002001653 ISheet 2 of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI.

replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp "Ni/A Certificate of Authorization Number Signed W/'

Expiration Date bLa A

A-141A"r /hl-Date to/i Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

_k--_&,*_/_

0 and Employed by I_

.of

._have Inspected the components described in this Owner's Report during'the penod

/,__"

__to

_2-

, and state that to the best of my knowledge and belief, the Owner hds performed examinations and taken c6rrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

(,Dsctor's Signature

/

Commissions

,4*X-

" -g National Board, State, Province, and Endorsements K1 Date I Sheet 2

of 2

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E21 -V RType : L1.52 V002001654 Y

Sheet I of 2

1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

I September 3 0,2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Chemical and Volume Control System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components :

Name Of Manufacturer Manufacturer Serial Number National Board No.

Other Identification Y'ear Built Repaired Replaced Or Replacement 4

4

.1.

/ No)

Pacific Scientific 2513 N/A P 0 FNP 2-29 1977 Replaced ASME Code Stamped

(['pe, I Nn*

Yes i

1'

+

4 Hyd Snubber Lisega 02615240 / 045 N/A P 0 QP020295 2002 Replacement No

7.

Description Ot Work Snubber SS-12684 was removed from its support by Southern Nuclear, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Southern Nuclear as part of a scheduled upgrade program Ref MIF 02041216 Name Of Component Mech Snubber "8. Test Conducted S1 Hydrostatic FJ Pneumatic 1:

Normal Operating Pressure 0 None [-] Other Pressure PSI Temperature or

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52 Job Number E21 - W002001654 I Sheet 2 of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section X!

replacement conforms to the rules of the repair or replacement

.Type Code Symbol Stamp Certificate of Authorization Number Signed V, /A Owner or Owner's Designee, Title Expiration Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

/A and Employed by W

&r,.of

..have inspected the components described in this Owner's Report during the period

__________._to

.,,,/-,_&t_

to

, and state that to the best of my knowledge and belief, the Owner has lerformed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection Commissions 1,A 3'.

?6 ýtor s Signature 27A2AA National Board, State, Province, and Endorsements P4/A Date I.'f

/ a-

'Date

/-

it

I 24994ýý gux'r M&L

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52 Job Number B13 - W002001646 Sheet I of 2

1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October 2, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Reactor Coolant System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section X1 Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped

,__(Yes

/ No)

Mech Snubber Pacific Scientific 3565 N/A PO FNP 2-29 1978 Replaced Yes Hyd Snubber Lisega 01615120 / 046 N/A P 0 QP020295 2002 Replacement No

_ I

_ I I

+

4

7.

Description Of Work Snubber 2RC-R147A was removed from its support by Southern Nuclear, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02041280

8.

Test Conducted

---] Hydrostatic

[]

Pneumatic [-] Normal OperatingPressure Z None []

Other Pressure PSI Temperature O F

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT)pe: L1.52 Job Number B13-W 002001646 I Sheet 2

of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section Ill Certificate of Compliance We certify that the statements made in this report are correct and this replacement conforms to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp

/A Certificate of Authorization Number M/

Expiration Date Signed jAthlN-jv4.

Date 0D/"

/o"L.

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of _

-_________and Employed by of

"~7jZ,.-s'*,/

e.e-,e..

LoA,./. ~haveinspected the components described m this Owner's Report during the period A,- Z to

, and state that to the best of my knowledge and belief, the Ownerehas performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

,.--"Vnspector's Signatdre Commissions 6:X

-72 9

_L",*1, National Board, State, Province, and Endorsements "IDate 7

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number B13-W RType: L1.52

'002001523

.1 I

1.

Owner Southern Nuclear Operating Company 40 Inverness Center Parkway Birmingham, Alabama 35242 (as agent for Alabama Power Company)

2.

Plant Farley Nuclear Plant Highway 95 South Columbia, Al. 36319 Sheet I of 2 Unit FNP 2 Date September 30, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Reactor Coolant System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section X! Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped I--_

(Yes / No)

Tubing Cylinder Grinnell Unknown N/A P.O FNP 2-29 1981 Replaced No Tubing Cylinder Grinnell Unknown N/A P 0 QP5148 1990 Replacement No

7.

Description Of Work Snubber 2RC-R2B was removed from its support by Williams Power Corporation, rebuilt by Wyle Laboratories, and was reinstalled by Williams Power Corporation The snubber tubing cylinder was replaced due to corrosion of the cylinder Ref MIF 02041991 "8.

Test Conducted D--

Hydrostatic 1"1 Pneumatic Normal Operating Pressure M None [-] Other Pressure PSI Temperature OF

\\

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52 Job Number B13 - W002001523 ISheet 2

of 2

9.

Remarks (Applicable M~ianufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this replacement conforms to the rules of the ASME Code,Section XI repair or replacement Type Code Symbol Stamp Kii/A Certificate of Authorization Number Expiration Date N1At Signed ALiA I46 11, Date I t/Ar/

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by pr44v C_.,.

of 4R.44 haverinspected the components described in this Owner's Report during the period

/

to

,,/,Aiz

, and state that to the best of my knowledge and belief, the Owner Has performed examinations and taken 6orrective measures desciibed in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions A

..XZ.r National Board, State, Province, and Endorsements

~Date e-'M'p--t"T' ]Signature iSheet 2

of 2

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number I B13 -'

RT~pe: L1.52 WA68 1398 B13.

1 r

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

_____________October_

Otobe,14,200

3. Work performed by Type Code Symbol Stamp N/A Name: Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Reactor Coolant System

5.

(a) Applicable Construction Code:

ASME Section I11, 19 71 Edition Winter 1972

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Safety Valve Crosby N56963-01-0013 N/A P.O. QP-3079 1989 Replaced Yes Safety Valve Crosby N56963-01-0006 N/A P O FNP2-2 1975 Replacement Yes

7. Description of Work Pressurizer safety valve Q2B13V003 IA was removed from its installed position and shipped offsite for testing and, if required, refurbishment. A previously refurbished safety valve was installed in place of the removed valve. Ref: MIF 02041337.

8. Test Conducted L Hydrostatic [] Pneumatic Z

Normal Operating Pressure [] None [n Other Pressure PSI Temperature F__

F

heet 1 nf 9

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number BI3 -, WVA6S139R RType: L1.52 B13 WA68398 I

Sheet 2 of 2

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

The replacement valve was previously tested and refurbished by Wyle Laboratones under purchase order QP000272.

Certificate of Compliance We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XM.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authorization Number N/A Expiration Date N/A Signed Maintenance Manager Date

] /

/

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of.

and employed by of "have inspected the components ftescribed in this Owner's Report during thý period X/6' Z to

.______/.__,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions

-~

nsperA Si gnature 67-#-

a 9 2-AY11d7 National Board, State, Province, and Endorsements

1 D ate

,'hs/z of 2

`-

Date

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number B41 - V002005392 RT)pe: L1.52 I

Sheet I

of 2

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Pomer Company)

October 11, 2002

3. Work performed by Type Code Symbol Stamp N/A Name:

PCI Energv Services Authorization Number Address:

One Energy Drive N/A P. 0. Box 3000 Expiration Date Lake Bluff, IL 60044 N/A

4. Identification of System Reactor Coolant Pump

5.

(a) Applicable Construction Code:

ASME Section 111, 19 71 Edition Summer 1972

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N-416-1 Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Pipe Babcock & Wilcox 2535/2533/2540 N/A P. 0 FNP2-2 1979 Replaced Yes Pipe Changwon Specialty A53470 N/A P 0 QP020505 2002 Replacement No Steel

_ Iv I

_ I

_ I I__.

1*

t

-t 4

4 4

+

4 4

1

.i.

1

t 4

1 4

+

d I

,I.

7. Description of Work The Component Cooling Water outlet pipe from the thermal barrier of Reactor Coolant Pump Q2B41P0001B exibited indications of leakage between the pump casing and the first flange. The pipe was replaced. Ref MIF 02042220 K.

8. Test Conducted F-1 Hydrostatic 1:] Pneumatic

[* Normal Operating Pressure

["-

None

[-] Other Pressure PSI Temperature F__

F

Form NIS-2 Owner's Report for Repairs or Replacements RType: L1.52 As required by the provisions of the ASME Code Section XI Job Number

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

B41-W002005392 Sheet 2

of 2 The pipe to pump casing weld was made and liquid penetrant exarmned by PCI Energy Services under the PCI Quality Assurance Program The pipe to flange weld was made by Southern Nuclear Operating Company.

The pipe to flange weld was liquid penetrant examined by Sonic Systems Incorporated, Inc, under the SNC Quality Assurance Program.

Radiography of the pipe to flange weld was performed by GE Inspection Services under the SNC quality Assurance Program Certificate of Compliance We certify that the statements made in the report are correct and this replacement conformas to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp NIA Certificate of Authorization Number N/A Expiration Date N/A Signed Maintenance Manager Date L

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by F,cz-

.z7, of

-7;6 A 70,-/

__--_-___"7"_.

have inspected the components detcribed in this Owner's Report during the period

___,/

z to

/______

,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection

_____Commuissions 6:y.7 7-9 vetor's Signature National Board, State, Province, and Endorsements I\\_Date W

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI I

Job Number B41 -vV002005393 RT 3pe: L1.52 Sheet I

of 2

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

October I 1, 2002

3. Work performed by Type Code Symbol Stamp N/A Name:

PCI Energy Services Authorization Number Address:

One Enermv Drive N/A P. 0. Box 3000 Expiration Date Lake Bluff, IL 60044 N/A

4. Identification of System Reactor Coolant Pump

5.

(a) Applicable Construction Code:

ASME Section I11, 19 71 Edition Summer 1972

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N-416-1 Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes I No)

Pipe Babcock & Wilcox 2537/2539/2534 N/A P. 0 FNP2-2 1979 Replaced Yes Pipe Changwon Specialty A53470 N/A P. 0 QP020505 2002 Replacement No Steel

7. Description o0 Work The Component Cooling Water outlet pipe from the thermal barrier of Reactor Coolant Pump Q2B41P0001C exibited indications of leakage between the pump casing and the first flange The pipe was replaced and a base metal repair was performed on the pipe flange Ref: MIF 02042218.

Test Conducted Hydrostatic F

Pneumatic Normal Operating Pressure E-'] None Other Pressure PSI Temperature O_

OF

Form NIS-2 Owner's Report for Repairs or Replacements RT.Npe: L1.52 As required by the provisions of the ASME Code Section XI Job Number

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

B41 -W002005393 Sheet 2

of 2 The pipe to pump casing weld was made and liquid penetrant examined by PCI Energy Services under the PCI Quality Assurance Program The pipe to flange weld and pipe flange base metal repair was made by Southern Nuclear Operating Company The pipe to flange weld and pipe flange base metal repair was liquid penetrant examined by Sonic Systems Incorporated. Inc, under the SNC Quality Assurance Program Radiography of the pipe to flange weld and pipe flange base metal repair was performed by GE Inspection Services under the SNC quality Assurance Program Certificate of Compliance We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI repair or replacement

`Type Code Symbol Stamp N/A Certificate of Authorization Number N/A Expiration Date N/A Signed f

Maintenance Managcer Date 1-/ z Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by of have inspected the components de cribed in this Owner's Report during the period to

,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

_________Commussions A 3 Z

1,11petor's Signature National Board, State, Province, and Endorsements "Date A

_Z

Class 2

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number RType: L1.52 I

P16 11 0.AU

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

Jan. 25. 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operatine Companv-Outaee and Modifications Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Service Water

5.

(a) Applicable Construction Code:

ASME 111 19 71 Edition SUM 71

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Piping SNCO P16 N/A P16 HCB 2002 Replacement No WO# 21299 Valve Anchor/Darling EB4001-1 N/A Q2P16V075 1992 Replaced YES Flowserve Valve Corporation E548T-I-2 N/A Q2P16V075 2002 Replacement YES

7. Description of Work This report documents the replacement of check valve Q2PI 6V075 along with some pipe and pipe fittings per MWR 2000416 and Q-2-P16-(S0l-2-9760)-WO# 21299 per DCP SO1-2-9760. Piping (6"-HCB-8) was modified by addition of a slip on flange.

8. Test Conducted El Hydrostatic El Pneumatic Z Normal Operating Pressure E None F-Other Pressure __

PSI Temperature __O_

F

(*P 0714* tit

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RType: L1.52 Job Number PI6 DCP 9760.01 Sheet 2

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

See DCP Issue History Report and Traveler Bill of Materials for applicable Matenal Issue numbers Piping was modified per DCP SOI-2-9760 and Traveler Work Order No. Q-2-PI6-(SO0-2-9760)-WO# 21299 The Containment Isolation Check Valve Q2P16V075 was replace under the same Traveler Work Order No. Q-2-PI6-(SO0-2-9760)-WO# 21299 and Work Request No. 2000416 of 2 Manufacture's Data Report for the Replacement Valve is on file in P 0 # QP020087.

Certificate of Compliance We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authorization Number N/A Expiration Date N/A Signed

,&?"t A &.

O&M Manager Date 1 01,4/1*0 Owner or Owner's Designee, Title r

f Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

,,and employed by

,o Z

of S.

,have inspected the components described in this Owner's Report during the period 7//L /-z.,

to

/__.______,_

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

6*.

2 -__ 4, ' /

4, Commissions e-,,.'2-O,,*,,

Inspecrl-s-8ignature National Board, State, Province, and Endorsements Date

____A

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number Nil Di RT)pe : L1.52

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

June 14, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company-Outage and Modifications Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam

5.

(a) Applicable Construction Code:

See Sheet 2*

19 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

SUPPORT SNC

Nil, N/A SCS-2H220 2001 REPLACED NO DCP B01-2-9711

_WO#

1002188 SUPPORT SNC

NI1l, N/A SCS-2H220X 2002 REPLACEMENT NO DCP B02-2-9801 WO# 2003177 Nil PIPING SNC NI1 N/A EBB-I 2002 REPLACEMENT NO WO# 2003177

7. Description of Work This report documents the fabrication and installation of Main Steam piping supports in Unit 2 Containment per the requirements of DCP B02-2-9801. Modified Pipe Whip Restraint (2MSR-G4) to a dual acting Restraint/Support by deleting support SCS-21-1220 and adding restraint lugs to PWR that is identified as SCS-2H220X Modified piping (32"-EBB-I) by welding (2)Wear Plates (3"x 4"x4")to pipe

8. Test Conducted Hydrostatic 1'-

Pneumatic

[-1 Normal Operating Pressure

[

None n" Other Pressure PSI Temperature OF 7-CP 9801.01

qhpr*f 1

nr

Form NIS-2 Owner's Report for Repairs or Replacements RT)pe: L1.52 As required by the provisions of the ASME Code Section XI Job Number Nil DCP 9801.01 Sheet 2

of 2

\\

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

See DCP Issue History Report and Work Order Bill of Materials for applicable Material Issue numbers

Supports designed to AISC, 1969 and welded to AWS Requirements using material traceability requirements of ASME III Pipe designed to Section II1, 1971 Edition Summer 71 Addenda Support SCS-2H220 was deleted per DCP B02-2-9801, WO4 S02003177. Support SCS-2H220 was previously modified per DCP BOI-2-971 1, WO# S01002188 Pipe Whip Restraint 2MSR-G4 was modified to act as a dual Restraint/Support, by adding restraint lugs that's identified as support SCS-2H220X per DCP B02-2-9801, WO# S02003 177 32"-EBB-I, Main Steam Piping was modified by welding (2) Wear Plates (3/8"x4"x4") to pipe as shown on sheet 16, Detail 3 and sheet 17, Detail 4 of WO# S02003177 per DCP B02-2-9801 Certificate of Compliance We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authorization Number N/A Expiration Date N/A Signed

_ O&M Manager Date D_

,__,/__

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

__and employed by I,

of A..

have inspected the componerits described in this Owner's Report during the period

_____to

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

________Commissions e'.o..

5

"/L',,4 ln.Cr's Signature National Board, State, Province, and Endorsements Date

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RType: L1.52 Job Number N1l, WO# M02005926 &

W1"l1 v'%X~n#t4 gl*,qn Ml4U07.

I of~i~ 2ihf~'

,,*zvi i tiu~uu.

neet 1

01 Z

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

October 4, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Outage and Modifications Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam

5.

(a) Applicable Construction Code:

See Sheet 2

19 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Nameof Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Support SNC N1l N/A 2MS-R516 2002 Repaired No WO# M02005926 Support SNC NI I N/A 2MS-R517 2002 Repaired No WO# M02005927

7. Description of Work This report documents the weld repair of Main Steam piping supports 2MS-R516 & 2MS-R517 in the Unit 2 Main Steam Valve Room R

T-f (1/2,...4.

*1 E] Hydrostatic

[-' Pneumatic E:1 Normal Operating Pressure 0] None

[]

Other Pressure

-____PSI Temperature O

0F Y

Form NIS-2 Owner's Report for Repairs or Replacements RType: L1.52 As required by the provisions of the ASME Code Section XI Job Number NlI, WO# M02005926 &

N1l, WO# M02005927 Sheet 2

of 2

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

See DCP SO1-2-9722 Issue History Report and Work Order Bill of Materials for apphlcable Material Issue numbers

Supports designed to AISC, 1969 and welded to AWS Requirements using material traceabihty requirements of ASME III On WO# M02005926 repair to welds includes piece number I I to existing stanchion clamps to correct undercut on bottom side and piece number 12 to piece number 14 to correct undersize weld on bottom side.

On WO# M02005927 repair to welds includes piece number 15 to piece number 17 to correct undersize weld Certificate of Compliance We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authorization Nunber N/A Expiration Date N/A Signed

-J

^

6

/*,-'

'v1cjr-, O&M Manager Date Owner or Owner's Designee, Tie Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

_-_.,_____,,,,__and employed by

,Z.'

.e,

- c¢,.

of t'*'*

.i Z'.*..,

have inspected the components described in this Owner's Report during the period

!,_/_

A__/_o._Zto 7.__,__,_

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

_______________-_______Commissions

', 3-r" 2H*pj3tor's Signature National Board, State, Province, and Endorsements Date Z-,./',/

Z

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E21 - Nh RType: L1.52 T002001655 Sheet I of 2

1.

Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

__________________________________September Sepembe 26.200

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification Of System Chemical and Volume Control System

5.

(a) Applicable Construction Code.

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Mech Snubber Pacific Scientific 2319 N/A P.O FNP 2-29 1977 Replaced Yes Hyd Snubber Lisega 02615240 / 037 N/A P 0 QP020295 2002 Replacement No I.

Description U1 WVorK Snubber SS-12722 was removed from its support by Williams Power Corporation. tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02041217

8.

Test Conducted D

Hydrostatic

] Pneumatic [-'

Normal Operating Pressure ['

None Other Pressure PSI Temperature OF

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E21 - W002001655 RType: L1.52 ISheet 2

of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section II Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code, Section Xl replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp Certificate of Authorization Number NJ/1A, MkirArA otWt-,

Owner or Owner's Designee, Title Expiration Date Date to,/Ibo Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by 9,&,-:Ve 4

of

___,_____________4*~

have inspected the components described in this Owner's Report duringthe period to

,and state that to the best of my knowledge and belief, the Owner has performed examinations and takefi corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

$-/

'pector's Stgnatuile Commissions

-,-z.3Z-National Board, State, Province, and Endorsements Signed

\\]4Date X'A/4 L4 &

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RTpe: L1.52 Job Number E21 - W002001657 Sheet I

of 2 S1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

September 29, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Chemical and Volume Control System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Mech Snubber Pacific Scientific 11181 N/A P 0 QP0542 1986 Replaced Yes Hyd Snubber Lisega 02615240 / 021 N/A P 0 QP020295 2002 Replacement No

.1.

1

.1

.1 1

__.1.

1 I-

+

.4

.1.

£ I

.i. ______

.1.

.L 4-1 ______

7.

Description Of Work Snubber SS-12723 was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref. MIF 02041258

-'8.

Test Conducted FD Hydrostatic 1

Pneumatic 1

Normal Operating Pressure Z None [:] Other Pressure PSI Temperature F__

F

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52 Job Number E21 - W002001657 ISheet 2 of 2

9.

Remarks (Applicable Manuiacturer's Data Reports T0 oie Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requniements ot ASME Section III Certificati We certify that the statements made in this report are correct and this ASME Code,Section XI e of Compliance replacement repair or replacement conforms to the rules of the i Type Code Symbol Stamp

,.4/A Certificate of Authorization Number t-1/,&

Signed Expiration Date Date j

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by, j,,-i,4,L..

,,nA.

AL of

.PA,..

?A¢ej.. _Z'.t,,

have inspected the components described in this Owner's Report during the period to Z

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken cbrrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions Y, Z

_,- 4f, ectorisq ignaturei National Board, State, Province, and Endorsements K.1 Date I Sheet 2 of 2 tj /A.

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E13 - W002001640 RT3pe: L1.52 Sheet I

of 2

1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

____________Septe___beSetembr,300200

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Containment Spray System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section Xl Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASAIE Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped

__(Yes I No)

Mlech Snubber Pacific Scientific 13622 N/A P.O. 72351 1980 Replaced No Forward Bracket Pacific Scientific N2728A NIA PO QP1536 1987 Replaced No Bracket Bolts Pacific Scientific Unknown N/A P0 23584 1984 Replaced No Mech. Snubber Pacific Scientific 2835 NIA P 0 FNP 2-29 1978 Replacement No Forward Bracket Basic - PSA Inc N1876 N/A PO QP010793 2001 Replacement No Bracket Bolts Basic - PSA Inc N3208 N/A PO QP010793 2001 Replacement No

7.

Description Of Work Snubber 2CS-R266B was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with another mechanical snubber by Williams Power Corporation as part of a scheduled upgrade program The forward bracket and bolts were replaced for convenience due to the location of the snubber. Ref MIFs 02042224 & 02042198

\\,.__

8.

Test Conducted j

"' Hydrostatic Pressure D

Pneumatic 1-"

Normal Operating Pressure [

None E] Other PSI Temperature ___

OF

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section X1 Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI replacement repair or replacement conforms to the rules of the Si jType Code Symbol Stamp Certificate of Authorization Number Signed Owner or Owner's Designee, Title Expiration Date Date t/h Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of e-.-,'*p.

and Employed by

,,e el-of

_ ;e have inspected the components described in this Owner's Report during the period

_h_ _

toy

,e

, and state that to the best of my knowledge and belief, the Ownerlhas performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable m any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

ý or's Signature Commissions a-,s YZf

.Z9A, National Board, State, Province, and Endorsements

-! f. ý;

-Z Date RType: L1.52 I ý

-k4 A M/A J

tnAA- ^4 6yq.-

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number RT.pe: L1.52 Y

Ell Ofl d0hetIo

1. Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

September 29, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address :

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Safety Injection System

5.

(a) Applicable Construction Code:

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Tubing Cylinder Grinnell Unknown N/A P0 FNP 2-29 1981 Replaced No Tubing Cylinder Grinnell Unknown N/A P 0 QP5148 1990 Replacement No I.

Descript~ion Ofi Work Snubber 231-tR,1.3 was removed from its support by Williams Power Corporation, tested by Wyle Labora and was reinstalled by Williams Power Corporation The snubber tubing cylinder was replaced due to corr Ref. MIF 02041943

8.

Test Conducted H

iydrostatic

[-] Pneumatic R Normal Operating Pressure Z None [--

Other Pressure PSI Temperature OF tories, rebuilt by Wyle Laboratories, osion of the cylinder.

VOOOO1AQR Sheet I of 2

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52 Job Number Ell -N1002001498 I Sheet 2

of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI.

Certificate of Authorization Number Signed Signd Dte A.F-

.4-1 J?

Owner or Owner's Designee, Title K_ I Type Code Symbol Stamp replacement Expiration Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of _

d__

and Employed by of r-¢

?-*.

invirspected the components described in this Owner's Report during the period

_____to

z.e"/

"Z

, and state that to the best of my knowledge and belief, the Owner'has performed exammations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

?5pctor's Signature Commissions 6,.,5'zg National Board, State, Province, and Endorsements K-" Date 1 1 3m -I A.

Date 10 I/.>

it conforms to the rules of the repair or replacement Sug" tta d.*-

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E13-'A¢002001639 RType: L1.52 Sheet I

of 2

1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

_____________________________________September 30, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph AM. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Containment Spray System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Mech Snubber Pacific Scientific 13615 N/A P 0 72351 1980 Replaced No Forward Bracket Pacific Scientific N2728A N/A PO QP1536 1987 Replaced No Bracket Bolts Pacific Scientific Unknown N/A P 0 23584 1984 Replaced No Mech Snubber Pacific Scientific 503 N/A P 0 FNP - 222 1977 Replacement No Forward Bracket Basic - PSA Inc.

N1648 N/A PO QP010793 2001 Replacement No Bracket Bolts Basic - PSA Inc.

N3208 N/A PO QP010793 2001 Replacement No

1.

Description Of Wyork Snubber 2CS-R266A was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with another mechanica snubber by Williams Power Corporation as part of a scheduled exchange program The forward bracket and bolts were replaced for convenience due to the location of the snubber. Ref. MIFs 02041190 & 02042199

,8.

Test Conducted 8

Hydrostatic c

Pneumatic [:

Normal Operating Pressure [

None M Other Pressure PSI Temperature F__

F

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT~pe: L1.52

. r=

s: kAppiicabue rdanuiactureirs Data Reports To Be Attached)

Job Number E 3-W00200A1o 61 Sheet 2

of 2

-A a D

11.

3--~'--

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp i-W1A~

Certificate of Authorization Number Signed Owner or Owner's Designee, Title Expiration Date Date D11 /

D "1 Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by

_Z,,___

of

,a.

,have inspected the components described in this Owner's Report during the period _,___

_to 7__,,

, and state that to the best of my knowledge and belief, the Owner'has performed examinations and taken cbrrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concernmg the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal mjury or property damage or loss of any kind arising from or connected with this inspection.

'frector's Signature Commissions 6',

TZ9

.VA44 National Board, State, Province, and Endorsements QJ~ae

/64/4Zi Owe o

wnrM eIAne il 1i Date

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RType: L1.52 Job Number NlI, WO# M02005926 &

NI11 WO# M02052M~771 S.

.. ~

m

-~u,...-

C

J

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

October 4. 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operatine Company Outaee and Modifications Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam

5.

(a) Applicable Construction Code:

See Sheet 2

19 Edition N/A Addenda.

N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A Addenda.

N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME "Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Support SNC N11 N/A 2MS-R516 2002 Repaired No WO# M02005926 Support SNC NI 1 N/A 2MS-R517 2002 Repaired No WO# M02005927

7. Description of Work This report documents the weld repair of Main Steam piping supports 2MS-R516 & 2MS-R517 in the Unit 2 Main Steam Valve Room

8. Test Conducted i-Hydrostatic I-] Pneumatic l Normal Operating Pressure

[Z None I]

Other Pressure PSI Temperature O

0F 1

4"

Form NIS-2 Owner's Report for Repairs or Replacements RType: L1.52 As required by the provisions of the ASME Code Section XI Job Number Nil, WO# M02005926 &

Nl1, WO# M02005927 Sheet 2 of 2

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

See DCP S01-2-9722 Issue History Report and Work Order Bill of Materials for applicable Material Issue numbers

Supports designed to AISC, 1969 and welded to AWS Requirements using material traceability requirements of ASME III On WO# M02005926 repair to welds includes piece number 11 to existing stanchion clamps to correct undercut on bottom side and piece number 12 to piece number 14 to correct undersize weld on bottom side On WO# M02005927 repair to welds includes piece number 15 to piece number 17 to correct undersize weld Certificate of Compliance We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authorization Nurber N/A Expiration Date N/A Signed O

( Q..

6 ',

1 O&M Manager Date

/

2.

Owner or Owner's Designee. Tdie Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by

,,,,e

,e--,L of

-7 eAL Z.o,,,

have inspected the components described in this Owner's Report during the period

/0___

A to 10Z,4/1 ' 2

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken 1corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

---....g4 tK*&-,,*

Commissions d,,, 53.

.. 27A.',

,!lp or's Signature National Board, State, Province, and Endorsements Date Z/,',

/

Z

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number NIl - W002001597 RT3pe: LI.52 q

Sheet I

of 2

1. Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

September 26, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Mare Steam System

5.

(a) Applicable Construction Code:

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Load Stud Pacific Scientific 2830 N/A PO QP1536 1987 Replaced No Load Stud Nuts Pacific Scientific Unknown N/A P 0 FNP 2-29 1981 Replaced No Load Stud Pacific Scientific None N/A P 0 QP3129 1989 Replacement No Load Stud Nuts Pacific Scientific None N/A P 0 QP3129 1989 Replacement No

7.

Description Of Work Snubber SS-13242A was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was reinstalled by Williams Power Corporation The load stud and load stud nuts were replaced as a result of damage during snubber removal Ref. MIF 02041199

8.

Test Conducted H

Hydrostatic

[--

Pneumatic M Normal Operating Pressure [

None [

Other Pressure PSI Temperature OF Z

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType : L1.52 Job Number N11 - W002001597 ISheet 2

of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI.

Type Code Symbol Stamp Certificate of Authorization Number I % 1A replacement repair or replacement Expiration Date conforms to the rules of the 1'ýi h Signed Owner or Owner's Designee, Title Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by 6-'. of have inspected the components described in this Owner's Report during'the penod to

,/.*'ZT,, -?-

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken dorrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector not his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

oJi;sCebr's Signature

\\-*1 Date Commissions AM :%1-9 National Board, State, Province, and Endorsements (e' y/

-

I Sheet 2

of 2

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number G...

24 -

V.

AOA1 S e.

1. Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

September 26, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Steam Generator Blowdown Treatment System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Mech Snubber Pacific Scientific 20439 N/A PO QP1470 1987 Replaced No Hyd Snubber Lisega 02615240 / 038 N/A P 0 QP020295 2002 Replacement No RT)pe: L1.52 Snubber SS-12848C was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02041261

8.

Test Conducted j Hydrostatic

[]

Pneumatic [:] Normal Operating Pressure [7 None Other Pressure PSI Temperature F__

F

NOgfifil*l Sheet I

of 2

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section X1 Job Number I G24 -M

9.

Remarks (Applicable Mianufacturer's Data Reports To Be Attached)

RT)pe: L1.52 T002001661 I Sheet 2

of 2

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements ot ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp Certificate of Authorization Number Expiration Date

____/_

Signed Owner or Owner's Designee, Title Date I,/Li/. t..L Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 495,!ý and Employed by of

'-e /

have tnspected the components described in this Owner's Report during the period

/

to

,7-.________

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desci ibed in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

ser's Commissions Ntn 7Z9 d State Pn

,, 'nspector's Signature National Board, State, Province, and Endorsements t-4-/A

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RType: L1.52 Job Number E21 - W099005644 Sheet I

of 2

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

July 21, 2001

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Chemical And Volume Control System

5.

(a) Applicable Construction Code:

ASME Section Ii, 19 86 Edition 1986

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number "

Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Seal Housing, Pacific 2E299-AD N/A P 0 QP-3929 1989 Replaced No Outboard Seal Housing, Pacific 2E299-AE N/A P 0 QP-3929 1989 Replaced No Inboard Seal Housing, Pacific 2E299-AH N/A P. O QP-3929 1989 Replacement No Outboard Seal Housing, Pacific 34409-AB N/A P 0. QP960582 1994 Replacement No Inboard

7. Description of Work The outboard seal was reported to be leaking on Charging Pump Q2E21P0002B. The outboard seal housing assembly was replaced with a previously refurbished assembly.

8. Test Conducted

[D Hydrostatic L-- Pneumatic E

Normal Operating Pressure

[R None

[L] Other Pressure PSI Temperature F__

F

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RType: L1.52 Job Number E21 - W099005644 I Sheet 2 of 2

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

The replacement seal housing assembly was removed from Charging Pump Q2E2 1P0002A under work order 20006337 and refurbished by SNC under work order 01002994.

Certificate of Compliance We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section Xl.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authorization Number N/A Expiration Date N/A Signed

& t7;..

Maintenance Manager Date 112-__r Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

__and employed by

2

'7 IAA,, 2 of

.Z2'ei*Ai.'s'*.

£A*,*,*e.

-Z"iL.v9-have inspected the components described in this Owner's Report during the period

___to 1-141,-z-

, and state that to the best ofmy knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions I

" Z,19

,Js eo? S Signatuir National Board, State, Province, and Endorsements K-' f Date z.

Date

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E21 - NN RTjpe: L1.52 002001660 Y

Sheet I of 2 1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October 1, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Chemical and Volume Control System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped No.__Replacement_(Yes

/ No)

Mech. Snubber Pacific Scientific 37965 N/A P.O. QP1470 1987 Replaced No Hyd Snubber Lisega 02615240 / 042 N/A P.O QP020295 2002 Replacement No I.

Description U0 Work Snubber SS-12766 was removed from its support by Southern Nuclear, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref. MIF 02041260

-'8. Test Conducted

[D Hydrostatic D

Pneumatic []

Normal Operating Pressure Z None F Other Pressure PSI Temperature F__

F

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT-.pe: L1.52 Job Number E21 - W002001660 ISheet 2

of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III replacement repair or replacement Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI Type Code Symbol Stamp 14M/

Certificate of Authorization Number fim4,vr A4 Dat Signed Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

_en72 and Employed by

,-_7____.4 have inpected the components described in this Owner's Report during the period

__-__to and state that to the best of my knowledge and belief, the Owner bas performed examinations and taken 'corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

lrepetior'giSignature Commissions 4--A*T 'Z Y ZA.X National Board, State, Province, and Endorsements Date conforms to the rules of the Expiration Date t, I/IAý Date 1-11-2 /-ý X'-

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E13 - W002001637 RT)pe: L1.52 Sheet I

of 2 I.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

____________Septe____bSepembe,30,200

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Containment Spray System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Mech Snubber Pacific Scientific 2168 N/A P 0 FNP 2-29 1978 Replaced No Forward Bracket Pacific Scientific Unknown N/A P 0 FNP 2-29 1981 Replaced No Bracket Bolts Pacific Scientific Unknown N/A PO FNP2-29 1981 Replaced No Mech. Snubber Pacific Scientific 501 N/A P.O. FNP -222 1977 Replacement No Forward Bracket Pacific Scientific N2771A N/A P O QP 1772 1987 Replacement No Bracket Bolts Nova Machine 8092338 N/A PO QP010575 2001 Replacement No Products Corp

1.

uescripton Of Work Snubber 2CS-R202B was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with another mechanical snubber by Williams Power Corporation as part of a scheduled replacement program The forward bracket and bolts were replaced for convenience due to location of snubber. Ref. MIFs 02041185 & 02042201 7

"8.

Test Conducted I

-D Hydrostatic 1

Pneumatic R Normal Operating Pressure 0 None R Other Pressure PSI Temperature OF

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT 3pe: LI.52 Job Number E 3 W00)A1 0 151-7 I Sheet 2 of2

9.

Remars vplablv M

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this replacement conforms to the rules of the ASME Code,Section XI.

repair or replacement Tye. Code Symbol Stamp kI/A Certificate of Authorization Number I/A Expiration Date Signed oLDate Oner or Owner's Designee, Title I

Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by,

,e of Az.

,haveeinspected the components described in this Owner's Report during the period

_A_,_A

_Z to

/,'g!q 7-

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken'cofrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection

(-t1ll'sctbr's Signature Commissions 6 -

' Z9 National Board, State, Province, and Endorsements

".-- I-'Date 2

nf 9

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number G24 -

1O02001l&*

RType: L1.52 Sheet I of 2 S1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October 2, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification Of System Steam Generator Blowdown Treatment System

5.

(a) Applicable Construction Code:

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped No. __Replacement_(Yes

/ No)

Mech Snubber Pacific Scientific 1221 N/A P.O QP0542 1986 Replaced Yes Hyd Snubber Lisega 02615240 / 026 N/A P 0 QP020295 2002 Replacement No

7.

Description Of Work Snubber SS-12848D was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02041263

,8.

Test Conducted F

Hydrostatic M Pneumatic [:] Normal Operating Pressure Z None [

Other Pressure PSI Temperature F__

F k

,L

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52 Job Number G24 - W002001662

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

I Sheet 2 of 2

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

.__,,_/

and Employed by,-,.-.,1 of

.._:,?;.4.s';,,-,,"%

.,S-,4 have inspected the components described in this Owner's Report during the period V//

to

,/*

t

-Z

, and state that to the best of my knowledge and belief, the Owner has performed examinations and takeh corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions 41_A yTzg9 Sspectors Signature National Board, State, Province, and Endorsements 1DateZ Certificate of Compliance We certify that the statements made in this report are correct and this replacement conforms to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp t*4 J Certificate of Authorization Number

_,_/A_

Expiration Date NIA.

Signed

/

4r-u...r A

Date Owner or Owner's Designee, Title

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number NI l -N RT~pe: L1.52 TO0200 1497 Sheet I of 2

1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October 2, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Main Steam System

5.

(a) Applicable Construction Code:

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, NIA Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components :

Name Of Manufacturer Manufacturer Serial Number National Board No.

Other Identification Year Built Repaired Replaced Or Replacement

-F i

I Grinnell Unknown N/A P.O FNP2-29 1981 Replaced ASME Code Stamped (Yes / No)

No I

+

4

+

4 Orifice Valve Grinnell Unknown N/A PO QPI546 1987 Replacement No Stems (2)

7.

Description Of Work Snubber 2MS-R807 was removed from its support by Southern Nuclear, tested and rebuilt by Wyle Laboratories and was reinstalled by Southern Nuclear The snubber orifice valve stems were replaced as a result of damage during removal Ref MIF 02041400 Name Of Component Orifice Valve Stems (2)

8.

Test Conducted D

Hydrostatic 1:- Pneumatic 1 Normal Operating Pressure

[

None [

Other Pressure PSI Temperature __O_

F

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT3pc: L1.52 Job Number NI I-She2014t 2 of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this replacement conforms to the rules of the ASME Code,Section XI repair or replacement Type Code Symbol Stamp rI/A Certificate of Authorization Number Expiration Date Signed t'

,lu 7-igkj'L-Date

_71_i>_--

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by,

c, of S,

-have mispected the components described in this Owner's Report durmg the period 0,__"_,_7 _

to

, and state that to the best of my knowledge and belief, the Owner'has'performed examinations and takeh c6rrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

,-~cor' Sigau-i Commissions 4;4 -2:.

7

/,

National Board, State, Province, and Endorsements

",,- I -"Date f--

ISheet 2 of 2

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E21 - 'V1002001647 RType: L1.52 Sheet I

of 2 1 1. Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October I, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Chemical and Volume Control System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped

"___(Yes

/ No)

Mech Snubber Pacific Scientific 38322 N/A P.O. QP2244 1988 Replaced No Hyd Snubber Lisega 02615240 / 022 N/A P.O QP020295 2002 Replacement No t

-t 4

4 J

1-

+

4

.4.

-4.

i

+4-4

¶

-t I-

+

4-1 L

I

-f 1

4-4-

4 4

4 L _________

7.

Description Of Work Snubber SS-12634 was removed from its support by Southern Nuclear, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02041201 Test Conducted Fý Hydrostatic

[F] Pneumatic D Normal Operating Pressure [7 None F Other Pressure PSI Temperature O F

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E21 - W002001647 RType: L1.52 ISheet 2

of 2

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)IShe

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements ol ASME Section IH]

Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI replacement conforms to the rules of the repair or replacement Type Code Symbol Stamp Certificate of Authorization Number Signed N /A Owner or Owner's Designee, Title Expiration Date Date t)>I7 /0

(-.

Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by of,.

^

of have Inspected the components described in this Owner's R~eport during the period to

,-,-/-.

, and state that to the best of my knowledge and belief, the Ownerlhas ierformed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector noi his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

SCommissions A4 -TZ 9 I r

ýor's Signature National Board, State, Province, and Endorsements M /A

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E

P1-V RT)pe: L1.52 E21 00

-R SetIo

1. Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October 1, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Safety Injection System

5.

(a) Applicable Construction Code.

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped

"-- __(Yes

/ No)

Mech Snubber Pacific Scientific 2811 N/A P 0 FNP 2-29 1978 Replaced Yes Hyd Snubber Lisega 00614810 /054 N/A PO QP010567 2001 Replacement No

7.

Description Of Work Snubber SS-12762A was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02040840 S

CoL dUIIUUcteU D

Hydrostatic E] Pneumatic [-] Normal Operating Pressure None jj Other I

Pressure PSI Temperature OF

TNO)OOI*R Sheet I

of 2

\\

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52 Job Number E21 - W002001658

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

ISheet 2 of 2

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code, Section Xl.

replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp Certificate of Authorization Number Signed M /&.

&-I/A Owner or Owner's Designee, Title Expiration Date Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

__,,,__and Employed by,,

6i.. of

"_______________________________________.__.___

have inspected the components described in this Owner's Report during the period to_1e,11,-1,,to

z.

, and state that to the best of my knowledge and belief, the Owner has performed examinations and take'n corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable m any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Irep'-todrs Signature Commissions 3

- r--**4 National Board, State, Province, and Endorsements Date ILI IA.

MA~lr A 6tt-

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number E21 - W002001659 RT~pe: L1.52 U

Sheet I

of 2

1. Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October 1, 2002

3. lWork Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Safety Injection System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped

___(Yes

/ No)

Mech Snubber Pacific Scientific 2801 N/A PO FNP 2-29 1978 Replaced Yes Hyd Snubber Lisega 61299 141 N/A PO QP960460 1996 Replacement No

_ I L__

I

_ I I

I I

7.

Description Of Work Snubber SS-12762B was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02040841

18.

Test Conducted

[

Hydrostatic 0

Pneumatic D Normal Operating Pressure [7 None 1"- Other Pressure PSI Temperature F__

F

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number 1 -

WTA~i1~Cf l

raa et rn t,

1

9.

Remarks (Anplicbe ahI inifactrteir's Da~ta, Renn-t T

lA4,L---

r-2AtU J

L

.t1 4LJ RType: L1.52

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificati We certify that the statements made in this report are correct and this ASME Code,Section XI eof Compliance replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp N 1A Certificate of Authorization Number Expiration Date Signed Owner or Owner's Designee, Title Date 1

h Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 6,,.,4 and Employed by,cW

ý- -I'--. -;.

of

,ZZ,4 have inspected the components described m this Owner's Report during the period

_Z to

.14__,11-_le

, and state that to the best of my knowledge and belief, the Owner has performed examinations and takeh corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

~4~ctor's Signature Commissions 6--,0 Z

T

..Z-A,,

National Board, State, Province, and Endorsements Date WN/A

-_*/'

baTu

/A e5iýW4-s-i, AMu r N kt-r I

4L e )

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number 171) 1 X

L.*.h,1-y '..'JU/UJIUYt*J

.-," [=s UI

/

1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October I, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Chemical and Volume Control System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped

((Yes I No)

Mech Snubber Pacific Scientific 10329 N/A P 0 QP0542 1986 Replaced Yes Hyd Snubber Lisega 02615240 / 044 N/A P 0 QP020295 2002 Replacement No RType: L1.52 q

'7.

fleer'rintinn AfU'nA' Snubber SS-12639 was removed from its support by Southern Nuclear, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02041205 A.

Test Conducted F-1j Hydrostatic

[]

Pneumatic Normal Operating Pressure 0 None [-

Other Pressure PSI Temperature F__

F 7*A*n*I*A*

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT)pe: L1.52 Job Number 0~

V.-A1Lh-~

A I

hi-~

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp Certificate of Authorization Number Signed 14./A

/~'/-~1-~--

M.4 A

tlA IV P 61L~

Owner or Owner's Designee, Title Expiration Date Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

,_and Employed by c d-e t2,-of

,o, have inspected the components described in this Owner's Report during the period to

.,,_,/-_.

Z

, and state that to the best of my knowledge and belief, the Ownerihasperformed examinations and takeni corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

I-Dtor's Signature Commissions (5:4.3*Z g National Board, State, Province, and Endorsements I b/ 71 0"-

11 -[DateM vp

.t ptanu C~~tLture sl Data R~eports I o Be Attached)

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number 1-2

(~A RType: L1.52

,J

.ULVUL10..

I

.-a

-1

1.

Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, A]. 36319 Date (as agent for Alabama Power Company)

October I, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address :

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Steam Generator Blowdown Treatment System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Mech Snubber Pacific Scientific 3521 N/A P.O FNP 2-29 1978 Replaced No Hyd. Snubber Lisega 01615120 /007 N/A P 0 QP020295 2002 Replacement No

7.

Description Of Work Snubber SS-12942A was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with a Lisega hydraulic snubber by Williams Power Corporation as part of a scheduled upgrade program Ref MIF 02041276 j

8

.Test Conducted

[ D Hydrostatic Pneumatic D-Normal Operating Pressure Z None [--I Other Pressure PSI Temperature OF l

C "1

Form NIS-2 Owner's Report For Repairs Or Replacemdnts As Required By The Provisions Of The ASME Code Section XI Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code, Section Xl.

replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp Certificate of Authorization Number Signed tdTh

2i

Owner or Owner's Designee, Title Expiration Date N /A wit'

/"

/l.r MirrL Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of _

_,_-____and Employed by f

have irrspected the components described in this Owner's Report during the period to

.,"yewZ

,and state that to the best of my knowledge and belief, the Owner as pierformed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection Commissions (5;e

-,Z7

-. Z-A/4 National Board, State, Province, and Endorsements 4 "Date RType: L1.52 t

lo I-

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k"*[ate

~o' Signature

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number I NIl.V RType: L1.52 1. Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October 2, 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Main Steam System

5.

(a) Applicable Construction Code

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Orifice Valve Gnnnell Unknown N/A P 0 FNP 2-29 1981 Replaced No Stems (2)

Orifice Valve Grinnell Unknown N/A PO QP1546 1987 Replacement No Stems (2) nninnu Ir C11 Shee I

fF, Snubber 2MS-R808 was removed from its support by Southern Nuclear, rebuilt by Wyle Laboratories and was reinstalled by Southern Nuclear.

The snubber orifice valve stems were replaced as a result of the replaced stems discovered as scored during rebuild Ref MIF 02041345

8.

Test Conducted 1

-" Hydrostatic E-'

Pneumatic "

Normal Operating Pressure Z None [* Other Pressure PSI Temperature OF JNfigfifi1*99

.*h wwt 1

nf" 9

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number "XTd I I Wnl nn"i~l/*l Mu~~~~[-

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r 1),~

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11II RType: L1.52

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.uriLurr s*at u3ia Reports 10 oJe Artacned)

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements ol ASME Section III Certificate We certify that the statements made in this report are correct and this ASME Code,Section XI.

of Compliance replacement repair or replacement conforms to the rules of the i Type Code Symbol Stamp

NIA, Certificate of Authorization Number Signed

- ba IA.

Expiration Date N__

___/A Date

/

1/ -/,tLZ.

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and Employed by r

!0of S.

,-*Z have inspected the components described in this Owner's Report during the period

.____/_-__.._to

,/.'r,7-z

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nol his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions

..-4 XZ0 National Board, State, Province, and Endorsements I - -

I *'tor's Signature E-,oUA

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52

1. Owner Southern Nuclear Operating Company 40 Inverness Center Parkway Birmingham, Alabama 35242 (as agent for Alabama Power Company)

Job Number N12 - W002001503 Farley Nuclear Plant Highway 95 South Columbia, Al. 36319 I Sheet I of 2 Unit FNP 2 Date

3. Work Performed By Type Code Symbol Stamp I

N/A Name: Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4.

Identification Of System Auxiliary Steam System

5.

(a) Applicable Construction Code.

See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Snubber Tie Rod Grinnell Unknown N/A P 0 FNP - 222 1977 Replaced No Snubber Tie Rod Gnnnell Unknown N/A P 0 23612 1983 Replacement No ASL3S5OctoberJ 2

)Un, es cl.i pJl onl orl)Vl Snubber 2AS-R42 was removed from its support by Southern Nuclear, rebuilt by Wyle Laboratories and was reinstalled by Southern Nuclear.

The snubber tie rod was replaced as a result of damage during removal Ref MIF 02041399

8.

Test Conducted j'-- Hydrostatic

[-] Pneumatic 1:J Normal Operating Pressure [7 None n Other Pressure PSI Temperature Sheet I of 2

rtnh*r9 9NN9

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RT)pe: L1.52 Job Number

9.

Remarks (Applicable Manufacturer's Data Reports To Be Attached)

N12 P-pe hanger weI Sheet 2

of 2

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASME Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI replacement repair or replacement conforms to the rules of the l

Type Code Symbol Stamp Certificate of Authorization Number Signed Owner or Owner's Designee, Title Expiration Date Date

/

Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

._______.,,__and Employed by C'e of

/

have inspected the components described in this Owner's Report during the period

!/4.'1.0 7 to

/___/

_______,and state that to the best of my knowledge and belief, the Owner fas performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection oSgt NSCommissions e-ýctor's Signature National Board, State, Province. and Endorsements Date N /A D-Av 2

of 2

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI Job Number G

1M Oheet 1 1. Owner

2.

Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Al. 36319 Date (as agent for Alabama Power Company)

October 3. 2002

3. Work Performed By Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification Of System Steam Generator Blowdown Treatment System

5.

(a) Applicable Construction Code See sheet 2, 19 Edition

Addenda, Code Case (b) Applicable Section X1 Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification Of Components Repaired Or Replaced and Replacement Components:

Name Of Name Of Manufacturer National Other Year Repaired ASME Component Manufacturer Serial Number Board Identification Built Replaced Or Code No.

Replacement Stamped (Yes / No)

Hyd. Snubber Lisega 9761406/47 N/A P 0 QP980185 1998 Replaced No Hyd Snubber Lisega 61287 / 79 N/A P 0 QP950277 1995 Replacement No RT~pe: L1.52

'I Snubber SS-12848A was removed from its support by Williams Power Corporation, tested by Wyle Laboratories and was replaced with another Lisega hydraulic snubber by Williams Power Corporation as a result of it failing the "as found" functional test.

J.

Test Conducted Hydrostatic Pneumatic [-1 Normal Operating Pressure 0 None [-

Other Pressure PSI Temperature O

0F VO07OD1 *qA Sheet I

of 2

Form NIS-2 Owner's Report For Repairs Or Replacements As Required By The Provisions Of The ASME Code Section XI RType: L1.52

7.

Remularks tAppzicable vanuraicturer s Data Reports I o Be Attacnea)

Job Number G24 - W002001 594 I Sheet 2 of 2

Pipe hanger was designed to AISC requirements and welded to AWS requirements using material traceability requirements of ASMIE Section III Certificate of Compliance We certify that the statements made in this report are correct and this ASME Code,Section XI.

replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp Certificate of Authorization Number Signed F

/k1411t!7-4t v Owner or Owner's Designee, Title

xpiration Date Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Piessure Vessel Inspectors and the State or Province of

,,__,_,__and Employed by,cvc:a--,

6 of have inspected the components described tn this Owner's Report during the penod Z//r//,

7 to n/*/

/e,

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desciibed in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection IFIr~or'-s Signature Commissions 6 :,f

' -*l

,-Al National Board, State, Province, and Endorsements

'Date

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nl - v v

7

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI ob Number nloi.

RType: L1.52

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company) 1 October 2, 2002

3. Work performed by Type Code Symbol Stamp N/A Name: Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Steam Generator

5.

(a) Applicable Construction Code:

ASME Section 111, 19 89 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N-496-1 Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped

____(Yes

/ No)

Helicoil Emhart Fastening 95582 N/A P. O QP020515 2001 Replacement No Teknologies pr i ___

I

'r

7. uescripton of Work In removing handhole cover IOC on Steam Generator Q2B2H-0001C, four bolts were galled. The # 3 and 4 bolt holes were successfully tapped after bolt removal, however, helicoils had to be installed in bolt holes # I and 7 to facilitate re-installation of the bolts. Ref: MIF 02042544.

Ii 8. T est C o n d u cte d 1 P e m t c r 7 S

Hydrostatic Pneumatic Normal Operating Pressure E

None El Other Pressure PSI Temperature F__

F A*P

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RT~ype: L1.52 IJob Number B21 - W002005582 ISet2 of 2

9.

Remarks tApplIcao)e Manutacturer's Data Reports to be attached)

I Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code, Section XM.

replacement repair or replacement conforms to the rules of the

,Type Code Symbol Stamp Certificate of Authorization Number Signed X

N/A Owner or Owner's Designee. Title Expiration Date N/A Maintenance Manaizer Date ZZ/ ly/ ý t...

Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

_.,_,_._/.

___and employed by e 6

WA of L-"AM00 have inspected the components described in this Owner's Report during the period to

/Z-

//,/

z.

, and state that to the best of my knowledge and belief; the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

lnVClc7's Signature Commissions el--W 3Z*'

...*-t, National Board, State, Province, and Endorsements i~t z_

N/A

\\-,.Date 2

of 2

" -- -Z-', Z ele- ý. 6 ý ý

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number 1B21 - AA RT)pe : L1.52 002005636 "1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company1 1

October 14, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Steam Generator

5.

(a) Applicable Construction Code:

ASME Section III, 19 89 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N-496-1 Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped

.__(Yes

/ No)

Helicoil Emhart Fastening 95582 N/A P. O QP020515 2001 Replacement No Teknologies

7. Description of Work In removing handhole covers IOC and IOD on Steam Generator Q2B21H-0001B, several bolts were galled. Helicoils were installed in bolt hole #

3 on the I OC cover and in bolt hole # 8 on the 1OD cover. Ref: MIF 02042544.

5. Test Conducted

[:

Hydrostatic n

Pneumatic

[

Normal Operating Pressure LI None DI Other Pressure PSI Temperature OF Sheet 1 of 2

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number Bi21 -IA0053 Sheet 2 of 2

7.

Remarks tAppcaDIe Mlanulacturer's Data Reports to be attached)

Certificat We certify that the statements made in the report are correct and this ASME Code,Section XI.

e of Compliance replacement repair or replacement conforms to the rules of the

-Type Code Symbol Stamp Certificate of Authorization Number Signed 91ý2or IOwner or Owi N/A N/A rner's Desienee. Title Expiration Date Maintenance Manager Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by

,,,7, s$

.0e,,- 6 A/e

,A of

, eA

.~e."-

have inspected the components des,'cribed in this Owner's Report during the period

,/z_.s-/_

to

/____/_'

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

!Atedor's Signature Commissions 1/W YZ.,

...Z2 4"

National Board, State, Province, and Endorsements RTe : L1.52 N/A

/

N/A er's Desi gnee, Tit] e Sheet 7

of 9

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI ob Number I E21 -v RType: L1.52

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

June 26, 2001

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Chemical And Volume Control System

5.

(a) Applicable Construction Code:

ASME Section II1, 19 86 Edition 1986

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Seal Housing, Pacific 2E299-AH NIA P. 0 QP-3929 1989 Replaced No Discharge End Seal Housing, Pacific 34409-AB N/A P. 0. QP960582 1994 Replaced No Suction End Seal Housing, Pacific M-1495 N/A P. O QP-3929 1985 Replacement No Discharge End Seal Housing, Pacific 2E299-AG N/A P 0 QP-3929 1989 Replacement No Suction End

7. Description of Work Due to degraded pump performance of Charging Pump Q2E21P0002A, the outboard seal housing assembly was replaced with a previously refurbished assembly.

02063

0.

I~

.UIU.C

[-I Hydrostatic El Pneumatic

[

Normal Operating Pressure 1'] None n

Other Pressure PSI Temperature OF

?¢O2t'g)06337

F

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number E21 -V02061 I Sheet 2 of' 2~--

RT)pe: L1.52

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

The replacement seal housing assembly was removed from Charging Pump QIE21POO02A under work order 9901233 and refurbished by SNC under work order 99002726.

Certificate of Compliance We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authonzation Number N/A Expiration Date N/A i

Maintenance Manager Date l__

Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

_____and employed by

-,e of have inspected the components d scribed in this Owner's Report during the period I aZ-/-r_

to

/-Z

/),e, *-.

, and state that to the best of my knowledge and belief, the Owner hias pe'rformed examinations and taken'corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection

-k-,ector s-Signatul-e Commissions e!:.,4 -TZ7-:6

.- /Z',I National Board, State, Province, and Endorsements z:

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I',-

Date z

vtqgoI3O*':la'7

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number ElI -"*

RT3pe: L1.52 t002005603

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

_____________Otober_

Otobe,13,200

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Compranv Maintenance Department Authorization Number N/A Address Josenh M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Residual Heat Removal System

5.

(a) Applicable Construction Code:

ASME Section III, 19 68 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Relief Valve Crosby N55222-00-0009 N/A P. O 38068 1986 Replaced No Relief Valve Crosby N55222-00-0007 N/A P. O FNP2-2 1972 Replacement No

7. Description of Work During the performance of surveillance test FNP-2-STP-628.0, valve Q2E1 IV0015B failed to meet the seat leakage acceptance criteria. The valve was replaced with a refurbished spare. Ref. MIF 02042227.

A0. I est Conauctea 1

-D Hydrostatic E-Pneumatic 1* Normal Operating Pressure

[--

None R

Other Pressure PSI Temperature F__

F Sheet 1 of 2

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI

[ob Number a~VAAr ID

-I, A~4 1!

lai k ppcablc tilanuiacrurer s trats Repor'ts to be attached)

RType: L1.52 Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code, Section XL replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp SCertificate of Authorization SignedA NIA Number a/1n.A-N/A Owner or Owner's Designee, Tit Expiration Date N/A Maintenance Manager Date

/_____________-

le Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

_and employed by.,5!n-,

/2,.,,

r.0.#

AA.,.-4 of

,',./

have inspected the components described in this Owner's Report during the period to

, A/, ZA 7-

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions 6r, "Zg National Board, State, Province, and Endorsements Date

?Mllctor's Signature JL*

I Jl'*J39 t*fi

C-JVI

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number B21 -_

RTjpe: L1.52 "1.

Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

I I

October 3. 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Companv Maintenance Department Authorization Number N/A Address:

Joseph M. Farlev Nuclear Plant Expiration Date N/A

4. Identification of System Steam Generator

5.

(a) Applicable Construction Code:

ASME Section III, 19 89 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A Addenda.

N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped

_(Yes

/ No)

Bolt Vicente Bernzbeita 35 N/A P 0. QP970783 1999 Replaced No Bolt Vicente Bemzbetta 28 N/A P. 0 QP970783 1999 Replaced No Bolt Vicente Bernzbeita 214 N/A P 0 QP970783 1999 Replaced No Bolt Vicente Berrizbeita 159 N/A P 0 QP970783 1999 Replaced No Bolt Vicente Bernzbeita 408 N/A P. 0 QP970783 1999 Replaced No During the removal of the top of tube sheet hand hole cover IOC for Steam Generator Q2B21H0001C, five (5) of the bolts galled in the bolt holes.

The bolts had to be destroyed to be removed and new bolts were installed in their place. Ref: MIF's 02042857 and 02042805.

8. Test Conducted 4

lHydrostatic

[

Pneumatic 1

Normal Operating Pressure

[n None ["] Other Pressure PSI Temperature OF WA681441

.qheet r*f q

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RType: L1.52 Job Number R91 - WA*Rh1AA1

_1._OwnerB21 Plan 141t

-1.

Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama. 36319 Date (as agent for Alabama Power Company)

October 3, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address :

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Steam Generator

5.

(a) Applicable Construction Code:

ASME Section I11, 19 89 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Bolt Ionics, Inc.

002 N/A P 0 QP020518 2002 Replacement No Bolt lonics, Inc.

005 N/A P. O QP020518 2002 Replacement No Bolt lonics. Inc.

003 N/A P. O QP020518 2002 Replacement No Bolt lonics. Inc.

004 N/A P. O QP020518 2002 Replacement No Bolt Vicente Bernzbeita 361 N/A P. O QP970783 1999 Replacement No I

f

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4 4

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Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RTpe* L1.52 Job Number B21-A68 4 1 I Sheet I -F 'ac

19. Remarks (Applicable Manufacturer's Data Reports to be attached)

Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code,Section XI rype Code Symbol Stamp Certificate of Authorization Numtx Signed Owner or Owner's Desionee. Title er N/A replacement repair or replacement conforms to the rules of the N/A Expiration Date Maintenance Manager Date N/A Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by 4-*,,

A-of

-7

&e- -,,

A, have inspected the components described in this Owner's Report during the'period e

to

,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Kpector's Signature Comrmssions

__-,4 -T 7-f National Board, State, Province, and Endorsements M.

)ate N/A Owner or Owner's Designee Title 7Z,

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI ob Number B21 -

RT~pe: L1.52 WA681432 I

-1.

Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highhay 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

_____________October_

ctobr 4,200

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Steam Generator

5.

(a) Applicable Construction Code:

ASME Section III, 19 89 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Editon N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Bolt Vicente Berrizbeita 457 N/A P. 0 QP970783 1999 Replaced No Bolt Vicente Berrzbeita 346 N/A P. 0 QP970783 1999 Replaced No Bolt Vicente Berrizbexta 413 N/A P. 0 QP970783 1999 Replaced No Bolt Vicente Berrizbeita 385 N/A P. 0 QP970783 1999 Replaced No Bolt Vicente Bemzbeita 441 N/A P. 0 QP970783 1999 Replaced No Bolt Vicente Berrizbeita 296 N/A P. o. QP970783 1999 Replaced No I.

Description of Work During the removal of the top of tube sheet hand hole covers IOC and 1OD for Steam Generator Q2B21H-0001B, one (1) bolt in cover 1OC and five (5) bolts in cover 1OD galled in the bolt holes. The bolts had to be destroyed in order to be removed and new bolts were installed in their

',lace. Ref: MIF 02042804.

Test Conducted 1

-]

Hydrostatic Pneumatic

-]Normal Operating Pressure

[Z None 0 Other Pressure PSI Temperature OF Sheet 1

of

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number B211 - WAA I Al)

RT 3 pe: L1.52

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama. 36319 Date (as agent for Alabama Power Company)

October 4, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Steam Generator

5.

(a) Applicable Construction Code:

ASME Section III, 19 89 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped

__(Yes

/ No)

Bolt Ionics, Inc 008 N/A P 0. QP020518 2002 Replacement No Bolt lonics. Inc 007 N/A P. 0 QP020518 2002 Replacement No Bolt lonics, Inc.

001 N/A P 0 QP021518 2002 Replacement No Bolt lonics. Inc 006 N/A P. 0 QP021518 2002 Replacement No Bolt Vicente Berrizbeita 241 N/A P. 0 QP970783 1999 Replacement No Bolt Vicente Berrlzbeita 249 N/A P 0 QP970783 1999 Replacement No I

t I

+

4

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1 I

I f

4 1

I I

t I

I I

4 1

4 t

1 4

1 1

1 4

LIZ!

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Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number B21 - WA681432 ISet3o 3

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

RT~pe: L1.52 Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code,Section XI.

replacement repair or replacement conforms to the rules of the j;Type Code Symbol Stamp Certificate of Authorization Numbe Signed

/16 M

N/A N/A Owner or Owner's Designee, Title Expiration Date Maintenance Manager Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of _

and employed by of have inspected the components described in this Owner's Report during'the period

___y--__-_-to

________Z____,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

rk-i',etor'so Sgnature Commissions

z

.TZ-

.-Z,t4 National Board, State, Province, and Endorsements N/A N/A Y

a t e

/: ?-., &/ Z7, ýý.w

-Z ISheet 3

of 3

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number I

B21 -W612 hpfIn

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

I__

IOctober 4, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address Joseph M. Farlev Nuclear Plant Expiration Date N/A

4. Identification of System Steam Generator

5.

(a) Applicable Construction Code:

ASME Section 111, 19 89 Edition N/A

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number "

Board Identification Built Replaced, or Code No.

Replacement Stamped

___(Yes

/ No)

Bolt Vtcente Bernzbeita 218 N/A P. O QP970783 1999 Replaced No Bolt Vicente Bernzbezta 414 N/A P. 0. QP970783 1999 Replaced No Bolt Ionics, Inc 009 N/A P. O QP020518 2002 Replacement No Bolt Vicente Berizbeita 373 N/A P. 0 QP970783 1999 Replacement No RT)pe L1.52

7. Descripton ot Work During the removal of the top of tube sheet hand hole covers 10A and lOC for Steam Generator Q2B21H0001A, one (1) bolt in each cover galled in the bolt hole. The bolts had to be destroyed in order to be removed and new bolts were installed in their place. Ref: MIF 02042795.

Test Conducted J

Hydrostatic

[-E Pneumatic

[-i Normal Operating Pressure M

None 0

Other Pressure PSI Temperature F

WAfiR147a

Form NIS-2 Owner's Report for Repairs or Replacements Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number B21 -WARI1 0

ID 11A I:~

t

7.

elar sz ppiale.J IvIiu1aI Lurer sata Rteports to De attacnea)

Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code,Section XI.

replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp Certificate of Authorization Signed N/A iNumber

ý9ý N/A Owner or Owner's Designee, Title Expiration Date Maintenance Manager Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

__,,,__and employed by of ______--_

__Z_,_

A,0 have inspected the components described in this Owner's Report during the period to 7-_

_______T___

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

t~mpetor sSignature Commissions L,3 -

._Zi.,

National Board, State, Province, and Endorsements RT~pe: L1.52 N/A N/A v

WA*IA92 I Qh..#

I f

1)

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number Nil -v.OIOV Ct

t I.

-" 1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Comp-)

October 29, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam System

5.

(a) Applicable Construction Code:

ASME Section 111, 19 71 Edition Summer 1973

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped

_(Yes

/ No)

Disc Assembly Atwood & Morrill

FNPSN5 N/A P. O. 22601 1984 Replaced No Disc Assembly Atwood & Morrill

FNPSN14 N/A P O 38053 1985 Replacement No RT3pe: L1.52

7. Description of Work During Inspection of Main Steam Isolation Valve Q2N1 IV0002C, the disc assembly was determined to be in need of replacement. A previously refurbished disc assembly was installed in the valve Ref: MIF 02040032.

See note on sheet 2 for explanation of asterisks.

8. Test Conducted P Hydrostatic

[-_ Pneumatic u Normal Operating Pressure 1--

None

-'Other Pressure PSI Temperature OF K

Vlq13913/32 q 12

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RType: L1.52 Job Number NI1 -WO02003313 N II -W0000313 I

Sheet 2 of 2

9. RemarKs kAppiicanle xianutacturer's Data Keports to be attached)

These disc assemblies were re-serialized by SNC to improve traceability of individual parts. See the spreadsheet attached to work order 02003313 for a detailed breakdown of manufacturers identification data for each part Certificat We certify that the statements made in the report are correct and this ASME Code,Section XI.

e of Compliance replacement repair or replacement conforms to the rules of the

'Type Code Symbol Stamp j Certificate of Authorizatior Signed N/A Number N/A Owner or Owner's Designee, Title Expiration Date Maintenance Manager Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

,,and employed by

,r of

.,_____,_.,have inspected the compdoents d6scribed in this Owner's Report during the period "i4'___

to

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Inis to's Sigaturýe.

" I

ýD a t e

/

Commissions National Board, State, Province, and Endorsements N/A 1-Ar/

L F

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number I Nil -¥ RT)pe: L1.52

-'1.

Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

October 29, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam System

5.

(a) Applicable Construction Code.

ASME Section 111, 19 71 Edition Summer 1973

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Disc Assembly Atwood & Morrill 4-30831 N/A P. O 22602 1984 Replaced Yes Disc Assembly Atwood & Morrill

FNPSNI6 N/A P 0 FNP2-22 1975 Replacement Yes

7. Description 0f Work During Inspection of Main Steam Isolation Valve Q2N 11V0002A, the disc assembly was deterrmned to be in need of replacement. A previously refurbished disc assembly was installed in the valve. Ref. MIF 02040036.

"3ee note on sheet 2 for explanation of asterisks.

t.

Test Conducted F-1 Hydrostatic E] Pneumatic

[E Normal Operating Pressure None

[-] Other Pressure PSI Temperature OF I

VO0200331 !

hpet l

nf 9

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RTpe: L1.52 Job Number N11 -WO02003311

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

This disc assembly was re-senalized by SNC to improve traceability of individual parts See the spreadsheet attached to work order 02003311 for a detailed breakdown of manufacturers identification data for each part Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code,Section XI.

Fype Code Symbol Stamp Certificate of Authorization Numix Signed

(

replacement repair or replacement conforms to the rules of the N/A N/A Expiration Da Owner or Owner's Designee, Title Maintenance Manager Date te N/A

(

-L 15-/0-t-.

Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

__,_and employed by,.c*

'-,."%qe-,

of have inspected the components scribed in this Owner's Report during the period 9/

-a to and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

(A(ee55ignaflMe Commissions National Board, State, Province, and Endorsements

)ate Zz4 z Sheet 2

of 2

N/A

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number V..

.in I

n

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

October 29, 2002

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farlev Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam System

5.

(a) Applicable Construction Code:

ASME Section 111, 19 71 Edition Summer 1973

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped

"(Yes / No)

Disc Assembly Atwood & Morrill 5R-341 N/A P. 0. FNP2-22 1984 Replaced No Nut Atwood & Morrill UNKNOWN N/A P 0 FNP2-22 1984 Replaced No Disc Assembly Atwood & Morrill

FNPSN15 N/A P. O 22601 1984 Replacement No Nut Mackson S44037 N/A P. 0 QP010884 2001 Replacement No RT~pe : L1.52

-/. [escription o0 Work During Inspection of Main Steam Isolation Valve Q2NI IV0001C, the disc assembly was determined to be in need of replacement. A previously refurbished disc assembly was installed in the valve. In addition, a shaft blind end cover retaining nut was misplaced and a new nut was checked

)ut of the warehouse and installed. Ref: MIF's 02040037 & 02043009. See note on sheet 2 for explanation of asterisks.

S-

8. Test Conducted Li Hydrostatic r-1 Pneumatic

[a Normal Operating Pressure

["1 None n] Other Pressure PSI Temperature OF WO0200* 10

h*pt 1

r

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RT~pe: L1.52

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

Job Number Nil -'VVO020033 10 ISheet 2

of 2

This disc assembly was re-seriahzed by SNC to improve traceability of individual parts See the spreadsheet attached to work order 02003310 for a detailed breakdown of manufacturers identification data for each part Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code,Section XI.

replacement repair or replacement conforms to the rules of the

,Type Code Symbol Stamp Certificate of Authonzation Number Signed Owner N/A N/A or Owner's Designee. Title Expiration Date Maintenance Manager Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by A,,

of

___*,__-__s have inspected the component~sdescribed in this Owner's Report during the period W

to

__/___to_._._,__,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind ansing from or connected with this inspection.

ector's Signature Commissions

---,'Z,

,t,,4, National Board, State, Province, and Endorsements N/A

-)

1 ate I Sheet 2

of 2 NII - V0020033 10 I

N/A

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RT3 pe: L1.52 Owner Southern Nuclear Operating Company 40 Inverness Center Parkway Birmingham, Alabama 35242 (as agent for Alabama Power Company)

IJob Number NI 1 - W002003307 Sheet I

of' 2

4

2. Plant Farley Nuclear Plant Highway 95 South Columbia, Alabama 36319 Unit FNP 2

Date

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam System

5.

(a) Applicable Construction Code:

ASME Section HI, 19 71 Edition Summer 1973

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Disc Assembly Atwood & Momll IR-340 N/A P 0 FNP-191 1975 Replaced No Disc Assembly Atwood & Morrill

FNPSN13 N/A P. 0 FNP2-22 1975 Replacement No P7 fl

... s7..

.'.*^

_t"l i

I.

Deit tioinll of v

OrKO During Inspection of Main Steam Isolation Valve Q2NI IV0001A, the disc assembly was determined to be in need of replacement. A previously refurbished disc assembly was installed in the valve. Ref-MIF 02040039.

"ee note on sheet 2 for explanation of asterisks.

Test Conducted I

-re Hydrostatic E" Pneumatic T

Normal Operating Pressure D

None

[D Other Pressure PSI Temperature F

I October 29, 2002 Sheet I or 2 "t

Sheet 1 of 2

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number Nl1 -'

I*heett2eo W002003307

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

This disc assembly was re-serialized by SNC to improve traceability of individual parts See the spreadsheet attached to work order 02003307 for a detailed breakdown of manufacturers identification data for each part.

Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code,Section XI.

reolacement repair or replacement conforms to the rules of the

,,Type Code Symbol Stamp Certificate of Authorizatiot I

Signed

/

N/A Number N/A Owner or Owner's Designee, Title Expiration Date Maintenance Manager Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by c,:of

*A__f Jn_"4

,___..-____,_,,,__have inspected the components described in this Owner's Report during the period

_-,1/___.._

to

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

ctors Signature Commissions

_A*,,

.TZO 2",,

National Board, State, Province, and Endorsements I-/, 12d a____Z RType: L1.52 N/A N/A Sheet 2

of 2

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number E21 -

RT)pe: L1.52

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

October 27, 2002

3. Work performed by Type Code Symbol Stamp N/A Name: Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Chemical & Volume Control System

5.

(a) Applicable Construction Code:

ASME Section Il, 19 74 Edition Summer 1975

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Relief Valve Crosby N55217-00-0012 N/A P.O. NQ52998 1990 Replaced Yes Relief Valve Crosby N66639-00-0005 N/A P.O. QP941391 1994 Replacement Yes

7. Description of Work Due to a slow upward trend in the level and temperatursf the contents of the Pressurizer Relief Tank, Letdown Orifices Outlet Relief Valve Q2E21 V0255 was believed to be leaking past the closed seat and was subsequently replaced with a spare valve.

Ref: MIF 02043775.

U

0. lest Conuucted IE Hydrostatic EI Pneumatic Normal Operating Pressure I-I None [l Other I

Pressure PSI Temperature OF

O02006325

.*h @*t 1

r.f 9

\\

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number P191 _

T

-1 C1_*If-A 1

I 4

fl tlJA~flJJLJ Jat.

~

kI4

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

The replaced valve was previously installed under MWR 282486 RType: L1.52 The replaced valve was given to FNP by Portland General Electric Company (Trojan Nuclear Plant) in return for a similar valve that had earlier been given to PGE By FNP. The purchase order number referenced on sheet I is the PGE purchase order number to Crosby.

Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code,Section XI.

replacement conforms to the rules of the repair or replacement

,Type Code Symbol Stamp Certificate of Authorization Numb(

Signed N/A er N/A Owner or Owner's Designee, Title Expiration Date Maintenance Manager Date NIA Z-/I W 0 -Z_

Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of q

and employed by "qe"-., a, of 4-e*A

_Zk 1_4-4,6 have inspected the components decribed in this Owner's Report during the period A

4 to to_"__'_/--

, and state that to the best of my knowledge and belief, the Owner has performed examinations and takeAi corfective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

Commissions 6SA*1 3Z--AI National Board, State, Province, and Endorsements

-,D~ate

~Z 4 N/A

'K~l--Dat ri/2 t/ure'

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI ob Number Nil -V RT 3pe: L1.52

-1.

Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2

Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

_______________________________October_

Otobe,29,200

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam System

5.

(a) Applicable Construction Code-ASME Section i1n, 19 71 Edition Summer 1973

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Disc Assembly Atwood & Morrill

FNPSN2 N/A P. O 67283 1981 Replaced No Disc Assembly Atwood & Morrill

FNPSN11 N/A P.0. 22602 1985 Replacement No I

I uescription oi Work Durinn Inspection of Main Steam Isolation Valve Q2NI I V0002B, the disc assembly was determined to be in need of replacement. A previously refurbished disc assembly was installed in the valve. Ref. MIF 02040034 See note on sheet 2 for explanation of asterisks.

8. Test Conducted ED Hydrostatic 1

Pneumatic 0

Normal Operating Pressure 1ii None

-"] Other Pressure PSI Temperature OF VO02003312 I

af

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI IJob Number N NII-W002003312 Sheet 2

of 2

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

These disc assemblies were re-serialized by SNC to improve traceability of individual parts See the spreadsheet attached to work order 02003312 for a detailed breakdown of manufacturers identification data for each part.

Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code,Section XI.

replacement repair or replacement conforms to the rules of the j 'ype Code Symbol Stamp Certificate of Authorizatioi Signed

/-

N/A nNumber N/A Owner or Owner's Designee, Title Expiration Date Maintenance Manaier Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by of -

have inspected the components delcribed in this Owner's Report during the period to

,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

s ~ *-i S/

CommissionstureNationa B dtss ctor' SigntureNational Board, State, Province, and Endorsements

.,,ate RTýNpe: L1.52 N/A 11"/t iloli I

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI ob Number N1l -V RT3pe: L1.52 NO02003309

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

_____________Oto___erOtobe

,29,200

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Main Steam System

5.

(a) Applicable Construction Code:

ASME Section i11, 19 71 Edition Summer 1973

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 89 Edition N/A

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Disc Assembly Atwood & Morrll

FNPSNI N/A P. 0 QP-1691 1987 Replaced No Disc Assembly Atwood & Morrll

FNPSNI2 N/A P.0. 22601 1984 Replacement No

7. uescripiionoi wvorK During Inspection of Main Steam Isolation Valve Q2N I1V0001iB, the disc assembly was determined to be in need of replacement. A previously refurbished disc assembly was installed in the valve. Ref: MIF 02040038.

See note on sheet 2 for explanation of asterisks.

<(8. Test Conducted

['j Hydrostatic

[-] Pneumatic

[2 Normal Operating Pressure

]

None LI Other Pressure PSI Temperature OF Sheet nf 7

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RT~pe : L1.52

7. Rtemarks tIAppnicaie lianuacturer-s tata Keports to e attached)

Job Number NIlI - W002003309 I Sheet 2 of 2

These disc assemblies were re-seria:ized by SNC to improve traceability of individual parts. See the spreadsheet attached to work order 02003309 for a detailed breakdown of manufacturers identification data for each part Certificate of Compliance We certify that the statements made in the report are correct and this ASME Code, Section XL.

replacement repair or replacement conforms to the rules of the 1 rype Code Symbol Stamp Certificate of Authorization Number Signed

/Yr Owner N/A N/A or Owner's Designee. Title Expiration Date Maintenance Mananer Date Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by

_cA_

of

__"__,____l__A-_

have inspected the components decribed in this Owner's Report during the period to

,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

(Jdor, s Signature Comirussions f;

_._______Z",_/,,

National Board, State, Province, and Endorsements N/A

-)ate Z-

-7 N/A

Class MC

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number F15 - V0 RTpe: L1.52

/002006179

'I

1. Owner

2. Plant Unit Southern Nuclear Operating Company Farley Nuclear Plant 40 Inverness Center Parkway Highway 95 South FNP 2 Birmingham, Alabama 35242 Columbia, Alabama 36319 Date (as agent for Alabama Power Company)

____________Otober____1Otobe 210,200

3. Work performed by Type Code Symbol Stamp N/A Name : Southern Nuclear Onerating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farley Nuclear Plant Expiration Date N/A

4. Identification of System Refueling Equipment

5.

(a) Applicable Construction Code:

ASME Section I11, 19 71 Edition Summer 1973

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 92 Edition 1992

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Cap Screw (6)

Stearns-Roger UNKNOWN N/A P. 0. FNP2-2 1974 Replaced No Corporation Cap Screw (1)

Cardinal Industrial RP1 N/A P. 0 QP-2143 1987 Replacement No Products Cap Screw (5)

Cardinal Industrial RP2 N/A P. 0 QP-2143 1987 Replacement No Products I. oescripuonot vVorK The blind flange was removed from Fuel Transfer Tube Assembly Q2F15K0003 to support outage activities. The bolting was VT-I examined while the flanged connection was demated. Six (6) cap screws were found to be in need of replacement. Six (6) new cap screws were installed Ref: MIF 02043546.

'8. Test Conducted I"

Hydrostatic

-'] Pneumatic

] Normal Operating Pressure en None n

Other Pressure PSI Temperature -___

F Sheet 1 of 2

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RTipe: LI.52 Job Number F15 - 'A I Sheet 2

of 2 T0020061 79

9. Remarks (Applicable Manutacturer's Data Reports to be attached)

Certificate of Compliance We certify that the statements made in the report are correct and this replacement conformis to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authorization Number N/A Expiration Date N/A Signed I/q (

A Maintenance Manager Date Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

__,__and employed by,,_*-

V_

e.-*Z of have inspected the components d~scribed in this Owner's Report during the period

//_____,____

to

/ z/

!!/ Z.

, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

~ or's Signature Date 7'

Comrmssions National Board, State, Province, and Endorsements

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI RT~pe: L1.52

1. Owner Southern Nuclear Operating Company 40 Inverness Center Parkway Birmingham, Alabama 35242 (as agent for Alabama Povier Company)

Job Number

,T52 - WA682239 9

a

2. Plant Farley Nuclear Plant Highway 95 South Columbia, Alabama 36319 Sheet 1 of 2 Unit FNP 2

Date October 11, 2002

3. Work performed by Type Code Symbol Stamp N/A Name: Southern Nuclear Operating Company Maintenance Department Authorization Number N/A Address:

Joseph M. Farlev Nuclear Plant Expiration Date N/A

4. Identification of System Containment Penetrations

5.

(a) Applicable Construction Code:

ASME Section II1, 19 71 Edition Summer 1971

Addenda, N/A Code Case (b) Applicable Section XI Utilized For Repairs Or Replacements, 19 92 Edition 1992

Addenda, N/A Code Case

6. Identification of Components Repaired or Replaced and Replacement Components:

Name of Name of Manufacturer National Other Year

Repaired, ASME Component Manufacturer Serial Number Board Identification Built Replaced, or Code No.

Replacement Stamped (Yes / No)

Nuts (16)

Texas Bolt Company DV32 N/A Daniel Construction Co.

1975 Replaced No P. 0 7047-0-63631 1

Nuts (16)

Nova Machine B87035 N/A P. O. QP010373 2001 Replacement No Prodiucts

7. Description of Work A VT-1 examination on the studs and nuts on the blind flange connections of penetration Q2T52PENE72 revealed that the nuts (16) on the blind flange connection on the Auxiliary Building side of the penetration were in need of replacement. Sixteen (16) new nut', were installed.

Ref: MIF 02042926.

K. 8. Test Conducted Hl Hydrostatic

[:] Pneumatic F-1 Normal Operating Pressure Z

None

['] Other Pressure PSI Temperature __O_

F

Form NIS-2 Owner's Report for Repairs or Replacements As required by the provisions of the ASME Code Section XI Job Number I ~T52 -

WT572 I Sheet 2 of2

9. Remarks (Applicable Manufacturer's Data Reports to be attached)

Certificate of Compliance We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.

repair or replacement Type Code Symbol Stamp N/A Certificate of Authorization Number N/A Expiration Date N/A Signed Maintenance Manager Date

/

Owner or Owner's Designee, Title Date RType: L1.52 Certificate of Inservice Inspection 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of

_eeaAq,1,c and employed by

^,rc g-5-eoeoA,,

e of

___R*-"s_.,,-

______.___..____,have inspected the components described in this Owner's Report during the period

/

/,

to

/_,__,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

s s

uo rCommissions 45::A.

.r,

,, spector's Signature National Board, State, Province, and Endorsements Sheet 2 of 9 WAfig*g0

IWE/IWL

J. M. FARLEY NUCLEAR PLANT UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 Containment examinations performed to meet the requirements of Subsection IWE/IWL during the Unit 2 RF 15 outage in accordance with the Containment inspection plan.

10/01/02 15:46:00 FIGURE I FNP-0-NDE: 100.24 FARLEY NUCLEAR PLANT VISUAL EXAMINATION RECORD VT-1 / IWE SOUTHERN NUCLEAR OPERATING COMPANY Unit 2 Line NumberlExamination Area/Weld Isometric Drawing Sheet No.

Q2TS2PENE 72-Outboard penetrationN/A N

N/A PHOTOS SKETCH LIGHT METER BATTERY POWERED WO/WAV00682239 ILLUMINATION VERIFICATION Yes

__ B & W

__ Yes Instrument Light Meter Prior to Exam IOOFc Procedure No FNP-0-NDE-100.24 X No

_Color X

No Intermediate NV/A Version No. 2.0 Serial No. FNP-MIM-5714 After Exam JOOFc Minor Version No. N/A TECHNIQUE EQUIPMENT LIGHTING TOOLS

____________________of_____Level Examiner Mixon, 1 Level X Direct

__ Mirror

__ Ambient X Scale

- Depth Gauge

__ Level H_

Remote Magnifier X Flashlight

__ Micrometer

__ Comparator Examnner N/A Level Video

__ CCTV Droplight Caliper Other Date (Month-Day-Year) 10/01/02 CONTAINMENT SURFACES BOLTING I BOLTED CONNECTIONS Coated Areas None

_Non-Coated Areas None Observed Observed N/A Observed Observed N/A

_ Inplace X

Disassembled None Flaking Cracking Observed Observed N/A Blistering Discoloration Cracking X

Peeling Wear Wear X

Discoloration Pitting Excessive Corrosion X

Other Excessive Corrosion

Other X

Arc Strikes Gouges Dents Surface Irregularities

Other Comments: Linear Indications (major dimension 3/16'7 noted on nuts on outboard penetration. Indications exhibit condition consistent with manufacturing defect. Indications reviewed and found to be acceptable in accordance with FNP.-0NDE-100.24, version 2.0 paragraph 10.2.

EVexi 7rf*"*u1,4 THE" AJUT5 mr-'"r r&E AC.EPTA4/dC 5TAuoAeO5 OD FAJP-O-AJDE-/0O. 2-1, A M nu/',-',

nlj'),iiTt I/lJI'

(,*rc.i[ZAJnr ft;UIT)

,an5 tn5I/IL6

/.

C-i/C/J &F 7/46m, 74_-.V I..1DULO p.0Tr 13* gŽ5*0.

$W to//oilt Reviewed by Position Date VT Lav-L:Eo/

Page I of I Version 2.0 r=V%1Gl"C-r=~tL1WC SUPPOMT "A$

0V5TL-IZM1W.

"rM4ATTrI4EIL-35 NO OC-1FM J-.

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I.EF. C, LZoo.ooZ.6S.

(

i/01/02 17:02:54 FIGURE 1 FNP-0-N C 100.24 FARLEY NUCLEAR PLANT VISUAL EXAMINATION RECORD VT-I / IWE Unit 2 Line Number/Examination Area/Weld Isometnc Drawing Sheet No.

_Q2TS2PENE 72-Inboard penetration N/A N/A PHOTOS SKETCH LIGHT METER BATTERY POWERED WO/WA W00682239 ILLUMINATION VERIFICATION

_Yes

__ B & W

_ Yes Instrument Light Meter Prior to Exam 10OFe Procedure No.

FNP-0-NDE-100 24 X No Color X_ No Intermediate N/A Version No 2.0 I Serial No. FNP-MIM-5714 After Exam IOOFe Minor Version No. N/A TECHNIQUE EQUIPMENT LIGHTING TOOLS Exa

_"m____

evel X Direct

_Mirror

_Ambient XScale

_iDepth Gauge

_L Level

_ Remote

- Magnifier XFlashlight

_ Micrometer

_ Comparator Examiner N/A Level

__ Video

__ CCTV

__ Droplight Caliper Other-Date (Month-Day-Year) 10/01/02 CONTAINMENT SURFACES BOLTING / BOLTED CONNECTIONS

__ Coated Areas None Non-Coated Areas None Observed Observed N/A Observed Observed N/A

_ Inplace X

Disassembled None Flaking Cracking Observed Observed N/A Blistering Discoloration Cracking X

Peeling Wear Wear X

Discoloration Pitting Excessive Corrosion X

Other Excessive Corrosion

Other X

Arc Strikes Gouges Dents Surface Irregularities

Other Comments' Reviewed by j Position Date I.VT Lev-EL ME 10 /1/oS/02.

Version 2.0 Page I of I

C~S XNPR-NEE,.D FARLEY NUCLEAR PLANT VISUAL EXAMINATION RECORD VT-1 / IWE SOUTHERN NUCLEAR OPERATING COMPANV Unit Line Number/Examination Area/Weld Isometric Drawing Shee No a

. '7%.q'IL PZW.AE *'?0 1 smeri,1a,*

1 Sh I

PHOTOS SKETCH LIGHT METER BATTERY POWERED WO/WA ILLUMINATION VERIFICATION SOZOM 19 Yes

_B&W

_Yes Instrument U-0 4-Priorto Exam.>Idt)AC ProcedureNo FNP-O-NDE-10024 Color lI Intermediate A//A.

Version No.

z2

(

Serial No. *V'd AIII'G'V7 After Exam >/Ofl, *_

Minor Version No TECHNIQUE EQUIPMENT LIGHTING TOOLS

_11_4 Examiner

- f__.__.

Ae<.4ect Mirror Ambient vwcale Depth Gauge Level

- Remote Magnifier

f¶ahlight Micrometer Comparator

-Examiner I Level

- Video

_ CCTV

_ Dmplight Caliper

!1414/

Other Date (Month-Day-Year)

/

t./.*z.

CONTAINMENT SURFACES BOLTING I BOLTED CONNECTIONS Coated Areas None Non-Coated Areas None Observed Observed N/A Observed Observed N/A

_ Inplace

.X.iSssembled None Flaking Cracking Observed Observed N/A Blistering Discoloration Cracking Peeling Wear Wear Discoloration Pitting Excessive Corrosion

Other

____Excessive Corrosion

Other Arc Stnkes Gouges Dents Surface Irregularities

Othfer Comments

"'Z.

k I,

,2 s-"

Reviewed by I Position Date Version 2.0 6

FNP-0-NDEC-0v.24 Page I of I

K..

3~'

R~-X./L FNP-0-NDE-L,,.24 FARLEY NUCLEAR PLANT VISUAL EXAMINATION RECORD VT-i I TWE SOuTHERN NIT'T EAR OPRATTN

CA1UDA NV Unit 11Line Numb-'xn 9at o AS 92M Isn~~

ng ISh PHOTOS sKcTr" LIGHT METER BATERY POWERED WOWA ILLUMINATION VERIFICATION

'J)

A 42-Yes

_B & W

_Yes Instrument L J]k 1

Prior to Exam On OC Procedure No.

FNP-0-NDE-100.24 SColor HIntermediate

/A, Version No.

-.,o 1_

_Serial No_ L*__

°__

l_ Afler Exam > Ltx, FC-.

MinorVersionNo.

A/IL TECHNIQUE EQUIPMENT LIGHTING TOOLS Examiner

/I\\'%VCO*

Wtl A.Lee

%'Kreet Mirror

_A bient

- Depth Gauge Level

_ Remote Magnifier

__ vlashlight

__ Mcrometer Comparator Examiner Al/A Level

-Video

-CCTV Droplighit Caliper Other Date (Month-Day-Year)

CONTAINMENT SURFACES BOLTING I BOLTED CONNECTIONS Coated Areas None Non-Coated Areas None Observed Observed N/A Observed Observed N/A

_place V

sembled None Flaking Cracking Observed Observed N/A Blistering Discoloration Cracking Peeling Wear Wear Discoloration Pitting Excessive Corrosion

Other Excessive Corrosion

'Other Arc Strikes Gouges Dents Surface Irregularities

-S s

' *Other Comments ni1 O",d4..

Reviewed by I Position Date Ve, 2.0 P.,

of I

1 10/05/02 09:18:08 SH-,RETD FIGURE 1 C

FNP-0=NDE-1 00.24 FARLEY NUCLEAR PLANT VISUAL EXAMINATION RECORD VT-i / IWE SOUTHERN NUCLEAR OPERATING COMPANY Unit 7-Line Number/Examination Area/Weld j

e 4

Isomnetnc Drawing IVhee NO.

14 PHOTOS SKETCH LIGHT METER BATTERY POWERED WO/WA ILLUMINATION VERIFICATION

%y z

00 z 00

_ Yes

_B & W

__ Yes Instrument ltJAIA.l4.

Prior to Exam ".P f'O

-ee 0O.3 Procedure No.

FNP-0-NDE-100 24 Z

4 o

Color vlo Nnoemexiate 1/1 Version No SerialNo

_/,

-Z1 4 AflerExam -,"J-0 0

0 Minor Version No TECIINIQUE EQUIPMENT LIGHTING D. P. I1-7,OZ TOOLS N/IA IExaminer Level j/Direct IdMirror

__Ambient Scale Depth Gauge Level Leve l,-.

Rem ote M agnifier

/I _'lashhght M icrom eter

- Com parator

_/k.I d 44 _1C Exam iner z

Le v eL T....

Video CCTV

- Droplight

_Caliper PAL94'Q,,4,YJ.

Other CAAO Date (Month-Day-Year)

CONTAINMENT SURFACES BOLTING BOLTED CONNECTIONS Coated Areas None Non-Coated Areas None Observed Observed N/A Observed Observed N/A

_ Inplace

/Disassembled None Flaking v1 Cracking Observed Observed N/A Blistering

%/-

Discoloration V

Cracking Peeling Wear oo" Wear Discoloration

/

Pitting Excessive Corrosion

Other Excessive Corrosion

Other Arc Strikes V

Gouges P 1 1*

Dents Surface Irregulanties

Other Comments

/Z I-ewaj (8-]a

,4AV 24 V,,rJA (Zs)

-aoVo~aTioe Reviewed by Position Date Pag,.. of 0

Versio,./. 0

" J/01/02 12:46:23

-"AI EI FIGURE 1 FNP-0-NDLi 00.24 FARLEY NUCLEAR PLANT VISUAL EXAMINATION RECORD VT-i / TWE S........

L., *

j.

Al

't.J~*-U*

ILJkj. Jktt*J.i-

. J IL A J,1.PVlIt-1 I-J.

ULit Line Number/Examination Area/Weld 7 pNS : OZF I5/< 000 3 I Isometnc Drawing Sheet No.

Unt 2 F____- I e

I I

..L.

PHOTOS SKETCH LIGHT METER BATTERY POWERED WO/WA ILLUMINATION VERIFICATION M

0 2-CC

" 7?

_Yes

_B & W

_Yes Instrument T

Prior to Exam 0 Z 30 Procedure No.

FNP-0-NDE-100.24 V/ No

_Color VNo Intermediate W/,4 Version No.

2 Serial No. FNP-MI Sl"Iti After Exam 0615 Minor Version No TECHNIQUE EQUIPMENT LIGHTING TOOLS P11,4 v.Direct Mirror

_Ambient

/Scale Depth Gauge Level E

i.n 0.L.e..

evel Remote

- Magnifier

.Flashlight

-- Micrometer

__ Comparator Examiner t

Level SVideo CCTV

_ Droplight

-Caliper

/ d.

Other Date (Month-Day-Year)

CONTAINMENT SURFACES BOLTING I BOLTED CONNECTIONS

_ Coated Areas None

_Non-Coated Areas None Observed Observed N/A Observed Observed N/A

_ Inplace

/Disassembled None Flaking 1

Cracking Observed Observed N/A Blistering Discoloration Cracking 1

Peeling Wear Wear V

Discoloration Pitting Excessive Corrosion

Other Excessive Corrosion

Other V

Arc Strikes Gouges Dents Surface Irregularities 1

Other Comments Ui Pr i.-oM

)S0 ON 6

gJP-e.. tA& Jr*N" So LTr5.

NIF.Z Reviewed by J

Position Date Version 2.0 Page I of I

NL-03-0167, J. M. Farley Unit 2, Inservice Inspection Report, Refueling 15, Interval 3, Period 1, Outage 1, Td Certs

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3.0 MATERIAL

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Subject:

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NL-03-0167, J. M. Farley Unit 2, Inservice Inspection Report, Refueling 15, Interval 3, Period 1, Outage 1, Td Certs

Text

3.0 MATERIAL

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