ML20140J292
| ML20140J292 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 05/05/1997 |
| From: | Mccollum W DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M97465, NUDOCS 9705140038 | |
| Download: ML20140J292 (23) | |
Text
_.
II-I DukePoua Company Wunw R. McCm.u Av. Jw Catauha Nudear Generatwn Deportment Vice President 4300 ConcordRoad (8W)R312;w Ottic e Yark. SC71745 (SW)S31306 Fax e
1
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DUKEPOWER i
i May 5, 1997 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk J
Washington, D.C. 20555-0001 i
Subject:
Duke Power Company Catawba Nuclear Station, Unit 1 Docket No. 50-413 Request for Additional Information (RAI)
Request for. Relief from 1989 edition of ASME Boiler' i
and Pressure Vessel Code,Section XI.
j Serial No. 96-04 i
4 Re:
Letter from NRC to William R.
McCollum dated March 7,
1997, Request for Additional Information I
d The following response is provided to address the questions submitted by the subject RAI.
Each question is restated below with'the response following.
A.
Based on the initial review of the licensee's submittal, i
the staff has concluded that either (a) the appropriate paragraph of the regulations has not been cited, or (b) the regulatory basis has not been adequately supported.
j-Request for Relief 96-04 was submitted pursuant to i
10CFR50.55a(a) (3) (ii), but no burden or undue hardship j
has been presented.
This request should be reviewed for the correct paragraph of the regulations to ensure that the request is evaluated in accordance with the
/ /
appropriate criteria, as discussed below.
i
[
The regulations provide that'a licensee may propose an alternative to the Code of Federal Regulations or the code /
requirements in accordance with 10 CFR 50.55a (a) (3) (i) or 10 CFR 50.55a (a) '(3) (ii).
Under 10 CFR 50.55(a) (3)
(i), the proposed alternative must be shown to provide an acceptable level of quality, i.e.,
essentially, be equivalent to the original requirement in terms of quality i
130083
- MMMMMpq i
9705140038 970505 PDR ADOCK 05000413 P
Document Control Desk Page 2 May 5, 1997 and safety.
Under 10 CFR 50.55a (a) (3 ) (ii), the licensee must show that compliance with the original requirement results in a hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Examples of hardship and / or unusual difficulty' include, but not limited to, excessive radiation exposure, disassembly of components solely to provide access for examination, and development of sophisticated tooling that would result in only minimal increase in examination coverage.
A licensee may also submit a request for relief from ASME requirements.
In accordance with 10 CFR 50.55a (g) (5)
(iii), if a licensee determines that conformance with certain Code requirements is impractical for its facility, l
the licensee shall notify the Commission and submit, as 1
specified in Section 50.4, information to support that determination.
When a licensee determines that an 5
inservice inspection requirement is impractical, e.g.,
the examination is limited by physical restrictions and the j
component would have to be redesigned or replaced to enable inspection, the licensee should cite 10 CFR 50.55a (g) (5) (iii).
The.NRC may, giving due consideration to j
the burden placed on the licensee, impose an alternative examination requirement.
l
Response
i.
l Request for Relief 96-04 was submitted on December 12, 1996 pursuant to 10CFR50.55a (a) (3) (ii).
This was in error and should have been submitted under 10CFR50.55a (g) (5) (iii).
100% coverage of the subject welds was impractical because of single-sided access, due to pipe-to-valve configuration and austenitic weld metal.
B.
Section XI, Appendix III, Paragraph III-4420, Reflectors Parallel to the Weld Seam, requires examination coverage in two beam path directions to detect reflectors parallel to the weld seam.
This can be accomplished by either scanning from two sides of the weld, or by using a sufficiently long beam path to provide two-directional coverage from one side of the weld.
The requirement for two-directional axial scan coverage should also be reflected in the coverage calculations.
However, the coverage calculations provided
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Document Control Desk Page 3 a
May~5, 1997 l
1 with the licensee's submittal only include scan coverage.in I
one axial direction (with two angles) and it appears that the second axial direction was not included in the l
calculation.
As a result, the calculated coverage may be 1
overstated.
Provide a discussion regarding the examinations I
performed in the axial direction (s) and how the coverage was calculated.
i Responses Reference to Appendix III in Parts III, IV, and VI of j
Request-for Relief 96-04, dated December 12, 1996 was an
-error. to this letter is Revision 1~to Request for Relief 96-04, denoting the corrected reference of ASME Section XI.
4 J
C. The Code requires both surface and volumetric examination i
of the subject Class 1 circumferential welds.
Confirm that
}
l the surface examination was performed to the extent required by the Code.
1 J
Response
I 1
3~
i Data sheets for the surface examinations of the subject j
circumferential welds (Item Numbers B09.011.163A and j
B09.011.164A) are included a's Attachments 2 and 3 to this letter.
The data sheets confirm the surface examinations were performed to the extent required by the code.
i.
{
As requested, a copy of this response is being sent to INEL.
Reasearch Center.
z
]
Should there be any questions concerning this request, please 1
l call D. Tower at (803) 831-3419.
Very-truly yours,
'f t
William R. McCollum, Jr.
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1
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Attachments i
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.m
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Document Control Desk Page 4 May 5, 1997 i
xc:
L. A.
Reyes Regional Administrator, Region II i
R.J.
Freudenberger, Senior Resident Inspector Catawba Nuclear Station i
P.S. Tam, Senior Project Manager ONRR Michael T.
Anderson INEL Research Center 2151 Porth Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 1
1 1
f ATTACHMENT 1 RELIEF REQUEST 96-04 REVISION 1 i
Request for Relief Serial No. 96-04 Revision 1l Page 1 of 4 DUKE POWER COMPANY STATION: CATAWBA NUCLEAR STATION UNIT 1 i
10-YEAR INTERVAL REQUEST FOR RELIEF NO. 96 04 Revision 1 1.
System / Component (s) for Which Relief is Requested:
i l
ASME Section XI Code Class: 1 Examination Category: B-J Circumferential Piping Welds - Safety Injection System j
Weld Number Item Number 1 nil 48-10 B09.011.163 e
1N1148-11 B09.011.164 4
ll.
Code Requirement:
j ASME Section XI,1989 Edition, Examination ( ~
gory B-J Pressure Retaining Welds In Piping, Table IWB-2500-1, Figure ? o nber IWB-2500-8. Item Number B09.011 requires a volumetric examination ol' essentially 100% of the weld length s
and adjacent base. material for all piping welds. Duke Power Company, with NRC approval, has adopted Code Case N-460 which defines " essentially 100%" as greater 4
than 90% coverage.
i 111.
Code Requirement from which Relief is Requested:
Relief is requested for the above identified Class 1 Circumferential Piping Welds from meeting the coverage requirements as defined in ASME Section XI, Figure IWB-2500-8, Examination Volume C-D-E-F.
Request for Relief Serial No. 96-04
~
Revision 1l Page 2 of 4 IV.
Basis for Relief:
During the ultrasonic examination of the welds shown in Attachment 1, coverage of the required examination volume as modified by Code Case N-460 could not be obtained. Causes of these limitations are single sided access due to pipe-to-valve i
configuration and austenitic weld metal. Where possible, a combination of angles and wave modes were used to maximize the coverage obtained. The weld and base metal at the component inside surface was covered from at least one direction with a minimum of one angle. The examinations were performed in accordance with ASME 1
Section XI, Appendix I and Appendix Vill,1992 Edition with the 1993 Addenda as allowed by Request for Relief 95-GO-003, dated September 12,1995.
V.
Alternate Examinations or Testing:
No additional examinations are planned during the current interval for Weld ID Numbers INIl48-10 and INil48-11. The use of radiography as an alternate j
volumetric examination method for Weld ID Numbers INIl48-10 and 1 Nil 48-11 is not feasible due to component thickness, geometric conngurations, and restrictions from physical barriers which prohibit access for the placement of source. image quality indicators, film, etc. Duke Power Company will continue to use Appendix VIII qualified ultrasonic examination procedures for detection of far side Haws, when examining them h austenitic weld metal.
VI.
Justification for the Granting of Relief:
Although the examination volume requirements as denned in ASME Section XI, Figure IWB-2500-8, Examination Volume C-D-E-F could not be met, the amount of coverage obtained for these examinations provides an acceptable level of quality and integrity. The inside surface of the pipe, within the required examination volume, received 100% coverage in the axial direction. If a surface connected circumferential flaw had been present,it would have been detected. For results of examinations, reference Attachment 2, pages 6 of 9 and 9 of 9. The welds in question connect the first and second check valves off the reactor coolant system and are one of the four paths for ECCS injection. in the unlikely event of their failure Duid would leak from the Cald Leg Accumulator (CLA) to the containment building floor. A drop in level from an accumulator with a corresponding increase in sump inputs would occur. An eventual alarm in the control room for CLA level would require action per Technical l
Request for Relief Serial No. 96-04 Revision 1l Page 3 of 4 1
Specification 3 / 4. 5.1. The limit on unidentified leakage is 1 gpm from sump input and is monitored by OAC point alarms. The Technical Specification 3 / 4. 6. 2 would be enforced if the unidentified leakage went above I gpm. These alarms would indicate a problem and allo,; adequate response time before the current margin in i
injection flow (Actual to test acceptance criteria) indicated by the ECCS flow balance testing is surpassed. Based on these evaluations,it is Duke Power Company's opinion that the limited coverage will not endanger the health and safety of the general public. Duke Power Company will perform UT examinations to the extent practical using procedures and personnel qualified in accordance with ASME Section XI, Appendix VIII,1992 Edition with 1993 Addenda.
1 Request for Relief
]
Serial No. 96-04 Revision 1 l Page 4 of 4 s
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Vll.
Implementation Schedule:
4 1
I; These examinati.ns will continue to be scheduled in accordance with the requirements of ASi4E Section XI for future Inspection Intervals at Catawba Nuclear 3
Station, Unit 1.
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Evaluated By:
di Date l
V dd #
f/!i2 NDE 1,evel 111 Reyk w Hy:
/2w, C
,Je Date V
V
I ffj LW Date.
Heviewed By:
i.
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e i
1 i
i Description Table E
4 UT Examination Data i
)
ASME Class 1 Inservice Inspection Request For Relief No. 96-04 For Catawba Unit 1 Based On ASME Section XI.1989 Coda 1
Page 1 of 1 1.acensee 1
Item No.
Exam Category System Or Area To Be Reason For Request Proposed Attemate
/ Figure No.
Component Examined Examination B09.011.163 B-J (NI) Safety injection Class 1 Limited scan due to geometric configuration.
None IWB-2500-8 System Circumferential Actual coverage obtained = 59.85%
Piping Weld j
B09.011.164 B-J (NI) Safety injection Class 1 Limited scan due to geometric configuration.
None IWB-2500-8 System Circumferential Actual coverage obtained = 61.00%
Piping Weld F
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_._.. _ _. _ _ _ _.RE4MASTM REuu %-Of kTTAeHMEATZ kfor4
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l FORM NDE-UT-1G i
DUKE POWER COMPANY ULTRASONIC CALIBRATION / EXAMINATION RECORD FOR NDT-136 INSTRUMENTS REVISION 5 3
~
Station:
Catawba Unit:
1 Date:
6/18/96 Sheet Number:
9601018 i
FC:
N/A Couplant:
ULTRAGEL 11 Batch Number 093001 l7 i
Procedure:
NDE-600 Rev:
Examiner: Jay A. Eaton h h Level: il Manufacturer STAVELEY Pyrometer SIN:
MCNDE 27025 l
Examiner. B. Dale Jolly g,[d Qgh Lml:
I Senal No:
975K Cal Due:
10/3/96 REFERENCE BLOCK
\\
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SIMULATOR BLOCK Soordi unit 81 Search unt 8 2 ID:
ROMPAS ID:
A09319 Reflector Type: RADIUS ID:
A09319 ReflectorType: RADIUS l
SIN:
A09319 Material:
SS Metal Path:
1*
MetalPath:
1" I
CABLES Search Unit # 1 L^^*;6; Rearch Unit # 2 L;^..g; Type: %B MO RG58 O Ro174 B Type:
Single @
Dual O Range 2.5 Range 5.0 Ske:
.5 SI2' 6
Delay 0.341 Delay 0.523 g
L Freq:
2.25 Mhz Velocity 0.124 Freq:
2.25 Mhz Velocity 0.12S Manuf:
KBA Manuf:
KBA Units IN Units IN i
Ser n :
43072 Display FILT1 Display FILT1 l
Initial Cal Time Ser no:
42967 Meas. g 45*
Freq 2.25 Meas. g M*
Freq 2.25 s u st 1406 su#2 1350 f
W MSWE Reject OFF W@
MSWE Reject OFF Cal Checks Wave Mode: Long. O Shear B i
Time Wave Mode: Long O Sheer @
Pulse 222 Puse 222 l
- Mod =I O Date s.u st s.u.82 Insels a
D a
Dm a
hh 1 Major Screen Div =
0.25 Indios 1 Major Screen Div =
0.5 inches 6t18t96 1418 1405 RgRe 2000 RgRh M
6H8/96 1430 141 C b Scan-anW D cire. 9 Scan: axw a cire. O
" ' 8"0
"'8"D 0 L Doel O guise Echo a oual O euise Echo a 8/18198 1440 1450 I
I FMAL Record Indcahons Limitations Scanning dB Scan Direction Exam Date and Time Surface Item No:
yes no yes no s.u #1 s.u #2 Axial Circ.
Start End Temp
- B09 011.1C5
- O O
O O
45 50 YES YES 6/18/96 1350 6/18t961418 72 F B09 011.186.
O B
O B
45 50 YES YES 6118/96 1350 6/f 8/961418 72*F O
O 9
0 45 50 YES YES 6/18196 1430 6/18/96 1450 72*F i
809 011.163 45 50 YES YES 6/18/96 1430 6I18/96 1450 72*F t
B09.012.163 O
O 3,,p Reviewer-Levet:
Dele:
Authoria C-? ' ^ ^.
Date:
C Larry Mauk5n M
I!
IW19f96
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REquasr rest Rauer SrM+
AT~AcmorTf %fs4 FORM NDE-UT-1G DUKE POWER COMPANY s
ULTRASONIC CALIBRATIONIEXAMINATION RECORD FOR NDT-136 INSTRUMENTS REVISION 5 l
Station:
Catawba Unit:
1 Date:
6/18/96 Sheet Number.
9601019 1
Procedure:
NDE-600 Rev-7 FC:
N/A Couplant:
ULTRAGEL 11 Batch Number.
093001 t
Examiner. Jay A. Eaton h j6 Level: 11 Manufacturer:
STAVELEY Pyrometer SIN:
MCNDE 27025 Examiner: B. Dale Jolly B. M.Mw Level: I Serial No:
975K Cal Due:
10/3/96
{
REFERENCE BLOCK
\\
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SIMULATOR BLOCK Search una # 1 Seardi unit 8 2 j
ID:
ROMPAS ID:
A09319 Reflector Type: RADIUS ID:
A09319 ReflectorType: RADIUS SIN:
A09319 Material:
SS Metal Path:
1" Metal Path:
1" l
CABLES Search Unit # 1 Settings Search Unit # 2 L:^." we Type:
S* B MO i
RG58 O R oir4 G Type:
Singie B Dual O a,nge 5.0 Range 2.5 Size:
.5 Size:
5 Delay 0.341 Delay 0.523 i'
s of w. C.,
0 Freq:
2.25 Mhz Freq-2.25 Mhz Velocity 0.124 i
Velodly 0.126 Length 6 FT Manuf:
KBA Manuf:
KBA UMs IN Uds IN Ser no:
43072 Initial Cal Time Ser no:
42967 Display FILT1 Display FILT1 Meas. g 45*
Freq 2.25 as. g 60*
Freq 2.25 I
sup1 1406 su#2 1350 Wedge:
MSW-QC Wedge:
MSW-QC Reject OFF Reject OFF CalChecks Wave Mode: 'Long. O Shear G Time Wave Mode: Lon9 O Sh= 0 eusse 222 puise 222 osse s u si s.u #2 inneels Bi-Model O Bi-Modal O Dampine 500
- Dampo, 500 s 18/96 1430 1441 Molor Screen Div =
0.25 inches 1 Major Screen Dw =
0.5 inches Rg Rate 2000 Rep Rm 2000 h
Scan; axial O circ-O Scan:
==w B
- O W18t96 1440 1450 s
M TORO
. sack: TBRO FINAL Dual O PulseEcho O Dual O Pulse Echo @
Record Indications Limitations Scanning dB Scan Direction Exam Date and Time w
l Stem No:
yes no yes no s.u 81 s.u #2 Axial Cire.
Start End Temp
- B09.011.164 -
O 8
8 0
45 50 YES YES W18/961430 6/18/96 1450 72*F B09 012.164 O
B (L ;E 45 50 YES YES 6/18t961430 6/18t961450 72*F
[
n Date:
Reviewer Level:
Date:
Authorized inspect.
[f hb'
YM Ill 6/19f96 ww me 44M
,wue:,,,-oim e u es 7. -u*
l A TTacassacT 2 #a s. 9 DUKE POWER COMPANY FORM NDE-UT-1G ULTRASONIC CAllBRATION/ EXAMINATION RECORD FOR NDT-136 INSTRUMENTS REVISION 5 Station:
Catawba Unit:
1 Date:
6/18/96 Sheet Numbec 9601020 Procedure:
NDE-600 Revt 7 FC:
N/A Couplant:
ULTRAGEL 11 Batch Numbec 093001 Examinen Jay A. Eaton h)[_
Level: !!
Manufacturen STAVELEY Pyrometer S/N:
MCNDE 27025 i i Examiner: B. Dale Jolly g QQ Level: I Serial No:
975K Cal Due:
10/3/96 REFERENCE BLOCK
\\
k SIMULATOR BLOCK ID:
ROMPAS Search Unit 81 Search Unit # 2 ID:
A09319 Reflector Type: RADIUS ID:
N/A Reflector Type:
N/A SIN:
A09319 Material:
SS Metal Path:
1" Metal Path:
N/A CABLES Search Unit # 1 Settings Search Unit # 2 Settings RG58 O RG174 g Type:
Single O Dual B R,nge 3o Type: Se O Dual O i
Range
- et connectors 0
y 0.770 W ay Freq-2.0 Mhz Velocity 0.227 Freq:
Mhz y
Manuf:
Sigma Manuf:
Units IN Units initial Cal Time Ser no:
2244-93001 Ser no-Display FILT1
"" 0= %
s u e1 1451 sus 2 Meas. g 60*L Freq 2.25 eas. g p,,q Wedge:
INT e
Reject OFF Reject T
Wave Mode: Long.O Shear O
- " d*
' "9 O Shear O Puise 222 Puise cate s u st s u.s2 intials Bi-Modal O Damping 500 am O Dann 6/18/96 1500 1 Major Screen Dtv =
0.5 inches 1 M81 8"
Rep Rale 2000 Rep Rate FINAL Scan: axial @
circ. O Scan: adal O
- O 7ggg Dual O Pulse Echo O Dual O Pulse Echo O aacic TORO Record Indications Limitations Scanning dB Scan Direction Exam Date and Twne Item No:
Surface yes no yes no s.u.#1 s.u #2 Axial Circ.
Start End Temp *
(
B09 011163 O
8 8
0 67 YES 6t18/961451 6/18/96 1500 72*F B09 011.164 Q
Q 67 YES 6/18/96 1451 6/18/96 1500 72*F n_
A'am M Revh..
Level:
Date:
AuthorizedinNs A' v&M CD te:&R w
s-n n x
Li feauest F ca. Re.ad % -
Arracuadrf /d 4os 9 FORM ME-m DUKE POWER COMPANY ISI LIMITATION REPORT Revision I Componer.'./ Weld ID: 1N1148-10 item No: B09.011.163 Remarks:
SURFACE BEAM DIRECTION
< WELD TAPER S NO SCAN 81 02 0 1 9 2 0 = 0 cm O LIMITED SCAN FROM L, _ _ _ _ _, to L _ _ _ _ _
INCHES FROM WO, _ _C@_ _, to _ _ 0;7_" _ _
ANGLE: O o O 45 8 60 8 Other 60*L FROM,_ o _ DEG to __360_DEG SURFACE BEAM DIRECTION
< VALVE CONFIGURATION E NO SCAN O1 82 8102 O cw O ccw O LIMITED SCAN FROM L - - _ _ _ _. to L _ _ _ _ _
INCHES FROM WO _ _ _._C_/L_ _. to _ _B_.E_YO_N_D _
i ANGLE-O o O 45 8 60 8 Other 60*L FROM,_ o_ _ DEG to _ 360_DEG SURFACE BEAM DIRECTION O NO SCAN O1 02 0 1 0 2 O cw 0 ccw O LIMITED SCAN FROM L to L INCHES FROM WO to ANGLE-O o O 4s O 60 0 Other FROM, _ _ _ DEG to _ _ _ _DEG SURFACE BEAM DIRECTION O NO SCAN O1 02 0102 O cw O ccw l
O LIMITED SCAN t
FROM L to L INCHES FROM WO to i
ANGLE-O o O 45 0 60 0 Gtt er FROM _ _ _ DEG to _ _ _ _
n Level:
II Date: 6/18/96 Sketch (s) attacged @ yes O no Sheet
/ of 3 Prepared By: Jay Eaton g
Reviewed By: Larry Mauldi ggg' Date:
6/19/96 Authorized Inspector yc Date: ),yg d
I 9
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DUKE POWER COMPANY NDE-91-1 s
Limited Examination Coverage Worksheet M
Revision 0 N
Examination Volume / Area Defined y
i O Base Metal O Weld O Near Surface O Botting O inner Radius 5K D
Area Calculation Volume Calculation f.42" X 1.85" =.777 sq. in. =.78 sq.in.
.78 sq. in. X 34.4" = 26.83 cu.in.
x l
i i
Coverage Calculations Area Length Volume Volume d
([n.
cu i )
(cu i )
Percent Coverage Scan # Angle D ree on qi )
Axial 45/60L 2
.72 34.4 24.77 26.83 92.32 Cire.
45 CW
.34 34.4 11.7 26.83 43.61 Cire.
45 CCW
.34 34.4 11.7 26.83 43.61 4 8.11 +-
80.49 x,100 5 59.85%
I f
Item No:
B09.011.163 nam.v.,
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nev,e.ee sy;torry u.uie,n Rygg.- tevei:
iii o.te: 7/22ise O
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lb aerrFol Y6dGF 96 9 A-rrnca.uer2 Pa sor9 NDE-UT-5 DUKE POWER COMPANY UT PkOFILE/ PLOT SHEET Revision 1 t
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0 Component ID/ Weld No.
_l Al.I 148-I D
- Remarks:
Profile taken 270' at:
0-90 i
ltem No: L 9.o //,/(,f i
A 4_
Examiner:
p JE_3 Level: E Date: l zz 9(,
Reviewed By:
J71;z.%al//a, _ Level: 2E-Date: /.J).96 180 Sheetl_of 3
(
i Authorized Inspector: O}/[{@(Micp//
Date: ~)-24Gf
$6pussr foA Nsuer % 04.
),TrAemear/ /d for9 f
DUKE POWER COMPANY ISI LIMITATION REPORT Revision 1 r
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Component /Wekt ID: 1NI148-11 Item No: Bo9.011.164 Remarks SURFACE-BEAM DIRECTION
< WELD TAPER B NO SCAN f
91 02 0 1 B 2 0 = 0 cm O LIMITED SCAN FROM L _ _ _ _ _ _. to L _ _ _ _ _
INCHES FROM WO _ __ _C_/_L_ __. to __ _ _0.7_" __ _
ANGLE: O o O 45 8 60 8 Other 60*L FROM._ _o _ DEG to _ __36_0_ __DEG SURFACE BEAM DIRECTION
< VALVE CONFIGURATION O NO SCAN O1 B2 B 1 020 = 0 cm O LIMITEDSCAN FROM L _ _ _ _ _ _. to L _ _ _ _ _
INCHES FROM WO _ _ __C_/L__ _. to _ _BE_YO_N_D _
P ANGLE: O o O 45 8 60 8 Other 60*L FROM._ _o __ DEG to _ __36_0__DEG SURFACE BEAM DIRECTION j
O NO SCAN O1 02 0 1 0 2 0 = 0 cm O LIMITED SCAN ii F ROM L _ _ _ _ _ _, to l _ _ _ _ _
INCHES FROM WO, _ _ _ _ _, to _ _ _ _ _ _
i ANGLE: O o O 45 0 60 0 Other FROM._ _ _ DEG to _ _ __ _DEG SURFACE BEAM DIRECTION O NO SCAN O1 02 0 1 0 2 0 = 0 c=
O LIMITED SCAN e
FROM L _ _ _ _ _ _. to L _ _ _ _ __
INCHES FROM WO _ _ _ _ _ _. to _ _ _ _ _ _
O o O 45 0 60 QOf e FROM DEGto ANGLE:
i Prepared By: Jay Eaton p
[ N avel:
ll Date: SI18196 Sketch (s) attached B yes Qno Sheet / of j
/ 1 6/19196 Authorized inspector'
[ fy)
Date: p.g,g Reviewed By: Lany Mauklin g hgDate:
g t
~.-_... _ _. _. _
9-o-
1 0
'4 DUKE POWER COMPANY NDE-91-1 M
Limited Examination Coverage Worksheet l%
Revision 0
- {f Examination Volume / Area Defined Q Base Metal S Weld O Near Surface O Bolting O inner Radius Area Calculation Volume Calculation
.33" X 1.6" =.528 sq. in. =.53 sq.in.
.53 sq. in. X 34.4" = 18.23 cu.in.
Coverage Calculations 1
Area Length Volume Volume i
Percent Coverage Scan # Angle D rection qt
( n.
u in ui Axial 45/60L 1
.45 34.4 15.48 18.23 84.91 Cire.
45 CW
.26 34.4 8.94 18.23 49.04 Cire.
45 CCW
.26 34.4 8.94 18.23 49.04 2.f. 3 C.
4 SV, (A x / oo :
4/*A h
item No:
B09.011.164 r
e,e9.,eeB,,.,e._
m Le..,
e.,e
-,e Level:
D.te 7/22/96 Reviewed By: Lany Ms.uldin gjgg Y
~.. _. _._
AEquerr fog HeGef 94--84 j
kTrotntotr2 A2 9or 9
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NDE-UT-5 DUKE POWER COMPANY i
Revision 1 i
UT PROFILE / PLOT SHEET t
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- Remarks.
I Profile taken 90 270 at:
0 Item No: hq.e 13,1,4L j
/T Examiner:
jK Level 3C Date: 7 rz. %
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Reviewed By: MM ' &,//u Level:-././.E Date: 7.U46 180 Sheet 7 of3 l
e Authorizedii4-Ator:d '
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ATTACHMENT 2
ATTACHMENT 2
NRC RAI LETTER l
Form NDE-35A l Revision 3 DUKE POWER COMPANY STATION Catawba UNIT 1
LIQUID PENETRANT EXAMINATION REPORT Weld /lD No. 1N1148-10 Material Type: O SS O CS O Inconel Diameter 10 Schedule / Thickness 140/1 O ISI O PSI O Other Procedure Rev. No.
16 Field Change No.(s) N/A W/O No.
96014620-01 SKETCH OF ITEM EXAMINED l
Surface Temperature 72'F M&TE S/N:
MCNDE 27025 Penetrant Materials Category:
A O A(SE) O BOC0D0 A(SE) Approved Penetrant Materials Data:
Batch Numbers Cleaner 94J01K Penetrant 95E05K Developer 95D07K Emulsifier N/A d
Fluorescent O Nonfluorescent O Black Light Intensity Verified Acceptance Standard:
AO D0 GO KO Time Date Other:
N/A CO FG JO MO o.
Type n ions NRI PlP S/N:
N/A Rejectable O Acceptable O Exam Limitations:
0 Yes
% Examined O No(100% Examined)
Comments:
Examiner Guy G. Bibb
[w I M Level:
11 Date:
6/18/96 Examiner: Gary J. Moss Md// ((/A,.o Level:
ll Date:
6/18/96 Reviewed By: Laay Mauldin MN YleMM Level:
Il Date:
6/18/96
' ~Date ()
/
Nil Review Date item No.
Final Review
$l26l9f,
/.
4' / R (l))- (
B09.011.163A
1 l
\\
S ATTACHMENT 3 l'
ATTACHMENT 3
NRC RAI LETTER l
Form NDE-35A l Revision 3 DUKE POWER COMPANY STATION Catawba UNIT 1
i LIQUID PENETRANT EXAMINATION REPORT Weld /lO No. 1N1148-11 Material Type: O SS O CS O inconel Diameter 10 ScheduleTThickness 140/1 O ISI O PSI O Other Procedure Rev. No.
16 Field Change No.(s) N/A W/O No.
96014620-01 SKETCH OF ITEM EXAMINED i
Surface Temperature 72*F I
M&TE S/N:
MCNDE 27025 l
1 Penetrant Materials Category:
A O A(SE) O BOCODO A(SE) Approved I
Penetrant Materials Data:
Batch Numbers Cleaner 94J01K 2
Penetrant 95E05K Developer 95D07K
)
Emulsifier N/A Fluorescent O
Nonfluorescent O Black Light Intensity Verified Acceptance Standard:
Time Date Other BO EO HO L0 Light Meter S/N:
N/A c0 F0 JO MO RepodaE eferen e Documents Re m aNe o.
Type n ions NRI 4
PIP S/N:
N/A Rejectable O Acceptable O Exam Limitations:
0 Yes
% Examined O No(100% Examined)
Comments:
Examiner Guy G. Bibb
[a M M Level:
11 Date:
6/18/96 Examiner Gary J. Moss Md/f M/
Level:
11 Date:
6/18/96 Reviewed By: Larry Mauldin [b M/1///I4 Level:
11 Date:
6/18/96 Final Review Date[/
/ / ANilRev w Date item No.
$5 4/2ll%
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B09.011.164A t