ML19327A403
| ML19327A403 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/03/1980 |
| From: | Aswell D LOUISIANA POWER & LIGHT CO. |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| IEB-80-08, IEB-80-8, LPL-14415, Q-3-A20.03.14, NUDOCS 8008060150 | |
| Download: ML19327A403 (14) | |
Text
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LOUISlANA P O W E R & L i G H T! P o. BOX 6008
- NEW OnLEANS. LOUISIANA 70174 242 cea naNoe srnesr
. (504) 366-2345 UTIUTIES SYSTEM O.L W M July 3, 1980 v<e %we=eo-ee %om LPL 14415 0-3-A20.03.14 Mr. Karl V. Seyfrit, Director, Region IV U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
SUBJECT:
Waterford 3 SES Docket No. 50-382 IE Bulletin 80-08
Dear Mr. Seyfrit:
We have reviewed the subject IE Bulletin concerning the containment pressure boundary welds between the piping penetration assemblies flued head and the penetration sleeve. We have reviewed the design of Waterford's penetrations with regard to NRC's concerns outlined in the bulletin and submit the following:
1.
The design of Waterford's containment piping penetration assemblies is of f.he type described in the bulletin.
2.
a.
The assemblies were designed and fabricated to the 1971 Edition of the ASME B&PV Code,Section III, up to and including the Winter 1973 Addenda.
The NRC Regulatorv Guide 1.19 does not apply to Waterford 3 (Reference FSAR Section 1.8.1.19).
b.
The design of the majority of Waterford's assemblies employs a flued head in which the guard or process pipe welds directly to the containment vessel nozzle.
This design includes a guard or process pipe to flued head weld, guard or process pipe to containment nozzle weld and, in some instances, a transition piece is welded to the guard pipe to enable the welding of the penetration to the containment nozzles.
The remaining penetration designs are similar to those shown in Figure NE-1120-1 of the ASME Section III.
The design requires thst all containment boundary butt welds 80080801S0' Q
Mr. Karl V. Seyfrit LPL 14415 Page 2 be radiographed per applicable codes. Other NDE performed on these welds include, ultrasonic, magnetic particle, liquid penetrant and/or visual examinations as required by specification and code.
c.
All but two welds are either consumable insert or open root. The remaining two welds, used to weld Penetrations 1 and 2 to the containment nozele, are non-butt corner welds which will be magnetic particle tested per NE-5262. Table 1, attached, identifies by penetration number, the size and material compositicn pressure boundary welds.
d.
Temp Flex, a penetration fabricator, performed the nondestructive examinations, including radiography, on all containment pressure boundary shop welds. The results of the nondestructive examination of field welds are indicated on Table 2.
Please note that since construction is under way, some welds have yet to be completed or examined, but examination will be in accordance with codes.
3.
This item is not applicable to Waterford 3.
If you have any questions on the above, please contact us.
Yours very truly, b K44%bf D. L. Aswell DLA/IH/dde Attachments cc: Director U. S. Nuclear Regulatory Commission Division of Reactor Construction Inspection Washington, D. C.
20555
TABLE 1 Guard Ploe Containment Nozzle Pene No.
Type
!!om Pipe Dia/Sch Material Fom Pipe Dia/Sch Material Flued Head Mat.
'l I
61[1/2" SA-155-KCF-70 CL 1 66/3" SA-516-GR-70 SA-350-LF2 66" OD End Ring SA-516-GR-70 2
I 61/1/2" SA-155-KCF-70 CL 1 66/3" SA-516-GR-70 SA-350-LF2 66" OD End Ring SA-516-GR-70 42-3/4[3/4" 44[1-1/[
3 I
SA-155-KCF-70 SA-36-GR-70 SA-350-LF2 44[1-1/4 42-3/4[3/4 SA-155-KCF-70
~
4 I
SA-516-GR-70 SA-350-LF2 5
III 14/80 SA-106B 14/80 SA-333-GR-6 SA-350-LF2 6
III 14/80 SA-106B 14/80 SA-333-GR-6 SA-350-LF2 7
III 8/40 SA-106B 8/80 SA-333-GR-6 SA-182-F304 8
III 8/40 SA-106B 8/80 SA-333-GR-6 SA-350-LF2 9
III 8/40 SA-106B 8/80
~ SA-333-CR-6 SA-350-LF2 10 II 48/1" SA-155-KCF-70 Flanged Joint to SA-350-LF2 (Mod)
CL 1 Cont Nozzle 11 II 48/1" SA-155-KCF-70 Flanged Joint to SA-350-LF2 1
(Mod)
CL 1 Cont Nozz1e 12 Not Applicable 13 Not Applicable 14 III 8/40 SA-106B 8/80 SA-333-GR-6 SA-350-LF2 15 III 14/40 SA-106B 14/140 SA-333-GR-6 SA-350-LF2 14/140 SA-106B 1
Containment Nozzle Guard Pipe Pene No.
Type Nom Pipe Dia/Sch Material Nom Pipe Dia/Sch Material Flued H e a d R1t.
16 III_
14/40 SA-106B 14/140 SA-333-GR-6 SA-350-LF2 14/140 SA-106B 17 III 14/40 SA-106B 14/140 SA-333-GR-6 SA-350-LF2 14/140 SA-106B 18 III 14/40 SA-106B 14/140 SA-333-CR -6 SA-350-LF2 14/140 SA-106B 19 III 14/40 SA-106B 14/140 SA-333-GR -6 SA-350-LF2 14/140 SA-106B 20 III 14/40 SA-106B 14/140 SA-333-CR-6 SA-350-LF2 14/140 SA-106B 21 III 14/40 SA-106B 14/140 SA-333-GR-6 SA-350-LF2 14/140 SA-106B 22 III 14/40 SA-106B 14/140 SA-333-GR-6 SA-350-LF2 14/140 SA-106B 23 III 14/40 SA-106B 14/140 SA-516-GR'-70 SA-350-LF2 14/140 SA-106B 24 III 14/40 SA-106B 14/140 SA-516-GR-70 SA-350-LF2 14/140 SA-106B 25 VI SA-516-GR70 48/1-1/4 SA-516-GR-70 N/A j
48-1/4"[1-1/4" 26 III 10/140 SA-106B 10/120 SA-333-GR-6 SA-182-F304 27 III 10/120 SA-106B 10/120 SA-333-GR -6 SA-182-F304 10/120 SA-333-GR-6 SA-182-F304 28 III 10/140 SA-1068 29 III 10/140 SA-106B 10/120 SA-333-CR-6 SA-182-F304 4
I N/A - Not Applicable 2
Containment Nozzle Guard Pipe Pene No.
Type.
Nom Pipe Dia/Sch Material Nom Pipe Dia/Sch Material Flued Head Mat.
30 III 10/140 SA-106B 10/120 SA-333-GR-6 SA-182-F304 31 III 8/40 SA-106B 8/80 SA-333-GR-6 SA-350-LF2 36[1-1/2" SA-516-CR-70 N/A 36[1-1/2" SA-106B 32 IV SA-106B 36[1-1/2" SA-516-CR-70 N/A 36ft-1/2" 33 IV 34A II 10/40 SA-312-TP-304 10/160 SB-168 SA-182-F304 35A II 10/40 SA-312-TP-304 10/160 SB-168 SA-182-F304 36 III 18/120 SA-106B 18/120 SA-333-GR-6 SA-182-F304 37 III 18/120 SA-106B 18/120 SA-333-GR-6 SA-182-F304 38 III 18/120 SA-106B 18/120 SA-333-GR-6 SA-182-F304 39 III 18/120 SA-106B 18/120 SA-333-GR-6 SA-182-F304 40 III 24/120 SA-106B 24/120 SA-516-GR-70 SA-182-F304 41 III
%/120 SA-106B 24/120 SA-516-GR-70 SA-182-F304 42 III 10/40 SA-106B 10/80 SA-333-GR-6 SA-182-F304 43 V
8/100 SA-106B 8/160 SA-333-GR-6 N/A 44 III 6/120 SA-106B 6/120 SA-333-GR-6 SA-182-F304 45 III 8/40 SA-106B 8/160 SA-333-GR-6 SA-350-LF2 46 III 8/40 SA-106B 8/160 SA-333-GR-6 SA-350-LF2 47 III 8/40 SA-106B 8/160 SA-333-CR-6 SA-350-LF2 N/A - Not Applicable 3
Containment Nozzle Guard Pipe P5ne No.
Type Nom Pipe Dia/Sch Material Nom Pipe Dia/Sch Material Flued Head Mat.
48 III 8/40 SA-106B 8/160 SA-333-GR-6 SA-350-LF2 49 II 10/80 SA-106B 10/80 SA-333-GR-6 SA-350-LF2 10/80 Weld Cap SA-234-WPB 50 Not Applicable 51 III 10/40 SA-106B 10/80 SA-333-GR-6 SA-182-F-304 52 III 8/80 SA-106B 8/80
'SA-333-GR-6 SA-350-LF2 53 II 6/80 SA-106B 6/80 SA-333-GR-6 SA-350-LF2 (Mod) 6/80 Weld Cap SA-234-WPB 54 II 6/80 SA-106B 6/80 SA-333-GR-6 SA-350-LF2 (Mod) 6/80 Weld Gap SA-234-WPB 55 III 14/60 SA-106B 14/140 SA-333-GR-6 SA-182-F-304 56 III 14/80 SA-106B 14/140 SA-333-GR-6 SA-182-F-304 57 III 14/80 SA-106B 14/140 SA-333-GR-6 SA-182-F-304 SA-106B 14/140 SA-333-GR-6 SA-182-F-304 58 III
, 14/80 59 III 8/100 SA-106B 8/160 SA-333-GR-6 SA-182-F-304
~
60 III 8/40 SA-106B 8/80 SA-333-GR-6 SA-182-F-304 61 III 8/40 SA-106B 8/80 SA-333-GR-6 SA-350-LF2 62 III 10/40 SA-106B 10/80 SA-333-GR-6 SA-182-F-304 63 II 10/80 SA-106B 10/80 SA-333-GR-6 SA-350-LF2 f
4
Centninment Nozzist Guerd Pipe Pine No.
Type Nom Pipe Dia/Sch Haterial Nom Pipe Dia/Sch Haterial Flued IIcad Mat.
64 Not Applicable 65-II 8/80 SA-106B 8/80 SA-333-GR-6 SA-350-LF2 (Mod) 8/80 Weld Cap SA-234-WPB 66 II 6/80 SA-106B 6/80 SA-333-GR-6 UA-350-LF2 (Mod) 6/80 Weld Cap S A-234-WPB 67 II 6/80 SA-106B 6/80 SA-333-GR-6 SA-350-LF2 6/80 Weld Cap SA-234-WPB SA-333-GR-6 SA-350-LF2 68 III 8/80 SA-106B 8/80 69 III 14/140 SA-106B 14/140 SA-333-GR-6 SA-182-F-304 70 III 14/140 SA-106B 14/140 SA-333-Gib 6 SA-182-F-304 71 III 8/80 SA-106B 8/80 SA-333-GR-6 SA-182-F-304 72 Not Applicable 1
5
I TABLE 2 in NDE Type of Method:
Weld Extent of Repairs /Tvoe Defects Remarks In process 1
MT Corner Scheduled completi1 Weld date 6-15-80 Weld to be comple9 2
MT Corner 8-80 Weld In process 3
RT Insert Information expec9 by 7-80 Weld to be complet-4 RT Insert by 8-80 5
RT Insert No Repairs Complete 6
RT Insert No Repairs Complete 7
RT Insert No Repairs Complete 8
RT Insert No Repairs Complete 9
RT Insert No Repairs Complete N/A 0
N/A 1
N/A 2
N/A 3
4 RT Insert RO Porosity Complete (PT of R1 No Repairs exCaV.
5 area)
Complete
.5 RT Insert No Repairs
.6 RT Insert RO - Slag inclusion Complete (PT of R1 - Slag inclusion R2 - No Repair excav.
area)
Complete
.7 RT Insert RO - Slag (PT of.
R1 - Slag & Porosity R2 - No Repair excav.
area)
I Complete
.8 RT Insert No Repair
Z o
NDE Type of i
Weld Extent of Repairs /Tvee Defects Remarks Method 9
RT Insert No Repair Complete O
RT Insert No Repair Complete 1
RT Insert RO - Slag Complete (PT of R1 - No Repair CxCav.
crea) 2 RT Insert No Repair Complete 3
RT Insert No Repair Complete 4
RT Insert.
No Repair Complete 5
RT Insert Weld 1 Complete PT Root R0 PT accept.
RT Slag, porosity, low cap R1 Details not available at this time R2 No Repair Weld 2 Rejected RW1 Crack, Porosity, Tungster Inclusion Slag 6
RT Insert Porosity Rejected 7
RT Insert No Repairs Complete 8
RT Insert No Repairs Complete 9
RT Insert R0 Incomplete penetration Rejected R1 Concavity, Bur n through 0
RT Insert No Repairs Complete 1
RT Insert No Repairs Complete 2
RT Insert Weld No. 2 Complete UT of R0 Slag, concavity repair R1 Not available at this time R2 Not available at this time Weld No. 3 Complete RO Incomplete fusion and slag R1 Incomplete fusion and slag R2 Not available at this time
?
R3 Incomplete fusion R4 Unconsumed Insert RS Concavity R6 Excessive penetration R7 Weld cap R8 Low cap
~
13 NDE Typa of Method Weld Extent of Repairs /Tvoe Defects Remarks 3
RT Insert Weld No. 2 Complete UT of R0 Burn throuch repair R1 Not available at this time Weld No. 3 R0 Not available at this time R1 Slag line R2 Porosity & Slag No Status 4
RT Insert No Status 5
RT Insert 6
RT Insert No Repairs Complete 7
RT Insert No Repairs Complete 48 RT Insert R0 Slag Reject R1 Slag
- 9 RT Insert No Repairs Complete 0
RT Insert 20 Slag Reject il RT Insert No Repairs Weld complete Requires PWHT Weld Complete 12 RT Insert Requires NDE i3 RT Insert Weld No. 2 Complete No Repairs RT Weld No. 3 PT of R0 Porosity excav.
R1 No Repairs area 14 RT Insert No Repairs Complete
.5 RT Insert No Repairs Complete 6
RT Insert No Repairs Complete
area 18 RT
' Insert No Repairs Complete 19 RT Insert No Repairs Complets Spare 50 n
4
.o NDE Type of Method Weld Extent of Repairs / Type Defects Remarks il RT Insert No Repairs Complete 12 RT Insert No Repairs Complete 13 RT Insert No Repairs Complete 54 RT Insert No Repairs Complete 55 RT Insert No Repairs Complete 56 RT Insert No Repairs
- Complete 57 R.T Insert No RSpairs
- Complete 58 RT Insert No Repairs Complete 59 RT Insert No Repairs Complete 50 RT Insert No Repairs Complete 51 RT Insert No Repairs Complete 52 RT Insert No Repairs
. Complete 53 RT Insert No Repairs Complete 54 Spare
. Complete 55 RT Insert No Repairs 56 RT Insert No Repairs
' Complete 57 RT Insert No Repairs Complete 58 RT Insert No Repairs Complete 59 RT Insert No Repairs Complete 70 RT Insert R0 Porosity Complete R1 No Repairs 71 RT Insert Weld to be comple' 8-80 Spare 72 s
e
L.OUISIANA P Q W E R & L i G H T[ F. O. BOX 6008 + NEW CALEANS. LOUlslANA 70174 242 osanoNes s1nes1
. (5041 366-2345 U
YS Q L ASWELL April 14, 1980 s,c, o,......., e,w e LPL 13628 3-A20.03.14 Mr. R. K. Stampley Ebasco Services, Inc.
Response Req:
Two Rector Street June 16, 1980 New York, New York 10006
SUBJECT:
Waterford SES Unit 3 I E Bulletin No. 30-08 Attached is the IE Bulletin 80-08 sent to LP&L by Nuclear Regulatory Cocmission.
Please review it and forward your recommendations to us no later than June 16, 1980.
If you have any questions, please let us know.
Yours very truly,
'Oanx D. L. Aswell DLA:IH!bms Attachment ec:
Ebasco (2), J. M. Brooks, J. Crnich (2), L. V. Maurin, D. B. Lester, F. J. Drummond, T. F. Gerrets, C. J. Decareaux, T. K. Armington, P..V. Prasankumar, D. C. Gibbs, C. A. Ponder, Richard Hymes, M.
I. Meyer.
L. L. Bass, Central Records a
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NUCLEAR REGULATORY COMMISSION UNITED STATES r
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'n REGloN IV L'!
611 RYAN PLAZA oRIVE SUITE 1000 w
'[ f ARLINGTON,TEXA5 76012
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April 7, 1980 In Reply Refer To:
RIV Docket No.
50-382/IE Bulletin No. 80-08 Louisiana Power and Light Co.
ATTN:
Mr. D. L. Aswell Vice President of Power Production 142 Delaronde Street New Orleans, Louisiana 70174 Gentlemen:
The enclosed IE Bulletin 80-08 is forwarded to you for action.
A written response is required.
If you desire additional information regarding this ratter, please contact this office.
Sincerely, f-0
/
.A, f.
e Karl V. Seyfrit i
Director
Enclosure:
1.
Listing of IE Bulletins Recently Issued l
~
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' N.:.:.:.
a
t SSINS No.: 6820 UNITED STATES Accessions No.:
NUCLEAR REGULATORY COMMISSION 7912190650 OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 i
IE Bulletin No. 80-08 Date:
April 7, 1980 Page 1 of 2 EXAMINATION OF CONTAINMENT LINER PENETRATION WELDS Description of Circumstances:
On March 20-23, 1979,. an NRC inspection at Nine Mile Point Unit 2, identified that certain nondestructive examinations performed on containment penetration welds did not satisfy the applicable ASME Boiler and Pressure Vessel (B&PV) t Code requirements.
The welds in question were the primary piping containment j
penetration flued head (integral fitting) to outer sleeve welds which form a part of the containment pressure boundary.
The examinations performed included ultrasonic and surface inspections of the outer surface.
Subsequent to the identification of this code problem at Nine Mile Point Unit 2, three welds previously found to be acceptable using ultrasonics were radio-graphed and two revealed indications in excess of the code allowable.
The indications revealed by radiography were slag and lack-of-fusion.
Preliminary NRC review indicates that the probable reason the indications were not detected by ultrasonics was due to masking from signals received from the backing bar.
i As a result of these findings, a complete re-examination program at Nine Mile 1
Point Unit 2 was initiated, wherein 10 of 17 welds previously examined and found to be acceptable using ultrasonics were re-examined by radiography before rework and found to have indications exceeding ASME Code allowables.
l 1
Additional information concerning Beaver Valley Unit 2 and North Anna 3 and 4 has also shown cases of flued head piping penetration weld defects exceeding ASME B&PV Code acceptance criteria when radiographed.
Original approved vendor procedures at Beaver Valley Unit 2 did not require volumetric examina-tion.
Radiography for information purposes disclosed the unacceptable indica-tions at North Anna 3 and 4. Specification deficiencies have also been discovered at Millstone 3 and River Bend where radiography of there welds was not required.
i The ASME B&PV Code. requires radiography of the subject welds with specified exceptions.
The licensees and their architect-engineer (Stone and Webster) had specified ultrasonics as the volumetric examination method because, in their judgement, radiography was impractical for the penetration geometry.
Radiography was successfully performed at North Anna 3 and 4 prior to the identification of this problem, and at Beaver Valley 2 and Nine Mile Point 2
-subsequent to NRC inspections.
This experience indicates that radiography was meaningful and more practical than UT examination of these penetration welds when backing bars are present.
O 7 9 ( E/ 9 0 G TO p
IE Bulletin No. 80-08 Date:
April 7, 1980 page 2 of 2 Action to be Taken by Licensee:
For all power reactor facilities with an operating license or a construction permit:
1.
Determine if your facility contains the flued head design for penetration connections, or other designs with containment boundary butt weld (s) between the penetration sleeve and process piping as illustrated in Figure NE 1120-1, Winter 1975 Addenda to the 1974, and later editions of the ASME B&PV Code.
2.
If an affirmative answer is reached for Item 1, determine the following:
Applicability of the ASME Code, including year and addenda and/or a.
Type of nondestructive examinations performed during construction, c.
Type of weld joint (including pipe material and size) and whether or not backing bars were used, d.
Results of construction nondestructive examinations, i.e.,
if repairs were required, this should be identified including extent of repairs and description of defects encountered during repair, if known.
3.
For those facilities committed during construction to perform volumetric examination of such penetrations through SAR commitments which have not performed radiography, justify not performing radiography or submit plans and schedules for performing radiographic examinations.
Within 90 days of the date of this Bulletin, facilities with an operatins license or a construction permit shall submit the information requested in Items 1, 2, and 3 of this Bulletin.
Reports shall be submitted to the Regional Director with a copy to the Director, Division of Reactor Construction Inspection, Washington, D. C.
20555.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80.
Approval was-given under a blanket clearance specifically for identified generic problems.
i 1
As sulletin No. 80-08 April 7, 1980 RECENTLY ISSUID II BULLETINS Bulletin Subj ect Date Issued Issued To No.
80-04 Analysis of a PWR Main 2/8/80 All PWR reactor facilities Steam Line Break With holding Operating Licenses Continued Feedwater (OLs) and to those nearing Addition Licensing 79-01B Environmental Qualification 2/29/80 All power reactor of Class IE Equipment facilities with an Operating License (OL) 80-05 Vacuum Condition Resulting 3/10/80 All PWR power reactor In Damage To Chemical facilities holding
' Volume Control System Operating Licenses (OLs)
(CVCS) Holdup Tanks and to those with a Construction Permit (CP) 80-06 Engineered Safety Feature 3/13/80 All power reactor facilitic (EST) Reset Controls with an Operating License (OL)79-03A Longitudinal Weld Defects 4/4/80 All power reactor facilitic In ASME SA-312 Type 304 with an Operating License Stainless Steel Pipe (OL) or Construction Per=it 1
(CP) 80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and BWR-4 Failure facilities with an Operati:
License (OL)
Enclosura.
1
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i
EBASCO SERVICES INC0HPORATED ENGINE E R s - C O N s TRUCTO R s - C O N SU LTANT s T\\VD RECTOR STRFET N EW YU RK. N.Y. 1000G c..a.oo. ass.... w p
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File: 4Q-P-4 1-I-8
'*r D L Acuell Vice Presidant - Power Production Louisiana Power & Light Company J42 Delaronde Street New Orleans, LA 70174 f,. f '.
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ac:
RATERFORD SES UNIT NO. 3
/
IE EULLETIN NO. 80-03
!(.-
P.af :
LPL-13628, dated April 14, 1980
Dear Mr Asuell:
Uc have revieued the subject IE Bulletin concerning the containment pressure boundary welds between the piping penetration assemblius flued head and the penetration sleeve. We have reviewed the design of Water-ford's penetrations with regard to NRC's concerns outlined in the bulletin and submit the following:
1.
The design of Caterford's containment piping penetration asseublics is of the type described in the bulletin.
2.
a.
The assemblies were designed and fabricated to the 1971 Edition of the ASME B&PV Code,Section III, up to and including the Winter 1973 Addenda. The NRC Regulatory Guide 1.19 does not apply to Waterford 3 (Reference FSAR Section 1.8.1.19).
b.
The design of the majority of Waterford's assemblics employs a flued head in which the guard or process pipe welds directly to the containment vessel nozzle. This design includes a guard or process pipe to flued head weld, guard or process pipe to containment nozzle weld and, in some instances, a transition piece is uelded to the guard pipe to enable the welding of the penetration to the containment nozzles.
The remaining penetration designs are similar to those shown in Figure NE-1120-1 of the ASME Section III. The design requires that all containment boundary butt welds be radiographed per applicable codes.
Other MDE perforced on these welds include, ultrasonic, magnetic par-ticle, liquid penetrant and/or visual examinations as required by-specification and code.
]
l 1
3 US ASCO SERVICES
. 8 %COR Pon At t b Ur:D L Aswell June 13, 1980 c.
All but two welds are either consumable insert or open root.
The remaining two welds, used to weld Penetrations 1 and 2 to the containment nozzle, are non-butt corner welds which will be' magnetic particle tested per :;E-5262. Table 1, attached, identifies by penetration number, the size and material composi-tion pressure boundary welds.
d.
Temp Flex, a penetration fabricator, performed the nondestruc-tive examinations, including radiography, on all containment pressure boundary shop welds.
The results of the nondestructive examination of field welds are indicated on Table 2.
Please note that since construction is under way, some welds have yet to be completed or examined, but examination will be in accord-ance with codes.
The remaining information will be forwarded to you when it beco=as available.
3.
This item is not applicable to Waterford 3.
1[youhaveanyquestionsontheabove,pleasecontact us.
Very truly yours, J F FRP.O!
Chief "echanical-Nuclear Engineer f'<j','s,,Q f /
/
&n 1
Ns.
/v DJM:j j Thl -
By: C F M Trapp Att cc:
D L Aswell L V Maurin D B Lester F J Drummond C J Decareaux T F Gerrets w/att C Gibbs.
T K irmington Power Production Dept - Nuc (2) w/att Waterford 3 Site (2) w/att LPSL Site QA w/att P V-Prasankumar
_ Project Engineer g
.