ML17272A944
| ML17272A944 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/25/1980 |
| From: | Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| GO2-80-79, GO2-80-95, NUDOCS 8005050335 | |
| Download: ML17272A944 (65) | |
Text
p CV)~i REGULATORY INFORMATION DISTRIBUTION SYSTEM {RIDS)
ACCESSION'BR:8005050335'OC
~ DATE: 80/Oil/25 NOTARIZED! YES DOCKET FACIL:50 397 WPPSS Nuclear Projects Unit 2E Washington Public Powe 05000397 AUTH INANE AUTHOR AFFILIATION RENBERGER<D.L, Washington Public Power Supply System RECIP NAME RECIPIENT AFFILIATION DENTONiH,R.
Office of Nuclear Reactor Regulation
SUBJECT:
F'orwards info re sacrificial shield wall corrective action plan. Design change does not require prior Ofc Nuclear Reactor Regulation approval as it is not unreviewed safety question
& does not involve change in Tech Specs, DISTRIBUTION CODE:
B001S COPIES RECEIVED:LTR
/ENCL Q SIZEl
'TITLE: PSAR/FSAR AMDTS and Related Corr espondence NOTES:
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E 09 GEOSCIEN BR 11 MECH ENG BR 13 NATL ENG BR 16 ANALYSIS BR 18 AUX SYS BR 20 I 8
C SYS BR 22 AD SITE TECH 27 EFFL TRT SYS 29 KIRKWOOD AD PLANT SYS AD SITE ANLYSIS HYDRO METEOR BR OELD EXTERNAL: 03 LPDR 30 ACRS 1
1 3
3 1
1 2
2 1
1 1
1 1
1 0
1 1
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1 10 10 02 NRC PDR 08 OPERA LIC BR 10 QAB 12 STRUC ENG BR 15 REAC SYS BR 17 CORE PERF BR
- 19. CONTAIN SYS 21 POWER SYS BR 26 ACCDNT ANLYS 28 RAD ASMT BR AD FOR ENG AD REAC SAFETY DIRECTOR NRR MPA 04 NSIC 1
1 1
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Washington Public Power Supply System A JOINT OPERATING AGENCY P. 0. BOX 958 3000 GSO. WASHINCSON WAY RICHI.ANO, WASHINCSON 99352 PHONC (509) 375.5000 G02-80-95 April 25, 1980 Docket No. 50-397 U. S. Nuclear, Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.
C.
20556 Attention:
H.
R. Denton, Director
Subject:
WPPSS NUCLEAR PROJECT NO.
2 NRR APPROVAL OF WNP-2 SACRIFICIAL SHIELD WALL WEL'D PREPARATION
Reference:
WPPSS,to NRC Region V letter, G02-80-79, D. L. Renberger to R. H. Engelken, subject, "Sacrificial Shield Wall (SSW) Corrective Action Plan"
Dear Hr. Denton:
Based on discussions with NRC Region V, it is our understanding that the Headquarters of the Office of Inspection and Enforcement is requesting approval from NRR on the WPPSS corrective action plan for replacement of the slot welds by a circumferential, partial penetration weld for joining rings 3 and 4 of the Sacrificial Shield Wall (SSW) of our WPPSS Nuclear Plant No.
2 (WNP-2).
This approval is considered necessary by I8E Headquarters before allowing WPPSS to proceed with the joint prepa-ration for the partial penetration weld.
Region V has indicated that ISE Headquarters is transmitting to you the information noted in the reference in parallel with this letter.
It is the opinion of WPPSS that this design change is not one requiring prior NRR approval, as it is not an unreviewed safety question and does not involve a change in the technical specifications.'lso, in light of the'fact that the operating license review for WNP-2 is still ongoing,
~an design changes will be appropriately documented in the FSAR for NRR review.
In any case, it is apparent that I&E Headquarters will be requesting prior NRR review and concurrence.
Accordingly, we are submitting to you formally, on'the docket, thirty copies of the refer ence information in goo Ii'
l f'
yg 'I
HR Denton Page 2
2-80-95 pril 25, 1980 order to expedite your review.
The preparation of the joint and the subsequent related work is now or will shortly become critical path for the project construction schedule.
Arrangements have been made for the welding machines, electrodes and preheat equipment.
An 'expedited review and approval by NRR of the reference document is necessary to prevent further delay and impact on critical project work.
WPPSS is prepared to meet with NRR at any time or place to discuss or present any of the material in order to expedite the review process.
It should.be neiterated that your concurrence is being requested by I&E b f
i uu i
i b i g
11 d
p d.
A di g1, y review should be so oriented.
The fundamental design reports for the Sacrificial Shield were subject to previous NRR review and approval as post-construction permit items.
The background for this is documented in the response to NRC question 130.38 on the WNP-2 docket submitted formally to you in Amendment 8 to the FSAR in February.
Very truly yours, D. L.
RENBERGER Assistant Director Technology DLR:OKE:cph e
1 cc:
V. Stel 1 o - Director, NRC, Wash.D.C.
MD Lynch - NRC, Wash.D.C.
(telecopy)
B.
Wood -
NUS ND Lewis - EFSEC, Olympia, Wn.
JR Lewi.sJ.-'PA P
RE Snaith - B8R, New York JJ Verderber B&R, New York JM Blas - B&R, New York RC Root - B&R, Site WNP-2 Files
STATE 'OF WASHINGTON) wPPss NUcLEAR PROJ EcT NQ.
)
ss SACRI FI CIAL SHIELD WALL COUNTY OF BENTON WELD PREPARATION D. L. RENBERGER, Being first duly sworn, deposes and says:
That he is the Assistant Director, Technology, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that he is authorized to submit the fore-going on behalf of said applicant; that he has read the foregoing and knows the contents thereof; and believes the same to be true to the best of his knowledge.
DATED 4 ni'/ 0'/, 1980 D. L.
RENBERGER On this day personally appeared before me D. L.
RENBERGER to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes therein mentioned.
GIVEN under my hand and seal this ~gtgday of
, 1980 Notary Pu
)c in and for he State of Washington Residing at
A 4
P 'f
INTBI:IfII..DISTRIBUTION
~
~C Bibb KD 'Cpwan OK Ear 1 e Harrpld TELECOPY GT Harper RT Johnson Dpcket Np.
50-397 JD Martin DL Renberger NO Strand Hr.
R.
H. Engelken, Director 4GaiimmhM NRC Region V
WD Vaughn Suite 202, Walnut Creek Plaza ME Witherspoon1990 N. California Boulevard SSW File Walnut Creek, California 94596 DLR/1 b e'CT/lb
Subject:
WPPSS NUCLEAR PROJECT NO.
2 sf 2
~
DOCKET NUMBER 50-397 pf 1 SACRIFICIAL SHIELD WALL SSW THIS LETTER SATISFIE~MMITMENTNp.
THIS LETTER IDOES) IDES NOTI ESTABLISH A NEW COMMITMENT.
WPPSS CORRESPONDENCE NO.
G02-80-79 March 25, 1980
(
)
CORRECTIVE ACTION PLAN
Reference:
NRC Region V Letter, R.
H. Engelken '.
r d,
WNP-2 Pipe. Whip Restraints and Sac i 'a S
e d Wall,, dated. February 8, 1980
Dear Mr. Engelken:
The corrective action plan for the sa i
'shield wall (SSW) has been finalized; It consists of pro justification for the slot weld replacem i by the partial penetration weld, perform-ing a welding defec tural impact assessment to.evaluate the SSW as-built struct a
bilities, selection and,qualification of the shiel materia r
'm gaps and concrete voids, and a
final repor a late a
discussing all items of concern on a
case-b ase a is.
e i
we
'efect/structural assessment
.is being performed i
ns r tive, bounding manner with the followi.ng considerations:
e Welding defects identified by the recent Burns and Roe SSW visual inspection of 100~ of accessible
- welds, o
Welding defects identified by magnetic particle examinations performed on the SSW by site contractors, o
Welding defects identified by ultrasonic examinations.
performed on the SSW by.
site contractors and Leckenby, To The SSW welding defect and repair history experienced by Leckenby during fabrication,
$07 ~
gO R
AUTHOR:
SECTION FOR APPROVAL OF APPROVED DATE s3 Dsf gC)
FOR SIGNATURE OF:
3-'2/-IF'ib
'ME Withers oon
Nr.
R.
H. Engelke Page 2
o Assessment of Leckenby NDE credibility, welding procedures and welder qualifications/capabilities, o
Lamellar tearing, o
The use of cold forming and heat straightening processes during SSW fabrication, o
SSM as-built dimension considerations with respect to the partial penetration weld at El. 541'-5",
and o.
The impact of the known welding defects and defect history and their extrapolation to the remainder of the SSW in conjunction with other welding related concerns mentioned above on the SSW functional capabilities.
This technical evaluation will establish the SSM acceptability as-is with appropriate justification or will identify corrective action/
repair as necessary.
This evaluation will be performed in a typical engineering manner, i.e., independent checking of the technical results.
The replacement of the slot welds by the partial penetration weld at El. 541'-5" is considered to be an equal and alternate method of achieving the horizontal shear design requirements.
We do not view it. as a change in design requiring prior NRC approva]
in that it is not an unreviewed safety question or change in technical specifications., Burns and Roe Technical Memorandum No. 1173, provides justification for the use of the partial penetration weld between SSW rings 3 and 4 including SSM as-built dimension considerations.
Attach-ments 2,. 3, 4 and 5 provide details for the joint preparation and welding of the partial penetration weld.
The preparation of this joint will provide additional information about the material in this area of the SSM; it does not. preclude any investigative work.
Considering the above and the reference, it is requested that the
. Supply System at this time be allowed to commence preparation of the'oint for the weld joining SSM rings 3 and 4.
A subsequent letter to NRC Region V will specifically address the proposed shield material and request your concurrence to proceed with shim gap shielding repair and welding of rings 3 and 4.
Very truly yours,
.D. L. Renberger Assistant Director, Technology
Nr. R. H. Engelken Page 3
DLR:DCT:der Attachments:
(1) Burns and Roe Technical Memorandum No. 1173, dated t1arch 19, 1980 (2)
Project Engineering Directive (PEO)
No. 215-W-1604 (3)
PED Ho. 215-CS-2741 (4)
PEO No. 215-W-2742 (5)
PED No. 215-W-2749 cc w/att:
V. Stello, HRC N.D. Lewis,. EFSEC, Olympia J.R.
- Lewis, BPA J.J.
Verderber, B&R N.Y.
R.C. Root, B&R Site WNP-2 Files
e s PC'HLN3KRL.
MuF~ QPP.AK 2 UH~.
C'Ply TQ:
JJVerderber w/1 CJSatir w/1 ACygelman w/1 DCBaker w/1 JO'Donnell w/1 MFialkow w/1 EFerrari w/1 DAT'F3/19/8 0 I
R. E. Snaith FRgR M. N. Fi:alkow W. O.
2808 EJWagner w/1 Washing on Publi'c Power Supply System GHarper w/1 WPPSS Nuclear Project No.
2 HTuthill w/1 Sacrificial Shield Wall - Assessment Program SF-2 w/2 Connection of, Uppe and Lower'all Segments pf w/1 TECHNICS>
. NENOEANDUN NO.
1173 db w/0
--*TM File w/1 1.
NRC Letter from R. E. Engelken to N.
O'. Strand dated 2/8/80,
Subject:
Washington'uclear Project, No. 2, Pipe Whip Restraints and Sacrificial Shield Hall.
I FERENCZS:
2.
WPPSS Letter WPBR-80-96 from R. M. Foley to J.
J.. Verderber,. dated 3/6/80,
Subject:
WPPSS Nuclear Project No. 2, Sacrificial Shield Hall (SSW)
Assessment Program.
3.
Calculation No. 6.19.37',.
Book No.
SV 489 Pages 45 - 61
Title:
WPPSS-Sanford No.
2 - Reactor Bldg.
Sacrificial Shield Wall,
Subject:
Correction Measures at Interface El. 541'-5".
4.
- Washington Public Power Supply System Nuclear Project No.. 2 Report No. WPPSS-74-2-R2-B, "Sac ificial Shield Wall Design Supplemental Information".
5.
ANCE Manual No. 41, "Plastic Design in Steel" i
~ '2nd Edition, 1971, Chapter 10:
Multistory
- Frames, pp. 246-247:
P h, Effee ts.
INTRODUCTION:.
It has been determined that the horizontal rings in the Sacrificial Shield Hall (SSW), located above and below the inte face at Elevation 541'-5", are not, welded together as shown on the contract drawings.
Correction measures to transmit the design horizontal shear between the channel r'ng above the inter ace and the box ring below the inter-face are recruired.
~
~
T~~CENECAL 51" NORANDUN NO.
>17 >
The contrac recuires tha" at each of 24 locations around the
- SSW, ou slot welds axe to be provided in the web of the uppe channel ing connecting to the lower box ring.
Zn lieu of this un ulfilled reauirement, it is proposed to install a
partial penetration groove weld along the exterior, circumfe ence between the two rings.
'tructural analysis in justification of the, proposed correction has been accompl'shed (Re erence
- 3).
This memorandum furnishes pertinent information relative to this analysis in compliance with letters from USNRC and HPPSS (References 1,
- 2).
The following is included:
V
~ >
a.
Description of cor ection weld
, b.
Design conside ations-c.
Analysis based on the design SSH configuration d..
Analysis fo as-built SSW dimensions.
DESCRIPTION OF CORHECTZON WELD The correction weld is a partial penetration groove weld with fillet weld reinforcement to be installed along the exterior circumference between the rings above and, below the interface at Eleva ion 541'-5".
The location and extent of the weld're shown in Figure 1; weld details are shown in Figure 2.
As shown in the figures, the correction weld is o be installed in each of the 24 panels around the SSH for the width available between 'the-column splice plates.
Preparation for. the groove weld recpxires xemoval of matexial from the channel ing.
The speci ic configuration of the weld in each panel, including the groove depth and the size of the fillet weld reinforcement, depends on the width of ledge at the intexface.
From the design viewpoint, a minimum overall weld depth of 2 inches, corresponding to an effective weld throat o~ 1 7/8 inches, is maintained in all configu ations.
DESIGN CONSIDERATIONS FOR CORRECTION HELD l.
Basic Data The analysis and design of'he proposed correction weld utilizes the-values of the stress resultants in the members and skin plates obtained in the analysis of the overall sacrificial shield wall.
A description'f the analysis and design of the SSW including loads, load combinations, and acceptance criteria was submitted to NRC by Report No. HPPSS-74-2-R2-B (Reference 4) and approved by NRC 'by lette dated Octobe 15, 1975.
Pace 3
'-TECHNICAL MZiXORANDU NO.
1173 Date Typed:
3/19/80 The analysis and design of the co rection weld is in con-formance with NRC Standard Revi'ew Plan (SRP) 3.8.3.
Tn, particular, reauirements relat've to loads, load combinations, and acceptance criteria are complied with.
The basis of design is the elastic working st ess method, Part 1 of the 1969 AZSC design speci icatio...
2.
Sianificant Loads The following significant loads, conside ed in the analysis and design of the sacri icial shield wall, are applicable to the
'orrection measures:
~V Dead and live loads Seismic, loads:
'ressur'zation of the annulus between RPV--and SSW Reactions due to pipe break Annulus pressurizations include those due to postulated pipe breaks in the ollowing lines:
Recirculation outlet lines Recirculation inlet lines Peedwater lines RHR/LPCI lines Pipe break reactions include those due to the preceding breaks and due to other, severe postulated breaks occurr'ng in the drywell prope Ten controlling breaks in the drywell are included.
.3.
Controllin Loadin and Load Combination The significant loads are considered in the load combinations of SRP 3.8.3 with egard to horizontal loads at the interface.
The controlling-loading with associated acceptance criteria with regard to horizontal loading pe panel is noted below:
SRP Combination 5:
1.6S D + L + Pa
+ Yr + E D I L dead, live load Pa:
annulus pressure due to break in feedwater line at azimuth 90 Yr..pipe reaction due to the feedwater line break Er:
combined ef ect (by SRSS) due to OBE seism'c events in the easterly, northerly, and vertical directions.
r Cr.NZ.CSJ
'\\ ~
IiZ~iORANDUM NO.
1173 ANALYSIS BASED ON DESIGN SSW CONFZGURATION Desi Concent.
The correction weld carries the horizontal shear loads which are transmitted between the ring channel above the interface and the ring box member below the interface.
The horizontal loads from the channel are due to horizontal reactions from the skin plates and columns which connect to the channel from above.
Reactions from the analysis o
the SSW in its design configuration axe used..
The shear loads from the skin plates are tangential (circumferential) in direction.
Shear loads from the columns have tangential and radial components.
The connection design is based on the"largest comb'ined shear load in any one panel due to the associated'skin plates and columns.
The same correct'on is applied to all panels.
2.
Desi Loads The largest combination of shear loads per panel in the controlling load combination 5'.has magnitudes as listed below:
Skin plates:
Tangential shear
= 318.1 kips Column:
Tangential shear
=
8.9 kips Radial shear
=
27.4 kips The total panel tangential
- shear, 327.0 kips, is taken to act with half applied along each flange of the ring channel.
The total panel radial shear, 27.4 kips, is taken to act along the line of the column web.
3.
Weld Desi Criteria Welding procedures will be qualified in accordance with the requirements of the Structural Welding Code AWSD1.1.
Weld design is based on allowable stresses ass'ociated with partial penetration groove welds.
Correction Weld Stress Anal sis The panel design loads result in tangential and radial shear resisting forces in the panel correction weld.
The total panel tangential load causes a uniform tangential force in the 'weld of 9.9 kips per inch.
A radial weld force which varies linearly between extreme values at the ends of the weld resists the moment on the weld due
to the eccentricity of'the applied tangential load along the interior face; the maximum value of this adial force 's 21.6 kips per inch.
An 'additional radial weld force with constant magnitude equal to 2.7 kips per inch acts over a limited portion of the weld near its end to resist the applied radial load along the column web line.
The maximum value of the resultant weld force occurs at the end of the weld and is ecpxal to 26.3 kips per inch.
S.
Controllin Desi Mar in The design margin, which is he ratio of the permissible stress to the ac ual stress, ecruals 2.3 for. the above maximum value of the weld foice.
ANALYSIS POR AS-BUILT'SW DIMENSIONS
,1..
Conceat for Anal sis As-built deviations of the SSN'which affect the proposed correction weld at. interface Elevation 541'-5" are illustrated in Pigure 3.
As shown in the figure, the deviations from verticality of the columns above the interface and the deviations from the design circulari"y of the ring channel members above the interface are involved.
The lateral displacement of one end of a member,'5, relative to the other end in conjunction with the primary axial load'n the member, P, results in additional (secon-dary) shears and moments in the member (reference
- 5).
This Ph effect with the associated end bending moments and shears is shown below:
(F' Q
Prom equilibrium considerations,'t is determined that:
'ZEC~ ETCAL N~ORAK3UM YO.
1173
~
~
Conservatively, the additional end moment M~ and the additional end shea Q~
are each evaluated as though the other is non-existent.
This is done in the following eq'uations.
M~.5 P~
2.
Desi Loads The controlling axial loads in the columns and ring channels are due to the same applied loads. taken in SRP Com-bination 5 which control for the transmission of shear across the interface.
The axial force in the ing channel is taken eaual to the design panel. tangential shear of 327.0 kips.,
The axial'orce in the column is taken as the total panel vertical load due to both column and skin plate reactions..'onservatively, the maximum vertical loads in the column and skin plates are used even though these are not located in the same panel as the panel which controls for shear.
The design vertical axial load is 316.5 kips.
l 3.
-Effect on Annulus Pressurization Kith respect to the effect of as-built SSN dimensions on annulus p essurization calcula ions, the fol owing is noted:
a.
The measurements of concern apply to the annulus space between the sacrific'al shield wall and the reflective insulation.
These. measurements are very difficult to obtain and are not available.
- Howevez, it is noted that the insulat'on support system is mounted on the SSÃ so that the dimension between insulation and wall would tend to be unaffected by the as-built deviations.
b.
For the design of the wall, HRC recuired that calcula'ted annulus pressurization loads be increased by 40 percent.
One of the reasons for this requirement was to account for as-built conditions being.different from the conditions assumed. in the analysis.
4.
Ma n'tude of As-Built Deviations The as-built deviations used in the analysis are based on the most conservative inte pretatioq of the revised erection tolerances which we e adopted for the ezection of the SSW togethe with a supplementary
~eld check of the deviations.
TECHNICAL HZNORAHDUN HO ~
1173
~ ~
Prior. to erection of the wall, the contractor reauested and was granted relaxation o
the or:ginal contract recruirements on erection tolerances.
The maximum permissible devia ion from c'rcularity was changed to + 0.90 inches in lieu of the original
+ 0.125 inches.
The maximum horizontal deviat'on-at the top of the wall rom the vertical line through the corresponding point in the base of the wail was rev'sed to + 0.90 inches in lieu of the original + 0.25 inches.
The most conservative interpretation o
the adopted tolerances results in the deviation values noted"'below.
These values a e used in the analysis.
a ~
Circularity The maximum tolerance is taken to occur at one column relative to the adjacent colunns on e'ither side.
Referring to Figure 3,
~ Q.'to -(0.'Io) ~ f.80 inches,.
ct Gt+i ci ct 1
b.
Verticality The maximum to'lerance is taken to occu at a column between Elevation 541'-5" and Elevation 549'-54"..
Using the terminology of Figure 3, 5= O.Ro -(0 Ro)
=
[.80 inches.
~ Field measurements pertinent to the vertical and circular deviations have recently been made.
The magnitudes of bv as de ined in Figure 3 were determined around the shield wall.
However, precise determination of the circular deviation is not practical due to interference of existing construction.
As a measure of the circular deviation, the radial deviation between the ring box member below the interface and the ring channel above the interface is used.
" Comparison o
the deviations from field measurements with those based on the tole ances makes apparent the conservative basis of the analysis.
Thus the analysis uses h> = 1.8 inches compared to a maximum me'asured value of 0.625 inches'.
Also, the analysis uses 4q, -ba'i+< = 1.8 inches compared to a corresponding value of 0.875 inches based on field data-.
~
~
.,'TECHNICAL MEMORANDUM NO.
5.
Correction Weld Stress Anal sis As noted in the Concept for Analysis, the design ax-'al oacs acting with the adopted cesign devia ions result i.n additional end momen s and shears in the columns and ring channels located above the interface.
The additional end moments 'n the column and ring channel are 285.0 inch kips and 294.3 inch kips respectively.
The associated increases in flexural stress in the members are less than 0.7 k'ps per square inch.,
This increase
'i.n stress is ela ively small and is wi hin the capacity of the wall members.
The additional column radial shear i:s 5.9 kips.
The additional, radial shear in each of the two ring members at the column is 13.4 kips.
- Thus,
- a. total. of 32.7 kips of additional radial shear results due to the design deviations.
Conservativelv, this additional radial, shear is taken to occur in the controlling panel used for the design of the correction weld.
The total panel radial shea is increased to 60.1 kips and the resulting local radial weld force increases to 6.0 kips.per inch from the previous
'alue of 2.7 kips per inch in the Analysis Based on Design SSW Configuration.
6'.
Desicm Marcrin With the above increase in panel radial shear, the design margin is 2.1 as compared to the previous value of 2.3.
CONCLUSION Based on the preceeding
- analysis, the proposed correction weld at interface Elevation 541'-5". has sufficient capacity to sustain the recuired loads.
The correction provides a design margin in excess of 2.1.
Pre@ared by:
Q,N
+la ow Approved. by:
P. O'Donnell
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CO~BI PROJECT ENGINEERING DIRECTIVE
.BURNS AND ROE, INC.
WPPSS NUCLEAR PROJECT, NO. 2 PROJECT ENGINEERING D I R E CTIVE 1
DATE 16 E
5 24 7I9 17 18 19 20 21 P R IOR ITY I
1604 6
7 8
9 10 1 1 12 13 14 15 nEASGN FOn P. E. D.:
Slot welds required per detail D 2038 (S782}
made to top of shims and do not connect ring 3 (Beam type 3) and ring 4 (Beam type 2} as required.
INFORMATION COPIES SHEET I OF~
REFERENCES SUBJECT Sac.
Shiel a
v e as LOCATION El ~ 541'-5" All A ENG. SYSTEM N A S/U SYST EMi QUALITYCl ASS ORIGliNATING-DOCUMENTS
'NCR 215-5688 DESCRIPTION OF WORK:
4 Replace slot welds with a partial penetration weld between the upper and lower rings as'shown on attached details with PCAW process being used for complete joint welding except for buttering that is required with SMAW'7018 All welding is to be performed per direction of Burns and Roe Welding Engineers,,
Addenda System and this PED which includes a work procedure with buttering, peening, grinding, visual inspection, MT inspection and a sequence.
IOZ 1.
THIS PED REVISES DIRECTION PREVIOUSLY PROVIDED BY THE FOLLOWING PEDIEI:
2.
THIS PED VOIDS DIRECTION PREVIOUSLY PROVIDED BY THE FOLLOWING PEDIs)'.
THIS PED WORK SHOULD BE OTHER WORK UNDER THE FOLLOWING PEO'S:
REVISE:
NONE DRAWINGS SPECIF ICATION APP ROVALS:
S I LI 'INEER DATE Pz)- Q I EAD DISCIPLINE ENGINEER DATE 4.
THIS PED DEPENDS ON THE PRIOR INSTALLATIONOF THE FOLLOWING PEDS:
S/U LIAISON ENGINEER DATE RESIDENT PROJECT ENGINEER DATE FIcV 1
BR 803-2
. g~qg7o370
/
REPAIR PROCEDURE FOR NCR !r'05688 AT THE 54 1 5
LEVEL IN REACTOR'ONTAlh~iKNT'VESSEL PURPOSE The purpose of this procedure is to establish the requirements for the structural steel repair welding inside the containment.
Any deviation from the requirements of this procedure will require specific approval of the Burns and. Roe Welding Engineer.
Deviation approvals vill be granted only after examination of the problem areas'and a-resolution given by Burns and Roe Welding Engineer by Addendum system.
Welding sequences shall be issued as attachments to this procedure.
Any changes or additions to weld sequences or other special instructions shall. re'quire approval by the Burns and Roe Welding Engineer.
The Quality Control Manager shall be responsible for assuring compliance with these proceduies.
2)
DOCUMENTATION Work packages shall be used for all str'uctural steel work and shall be prepared in accordance with this procedure.
The Structural Steel Weld Record form.shall. be used for structural steel welding documentation.
Meld repairs, if required, shall be documented on the Structural Steel.
'eld Repair forms.
The loss of Preheat/Interruption of'eld Sequence form shall be used to document such occurences.
If cracks are discovered, an Inspection Report will.also be initiated.
Upon completion of the form, a copy will also be immediately given to Burns and Roe Welding Engineer on duty for approval.
Preheat recorder charts shall be identified by weld, iso., or dwg. no.,
and transmitted, upon completion of work, to the Q.A., vault.
3)
MATERIAL REF, DOQ DivG Electrode Control shall be-in accordance with the work procedure.
Electrodes shall be purchased in hermetically sealed. containers and shall be dried for 0
0 at least one(l) hour at temperatures between 750 F.
and 800 F. prior to issuance.
Electrodes shall be maintained at a minimum temperature of 250 F.
after the high temperature bake until withdrawn'or use or temporary storage in porta'ole ovens or a storage oven conveniently placed near the work area.
Electrodes. shall be removed from portable ovens one at a time and used immediately. 'lectrodes that have been or are wet shall be bent and giscarded in an a
roved container. (Note:
FCAW wire does not require pre-baking).
--5( qj VfPPSS NUCLEAR PROJEC7 NO. 2 BURNS AND ROE ls",C.
4 )
WELDER QUALIFICATIONS Ill welders using this procedure shall be qualified to unlimited thickness and all positions in accordance with approved weld pro-cedures and AMS Dl.l.
Welders qualified by groove welds on 8" sched.
120 "pipe or larger and on plates 1" or over are quali ied for all "thicknesses of s:ruc-trual steel 5)
PROCEDURE PREHEAT PROCEDURE AND REgUIREN"NTS The following material shall be on hand prior to preheat and weldint operations:
a)
Heating torches b)
F~ating coils or blankets c)
Heat retaining. blankets
- 6) 'ORCH HEATING d)
Clips for holding coils, blankets, etc., in place.
e). Temperature control and
. e-cording equipment.
1)
Torches may be used for applications involving arc-air gouging,
'attaching strongbacks, heater blanket clips> tacking, backing bars, and minor repairs.
Preheat shall be 200 P.+
25 P.
tt9.th a
15
'inute soak time.
2)
Heating torches may be used to locally preheat the struciure and weld site in the areas to be tack welded.
- 3) 'eating torches shall be used with a neutral flame.
O',
When preheai is obtained ihrough torch heating.for other than temporary
.ack welds, g.C. shall frequently monitor the site boih prior io and 'during welding to assure that minimum preheat and maximum intel pass tempt<<nature'equirements are main.ained.
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be:
150oF. to 200oF. for at 1o'ast 2" in each direction from the weld site, with a 15 minute soak zime at temperature prior to beginning work.
9)
Welders and/or operators shall be provided temperature indicating
. crayons or contact pyrometers to assure that pr'cheat require~ants are being. met.
MAXIMUM INTERPASS PREHEAT
'EMPERATURE Welds to Sacrificial Shield Wall and within 24-" of" the
. Sacrificial Shield Wall.
200 - 25 F
250 F.
The minimum preheat and maximum interpass temperature for all welding shall be as noted above;
?0)
FIT-UP'ND TACKING The-joint gap for structural and partial penetration welds. shall not exceed 3/16" for material thicknesses less than 3". The joint gap shall not exceed 5/16"for material thicknesses 3" and above.
Such-joints shall incorporate adequate backing against, which to weld.
The root opening for single bevel grooves against backing bars shall be as follows.
1/4" min. to 9/16" max. backing bar removed. after weld ng.
. 3/8" min. to 9/16" max. backihg bar left on.
Tack welds shall be subject to the same quality requirements as the Final wells except that discontinuities such as undercut and unfilled craters need not be removed before the final arc weld.
Preheat is mandatory for single pass tack welds which are remelted and incorporated into continuous arc welds (final welds).
Tack welds must be large enough to prevent shifting or cracking during subsequent welding.
They must be clean, contain no cracks, lack of fusion,:or slag and should be designed to become part of the final weld.
r Tack welds which are incorporated into the final welds shall be made with electrodes meeting the requirements of the final welds and shall horouahlv.
NPPSS NUCLEAR PROJECT NO. 2 BURNS AND ROE O'C.
r"EO i
4) 5 So~LE Rfv1&vfQ
J we ding snail.
perfo=ed using approved we18%g proce"ure accorcing to AWS D1.1 and Speci" cation Sect'on 2808-215-17D.
A stringer bead technique sha'1 be usec to "he greates:
extent poss ole.
En an.; case, tne viatn o=
bead sna' no-exceed "hree (3) co"e d'a e"ers o
- "he e ect"ode (except
=o" c -'h e:c
= '::. cc"ec v re which shall not exceed, 3/8" in width.
- ne minim" s'
of a "oot "ass sna 'e su icient to preven" c"ack ng ana the m~imum tnickness o= layers suoseouent to root pass shall be 1/8" fo welas made in tne flat position and 3/16" for welas made in any othe" position.
Each wela pass o
aeposited veld metal shall oe thoroughly cleaned using slagging picks,
='re brus'nes, or by grinding..
Any cracks, blow holes, or other defec"s that appear on the surface of weld beaas shall be-emovec by chipping or grinding before the next cover'ng weld bead is deppsited.
All we'd beads, except -hose in the root and final layers, shall be peened immediately afte" removal o: slag.
- However, any visible defects such as porosity, cracks, or slag pockets must be removed by grinding prior to peening.
Peening sha'1 be done using an air hammer with a round nose tool
. of a minimum diameter of one quarter inch (<").
Peening shall be done in a straight and continuous line.
Care shall be exercised to prevent scaling or flaking of weld base metal from over-peening.
Peening shall be usec 'n all cases, except where specifically prohibited by a note on the weld sequence sheet.
Ai-operatea "needle" slagging guns shall not be used for peening'urposes.
Peen p r shetch attached.
No downhill welding wil'e pe~tted.
Beat inpu-range shall not exceed the following:
35k)/in. heat input shell be maximum for welding.
Buttering may be done horizontally, verticallv (up); or any combination of he two.
Requirements fo" buttering, if any', are sho<<w on weld seauence sheet.
Buttering does not require peening.
All groove welds and all:fillet welds against the Sac. Wall require that the Sac. h'all be buttered, anc the, Z.D. oi all weld joints shall be butte"ed prior to welding.
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1)
After root passes have been applied all remaining passes shall be peened.
- 2)
M.P.T.'inal weld at preheat temp.
and 72 hrs. after complete cool down.
- Except cover pass.
~ A'BED/ww&rz WPFSS NUCLEAR PROJECT NQ. 2 BURNS AND ROE. lNC.
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7 YPJCAl C8 Sc A8r 5'c/D d rAll hOT:"S: "A) 4'-IX" cascade area's shall 'be made, irst, to assure that there is no movement; to the wal!., a'so to establish-the stability for the remaini g
welding.
B) All remaning welding may be completed in a different sequence i= so d'esignated by B 6 R Welding. Engineer.
- 1) Four (4) ~elders to weld simultaneously throughout sequence.
- 2) First sequence to start at AZ; 7 -30'.
3)
Second sequence to start at AZ 191 -30'.
- 4) Th'rd sequence to start at, AZ. 103 -30'-
5)
Ho welder shall proceed,. ahead of any other welder in a sequence.
- 6) Each sequence number consists of approx~tely 11".
V(PPSS NUCLEAR PROJECT HQ. 2 BURHS AND ROE, INC.
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VE'PPSS NUCLEAR PRO.tECT NQ. ".
c'IYiG IION:
PAGE:
PARA:
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BURNS AND ROE, 1HC.
SHT. Q 0
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COD PROJECT ENGINEERING D(R ECTIVE BURNS AND ROE, INC.
~
WPPSS NUCLEAR PROJECT N0,2 REASON FOR P. E. D.:
P ROJECT.
ENGINEERING DIRECTIVE 1
2 3
4 DATE gg INFORMATION~/g COPIES
-CS-7
/
PRIORITY SHEET 1 OF.~
SaOT k~Ios HzcpuipEc RZ DEr<<~ 0-ZO38 (~b'av) M~OE To 7oa op Sui~s A'uo Do+oT Cowu'icy CPiuq 3 (8zwm r)~O~
A~o Ri~g 4'(SE~~ ryPzO~) A'
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REFERENCES SUBJECT AC. SH!E'LD NIALL ELDS LOCATION EZ.54/-'5 LZ A)PdC/hlO ENG. SYSTEM W/A S/U SYSTEM QUALITYCLASS 2
ORIGINATING DOCUMENTS MC'Ci'/5-5Q8g DESCRIPTION OF WORK:
REPXPcE SL'oT WEios tviriiA PA'RyiAK PEuErp/~riow km'.o Bzg WEEnl jul &Pres A~a EoN/EQ Ci~jwcig As DEyAiiED o~ ShEEys 3 7hc7U 5 ow 7uis /E.D k~~D PB+a~p/orion Se~~z BE As Dt~acyEn Gu PE.D 2/9-W-2742.
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Semi 8EAS DiaZCrZP Oa) FD 2/5M-2746.
WzzO Sufi/ BE/I////ATE As Oie~craa &PE.D PI5'-bv'-/@04.
1.
THIS PED REVISES DIRECTION PREVIOUSLY PROVIDED BY THE FOLLOWING PEDIE):
2.
THIS PED VOIDS DIRECTION PREVIOUSLY PROVIDED BY THE FOLLOWINGPEDBI:
3.
THIS PED WORK SHOULD BE COORDINATED WITH KNOWN 2/+
OTHER WORK 2/S-W 87 UNDER THE FOLLOWINGPED'S:
REVISE:
NONE DRAWINGS SF EC I FI C AT I 0 N APPROV LS:.m~> ~)
EN/
ER EAD DISCIPLINE ENGINEER
'l~I 3
5i~I'ATE 4.
THIS PED DEPENDS ON THE PRIOR INSTALLATIONOF THE FOLLOWING PEDS:
REV 1
BR 803-2 S/U LIAISON ENGINEER DATE g 7437/
RESIDENT PROJECT ENGINEER DATE
~
PROJECT ENGINEERING DIRECTIVE COOE 2
I PROJECT ENGINEERING OIRECi IVE
-C WNP2 BURNS'(ROE, INC.
PAGE 2OFN REFERENCE DRAWINGS SUF F IX ORAWING NO.
SHEET NO.
'1 2
REV.
3 4
5 6
7 8
9 1011 12 1314 15 REFERENCE DRAWINGS ORAWINGNO..
SHEET NO, SUFFIX REV.
22 23 24 25 26 27 28 32 33 34 35 36 37 26 27 28 29 30 31 35 38 37 38 39 SFCTION:
REFERENCE SPEC. PARAGRAPHS PAGE PARAGRAPH REV.
REV 1 BR 803-1 1
2 3
4 5
6 8
9 10 ll 12 13 14 15 16 18 20 21 23 24 25 27
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NO. 2 PROJECT EN GIf'ER ING ulh ECTIVE PROJ-i 7 EiVGINEERING DIR CTIV~
2 Il 5
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',15 I 11 19 t19
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REASON FOR P. =. D.:
I this PKD is for the preparation of the partial penetration weld joint to be used on the sac.
wall at 541'-5" el.
IhrO(iI!Ai ivli COPIES I
SHE=71 Or REF" RENCES SUBJECT Sac.
Shield Wall Welds ENG. SYSTEM N/A LOCATION 541 '5" All A I
QUALITYC'SS ORIG INATlf"G DOCUMENTS Q
DESCRIPTION OF WORK:
Refer to pages 2 through 6 of this PED for direction of weld joint preparation as shown on attached details.
V)
I-O 1.
THIS PED REVISES DIRECTION PREVIOUSLY PROVIDED BY THE FOI.LOWING PED(s):
2.
THIS PED VOIDS DIRECTION PREVIOUSI.Y PROVIDED BY
'THE FOLLOWING PEDI!)'.
THIS PED WORK SHOULD BE COORDINATED WITH KNOWN~I~~
OTHER WORK 40 REVISE:
NONE DRAWINGS SPECIFICATION AFP ROVALS:
D' iI"-'GINEER LEAD DISCIPLItviE "NGINEFR 4.
THIS PED DEPENDS UN THE PR IOR INSTALLATIONOF T)aE FOLLOW!tvG I'ED'S:
S/U LIAISON ENGI \\
R DATE RiESIDENT PROJECT ENGINEER DATE R=-V
> BR803-2
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NPPSS NUCLEAR PROJECT NO. 2 8URNS AND ROE. INC.
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