ML20217K505
| ML20217K505 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/05/1997 |
| From: | Kofron K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BYRON-97-5180, NUDOCS 9708150276 | |
| Download: ML20217K505 (29) | |
Text
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o,mmonwc:nn namn onnsun, H)run km r:tmg vt:non 4 i n%0 North Grrnen Limrt h l(oad
' H) n m, II. 61Olo 979 4 TelH142444441 August 5,1997 -
!!!'R: IlYRON 97 5180 Fil.lb 3.11.0321 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Ilyron Station First Ten Year Interval insen-ice Inspection Program Relief Requests NR 22, NR-23 and NR 24 Ilyron Nuclear Power Station, Units 1 and 2 NilC_DadrLNtunbmL5Dd54 and 455 The purpose of this letter is to document llyron Station's plan to revise the First Interval inservice Inspection Program Plan for Units 1 and 2 with three requests for code relief as specifiul in 10CFR50.55a(3)(ii) and 10CFR50.55a(g)(5)(iii).
Commonwealth Edison Company (Comed) is providing the attached information regarding the surface ex:unination of penetration attachment welds, inaccessible welds under branch pipe saddle plates and pressurizer seismic restraint lugs for Ilyron Station, Units 1 and 2. i 10CFR50.55a(g)(5)(iii) stipulaes that when the licensee determines that examinations I rey sired by the code or addenda are impractical,information shall be supplied to the Commission to support the determinations. Therefore, pursuant to 10CFR50.55a(g)(5)(iii),
this information is being provided in the form of relief requests NR 22 and NR 24. Relief .
a request NR 22 proposes to revise the inservice inspection requirements for surface examination of the inaccessible welds inside of pipe penetration sleeves. Relief request NR- l(( (]i [
24 proposes to revise the inservice inspection requirements for surface examination of the it. accessible welds under the reinforcement saddle plate of pipe branch connections.
10CFR50.55a(3)(ii) stipulates that when the licensee determines that examinations required by the code or addenda would result in hardship or unusual difficulty, information shall be suppli?d to the Commission to support the detenninations. Therefore, pursuant to 10CFR50.55a(3)(ii), this information is being provided in the form of relief request NR-23.
Relief request NR-23 p oposes to revise the inservice inspection requirements for surface examination of the inaccessible portions of the pressurizer seismic restraint lugs.
9708 5 " 150276 .m-e ,
970005** @ . lEHRISI!!
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Corniki respectfully requests that the Nuclear llegulatory Co'ntnission (USN1(C) review and approve the attached telief requests based on the geometric limitations and supporting justi6 cations provided.
Please address any cornments or questions regarding this request to Marcia ir$niak, Nuclear 1.icensing Administrator, at 008) 66M181.
Sincerely, s kw is.'l K ofro 9 Station Ma anger Ilyron Station Attachinctifs ec: G. Dick, flyron Project Manager NI(It A.11. licach,llegional Administrator ltill S. Ilurgess, Senior flesident inspector Ilyron Of6ce of Nuclear Safety IDNS
t Nesision 0 Page I of 6 i HYNON UNIT I ANil2 INSERVICE INSPECTION REI,lEF REOlfEST NR 22 P
COMPONr.NT lill:N11FICAllON i
Code Clanet 2
Reference:
IWC 25001 Esamination Category: CC IIem Numbers C3.20 llencription: Alternative Rules for the Inservice inspection ofinaccessible Welds on Welded Penetration Integral Attachments Component Number (s): See Table I for component listing.
COllll RI:OUlHl:MI:NT Subsection IWC, Table IWC 25001, lixamination Category C.C. Item C3.20 requires surface examination of the Integrally Welded Attachments to Piping (irigure IWC 2500 5).
It Asis FOR RI:141EE Pursuant to 10 CI R 50.55a(a)(3)(ii), reliefis equested on the basis that compliance with the Code ,
requirement would result in hardship or unusual dif0culty without a compensating increase in the level of quality and safety.
Some penetrations at flyron were origina'ly designed where one of the integral attachment welds is inside the
< penetration assembly, thus making the welds inaccc5sible for inservice inspection (see Figure 1). Access from outside of the closed end of the penetration assembly fbr examiners is prohibited by the integral attachment. Access from the open end of the penetration is severely restrained due to the penetration geometry. See Figures I,2, and 3 for penetration details. The integral attachment weld is set back some distance inside the penetration assembly and the clearance between the pipe and penetration sleeve is small.
See Table i for these dimensions.
To satisfy the Code requirement to perform a surface examination of this weld, modification to the penetration assembly and/or piping to allow access would be required. Ilyron would incur significant engineering and installation costs to perform such a modification without a compensating increase in the level of quality and safety to,iustify such modifications.
The limited access to these welds, as described in this relief request, was later acknowledged in the 1995 lidition of the ASMll Code. Paragraph IWC 1223 exempts from examination welds or portions of welds that are located inside a penetration.
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l Ne56660m o Page 2 of 6 i liYMON UNIT I ANil2 1 INSERVICE INSPECTION l
. RELIEF MEOUEST NH.22 i
1 PROPOhl:D Al/II:NNATI: PROVISIONS !
When a weld is scheduled for inspection, a surface examination of the accessible weld on the exposed outside l surface of the penetration will be performed, in conjunction with the surface examination, the periodic VT 2 :
examinations sa accordance with the requirements of ASMll Section XI. Table IWC 25001, !!nmination l Category Coll will provide tensonable assurance of continued structural integrity of the piping systems. l l ,
- M'l'LlCAltli TIMI
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'ihin relief request will be required for the I'irst Ten Year inspection interval.
M'PHOYAl, hTATUS i
l'ending NRC review, l
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, Netl*lon 0 Page 3 of 6 HYNON UNIT I AND 2 INSERVICE INSPECTION l l
EELIEF REOUEST NH 12 . ;
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TA8111 yN Pf N llllDt NilflCAfl0N 16 0 PIPE ATTACH CONCRETE PEN. PEN. $ ELECTED TYPE WIAltt.R LINE WELD DRAWING THICK THICK THtCK $LTE CLEAR. FOR EAAM (T,) (T,) (Tc) (Pe) 2 iPC-066 1S104B 12" C15 1SI12 1.125" 2" 3'.6" 24"O 4.9" l 2 1PC-068 1RH01BA 12" C03 1RH-04 0 375" 2" 3' 6" 24"O 4 9" X +
2 iPC-075 1RH01BB 12" C03 1RH-08 0 375" 2" 3' 6" 24"O 4.9' 2 2PC-066 2Sl04812" CO2- 2SI12 1.125" 2" 3' 6" 24"O 4.9" X ,
e 2 2PC 068 2RH01BA 12" C03 2RH 12 0.375" 2" 3' 6" 24"O 4.9" X
- 2 2PC-075 2RH01BB 12" C03 2RH 11 0.375" 2" 3' 6" 24"O 4.9" 3 1 AB 111 1RH03AA 8" C33 1RH 03 0.322" 1" 3' 0" 18"O- 4.3" X 3 1AB 115 1RH03AB 8" C52 1RH-07 0.322" 1" 3' 0" 18"O 4.3" -
3 iPC 050 1Sl05BA-8" C01A 1S104 0.906" 2" 3' 6" 24*0 7.0" 3 1PC-051 iS105BB-8" C01A 1SI26 0.906" 2" 3' 6" 24"O 70" 3 1PC 099 1FW87CD-6"- C04 1FW 12 0.432" 2" 4' 6" 16"O 3.8" 3 1PC 100 1FW87CA-6" C04 1FW 11 0 432" 2" 4' 6" 16"O 3.8" X 3 1PC 101 1FW87CB-6" C04 1FW-06 0.432" 2" 4' . 6" 16"O 3.8" 3 iPC 102 1FW87CC-6" C04 1FW 10 0.432" 2" 4' 6" 16"O 38" 3 2AB 128 2RH03AA 8" C49 2RH 10 ' 0 322" 1 %" 3' 0" 18"O 4.3" X 3 2AB 133 2RH03AB 8" C51 2RH 07 0 322" 1 %" 3' 0" 18"O 4.3" 3 2PC 050 2Sl05BA-8" CO2 2SI-04 0.906" 2" 3' 6" 24"O 7.0" X 3 2PC-051 2S105BB-8" C02 2SI26 0.906" 2" 3' 6" 24"O 7.0" 3 2PC 099 2FW87CD-6" C04 2FW 12 0.432" 2" 4' 6" 16"O 38" 3 2PC 100 2FW87CA-6" C04 2FW 11 0.43?" 2" 4'.6" 16"O 3.8" X 3 2PC 101 2FW87CB-6" C04 2FW-06 0 432" 2" 4' 6" 16"O 3.8" 3 2PC 102 2FW87CC-6" C04 2FW-10 0.432" 2" 4' - 6" 16"O 3.8" 27 1AB-064 1RH02AA 8" C20 1RH 05 0.322" 1" 3' 0" 28"O 5.0" X 27 1AB-074 1RH02AB 8" C25 1RH-09 0.322" 1" 3' 0" 26"O 5.0" l 27 2AB-036 2RH02AA-8" C47 2RH 05 0.322" 1" 3' 0" 29"O 5.0" X 27 2AB-068 2RH02AB 8" C53 2RH 09 0.322" 1" 3' 0" 26"O 5.0" Note: See Figures I,2 and 3 for drawings of the penetration configurations.
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e linition 0 l' age 4 of 6 IlYRON UNIT I AND 2 INSEltVICE INSPECTION lt1 LIEF IEOtIEST NR 22 Figure I Containtnent Penetrations (Drawing not to scale) 7u;< - , r, ,
See Detail A <<
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V Pressure Retalning Pipe N Inaccessible Weld 1 Pc Type 2 J & ,
Penetration .
3 ' ~ Anchor (typical) -
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3 I ll Pc U Pressure Retaining Pipe
- Accessible Weld N , ,
Type 3 Penetration -
P" '
(typical) :
be y,f Note: See Table 1 for dimensions as applied to each penetration.
HeSitil'n0 l' age 5 of 6 ggy g g y p sgr : A N D 2 INSI',RVICI: 1NSI'ECTION l i
luiLUiEJUiOUEST NR 22 I?igure 2: Auxiliary llullding Walll'enetretions (llrawing not to scale)
See Detail B -
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.:) llPc y Pressure Retaining Pipe
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Anchor Plate Detail N Penetration _
(typical) .,
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I l* Tc -l O-Pressure Retaining Pipe Detail 4 ,
Penetration -
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Note: See Table 1 Ibr dimensions as applied to each penetration.
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l Hrsision 0 Page 6 of 6 l
llYRON UNIT I AND 2 INSElWICE INSPECI'lON RiiLIEF ltEOUEST N1122 4
- Figure 3: Attachment Weld 1)ctails (Drawing not to scale)
Penetration ,
Attachment
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45'
? 45'
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Tw ir Detail A Process Pipe Walt Detail B Note: See Table 1 for dimensions as applied ta cach penetration.
4
Revision 0 Page 1 of 5 HYRON UNIT I ANI)2 INSERVICE INSPECTION REl.10F REOUEST NR 2,2 COMIT)NI:NT IDI:NTIFICATION Cmle Class: 1
Reference:
IWD 2500-1 Esamination Category: 1111 Item Number: 118.20 Iheription: Alternate Rules for the Inservice Inspection of the Pressurizer Seismic Lug Welds.
Cominment Numbers: IRY.01.S, PSt 01, PSL-02 PSt-03, PSI-04 2RY.01.S, PSt 01,l'St 02, PSL 03.PSt 04
[ORKUOUlHr.Mf.NT Subsection IWil, Table IWil 25001, Examination Category 1111, item 118.20 requires surface examination of integrally Welded Attachments to the Pressuriier, Figure IWII 250015.
HAM FOR BLljff Pursuant to 10 CFR 50.5Sn(a)(3)(ii), reliefis requested on the basis that compliance with the Code
! requirement wouM result in hardship or unusual dif0culty without a compensating increase in the level of quality and safety.
H3:en Units I and 2 Pressuriier seismic lugs are welded to the Pressurlier shell. There are four seismic lugs per unit, located 90' apart (See Figure 1). In order to perform examinations on the seismic lug welds, the outside surface of the lower vessel shell to lug area must be accessible. The entire exam surface is not accessible since it is cos cred by the seismic lug restraint and lower Pressurizer shell insulation, in addition, the con 0guration of the Pressuriier cof0n limits access to the seismic lugs. The impact of remos ing the seismic lug restraint, altering the Pressuriier coffin and removing the lower shell insulation is presented below. See Attachment 2 for photographs of the Pressuriier Lugs and the surrounding area.
'Ihe seismic lug restraint (Figure 1), which surrounds the lug prohibits access needed to perform a meaningful surface exam. There ase four restraints located at about the 428' elevation, one for each lug, which were not designed for removal. The top of the concrete Door at this location is at 428'4" elevation. This Door, which is 2'.6" thick, interferes with access to three of the four lugs (See Figure 2). In addition, the Pressuriier cofHn itself severely limits access to remaining seismic restraint (Figme 1). All of the restraints, which are embedded in the concrete, would require major modification to tb: existing Pressurizer cof0n to allow for removal and access. This modi 0 cation would require the redes'gn of the seismic restraint and Pressurizer cof0n to allow for periodic removal and access to the seismic restraints, implementation of this redesign would require significant engineering resources, construction researces and sign,0 cant dose to plant personnel. See Attachment 1, Insulation on the lower shell of the Pressuriier prohibits access needed to perform a meaningful visual examination of the seismic lug ueld areas. The removal of the insulation covering the lower Pressuriier shell to seismic lug area will result in high radiation exposure to plant personnel. Access from below would
- 1. ;
l Revision 0 Page 2 of 5 HYRON UNIT 1 AND 2 INSERVICE INSPECTION HEl lEF REOUEST NR 23 H A%19 FOR lEl,1f.E (cont'd) ;
require scaffolding from the 40l' elevation grating to the 428' elevation of the seismic restraint. To remove the Pressurlier shell insulation, access would be required from both sides. As stated above, access to the top of three of the seismic lugs restraints is limited by the Pressurizer coffin con 0guration (Figure 1) and the concrete floor will limit access from the bottom of all four lugs (Figure 2). The current configuration of the scismic restraint also only allows limited access fbr visual examination. To provide suitable access for all ,
four seismic lug restraints would require major modi 0 cations and significant resources. ,
Even if the insulation is removed, full visual examination of the scismic lugs cannot be achieved. The Pressuriier cof0n, concrete floor and scismic restraint geometry would greatly limit access to all sides. lhe resulting coverage would only be a small percentage of the weld volume. The limited data obtained from these examinations do not provide a compensatory increase in quality and safety tojustify the hazards of personnel radiation exposure to obtain the data.
These restraints are designed to resist rotational and translational movements by providing lateral support during a seismic event (llyron/llraidwood UFSAR, Section 3.9.3.4.1.2). During normal operations, the scismic lugs are under no load and the opportunity for flaw initiation and propagation is non existent.
During the Unit I tilR07 outage, an attempt was made to perform a surface examination of the seismic lugs.
The extent of the coverage obtained is shown in Figure 3, The coverage achieved was limited by the restraint, ikior, and the amount ofinsulation that was removed. Full removal of the insulation would only be possible with the construction of a 20' scaffold 360* around the pressuriier. The ring ofinsulation at the level of the top surface of the 428' elevation concrete platform and below is overlapped by and riveted to the ring below.
These two rings would have to be removed before limited access to the lower surface of the lugs can be achieved. This access would be limited by the narrow distance between the pressuriier and the attachment plate and the bottom of the lug and the bottom of Hoor at 428' elevation (see Figure 2. View 1111).
a PROPONrD AI,TFRNATI' PROVISIONS For the First inspection interval, a surface examination was performed on those areas of the lug welds necessible from the 428' elevation slab (approximately 21%%). This exam along with the periodic VT 2 examinations in accordance with the requirements of ASME Section XI, Table IWil 25001, Examination Category ll P, and applicable reactor coolant systems monitoring requirements specified in the Technical Speci0 cations will provide reasonable assurance of continued structural integrity of the Pressuriier shell and seismic lugs.
APPL.lCABt1 TIMF PERIOD
'this relief request will be required for the Orst ten year inspection Interval.
APPROVAL, STATM ,
Pending NRC review J
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Revinnon 0 l' age 3 of 5 in' HON UNIT I AND 2 INSERYlCE INSPECTION llEl.1EF REOUEST NR 23 Figure 1: Plan at Clevation 42N'.71/2" (1)rawing not to scale)
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UNIT 1 AS SHOWN UNIT 2 REVERSED
Reslilon 0 l' age 4 of 5 HYRON UNIT I AND 2 -
INSERVICE INSI'ECTION i
HEI,lEF REOUFET NR 23 !
F6gure 2: l'ressuriecr Seismic Restraint Details (Drawing not to scale)
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Revision 0 l' age 5 of 5 HYRON UNIT I AND 2 INSERVICE INSI'ECTION
}{libiEF REOUEST NR 21 Figure 3: Surface Examination Coverage Obtained (Drawing not to scale) ll 'i i i il ll l!
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PSL-04
!- - I J6 h 6" :l WSM Examination Coverage Obtained ,
Total Required per Lug: 28" Perimeter (112" total for 4 lugs)
PSL-01: 6" (21.42%)
PSL-02: 12" (42.85%)
PSL-03: 6" (21.42%)
PSL-04: 0" - (0.00%)
TOTAL: 24" (21.42%)
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Revision 0 Attachment i IlYRON UNIT I AND 2 INSERVICE INSPECTION IELIEEXiiDilEST NR 23 ESTIMATED MAN HOURS AND DOSE PERSONNEL MAN HOURS Carpenters 100 Labors 120 Insulators 280 Inspectore 10 TOTAL 570 PERSONNEL DOSE TOTAL DOSE RATE Dose Rate _ _ -
Carpenters 5 mRH 800 15 mRH Labors 3 mRH 360 Insulators 3 mRH 840 Inspectors 3 mRH 30 tow 2030 Insulation Panels Estimates provided by the support organizations. Dose Rate 3 mRH Dose rates established by RP survey #96 3105 on 9/11/96 "'"9 " /
[ 428' EL Ring o upper $
Ring o Lower Dose Rate 3 mRH Dose Rate .. _ . . _ -
5 mRH 7+. , -,
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o' Revision 0 Attachment 2 IlYRON UNIT I AND 2 INSERVICE INSPECTION llELIEF REOUEST NB-U LOCATION AND DIRECTION OF PHOTOGRAPHS PRESSURIZER COFFIN _
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4 gp Revision 0 Page 1 of 5 -
HYRON UNIT I AND 2 INSERVICE INSPECTION
.REl.1EF REOUEST NR-24 COMPONENT IDENTIFICATION Code Class: 2
Reference:
- IWC-2500 Examination Category: C-F item Numbers: C5.31 and C5.32
Description:
A' ternate Examination of Branch Pipe Connections with Reinforcement Saddles Component Numbers: See Table 1 for Unit I and Table 2 for Unit 2 CODE REOUIREMENT Subsection IWC, Table IWC-2500-1, Examination Category C-F, items C5.31 and C5.32 require surface examination of the pressure retaining pipe branch connection welds as shown in Figure IWC-250013.
HASIS FOR REl.lEF Pursuant to 10 CFR 50.55a(g)(5)(iii), reliefis requested on the basis that the conformance with the code requirements is impractical.
The design of certain branch pipe connection welds calls for the use of reinforcement saddles. These saddles are fillet welded over the pressure retaining branch pipe to main pipe connection and the initial portion of the intersecting branch longitudinal weld. When in place, the saddle plate completely encases these welds as illustrated in Figure 1. This design precludes any type of surface examination from being performed on the two concealed welds and adjacent base material surfaces.
Assurance of the continued integrity of thesejoints is afforded by the fact that the reinforcement saddle strengthens thejoint and reduces the stresses on the obstructed circumferential branch-to-pipe weld and branch longitudinal piping welds.
Additional assurance of the continued integrity of thesejoints is provided by the surface examinations perfonned under the liigh Energy Augmented Inspection Program. These examinations are performed on all branch connection saddle plate welds in the Main Steam System that are included in the break exclusion areas, Based on the above, Byron Station requests relief from the ASME Section XI requirements for the surface examination of Class 2 branch pipe connection welds that are designed with a reinforcemeat saddle.
l 1
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Revision 0 l' age 2 of 5 HYRON UNIT I ANI)2 INSERVICE INSPECTION REl.1EF REOUEST NR 23 l'ROPosEI) Al/IERNATE PROVislONS When the pressure retaining welds are made inaccessible due to the use of a reinforcement saddle,Ilyron Station will perform an alternative surface examination of:
a) the saddle-to-branch pipe weld and adjoining base material (identified as Alt-A on Main Steam piping and Alt il on Safety injection piping), and b) the saddle to-main pipe and adjoining base material * (identified as Alt il on Main Steam piping and All A on Safety injection piping). and c) the required 2%T area of the branch longitudinal weld and adjoining base material will begin at the -
intersection of the longitudinal and saddle-to-branch welds and extend for 2%T of the branch pipe nominal thickness.
Additionally, a VT 2 visual examination of the area will be performed in conjunction with the required Class 2 System Pressure Tests.
- Note: The saddle-to-main pipe wcld is part of the surface examination requirement ofIWC 25001, l'igure 13 'ihe two welds (saddle-to-branch pipe and saddle-to-main pipe) were scheduled separately and given different sumxes.
AITLICAIEE.TlME l'alOD This relief request will be required for the first ten > car inspection interval.
AlTROVAI, STATilS Pending NRC review I
F
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it' Revision 0 Page 3 of 5 l IlYRON UNIT 1 AND 2 2 INSERVICE INSPECTION REI,lEF REOUEST NR-24 TAllLE 1: Unit 1 Saddle Reinforced Hranch Connection Welds ITEM LINE WELD NUMBER DRAWING EXAMINATION NUMBER NUMBER PRIMARY ALTERNATES NUMBER AsME AUGMENT COMMENTS C5 31 1MS07BA 28" C03 C03A/B 1 MS-04 X Both Welds Examined C5.31 1MS07BA 28" C04 CJ4A/B 1MS-04 X Both Welds Examined C5.31 ' MS07BA-28"
. C05 COSA/B iMS-04 X Both Welds Examined C5.31 1MS07BA-28" C09 C09A/B 1MS-04 X Both Welds Examined C5 31 1MS07BA 28" C10 C10A/B iMS-04 X Both Welds Examined C5.31 1MS078B-28" C03 C03A/B 1MS-06 X Both Welds Examined C5.31 1MS07B8-28" C04 C04A/B iMS-06 X Both Welds Examined C5.31 1MS0788-28" C05 COSA/B 1MS-06 X Both Welds Examined C5 31 1MS07BB-28" C06 C06A/B 1MS-06 X Both Welds Examined C5.31 1MS0780-28" C10 C10A/B 1MS-06 X Both Welds Examined C5.31 1MS07BC-28" C03 C03A/B 1MS-08 X Both Welds Examined C5.31 1MS07BC-28" C04 C04A/B 1MS-08 X Both Welds Examined C5.31 1MS07BC-28" C05 COSA/B 1MS-08 X Both Welds Examined C5.31 1M307BC 28" C06 C06A/B 1MS-08 X Both Welds Examined C5 31 1MS07BC-28" C07 C07A/B iMS-08 X Both Welds Examined C5.31 1MS07BD-28" C03 C03A/B 1MS-02 X Both Welds Examined C5 31 1MS07BD-28" C04 C04A/B 1MS-02 X Both Welds Examined C5.31 1MS07BD-28" C05 C05A/B_ _1MS-02_
X Both Welds Examined C5.31 1MS07BD 28" C09 C09A/B 1MS-02 X Both Welds Examined C5 31 1MS07BD-28" C10 C10A/B 1MS-02 X Both Welds Examined C5.31 1Sl06BA-24" C18 C18A/B 1S1-24 X Both Welds Examined C5 31 1 SIO6BB-24" C24 C24A/B 1SI-24 X Both Welds Examined
' C5.32 1 RH01CA-16" C01L -
1RH-04 X Adjacent to 1S106BA-24*,
C18B C5.32 1RH01CB 16" C01L -
1RH-08 X Adjacent to 1Sl06BB-24',
C24B Note. An alternate area for the C5.32 welds is not designated. The code required examination is the 2%T length from the intersecting primary circumferential weld. The alternate examination area is the 2%T length from the intersecting circumferential saddle plate to branch pipe weld.
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Revision 0 l' age 4 of 5 IlYRON UNIT I AND 2 INSERVICE INSI'ECTION REl.lEF REOUEST NR 23 TAllt.E 2: Unit 2 Saddle Reinforced liranch Connection Welds ITEM LINE WELD NUMBER DRAWING EXAMINATION NUMBER NUM8ER PRIMARY ALTERNATES NUMBER AsME AUGMENT COMMENTS C531 2MS07AA-28" C12 C12A/B 2MS 04 X Both Welds Examined C5 31 2MS07AA 28" C13 C13A/B 2MS-04 X Both Welds Examined
~X~
~ ~
~C51i~ 2MS075^!28 # ~C N- ~C13hB~ ~2 )AS! 64' BotfiW5IdiiExamined C5.31 2MS07AA-28" C15 C15NB 2MS-04 X Both Welds Examined C5 31 2MS07AA-28" C16 C16A/B 2MS-04 X Both Welds Examined C5.31 2MS07AB-28" C15 C15A/B 2MS-06 ~
X Both Welds Examined
' CST 31~ 2 sis 0'7XBT 28# CIG- ~ ~i6hB~ C '2 M S M T B6itiWeiiiiExamirid C531 2MS07AB-28" C17 C17A/B 2MS-06 X Both Wolds Examined C5.31 2MS07AB 28" C18 C18A/B 2MS-06 X Both Welds Examined C5 31 2MS07AB-28" C19 C19A/B 2MS-06 X Both Welds Examined C5 31 2MS07AC 28" C15 C15A/B 2MS-08 X Both Welds Examined C5 31 2MS07AC-28" C16 C16A/B 2MS-08 X Both Welds Examined C5 31 2MS07AC-28"~
C17 C17A/B 2MS-08 ~~- -~
X Both Welds Examined
~ ~
"CE3T 2MSOf C 28"' -C18~ ~ Ci8kB~ ~2MS08~~ X Bot'h Welds EiainIried C5 31 2MS07AC 28" C19 C19A/B 2MS-08 X Both Welds Examined
_C5_ 31_ 2MS07AD-28"
_C12_ _C12A/B_ __ _2MS-02_ __ _ ,
X Both Welds Examined
._C 5;31_ 2MS07AD;28"_ _C13_
C13A/B 2MS-02 X Both Welds Examined C5.31 2MS07AD-28" C14 _C14A/B_ _ _ __2MS-02 X Both Welds Examined __
C5.31 2MS07AD-28" C15 C15A/B 2MS-02 X Both Welds Examined C5 31 2MS07AD-28" C16 C16A/B ~ 2MS-02 i X BoitiiMeiaiExamined~
C5 31 2Sl06BA-24" C26 C26A/B 2SI24 X i C268 Examined C5.31 2S10688 24" C26 C26A/B 2SI-24 X j C26A Examined C5.32 2RH01CA 16" C01L - 2RH-04 X Adjacent to 2S106BA-24',
C26B C5.32 2RH01CB-16" C01L - 2RH 08 X Adjacent to 2Sl06BB-24",
C26B Note: An altemate area for the C5 32 welds is not designated. The code required examination is the 2%T length from the intersecting primary circumferential weld. The alternate examination area is the 2%T length from the intersecting circumferential saddle plate to branch pipe weld.
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- l. af Revision 0 - Page 5 of 5 IlYRON UNIT 1 AND 2 INSERVICE INSPECTION REl.lEF REOUEST NR-24 Figure I: Typical Saddle Reinforced 13 ranch Connection Weld Detail (Drawing Not to Scale)
NOTE Alternate exam areas are identified differently for the MS TELLTALE and Si systems. Refer to the HOLE applicable isometric drawings.
ALTERNATE F
EXAM AREA i(
SADDLE PLATE
- '\
,/, BRANCH
/' PIPING fj II . ._
ALTERNATE EXAM AREA 2V2T INACCESSIBLE g AREAS +i e
\\ n PRIMARY BRANCH
\CIRCUMFERENTIAL LONGITUDINAL PRESSURE RETAINING WELDS PIPING