ML101130187
| ML101130187 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/19/2010 |
| From: | Price J Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 10-189, FOIA/PA-2011-0115 | |
| Download: ML101130187 (175) | |
Text
{{#Wiki_filter:Dominion Nuclear Connecticut, Inc. 5000 Dominion Boulevard, Glen Allen, Virginia 23060 Dominion Web Address: www.dom.com April 19, 2010 U.S. Nuclear Regulatory Commission Serial No. 10-189 Attention: Document Control Desk NSS&L/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3 ASME SECTION XI INSERVICE INSPECTION PROGRAM RELIEF REQUESTS FOR LIMITED COVERAGE EXAMINATIONS PERFORMED IN THE SECOND 10-YEAR INSPECTION INTERVAL Millstone Power Station Unit 3's (MPS3) second 10-year interval for the inservice inspection program concluded on April 22, 2009. During this interval, the components identified in Attachments 1 through 10 received less than the required examination coverage. Accordingly, pursuant to 10 CFR 50.55a(g)(5)(iii), Dominion Nuclear Connecticut, Inc. (DNC) requests relief on the basis that the required examination coverage is impractical due to physical obstructions and limitations imposed by design, geometry and materials of construction of the subject components. Attachments 1 through 10 contain the relief requests and the basis for these requests. These relief requests have been reviewed and approved by the station's Facility Safety Review Committee. If you have any questions or require additional information, please contact Wanda Craft at (804) 273-4687. Sincerely, c.AlPrice ice resident - Nuclear Engineering AW-7 K("f
Serial No. 10-189 MPS3 Limited Exam Relief Requests Page 2 of 2 Attachments:
- 1. Relief Request IR-2 Examination Category B-A, Pressure Retaining Welds in Reactor Vessel.
- 2. Relief Request IR-2 Examination Category B-B, Pressure Retaining Welds In Vessels Other Than Reactor Vessels.
- 3. Relief Request IR-2 Examination Category B-D, Full Penetration Welds of Nozzles in Vessels - Inspection Program B.
- 4. Relief Request IR-2-54, Examination Category B-H, Integral Attachments for Vessels.
- 5. Relief Request IR-2-55, Examination Category C-A, Pressure Retaining Welds in Pressure Vessels..
- 6. Relief Request IR-2-56, Examination Category C-C, Integral Attachments of Vessels, Piping, Pumps, and Valves.
- 7. Relief Request IR-2-57, Examination Category C-F-I, Pressure Retaining Welds in Austenitic Stainless Steel High Alloy Piping.
- 8. Relief Request IR-2-58, Examination Category F-A, Supports.
- 9. Relief Request IR-2-59, Examination Category R-A, Risk Informed Piping Examinations.
- 10. Relief Request IR-2-60, Examination Category B-P, All Pressure Retaining Components.
Commitments made in this letter:
- 1. None cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Ms. C. J. Sanders NRC Project Manager, Mail Stop 8B3 U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 1 RELIEF REQUEST IR-2-51 EXAMINATION CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 1 of 30 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality
- 1. ASME Code Components Effected ASME Code Class: Code Class 1 Examination Category: B-A, Pressure Retaining Welds in Reactor Vessel Item Numbers: B1.11, Shell Welds - Circumferential B1.12, Shell Welds - Longitudinal B13.21, Head Welds - Circumferential B13.22, Head Welds - Meridional Component Identification: Listed in Table 1
- 2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No addenda
3. Applicable Code Requirement
ASME Section Xl, 1989 Edition, Examination Category B-A requires volumetric examination of 100 percent of the weld volume as defined in ASME Section Xl Table IWB-2500-1 and shown in Figures IWB-2500-1, IWB-2500-2 and IWB-2500-3. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147 Rev. 15, allows credit for essentially 100 percent coverage of the weld provided greater than 90 percent of the required volume has been examined.
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100 percent volumetric examination coverage requirement for the subject Welds. Due to the design of the reactor vessel, geometric configuration and permanent obstructions limit the volumetric examination coverage of the subject welds.
During the second 10-year reactor pressure vessel examination, the best available technology was utilized in performing the automated ultrasonic examination. The examinations were performed with equipment, procedures and personnel qualified in accordance with the requirements of ASME Section Xl,
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 2 of 30 Appendix VIII, 1995 Edition thru 1996 Addenda as modified by the Performance Demonstration Initiative (PDI) program. A total of 58 permanent incore instrument nozzles penetrate the bottom head and six core support lugs permanently attached to the vessel interior limit the access to the lower head welds. The close proximity of the inlet nozzle and outlet nozzle boss limits the ultrasonic scanning of the upper shell longitudinal seam welds. These noted obstructions prevent achieving the essentially 100 percent volume examination coverage required by code. The limitations and the actual examination coverage attained for each weld for which relief is requested are noted in the Table 1. Isometric drawings, coverage calculations and limitation sketches are provided in this attachment. TABLE 1- Examination Category B-A Welds with Limited Volumetric Coverage Weld Code Item Configuration Comments Ultrasonic Identification Number Examination Coverage Attained (%) 101-122A B1.12 Upper Shell longitudinal Limited examination due to the 74 Seam at 90 Azimuth inlet nozzles proximity to the (Az.) weld. One recordable subsurface indication was identified and evaluated as acceptable per IWB 3510-1. 101-122B B13.12 Upper Shell longitudinal Limited examination due to 87 Seam at 210 Az. obstruction caused by outlet nozzle boss. No recordable Indications were detected. 101-122C B1.12 Upper Shell longitudinal Limited examination due to 87 Seam at 330 Az. obstruction caused by outlet nozzle boss. No recordable Indications detected.
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 3 of 30 TABLE 1- Examination Category B-A Welds with Limited Volumetric Coverage Weld Code Item Configuration Comments Ultrasonic Identification Number Examination Coverage Attained (%) 101-141 B1.11 Lower Shell To Bottom Limited examination due to 54 Head Torus obstruction caused by permanent core support lugs. One recordable subsurface indication identified and evaluated as acceptable per IWB 3510A1. 101-154A B1.22 Torus Peel Segment at 0 Limited examination due to 70 Az. obstruction caused by permanent core support lugs and incore instrument nozzles. No recordable indications were detected. 101-154B B1.22 Torus Peel Segment at Limited examination due to .84 90 Az. obstruction caused by permanent incore instrumentation nozzles. No recordable indications were detected. 101-154C B1.22 Torus Peel Segment at Limited examination due to 84 180 Az. obstruction caused by permanent core support lugs. No recordable indications were detected. 102-151 B1.21 Torus To Dollar Plate Limited examination due to 38 Weld obstruction caused by permanent incore instrument nozzles. No recordable indications were
.detected.
- 5. Burden Caused by Compliance To increase examination coverage on the subject welds requires a significant design modification or replacement of components with a different design to eliminate the noted obstructions. This is impractical due to the cost, additional radiation exposure and impact to plant equipment.
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 4 of 30
- 6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination on the accessible portions of the subject welds to the maximum extent practical given the limitations caused by the geometric configuration and permanent obstructions. Additionally, a visual examination (VT-2) is performed at the end of each refueling outage during the system leakage tests as required by Section Xl, IWB-2500-1, Category B-P.
Based upon the examination volumes that were obtained with acceptable results along with the visual (VT-2) examination performed each refueling outage, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.
- 7. Period for Which Relief is Requested The relief is requested for the second 10-year inspection interval for Millstone Power Station Unit 3, which began on April 23, 1999 and ended April 22', 2009.
LLOC 0 6z co (I) 0-(D a) mE C/5~
0 1- 1
- I I
- I
... I 6 I ' 5 I I IT
. . 3 .. 2 I i f
0 5) - tan....,. asa.,... a) a) a) 0f)) an.*-t- a OEAW VESSEL FILM VEW PLAN 0 taunamir A&m naew-a m aalz& ana anlnng
. m - m ?aa~~n 0d.l aa~,..aa n-aMlalanin A.
* -,"'P. "a 2111..
acnal anN~L Ac-llol!Hll n.
,Na REFSTOCE 05455
-a a.a .,,aa N aa .--' .
w aara~~ja ~ tma a l Aflaan a IA a a.,fl.l~l- f anal
,A l a-d l-ll- InI o "
- Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 7 of 30 AR EVA Dominion-Coverage Layout & Calculations Weld
Description:
Upper Shell Long. Seam @ 90° ASME Code Item No.: B1I.12 Millstone Weld ID: 101-122A ASME Code Figure No.: IWB-2500-2 TWS Weld Designator: W06 AREVA Drawing No.: 8017264 AGGREGATE COVERAGE: 74% Zone.Coverage Obtained lnn 16%T v'79%:-1'tt5T~ft% Examination Volume Definition Weld Length: 97.98 in. Area Measurement ~ Volume Calculation Inner 15%T *19.76 sq. in. Inner 15%T 1936.1 cu. in. Outer 85%/T 119.16 sq. in. iOuter 850/T 11675.3 cu. in. Limitations Limits scan by:; Compensation(s) Inlet Nozzles Nozzle proximity to Weld None Ecami.66 n C.verag Calcu~labnslTr-ated as D4n Siedh'iq )oW
- Exam. -- Area~ Length~ Volijme Voldnie --
EnAngle Beam Examined Exbminod Eanh Examined n Per-e LiniNGSed ita in
# d, (dg. . Dirootioh (sq. in.) fin-) (cu. in.) (cu. i, ~mnd Lmtd iiain I 70L145L-A Up ,:-1,9.76 97.98 >1936.1, 1936.1 100.0% "No 2 ý7OL/45L Down -19.76 97.98- 1936.1 1936.1 100.0% No 3 70 5L WA 19.76 46.93 -927.3 -1936.1 479ek Inlet NozzlJes, 4 100145L -.- COW §19.7&t -46.93 C927.3r 1936.1> 47.9% Yes Inlet Nozzibsý 0/T OUTR 8I - - - TotaIsS v 5726.8 C 7744.3 7319% .
OUE85TtasT650 50.2 79
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 8 of 30 A A REVA
*Domnuinio-I I I~I~I
- Scan Perpendicular to Weld wol 161-122A B1,21 IWB-2500-3 RV Scan Coverage (Scan Limitations shown)
Note: Coverage for W06 near weld te-ins completed during Upper Circumferential Weld. (W01) and Lower Circumferential Weld (W02) scans. (
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 9 of 30 AR EVA Dominic.- Coveraae Layout & Calculations Weld
Description:
Upper Shell Long. Seams @ 210' and 330', ASME Code Item No.: B1I.12 ASME Code Figure No.: IWB-2500-2 Millstone Weld ID (TWS Weld Designator); 101-122B (W07) & 101-122C (W08) AREVA Drawing No.: 8017264 Note: W07 is shown in example. It is representative of 1,01-122C,(W08)@ .33 0 ' AGGREGATE COVERAGE: 87% Zone Co~verage Obtained Inner I.-T:,tt/77 9 . %t0 . ue 6T:741 Examination Volume Definition Weld Length: 56.12 in.
/Area Measurement jFolume Calculation Inner 15%T 791.14 sq. in. Inner 15%T . 4441.3 cu.-in.
Outer 85%T 493 .51 sq. in. 1Outer 85%T 27695.8 cu. in. Limitations Limits 'scan by: Compensation(s) Outlet Nozzles Nozzle proximity to Weld Up Direction, below weld - Scan as single side Down Direction, above weld - Scan as single side
-.- xam. Area, Length Vclum6ý Volume-,
"Agle Beam Exariiined rExamnihed Examined Required .Perce~ntt - ,
Entry#it Adeb)' Dilrection K spSWi,) ;:6(in' (cu In.) '(cuin.):. Eiamin6d, ULinitbcl - Linlitaution
-1&12- '70U/45L' Up,&DUown '74.077 5612 416 443 '936' Yes: , Outlet Nozz~ 8m 31 70IJ45L........7:5 -,56:12_ 4 3958.7 4441.3 '89.1% s ult6z e oss' 4-- 7"% U4w CW 70.154 56ý.112 39587ý 4441.3 ' 89.1%' - Yes Outlet No~zzl Boss
- , ,, Totals: 1207r4.2 13324.0' 90A OUTERt.,8%T-> ' . 2-
.Exam.< Area, Length- Volume., Volume. ....... .
Angle Beam ýExaminied Lx~riiihd E-ýarjnled Required Percent Entry # '-,(deg.) Dieto s~n) .iL c.i.'(uin.) ExamiInedI Liiledf, Li-vmitations IA82ý ' 45Ll45S' 'Up &.Down 471'.95 '56.2 1 26485. 27695.8 95.6%/-- Yes OultNozzle Boss>' L- 3ý "5 4, /45: oW' 36 ..39 5
'56.1 2 i6&z14 . 27695.8 78.3/a Yes Outlet NonzleBoss~
4C 514K :cw 36.-39 56.'1'2 21'684.2 -2769586 78.3W4 Yes outlet Nzle Boss
-- , Totals-: 60454.2' 83087,3 841%
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 10 of 30 A AR EVA D~ominion-
-180 II I Ij I I~I I ~
Scan Perpendicular to Weld W/07 10112B IWIB-2500-3 RV Scan Coverage (Scan Limitations shown) Note: Coverage for W07 near weld tie-ins completed during Upper Circumferential Weld (W01) and Lower Circumferential Weld (W02) scans. Lower Circumferential Weld also completes parallel scan due ,to shortened length of weld.
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 11 of 30 AREVA W eDomin-Coverage Layout & Calculations Weld
Description:
Lower Shell to Bottom Head Torus ASME Code Item No.: B1.11 Millstone Weld ID: 101-141 ASME Code Figure No.: IWB-2500-1 TWS Weld Designator: W04 AREVA Drawing No.: 8017264 AGGREGATE COVERAGE: 54% Zone Coverage Obtained Inner 15%T: 53.3% Outer85%T: 55.6% Examination Volume Definition Weld Length: 544.50 in. Area Measurement Volume Calculation Inner 15%T 6.13 sq. in. Inner 15%T 3337.8 cu. In. Outer 85%T 39.78 sq, in. lOuter 85%T 21660.2 cu. In. Limitations Limits scan by: Compensation(s) Lugs (6) Reduction inaxial &circ scan dstance Scan area twice by rotating contact head Examination Coverage Calculations (Treated as DualSided Examination) INNER 15%T (Between lugs) / Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. in.) (Lc. in.) Examined Limited Limitations t 701J45L Up 6.13 272-29 1669.1 3337.8 50.0% Yes, Lugs 2 70LU45L Down 6.13 272.29 1669.1 3337.8 50.0% Yes Lugs 3 70LU45L CW 6.13 308.60 1891.7 3337.8 56.7% Yes Lugs 4 70LJ45L CCW 6.13 308.60 1891.7 3337.6 56.7% Yes ,Lugs Totals: 7121.7 13351.2 53.3% OUTER 85%T (Between lugs) Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq.in.) (in.) (cu. in.) (cu. in.) Examined Limited Limitations I 451145S Up 39.78 290.44 11553.7 21660.2 53.3% Yes Lugs 2 45L/45S Down 39.78 290.44 11553.7 21660.2 53.3%. Yes Lugs 3 451J45S . CW 39.78 308.60 12276.1 21660.2 56.7% Yes Lugs 4 45L/45S CCW 39.78 308.60 12276.1 21660.2 56.7% Yes Lugs Totals: 47659,6 86641.0 56.0% Examination Coverage Calculations (Treated as Dual Sided Examination) INNER 15%T (Limitation scan under lugs) Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. in.) (in.) (cu. In.) (cu. in.) Examined Limited Limitations 1 70LU45L Up 0.00 272.29 0.0 3337.8 0.0% Yes Lugs 2 70LU45L Down 0.00 272.29 0.0 3337.8 0.0% Yes Lugs 3 70LU45L CW 0.00 235.98 0.0 3337.8 0.0% Yes Lugs 4 70UJ45L CCW 0.00 235.98 0.0 3337.8 0.0% Yes Lugs Totals: 0.0 13351.2 0.0% OUTER 85%T (Limitation scan under lugs) Exam. Area Length Volume . Volume Angle Beam Examined Examined Examined Required Percent Entry # (deg.) Direction (sq. In.) (in.) (cu. in.) (cu. in.) Examined Limited Limitations 1 45LJ45S Up 1.91 272.29 520.1 21660.2 2.4% Yes Lugs 2 451J45S Down 0.00 272.29 0.0 21660.2 0.0% Yes Lugs 3 45J45S CW 0.00 235.98 0.0 21660.2 0.0% Yes Lugs 4 451145S CCW 0.00 235.98 0.0 21660.2 0.0% Yes Lugs Totals: 520.1 86641.0 0.6%
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 12 of 30 A AR EVA PlDominion-RV Scan Coverage (Circumferential Scan - Parallel to weld) Note: No coverage possible for circumferentialscans underlugs (6 total) RV Scan Coverage (Axial Scan - Perpendicular to weld) Note: Under lug axial scans are 3001h circumferentiallength centered on lug (6 total)
"WeldIdentidicat6ion TWS146.:'W04-:
-Mililstone No..- 101 -141,
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 13 of 30 AR EVA Dominion-Coverage Layout & Calculations Weld
Description:
Torus Peal Segment @ 0 ASME Code Item No.: B13.22 Millstone Weld ID: 101-154A ASME Code Figure No.: IWB-2500-3 TWS Weld Designator: W15 AREVA Drawing No.: 8017264 AGGREGATE COVERAGE: 70% Zone Coverage Obtained Examination Volume Definition Weld Length: 44.71 in. Area Measurement IVolume Calculation Inner 15%T 5.46 sq. in. inner 15%T 244.1 cu. in. Outer 85%T 30.91 sq. in. IOuter 85%T 1382.0 cu. in. Limitations Limits scan by: Compensation(s) Incores &Lugs Reduction in scan length None
,Exam ination, Co6verge Cajc~laiofons (Tretr a ul ka Ea-naln INNER 15%TJ '- ,7 1- Exam. Ar-- LengtnhVolumne 'Volume ~
En 4191Ahe Beam E-xzmned ExYamnined Examined Required; Percen~t Entry (dfg;) lrect D i'o'n .sqiin) (in.) c(icu.n.)
- cu. in.) xiimined LimiIed Lim ,itaions I -70LJ45L Up 5ý46 - 37.84, 206.6 ~'24-4.1 84.61ý Yes- tncore &,Lug.,
2 7L0J45L Dawn- 5.... 37.84i, -20ý6j 24-4 1 84- Ys*6v... cor* &'Lug 3 70ij45L: CW 5.4~6 'T 27.8,3 152.0' 244.1 i62-2%1 Yes, Incorel & Lu g
- 4. 7101L/4 I5L, iCOW 5.46 -27.83 152.0 24-4.1 .62.2% Yes lncoero&Lug Toas 717.1 976.5 73.4%
OUTER85/ 0 T ~'7 Exam. Area. Lenfgth 7Volume Volume - Aýngle Beam Examined ExkaminedA Exami~ned Required 'Percent - Entr # (deg) Direction (sq in.) ir.) (cu. In.ý oGu. in.) Examined Limited LiMitatikhs i 45L/45S -Up 30.91 37.84 ~,116,9.6. 13812.0 :84.6% Yes Incore&.Lug 2 46LI45S Dawn 30.91'- 37.84'i m1169.6 -t1332.0' -84.6k Yes e &icLug' 3 45L/45S O*W 30.91 - 21.B3--- 13i2.0
;674.8, 48.8% Yes Incore &,Lug, 4 -4515458 COWN 30.91- 21.8 13 8174.8 1382.0 '48,8%1 Yes Ihcore & Lug Toal. 3688.8 56527.9' 66.7%
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 14 of 30 A AR EVA WDoominion-LimitedPlot 85%T Coverage (Axial Scan - Parallel to weld) due to Lug and Incore 1ýId ldentifcatfon TWS-Jio.: W15~A W'Mjlilstone.No ý10 54-A
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 15 of 30 AREVA -fDominion-15%T Coverage Plot (Axial Scan - Parallel to weld) Limited due to Lug and Incore iWeld .Identification.. jrs Wo.:W1 MiIlston~e No. 1O1-1564A
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 16 of 30 AA AR EVA ! Dominion-Weld Identification TWS No.:,W15 f~1U~stne o.:101-11541A l . . . . . . ... . . . . . . . . . . . .. I 15% & 85% T Coverage Plot (Circumferential Scan - Perpendicular to weld) Limited due to Lug and Incore 15% & 85% T Total Cross Sectional Area
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 17 of 30 AR .V A R.E VA Coverage Layout & Calculations Weld
Description:
Torus Peal Segment.@ 900 ASME Code Item No.: B1i.22 Millstone Weld ID: 101-154B ASME Code Figure No.: IWB-2500-3 TWS Weld Designator: W16 AREVA Drawing No.: 8017264 AGGREGATE COVERAGE: 84% Zone Coveirage Obtained Examination Volume Definition Weld Length: 44.71 In. Area Measurement Volume Calculation Inner 15%/T 5.46 sql in. Inner 15.%T 244.1 cu. lfl. Outer 85%T .30.91 sq. in. 1Outer 85%/T . .1382.0 cu. in. Limitations Limits scan by:. Compensation(s)
!ncore Reduction in Scan length None, INNER15%T -
Exam Area Length Volumre -Volume . --- Angle Beamn Examined Exaihined &ExamIned Require Percent En~y#de.) D'~to- ý:in) in. (cu. in:) (cu.in.) Examined Umited Lmitnafion5' 1Vt TOLI4SL 'Up 5.46 43.33 236.6 U244.1-* 9689% Yes K' ' Incore 2 70L1-45L Down ,5ý48 4045 220:9~ 244,1> 905k Yes~7 inoore 3 70L145L OW 5,48 3500O 191.1 9 244.1> 78.3% Yes imoore 4 70L145L CCOW 5-48 35.00 191.1. -I24-41C 78.3%, Yes lnooAre Totals: 839.6 976.5 86.0k OUITER 0/aT ./ Ex ci- Area: Length Volumb Volume Angle Beam Examined Examined Examined Itepuired ,Percent
-Entry#t (degý) Dzrefitoni ->(sq.-in,) (in:)- (cuý m-.) (cu.nh.) Examined Limited'- Limurltitons~
1 .- 45L/45S &Up2 30.91 43.~33 12l39.3 1'T382,0, 9639k% Yes.) s . Icore>A Is 45IJ45§ tDownF 30.91 40,45-* 1203tIý2O Ocr q % e 3 451-)456,- CW-V t30.1 -,32.00, 989.1 13520' >7 1X6% Yes - -. more-4 4U45 I CO.W r 30.91 32.00 ~9 8, 9 1 1832.0 71ý6% Yes K Ilicore,( Totals: 4567.9 -5527.;9 82l6%
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 18 of 30 A AREVA Dpominiow-U 85%T Coverage Plot (Axial Scan - Parallel to weld) Limited due to Incore Weld IddentIfiatidn TWS4O.:'W16 : Mfillstone No.: 10O1'-15 4B
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 19 of 30 A AREVA SpDominion-15%T Coverage Plot (Axial Scan - Parallel to weld) Limited due.to Incore W.IdWe tfiation., 1SNo.,,-W 6~ Mw'16itoe-4No.: 1,61:154B.
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 20 of 30 A AREVA W-Dominion-15% & 85% T Coverage Plot (Circumferential Scan - Perpendicular to weld) Limited due to Incore Wed IdeitifiCat(ion-Mlillstone No.54&101-154B3
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 21 of 30 AREVA PDominion-Coverage Layout & Calculations Weld
Description:
Torus Peal Segment.@ 1800 ASME Code Item No.: B1.22 Millstone Weld ID: 101-154C ASME Code Figure No.: IWB-2500-3 TWS Weld Designator: W1 7 AREVA Drawing No.: 8017264 AGGREGATE COVERAGE: 84%
'Zone Coverage Obtained rl'nnerl5%T:.........[..
. ' . .' uter sTi" "4.0 : > - "
Examination Volume Definition Weld Length: 44.71 in. Area Measurement IVolume Calculation Inner 15%T 5.46 sq. in. Inner 15%T 2441 cu. in. Outer 85%T 30.91 sq. in. lOuter 85%T 1382.0 cu. in. Limitations Limits scan by: Compensation(s) Lug Reduction inScan length None 7? .Examination Coverage Calculations (7)eated as,zDua iedEaiato) ' INNER 16%T K, -Exam.,; Area Lengt Volumeý Volume-An'gle~ Beam~ Exanined Examined Examined Re-quired Percent' Entr de Direction (s. in.) c in (cu. In Examined Limited Limitations 1 70LU45L Ulp 546 42.05 229.6 - 2441 94.1% Yes Lugs
*2 761j45L- Dow 5.46 39.17 213-9 "244.1 887.6% 1 Yes Lg 3 ,L15 C1W' - 5.40 34.48 188.3 244.11 '77% 1 - yes tugs "4 -. 701451S 7 CCW"? "5.46 34.48 188.3 2441 77,1 %- tYes Lugs 1 Totals: 120.0 976.5 84.0%jt.:
OUTER,85%TT'
" Exam: '" < Area ~ength L Volume Volume . ..
-'Ajigle' 'Be-am Examined Examined Examjined Reiquired Percent -
Entry 4 (deg)' Dir~ction (siq. in.) (in.)' (ou;.in.)'. (cu in.) Examined' Limited' Lim~tations I 45L/458 Up -30.91 42.05 .1299.8' 1382.0 '>94.1% Yes Ltugs' 2" 451J453 Down "30.9.1 . 39:17 14 38. 87.6% Yes J Lugsw 3" 451145 -'W ~ 30.91 34:48,' 10165.8- 1382. 77.1W%: Yes . uj 4 ' 45LJ45S' 0,W '30.91 $4.48- 1065.8"ý 1382.0; 77.1%~~ Yes. L'ugs' N ' Totals:- 4642.1 5527,§~ a 4.0%
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 22 of 30 IA AR EVA PDominion-85%T Coverage Plot (Axial Scan - Parallel to weld) Limited due to Lug Miltone NO.: 101,-154C~
,Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 23 of 30 C
A AR EVA .pDominion-15%T Coverage Plot (Axial Scan - Parallel to weld) Limited due to Lug VW10Idd ldeTfifcation T,%NS No.: W17, MIstonelio: 01 0r1-54C ,
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 24 of 30 D50ominion-AR EVA p. 15% & 85% T Coverage Plot (Circumferential Scan - Perpendicular to weld) Limited due to Lug Weld Identifcation
-TWS'No..:W1 7j.
Millstone No .,"101-1:540'
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 25 of 30 AREVA Coverage Layout & Calculations Weld
Description:
Torus to Dollar Plate Weld ASME Code Item No.: B1.21 Millstone Weld ID: 102-151 ASME Code Figure No.: IWB-2500-3 TWS Weld Designator: W05 AREVA Drawing No.: 8017264 AGGREGATE COVERAGE: 38 % Zone Coverage Obtained Inner 15%T: 37.6% Outer 85%T: 37.7% Examination Volume Definition Weld Length: 425.10 in. Area Measurement Volume Calculation Inner 15%T 7.01 sq. in. Inner 15%T 2980.0 cu. in. Outer 85%T 40.93 sq. in. Outer 85%T 17399.3 cu. in. Limitations Limits scan by: Compensation(s) Incores Preventing full movement of Head Breaking circ scan into multiple regions to maximize scan coverage Examination Coverage Calculations (Treated as Dual Sided Examination) INNER 15%T Exam. Area Length Volume Volume
!*Entry # Angle (deg/.) Beam Direction Examined (sq. in.) Examined (in.,) Examined (cu. In-) Required (cu. In-) Percent Examined Limited Limitations.
1 70145L Up 7.01 159.41 1117.5 2980.0 37.5% Yes Incores 2 70LU45L Down 7.01 159.41 1117.5 2980.0 37.5% Yes Incores 3 70U45L CW 7.01 159.41 1117.5 2980.0 37.5% Yes Incores 4 70U45L. CCW 7.01 159.41 1117.5 2980.0 37.5% Yes Incores Totals: 4469.9 11919.8 37.5% OUTER 85%T Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Entry# (deg.) Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined Limited Limitations 1 45LJ45S Up 40.93 159.41 6524.7 17399.3 37.5% Yes Incores 2 45L/458 Down 40.93 159.41 6524.7 17399.3 37.5% Yes Incores 3 45L-45S CW 40.93 159.41 6524.7 17399.3 37.5% Yes Incores 4 451-145S CCW 40.93 159.41 6524.7 17399.3 37.5% Yes Incores Totals: 26098.6 69597.4 -37.5% Examination Coverage Calculations (Treatedas Dual Sided Examination) INNER 15%T (LIMITED REGIONS) Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent Ent (de . Direction (sq. in.) (in.) (cu. in.) (cu. in.) Examined Limited Limitations 1 701J45L Up 0.00 0.00 0.0 2980.0 0.0% Yes Inoores 2 70U45L Down 0.00 0.00 0.0 2980.0 0.0% Yes Incores 3 70LU46L CW 0.00 0.00 0.0 2980.0 0.0% Yes Incores
.4 70LU45L COW 0.00 0.00 0.0 2980.0 0.0% Yes Incores Totals: 0.0 11919.8 0.0%
OUTER 85%T (LIMITED REGIONS) Exam. Area Length Volume Volume Angle Beam Examined Examined Examined Required Percent
-Entry # - - (deg,.)- - Direction (cci. in.) (in.) - (cu. n) -(cu; in) Examined Limited Limitations 1 451-1455 Up 0.00 0.00 0.0 17399.3 0.0% Yes Incores 2 451-145S Down 1.55 101.55 157.4 17399.3 0.9%/ Yes Incores 3 451-45S CW 0.00 0.00 0.0 17399.3 0.0% Yes Incores 4 451J45S CCW 0.00 0.00 0.0 17399.3 0.0% Yes Incores Totals: 157.4 69597.4 0.2%
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 26 of 30 A AREVA Dominnion-UNLIMITED RV 00 SCAN REGIONS LIMITED AN SCAN RE GION-S a 0 a 0 0 0 0 a 0 0 44* 0 0 0 0 0 0 0 RV 2700 0 0 .0 0 90
- 0 0 0 0 0 0 0 0
0 0 0 4 0,a 0 a RV 180* I'
*RV Scan. Coverage Top View Weld-IdentifidefiOn-
*TWSNo.::W05.
-MilI sItone No.*: 02-4 51, (I
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 27 of 30 A AREVA D0.ominion-INCORE e 90' QUAD 85%T Coverage Plot (No Limitation - between Incores) (Axial Scan - Perpendicular to weld)
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 28 of 30 AREVA DotminicW-INCORE @ 90' QUAD 15%T Coverage Plot (No Limitation- between incores) (Axial Scan - Perpendicular to weld) . .
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 29 of 30 AR EVA W"Dominion- ) m Weld Identification TWS No.; W05, Millistonie No.: 102-151 INCnRE e 90' QUAD 15% & 85% T Coverage Plot (Circumferential Scan - Parallel to weld) (No Limitation- between incores)
Serial No. 10-189 MPS3 Request No. IR-2-51 Attachment 1, Page 30 of 30 AREVA WDominion-Weld Identification TINS. ýNo.: W051 1/2
ý,Miillstone No.-: 10 1-51 L55 aq In OBSTRUCTED (TOTAL 61*)
INCnRE e 90 QUADI 85%T Coverage Plot (Limitation - Near Incores) (Axial Scan - Perpendicular to weld) Note: 15%T Axial Scan (Perpendicular to weld) - No Coverage near Incores. 15%T & 85%T Circumferential Scan (Parallel to weld) - No Coverage near Incores.
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 2 RELIEF REQUEST IR-2-52 EXAMINATION CATEGORY B-B PRESSURE RETAINING WELDS'IN VESSELS OTHER THAN REACTOR VESSELS DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MP3 Request No. IR-2-52 Attachment 2, Page 1 of 10 Relief Requested In Accordance with 1,0 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality
- 1. ASME Code Components Effected ASME Code Class: Code Class 1 Examination Category: B-B, Pressure Retaining Welds in Vessels other than Reactor Vessels Item Numbers: B2.11, Pressurizer, Shell-to-Head Welds, Circumferential B2.40, Steam Generator, Tube Sheet-to-Head Weld Component Identification: Listed in Table 1
- 2. Applicable Code Addition and Addenda ASME Section XI, 1989 Edition, No addenda
3. Applicable Code Requirement
ASME Section Xl, 1989 Edition, Examination Category B-B requires volumetric examination of. 100 percent of the weld volume as defined in Table IWB-2500-1 and shown in Figures IWB-2500-1 and IWB-2500-6. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147 Rev. 15, allows credit for essentially 100 percent coverage of the welds provided greater than 90 percent of the required volume has been examined.
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from essentially 100 percent volumetric examination coverage requirement for the subject welds due to the geometric configuration and permanent obstructions which limit the volumetric coverage that can be attained.
The pressurizer shell to upper head Weld (03-007-SW-J) examination is limited due to seven permanently welded 2" x 2" insulation support ring mounting pads, four 3" diameter instrument taps and four vertical support members from a pressurizer safety valve restraint that obstruct portions of the subject weld and preclude achieving the required 100 percent volume examination coverage.
Serial No. 10-189 MP3 Request No. IR-2-52 Attachment 2, Page 2 of 10 The steam generator tube sheet to head weld (03-003-SW-Z) examination is limited due to the close proximity of the tube sheet flange that limits scanning on the tube sheet side of the weld. Additional limitations are due to 4 lower steam generator support vertical members that obstruct portions of the subject weld and preclude achieving the required 100 percent volume examination coverage. Isometric drawings, coverage calculations and limitation sketches are provided in this attachment. TABLE 1- Examination Category B-B Welds with Limited Volumetric Coverage Weld Number Item Configuration Comments Ultrasonic Number Examination Coverage 03-007-SW-J B2.11 Pressurizer shell to Limited examination due 74.7 upper head weld to obstruction caused by permanent insulation support ring mounting pads and pressurizer safety valve restraint members. No recordable indications were detected. 03-003-SW-Z B2.40 Steam generator Limited examination due 81.5 tube sheet to head to obstruction caused by weld tube sheet flange and steam generator lower support members. No recordable indications were detected.
- 5. Burden Caused by Compliance To increase the examination coverage for weld number 03-007-SW-J requires removal of the permanently welded insulation support ring mounting pads by cutting the mounting pad welds and then reinstalling the mounting pads by welding following completion of the examination. Additionally, removal of the pressurizer safety valve restraint would be required which also requires removal of the safety valves and associated piping to provide clearance necessary for the restraint to be removed.
Serial No. 10-189 MP3 Request No. IR-2-52 Attachment 2, Page 3 of 10 To attempt removal of the massive restraint could also subject adjacent plant equipment to potential damage during the removal process. To increase the examination coverage for weld number 03-003-SW-Z requires removal of the lower steam generator support members which provide stability and support the weight of the steam generator. Additionally, a significant design modification or replacement of the component with a different design is required to eliminate the obstructions caused by the location of the tubesheet. These options to meet the 100 percent Code examination requirements are considered impractical due to the cost, additional radiation exposure, and impact to plant equipment.
- 6. Proposed Alternative Examination and Basis for Use The subject welds received a volumetric examination utilizing the best available techniques on the accessible portions of welds to the extent practical. Additionally, a visual (VT-2) examination is performed at the end of each outage during the system leakage tests as required by Section Xl, Table IWB-2500-1, Category B-P.
Based upon the examination volumes that were obtained with acceptable results and the visual (VT-2) examination performed each refueling outage, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.
- 7. Duration of Proposed Alternative Relief is requested for the second 10-year inspection interval for Millstone.Power Station Unit 3, which began on April 23, 1999 and ended April 22, 2009.
a) C\j 0 OD LO c 0 a) 0) Z0 Zo CO -ia , a-
.= U)
(D U) a) (D ir E CO co TOP VIEW Il A~l.ll1. l . 1't ll !11
C\j C CD
~LO o0)
Z ca 0) a) C\T Cl) L0~ WOO..* pMRUE DI"
#V
ýRE.
0)C~Cj 00 LO-I
'7 Wa) 4.
I MAL"~ =MM,4ff AEV BJI1DIW V.DA
&IM
+/-A~AJA~
SvcIGS
.EF WAYTAONATM.
UjG n3i00 SEON*AL tLVATION
*BOTTOM VIEW IS6EQ*.Y I MANWAY STUDS DETAIL SECcON.-8
00 LO - g
- cjJ MTAM T~~AOR sECTIONB6%
09AWINGS C< L~fAGMRwaýtTPU*JMPOt Il
Serial No. 10-189 MP3 Request No. IR-2-52 Attachment 2, Page 8 of 10
'A1TACHMENT 1 L
COVERAGE CALCULAT1ON DATA SHEET "1 .I I *1 UI Pant MlusrTe, - , _ Awn M
*liU Ilglll*l
-k. ni_ I ILM System 2?a rzf Percentage of Ame Examined 1. b Component ID ~ ~ Exatmination Data Sheet a.
Component Desoiiption RZ SUL.. 1)6A. Calibration Data Sheet #IifI Procedure No. M-*--7 ".Rev_.* Page Yt j of K' " Calculatln Type Surface[] ' Volumetric
Serial No. 10-189 MP3 Request No. IR-2-52 Attachment 2, Page 9 of 10 ATTAO.HMENT i COVERAGE CALCULATION DATA SHEET Plant ,;l.t. Unit AWONumber . -*-I 427G System ,/A S Percentage of Area Examined ComponentID - 3- oo3 -$CJfZ. Examination Data Sheet# 311-. - oYy Component Description T%.6..lct d cjo,) t*,.kkA* Cahlbration Data Sheet#0 as Procedure No.Mv P-!LAT-7 _ Rev o0:-O'4 Page 1,2.A of JA13 Calculation Type Surfacef7 Volumetric E
'Coverage: Calculation I Equation I Sketch Area C- *.5c=, c" \-,. t 0c.'A",
,SCOI^ H *- P..-*\*,-\ 8°/,, Exarniner comments Sk A I -+v-, L j k e.Ldo 1 - i,1tSlI I ,~(Z~
- L\
Levelof~s W6 P-)Cr-2 t~!~nceRev. 000-0`1 t-- ii of Ii
Serial No. 10-189 MP3 Request No. IR-2-52. Attachment 2, Page 10 of 10 Millstone Unit 3 Ultrasonic Examination Sketch Sheet Referencel1: I11- 0 qWYve 03 taPkq.: y Page: aii of5~ 1 Sketch Area
?Vc CVt(ro 5 t- *E4Qr 'a PorcAI~~eA 5C~.n5 p1-"oi e.C
-Ze b4.
-r o $L.ffb rw~cj .~"
A/ -pu r Commanft: . . I-- J.- 4
!U e r o.+ 6.J-hrp 4. sc L5
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 3 RELIEF REQUEST IR-2-53 EXAMINATION CATEGORY B-D FULL PENETRATION WELDS OF NOZZLES IN VESSELS'- INSPECTION PROGRAM B DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 1 of 35 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality
- 1. ASME Code Components Effected ASME Code Class: Code Class 1 Examination Category: B-D, Full Penetration Welds of Nozzles in Vessels -
Inspection Program B Item Numbers: B3.1 10, Pressurizer, Nozzle-to-Vessel Welds B3.130, Steam Generator, Nozzle-to-Vessel Welds B3.90, Reactor Vessel, Nozzle-to-Vessel Welds Component Identification: Listed in Table 1
- 2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No addenda
3. Applicable Code Requirement
ASME Section Xl, 1989 Edition, Examination Category B-D requires volumetric examination of 100 percent of the weld volume as defined in Table IWB-2500-1 and shown in figure IWB-2500-7. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147 Rev. 15, allows credit for essentially 100 percent coverage of the welds provided greater than 90 percent of the required volume has been examined.
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100% volumetric examination coverage requirement of the subject welds due to the geometric configuration and permanent obstructions which limit the volumetric coverage that can be attained.
The steam generator nozzle to head welds, and the pressurizer spray, safety, and relief nozzle to head welds were examined with a manual ultrasonic technique using the best available technology to achieve the maximum examination coverage practicable. Due to the nozzle configuration with its outside diameter taper, scanning on the nozzle side
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 2 of 35 f of the weld is limited to circumferential scans only and prevents attaining 100 percent examination coverage. The pressurizer surge nozzle to head weld was examined with a manual ultrasonic technique using the best available technology available to achieve the maximum examination praciicable. There are 78 pressurizer heaters that penetrate the pressurizer bottom head. Due to permanent obstructions caused by these pressurizer heater penetrations, scanning was limited on the head side of the weld which prevents attaining 100 percent examination coverage. The reactor vessel nozzle to head welds were examined using automated ultrasonic technique during the 10-year reactor vessel examination. The examinations were performed with equipment, procedures and personnel qualified in accordance with the requirements of ASME Section Xl, Appendix VIII 1995 Edition thru 1996 Addenda as. modified by the Performance Demonstration Initiative (PDI). Due to the permanent obstruction of the outlet nozzle boss, scanning was limited on the shell side of the welds which prevent attaining 100 percent examination coverage. Isometric drawings and limitation sketches are provided in this attachment. TABLE 1- Examination Category B-D Welds with Limited Volumetric Coverage Weld Code Item Configuration Comments Ultrasonic Identification Number Examination Coverage 03-006-SW-U B13.130 Steam generator Scan limitations due to tapered nozzle 77.77 Outlet Nozzle to configuration restricting the axial scans Head weld. from the nozzle side. No recordable indications were detected. 03-006-SW-V B13.130 Steam generator Inlet Scan limitations due to tapered nozzle 77.77 Nozzle to Head weld configuration restricting the axial scans from the nozzle side. No recordable indications were detected. 03-007-SW-A B3.1 10 Pressurizer Safety Scan limitations due to tapered nozzle 77.70 Nozzle to Head Weld configuration restricting the axial scans from the nozzle side. No recordable indications were detected. 03-007-SW-B B3.1 10 Pressurizer Safety Scan limitations due to tapered nozzle 77.70 Nozzle to Head Weld configuration restricting the axial scans from the nozzle side. No recordable indications were detected. 03-007-SW-C B3. 110 Pressurizer Safety Scan limitations due to tapered nozzle 77.706 I Nozzle to Head Weld configuration restricting the axial scans from the nozzle side. No recordable _indications were detected.
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 3 of 35 TABLE 1- Examination Category B-D Welds with Limited Volumetric Coverage Weld Code Item Configuration Comments Ultrasonic Identification Number Examination Coverage (%) 03-007-SW-D B3.1 10 Pressurizer Relief Scan limitations due to tapered nozzle 77.70 Nozzle to Head Weld configuration restricting the axial scans from the nozzle side. No recordable indications were detected. 03-007-SW-E B3.110 Pressurizer Spray Scan limitations due to tapered nozzle 77.70 Nozzle to Head Weld configuration restricting the axial scans from the nozzle side. No recordable indications were detected. 03-007-SW-S B3. 110 Pressurizer Surge Limited coverage due to obstructions 64.16 Nozzle to Head Weld from pressurizer heaters. No recordable indications were detected. 107-121A B3.90 RPV Outlet Nozzle to Scan limitations due to obstruction from 70.00 Shell Weld the nozzle boss. No recordable indications were detected. 107-121B, B3.90 RPV Outlet Nozzle to Scan limitations due to obstruction from 70.00 Shell Weld the nozzle boss. No recordable indications were detected. 107-121C B3.90 RPV Outlet Nozzle to Scan limitations due to obstruction from 70.00 Shell Weld the nozzle boss. One subsurface indication was detected that was _evaluated as acceptable to IWB-3512-1. 107-121D B3.90 RPV Outlet Nozzle to Scan limitations due to obstruction from 70.00 Shell Weld the nozzle boss. Two subsurface indications detected and evaluated as acceptable to IWB-3512-1.
- 5. Burden Caused by Compliance To increase examination coverage on the subject welds requires a significant design modification or replacement of components with a different design to eliminate the noted obstructions, which is considered impractical due to the cost, additional radiation exposure and impact to plant equipment.
- 6. mProposed I
Alternative and Basis for Use The subject welds received a volumetric examination utilizing the best available techniques on the accessible portions of welds to the extent practical. Additionally, a visual (VT-2) examination was performed at the end of each refueling outage during the system leakage tests as required by Section XI, Table IWB-2500-1, Category B-P.
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 4 of 35 Based upon the examinations volumes attained with acceptable results and the visual (VT-2) examination performed each refueling outage, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.
- 7. Duration of Proposed Alternative The relief is requested for the second ten-year inspection interval for Millstone Unit No.
3, which began on April 23, 1999 and ended April 22, 2009.
CD CD 0CD, Z Z.. (Q C CD' M) WA CD
/
TOP VIEW R~EFERENCE DRAWINGS:
*CK M -tr Il a4~S CO.OO6
ýPtltlJ
-r CA)
C/) CD
- l. *' 'a $ A hJ (a 0 z
CD 0 0 a)CJ
(C/) 3nX C,:D -0 / wi Z Z (D 0 0 CD 0 C 01n CA) (D
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 8 of 35 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant mill Unit : AWO Number M-6.6,4- ItOR,7 . System Percentage of Area Examined '77. 1'7 Component IDll)- OC'( SW- U Examination Data Sheet . 31o - 02 - Component Description OQTL..T 4ox..E ro ýtOA Calibration Data Sheet #1 ProcedureNo. MP-LrT-7 Rev 000-0.. Page 2* of %..._. Calculation Type Surface [3 Volumetioo..._ Coverage Calculation I E-quation I Sketch Area Ic.t." ..... ............................... 0 ExaasnerComrnents Ge COW- 11.1( too u5v 11-11,16
% toe 1>5 %
-S OX, 791.,77 Vg d6 96-4--r'
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 9 of 35 ATTACHMEN4T I COVERAGE CALCULATION DATA SHEET Plant P -Unit AWO Number M5- &q- *-llol System_____________ Percentage of Area Examined Component ID o3 3- 0(.o Sw - V Examination Data Sheet# .3. 0-;o01-00L-3* Component Description, wLeT Iox. T- I4cA .Caribratior Data Sheet , ProcedureNo 1. L4,17-.-. Rev oo --o4_ page . of . Calculation Type Surface EI] Volumrr.etrR _ Coveprge Calcullon IEgquaton I Sketch Area l ..o0 l L-AI, 1 ExarnIner Commnuirts 1. a.=: IIit fw 2: U. k U 2A z U-11 ek
~ ~ ~ar!*Ata i a10/
17)
?.A to& &-w
£,,e\" tuS 0 7b/
11 VAi 16-no 015 = 0%it1 I)04-'U %a 0'Me q} r-v) I.}'*3 -:, 1%.'% 0 6)5 00, t / I ~6.tAi@~11L~AI~O VELO eROU~A& W.I! Tc1-9 L-5~'*d44MZ ZS %!v"aA II
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 10 of 35
'ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant N\', unit UJW*_ _ AWONumber >t- \'I*-a System (.. C
- Percentage of Area .Examined -11.1%
Component ID o ad W- Examination.Data Sheet #- -/ I_ Component Description \hp ,&L-o mu,. Calibration Data Sheet # i%.. -. , Procedure No. .f X' T Rev 0 Page of .9. Calculation Type Surface El Volumetric __ Coverage Calculation I Equation /Sketch -Area
<1*CON A jaV4v t* P P, -% %
GAN OVA\SA~toz 1oo'ý,, JG4~O fJ S j\- (o se w.60,0AL4.t- O%, SC-1460 YAJ tCALQi - Examiner Comments Swkl.- ýý 4ý- c--Vc
4eý* Tr tT " . k I I I I I 4~. C/) CD~ CA0 C/ CD oD0 CA) cn00 (11CA (D
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 12 of 35
'ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET plant f kv-s-i~ Unit~ AWONumber o t. ýII-P~
System. C_ ' Percentage of Area Examined '1 1.1 %7, Component ID ,- - .% Examination .Data Sheet # __ _ _ _ Component Description __,___ ___:__ .__-__ CalibrationDal______ _ ........ ProcedureNo. -("\V-XXT-"- Rev 0 Page " of 1 Calculation Type Surface E] Volumetric' _ Coverage Calculation /Equatlon /Sketch Area
*Cr_', O 0 'JJeL-t -" oo P
SC.tL s' 0o pA S -o
,sCc -600 - %00A0L
. ,, _' /. J C V.,
Examiner Comments sj~- k. -r~~o~
%, skeA4c,.
4
00 iD M [D = N 0 / CD0 no 0
-P II W 0 nCA) (D
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 14 of 35 CQVERAGE CALCULATION DATA SHEET plant s-* " AWO Number ot- M'a4'-i System (. C I Percentage of Area Examined "11.1 Component ID OYl. MC*1
- - . Examination.Data Sheet ,4,,
/.
Component.Description SA$ 3. bvkU Calibration Data Sheet f ~ I .2-'.3 Procedure No.. (vX-Xt-L Rev 0 Page___ of A Calculation Type Surface[3 Volumetric _
"Coverage Calculation I Equation I.$ketch Area Saar.'0 weN-t -- C%
5cAtN 4cP 40-Ak S%0%K - I 6~ 600 o-j I e SCAN. t-Wo°**L* . ,:v, J 0 ,C 0 .. . j~10 cvldk-J'Q ce, vqwoo z~xamrner toniments S,- &>.*g *.. c..,A,6. - Soe** kA* ,,__
,J %J.
Noz2~L~
.I 3C-0 M D~
CD OZZ CD0 wcnco1
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 16 of 35
.A-ACHMENT 1 COVERAGE CALCULATION DATA'SHEET Plant W S,-oNt. f.itnk AWO Number 0 L- \,14*..
System . " - Percentage of Area Examined - 1 .' , Component ID O01- 0o0 SW - C Examination Data Sheet #_ .... ___ ___ Component Description ý&. VIA.'JJ Calibration Da(a Sheet # 3/,,ii. ProcedureNo-. C\ -X'(-T.-2 Rev 0 Page -7 of Calculation Type. Surface El Voiumetric'% ___________________ Coverage Calculation I Equation I Sketch -Area tL1 SCANJ: kVa WOV4-AL Slvi- A
$*JtW'---/*-
L£o~ V0t~A-VLL - (04% 1]'"o** *"
$cc.N 600 ExaminerC~mmtents
~~s)~ Ž ~ coLArT~
/
-r -r W.CAC) -7 I I I I I I I
3CA)
~CDM CDO
-0
~Cr CD~(
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 18 of 35 COVERAGE CALCULATION DATA SIHEET Plant VA-Vi,-e'N-- (ait a AWO Number __,_ t - _1__
,_.4_
system , , Percentage of Area Examined -1 *1,1 Component I .... o-Opt - L*J- F- Examination Data Sheet #___ _ __ __ Component.Description ,SlP4-. tpow 1. Calibration Data Sheet _ /a Procedure No. X ' .Rev C Page L" .of "L._9 I! Calculation Type Surface Volumetric, '
.1 ii Coverage Calculation I Equation I Sketch Area AwO 00 WeLts GCAN LAksM P-I'~ ~ S~r iO -b SCA.O (0e w.W4 -0 to 0~
,Sew' GO a ct.u.r
's CcN 1,00 ~L~i ri Doc h -,1II I-/ CcVtc)- 1ý;
Examlher'Comments e-: A ~..
.'A
.t
IL I 44A CD
~--CfJ (CA) 0 0 OCA) (0
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 20 of 35 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant M i.LL -o.E" Unit AWONumber M o& t,4 'At-E: System ( C s Percentage of Area Examined ("-. I. Component ID 03,- 0 0 "7 - S*.)- 'S Examination Data Sheet # I. - Component Description :UI.&m _* iv a-.,, 4-riA Calibration Data Sheet# 1" Z, ProcedureN ,*-AA.,4r-rl--7gZRev ,ooz Page to of I"f Calculation Type Surface f] Volumetric [, Coverage Calculation I Equation I Sketch Area VESSEL WELD 13" THICK [-.CLAD) 11.5" WELD WIDTH I CLASS I CODE VOLUME OBSTRUCTED DUE TO CONFIGURATION AND PZR HEATERS SC ,A-N 0° '" 81% SCAN 45" NORMAL VESSEL SIDE 40% SCAN 45" NORMAL NOZZLE SIDE 66% SCAN 60" NORMAL VESSEL SIDE 25.4% SCAN 60' NORMAL NOZZLE SIDE 41% SCAN 45' PARALLELCW 81% SCAN 45' PARALLEL CCW 81% SCAN 60" PARALLEL CW 81% SCAN 60° PARALLEL CCW 81% TOTAL 577.419 6416%,Coverage Obtained Examiner Comments SF--_AT-Ai'*_ Af-*_
,- PLTrS
Outage No.: 3R12 Report No.: 312-01-003 UT Indication/Coverage Plot Sunmmnry No.: NIA Page No.: ../ of Site: MILLSTONE Unit: 3 Drawing No.: 26212-20905 Component ID: ' 03-007-SW-S Descrption:. SURGE NOZZLE TO LowER HEAD - Procedure: ER-AA-NDE-UT-702 RE6 002 Prepared By: W.L.THOMAS . Level: III Signature: Date: 10121108 SCAN 0o 3.8" NOZZLE TOTAL 0 DEO. CODE EXAM VOLUME - 14.4 SQ. IN, TOTAL 0 DEG AREA EXAMINED = 11.67 SQ. IN. TOTAL 0.DEG AREA NOT EXAMINED - 2.73 SQ. IN.
~CD TOTAL 0 DEG CODE EXAM VOLUME EXAMINED - 81%
CCD CD-(ZZ CD 0 CA CA)C.c
Outage No.: 3R12 Report No.: 312-01-003 UT Indication/Coverage Plot Summary No.: NIA Page No.: of Site: MILLSTONE Unit 3 Drawing No.: 25212-20905 Component ID: 03-007-SW-S Desciption: SURGE NOZZLE TO LOWER HEAD Procedure: ER-AA-NDE-UT-702 REV 002 Prepared By:. W.LThOMAS Level: Ill. Signature: Date: 10121108 SCAN 45" NORMAL VESSEL SIDE IMEA1 OBSWMUCTIOf NOZZL2E 3C-) CD M nCD0
- C/
C: CD CD TOTAL 45 DEG CODE EXAM VOLUM-dE REQUI*ED = 14.4 SQ. IN. TOTAL 45 DEG VESSEL SIDE AREA EXAMND- 5.8 SQ. IN. - (a ZZ (D 0 C TOTAL 45 DEO VESSEL SIDE A*EANOT EXAMINED 8.6 SQ. IN. TOTAL 45 DBG VESSEL SIDE CODE VOLUME EXAMINED = 400A 00 d.~M~~.4c..jf%-s C-40 99) CA cnCA) (
-n 0
Outage No.: 3R12 I LIT IndicatIoniCoverage Plot Report No.: Summary No.: Page No.: 312-01-003 of N/A 3 Drawing No.: 25212-20905 03-007-sw-s Site: MILLSTONE Unit: Component 10: Deseriptic Pmredure: _R-A on: SURGE NOZZLE TO LOWER HEAD 002 NDE-UT-702 Prepared By: W.L.THOMAS ' Level: III . Signature 0" Date: 10121/08 SCAN 45* NORMAL NOZZLE SIDE NOZ= 0 ZCDM C)) CD CD TOTAL 45 DEG CODS EAMVOLUME PEQU*RED 14.4 SQ IN. A TOTAL 45 DEONOZZLE SDE AREA EXAMINED = 9.49 SQ IN. TOTAL 45 DEG NOZZLE SIDE AREA NOT EXAMINED = 4.91 SQ IN. oZ CDO0 0 TOTAL 43 DEG NOZZLE SIDE CODE VOLUME EXAMINED - 66% CA)i (0
Outage No.: 3R12 Report No.: 312-01-003 UT IndicationlCoverage Plot Summary No.: NIA Page No.: of Site: MILLSTONE Unit: 3 Drawing No.: 25212-20905 Component ID: 03-007-SW-8
== Description:== SURGE NOZZLE TO LOWER HEAD Procedure: ER-AA-NDE.UT-702 REV 002 Prepared By:. W.LTHOMAS Level: III Signature: Date: 10121108 SCAN 60" NORMAL VESSEL SIDE 3.8" NOZZLE
+ 41 U)
CD M TOTAL 60 DEG CODE EXAM VOLUME -14.4 SQ IN. ~-U) TOTAL 60 DEO VESSEL SIDE AREA EXAMINED = 3.66 SQ. IN. TOTAL 60 DEO VESSEL SIDE AREA NOT EXAMED = 10.74 SQ. IN. TOTAL 60 DE( VESSEL SIDE CODE VOLUME EXAMINED = 25.4% (aZZ 09 WCn M1 Cn CA) (D
Outage No.: 3R12 Report No.: 312.01-003 UT Indication/Coverage Plot Summary No.: N/A Page No.: o Of.L.- Site: MILLSTONE Unit-. 3 Drawing No.: 25212-20905 Component ID: 03-007-SW-S
== Description:== SURGE NOZZLE TO LOWER HEAD Procedure: ER-AA-NDE-UT-702 REV 002 Prepared By: . W.L.THOMAS Level: !ii Signature: Date: 10/21108
.SCAN 60° NORMAL NOZZLE SIDE 3.r' HEATP.OHSBMUCTION NOZZLE
-C/)
CD) TOTAL 60 DEG CODE EXAM VOLUME REQUIRED = 14.4 SQ IN. C CD-TOTAL 60 DEG NOZZLE SIE AREA EXAMINED - 6.36 SQ IN. TOTAL 60 DEG NOZZLE SIDE AREA NOT EXAMINED - 8.04 SQ IN, CD0 TOTAL 60 DEO NOZZLE SIDE CODE VOLUME EXAMINED - 41% CA) 0 (P CA) (D
Outage No.: 3R12 A T UT IndicationlCoverage Plot Report No.: 312-01-003
...... Summary No.:
Page No.: I-. of NIA is- 7 Site: MILLSTONE Unit 3 Drawing No.: 25212-20905 Component ID: 0.3-007-SW-S Descriptl on: SURGE NOZZLE TO LOWER HEAD Procedure: ER-AA-NDE-UT4702 REV 002 Prepared By: W.L.THOMAS Level: Il _ signature: 1=1...8 Date, SCAN 45" PARALLEL CW
-MRAM OBSMUcrMON
ý----1J5-NOZZMS PZR BOTrTOM 3.0' TOTAL 45 DEG CIRC SCAN CW CODE MXAM VOLUME REQUIE D 14.4 SQ IN.
TOTAL 45 DEG CIAC SCAN CW AREA EXAMNED 11.67 SQ. IN. TOTAL 45 DEG CIRC SCAN CW AREA NOT EXAMINED - 2.73 SQ. IN TOTAL 45 DEO C*RC SCAN CW CODE VOLUAE = 81%
=3 CD
Outage No.: 3R12 Report No.: 312-01-003 UT IndicationlCoverage Plot Summary No.: NMA Page No,: 1_3 -Of Site: MILLSTONE Unit: 3 Drawing No.: 25212-20905 Component ID: - 03-007SW-S
== Description:== SURGE NOZZLE TO LOWER HEAD Procedure: ER-AA-NDE-UT-702 REV 002
* "0' Prepared By: W.LTHOMAS Level: III Signature: ___-__ ,.__"---_-__ Date: 10121108 SCAN 45" PARALI. EL CCW TOTAL 45 DEG CIRC SCAN CCW CODE EXAM VOLUME R13QUMRD =14.4 SQ IN. CD M TOTAL 45 DEG CIRC SCAN CCW ARBA EXAMIND 11,67SQ IN.
TOTAL 45 DEG CIRC SCAN CCW AREA NOT EXAMIND 2.73 SQ IN. (a ZZ TOTAL 45 DEG CIRC SCAN CCW CODE VOLUME ACHIEVED = 81% (00 01 CIOC.0
Outage No.: 3R12 UT IndicationlCoverage Plot Report No.: 312-01-003 Summary No.: NIA Page No.: of - Site:. MILLSTONE Unit 3 Drawing No.: 25212-20905 Con 1pornent ID: 03-007-SW-S
== Description:== SURGE NOZZLE TO LOWER HEAD Procedure: ER-AA-NI ~E-UT-702 REV 002 Prepared By: W.L.THOMAS Level: III Signature: Date: 10121108 SCAN 60" PARALLEL CW 3s-d. NOZZLE TOTAL 60 DEG CIRC SCAN CW CODE EXAM VOLUME REQUIRED 14.4 SQ IN. CA) TOTAL 60 DEG CIRC SCAN CW AREA EXAMINED = 31.67 SQ IN. TOTAL 60 DEG CIRC SCAN CW AREA NOT EXAMED - 2.13 SQ IN.
~CD TOTAL 60 DEG CIRC SCAN CW CODE VOLUME ACHIEVED 82%
m) -" 020 0 W (Ji
~C~o co(
Outage No.: 3R12 RA UT Indication/Coverage Plot Report No.: 312-01-003 Summary No.: NIA Page No.: of at Site: MILLSTONE Unit: 3 Drawing No.: 25212-20905 Component ID: 03-007-SW-S
== Description:== SURGE NOZZLE TO LOWER HEAD Procedure: ER-AA-NDE-UT-702 REV 002 Prepared By: W.LTHOMAS Level: III Signature: ýOE- Date: 10121108 SCAN 600 PARALLEL CCW NOZ2ZI 0 TOTAL 60 DEG CIRC SCAN CCW CODE EXAM VOLUME REQUIRED 14.4 SQ. IN. TOTAL 60 DEG CIRC SCAN CCW AREA EXAMINED = 11.67 SQ, IN. TOTAL 60 DEG CIRC SCAN CCW AREA NOT EXAMINED = 2.73 SQ IN. SiQ U1C)
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 30 of 35
.. .... ,/ ... .. .. ...... .. . ........ . .... ... .. ,... .... .... ........
AREVA Coveraae Layout & Calculations Weld
Description:
Outlet Nozzle to Shell @ 22f, 158°, 202", 3380 ASME Code Item No.: B3.90 ASME Code Figure No.: IWB-2500-7 Millstone Weld ID (TWS Weld Designator): 107-121A (W19), 107-121 B (W25) 107-121C (W27), 107-121D (W33) AREVA Drawing No.: 8017264 AGGREGATE COVERAGE: 70% Zone Coverage Obtained Examination Volume Definition Area Measurement *Volume Calculation Area Measurement not calculated for nozzles. IInner 15%T 697.6 cu. in. ____________________________ uter 85%T 6353.6 cu. in. Limitations Limits scan by: Compensation(s) Nozzle Boss Reduction In scan index None
- ~~~Examirfintion Co7crng C6elu 1ielon (Treated as Dual SddEaiain INNERI5%T ~ , ><~1 * ~ .
Exam, Length Volume V, - -
~Angle Kýean Eamiined E~aminned Required Percent .-. 7 Entrv # (Ay.) Direction. (degc) (cu.in.) (cu. in.) Examwind.Lhirmtd Limitations 1 70L145L Shell Ra6dia ý360~ 6.97,6 697.6 1C)00.0% Yes* Nozzle B~oss -
2 16L145S Bor Rdil 360 697.6 697.,' 100.0% INo 3 70L145L' Shell1' OW 360 48,0 6D7.6 6.9%1 Yes Nozzle Boýss 4 70L14ý5L She-ll:,COW 360 48.0 69776> . 9% Yesj Nozzle Boss Totals: 793.6' 20-92.8 53.4% This coverage is satisfied with the scan form, the nozzle b&o f- Ae, OVTER 85%T
&~am.> Length Volume, Volini$ Vc ->
jAngle Beam Examined Examined Required Percent - - Enitry# (deg-) .Direction (iW) (cu. )n.) i'cudj- ' Examined Limited ' Umitatkins 1 1iSJ4?5S, Born: ,Rqihi In, 360 E 53 , 63t3.6 1O9.9%/1 No 3 45l4s Shell OW 36W) 80ý61& 653.6~ 79.3%. Yes' NozzleBoss 4 45lJ3 She~ll- COW,- - 360' 5036.8 6353ý.6: 79.3% Yes? -- Nozzle Bo~ss Totals: 16427.2 19060.8 86.2%
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 31 of 35 AA 'AR EVA" D00ominionw HORIZONTAL SECTION VIEW VERTICAL SECTION VIEW VESSEL SUPPORT OUTLET NOZZLES
'It D & H ONLY 15%T & 85%T Coverage Plot (Radial Scan - Perpendicular to weld from Nozzle Bore) iM111stone N~o, (,TWS'No.): -107-i2-'M 9,ý17ýý-'
121 B.(W2ý5)'1,07-1-21,& I-('7 21,07W129,
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 32 of 35
*Domi.io-AREVA 15%T Coverage Plot (Radial Scan - Perpendicular to weld from Shell ID)
Beam Direction away from Bore ID Ides tifration. .Weld Millstone:No..(TWS No.'):, 1,7-121A(W19),107 K 121,B (W25) 1074.121 C (W27)10 7-121bý p-(W33
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 33 of 35 ARE VA Dominion-VESSEL SUPPORT OUTLET NOZZLES nl k. P- nuM v 15%T Coverage Plot (Radial Scan - Perpendicular to weld from Shell ID) Beam Direction toward Bore ID
'WeWdIdentificatin -
-MiIlstoneN&ý(TW No~.).- 1071,2lA,ý(WI 9)"r 1'07-121 B (W25),107-'1'C:(W27)" 107-7121DJW33)':
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 34 of 35 A AR EVA S Dominion-
.15% T Coverage Plot (Circumferential Scan - Perpendicular to weld from Shell ID)
Weld'lde~ntificatloný'-`- 11 Millstone No. (TWVSýNo)::1O7-12. A(97177
'2B(W2) 10-1 21'CW2) O-2 (Wa3
Serial No. 10-189 MPS3 Request No. IR-2-53 Attachment 3, Page 35 of 35 A AR EVA PDomiation-85% T Coverage Plot (Circumferential Scan - Perpendicular to weld from Shell ID) WeldI Identifica ion.,: i121B(W25)'1V7-121C' -1077 -12.1D1(W33) C
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 4 RELIEF REQUEST IR-2-54 EXAMINATION CATEGORY B-H, INTEGRAL ATTACHMENTS FOR VESSELS DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MPS3 Request No: IR-2-54 Attachment 4, Page 1 of 7 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality
- 1. ASME Code Components Effected ASME Code Class: Code Class 1 Examination Category: B-H, Integral Attachments for Vessels Item Numbers: B8.20, Pressurizer Component Identification: Listed in Table 1
- 2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No addenda
3. Applicable Code Requirement
ASME Section Xl, 1989 Edition, Examination Category B-H requires surface examination of 100 percent of the weld length as defined in Table IWB-2500-1 and shown in figure IWB 2500-15 for the subject welds. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147 Rev. 15, allows credit for essentially 100 percent coverage of the welds provided greater than 90 percent of the required volume has been examined.
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100% surface examination coverage requirement of the subject welds due to obstructions caused by a component support structure which limits the surface examination coverage that can be attained.
The subject attachment welds and their associated lugs provide attachment points for the pressurizer safety valve and piping restraint. There are 8 welded lugs consisting of 4 pairs with each pair located approximately every 90 degrees around the circumference of the pressurizer. With the pressurizer safety valve
Serial No. 10-189 MPS3 Request No: iR-2-54 Attachment 4, Page 2 of 7 restraint in place, the support brackets mount over the positioning lugs and are pinned in place. These support brackets overlap approximately 80 percent of each attachment lug and their associated welds leaving this portion of each weld inaccessible for examination. The support requires disassembly and removal to increase the examination coverage for these welds; however, due to the massive physical size of the support (weighing an estimated 10,000 pounds), specialized rigging and handling techniques are required to attempt removal. Due to the size of the support, its movement during the removal activity presents the potential to damage adjacent plant equipment. Reinstallation with critical alignments is also a concern. In addition, the support is configured in such a manner that the pressurizer safety lines route through the support members inhibiting the removal of the support without removal of the pressurizer safety valves and associated piping. The use of ultrasonic examination was evaluated and due to the weld configuration and access, it was determined that no meaningful results could be attained. Additionally, liquid penetrant was considered and evaluated. Due to the confined space under the bracket, it was determined that no additional coverage could be expected. Support configuration drawings and limitation sketch are provided in this attachment. TABLE 1- Examination Category B-H Welds with Limited Surface Examination Coverage Weld Number Code Item Configuration Comments Surface Number Examination Coverage 03-007-SW-TL B8.20 Pressurizer North Limited accessibility due to 20 Support Bracket Lug the obstruction of the restraint (Left) brackets. No recordable indications were detected. 03-007-SW-TR B8.20 Pressurizer North Limited accessibility due to 20 Support Bracket Lug the obstruction of the restraint (Right) brackets. No recordable indications were detected.
Serial No. 10-189 MPS3 Request No: IR-2-54 Attachment 4, Page 3 of 7 TABLE 1- Examination Category B-H Welds with Limited Surface Examination Coverage Weld Code Configuration Comments Surface Identification Item Examination Number Coverage N%) 03-007-SW-VL B8.20 Pressurizer South Limited accessibility due to 20 Support Bracket Lug the obstruction of the restraint (Left) brackets. No recordable indications were detected. 03-007-SW-VR B8.20 Pressurizer South Limited accessibility due to 20 Support Bracket Lug the obstruction of the restraint (Right) brackets. No recordable indications were detected. 03-007-SW-WL B8.20 Pressurizer East Limited accessibility due to 20 Support Bracket Lug the obstruction of the restraint (Left) brackets. No recordable indications were detected. 03-007-SW-WR B8.20 Pressurizer East Limited accessibility due to 20 Support Bracket Lug the obstruction of the restraint (Right) brackets. One 1.1 in. long lihear indication was detected and evaluated as a laminar flaw in the integral attachment material and was acceptable per IWB 3516.2(b). 03-007-SW-XL B8.20 Pressurizer West Limited accessibility due to 20 Support Bracket Lug the obstruction of the restraint (Left) brackets. No recordable indications were detected. 03-007-SW-XR B8.20 Pressurizer West Limited accessibility due to 20 Support Bracket Lug the obstruction of the restraint (Right) brackets. No recordable indications were detected.
- 5. Burden Caused by Compliance To increase examination coverage on the subject welds requires removal of a massive component restraint, which would also require removal of pressurizer
Serial No. 10-189 MPS3 Request No: IR-2-54 Attachment 4, Page 4 of 7 safety valves and associated piping. Removal of the restraint is considered impractical due to the increased radiation exposure and impact to plant equipment.
- 6. Proposed Alternative and Basis for Use The subject welds received a surface examination utilizing the best available techniques on the accessible portions of welds to the extent practical.
Additionally, a visual (VT-2) examination was performed at the end of each refueling outage during the system leakage tests as required by Section Xl, Table IWB-2500-1, Category B-P. Based upon the surface examination coverage that was obtained with acceptable results and the visual (VT-2) examination performed each refueling outage, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.,
- 7. Duration of Proposed Alternative The relief is requested for the second 10-year inspection interval for Millstone Power Station Unit 3, which began on April 23, 1999 and ended April 22, 2009.
BOTTOM VIEW LOP VIEW REPERENC~oRAw~NGs:
*0. *OTIRMCJSL 2 5 0 I 004J4 SSWLEfl22 . 1 004-OOS 2 IIO4JSII.e ntAaflIflO-Oe-004C
- UOtJIt i*WflttIflZtC00001 co. 0. C
'CD- C")
CD
- - -"CD Co-.
z
-0,, 0
~"0Z w0.
B A III!I1S~ ~o A 00
-,4 4:, co
o ca S-w U) 0- a a) E IPRES-S4RIZER SAFETY WAV ASSY ETANTS
Serial No. 10-189 MPS3 Request No: IR-2-54 Attachment 4, Page 7 of 7
$oFe'y~
t(MLVIý rce""& -,,ý 4 wrp-41/c Attachment lug / weld orientation - (8) lugs typical welded on both sides
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 5 RELIEF REQUEST IR.-2-55 EXAMINATION CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MPS3 Request No, IR-2-55 Attachment 5, Page 1 of 4 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality
- 1. ASME Code Components Affected ASME Code Class: Code Class 2 Examination Category: C-A, Pressure Retaining Welds in Pressure Vessels Item Number: C1.20, Head Circumferential Welds Component Identification: Weld Number 03-073-008
- 2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No addenda
3. Applicable Code Requirement
ASME Section Xl, 1989 Edition, Category C-A requires volumetric examination of 100 percent of the weld length as defined in Table IWC-2500-1 and shown in Figure IWC 2500-1. The alternative requirements of ASME Section XI, Code Case N-460, approved for use in-Regulatory Guide 1.147 Rev. 15, allows credit for essentially 100 percent coverage of the welds provided greater than 90 percent of the required volume has been examined.
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100% volumetric examination coverage requirement of the subject welds due to the geometric configuration and permanent obstructions which limit the volumetric examination coverage that can be attained.
The "A" Residual Heat Removal Heat exchanger lower head to shell weld was, examined with a manual ultrasonic technique using the best technology available to achieve the maximum examination coverage practicable.
Serial No. 10-189 MPS3 Request No. IR-2-55 Attachment 5, Page 2 of 4 Due to the original design of the heat exchanger, the position of the inlet and outlet nozzle to shell reinforcing plates are in close proximity to the subject head to flange weld limiting the ultrasonic examination coverage from the shell side of the weld. Coverage calculations and limitation sketches are provided in this attachment. TABLE 1- Examination Category C-A Welds with Limited Volumetric Coverage Weld Code Configuration Comments Ultrasonic Identification Item Examination Number Coverage 03-073-008 Cl .20 "A"RHR Heat Exchanger Limited accessibility due to the 79.7 Lower Head to Shell Weld obstruction of the nozzle reinforcement plates. No recordable indications were detected.
- 5. Burden Caused by Compliance To increase examination coverage on the subject welds requires removal of the permanently welded reinforcing plates that are part of the original heat exchanger design or replacement of the heat exchanger with a design that would allow for complete examination coverage of the subject weld. This option to meet the 100 percent code examination requirement is considered impractical due to the cost, increased radiation exposure and impact to plant equipment.
- 6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination utilizing the best available techniques on the accessible portions of welds to the extent practical. Additionally, a visual (VT-2) examination is performed during each inspection period during the system leakage tests as required by Section Xl, Table IWC-2500-1, Category C-H.
Based upon the examination volumes that were attained with acceptable results along with the visual (VT-2) examination performed each inspection period, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.
- 7. Duration of Proposed Alternative The relief is requested for the second 10-year inspection interval for Millstone Power Station Unit 3, which began on April 23, 1999 and ended April 22, 2009.
- 0) 0Z z~
Co 0-a, vIA~~ i*OETAS$0. 410 REF DRAWINGS VENOOR aOAT 5495 REV.0-3
- 1. LES
Serial No. 10-189 MPS3 Request No. IR-2-55 Attachment 5, Page 4 of 4 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant /A1LL*'ToK3E Unit 3 AWONumber / -- \LA3 . System 94.s , Percentage of Area Examined 1 q. Component ID 03 -_Q0* -00?) Examination Data Sheet # Component Description .AEu -. m-ý'O0. e- OSAtA Calibration Data Sheet # Procedure No. m.9-)T(-- . Rev 0 Page_ _ of Calculation Type Surface El Volumetric., Coverage Calculation I Equation I/Sketch Area
\ /1
,,, 5 AKIAL S LOWFL."E'0O 5WE (21 ot'%AL'jot0A/.
14 cleC 5CAIJ 5"7Ak.L s'5 cb/cF 59,q 1.1 Examiner comments )( we- ie . ý,A ismcjtý 6o _s"E.UL mp tS E -- r~OWT 617 I ~ ~FA'A~Fr~ CI~) Lc~a~&~c.~ ~ni~J or'.~ 'JES5tL -TTL CrA#1 iJAj4IrA1Of\3IS
-7 0t.L 1:~I t L V)A\JE EKAAA ,041 IAF.Ab E9A-rý, nCAJO05ýQf OPTA1A'UOA C0VUieA_-r , 00 AtzrAnjrUA4L_ .1ZojTeAGV_
Pý01-b VMZW 76L- E"/4I
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 6 RELIEF REQUEST IR-2-56 EXAMINATION CATEGORY C-C INTEGRAL ATTACHMENTS OF VESSELS, PIPING. PUMPS, AND VALVES I/ DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MPS3 Request No. IR-2-56 Attachment 6, Page 1 of 4 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality
- 1. ASME Code Components Affected ASME Code Class: Code Class 2 Examination Category: C-C, Integral Attachments of Vessels, Piping, Pumps, and Valves Item Numbers: C3.20, Piping Component Identification: RHS-4-PSR052 pipe support lug attachment welds within the Residual Heat Removal System (RHS)
- 2. Applicable Code Addition and Addenda ASME Section XI, 1989 Edition, No addenda
3. Applicable Code Requirement
ASME Section Xl, 1989 Edition, Examination Category C-C requires surface examination of essentially 100 percent of the weld length as defined in Table IWB-2500-1 and shown in Figure IWB 2500-5 for the subject welds. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in.Regulatory Guide 1.147 Rev. 15, allows credit for essentially 100 percent coverage of the welds provided greater than 90 percent of the required surface has been examined.
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100% surface examination coverage requirement of the subject welds due to the geometric configuration and permanent obstructions caused by the pipe support members, which limit the surface examination coverage that can be attained.
The surface examination of the subject welds were performed to the maximum extent practicable with the limitations caused by obstruction of the permanently welded support members and the physical location of the pipe in close proximity to a permanent building wall structure.
Serial No. 10-189 MPS3 Request No. IR-2-56 Attachment 6, Page 2 of 4 The subject attachment welds consist of a set of welds for eight lugs welded to RHS piping pressure boundary to restrict pipe support clamp movement. There are four welded lugs located on each side of the clamp. Each lug is welded on three sides. The examination of the attachment welds for these eight lugs is restricted because access to the welds is limited by permanently welded structural support members and the location of a permanent building wall. The welds associated with four of the eight lugs are completely inaccessible for examination due to the physical location of the support members on the top and bottom of the pipe and the location of the pipe in close proximity to a building wall which prohibits access to one side of the pipe. The welds associated with the remaining four lugs are restricted from examination on one of the three welded sides due to the permanent support members located on the top and bottom of the pipe that abuts these welds. This limits the coverage on each of these four welded lugs to 66 percent each. The aggregate coverage calculated for the set of eight lugs was 33 percent. The support design drawing is attached for reference. TABLE 1- Examination Category C-C Welds with Limited Volumetric Coverage Identification Code Configuration Comments Ultrasonic Number Item Examination Number Coverage _N) RHS-4-PSR052 B8.20 Set of (8) piping lug Limited examination due to the 33 attachment welds for obstruction caused-by the support RHS-4-PSR052 permanent support members and building wall. No recordable indications were detected.
- 5. Burden Caused by Compliance To increase the examination coverage on the subject welds requires removal of the permanent support members by physically cutting the support members apart and replacing the support members by rewelding following the completion of the surface examination. Removal of the permanently welded support members is considered to be impractical based on the increased radiation exposure and impact to plant equipment.
1, Serial No. 10-189 MPS3 Request No. IR-2-56 Attachment 6, Page 3 of 4
- 6. Proposed Alternative and Basis for Use The subject welds received a surface examination utilizing the best available techniques on the accessible portions of welds to the extent practical.
Additionally, a visual (VT-2) examination is performed each inspection period on the piping during the system leakage tests as required by Section Xl, Table IWB-2500-1, Category C-H. Based upon the surface examination coverage that was attained with acceptable results and the visual (VT-2) examination performed each inspection period, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance"of structural integrity of the subject welds.
- 7. Duration of Proposed Alternative The relief is requested for the second 10-year inspection interval for Millstone Power Station Unit 3, which began on April 23, 1999 and ended April 22, 2009.
STRESS J PIPE MOVEMENT COLD TO HOT (IN.) HYDROTEST LOAD CALC NO.-REV.(PTN.NC) jV7-q*NOW 47102Z4 +0.05 I I,
+0,.OI Il~ o.
"0.0
.0 LS I CALLED NORTH (1i4o) L -
CONC C x.5T) q--
-CL EL Il :
ICmotLD 1N-5ERTS (EX(51; LOCATiO', PLAN
- {(EP- 71P .G-15) 4-2 4l
-i r 3>
NOTES:
-:;It- I'I-(2 ý'/ -- 1 I. SCALE: I1'0-1 UOS.
V.StECTION. Z. FOR GENERAL NOTES AND REFERENCE DRAWINGS. SEE 12179-BZ- 718 -3 3 W/ELD FOR- IrEfr8 To5 (TYR) 27 INSULAZI3ON7 (TYP) -- MARK NO. -RHS-4-PbRO.a 0 A NUCLEAR SAFETY RELATED
ýwl~.~~7 QA CAT I PLAN .- 7* *(.p-) " "NRTHEAST NUCLEAR ENERGY COMPANY LOADJING SUPPORT LOADS CS." -NORTHEAST , UTILITIE.'
C OND~ITrI ON' x(LBS) WFv (LN.S)jFz(LBS) IýMx(FT-LBS) Mz(FT-LBS; MFTLS SEE 6 ozLo o; /* P * .... MILLSTONE NUCt EAR POWER P NORMAL/UPSET
- I -20 +-5s73 zI m ,,-
- a..1 115 - I-Im ECHr~O~oR~ iw-0 -_ E
.s ~n~RESIDUAL
, STATION-UNIT NO. 3
ýIE5 REMOVw Ppc..
AII FAULTED -' + 979 [o 2 Il*frl5-B.-7Ble,-)- T= . .- I ÷I -
\..lj:
*-PIPE SUPPORT DETAILS
!
- i i CID IKI THE INFORMATION ON THIS DRAWING MRAYNOT BE
~I~j ,I0I COPIED OR USED FOR OTHER THAN THE CONSTRUCTION MAINTENANCE OR REPAIR OF THE PLANT FACILITY DESCRIBED IN THE TITLE BLOCK SAROS 4 1 LEVCLS WOKP STONE ý' WEB3TER BOSTON, ENG;NEERING MASS. CORP, I . SHEET O.S-F OF a 2. 2 CD-I CDf cl) DESIGNED-Y BAB DRA.Itl Cl *SOI C-*ft AN DANK CIK* 81 BA13 CD A' 0m CIO z (a 0 CD 0p
,0
.4.0)
Th
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 7 RELIEF REQUEST IR-2-57 EXAMINATION CATEGORY C-F-1 PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL HIGH ALLOY PIPING DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 1 of 40 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
-- Inservice Inspection Impracticality
- 1. ASME Code Components Affected ASME Code Class: Code Class 2 Examination Category: C-F-i, Pressure Retaining Welds in Austenitic Stainless Steel High Alloy Piping Item Number: C5.1 1, Piping Welds > 3/8 in. Nominal Wall Thickness for Piping > NPS 4 in. - Circumferential welds C5.21, Piping Welds > 1/5 in. Nominal Wall Thickness for Piping > NPS 2in. and < 4 in. - Circumferential welds Component Identification: Listed in Table 1
- 2. Applicable Code Addition and Addenda ASME Section Xl 1989 Edition, No Addenda Austenitic piping welds with single side access subject to ultrasonic examination with Supplement 2 of Appendix VIII to the 1995 Edition with 1996 Addenda of ASME Section Xl.
3. Applicable Code Requirement
ASME Section Xl, 1989 Edition, Examination Category C-F-1 requires 100 percent volumetric examination coverage for circumferential piping welds as defined in Table IWC-2500-1 and shown in Figure IWC-2500-7. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147 Rev. 15, allows credit for essentially 100 percent coverage of the weld provided greater than 90 percent of the required volume has been examined. 10 CFR 50.55a(b)(2)(xv)(A), requires the following 'examination coverage criteria when applying Supplement 2 to Appendix VIII:
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 2 of 40 (1) Piping must be examined in two axial directions and when examination in the circumferential direction is required, the circumferential examination must be performed in two directions, provided access is available. (2) Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic wAelds. Where examination from both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single sided Appendix VIII demonstration using flaws on the opposite side of the weld. 10 CFR 50.55a(b)(2)(xvi)(B), requires that examinations performed from one side of a ferritic or stainless steel pipe weld must be conducted with equipment, procedures, and personnel that have demonstrated proficiency with single side examinations. To demonstrate equivalency to the two sided examinations, the demonstration must be performed to the requirements of Appendix VIII as modified by this paragraph and §50.55a(b)(2)(xv)(A).
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the essentially 100%
volumetric examination coverage requirement for austenitic piping welds with single side access. There are currently no Performance Demonstration Initiative (PDI) qualified single side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic piping welds. Current technology, is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to US nuclear applications. PDI Performance Demonstration Qualification Summary (PDQS) certificates for austenitic piping list the limitation that single side examination is performed on a best effort basis. The best effort qualification is provided in place of a complete single side qualification to demonstrate that the examiners qualification and the subsequent weld examination is based on application of the best available technology. When the examination area is limited to one side of an austenitic weld, examination coverage does not comply with 10 CFR 50.55a(b)(2)(xv)(A) and proficiency demonstrations do not comply with 10 CFR 50.55a(b)(2)(xvi)(B) and full coverage credit may not be claimed. Based on the configuration limited to single side access, relief is requested for complying with the essentially 100 percent required examination coverage for the following piping welds listed in Table 1. The subject piping welds are located Within the Chemical and Volume Control (CHS), Quench Spray (QSS), Residual Heat
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 3 of 40 Removal (RHS), Containment Recirculation Spray (RSS), High Pressure Safety Injection (SIH) and Low Pressure Safety Injection (SIL) systems. Note that examination coverage listed is that attained during examination with no credit taken for the far side of each weld in which examination from that side could not be performed. Limitation sketches are provided in this attachment. Table 1- Limited Examination Category C-F-i, Pressure Retaining Welds in Austenitic Stainless Steel High Alloy Piping Weld Number Code Item Configuration Limitation and Results Ultrasonic Number Examination Coverage CHS-30-1 1-SW-E C5.1 1 6 " Pipe-To-Flange Examination limited to the pipe side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. CHS-30-12-SW-B C5.1 1 6" Pipe-To-Flange Examination limited to the pipe side only 49.5 due to taper of the flange within close proximity of the weld. No recordable indications identified. CHS-30-12-SW-C C5.11 6" Flange-To-Pipe Examination limited to the pipe side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. CHS-30-13-SW-B C5.1 1 6" Flange-To-Elbow Examination limited to the pipe side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. CHS-507-1 0-SW- C5.21 4" Elbow-to-Tee Axial Scan limited to 64.7 percent and circ 72.5 1:1 scan limited to 83 percent on the elbow side due to restriction caused by the intrados of the elbow. Axial scan limited to 62.4 percent and circ scan limited to 80 percent on the tee side due to the restriction caused by branch of the tee. Total combined coverage of 72.5 percent. No recordable indications identified. CHS-507-FW-19 C5.21 4" Pipe-to-Valve Examination limited to the pipe side only 46 due to taper of the valve within close proximity of the weld. No recordable indications identified. QSS-3-4-SW-K C5.11 12" Pipe-To-Flange Examination limited to the pipe side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. QSS-3-FW-5BR C5.1 1 12" Flange-To-Pipe Examination limited to the pipe side only 44 due to taper of the flange within. close proximity of the weld. Additional limitation due to welded support
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 4 of 40 Weld Number Code Item Configuration Limitation and Results Ultrasonic Number Examination Coverage (%) that limits the pipe side axial scan to 72 percent. No recordable indications identified. QSS-6-3-SW-D C5.11 14" Pipe-To-Flange Examination limited to the pipe side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. QSS-6-4-SW-B C5.11 14" Flange-To-Elbow Examination limited to the elbow side only 50 due to taper of the flange within close proximity of the weld. No recordable indications.identified. QSS-6-4-SW-D C5.11 14" Pipe-To-Flange Examination limited to the pipe side only -48.5 due to taper of the flange within close proximity of the weld. Additional limitation. due to a weldolet on the pipe side of the weld limiting the pipe side axial scan to 96.5 percent and circ scan to 97.5 percent. No recordable indications identified. __ *_ .... __ RHS-501-FW-6 C5.1 1 12" Valve-To-Pipe Examination limited to the pipe side only -50 due to taper of the valve within close proximity of the weld. No recordable indications identified. RHS-502-FW-7 C5.1 1 12" Valve-To-Pipe Examination limited to the pipe side only 50 due to taper of the valve within close proximity of the weld. No recordable indications identified. RHS-6-2-SW-K C5.11 14" Pipe-To-Flange Examination limited to the pipe side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. RHS-6-FW-4 C5.11 14" Pipe-To-Pump Examination limited to the pipe side only 50:- Nozzle due to taper of the nozzle within close proximity of the weld. No recordable indications identified. RSS-1 1-2-SW-B C5.11 16" Flange-To-Elbow Examination limited to the elbow side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. RSS-1 SW-B C5.11 12" Flange-To-Pipe Examination limited to the pipe side only 49.5 due to taper of the flange within close proximity of the weld. No recordable indications identified. RSS-1 5-3-SW-B C5.11 12" Valve-To-Pipe Examination limited to the pipe side only 50 due to taper of the valve within close proximity of the weld. No recordable indications identified. RSS-16-2-SW-B C5.11 12" Valve-To-Pipe Examination limited to the pipe side only 50 due to taper of the valve within close proximity of the weld. No recordable indications identified.
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 5 of 40 Weld Number Code Item Configuration Limitation and Results Ultrasonic Number Examination Coverage (%) RSS-19-4-SW-G C5.11 16" Reducer-To- Examination limited to the reducer side 48.5 Nozzle only due to the taper of the nozzle in close proximity of the weld. Additional limitation caused by a weldolet on the reducer side of the weld limiting the axial to 94 percent. No recordable indications identified. RSS-21-4-SW-G C5.11 16" Reducer-To- Examination limited to the reducer side 49 Flange only due to taper of the flange within close proximity of the weld. Additional limitation caused by a weldolet on the reducer side of the weld limiting the axial to 96 percent. No recordable indications identified. RSS-8-2-SW-R C5.11 16" Flange-To-Elbow Examination limited to the elbow side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. SIH-12-3-SW-C C5.11 6" Pipe-To-Flange Examination limited to the pipe side only 49.5 due to taper of the flange within close proximity of the weld. No recordable indications identified. SIH-12-FW-3 C5.11 6" Pipe-To-Valve Examination limited to the pipe side only 50 due to taper of the valve within close proximity of the weld. No recordable indications identified. SIH-4-3-SW-B C5.21 4" Flange-to-Pipe Examination limited to the pipe side only 41 due to taper of the flange within close proximity of the weld. No recordable indications identified. SIL-1 1-FW-3 C5.11 8" Valve-To-Pipe Examination limited to the pipe side only 50 due to taper of the valve within close proximity of the weld. No recordable indications identified. SIL-152A-FW-1 C5.11 24" Flange-To-Pipe Examination limited to the pipe side only 50 due to taper of the flange within close proximity of the weld. No recordable indications identified. SIL-25-FW-1-5M C5.11 8" Pipe-To-Tee Axial scan limited to elbow side only due to 75 the taper of the tee within close proximity of'the weld. Circumferential scan performed on both the elbow and tee side. No recordable indications identified. SIL-25-FW-1-8M C5.11 8" Pipe-To-Tee Axial scan limited to elbow side only due to 75 the taper of the tee within close proximity of the weld. Circumferential scan performed on both the elbow and tee side. No recordable indications identified.
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 6 of 40 Weld Number Code Item Configuration Limitation and Results Ultrasonic Number Examination, Coverage (%) SIL-25-FW-2. C5.11 8" Valve-To-Pipe Examination limited to the pipe side only 45 due to taper of the valve within close proximity of the weld. Additional limitation due to a weldolet on the pipe side of the weld limiting the pipe side axial scan to 90 percent and circ scan to 90 percent. No recordable indications identified. SIL-25-FW-3 C5.11 8" Valve-To-Pipe Examination limited to the pipe side only 50 due to taper of the valve within close proximity of the weld. No recordable indications identified. SIL-40-FW-1 C5.11 6" Valve-To-Pipe Examination limited to the pipe side only 50 due to taper of the valve within close proximity of the weld. Recordable indications identified and evaluated as acceptable ID Geometry. SIL-9-FW-1 C15.11 6" Pipe-To-Valve Examination limited to the pipe side only 50 due to taper of the valve within close proximity of the weld. No recordable indications identified.
- 5. Burden Caused by Compliance Compliance with code requirements requires extensive modification or replacement of components with a design that allows examination from both sides of the weld.
This option to meet the required 100 percent volume examination coverage is considered impractical based on the cost, additional radiation exposure and impact to plant equipment.
- 6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination to the maximum extent practical utilizing the best available techniques, as qualified through the Performance Demonstration Initiative (PDI) for Supplement 2 with demonstrated best effort for single sided examination, from the accessible side of the weld.
Additionally, a visual (VT-2) examination is performed each inspection period during the system leakage tests as required by Section Xl, Table IWC-2500-1, Category C-H. Based on the volumetric examination coverage attained with acceptable results and the visual (VT-2) examination performed each inspection period, it is reasonable to conclude that service induced degradation would be detected. Therefore, these
Serial No. 10-189 IMPS3 Request No. IR-2-57 Attachment 7, Page 7 of 40 proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject welds.
- 7. Period for Which Relief is Requested The relief is requested for examinations performed during the second 10-year inspection interval for Millstone Power Station Unit 3, which began on April 23, 1999 and ended April 22, 2009.
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 8 of 40 ATrAHET MR.tI~Tk3nt WO Number AAIl-a -Q-1 Sy-Atei .4, e_ Peirc-nge of Arealbcamined 5 -eompooent. I- reu.- ,o..iI e- A.. Examdnaffannata.8beet#" -~-'~
.CornporteatDescnption falirP~ Washed# k
*PcdurN~Ac~d--ROtV 0 14g : of '
"--CeIutavw~TYpe awfaceD0 volametIw _______________
'PIPE 5VECVC 5-V VLAjpE7,11 AXA !$,4AP 0 a .
~x$.fsranfl IAAAI-&M~ ~ftAd SID% OWý tl.-.1 TO IWP.
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 9 of 40 SATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant A, I L T1- N -rE Unit 3 AWONumber M3-v0.-113c1'9O System -r P 4 7 u) t 3 Percentage of Area Examined A9. 50 '/. ComponentlD_ . . ExamlnalionDataSheet# 3 \1 -o-\94 Component Description
- Calibration Data Sheet # 2t\k - \
-C)* t Procedure No.E -,A-4bt-u-r-* Rev 0 Page _ _ of 4 Calculation Type Surface Li Volumetric 21 Coverage Calculation I Equation I Sketch Area PjES\OC CIVCc SjCAv4 l -5;D 02Ci ',5, Ct"AZ,&[
Examiner Comments vXtAAA c-,&r, >4 j- -~~T (z -A4AA s r M Em
\ANG I.
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 10 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant ,,.LLV-o:.E. Unit 3 AWONumber A..-(- \'..090 System , , . Z C"JF .9 5 Percentage of Area Examined 50-1. Component ID ,
- Examination Data Sheet # 'I.. &in -- k 0 Component Description y- roc- r -- 1yE Calibration Data Sheet # * . - \- '0 Procedure No.rjLAA M!c-jr-,Aoi Rev a Page . of '
Calculation Type Surface [] Volumetric M Coverage Calculation i Equation I Sketch Area
ý:ýAoc,)E -SktE C:(lC S o'h V:9.
L c t- AQ .AL51$LAIA 0J i%CCF E51t -CEtvct< 010 Examiner Comments ~ ~ ~ ~ ~ -nV-KA~
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 11 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant Mbp. Unit 3 AWO Number .,A3-OU-o 3 o'io System C 7 7oS Q 3- Percentage of Area Examined 0 ComponentID r- 5 *3o-*-*,J -. % Examination Data Sheet# ) k \ - k . Component Description XLA0CE- -EpG0 Calibration Data Sheet## \\- 0 \- V l Procedure No. E*A-t'-*T-'- Rev Page 4 of _ _ Calculation Type Surface [] Volumetric [ _ Coverage Calculation / Equation I Sketch Area V0 L0 AI
?IEf'E $iDE CAIC AL ,CA" O,
.C .'.A5,AA 0 /.
E jr A cýuC A W Examiner Comments .,, sto P19E 4ý,,r o-ýq 3L) "TO " LAt&E
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 12 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET MLLSTot)E Plant AA Unit AWONumber AA. -- O.a.9' System, c 45 Percentage of Area Examined 7"9. 5'. Component ID C 44s -ri-i6 Os -t (. Examination Data Sheet # Componernt.Description F-L-2t )-TSE . Calibration Data Sheet # Procedure No. M P-.t'- -z, Rev 0. Page ? of _ _ Calculation Type Surface [] - Volumetric Coverage Calculation I Eguatlon Sketch Area (,7L. J!1V L EL~ioI.w A~iAL zsAl-i Prip? 5 b E Lv7* L
%ITI(" " -y '1, 04 O 3 ,L ^cc,.*"JT FOC ,JS UMtTAT(OO = 64,.7 7.
lu L-TI PIN-'i " " 1,?' ' 201t MO A(Cd.kJ T VoC b:5 UAAI rAT O?*) x/. .q c24-C "cAO TL.EP 5%b. WIM- (.AIJ Lk-IMTAT1ON) zo '.
ýTTAL COQEIVV &CJ -ý ti~ ý- ý ExamlnerComments :Sr FVAAA IýATA SM7r-- F S L.At.J ATIOM0 oAt'A, AO U/iA
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 13 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant M1 LL-$'KO)Jr Unit -S AWONuMber System H5 Percentage of Area Examined. Component ID e_!US_-5i-I" F0-tq Examination Data Sheet # Component Description PFPE- \jAL.jE Calibration Data Sheet # Procedure No./MfP- ' -; Rev 0 Page 6 of 6 Calculation Type. Surface El - Volumetricw Coverage Calculation I Equatlon I Sketch -Area
'Q AL\J AXIAL :CAO PIP'E .51C (-70'L) V A)(tAL .CA" \JALV_ St1bE (.6*1-) Olt
-T-orAL Co~Jfc,.E--*,q *6 -H
*2-~ 4'g °/,
Examlner'Comments .4 1 A
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 14 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant ,MtLLsrobE Unit 3 AWONumber J System Q*S, zoiOý 9-7 Percentage of Area Examined -- 'I, Component ID (sS-3---,LZ--K. Examination Data Sheet# 3, --- -4, Component.Descriptlon _.9AE- Ot G: Calibration Data Sheet# .-LA i . Procedure Nom ?-,PiT- T-. Revcc-x*L.. Page L of G Calculation Type Surface E] - Volumete.o Coveiap!e Calculation ! Equation ISketch -Area
~LO QI'$ S, ,,,. .
01')T ckAcG SrA.0 too1. u?,5*r AI£C.A SC.AN : 00t
^X>~ t 5CAWJ0
" A-X*. kA0I- Sc -wO Tcr* 14 .... z Examiner Comments V'IAM Nr
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 15 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant A16LSTOINŽE Unit. 3 AWONumber M~-()-o\Y3aLý) System QS.S /2Z0,or 9-7 Percentage of Area Examined 14 J4 Component ID ( "- ,-%-'--? Examination DataSheet # .30q-b(2 F-j" Component.Descriptlon \JALuf_ - 'p C,, calibration Data Sheet # 30 -O I- t8" Procedure NoAP--fb-,T-o - Revcob-ýOa Page 5 of S Calculation Type Surface [] Volumetric Covetage Calculation I Equation fISketchArea T. N* .C. ,.$CA0 100'L rjt,3s AytA Sc~w -7 7 Y AO',AL, -{ L t. "Gr, . " .) or... 0FO1>r, 5 .O, A %A E~~~UAL5'P4n 7ý.VAAI~rCG\EIk3~ Examiner Comments ~EAA4 ýK wrý, - L VLAkCv Q~ ~.~ A~XIAL 5-CAM ~~~r TZ)4> 9 AOJt 3.d'
-Mi -.1.~ N)r f F~b~t 19 "
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 16 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant j.m%,t ,-ro- z Unit 3 AWO Number A A--.I - System S/ zo,'ic orU Percentage of Area Examined EoL ComponentID , -..- .*-r> Examination Data Sheet# 3 01
-1 Component Description PIer- V
-A WG Calibration Data Sheet##1 ' *- _.X5 Procedure No.c(.AArb.Qu'r-so-- Rev . Page 4 of M Calculation Type Surface D2 Volumetric 3 Coverage Calculation I Equation I Sketch Area ct70.
'70 '~ J 7ý--rJGC, $A\t~ AYIlAk- 5C-ArJc) ancCm ts- CoJECA&,. -L Li "O ,
Examiner Comments tjri ý2CAJ 'Vehv¶ ocn~ TL-0C-C~f6.)ATko',J-.
Serial No. 1'0-189 MPS3 Request No. IR-2-57 Attachment 7, Page 17 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant m;%-L.5Tp Ioso E" Unit 3 AWO Number .M .'5 - C1..* System Q 55./':o -,4 . Percentage of Area Examined 50*4 Component ID S-.,-H-,' -B Examination Data Sheet# ( .%*=o\-11 q Component Description qLkc.F - Calibration Data Sheet# l -oi 1-2 ProcedureNo.EgAA-.b-ki-i*-*o* Rev 0 Page of Calculation Type Surface [] Volumetric coverage Calculation I Equation ' Sketch Area V LA IQ G C EL(ýOk stý5 F l JZV_ $CAIJ O0"L, TuoA\. COtJZ7 9A&V 1*'a0oA, Examiner Comments _,j _ZAj Q~ EL~m.)& .>t:>E W . p.ira-xcA~t ( -AYAL SIZA J PEýA,'IrtOeSsýMV-bI . a.M"~ lS ~dL (I~ 5eCAFKS. .
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 18 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant ALL!'* .... Unit_. AWONumber M,..CA- ? Z0:5 System q iýs Percentage of Area Examined 4 " Component ID . ..5s-(4--- 60 Examination Data Sheet# 31o-011 -kt. Component Description POiP- 7LAKJ&E Calibration Data Sheet#0 31 k:Lt, Procedure No.;r9-AA-.Wp.,bJr-.0-. Rev o Page L4 of '- Calculation Type Surface fl Volumetric _ Coverage Calculation I Equation I Sketch Area kj C XJL ~ETr
\ 1 ",,, /
\ / -,-.
T!1-AVGE:Sll>'t Pl~,IJý ACLIA S%%>ECtLr Z '5l,:.(.A"J
¶SCA- (.'
r,1-bAK)(, 5itD AAlAL l4 O-1
-T-TA,, CoJE*4-A -q -
Examiner Comments P C 'Y W TQLLTX 9XtYQkCTk.& (,0 <' -7 A~r tAL, 'eArJ.Aw5 WDD-JQGI MA~1)E kl'-.-15" - Kt, CEAA'A E&-O FLA'I'J& :sipO t>:-
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 19 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant/vM bS'tTOt*L Unit 2, AWO Number________________ System .. S Percentage of Area Examined 50 0 Component ID (-P$ - .
- t: -& n Examination Data Sheet # ,V'.4 Component Description *J A_\JU-'P\* Calibration Data Sheet#
Procedure No..AP *-'-.. Rev 0o0 -O Page / of.J . Calculation TyPe Surface [1 Volumetric Coverage Calculation I Equation I Sketch Area
\J A L\ PS.
VýJE 5tb-E: C\ZC. --.-.At,) *0 PjAk.xE t CiQcg . "5C.AO ' C"o
'IJ A\,.J7 '>%% ",t.. Aý AL- "5*CAr 0 '[
ExaminerComments 'L- 5-AAe "*3 IJ \AL\)J' G U(ZATO*J , U,\ -V ,
)-"I-A\ l~ r-kpAA PQV\J%)J'5 IfCAA' rýTIA AA f-b '*3tS XAtAr pt ~\WXk CAL JL)ýATNOQ- .. JA-ý QN-AJk V-Q PP-FCJUý CY.AAA S)AX(A Qt-3 11i 5*
Serial'No./10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 20 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant ,ll bL.KJ'*, Unit
- AWO Number_ ___ ___
System IZ*.\ Percentage of Area Examined )" Component ID f5 -,.J-- Examination Data Sheet# ,__/4_ _ _ Component Description ,JAL/\j - P i P Calibration Data Sheet # -- ' Procedure No. A -M.T- - Rev _ -X)
-OC Page LI of JI Calculation Type Surface [ Volumetric M Coverage Calculation I Equation I Sketch Area
. f* 5.cAr \OC"L
\JALV"\JC $b ck $(A'S J "
\JAL'"JC AY-kAL "CA, C)
C
-,,CCTAX :o"Jg&\.E - ".,. I5O' Examiner Comments S pF!- Ej(AAAM d'r 5 'A
\J U CC- C,- a AT I QL kATA O ,rTA Wkt "4A1 .2 Q F
_L3/4-0AA 4..) , AAA N ,.rI- - U-( k %-_"A.M A'-T"A U _.__O*2- C\-*S AL-C OLA'\k ,J " ,2 "IlJt) QA
,)t', \(15t)s[ .
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 21 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant M Lk 7- O Unit, 73 AWONumber AA.1-O1- -\3 -. System Percentage of Area Examined SYI Component ID'QtA,- (Q, -. 'A - - Examination Data Sheet #if, ,3 1q Component Description . - E AL&__ Calibration Data Sheet # q 13q Procedure No.P-i::.TT- - RevQ:3C--1 Page
- of 5 Calculation Type Surface E] Volumetric. _.
Coverage Calculation I EquaitonSketch -Area
,9f AXIAL- 5eA"3 O"/,
t>05'1' AXIAL- S5CAN3 07 4V'AZ ~h Examiner Comments A ,
-,, &,:"ý, ,._, N I~.,n ~OYfl ~ l.a n,. .roar I-) &=,.ý Lau -- 642-2 t-y L- 0 2::= !:--- -112
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 22 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant AA--,"o*.... Unit 3 AWONumber ,AA,,'?-(0t k 3- ;D System 9LOS Percentage of Area Examined *b 1. Component ID, Examination Data Sheet##L& 309 Component Description I 1 - \LM P Calibration Data Sheet # ( 0 '-0 I4) Procedure NoJM 9P-ftiT-OT- ý- Rev 000 -01 Page 5 of, Calculation Type Surface E] Volumetric: Coverage Calculation I Equation I Sketch Area u,,st" AcIAL 5(CA*J IO0 *[ r)NJST ci,*C NrJsr Aitý SCAN sc.AMJo too0 7 a T A t- .LAqO (
-toTAL-?q Examiner comments -t,0 '>(.AO~ (-io.m S~rPA)5tbEý riCtht~U~~~
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 23 of 40
./
ATTACH,MENT 1 COVERAGE CALCULATION DATA SHEET Plant -A4ILkA-STO7hE Unit 3 AWO Number AA_7*O7-Q 4 3H, A .. System -2.... Percentage of Area Examined "--! .Componenttl) S- '- xamlnalon Data Sheet4 #__- __oq_- _______ Component Description *.,& -
- Calibration Data -Sheet# ,0% I P4 ProcedureNo.MP-P r-U-J(-;*- Rlevcno-ýI Page S7. of S Calculation Type Surface [1Volumetric Coverage GalcUlatkrn /Eqgatlon tSketch -Area t)IJ'~ 5~'VC~kLC Z5C.-rJ \0 ups'Tr .'At-E AIXA,- 5C*A*0 Exomlner Comments o -A u#-Ir (>O t -M 9kAt',,3C-,r co' "o- '
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 24 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant . ILL L "OLSY Unit.iL. AWONumber kA . System q- /; o r 2 Percentage of Area Examined L4 -. 5 I Component ID b-s5 !>w.-
, ExaminahlDn Data Sheet# sj\N\.-
Component Description FL i . . E - Calibration Data Sheet # 3 t -O- X3$ Procedure No.,.¢ AA- i.Rev < Zujr- Page . of Calculation Type Surface 0 Volumetric [A Coverage Calculation / Equation I Sketch Area A,... C-0.(A &C t L( z Examiner Comments 1 jcL M ~lj F-~~ rC tJ TT) C otJ~uA1~
/
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 25 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET PlantA MI LLzSTOKýE Unit Z AWO Number M--. -o\- System ?,-SS Percentage of Area Examined 50 °1 .Component ID R -S *_,3- 1 Examination Data Sheet # 3J q - of - j-I , component Description ,4 A \I _- Calibration Data-Sheet # 30q -of -4 q-- Procedure No P-Pr'-uT- - Revo Page
- of S Calculation Type Surface E] Volumetric, Coverage Calculation 1Equation /.Sketch -Area i.1
*JP!%T~ AXAL AL, %AAI *3S A IAK. GctA' V-1_0 __ -
ExamlnerComments OJo E."A.M veo, \JAIi . .5 7n.
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 26 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant M_.L},STQK. Unit 3 AWO Number M 3-o 4- o0' t S System i & /
- ton Percentage of Area Examined _______o Component ID .ss-t - *. Examination Data Sheet#._t\-0*-
-3v Component Description \_ A Lu E PV Calibration Data Sheet# 3\X-O01 t3o Procedure No~c.A.*_, *. Rev - Page S of 5 Calculation Type Surface El Volumetric 0i Coverage Calculation I Equation I Sketch Area U 1-5 _rlll t SCA.J0
,, f *,,
$L AxIAL- SCAW 011,
*Jt" ::.S *I=.'T V S CAO0 0
bo v,3srA sttr AO c 0". It"-I - Examiner Comments Q~~6,R. f~~~\I.Y ~. i ~C,~O~~~ K
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 27 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant a.,iLS.TO:JE Unit 2 AWO NumblerM '-1'-*,04 M System ,,j, / 2 J, o' Percentage of Area Examined H Component ID Q:"5~*%'It-4 - Examination Data Sheet # * \ \- 3 Component Description v ouc!;g _tx v ..ý% - .E Calibration Data Sheet # X
\ -
Procedure No. -gA.t,"o.Rev o Page 4 of { Calculation Type Surface [] volumetridc' I Coverage Calculation I Equation I Sketch Area rLA 6 C. (eo"
*.asT ~
<-(* &cA-I~ (-0 EoJt - AYkAL - -AO o-1 Examiner Comments t~ t7/& VfiaA V"Out SIDE c W6UrT:IJ*'D(O~
A~kAL- SCAK3~ I AA 20-r Q-'.JtW 'SibE TxiUE -Mn WELbO,.A'T A rt3 - d f,
%Ž.(J415" CAK-3 - '.Y'*'
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 28 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant , ojLL*T0$. . Unit 23 AWO Number A.3 - oQ- o- *0 5" System ,5,5 / n _ o Percentage of Area ExamlnedC-t' . N9 491 ( Component ID 9 - -'SS - :Sv',- G Examination Data Sheet# 3\k\-ak- s33 Component Description Cyc.c&- L--, Calibration Data Sheet4f . -o \-. t3 Procedure NOE.-_tzc,.-U'>T-boa Rev o Page 5 of 5 Calculation Type Surface [i Volumetric [ _ Coverage Calculation I Equation.] Sketch Area VLA'L SAX\AtL !ýC-Ars -A~/ U ~MITI~t O AT Tt0 VO't Aw-
- sriTci-c~ -to A.oELoo T. -ToTAl.
'OA-4 44 1~~4=~~I 96-1. ,CLAW CQvJRA~at ArWC\A)~Co Examiner Comments k)cj s<,Av,) vizr)m htJ,-- TV Fi-AtJ&9- .
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 29 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant AAI.STOC 2 Unit 3 AWONumber ,AS-o<a.-O -7N-System
- _. E- ' oo Percentage of Area Examined, 50Q/,
Component ID .s,-. Examination Data Sheet# , 0o -c-.l 101 Component Description
- L, t C. a-. E Calibration Data Sheet # 3 %o--O - kO -
Procedure Nomp.9qzu- 0 T- a Rev ooo--0 3 Page ' of 6 Calculation Type Surlface l Volumetric 0 coverage Calculation I Equation I Sketch Area SL Ao vW FLAVJ&r- 751t) CQc 6CAW' FLAVJ&E st 'AYAL $CA- 0M C. TCOTtAL C0o~jIE9-A&-- L-4 a Examiner Comments on ,,_WrO 9LeSO& *AE T ,tp'U ýW%(U-An~
"-20" A-XIAL S<ALJ PEgT--*h-A - ýQV! VIPLE5M5,TAL- goanjlzAcE orf VA(ý- '$.b, 7-
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 30 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET plant .. Sto . Unit 3 AWO Number -M3- -o4- 0*-1 -z System --- k / oA,- o1 o Percentage of Area Examined L 1. S Component ID S 2.r - -o Examination Data Sheet# 3 *-oltoc Component Description
- rLAJ Calibration Data Sheet # 3 kI ok- %o1 Procedure No.[.-A-*.4>E-OT-,o Rev o Page ' of N Calculation Type Surface D Volumetric ,]
Coverage Calculation I Equation I Sketch Area ('? Slt A &FIA S Exa-mterm Snit AX IAL SC Ve. 1, cJ4Afl
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 31 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant.IL=L.5To~ Unit 3 \ AWO Number ,..O--oVqO) System f s 4zoj_ Q9c) Percentage of Area Examined 50"t Component ID 5 y4-i :x-F'j-3 Examination Data Sheet# ,M1- OC-U 1 Component Description JALV e~
-\r Calibration Data Sheet # 31 *o1 -0
- 1 Procedure No. _ Rev _ Page L of _4 Calculation Type Surface El Volumetric W1 Coverage Calculation I Equation I Sketch Area I,~~~ //_____
"-A'\'T.*u C IZC 5CAbWO
'Ar SýOC AXIAL'S.A 0, k lt- AL. - 5COýVAC X1 $CA tJ ý0 -4zS Examiner Comments K'ý6 ,SA 9(, AA \IAL r tc kSC O
-ToC0Q171 Lj
- ýJ .eAnrv
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 32 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant M tt-LS T ,) C7 Unit 3 AWONumber A'13.-O-p- j 3?, System Sig Percentage of Area Examined '41 ". Component ID l) iA-Lt - - . Examination Data Sheet # Component.Description W
-4" ý c r - P PE Calibration Data Sheet #
Procedure No..AA p-ar-g Rev of /0 . Calculation Type Surface [] Volumetric Coverage Calculation I Equation/ Sketch Area q6 (.' -7o0 cJPA~ CALIC,)A-rI.k 05$ýQ&~ !5CAO AK3GL5,0t' MAY, CO\WE7A&E7 SCA I-' -70" A- AICAP4 VIOM PIPC SIOS ~w S;rAN X. A)((Atý 6cAw irem FA#-&F SIDI SCAhW 3 CO- 61A*J FVOA PIP5 S~t~r-ScKAJqq CJ ZC A A<J JZ TLA0(rE tA SIO0-EalnALr COQmA6E q 411 1t Examinenr Commrents I
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 33 of 40 ATTACHMENT I1 COVERAGE CALCULATION DATA SHEET Plant A- I QLS
) E: Unit -5 AWO Num ueber.. ..
System SuL Percentage of Area Examined 570i° Component ID.5L-I I- FWJ -3 Examination Data Sheet# -. 'q Component.Description \,AL-'JE- P t*" Calibration Data.Shoet # ,,l),C. ' (P4 Procedure No.M_- F-*e-L - e-RYQ=-- Page . of 6 Calculation Type Surface E] Volumetric Coverage Calculation / Equation I Sketch -Area
',J~ ~~-kQ A ~ 'C ,E:
",JAL\JE. $tL>E c&Q*c "z$_.-A' OfJ P'I5 Stbý- AOC AL- SCAf M
\JALAJE.EIb*F AdIAL- ý5CAtj
., e "T~mAu q Too ¢q: o.-o,
* /
Exmi~mner Comments K)o -,A 00 V C VQ
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 34 of 40 Millstone Unit 3 Ultrasonic Examination Sketch Sheet Reference ID;:[1,-152A.Fw-1 Data Pkg.: f312-O1-00 I Page: I3 ."Iof i-.f Sketch Area p'pe UfSTA, Oz Sr~ I IOO/o 0 7 O DI,vsT Ab'alSa n- 670f rotsi CoU~te Scn 0o /0 Comments:
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 35 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEETp ,- Plant MiLLSTOMF- Unit. AWONumber M3-ýf-/-I7'72 System ,- iT Compoent I 1 Percentage of Area Examined 310-01-08/ ComponentlID ,5t L :,V Examination Data Sheet A# V _0= Component Description 21PPE To !<F5(F"-rT-F Calibration Data Sheet# 3/O6- 6)1 -[ OC Procedure No..AP- I-1IT-a3 Rev - Page 2 of Calculation Type Surface El Volumetric , Coverage Calculation I Equation ISketch Area UtPgT. CIRC SciAJS 106Y4 Dw ST'. C1 r S,- *As NS 1t),7 LLPsT-. Ax 8ciS Lo/ D?~-sT. AX SCANS 0 0. ToTAL- 0 r S<.Ats 300. Or P*vf100L - q40 '% T 3 OO 0 '
-15S% T67-AL C.40FMc2GE ACN(WIv )
Examiner Comments I-I4fcL/ s APA=. £ou'Fo% tA*J FEvy P/Evious IATA ,DfTEfV 512j1q< I
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 36 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET , Plant MiIIqTh'&NF. Unit AWONumber M,3.. u- -- I I'7'7 R . System fr ._MLi7?6-1 T-6'rg Percentage of Area Examined Component ID S I L.- @.-. -4 Examination Data Sheet## I, Component Description s "X g *s "TE. t-{io P, PE- Calibration Data Sheet 2 /1) - Q - £ g q7t Procedure NoMPIo-PDr.tV- I, Rev O0-03 Page .3 of 3 Calculation Type Surface [] yolumetric M] Coverage Calculation I Equation I Sketch Area UPST. CRC Sc-AI4S 00__ ONST C-11. SCAINS LLPST. AX SCAN5 00/0 Df1 ST. AX .SCAAIS' ThTAL 01 -qCANS . Q or PoSSI&1. LiOO% K, 30/70 -757P "r6r"AL .0u6RAGE AckMe)ieD ExamInerComments 7-HirI*woe
~:S 14&)"3
,*6 e,,,1)4-- I-M 1-'LI/. CAMI / e Ou gk,-,,'A PNIeKiIsS S
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 37 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant M* tTO 'l-- Unit 3 AWO Number System *, L Percentage of Area Examined q §5/o Component ID EL-S $ -[J -- Examination Data Sheet# Component Description El PE - -JAv.'J E' Calibration Data Sheet # Procedure No. AA P -(\T.-T- :2- Rev ox.*-c Page _ of Calculation Type Surface [] Volumetric Coverage Calculation I Equation I Sketch Area PI PE A PiPS tW$rt <:kC ScAr-i 1 PIKt -Wý AXIALý :5i.IJ '~Y'
*J.AL\J-C ">'bE CvC- 5,cAI (:)4
\)AAJF-.. -5t>, A\AL.<--CA-A" Examiner Comments A-Ex.Am UAAIrFW 5/g -z ~s Wi&ýLT'/).~
Tc~A r~-~r' ~ o5,c-3OýCW', C~-¶tTA 1(t~Y PEF-\Ei-(fA. I ,..or ~ .. ,rnfl,-t c~/-4 tACu
-,0- CACO ý;CAO
~r~\A~VAT\ X A-CA o1?YA'y-.51 'ýtAA PIMQ'J0-S ~AA C. (AýýrJý SI/-/95.
U-CT -(-AAAtbA1rAQ 2Toý- C2A&" AT-Oý) \JA', 1,)V- VW> ZEoAA PrZN\~) bATA T-0 ý,)/\L\jf- C0.,3ý--tGJeA'r10)-)'
,t-J ý-'~fs ci~ t~t ,XA ') T J L4
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 38 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant MV.LL-ý$TOý'.) Unit 3 AWO Number .*'- system ,__- Percentage of Area Examined .. _,______/._ Component ID ,0 - A :1 - , -5 Examination Data Sheet # ,,_l-t A), Component Description P?*, A- CJAJE Calibration Data Sheet # ti}/"r Procedure No. AnvP-*-xr - *- Rev ooo-o4 Page 4 of' Calculation Type Surface [] Volumetric _, Coverage Catculation I Equation I Sketch Area SP*P 'J.AL \J C k\PE 5>t:C C 1$CAt,4 kOO jIALUJEt 5 -E AAL- 5CAV ) C
"-TOt AALG-Examiner Comments 1- kt -, x-~(A-rV-ko r-.. . JP~c-RC5 ý 'AtA'ý
~~týQc:)AA 'PE',JioQ$ ~C(AAA tDATrA f~'5 J YAAA K)ATA Or,51-h 7Q q~K T-A7-W C A LCý)k A:Ekbr JA5 !tA Qj%)AA. ý&r-'JWUbý ;F(,A/0 Eý^-A Qt-J tot ~ (L~f~.
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 39 of 40 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant. MiLLS7zt'jF.- Unit _- _ AWONumber .2 -- V 2'- System : "L Percentage of Area Examined 7,55 2 Component ib '- Y% V~z'" j .... *'- Examination Data Sheet # , . Component Description VALqC- -n -f.i ?F_ Calibration Data Sheet # 3 0 ( -o / - Procedure No. .. kP.XT-,,L+ Rev c>o. c Page (0 Of Calculation Type Surface [] Volumetric 2* Coverage Calculation / Equation ISketch Area
,lTRd 6.¶'c ;2-L. -I" L ,
Examiner Comments
- i. 4cJ .. , C.-' . 5CAiJ
.. e*.+Cv-6 too 9?-7'D*-
Reviewers Comment: 50 percent coverage credited due to single sided exam
Serial No. 10-189 MPS3 Request No. IR-2-57 Attachment 7, Page 40 of 40 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant M,______- _____,. Unit d AWONumber Ol-l3\O System. S1.1 -..-- Percentage of Area Examined *' 0 / . .Component ID - - F'vJ- I Examination Data Sheet # 3,oj-0-4 /7 Component Description .Pip, - \v
. . At Calibration Dat.ht Ca..ra*o ., ,1.
Da / ?*""; Procedure No..4m PQI- UT7-- Rev00oc)-o0 Pao 3 of 3 Calculation Type Surface El Volumetro*l Coverag Cculatin I Eqution/ Sketth -Area Examiner Comments - 50010 CQIjQC8fe - Lhip-,Aý, -
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 8 RELIEF REQUEST IR-2-58 EXAMINATION CATEGORY F-A SUPPORTS DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MPS3 Request No. IR-2-58 Attachment 8, Page 1 of 3 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality
- 1. ASME Code Components Affected ASME Code Class: Code Class 1 Examination Category: F-A, Supports Item Numbers: F1.40, Supports Other than Piping Supports Component Identification: Reactor Vessel Supports, 3-RVS-1, 3-RVS-2, 3-RVS-3 and 3-RVS-4
- 2. Applicable Code Addition and Addenda ASME Section Xl, 1989 Edition, No addenda with the alternative requirements of Code Case N-491-2, approved for use in Reg. Guide 1.147 Revision 15.
3. Applicable Code Requirement
ASME Section Xl, Code Case N-491-2, Table 2500-1 requires that supports for other than piping are subject to a VT-3 visual examination once each inspection interval.
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from performing the visual examination of the subject supports to the extent required by code due to permanent obstruction caused by the reactor vessel insulation panels.
The Millstone reactor vessel has four supports located under two cold leg nozzles and two hot leg nozzles. The support assembly of each of these nozzles consists of a nozzle pad and steel plates positioned between a steel support structure that is welded to the neutron shield tank as shown in the figure in this attachment. The support is designed to act as a vertical restraint, loaded in compression so it is not subject to the typical failure mechanisms associated with stress at ridged connections and loosened fasteriers. The majority of each support is encased in permanent insulation panels of the reactor vessel and the reactor vessel nozzles. Only a portion (approximately 10%) of the end of each support is accessible for VT-3 visual examination.
Serial No. 10-189 MPS3 Request No. IR-2-58 Attachment 8, Page 2 of 3 The supports are located in a congested, confined space below the permanent refueling cavity seal ring. The area can only be accessed by entry through a seal ring hatch. In addition to the difficult access, the radiation levels are approximately 50mr per hour. It is estimated that the removal and reinstallation of the permanent insulation panels in this confined space would result in additional exposure of approximately 2 man-rem. Additionally, it is anticipated that modification and/or removal of the permanent cavity seal ring would be required to support access for this project. The reactor vessel support assembly drawing is attached.
- 5. Burden Caused by Compliance To increase the direct visual examination coverage of the subject supports requires removal of the reactor vessel insulation panels.
Removal of the reactor vessel insulation panels to meet the 100 percent code examination requirement is impractical due to the access restrictions, high radiation levels and support design.
- 6. Proposed Alternative and Basis for Use The subject supports received a VT-3 visual examination on the accessible portions to the maximum extent practical with the insulation in place. In addition, the insulation was examined for any evidence of disturbance or degradation which may be attributed to abnormal support disturbance.
Based on the visual examination coverage attained, the proposed alternative provides an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject supports.
- 7. Duration of Proposed Alternative The relief is requested for the second 10-year inspection interval for Millstone Power Station Unit 3, which began on April 23, 1999 and ended April 22, 2009.
- 8. Precedents A similar request for relief (IR-28) was approved for the first interval at Millstone Unit 3 by letter dated November 3, 1999, ADAMS Accession No. M993220119.
ce) Ic'j 0 (Y) 0'0 0-C6 cv) E Co) 01) SECTION A-A DETAIL A
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 9 RELIEF REQUEST IR-2-59 EXAMINATION CATEGORY R-A RISK INFORMED PIPING EXAMINATIONS DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 1 of 25 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
-- Inservice Inspection Impracticality
- 1. ASME Code Components Affected ASME Code Class: Code Class 1 Examination Category: R-A, Risk Informed Piping Examinations Item Number: R .1.1, Elements Subject to Thermal Fatigue R1.20, Elements Not Subject to a Damage Mechanism Component Identification: Listed in Table 1
- 2. Applicable Code Addition and Addenda ASME Section Xl 1989 Edition, No Addenda Austenitic piping welds with single side access subject to ultrasonic examination with Supplement 2 of Appendix VIII to the 1995 Edition with 1996 Addenda of ASME Section XI. /
3. Applicable Code Requirement
The examination requirements for Class 1 piping wel~ds are governed by the Risk Informed Inservice Inspection program that was approved by the NRC in a Safety Evaluation dated March12, 2002 (ADAMS Accession No. ML020570312). This program was developed in accordance with the Westinghouse Owners Group Topical Report WCAP-14572, Revision 1-NP-A. The WCAP Table 4.1-1, Examination Category R-A, Risk Informed Piping Examinations, requires 100 percent of the weld to be examined. The alternative requirements of ASME Section Xl, Code Case N-460, approved for use in Regulatory Guide 1.147 Rev. 15, allow credit for. essentially 100 percent coverage of the weld provided greater than 90 percent of the required volume has been examined. 10 CFR 50.55a(b)(2)(xv)(A), requires the following examination coverage when applying Supplement 2 to Appendix VIII' (1) Piping must be examined in two axial directions and when examination in the circumferential direction is required, the circumferential examination must be performed in two directions, provided access is available.
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 2 of 25 (2) Where examination from both sides is not possible, full coverage credit may be claimed from a single side for ferritic welds. Where examination from both sides is not possible on austenitic welds, full coverage credit from a single side may be claimed only after completing a successful single side Appendix VIII demonstration using flaws on the opposite side of the weld. 10 CFR 50.55a(b)(2)(xvi)(B), requires that examinations performed from one side of a stainless steel pipe weld must be conducted with equipment, procedures, and personnel that have demonstrated proficiency with single side examinations. To demonstrate equivalency to the two sided examinations, the demonstration must be performed to the requirements of Appendix VIII as modified by this paragraph and §50.55a(b)(2)(xv)(A).
- 4. Impracticality of Compliance Pursuant to 10 CFR 50.55a(g)(5)(iii), relief is requested from the 100 percent volumetric examination coverage requirement for austenitic piping welds with single side access.
There are currently no Performance Demonstration Initiative (PDI) qualified single side examination procedures that demonstrate equivalency to two-sided examination procedures on austenitic piping welds. Current technology is not capable of reliably detecting or sizing flaws on the far side of an austenitic weld for configurations common to US nuclear applications. PDI Performance Demonstration Qualification Summary (PDQS) certificates for austenitic piping list the limitation that single side examination is performed on a best effort basis. The best effort qualification is provided in place of a complete single side qualification to demonstrate that the examiners qualification and the subsequent weld examination is based on application of the best available technology. When the examination area is limited to one side of an austenitic weld, examination coverage does not comply with 10 CFR 50.55a(b)(2)(xv)(A) and proficiency demonstrations do not comply with 10 CFR 50.55a(b)(2)(xvi)(B) and full coverage credit may not be claimed. Based on the configuration limited to single side access, relief is requested on
,complying with the 100 percent required examination coverage for the piping welds listed in Table 1. Note that examination coverage listed is that which was obtained during examination with no credit taken for the far side of each weld.
Component configuration sketches are provided in this attachment.
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 3 of 25 Table 1- Examination Category R-A Welds with Limited Volumetric Coverage Weld Item Configuration Comments Ultrasonic Identification Number Examination Coverage (%) 408044-FW-10-1 R1.20 1.5" Pipe-To-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. Note this was a preservice examination associated with a valve replacement. No recordable indications were detected. 408044-FW-5 R1.20 1.5" Valve-To-Pipe Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. Note this was a preservice examination associated with a valve replacement. No recordable ___indications were detected. RCS-150-FW-2 R1.11 2" Valve-To-Pipe Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-15-FW-28 R1.20 27.5" Pipe-To-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-504A-FW-4 R1.11 8" Pipe-To-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-504C-FW-4 R1.11 8" Pipe-To-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-513-FW-25 R1.11 3" Valve To-Pipe Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-513-FW-29 R1.11 3" Valve-To-Pipe Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-5-FW-8 R1.20 27.5" Pipe-To7Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected.
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 4 of 25 Table 1- Examination Category R-A Welds with Limited Volumetric Coverage Weld Item Configuration Comments Ultrasonic Identification Number Examination Coverage (%) RCS-10-FW-18 R1.20 27.5" Pipe-to-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-20-FW-38 R1.20 27.5" Pipe-to-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-LP2-HL1- R1.20 29" Pipe-To-Nozzle Limited examination from the pipe 50 SW-C side only due to the taper of.the nozzle within close proximity of the weld. No recordable indications were detected. RCS-LP3-FW-27 R1.11 6" Valve -To-Pipe Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. RCS-LP4-FW- R1.20 29" Pipe-To-Nozzle Limited examination from the pipe 50 HL1-CMR side only due to the taper of the nozzle within close proximity of the weld. No recordable indications were detected. RHS-501-FW-3 R1.11 .12" Valve-To-Pipe Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No. recordable indications were detected. RHS--502-FW-3 R1.1i1 12" Valve-To-Pipe Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. SIL-13-FW-5 R1.11 6" Pipe-To-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. Recordable indications were detected that were evaluated as acceptable root geometry. SIL-4-FW-10 R1.11 10" Pipe-To-Valve Limited ,examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. SIL-5-FW-10 R1.11 10" Pipe-To-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected. SIL-6-FW-10 R1.11 10" Pipe-To-Valve Limited examination from the pipe 50 side only due to the taper of the valve within close proximity of the weld. No recordable indications were detected.
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 5 of 25
- 5. Burden Caused by Compliance Compliance with code requirements requires extensive modification or replacement of components with a design that allows examination from both sides of the weld. This option to meet the 100 percent examination coverage requirement is considered impractical due to cost, additional radiation exposure and impact to plant equipment.
- 6. Proposed Alternative and Basis for Use The subject welds received a volumetric examination to the maximum extent practical utilizing the best available techniques, as qualified through the Performance Demonstration Initiative (PDI) for Supplement 2 with demonstrated best effort for single side examination, from the accessible side of the weld.
Additionally a visual (VT-2) examination was performed each refueling outage during the system leakage tests as required by Section Xl, Table IWB-2500-1, Category B-P. Based on the volumetric examination coverage attained with acceptable results, and the visual (VT-2) examination performed each refueling outage, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject
.welds.
- 7. Duration of Proposed Alternative Relief is requested for the second 10-year inspection interval for Millstone Power Station Unit 3, which began on April 23, 1999 and ended April 22, 2009.
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 6 of 25 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant ..,,1 1- LSTDoJE Unit .3 AWO Number A*,*--o(, )ooq S System Vc.'5 Percentage of Area Examined "5 ComponentlD 4oZOqq- tO-i Examination Data Sheet# \ 1 <7 - ý-1 Component Description ,Jy--t -t Calibration Data Sheet# W. 1-6,
-- \si Procedure No e.- -c- 'rO
, Rev 0 Page 6 of ('
Calculation Type Surface [] Volumetric Coverage Calculation I Equation ISketch Area
-J AL J E PE
%JAx-\J C 15%ZC $Ct tJ
- 1ot "TbTA L CO\S-..jAt- "( 0o-.00
" 0, IExaminer Comments .90 --YI2O -e,0(-- QP- Z51t r1 \)AL\J Vt LJ5
~ IIA.J,,.cciý)51A~CI,.
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 7 of 25 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plant A,1,LL-'!0.o; Unit 3 AWO Number .M?--pt,-0oo.4. System 5 v Percentage of Area Examined -5O'/ Component ID 0oT'o Q4' (I &-, Examination Data Sheet # 3 I1-o0- k;5 Component Description etch- \JALjyrE Calibration Data Sheet # 6k %- 01 a . Procedure Rev Page -7 of .-7 Calculation Type Surface 1] Volumetric [] Coverage Calculation I Equation I Sketch Area V A L V,-
/
45M zo 9%\05 $kt> CIeC :SCAN3 to,
\)AL'JC SME Cic Se-A0
\JAL).JE SIDE. AXIAL ;5CAr'J(',
-arL-6 t A&t 1.4 ")-00q r Examiner Comments _0 5ek 00 :ýb -MJA %.JE. SLw)bAv,5
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 8 of 25 Millstone Power Station GE! NERIC SKETCH SHEET Plant . I rye- Unit 3 Page I of Systemr-t.*,, ,-- Zone O0 q Cal. Data Sheet # 309-0-1o Component ID RCS- 15o- 47"4O-Z* Exam. Data Sheet # 4 , Lýe. cY~~~3S ~ ~ca CC,~c4c_ 1. oI ,t1dL Examiner Comments .
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 9 of 25 Millstone Power Station GE!NERIC SKETCH SHEET Plant M;LI,5j (r Unitt Page I of A System IR C,.5 Zone 0 114 Cal. Data Sheet # %-- fi . Component ID , C,- - F(-_-,.z Exam. Data Sheet# afA Examiner Comments 0% ("CO Y ct P_,
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 10 of 25 ATTACHMENT I COVERAGE CALCULATION DATA SHEET Plat M . TE N _ Unft ... AWO Number 01-*4310 System. RCS P*erdage of Area xamined "/o .Componint IID RC5,.--_4A,- VW-,4 Examlnation DataSheet# . -- Component Dewcrptlon PW5ITO VAbJ Caflbration Data.Sheaet# ,4A ProoedureNo.MP-82r.-UFT-; Rev.* -O.0 Page& of . Calculation Type Swface El Volun.*trlo.. _ Cover!ge CalcUlatiQn lEgqaon Ikot(h.Area PIPE
- VALV 45 Examineor Comments 50/. *Com Cbv9zAez-'&mEEvEn cuE n- Gwc-4-r-- SiwD
~S. l~xAM VOLU~4E
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 11 of 25
-ATTACHIAEN I COVERAGE CALCU*ATION DATA SHEET Plant . ,,-. E Unit .3 AWONumber 0I1-IH31D System. RC) Percentage of Area Fxamined 6-0'/,
Component ID .. *.aminafton ExRCS-!C-FV- Data Sheet #, .. --- 1 .3 ComponentDecriptIon PiVE TbVALtE Calibration Data.Sheet ##. f ', 3oq-taj . Procedure No., MP- PDI:ZT-;t ,ev oa Page Of (A Caiouatlon Type. Surface D VolwnetrIjoG __________________ Cove.a.
. e Ca. *itin
- ii1' g t* l I .koth Area
//
\., /: ,
Examinor 06hinments bE L0VFJ-RAc5 'ACHIC-VED OuPF tb Sit4(ji F SitED Cr, PYAIA \ ItnwIF:
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 12 of 25 Millstone Power Station GElNERIC SKETCH SHEET Plant AMuLL5-"ot, Unit 3 Page 3 of £. System Pt.ES*Eo,5 *_X_2 Zone o6 1 Cal. Data Sheet # ;;z,- ,5-Component ID RcS -_l3 -FW -2E Exam. Data Sheet # A IJ Cwirpa &E pLdr q56 e 70" 70 Examiner Comments O-E 5 z..DE. FxE P -V4VO To Boby n 'p,? .O*F2 51%
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 13 of 25 Millstone Power Station GEPlERIC SKETCH SHEET Plant MX si* OJEi , Unit Page 3 of C System PgFs5_,j AzX0R Zone ,. 1 Cal. Data Sheet# 3oz-ovj- la.. Component ID P-CS 1 -f u -. 2q-g Exam. Data Sheet # ___ ____ C-OVE4" Plar ji5"000 r FLOW ExaminerComments O-J E 5Xpa * *.* , £ o V aLp" I 7a
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 14 of 25 Millstone Power Station GEtNERIC SKETCH SHEET Plant ,,l - Unit Page ._._-of System % Q.* Zone cL2_ Cal. Data Sheet# 31g-01 ,-I. Component ID -",I,,(,O -5
,RCS Exam. Data Sheet # . ^ A Examiner Comments _)% ('Covcfra 0te
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 15' of 25 GENERIC SKETCH SHEET Plant Unit_ _ _ Page 0- of 2. 3 System C Zone L3? Exam Package- / - f) I - (on e, Component ID fRC.*'5 - - -',- /,
\ /
\ I
\ /
\. /
~/
! *, / (
25
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 16 of 25 GENERIC SKETCH SHEET Plant tA9 Unit _ Page ,* of ,,.L System _ _ -- _ _Zone ____(IS Exam Package 3," Q - 6? -o1 Component ID____________________
\C /
\ /
ey~itr\
/
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 17 of 25 Millstone Power Station GEMIERIC SKETCH SHEET Plant M.LLumv , Unit 3 Page _3of 3 System RCS Zone 15. Cal Daia Sheet # I3n - O1-3o Componentl qC 5-L-Pj--Lj--Su.-C Exam. Data Sheet # ,__A Examiner Comments .0Z (,5e . (O+.-
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 18 of 25 ATTACHIMPNT I COVERAGE CALCU*LTON DATA SHEET Plant (wlls}aue. unit 3 AWO Numiber Oj.- IjLIO System- IRCS Perentage of Area Examhied 50%/3 .ComponentID C.- LP3-YF-J - . .ExaqnaationDataSheet# 3 -oQt-13 0 1 Component Description -to p-
- g. 40 Calibration Data..Shdee 9 &A ProoedureNomf-PII-oAT-ýo -Rev 3O-O6I, Page3, of 5 I calculation Type Surfacw[ VolumQWEtrcý _________________
Co.' " go Calcflation ./Eqati.onl/ketbh kAe vo aa, Pipe 4460-(, U(P( 46!0~ Vxem\w.C nvonts ~,-i:L. \o~r.s Examlnor'C6mmonts 'ý,Odh-.
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 19 of 25 Millstone Unit-3 Ultrasonic Weld Thickness Profil'e Reference IMIACS-L P4W-Iw- . -CILA Data Pkg.:t I.O2-OI-0o9 Page: M of I ..-. . .... , .... I *Weld Edge Crown Height: FLYS11 Crown'Wldth: . A Dla.: 2 /IZ1 Weld Length: N4 4 Long Seam: A Profile Area 12 . Ij 0 k L6
/
/'
/
N Comments: PIL P C rk I - -r m .
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 20 of 25 Millstone Power Station GEt 4ERIC SKETCH SHEET Plant /1- I1-SONJ. Unit Page ofIt System R#HS Zone ?-n Cal. Data Sheet # 3ol- o- 1.3i-Component ID - 9445 - so t - F V/ -3 Exam. Data Sheet ,__A f Examiner Gomments 2 A' C'OVr-RA6-F- F-YAND)EC 1XE ThE 6 OF Ccj- &49Pe So ýý co VE-A&a .
Outage No.: 3R12 Report No.: 312-01-016 UT Indication/Coverage Plot Summary No.: WA Page No.: 4 of 6 Site: MILLSTONE Unit: 3 Drawing No.: 25212-20930 Component ID: RHS-502-FW-3
== Description:== VALVE TCI PIPE Procedure: ER-AA-NDE-UT-802 REV 000 Prepared By: W.L.THOMAS Level: III Signature: __ Date: 10122108 FLOW VALVE D "1 PIPE 50 %CODE COVERAGE
.56SQIN. OFATOTALOF1.12SQIN'" "',
CD
~CD
.21 SQ. IN NOT EXAMIND (n (bZZ 15.6% BEST EFFORT AX US .35 SQ IN.
01(( rIM ,A/lIA~
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 22 of 25 GENERIC SKETCH SHEET Plant ' M*XLL57"v1JE Unit _-_ Page (A of kt System -kC.S Zone - 6.2 - Exam Package 310 - e j- tDL-- Component ID 5rL- I'l- F 3)57 0 EiaminerCommnents: D) £ORL .O*T' 6,156-ETRlY Xt--3Tt A-XT7rrJT 340
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 23 of 25 Millstone Unit 3 Ultrasonic Weld Thickness Profile L"eern ce7OI:l / - * *
- I Data Pkg.:[ / </
- T Page: *--- -lof°
- 0. 190.- --
--- 270 25,, C entirline Weld de Position il 1 /.44// __5"-_- 2. ", ;1 TF.
2 _D re CF TOE. 4 -q7-CL 5 _ 7 8 FLOW I Crown Height: / 'Crown Width: t
,A Olia.: 1&o Weld Length: 3.?.o Long Seam: A/ /
Profile Area Comments:.7 ~ ~ ~ te ~zz
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 24 of 25 ATTACHMENT 1 COVERAGE CALCULATION DATA SHEET Plant h6T.Lt*a*s... Unit -- AWO Number M r . 1"7 System R C.-5 Percentage of Area Examined 5-b0 20 Component ID 5X L - 5"- ELJ- I0 Examination Data Sheet # 310 0 i Component Description V/ILUF M7c -f'Pf Calibration Data Sheet # ... ,4 Procedure No.-MPt,'-t3T-Z Rev. 006-i3 Page L. of . Calculation Type Surface [] Volumetric Coverag*e Calculation I E~quation ISketch Area r C.0
Serial No. 10-189 Request No. IR-2-59 Attachment 9, Page 25 of 25 Millstone Unit 3 Ultrasonic Weld Thickness Profile Rýeference ID:j 4ý4'. Data Fkg.:t i)- 5 Page: FTT of LTI1
' OF..
.ICt1rie Weld *Wetd Edge Position 0 900 1'80, 2700 3 _2M 4 6F1n TOE* 4 C____
CL /.520 TOE* 6 /A=/e I........ Side 9_..'_ ______ ______ FLOW Crown Height: FZa,511 Crown Width: /,536 Dla.: j*, Wel( Length:.3 *, Long Seam: Profile Area V N,> Comments: 401 t.1, I-
Serial No. 10-189 Docket No. 50-423 ATTACHMENT 10 RELIEF REQUEST IR-2-60 EXAMINATION CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS DOMINION NUCLEAR CONNECTICUT, INC. MILLSTONE POWER STATION UNIT 3
Serial No. 10-189 MPS3 Request No. IR-2-60 Attachment 10, Page 1 of 5 Relief Requested In Accordance with 10 CFR 50.55a(g)(5)(iii)
--Inservice Inspection Impracticality--
- 1. ASME Code Components Affected ASME Code Class: Code Class 1 Examination Category: B-P, All Pressure Retaining Components Item Number: B135.11, Reactor Vessel, Pressure Retaining Boundary
Description:
Pressure Testing Requirements for the Reactor Pressure Vessel (RPV) Flange Leak-Off Piping Component Identification: NPS 1 RPV Flange Seal Leak-Off Piping
2. Applicable Code Edition and Addenda
ASME Section XI, 1989 Edition, No Addenda, with the alternative requirements of ASME Code Case N-498-4, approved for use in Regulatory Guide 1..147 Revision. 15.
3. Applicable Code Requirement
The 1989 Edition of ASME Section XI, Table IWB-2500-1, Examination Category B-P, requires all pressure retaining components to be subject to a system hydrostatic test in accordance with IWB-5222. ASME Code Case N-498-4 allows a system leakage test at or near the end of each inspection interval as an alternative to the 10-year system hydrostatic test required by Table IWB-2500-1. The boundary subject to test pressurization during the leakage test conducted at or near the end of each inspection interval shall extend to all Class 1 pressure retaining components within the system boundary with a test pressure not less than the pressure corresponding to 100% rated reactor power.
- 4. Impracticality of Code Compliance The Reactor Pressure Vessel (RPV) head flange seal leak detection piping is shown in Figures 1 and 2 in this attachment. The piping is separated from the reactor
Serial No. 10-189 MPS3 Request No. IR-2-60 Attachment 10, Page 2 of 5 coolant pressure boundary by one passive membrane, which is an o-ring located on the inner vessel flange. A second o-ring is located on the outside of the tap in the vessel flange. Failure of the inner o-ring is the only condition under which this line is pressurized. Therefore, the line is not expected to be pressurized during the system pressure test following a refueling outage. The configuration of this piping precludes system. pressure testing while the vessel head is removed because the configuration of the vessel tap coupled with the high test pressure prevents the tap in the flange from being temporarily, plugged or connected to other piping. The opening in the flange is smooth walled, making the effectiveness of a temporary seal very limited. Failure of a temporary test seal could possibly cause ejection of the device used for plugging or connecting to the vessel flange. The configuration also precludes pressurizing the line externally with the head installed. The top head of the vessel contains two grooves that hold the o-rings. The o-rings are held in place by a series of retainer clips',that are housed in recessed cavities in the flange-face. If a pressure test were to be performed with the head on, the inner o-ring would be pressurized in a direction opposite to its design function. This test pressure would result in a net inward force on the inner o-ring that would tend to push it into the recessed cavity that houses the retainer clips. The thin o-ring material would likely be damaged by the inward force.
- 5. Burden Caused by Compliance The RPV flange seal leak-off line is only pressurized in the event of a failure of the inner 0-ring. Purposely failing or not installing the inner o-ring in order to perform a pressure test requires installing a new o-ring set with the time and radiation exposure associated with removing and reinstalling the RPV head a second time to replace the o-rings.
This option is considered impractical due to the cost, increased radiation exposure. and impact to outage duration.
- 6. Proposed Alternative and Basis for Use A VT-2 visual examination will be performed each outage on the unpressurized subject piping as part of the Class 1 leakage test. If the inner o-ring should leak during the operating cycle it will be identified by an increase in temperature of the leak-off line above ambient temperature which is an indication of o-ring seal leakage.
This high temperature would actuate an alarm in the Control Room, which would be closely monitored by procedurally controlled operator actions allowing identification of any further compensatory actions required. This leakage would be collected in the primary drain transfer tank. Additionally, the flange seal leak-off line is essentially a leakage collection/detection system and the line would only function as a Class 1 pressure boundary if the inner o-ring fails, thereby pressurizing the line. If any significant leakage does occur in the
Serial No. 10-189 MPS3 Request No. IR-2-60 Attachment 10, Page 3 of 5 leak-off line piping itself during this time of pressurization, it would clearly exhibit boric acid accumulation and be discernable during the proposed VT-2 visual examination that will be performed unpressurized as proposed in this request. Based upon the above, it is reasonable to conclude that service induced degradation would be detected. Therefore, these proposed alternatives will provide an acceptable level of quality and safety by providing reasonable assurance of structural integrity of the subject piping. Future pressure testing of this line will be performed in accordance with the Third Interval relief request IR-3711 which was submitted on April 28, 2009, and is currently awaiting approval.
- 7. Duration of Proposed Alternative Relief is requested for the second 10-year inspection interval for Millstone Power Station Unit 3, which began on April 23, 1999 and ended April 22, 2009.
- 8. Precedents
-A similar request for relief was previously approved for Limerick Generating Station, Units 1 and 2 by letter dated January 27, 2009 (ADAMS Accession No. ML090060218).
Serial No. 10-189 MPS3 Request No. IR-2-60 Attachment 10, Page 4 of 5 Figure 1: REACTOR PRESSURE VESSEL HEAD FLAGE LEAK-OFF LINE CONFIGURATION
Serial No. 10-189 MPS3 Request No. IR-2-60 Attachment 10, Page 5 of 5 Omer flang! 5"I pink ftoliq Lo ffAS2 N A5 C e tl sh RMuNT 1P 9 7 se. P41il "'A' etho3l AA" Vessel Flanqe Sectional 'iew Figure 2 REACTOR PRESSURE VESSEL HEAD FLAN{GE LEAK-OFF LINE DETAILS 2}}