ML20198H161

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Forwards Preservice Insp Relief Requests for Exams Found Impractical Per 10CFR50.55(a)(g)5(iii),to Resolve SER Outstanding Issue 4.Final Preservice Insp Rept Will Be Submitted by 860715 & Will Include Encl Relief Requests
ML20198H161
Person / Time
Site: Seabrook  
Issue date: 05/28/1986
From: Devincentis J
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To: Noonan V
Office of Nuclear Reactor Regulation
References
SBN-1072, NUDOCS 8605300139
Download: ML20198H161 (47)
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Text

{{#Wiki_filter:~ { Ab SEABROOK STATION [ Enginzering Office ej (m d May 28, 1986 Put$c Service of New Hampshire SBN-1072 T.F. B7.1. 2 NEW HAMPSHIRE YANKEE DIVISION United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) PSNH Letter (SBN-909), dated December 20, 1985, "Preservice Inspection (PSI) and Inservice In-spection (ISI) Program (SER Outstanding Issue No. 4 and Licensing Condition 4)", J. DeVincentis to V. S. Noonan J (c) PSNH Letter (SBN-1051), dated May 15, 1986, "Preservice Inspection Program (SER Outstanding Issue No. 4), UT Examination of Cast Stainless Steel", J. DeVincentis to V. S. Noonan Subj ect : Preservice Inspection Program (PSI) (SER Outstanding Issue No. 4), Relief Requests

Dear Sir:

h Enclosed, herewith, please find Seabrook Station Unit 1 PSI Relief Requests for examinations determined to be impractical pursuant to 10CFR50.55(a)(g)S(iii). The nine relief requests included are listed below by number and subject. PR-1 Reactor Vessel Welds PR-2 Pressurizer and Steam Cenerator Welds (Class 1) PR-3 RCP Discharge Nozzle to Piping Welds PR-4 Class 1 Piping Welds PR-5 Pump and Valve Internal Pressure Boundary Surfaces PR-6 Steam Generator, Residual Heat Removal, and Letdown Heat Exchanger Welds PR-7 RHR Heat Exchanger Nozzles PR-8 Containment Building Spray Piping PR-9 Class 2 Piping Welds h h !K 3 E 1 Seabrook Station Construction Field Office. P.O. Box 700 Seabrook, NH 03874

\\ United States Nuclear Regulatory Commission Attention: Mr. Vincent S. Noonan Page 2 These relief requests will become a part of the final PSI Report. In accordance with previous discussion with the Staf f, the final PSI Report will be submitted by July 15, 1986. We trust that the enclosed is acceptable and request that the resolution of this issue be reflected in the next supplement to Seabrook's SER. Very truly yours, y .f av John DeVincentis Director of Engineering Enclosure cc: Atomic' Safety and Licensing Board Service List

1 Disn3 Curran, Esquire Colvin A. Cenn::( Harmon & Weiss City Manager q 2001 S. Street, W.W, City Hall ) Suite 436 126 Daniel Stredt Portsmouth, NH 03801 Washington, D.C. 20009 Sharwin E. Turk, Esq. Stephen E. Merrill, Require Offlee of the Executive Lessa Director Attoimey Cenorm1 ) U.S. Nuclear Regulatory Coemission Caorge Dana Sisbee, Enquire Tenth Floor Assistant Attorney Ceneral Washington, DC 20555 effice of the Attorney Cenein1 25 Capitol Street. Robert A. Backus, Esquire Concord, MN 03301-6397 114 Lowell Street P.O. Box 516 Mr. J. P. Nedeau Manchester, NH 03105 5electmen's Office 10 Central Road Philip Ahrens, Esquire Eye, NH 03870 Assistant Attorney General Department of The Attorney General Mr. Angie Neth1 rom Statehouse Station #6 Chairman of the Board of Selectasn hugusta ME 04333 Town of NewtNty Newbury, MA 01950 Mrs. Sandra Cavutis chairman, Board of Selectmen Mr. Willian 5. Lord ( RFD 1 - Sox 1154 poord of selCeteen Kennsington, NH 03827 Town Hall - Friend Street Amesbury, MA 01913 Carol S. Sneider. Esquire Assistant Attorney General Senator Gordon J. Humphrey Department of the Attorney General 1 Pillsbury Street One Ashburton Place, 19th Floor Concord, NH 03301 Boston, MA 02108 (ATTN: Herb Boyntori) Senator Cordon J. Hwephrey N. Joseph Flynn, Require U.S. Senate Office of General Counset Washipston, DC 20510 Federal Energency Manage.?.ent Agency g (ATTW: Tom Burack) 500 C Street SW Washington, DC 20472 Richard A. Hampe. Esq. Hampe and McNicholas Paul McEachern, Esquire 35 Pleasant Street Matthew T. Brock, Esquire Concord, NH 03301 Shaines & Netachern l 25 Maplewood Avenue Donald E. Chick P.O. Box 360 Town Manager Portsmouth, NH 03801 Town of Exeter 10 Front Street Cary W. Holmes, Esq. l Exeter, BH 03833 Holmes & Ells l 47 Winnacunnet Road Brentwood Board of Selectmen Hampton, NH 03841 RFD Dalton Road Brentwood, NH 03833 Mr. Ed Thomas FEMA Jtegion I Peter J. Mathews, Mayor 442 John W. McCormack PO & Courthouse City Hall Bostoh, MA 02109 Newburyport MA 01950 Stanley W. Knowles, Chairman Board of Selectman P.O. Box T10 North Hampton, NH 03862

Seabcock Ituclear Power Station Unit No. 1 R,Qigfrom Preservice Inspectipn Requirintents Rcljef Jenueste PR-1 Cgpponent Id_entificati,og: Reactor Vessel Welde Code Class: 5 Examination Category: bra.and B-D Coda Requitecents For Scabrook Unit No. 1 a volumetric (ulcrasonic) examination of 100 percent of the weld langth shall be conducted for the following items in accordance with ASME E&PV C6de, 1977 Edition tbrough the Summer 1978 Addendun, Sub-article IWB-2500: Item Description B '1. ' 1 Shell circumfersntial welds 1 B-1.12 Longitudinal shell weltis E-1.21 P.ead circumferential welds E-1.22 Lower head aeridional weld 4 B-1.30 Shell-ca-Flange veld B-3.90 NocrJe to shall welds ,Co,de Relief,Reguey : Pursuant to 10CF850.55(a)(g)5(iii), relief ic requested from performing the prescevice volumetric examination of the inaccessible partion of the subject vessel velds. Besit for Relieft Geonstrip configuration and permaneet obstrections prohibit 100 percent volumetric examination of the code required V61ene. The PBI limitations and the specific relief (ts !. hey apply to each veld,.are noted in the attached table. Support for Relief /Alternit;tinxartirgtitma: A. The subject weids received both voiuinetric cramination by radiography and surface examinationa during fib?1caticn, in eccordance with ASME Eection III requicelents which provide adequate assurance of the struc-tural integrity of the velds. 3. A construction hy.drostatic tast was conducted successfully on the Cicss 1 pressure boundary of which theen welds are a part thereof in accordance with the requirements of ASME Section III. C. In-service system leakage rests will bs performed per Category B-P. T&b2.e IWB-2500-1 each ref ueling outage.

Relief Request: PR-1 Page 2 of 12 The following table lists the percent of required coverage, either for ASME Code or RG l.150 examinations, that was obtained for examinations identified as " limited" in the examination documentation. This applies to the automated examination of the RPV welds and the nozzle to safe end welds, and the manual examination of the closure head welds. The comple-tion percentage was determined by calculating the percentage of actual vs. required coverage for each examination direction, i.e., two directions perpendicular and two directions parallel. A weight factor of.25 was then applied to the actual percent of coverage in each direction. Included in the table as the " Basis for Relief" is the cause of the limitation. e

Rzlief Rzquest: PR-1 Page 3 of 12 CODE PERCENTAGE COMPLETE COMPONENT ID DESCRIPTION CATEGORY ASME CODE RG l.150 BASIS FOR REllEF 1-SB-RV-103-101 Closure head dome section to BA 50 50 One sided examination due to CRD torus assy. circumferential shield. Obstruction due to lifting weld lugs. 101-101 Torus assy. to closure head BA 50 50 One sided examination due to closur flange circumferential weld head configuration. 101-121 Vessel flange assy to upper BA 82 56 Obstruction presented by transition shell assy. circumferential from RPV flange to upper shell weld assy. 103-121 Upper shell assy. to BA 93 100 Obstructions presented by inlet and intermediate shell assy. outlet nozzles. circumferential weld 104-l41 Lower shell assy, to bottom BA 68 74 Obstructions presented by core torus assy. circumferential support lugs. weld 102-151 Bottom torus assy. to bottom BA 68 Not Obstructions presented by bottom he dome section circumferential Required instrumentation nozzles. weld 101-122-42* Upper shell longitudinal weld BA 68 73 obstructions presented by transitio at 42* at RPV upper shell to flange weld, outlet nozzle knuckle, 'and inlet nozzle edge. 101-122-162* Upper. hell longitudinal BA 82 88 Obstructions presented by transitio weld at 162* at RPV upper shell to flange weld a outlet nozzle knuckle. 101-122-282* Upper shell longitudinal BA 94 85 obstruction presented by transition weld at 282* at RPV upper shell to flange weld a inlet nozzle edge. I i

R211cf Rsquzst: PR-1 Page 4 of 12-CODE PERCENTAGE COMPLETE COMPONENT ID DESCRIPTION CATEGORY ASME CODE RG l.150 BASIS FOR RELIEF l-SB-RV-101-154-0* Bottom head torus assy. BA 80 80 Obstructions presented by instru-meridional wald at O' mentation nozzles and core support lug. 101-154-90* Bottom head torus essy. BA 89 88-Obstructions presented by instru-meridional weld at 90* mentation nozzles. 101-154-180* Bottom head torus assy. BA '82 83 Obstructions presented by instru-merldlocal wald at 180' rantation nozzles and core support lug. 101-154-270' Bottom head torus assy. 8A 93 98 Obstruction presented by instru-merldlonal weld at 270* mentation nozzle. 107-121-A Upper shell to outlet 80 84 74 Obstruction presented by nozzle nozzle "A" knuckle. 107-121-D Upper shall to outlet 80 84 76 Obstruction presented by nozzle nozzio "D" knuckle. 107-121-E Upper shell to outlet BD 84 67 obstruction presented by cozzle no2zle "E"

knuckle, 107-121-H Upper shelt to outlet 80

- 89 80 Obstruction presented by nozzle nozzle "il"

knuckle, IQS-I21-B Upper shell to intet 80 100 96 Obstruction presented by outlet nozzlo "B" nozzle knuckle.

105-121-C upper shell to inlet no 100 SS obstruction presented by outlet nozzle "C" nozzle knuckle. 105-121-F Upper shall to inlet 80 100 99 Obstruction presented by outlet ~ nozzle "F" ndzzle knuckle. 4 -w-w -s -e e = w - w - =-

.~ ,.... ~..- .'Rslief Request PR-1

Page 5 of 12 CODE PERCENTAGE COMPLETE

- COMPONENT ID' DESCRIPTION CATECORY ASME CODE RG 1. t 50 -SAsiS FOR RELIEF- . 1-SB-RV- ~! 105-121-G Upper chet t 'to inlet PD 100 98 obstruction presented by outlet nozzle "G" nozzle knuckle.- t 4 C L L 9 e h I P

Relief Request: PR-1 DOCUMENT NO. any PAGE 6 op 12 ( NUCLEAR ENERGY SERVICES, INC. l 103-10ll NOTE: WELD IDENTIFICATION CLOSURE HEAD NOS. HAVE THE PRE-FIX l-SB-RV, l iO!-iOil 1 } l i l \\ \\( NIOt-12ll \\ UPPER SHELL \\. \\ \\ sflO3-12il ) /[ u n / / / i I INTERMEDIATE / / SHELL A ioi_i7ll f f / u / c -n N' j g k g i \\ \\ \\ LCWER \\. \\ SHELL N /104-14ll l g s \\ \\ l U >] E s i TIEL*5 ----- g j I "?!" "'" CIRCUM FERENTIAI., WELD MAP REACT. VESSEL ASS'BD 10 2 -1511

    • O ao ao A-02 v.T w

=ce9/3/92 CLASS I BOTTOM HEAD i prea/23/g2 " " SEABROOK N.R S. mu ro sexa FCRM 8 NES 205 2/80

Relief Request: PR-1 DOCUMENT NO. m PAGE 7 OF l' ,[ NUCLEAR ENERGY SERVICES. INC. 360' 270 100 90 0 338 193 247 202 158 11 3 67 22 I I I I I I I m 101-122-282-- ici.121 101-12 2-16 2 -101-12 2-4 [ M s r o e n = 101-124-120 ~ 101-124-240 101-12 4 - 0 101-171 101-142-330 101-14 2-210 101-14 2-9 0 3 p a a p r, t 104-142-126-104-142-300-104 142-2401. - 104 142-180* 104-142-60 - IO4-l42-0 l ]"l F2 g NOTE: WELD IDENTIFICATION NOS. J" "'" LONGITUDINAL i HAVE THE PREFIX l-SB-RV. REACT S L ASS'BLY

==+ 0 r= = A-03 1 [6 CLASSI

    • ' SEABROOK N.R S.

NOT TO SCALE FORM # NES 205 2/80

Relief Request: PR-1 DOCUMENT NO. 8 OF 12 PAGE NUCt. EAR ENERGY SERVICES. INC. 90 o 101-10 4-45 -- I 101-10 4-135 7 7 N O* t-18 0 10 3 -101 TOP 101-101 VIEW J k l 101-10 4-31S 20 101-104-225 I TORUS ASS'BLY 103-10lj MERIDIONAL WELD SECTIONAL l VIEW 101-10 4-13 5" 101-104 45-1_ i 101-101 c. + r-e I Q E% "E~ CLOSURE HEAD WELD MAP NOTE: aev O m= A-04 WELD IDENTIFICATION NOS, HAVE THE PREFIX l-SB-RV. CLASS l ~" SEABROOK N.R S. NOT TO SCALE FORM 8 NES 205 2/80 l

Relief Request: PR-1 DOCUMENT NO. PAGE 9 OF 12 NUCLEAR ENERGY SERVICES. INC. [ IOI-154-2 Xf I 'l01-154-0 101-154-18 0 BOTTOM VIEW d-18 0, Y 10 2-151 10 4-141 l 0 101-154-9 0 - l i Y 101-141 1 J V TORUS ASSEl.iBLY SECTIONAL. MERIDIONAL WELD vlEW -A 10 2-151 n ra ng 5',$4'" "'" BOTTOM HEAD-WELD MAP i NOTE: REACT. VESSEL ASS'BLY WELD IDENTIFICATION NOS. .,v O m ao A-05 HAVE THE PREFIX l-SB-RV. - TE b> oarF/4#1 CLASSI -M oaol23/82 "**" SEABROOK N.R S. j asOF YO SCALE FORM 8 NES 205 2/80

Relief Request: PR-1 DOCUMENT NO. NUCLEAR ENERGY SERVICES, INC. 105-121-Gl I SE-302-121-F SE-302-121-G l l105-121-F g p} l SE-3OI-121-Eh

  • h 107-121-H l lIR-128-lOl-F IR-128 lOI-Gl Eg Q'(',

lIR-128-3OI-El lIR-128-3OI-H lO7-121-E SE-3OI-121 Hj Pm er O. 18 0* t llO7-121-Al 'IR 128-30FDI lIR-124-3OI-A l IIR-128-lOI-C lIR-128-lOI-B 9A sa I lSE-3OI-121-Db SE-3OI-121-Al llO7-121-D h c'[a 10 5-121-81 C ISE-302-121-Cl l SE-302-121-Bl 90* llOS-121-Cl l 1 b NOTE: ALL IDENTIFICATION NOS. HAVE ,, r u THE PREFIX l-SB-RV-FOR NOZZLE WELD MAP COMRLETE IDENTIFICATION. REACT VESSEL AS$BLY avv 0 ree A-06 S. I[.gy3 CLASSI ' * " * ' SEABROOK N.R S. Wf 80 SCALE FORM 8 NES 205 2/80 l l

Relief Request: PR-1 DOCUMENT NO. PAGE 11 OF 12 NUCLEAR ENERGY SERVICES, INC. TES 1213112-Bl-212-Il2-E l ETRATI 1215-1l2-01-, 1214 ll2-Df /,7 i 'O \\. g g g@/,x l214-il2-E l \\ Te 8@ O \\\\ l214-il2-F 1214 il2 Cl g g g g g~ 77 215-il2 DI 1215 112 8 s OOG O h@ @ h l213-il2-C l s u F0 8 213 Il2-Al h @ll SB-RV 503 lOf l @h h@ -{ 212-Il2-G 1215-Il2-A hh@ hh l214 il2 Gl l \\1214-ll2 \\l\\@e@e@e@e

  1. l24-Il2-Hl 1214 il2 Bl hh@b m

A N 731 N l212 Il2-A}- -{215-il2-El, 3 112-D1-n a 5. -.-.. I "'"TO P HEAD NOTE: PENETRATIONS lh CRD HOUSING WELD IDENT. REACT. VE5SEL ASSBLY NOS.ARE PRECEDED BY m I = *A-07 3 1-SB-RV. => / /4 ev s SECTICN VIEW "' "" SEABROOK ' N.P. S. CCNWCL CD HOUSING .,,o,m, FORM # NES 205 2/80 t

Relief Request: PR-1 DOCUMENT NO. PAGE 12 OF 12 ( NUCt. EAR ENERGY SERVICES. INC. O' INSTRUMENT PENETRATION 7 $(f kN NUMBERS s sa m 3 \\ n 4e \\ 4 2s m + m 8 is W M 16 83 c .M 2? M En 3b 6 t 2.. 4(, 270' 90* ~ n. s_ .u e s.. 3 ao. si. ?! .t* . 20 w srn 23 et 4a i n 2s .ss SS 16 39 M1 $4 47 CORE SUP' PORTS 180* DOT TOM HEAD INSTRUMENT PENETRATION LOCATION NOTE: ALL BOTTOM HEAD PARTIAL PENETRATION WELD NOS. ARE PRECEEDED N N b,==- -. BY I-SB-RV-2OI-15!- FOR COMPLETE IDENTIFICATION. '"" BOTTOM HEAD PARTIAL PENETRATION REACT. VESSEL ASS BLY vO

=== A-08 - Tc4.J o.re sif r;L ~Jh-oars 9h4/92 "*"*' SEABROOK N. R S. er ro scas FORM s NES 205 2/80

Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-2 Component Identification: Pressurizer and Steam Generator Welds Code Class: 1 Examination Category: B-B and B-D Code Requirement: For Seabrook Unit No. 1 a volumetric (ultrasonic) examination of 100 percent of the weld length and 100 percent of the nozzle inner radius areas shall be con-ducted for the following items in accordance with ASME B&PV Code, 1977 Edition through the Summer 1978 Addendum, Subarticle IWB-2500: Item Description B2.11 Circumferential Shell-to-Head Welds (Pressurizer) B2.12 Longitudinal Shell Welds (Pressurizer) B2.40 Tube Sheet-to-Head Welds (Steam Generators) B3.30 Nozzle-to-Vessel Welds (Pressurizer) B3.40 Nozzle Inside Radius Section (Pressurizer) Code Relief Request: Pursuant to 10CFR50.55(a)(g)5(iii), relief is requested from performing the preservice volumetric examination of the inaccessible portions of the subject vessel welds and inner radius areas. " Basis for Relief: Geometric configuration and permanent obstructions prohibit performance of a 100 percent volumetric examination of each of the subject welds. The PSI limitations and the specific relief as they apply to each weld, are noted in the attsched table for each component. Support for Relief / Alternate Examinations: A. The subject welds received both volumetric examination by radiography and surface examinations during fabrication, in accordance with ASME Section III requirements, which provide adequate assurance of the struc-tural integrity of the welds. B. A construction hydrostatic test was conducted successfully on the Class 1 pressure boundary, of which these welds are a part thereof, in accordance with the requirements of ASME Section III. C. In-service system leakage tests will be performed per Category B-P, Table IWB-2500-1 each refueling outage.

Relief Request. PR-2 Table 1 Page 2 of S Pressurizer Limitations Weld Data Code Exam Technique C ilcuration/ Limitation CRV Identification Sheet Item Angle Coverage Number (1) Number RC-E-10-A-NZ 6466-11 B 3.30 45* 1 Vee Nozzle to Shell 75% RC-E-10 A-N Z 6466-10 B 3.30 60" l Vee Nozzle to Shell 755 RC-E-10-B-NZ 6466-11 B 3.30 45* } Vee Nozzle to Shell 75% RC-E-10-B-NZ 6466-10 B 3.30 60* 3 Vee Nozzle to Shell 75% RC-E-10-C-NZ 6466-11 B 3.30 45 3 Vee Nozzle to Shell 75% RC-E-10-C-NZ 6466-10 B 3.30 60 i Vee Nozzle to Shell 75 % RC-E-10-D-NZ 6466-11 B 3.30 45* 1 Vee Nozzle to Shell 75% RC-E-10-D-NZ 6466-10 B 3.30 60 i Vee Nozzle to Shell 75% RC-E-10-SP-NZ 6466-11 B 3.30 45" l Vee Nozzle to Shell '755 RC-E-10-SP-NZ 6466-10 B 3,30 60* 1 Vee Nozzle to Shell 75%

Relief Riquest: PR-2 Table 1 Page 3 of S Pressurizer Limitations Technique Configuration / Limitation Co age Ag Identi i ation Number (1) Number 1-RC-E-10-4 6466-6 B2.11 0* 0* Shell to Shell 96% 1-RC-E-10-4 6466-8 B2.11 45' Cire. and Axial Shell to Shell 96% 1-RC-E-10-4 6466-7 B2.11 60* Cire. and Axial Shell to Shell 96% 1-RC-E-10-9 6466-15 B2.11 0* 0* Shell to Upper Head 95% 1-RC-E-10-9 6466-8 B2.11 45' Circ. and Axial Shell to Upper Head 95% 1-RC-E-10-9 6466-13 B2.11 60* Circ, and Axial Shell to Upper Head 95% 1-RC-E-10-1 6466-9 B2.11 0* 0* Lower Head to Shell 99% 1-RC-E.10-1 6466-8 B2.11 45' Circ and Axial Lower Head to Shell 79% 1-RC-E-10-1 6466-10 B2.11 60* Cire, and Axial Lower Head to Shell 80% 1-RC-E-10-S-NZ 6466-15 B3.30 0* 0* Surge Nozzle to Lower Head 74% 1-RC-E-10-S-NZ 6466-14 B3.30 45" Circ. and Axial Surge Nozzle to Lower Head 74% 1-RC-E-10-S-NZ 6466-13 B3.30 60* Cire. and Axial Surge Nozzle to Lower Head 74% 1-RC-E-10-S-NZ 6467-11 B3.40 70* Inner Strrge Nozzle to Lower Head 74% Radius 1. Data sheet number refers to data sheet containing incomplete scan.

Relief of Request: PR-2 Tabic 2 Page 4 of 5 Steam Generator Linitations Weld Data Code Eram Technique Configuration / Limitation CRV Identification Sheet Item Angle Coverage Number (1) Number _ 1-RC-E-11A-2A-NZ 6465-42 8 3.50 45* 1 Vee Nozzle to Shell 75% 1-RC-E-11A-2A-NZ 6465-48 B 3.50 60 i Vee Nozzle to Shell 75% 1 RC-E-11A-2B-NZ 6465-42 B '.50 45 3 Vee Nozzle to Shell 75% 1-RC-E-11A-2B-NZ 6465-48 B 3.50 60 i Vee Nozzle to Shell 75% 1-RC-E-11B-2A-NZ 6465-52 B 3.50 45 i Vee Nozzle to Shell 75% 1-RC-E-11B-2A-NZ 6465-44 B 3.50 60 l Vee Nozzle to Shell 75% 1-RC-E-11B-2B-NZ 6465-52 B 3.50 45 3 Vee Nozzle to Shell 75% 1-RC-E-11B-2B-NZ 6465-44 8 3.50 60* i Vee Nozzle to Shell 75% 1-RC-E-11C-2A-N: 6465-49 8 3.50 45 i Vee Nozzle to Shell 75% 1-RC-E-11C-2A-NZ 6465-47 B 3.50 60" l Vee Nozzle to Shell 75% 1-RC-E-11C-2B-NZ 6465-49 B 3.50 45 l Vee Nozzle to Shell 75% 1-RC-E-11C-2B-NZ 6465-47 B 3.50 60 i Vee Nozzle to Shell 75% l-RC-E-11D-2A-NZ 6465-46 B 3.50 45* 3 Vee Nozzle to Shell 75% 1-RC E-11D 2A-NZ 6465-50 B 3.50 60* } Vee Nozzle to Shell 75% 1-RC-E-11D-2B-NZ 6465-46 B ?.50 45* 3 Vee Nozzle to Shell 75% l-RC E-11D-2B-NZ 6465-50 B 3.50 60 i Vee Nozzle to Shell 75%

Relief R qu::ct: PR-2 age S of S Table 2 ' Steam Generator Limitations Data Code CRV Sheet item Technique Configuration / Limitation Weld Coverage Angle Identification Number (1) Number 1-RC-E-11A Seam.1 6465-011 B2.40 0* 0* Tubesheet to lower head. 4 78% S/G supports Tubesheet to Iwoer head. 4 78% 1-RC-E-11A Seam 1 6465-008 D2.40 45' Cire, and Axial S/G supports Tubesheet to lower head. 4 58% 1-RC-E-11A Seam 1 6465-007 B2.40 60* Circ. and Axial-S/G supports and surface contour. 78% 1-RC-E-11B Seam 1 6465-034 B2.40 0* 0* Tubesheet to lower head 4 S/G supports .78% Tubesheet to lower head 4 1-RC-E-llB Sean 14 6465-036 B2.40 45* Circ, and Axial S/G supports Tubesheet to lower head. 4 78% 1-RC-E-11B Seam 1 6465-035 B2.40 60* Cire. and Axial S/G supports 1-RC-E-11C Seam i 6465-036 B2.40 0* 0* Tubesheet to lower head. 4 78% S/G supports 1-RC-E-11C Seam 1 6465-028 B2.40 45* Cire, and Ax'ial Tubesheet to lower head. 4 78% S/G supports Tubesheet to lower head. 4 78% 1-RC-E-11C Seam 1 6465-029 B2.40 60* Cire. and Axial S/G supports 1-RC-E-11D Seam 1 6465-020 B2.40 0* 0* Tubesheet to lower head. 4 78% S/G supports Tubesheet to lower head. 4 78% 1-RC-E-11D Seam 1 6465-036 B2.40 45* Circ. and Axial S/G supports 1-RC-E-11D Seam 1 6465-021 B2.40 60* Circ. and Axial Tubesheet to lower head. 4 78% S/G supports i 1. Data sheet numb 2r refers to lata sheet containing limi.ted scan.

Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-3 Component identification: Reactor Coolant Pump discharge nozzle to piping welds Code Class: 1 Examination Category: B-J Code Requirement: For Seabrook Unit No. 1, volumetric (ultrasonic) and surface examination of 100 percent of the length of each weld in the main coolant piping system shall be conducted in accordance with the ASME, B&PV Code 1977 Edition through the Summer 1978 Addendum, Subarticle IWB-2500. Code Relief Request: Pursuant to 10CFR50.55(a)(g)5(111), relief is requested from performing the preservice volumetric examination of the inaccessible portions of the welds listed in Table 1 attached. Basis for Request: Due to the unique construction of these welds, it is not possible to verify complete coverage of the code required volume. Each weld consists of a cast stainless steel pump casing (SA-351, CF8A) welded to a wrought stainless pipe (SA-376, TP-304N). In order to provide a satisfactory transition taper between the pump and piping, the pipe side was overlaid with weld material. (See attached sketch.) The welds were scanned by Westinghouse using a 41* refracted longitudinal (RL) wave frou both sides of the weld. Due to the taper of the pump nozzle, the resulting angle in the material was essentially O' relative to the I.D. sur-face, when using the 41* RL fixutre on the pump side. This was confirmed during the examination by th( presence of a str?ng backwall signal. The pipe side of each weld was scanned by NES using a 45' shcar wave. Due to the metal-lurgical structure of the weld overlay on the pipe and the effect this type of material typically has on shaar waves combined with the existance of a veld material / oat.e material interface paralled to the 1.D., the angle of the shear wave in the material and resultant coverage cannot be determined. Both sides of the welds were completely scanned with 0* longitudinal beams. This particular weld geometry and associated technical difficulties resulting from the metallurgical conditons encountered is a generic problem with plants of similar design. Methods of improving the results obtainable from examina-tion of this geometry are currently under development within the industry. New Hampshire Yankee will continue to evaluate the results of these efforts and adopt any new techniques and technologies that they determine will improve the quality of their examinations as they become available.

Relief Request: PR-3 Page 2 of 4 Support for Relief / Alternate Examinations: A. The subject welds received both a volumetric examination by radiography .and surface examination during fabrication as required by ASME Section III. These examinations provide adequate assurance of the structural integrity of the welds. B. A construction hydrostatic test was conducted successfully on the Class 1 Pressure Boundary of which these welds are a part. C. In-service system leakage tests will be performed per Code Category B-P, Table IWB-2500-1. D.. The welds were completely scanned during PSI using the best techniques available subject to the limitations described above. 4 4 4 t 1 4 I s I i i l 4 0 i k ..-.m_.

Relief Request: PR-3 Page 3 of 4 l 1 s' ~ .'h l N. t ~ h .45 ---** Ace 3 \\ \\. W'

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Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-4 Component Identification: Class 1 Piping Welds and Safe End Welds Code Class: 1 Examination Category: B-J and B-F Code Requirement: For Seabrook Unit No. 1, volumetric (ultrasonic) and surface examination of 100 percent of the length of each weld in the main coolant piping system shall be conducted in accordance with the ASME, B&PV Code 1977 Edition through the Summer 1978 Addendum, Subarticle IWB-2500. Code Relief Request: Pursuant to 10CFR50.55(a)(g)5(iii), relief is requested from performing the preservice volumetric examination of the inaccessible portions of the welds listed in Table 1 attached. Basis for Request: Geometric configuration, permanent obstructions, and structural inter-ferences prohibit 100 percent volumetric exam coverage of the Code required examination volume. Relief is, therefore, requested from performing pre-service examinations on the inaccessible portions of the volume required as noted in Table 1. It should be noted that the Westinghouse developed-UT technology for cast stainless steel piping was utilized in performing all exams on the cast portions of the main coolant piping. This technique was developed as a best effort method of examinin2 ca s t stainless steel, which is a generic problem encountered in Westinghouse plants of similar design. In doing so, the alternate examinstion provisions of ASME Section X1, Subsubarticle IWA-2240 and ASME Section XI, Paragraph T-i10(7) were evoked. A 0' longitudinal beam examinatian was conducted on all cast stainless steel welds to map ID geometry contours. This was done in addition to Section XI requirements to aid in the performance and evaluation of angle beam examina-tion results. Complete examinations which met the requirements of ASME Section XI were performed on welds of similar configuration using the same inspection tech-niques, equipment and procedures as those partially inspected or uninspected welds. Since the partially inspected or uninspected welds will see the same operating and environmental conditions as the inspected welds, a reasonable assurance of the structural integrity of the welds for which relief is re-quested has been attained, u

l Relief Request: PR-4 Page 2 of 7 Proposed Alternative Examinations: A. The subject welds received both volumetric examination by radiography and surface examinations during fabrication in accordance with ASME Section III requirements. Having met these requirements, adequate assurance of the structural integrity of the subject welds is provided. B. A preoperational cold hydrostatic test was conducted successfully on the Class 1 Pressure Boundary, of which these welds are a part thereof, per the requirements of ASME Section III. C. In-service system leakage tests will be performed per Category B-P, IRB-2500-1 as well as surface and volue:tric exams on the accessible portions of the welds shown on Tabic 1, as required by Section XI selection criteria. Any advances in UT technology will be evaluated to determine its application for achieving maximum volume coverage g esults and applied where deemed appropriate by New Hampshire

Relief Riquest: PR-4 \\ Page 3 of 7 Pipe Weld Scan Limita'_ tons Table IWB-2500-1, Category B-J, B-P Data Code CRV Weld Sheet Item Technique Configuration / Limitation ^"E

  • Identification Number (1)

Number REACTOR COOLANT MAIN LOOP PIPING Loop-l 1-RC-1-1-1 None B9.11 65 RL 1/2 Vee Axial-Safe End-to-Pipe / e al urgy 75% 1 Direction (Safe End Side) 1/2 Vee Cire. 1-RC-2-1-2 None B9.11 40*RL b Vee Elbow Side Elbow-to-Pipe / Structural Steel 95% Axial and Circ. 1-RC-2-1-5 None B9.11 42"RL b Vee Elbow Side Pipe-to-Elbow / Structural Steel 95% Axial and Circ. 1-RC-2-1-6 None B9.ll 41 RL Vee Elbow Side Elbow-to-Pump / Surface Indentation 99% Axial and Cire. 1-RC-3-1-1 None B9.11 41*RL Vee Pump Side Pump-to-Pipe / Metallurgy 0% Axial and Circ. 1-RC-3 1-3 None B9.11 40*RL h Vee Elbow Side Elbow-to-Safe End/ Surface Geometry 1% Axial and Circ. (Elbow Side) 1-RC-3-1-3 None B9.11 None Elbow-to-Safe End/ Metallurgy 0% (Safe End Side) Loop-2 1 -RC 1-1 None B9.11 65 RL } Vee Axial-Safe End-to-Pipe / Metallurgy 75t 1 Direction (Safe End Side) l Vee Cire. 1-RC-5-1-2 None B9.11 40*RL h Vee Elbow Side Elbow-to-Pipe / Structural Steel 93% Axial and Cire. 1-RC-5-1-5 None B9.11 40*RL Vee Elbow Side Pipe-to-Elbow / Structural Steel 95% Axial and Cire. 1-RC-6-1-1 None B9.11 42*RL Vee Pump Side Pump-to-Pipe / Metallurgy 0% Axial and Circ. 1-RC-6-1-3 None B9.11 40*RL S Vee Elbow Side Elbow-to-S1fe End/ Surface Geometry 1% \\xial and Cire. (Elbow Side)

R lief R;quact: PR-4 Pig 2 4 of 7 Table 1 Pipe Weld Scan Limitations Table IWB-2500-1. Category B-J, B-F Data Code CRV Wald Exam Sheet Item Technique Configuration / Limitation Identification Angle Coverage Number Number Loop 2 Cont. Elbow-to-Safe End/ Metallurgy 0% 1-RC-6-1-3 N6ne E9.11 None-(Safe End Side) g Loop 3 Safe End-to-Pipe / Metallurgy 75% 1-RC-7-1-1 None B9.ll 650 RL } Vee Axial. (Safe End Side) 1 Direction 3 Vee Circ. l FC-8-1-2 None B?.11 41*RL h Vee Elbow Side Elbow-to-Pipe / Structural Steel 94% i Axial and Circ. 0% 1-RC-9-1-? None B9.11 42*RL h Vee Pump Side Pump-to-Pipe / Metallurgy Axial and Cire. 1-RC-9-1-3 None B9.11 40*RL Vee Elbow Side Elbew-to-Safe End/ Surface Geometry 1% Axial and Cire. (Elbow Side) Elbow-to-Safe End/ Metallurgy 0% None 1-RC-9-1-3 None B9.11 (Safe End Side) Loop 4 Safe End-to-Pipe / Metallurgy 7S% 'l-RC-1C-1-1 None B9.11 65 RL i Vee Axial. (Safe End Side) 1 Direction } Vee Cire. 0% 1-RC-12-1-1 None B9.11 41*RL h Vee Pump Side Pump-to-Pipe / Metallurgy Axial and Circ. 1-RC-12-1-3 None B9.11 40*RL h Vee Elbow Side Elbow-to-Safe End/ Surface Geometry 1% Axial and Circ. (Elbow Side) Elbow-to-Safe End/ Metallurgy 0% None 1-RC-12-1-3 None B9.11 (Safe End Side)

R211 f R quirt: PR-4 Page 5 of 7 Table 1 Pipe Weld Scan Limitations Table IWB-2500-1, Category B-J, B-F Technique Configuration / Limitation Ident ation Angl E Number Number Branch Piping 1-SI-203 2 6462-229 B9.11 45*S 1 Vee Axial Valve-to-Pipe / Permanent Obstruction 84% 1 Vee Cire. 1-Ril-158-5-19 6462-203 B9.11

  • RL h Axial Pipe-to-Reducer / [

ometry 75S 1-RH-158-5-20 6462-203 B9.11 45*RL Vee Axial Pipt-to-Pipe / 7SZ em 45 S Vee Cire. 1-Ril-160-17-2 6462-340 B9.11 45*RL h Vee Axial Pipe-to-Tee /"*u"rface Geometry "#EY 50% S 45"S b Vee Cire. 1-RC-48-2-2 6462-358 B9.11 45*RL h Vee Axial Pipe-to-Tec/ "* *"'""#87 50%

    • #Y 45*S Vee Cire.

Limited by 1-RC-1-1-5B 6462-131 B9.3 1 45* Full Vee Axial only 12" Branch Connection / Weld 1-RC 33% 1-2 and sur-6462-132 face contour i ed ce 1-RC-3-1-5B 6462-137 B9.31 45* Full Vee Axial only 10" nch 50% 7 g scan 1-RC-4-1-5B 6462-130 B9.31 45' Full Vee Axial only 6 Brmh / r on CI 50% scan 1-RC-6-1-3B 6462-132 B9.31 45* Full Vee Axial only 10" Branch Limited by surface 50% j Connection contour on Circ. scan 1-RC-7-1-5B 6462-137 B9.31 45* Full Vee Axial only 14" Branch Limited by surface 50% j Connection contour on Circ. scan

Relief R1 guest: PR-4 Pag 3 6 of 7 Table 1 Pipe Weld Scan Limitations Table IWB-2500-1, Category B-J, B-F ec nique n gura n/ ation Co age An Ident i ation Number Number 1-RC-7-1-6B 6462-132 B9.31 45* Full Vee Axial only 6 ran / r 50% scan y ace 1-RC-9-1-4B 6462-125 B9.31 45* Full Vee Axial only 10" Br m h j g 50% l-RC-10-1-5B 6462-137 B9.31 45* Full Vee Axial only 12" Br nch j 50% ace l-RC-12-1-4B 6462-130 B9.31 45' Full Vee Axial only 10" Branch j 50% Safe End Welds-Reactar Vessel 1-SB-RV-301-121-D None B5.10 Composite Vee Nozzle-to-Safe End/ID Geometry 97% Axial and Cire. Safe End Welds-Steam 3enerator 1-RC-1-1-3 6463-120 B5.30 45' h Vee Nozzle-to-Elbow / Surface Geometry 25% Axial only (Nozzle Side) One Direction (Carbon Steel Only) 1-RC-2-1-1 6463-129 B5.30 45 h Vee Nozzle-to-Elbow / Surface Geometry 25% Axial only (Nozzle Side) One Direction (Carbon Steel only) 1-RC-4-1-3 6463-125 B5.30 45* h Vee Nozzle-to-Elbow / Surface Geometry 25% Axial Only (Nozzle Side) (Carbon Steel only)

R lief Requista PR-4 Table 1 Page 7 of 7 Pipe Wald Scan Limitations Table IWB-2500-1, Categoty B-J, B-F D ta Code CRV Weld Exam Technique Configuration / Limitation Identification Angle Coverage N br N br 1-RC-5-1-1 6463-124 B5.30 45' Vee Nozzle-to-Elbow / Surface Geometry 25% Axial Only (Nozzle Side One Direction Carbon Steel Only) 1-RC-7-1-3 6463-124 B5.30 45' h Vee Nozzle-to-Elbow / Surface Geometry 25% Axial Only (Nozzle Side Carbon Steel Only) One Direction 1-RC-8-1-3 6463-81 B5.30 45* Vee Nozzle-to-Elbow / Surface Geometry 25% Axial Only One Direction 1-RC-101-3 6463-127 B5.30 45' Vee Nozzle-to-Elbow / Surface Geometry 25% Axial Only One Direction 1-RC-Il-1-3 6463-56 Bs.30 45* Vee Nozzle-to-Elbow / Surface Geometry 25% Axial Only One Direction 1. Data sheet number, where given, refers to data sheet coltaining incomplete sc.::n. 2. S = Shear RL = Refracted Lo Tgitudinal

i 6' l Seabrook Nuclear P6.wr Station Unit Uc. 1 Relief From Preservice ^Catpection Requirements Reliaf._ Request; PR-5 1 i Cooponent Idehtification: Pump and Valve Internal Pressure Bour.dary Surfaces Code. Class: 1 Exanination Category: B-1-1 and B-M-2 Code Requircaent: For Seabrock Unit No. 1, a visuni cxnmingt&on (Yre3) of the internal surfaces sba11 be conducted f or the following items in accordanca stith ASSE B&PV Code, 1977 Edition through the Summer ITIB. Addendum. Iten Description 1. B12.40 valve bodies exceeding 4" Nos B12.20 ? ump casiogs 4 Notet Eraninations are linited to: A. One valve within cach group of valves that.are of the same design, manu-facturing niethod, and are. performing similar functions in the system. B. Ona pump pet group performing similar functions. I P Code Relief Request: t Pursuant to 1GCFR50-$$(a)(g)S(iii), relief is requested from performing a prescrylce visual examlnation (VT-3). r l Support for Relie.f/ Alternate Examinations l For.the reactor coolant pump cssings and 33 valve bodies (see Table 1 attached) i in the rccctor coolant, pressuri.zer, safety injection, and residtal heat re-moval systems. relief is requented from disassenhly of an operable valve or pump for the performing a preservice visual exazination (VT-3). The requirement to disassemble en operable valve or pump for the sole purpose of performing a visual examination C/T-3) of the internal pressure retaining boundary is impractical and not con:ensurate to the increased assurance of safety achieved!by this inspecticn. Class 1 valves and pumps are installed in their respective sys' ens and all active valves completed functional testing c in accordance with ASME Section EE. Article IWV.. To disassemb'le these items would provide a very small potential for increasing plant safety margins with a disproportionate impact on expenditures of plant maapewer and resources, i i 1.

Relief Request: PR-5 Page 2 of 3 The manufacturer's test data will be used in lieu of a preservice visual examination (VT-3). This includes documentation of examinations performed during fabrication and installation of the subject valves. The examina-tions performed may include volumetric, surface, and visual examinations, as required by ASME Section II, Material Specifications for Ferrous and Nonferrous Materials, and ASME Section Ill, Construction and Installation Requirements. Class 1 valves and pumps are subjected to numerous types of nondestructive testing and a rigorous quality assurance program during all stages of fab-rication, storage, and installation. These valves and pumps have been found acceptable by the manufacturer, the ASME Authorized Nuclear Inspector, and New Hampshire Yankee's Quality Assurance. During maintenance of Class 1 pumps, a visual examination (VT-3) will be performed during in-service.

b-l Relict Krqu st: PR-5 Pign 3 of 3 Table 1 Class 1 Pumps and Valves Subject to Internals Visuals per IWB-2500-1 Cat. B-L-2, B-M-2 Group

  • Valve I.D.

System Description Manufacturer 1. 1-RC-V22 Reactor Coolant 12" Gate Westinghouse 1-RC-V23 Reactor Coolant 12" Gate Westinghouse 1-RC-V87 Reactor Coolant 12" Gate Westinghouse 1-RC-V88 Reactor Coolant 12" Gate Westinghouse 2.~ 1-RC-V115 Reactor Coolant 6" Relief Crosby 1-RC-V116 Reactor Coolant 6" Relief Crosby 1-RC-V117 Reactor Coolant 6" Relief Crosby 3. 1-RH-V15 Residual Heat Removal 6" Check Westinghouse 1-RH-V29 Residual Heat Removal 6" Check Westinghouse 1-RH-V30 Residual Heat Removal 6" Check Westinghouse 1-RH-V31 Residual Heat Removal 6" Check Westinghouse 1-RH-V52 Residual Heat Removal 6" Check Westinghouse 1-RH-V53 Residual Heat Removal 6" Check Westinghouse 1-RH-V50 Residual Heat Removal 8" Check Westinghouse 1-RH-V51 Residual Heat Removal 8" Check Westinghouse 4. 1-RH-V59 Residual Heat Removal 6" Gate Valve Westinghouse 1-RH-V61 Residual Heat Removal 6" Gate Valve Westinghouse 1-RH-V63 Residual Heat Removal 6" Gate Valve Westinghouse 1-RH-V65 Residual Heat Removal 6" Gate Valve Westinghouse 5. 1-SI-V3 Safety Injection 10" Gate Valve Westinghouse 1-SI-V17 Safety Injection 10" Gate Valve Westinghouse 1-SI-V32 Safety Injection 10" Gate Valve Westinghouse 1-SI-V47 Safety Injection 10" Gate Valve Westinghouse 6. 1-SI-V5 Safety Injection 10" Check Valve Westinghouse 1-SI-V6 Safety Injection 10" Check Valve Westinghouse 1-SI-V20 Safety Injection 10" Check Valve Westinghouse 1-SI-V21 Safety Injection 10" Check Valve . }lestinghouse 1-SI-V35 Safety Injection 10" Check Valve Westinghouse 1-SI-V36 Safety Injection 10" Check Valve Westinghouse 1-SI-V50 Safety Injection 10" Check Valve Westinghouse 1-SI-V51 Safety Injection 10" Check Valve Westinghouse 1-SI-V82 Safety Injection 6" Check Valve Westinghouse 1-SI-V87 Safety Injection 6" Check Valve Westinghouse Group

  • Pump I.D.

System Description Nbnufacturer 1. 1-RC-P-1A Reactor Coolant 31"x27.5" Centrifugal Pump Westinghouse 1-RC-P-1B Reactor Coolant 31"x27.5" Centrifugal Pump Westinghouse 1-RC-P-1C Reactor Coolant 31"x27.5" Centrifugal Pump Westinghouse 1-RC-P-1D Reactor Coolant 31"x27.5" Centrifugal Pump Westinghouse

  • Examinations required are limited to one (1) pump or valve in each group.

i l l Seabrook Ncc1 car Power Station Unit No. 1 t Relief From Preservice Inspectice Requirements 4 Relief Request: PR-6~ Component Identification: Steam Generator, Residual Meat Removal and Excess Letdown heat Exchanger Welds Code Class: 2 Examinatien Category: C-A and C-3 Code Requirement: f For Seabrook Unit No.1, a volunetriz (ultrasonic) examination of 109 percent of the weld length and 100% of the nozzle inner radius areas shall be conducted for the folleving items in accordance with ASME B&PV Code,1977 Edition through the Summer 1978 Addendum, Subarticle IWC-2500: .Iten DescriFeign C-1.10 Shell circumferential velds C-1.20 Head circumferential welds C-1,30 Tubcshect-to-Shell weld C-2.20 Nozzle to shell velds 'e Code Relief Requestt Purusant to IOCFR50.55(a)(g)5(iii), relief is requested from performing the preservice volumetric examination of the inaccessible portion cf the subject vessel velds. 3 Basis for Kelief: l Geometric configuration and permanent obstructions prohibit the performance of a 100 percent volumetric examinatica of each of the subject velds. The PSI limitations and the specific relief, as they apply to cach veld, are noted in the attached table for each component. Support for Relief / Alternate Examinations: 1 l' A. The subject welds received both volumetric exacination by radiography I and surface examinations during fsbrication in accordance with ASSIE [ Section III requirements which provide adequate assurance of the struc-tural integrity of the welds. B. A construction hydrostatic test was conducted successfully en the Class 1 pressure boundary, of which these welds are a part thereof, in accordance with the requiremetns of ASME Section III. C. In-service system leakage tests will be performed per Category C-H Table IWC-2500-1 each refueling cutage. I 4 f a

Relief Request: PR-6 Page 2 of 5 Table 1 Steam Generator Limitations =--- CRV Weld Exam I'* * ' IE"' Technique Qnfiguration/ Limitation Angle YdentifIcation Number (1) Number 1-RC-E-11A Seam 8 6465-005 C1.20 0' 0* Upper shell to hea.l. 4 plates 98% 1-RC-E ~.1A Seam 8 6465-011 C1.20 45* Circ, and Axtal Upper shell to head. 4 plates 98% 1-RC-E-IIA Seam 8 6465 C1.20 60* Circ. and Axial Upper shell to head, 4 plates 80% and surface contour. 1-RC-E-11A Seam 6 6465-006 C1.10 0* 0* Sheli to transition. 2 plates and l 96% 4 Instrumentation lines j 1-RC-E-11A Seam 6 6465-002 C1.10 45* Circ. and Axial Shell to transition. 2 plated and 96% ~ 4 Instrumentation. lines 1-RC-E-11A Seam 6 6465-003 C1.10 60* Circ. and Axial Shell to tr insition. 2 plates and 82% 4 instrumentation linest also i surface contour of weld 1-RC-E-11A Seam 5 6465-012 C1.10 60* Circ. and Axial Transition to shell. Surface 80% contour. 1-RC-E-IIA Seam 3 6465-010 C1.10 0* 0* Shell to stub barrel. Surface 99% gouge. 1-RC-E-11A Seam 3 6465-009 C1.10 45* Cire, and Axial Shell to stub barrel. Surface 99% gauge. 1-RC-E-11A Seam 3 6465-013 C1.10 60* Circ, and Axial Shell to stub barrel. Surface 91% gouge. 1-RC-E-11A Seam 2 6465-014 C1.30 45* Axial Stub barrel to tubesheet. Tube-86% sheet flange, and hand way. 1-RC-E-11A Seam 2 6465-015 C1.30 60* Axial Stub barrel to tubesheet. Tube-80% sheet flange and handway. 1-RC-E-IIA-16IR None C2.20 None None Steam outlet nozzle inner 0 *s radius /ID geometry 1-RC-E-11B-16IR None C2.20 None None Steam outlet nozzle inner 0% radius /ID geometry 1-RC-E-11C-161R None C2.20 None None Steam outlet nozzle inner 0 *6 radius /ID geometry 1-RC-E-11D-16IR None C2.20 None None steam outlet nozzle inner 0 *6 radius /ID geometry

Relirf Requ11t: PR-6 Page 3 of 5 Table 1 Steam Generator Limitations Data Code Weld Sheet Item Technique Configuration / Limitation ^"E " Identification Number (1) Number l-RC-E-llB Seam 6 6465-040 C1.10 0* 0* Transition to shell. 6 pads 95% l-RC-E-llB Seam 6 6465-033 C1.10 45* Axial Transition to shell. 6 pads 95% l-RC-E-llB Seam 6 6465-032 C1.10 60* Axial Transition to shell. 6 pads 95% l-RC-E-llB Seam 5 6465-040 C1.10 0* 0* Shell to transition. Surface 72% Contour. 1-RC-E-llB Seam 5 6465-030 C1.10 45* Circ. and Axial Shell to transition. Surface 75% contour. 1-RC-E-11B Seam 5 6465-032 C1.10 60* Circ. and Axial Shell to transition. Surface 79% Contour. 1-RC-E-11B Seam 3 6465-031 C1.10 0* 0* Shell to stub barrel. Surface 71% contour. 1-RC-E-IIB Seam 3 6465-033 Cl.10 45* Circ. and Axial Shell to stub barrel. Surface 79% Contour. 1-RC-E-IIB Seam 3 64650-032 C1.10 60" Circ. and Axial Shell to stub barrel. Surface 80% contour. 1-RC-E-llB-llNZ 6465-037 C2.20 0* 0* Nozzle to shell. Nozzel and 99% surface contour. 1-RC-E-IIB-llNZ 6465-038 C2.20 45* Circ. and Axial Nozzle to shell. Nozzle and 89% curface contour. 1-RC-E-IIB-llNZ 6465-039 C2.20 60* Circ. and Axial Nozzle to shell. Nozzle and 84% surface contour. 1-RC-E-IIC Seam 6 6465-040 C1.10 0* 0* Transition to shell. 6 pads 95% 1-RC-E-11C Seam 6 6465-039 C1.10 45* Axial Transition to shell. 6 pads 95% l-RC-E-IIC Seam 6 6465-041 C1.10 60* Axial fransition to shell. 6 pads 95% l-RC-E-llc Seam 5 6465-031 C1.10 0* 0* 3 hell to tt'nsition. Surface 77%

ontour,

~. - ~. ~. Relief R:quagt: PR U - i Page 4 of'S Table 1 + Steam Generator Limitations E" *

  • " " 9"*

Cov age Ident ication A gl Number (3) Number i 1-RC-E-11C Seam 5 6465-031 C1.10 45* Cire. and Axial Shell to transition. Surface 78% Contour. 1-RC-E-11C Seam 5 6465-032 Cl'.10 60* Circ. and Axial Shell to transition. Surface 78%. contour. 1-RC-E-11C -11 6467-8 C2.20 70* Skew (inner radius) Nozzle to shell. Surface contour 0% l-RC-E-11D Seam 6 6465-017 C1.10 0* 0* Transition to shell. Surface 88% contour and 6 pads. 1-RC-E-IID Seam 6 6465-019 C1.10 45' Circ. and Axial Transition to shell. Surface 91% contour and 6 pads. i 1-RC-E-IID Seam 6 6465-018 C1.10 60* Cire. and Axial Transition.to shell. Surface 92% contour and 6 pads. 4 l 1-RC-E-11D Seam 5 6465-017 C1.10 0* 0* Shell.to transition. Surface 85% contour for a 5" square area and weld contour, l 1-RC-E-11D Seam 5 6465-022 C1.10 45" Cire. and Axial Shell to transition. Surface 83% contour for a 5" square area and weld contour. l-RC-E-11D Seam 5 6465-018 C1.10 60* Circ. and Axial Shell to transition. Surface 79% contour for a 5" square area and weld contour. l-RC-E-11D 16NZ 6465-020 C2.20 0* O' Nozzle to shell. Nozzle and 57% and surface contour. 1-RC-E-11D 16NZ 6465-036 C2.20 45* Circ. and Axial Nozzle to.shell. Nozzle and 57% and surface contour. 1-RC-E-11D 16NZ 6465-021 C2.20 60* Circ. and Axial Nozzle to shell. Nozzle and 57% surface contour. i i 1. Data sheet number refers to da:a sheet containing imcomplete scan. 1

Relinf R: quint: PR-6 Pagu 5 of 5 Table 2 Exce ss Letdown HX and Regenerative HX Limitations k' eld Exam heet e Technique Configuration / Limitation ^"E * "*##E" Identification Number (1) Number -~ Permanent 1 Vee Axial 1-CS-E-3C 6487-4 C1 20 45 Head-to-Flange / Obstruction 46.4% 1 Vee Cire. Surface Geometry 1-REG-4A 6487-7 C1.10 45* b Vee Axial and Circ. Shell-to-Bonnet / Permanent 70.4% Channel Obstruction 1-REG-4B 6487-7 C1.10 45* h Vee Axial and Cire. Shell-to-Bonnet / Permanent 70.4% Channel Obstruction 1. Data sheet numbe r refers to data sheet con :aining inconplete scan.

F Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-7 Component Identification: RHR Heat Exchanger Gozzles Code Class: 2 Examination Category: C-B Code Item No.: C2.20 Code Requirement: For Seabrook Unit No. 1, volumetric and surface examinations of the nozzle-to-shell welds (C2.20) for the residual heat removal heat exchangers shall be conducted in accordance with ASME B&PV Code, 1977 Edition through the Summer 1978 Addendum, Subarticle IWC-2500. Code Relief Request: Pursuant to 10CFR50.55(a)(g)S(iii), relief is requested from performing the preservice ultrasonic examination of the nozzle to vessel welds on the tube side waterbox of the RHR Heat exchangers. Reason for Relief: Table IWC-2500-1. Category C-B, requires a volumetric examination of nozzle welds in vessels whose thickness exceeds 1/2" nominal. By reference to the Examination Requirements Figure, IWC-2500-4, it is apparent that this require-ment was intended for nozzles whose pressure retaining attachment weld thick-ness is equal to or greater than the vessel nominal thickness. In the case of the Seabrook RHR Heat Exchangers, the weld geometry for the inlet and out-let nozzles is such that the weld thickness is full penetration for the nozzle thickness (3/8") only. (See attached sketch Figure 1.) Additionally, the weld geometry does not lend itself to meaningful ultrasonic examination. Propo sed Alternate Examinations: 1. Since the weld thickness is ( 1/2" nominal, PSI examinations were per-formed in accordance with the requirements of Code Item Number C2.10 and Examination Requirements Figure IWC-2520-3 for nozzles in vessels 1/2" or less in nominal thickness. 2. The subject welds received both volumetric examination by radiography and surface examination during fabrication in accordance with the requirements of ASME Section III which provides adequate assurance of the structural integrity of the welds.

Relief Request: PR-7 Page 2 of 3 3. A preservice hydrostatic test was successfully conducted on the Class 2 portion of the heat exchanger, which includes the nozzle-to-shell welds, in accordance with ASME Section III. 4. Regular system pressure tests will be performed inservice in accordance with the requirements of Table IWC-2500-1, Category C-B. l

b r#"- Relief Rzquest: PR-7 Page 3 of 3 Seabrook Station Unit 1 Figure 1 40N*960SetOt'AN / / e4* 5 ao*

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i Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-8 Component Identification: Containment Building Spray Piping beyond the last downstream valve Code Class: 2 Examination Category: C-F Code Item No.: C5.20 Code Requirement: For Seabrook Unit No. 1, volumetric and surface examination of 100 percent of the length of each weld requiring examination shall be conducted in accor-dance with the ASME B&PV Code, Section XI, 1977 Edition through the Summer 1978 Addendum. Code Relief Request: Pursuant to 10CFR50.55(a)(g)5(iii), relief is requested f rom performing the preservice volumetric and surface examinations on the Containment Building Spray Headers beyond the last downstream valve. Reason for Relief: 1. The subject lines are normally empty and are required to function only in the unlikely event of a major loss of coolant accident or a main steam line break. 2. The subject lines are not exposed to fluctuating stresses, so that pro-pagation of cracks due to defects in the pipe is unlikely. 3. Spray piping welds are examined by radiography during fabr'ication, so that large defects that could cause catastrophic failure during system operation would be detected and repaired during fabrication and installa-tion of the piping. 4. This piping contains hundreds of open nozzles so that splits or cracks which do not directly cause catastrophic failure would not have a marked effect on the function of the system. 5. System pressure is low, so that pressure stresses in the piping would be unlikely to cause failure in the presence of small defects. Proposed Alternative Examinations: 1. The subject welds received volumetric examination by radiography during fabrication in accordance with ASME Section III requirements. Having met these requirements, adequate assurance of the structural integrity of the subject welds is provided.

~ -. l,_,---- Ralief Request: PR-8 Page 2 of 2 2. A Section III hydrostatic test was conducted successfully on the Class 2 pressure boundary, of which these welds are a part thereof. 3. During inservice, an air test to demonstrate unimpaired flow will be conducted on the subject portion of the Containment Building Spray Headers in accordance with ASME Section XI, Subparagraph IWC-5222(c). 4

t-Seabrook Nuclear Power Station Unit No. 1 Relief From Preservice Inspection Requirements Relief Request: PR-9 y Component Identification: Class 2 Piping Welds Code Class: 2 Examination Category: C-F Code Requirement: I' For Seabrook Unit No. 1, volumetric (ultrasonic) and surface examinations i of 100 percent of the length of each weld requiring examination shall be conducted in accordance with the ASME B&PV Code, Section XI,1977 Edition through the Summer 1978 Addendum. Code Relief Request: l Purusant to 10CFR50.55(a)(g)S(iii), relief is requested from performing the preservice volumetric and/or surface examinations on the inaccessible portions of the welds listed in Table 1 (attached). Basis for Relief: e Geometric configuration, permanent obstructions and/or structural inter-ferences, prohibit 100 percent examination coverage of the Code required = volume. Relief, is, therefore, requested from performing preservice exam-inations on the inaccessible portions of certain circumferential welds as noted in Table 1 (attached). I Proposed Alternative Examinations: A. The subject welds received volumetric examination by radiography during i fabrication in accordance with ASME Section III requirements. Having } met these requirements, adequate assurance of the structural integrity j of the subject welds is provided. B. A Section III hydrostatic test was conducted successfully on the Class 2 Pressure Boundary, of which these welds are a part thereof. C. In-service system leakage tests will be performed per Category C-H, Table IWC-2500-1 as well as surface and volumetric exams on the accessible por-7 tions of the welds shown on Table 1, as required by Section XI selection i criteria. Any advances in UT technology will be evaluated to determine its application for achieving maximum volume coverage and results and applied where deemed appropriate by New Hampphire Yankee. i I f .----_.~~r... ,___y. ,..--.m.,., r,,, ,,. _ ~ _ ,m..---.,

Table 1 PR-9 Pipe tield Scan Limitations Table INC-2500-1 Category C-F Pego 2 cf 3 Weld Data Code Exam Technique Configuration / Limitation CRV Identification Sheet Item Ang1c(2) Coverage Number (I) Number 1-RH-158-4-2 6462-294 C5.21 45*RL l Vee Axial Pipe-to-Flange / Metallurgy 50% 45*S } Vee Cire. Surface Geometry 1-MS-4002 6LU 6463-067 C5.22 45*S li Vee Axial Pipe LonFitudinal Su r f ac e i Vee Cire. Weld Scam Contour 99.6% MS-4000-41-4B 6463-038 C5.31 45*S Full Vee Axial 6" Branch Permanent i Vee Circ. Connection Obstruction 70% MS-4000-41-13B 6463-038 C5.31 45 S Full Vee Axial 6" Branch Permanent i Vee Circ. Connection Obstructions 59% MS-4001-41-4B 6463-038 C5.31 45*S Full Vee Axial 6" Branch Permanent lVee Circ. Connection Obstruction 70% MS-4003-37-33 6463-038 C5.31 45*S Full Vee Axial 6" Branch Permanent } Vee Cire. Connection Obstruction 95% MS-4001-41-3B 6463-038 C5.31 45*S Full Vee Axial 6" Branch Permanent 65% lVee Circ. Connection Obstruction i

Table 1 PR-9 Pipe Weld Scan Limitations Page 3 of 3 Table IWC-2500-1 Category C-F l E!e l d Data Code Exam Technique Configuration / Limitation CRV Coverage Identification Sheet Item Angle (2) Number (I) Number MS-4002-37-3B 6463-038 C5.31 45 S Full Vee Axial 6" Branch Permanent ] Vee Cire. Connection Obstruction 95% MS-4001-41-13B 6463-038 C 5.31 45*S Full Vee Axial 6" Branch Permanent 70% 1 Vee Circ. Connection Obstruction (1) Data sheet number,where given, refers to data sheet containing Lncomplete scan. Shear Wave (2) S = RL= Refracte d Longitudi nal Wave 4 ,}}

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