Text

Request for Relief from ASME Section XI Volumetric Examination Requirements - Fourth 10-Year Interval
	ML16188A269
Person / Time
Site:	Pilgrim
Issue date:	06/29/2016
From:	Perkins E; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PNPS-ISI-001
	Download: ML16188A269 (126)
	v • d • e

A Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station

=--=* Entergx 600 Rocky Hill Road Plymouth. MA 02360 June 29, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

. Requests for Relief from American Society of Mechanical Engineers (ASME)

Section XI Volumetric Examination Requirements - Fourth 10-Year Interval Pilgrim Nuclear Power Station Docket No. 50-293 Renewed License No. DPR-35 LETTER NUMBER: 2.16.036

Dear Sir or Madam:

Pursuant to 1O Code of Federal Regulations (CFR) 50.55a(g)(6)(i), Entergy Nuclear Operations, Inc. (Entergy) requests relief from the requirements of the ASME, Boiler and Pressure Vessel Code,Section XI pertaining to volumetric examinations at Pilgrim Nuclear Power Station (PNPS). In several locations, the required coverage cannot be obtained due to interference or geometry. Individual relief requests are provided in the attachments, divided by examination category.

10 CFR 50.55a(g)(5)(iii) requires that the basis for the determination of impracticality be submitted to the NRC for review and approval within 12 months after the expiration of the 120-month inspection interval. These reliefs are for the Fourth PNPS 10-Year lnservice Inspection Interval. The fourth 10-year interval started on July 1, 2005. The fourth 10-year interval ended June 30, 2015.'

There are no new regulatory commitments made in this submittal.

If you have any questions or require additional information, please contact me at (508) 830-8323.

Sincerely,

~g\"k~~ 4 Everett P. Perkins, Jr.

Regulatory Assurance Manager EPP/mew Attachments:

1. Request for Relief - PNPS-ISl-001

2. Request for Relief - PNPS-ISl-002

3. Request for Relief - PNPS-ISl-003

4. Request for Relief - PNPS-ISl-004

5. Request for Relief - PNPS-ISl-005

6. Component Limited Examination Information

Entergy Nuclear Operations, Inc. Letter No. 2.16.036 Pilgrim Nuclear Power Station Page 2 of 2 cc: Mr. Daniel H. Dorman Regional Administrator, Region I U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 Ms. Booma Venkataraman, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8C2A Washington, DC 20555 NRC Senior Resident Inspector Pilgrim Nuclear Power Station

Attachment 1 to Letter 2.16.036 Request for Relief - PNPS-151-001 (58 Pages) to Letter 2.16.036 Page 1 of 58 REQUEST FOR RELIEF - PNPS-ISl-001 Components I Reactor Vessel Shell and Head welds I See Attachment 6 Table 1-1 Numbers: for component numbers Code Classes: American Society of Mechanical Engineers (ASME) Code Class 1

References:

ASME Section XI 1998 Edition w/ 2000 Addenda, Table IW8-2500-1, ASME Section XI 2001 Edition w/ 2003 Addenda, Table IW8-2500-1, Code Case N-460 Examination Category:* 8-A Item Number{s) 81.12, 81.21

==

Description:==

Pressure Retaining Welds in Reactor Vessels - Inspection Program 8

Unit/ Inspection Pilgrim Nuclear Power Station (PNPS) I Fourth (4th) 10-Year Interval Interval Applicability:

I. CODE REQUIREMENTS ASME Section XI, Table IW8-2500-1, Examination Category 8-A, "Pressure Retaining Welds in Reactor Vessels":

Item 81 .12 requires a volumetric examination of Reactor Vessel Longitudinal Shell Weld volume, as depicted in Figures IW8-2500-2 as applicable.

Item 81 .21 requires a volumetric examination of Reactor Vessel Circumferential Head Weld volume, as depicted in Figures IW8-2500-3 as applicable.

II. RELIEF REQUEST Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Nuclear Operations, Inc. (Entergy) requests relief from achieving the Code-required coverage when performing volumetric examinations of the components identified in Attachment 6 Table 1-1.

Ill. BASIS FOR RELIEF During ultrasonic examination of the Reactor Vessel (RV) shell and head welds listed in Table 1-1, greater than 90% coverage of the required examination volume could not be obtained. Examinations were performed utilizing a POI Appendix VIII Supplement 4 and Supplement 6 qualified procedure specific to Reactor Vessel Assembly welds.

Due to the geometric configuration of the components, effective volumetric examination could only be performed from outside the vessel on the RV circumferential head weld.

The of 60"refracted longitudinal (RL) beam angle used in the axial and circumferential direction was not able to achieve greater than 90% code required volume of the RV to Letter 2.16.036 Page 2 of 58 circumferential head weld as required by Code Case N-460. Also, due to plant configuration, effective volumetric examination could only be performed from the inside of the vessel on the RV Longitudinal Shell welds. The use of 45°shear and 70° RL beam angles in the axial and circumferential direction were not able to achieve greater than 90% code required volume of the RV Longitudinal Shell welds. See Attachment 6 Table 1-1 for additional information.

Radiography is not practical on this type of vessel welds configuration, which prevent placement of the film and exposure source. To effectively perform any significant additional Code allowable ultrasonic examinations, modification and/or replacement of the component would be required. The examinations performed on the subject items in addition to the examination of other vessel welds contained in the lnservice Inspection program would detect generic degradation, if it existed, therefore demonstrating an acceptable level of integrity.

IV. PROPOSED ALTERNATIVE EXAMINATIONS No alternative testing is proposed at this time. Entergy has examined these welds to the extent practical and will continue to perform pressure testing on the subject components as required by the Code.

V. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:

°The Commission will evaluate determinations under paragraph (g)(5) of this section that Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

Entergy believes that it is impractical to obtain greater examination coverage on these welds. To effectively obtain significant additional coverage woula necessitate modification and/or replacement of the component. The examinations performed on the subject welds, in addition to the examination of similar welds contained in the program, would detect generic degradation, if it existed, demonstrating an acceptable level of integrity. Entergy requests the proposed relief be authorized pursuant to 10 CFR 50.55a(g)(6)(i).

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Rounding metliods moy effect calculotMI values. FV*Full \IOlume, NS-Near Surface. Weld length in inches-

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HITACHI Pilgrim Unit 1 Reference Drawings co :::0 00 "ti
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&am Volume: 67.llO Area Sq. in. Automated AA.Ito mated Automated Auti.Jmated 70° T-SCOO CW~Sll NSl A 9.8 9.8 0.1 15.00 OA%
70' T*SCOO CCW IS4 NS] A 9.8 9,S 0.1 15.00 OA'Hi 5..()%
45*r-sc.on IS6 FVJ A I 57.6 S?.6 0.9 15.00 70° P-Sc<ln UP ISJl NSI A 9.8 9.B 0.1 15.00 OA%
1rr P-SCon ON lS4 NSI A. 9.8 9JI 0.1 15.00 0.4% :::0
"'C 45" P* ~ 1:.0 l"VI A 57.6 57.6 0.9 15.vu 50% < I r I 70" T-Sc1:1n CVJ tsi. NSI t.l I
70" f-Scxm ccw iS4 l'fSl 1 (,,)
(,,)
45* T-Scan ts6 FVJ 00 70' P*Saln UP IS/I N51 (')
70- P-SCOO ON lS4 NSJ 4 s* P-scon 156 FVI 70" T*Smn ON 154 NSI 70-f*Scon CCWIS4 ~I 45* T-Scon CS6 FVJ 70' P*Scon UP (54 NSI I
70"'P-SC:Qn ON 154 NS] -
45' P*Sam 156 FVJ
'*' Totol Composite Coverage* 11.6%
.... 0 tln.tE Comm~nts: A
AUtomotecl scor'W\ing was restncted di.re to the stvoud repair hardware. Scanner heod fooo9 down.
Nole. R(lllnding methods moy offe<t colclAoted volues.. fV-FIJll volume, NS*NeorSurioce. Weld lenoth in inches.
HTACH Pilgrim Unit 1 Reference Drawings Viewed from Back Side of Package

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~~ Coverage Calculation Sheet Pilgrim Unit 1- RFO 20 Weld RPV-L-2-339A (Shell Course 3) cooe CROSS.SECTIONAL AREA TOTAl CODE COVERAGE Percerit W d l.e'ngth = 111.90 A.equfred &om Areo Sc:onned of Area W Id Length Percent El<<lm Volume
52.40 ArlCI SQ, In. Automated .Automa~ Alltomoted Automcrted 7<Y' li*Scon CWIS4 NSI A 7.1 1.? 0.0 26.90 02%
70.. T*Scon CCWIS4 NSI A 7.7 6.0 0.1 26.90 0.7%
45" T-ScanlS6 FVJ A 44.7 31.2 0.6 26.90 7.2%
70" P*Scan UP ($11 NS} A 1.1 I I 6.8 0.1 26.90 0.8%
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10* P-Scan ON *~ l"SI 45* P*Scan ts6 fVl
% Total Composite Covernge ... 18.0%
.... ow*-
lComments: A* .Automateod scanning wcs restricted due to proJ<imfty of Guide Rod. Feedwoh!r End Brod<el ond lntemol core Spray piping.
1 Scanner tM!CJd facing down.
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Note - Roooding methods m~ affect ookuloted volues. FV-full 11olume, NS-~ear Surface. Weld lellQthin inches.
H ITACHI Pilgrim Unit 1 Reference Drawings Viewed from Back Side of Package
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HITACHI Coverage Calculation Sheet Pilgr im Unit 1- RFO 20 Weld RPV-L-2-3398 [Shell Course 3t CODE CROSS-SECTIQ~Al AREA TOTAt. CODE COVERAGE Percent Weld L n9th* 111.90 Required EJcom Area S(anned ofAfeo W.Jd I. ngth P9rc:ent E)cam Volume = 52.40 Ateo 5<1. in. Automated Auto mat.cl Automotitd Avtomoted 70"T-Scon CWl5'1 NSI A 7.7 7.7 O.l 45.50 1.S'K 70" 1-Si;;on CON IS4 NSI A 7.7 7,7 0.1 45.SO l .S'Jl6 45* T* Scan [S6 FV) A 4A.7 44.7 0.9 45.50 17.3%
70- P-Sc:on UP {$4 NSI A 7.7 1.7 0,1 4S.50 1.5%
70" P-Scof'I ON IS4 NSJ A 7.7 7.7 0.1 4S.SO 1.5% ::ti 45" P*Scari 156 FVJ A 44.7 ~.7 0.9 45.50 17.3% '"C
< I 70" T~scon cw 154 NSJ B 7.7 7.7 0.1 29.00 1.09' r I NI 70" T-Sam CON IS4 NSI 13 7.7 1,7 0.1 29.00 1.0% (,.)
45" T-Scan CS6 FV1 B 44.7 44.7 0.9 29.00 11.1% (..,)
70" P-Scon UP (54 NSI B 7.7 1.7 O.l 29.00 1.09' c.o CJ 70" P-Scon ON IS4 NS2 B 7.7 7.7 O.l 29.00 1.0%
45* P-Scan (56 FVJ B 44.7 6.4.7 0.9 l~.00 11.1%
70" T-Scon CW CS4 NSI c 7.7 7,J 0.1 3.00 0,.l96 70' T*Sean CON ISli NSI c 7.7 3.2 0.0 J,00 0.0%
llS" T-SCon [SS FV) c 44.7 39.4 o.a 3.00 1.09' 70" P-Scori UP l54 NSJ . c 7.7 2.5 0.0 3.00 0.0%
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% Totol Composite Ccwefage
69.0%
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COmments: A- Automated scanning was not r@~rkt.ed Seonner heod toeing down.
B- Automated sconnfn9 wos nol restric:led. scanner he<id focing up.
C - Aulomoted sconnif'lg wos r"'strided. Specimen brod<el Scaooer head facing up.
Note
ROl.WldintJ methods mew affect colculatecl values. FV-Full volume. NS-:Neor Surfrxe. wetcl lel"IQth in 1rw:hes.
HITACHI Pilgrim Unit 1 Reference Drawings VieNed from Back Side of Package
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HITACHI Pilgrim Unit 1 Reference Drawings 3-339A 116° 509.9"
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HITACHI Pilgrim Unit 1 Reference Drawings 3-339A 116° 509.9" 352.6'
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Area Sa. In. Automated A"tomcrted Aut.amat&d Automated 70-T-Scan CWl5'1 NSI A 1.7 7.7 0.1 32.90 L1%
70-T-Scon*CCWl54 NSI *'
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45" T-ScaolS6 FVl A 44.7 44.7 0.9 32.90 12.5%
7r:r P*Scan UP ts4 NS} A 7.7 7.7 ..
O.l 32.90 1.1%
70" P-Scon ON 154 NSl A 7.7 -* ... 7.7 0.1 :3i,90 1.1% ;;o
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45"T-SC<lli IS6 FVI 44.7 44.7 0.9 49.00 18.7% (.,.)
(0 70'" P*Scan UP IS4 NSI B 7.7 7.7 0.1 49.00 1.6% ()
1r:r P-Scan ON 154 NSJ B 7,7 7.7 0.1 49.00 1.6%
45"-P*Scan i;>o rv1 B 44.7 44.7 0.9 49.00 lB.r'ltl
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45* T*Scon 156 fVJ 70° P.Scan UPtS411151 70"' P-SCon 0111 (54 NSl 45* P.!)C_o.n 1sfi FVI .
% Total Composite Coveroge = 73.2%
"*" 0 flt.If~
Comments: A* Atitomoted SCtlnnlng wos restricted due ta the feedwoter sporger. Sconner head fating ifown.
B- Auto1'11(1ted scanning was restricted due to the cote spray piping. Samn~r !lead facing ~-
Nole - R<:Kindiog methods may affect ailclJol.l!d valll@S. FV*Full volvrne. f\IS.-Neo.r Surfoce. Weld length ln inches.
HITACHI Pilgrim Unit 1 Reference Drawings Vie.Ned from Back Side of Package 1l.l1' 5QllAld6
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HITACHI Pilgrim Unit 1 Reference Drawings
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TACH Pilgrim Unit 1 Reference Drawings 462.4" 236°
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Manual RPV Examination 8 HITACHI Coverage Calculation Sheet Pilgrim Dollar Plate Weld - RPV-BH-Cl CODE CROSS.SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length ;; 596.0 Required Exam Area Scanned of Area Weld J.ength Percent Exam Volume= 29.S Area So.in. Manual Achieved Achieved Achieved 60Q T-Scon UP (S4 UCl A 3.6 2.3 3.9% 588.0 1.9%
60° T-Scon ON 154 UC) A 3.6 0.0 0.0% 588.0 0.0%
. 60° T-Scon (56 FV) A 25.9 23.3 79.0% 588.0 39.0%
60° P-Scan CW (54 UC) A 3.6 3.6 6.1% 588.0 3.0%
60° P-Scan CON (54 UC) A 3.6 3.6 6.1% 588.0 3.0%
60° P-Scan 156 FVI A 25.9 12.2 41.4% 588.0 20.4%
.,,;;o 60° T-5con UP (54 UC) B 3.6 2.1 3.6% 8.0 0.0%
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0 Pilgrim RPV-BH-1 Weld 61:1'5" Eia-< "°*"1le
l 6 Sc;.
60"56 E><<'.r> Girne . zss ~
6D'!" S4 ~ ~~ . 2.J I l l )4.11\.
OO'TS6flllll'l~~*U3S;j. n fiO"> 5" £>cr ..W.me ~
3 6 f 3.6 r.:i 1n 60"* S6 ---*1215'\
Exam natton Seo um1ts Area not sca nned in eit her the Area not scanne d in t he para ll el Area not covere d due to t hermocoupl e Transverse or Para ll el directions looking to w eld direction looking for a><i al i nterfer ences, noted on previous examination for axial and clrc flaw s. fla ws re port and PR R-42 for Interval 3
Attachment 2 to Letter 2.16.036 Request for Relief- PNPS-151-002 (34 Pages) to Letter 2.16.036 Page 1 of 34 REQUEST FOR RELIEF - PNPS-ISl-002 Components I Reactor Vessel Nozzle Welds I See Attachment 6 Table 2-1 for Numbers: component numbers Code Classes: American Society of Mechanical Engineers (ASME) Code Class 1
References:
ASME Section XI 1998 Edition w/ 2000 Addenda, Table IW8-2500-1, ASM E Section XI 2001 Edition w/ 2003 Addenda , Table IW8-2500-1, Code Case N-460 Examination Category: 8-D Item Number(s) 83.90
==
Description:==
Full Penetration Welded Nozzles in Vessels - Inspection Program 8 Unit/ Inspection Pilgrim Nuclear Power Station (PNPS) I Fourth (4th) 10-Year Interval Interval Applicability:
I. CODE REQUIREMENTS ASME Section XI , Table IW8-2500-1, Examination Category 8-D, "Full Penetration Welded Nozzles in Vessels - Inspection Program 8":
Item 83.90 requires a volumetric examination of Reactor Vessel Nozzle-to-Vessel Weld volume, as depicted in Figures IW8-2500-7(a) through (d), as applicable.
II. RELIEF REQUEST Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Nuclear Operations, Inc. (Entergy) requests relief from achieving the Code-required coverage when performing volumetric examinations of the components identified in Attachment 6 Table 2-1.
Ill. BASIS FOR RELIEF During ultrasonic examination of the non-Appendix VIII Pressurizer Nozzle-to-Vessel welds listed in Attachment 6 Table 2-1, greater than 90% coverage of the required examination volume could not be obtained. Examinations were performed utilizing Entergy approved procedures specific to ferretic vessels greater than 2 inches in thickness .
Due to the geometric configuration of the components, effective volumetric examination could only be performed from the shell side of the welds. Theo*, 45 °, 60° and 70 " beam angles used in the axial and circumferential direction were not able to achieve greater to Letter 2.16.036 Page 2 of 34 than 90% code required volume as required by Code Case N-460. See Attachment 6 Table 2-1 for additional information .
Radiography is not practical on these types of nozzle-to-vessel weld configurations, which prevent placement of the film and exposure source. To effectively perform any significant additional Code allowable ultrasonic examinations, modification and/or replacement of the component would be required. The examinations performed on the subject items in addition to the examination of other vessel welds contained in the lnservice Inspection program would detect generic degradation, if it existed, therefore demonstrating an acceptable level of integrity.
IV. PROPOSED ALTERNATIVE EXAMINATIONS No alternative testing is proposed at this time. Entergy has examined these welds to the extent practical and will continue to perform pressure testing on the subject components as required by the Code.
V. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:
The Commission will evaluate determinations under paragraph (g)(5) of this section that Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Entergy believes that it is impractical to obtain greater examination coverage on these welds. To effectively obtain significant additional coverage would necessitate modification and/or replacement of the component. The examinations performed on the subject welds, in addition to the examination of similar welds contained in the program, would detect generic degradation, if it existed, demonstrating an acceptable level of integrity. Entergy requests the proposed relief be authorized pursuant to 10 CFR 50.55a(g)(6)(i).
Reactor Pressure Vessel Coverage
~ ;( ) HITACHI Calculation Sheet
~
Pilgrim Unit-1 RF0-17 Weld RPV-NlA-NV CODE CROSS-SECTIONAL AREA TOTAl CODE COVERAGE Required Exam Percent Weld Length = 360 Area sq. in. Area Scanned ofAreo Weld Length Percent
!:Mam Volume = 29.7 IRS-Scan LKCW 1541 A 4.1 4.1 13.8% 360 3.5%
IRS*Scon LKCCW IS4} A 4.1 4.1 13.8% 360 3.5%
60' P-Scon IS61 A ZS.6 ts 5.1% 360 2.5%
60° T-Scon 1541 A 4.1 4.1 13.8% 360 6.9%
60' T*Scan 1561 A 25.6 16.3 54.9% 360 27.4%
ti "ti
< I z.....
~
z
% Total Composite Coverage = 43.8%
1
0 9/l)/Ol Comments A* Scanned oreo 360'. Scanning limited due to nozzle configuration.
Note
Rounding methods moy affect r-1llculoted values. 54-Supplement 4 underclod volume, 56-Supplement 6 volume. Weld lenoth in deorees to Letter 2.16.036 Page 4 of 34 RPV-N1A-NV Pilgrim Nl Nozzle - Recirculation Outlet 6(J~S4&.1R$(J<OmValume=4, 1 Sq. In 60" SG EXam Volume= 25.6 Sq. tn.
6(1° S4 T-Scon Exam Volume .. 4.1 Sq. In 60" S6 T-Scon Exam Volume- = 1.6-3 5q. tn.
IRS P-Scan Exam Volume,. 4.1 Sq_In 60" 56 P-Scoo Exom Volime = 1-S Sq. In.
15.r W'l-Scon I
Area not scanned in the Area not scanned in either parallel to weld direction the Transverse or Parallel looking for axial flaws directions looking for axial and circ flaws .
~; , Reactor Pressure Vessel Coverage HITACHI Calculation Sheet Pilgrim Unit-1 RF0-17 Weld RPV-N2A-NV CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Required Exam Percent Weld length = 360 Area sq. In. Area Scanned of Area Weld Length Percent Exam Volume
36.2 IRS-Scon LKCW 1541 A 4.0 4.0 11.0% 360 2.8%
IRS-Scon lKCCW 1541 A 4.0 4.0 ll.0% 360 2.8%
60" P-Scan 1561 A 32.2 3.3 9.1% 360 4.6%
60* T-Seen (541 A 4.0 4.0 11.0% 360 5.5%
60" T-Scon 1561 A 32.2 13.0 35.9% 360 18.0%
o
-a
<om Volume~ 4.0 Sq. In 60' 56 T-Scon £lCom Volume* 13.0 Sq. In.
IRS P*Scon Ellom Volume" 4.0 Sq. In 60' 56 P*Scon EKOm Volume" 3.3 Sq. In.
!SY 60' T*Sc-cm I
Area not scanned In the Area not scanned in either the parallel to weld direction Transverse or Parallel looking for axial flaws directions looking for axial and
/
. Reactor Pressure Vessel Coverage HITACHI Calculation Sheet Pilgrim Unit-1 RF0-17 Weld RPV-N28-NV CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Required Eleam Percent Weld Length
360 Area sq. In. Area Scanned of Area Weld Length Percent Exam Volume"' 36.2 IRS-Scan LKCW IS41 A 4.0 4.0 11.0% 360 2.8%
IRS-Scan LKCCW (541 A 4.0 4.0 11.0% 360 2.8%
60" P-Scon 1561 A 32.2 3.3 9.1% 360 4.6%
60* T-5con (541 A 4.0 4.0 11.0% 360 S.5%
WT-Scan 1561 A 32.2 13.0 35.9% 360 18.0%
0 "tJ
< I z
I\)
CDI z
% Total Composite Coverage = 33.6%
... 0 flll!Ol Comments A* Scanned area 360'. Scanning limited due to nozzle configuration.
Note
Roundina metbQds may affect colculated values. 54-Supplement 4 underclod volume, 56-Supplement 6 volume. Weld length in degree~
c:::::: - "/ l . - J&J ,_ 4 .f_ "'
to Letter 2 .16.036 Page 8 of 34 RPV-N2B-NV Pilgrim N2 Nozzle - Recirculation Inlet 60° 54 &IRS Exam Volume .. 4.0 Sq. In 60' S6 Exam Volume= 32.2 Sq. In.
60" S4 T-Scon Exam Volume= 4.0 Sq. In 60° S6 T-Scon Exam Volume"' 13.0 Sq. In.
IRS P-Scon Elcom Volume = 4.0 Sq. In 60' 56 P-Scon Exam Volume =3.3 Sq. In.
t-----------1 Area not scanned in the /Vea not SC<Jnned in either the parallel to weld direction Transverse or Parallel looking for axial flaws directions looking for axial and
m.--..::..
HITACHI Reactor Pressure Vessel Coverage Calculation Sheet Pilgrim Unit-1 RF0-17 Weld RPV*N2C-NV CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Required Exam Percent Weld Length
360 Area sq. In. Area Scanned of Area Weld Length Percent EHomVolume* 36.2 IRS-Scan LKCW IS41 A 4.0 4.0 110% 360 2.8%
IRS-Scan LKCCW IS41 A 4.0 4.0 110% 360 2.8%
60" P-Scon lS61 A 32.2 3.3 9.1% 360 4.6%
60" T-Scan (541 A 4.0 4.0 11.0% 360 5.5%
bU" T-Scan !S61 A 32.2 13.0 35.9% JOU 18.0%
o
-a
< I zN
(')
z
% Total Composite Coverage= 33.6%
0 !lllll<ll Comments A - Scanned area 360°. Scanning limited due to nozzle configuration.
Note - Roundina methods may offec:Lc.alculoted values. 54-Supptement 4 underclad volume. 56-Supplement 6 volume. Weld lenath in degrees
"'"'- /_.)' <:* J
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to Letter 2.16.036 Page 10 of 34 RPV-N2C-NV Pilgrim NZ Nozzle - Recirculation Inlet 60° S4 & IRS Exam Volume = 4.0 Sq. In 60° S6 Exam Volume .. 32.2 Sq. In.
60" S4 T-Scan Exam Volume = 4.0 Sq. In 60" S6 T-Scan Exam Volume
13.0 Sq. In.
IRS P-Scan Exam Volume 2 4.0 Sq. In 60° S6 P-Scon Exam Volume= 3.3 Sq. tn.
l en 51.
Area not scanned in the Area not scanned in either parallel to weld direction the Transverse or Parallel looking for axial fl aws directions looking for axial and circ flaws .
e GE Energy* Nuclear Reactor Pressure Vessel Coverage Calculation Sheet Pilgrim Unit-1 , 2007 RPV-N3A-NV CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume= 27.6 Area Sa. In. Area Scanned of Area Weld Length Percent 60° T-Scan l $4 A* 4.5 4.5 16.3% 360 8.2%
60° T*Scan I 56 A 23.1 9.1 33.0% 360 16.5%
IRS P*Scan S4 A 4.5 4.5 16.3% 360 8.2"k
0 S0° P*Scan ($6) A 23.1 2.8 10.1% 360 5.1% -a S0° T*Scan1 S4 z'
(...)
so* T*Scan SS
~
IRS P*Scan $4 z 60" P*Scan (SS) <
so* T -Scan S4 so* T-Scan ss IRS P-Scan S4 60° P-Scan (S6 60° T-Scan lS4 so* T*Scan* 56 IRS P-Scan 54 so* P*Scan (86)
% Total Composite Coverage = 37.9%
flev 0 9123.<liS Comments:
Examination volume in accordance with Code Case N*613-1.
A* - Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed iaw. 1OCFFl50.55a.
Note - Rounding methods may affect calculated values. Weld lenoth in deQrees.
/c;v.,. <e.../ i ~ c; ,_____ ' lx ) .;I _,,, .vh,_/..., ...,.
to Letter 2.16 .036 Page 12 of 34 RPV-N3A-NV Pilgrim Weld N3 Main Steam 60° FV Exam Volume
23. 1 Sq. In.
=
so* (Inner 15% n Exam Ve>Une <4.5 Sq. In.
60" FV T-5can achieved ,. 9.1 Sq. In.
60" (Inner 1s%n T-Scan achieved= 4.5 Sq. In.
60" FV P-Scan ac:tlieved
2.8 Sq. In.
so* (Inner 1s%n IR & P-Scan achieved= 4 .5 Sq. In.
Exam vok.Jme in accordane& with Code Case N-613-1 .
50*p 60"T I
Area not scanned in either t he Area not scanned in the Transverse or Parallel directions parallel to weld direction looking for a>tlal and clrc flaws.
looking for axial flaws
Reactor Pressure Vessel
GE E""'fly - Nuclear Coverage Calculation Sheet Pilgrim Unit-1, 2007 RPV-N3B-NV CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 27.6 Area SQ. In. Area Scanned of Area Weld Length Percent 60° T-Scan (S4l A* 4.5 4.5 16.3% 360 8.2%
60° T*Scan CS61 IRS P-Scan S4 so* P*Scan CS6)
A A
23.1 4.5 9 .1 4.5 33.0%
16.3%
360 360 16.5%
8.2% .,,;::o A 23.1 2.8 10.1% 360 5.1% <I z
(,.)
60° T -Scan <S4 OJ 60° T-Scan IS6l I IRS P-Scan CS4\ z 60° P-Scan (S6l <
60° T*Scan S4l 60° T-Scan S6 IRS P-Scan S4 so* P*Scan S6 60° T-Scan CS4l so* T-Scan S6 IRS P-Scan S4 60° P*Scan (S6)
% Total Composite Coverage = 37.9%
Rf\1091:1)115 Comments:
Examination volume in accordance with Code Case N-613-1 .
A'
Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed law. 10CFRS0.55a.
Note - Rounding methods may affect calculated~Wetd length in decrees.
/6....u../ ~-~ ,.,s; <:;;.,, ' / __x__ ) ,,._,,,, v/.. .. /......,.
to Letter 2.16 .036 Page 14 of 34 RPV-N3B-NV Pilgrim Weld N3 Main Steam 60" FV Exam Volume "23.1 Sq. In.
60' (Inner 15% T) Exam Volume" 4.5 Sq. In.
60' FV T-5can actlleved " 9.1 Sq. In.
60' (Inner 15%T) T-Scan achieved "4.5 Sq. In.
60" FV P*Salo achieved : 2.8 Sq. In.
60' (loner 15%T) IR & P-Scan achieved= 4.5 Sq. In.
Exam volurne In acoonlance wi1h Code Case N-613-1 .
60'T I
Area not scanned In the Area nol scanned in either the parallel to weld direction Transverse or Parallel looking for axial flaws directions looking for axial and
Reactor Pressure Vessel
GE Energy* Nuclear Coverage Calculation Sheet Pilgrim Unit-1, 2007 RPV-N3C-NV CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length :: 360. Required Exam Percent Exam Volume= 27.6 Area Sq. In. Area Scanned of Area Weld Length Percent 60° T*Scan S4) A* 4.5 4.5 16.3% 360 8.2"/o 60° T*Scan t S6) A 23 .1 9.1 33.0% 360 16.5%
o IRS P-Scan S4) A 4.5 4.5 16.3% 360 8.2% \J 60° P* Scan ($6} A 23.1 2.8 10.1% 360 5.1% <I zw so* T-Scan CS4) n 60° T -Scan S6) I IRS P-Scan S4) z 60° P-scan S6) <
60° T*Scan $4}
60° T-Scan SS)
IRS P-Scan S4) 60° P-Scan (S6) so* T*Scan S4lso* T-scan SS)
IRS P-Scan S4lso* P*Scan (S6)
% Total Composite Coverage = 37.9%
~ - 0 9'2~
Comments:
Examination volume in accordance with Code Case N-613-1.
A'* Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed law. 10CFA50.55a.
Note - Roundino methods mav affect calculated values. Weld lenoth in deorees
2-. -.....-.i J, . j),v__ I '-
to Letter 2.16.036 Page 16 of 34 RPV-N3C-NV Pilgrim Weld N3 Main Steam 60' Fl/ Exam Volume ~ 23.1 Sq. In.
n 60°(I..-111% Exam Volume* 4 .5 Sq. In.
60° Fl/ T*Sa!n achieved
9.1 Sq. In.
=
60° {Inn<< Ui%T) T-$can achlelled 4.5 Sq. In.
eo*FVP-5eanachieved=L85q. ln.
60°(Inner15%T) IR & P-&:an achieved= 4.5 Sq. In.
eum volume In 8CCOfdance with Code Case N-613-1 .
eo*p oo*T Area not sc<1nned in the Area not scanned in either the parallel to weld direction Transverse or Parallel looking for aMial flaws directions looking for axial and
Reactor Pressure Vessel
GE Energy* Nuclear Coverage Calculation Sheet Pilgrim Unit-1, 2007 RPV-N3D-NV CODE CROSS.SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 27.6 Alea Sa. In. Alea Scanned of Area Weld Length Percent 60° T-Scan lS4l A" 4.5 4.5 16.3% 360 8.2%
60° T*Scan (86) A 23.1 9.1 33.0% 360 16.5%
IRS P-Scan (S4l A 4.5 4.5 16.3% 360 8.2%
60° P*Scan (S6) A 23.1 2.8 10.1% 360 5.1% ;;o
""C 60° T*Scan lS4l <om Volt.ml! = 9.6 Sq II\
60" 56 f><om Volume
Sll.9 Sq. In 60" S4 IRS-Scan LKCW ochievl!d = 9.6 Sq. In 60" 54 IRS*Scon LKCCW o~
9.6 Sq. In, 60° 56 P-Scon ocNeved = 14.0 Sq. In.
60" S4 T-Scon ochieved
9.6 Sq, In.
60° 56 T-Scon achieved* l0.4 Sq. In.
Area not scanned in the Area not scanned in either the parallel to weld direction Transverse or Parallel directions looking for axial flaws loo ing for airial and circ flaws.
I HITACHI Reactor Pressure Vessel Coverage Pilgrim RF0-18, 2011 N4B - Feedwater Calculation Sheet CODE CROSS-SECTIONAL AREA TOTALCOOECOVERAGE Required Exom Percent Weld Length = 360 Area sq. In. Area Scanned of Areo Weld length Percent EKom Volume .. &i..s IRS-Scan LKCW (541 A 9.6 9.6 14.996 360 3. 796 IRS-Scan LKCCW IS41 A 9.6 9.6 14.996 360 3.7%
60" P-Scan (561 A 54.9 14.0 21.7% 360 10.996 60" T-Scon 1541 A 9.6 9.6 14.996 360 7.496 60" 1-scon 1561 A 54.9 30.4 41.196 .l60 23.696
0 "C
Idirections looking for axial flaws looking for axial and circ flaws.
I HITACHI Reactor Pressure Vessel Coverage Pilgrim RF0-18, 2011 N4C - Feedwater Calculation Sheet CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Required EMam Percent Weld Length = 360 Area sq. In. Area Scanned of Area Weld Length Percent EMam Volume = 64.S IRS-Scan LKCW IS41 A 9.6 9.6 14.9% 360 3.7'16 IRS-Scan LKCCW 154) A 9.6 9.6 14.9'16 360 3.796 60" P*Scon (S61 A 54.9 14.0 21.7% 360 10.996 60" T*Scon (S4l A 9.6 9.6 14.996 360 7.496 w* T-Scan tS61 A 54.9 30.11 47.1% .>DU 23.b'lb
o
"'C
mments A* Scanned oreo 360*. Scanning limited due to nozzle configuration.
Note
Rounding methods moy affect colculoted values. 54-Supplement 4 underclad volume, 56-Supplement 6 volume. Weld length in deorees Report PNPS-RFOlB-017 Page 5 of 7 to Letter 2.16.036 Page 24 of 34 RPV-N4C-NV Pilgrim Feedwater Nozzle 60" S4 EllOITI Volume = 9.6 Sq. In.
60" S6 El<orn Volume
54.9 Sq. In.
60" S4 IRS* Scon LJ<CW achieved = 9.6 Sq. In.
60" 54 IRS-SCOll LKCCW achieved= 9.6 Sq. In.
60" 56 P*SCon ochieved
14.0 Sq. In.
60" S4 T*Scan achieved* 9.6 Sq. In.
60" S6 T*Scan achl!wd = 30.4 Sq. In.
Area not scanned inthe Area not scanned in either the
parallel to weld direction Transverse or Parallel directions looking for axial flaws looking for axial and circ flaws.
I HITACHI Reactor Pressure Vessel Coverage Pilgrim RF0-18, 2011 N4D - Feedwoter Calculation Sheet CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Required Exam Percent Weld Length = 360 Area sq. In. AntoScaMed of Area Weld Length Percent Eicam Volume* 64.S IRS*Scan LKCWIS41 A 9.6 9.6 14.9% 360 3.796 IRS*Scan LKCCW 1541 A 9.6 9.6 14.9% 360 3.796 60" P-Scon 1561 A 54.9 14.0 21.7% 360 10.9%
60" T-Scon 1541 A 9.6 9.6 14.9% 360 7.4%
w- T-scan 1561 A 54.9 30.4 47.J.'lf> 360 23.696
a "ti
<I z
~
cI z
% Total Composite Coverage "' 49.3%
Root.* f/lJ/C!
Comments A- Scanned area 360°. Scanning limited due to nozzle configuration.
Note - RaundinQ methods may affect calculated values. 54-Suoolement 4 underclad volume. 56-Supplement 6 volume. Weld length in decrees Report PNPS-RFOlB-019 Page 5 of7 to Letter 2.16.036 Page 26 of 34 RPV-N4D-NV Pilgrim Feedwater Nozzle 60" 54 Exam Volume
9.6 Sq. In.
60" S6 Exom Volume
54.9 Sq. In.
60" 54 IRS-Scan LKCW achieved "' 9.6 Sq. In.
60" 54 IRS-Scan LKCCW ochleved = 9.6 Sq. In.
60" 56 P-SCan achieved* 14.0 Sq. In.
60" S4 T-Scon achieved* 9.6 Sq. In.
60" 56 T*Scan cchk!ved = 30.4 Sq. In.
15.T Area not scanned in the Area not se<1nned in either the parallel to weld direction Transverse or Parallel directions looking for axial flaws looking for axial and circ flaws.
Reactor Pressure Vessel
GE Energy* Nuclear Coverage Calculation Sheet Pilgrim Unit-1, 2007 RPV-N6A-NV CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Weld Length = 360. Required Exam Percent Exam Volume = 23.2 Area Sq. In. Area Scanned of Area Weld Length Percent 60° T *Scan lS4 l A* 3.7 3.7 15.9% 3SO 8.0%
60° T*Scan (SS A 19.5 9.0 38.8% 360 19.4%
IRS P-Scan lS4 A 3.7 3.7 15.9% 360 8.0%
so* P-Scan (SS A 19.5 3.5 15.1% 360 7.5% :::0
'"O S0° T*Scan (S4)

IRS P*Scan IS4 ~
so* P-scan (SS z 60° T*Scan (S4) oo~ T*Scan (S6 IRS P*Scan (S4 60° P-Scan (S6 60° T-Scan (S4) so* T-Scan (SS IRS P-Scan ($4) so* f-'*Scan (S6)
% Total Composite Coverage = 42.9%
Rev 0 ll/2~
Comments:
A** Single side access, 100% credit of the achieved Supplement 4 T-scan volume claimed law. 10CFR50.55a.
Note
Roundina methods may affect calculated values. Weld leoath In degrees.
k-: .....
~ ~..,, ~ ,) l:f'y <:; _ . ./ .>-£-. ) ~ .:;u- ......;.;.. .......~ -
to Letter 2.16.036 Page 28 of 34 RPV-N6A-NV Pilgrim Unit-1 Weld N6 Core Spray 60" FV Exam Volume= 19.5 Sq, In, 60' (Inner 15%1) EMm Volllne = 3.7 Sq. In.
60' FV T.scan ;idlleved
9.0 Sq. In.
eo* (Inner 15%T) T-SQ!n achkMld = 3.7 Sq. In.
W FV P*Scan edlieved = 3.5 Sq. In.
60' (Inner 15%T) IRS & P-Scan llCllieved
3.7 Sq. In.
60"TIP eo*p 60"T Area not scanned Inthe Am not scanned ineither the parallel to welddirection Transverse or Parallel directions looking for axialflaws lookirt for axial and clrc flaw~.
e HITACHI SP2000 RPV Examination Coverage Calculation Sheet Pilgrim Unit-1 / RF0-20 RPV-N7A-NV CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Percent Weld Length "' 180.00 Required Exam Area Scanned of Area Weld Length Percent Exam Volume= 15.80 Area Sq. In.
50* T-Scon 156 A 14.00 6.80 0.43 180.00 21.5%
50* T-Scon IS41 A 1.80 1.80 0.11 180.00 5.796 IRS P-Scon 155) A 1.80 1.80 1.00 180.00 50.0%
Percent Weld Length : 180.00 Required Exam Area Scanned of Area Weld Length Percent
ti Exam Volume

14.50 Area Sq. in.
"'CJ 60°T-Scon156 B 12.30 11.20 0.71 180.00 35.4% < I 60" T-Scon 1541 IRS P-Scon (SS)
B 2.20 2.20 2.20 2.20 0.14 1.00 180.00 7.0%
50.0%
z......
B 180.00
~
60° T-Scon (56 z 60" T-Scan 1541 <
IRS P-Scon 1551 60°T-Scan (56 60° T-Scon 154)
IRS P-Scan 1551
% Total Composite Coverage= 84.896 Rev.O 9113/CIS Comments: A- Manual scanning was limited due to the nozzle configuration. Top side of offset nozzle.
B - Manual scanning was limited due to the nozzle configuration. Bottom side of offset nozzle.
~e 8of'q Examination volume is in accordance with Code Cose N-613-1. Circumferential examination of the outer 85%T is not required by the 2001 Edition with 2003 Addenda.
r- J
I > ,, ..
Note - Rounding methods may affect calculated values. UC-Underclod, FV-Full volume. NS-Near Surface. Weld lencith in degrees.
. I I to Letter 2.16.036 Page 30 of 34 RPV-N7A-NV
HITACHI N7A Top Side lN7A Bottom Side Top Head N7A Nozzle S6C-~ U.J5"1ft
"--'°"'~*11S.:~
w....,.~ * .......w
lll~*
~----~~
11S. ....
$il4NCWfa:'N~~_,...... .. ll5ootll> ... ~
Top Head N7A Nozzle
...... _..,...~ ...,...
s. ..... ,_..,.. ........ , ... ...
Area not scanned in either Cross Sectional Coverage 0° and 180° the Transverse or Parallel directions looking for axial
~nn ,...j,.,.,. fl~u1c
Reactor Pressure Vessel Coverage
~ HITACHI Calculation Sheet Pilgrim Unit-1 RF0-17 Weld RPV-N9A-NV CODE CROSS*SECTIONAL AREA TOTAL CODE COVERAGE Required EJcam Percent Weld length = 360 Area sq. In. Area Scanned of Area Weld Length Percent Exam Volume
32.1 IRS*Scan LI<CW (541 A 5.3 5.3 16.5% 360 4.1%
IRS-Scan LKCCW IS4l A 5.3 5.3 16.5% 360 4.1%
&o* P-Scan 1561 A 26.8 21.9 68.2% 360 34.1%
Go* T-Scan IS4l A 5.3 5.3 16.5% 360 8.3%
60" T-Scan 1561 A 26.8 22.9 7L3% 360 35.7%
. :::0
"'C
< I z<O
~
z
% Total Composite Coverage = 86.3%
Rt1 0 9/ll/OS Comments A - Scanned area 360*. Scanning limited due to nozzle configuration.
Note* Rounding methods may offactrnlculoted values. S4*Supplement 4 underclod volume, 56-Supplement 6 volume. Weld length in degree~
~ ... r r I c>. w., ~,,,..:-./~ )L.....u ..,,,6.,/...1 to Letter 2.16 .036 Page 32 of 34 RPV-N9A-NV Pilgrim N9 Nozzle - Jet Pump Instr.
60. S4 &. IRS El<<lm Volume s S.3 Sq. In 60" S6 E><om volume
26_8 Sq_In.
60- S4 T* Scon E><om Volume
5.3 Sq, In 60" S6 T-Scon El<<lm Volume ~ 22.9 SQ- In.
IRS P-Scon E><am Volume* 5.3 Sq. In 60" 56 P-Scon Exom Volume
21.9 Sq. In.
15.J" 60"T;Sccm Area not scanned In the Area not scanned In either t he parall el to weld direction Tra nsverse or Parall el directions looking for axial flaws looking for axial and circ fla ws.
81 HITACHI Reactor Pressure Vessel Coverage Calculation Sheet Pilgrim RF0-18, 2011 NlO - CRD Return CODE CROSS-SECTIONAL AREA TOTAL CODE COVERAGE Required Exam Percent Weld Length
360 Area sq. In. Area Scanned of Area Weld Length Percent Exom Volume = 58.6 IRS-Scan LKCW 1541 A 6.5 6.5 11.196 360 2.8%
IRS-Scan LKCCW (541 A 6.5 6.5 11.1% 360 2.896 60- P-Scon 1561 A 52.1 13.3 22.796 360 11.396 60" T-Scon (541 A 6.5 6.5 ll.196 360 5.596 DU T-Scan l:>DJ A 52.1 24.9 42.596 360 21.2%
.,,:::0
-:=:
z 0
I z
% Total Composite Coverage"' 43.7%
tl<v.O 9/ll/ll!
Comments A - Scanned area 360". Scanning limited due to nozzle configuration.
Note - Rounding methods may affect colculoted values. S4-Supplement 4 underclod volume, S6-Suoolement 6 volume. Weld lenoth in decrees PNPS RF018-021 Poge 6 of 7 to Letter 2.16.036 Page 34 of 34 RPV-N10-NV Pilgrim CRD Nozzle 60" 54 Exam Volume
6.S Sq. In.
60" S6 Exam Volume
52.1 Sq. In 60" 54 IRS-Scon LKCW achieved
6.5 Sq. tn.
60" 54 IRS-Scon LKCCW ochieved - 6.5 Sq. In.
60" 56 P-SCon achieved - 13.3 Sq. In.
60" 54 T-SCon achieved - 6. so Sq. In.
60" S6 T-Scon achieved
24.9 Sq. In Area not scanned in the Area not scanned In either t he parallel to weld direction Tra n sver~e or Parallel directions looking for axia l flaws looking for aKial and clrc Oaws.
Attachment 3 to Letter 2.16.036 Request for Relief - PNPS-151-003 (3 Pages) to Letter 2.16.036 Page 1 of 3 REQUEST FOR RELIEF - PNPS-ISl-003 Components I Reactor Vessel Attachment Weld I RPV-S8W-270 Numbers:
Code Classes: American Society of Mechanical Engineers (ASME) Code Class 1
References:
ASME Section XI 1998 Edition w/ 2000 Addenda , Table IW8-2500-1, ASME Section XI 2001 Edition w/ 2003 Addenda, Table IW8-2500-1, Code Case N-460 Examination Category: 8-K ltemNumber(s) 810.10
==
Description:==
Welded Attachments for Vessels , Piping, Pumps, and Valves -
Inspection Program 8 Unit/ Inspection Pilgrim Nuclear Power Station (PNPS) I Fourth (4th) 10-Year Interval Interval Applicability:
I. CODE REQUIREMENTS ASME Section XI, Table IW8-2500-1, Examination Category 8-K, "Welded Attachments for Vessels, Piping, Pumps, and Valves - Inspection Program 8":
Item 810.10 requires a surface examination of the RV welded attachment, as depicted in Figure IW8-2500-15.
II. RELIEF REQUEST Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Nuclear Operations, Inc. (Entergy) requests relief from achieving the Code-required coverage when performing surface examinations of the Reactor Vessel Attachment Weld I RPV-SBW-270.
Ill. BASIS FOR RELIEF During surface examination of the Reactor Vessel Attachment Weld I RPV-SBW-270, greater than 90% coverage of the required examination area could not be obtained.
Examinations were performed utilizing Entergy approved procedures specific to magnetic particle examination.
Due to the geometric configuration of the component and permanent structural steel, effective surface examination could only be performed on the top side of the weld. See Attachment 6 Table 3-1 for additional information.
Radiography is not practical on these types of welded attachment configurations, which prevent placement of the film and exposure source. To effectively perform any to Letter 2.16.036 Page 2 of 3 significant additional Code allowable surface examinations, modification and/or replacement of the component would be required . The examinations performed on the subject items in addition to the examination of other vessel welds contained in the lnservice Inspection program would detect generic degradation, if it existed, therefore demonstrating an acceptable level of integrity.
IV. PROPOSED ALTERNATIVE EXAMINATIONS No alternative testing is proposed at this time. Entergy has examined this weld to the extent practical.
V. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:
The Commission will evaluate determinations under paragraph (g)(5) of this section that Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Entergy believes that it is impractical to obtain greater examination coverage on these welds. To effectively obtain significant additional coverage would necessitate modification and/or replacement of the component. The examinations performed on the subject weld, in addition to the examination of similar welds contained in the program, would detect generic degradation, if it existed, demonstrating an acceptable level of integrity. Entergy requests the proposed relief be authorized pursuant to 10 CFR 50.55a(g)(6)(i).
to Letter 2.16.036 Page 3 of 3 RPV-SBW-270 Component III>: RPV*SBW-270 Limited Exam CGverage Side View Top View of lug RP'V~SBW-270 Ir 8 .18r Plan View 10"
< )
Examined weld on top of lug= U ..
Not examined (Inaccessible)
Bottom of lug =12" Side of lug= 4.375.. >< 2 = 8 . 75..
Total possible exam surface= 32.*75" Achieved Examination Coverage= 12 + 32.75 = 36.6%
Attachment 4 to Letter 2.16.036 Request for Relief - PNPS-ISl-004 (4 Pages) to Letter 2.16.036 Page 1 of 4 REQUEST FOR RELIEF - PNPS-ISl-004 Components I Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Numbers: Piping I DC-10-F10R and DC-14-F31 Code Classes: American Society of Mechanical Engineers (ASME) Code Class 2
References:
ASME Section XI 1998 Edition w/ 2000 Addenda , Table IWB-2500-1, ASME Section XI 2001 Edition w/ 2003 Addenda, Table IWB-2500-1, Code Case N-578, Code Case N-460 Examination Category: C-F-1 Item Number(s) C5.11
==
Description:==
Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping - Inspection Program 8 Unit/ Inspection Pilgrim Nuclear Power Station (PNPS) I Fourth (4th) 10-Year Interval Interval Applicability:
I. CODE REQUIREMENTS ASME Section XI, Table IWC-2500-1 , Examination Category C-F-1 , "Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping":
Item C5.11 requires a volumetric examination of Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping volume, as depicted in Figures IWC-2500-7 as applicable.
II. RELIEF REQUEST Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Nuclear Operations, Inc. (Entergy) requests relief from achieving the Code-required coverage when performing volumetric examinations of the components identified in Attachment 6 Table 4-1.
Ill. BASIS FOR RELIEF During ultrasonic examination of the austenitic stainless steel piping welds listed in Attachment 6 Table 4-1, greater than 90% coverage of the required examination volume could not be obtained.
Examinations were performed utilizing a POI Appendix VIII Supplement 2 qualified procedure specific to austenitic piping welds.
Due to the geometric configuration of the components , effective volumetric examination could only be performed from the pipe side of the weld. The 45°, 60° shear and 60"refracted longitudinal (RL) beam angles used in the axial and circumferential direction were not able to achieve greater than 90% code required volume of the austenitic stainless steel circumferential welds as required by Code Case N-460.
to Letter 2.16.036 Page 2 of 4 To effectively perform any significant additional Code allowable ultrasonic examinations, modification and/or replacement of the component would be required . The examinations performed on the subject items in addition to the examination of other piping welds contained in the lnservice Inspection program would detect generic degradation , if it existed , therefore demonstrating an acceptable level of integrity.
IV. PROPOSED ALTERNATIVE EXAMINATIONS No alternative testing is proposed at this time. Entergy has examined these welds to the extent practical and will continue to perform pressure testing on the subject components as required by the Code.
V. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:
The Commission will evaluate determinations under paragraph (g)(5) of this section that Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and wil l not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Entergy believes that it is impractical to obtain greater examination coverage on these welds. To effectively obtain significant additional coverage would necessitate modification and/or replacement of the component. The examinations performed on the subject welds , in addition to the examination of similar welds contained in the program, would detect generic degradation, if it existed , demonstrating an acceptable level of integrity. Entergy requests the proposed relief be authorized pursuant to 10 CFR 50.55a(g)(6)(i).
to Letter 2.16 .036 Page 3 of 4 DC-10-F10R Compone111t 10 : IDC*10*F10R.
Limited Exam Coverage Profile Single side access only due to valve lo pipe configuration. Far side area scanned 45$
With 60 degree RL tor Best Effort per procedure.
w 0.44* H x 1.zr x sr L = 30.598 x 2 (ale)
= 61 .195 = 46.92",i, Best Effort Coverage Pipe Axial Scan area limited due to Drain Line 0.44" H x 1.38" W x 2-T L = 1.639 Circl Scan area fimited due to Drain Line 0.44'H x 0.68" W ~ 2.7" L = 0 .808 View Looking Up The CRV obtained was limited to 51 19% in the axial and circ directJOn. The examination was imlted to scanning from the pipe side o~ due to the limijed length of scan araa fi'om valve, taper and weld crown.
I The CRV is based on a 0.44" H x 2.6" W x 57' L volume 1
= 65.21" x 2 (NC)= 130.42" ~ 0.68"C Pipe side coverage was calculated based on the accessible area not obstructed by drain. Pipe 5'de volume is 0.44 H x 1.38 W x 57 L
34.81x2 (ale)*
69.22. Tomi obslJUcted area 2.447.
69.22 - 2.447. 66.773 1 130.42 *. 5119 = 51 19%
The Best Effort area obtained was 61 .195" = 46 92%
Total area scanned Including Best Effort= 96.11%
Drain Line to Letter 2.16.036 Page 4 of 4 DC-14-F31 Component liD: DC-1 4-F31 Limited exam coverage Profile Valve Pipe
~ Area not scanned in axial or circ direction due to valve to pipe configuration . Far side area scanned with 60 degree RL for best effort per procedure.
The CRV obtained was limited to 50%. The examination was limited lo scanning from the pipe side only due to the limited length of scan area on the valve, taper and weld crown .
The CRV is based on a 0.3" H x 1.65" W volume= 0.495", 50% = 0.248" The Best Effort area obtained was 0.248-" =500/.:,
Total area scanned including Best Effort= 100%
Attachment 5 to Letter 2.16.036 Request for Relief - PNPS-151-005 (12 Pages) to Letter 2.16.036 Page 1 of 12 Request for Relief - PNPS-ISl-005 Components I See Attachment 6 Table 5-1 Numbers:
Code Classes: American Society of Mechanical Engineers (ASME) Code Class 1 and 2
References:
ASME Section XI 1998 Edition w/ 2000 Addenda, ASME Section XI 2001 Edition w/ 2003 Addenda, Code Case N-578 Code Case N-716 Examination Category: R-A Item Number(s) R1 .11 , R1 .20
==
Description:==
Risk Informed Piping Welds Unit/ Inspection Pilgrim Nuclear Power Station I Fourth (4th) 10-Year Interval Interval Applicability:
I. CODE REQUIREMENTS ASME Section XI , Code Case N-716, Examination Category R-A "Risk Informed Piping Welds":
Item R1 .11 (Elements Subject to Thermal Fatigue) requires a volumetric examination of Risk Informed Piping Weld volume.
Item R1 .20{Elements Not Subject to a Damage Mechanism) requires a volumetric examination of Risk Informed Piping Weld volume.
II. RELIEF REQUEST Pursuant to 10 CFR 50.55a(g)(6)(i), Entergy Nuclear Operations, Inc. (Entergy) requests relief from achieving the Code-required coverage when performing volumetric examinations of the components identified in Attachment 6 Table 5-1.
to Letter 2.16.036 Page 2of12 Ill. BASIS FOR RELIEF During ultrasonic exam ination of the Appendix VIII Circumferential piping welds listed in Attachment 6 Table 5-1 , greater than 90% coverage of the required examination volume could not be obtained .
Examinations were performed utilizing Entergy approved procedures specific to austenitic stainless steel piping welds .
Due to the geometric configuration of the components , effective volumetric examination could only be performed as noted in the Table 5-1 . The 45*, 60° and 70" beam angles use in the axial and circumferential direction were not able to achieve greater than 90% code required volume as required by Code Case N-460. See Attachment 6 Table 5-1 for additional information.
To effectively perform any significant additional Code allowable ultrasonic examinations , modification and/or replacement of the component would be required . The examinations performed on the subject items in addition to the examination of other piping welds contained in the lnservice Inspection program would detect generic degradation , if it existed , therefore demonstrating an acceptable level of integrity.
IV. PROPOSED ALTERNATIVE EXAMINATIONS No alternative testing is proposed at this time. Entergy has examined these welds to the extent practical and will continue to perform pressure testing on the subject components as required by the Code.
V. CONCLUSION 10 CFR 50.55a(g)(6)(i) states:
The Comm ission will evaluate determinations under paragraph (g)(5) of th is section that Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Entergy bel ieves that it is impractical to obtain greater examination coverage on these welds . To effectively obtain sign ificant additional coverage would necessitate modification and/or replacement of the component. The examinations performed on the subject welds , in addition to the examination of similar welds contained in the program , would detect generic degradation, if it existed , demonstrating an acceptable level of integrity. Entergy requests the proposed relief be authorized pursuant to 10 CFR 50.55a(g)(6)(i).
to Letter 2.16.036 Page 3 of 12 2R-HB-3 0 and 180 Degree Limitation 60RL 45 s 455 Cross.
, ---- ,----- --------- 4.. - -ot...._..~.....
Header Area not sca nned from both sides of the weld due to coofiguration. Limited area at o*
Approximately 23" at o* and 23" at 180" along the circumference of the weld were limited to single side access. 23" Risk informed exam volume is (5.156" W x 0.531 " H x 69.5" L).
CRV = 190.279" = 100%
NS volume scanned is (3.876 W x 0.531
H x 69.5" L) 143.04". FS volume scanned is (1 .281wx0.53 1" H x 23_5* L) 15.98* . 143.04(NS}+
15.98(FS) =159.021190 .279=83 .57% CRV obtained.
Limited volume not scanned is (1.281Wx0.531" H x 4tl" L) 31.289".
See diaaram below.
Limited area a t 180° 23" to Letter 2.16.036 Page 4of 12 Component ID: 12-0-24 Limited exam coverage PmfiJe 70S 45S 60$ 60S Penetration Pipe I
Area scanned for circ flaws providing Best Area not scanned for circ flaws to obtain Best Effort coverage in the axial direction using 70 Effort coverage in the axial direction. Coverage Shear per the procedure. Coverage limited limited due lo weld crown and component due to weld crown and component geometry. geometry.
The CRV obtained was limited to 50% in the axial direction. The examination was limited to scanning from the pipe side only due to the limited length of scan area, penetration taper and weld crown. Scanning in the circumferential direction was performed utilizing manual skewing in both the CW and CCW directions upstream and downstream lo obtain coverage.
The CRV is based on a 0.12" H x 1.T'W volume"' 0.204", 50% "'0.102" The Best Effort area obtained was 0.057" = 27.9%
Total area scanned including Best Effort = 77 ..9%
to Letter 2.16.036 Page 5 of 12 Co*m ponent ID : 14-A 1OA Limited Exa m Coverage 45-S Ci rc Valve 40 & SO S/RL PA, Circ & Ax
\
\
\
"\
\
\
\
/
/
/
Code Required Volume (CRV) \ Pipe
\ I '
"\
\
/
.. ./ .
Area not covered by either 45 Shear Gire, 40
& 50 S/RL PA, Ax - Circ scan.
,,,,,,,,,,,,,'\: A rea not covered by either 40 & 50 S/ RL PA, Circ & Ax Area not covered by 40 S/RL PA, Circ
&Ax
WaH Thickness I Slhr. fllilBil. UM: ! ~No.!
HITACHI Profile Sheet l'IOjtcl: @FOJO eNPSAEQI~
System:
Posi1bt O" w " lllO' l111' till.
~llDNll!l'ibet: ~
PY m
1.511 rn
"'" "'" NIA NIA Hiit H/A (i(Wl~ ru:
0.61r' Ii/It NIA NIA CrownWld ' .!IJ.':
1'&l!f UPST CQlllPOllCl!t NIA
~Olometer: u 0.5aS" H/A NIA
" n Weldlengllr. M 0 NIA O.M
"'" NIA 3
"C 0
s
-(I)
s c
14*A-10A
.\S'S ManualClrcScans I Wond 50'S/Rt'
~ EllllmVdul114t Pipe l'Ndont1$ obtQ!fl1d ftOlll prlVious daUJ.
wt'.d roat Oeotri<<ll)I ~ diliM lilt 17Q11il!QIJon.
Monuol CClllWfllionol clrc: scans per£amied Ill obtoln odditlonol COv*'O!li in QtQOJ
C.ode @IOOm YOILrllr
O.l7 sq. in, I COmJl0$ilf CMrogc llChiMd
lU,._
~5alll~l"'1td*0.10SQ. n ?7,IM Ci'cSconAd-.!Mdo..11sci.ln. ~.19' 1l1::51QfalldJm Ora.i<<lby.
!~~~~~"- Dote:
Pogt ll d li to Letter 2.16.036 Page 7 of 12 Component ID :1 4-B-10A Umited Coverage Plot 45-S Circ Valve 40 & 50 S/RL. PA, Ci~c & Ax Code Required Volume (CRV) Pipe Area not covered by either 45 Shear Circ, 40
& 50 S/RL PA, Ax - Circ scan.
Area not covered by either 40 & 50 S/RL
"'''''''x PA, Circ&Ax Area 110! covered by 40 S/RL PA, Circ
&Ax
-u r )>
Ill CD :::::
ca ::::: Ill CD CD ()
..... ~
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- 0) :::J f\.) 0 01 wall Thickness Sile: et!D Unit 1 . *port NO.:
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HITACHI l Profile Sheet PrOjl!d: mill fflPS llFOl<<-OOZ 0) 51'$tcrrt l'C!!iilictl I I
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HIA HIA WA HJA J CtOWt> MelQht e.r z I H/A NIA Hiit NIA l:
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"'1minol Oiomli1cr.; mg:
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Thidoness ~ lrom FJ11MOu' data.
W.td root veomeuy c'liff,""'!11 d!Jl1!>Q Ull! eianlna!IQO, Manucil COOYl!fl&IQ11QI t ~5 pl!lfllt!rlitd to obl.Oorl <:C'lt!fage In Ofl'oS llqW.ed lo 1111 PA $eatth unlL Co.to 1t,...,., ldllme
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to Letter 2.16.036 Page 9 of 12 Component ID: lOR-IA-6 limited Exam Coverage Valve Pipe Single side access area not covered in the axial direction by procedure due to component configuration. 60 Rl used for Gire Flaw scan to obtain best effort coverage on the far side per procedure. 50% CRV achieved 100% with best effort.
Code Box (CRV) dimensions = 0.35" H x 1.T' W x 57" l Best effort far side box = 0.35" H x 0.85" W x 57" L to Letter 2.16 .036 Page 10of12 Component ID: 110R*IA*7 Limited Exam Coverage 455 45 s 60RL Va lve P~pe Single side access area not covered in the axial direction by procedure due to component configuration. 60 RL used for Circ Flaw scan to obta.in best effort coverage on the far side per procedure. 71.88% CRV achieved, 100% with best effort.
Code Box (CRV) dimensions"' 0.35" H x 3.2" W x 57" L Best effort far side box =0.35" H x 0.90" W x sr L
Attachm ent 5 to Letter 2.16.036 Page 11 of 12 Component 10 1
10R.-IB-14 limited Coverage 4SS 60Rl 455 Fluecl Head Pipe Single side access area not covered in the axial direction by procedure due to component configuration. 60 Rl used for Gire Flaw scan to obtain best effort coverage on the far side per procedure. 78.62% CRV achieved , 100% with best effort.
Code Box (CRV) dimensions= 0.3" H x 3.6" W x 57" L = 61 .56 NS volume scanned 0.3" H x 2.83" W x 57" = 48.4/6 1.56 =78.62% CRV obtained per procedure.
Best effort far side box =0.3" H x o.77" W x 57" L - 13.167 to Letter 2.16 .036 Page 12 of 12 Component II): 14R-A-11 45S 45S 70 L Va~ve 6A Pipe 0.653
0.667" 0.589/t 0.610
~ Far side area scanned with 45 and 70 degree shear for best effort per procedure.
The CRV obtained was limited to 50% in the axial and circ directions. The examination was ~imited to scanning from the pipe side only due to the limited length of scan area, valve taper and weld crown.
The CRV is based on a 0.28 H x 2.0" W x 34.5" L volume= 19.32", 100%
The Best Effort area obtained was 0.28" H x 1.0" W x 34.5" l = 9.66" = 50%
Total area scanned including Best Effort = 100%
Attachment 6 to Letter 2.16.036 Component Limited Examination Information (7 Pages) to Letter 2.16.036 Page 1 of 7 Table 1 Category B-A Component Information Cat Item Comp ID Item Description Material 1 and Material 2 and Examination Examination Limitations and Results No. Product Form Product Form Code Coverage Obtained B-A B1.12 RPV-L Lower Intermediate Shell Vertical Rolled Plate - Rolled Plate - 88.40% RPV Intermediate Shell Vertical Weld @ 60°. Jet Pump riser brace 338A Weld SA533 Gr. B SA533 Gr. B welded to the RPV shell wall is directly in the scan path to the CL1 CL1 transducer array. Exam results are acceptable with no indications recorded.
B-A B1 .12 RPV-L Lower Intermediate Shell Vertical Rolled Plate - Rolled Plate - 89.70% RPV Intermediate Shell Vertical Weld @180°. Scanning was 338B Weld SA533 Gr. B SA533 Gr. B restricted due to proximity of the Guide Rod Bracket. Exam results CL1 CL1 are acceptable with no indications recorded.
B-A B1.12 RPV-L Lower Intermediate Shell Vertical Rolled Plate - Rolled Plate - 55.60% RPV Intermediate Shell Vertical Weld @300°. Jet Pump riser brace 338C Weld SA533 Gr. B SA533 Gr. B and RPV suNeillance Specimen Holder and Support Brackets welded CL1 CL1 to the RPV walls and directly in the scan path of the array. Shroud Tie Bar @ 315° prevents maneuvering of the scanner tooling to fully access the weld. Exam results are acceptable with no indications recorded.
B-A B1.12 RPV-L Lower Shell Vertical Weld Rolled Plate - Rolled Plate - 75.80% RPV Lower Shell Vertical Weld @75°. Shroud support and associated 338A SA533 Gr. B SA533Gr. B gusset plates would not allow the scanner tooling to completely CL1 CL1 position the transducer array to the bottom of the weld, where the RPV vertical weld intersects with the shroud support plate. Exam results are acceptable with no indications recorded.
B-A B1.12 RPV-L Lower Shell Vertical Weld Rolled Plate - Rolled Plate - 71.50% RPV Lower Shell Vertical Weld@ 195°. Shroud support and 338B SA533 Gr. B SA533 Gr. B associated gusset plates would not allow the scanner tooling to CL1 CL1 completely position the transducer array to the bottom of the weld, where the RPV vertical weld intersects with the shroud support plate.
Exam results are acceptable with no indications*recorded.
B-A B1.12 RPV-L Lower Shell Vertical Weld Rolled Plate - Rolled Plate - 11.60% RPV Lower Shell Vertical Weld @315°. (1) Shroud support and 338C SA533 Gr. B SA533 Gr. B associated gusset plates would not allow the scanner tooling to CL1 CL1 completely position the transducer array to the bottom of the weld, where the RPV vertical weld intersects with the shroud support plate.
(2) The shroud tie bar@315° prevents maneuvering of the scanner tooling to fully access the weld. (3) N2K Nozzle radius prevents even contact of the scanner tooling. Exam results are acceptable with no indications recorded.
B-A B1.12 RPV-L Upper Intermediate Shell Vertical Rolled Plate - Rolled Plate - 18.00% RPV Upper Shell Vertical Weld @355°. Automated scanning was 339A Weld SA533 Gr. B SA533 Gr. B restricted due to proximity of Guide Rod, Feedwater End Bracket and CL1 CL1 internal Core Spray piping. The auto coverage was calculated to be 18%. Achieved coverage during RFO 14 was 81 %. The change in the achieved coverage is due to the differences in the design of the inside surface scanner utilized. Supplemental examination from the outside surface is not possible due to the design of the bio shield.
Exam results are acceotable with no indications recorded.
B-A B1.12 RPV-L Upper Intermediate Shell Vertical Rolled Plate - Rolled Plate - 69.00% RPV Upper Shell Vertical Weld @ 115°. Feedwater and Core Spray 339B Weld SA533 Gr. B SA533 Gr. B Spargers prevent maneuvering of the scanner tooling to fully access CL1 CL1 the weld and the angle of ID taper due to RPV shell course plate thickness change. Exam results are acceptable with no indications recorded.
to Letter 2.16.036 Page 2of7 Table 1 Category B-A (Cont.)
Component Information Cat Item Comp ID Item Description Material 1 and Material 2 and Examination Examination Limitations and Results No. Product Form Product Form Code Coverage Obtained B-A B1.12 RPV-L Upper Intermediate Shell Vertical Rolled Plate - Rolled Plate - 73.20% RPV Upper Shell Vertical Weld @ 235°. Feedwater and Core Spray 339C Weld SA533 Gr. B SA533 Gr. B Spargers prevent maneuvering of the scanner tooling to fully access CL1 CL1 the weld. Exam results are acceptable with no indications recorded.
B-A B1.21 RPV-BH-C1 Bottom Head Circ. Weld Rolled Plate Rolled Plate - 68.20% RPV Bottom Head Circumference Weld. The examination was limited SA533 Gr. B SA533 Gr. B due to the proximity of the RPV skirt on the lower side of the weld.
CL1 CL1 Also, the exam was slightly limited by thermocouples on the bottom head. No recordable indications were detected utilizing a 60°RL wave search unit. Three previously recorded indications were observed below recordable levels.
to Letter 2.16.036 Page 3 of 7 Table 2 Category B-D Component Information Cat Item Comp ID Item Description Material 1 and Material 2 and Examination Examination Limitations and Results No. Product Form Product Form Code Coverage Obtained 8-D 83.90 RPV-N1A- Recirculation Outlet Nozzle-to- Rolled Plate - Nozzle Forging 43.80% Manual scanning was restricted by the nozzle configuration. No NV Vessel Weld SA533 Gr. 8 - SA508 CL 2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N2A- Recirculation Inlet Nozzle-to-Vessel Rolled Plate - Nozzle Forging 33.60% Manual scanning was restricted by the nozzle configuration. No NV Weld SA533 Gr. 8 - SA508 CL2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N28- Recirculation Inlet Nozzle-to-Vessel Rolled Plate - Nozzle Forging 33.60% Manual scanning was restricted by the nozzle configuration. No NV Weld SA533 Gr. 8 -SA508 CL2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N2C- Recirculation Inlet Nozzle-to-Vessel Rolled Plate - Nozzle Forging 33.60% Manual scanning was restricted by the nozzle configuration. No NV Weld SA533 Gr. 8 -SA508 CL 2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N3A- Main Steam Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 37.90% Scanning was performed from the vessel OD surface, and was NV SA533 Gr. 8 - SA508 CL 2 restricted due to nozzle configuration. No relevant indications were CL1 recorded.
8-D 83.90 RPV-N38- Main Steam Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 37.90% Scanning was performed from the vessel OD surface, and was NV SA533 Gr. 8 -SA508 CL2 restricted due to nozzle configuration. No relevant indications were CL1 recorded.
8-D 83.90 RPV-N3C- Main Steam Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 37.90% Scanning was performed from the vessel OD surface, and was NV SA533 Gr. 8 -SA508 CL2 restricted due to nozzle configuration. No relevant indications were CL1 recorded.
8-D 83.90 RPV-N3D- Main Steam Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 37.90% Scanning was performed from the vessel OD surface, and was NV SA533 Gr. 8 -SA508 CL2 restricted due to nozzle configuration. No relevant indications were CL1 recorded.
8-D 83.90 RPV-N4A- Feedwater Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 49.30% Manual scanning was restricted by the nozzle configuration. No NV SA533 Gr. 8 -SA508 CL2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N48- Feedwater Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 49.30% Manual scanning was restricted by the nozzle configuration. No NV SA533 Gr. 8 -SA508 CL 2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N4C- Feedwater Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 49.30% Manual scanning was restricted by the nozzle configuration. No NV SA533 Gr. 8 -SA508 CL2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N4D- Feedwater Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 49.30% Manual scanning was restricted by the nozzle configuration. No NV SA533 Gr. 8 -SA508 CL2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N6A- Core Spray Nozzle-to-Vessel Weld Rolled Plate - Nozzle Forging 42.90% Scanning was performed from the vessel OD surface, and was NV SA533 Gr. 8 - SA508 CL 2 restricted due to nozzle configuration.
CL1 8-D 83.90 RPV-N7A- Head Spray Nozzle-to-Closure Rolled Plate - Nozzle Forging 84.80% Reactor pressure vessel nozzle to vessel top head weld. Limitations in NV Head Weld SA533 Gr. 8 - SA508 CL 2 weld coverage were identified due to the nozzle configuration (proximity CL1 to the weld). This limitation exists at varying degrees for the entire length. No relevant indications were recorded.
to Letter 2.16.036 Page 4 of 7 Table 2 Category B-D (Cont.)
Component Information Cat Item Comp ID Item Description Material 1 and Material 2 and Examination Examination Limitations and Results No. Product Form Product Form Code Coverage Obtained 8-D 83.90 RPV-N9A- Jet Pump Instrument Nozzle-to- Rolled Plate - Nozzle Forging 86.30% Manual scanning was restricted by the nozzle configuration. No NV Vessel Weld SA533 Gr. 8 -SA508 CL2 relevant indications were recorded.
CL1 8-D 83.90 RPV-N10-NV Control Rod Return Nozzle-to- Rolled Plate - Nozzle Forging 43.70% Manual scanning was restricted by the nozzle configuration. No Vessel Weld SA533 Gr. 8 -SA508 CL2 relevant indications were recorded.
CL1 to Letter 2.16.036 Page 5 of 7 Table 3 Category B-K Component Information Cat Item Comp ID Item Description Material 1 and Material 2 and Examination Examination Limitations and Results No. Product Form Product Form Code Coverage Obtained B-K 810.10 RPV-SBW- RPV Stabilizer Weld Rolled Plate - Plate - SA302 36.60% RPV Attachment Weld Stabilizer Bracket Weld at 270°. Lower and 270 SA533 Gr. B Gr.B adjacent sides of the attachment could not be examined due to access CL1 limitation. No relevant indications were recorded.
to Letter 2.16.036 Page 6 of 7 Table 4 Category C-F-1 Component Information Cat Item Comp ID Item Description Material 1 and Material 2 and Examination Examination Limitations and Results No. Product Form Product Form. Code Coverage Obtained C-F-1 C5.11 DC-10-F10R Pipe-to-Valve Weld, Line# 18"- Pipe - 18" A358 Valve - 18" 51.19% Coverage is limited due to single sided exam. Intermittent geometry GB-10 Gr. TP304 A351 Gr. CF8M 360° C-F-1 C5.11 DC-14-F31 Pipe-to-Valve Weld, Line# 10-DC- ~ Pipe - 1O" A376 Valve-10" 50.00% Coverage is limited due to single sided exam. No relevant indications 14 Gr. TP304 A351 Gr. CF8M were recorded.
to Letter 2.16.036 Page 7 of 7 Table 5 Category R-A Component Information Cat Item Comp ID Item Description Material 1 and Material 2 and Examination Examination Limitations and Results No. Product Form Product Form Code Coverage Obtained R-A R1.20 2R-HB-3 Cross-to-Header Weld, Line# 22"- Pipe -22" Pipe- 22" 83.57% Coverage is limited due to single sided exam. No relevant indications DCA-2 SA354 GR. SA354 GR. were recorded.
TP316 TP316 R-A R1.20 12-0-24 Pipe-to Flued Head Weld Pipe - 6" SA376 Flued Head - 50.00% Coverage is limited due to single sided exam. Intermittent geometry Gr. TP304 A403 Gr. WP- 360° 304 R-A R1.20 14-A-10A Valve-to-Pipe DM Weld Pipe - 10" A106 Valve -10" 50.00% Core Spray System carbon steel pipe to stainless steel valve which Gr. B A351 Gr. CF8M had an lnconel 182 welded overlay end preparation on the carbon steel pipe prior to welding. Weld was made utilizing lnconel 182 weld material. No indications associated with IGSCC recorded. Weld root geometry was imaged 360° with the phased array sector scan using angles greater than the maximum 50° beam angle defined for coveraoe.
R-A R1.20 14-B-10A Valve-to-Pipe DM Weld, Line#* 1O"- Pipe - 10" A106 Valve -10" 50.00% Core Spray System carbon steel pipe to stainless steel valve which DBA-14 Gr. B A351 Gr. CF8M had an lnconel 182 welded overlay end preparation on the carbon steel pipe prior to welding. Weld was made utilizing lnconel 182 weld material. No indications associated with IGSCC recorded. Weld root geometry was imaged 360° with the phased array sector scan using angles greater than the maximum 50° beam angle defined for coveraae.
R-A R1.11 10R-IA-6 Pipe-to-Valve Weld, Line # 18" - Pipe -18" A358 Valve-18" 50.00% Residual Heat Removal (RHR) System stainless steel pipe to stainless DCA-10 Gr. TP304 A351 Gr. CF8M steel valve welds utilizing stainless steel weld metal. Examination coverage is limited on these welds due to the pipe to component configurations. Qualified examination coverage could only be claimed for the base material and weld heat affected zone on the pipe side.
Intermittent oeometrv 3.60° R-A R1.11 10R-IA-7 Valve-to-Pipe Weld, Line# 18"- Pipe - 18" A358 Valve -18" 71.88% Residual Heat Removal (RHR) System stainless steel pipe to stainless DCA-10 Gr. TP304 A351 Gr. CF8M steel valve welds utilizing stainless steel weld metal. Examination coverage is limited on these welds due to the pipe to component configurations. Qualified examination coverage could only be claimed for the base material and weld heat affected zone on the pipe side.
Intermittent aeometrv 360° R-A R1.20 10R-IB-14 Pipe-to-Flued Head Weld Pipe - 18" A358 Flued Head - 78.62% Coverage is limited due to single sided exam. Root geometry and ID Gr. TP304 A403 Gr. WP- undercut recorded 360° intermittently.
304 R-A R1.20 14R-A-11 Pipe-to-Valve Weld, Line# 1O"- Pipe - 1O" SA- Valve-10" 50.00% Coverage is limited due to single sided exam. No relevant indications DBA-14 358, Gr. TP316 A351 Gr. CF8M were recorded.

v t e Letter Sequence Request
CAC:MF8092, (Open)
Initiation Request Acceptance Administration Questions 9 December 2016 Answers Results Approval... Other:
MONTHYEAR2016-06-29 [Table View]

ML16188A269

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