Indian Point Energy Center 450 Broadway, GSB En TO?' · ASME Cat B-D. NRC Relief Granted, Date 6-3-97, TAC No. M88559. ASME Code Category B-J "Pressure Retaining Welds in Piping"

Indian Point Energy Center450 Broadway, GSBP.O. Box 249En TO?' Buchanan, N.Y. 10511-0249Tel (914) 734-6700

R. Walpole(914) 734-6710

March 26, 2008

Re: Indian Point Unit 2Docket No. 50-247

NL-08-053

U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001

Subject: 10 CFR 50.55a Request RR-CRV-75 - Relief from Examinations ofComponent Welds with Less Than Essentially 100% ExaminationCoverage for Third-Ten Year Inservice Inspection Interval Closeout

Reference: 1. Con Edison Letter NL-94-006, "Third Ten-Year Interval InserviceInspection Program," dated January 24, 1994.

2. ASME Section Xl, Code Case N-460, "Alternative ExaminationCoverage for Class 1 and Class 2 Welds, Section Xl, Division 1"

Dear Sir or Madam:

Indian Point Unit 2 (IP2) Third ten-year inservice inspection interval ended on March 1,2007. During the Third interval, IP2 completed the required in-service examinations inaccordance with the program plan (Reference 1); except, certain components could notfully meet the volumetric examination requirements stipulated in the ASME Section XICode, 1989 Code Edition, with No Addenda, including the clarifications provided in theASME Code Case N-460 (Reference 2). Entergy has determined that conformance withthe code requirement of essentially 100% coverage of weld volume or area examinedwas impractical due to various constraints and limitations. Accordingly, pursuant to 10CFR 50.55a (g)(5)(iii), Entergy submits the attached IP2 Relief Request, RR-CRV-75,for NRC review and approval. Relief Request, RR-CRV-75, proposes alternativeswhere the requirement of "essentially 100%" volumetric examination was not feasibledue to construction limitations, obstructions, accessibility, and examination techniques.The alternatives and justifications are explained in the attached relief request providinga list of components which requires relief pursuant to 10 CFR 50.55a. The alternativesand justifications provide acceptable level of quality and safety and will not adverselyimpact the health and safety of the public.

ALI 7AJ~

Indian Point Unit2Docket No. 50-247

NL-08-053Page 2 of 2

There are no new commitments identified in this submittal. If you have any questions orrequire additional information, please contact Mr. R Walpole at (914) 734-6710.

Sincerely,

R WalpoleLicensing ManagerIndian Point Energy Center

Attachment:

A. 10 CFR 50.55a Relief Request RR-CRV-75

cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORLMr. Samuel J. Collins, Regional Administrator, NRC Region 1NRC Resident Inspector, IP2Mr. Paul D. Tonko, President NYSERDAMr. Paul Eddy, New York State Dept. of Public Service

Attachment A to NL-08-053

10 CFR 50.55A RELIEF REQUEST RR-CRV-75

RELIEF FROM EXAMINATIONS OF COMPONENT WELDS WITH LESS THANESSENTIALLY 100% EXAMINATION COVERAGE

FOR THIRD-TEN YEAR INSERVICE INSPECTION INTERVAL CLOSEOUT

ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 2

DOCKET NO 50-247

Attachment ADocket No. 50-247

NL-08-053Page 1 of 71

10 CFR 50.55a Relief Request RR-CRV-75

Proposed Alternative In Accordance with 10 CFR 50.55a(g)(5)(iii)

Inservice Inspection Impracticability

1. ASME Code Comoonent(s) Affected

Code Class:

ExaminationCategories:

Item Numbers:

Class 1 (Quality Group A)

B-A, B-D, and R-A

B1.22, B1.40, B3.120, and R1.20

2. Applicable Code Edition and Addenda

The Code of Record for Indian Point Unit 2 Inservice Inspection Third Ten-YearInterval is the ASME Section XI Code, 1989 Edition, No Addenda.

3. Anolicable Code Reauirements

IWB-2500, states in part, "Components shall be examined and tested as specified inTable IWB-2500-1. The method of examination for the components and parts of thepressure retaining boundaries shall comply with those tabulated in Table IWB-2500-1, except where alternate examination methods are used that meet the requirementsof IWA-2240". Table IWB-2500-1 requires that a volumetric and/or surfaceexamination be performed on specified components based on Code Category andItem Number. The applicable examination area or volume and method required areshown below from Table IWB-2500-1:

<ASME~ AS [ SME Section XlExamnExamination ~7~ASME Item~ Requirements/ Figure NDE Examination

-Category . Number N umber MethodB-A B 1.22 IWB-2500-3 VolumetricB-A B1.40 IWB-2500-5 Volumetric & Surface

B-D B3.120 IWB-2500-7 VolumetricR-A R1.20 IWB-2500-8 Volumetric

4. Impracticality of Compliance

Relief is requested from performing a complete coverage examination of the entirevolume of area required. Entire volume or area required is defined by ASME SectionXl Code Case N-460 titled "Alternative Examination Coverage for Class and ClassWelds, Section XI, Division 1 ."

Code Case N-460 states in part, "...when the entire examination volume or areacannot be examined ... a reduction in examination coverage.. .may be acceptedprovided the reduction in coverage for that weld is less than 10%."

The NRC through, Information Notice 98-42 titled "Implementation of10CFR50.55a(g) Inservice Inspection Requirements," termed the reduction in


NL-08-053Page 2 of 71


coverage of less than 10% to be essentially 100 percent." Information Notice 98-42states, in part, "The NRC has adopted and has further refined the definition of'essentially 100% percent' to mean 'greater than 90 percent'...has been applied toall examinations of welds or other areas required by ASME Section Xl."

The construction permit for Indian Point Unit 2 was issued on October 14, 1966. Atthat time, the ASME Boiler and Pressure Vessel Code covered fabrication of onlynuclear vessels. Piping, pumps, and valves were built primarily to the rules ofUSAS B31.1.0-1955, Power Piping. The IP2 systems and components weredesigned and fabricated before the examination requirements of ASME Section XIwere formalized and published. Therefore, IP2 was not specifically designed to meetthe requirements of ASME Section Xl and full compliance is not feasible or practicalwithin the limits of the current plant design.

10 CFR 50.55a recognizes the limitations to inservice inspection of componentsin accordance with Section XI of the ASME Code that are imposed due to earlyplants' design and construction, as follows:

10 CFR 50.55a(g)(5)(iii): If the licensee has determined that conformancewith certain code requirements is impractical for its facility, the licensee shallnotify the Commission and submit, as specified in § 50.4, information tosupport the determinations.

Accordingly, pursuant to 10 CFR 50.55a(g)(5)(iii), Entergy has determined thatconformance with the code requirement of essentially 100% coverage of weldvolume or area examined was impractical due to various constraints and limitationsas stated above. Entergy requests NRC approval of the proposed alternative asstated below.

Relief is requested from performing an examination of "essentially 100% of therequired volume or area as applicable for the identified components in Table 1below.

ASME Code Category and Item Numbers where previous relief requests weregranted for coverage limitations not identified in Table 1 are as follows:

Class 1 (Quality Group A)

ASME Code Category B-A, "Pressure Retaining Welds in Reactor Vessel HeadWelds," (Item Nos. B1.21 and B1.22), are not listed in Table 1. Relief was submittedand granted for coverage limitations for meridional welds RVHM-1, RVHM-3, &RVHM-5 in the following approved relief request:

* Relief Request RR-06, Rev. 1, Reactor closure head circumferential welds. NRCRelief Granted, Date 6-3-97 3rd Int. TAC No. M88559.

ASME Code Category B-D and B-J, "Surface examination of Reactor Vessel Nozzleto Safe End Welds" (Item Nos. B5.10 and B9.11), are not listed in Table 1. Reliefwas submitted and granted for impracticality of examination in the followingapproved relief request:


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* Relief Request RR-1 1, Rev. 1, Surface examination of Reactor Vessel Nozzle toSafe End Welds. NRC Relief Granted, Date 6-3-97 3rd Int. TAC No. M88559.

ASME Code Category B-B, ."Pressure Retaining Welds in Vessels Other thanReactor Vessels," (Item Nos. B2.11 and B2.12), Pressurizer Shell-to-Head welds,not listed in Table 1. Relief was submitted and granted for coverage in the followingapproved relief request:

* Relief Request RR-07, Pressurizer shell to head, circumferential and longitudinalwelds. NRC Relief Granted, Date 6-3-97, TAC No. M88559.

ASME Code Category B-B, "Pressure Retaining Welds in Vessels Other thanReactor Vessels," and Category B-D, "Full Penetration Welds of Nozzles inVessels," (Item Nos. B2.51, B2.80, B3.150, and B3.160), Regenerative HeatExchanger vessel welds, not listed in Table 1. Relief was submitted and granted forcoverage in the following approved relief requests:

" Relief Request RR-08, Rev. 2, Regenerative Heat Exchanger vessel welds andinner radius sections. ASME Cat: B-B, B-D. NRC Relief Granted, Date 6-3-97,TAC No. M88559.

* Relief Request RR-60, Alternative to eliminate ASME Cat. B-B and B-D weldexaminations on regenerative heat exchanger. NRC Relief Granted, Date1/17/2003, TAC No. MB5834.

ASME Code Category B-D "Pressure Retaining Welds in Vessels Other thanReactor Vessels," (Item No. B3.120), Pressurizer Nozzle Inside Radius, are notlisted in Table 1. Relief was submitted and granted for coverage in the followingapproved relief request:

* Relief Request RR-09, Rev. 1, Pressurizer Inside Radius sections.ASME Cat B-D. NRC Relief Granted, Date 6-3-97, TAC No. M88559.

ASME Code Category B-J "Pressure Retaining Welds in Piping" (Item No. B9.11 andB9.12), are not listed in Table 1. Relief was submitted and granted for coverage inthe following approved relief requests:

" Relief Request RR-27, Reactor coolant piping, longitudinal welds. ASME Cat: B-J. NRC Relief Granted, Date 6-3-97, TAC No. M88559.

* Relief Request RR-51, Line 351, Weld 351-2, >90% examination coverage. NRCRelief Granted, Date 11/7/2000, TAC No. MA6909.

ASME Code Category B-K, "Integral Attachments for Pumps," (Item No. B10.10),are not listed in Table 1. Relief was submitted and granted for coverage in thefollowing approved relief request:

* Relief Request RR-38, Documentation of less than 90% coverage, RCP integralwelded attachments. NRC Relief Granted, Date 3-21-00, TAC No. MA5918.


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Class 2 (Quality Group B)

ASME Code Categories C-A, C-B, C-C, (Item Nos. C1.10, C1.20, C2.31, C3.10), arenot listed in Table 1. Relief was submitted and granted for coverage in the followingapproved relief requests:

* Relief Request RR-16, Residual Heat Exchange nozzle to vessel and integralattachment welds. NRC Relief Granted, Date 6-3-97, TAC No. M88559.

* Relief Request RR-52, RHRHX, Welds RHX C22-1 & C22-2. NRC ReliefGranted, Date 11/7/2000, TAC No. MA6909.

5. Burden Caused By Compliance

Compliance with the examination coverage requirements of ASME Section Xl wouldrequire extensive engineering, modification, redesign, or replacement ofcomponents where geometry is inherent to the component design.

6. Proposed Alternative and Basis for Use

Proposed Alternative

A) The components listed in Table 1 have already been examined by the availablemethods to the maximum extent practical. No additional volumetric or surfaceexaminations will be performed on the components for the 3rd InserviceInspection Interval.

B) A visual inspection (VT-2) was performed by VT-2 qualified operators on thesubject components during the system pressure tests (with no leakage detected)as required by code category B-P (each refueling outage).

Basis for Use

The Reactor Pressure Vessel and Pressurizer, and class 1 piping were designedand fabricated to Codes in effect during the late 1960's. These Codes did not requirethat there be full access for Inservice inspection, as was required by later Codes.

ASME Code Category B-A, Item No. B13.22, Meridional Welds-RVHM-2, RVHM-4, &RVHM-6: The RV closure head peel segment to disc circumferential weld andportions of the intersecting meridional welds are completely enclosed within thepattern of CRDM penetrations inside the shroud and, as such, are completelyInaccessible for volumetric examination as would be required by IWB-2500. (SeeAttachment 1)

ASME Code Category B-A, Item No. B1.40, RV Head Flange Circ Weld RVHC-2:The Reactor Vessel Flang-to-Head circ weld has limited accessibility due to thecontour of the flange head and the interference of the lifting lug. (See Attachment 2)

ASME Code Category B-D, Item No. B3.120, Pressurizer Spray & Surge NozzleInside Radius Welds PZRN-1 and PZRN-6: The nozzles of the pressurizer are castwith the vessel heads. The as-cast surface of the heads combined with thegeometry of this area makes ultrasonic examination of the inner radii impractical.


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The spray nozzle inner radius (PZRN-1) is also covered by an array of nozzle heads.The surge nozzle inner radius (PZRN-6) is also inaccessible due to the area beingcovered by a retaining basket. (See Attachment 3)

ASME Code Category R-A, Item No. R1.20, RCS Pipe to Safe-End Circ WeldsRCC-21-1, RCC-22-1, RCC-23-1, and RCC-24-1: These reactor vessel pipe to safeend had limitations due to the tapered area of the weld overlay on the ID of the pipe.(See Attachment 4)

Physical obstructions imposed by design, geometry and materials of constructionare typical of vessel appurtenances, structural and component support members,adjacent component weldments in close proximity, and unique componentconfigurations.

As a minimum, all components received the required examination(s) to the extentpractical with regard to the limited or lack of access available. The examinationsconducted confirmed satisfactory results evidencing no unacceptable flaws present,even though "essentially 100%" coverage was not attained. IP2 has concluded thatif any active degradation mechanisms were to exist in the subject welds, thosedegradations would have been identified in the examinations performed.

For volumetric (ultrasonic) examinations, the transition to PDI examinations variedthe means of coverage determination based on code requirements. Earlier Codeexamination coverage was determined by a simple average of the examinationscans performed. Later examinations performed per PDI requirements identifycoverage based on a simple average of the scans per the requirement of PDI andCFR. The attachments within identify the means of determining examinationcoverage and are based on the requirements at the time the examinations wereperformed.

To summarize, IP2 has examined all components in the 3rd 10-Yr Interval ISIProgram and associated augmented programs to the maximum extent possiblegiven the inspection limitations discussed above.

When the IP2 ISI Program is viewed in total, the overall degree of coverageobtained is still greater than 90%, i.e. essentially 100%. For this and the otherreasons detailed in this request, Entergy believes that the limited coverage obtainedon the components listed in Table 1 is not significant and will provide an adequatelevel of quality and safety for examination of the affected welds, and will notadversely impact the health and safety of the public.

.7. Duration of Proposed Alternative

Relief is requested for the third ten-year interval of the Inservice Inspection Programfor Indian Point Unit 2, which began July 1, 1995 and concluded March, 2007.


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8. Attachment

Indian Point Unit 2 Third Interval ISI program datasheets for examinations with lessthan "Essentially 100%" coverage are attached (Attachments 1 - 4)

9. References

I. NRC Information Notice 98-42, "Implementation of 10CFR50.55a(g) InserviceInspection Requirements."

2. ASME Section XI Code Case N-460, "Alternative Examination Coverage forClass 1 and Class 2 Welds."

3. ASME Section XI Code Case N-613-1, "Ultrasonic Examination of FullPenetration Nozzles in Vessels, Examination Category B-D, Item No's. B3.10and B3.90, Reactor Nozzle-To-Vessel Welds."

4. Relief Request RR-63, Risk-Informed In-service Inspection Program. ASME CatB-F, B-J. Ref: EPRI TR-112657. NRC Relief Granted, Date 03/19/2004, TACNo. MC0624.

5. Relief Request RR-67, Code Case N-613-1: Alternative for reduced (UT) examfor Full Penetration Nozzles in Vessels, ASME Category B-D, item No's. B3.10and B3.90. NRC Relief Granted, Date 7/7/2004, TAC No. MC1698.

6. Relief Request RR-73, Extend the Third 10-Yr Reactor Vessel Weld ExaminationInservice Inspection one refueling cycle; including ASME Code Categories B-AItem B1.12, Item B1.21, Item B1.22, Item B1.30, ASME Code Category B-D,Item B3.90, & Item B3.100. NRC granted via SER, TAC No. MC7306, datedFebruary 22, 2006.


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Table 1

Summary of Components with Less than "Essentially 100% Code Required Coverage"

~ASME' to,,Pretg I. •C.... ASME , ,Component ... Component -i.. NDE Condition L imeiting]e N RCS ID[ 1 MrV TMethod CodI ergnaccesibedut e o

tecipii y 'Achievedl

UppRCSern elds (UoMT) CRDM Penetration 85% Attachment1B-A BRVHM-2 U and Shroud area.

B Inaccessible due to aRV Upper Head VolumetricB-A B1.22 RCS RVHM-4 CRDMn d Penetration 85% Attachment 1

I•Merio onal vvelds (UT)_____________ and Shroud area.

______ jInaccessible due to

Uppe Hea 1One sided examB-A B i .40 RCS RVHC-2 RV Upper Head Volumetric j due to Flange and 50% Atcmn2

B-AB1.0 CS VH-2 lane eld •/(UT/MT) •: Head shroud

i• •_ interference

B-D B3.120 2 RCS PZRN-1 Ienner (t f nozzerhed ad 0% baAttachment 3J_ __ __ 1 Radius Weld (UT)

RI Ups er Surg 1 Volumetric Covered by a IB-D B3.120 RCS U PZRN-6 Noz. Inner Radius I retaining basket 0% Attachment 3

__g e Weld (UT'...')RCS Pipe to Safe-, . Limitation dueto

R-DA B3Ri .201 RCS RCC 21-1 1 End Circ Weld VolumTric of the 88% Attachment 4metric Cotaered areaJ R@20 0

I (UT) orerainong thekeD


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RRSMEE tapero d of tCo ~ ASMVE Component ~Component~ NDE Cndition Limiting- erea o

Ie tem N. ID Description Method Coverage I DCatecioryl _____ __ _________ ____ ___________ ___

]RCSPipe to@Safe- 1, Limitation due to I -

R.0 RC C 221 End Circ Weld Volumetrice of the 88.5% Attachment 4i-I- R1.20 ROS RCC22-1 RO@1580 (UT) overlay on the ID _______ __

1. n P t UtRCS Pipe to Safe- Volumpetric Lmatsionfued tR-A Ri1.201 ii RCS RCC 23-1 End Circ Weld Tt) tapered area of the 89% Attachment 4i

welds ithdtmninfe iRO@3380 omleo verlay on the IDrcufeenialpiinwedsweeasine1RS e Circ werel c Lmitation due to

R-A R1.20 RoCS RCC 24-1 Eoneusd (UT) taper area f the 89% n Attachment____ -_____________ 0 overlay on the ID _ _____

Notes:

1 . Indian Point Unit 2 received NRC approval on March 19, 2004 (TAO No. MC0624) to implement a risk-informed inspection program for Class 1 CategoryB-F and B-J piping welds based on the methodology detailed in EPRI Topical Report TR-1 12657, Revision B-A, and Code Case N-578 as an alternativeto the requirements of the 1989 edition ASME Xl code, No addenda. The risk-informed methodology used at IP2 includes all category B-F and B-Jwelds in the determination of the final risk-informed inspection sample of 61 Class 1 welds. In 2006, Class 1 circumferential piping welds were assignedalternate examination category and code item numbers that were consistent with ASME Section XA Code Case N-578-1. The numbering systemestablished in Code Case N-578-1 is similar to the one used in Code Case N-578. However, the Code Case N-578-1 numbering system is morecomplete and more accurately reflects the technical criteria established in EPRI Topical Report No. TR-1 12657. For these reasons, the numberingsystem established in Code Case N-578-1 was used instead of the one shown in Code Case N-578; and is carried forward into the fourth interval. Itemnumber RI.20 as shown in Table 1 of RR-CRV-75 is not listed in Code Case N-578 but was included in Code Case N- 578-1 as a means to categorizeelements that are not subject to a damage mechanism. Inclusion of item number R1 .20 in Table 1 has no substantive impact on relief request RR-CRV-75.


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Attachment 1

Code Category B-A: Pressure Retaining Welds in Reactor Vessel

Item No. B1.22 Reactor Vessel Closure & Bottom Head Welds - Meridional

Components Numbers:

RVHM-2 Reactor Vessel Bottom Head Weld - MeridionalRVHM-4 Reactor Vessel Bottom Head Weld - MeridionalRPVM-6 Reactor Vessel Bottom Head Weld - Meridional

Basis:

Meridional welds RVHM-2, RVHM-4, & RVHM-6 exam coverage are obstructed by theCRDM penetrations, RV head shroud, and flange contour. Examinations of thesemeridional welds were conducted to inspect as much as reasonably practical. These examswere limited by geometry or access. (See Relief Request RR-06, Rev.1, Reference 1,below)

The total meridional weld length from the RV head flange weld to the top of the head peelsegment weld is -57 inches. With the head shroud cover in place, approximately 32 inchesof weld length is inaccessible; therefore, only -25 inches of weld length is accessible forexamination. Of this accessible weld length of -25 inches, only 85% of exam coverage wasobtained, which is less then 91% coverage as stated in the NRC SER (Reference 1 below).

In summary, the reactor vessel closure head meridional welds were volumetrically examinedto the extent practical. Three of the six meridional welds (RVHM-2, RVHM-4, & RVHM-6)were available for approximately 85% rather than 91% of their length for volumetricexamination. Attachment 1 shows the Reactor Vessel drawing with the shroud and CRDM'scovering most of the meridional welds and the

References

1. Relief Request RR-06, Rev. 1, for Items B1.21 and B1.22 has been previouslygranted for RVHM-2, RVHM-4, RVHM-6, RVHM-1, RVHM-3, & RVHM-5 via SER,TAC No. M88559, dated June 3, 1997.


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Attachment 1

RV Upper Head CRDMs/ShroudSupport (Ref. 206913)

-GQYG "W.. V4k.Atd" 0`44

FGw* A"06-

REACTOR PZE55URE VE55ELNO1 A T"U C,4147ATI-W. Fall


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Attachment 1

RV Upper Head Meridional Welds/CRDMs/Shroud (Ref. 206913)

-A rCT1P

COMATNOL ~OD DEIVE.

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SFC.ION B-


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Attachment 1

RV Upper Head Meridional Weld RVHM-2

Weld No.: RVHM2Summary No.: 206913-RVHM2Report No.: 04-UT097Page 5 of f-

c - '.T

Coverage Plot

1. The weld was scanned 100% perpendicular with a 600 RL using a Zone 1and Zone 2 Cal.

2. < 100% coverage was achieved when scanned parallel to the Weld due to theflange at the bottom of the weld and a taper 25" up on the weld.

3. < 1% of the lower 15% of the weld was scanned in all four directions.

4. Using one sided qualified personnel, 100% of the upper 85% was covered inone direction perpendicular and one direction parallel.

5. Weld coverage of the lower 25" of the weld = 85%.

V -O

'4


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Attachment 1

RV Upper Head Meridional Weld RVHM-4

Supplemental Report •7L 3 oW3

Report No.: 06-UT097

Page: 2 of 2

Summary No.: 206913-RVHM4

Examiner: Serth, Joseph Lvel: PDI Reviewer: Date:

Examiner: Gronewod .,PDI Site Revie. Date:

Other: NIA l: NVA ANII Review: Date:

Comments:

Coverage Plot

1. The weld was scanned 100% perpendicular with a 60" RL using a Zone 1 and Zone 2 Cal.

2. < 100% coverage was achieved when scanned parallel to the weld duo to the flange at the bottom of the weld and a taper25" up on the weld.

3. < '% of the lower 15% of the weld was scanned In all four directions.

4. Using one sided qualified personnel. 100% of the upper 85% was covered in one direction perpendicular and one directionparallel.

5. Weld coverage of the lower 25" of the weld = 85%.


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Attachment 1

RV Upper Head Meridional RVHM-6

Weld No.: RVHM6Siumtnivr No,: 206913-RNIVHN6Report. No.: 04-,UT084Page (. of 6

Coverage Plot

1. The weld was scanned 1001% perpendicular with a 60' R.L using a Zone Iaind Zone 2 Cal.

2. < 100"0% coverage wva achieved when an::!nred parallel Io the weld due to the

iilange at the bottof) of the weld aind a taper 25" tilu on ihe weld.

3. < I (X f lthe lower I 5% of the weld was s anned in all four directions.

4. Using one sided qualilied pt-rsonnel,. 1(00'X of the tipper •5'ý/% was covered inone direction perpendicular aind one direction parallel.

5. Weld coverage of the lower 25" ofi die weld 85%.

6Cc"

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.X .,. .. .-I.-I /

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Attachment 2

RV Flange-to-Head Weld RVHC-2

Code Category B-A: Pressure Retaining Welds in Reactor Vessel

Item No. B1.40 Reactor Vessel Closure Head Flange-to-Head Weld -Circumferential

Components Number:

RVHC-2 Reactor Vessel Closure Head Weld - Circumferential

Basis:

Table IWB-2500-1, Examination Category B-A, Item B1.40, requires 100% volumetric andsurface examination of the reactor vessel head-to-flange weld, as defined by Figure IWB-2500-5. Entergy performed the volumetric examination to the extent practical; resulting inapproximately fifty percent (50%) of the weld volume was ultrasonically examined for 2/3 ofthe weld length in 1997. Eighty four percent (84%) coverage was obtained using updatedequipment and better technique in the last 1/3 of the weld length in 2004 (See attached).The surface examination conducted confirmed satisfactory results evidencing nounacceptable flaws present. Based on the percent of the volumetric examination completedand the Code-required surface examination, it is reasonable to conclude that degradation, ifpresent, would have been detected.

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Attachment 2

RVHC-2 Flange to Head

Cu-st-uc:ors Pag

Weld


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Attachment 2

RVHC-2 Flange to Head Weld

Co~struc-ors Page 2 of _Z_

INSP~T1ON SKETCH SHEETINSPECTICN SKETCH SHEET

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PAGE 8 OF 15

)Westinghouse LIMITATION TO EXAMINATION

,LANT INDIAN POINT UNIT 2 SKETCH A206913-1

;YST .COMP RPV .__..__l___.// PROCEDURE IPEC-UT-210, Rev. 1

XAMINE R . / .. : DATE 11/4/2004

IELAAED TO: UT X PT MT VT IDENT. NO- RVHC2 "Head to Flange"

ROVIDE GENERAL INFORMATION TO DESCRIBE APPROXIMATE SIZE, LOCATION AND TYPE OF LIMITATION.

S0' 100% 760- 9=84%ICCW 45' 100%cW 45° 100%

LKDN 45' 100%LKUP 45' 39%

COWv 60% 100%CW 60% 100%

LK DN 60% 100%

LKUP 60% 21%

NTERGY REVIEW I DATE" I ANIIREV

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Attachment 3

Code Category B-D: Full Penetration Welds of Nozzles in Vessels

Item No. B3.120 Pressurizer Nozzle Inside Radius Section

Components Number:

PZRN-1 Pressurizer Spray Nozzle Inner RadiusPZRN-6 Pressurizer Surge Nozzle Inner Radius

Basis

During the remote visual examinations of the Pressurizer inner radius examinationsconducted in May of 1997; an assessment of the ability to remote visually examine thePZRN-1 & PZRN-6 nozzles were conducted by a Level III visual examiner. The remotevisual examination revealed that the thermal shield used in the manufacture of the PZRN-1nozzle completely blocks the view of the inner radius. PZRN-1 is also covered by an arrayof nozzle heads. PZRN-6 is also inaccessible due to the area being covered by a retainingbasket. Further, discussions that were had with the two ISI examination vendors thatserviced Indian Point 2 during the Third Interval confirmed our earlier opinion that the nozzleconfiguration of both the PZRN-1 and PZRN-6 nozzles precluded the examination of thoselocations, even with the most advanced ultrasonic systems, currently in use. No coveragewas obtained. (See Attachment 3).

In lieu of the Code-required volumetric examination once in ten years, the PressurizerSpray and Surge nozzle areas, PZRN1 & PZRN-6, were visually examined (VT-2) aftereach refueling outage for evidence of leakage during system pressure tests performed inaccordance with IWB-2500, Category B-P, and Code Case N-498. As a result no evidenceof leakage were detected these areas. It is expected than any through wall defects wouldbe detected by this examination prior to failure of the pressurizer. This is based on theexpectation that the component would experience leakage before a catastrophic failure("leak before break").

The inner radius area of pressurizer nozzles PZRN-2, PZRN-3, PZRN-4, and PZRN-5 wereexamined as proposed by Indian Point 2 Relief Request 9, Rev. 1, Reference 1. NozzlesPZRN-2, PZRN-4, and PZRN-5 were completed in May of 1997, and Nozzle PZRN-3completed in April of 2006; with no recordable indications.

References:

1. NRC SER Relief Request RR-09 Rev. 1, Granted Date 6-3-97, TAC No. M88559.

2. Westinghouse Drawing No. 681J281, "General Assembly & Final Machining(1800 CU FT) Pressurizer.

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NL-08-053Page 25 of 71


Attachment 4

Code Category R-A: Risk-Informed RV Nozzle Safe-End Weld(Formally Category B-F)

Item No. R1.20 Reactor Vessel Nozzle Safe-End Welds -Circumferential

Components Number:RCC 21-1 RCS Pipe to Safe-End Circ Weld RO @ 2020RCC 22-1 RCS Pipe to Safe-End Circ Weld RO @ 1580RCC 23-1 RCS Pipe to Safe-End Circ Weld RO @ 3380RCC 24-1 RCS Pipe to Safe-End Circ Weld RO @ 0220

BasisExamination Data Summary

All automated ultrasonic examinations (implementation of Appendix VIII) were conducted inaccordance with the ASME Code, Section XI, 1995 Edition with 1996 Addenda as modified by1 OCFR50.55a(b)(2Xxiv, xv and xvi). Examination scan plans were prepared to the requirementsof procedure PDI-ISI-254-SE Rev. 2.

Code Examinations

Examinations were conducted completely by the contact technique using two WesDynePARAGON multi-channel data acquisition systems, one interfaced to each SUPREEM robot andscanning platform. All examinations were conducted to the maximum extent practical with theaccess provided and within the limitation of component geometry.

Ultrasonic detection scans for the primary nozzle to safe-end and safe-end to pipe/elbow weldswere examined from the ID surface using 700 L- wave transducers applied four-directionally.Axial scans were performed at a 0.25" increment and the circumferential scans were conductedat a 0.080" incremental distance. This exam interrogated the inner 1/3 thickness volume. Thesafe-end to nozzle welds (RCC-21 -1, RCC-22-1, RCC-23-1, & RCC-24-1) had limitations due tothe tapered area of the weld overlay on the ID (See Attachment 4). Eddy current techniqueswere also employed to examine the inner surfaces of the dissimilar metal and pipe/elbow weldsand the adjacent examination volumes where ID geometry presents a limitation to the detectionof axial flaws as defined in the PDQS for the qualified Appendix VIII technique. As a result, allareas of limitations were fully examined by the supplemental eddy current techniques with norecordable indications.

Examination Results (primary Inlet and Outlet Nozzles)

Automated ultrasonic examinations of the Indian Point Unit 2 Primary Inlet and Outlet RV Nozzlewelds had no recordable indications. Supplemental eddy current examinations of the Nozzle toSafe End and Safe End to Pipe/Elbow welds from the nozzle bore yielded no recordableindications.


NL-08-053Page 26 of 71


Attachment 4

Reactor Vessel Nozzle Safe-End Welds (A206913)

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NL-08-053Page 28 of 71


Attachment 4

RV Nozzle Circ Weld RCC-21-1 (Datasheet)

REACTOR VESSEL WELD RESULTS SUMMARY

PLANT NAME Indian Point Unit 2

WELD NO. RCC-21-1 COMPONENT Outlet Pipe @ 22'"

LIMITATIONS: NO j- YES KI See Coverage Breakdown Sheet

RESULTS NO. OF INDICATIONS' N/A

NI X STATUS N/IA

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EXAM DOCUMENTATION INDICATION DOCUMENTATION

L-I PARAGON ANALYSIS LOG LI ASSESSMENT SHEET

Lii PARAGON ACQUISITION LOG -,- PARAGON HARD COPY

fxj_ SCAN PRINT OUT =- OTHER (Specify)

F-ICOVERAGE BREAKDOWN

Comments:Procedure limited for the detection of axial flaws per the PDI issued PDQSdocument, CW/CCW scans were peifromed and areas of limitation were fu ___

examined _by -Lip1,enentai Eddy Current Technues.------.-

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R.V. COVERAGE ES. ATE BREAKDOWNS

PLANT NAME Indian Point

WesDyneWELD NO. RCC-21-1

InternationalCOMPONENT Outlet Pipe @ 2020

BEAM ANGLE BREAK DOWN

BEAM DIRECTION 70 L. _ __"__ __'__"_'"

____ ____ ___ Code -MRP ____

Perpendicular 97.00 97.00

Parallel 79.00 77.00

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10 Year Reactor Pressure Vessel ISILimited Examination Coverage Summary Table

CODE COVERAGE MRP COVERAGE~

RCC-21-1 AX 206.81 5.3 97 NIA- N/A N/A Litt-Of f due to overlay N/A

i transitionRCC2 -1 C~c 06.1 3,5 9 iA N/A NIA Lift-Off due to overlay t00

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The perpendicular scans were limited in select areas around the circumference and not 360 degrees, The circ scans were limited 360 degree in theeffected areas, Eddy Current examination was used to supple79entthe limited areas and obtained 100LO coverage

Exam ner:. Date:Examinet: .<-" 1•:.--5/;'- Date: "7?~', "bL '/:'

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DATA ACQUISITION LOG # 202-SE

Utility: Entergy Plant: Indian Point _ Uni: 2 1Outage:- R17Procedure No: PD.-S-254-SE I Procedure Rev. No.:Applicable Sensitivity Calibration Data Sheet N .o____-__ E___E-0

UT Examiner Signature: ! / •,A-.,/ / evel: Ill D2at: 05-02-06

Data File Name Weld No/ Index' Scan Total # 'AVE' Gain 1 I Date Time CommentsStart Start of Signal Adj. o ,Sweeps Amplitude (dB) &d

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NL-08-053Page 38 of 71


Attachment 4




WELD NO. RCC-22-1 COMPONENT Outlet Pipe @ 158"

LIMITATIONS: NO E] YES [F] See Coverage Breakdown Sheet

RESULTS NO. OF INDICATIONS N/A

NI X STATUS N/A

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=t- COVERAGE BREAKDOWN

Comments.Procedure limited for the detection of axial flaws per the PDI issued PDOSdocument. CW/CCW scans were perfromed and areas of limitation were full_examined by supjlemental Eddy Current Techniques.

S/ _____________•__

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BEAM DIRECTION J70 L:ICode MRP I i .. =.



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UUMBINED AVE.RA(G 88.00. Analyst //A _,,/ Date 2________e7

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Page 1 of 1


Utility: Entergy Plant: I lndian Point

Procedure N'o:T P0-ISI-264-SE2Applicable Sensitivity Calibration Data Sheet No: DET-SE-01

T a. ..t . . ....

UT Examiner Signature:

Unit: 1 2 Outage: IR17

Procedure Rev. No.:

III Date: 05-02-06

Data File Name IndexStart

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WN158-SE-PRP-ON RCC-22-1 0. 11375' 366 CHI-9 -3 DS 05-02-06 0403_ CH2-9

WN158-SE-PAR-ON RCC-22-1 118.5' 01 52 1 CH1-12 -3 DS 05-2-06 2336CH2-10CH3-14CH4-9

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ANALYSIS LOG # 158-SE

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No. ci . =I e

WN158-SE-PRP-ON 1 :70 IN X ON 05-02-06WN1 58-SE-PRP-ON 2 70 OUT X ON 05-02-06WNt58-SE-PRP-ON 3 i0 NO WASTAGE DETECTED ON 05-02-08WN158-SE-PRP-ON 4 0 NO WASTAGE DETECTED DN 05-02-06

WN158-SE-PAR-ON 1 70 COW X DN 05-02-06WN158-SE-PAR-ON 2 70 0CW X ON 05-02-06

WN158-SE-PAR-ON 3 70 CCW X ON 05-02-06WN158-SE-PAR-ON 4 70 CW X ON 05-02-06

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WN1S58SE-PAR-ON I CIRC X FS 16-2-06

WN158-SE-PAR-ON 2 CIRC X FS I 6-2-06

WN-168-SE-PRP-ON I AXIAL X FS / 5.2-06

WN-*58-SE-PRP-ON 2 AXIAL X FS /5-2-06

_____ _ i__ _ _ _ __ _ _ _ _ J _ _ __ _ _ _ _ _ _ _ _

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NL-08-053Page 52 of 71


Attachment 4




WELD NO RCC-23-1 COMPONENT Outlet Pipe @ 338T

LIMITATIONS. NO fj YES [X7 See Coverage Breakdown Sheet


NI X STATUS N/A

RI


=XPARAGON ANALYSIS LOG ="-'ASSESSMENT SHEET

7]J PARAGON ACQUISITION LOG. .. L PARAGO.N. HARD CQPY

11 SCAN PRINT OUT = OTHER (Specify)

=COVERAGE BREAKDOWN

Comments:Procedure limited for the detection of axial flaws per the PDI issued PDQSdocument. CWtCCW scans were perfromed and areas of limitation were fullyexamined by supplemental Eddy Current Techniques.

Utility -eview - '' Dae /-- --Analyst , " -. ... Date• "--4

ANII Review______

_.

PLANT NAME

R.V. COVERAGE EST ATE BREAKDOWNS

Indian Point

WesDyneWELD NO.

COMPONENT

RCC-23-1

InternationalOutlet Pipe @ 3380


BEAM DIRECTION 70 L _______________

Code MRP



AVERAGE 89.00 88.00

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Comments: Procedure limited for the detection of axial flaws per the PDI issued PDQSdocument. CW/CCW scans were perfromed and areas of limitation were fullyexamined by supplemental Eddy Current Techniques.Limitation due to tapered area of the overlay 'n the ID- See sketch in Tab B //ICOMBINED AVERAGE 88.50

Analyst /A 4 -, / - Date Zýýc

00

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Comp... n . ie~iu .. iu ~ai atio ýarqinvAt o Examinatio Ex nn ~aiai x~~tpiCwt~ urn(T

RCC-23-1 Ax 206.81 2.1 99 N/A N/A N/A Lift-Off due to overlay N/Atransition

RCC-23-1 Circ 206".81 43.65 79 N/A N/A N/A Lift-Off due to overlay 100I__ _transition

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The perpendicular scans were limited in select areas around the circumference and not 360 degrees. The circ scans were limited 360 degree in theeffected areas. Eddy Current examination was used to sun~nlement the limited areas and n~htained I (1fl/, eoen•

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Utility: I Entergy _Plant: Indian Point Unit: 2 outage: R17Procedure No: PDI-ISI-254-SE Procedure Rev. No.: 2Applicable Sensitivity Calibration Data Sheet No: DET-SE-01

UT Examiner Signature:;o " Level: 1I Date: 05-02-06

Data File Name Weld Noo, Index Scan Total # 'AVE' Gain Date Time CommentsStart Start of Signal Adj.

Sweeps Amplitude (dB) &.2 (mmldd/yy)0-

WN338.SE-PRP-ON RCC-23-1 0. 113.75" 366 CH1-11 -3 DS 05-01-06 2227CH2-9

WN338-SE-PAR-ON RCC-23-1 118.5': 0. 52 CH1-12 -3 DS 05-02-06 2022CH2-10CH3-14CH4-9

Ene~yReview 72$') 1L ae 1

Forni 1Date 5-' -

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Disk No: I N/A

Utility: 1 Entergy

Procedure No: I PDM-ISI-254-SEPlant: I Indian Point Unit: I 2 Outage: I R17

Weld No: I-RCC-23-1 I Weld Type: I SE I Exam.

Procedure Rev. No.: 2

Surface- 1L0D

N Anal. Release: 6.1.6Applicable Sensitivity Calibration Data Sheet No: ] DET-SE-01

UT Examiner Signature: IIAcquisition Log No: i 338-SE I PARAGO I

Level: (i II Date: i 05-02-06

Data File Name UT" Beam Angle t NI RI RI Examiner ID I DateChannel Beam Direction Resolution / Comments / Limitations

No. .. a CV .•.CUG,

WN338-SE-PRP-ON 1 70 IN X DN 05-01-06WN338-SE-PRP-ON 2 70 OUT X DN 05-01-06WN338-SE-PRP-ON 3 0 NO WASTAGE DETECTED DN 05-01-06WN338-SE-PRP-ON 4 0 NO WASTAGE DETECTED DN 05-01-06

WN338-SE-PAR-ON 1 7 0 CCW X DN 05-02-06WN338-SE-PAR-ON 2 70 CW X ON 05-02-06WN338-SE-PAR-ON 3 70 CCW X DN 05-02-06WN338-SE-PAR-ON 4 70 CW X ON 05-02-06

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Procedure No: WDI-STD-146

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Applicable Sensitivity Calibration Data Sheet No: ET-1

Plant: Indian PointUnit: 2 I Outage: 2R17

I Procedure Rev. No.: 5WldT~ype; SAFE END

ET Examiner Signature:: Level I

Acquisition Log No: SE-338

Dat52-06

Data ET ET Probe Scan NI RI RI Examiner ID 1 Date

File Name Probe Direction Resolution I Comments I LimitationsNo. A~a rC.l

WN338-SE-PAR-ON I CIRC X FS /'6-2-06

WN338-SE-PAR-ON 2 CIRC X FS / 5-2-06

WN-338-SE-PRP-ON 1 AXIAL X FS 15-2-06

WN-338-SE-PRP-ON 2 AXIAL X FS / 5-2-06

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NL-08-053Page 62 of 71


Attachment 4




WELD NO. RCC-24-1 COMPONENT Outlet Pipe weld @ 22'

LIMITATIONS: NO I YES __ see Coverage Breakdown Sheet


NI X STATUS N/A

RI


-,PARAGON ANALYSIS LOG Li ASSESSMENT SHEETi-- 1PARAGON ACQUISITION LOG LZPARAGONHARDCOPY

)K.'jSCAN PRINT OUT =i] OTHER (Specify)

-- COVERAGE BREAKDOWN

Comments:Procedure limited for the detection of axial flaws per the PDI issued PDOSdocument. CW/CCW scans were perforned and areas of limitation were fullyexamined by supplemental Eddy Current Technirqss.

Utility Revie - "S)Anaiyst 4"' ' Date:

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Comments: Procedure limited for the detection of axial flaws per the PDI issued PDQSdocument. CW/CCW scans were perfromed and areas of limitation were fully

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COMBINED AVERAGE 88.50: Analyst / Date %/ 4'z. / / - -

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Page 1 of 1


Utility: Entergy _ _Plant: Indian Point Unit: 2 O R

Procedu. Po64-SE P edure Rev. No.: 2Applicable Sensitivity CaliWration DataShtetNo.] DET-SE-01

UT Examiner Signature: Level: II Dt / *

Data File Name Wel, N I. index Scan Total # AVE' Gain I Date Time CommentsStart Start of Signal Adj. .

Sweeps Amplitude (dB) . i

WN22-SE-PRP-ON RCC-24-1 0° ! 113.75- 366 CHl-11 -3 DS 05-01-06 00091 52 CH2-10

WN22-SE-PAR-ON RCC-24-1 118.5-- 0. 52 CHI-9 -3 JJJ 05-02-06 1631 iCH2-7

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.... ...: .N.A .......Utility; Entergy Pln;.ninPitUi: 2 Outage: IR17Procedure o.: P.....IP-I2o5e , Rev. No.: 2Weld No: I.RC -24-1 Weld-Type: SE Exam. Surface: IDApplicable Sensitivity Calibration Data Sheet No: 60DET-SE-01 Acquisition Log No: 1 22-SE j PARAGON Anal. Release: 6.1.6I / \ -o_-- -- •--;_. 1• ... • Le .e.. I li/ N Dat-e- 05-02-06--

Data File Name UT Beam Angle wI ,•/ RI RI Examiner ID ! DateChannel Beam Direction Resolution I Comments / Limitations

WN22-SE-PRP-ON 1 ý70 iN X DN 05-01-06WN22-SE-PRP-ON 2 70 OUT X DN 05-01-08WN22-SE-PRP-ON 3 0 NO WASTAGE DETECTED DN 05-01-06WN22-SE-PRP-ON 4 0 o NO WASTAGE DETECTED DN 05-01-06

WN22-SE-PAR-ON 1 7i0 CCW X DAM 05-02-06WN22-SE-PAR-ON 2 70 CW X DAM 05-2-06WN22-SE-PAR-ON 3 70 CCW X DAM 05-02-08WN22-SE-PAR-ON 4 70CW X DAM 05-02-06

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Utility: Entergy Plant: Indian Point Unit: 2 1 Outage: 2R17

Proceduwe No: WDI-STD-146 Procedure Rev. No,: 5

Weld No. RCC-24-1 Weld Type: SAFE END

Applicable Sensitivity Calibration Data Sheet No: ET1 Acquisition Log No: SE.22

ET Examiner Signature: 1_ . Level 11.. . . . . . . . . . Date: 5-3-06. ....... _- - -... .. .-.. _ ... .... ...

-7___________________ 1j ____________

Data

File NameET

ProbeNo,

ET Probe ScanDirection

Ni RI RIResolution I Comments I Limitations

Examiner ID I Date

WN22-SE-PAR-ON 1 RX JDF 15-306WN22-SE-PAR-ON 2 1 CIRC X JDF / 5-3-06

WN-22-SE-PRP-ON 2 AXIAL X JDF I-3-06

WN-22-SE-PRP-ON . 2 AXIAL X JDF 15-3-06

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InternationalCOMPONENT Outlet Pipe weld @ 220


BEAM DIRECTION 70L J I " -....... Code I MRP ..


Parallel 79.00 7-7.00

AVERAGE .... 89.00 818.00

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Comments: Procedure limited for the detection of axial flaws per the PD1 issued PDQSdocument. CW/CCW scans were perfromed and areas of limitation were fullyexamined by supplemental Eddy Current Techniaues.Limitation due to tapered area of the overlay on the ID- See sketch in Tab B

COMBINED AVERAGE 88.50' I IAnalyst - Date _ /_/__ ___

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Documents

Indian Point Energy Center 450 Broadway, GSB En TO?' · ASME Cat B-D. NRC Relief Granted, Date 6-3-97, TAC No. M88559. ASME Code Category B-J "Pressure Retaining Welds in Piping"