Text

Attachment 2, ANP-3418NP, Revision 0, Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2) Licensing Report. (Non-Proprietary)
	ML16004A179
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/31/2015
From:	; AREVA
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML16004A183	List: 1CAN121502, Evaluations Described Response to Requests for Additional Information 3, 5, 6(a), and 7, Reactor Vessel Internals Aging Management Program Plan; ML16004A179;
References
	1CAN121502 ANP-3418NP, Rev. 0
	Download: ML16004A179 (124)
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Attachment 2 to 1CAN121 502 AREVA Document ANP-3418NP, Revision 0, "Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2) Licensing Report" NON-PROPRIETARY

AR EVA Arkansas Nuclear One Unit I Reactor ANP-3418NP Revision 0 Vessel Internals License Renewal Scope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2)

Licensing Report December 2015 AREVA Inc.

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq Report Pagqei Nature of Changes Section(s)

Item or Page(s) Description and Justification 1 All Initial Issue

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pacqe ii Contents

1.0 INTRODUCTION

..................................................................... 1-1 2.0 METHODOLOGY.................................................................... 2-1 3.0 COMPARISON....................................................................... 3-1 3.1 Scope Definition .............................................................. 3-1 3.1.1 Identification of ANO-1 License Renewal Scope for RV Internals........................................................... 3-2 3.1.2 Component Items and Welds Contained in MRP-189, Rev. 1I................................................................. 3-6 3.2 Component Item and Weld Comparison .................................. 3-39 3.2.1 Plenum Cover Welds ............................................... 3-42 3.2.2 Plenum Cylinder and Reinforcing Plate and Round Bar Welds ........................................................... 3-42 3.2.3 Tie Plate and Weld for Replacement UCB Bolting ............... 3-42 3.2.4 Miscellaneous Locking Device Parts and Welds for the Vent Valves...................................................... 3-43 3.2.5 Tie Plate Weld for Replacement LTS Bolting ..................... 3-50 3.2.6 RVLMS Probe Supports and Welds within the RV Internals ............................................................. 3-51 3.2.7 Remaining Surveillance Specimen Holder Tube (SSHT) Assemblies ................................................. 3-51 3.2.8 Thermal Shield Welds .............................................. 3-52 3.3 Material Comparison........................................................ 3-53 3.4 Program Modification Assessment........................................ 3-59 3.4.1 Identification of Screening Parameters............................ 3-59 3.4.2 Characterization and Screening for Degradation................. 3-76 3.4.3 Failure Modes and Effects Criticality Analysis (FMECA)............................................................. 3-85 3.4.4 Engineering Evaluation and Assessment ......................... 3-99

4.0 CONCLUSION

S ..................................................................... 4-1

5.0 REFERENCES

....................................................................... 5-1

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe iii List of Tables Table 3-1 Comparison of ANO-1 RV Internals License Renewal Scope to MRP-189 Revision 1 Component Items................................... 3-13 Table 3-2 Comparison of ANO-1 RV Internals License Renewal Scope to MRP-189 Revision 1 Welds................................................ 3-24 Table 3-3 Component Items and Welds within ANO-1 RV Internals License Renewal Scope but Not Contained in MRP-1 89, Revision 1............ 3-40 Table 3-4 Component Items and Welds within ANO-1 RV Internals License Renewal Scope and Contained in MRP-189, Revision 1 but With Different Material Designations ............................................. 3-53 Table 3-5 Plenum Cover Screening Parameters ...................................... 3-62 Table 3-6 Plenum Cylinder Welds Screening Parameters .......................... 3-62 Table 3-7 Tie Plate and Weld for Replacement UCB Bolting Screening Parameters................................................................... 3-63 Table 3-8 Miscellaneous Locking Device Component Items and Welds for the Vent Valves Screening Parameters ....................................... 3-64 Table 3-9 Tie Plate Weld for Replacement LTS Bolting Screening Parameters .. 3-67 Table 3-10 RVLMS Probe Supports within the RV Internals Screening Parameters.................................................................. 3-67 Table 3-11 Remaining SSHT Assemblies Screening Parameters ................... 3-72 Table 3-12 Thermal Shield Screening Parameters.................................... 3-74 Table 3-13 Plenum Cover Screening Results ......................................... 3-77 Table 3-14 Plenum Cylinder Welds Screening Results.............................. 3-77 Table 3-15 Tie Plate and Weld for Replacement UCB Bolting Screening Results....................................................... ................ 3-78 Table 3-16 Miscellaneous Locking Device Component Items and Welds for the Vent Valves Screening Results ............................................ 3-78 Table 3-17 Tie Plate Weld for Replacement LTS Bolting Screening Results........3-80 Table 3-18 RVLMS Probe Supports within the RV Internals Screening Results....3-80 Table 3-19 Remaining SSHT Assemblies Screening Results ........................ 3-83 Table 3-20 Thermal Shield Screening Results......................................... 3-84 Table 3-21 Plenum Cover EMECA Results ............................................ 3-86 Table 3-22 Plenum Cylinder Welds FMECA Results ................................. 3-86 Table 3-23 Tal -3 Tie Plate and Weld for UCB Bolting FMECA Results.................... 3-87

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paae iv Table 3-24 Vent Valves EMECA Results .............................................. 3-88 Table 3-25 Tie Plate for Replacement LTS Bolting FMECA Results ................ 3-91 Table 3-26 RVLMS Probe Supports within the RV Internals FMECA Results ..... 3-92 Table 3-27 Remaining SSHT Assemblies FMECA Results .......................... 3-96 Table 3-28 Thermal Shield FMECA Results........................................... 3-98

AR EVA Inc. AN IP-3418NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

I irn*.ninn Rennrt PoAa v List of Figures Replacement UCB Bolts with 2-Hole and 3-Hole Tie Plates and Figure 3-1 Locking Cups at ANO-1 .................................................... 3-43 Figure 3-2 Core Support Shield Assembly ............................................ 3-45 Figure 3-3 Vent Valve Assembly....................................................... 3-46 Figure 3-4 Typical Core Support Shield Vent Valve - Outside (RV Side) View....3-47 Figure 3-5 Typical Core Support Shield Vent Valve - Inside (Core Side) View....3-48 Figure 3-6 Schematic of Select Original Vent Valve Locking Device Component Items - Cross-Section View.... .............................. 3-49 Figure 3-7 Schematic of Select Modified Vent Valve Locking Device Component Items........................................................... 3-50 Figure 3-8 LTS Bolts (Replacement) and LOB Bolts (Original) at ANO-1 (LOB Bolt Locking Clip Not Shown).............................................. 3-51

AREVA Inc. A IP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Repoort P~aqevi II I ==

Nomenclature Acronym or Definition Abbreviation ANO-1 Arkansas Nuclear One Unit 1 AMP Aging management program AMR Aging management review ASTM American Society of Testing and Materials ASME American Society of Mechanical Engineers (now ASTM International)

B&PV Boiler & Pressure Vessel B&W Babcock and Wilcox BWOG B&W Owners' Group CBA Core barrel assembly CFR Code of Federal Regulations CRDM Control rod drive mechanism CRGT Control rod guide tube CSA Core support assembly CSS Core support shield CUE Cumulative usage factor DCP Design change package EPRI Electric Power Research Institute FCA Eield change authorization ED Elow distributor EMECA Eailure modes, effects, and criticality analysis I&E Inspection and evaluation IASCC. Irradiation assisted stress corrosion cracking IE Irradiation embrittlement ISI Inservice inspection ISR Irradiation-enhanced stress relaxation LCB Lower core barrel LIA Lower internals assembly LOCA Loss of coolant accident LRA License renewal application LTS Lower thermal shield MRP Materials Reliability Program NRC Nuclear Regulatory Commission NSSS Nuclear steam system supplier

AREVA Inc.Ai IP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2) i kensina Re[}ort Paae vii Acronym or Definition Abbreviation PH Precipitation-hardenable PWR Pressurized water reactor QADP Quality assurance data package RCS Reactor coolant system RV Reactor vessel RVLMS Reactor vessel level monitoring probe SER Safety evaluation report SST Stainless steel SOCC Stress corrosion cracking SRP Standard review plan SSCs Systems, structures, and components SSHT Surveillance specimen holder tube TE Thermal aging embrittlement UCB Upper core barrel UNS Unified numbering system US United States UTS Upper thermal shield VS Void swelling

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe 1-1

1.0 INTRODUCTION

Management of aging effects in reactor vessel (RV) internals is required for nuclear plants applying for renewed operating licenses, as specified in the Nuclear Regulatory Commission (NRC) Standard Review Plan (SRP) for License Renewal Applications (LRAs) (1). The United States (US) nuclear industry has been actively engaged in supporting the industry goal of responding to these requirements. Various programs have been established within the industry over the past decade to develop guidelines for managing the aging effects of pressurized water reactor (PWR) RV internals. In 1997, the Babcock & Wilcox Owners Group (BWOG) issued BAW-2248, "Demonstration of the Management of Aging Effects for the Reactor Vessel Internals" (2).

In December 2008, the Electric Power Research Institute (EPRI) issued Revision 0 of Materials Reliability Program (MRP)-227 inspection and evaluation (I&E) guidelines for managing long-term aging of PWR RV internals and submitted the report to the NRC for review and approval in January 2009. In June 2011, the safety evaluation report (SER) for MRP-227, Revision 0 was issued by the NRC and was revised to Revision 1 in December 2011. This revised SER Revision I is included in the NRC approved MRP-227-A report (3). MRP-227-A provides generic augmented inspection requirements for the currently operating fleet of US PWRs.

AREVA' Inc., ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 1-2 Section 3.0 of the SER for MRP-227 documents the staff's evaluation and findings pertaining to the adequacy of the included aging management program (AMP) recommendations. In particular, Section 3.0 documents NRC staff concerns with MRP-227 and the basis for limitations and conditions being placed on the use of MRP-227 as well as licensee/applicant action items that are required to be addressed by applicants/licensees who choose to implement the NRC-approved version of MRP-227.

Entergy Operations, Inc. (hereafter Entergy) implemented MRP-227-A for Arkansas Nuclear One Unit 1 (ANO-1) in Reference (4). To meet-the NRC conditions upon the use of MRP-227, Entergy must perform the appropriate evaluation, analyses, and other required actions to fulfill the applicant/licensee action items specified in MRP-227-A. Of specific interest to this document, Section 4.2.2 of the MRP-227 SER defines Applicant/Licensee Action Item 2 as follows:

As discussed in Section 3. 2.5.2 of this SE, consistent with the requirementsaddressed in 10 CFR 54.4, each applicant/licenseeis responsible for identifying which RV Internals components are within the scope of LR for its facility. Applicants/licenseesshall review the information in Tables 4-1 and 4-2 in MRP-189, Revision 1, and Tables 4-4 and 4-5 in MRP-191 and identify whether these tables contain all of the RV Internals components that are within the scope of LR for their facilities in accordance with 10 CFR 54.4. If the tables do not identify all the RV Internals components that are within the scopne of LR for its facility, the applicantor licensee shall identify the missing component(s) and propose any necessary modifications to the program defined in MRP-227, as modified by this SE, when submitting its plant-specific AMP. The AMP shall provide assurance that the effects of aging on the missing component(s) will be managed for the period of extended operation. This issue is Applicant/Licensee Action Item 2.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 1-3 The purpose of this document is to perform a comparison between the ANO-1 RV internals license renewal scope and Tables 4-1 and 4-2 of MRP-1 89, Revision 1 (component items, welds, and materials) to satisfy Applicant/Licensee Action Item 2.

MRP-1 89, Revision 1 performs a categorization of the RV internals component items specific to the Babcock & Wilcox (B&WV) design (5). Note that MRP-1 91 is not considered because it is not applicable to the B&W design. Any ANO-1 RV internals component items/welds/materials not reported in the relevant MRP-1 89, Revision 1 tables will be identified and evaluated and any necessary modifications to the MRP-227-A program will be proposed.

Information considered by AREVA to be proprietary is bracketed using the following brackets: [ ]

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 2-1 2.0 METHODOLOGY The methodology used in this document to complete the comparison described in Section 1 .0 is as follows:

a. Define the scope for license renewal.

b. Identify the RV internals component items and welds and their materials within the scope of the license renewal and subject to an aging management review (AMR) for ANO-I.

c. List the relevant RV internals component~items and welds and their materials.

d. List component items and welds and their materials contained in Tables 4-1 and 4-2 of MRP-189, Revision 1.

e. Compare the tabulated component items and welds and their materials defined in Steps c and d and identify whether the MRP-1 89, Revision 1 tables contain all of the RV internals component items and welds and materials that are within the scope of license renewal and subject to an AMR for ANO-I.

f.Propose any necessary modifications to the program defined in MRP-227-A to manage the aging effects of the identified ANO-1 RV internals component items and welds and their materials that are not included in MRP-1 89, Revision 1. This will be completed through the same screening methodology used to develop MRP-227-A. As described in MRP-227-A, the following sequence steps will be used:

Identify RV internals components, materials, and environments

Identify degradation screening criteria

Characterize components and screen for degradation (A, non-A)

Failure Modes, Effects, and Criticality Analysis (FMECA) review

Severity categorization (A, B, C)

Engineering evaluation and assessment

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Pa~qe 2-2

g. Categorize for inspection (primary, expansion, existing, no additional measures) and aging management strategy

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe 3-1 3.0 COMPARISON 3.1 Scope Definition License renewal requirements for power reactors are defined in Title 10 of the Code of Federal Regulations, Part 54 (10 CFR 54) (6) and are based on the following key principles:

1. The regulatory process is adequate to ensure the safety of all currently operating plants, with the possible exception of the detrimental effects of aging.

2. The plant-specific licensing basis must be maintained during the renewal term in the same manner and to the same extentas during the original licensing term.

In implementing these two principles, 10 CFR 54.4 (7) defines systems, structures, and components (SSCs) included in the scope of license renewal as the following:

1. Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1)) to ensure the following functions i) The integrity of the reactor coolant pressure boundary; ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in

§50.34(a)(1), §50.67(b)(2), or §100.11 of this chapter, as applicable.

2. All nonsafety-related systems, structures, and components whose failure could prevent satisfactory accomplishment of any of the functions identified in paragraphs (1)(i), (ii), or (iii) of this section.

AREVA Inc. ANP-.341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq~ Report Paqe 3-2

3. All SSCs relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for fire protection, environmental qualification, pressurized thermal shock, anticipated transients without scram, and station blackout.

Following the determination of the SSCs that fall within the scope of 10 CFR 54.4, the applicant reviews these SSCs to determine which are subject to an AMR. Per 10 CFR 54.21 (8), an in-scope SSC is subject to an AMR if the component:

'1. performs an intended function without moving parts or without a change in configuration or properties, and

2. is not subject to replacement based on a qualified life or specified time period.

3.1,1 Identification of ANO-1 License Renewal Scope for RV Internals The demonstration of the effect of aging on the ANO-1 RV internals is performed in an internal Entergy site-specific report for ANO-I. The intended functions of the ANO-1 RV internals include the five RV internals intended functions listed in BAW-2248 (2) as well as three additional site-specific intended functions listed in the Entergy site-specific report. These intended functions are listed below:

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe 3-3

1. Provide support and orientation of the reactor core (i.e., the fuel assemblies). (from BAW-224 8)

2. Provide support, orientation, guidance, and protection of the control rod assemblies.

(from BAW-2248)

3. Provide a passageway for the distribution of the reactor coolant flow to the reactor core. (from BAW-2248)

4. Provide a passageway for support, guidance, and protection for the incore instrumentation. (from BAW-2248)

5. Provide a secondary core support for limiting the downward displacement of the core support structure in the event of a postulated failure of the core barrel. (from BAW-2248)

6. Support the reactor vessel level monitoring system (RVLMS) probe. (site-specific))

7. Provide gamma and neutron shielding. (site-specific))

8. Provide support for the surveillance specimen assemblies in the annulus between the thermal shield and the RV wall. (site-specific)

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq Report Paqe 3-4 The license renewal scope for ANO-1 RV internals relies heavily on BAW-2248. As defined in BAW-2248, the RV internals scope consists of two major structural sub-assemblies located within, but not integrally attached to (i.e., not welded to) the RV.

These major sub-assemblies are the plenum assembly and the core support assembly (CSA). For the purpose of defining materials, fasteners, construction, and assembly, the GSA can be further divided into three principle sub-assemblies: the core support shield (CSS) assembly, the core barrel assembly (CBA), and the lower internals assembly (LIA). The mechanical fasteners (bolting) joining these sub-assemblies and associated items are within the scope of this report. The welds within the scope of the RV internals report include the major structural welds that form or join the major sub-assembly cylinders and flanges and minor structural welds joining parts such as lifting lugs, support pipes, and tubes to the major sub-assemblies. There are no pressure-retaining or pressure boundary welds within the scope of this report.

Two items not contained in the BAW-2248 scope are part of the license renewal scope for ANO-1 RV internals. [

Several other site-specific clarifications are made to the BAW-2248 scope for ANO-I.

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensin~q Report Paqe 3-5 One of the ANO-1 control rod drive mechanism (CRDMs) was removed by a design change package (DCP) in order to install the RVLMS. Although the level probes themselves are instruments that are not in the scope of license renewal, the pressure boundary function of the RVLMS flange and the support assemblies in the reactor are in the scope of license renewal but not addressed within the license renewal documents for the ANO-1 RV internals. Only the portions of the RVLMS internal to the reactor are included in the internal Entergy site-specific report. [

BAW-2248 discusses both the original and modified vent valve locking device configurations. Based on available records, the original locking devices on some of the vent valve assemblies have been modified.

BAW-2248 discusses the thermal shield bolting replacements that were performed. Per an ANO-1 DCP, the [ I lower grid-to-thermal shield bolts and locking tabs were replaced. [

.]BAW-2248 also discusses the upper core barrel (UCB) bolting replacements that were performed. In accordance with an ANO-1 DCP,

[

Therefore, a review of the site-specific documentation verified that the scope and materials described in BAW-2248 accurately represent the ANO-1 RV internals with the exception of:

The RVLMS components internal to the reactor.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensin~q Report Paoqe 3-6

Portions of the ANO-1 surveillance specimen holder tube (SSHT) are still installed at ANO-1. Although the specimens have been removed and these components are not required to maintain their integrity for the specimens, these components must not become loose parts. Therefore, the remaining SSHT components have been added to the scope.

Confirmation that the internal Entergy site-specific report accurately reflects the current ANO-1 bolting configuration.

The thermal shield and thermal shield upper restraint assemblies support an intended function and are subject to an AMR.

3.1.2 Component Items and Welds Contained in MRP-1 89, Rev. 1 The RV internals component items and welds and their materials of construction contained in Tables 4-1 and 4-2 of MRP-189, Revision 1 are compared against the AN 0-1 RV internals component items and welds and their materials of construction within the scope of license renewal in Table 3-1 (component items) and Table 3-2 (welds) of this document. The RV internals component items and welds contained in the ANO-1 RV internals scope of license renewal but not contained in Tables 4-1 and 4-2 of MRP-1 89, Revision 1 are identified in bold font in both Table 3-1 (component items) and Table 3-2 (welds) of this document. Component items and welds contained in the MRP-1 89, Revision 1 tables that are additional beyond those ANO-1 RV internals component items within the scope of license renewal are not listed. These component items and welds are outside the scope of this document as well as the description of the applicable licensee/applicant action item (specific action item wording is given in Section 1.0). The following sections provide details for items of interest for the ANO-1 RV internals.

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Page 3-7 3.1.2.1 [ ]

3.1.2.2 RV Internals High-Strength Bolting

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal S cope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2)

LicensinQ Report Pa~qe 3-8 3.1.2,3 Surveillance Specimen Holder Tubes As noted in Section 3.1.1, portions of the SSHT assemblies were removed and the remaining portions of the SSHT assemblies are not in service at ANO-1. Although the specimens have been removed and these components are not required to maintain their integrity for the specimens, these components must not become loose parts.

Therefore, the portions of the SSHT assemblies remaining that are within the scope of license renewal for the ANO-1 RV internals are identified in the internal Entergy site-specific report.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Rep~ort Paqe 3-9 3.1.2.4 Reactor Vessel Level Monitoring Probe Supports As identified in Section 3.1 .1, the RVLMS probe supports (not the probe itself) are within the scope of license renewal. [

]

AREVA Inc. AN IP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensina Renort Pagqe 3-10

.......... 17 - .wp w. -

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Paqe 3-11 3.1.2.5 RV Internals Welds The RV internals welds and their materials of construction contained in Table 4-2 of MRP-1 89, Revision 1 are compared against the ANO-1 RV internals welds and their materials of construction within the scope of license renewal in Table 3-2 of this document.

] Therefore, the following justified assumptions were used to identify the specific ANO-1 welds and their materials for comparison:

For the vent valve locking devices, both original and modified designs will be evaluated in this document.

For those component items that are based on BAW-2248, the internal Entergy site-specific report was used to identify the component items and assemblies contained in the scope. Pertinent drawings, quality assurance data package (QADP), and other information was used to develop a listing of welds and their materials.

For the replacement UCB and lower thermal shield (LTS) bolt locking devices, pertinent drawings were used to develop listing of welds and their materials.

For the RVLMS, the appropriate internal AREVA drawings associated with the

] were located and the welds contained in these drawings were considered in the scope for ANO-I.

For the remaining portions of the SSHT assemblies still installed at ANO-1, the appropriate internal AREVA drawings were located and the welds contained in these drawings were considered in the scope for ANO-1.

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For the thermal shield and thermal shield upper restraint, the appropriate internal AREVA drawings were located and the welds contained in these drawings were considered in the scope for ANO-I.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqie 3-13 Table 3-1 Comparison of ANO-1 RV Internals License Renewal Scope to MRP-189 Revision 1 Component Items Item ANO-1 RV Internals Component Item T AComponent NO-I RV Internals Item MRP-190 Identifier1 MRP-I 89, Revision 1 Component Item (MRP-1 89, MRP-I189, Revision 1 Component Item I Material Revision I, Table 4-1 (5)) Material (MRP-I189, I Revision I,

____ ___

_ ______ ___

___ ___

_______I

____ ___ ___ ___ __ ____ ___ ___ ___ ___ ___ Table 3-2 (5))

Plenum Cover Assembly_____________

I Plenum Cover Weldment A 240-63 Type 304 P.1.1 Weldment Ribs A 240 Type 304 Ribs 2 Rib Pads A 2752-65 Type 304 P.1.2 Weldment Rib Pads A 276 Type 304 3 Plenum Cover Bottom Fla~nge A 240-63 Type 304 P.1.3 Bottom Flange A 240 Type 304 4 Plenum Cover Support A 240-63 Type 304 P.1.4 Support Flange A 240 Type 304 Flange 5 Plenum Cover Support Ring A 240-63 Type 304 P.1.5 Support Ring A 240 Type 304 6 Plenum Cover Plate A 240-63 Type 304 P.1.6 Cover Plate A 240 Type 304 7 Lifting Lugs A 240-63 Type 304 P.1.7 Lifting Lugs A 240 Type 304 8 Base Blocks A 240-63 Type 304 P.1.8 Base Blocks for Lifting Lugs A 240 Type 304 9 Lifting Lugs-to-Base Block A 193-65 Grade B8 P.1.9 Lifting Lugs-to-Base Block A 193 Grade B8 Bolts Bolts__________

10 Locking Cups A 167 Type 304 P.1.10 Locking Cups Al167 Type 304

Plenum Cylinder ______________

11 Cylinder A 240-63 Type 304 P.2.1 Cylinder A 240 Type 304 12 Top Flange A 473-63 Type 304 P.2.2 Top Flange A 473 Type 304 13 Bottom Flange A 473-63 Type 304 P.2.3 Bottom Flange A 473 Type 304 14 Reinforcing Plates A 240-63 Type 304 P.2.4 .,Reinforcing Plates A 240 Type 304 SMRP-190 contains the original FMECA, which was later incorporated into MRP-1 89. The identifier is included for easy reference.

2This is believed to be a typographical error, and intended to be A 276-65, supported by comparison to the material comparison in the appropriate QADP.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Page 3-14 Item ANO-1 RV Internals ANO-1 RV Internals MRP-190 MRP-1 89, Revision 1 MRP-1 89, Revision Component Item Component Item Identifier' Component Item (M~RP-1 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-1 89, Revision 1, Table 3-2 (5))

15 Round Bars A 276-65 Type 304 P.2.5 Round Bars A 276 Type 304 16 Top Flange-to-Cover Bolts A 193-65 Grade B8 P.2.6 Top Flange-to-Cover Bolts A 193 Grade B8 17 Locking Cups A 167 Type 304 P.2.7 Locking Cups A 167 Type 304 18 Bottom Flange-to-Upper Grid A 193-65 Grade B8 P.2.8 Bottom Flange-to-Upper Grid A 193 Grade B8 Screws Bolts 19 Locking Cups Al167 Type 304 P.2.9 Locking Cups Al167 Type 304

_________________________Upper Grid Assembly ________________________

20 Upper Grid Rib Section A 240-63 Type 304 P.3.1 Rib Section A 240 Type 304 21 Upper Grid Ring Forging A 473-65 Type 304 P.3.2 Ring Forging A 473 Type 304 22 Rib-to-Ring Screws A 193-65 Grade B8 P.3.3 Rib-to-Ring Cap Screws A 193 Grade B8 23 Lockpins AISI Type 304 P.3.4 Locking Pins AISI Type 304 24 Fuel Assembly Support Pads A 276-65 Type 304 P.3.5 Fuel Assembly Support Pads A 276 Type 304 25 Dowels AMS 5667F P.3.6 Dowels AMS 5667F UNS 07750 26 Cap Screw A 193-65 Grade B8 P.3.7 Cap Screw A 193 Grade B8 Control Rod Guide Tube (CRGT) Assembly _________

27 CRGT Pipe A 312-64 Type 304 P.4.1 Pipe A 312 Grade TP304 28 CRGT Flange A 240-63 Type 304 P.4.2 Flange A 240 Type 304 29 Flange-to-Upper Grid Screws A 193-65 Grade B8 P.4.3 Flange-to-Upper Grid Cap A 193 Grade B8 Screws 30 Dowel A 276-65 Type 304 P.4.4 Flange Dowels A 276 Type 304 31 CRGT Spacer Castings A 351-65 Grade CF3M P.4.5 Spacer Castings A 351-65 Grade CF3M 32 Spacer Castings Screws A 193-65 Grade B8 P.4.6 Spacer Casting Cap Screws A 193 Grade B8

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 3-15 Item ANO-1 RV Internals ANO-1 RV Internals MRP-190 MRP-1 89, Revision 1 MRP-1 89, Revision Component Item Component Item Identifier' Component Item (MRP-1 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-1 89, Revision 1,

_________________

________Table 3-2 (5))

33 Spacer Casting Washer AISI Type 304 P.4.7 Spacer Casting Washers AISI Type 304 34 CRGT Rod Guide Tubes SA-240-63 Type 304L P.4.8 Rod Guide Tubes SA-240 Type 304L 35 CRGT Rod Guide Sectors SA-240-63 Type 304L P.4.9 Rod Guide Sectors SA-240 Type 304L

_______________________Core Support Shield (CSS) Assembly _________

36 Core Support Shield Cylinder A 240-63 Type 304 S.1 Cylinder A 240 Type 304 37 Top Flange A 473-63 Type 304 s.2 Top Flange A 473 Type 304 38 Bottom Flange A 473-63 Type 304 S.3 Bottom Flange A 473 Type 304 39 Core Support Shield-to-Core A 453 (A 286) Grade 660, S.4c (ANO-1) UCB: Replacement A 453 Grade 660 Barrel Replacement Bolts Condition A A-286 CSS-to-Core Barrel Class A (114 replacement) Bolts 40 Locking Cups &Tie Plates A 240-74 or A 479-75 S.5b Locking Cups 3 A 240 Type 304L (replacement bolts) Type 304L 41 Outlet Nozzles A 473-63 Type 304 S.6a Outlet Nozzles A 473 Type 304 42 Vent Valve Nozzles A 473-63 Type 304 S.7 Vent Valve Nozzles A 473 Type 304 43 Vent Valve Guide Blocks A 276-65 Type 304 S.8 Vent Valve Nozzle Guide A 276 Type 304 Blocks 44 Vent Valve Body A-351 Grade CF8 S.9 Vent Valve Body A 351 Grade CF8 45 Retaining Rings AMS 5658 S.10 Vent Valve Top and Bottom AMS 5658 Type 15-5

___ _______________Retaining Rings PH 46 Jack Screws AMS 5737C S. 11 Vent Valve Jack Screws AMS 5737C Alloy A-

____ ___ ___

___________________286 ____ ___ ___

3This comPonent item is identified in bold font because the tie plate is not identified in MRP-1 89, Revision 1, Table 4-1 (5).

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Paqie 3-16 Item ANO-1 RV Internals ANO-1 RV Internals MRP-190 MRP-1 89, Revision 1 MRP-1 89, Revision Component Item Component Item Identifier1 Component Item (MRP-1 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-189, Revision 1, Table 3-2 (5))

47 Misc. Locking Device Parts A 240 Type 3044 N/A No similar component item No similar item in SA-479 Type 3044 in MRP-1 89, Revision 1, MRP-1 89, Revision SA-1 82 Type 3044 Table 4-1 1, Table 3-2 SA-193 Grade B8 or B8M 4 MIL-N-23228A Condition A or SB-i 684 M IL-N-23229A AM.2T1 Condition A or SB-i1664 AMS-56622 or SA-637 Grade 7184 A-240 Type 3045 A-276 Type 3Q4 5 A-276 Type 4315 A-286 5 _____________

48 Round Bars A 276-65 Type 304 S.15 Round Bars A 276 Type 304 49 Flow Deflectors A 240-63 Type 304 S. 16 Flow Deflectors A 240 Type 304 50 Lifting Lugs A 276-65 Type 304 S.17 Lifting Lugs A 276 Type 304 Core Barrel Assembly_(CBA)_____________ _________

51 Core Barrel Cylinders A 240-63 Type 304 B.1 Core Barrel Cylinder 1 A 240 Type 304 52 Top Flange A 473-63 Type 304 B.2 jTop Flange A 473 Type 304 53 Bottom Flange A 473-63 Type 304 B.3 Bottom Flange A 473 Type 30 c

hs(omponent item is part of the modified locking device for the vent valves.

5 This component item is part of the original locking device for the vent valves.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensina Report Pacle 3-17 Item ANO-1 RV Internals ANO-1 RV Internals MRP-190 MRP-1 89, Revision 1 MRP-1 89, Revision Component Item Component Item Identifier' Component Item (MRP-1 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-1 89, Revision 1, Table 3-2 (5))

54 Lower Internals Assembly-to- A 453 (A 286) Grade 660, B.4a LCB: Original A-286 Lower A 453 Grade 660 Core Barrel Bolts (all original) Condition A Grid Assembly-to-Core Barrel Class A Bolt 55 Locking Clips A 240-63 Type 304L B.5a Locking Clips A 240 Type 304L 56 Core Barrel-to-Thermal A 453 (A 286) Grade 660, B.6a UTS: A-286 Thermal Shield A 453 Grade 660 Shield Bolts (all original) Condition A Bolts Class A 57 Locking Clips A 240-63 Type 304L B.7 Locking Clips A 240 Type 304L 58 Baffle Plates A 240-63 Type 304 B.17 Baffle Plates A 240 Type 304 59 Formers A 240-63 Type 304 B.18 Former Plates A 240 Type 304 60 Barrel-to-Former Bolts A 193-65 Grade B8 B.19 Core Barrel-to-Former Plate A 193 Grade B8 Cap Screws 61 Locking Pins AISI Type 304 B.20 Locking Pins AISI Type 304 62 Dowels AMS 5667F B.21 Core Barrel-to-Former Plate AMS 5667F UNS Dowels N07750 63 Baffle-to-Former Bolts A 193-65 Grade B8 B.22 Baffle-to-Former Hex Head A 193 Grade B8 Bolts (except F4) 64 Locking Pins AISI Type 304 B.23 Locking Pins AISI Type 304 65 Baffle-to-Former Shoulder A 193-65 Grade B8 B.24 Baffle-to-Former Shoulder A 193 Grade B8 Screws Screws (F4) 66 Locking Dowel A 276-65 Type 304 B.25 Locking Dowels A 276 Type 304 67 Baffle-to-Baffle Bolts A 193-65 Grade B8 B.26 Baffle-to-Baffle 12 Pt Bolts A 193 Grade B8 66 Locking Rings AISI Type 304 B.27 Locking Rings AISI Type 304 Lower Grid Assembly _____________

67 T Lower Grid Rib Section A 240-63 Type 304 L.1.1 Lower Grid Rib Section A 240 Type 304 68 jFuel Assembly Support Pads A 276-65 Type 304 L.1.2 Lower Grid Fuel Assembly A 276 Type 304 I ____________________

__________________j ________Support Padsj

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paae 3-18 Item ANO-1 RV Internals ANO-1 RV Internals MRP-190 MRP-189, Revision 1 MRP-189, Revision Component Item Component Item Identifier' Component Item (MRP-I 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-I189, Revision 1,

________

_____________________ Table 3-2_(5))

69 Dowels AMS 5667F L.1.3 Dowels AMS 5667F UNS N07750 70 Cap Screw A 193-65 Grade B8 L.1,4 Cap Screws A 193 Grade 88 71 Rib-to-Shell Forging Screw A 193-65 Grade B8 L.1.5 Rib-to-Shell Forging Cap A 193 Grade B8 Screws 72 Locking Pin AISI Type 304 L.1.6 .Locking Pins AISI Type 304 73 Lower Grid Flow Distributor A 240-63 Type 304 L.1.7 Lower Grid Flow Distributor A 240 Type 304 Plate Plate 74 Orifice Plugs A 276-65 Type 304 L.1.8 Orifice Plugs A 276 Type 304 75 Lower Grid Forging A 473-65 Type 304 L.1 .9a Lower Grid Forging A 473 Type 304 76 Lower Grid Shell Forging A 473-65 Type 304 L.1 .10 Lower Grid Shell Forging A 473 Type 304 77 Lower Internals Assembly-to- A 453 (A286) Grade 660, L.1.11c LTS: Replacement A-286 A 453 Grade 660 Thermal Shield Bolts Condition A Lower Grid Assembly-to- Class A

___(replacement) Thermal Shield Bolts 78 Locking Cups &Tie Plates A 240-74 or A 479-75, L.1.12 Locking Cups &Ties Plates A 240 Type 304L (replacement bolts) Type,304 L A 479-75 Type 304L 79 Guide Blocks A 276-65 Type 304 L.1 .13 Guide Block A 276 Type 304 80 Guide Block Bolts A 193-65 Grade 88 L.1.14a Guide Block Bolts A 193 Grade B88 81 Guide Block Washers A 193-65 Grade 88 L.1.14b Guide Block Washers A 193 Grade B88 82 Dowel AMS 5667F L.l15.Dowels AMS 5667F UNS N07750 83 Shock Pads A 276-65 Type 304 L.1 .16a&b Shock Pads A 276 Type 304 84 Shock Pad Bolts A 193-65 Grade 88 L.1.17a Bolts A 193 Grade B88 85 Support Post Pipes A 312-64 Type 304 L.1.18 Support Post Pipes A 312 Grade TP304 86 Bolting Plugs A 276-65 Type 304 L.1.19 Bolting Plugs A 276 Type 304

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Paqe 3;19 Item ANO-1 RV Internals ANO-1 RV Internals MRP-190 MRP-1 89, Revision 1 MRP-1 89, Revision Component Item Component Item Identifier1 Component Item (MRP-1 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-189, Revision 1,

_________Table 3-2_(5))

87 Support Post Cap Screws A 193-65 Grade B8 L.1.20 Cap Screws A 193 Grade B8 88 Locking Pin AISI Type 304 L.1.21 Locking Pins AISI Type 304 Flow Distributor Assembly________________________

89 Flow Distributor Head A 240-63 Type 304 L.2.1 Flow Distributor Head A 240 Type 304 90 Flow Distributor Flange A 473-63 Type 304 L.2.2 Flow Distributor Flange A 473 Type 304 91 Shell Forging-to-Flow A 453-65 (A 286) Grade L.2.3a FD: A-286 Flow Distributor-to- A 453-65 Grade 660, Distributor Bolts 660 Lower Grid Shell Forging Class A Bolts 92 Locking Clip A 240-63 Type 304 L.2.4 Locking Clips A 240 Type 304 93 Incore Guide Support Plate A 240-63 Type 304 L.2.5 IMI Guide Support Plate A 240 Type 304 94 Clamping Ring A 240-63 Type 304 L.2.6 IMI Guide Support Plate A 240 Type 304

___________________Clamping Ring 95 Dowel A 276-65 Type 304 L.2.7 IMI Guide Support Plate A 276 Type 304 Dowel Incore Guide Tube Assembly__________

96 Incore Guide Tubes A 276-65 Type 304 L.3.1 IMI Guide Tubes A 276 Type 304 97 Gussets A 276-65 Type 304 L.3.2 IMI Guide Tube Gussets A 276 Type 304 98 Guide Tube Nuts A 276-65 Type 304 L.3.4 ]MI Guide Tube Nuts A 276 Type 304 99 Guide Tube Washers A 276-65 Type 304 L.3.3 IMI Guide Tube Washers A 276 Type 304 100 Locking Clips A 240-63 Type 304 L.3.5 Locking Clips A 240 Type 304 101 Spiders A 351-65 Grade CF8 L.3.6 IMI Guide Tube Spider A 351-65 Grade CF8

_______________________

____________________ _________Castings

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing~ Report Paqe 3-20 Item ANO-1 RV Internals T ANO-1 RV Internals MRP-190 MRP-1 89, Revision 1 MRP-1 89, Revision Component Item Component Item Identifier 1 Component Item (MRP-1 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-189,

- . I

____________________

__________________ ____ ____ ______________Table___

Revision 1, Tabl 23-2(5)

Reactor Vessel Level

itoring System (RVLMS)__________

102 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

___Table 4-1 1, Table 3-2 103 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

___Table 4-1 1, Table 3-2 104 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

___Table 4-1 1, Table 3-2 105 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

________________Table 4-1 1, Table 3-2 106 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision Table 4-1 1, Table 3-2 107 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

___Table 4-1 1, Table 3-2 108 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

__________________Table 4-1 1, Table 3-2 109 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

______________Table 4-1 1, Table 3-2 110 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

_________________ ______________ ______Table 4-1 1, Table 3-2

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Page 3-21 Item ANO-1 RV Internals ANO-1 RV Internals MRP-190 MRP-1 89, Revision 1 MRP-1 895 Revision Component Item Component Item Identifier 1 Component Item (MRP-1 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-189, Revision 1, Table 3-2 (5))

111 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision Table 4-1 1, Table 3-2 112 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision Table 4-1 1, Table 3-2 113 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

___Table 4-1 1, Table 3-2 114 N/A No similar component item No similar item in in MRP-1 89, Revision I, MRP-1 89, Revision

_________________ _____________________Table 4-1 1, Table 3-2

______________________Remaining Portions of the SSHT 15N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

_____________________________ ______Table 4-1 1, Table 3-2 6AS noted in Reference 9, initial inspections were performed with underwater video cameras with the RV internals in the vessel to assess damage prior to RV internals removal. The RV internals were then removed from the vessel for further inspection and repair, including complete removal of the SSHTs from the CSA prior to inspections and repairs. [

]

Hitrclinternal AREVA records indicate this material is [ JThe screening criteria in MRP-189, Revision I do not differentiate among these material differences.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Page 3-22 Item ANO-1 RV Internals ANO-1 RV Internals MRP-190 MRP-1 89, Revision 1 MRP-1 89, Revision Component Item Component Item Identifier 1 Component Item (MRP-1 89, 1 Component Item Material Revision 1, Table 4-1 (5)) Material (MRP-189, Revision 1, Table 3-2 (5))

116 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision Table 4-1 1, Table 3-2 117 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision Table 4-1 1, Table 3-2 118 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision

___Table 4-1 1, Table 3-2 119 N/A No similar component item No similar item in in MRP-189, Revision 1, MRP-189, Revision Table 4-1 1, Table 3-2 8

As described in Reference 9, the 'bracket', part 227 (part of the anti-rotation hinge), is believed to have been removed with the SSHTs and not be remaining at A.-.[ ]

9Historical internal AREVA records indicate this material is among these material differences.

[ IThe screening criteria in MRP-1 89, Revision 1 do not differentiate 10Hsoia internal AREVA records indicate this material is [ IThe screening criteria in MRP-1 89, Revision I do not differentiate among these material differences.

11Historical internal AREVA records ind~icate this material~is [ IThe screening criteria in MRP-1 89, Revision 1 do not differentiate among these material differences.

12 [

13Historical internal AREVA records indicate this material is[

among these material differences. IThe screening criteria in MRP-1 89, Revision 1 do not differentiate

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Page 3-23 Item ANO-1 RV Internals ANO-1 RV Internals Material MRP-190 IRevision MRP-1 89, Revision 1 I

1, Table 4-1 (5))

MRP-I 89, Revision Material (MRP-1 89, Revision 1,

____ ___ ___ ___ ___ ___ I _ ___ ___ ___ ___ ___ ___ Table 3-2 (5))

Thermal Shield and Thermal Shield Upper Restraint 120 Thermal Shield Upper A 240-63 Type 304 B.1 1 Thermal Shield Upper A 240 Type 304 Restraint Restraint "A" and "B"Blocks 121 Upper Restraint Shim A 240-63 Type 304 B.12 Thermal Shield Upper A 240 Type 304 Restraint Shims 122 Upper Restraint Dowel A 453-65 Grade 6601 B.15 Thermal Shield Upper A 453-65 Grade 660 Restraint Dowels (not Class A exposed) .

123 Upper Restraint Dowel A 276-65 Type 304 B.14 Thermal Shield Upper A 276 Type 304 Restraint Upper Plugs 124 Upper Restraint Locking A 240-63 Type 304 B.7 Locking Clips A 240 Type 304L Clipi 5 125 Thermal Shield Cylinder A 240-63 Type 304 B.10 Thermal Shield Cylinder A 240 Type 304 14Historical internal AREVA records indicate this material is differentiate among these material differences.

[ .] The screening criteria in MRP-1 89, Revision I do not 15Afe review of the description of this component item and the appropriate thermal shield upper restraint drawing, this locking clip is determined to be the locking clip for the upper thermal shield bolt, as identified as item 57 in Table 3-1. Therefore, this component item is not evaluated inthis table line item or any further inthis document.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision i Comparison (MRP-227-A Action Item 2)

Licensina Report Pa~qe 3-24 Table 3-2 Comparison of ANO-1 RV Internals License Renewal Scope to MRP-189 Revision 1 Welds Item ANO-1 RV Internals Weld AN-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision 1 WedMaterial (MRP-1 89, Revision I, Table Weld Material A Ied4-2 (5)) (MRP-1 89, Revision

____ ___

___ ______

___ ___

___ ___ ___ _ __ ___ ___ ___ ___ ___ 1, Table 4-2_(5))

Plenum Cover Assembly I WC-18 (support ring segment- Type 308L WC-18 (two plenum cover Type 308 to-support ring segment weld) support ring segments to form a complete plenum cover

_____support ring weld) 2 WC-19 (support ring-to-support Type 308L WC-19 (plenum cover support Type 308L flange weld) ring to plenum cover support

______flange)

A 3 WC-28 (rib-to-rib weld) Type 308 / Type 308L WC-28 (plenum cover Type 308L weldment ribs to each other weld) 4 WC-29 (rib-to-support ring and Type 308 / Type 308L WC-29 (plenum cover Type 308L rib-to-support flange weld, weldment ribs to support ring weldment-to-support flange and support flange weld) weld) ___________

5 WC-30 (bottom flange-to-rib Type 308 WC-30 (plenum cover bottom Type 308L weld) flange to plenum cover weldment ribs weld) 6 WC-31 (cover plate-to-rib weld) Type 308 WC-31 (plenum cover plate to Type 308L plenum cover weldment ribs weld) 7 WC-33 (bottom flange-to-dowel Inco 69 WC-33 (X-750 dowels to Alloy 82 weld) plenum cover bottom flange

_______ ______

______ _____ ______ ______ ______weld)_ _ _ _ _ _ _ _ _ _

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

I iro neinn JDnr~rf- p~~9L~

Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision 1 Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

______________

___________________ _________________ 1, Table 4-2_(5))

8 WC-75 (locking cup-to-base Type 308L WC-75 (locking cup (for Type 308L block) plenum cover lifting lug bolt) to lifting lug base block weld) 9 WC-84 (letter plate-to-rib weld) Type 308 WC-84 (orientation letter (W) Type 308/Type 308L to plenum cover weldment ribs weld) 10 WC-124 (support ring-to-support Type 308L WC-124 (plenum cover Type 308L flange weld) support ring to plenum cover support flange (WC-124 on the ID side, WC-19 on the OD side) weld) __________

11 WC-126 (support flange-to- Type 308 WC-126 (plenum cover Type 308L plenum cover weldment weld) support flange to the bottom of plenum cover weldment ribs weld) __________

12 WC-127 (plenum cover Type 308 I Type 308L WC-127 (plenum cover lifting Type 308 weldment-to-base block) lug base block between 2 plenum cover weldment ribs weld)__________

13 WC-128 (plenum cover Type 308 IType 308L WC-128 (plenum cover lifting Type 308 weldment-to-base block) lug base block between 2 plenum cover weldment ribs weld) __________

14 WC-129 (plenum cover Type 308 WC-129 (Plenum cover lifting Type 308 weldment-to-base block) lug base block between 2 plenum cover weldment ribs

____ ___ ___ ____ ____ ___weld) 15 WC-133 (pad-to-rib weld) Type 308L WC-133 (plenum cover rib Type 308L pads to plenum cover weldment rib weld) __________

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1. Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 3-26 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision 1 Weld Material (MRP-I189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

____

______ _ _____ ____ ___ ____ ___ ___ 1, Table 4-2_(5))

16 WC-142 (letter plate-to-cover Type 308L WC-142 (orientation letter Type 308L plate weld) plate (Letter W) to plenum

_____ ~~~~~cover rib weld) __________

17 WC-142 (cover plate-to-rib Type 308L WC-142 (plenum cover plate Type 308L weld) to the top of plenum cover weldment rib weld) 18 WC-142 (bottom flange-to-rib Type 308L No similar weld in MRP-189, No similar weld in weld) Revision 1, Table 4-2 MRP-189, Revision

____ _____________________1, Table 4-2 19 WC-253 (pipe plug-to-support Austenitic Stainless No similar weld in MRP-189, No similar weld in flange) Steel Weld 16 Revision 1, Table 4-2 MRP-1 89, Revision

____ __

___ ______ __________ ____ ___ __ ___ ____ ___ ___ __1, Table 4-2 Plenum Cylinder 20 WC-34 (plenum cylinder-to-top Type 308L (WC-34) plenum cylinder to Type 308L and bottom flanges) top and bottom plenum cylinder flanges circumferential seam weld 21 WC-35 (plenum cylinder-to- Type 308L No similar weld in MRP-189, No similar weld in reinforcing plate) Revision 1, Table 4-2 MRP-189, Revision

__________________ 1, Table 4-2 22 WC-36 (plenum cylinder-to- Type 308 / Type 308L No similar weld in MRP-1 89, No similar weld in reinforcing plate) Revision I, Table 4-2 MRP-I 89, Revision I, Table 4-2 23 WC-37 (plenum cylinder vertical Type 308L WC-37 (plenum cylinder Type 308L seam weld) vertical seam weld) __________

16 Both of the component items being joined are fabricated from austenitic stainless steel. Therefore it is reasonable to assume that the weld joining them is austenitic stainless steel.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report - Pagqe 3-27 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-I189, Revision I Weld Material (MRP-189, Revision I, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

____________________1, Table 4-2 (5))

24 WC-38 (plenum cylinder-to- Type 308 / Type 308L No similar weld in MRP-1 89, No similar weld in round bar weld) Revision 1, Table 4-2 MRP-I189, Revision 1, Table 4-2 25 WC-39 (plenum cylinder-to- Type 308 / Type 308L No similar weld in MRP-1 89, No similar weld in reinforcing plate) Revision 1, Table 4-2 MRP-1 89, Revision

____

___ _____ _ ___

___ ___

___ ______ ___ ___1,, Table 4-2 26 WC-66 (locking cup-to-plenum Type 308L WC-66 (locking cup (for bolts Type 308L cylinder weld) joining plenum cylinder top flange to plenum cover bottom flange) to plenum

______________________ _________________cylinder top flange) 27 WC-66 (locking cup-to-plenum Type 308L WC-66 (locking cup (for bolts Type 308L cylinder weld) -joining plenum cylinder bottom flange to upper grid ring forging) to plenum

________________________ ___________________ cylinder bottom flange) __________

_________________________Upper Grid Assembly __________

28* WC-22 (dowel locking weld) Inco 69 WC-22 (X-750 dowel to upper Alloy 82 grid fuel pad weld (Except

____ ____ ___

___DB)) ____ ___

29 WC-23 (cap screw locking weld) Type 308L WC-23 (cap screw to upper Type 308L

________________________ ___________________grid fuel pad weld) __________

30 WC-95 (upper grid rib section- Type 308L WC-95 (locking pin (for cap Type 308L to-locking pin weld) screw to joining upper grid rib section to upper grid ring forging) to upper grid rib section weld) 31 WC-96 (dowel locking weld) lnco 69 WC-96 (X-750 dowel (for Alloy 82 alignment) to upper grid rib section weld) __________

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensina Re~ort Paae 3-28 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision I Weld Material (MRP-1 89, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

_______

___ _____ ______ ___ ____ ___ ___ ___ ___ ___ ___ ___ ___ 1, Table 4-2_(5))

32 WC-173 (support pad-to-upper Type 308L WC-173 (fuel grid pad to Type 308L grid weld) ____________ upper grid rib section weld) __________

CRGT Assembly ________

33 WC-40 (CRGT assembly-to- Type 308L WC-40 (washer to CRGT pipe Type 308L

-washer assembly) and spacer bolt weld (WC-64 for top spacer))

34 WC-40 (socket head cap screw- Type 308L WC-40 (washer to CRGT pipe Type 308L to-washer assembly) and spacer bolt weld (WC-64 for top spacer))

35 WC-41 (pipe-to-flange weld) Type 308 WC-41 (CRGT flange to Type 308L CRGT pipe weld (all around except at the 4 scallops)) __________

36 WC-42 (flange-to-dowel weld) Type 308L WC-42 (Type 304 dowel to Type 308L CRGT flange weld) 37 WC-64 (washer assembly-to- Type 308L WC-64 (washer to CRGT pipe Type 308L CRGT assembly) and spacer bolt weld (also

_____see WC-40))

38 WC-65 (CRGT assembly-to- Type 308L WC-65 (CRGT pipe to Type 308L

____ plenum cover assembly) plenum cover plate weld) 39 WC-67 (CRGT assembly-to-cap Type 308L WC-67 (CRGT flange cap Type 308L screw weld) screw (joining upper grid rib section) to CRGT flange

_____

_____ _____ _____ _____ ____weld) _ _ _ _ _ _ _ _ _ _

Core Support Shield Assembly Type 308 / Type 308L WC-43 (core support shield Type 308L cylinder to top and bottom flange circumferential seam weld)

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuciear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensin~q Report Paaqe 3-29 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision 1 Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

_______ ___ ___ _____ ______ ____ ___ ___ ___ ___ ___ ___ ___ ___ 1, Table 4-2 (5))

41 WC-44 (cylinder-to-vent nozzle) Type 308 WC-44 (core support shield Type 308 cylinder to vent nozzle weld) __________

42 WC-45 (cylinder-to-vent nozzle) Type 308 WC-45 (core support shield Type 308 cylinder to vent nozzle weld (opposite WC-44)) __________

43 WC-46 (cylinder-to-outlet Type 308 WC-46 (core support shield Type 308 nozzle) cylinder to outlet nozzle weld) 44 WC-47 (cylinder-to-outlet Type 308 WC-47 (core support shield Type 308 nozzle) cylinder to outlet nozzle fillet

_____weld (opposite WC-46))

45 WC-48 (flow deflector segments Type 308 WC-48 (flow deflector (U- Type 308 weld) baffle) segments weld) 46 WC-49 (top flange-to-lifting lug Type 308 WC-49 (core support shield Type 308 weld) lifting lug to top flange weld) 47 WC-50 (top flange-to-lifting lug Type 308 WC-50 (core support shield Type 308 weld) lifting lug to top flange weld (opposite WC-49))

48 WC-51 (cylinder vertical seam Type 308 / Type 308L WC-51 (core support shield Type 308L weld) cylinder vertical seam weld) 49 WC-52 (cylinder-to-round bar Type 308 I Type 308L WC-52 (round (LOCA) bars to Type 308 weld) core support shield cylinder ID surface weld) 50 WC-53 (cylinder-to-flow. defector Type 308 WC-53 (flow deflector (U- Type 308L segments weld) baffle) to core support

____ ______________________cylinder weld) 51 WC-1 05 (guide block-to-vent Type 308L " WC-1 05 (guide block to core Type 308L nozzle weld) support shield vent nozzle fillet weld) __________

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensina Renort Paae 3-30 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision I Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

____ ______ ___ ___ ____ ____ ___ ______ __1, Table 4-2_(5))

52 (replacement) upper core barrel Type 308L No similar weld in MRP-189, No similar weld in bolt locking cup-to-tie plate weld Revision 1, Table 4-2 MRP-I189, Revision

____ I, Table 4-2 53 (modified vent valve locking SFA 5.11 E-NiCrF-3 or No similar weld in MRP-189, No similar weld in device) bolt locking cup weld SEA 5.14 ER-Ni-Cr-3 Revision 1, Table 4-2 MRP-1 89, Revision

___________ ______ ___ ____ , Table 4-2 54 (modified vent valve locking SEA 5.4 E308 or E308L No similar weld in MRP-1 89, No similar weld in device) plug over pin weld or Revision 1, Table 4-2 MRP-1 89, Revision SFA 5.9 ER308 or 1, Table 4-2 ER308L 55 (modified vent valve locking SEA 5.11 E-NiCrF-3 or No similar weld in MRP-1 89, No similar weld in device) jackscrew locking cup SEA 5.14 ER-Ni-Cr-3 Revision 1, Table 4-2 MRP-1 89, Revision weld 1, Table 4-2 56 (original vent valve locking Type 316 No similar weld in MRP-I189, No similar weld in device) socket head cap screw Revision 1, Table 4-2 MRP-189, Revision locking weld _______________________ 1, Table 4-2 Core Barrel Assembly __________

57 WC-1 1 (cylinder-to-top and Type 308 I Type 308L WC-1 1 (top and bottom core Type 308L bottom flange) barrel cylinders to top and bottom core barrel flanges

_____circumferential seam weld) 58 WC-15 (bolt locking wire weld) Type 308L WC-15 (core barrel-to-former Type 308L plate cap screw locking pin to core barrel cylinder weld.)

59 WC-15 (cap screw locking wire Type 308L WC-15 (baffle-to-former bolt Type 308L weld) locking pin to baffle plate

_____ ~~~~~weld) __________

60 WC-16 (locking ring lock weld) Type 308L WC-16 (baffle-to-baffle bolt Type 308L locking ring to baffle plate

___________

_____ __

______

___ _____ ______ _____weld) _ _ _ _ _ _ _ _ _ _

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensina Reoort Paoe 3-31 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision I Weld MRP-1 89, Revision I Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

____________________1, Table 4-2 (5))

61 WC-20 (cylinder vertical seam Type 308L WC-20 (core barrel top and Type 308L weld) bottom cylinder vertical seam weld) 62 WC-21 (cylinder circumferential Type 308 / Type 308L WC-21 (core barrel top Type 308L weld) cylinder to core barrel bottom cylinder circumferential seam weld) 63 WC-94 (dowel-to-shoulder Type 308L WC-94 (plug weld locking Type 308L screw weld) dowel flush with special flat head baffle-to-former shoulder screw) ___________

64 WC-1 30 (dowel locking weld) Inco 69 WC-1 30 (X-750 dowel to top Alloy 82 and bottom core barrel cylinders fillet weld) 65 WC-141 ((original) lower core Type 308L WC-141 (locking clip (for Type 308L barrel bolt locking clip-to-lower original LCB bolt) to lower grid shell forging) _____________ grid shell forging weld) ___________

Lower Grid Assembly__________

66 WC-3 (dowel locking weld) Inco 69 WC-3 (X-750 dowel to lower -Alloy 69 fuel assembly pad weld) 67 WC-4 (dowel locking weld) Inc:o 69 WC-4 (X-750 dowel to lower Alloy 82 grid shell forging weld) ___________

68 WC-5 (lower grid forging-to- Type 308. WC-5 (support post to lower Type 308 / Type 308L support post weld) grid forging weld)_________

69 WC-8 (lower grid shell forging- Type 308 WC-8 (lower grid forging (or Type 308 I Type 308L to-lower grid forging) weldment) to lower grid shell

__________________________

____________________forging weld)___________

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Page 3-32 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision I Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

____

___

___ _____

__ ___ ____ ___ ____ __ 1, Table 4-2_(5))

70 WC-26 (lower grid shell forging- Type 308 WC-26 (flow distributor plate Type 308 / Type 308L to-flow distributor plate) to lower grid shell forging

_____ _____

__________weld)_

__________ _ _ _ _ _ _ _ _ _

71 WC-27 (flow distributor plate-to- Type 308L WC-27 (support post to flow Type 308L support post weld) distributor plate weld) __________

72 WC-59 (cap screw locking weld) Type 308L WC-59 (cap screw to lower Type 308L

__________________ fuel assembly pad weld) 73 WC-97 (support post pipe-to- Type 308 WC-97 (bolting plug to Type 308 I Type 308L

____bolting plug) _____________ support post weld) 74 WC-98 (dowel locking weld) Inco 69 WC-98 (X-750 dowel to lower Alloy 69

____ __________________ grid rib section weld) 75 WC-99 (locking wire for cap Type 308L WC-99 (locking pin (for lower Type 308L screw) grid rib section cap screw) to

_____lower grid rib section weld) 76 WC-1 00 (locking wire for cap Type 308L WC-1 00 (locking pin (for Type 308L screw) lower grid support post cap screw) to lower grid rib section weld) 77 WC-1 01 (bolt-to-shock pad Type .308L WC-1 01 (shock pad bolt to Type 308L weld) shock pad fillet weld) 78 WC-1 02 (bolt-to-washer weld) Austenitic Stainless WC-1 02 (guide block bolt to Type 308L

___Steel Weld16 washer fillet weld) 79 WC-103 (washer-to-guide block Austenitic Stainless WCF-103 (guide block bolt Type 308L weld) Steel Weld 16 washer to guide block-A and

________________________ __________________guide block-B weld) __________

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincj Report Pane 3-33 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision 1 Weld Material (MRP-1 89, Revision I, Table Weld Material 4-2 (5)) (MRP-I189, Revision

____

____ ___

_ _ ____

____ ___ ____ __1, Table 4-2 (5))

80 WC-104 (dowel-to-guide block Nickel-based Alloy WCF-104 (X-750 dowel to Alloy 82 weld) Weld 17 guide block-A and guide

_____block-B weld) 81 WC-142 (lower grid forging-to- Type 308 WC-142 (lower grid forging Type 308L lower grid shell forging weld) (or weldment) to lower grid

______shell forging weld) 82 WC-142 (support post-to-flow Type 308L WC-142 (support post to flow Type 308L distributor plate weld) ___________ distributor plate weld) 83 WC-142 (lower grid shell Austenitic Stainless WC-142 (flow distributor plate Type 308L forging-to-flow distributor plate) Steel Weld 16 to lower grid shell forging

____ __________________weld) 84 WC-173 (support pad-to-lower Type 308L WC-173 (fuel grid pad to Type 308L

___ grid rib section weld) lower grid rib section weld) 85 WC-240 (orifice plugs-to-flow Type 308L WC-240 (orifice plugs to flow Type 308L distributor plate weld) distributor plate weld) 86 (replacement) lower thermal Type 308 No similar weld in MRP-1 89, No similar weld in shield bolt locking cup-to-tie Revision 1, Table 4-2 MRP-189, Revision plate weld ________________________ 1, Table 4-2 Flow Distributor Assembly __________

87 WC-57 (flow distributor flange- Type 308L WC-57 (flow distributor flange Type 308L to-flow distributor head weld) to flow distributor head

______ ~~~~~circumferential seam weld) ___________

88 WC-58 (dowel-to-flow distributor Inco 69 WC-58 (X-750 dowel to flow Alloy 82 flange weld) ____________ distributor flange weld) __________

17 One component item being joined is fabricated from austenitic stainless steel while the other component item is fabricated from Alloy X-750. Therefore it is reasonable to assume that the weld joining them is nickel-based alloy.

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

I ii-_An~inn, l~nnrt PAn*_ .o,-.°,4 Item ANO-1 RV internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision I Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

_________________ ,_Table 4-2_(5))

89 WC-60 ((original) flow distributor Type 308L WC-60 (flow distributor (FD) Type 308L bolt locking clip-to-flow bolt locking clip to flow distributor flange) distributor flange weld) __________

90 WC-157 (clamping ring vertical Austenitic Stainless WC-157 (IMI guide support Type 308 seam weld) Steel Weld 16 plate clamping ring vertical seam weld)__________

91 WC-161 (dowel locking weld) Austenitic Stainless WC-161 (dowel (for clamping Type 308L Steel Weld1 6 ring) to flow distributor flange

_____

__________

_____ _____ _____ _____ ____weld) _ _ _ _ _ _ _ _ _ _

Incore Guide Tube Assembly __________

92 WC-158 (incore instrument Type 308L WC-158 (incore instrument Type 308L guide tubes-to-flow distributor guide tubes (center) to flow head weld) ____________ distributor head weld) 93 WC-158 (incore instrument Type 308L WC-158 (incore instrument Type 308L guide tubes-to-flow distributor guide tubes (peripheral) to

___head weld) flow distributor head weld) 94 Wc-159 (incore instrument Type 308L WC-159 (incore instrument Type 308L guide tube-to-flow distributor guide tubes (center) to flow head and gusset) distributor head and gusset

____ ___ ___ ____ ____ ___weld) 95 WC-160 (spider-to-lower grid rib Type 308L WC-160 (spider to lower grid Type 308L section weld) ____________rib section weld) 96 WC-187 (locking clip-to-incore Type 308L WC-187 (nut locking clip to Type 308L instrument guide tube nut weld) incore instrument guide tube nut weld) 97 WC-188 (locking clip-to-incore Type 308L wc-188 (nut locking clip to Type 308L instumen tbe wld)incore gude instrument guide tube instrumenguidetbeweld)weld)__________

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paoqe 3-35 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-I189, Revision I Weld Material (MRP-189, Revision I, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

___________ _______ ___ ___ ___ ____ ___ ___ ____ ___ ___ ____ ___ __ 1,_Table 4-2 (5))

Reactor Vessel Level Monitoring System (RVLMS)__________

98 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

__._ 1, Table 4-2 99 No similar weld in MRP-1 89, No similar weld in Revision 1, Table 4-2 MRP-189, Revision

____ 1, Table 4-2 100 No similar weld in MRP-1 89, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

____ ___ ___ __ ____ ___ ____ _ ___ ____ ___ ____ __1, Table 4-2 101 No similar weld in MRP-1 89, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

_______________________1, Table 4-2 102 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

_______________________1, Table 4-2 103 No similar weld in MRP-1 89, No similar weld in Revision 1, Table 4-2 MRP-I89, Revision

____ _____________________1, Table 4-2 104 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-I189, Revision

____

___ ______ __ ___ ___ ____ ___ ____ ___ ___ ___ ___1, Table 4-2 105 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-189, Revision

____ ______________________1, Table 4-2 106 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-I189, Revision

____

______ _ ____ ________ ______ ___ ____ _ _ ___ ___ ____ ___ ___ __1,_Table 4-2

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Pacie 3-36 item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-189, Revision I Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

__________ _ ____ ___

_______ ___ ____ ___ _ _ ___ ____ ___ ___ ___ __ 1,_Table 4-2 (5))

107 No similar weld in MRP-1 89, No similar weld in Revision 1, Table 4-2 MRP-189, Revision

_______ ___ ____ ___ __ ____ ___ ____

___ ___ ___1, Table 4-2 108 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

____1, Table 4-2 109 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

_______________________ 1, Table 4-2 110 No similar weld in MRP-1 89, No similar weld in Revision 1, Table 4-2 MRP-189, Revision I. Table 4-2 Remaining Portions o._f the SSHT_________

111 No similar weld in MRP-1 89, No similar weld in Revision 1, Table 4-2 MRP-189, Revision

_______ ____ ___ ___ _ __ ___ ___ ____ ___ ___1, Table 4-2 112 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

____ ______________________1, Table 4-2 113 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

___________________1, Table 4-2 114 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-189, Revision

____ _______________1, Table 4-2 115 No similar weld in MRP-189, No similar weld in Revision I, Table 4-2 MRP-I 89, Revision

_______ ___ ___ ___ ______ ___ ___ ___ _ __ ___ ___ ___ ___ ___1, Table 4-2

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

I ifnfn~inn~ P~nrfr P~Ar -.*

Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision 1 Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

__________ _ _____ ____ ___ ____ ___ ___ 1, Table 4-2 (5))

116 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

____ 1, Table 4-2 117 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-189, Revision

____

___

______

___ __

_____ ___

___ ___ ___ ____ __ ___ ___ ____ ___ ___ ___ 1, Table 4-2 118 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-189, Revision

_______

___ ___

_______

___

___ ___ ___ ____ ___ ___ ____ ___ ___ ___ 1, Table 4-2 Thermal Shield and Thermal Shield Upper Restraint __________

119 WC-12 (cylinder vertical seam Austenitic Stainless WC-12 (top and bottom Type 308L weld) Steel Weld 16 thermal shield cylinder

_____vertical seam weld) 120 WC-13 (upper-to-lower cylinder Type 308 / Type 308L WC-13 (top thermal shield Type 308L

-. weld) cylinder) 121 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

____ 1, Table 4-2 122 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

__________________ 1, Table 4-2 123 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

____ 1, Table 4-2 124 -"WC-176 ((original) upper Type 308L WCF-176 (locking clip (for Type 308L thermal shield bolt locking clip- original UTS bolts) to thermal to-upper restraint) shield upper restraint "A"

_______ ______

_____ ______

______ ______ ______weld)_ _ _ _ _ _ _ _ _ _

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A ActiOn Item 2)

LicensinQl Report *.Pane 3-38 Item ANO-1 RV Internals Weld ANO-1 RV Internals MRP-1 89, Revision 1 Weld MRP-1 89, Revision 1 Weld Material (MRP-189, Revision 1, Table Weld Material 4-2 (5)) (MRP-1 89, Revision

____ ___ ___ ___ ____ ___ ___ ___ ___ ____ ___ ___ 1, Table 4-2_(5))

125 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-1 89, Revision

_______________________1, Table 4-2 126 No similar weld in MRP-189, No similar weld in Revision 1, Table 4-2 MRP-189, Revision 1, Table 4-2 127 WC-220 (plug-to-thermal shield Type 308L WCF-220 (plug to thermal Type 308L restrint eld)shield upper restraint "A"

______ _____

_____ __ _________ _____ ______ _____weld) _ _ _ _ _ _ _ _ _ _

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Paqe 3-39 3.2 Component Item and Weld Comparison As illustrated in Table 3-1 and Table 3-2, the component items and welds that are included in the scope of license renewal for the RV internals for ANO-1 but are not included in MRP-189, Revision I are listed in Table 3-3. The comparison of materials is performed in Section 3.3. The differences for the component items and welds listed in Table 3-3 fall within one of eight categories, which are addressed below. The subsections below give a brief background about each component item or weld that is not included in MRP-1 89, Revision 1.

1. Plenum cover welds (Table 3-2 item numbers 18 and 19)

2. Plenum cylinder and reinforcing plate and round bar welds (Table 3-2 item numbers 21, 22, 24, and 25)

3. Tie plate and weld for replacement upper core barrel (UCB) bolting (Table 3-1 item number 40, Table 3-2 item number 52)

4. Miscellaneous locking device parts and associated welds for the vent valves (Table 3-1 item number 47, Table 3-2 item numbers 53-56)

5. Tie plate weld for replacement lower thermal shield (LTS) bolting (Table 3-2 item number 86)

6. Reactor Vessel Level Monitoring System (RVLMS) probe supports (including welds) within the RV internals (Table 3-1 item numbers 102-114, Table 3-2 item numbers98-110)

7. Remaining Surveillance Specimen Holder Tube (SSHT) assemblies (including welds) (Table 3-1 item numbers 115-119, Table 3-2 item numbers 111-118)

8. Thermal shield welds (Table 3-2 item numbers 121-123, 125-126)

AREVA Inc. AN IP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

I ic.*.n.inn R*.nort Table :3-3 Component Items and Welds within ANO-1 RV Internals License Renewal Scope but Not Contained in MRP-1 89, Revision 1 Document Table [Table

[Number I Item lComponent

_ _ _ _

Item _or Weld_ Name _ _

Plenum Cover Assembly Table 3-2 [ 18 _ _ __ __ _

Table 3-2 [ 19 Plenum Cylinder Assembly Table 3-221 1t Table 3-2 22_________________________

Table 3-2 2 Table 3-2 2 Core Support Shield Assembly Table 3-1 40 Table 3-1 47 Table 3-2 52 Table 3-2 53 Table 3-2 54 Table 3-2 55 Table 3-2 56 Table 3-2 86 Reactor Vessel Level Monitoring System (RVLMS)

Table 3-1 102 Table -1 10 Table 3-1 104 Table 3-1 105 Table 3-1 106 Table 3-1 107 Table 3-1 108 Table 3-1 109 Table 3-1 1109 Table 3-1 111 Table 3-1 112 Table 3-1 113 Table 3-1 114

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensin q Report Panqe 3-41 Document Table Table Item Component Item or Weld Name Number Table 3-2 98 Table 3-2 99 Table 3-2 100 Table 3-2 101 Table 3-2 102 Table 3-2 103 Table 3-2 104 ______________________

Table 3-2 105 Table 3-2 106 Table 3-2 107 Table 3-2 108 Table 3-2 .109 Table 3-2 110 Remaining Portions of the SSHT Table 3-1 115 Table 3-1 116 _______________________

Table 3-1 117 Table 3-1 118 Table 3-1 119 ________________ ______

Table 3-2 111 Table 3-2 112 Table 3-2 113 Table 3-2 114 Table 3-2 115 Table 3-2 116 Table 3-2 117 Table 3-2 118 Thermal Shield and Thermal Shield Upper Restraint Table 3-2 121 Table 3-2 122 Table 3-2 123 Table 3-2 125 Table 3-2 126

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe 3-42 3.2.1 Plenum Cover Welds

[

3.2.2 Plenum Cylinder and Reinforcing Plate and Round Bar Welds Two reinforcing plates are welded to the lower inner surface of the plenum cylinder opposite the CSS outlet nozzles. Both the reinforcing plates and the plenum cylinder have small holes to permit some of the reactor coolant coming up into the plenum to flow directly to the outlet nozzles. Additionally, in order to ensure that the space between the plenum cylinder and the CSS does not collapse and prevent flow through the outlet nozzles, a set Of round bars or lugs are welded to the outer surface of the plenum cylinder at each of the outlet nozzle areas. These lugs fit against similar lugs welded to the inner surface of the CSS.

3.2.3 Tie Plate and Weld for Replacement UCB Bolting The tie plates for the replacement UCB bolting include a [

J The tie plates for both designs are fabricated from (S)A 240 Grade 304L or (S)A 479 Grade 304L [

] Refer to Figure 3-1 for an illustration of the replacement UCB bolts with the 2-hole and 3-hole tie plates and locking cups at ANO-I.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 3-43 Figure 3-1 Replacement UCB Bolts with 2-Hole and 3-Hole Tie Plates and Locking Cups at ANO-1 3.2.4 Miscellaneous Locking Device Parts and Welds for the Vent Valves ANO-1 has eight 14-inch vent valves mounted on a vent valve mounting ring/nozzle that is welded into the CSS cylinder as shown in' Figure 3-2. To accommodate the vent valves, the inner surfaces of the rings have lips and flanges. Each vent valve consists of a hinged disc, a valve body with sealing surfaces, a split-retaining ring and fasteners (that retain and seal the perimeter of the valve assembly), and an alignment device (to maintain the correct orientation), as illustrated in Figure 3-3, Figure 3-4, and Figure 3-5.

Refer to Figure 3-6 and Figure 3-7 for a schematic of select original and modified locking device component items that secure, the split-retaining ring into the vent valve nozzle.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 3-44 Vent valve component parts, including the disc, are designed to minimize the possibility of loss of parts to the RCS, and all operating fasteners include a positive locking device.

The hinged-disc includes a device for remote testing and verification of proper disc function. The external side of the disc is contoured to absorb the impact load of the disc on the RV inside wall without transmitting excessive impact loads to the hinge parts as a result of a loss-of-coolant accident (LOCA). The hinge assembly consists of a shaft, two valve body journal receptacles, two valve disc journal receptacles, and four flanged shaft journals (bushings). The valve disc journal contains integral exercise lugs for remote operation of the disc with the valve installed in the CSS.

The function of the swing check valves is to relieve pressure in the interior of the CSA during a large break LOCA, equalizing pressure in the upper plenum area preventing the reversal of coolant flow through the core. For all normal operating conditions, the vent valve is closed, preventing bypass flow. In the event of a rupture of the RV inlet pipe, the valve will open to vent steam generated in the core directly to the break, thus permitting the core to be flooded and adequately cooled after emergency core coolant has been supplied to the RV. [

Past operational issues have been identified related to the vent valve jackscrew bushing and locking devices in the B&W-designed units. These issues resulted in modifications to and redesigns of the locking devices on several of the units. The crimped locking cups that are part of the modified locking device have also been found to be torn. Since records indicate that some locking devices have been modified, both locking devices designs (original and modified) are evaluated herein.

AI* IP-341 8NP In.y, Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, AREVA...*

Revision 1 Comparison (MRP-227-A Action Item 2) l ici*n~inn R~nnrt Pacie II 3-45 Figure 3-2 Core Support Shield Assembly LfigLug G-uide ylinde Outlet SRound Bar Nozzle Nozzle

~CSS Bottom l Flange

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensin~q Report Pa~qe 3-46 Figure 3-3 Vent Valve Assembly RiHinge Section Z-Z

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq Report Paqe 3-47 Figure 3-4 Typical Core Support Shield Vent Valve - Outside (RV Side) View

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Paqie 3-48 Figure 3-5 Typical Core Support Shield Vent Valve - Inside (Core Side) View

AREVA Inc. ANP-341 8NP

-* Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Pacqe 3-49 Figure 3-6 Schematic of Select Original Vent Valve Locking Device Component Items - Cross-Section View-

AREVA Inc. AINIP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensina Report Paae 3-50 Figure 3-7 Schematic of Select Modified Vent Valve Locking Device Component Items 3.2.5 Tie Plate Weld for Replacement LTS Bolting

] Refer to Figure 3-8 for an illustration of the replacement LTS bolts with the tie plates (and locking cups) at ANO-I.

AREVA inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe 3-51 Figure 3-8 LTS Bolts (Replacement) and LCB Bolts (Original) at ANO-1 (LCB Bolt Locking Clip Not Shown) 3.2.6 RVLMS Probe Supports and Welds within the RV Internals To satisfy the NRC's requirements for monitoring for inadequate core cooling, Entergy installed the RVLMS at ANO-1.. The installation of this device requires replacement of the center CRDM with hardware designed to support and guide the probes. The assemblies that contain the component items and welds within the scope of license renewal are the [

3.2.7 Remaining Surveillance Specimen Holder Tube (SSHT) Assemblies As noted in Section 3.1.2.3, portions of the SSHT assemblies were removed and the remaining portions of the SSHT assemblies are not in service at ANO-1.

The following information is repeated from Table 3-1 footnotes 6, 8, and 12 for information.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 3-52 As noted in Reference 9, initial inspections were performed with underwater video cameras with the RV internals in the vessel to assess damage prior to RV internals removal. The RV internals were then removed from the vessel for further inspection and repair, including complete removal of the SSHTs from the CSA prior to inspections and repairs [

As described in Reference 9, the 'bracket', part 227 (part of the anti-rotation hinge), is believed to have been removed with the SSHTs and be not remaining at ANO-I. [

]

[

]

3.2.8 Thermal Shield Welds

]

AREVA Inc. A *IP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

I ir~nsinr R*.nnrf Paae 3-53 3.3 Material Comparison As illustrated in Table 3-1 and Table 3-2, the component items and welds that are included in the scope of license renewal for the RV internals for ANO-1 and are included in MRP-1 89, Revision 1 but the material designations are different, are listed in Table 3-

4. Note that components items and welds included in the scope of license renewal for the RV internals for ANO-1 but not included in MRP-l189, Revision 1 are discussed in Section 3.2 and will be assessed in Section 3.4.

Table 3-4 ComponentlItems and Welds within ANO-1 RV Internals License Renewal Scope and Contained in MRP-1 89, Revision 1 but With Different Material Designations Document Table Component Item or Weld Name ANO-1 Scope MRP-1 89, Table Item Material Revision 1 Number Material Table 3-1 25 Dowels AMS 5667F AMS 5667F UNS 07750 Table 3-1 39 UCB Bolts (Replacement) A 453 (A 286) A 453 Grade 660 Grade 660, Class A Condition A Table 3-1 40 UCB Bolts Locking Cups & Tie A 240-74 or A 479- A 240 Type 304L Plates (Replacement Bolts) 75 Type 304L Table 3-1 45 Vent Valve Retaining Rings AMS 5658 AMS 5658 Type 15-5 PH Table 3-1 46 Vent Valve Jack Screws AMS 5737C AMS 5737C Alloy A-286 Table 3-1 54 LCB Bolts (Original) A 453 (A 286) A 453 Grade 660 Grade 660, Class A Condition A Table 3-1 56 UTS Bolts (Original) A 453 (A 286) A 453 Grade 660 Grade 660, Class A Condition A Table 3-1 62 Dowels (for Barrel-to-Former AMS 5667F AMS 5667F UNS Bolts) N07750 Table 3-1 69 Dowels (for Fuel Assembly AMS 5667F AMS 5667F UNS Support Pads) N07750 Table 3-1 77 LTS Bolts (Replacement) A 453 (A286) Grade A 453 Grade 660

____________________ 660, Condition A Class A Table 3-1 82 Dowels (for Guide Blocks) AMS 5667F AMS 5667F UNS N07750

AREVA Inc. ANJIP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

I ic.*n~qinn Rent~rt Paae~ 3-54 Document Table Component Item or Weld Name ANO-1 Scope MRP-1 89, Table Item Material *Revision I Number Material Table 3-1 91 FD Bolts (Original) A 453-65 (A 286) A 453-65 Grade Grade 660 660, Class A Table 3-2 Various Various Type 308 Type 308L Table 3-2 Various Various Type 308L Type 308 Table 3-2 Various Various Austenitic Stainless Type 308 / Type Steel Weld 308L Table 3-2 Various Various Alloy 69 Alloy 82 Table 3-2 80 WC-1 04 Nickel-Based Alloy Alloy 82 Weld The material designation differences for the component items and welds listed in Table 3-4 fall within one of eleven categories, which are addressed below:

1. Bolting (Original [UTS, LOB], Replacement [UCB, LTS]) where the scope for the ANO-1 license renewal specifies American Society of Testing and Materials (ASTM)

A 453 Grade 660, Condition A and MRP-1 89, Revision I specifies ASTM A 453 Grade 660 Class A.

2. Bolting (Original [FD]) where the scope for the ANO-I license renewal specifies ASTM A 453 Grade 660 and MRP-1 89, Revision 1 specifies ASTM A 453 Grade 660 Class A.

AREVA Inc. A IP-341 8NP Revision 0 Arkansas Nucrear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Sic.~n~ina Renort PaGa 3-55

-3. Dowels where the scope for the ANO-1 license renewal specifies AMS 5667F and MRP-1 89, Revision 1 specifies AMS 5667F UNS N07750.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensin~q Rep~ort Paoqe 3-56

4. Vent Valve Retaining Rings where the scope for the ANO-1 license renewal specifies AMS 5658 and MRP-1 89, Revision 1 specifies AMS 5658 Type 15-5 PH.

5. Vent Valve Jack Screws where the scope for the ANO-1 license renewal specifies AMS 5737C and MRP-1 89, Revision 1 specifies AMS 5737C Alloy A-286.

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-2_27-A Action Item 2)

Licensingi Report Page 3-57

6. UCB Bolts Locking Cups & Tie Plates where the scope for the ANO-1 license renewal specifies A 240-74 or A 479-75 Type 304L and MRP-1 89, Revision 1 specifies A 240 Type 304L.

7. Various welds where the scope for the ANO-1 license renewal specifies Type 308 and MRP-1 89, Revision 1 specifies Type 308L.

8. Various welds where the scope for the ANO-1 license renewal specifies Type 308L and MRP-1 89, Revision 1 specifies Type 308.

AREVA Inc. ANIP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

L ir~n~ina Re~nnr' Paae 3-58

9. Various welds where the scope for the ANO-1 license renewal specifies an austenitic stainless steel weld and MRP-1 89, Revision 1 specifies Type 308 / Type 308L.

10. Various welds where the scope for the ANO-1 license renewal specifies Alloy 69 and MRP-l189, Revision I specifies Alloy 82.

11 . One weld where the scope for the ANO-l license renewal specifies a nickel-based alloy weld and MRP-1 89, Revision 1 specifies Alloy 82.

Therefore, for the component items and welds identified in Table 3-4, which are included in both the scope for the ANO-1 license renewal and MRP-1 89, Revision 1, no additional aging degradation mechanisms are screened in as a result of these differences and no additional aging management recommendations are necessary.

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe 3-59 3.4 Program Modification Assessment Since ANO-1 RV internals component items and welds were identified in the preceding sections that are not included in MRP-189, Revision 1, it is necessary to consider if modifications to the program outlined in MRP-227-A are required to address the additional component items and welds. The following subsections assess whether modifications are needed. Note that the materials of construction for the various component items and welds are listed in Table 3-1 and Table 3-2.

3.4.1 Identification of Screening Parameters The screening parameters are listed in Table 3-5 through Table 3-12 for the various component items and welds identified in Section 3.2.

The environmental parameters for the plenum cover welds are the same as those listed in MRP-1 89, Revision 1 for the plenum cover. The environmental parameters for the plenum cylinder welds are the same as those listed in MRP-1 89, Revision 1 for the plenum cylinder. The environmental parameters for the tie plate and weld for replacement UCB bolting are the same as those listed in MRP-1 89, Revision 1 for the UCB bolt itself. The environmental parameters for the vent valve miscellaneous locking device component items and welds are the same as for the other vent valve items. The environmental parameters for the tie plate for replacement LTS bolting are the same as those listed in MRP-1 89, Revision 1 for the LTS bolt itself.

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe 3-60 The temperature for the RVLMS probe supports within the RV internals is the same as those listed in MRP-189, Revision 1 for the control rod guide tube (CRGT) assembly.

The fluence value listed in MRP-1 89, Revision 1 for the CRGT assembly component items and welds are < 5E18 n/cm 2 (E > 1 MeV). ["

] The environmental parameters for the remnants of the SSHT assemblies are the same as those listed in MRP-189, Revision 1 for the CSS or thermal shield cylinders to which they are affixed. The environmental parameters for the thermal shield welds are the same as those listed in MRP-189, Revision I for the thermal shield.

For the other items in this section, the operating stress was assumed to exceed the MRP-1 89, Revision 1 screening criteria (unless otherwise noted).

Fatigue for was assumed to be very low (<0.1 cumulative usage factor (C.UE)), which is similar to all RV internals component items.

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Pacqe 3-61 Unless otherwise noted, information regarding the welding type (i.e., single pass or multi-pass) was not located for welds. (

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Paqe 3-62 Table 3-5 Plenum Cover Screening Parameters Component Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item/Weld Category Specification Type, (0F) Exposure Stress (ksi) > 20% Weld (CUF Description Grade, or (n/cm 2), >0.1)

Class E> 1MeV__ __ ___

I. 4 .1 I. 4 4 4 (CUF

>0.1)

Fatigue Bolting Weld Multi-Pass

> 1MeV ENeutron (ksi)

Operating

> 20%

Cold Work Stress Temperature Exposure TableMaterial 3-6 Plenum (°F)Cylinder (nlcm2),

Welds Screening Parameters Material Type, or Material Specification Grade, Component Category Component Item/Weld Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item/Weld Description Category Specification Type, (0F) Exposure Stress (ksi) ~ 20% Weld (CUF Description Grade, Classor (nlcm2), ~0.1)

Class E>IMeV ______ ______

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq Report Panqe 3-63 Table 3-7 Tie Plate and Weld for Replacement UCB Bolting Screening Parameters Component Material Material Material Temperature' Neutron Operating Cold Work Multi-Pass Fatigue Bolting ltem/Weld Category Specification Type, (°F) Exposure Stress (ksi) _>20% Weld (CUF Description Grade, or (nlcm 2), >0.1)

Class E>*I i~eV ___

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Paaqe 3-64 Table 3-8 Miscellaneous Locking Device Component Items and Welds for the Vent Valves Screening Parameters Component Material Material Material Temperature Neutron Operating Cold Work>~ Multi-Pass Fatigue Bolting ItemlWeld Category Specification Type, (°F) Exposure Stress (ksi) 20% Weld (CUF Description Grade, or (nlcm=), _>0.1)

Class E > 1MeV 18 [ ]

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paae 3-65 Component Material Material Material Temperature Neutron Operating Cold Work>Ž Multi-Pass Fatigue Bolting DecIptionel CaeoySecfcto Grade, or F) nxposur Stes0.1)20 Wl (U ItmDedipio Caeorrpciiaio dye, or F) (Exposur Stes0ks) 201Wl)(U Class E>* 1MeV __ ___

+ + *4- 4 4 4 4 4 4 4 4 + + 4 4 4 4 4 4 4 4 1 4 4 4 4 4 - I 4 4 4 4 4 4 4 4 4 4 4

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq Report Paaqe 3-66 Component Material Material Material Temperature Neutron Operating Cold Work>~ Multi-Pass Fatigue Bolting Item/Weld Category Specification Type, (0F) Exposure Stress (ksi) 20% Weld (CUF Description Grade, or (n/cm 2), >0.1)

Class E > 1MeV___-

I- + + * + t I-b b a a a a

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Paae 3-67 Table 3-9 Tie Plate Weld for Replacement LTS Bolting Screening Parameters Component Material Material Material Temperature Neutron Operating Cold Work>-. Multi-Pass Fatigue Bolting Item/Weld Category Specification Type, (°F) Exposure Stress (ksi) 20% Weld (CUF Description Grade, or (nlcm2), >0.1)

Class E > MeV Table 3-10 RVLMS Probe Supports within the RV Internals Screening Parameters Component Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item/Weld Category Specification Type, (0F) Exposure Stress (ksi) _>20% Weld (CUF Description Grade, or (n/cm 2), >0.1)

Class E >IMeV__ __ ___

0 DescrptionGrade orRevision>0. Sop ndlRas8,Reiso 1Cmprio>(RP271MctonIem2 OeUntMaterialeatr ese ItenlsLceseRnea Component MaterialNcla Arana Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item/Weld Category Specification Type, (0F) Exposure Stress (ksi) ~ 20% Weld (CUF Description Grade, or (n/cm 2), ~O.1)

Class E>IMeV

+ + 4 4 +

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Page 3-69 Component Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting DecIptionel Caeoy Sefcto Grade, orF)(nlcmsur StesOks) >.01)l (U Dtmlesidio Caeorrpciiaiodye, (or)(Exposur Stes0k.)1)0 Wl (U jClass E>I1MeV _ _ _ _ _ _ _ _ _ _ _ _ _ _

AREVA Inc. ANP-341 8NP

-Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Paae 3-70 Component Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item/Weld Category Specification Type, (0 F) Exposure Stress (ksi) > 20% Weld (CUF Description Grade, or (n/cm 2), >0.1)

Class E

1MeV________

AREVA Inc. *ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2)

Licensing Report Paqe 3-71 Component Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item/Weld Category Specification - Type, (0F) Exposure Stress (ksi) > 20% Weld (CUF Description Grade, or (nlcm 2), >0.1)

Class E > MeV I. 1" + + 4 4

& & J d d

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit I Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq Report Paqe 3-72 Table :3-11 Remaining SSHT Assemblies Screening Parameters Component Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item Category Specification Type, (°F) Exposure Stress (ksi) > 20% Weld (CUF Description Grade, or (nlcm 2 ), Ž0.1)

Class E > 1MeV _____

Arkaonnsa NulatriaOn MntRactoria VeseaIternals LTenserenuewaluSconpeanMrat8,Reiiong 1 Comparionk MRt-Pass FactionuIem 2)in Grederr (a/cm),>-.1 D ienripina Material Component Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item Category Specification Type, (0F) Exposure Stress (ksi) ~ 20% Weld (CUF Description Grade, or (nlcm2 ), ~O.1)

Class E>IMeV

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Page 3-74 Table 3-12 Thermal Shield Screening Parameters Component Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item/Weld Category Specification Type, (°F) Exposure Stress (ksi) > 20% Weld (CUF Description Grade, or (n/cm2 ), >0.t)

Class E> 1MeV

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing~ Report Page 3-75 Component Material Material Material Temperature Neutron Operating Cold Work Multi-Pass Fatigue Bolting Item/Weld Category Specification Type, (0 F) Exposure Stress (ksi) > 20% Weld (CUF Description Grade, or (n/cm ), >_0.1)

Class E > 1MeV

1. b ____________ L L ______________ b

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Pa~qe 3-76 3.4.2 Characterization and Screening for Degradation In this section, the component items and welds identified in Section 3.2 are screened using the process set forth in MRP-1 89, Revision 1. The screening criteria are defined in Table 3-1 of MRP-189, Revision 1. Using these criteria, each age-related degradation mechanism is screened for each item identified in the tables in Section 3.4.1. An aging mechanism is screened "in" (Category Not A) if the screening criteria are met or exceeded for the particular item. The results of this initial screening are shown in Table 3-13, Table 3-14, Table 3-15, Table 3-16, Table 3-17, Table 3-18, Table 3-19, and Table 3-20.

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensina Reoort Paae 3-77 Table 3-13 Plenum Cover Screening Results

.=E o.) -

Component Item Description Material Category 0 c. *. -o n xo2

-- u. E. .- =. 00 U- * "E o~ -

I.-L wu > n A A A A A A A A A A A A A A A A Table 3-14 Plenum Cylinder Welds Screening Results

E o2E o Component Item Description Material Category 0O ci, .2* _ 2 A A A A A A A A A A A A A A A A

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinqi Report Pacqe 3-78 Table 3-15 Tie Plate and Weld for Replacement UCB Bolting Screening Results

- 0 ._= C 0 0 .

Component Item Description Material Category * .* * * ** .= * ***,

mE *E o - -

Nt A A A A A A A A

A A A A A A A A Table 3-16 Miscellaneous Locking Device Component Items and Welds for the Vent Valves Screening Results 0

0)E .2E =0 .

2 Cf- Q.

o

0 *0 "

Component Item Description Material Category (u 0 _ -

_ ,, ,* * ,UcnxO*

mE ."E "5-i-w w > r A A Not A A A A A A A A Not A A A A A A Nt A Not A A A A A A A

A A Not A A A A A A

AREVA Inc. ANP-341 8NP L Revision 0 Arkansas Nuclear One Unit I ReactorVessel Internals License Renewal Scope and MRP-1 89, Revision 1. Comparison (MRP-227-A Action Item 2)

Licensina Renort Paae 3-79

-a) °E .E-Component Item Description Material Category tO

0 * ** ** *.

-~ ,, E. cn,

" ,.~

.*E ='E "6 -

I.wL A A A A Not A A A A A A A A A A A A A A A A Not A A A A Nt A A A A A A A A

Nt A A A A A A A A

A A A A A A A A Nt A A A A A A A A

Nt A A A A A A A

__ __ __ _A A A A A A A A Not AA A A A A A A AA AA A A A A No A A A A A A A Ao AA A A A A A A

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2)

Licensingq Report Panqe 3-80 Table 3-17 Tie Plate Weld for Replacement LTS Bolting Screening Results Table 3-18 RVLMS Probe Supports within the RV Internals Screening Results

P"(D ,1 " U 0 =.. *'E .E -= o=

Component Item Description Material Category 0° _

A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq Report Paqe 3-81

~0 c .

Component Item Description Material Category V u* * .* "-.

.*E *E o -

A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A-- A A A A A A A A A A A A A A A A A A A

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinq Report -Pagqe 3-82 (3<--2 02 no.

Component Item Description Material Category 3C W.2a I- .. m

.mE *E -

A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingi Report Page 3-83 Table 3-19 Remaining SSHT Assemblies Screening Results

~

tO ~ )- 't "

Component Item Description Material Category 0t <u) *--" "'-u *R =, -

1= "E o - -

Not A A A A A A A A Not A A A A A A A A Not A A A A A Not A A Not A Not A A A A A A A A Not A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A Not A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A A

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Licensina Reoort Paae 3-84 Table 3-20 Thermal Shield Screening Results Component Item Description Material Category C) o

E "E o --

A A A A A Not A A A A A A A A Not A A A A A A A A Not A A A A A A A A Not A A A A A A A A Not A A A

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensin~q Report Paqe 3-85 3.4.3 Failure Modes and Effects Criticality Analysis (FMECA)

The objective of the failure modes and effects criticality analysis (FM ECA) is to provide a systematic, qualitative review to identify the ANO-1 RV internals component items, welds, and age-related degradation mechanisms that potentially result in functional degradation leading to significant risk. The FMECA is used to examine the susceptibility as well as safety and economic consequences of the identified RV internals component items, welds/age-related degradation mechanism combinations. The FMECA approach uses inductive reasoning to ensure that the potential failure of each subcomponent is analyzed to determine the results or effects on the system and to classify each potential failure mode according to its severity (5).

Each failure mode was judged on its importance to risk, based on the susceptibility and severity of consequences. Consequences were examined from two perspectives:

safety and economic. A risk matrix was developed to correlate the consequence severity of a particular age-related degradation mechanism with the susceptibility of that particular mechanism. Different risk banks were used within the matrix to categorize the level of risk of a particular component item/degradation mechanism pair, and provide guidance on the strategies that should be developed to reduce the corresponding risk and a basis for ranking and categorization. The risk matrix utilized in MRP-1 89, Revision 1 in the development of MRP-227-A was similarly used for the relevant ANO-1 RV internals component items and welds and the results are shown in Table 3-21, Table 3-22, Table 3-23, Table 3-24, Table 3-25, Table 3-26, Table 3-27, and Table 3-28.

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Licensingi Report Pagie 3-86 Table 3-21 Plenum Cover FMECA Results Table 3-22 Plenum Cylinder Welds FMECA Results SCC IASCO ISR & Creep Wear Fatigue TE IEVS --

>. a >. a ,,, m . a ,,, .oaw,* w > a,,,

o a w* a

~A A~A A. AA AA AA AA aA a AlA A 0 ~ A A A 0A A A A A AoA A A A A A A A A A A A A A A A A A A

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessei Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensina Report Paae 3-87 Table 3-23 Tie Plate and Weld for UCB Bolting FMECA Results

-oSCC ASCC ISR & Creep Wear Fatigue TE IE VS 0*

. _,-oa - . a=, 0 8211IIA AA , AA AA A A AA AAAB

AREVA Inc. ANP-3418NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensing Report Page 3-88 Table 3-24 Miscellaneous Locking Device Component Items and Welds for the Vent Valves FMECA Results

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Licensingq Rep~ort Page 3-89

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Licensinci Report Pane 3-90 SCC IASCC ISR & Creep Wear Fatigue TE IE VS Coa g a a a-

&aE .9 .eCeo)E B 1 2o I~ II A A8~

0~ O . A0 A 0 ~ A0~ A .A AO A A 0 A A A Ca u ~ a o~ g ~ ~ o~a ~ ~o a C ~ ~ g ~ ~go~/

00 A A A AOUA A A A A A A Aa.E A A A A

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensinqi Report Pagie 3-91 Table 3-25 Tie Plate for Replacement LTS Bolting FMECA Results scc ASOC SR & Creep Wear FatiQue TE IE VS 0 Td 1 U ~C U U ~C U ~C U ~C U ~C U -~ C U ~C e ~ m a am ~ am ~. a m ~. ~ ~em ~. m > a a m ~ C ~em E Id-----0) a5 o~E .~ a ~ CE .~ a ~E -~ a ~ CE 2 ~E ~ a ~2 aE ~ 0) ~0 .C 0 0)~

eo ~ aOU ~ aU ~ aOO ~ ~OO ~EQ ~O ~ ~

ri Ca ~

aOUU) ~E~~OU a og ~~E Wa ~ a 0 g~

a U) U) ~

~o ~ ~ ~C

~ag U) m

~ o.~

0W -aa U)~gg W _ ~

U) m

~ a 0[Ii 0C 1~

W U) 0 W ~ W U) W *~

!A A A A AA AA A A A A A A A A A A A A A A A A A A A A A

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision I Comparison (MRP-227-A Action Item 2)

I i,~an~inn Pannff Pmni .* -_q9 Table 3-26 RVLMS Probe Supports within the RV Internals FMECA Results scc ASCO SR & Creep Wear Fatigue TE- IE- VS-111111 511111

- - - - - - - - - - - - - - - - - - - - - - C C) a a a a a

[HIll a

9 C C C C a C C C U C C

~a a~ ~e.ao~aE C

~a C~ ~ am ~a U

C Ca

~m C

~

U C

C CW am C

~

U C ~a

~m ~I~I4I ~jB~ C C~

~m C U C ~a am 6 Cu a c ce ~0 g ~U~aC~ -a aD E

wOU

~

~E~0u

~) C ~ >~ inC 0

a C~ ~ ~) C >~ a C 00 ~ G) C ~ >~ a C 0 C

C C ~ ~a ~ ~a ~-a.t~ ~C CO~J '~C 0.

0 - - uio a Cl) wo co CI) o ii, U~

Cl) wo cu Ci) uju ci, Ci) wu ~ Ci) wu cc~

ci, Cl) wu C 0

A AA AA AA AA AA AA AA AA A AA AA AA AA AA AA AA AA A AA AA AA AA AA AA AA AA A AA AA AA AA AA AA AA AA A AA AA AA AA AA AA AA AA A AA AA AA AA AA AA AA AA A AA AA AA AA AA AA AA AA

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Licensinq Report Page 3-93

AREVA Inc. ANP-341 8NP

~Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89,. Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paaqe 3-94 T

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LicensinQ Report Paaqe 3-95

-D Soc ASOC ISR&creep Wear Fatigue

TE- - - - - - IE- - - - - - VS- - - 0 C)

C a C a *C a ~C W C a C

~e ~a ~a a C CW C ~a ~

.CC C~ ~ C~

~.-a C~ m ~ ~O m = ~U m ~ _ ~.0 mam ~= ~. a~ m .~ ~~-a a m Z ~ am

~ ~2

~ a~ ~

~

aE .C .C

~

0' 2

~

aE .C .C

~

C)~

2 aE .a ~ 2 aE _

~ C)~.

~ ~

~O .~

.~ ~

a o2

~ aE

~C a ~

a C)~ ~C .a Z-C -

ca ~ C~ ~ u~ a Cg ~ - a ~ 0 -~ ~ U ~ D~ U .t~ a .~ aC~ ~ a ~ C

~ ac ~ a C'~ ~ a C >. a a C U COo a CO 3 ~ COo ~ CO 3 '~ CO 0

~ CO 0

~ COo CO LU CO LU CO LU CO CLI CO LU CO LU CO LU CO LU C-,

A 'AA AA AA AA AA AA

AA AA A AA AA AA AA AA AA AA AA

AREVA Inc. ANP-341 8NP Revision C Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paaqe 3-96 Table 3-27 Remaining SSHT Assemblies FMECA Results

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Licensing Report Paqe 3-97

-o SCC ASCC 1SR & &*eep Wear Fatigue TE IE VS 0*

0 o a*o-a=o.a..=

0 ~ 0 .o a ~ -! a 0o 03 I~ 03 a m t* eml *1 Il C U0 1at*LI6 'l t A A- A A A A A A~ Am ŽA Am A

,

.- 5 ~~ ,A A E~ ~ 2a A2 AEAm 2A E A A Am A A A m A A A5 A AA AEAA A 0 oA A AE A A

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Pagqe 3-98 Table :3-28 Thermal Shield FMECA Results SCC IASCC ISR & Creep Wear Fatigue TE tE VS o

,_- ° *o * - **.2 - 0)*

. a aa...a.. a. a o-o A AAAA AA AA, A 1 I II A A U A CAA B 1 I SCA C A C A A AA ~ a B 13 II AA A AA AA A AA AA 1 3 I IIIAg!A A BU1111 AA aA aA A am A A A A a A A a A B, a 3 mII A

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensincq Report Pacqe 3-99 3.4.4 Engineering Evaluation and Assessment The component items and welds not included in MRP-1 89, Revision 1 that screened as non-Category A include the tie plate from the replacement UCB bolts, various parts of the original vent valve locking device [

] various parts of the modified vent valves locking device

[ I and the hex head cap screw in the remaining SSHT assembly. The aging degradation mechanisms that lead to these component items and welds being screened as non-Category A are SCC, wear, thermal aging embrittlement (TE), and irradiation stress relaxation (ISR) and creep.

Thermal aging embrittlement itself does not cause failure. However, TE can cause a reduction in the toughness of the material, leading to an increased susceptibility to failure (18).

3.4.4.1 Replacement Upper Core Barrel Bolts Tie Plate The replacement UCB bolts and their locking mechanism [

] are depicted in Figure 3-1. [

]

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Licensina Reoort Paae 3-100 As noted in Table 5-1 in the PWR Internals Aging Management Program Plan for ANO-1 (4), the locking devices of the UCB bolts are considered a "Primary" component item (consistent with MRP-227-A) and a visual (VT-3) examination of the UCB bolt locking devices is performed on the 10-year inservice inspection (ISI) interval. As noted in Table 5-4 of Reference (4), the examination acceptance criteria (specific relevant condition) for the visual examination of the UCB bolt locking devices is evidence of broken or missing bolt locking devices. As noted above, [

] Therefore, these situations are expected to be covered by the examination acceptance criteria (specific relevant condition) described in Table 5-4 of Reference (4).

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Licensingq Report Paaqe 3-101

] the inspection frequency described for the UCB bolt locking devices in Reference (4).

Therefore, [ ] locking devices of the replacement UCB bolts at ANO-1 does not need any further aging management beyond that detailed in Reference (4) and is satisfactory as a "Primary" component item, as described in Reference (4).

3.4.4.2 Original and Modified Vent Valve Locking Devices As stated in the PWR Internals Aging Management Program Plan for ANO-1 (4), based on advice from AREVA 19 , the vent valve locking devices (both original and modified) should be included as an existing program under MRP-227-A. Based on this recommendation, the vent valve locking devices (both original and modified) were included in Table 5-3 of Reference (4), to perform a visual (VT-3) examination to look for wear in the original vent valve locking devices and cracking due to SCC for the modified vent valve locking devices. However, this guidance does not address the

[ ] within the original vent valve locking devices identified herein.

19Future revisions to MRP-227 may classify examination of these component items differently; however current guidance, based on MRP-227-A (3) and AREVA recommendations, is to classify examination of these component items as "Existing Programs' utilizing aging management elements contained in the ANO-1 technical requirements manual.

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Licensingq Report Page 3-102 To meet the intended function described in Section 3.2.4, structural integrity of the vent valve assembly must be maintained to ensure the vent valve remains in the CSS nozzle and functional. [

] As shown in Table 5-1 of Reference (4), the vent valve retaining rings are considered primary component items within the MRP-227 program at ANO-I. Table 5-1 of Reference (4) delineates that 100% of the accessible surfaces of the retaining rings are to be inspected via visual VT-3 inspection on the 10-year ASME B&PV Code Section XI ISI interval. [

]

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Licensingq Report Pacqe 3-103 Per Note 1 of Table 5-3 in Reference (4), a verification of the operation of each vent valve shall also be performed through manual actuation of the valve. The valves are verified to be not stuck in the open position and that no abnormal degradation has occurred. The valves are examined for evidence of leakage between the valve disc and the valve body (i.e., flow lines across the sealing surface), cracking of lock welds and locking cups, jack screws for proper position, and wear. [

]Therefore, the [ ] of the original vent valve locking device are further categorized as "Existing Programs" for ANO-I. If this degradation were to occur, it would likely be detected (prior to loss of intended function) by the visual inspection and operability testing performed each refueling outage or the VT-3 inspection performed during the 10-year ISI intervals. The potential for [

] is adequately managed by the existing plant Technical Requirements Manual and the MRP-227-A inspection requirements invoked through Reference (4).

3.4.4.3 Cap Screw in the Remaining SSHT Assembly The cap screw (Part 114) secures a portion of the remaining SSHT assembly to the thermal shield. In addition, the [

AREVA Inc. ANP-341 8NP Revision 0 Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2)

Licensingq Report Paqe 3-104 The susceptibility category listed in Table 3-27 for the cap screw is a Category C, which is based on the likelihood of susceptibility to irradiation stress relaxation. Based on a fluence of [ ] for the cap screw given in Table 3-1 1 of this document and comparing this fluence to the lower bound curve in Figure H-7 in MRP-175 [18], [

] However, as noted in Section 3.1.1 of this document, the function of this cap screw is [ J The FMECA results for the cap screw weld (WC-121) in Table 3-27 indicate this weld is screened out of all age-related degradation mechanisms; [

Therefore, irradiation stress relaxation and creep is downgraded to Category A for this item. It is unlikely that the cap screw or the remaining SSHT assembly this cap screw is responsible for securing could become loose parts due to irradiation stress relaxation and creep of the cap screw. Therefore, since irradiation stress relaxation and creep is downgraded to Category A for this component item, this cap screw does not require any further aging management.

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Licensingq Report Paqe 4-1

4.0 CONCLUSION

S As required by Applicant/Licensee Action Item 2 for the MRP-227-A SER, this report completes the comparison between Table 4-1 and 4-2 in MRP-189, Revision 1 and the component items and welds designated in the scope of license renewal for ANO-1. As described above, three groupings of component items were identified as being within the scope of license renewal and subject to an AMR, but were not included in the relevant MRP-1 89, Revision 1 tables:

Replacement UCB Bolt Tie Plate

Original and Modified Vent Valve Locking Devices

Cap Screw for Remaining SSHT Assembly A review of background information pertaining to the replacement UCB tie plate, original and modified vent valve locking devices, and the cap screw for the remaining SSHT assembly was completed. The appropriate component items and welds of interest were identified. The sequence steps as described in MRP-1 89, Revision 1 Sections 3 and 4 were used to evaluate the aging mechanisms and resultant aging effects on the component items and welds that could result in degradation leading to significant risk.

The material types as well as screening parameters such as temperature, fluence, and operating stresses were identified (or assumed with justification). These parameters were then used for comparison to the screening criteria from MRP-1 89, Revision i to perform the initial screening of these component items and welds for degradation. A FMECA was performed, and a preliminary categorization using the degradation screening results as well as the EMECA was performed. An engineering evaluation and assessment was used to categorize the component items for inspection. Finally, the results of the evaluation were reviewed for any necessary modifications to the program defined in MRP-227-A.

The results are as follows:

Replacement UCB Bolt Tie Plate - Categorized as "Primary" as described in Reference (4)

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Licensin~q Report Paqe 4-2

Original and Modified Vent Valve Locking Devices - Categorized as "Existing Programs" as described in Reference (4) and the internal Entergy site-specific report

Cap Screw for the Remaining SSHT Assembly - Categorized as "Category A"and no further aging management is required

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Licensingq Report Pagqe 5-1

5.0 REFERENCES

1. NRC Document NUREG-1800, Revision 2, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants - Final Report," December 2010 (ADAMS Accession Number ML103490036).

2. AREVA Document BAW-2248, "Demonstration of the Management of Aging Effects for the Reactor Vessel Internals," July 1997, ADAMS Accession Number 9708130203.

3. Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A). EPRI, Palo Alto, CA:

2011. 1022863.

4. Entergy Operations, Inc. Letter, 1CAN051403 to the NRC dated May 20, 2014 (ADAMS Accession Number ML14141A554), Attachment 1, "PWR Internals Aging Management Program Plan for Arkansas Nuclear One Unit 1," Structural Integrity Report Number 1200459.401, Revision 1, May 2014 (ADAMS Accession Number ML14141A555).

5. Materials Reliability Program: Screening, Categorization, and Ranking of B&W-Designed PWR Internals Component Items (MRP-1 89-Rev. 1).

EPRI, Palo Alto, CA: 2009. 1018292.

6. Code of Federal Regulations, Title 10, Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants."

7. Code of Federal Regulations, Title 10, Part 54.4, "Scope."

8. Code of Federal Regulations, Title 10, Part 54.21, "Contents of application

- technical information."

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Licensingq Report Panqe 5-2

9. Letter from William Cavanaugh III (Arkansas Power & Light Company) to Director of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commission, "Arkansas Power & Light Company, Arkansas Nuclear One

- Unit 1, Docket No. 50-31 3, License No. DPR-51, 'Surveillance Specimen Holder Tube Repair RePort'," NRC Accession Number 4004007815, June 1, 1976.

10. ASTM A 453-65, "Standard Specification for High-Strength, High-Temperature Bolting Materials with Expansion Coefficients Comparable to Austenitic Steels," American Society for Testing and Materials.

11 .ASTM A 453-1 2, "Standard Specification for High-Temperature Bolting, with Expansion Coefficients Comparable to Austenitic Stainless Steels,"

ASTM International.

12. Aeronautical Material Specifications, AMS5667F, "Alloy, Corrosion and Heat Resistant, Nickel Base - 15.5Cr- 7 Fe - 2.5 Ti - 1 (Cb+Ta) -

0.7A1)," Revised 1/15/60.

13. ASME Boiler & Pressure Vessel Code, 2013 Edition,Section II, Part B, SB-637, "Specification for Precipitation-Hardening Nickel Alloy Bars, Forgings, and Forging Stock for High-Temperature service."

14. Aeronautical Material Specifications, AMS 5658, "Steel Bars, Forgings, and Rings, Corrosion Resistant, 15Cr-5Ni-4Cu," Issued 9/1/65.

15. Herny, E., et. al., "Study by Differential Thermal Analysis of Reverse Spinodal Transformation in 15-5 PH Alloy," Solid State Phenomena, Volumes 172-174, pages 338-343, 2011 Trans Tech Publications.

16. Aeronautical Material Specifications, AMS 5737C, "Steel, Corrosion and Heat Resistant, 15Cr-26Ni-1.3Mo-2.1Ti-0.3V, Consumable Electrode Melt, 1650F (899C) Annealed and Precipitation Heat Treated," Revised 3/15/66.

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Licensin~q Report Paqe 5-3 17.ASME Boiler & Pressure Vessel Code, 2013 Edition,Section II, Part A, SA-638, "Specification for Precipitation Hardening Iron Base Superalloy Bars, Forgings, and Forging Stock for High-Temperature Service."

18. Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism Screening and Threshold Values (MRP-1 75). EPRI, Palo Alto, CA: 2005. 1012081.