Text

to ANP-3285, Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld and Revision 0 to ANP-3359NP, Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison. (Non-Proprietary)
	ML15113B134
Person / Time
Site:	Davis Besse
Issue date:	04/21/2015
From:	; AREVA
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15113B131	List: L-15-139, License Renewal Reactor Vessel Internals Inspection Plan; ML15113B133; ML15113B134;
References
	L-15-139 ANP-3285, Rev. 0, ANP-3359NP, Rev. 0, MRP-189, Rev. 1
	Download: ML15113B134 (68)
	v • d • e

Enclosure B Davis-Besse Nuclear Power Station, Unit No. I (Davis-Besse)

Letter L-1 5-139 AREVA NP Report No. ANP-3285 Revision 0.

"Confirmation of Stress Relief for the DB-1 Core Support Shield UDDer Flange Weld" 8 pages follow

uontronea uocument A

AREVA ANP-3285 Confirmation of Stress Relief for the Revision 0 DB-1 Core Support Shield Upper Flange Weld March 2014 AREVA Inc.

uontroiiea uocument AREVA Inc. ANP-3285 Revision 0 Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld Page i Contents Paaqe 1.0 INTR O DUC T IO N ............................................................................................... 1-1 2 .0 S UMMAR Y ........................................................................................................ 2-1 3.0 R EC O R DS S EA R C H......................................................................................... 3-1 4 .0 R E F E R E NC E S .................................................................................................. 4 -1

uontroaiea uocument AREVA Inc. ANP-3285 Revision 0 Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld Paae ii Nomenclature Acronym Definition B&W Babcock and Wilcox CE Combustion Engineering DB-1 Davis-Besse Unit 1 CSS Core Support Structure MRP Materials Reliability Program NSSS Nuclear Steam Supply System PWR Pressurized Water Reactor QADP Quality Assurance Data Package RV Reactor Vessel

uontroilea uocument AREVA Inc. ANP-3285 Revision 0 Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld Page 1-1

1.0 INTRODUCTION

The Materials Reliability Program (MRP) developed inspection and evaluation guidelines in MRP-227-A (Reference 1) for managing long-term aging of reactor vessel internals components of pressurized water reactors (PWRs). These guidelines contain mandatory and needed requirements and an implementation schedule for Babcock &

Wilcox (B&W) nuclear steam supply systems (NSSSs) currently operating in the United States. The guidelines also contain applicant/licensee action items that shall be addressed by applicants/licensees who choose to implement the NRC approved version of MRP-227.

The fourth of these applicant/licensee action items is for the applicants/licensees of currently operating B&W NSSS units to confirm that the core support structure (CSS) upper flange weld was stress relieved during the original fabrication of the reactor vessel (RV) in order to confirm the applicability of MRP-227, as approved by the NRC, to their facility. If the stress relief was not performed, applicants/licensees must inspect this component as a "Primary" inspection category component consistent with the recommendations in MRP-227, as approved by the NRC, for the Westinghouse and Combustion Engineering (CE) upper core support barrel welds.

The purpose of this report is to address the above action item for the B&W-fabricated Davis-Besse Unit 1 (DB-1) RV internals.

uontroiiea uocument AREVA Inc. ANP-3285 Revision 0 Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld Page 2-1 2.0

SUMMARY

A records search was conducted to confirm that the CSS upper flange weld in the RV internals was stress relieved during original fabrication of the DB-1 RV internals. The detailed, signed and dated, step-by-step fabrication records of interest were reviewed.

Based on the records search reported in the following sections, a low frequency, vibratory stress relief was performed on the CSS upper flange weld during original fabrication of the DB-1 RV internals.

uontroiiea uocument AREVA Inc. ANP-3285 Revision 0 Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld Page 3-1 3.0 RECORDS SEARCH The double U-Groove, double V-Groove, and J-Groove welds listed in MRP-189, Rev. 1 (Reference 2) Table 4-2 were reviewed. The welds from this table selected for this records search are large structural vertical or circumferential seam welds and large nozzle welds.

After the welds were selected, applicable drawings were reviewed to gain possible fabrication sequence history, and the records for the applicable mark (MK) and assembly numbers were searched. The MK numbers were obtained from the appropriate design drawings and confirmed by review of the associated fabrication records and the quality assurance data package (QADP).

The DB-1 fabrication records at the AREVA Lynchburg Old Forest Road facility were reviewed. The records search focused on the actual weld fabrication sequences and any post-weld stress relief performed on the welds of interest. The goal of the search was to find the detailed fabrication process sheets that show signed and dated evidence of completed process steps.

The welds investigated in this records search, including the CSS Upper Flange weld, are confirmed to have been stress relieved with a low frequency, vibratory stress equalization (Reference 3).

uontrooiea uocument AREVA Inc. ANP-3285 Revision 0 Confirmation of Stress Relief for the DB-1 Core Support Shield Upper Flange Weld Page 4-1

4.0 REFERENCES

1. MaterialsReliability Program:PressurizedWater Reactor InternalsInspection and Evaluation Guidelines (MRP-227-A). EPRI, Palo Alto, CA: 2011. 1022863.

2. MaterialsReliability Program:Screening, Categorization,and Ranking of B& W-Designed PWR Internals Component Items (MRP-189-Rev. 1). EPRI, Palo Alto, CA: 2009. 1018292.

3. All supporting documents are available for NRC review at AREVA facilities.

Enclosure C Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse)

Letter L-1 5-139 AREVA NP Report No. ANP-3359NP Revision 0.

"Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189. Revision I Comparison" (Non-Proprietary) 54 pages follow

uontroiiea uocumen:

A AREVA ANP-3359NP Davis-Besse Reactor Vessel Internals Revision 0 License Renewal Scope and MRP-189, Revision 1 Comparison December 2014 AREVA Inc.

uontroaoea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Pagei Contents Page 1.0 INT R O DUC T ION ............................................................................................... 1-1 2 .0 ME T HO DO LO G Y .............................................................................................. 2-1 3 .0 C O MP AR IS O N .................................................................................................. 3-1 3 .1 S co pe Defin itio n ...................................................................................... 3-1 3.1.1 Identification of D-B License Renewal Scope for RV Inte rn a ls ....................................................................................... 3 -2 3.1.2 Component Items Contained in MRP-1 89, Rev. 1 ....................... 3-2 3.2 Component Item Comparison ............................................................... 3-25 3.2.1 Vent Valve Locking Device ........................................................ 3-25 3.2.2 Lower Grid Guide Block Attachment Replacement .................... 3-29 3.3 Program Modification Assessment ....................................................... 3-30 3.3.1 Materials of Construction ........................................................... 3-30 3.3.2 Identification of Screening Parameters ...................................... 3-31 3.3.3 Characterize and Screen for Degradation .................................. 3-34 3.3.4 Failure Modes and Effects Criticality Analysis (F ME C A) .................................................................................... 3 -3 7 3.3.5 Engineering Evaluation and Assessment ................................... 3-40 4 .0 C O NC LUS IO NS ................................................................................................ 4 -1 5 .0 R E FE R E NC E S .................................................................................................. 5-1

uontrouea uocumern AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page ii List of Tables Table 3-1: Comparison of D-B RV Internals License Renewal Scope to MRP-189 R evision 1 C om ponent Item s .................................................................. 3-6 Table 3-2: Comparison of D-B RV Internals License Renewal Scope to MRP-189 R evisio n 1 We ld s .................................................................................. 3-16 Table 3-3: Materials of Construction for Vent Valve Miscellaneous Locking D e v ice Ite m s ......................................................................................... 3 -3 0 Table 3-4: Materials of Construction for Lower Grid Guide Block Attachment R e placem e nt Item s ............................................................................... 3-3 1 Table 3-5: Original Vent Valve Miscellaneous Locking Device Parts Screening P a ra m e te rs ........................................................................................... 3 -3 2 Table 3-6: Lower Grid Guide Block Attachment Replacement Parts Screening P a ra m e te rs ........................................................................................... 3 -3 3 Table 3-7: Original Vent Valve Miscellaneous Locking Device Parts Screening R e s u lts .................................................................................................. 3 -3 5 Table 3-8: Lower Grid Guide Block Attachment Replacement Parts Screening R e s u lts .................................................................................................. 3 -3 6 Table 3-9: Original Vent Valve Miscellaneous Locking Device Parts FMECA R e s u lts .................................................................................................. 3 -3 8 Table 3-10: Lower Grid Guide Block Attachment Replacement Parts FMECA R e s u lts .................................................................................................. 3 -3 9

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page iii List of Figures Figure 3-1: V ent V alve A ssem bly ............................................................................... 3-27 Figure 3-2: Typical Vent Valve (External Core Support Shield View) ......................... 3-27 Figure 3-3: Typical Vent Valve (Inside Core Support Shield View) ............................ 3-28 Figure 3-4: Original Vent Valve Locking Device Miscellaneous Parts ........................ 3-28 Figure 3-5: Lower Grid Guide Block Assembly ........................................................... 3-29

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Paae iv Nomenclature Acronym or Definition Abbreviation AMP Aging management program AMR Aging management review ASTM American Society of Testing and Materials B&W Babcock and Wilcox BB Baffle-to-baffle CBF Core barrel-to-former CFR Code of Federal Regulations CRGT Control rod guide tube CSS Core support shield D-B Davis-Besse Nuclear Power Station EPRI Electric Power Research Institute FB Baffle-to-former FD Flow distributor FENOC FirstEnergy Nuclear Operating Company FMECA Failure modes, effects, and criticality analysis HTH Hot-rolled, high temperature annealed and aged condition I&E Inspection and evaluation IASCC Irradiation assisted stress corrosion cracking IE Irradiation embrittlement IMI Incore monitoring instrumentation ISI Inservice inspection ISR Irradiation enhanced stress relaxation LCB Lower core barrel LOCA Loss of coolant accident LRA License renewal application LTS Lower thermal shield MRP Materials Reliability Program NRC Nuclear Regulatory Commission PH Precipitation hardenable PWR Pressurized water reactor RV Reactor vessel SER Safety evaluation report

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paae v Acronym or Definition Abbreviation SS Stainless steel SCC Stress corrosion cracking SSCs Systems, structures, and components SSHT Surveillance specimen holder tube TE Thermal embrittlement UCB Upper core barrel US United States UTS Upper thermal shield VS Void swelling

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Pagqe 1-1

1.0 INTRODUCTION

As part of the safety evaluation report (SER) for the license renewal application (LRA) of the Davis-Besse Nuclear Power Station (D-B), the United States (US) Nuclear Regulatory Commission (NRC) confirmed the applicability of License Renewal Commitment Item Number 15 [1]. Item Number 15 describes the D-B commitment to submit a plant-specific inspection plan for ensuring the implementation of the Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 227 program guidelines as amended by the MRP-227 NRC safety evaluation.

In December 2008, EPRI issued Revision 0 of MRP-227 inspection and evaluation (I&E) guidelines for managing long-term aging of pressurized water reactor (PWR) reactor vessel (RV) internals and submitted the report to the NRC for review and approval in January 2009. In June 2011, the SER for MRP-227, Revision 0 was issued by the NRC and was revised to Revision 1 in December 2011. This revised SER Revision 1 is included in the NRC-approved MRP-227-A report [2]. MRP-227-A provides generic augmented inspection requirements for the currently operating fleet of US PWRs.

Section 3.0 of the SER for MRP-227 documents the staffs 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. FirstEnergy Nuclear Operating Company (FENOC) plans to implement MRP-227-A for D-B. To meet the commitment detailed in the D-B LRA and the NRC conditions upon the use of MRP-227, FENOC 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:

uontroowea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Paqie 1-2 "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/licensees shall 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 accordancewith 10 CFR 54.4. If the tables do not identify all the RV Internals components that are within the scope 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/LicenseeAction Item 2."

The purpose of this document is to perform a comparison between the D-B RV internals license renewal scope and Tables 4-1 and 4-2 of MRP-1 89, Revision 1 to satisfy Applicant/Licensee Action Item 2. MRP-189, Revision 1 performs a categorization of the RV internals component items specific to the Babcock & Wilcox (B&W) design [3]. Note that MRP-1 91 is not considered because it is not applicable to the B&W design. Any D-B RV internals component items not reported in the relevant MRP-189 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: [ I

uontrowiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 2-1 2.0 METHODOLOGY The methodology used in this document to complete the comparison described in Section 1.0 is as follows:

1. Define the scope for license renewal.

2. Identify the RV internals component items within the scope of the license renewal and subject to aging management review (AMR) for D-B.

3. List the relevant RV internals component items and welds.

4. List component items and welds contained in Tables 4-1 and 4-2 of MRP-1 89, Revision 1.

5. Compare the tabulated component items defined in Steps 3 and 4 and identify whether the MRP-1189, Revision 1 tables contain all of the RV internals component items and welds that are within the scope of license renewal and subject to AMR for D-B.

6. Propose any necessary modifications to the program defined in MRP-227-A to manage the aging effects of the identified D-B RV internals component items that are not included in MRP-189, 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:

a. Identify RV internals components, materials, and environments

b. Identify degradation screening criteria

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

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

e. Severity categorization (A, B, C)

f. Engineering evaluation and assessment

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

uontroiaea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 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) [4] and are based on the following key principles:

1. The regulatory process is adequate to ensure that the licensing bases of all currently operating plants maintain an acceptable level of safety with the possible exceptions of the detrimental aging effects on the functions of certain systems, structures, and components (SSCs), as well as a few other safety-related issues, during the period of extended operation.

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

In implementing these two principles, 10 CFR 54.4, "Scope," defines SSCs included in the scope of license renewal as the following:

1. those that are safety-related,

2. those whose failure could affect safety-related functions, and

3. those that are relied on to demonstrate compliance with NRC 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 AMR. An in-scope SSC is subject to 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.

uontroaiea uocumernt AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-2 3.1.1 Identification of D-B License Renewal Scope for RV Internals The D-B RV internals components within the scope of license renewal and subject to AMR are determined based on the safety-related intended functions of the components. The safety-related intended functions are defined as:

1. Provide support for the core and maintain core in a coolable configuration under all operating conditions

2. Provide shielding to attenuate radiation generated in the core

3. Control primary coolant distribution to the core as required for design heat removal capability

4. Provide support and alignment for control rod drive mechanisms, control rods, and incore detectors The D-B RV internals components within the scope of license renewal that support these intended functions are detailed in the Aging Management Review of the Reactor Vessel Internals for D-B (herein referred to as the "D-B AMR document").

3.1.2 Component Items Containedin MRP-189, Rev. I The RV internals component items contained in Tables 4-1 and 4-2 of MRP-1 89, Revision 1 are compared against the D-B RV internals component items within the scope of license renewal in Table 3-1 (component items) and Table 3-2 (welds) of this document. Component items contained in the MRP-189 tables that are not in the D-B RV internals scope of license renewal are not listed. These component items 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).

3.1.2.1 Vent Valves As described in the SER for MRP-227, the vent valve disc, disc shaft, and hinge pin were determined to be active components. As described in Section 3.1, components that perform an intended function with a change in configuration are not subject to AMR. Therefore, these components are excluded from Table 3-1 below.

uontroioea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-3 3.1.2.2 RVlnternals Welds Table 3-2 below details the comparison of the D-B RV internals welds to the MRP-1 89, Revision 1 Table 4-2 items. The D-B AMR document does not explicitly identify all welds used to fabricate the internals (as detailed in Table 4-2 of MRP-189, Revision 1). Therefore, the following process was used to identify the specific D-B welds for comparison. First, any specific weld described in the D-B AMR document was identified in Table 3-2 adjacent to the equivalent MRP-189, Revision 1 weld. Next, an assumption was made that specific assembly descriptions in the D-B AMR document included the relevant fabrication welds. For example, the D-B AMR document identifies the "plenum cylinder assembly" as a component within the scope of license renewal and subject to AMR. This document assumes that this line item includes all relevant fabrication welds for the plenum cylinder assembly (WC-34, WC-37, WC-66, WC-1 31, and WC-132). Finally, a fabrication records search of the D-B reactor vessel internals was completed in 2006 for use during the preparation of MRP-1 89, Revision 1. The search reviewed D-B internals fabrication records including weld data sheets, quality assurance data packages, and fabrication process travelers. The results of that fabrication records search were used to identify the D-B specific welds during the comparison to MRP-1 89, Revision 1 Table 4-2.

3.1.2.3 RV Internals Bolting In response to industry and site experience, D-B has replaced the majority of the precipitation hardenable (PH) stainless steel (SS) (Alloy A-286) bolts for the reactor vessel internals. All the lower thermal shield (LTS) bolts were replaced with Alloy X-750 bolts in the hot-rolled, high temperature annealed and aged condition (HTH). Most of the original surveillance specimen holder tube (SSHT) bolts (68 of 72 bolts) were replaced with Alloy X-750 HTH bolts (with stainless steel locking devices). The remaining four original SSHT bolt locations no longer have a functional bolt. For the upper and lower core barrel bolts, only partial replacements with the Alloy X-750 HTH bolts were completed (117 of 120 upper core barrel (UCB) and 60 of 108 lower core barrel (LCB) bolts). It should be noted that, while three original UCB bolts remain, their original locking devices were replaced and are no longer in service. The original locking devices for the 48 remaining LCB bolts remain in service.

uonroiaea uocumern AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-4 In addition, each replacement bolt (for the UCB, LCB, LTS, and SSHT) utilized a nickel-based alloy (Alloy X-750) cylindrical compression collar in the bolt design. This compression collar served to maintain the bolt pre-load during service to account for differences in thermal expansion coefficients between the Alloy X-750 bolt material and the stainless steel RV internals components. While these compression collars are not explicitly included in Table 4-1 of MRP-1 89, Revision 1, for the comparison below these items are assumed to be included with the Alloy X-750 bolting itself.

The D-B AMR document lists "locking clip" as part of the Lower Grid Assembly. Following the replacement of the LTS bolts along with the associated locking devices (as discussed above),

locking clips are no longer used as part of the Lower Grid Assembly. Therefore, "locking clips" are not included in the Lower Grid Assembly section of Table 3-1. (Note: the original LCB bolt locking clips are included in the Core Barrel Assembly section of Table 3-1.)

3.1.2.4 Surveillance Specimen Holder Tubes As stated in Section 3.3 of MRP-189, Revision 1, the SSHT assemblies were specifically excluded from the screening performed in MRP-1 89, Revision 1 due to the plant-specific changes to the assemblies. The SSHT assemblies are in service at D-B; however, as described in Section 2.3.1.2 of the D-B License Renewal Application, the SSHT assemblies were determined to not perform a safety function (as described in Section 3.1.1 of this document) and, therefore, are not subject to AMR [5]. The NRC concluded that D-B appropriately identified all reactor vessel internals components within the scope of license renewal in Section 2.3.1.2.3 of their SER [1]. Therefore, the SSHT components are not subject to AMR and are not screened further in this document.

3.1.2.5 Plenum Cylinder Reinforcement Casting In Section 2.3.2 and Table 3-2 of MRP-189, Revision 1, the plenum cylinder reinforcing plates are described as thick stainless steel (ASTM A 240, Type 304) plates welded to the inner surface of the plenum cylinder with a set of small round bars or lugs welded to the plate outer surface to ensure an acceptable coolant flowpath during design basis transients. As described in the D-B AMR document, the D-B plenum cylinder reinforcement plate is a different material than the reinforcement plates in the other B&W designed units as described in MRP-189,

uontrooiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paqe 3-5 Revision 1. For D-B, a stainless steel casting (ASTM A 351, Grade CF-8) with the lugs integrally cast with the plate is welded directly into the plenum cylinder. Therefore, the specific D-B material type for this component is not consistent with material type defined for this component in MRP-189, Revision 1. However, this component had been previously screened, and it was determined that the delta ferrite content of these castings is less than 13%, which is below the 20% delta ferrite screening value in MRP-175 for thermal aging embrittlement.

Therefore, this would result in the component being placed with the Category "A" items during the screening process in MRP-189. As such, no additional evaluations are required. This is consistent with Item 14 in Table 3-1 below.

3.1.2.6 Lower Grid Guide Blocks The original attachment method for the guide blocks to the lower grid was with a washer and bolt assembly that were welded to each other and the guide block and an Alloy X-750 dowel that was similarly welded to the guide block. This design is reflected in MRP-1 89, Revision 1.

However, subsequent to original hot functional testing, D-B modified the guide block attachment on the lower grid assembly. The bolts, washers, and dowels (along with the welds) were removed, and the dowels were replaced with Alloy A-286 dowels that were welded to the guide blocks. The guide block was welded to the lower grid with a continuous fillet weld. Therefore, Table 3-1 below reflects that the guide block bolting has been removed from service and the actual dowel in service is fabricated of stainless steel material. Table 3-2 reflects that the bolting welds and the nickel-alloy weld to the Alloy X-750 dowel have been removed from service. The additional welds on the modified D-B guide blocks and on the dowel are included in Table 3-2.

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-6 Table 3-1: Comparison of D-B RV Internals License Renewal Scope to MRP-189 Revision 1 Component Items MRP-190 MRP-189 Component Item Item D-B RV Internals Component Item Reference Identifier (MRP-189 Table 4-1) [3]

Plenum Cover Assembly 1 Weldment Rib D-B AMR P.1.1 Weldment Ribs Document 2 Rib Pad D-B AMR Document P.1.2 Weldment Rib Pads 3 Flnge0-B Botom AMR 3 Bottom Flange Document P.1.3 Bottom Flange 4 Support Flange D-B AMR Document P.1.4 Support Flange 5 ing0-B Suport AMR 5 Support Ring Document P.1.5 Support Ring 6 Plate D-B AMR P.1.6 Cover Plate Document 7 Lifting Lug D-B AMR P.1.7 Lifting Lugs Document 8 Block D-B AMR Document P.1.8 Base Block for Lifting Lugs 9 Lifting Lug to Base Block Bolts DocuMR P.1.9 Lifting Lug to Base Block Bolts Liftng Bas Blck Lg BltsDocument t

10 Locking Cup 1u D-B AMR Document P.1.10 Locking Cups

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-7 MRP-19 MRP-189 Component Item Item D-B RV Internals Component Item Reference RP-190 M C Identifier (MRP-189 Table 4-1) [3]

Plenum Cylinder Assembly 11 Cylinder D-B AMR P.2.1 Cylinder Document 12 Top Flange D-B AMR Document P.2.2 Top Flange 13 Bottom Flange D-B AMR P.2.3 Bottom Flange Document 14 Reinforcing Plate D-B AMR Refer to Section 3.1.2.5 Document 0-B AMR 15 Top Flange to Cover Bolts Document P.2.6 Top Flange to Cover Bolts 16 Locking Cup D-B AMR P.2.7 Locking Cups Document 0-B AMR 17 Bottom Flange to Upper Grid Screw Document P.2.8 Bottom Flange to Upper Grid Bolts 18 Locking Cup D-B AMR Document P.2.9 Locking Cups Upper Grid Assembly 19 Rib Section D-B AMR P.3.1 Rib Section Document 0-B AMR 20 Fuel Assembly Support Pad Document P.3.5 Fuel Assembly Support Pads 21 Dowel D-B AMR P.3.6 Dowels Document 22 Cap Screw D-B AMR P.3.7 Cap Screws Document

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-8 MRP-190 MRP-189 Component Item Item D-B RV Internals Component Item Reference Idet19e MRP-189 Table4 t[3 Identifier (MRP-189 Table 4-1) [3]

23 Ring Forging D-B AMR P.3.2 Ring Forging Document 24 Rib to Ring Screw D-oc AMR P.3.3 Rib to Ring Cap Screws Document 25 Lock Pin D-B AMR Document P.3.4 Locking Pins Control Rod Guide Tube (CRGT) Assembly 26 CRGT Pipe D-B AMR P.4.1 Pipe Document 27 CRGT Flange D-B AMR Document P.4.2 Flange 0-B AMR 28 Flange to Upper Grid Screw Document P.4.3 Flange to Upper Grid Cap Screws 29 Dowel DocumentFlange D-B AMR Document P.4.4 Dowels 0-B AMR 30 CRGT Spacer-Casting Document P.4.5 Spacer Castings D-B AMR 31 Spacer Casting Screw Document P.4.6 Spacer Casting Cap Screws D-B AMR 32 Spacer Casting Washer Document P.4.7 Spacer Casting Washers D-B AMR 33 CRGT Rod Guide Tube DocuMe Document P.4.8 Rod Guide Tubes 0-B AMR 34 CRGT Rod Guide Sector DocuMe Document P.4.9 Rod Guide Sectors

ANP-3359NP AREVA Inc.

Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-9 Item D-B RV Internals Component Item cRP-1e89 eMRP-190 Component Item Reference Identifier (MRP-189 Table 4-1) [3]

Core Support Shield (CSS) Assembly D-B AMR 35 Core Support Shield Cylinder Document S.1 Cylinder 36 Top Flange D-B AMR S.2 Top Flange Document 37 Bottom Flange D-B AMR Document S.3 Bottom Flange 0-B AMR 38 Upper Core Barrel Bolts (original) Document S.4a UCB: Original A-286 CSS to Core Barrel Bolts 39 Core Support Shield to Core Barrel (UCB) D-B AMR S.d UCB: Replacement X-750 CSS to Core Barrel Bolts - Replacement Document Bolts 40 Not in service S.5a Locking Clips (Locking Devices for Original UCB Refer to Section 3.1.2.3 Bolts) 0-B AMR 41 UCB Bolts Locking Devices (Replacement) Document S.5b Locking Cups and Washers 0-B AMR 42 UCB Bolts Locking Devices (Replacement) Document S.5c Tie Plates 43Nozzle Outlet D~~-B AMR S6 atOte oze 44 CSS Mounting Rings D-B AMR Document S.7 Vent Valve Nozzles 0-B AMR 45 Vent Valve Guide Block DocuMe S.8 Vent Valve Nozzles Guide Blocks Document 46 Vent Valve Assembly D-B AMR Document S.9 Vent Valve Body

ANP-3359NP AREVA Inc.

Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-10 MRP-190 MRP-189 Component Item Item D-B RV Internals Component Item Reference IRet19e MRP-189 Table4)[m Identifier (MRP-189 Table 4-1) [3]

47 Vent Valve Top Retaining Ring D-B AMR Document S.10 Vent Valve Top Retaining Ring 0-B AMR 48 Vent Valve Bottom Retaining Ring Document S.10 Vent Valve Bottom Retaining Ring 49 Vent Valve Assembly D-B AMR S.1 Vent Valve Jack Screws Document 50 Vent Valve Assembly D-B AMR Document S.13 Disc Bushing Vent Valve Assembly (Original Vent Valve D-B AMR No corresponding component items included in Miscellaneous Locking Device Parts) Document MRP-189, Revision 1 for D-B 52 Round Bar D-B AMR Document S.15 Round Bars 53 Flow Deflector D-B AMR Document S.16 Flow Deflectors 54 LitingLug0-B AMR 54 Lifting Lug Document S.17 Lifting Lugs Core Barrel Assembly 55 Core Barrel Cylinder D-B AMR Document B.1 Core Barrel Cylinder 56 Top Flange Document D-BocMe B2TpFag B.2 Top Flange 57 Bottom Flange D-B AMR Document B.3 Bottom Flange 58 Lower internals assembly to core barrel D-B AMR B.4a LCB: Original A-286 Lower Grid Assembly to Core (LCB) bolts - original Document Barrel Bolts

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-11 MRP-190 MRP-189 Component Item Item D-B RV Internals Component Item Reference MRet1ie MRP-189 Table4 t[1 Identifier (MRP-1 89 Table 4-1) [3]

59 Lower internals assembly to core barrel D-B AMR B.4d LCB: Replacement X-750 Lower Grid Assembly to (LCB) bolts - replacement Document Core Barrel Bolts LCB Bolts (Original) Locking Devices D-B AMR B.5a Locking Clips 60 (Locking Clip) Document 61 LCB Bolts (Replacement) Locking Devices D-B AMR B.5b Tie Plates (Locking Cup) Document LCB Bolts (Replacement) Locking Devices D-B AMR B.5b Locking Cups 62 (Tie Plate) Document 0-B AMR 63 Core barrel to thermal shield (UTS) bolts Document B.6a UTS: A-286 Thermal Shield to Core Barrel Bolts D-B AMR 64 UTS Bolts Locking Devices (Locking Clips) Document B.7 Locking Clips D-B AMR 65 SSHT Bolts (Replacement) Document B.8b X-750 Replacement SSHT to Thermal Shield Bolts 66 SSHT Replacement Bolts Locking Devices D-B AMR B.9 Replacement SSHT to Thermal Shield Bolts (Locking Cup and Tie Plate) Document Locking Cups and Tie Plates 67 Thermal Shield D-B AMR B.10 Thermal Shield Cylinder Document 0-B AMR 68 Thermal Shield Upper Restraint "A" and "B" DocuMe Document B.1 1 Thermal Shield Upper Restraint "A"and "B" Blocks 69 Thermal Shield Upper Restraint Shims AREVA Drawing B.12 Thermal Shield Upper Restraint Shims 70 Hardfacing AREVA Drawing B.13 Thermal Shield Upper Restraint Hardfacing ("A" and "B" Blocks) 71 Plug AREVA Drawing B.14 Thermal Shield Upper Restraint Upper Plugs

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-12 Item D-B RV Internals Component Item Reference MRP-190 MRP-189 Component Item Identifier (MRP-189 Table 4-1) [3]

72 Thermal Shield Restraint Dowel D-B AMR DouetB.15 Thermal epsd Shield Upper Restraint Dowels (not

Document exposed)

Thermal Shield Upper Restraint Cap Screw D-B AMR Thermal Shield Upper Restraint Cap Screws (not Document exposed) 74 Baffle Plate D-B AMR Document B.17 Baffle Plates 75 Formers D-B AMeR Document B.18 Former Plates D-B AMR 76 Barrel to Former Bolts Document B.19 Core Barrel to Former Plate Cap Screws 77 Locking Pin D-B AMR Document B.20 Locking Pins 78 Alloy X-750 Core Barrel-to-Former Plate D-B AMR B.21 Core Barrel to Former Plate Dowels Dowel Document 79 Baffle to Former Bolts DocuMR B.22 Baffle to Former Hex head Bolts (except F4)

Baffl oltsDocument to Frmer 82 80 Locking Pin D-B AMR Document B.23 Locking Pins D-B AMR 81 Baffle to Former Shoulder Screws Document B.24 Baffle to Former Shoulder Screws (F4) 82 Locking Dowel D-B AMR Document B.25 Locking Dowels 83 Baffle to Baffle Bolts D-B AMR B.26 Baffle to Baffle 12 Pt Bolts Document 84 Locking Ring D-B AMR Document B.27 Locking Rings

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-13 Item D-B RV Internals Component Item Reference MRP-190 MRP-189 Component Item Identifier (MRP-189 Table 4-1) [3]

Lower Grid Assembly 0-B AMR 85 Lower Grid Rib Section DocuMe Document L.1.1 Lower Grid Rib Section 0-B AMR 86 Fuel Assembly Support Pad Document L.1.2 Lower Grid Fuel Assembly Support Pad 87 Dowel D-B AMR Document L.1.3 Dowels 88 Cap Screw D-B AMR Document L.1.4 Cap Screws 89 Cap Screw D-B AMR Document L.1.5 Rib to Shell Forging Cap Screws 90 Locking Pin D-B AMR Document L.1.6 Locking Pins 91 Lower Grid Flow Distributor Plate D-B AMR L.1.7 Lower Grid Flow Distributor Plate Document 92 Orifice Plug D-B AMR Document L.1.8 Orifice Plugs 93 Lower Grid Forging D-B AMR L.1.9a Lower Grid Forging Document 94 Lower Grid Flange D-B AMR Document L.1.10 Lower Grid Shell Forging 95 Lower Internals Assembly to Thermal Shield D-B AMR L.1.1 1c LTS: Replacement X-750 Lower Grid Assembly to (LTS) Bolts Document Thermal Shield Bolts 96 LTS Replacement Bolt Locking Device D-B AMR L.1.12 Locking Cups

____(Locking Cup) Document I..2LcigCp

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-14 MRP-190 MRP-189 Component Item Item D-B RV Internals Component Item Reference Mdeti9e MRP-189 Taboe Item Identifier (MRP-189 Table 4-1) [3]

97 LTS Replacement Bolt Locking Device (Tie D-B AMR L.1.12 Tie Plates Plate) Document 98Bock0-B Gude AMR 98 Guide Block Document L.1.13 Guide Blocks (mating with Guide Lugs on RV)

Not in service L.1.14a, 99Section 3126 L.1.14b, Guide Block Bolts, Washers, and Dowels Referto SeL.1.15 100 Dowel Cap D-B AMR No corresponding component items included in Document MRP-189, Revision 1 for D-B D-B AMR No corresponding component items included in Document MRP-1 89, Revision 1 for D-B 102 Shock Pad D-B AMR L.1.16a&b Shock Pads Document 103 Shock Pad Bolt D-B AMR Document L.1.17a Bolts 104 Support Post Pipe D-B AMR L.1.18 Support Post Pipes Document 105 Bolting Plug Document L.1.19 Bolting Plugs 0-B AMR 106 Support Post Cap Screw Document L.1.20 Cap Screws 107 LckingPin0-B AMR 107 Locking Pin Document L.1.21 Locking Pins Flow Distributor Assembly 108 Flow Distributor Head D-B AMR Document L.2.1 Flow Distributor Head I

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-15 Item D-B RV Internals Component Item Reference MRP-190 MRP-189 Component Item Identifier (MRP-189 Table 4-1) [3]

D-B AMR 109 Flow Distributor Flange Document L.2.2 Flow Distributor Flange 110 Shell Forging to Flow Distributor Bolts D-B AMR DouetL2.3aFognBlt FD: A-286 Flow Distributor to Lower Grid Shell Document Forging Bolts 111 Locking Clip D-B AMR L24 Locking Clips Document D-B AMR 112 Incore Guide Support Plate Document L.2.5 IMI Guide Support Plate 113 Clamping Ring D-B AMR Document L.2.6 IMI Guide Support Plate Clamping Ring 114 owelD-B AMR 114 Dowel Document L.2.7 IMI Guide Support Plate Dowel Incore Monitoring Instrumentation (IMI) Guide Tube Assembly 115 Incore Guide Tube D-B AMR Document L.3.1 IMI Guide Tubes 116 Gusset D-B AMR L.3.2 IMI Guide Tube Gussets Document 117 Guide Tube Washer D-B AMR Document L.3.3 IMI Guide Tube Washers 118 Guide Tube Nut D-B AMR Document L.3.4 IMI Guide Tube Nuts 119 Locking Clip D-B AMR Document L35 Locking Clips 120 Spider D-B AMR Document L.3.6 IMI Guide Tube Spider Castings

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-16 Table 3-2: Comparison of D-B RV Internals License Renewal Scope to MRP-189 Revision 1 Welds Item D-B RV Internals Weld Item Reference Weld ID MRP-189 Weld Description MRP-190 R(MRP-189 Table 4-2) [3] Component IlDs Core Barrel Assembly Core barrel cylinder (including D-B AMR Top and bottom core barrel cylinders to top B.1, B.2, and 1 vertical and circumferential seam Document WC-1 1 and bottom core barrel flanges B.3 welds) circumferential seam weld 2 Thermal shield assembly D-B AMR WC-12 Top and bottom thermal shield cylinder B.10 Document vertical seam weld D-B AMR Top thermal shield cylinder to bottom 3 Thermal shield assembly Document WC-13 thermal shield cylinder circumferential seam B.10 weld 4 Inaccessible locking device and D-B AMR WC-15 Core barrel-to-former plate cap screw B.19 and B.1 locking weld (CBF bolts) Document locking pin to core barrel cylinder weld 5 Accessible locking device and D-B AMR WC-15 Baffle-to-former bolt locking pin to baffle 8.23 and 8.17 locking weld (FB bolts) Document plate weld Accessible locking device and D-B AMR Baffle-to-baffle bolt locking ring to baffle 6 locking weld (internal and external Document WC-16 plateB.27 and B.17 BB bolts) Documentplateweld Core barrel cylinder (including D-B AMR Core barrel top and bottom cylinder vertical 7 vertical and circumferential seam Document WC-20 Ce bel B. 1 welds) seam weld Core barrel cylinder (including D-B AMR Core barrel top cylinder to core barrel 8 vertical and circumferential seam WC-21 B.1-welds) Document bottom cylinder circumferential seam weld 9 Core barrel assembly D-B AMR WC-94 Plug weld locking dowel flush with special B.24 and B.25 Document flat head baffle-to-former shoulder screw 10 Alloy X-750 dowel-to-core barrel D-B AMR WC-130 X-750 dowel to top and bottom core barrel B.1 cylinder fillet welds Document cylinders fillet weld

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-17 MRP-1 89 Weld Description MRP-1 90 Item D-B RV Internals Weld Item Reference Weld ID MRP-189 Tale MPoet0 (MRP-189 Table 4-2) [3] Component IDs Lower core barrel (LCB) bolts D-B AMR L 11 (original) and their locking devices D WC-141 ocking clip (for original LCB bolt) to lower B.6a and L.1.10 I (locking clip weld) Document grid shell forging weld 12 Alloy X-750 dowel to core barrel D-B AMR WC-164 X-750 dowel to core barrel cylinder weld B.1 cylinder fillet welds Document (both ends) 13 Thermal shield assembly D-B AMR Plug dowel to thermal shield upper restraint B.15 and B.11 Document WCF-220 "A" weld Core Support Shield Assembly 14 Thermal shield assembly WCF-176 Locking clip (for original UTS bolts) to S.5a and B.11 Document thermal shield upper restraint "A" weld 15 Core support shield cylinder D-B AMR WC-43 Core support shield cylinder to top and S.1, S.2, and S.3 Document bottom flange circumferential seam weld 16 Core support shield cylinder D-B AMR WC-44 Core support shield cylinder to vent valve S.1 and S.7 Document nozzle weld

.17 Core support shield cylinder D-B AMR Core support shield cylinder to vent valve S.1 and S.

Document nozzle weld (opposite WC-44) S.1_andS.7 18 Core support shield cylinder D-B AMR WC-46 Core support shield cylinder to outlet nozzle S.1 and S.6a&b Document weld 19 Core support shield cylinder D-B AMR Document WC-47 Core support shield WC-46) cylinder to outlet nozzle S.1 and S.6a&b fillet weld (opposite 20 dflecorD-B Fow AMR 20 Flow deflector Document WC-48 Flow deflector (U-baffle) segments weld S.16 21 Core support shield cylinder D-B AMR Core support shield lifting lug to top flange S.17 and S.2 Document WC-49 weld 22 Core support shield cylinder WC-50 Core support shield lifting lug to top flange S.17 and S.2 Document weld (opposite WC-49) I _I

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-18 MRP-189 Weld Descri ption MRP-190 Item D-B RV Internals Weld Item Reference Weld ID Tale4-2) [3]

MRP-189 Table MPoet0 (MRP-189 Component IDs 23 Core support shield cylinder D-B AMR WC-51 Core support shield cylinder vertical seam SA Document C-1 weld 24 Core support shield cylinder D-B AMR Round (LOCA) bars to core support shield S.15 and S.1 Document cylinder ID surface weld 25 Core support shield assembly D-B AMR WC-53 Flow deflector (U-baffle) to core support S.16 and S.1 Document shield cylinder weld 26 Core support shield assembly D-B AMR WC-105 Guide block to core support shield vent S.8 and S.7 Document nozzle fillet weld 27 Core support shield assembly D-B AMR WCF-264 Locking clip (for original UCB A-286 bolts) S.5a and S.3 Document to core support shield bottom flange weld 28 Core support shield assembly D-B AMR WCF-265 Locking clip (for original UCB A-286 bolts) S.5a and S.3 Document to core support shield bottom flange weld CRGT Assembly 29 Control rod guide tube assembly D-B AMR WC-40 Washer to CRGT pipe and spacer bolt weld P.4.7 and P.4.1 Document (WC-64 for top spacer) 30 Control rod guide tube assembly D-B AMR WC-41 CRGT flange to CRGT pipe weld (all around P.4.2 and P.4.1 Document except at the 4 scallops)

D-B AMR 31 Control rod guide tube assembly Document WC-42 Type 304 dowel to CRGT flange weld P.4.4 and P.4.2 32 Control rod guide tube assembly D-B AMR WC-64 Washeto CRGT pipe and spacer bolt weld P.4.7 and P.4.1 Document (also see WC-40)

D-B AMR 33 Control rod guide tube assembly Document WC-65 CRGT pipe to plenum cover plate weld P.4.1 and P.1.6 34 Control rod guide tube assembly D-B AMR WC-67 CRGT flange cap screw (oining upper grid P.4.3 and P.4.2 Document rib section) to CRGT flange weld

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-19 Item D-B RV Internals Weld Item Reference Weld ID MRP-189 Weld Description MRP-190 I (MRP-189 Table 4-2) [31 Component IDs Flow Distributor Assembly 35 Flow distributor assembly D-B AMR WC-57 Flow distributor flange to flow distributor L.2.2 and L.2.1 Document head circumferential seam weld 36 Alloy X-750 dowel to flow distributor D-B AMR WC-58 X-750 dowel to flow distributor flange weld L.2.2 36 flange welds Document 37 D-B AMR WC-60 Flow distributor (FD) bolt locking clip to flow L.2.4 and L.2.2 Flow distributor assembly Document distributor flange weld 38 Clamping ring D-B AMR WC-157 IMI guide support plate clamping ring L.2.6 Document vertical seam weld D-B AMR WC-161 Dowel (for clamping ring) to flow distributor L.2.7 and L.2.2 39 Flow distributor assembly Document flange weld IMI Guide Tube Assembly 40 D-B AMR WC-158 Incore instrument guide tubes (center) to L.3.1 and L.2.1 Flow distributor assembly Document flow distributor head weld 41 Incore guide tube assembly D-B AMR WC-158 Incore instrument guide tubes (peripheral) L.3.1 and L.2.1 Document to flow distributor head weld D-B AMR WC-159 Incore instrument guide tubes (center) to L.3.1, L.2.1, and 42 Incore guide tube assembly Document flow distributor head and gusset weld L.3.2 43 riblisectionuewspider to lower grid DocumentR WC-160 Spider to lower grid rib section weld L.3.6 and L.1.1 44 Incore guide tube assembly D-B AMR WC-187 Nut locking clip to incore instrument guide L.3.5 and L.3.4 Document tube nut weld 45 0noegietueasml

-B AMR W-88 Nut locking clip to incore instrument guide L.3.5 and L.3.1 Increguie ub asemlyDocument tube weld IC18

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-20 Item D-B RV Internals Weld Item Reference Weld ID RP-189 Weld Description MRP-190 (MRP-189 Table 4-2) [3] Component IDs Lower Grid Assembly 46 Alloy X-750 dowel to lower grid 0-B AMR sheAllfori shell forging weldsd X-75 welds DoAMet Document WC-4 X-750 dowel to lower grid shell forging weld L.1.10 0-B AMR 47 Lower grid assembly Document WC-5 Support post to lower grid forging weld L.1.18 and L.1.10 48 Lower grid assembly D-B AMR WC-8 Lower grid forging (or weldment) to lower L.1.9a&b and Document grid shell forging weld L.1.10 49 Lower grid assembly D-B AMR WC-26 Flow distributor plate to lower grid shell L.1.7 and L.1.10 Document forging weld 50 Lower grid assembly D-B AMR Document WC-27 Support post to flow distributor plate weld L.1.18 and L.1.7 Lower fuel assembly support pads: 0-B AMR 51 cap screw and associated locking Document WC-59 Cap screw to lower fuel assembly pad weld L.1.4 and L.1.2 weld Document 0-B AMR 52 Lower grid assembly Document WC-97 Bolting plug to support post weld L.1.19 and L.1.18 53 Alloy X-750 dowel to lower grid rib 0-B AMR section X weld dweld section DoAMet Document WC-98 X-750 dowel to lower grid rib section weld L.1.3 and L.1.1 54 Lower grid assembly D-B AMR WC-99 Locking pin (for lower grid rib section cap L.1.6 and L.1.1 Document screw) to lower grid rib section weld 55 Lower grid assembly D-B AMR WC-100 Locking pin (for lower grid support post cap L.1.21 and L.1.1 Document screw) to lower grid rib section weld 0-B AMR L.1.17a and 56 Lower grid assembly Document WC-101 Shock pad bolt to shock pad fillet weld L.1.16a&b

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Pa~ge 3-21 MRP-189 Weld Description MRP-190 Item D-B RV Internals Weld Item Reference Weld ID MRP-189 Tale MPoet0 (MRP-1 89 Table 4-2) [3] Component IDs Lower grid guide block to lower grid D-B AMR No corresponding component items 57 assembly weld (See Section Document included in MRP-189, Revision 1 for 0-B 3.1.2.6) ninlddiP-8,R 1cm vso 1frD-58 Lower grid assembly D-B AMR WC-142 Lower grid forging (or weldment) to lower L.1.9a & b and Document grid shell forging weld L.1.10 0-B AMR 59 Lower grid assembly Document WC-142 Support post to flow distributor plate weld L.1.18 and L.1.7 60 Lower grid assembly D-B AMR WC-142 Flow distributor plate to lower grid shell L.1.7 and L.1.10 Document forging weld 61 Lower fuel assembly support pads: D-B AMR WC-173 Fuel grid pad to lower grid rib section weld L.1.2 and L.1.1 pad to rib section weld Document 0-B AMR 62 Lower grid flow distributor plate Document WC-240 Orifice plugs to flow distributor plate weld L.1.8 and L.1.7 63 Not in service D-B AMR WCF-103 Guide block bolt washer to guide block weld L. 1.14b, L.1.15, Refer to Section 3.1.2.6 Document WCF-1 04 X-750 dowel to guide block weld and L. 1.13 Lower grid assembly: Alloy A-286 0-B AMR No corresponding component items 64 dowel to guide block welds (See Document included in MRP-189, Revision 1 for 0-B Section 3.1.2.6) _ocumentincludedinM_-189,_Revision_1_forD-Lower grid assembly: Alloy X-750 0-B AMR X-750 dowel to lower fuel assembly pad 65 dowel-to-lower fuel assembly Document WC-3 weldL.1.2 and L.1.3 support pad welds Plenum Cover Assembly 0-B AMR Two plenum cover support ring segments to 66 Plenum cover assembly Document WC-18 form a complete plenum cover support ring P.1.5 weld 67 Plenum cover assembly D-B AMR WC-19 Plenum cover support ring to plenum cover P.1.5 and P.1.4 Document support flange weld

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Pagqe 3-22 MRP-189 Weld Description MRP-190 Item D-B RV Internals Weld Item Reference Weld ID MRP-189 Tale MPoet0 (MRP-189 Table 4-2) [3] Component IDs D-B AMR Plenum cover weldment ribs to each other 68 Plenum cover assembly Document WC-28 weld P.1.1 69 Plenum cover assembly D-B AMR WC-29 Plenum cover weldment ribs to support ring P.1.1, P.1.4, and Document and support flange weld P.1.5 70 Plenum cover assembly D-B AMR WC-30 Plenum cover bottom flange to plenum P.1.3 and P.1.1 Document cover weldment ribs weld 71 Plenum cover assembly D-B AMR WC-31 Plenum cover plate to plenum cover P.1.6 and P.1.1 Document weldment ribs weld 72 Alloy X-750 dowels to plenum cover D-B AMR WC-33 X-750 dowels to plenum cover bottom P.1.3 bottom flange welds Document flange weld 73 Plenum cover assembly D-B AMR WC-75 Locking cup (for plenum cover lifting lug P.1.10 and P.1.8 Document bolt) to lifting lug base block weld 0-B AMR Plenum cover support ring to plenum cover 74 Plenum cover assembly Document WC-124 support flange (WC-124 on the ID side, WC- P.1.5 and P.1.4 19 on the OD side) weld 75 Plenum cover assembly D-B AMR WC-126 Plenum cover support flange to the bottom P.1.4 and P.1.1 Document of plenum cover weldment ribs weld 76 Plenum cover assembly D-B AMR WC-127 Plenum cover lifting lug base block between P.1.8 and P.1.1 Document 2 plenum cover weldment ribs weld 77 Plenum cover assembly D-B AMR WC-128 Plenum cover lifting lug base block between P.1.8 and P.1.1 Document 2 plenum cover weldment ribs weld 78 Plenum cover assembly D-B AMR WC-129 Plenum cover lifting lug base block between P.1.8 and P.1.1 Document 2 plenum cover weldment ribs weld 79 Plenum cover assembly D-B AMR WC-133 Plenum cover rib pads to plenum cover P.1.2 and P.1.1 P Document weldment rib weld

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-23 Item D-B RV Internals Weld Item Reference Weld ID MRP-189 Weld Description MRP-190 (MRP-189 Table 4-2) [3] Component IlDs 80 Plenum cover assembly D-oc AMR WC-142 Plenum cover plate to the top of plenum P1.6 and P1.1 Document cover weldment rib weld 81 Plenum cover assembly D-B AMR Plenum cover weldment rib to the other P.1.1 Document WC-142 weldment rib weld 82 Plenum cover assembly D-B AMR WC-142 Plenum cover rib pads to plenum cover P.1.2 and P.1.5 Document support ring weld Plenum Cylinder Assembly 83 Plenum cylinder assembly D-B AMR WC-34 Plenum cylinder to top and bottom plenum P.2.1, P.2.2, and Document cylinder flanges circumferential seam weld P.2.3 84 Plenum cylinder assembly D-B AMR WC-34 Plenum cylinder bottom flange to P.2.3 and P.2.4 Document reinforcement weld 85 Plenum cylinder assembly D-B AMR Document WC-37 Plenum cylinder vertical seam weld P21 D-B AMR Locking cup (for bolts joining plenum 86 Plenum cylinder assembly Document WC-66 cylinder top flange to plenum cover bottom P.2.7 and P.2.2 flange) to plenum cylinder top flange weld Locking cup (for bolts joining plenum 87 Plenum cylinder assembly D-B AMR WC-66 cylinder bottom flange to upper grid ring P.2.9 and P.2.3 Document forging) to plenum cylinder bottom flange weld 88 Plenum cylinder assembly D-B AMR WC-131 Plenum cylinder reinforcement to plenum P.2.4 and P.2.1 Document cylinder weld 89 Plenum cylinder assembly D-B AMR WC-132 Plenum cylinder reinforcement to plenum P.2.4 and P.2.1 Document cylinder weld (opposite WC-1 31 weld)

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-24 MRP-189 Weld Description MRP-190 Item

____i D-B RV Internals Weld Item Reference eeec Weld ed ID MRP-189 Wele (MRP-189 Table 4-2) [31 TComponent mpoe90 IDs Upper Grid Assembly 90 Upper grid assembly D-B AMR Cap screw to upper grid fuel assembly P.3.7 and P.3.5 Document WC-23 support pad weld D-B AMR Locking pin (for cap screw to joining upper 91 Upper grid assembly Document WC-95 grid rib section to upper grid ring forging) to P.3.4 and P.3.1 upper grid rib section weld 92 Upper grid assembly D-B AMR WC-173 Fuel assembly support pad to upper grid rib P.3.5 and P.3.1 Document section weld 93 Alloy X-750 dowel to upper grid rib D-B AMR WC-96 X-750 dowel (for alignment) to upper grid rib P.3.1 section bottom flange welds Document section weld

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paqie 3-25 3.2 Component Item Comparison As illustrated in Table 3-1, the component items that are included in the scope of license renewal and subject to AMR for D-B, but are not included in MRP-1 89, Revision 1, are the vent valve miscellaneous locking device parts (Table 3-1, Item 51) and the items (Table 3-1, Items 100 and 101) and welds (Table 3-2, Items 57 and 64) associated with the lower grid guide block attachment replacement. Note that even though the lower grid guide blocks (Table 3-1, Item

98) were screened as part of MRP-1 89, Revision 1, these guide blocks were modified in that they were welded to the lower grid and, therefore, need to re-screened.

3.2.1 Vent Valve Locking Device D-B has four vent valves installed in the core support shield (CSS) cylinder to a vent valve mounting ring (also called vent valve nozzle) that is welded into the CSS cylinder (refer to Figure 3-1, Figure 3-2, and Figure 3-3). 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). Refer to Figure 3-4 for an illustration of the miscellaneous locking devices that secure the split-retaining ring into the vent valve nozzle. Vent valve component parts, including the disc, are designed to minimize the possibility of lost parts to the reactor coolant system, and therefore, 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 reactor vessel inside wall without transmitting excessive impact loads to the hinge parts as a result of a loss of coolant accident. The hinge assembly consists of a shaft (hidden by cover plates), 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 swing check vent valves are meant to relieve pressure in the interior of the core support shield assembly during a large break loss of coolant accident (LOCA), preventing backpressure from reversing coolant flow through the core and limiting emergency core cooling flow into the core. For all normal operating conditions, the vent valve is closed. In the event of a rupture of

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-26 the reactor vessel 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 reactor vessel. Therefore, the vent valves are passive devices that have no function during normal operation. However, degradation of the vent valve locking device parts may either prevent the vent valve from fully closing under normal operating conditions (causing increased bypass flow) or from fully opening under the required accident conditions.

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. It is relevant to note that the D-B four RV internals vent valves are not located near the outlet nozzles. Proximity to the outlet nozzles has been identified as a driving factor in the initiator of the component wear due to flow induced vibrations. In addition, a review of the D-B site Spring 2010 outage vent valve video indicates that all four of the D-B vent valves have the original locking devices and that no repair or replacement was completed on these components.

uonroiieci uocurnen AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-27 Finge shell valve Body-L"9 RttahibkV Ring Mouflng - DWs Rting COre StUPclt Sectin Z-Z Figure 3-1: Vent Valve Assembly Figure 3-2: Typical Vent Valve (External Core Support Shield View)

uontro;'e uocurnent AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-28 Figure 3-3: Typical Vent Valve (Inside Core Support Shield View)

Figure 3-4: Original Vent Valve Locking Device Miscellaneous Parts

uontroiea vocumenti AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-29 3.2.2 Lower Grid Guide Block Attachment Replacement The lower grid guide assembly includes twelve sets of guide blocks located equidistant around the periphery of the outside vertical wall of the lower grid shell forging. These blocks function to provide precision clearances with the reactor vessel guide lugs that are welded to the inside wall of the reactor vessel. Refer to Figure 3-5 for an illustration of the lower grid guide block assembly. As described in Section 3.1.2.6, following hot functional testing, the D-B lower grid guide block attachment was modified after it was determined that the testing had caused guide blocks to become loose and out of position. The lower grid guide block attachment replacement was comprised of a stainless steel dowel held in place with a welded dowel cap, and a continuous fillet weld around the guide block to the lower grid forging.

Figure 3-5: Lower Grid Guide Block Assembly

uontronea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-30 3.3 ProgramModificationAssessment Because D-B RV internals components 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 delineated in MRP-227-A are required to address the additional components. The following subsections assess whether modifications are needed.

3.3.1 Materials of Construction The general materials of construction are listed in"Table 3-3 for the vent valve miscellaneous locking device items and in Table 3-4 for the lower grid guide block attachment replacement items. All items are fabricated of various alloys of stainless steel.

Table 3-3: Materials of Construction for Vent Valve Miscellaneous Locking Device Items Subcomponent or S t Weld Part Number Subcomponent or Weld Part Description Material

-t *1-

+ 4.

+ +

1- i

uon'trollea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paae 3-31 Table 3-4: Materials of Construction for Lower Grid Guide Block Attachment Replacement Items Subcomponent or Subcomponent or Weld Part Description Material Weld Part Number t I.

3.3.2 Identification of Screening Parameters The screening parameters are listed in Table 3-5 for the vent valve miscellaneous locking device items and in Table 3-6 for the lower grid guide block attachment replacement items. The environmental parameters for the vent valve miscellaneous locking device items are the same as for the other vent valve items (see Table 3-2 of MRP-1 89, Revision 1, Identifiers S.7-S.14).

Similarly, environmental parameters for the lower grid guide block attachment replacement items are the same as for the guide blocks (see Table 3-2 of MRP-1 89, Revision 1, Identifier L.1.13). Operating stresses for either the original vent valve locking device items or the lower grid guide block attachment replacement items were not located during the preparation of this task. Unless otherwise noted, the welds were not confirmed to be or not to be multi-pass welds, but due to their small size, they are assumed to not be multi-pass welds. The one exception is the guide block to lower grid weld (WCF-344), which is a multi-pass weld. The delta ferrite content for WCF-344 was required to be in the range of 5 to 20%.

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paae 3-32 Table 3-5: Original Vent Valve Miscellaneous Locking Device Parts Screening Parameters Sucmpnn SbopoetMaterial Neutron Subcomponent Subcomponent Material Material Type, Temp Exposure Operating Cold Multi- Fatigue Part or Weld or Weld Part Category Spec Grade, (TF) (n/cm 2 , Stress Work pass Usage Bolting Number Description orClass E>IMeV) (ksi) 1 >20% Weld Factor2

__

1 I I I....

__ ___

Operating stresses for these subcomponents were not located.

__ _ _ _ _

2 Fatigue for these subcomponents is assumed to be very low (<0.1), similar to that of most reactor vessel internals items.

3 Alloy A-286 spring wire is assumed to have surface cold work following manufacture 4

These items are non-bolting and not crimped, thus it is unlikely that these items exceed the stress screening criteria.

5 Due to the nature of these welds, it is assumed that the operating stress is very low and below the screening criteria.

6 Determination of a multi-pass nature for these welds is not possible. However due to the small size of these welds, it is unlikely that this is a multi-pass weld and therefore, assumed to be a single pass weld.

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison Page 3-33 Table 3-6: Lower Grid Guide Block Attachment Replacement Parts Screening Parameters Material Neutron Subcomponent Subcomponent Material Material Type, Temp Exposure Operating Cold Multi- Fatigue or Weld Part or Weld Part Stress Work pass Usage Bolting Number Description Category Spec Grade, (OF) (n/cm2, 7 or Class E>IMeV) (ksi) >20% Weld Factor 7 Operating stresses for these subcomponents were not located.

8 Due to the nature of this weld, it is assumed that the operating stress is very low and below the screening criteria.

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paqe 3-34 3.3.3 Characterizeand Screen for Degradation In this section, the original vent valve locking devices and lower grid guide block attachment replacement items are screened using the process set forth in MRP-189, Revision 1. The screening criteria are defined in Table 3-1 of MRP-1 89, Revision 1. Using these criteria, each age-related degradation mechanism is screened for each item identified in Table 3-5 and Table 3-6. An aging mechanism is screened "in" if the screening criteria are met or exceeded for the particular item. Unless otherwise noted, for unknown characteristic values (i.e., operating stress), the value is assumed to exceed the screening criteria. The results of this initial screening are shown in Table 3-7 and Table 3-8.

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-35 Table 3-7: Original Vent Valve Miscellaneous Locking Device Parts Screening Results 0.

.)

0 Subcomponent IM. *"

or Paet Subcomponent or Weld Subompnen Material Category or Wel "- (

Number Part Description E r- E "-

EE 25 U))

u. L-U h-u > h-x Austenitic SS A A Not A A A A A A Austenitic SS A A Not A A A A A A Austenitic PH SS Not A A Not A A A A A A Austenitic SS A A Not A A A A A A Martensitic SS A A A A Not A A A A Austenitic SS A A A A A A A A Austenitic SS A A A A A A A A Martensitic SS A A A A Not A A A A Austenitic SS A A A A A A A A SCC = Stress CorrosionCracking IASCC = IrradiationAssisted Stress CorrosionCracking

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-36 Table 3-8: Lower Grid Guide Block Attachment Replacement Parts Screening Results CL Subcomponent Subcomponent Part or Weld Ma terilacaegor 0')

,C,.

or Weld Part Material Category .EE - UE)

Number E o- E o 2 o.2 o.2 U _ u. -u W-u > ,t Austenitic SS Not A A NotA A A A A A Austenitic SS Not A A Not A A A A A A Austenitic PH SS A A A A A A A A Austenitic SS A A A A A A A A Austenitic SS A A A A A A A A Austenitic SS A A A A A A A A SCC = Stress Corrosion Cracking IASCC = IrradiationAssisted Stress Corrosion Cracking

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paqie 3-37 3.3.4 FailureModes and Effects CriticalityAnalysis (FMECA)

The objective of the FMECA is to provide a systematic, qualitative review to identify the D-B RV internals subcomponents 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 subcomponent/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.

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 the development of MRP-227-A was similarly used for the relevant D-B RV internals subcomponents and welds and the results are shown in Table 3-9 and Table 3-10.

AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paae 3-38 Table 3-9: Original Vent Valve Miscellaneous Locking Device Parts FMECA Results sCC IASCC ISR & Creep Wear Fatigue TE IE VS 0

(D di 4) (iiDi d) i0

.. C oC C o ., C C -

Q n n aCd C d 0 C L) C CD n~ d C) C S) diCd d) a) -M ) C) C13 d)U C 0md -Md 0 C oo W W ao

._M a) 0)

C .am M aC C 0 d .Mi C C_ .am 2 Mi

. 0 C -a Mm E E

>. Cam .C >. d am .T d am C. . a-di am > r_am .C , ia- C > m . .d m .

0 - = - 0 W W 0 X~ U C) X~ W C) U) 0 f (n~ 0 W Cd 0 of

.C.C C _

di

-0 0 0A >

o. . U Zi 0 >. 0 i >. 0 > 0 L) i > 0 >. 0 d > 0 0 > 0u. 0 d > 0 > 0 a d > aD A C)d AC12ICi Ci Of I AAAAA CL E0 0 cn 0. U) U) W (12WU 0(( )WnU)

W W 0 U) U) WU U) W 0 (n U) W Un W U W) U) W UD W 0 (n U) WU( W LU CU) U) W en W 0 U) U) W U) WU C.U A A A A A A C 1 2 1 111 B A A A A A A A A B A A A A A A C 1 2 1 111 B A A A A A A A A B B 12111 A A A A A C 1 2 1 111 B A A A A A A A A B A A A A A AC 1 2 1111 BCA A 1A A A A A A B AA A A A A A A A A 121111 B A A A A B AA A A A A A A A A A A A A A A A AA A A A A A A A AA A A A A A A AA A A A A A A A AC 121111 B A A A A B A AA AA AA AA AA A A AA AA SCC = Stress Corrosion Cracking,IASCC = IrradiationAssisted Stress Corrosion Cracking, ISR = Irradiationenhanced Stress Relaxation, TE = Thermal Embrittlement, IE = IrradiationEmbrittlement, VS = Void Swelling

ANP-3359NP AREVA Inc.

Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-39 Table 3-10: Lower Grid Guide Block Attachment Replacement Parts FMECA Results scc IASCC ISR & Creep Wear Fatigue TE IE VS 0

aC o

a) (-

C 0

C

C

M0 C -

a a a a aa -0 'a a a a aD a a a a -(D a o0

) D 'a a) a) a a) a0 C U j U aC C) U=J C on) 0 fl C C on r_ OnU C or M C or ar_ C ar M 0UM

_ a- M C a Cz aT a0 C Ca a0 n a) a .- ,. a. am .C >. a am .7 > a _ am .M > a D am Ccc- .C >. a- am M Ua a Cam M

.~0 a) CO Ba) T A a) 0 Aa A 0B o M 0M(

2aU I 0A OV > a o m M a M A (D 0 AM

M a C 0) o )0l fta (D a 0 ) 0 2:1 a 0 a) 0 a: c00:0 xa) a4 a: 0 0 a) a: 0 0 U)OM M cc.

a C/)UW a-a M Ca L)

W) 0U U Cn Wi M

Ca a

L)

W M

0

~ D 1a (n Wu C) m W

U 0 Ca) Ca U m) 0 CaW 0 0 a '0 M Ca) CO W M

fn LU 0 aa U

Ca Cn WU Ca a

WU C

U Ca U) W C

C w a

CO

0) Ca U

Ca C

W Ua W C-0 (.)

CA0 C 0 U0 T L A A 9r S2 A 0 Q SA mg 0 S2 A 0 SA SA A:

B 12111 A A A A A B 12111 A A A A A A A A A A AA 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 AeA A A A dA Ai A AA A A A A A A A A A A A A A A A A A SCC = Stress Corrosian Cracking, IASCC =Irradiatian Assisted Stress Carrasian Cracking, ISR Irrnadiatianenhanced Stress Relaxatian, TE =Thermal Embritttement, IE = Irradiation Embrittlenient, VS = Void Swelling

uontroiiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-40 3.3.5 EngineeringEvaluation and Assessment As can be seen from Table 3-9 and Table 3-10, the subcomponent parts not included in MRP-189, Revision 1 that remain as non-Category A following the FMECA include various parts of the original vent valve locking device ( [

] ) and no parts from the lower grid guide block attachment replacement items.

The aging mechanisms that lead to these subcomponents being screened as non-Category A are thermal embrittlement and wear. Thermal embrittlement itself does not cause failure.

However, this embrittlement can cause a reduction in the toughness of the material, leading to an increased susceptibility to failure.

As stated in Section 3.2.1, industry experience with the original vent valve locking devices has indicated that wear can be a concern with damage sustained on the locking devices due to flow induced vibration forces. This resulted in several of the B&W-designed units replacing the vent valves nearest to the core support shield outlet nozzles as this was determined to be the area of susceptibility and where the locking device damage was primarily located. As previously stated, D-B has four RV internals vent valves (as compared to eight for the other B&W-designed units) and these four valves are not located near the outlet nozzles. Therefore, it is unlikely that any of the D-B original vent valve locking devices will experience this wear degradation. However, wear was conservatively identified as an applicable aging mechanism [

] due to the operating history for these components.

These original vent valve locking device parts have limited accessibility for inspection (refer to Figure 3-3 and Figure 3-4). As stated in the D-B AMR document, the vent valve assemblies have a "Support" intended function. To meet this intended function, structural integrity of the vent valve assembly must be maintained to ensure the vent valve remains in the CSS nozzle and functional. The function of the vent valve jackscrew is to maintain the retaining rings position and to prevent the retaining rings from backing out of the mounting ring groove in the CSS nozzle. The function of the vent valve locking device ( [

] ) is to prevent the jackscrew from

uontrollea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 3-41 turning during reactor operation. As shown in the D-B AMR document, the retaining rings are considered primary component items within the MRP-227 program at D-B. Section 4.3.1 of MRP-227-A delineates that the retaining rings are to be inspected via visual VT-3 inspection on the 10-year ASME Boiler and Pressure Vessel (B&PV) Code Section XI Inservice Inspection (ISI) interval [2]. If the function [

] were degraded during service, the visual inspection of the retaining rings in the vicinity of these subcomponent items (refer to Figure 3-3), would indicate that the jackscrew had turned and was out of design position. The observation that the jackscrew and retaining rings are in their design configuration is verification that the locking devices are fulfilling their design function.

In addition, D-B performs a visual inspection on the valve body and valve disc as well as an operability test during each refueling outage (at least once per 24 months). This inspection and operability test is required through the unit's Technical Specifications. Therefore, the

[ I subcomponents of the original vent valve locking device are further categorized as "Existing Programs" for D-B. Note that the addition of the original vent valve miscellaneous locking device parts as an "Existing Program" is currently under industry review.

It is unlikely that thermal embrittlement or wear to these subcomponents would lead to a loss of intended function for the vent valve locking device. 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 thermal embrittlement and wear on the original vent valve locking devices is adequately managed by the existing plant Technical Specifications and the MRP-227-A inspection requirements invoked through the D-B ISI Program.

uontroiieci uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Page 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-1 89, Revision 1 and the component items designated in the scope of license renewal for D-B. As described above, two component items were identified as being within the scope of license renewal and subject to AMR, but were not included in the. relevant MRP-1 89, Revision 1 tables:

Original Vent Valve Miscellaneous Locking Device Parts

Lower Grid Guide Block Attachment Replacement Parts A review of background information pertaining to the original vent valve locking devices and the lower grid guide block attachment replacement parts was completed. The appropriate subcomponent items of interest were identified. The sequence steps as described in MRP-189, Revision 1 Sections 3 and 4 were used to evaluate the aging mechanisms and resultant aging effects on the subcomponents 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-189, Revision 1 to perform the initial screening of these items for degradation. A FMECA was performed, and a preliminary categorization using the degradation screening results as well as the FMECA was performed. An engineering evaluation and assessment was used to categorize the subcomponent 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:

" Original Vent Valve Miscellaneous Locking Device Parts - Categorized as "Category A" or "Existing Programs". (Note: The addition of certain original vent valve miscellaneous locking device parts as an "Existing Program" is currently under industry review.)

Lower Grid Guide Block Attachment Replacement Parts - Categorized as "Category A" The potential for failure of the locking devices on the original vent valve assemblies due to thermal embrittlement and wear is adequately managed by the ASME B&PV Code Section XI

uornrooiea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Pagqe 4-2 programmatic controls along with the valve testing and inspection requirements each refueling outage (as required by plant Technical Specifications).

However, it is noted that the existing program in place for the original vent valve locking device aging management at D-B is not identified as such in Table 4-7 of MRP-227-A. AREVA is working with the PWR Owners Group and EPRI to establish interim guidance to account for this discrepancy and incorporate the appropriate information into the next revision of MRP-227. In this report, D-B assumes that the visual inspections currently performed are equivalent to an Existing Program for MRP-227 implementation.

uontrollea uocument AREVA Inc. ANP-3359NP Revision 0 Davis-Besse Reactor Vessel Internals License Renewal Scope and MRP-1 89, Revision 1 Comparison Paae 5-1

5.0 REFERENCES

1. US Nuclear Regulatory Commission, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, September 2013 (Accession No. ML13248A267).

2. MaterialsReliability Program:PressurizedWater Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A). EPRI, Palo Alto, CA: 2011. 1022863.

3. MaterialsReliability Program.: Screening, Categorization,and Ranking Qf B& W-Designed PWR Internals Component Items (MRP-189-Rev. 1). EPRI, Palo Alto, CA: 2009. 1018292.

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

5. "Davis-Besse Nuclear Power Station License Renewal Application," August, 2010.

Enclosure D Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse)

Letter L-1 5-139 AREVA NP Affidavit to Support the Disclosure Request for the Proprietary Assessment Report 3 pages follow

AFFIDAVIT.

COMMONWEALTH OF VIRGINIA )

) ss.

CITY OF LYNCHBURG )

1. My name is Gayle Elliott. I am Manager, Product Licensing, for AREVA Inc.

(AREVA) and as such I am authorized to execute this Affidavit.

2. I am familiar with the criteria applied by AREVA to determine whether certain AREVA information is proprietary. I am familiar with the policies established by AREVA to ensure the proper application of these criteria.

3. I am familiar with the AREVA information contained in the document ANP-3359P titled "Davis Besse Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison," dated December 2014 and referred to herein as "Document."

Information contained in this Document has been classified by AREVA as proprietary in accordance with the policies established by AREVA Inc. for the control and protection of proprietary and confidential information.

4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.

5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is

requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."

6. The following criteria are customarily applied by AREVA to determine whether information should be classified as proprietary:

(a) The information reveals details of AREVA's research and development plans and programs or their results.

(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.

(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA.

(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA in product optimization or marketability.

(e) The information is vital to a competitive advantage held by AREVA, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of AREVA.

The information in this Document is considered proprietary for the reasons set forth in paragraphs 6(c), 6(d) and 6(e) above.

7. In accordance with AREVA's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8, AREVA policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.

44 SUBSCRIBED before me this day of O-ylaap.d 2015.

J 7-3

v t e Letter Sequence Other
TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed)
Initiation Request, Request, Request, Request Acceptance... Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance Meeting Questions 28 February 2011 17 February 2011 17 March 2011 21 March 2011 18 March 2011 5 April 2011 30 March 2011 20 April 2011 2 May 2011 19 May 2011 20 June 2011 11 July 2011 12 July 2011 21 July 2011 21 July 2011 27 July 2011 11 August 2011 12 September 2011 9 September 2011 22 September 2011 11 October 2011 8 November 2011 22 November 2011 2 December 2011 2 December 2011 2 December 2011 27 December 2011 13 December 2011 21 December 2011 29 December 2011 12 July 2011 12 July 2011 12 July 2011 23 January 2012 30 January 2012 19 January 2012 1 February 2012 9 February 2012 27 January 2012 21 February 2012 22 February 2012 2 March 2012 27 February 2012 22 February 2012 24 February 2012 16 February 2012 27 February 2012 15 May 2012 28 February 2012 2 April 2012 ... further results Answers 18 March 2011 23 March 2011 23 March 2011 15 April 2011 20 April 2011 5 May 2011 24 May 2011 3 June 2011 24 June 2011 17 June 2011 22 July 2011 26 August 2011 17 August 2011 16 September 2011 7 October 2011 21 October 2011 9 November 2011 23 November 2011 5 April 2012 25 May 2012 14 June 2012 5 July 2012 11 July 2012 16 August 2012 16 August 2012 7 September 2012 2 November 2012 20 November 2012 20 December 2012 21 January 2013 12 February 2013 28 February 2013 14 March 2013 19 April 2013 21 May 2013 17 May 2013 4 June 2013 31 January 2014 11 March 2014 3 July 2014 29 July 2014 16 September 2014 28 October 2014 28 January 2015 15 April 2011 29 April 2011 9 March 2012 25 May 2012 Results Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval Other: L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples, L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems., L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21, L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal, L-12-444, Submittal of Contractor Equivalent Margins Assessments for Reactor Vessel Welds (Nonproprietary Versions), L-12-456, Notification of Closure of Commitments Related to the Review of the License Renewal Application, L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45), L-13-330, License Renewal Application Amendment No. 46 - Annual Update, L-13-341, Review of the Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 48, L-14-206, License Renewal Application Amendment No. 50 - Annual Update, L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55, L-15-139, License Renewal Reactor Vessel Internals Inspection Plan, L-15-214, License Renewal Application Amendment No. 59 - Annual Update, L-15-309, License Renewal Application Amendment No. 60, L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits., ML102450565, ML111050091, ML11110A089, ML11110A091, ML11110A092, ML11110A093, ML11110A094, ML11110A095, ML11110A105, ML11110A106, ML11110A107, ML11122A014, ML11126A017, ML11126A018, ML11126A019, ML11126A020, ML11126A021, ML11126A022, ML11126A023, ML11126A024, ML11126A025, ML11126A026, ML11126A032, ML11126A033, ML11126A034, ML11126A035, ML11126A036, ML11126A037, ML11126A038, ML11126A039, ML11126A040, ML11126A041, ML11126A042, ML11126A043... further results
MONTHYEAR2011-02-25 [Table View]

ML15113B134

Text

1.0 INTRODUCTION

SUMMARY

4.0 REFERENCES

1.0 INTRODUCTION

4.0 CONCLUSION

5.0 REFERENCES

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