ML12340A751

Official Exhibit - NYSR00306-00-BD01 - EPRI, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, (MRP-227-Rev. 0), Report 1016596, Excerpted: Pp. 3-9, 4-54 - 4-67.

ML12340A751
Person / Time
Site:	Indian Point
Issue date:	10/01/2012
From:	Electric Power Research Institute
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
07-858-03-LR-BD01, RAS 23554, Indian Point 50-247-LR and 50-286-LR
Download: ML12340A751 (16)

Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3) NYSR00306 ASLBP #: 07-858-03-LR-BD01 Revised: October 1, 2012 Docket #: 05000247 l 05000286 EXCERPT Exhibit #: NYSR00306-00-BD01 Identified: 10/15/2012 Admitted: 10/15/2012 Withdrawn:

Rejected: Stricken:

Other:

Materials Reliability Program:

Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-Rev. 0)

Component Categorization and Aging Management Strategy Development Figure 3-5 Overview of typical Westinghouse internals 3-9

Aging Management Requirements Wear Area Figure 4-20 Typical Westinghouse control rod guide card (17x17 fuel assembly) 4-54

Aging Management Requirements Lower Flange Weld Figure 4-21 Typical Westinghouse control rod guide tube assembly 4-55

Aging Management Requirements Figure 4-22 Major fabrication welds in typical Westinghouse core barrel 4-56

Aging Management Requirements Figure 4-23 Bolt locations in typical Westinghouse baffle-former-barrel structure. In CE plants with bolted shrouds, the core shroud bolts are equivalent to baffle-former bolts and barrel-shroud bolts are equivalent to barrel-former bolts 4-57

Aging Management Requirements









  

 





 

Figure 4-24 Baffle-edge bolt and baffle-former bolt locations at high fluence seams in bolted baffle-former assembly (note: equivalent baffle-former bolt locations in bolted CE shroud designs are core shroud bolts) 4-58

Aging Management Requirements High Fluence Seams Figure 4-25 High fluence seam locations in Westinghouse baffle-former assembly 4-59

Aging Management Requirements Potential Gaps at Baffle-Former Plate Levels Potential Bowing Along High Fluence Seam Figure 4-26 Exaggerated view of void swelling induced distortion in Westinghouse baffle-former assembly. This figure also applies to bolted CE shroud designs 4-60

Aging Management Requirements Vertical Displacement Figure 4-27 Vertical displacement of Westinghouse baffle plates caused by void swelling. This figure also applies to bolted CE shroud designs 4-61

Aging Management Requirements Hold-down spring Figure 4-28 Schematic cross-sections of the Westinghouse hold-down springs 4-62

Aging Management Requirements Core Barrel Thermal Shield Thermal Shield Flexure Core Support Figure 4-29 Location of Westinghouse thermal shield flexures 4-63

Aging Management Requirements Figure 4-30 CE lower support structure assembly for plants with integrated core barrel and lower support structure with a core support plate (this design does not contain a lower core barrel flange)

CSP a) b) c) a) Early support column design b) Winged support column design and plants with second generation core support assemblies c) Later support column design used in plants with second generation core support assemblies Figure 4-31 CE core support columns 4-64

Aging Management Requirements Figure 4-32 Schematic indicating location of Westinghouse lower core support structure. Additional details shown in Figure 4-33 Figure 4-33 Westinghouse lower core support structure and bottom mounted instrumentation columns. Core support column bolts fasten the core support columns to the lower core plate 4-65

Aging Management Requirements Figure 4-34 Typical Westinghouse core support column. Core support column bolts fasten the top of the support column to the lower core plate Figure 4-35 Examples of Westinghouse bottom mounted instrumentation column designs 4-66

Aging Management Requirements Weld Weld Figure 4-36 Typical Westinghouse thermal shield flexure 4.4 Existing Programs Component Requirements Existing Programs components are those PWR internals for which current aging management activities required to maintain functionality are being implemented. The continuation of these activities is credited within these guidelines for adequate aging management for specific components.

Included in the Existing Programs are PWR internals that are classified as removable core support structures. ASME Section XI, IWB-2500, Examination Category B-N-3 [2] does not list component specific examination requirements for removable core support structures.

Accordingly, factors such as original design, licensing and code of construction variability could result in significant differences in an individual plants current B-N-3 requirements. These guidelines credit specific components contained within the general B-N-3 classification for maintaining functionality.

These examination requirements, as applied to the components designated in Tables 4-7, 4-8, and 4-9, have been determined to provide sufficient aging management for these components.

Table 4-7 B&W plants Existing Programs components No existing generic industry programs were considered sufficient for monitoring the aging effects addressed by these guidelines for B&W plants. Therefore, no components for B&W plants were placed into the Existing Programs group.

4-67