ML11356A281

New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000306, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-Rev. 0)

ML11356A281
Person / Time
Site:	Indian Point
Issue date:	12/22/2011
From:	Electric Power Research Institute
To:	Atomic Safety and Licensing Board Panel
SECY RAS
Shared Package
ML11356A279	List: ML11356A280 ML11356A281 ML11356A282 ML11356A283 ML11356A284 ML11356A285 ML11356A286 ML11356A287 ML11356A288 ML11356A290 ML11356A291 ML11356A292 ML11356A294
References
RAS 21617, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML11356A281 (15)

Text

NYS000306 Submitted: December 22, 2011 EXCERPT 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 er rm Fo s e t aff B o l l

B Baffle Edge Bolts 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 4-32 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.

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