ML20073F554

Shroud Stabilizers Legend or Description of Groups

ML20073F554
Person / Time
Site:	Peach Bottom
Issue date:	09/12/1994
From:	Ahmann R, Lenz M, Trovato J GENERAL ELECTRIC CO.
To:
Shared Package
ML20073F527	List: ML20073F519 ML20073F533 ML20073F544 ML20073F554 ML20073F567 ML20073F661 ML20073F681
References
25A5580, NUDOCS 9410030157
Download: ML20073F554 (7)

Text

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EIS IDENT: SHROUD STABILIZERS REVISION STATUS SHEET DOC TITLE SHROUD STABILIZERS LEGEND OR DESCRIPTION OF GROUPS TYPE: CODE DESIGN SPECIFICATION FMF: PEACH BOTTOM 2 AND 3 MPL NO: PRODUCT

SUMMARY

SEC. 7 THIS ITEM 15 OR CONTAINS A SAFETY RELATED ITEM YESI NO n EOUIP CLASS CODE P_

REVISION I

SEP 121994 A

RM-01386 PRINTS TO MADE BY APPROVALS GENERAL ELECTRIC COMPANY 175 CURTNER AVENUE J.L. TROVATO 8-22 94 M.O. LENZ 9-12-94 SAN JOSE, CALIFORNIA 95125 CHK BY ISSUED SEP 12 ggg J.L. TROVATO 9-12 94 R.J. AHMANN CONT ON SHEET 2 l

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1. SCOPE 1.1 This document defines the ASME Code design requirements for the shroud repair for welds H1 through H7.

2. APPLICABLE DOCUMENTS 2.1 Gener ' Electric Documents. The following documents farm a part of this specification to the extent specified herein.

2.1.1 Supportine Documents a.

Reactor Vessel - Power Rerate 25A5341 Rev. O b.

Reactor Pressure Vessel, Purchase Specification 21A1111 Rev. 9 c.

Reactor Vessel, Purchase Part 886D499 P2 Sheet No.

Revision No.

1

.11 2

8 3

3 4

6 5

3 6

4 7

6 8

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- d.

Reactor Thermal Cycles 729E762 Rev. 0 e.

Nozzle Thermal Cycles 135B9990 Sheet No.

Revision No.

1 1

2-8 0

f.

Vessel Flange Bolting 885D911 Rev.2 g.

Nozzle End Preparation 107C5305 Rev.2 h.

Standard Requirements For Core Structure 21A3319 Rev.1 2.1.2 Sucolemental Documents. Documents under the following identities are to be used with this specification:

a.

Shroud Stabilizer Hardware Design Specification 25A5579 l

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2.2 Codes and Standards. The following documents oFtl2e specifie'd issue form a pan of this

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l 2.2.1 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section III,1965 Edition and Addenda through Winter 1965 a.

b.

Section XI,1980 Edition and Addenda through Winter 1981 2.2.2 Other Documents

a. UFSAR, Peach Bottom 2 and 3 VPF 1896-064-7

b. Shroud Support VPF 1896-142-1

c. Design Cenification VPF 1896-146-1

d. Design Stress Repon VPF 1896-148-2

c. Final Design Report

3. GENERAL DEFINITION 3.1 The purpose of the shroud stabilizers is to structurally replace all of the horizontal welds (H1 through H7) in the shroud. These welds were required to both horizontally and venically suppon the core top guide, core support plate, and shroud head, and to prevent core bypass flow to the downcomer region. The core top guide and core support plate horizontally support the fuel assemblies and maintain the correct fuel channel spacing to permit control rod insenion, as well as having other structural functions.

3.2 All of the non ASME Code requirements for the shroud stabilizers are defined in the Document of Paragraph 2.1.2.a. The ASME Code requirements are defined herein.

4. REQUIREMENTS 4.1 The shroud stabilizer construction shall be performed in accordance with a Section XI Replacement Program per the requirements of Article IWA-7000. The core shroud was not supplied as a ASME Code component. However,Section XI requires In Service Inspection (ISI) of the Core Suppon Structures.

The required Replacement Program is different than most Replacement Programs, because the stabilizers are not a direct replacement. Instead, the structural functions of the shroud horizontal welds are replaced by new components. Any defects found in the shroud horizontal welds are acceptable after the installation of the stabilizers.

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4.2 The shroud stabilizers shall be constmeted t6 the original Owners Requirements (document of Paragraph 2.1.1.h) for the shroud, as there was no Code of Constmetion.

4.3 The shroud stabilizers change the points of application of the forces applied to the reactor pressure vessel from the core shroud. These new forces shall be analyzed in accordance with the original Code of Construction (document in Paragraph 2.2.1.a).

4.4 The new forces and their points of application are defined in Figure 1, and in Table 1. The values given in Figure 1, and in Table 1 shall be combined with the forces defined in the Design Specification (documents of Paragraphs 2.1.1.a through 2.1.1.e).

4.5 The original purchase specification for the reactor pressure vessel (document of Paragraph 2.1.1.b) specified that the boundary of jurisdiction of Section III of the ASME Code (document of Paragraph 2.2.1.a) shall include all attachments to the pressure bounday pans, but does not include the components that are welded to the attachments. Thus, the jurisdiction of the original Code of Construction included all weld build up pads used to attach internal components to the reactor pressure vessel, but did not include the shroud support within the bounday of Code jurisdiction. The boundary of ASME Code jurisdiction is shown in Figure 2. The document of Paragraph 2.2.1.a shall be used as a guide for the analysis of the shroud support.

4.6 The analysis required by this Design Specification shall be Certified.

5.0 PROFESSIONAL ENGINEER CERTIFICATION To the best of my knowledge and belief, this Design Specification satisfies the requirements of the ASME Boiler and Pressure Vessel Code 1965 Edition with Addenda through Winter 1965.

Date:

Signature:

License Number:

State:

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ADDITIONAL DESIGN MECHANICAL LOADS Force DBE + Normal Pressure MCE + LOCA 33,400 lbs 89,600 lbs Fi 16,800 lbs 31,200 lbs F2 168,600 lbs 448,770 lbs F3 F, F, and F are discrete loads applied over a small area. At any one point in time, F and F2 1

1 2

3 are each applied to one location. At any one point in time, F is applied to 4 locations 90* apart 3

for the installation of four shroud stabilizer assemblies. DBE is a Design Basis Earthquake (OBE).

MCE is a Maximum Credible Earthquake (SSE).

The stress intensities shall meet the stress allowables of the ASME Code,Section III, for the load combinations defined by the Peach Bottom UFSAR. The original Code of Construction did not include Faulted load combinations. Faulted load combinations shall meet the stress allowables as defined by the Peach Bottom UFSAR for the reactor pressure vessel.

TABLE 1

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8 SECTION lli NON-CODE INTERNALLY 9~ CLASS A SUPPORTED STRUCTURE I

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BOUNDARY OF ASME CODE JURISDICTION FIGURE 2