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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems 1999-09-27
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20107L9271996-01-0303 January 1996 Offsite Dose Calculation Manual,Rev 9,Peach Bottom Atomic Power Station Units 2 & 3 ML20095G0791995-09-22022 September 1995 Addendum 1 to Rev 2 to ISI Program Second Ten Yr Interval Units 2 & 3 for Peach Bottom Atomic Power Station ML20092C6141995-08-23023 August 1995 Rev 2 to Fabrication Spec 25A5601, Fabrication of Shroud Stabilizer ML20086A5531994-09-29029 September 1994 Rev 6 to GP-23, Diesel Generator Outages ML20073J7701994-09-24024 September 1994 Rev 0 to Installation Spec 25A5581, Stabilizer Installation ML20073J7311994-09-24024 September 1994 Rev 1 to Fabrication Spec 25A5601, Fabrication of Shroud Stabilizer ML20073J7251994-09-24024 September 1994 Rev 1 to Core Design Spec 25A5580, Shroud Stabilizers ML20073J7171994-09-24024 September 1994 Rev 1 to Design Spec 25A5579, Shroud Stabilizer Hardware ML20086A5211994-09-16016 September 1994 Rev 5 to Administrative Guideline Procedure AG-43, Guideline for Performance of Sys Outages ML20073F5541994-09-12012 September 1994 Shroud Stabilizers Legend or Description of Groups ML20073F5441994-09-12012 September 1994 Shroud Stabilizer Hardware Legend or Description of Groups ML20073F5671994-09-0909 September 1994 Fabrication of Shroud Stabilzer Legend or Description of Groups ML20073F5331994-08-31031 August 1994 Rev 0 to GENE-771-54-0894, Project Instruction Shroud Repair for H1 Through H7 Welds for PECO Energy Peach Bottom Atomic Power Station ML20073F6811994-08-29029 August 1994 Draft Rev 0 to Installation Spec 25A5581, Stabilizer Installation ML20056G0941993-07-0101 July 1993 Rev 5 of ODCM for Pbaps,Units 2 & 3 ML20056G0981992-12-28028 December 1992 Rev 0 to Procedure RW-C-100, Solid Radwaste Sys Pcp. Procedure Supersedes RW-800 at LGS & RW-120 & RW-121 at PBAPS ML20085E4601991-07-12012 July 1991 Rev 2 to M-710, Peach Bottom Atomic Power Station Units 2 & 3 Spec for Pump & Valve Inservice Testing Program Second 10-Yr Interval ML20082L8791991-06-0606 June 1991 Rev 4 to ODCM ML20062G4691990-07-0303 July 1990 Inservice Insp Program Second 10-Yr Interval ML20151Z3911988-08-23023 August 1988 Restart Power Testing Program (Power Ascension) ML20153G0551988-06-28028 June 1988 Rev 2 to Offsite Dose Calculation Manual ML20151D0531988-04-0808 April 1988 Rev 1 to Section I, Corporate Action, of Plan for Restart of Peach Bottom Atomic Power Station ML20151G4601988-04-0808 April 1988 Rev 1 to Section II, Peach Bottom Atomic Power Station Action, of Plan for Restart of Peach Bottom Atomic Power Station ML20196C6811988-02-12012 February 1988 Section II of Plan for Restart of Peach Bottom Atomic Power Station ML20236T0751987-11-25025 November 1987 Plan for Restart of Peach Bottom Atomic Power Station, Section I:Corporate Action ML20235Z1971987-10-0808 October 1987 Public Version of Rev 17 to EP-102, Unusual Event Response, Rev 16 to EP-103, Alert Response, Rev 17 to EP-104, Site Emergency Response, Rev 16 to EP-105, General Emergency Response & Rev 18 to App P of EP-209 ML20237L4991987-08-10010 August 1987 Public Version of Emergency Plan Implementing Procedures, Including Rev 16 to EP-102, Unusual Event Response, Rev 15 to EP-103, Alert Response & Rev 16 to EP-104, Site Emergency Response. W/870826 Release Memo ML20236L7911987-08-0707 August 1987 Commitment to Excellence Action Plan ML20237K1741987-06-17017 June 1987 Rev 4 to Solid Radwaste Sys Process Control Program ML20214V2951987-04-28028 April 1987 Description of Plans for Recirculation & RHR Sys Piping Replacement at Peach Bottom Unit 3 ML20151Y3361987-04-23023 April 1987 Rev 1 to Procedure EP-8653, Reactor Water Level Pressure Compensation Instruments ML20212R1161987-03-31031 March 1987 Public Version of Revs to Emergency Plan Implementing Procedures,Including Rev 15 to EP-102, Unusual Event Response & Rev 2 to EP-205A.2, Obtaining Drywell Gas Samples from Containment Atmosphere Dilution Cabinets ML20237K1301987-03-13013 March 1987 Rev 1 to Offsite Dose Calculation Manual ML20237K1511987-03-11011 March 1987 Rev 3 to Solid Radwaste Sys Process Control Program ML20210T9101987-01-0606 January 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 14 to EP-102, Unusual Event Response, Rev 14 to EP-103, Alert Response & Rev 15 to EP-104, Site Emergency Response ML20215N4241986-10-21021 October 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 4 to EP-205A.13, Sample Preparation & Handling of Highly Radioactive Liquid & Gas Samples ML20214E6191986-10-0707 October 1986 Public Version of Emergency Plan Implementing Procedures, Including Rev 16 to EP-101, Classification of Emergencies, Rev 13 to EP-102, Unusual Event Response & Rev 13 to EP-103, Alert Response. W/Dh Grimsley 861118 Release Memo ML20203G4661986-07-15015 July 1986 Public Version of Emergency Plan Implementing Procedures, Including Rev 18 to EP-209,App D-3, Fire & Damage Team & Rev 20 to EP-209,App I-2 Chemistry & Health Physics Contractor Call List. W/860728 Release Memo ML20203J7851986-06-17017 June 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 19 to EP-209,App D-2, Dose Assessment Team & Rev 22 to EP-209,App D-4, Personnel Safety Team ML20203E9111986-03-29029 March 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Index,Rev 12 to EP-209 App a, Immediate Notification Call List & Rev 19 to EP-209 App C. W/860423 Release Memo ML20141F5891986-02-0404 February 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Emergency Plan Procedures Index & Rev 15 to EP-101 Re Classification of Emergencies ML20137Z5041985-11-18018 November 1985 Public Version of Emergency Plan Implementing Procedures, Including Rev 8 to EP-201, Technical Support Ctr Activation & Rev 8 to EP-202, Operations Support Ctrs Activation ML20198B8381985-10-31031 October 1985 NRC-Observed Emergency Response Exercise Manual,Peach Bottom Power Station 1999-04-20
[Table view] |
Text
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GENudarEmyy 25A5580 SH NO.1 REV.1 I
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 IS OR CONTAINS A SAFETY RELATED ITEM YES3 NO r'l EQUIP CLASS CODE P_
REVISION C
A RM-01386 9/12/94 l
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JTROVATO SEP 2 41994 RJA f
CONTROL ISSUE RM-01502 CHK BY: J TROVATO t
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6 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 9-12-94 J.L. TROVATO 9-12-94 R.J. AHMANN CONT ON SHEET 2 MS-WORD 9410070097 940926 PDR ADOCK 05000277 P
PDR
N 25A5580 SH NO. 2 REV.1
- 1. SCOPE 3
1.1 This document defines the ASME Code design requirements for the shroud repair for welds H1 through H7.
- 2. APPLICABLE DOCUMENTS 2.1 General Electric Documents. The following documents form a part of this sp c'fication to the extent specified herein.
i 2.1.1 Supponine Documents a.
Reactor Vessel - Power Rerate 25A5341 Rev. 0 b.
Reactor Pressure Vessel, Purchase Specification 21 A1111 Rev. 9 c.
Reactor Vessel, Purchase Part 886D499 P2 Sheet No.
Revision No.
I 11 2
8 3
3 4
6 5
3 6
4 l
7 6
8 0
i I
l d.
Reactor Thermal Cycles 729E762 Rev. O
\\
e.
Nozzle Thermal Cycles 135B9990 l
Sheet No.
Revision No.
1 1
2-8 0
i l
f.
Vessel Flange Bolting 885D911 Rev.2 g.
Nozzle End Preparation 107C5305 Rev.2 h.
Standard Requirements For Core Stmeture 21A3319 Rev.1 l
2.1.2 Supplemental Documents. Documents under the following identities are to be used with this i
specification:
a.
Shroud Stabilizer Hardware Design Specification 25A5579 l
Y GENuckarEnergy 25A5580 s,, no. 3 REV. I 2.2 Codes and Standards. The following documents of the specified issue fonn a part of this specification to the extent specified herein.
2.2.1 American Society of Mechanical Encineers (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
- b. Shroud Support VPF 1896-064-7
- c. Design Certification VPF 1896-142-1
- d. Design Stress Repon VPF 1896-146-1
- e. Final Design Report VPF 1896-148-2
- 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 vertically support the core top guide, core suppon plate, and shroud head, and to prevent core bypass flow io 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 insertion, 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 Support Stmetures.
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.
l
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'Y GENudearEnergy 25A558o su no. s l'
REV.1 4.2 The shroud stabilizers shall be constructed to the original Owners Requirements (document of
(
Paragraph 2.1.1.h) for the shroud, as there was na Code of Construction.
4.3 The shroud stabilizers change the points of application of the forces applied to the reactor l
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 4.4 The new forces and their points of application are defined in Figure 1, and in Table 1. The j
values given in Figure 1, and in Table 1 shall be combined with the forces defined in the Design 1
j Specification (documents of Paragraphs 2.1.1.a through 2.1.1.e).
i l
4.5 The original purchase specification for the reactor pressure vessel (document of Paragraph j
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 boundary parts, 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 boundary of Code jurisdiction. The boundary of ASME Code jurisdiction is shown in Figure 2.
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.
ate: 8M 26 /994 i
Signature:
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tate:
License Number.
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NNb 25A5580 SH NO. 5 REV.1 ADDITIONAL DESIGN MECHANICAL LOADS Force DBE + Normal Pressure MCE + LOCA F1 33,400 lbs 89,600 lbs F2 16,800 lbs 31,200 lbs F3 168,600 lbs 448,770 lbs F, F, and F are discrete loads applied over a small area. At any one point in time, F and F2 1
2 3
1 3 s applied to 4 locations 90* apan are each applied to one location. At any one point in time, F i
for the installation of four shroud stabilizer assemblies. DBE is a Design Basis Eanhquake (OBE).
MCE is a Maximum Credible Earthquake (SSE).
For a Main Steam Line LOCA without seismic loads, F3 = 321,933 lbs.
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 l
4
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4
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- + - - * -
e
- - + - -
W
-1 a-J-Lw m.a.-E Ma
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N 25A5580 SH NO. 6 REV.1 i
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r I
2 h
F, 244 in. ---
J' F3 72 in.
1 6
n u
,W
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4.25 m.
FIGURE 2 J
l APPLICATION OF DESIGN MECHANICAL LOADS FIGURE 1
i N
25A5580 SH NO. 7 REV.1 FINAL I
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i 1
8 SECTION ill
' NON-CODE INTERNALLY CLASS A SUPPORTED STRUCTURE f
'I RPV REQUIRED BOUNDARY I
i OF JURISDICTION i
e
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SHROUD SUPPORT j
CYUNDER k
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' STRUCRJRAL d
h WELD DEPOSIT
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SHROUD SUPPORT' f
j:
PLATE I.
l 3
SEE DOCUMENT IN PARAGRAPH 2.2.2.B FOR DIMENSIONS 1
1 i
BOUNDARY OF ASME CODE JURISDICTION FIGURE 2
(
B
.