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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
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W/831031 & 840709 Release Memo ML20108E0491983-10-28028 October 1983 Rev 4 to Procedure HNP-4858, Naturally Occurring Phenomenon ML20080L0651983-10-12012 October 1983 Rev 1 to Procedure HNP-4848, Determination of Extent of Core Damage Under Accident Conditions ML20081L9461983-10-12012 October 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures HNP-4827 Re Offsite Radiological Environ Monitoring During Emergencies & HNP-4852 Re Offsite Dose Estimation 1998-04-30
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ATTACIIMENT 3 GENE SPECIFICATION 25A5717, REVISION 1 SIIROUD STABILIZERS CODE DESIGN SPECIFICATION IIATCII UNIT 2 JUNE 1995 9507120268 950703 PDR ADOCK 05000366 P PDR
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1 DOCUS!ENT TITLE SHROUD STABILI7.ERS 1.EGEND OR DESCRIPTION OF CdlOUPS TYPE: CODE DESIGN SPEC.
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I PRINTS TO hlADEIW APPROVALS GENERAL ELECTRIC COh1PANY 175 CURTNER AVENUE J. l.. TROVATO 1/26/95 51. R. SCIIRAG 5/12/95 SAN JOSE CALIFORNIA 95125 O CilKD IW: ISSUED J. I.. TROVATO -1/26/95 R. J. AlINIANN 5/17/95 CONT ON S11EET 2 J
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- 1. SCOPE 1.1 This document defines the AShfE Code design requirements for the shroud stabilizers for welds H1 through H8.
- 2. APPLICABLE DOCUhfENTS 2.1 General Electric Documents. The following documents form a part of this specification to the extent specified herein.
2.1.1 Supporting Documents
- a. Purchase Specification, Reactor Vessel 21 A9340, Rev. I
- b. Purchase Specification Data Sheet, Reactor Vessel 21 A9340AC, Rev.10
- c. Purchased Part Drawing, Reactor Vessel 922D167, Rev. 9
- d. Interface Control Drawing, Reactor Vessel Loadings 761E380, Rev. 3 p
- c. Information Drawing, Reactor Cycles 761E246,Rev.I
- f. Information Drawing, Reactor Vessel Nozzle Thermal Cycles 158B8369P3, Rev. 2
- g. Purchased Part Drawing, Nozzle Safe End Requirements 921D562, Rev. O
- h. Purchased Part Drawing, Vessel Flange Bolting 921 D706, Rev. O
- i. Standard Requirements for Core Structure 21 A3319, Rev. 5 2.1.2 Eupplemental Documents. Documents under the following identities are to be used with this specification:
- a. Shroud Repair Hardware Design Specification 25A5718 2.2 Codes and Standards. The following documents of the specified issue form a part of this specification to the extent specified herein.
2.2.1 Aluninm Society of Mechanical Encineers (ASME) Boiler and Pressure Vessel Code
- a.Section III,1968 Edition and Addenda through Summer 1970
- b.Section XI,1980 Edition and Addenda through Winter 1981 l
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2.2.2 Other Documents
- a. FSAR, Hatch Unit 2
- b. Combustion Engineering Drawing 11570-844-001 Rev. 3, Shroud Support Details and Assembly
- 3. GENERAL DEFINITION 3.1 The purpose of the shroud stabilizers is to structurally replace all of the horizontal girth welds in the shroud and shroud support. These welds we're required to both horizontally and vertically support 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 insertion.
3.2 All of the non ASNIE Code requirements for the shroud stabilizers are defined in the Document in Paragraph 2.1.2.a. The ASSIE Code requirements are defined herein.
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( 4. REQUIREh!ENTS 4.1 The shroud stabilizer construction shall be performed per a Section XI Replacement Program per Article IWA-7000. The core shroud was not supplied per the ash 1E Code Section III. Ilowever,Section XI requires ISI of Core Support 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 and shroud support horizontal welds are replaced by new components. Any defects found in the shroud horizontal welds are structurally acceptable after the installation of the stabilizers.
4.2 The shroud stabilizers shall be constructed to the original Owner's Requirements (Paragraph 2.1.1.i) for the shroud as there was no Code of Construction, because Section III, Subsection NG did not exist.
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 per the l 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 Table 1. The values given in Figure 1 and Table 1 shall be combined with the forces defined in the original Design Specification (Paragraph 2.1.1.a. through h.). The seismic loads include consideration of the 1/2 SNIE (Seismic Alargin Earthquake) as a design basis carthquake (DBE) in addition to the DBE identified in the document in Paragraph 2.2.2.a.
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GENuclearEnergy 5^5717 su so.4 REV.1 0
4.5 The' Document in Paragraph 2.1.1.a through h (original Design Specification) consenatively defined the Boundary of CodeJurisdiction as including the shroud support (Figure 2). The Document in Paragraph 2.2.1.a (original Code for RPV Construction) did not require the Boundary ofJurisdiction to be inboard of the weld of the shroud support plate to the reactor pressure vessel. Paragraphs N-110, N-145, N-150, N-152, N-310, N-474, and N-518 of the original Code of Construction do not require any internal attachments to be part of the Class A Vessel. However, GE consenatively classified the internal shroud support plate and the shroud support cylinder as part of the Class A Vessel per N-150.
4.5.1 Weld H8 was not required to be classified as part of the Class A Vessel. Therefore, for the purposes of this replacement, it shall not be considered as a Section III, Subsection NB weld. Thus, this weld can be replaced in the same manner as the remainder of the shroud welds. For the purpose of the shroud stabilizer, the boundary of ASNIE Code Section III, Subsection NBjurisdiction shall be redefined to terminate at the weld between the shroud support plate to the structural weld deposits on the low alloy steel shell (Figure 2).
4.6 The analysis of additional loads required by this Design Specification shall be Certified per Paragraph N-142 of Section III.
5.0 PROFESSIONAL ENGINEER CERTIFICATION To the best of my knowledge and belief, this Design specification satisfies the requirements of the AShlE Boiler and Pressure Vessel Code, Section 111,1968 Edition with Addenda through Winter 1970.
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l Force Upset Emergency Faulted l Fi 236,000. Lbs 367,000. Lbs 367,000. Lbs F2 347,000. Lbs 582,000. Lbs 882,000. Lbs F3 161.000. Lbs 179,000. Lbs 476,000. Lbs l
Fi , F2 , and F3are discrete loads applied over a small area. At any one point in time,1 Fi and 1 F2 are applied to one circumferential location, and F3 is applied to 1 location 180 from the Fi , Fucircumferential location.
The above loads are bounding for all load conditions including recirculation line LOCA.
The primary stress intensities shall meet the code allowables.
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