ML033000133
| ML033000133 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/06/2002 |
| From: | Hinton B, Kielb J, O'Brien P Westinghouse |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L-2003-222 CN-CI-02-51-NP | |
| Download: ML033000133 (7) | |
Text
St. Lucie Unit 1 Docket No. 50-335 L-2003-222 Attachment 2 Page 1 Calculation Note CN-CI-02-51 Rev. 00 RCS Hot Leg RTD Nozzle and Flow Measurement Nozzle Repair - Design Verification for St. Lucie Units 1 & 2 (Non-Proprietary Version)
(6 Pages)
Calculation Note CN-CI-02-51 Rev. 00 RCS Hot Leg RTD Nozzle and Flow Measurement Nozzle Repair - Design Verification for St. Lucle Units 1 & 2 (Proprietary Version)
(57 Pages)
Attachments 3 and 4 Contain 10 CFR 2.790 Information
I Westinghouse Non-Proprietary Class 3 WESTINGHOUSE ELECTRIC COMPANY LLC I
Title:
RCS Hot Leg RTD Nozzle and Flow Measurement Nozzle Repair - Design Verification for St. Lucle Units I and 2 Authogs) Name(s)
John F. Klb SIgnature I Dais la, b','
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For Pages For Pages
-All Verffier(B) Name(s)
Paod Odnen Signature-I Date Maager Name Brumc Hriton Srgnaturz I DM'4 6A" 02002 Westinghouse Electric Company hLG S Westinghouse C:ACN--C42-51-NP.doc Ward Vemlon 3.0
WESTINGHOUSE ELECTRIC COMPANY LLC Cahftfion Wote Nurnber Revis nPage CN-CI-02-51-NP I
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Record of Revisions Rev Date Revision Description.
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Table Of Contents 1.0 Introduction...................................
4 1.1 Background / Purpose......................
12 Limits of Applicability....................
l 2.0 Summary of Results and Conclusions 5
3.0 Assumptions and Open Items.............................
5 3.1 D1scussion of Major Assumptions 3.2 Open items......................................................................................................................
4.0 Acceptance Criteria.....................................
5 5.0 Computer Codes Used In Calculation 5
6.0 Calculations 5
6.1 Method Discussion..........................................................................................................
6.2 Input.................................................................................................................................
6.3 Evaluations, Analysis, Detailed Calculations and Results................................................
7.0 References C:"CN-CI-02-51-N.doc Wr va~.
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4 1.0 Introduction 1.1 Background I Purpose Florida Power and Light Company (FPL), as the operating agent for St. Lucie Nuclear Plants, Units I and 2, has requested this analysis of welded nozzle repairs of Its Reactor Coolant System (RCS) hot leg RTD and Flow Measurement nozzles for one fuel cycle. The RTD and Flow Measurement nozzles, referred to herein as instrumentation nozzles are Inconel Alloy 600 (SB-166) construction, and are welded 'to the SA-516 Grade 70 hot leg piping. The existing weld is a J-groove partial penetration weld on the ID of the hot leg.
Industry experience has shown that the cracks caused by primary water stress corrosion cracking (PWSCC) may develop In the nozzle base metal or in the J-weld, possibly leading to leakage of the reactor coolant.
FPL has indicated In Its Purchase Order (Reference 23) that during the upcorming St. Lucie Unit 1 outage (cycle 18) these nozzles will be examined for evidence of leakage. Nozzles showing evidence of leakage will be repaired, with an expectation that the repair will be adequate for one more fuel cycle. As directed by Reference 23, the repair will consist of an additional partial penetration weld with a fillet reinforcement applied to the external surface of the hot leg pipe at the junction with the nozzle. The weld joint will comply with Figure NB-4244 (d)-1, design (e), of Reference 3, with the exception that the A dimension will be zero (0)
Inches (I.e., no gap). Additionally, Appendix B3 indicates FP&L wil. use a minimum weld size of.250 inch. A figure showing the RTD nozzle in a section of the Hot Leg Is provided below.
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The existing weld will no longer be considered the pressure boundary, thereby relocating the pressure boundary function from the Interior to the exterior weld on the hot leg pipe. The nozzle will not be severed and the existing J-weld will not be disturbed. Although this Is not a typical design configuration - due to the differential thermal expansion thaets caused between the nozzle and the pipe wall - this repair approach has been used before as a short-term repair option. Note that since the Inner weld is no longer considered the pressure boundary, the primary coolant can be In contact with the carbon steel vessel. Reference 24 concludes that this Is acceptable for the required one fuel cycle of operation that Is the basis for this calculation note.
The purpose of this calculation note is to provide documentation that the weld repair is acceptable per the criteria of Reference 3.
2.0 Summary of Results and Conclusions Infornation for Sections 2.0 - 2.3 Is proprietary to Westinghouse Electric.
3.0 Assumptions and Open Items Information for Sections 3.0 - 3.2 Is proprietary to Westinghouse Electric.
4.0 Acceptance Criteria Information for Section 4.0 is proprietary to Westinghouse Electric.
5.0 Computer Codes Used In Calculation Information for Section 5.0 Is proprietary to Westinghouse Electric.
6.0 Calculations Information for Sections 6.0 - 6.3 Is proprietary to Westinghouse Electric.
7.0 References
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- 2. ASME Boiler and Pressure Vessel Code, Section Xl, Division 1, 1989 Edition
- 3. ASME Boler and Pressure Vessel Code, Section lIl, Division 1, Subsection NB. 1989 Edition
- 4. ASME Boller and Pressure Vessel Code, Section lii, Division 1, Appendices, 1989 Edition 5-l C'iMCNI-02-5t.NPdoc vio3.
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