ML070870134
| ML070870134 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/21/2007 |
| From: | General Electric Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| DRF 0000-0064-9390, DRF 0000-0065-6012-R1 GE-NE-000-0064-9392-R2-NP | |
| Download: ML070870134 (8) | |
Text
ATTACHMENT 5 GE Non-Proprietary Report GE-NE-000-0064-9392-NP-R2, Pilgrim Unit 1, IGSCC Assessment of Shroud Repair X-750 Component Other Than The Replacement Upper Support Assembly and Tie Rod Nut (5 pages)
GE Energy, Nuclear General AlecIric Company 6705 Vallecitos Road, Sunol CA 94586 GE-NE-0000-0064-9392-R2-NP DRF Section 0000-0065-6012-RRI DRF 0000-0064-9390 Class I March 2007 Pilgrim Unit 1 IGSCC Assessment of Shroud Repair X-750 Components Other Than The Replacement Upper Support Assembly and Tie Rod Nut
GE Energy, Nuclear IMPORTANT NOTICE REGARDING THE CONTENTS OF THIS REPORT Please Read Carefully NON-PROPRIETARY INFORMATION NOTICE This is a non-proprietary version of the document GE-NE-0000-0064-9392-P-R 1, which has the proprietary information removed.
Portions of the document that have been removed are indicated by an open and closed double brackets as shown here ((
]1]
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please Read Carefully The only undertakings of the General Electric Company (GE) respecting information in this document are contained in the contract between the company receiving this document and GE.
Nothing contained in this document shall be construed as changing the applicable contract. The use of this information by anyone other than a customer authorized by GE to have this document, or for any purpose other than that for which it is intended, is not authorized. With respect to any unauthorized use, GE makes no representation or warranty, and assumes no liability as to the completeness, accuracy or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.
GE Energy, Nucletir Revision Control Sheet Revision Date Description Rev. 0 (Draft)
March 08, 2007 Draft Report for Customer Review RevI March 15, 2007
'The calculated stress for Item 15 lower spring of Table I is revised.
Rev 2 March 21, 2007 Footnote 4 added to item 15 of Table I1 1Patge 14(~3
GE Energy, Nuclear
- 1. SCOPE AND OBJECTIVE This summary report provides results of the intergranular stress corrosion cracking (IGSCC) evaluation of Alloy X-750 components of the shroud repair other than the replacement upper support stabilizer and tie rod nut (herein, called the other X-750 components). The results of this evaluation provide a basis for In-Service-Inspection recommendations for the other X-750 components. The components evaluated in this task are shown in Figure i.
- 2. IGSCC EVALUATION 3] The maximum principal tensile stress (P,,, + Ph + Q + F) of the components are calculated using hand calculation method. Where necessary appropriate stress concentration factors (SCFs) are considered in the calculations.
In general, for the calculations involving screw threads the SCF of ((
)) has been considered. The SCFs for the other components are obtained from handbooks. The yield strength of ((
)) psi for the X-750 material (ASTM B637 UNS N07750 Type 3) has been used in the calculations.
- 3. EVALUATION RESULTS The maximum principal tensile stresses (P,, + Ph, + Q + F) and the associated stress ratios are tabulated in Table 1.
Pa.ge 2 o1 3
[t (GE Energy, Nuclear Figure 1 - Scope of IGSCC Evaluation (Other X-750 Components) j 1]
Page 3 of 3
GE Energy, Nuclear Table 1 - "Other X-750 Components"- Vertical and Horizontal Load Paths (Other than the Replacement of Upper Support Stabilizer and Tie Rod Nut)
Calculated No.
Assembly Components FEA Stress Sy Ratio Note Name (Pm+Pb+Q+F) 2 3
4 5
6 10 11 121 131 1,2,3 14 15 II 4 Note I. The calculated stress is based on the initial bolt torque value of [
))ft-lbs.
- 2. For the calculations involving screw threads the SCF = ((
)) have been considered.
- 3. A repair that retains the torsion arm function will be implemented in conjunction "with stabilizer support replacement.
4ý For the lower spring, tthe lowest CMTR value f'or S, at 550"F is ((
))psi. The actual stress ratio using this CMTR S,, is [
]
Paige 4 oI 3
o PILGRIM STATION REACTOR POWER Data from 90
,% Power 80-70 60-50 8
40 300 20-10-3/13 3/14 3/15 3/16 3/17 3/18 3/19 3/20 3/21 3/22 3/23
'PI' Data readings collected every 10 minutes.