L-09-179, Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods
ML091950627 | |
Person / Time | |
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Site: | Davis Besse ![]() |
Issue date: | 07/13/2009 |
From: | Allen B FirstEnergy Nuclear Operating Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
L-09-179, TAC ME0477, TAC ME0478 | |
Download: ML091950627 (136) | |
Text
FENOC F0-IO 5501 North State Route 2 FirstEnergyNuclear OperatingCompany Oak Harbor,Ohio 43449 Barny S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 July 13, 2009 L-09-179 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Response to Requests for Additional Information Related to Alternative Dissimilar Metal Weld Repair Methods (TAC Nos. ME0477 and ME0478)
By correspondence dated January 30, 2009, FirstEnergy Nuclear Operating Company (FENOC) submitted alternatives to requirements associated with reactor vessel nozzle, reactor coolant pump nozzle, and reactor coolant piping weld repairs for the Davis-Besse Nuclear Power Station.
By letters dated June 11 and June 15, 2009, the Nuclear Regulatory Commission (NRC) staff requested additional information to complete its review. Attachment 1 provides responses to the NRC's June 11 questions, as modified during a teleconference between FENOC and NRC staff on July 6, 2009. Attachment 2 provides responses to the NRC's June 15 questions, as modified during teleconferences on June 23 and July 6, 2009. FENOC's 10 CFR 50.55a Requests RR-A32 and RR-A33, Enclosures A and B respectfully, have been updated to correct cross-referencing errors, incorporate minor clarifications and improve readability. The reactor coolant pump inlet nozzles have also been deleted from Request RR-A32.
There are no regulatory commitments contained in this submittal. Commitments made on January 30, 2009 remain unchanged. If there are any questions or additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071.
Sincerely, Barry S. Allen
Davis-Besse Nuclear Power Station Letter L-09-179 Page 2 of 2 Attachments:
- 1. Response to 6/11/09 Request for Additional Information Related to Requests RR-A32 and RR-A33, Alternative Dissimilar Metal Weld Repair Methods.
- 2. Response to 6/15/09 Request for Additional Information Related to Requests RR-A32 and RR-A33, Alternative Dissimilar Metal Weld Repair Methods
Enclosures:
A. 10 CFR 50.55a Request Number RR-A32, Revision 0 B. 10 CFR 50.55a Request Number RR-A33, Revision 0 cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board
Attachment 1 L-09-179 Response to 6/11/09 Request for Additional Information Related to Requests RR-A32 and RR-A33, Alternative Dissimilar Metal Weld Repair Methods Page 1 of 16 By letter dated June 11, 2009, the Nuclear Regulatory Commission (NRC) staff requested additional information related to requests for alternative dissimilar metal weld repair methods for reactor vessel nozzles, reactor coolant pump nozzles, and reactor coolant piping associated with the Davis-Besse Nuclear Power Station (DBNPS).. The FirstEnergy Nuclear Operating Company (FENOC) responses for DBNPS are provided below. The NRC staffs questions are presented in bold, followed by FENOC's responses.
REQUEST RR-A32 1.2 Section 4.0, page 3, states that the OWOL will be applied to a dissimilar metal weld (DMW) if the maximum depth of defects in the DMW is less than 50 percent through wall, and the FSWOL will be installed if the maximum depth of defects is greater than 50 percent through-wall. This description is not clear as to the exact locations of the flaws in the DMW by which the OWOL is applicable to be installed.
- a. The primary water stress-corrosion cracking (PWSCC) flaws are initiated from the inner surface of the DMW based on industry's operating experience. One of the bases for the overlay design is that the overlay will generate compressive stresses in the inner region of the pipe wall to mitigate the flaw initiation and growth. However, Section 4.0 does not clearly state the initiation site of the 50 percent through wall flaw. Specify the flaw location (i.e., where is the flaw initiated) for the application of the OWOL.
Response
The flaw initiation site is the inside surface of the dissimilar metal weld and susceptible material. Section 4 of Request RR-A32 has been revised to specify that inside surface connected planar flaws less than 50 percent through-wall allow the use of optimized weld overlay.
- b. In addition, the staff has identified the following scenarios: (1) if a 50 percent through wall flaw is detected inside the DMW during the pre-installation inspection, (but is not connected to the inside surface of the pipe (i.e., an embedded flaw), discuss which weld overlay, OWOL or FSWOL, will be installed; (2) if the embedded flaw is greater than 50 percent through wall which means that a portion of the flaw is located in the outer 50 percent region and a portion of the flaw is located in the inner 50 percent region of the pipe wall thickness, discuss which overlay (OWOL or FSWOL) will be installed; (3) if the embedded flaw is less than 50 percent through wall and is located in the outer 50 percent region of the pipe wall thickness, discuss which overlay, OWOL or FSWOL, will be installed; and (4) if the embedded flaw is less than 50 percent through wall L-09-179 Page 2 of 16 and is located in the inner 50 percent region of the pipe wall thickness, discuss which weld overlay, OWOL or FSWOL, will be installed.
Response
In general, embedded flaws will be evaluated in accordance with the rules of American Society of Mechanical Engineers (ASME)Section XI. Unacceptable flaws will be repaired in accordance with the'requirements of IWA-4000. Either an Optimized Weld Overlay (OWOL), as described in Request RR-A32, or a Full Structural Weld Overlay (FSWOL), as described in Request RR-A33, may be used, provided the embedded flaw. is bound by the design assumptions made in the applicable overlay (OWOL or FSWOL) design. The following responses are provided for each scenario.
Response to (1): If a 50 percent through-wall flaw is detected inside the DMW during the pre-installation inspection, but is not connected to the inside surface of the pipe (i.e., an embedded flaw), a flaw evaluation will be performed to the requirements of IWA-3300 and IWB-3640 of ASME Code, Section Xl. If the flaw is found acceptable for the operating period, an OWOL may be applied. If the flaw is judged to be unacceptable, a FSWOL will be applied.
Response to (2): If the embedded flaw is greater than 50 percent through-wall, which means that a portion of the flaw is located in the outer 50 percent region and a portion of the flaw is located in the inner 50 percent region of the pipe wall thickness, an IWA-3300 analysis and an IWB-3640 analysis will be performed. If the flaw is acceptable for continued operation, an OWOL may be applied. If the flaw is judged to be unacceptable, a FSWOL will be applied.
Response to (3): If the embedded flaw is less than 50 percent through-wall and is located in the outer 50 percent region of the pipe wall thickness, an IWA-3000 analysis and an IWB-3640 analysis will be performed. If the flaw is acceptable for continued operation, an OWOL may be applied. If the flaw is judged to be unacceptable, a FSWOL will be applied.
Response to (4): If the embedded flaw is less than 50 percent through-wall and is'located in the inner 50 percent region of the pipe wall thickness, an OWOL may be applied.
- c. If a flaw regardless of its depth is initiated from the outside surface of the pipe, discuss whether the OWOL is applicable.
Response
If flaws connected to the outside surface are either removed, reduced in size, or weld repaired and the flaw is bound by the design assumptions made in the overlay design, an OWOL may be applied.
L-09-179 Page 3 of 16 1.3 Attachment I to the relief request provides only background and technical basis rather than requirements for the weld overlay design. Nevertheless, Section A1.1 of Attachment I to the relief request discusses the pre-installation inspection requirements. Please provide the pre-installation examination requirement in Section 5 of the relief request and Section A2.1 of Attachment 2 to the relief request.
Response
The pre-installation examination requirements were added to Section 5 of the request and introduction section of Attachment 2 to the request.
1.4 Figure 5-2 on page 6 shows that the proposed weld overlay does not cover the stainless steel weld between the safe end and the RCP pump nozzle. (a)
Confirm that the weld overlay will not cover the stainless steel weld, and (b) If the stainless steel weld will not be covered with the weld overlay, discuss whether the OWOL has sufficient length to support ultrasonic testing (UT) of the DMW.
Response
The weld overlay will not cover the stainless steel weld between the reactor coolant pump casing and the stainless steel pipe on the discharge of the reactor coolant pumps. The length of the weld overlay is sized to facilitate ultrasonic examination of the weld overlay.
RR-A32 Attachment I 1.5 Section A1.1, Page 2, 4 th paragraph, states that the OWOL thickness is based on the actual internal pressure, pipe loads, and the allowable flaw size criteria of American Society of Mechanical Engineers (ASME) Code Section Xl, paragraph IWB-3641. Specify the exact criteria or cite the specific subparagraph in IWB-3641 from specific edition or addenda of the ASME Code, Section Xl.
Response
Request RR-A32, Attachment 1, provides the background, general requirements, and technical bases for optimized weld overlays (OWOLs) as discussed in MRP-169, Revision 1. Criteria for design of an OWOL are provided in Section A2.2 of Attachment 2 to the request.
1.6 Section A1.2 discusses the improvement on residual stresses of the DMW following the OWOL installation. The licensee has committed to submit, prior to entry into Mode 4, a residual stress profile in the nozzle to show that crack initiation due to PWSCC is highly unlikely. However, in order to approve the relief request, the NRC staff needs to have the assurance that the residual stresses in the subject DMWs at DBNPS are acceptable to mitigate PWSCC.
The licensee has referenced MRP-169 which contains the results of residual stresses for the OWOL. Clarify whether the residual stress analysis performed for the generic OWOL in MRP-169 is applicable to the DMWs in the subject
Attachment 1 L-09-1 79 Page 4 of 16 nozzles in the DBNPS relief request. In the response, provide a comparison of the DMWs and nozzle configurations between the MRP-169 model and at DBNPS to show whether the MRP-169 residual stress analysis bounds the subject DMWs in the relief request.
Response
Section A1.2 provides the methodology for residual stress improvement as described in MRP-169, Revision 1. As noted in Section 2 of Attachment 2 to the request, a joint-specific residual stress analysis was performed for the Davis-:
Besse reactor coolant pump (RCP) discharge piping OWOL geometry. As a result, the MRP-169 models were not used to bound the Davis-Besse dissimilar metal weld residual stresses.
MRP-1 69, Revision 1 provides a methodology used in the residual stress analysis. However, the thickness, configuration of the component, inside diameter repair and amount of carbon steel surface area to be covered are specific to Davis-Besse and different than the MRP-169 examples. As a result, a direct comparison can not be made.
1.7 Section A1.3, Page 4, last paragraph, states that a flaw in the DMW extending into the outer 25 percent of the pipe wall would violate the design basis of the OWOL. (1) After the OWOL is installed, if a flaw is detected in the outer 25 percent region of the DMW wall thickness during the inservice inspection, discuss how the flaw will be dispositioned prior to plant restart because any flaw remaining in the outer 25 percent region of the DMW wall thickness would violate the design basis, and (2) Before the OWOL is installed, if a flaw is detected in the outer 25 percent region of the DMW wall during pre-installation inspection, discuss how the flaw will be dispositioned prior to overlay installation and discuss whether OWOL or FSWOL will be applied in this situation.
Response
(1) If an inside connected flaw is discovered in the outer 25 percent of the dissimilar metal weld base material during inservice inspection, the flaw will be evaluated against the overlay design basis to determine if the weld is acceptable for continued service. If not, repair or replacement activities will be performed in accordance with IWA-4000.
- (2) If an inside connected flaw is discovered in the outer 25 percent of the dissimilar metal weld base material during pre-overlay ultrasonic examination, either the flaw will be reduced to an acceptable size in accordance with IWA-4000 and/or a FSWOL will be applied.
RR-A32 Attachment 2
.1.8 Section A2.2, page 2, requires a certain flaw size be assumed in the design analysis and crack growth calculations. However, Section A2.2, Page 3, states that if inspection in accordance with a full qualification to the modified L-09-179 Page 5 of 16 requirements of ASME Code, Section Xl, Appendix VIII, Supplement 11 cannot be performed for both the axial and circumferential 50 percent through-wall flaws, four alternatives will be applied. The discussion regarding flaw sizing with respect to UT capability in Section A2.2 is confusing due to the "If statement" regarding the UT qualification. The staff needs to evaluate the design requirements that are being used for the OWOL.
- a. Please state the exact flaw assumptions used in the DBNPS OWOL design and flaw growth calculations based on the current understanding of qualified UT capability that will be used at DBNPS.
Response
The OWOL design assumes that an inside surface connected axial flaw is 100 percent through-wall. The design also assumes that the inside surface connected circumferential flaw is 75 percent through-wall.
- b. State the size of the flaw that the current UT is qualified to detect after OWOL installation at DBNPS and provide the technical basis to support the UT qualification.
Response
The modified requirements to ASME Code Section XI, Appendix VIII, Supplement 11, as outlined in Attachment 5, will interrogate the outer 50 percent of the base material for circumferential flaws and the outer 25 percent of the base material for axial flaws. FENOC is aware that the Performance Demonstration Initiative (PDI) qualification protocols for detecting circumferential flaws in the outer 50 percent have been reviewed by the NRC and Pacific Northwest National Laboratory (PNNL) at the Electric Power Research Institute (EPRI)
Nondestructive Examination (NDE) Center in February 2009 and found acceptable for use. Attachment 1 and Figure A2-2 require axial flaws in the outer 25 percent of the base material and circumferential flaws in the outer 50 percent of the base material be detected by the ultrasonic examination. Attachment 5 revises paragraph 1.1 (d)(1) of Supplement 11 to decrease the flaw size used in PDI qualifications from 75 percent to 50 percent through-wall from the inside surface. This change increases the qualified examination depth and will ensure that the ultrasonic examination procedure is qualified to detect circumferential flaws in the outer 50 percent of the base material. There is no change in the qualification to detect axial flaws as the original PDI qualification required flaws be at least 75 percent through-wall from the inside surface.
- c. It appears that Section A2.2 does not provide criteria for the location of the flaw (surface connected or embedded) under which OWOL is applicable to be installed. The licensee needs to discuss the factors/conditions by which the OWOL is applicable for installation, such as the location of the flaw (e.g., in the region of the pipe wall thickness and initiation site), the depth of the flaw, and the combination of thetwo factors. The licensee needs to incorporate, in Section A2.2 or some other section in Attachment 2 to the relief request, the factors/conditions/criteria by which the OWOL is applicable to be installed.
Attachment I L-09-179 Page 6 of 16
Response
As noted in Section A2.2(1) and (2), an OWOL may only be used for repair of flaws with a maximum depth of 50 percent through the original wall thickness of the item. These sections were revised to indicate that the flaw is inside surface connected and no greater than 50 percent through-wall.
1.9 Section A2.2, page 3. The third bullet (alternative) states that "... An additional design requirement is added to show that ASME Code Section Xl design criteria are met for a 100% through-wall axial flaw..." Specify the "additional" design requirement.
Response
The ultrasonic examination procedures, qualified to the modified requirements of ASME Code Section Xl, Appendix VIII, Supplement 11, are capable of detecting circumferential flaws in the upper 50 percent of the base material, but are only capable of detecting axial flaws in the upper 25 percent of the base material. As a result, a design requirement was'added Section A2.2 to show that ASME Code Section X1 design criteria are met for a 100 percent through-wall axial flaw. This paragraph has been revised to specify this design requirement.
1.10 Section A2.2, page 3. The fourth bullet (alternative) states that" ... An analysis of fatigue and PWSCC growth must demonstrate that any growth shall not impair the ASME Code Section Xl acceptance criteria for the OWOL at the end of the inspection interval ... " (a) Clarify whether the growth calculation is for the flaw growth in the DMW, in the OWOL, or in both components, and (b) It is not clear as to the exact acceptance criteria in the phrase..." impair the ASME Code Section Xl acceptance criteria... " The specific ASME subarticle with the edition and addenda of the ASME Code,Section XI that contains the acceptance criteria should either be cited or provided.
Response
The PWSCC growth calculation is for the Alloy 82/182 dissimilar metal weld. As noted in Section A2.2, Structural Sizing, the weld overlay must meet the IWB-3640 rules for allowable flaw sizes in austenitic piping. Reference to IWB-3640 has been added to this bullet. The 1995 Edition through the 1996 Addenda is applicable to Davis-Besse.
1.11 Section A2.2, Page 4, first paragraph, Residual Stress Analysis, states that thermal boundary conditions (wet or dry) will be considered in the residual stress analyses.
- a. Discuss whether water will be present inside the pipe when the OWOL is installed at DBNPS.
Response
The piping may be in either condition (water-backed or dry).
L-09-179 Page 7 of 16
- b. Discuss whether residual stresses are analyzed based on the actual condition (wet or dry) when the OWOL will be installed.
Response
The residual stress analysis assumed the piping was dry.
- c. The licensee states that the residual stress analysis assumes a conservative pre-overlay residual stress condition from the weld repair during construction. Provide the depth of the postulated flaw for the inside surface weld repair during construction that is assumed. in the residual stress analysis.
Response
A 25 percent wall thickness inside diameter repair was assumed in the residual stress analysis. Structural Integrity has performed an evaluation of 25 percent and 50,percent wall thickness inside diameter repairs for thick wall large diameter nozzles, which showed that the repair depth does not have a significant influence on post weld-overlay residual stress distributions. The analysis was presented to the NRC staff on April 9, 2009 and was agreed to as the basis for the NRC Phase IV OWOL mockup.
- d. Discuss whether the repair depth of the postulated flaw bounds the worst weld repair in the field.
Response
The RCP discharge piping dissimilar metal weld was a shop weld. Shop weld records, including weld repair history and repair depth, are not available on site.
As such, a 25 percent through wall inside diameter repair assumption was used for the residual stress analysis of the overlays to bound any recorded repairs. As noted in FENOC's response to RAI question 1.11 .c above, analyses forinside diameter repairs for thick wall large diameter nozzles (up to 50 percent through wall inside diameter repairs) show that the repair depth does not have a significant influence on post weld-overlay residual stress distributions.
As discussed during a July 6, 2009 teleconference, similar analyses were presented to the NRC staff on April 9, 2009, and it was agreed to as the basis for the NRC Phase IV OWOL mockup.
1.12 Section A2.3, page 5, third paragraph, Examination Requirements, states that
"...If 100 percent coverage of the required volume for axial flaws cannot be achieved, but essentially 100 percent coverage for circumferential flaws (100 percent of the susceptible volume) can be achieved, the examination for axial flaws shall be performed to achieve the maximum coverage practicable, with.
limitations noted in the examination report. The examination coverage requirements shall be considered to be met..."
- a. Clarify why 100 percent examination of the required volume for axial flaws cannot be achieved.
L-09-179 Page 8 of 16
Response
This statement was included to acknowledge the cast austenitic stainless steel (CASS) material associated with the reactor coolant pump inlet (which is no longer included in Request RR-A32) dissimilar metal weld as there are no ASME Section Xl, Appendix VIII, qualified ultrasonic examination techniques for the cast stainless steel portion of the examination volume. The reactor coolant pump discharge dissimilar metal weld does not contain CASS material.
- b. The staff notes that the detection of 50 percent through-wall axial flaws in the DMW after OWOL installation, has not yet been qualified as stated in Section A2.2 and the current UT technology does not provide reliable results for the examination of the CASS material from which the RCP nozzles are fabricated. In light of these issues, discuss the estimated coverage that will be achieved (i.e., maximum coverage practicable) for the examination of axial flaws in the required examination volume shown in Figure A2-2; and, discuss the estimated coverage that will be achieved for the examination of axial flaws in the DMW (i.e., the susceptible material) for the preservice and inservice examinations.
Response
An OWOL will not be applied to the reactor coolant pump inlet dissimilar metal weld. The reactor coolant pump discharge dissimilar metal weld does not contain CASS material.
- c. Provide estimated examination coverage for all nozzles and associated DMWs.
Response
The reactor coolant pump discharge OWOL is designed to permit ultrasonic examination of the examination volume shown in Figure A2-2 and approximately 100 percent coverage of the examination volume is expected.
1.13 Section A2.3, Page 6.
- a. The inspection schedule table on page 6 is confusing. Clarify why the table provides an inspection schedule for the "full structural" overlay even though Request RR-A32 is strictly related to the OWOL.
Response
The inspection table on page 6 has been deleted.
- b. Provide detailed requirements for preservice and inservice inspection regarding acceptance criteria for detected flaws in the OWOL and base metal, because the proposed requirements on page 6 of Section A2.3 are inadequate. The requirements should be similar to theinspection requirementsfor the FSWOL in Section Al.4(b), PreserviceInspection, and A1.4(c), Inservice Inspection, of Attachment I to Relief Request RR-A33.
L-09-179 Page 9 of 16
Response
The inservice inspection requirements outlined in Request RR-A32, Section A2.3, have been revised. The revised requirements are based on the methodology contained in Code Case N-770 for preservice and inservice inspection of welds mitigated with stress improvement. FENOC recognizes that Code Case N-770 is subject to rulemaking by the NRC and future inservice examinations will be in accordance with the rulemaking.
1.14 Section A2.3, Page 6.
- a. For FSWOL or OWOL of a cracked DMW (Category F), the proposed examination schedule is every 5 years. However, the inspection schedule in Section A1.4(c)(2) of Attachment I to Relief Request RR-A33 (for the FSWOL) requires UT during the first or second refueling outage following overlay application. Discuss the discrepancy.
- b. For OWOL of a cracked DMW (category F), the proposed examination schedule is every 5 years. This inspection schedule is not consistent with the inspection requirements of Section A1.4(c)(2) of Attachment I to Relief Request RR-A33 which requires UT during the first or second refueling outage following the overlay application. Provide technical basis to support the 5-year inspection schedule.
Combined response (a) and (b):
The inservice inspection requirements outlined in Request RR-A32, Section A2.3, have been revised. The revised requirements are based on the methodology contained in Code Case N-770 for the inservice inspection of welds mitigated with stress improvement. FENOC recognizes that Code Case N-770 is subject to rulemaking by the NRC and future inservice examinations will be in accordance with the rulemaking.
1.15 The footnote on Figure [A2-2] states that "...to a depth of the outer 50 percent (optimized weld overlay) of underlying material (A-B-C-D) ... " This statement is not consistent with the statements on page 3 of Section A2.2 in which it is assumed that the volumetric examination for the axial flaw may not be qualified for a depth of outer 50 percent of underlying material. Please revise the footnote to be consistent with the actual UT capability at DBNPS at the time of the submittal or response to this request for additional information, or clarify the discrepancy.
Response
Figure A2-2, including the footnote, has been revised to specify that the examination volume for axial flaws includes only the outer 25 percent of the underlying material.
1.16 The RCP nozzle is made of CASS material and UT of CASS material has not yet been qualified to the requirements of ASME Code,Section XI. For the FSWOL design, the staff has provided licensees with two options to compensate for L-09-179 Page 10 of 16 the inadequacy of the current UT capability. Licensee may assume either 100 percent postulated flaw in the DMW (Option 1) or a 75 percent flaw but increase the DMW inspection frequency (Option 2).
Response
An OWOL will not be applied to the reactor coolant pump inlet dissimilar metal weld (DMW). The reactor coolant pump discharge DMW does not contain CASS material.
- b. Discuss the procedures that will be used to perform UT of the DMW from the CASS pump nozzle side.
Response
An OWOL will not be applied to the reactor coolant pump Inlet dissimilar metal weld. The reactor coolant pump discharge dissimilar metal weld does not contain CASS material.
1.17 Discuss whether the same welding sequences, heat input, interpass cooling temperatures, number of weld heads, and weld head travel directions for the original dissimilar butt weld fabrication and overlay installations will be included in the finite element model to analyze the residual stresses.
Response
The residual stress analyses include the heat efficiency factor associated with the actual welding process, thermal boundary conditions (wet or dry), weld progression direction, and interpass temperature limits to be employed during the actual overlay welding process.
RR-A32 Attachment 3 1.18.1 Section A3-1(b) states that the maximum area of a weld overlay using the ambient temperature temper bead welding over the ferritic base material shall be 600 square inches. The maximum area that the staff has approved for the FSWOL design is the 500 square inch area. The staff is concerned about the potential distortion and cracking with large welded area on the ferritic nozzle.
The industry has provided stress analyses to demonstrate the acceptability of the 500 square-inch area, but has not provided a stress analysis for the 600 square-inch area. The licensee states that the current industry analysis for the 500 square-inch area would support the proposed 600 square-inch area.
- a. Provide a technical justification of whether and how the results of the stress analysis for the 500 square-inch area can be extrapolated for the 600 square-inch area. If a plant-specific analysis is performed to support the proposed 600 square-inch area on the ferritic nozzle, a finite element analysis should be performed to demonstrate that the residual stresses in the nozzle are acceptable and that the nozzle will not be distorted L-09-179 Page 11 of 16 significantly. The analysis should consider necessary loadings, including bending moments and thermal expansions. The ASME Code Section III stress allowables will not be exceeded with a weld area of 600 square inches. This analysis should be submitted for staff review.
Response
Final design has determined that the ambient temper bead weld area will be less than 700 square inches over the carbon steel elbow surface. EPRI Report 1011898, November 2005, "RRAC Code Justification for the Removal of the 100 Square Inch Temper Bead Weld Limitation" concludes with the following statement: "The restriction on surface area of repairs should be increased to 500 in2 based on the results of analyses and testing performed to date. The Code should provide an option to users to justify repairs beyond 500 square inches by additional analysis and evaluation." In accordance with this report, a document summarizing the results of two or more residual stress analyses of different surface areas over the ferritic material will be prepared. These results will be used to illustrate that different area coverages have a negligible impact on the residual stress results and radial displacements (i.e., variations on the order of tens of mils or less) when comparing the pre-overlay component to the post-overlay component. This summary document will reference the calculations from which the residual stress and radial displacement information is extracted and will be forwarded to the NRC as discussed within Commitment 1 attached to FENOC's correspondence dated January 30, 2009.
- b. The 600 square-inch area will be applicable to the weld material deposited on the carbon steel elbow. The model in the industry analysis for the 500 square-inch area is a straight pipe. An elbow may present different stress distribution and there is a potential for stress risers with the overlay material on the elbow. Provide the basis of how the current 500 square-inch area analysis is applicable to the subject elbow.
Response
The residual stress and radial displacement is determined at the DMW using a computer model with the same component geometry as the weld overlay application. The elbow configuration and the cladding are modeled. The residual stress and radial displacement is evaluated comparing the pre-weld overlay component to the post-weld overlay component. The areas the model examines includes the DMW and surface area deposited over the carbon steel for at least two selected different area coverages on the carbon steel. The residual stress analysis uses the same component geometry as the ferritic base material to which the ambient temper bead process is to be applied. The residual stress is shown to be beneficial for the increased overlay size, both length and thickness, and the radial displacement is shown to be insignificant with a negligible difference as a result of increased overlay length or thickness.
L-09-179 Page 12 of 16
Clarify whether the current 500 square-inch area analysis contains stainless steel cladding on the inside of the pipe and if not, justify the applicability of the current analysis. The 600 square-inch area question also applies to Relief Request RR-A33.
Response
The residual stress analysis includes the stainless steel cladding on the ferritic components.
RR-A32 Attachment 5: Performance Demonstration Initiative (PDi) 1.19 Paragraph 1.1(d)(1) of Supplement 11 requires that all cracks must extend at least 75 percent through-wall from the inside surface of the pipe and may extend to 100 percent through the base metal. The proposed alternative requires flaws to extend at least 50 percent through-wall from the inside surface. However, RR-A32 Attachment 1, page 1, 6 th paragraph, states that nondestructive examination qualification for axial flaws shall be done to the current requirements from Appendix VIII, Supplement 11 for a 75 percent through-wall flaw. Clarify the discrepancy regarding the UT qualification for the axial flaw size between requirements in Attachment I and Attachment 5.
Response
Request RR-A32 Attachment 1 and Figure A2-2 require axial flaws in the outer 25 percent of the base material and circumferential flaws in the outer 50 percent of the base material be detected by the ultrasonic examination. Attachment 5 paragraph 1.1 (d)(1) of Supplement 11 was revised to decrease the flaw size used in PDI qualifications from 75 percent to 50 percent through-wall from the inside surface. This change increases the qualified examination depth and will ensure that the ultrasonic examination procedure is qualified to detect circumferential flaws in the outer 50 percent of the base material. There is no change in the qualification to detect axial flaws as the original PDI qualification required flaws be at least 75 percent through-wall from the inside surface.
1.20 Paragraph 2.2 of Supplement 11 requires that for flaws in the base grading units, the candidate shall estimate the length of that part of the flaw that is in the outer 25 percent of the base wall thickness. The proposed alternative requires "...50 percent of the base metal wall thickness..." Clarify whether the proposed wording should be revised to read "outer 50 percent" of the base metal wall thickness.
Response
The proposed alternative to Paragraph 2.2(d) of Supplement 11 (Attachment 5 of this request) was revised to read:
"(d) For flaws in base metal grading units, the candidate shall estimate the length of that part of the flaw that is in the outer 50 percent of the base metal wall thickness."
L-09-179 Page 13 of 16 1.21 The proposed alternative to Pa-rgraph 3.2 of Supplement 11 requires that
"...50 percent [through]-base-metal position..." Clarify whether the alternative should be revised to read "... The length of base metal cracking is measured at the 50 percent through-base-metal position from the inside surface of the pipe/dissimilar metal weld..."
Response
The proposed alternative to Paragraph 3.2(a) of Supplement 11 (Attachment 5 of this request) was revised to read:
"(a) The RMS error of the flaw length measurements, as compared to the true flaw lengths, is less than or equal to 0.75 inch. The length of base metal flaws is measured at the 50 percent through-base-metal position."
1.22 The alternative is silent on the requirements for the representative mockups, base materials, weld material, weld butter, and overlay material that will be used for the performance demonstration test specimens. Provide the requirements for the representative mockups, base material, and overlay material for the performance demonstration test specimens. Specifically:
- a. Discuss the mockup configuration (e.g., pipe diameter) and general requirements;
- b. Discuss the fabrication of the mockup;
- c. Discuss whether cast austenitic stainless steel materials are used in mockup;
- d. Discuss whether the RCP nozzles are addressed by the mockups used in the qualification.
- e. Discuss the differences, if any, between the mockups and the RCP nozzles in the field. If there are differences, discuss why the differences are acceptable to qualify the ultrasonic examination per Performance Demonstration Initiative (PDI).
Response
Examination of OWOLs is an extension of the existing ASME Appendix VIII, Supplement 11, PDI Program for the examination of full structural weld overlays.
The only difference is that the qualified examination depth has been extended from the outer 25 percent of the base material for full structural weld overlays to the outer 50 percent of the base material for optimized weld overlays. Existing PDI protocol for mockups and the qualification of the ultrasonic procedures for field use has not changed from previously approved requirements for full structural weld overlays. FENOC understands that this program, including an extension of the program to OWOLs, has been reviewed by the NRC and PNNL.
L-09-179 Page 14 of 16 REQUEST [RR-A331 2.2 Figure 5-3 shows the proposed FSWOL covering the core flood nozzle, the DMW, and safe end. The figure does not show the weld that joins the safe end with the pipe which is also not shown. Clarify whether the proposed FSWOL will cover the weld that joins the safe end and the pipe as well as cover a part of the core flood pipe. This question also applies to Figure 5-4 regarding the cold-leg drainline configuration.
Response
The full structural weld overlay will cover only the nozzle to safe end weld. The safe end to core flood pipe weld is not affected by the overlay. Only the nozzle to elbow weld will be covered in the cold leg drain line application.
RR-A33 Attachment'!
2.3 Section A1.2.2(c)(1) states that for P-No. 1 base materials, the Construction Code post weld heat treat exemptions permitted for circumferential butt welds may be applied to exempt the weld overlay from post weld heat treat with the following clarifications. Section A1.2.2(c)(1)(a) states that the nominal weld thickness is defined as the maximum overlay thickness applied over the ferritic base material. Section A1.2.2(c)(1)(b) states that the base material thickness is defined as the maximum thickness of the ferritic material where the overlay is applied. The staff has not accepted the exemption for the post weld heat treatment at the present as described in these sections. Provide either justification for these sections or remove them from RR-A33 Attachment 1.
Response
Section A1.2.2(c) has been revised to require the use of ambient temper bead welding.
2.4 Section A1.2.2(d)(3) states that "...The filler material used shall meet the minimum requirements for delta ferrite..." Discuss the minimum requirements for delta ferrite. Also there is no identification of the weld material. The staff suggests that the wording on Section A2.1(d)(3) from Attachment 2 of Relief Request RR-A32 be used in Section AI.2.2(d)(3).
Response
The delta ferrite requirements contained in Request RR-A32 Section A2.1 (d)(3) have been included in Request RR-A33 Section A1.2.2(d)(3). The specific stainless steel weld material type to be used will be evaluated and selected upon completion of the investigation into hot cracking issues at other facilities, as discussed in FENOC's response to RAI question 2.12 L-09-179 Page 15 of 16 2.5 Section A1.3(a)(5) states that the depths associated with the [postulated flaw]
lengths are specified in A1.3(a)(3) and A.1.3(a)(4). However, Section A1.3(a)(3) does not exist and Section A1.3(a)(4) does not provide the flaw depth. Also Sections A1.3(a)(1) and A1.3(a)(2) do not exist in Section A1.3. Clarify.
Response
The paragraph numbering under Section Al.3(a) was incorrect. Request RR-A33 has been revised to correct the numbering scheme.
2.6 Section A1.3(a)(8) states that "...any inside-surface-connected planar flaw found by the overlay preservice inspection of Al.4(b) that exceeds the depth of (3), (4) or (5) above..." Sections A1.3(a)(3), (4), and (5) either do not exist or do not pertain to the flaw depth. Clarify.
Response
The paragraph numbering under Section A1.3(a) was incorrect. Request RR-A33 has been revised to correct the numbering scheme.
2.7 On page 8, clarify whether "Inservice Inspection" should be identified as "(c)
Inservice Inspection".
Response
"Inservice Inspection" should have been " (c) Inservice Inspection." Request RR-A33 has been revised to correct this error.
2.8 Section A1.4(b)(2) states that "...Planar flaws in the outer 25 percent of the base metal thickness shall meet the design analysis requirements of 2(b)..."
Section 2(b) does not exist in Attachment I of RR-A33. Clarify the discrepancy.
Response
The paragraph reference in A1.4(b)(2) should have been to A1.3. Request RR-A33 has been revised to correct this reference.
2.9 Section A1.4(c)(2) references A1.3(a)(3) which does not exist. Clarify.
Response
The paragraph numbering under Section A1.3(a) was incorrect. Request RR-A33 has been revised to correct the numbering scheme.
2.10 Section A1.4(c)(8) includes two options to handle the problems in UT of cast austenitic stainless steel components (i.e., RCP nozzles). Option 1 is to assume a 100 percent initial flaw in the DMW. Option 2 is to assume a 75 percent initial flaw in the DMW with an increase inspection schedule. The staff allows either option to be implemented -by licensees. However, as it is written in Section A1.4(c)(8), it is not clear which option was chosen for the weld overlay at Davis-Besse. Revise Section A1.4(c)(8) to identify the option that will be used at Davis-Besse.
L-09-179 Page 16 of 16 Response.:
Section A1.4(c)(8) has been deleted from Request RR-A33, Attachment 1, and the inservice inspection requirements revised. The inservice inspection frequency is determined based on the methodology contained in Code Case N-770 for the inservice inspection of welds mitigated by full structural weld overlay as described in Request RR-A33, Section A1.4(c)(4). Code Case N-770 recognizes the inability to interrogate the cast stainless steel material and provides additional requirements for the inservice inspection frequency. FENOC recognizes that Code Case N-770 is subject to rulemaking by the NRC and future inservice examinations will be in accordance with the rulemaking.
RR-A33 Attachment 2 2.11 [RR-A33] Attachment 2 provides a comparison of the requirements in Supplement 11 of the ASME Code, Section Xl to the proposed PDI program.
The PDI program discussed in RR-A33 Attachment 2 appears to be for the OWOL design because some requirements discuss 50 percent through wall flaws instead of 75 percent through wall flaws. However, Relief Request RR-A33 is, specifically for the FSWOL design. Explain why the PDI program for the OWOL design is presented in the FSWOL relief request.
Response
Examination of OWOLs is an extension of the existing ASME Appendix VIII, Supplement 11, PDI Program for the examination of FSWOLs. The PDI program for the OWOL design decreases the flaw size used in PDI qualifications from 75 percent to 50 percent through-wall from the inside surface. As this change increases the qualified examination depth, it bounds the examination requirements for FSWOLs.
General Comments 2.12 During recent weld overlay campaigns, some licensees have experienced hot cracking in the first Alloy 52M layer covering the stainless steel buffer layer on the stainless steel safe end and pipe segment. Discuss whether a stainless steel buffer layer will be applied on the safe end or pipe. Discuss measures that will be implemented to prevent hot cracking from occurring during overlay installation at DBNPS.
Response
A stainless steel buffer layer is planned to be applied to the stainless steel safe end or nozzle. FENOC is also monitoring the investigation taking place to review the hot cracking issue experienced at another site, and reviewing the lessons-learned for applicability.
Attachment 2 L-09-179 Response to 6/15/09 Request for Additional Information Related to Requests RR-A32 and RR-A33, Alternative Dissimilar Metal Weld Repair Methods Page 1 of 26 By letter dated June 15, 2009, the Nuclear Regulatory Commission (NRC) staff requested additional information related to requests for alternative dissimilar metal weld repair methods for reactor vessel nozzles, reactor coolant pump nozzles, and reactor coolant piping associated with the Davis-Besse Nuclear Power Station (DBNPS). The FirstEnergy Nuclear Operating Company (FENOC) responses for DBNPS are provided below. The NRC staffs questions are presented in bold, followed by FENOC's responses.
REQUEST RR-A32 1.1 Please provide following information for the staff to perform an independent analysis of the overlaid RCP nozzles:
- a. Dimensions (axial and diameter) of the RCP inlet and discharge nozzles, dissimilar metal welds (DMW), butter, pipe elbow, safe end and stainless steel weld at the RCP discharge nozzles, and pipe cladding. The drawing should include bevel and weld land details.
Response
Dimensions used to generate the finite element models for the reactor coolant pump (RCP) discharge piping DMW are shown in the following three figures, Figures 1 through 3.
CD1) 0(6
-4; I+)
Figure 1. Reactor Coolant Pump Discharge Nozzle Dimensions Used
C:)
-,(0 CD)
IRigure 2. Reactor Coolant Pump Discharge Nozzle, Safe End, and Weld Dimensions Used
a1) ,
CDP 0
-4 CD" 0
O')
[7]
. j . .. ____.....18-5_....7'"'.
/-- .'*As-Modeledi [A-MOdele.1"0
... , > 3] *",
[7] , 0 /
._ I - . -
S/ /
V7]
Figure 3. Reactor Coolant Pump Discharge Safe End, Safe End-to-Piping Weld, ID Weld Repair, and Attached Piping Dimensions Used L-09-179 Page 5 of 26
- b. Geometry, material properties, locations, and process steps of repairs made, if any, in the Alloy 82/182 DMW, the adjacent nozzle, or safe end, prior to weld overlay installation.
Response
- The RCP discharge piping DMW consists of stainless steel A-376 Type 316 piping welded to an A-516 Grade 70 Carbon Steel 24 degree elbow using Alloy 82/182 weld materials. The carbon steel elbow is cladded.
" Base material and weld geometry is described in FENOC's response to RAI question 1.1.a.
- The material properties for the base material and weld are provided in FENOC's response to RAI question 1.1.e.
- As discussed during a July 6, 2009 teleconference, the RCP discharge piping DMW was a shop weld. Shop weld records, including any weld repair locations and process steps, are not available on site.
- c. OWOL geometry such as thickness and length (if unavailable at this time, provide recommended/design overlay geometry).
Response
The minimum OWOL weld dimensions for the RCP discharge piping are:
ILocation Thickness (inches)
Length (inches) from Diýýý 0.6543 3.4587 1 I
).3800 1 3.9932
Response
The minimum FSWOL weld dimensions for the RCP discharge piping are:
Location Thickness Length (inches) from DMW (inches)
Elbow Side 1.0097 3.4587 Safe End Side 1.0097 4.0024 The minimum FSWOL weld dimensions for the RCP inlet nozzle are:
Location Thickness Length (inches) from DMW (inches)
Elbow Side 1.117 2.80 Nozzle Side 1.117 3.19 L-09-179 Page 6 of 26
- e. Materials and material properties to be used (full stress-strain curves used in residual stress analysis if possible; yield and ultimate strengths for each material are needed at a minimum).
Response
The configuration of the RCP discharge piping is shown in Figure 5-1 within Request RR-A32.
MATERIALS RCP Outlet Nozzle to Safe End Safe End Safe End to Elbow Clad Nozzle Weld Elbow Weld A-351 SS Type 316 A-376 Alloy 82/1822 A-516 SA240-304L Grade CF8M (Assumed)' Type 316 Grade 70 1 Stainless Steel (SS) Type 316 will be treated as SA-376 Type 316 2Alloy 82/182 elastic properties are equivalent to Alloy 600 Properties used in the overlay design for these materials are listed in the following tables, Tables 1 through 10.
L-09-179 Page 7 of 26 Table 1 Elastic Properties for A-376, Type 316, A-351 Grade CF8M, A-336 Grade F8M, SA-403 WP 316 (16Cr-12Ni-2Mo)
Young's Mean Thermal Thermal Conductivity Specific Heat 2 Temperature Modulus Expansion (OF) (x10 6 psi) (xl0"6 fnjin/*M (x10"4 Btu/sec-in-'F) (Btu/lb-'f) 70 28,3 8.5 1.90 0.121 100 28.1' 8.6 1.92 0,121 150 27.9' 8.8 1.99 0,124 200 27.6 8.9 2.04 0.124 250 27.3' 9.1 2.11 0,127 300 27.0 9.2 2.15 0.127 350 26,8' 9.3 2.20 0.128 400 26.5 9.5 2.27 0.129 450 26.2' 9,6 2.31 0.130 500 25.8 9.7 2.36 0.130 550 25.6' 9.8 2.43 0.133 600 25.3 9.8 2.48 0.133 650 25.1' 9.9 2.52 0.133 700 24.8 10.0 2.59 0.135 1100 22.1 10.5 3.01 0.141 15 003 18.1 10.8 3.40 0.145 25003 0.1 11.5 4.40 0.155 Density (p) = 0.283 lb/iib 3, assumed temperature independent.
Poisson's Ratio (u) = 0.3, assumed temperature independent.
Notes:
1 Interpolated 2 Specific Heat Values are derived from the equation shown in General Note (a) of Table TCD of the ASME Boiler and Pressure Code,Section II, Part D, Material Properties, 2001 Edition with Addenda through 2003.
Specific Heat - TC/(TD x density).
3 Values per Structural Integrity Calculation No. 0800777.302, Rev. 2, "Material Properties for Residual Stress Analyses, Including MISO Properties."
a IF = degree(s) Fahrenheit 0 psi = pounds per square inch a in = inch 0 Btu = British thermal unit a sec = second 6 lb = pound 0 in 3= cubic inch L-09-179 Page 8 of 26 Table 2 Elastic-Plastic Properties for A-376, Type 316, A-351 Grade CF8M, A-336 Grade F8M, SA-403 WP 316 (16Cr-12Ni-2Mo)
True True Temperature Strain Stress CF) (in/in) (psi) 0.0014982 42400 0,1300043 69800 70 0.2546138 97200 0'4219726 124600 0.6325849 152000 0.0012791 33000 0.0616081 52500 500 0.1421800 72000' 0.2692310 91500 0.4511647 111000 0.0011573 28700 0.0471341 48775 700 0.1211840 68850 0.2457186 88925 0.4321680 109000 0.0010407 23000 0.0262971 38000 1100 0.0768737 53000 0.1739465 68000 0.3357481 83000 0.0006630 12000 0.0301352 17250 1500 0.0772324 22500 0,1632721 27750 0.3037215 33000 0.0100000 1000 0.2543666 2000 2500 0.4621339 3000 0,7070397 - 4000 1 0.9840915 5000
- I U OF = degree(s) Fahrenheit U in = inch U psi =_pounds per square inch L-09-179 Page 9 of 26 Table 3 Elastic Properties for Alloy 82/182 Temperature Young's Mean Thermal2 Thernmal Conductivity Specific Heat Tmetre (OF)0 Moduluspsi) tx10'6 Expansion in/in/OF)
X4 (xl Btu/see-in-°F) (Btu/ib-0 F) 70 31.0 6,8 1.99 0.108 100 30.81 6,9 2.01 0.109 150 30,5' 7.0 2.06 0,111 200 30.2 7.1 2.11 0.113 250 30.0' 7.2 2.15 0,114 300 29.8 7.3 2,22 0.116 350 29.7' 7.4 2,27 0.116 400 29.5 7.5 2.34 0.118 450 293' 7.6 2.38 0.118 500 29.0 7.6 2.45 0.120 550 28.9' 7.7 2.50 0,121 600 28.7 7,8 2.57 0.123 650 28.5'- 7,8 2.62 0,123 700 28.2 7.9 2.69 0.125 1100 25.9 8.4 3.19 0,139 1500, 23.1 9,0 3.70 0.148 2500' 0,1 10.0 5.09 0.177 Density (p)= 0.300 lb/in 3, assumed temperature independent.
Poisson's Ratio (u) = 0.29, assumed temperature independent.
Notes:
1 Interpolated 2 Specific Heat Values are derived from the equation shown in General Note (a) of Table TCD of the ASME Boiler and Pressure Code,Section II,, Part D, Material Properties, 2001 Edition with Addenda through 2003.
Specific Heat - TC/(TD x density).
3 Values per Structural Integrity Calculation No. 0800777.302, Rev. 2, "Material Properties for Residual Stress Analyses, Including MISO Properties."
- OF = degree(s) Fahrenheit
- psi = pounds per square inch
" in = inch
- Btu = British thermal unit
- sec = second
- lb = pound
" in3 = cubic inch L-09-179 Page 10 of 26
.Table 4 Elastic-Plastic Properties for Alloy 82/182 True True Temperature Strain Stress (iF) (in/in) (psi) 0.0017581 54500 0.0626142 77125 70 0.1323668 99750 0.2410555 122375 0.3972410 145000 0.0016379 47500 0.0608769 67625 500 0.1300082 87750 0.2382802 107875 0.3943945 128000 0.0016596 46800 0.0622784 66350 700 0.1321471 85900 0.2412033 105450 0.3980922 125000 0.0017375 45000 0.0688026 62250 1100 0.1404333 79500 0.2499634 96750 0,4053648 114000 0.0012900 29800 0.1814980 41100 1500 0.2996116 52400 0.4484683 63700 0.6285114 75000 0.0100000 1000 0.2543666 2000 2500 0.4621339 3000 0,7070397 4000 1 0,9840915 5000 U *F = degree(s) Fahrenheit U in = inch U psi = pounds per square inch L-09-179 Page 11 of 26 Table 5 Elastic Properties for SA-516 Grade 70 (<4 inches thick, Carbon < 0.3%)
Temperature Young's Mean Thermal Thermal Conductivity Specific Heae Modulus Expansion NO (x10 6 psi) 0 (x10 4 Btu/sec-in-'F) (Btu/lb-'F) 70 29.5 6.4 8.13 0.103 100 29.3' 6.5 8.03 0,105 150 29.1' 6.6 7.89 0.108 200 28.8 6.7 7.78 0.112 250 28.6' 6.8 7.62 0,115 300 28.3 6.9 7.48 0.118 350 T50 7.0 7.31 0.121 400 27.7 7.1 7.15 0.123 450 27.5' 7.2 7.01 0.125 500 27.3 7.3 6.83 0.128 550 27.0' 7.3 6.67 0.130 600 26.7 7:4 6.48 0,132 650 26.1' 7.5 6.32 0.135 700 25.5 7.6 6.16 0.138 1100 18.0 8.2 4.84 0.171 15003 5.0 8.6 3.63 0,198 2500T 0.1 9.5 2.31 0.204 Density (p)= 0.283 lb/in 3, assumed temperature independent.
Poisson's Ratio (u)= 0.3, assumed temperature independent.
Notes:
1 Interpolated 2 Specific Heat Values are derived from the equation shown in General Note (a) of Table TCD of the ASME Boiler and Pressure Code,Section II, Part D, Material Properties, 2001 Edition with Addenda through 2003.
Specific Heat - TC/(TD x density)..
3 Values per Structural Integrity Calculation No. 0800777.302, Rev. 2, "Material Properties for Residual Stress Analyses, Including MISO Properties."
0 OF = degree(s) Fahrenheit 0 psi = pounds per square inch a in = inch 0 Btu = British thermal unit 0 sec = second 0 lb = pound 0 in = cubic inch L-09-1 79 Page 12 of 26 Table 6 Elastic-Plastic Properties for SA-516 Grade 70 (<4 inches thick, Carbon < 0.3%)
TmeaueTruc True T (meraur Strain Stress
( 0F)(iu/in) (psi) 0.0012881 38000 0.0031809 48250 70 0.0104401 58500 0.0374803 68M5 0.1224852 79000 0,0011355 31000 0.0021324 43000 500 0.0069050 55000 0.0303574 67000 0.1222991 79000 0.0010667 27200 0.0018781 40150 700 0.0056595 53100 0.0271289 66050 0.1222079 79000 0.001 1667 21000 0.0917411 27000 1100 0.1656717 33000 0.27 13432 39000 0.4143524 45000 0.0030000 15000 0,2558446 18750 1500 0.3673114 22500 0.4988409 26250 0.6504237 30000 0.0100000 1000 0.2543666 2000 25000.4621339 3000 0.7070397 4000
______________ 0.9840915 5000 U IF= degree(s) Fahrenheit U in = inch U psi = pounds per square inch L-09-179 Page 13 of 26 Table 7 Elastic Properties for SA-240-304L, SA-371 ER308L and. ER308L (18Cr-8Ni)
Young's Mean Tiermal Thermal Conductivity Specific Heat2 (TF)emxl0tuModulus Expansion (x1O"4 Btu/sec-in-'F) (Btu/lb-'F)
( 0) (X10 6 psi) (.X10-6Iinfi1I/
70 28.3 8.5 1,99 0.116 100 28.1' 8.6 2.01 0.117 150 27,91 8.8 2.08 0.120 200 27,6 8.9 2.15 0.122 250 27.3' 9.1 2.22 0.124 300 27.0 9.2 2.27 0.125 350 26.8' 9.3 2,34 0.127 400 26.5 9.5 2.41 0.129 450 26.2' 9.6 2.45 0.130 500 25.8 9.7 2.52 0,131 550 25.6' 9.8 2.57 0.132 600 25.3 9.8 2,62 0.133 650 25.11 9.9 2.69 0.134 700 24.8 10.0 2.73 0.135 1100 22.1 10.5 3.15 0.140 1500, 18,1 10.8 3.54 0.145 2500' 0.1 11.5 4.86 0.159 Density (p)= 0.283 lb/in3, assumed temperature independent.
Poisson's Ratio (u)=0.3, assumed temperature independent.
Notes:
1 Interpolated 2 Specific Heat Values are derived from the equation shown in General Note (a) of Table TCD of the ASME Boiler and Pressure Code,Section II,Part D, Material Properties, 2001 Edition with Addenda through 2003.
Specific Heat - TC/(TD x density).
3 Values per Structural Integrity Calculation No. 0800777.302, Rev. 2, "Material Properties for Residual Stress Analyses, Including MISO Properties."
- IF = degree(s) Fahrenheit a psi = pounds per square inch e in = inch a Btu = British thermal unit a sec = second
- lb= pound a in3= cubic inch L-09-179 Page 14 of 26 Table 8 Elastic-Plastic Properties for SA-240-304L, SA-371 ER308L and ER308L (18Cr-8Ni)
True True Temperature Strain Stress
(*F) (in/in) (psi) 0.0012367 35000 0.0777489 64750 70 0.1821409 .94500 0.3382732 124250 0.5503345 154000 0.0008527 22000 0.0358911 42750 500 0.1059492 63500 0.2314091 84250 0.4262954 105000 0.0008065 20000 0.0281096 40000 700 0.0908367 60000 0.2111270 80000 0.4075613 100000 0.0007421 16400 0.0138355 30050 1100 0.0519078 43700 0.1392265 57350 0.3044729 71000 0.0007182 13000 0.0652982 18250 1500 0.1354897 23500 0.2429079 28750 0.3950595 34000 0.0100000 1000 0.2543666 2000 2500 0.4621339 3000 0.7070397 4000 0.9840915 5000 U 'F = degree(s) Fahrenheit U in = inch psi = pounds per square inch L-09-179 Page 15 of 26 Table 9 Elastic Properties for Alloy 52M/1 52 Temperature Young's Mean Thermal Thermal Conductivity Specific Heat2 Modulus Expansion (xl0-4 (x10 6 psi) (x0"in/nF) Btulscc-in-) (1tuIb41) 70 30.3 7.7 1.57 0.107 100 30.11 7.8 1.62 0.108 150 29.8' 7.8 1.69 0.110 200 29.5 7.9 1.76 0.112 250 29.3 ' 7.9 1.83 0.114 300 29,1 7,9 1.90 0.116 350 29.0' 8.0 1.97 0.117 400 28.8 8.0 2.04 0.118 450 28.67 8.1 2.11 0.119 500 28,3 8.1 2.18 0.121 550 28.2' 8.1 2.25 0.122 600 28.1 8.2 2.31 0.123 650 27.9' 8.2 2.38 0.124 700 27.6 8.3 2.45 0.125 1100 25.3 8.5 3.03 0.135 1500 3 22.6 8.8 3.59 0.147 2500" 0.1 9.5 5.09 0.167 Density (p)= 0.293 lb/in 3, assumed temperature independent.
Poisson's Ratio (u)= 0,29, assumed temperatwre independent.
Notes:
1 Interpolated 2 Specific Heat Values are derived from the equation shown in General Note (a) of Table TCD of the ASME Boiler and Pressure Code,Section II, Part D, Material Properties, 2001 Edition with Addenda through 2003.
Specific Heat - TC/(TD x density).
3 Values per Structural Integrity Calculation No. 0800777.302, Rev. 2, "Material Properties for Residual Stress Analyses, Including MISO Properties."
" IF = degree(s) Fahrenheit
" psi = pounds per square inch
" in = inch
" Btu = British thermal unit
" sec = second b=pound lb,
- in = cubic inch L-09-179 Page 16 of 26
- , Table 10 Elastic-Plastic Properties for Alloy 52M/152 True True T (mperat)re Strain Stress
(°() n/in) (psi) 0.0016073 48700 0.0630592 75275 70 0.1421644 101850 0.2663752 128425 0.4441853 155000 0.0012898 36500 0.0396551 59125 500. 0.1033755 81750 0.2147115 104375 0.3873830 127000 0,0012500 34500 0.0354049 57125 700 0.0968184 79750 0.2076735 102375 0.3836597 125000 0.0012530 31700 0.0493023 50775 1100 0.1202071 69850 0.2373289 88925 0.4112380 108000 0.0012434 28100 0,2618302 44075 1500 0.4304344 60050 0.6289623 76025 0.8547593 92000 0.0100000 1000' 0.2543666 2000 2500 0.4621339 3000 0,7070397 4000 0.9840915- 5000 U IF = degree(s) Fahrenheit U in = inch U .psi = pounds per square inch L-09-179 Page 17 of 26
- f. Sequencing of welding, cladding or buttering and heat treatment of original Alloy 82/182 DMWs and safe ends, including assumed root pass grind-out and re-weld.
Response
As discussed during a July 6, 2009 teleconference, the RCP discharge piping dissimilar metal weld was a shop weld. Shop weld records, including weld sequences and repairs, are not available on site. Fabrication drawings indicate that the carbon steel elbow was buttered with Alloy 82/182 material prior to welding to the stainless steel pipe. The RCP discharge piping dissimilar metal weld was not heat treated following fabrication.
- g. Weld overlay pass direction and sequence forthe OWOL (1 weld head vs.
multiple weld heads, sequence of weld passes, and the direction of the weld pass).
Response
For the reactor coolant pump discharge piping optimized weld overlay, the weld pass progression will be 360 degrees orbital (welding in both directions) using two weld heads. Weld pass direction will begin on the elbow and progress towards the pump nozzle.
- h. Weld overlay materials, including extent and thickness of stainless steel buffer layer if any.
Response
The stainless steel buffer layer will be installed on the Stainless steel safe end portion of the weld joint, as shown in Figure 5-1 within Request RR-A32. The buffer layer will extend to the portions of the stainless steel materials in contact with the Alloy 52M overlay weld material.
The stainless steel buffer layer size and materials may change. The specific weld material type to be used will be determined and evaluated upon completion of the investigation into hot cracking issues at other facilities.
Response
The residual stress analysis assumes a weld pass heat input of 35 kilojoules/inch (kJ/in) and a heat efficiency of 80 percent for the reactor coolant pump discharge piping weld overlay.
The welding parameters may change based upon the investigation into hot cracking issues at other facilities L-09-179 Page 18 of 26
- j. Weld inter-pass cooling temperature.
Response
Maximum interpass temperature is 350 degrees Fahrenheit.
- k. Convective heat transfer coefficient used for outside diameter and inside diameter surfaces.
Response
A heat transfer coefficient of 5.0 Btu/hr-ft2 -OF at 70°F bulk temperature is used.
- Btu = British thermal unit 0 hr = hour
- ft2 = square foot a OF = degree(s) Fahrenheit I. In-process stress relieving heat treatment parameters.
Response
The weld overlays are not subjected to stress relief heat treatment.
REQUEST [RR-A331 2.1 a. Provide dimensions (axial and diameter) of the nozzles, DMWs, butter, pipe/elbow, safe-end, and pipe cladding for the core flood nozzles and cold-leg drain line nozzles.
Response
Dimensions used to generate the finite element models for core flood nozzles are shown in the following two figures, Figures 1 and 2.
CD.O (0 -4 0
kd4.3M6 (3 (toBncaMft
.4.
(3)
- 0) N) o-29-1(w PI R*-I-tir Cd20"1 (31
0D 0 0 --3 0-3CD 1-
[3] [3((31 1.603" lie 13] (As-Modeled]
70" i [31
[As.-Modele "
i~~ql=-';'*:~~3 / Tap""...er1Tae
[AS-Modeled)] , D~15.S,8, ..
!4o u.614"
[As-Mode~ledI l NozeSf d and W i
, (31 D-- 1 D=1121m
[3) i:! [a [3 * :" [,As.odeleid]
Figure 2. Core Flood Nozzle Safe End and Weld Dimensions L-09-179 Page 21 of 26 Dimensions used to generate the finite element models for the cold leg drain nozzles are shown in the following two figures, Figures 1 and 2.
P;71 F.~ -~ ~k a f2i 1-91
- n-va" P1 Ill 121 P1 (7) P1II 151 Figure, 1. Ci61d:cgl)rain NuzzleDimensions L-09-179 Page 22 of 26 Figliie2. Cold Leg Draiii N6zzlc safe Ed aid;Weld Dimensions L-09-179 Page 23 of 26
Response
Dimensions used to generate the finite element models for the reactor coolant pump suction nozzle dissimilar metal weld are shown in the following three figures, Figures 1 through 3.
(O Figure 1. RCP Suction Nozzle Dimensions L-09-179 Page 24 of 26 Figure 2. RCP Suction Nozzle Overall Weld Dimensions L-09-179 Page 25 of 26 Figure 3. Nozzle-to-Elbow Weld Preparation Dimensions L-09-179 Page 26 of 26
- b. In the design drawing please show whether stainless steel buffer layer will be installed.
Response
The stainless steel buffer layer will be installed on the stainless steel portions of the weld joints as shown in Figures 5-1 through 5-4 within Request RR-A33. The buffer layer will extend to the portions of the stainless steel materials in contact with the Alloy 52M overlay weld material.
The stainless steel buffer la*,er size and materials may change. The specific weld material type to be used will be determined and evaluated upon completion of the investigation into hot cracking issues at other facilities.
Davis-Besse Nuclear Power Station 10 CFR 50.55a Request Number RR-A32, Revision 0 Page I of 13 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. American Society of Mechanical Engineers (ASME) Code Component(s) Affected Components: Reactor Coolant Pump Discharge Piping Dissimilar Metal Welds Code Class: Class 1 Examination Categr: B-J Code Item Number: B9.11 Weld Numbers: Description.... Size Materials ..
RC-MK-B-59-1-SW143B Reactor Coolant Nominal Stainless Steel Pipe / Alloy 82-Pump 1-1 28 inch 182 Weld / Carbon Steel Elbow Discharge Piping ID RC-MK-B-44-1-SW69B Reactor Coolant Nominal Stainless Steel Pipe / Alloy 82-Pump 1-2 28 inch 182 Weld / Carbon Steel Elbow Discharge Piping ID RC-MK-A-61-1-SW69A Reactor Coolant Nominal Stainless Steel Pipe / Alloy 82-Pump 2-1 28 inch 182 Weld / Carbon Steel Elbow Discharge Piping ID RC-MK-B-56-1-SW143A Reactor Coolant Nominal Stainless Steel Pipe / Alloy 82-Pump 2-2 28 inch 182 Weld / Carbon Steel Elbow Discharge Piping ID Notes:
- Stainless Steel Pipe - A-376 Type 316 (Pý8)
Carbon Steel Elbow - A 516 Grade 70 (P-i) 24 degree elbow internally clad with SA 240-304L
- ID = Inside Diameter
- 2. Applicable Code Edition and Addenda American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI - 1995 Edition through 1996 Addenda
3. Applicable Code Requirement
- .IWA-4410(a) of ASME Code Section XI states:
"'Repair/replacement activities shall be performed in accordance with the Owner's Requirements and the original Construction Code of the component or system, except as provided in IWA-4410 (b), (c), and (d)."
RR-A32 Page 2 of 13 IWA-4410(b) of ASME Code Section XI states in part:
"Later Editions and Addenda of the Construction Code, or a later different Construction Code, either in its entirety or portions thereof, and Code Cases may be used, provided the substitution is as listed in IWA-4221 (b)."
IWA-4410(c) of ASME Code Section XI states:
"Alternatively, the applicable requirements of IWA-4600 may be used for welding and the applicable requirements of IWA-4700 may be used for heat exchanger tube plugging and sleeving."
ASME Code Section XI, Appendix VIII, Supplement 11 provides requirements for the qualification requirements for the ultrasonic examination of Overlaid Wrought Austenitic Piping Welds.
- 4. Reason for Request Dissimilar metal welds containing nickel welding alloys 82 and 182 have experienced primary water stress corrosion cracking in components operating at pressurized water reactor temperatures.
The FirstEnergy Nuclear Operating Company (FENOC) proposes to mitigate the primary water stress corrosion cracking susceptibility of the Davis-Besse Nuclear Power Station (Davis-Besse) reactor coolant pump outlet dissimilar metal welds by installing an optimized weld overlay (OWOL) on the reactor coolant pump dissimilar metal welds.
This approach provides an alternative to inspection alone as a means to assure the structural integrity of these locations. Inside surface connected planar flaws less than 50 percent through wall allow the use of optimized weld overlay. If inside surface connected planar flaws greater than 50 percent through wall are detected, FENOC intends to apply a full structural weld overlay for mitigation as noted in FENOC Alternative RR-A33, contingent upon authorization by the NRC.
Currently, there are no generically accepted criteria for a licensee to apply a full structural weld overlay or an optimized weld overlay to Alloy 82/182 weld material. The issue and addenda of ASME Code Section XI applicable to Davis-Besse does not contain requirements for weld overlays. Dissimilar metal weld overlays have been applied to components at Davis-Besse using the modified requirements of ASME Code Cases N-504-2 and N-638-1. However, since ASMIE Code Case N-504 (and its later versions) is written specifically for stainless steel pipe to pipe weld full structural overlays, and ASME Code Case N-638-1 contains unnecessary restrictions and requirements, an alternative is proposed. This request describes the requirements FENOC proposes to design and install optimized weld overlays on reactor coolant pump dissimilar metal welds.
- 5. Proposed Alternative and Basis for Use Pursuant to IOCFR 50.55a (a)(3)(i), FENOC proposes the use of the alternative described in Attachments 2, 3 and 5 to this request. This alternative is based in part on the methodology contained in ASME Code Case N-740-2.
Appendix VIII, Supplement 11 of the 1995 Edition, -1996 Addenda of ASME Code Section XI [reference 1] specifies requirements for performance demonstration of
RR-A32 Page 3 of 13 ultrasonic examination procedures, equipment, and personnel used to detect and size flaws in full structural overlays of wrought austenitic piping welds. Appendix VIII does not explicitly address optimized weld overlay applications. Relief is requested to allow use of the Performance Demonstration Initiative (PDI) program implementation of Appendix VIII for qualification of ultrasonic examinations used to detect and size flaws in the preemptive structural weld overlays of this request. The proposed modifications to Appendix VIII, Supplement 11 for use on optimized weld overlays are detailed in Attachment 5. Appendix VIII, Supplement 11 requires further qualification and modification for optimized weld overlay applications. Attachment 5 describes the proposed modifications to be implemented.
The use of the alternative described in Attachments 2, 3, and 5 is requested on the basis that the proposed requirements will provide an acceptable level of quality and safety.
ASME Code Case N-740-2 has been approved recently by the ASME Code Committee to specifically address full structural overlays on nickel alloy dissimilar metal welds.
ASME Code Case N-740-2 also incorporates the latest approved versions of ASME Code Case N-638-1. However, ASME Code Case N-740-2 has not yet been accepted by the NRC in Regulatory Guide 1.147. ASME Code Case N-504-3 has been conditionally accepted in Revision 15 of Regulatory Guide 1.147 with the condition that the provisions of ASME Code Section XI, Nonmandatory Appendix Q, Weld Overlay Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Weldments, must be met.
Electric Power Research Institute (EPRI) Materials Reliability Program Report MRP- 169
[reference 8] provides the basis and requirements for optimized weld overlay design.
Chapter 4 of MRP-169, Design Requirements, provides specific guidance on the design of overlays. Chapter 7 of MRP-169, Examination Requirements, also provides guidance on optimized weld overlay inspections. MRP- 169, revision 1, was submitted for NRC review and approval in April 2008. This submittal included responses to NRC staff submitted requests for additional information on the document which were also incorporated into MRP-169, revision 1.
FENOC proposes to use the alternative requirements for design, analysis and preservice and inservice inspection of preemptive weld overlays enumerated in MRP- 169, including the most recent revisions requested by the NRC, in accordance with Attachments 1 and 2.
Weld overlay materials, surface preparation, welding requirements, pressure testing, and acceptance examination shall be performed in accordance with Attachments 2 and 3 which are based on methodology contained in ASME Code Case N-740-2. This approach provides an acceptable method for preventing primary water stress corrosion cracking and for reducing defects that may be observed in these welds to an acceptable size. The use of weld overlay filler metals that are resistant to primary water stress corrosion cracking (for example, Alloy 52/52M), weld overlay procedures that create compressive residual stress profiles in the original weld, and post overlay preservice and inservice inspection requirements provide assurance that structural integrity is maintained for the life of the plant. The weld overlays shall also meet the applicable stress limits from ASME Code Section III. Crack growth evaluations for primary water stress corrosion cracking and fatigue of as-found (or conservatively postulated) flaws shall demonstrate that structural integrity is maintained.
Rupture of the large primary loop piping at Davis-Besse has been eliminated as the structural design basis. The effects of the weld overlay application on the leak-before-
RR-A32' Page 4 of 13 break analysis shall be evaluated to show the effects do not invalidate the conclusions of the existing design basis.
FENOC plans to perform a pre-overlay ultrasonic examination of the dissimilar metal Alloy 82/192 welds identified in Section 1. If no inside surface connected defects greater than 50 percent through wall are detected, FENOC plans to apply an optimized weld overlay to the dissimilar metal Alloy 82/182 weld. The requirements for the optimized weld overlay design and analyses are based upon M!RP-169 as described in Attachment 1.
Optimizedweld overlay implementation requirements are detailed in Attachments 2 and
- 3. The requirements of ASME Code Cases N-504-3 and N-638-1, as modified by ASME Code Section XI, Nonmandatory Appendix Q, are compared to the requirements proposed in the request for relief within Attachment 4. NDE qualification requirements are detailed in Attachment 5.
Any indications discovered during the pre-overlay ultrasonic examination that are not inside surface connected will be evaluated in accordance with the requirements of ASME Section XI, and if required, repaired in accordance with IWA-4000.
Schematic Configurationfor OWOL Locations Reactor CoolantPump Discharge Piping DissimilarMetal Welds The reactor coolant pump outlets (discharge) are fabricated from cast austenitic stainless steel and attached to 28-inch austenitic stainless steel piping which acts as a safe end. The piping is then attached to an elbow fabricated from carbon steel internally clad with stainless steel. The carbon steel elbow is buttered with Alloy 82/182 weld material. The dissimilar metal weld is fabricated from Alloy 82/182 weld metal.
'Weld Overlay CS Elbow" Safe Ený d Pump 0' SSCiadding Butter Notes:
- 1. Elbow - A-516, Grade 70, internally clad With SA240-304L
- 2. Safe End-A-376, Type 316
- 3. Cast Stainless Steel Pump Outlet (Discharge) - A-351-Grade CF8M, Type 316 Figure 5-1 Schematic Configuration for OWOL for Reactor Coolant Pump Outlets (Discharge)
RR-A32 Page 5 of 13 Suitability ofProposedPost Overlay Nondestructive Examination (NDE)
As a part of the design of the weld overlay, the weld length, surface finish, and flatness are specified to allow qualified ASME Code Section XI, Appendix VIII ultrasonic examinations, as implemented through the EPRI PDI Program, of the weld overlay and the required Volume of the base material and original weld. The examinations specified in this proposed alternative provide adequate assurance of structural integrity for the following reasons:
" The ultrasonic (UT) examinations to be performed with the proposed alternative are in accordance with ASME Code Section XI, Appendix VIII, Supplement 11, as implemented through the PDI. These examinations are considered more sensitive for detection of defects, either from fabrication or service induced, than either ASME Code Section III radiography or ultrasonic examination methods. Further, construction flaws have been included in the PDI qualification sample sets for evaluating procedures and personnel.
" ASME Code Section XI has developed acceptance criteria and evaluation methodology to be utilized with the results from these more sensitive examinations. They consider the materials in which the flaw indications are detected, the orientation and size of the indications, and ultimately their potential structural effects on the component. The acceptance criteria include allowable flaw indication tables for planar flaws (Table IWB-3514-2) and for laminar flaws (Table IWB-3514-3).
" A laminar flaw is defined in ASME Code Section XI as a flaw oriented within 10 degrees of a plane parallel to the surface of the component. This definition is applicable to welds and weld overlays as well as base materials. The standard imposed for evaluating laminar flaws in ASME Code Section XI is more restrictive than the ASME Code Section III standard for evaluating laminations. The Section XI laminar flaw standards, Table IWB-3514-3, are supplemented in Attachment 2 such that the total laminar flaw shall not exceed 10 percent of the weld overlay surface areaand no linear dimension of the laminar flaw shall exceed 3 inches. For weld overlay areas where examination is precluded by the presence of the flaw, it is required to postulate the area as being cracked.
" Any planar flaws found during either the weld overlay acceptance or preservice examinations are required to meet the preservice standards of ASME Code Table IWB-3514-2. In applying the planar flaw standards, the thickness of the component is defined as the thickness of the weld overlay and the issue of any flaws masked from examination is addressed as a part of the proposed alternative.
" Weld overlays for repair of cracks in piping are not addressed by ASME Code Section III. ASME Code Section III utilizes nondestructive examination procedures and techniques with flaw detection capabilities that are within the practical limits of workmanship standards for welds. These standards are most applicable to volumetric examinations conducted by-radiographic examination. Radiography (RT) of weld overlays is not practical because of the presence of radioactive material in the reactor coolant system and water in the pipes. The ASME Code Section III acceptance standards are written for a range of fabrication flaws including lack of fusion, incomplete penetration, cracking, slag inclusions, porosity, and concavity. However, experience and fracture mechanics have demonstrated that many of the flaws that would be rejected
RR-A32 Page 6 of 13 using ASME Code Section III acceptance standards do not have a significant effect on the structural integrity of the component. The proposed alternatives in Attachments 2 and 3 were written to specifically address weld overlays, and not only does this alternative adequately examine the weld overlays, but it provides more appropriate examinations and acceptance criteria than the staff imposed position.
The ASME Code Section XI acceptance standards are the logical choice for evaluation of potential flaw indications in post-overlay examinations, in which unnecessary repairs to the overlays would result in additional personnel radiation exposure without a compensating increase in safety and quality, and could potentially degrade the effectiveness of the overlays by affecting the favorable residual stress field that they produce. They are consistent with previous criteria approved by the NRC for weld overlay installations.
Weld overlays have been used for repair and mitigation of cracking in boiling water reactors for many years. In Generic Letter 88-01, the NRC approved the use of ASME Code Section XI inspection procedures for determining the acceptability of installed weld overlays. In addition, for a number of years the NRC has accepted various versions of ASME Code Case N-504 in Regulatory Guide (RG) 1.147 with no conditions regarding the use of ASME Code Section XI acceptance standards for determining the acceptability of weld overlays. ASME Code Case N-504 (and its later versions) was developed to codify the boiling water reactor weld overlay experience, and NRC approval is consistent with the NRC acceptability of boiling water reactor (BWR) weld overlays. Similarly, ASME Code Case N-638 was acceptable for use in RG 1.147 Revision 13 with no conditions and has been approved by the NRC for use in both boiling water reactor and pressurized water reactor (PWR) weld overlay installations using the ASME Code Section XI acceptance standards. The NRC staff found the use of the ASME Code Section XI, Appendix VIII, Supplement 11 acceptable for identifying both construction and service induced flaws in the Safety Evaluation Report (SER) for DC Cook Plant dated February 19, 2006 and tacitly approved the associated ASME Code Section XI acceptance criteria, Tables IWB-3514-2 and IWB-3514-3. The staff also accepted the use of Section XI acceptance standards in an SER dated July 21, 2004 for the Three Mile Island Plant, for disposition of flaws identified in a weld overlay by PDI qualified ultrasonic examinations, with additional restrictions similar to those proposed herein for regions in which inspection is precluded by the flaws.
Suitability of ProposedAmbient Temperature Temper Bead Technique The overlays addressed by this alternative shall be performed using ambient temperature temper bead welding in lieu of post weld heat treatment, in accordance with Attachment 3.
Research by the Electric Power Research Institute (EPRI) and other organizations on the use of an ambient temperature temper bead process using the machine gas tungsten arc welding (GTAW) process is documented in EPRI Report GC- 111050 [reference 3].
According to the EPRI report, repair welds performed with an ambient temperature temper bead procedure utilizing the machine gas tungsten arc welding process exhibit mechanical properties equivalent to or better than those of the surrounding base material. Laboratory testing, analysis, successful procedure qualifications, and successful repairs have all demonstrated the effectiveness of this process.
The effects of the ambient temperature temper bead welding process of Attachment 3 on mechanical properties of repair welds, hydrogen cracking, cold restraint cracking, and extent of overlay coverage of ferritic base metal are addressed in the following paragraphs.
RR-A32 Page 7 of 13 Mechanical Propertiesof Repair Welds The principal reasons to preheat a component prior to repair welding is to minimize the potential for cold cracking. The two cold cracking mechanisms are hydrogen cracking and restraint cracking. Both of these mechanisms occur at ambient temperature. Preheating slows down the cooling rate resulting in a ductile, less brittle microstructure thereby lowering susceptibility to cold cracking. Preheat also increases the diffusion rate of monatomic hydrogen that may have been trapped in the weld during solidification. As an alternative to preheat, the ambient temperature temper bead welding process utilizes the tempering action of the welding procedure to produce tough and ductile microstructures.
Because precision bead placement and heat input control are utilized in the machine gas tungsten arc welding process, effective tempering of weld heat affected zone (HAZ) is possible without the application of preheat. According to Section 2-1 of EPRI Report GC- 111050, "the temper bead process is carefully designed and controlled such that successive weld beads supply the appropriate quantity of heat to the untempered heat affected zone such that the desired degree of carbide precipitation (tempering) is achieved.
The resulting microstructure is very tough and ductile."
The IWA-4600 temper bead process also includes a postweld soak requirement.
Performed at 300 degrees Fahrenheit for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (P-No. 3 base materials and conservative for P-I materials of this thickness which are used in this application), this postweld soak assists diffusion of any remaining hydrogen from the repair weld. As such, the postweld soak is a hydrogen bake-out and not a postweld heat treatment as defined by the ASME Code. At 300 degrees Fahrenheit, the postweld soak does not stress relieve, temper, or alter the mechanical properties of the weldment in any manner. Since the potential for hydrogen absorption is greatly diminished by the use of gas tungsten arc welding temper bead process, no postweld soak is needed for this application.
The alternative in Attachment 2 establishes detailed welding procedure qualification requirements for base materials, filler metals, restraint, impact properties, and other procedure variables. The qualification requirements provide assurance that the mechanical properties of repair welds are equivalent to or superior to those of the surrounding base material.
Hydrogen Crackin<
Hydrogen cracking is a form of cold cracking. It is produced by the action of internal tensile stresses acting on low toughness heat affected zones. The internal stresses are produced from localized build-ups of monatomic hydrogen. Monatomic hydrogen forms when moisture or hydrocarbons interact with the welding arc and molten weld pool. The monatomic hydrogen can be entrapped during weld solidification and tends to migrate to transformation boundaries or other microstructure defect locations. As concentrations build, the monatomic hydrogen recombines to form molecular hydrogen - thus generating localized internal stresses at these internal defect locations. If these stresses exceed the fracture toughness of the material, hydrogen induced cracking occurs. This form of cracking requires the presence of hydrogen and low toughness materials. It is manifested by intergranular cracking of susceptible materials and normally occurs within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of welding.
IWA-4600 establishes, elevated preheat and postweld soak requirements. The elevated preheat temperature of 300 degrees Fahrenheit increases the diffusion rate of hydrogen
RR-A32 Page 8 of 13 from the weld. The postweld soak at 300 degrees Fahrenheit was also established to bake-out or facilitate diffusion of any remaining hydrogen from the weldment. However, while hydrogen cracking is a concern for shielded metal arc welding (SMAW), which uses flux covered electrodes, the potential for hydrogen cracking is significantly reduced when using machine gas tungsten arc welding.
The machine gas tungsten arc welding process is inherently free of hydrogen. Unlike the SMAW process, gas tungsten arc welding filler metals do not rely on flux coverings that may be susceptible to moisture absorption from the environment. Conversely, the gas tungsten arc welding process utilizes dry inert shielding gases that cover the molten weld pool from oxidizing atmospheres. Any moisture on the surface of the component being welded vaporizes ahead of the welding torch. The vapor is prevented from being mixed with the molten weld pool by the inert shielding gas that blows the vapor away before it can be mixed. Furthermore, modem filler metal manufacturers produce wires having very low residual hydrogen. This is important because filler metals and base materials are the most realistic sources of hydrogen for the automatic or machine gas tungsten arc welding temper bead process. Therefore, the potential for hydrogen-induced cracking is greatly reduced by using the machine gas tungsten arc welding process. Extensive research has been performed by EPRI [reference 7] which provides a technical basis, for starting the 48-hour hold after completing the third temper bead weld layer rather than waiting for the weld overlay to cool to ambient temperature. The hold time required by Code Case N-638-4 and N-740-2 shall be implemented in accordance with this latest research. This approach has been previously reviewed and approved by the NRC for pressurizer nozzle overlays.
Cold Restraint Cracking Cold cracking generally occurs during cooling at temperatures approaching ambient temperature. As stresses build under a high degree of restraint, cracking may occur at defect locations. Brittle microstructures with low ductility are subject to cold restraint cracking. However, the ambient temperature temper bead process is designed to provide a sufficient heat inventory so as to produce the desired tempering for high toughness.
Because the machine gas tungsten arc welding temper bead process provides precision bead placement and control of heat, the toughness and ductility of the heat affected zone is typically superior to the base material. Therefore, the resulting structure shall be appropriately tempered to exhibit toughness sufficient to resist cold cracking.
Area Limitation IWA-4600 and early versions of Code Case N-638 for temper bead welding contained a limit of 100 square inches for the surface area of temper bead weld over the ferritic base metal. The associated limitation proposed in this alternative is 700 square inches.
EPRI Report NP-10 11898, November 2005, [reference 2] describes the technical justification for allowing increased overlay areas up to 500 square inches over ferritic material. The white paper contained in this report notes that the original limit of 100 square inches in Code Case N-638-1 was arbitrary. It cites evaluations of a 12-inch diameter nozzle weld overlay to demonstrate adequate tempering of the weld heat affected zone (Section 2a of the white paper), residual stress evaluations demonstrating acceptable residual stresses in weld overlays ranging from 100 to 500 square inches (Section 2b of the white paper), and service history in which. weld repairs exceeding 100 square inches were NRC approved and applied to dissimilar weld metal nozzles in several BWRs and PWRs
RR-A32 Page 9 of 13 (Section 3c of the white paper). Some of the cited repairs are greater than 15 years old, and have been inspected several times with no evidence of any continued degradation.
Section 5.1, Analyses Conclusions, in EPRI Report NP- 10 11898, when evaluating the 100 square inch and 500 square inch repair sizes provides the following statement.
"Results demonstrate that a larger weld repair area does not have a significant adverse effect on the weld residual stress. In some cases, the larger repair area is much more beneficial because of the lower tensile residual stress or higher compressive residual stress. Especially for the case of axial weld repair where an axial crack could exist, the hoop stress is more compressive or less tensile within the weld repair and outside the repair area. The larger repair area could be less susceptible to the crack growth, due to either stress corrosion or fatigue."
Section 5.2, Overall Conclusions, in EPRI Report NP-101 1898, also states that:
"The restriction on surface area for temper bead welding was arbitrary, is overly restrictive, leads to increased cost and dose for repairs and does not contribute to safety."
Additionally, "there is no direct correlation of residual stresses with surface area of the repair either for cavity or overlay repairs done using temper bead welding. Cases have been analyzed up to 500 square inches that verify that residual stresses for cavity repairs are at an acceptable level and that residual stresses associated with weld overlay repairs remain compressive in the weld region for larger area repairs as well as for smaller area repairs."
Due to the outside diameter of the reactor coolant pump piping, the weld overlay repair may extend to greater than 600 square inches of surface area on the carbon steel component, but less than 700 square inches of surface area. Consequently, the proposed alternative includes a maximum individual weld overlay area requirement of 700 square inches discussed in the General Requirements of Attachment 3.
Analyses and Verifications The following list of analyses and verifications are performed subject to the specific design, analysis, and inspection requirements that have been defined in this request.
- 1. Nozzle specific stress analyses shall be performed to establish a residual stress profile in the nozzle. Inside diameter (ID) weld repairs shall be assumed in these analyses to effectively bound any actual weld repairs that may have occurred in the nozzles. The analysis shall then simulate application of the weld overlays to determine the final residual stress profile. Post weld overlay residual stresses at normal operating conditions shall be shown to result in a stress state on the inside surface of each component, that assures that further crack initiation due to primary water stress corrosion cracking is highly unlikely.
- 2. Fracture mechanics analyses shall be performed to predict crack growth. Crack.
growth due to primary water stress corrosion cracking and fatigue crack growth in the original dissimilar metal weld shall be evaluated. The crack growth analyses shall consider all design loads and transients, plus the post weld
RR-A32 Page 10 of 13 overlay through-wall residual stress distributions, and shall demonstrate that the assumed cracks shall not grow beyond the design bases for the weld overlays (that is, through 75 percent of the original dissimilar metal weld thickness) for the time period until the next scheduled inservice inspection. The crack growth analyses shall determine the time period for the assumed cracks to grow to the design basis for the weld overlays.
- 3. The analyses shall demonstrate that the application of the weld overlays does not impact the conclusions of the existing nozzle stress reports. ASME Code Section III stress and fatigue criteria shall be met for the regions of the overlays remote from observed (or assumed) cracks.
- 4. The original leak-before-break calculations shall be updated with an evaluation demonstrating that due to the efficacy of the overlay for primary water stress corrosion cracking mitigation, concerns for original weld susceptibility to cracking has been resolved. The effects of the mitigation on the leak-before-break analysis shall be evaluated to show the effects of application of weld overlays do not invalidate the conclusions of the existing design basis.
- 5. Shrinkage shall be measured during the overlay application. Shrinkage stresses arising from the weld overlays at other locations in the piping sy~stems shall be demonstrated to not have an adverse effect on the systems. Clearances of affected supports and restraints shall be checked after the overlay repair, and shall be reset within the design ranges as required.
- 6. The total added weight on the piping systems due to the overlays shall be evaluated for potential impact on piping system stresses and dynamic characteristics.
- 7. The as-built dimension of the weld overlays shall be measured and evaluated to demonstrate that they equal or exceed the minimum design dimensions of the overlays.
Summaries of the results of the analyses listed in Items I through 4 above will be submitted to the NRC prior to entry.into Mode 4 following completion of the weld overlays. Items 5 though 7 are performed following installation of the weld overlays and results shall be included in the design modification package closure documents.
This information shall be available to resident or field inspectors for review as needed.
The following information will be submitted to the NRC within 14 days of completion of the final ultrasonic examination of the overlaid welds. Also included in the results will be a discussion of any repairs to the overlay material and/or base metal and the reason for the repair.
A listing of indications detected 1 The recording criteria of the ultrasonic examination procedure to be used for the examination of the Davis-Besse overlays requires that all indications, regardless of amplitude, be investigated to the extent necessary to provide accurate characterization, identity, and location. Additionally, the procedure requires that all indications, regardless of amplitude, that cannot be clearly attributed to the geometry of the overlay configuration be considered flaw indications.
RR-A32 Page 11 of 13 The disposition of all indications using the standards of ASME Code Section XI, IWB-3514-2 'and/or IWB-3514-3 criteria and, if possible, the type and nature of the indications2 Conclusions Quality and Safety of ProposedAlternative Implementation of the alternatives to IWA-4600 of ASME Code Section XI described in Attachments 2 and 3 of this request shall produce effective repairs for potential primary water stress corrosion cracking in the identified welds and improve piping geometries to permit ASME Code Section XI, Appendix VIII UT examinations as implemented through the PDI program. Weld overlay repairs of dissimilar metal welds have been installed and performed successfully for many, years in both PWR and BWR applications. The alternative provides improved structural integrity and reduced likelihood of leakage for the primary system.
Accordingly, the use of the alternative provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i).
6.' Duration of Proposed Alternative The provisions of this alternative are applicable to the Third Ten-Year Inservice Inspection Interval for Davis-Besse which commenced on September 21, 2000 and will end on September 20, 2012.
The weld overlays installed in accordance with the provisions of this alternative shall remain in place for the design'life of the repair established as described in Attachments 1, 2, 3, and 5. -
- 7. References
- 1. ASME Boiler and Pressure Vessel Code,Section XI, 1995 Edition through 1996 Addenda, Appendix VIII, Supplement 11, "Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds."
- 2. EPRI Report 1011898, November 2005, "RRAC Code Justification for the Removal of the 100 Square Inch Temper Bead Weld Limitation," EPRI, Palo Alto, CA, and Structural Integrity Associates, Inc., San Jose, CA.
- 3. EPRI Report GC-1 11050, November 1998, "Ambient Temperature Preheat for Machine GTAW Temper Bead Applications," EPRI, Palo Alto, CA, and Structural Integrity Associates, Inc., San Jose, CA.
- 4. ASME Boiler and Pressure Vessel Code,Section XI, 1995 Edition with Addenda through 1996, Appendix VIII, Supplement 10.
- 5. EPRI Materials Reliability Program Report: Crack Growth Rates for Evaluating PWSCC of Alloy 82, 182, and 132 Welds (MRP-1 15), EPRI, Palo Alto, CA, and Dominion Engineering, Inc., Reston, VA: November 2004. 1006696.
2 The ultrasonic examination procedure requires that all suspected flaw indications are to be plotted on a cross sectional drawing of the weld and that the plots should accurately identify the specific origin of the reflector.
RR-A32 Page 12 of 13
- 6. ASME Code Case N-740-2 "Dissimilar Metal Weld Overlay for Repair or Mitigation of Class 1, 2, and 3 Items,"
- 7. EPRI Report 1013558, Temperbead Welding Applications 48 Hour Hold Requirements for Ambient Temperature Temperbead Welding, EPRI, Palo Alto, CA and Hermann & Associates, Key Largo, FL, December 2006.
- 8. EPRI Materials Reliability Program: Technical Basis for Preemptive Weld Overlays for Alloy 82/182 Butt Welds in PWRs (MRP-169), Rev. 1, EPRI, Palo Alto, CA and Structural Integrity Associates, Inc., San Jose, CA; June 2008, 1016602.
- 9. G. Wilkowski, H. Xu, D. J. Shim, and D. Rudland, "Determination of the Elastic-Plastic Fracture Mechanics Z-factor for Alloy 82/182 Weld Metal Flaws for Use in the ASME Code Section XI Appendix C Flaw Evaluation Procedures,"
PVP2007-26733, Proceedings of ASME-PVP 2007: 2007 ASME Pressure Vessels and Piping Division Conference, San Antonio, TX, 2007.
- 10. NUREG/CR-4082, Volume 8, "Summary of Technical Results and Their Significance to Leak-Before-Break and In-Service Flaw Acceptance Criteria, March 1984-January 1989.
- 11. A.F.
Deardorff et al,
"Net Section Plastic Collapse Analysis of Two-Layered Materials and Application To Weld Overlay Design", ASME PVP 2006 Pressure Vessels and Piping Division Conference, Vancouver, Canada, July 2006, PVP2006-ICPVT 11-93454.
- 12. W. Hibner, B. Johansson, and M. de Pourbaix, Studies of the Tendency to Intergranular Stress Corrosion Cracking of Austenitic. Fe-Cr-Ni Alloys in High Purity Water at 300 0 C, Studsvik report AE-437, Nykoping, Sweden, 1971.
- 13. W. Debray and L. Stieding, Materials in the Primary Circuit of Water-Cooled Power Reactors, International Nickel Power Conference, Lausanne, Switzerland, May 1972, Paper No. 3.
- 14. C. Amzallag, et al., "Stress Corrosion Life Assessment of 182 and 82 Welds used in PWR Components," Proceedings of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 2001.
- 15. NUREG/CR-6907, "Crack Growth Rates of Nickel Alloy Welds in a PWR Environment," U.S. Nuclear Regulatory Commission (Argonne National Laboratory), May 2006.
- 16. EPRI Material Reliability Program Report: Primary System Piping Butt Weld Inspection and Evaluation Guidelines (MIRP-139), EPRI, Palo Alto, CA: August 2005. 1010087.
- 17. ASME Code Case N-638-1 "Similar and Dissimilar Metal Welding Using Ambient Temperature GTAW Temper Bead Technique"
- 18. ASME Code Case N-638-2 "Similar and Dissimilar Metal Welding Using Ambient Temperature GTAW Temper Bead Technique"
RR-A32 Page 13 of 13
- 19. ASME Code Case N-638-3 "Similar and Dissimilar Metal Welding Using Ambient Temperature GTAW Temper Bead Technique"
- 20. ASME Code Case N-638-4 "Similar and Dissimilar Metal Welding Using Ambient Temperature GTAW Temper Bead Technique"
- 21. ASME Code Case N-504-2 "Alternative Rules for Repair if Classes 41,2, and 3 Austenitic Stainless Steel Piping"
- 22. ASME Code Case N-504-3 "Alternative Rules for Repair if Classes 1, 2, and 3 Austenitic Stainless Steel Piping"
- 23. ASME Code Case N-770 "Alternative Examination Requirements and Acceptance Standards for Class I PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities"
- 24. D. Buisine, et al., "PWSCC Resistance of Nickel Based Weld Metals with Various Chromium Contents," Proceedings: 1994 EPRI Workshop on PWSCC of Alloy 600 in PWRs, EPRI, Palo Alto, CA: 1995. TR-105406, Paper D5.
RR-A32, ATTACHMENT 1 Page 1 of 11 BACKGROUND AND TECHNICAL BASIS FOR DAVIS-BESSE REACTOR COOLANT PUMP DISSIMILAR METAL WELD OVERLAYS The following discussion is based on Chapters 4 and 7 of MRP-169 and summarizes the background and technical basis for the design, analysis and inspection requirements for the reactor coolant pump dissimilar metal weld overlays to be applied at the Davis,-Besse Nuclear Power Station (Davis-Besse). The design of the overlays shall be optimized weld overlays that meet the requirements stated in this attachment. Detailed requirements for the application of the overlays are specified in Attachments 2 and 3.
A1.1 Weld Overlay Sizing The fundamental assumption of structural weld overlay sizing is that a crack is present in the original pipe or nozzle weld, which must be evaluated in accordance with ASME Code Section XI flaw evaluation rules. These rules are applied to Davis-Besse to establish an end-of-evaluation-period allowable flaw size and are based on the maximum size flaw that can be sustained in the component without violating original ASMIE Code Section III design margins (typically ASME Code Section III for primary system components). ASME Code Section XI also includes a general restriction that this flaw size shall not be greater than 75 percent of the component nominal wall thickness.
For preemptive weld overlays on dissimilar metal welds, an "optimized" structural weld overlay is defined in reference 8 as an acceptable alternative to full structural overlays when there are no flaws present in the weld or any observed flaws are limited in size. For an optimized weld overlay, the design basis flaw assumption is still 360 degrees around the weld, the same as for a full structural weld overlay, but with a depth equal to 75 percent of the original pipe wall. Key features of the optimized weld overlay design and inspections are as follows:
- An additional design requirement to show that ASME Code Section XI design criteria are met for a 100 percent through-wall axial flaw.
- An analysis of fatigue and primary water stress corrosion cracking crack growth that demonstrates that any growth shall not impair the ASME Code Section XI acceptance criteria for the optimized weld overlay at the end of the inspection interval.
- Nondestructive examination (NDE) qualification of procedures and personnel for axial flaws shall be done to the current requirements from Appendix VIII, Supplement 11 ,for a 75 percent through-wall flaw.
- NDE qualification for procedures and personnel for a 50 percent through-wall circumferential flaw to appropriately modified requirements of ASME Code Appendix VIII, Supplement 11 that include the appropriate flaw size distribution, flaw location distribution or grading unit requirements, as well as the demonstration acceptance criteria (for example, permissible false calls over the entire range of the inspected thickness.)
RR-A32, Attachment 1 Page 2 of 11 The optimized weld overlay flaw size assumption is a reasonable and conservative design basis for preemptive overlays, since:
- 1. The pipe shall have been inspected immediately prior to the overlay application, using an inspection technique qualified in accordance with ASME Code Section XI, Appendix VIII and found to exhibit no evidence of inner surface connected cracking greater than 50 percent of the wall thickness in the original weld. (Since the optimized weld overlay design basis flaw is 75 percent of the original pipe wall, the initial examination must cover the outer 50 percent of the original wall thickness in the primary water stress corrosion cracking susceptible material to assure a conservative margin for post overlay inservice inspection.)
- 2. Post-overlay ultrasonic examinations (and future inservice inspections) shall be required to verify the integrity of the applied weld overlay, and the examination volume for these inspections is increased to include the weld overlay plus the outer 50 percent of the original pipe wall as detailed in Section A1.3 - Inspectability Considerations.
With a design basis crack depth assumption for optimized weld overlay sizing that is 75 percent of original wall thickness, the assumed flaw already meets the general ASME Code Section XI 75 percent criterion without an overlay. Thus, the resulting optimized weld overlay thickness shall not be controlled by this somewhat arbitrary limit, but instead be based on the actual internal pressure and pipe loads at the location of the dissimilar metal weld being overlaid, and the ASME Code Section XI Paragraph IWB-3641 allowable flaw size criteria. In some cases, the minimum thickness required to provide compressive residual stresses may govern the overlay size as discussed in Section A 1.2 - Residual Stress Improvement.
In applying Paragraph IWB-3641 allowable flaw size criteria to structural sizing of optimized weld overlays, some additional considerations apply that are not applicable to full structural weld overlays (FSWOLs). Specifically, since optimized weld overlays take some credit for the underlying dissimilar metal weld material, the design must account for potential lower toughness of that material (particularly at the fusion line with the low alloy or carbon steel component)
[reference 9]. Reference 9 defines a Z-factor approach to address this concern. Furthermore, primary water stress corrosion cracking in the dissimilar metal weld may also be located near the stainless steel fusion line, and in such cases, tests and analyses [reference 10] have shown that the limit load solution for net section collapse should use the flow stress of the lower strength stainless steel material rather than that of the Alloy 82/182 weldment. An optimized weld overlay actually represents a special case in which the piping system loads are carried by a two-layer cylinder. The above low toughness/low strength considerations are-applicable to the inner layer (that is, the outer 25 percent of the original dissimilar metal weld), but not to the outer layer (the Alloy 52 weld overlay, which carries a large portion of the load). An analysis technique for addressing this two-layer problem in weld overlay design is presented in reference 11. In the design of optimized weld overlays for Davis-Besse reactor coolant pump dissimilar metal welds, the two layer approach described in reference 11 shall be used to address potential cracks near the fusion lines of the dissimilar metal weld.
ASME Code Cases N-504-3 and N-740-2 also provide guidance for weld overlay length sizing, and these are the same for both full structural weld overlays and optiniized weld overlays. The underlying requirement is that sufficient weld overlay length be provided on either side of the observed crack to allow for adequate transfer of axial loads between the pipe and the weld overlay. For axisymmetric loading of a cylinder, local loading effects can be shown to attenuate to a small fraction of their peak value at an axial distance of 0.75'IRt from the point of loading
RR-A32, Attachment I Page 3 of 11 (where R is the outer radius and t is the nominal wall thickness of the cylinder). Thus, if the weld overlay length is set equal to 0.754Rt on either side of the crack, resulting in a total weld overlay length of 1.5'IRt, the overlay shall extend beyond any locally elevated stresses due to the crack.
In application of weld overlays preemptively, however, no crack will have been detected, so the above criterion is conservatively applied such that the minimum weld overlay length must be 0.754Rt beyond either side of the susceptible material. This shall result in a total weld overlay length equal to 1.5*IRt plus the length of susceptible material (Alloy 82 or 182 weld metal and buttering) on the outside diameter surface of the original dissimilar weld metal. It is noted that the 0.754IRt recommendation is only a rule of thumb, and that shorter lengths may be used if justified by stress analysis of the specific optimized weldoverlay configuration, to demonstrate that adequate load transfer and stress attenuation are achieved.
Other considerations also factor into the Davis-Besse reactor coolant pump dissimilar weld metal overlay designs. These include that the overlays must be of sufficient length and thickness to achieve the desired tensile residual stress reduction over the entire extent of susceptible material on the inside surface of the component discussed in Section A 1.2, that the length and other aspects of the weld overlay design result in an inspectable configuration discussed in Section A1.3, and that no unacceptable structural discontinuities are created. For optimized weld overlays that overlay a tapered transition (or create one), the design must satisfy the ASME Code Section III (latest edition) requirements of NB-4250 that allow for a maximum 30 degree transition angle between adjacent sections, unless detailed analyses are performed of the specific configuration to establish applicable stress indices for fatigue evaluation.
The specific overlay design and analysis requirements for the Davis-Besse reactor coolant pump dissimilar metal welds are itemized in Attachment 2, Section A2.2.
A1.2 Residual Stress Improvement A key aspect of the weld overlay design process is to demonstrate that favorable tensile residual stress reduction occurs such that primary water stress corrosion cracking initiation and growth is mitigated. Extensive analytical and experimental work was performed on weld-overlaid boiling water reactor pipe-to-pipe welds of various pipe sizes to demonstrate that favorable residual stresses result for full-structural weld overlays [reference 8]. A recent preemptive weld overlay test program also demonstrated that measured residual stresses in a typical pressurized water reactor mid-sized dissimilar weld metal weld overlay were highly favorable when applied to a weld with a severe inside surface repair [reference 8, chapter 5].
Joint specific, overlay specific weld residual stress analysis shall be performed for each unique Davis-Besse reactor coolant pump dissimilar weld metal optimized weld overlay configuration.
These shall be performed with analysis methods and tools that are appropriate for this type of analysis, including transient thermal analysis capability, non-linear elastic-plastic modeling capability, and temperature dependent material properties. The residual stress analyses shall consider the heat efficiency factor associated with the actual welding process, thermal boundary conditions (wet or dry) and interpass temperature limits.
Finally, the residual stress condition of the dissimilar weld metal joint has a significant bearing on its susceptibility to primary water stress corrosion cracking, especially as influenced by in-process repairs performed during plant construction. In fact, in essentially all cases in which primary water stress corrosion cracking has been discovered in pressurized water reactor butt welds, evidence of significant in-process repairs during construction has been found. Thus to
RR-A32, Attachment I Page 4 of 11 adequately demonstrate the favorable residual stress effects of a weld overlay, the residual stress analyses start with a highly unfavorable, pre-overlay residual stress condition such as that which would result from an inside diameter surface weld repair during construction. If the nozzle-specific weld overlay design is shown to produce favorable residual stresses in this severe case, it mitigates primary water stress corrosion cracking in the dissimilar weld metal. Acceptable residual stresses for purposes of satisfying this requirement are those which, after application of the weld overlay, are compressive on the inside surface of the nozzle, over the entire length of primary water stress corrosion cracking susceptible material on the inside surface, at operating temperature, but prior to applying operating pressure and loads. After application of operating pressure and loads, the resulting inside surface stresses must be less than 10,000 pounds per square inch tensile. As documented in references 12 through 14, laboratory data and field observations have shown that high stresses,. on the order of the material yield strength, are necessary to initiate primary water stress corrosion cracking. Thus limiting inside diameter surface stresses under sustained steady state conditions to less than 10,000 pounds per square inch ensures a very low probability of initiating new primary water stress corrosion cracking cracks after application of the weld overlay.
A separate primary water stress corrosion cracking crack growth criterion shall be satisfied to demonstrate the acceptability of the post-weld overlay residual stress distribution. This criterion requires that any cracks detected in the pre- or post-overlay inspections, or that are not within the examination volumes in the primary water stress corrosion cracking susceptible material, would not grow by primary water stress corrosion cracking to the point that they would violate the overlay design basis (75 percent through-wall for optimized weld overlays). Since there is no generally accepted primary water stress corrosion cracking crack growth threshold for Alloy 82/182 weld metals, satisfying this criterion generally requires that the crack tip stress intensity factor due to residual stresses, operating pressure and sustained, steady-state loads, be compressive up to the greater of the maximum flaw size detected (either pre- or post-overlay) or the maximum flaw size in primary water stress corrosion cracking susceptible material that could be missed by the applicable inspections.
The above combination of inside diameter surface stress and crack growth criteria, in conjunction with required post-overlay inspections, provides protection against initiating new primary water stress corrosion cracking cracks after application of the weld overlay and/or propagation of pre-existing cracks that would violate the overlay design basis.
A1.3 Inspectability Considerations One additional aspect of weld overlay design is that it must be inspectable. As discussed previously, post overlay examination requirements for optimized weld overlays include the weld overlay itself, plus the outer 50 percent of the original pipe wall thickness. This examination requirement applies to optimized weld overlays, which use as their design basis a crack completely through the original pipe wall thickness. The 50 percent of original pipe wall thickness examination requirement is seen as providing added margin by verifying the arrest of an existing flaw and advanced warning in the unlikely case that the crack is not arrested before propagating into the weld overlay. In this case, a flaw would violate the design basis if it extended into the outer 25 percent of the pipe wall. Thus the examination must provide additional coverage to preserve a similar "advanced warning" examination volume. Thus, since the optimized weld overlay design basis flaw is 75 percent of the original pipe wall, then the post-weld overlay examination (and subsequent inservice inspections) must cover the weld overlay material plus the outer 50 percent of the original wall thickness in the primary water stress corrosion cracking susceptible material.
RR-A32, Attachment I Page 5 of 11 A summary of the required post-overlay examinations, overlay acceptance examinations, preservice inspections and inservice inspections is included in Attachment 2, Section A2.3.
ASME Code Section XI, 1995 Edition and later includes NRC accepted rules for inspection of welds in piping that require the procedures, equipment, and personnel to be qualified by a performance demonstration in accordance with ASME Code Section XI, Appendix VIII, Supplement 11. The utilities sponsored a performance demonstration initiative (PDI),
implemented at the EPRI Nondestructive Examination Center, which satisfies these requirements, as amended for weld overlay repairs, and a number of organizations have successfully qualified personnel and techniques to inspect weld overlays under that program. Therefore, as has been the case for full structural weld overlay repairs, ASME Code Section XI, Appendix VIII, Supplement 11 shall be implemented for optimized weld overlays. The overlay design, including surface preparation specifications, shall be reviewed to confirm that an examination of the optimized weld overlay can be performed in accordance with the PDI qualification requirements as described in Attachment 2.
A1.4 Fatigue Considerations There are two issues that must be addressed from a fatigue viewpoint relative to installation of a weld overlay on an existing weld. The first involves evaluation of potential growth of cracks due to cyclic loadings at the overlay location. The second involves assuring that additional stresses are not created by the application of the overlay that would contribute to an unacceptable end-of-life fatigue usage factor in the region where the overlay is being applied.
The sensitivity to fatigue effects depends upon whether or not there are significant cyclic loadings at the overlay location and if there are structural discontinuities in addition to the overlay that result in stress concentrations. The most severe cyclic loading effects are generally due to thermal transients. The effects of pressure cycles are generally not significant since the applied stresses must meet primary stress limits in the design process. Piping thermal expansion moments are generally not significant, unless there are a significant number of thermal transients or if there are stratification effects in the associated piping. By performing fatigue evaluations for the overlaid locations, the potential for adverse fatigue effects is evaluated and an appropriate inspection interval determined.
Fatigue Crack Growth The potential for a flaw to grow from an initial flaw size to the allowable size for the overlay shall be evaluated by performing a crack growth analysis. The following steps are included:
" Determine the loading conditions that must be considered. The loadings considered in the original plant design, including any later changes, must be determined. For purposes of crack growth analysis, the number of cycles per heatup/cooldown cycle is established.
" Determine the applied stresses, including through-wall and circumferential distribution, at the weld overlay location for each loading condition. Stresses in both the hoop and axial direction must be quantified. This may include loads due to:
o Pressure
" Residual stresses
RR-A32, Attachment 1 Page 6 of 11 o Bending moments due to dead weight, piping thermal expansion, nozzle anchor movement effects, seismic operating basis earthquake (OBE), and stratification, as applicable o Local thermal stratification, if applicable o Thermal transient through-wall stresses
" Characterize the initial flaw depth and aspect ratio. If the location is inspected using a PDI qualified examination and no flaws are detected prior to application of the weld overlay, an initial circumferential flaw depth greater than or equal to 10 percent of the nominal pipe or nozzle thickness shall be assumed, with a length equal to the wall thickness (a/1 = 0.1 aspect ratio flaw). An initial axial flaw greater than or equal to 10 percent of the pipe wall thickness with an aspect ratio (1/a) equal to the length of the Alloy 600 weld at the outside surface divided by the pipe wall thickness shall also be assumed.
" The fatigue crack growth law is based on Alloy 600 in the pressurized water reactor environment. Reference 15 indicates that the fatigue crack growth rate (FCGR) of Alloy 182 in the pressurized water reactor environment is a factor approximately 5 higher than that of Alloy 600 in air under the same loading conditions. The fatigue crack growth rate for Alloy 600 in air obtained from NUREG/CR-6443 is given by:
(da/dN).j = CA600 (1-0.82R)ý-ý (AK) 4"'. units of m/cycle where:
CA606 = 4.835x10M + 1.622x10-&6T - 1.49 x10'-8T2 + 4.355 x10 21 T3 T = temperature inside pipe, 'C (taken as the maximum dturing the transient)
R = R-ratio = 5 AK = K_, - K*. = range of stress intensity factor. Mpa-rn° Note that a factor of 5 shall be applied to this equation to account for the pressurized water reactor environment in accordance with reference 15. Also, -
note that crack growth rate in accordance with reference 15 is independent of rise time of the transient.
Crack growth analysis is then conducted on a cycle-by-cycle basis for a period equal to the standard ASME Code Section XI inspection interval (ten years) or to end of life, including license renewal period where applicable. If the crack growth analysis is performed for a calculation period shorter than the end of life, then inservice inspections must be performed at an interval no greater than that evaluation period.
If a flaw is detected in either pre- or post-overlay inspections that is greater than the -
initial flaw sizes specified above (that is, 50 percent through-wall for optimized weld overlays) for fatigue crack growth calculations, then the calculations must address the actual depths observed, in addition to the assumed flaw depths.
The allowable end-of-evaluation period flaw size is that considered in the design basis for structural sizing of the weld overlay (that is, 75 percent of the original wall thickness for optimized weld overlays). If the crack growth analysis shows that fatigue crack growth does not
RR-A32, Attachment I Page 7 of 11 grow a flaw to the design basis depth prior to the end of life, the ASME Code Section XI inspection requirements shall be used for subsequent inservice inspections (after any intermediate inspections imposed by MRP-139, as discussed in' Section Al.9 below). If the crack growth analysis shows that the crack grows to the allowable flaw size, then the inspection interval must be decreased to no greater than the time interval predicted for the flaw to reach the allowable flaw size.
Fatigue Usage Evaluation The fatigue usage at optimized weld overlay locations may be increased due to addition of the weld overlay since the through-wall thermal stresses may be increased (greater thickness) and there will be structural discontinuities at the weld overlay to piping and nozzle transitions. To assess this potential, a fatigue usage analysis shall be conducted for regions of the overlay remote from the observed or assumed crack using the applicable rules of ASME Code Section III for Class 1 components (NB-3600 for piping and NB-3200 for vessel nozzles). Code Editions and Addenda later than the original Construction Code may be used, as allowed by ASME Code Section XI, Appendix L.
A1.5 Leak-Before-Break Leak-before-break (LBB) analyses evaluate postulated flaw growth in the primary loop piping of the reactor coolant system. There are existing reports that provide the technical basis for eliminating large primary loop pipe rupture as the structural design basis for Davis-Besse.
- However, the current technical basis for regulatory approval of LBB applications does not provide for evaluation of active degradation mechanisms other than fatigue and thus is at odds with recent operating experience with primary water stress corrosion cracking and the actions being taken to mitigate and manage its effects. Consequently, efforts are underway within the NRC and EPRI to develop a more robust technical basis for determining that "...the probability of fluid system piping rupture is extremely low under conditions consistent with the design basis for the piping."
The original LBB calculations for Davis-Besse will be updated with an evaluation demonstrating that due to the efficacy of the overlay for primary water stress corrosion cracking mitigation, concerns for original weld susceptibility to cracking have been resolved. Critical crack sizes and leakage shall be evaluated with the weld overlay in place, including the effects of crack morphology, to demonstrate that margins exist for detection of leakage from one-half critical flaw sizes. The effects of the mitigation on the leak-before-break analysis shall be evaluated to show the effects of application of weld overlays do not invalidate the conclusions of the existing design basis.
A1.6 Evaluation of Weld Overlay Effects on Piping System Stresses may develop in other locations of a piping system due to the weld shrinkage at the overlays. These stresses are system wide, and similar in nature to restrained free end thermal expansion or contraction stresses. The level of stresses resulting from weld overlay shrinkage depends upon the amount of shrinkage that occurs and the piping system geometry (that is, its stiffness). Overlay weld shrinkage may also produce displacements at locations in the system such as pipe hangers and pipe whip restraints that need to be checked against design tolerances.
Finally, the added mass and stiffness produced by the weld overlay may have an effect on the dynamic response characteristics of the system. I I
RR-A32, Attachment I Page 8 of 11 To address these effects, the following actions shall be taken following application of a weld overlay:
- 1. Measurementof Weld Overlay Shrinkage - Punch marks shall be applied at several azimuthal locations on the piping and/or nozzles, beyond the ends of the overlays, and the distance measured between those punch marks before and after application of the overlays.
- 2. Evaluationof Shrinkage Stresses - The stresses due to the measured shrinkage shall then be evaluated via a piping model, or other evaluation means. Although there are no directly applicable ASME Code Section III stress limits that apply to such sustained secondary stresses, a guideline is to compare them to the primary plus secondary stress limit. Such stresses may also affect primary water stress corrosion cracking crack growth evaluations of other susceptible welds in the system (with or without weld overlays).
- 3. System Walk Downs - Due to displacements produced by weld overlay shrinkage in the piping system, it is also required that, after application of the overlay, a walk-down be performed to check supports to verify tolerances.
- 4. Evaluationof Mass and Stiffness Effects - The mass added to the piping systems by the weld overlay and the effect of the overlay on piping system stiffness shall also be evaluated, based on as-built dimensions, to determine if they have any significant effects on dynamic analyses of the system.
Details of the specific overlay design and analysis requirements for the Davis-Besse reactor vessel reactor coolant pump dissimilar metal welds are itemized in Attachment 2, Section A2.2.
A1.7 Weld Overlay Inspection Inspections of weld overlays of pressurized water reactor system butt welds involve two aspects.
One is the type of examination and the other is the required interval. The examinations to be applied to the Davis-Besse reactor coolant pump dissimilar metal weld overlays are discussed in the following sections and the detailed requirements are itemized in Attachment 2, Section A2.3.
A1.8 Types of Examination for Weld Overlays Requirements for the type of examinations and associated examination volumes for full structural weld overlays are defined in ASME Code Section XI, Appendix Q and ASME Code Cases N-504-3 and N-740-2.
These requirements are consistent with current PDI techniques and were originally developed for weld overlay repairs of intergranular stress corrosion cracking (IGSCC) in boiling water reactor stainless steel welds, where the initiating flaws are fully characterized with respect to length and depth. Since the full structural weld overlay designs for these repairs assumed that the original flaw is completely through the original pipe wall, inspection of the outer 25 percent of the original pipe wall along with the weld overlay is specified for preservice and subsequent inservice examinations, such that it provides some advance warning if flaws were to unexpectedly propagate into that region, before they violate the overlay design basis. Also, the ultrasonic examination technology available at the time ASME Code Case N-504 was issued could reliably support examinations of the outer 25 percent of the original pipe wall.
RR-A32, Attachment I Page 9 of 11 However, for optimized weld overlays where the weld overlay design assumes the existence of a flaw 75 percent through the original wall thickness, it is desired to provide a similar "advance warning" examination volume for the unlikely event that a flaw would initiate and begin propagating after application of the overlay. For this design assumption, examination coverage for weld overlay preservice inspections and subsequent inservice inspections are increased to include the thickness of the weld overlay plus the outer 50 percent of the original pipe wall thickness. This provides additional margin to account for the uncertainty regarding the pre-weld overlay status of the original weld and is well within current ultrasonic examination capabilities.
For full structural preemptive weld overlays, where the weld overlay design assumes the existence of a flaw 100 percent through the original pipe wall, inspection of the outer 25 percent of the original pipe wall along with the weld overlay shall continue to be the requirement. Details of the examination requirements and exam volumes for optimized weld overlays are provided in Figures A2-1 and A2-2 of Attachment 2. These are consistent with the current requirements for full structural weld overlays (ASME Code Section XI Appendix Q and ASME Code Cases, N-504-3 and N-740-2) and the expanded exam volume requirement for optimized weld overlays described in MRP-169 [reference 8].
As discussed above, weld overlays must conform to the rules in the ASME Code Section XI for welds in piping that require the procedures, equipment, and personnel to be qualified by a performance demonstration in accordance with Appendix VIII, as amended in 10 CFR 50.55a.
Currently, FENOC uses the PDI qualification process to satisfy these requirements. Procedures, equipment, and personnel used for examination of preemptive weld overlays at Davis-Besse shall be qualified in accordance with the PDI process. Currently,Section XI Appendix VIII only includes qualification requirements for full structural weld overlays (Supplement 11).
- Attachment 2 to this 10 CFR 50.55a Request contains a description of the essentially equivalent PDI qualification program that is being used to qualify optimized weld overlay examinations.
A1.9 Inspection Interval and Sample Size for Preemptive Weld Overlays The inservice inspection interval and sample size for IGSCC mitigating weld overlays in boiling water reactor weldments are defined in NUREG-0313, which defines examination requirements in terms of the category of intergranular stress corrosion cracking susceptible weldment. The.
categories of weldments are based on 1) the IGSCC resistance of the materials in the original weldment, 2) whether or not stress improvement (or overlay) has been performed on the original weldment, 3) whether or not a post stress improvement ultrasonic examination has been performed, 4) the existence (or not) of cracking in the original weldment, and 5) the likelihood of undetected cracking in the original weldment prior to the application of the overlay. The categories range from A through G, with the higher letter categories requiring augmented inspection intervals and/or sample size. Category A is the lowest category, consisting of piping that has been replaced (or originally fabricated) with intergranular stress corrosion cracking resistant material.
The EPRI Materials Reliability Program (MRP) Primary System Piping Butt Weld Inspection and Evaluation Guidelines (MRP-139) utilize a similar classification scheme [reference 16].
Specifically, in accordance with MRP-139, primary water stress corrosion cracking susceptible weldments with no known cracks (based on examination) that have been reinforced by a full structural weld overlay made of primary water stress corrosion cracking resistant material are designated Category B. Primary water stress corrosion cracking susceptible weldments that contain known cracks that have been repaired by a full structural weld overlay are designated Category F.
RR-A32, Attachment I Page 10 of 1I For overlay applications in which a pre-overlay examination is performed and no primary water stress corrosion cracking-like indications are detected, the absence of cracking in the original weldment, the structural reinforcement and resistant material supplied by the overlay, the residual stress improvement provided by the overlay, and the requirement to do a PDI qualified examination immediately following application of the overlay are deemed to be consistent with MIRP- 139 Category B for either full structural or optimized weld overlays. Therefore the following requirements for subsequent inservice inspections shall be satisfied:
- 1. For primary water stress corrosion cracking susceptible weldments for which an inservice inspection is performed in accordance with ASME Code Section XI, Appendix VIII, Supplement 10 [reference 4] immediately prior to application of the overlay, and such inservice inspection demonstrates the weld to be absent of any flaws or crack-like indications, future in-service inspections of the welds shall be performed at intervals consistent with current ASME Code Section XI requirements. This requirement is consistent with MRP- 139 Category B, except that it is independent of whether the overlay is a full structural or optimized weld overlay.
- 2. For primary water stress corrosion cracking susceptible weldments for which an inservice inspection in accordance with ASME Code Section XI, Appendix VIII, Supplement 10
[reference 4] is not performed immediately prior to application of the overlay, or in which flaws or crack-like indications are detected, the weldment shall be assumed to be cracked. In such cases, future inservice inspections shall be performed consistent with requirements for cracked, weld overlay repaired weldments (MRP-139 Category F).
After the weld overlay and initial post-overlay examination, such weldments shall be inspected once in the next five years. If no new indications are seen or if no growth of existing indications is observed in the examination volume, the inspection interval shall revert to the existing ASME Code program.
- 3. In any case, if a post-overlay pre-service or inservice inspection detects a planar flaw in the weld overlay examination volume (Figure A2-2), it shall be addressed in the crack growth analyses described in Sections A1.2 and A1.4. If the flaw is found acceptable, the weld overlay examination volume shall be reexamined during the first or second refueling outage following discovery of the flaw.
A1.1O Dissimilar Metal Weld Examination Requirements The current requirements for inservice inspection of dissimilar metal welds (greater than 4 inches nominal pipe size) are defined in ASME Code Section XI and summarized as follows:
InitialPreservice and Subsequent Inservice Inspections:
Surface: Liquid penetrant examination of weld and heat affected zone surfaces Volumetric: Ultrasonic examination of inner 33 percent of original weld and heat affected zone Requirements for the inspection interval and sample size for dissimilar metal welds are defined in ASME Code Section XI as 100 percent of welds inspected every ten years (Category B-F or B-J Note (l)(c)).
RR-A32, Attachment 1
< Page 11 ofll As noted above, the Materials Reliability Program (MRP), sponsored by EPRI, has issued MRP-139 containing guidelines requiring augmented examinations for primary water stress corrosion cracking susceptible butt welds that are similar in concept to the NUREG-0313 requirements for boiling water reactor intergranular stress corrosion cracking susceptible welds. These guidelines are not repeated here, but involve inspections as often as once every inspection period (3 1/3 years) for unmitigated welds in higher temperature locations of the reactor coolant system (for example, pressurizer and hot leg nozzles).
RR-A32, ATTACHMENT 2 Page 1 of 9 REQUIREMENTS APPLICABLE TO DAVIS-BESSE NOZZLE WELD OVERLAYS FENOC proposes to use the following detailed requirements for the design, analysis, fabrication, examination, and pressure testing of the Davis-Besse reactor coolant pump dissimilar metal weld overlays. These requirements, which are derived from applicable portions of ASME Code Case N-740-2
[reference 6], MIRP-169 Rev. I [reference 8] and MRP-139 [reference 16], provide an acceptable methodology for reducing potential defects in these austenitic nickel alloy welds to an acceptable size or mitigating the potential for future primary water stress corrosion cracking by increasing the wall thickness through deposition of weld overlays. The weld overlays shall be applied by deposition of weld reinforcement (weld overlay) on the outside surface of the piping, nozzles, and associated dissimilar metal welds, including ferritic materials when necessary, in accordance with the following:
Prior to application of the optimized weld overlay, a pre-overlay ultrasonic examination of the dissimilar metal Alloy 82/182 weld will be performed. If no inside surface connected defects greater than 50 percent through wall are detected, an optimized weld overlay may be applied to the dissimilar metal Alloy 82/182 weld.
A2.1 MATERIALS AND WELDING REQUIREMENTS (a) An optimized weld overlay shall be applied by deposition of weld reinforcement (weld overlay) on the outside surface of circumferential welds. This proposed method applies to austenitic nickel alloy and austenitic stainless steel welds between the following:
5 P-No. 8 or P-No. 43 and P-Nos. 1, 3, 12A, 12B, or 12C P-No. 8 and P-No. 43 Between P-Nos. 1, 3, 12A, 12B, and 12C materials (b) If a weld overlay on any of the material combinations in A2.1 (a) obstructs a required examination of an adjacent P-No. 8 to P-No. 8 weld, the overlay may be extended to include overlaying the adjacent weld.
(c) Weld overlay filler metal shall be nickel alloy (28 percent chromium minimum, ERNiCrFe-7/7A) meeting the requirements of A2. 1(e) below applied 360 degrees around the circumference of the item and deposited using a Welding Procedure Specification (WPS) for groove welding, qualified in accordance with the Construction Code and Owner's Requirements identified in the Repair/Replacement Plan. As an alternative to the postweld heat treatment requirements of the Construction Code and Owner's requirements, ambient-temperature temper bead welding in accordance with Attachment 3 shall be used.
(d) Prior to deposition of the weld overlay,, the surface. to be weld overlaid shall be examined using the liquid penetrant method. Indications with major dimension greater than 1/16 inch (1.5 millimeters) shall be removed, reduced in size, or weld repaired in accordance with the following requirements.
(1) One or more layers of weld metal shall be applied to seal unacceptable indications in the area to be repaired with or without excavation. The thickness of these layers shall not be used in 5 P- Nos. 12A, 12B, and 12C designations refer to specific material classifications originally identified in ASME Code Section III and subsequently reclassified in a later Edition of ASME Code Section IX.
RR-A32, Attachment 2 Page 2 of 9 meeting weld reinforcement design thickness requirements. Peening the unacceptable indication prior to welding is permitted.
(2) If weld repair of indications identified in A2. 1(d) is required, the area where the weld overlay is to be deposited, including any local weld repairs or initial weld overlay layer, shall be examined by the liquid penetrant method. The area shall contain no indications with major dimension greater than 1/16 inch (1.5 millimeters) prior to application of the structural layers of the weld overlay.
(3) To reduce the potential of hot cracking when applying an austenitic nickel alloy over P-No. 8 base metal, it is permissible to apply a layer or multiple buffer (transitional) layers of austenitic stainless steel filler material metal over the austenitic stainless steel base metal. The stainless steel filler metal shall have a delta ferrite content of 5 - 15 Ferrite Number (FN) as reported on the Certified Material Test Report (CMTR). The thickness of these buffer layers shall not be used in meeting weld reinforcement design thickness requirements.
(e) Weld overlay deposits shall meet the following requirements:
The austenitic nickel alloy weld overlay shall consist of at least two weld layers deposited using a filler material with a chromium (Cr) content of at least 28 percent. The first layer of weld metal deposited may not be credited toward the required thickness except that a first diluted layer may be credited toward the required thickness, provided the portion of the layer over the austenitic base material, austenitic filler material weld, and the associated dilution zone from an adjacent ferritic base material contain at least 24 percent Cr, and the Cr content of the deposited weld metal is, determined by chemical analysis of the production weld or of a representative coupon taken from a mockup prepared in accordance with the WPS for the production weld. Downhill welding shall not be permitted for deposition of any layer.
(f) This proposed method is only for welding in applications predicted not to have exceeded fast neutron (E >1 MeV) fluence of 1 x 1017 neutrons per square centimeter prior to welding.
(g) A new weld overlay shall not be installed over the top of an existing weld overlay that has been degraded in service.
A2.2 DESIGN AND ANALYSIS REQUIREMENTS Structural Sizing OWOL - For an optimized weld overlay (OWOL), the overlay must meet the same ASME Code Section XI, Division 1, Class I rules for allowable flaw sizes in austenitic piping (Paragraph IWB-3640) in the presence of the following flaw size assumptions:
- 1) For repair of circumferentially-oriented flaws, in the underlying base material'or, weld, the flaws shall be assumed to be 75 percent through the original wall thickness of the item for the entire circumference. An optimized weld overlay may only be used for repair of inside surface connected circumferential flaws with a maximum depth of 50 percent through the original wall thickness of the item.
- 2) For repair axial flaws in the underlying base material or weld, the flaws shall be assumed to be 75 percent through the original wall thickness of the item for the entire axial length of the
RR-A32, Attachment 2 Page 3 of 9 flaw or combined flaws, as applicable. An optimized weld overlay may only be used for repair of inside surface connected axial flaws with a maximum depth of 50 percent through the original wall thickness of the item.
- 3) For mitigative optimized overlays, the assumed inside surface connected flaw in the underlying base material or weld shall be based on the limiting case of the two below:
(a) 75 percent through-wall for the entire circumference (b) 75 percent through-wall for 1.5 inches or the combined width of the weld pluis buttering, whichever is greater, in the axial direction
- 4) The overlay design thickness shall be verified, using only the weld overlay thickness conforming to the deposit analysis requirements of A2. 1(e).
- 5) The optimized weld overlay design must also account for potential lower toughness/lower strength of the underlying base material and dissimilar metal weldment that is credited in the flaw evaluation (that is, the outer 25 percent of the original wall thickness of the item).
References 9 through 11 provide an acceptable method for addressing this issue.
As ultrasonic examination procedures, qualified to the modified requirements of ASME Code Section XI, Appendix VIII, Supplement 11 are capable of detecting circumferential flaws in the upper 50 percent of the base material, but are only capable of detecting axial flaws in the upper 25 percent of the base material, the following will be included within the optimized weld overlay design requirements.
- A design requirement is added to show that ASME Code Section XI design criteria are met for a 100 percent through-wall axial flaw.
- An analysis of fatigue and primary water stress corrosion cracking crack growth must demonstrate that any growth shall not impair the ASME Code Section XI acceptance criteria (IWB-3640) for the optimized weld overlay at the end of the inspection interval.
ASME Code Case N-740-2 states that the axial length and end slope of the weld overlay must be sufficient to provide for load redistribution from the overlaid component to the weld overlay and back, such that applicable stress limits of NB-3200 are satisfied. It also states that the end transition slope of the overlay shall not exceed 30 degrees unless specifically analyzed to justify steeper slopes. ASME Code Section III stress analyses shall be performed to assure that the weld overlay length and end slope meet these requirements. These requirements are applicable to both full structural weld overlays and optimized weld overlays.
In addition to the overlay thickness calculated as described above, Paragraph IWB-3640 also contains the requirement that the flaw being evaluated not be greater than 0.75t, where t is the nominal wall thickness, including the weld overlay. An additional separate check is made to demonstrate that this requirement is met for all sections within the primary water stress corrosion cracking susceptible material.
Residual Stress Analysis Joint specific, overlay specific weld residual stress analyses shall be performed for each unique Davis-Besse reactor coolant pump dissimilar weld metal optimized weld overlay geometry. The residual stress analyses shall consider the heat efficiency factor associated with the actual welding process, thermal boundary conditions (wet or dry) and interpass temperature limits, and shall assume a conservative pre-overlay residual stress condition such as that which would result from an ID surface weld repair during construction. The acceptance criteria for such residual stress analysis are two-fold:
RR-A32, Attachment 2 Page 4 of 9 1 The resulting residual stresses on the inside surface over the entire length of primary water stress corrosion cracking susceptible material under the optimized weld overlay shall be less than or equal to 10,000 pounds per square inch tensile.
2 A separate primary water stress corrosion cracking crack growth criterion must also be satisfied to demonstrate that any flaws detected in the pre-overlay inspection, or that are not within the post-overlay exam volumes, shall not grow to exceed the applicable overlay design basis flaw size. Specifically, for an optimized weld overlay, this analysis must show that an assumed axial or circumferential flaw no less than 50 percent through the original wall .
thickness would not grow to exceed 75 percent through-wall. If actual flaw depths exceeding these initial flaw size assumptions are observed in any inspections, their actual depths must be considered in the analyses, in addition to the assumed flaw depths.
Fatigue Evaluation FatigueCrack Growth - Fatigue crack growth analyses shall be performed to demonstrate that the assumed flaw sizes specified above for primary water stress corrosion cracking analysis (that is, 50 percent through wall for optimized weld overlays) shall not exceed the overlay design basis flaw size in the period until the next scheduled inservice inspection. If actual flaw depths exceeding these initial flaw size assumptions are observed in any inspections, their actual depths must be considered in the analyses, in addition to the assumed flaw depths.
The allowable end-of-evaluation period flaw size is that considered in the design basis for structural sizing of the weld overlay (that is, 75 percent of the original wall thickness). If the fatigue crack growth analysis shows that the assumed flaw shall not grow to the design basis depth for the normal ASME Code Section XI inspection interval or greater, then the Section XI ten-year interval is justified for subsequent inservice inspections. If the crack growth analysis shows that the crack grows to the allowable flaw size, then the inspection interval must be decreased to no greater than the time interval predicted for the flaw to reach the allowable flaw size. Detailed future inservice inspection requirements for the overlaid item are specified in Section A2.3.
Fatigue Usage Factor- The fatigue usage analysis of the weld overlay, other than at the assumed crack location, shall be conducted using the applicable rules of ASME Code Section III for Class 1 components (NB-3600 for piping and NB-3200 for vessel nozzles). ASME Code Editions and Addenda later than the original Construction Code may be used for this evaluation, as allowed by ASME Code Section XI, Appendix L. (The assumed crack location is covered by the above fatigue crack growth evaluation..) The fatigue usage factor shall be calculated for the remaining plant lifetime, including license renewal period where applicable.
Leak-Before-Break Evaluation The plant-specific leak-before-break (LBB) analyses for Davis-Besse will be revised to address the effects of the weld overlay on LBB. The analysis shall demonstrate that the flaw size and leakage rate margins specified in Standard Review Plan (SRP) Section 3.6.3 are met for the overlaid nozzle locations.
Effects on Piping System The effects of any changes in applied loads or movements, as a result of weld shrinkage from the weld overlay, on other items in the piping system (for example, support loads and clearances, nozzle loads, and
RR-A32, Attachment 2 Page 5 of 9 changes in system flexibility and weight due to the weld overlay) shall be evaluated. Existing flaws previously accepted by analytical evaluation shall be evaluated in accordance with Paragraph IWB-3640.
A2.3 EXAMINATION REQUIREMENTS Ultrasonic examination procedures and personnel shall be qualified in accordance with the modified requirements to ASME Code Section XI, Appendix VIII, Supplement 11, as described in Attachment 5.
The examination shall be performed to the maximum extent practicable, for axial and circumfet-titial flaws. If 100 percent coverage 6f the required volume for axial flaws cannot be achieved, but essentially 100 percent coverage for circumferential flaws (100 percent of the susceptible volume) can be achieved, the examination for axial flaws shall be performed to achieve the maximum coverage practicable, with limitations noted in the examination report. The examination coverage requirements shall be considered to be met. For welds containingcast stainless steel materials the examination volume includes only the susceptible material (non-stainless steel) volume.
Weld Overlay Acceptance Examination (1) The weld overlay shall have a surface finish of 250 micro-inches (pin) or 6.3 micrometers (lrm) roughness measurement systemo (RMS) or better and contour that permits ultrasonic examination in accordance with procedures qualified in accordance with ASME Code Section XI, Appendix VIII. The weld overlay shall be inspected to verify acceptable configuration. .
(2) The weld overlay and the adjacent base material for at least 1/22 inch (13 millimeters) from each side of the overlay shall be examined using the liquid penetrant method. The weld overlay shall satisfy the surface examination acceptance criteria for welds of the Construction Code or NB-5300. The-adjacent base material shall satisfy the surface examination acceptance criteria for base material of the Construction Code or NB-2500. If ambient temperature temper bead welding is performed, the liquid penetrant examination of the completed weld overlay shall be conducted no sooner than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following completion of the three tempering layers over the ferritic steel.
(3) The examination volume A-B-C-D in Fig. A2-1(a) shall be ultrasonically examined to assure adequate fusion (that is, adequate bond) with the base material and to detect welding flaws, such as interbead lack of fusion, inclusions, or cracks. The interface C-D shown between the overlay and the weld includes the bond and heat-affected zone from the overlay. If ambient temperature temper bead welding is performed, the ultrasonic examination shall be conducted at leasf 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following completion of the three tempering layers over the ferritic steel. Planar flaws detected in the weld overlay acceptance examination shall meet the preservice examination standards of Table IWB-3514-2. In applying the acceptance standards to planar indications, the thickness, tl or t2, defined in Fig. A2-1(b), shall be used as the nominal wall thickness in Table IWB-3514-2, provided the base material beneath the flaw (that is, safe end, nozzle, or piping material) is not susceptible to stress corrosion cracking (SCC). For susceptible material, tl shall be used. If a flaw in the overlay crosses the boundary between the two regions, the more conservative of the two dimensions (t, or t 2) shall be used. Laminar flaws in the weld overlay shall meet the following requirements:
(a) The acceptance standards of Table IWB-3514-3 shall be met; with the additional limitation that the total laminar flaw shall not exceed 10 percent of the weld surface area, and that no linear dimension of the laminar flaw area shall exceed the greater of 3 inches (76 millimeters) or 10 percent of the pipe circumference.
RR-A32, Attachment 2 Page 6 of 9 (b) For examination volume A-B-C-D in Fig. A2-l(a), the reduction in coverage due to laminar flaws shall be less than 10 percent. The uninspectable volume is the volume in the weld overlay underneath the laminar flaws for which coverage cannot be achieved with the angle beam examination method.
(c) Any uninspectable volume in the weld overlay shall be assumed to contain the largest radial planar flaw that could exist within that volume. This assumed flaw shall meet the preservice examination acceptance standards of Table 1WB-3514-2, with nominal wall thickness as defined above for planar flaws. Alternatively, the assumed flaw shall be evaluated and shall meet the requirements of Paragraphs IWB-3640, IWC-3640, and IWD-3640, as applicable.
Both axial and circumferential planar flaws shall be assumed.
(4) After completion of all welding activities, VT-3 visual examination shall be performed on all affected restraints, supports, and snubbers, to verify that design tolerances are met.
Preservice and Inservice Inspection Examination Requirements - In addition to the above overlay acceptance exam, the preservice and inservice examination volume identified in Figure A2-2 shall be inspected by techniques qualified in accordance with the modified requirements to ASME Code Section XI, Appendix VIII, Supplement 11 or its equivalent as described in Attachment 5.
PreserviceExamination (1) The examination volume in Fig. A2-2 shall be ultrasonically examined. The angle beam shall be directed perpendicular and parallel to the piping axis, with scanning performed in four directions, to locate and size any planar flaw that have propagated into the outer 25 percent of the base metal thickness or into the weld overlay.
(2) The preservice examination acceptance standards of IWB-3514 shall be met for the weld overlay. In applying the acceptance standards to planar indications, the thickness, tl or t2, defined in Fig. A2-1(b) shall be used as the nominal wall thickness in IWB-3514, provided the base material beneath the flaw (that is, safe end, nozzle, or piping material) is not susceptible to SCC. For susceptible material, tj shall be used. Planar flaws in the outer 25 percent of the base metal thickness shall meet the design analysis requirements of 2.22 (3) The flaw evaluation requirements of IWB-3640, IWC-3640, or JWD-3640 shall not be applied to planar flaws, identified during preservice examination, that exceed the preservice examination acceptance standards of JWB-3514.
Inservice Examination (1) The weld overlay examination shall be added to the inspection plan. The weld overlay inspection interval shall not be greater than the life of the overlay as determined in A 1.3(a) above. All weld overlays shall be examined prior to the end of their design life.
(2) For welds whose pre-overlay examination did not reveal any inside surface connected planar flaws, the examination volume in Fig. A2-2 shall be ultrasonically examined within 10 years following application of the optimized weld overlay. If multiple welds are mitigated in the same inspection period, examinations shall be spread throughout years 3 through 10 following application, similar to provisions in IWB-2412(b). Examinations volumes which show no indication of cracking shall be placed into a population to be examined on a sample basis. Twenty-five percent of this population shall be examined once each inspection interval.
RR-A32, Attachment 2 Page 7 of 9 (3) For welds whose pre-overlay examination revealed inside surface connected planer flaws, the examination volume in Fig. A2-2 shall be ultrasonically examined once during the first or second refueling outage following application of the optimized weld overlay. Examination volumes that show no indication of crack growth or new cracking shall be placed into a population to be examined on a sample basis. Twenty-five percent of this population shall be added to the Inservice Inspection Program in accordance with IWB-2412(b) and examined once each inspection interval.
(4) The weld overlay examination volume in Fig. A2-2 shall be ultrasonically examined to determine if any new or existing planar flaws have propagated into the outer 50 percent of the base material thickness for circumferential flaws, or into the outer 25 percent of the base material thickness for axial flaws, or into the overlay. The angle beam shall be directed perpendicular and parallel to the piping axis, with scanning performed in four directions.
(5) The weld overlay shall meet the inservice examination acceptance standards of IWB-3514. In applying the acceptance standards to planar indications, the thickness, t1 or t2, defined in Fig. A2- 1(b) shall be used as the nominal wall thickness in IWB-3514, provided the base material beneath the flaw (that is, safe end, nozzle, or piping material) is not susceptible to SCC. For susceptible material, tj shall be used. If the acceptance standards of IWB-3514 cannot be met, the weld overlay shall meet the acceptance standards of IWB-3600, IWC-3600, or IWD-3600, as applicable. If a planar circumferential flaw is detected in the outer 50 percent of the base material thickness or if a planar axial flaw is detected in the outer 25 percent of the base material thickness, it shall meet the design analysis requirements of A2.2. Any indication characterized as stress corrosion cracking in the weld overlay material is unacceptable.
(6) If inservice examinations reveal planar flaw growth, or new planar flaws, meeting the acceptance standards of IWB-3514, IWB-3600, IWC-3600, or IWB-3600, the weld overlay examination volume shall be reexamined during the first or second refueling outage following discovery of the growth or new flaws.
(7) For weld overlay examination volumes with unacceptable indication, the weld overlay and original defective weld shall be removed. A repair/replacement activity shall be performed in accordance with IWA-4000.
A2.4 PRESSURE TESTING A system leakage test shall be performed in accordance with IWA-5000.
A2.5 DOCUMENTATION Use of this proposed method shall be documented on Form NIS-2.
RR-A32, Attachment 2 Page 8 of 9 End Transition Slope (not to exceed 30-degrees, unless analyzed)
(a) Examination Volume A-B-C-D A
E ý b_ -
ti r- b -1 F B N
I D3 Hw I/ tG C t2 (b) Thickness (t1 and t 2 ) for Table IWB-3514-2 Notes:
(a) Dimension b is equivalent to the nominal thickness of nozzle or pipe being overlaid, as appropriate.
(b) The nominal wall thickness is tj for flaws in E-F-G-H, and t 2 for flaws in A-E-H-D or F-B-C-G.
(c) For flaws that span two examination volumes (such as illustrated at F-G in the figure), the ti thickness shall be used.
(d) The weld includes the nozzle or safe end butter, where applied, plus any stress corrosion cracking susceptible base material in the nozzle.
Figure A2-1 Acceptance Examination Volume and Thickness Definitions
RR-A32, Attachment 2 Page 9 of 9 1/2 in. 7A " in.
I 7R 1/2 t/4 (Axial Flaws) t/2 (Circumferential Flaws)
Optimized Weld Overlay Preservice and Inservice Examination Volume A-B-C-D Volumetric: Overlay directly over original primary water stress corrosion cracking susceptible weldment (including nozzle, buttering, dissimilar weld metal and primary water stress corrosion cracking susceptible safe-end if present) plus 1/2inch beyond the as-found flaw and at least V inch beyond the toes of the original weld including weld-end butter, to a depth of the outer 50 percent for the detection of circumferential flaws and to a depth of the outer 25 percent for the detection of axial flaws of underlying material (A-B-C-D).
Figure A2-2 Preservice and Inservice Inspection Requirements for Weld Overlays
RR-A32. ATTACHMENT 3 Page 1 of 4 TEMPER BEAD WELDING REQUIREMENTS A3-1 GENERAL REQUIREMENTS (a) This Attachment applies to dissimilar austenitic filler metal welds between P-Nos. 1, 3, 12A, 12B, and 12C materials and their associated welds and welds joining P- No. 8 or 43 materials to P-Nos. 1, 3, 12A, 12B, and 12C materials with the following limitation. This Attachment shall not be used to repair SA-302 Grade B material unless the material has been modified to include from 0.4 percent to 1.0 percent nickel, quenching, tempering, and application of a fine grain practice.
(b) The maximum area of an individual weld overlay based on the finished surface over the ferritic base material shall be greater than 600 square inches (390,000 square millimeters), but less than 700
)square inches (455,000 square millimeters).
(c) Repair/replacement activities on a dissimilar-metal weld in accordance with this Attachment are limited to those along the fusion line of a nonferritic weld to ferritic base material on which 1/8inch (3 millimeters) or less of nonferritic weld deposit exists above the original fusion line.
(d) If a defect penetrates into the ferritic base material, repair of the base material, using a nonferritic weld filler material, may be performed in accordance with this Attachment, provided the depth of repair in the base material does not exceed %inch (10 millimeters).
(e) Prior to welding, the area to be welded and a band around the area of at least 111/2 times the component thickness or 5 inches (130 millimeters), whichever is less, shall be at least 50 degrees Fahrenheit (10 degrees Celsius).
) Welding materials shall meet the Owner's Requirements and the Construction Code and Cases specified in the Repair/Replacement Plan. Welding materials shall be controlled so that they are identified as acceptable until consumed.
(g) Peening may be used, except on the initial and final layers.
A3-2 WELDING QUALIFICATIONS The welding procedures and operators shall be qualified in accordance with ASME Code Section IX and the requirements of A3-2.1 and A3-2.2.
A3-2.1 Procedure Qualification (b) The base materials for the welding procedure qualification shall be of the same P-Number and Group Number as the materials to be welded. The materials shall be postweld heat treated to at least the time and temperature that was applied to the materials being welded.
(c) The maximum interpass temperature for the first three layers of the test assembly shall be 150 degrees Fahrenheit (66 degrees Celsius).
(d) The weld overlay shall be qualified using groove weld coupon. The test assembly groove depth shall be at least 1 inch (25 millimeters). The test assembly thickness shall be at least twice the test-assembly groove depth. The test assembly shall be large enough to permit removal of the required test specimens. The test assembly dimensions on either side of the groove shall be at least 6 inches (150 millimeters). The qualification test plate shall be prepared in accordance with Figure A3-1.
RR-A32, Attachment 3 Page 2 of 4 (e) Ferritic base material for the procedure qualification test shall meet the impact test requirements of the Construction Code and Owner's Requirements. If such requirements are not in the Construction Code and Owner's Requirements, the impact properties shall be determined by Charpy V-notch impact tests of the procedure qualification base material at or below the lowest service temperature of the item to be repaired. The location and orientation of the test specimens shall be similar to those required in A3-2. 1(f) but shall be in the base metal.
69 Charpy V-notch tests of the ferritic heat-affected zone (HAZ) shall be performed at the same temperature as the base metal test of A3-2.1 (d). Number, location, and orientation of test specimens.
shall be as follows:
(1) The specimens shall be removed from a location as near as practical to a depth of one half the thickness of the deposited weld metal. The coupons for HAZ impact specimens shall be taken transverse to the axis of the weld and etched to define the HAZ. The notch of the Charpy V-notch specimen shall be cut approximately normal to the material surface in such a manner as to include as much of the heat affected zone as possible in the resulting fracture.
(2) If the material thickness permits, the axis of a specimen shall be inclined to allow the root of the notch to be aligned parallel to the fusion line.
(3) If the test material is in the form of a plate or forging, the axis of the weld shall be oriented parallel to the principal direction of rolling or forging.
(4) The Charpy V-notch test shall be performed in accordance with SA-370. Specimens shall be in accordance with SA-370, Figure 11, Type A. The test shall consist of a set of three full-size 10 millimeters by 10 millimeters specimens. The lateral expansion, percent shear, absorbed energy, test temperature, orientation, and location of all test specimens shall be reported in the Procedure Qualification Record.
(g) The average lateral expansion value of the three HAZ Charpy V-notch specimens shall be equal to or greater than the average lateral expansion value of the three unaffected base metal specimens.
However, if the average lateral expansion value of the HAZ Charpy- V-notch specimens is less than the average value for the unaffected base metal specimens and the procedure qualification meets all other requirements of this Attachment, either of the following shall be performed:
(1) The welding procedure shall be requalified.
(2) An Adjustment Temperature for the procedure qualification shall be determined in accordance with the applicable provisions of Paragraph NB-4335.2 of ASME Code Section III, 2001 Edition with the 2002 Addenda. The reference nil-ductility temperature (RTNDT) or lowest service temperature of the materials for which the welding procedure will be used shall be increased by a temperature equivalent to that of the Adjustment Temperature.
A3-2.2 Performance Qualification Welding operators shall be qualified in accordance with ASME Code Section IX.
A3-3 WELDING PROCEDURE REQUIREMENTS The welding procedure shall include the following requirements:
(a) The weld metal shall be deposited by the automatic or machine gas tungsten arc welding process.
(b) Dissimilar metal welds shall be made using A-No. 8 weld metal (QW-442) for P-No. 8 to P-No. 1, 3,
RR-A32, Attachment 3 Page 3 of 4 or 12 (A, B, or C) weld joints or F-No. 43 weld metal (QW-432) for P-No. 8 or 43 to P-No. 1, 3, or 12 (A, B, or C) weld joints.
(c) The area to be welded shall be buttered with a deposit of at least three layers to achieve at least 1/8 inch (3 millimeters) overlay thickness with the heat input for each layer controlled to within +/- 10 percent of that used in the procedure qualification test. The heat input of the first three layers shall not exceed 45 kilojoule/inch (1.8 kJ/millimeter) under any conditions. Particular care shall be taken in the placement of the weld layers of the austenitic overlay filler material at the toe of the overlay to ensure that the heat affected zone and ferritic base metal are tempered. Subsequent layers shall be deposited with a heat input not exceeding that used for layers beyond the third layer in the procedure qualification.
(d) The maximum interpass temperature for field applications shall be 350 degrees Fahrenheit (180 degrees Celsius) for all weld layers regardless of the interpass temperature used during qualification.
The interpass temperature limitation of QW-406.3 need not be applied.
(e) The interpass temperature shall be determined as follows:
(1) temperature measurement (for example, pyrometers, temperature-indicating crayons, and thermocouples) during welding. If direct measurement is impractical, interpass temperature shall be determined in accordance with A3-3(e)(2) or (3).
(2) heat-flow calculations, using at least the variables listed below (a) welding heat input (b) initial base material temperature (c) configuration, thickness, and mass of the item being welded (d) thermal conductivity and diffusivity of the materials being welded (e) arc time per weld pass and delay time between each pass (0 arc time to complete the weld (3) measurement of the maximum interpass temperature on a test coupon that is no thicker than the item to be welded. The maximum heat input of the welding procedure shall be used in welding the test coupon.
69 Particular care shall be given to ensure that the weld region is free of all potential sources of hydrogen. The surfaces to be welded, filler metals, and shielding gas shall be suitably controlled.
RR-A32, Attachment 3 Page 4 of 4 Discard Transverse Side Bend t 4 Reduced Section Tensile Transverse Side Bend HAZ Charpy
/x V-Notch Transverse Side Bend Reduced Section Tensile Transverse Side Bend Discard I ,* Fusio metal line I " Of Heat affected "*
zone (HAZ)
Note:
Base metal Charpy impact specimens are not shown. This figure illustrates a similar-metal weld.
Figure A3-1 Qualification Test Plate
RR-A32, ATTACHMENT 4 Page 1 of 5 COMPARISON OF ASME CODE CASE N-504-3 AND APPENDIX Q OF ASME CODE SECTION XI WITH THE PROPOSED ALTERNATIVE OF ATTACHMENTS 1, 2 AND 3 FOR WELD OVERLAY Code Case N-504-3 and Appendix Q of ASME Code Section XI Proposed Alternative of Attachments 1, 2, and3 Code Case N-504-3 provides requirements for reducing a defect to a flaw of The proposed alternative of Attachments 1,2 and 3 provides requirements for acceptable size by deposition of weld reinforcement (weld overlay) on the installing a repair preemptive optimized weld overlay by deposition of weld outside surface of the pipe using austenitic stainless steel filler metal as an reinforcement (weld overlay) on the outside surface of the item using Nickel alternative to defect removal. Code Case N-504-3 is applicable to austenitic Alloy 52M filler metal. Attachment 2 is applicable to dissimilar metal welds stainless steel piping only. According to Regulatory Guide 1.147, the associated with nickel alloy materials. The proposed alternative of Attachment provisions of Nonmandatory Appendix Q of ASME Code Section XGmust also 2 is based on Code Case N-740-2.
be met when using this Case. Therefore, the Code Case N-504-3 requirements presented below have been supplemented by Appendix Q of ASME Code Section XI.
General Requirements General Requirements Code Case N-504-3 and Appendix Q are only applicable to P-No. 8 austenitic As specified in paragraph A2. 1(a), the proposed alternative is applicable to stainless steels. dissimilar metal 82/182 welds joining P-No. 3 to P-No. 8 or 43 materials and P-No. 8 to P-No. 43 materials. It is also applicable to austenitic stainless steel welds joining P-No. 8 materials.
Basis: Code Case N-504-3 and Appendix Q are applicableto austenitic weld overlays ofP-No. 8 austenitic stainless steel materials.Based on Code Case N-740-2, the proposedalternativeofAttachment 2 was specifically written to address the applicationof weld overlays over dissimilarmetal welds and austeniticstainless steel welds.
According to paragraph (b) of Code Case N-504-3 as supplemented by The weld filler metal and procedure requirements of paragraph A2. I(b) are Appendix Q, weld overlay filler metal shall be low carbon (0.035 percent equivalent to Code Case N-504-3 and Appendix Q except as noted below:
maximum) austenitic stainless steel applied 360 degrees around the - Weld overlay filler metal shall be austenitic nickel Alloy 52M circumference of the pipe, and shall be deposited using a Welding Procedure (ERNiCrFe-7A) filler metal which has a chromium content of at least 28 Specification for groove welding, qualified in accordance with the percent. If a stainless steel buffer layer is used as permitted by N-740-2, the Construction Code and Owner's Requirements and identified in the ferrite content of the filler material shall be 5 - 15FN as required by the Repair/Replacement Plan. Constfuction Code.
As an alternative to post-weld heat treatment, the provisions for "Ambient Temperature Temper Bead Welding" may be used on the ferritic nozzle as described in Attachment 3.
RR-A32, Attachment 4 Page 2 of 5 Basis: The weld overlay shall be depositedwith ERNiCrFe-7A (Alloy 52M) filler metal. It has been includedinto ASMIE Code Section IX as F-No. 43filler metals. Containing28.0 - 31.5 percent chromium (roughlytwice the chromium content of 82/182filler metal), thisfiller metal has excellent resistance to primarywater stress corrosion cracking. This point has been clearly documented in EPRI Technical Report MRP-115, Section 2.2. Regarding the WPS, the requirements ofA ttachments 2 and 3 provide clarificationthat the WPS usedfor depositingweld overlays must be qualifiedas a groove welding procedure to ensure that mechanicalpropertiesof the WPS areappropriately established Where welding is performed onferriticnozles, an ambient temperature temper bead WPS shall be used Suitability ofan ambient temperature temper bead WPS is addressed in Section 5 ofthis Request According to paragraph (e) of Code Case N-504-3 as supplemented by The weld overlay described in Attachments I and 2 is deposited using nickel Appendix Q, the weld reinforcement shall consist of at least two weld layers alloy 52M filler metal instead of austenitic stainless steel filler metals.
having as-deposited delta ferrite content of at least 7.5 FN. The first layer of Therefore, the basis for crediting the first layer towards the required design weld metal with delta ferrite content of at least 7.5 FN shall constitute the first thickness shall be based on the chromium content of the nickel alloy filler layer of the weld reinforcement that may be credited toward the required metal. According to paragraph A2. l(e), the first layer of nickel alloy 52M thickness. Alternatively, first layers of at least 5 FN provided the carbon deposited weld metal may be credited toward the required thickness provided content is determined by chemical analysis to be less than 0.02 percent. the portion of the layer over the austenitic base material, austenitic weld, and the associated dilution zone from an adjacent ferritic base material contains at least 24 percent chromium. The chromium content of the deposited weld metal may be determined by chemical analysis of the production weld or from a representative coupon taken from a mockup prepared in accordance with the WIPS for the production weld.
Basis: The weld overlayshall be depositedwith ERNiCrFe-7A (Alloy 52M) filler metal. Creditfor thefirst weld layer may not be taken toward the requiredthickness unless it has been shown to contain at least 24 percent chromium. This is a sufficient amount of chromium to preventprimarywater stress corrosion cracking.Section 2.2 of EPRI Technical Report MRP-115 states thefollowing: "The only well explored effect of the compositional differences among the weld alloys on primary water stress corrosioncracking is the influence of chromium. Buisine, et al. (Reference 24) evaluated the primary waterstress corrosion cracking resistanceof nickel-based weld metals with various chromium contents rangingfrom about 15 percent to 30 percent chromium. Testing was performed in doped steam and primarywater. Alloy 182, with about 14.5 percent chromium, was the most susceptible.Alloy 82 with 18-20 percent chromium took three orfour times longer to crack. For
RR-A32, Attachment 4 Page 3 of 5 chromium contents between 21 and 22 percent,no stress corrosion crack initiationwas observed... "
Design and Crack Growth Considerations Design and Crack Growth Considerations The design and flaw characterization provisions of Code Case N504-3, The design and flaw evaluation provisions in the proposed alternative are the paragraphs (f) and (g) as supplemented by Appendix Q are summarized below: same as Code Case N-504-3 as supplemented in Appendix Q with the exceptions below. The proposed design and flaw evaluation provisions are (i) Flaw characterization and evaluation are based on the as-found flaw. Flaw based on postulated flaws or as-found flaws.
evaluation of the existing flaws is based on IWB3640 for the design life. - For optimized weld overlay crack growth evaluations, a flaw with a depth of 10 percent and a circumference of 360 degrees shall be assumed or the as-
- Multiple circumferential flaws shall be treated as one flaw of length equal to found flaw size shall be used. The size of the flaws shall be projected to the the sum of the lengths of the individual flaws. end of the design life of the overlay. Crack growth, including both stress corrosion and fatigue crack growth, shall be evaluated in the materials in
- Circumferential flaws are postulated as 100 percent through-wall for the accordance with IWB-3640. If the flaw is at or near the boundary of two entire circumference with one exception. When the combined length of different materials, evaluation of flaw growth in both materials is required.
circumferential. flaws does not exceed 10 percent of the circumference, the flaws are only assumed to be 100 percent through-wall for the combined length - For optimized weld overlay design, flaws shall be assumed to be 75 percent of the flaws. through the original wall thickness for the entire circumference or in the case flaws are found by examination, evaluations shall be performed to assure the
- For axial flaws 1.5 inches or longer, or for five or more axial flaws of any assumed crack depth is a bounding condition.
length, the flaws shall be assumed to be 100 percent through-wall for the axial length of the flaw and entire circumference of the pipe. Basis: If an optimized weld overlay is applied,a Section X, Appendix VIII inservice examinationshall be performed on the welds so the condition shall (ii) For four or fewer axial flaws less than 1.5 inches in length, the weld be known. Preemptiveor repairoverlays shall be installedin accordancewith overlay thickness need only consist of two or more layers of weld metal Attachment 2 to proactively addressand mitigate anyfuture primary water meeting the deposit analysis requirements. stress corrosioncracking issues with the subject welds. Flaw assumptions are based on the requirements of MRP-169 and the requirements of Code Case N-(iii) The axial length and end slope of the weld overlay shall cover the weld 740-2 (see Attachments I & 2).
and HAZs on each side of the weld, and shall provide for load redistribution from the item into the weld overlay and back into the item without violating A preservice volumetric examinationshall be performed after applicationof applicable stress limits of the Construction Code. Any laminar flaws in the the weld overlay usingan ASME Code Section X, Appendix VIII (as weld overlay shall be evaluated in the analysis to ensure that load redistribution implemented through PDI)examinationprocedure. This examinationshall complies with the above. These requirements are usually met if the weld verify that there is no cracking in the upper 50 percent in the case ofan overlay extends beyond the projected flaw by at least 0.75(Rt)'2. optimized weld overlay. The preservice examination shall also demonstrate that the assumed through-wallcrack depths are conservative.However, if any (iv) Unless specifically analyzed, the end transition slope of the overlay shall crack-likeflaws are identified in the upper 25 percent ofthe originalweld or not exceed 45 degrees, and a slope of not more than 1:3 is recommended. base material by the preservice examination, then the as-foundflaw (postulated75 percent through-wallflaw plus the portionof theflaw in the (v) The overlay design thickness of items shall be based on the measured upper 25 percent) shall be usedfor the crackgrowth analysis. With regardto diameter, using only the weld overlay thickness conforming to the deposit design,flaws are consideredto be either 75 percent through-wallfor assumed analysis requirements. The combined wall thickness at the weld overlay, any crack depth or 100 percent through the original weld when a flaw is identified
RR-A32, Attachment 4 Page 4 of 5 planar flaws in the weld overlay, and the effects of any discontinuity (for by inspection and no structuralcredit is takenfor the weld. See Attachment 2 example, another weld overlay or reinforcement for a branch connection) for requirementsfor axial cracks mitigated by optimized weld overlay. All 1
within a distance of 0.75(Rt) 2 from the toes of the weld overlay, shall be other requirements are equivalent to Code Case N-504-3 as supplemented by evaluated and meet the requirements of IWB-, IWC-, or IWD-3640. Appendix Q.
(vi) The effects of any changes in applied loads, as a result of weld shrinkage or existing flaws previously accepted by analytical evaluation shall be -
evaluated in accordance with IWB-3640, IWC-3640, or tWD-3640, as applicable.
Examination and Inspection Examination and Inspection Acceptance Examination The acceptance standards in Attachments I and 2 are identical to those of Q-4100(c) states that the examination volume in Figure Q-4100-1 shall be paragraph Q-4100(c) except that the proposed method includes requirements ultrasonically examined to assure adequate fusion (that is, adequate bond) with and clarifications that are not included in Appendix Q. First, it specifies that the base metal and to detect welding flaws, such as inter-bead lack of fusion, the ultrasonic examination shall be conducted at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after inclusions, or cracks. Planar flaws shall meet the preservice examination completing the third layer of the weld overlay when ambient temperature standards of Table lWB-3514-2. Laminar flaws shall meet the following: temper bead welding is used. Secondly, it provides the following clarifications:
Itnterface C-D in Figure A2-1[between the weld overlay and the weld includes the bond and the HAZ from the weld overlay.
- In applying the acceptance standards, wall thickness "t," shall be the thickness of the weld overlay.
Basis: Appendix Q is applicable to austenitic stainless steel materialsonly; therefore, ambient temperature temper bead welding would not be applicable.
Ambient temperature temper bead welding is applicableto weldingperformed in the proposedalternative. When ambient temperature temper bead welding is performed, nondestructive examinations must be performedat least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completing the thirdlayer of the weld overlay to allow sufficient time for hydrogen cracking to occur (if it is to occur). Technicaljustificationfor startingthe 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completion of the third layer ofthe weld overlay is providedin Section 5 of the Request. The other two changes are simply clarificationsthat were added to ensure that the examinationrequirements were appropriatelyperformed.
Q-4100(c)(1) states that laminar flaws shallmeet the acceptance standards of The acceptance standards of the proposed method are identical to paragraph Q-Table IWB-3514-3. 4100(c)(1) except that the proposal includes the additional limitation that the total laminar flaw shall not exceed 10 percent of the weld surface area and that
RR-A32, Attachment 4 Page 5 of 5 no linear dimension of the laminar flaw area exceeds 3.0 inches.
Basis: These changes were made to provide additionalconservatism to the weld overlay examination and to reduce the size of the un-inspectable volume beneath a laminarflaw. See Section 5 of this Requestfor additional information.
Q-4100(c)(4) allows the performance of radiography in accordance with the The acceptance standards of the proposed alternative do not include the Construction Code as an alternative to Q-4100(c) (3). radiographic alternative of paragraph Q-4100(c)(4).
Basis: The UT examinationsperformedin accordancewith the proposed alternativeare in accordance with ASME Code, Section X1 Appendix VIII, Supplement II as implemented through the PDL These examinationsare consideredmore sensitivefor detection ofdefects, eitherfrom fabrication or service-induced,than either ASME Code,Section III radiographicor ultrasonic methods. Furthermore, constructiontype flaws have been included in the PDIqualficationsample sets for evaluatingproceduresand personnel.
See Section 5 of this Request for additionaljustification.
Preservice Inspection Preservice Inspection Q-4200(b) states that the preservice examination acceptance standards of Table The acceptance standards of the proposed alternative are identical to paragraph IWB-3514-2 shall be met for the weld overlay. Cracks in the outer 25 percent Q-4200(b) except proposed alternative includes the following statement: "In of the base metal shall meet the design analysis requirements of Q-3000. applying the acceptance standards, wall thickness, shall be the thickness of the weld overlay."
Basis: This provision is actuallya clarificationthat the nominal wall thickness of Table IWB-3514-2 shall be consideredthe thickness of the weld overlay. It must be remembered that the acceptance standardswere originally writtenfor the welds identified in IWB-2500. Because IWB-2500 does not address weld overlays, this clarificationwas provided to avoid any potentialconfusion.
However, defining the weld overlay thickness as the nominal wall thickness of Table IWB-3514-2 has always been the practicesince it literallybecomes the new design wall of the piping or component nozzle.
Pressure Testing Pressure Testing (h) The completed repair shall be pressure tested in accordance with IWA- The pressure testing requirements included in the alternative are similar to 5000. A system hydrostatic test is required if the flaw penetrated the pressure paragraph (h) of Code Case N-504-3 except that only a system leakage test per boundary. A system leakage test may be performed if pressure boundary is not IWA-5000 is required.
penetrated.
RR-A32, ATTACHMENT 5 Page 1 of 7 PROPOSED ALTERNATIVE TO ASME CODE SECTION XI APPENDIX VIII FOR COMPATIBILITY WITH THE PERFORMANCE DEMONSTRATION INITIATIVE PROGRAM SUPPLEMENT 11 - QUALIFICATION REQUIREMENTS FOR FULL STRUCTURAL PIPORM OREQUIREMENTS OVERLAID W WROUGHTOUGHTU STRUICTURALNGThe AUSTENITIC PIPING Proposed Alternative Rqieet to Supplement 11 WELDS Requirements Title Alternative: "Qualification Requirements for Overlaid Wrought Austenitic Piping Welds:
Basis: The title was clarified to be applicablefor all overlays on wrought austeniticpiping welds. The specific qualification shall detail the range of qualification.
10 SPECIMEN REQUIREMENTS 1.1 General. The specimen set shall conform to the following requirements.
(b) The specimen set shall consist of at least three specimens having different nominal pipe diameters and overlay thicknesses. They shall include the minimum Alternative: (b) The specimen set shall include' and maximum nominal pipe diameters for which the specimens with overlays not thicker than 0.1 inch more examination procedure is applicable. Pipe diameters than the minimum thickness, nor thinner than 0.25 inch of within a range of 0.9 to 1.5 times a nominal diameter the maximum nominal overlay thickness for which the shall beconsidered equivalent. If the procedure is applicable to pipe diameters of 24 inches or larger, the Basis:
Bss Tooaodc~uin avoid confusion, theh overlay vra thickness hcns specimen set must include at leas :tone specimen 24 inches or larger but need not include the maximum 24/- tolerance containedin the last sentence was reworded diameter. The specimen set must include at least one and the phrase "and the remaindershall be alternative specimen with overlay thickness within minus 0.1 inch flaws" was added to the next to last sentence in to plus 0.25 inch of the maximum nominal overlay paragraph].](d)(]).
thickness for which the procedure is applicable.
(d) Flaw Conditions
RR-A32, Attachment 5 Page 2 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL STRUCTURAL The Proposed Alternative to Supplement 11 OVERLAID WROUGHT AUSTENITIC PIPING Requirements WELDS Alternative: (1) ... must be in or... extending at least 50 percent through... intentional overlay fabrication flaws shall not interfere with ultrasonic detection or characterization of the base metal flaws. Specimens containing intergranular stress corrosion cracking shall be used when available. At least 70 percent of the flaws in the detection and sizing tests shall be cracks and the remainder shall be alternative flaws. Alternative flaw mechanisms, if used, shall provide crack-like reflective j1 characteristics and shall be limited by the following:
(a) The use of alternative flaws shall be limited to when the implantation of cracks produces spurious reflectors that are uncharacteristic of actual, flaws.
(b) Flaws shall be semi elliptical with a tip width of less than or equal to 0.002 inch.
Basis: This paragraphrequiresthat all base metalflaws be cracks and to extend at least 50 percent through the base metal wall. Implanting a crack requiresexcavation (1) Base metal flaws. All flaws must be cracks in or of the base materialon at least one side of the flaw. While near the - butt weld heat-affected zone, open to the this may be satisfactoryforferriticmaterials, it does not inside surface, and extending at least 75 percent produce a useable axialflaw in austenitic materials through the base metal wall. Flaws may extend 100 because the sound beam, which normallypasses only percent through the base metal and into the overlay through base material,must now travel through weld material; in this case, intentional overlay fabrication materialon at least one side, producing an unrealistic flaws shall not interfere with ultrasonic detection or flaw response. To resolve this issue, the PDIprogram characterization of the cracking. Specimens containing revised this paragraphto allow use of alternativeflaw intergranular stress corrosion cracking shall be used mechanisms under controlled conditions. For example, when available.
alternativeflaws shall be limited to when implantation.of cracks precludes obtainingan effective ultrasonic response,flaws shall be semi elliptical with a tip width of less than or equal to 0. 002 inch, and at least 70 percent of the flaws in the detection and sizing test shall be cracks and the remaindershall be alternativeflaws. To avoid confusion, the overlay thickness tolerance containedin paragraph1.1 (b) last sentence, was reworded and the phrase '.'and the remaindershall be alternativeflaws" was added to the next to last sentence. Paragraph
- 1. 1(d)(1) includes the statement that intentionaloverlay fabricationflaws shall not interfere with ultrasonic detection or characterizationof the base metalflaws.
Additionally 1.1 (d)(1) was revised to state thatflaws must extend at least 50 percent through the base metal wall.
This allows qualification to take advantage of additional test specimens to demonstrate increasedexamination depth.
(e) Detection Snecimens
RR-A32, Attachment 5 Page 3 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL STRUCTURAL PIPORM OREQUIREMENTS OVERLAID W WROUGHT OUGHT AUSTENITIC STRUIICTURALNGThe PIPING Proposed Alternative Rqieet to Supplement 11 WELDS Requirements Alternative: (1) At least 20 percent but less than 40 percent of the base metal flaws shall be oriented within
+/-20 degrees of the pipe axial direction. The remainder shall be oriented circumferentially. Flaws shall not be open to any surface to which the candidate has physical (1) At least 20 percent but less than 40 percent of the or visual access.
flaws shall be oriented within +/-20 degrees of the pipe Basis: The requirementforaxially oriented overlay axial direction. The remainder shall be oriented fabricationflaws was excludedfrom the PDIProgram as circumferentially. Flaws shall not be open to any an improbable scenario. Weld overlays are typically surface to which the candidate has physical or visual applied using automated gas tungsten arc welding access. The rules of IWA-3300 shall be used to techniques with thefiller metal applied in a determine whether closely spaced flaws should be circumferentialdirection. Because resultantfabrication treated as single or multiple flaws. induced discontinuitieswould also be expected to have major dimensions orientedin the circumferential direction axial overlayfabricationflaws.are unrealistic.
The requirementfor using IWA-3300 for proximity flaw evaluation was excluded; instead indicationsshall be sized basedon their individual merits.
Alternative: (2) Specimens shall be divided into base metal and overlay fabrication grading units. Each (specimen shall contain one or both types of grading units.
(2) Specimens shall be divided into base and overlay Flaws shall not interfere with ultrasonic detection or grading types of units. Each grading specimen shall contain one or both units,.hrceiain characterization offohrfas other flaws.
Basis: Inclusion of "metal" and 'fabrication"provides clarification.Flaw identification is improved by ensuring, flaws are not-masked by otherflaws.
Alternative: (a)(1) A base metal grading unit includes the overlay material and the outer 50 percent of the original overlaid weld. The base metal grading unit shall extend circumferentially for at least 1 inch and shall start at the weld centerline and be wide enough in the axial direction (a)(1) A base grading unit shall include at least 3 inches to encompass one half of the original weld crown and a of the length of the overlaid weld. The base grading minimum of 0.50 inch of the adjacent base material.
unit includes the outer 25 percent of the overlaid weld Basis: The phrase "and base metal on both sides, " was and base metal on both sides. The ofte egrading unit inadvertently included in the description of a base metal gradingunit, The PDIprogram intentionallyexcludes shall not include the inner 75 percent of the overlaid this requirementbecause some of the qualification weld and base metal overlay material, or base metal-to- samples includeflaws on both sides of the weld To avoid overlay interface. confusion several instances of the term "cracks" or "cracking" were changed to the term 'flaws" because of the use of alternativeFlaw mechanisms. Modified to require that a base metal gradingunit include at least]inch of the length of the overlaidweld, rather than 3 inches.
RR-A32, Attachment 5 Page 4 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL STRUCTURAL The Proposed Alternative to Supplement 1 OVERLAID WROUGHT AUSTENITIC PIPING Requirements WELDS Alternative: (a)(2) When base metal flaws penetrate into (a)(2) When base metal cracking penetrates into the the overlay material, the base metal grading unit shall not overlay material, the base grading unit shall include the be used as part of any overlay fabrication grading unit.
overlay metal within 1 inch of the crack location. This Basis: Substitutedterms provide clarificationand are portion of the overlay material shall not be used as part consistent with ld(1) above. The PDIprogramadjustsfor of any overlay grading unit. this conservative changefor excluding this type grading unit.
( Alternative: (a)(3) Sufficient unflawed overlaid weld and unflaWhen,at base gradingho unit is d esigndtbeld a base metal shall exist on all sides of the grading unit to unflawed, at least 1 inch of unflawed overlaid weld and prcueitfrngelciosrmadcntlw.
base metal shall exist on either side of the base grading preclude interfering reflections from adjacent flaws.
base. mhet shlexisnt onwedlegthuser s id of e basegBasis: Modified to requiresufficient unflawed overlaid unit. The segment of weld length used in one base weld and base metal to exist on all sides of the grading grading unit shall not be used in another base grading unit to preclude interferingreflectionsfrom adjacent unit. Base gradingunits need not be uniformly spaced flaws, rather than the I inch requirement.
around the specimen.
Alternative: (b)(1) An overlay fabrication grading unit shall include the overlay material and the base metal-to-overlay interface for a length of at least 1 inch Basis: The PDIprogram reduces the base metal-to-(b)(1) An overlay grading unit shall include the overlay overlay interface to at least 1 inch (in lieu of a minimum material and the base metal-to-overlay interface of at of 2 inches) and eliminates the minimum rectangular least 6 square inches. The overlay grading unit shall be dimension. This criterionis necessary to allow use of rectangular, with minimum dimensions of 2 inches. existing examinationspecimens that werefabricatedin order to meet NRC Generic Letter 88-01. This criterion may be more challenging than the ASME Code because of the variability associatedwith the shape of the grading unit.
Alternative: (b)(2) Overlay fabrication grading units designed to be unflawed shall be separated by unflawed overlay material and unflawed base metal-to-overlay interface for at least 1 inch at both ends. Sufficient unflawed overlaid weld and base metal shall exist on both (b)(2) An overlay grading unit designed to be unflawed sides of the overlay' fabrication grading unit to preclude unflawed base metal-to-overlay interface for at least 1 interfering reflections from adjacent flaws. The specific inchlaround inch around itsentire its entire petalittelay perimeter. inTere The sspecific ific ateaust1 area used area b sdi used innte one overlay vrafabrication arcto grading rdn unitntshall not in one overlay grading unit shall not be used in another be used in another overlay fabrication grading unit.
overlay grading unit. Overlay grading units need not be Overlay fabrication grading units need not be spaced spaced uniformly about .the specimen. nfrl bu h pcmn Basis: Paragraph1.] (e)(2)(b)(2) states that overlay fabricationgradingunits designed to be unflawed shall be separatedby unflawed overlay materialand unflawed base metal-to-overlay interfacefor at least 1 inch at both ends, rather than aroundits entire perimeter.
RR-A32, Attachment 5 Page 5 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL STRUCTURAL The Proposed Alternative to Supplement 11 OVERLAID WROUGHT AUSTENITIC PIPING Requirements WELDS Alternative:...base metal grading units, ten unflawed base metal grading units, five flawed overlay fabrication grading units, and ten unflawed overlay fabrication (b)(3) Detection sets shall be selected from Table VIII-grading units. For each type of grading unit, the set shall S2-1. The minimum detection sample set is five contain at least twice as many unflawed as flawed flawed base grading units, ten unflawed base grading grading units. For initial procedure qualification, units, five flawed overlay grading units, and ten detection sets shall include the equivalent of three unflawed overlay grading units. For each type of personnel qualification sets. To qualify new values of grading unit, the set shall contain at least twice as many essential variables, at least one personnel qualification set unflawed as flawed grading units.
is required.
Basis: Clarifiedthe guidancefor initialprocedure qualifications versus qualifying new values of essential variables.
(f) Sizing Specimen Alternative: (1) The...least 40 percent of the flaws shall be open to the inside surface. Sizing sets shall contain a distribution of flaw dimensions to assess sizing (1) The minimum number of flaws shall be ten. At least. capabilities. For initial procedure qualification, sizing sets 30 percent of the flaws shall be overlay fabrication shall include the equivalent of three personnel flaws. At least 40 percent of the flaws shall be cracks qualification sets. To qualify new values of essential open to the inside surface. variables, at least one personnel qualification set is required.
Basis: Clarifiedthe guidancefor initialprocedure qualificationsversus qualifying new values of essential variables and is consistent with 1. 1 (d)(]) above..
Alternative: (3) Base metal flaws (3) Base metal cracking used for length sizing used... circumferentially.
Basis: Clarifiedwording to be consistent with 1.1 (d)(1) demonstrations shall be oriented circumferentially. above.
(4) Depth sizing specimen sets shall include at least two Alternative: (4) Depth sizing specimen sets shall include distinct locations where cracking in the base metal at least two distinct locations where a base metal flaw extends into the overlay material by at least 0.1 inch in . extends into the overlay material by at least 0.1 inch in the through-wall direction.
Basis: Clarifiedwording to be consistent with 1.ld(])
above.
2.0 Conduct of Performance Demonstration The specimen inside surface and identification shall be concealed from the candidate. All examinations shall Alternative: The specimen ...prohibited. The overlay be completed prior to grading the results and presenting fabrication flaw test and the base metal flaw test may be the results to the candidate. Divulgence of particular performed separately.
specimen results or candidate viewing of unmasked is specimens after the performance demonstration prohibited.
2.1 Detection Test.
Flawed and unflawed grading units shall be randomly mixed. Although the boundaries of specific grading Alternative: Flawed... (base metal or overlay units shall not be revealed to the candidate, the fabrication).., each specimen..
candidate shall be made aware of the type or types of Basis:C eaoh simen.
grading units (base or overlay) that are present for each specimen.
RR-A32, Attachment 5 Page 6 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL STRUCTURAL The ProposedPIPORM Alternative to Supplement 11 OVERLAID WROUGHT AUSTENITIC PIPING Requirements WELDS 2.2 Length Sizing Test (d) For flaws in base grading units, the candidate shall Alternative: (d) For... base metal grading.., outer 50 estimate the length of that part of the flaw that is in the percent of the base metal wall thickness.
outer 25 percent of the base wall thickness. Basis: Clarifiedwordingfor consistency and to be consistent with 1.1(d)(1) above.
2.3 Depth Sizing Test.
Alternative: (a) The depth sizing test may be conducted separately or in conjunction with the detection test.
(b) When the depth sizing test is conducted in conjunction with the detection test and the detected flaws do not For the depth sizing test, 80 percent of the flaws shall satisfy the requirements of 1.1(f), additional specimens be sized at a specific location on the surface of the shall be provided to the candidate. The regions containing specimen identified to the candidate. For the remaining a flaw to be sized shall be identified to the candidate. The flaws, the regions of each specimen containing a flaw andiate shall d er intheai th ofnthetflaw to be sized shall be identified to the candidate. The candidate shall determine the maximum depth of the in each region.
flaw in each region. (c) For a separate depth sizing test, the regions of each specimen containing a flaw to be sized shall be identified to the candidate. The candidate shall determine the maximum depth of the flaw in each region.
Basis: Clarifiedwording to better describe process.
3.0 ACCEPTANCE CRITERIA 3.1 Detection Acceptance Criteria Examination Examinatiedon procedures, proeduresion equipment, eqente and andupersonnel psonnel are a Alternative: Examination procedures are qualified for qualified for detection when the results of the . dectowhn performance demonstration satisfy the acceptance detection when:
- a. All flaws within the scope of the procedure are detected criteria of Table Vl11-S2-1 for both detection and false and the results of the performance 'demonstration satisfy call.hal Te besatsfid citeia spartel bythe the acceptance criteria of Table VIII-S2-1 for false calls.
demonstration results for base grading units and for b. At least one successful personnel demonstration has been performed meeting the acceptance criteria defined in (c).
- c. Examination equipment and personnel are qualified for detection when the results of the performance demonstration satisfy the acceptance criteria of Table VIII-S2-1 for both detection and false calls.
- d. The criteria in (b) and (c) shall be satisfied separately by the demonstration results for base metal grading units and for overlay fabrication grading units.
Basis: Clarifiedwording to better describe the difference between procedure qualification and equipment and personnelqualifications.
3.2 Sizing Acceptance Criteria (a) The RMS error of the flaw length measurements, as Alternative: (a) The...base metal flaws are...outer 50 flawoflengths, is less than orisequal pernt though- base-metal position.
compared to 0.75 inch. Thetrue to the length base metal cracking percent though-base-metal position.
toasured 0.5 i the l5perengthofbase metal crackingi Basis: Clarifiedwording to'be consistent with ]. I(d)(1) measured at the 75 percent through-base-metal above.
position.___________________________
RR-A32, Attachment 5 Page 7 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL STRUCTURAL The ProposedPIPORM Alternative to Supplement 11 OVERLAID WROUGHT AUSTENITIC PIPING Requirements WELDS Alternative: This requirement is omitted.
Basis: The requirementfor reportingall extensions of (b) All extensions of base metal cracking into the cracking into the overlay is omittedfrom the PDI overlay material by at least 0.1 inch are reported as Programbecause it is redundantto the RMS calculations overlay materuialob theoverla in ch r rteport. a performed in paragraph3.2(c) and its presence adds being intrusions into the overlay material, confusion and ambiguity to depth sizing as requiredby paragraph3.2(c). This also makes the weld overlay program consistent with the supplement 2 depth sizing criteria.
Davis-Besse Nuclear Power Station 10 CFR 50.55a Request Number RR-A33, Revision 0 Page 1 of 18 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. American Society of Mechanical Engineers (ASME) Code Components Affected Components: Reactor Coolant Pump Inlet Nozzle Dissimilar Metal Welds Code Class: ClassCla SExaminati*nCategry- B-J Code Item Numnber:~ 19.1 1 Weld Numbers: >Description ~size Nlaterials RC-MK-A-67-1-FW134B Reactor Coolant Norminal Cast Stainless Steel Inlet Pump 1-1 28 inch Nozzle /.Alloy 82-182 Weld /
Suction Nozzle ID Carbon Steel Elbow RC-MK-A-67-3-FW105B Reactor Coolant Nominal CastStainless Steel Inlet Pump 1-2 28 inch Nozzle / Alloy 82-182 Weld /
Suction Nozzle ID Carbon Steel Elbow RC-MK-A-67-1-FW105A Reactor Coolant Nominal Cast Stainless Steel Inlet Pump 2-1 28 inch Nozzle / Alloy 82-182 Weld /
Suction Nozzle ID Carbon Steel Elbow RC-MK-A-67 FW134A Reactor Coolant Nominal Cast Stainless Steel Inlet Pump 2-2 28 inch Nozzle / Alloy 82-182 Weld /
Suction Nozzle ID Carbon Steel Elbow
- Cast Stainless Steel Inlet A- 351 Grade CF8M (P-8)
Carbon Steel Elbow - A 516 Grade 70 (P41) 90 degree elbow internally clad with SA 240-304L
- ID = Inside Diameter
RR-A33 Page 2 of 18 Components: Reactor Coolant Pump Discharge Piping Dissimilar Metal Welds Code Class: Class 1 Examination Category: B-J Code Item Number:_ B9.11 3 Weld Numbers: . Description Size 2 Mvaterials i
RC-MK-B-59-1-SW143B Reactor Coolant Nominal Stainless Steel Pipe / Alloy 82-Pump 1-1 28 inch 182 Weld / Carbon Steel Elbow Discharge Piping ID RC-MK-B-44-1-SW69B Reactor Coolant Nominal Stainless Steel Pipe / Alloy 82-Pump 1-2 28 inch 182 Weld / Carbon Steel Elbow Discharge Piping ID RC-MIK-A-61-1-SW69A Reactor Coolant Nominal Stainless Steel Pipe / Alloy 82-Pump 2-1 28 inch 182 Weld / Carbon Steel Elbow Discharge Piping ID RC-MK-B-56-1-SW143A Reactor Coolant Nominal Stainless Steel Pipe / Alloy 82-Pump 2-2 28 inch 182 Weld / Carbon Steel Elbow Discharge Piping ID 3 Stainless Steel Pipe- A-376 Type 316 (P-8)
Carbon Steel Elbow - A 516 Grade 70 (P-I) 24 degree elbow internally clad with SA 240-304L Components: Y Reactor Vessel Core Flood Nozzle Dissimilar Metal Welds Class: .Code Class 1 Examination Category: B-F Code Item Number: B5.10 Weld Numbers: Deseription Siz~e
- 2 Materials RC-RPV-WR-53-Y Core Flood 1-1 Nominal Low Alloy Steel Nozzle / Alloy Safe-End to RV 12 5/8 82-182 Weld / Stainless Steel Nozzle (Y-Axis) inch ID Safe End RC-RPV-WR-53-W Core Flood 1-2 Nominal Low Alloy Steel Nozzle / Alloy Safe-End to RV 12 5/8 82-182 Weld / Stainless Steel Nozzle (X-Axis) inch ID Safe End
- Low Alloy Steel Nozzle - SA-508 Class 2 (P-3) internally clad with SA 371-ER 308L
- Stainless Steel Safe End - SA-336 F8M (P-8)
RR-A33 Page 3 of 18 romoonents=*:*Reactor Coolant System Cold Leg Drain Line Dissimilar Metal ode Cass: Class I Examimatii tegory: B-J Code iUm Number: B9.21 Weld Number ~ 2Dq iiption, Size Maiterials ~
RC-40-CCA-18-3-FW9 Cold Leg 1-2 Drain Nominal Carbon Steel Nozzle / Alloy 82-Nozzle To Pipe 2 1/2 inch 182 Weld / Stainless Steel ID Elbow RC-40-CCA-18-7-FW25 Cold Leg 2-1 Drain Nominal Carbon Steel Nozzle / Alloy 82-Nozzle To Drain 2 1/2 inch 182 Weld / Stainless Steel Pipe ID Elbow RC-40-CCA-18-5-FW18 Cold Leg 2-2 Drain Nominal Carbon Steel Nozzle / Alloy 82-Nozzle To Drain 2 1/2/2 inch 182 Weld / Stainless Steel Pipe ID Elbow
- Carbon Steel Nozzle - A-105 Grade 2 (P-i) internally clad with SA-371 ER 308L stainless steel Stainless Steel Elbow - SA-403 WP 316 (P-8)
- 2. Applicable Code Edition and Addenda American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code)Section XI - 1995 Edition through 1996 Addenda
- 3. ADolicable Code Reouirement IWA-4410(a) of ASME Code Section XI states:
"Repair/replacement activities shall be performed in accordance with the Owner's Requirements and the original Construction Code of the component or system, except as provided in IWA-4410 (b), (c), and (d)."
IWA-4410(b) of ASME Code Section XI states in part:
"Later Editions and Addenda of the Construction Code, or a later different Construction Code, either in its entirety or portions thereof, and Code Cases may be used, provided the substitution is as listed in IWA-4221(b)."
IWA-4410(c) of ASME Code Section XI states:
"Alternatively, the applicable requirements of IWA-4600 may be used for welding and the applicable requirements of IWA-4700 may be used for heat exchanger tube plugging and sleeving."
ASME Code Section XI, Appendix VIII, Supplement 11 provides requirements for the qualification requirements for the ultrasonic examination of Full Structural Overlaid Wrought Austenitic Piping Welds.
RR-A33 Page 4 of 18
4. Reason for Request
Dissimilar metal welds (DMWs) containing nickel welding alloys 82 and 182 have experienced primary water stress corrosion cracking (PWSCC) in components operating at pressurized water reactor temperatures.
FirstEnergy Nuclear Operating Company. (FENOC) proposes to mitigate the primary water stress corrosion cracking susceptibility of the Davis-Besse Nuclear Power Station (Davis-Besse) reactor coolant pump inlet and discharge, the cold leg drain nozzle, and the reactor vessel core flood nozzle dissimilar metal welds by installing a full structural weld overlay (full structural weld overlay) on each of the dissimilar metal welds. This approach provides an alternative to inspection alone as a means to assure the structural integrity of these locations. Davis-Besse may choose to apply preemptive full structural weld overlays without performance of an ultrasonic examination prior to the design and application of the weld overlay contingent upon authorization from the NRC.
Currently, there are no generically accepted criteria for a licensee to apply a full structural weld overlay to Alloy 82/182 weld material. The issue and addenda of ASME Code Section XI applicable to Davis-Besse does not .contain requirements for weld overlays. Dissimilar metal weld overlays have been applied to other components at Davis-Besse using the modified requirements of ASME Code Cases N-504-2 and N-638-1. However, since Code Case N-504 (and its later versions) is written specifically for stainless steel pipe-to-pipe weld full structural overlays, and Code Case N-638-1 contains unnecessary restrictions and requirements, an alternative is desired. This request describes the requirements FENOC proposes to use to design and install full structural weld overlays on reactor vessel nozzle and reactor coolant piping dissimilar metal welds.
- 5. Proposed Alternative and Basis for Use Pursuant to IOCFR 50.55a (a)(3)(i), FENOC proposes as an alternative to the ASME Code requirements stated above, the use of the alternative described in Attachment I to this request to perform full structural weld overlays. This alternative is based on the methodology contained in ASME Code Case N-740-2.
Appendix VIII, Supplement I I of the 1995 Edition, 1996 Addenda of ASME Code Section XI [reference 1] specifies requirements for performance demonstration of ultrasonic examination procedures, equipment, and personnel used to detect and size flaws in full structural overlays of wrought austenitic piping welds. Relief is requested to allow use of the Performance Demonstration Initiative (PDI) program implementation of Appendix VIII for qualification of ultrasonic examinations used to detect and size flaws in the preemptive structural weld overlays of this request. The proposed modifications to Appendix VIII, Supplement 11 for use on full structural weld overlays are detailed in Attachment 2.
The use of this alternative is requested on the basis that the proposed requirements will provide an acceptable level of quality and safety.
FENOC plans to apply a full structural Alloy 52M overlay to each of the dissimilar metal Alloy 82/182 dissimilar metal welds identified in Section 1.0, unless optimized weld overlays are applied as proposed within FENOC Alternative RR-A33. Electric Power Research Institute (EPRI) Materials Reliability Program MRP-169 [reference 8] provides
RR-A33 Page 5 of 18 the basis and requirements for the weld overlay techniques. The MIRP-169 design requirements that apply to Davis-Besse are detailed in Attachment 1 and the implementation requirements that apply are detailed in Attachments 1 and 2.
ASME Code Case N-740-2 has been approved recently by the ASME Code Committee to specifically address full structural overlays on nickel alloy dissimilar metal welds.
ASME Code Case N-740-2 also incorporates the latest approved versions of ASME Code Case N-638. However, ASME Code Case N-740-2 has not yet been accepted by the NRC in Regulatory Guide 1.147. ASME Code Case N-504-3, which provides requirements for weld overlay of stainless steel piping, has been conditionally accepted in Revision 15 of Regulatory Guide 1.147 with the condition that the provisions of ASME Code Section XI, Nonmandatory Appendix Q, Weld Overlay. Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Weldments, must be met. A comparison of the proposed alternative and ASME Code Case N-504-3/Appendix Q is provided in Attachment 3.
The proposed alternative provides an acceptable methodology for preventing primary water stress corrosion cracking and for reducing defects that may be observed in these welds to an acceptable size. The use of weld overlay filler metals that are resistant to primary water stress corrosion cracking (for example, Alloy 52/52M), weld overlay procedures that create compressive residual stress profiles in the original weld, and post overlay preservice and inservice inspection requirements provide assurance that structural integrity is maintained for the life of the plant. The weld overlays shall also meet the applicable stress limits from ASMIE Code Section III. Crack growth evaluations for primary water stress corrosion cracking and fatigue of as-found (or conservatively postulated) flaws shall demonstrate that structural integrity will be maintained.
Rupture of the large primary loop piping at Davis-Besse has been eliminated as the structural design basis. The effects of the weld overlay application on the leak-before-break'ahalysis will be evaluated to show the effects of do not invalidate theconclusions of the existing design basis.
Schematic Configurationfor FSWOL Locations Schematic representations of the weld overlay for the reactor coolant pump inlet and discharge dissimilar metal welds are presented in Figures 5-1 and 5-2, respectively.
Schematic representations of the weld overlay for the reactor vessel core flood nozzles and reactor coolant pump cold leg drain nozzles dissimilar metal welds are presented in Figures 5-3 and 5-4, respectively.
RR-A33 Page 6 of 18 Reactor CoolantPump Inlet Nozzle DissimilarMetal Welds The inlet to the reactor coolant pumps is a 28-inch carbon steel elbow that is welded to the cast stainless steel pump inlet. The carbon steel elbow is buttered with Alloy 82/182 weld material. The carbon steel elbow is internally clad with stainless steel.
The carbon steel elbow is welded to the pump inlet with Alloy 82/182 weld material.
- ss SS"Cladding Butter Notes:
- 1. Elbow - A-516, Grade 70 carbon steel, internally clad with SA240-304L
- 2. Cast Stainless Steel Pump Inlet - A-351 Grade CF8M, Type 316 Figure 5-1 Schematic Configuration for FSWOL for Reactor Coolant Pump Inlets (Suction)
RR-A33 Page 7 of 18 Reactor CoolantPump Discharge Piping DissimilarMetal Welds The reactor coolant pump outlets (discharge) are fabricated from cast austenitic stainless steel and attached to 28-inch austenitic stainless steel piping which acts as a safe end. The piping is then attached to an elbow fabricated from carbon steel internally clad with stainless steel. The carbon steel elbow is buttered with Alloy 82/182 weld material. The dissimilar metal weld is fabricated from Alloy 82/182 weld metal.
'Weld'Overlay SS Cladding Butter Notes:
- 1. Elbow - A-516, Grade 70, internally clad with SA240-304L
- 2. Safe End - A-376, Type 316
- 3. Cast Stainless Steel Pump Outlet (Discharge) - A-351 Grade CF8M, Type 316 Figure 5-2 Schematic Configuration for FSWOL for Reactor Coolant Pump Outlets (Discharge)
RR-A33 Page 8 of 18 Reactor Vessel Core FloodNozzle DissimilarMetal Welds The core flood nozzle is a horizontal 14 inch low alloy steel nozzle welded to the carbon steel reactor vessel, and is internally clad with stainless steel. The nozzle is welded to a stainless steel safe end with Alloy 82/182 weld material. The stainless steel safe end is then welded to a 14 inch stainless steel pipe.
Notes:
- 1. Safe End - SA-336, F8M
- 2. LAS Nozzle - SA-508, Class 2, internally clad with SA 371-ER 308L Figure 5-3 Schematic Configuration for FSWOL for RPV Core Flood Nozzles
RR-A33 -
Page 9 of 18 Reactor Coolant System Cold Leg DrainLine DissimilarMetal Welds The Reactor Coolant Pump inlet lines have a drain connection at the low point of the line. Each cold leg drain nozzle is a vertical 2 V2 inch carbon steel nozzle that is welded to the carbon steel Reactor Coolant piping, and is internally clad with stainless steel. The dissimilar metal weld is ,fabricated from Alloy 82/182 weld metal.
Weld Overlay. 4 Notes:
- 1. Elbow - SA403, Grade WP316
- 2. Carbon Steel Nozzle -Ar105, Grade 2, internally clad with SA371 ER308L Figure 5-4: Schematic Configuration for FSWOL for RCP Cold Leg Drain Line Nozzles Suitability of ProposedPost Overlay Nondestructive Examination (NDE)
As a part of the design of the weld overlay, the weld length, surface finish, and flatness are specified to allow qualified ASME Code Section XI, Appendix VIII ultrasonic examinations, as implemented through the EPRI PDI Program, of the weld overlay and the required volume of the base material and original weld. The examinations specified in this proposed alternative provide adequate assurance of structural integrity for the following reasons:
- The ultrasonic (UT) examinations to be performed with the proposed alternative are in accordance with ASME Code Section XI, Appendix VIII, Supplement 11, as implemented through the PDI. These examinations are considered more sensitive for detection of defects, either from fabrication or service induced, than either ASME Code Section III radiography or ultrasonic methods. Further, construction flaws have been included in the PDI qualification sample sets for evaluating procedures and personnel.
- ASME Code Section XI has specific acceptance criteria and evaluation methodology to be utilized with the results from these more sensitive examinations. They consider the materials in which the flaw indications are detected, the orientation and size of the indications, and ultimately their potential structural effects on the
RR-A33 Page 10 of 18 component. The acceptance criteria include allowable flaw indication tables for planar flaws (Table IWB-3514-2) and for laminar flaws (Table IWB-3514-3).
" A laminar flaw is defined in ASME Code Section XI as a flaw oriented within 10 degrees of a plane parallel to the surface of the component. This definition is applicable to welds and weld overlays as well as base materials. The standard imposed for evaluating laminar flaws in ASME Code Section XI is more restrictive than the Section III standard for evaluating laminations. The ASME Code Section XI laminar flaW standards, ASME Code Table IWB-3514-3, are supplemented in Attachment 1 such that the total laminar flaw shall not exceed 10 percent (%) of the weld overlay surface area and no linear dimension of the laminar flaw shall exceed 3 inches. For weld overlay areas where examination is precluded by the presence of the flaw, it is required to postulate the area as being cracked.
" Any planar flaws found during either the weld overlay acceptance or preservice examinations are required to meet the preservice standards of ASME Code Table IWB-3514-2. In applying the planar flaw standards, the thickness of the component shall be defined as the thickness of the weld overlay and the issue of any flaws masked from examination shall also be addressed as a part of the proposed alternative.
" Weld overlays for repair of cracks in piping are not addressed by ASME Code Section III. ASME Code Section III utilizes nondestructive examination procedures and techniques with flaw detection capabilities that are within the practical limits of workmanship standards for welds. These standards are most applicable to volumetric examinations conducted by radiographic examination.
Radiography (RT) of weld overlays is not practical because of the presence of radioactive material in the reactor coolant system and water in the pipes. The ASME Code Section III acceptance standards are written for a range of fabrication flaws including lack of fusion, incomplete penetration, cracking, slag inclusions, porosity, and concavity. However, experience and fracture mechanics have demonstrated that many of the flaws that would be rejected using ASME Code Section III acceptance standards do not have a significant effect on the structural integrity of the component. The proposed alternatives in Attachments 1 and 2 were written to specifically address weld overlays, and not only does this alternative adequately examine the weld overlays, but it provides more appropriate examinations and acceptance criteria than the staff imposed position. Conversely, the imposition of ASME Code Section III acceptance standards to weld overlays is inconsistent with years of NRC precedence and without justification given the evidence of past NRC approvals and operating experience.
The ASME Code Section XI acceptance standards are the logical choice for evaluation of potential flaw indications in post-overlay examinations, in which unnecessary repairs to the overlays would result in additional personnel radiation exposure without a compensating increase in safety and quality, and could potentially degrade the effectiveness of the overlays by affecting the favorable residual stress field that they produce. They are consistent with previous criteria approved by the NRC for weld overlay installations.
Weld overlays have been used for repair and mitigation of cracking in boiling water reactors for many years. In Generic Letter 88-01, the NRC approved the use of ASME Code Section XI inspection procedures for determining the acceptability of installed weld.
RR-A33 Page 11 of 18 overlays. In addition, for a number of years the NRC has accepted various versions of ASME Code Case N-504 in RG 1.147 with no conditions regarding the use of ASME Code Section XI acceptance standards for determining the acceptability of weld overlays. ASME Code Case N-504 (and its later versions) was developed to codify the boiling water reactor (BWR) weld overlay experience and NRC approval is consistent with the NRC acceptability of BWR weld overlays. Similarly, ASME Code Case N-638 was acceptable for use in RG 1.147 Revision 13 with no conditions and has been approved by the NRC for use in both BWR and PWR weld overlay installations using the ASME Code Section XI acceptance standards. The NRC staff found the use of the ASME Code Section XI, Appendix VIII, Supplement 11 acceptable for identifying both construction and service induced flaws in the Safety Evaluation Report (SER) for DC Cook Plant dated February 19, 2006 and tacitly approved the associated ASME Code Section XI acceptance criteria, Tables IWB-3514-2 and IWB-3514-3. The staff also accepted the use of ASME Code Section XI acceptance standards in an SER dated July 21, 2004 for the Three Mile Island Plant, for disposition of flaws identified in a weld overlay by PDI qualified ultrasonic examinations, with additional restrictions similar to those proposed herein for regions in which inspection is precluded by the flaws.
Suitability ofProposedAmbient Temperature Temper Bead Technique The overlays addressed by this alternative shall be performed using ambient temperature temper bead welding in lieu of Post Weld Heat Treatment, in accordance with Attachment
- 1. Research by the Electric Power Research Institute (EPRI) and other organizations on the use of an ambient temperature temper bead process using the machine gas tungsten arc welding (GTAW) process is documented in EPRI Report GC-1 11050 [reference 3].
According to the EPRI report, repair welds performed with an ambient temperature temper bead procedure utilizing the machine gas tungsten arc welding process exhibit mechanical properties equivalent to or better than those of the surrounding base material. Laboratory testing, analysis, successful procedure qualifications, and successful repairs have all demonstrated the effectiveness of this process.
The effects of the ambient temperature temper bead welding process of Attachment I on mechanical properties of repair welds, hydrogen cracking, cold restraint cracking, and extent of overlay coverage of ferritic base metal are addressed in the following paragraphs.
Mechanical Propertiesof Repair Welds The principal reasons to preheat a component prior to repair welding is to minimize the potential for cold cracking. The two cold cracking mechanisms are hydrogen cracking and restraint cracking. Both of these mechanisms occur at ambient temperature. Preheating slows down the cooling rate resulting in a ductile, less brittle microstructure thereby lowering susceptibility to cold cracking. Preheat also increases the diffusion rate of monatomic hydrogen that may have been trapped in the weld during solidification. As an alternative to preheat, the ambient temperature temper bead welding process utilizes the tempering action of the welding procedure to produce tough and ductile microstructures.
Because precision bead placement and heat input control are utilized in the machine gas tungsten arc welding process, effective tempering of weld heat affected zone (HAZ) is possible without the application of preheat. According to Section 2-1 of EPRI Report GC- 111050, "the temper bead process is carefully designed and controlled such that successive weld beads supply the appropriate quantity of heat to the untempered heat
RR-A33 Page 12 of 18 affected zone such that the desired degree of carbide precipitation (tempering) is achieved.
The resulting microstructure is very tough and ductile."
The IWA-4600 temper bead process also includes a postweld.soak requirement.
Performed at 300 degrees Fahrenheit (0F) for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (P-No. 3 base materials), this postweld soak assists diffusion of any remaining hydrogen from the repair weld. As such, the postweld soak is a hydrogen bake-out and not a postweld heat treatment as defined by the ASME Code. At 300 degrees Fahrenheit, the postweld soak does not stress relieve, temper, or alter the mechanical properties of the weldment in any manner. Since the potential for hydrogen absorption is greatly diminished by the use of gas tungsten arc welding temper bead process, no postweld soak is needed for this application.
The alternative in Attachment 1 establishes detailed welding procedure qualification requirements for base. materials, filler metals, restraint, impact properties, and other procedure variables. The qualification requirements provide assurance that the mechanical properties of repair welds shall be equivalent to or superior to those of the surrounding base material.
Hydrogen Cracking Hydrogen cracking is a form of cold cracking. It is produced by the action of internal tensile stresses acting on low toughness heat affected zones. The internal stresses are produced from localized build-ups of monatomic hydrogen. Monatomic hydrogen forms when moisture or hydrocarbons interact with the welding arc and molten weld pool. The monatomic hydrogen can be entrapped during weld solidification and tends to migrate to transformation boundaries or other microstructure defect locations. As concentrations build, the monatomic hydrogen recombines to form molecular hydrogen - thus generating localized internal stresses at these internal defect locations. If these stresses exceed the fracture toughness of the material, hydrogen induced cracking occurs. This form of cracking requires the presence of hydrogen and low toughness materials. It is manifested by intergranular cracking of susceptible materials and normally occurs within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of welding.
IWA-4600 establishes elevated preheat and postweld soak requirements. The elevated preheat temperature of 300 degrees Fahrenheit increases the diffusion rate of hydrogen from the weld. The postweld soak at 300 degrees Fahrenheit was also established to bake-out or facilitate diffusion of any remaining hydrogen from the weldment. However, while hydrogen cracking is a concern for shielded metal arc welding (SMAW), which uses flux covered electrodes, the potential for hydrogen cracking is significantly reduced when using machine gas tungsten arc welding.
The machine gas tungsten arc welding process is inherently free. of hydrogen. Unlike the shielded metal arc welding process, gas tungsten arc welding filler metals do not rely on flux coverings that may be susceptible to moisture absorption from the environment.
Conversely, the gas tungsten arc welding process utilizes dry inert shielding gases that cover the molten weld pool from oxidizing atmospheres. Any moisture on the surface of the component being welded is vaporized ahead of the welding torch. The vapor is prevented from being mixed with the molten weld pool bythe inert shielding gas that blows the vapor away before it can be mixed. Furthermore, modem filler metal manufacturers produce wires having very low residual hydrogen. This is important
RR-A33 Page 13 of 18 because filler metals and base materials are the most realistic sources of hydrogen for the automatic or machine gas tungsten arc welding temper bead process. Therefore, the potential for hydrogen-induced cracking is greatly reduced by using the machine gas tungsten arc welding process. Extensive research has been performed by EPRI [reference 7] which provides a technical basis for starting the 48-hour hold after completing the third temper bead weld layer rather than waiting for the weld overlay to cool to ambient temperature. The hold time required by ASME Code Cases N-638-4 and N-740-2 shall be implemented in accordance with this latest research. This approach has been previously reviewed and approved by the NRC for pressurizer nozzle overlays.
Cold Restraint Cracking Cold cracking generally occurs during cooling at temperatures approaching ambient temperature. As stresses build under a high degree of restraint, cracking may occur at defect locations. Brittle microstructures with low ductility are subject to cold restraint cracking. However, the ambient temperature temper bead process is designed to provide a sufficient heat inventory so as to produce the desired tempering for high toughness.
Because the machine gas tungsten arc welding temper bead process provides precision bead placement and control of heat, the toughness and ductility of the heat affected zone is typically superior to the base material. Therefore, the resulting structure shall be appropriately tempered to exhibit toughness sufficient to resist cold cracking.
Area Limitation IWA-4600 and early versions of ASME Code Case N-638 for temper bead welding contained.a limit of 100 square inches for the surface area of temper bead weld over the ferritic base metal. The associated limitation proposed in this alternative is 700 square inches.
EPRI Report NP-101 1898, November 2005, [reference 2] describes the technical justification for allowing increased overlay areas up to 500 square inches over ferritic material. The white paper contained in this report notes that the original limit of 100 square inches in ASME Code Case N-638-1 was arbitrary. It cites, within Section 2a of the white paper, evaluations of a 12-inch diameter nozzle weld overlay to demonstrate adequate tempering of the weld heat affected zone residual stress evaluations demonstrating acceptable residual stresses in weld overlays ranging from 100 to 500 square inches per Section 2b of the white paper, and service history in which weld repairs exceeding 100 square inches were NRC approved and applied to dissimilar metal weld nozzles in several BWRs and PWRs as discussed within Section 3c of the white paper.
Some of the cited repairs are greater than 15 years old, and have been inspected several times with no evidence of any. continued degradation.
Section 5.1, Analyses Conclusions, in EPRI Report NP- 10 11898, when evaluating the 100 square inch and 500 square inch repair sizes provides the following statement.
"Results demonstrate that a larger weld repair area does not have a significant adverse effect on the weld residual stress. In some cases, the larger repair area is much more beneficial because of the lower tensile residual stress or higher compressive residual stress. Especially for the case of axial weld repair where an axial crack could exist, the hoop stress is more compressive or less tensile within the weld repair and outside the
RR-A33 Page 14 of 18 repair area. The larger repair area could be less susceptible to the crack growth, due to either stress corrosion or fatigue."
Section 5.2, Overall Conclusions, in EPRI Report NP-101 1898, also states that:
"The restriction on surface area for temper bead welding was arbitrary, is overly restrictive, leads to increased cost and dose for repairs and does not contribute to safety."
Additionally, "there is no direct correlation of residual stresses with surface area of the repair either for cavity or overlay repairs done using temper bead welding. Cases have been analyzed up to 500 square inches that verify that residual stresses for cavity repairs are at an acceptable level and that residual stresses associated with weld overlay repairs remain compressive in the weld region for larger area repairs as well a for smaller area repairs."
Due to the outside diameter of the reactor coolant pump piping, the weld overlay repair may extend up to greater than 600 square inches of surface area on the carbon steel component, but less than 700 square inches of surface area. Consequently, the proposed alternative includes a maximum individual weld overlay area requirement of 700 square inches, as discussed within General Requirement A2.2(b) of Attachment 1.
Analyses and Verifications The following list of analyses and verifications shall be performed subject to the specific design, analysis, and inspection requirements that have been defined in this relief request.
- 1. Nozzle specific stress analyses shall be performed to establish a residual stress profile in the nozzle. Inside diameter (ID) weld repairs shall be assumed in these analyses to effectively bound any actual weld repairs that may have occurred in the nozzles. The analysis shall then simulate application of the weld overlays to determine the final residual stress profile. Post weld overlay residual stresses at normal operating conditions shall be shown to result in a stress state on the inside surface of each component, that assures that further crack initiation due to primary water stress corrosion cracking is highly unlikely.
- 2. Fracture mechanics analyses shall be performed to predict crack growth.. Crack growth due to primary water stress corrosion cracking The and fatigue crack growth in the original dissimilar metal weld shall be evaluated. crack growth analyses shall consider all design loads and transients, plus the post weld overlay through-wall residual stress distributions, and shall demonstrate that the assumed cracks shall not grow beyond the design bases for the weld overlays (that is, through the original dissimilar metal weld thickness) for the time period until the next scheduled inservice inspection. The crack growth analyses shall determine the time period for the assumed cracks to grow to the design basis for the weld overlays.
- 3. The analyses shall demonstrate that the application of the weld overlays does not impact the conclusions of the existing nozzle stress reports. ASME Code Section III stress and fatigue criteria shall be met for the regions of the overlays remote from observed (or assumed) cracks.
RR-A33 Page 15 of 18
- 4. The original leak-before-break calculations will be updated with an evaluation demonstrating that due to the efficacy of the overlay for primary water stress corrosion cracking mitigation, concerns for original weld susceptibility to cracking has been resolved. The effects of the mitigation on the leak-before-break analysis shall be evaluated to show the effects of application of weld overlays do not invalidate the conclusions of the existing design basis.
- 5. Shrinkage shall be measured during the overlay application. Shrinkage stresses arising from the weld overlays at other locations in the piping systems shall be demonstrated to not have an adverse effect on the systems. Clearances of affected supports and restraints shall be checked after the overlay repair, and shall be reset within the design ranges as required.
- 6. The total added weight on the piping systems due to the overlays shall be evaluated for potential impact on piping system stresses and dynamic characteristics.
- 7. The as-built dimension of the weld overlays shall be measured and evaluated to demonstrate that they equal or exceed the minimum design dimensions of the overlays.
Summaries of the results of the analyses listed in Items I through 4 above will be submitted to the NRC prior to entry into Mode 4 following completion of the weld overlays. Items 5 though 7 are performed following installation of the weld overlays and results shall be included in the design modification package closure documents. This information shall be available to resident or field inspectors for review as needed.
The following information will be submitted to the NRC within 14 days of completion of the final ultrasonic examination of the overlaid welds. Also included in the results will be a discussion of any repairs to the overlay material and/or base metal and the reason for the repair.
- a listing of indications detected
- the disposition of all indications using the standards of ASME Code Section XI, IWB-3514-2 and!or IWB-3514-3 2
criteria and, if possible, the type and nature of the indications Conclusions Quality and Safety of ProposedAlternative Implementation of the alternative to IWA-4600 of ASME Code Section XI described in Attachments 1 and 2 of this request shall produce effective repairs for The recording criteria of the ultrasonic examination procedure to be used for the examination of the Davis-Besse overlays requires that all indications, regardless of amplitude, be investigated to the extent necessary to provide accurate characterization, identity, and location. Additionally, the procedure requires that all indications, regardless of amplitude, that cannot be clearly attributed to the geometry of the overlay configuration be considered flaw indications.
2 The ultrasonic examination procedure requires that all suspected flaw indications are to be plotted on a cross sectional drawing of the weld and that the plots should accurately identify the specific origin of the reflector.
RR-A33 Page 16 of 18 potential primary water stress corrosion cracking in the identified welds and improve piping geometries to permit ASME Code Appendix VIII ultrasonic examinations as implemented through the PDI program. Weld overlay repairs of dissimilar metal welds have been installed and performed successfully for many years in both pressurized water reactor and boiling water reactor applications. The alternative provides improved structural integrity and reduced likelihood of leakage for the primary system. Accordingly, the use of the alternative provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(a)(3)(i).
- 6. Duration of Proposed Alternative The provisions of this alternative are applicable to the third ten-year in-service inspection interval for Davis-Besse which commenced on September 21, 2000 and will end on September 20, 2012.
The weld overlays installed in accordance with-the provisions of this alternative shall remain in place for the design life of the repair established as described in Attachments 1 and 2.
- 7. References
- 1. ASME Boiler and Pressure Vessel Code,Section XI, 1995 Edition through 1996 Addenda, Appendix VIII, Supplement 11, "Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds."
- 2. EPRI Report 1011898, November 2005, "RRAC Code Justification for the Removal of the 100 Square Inch Temper Bead Weld Limitation", EPRI, Palo Alto, CA, and Structural Integrity Associates, Inc., San Jose, CA.
- 3. EPRI Report GC- 111050, November 1998, "Ambient Temperature Preheat for Machine GTAW Temper bead Applications", EPRI, Palo Alto, CA, and Structural, Integrity Associates, Inc., San Jose, CA.
- 4. ASME Boiler and Pressure Vessel Code,Section XI, 1995 Edition with Addenda through 1996, Appendix VIII, Supplement 10.
- 5. EPRI Materials Reliability Program Report: Crack Growth Rates for Evaluating PWSCC of Alloy 82, 182, and 132 Welds (MRP-1 15), EPRI, Palo Alto, CA, and Dominion Engineering, Inc., Reston, VA: November 2004. 1006696.
- 6. ASME Code Case N-740-2 "Dissimilar Metal Weld Overlay, for Repair or Mitigation of Class 1, 2, and 3 Items".
- 7. EPRI Report 1013558, Temperbead Welding Applications, 48 Hour Hold Requirements for Ambient Temperature Temperbead Welding, EPRI, Palo Alto, CA and Hermann & Associates, Key Largo, FL, December 2006.
- 8. EPRI Materials Reliability Program Report: Technical Basis forPreemptive Weld Overlays for Alloy 82/182 Butt Welds in PWRs (MIRP-169), Revision 1, EPRI, Palo Alto, CA and Structural Integrity Associates, Inc., San Jose, CA; June 2008, 1016602.
RR-A33 Page 17 of 18
- 9. G. Wilkowski, H. Xu, D. J. Shim, and D. Rudland, "Determination of the Elastic-Plastic Fracture Mechanics Z-factor for Alloy 82/182 Weld Metal Flaws for Use in the ASME Section XI Appendix C Flaw Evaluation Procedures," PVP2007-26733, Proceedings of ASME-PVP 2007: 2007 ASME Pressure Vessels and Piping Division Conference, San Antonio, TX, 2007.
- 10. NUREG/CR-4082, Volume 8, "Summary of Technical Results and Their Significance to Leak-Before-Break and In-Service Flaw Acceptance Criteria, March 1984-January 1989.
- 11. A.F.
Deardorff et al,
"Net Section Plastic Collapse Analysis of Two-Layered Materials and Application To Weld Overlay Design", ASME PVP 2006 Pressure Vessels and Piping Division Conference, Vancouver, Canada, July 2006,'
PVP2006-ICPVTI 1-93454.
- 12. W. Hilbner, B. Johansson, and M. de Pourbaix, Studies of the Tendency to Intergranular Stress Corrosion Cracking of Austenitic Fe-Cr-Ni Alloys in High Purity Water at'300°C, Studsvik report AE-437, Nykoping, Sweden, 1971.
- 13. W. Debray and L. Stieding, Materials in the Primary Circuit of Water-Cooled Power Reactors, International Nickel Power Conference, Lausanne, Switzerland, May 1972, Paper No. 3.
- 14. C. Amzallag, et al., "Stress Corrosion Life Assessment of 182 and 82 Welds used in PWR Components," Proceedings of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 2001.
- 15. NUREG/CR-6907, "Crack Growth Rates of Nickel Alloy Welds in a PWR Environment," U.S. Nuclear Regulatory Commission (Argonne National Laboratory), May 2006.
- 16. EPRI Material Reliability Program Report: Primary System Piping Butt Weld Inspection and Evaluation Guidelines (MRP-139), EPRI, Palo Alto, CA: August 2005. 1010087.
- 17. ASME Code Case N-638-1 "Similar and Dissimilar Metal Welding Using Ambient Temperature GTAW Temper Bead Technique"
- 18. ASME Code Case N-638-2 "Similar and Dissimilar Metal Welding Using Ambient Temperature GTAW Temper Bead Technique"
- 19. ASME Code Case N-638-3 "Similar and Dissimilar Metal Welding Using Ambient Temperature GTAW Temper Bead Technique"
- 20. ASME Code Case N-638-4 "Similar and Dissimilar Metal Welding Using.
AmbientTemperature GTAW Temper Bead Technique"
- 21. ASME Code Case N-504-2 "Alternative Rules for Repair if Classes 1, 2, and 3 Austenitic Stainless Steel Piping"
- 22. ASME Code Case N-504-3 "Alternative Rules for Repair if Classes1, 2, and 3 Austenitic Stainless Steel Piping"
RR-A33 Page 18 of 18
- 23. ASME Code Case N-770 "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities"
- 24. D. Buisine, et al., "PWSCC Resistance of Nickel Based Weld Metals with Various Chromium Contents," Proceedings: 1994 EPRI Workshop on PWSCC of Alloy 600 in PWRs, EPRI, Palo Alto, CA: 1995. TR-105406, Paper D5.
RR-A33, ATTACHMENT 1 Page 1 of 13 PROPOSED ALTERNATIVE FOR DAVIS-BESSE RPV NOZZLE AND REACTOR COOLANT PUMP DISSIMILAR METAL WELD OVERLAYS A
1.1 INTRODUCTION
FENOC proposes the following detailed requirements for the design, analysis, fabrication, examination, and pressure testing of the Davis-Besse reactor pressure vessel core flood and cold leg drain line nozzle dissimilar metal weld overlays and reactor coolant pump inlet and discharge dissimilar metal weld overlays. These requirements, which are derived from applicable portions of ASME Code Case N-740-2, provide an acceptable methodology for reducing potential defects in these austenitic nickel alloy welds to an acceptable size or mitigating the potential for future primary water stress corrosion cracking by increasing the wall thickness through deposition of weld overlays. The weld overlays shall be applied by deposition of weld reinforcement (weld overlay) on the outside surface of the piping, nozzles, and associated dissimilar metal welds, including ferritic materials when necessary, in accordance with the following requirements:
A1.2 GENERAL REQUIREMENTS A1.2.1 Definitions (a) full structural weld overlay, deposition of weld reinforcement on the outside diameter of the piping, component, or associated weld, such that the weld reinforcement is capable of supporting the design loads, without consideration of the piping, component, or associated weld beneath the weld reinforcement. Full structural weld overlay can be either mitigative or repair weld overlay as defined in A1.2.1(b) and (c).
(b) mitigative weld overlay, weld overlay that is applied over material with no inside-surface-connected flaws found during an examination performed in accordance with A1.3(a)(3), prior to the weld overlay being applied (c) repair weld overlay, weld overlay that is applied over material with an inside-surface-connected flaw or subsurface defect, or where a pre-weld overlay examination is not performed (d) SCC susceptible materials, for this proposed alternative, the stress-corrosion-cracking (SCC)
- susceptible materials are Unified Numbering System (UNS) N06600, N06082, or W86182 in pressurized water reactor environments; or UNS N06600, W86182, or austenitic stainless steels and.
associated welds in boiling water reactor environments.
A1.2.2 General Overlay Requirements (a) A full-structural weld overlay shall be applied by deposition of weld reinforcement (weld overlay) on the outside surface of circumferential welds. This proposed method applies to austenitic nickel alloy and austenitic stainless steel welds between the following:
P-No. 8 or P-No. 43 and P-Nos. 1, 3, 12A, 12B, or 12C P-No. 8 and P-No. 43 Between P-Nos. 1, 3, 12A, 12B, and 12C materials (b) If a weld overlay on any of the material. combinations in.A1.2.2(a) obstructs a required examination of an adjacent P-No. 8 to P-No. 8 weld, the overlay may be extended to include overlaying the adjacent weld.
RR-A33, Attachment I Page 2 of 13 (c) Weld overlay filler metal shall be austenitic nickel alloy (28 percent chromium minimum, ERNiCrFe-7/7A) meeting the requirements of 1.2(e)(1) or (2), as applicable, applied 360 degrees around the circumference of the item and deposited using a Welding Procedure Specification (WPS) for groove welding, qualified in accordance with the Construction Code and Owner's Requirements identified in the Repair/Replacement Plan. As an alternative to the post weld heat treatment (PWHT) requirements of the Construction Code and Owner's requirements, ambient-temperature temper bead welding in accordance with A2.1 shall be used.
(d) Prior to deposition of the weld overlay, the surface to be weld overlaid shall be examined using the liquid penetrant method. Indications with major dimensions greater than 1/16 inch (1.5 millimeters) shall be removed, reduced in size, or weld repaired in accordance with the following requirements:
(1) One or more layers of weld metal shall be applied to seal unacceptable indications in the area to be repaired with or without excavation. The thickness of these layers shall not be used in meeting weld reinforcement design thickness requirements. Peening the unacceptable indication prior to welding is permitted.
(2) If weld repair of indications identified in A1.2.2(d) is required, the area where the weld overlay is to be deposited, including any local weld repairs or initial weld overlay layer, shall be examined by the liquid penetrantmethod. The area shall contain no indications with major dimensions greater than 1/16 inch (1.5 millimeters) prior to application of the structural layers of the weld overlay.
(3) To reduce the potential of hot cracking when applying an austenitic nickel alloy over P-No. 8 base metal, it is permissible to apply a layer or multiple layers of austenitic stainless steel filler material over the austenitic stainless steel base metal. The stainless steel filler metal shall have a delta ferrite content of 5 - 15 Ferrite Number (FN), as reported on the Certified Material Test Report.
The thickness of these buffer layers shall not be used in meeting weld reinforcement design thickness requirements.
(e) Weld overlay deposits shall meet the following requirements:
(1) The austenitic stainless steel weld overlay shall consist of at least two weld layers having as-deposited delta ferrite content of at least 7.5 FN. The first layer of weld metal with delta ferrite content of at least 7.5 FN shall constitute the first layer of the weld reinforcement that may be credited toward the required thickness. Alternatively, layers of at least 5 FN are acceptable, provided the carbon content of the deposited weld metal is determined by chemical analysis to be less than 0.02 percent.
(2) The austenitic nickel alloy weld overlay shall consist of at least twbweld layers deposited using a filler material with a chromium (Cr) content of at least 28 percent. The first layer of weld metal deposited may not be credited toward the required thickness except that a first diluted layer may be credited toward the required thickness, provided the portion of the layer over the austenitic base material, austenitic filler material weld, and the associated dilution zone from an adjacent ferritic base material contain at least 24 percent Cr, and the Cr content of the deposited weld metal is determined by chemical analysis of the production weld or of a representative coupon taken from a mockup prepared in accordance with the weld procedure for the production weld.
(6) This case is only for welding in applications predicted not to have exceeded thermal neutron (E < 0.5 eV) fluence of I x 1017 neutrons per cm 2 prior to welding.
(g) A new weld overlay shall not be installed over the top of an existing weld overlay that has been in service.
RR-A33, Attachment I Page 3 of 13 A1.3 CRACK GROWTH AND DESIGN (a) Crack Growth Calculation ofFlaws in the Original Weld or Base Metal. The size of all flaws detected or postulated in the original weld or base metal shall be used to define the life of the overlay. The inspection interval shall not be longer than the shorter of the life of the overlay or the period specified in A 1.4(c). Crack growth due to both stress corrosion and fatigue, shall be evaluated. Flaw characterization and evaluation shall be based on the examination results or postulated flaw, as described below. If the flaw is at or near the boundary of two different materials, evaluation of flaw growth in both materials is required.
(1) For repair overlays, the initial flaw size for crack growth in the original weld or base metal shall be based on the as-found flaw or postulated flaw, if no pre-overlay examination is performed.
(2) For postulated flaws, the axial flaw length shall be 1.5 inches (38 millimeters) or the combined width of the weld plus buttering plus any adjacent SCC susceptible material, whichever is greater.
The circumferential flaw length shall be assumed to be 360 degrees. The depths associated with these lengths are specified in A1.3(a)(3) and Al.3(a)(4).
(3) If an Appendix VIII, Supplement 10, or Supplement 2, as applicable, ultrasonic examination is performed prior to application of the overlay, and no inside-surface-connected planar flaws are discovered, initial flaws originated from the inside surface of the weldment equal to 10 percent of the original wall thickness shall be assumed in both the axial and circumferential directions, and the overlay shall be considered mitigative.
(4) If an Appendix VIII, Supplement 10, or Supplement 2, as applicable, ultrasonic examination is not performed prior to application of the overlay, initial inside-surface-connected planar flaws equal to at least 75 percent through the original wall thickness shall be assumed, in both the axial and circumferential directions, and the overlay shall be considered a repair. For cast austenitic stainless steel (CASS) items, a 100 percent through-wall flaw shall be assumed unless the subsequent inservice inspection schedule is modified as discussed in A1.4(c)(4).
(5) There may be circumstances in which an overlay examination is performed using an ultrasonic examination procedure qualified in accordance with Appendix VIII, Supplement 11 for depths greater than the outer 25 percent of the original wall thickness (Fig. A 1-2). For such cases, the initial flaw depths are assumed to be the detected depth found by the Appendix VIII, Supplement 11 qualified examination, plus the postulated worst-case flaw in the region not covered by the Appendix VIII ultrasonic examination.
(6) In determining the life of the overlay, any inside-surface-connected planar flaw found by the overlay preservice inspection of A 1.4(b) that exceeds the depth of (3), (4), or (5) above shall be used as part of the initial flaw depth. The initial flaw depth assumed is the detected flaw depth plus the postulated worst-case flaw depth in the region of the pipe wall thickness that was not examined using an ultrasonic examination procedure meeting Appendix VIII for that region. An overlay meeting this condition shall be considered a repair, rather than mitigation.
(b) StructuralDesign and Sizing of the Overlay. The design of the weld oerlay shall satisfy the following, using the assumptions and flaw characterization requirements in A 1.3(a). The following design analysis shall be completed in accordance with IWA-43 11:
(1) The axial length and end slope of the weld overlay shall cover the weld and heat-affected zones on each side of the weld, as well as any stress corrosion cracking susceptible base material adjacent to the weld, and provide for load redistribution from the item into the weld overlay and back into the item without violating applicable stress limits of NB-3200. Any laminar flaws in the weld overlay shall be evaluated in the analysis to ensure that load redistribution complies with the above.
RR-A33, Attachment 1 Page 4 of 13 These requirements are usually satisfied if the weld overlay full thickness length extends axially beyond the SCC-susceptible material or projected flaw by at least 0.75, R1, where R is the outer radius of the item and t is the nominal wall thickness of the item at the applicable side of the overlay (that is, R and t of the nozzle on the nozzle side and R and t of the safe-end on the safe-end side).
(2) Unless specifically analyzed in accordance with A1.3(b)(1), the end transition slope of the overlay shall not exceed 30 degrees.
(3) The assumed flaw in the underlying base material or weld shall be based on the limiting case of A1.3(b)(3)(a) and (b) that results in the larger required overlay thickness.
(a) 100 percent through-wall circumferential flaw for the entire 'circumference (b) 100 percentthrough-wall flaw with length of 1.5 inches (38 millimeters), or the combined width of the weld plus buttering plus any SCC-susceptible material, whichever is greater, in the axial direction (4) The overlay design thickness shall be verified, using only the weld overlay thickness conforming to the deposit analysis requirements of A1.2.2(e). The combined wall thickness at the weld overlay, any postulated worst-case planar flaws under the laminar flaws in the weld overlay, and the effects of any discontinuity (for example, another weld overlay or reinforcement for a branch connection) within a distance of 2.5, Rt, from the toes of the weld overlay, including the flaw size assumptions defined in A1.3(b)(3) above, shall be evaluated and shall meet the requirements of IWB-3640, IWC-3640, or IWD-3640, as applicable.
(5) The effects of any changes in applied loads, as a result of weld shrinkage from the entire overlay, on other items in the piping system (for example, support loads and clearances, nozzle loads, and changes in system flexibility and weight due to the weld overlay) shall be evaluated. Existing flaws previously accepted by analytical evaluation shall be evaluated in accordance with IWB-3640, IWC-3640, or IWD-3640, as applicable.
A1.4 EXAMINATION In lieu of all other examination requirements, the examination requirements of this proposed method shall be met for the life of the overlay. Nondestructive examination methods shall be iný accordance with IWA-2200, except as specified herein. Nondestructive examination personnel shall be qualified in accordance with IWA-2300. Ultrasonic examination procedures and personnel shall be qualified in accordance with the modified requirements to ASME Code Section XI, Appendix VIII, Supplement 11 as described in . The examination shall be performed to the maximum extent practicable, for axial and circumferential flaws. If 100 percent coverage of the required volume for axial flaws cannot be achieved, but essentially 100 percent coverage for circumferential flaws (100 percent of the susceptible volume) can be achieved, the examination for axial flaws shall be performed to achieve the maximum coverage practicable, with limitations noted in the examination report. The examination coverage requirements shall be considered to be met. For welds containing cast stainless steel materials the examination volume includes only the susceptible material (non-stainless steel) volume.
(a) Acceptance Examination (1) The weld overlay shall have a surface finish of 250 micro-inches (jin), 6.3 micrometer (gm) roughness measurement system (RMS) or better and contour that permits ultrasonic examination in accordance with procedures qualified in accordance with ASME Code Section XI, Appendix VIII.
The weld overlay shall be inspected to verify acceptable configuration.
JRR-A33, Attachment I Page 5 of 13 (2) The weld overlay and the adjacent base material for at least 1/2 inch (13 millimeters) from each side of the overlay shall be examined using the liquid penetrant method. The weld overlay shall satisfy the surface examination acceptance criteria for welds of the Construction Code or NB-5300.
The adjacent base material shall satisfy the surface examination acceptance criteria for base material of the Construction Code or NB-2500. If ambient temperature temper bead welding is performed, the liquid penetrant examination of the completed weld overlay shall be conducted no sooner than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following completion of the three tempering layers over the ferritic steel.
(3) The examination volume A-B-C-D in Figure Al-l(a) shall be ultrasonically examined to assure adequate fusion (that is, adequate bond) with the base material and to detect welding flaws, such as interbead lack of fusion, inclusions, or cracks. The interface C-D shown between the overlay and weld includes the bond and heat- affected zone from the overlay. If ambient temperature temper bead welding is performed, the ultrasonic examination shall be conducted no sooner than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following completion of the three tempering layers over the ferritic steel. Planar flaws detected in the weld overlay acceptance examination shall meet the preservice examination standards of IWB-3514.
In applying the acceptance standards to planar indications, the thickness, t1 or t 2 defined in Figure Al-1 (b) shall be used as the nominal wall thickness in IWB-3514, provided the base material beneath the flaw (that is, safe end, nozzle, or piping material) is not susceptible to stress corrosion cracking. For susceptible material, t, shall be used. If a flaw in the overlay crosses the boundary between the two regions, the more conservative of the two dimensions (t, or t2) shall be used. Laminar flaws in the weld overlay shall meet the following requirements:
(a) The acceptance standards of IWB-3514 shall be met, with the additional limitation that the total laminar flaw area shall not exceed 10 percent of the weld surface area and that no linear dimension of the laminar flaw area shall exceed the greater of 3 inches (76 millimeters) or 10 percent of the pipe circumference.
(b) For examination volume A-B-C-D in Figure A1-1(a), the reduction in coverage due to laminar flaws shall be less than 10 percent. The uninspectable volume is the volume in the weld overlay underneath the laminar flaws for which coverage cannot be achieved with the angle beam examination method.
(c) Any uninspectable volume in the weld overlay shall be assumed to contain the largest radial planar flaw that could exist within that volume. This assumed flaw shall meet the preservice examination acceptance standards of IWB-3514, with nominal wall thickness as defined above the planar flaws. Alternatively, the assumed flaw shall be evaluated and meet the requirements of IWB-3640, IWC-3640, and IWD-3640, as applicable. Both axial and circumferential planar flaws shall be assumed.
(4) After completion of all welding activities, VT-3 visual examination shall be performed on all affected restraints, supports, and snubbers, to verify that design tolerances are met.
RR-A33, Attachment 1 Page 6 of 13 End Transition Slope (niotto exceed 30-degrees. unless anatyzed)
A B 0C (a) Examination Volume A-B-C-D A E.. [........ B D G C t2 (b) Thickness (t, and t-) for Table 1WB-3514-2 Notes:
1 Dimension b is equivalent to the nominal thickness of the nozzle or pipe being overlaid, as appropriate.
2 The nominal wall thickness is tj for flaws in E-F-G-H, and t2 for flaws in A-E-H-D or F-B-C-G.
3 For flaws that span two examination volumes (such as illustrated at F-G), the t1 thickness shall be used.
4 The weld includes the nozzle or safe end butter, where applied, plus any stress corrosion cracking susceptible base material in the nozzle.
Figure Al-i Examination Volume and Thickness Definitions
RR-A33, Attachment I Page 7 of 13 (b) PreserviceInspection (1) The examination volume in Fig. A1-2 shall be ultrasonically examined. The angle beam shall be directed perpendicular and parallel to the piping axis, with scanning performed in four directions, to locate and size any planar flaw that have propagated into the outer 25 percent of the base metal thickness or into the weld overlay. For weld overlays on cast austenitic stainless steel base materials, if a 100 percent through-wall flaw is used for crack growth, only planar flaws that have propagated into the weld overlay, or are in the overlay, are required to be located and sized.
(2) The preservice examination acceptance standards of IWB-3514 shall be met for the weld overlay.
In applying the acceptance standards to planar indications, the thickness, tl or t2, defined in Fig. Al-1(b) shall be used as the nominal wall thickness in IWB-3514, provided the base material beneath the flaw (that is, safe end, nozzle, or piping material) is not susceptible to SCC. For susceptible material, tl shall be used. Planar flaws in the outer 25 percent of the base metal thickness shall meet the design analysis requirements of A1.3(b).
(3) The flaw evaluation requirements of IWB-3640, IWC-3640, or IWD-3640 shall not be applied to planar flaws, identified during preservice examination, that exceed the preservice examination acceptance standards of IWB-3514.
Minimum 1/2 in. (13 mm) Minimum 1/2 ini.(13 mm) (Note l),
As-foundFw Examination Volume A-B-C-D Notes:
I The weld includes the nozzle or safe end butter, where applied.
2 For axial or circumferential flaws, the axial extent of the examination volume shall extend at least 1/22 inch (13 millimeters) beyond the as-found flaw and at least 1/22 inch (13 millimeters) beyond the toes of the original weld, including weld end butter, where applied.
Figure AI-2 Preservice and Inservice Examination Volume
RR-A33, Attachment 1 Page 8 of 13 (c) Inservice Inspection (1) For welds whose pre-overlay examination did not reveal any inside surface connected planer flaws, the welds shall be placed into a population of full structural weld overlays to be examined on a sample basis. Twenty-five (25) percent of this population shall be added to the ISI Program and shall be examined once each inspection interval. If multiple welds are mitigated in the same inspection period, examinations shall be spread throughout years 3 through 10 following application, similar to provisions in IWB-2412(b). The 25 percent sample shall consist of the same welds in the same sequence during successive intervals to the extent practical provided the 25 percent sample contains welds that experience the hottest operating temperature in the population. If hot leg and cold leg welds are included in the population, the 25 percent sample does not need to include the cold leg welds. All weld overlays, including those not in the 25 percent sample, shall be examined prior to the end of their design life as determined in A 1.3(a).
(2) For welds whose pre-overlay examination revealed inside surface connected planar flaws, or for which a pre-overlay examination was not performed, the weld overlay shall be ultrasonically examined during the first or second refueling outage following application. Examination volumes that show no indication of crack growth or new cracking shall then be placed into a population of full structural weld overlays to be examined on a sample basis. Twenty-five (25) percent of this population shall be added to the ISI Program in accordance with IWB-2412(b). The 25 percent sample shall consist of the same welds in the same sequence during successive intervals to the extent practical provided the 25 percent sample contains welds that experience the hottest operating temperature in the population. If hot leg and cold leg welds are included in the population, the 25 percent sample does not need to include the cold leg welds. All weld overlays, including those not in the 25 percent sample, shall be examined prior to the end of their design life as determined in A1.3(a).
(3) The weld overlay examination volume in Fig. AI-2 shall be ultrasonically examined to determine if any new or existing planar flaws have propagated into the outer 25 percent of the base material thickness or into the overlay. The angle beam shall be directed perpendicular and parallel to the piping axis, with scanning performed in four directions.
(4) For cast stainless steel items, the required examination volume shall be examined to the maximum extent practical including 100 percent of the susceptible material volume (non-stainless steel volume). If 100 percent of the susceptible material volume is examined both before and after mitigation, and no inside surface connected planar flaws are detected, the inspection frequency of (2) above for uncracked items is applicable. If 100 percent of the susceptible material is not examined in the pre and post mitigation volume examinations, the inspection frequency of (3) above for cracked items shall be applied with the following exceptions:
(a) The inspection of the mitigated weld shall not be credited to satisfy the requirement of the 25 percent inspection sample every inspection interval. The mitigated weld shall be inspected each inspection interval.
(b) If the required examination volume, including 100 percent of the susceptible material volume, is subsequently examined using a qualified ultrasonic examination and no planar flaws are detected, the weld may be placed in the 25 percent inspection sample population as noted in (3) above.
(5) The weld overlay shall meet the inservice examination acceptance standards of IWB-3514. In applying the acceptance standards to planar indications, the thickness, t1 or t2, defined in Fig. A 1-1 (b)
RR-A33, Attachment 1 Page 9 of 13 shall be used as the nominal wall thickness in IWB-3514, provided the base material beneath the flaw (that is, safe end, nozzle, or piping material) is not susceptible to SCC. For susceptible material, t1 shall be used. If the acceptance standards of IWB-3514 cannot be met, the weld overlay shall meet the acceptance standards of IWB-3600, IWC-3600, or IWD-3600, as applicable. If a planar flaw is detected in the outer 25 percent of the base material thickness shall meet the design analysis requirements of A 1.3. Any indication characterized as stress corrosion cracking in the weld overlay material is unacceptable.
(6) If inservice examinations reveal planar flaw growth, or new planar flaws, meeting the acceptance standards of IWB-3514, IWB-3600, IWC-3600, or IWB-3600, the weld overlay examination volume shall be reexamined during the first or second refueling outage following discovery of the growth or new flaws.
(7) For weld overlay examination volumes with unacceptable indications in accordance with Al.4(c)(5), the weld overlay and original defective Weld shall be removed. A repair/replacement activity shall be performed in accordance with IWA-4000.
(d) Additional Examinations.If inservice examinations reveal a defect, in accordance with A 1.4(c)(4),
planar flaw growth into the weld overlay design thickness, or axial flaw growth beyond the specified examination volume, additional weld overlay examination volumes, equal to the number scheduled for the current inspection period, shall be examined prior to return to service. If additional defects are found in the second sample, 50 percent of the total population of weld overlay examination volumes shall be examined prior to return to service. If additional defects are found, the entire remaining population of weld overlay examination volumes shall be examined prior to return to service.
A1.5 PRESSURE TESTING A system leakage test shall be performed in accordance with IWA-5000.
A1.6 DOCUMENTATION Use of this proposed method shall be documented on Form NIS-2.
RR-A33, Attachment I Page 10 of 13 A2.1 AMBIENT-TEMPERATURE TEMPER BEAD WELDING A2.2 GENERAL REQUIREMENTS (a) This Attachment applies to dissimilar austenitic filler metal welds between P-Nos. 1, 3, 12A, 12B, and 12C materials and their associated welds and welds joining P- No. 8 or 43 materials to P-Nos.
1, 3, 12A, 12B, and 12C materials with the following limitation. This Attachment shall not be used to repair SA-302 Grade B material unless the material has been modified to include from 0.4 percent to 1.0 percent nickel, quenching, tempering, and application of a fine grain practice.
(b) The maximum area of an individual weld overlay based on the finished surface over the ferritic base material shall be greater than 600 square inches (390, 000 square millimeters), but less than 700 square inches (455,000 square millimeters).
(c) Repair/replacement activities on a dissimilar-metal weld in accordance with this Attachment are limited to those along the fusion line of a nonferritic weld to ferritic base material on which i1/8 inch (3 millimeters) or less of nonferritic weld deposit exists above the original fusion line.
(d) If a defect penetrates into the ferritic base material, repair of the base material, using anonferritic weld filler material, may be performed in accordance with this Attachment, provided the depth of repair in the base material does not exceed %inch (10 millimeters).
(e) Prior to welding, the area to be welded and a band around the area of at least 11 2 times the component thickness or 5 inches (130 millimeters), whichever is less, shall be at least 50 degrees Fahrenheit (10 degrees Celsius).
69 Welding materials shall meet the Owner's Requirements and the Construction Code and Cases specified in the Repair/Replacement Plan. Welding materials shall be controlled so that they are identified as acceptable until consumed.
(g) Peening may be used, except on the initial and final layers.
A2.3 WELDING QUALIFICATIONS The welding procedures and operators shall be qualified in accordance with ASME Code Section IX and the requirements of A2.3.1 and A2.3.2.
A2.3.1 Procedure Qualification (a) The base materials for the welding procedure qualification shall be of the same P-Number and Group Number as the materials to be welded. The materials shall be postweld heat treated to at least the time and temperature that was applied to the materials being welded.
(b) The maximum interpass temperature for the first three layers of the test assembly shall be 150 degrees Fahrenheit (66 degrees Celsius).
(c) Theweld overlay shall be qualified using groove weld coupon. The test assembly groove depth shall be at least 1 inch (25 millimeters). The test assembly thickness shall be at least twice the test
RR-A33, Attachment 1 Page 11 of 13 assembly groove depth. The test assembly shall be large enough to permit'removal of the required test specimens. The test assembly dimensions on either side of the groove shall be at least 6 inches (150 millimeters). The qualification test plate shallbe prepared in accordance with Figure A2-1.
(d) F erritic base material for the procedure qualification test shall meet the impact test'requirements of the Construction Code and Owner's Requirements. If such requirements are not in the Construction Code and Owner's Requirements, the impact properties shall be determined by Charpy V-notch impact tests of the procedure qualification base material at or below the lowest service temperature of the item to be repaired. The location and orientation of the test specimens shall be similar to those required in A2.3.1 (e) but shall be in the base metal.
(e) Charpy V-notch tests of the ferritic heat-affected zone (HAZ) shall be performed at the same temperature as the base metal test of A2.3.1 (d). Number, location, and orientation of test specimens shall be as follows:
(1) The specimens shall be removed from a location as near as practical to a depth of one-half the thickness of the deposited weld metal. The coupons for HAZ impact specimens shall be taken transverse to the axis of the weld and etched to define the HAZ. The notch of the Charpy V-notch specimen shall be cut approximately normal to the material surface in such a manner as to include as much HAZ as possible in the resulting fracture.
(2) If the material thickness permits, the axis of a specimen shall be inclined to allow the root of the notch to be aligned parallel to the fusion line.
(3) If the test material is in the form of a plate or forging, the axis of the weld shall be oriented parallel to the principal direction of rolling or forging.
(4) The Charpy V-notch test shall be performed in accordance with SA-370. Specimens shall be in accordance with SA-370, Figure il, Type A. The test shall consist of a set of three ftill-size 10 millimeters by 10 millimeters specimens. The lateral expansion, percent shear, absorbed energy, test temperature, orientation, and location of all test specimens shall be reported in the Procedure Qualification .Record.
(/ The average lateral expansion value of the three HAZ Charpy V-notch specimens shall be equal to or greater than the average lateral expansion value of the three. unaffected base metal specimens.
However, if the average lateral expansion value of the HAZ Charpy V-notch specimens is less than the average value for the unaffected base metal specimens, and the procedure qualification meets all, other requirements of this Attachment, either of the following shall be performed:
(1) The welding procedure shall be requalified.
(2) An Adjustment Temperature for the procedure qualification shall be determined in accordance with the applicable provisions of Paragraph NB-4335.2 of Section III, 2001 Edition with the 2002 Addenda of the ASME Code. The reference nil-ductility temperature (RTNTT) or lowest service temperature of the materials for which the welding procedure will be used shall be increased by a temperature equivalent to that of the Adjustment Temperature.
A2.3.2 Performance Qualification Welding operators shall be qualified in accordance with ASME Code Section IX.
RR-A33, Attachment 1 Page 12 of 13 A2.4 WELDING PROCEDURE REQUIREMENTS The welding procedure shall include the following requirements:
(a) The weld metal shall be deposited by the automatic or machine gas tungsten arc welding process.
(b) Dissimilar metal welds shall be made using A-No. 8 weld metal (QW-442) for P-No. 8 to P-No. 1, 3, or 12 (A, B, or C) weld joints or F-No. 43 weld metal (QW-432) for P-No. 8 or 43 to P-No. 1, 3, or 12 (A, B, or C) weld joints.
(c) The area to be welded shall be buttered with a deposit of at least three layers to achieve at least 1/8 inch (3 millimeters) overlay thickness with the heat input for each layer controlled to within +/- 10 percent of that used in the procedure qualification test. The heat input of the first three layers shall not exceed 45 kilojoule [kJ]/inch or 1.8 kJ/millimeter under any conditions. Particular care shall be taken in the placement of the weld layers of the austenitic overlay filler material at the toe of the overlay to ensure that the heat affected zone and ferritic base metal are tempered. Subsequent layers shall be deposited with a heat input not exceeding that used for layers beyond the third layer in the procedure qualification.
(d) The maximum interpass temperature for field applications shall be 350 degrees Fahrenheit (180 degrees Celsius) for all weld layers regardless of the interpass temperature used during qualification. The interpass temperature limitation of QW-406.3 need not be applied.
(e) The interpass temperature shall be determined as follows:
(1) temperature measurement (for example, pyrometers, temperature-indicating crayons, and thermocouples) during welding. If direct measurement is impractical, interpass temperature shall be determined in accordance with A2.4(e)(2) or (3).
(2) heat-flow calculations, using at least the variables listed below (a) welding heat input (b) initial base material temperature (c) configuration, thickness, and mass of the item being welded (d) thermal conductivity and diffusivity of the materials being welded (e) arc time per weld pass and delay time between each pass 09 arc time to complete the weld (3) measurement of the maximum interpass temperature on a test coupon that is no thicker than the item to be welded. The maximum heat input of the welding procedure shall be used in welding the test coupon.
- 64) Particular care shall be given to ensure that the weld region is free of all potential sources of hydrogen. The surfaces to be welded, filler metals, and shielding gas shall be suitably controlled.
RR-A33, Attachment 1 Page 13 of 13 Note:
Base metal Charpy impact specimens are not shown. This figure illustrates a similar-metal weld.
Figure A2-1 Qualification Test Plate
RR-A33, ATTACHMENT 2 Page 1 of 7 PROPOSED CHANGES TO ASME CODE SECTION XI APPENDIX VIII FOR COMPATIBILITY WITH THE PERFORMANCE DEMONSTRATION INITIATIVE PROGRAM SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL The Proposed Alternative to Supplement 11 STRUCTURAL OVERLAID WROUGHT AUSTENITIC PIPING WELDS Requirements Title Alternative: "Qualification Requirements for Overlaid Wrought Austenitic Piping Welds:
Basis: The title was clarified to be applicablefor all overlays on wrought austeniticpiping welds. The specific qualificationshall detail the range of qualification.,
10 SPECIMEN REQUIREMENTS 1.1 General. The specimen set shall conform to the following requirements.
(b) The specimen set shall consist of at least three specimens having different nominal pipe diameters and overlay thicknesses. They shall include the minimum and maximum nominal pipe Alternative: (b) The specimen set shall include diameters for which the examination procedure is specimens with overlays not thicker than 0.1 inch applicable. Pipe diameters within a range of 0.9 to more than the minimum thickness, nor thinner than 1.5 times a nominal diameter shall be considered 0.25 inch of the maximum nominal overlay equivalent. If the procedure is applicable to pipe thickness for which the examination procedure is diameters of 24-inch or larger, the specimen set applicable.
must include at least one specimen 24-inch or Basis: To avoid confusion, the overlay thickness larger but need not include the maximum tolerance contained in the last sentence was diameter. The specimen set must include at least reworded and the phrase "and the remaindershall one specimen with overlay thickness within minus be alternativeflaws" was added to the next to last 0.1 inch to plus 0.25 inch of the maximum sentence in paragraph1.1 (d)(1).
nominal overlay thickness for which the procedure is applicable.
(d) Flaw Conditions Alternative: (1) ... must be in or... extending at least 50 percent through... intentional overlay be cracks in fabrication flaws shall not interfere with ultrasonic farctoflwshlntiteeewthursnc (1) Basthemetal (1) Base flaws. All metalproflmaws Alltflaw must flaws must-ferckd idetection or characterization of the base metal flaws.
or near the approximate butt weld heat-affected Spcmncotingneraulrsescroin zone, open to the inside surface, and extending at Specimens containing intergranular stress corrosion least 75 percent through the base metal wall. cracking shall be used when available. At least 70 Flaws may extend 100 percent through the base percent of the flaws in the detection and sizing tests metal and into the overlay material; in this case, shall be cracks alternative andAlternative flaws. the remainder flawshall be mechanisms, if intentional overlay fabrication flaws shall, not interfere with ultrasonic detection or used, shall provide crack-like reflective characteristics and shall be limited by the following:
characterization of the cracking. Specimens (a) The use of alternative flaws shall be limited to containing IGSCC shall be used when available, when the implantation of cracks produces spurious reflectors that are uncharacteristic of actual flaws.
(b) Flaws shall be semi elliptical with a tip width. of
RR-A33, Attachment 2 Page 2 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL The Proposed Alternative to Supplement 11 STRUCTURAL OVERLAID WROUGHT Requirements AUSTENITIC PIPING WELDS Jless than or equal to 0.002 inches.
Basis: This paragraphrequires that all base metal flaws be cracks and to extend at least 75 percent through the base metal wall. Implanting a~crack requires excavation of the base materialon at least one side ofthe flaw. While this may be satisfactory forferriticmaterials,it does not produce a useable axialflaw in austenitic materials because the sound beam, which normally passes only through base material,must now travel through weld material on at least one side, producing an unrealisticflaw response. To resolve this issue, the PDIprogram revised this paragraphto allow use of alternative flaw mechanisms under controlled conditions. For example, alternativeflaws shall be limited to when implantation ofcracks precludes obtaining an effective ultrasonicresponse,flaws shall be semi ellipticalwith a tip width of less than or equal to 0.002 inches, and at least 70 percent of the flaws in the detection and sizing test shall be cracks and the remaindershall be alternativeflaws. To avoid confusion, the overlay thickness tolerance contained in paragraph1.1 (b) last sentence, was reworded and the phrase "and the remainder shall be alternativeflaws" was added to the next to last sentence. Paragraph1. 1 (d)(1) includes the statement that intentional overlayfabricationflaws shall not interfere with ultrasonicdetection or characterizationof the base metalflaws.
Additionally, 1.1 (d)(1) was revised to state that flaws must extend at least 50 percent through the base metal wall. This allows qualificationto take advantage of additionaltest specimens to demonstrate increasedexamination depth.
(e) Detection Specimens Alternative: (1) At least 20 percent but less than 40 percent of the base metal flaws shall be oriented (1) At least 20 percent but less than 40 percent of within +/-20 degrees of the pipe axial direction. The the flaws shall be oriented within +/-20' of the remainder shall be oriented circumferentially. Flaws pipe axial direction. The remainder shall be shall not be open to any surface to which the oriented circumferentially. Flaws shall not be candidate has physical or visual access.
open to any surface to which the candidate has Basis: The requirementfor axially oriented overlay physical or visual access. The rules of IWA-3300 fabricationflaws was excluded from the PDI shall be used to determine whether closely spaced Programas an improbable scenario. Weld overlays flaws should be treated as single or multiple are typically applied using automatedgas tungsten flaws. arc welding techniques with the filler metal applied in a circumferentialdirection. Because resultant fabrication induceddiscontinuities would also be expected to have malor dimensions oriented in the
RR-A33, Attachment 2 Page 3 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL STRUCTURAL OVERLAID WROUGHT The Proposed Alternative to Supplement 11 AUSTENITIC PIPING WELDS Requirements circumferentialdirectionaxial overlay fabrication flaws are unrealistic. The requirementfor using JWA-3300 for proximityflaw evaluation was excluded; instead indicationsshall be sized based on their individual merits.
Alternative: (2) Specimens shall be divided into base metal and overlay fabrication grading units.
Each specimen shall contain one or both types of (2) Specimens shall be divided into base and grading units. Flaws shall not interfere with ultrasonic detection or characterization of other overlay grading units. Each specimen shall flaws.
contain one or both types of grading units. Basis: Inclusion of "metal" and 'fabrication" provides.cl2rification. Flaw identification is improved by ensuringflaws are not masked by other flaws.
Alternative: (a)(1) A base metal grading unit includes the overlay material and the outer 50 percent of the original overlaid weld. The base metal grading unit shall extend circumferentially for at least 1 inch and shall start at the weld centerline and be wide enough in the axial direction to encompass (a)(1) A base grading unit shall include at least 3 one half of the original weld crown and a minimum inch of the length of the overlaid weld. The base of 0.50" of the adjacent base material.
grading unit includes the outer 25 percent of the Basis: The phrase "andbase metal on both sides,"
overlaid weld and base metal on both sides. The was inadvertently included in the description of a base grading Unit shall not include the inner 75 base metal grading unit, The PDIprogram percent of the overlaid weld and base metal intentionally excludes this requirement because overlay material, or base metal-to-overlay some ofthe qualificationsamples includeflaws on interface. both sides of the weld. To avoid confusion several instances of the term "cracks" or "cracking" were changed to the term 'flaws" because of the use of alternativeFlaw mechanisms. Modfied to require that a base metal gradingunit include at least] inch of the length of the overlaid weld, ratherthan 3 inches.
Alternative: (a)(2) When base metal flaws penetrate (a)(2) When base metal cracking penetrates into into the overlay material, the base metal grading unit the overlay material, the base grading unit shall shall not be used as part of any overlay fabrication include the overlay metal within 1 inch of the grading unit.
crack location. This portion of the overlay Basis: Substituted terms provide clarificationand material shall not be used as part of any overlay are consistentwith ld(1) above. The PDIprogram grading unit. adjusts for this conservative change for excluding this type gradingunit.
(a)(3) When a base grading unit is designed to be Alternative: (a)(3) Sufficient unflawed overlaid unflawed, at least 1 inch of unflawed overlaid weld and base metal shall exist on all sides of the
RR-A33, Attachment 2 Page 4 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL The Proposed Alternative to Supplement 11 STRUCTURAL OVERLAID WROUGHT Requirements AUSTENITIC PIPING WELDS weld and base metal shall exist on either side of *grading unit to preclude interfering reflections from the base grading unit. The segment of weld length adjacent flaws.
used in one base grading unit shall. not be used in Basis: Modified to requiresufficient unflawed another base grading unit. Base grading units need overlaidweld and base metal to exist on all sides of not be uniformly spaced around the specimen. the grading unit to preclude interferingreflections from adjacentflaws, ratherthan the ] inch requirement.
Alternative: (b)(l) An overlay fabrication grading unit shall include the overlay'materialand the base metal-to-overlay interface for a length of at least I inch (b)(1) An overlay grading unit shall include the Basis: The PDIprogram reduces the base metal-to-overlay material and the base metal-to-overlay overlay interface to at least 1 inch (in lieu of a interface of at least 6 inm2-.
The overlay grading minimum of 2 inches) and eliminates the minimum unit shall be rectangular, w ith minimum rectangulardimension. This criterion is necessary dimensions of 2 inches. to allow use of existing examination specimens that were fabricated in order to meet NRC Generic Letter 88-01. This criterionmay be more challenging than the ASME Code because of the K variability associatedwith the shape of the grading unit.
Alternative: (b)(2) Overlay fabrication grading units designed to be unflawed shall be separated by unflawed overlay material and unflawed base metal-to-overlay interface for at least 1 inch at both ends.
Sufficient unflawed overlaid weld and base metal (b)(2) An overlay grading unit designed to be shall, exist on both sides of the overlay fabrication unflawed shall be surrounded by unflawed overlay grading unit to preclude interfering reflections from material and unflawed base metal-to-overlay adjacent flaws. The specific area used in one interface for at least 1 inch around its entire overlay fabrication grading unit shall not be used in perimeter. The specific area used in one overlay another overlay fabrication grading unit. Overlay grading unit shall not be used in another overlay fabrication grading units need not be spaced grading unit. Overlay grading units need not be uniformly about the specimen.
spaced uniformly about the specimen. Basis: Paragraph1.1 (e)(2)(b)(2) states that overlay fabricationgrading units designed to be unflawed shall be separatedby unflawed overlay material and unflawed base metal-to-overlay interfacefor at least 1 inch at both ends, rather than aroundits entire perimeter.
(b)(3) Detection sets shall be selected from Table Alternative:...base metal grading units, ten VIII-S2-1. The minimum detection sample set is unflawed base metal grading units, five flawed five flawed base grading units, ten unflawed base overlay fabrication grading units, and ten unflawed grading units, five flawed overlay grading units, overlay fabrication grading units. For each type of and ten unflawed overlay grading units. For each grading unit, the set shall contain at least twice as type of grading unit, the set shall contain at least many unflawed as flawed grading units. For initial twice as many unflawed as flawed grading units. procedure qualification, detection sets shall include
RR-A33, Attachment 2 Page 5 of 7 SUPPLEMENT 11 - QUALIFICATION IPDI PROGRAM:
REQUIREMENTS FOR FULL The Proposed Alternative to Supplement 11 STRUCTURAL OVERLAID WROUGHT Requirements AUSTENITIC PIPING WELDS the equivalent of three- personnel qualification sets.
To qualify new values of essential variables, at least one personnel qualification set is required.
Basis: Clarified the guidancefor initialprocedure qualifications versus qualifing new values of essential variables.
(f) Sizing Specimen Alternative: (1) The ...least 40 percent of the flaws shall be open to the inside surface. Sizing sets shall contain a distribution of flaw dimensions to assess (1) henmberof inimm lawsshal beten Atsizing capabilities. For initial procedure l1Teas 30npercent me ofth flaws shall overlAy be qualification, sizing sets shall include the equivalent fbiainfasAtleast percent 40 ofsalb the flawsvra of three personnel qualification sets. To qualify new fabrcaton Atleatlaws40perentof te faws values of essential variables, at least one personnel shall be cracks open to the inside surface. qualification set is required.
Basis: Clarified the guidancefor initialprocedure qualifications versus qualifying new values of essential variables and is consistent with 1.1(d) (1) above..
Alternative: (3) Base metal flaws (3) Base metal cracking used for length sizing used... .circumferentially.
demonstrations shall be oriented Basis: Clarified wording to be consistent with circumferentially. 1.1(d)(1) above.
(4) ept sizng etsshal inlud at pecmen Alternative: (4) Depth sizing specimen sets shall todsizingt specaimenses sheecallinincldath (4lepsth include at least two distinct locations where a base base metal extends into the overlay material by at mtlfa xed noteoelymtra ya least 0.1 inch in the through-wall direction. least 0.1 inch in the through-wall direction.
Basis: Clarifiedwording to be consistent with 1.1(d)(1) above.
2.0 Conduct of Performance Demonstration The specimen inside surface and identification*
shall be concealed from the candidate. All examinations shall be completed prior to grading Alternative: The specimen ... .prohibited. The the results and presenting the results to the overlay fabrication flaw test and the base metal flaw candidate. Divulgence of particular specimen test may be performed separately.
results or candidate viewing of unmasked Basis: Clarifiedwording to describeprocess.
specimens after the performance demonstration is prohibited.
2.1 Detection Test.
Flawed and unflawed grading units shall be randomly mixed. Although the boundaries of Alternative: Flawed ... (base metal or overlay specific grading units shall not be revealed to the fabrication)... .each specimen.
candidate, the candidate shall be made aware of Basis: Clarifiedwording similar to 1. 1(e)(2) above.
the type or types of grading units (base or overlay) that are present for each specimen.
2.2 Length Sizing Test (d) For flaws in base grading units, the candidate Alternative: (d) For .. , base metal grading ... 50 shall estimate the length of that part of the flaw percent of the base metal wall thickness.
RR-A33, Attachment 2 Page 6 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL The Proposed Alternative to Supplement 11 STRUCTURAL OVERLAID WROUGHT Requirements AUSTENITIC PIPING WELDS that is in the outer 25 percent of the base wall Basis: Clarifiedwordingfor consistency and to be thickness. consistent with 1.1 (d)(1) above.
2.3 Depth Sizing Test.
Alternative: (a) The depth sizing test may be conducted separately or in conjunction with the detection test.
(b) When the depth sizing test is conducted in conjunction with the detection test and the detected For the depth sizing test, 80 percent of the flaws flaws do not satisfy the requirements of 1.1(f),
shall be sized at a specific location on the surface additional specimens shall be provided to the of the specimen identified to the candidate. For candidate. The regions containing a flaw to be sized the remaining flaws, the regions of each specimen shall be identified to the candidate. The candidate containing a flaw to be sized shall be identified to shall determine the maximum depth of the flaw in the candidate. The candidate shall determine the each region.
maximum depth of the flaw in each region. (c) For a separate depth sizing test, the regions of each specimen containing a flaw to be sized shall be identified to the candidate. The candidate shall determine the maximum depth of the flaw in each region.
Basis: Clarifiedwording to better describe process.
3.0 ACCEPTANCE CRITERIA 3.1 Detection Acceptance Criteria Examination procedures, equipment, andfodectnwh: Alternative: Examination procedures are qualified personnel are persnnelarefor detection when:
qualified for detection when the results of the a. All flaws within the scope of the procedure are performance demonstration satisfy the acceptance detected and the results of the performance criteria of Table Vdeo-S2-1 for both detection and demonstration satisfy the acceptance criteria of critriaof Vll-S21abl fr bth dtecionand Table VIII-S2-1 for false calls.
false calls. The criteria shall be satisfied Tb.lea one sucsfuls peso separately by the demonstration results for base b. At least one successful personnel demonstration separatelynbysthndemonstration esultsgforibase has been performed meeting the acceptance criteria grading units and for overlay grading units, defined in (c).
- c. Examination equipment and personnel are qualified for detection when the results of the performance demonstration satisfy the acceptance criteria of Table VIII-S2-1 for both detection and false calls.
- d. The criteria in (b) and (c) shall be satisfied separately by the demonstration results for base metal grading units and for overlay fabrication grading units.
Basis: Clarifiedwording to better describe the difference between procedure qualificationand equipment andpersonnel qualifications.
3.2 Sizing Acceptance Criteria (a) The RMS error of the flaw length Alternative: (a) The...base metal flaws is ... 50 measurements, as compared to the true flaw percent though-base-metal position.
lengths, is less than or equal to 0.75 inch. The Basis: Clarifiedwording to be consistent with length of base metal cracking is measured at the 1.1(d)(1) above.
RR-A33, Attachment 2 Page 7 of 7 SUPPLEMENT 11 - QUALIFICATION PDI PROGRAM:
REQUIREMENTS FOR FULL The Proposed Alternative to Supplement 11 STRUCTURAL OVERLAID WROUGHT Requirements AUSTENITIC PIPING WELDS 75 percent through-base-metal position.
Alternative: This requirement is omitted.
Basis: The requirementfor reporting all extensions (b) All extensions of base metal cracking into the of cracking into the overlay is omittedfrom the PDI (b)rllyextensions byase meastal cringh intrported Programbecause it is redundant to the RMS ,
overlay material by at least 0.1 inch are reported calculationsperformed in paragraph3.2(c) and its as being intrusions into the overlay material. presence adds confusion and ambiguity to depth sizing as requiredby paragraph3.2(c). This also makes the weld overlay program consistentwith the supplement 2 depth sizing criteria.
RR-A33, ATTACHMENT 3 Page I of 5 COMPARISON OF ASME CODE CASE N-504-3 AND APPENDIX Q OF ASM[E CODE SECTION XI WITH THE PROPOSED ALTERNATIVE OF ATTACHMENT 1 FOR WELD OVERLAY ASME Code Case N-504-3 and Appendix Q of ASMIE Code Section XI Proposed Alternative of Attachment I ASME Code Case N-504-3 provides requirements for reducing a defect to a The proposed alternative of Attachment I provides requirements for installing flaw of acceptable size by deposition of weld reinforcement (weld overlay) on a repair or preemptive full structural weld overlay or preemptive optimized the outside surface of the pipe using austenitic stainless steel filler metal as an weld overlay by deposition of weld reinforcement (weld overlay) on the alternative to defect removal. ASME Code Case N-504-3 is applicable to outside surface of the item using Nickel Alloy 52M filler metal. Attachment I austenitic stainless steel piping only. According to Regulatory Guide 1.147, is applicable to dissimilar metal welds associated with nickel alloy materials.
the provisions of Nonmandatory Appendix Q of ASME Code Section XI must The proposed alternative of Attachment l is based on ASME Code Case N-also be met when using this Case. Therefore, the Code Case N-504-3 740-2.
requirements presented below have been supplemented by Appendix Q of ASME Code Section XI.
General Requirements General Requirements ASME Code Case N-504-3 and Appendix Q are only applicable to P-No. 8 As specified in paragraph 1.1(a), the proposed alternative is applicable to austenitic stainless steels. dissimilar metal 82/182 welds joining P-No. 3 to P-No. 8 or 43 materials and P-No. 8 to P-No. 43 materials. It is also applicable to austenitic stainless steel welds joining P-No. 8 materials.
Basis: ASME Code Case N-504-3 andAppendix Q are applicable to austenitic weld overlays of P-No. 8 austeniticstainless steel materials.Based on ASME Code Case N-740-2, the proposed alternativeofAttachment I was specifically written to address the applicationofweld overlays over dissimilarmetal welds and austeniticstainlesssteel welds.
According to paragraph (b) of ASME Code Case N-504-3 as supplemented by The weld filler metal and procedure requirements of paragraph 1.1(b) are Appendix Q, weld overlay filler metal shall be low carbon (0.035 percent equivalent to ASME Code Case N-504-3 and Appendix Q except as noted max.) austenitic stainless steel applied 360 degrees around the circumference below:
of the pipe, and shall be deposited using a Welding Procedure Specification for groove welding, qualified in accordance with the Construction Code and - Weld overlay filler metal shall be austenitic Nickel Alloy 52M Owner's Requirements and identified in the Repair/Replacement Plan. (ERNiCrFe-7A) filler metal which has a chromium content of at least 28 percent. Ifa stainless steel buffer layer is used as permitted by N-740-2, the ferrite content of the filler material shall be 5 - 15FN as required by the Construction Code.
As an alternative to post-weld heat treatment, the provisions for "Ambient
RR-A33, Attachment 3 Page 2 of 5 Temperature Temper Bead Welding" may be used on the ferritic nozzle as described in Attachment 1.
Basis: The weld overlay shall be deposited with ERNiCrFe-7A (Alloy 52M) filler metal. It has been includedinto ASME Code Section IXoas F-No. 43filler metals. Containing28.0 - 31.5 percent chromium (roughly twice the chromium content of 82/182filler metal), this filler metal has excellent resistance to primary water stress corrosion cracking. This point has been clearly documented in EPRI Technical Report MiRP-1 15, Section 2.2. Regardingthe weldingprocedure specification (WVPS), the requirements ofaAttachments 2 and 3 provide clarificationthat the WPS usedfor depositing weld overlays must be qualified as a groove welding procedureto ensure that mechanicalproperties ofthe WPS are appropriatelyestablished Where welding is performedon ferritic nozzles, an ambient temperature temper bead WPS shall be used Suitability of an ambienttemperature temper bead WPS is addressedin Section 5 of this Request According to paragraph (e) of ASME Code Case N-504-3 as supplemented by The weld overlay described in Attachment I is deposited using nickel Alloy Appendix Q, the weld reinforcement shall consist of at least two weld layers 52M filler metal instead of austenitic stainless steel filler metals. Therefore, the having as-deposited delta ferrite content of at least 7.5 FN. The first layer of basis for crediting the first layer towards the required design thickness is based weld metal with delta ferrite content of at least 7.5 FN shall constitute the first on the chromium content of the nickel alloy filler metal. According to layer of the weld reinforcement that may be credited toward the required paragraph AI.l(e), the first layer of nickel Alloy 52M deposited weld metal thickness. Alternatively, first layers of at least 5 FN provided the carbon may be credited toward the required thickness provided the portion of the layer content is determined by chemical analysis to be less than 0.02 percent. over the austenitic base material, austenitic weld, and the associated dilution zone from an adjacent ferritic base material contains at least 24 percent chromium. The chromium content of the deposited weld metal may be determined by chemical analysis of the production weld or from a representative coupon taken from a mockup prepared in accordance with the WPS for the production weld.
Basis: The weld overlay shall be depositedwith ERNiCrFe-7A (Alloy 52M) filler metal Creditfor the first weld layer may not be taken toward the requiredthickness unless it has been shown to contain at least 24 percent chromium. This is a sufficient amount of chromium to prevent primary water stress corrosion cracking.Section 2.2 of EPRI TechnicalReport MRP-115 states thefollowing: "The only well explored effect of the compositional differences among the weld alloys on primarywater stress corrosion cracking is the influence of chromium. Buisine, et al. (Reference 24) evaluated the primary water stress corrosioncracking resistanceof nickel-basedweld metals with various chromium contents ranvine from about 15 percent to 30 tercent
RR-A33, Attachment 3 Page 3 of5 chromium. Testing was performed in doped steam andprimary water.Alloy 182, with about 14.5 percent chromium, was the most susceptible. Alloy 82 with 18-20percent chromium took three orfour times longer to crack, For chromium contents between 21 and 22 percent,no stress corrosion crack initiationwas observed... "
Design and Crack Growth Considerations Design and Crack Growth Considerations The design and flaw characterization provisions of ASME Code Case N504-3, The design and flaw evaluation provisions in the proposed alternative are the paragraphs (f) and (g) as supplemented by Appendix Q are summarized below: same as ASME Code Case N-504-3 as supplemented in Appendix Q with the exceptions below. The proposed design and flaw evaluation provisions are (i) Flaw characterization and evaluation are based on the as-found flaw. Flaw based on postulated flaws or as-found flaws.
evaluation of the existing flaws is based on 1WB3640 for the design life.
- For weld overlay crack growth evaluations, a flaw with a depth of 10 percent
- Multiple circumferential flaws shall be treated as one flaw of length equal to and a circumference of 360 degrees shall be assumed or the as-found flaw size the sum of the lengths of the individual flaws. shall be used. The size of the flaws shall be projected to the end of the design life of the overlay. Crack growth, including both stress corrosion and fatigue
- Circumferential flaws are postulated as 100 percent through-wall for the crack growth, shall be evaluated in the materials in accordance with IWB-entire circumference with one exception. When the combined length of 3640. If the flaw is at or near the boundary of two different materials, circumferential flaws does not exceed 10 percent of the circumference, the evaluation of flaw growth in both materials is required.
flaws are only assumed to be 100 percent through-wall for the combined length of the flaws. Basis:. A preservicevolumetric examinationshall be performed after applicationofthe weld overlay using an ASAE Code Section X1, Appendix VIII
- For axial flaws 1.5 inches or longer, or for five or more axial flaws of any (as implemented through PDI)examinationprocedure. This examination shall length, the flaws shall be assumed to be 100 percent through-wall for the axial verify that there is no cracking in the upper 25 percent of the originalweld and length of the flaw and entire circumference of the pipe. base materialfor afull structuralweld overlay. The preservice examination shall also demonstrate that the assumed through-wallcrack depths are (ii) For four or fewer axial flaws less than 1.5 inches in length, the weld conservative. However, if any crack-likeflaws are identified in the upper 25 overlay thickness need only consist of two or more layers of weld metal percent of the originalweld or base materialby the preservice examination, meeting the deposit analysis requirements. then the as-foundflaw (postulated75 percent through-wallflaw plus the portionof theflaw in the upper 25 percent)shall be usedfor the crackgrowth (iii) The axial length and end slope of the weld overlay shall cover the weld analysis. With regardto design,flaws are consideredto be either 75 percent and HAZs on each side of the weld, and shall provide for load redistribution through-wallfor assumedcrack depth or 100 percent through the original from the item into the weld overlay and back into the item without violating weld when aflaw is identified by inspection and no structuralcredit is taken applicable stress limits of the Construction Code. Any laminar flaws in the for the weld. All other requirements are equivalent to ASME Code Case N-504-weld overlay shall be evaluated in the analysis to ensure that load redistribution 3 as supplementedby Appendix Q.
complies with the above. These requirements areusually met if the weld 2
overlay extends beyond the projected flaw by at least 0.75(Rt)" .
(iv) Unless specifically analyzed, the end transition slope of the overlay shall not exceed 45 degrees, and a slope of not more than 1:3 is recommended.
RR-A33, Attachment 3 Page 4 of 5 (v) The overlay design thickness of items shall be based on the measured diameter, using only the weld overlay thickness conforming to the deposit analysis requirements. The combined wall thickness at the weld overlay, any planar flaws in the weld overlay, and the effects of any discontinuity (for example, another weld overlay or reinforcement for a branch connection) 10 within a distance of 0.75(Rt) from the toes of the weld overlay, shall be evaluated and meet the requirements of 1WB-, IWC-, or 1WD-3640.
(vi) The effects of any changes in applied loads, as a result of weld shrinkage or existing flaws previously accepted by analytical evaluation shall be evaluated in accordance with IWB-3640, IWC-3640, or IWD-3640, as applicable.
Examination and Insoection Examination and lnsnection Examination and Insnection Acceptance Examination The acceptance standards in Attachment 1 are identical to those of paragraph Q-4100(c) states that the examination volume in Figure Q-4100-1 shall be Q-4100(c) except that the proposed method includes requirements and ultrasonically examined to assure adequate fusion (that is, adequate bond) with clarifications that are not included in Appendix Q. First, it specifies that the the base metal and to detect welding flaws, such as inter-bead lack of fusion, ultrasonic examination shall be conducted at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completing inclusions, or cracks. Planar flaws shall meet the preservice examination the third layer of the weld overlay when ambient temperature temper bead standards of Table IWB-3514-2. Laminar flaws shall meet the following: welding is used. Secondly, it provides the following clarifications:
- The interface C-D between the weld overlay and the weld includes the bond and the HAZ from the weld overlay.
- In applying the acceptance standards, wall thickness "t," shall be the thickness of the weld overlay.
Basis: Appendix Q is applicable to austenitic stainless steel materialsonly; therefore, ambient temperature temper bead welding would not be applicable.
It is applicableto welding performedin the proposedalternative. When ambient temperature temper bead welding is performed, nondestructive examinationsmust be performed at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completing the third layer of the weld overlay to allow sufficient time for hydrogen cracking to occur (if it is to occur). Technicaljustificationfor startingthe 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completion ofthe third layer ofthe weld overlay isprovided in Section 5 of the Request. The other two changes are simply clarificationsthat were added to ensure that the examination requirementswere appropriatelyperformed Q-4100(c)(1) states that laminar flaws shall meet the acceptance standards of The acceptance standards of the proposed method are identical to paragraph Q-Table IWB-3514-3. 4100(c)(1) exceot that the oroDosal includes the additional limitation that the
RR-A33, Attachment 3 Page 5 of 5 total laminar flaw shall not exceed 10 percent of the weld surface area and that no linear dimension of the laminar flaw area exceeds 3.0 inches Basis: These changes were made to provide additionalconservatism to the weld overlay examination and to reduce the size ofthe un-inspectable volume beneath a laminarflaw. See Section 5 ofthis Requestfor additional information.
Q-4100(c)(4) allows the performance of radiography in accordance with the The acceptance standards of the proposed alternative do not include the Construction Code as an alternative to Q-4100(c) (3). radiographic alternative of paragraph Q-4100(c)(4).
Basis: The ultrasonic examinationsperformed in accordancewith the proposedalternativeare in accordancewith ASME Cod,Section X1, Appendix VIII, Supplement 11 as implemented through the PD!. These examinationsare consideredmore sensitivefor detection of defects, eitherfrom fabricationor service-induced,than either ASMIE Code Section III radiographicor ultrasonic methods. Furthermore,constructiontypeflaws have been includedin the PDI qualificationsample sets for evaluatingproceduresandpersonnel. See Section 5 of this Requestfor additionaljustfication.
Preservice Inspection Preservice Inspection Q-4200(b) states that the preservice examination acceptance standards of Table The acceptance standards of the proposed alternative are identical to paragraph tIWB-3514-2 shall be met for the weld overlay. Cracks in the outer 25 percent Q-4200(b) except proposed alternative includes the following statement: "In of the base metal shall meet the design analysis requirements of Q-3000. applying the acceptance standards, wall thickness, shall be the thickness of the weld overlay."
Basis: This provisionis actually a clarificationthat the nominal wall thickness of Table IWB-3514-2 shall be considered the thickness of the weld overlay. It must be remembered that the acceptance standards were originally writtenfor the welds identified in IWB-2500. Because IWB-2500 does not addressweld overlays, this clarificationwas providedto avoid any potentialconfusion.
However, defining the weld overlay thickness as the nominal wall thickness 6f Table IWB-3514-2 has always been the practicesince it literally becomes the new design wall of the piping or component nozzle.
Pressure Testing Pressure Testing (h) The completed repair shall be pressure tested in accordance with IWA- The pressure testing requirements included in the alternative are similar to 5000. A system hydrostatic test is required if the flaw penetrated the pressure paragraph (h) of ASME Code Case N-504-3 except that only a system leakage boundary. A system leakage test may be performed if pressure boundary is not test per IWA-5000 is required.
penetrated.