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| | number = ML17069A187 | | | number = ML17069A187 |
| | issue date = 03/22/2017 | | | issue date = 03/22/2017 |
| | title = Waterford Steam Electric Station, Unit 3 - Request for Alternative to 10 CFR 50.55a(c) ASME Code Section Iii Code Case 1361-1, Relief Request W3-ISI-024 (CAC No. MF7752) | | | title = Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024 |
| | author name = Pascarelli R J | | | author name = Pascarelli R |
| | author affiliation = NRC/NRR/DORL | | | author affiliation = NRC/NRR/DORL |
| | addressee name = | | | addressee name = |
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| | docket = 05000382 | | | docket = 05000382 |
| | license number = NPF-038 | | | license number = NPF-038 |
| | contact person = Pulvirenti A L | | | contact person = Pulvirenti A |
| | case reference number = CAC MF7752, W3-ISI-024 | | | case reference number = CAC MF7752, W3-ISI-024 |
| | document type = Code Relief or Alternative, Letter, Safety Evaluation | | | document type = Code Relief or Alternative, Letter, Safety Evaluation |
| | page count = 7 | | | page count = 7 |
| | project = CAC:MF7752 | | | project = CAC:MF7752 |
| | stage = Approval | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Site Vice President Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 March 22, 2017 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 22, 2017 Site Vice President Entergy Operations, Inc. |
| | Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WATERFORD STEAM ELECTRIC STATION, UNIT 3 -REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c) ASME CODE SECTION Ill, CODE CASE 1361-1, RELIEF REQUEST W3-ISl-024 (CAC NO. MF7752) | | WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c) ASME CODE SECTION Ill, CODE CASE 1361-1, RELIEF REQUEST W3-ISl-024 (CAC NO. MF7752) |
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| ==Dear Sir:== | | ==Dear Sir:== |
| By letter dated May 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16144A218), Entergy Operations, Inc. (the licensee), submitted Relief Request (RR) W3-ISl-024, proposing an alternative to the weld requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) at Waterford Steam Electric Station, Unit 3 (Waterford 3). Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(z)(1 ), the licensee requested to use the alternative proposed in RR W3-ISl-024 on the basis that the proposed alternative will provide an acceptable level of quality and safety. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject request and has determined, as set forth in the enclosed safety evaluation, that for RR W3-ISl-024, the proposed alternative will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for this proposed alternative. Therefore, the NRC staff authorizes the use of the proposed alternative for the duration of the operating license for Waterford 3. | | |
| If you have any questions, please contact the Project Manager, April Pulvirenti at 301-415-1390 or via e-mail at April.Pulvirenti@nrc.gov. Docket No. 50-382 | | By letter dated May 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16144A218), Entergy Operations, Inc. (the licensee), submitted Relief Request (RR) W3-ISl-024, proposing an alternative to the weld requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) at Waterford Steam Electric Station, Unit 3 (Waterford 3). |
| | Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(z)(1 ), the licensee requested to use the alternative proposed in RR W3-ISl-024 on the basis that the proposed alternative will provide an acceptable level of quality and safety. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject request and has determined, as set forth in the enclosed safety evaluation, that for RR W3-ISl-024, the proposed alternative will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for this proposed alternative. Therefore, the NRC staff authorizes the use of the proposed alternative for the duration of the operating license for Waterford 3. |
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| | If you have any questions, please contact the Project Manager, April Pulvirenti at 301-415-1390 or via e-mail at April.Pulvirenti@nrc.gov. |
| | Sincerely, Robert J. Pascarelli, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl: Distribution via Listserv Sincerely, Robert J. Pascarelli, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c} ASME CODE SECTION 111 CODE CASE 1361-1. RELIEF REQUEST W3-ISl-024 WATERFORD STEAM ELECTRIC STATION. UNIT 3 ENTERGY OPERATIONS. INC. DOCKET NO. 50-382
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| ==1.0 INTRODUCTION== | | Safety Evaluation cc w/encl: Distribution via Listserv |
| By letter dated May 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16144A218), Entergy Operations Inc. (the licensee), submitted Relief Request (RR) W3-ISl-024 under the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z)(1 ), from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) weld requirements at the Waterford Steam Electric Station, Unit 3 (Waterford 3). Pursuant to 10 CFR 50.55a(z)(1 ), the licensee proposed an alternative to allow the fillet weld with a maximum diametral clearance of 0.062 inches between the pressurizer heater sheath and sleeve instead of 0.045 inches as specified in ASME Code Section Ill, Code Case 1361-1. The alternative is proposed for the remainder of the Waterford 3 operating license. | | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c} |
| | ASME CODE SECTION 111 CODE CASE 1361-1. RELIEF REQUEST W3-ISl-024 WATERFORD STEAM ELECTRIC STATION. UNIT 3 ENTERGY OPERATIONS. INC. |
| | DOCKET NO. 50-382 |
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| | ==1.0 INTRODUCTION== |
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| | By letter dated May 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16144A218), Entergy Operations Inc. (the licensee), submitted Relief Request (RR) W3-ISl-024 under the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z)(1 ), from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) weld requirements at the Waterford Steam Electric Station, Unit 3 (Waterford 3). Pursuant to 10 CFR 50.55a(z)(1 ), the licensee proposed an alternative to allow the fillet weld with a maximum diametral clearance of 0.062 inches between the pressurizer heater sheath and sleeve instead of 0.045 inches as specified in ASME Code Section Ill, Code Case 1361-1. The alternative is proposed for the remainder of the Waterford 3 operating license. |
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| | ==2.0 REGULATORY EVALUATION== |
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| ==2.0 REGULATORY EVALUATION==
| | Pursuant to 10 CFR 50.55a(c)(1 ), reactor coolant pressure boundary components must meet the requirements for Class 1 components of Section Ill of the ASME Code to which the licensee adheres, except as provided in paragraphs (c)(2) through (c)(4) of 10 CFR 50.55a. |
| Pursuant to 1 O CFR 50.55a(c)(1 ), reactor coolant pressure boundary components must meet the requirements for Class 1 components of Section Ill of the ASME Code to which the licensee adheres, except as provided in paragraphs (c)(2) through (c)(4) of 10 CFR 50.55a. Pursuant to 10 CFR 50.55a(c)(3), "Applicable Code Cases and conditions on their use," the licensee applies ASME Code Case 1361-1, "Socket Welds, Section 111," dated April 27, 1967. This ASME code case is incorporated into the Waterford 3 Updated Final Safety Analysis Report (UFSAR) Section 5.2.1.2, "Applicable Code Cases," and identifies ASME Code Section Ill, Code Case 1361-1, as the applicable ASME Code for part of the original pressurizer assembly. ASME Code Case 1361-1 was later replaced by ASME Code Case 1361-2, dated March 1, 1979. As stated, in part, in 10 CFR 50.55a(b)(4)(ii): If an applicant or licensee has previously applied a Code Case and a later version of the Code Case is incorporated by reference in paragraph (a) of this section, the applicant or licensee may continue to apply the previous version of the Code Case as authorized or may apply the later version of the Code Case, including any NRG-specified conditions placed on its use, until it updates its Code of Record for the component being constructed. Enclosure In Regulatory Guide (RG) 1.84 "Design, Fabrication, and Materials Code Case Acceptability, ASME Section 111," Revision 36, dated August 2014 (ADAMS Accession No. ML 13339A515), ASME Code Case 1361-2 is endorsed by NRC staff on the condition that the Code Case is applied in connection to Section Ill, paragraph NB-3356, "Fillet Welds." The alternative requested by the licensee is in connection with fillet welds for pressurizer heater sleeves. Therefore, the licensee meets the conditions to apply ASME Code Case 1361-2, and pursuant to 10 CFR 50.55a(b)(4)(ii), the licensee may also continue to apply ASME Code Case 1361-1. Pursuant to 1 O CFR 50.55a(z), alternatives to the requirements of paragraph (c) of 1 O CFR 50.55a may be used when authorized by the Director, Office of Nuclear Reactor Regulation. A proposed alternative must be requested and authorized prior to implementation. The licensee must demonstrate ( 1) the proposed alternative would provide an acceptable level of quality and safety; or (2) compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The U.S. Nuclear Regulatory Commission (NRC) has approved similar relief requests for the Palo Verde Nuclear Generation Station, Units 1, 2 and 3, on November 19, 2004, (ADAMS Accession No. ML043240213), and for San Onofre Nuclear Generating Station, Units 2 and 3, on February 8, 2006, (ADAMS Accession No. ML060410323). Based on the above, and subject to the following technical evaluation, the NRC staff finds that the licensee continues to apply ASME Code Case 1361-1, and that regulatory authority exists for the licensee to propose, and NRC to authorize, an alternative to ASME Code Case 1361-1. | | Pursuant to 10 CFR 50.55a(c)(3), "Applicable Code Cases and conditions on their use," the licensee applies ASME Code Case 1361-1, "Socket Welds, Section 111," dated April 27, 1967. |
| | This ASME code case is incorporated into the Waterford 3 Updated Final Safety Analysis Report (UFSAR) Section 5.2.1.2, "Applicable Code Cases," and identifies ASME Code Section Ill, Code Case 1361-1, as the applicable ASME Code for part of the original pressurizer assembly. |
| | ASME Code Case 1361-1 was later replaced by ASME Code Case 1361-2, dated March 1, 1979. As stated, in part, in 10 CFR 50.55a(b)(4)(ii): |
| | If an applicant or licensee has previously applied a Code Case and a later version of the Code Case is incorporated by reference in paragraph (a) of this section, the applicant or licensee may continue to apply the previous version of the Code Case as authorized or may apply the later version of the Code Case, including any NRG-specified conditions placed on its use, until it updates its Code of Record for the component being constructed. |
| | Enclosure |
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| ==3.0 TECHNICAL EVALUATION==
| | In Regulatory Guide (RG) 1.84 "Design, Fabrication, and Materials Code Case Acceptability, ASME Section 111," Revision 36, dated August 2014 (ADAMS Accession No. ML13339A515), |
| 3.1 Licensee's Request for Alternative 3.1.1 Components Affected The affected components are 30 Code Class 1 pressurizer heater sleeves, Item Number RC MPZR0001. 3.1.2 Applicable Code Requirements The applicable construction code for the Waterford 3 pressurizer vessel is ASME Code Section Ill, 1971 Edition through Summer 1971 Addenda. The applicable ASME Code is ASME Code Case 1361-1, dated April 27, 1967. ASME Code Case 1361-1 states, in part: Appurtenances with outside diameter equal to that of 2-inch standard pipe size and less may be constructed using weld joints in accordance with Fig. 1, provided all the following requirements are met: 1) The design of the joint shall be such that stresses will not exceed the limits described in NB-3220, N417, and tabulated in Tables 1-1.1 and 1-1.2. 2) A fatigue strength reduction factor of not less than 4 shall be used in fatigue analyses of the joints.
| | ASME Code Case 1361-2 is endorsed by NRC staff on the condition that the Code Case is applied in connection to Section Ill, paragraph NB-3356, "Fillet Welds." The alternative requested by the licensee is in connection with fillet welds for pressurizer heater sleeves. |
| 3) The finished welds shall be examined by a magnetic particle method in accordance with NB-5000 .... 4) End closure connections may be made with fillet welds or partial penetration welds provided the conditions ... are met. Per Figure 1 of Code Case 1361-1, "Weld Connection for Appurtenances 2-inch Pipe Size and Smaller which are Attached to Nozzles," where cMAX = diametral clearance between connecting parts, cMAX = 0.045 inches is specified. 3.1.3 Licensee's Proposed Alternative The licensee proposes an alternative to allow a fillet weld with a maximum 0.062-inch diametral clearance between the connecting pressurizer heater sleeves and pressurizer heater sheaths, instead of a diametral clearance of 0.045 inches as specified in ASME Code Case 1361-1. The alternative is proposed to apply to all applicable pressurizer heater shims and sheaths. 3.1.4 Licensee's Basis for Authorization of the Proposed Alternative As described in the licensee's application dated May 19, 2016, the basis for the requirement of a 0.45-inch diametral clearance is not specified in ASME Code Case 1361-1. However, maintaining a relatively small clearance between the parts will ensure that the bending stresses that can be imparted on the fillet weld due to deflection of the parts will not exceed the limits described in NB-3220, "Stress Limits for Other Than Bolts." Therefore, the licensee states that the heater sheath to sleeve fillet weld should be evaluated on the basis of whether the weld complies with the stress and fatigue requirements of ASME Code Case 1361-1. In the application for the proposed alternative, the licensee provided an analysis of the stresses on the fillet weld using the proposed diametral clearance between the parts of 0.062 inches. According to the analysis, the proposed joint configuration complies with ASME Code NB-3220 for allowable primary membrane, primary membrane plus bending, primary plus secondary, and fatigue stresses. The licensee's justification for the proposed alternative is that although the maximum diametral clearance of 0.62 inches will exceed the 0.45-inch requirement of ASME Code Case 1361-1, the reconfigured weld joint will continue to meet the stress and fatigue strength requirements specified in ASME Code Case 1361-1, and therefore remain acceptable from a stress/fatigue perspective. Thus the alternative would provide an acceptable level of quality and safety, meeting the requirements of 1 O CFR 50.55a(z)(1 ). 3.2 NRC Staff's Evaluation The licensee proposed an alternative to allow the fillet weld with a maximum 0.062-inch diametral clearance between connecting parts, instead of 0.045 inches as specified in ASME Code Case 1361-1. This code case was revised to ASME Code Case 1361-2, which was endorsed by the NRC staff in RG 1.84, Revision 36. The NRC staffs evaluation of the licensee's proposed relief request to increase the diametral clearance between the heater sleeve and heater sheath focused on the new stresses that would be seen by the connecting joints. ASME Code Case 1361-1 contains the following requirements concerning the design of weld joints between appurtenances:
| | Therefore, the licensee meets the conditions to apply ASME Code Case 1361-2, and pursuant to 10 CFR 50.55a(b)(4)(ii), the licensee may also continue to apply ASME Code Case 1361-1. |
| 1. The design of the joint shall be such that stresses will not exceed the limits described in NB-3220, and tabulated in Tables 1-1.1 and 1-1.2. 2. A fatigue strength reduction factor of not less than four shall be used in the fatigue analyses of the joints. The specific value of diametral clearance that is contained in ASME Code Case 1361-1 is intended to maintain the relatively small clearance between the parts, limiting the amount of bending stresses that can be imparted on the fillet weld due to deflection of the parts. However, the primary assurance of safety is demonstrated by satisfying the ASME Code stress limits. Therefore, the NRC staff's acceptance of the proposed increase in diametral clearance will be based on whether the stress/fatigue requirements stated above are met. ASME Section Ill, NB-3220, specifies loading conditions that need to be considered and specifies the stress limits that must be satisfied for these load conditions. The specific stresses to be considered for the sleeve-to-sheath weld are general primary stress, primary membrane-plus-bending stress, and primary-plus-secondary stress. The licensee accounted for the increased diametral clearance by reducing the weld throat area used to calculate the stresses in the finite element model analysis. The NRC staff reviewed the licensee's calculation and concluded that this analysis was satisfactorily performed, and that all resultant stresses were within the acceptance criteria required by NB-3220. Therefore, the staff finds that stress requirements have been satisfied. ASME Section Ill, NB-3222.4(d), "Components Not Requiring Analysis for Cyclic Operation," identifies the requirements for components not requiring fatigue analysis. The licensee has performed evaluation to demonstrate that NB-3222.4(d), conditions (1) through (6), are met and the component is exempt from a fatigue analysis. The NRC staff reviewed the licensee's evaluation and concluded that all the requirements of NB-3222.4(d)(1) through (6) are met. Therefore, the staff finds that the fillet weld is exempted from a fatigue analysis and the fatigue requirement has been satisfied. On the basis mentioned above, the proposed weld joint is acceptable from a stress/fatigue perspective. Therefore, the proposed weld joint meets the stress/fatigue requirements of ASME Code Case 1361-1 .
| | Pursuant to 10 CFR 50.55a(z), alternatives to the requirements of paragraph (c) of 10 CFR 50.55a may be used when authorized by the Director, Office of Nuclear Reactor Regulation. A proposed alternative must be requested and authorized prior to implementation. |
| | The licensee must demonstrate ( 1) the proposed alternative would provide an acceptable level of quality and safety; or (2) compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| | The U.S. Nuclear Regulatory Commission (NRC) has approved similar relief requests for the Palo Verde Nuclear Generation Station, Units 1, 2 and 3, on November 19, 2004, (ADAMS Accession No. ML043240213), and for San Onofre Nuclear Generating Station, Units 2 and 3, on February 8, 2006, (ADAMS Accession No. ML060410323). |
| | Based on the above, and subject to the following technical evaluation, the NRC staff finds that the licensee continues to apply ASME Code Case 1361-1, and that regulatory authority exists for the licensee to propose, and NRC to authorize, an alternative to ASME Code Case 1361-1. |
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| ==4.0 CONCLUSION== | | ==3.0 TECHNICAL EVALUATION== |
| The NRC staff has reviewed the subject request and has concluded, on the basis that the ASME Code stress qualification for the fillet weld integrity has been demonstrated and the component is able to perform its intended function, that the alternative proposed in RR W3-ISl-024 will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for this proposed alternative. Therefore, the NRC staff authorizes the use of the proposed alternative for the duration of the operating license for Waterford 3. Principal Contributor: K. Hsu Date: March 22, 201 7 | | |
| | 3.1 Licensee's Request for Alternative 3.1.1 Components Affected The affected components are 30 Code Class 1 pressurizer heater sleeves, Item Number RC MPZR0001. |
| | 3.1.2 Applicable Code Requirements The applicable construction code for the Waterford 3 pressurizer vessel is ASME Code Section Ill, 1971 Edition through Summer 1971 Addenda. The applicable ASME Code is ASME Code Case 1361-1, dated April 27, 1967. ASME Code Case 1361-1 states, in part: |
| | Appurtenances with outside diameter equal to that of 2-inch standard pipe size and less may be constructed using weld joints in accordance with Fig. 1, provided all the following requirements are met: |
| | : 1) The design of the joint shall be such that stresses will not exceed the limits described in NB-3220, N417, and tabulated in Tables 1-1.1 and 1-1.2. |
| | : 2) A fatigue strength reduction factor of not less than 4 shall be used in fatigue analyses of the joints. |
| | : 3) The finished welds shall be examined by a magnetic particle method in accordance with NB-5000 .... |
| | : 4) End closure connections may be made with fillet welds or partial penetration welds provided the conditions ... are met. |
| | Per Figure 1 of Code Case 1361-1, "Weld Connection for Appurtenances 2-inch Pipe Size and Smaller which are Attached to Nozzles," where cMAX = diametral clearance between connecting parts, cMAX =0.045 inches is specified. |
| | 3.1.3 Licensee's Proposed Alternative The licensee proposes an alternative to allow a fillet weld with a maximum 0.062-inch diametral clearance between the connecting pressurizer heater sleeves and pressurizer heater sheaths, instead of a diametral clearance of 0.045 inches as specified in ASME Code Case 1361-1. The alternative is proposed to apply to all applicable pressurizer heater shims and sheaths. |
| | 3.1.4 Licensee's Basis for Authorization of the Proposed Alternative As described in the licensee's application dated May 19, 2016, the basis for the requirement of a 0.45-inch diametral clearance is not specified in ASME Code Case 1361-1. However, maintaining a relatively small clearance between the parts will ensure that the bending stresses that can be imparted on the fillet weld due to deflection of the parts will not exceed the limits described in NB-3220, "Stress Limits for Other Than Bolts." Therefore, the licensee states that the heater sheath to sleeve fillet weld should be evaluated on the basis of whether the weld complies with the stress and fatigue requirements of ASME Code Case 1361-1. In the application for the proposed alternative, the licensee provided an analysis of the stresses on the fillet weld using the proposed diametral clearance between the parts of 0.062 inches. According to the analysis, the proposed joint configuration complies with ASME Code NB-3220 for allowable primary membrane, primary membrane plus bending, primary plus secondary, and fatigue stresses. |
| | The licensee's justification for the proposed alternative is that although the maximum diametral clearance of 0.62 inches will exceed the 0.45-inch requirement of ASME Code Case 1361-1, the reconfigured weld joint will continue to meet the stress and fatigue strength requirements specified in ASME Code Case 1361-1, and therefore remain acceptable from a stress/fatigue perspective. Thus the alternative would provide an acceptable level of quality and safety, meeting the requirements of 10 CFR 50.55a(z)(1 ). |
| | 3.2 NRC Staff's Evaluation The licensee proposed an alternative to allow the fillet weld with a maximum 0.062-inch diametral clearance between connecting parts, instead of 0.045 inches as specified in ASME Code Case 1361-1. This code case was revised to ASME Code Case 1361-2, which was endorsed by the NRC staff in RG 1.84, Revision 36. |
| | The NRC staffs evaluation of the licensee's proposed relief request to increase the diametral clearance between the heater sleeve and heater sheath focused on the new stresses that would be seen by the connecting joints. ASME Code Case 1361-1 contains the following requirements concerning the design of weld joints between appurtenances: |
| | : 1. The design of the joint shall be such that stresses will not exceed the limits described in NB-3220, and tabulated in Tables 1-1.1 and 1-1.2. |
| | : 2. A fatigue strength reduction factor of not less than four shall be used in the fatigue analyses of the joints. |
| | The specific value of diametral clearance that is contained in ASME Code Case 1361-1 is intended to maintain the relatively small clearance between the parts, limiting the amount of bending stresses that can be imparted on the fillet weld due to deflection of the parts. However, the primary assurance of safety is demonstrated by satisfying the ASME Code stress limits. |
| | Therefore, the NRC staff's acceptance of the proposed increase in diametral clearance will be based on whether the stress/fatigue requirements stated above are met. |
| | ASME Section Ill, NB-3220, specifies loading conditions that need to be considered and specifies the stress limits that must be satisfied for these load conditions. The specific stresses to be considered for the sleeve-to-sheath weld are general primary stress, primary membrane-plus-bending stress, and primary-plus-secondary stress. The licensee accounted for the increased diametral clearance by reducing the weld throat area used to calculate the stresses in the finite element model analysis. The NRC staff reviewed the licensee's calculation and concluded that this analysis was satisfactorily performed, and that all resultant stresses were within the acceptance criteria required by NB-3220. Therefore, the staff finds that stress requirements have been satisfied. |
| | ASME Section Ill, NB-3222.4(d), "Components Not Requiring Analysis for Cyclic Operation," |
| | identifies the requirements for components not requiring fatigue analysis. The licensee has performed evaluation to demonstrate that NB-3222.4(d), conditions (1) through (6), are met and the component is exempt from a fatigue analysis. |
| | The NRC staff reviewed the licensee's evaluation and concluded that all the requirements of NB-3222.4(d)(1) through (6) are met. Therefore, the staff finds that the fillet weld is exempted from a fatigue analysis and the fatigue requirement has been satisfied. |
| | On the basis mentioned above, the proposed weld joint is acceptable from a stress/fatigue perspective. Therefore, the proposed weld joint meets the stress/fatigue requirements of ASME Code Case 1361-1 . |
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| | ==4.0 CONCLUSION== |
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| | The NRC staff has reviewed the subject request and has concluded, on the basis that the ASME Code stress qualification for the fillet weld integrity has been demonstrated and the component is able to perform its intended function, that the alternative proposed in RR W3-ISl-024 will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for this proposed alternative. Therefore, the NRC staff authorizes the use of the proposed alternative for the duration of the operating license for Waterford 3. |
| | Principal Contributor: K. Hsu Date: March 22, 201 7 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WATERFORD STEAM ELECTRIC STATION, UNIT 3-REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c) ASME CODE SECTION Ill, CODE CASE 1361-1, RELIEF REQUEST W3-ISl-024 (CAC NO. MF7752) DATED MARCH 22, 2017 DISTRIBUTION: PUBLIC Branch Reading RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4-2 Resource RidsNrrDeEpnb Resource RidsNrrLAPBlechmanResource RidsNrrPMWaterford Resource RidsRgn4MailCenter Resource JBowen, EDO RIV ADAMS A ccess1on N ML 17069A187 o. *b 1y memo d t d J I 5 2016 ae UIY , OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA N RR/DE/EMCB/BC(A)* NRR/DORL/LPL4/BC NAME APulvirenti PBlechman YLi RPascarelli DATE 3/16/2017 3/15/2017 7/05/2016 3/22/2017 OFFICIAL RECORD COPY | | WATERFORD STEAM ELECTRIC STATION, UNIT 3- REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c) ASME CODE SECTION Ill, CODE CASE 1361-1, RELIEF REQUEST W3-ISl-024 (CAC NO. MF7752) DATED MARCH 22, 2017 DISTRIBUTION: |
| }} | | PUBLIC Branch Reading RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4-2 Resource RidsNrrDeEpnb Resource RidsNrrLAPBlechmanResource RidsNrrPMWaterford Resource RidsRgn4MailCenter Resource JBowen, EDO RIV ADAMS A ccess1on No. ML17069A187 *b1y memo dae t d J UIY I 5, 2016 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DE/EMCB/BC(A)* NRR/DORL/LPL4/BC NAME APulvirenti PBlechman YLi RPascarelli DATE 3/16/2017 3/15/2017 7/05/2016 3/22/2017 OFFICIAL RECORD COPY}} |
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Category:Code Relief or Alternative
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Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
ML20022A2582020-01-28028 January 2020
Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control
ML20002A0202020-01-13013 January 2020
Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System
ML19254A6032019-09-19019 September 2019
Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1
ML19247B1972019-09-0909 September 2019
Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination
ML19232A0252019-08-27027 August 2019
Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities
W3F1-2019-0052, CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2)2019-07-18018 July 2019
CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2)
CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019
Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1
W3F1-2018-0065, Request for Relief from ASME Section XI Volumetric Examination Requirements - Third 10-Year Interval, W3-ISI-0322018-11-30030 November 2018
Request for Relief from ASME Section XI Volumetric Examination Requirements - Third 10-Year Interval, W3-ISI-032
ML18128A0672018-06-0808 June 2018
Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4
ML17341A1202017-12-11011 December 2017
Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049)
ML17328A8822017-11-29029 November 2017
Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47)
CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017
Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1
ML17069A1872017-03-22022 March 2017
Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024
ML16235A2282016-12-0909 December 2016
Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants
ML16182A2702016-07-0606 July 2016
Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program
ML16096A2692016-06-0606 June 2016
Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1
CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015
Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division
ML14070A0082014-03-26026 March 2014
Request for Alternative W3-ISI-023, ASME Code Case N-770-1 Successive Examinations, Third 10-Year Inservice Inspection Interval
ML13192A2222013-08-0202 August 2013
Request for Alternative W3-ISI-021, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval
ML13128A1292013-05-31031 May 2013
Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval
ML13085A1592013-03-26026 March 2013
Verbal Authorization on 12/18/2012, Request for Alternative W3-ISI-021, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval
ML13085A1252013-03-26026 March 2013
Verbal Authorization on 12/18/2012, Revised Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval
ML12293A3622012-11-0808 November 2012
Relief Request VRR-WF3-2012-1 Associated with Category a Leak Test of Component Cooling Water Check Valve ACC-108B for the Third 10-Year Inservice Inspection Interval
W3F1-2012-0085, Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request2012-10-16016 October 2012
Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request
ML12234A6352012-08-21021 August 2012
Verbal Authorization of Relief Request VRR-WF3-2012-1
ML1133301372012-01-0404 January 2012
Request for Alternative W3-CISI-002 to ASME Code, Section XI, IWE-5221 for Post-repair Testing of Steel Containment Vessel Opening, Third 10-Year Inservice Inspection Interval
ML1125701682011-10-14014 October 2011
Request for Alternative W3-ISI-019 from Inservice Inspection Requirements of Reactor Vessel Head In-Core Instrument Nozzles, Third 10-Year Inservice Inspection Interval
ML1125702732011-10-14014 October 2011
Request for Alternative W3-ISI-018 from Inservice Inspection Requirements of Reactor Pressure Vessel Head Control Element Drive Mechanism Nozzles, Third 10-Year Inservice Inspection Interval
ML1035703922011-01-13013 January 2011
Relief Request No. W3-ISI-017, Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection, for Third 10-Year Inservice Inspection Interval
ML1029903712010-11-23023 November 2010
Correction to May 18, 2010 Safety Evaluation for Relief Request No. W3-CISI-001 Regarding Post Repair Testing of the Steel Containment Vessel Opening
ML1015905742010-06-30030 June 2010
Relief Request Nos. WF3-ISI-007 to WF3-ISI-014 from ASME Code, Section XI Volumetric Examination Requirements - Second 10-Year Interval
ML1008500892010-05-18018 May 2010
Relief Request W3-CISI-001, Request for Alternative to ASME IWE-5521, Post Repair Testing of the Steel Containment Vessel Opening
ML1008203552010-03-23023 March 2010
Request for Additional Information Round 2, Relief Request Nos. WF3-ISI-007 to WF3-ISI-014 from ASME Code, Section XI Volumetric Examination Requirements - Second 10-Year Interval
W3F1-2010-0018, Request for Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection2010-02-22022 February 2010
Request for Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection
W3F1-2010-0002, Request for NRC Alternative to ASME IWE-5521 Regarding Post Repair Testing of Waterford 3's Steel Containment Vessel-Opening2010-02-0909 February 2010
Request for NRC Alternative to ASME IWE-5521 Regarding Post Repair Testing of Waterford 3's Steel Containment Vessel-Opening
2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-7162010-01-28028 January 2010
Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
ML0931604422009-11-0404 November 2009
Email Verbal Authorization of Request for Alternative W3-ISI-015 - Third 10-year Inservice Inspection Interval
ML0930808142009-11-0404 November 2009
Email Verbal Authorization of Request for Alternative - W3-ISI-016
ML0912103752009-06-12012 June 2009
Relief, Request for Alternative W3-ISI-006, from Requirements of ASME Code Section XI, for Second 10-Year Inservice Inspection Interval
ML0903708982009-03-0606 March 2009
Unit 3 - Request for Alternative CEP-ISI-012, Use Alternative Requirements in ASME Code Case N-753
CNRO-2009-00001, Relief Requests for Third 120 Month Inservice Inspection Interval2009-01-23023 January 2009
Relief Requests for Third 120 Month Inservice Inspection Interval
CNRO-2008-00035, Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 8052008-11-20020 November 2008
Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 805
ML0809801202008-04-28028 April 2008
Request for Alternative W3-ISI-005, Request to Use ASME Code Case N-716
ML0809502732008-04-21021 April 2008
Revised Request for Alternative W3-R&R-006 to ASME Code Requirements for Weld Overlay Repairs for Second 10-Year Inservice Inspection
ML0802504912008-02-15015 February 2008
Request for Alternative W3-ISI-003 to ASME Code Requirements to Allow Extension to Second 10-Year Inservice Inspection Interval Beyond That Currently Allowed by ASME Subsection IWA-2340(d)
ML0725600262007-09-24024 September 2007
Withdrawal of W3-ISI-002, Request for Alternative
CNRO-2007-00027, Request for Alternative W3-ISI-004 Proposed Alternative to Second Interval ISI Examinations2007-08-0707 August 2007
Request for Alternative W3-ISI-004 Proposed Alternative to Second Interval ISI Examinations
ML0701200812007-02-0202 February 2007
River Bend Station, & Waterford Steam Electric Station, Unit 3 - Request for Alternative CEP-PT-001, Visual Exam of Vent & Drain Leakage Tests (TAC MD1399, MD1400, MD1401, MD1402, & MD1403)
2021-10-28
[Table view]
Category:Letter
MONTHYEARIR 05000382/20230102024-01-31031 January 2024
Comprehensive Engineering Team Inspection Report 05000382/2023010
IR 05000382/20230032024-01-23023 January 2024
Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003
ML24012A1962024-01-12012 January 2024
Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and
ML23340A2292023-12-28028 December 2023
Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR
ML23349A1672023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting
ML23352A0292023-12-13013 December 2023
Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection
ML23340A1592023-12-13013 December 2023
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
ML23333A1362023-11-29029 November 2023
Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23325A1442023-11-21021 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23312A1832023-11-14014 November 2023
Integrated Inspection Report 05000382/2023003 and Notice of Violation
ML23311A2082023-11-0909 November 2023
Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV
IR 05000382/20234012023-10-0404 October 2023
Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only)
IR 05000382/20230052023-08-21021 August 2023
Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005)
IR 05000382/20233012023-08-15015 August 2023
NRC Initial Operator Licensing Examination Approval 05000382/2023301
IR 05000382/20230022023-08-0808 August 2023
Integrated Inspection Report 05000382/2023002
IR 05000382/20234022023-08-0707 August 2023
NRC Security Inspection Report 05000382/2023402 (Full Report)
IR 05000382/20230402023-07-12012 July 2023
Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter
ML23191A4562023-07-10010 July 2023
Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information
ML23158A1042023-06-0808 June 2023
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401
ML23145A2272023-06-0202 June 2023
95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion
ML23130A2732023-05-10010 May 2023
and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
IR 05000382/20230012023-04-24024 April 2023
Integrated Inspection Report 05000382/2023001, Independent Spent Fuel Storage Installation Report 07200075/2023001, and Exercise of Enforcement Discretion
ML23111A2132023-04-21021 April 2023
Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities
ML23110A1122023-04-20020 April 2023
Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
ML23108A2542023-04-18018 April 2023
WCGS Information Request, Security IR 2023401
IR 05000382/20234032023-04-17017 April 2023
Security Baseline Inspection Report 05000382/2023403
ML23093A2122023-04-0303 April 2023
Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022
ML23089A0602023-03-30030 March 2023
Entergy Operations, Inc. - Fleet Project Manager Assignment
ML23088A3922023-03-29029 March 2023
Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))
ML23080A2882023-03-21021 March 2023
Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc
ML23059A2592023-03-0707 March 2023
Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML23065A2002023-03-0303 March 2023
EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors
ML23060A1092023-03-0101 March 2023
Proof of Financial Protection (10 CFR 140.15)
IR 05000382/20220062023-03-0101 March 2023
Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006)
ML22322A1092023-02-17017 February 2023
Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
IR 05000382/20230902023-02-0101 February 2023
Final Significance Determination of a White Finding, NOV, and Follow-Up Assessment Letter; NRC Inspection Report 05000382/2023090
ML23032A5062023-02-0101 February 2023
Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022
ML23030A6642023-01-27027 January 2023
Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors
IR 05000382/20220042023-01-26026 January 2023
Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001
ML23024A0822023-01-20020 January 2023
Stephens Insurance, Entergy - 2023 Nuclear Energy Liability Evidence of Financial Protection
ML23018A2202023-01-18018 January 2023
Quality Assurance Program Manual Reduction in Commitment
IR 05000382/20220912023-01-12012 January 2023
Emergency Preparedness Inspection Report 05000382/2022091 and Preliminary White Finding and Apparent Violation
IR 05000382/20220032023-01-0505 January 2023
Revised Integrated Inspection Report 05000382/2022003
ML22342B1402022-12-0202 December 2022
56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors
ML22300A2082022-11-30030 November 2022
Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22332A5292022-11-29029 November 2022
Notification of NRC Initial Operator Licensing Examination 05000382/2023301
IR 05000382/20220132022-11-28028 November 2022
Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013
IR 05000382/20220022022-11-0101 November 2022
Revised Integrated Inspection Report 05000382/2022002
2024-01-31
[Table view]
Category:Safety Evaluation
MONTHYEARML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
ML22322A1092023-02-17017 February 2023
Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML22300A2082022-11-30030 November 2022
Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22194A9012022-07-20020 July 2022
Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2
ML22153A4452022-07-0808 July 2022
Issuance of Amendment No. 267 for Reactor Coolant System Pressure/Temperature Limits and Low Temperature Overpressure Setpoints Applicable for 55 Effective Full Power Years
ML22145A0152022-05-27027 May 2022
Issuance of Amendment No. 266 to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
ML22104A2222022-05-12012 May 2022
Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554
ML22075A1022022-04-29029 April 2022
Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual
ML22083A1242022-04-28028 April 2022
Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2
ML22061A2172022-03-15015 March 2022
Revision of the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule
ML22007A3172022-01-18018 January 2022
1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
ML21313A0082021-12-0808 December 2021
Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML21166A1832021-09-15015 September 2021
Issuance of Amendment No. 261 Regarding Removal and Relocation of Boration System Technical Specifications
ML21131A2432021-08-24024 August 2021
Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System
ML21082A3022021-05-19019 May 2021
Issuance of Amendment No. 259 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML20280A3292020-10-20020 October 2020
Issuance of Amendment No. 258 Regarding Technical Specification 3/4.8.1 Surveillance Requirements
ML20205L5742020-08-25025 August 2020
Issuance of Amendment No. 257 Control Room Air Condition System Technical Specifications
ML20226A2722020-08-18018 August 2020
Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI
ML20022A2582020-01-28028 January 2020
Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control
ML20002A0202020-01-13013 January 2020
Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System
ML19275D4382019-10-24024 October 2019
Redacted - Issuance of Amendment No. 256 for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components
ML19282D8922019-10-15015 October 2019
Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule
ML19254A6032019-09-19019 September 2019
Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1
ML19175A0422019-09-11011 September 2019
Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules
ML19247B1972019-09-0909 September 2019
Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination
ML19232A0252019-08-27027 August 2019
Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities
ML19164A0012019-06-28028 June 2019
Issuance of Amendment No. 254 Regarding Revision of Technical Specification 3/4.7.4, Ultimate Heat Sink,
ML19157A3162019-06-12012 June 2019
Authorization of Proposed Alternative to ASME Code Case N-770-2
ML19022A3372019-02-13013 February 2019
Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload
ML18282A0302018-10-18018 October 2018
Proposed Alternative to ASME Code, Section XI, Regarding Charging Pipe Visual Inspection
ML18180A2982018-07-23023 July 2018
Issuance of Amendment No. 252 Adoption of the Raptor-M3G Code for Neutron Fluence Calculations
ML18128A0672018-06-0808 June 2018
Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4
ML18026B0532018-04-26026 April 2018
Issuance of Amendment No. 251 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control,(Cac No. MF9537; EPID L-2017-LLA-0205)
ML17341A1202017-12-11011 December 2017
Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049)
ML17328A8822017-11-29029 November 2017
Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47)
ML17192A0072017-07-27027 July 2017
Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3
ML17069A1872017-03-22022 March 2017
Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024
ML17045A1482017-03-0303 March 2017
Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML16235A2282016-12-0909 December 2016
Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants
ML16278A0172016-10-19019 October 2016
Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code
ML16251A6202016-09-13013 September 2016
Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097)
ML16159A4192016-07-26026 July 2016
Issuance of Amendment No. 249 Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control
ML16182A2702016-07-0606 July 2016
Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program
ML16126A0332016-06-27027 June 2016
Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c)
ML16096A2692016-06-0606 June 2016
Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1
ML16093A0282016-05-31031 May 2016
Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1
ML16077A2702016-05-10010 May 2016
Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule
ML15289A1432015-11-13013 November 2015
Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times
ML15267A7972015-10-0606 October 2015
Safety Evaluation Regarding the Aging Management Program for Reactor Vessel Internals
ML15139A4832015-08-31031 August 2015
Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power
2023-05-01
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 22, 2017 Site Vice President Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c) ASME CODE SECTION Ill, CODE CASE 1361-1, RELIEF REQUEST W3-ISl-024 (CAC NO. MF7752)
Dear Sir:
By letter dated May 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16144A218), Entergy Operations, Inc. (the licensee), submitted Relief Request (RR) W3-ISl-024, proposing an alternative to the weld requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) at Waterford Steam Electric Station, Unit 3 (Waterford 3).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(z)(1 ), the licensee requested to use the alternative proposed in RR W3-ISl-024 on the basis that the proposed alternative will provide an acceptable level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the subject request and has determined, as set forth in the enclosed safety evaluation, that for RR W3-ISl-024, the proposed alternative will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for this proposed alternative. Therefore, the NRC staff authorizes the use of the proposed alternative for the duration of the operating license for Waterford 3.
If you have any questions, please contact the Project Manager, April Pulvirenti at 301-415-1390 or via e-mail at April.Pulvirenti@nrc.gov.
Sincerely, Robert J. Pascarelli, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c}
ASME CODE SECTION 111 CODE CASE 1361-1. RELIEF REQUEST W3-ISl-024 WATERFORD STEAM ELECTRIC STATION. UNIT 3 ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382
1.0 INTRODUCTION
By letter dated May 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16144A218), Entergy Operations Inc. (the licensee), submitted Relief Request (RR) W3-ISl-024 under the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z)(1 ), from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) weld requirements at the Waterford Steam Electric Station, Unit 3 (Waterford 3). Pursuant to 10 CFR 50.55a(z)(1 ), the licensee proposed an alternative to allow the fillet weld with a maximum diametral clearance of 0.062 inches between the pressurizer heater sheath and sleeve instead of 0.045 inches as specified in ASME Code Section Ill, Code Case 1361-1. The alternative is proposed for the remainder of the Waterford 3 operating license.
2.0 REGULATORY EVALUATION
Pursuant to 10 CFR 50.55a(c)(1 ), reactor coolant pressure boundary components must meet the requirements for Class 1 components of Section Ill of the ASME Code to which the licensee adheres, except as provided in paragraphs (c)(2) through (c)(4) of 10 CFR 50.55a.
Pursuant to 10 CFR 50.55a(c)(3), "Applicable Code Cases and conditions on their use," the licensee applies ASME Code Case 1361-1, "Socket Welds, Section 111," dated April 27, 1967.
This ASME code case is incorporated into the Waterford 3 Updated Final Safety Analysis Report (UFSAR) Section 5.2.1.2, "Applicable Code Cases," and identifies ASME Code Section Ill, Code Case 1361-1, as the applicable ASME Code for part of the original pressurizer assembly.
ASME Code Case 1361-1 was later replaced by ASME Code Case 1361-2, dated March 1, 1979. As stated, in part, in 10 CFR 50.55a(b)(4)(ii):
If an applicant or licensee has previously applied a Code Case and a later version of the Code Case is incorporated by reference in paragraph (a) of this section, the applicant or licensee may continue to apply the previous version of the Code Case as authorized or may apply the later version of the Code Case, including any NRG-specified conditions placed on its use, until it updates its Code of Record for the component being constructed.
Enclosure
In Regulatory Guide (RG) 1.84 "Design, Fabrication, and Materials Code Case Acceptability, ASME Section 111," Revision 36, dated August 2014 (ADAMS Accession No. ML13339A515),
ASME Code Case 1361-2 is endorsed by NRC staff on the condition that the Code Case is applied in connection to Section Ill, paragraph NB-3356, "Fillet Welds." The alternative requested by the licensee is in connection with fillet welds for pressurizer heater sleeves.
Therefore, the licensee meets the conditions to apply ASME Code Case 1361-2, and pursuant to 10 CFR 50.55a(b)(4)(ii), the licensee may also continue to apply ASME Code Case 1361-1.
Pursuant to 10 CFR 50.55a(z), alternatives to the requirements of paragraph (c) of 10 CFR 50.55a may be used when authorized by the Director, Office of Nuclear Reactor Regulation. A proposed alternative must be requested and authorized prior to implementation.
The licensee must demonstrate ( 1) the proposed alternative would provide an acceptable level of quality and safety; or (2) compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The U.S. Nuclear Regulatory Commission (NRC) has approved similar relief requests for the Palo Verde Nuclear Generation Station, Units 1, 2 and 3, on November 19, 2004, (ADAMS Accession No. ML043240213), and for San Onofre Nuclear Generating Station, Units 2 and 3, on February 8, 2006, (ADAMS Accession No. ML060410323).
Based on the above, and subject to the following technical evaluation, the NRC staff finds that the licensee continues to apply ASME Code Case 1361-1, and that regulatory authority exists for the licensee to propose, and NRC to authorize, an alternative to ASME Code Case 1361-1.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Request for Alternative 3.1.1 Components Affected The affected components are 30 Code Class 1 pressurizer heater sleeves, Item Number RC MPZR0001.
3.1.2 Applicable Code Requirements The applicable construction code for the Waterford 3 pressurizer vessel is ASME Code Section Ill, 1971 Edition through Summer 1971 Addenda. The applicable ASME Code is ASME Code Case 1361-1, dated April 27, 1967. ASME Code Case 1361-1 states, in part:
Appurtenances with outside diameter equal to that of 2-inch standard pipe size and less may be constructed using weld joints in accordance with Fig. 1, provided all the following requirements are met:
- 1) The design of the joint shall be such that stresses will not exceed the limits described in NB-3220, N417, and tabulated in Tables 1-1.1 and 1-1.2.
- 2) A fatigue strength reduction factor of not less than 4 shall be used in fatigue analyses of the joints.
- 3) The finished welds shall be examined by a magnetic particle method in accordance with NB-5000 ....
- 4) End closure connections may be made with fillet welds or partial penetration welds provided the conditions ... are met.
Per Figure 1 of Code Case 1361-1, "Weld Connection for Appurtenances 2-inch Pipe Size and Smaller which are Attached to Nozzles," where cMAX = diametral clearance between connecting parts, cMAX =0.045 inches is specified.
3.1.3 Licensee's Proposed Alternative The licensee proposes an alternative to allow a fillet weld with a maximum 0.062-inch diametral clearance between the connecting pressurizer heater sleeves and pressurizer heater sheaths, instead of a diametral clearance of 0.045 inches as specified in ASME Code Case 1361-1. The alternative is proposed to apply to all applicable pressurizer heater shims and sheaths.
3.1.4 Licensee's Basis for Authorization of the Proposed Alternative As described in the licensee's application dated May 19, 2016, the basis for the requirement of a 0.45-inch diametral clearance is not specified in ASME Code Case 1361-1. However, maintaining a relatively small clearance between the parts will ensure that the bending stresses that can be imparted on the fillet weld due to deflection of the parts will not exceed the limits described in NB-3220, "Stress Limits for Other Than Bolts." Therefore, the licensee states that the heater sheath to sleeve fillet weld should be evaluated on the basis of whether the weld complies with the stress and fatigue requirements of ASME Code Case 1361-1. In the application for the proposed alternative, the licensee provided an analysis of the stresses on the fillet weld using the proposed diametral clearance between the parts of 0.062 inches. According to the analysis, the proposed joint configuration complies with ASME Code NB-3220 for allowable primary membrane, primary membrane plus bending, primary plus secondary, and fatigue stresses.
The licensee's justification for the proposed alternative is that although the maximum diametral clearance of 0.62 inches will exceed the 0.45-inch requirement of ASME Code Case 1361-1, the reconfigured weld joint will continue to meet the stress and fatigue strength requirements specified in ASME Code Case 1361-1, and therefore remain acceptable from a stress/fatigue perspective. Thus the alternative would provide an acceptable level of quality and safety, meeting the requirements of 10 CFR 50.55a(z)(1 ).
3.2 NRC Staff's Evaluation The licensee proposed an alternative to allow the fillet weld with a maximum 0.062-inch diametral clearance between connecting parts, instead of 0.045 inches as specified in ASME Code Case 1361-1. This code case was revised to ASME Code Case 1361-2, which was endorsed by the NRC staff in RG 1.84, Revision 36.
The NRC staffs evaluation of the licensee's proposed relief request to increase the diametral clearance between the heater sleeve and heater sheath focused on the new stresses that would be seen by the connecting joints. ASME Code Case 1361-1 contains the following requirements concerning the design of weld joints between appurtenances:
- 1. The design of the joint shall be such that stresses will not exceed the limits described in NB-3220, and tabulated in Tables 1-1.1 and 1-1.2.
- 2. A fatigue strength reduction factor of not less than four shall be used in the fatigue analyses of the joints.
The specific value of diametral clearance that is contained in ASME Code Case 1361-1 is intended to maintain the relatively small clearance between the parts, limiting the amount of bending stresses that can be imparted on the fillet weld due to deflection of the parts. However, the primary assurance of safety is demonstrated by satisfying the ASME Code stress limits.
Therefore, the NRC staff's acceptance of the proposed increase in diametral clearance will be based on whether the stress/fatigue requirements stated above are met.
ASME Section Ill, NB-3220, specifies loading conditions that need to be considered and specifies the stress limits that must be satisfied for these load conditions. The specific stresses to be considered for the sleeve-to-sheath weld are general primary stress, primary membrane-plus-bending stress, and primary-plus-secondary stress. The licensee accounted for the increased diametral clearance by reducing the weld throat area used to calculate the stresses in the finite element model analysis. The NRC staff reviewed the licensee's calculation and concluded that this analysis was satisfactorily performed, and that all resultant stresses were within the acceptance criteria required by NB-3220. Therefore, the staff finds that stress requirements have been satisfied.
ASME Section Ill, NB-3222.4(d), "Components Not Requiring Analysis for Cyclic Operation,"
identifies the requirements for components not requiring fatigue analysis. The licensee has performed evaluation to demonstrate that NB-3222.4(d), conditions (1) through (6), are met and the component is exempt from a fatigue analysis.
The NRC staff reviewed the licensee's evaluation and concluded that all the requirements of NB-3222.4(d)(1) through (6) are met. Therefore, the staff finds that the fillet weld is exempted from a fatigue analysis and the fatigue requirement has been satisfied.
On the basis mentioned above, the proposed weld joint is acceptable from a stress/fatigue perspective. Therefore, the proposed weld joint meets the stress/fatigue requirements of ASME Code Case 1361-1 .
4.0 CONCLUSION
The NRC staff has reviewed the subject request and has concluded, on the basis that the ASME Code stress qualification for the fillet weld integrity has been demonstrated and the component is able to perform its intended function, that the alternative proposed in RR W3-ISl-024 will provide an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for this proposed alternative. Therefore, the NRC staff authorizes the use of the proposed alternative for the duration of the operating license for Waterford 3.
Principal Contributor: K. Hsu Date: March 22, 201 7
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3- REQUEST FOR ALTERNATIVE TO 10 CFR 50.55a(c) ASME CODE SECTION Ill, CODE CASE 1361-1, RELIEF REQUEST W3-ISl-024 (CAC NO. MF7752) DATED MARCH 22, 2017 DISTRIBUTION:
PUBLIC Branch Reading RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4-2 Resource RidsNrrDeEpnb Resource RidsNrrLAPBlechmanResource RidsNrrPMWaterford Resource RidsRgn4MailCenter Resource JBowen, EDO RIV ADAMS A ccess1on No. ML17069A187 *b1y memo dae t d J UIY I 5, 2016 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DE/EMCB/BC(A)* NRR/DORL/LPL4/BC NAME APulvirenti PBlechman YLi RPascarelli DATE 3/16/2017 3/15/2017 7/05/2016 3/22/2017 OFFICIAL RECORD COPY
