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Category:Letter type:CNRO
MONTHYEARCNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00023, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary2020-12-17017 December 2020 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary CNRO-2020-00016, 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)2020-08-12012 August 2020 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) CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary CNRO-2019-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2019-03-28028 March 2019 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2019-00007, Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report2019-03-28028 March 2019 Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report CNRO-2019-00013, Entergy Response to Confirmatory Order EA-17-132/EA-17-1532019-03-21021 March 2019 Entergy Response to Confirmatory Order EA-17-132/EA-17-153 CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 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 CNRO-2018-00051, Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K2018-12-28028 December 2018 Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K CNRO-2018-00039, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J2018-09-27027 September 2018 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J CNRO-2018-00021, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table 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 CNRO-2017-00010, Entergy Operations, Inc. - Decommissioning Funding Status Report2017-03-31031 March 2017 Entergy Operations, Inc. - Decommissioning Funding Status Report CNRO-2017-00007, Nuclear Property Damage Insurance (10 CFR 50.54(w)(3))2017-03-30030 March 2017 Nuclear Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00023, Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities2016-12-0101 December 2016 Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities CNRO-2016-00017, Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual2016-07-19019 July 2016 Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual CNRO-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)2016-06-0202 June 2016 Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated) CNRO-2016-00008, Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2016-03-30030 March 2016 Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00004, Notice Regarding Acquisition of Title to Leased Interest2016-02-10010 February 2016 Notice Regarding Acquisition of Title to Leased Interest CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 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 Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 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 Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 CNRO-2015-00022, Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code2015-11-20020 November 2015 Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code CNRO-2015-00023, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM)2015-11-0606 November 2015 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2015-00020, ISFSI and Waterford 3 Steam Electric Station and ISFSI Re Required Notification of Receipt of All Required Regulatory Approvals of the Proposed Transfer Actions and Documentary Evidence of Required Insurance2015-09-23023 September 2015 ISFSI and Waterford 3 Steam Electric Station and ISFSI Re Required Notification of Receipt of All Required Regulatory Approvals of the Proposed Transfer Actions and Documentary Evidence of Required Insurance CNRO-2015-00018, Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1.2015-08-20020 August 2015 Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 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 CNRO-2015-00012, Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual2015-04-30030 April 2015 Arkansas, Units 1 & 2, Grand Gulf, River Bend, Waterford, Unit 3, Indian Point, Units 1, 2, & 3, Pilgrim, James A. FitzPatrick, Big Rock, Palisades - Submittal of Revision of Quality Assurance Program Manual CNRO-2015-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2015-03-27027 March 2015 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2015-00011, Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 20142015-03-27027 March 2015 Grand Gulf Nuclear Station Unit 1 and Waterford 3 Steam Electric Station Submittal of Decommssioning Funding Status Report for 2014 CNRO-2015-00007, ISFSI, Waterford, Unit 3, and ISFSI, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License Amendments2015-01-30030 January 2015 ISFSI, Waterford, Unit 3, and ISFSI, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License Amendments CNRO-2014-00009, Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations2014-07-24024 July 2014 Response to Request for Additional Information for Review of the Decommissioning Funding Plans for Entergy Operations, Inc., Independent Spent Fuel Storage Installations CNRO-2014-00007, ISFSI, Waterford 3 and ISFSI - Application for Order Approving Transfers of Licenses and Conforming License Amendments2014-06-10010 June 2014 ISFSI, Waterford 3 and ISFSI - Application for Order Approving Transfers of Licenses and Conforming License Amendments CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2014-00004, Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/20142014-04-0303 April 2014 Unit 3, Letter (CNRO-2014-00002/ENOC-14-00010) of Same Subject 03/31/2014 CNRO-2014-00001, Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-0962014-02-26026 February 2014 Completion of Change to the Entergy Quality Assurance Program Manual with Regards of Confirmatory Order EA-11-096 CNRO-2013-00009, Grant Gulf, River Bend, Unit 1 and Waterford 3, Response to Request for Additional Information Regarding 2013 Decommissioning Fund Status Report - Entergy Operations, Inc2013-06-20020 June 2013 Grant Gulf, River Bend, Unit 1 and Waterford 3, Response to Request for Additional Information Regarding 2013 Decommissioning Fund Status Report - Entergy Operations, Inc CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G CNRO-2013-00008, Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-04-16016 April 2013 Arkansas, Units 1, 2 & ISFSI, Grand Gulf, ESP and ISFSI, River Bend, Unit 1 and ISFSI and Waterford 3 and ISFSI, Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2013-00006, Decommissioning Funding Status Report - Entergy Operations, Inc2013-03-29029 March 2013 Decommissioning Funding Status Report - Entergy Operations, Inc CNRO-2013-00004, Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2013-03-25025 March 2013 Entergy Operations, Inc. and Entergy Nuclear Operations, Inc., Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications CNRO-2012-00007, Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc2012-10-15015 October 2012 Grand Gulf Nuclear Station & Waterford 3 Steam Electric Station Status of Decommissioning Funding - Entergy Operations, Inc CNRO-2012-00006, Updated Schedule of Submittal of Future License Renewal Applications for Entergy Plants2012-10-11011 October 2012 Updated Schedule of Submittal of Future License Renewal Applications for Entergy Plants CNRO-2012-00004, Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications2012-05-21021 May 2012 Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012 Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G 2021-10-06
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a Entergy Operations, Inc.
P.. Box 31995 Jackson, MS 39286-1995 CNRO-2002-00002 January 17, 2002 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Entergy Operations, Inc.
Meeting to Discuss Mechanical Nozzle Seal Assembly Design Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 & 50-368 License Nos. DPR-51 & NPF-6 Waterford Steam Electric Station - Unit 3 Docket No. 50-382 License No. NPF-38
REFERENCE:
Letter CNRO-2002-00001 from Entergy Operations, Inc, to the NRC, "Letter of Intent - Proposed Alternatives to ASME Code Requirements," dated January 16, 2002
Dear Sir or Madam:
As discussed in the referenced letter, Entergy Operations, Inc. (Entergy) requested a meeting with the appropriate NRC staff representatives to discuss technical information related to the use of an improved Mechanical Nozzle Seal Assembly (MNSA) on various locations of the Reactor Coolant System (RCS). This meeting is tentatively scheduled for January 31, 2002.
Entergy considers much of the information we will discuss at the meeting to be proprietary and confidential pursuant to 10 CFR 2.790(a)(4) and 10 CFR 9.17(a)(4). As such, Entergy requests the information be withheld from public disclosure. The affidavit supporting this request is provided in Attachment 1. The information to be presented at the meeting is provided in Attachment 2. A redacted version of the information is provided in Attachment 3.
CNRO-2002-00002 Pace 2 of 2 If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756.
This letter contains no commitments.
Sincerely, hn R. Hamilton Manager, Engineering Programs JRH/GHD/baa Attachments:
- 1. Affidavit
- 2. Proprietary Information
- 3. Redacted Information cc: Mr. C. G. Anderson (ANO)
Mr. W. R. Campbell (ECH)
Mr. J. T. Herron (W3)
Mr. J. E. Venable (ECH)
Mr. T. W. Alexion, NRR Project Manager (ANO-2)
Mr. R. L. Bywater, NRC Senior Resident Inspector (ANO)
Mr. T. R. Farnholtz, NRC Senior Resident Inspector (W3)
Mr. R. A. Gramm, Section Chief, NRR Licensing Project Directorate IV Mr. E. W. Merschoff, NRC Regional Administrator, Region IV Mr. N. Kalyanam, NRR Project Manager (W3)
Mr. W. D. Reckley, NRR Project Manager (ANO-1)
CRNO-2002-00002 AFFIDAVIT I, John R. Hamilton, Manager, Engineering Programs, of Entergy Operations, Inc. (Entergy) do hereby affirm and state:
- 1. Entergy is providing information in support of a request to be made to the NRC staff.
The document being provided in Attachment 2 ["Comparison of Mechanical Nozzle Seal Assemblies (MNSA) and a Second Generation MNSA Design (MNSA-2)"]
contains technical information developed by Entergy and Westinghouse. This document constitutes proprietary commercial information that should be held in confidence by the NRC pursuant to 10 CFR 9.17(a)(4) and the policy reflected in 10 CFR 2.790, because:
- i. This information is being held in confidence by Entergy.
ii. This information is of a type that is held in confidence by Entergy, and there is a rational basis for doing so because the information contains commercially viable technical information developed and funded by Entergy.
iii. This information is being transmitted to the NRC in confidence.
iv. This information is not available in public sources and could not be gathered readily from other publicly available information.
- v. Public disclosure of this information would create substantial harm to the competitive position of Entergy by disclosing commercially viable technical information.
- 2. Accordingly, Entergy requests that the designated document be withheld from public disclosure pursuant to 10 CFR 2.790(a)(4) and 10 CFR 9.17(a)(4).
I declare under penalty of perjury that the foregoing is true and correct.
Executed on January 17, 2002 Joh-. Hamilton
CNRO-2002-00002 Page 1 of 8 REDACTED INFORMATION COMPARISON OF MECHANICAL NOZZLE SEAL ASSEMBLIES (MNSA)
WITH THE SECOND GENERATION MNSA DESIGN (MNSA-2)
REDACTED INFORMATION
CNRO-2002-00002 Page 2 of 8 REDACTED INFORMATION COMPARISON OF MNSA AND MNSA-2 DESIGN FEATURES
1.0 BACKGROUND
The Mechanical Nozzle Seal Assembly (MNSA) was designed as a replacement for the partial penetration J-groove welds that attach Alloy 600 nozzles to reactor coolant piping or vessels. MNSA provides a seal against leakage and provides structural restraint for the nozzle even with a 360-degree weld failure. MNSA has been installed on actively leaking nozzles and also as a pre-emptive measure on susceptible nozzles. Its advantage over a welded repair is that it can be installed in much less time than welded repairs on carbon steel vessels. In addition, it does not require drain-down, which can result in significant schedule impact if the leak occurs below the mid-loop elevation or in a pressurizer heater sleeve or instrument nozzle below the refueling water level.
2.0 PURPOSE Entergy has proposed a second generation of the MNSA, hereafter referred to as the MNSA-2, which takes full advantage of previous qualification and design efforts associated with MNSA. This discussion qualitatively highlights the similarities and the differences between previously installed Westinghouse MNSA and MNSA-2. It was prepared as a quality class 3 document.
3.0 COMPARISON Both MNSA and MNSA-2 use the same materials of construction and the same seal material. They are both attached with a similar four-bolt pattern. The seal is loaded by tensioning bolts or studs. MNSA-2 uses the same applied torque (or less), than MNSA.
3.1 SEAL POSITIONING / ENCAPSULATION Both MNSA and MNSA-2 use nuclear grade Grafoil as the sealing material. The seals are procured to the same specification and similar drawings that control the as-received density and configuration. The seals are approximately the same size and are weighed to verify that the density is within a specified range as part of the final inspection. During MNSA assembly, several split components are positioned around the base of the nozzle to create a cavity for the seal. As MNSA is assembled by torquing the bolts, the seal is compressed into a predetermined volume that is smaller than the as-processed seal volume. The MNSA components eventually reach a "metal-to-metal" or hard stop condition. At that point, the compression stress within the seal is significantly higher than reactor coolant pressure and blocks coolant from escaping. In the MNSA design, the seal is applied directly to the REDACTED INFORMATION
CNRO-2002-00002 Page 3 of 8 REDACTED INFORMATION The encapsulating MNSA components must be shaped to fit the particular surface profile adjacent to the nozzle. In the case of heater sleeves, where there are many different surface profiles on the bottom of the pressurizer, a special seal together with customized MNSA machined components are reauired for each location.
The original MNSA design requires that the surface of the pipe or vessel where the seal rdcirlim ha fr== nf ei1injfir-nt rfnAr l1nimnrfwdeinn 3.2 SEAL LOADING As described, the original MNSA components reach a metal-to-metal hard stop during assembly. Each design that departs significantly from a previous one is tested with thE ssecific sloDe aeometrv. etc. to verify sealina intearitv.
3.3 LEAK-OFF DIVERSION The original MNSA has been approved previously by the NRC for a two-cycle period of use based on the NRC's evaluation of potential corrosion effects. The evaluation considered:
REDACTED INFORMATION
CNRO-2002-00002 Page 4 of 8 REDACTED INFORMATION
- 1. Corrosion/erosion of the carbon steel holes in the pipe or pressurizer - judged to be insignificant
- 2. Boric acid corrosion of the materials of construction for the MNSA - also found to be acceptable based on CEOG corrosion testing
- 3. Galvanic corrosion - there is no history of problems in similar applications with Grafoil contacting carbon steel
- 4. Potential for SCC failures of the A286 bolts - also found acceptable With regard to the A286 bolts, the evaluation concluded that the bolts could be exposed to boric acid deposits or slurries, if the MNSA leaks. This evaluation was appropriate because the design did not include provisions for capturing or diverting seal leakage away from the bolting materials. Even so, at the stress levels that exist in the bolts, including a stress concentration factor of four, the bolts will function satisfactorily.
REDACTED INFORMATION
CNRO-2002-00002 Page 5 of 8 REDACTED INFORMATION 3.4 Qualification of MNSA and MNSA-2 MNSA was originally qualified by a series of tests and analyses. With each specific new application, a Design Specification and a Design Report were prepared. For MNSA-2 applications on Entergy pressurizers, the same approach will be utilized.
REDACTED INFORMATION
CNRO-2002-00002 Page 6 of 8 REDACTED INFORMATION REDACTED INFORMATION
CNRO-2002-00002 Page 7 of 8 REDACTED INFORMATION REDACTED INFORMATION
CNRO-2002-00002 Attachment 3 Page 8 of 8 REDACTED INFORMATION 4.0 ACCEPTABILITY of MNSA-2 AS AN ALTERNATE DESIGN In September 2001, ASME Code Subcommittee III voted affirmatively in response to Inquiry NI01-07, which inquired if the requirements for welded attachment of nozzles (NB-3337.1) can be waived provided the basic stress limits of NB-3200 (Design by Analysis) are met in an alternate design such as MNSA. MNSA and MNSA-2 are both acceptable alternatives designed in accordance with ASME NB-3200, the only difference being that MNSA-2 incorporates improvements over MNSA. These added features are designed to extend its operating life, in the form of a live-loaded seal and controlled leak-off diversion that reduces exposure of the carbon steel pipe or vessel, as well as the MNSA-2 fasteners, to RCS leakage in an oxygenated environment.
5.0 CONCLUSION
The knowledge acquired in the design, development, and deployment of the original MNSA has been applied to MNSA-2 and is being supplemented where required to validate the imnmvPmPnfkq All other process steps such as detailed design, manufacturing, installation, and QA / QC activities applicable to MNSA also control the deployment of MNSA-2.
REDACTED INFORMATION