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| | number = ML060950220 | | | number = ML060950220 |
| | issue date = 03/22/2006 | | | issue date = 03/22/2006 |
| | title = 2006/03/22-GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) | | | title = GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) |
| | author name = Morgan M | | | author name = Morgan M |
| | author affiliation = NRC/NRR/ADRO/DLR/RLRC | | | author affiliation = NRC/NRR/ADRO/DLR/RLRC |
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| =Text= | | =Text= |
| {{#Wiki_filter:X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 1 AUDIT W ORKSHEET GALL R EPORT AMP PLANT: ______________________________ | | {{#Wiki_filter:AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________ |
| LRA AMP: __________________________ | | LRA AMP: __________________________ REVIEWER: ______________________ |
| R EVIEWER: ______________________
| | GALL AMP: X.S1, Concrete Containment Tendon Prestress DATE: __________________________ |
| GALL AMP: X.S1, Concrete Containment Tendon Prestress DATE: __________________________ | | Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. In order to ensure the adequacy of prestressing forces in Consistent with GALL AMP: Yes No Description prestressed concrete containment tendons during the extended Document(s) used to confirm Criteria: |
| Program Element Auditable GALL Criteria Documentation of Audit Finding Program Description A. In order to ensure the adequacy of prestressing forces in prestressed concrete containment tendons during the extended period of operation, an applicant shall develop an aging management program (AMP) under 10 CFR 54.21(c)(1)(iii). The AMP consists of an assessment of the results of inspections performed in accordance with the requirements of Subsection IWL of the ASME Section XI Code, as supplemented by the requirements of 10 CFR 50.55a(b)(2)(ix) or (viii) in the later amendment of the regulation. The assessment related to the adequacy of the prestressing force will consist of the establishment of (1) acceptance criteria and (2) trend lines. Consistent with GALL AMP: | | period of operation, an applicant shall develop an aging management program (AMP) under 10 CFR 54.21(c)(1)(iii). |
| Yes No Document(s) used to confirm Criteria:
| | The AMP consists of an assessment of the results of inspections performed in accordance with the requirements of Comment: |
| Comment: " B. The acceptance criteria will normally consist of predicted lower limit (PLL) and the minimum required prestressing force, also called minimum required value (MRV). NRC Regulatory Guide 1.35.1 provides guidance for calculating PLL and MRV. Consistent with GALL AMP:
| | Subsection IWL of the ASME Section XI Code, as supplemented by the requirements of 10 CFR 50.55a(b)(2)(ix) or (viii) in the later amendment of the regulation. The assessment related to the adequacy of the prestressing force will consist of the establishment of (1) acceptance criteria and (2) trend lines. |
| Yes No Document(s) used to confirm Criteria: | | B. The acceptance criteria will normally consist of predicted Consistent with GALL AMP: Yes No lower limit (PLL) and the minimum required prestressing force, Document(s) used to confirm Criteria: |
| | also called minimum required value (MRV). NRC Regulatory Guide 1.35.1 provides guidance for calculating PLL and MRV. |
| | Comment: |
| | C. The trend line represents the trend of prestressing forces Consistent with GALL AMP: Yes No based on the actual measured forces. NRC Information Notice Document(s) used to confirm Criteria: |
| | IN 99-10 provides guidance for constructing the trend line. The goal is to keep the trend line above the PLL because, as a result of any inspection performed in accordance with ASME Section XI, Subsection IWL, if the trend line crosses the PLL, the Comment: |
| | X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 1 |
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| Comment: " C. The trend line represents the trend of prestressing forces based on the actual measured forces. NRC Information Notice IN 99-10 provides guidance for constructing the trend line. The goal is to keep the trend line above the PLL because, as a result of any inspection performed in accordance with ASME Section XI, Subsection IWL, if the trend line crosses the PLL, the Consistent with GALL AMP:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element existing prestress in the containment tendon could go below the MRV soon after the inspection and would not meet the requirements of 10 CFR 50.55a(b)(2)(ix)(B) or 10 CFR 50.55a(b)(2)(viii)(B). |
| Yes No Document(s) used to confirm Criteria: | | D. As evaluated below, this time limited aging analysis (TLAA) is Consistent with GALL AMP: Yes No an acceptable option to manage containment tendon prestress Document(s) used to confirm Criteria: |
| | force, except for the program element/attribute regarding operating experience. Thus, it is recommended that the staff should further evaluate an applicant's operating experience related to the containment tendon prestress force. The AMP Comment: |
| | related to the adequacy of prestressing force for containments with grouted tendons will be reviewed on a case-by-case basis. |
| | : 1. Scope of A. The program addresses the assessment of containment Consistent with GALL AMP: Yes No Program tendon prestressing force when an applicant chooses to perform Document(s) used to confirm Criteria: |
| | the containment prestress force TLAA using 10 CFR 54.21(c)(1)(iii). |
| | Comment |
| | : 2. Preventive A. Maintaining the prestress above the MRV, as described Consistent with GALL AMP: Yes No Actions under program description above, will ensure that the structural Document(s) used to confirm Criteria: |
| | and functional adequacy of the containment are maintained. |
| | Comment: |
| | : 3. Parameters A. The parameters to be monitored are the containment tendon Consistent with GALL AMP: Yes No Monitored/ prestressing forces in accordance with requirements specified in Document(s) used to confirm Criteria: |
| | Inspected Subsection IWL of Section XI of the ASME Code, as incorporated by reference in 10 CFR 50.55a. |
| | Comment: |
| | X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 2 |
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| | Program Auditable GALL Criteria Documentation of Audit Finding Element |
| | : 4. Detection of A. The loss of containment tendon prestressing forces is Consistent with GALL AMP: Yes No Aging Effects detected by the program. Document(s) used to confirm Criteria: |
| | Comment: |
| | : 5. Monitoring A. The estimated and measured prestressing forces are plotted Consistent with GALL AMP: Yes No and Trending against time and the PLL, MRV, and trending lines developed Document(s) used to confirm Criteria: |
| | for the period of extended operation. |
| | Comment: |
| | : 6. Acceptance A. The prestressing force trend lines indicate that existing Consistent with GALL AMP: Yes No Criteria prestressing forces in the containment tendon would not be Document(s) used to confirm Criteria: |
| | below the MRVs prior to the next scheduled inspection, as required by 10 CFR 50.55a(b)(2)(ix)(B) or 10 CFR 50.55a(b)(2)(viii)(B). |
| | Comment: |
| | : 7. Corrective A. If acceptance criteria are not met, then either systematic Consistent with GALL AMP: Yes No Actions retensioning of tendons or a reanalysis of the containment is Document(s) used to confirm Criteria: |
| | warranted to ensure the design adequacy of the containment. |
| | As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the corrective actions. Comment: |
| | : 8. A. As discussed in the appendix to this report, the staff finds the Consistent with GALL AMP: Yes No Confirmation requirements of 10 CFR Part 50, Appendix B, acceptable to Document(s) used to confirm Criteria: |
| | Process address the confirmation process. |
| Comment: | | Comment: |
| X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 2 Program Element Auditable GALL Criteria Documentation of Audit Finding existing prestress in the containment tendon could go below the MRV soon after the inspection and would not meet the requirements of 10 CFR 50.55a(b)(2)(ix)(B) or 10 CFR 50.55a(b)(2)(viii)(B).
| | : 9. A. As discussed in the appendix to this report, the staff finds the Consistent with GALL AMP: Yes No X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 3 |
| " D. As evaluated below, this time limited aging analysis (TLAA) is an acceptable option to manage containment tendon prestress force, except for the program element/attribute regarding operating experience. Thus, it is recommended that the staff should further evaluate an applicant's operating experience related to the containment tendon prestress force. The AMP related to the adequacy of prestressing force for containments with grouted tendons will be reviewed on a case-by-case basis. Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
| | |
| Comment: 1. Scope of Program A. The program addresses the assessment of containment tendon prestressing force when an applicant chooses to perform the containment prestress force TLAA using 10 CFR 54.21(c)(1)(iii). Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria: | |
| | |
| Comment 2. Preventive Actions A. Maintaining the prestress above the MRV, as described under program description above, will ensure that the structural and functional adequacy of the containment are maintained. Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
| | |
| Comment: 3. Parameters Monitored/ Inspected A. The parameters to be monitored are the containment tendon prestressing forces in accordance with requirements specified in Subsection IWL of Section XI of the ASME Code, as incorporated by reference in 10 CFR 50.55a. Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
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| |
|
| | Program Auditable GALL Criteria Documentation of Audit Finding Element Administrative requirements of 10 CFR Part 50, Appendix B, acceptable to Document(s) used to confirm Criteria: |
| | Controls address the administrative controls. |
| Comment: | | Comment: |
| X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 3 Program Element Auditable GALL Criteria Documentation of Audit Finding 4. Detection of Aging Effects A. The loss of containment tendon prestressing forces is detected by the program. Consistent with GALL AMP:
| | : 10. Operating A. The program incorporates the relevant operating experience Consistent with GALL AMP: Yes No Experience that has occurred at the applicant's plant as well as at other Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | plants. The applicable portions of the experience with prestressing systems described in NRC Information Notice 99-10 could be useful for the purpose. However, tendon operating experience could be different at plants with prestressed Comment: |
| Comment: 5. Monitoring and Trending A. The estimated and measured prestressing forces are plotted against time and the PLL, MRV, and trending lines developed for the period of extended operation. Consistent with GALL AMP:
| | concrete containments. The difference could be due to the prestressing system design (e.g., button-headed, wedge, or swaged anchorages), environment, and type of reactor (i.e., |
| Yes No Document(s) used to confirm Criteria:
| | PWR and BWR). Thus, the applicant's X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 4 |
| | |
| Comment: 6. Acceptance Criteria A. The prestressing force trend lines indicate that existing prestressing forces in the containment tendon would not be below the MRVs prior to the next scheduled inspection, as required by 10 CFR 50.55a(b)(2)(ix)(B) or 10 CFR 50.55a(b)(2)(viii)(B). Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
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| Comment: 7. Corrective Actions A. If acceptance criteria are not met, then either systematic retensioning of tendons or a reanalysis of the containment is warranted to ensure the design adequacy of the containment. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the corrective actions. Consistent with GALL AMP:
| | EXCEPTIONS Item Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| Yes No Document(s) used to confirm Criteria:
| | 1. |
| | 2. |
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| |
|
| Comment: 8.
| | ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| Confirmation Process A. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the confirmation process. Consistent with GALL AMP:
| | 1. |
| Yes No Document(s) used to confirm Criteria:
| | 2. |
|
| |
|
| Comment: 9. A. As discussed in the appendix to this report, the staff finds the Consistent with GALL AMP:
| | DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1. |
| Yes No X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 4 Program Element Auditable GALL Criteria Documentation of Audit Finding Administrative Controls requirements of 10 CFR Part 50, Appendix B, acceptable to address the administrative controls.
| | 2. |
| Document(s) used to confirm Criteria:
| | 3. |
| Comment: 10. Operating Experience A. The program incorporates the relevant operating experience that has occurred at the applicant's plant as well as at other plants. The applicable portions of the experience with prestressing systems described in NRC Information Notice 99-10 could be useful for the purpose. However, tendon operating experience could be different at plants with prestressed concrete containments. The difference could be due to the prestressing system design (e.g., button-headed, wedge, or swaged anchorages), environment, and type of reactor (i.e., PWR and BWR). Thus, the applicant's Consistent with GALL AMP:
| | 4. |
| Yes No Document(s) used to confirm Criteria:
| | X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 5}} |
| | |
| Comment:
| |
| X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 5 EXCEPTIONS Item Number Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| |
| ENHANCEMENTS Item Number Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| |
| DOCUMENT REVIEWED D URING A UDIT Document Number Identifier (number) Title Revision and/or Date 1. 2. 3. 4. -.}} | |
Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: BVY 06-009, 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E, BVY 06-076, 2006/08/10-Vermont Yankee - License Renewal Application, Amendment 8, BVY 06-079, 2006/08/22-Vermont Yankee License Renewal Application, Amendment 11, BVY 06-083, 2006/09/05-Vermont Yankee License Renewal Application, Amendment 12, BVY 06-095, E-mail: (PA-LR) Copy of SAMA Response, BVY 06-096, 2006/10/20-Vermont Yankee - License Renewal Application, Amendment No. 17, BVY 06-097, 2006/10/31-Vermont Yankee License Renewal Application, Amendment 19, BVY 06-098, E-mail: (PA-LR) Copy of Vhs RAI Response, BVY 07-003, Email: (PA-LR) Vermont Yankee Nuclear Power Station License Renewal Commitment List, Rev. 5, BVY 07-009, License Renewal Application, Amendment 24, BVY 07-018, License Renewal Application, Amendment 26, BVY 07-034, License Renewal Application Annual Update, BVY 07-035, (PA-LR) Bvy 07-035 VY Lr SER Comments, BVY 07-047, License Renewal Application, Amendment 27, Submitted on January 25, 2006, BVY 07-058, License Renewal Application, Amendment 29, BVY 07-062, License Renewal Application, Amendment 30, BVY 07-066, License Renewal Application, Amendment 31, BVY 08-016, (PA-LR) Emailing Bvy 08-016 Final SER Review Comments, BVY 10-069, License Renewal Application Annual Update Information, ML060950195, ML060950215, ML060950218, ML060950220, ML060950224, ML060950235, ML060950250, ML060950258, ML060950262, ML060950269, ML060950271, ML060950277, ML060950279, ML060950284, ML060950290, ML060950301, ML060950311, ML060950323, ML060950328, ML060950331, ML060950347, ML060950351, ML060950356, ML060950364, ML060950370, ML060950372, ML060950375, ML060950540, ML060950549, ML060950559, ML060950567... further results
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MONTHYEARML0629203681987-12-31031 December 1987 VY Annual Ecological Studies of the CT River Report 16-final.pdf Project stage: Other ML0629203651989-12-31031 December 1989 VY Annual Ecological Reports from the 1980's (1989) Project stage: Other ML0609503511998-02-28028 February 1998 GALL AMP: XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) Project stage: Other BVY 06-009, 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E2006-01-25025 January 2006 2006/01/25-Vermont Yankee Nuclear Power Station Applicant'S Environmental Report Operating License Renewal Stage, Appendix E Project stage: Other ML0609505792006-03-22022 March 2006 GALL AMP: XI.M24, Compressed Air Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506202006-03-22022 March 2006 GALL AMP: XI.M31, Reactor Vessel Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505962006-03-22022 March 2006 GALL AMP: XI.M27, Fire Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502792006-03-22022 March 2006 GALL AMP: XI.M3, Reactor Head Closure Studs (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609506292006-03-22022 March 2006 GALL AMP: XI.M33, Selective Leaching of Materials (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506372006-03-22022 March 2006 GALL AMP: XI.M36, External Surfaces Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502842006-03-22022 March 2006 GALL AMP: XI.M4, BWR Vessel Id Attachment Welds (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502202006-03-22022 March 2006 GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001472006-03-22022 March 2006 GALL AMP: XI.S8, Protective Coating Monitoring and Maintenance Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001342006-03-22022 March 2006 GALL AMP: XI.S5, Masonry Wall Progam (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502182006-03-22022 March 2006 GALL AMP: X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609505592006-03-22022 March 2006 GALL AMP: XI.M20, Open-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503472006-03-22022 March 2006 GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors Project stage: Other ML0609505402006-03-22022 March 2006 GALL AMP: XI.M18, Bolting Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505672006-03-22022 March 2006 GALL AMP: XI.M21, Closed-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001012006-03-22022 March 2006 GALL AMP: XI.S2, ASME Section XI, Subsection Iwl (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505732006-03-22022 March 2006 GALL AMP: XI.M23, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506102006-03-22022 March 2006 GALL AMP: XI.M29, Aboveground Steel Tanks (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502902006-03-22022 March 2006 GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP) Project stage: Other ML0610001382006-03-22022 March 2006 GALL AMP: XI.S6, Structures Monitoring Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001262006-03-22022 March 2006 GALL AMP: XI.S4, 10 CFR 50, Appendix J (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502242006-03-22022 March 2006 GALL AMP: XI.E1, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506062006-03-22022 March 2006 GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503752006-03-22022 March 2006 GALL AMP: XI.M17, Flow-Accelerated Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000782006-03-22022 March 2006 GALL AMP: XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505702006-03-22022 March 2006 GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503722006-03-22022 March 2006 GALL AMP: XI.M16, PWR Vessel Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503642006-03-22022 March 2006 GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502772006-03-22022 March 2006 GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609506242006-03-22022 March 2006 GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503112006-03-22022 March 2006 GALL AMP: XI.M7, BWR Stress Corrosion Cracking (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502352006-03-22022 March 2006 GALL AMP: XI.E2, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506342006-03-22022 March 2006 GALL AMP: XI.M35, One-Time Inspection of ASME Code Class 1 Small Bore Piping (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502502006-03-22022 March 2006 GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001432006-03-22022 March 2006 GALL AMP: XI.S7, Rg 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505872006-03-22022 March 2006 GALL AMP: XI.M26, Fire Protection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609501952006-03-22022 March 2006 GALL AMP: Plant-Specific (Audit Worksheet - GALL Report AMP) Project stage: Other ML0609503702006-03-22022 March 2006 GALL AMP: XI.M15, Neutron Noise Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503012006-03-22022 March 2006 GALL AMP: XI.M6, BWR Control Rod Drive Return Line Nozzle (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503282006-03-22022 March 2006 GALL AMP: XI.M9, BWR Vessels Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000962006-03-22022 March 2006 GALL AMP: XI.S1, ASME Section XI, Subsection IWE (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502692006-03-22022 March 2006 GALL AMP: XI.E6, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609502622006-03-22022 March 2006 GALL AMP: XI.E5, Fuse Holder (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503312006-03-22022 March 2006 GALL AMP: XI.M10, Boric Acid Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other 1998-02-28
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Category:Report
MONTHYEARML21075A1772021-03-15015 March 2021 Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request BVY 20-026, Defueled Safety Analysis Report, Revision 22020-09-23023 September 2020 Defueled Safety Analysis Report, Revision 2 BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019 ML19198A2522019-06-20020 June 2019 Alternate Disposal Request - Rail Shipments (License DPR-28, Docket No. 50-271) ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML15266A4302015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 24, Flow Diagram Instrument Air System. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M. ML15266A4452015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 2 ML15266A4442015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 1 ML15266A4402015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 8 ML15266A4362015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 7 ML15266A4352015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 6 ML15266A4342015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 5 ML15266A4332015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 4 ML15266A4322015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 31, Flow Diagram Instrument Air System. Sheet 3 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 22015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2 ML15266A4292015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 37, Flow Diagram Instrument Air System. Sheet 1 ML15266A4282015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 100, Flow Diagram Service Water System. Sheet 2 ML15266A4272015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 92, Flow Diagram Service Water System. Sheet 1 ML15266A4262015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191152, Rev. 14, General Arrangement Radwaste Building Section. ML15266A4252015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191151, Rev 19, General Arrangement Radwaste Building Plans. ML15266A4242015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191150, Rev. 20, General Arrangement Reactor Building Section. ML15266A4232015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191149, Rev. 27, General Arrangement Reactor Building Plans Sheet 2. ML15266A4222015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191148, Rev. 23, General Arrangement Reactor Building Plans Sheet 1. ML15266A2722015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report - List of Effective Pages BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 52015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5 ML15266A2832015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, DSAR Drawing List BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R. ML15266A2712015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, DSAR Changes ML15266A2732015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, UFSAR to DSAR Conversion Matrix ML15267A6092015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 3 BVY 15-046, Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf.2015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf. ML15267A6612015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M. ML15267A6592015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191592, Control Room Building Fl Plan El 248.50 & Fdn Plan-R, Sheet 1 ML15267A6562015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R. ML15267A6542015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R. ML15267A6512015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191463, Circulating Water System Discharge Structure Reinf, Sheet 2 ML15267A6492015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1 ML15267A6472015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191453, Circulating Water System Intake Structure-M, Sheet 3 ML15267A6452015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191452, Circulating Water System Intake Structure-V, Sheet 2 ML15267A6412015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191451, Circulating Water System Intake Structure-M, Sheet 1 ML15267A6112015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5 ML15267A6102015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 120/240V Vital AC and Instrument AC One Line Diagram, Sheet 4 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 12015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1 ML15267A6082015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 2 ML15267A6072015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1 ML15267A6062015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2 ML15267A6052015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 30, 480V Aux. One Line Diagram Swgr BUS-9, MCC-9A, 9C. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 12015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R. 2021-03-15
[Table view] Category:Miscellaneous
MONTHYEARML21075A1772021-03-15015 March 2021 Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019 ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum BVY 15-049, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask BVY 15-018, Transmittal of Biennial 10 CFR 50.59 Report2015-03-0202 March 2015 Transmittal of Biennial 10 CFR 50.59 Report BVY 14-085, Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2014-12-19019 December 2014 Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb) BVY 14-011, Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ...2014-02-25025 February 2014 Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ... BVY 13-090, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2013-10-0202 October 2013 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask BVY 12-081, Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-21021 November 2012 Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML12160A3732012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daichii Nuclear Plant Accident TAC No. ME8747) ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants BVY 07-079, Update of Aging Management Program Audit Q&A Database2007-11-14014 November 2007 Update of Aging Management Program Audit Q&A Database BVY 07-004, Emergency Response Data System (ERDS) Data Point Library Update2007-06-21021 June 2007 Emergency Response Data System (ERDS) Data Point Library Update ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007 Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006 L-87-005, Various CRS 08/09/2005 to 02/08/20072007-02-0808 February 2007 Various CRS 08/09/2005 to 02/08/2007 ML0706703802007-02-0101 February 2007 NDE Reports 07-001 Thru 07-008 ML0701705912007-01-0909 January 2007 VYNPS - SEIS Web Reference - Us Census Glossary ML0701701982006-12-15015 December 2006 VYNPS - SEIS Web Reference - Connecticut River Migratory Fish Counts 1967-2005 ML0629204232006-10-0303 October 2006 (E-Mail) Cooling Tower Report for VY ML0629203422006-09-18018 September 2006 (E-Mail) Air Emissions Inventory Report for 2005 and MSDS for Nalco H-550 ENOC-06-00018, Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 20062006-08-29029 August 2006 Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 2006 BVY 06-068, Cycle 25 Startup Test Report Following Power Ascension and Testing2006-08-0101 August 2006 Cycle 25 Startup Test Report Following Power Ascension and Testing CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006 Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee ML0618803852006-05-22022 May 2006 Windham Regional Plan Draft, May 22, 2006 ML0704404852006-05-12012 May 2006 AMRM-16, Revision 0, Aging Management Review of the Instrument Air System. ML0704404832006-05-12012 May 2006 AMRM-15, Revision 0, Aging Management Review of the Fuel Oil System. ML0704404782006-05-12012 May 2006 AMRM-15, Aging Management Review of the Fuel Oil System ML0704404742006-05-12012 May 2006 AMRM-12, Aging Management Review of the Reactor Building Closed Cooling Water System ML0704404862006-05-11011 May 2006 AMRM-30, Rev. 01, Aging Management Review of Ns Systems Affecting Safety Systems BVY 06-033, Cycle 24 10 CFR 50.59 Report2006-04-24024 April 2006 Cycle 24 10 CFR 50.59 Report BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan2006-03-26026 March 2006 Revision 1 to Steam Dryer Monitoring Plan ML0609503562006-03-22022 March 2006 GALL AMP: XI.M13, Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) ML0609503642006-03-22022 March 2006 GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) ML0609502712006-03-22022 March 2006 GALL AMP: XI.M1, ASME Section XI Inservice Inspection, Subsections Iwb, Iwc, and Iwd (Audit Worksheet, GALL Report AMP) ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP) ML0609502772006-03-22022 March 2006 GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP) ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP) ML0609505702006-03-22022 March 2006 GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP) ML0609502202006-03-22022 March 2006 GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) ML0609502502006-03-22022 March 2006 GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) ML0609502582006-03-22022 March 2006 GALL AMP: XI.E4, Metal Enclosed Bus (Audit Worksheet GALL Report AMP) ML0609502622006-03-22022 March 2006 GALL AMP: XI.E5, Fuse Holder (Audit Worksheet GALL Report AMP) ML0609503472006-03-22022 March 2006 GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors ML0609506062006-03-22022 March 2006 GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP) ML0609506242006-03-22022 March 2006 GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP) ML0609502902006-03-22022 March 2006 GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP) ML0610000902006-03-22022 March 2006 GALL AMP: XI.M39, Lubricating Oil Analysis Program (Audit Worksheet GALL Report AMP) ML0609503312006-03-22022 March 2006 GALL AMP: XI.M10, Boric Acid Corrosion (Audit Worksheet GALL Report AMP) 2021-03-15
[Table view] |
Text
AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________
LRA AMP: __________________________ REVIEWER: ______________________
GALL AMP: X.S1, Concrete Containment Tendon Prestress DATE: __________________________
Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. In order to ensure the adequacy of prestressing forces in Consistent with GALL AMP: Yes No Description prestressed concrete containment tendons during the extended Document(s) used to confirm Criteria:
period of operation, an applicant shall develop an aging management program (AMP) under 10 CFR 54.21(c)(1)(iii).
The AMP consists of an assessment of the results of inspections performed in accordance with the requirements of Comment:
Subsection IWL of the ASME Section XI Code, as supplemented by the requirements of 10 CFR 50.55a(b)(2)(ix) or (viii) in the later amendment of the regulation. The assessment related to the adequacy of the prestressing force will consist of the establishment of (1) acceptance criteria and (2) trend lines.
B. The acceptance criteria will normally consist of predicted Consistent with GALL AMP: Yes No lower limit (PLL) and the minimum required prestressing force, Document(s) used to confirm Criteria:
also called minimum required value (MRV). NRC Regulatory Guide 1.35.1 provides guidance for calculating PLL and MRV.
Comment:
C. The trend line represents the trend of prestressing forces Consistent with GALL AMP: Yes No based on the actual measured forces. NRC Information Notice Document(s) used to confirm Criteria:
IN 99-10 provides guidance for constructing the trend line. The goal is to keep the trend line above the PLL because, as a result of any inspection performed in accordance with ASME Section XI, Subsection IWL, if the trend line crosses the PLL, the Comment:
X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 1
Program Auditable GALL Criteria Documentation of Audit Finding Element existing prestress in the containment tendon could go below the MRV soon after the inspection and would not meet the requirements of 10 CFR 50.55a(b)(2)(ix)(B) or 10 CFR 50.55a(b)(2)(viii)(B).
D. As evaluated below, this time limited aging analysis (TLAA) is Consistent with GALL AMP: Yes No an acceptable option to manage containment tendon prestress Document(s) used to confirm Criteria:
force, except for the program element/attribute regarding operating experience. Thus, it is recommended that the staff should further evaluate an applicant's operating experience related to the containment tendon prestress force. The AMP Comment:
related to the adequacy of prestressing force for containments with grouted tendons will be reviewed on a case-by-case basis.
- 1. Scope of A. The program addresses the assessment of containment Consistent with GALL AMP: Yes No Program tendon prestressing force when an applicant chooses to perform Document(s) used to confirm Criteria:
the containment prestress force TLAA using 10 CFR 54.21(c)(1)(iii).
Comment
- 2. Preventive A. Maintaining the prestress above the MRV, as described Consistent with GALL AMP: Yes No Actions under program description above, will ensure that the structural Document(s) used to confirm Criteria:
and functional adequacy of the containment are maintained.
Comment:
- 3. Parameters A. The parameters to be monitored are the containment tendon Consistent with GALL AMP: Yes No Monitored/ prestressing forces in accordance with requirements specified in Document(s) used to confirm Criteria:
Inspected Subsection IWL of Section XI of the ASME Code, as incorporated by reference in 10 CFR 50.55a.
Comment:
X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 2
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 4. Detection of A. The loss of containment tendon prestressing forces is Consistent with GALL AMP: Yes No Aging Effects detected by the program. Document(s) used to confirm Criteria:
Comment:
- 5. Monitoring A. The estimated and measured prestressing forces are plotted Consistent with GALL AMP: Yes No and Trending against time and the PLL, MRV, and trending lines developed Document(s) used to confirm Criteria:
for the period of extended operation.
Comment:
- 6. Acceptance A. The prestressing force trend lines indicate that existing Consistent with GALL AMP: Yes No Criteria prestressing forces in the containment tendon would not be Document(s) used to confirm Criteria:
below the MRVs prior to the next scheduled inspection, as required by 10 CFR 50.55a(b)(2)(ix)(B) or 10 CFR 50.55a(b)(2)(viii)(B).
Comment:
- 7. Corrective A. If acceptance criteria are not met, then either systematic Consistent with GALL AMP: Yes No Actions retensioning of tendons or a reanalysis of the containment is Document(s) used to confirm Criteria:
warranted to ensure the design adequacy of the containment.
As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the corrective actions. Comment:
- 8. A. As discussed in the appendix to this report, the staff finds the Consistent with GALL AMP: Yes No Confirmation requirements of 10 CFR Part 50, Appendix B, acceptable to Document(s) used to confirm Criteria:
Process address the confirmation process.
Comment:
- 9. A. As discussed in the appendix to this report, the staff finds the Consistent with GALL AMP: Yes No X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 3
Program Auditable GALL Criteria Documentation of Audit Finding Element Administrative requirements of 10 CFR Part 50, Appendix B, acceptable to Document(s) used to confirm Criteria:
Controls address the administrative controls.
Comment:
- 10. Operating A. The program incorporates the relevant operating experience Consistent with GALL AMP: Yes No Experience that has occurred at the applicant's plant as well as at other Document(s) used to confirm Criteria:
plants. The applicable portions of the experience with prestressing systems described in NRC Information Notice 99-10 could be useful for the purpose. However, tendon operating experience could be different at plants with prestressed Comment:
concrete containments. The difference could be due to the prestressing system design (e.g., button-headed, wedge, or swaged anchorages), environment, and type of reactor (i.e.,
PWR and BWR). Thus, the applicant's X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 4
EXCEPTIONS Item Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed Number (Identifier, Para.# and/or Page #)
1.
2.
ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #)
1.
2.
DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1.
2.
3.
4.
X.M1 Metal Fatigue of Reactor Coolant Pressure Boundary 5