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| | number = ML060950351 | | | number = ML060950351 |
| | issue date = 02/28/1998 | | | issue date = 02/28/1998 |
| | title = 2006/03/22-GALL AMP: XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) | | | title = GALL AMP: XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) |
| | author name = Morgan M J | | | author name = Morgan M |
| | author affiliation = NRC/NRR/ADRO/DLR/RLRC | | | author affiliation = NRC/NRR/ADRO/DLR/RLRC |
| | addressee name = | | | addressee name = |
| Line 9: |
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| | docket = 05000271 | | | docket = 05000271 |
| | license number = | | | license number = |
| | contact person = morgan M J NRR/NRC/DLR/RLRC, 415-2232 | | | contact person = morgan M NRR/NRC/DLR/RLRC, 415-2232 |
| | case reference number = TAC MC9668 | | | case reference number = TAC MC9668 |
| | package number = ML060950189 | | | package number = ML060950189 |
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| =Text= | | =Text= |
| {{#Wiki_filter:XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 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: XI.M12, Thermal Aging Embrittlement of Cast Austenitic DATE: __________________________ |
| GALL AMP: XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)_ | | Stainless Steel (CASS)_ |
| DATE: __________________________
| | Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. The reactor coolant system components are inspected in Consistent with GALL AMP: Yes No Description accordance with the American Society of Mechanical Engineers Document(s) used to confirm Criteria: |
| Program Element Auditable GALL Criteria Documentation of Audit Finding Program Description A. The reactor coolant system components are inspected in accordance with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI. This inspection is augmented to detect the effects of loss of fracture toughness due to thermal aging embrittlement of cast austenitic stainless steel (CASS) components. This aging management program (AMP) includes (a) determination of the susceptibility of CASS components to thermal aging embrittlement based on casting method, molybdenum content, and percent ferrite, and Consistent with GALL AMP: | | (ASME) Boiler and Pressure Vessel Code, Section XI. This inspection is augmented to detect the effects of loss of fracture toughness due to thermal aging embrittlement of cast austenitic stainless steel (CASS) components. This aging management Comment: |
| Yes No Document(s) used to confirm Criteria:
| | program (AMP) includes (a) determination of the susceptibility of CASS components to thermal aging embrittlement based on casting method, molybdenum content, and percent ferrite, and B. (b) for potentially susceptible components, as defined Consistent with GALL AMP: Yes No below, aging management is accomplished through either Document(s) used to confirm Criteria: |
| Comment: " B. (b) for "potentially susceptible" components, as defined below, aging management is accomplished through either enhanced volumetric examination or plant- or component-specific flaw tolerance evaluation. Additional inspection or evaluations to demonstrate that the material has adequate fracture toughness are not required for components that are not susceptible to thermal aging embrittlement. Consistent with GALL AMP:
| | enhanced volumetric examination or plant- or component-specific flaw tolerance evaluation. Additional inspection or evaluations to demonstrate that the material has adequate fracture toughness are not required for components that are not Comment: |
| Yes No Document(s) used to confirm Criteria:
| | susceptible to thermal aging embrittlement. |
| Comment: " C. For pump casings and valve bodies, based on the assessment documented in the letter dated May 19, 2000, from Christopher Grimes, Nuclear Regulatory Commission (NRC), to Douglas Walters, Nuclear Energy Institute (NEI), screening for susceptibility to thermal aging is not required. The existing ASME Section XI inspection requirements, including the alternative requirements of ASME Code Case N-481 for pump casings, are adequate for all pump casings and valve bodies. Consistent with GALL AMP:
| | C. For pump casings and valve bodies, based on the Consistent with GALL AMP: Yes No assessment documented in the letter dated May 19, 2000, from Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | Christopher Grimes, Nuclear Regulatory Commission (NRC), to Douglas Walters, Nuclear Energy Institute (NEI), screening for susceptibility to thermal aging is not required. The existing ASME Section XI inspection requirements, including the Comment: |
| | alternative requirements of ASME Code Case N-481 for pump casings, are adequate for all pump casings and valve bodies. |
| | XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 1 |
| | |
| | Program Auditable GALL Criteria Documentation of Audit Finding Element |
| | : 1. Scope of A. The program includes screening criteria to determine which Consistent with GALL AMP: Yes No Program CASS components are potentially susceptible to thermal aging Document(s) used to confirm Criteria: |
| | embrittlement and require augmented inspection. The screening criteria are applicable to all primary pressure boundary and reactor vessel internal components constructed from SA-351 Grades CF3, CF3A, CF8, CF8A, CF3M, CF3MA, CF8M, with Comment service conditions above 250°C (482°F). The screening criteria for susceptibility to thermal aging embrittlement are not applicable to niobium-containing steels; such steels require evaluation on a case-by-case basis. For potentially susceptible components, aging management is accomplished either through volumetric examination or plant- or component-specific flaw tolerance evaluation. |
| | B Based on the criteria set forth in the May 19, 2000 NRC letter, Consistent with GALL AMP: Yes No the susceptibility to thermal aging embrittlement of CASS Document(s) used to confirm Criteria: |
| | components is determined in terms of casting method, molybdenum content, and ferrite content. For low-molybdenum content (0.5 wt.% max.) steels, only static-cast steels with >20% |
| | ferrite are potentially susceptible to thermal embrittlement. Comment: |
| | Static-cast low-molybdenum steels with 20% ferrite and all centrifugal-cast low-molybdenum steels are not susceptible. For high-molybdenum content (2.0 to 3.0 wt.%) steels, static-cast steels with >14% ferrite and centrifugal-cast steels with >20% |
| | ferrite are potentially susceptible to thermal embrittlement. |
| | Static-cast high-molybdenum steels with 14% ferrite and centrifugal-cast high-molybdenum steels with 20% ferrite are not susceptible. In the susceptibility screening method, ferrite content is calculated by using the Hulls equivalent factors (described in NUREG/CR-4513, Rev. 1) or a method producing an equivalent level of accuracy (+/-6% deviation between measured and calculated values). A fracture toughness value of 255 kJ/m2 (1,450 in.-lb/in.2) at a crack depth of 2.5 mm (0.1 in.) |
| | is used to differentiate between CASS materials that are nonsusceptible and those that are potentially susceptible to XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 2 |
| | |
| | Program Auditable GALL Criteria Documentation of Audit Finding Element thermal aging embrittlement. Extensive research data indicate that for nonsusceptible CASS materials, the saturated lower-bound fracture toughness is greater than 255 kJ/m2 (NUREG/CR-4513, Rev. 1). |
| | C For pump casings and valve bodies, screening for Consistent with GALL AMP: Yes No susceptibility to thermal aging embrittlement is not required. The Document(s) used to confirm Criteria: |
| | staffs conservative bounding integrity analysis shows that thermally aged CASS valve bodies and pump casings are resistant to failure. For all pump casings and valve bodies greater than nominal pipe size (NPS) 4 in., the existing ASME Comment: |
| | Section XI inspection requirements, including the alternative requirements of ASME Code Case N-481 for pump casings, are adequate. ASME Section XI, Subsection IWB, requires only surface examination of valve bodies less than NPS 4 in. For valve bodies less than NPS 4 in., the adequacy of inservice inspection (ISI) according to ASME Section XI has been demonstrated by an NRC-performed bounding integrity analysis (Reference letter from Christopher Grimes dated May 19, 2000). |
| | : 2. Preventive A. The program consists of evaluation and inspection and Consistent with GALL AMP: Yes No Actions provides no guidance on methods to mitigate thermal aging Document(s) used to confirm Criteria: |
| | embrittlement. |
| Comment: | | Comment: |
| XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 2 Program Element Auditable GALL Criteria Documentation of Audit Finding 1. Scope of Program A. The program includes screening criteria to determine which CASS components are potentially susceptible to thermal aging embrittlement and require augmented inspection. The screening criteria are applicable to all primary pressure boundary and reactor vessel internal components constructed from SA-351 Grades CF3, CF3A, CF8, CF8A, CF3M, CF3MA, CF8M, with service conditions above 250°C (482°F). The screening criteria for susceptibility to thermal aging embrittlement are not applicable to niobium-containing steels; such steels require evaluation on a case-by-case basis. For potentially susceptible components, aging management is accomplished either through volumetric examination or plant- or component-specific flaw tolerance evaluation. Consistent with GALL AMP:
| | : 3. Parameters A. The AMP monitors the effects of loss of fracture toughness Consistent with GALL AMP: Yes No Monitored/ on the intended function of the component by identifying the Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | Inspected CASS materials that are susceptible to thermal aging embrittlement. For potentially susceptible materials, the program consists of either enhanced volumetric examination to detect and size cracks or plant- or component-specific flaw tolerance Comment: |
| Comment " B Based on the criteria set forth in the May 19, 2000 NRC letter, the susceptibility to thermal aging embrittlement of CASS components is determined in terms of casting method, molybdenum content, and ferrite content. For low-molybdenum content (0.5 wt.% max.) steels, only static-cast steels with >20%
| | evaluation (loss of fracture toughness is of consequence only if cracks exist). |
| ferrite are potentially susceptible to thermal embrittlement. Static-cast low-molybdenum steels with 20% ferrite and all centrifugal-cast low-molybdenum steels are not susceptible. For high-molybdenum content (2.0 to 3.0 wt.%) steels, static-cast steels with >14% ferrite and centrifugal-cast steels with >20%
| | XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 3 |
| ferrite are potentially susceptible to thermal embrittlement. Static-cast high-molybdenum steels with 14% ferrite and centrifugal-cast high-molybdenum steels with 20% ferrite are not susceptible. In the susceptibility screening method, ferrite content is calculated by using the Hull's equivalent factors (described in NUREG/CR-4513, Rev. 1) or a method producing an equivalent level of accuracy (+/-6% deviation between measured and calculated values). A fracture toughness value of 255 kJ/m 2 (1,450 in.-lb/in.
| |
| : 2) at a crack depth of 2.5 mm (0.1 in.) is used to differentiate between CASS materials that are nonsusceptible and those that are potentially susceptible to Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
|
| |
|
| | Program Auditable GALL Criteria Documentation of Audit Finding Element |
| | : 4. Detection of A. For pump casings and valve bodies and not susceptible Consistent with GALL AMP: Yes No Aging Effects piping, no additional inspection or evaluations are required to Document(s) used to confirm Criteria: |
| | demonstrate that the material has adequate fracture toughness. |
| | For potentially susceptible piping, because the base metal does not receive periodic inspection per ASME Section XI, the CASS AMP provides for volumetric examination of the base Comment: |
| | metal, with the scope of the inspection covering the portions determined to be limiting from the standpoint of applied stress, operating time, and environmental considerations. Examination methods that meet the criteria of the ASME Section XI, Appendix VIII, are acceptable. |
| | B Alternatively, a plant- or component-specific flaw tolerance Consistent with GALL AMP: Yes No evaluation, using specific geometry and stress information, can Document(s) used to confirm Criteria: |
| | be used to demonstrate that the thermally-embrittled material has adequate toughness. |
| | Comment: |
| | : 5. Monitoring A. Inspection schedules in accordance with IWB-2400 or IWC- Consistent with GALL AMP: Yes No and Trending 2400 and reliable examination methods provide timely detection Document(s) used to confirm Criteria: |
| | of cracks. |
| | Comment: |
| | : 6. Acceptance A. Flaws detected in CASS components are evaluated in Consistent with GALL AMP: Yes No Criteria accordance with the applicable procedures of IWB-3500 or Document(s) used to confirm Criteria: |
| | IWC-3500. |
| Comment: | | Comment: |
| XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 3 Program Element Auditable GALL Criteria Documentation of Audit Finding thermal aging embrittlement. Extensive research data indicate that for nonsusceptible CASS materials, the saturated lower-bound fracture toughness is greater than 255 kJ/m 2 (NUREG/CR-4513, Rev. 1). " C For pump casings and valve bodies, screening for susceptibility to thermal aging embrittlement is not required. The staff's conservative bounding integrity analysis shows that thermally aged CASS valve bodies and pump casings are resistant to failure. For all pump casings and valve bodies greater than nominal pipe size (NPS) 4 in., the existing ASME Section XI inspection requirements, including the alternative requirements of ASME Code Case N-481 for pump casings, are adequate. ASME Section XI, Subsection IWB, requires only surface examination of valve bodies less than NPS 4 in. For valve bodies less than NPS 4 in., the adequacy of inservice inspection (ISI) according to ASME Section XI has been demonstrated by an NRC-performed bounding integrity analysis (Reference letter from Christopher Grimes dated May 19, 2000).Consistent with GALL AMP:
| | B Flaw tolerance evaluation for components with ferrite content Consistent with GALL AMP: Yes No up to 25% is performed according to the principles associated Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | with IWB-3640 procedures for submerged arc welds (SAW), |
| | | disregarding the Code restriction of 20% ferrite in IWB-XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 4 |
| Comment: 2. Preventive Actions A. The program consists of evaluation and inspection and provides no guidance on methods to mitigate thermal aging embrittlement. Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
| | |
| Comment: 3. Parameters Monitored/ Inspected A. The AMP monitors the effects of loss of fracture toughness on the intended function of the component by identifying the CASS materials that are susceptible to thermal aging embrittlement. For potentially susceptible materials, the program consists of either enhanced volumetric examination to detect and size cracks or plant- or component-specific flaw tolerance evaluation (loss of fracture toughness is of consequence only if cracks exist). Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
|
| |
|
| | Program Auditable GALL Criteria Documentation of Audit Finding Element 3641(b)(1). Extensive research data indicate that the lower-bound fracture toughness of thermally aged CASS materials Comment: |
| | with up to 25% ferrite is similar to that for submerged arc welds (SAWs) with up to 20% ferrite (Lee et al., 1997). Flaw evaluation for piping with >25% ferrite is performed on a case-by-case basis by using fracture toughness data provided by the applicant. |
| | : 7. Corrective A. Repair is performed in conformance with IWA-4000 and IWB- Consistent with GALL AMP: Yes No Actions 4000 or IWC-4000, and replacement in accordance with IWA- Document(s) used to confirm Criteria: |
| | 7000 and IWB-7000 or IWC-7000. 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. Site quality assurance (QA) procedures, review and approval Consistent with GALL AMP: Yes No Confirmation processes, and administrative controls are implemented in Document(s) used to confirm Criteria: |
| | Process accordance with the requirements of 10 CFR Part 50, Appendix B. 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 and administrative controls. Comment: |
| | : 9. A. See Item 8, above. Consistent with GALL AMP: Yes No Administrative Document(s) used to confirm Criteria: |
| | Controls Comment: |
| | : 10. Operating A. The AMP was developed by using research data obtained on Consistent with GALL AMP: Yes No Experience both laboratory-aged and service-aged materials. Based on this Document(s) used to confirm Criteria: |
| | information, the effects of thermal aging embrittlement on the intended function of CASS components are effectively managed. |
| Comment: | | Comment: |
| XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 4 Program Element Auditable GALL Criteria Documentation of Audit Finding 4. Detection of Aging Effects A. For pump casings and valve bodies and "not susceptible" piping, no additional inspection or evaluations are required to demonstrate that the material has adequate fracture toughness. For "potentially susceptible" piping, because the base metal does not receive periodic inspection per ASME Section XI, the CASS AMP provides for volumetric examination of the base metal, with the scope of the inspection covering the portions determined to be limiting from the standpoint of applied stress, operating time, and environmental considerations. Examination methods that meet the criteria of the ASME Section XI, Appendix VIII, are acceptable. Consistent with GALL AMP: | | XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 5 |
| Yes No Document(s) used to confirm Criteria:
| |
| Comment: " B Alternatively, a plant- or component-specific flaw tolerance evaluation, using specific geometry and stress information, can be used to demonstrate that the thermally-embrittled material has adequate toughness. Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
| | |
| Comment: 5. Monitoring and Trending A. Inspection schedules in accordance with IWB-2400 or IWC-2400 and reliable examination methods provide timely detection of cracks. Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
| | |
| Comment: 6. Acceptance Criteria A. Flaws detected in CASS components are evaluated in accordance with the applicable procedures of IWB-3500 or IWC-3500. Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
| | |
| Comment: " B Flaw tolerance evaluation for components with ferrite content up to 25% is performed according to the principles associated with IWB-3640 procedures for submerged arc welds (SAW), disregarding the Code restriction of 20% ferrite in IWB-Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
|
| |
|
| XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 5 Program Element Auditable GALL Criteria Documentation of Audit Finding 3641(b)(1). Extensive research data indicate that the lower-bound fracture toughness of thermally aged CASS materials with up to 25% ferrite is similar to that for submerged arc welds (SAWs) with up to 20% ferrite (Lee et al., 1997). Flaw evaluation for piping with >25% ferrite is performed on a case-by-case basis by using fracture toughness data provided by the applicant.
| | EXCEPTIONS Item Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| Comment: 7. Corrective Actions A. Repair is performed in conformance with IWA-4000 and IWB-4000 or IWC-4000, and replacement in accordance with IWA-7000 and IWB-7000 or IWC-7000. 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:
| | 1. |
| Yes No Document(s) used to confirm Criteria:
| | 2. |
| Comment: 8.
| |
| Confirmation Process A. Site quality assurance (QA) procedures, review and approval processes, and administrative controls are implemented in accordance with the requirements of 10 CFR Part 50, Appendix B. 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 and administrative controls. Consistent with GALL AMP:
| |
| Yes No Document(s) used to confirm Criteria:
| |
|
| |
|
| Comment: 9.
| | ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| Administrative Controls A. See Item 8, above. Consistent with GALL AMP:
| | 1. |
| Yes No Document(s) used to confirm Criteria:
| | 2. |
|
| |
|
| Comment: 10. Operating Experience A. The AMP was developed by using research data obtained on both laboratory-aged and service-aged materials. Based on this information, the effects of thermal aging embrittlement on the intended function of CASS components are effectively managed. Consistent with GALL AMP:
| | DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1. |
| Yes No Document(s) used to confirm Criteria:
| | 2. |
| | | 3. |
| Comment:
| | 4. |
| XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 6 EXCEPTIONS Item Number Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| | XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 6}} |
| 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 |
|---|
|
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
|
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
[Table View] |
|
|---|
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: XI.M12, Thermal Aging Embrittlement of Cast Austenitic DATE: __________________________
Stainless Steel (CASS)_
Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. The reactor coolant system components are inspected in Consistent with GALL AMP: Yes No Description accordance with the American Society of Mechanical Engineers Document(s) used to confirm Criteria:
(ASME) Boiler and Pressure Vessel Code,Section XI. This inspection is augmented to detect the effects of loss of fracture toughness due to thermal aging embrittlement of cast austenitic stainless steel (CASS) components. This aging management Comment:
program (AMP) includes (a) determination of the susceptibility of CASS components to thermal aging embrittlement based on casting method, molybdenum content, and percent ferrite, and B. (b) for potentially susceptible components, as defined Consistent with GALL AMP: Yes No below, aging management is accomplished through either Document(s) used to confirm Criteria:
enhanced volumetric examination or plant- or component-specific flaw tolerance evaluation. Additional inspection or evaluations to demonstrate that the material has adequate fracture toughness are not required for components that are not Comment:
susceptible to thermal aging embrittlement.
C. For pump casings and valve bodies, based on the Consistent with GALL AMP: Yes No assessment documented in the letter dated May 19, 2000, from Document(s) used to confirm Criteria:
Christopher Grimes, Nuclear Regulatory Commission (NRC), to Douglas Walters, Nuclear Energy Institute (NEI), screening for susceptibility to thermal aging is not required. The existing ASME Section XI inspection requirements, including the Comment:
alternative requirements of ASME Code Case N-481 for pump casings, are adequate for all pump casings and valve bodies.
XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 1
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 1. Scope of A. The program includes screening criteria to determine which Consistent with GALL AMP: Yes No Program CASS components are potentially susceptible to thermal aging Document(s) used to confirm Criteria:
embrittlement and require augmented inspection. The screening criteria are applicable to all primary pressure boundary and reactor vessel internal components constructed from SA-351 Grades CF3, CF3A, CF8, CF8A, CF3M, CF3MA, CF8M, with Comment service conditions above 250°C (482°F). The screening criteria for susceptibility to thermal aging embrittlement are not applicable to niobium-containing steels; such steels require evaluation on a case-by-case basis. For potentially susceptible components, aging management is accomplished either through volumetric examination or plant- or component-specific flaw tolerance evaluation.
B Based on the criteria set forth in the May 19, 2000 NRC letter, Consistent with GALL AMP: Yes No the susceptibility to thermal aging embrittlement of CASS Document(s) used to confirm Criteria:
components is determined in terms of casting method, molybdenum content, and ferrite content. For low-molybdenum content (0.5 wt.% max.) steels, only static-cast steels with >20%
ferrite are potentially susceptible to thermal embrittlement. Comment:
Static-cast low-molybdenum steels with 20% ferrite and all centrifugal-cast low-molybdenum steels are not susceptible. For high-molybdenum content (2.0 to 3.0 wt.%) steels, static-cast steels with >14% ferrite and centrifugal-cast steels with >20%
ferrite are potentially susceptible to thermal embrittlement.
Static-cast high-molybdenum steels with 14% ferrite and centrifugal-cast high-molybdenum steels with 20% ferrite are not susceptible. In the susceptibility screening method, ferrite content is calculated by using the Hulls equivalent factors (described in NUREG/CR-4513, Rev. 1) or a method producing an equivalent level of accuracy (+/-6% deviation between measured and calculated values). A fracture toughness value of 255 kJ/m2 (1,450 in.-lb/in.2) at a crack depth of 2.5 mm (0.1 in.)
is used to differentiate between CASS materials that are nonsusceptible and those that are potentially susceptible to XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 2
Program Auditable GALL Criteria Documentation of Audit Finding Element thermal aging embrittlement. Extensive research data indicate that for nonsusceptible CASS materials, the saturated lower-bound fracture toughness is greater than 255 kJ/m2 (NUREG/CR-4513, Rev. 1).
C For pump casings and valve bodies, screening for Consistent with GALL AMP: Yes No susceptibility to thermal aging embrittlement is not required. The Document(s) used to confirm Criteria:
staffs conservative bounding integrity analysis shows that thermally aged CASS valve bodies and pump casings are resistant to failure. For all pump casings and valve bodies greater than nominal pipe size (NPS) 4 in., the existing ASME Comment:
Section XI inspection requirements, including the alternative requirements of ASME Code Case N-481 for pump casings, are adequate. ASME Section XI, Subsection IWB, requires only surface examination of valve bodies less than NPS 4 in. For valve bodies less than NPS 4 in., the adequacy of inservice inspection (ISI) according to ASME Section XI has been demonstrated by an NRC-performed bounding integrity analysis (Reference letter from Christopher Grimes dated May 19, 2000).
- 2. Preventive A. The program consists of evaluation and inspection and Consistent with GALL AMP: Yes No Actions provides no guidance on methods to mitigate thermal aging Document(s) used to confirm Criteria:
embrittlement.
Comment:
- 3. Parameters A. The AMP monitors the effects of loss of fracture toughness Consistent with GALL AMP: Yes No Monitored/ on the intended function of the component by identifying the Document(s) used to confirm Criteria:
Inspected CASS materials that are susceptible to thermal aging embrittlement. For potentially susceptible materials, the program consists of either enhanced volumetric examination to detect and size cracks or plant- or component-specific flaw tolerance Comment:
evaluation (loss of fracture toughness is of consequence only if cracks exist).
XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 3
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 4. Detection of A. For pump casings and valve bodies and not susceptible Consistent with GALL AMP: Yes No Aging Effects piping, no additional inspection or evaluations are required to Document(s) used to confirm Criteria:
demonstrate that the material has adequate fracture toughness.
For potentially susceptible piping, because the base metal does not receive periodic inspection per ASME Section XI, the CASS AMP provides for volumetric examination of the base Comment:
metal, with the scope of the inspection covering the portions determined to be limiting from the standpoint of applied stress, operating time, and environmental considerations. Examination methods that meet the criteria of the ASME Section XI, Appendix VIII, are acceptable.
B Alternatively, a plant- or component-specific flaw tolerance Consistent with GALL AMP: Yes No evaluation, using specific geometry and stress information, can Document(s) used to confirm Criteria:
be used to demonstrate that the thermally-embrittled material has adequate toughness.
Comment:
- 5. Monitoring A. Inspection schedules in accordance with IWB-2400 or IWC- Consistent with GALL AMP: Yes No and Trending 2400 and reliable examination methods provide timely detection Document(s) used to confirm Criteria:
of cracks.
Comment:
- 6. Acceptance A. Flaws detected in CASS components are evaluated in Consistent with GALL AMP: Yes No Criteria accordance with the applicable procedures of IWB-3500 or Document(s) used to confirm Criteria:
IWC-3500.
Comment:
B Flaw tolerance evaluation for components with ferrite content Consistent with GALL AMP: Yes No up to 25% is performed according to the principles associated Document(s) used to confirm Criteria:
with IWB-3640 procedures for submerged arc welds (SAW),
disregarding the Code restriction of 20% ferrite in IWB-XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 4
Program Auditable GALL Criteria Documentation of Audit Finding Element 3641(b)(1). Extensive research data indicate that the lower-bound fracture toughness of thermally aged CASS materials Comment:
with up to 25% ferrite is similar to that for submerged arc welds (SAWs) with up to 20% ferrite (Lee et al., 1997). Flaw evaluation for piping with >25% ferrite is performed on a case-by-case basis by using fracture toughness data provided by the applicant.
- 7. Corrective A. Repair is performed in conformance with IWA-4000 and IWB- Consistent with GALL AMP: Yes No Actions 4000 or IWC-4000, and replacement in accordance with IWA- Document(s) used to confirm Criteria:
7000 and IWB-7000 or IWC-7000. 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. Site quality assurance (QA) procedures, review and approval Consistent with GALL AMP: Yes No Confirmation processes, and administrative controls are implemented in Document(s) used to confirm Criteria:
Process accordance with the requirements of 10 CFR Part 50, Appendix B. 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 and administrative controls. Comment:
- 9. A. See Item 8, above. Consistent with GALL AMP: Yes No Administrative Document(s) used to confirm Criteria:
Controls Comment:
- 10. Operating A. The AMP was developed by using research data obtained on Consistent with GALL AMP: Yes No Experience both laboratory-aged and service-aged materials. Based on this Document(s) used to confirm Criteria:
information, the effects of thermal aging embrittlement on the intended function of CASS components are effectively managed.
Comment:
XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 5
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.
XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) 6
