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| | number = ML061000143 | | | number = ML061000143 |
| | issue date = 03/22/2006 | | | issue date = 03/22/2006 |
| | title = 2006/03/22-GALL AMP: XI.S7, Rg 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (Audit Worksheet GALL Report AMP) | | | title = GALL AMP: XI.S7, Rg 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (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 = |
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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 = %dam200611, TAC MC9668 | | | case reference number = %dam200611, TAC MC9668 |
| | package number = ML060950189 | | | package number = ML060950189 |
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| =Text= | | =Text= |
| {{#Wiki_filter:XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 1 AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________ | | {{#Wiki_filter:AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________ |
| | LRA AMP: __________________________ REVIEWER: ______________________ |
| | GALL AMP: XI.S7, RG 1.127, Inspection of Water-Control Structures DATE: __________________________ |
| | Associated With Nuclear Power Plants Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. Nuclear Regulatory Commission (NRC) Regulatory Guide Consistent with GALL AMP: Yes No Description (RG) 1.127, Revision 1, "Inspection of Water-Control Structures Document(s) used to confirm Criteria: |
| | Associated with Nuclear Power Plants," describes an acceptable basis for developing an inservice inspection and surveillance program for dams, slopes, canals, and other water-control structures associated with emergency cooling water systems or Comment: |
| | flood protection of nuclear power plants. The RG 1.127 program addresses age-related deterioration, degradation due to extreme environmental conditions, and the effects of natural phenomena that may affect water-control structures. The RG 1.127 program recognizes the importance of periodic monitoring and maintenance of water-control structures so that the consequences of age-related deterioration and degradation can be prevented or mitigated in a timely manner. |
| | RG 1.127 provides detailed guidance for the licensee's inspection program for water-control structures, including guidance on engineering data compilation, inspection activities, technical evaluation, inspection frequency, and the content of inspection reports. Water-control structures covered by the RG 1.127 program include concrete structures; embankment structures; spillway structures and outlet works; reservoirs; cooling water channels and canals, and intake and discharge structures; and safety and performance instrumentation. RG XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 1 |
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| LRA AMP: __________________________
| | Program Auditable GALL Criteria Documentation of Audit Finding Element 1.127 delineates current NRC practice in evaluating inservice inspection programs for water-control structures. The attributes of an acceptable aging management program (AMP) for license renewal are described below. |
| R EVIEWER: ______________________
| | For plants not committed to RG 1.127, Revision 1, aging management of water-control structures may be included in the Structures Monitoring Program (XI.S6). Even if plant is committed to RG 1.127, Revision 1, aging management of certain structures and components may be included in the Structures Monitoring Program (XI.S6). However, details pertaining to water-control structures are to incorporate the attributes described herein. |
| GALL AMP: XI.S7, RG 1.127, Inspection of Water-Control Structures Associated With Nuclear Power Plants DATE: __________________________
| | : 1. Scope of A. RG 1.127 applies to water-control structures associated with Consistent with GALL AMP: Yes No Program emergency cooling water systems or flood protection of nuclear Document(s) used to confirm Criteria: |
| Program Element Auditable GALL Criteria Documentation of Audit Finding Program Description A. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.127, Revision 1, "Inspection of Water-Control Structures Associated with Nuclear Power Plants," describes an acceptable basis for developing an inservice inspection and surveillance program for dams, slopes, canals, and other water-control structures associated with emergency cooling water systems or flood protection of nuclear power plants. The RG 1.127 program addresses age-related deterioration, degradation due to extreme environmental conditions, and the effects of natural phenomena that may affect water-control structures. The RG 1.127 program recognizes the importance of periodic monitoring and maintenance of water-control structures so that the consequences of age-related deterioration and degradation can be prevented or mitigated in a timely manner. RG 1.127 provides detailed guidance for the licensee's inspection program for water-control structures, including guidance on engineering data compilation, inspection activities, technical evaluation, inspection frequency, and the content of inspection reports. Water-control structures covered by the RG 1.127 program include concrete structures; embankment structures; spillway structures and outlet works; reservoirs; cooling water channels and canals, and intake and discharge structures; and safety and performance instrumentation. RG Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria: | | power plants. The water-control structures included in the RG 1.127 program are concrete structures; embankment structures; spillway structures and outlet works; reservoirs; cooling water channels and canals, and intake and discharge structures; and Comment safety and performance instrumentation. |
| | : 2. Preventive A. No preventive actions are specified; RG 1.127 is a monitoring Consistent with GALL AMP: Yes No Actions program. Document(s) used to confirm Criteria: |
| | Comment: |
| | : 3. Parameters A. RG 1.127 identifies the parameters to be monitored and Consistent with GALL AMP: Yes No Monitored/ inspected for water-control structures. The parameters vary Document(s) used to confirm Criteria: |
| | Inspected depending on the particular structure. Parameters to be monitored and inspected for concrete structures include cracking, movements (e.g., settlement, heaving, deflection), |
| | conditions at junctions with abutments and embankments, Comment: |
| | erosion, cavitation, seepage, and leakage. |
| | B. Parameters to be monitored and inspected for earthen Consistent with GALL AMP: Yes No embankment structures include settlement, depressions, sink Document(s) used to confirm Criteria: |
| | XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 2 |
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| | Program Auditable GALL Criteria Documentation of Audit Finding Element holes, slope stability (e.g., irregularities in alignment and variances from originally constructed slopes), seepage, proper functioning of drainage systems, and degradation of slope protection features. Further details of parameters to be Comment: |
| | monitored and inspected for these and other water-control structures are specified in Section C.2 of RG 1.127. |
| | : 4. Detection of A. Visual inspections are primarily used to detect degradation of Consistent with GALL AMP: Yes No Aging Effects water-control structures. In some cases, instruments have been Document(s) used to confirm Criteria: |
| | installed to measure the behavior of water-control structures. |
| | RG 1.127 indicates that the available records and readings of installed instruments are to be reviewed to detect any unusual performance or distress that may be indicative of degradation. Comment: |
| | RG 1.127 describes periodic inspections, to be performed at least once every five years. Similar intervals of five years are specified in ACI 349.3R for inspection of structures continually exposed to fluids or retaining fluids. Such intervals have been shown to be adequate to detect degradation of water-control structures before they have a significant effect on plant safety. |
| | RG 1.127 also describes special inspections immediately following the occurrence of significant natural phenomena, such as large floods, earthquakes, hurricanes, tornadoes, and intense local rainfalls. |
| | : 5. Monitoring A. Water-control structures are monitored by periodic inspection Consistent with GALL AMP: Yes No and Trending as described in RG 1.127. In addition to monitoring the aging Document(s) used to confirm Criteria: |
| | effects identified in Attribute (3) above, inspections also monitor the adequacy and quality of maintenance and operating procedures. RG 1.127 does not discuss trending. |
| Comment: | | Comment: |
| XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 2 Program Element Auditable GALL Criteria Documentation of Audit Finding 1.127 delineates current NRC practice in evaluating inservice inspection programs for water-control structures. The attributes of an acceptable aging management program (AMP) for license renewal are described below. For plants not committed to RG 1.127, Revision 1, aging management of water-control structures may be included in the Structures Monitoring Program (XI.S6). Even if plant is committed to RG 1.127, Revision 1, aging management of certain structures and components may be included in the Structures Monitoring Program (XI.S6). However, details pertaining to water-control structures are to incorporate the attributes described herein. 1. Scope of Program A. RG 1.127 applies to water-control structures associated with emergency cooling water systems or flood protection of nuclear power plants. The water-control structures included in the RG 1.127 program are concrete structures; embankment structures; spillway structures and outlet works; reservoirs; cooling water channels and canals, and intake and discharge structures; and safety and performance instrumentation. Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria: | | XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 3 |
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| Comment 2. Preventive Actions A. No preventive actions are specified; RG 1.127 is a monitoring program. Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element |
| Comment: 3. Parameters Monitored/ | | : 6. Acceptance A. Acceptance criteria to evaluate the need for corrective Consistent with GALL AMP: Yes No Criteria actions are not specified in RG 1.127. However, the Evaluation Document(s) used to confirm Criteria: |
| Inspected A. RG 1.127 identifies the parameters to be monitored and inspected for water-control structures. The parameters vary depending on the particular structure. Parameters to be monitored and inspected for concrete structures include cracking, movements (e.g., settlement, heaving, deflection), conditions at junctions with abutments and embankments, erosion, cavitation, seepage, and leakage. Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria:
| | Criteria provided in Chapter 5 of ACI 349.3R-96 provides acceptance criteria (including quantitative criteria) for determining the adequacy of observed aging effects and specifies criteria for further evaluation. Although not required, Comment: |
| | plant-specific acceptance criteria based on Chapter 5 of ACI 349.3R-96 are acceptable. Acceptance criteria for earthen structures such as dams, canals, and embankments are to be consistent with programs falling within the regulatory jurisdiction of the Federal Energy Regulatory Commission (FERC) or the U.S. Army Corps of Engineers. |
| | : 7. Corrective A. RG 1.127 recommends that the licensee's inservice Consistent with GALL AMP: Yes No Actions inspection and surveillance program include periodic Document(s) used to confirm Criteria: |
| | inspections of water-control structures to identify deviations in structural conditions due to age-related deterioration and degradation from the original design basis. When findings indicate that significant changes have occurred, the conditions Comment: |
| | are to be evaluated. This includes a technical assessment of the causes of distress or abnormal conditions, an evaluation of the behavior or movement of the structure, and recommendations for remedial or mitigating measures. 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. |
| | : 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 Administrative requirements of 10 CFR Part 50, Appendix B, acceptable to Document(s) used to confirm Criteria: |
| | Controls address the administrative controls. |
| | XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 4 |
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| Comment: " B. Parameters to be monitored and inspected for earthen embankment structures include settlement, depressions, sink Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element Comment: |
| XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 3 Program Element Auditable GALL Criteria Documentation of Audit Finding holes, slope stability (e.g., irregularities in alignment and variances from originally constructed slopes), seepage, proper functioning of drainage systems, and degradation of slope protection features. Further details of parameters to be monitored and inspected for these and other water-control structures are specified in Section C.2 of RG 1.127.
| | : 10. Operating A. Degradation of water-control structures has been detected, Consistent with GALL AMP: Yes No Formatted: Bullets and Numbering Experience through RG 1.127 programs, at a number of nuclear power Document(s) used to confirm Criteria: |
| Comment: 4. Detection of Aging Effects A. Visual inspections are primarily used to detect degradation of water-control structures. In some cases, instruments have been installed to measure the behavior of water-control structures. RG 1.127 indicates that the available records and readings of installed instruments are to be reviewed to detect any unusual performance or distress that may be indicative of degradation. RG 1.127 describes periodic inspections, to be performed at least once every five years. Similar intervals of five years are specified in ACI 349.3R for inspection of structures continually exposed to fluids or retaining fluids. Such intervals have been shown to be adequate to detect degradation of water-control structures before they have a significant effect on plant safety. RG 1.127 also describes special inspections immediately following the occurrence of significant natural phenomena, such as large floods, earthquakes, hurricanes, tornadoes, and intense local rainfalls. Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria:
| | plants, and in some cases, it has required remedial action. No loss of intended functions has resulted from these occurrences. |
| | | Therefore, it can be concluded that the inspections implemented in accordance with the guidance in RG 1.127 have been Comment: |
| Comment: 5. Monitoring and Trending A. Water-control structures are monitored by periodic inspection as described in RG 1.127. In addition to monitoring the aging effects identified in Attribute (3) above, inspections also monitor the adequacy and quality of maintenance and operating procedures. RG 1.127 does not discuss trending. Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria:
| | successful in detecting significant degradation before loss of intended function occurs. |
| | | NOTE: For dam inspection and maintenance, programs under the regulatory jurisdiction of FERC or the U.S. Army Corps of Engineers, continued through the period of extended operation, will be adequate for the purpose of aging management. For programs not falling under the regulatory jurisdiction of FERC or the U.S. Army Corps of Engineers, the staff will evaluate the effectiveness of the aging management program based on compatibility to the common practices of the FERC and Corps programs. |
| Comment:
| | XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 5 |
| XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 4 Program Element Auditable GALL Criteria Documentation of Audit Finding 6. Acceptance Criteria A. Acceptance criteria to evaluate the need for corrective actions are not specified in RG 1.127. However, the "Evaluation Criteria" provided in Chapter 5 of ACI 349.3R-96 provides acceptance criteria (including quantitative criteria) for determining the adequacy of observed aging effects and specifies criteria for further evaluation. Although not required, plant-specific acceptance criteria based on Chapter 5 of ACI 349.3R-96 are acceptable. Acceptance criteria for earthen structures such as dams, canals, and embankments are to be consistent with programs falling within the regulatory jurisdiction of the Federal Energy Regulatory Commission (FERC) or the U.S. Army Corps of Engineers. Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria:
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| Comment: 7. Corrective Actions A. RG 1.127 recommends that the licensee's inservice inspection and surveillance program include periodic inspections of water-control structures to identify deviations in structural conditions due to age-related deterioration and degradation from the original design basis. When findings indicate that significant changes have occurred, the conditions are to be evaluated. This includes a technical assessment of the causes of distress or abnormal conditions, an evaluation of the behavior or movement of the structure, and recommendations for remedial or mitigating measures. 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: Yes No Document(s) used to confirm Criteria:
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| Comment: 8.
| | EXCEPTIONS Item Program Elements LRA Exception Description Basis for Accepting Exception 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: Yes No Document(s) used to confirm Criteria:
| | 1. |
| Comment: 9.
| | 2. |
| Administrative Controls 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 administrative controls. Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria:
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| XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 5 Program Element Auditable GALL Criteria Documentation of Audit Finding Comment: 10. Operating Experience A. Degradation of water-control structures has been detected, through RG 1.127 programs, at a number of nuclear power plants, and in some cases, it has required remedial action. No loss of intended functions has resulted from these occurrences. Therefore, it can be concluded that the inspections implemented in accordance with the guidance in RG 1.127 have been successful in detecting significant degradation before loss of intended function occurs. NOTE: For dam inspection and maintenance, programs under the regulatory jurisdiction of FERC or the U.S. Army Corps of Engineers, continued through the period of extended operation, will be adequate for the purpose of aging management. For programs not falling under the regulatory jurisdiction of FERC or the U.S. Army Corps of Engineers, the staff will evaluate the effectiveness of the aging management program based on compatibility to the common practices of the FERC and Corps programs. Consistent with GALL AMP: Yes No Document(s) used to confirm Criteria:
| | ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| | 1. |
| | 2. |
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| Comment: Formatted: Bullets and Numbering XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 6 EXCEPTIONS Item Number Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| | DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1. |
| ENHANCEMENTS Item Number Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| | 2. |
| DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1. 2. 3. 4. -.}} | | 3. |
| | 4. |
| | XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 6}} |
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
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AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________
LRA AMP: __________________________ REVIEWER: ______________________
GALL AMP: XI.S7, RG 1.127, Inspection of Water-Control Structures DATE: __________________________
Associated With Nuclear Power Plants Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. Nuclear Regulatory Commission (NRC) Regulatory Guide Consistent with GALL AMP: Yes No Description (RG) 1.127, Revision 1, "Inspection of Water-Control Structures Document(s) used to confirm Criteria:
Associated with Nuclear Power Plants," describes an acceptable basis for developing an inservice inspection and surveillance program for dams, slopes, canals, and other water-control structures associated with emergency cooling water systems or Comment:
flood protection of nuclear power plants. The RG 1.127 program addresses age-related deterioration, degradation due to extreme environmental conditions, and the effects of natural phenomena that may affect water-control structures. The RG 1.127 program recognizes the importance of periodic monitoring and maintenance of water-control structures so that the consequences of age-related deterioration and degradation can be prevented or mitigated in a timely manner.
RG 1.127 provides detailed guidance for the licensee's inspection program for water-control structures, including guidance on engineering data compilation, inspection activities, technical evaluation, inspection frequency, and the content of inspection reports. Water-control structures covered by the RG 1.127 program include concrete structures; embankment structures; spillway structures and outlet works; reservoirs; cooling water channels and canals, and intake and discharge structures; and safety and performance instrumentation. RG XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 1
Program Auditable GALL Criteria Documentation of Audit Finding Element 1.127 delineates current NRC practice in evaluating inservice inspection programs for water-control structures. The attributes of an acceptable aging management program (AMP) for license renewal are described below.
For plants not committed to RG 1.127, Revision 1, aging management of water-control structures may be included in the Structures Monitoring Program (XI.S6). Even if plant is committed to RG 1.127, Revision 1, aging management of certain structures and components may be included in the Structures Monitoring Program (XI.S6). However, details pertaining to water-control structures are to incorporate the attributes described herein.
- 1. Scope of A. RG 1.127 applies to water-control structures associated with Consistent with GALL AMP: Yes No Program emergency cooling water systems or flood protection of nuclear Document(s) used to confirm Criteria:
power plants. The water-control structures included in the RG 1.127 program are concrete structures; embankment structures; spillway structures and outlet works; reservoirs; cooling water channels and canals, and intake and discharge structures; and Comment safety and performance instrumentation.
- 2. Preventive A. No preventive actions are specified; RG 1.127 is a monitoring Consistent with GALL AMP: Yes No Actions program. Document(s) used to confirm Criteria:
Comment:
- 3. Parameters A. RG 1.127 identifies the parameters to be monitored and Consistent with GALL AMP: Yes No Monitored/ inspected for water-control structures. The parameters vary Document(s) used to confirm Criteria:
Inspected depending on the particular structure. Parameters to be monitored and inspected for concrete structures include cracking, movements (e.g., settlement, heaving, deflection),
conditions at junctions with abutments and embankments, Comment:
erosion, cavitation, seepage, and leakage.
B. Parameters to be monitored and inspected for earthen Consistent with GALL AMP: Yes No embankment structures include settlement, depressions, sink Document(s) used to confirm Criteria:
XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 2
Program Auditable GALL Criteria Documentation of Audit Finding Element holes, slope stability (e.g., irregularities in alignment and variances from originally constructed slopes), seepage, proper functioning of drainage systems, and degradation of slope protection features. Further details of parameters to be Comment:
monitored and inspected for these and other water-control structures are specified in Section C.2 of RG 1.127.
- 4. Detection of A. Visual inspections are primarily used to detect degradation of Consistent with GALL AMP: Yes No Aging Effects water-control structures. In some cases, instruments have been Document(s) used to confirm Criteria:
installed to measure the behavior of water-control structures.
RG 1.127 indicates that the available records and readings of installed instruments are to be reviewed to detect any unusual performance or distress that may be indicative of degradation. Comment:
RG 1.127 describes periodic inspections, to be performed at least once every five years. Similar intervals of five years are specified in ACI 349.3R for inspection of structures continually exposed to fluids or retaining fluids. Such intervals have been shown to be adequate to detect degradation of water-control structures before they have a significant effect on plant safety.
RG 1.127 also describes special inspections immediately following the occurrence of significant natural phenomena, such as large floods, earthquakes, hurricanes, tornadoes, and intense local rainfalls.
- 5. Monitoring A. Water-control structures are monitored by periodic inspection Consistent with GALL AMP: Yes No and Trending as described in RG 1.127. In addition to monitoring the aging Document(s) used to confirm Criteria:
effects identified in Attribute (3) above, inspections also monitor the adequacy and quality of maintenance and operating procedures. RG 1.127 does not discuss trending.
Comment:
XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 3
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 6. Acceptance A. Acceptance criteria to evaluate the need for corrective Consistent with GALL AMP: Yes No Criteria actions are not specified in RG 1.127. However, the Evaluation Document(s) used to confirm Criteria:
Criteria provided in Chapter 5 of ACI 349.3R-96 provides acceptance criteria (including quantitative criteria) for determining the adequacy of observed aging effects and specifies criteria for further evaluation. Although not required, Comment:
plant-specific acceptance criteria based on Chapter 5 of ACI 349.3R-96 are acceptable. Acceptance criteria for earthen structures such as dams, canals, and embankments are to be consistent with programs falling within the regulatory jurisdiction of the Federal Energy Regulatory Commission (FERC) or the U.S. Army Corps of Engineers.
- 7. Corrective A. RG 1.127 recommends that the licensee's inservice Consistent with GALL AMP: Yes No Actions inspection and surveillance program include periodic Document(s) used to confirm Criteria:
inspections of water-control structures to identify deviations in structural conditions due to age-related deterioration and degradation from the original design basis. When findings indicate that significant changes have occurred, the conditions Comment:
are to be evaluated. This includes a technical assessment of the causes of distress or abnormal conditions, an evaluation of the behavior or movement of the structure, and recommendations for remedial or mitigating measures. 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.
- 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 Administrative requirements of 10 CFR Part 50, Appendix B, acceptable to Document(s) used to confirm Criteria:
Controls address the administrative controls.
XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 4
Program Auditable GALL Criteria Documentation of Audit Finding Element Comment:
- 10. Operating A. Degradation of water-control structures has been detected, Consistent with GALL AMP: Yes No Formatted: Bullets and Numbering Experience through RG 1.127 programs, at a number of nuclear power Document(s) used to confirm Criteria:
plants, and in some cases, it has required remedial action. No loss of intended functions has resulted from these occurrences.
Therefore, it can be concluded that the inspections implemented in accordance with the guidance in RG 1.127 have been Comment:
successful in detecting significant degradation before loss of intended function occurs.
NOTE: For dam inspection and maintenance, programs under the regulatory jurisdiction of FERC or the U.S. Army Corps of Engineers, continued through the period of extended operation, will be adequate for the purpose of aging management. For programs not falling under the regulatory jurisdiction of FERC or the U.S. Army Corps of Engineers, the staff will evaluate the effectiveness of the aging management program based on compatibility to the common practices of the FERC and Corps programs.
XI.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 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.S7 RG 1.127 Inspection of Water-Control Structures Associated With Nuclear Power Plants 6