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| | number = ML060950570 | | | number = ML060950570 |
| | issue date = 03/22/2006 | | | issue date = 03/22/2006 |
| | title = 2006/03/22-GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP) | | | title = GALL AMP: XI.M22, Boraflex Monitoring (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 = %dam200611, TAC MC9668 | | | case reference number = %dam200611, TAC MC9668 |
| | package number = ML060950189 | | | package number = ML060950189 |
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| =Text= | | =Text= |
| {{#Wiki_filter:XI.M22 Boraflex Monitoring 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.M22, Boraflex Monitoring DATE: __________________________ |
| GALL AMP: XI.M22, Boraflex Monitoring DATE: __________________________ | | Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. A Boraflex monitoring program for the actual Boraflex panels Consistent with GALL AMP: Yes No Description is implemented in the spent fuel racks to assure that no Document(s) used to confirm Criteria: |
| Program Element Auditable GALL Criteria Documentation of Audit Finding Program Description A. A Boraflex monitoring program for the actual Boraflex panels is implemented in the spent fuel racks to assure that no unexpected degradation of the Boraflex material would compromise the criticality analysis in support of the design of spent fuel storage racks. The applicable aging management program (AMP), based on manufacturer's recommendations, relies on periodic inspection, testing, monitoring, and analysis of the criticality design to assure that the required 5% subcriticality margin is maintained. The frequency of the inspection and testing depends on the condition of the Boraflex, with a maximum of five years. Certain accelerated samples are tested every two years. Results based on test coupons have been found to be unreliable in determining the degree to which the actual Boraflex panels have been degraded. Therefore, this AMP includes: (1) performing neutron attenuation testing, called blackness testing, to determine gap formation in Boraflex panels; (2) completing sampling and analysis for silica levels in the spent fuel pool water and trending the results by using the EPRI RACKLIFE predictive code or its equivalent on a monthly, quarterly, or annual basis (depending on Boraflex panel condition); and (3) measuring boron areal density by techniques such as the BADGER device. Corrective actions are initiated if the test results find that the 5% subcriticality margin cannot be maintained because of current or projected future Boraflex Consistent with GALL AMP: | | unexpected degradation of the Boraflex material would compromise the criticality analysis in support of the design of spent fuel storage racks. The applicable aging management program (AMP), based on manufacturers recommendations, Comment: |
| Yes No Document(s) used to confirm Criteria:
| | relies on periodic inspection, testing, monitoring, and analysis of the criticality design to assure that the required 5% subcriticality margin is maintained. The frequency of the inspection and testing depends on the condition of the Boraflex, with a maximum of five years. Certain accelerated samples are tested every two years. Results based on test coupons have been found to be unreliable in determining the degree to which the actual Boraflex panels have been degraded. Therefore, this AMP includes: (1) performing neutron attenuation testing, called blackness testing, to determine gap formation in Boraflex panels; (2) completing sampling and analysis for silica levels in the spent fuel pool water and trending the results by using the EPRI RACKLIFE predictive code or its equivalent on a monthly, quarterly, or annual basis (depending on Boraflex panel condition); and (3) measuring boron areal density by techniques such as the BADGER device. Corrective actions are initiated if the test results find that the 5% subcriticality margin cannot be maintained because of current or projected future Boraflex XI.M22 Boraflex Monitoring 1 |
| Comment:
| |
| XI.M22 Boraflex Monitoring 2 Program Element Auditable GALL Criteria Documentation of Audit Finding degradation. 1. Scope of Program A. The AMP manages the effects of aging on sheets of neutron-absorbing materials affixed to spent fuel racks. For Boraflex panels, gamma irradiation and long-term exposure to the wet pool environment cause shrinkage resulting in gap formation, gradual degradation of the polymer matrix, and the release of silica to the spent fuel storage pool water. This results in the loss of boron carbide in the neutron absorber sheets. Consistent with GALL AMP: | |
| Yes No Document(s) used to confirm Criteria:
| |
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| |
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| Comment: 2. Preventive Actions A. For Boraflex panels, monitoring silica levels in the storage pool water, measuring gap formation by blackness testing, periodically measuring boron areal density, and applying predictive codes, are performed. These actions ensure that degradation of the neutron-absorbing material is identified and corrected so the spent fuel storage racks will be capable of performing their intended functions during the period of extended operation, consistent with current licensing basis (CLB) design conditions. Consistent with GALL AMP: | | Program Auditable GALL Criteria Documentation of Audit Finding Element degradation. |
| Yes No Document(s) used to confirm Criteria:
| | : 1. Scope of A. The AMP manages the effects of aging on sheets of neutron- Consistent with GALL AMP: Yes No Program absorbing materials affixed to spent fuel racks. For Boraflex Document(s) used to confirm Criteria: |
| | | panels, gamma irradiation and long-term exposure to the wet pool environment cause shrinkage resulting in gap formation, gradual degradation of the polymer matrix, and the release of silica to the spent fuel storage pool water. This results in the Comment: |
| Comment: 3. Parameters Monitored/ Inspected A. The parameters monitored include physical conditions of the Boraflex panels, such as gap formation and decreased boron areal density, and the concentration of the silica in the spent fuel pool. These are conditions directly related to degradation of the Boraflex material. When Boraflex is subjected to gamma radiation and long-term exposure to the spent fuel pool environment, the silicon polymer matrix becomes degraded and silica filler and boron carbide are released into the spent fuel pool water. As indicated in the Nuclear Regulatory Commission (NRC) Information Notice (IN) 95-38 and NRC Generic Letter (GL) 96-04, the loss of boron carbide (washout) from Boraflex is characterized by slow dissolution of silica from the surface of the Boraflex and a gradual thinning of the material. Because Boraflex contains about 25% silica, 25% polydimethyl siloxane polymer, and 50% boron carbide, sampling and analysis of the presence of silica in the spent fuel pool provide an indication of depletion of boron carbide from Boraflex; however, the degree Consistent with GALL AMP:
| | loss of boron carbide in the neutron absorber sheets. |
| Yes No Document(s) used to confirm Criteria:
| | : 2. Preventive A. For Boraflex panels, monitoring silica levels in the storage Consistent with GALL AMP: Yes No Actions pool water, measuring gap formation by blackness testing, Document(s) used to confirm Criteria: |
| | periodically measuring boron areal density, and applying predictive codes, are performed. These actions ensure that degradation of the neutron-absorbing material is identified and corrected so the spent fuel storage racks will be capable of Comment: |
| | performing their intended functions during the period of extended operation, consistent with current licensing basis (CLB) design conditions. |
| | : 3. Parameters A. The parameters monitored include physical conditions of the Consistent with GALL AMP: Yes No Monitored/ Boraflex panels, such as gap formation and decreased boron Document(s) used to confirm Criteria: |
| | Inspected areal density, and the concentration of the silica in the spent fuel pool. These are conditions directly related to degradation of the Boraflex material. When Boraflex is subjected to gamma radiation and long-term exposure to the spent fuel pool Comment: |
| | environment, the silicon polymer matrix becomes degraded and silica filler and boron carbide are released into the spent fuel pool water. As indicated in the Nuclear Regulatory Commission (NRC) Information Notice (IN) 95-38 and NRC Generic Letter (GL) 96-04, the loss of boron carbide (washout) from Boraflex is characterized by slow dissolution of silica from the surface of the Boraflex and a gradual thinning of the material. Because Boraflex contains about 25% silica, 25% polydimethyl siloxane polymer, and 50% boron carbide, sampling and analysis of the presence of silica in the spent fuel pool provide an indication of depletion of boron carbide from Boraflex; however, the degree XI.M22 Boraflex Monitoring 2 |
|
| |
|
| | Program Auditable GALL Criteria Documentation of Audit Finding Element to which Boraflex has degraded is ascertained through measurement of the boron areal density. |
| | : 4. Detection of A. The amount of boron carbide released from the Boraflex Consistent with GALL AMP: Yes No Aging Effects panel is determined through direct measurement of boron areal Document(s) used to confirm Criteria: |
| | density and correlated with the levels of silica present with a predictive code. This is supplemented with detection of gaps through blackness testing and periodic verification of boron loss through areal density measurement techniques such as the Comment: |
| | BADGER device. |
| | : 5. Monitoring A. The periodic inspection measurements and analysis are to be Consistent with GALL AMP: Yes No and Trending compared to values of previous measurements and analysis to Document(s) used to confirm Criteria: |
| | provide a continuing level of data for trend analysis. |
| | Comment: |
| | : 6. Acceptance A. The 5% subcriticality margin of the spent fuel racks is to be Consistent with GALL AMP: Yes No Criteria maintained for the period of extended operation. Document(s) used to confirm Criteria: |
| Comment: | | Comment: |
| XI.M22 Boraflex Monitoring 3 Program Element Auditable GALL Criteria Documentation of Audit Finding to which Boraflex has degraded is ascertained through measurement of the boron areal density. 4. Detection of Aging Effects A. The amount of boron carbide released from the Boraflex panel is determined through direct measurement of boron areal density and correlated with the levels of silica present with a predictive code. This is supplemented with detection of gaps through blackness testing and periodic verification of boron loss through areal density measurement techniques such as the BADGER device. Consistent with GALL AMP:
| | : 7. Corrective A. Corrective actions are initiated if the test results find that the Consistent with GALL AMP: Yes No Actions 5% subcriticality margin cannot be maintained because of the Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | current or projected future degradation. Corrective actions consist of providing additional neutron-absorbing capacity by Boral or boron steel inserts, or other options, which are available to maintain a subcriticality margin of 5%. As discussed Comment: |
| Comment: 5. Monitoring and Trending A. The periodic inspection measurements and analysis are to be compared to values of previous measurements and analysis to provide a continuing level of data for trend analysis. Consistent with GALL AMP:
| | in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the corrective actions. |
| Yes No Document(s) used to confirm Criteria:
| | : 8. A. Site quality assurance (QA) procedures, site review and Consistent with GALL AMP: Yes No Confirmation approval processes, and administrative controls are Document(s) used to confirm Criteria: |
| Comment: 6. Acceptance Criteria A. The 5% subcriticality margin of the spent fuel racks is to be maintained for the period of extended operation. Consistent with GALL AMP:
| | Process implemented in accordance with the requirements of 10 CFR XI.M22 Boraflex Monitoring 3 |
| Yes No Document(s) used to confirm Criteria: | |
|
| |
|
| Comment: 7. Corrective Actions A. Corrective actions are initiated if the test results find that the 5% subcriticality margin cannot be maintained because of the current or projected future degradation. Corrective actions consist of providing additional neutron-absorbing capacity by Boral or boron steel inserts, or other options, which are available to maintain a subcriticality margin of 5%. 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:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element 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 Comment: |
| Yes No Document(s) used to confirm Criteria: | | and administrative controls. |
| | : 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 NRC IN 87-43 addresses the problems of development Consistent with GALL AMP: Yes No Experience of tears and gaps (average 1-2 in., with the largest 4 in.) in Document(s) used to confirm Criteria: |
| | Boraflex sheets due to gamma radiation-induced shrinkage of the material. NRC INs 93-70 and 95-38 and NRC GL 96-04 address several cases of significant degradation of Boraflex test coupons due to accelerated dissolution of Boraflex caused by Comment: |
| | pool water flow through panel enclosures and high accumulated gamma dose. Two spent fuel rack cells with about 12 years of service have only 40% of the Boraflex remaining. In such cases, the Boraflex may be replaced by boron steel inserts or by a completely new rack system using Boral. Experience with boron steel is limited; however, the application of Boral for use in the spent fuel storage racks predates the manufacturing and use of Boraflex. The experience with Boraflex panels indicates that coupon surveillance programs are not reliable. Therefore, during the period of extended operation, the measurement of boron areal density correlated, through a predictive code, with silica levels in the pool water is verified. These monitoring programs provide assurance that degradation of Boraflex sheets is monitored, so that appropriate actions can be taken in a timely manner if significant loss of neutron-absorbing capability is occurring. These monitoring programs ensure that the Boraflex sheets will maintain their integrity and will be effective in performing its intended function. |
| | XI.M22 Boraflex Monitoring 4 |
|
| |
|
| Comment: 8. Confirmation Process A. Site quality assurance (QA) procedures, site review and approval processes, and administrative controls are implemented in accordance with the requirements of 10 CFR Consistent with GALL AMP:
| | EXCEPTIONS Item Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| Yes No Document(s) used to confirm Criteria:
| | 1. |
| | 2. |
|
| |
|
| XI.M22 Boraflex Monitoring 4 Program Element Auditable GALL Criteria Documentation of Audit Finding 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.
| | ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| Comment: 9. 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 NRC IN 87-43 addresses the problems of development of tears and gaps (average 1-2 in., with the largest 4 in.) in Boraflex sheets due to gamma radiation-induced shrinkage of the material. NRC INs 93-70 and 95-38 and NRC GL 96-04 address several cases of significant degradation of Boraflex test coupons due to accelerated dissolution of Boraflex caused by pool water flow through panel enclosures and high accumulated gamma dose. Two spent fuel rack cells with about 12 years of service have only 40% of the Boraflex remaining. In such cases, the Boraflex may be replaced by boron steel inserts or by a completely new rack system using Boral. Experience with boron steel is limited; however, the application of Boral for use in the spent fuel storage racks predates the manufacturing and use of Boraflex. The experience with Boraflex panels indicates that coupon surveillance programs are not reliable. Therefore, during the period of extended operation, the measurement of boron areal density correlated, through a predictive code, with silica levels in the pool water is verified. These monitoring programs provide assurance that degradation of Boraflex sheets is monitored, so that appropriate actions can be taken in a timely manner if significant loss of neutron-absorbing capability is occurring. These monitoring programs ensure that the Boraflex sheets will maintain their integrity and will be effective in performing its intended function. 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.M22 Boraflex Monitoring 5 EXCEPTIONS Item Number Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| | XI.M22 Boraflex Monitoring 5}} |
| 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] |
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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
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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
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BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan2006-03-26026 March 2006
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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)
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GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP)
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GALL AMP: XI.M1, ASME Section XI Inservice Inspection, Subsections Iwb, Iwc, and Iwd (Audit Worksheet, GALL Report AMP)
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GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP)
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GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP)
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GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP)
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GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP)
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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)
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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.M22, Boraflex Monitoring DATE: __________________________
Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. A Boraflex monitoring program for the actual Boraflex panels Consistent with GALL AMP: Yes No Description is implemented in the spent fuel racks to assure that no Document(s) used to confirm Criteria:
unexpected degradation of the Boraflex material would compromise the criticality analysis in support of the design of spent fuel storage racks. The applicable aging management program (AMP), based on manufacturers recommendations, Comment:
relies on periodic inspection, testing, monitoring, and analysis of the criticality design to assure that the required 5% subcriticality margin is maintained. The frequency of the inspection and testing depends on the condition of the Boraflex, with a maximum of five years. Certain accelerated samples are tested every two years. Results based on test coupons have been found to be unreliable in determining the degree to which the actual Boraflex panels have been degraded. Therefore, this AMP includes: (1) performing neutron attenuation testing, called blackness testing, to determine gap formation in Boraflex panels; (2) completing sampling and analysis for silica levels in the spent fuel pool water and trending the results by using the EPRI RACKLIFE predictive code or its equivalent on a monthly, quarterly, or annual basis (depending on Boraflex panel condition); and (3) measuring boron areal density by techniques such as the BADGER device. Corrective actions are initiated if the test results find that the 5% subcriticality margin cannot be maintained because of current or projected future Boraflex XI.M22 Boraflex Monitoring 1
Program Auditable GALL Criteria Documentation of Audit Finding Element degradation.
- 1. Scope of A. The AMP manages the effects of aging on sheets of neutron- Consistent with GALL AMP: Yes No Program absorbing materials affixed to spent fuel racks. For Boraflex Document(s) used to confirm Criteria:
panels, gamma irradiation and long-term exposure to the wet pool environment cause shrinkage resulting in gap formation, gradual degradation of the polymer matrix, and the release of silica to the spent fuel storage pool water. This results in the Comment:
loss of boron carbide in the neutron absorber sheets.
- 2. Preventive A. For Boraflex panels, monitoring silica levels in the storage Consistent with GALL AMP: Yes No Actions pool water, measuring gap formation by blackness testing, Document(s) used to confirm Criteria:
periodically measuring boron areal density, and applying predictive codes, are performed. These actions ensure that degradation of the neutron-absorbing material is identified and corrected so the spent fuel storage racks will be capable of Comment:
performing their intended functions during the period of extended operation, consistent with current licensing basis (CLB) design conditions.
- 3. Parameters A. The parameters monitored include physical conditions of the Consistent with GALL AMP: Yes No Monitored/ Boraflex panels, such as gap formation and decreased boron Document(s) used to confirm Criteria:
Inspected areal density, and the concentration of the silica in the spent fuel pool. These are conditions directly related to degradation of the Boraflex material. When Boraflex is subjected to gamma radiation and long-term exposure to the spent fuel pool Comment:
environment, the silicon polymer matrix becomes degraded and silica filler and boron carbide are released into the spent fuel pool water. As indicated in the Nuclear Regulatory Commission (NRC) Information Notice (IN) 95-38 and NRC Generic Letter (GL) 96-04, the loss of boron carbide (washout) from Boraflex is characterized by slow dissolution of silica from the surface of the Boraflex and a gradual thinning of the material. Because Boraflex contains about 25% silica, 25% polydimethyl siloxane polymer, and 50% boron carbide, sampling and analysis of the presence of silica in the spent fuel pool provide an indication of depletion of boron carbide from Boraflex; however, the degree XI.M22 Boraflex Monitoring 2
Program Auditable GALL Criteria Documentation of Audit Finding Element to which Boraflex has degraded is ascertained through measurement of the boron areal density.
- 4. Detection of A. The amount of boron carbide released from the Boraflex Consistent with GALL AMP: Yes No Aging Effects panel is determined through direct measurement of boron areal Document(s) used to confirm Criteria:
density and correlated with the levels of silica present with a predictive code. This is supplemented with detection of gaps through blackness testing and periodic verification of boron loss through areal density measurement techniques such as the Comment:
BADGER device.
- 5. Monitoring A. The periodic inspection measurements and analysis are to be Consistent with GALL AMP: Yes No and Trending compared to values of previous measurements and analysis to Document(s) used to confirm Criteria:
provide a continuing level of data for trend analysis.
Comment:
- 6. Acceptance A. The 5% subcriticality margin of the spent fuel racks is to be Consistent with GALL AMP: Yes No Criteria maintained for the period of extended operation. Document(s) used to confirm Criteria:
Comment:
- 7. Corrective A. Corrective actions are initiated if the test results find that the Consistent with GALL AMP: Yes No Actions 5% subcriticality margin cannot be maintained because of the Document(s) used to confirm Criteria:
current or projected future degradation. Corrective actions consist of providing additional neutron-absorbing capacity by Boral or boron steel inserts, or other options, which are available to maintain a subcriticality margin of 5%. As discussed Comment:
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. Site quality assurance (QA) procedures, site review and Consistent with GALL AMP: Yes No Confirmation approval processes, and administrative controls are Document(s) used to confirm Criteria:
Process implemented in accordance with the requirements of 10 CFR XI.M22 Boraflex Monitoring 3
Program Auditable GALL Criteria Documentation of Audit Finding Element 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 Comment:
and administrative controls.
- 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 NRC IN 87-43 addresses the problems of development Consistent with GALL AMP: Yes No Experience of tears and gaps (average 1-2 in., with the largest 4 in.) in Document(s) used to confirm Criteria:
Boraflex sheets due to gamma radiation-induced shrinkage of the material. NRC INs 93-70 and 95-38 and NRC GL 96-04 address several cases of significant degradation of Boraflex test coupons due to accelerated dissolution of Boraflex caused by Comment:
pool water flow through panel enclosures and high accumulated gamma dose. Two spent fuel rack cells with about 12 years of service have only 40% of the Boraflex remaining. In such cases, the Boraflex may be replaced by boron steel inserts or by a completely new rack system using Boral. Experience with boron steel is limited; however, the application of Boral for use in the spent fuel storage racks predates the manufacturing and use of Boraflex. The experience with Boraflex panels indicates that coupon surveillance programs are not reliable. Therefore, during the period of extended operation, the measurement of boron areal density correlated, through a predictive code, with silica levels in the pool water is verified. These monitoring programs provide assurance that degradation of Boraflex sheets is monitored, so that appropriate actions can be taken in a timely manner if significant loss of neutron-absorbing capability is occurring. These monitoring programs ensure that the Boraflex sheets will maintain their integrity and will be effective in performing its intended function.
XI.M22 Boraflex Monitoring 4
EXCEPTIONS Item Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed Number (Identifier, Para.# and/or Page #)
1.
2.
ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #)
1.
2.
DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1.
2.
3.
4.
XI.M22 Boraflex Monitoring 5
