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| {{#Wiki_filter:XI.M15 Neutron Noise 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.M15, Neutron Noise Monitoring DATE: __________________________ |
| GALL AMP: XI.M15, Neutron Noise Monitoring DATE: __________________________ | | Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. The program relies on monitoring the excore neutron detector Consistent with GALL AMP: Yes No Description signals due to core motion to detect and monitor significant loss Document(s) used to confirm Criteria: |
| Program Element Auditable GALL Criteria Documentation of Audit Finding Program Description A. The program relies on monitoring the excore neutron detector signals due to core motion to detect and monitor significant loss of axial preload at the core support barrel's upper support flange in pressurized water reactors (PWRs). This inservice monitoring program is based on the recommendations from the American Society of Mechanical Engineers operation and maintenance standards and guides (ASME OM-S/G)-1997, Part 5, "Inservice Monitoring of Core Support Barrel Axial Preload in Pressurized Water Reactors Power Plants." Consistent with GALL AMP: | | of axial preload at the core support barrels upper support flange in pressurized water reactors (PWRs). This inservice monitoring program is based on the recommendations from the American Society of Mechanical Engineers operation and maintenance Comment: |
| Yes No Document(s) used to confirm Criteria: | | standards and guides (ASME OM-S/G)-1997, Part 5, Inservice Monitoring of Core Support Barrel Axial Preload in Pressurized Water Reactors Power Plants. |
| | : 1. Scope of A. The program includes measures to monitor and detect loss of Consistent with GALL AMP: Yes No Program axial preload (loss of axial restraint) at the core support barrels Document(s) used to confirm Criteria: |
| | upper support flange in PWRs. The loss of axial restraint may arise from long-term changes resulting from abnormal wear at the reactor vessel core barrel mating surface or short-term changes due to improper installation of the reactor internals. Comment The program also includes guidelines for further data acquisition that may be needed to define future plant operation and/or program plans in order to maintain the capability of the structure/components to perform the intended function. |
| | : 2. Preventive A. The program is a monitoring/detection program that provides Consistent with GALL AMP: Yes No Actions early indication and detection of the onset of aging degradation Document(s) used to confirm Criteria: |
| | of the core support barrelhold-down mechanism prior to a scheduled shutdown, thus reducing outage time and avoiding potential damage to the core support barrel and fuel assemblies. The AMP does not rely on preventive actions. Comment: |
| | XI.M15 Neutron Noise Monitoring 1 |
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| Comment: 1. Scope of Program A. The program includes measures to monitor and detect loss of axial preload (loss of axial restraint) at the core support barrel's upper support flange in PWRs. The loss of axial restraint may arise from long-term changes resulting from abnormal wear at the reactor vessel core barrel mating surface or short-term changes due to improper installation of the reactor internals. The program also includes guidelines for further data acquisition that may be needed to define future plant operation and/or program plans in order to maintain the capability of the structure/components to perform the intended function. Consistent with GALL AMP:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element |
| Yes No Document(s) used to confirm Criteria: | | : 3. Parameters A. The program relies on the use of excore neutron detector Consistent with GALL AMP: Yes No Monitored/ signals to provide information on the conditions of the axial Document(s) used to confirm Criteria: |
| Comment 2. Preventive Actions A. The program is a monitoring/detection program that provides early indication and detection of the onset of aging degradation of the core support barrelhold-down mechanism prior to a scheduled shutdown, thus reducing outage time and avoiding potential damage to the core support barrel and fuel assemblies. The AMP does not rely on preventive actions. Consistent with GALL AMP:
| | Inspected preload. The excore neutron flux signal is composed of a steady state, direct current (DC) component that arises from the neutron flux produced by the power operation of the reactor, as well as a fluctuating (noise-like) component. This fluctuating Comment: |
| Yes No Document(s) used to confirm Criteria:
| | signal arises from the core reactivity changes due to lateral core motion from the loss of axial preload. This core motion is mainly the result of beam mode vibration of the core support barrel. |
| | Despite the fact that this beam mode vibration provides only a very weak neutron noise source, it may be reliably detected and identified through Fourier Analysis of the fluctuating signal component of the excore neutron flux signal. This signal component has the characteristics of having 180-degree shifts and a high degree of coherence between signals obtained from pairs of excore neutron detectors that are positioned on diametrically opposite sides of the core. The neutron noise signals are characterized by parameters, which include the auto correlation, cross correlation, coherence, and phase. These parameters are to be monitored and evaluated. |
| | : 4. Detection of A. Flow-induced vibration of the core support barrel will change Consistent with GALL AMP: Yes No Aging Effects the thickness of the downcomer annulus (water gap). This Document(s) used to confirm Criteria: |
| | variation in the thickness will give rise to fluctuating changes in the neutron flux, as monitored by the excore neutron detectors. |
| | The natural frequencies and the amplitudes of the vibratory motion of the core barrel are related to the effective axial Comment: |
| | preload at the upper support flange of the core support barrel. |
| | Monitoring of the neutron noise signal obtained with the neutron flux detectors located around the external periphery of the reactor vessel provides detection of anomalous vibrational motion of the core support barrel, and hence significant loss of the axial preload. Decrease in the axial preload leads to decreases in the core support barrel beam mode frequency and an increase in the magnitude of the noise signal. The overall XI.M15 Neutron Noise Monitoring 2 |
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| Comment:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element effect of a decrease in the axial preload is to shift the neutron noise power spectrum toward larger amplitudes for the lower frequency region. |
| XI.M15 Neutron Noise Monitoring 2 Program Element Auditable GALL Criteria Documentation of Audit Finding 3. Parameters Monitored/ Inspected A. The program relies on the use of excore neutron detector signals to provide information on the conditions of the axial preload. The excore neutron flux signal is composed of a steady state, direct current (DC) component that arises from the neutron flux produced by the power operation of the reactor, as well as a fluctuating (noise-like) component. This fluctuating signal arises from the core reactivity changes due to lateral core motion from the loss of axial preload. This core motion is mainly the result of beam mode vibration of the core support barrel. Despite the fact that this beam mode vibration provides only a very weak neutron noise source, it may be reliably detected and identified through Fourier Analysis of the fluctuating signal component of the excore neutron flux signal. This signal component has the characteristics of having 180-degree shifts and a high degree of coherence between signals obtained from pairs of excore neutron detectors that are positioned on diametrically opposite sides of the core. The neutron noise signals are characterized by parameters, which include the auto correlation, cross correlation, coherence, and phase. These parameters are to be monitored and evaluated. Consistent with GALL AMP:
| | : 5. Monitoring A. The neutron noise random fluctuation in the signals from the Consistent with GALL AMP: Yes No and Trending excore detectors are monitored, recorded, and analyzed to Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | identify changes in the beam mode natural frequency of the core support barrel and its direction of motion for the purpose of a timely determination of the need and urgency for a detailed inspection and examination of the reactor vessel internals hold- Comment: |
| Comment: 4. Detection of Aging Effects A. Flow-induced vibration of the core support barrel will change the thickness of the downcomer annulus (water gap). This variation in the thickness will give rise to fluctuating changes in the neutron flux, as monitored by the excore neutron detectors. The natural frequencies and the amplitudes of the vibratory motion of the core barrel are related to the effective axial preload at the upper support flange of the core support barrel. Monitoring of the neutron noise signal obtained with the neutron flux detectors located around the external periphery of the reactor vessel provides detection of anomalous vibrational motion of the core support barrel, and hence significant loss of the axial preload. Decrease in the axial preload leads to decreases in the core support barrel beam mode frequency and an increase in the magnitude of the noise signal. The overall Consistent with GALL AMP:
| | down mechanism and mating component surfaces. These activities and analytical methodology are performed, and associated personnel are qualified, in accordance with site-controlled procedures and processes as indicated by vendor, industry, or regulatory guidance documents. |
| Yes No Document(s) used to confirm Criteria: | | The neutron noise monitoring program has three separate phases: a baseline phase, a surveillance phase, and a diagnostic phase. The baseline phase establishes the database to be used as a reference for developing limits and trends in the surveillance phase and to support data evaluation and interpretation in the diagnostic phase. During the baseline phase, data on the time history and DC level of each neutron flux detector and each cross-core detector pair are obtained. |
| | From this database, the characteristic amplitudes and frequencies of the core barrel motion are extracted. The wide and narrow frequency bands with their associated normalized root mean square (NRMS) values are established. The ASME-OMS/G-1997, Part 5, recommends collecting the baseline data during the first fuel cycle that the neutron noise monitoring program is applied to an already operating plant. Whenever XI.M15 Neutron Noise Monitoring 3 |
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| | Program Auditable GALL Criteria Documentation of Audit Finding Element significant changes takes place for the core, reactor internals, or operating conditions, additional baseline data is obtained. |
| | B. In the surveillance phase, routine neutron noise monitoring of Consistent with GALL AMP: Yes No normal plant operations is performed over the life of the plant. Document(s) used to confirm Criteria: |
| | The DC level and data for frequency analysis of each detector and two pair of cross-core detectors, may be collected. |
| | Comparisons of the measured amplitude and frequency data, with limits established from the baseline data, are made. In Comment: |
| | using neutron noise monitoring, accounts are taken of the effect of core burn-up, decreasing boron concentration, changes in fuel management, and in-core contact with the reactor vessel mechanical snubbers, which may affect the neutron noise signatures. Proper allowances for these factors during the baseline and surveillance phases will help toward detecting loss of axial preload before the core barrel becomes sufficiently free to wear against the reactor vessel and will also reduce the need to invoke the diagnostic phase. |
| | C. If the diagnostic phase becomes necessary, then evaluations Consistent with GALL AMP: Yes No are carried out to establish whether any deviations from the Document(s) used to confirm Criteria: |
| | baseline data detected during the surveillance phase arises from core barrel motion due to loss of axial preload. The need and frequency of additional data collection on the time history and DC level of each neutron flux detector and each cross-core Comment: |
| | detector pair collection are guided by the results of these evaluations. |
| | XI.M15 Neutron Noise Monitoring 4 |
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| | Program Auditable GALL Criteria Documentation of Audit Finding Element |
| | : 6. Acceptance A. If evaluation of the baseline data indicates normal operation Consistent with GALL AMP: Yes No Criteria for the applicable structure/component, the surveillance phase Document(s) used to confirm Criteria: |
| | may commence. If evaluation indicates anomalous behavior, the monitoring program enters the diagnostic phase. |
| Comment: | | Comment: |
| XI.M15 Neutron Noise Monitoring 3 Program Element Auditable GALL Criteria Documentation of Audit Finding effect of a decrease in the axial preload is to shift the neutron noise power spectrum toward larger amplitudes for the lower frequency region. 5. Monitoring and Trending A. The neutron noise random fluctuation in the signals from the excore detectors are monitored, recorded, and analyzed to identify changes in the beam mode natural frequency of the core support barrel and its direction of motion for the purpose of a timely determination of the need and urgency for a detailed inspection and examination of the reactor vessel internals hold-down mechanism and mating component surfaces. These activities and analytical methodology are performed, and associated personnel are qualified, in accordance with site-controlled procedures and processes as indicated by vendor, industry, or regulatory guidance documents. The neutron noise monitoring program has three separate phases: a baseline phase, a surveillance phase, and a diagnostic phase. The baseline phase establishes the database to be used as a reference for developing limits and trends in the surveillance phase and to support data evaluation and interpretation in the diagnostic phase. During the baseline phase, data on the time history and DC level of each neutron flux detector and each cross-core detector pair are obtained.
| | B. During the surveillance phase, if deviations from the baseline Consistent with GALL AMP: Yes No fall within predetermined acceptable limits, the surveillance will Document(s) used to confirm Criteria: |
| From this database, the characteristic amplitudes and frequencies of the core barrel motion are extracted. The wide and narrow frequency bands with their associated normalized root mean square (NRMS) values are established. The ASME-OMS/G-1997, Part 5, recommends collecting the baseline data during the first fuel cycle that the neutron noise monitoring program is applied to an already operating plant. Whenever Consistent with GALL AMP:
| | continue. Otherwise, the diagnostic phase will commence. |
| Yes No Document(s) used to confirm Criteria: | |
| | |
| Comment: | | Comment: |
| XI.M15 Neutron Noise Monitoring 4 Program Element Auditable GALL Criteria Documentation of Audit Finding significant changes takes place for the core, reactor internals, or operating conditions, additional baseline data is obtained. " B. In the surveillance phase, routine neutron noise monitoring of normal plant operations is performed over the life of the plant. The DC level and data for frequency analysis of each detector and two pair of cross-core detectors, may be collected. Comparisons of the measured amplitude and frequency data, with limits established from the baseline data, are made. In using neutron noise monitoring, accounts are taken of the effect of core burn-up, decreasing boron concentration, changes in fuel management, and in-core contact with the reactor vessel mechanical snubbers, which may affect the neutron noise signatures. Proper allowances for these factors during the baseline and surveillance phases will help toward detecting loss of axial preload before the core barrel becomes sufficiently free to wear against the reactor vessel and will also reduce the need to invoke the diagnostic phase. Consistent with GALL AMP:
| | : 7. Corrective A. Initial results from the diagnostic phase of the program may Consistent with GALL AMP: Yes No Actions be used to determine whether there is a need to increase the Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | minimum frequency with which the surveillance data are acquired. In addition, if necessary, corrective actions may be taken to change the type of data acquisition and analysis from that previously recommended for the surveillance part of the Comment: |
| | | program. The data trends may be established to guide further data acquisition that may be needed to define future plant operation and/or program plans. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the corrective actions. |
| Comment: " C. If the diagnostic phase becomes necessary, then evaluations are carried out to establish whether any deviations from the baseline data detected during the surveillance phase arises from core barrel motion due to loss of axial preload. The need and frequency of additional data collection on the time history and DC level of each neutron flux detector and each cross-core detector pair collection are guided by the results of these evaluations. Consistent with GALL AMP:
| | : 8. A. Site quality assurance (QA) procedures, review and approval Consistent with GALL AMP: Yes No Confirmation processes, and administrative controls are implemented in Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | Process accordance with the requirements of 10 CFR Part 50, Appendix B. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the confirmation process and administrative controls. Comment: |
| | : 9. A. See Item 8, above. Consistent with GALL AMP: Yes No Administrative Document(s) used to confirm Criteria: |
| | Controls XI.M15 Neutron Noise Monitoring 5 |
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| Comment:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element Comment: |
| XI.M15 Neutron Noise Monitoring 5 Program Element Auditable GALL Criteria Documentation of Audit Finding 6. Acceptance Criteria A. If evaluation of the baseline data indicates normal operation for the applicable structure/component, the surveillance phase may commence. If evaluation indicates anomalous behavior, the monitoring program enters the diagnostic phase. Consistent with GALL AMP:
| | : 10. Operating A. The neutron noise monitoring program and procedures were Consistent with GALL AMP: Yes No Experience developed by the industry and published as a guide in ASME Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | OM-S/G-1997, Part 5, an American National Standard. This monitoring program and procedures have been effective in limited industry use for monitoring and detecting loss of core support barrel axial preload in PWR power plants. Comment: |
| Comment: " B. During the surveillance phase, if deviations from the baseline fall within predetermined acceptable limits, the surveillance will continue. Otherwise, the diagnostic phase will commence. Consistent with GALL AMP:
| | XI.M15 Neutron Noise Monitoring 6 |
| Yes No Document(s) used to confirm Criteria:
| |
| Comment: 7. Corrective Actions A. Initial results from the diagnostic phase of the program may be used to determine whether there is a need to increase the minimum frequency with which the surveillance data are acquired. In addition, if necessary, corrective actions may be taken to change the type of data acquisition and analysis from that previously recommended for the surveillance part of the program. The data trends may be established to guide further data acquisition that may be needed to define future plant operation and/or program plans. 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:
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| 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. Site quality assurance (QA) procedures, review and approval processes, and administrative controls are implemented in accordance with the requirements of 10 CFR Part 50, Appendix B. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the confirmation process and administrative controls. Consistent with GALL AMP:
| | 1. |
| Yes No Document(s) used to confirm Criteria:
| | 2. |
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| Comment: 9.
| | ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| Administrative Controls A. See Item 8, above. Consistent with GALL AMP:
| | 1. |
| Yes No Document(s) used to confirm Criteria:
| | 2. |
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| XI.M15 Neutron Noise Monitoring 6 Program Element Auditable GALL Criteria Documentation of Audit Finding Comment: 10. Operating Experience A. The neutron noise monitoring program and procedures were developed by the industry and published as a guide in ASME OM-S/G-1997, Part 5, an American National Standard. This monitoring program and procedures have been effective in limited industry use for monitoring and detecting loss of core support barrel axial preload in PWR power plants. 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. |
| Comment:
| | 3. |
| XI.M15 Neutron Noise Monitoring 7 EXCEPTIONS Item Number Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| | 4. |
| 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. -.}} | | XI.M15 Neutron Noise Monitoring 7}} |
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 ML0609506372006-03-22022 March 2006 GALL AMP: XI.M36, External Surfaces Monitoring (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 ML0609506322006-03-22022 March 2006 GALL AMP: XI.M34, Buried Piping and Tanks Inspection (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 ML0609506202006-03-22022 March 2006 GALL AMP: XI.M31, Reactor Vessel Surveillance (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 ML0609505962006-03-22022 March 2006 GALL AMP: XI.M27, Fire Water System (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 ML0609505822006-03-22022 March 2006 GALL AMP: XI.M25, BWR Reactor Water Cleanup System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505792006-03-22022 March 2006 GALL AMP: XI.M24, Compressed Air Monitoring (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 ML0609505402006-03-22022 March 2006 GALL AMP: XI.M18, Bolting Integrity (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 ML0609502182006-03-22022 March 2006 GALL AMP: X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary (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 ML0610001472006-03-22022 March 2006 GALL AMP: XI.S8, Protective Coating Monitoring and Maintenance Program (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 ML0610001382006-03-22022 March 2006 GALL AMP: XI.S6, Structures Monitoring 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 ML0610001262006-03-22022 March 2006 GALL AMP: XI.S4, 10 CFR 50, Appendix J (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 ML0610000962006-03-22022 March 2006 GALL AMP: XI.S1, ASME Section XI, Subsection IWE (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503232006-03-22022 March 2006 GALL AMP: XI.M8, BWR Penetrations (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 ML0609503012006-03-22022 March 2006 GALL AMP: XI.M6, BWR Control Rod Drive Return Line Nozzle (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 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 ML0609503722006-03-22022 March 2006 GALL AMP: XI.M16, PWR Vessel Internals (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 ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (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 ML0609505672006-03-22022 March 2006 GALL AMP: XI.M21, Closed-Cycle Cooling Water System (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 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 ML0609506062006-03-22022 March 2006 GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (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 ML0609506242006-03-22022 March 2006 GALL AMP: XI.M32, One-Time Inspection (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 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) 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 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 ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (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 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 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 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 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.M15, Neutron Noise Monitoring DATE: __________________________
Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. The program relies on monitoring the excore neutron detector Consistent with GALL AMP: Yes No Description signals due to core motion to detect and monitor significant loss Document(s) used to confirm Criteria:
of axial preload at the core support barrels upper support flange in pressurized water reactors (PWRs). This inservice monitoring program is based on the recommendations from the American Society of Mechanical Engineers operation and maintenance Comment:
standards and guides (ASME OM-S/G)-1997, Part 5, Inservice Monitoring of Core Support Barrel Axial Preload in Pressurized Water Reactors Power Plants.
- 1. Scope of A. The program includes measures to monitor and detect loss of Consistent with GALL AMP: Yes No Program axial preload (loss of axial restraint) at the core support barrels Document(s) used to confirm Criteria:
upper support flange in PWRs. The loss of axial restraint may arise from long-term changes resulting from abnormal wear at the reactor vessel core barrel mating surface or short-term changes due to improper installation of the reactor internals. Comment The program also includes guidelines for further data acquisition that may be needed to define future plant operation and/or program plans in order to maintain the capability of the structure/components to perform the intended function.
- 2. Preventive A. The program is a monitoring/detection program that provides Consistent with GALL AMP: Yes No Actions early indication and detection of the onset of aging degradation Document(s) used to confirm Criteria:
of the core support barrelhold-down mechanism prior to a scheduled shutdown, thus reducing outage time and avoiding potential damage to the core support barrel and fuel assemblies. The AMP does not rely on preventive actions. Comment:
XI.M15 Neutron Noise Monitoring 1
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 3. Parameters A. The program relies on the use of excore neutron detector Consistent with GALL AMP: Yes No Monitored/ signals to provide information on the conditions of the axial Document(s) used to confirm Criteria:
Inspected preload. The excore neutron flux signal is composed of a steady state, direct current (DC) component that arises from the neutron flux produced by the power operation of the reactor, as well as a fluctuating (noise-like) component. This fluctuating Comment:
signal arises from the core reactivity changes due to lateral core motion from the loss of axial preload. This core motion is mainly the result of beam mode vibration of the core support barrel.
Despite the fact that this beam mode vibration provides only a very weak neutron noise source, it may be reliably detected and identified through Fourier Analysis of the fluctuating signal component of the excore neutron flux signal. This signal component has the characteristics of having 180-degree shifts and a high degree of coherence between signals obtained from pairs of excore neutron detectors that are positioned on diametrically opposite sides of the core. The neutron noise signals are characterized by parameters, which include the auto correlation, cross correlation, coherence, and phase. These parameters are to be monitored and evaluated.
- 4. Detection of A. Flow-induced vibration of the core support barrel will change Consistent with GALL AMP: Yes No Aging Effects the thickness of the downcomer annulus (water gap). This Document(s) used to confirm Criteria:
variation in the thickness will give rise to fluctuating changes in the neutron flux, as monitored by the excore neutron detectors.
The natural frequencies and the amplitudes of the vibratory motion of the core barrel are related to the effective axial Comment:
preload at the upper support flange of the core support barrel.
Monitoring of the neutron noise signal obtained with the neutron flux detectors located around the external periphery of the reactor vessel provides detection of anomalous vibrational motion of the core support barrel, and hence significant loss of the axial preload. Decrease in the axial preload leads to decreases in the core support barrel beam mode frequency and an increase in the magnitude of the noise signal. The overall XI.M15 Neutron Noise Monitoring 2
Program Auditable GALL Criteria Documentation of Audit Finding Element effect of a decrease in the axial preload is to shift the neutron noise power spectrum toward larger amplitudes for the lower frequency region.
- 5. Monitoring A. The neutron noise random fluctuation in the signals from the Consistent with GALL AMP: Yes No and Trending excore detectors are monitored, recorded, and analyzed to Document(s) used to confirm Criteria:
identify changes in the beam mode natural frequency of the core support barrel and its direction of motion for the purpose of a timely determination of the need and urgency for a detailed inspection and examination of the reactor vessel internals hold- Comment:
down mechanism and mating component surfaces. These activities and analytical methodology are performed, and associated personnel are qualified, in accordance with site-controlled procedures and processes as indicated by vendor, industry, or regulatory guidance documents.
The neutron noise monitoring program has three separate phases: a baseline phase, a surveillance phase, and a diagnostic phase. The baseline phase establishes the database to be used as a reference for developing limits and trends in the surveillance phase and to support data evaluation and interpretation in the diagnostic phase. During the baseline phase, data on the time history and DC level of each neutron flux detector and each cross-core detector pair are obtained.
From this database, the characteristic amplitudes and frequencies of the core barrel motion are extracted. The wide and narrow frequency bands with their associated normalized root mean square (NRMS) values are established. The ASME-OMS/G-1997, Part 5, recommends collecting the baseline data during the first fuel cycle that the neutron noise monitoring program is applied to an already operating plant. Whenever XI.M15 Neutron Noise Monitoring 3
Program Auditable GALL Criteria Documentation of Audit Finding Element significant changes takes place for the core, reactor internals, or operating conditions, additional baseline data is obtained.
B. In the surveillance phase, routine neutron noise monitoring of Consistent with GALL AMP: Yes No normal plant operations is performed over the life of the plant. Document(s) used to confirm Criteria:
The DC level and data for frequency analysis of each detector and two pair of cross-core detectors, may be collected.
Comparisons of the measured amplitude and frequency data, with limits established from the baseline data, are made. In Comment:
using neutron noise monitoring, accounts are taken of the effect of core burn-up, decreasing boron concentration, changes in fuel management, and in-core contact with the reactor vessel mechanical snubbers, which may affect the neutron noise signatures. Proper allowances for these factors during the baseline and surveillance phases will help toward detecting loss of axial preload before the core barrel becomes sufficiently free to wear against the reactor vessel and will also reduce the need to invoke the diagnostic phase.
C. If the diagnostic phase becomes necessary, then evaluations Consistent with GALL AMP: Yes No are carried out to establish whether any deviations from the Document(s) used to confirm Criteria:
baseline data detected during the surveillance phase arises from core barrel motion due to loss of axial preload. The need and frequency of additional data collection on the time history and DC level of each neutron flux detector and each cross-core Comment:
detector pair collection are guided by the results of these evaluations.
XI.M15 Neutron Noise Monitoring 4
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 6. Acceptance A. If evaluation of the baseline data indicates normal operation Consistent with GALL AMP: Yes No Criteria for the applicable structure/component, the surveillance phase Document(s) used to confirm Criteria:
may commence. If evaluation indicates anomalous behavior, the monitoring program enters the diagnostic phase.
Comment:
B. During the surveillance phase, if deviations from the baseline Consistent with GALL AMP: Yes No fall within predetermined acceptable limits, the surveillance will Document(s) used to confirm Criteria:
continue. Otherwise, the diagnostic phase will commence.
Comment:
- 7. Corrective A. Initial results from the diagnostic phase of the program may Consistent with GALL AMP: Yes No Actions be used to determine whether there is a need to increase the Document(s) used to confirm Criteria:
minimum frequency with which the surveillance data are acquired. In addition, if necessary, corrective actions may be taken to change the type of data acquisition and analysis from that previously recommended for the surveillance part of the Comment:
program. The data trends may be established to guide further data acquisition that may be needed to define future plant operation and/or program plans. 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. Site quality assurance (QA) procedures, review and approval Consistent with GALL AMP: Yes No Confirmation processes, and administrative controls are implemented in Document(s) used to confirm Criteria:
Process accordance with the requirements of 10 CFR Part 50, Appendix B. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the confirmation process and administrative controls. Comment:
- 9. A. See Item 8, above. Consistent with GALL AMP: Yes No Administrative Document(s) used to confirm Criteria:
Controls XI.M15 Neutron Noise Monitoring 5
Program Auditable GALL Criteria Documentation of Audit Finding Element Comment:
- 10. Operating A. The neutron noise monitoring program and procedures were Consistent with GALL AMP: Yes No Experience developed by the industry and published as a guide in ASME Document(s) used to confirm Criteria:
OM-S/G-1997, Part 5, an American National Standard. This monitoring program and procedures have been effective in limited industry use for monitoring and detecting loss of core support barrel axial preload in PWR power plants. Comment:
XI.M15 Neutron Noise Monitoring 6
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.M15 Neutron Noise Monitoring 7