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| | number = ML060950364 | | | number = ML060950364 |
| | issue date = 03/22/2006 | | | issue date = 03/22/2006 |
| | title = 2006/03/22-GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) | | | title = GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) |
| | author name = Morgan M | | | author name = Morgan M |
| | author affiliation = NRC/NRR/ADRO/DLR/RLRC | | | author affiliation = NRC/NRR/ADRO/DLR/RLRC |
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| {{#Wiki_filter:XI.M14 Loose Part Monitoring 1 AUDIT W ORKSHEET GALL R EPORT AMP PLANT: ______________________________ | | {{#Wiki_filter:AUDIT W ORKSHEET GALL REPORT AMP PLANT: ______________________________ |
| LRA AMP: __________________________ | | LRA AMP: __________________________ REVIEWER: ______________________ |
| R EVIEWER: ______________________
| | GALL AMP: XI.M14, Loose Part Monitoring DATE: __________________________ |
| GALL AMP: XI.M14, Loose Part Monitoring DATE: __________________________ | | Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. The program relies on an inservice monitoring program to Consistent with GALL AMP: Yes No Description detect and monitor loose parts in light-water reactor (LWR) Document(s) used to confirm Criteria: |
| Program Element Auditable GALL Criteria Documentation of Audit Finding Program Description A. The program relies on an inservice monitoring program to detect and monitor loose parts in light-water reactor (LWR) power plants. This in-service loose part monitoring (LPM) 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 12, "Loose Part Monitoring in Light-Water Reactor Power Plants." Consistent with GALL AMP: | | power plants. This in-service loose part monitoring (LPM) 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 12, Loose Comment: |
| Yes No Document(s) used to confirm Criteria: | | Part Monitoring in Light-Water Reactor Power Plants. |
| | : 1. Scope of A. The program includes measures to monitor and detect Consistent with GALL AMP: Yes No Program metallic loose parts by using transient signals analysis on Document(s) used to confirm Criteria: |
| | acoustic data generated due to loose parts impact. The program is applicable, but not necessarily limited to, the reactor vessel and primary coolant systems in pressurized water reactors (PWRs) and the reactor recirculation system in boiling water Comment reactors (BWRs). The detection and monitoring system includes a set of accelerometers installed in the vicinity of regions where loose parts impact is likely to occur. The system incorporates the capability of automatic annunciation (audible and visual), |
| | audio monitoring, automatic and manual signal recording, and acoustic signal analysis/evaluation. Measures for personnel radiation exposure and safety are included as part of the requirements of the LPM system. The objective of the LPM program is to provide early indication of component degradation. |
| | XI.M14 Loose Part Monitoring 1 |
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| Comment: 1. Scope of Program A. The program includes measures to monitor and detect metallic loose parts by using transient signals analysis on acoustic data generated due to loose parts impact. The program is applicable, but not necessarily limited to, the reactor vessel and primary coolant systems in pressurized water reactors (PWRs) and the reactor recirculation system in boiling water reactors (BWRs). The detection and monitoring system includes a set of accelerometers installed in the vicinity of regions where loose parts impact is likely to occur. The system incorporates the capability of automatic annunciation (audible and visual), audio monitoring, automatic and manual signal recording, and acoustic signal analysis/evaluation. Measures for personnel radiation exposure and safety are included as part of the requirements of the LPM system. The objective of the LPM program is to provide early indication of component degradation. Consistent with GALL AMP:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element |
| Yes No Document(s) used to confirm Criteria:
| | : 2. Preventive A. The aging management program (AMP) is a Consistent with GALL AMP: Yes No Actions monitoring/detection program that provides early indication and Document(s) used to confirm Criteria: |
| | | detection of the onset of aging degradation. It does not rely on preventive actions. |
| Comment XI.M14 Loose Part Monitoring 2 Program Element Auditable GALL Criteria Documentation of Audit Finding 2. Preventive Actions A. The aging management program (AMP) is a monitoring/detection program that provides early indication and detection of the onset of aging degradation. It does not rely on preventive actions. Consistent with GALL AMP:
| | Comment: |
| Yes No Document(s) used to confirm Criteria:
| | : 3. Parameters A. The program relies on the use of transient acoustic signals to Consistent with GALL AMP: Yes No Monitored/ provide information on the occurrence of metallic loose part Document(s) used to confirm Criteria: |
| Comment: 3. Parameters Monitored/
| | Inspected impact. Reactor coolant system (RCS) background noise may mask the noise generated due to loose part impact. These background noises may arise from sources such as coolant flow and mechanically and hydraulically generated vibrations. To Comment: |
| Inspected A. The program relies on the use of transient acoustic signals to provide information on the occurrence of metallic loose part impact. Reactor coolant system (RCS) background noise may mask the noise generated due to loose part impact. These background noises may arise from sources such as coolant flow and mechanically and hydraulically generated vibrations. To differentiate loose part impact noise from background noise, ASME OM-S/G-1997, Part 12, recommends that the monitoring system sensitivity be set on the basis of the background noise and that maximum sensitivity be accomplished that is consistent with an acceptable false alarm rate arising from the background noise. Consistent with GALL AMP:
| | differentiate loose part impact noise from background noise, ASME OM-S/G-1997, Part 12, recommends that the monitoring system sensitivity be set on the basis of the background noise and that maximum sensitivity be accomplished that is consistent with an acceptable false alarm rate arising from the background noise. |
| Yes No Document(s) used to confirm Criteria:
| | : 4. Detection of A. Impact signals contain significant information on the size of Consistent with GALL AMP: Yes No Aging Effects the impacting object, the impact force and energy, and the Document(s) used to confirm Criteria: |
| | | composition and shape of both the component struck and the impacting object. In general, the magnitude of the impact signal increases with the impact mass and impact velocity. However, the frequency response increases with increasing velocity and Comment: |
| Comment: 4. Detection of Aging Effects A. Impact signals contain significant information on the size of the impacting object, the impact force and energy, and the composition and shape of both the component struck and the impacting object. In general, the magnitude of the impact signal increases with the impact mass and impact velocity. However, the frequency response increases with increasing velocity and decreasing mass. These data may be used to extract information on possible loose part impact and differentiate it from background noise. Consistent with GALL AMP:
| | decreasing mass. These data may be used to extract information on possible loose part impact and differentiate it from background noise. |
| Yes No Document(s) used to confirm Criteria: | | : 5. Monitoring A. The impact signals, collected data, frequency, and Consistent with GALL AMP: Yes No and Trending characteristics are recorded, monitored, and evaluated to locate Document(s) used to confirm Criteria: |
| | and identify the source and cause of the acoustic signals for the purpose of determining the need and urgency for a detailed inspection and examination of the suspected reactor vessel internals components. These activities are performed and Comment: |
| | associated personnel are qualified in accordance with site XI.M14 Loose Part Monitoring 2 |
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| Comment: 5. Monitoring and Trending A. The impact signals, collected data, frequency, and characteristics are recorded, monitored, and evaluated to locate and identify the source and cause of the acoustic signals for the purpose of determining the need and urgency for a detailed inspection and examination of the suspected reactor vessel internals components. These activities are performed and associated personnel are qualified in accordance with site Consistent with GALL AMP:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element controlled procedures and processes, as indicated by vendor, industry, or regulatory guidance documents. |
| Yes No Document(s) used to confirm Criteria: | | : 6. Acceptance A. The LPM alarms that suggest metallic impacts are further Consistent with GALL AMP: Yes No Criteria evaluated to verify LPM operability and to determine the location Document(s) used to confirm Criteria: |
| | of the impact, the impact energy, and mass. Plant process data are reviewed for anomalous behavior, and diagnostic results are assessed by plant personnel. |
| Comment: | | Comment: |
| XI.M14 Loose Part Monitoring 3 Program Element Auditable GALL Criteria Documentation of Audit Finding controlled procedures and processes, as indicated by vendor, industry, or regulatory guidance documents. 6. Acceptance Criteria A. The LPM alarms that suggest metallic impacts are further evaluated to verify LPM operability and to determine the location of the impact, the impact energy, and mass. Plant process data are reviewed for anomalous behavior, and diagnostic results are assessed by plant personnel. Consistent with GALL AMP:
| | : 7. Corrective A. If LPM diagnostics indicate the presence of loose parts, then Consistent with GALL AMP: Yes No Actions corrective actions are taken. In some cases, the results of the Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | diagnostic may indicate the signal is due to a change in the plant background noise characteristics and not due to the presence of loose parts. In such cases, the LPM alarm rates may in time become so high as to be unacceptable in practice. Comment: |
| | Adjustment of the alarm threshold (set points) is allowed. |
| | However, the reason for the change in background noise is to be investigated and understood, and the set point change is to be documented. 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.M14 Loose Part Monitoring 3 |
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| Comment: 7. Corrective Actions A. If LPM diagnostics indicate the presence of loose parts, then corrective actions are taken. In some cases, the results of the diagnostic may indicate the signal is due to a change in the plant background noise characteristics and not due to the presence of loose parts. In such cases, the LPM alarm rates may in time become so high as to be unacceptable in practice. Adjustment of the alarm threshold (set points) is allowed. However, the reason for the change in background noise is to be investigated and understood, and the set point change is to be documented. 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 Comment: |
| Yes No Document(s) used to confirm Criteria:
| | : 10. Operating A. The loose part monitoring program is extensively and Consistent with GALL AMP: Yes No Experience effectively used by the industry. The program has been Document(s) used to confirm Criteria: |
| | developed and published as a standard in the ASME Standards and Guides for Operation and Maintenance of Nuclear Power Plants, Part 12, an American National Standard. Part 12 was developed on the basis of knowledge gained from operating Comment: |
| | experience and research conducted since the Nuclear Regulatory Commission (NRC) issued Regulatory Guide (RG) 1.133 in May 1981. |
| | XI.M14 Loose Part Monitoring 4 |
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| Comment: 8. Confirmation Process A. Site quality assurance (QA) procedures, review and approval processes, and administrative controls are implemented in accordance with the requirements of 10 CFR Part 50, Appendix B. As discussed in the appendix to this report, the staff finds the requirements of 10 CFR Part 50, Appendix B, acceptable to address the confirmation process and administrative controls. Consistent with GALL AMP:
| | 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. |
|
| |
|
| 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.M14 Loose Part Monitoring 4 Program Element Auditable GALL Criteria Documentation of Audit Finding Comment: 10. Operating Experience A. The loose part monitoring program is extensively and effectively used by the industry. The program has been developed and published as a standard in the ASME "Standards and Guides for Operation and Maintenance of Nuclear Power Plants," Part 12, an American National Standard. Part 12 was developed on the basis of knowledge gained from operating experience and research conducted since the Nuclear Regulatory Commission (NRC) issued Regulatory Guide (RG) 1.133 in May 1981. 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.M14 Loose Part Monitoring 5 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. -
| | XI.M14 Loose Part Monitoring 5}} |
| 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
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ML19198A2522019-06-20020 June 2019
Alternate Disposal Request - Rail Shipments (License DPR-28, Docket No. 50-271)
ML16176A3392016-10-28028 October 2016
Decommissioning Lessons Learned Report and Transmittal Memorandum
ML15266A4302015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 24, Flow Diagram Instrument Air System. Sheet 2
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.2015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.
ML15266A4452015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 2
ML15266A4442015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 1
ML15266A4402015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 8
ML15266A4362015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 7
ML15266A4352015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 6
ML15266A4342015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 5
ML15266A4332015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 4
ML15266A4322015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 31, Flow Diagram Instrument Air System. Sheet 3
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 22015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2
ML15266A4292015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 37, Flow Diagram Instrument Air System. Sheet 1
ML15266A4282015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 100, Flow Diagram Service Water System. Sheet 2
ML15266A4272015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 92, Flow Diagram Service Water System. Sheet 1
ML15266A4262015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191152, Rev. 14, General Arrangement Radwaste Building Section.
ML15266A4252015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191151, Rev 19, General Arrangement Radwaste Building Plans.
ML15266A4242015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191150, Rev. 20, General Arrangement Reactor Building Section.
ML15266A4232015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191149, Rev. 27, General Arrangement Reactor Building Plans Sheet 2.
ML15266A4222015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191148, Rev. 23, General Arrangement Reactor Building Plans Sheet 1.
ML15266A2722015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report - List of Effective Pages
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 52015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5
ML15266A2832015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, DSAR Drawing List
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.2015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.
ML15266A2712015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, DSAR Changes
ML15266A2732015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, UFSAR to DSAR Conversion Matrix
ML15267A6092015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 3
BVY 15-046, Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf.2015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf.
ML15267A6612015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.
ML15267A6592015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191592, Control Room Building Fl Plan El 248.50 & Fdn Plan-R, Sheet 1
ML15267A6562015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.
ML15267A6542015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.
ML15267A6512015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191463, Circulating Water System Discharge Structure Reinf, Sheet 2
ML15267A6492015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1
ML15267A6472015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191453, Circulating Water System Intake Structure-M, Sheet 3
ML15267A6452015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191452, Circulating Water System Intake Structure-V, Sheet 2
ML15267A6412015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191451, Circulating Water System Intake Structure-M, Sheet 1
ML15267A6112015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5
ML15267A6102015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 120/240V Vital AC and Instrument AC One Line Diagram, Sheet 4
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 12015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1
ML15267A6082015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 2
ML15267A6072015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1
ML15267A6062015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2
ML15267A6052015-09-0101 September 2015
Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 30, 480V Aux. One Line Diagram Swgr BUS-9, MCC-9A, 9C. Sheet 1
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 12015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1
BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.2015-09-0101 September 2015
Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.
2021-03-15
[Table view]
Category:Miscellaneous
MONTHYEARML21075A1772021-03-15015 March 2021
Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request
BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019
72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019
ML16176A3392016-10-28028 October 2016
Decommissioning Lessons Learned Report and Transmittal Memorandum
BVY 15-049, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-08-19019 August 2015
Submittal of 10 CFR 71.95 Report Involving 8-120B Cask
BVY 15-018, Transmittal of Biennial 10 CFR 50.59 Report2015-03-0202 March 2015
Transmittal of Biennial 10 CFR 50.59 Report
BVY 14-085, Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2014-12-19019 December 2014
Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)
BVY 14-011, Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ...2014-02-25025 February 2014
Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ...
BVY 13-090, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2013-10-0202 October 2013
Submittal of 10 CFR 71.95 Report Involving 8-120B Cask
BVY 12-081, Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-21021 November 2012
Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
ML12160A3732012-06-11011 June 2012
Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daichii Nuclear Plant Accident TAC No. ME8747)
ML1127000692011-09-26026 September 2011
Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants
ML1108712502011-03-24024 March 2011
BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages
ML1012704392010-05-0505 May 2010
Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
BVY 07-079, Update of Aging Management Program Audit Q&A Database2007-11-14014 November 2007
Update of Aging Management Program Audit Q&A Database
BVY 07-004, Emergency Response Data System (ERDS) Data Point Library Update2007-06-21021 June 2007
Emergency Response Data System (ERDS) Data Point Library Update
ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007
Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006
L-87-005, Various CRS 08/09/2005 to 02/08/20072007-02-0808 February 2007
Various CRS 08/09/2005 to 02/08/2007
ML0706703802007-02-0101 February 2007
NDE Reports 07-001 Thru 07-008
ML0701705912007-01-0909 January 2007
VYNPS - SEIS Web Reference - Us Census Glossary
ML0701701982006-12-15015 December 2006
VYNPS - SEIS Web Reference - Connecticut River Migratory Fish Counts 1967-2005
ML0629204232006-10-0303 October 2006
(E-Mail) Cooling Tower Report for VY
ML0629203422006-09-18018 September 2006
(E-Mail) Air Emissions Inventory Report for 2005 and MSDS for Nalco H-550
ENOC-06-00018, Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 20062006-08-29029 August 2006
Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 2006
BVY 06-068, Cycle 25 Startup Test Report Following Power Ascension and Testing2006-08-0101 August 2006
Cycle 25 Startup Test Report Following Power Ascension and Testing
CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006
Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee
ML0618803852006-05-22022 May 2006
Windham Regional Plan Draft, May 22, 2006
ML0704404852006-05-12012 May 2006
AMRM-16, Revision 0, Aging Management Review of the Instrument Air System.
ML0704404832006-05-12012 May 2006
AMRM-15, Revision 0, Aging Management Review of the Fuel Oil System.
ML0704404782006-05-12012 May 2006
AMRM-15, Aging Management Review of the Fuel Oil System
ML0704404742006-05-12012 May 2006
AMRM-12, Aging Management Review of the Reactor Building Closed Cooling Water System
ML0704404862006-05-11011 May 2006
AMRM-30, Rev. 01, Aging Management Review of Ns Systems Affecting Safety Systems
BVY 06-033, Cycle 24 10 CFR 50.59 Report2006-04-24024 April 2006
Cycle 24 10 CFR 50.59 Report
BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan2006-03-26026 March 2006
Revision 1 to Steam Dryer Monitoring Plan
ML0609503562006-03-22022 March 2006
GALL AMP: XI.M13, Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP)
ML0609503642006-03-22022 March 2006
GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP)
ML0609502712006-03-22022 March 2006
GALL AMP: XI.M1, ASME Section XI Inservice Inspection, Subsections Iwb, Iwc, and Iwd (Audit Worksheet, GALL Report AMP)
ML0609505492006-03-22022 March 2006
GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP)
ML0609502772006-03-22022 March 2006
GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP)
ML0609502152006-03-22022 March 2006
GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP)
ML0609505702006-03-22022 March 2006
GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP)
ML0609502202006-03-22022 March 2006
GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP)
ML0609502502006-03-22022 March 2006
GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP)
ML0609502582006-03-22022 March 2006
GALL AMP: XI.E4, Metal Enclosed Bus (Audit Worksheet GALL Report AMP)
ML0609502622006-03-22022 March 2006
GALL AMP: XI.E5, Fuse Holder (Audit Worksheet GALL Report AMP)
ML0609503472006-03-22022 March 2006
GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors
ML0609506062006-03-22022 March 2006
GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP)
ML0609506242006-03-22022 March 2006
GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP)
ML0609502902006-03-22022 March 2006
GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP)
ML0610000902006-03-22022 March 2006
GALL AMP: XI.M39, Lubricating Oil Analysis Program (Audit Worksheet GALL Report AMP)
ML0609503312006-03-22022 March 2006
GALL AMP: XI.M10, Boric Acid Corrosion (Audit Worksheet GALL Report AMP)
2021-03-15
[Table view] |
Text
AUDIT W ORKSHEET GALL REPORT AMP PLANT: ______________________________
LRA AMP: __________________________ REVIEWER: ______________________
GALL AMP: XI.M14, Loose Part Monitoring DATE: __________________________
Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. The program relies on an inservice monitoring program to Consistent with GALL AMP: Yes No Description detect and monitor loose parts in light-water reactor (LWR) Document(s) used to confirm Criteria:
power plants. This in-service loose part monitoring (LPM) 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 12, Loose Comment:
Part Monitoring in Light-Water Reactor Power Plants.
- 1. Scope of A. The program includes measures to monitor and detect Consistent with GALL AMP: Yes No Program metallic loose parts by using transient signals analysis on Document(s) used to confirm Criteria:
acoustic data generated due to loose parts impact. The program is applicable, but not necessarily limited to, the reactor vessel and primary coolant systems in pressurized water reactors (PWRs) and the reactor recirculation system in boiling water Comment reactors (BWRs). The detection and monitoring system includes a set of accelerometers installed in the vicinity of regions where loose parts impact is likely to occur. The system incorporates the capability of automatic annunciation (audible and visual),
audio monitoring, automatic and manual signal recording, and acoustic signal analysis/evaluation. Measures for personnel radiation exposure and safety are included as part of the requirements of the LPM system. The objective of the LPM program is to provide early indication of component degradation.
XI.M14 Loose Part Monitoring 1
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 2. Preventive A. The aging management program (AMP) is a Consistent with GALL AMP: Yes No Actions monitoring/detection program that provides early indication and Document(s) used to confirm Criteria:
detection of the onset of aging degradation. It does not rely on preventive actions.
Comment:
- 3. Parameters A. The program relies on the use of transient acoustic signals to Consistent with GALL AMP: Yes No Monitored/ provide information on the occurrence of metallic loose part Document(s) used to confirm Criteria:
Inspected impact. Reactor coolant system (RCS) background noise may mask the noise generated due to loose part impact. These background noises may arise from sources such as coolant flow and mechanically and hydraulically generated vibrations. To Comment:
differentiate loose part impact noise from background noise, ASME OM-S/G-1997, Part 12, recommends that the monitoring system sensitivity be set on the basis of the background noise and that maximum sensitivity be accomplished that is consistent with an acceptable false alarm rate arising from the background noise.
- 4. Detection of A. Impact signals contain significant information on the size of Consistent with GALL AMP: Yes No Aging Effects the impacting object, the impact force and energy, and the Document(s) used to confirm Criteria:
composition and shape of both the component struck and the impacting object. In general, the magnitude of the impact signal increases with the impact mass and impact velocity. However, the frequency response increases with increasing velocity and Comment:
decreasing mass. These data may be used to extract information on possible loose part impact and differentiate it from background noise.
- 5. Monitoring A. The impact signals, collected data, frequency, and Consistent with GALL AMP: Yes No and Trending characteristics are recorded, monitored, and evaluated to locate Document(s) used to confirm Criteria:
and identify the source and cause of the acoustic signals for the purpose of determining the need and urgency for a detailed inspection and examination of the suspected reactor vessel internals components. These activities are performed and Comment:
associated personnel are qualified in accordance with site XI.M14 Loose Part Monitoring 2
Program Auditable GALL Criteria Documentation of Audit Finding Element controlled procedures and processes, as indicated by vendor, industry, or regulatory guidance documents.
- 6. Acceptance A. The LPM alarms that suggest metallic impacts are further Consistent with GALL AMP: Yes No Criteria evaluated to verify LPM operability and to determine the location Document(s) used to confirm Criteria:
of the impact, the impact energy, and mass. Plant process data are reviewed for anomalous behavior, and diagnostic results are assessed by plant personnel.
Comment:
- 7. Corrective A. If LPM diagnostics indicate the presence of loose parts, then Consistent with GALL AMP: Yes No Actions corrective actions are taken. In some cases, the results of the Document(s) used to confirm Criteria:
diagnostic may indicate the signal is due to a change in the plant background noise characteristics and not due to the presence of loose parts. In such cases, the LPM alarm rates may in time become so high as to be unacceptable in practice. Comment:
Adjustment of the alarm threshold (set points) is allowed.
However, the reason for the change in background noise is to be investigated and understood, and the set point change is to be documented. 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.M14 Loose Part Monitoring 3
Program Auditable GALL Criteria Documentation of Audit Finding Element Comment:
- 10. Operating A. The loose part monitoring program is extensively and Consistent with GALL AMP: Yes No Experience effectively used by the industry. The program has been Document(s) used to confirm Criteria:
developed and published as a standard in the ASME Standards and Guides for Operation and Maintenance of Nuclear Power Plants, Part 12, an American National Standard. Part 12 was developed on the basis of knowledge gained from operating Comment:
experience and research conducted since the Nuclear Regulatory Commission (NRC) issued Regulatory Guide (RG) 1.133 in May 1981.
XI.M14 Loose Part 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.M14 Loose Part Monitoring 5
