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| | number = ML060950347 | | | number = ML060950347 |
| | issue date = 03/22/2006 | | | issue date = 03/22/2006 |
| | title = 2006/03/22-GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors | | | title = GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors |
| | author name = Morgan M J | | | author name = Morgan M |
| | author affiliation = NRC/NRR/ADRO/DLR/RLRC | | | author affiliation = NRC/NRR/ADRO/DLR/RLRC |
| | addressee name = | | | addressee name = |
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| | docket = 05000271 | | | docket = 05000271 |
| | license number = | | | license number = |
| | contact person = morgan M J NRR/NRC/DLR/RLRC, 415-2232 | | | contact person = morgan M NRR/NRC/DLR/RLRC, 415-2232 |
| | case reference number = %dam200611, TAC MC9668 | | | case reference number = %dam200611, TAC MC9668 |
| | package number = ML060950189 | | | package number = ML060950189 |
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| =Text= | | =Text= |
| {{#Wiki_filter:XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWR's 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.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper DATE: __________________________ |
| GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors DATE: __________________________ | | Reactor Vessel Closure Heads of Pressurized Water Reactors Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. This program is established to ensure that augmented Consistent with GALL AMP: Yes No Description inservice inspections (ISI) of all nickel-alloy vessel head Document(s) used to confirm Criteria: |
| Program Element Auditable GALL Criteria Documentation of Audit Finding Program Description A. This program is established to ensure that augmented inservice inspections (ISI) of all nickel-alloy vessel head penetration (VHP) nozzles welded to the upper reactor vessel (RV) head of a PWR-designed light-water reactor will continue to be performed as mandated by the interim requirements in Order EA-03-009, "Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (PWRs)," as amended by the First Revision of the Order, or by any subsequent NRC requirements that may be established to supersede the requirements of Order EA-03-009. Since 1997, the Nuclear Regulatory Commission (NRC) has issued a number of generic communications on the topic of primary water stress corrosion cracking (PWSCC) in upper VHP nozzles. These generic communications included issuance of NRC Generic Letter (GL) 97-01, Bulletin 2001-01, Bulletin 2002-01, and Bulletin 2002-02. In response to its reviews of the industry's responses to these generic communications, the staff determined that PWSCC-induced cracking of upper VHP nozzles was a significant safety issue for operating PWRs that warranted issuance of an NRC Order for augmented inspection of PWR upper VHP nozzles and upper RV heads. On February 11, 2003, the Commission issued Order EA-03-009 to all holders of PWR operating licenses. Order EA-03-009 was issued in accordance with the regulatory bases and Consistent with GALL AMP: | | penetration (VHP) nozzles welded to the upper reactor vessel (RV) head of a PWR-designed light-water reactor will continue to be performed as mandated by the interim requirements in Order EA-03-009, Issuance of Order Establishing Interim Comment: |
| Yes No Document(s) used to confirm Criteria:
| | Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (PWRs), as amended by the First Revision of the Order, or by any subsequent NRC requirements that may be established to supersede the requirements of Order EA-03-009. Since 1997, the Nuclear Regulatory Commission (NRC) has issued a number of generic communications on the topic of primary water stress corrosion cracking (PWSCC) in upper VHP nozzles. These generic communications included issuance of NRC Generic Letter (GL) 97-01, Bulletin 2001-01, Bulletin 2002-01, and Bulletin 2002-02. In response to its reviews of the industrys responses to these generic communications, the staff determined that PWSCC-induced cracking of upper VHP nozzles was a significant safety issue for operating PWRs that warranted issuance of an NRC Order for augmented inspection of PWR upper VHP nozzles and upper RV heads. On February 11, 2003, the Commission issued Order EA-03-009 to all holders of PWR operating licenses. Order EA-03-009 was issued in accordance with the regulatory bases and XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 1 |
| Comment:
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| XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWR's 2 Program Element Auditable GALL Criteria Documentation of Audit Finding requirements of 10 CFR 2.202 and the adequate protection backfit provisions of 10 CFR 50.109. In this Order, the NRC required specific augmented inspections of reactor vessel closure heads and the associated nickel-alloy penetration nozzles in U.S. PWRs. The NRC issued the First Revised Order EA-03-009 on February 20, 2004, to clarify which locations of the PWR vessel head penetration nozzles were applicable to the requirements of the Order. All PWR licensees in the U.S. were required to submit 20-day and 60-day responses to Order EA-03-009 and to First Revised Order EA-03-009 (henceforth referred to in this document collectively as "the Order, as amended"). The Order, as amended, established a mandated augmented inspection process for upper VHP nozzles and upper RV heads that supplements the leakage tests and visual VT-2 examinations requirements established in Section XI of the ASME Boiler and Pressure Vessel Code, Table IWB-2500-1, Examination Category B-P. The interim requirements of the Order, as amended, also established the NRC's required technical method for calculating the susceptibility ranking of a plant's upper VHP nozzles to PWSCC and a required process for establishing the inspection methods and inspection frequencies for a plant's VHP nozzles in accordance with its susceptibility ranking. 1. Scope of Program A. The program is focused on managing the effects of cracking due to PWSCC of the nickel-alloy used in the fabrication of the upper VHP nozzles at PWR-designed nuclear facilities. The scope of this AMP is limited to upper VHP nozzles, including control rod drive mechanism (CRDM) nozzles, control element drive mechanism (CEDM) nozzles, thermocouples (TC) nozzles, in-core instrumentation (ICI) nozzles, and vent line nozzles; associated J-groove welds; and the adjoining upper RV closure head. Consistent with GALL AMP: | |
| Yes No Document(s) used to confirm Criteria:
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| Comment XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWR's 3 Program Element Auditable GALL Criteria Documentation of Audit Finding 2. Preventive Actions A. Preventive measures to mitigate PWSCC are in accordance with PWR water chemistry guidelines for primary coolant systems, as established in EPRI Topical Report TR-105714 (applicants for license renewal may credit the version of the report on record at the facility at the time of submittal of its application). The program description and the evaluation and technical basis of monitoring and maintaining reactor coolant water chemistry are presented in Chapter XI.M2, "Water Chemistry." Consistent with GALL AMP:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element requirements of 10 CFR 2.202 and the adequate protection backfit provisions of 10 CFR 50.109. In this Order, the NRC required specific augmented inspections of reactor vessel closure heads and the associated nickel-alloy penetration nozzles in U.S. PWRs. The NRC issued the First Revised Order EA-03-009 on February 20, 2004, to clarify which locations of the PWR vessel head penetration nozzles were applicable to the requirements of the Order. All PWR licensees in the U.S. |
| Yes No Document(s) used to confirm Criteria: | | were required to submit 20-day and 60-day responses to Order EA-03-009 and to First Revised Order EA-03-009 (henceforth referred to in this document collectively as the Order, as amended). The Order, as amended, established a mandated augmented inspection process for upper VHP nozzles and upper RV heads that supplements the leakage tests and visual VT-2 examinations requirements established in Section XI of the ASME Boiler and Pressure Vessel Code, Table IWB-2500-1, Examination Category B-P. The interim requirements of the Order, as amended, also established the NRCs required technical method for calculating the susceptibility ranking of a plants upper VHP nozzles to PWSCC and a required process for establishing the inspection methods and inspection frequencies for a plants VHP nozzles in accordance with its susceptibility ranking. |
| Comment: 3. Parameters Monitored/ Inspected A. The program monitors for cracking/PWSCC and loss of material/wastage in the upper VHP nozzles to ensure the structural integrity of the VHP nozzles prior to a loss of their intended safety function. Consistent with GALL AMP:
| | : 1. Scope of A. The program is focused on managing the effects of cracking Consistent with GALL AMP: Yes No Program due to PWSCC of the nickel-alloy used in the fabrication of the Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria:
| | upper VHP nozzles at PWR-designed nuclear facilities. The scope of this AMP is limited to upper VHP nozzles, including control rod drive mechanism (CRDM) nozzles, control element drive mechanism (CEDM) nozzles, thermocouples (TC) nozzles, Comment in-core instrumentation (ICI) nozzles, and vent line nozzles; associated J-groove welds; and the adjoining upper RV closure head. |
| | XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 2 |
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| Comment: " B. The program also monitors for evidence of reactor coolant leakage as a result of through-wall cracks that may exist in the upper VHP nozzles or their associated partial penetration J-groove welds. Evidence of reactor coolant leakage may manifest itself in the form of boric acid residues on the upper RV head or adjacent components or in the form of corrosion products that result from rusting of the low-alloy steel materials used to fabricate the RVs. Consistent with GALL AMP:
| | Program Auditable GALL Criteria Documentation of Audit Finding Element |
| Yes No Document(s) used to confirm Criteria: | | : 2. Preventive A. Preventive measures to mitigate PWSCC are in accordance Consistent with GALL AMP: Yes No Actions with PWR water chemistry guidelines for primary coolant Document(s) used to confirm Criteria: |
| Comment: 4. Detection of Aging Effects A. Implementation of inspections required by the Order, as amended, or any subsequent NRC requirements, as applicable, assures detection of cracks in the upper VHP nozzles and any loss of material/wastage of the upper RV head prior to a loss of intended function of the components. Detection of cracking (including those induced by PWSCC) is accomplished through implementation of a combination of bare-metal visual examination and/or non-visual examination techniques, as discussed in the Order, as amended. Bare-metal visual examinations required by the Order, as amended, are used to detect reactor coolant leakage from the VHP nozzles or their Consistent with GALL AMP:
| | systems, as established in EPRI Topical Report TR-105714 (applicants for license renewal may credit the version of the report on record at the facility at the time of submittal of its application). The program description and the evaluation and Comment: |
| Yes No Document(s) used to confirm Criteria: | | technical basis of monitoring and maintaining reactor coolant water chemistry are presented in Chapter XI.M2, "Water Chemistry. |
| | : 3. Parameters A. The program monitors for cracking/PWSCC and loss of Consistent with GALL AMP: Yes No Monitored/ material/wastage in the upper VHP nozzles to ensure the Document(s) used to confirm Criteria: |
| | Inspected structural integrity of the VHP nozzles prior to a loss of their intended safety function. |
| Comment: | | Comment: |
| XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWR's 4 Program Element Auditable GALL Criteria Documentation of Audit Finding associated J-groove welds and for any loss of material that may be induced as a result of boric-acid wastage. " B. Non-visual examination techniques required by the Order, as amended, are also used to detect these aging effects and are performed using either surface examination techniques (eddy current or penetrant testing) or volumetric examination techniques (ultrasonic testing). Consistent with GALL AMP:
| | B. The program also monitors for evidence of reactor coolant Consistent with GALL AMP: Yes No leakage as a result of through-wall cracks that may exist in the Document(s) used to confirm Criteria: |
| Yes No Document(s) used to confirm Criteria: | | upper VHP nozzles or their associated partial penetration J-groove welds. Evidence of reactor coolant leakage may manifest itself in the form of boric acid residues on the upper RV head or adjacent components or in the form of corrosion Comment: |
| | products that result from rusting of the low-alloy steel materials used to fabricate the RVs. |
| | : 4. Detection of A. Implementation of inspections required by the Order, as Consistent with GALL AMP: Yes No Aging Effects amended, or any subsequent NRC requirements, as applicable, Document(s) used to confirm Criteria: |
| | assures detection of cracks in the upper VHP nozzles and any loss of material/wastage of the upper RV head prior to a loss of intended function of the components. Detection of cracking (including those induced by PWSCC) is accomplished through Comment: |
| | implementation of a combination of bare-metal visual examination and/or non-visual examination techniques, as discussed in the Order, as amended. Bare-metal visual examinations required by the Order, as amended, are used to detect reactor coolant leakage from the VHP nozzles or their XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 3 |
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| Comment: " C. The specific types of examinations to be implemented are dependent on a plant's susceptibility ranking for its VHP nozzles. Inspection methods selected for examination are implemented in accordance with appropriate inspection requirements of Section IV.C of the Order, as amended, as applicable for a plant's susceptibility ranking (i.e., in accordance with the appropriate inspection methods mandated for "Low," "Moderate," "High," or "Replaced" susceptibility category plants). Any deviations from implementing the appropriate required inspection methods of the Order, as amended, will be submitted for NRC review and approval in accordance with the Order, as amended. Consistent with GALL AMP: | | Program Auditable GALL Criteria Documentation of Audit Finding Element associated J-groove welds and for any loss of material that may be induced as a result of boric-acid wastage. |
| Yes No Document(s) used to confirm Criteria: | | B. Non-visual examination techniques required by the Order, as Consistent with GALL AMP: Yes No amended, are also used to detect these aging effects and are Document(s) used to confirm Criteria: |
| | performed using either surface examination techniques (eddy current or penetrant testing) or volumetric examination techniques (ultrasonic testing). |
| | Comment: |
| | C. The specific types of examinations to be implemented are Consistent with GALL AMP: Yes No dependent on a plants susceptibility ranking for its VHP Document(s) used to confirm Criteria: |
| | nozzles. Inspection methods selected for examination are implemented in accordance with appropriate inspection requirements of Section IV.C of the Order, as amended, as applicable for a plants susceptibility ranking (i.e., in accordance Comment: |
| | with the appropriate inspection methods mandated for Low, Moderate, High, or Replaced susceptibility category plants). |
| | Any deviations from implementing the appropriate required inspection methods of the Order, as amended, will be submitted for NRC review and approval in accordance with the Order, as amended. |
| | : 5. Monitoring A. As required by the Order, as amended, inspection schedules Consistent with GALL AMP: Yes No and Trending and frequencies for the applicants VHP nozzles are Document(s) used to confirm Criteria: |
| | implemented in accordance with required frequencies for the plants susceptibility category (i.e., in accordance with the specific inspection frequencies required for Low, Moderate, High, or Replaced susceptibility categories, as based on the Comment: |
| | total effective degradation years). Any deviations from implementing the required inspection frequencies mandated by XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 4 |
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| Comment: 5. Monitoring and Trending A. As required by the Order, as amended, inspection schedules and frequencies for the applicant's VHP nozzles are implemented in accordance with required frequencies for the plant's susceptibility category (i.e., in accordance with the specific inspection frequencies required for "Low," "Moderate,"
| | Program Auditable GALL Criteria Documentation of Audit Finding Element the Order, as amended, will be submitted for NRC review and approval in accordance with the Order, as amended. |
| "High," or "Replaced" susceptibility categories, as based on the "total effective degradation years"). Any deviations from implementing the required inspection frequencies mandated by Consistent with GALL AMP:
| | Disposition of flaw indications detected during required examinations is implemented in accordance with the Acceptance Criteria and Corrective Actions Program attributes of this AMP. |
| Yes No Document(s) used to confirm Criteria: | | : 6. Acceptance A. Relevant flaw indications detected as a result of the Consistent with GALL AMP: Yes No Criteria augmented inspections of the upper VHP nozzles are to be Document(s) used to confirm Criteria: |
| | evaluated in accordance with acceptable law evaluation criteria provided in a letter from Mr. Richard Barrett, NRC, Office of Nuclear Reactor Regulation (NRR), Division of Engineering to Alex Marion, Nuclear Energy Institute (NEI), dated April 11, Comment: |
| | 2003, or in accordance with NRC-approved Code Cases that incorporate the flaw evaluation procedures and criteria of the NRCs April 11, 2003, letter to NEI. |
| | : 7. Corrective A. Relevant flaw indications in the upper VHP nozzles or their Consistent with GALL AMP: Yes No Actions associated nickel-alloy J-groove weld materials are Document(s) used to confirm Criteria: |
| | unacceptable for further service and are corrected through implementation of appropriate repair or replacement activities. |
| | Comment: |
| | B. In addition, detection of leakage or evidence of cracking in Consistent with GALL AMP: Yes No the VHP nozzles (including associated J-groove welds) of plants Document(s) used to confirm Criteria: |
| | ranked in the Low, Moderate, or Replaced susceptibility categories requires that the plants VHP nozzles be immediately reclassified to the High susceptibility category and that the required augmented inspections for High susceptibility VHP Comment: |
| | nozzles be implemented, commencing from the same outage in which the leakage or cracking was detected. Repair and replacement procedures and activities either must comply with ASME Section XI, as invoked by the requirements of 10 CFR 50.55a, or conform with applicable ASME Code Cases that have been endorsed in 10 CFR 50.55a by reference in the latest version of NRC Regulatory Guide 1.147. Alternative XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 5 |
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| | Program Auditable GALL Criteria Documentation of Audit Finding Element repair/replacement activities suggested instead of those endorsed by the NRC in either Section XI or NRC-approved Code Cases must be requested for NRC approval in accordance with either the acceptable alternative provisions of 10 CFR 50.55a(a)(3)(i) or hardship provisions of 10 CFR 50.55a(a)(3)(ii). |
| | : 8. A. Site quality assurance (QA) procedures, review and approval Consistent with GALL AMP: Yes No Confirmation processes are implemented in accordance with the Document(s) used to confirm Criteria: |
| | Process 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, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, Comment: |
| | acceptable to address confirmation process and administrative controls. |
| | : 9. A. See Item 8, above. Consistent with GALL AMP: Yes No Administrative Document(s) used to confirm Criteria: |
| | Controls Comment: |
| | : 10. Operating A. PWSCC is occurring in the VHP nozzles of U.S. PWRs, as Consistent with GALL AMP: Yes No Experience described in the program description above. In addition, Document(s) used to confirm Criteria: |
| | applicants for license renewal should reference plant-specific operating experience that is applicable to PWSCC of its VHP nozzles. |
| Comment: | | Comment: |
| XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWR's 5 Program Element Auditable GALL Criteria Documentation of Audit Finding the Order, as amended, will be submitted for NRC review and approval in accordance with the Order, as amended. Disposition of flaw indications detected during required examinations is implemented in accordance with the Acceptance Criteria and Corrective Actions Program attributes of this AMP. 6. Acceptance Criteria A. Relevant flaw indications detected as a result of the augmented inspections of the upper VHP nozzles are to be evaluated in accordance with acceptable law evaluation criteria provided in a letter from Mr. Richard Barrett, NRC, Office of Nuclear Reactor Regulation (NRR), Division of Engineering to Alex Marion, Nuclear Energy Institute (NEI), dated April 11, 2003, or in accordance with NRC-approved Code Cases that incorporate the flaw evaluation procedures and criteria of the NRC's April 11, 2003, letter to NEI. Consistent with GALL AMP: | | XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 6 |
| Yes No Document(s) used to confirm Criteria:
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| Comment: 7. Corrective Actions A. Relevant flaw indications in the upper VHP nozzles or their associated nickel-alloy J-groove weld materials are unacceptable for further service and are corrected through implementation of appropriate repair or replacement activities. Consistent with GALL AMP:
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| Yes No Document(s) used to confirm Criteria:
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| Comment: " B. In addition, detection of leakage or evidence of cracking in the VHP nozzles (including associated J-groove welds) of plants ranked in the "Low," "Moderate," or "Replaced" susceptibility categories requires that the plant's VHP nozzles be immediately reclassified to the "High" susceptibility category and that the required augmented inspections for "High" susceptibility VHP nozzles be implemented, commencing from the same outage in which the leakage or cracking was detected. Repair and replacement procedures and activities either must comply with ASME Section XI, as invoked by the requirements of 10 CFR 50.55a, or conform with applicable ASME Code Cases that have been endorsed in 10 CFR 50.55a by reference in the latest version of NRC Regulatory Guide 1.147. Alternative 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. |
| Comment:
| | 2. |
| XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWR's 6 Program Element Auditable GALL Criteria Documentation of Audit Finding repair/replacement activities suggested instead of those endorsed by the NRC in either Section XI or NRC-approved Code Cases must be requested for NRC approval in accordance with either the acceptable alternative provisions of 10 CFR 50.55a(a)(3)(i) or hardship provisions of 10 CFR 50.55a(a)(3)(ii). 8.
| |
| Confirmation Process A. Site quality assurance (QA) procedures, review and approval processes 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, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," acceptable to address confirmation process and administrative controls. Consistent with GALL AMP:
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| Yes No Document(s) used to confirm Criteria:
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| Comment: 9. Administrative Controls A. See Item 8, above. Consistent with GALL AMP:
| | ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #) |
| Yes No Document(s) used to confirm Criteria:
| | 1. |
| Comment: 10. Operating Experience A. PWSCC is occurring in the VHP nozzles of U.S. PWRs, as described in the program description above. In addition, applicants for license renewal should reference plant-specific operating experience that is applicable to PWSCC of its VHP nozzles. Consistent with GALL AMP:
| | 2. |
| Yes No Document(s) used to confirm Criteria:
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| Comment:
| | DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1. |
| XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWR's 7 EXCEPTIONS Item Number Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| | 2. |
| ENHANCEMENTS Item Number Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed (Identifier, Para.# and/or Page #) 1. 2. -
| | 3. |
| DOCUMENT REVIEWED D URING A UDIT Document Number Identifier (number) Title Revision and/or Date 1. 2. 3. 4. -.}} | | 4. |
| | XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 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 ML0609505792006-03-22022 March 2006 GALL AMP: XI.M24, Compressed Air Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506202006-03-22022 March 2006 GALL AMP: XI.M31, Reactor Vessel Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505962006-03-22022 March 2006 GALL AMP: XI.M27, Fire Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502792006-03-22022 March 2006 GALL AMP: XI.M3, Reactor Head Closure Studs (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609506292006-03-22022 March 2006 GALL AMP: XI.M33, Selective Leaching of Materials (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506372006-03-22022 March 2006 GALL AMP: XI.M36, External Surfaces Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502842006-03-22022 March 2006 GALL AMP: XI.M4, BWR Vessel Id Attachment Welds (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502202006-03-22022 March 2006 GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001472006-03-22022 March 2006 GALL AMP: XI.S8, Protective Coating Monitoring and Maintenance Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001342006-03-22022 March 2006 GALL AMP: XI.S5, Masonry Wall Progam (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502182006-03-22022 March 2006 GALL AMP: X.M1, Metal Fatigue of Reactor Coolant Pressure Boundary (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609505592006-03-22022 March 2006 GALL AMP: XI.M20, Open-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503472006-03-22022 March 2006 GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors Project stage: Other ML0609505402006-03-22022 March 2006 GALL AMP: XI.M18, Bolting Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505672006-03-22022 March 2006 GALL AMP: XI.M21, Closed-Cycle Cooling Water System (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001012006-03-22022 March 2006 GALL AMP: XI.S2, ASME Section XI, Subsection Iwl (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505732006-03-22022 March 2006 GALL AMP: XI.M23, Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506102006-03-22022 March 2006 GALL AMP: XI.M29, Aboveground Steel Tanks (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502902006-03-22022 March 2006 GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP) Project stage: Other ML0610001382006-03-22022 March 2006 GALL AMP: XI.S6, Structures Monitoring Program (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001262006-03-22022 March 2006 GALL AMP: XI.S4, 10 CFR 50, Appendix J (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502242006-03-22022 March 2006 GALL AMP: XI.E1, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506062006-03-22022 March 2006 GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503752006-03-22022 March 2006 GALL AMP: XI.M17, Flow-Accelerated Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000782006-03-22022 March 2006 GALL AMP: XI.M38, Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505702006-03-22022 March 2006 GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503722006-03-22022 March 2006 GALL AMP: XI.M16, PWR Vessel Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503642006-03-22022 March 2006 GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502772006-03-22022 March 2006 GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609506242006-03-22022 March 2006 GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503112006-03-22022 March 2006 GALL AMP: XI.M7, BWR Stress Corrosion Cracking (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502352006-03-22022 March 2006 GALL AMP: XI.E2, Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits (Audit Worksheet GALL Report AMP) Project stage: Other ML0609506342006-03-22022 March 2006 GALL AMP: XI.M35, One-Time Inspection of ASME Code Class 1 Small Bore Piping (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502502006-03-22022 March 2006 GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) Project stage: Other ML0610001432006-03-22022 March 2006 GALL AMP: XI.S7, Rg 1.127, Inspection of Water-Control Structures Associated with Nuclear Power Plants (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP) Project stage: Other ML0609505872006-03-22022 March 2006 GALL AMP: XI.M26, Fire Protection (Audit Worksheet GALL Report AMP) Project stage: Other ML0609501952006-03-22022 March 2006 GALL AMP: Plant-Specific (Audit Worksheet - GALL Report AMP) Project stage: Other ML0609503702006-03-22022 March 2006 GALL AMP: XI.M15, Neutron Noise Monitoring (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503012006-03-22022 March 2006 GALL AMP: XI.M6, BWR Control Rod Drive Return Line Nozzle (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503282006-03-22022 March 2006 GALL AMP: XI.M9, BWR Vessels Internals (Audit Worksheet GALL Report AMP) Project stage: Other ML0610000962006-03-22022 March 2006 GALL AMP: XI.S1, ASME Section XI, Subsection IWE (Audit Worksheet GALL Report AMP) Project stage: Other ML0609502692006-03-22022 March 2006 GALL AMP: XI.E6, Electrical Cable Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet, GALL Report AMP) Project stage: Other ML0609502622006-03-22022 March 2006 GALL AMP: XI.E5, Fuse Holder (Audit Worksheet GALL Report AMP) Project stage: Other ML0609503312006-03-22022 March 2006 GALL AMP: XI.M10, Boric Acid Corrosion (Audit Worksheet GALL Report AMP) Project stage: Other 1998-02-28
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Category:Report
MONTHYEARML21075A1772021-03-15015 March 2021 Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request BVY 20-026, Defueled Safety Analysis Report, Revision 22020-09-23023 September 2020 Defueled Safety Analysis Report, Revision 2 BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019 ML19198A2522019-06-20020 June 2019 Alternate Disposal Request - Rail Shipments (License DPR-28, Docket No. 50-271) ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum ML15266A4302015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 24, Flow Diagram Instrument Air System. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M. ML15266A4452015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 2 ML15266A4442015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 1 ML15266A4402015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 8 ML15266A4362015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 7 ML15266A4352015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 6 ML15266A4342015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 5 ML15266A4332015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 4 ML15266A4322015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 31, Flow Diagram Instrument Air System. Sheet 3 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 22015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2 ML15266A4292015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 37, Flow Diagram Instrument Air System. Sheet 1 ML15266A4282015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 100, Flow Diagram Service Water System. Sheet 2 ML15266A4272015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 92, Flow Diagram Service Water System. Sheet 1 ML15266A4262015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191152, Rev. 14, General Arrangement Radwaste Building Section. ML15266A4252015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191151, Rev 19, General Arrangement Radwaste Building Plans. ML15266A4242015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191150, Rev. 20, General Arrangement Reactor Building Section. ML15266A4232015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191149, Rev. 27, General Arrangement Reactor Building Plans Sheet 2. ML15266A4222015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191148, Rev. 23, General Arrangement Reactor Building Plans Sheet 1. ML15266A2722015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report - List of Effective Pages BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 52015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5 ML15266A2832015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, DSAR Drawing List BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R. ML15266A2712015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, DSAR Changes ML15266A2732015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, UFSAR to DSAR Conversion Matrix ML15267A6092015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 3 BVY 15-046, Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf.2015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf. ML15267A6612015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191595, Control Room Bldg. Ext. Wall Elevs.-M. ML15267A6592015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191592, Control Room Building Fl Plan El 248.50 & Fdn Plan-R, Sheet 1 ML15267A6562015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191529, Reactor Building Reactor Vessel Pedestal Mat - M&R. ML15267A6542015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R. ML15267A6512015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191463, Circulating Water System Discharge Structure Reinf, Sheet 2 ML15267A6492015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1 ML15267A6472015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191453, Circulating Water System Intake Structure-M, Sheet 3 ML15267A6452015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191452, Circulating Water System Intake Structure-V, Sheet 2 ML15267A6412015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191451, Circulating Water System Intake Structure-M, Sheet 1 ML15267A6112015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5 ML15267A6102015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 120/240V Vital AC and Instrument AC One Line Diagram, Sheet 4 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 12015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1 ML15267A6082015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 2 ML15267A6072015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1 ML15267A6062015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2 ML15267A6052015-09-0101 September 2015 Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 30, 480V Aux. One Line Diagram Swgr BUS-9, MCC-9A, 9C. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 12015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191461, Circulating Water System Discharge Structure - Sections, Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R.2015-09-0101 September 2015 Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191483, Reactor Building Foundation Mat Plan - M&R. 2021-03-15
[Table view] Category:Miscellaneous
MONTHYEARML21075A1772021-03-15015 March 2021 Response to Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019 ML16176A3392016-10-28028 October 2016 Decommissioning Lessons Learned Report and Transmittal Memorandum BVY 15-049, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask BVY 15-018, Transmittal of Biennial 10 CFR 50.59 Report2015-03-0202 March 2015 Transmittal of Biennial 10 CFR 50.59 Report BVY 14-085, Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2014-12-19019 December 2014 Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb) BVY 14-011, Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ...2014-02-25025 February 2014 Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ... BVY 13-090, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2013-10-0202 October 2013 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask BVY 12-081, Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-21021 November 2012 Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML12160A3732012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daichii Nuclear Plant Accident TAC No. ME8747) ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants BVY 07-079, Update of Aging Management Program Audit Q&A Database2007-11-14014 November 2007 Update of Aging Management Program Audit Q&A Database BVY 07-004, Emergency Response Data System (ERDS) Data Point Library Update2007-06-21021 June 2007 Emergency Response Data System (ERDS) Data Point Library Update ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007 Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006 L-87-005, Various CRS 08/09/2005 to 02/08/20072007-02-0808 February 2007 Various CRS 08/09/2005 to 02/08/2007 ML0706703802007-02-0101 February 2007 NDE Reports 07-001 Thru 07-008 ML0701705912007-01-0909 January 2007 VYNPS - SEIS Web Reference - Us Census Glossary ML0701701982006-12-15015 December 2006 VYNPS - SEIS Web Reference - Connecticut River Migratory Fish Counts 1967-2005 ML0629204232006-10-0303 October 2006 (E-Mail) Cooling Tower Report for VY ML0629203422006-09-18018 September 2006 (E-Mail) Air Emissions Inventory Report for 2005 and MSDS for Nalco H-550 ENOC-06-00018, Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 20062006-08-29029 August 2006 Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 2006 BVY 06-068, Cycle 25 Startup Test Report Following Power Ascension and Testing2006-08-0101 August 2006 Cycle 25 Startup Test Report Following Power Ascension and Testing CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006 Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee ML0618803852006-05-22022 May 2006 Windham Regional Plan Draft, May 22, 2006 ML0704404852006-05-12012 May 2006 AMRM-16, Revision 0, Aging Management Review of the Instrument Air System. ML0704404832006-05-12012 May 2006 AMRM-15, Revision 0, Aging Management Review of the Fuel Oil System. ML0704404782006-05-12012 May 2006 AMRM-15, Aging Management Review of the Fuel Oil System ML0704404742006-05-12012 May 2006 AMRM-12, Aging Management Review of the Reactor Building Closed Cooling Water System ML0704404862006-05-11011 May 2006 AMRM-30, Rev. 01, Aging Management Review of Ns Systems Affecting Safety Systems BVY 06-033, Cycle 24 10 CFR 50.59 Report2006-04-24024 April 2006 Cycle 24 10 CFR 50.59 Report BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan2006-03-26026 March 2006 Revision 1 to Steam Dryer Monitoring Plan ML0609503562006-03-22022 March 2006 GALL AMP: XI.M13, Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) (Audit Worksheet GALL Report AMP) ML0609503642006-03-22022 March 2006 GALL AMP: XI.M14, Loose Part Monitoring (Audit Worksheet GALL Report AMP) ML0609502712006-03-22022 March 2006 GALL AMP: XI.M1, ASME Section XI Inservice Inspection, Subsections Iwb, Iwc, and Iwd (Audit Worksheet, GALL Report AMP) ML0609505492006-03-22022 March 2006 GALL AMP: XI.M19, Steam Generator Tube Integrity (Audit Worksheet GALL Report AMP) ML0609502772006-03-22022 March 2006 GALL AMP: XI.M2, Water Chemistry (Audit Worksheet, GALL Report AMP) ML0609502152006-03-22022 March 2006 GALL AMP: X.E1. Environmental Qualification (EQ) of Electric Components (Audit Worksheet GALL Report AMP) ML0609505702006-03-22022 March 2006 GALL AMP: XI.M22, Boraflex Monitoring (Audit Worksheet GALL Report AMP) ML0609502202006-03-22022 March 2006 GALL AMP: X.S1, Concrete Containment Tendon Prestress (Audit Worksheet GALL Report AMP) ML0609502502006-03-22022 March 2006 GALL AMP: XI.E3, Inaccessible Medium-Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements (Audit Worksheet GALL Report AMP) ML0609502582006-03-22022 March 2006 GALL AMP: XI.E4, Metal Enclosed Bus (Audit Worksheet GALL Report AMP) ML0609502622006-03-22022 March 2006 GALL AMP: XI.E5, Fuse Holder (Audit Worksheet GALL Report AMP) ML0609503472006-03-22022 March 2006 GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors ML0609506062006-03-22022 March 2006 GALL AMP: XI.M28, Buried Piping and Tanks Surveillance (Audit Worksheet GALL Report AMP) ML0609506242006-03-22022 March 2006 GALL AMP: XI.M32, One-Time Inspection (Audit Worksheet GALL Report AMP) ML0609502902006-03-22022 March 2006 GALL AMP: XI.M5, BWR Feedwater Nozzle (Audit Worksheet, GALL Report AMP) ML0610000902006-03-22022 March 2006 GALL AMP: XI.M39, Lubricating Oil Analysis Program (Audit Worksheet GALL Report AMP) ML0609503312006-03-22022 March 2006 GALL AMP: XI.M10, Boric Acid Corrosion (Audit Worksheet GALL Report AMP) 2021-03-15
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AUDIT WORKSHEET GALL REPORT AMP PLANT: ______________________________
LRA AMP: __________________________ REVIEWER: ______________________
GALL AMP: XI.M11A, Nickel Alloy Penetration Nozzles Welded to the Upper DATE: __________________________
Reactor Vessel Closure Heads of Pressurized Water Reactors Program Auditable GALL Criteria Documentation of Audit Finding Element Program A. This program is established to ensure that augmented Consistent with GALL AMP: Yes No Description inservice inspections (ISI) of all nickel-alloy vessel head Document(s) used to confirm Criteria:
penetration (VHP) nozzles welded to the upper reactor vessel (RV) head of a PWR-designed light-water reactor will continue to be performed as mandated by the interim requirements in Order EA-03-009, Issuance of Order Establishing Interim Comment:
Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors (PWRs), as amended by the First Revision of the Order, or by any subsequent NRC requirements that may be established to supersede the requirements of Order EA-03-009. Since 1997, the Nuclear Regulatory Commission (NRC) has issued a number of generic communications on the topic of primary water stress corrosion cracking (PWSCC) in upper VHP nozzles. These generic communications included issuance of NRC Generic Letter (GL) 97-01, Bulletin 2001-01, Bulletin 2002-01, and Bulletin 2002-02. In response to its reviews of the industrys responses to these generic communications, the staff determined that PWSCC-induced cracking of upper VHP nozzles was a significant safety issue for operating PWRs that warranted issuance of an NRC Order for augmented inspection of PWR upper VHP nozzles and upper RV heads. On February 11, 2003, the Commission issued Order EA-03-009 to all holders of PWR operating licenses. Order EA-03-009 was issued in accordance with the regulatory bases and XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 1
Program Auditable GALL Criteria Documentation of Audit Finding Element requirements of 10 CFR 2.202 and the adequate protection backfit provisions of 10 CFR 50.109. In this Order, the NRC required specific augmented inspections of reactor vessel closure heads and the associated nickel-alloy penetration nozzles in U.S. PWRs. The NRC issued the First Revised Order EA-03-009 on February 20, 2004, to clarify which locations of the PWR vessel head penetration nozzles were applicable to the requirements of the Order. All PWR licensees in the U.S.
were required to submit 20-day and 60-day responses to Order EA-03-009 and to First Revised Order EA-03-009 (henceforth referred to in this document collectively as the Order, as amended). The Order, as amended, established a mandated augmented inspection process for upper VHP nozzles and upper RV heads that supplements the leakage tests and visual VT-2 examinations requirements established in Section XI of the ASME Boiler and Pressure Vessel Code, Table IWB-2500-1, Examination Category B-P. The interim requirements of the Order, as amended, also established the NRCs required technical method for calculating the susceptibility ranking of a plants upper VHP nozzles to PWSCC and a required process for establishing the inspection methods and inspection frequencies for a plants VHP nozzles in accordance with its susceptibility ranking.
- 1. Scope of A. The program is focused on managing the effects of cracking Consistent with GALL AMP: Yes No Program due to PWSCC of the nickel-alloy used in the fabrication of the Document(s) used to confirm Criteria:
upper VHP nozzles at PWR-designed nuclear facilities. The scope of this AMP is limited to upper VHP nozzles, including control rod drive mechanism (CRDM) nozzles, control element drive mechanism (CEDM) nozzles, thermocouples (TC) nozzles, Comment in-core instrumentation (ICI) nozzles, and vent line nozzles; associated J-groove welds; and the adjoining upper RV closure head.
XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 2
Program Auditable GALL Criteria Documentation of Audit Finding Element
- 2. Preventive A. Preventive measures to mitigate PWSCC are in accordance Consistent with GALL AMP: Yes No Actions with PWR water chemistry guidelines for primary coolant Document(s) used to confirm Criteria:
systems, as established in EPRI Topical Report TR-105714 (applicants for license renewal may credit the version of the report on record at the facility at the time of submittal of its application). The program description and the evaluation and Comment:
technical basis of monitoring and maintaining reactor coolant water chemistry are presented in Chapter XI.M2, "Water Chemistry.
- 3. Parameters A. The program monitors for cracking/PWSCC and loss of Consistent with GALL AMP: Yes No Monitored/ material/wastage in the upper VHP nozzles to ensure the Document(s) used to confirm Criteria:
Inspected structural integrity of the VHP nozzles prior to a loss of their intended safety function.
Comment:
B. The program also monitors for evidence of reactor coolant Consistent with GALL AMP: Yes No leakage as a result of through-wall cracks that may exist in the Document(s) used to confirm Criteria:
upper VHP nozzles or their associated partial penetration J-groove welds. Evidence of reactor coolant leakage may manifest itself in the form of boric acid residues on the upper RV head or adjacent components or in the form of corrosion Comment:
products that result from rusting of the low-alloy steel materials used to fabricate the RVs.
- 4. Detection of A. Implementation of inspections required by the Order, as Consistent with GALL AMP: Yes No Aging Effects amended, or any subsequent NRC requirements, as applicable, Document(s) used to confirm Criteria:
assures detection of cracks in the upper VHP nozzles and any loss of material/wastage of the upper RV head prior to a loss of intended function of the components. Detection of cracking (including those induced by PWSCC) is accomplished through Comment:
implementation of a combination of bare-metal visual examination and/or non-visual examination techniques, as discussed in the Order, as amended. Bare-metal visual examinations required by the Order, as amended, are used to detect reactor coolant leakage from the VHP nozzles or their XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 3
Program Auditable GALL Criteria Documentation of Audit Finding Element associated J-groove welds and for any loss of material that may be induced as a result of boric-acid wastage.
B. Non-visual examination techniques required by the Order, as Consistent with GALL AMP: Yes No amended, are also used to detect these aging effects and are Document(s) used to confirm Criteria:
performed using either surface examination techniques (eddy current or penetrant testing) or volumetric examination techniques (ultrasonic testing).
Comment:
C. The specific types of examinations to be implemented are Consistent with GALL AMP: Yes No dependent on a plants susceptibility ranking for its VHP Document(s) used to confirm Criteria:
nozzles. Inspection methods selected for examination are implemented in accordance with appropriate inspection requirements of Section IV.C of the Order, as amended, as applicable for a plants susceptibility ranking (i.e., in accordance Comment:
with the appropriate inspection methods mandated for Low, Moderate, High, or Replaced susceptibility category plants).
Any deviations from implementing the appropriate required inspection methods of the Order, as amended, will be submitted for NRC review and approval in accordance with the Order, as amended.
- 5. Monitoring A. As required by the Order, as amended, inspection schedules Consistent with GALL AMP: Yes No and Trending and frequencies for the applicants VHP nozzles are Document(s) used to confirm Criteria:
implemented in accordance with required frequencies for the plants susceptibility category (i.e., in accordance with the specific inspection frequencies required for Low, Moderate, High, or Replaced susceptibility categories, as based on the Comment:
total effective degradation years). Any deviations from implementing the required inspection frequencies mandated by XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 4
Program Auditable GALL Criteria Documentation of Audit Finding Element the Order, as amended, will be submitted for NRC review and approval in accordance with the Order, as amended.
Disposition of flaw indications detected during required examinations is implemented in accordance with the Acceptance Criteria and Corrective Actions Program attributes of this AMP.
- 6. Acceptance A. Relevant flaw indications detected as a result of the Consistent with GALL AMP: Yes No Criteria augmented inspections of the upper VHP nozzles are to be Document(s) used to confirm Criteria:
evaluated in accordance with acceptable law evaluation criteria provided in a letter from Mr. Richard Barrett, NRC, Office of Nuclear Reactor Regulation (NRR), Division of Engineering to Alex Marion, Nuclear Energy Institute (NEI), dated April 11, Comment:
2003, or in accordance with NRC-approved Code Cases that incorporate the flaw evaluation procedures and criteria of the NRCs April 11, 2003, letter to NEI.
- 7. Corrective A. Relevant flaw indications in the upper VHP nozzles or their Consistent with GALL AMP: Yes No Actions associated nickel-alloy J-groove weld materials are Document(s) used to confirm Criteria:
unacceptable for further service and are corrected through implementation of appropriate repair or replacement activities.
Comment:
B. In addition, detection of leakage or evidence of cracking in Consistent with GALL AMP: Yes No the VHP nozzles (including associated J-groove welds) of plants Document(s) used to confirm Criteria:
ranked in the Low, Moderate, or Replaced susceptibility categories requires that the plants VHP nozzles be immediately reclassified to the High susceptibility category and that the required augmented inspections for High susceptibility VHP Comment:
nozzles be implemented, commencing from the same outage in which the leakage or cracking was detected. Repair and replacement procedures and activities either must comply with ASME Section XI, as invoked by the requirements of 10 CFR 50.55a, or conform with applicable ASME Code Cases that have been endorsed in 10 CFR 50.55a by reference in the latest version of NRC Regulatory Guide 1.147. Alternative XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 5
Program Auditable GALL Criteria Documentation of Audit Finding Element repair/replacement activities suggested instead of those endorsed by the NRC in either Section XI or NRC-approved Code Cases must be requested for NRC approval in accordance with either the acceptable alternative provisions of 10 CFR 50.55a(a)(3)(i) or hardship provisions of 10 CFR 50.55a(a)(3)(ii).
- 8. A. Site quality assurance (QA) procedures, review and approval Consistent with GALL AMP: Yes No Confirmation processes are implemented in accordance with the Document(s) used to confirm Criteria:
Process 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, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, Comment:
acceptable to address confirmation process and administrative controls.
- 9. A. See Item 8, above. Consistent with GALL AMP: Yes No Administrative Document(s) used to confirm Criteria:
Controls Comment:
- 10. Operating A. PWSCC is occurring in the VHP nozzles of U.S. PWRs, as Consistent with GALL AMP: Yes No Experience described in the program description above. In addition, Document(s) used to confirm Criteria:
applicants for license renewal should reference plant-specific operating experience that is applicable to PWSCC of its VHP nozzles.
Comment:
XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 6
EXCEPTIONS Item Program Elements LRA Exception Description Basis for Accepting Exception Documents Reviewed Number (Identifier, Para.# and/or Page #)
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ENHANCEMENTS Item Program Elements LRA Enhancement Description Basis for Accepting Enhancement Documents Reviewed Number (Identifier, Para.# and/or Page #)
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DOCUMENT REVIEWED DURING AUDIT Document Number Identifier (number) Title Revision and/or Date 1.
2.
3.
4.
XI.M11A Nickel Alloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of PWRs 7