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| {{#Wiki_filter:February 19. 2010 LICENSEE: Arizona Public Service Company | | {{#Wiki_filter:February 19. 2010 LICENSEE: Arizona Public Service Company FACILITY: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 |
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| FACILITY: Palo Verde Nuclear Generating Station, Units 1, 2, and 3 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==SUMMARY== | | ==SUMMARY== |
| OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 28, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on January 28, 2010, to discuss and clarify the staff's draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's draft RAI. | | OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 28, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on January 28, 2010, to discuss and clarify the staffs draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs draft RAI. provides a listing of the participants and Enclosure 2 contains a listing of the draft RAI discussed with the applicant, including a brief description on the status of the items. |
| provides a listing of the participants and Enclosure 2 contains a listing of the draft RAI discussed with the applicant, including a brief description on the status of the items. | | The applicant had an opportunity to comment on this summary. |
| The applicant had an opportunity to comment on this summary. | | /RA/ |
| | Lisa M. Regner, Senior Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-528, 50-529, and 50-530 |
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| | ==Enclosures:== |
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| /RA/ Lisa M. Regner, Senior Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-528, 50-529, and 50-530
| | As stated cc w/encls: See next page |
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| ==Enclosures:==
| | ML100320041 OFFICE PM:RPB2:DLR LA:RPOB:DLR BC:RPB2:DLR PM:RPB2:DLR NAME LRegner DFigueroa DWrona LRegner (Signature) |
| As stated cc w/encls: See next page
| | DATE 02/17/10 02/04/10 02/18/10 02/19/10 |
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| ML100320041 OFFICE PM:RPB2:DLR LA:RPOB:DLR BC:RPB2:DLR PM:RPB2:DLR NAME LRegner DFigueroa DWrona LRegner (Signature) DATE 02/17/10 02/04/10 02/18/10 02/19/10 Memorandum to Arizona Public Service Company from Lisa M. Regner dated February 19, 2010
| | Memorandum to Arizona Public Service Company from Lisa M. Regner dated February 19, 2010 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==SUMMARY== | | ==SUMMARY== |
| OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 28, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION DISTRIBUTION | | OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 28, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION DISTRIBUTION: |
| : | | HARD COPY: |
| HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsOpaMail Resource ------------- L. Regner D. Drucker R. Hall B. Mizuno, OGC R. Treadway, RIV G. Pick, RIV | | DLR RF E-MAIL: |
| | PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsOpaMail Resource |
| | ------------- |
| | L. Regner D. Drucker R. Hall B. Mizuno, OGC R. Treadway, RIV G. Pick, RIV |
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| ENCLOSURE 1 TELEPHONE CONFERENCE CALL PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JANUARY 28, 2010 PARTICIPANTS AFFILIATIONSLisa Re gner U.S. Nuclear Re gulator y Commission (NRC) Robert Sun NRC Wilkins Smith NRC Bob Jackson Advanced Technolo gies and Laboratories (ATL) International, Inc.
| | TELEPHONE CONFERENCE CALL PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JANUARY 28, 2010 PARTICIPANTS AFFILIATIONS Lisa Regner U.S. Nuclear Regulatory Commission (NRC) |
| Wa yne Pavanich ATL An gela Krainik Arizona Public Service Com p an y (APS)Glenn Michael APS Richard Bads gard APS Eric Blocher Strate gic Teamin g and Resource Sharin g (STARS) AllianceDavid Li pinski STARS Gordon Chen STARS
| | Robert Sun NRC Wilkins Smith NRC Bob Jackson Advanced Technologies and Laboratories (ATL) International, Inc. |
| | Wayne Pavanich ATL Angela Krainik Arizona Public Service Company (APS) |
| | Glenn Michael APS Richard Badsgard APS Eric Blocher Strategic Teaming and Resource Sharing (STARS) Alliance David Lipinski STARS Gordon Chen STARS ENCLOSURE 1 |
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| ENCLOSURE 2 DRAFT REQUESTS FOR ADDITIONAL INFORMATION PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION JANUARY 28, 2010
| | DRAFT REQUESTS FOR ADDITIONAL INFORMATION PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION JANUARY 28, 2010 The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on January 28, 2010, to discuss and clarify the following draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, license renewal application (LRA). |
| | DRAFT RAI 3.x.1-1 |
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| The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on January 28, 2010, to discuss and clarify the following draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, license renewal application (LRA).
| | ==Background:== |
| DRAFT RAI 3.x.1-1
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| | Table 3.2.1 of the LRA, item 3.2.1.21 states, Not applicable. PVNGS has no in-scope high-strength steel closure bolting exposed to air with steam or water leakage in the Engineered Safety Features system. |
| Background===
| | The discussion in item 3.2.1.22 states, Not applicable. PVNGS has no closure bolting in Engineered Safety Features systems that is exposed to an environment of water [sic] with steam or water leakage, so the applicable NUREG-1801 line was not used. |
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| | Table 3.3.1 of the LRA, item 3.3.1.42 states, Not applicable. PVNGS has no in-scope steel closure bolting exposed to air with steam or water leakage in the auxiliary systems, so the applicable NUREG-1801 line was not used. |
| Table 3.2.1 of the LRA, item 3.2.1.21 states, "Not applicable. PVNGS has no in-scope high-strength steel closure bolting exposed to air with steam or water leakage in the Engineered Safety Features system." | | The discussion in item 3.3.1.44 states, Not applicable. PVNGS has no in-scope steel closure bolting exposed to condensation in the compressed air system, so the applicable NUREG-1801 line was not used. |
| The discussion in item 3.2.1.22 states, "Not applicable. PVNGS has no closure bolting in Engineered Safety Features systems that is exposed to an environment of water [ | | Issue: |
| sic] with steam or water leakage, so the applicable NUREG-1801 line was not used." | | The discussions in the LRA items described above are not sufficient for the staff to determine whether there is no in-scope closure bolting used in these systems or whether the in-scope closure bolting is used, but these bolts are not exposed to an environment of air with steam or water leakage. |
| Table 3.3.1 of the LRA, item 3.3.1.42 states, "Not applicable. PVNGS has no in-scope steel closure bolting exposed to air with steam or water leakage in the auxiliary systems, so the applicable NUREG-1801 line was not used." | | The discussion in LRA item 3.2.1.22 appears to contain a typographic error, with the word water being used where the word air is intended. |
| The discussion in item 3.3.1.44 states, "Not applicable. PVNGS has no in-scope steel closure bolting exposed to condensation in the compressed air system, so the applicable NUREG-1801 line was not used." | |
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| Issue: The discussions in the LRA items described above are not sufficient for the staff to determine whether there is no in-scope closure bolting used in these systems or whether the in-scope closure bolting is used, but these bolts are not exposed to an environment of air with steam or water leakage. | |
| The discussion in LRA item 3.2.1.22 appears to contain a typographic error, with the word "water" being used where the word "air" is intended. | |
| Request: | | Request: |
| * Clarify whether the discussion in 3.2.1.21 means a) that no high strength closure bolting is used or b) that high strength closure bolting is used, but is not in an environment of air with steam or water leakage. | | * Clarify whether the discussion in 3.2.1.21 means a) that no high strength closure bolting is used or b) that high strength closure bolting is used, but is not in an environment of air with steam or water leakage. |
| | ENCLOSURE 2 |
| * If high strength closure bolting is used, then, provide the basis for your claim that the high strength closure bolting cannot be in an environment of air with steam or water leakage and explain whether monitoring of the high strength bolting is needed to manage the potential aging effect of cracking. | | * If high strength closure bolting is used, then, provide the basis for your claim that the high strength closure bolting cannot be in an environment of air with steam or water leakage and explain whether monitoring of the high strength bolting is needed to manage the potential aging effect of cracking. |
| * Verify if there is a typographic error in 3.2.1.22 and provide the basis for your claim that closure bolting in the Engineered Safety Features (ESF) systems cannot be in an environment of air with steam or water leakage. | | * Verify if there is a typographic error in 3.2.1.22 and provide the basis for your claim that closure bolting in the Engineered Safety Features (ESF) systems cannot be in an environment of air with steam or water leakage. |
| * Provide the basis for your claim in Table 3.3.1, item 3.3.1.42 that in-scope steel closure bolting will not be exposed to air with steam or water leakage in the auxiliary systems. | | * Provide the basis for your claim in Table 3.3.1, item 3.3.1.42 that in-scope steel closure bolting will not be exposed to air with steam or water leakage in the auxiliary systems. |
| * Provide the basis for your claim in Table 3.3.1, item 3.3.1.44, that in-scope steel closure bolting will not be exposed to condensation in the compressed air system. | | * Provide the basis for your claim in Table 3.3.1, item 3.3.1.44, that in-scope steel closure bolting will not be exposed to condensation in the compressed air system. |
| Discussion | | Discussion: Based on the discussion with the applicant, the staff will revise the question as follows. The revised question will be sent as a formal RAI. |
| : Based on the discussion with the applicant, the staff will revise the question as follows. The revised question will be sent as a formal RAI. | | DRAFT RAI 3.3-1 |
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| DRAFT RAI 3.3-1
| | ==Background:== |
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| ===Background===
| | Table 3.2.1 of the LRA, item 3.2.1.21 states, Not applicable. PVNGS has no in-scope high-strength steel closure bolting exposed to air with steam or water leakage in the Engineered Safety Features system. |
| :
| | The discussion in item 3.2.1.22 states, Not applicable. PVNGS has no closure bolting in Engineered Safety Features systems that is exposed to an environment of water [sic] |
| Table 3.2.1 of the LRA, item 3.2.1.21 states, "Not applicable. PVNGS has no in-scope high-strength steel closure bolting exposed to air with steam or water leakage in the Engineered Safety Features system." | | with steam or water leakage, so the applicable NUREG-1801 line was not used. |
| The discussion in item 3.2.1.22 states, "Not applicable. PVNGS has no closure bolting in Engineered Safety Features systems that is exposed to an environment of water [ | | Table 3.3.1 of the LRA, item 3.3.1.42 states, Not applicable. PVNGS has no in-scope steel closure bolting exposed to air with steam or water leakage in the in the auxiliary systems, so the applicable NUREG-1801 line was not used. |
| sic] with steam or water leakage, so the applicable NUREG-1801 line was not used." | | The discussion in item 3.3.1.44 states, Not applicable. PVNGS has no in-scope steel closure bolting exposed to condensation in the compressed air system, so the applicable NUREG-1801 line was not used. |
| | Issue: |
| | The discussion in the LRA, item 3.2.1.21, is not sufficient for the staff to determine whether there is no in-scope high-strength closure bolting used in the Engineered Safety Feature (ESF) systems or whether high-strength closure bolting is used but these bolts are not exposed to an environment of air with steam or water leakage. |
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| Table 3.3.1 of the LRA, item 3.3.1.42 states, "Not applicable. PVNGS has no in-scope steel closure bolting exposed to air with steam or water leakage in the in the auxiliary systems, so the applicable NUREG-1801 line was not used."
| | The discussions in the LRA, items 3.2.1.22, 3.3.1.42, and 3.3.1.44, are not sufficient for the staff to determine why the environments identified in the Generic Aging Lessons Learned (GALL) Report are not applicable for steel closure bolting in the ESF and auxiliary systems. |
| | Request: |
| | a) For Table 3.2.1, item 3.2.1.21, clarify whether high strength closure bolting is used in ESF systems. |
| | b) For Table 3.2.1, item 3.2.1.22 and for Table 3.3.1, items 3.3.1.42 and 3.3.1.44, clarify the basis for your claim that the environments listed in the GALL Report are not applicable for steel closure bolting in ESF or auxiliary systems. |
| | DRAFT RAI 3.3.2-1 |
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| The discussion in item 3.3.1.44 states, "Not applicable. PVNGS has no in-scope steel closure bolting exposed to condensation in the compressed air system, so the applicable NUREG-1801 line was not used."
| | ==Background:== |
| Issue: The discussion in the LRA, item 3.2.1.21, is not sufficient for the staff to determine whether there is no in-scope high-strength closure bolting used in the Engineered Safety Feature (ESF) systems or whether high-strength closure bolting is used but these bolts are not exposed to an environment of air with steam or water leakage. The discussions in the LRA, items 3.2.1.22, 3.3.1.42, and 3.3.1.44, are not sufficient for the staff to determine why the environments identified in the Generic Aging Lessons Learned (GALL) Report are not applicable for steel closure bolting in the ESF and auxiliary systems.
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| Request: a) For Table 3.2.1, item 3.2.1.21, clarify whether high strength closure bolting is used in ESF systems.
| | Table 3.3.2-2 of the LRA, page 3.3-76, includes two aging management review (AMR) line items for closure bolting made of stainless steel in an environment of borated water leakage. For one of these line items, the aging effect requiring management (AERM) is identified as loss of preload which is managed by the Bolting Integrity AMP (B2.1.7); for the other of these line items, the AERM is identified as none, and no aging management program (AMP) is recommended. There also are similar pairs of AMR line items for closure bolting in other LRA tables where for identical materials and environments one AMR line item identifies the AERM as loss of preload managed by the Bolting Integrity AMP and the other line identifies the AERM as none, with no AMP recommended. These occur in LRA Table 3.3.2-4, page 3.3-89 (stainless steel, plant indoor air); Table 3.3.2-5, page 3.3-101 (stainless steel, plant indoor air); Table 3.3.2-7, page 3.3-107 (copper alloy, plant indoor air); Table 3.3.2-8, page 3.3-114 (stainless steel, borated water leakage); and Table 3.3.2-9, page 3.3-122 (copper alloy, plant indoor air). |
| b) For Table 3.2.1, item 3.2.1.22 and for Table 3.3.1, items 3.3.1.42 and 3.3.1.44, clarify the basis for your claim that the environments listed in the GALL Report are not applicable for steel closure bolting in ESF or auxiliary systems.
| | Issue: |
| DRAFT RAI 3.3.2-1
| | Because one of the AMR line items identifies the aging effect of loss of preload to be managed by the Bolting Integrity program and the other AMR line, with the same component, material and environment combination, states that there is no aging effect, the two AMR result lines appear to contradict each other. |
| | Request: |
| | Explain why the AMR line items discussed above specify differing results for closure bolting for the same material and environment. |
| | Discussion: The applicant indicated that the question is clear. This draft question will be sent in a formal RAI, but the question will be re-numbered as 3.3-2. |
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| | DRAFT RAI 3.3.2.2.4-1 |
| Background===
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| : Table 3.3.2-2 of the LRA, page 3.3-76, includes two aging management review (AMR) line items for closure bolting made of stainless steel in an environment of borated water leakage. For one of these line items, the aging effect requiring management (AERM) is identified as loss of preload which is managed by the Bolting Integrity AMP (B2.1.7); for the other of these line items, the AERM is identified as "none," and no aging management program (AMP) is recommended. There also are similar pairs of AMR line items for closure bolting in other LRA tables where for identical materials and environments one AMR line item identifies the AERM as loss of preload managed by the Bolting Integrity AMP and the other line identifies the AERM as "none," with no AMP recommended. These occur in LRA Table 3.3.2-4, page 3.3-89 (stainless steel, plant indoor air); Table 3.3.2-5, page 3.3-101 (stainless steel, plant indoor air); Table 3.3.2-7, page 3.3-107 (copper alloy, plant indoor air); Table 3.3.2-8, page 3.3-114 (stainless steel, borated water leakage); and Table 3.3.2-9, page 3.3-122 (copper alloy, plant indoor air).
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| Issue: Because one of the AMR line items identifies the aging effect of loss of preload to be managed by the Bolting Integrity program and the other AMR line, with the same component, material and environment combination, states that there is no aging effect, the two AMR result lines appear to contradict each other.
| | ==Background:== |
| Request: Explain why the AMR line items discussed above specify differing results for closure bolting for the same material and environment.
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| Discussion
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| : The applicant indicated that the question is clear. This draft question will be sent in a formal RAI, but the question will be re-numbered as 3.3-2. DRAFT RAI 3.3.2.2.4-1
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| ===Background===
| | LRA Sections 3.3.2.2.4.1 Stainless steel PWR non-regenerative heat exchanger components exposed to borated water, 3.3.2.2.4.2 Stainless steel PWR regenerative heat exchanger components exposed to borated water, and 3.3.2.2.4.3 Stainless steel pump casings in the chemical and volume control system state that the Water Chemistry program (B2.1.2) and the One-Time Inspection program (B2.1.16) will manage cracking due to stress corrosion cracking (SSC) and cyclic loading for the stainless steel charging and volume control system (CVCS) letdown (non-regenerative) heat exchanger components, CVCS and nuclear sampling systems regenerative heat exchanger components and stainless steel pump casings exposed to treated borated water. GALL Items VII.E1-5, VII.E1-7, VII.E1-9 recommend AMP XI.M2 Water Chemistry and a plant-specific program to manage cracking due to SSC and cyclic loading for these components. |
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| | Issue: |
| LRA Sections 3.3.2.2.4.1 Stainless steel PWR non-regenerative heat exchanger components exposed to borated water, 3.3.2.2.4.2 Stainless steel PWR regenerative heat exchanger components exposed to borated water, and 3.3.2.2.4.3 Stainless steel pump casings in the chemical and volume control system state that the Water Chemistry program (B2.1.2) and the One-Time Inspection program (B2.1.16) will manage cracking due to stress corrosion cracking (SSC) and cyclic loading for the stainless steel charging and volume control system (CVCS) letdown (non-regenerative) heat exchanger components, CVCS and nuclear sampling systems regenerative heat exchanger components and stainless steel pump casings exposed to treated borated water. GALL Items VII.E1-5, VII.E1-7, VII.E1-9 recommend AMP XI.M2 "Water Chemistry" and a plant-specific program to manage cracking due to SSC and cyclic loading for these components. | | The staff notes that various heat exchangers and pump casing will be subjected to different cyclic loads depending on operating history and therefore each component would need a separate inspection to detect cracking. One-time inspection uses representative sampling to detect aging of components with similar environments. Although all these components are subjected to a treated borated water environment, the cyclic loading history will be different for each component. It is not clear to the staff how the heat exchanger and pump casing one-time inspection program accounts for cyclic loading history for the various components. |
| | Request: |
| | Explain how the heat exchanger and pump casing one-time inspection program accounts for the cyclic loading history for the various components. |
| | Discussion: Based on the discussion with the applicant, the staff deleted the question. |
| | DRAFT RAI 3.3.2.2.5-1 |
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| Issue: The staff notes that various heat exchangers and pump casing will be subjected to different cyclic loads depending on operating history and therefore each component would need a separate inspection to detect cracking. One-time inspection uses representative sampling to detect aging of components with similar environments. Although all these components are subjected to a treated borated water environment, the cyclic loading history will be different for each component. It is not clear to the staff how the heat exchanger and pump casing one-time inspection program accounts for cyclic loading history for the various components.
| | ==Background:== |
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| Request: Explain how the heat exchanger and pump casing one-time inspection program accounts for the cyclic loading history for the various components.
| | Section 3.3.2.2.5.1 of the LRA states that the External Surfaces Monitoring Program will manage hardening and loss of strength from elastomer degradation for elastomer external surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. It also states that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program will manage hardening and loss of strength from elastomer degradation for elastomer internal surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. |
| Discussion
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| : Based on the discussion with the applicant, the staff deleted the question.
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| DRAFT RAI 3.3.2.2.5-1
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| ===Background===
| | Issue: |
| : Section 3.3.2.2.5.1 of the LRA states that the External Surfaces Monitoring Program will manage hardening and loss of strength from elastomer degradation for elastomer external surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. It also states that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program will manage hardening and loss of strength from elastomer degradation for elastomer internal surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. Issue: In Table XI.D of the GALL Report, the temperature of 95 degrees Fahrenheit is identified as a temperature limit below which any thermal aging of organic materials can be considered to be insignificant over the period of extended operation. However, being below this temperature limit does not preclude hardening and loss of strength of due to other aging mechanisms such as exposure to ozone, oxidation, and radiation.
| | In Table XI.D of the GALL Report, the temperature of 95 degrees Fahrenheit is identified as a temperature limit below which any thermal aging of organic materials can be considered to be insignificant over the period of extended operation. However, being below this temperature limit does not preclude hardening and loss of strength of due to other aging mechanisms such as exposure to ozone, oxidation, and radiation. |
| Request: | | Request: |
| * Considering potential aging mechanisms other than thermal aging of organic material, provide a technical basis for using a lower temperature limit of 95 degrees Fahrenheit to select which in-scope elastomer components will be managed for the aging effect of hardening and loss of strength. | | * Considering potential aging mechanisms other than thermal aging of organic material, provide a technical basis for using a lower temperature limit of 95 degrees Fahrenheit to select which in-scope elastomer components will be managed for the aging effect of hardening and loss of strength. |
| * Identify which plant systems contain in-scope elastomer components that will be inspected using this criteria and which plant systems will use this criteria to eliminate inspection of all in-scope elastomer components. | | * Identify which plant systems contain in-scope elastomer components that will be inspected using this criteria and which plant systems will use this criteria to eliminate inspection of all in-scope elastomer components. |
| Discussion | | Discussion: Based on the discussion with the applicant, the staff revised the request of this question as follows. The revised question will be sent as a formal RAI. |
| : Based on the discussion with the applicant, the staff revised the request of this question as follows. The revised question will be sent as a formal RAI. | | DRAFT RAI 3.3.2.2.5-1 |
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| DRAFT RAI 3.3.2.2.5-1
| | ==Background:== |
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| ===Background===
| | Section 3.3.2.2.5.1 of the LRA states that the External Surfaces Monitoring Program will manage hardening and loss of strength from elastomer degradation for elastomer external surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. It also states that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program will manage hardening and loss of strength from elastomer degradation for elastomer internal surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. |
| : Section 3.3.2.2.5.1 of the LRA states that the External Surfaces Monitoring Program will manage hardening and loss of strength from elastomer degradation for elastomer external surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. It also states that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program will manage hardening and loss of strength from elastomer degradation for elastomer internal surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit.
| | Issue: |
| | | In Table XI.D of the GALL Report, the temperature of 95 degrees Fahrenheit is identified as a temperature limit below which any thermal aging of organic materials can be considered to be insignificant over the period of extended operation. However, being below this temperature limit does not preclude hardening and loss of strength due to other aging mechanisms such as exposure to ozone, oxidation, and radiation. |
| Issue: In Table XI.D of the GALL Report, the temperature of 95 degrees Fahrenheit is identified as a temperature limit below which any thermal aging of organic materials can be considered to be insignificant over the period of extended operation. However, being below this temperature limit does not preclude hardening and loss of strength due to other aging mechanisms such as exposure to ozone, oxidation, and radiation. | | Request: |
| Request: Identify which plant systems contain in-scope elastomer components that will be inspected using this criteria and which plant systems will use this criteria to eliminate inspection of all in-scope elastomer components. | | Identify which plant systems contain in-scope elastomer components that will be inspected using this criteria and which plant systems will use this criteria to eliminate inspection of all in-scope elastomer components. |
| Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc: Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, AZ 85007 Mr. Douglas Kent Porter, Senior Counsel Southern California Edison Company Law Department, Generation Resources P.O. Box 800 Rosemead, CA 91770 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 40 Buckeye, AZ 85326 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Chairman Maricopa County Board of Supervisors 301 W. Jefferson, 10th Floor Phoenix, AZ 85003 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 S. 40th Street Phoenix, AZ 85040 Mr. Ron Barnes, Director Regulatory Affairs Palo Verde Nuclear Generating Station Mail Station 7636 P.O. Box 52034 Phoenix, AZ 85072-2034 Mr. Dwight C. Mims, Vice President Regulatory Affairs and Plant Improvement Palo Verde Nuclear Generating Station Mail Station 7605 P.O. Box 52034 Phoenix, AZ 85072-2034 Mr. John C. Taylor, Director, Nuclear Generation El Paso Electric Company 340 E. Palm Lane, Suite 310 Phoenix, AZ 85004
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| Mr. James Ray Public Service Company of New Mexico 2401 Aztec NE, MS Z110 Albuquerque, NM 87107-4224 Mr. Geoffrey M. Cook Southern California Edison Company 5000 Pacific Coast Highway, Bldg. D21 San Clemente, CA 92672 Mr. Robert Henry Salt River Project 6504 E. Thomas Road Scottsdale, AZ 85251 Mr. Jeffrey T. Weikert Assistant General Counsel El Paso Electric Company Mail Location 167 123 W. Mills El Paso, TX 79901
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| Mr. Eric Tharp Los Angeles Department of Water & Power Southern California Public Power Authority P.O. Box 51111, Room 1255-C Los Angeles, CA 90051-0100
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| Mr. Brian Almon Public Utility Commission William B. Travis Building P.O. Box 13326 1701 N. Congress Avenue Austin, TX 78701-3326 | | Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc: |
| | Mr. Steve Olea Mr. John C. Taylor, Director, Nuclear Arizona Corporation Commission Generation 1200 W. Washington Street El Paso Electric Company Phoenix, AZ 85007 340 E. Palm Lane, Suite 310 Phoenix, AZ 85004 Mr. Douglas Kent Porter, Senior Counsel Southern California Edison Company Mr. James Ray Law Department, Generation Resources Public Service Company of New Mexico P.O. Box 800 2401 Aztec NE, MS Z110 Rosemead, CA 91770 Albuquerque, NM 87107-4224 Senior Resident Inspector Mr. Geoffrey M. Cook U.S. Nuclear Regulatory Commission Southern California Edison Company P.O. Box 40 5000 Pacific Coast Highway, Bldg. D21 Buckeye, AZ 85326 San Clemente, CA 92672 Regional Administrator, Region IV Mr. Robert Henry U.S. Nuclear Regulatory Commission Salt River Project 612 E. Lamar Blvd., Suite 400 6504 E. Thomas Road Arlington, TX 76011-4125 Scottsdale, AZ 85251 Chairman Mr. Jeffrey T. Weikert Maricopa County Board of Supervisors Assistant General Counsel 301 W. Jefferson, 10th Floor El Paso Electric Company Phoenix, AZ 85003 Mail Location 167 123 W. Mills Mr. Aubrey V. Godwin, Director El Paso, TX 79901 Arizona Radiation Regulatory Agency 4814 S. 40th Street Mr. Eric Tharp Phoenix, AZ 85040 Los Angeles Department of Water & Power Southern California Public Power Authority Mr. Ron Barnes, Director P.O. Box 51111, Room 1255-C Regulatory Affairs Los Angeles, CA 90051-0100 Palo Verde Nuclear Generating Station Mail Station 7636 Mr. Brian Almon P.O. Box 52034 Public Utility Commission Phoenix, AZ 85072-2034 William B. Travis Building P.O. Box 13326 Mr. Dwight C. Mims, Vice President 1701 N. Congress Avenue Regulatory Affairs and Plant Improvement Austin, TX 78701-3326 Palo Verde Nuclear Generating Station Mail Station 7605 P.O. Box 52034 Phoenix, AZ 85072-2034 |
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| Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc: Mr. Randall K. Edington Executive Vice President Nuclear/CNO Arizona Public Service Company P.O. Box 52034, Mail Station 7602 Phoenix, AZ 85072-2034}} | | Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc: |
| | Mr. Randall K. Edington Executive Vice President Nuclear/CNO Arizona Public Service Company P.O. Box 52034, Mail Station 7602 Phoenix, AZ 85072-2034}} |
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Category:Conference/Symposium/Workshop Paper
MONTHYEARML21194A2502021-08-10010 August 2021 RIC 2021 - Ai EPRI-Artificial Intelligence and Development at EPRI ML12157A2722012-06-11011 June 2012 5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a ML1026600672010-10-15015 October 2010 9/22/10 Summary of Teleconference Held Between U.S. NRC and Arizona Public Service Company, Concerning Draft Request for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, LRA ML1019401422010-10-15015 October 2010 July 8, 2010, Summary of Telephone Conference Call Held Between USNRC and Arizona Public Service Company Concerning D-RAI Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Application ML1017303312010-07-23023 July 2010 06/17/10 Summary of Telephone Conference Call Held Between NRC and Arizona Public Service Co., Concerning Draft Request for Additional Information Pertaining to Palo Verde, Units 1, 2 & 3 License Renewal Application ML1013408292010-07-14014 July 2010 License Renewal - Summary of Conference Calls on Metal Fatigue ML1016005472010-06-25025 June 2010 Summary of Telephone Conference Calls Between the NRC and Arizona Public Service Company Concerning Draft RAI Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Application ML1013302862010-06-0202 June 2010 04/23/10 Summary of Telepone Conference Call Held Between NRC and Arizona Public Service Co., Concerning Palo Verde, Units 1, 2 & 3 License Renewal Application ML1001506182010-03-12012 March 2010 Summary of Telephone Conference Call Held Between NRC and Arizona Public Service Company, Concerning Containment Coatings Pertaining to the Palo Verde, Units 1, 2, and 3, LRA ML1003200412010-02-19019 February 2010 Summary of Telephone Conference Call Held on January 28, 2010, Between the U.S. NRC and Arizona Public Service Company, Concerning Draft RAIs Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Applic ML0908300312009-04-15015 April 2009 01/30/2009 Summary of Telephone Conference Call Held Between NRC and Arizona Public Service Company Pertaining to the Palo Verde Nuclear Operating Station, Units 1, 2, and 3, License Renewal Application ML0510401002005-04-0505 April 2005 Palo Verde Meeting Slides and Predecisional Enforcement & Regulatory Conference Attendance ML18192A8511975-09-30030 September 1975 a Comparison of Experimental and Theoretical Investigations of Embedment Effects on Seismic Response 2021-08-10
[Table view] Category:Meeting Summary
MONTHYEARML23258A1402023-09-27027 September 2023 Summary of August 31, 2023, Presubmittal Meeting with Arizona Public Service Company to Discuss Planned Submittal of License Renewal Commitment Regarding Alloy 600 Management Program Plan at Palo Verde Station, Units 1, 2, & 3 ML23150A1982023-06-0505 June 2023 Summary of 5/25/2023, Presubmittal Meeting with Arizona Public Service Company to Discuss ASME, Section XI Appendix L Alternate Approach to Pressurizer Surge Line Inspections at Palo Verde, Units 1, 2, and 3 ML23097A0692023-04-14014 April 2023 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed License Amendment Request Regarding Containment Temperature and Safety Injection Tank Volume at Palo Verde Units 1, 2, and 3 ML23095A0932023-04-0606 April 2023 Summary of April 4, 2023, Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed License Amendment Request to Adopt TSTF-266 at Palo Verde Nuclear Generating Station ML23072A0312023-03-14014 March 2023 March 1, 2023, Summary of Meeting with Arizona Public Service Company to Discuss Proposed 10 CFR 20.1703 and 20.1705 Requests to Use Supplied Air Suits at Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ML22314A2742022-11-15015 November 2022 October 27, 2022 Meeting with Arizona Public Service Company to Discuss Proposed LAR to Adopt TSTF-107, Revision 4, Separate Control Rods That Are Untrippable Versus Inoperable, for Palo Verde, Units 1, 2, & 3 ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22098A0322022-04-20020 April 2022 Summary of April 6, 2022, Public Meeting with Arizona Public Service Company to Discuss Upcoming License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-487 (EPID L-LRM-0025) ML21347A9522021-12-14014 December 2021 Summary of December 9, 2021, Public Meeting with Arizona Public Service Company to Discuss Upcoming LAR to Adopt TSTF-567, Add Containment TS to Address GSI-191 Issues for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ML21333A0022021-12-0202 December 2021 Summary of Pre-Submittal Meeting with Arizona Public Service Company RIPE Exemption for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ML21278A5462021-10-13013 October 2021 Summary of Meeting with Arizona Public Service Company to Discuss Relief Request No. 68 for Certain ASME Code Piping for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ML21245A4152021-09-0808 September 2021 Summary of Public Meeting with Arizona Public Service Company to Discuss Upcoming Exemption to Eliminate Diverse Auxiliary Feedwater Actuation System Using Risk-Informed Process for Evaluations for Palo Verde Nuclear Generating Station ML21168A2632021-06-24024 June 2021 Summary of June 16, 2021, Public Meeting with Arizona Public Service Company to Discuss Upcoming Relief Request No. 67, Extension of Containment Tendon Inservice Testing from 10 Years to 20 Years for Palo Verde Nuclear Generating Station, U ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21134A0002021-05-18018 May 2021 Summary of Public Meeting with Arizona Public Service Company to Discuss Upcoming Order License Transfer from Pnm to Salt River Project Agriculture Improvement and Power District for Palo Verde, Units 1 and 2 and the ISFSI ML21061A3202021-03-10010 March 2021 Summary of February 25, 2021, Public Meeting with Nuclear Energy Institute to Further Discuss the Inclusion of TSTF-425 Under the Risk-Informed Process for Evaluations Initiative ML21055A8502021-02-24024 February 2021 Public Meeting Summary ML21011A2742021-01-26026 January 2021 Summary of January 6, 2021, Public Meeting with Arizona Public Service Company to Discuss Upcoming LAR Regarding Containment Integrated Leak Rate Test Permanent Extension to 15 Years for Palo Verde Nuclear Generating Station, Units 1, 2, an ML20189A2832020-07-0707 July 2020 Summary of Region IV Annual Assessment Public Meeting ML19219A6122019-08-13013 August 2019 Summary of July 11, 2019, Teleconference with APS to Discuss Proposed License Amendment Request to Revise the Emergency Plan for Palo Verde Nuclear Generating Station ML17353A1902017-12-29029 December 2017 Summary of 12/12/2017, Public Meeting with Arizona Public Service Company, on Proposed Relief Request 50 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ML17003A0352017-01-0404 January 2017 Summary of Pre-Application Meeting with Arizona Public Service to Discuss a Proposed Second Emergency License Amendment Request to Revise Technical Specification 3.8.1, AC (Alternating Current) Sources - Operating, for Palo Verde Nuclear ML16088A0602016-04-15015 April 2016 3/24/16 Summary of Pre-application Meeting with Arizona Public Service Company to Discuss Next Generation Fuel License Amendment Request for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ML16028A3942016-02-12012 February 2016 Summary of Prelicensing Meeting with Arizona Public Service Company to Discuss Next Generation Fuel License Amendment Request for Palo Verde, Units 1, 2, and 3 ML16011A0582016-01-21021 January 2016 Summary of Public Meeting Via Conference Call with Arizona Public Service Company Regarding Ongoing Resolution of Generic Letter 2004-02 for Palo Verde, Units 1, 2, and 3 ML15306A2352015-11-13013 November 2015 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Degraded Voltage Relay Setpoints License Amendment Request for Palo Verde, Units 1, 2, and 3 ML15286A0282015-10-23023 October 2015 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Revised Methodology for Spent Fuel Pool Criticality Analysis and Associated Technical Specification Changes for Palo Verde, Units 1, 2, and 3 (CAC MF6600-MF6602) ML15268A1312015-10-0505 October 2015 Summary of Public Meeting Via Conference Call with Arizona Public Service Company Regarding Ongoing Resolution of Generic Letter 2004-02 for Palo Verde, Units 1, 2, and 3 ML15239B3222015-09-0909 September 2015 Summary of Public Meeting Via Conference Call with Arizona Public Service Company Regarding Ongoing Resolution of Generic Letter 2004-02 for Palo Verde, Units 1, 2, and 3 ML15244B0772015-09-0101 September 2015 Summary of Annual Assessment Meeting with Arizona Public Service Regarding Palo Verde Nuclear Generating Station 2014 Performance ML15173A2892015-06-30030 June 2015 June 9, 2015, Summary of Category 1 Public Meeting with Arizona Public Service Company to Discuss Palo Verde Nuclear Generating Station Seismic Hazard Reevaluation Associated with Implementation of Japan Lessons-Learned NTTF Recommendation ML15140A3142015-06-16016 June 2015 Summary of Preapplication Meeting with Arizona Public Service Company to Discuss Revised Methodology for Spent Fuel Pool Criticality Analysis and Associated Technical Specification Changes for Palo Verde, Units 1, 2, and 3 (TAC MF5843-MF584 ML15117A0422015-04-29029 April 2015 Memorandum to File Summarizing 4/24/15 Telephone Conference Granting Verbal Relief for Relief Request 53, Request for Approval of an Alternative to ASME Code, Section XI, Requirements for Flaw Removal ML15078A0052015-03-25025 March 2015 Summary of 2/18/2015 Preapplication Meeting with Arizona Public Service Company to Discuss License Amendment Request for Palo Verde, Units 1, 2, and 3 on TSTF-505, Risk-Informed Technical Specifications ML14150A1772014-06-0202 June 2014 Summary of Conference Call Regarding Spring 2014 Steam Generator Tube Inspections ML14136A0582014-06-0202 June 2014 5/14/2014 Summary of Meeting with Arizona Public Service Company to Discuss Flooding Hazard Reevaluation Extension Request for Palo Verde, Units 1, 2, and 3; Near-Term Task Force Recommendation 2.1 ML14099A4692014-04-21021 April 2014 Summary of 4/2/2014 Pre-Application Meeting with Arizona Public Service Company to Discuss Extension of Authorized Repair to Palo Verde, Unit 3, Bottom Mounted Instrumentation to End-of-Unit Life ML13333B5742013-12-0505 December 2013 Summary of 11/1/2013 Conference Call Regarding the Fall 2013 Steam Generator Tube Inspections ML13330A5732013-12-0505 December 2013 Verbal Authorization of Relief Request 51, Alternative to ASME Code for Flaw Removal, Reactor Vessel Bottom-mounted Instrumentation Nozzle, Third 10-Year ISI Interval ML13312A5402013-11-18018 November 2013 11/5/2013 Summary of Preapplication Meeting to Discuss License Amendment Request to Incorporate Nuclear Energy Institute NEI-11-04 Quality Assurance Program at Palo Verde, Units 1, 2, and 3 ML13311B1832013-11-18018 November 2013 Summary of Meeting with Arizona Public Service Company to Discuss Non-destructive Examination Efforts, Repairs, and Progress on Root Cause Identified During Inspection of Bottom-Mounted Instrumentation Nozzles at Palo Verde, Unit 3 ML13234A0052013-08-26026 August 2013 8/21/2013 - Summary of Preapplication Meeting with Arizona Public Service Company Low Pressure Safety Injection Pump Single Failure Analysis for Minimum Required Refueling Water Tank Transfer Volume at Palo Verde, Units 1, 2, and 3 ML13203A0852013-08-0505 August 2013 Summary of Preapplication Meeting with Arizona Public Service Company to Discuss License Amendment Request Related to the Startup Test Activity Reduction Program at Palo Verde, Units 1, 2, and 3 (TAC Nos. MF1932-MF1934) ML13154A4502013-06-26026 June 2013 Summary of Meeting Via Conference Call with Arizona Public Service Co. to Discuss Palo Verde Request to Revise Technical Specifications; Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev 3 (TAC ME8160-ME816 ML13161A2522013-06-26026 June 2013 Summary of Conference Call with Arizona Public Service Company to Discuss Draft Requests for Additional Information for Palo Verde, Units 1, 2, and 3 NRC Order Number EA-12-049 Related to Mitigation Strategies (TAC Nos. MF0829-MF0831) ML13154A4322013-06-13013 June 2013 5/30/13 Summary of Conference Call with Arizona Public Service Company to Discuss Draft Requests for Additional Information for Palo Verde, Units 1, 2, and 3 NRC Order Number EA-12-049 Related to Mitigation Strategies (TAC Nos. MF0829-MF083 ML12244A2152012-09-20020 September 2012 8/30/2012 Summary of Meeting with Arizona Public Service Company to Discuss Relief Request 48 - Alternative to ASME Section III, Phased Array Ultrasonic Examination Techniques for Palo Verde, Units 1, 2, and 3 ML12157A2722012-06-11011 June 2012 5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a ML1115704912011-06-0202 June 2011 Meeting Summary for Public Meeting with Arizona Public Service to Discuss the Performance Results for Palo Verde, Units 1, 2 and 3 for the Period of January 1 Through December 31, 2010 ML1111900662011-04-29029 April 2011 3/27/11 Correction to Summary of Pre-Licensing Meeting with Arizona Public Service Company to Discuss Potential Submittal to Revise Technical Specification 3.7.4, Atmospheric Dump Valves, for Palo Verde, Units 1, 2, and 3 (TAC Nos. ME5233-M 2023-09-27
[Table view] Category:Memoranda
MONTHYEARML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21061A3202021-03-10010 March 2021 Summary of February 25, 2021, Public Meeting with Nuclear Energy Institute to Further Discuss the Inclusion of TSTF-425 Under the Risk-Informed Process for Evaluations Initiative ML21006A3242021-01-0707 January 2021 Approval of the Risk-Informed Process for Evaluations ML19120A1972019-04-26026 April 2019 Memo to File Environmental Assessment and Finding of No Significant Impact for Arizona Public Service Company'S Decommissioning Funding Plan Submitted in Accordance with 10 CFR 73.30(b) and 10 CFR 72.30(c) for Palo Verde ISFSI ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML17128A4522017-05-0808 May 2017 Lessons Learned from Modeling the Flex Steam Generator Feed Pump for Palo Verde Nuclear Generating Station ML17082A4462017-03-28028 March 2017 PVNGS Units 1, 2, and 3 Transition to CE 16x16 Ngf - Draft RAIs Rev 3 ML17027A2842017-01-27027 January 2017 Charter for the NRC Special Inspection Team at Palo Verde Nuclear Generating Station-Review of Licensee Actions Related to the Failure of the Unit 3 Train B Emergency Diesel Generator ML17018A1232017-01-17017 January 2017 Management Directive 8.3 Evaluation for Palo Verde Unit 3 Emergency Diesel Generator Failure ML17003A0832017-01-0303 January 2017 Safety Evaluation Input Regarding Changes to Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML17003A3892017-01-0303 January 2017 Safety Evaluation Input Regarding the Palo Verde Nuclear Generating Station Unit 3 Emergency Request to Extend Diesel Generator 3B Completion Time ML17004A2092017-01-0303 January 2017 Safety Evaluation Input for Palo Verde Nuclear Generating Station, Unit 3, Llcense Amendment Request for a One-Time Extension of the 3B Emergency Diesel Generator Completion Time ML16358A4152016-12-23023 December 2016 Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML15205A3602015-07-24024 July 2015 Assessment of Cyber Security Program Draft Temporary Instruction (Ti) Performed at Palo Verde Nuclear Generating Station ML15117A0422015-04-29029 April 2015 Memorandum to File Summarizing 4/24/15 Telephone Conference Granting Verbal Relief for Relief Request 53, Request for Approval of an Alternative to ASME Code, Section XI, Requirements for Flaw Removal ML14115A0452014-06-25025 June 2014 Issuance of Amendment Nos. 193, 193, and 193, Adopt Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 ML13238A0352014-04-22022 April 2014 Memo from P. Lee to M. Markley Palo Verde RAI Memorandum ML13330A5732013-12-0505 December 2013 Verbal Authorization of Relief Request 51, Alternative to ASME Code for Flaw Removal, Reactor Vessel Bottom-mounted Instrumentation Nozzle, Third 10-Year ISI Interval ML13324A4942013-11-19019 November 2013 Deferral of Baseline Inspection Activities ML13294A3732013-10-21021 October 2013 11/4/13 Notice of Meeting with Arizona Public Service Company to Discuss Non-destructive Examination Efforts, Repairs, and Progress on Root Cause Identified During Inspection of Bottom-Mounted Instrumentation Nozzles at Palo Verde, Unit 3 ML13281A2032013-10-0909 October 2013 11/5/2013 Notice of Preapplication Meeting to Discuss License Amendment Request to Incorporate Nuclear Energy Institute NEI-11-04 Quality Assurance Program at Palo Verde, Units 1, 2, and 3 ML13199A0082013-07-22022 July 2013 Meeting Notice with Arizona Public Service Company Low Pressure Safety Injection Pump Single Failure Analysis for Minimum Required Refueling Water Tank Transfer Volume at Palo Verde, Units 1, 2, and 3 ML13154A4832013-06-0404 June 2013 Rai'S Following Ifib Analysis of Ap'S 2013 Decommissioning Funding Status Report for Palo Verde Units 1, 2 and 3 ML13143A0892013-05-23023 May 2013 Meeting Notice with Arizona Public Service Company to Discuss the U.S. Nuclear Regulatory Commission (NRC) Staff'S Draft Request for Additional Information Relating to the February 28, 2013, Submittal ML13105A0182013-05-16016 May 2013 Request for Additional Information Regarding APS Overall Integrated Plan in Response to Order EA-12-049 ML13127A2432013-05-0808 May 2013 5/29/13 Meeting Via Conference Call with Arizona Public Service Company to Discuss Palo Verde Request to Revise Technical Specifications; Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev 3 (TAC ME8160-ME81 ML12227A8562012-08-17017 August 2012 Notice of Meeting with Arizona Public Service Company to Discuss Relief Request 48 - Alternative to ASME Section III, Phased Array Ultrasonic Examination Techniques for Palo Verde, Units 1, 2, and 3 ML12157A2722012-06-11011 June 2012 5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a ML1104604622011-02-15015 February 2011 Minutes Meeting of Palo Verde Nuclear Generating Station Units 1, 2, and 3 License Renewal Subcommittee, September 8, 2010, in Rockville, Maryland ML1030105232010-11-16016 November 2010 Summary of Teleconference Held on Between the U.S. NRC and Arizona Public Service Company, Concerning Draft Follow-Up Request for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2 and 3, LRA ML1029905302010-11-16016 November 2010 Summary of Telephone Conference Call Held on October 22, 2010, Btw the USNRC and Arizona Public Service Company, Concerning D-RAI Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, LRA ML1030900182010-11-0505 November 2010 Notice of Meeting with Arizona Public Service Company to Discuss Palo Verde, Units 1, 2, and 3 License Amendment Request to Revise Technical Specification 3.7.4, Atmospheric Dump Valves. ML1020305002010-10-15015 October 2010 Summary of Tele Conf Call Held on 7/21/10, Btw the USNRC and Arizona Public Service Company, Concerning Draft Request for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal App ML1019401422010-10-15015 October 2010 July 8, 2010, Summary of Telephone Conference Call Held Between USNRC and Arizona Public Service Company Concerning D-RAI Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Application ML1027801622010-10-13013 October 2010 9/15/10 Summary of Public Meeting to Discuss the Draft Supplemental Environmental Impact Statement for Palo Verde Nuclear Generating Station ML1028003402010-10-13013 October 2010 Final Response to Task Interface Agreement - Requirements for Degraded Voltage Relay Setpoints at Palo Verde Nuclear Generating Station (TIA 2010-005 ML1024303382010-10-0505 October 2010 Letter Summary of Telephone Conference Call Held on 8/31/10 Btw the USNRC and Arizona Public Service Company, Concerning Draft Request for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Lr ML1023102542010-08-24024 August 2010 Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement (Dseis) for Palo Verde Nuclear Generating Station ML1021606502010-08-0909 August 2010 Transmittal Letter Advisory Committee on Reactor Safeguards Review of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Application - Safety Evaluation Report ML1017600272010-07-19019 July 2010 Summary of Telecon Calls Held on May 5, May 19, and June 16, 2010 Between the USNRC and Arizona Public Service Company, Concerning D-RAI Pertaining to the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, License Renewal Application ML1013407882010-06-0202 June 2010 Summary of Tele Conf Call Held on 4/14/10, Btw USNRC and APS, Concerning D-RAI Pertaining to the PVNGS, Units 1,2 and 3, License Renewal Application ML1013302522010-06-0202 June 2010 4-13-2010, Telecon Summary Re Draft Request for Additional Information Pertaining to the License Renewal Application ML1013302862010-06-0202 June 2010 04/23/10 Summary of Telepone Conference Call Held Between NRC and Arizona Public Service Co., Concerning Palo Verde, Units 1, 2 & 3 License Renewal Application ML1013406662010-06-0202 June 2010 Summary of Tele Conf Call Held on 4/12/10, Btw the USNRC and APS, Concerning the PVNGS, Units 1, 2, and 3, License Renewal Application ML1013407042010-06-0202 June 2010 License Renewal, May 14, 2010 Conference Call Summary ML1010606402010-04-27027 April 2010 Summary of Tele Conference Call Held on 4/9/10, Btw the USNRC and Arizona Public Service Company, Concerning Draft Requests for Additional Information Pertaining to the Palo Verde Nuclear Generating Station, Units 1,2, and 3, License Renewa ML1009804822010-04-20020 April 2010 05/06/10 Notice of Public Working Meeting with Arizona Public Service to Discuss Issues Related to the Palo Verde Nuclear Generating Station License Renewal Application 2022-06-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24011A1002024-01-10010 January 2024 March 2024 Emergency Preparedness Program Inspection - Request for Information ML23334A1612023-11-30030 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - RAIs Associated with License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue ML23334A0072023-11-29029 November 2023 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR That Revises TSs 3.5.1, SITs - Operating; 3.5.2, SIT Shutdown; 3.6.5, Containment Air Temperature; and SRs for TS 3.5.1, SITs Operating ML23298A1232023-10-25025 October 2023 NRR E-mail Capture - Palo Verde, Unit 1 - RAIs for Relief Request 70, Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle ML23031A3392023-01-31031 January 2023 In-service Inspection Request for Information ML23013A0632023-01-13013 January 2023 NRR E-mail Capture - Palo Verde Unit 1 -Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22348A1672022-12-14014 December 2022 March 2023 Emergency Preparedness Exercise Inspection - Request for Information ML22339A2372022-12-0505 December 2022 NRR E-mail Capture - Palo Verde Unit 1 Request for Additional Information - U1R23 Inspection Summary Report for Steam Generator Tubing ML22272A3252022-09-29029 September 2022 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML22209A1752022-07-28028 July 2022 Inservice Inspection Request for Information ML22187A2632022-07-0606 July 2022 Notification of Inspection (NRC IR 05000528/2022004, 05000529/2022004 and 05000530/2022004) and Request for Information ML22067A2292022-03-0202 March 2022 Inservice Inspection Inspection PWR Request for Information ML22055A5842022-02-24024 February 2022 NRR E-mail Capture - Palo Verde, Unit 3 - Final RAIs for 22nd Refueling Outage (Spring 2021) Steam Generator Tube Inservice Inspection Report ML22035A3302022-02-10010 February 2022 Requests for Confirmation of Information for Exemption to Delete Diverse Auxiliary Feedwater Actuation System Based on Risk-Informed Process for Evaluations ML22025A4012022-01-0303 January 2022 March 2022 Emergency Preparedness Program Inspection - Request for Information ML21245A2222021-09-0101 September 2021 Request for Information ML21200A2392021-07-20020 July 2021 Docs Request AC - AA August 2021 ML21154A0082021-05-26026 May 2021 NRR E-mail Capture - Palo Verde 1, 2 and 3 - Official RAIs for LAR Associated with Permanent Extension of Containment ILRT Frequency to 15 Years (Type a) and CIV Leak Rate Test Frequency to 75 Months (Type C) ML21064A2372021-03-0303 March 2021 ISI Request for Information Rls ML21042B9692021-02-18018 February 2021 Notification of NRC Design Bases Assurance Inspection and Initial Request for Information ML21043A1462021-02-11011 February 2021 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAI for an Order Associated with Indirect License Transfer from Public Service Company of New Mexico to Avangrid, Inc ML21023A0212021-01-13013 January 2021 PVNGS PI&R Request for Information RA ML21011A1972021-01-12012 January 2021 Unit 2, and Unit 3 - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000528/2021012, 05000529/2021012 and 05000530/2021012) and Request for Information ML20227A0992020-08-14014 August 2020 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML20118D1362020-04-28028 April 2020 Licensed Operator Positive Fitness-For-Duty Test Request for Additional Information ML20049A0992020-02-14014 February 2020 Notification of Cyber Security Inspection (NRC Inspection Report 05000528/2020401; 05000529/2020401; and 05000530/2020401) and Request for Information ML20049A0252020-02-12012 February 2020 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 1 - Official RAIs for License Amendment Request Associated with Changes to Emergency Plan Staffing Requirements ML20021A3172020-01-21021 January 2020 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 1 - Official RAIs for Relief Request 64, Impractical Examinations for the Third 10-Year ISI Interval ML19317D0782019-11-13013 November 2019 NRR E-mail Capture - Palo Verde 1 - Requests for Additional Information on Unit 1 21st Refueling Outage Steam Generator Tube Inspection Report ML19234A3202019-08-29029 August 2019 Redacted - Request for Additional Information for Amendment and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel (EPID L-2018-LLA-0194; EPID L-2018-LLE-0010) ML19155A1842019-05-30030 May 2019 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 3 - Mvib Official RAIs for RR-63, Impractical Examinations for the Third 10-Year ISI Interval ML19095A6552019-04-0404 April 2019 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Unit 3 - Mphb Official RAIs for RR-63, Impractical Examinations for the Third 10-Year ISI Interval ML19044A7342019-02-13013 February 2019 NRR E-mail Capture - Palo Verde1, 2, and 3 - Official Requests for Additional Information for RR 62, Third and Fourth 10-Year ISI Intervals, Proposed Alternative - Pressurizer Heat Sleeve Repairs ML19008A3612019-01-0808 January 2019 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for LAR Associated with Response Time Testing of Pressure Transmitters ML18341A0252018-12-0303 December 2018 Notification of NRC Design Bases Assurance Inspection (Teams)(05000528/2019011, 05000529/2019011, and 05000530/2019011) and Initial Request for Information ML18271A0392018-10-0202 October 2018 Non Proprietary - Supplemental Information Needed for Acceptance of Requested License Amendments and Exemptions Implementation of Framatome High Thermal Performance Fuel (Epids L-2018-LLA-0194 and L-2018-LLE-0010) ML18221A5102018-08-23023 August 2018 Request for Additional Information License Amendment Request to Adopt Risk-Informed Completion Times (CAC Nos. MF6576, MF6577, and MF6578; EPID: L-2015-LLA-0001) ML18229A3132018-08-17017 August 2018 NRR E-mail Capture - Request for Additional Information Relief Request 58: Impractical Examinations for the Third 10-Year Inservice Inspection Interval Arizona Public Service Company Palo Verde Nuclear Generation Station, Unit 2 - Second Se ML18227A8672018-08-15015 August 2018 NRR E-mail Capture - Request for Additional Information Relief Request 58: Impractical Examinations for the Third 10-Year Inservice Inspection Interval Arizona Public Service Company Palo Verde Nuclear Generation Station, Unit 2 ML18124A0112018-05-0303 May 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official Eeob RAIs for TSTF-505 (4b) LAR (CAC Nos. MF6576, MF6577, and MF6578; EPID L-2015-LLA-0001) ML18099A0072018-04-0606 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Official RAIs for 10 CFR 50.69 LAR (CAC Nos. MF9971, MF9972, and MF9973; EPID L-2017-LLA-0276) ML18094B1122018-04-0404 April 2018 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAIs for TSTF-505 (Initiative 4b) LAR (CAC Nos. MF6576, MF6577, and MF6578: EPID L-2015-LLA-0001) ML18066A7032018-03-0707 March 2018 Notification of Nrc Design Bases Assurance Inspection (Programs) 05000528/2018011, 05000529/2018011, and 05000530/2018011 Initial Request for Information ML17248A0162017-08-31031 August 2017 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Final RAI for RRs PRR-03, PRR-04 and PRR-05, Pump Testing ML17107A0052017-04-14014 April 2017 NRR E-mail Capture - Palo Verde 1, 2, and 3 - Ngf LAR and Exemption RAIs (CAC Nos. MF8076 to MF8081) ML17082A4462017-03-28028 March 2017 PVNGS Units 1, 2, and 3 Transition to CE 16x16 Ngf - Draft RAIs Rev 3 ML17003A0182017-01-0202 January 2017 NRR E-mail Capture - Palo Verde, Unit 3 - Draft RAIs for the Second Emergency LAR Associated with EDG 3B Failure ML16258A0312016-09-14014 September 2016 PVNGS Units 1-3 - Notif of NRC Insp of the Implementation of Mitigation Strategies and Spent Fuel Pool Instr. Orders and Emer. Prep. Comm./Staffing/Multi-Unit Dose Assessment Plns(05000528/ 2016009;05000529/2016009;and 05000530/2016009) and ML16111B3312016-04-20020 April 2016 Notification of NRC Component Design Bases Inspection (05000528/2016007; 05000529/2016007; 05000530/2016007) and Initial Request for Information ML16083A2502016-03-23023 March 2016 NRR E-mail Capture - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Official RAIs for EAL LAR 2024-01-10
[Table view] |
Text
February 19. 2010 LICENSEE: Arizona Public Service Company FACILITY: Palo Verde Nuclear Generating Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 28, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on January 28, 2010, to discuss and clarify the staffs draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs draft RAI. provides a listing of the participants and Enclosure 2 contains a listing of the draft RAI discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Lisa M. Regner, Senior Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-528, 50-529, and 50-530
Enclosures:
As stated cc w/encls: See next page
ML100320041 OFFICE PM:RPB2:DLR LA:RPOB:DLR BC:RPB2:DLR PM:RPB2:DLR NAME LRegner DFigueroa DWrona LRegner (Signature)
DATE 02/17/10 02/04/10 02/18/10 02/19/10
Memorandum to Arizona Public Service Company from Lisa M. Regner dated February 19, 2010
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JANUARY 28, 2010, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ARIZONA PUBLIC SERVICE COMPANY, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
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L. Regner D. Drucker R. Hall B. Mizuno, OGC R. Treadway, RIV G. Pick, RIV
TELEPHONE CONFERENCE CALL PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JANUARY 28, 2010 PARTICIPANTS AFFILIATIONS Lisa Regner U.S. Nuclear Regulatory Commission (NRC)
Robert Sun NRC Wilkins Smith NRC Bob Jackson Advanced Technologies and Laboratories (ATL) International, Inc.
Wayne Pavanich ATL Angela Krainik Arizona Public Service Company (APS)
Glenn Michael APS Richard Badsgard APS Eric Blocher Strategic Teaming and Resource Sharing (STARS) Alliance David Lipinski STARS Gordon Chen STARS ENCLOSURE 1
DRAFT REQUESTS FOR ADDITIONAL INFORMATION PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION JANUARY 28, 2010 The U.S. Nuclear Regulatory Commission (the staff) and representatives of Arizona Public Service Company (the applicant) held a telephone conference call on January 28, 2010, to discuss and clarify the following draft request for additional information (RAI) concerning the Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3, license renewal application (LRA).
DRAFT RAI 3.x.1-1
Background:
Table 3.2.1 of the LRA, item 3.2.1.21 states, Not applicable. PVNGS has no in-scope high-strength steel closure bolting exposed to air with steam or water leakage in the Engineered Safety Features system.
The discussion in item 3.2.1.22 states, Not applicable. PVNGS has no closure bolting in Engineered Safety Features systems that is exposed to an environment of water [sic] with steam or water leakage, so the applicable NUREG-1801 line was not used.
Table 3.3.1 of the LRA, item 3.3.1.42 states, Not applicable. PVNGS has no in-scope steel closure bolting exposed to air with steam or water leakage in the auxiliary systems, so the applicable NUREG-1801 line was not used.
The discussion in item 3.3.1.44 states, Not applicable. PVNGS has no in-scope steel closure bolting exposed to condensation in the compressed air system, so the applicable NUREG-1801 line was not used.
Issue:
The discussions in the LRA items described above are not sufficient for the staff to determine whether there is no in-scope closure bolting used in these systems or whether the in-scope closure bolting is used, but these bolts are not exposed to an environment of air with steam or water leakage.
The discussion in LRA item 3.2.1.22 appears to contain a typographic error, with the word water being used where the word air is intended.
Request:
- Clarify whether the discussion in 3.2.1.21 means a) that no high strength closure bolting is used or b) that high strength closure bolting is used, but is not in an environment of air with steam or water leakage.
ENCLOSURE 2
- If high strength closure bolting is used, then, provide the basis for your claim that the high strength closure bolting cannot be in an environment of air with steam or water leakage and explain whether monitoring of the high strength bolting is needed to manage the potential aging effect of cracking.
- Verify if there is a typographic error in 3.2.1.22 and provide the basis for your claim that closure bolting in the Engineered Safety Features (ESF) systems cannot be in an environment of air with steam or water leakage.
- Provide the basis for your claim in Table 3.3.1, item 3.3.1.42 that in-scope steel closure bolting will not be exposed to air with steam or water leakage in the auxiliary systems.
- Provide the basis for your claim in Table 3.3.1, item 3.3.1.44, that in-scope steel closure bolting will not be exposed to condensation in the compressed air system.
Discussion: Based on the discussion with the applicant, the staff will revise the question as follows. The revised question will be sent as a formal RAI.
DRAFT RAI 3.3-1
Background:
Table 3.2.1 of the LRA, item 3.2.1.21 states, Not applicable. PVNGS has no in-scope high-strength steel closure bolting exposed to air with steam or water leakage in the Engineered Safety Features system.
The discussion in item 3.2.1.22 states, Not applicable. PVNGS has no closure bolting in Engineered Safety Features systems that is exposed to an environment of water [sic]
with steam or water leakage, so the applicable NUREG-1801 line was not used.
Table 3.3.1 of the LRA, item 3.3.1.42 states, Not applicable. PVNGS has no in-scope steel closure bolting exposed to air with steam or water leakage in the in the auxiliary systems, so the applicable NUREG-1801 line was not used.
The discussion in item 3.3.1.44 states, Not applicable. PVNGS has no in-scope steel closure bolting exposed to condensation in the compressed air system, so the applicable NUREG-1801 line was not used.
Issue:
The discussion in the LRA, item 3.2.1.21, is not sufficient for the staff to determine whether there is no in-scope high-strength closure bolting used in the Engineered Safety Feature (ESF) systems or whether high-strength closure bolting is used but these bolts are not exposed to an environment of air with steam or water leakage.
The discussions in the LRA, items 3.2.1.22, 3.3.1.42, and 3.3.1.44, are not sufficient for the staff to determine why the environments identified in the Generic Aging Lessons Learned (GALL) Report are not applicable for steel closure bolting in the ESF and auxiliary systems.
Request:
a) For Table 3.2.1, item 3.2.1.21, clarify whether high strength closure bolting is used in ESF systems.
b) For Table 3.2.1, item 3.2.1.22 and for Table 3.3.1, items 3.3.1.42 and 3.3.1.44, clarify the basis for your claim that the environments listed in the GALL Report are not applicable for steel closure bolting in ESF or auxiliary systems.
DRAFT RAI 3.3.2-1
Background:
Table 3.3.2-2 of the LRA, page 3.3-76, includes two aging management review (AMR) line items for closure bolting made of stainless steel in an environment of borated water leakage. For one of these line items, the aging effect requiring management (AERM) is identified as loss of preload which is managed by the Bolting Integrity AMP (B2.1.7); for the other of these line items, the AERM is identified as none, and no aging management program (AMP) is recommended. There also are similar pairs of AMR line items for closure bolting in other LRA tables where for identical materials and environments one AMR line item identifies the AERM as loss of preload managed by the Bolting Integrity AMP and the other line identifies the AERM as none, with no AMP recommended. These occur in LRA Table 3.3.2-4, page 3.3-89 (stainless steel, plant indoor air); Table 3.3.2-5, page 3.3-101 (stainless steel, plant indoor air); Table 3.3.2-7, page 3.3-107 (copper alloy, plant indoor air); Table 3.3.2-8, page 3.3-114 (stainless steel, borated water leakage); and Table 3.3.2-9, page 3.3-122 (copper alloy, plant indoor air).
Issue:
Because one of the AMR line items identifies the aging effect of loss of preload to be managed by the Bolting Integrity program and the other AMR line, with the same component, material and environment combination, states that there is no aging effect, the two AMR result lines appear to contradict each other.
Request:
Explain why the AMR line items discussed above specify differing results for closure bolting for the same material and environment.
Discussion: The applicant indicated that the question is clear. This draft question will be sent in a formal RAI, but the question will be re-numbered as 3.3-2.
DRAFT RAI 3.3.2.2.4-1
Background:
LRA Sections 3.3.2.2.4.1 Stainless steel PWR non-regenerative heat exchanger components exposed to borated water, 3.3.2.2.4.2 Stainless steel PWR regenerative heat exchanger components exposed to borated water, and 3.3.2.2.4.3 Stainless steel pump casings in the chemical and volume control system state that the Water Chemistry program (B2.1.2) and the One-Time Inspection program (B2.1.16) will manage cracking due to stress corrosion cracking (SSC) and cyclic loading for the stainless steel charging and volume control system (CVCS) letdown (non-regenerative) heat exchanger components, CVCS and nuclear sampling systems regenerative heat exchanger components and stainless steel pump casings exposed to treated borated water. GALL Items VII.E1-5, VII.E1-7, VII.E1-9 recommend AMP XI.M2 Water Chemistry and a plant-specific program to manage cracking due to SSC and cyclic loading for these components.
Issue:
The staff notes that various heat exchangers and pump casing will be subjected to different cyclic loads depending on operating history and therefore each component would need a separate inspection to detect cracking. One-time inspection uses representative sampling to detect aging of components with similar environments. Although all these components are subjected to a treated borated water environment, the cyclic loading history will be different for each component. It is not clear to the staff how the heat exchanger and pump casing one-time inspection program accounts for cyclic loading history for the various components.
Request:
Explain how the heat exchanger and pump casing one-time inspection program accounts for the cyclic loading history for the various components.
Discussion: Based on the discussion with the applicant, the staff deleted the question.
DRAFT RAI 3.3.2.2.5-1
Background:
Section 3.3.2.2.5.1 of the LRA states that the External Surfaces Monitoring Program will manage hardening and loss of strength from elastomer degradation for elastomer external surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. It also states that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program will manage hardening and loss of strength from elastomer degradation for elastomer internal surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit.
Issue:
In Table XI.D of the GALL Report, the temperature of 95 degrees Fahrenheit is identified as a temperature limit below which any thermal aging of organic materials can be considered to be insignificant over the period of extended operation. However, being below this temperature limit does not preclude hardening and loss of strength of due to other aging mechanisms such as exposure to ozone, oxidation, and radiation.
Request:
- Considering potential aging mechanisms other than thermal aging of organic material, provide a technical basis for using a lower temperature limit of 95 degrees Fahrenheit to select which in-scope elastomer components will be managed for the aging effect of hardening and loss of strength.
- Identify which plant systems contain in-scope elastomer components that will be inspected using this criteria and which plant systems will use this criteria to eliminate inspection of all in-scope elastomer components.
Discussion: Based on the discussion with the applicant, the staff revised the request of this question as follows. The revised question will be sent as a formal RAI.
DRAFT RAI 3.3.2.2.5-1
Background:
Section 3.3.2.2.5.1 of the LRA states that the External Surfaces Monitoring Program will manage hardening and loss of strength from elastomer degradation for elastomer external surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit. It also states that the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program will manage hardening and loss of strength from elastomer degradation for elastomer internal surfaces exposed to plant indoor air (uncontrolled) in locations where the ambient temperature cannot be shown to be less than 95 degrees Fahrenheit.
Issue:
In Table XI.D of the GALL Report, the temperature of 95 degrees Fahrenheit is identified as a temperature limit below which any thermal aging of organic materials can be considered to be insignificant over the period of extended operation. However, being below this temperature limit does not preclude hardening and loss of strength due to other aging mechanisms such as exposure to ozone, oxidation, and radiation.
Request:
Identify which plant systems contain in-scope elastomer components that will be inspected using this criteria and which plant systems will use this criteria to eliminate inspection of all in-scope elastomer components.
Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc:
Mr. Steve Olea Mr. John C. Taylor, Director, Nuclear Arizona Corporation Commission Generation 1200 W. Washington Street El Paso Electric Company Phoenix, AZ 85007 340 E. Palm Lane, Suite 310 Phoenix, AZ 85004 Mr. Douglas Kent Porter, Senior Counsel Southern California Edison Company Mr. James Ray Law Department, Generation Resources Public Service Company of New Mexico P.O. Box 800 2401 Aztec NE, MS Z110 Rosemead, CA 91770 Albuquerque, NM 87107-4224 Senior Resident Inspector Mr. Geoffrey M. Cook U.S. Nuclear Regulatory Commission Southern California Edison Company P.O. Box 40 5000 Pacific Coast Highway, Bldg. D21 Buckeye, AZ 85326 San Clemente, CA 92672 Regional Administrator, Region IV Mr. Robert Henry U.S. Nuclear Regulatory Commission Salt River Project 612 E. Lamar Blvd., Suite 400 6504 E. Thomas Road Arlington, TX 76011-4125 Scottsdale, AZ 85251 Chairman Mr. Jeffrey T. Weikert Maricopa County Board of Supervisors Assistant General Counsel 301 W. Jefferson, 10th Floor El Paso Electric Company Phoenix, AZ 85003 Mail Location 167 123 W. Mills Mr. Aubrey V. Godwin, Director El Paso, TX 79901 Arizona Radiation Regulatory Agency 4814 S. 40th Street Mr. Eric Tharp Phoenix, AZ 85040 Los Angeles Department of Water & Power Southern California Public Power Authority Mr. Ron Barnes, Director P.O. Box 51111, Room 1255-C Regulatory Affairs Los Angeles, CA 90051-0100 Palo Verde Nuclear Generating Station Mail Station 7636 Mr. Brian Almon P.O. Box 52034 Public Utility Commission Phoenix, AZ 85072-2034 William B. Travis Building P.O. Box 13326 Mr. Dwight C. Mims, Vice President 1701 N. Congress Avenue Regulatory Affairs and Plant Improvement Austin, TX 78701-3326 Palo Verde Nuclear Generating Station Mail Station 7605 P.O. Box 52034 Phoenix, AZ 85072-2034
Palo Verde Nuclear Generating Station, Units 1, 2, and 3 cc:
Mr. Randall K. Edington Executive Vice President Nuclear/CNO Arizona Public Service Company P.O. Box 52034, Mail Station 7602 Phoenix, AZ 85072-2034