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| | number = ML13030A401 | | | number = ML13030A401 |
| | issue date = 01/30/2013 | | | issue date = 01/30/2013 |
| | title = Palo Verde, Units 1, 2, and 3 - Request for Additional Information E-mail, Relief Request 49, Alternative to ASME Code Section Xi for Reactor Vessel Head Flange Seal Leak Detection Piping, Third 10-Year Inservice Inspection Interval (TAC MF | | | title = Request for Additional Information E-mail, Relief Request 49, Alternative to ASME Code Section XI for Reactor Vessel Head Flange Seal Leak Detection Piping, Third 10-Year Inservice Inspection Interval (TAC MF0447-MF0449) |
| | author name = Gibson L K | | | author name = Gibson L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Roehler R | | | addressee name = Roehler R |
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| | docket = 05000528, 05000529, 05000530 | | | docket = 05000528, 05000529, 05000530 |
| | license number = NPF-041, NPF-051, NPF-074 | | | license number = NPF-041, NPF-051, NPF-074 |
| | contact person = Gibson L K | | | contact person = Gibson L |
| | case reference number = TAC MF0447, TAC MF0448, TAC MF0449 | | | case reference number = TAC MF0447, TAC MF0448, TAC MF0449 |
| | document type = E-Mail, Request for Additional Information (RAI) | | | document type = E-Mail, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:Lent, Susan From: Gibson, Lauren Sent: Wednesday, January 30, 20132:40 PM To: 'Robert. Roehler@aps.com' Subject: RAls for RR49 Reactor Vessel Head Flange Seal Leak Detection Piping (TAC Nos. MF0447, 8,9) Attachments: MF0447 RAls.doc Rob, By letter dated December 19, 2012 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 12361A256), Arizona Public Service Company (APS, the licensee) submitted "Reactor Pressure Vessel Head Flange Seal Leak Detection Piping -Relief Request No. 49" for U. S. Nuclear Regulatory Commission (NRC) review and authorization. The licensee has proposed an alternative to the system leakage test of reactor pressure vessel (RPV) flange leak-off line that is required by the American Society of Mechanical Engineers (ASIVIE) Boiler and Pressure Vessel Code (Code), Section XI, Table 2500-1, Examination Category C-H, at Palo Verde Nuclear Generating Station (PVNGS), Units 1,2, and 3. Specifically, instead of pressurizing the subject lines to the system leakage test pressure required by IWC-5221, the licensee proposes to pressurize the line using the static pressure head of the refueling water prior to performing a VT-2 visual examination. In order to complete our review, the staff requests the following additional information. The Nuclear Regulatory Commission (NRC) staff has reviewed the submitted information and determined that the additional information identified in the enclosure is needed to complete its review. On January 30, you confirmed a response date of February 22, 2013. Thank you, Lauren Lauren K. Gibson Project Manager Columbia Generating Station Palo Verde Nuclear Generating Station Division of Operatillg Reactor Licensing U.S. Nuclear Regulatory Commission (301) 415-1056 1 REQUEST FOR ADDITIONAL INFORMATION REACTOR VESSEL HEAD FLANGE SEAL LEAK DETECTION PIPING -RELIEF REQUEST NO. 49 ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 DOCKET NOS. SO-S28, SO-S29, AND SO-S30 By letter dated December 19, 2012 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 12361A2S6), Arizona Public Service Company (APS, the licensee) submitted "Reactor Pressure Vessel Head Flange Seal Leak Detection Piping -Relief Request No. 49" for U. S. Nuclear Regulatory Commission (NRC) review and authorization. The licensee has proposed an alternative to the system leakage test of reactor pressure vessel (RPV) flange leak-off line that is required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), Section XI, Table IWC-2S00-1, Examination Category C-H, at Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3. Specifically, instead of pressurizing the subject lines to the system leakage test pressure required by IWC-S221, the licensee proposes to pressurize the line using the static pressure head of the refueling water prior to performing a VT -2 visual examination. I n order to complete our review, the staff requests the following additional information. What are the scheduled end dates for the PVNGS, Unit 1,2, and 3 third inservice inspection The proposed alternative is being submitted pursuant to Title 10 of the Code of Federal Regulations, Part SO (10 CFR SO), paragraph SSa(g)(S)(ii), revised inservice inspection program for a facility conflicts with the technical specification for the facility, but cites the provisions of 10 CFR SO.SSa(a)(3)(ii), hardship without a compensating increase in the level of quality and safety. Please confirm that the relief request is being submitted pursuant to 10 CFR SO.SSa(a)(3)(ii). Provide a brief description of the operation of the RPV flange seal leak detection system, i.e., how the pressure in the leak-off line is measured and monitored, how the operators are alerted to a leakage condition and how they respond. If O-ring leakage trips the leak-off alarm and rapid depressurization of the leak-off line subsequently occurs, does the control room annunciator continue to show an indication? Are there other control room indications of O-ring leakage? Provide a piping and instrumentation diagram (P&ID) and a piping isometric drawing showing the RPV flange seal leak detection piping. What is the material of construction of the leak-off line? ENCLOSURE | | {{#Wiki_filter:Lent, Susan From: Gibson, Lauren Sent: Wednesday, January 30, 20132:40 PM To: 'Robert. Roehler@aps.com' |
| -Describe PVNGS experience with degradation (corrosion, stress corrosion cracking, fatigue, etc.) of the RPV flange seal leak detection piping. Potential O-ring leakage during service is detected with a pressure element in the off line. The proposed alternative would utilize the static fluid head of the refueling water to pressurize the leak-off line prior to a VT-2 examination. What is the fluid head pressure that exists in the line when the refueling cavity has been filled to its normal refueling water level? What is the trip pressure for the O-ring leakage alarm indication in the control room? Discuss whether a system leakage test of the RPV flange seal leak detection piping could be performed at a pressure higher than that of the refueling water fluid head prior to removing the head at the beginning of the refueling outage. Describe any hardship associated with this sequence. In order for a fluid leak in a pressurized line to be observed with a VT-2 examination, sufficient time must have elapsed between the time that the line was pressurized and the time that the examination is performed. Specify the minimum time between the time that the line is pressurized and the time that the VT-2 examination is performed for both uninsulated lines and insulated lines (as appropriate). Provide a technical justification based on the pressure in the leak-off line during the leakage test for the hold time. | | |
| }} | | ==Subject:== |
| | RAls for RR49 Reactor Vessel Head Flange Seal Leak Detection Piping (TAC Nos. MF0447, 8,9) |
| | Attachments: MF0447 RAls.doc Rob, By letter dated December 19, 2012 (Agencywide Document Access and Management System (ADAMS) |
| | Accession No. ML12361A256), Arizona Public Service Company (APS, the licensee) submitted "Reactor Pressure Vessel Head Flange Seal Leak Detection Piping - Relief Request No. 49" for U. S. Nuclear Regulatory Commission (NRC) review and authorization. The licensee has proposed an alternative to the system leakage test of reactor pressure vessel (RPV) flange leak-off line that is required by the American Society of Mechanical Engineers (ASIVIE) Boiler and Pressure Vessel Code (Code), Section XI, Table IWC 2500-1, Examination Category C-H, at Palo Verde Nuclear Generating Station (PVNGS), Units 1,2, and 3. |
| | Specifically, instead of pressurizing the subject lines to the system leakage test pressure required by IWC-5221, the licensee proposes to pressurize the line using the static pressure head of the refueling water prior to performing a VT-2 visual examination. In order to complete our review, the staff requests the following additional information. |
| | The Nuclear Regulatory Commission (NRC) staff has reviewed the submitted information and determined that the additional information identified in the enclosure is needed to complete its review. |
| | On January 30, you confirmed a response date of February 22, 2013. |
| | Thank you, Lauren Lauren K. Gibson Project Manager Columbia Generating Station Palo Verde Nuclear Generating Station Division of Operatillg Reactor Licensing U.S. Nuclear Regulatory Commission (301) 415-1056 1 |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION REACTOR VESSEL HEAD FLANGE SEAL LEAK DETECTION PIPING - RELIEF REQUEST NO. 49 ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 DOCKET NOS. SO-S28, SO-S29, AND SO-S30 By letter dated December 19, 2012 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 12361A2S6), Arizona Public Service Company (APS, the licensee) submitted "Reactor Pressure Vessel Head Flange Seal Leak Detection Piping - Relief Request No. 49" for U. S. Nuclear Regulatory Commission (NRC) review and authorization. The licensee has proposed an alternative to the system leakage test of reactor pressure vessel (RPV) flange leak-off line that is required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), Section XI, Table IWC-2S00-1, Examination Category C-H, at Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3. |
| | Specifically, instead of pressurizing the subject lines to the system leakage test pressure required by IWC-S221, the licensee proposes to pressurize the line using the static pressure head of the refueling water prior to performing a VT-2 visual examination. In order to complete our review, the staff requests the following additional information. |
| | : 1. What are the scheduled end dates for the PVNGS, Unit 1,2, and 3 third 10-year inservice inspection interval? |
| | : 2. The proposed alternative is being submitted pursuant to Title 10 of the Code of Federal Regulations, Part SO (10 CFR SO), paragraph SSa(g)(S)(ii), revised inservice inspection program for a facility conflicts with the technical specification for the facility, but cites the provisions of 10 CFR SO.SSa(a)(3)(ii), hardship without a compensating increase in the level of quality and safety. Please confirm that the relief request is being submitted pursuant to 10 CFR SO.SSa(a)(3)(ii). |
| | : 3. Provide a brief description of the operation of the RPV flange seal leak detection system, i.e., how the pressure in the leak-off line is measured and monitored, how the operators are alerted to a leakage condition and how they respond. |
| | : a. If O-ring leakage trips the leak-off alarm and rapid depressurization of the leak-off line subsequently occurs, does the control room annunciator continue to show an indication? |
| | : b. Are there other control room indications of O-ring leakage? |
| | : 4. Provide a piping and instrumentation diagram (P&ID) and a piping isometric drawing showing the RPV flange seal leak detection piping. |
| | S. What is the material of construction of the leak-off line? |
| | ENCLOSURE |
| | |
| | - 2 |
| | : 6. Describe PVNGS experience with degradation (corrosion, stress corrosion cracking, fatigue, etc.) of the RPV flange seal leak detection piping. |
| | : 7. Potential O-ring leakage during service is detected with a pressure element in the leak off line. The proposed alternative would utilize the static fluid head of the refueling water to pressurize the leak-off line prior to a VT-2 examination. |
| | : a. What is the fluid head pressure that exists in the line when the refueling cavity has been filled to its normal refueling water level? |
| | : b. What is the trip pressure for the O-ring leakage alarm indication in the control room? |
| | : 8. Discuss whether a system leakage test of the RPV flange seal leak detection piping could be performed at a pressure higher than that of the refueling water fluid head prior to removing the head at the beginning of the refueling outage. Describe any hardship associated with this sequence. |
| | : 9. In order for a fluid leak in a pressurized line to be observed with a VT-2 examination, sufficient time must have elapsed between the time that the line was pressurized and the time that the examination is performed. Specify the minimum time between the time that the line is pressurized and the time that the VT-2 examination is performed for both uninsulated lines and insulated lines (as appropriate). Provide a technical justification based on the pressure in the leak-off line during the leakage test for the hold time.}} |
Letter Sequence RAI |
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MONTHYEARML12361A2562012-12-19019 December 2012
Request for Relief from the American Society of Mechanical Engineers (ASME) Code, Section XI, Reactor Vessel Head Flange Seal Leak Detection Piping - Relief Request No. 49
Project stage: Request
ML13009A0842013-01-0909 January 2013
Acceptance Review Email, Relief Request 49, Alternative to ASME Code Section XI for Reactor Vessel Head Flange Seal Leak Detection Piping, Third 10-Year Inservice Inspection Interval
Project stage: Acceptance Review
ML13030A4012013-01-30030 January 2013
Request for Additional Information E-mail, Relief Request 49, Alternative to ASME Code Section XI for Reactor Vessel Head Flange Seal Leak Detection Piping, Third 10-Year Inservice Inspection Interval (TAC MF0447-MF0449)
Project stage: RAI
ML13063A0622013-02-22022 February 2013
Response to Request for Additional Information (RAI) - Request for Relief from the American Society of Mechanical Engineers (ASME) Code, Section XI, Reactor Vessel Head Flange Seal Leak Detection Piping - Relief Request 49
Project stage: Response to RAI
ML13085A2542013-04-0404 April 2013
Relief Request 49, Alternative to ASME Code, Section XI, for Reactor Vessel Head Flange Seal Leak Detection Piping, Third 10-Year Inservice Inspection Interval
Project stage: Other
2013-01-09
[Table View] |
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Category:E-Mail
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
ML23243B0082023-08-31031 August 2023
NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX)
ML23233A0132023-08-18018 August 2023
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of License Renewal Commitment for Pressurizer Surge Line Welds Inspection Program to Manage Environmentally Assisted Fatigue
ML23220A0512023-08-0303 August 2023
NRR E-mail Capture - Re Palo Verde 1, 2, and 3 - SUNSI Review of UFSAR, Rev. 22
ML23202A0162023-07-20020 July 2023
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Revise 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
ML23143A1332023-05-23023 May 2023
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR Revising TS 3.3.11 to Adopt TSTF-266-A, Rev. 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls
ML23130A0132023-05-10010 May 2023
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for Authorized Use of Mururoa Supplied Air Suits (Models V4F1 and MTH2) Pursuant to 10 CFR 20.1703 and 10 CFR 20.1705
ML23017A0932023-01-17017 January 2023
NRR E-mail Capture - Palo Verde - Acceptance of License Amendment Request Regarding Adoption of TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable (L-2022-LLA-0181)
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
ML22173A0682022-06-17017 June 2022
Email Concurrence on SE Input for Columbia Pltr LAR
ML22167A1872022-06-16016 June 2022
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Revised Acceptance Review of LAR to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
ML22136A0922022-05-16016 May 2022
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Adopt TSTF-487-A, Revision 1, Relocate DNB Parameters to the COLR
ML22075A1902022-03-16016 March 2022
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
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
ML22034A0132022-02-0202 February 2022
NRR E-mail Capture - Palo Verde, Unit 2 - Verbal Approval of RR-69 to Extend Containment Tendon Inspection from 2/8/22 to 6/8/22
ML22032A0312022-01-31031 January 2022
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for an Exemption Regarding Elimination of Dafas Using RIPE Process
ML22025A4012022-01-0303 January 2022
March 2022 Emergency Preparedness Program Inspection - Request for Information
ML21333A1982021-11-19019 November 2021
NRC Review of PVNGS Training Needs Analysis and Training Required by Condition I of the Confirmatory Order EA-20-054
ML21306A1882021-10-18018 October 2021
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Second Pre-submittal Meeting for the Proposed Exemption to Eliminate Dafas Using RIPE Process
ML21272A0592021-09-28028 September 2021
NRR E-mail Capture - Palo Verde 1, 2, and 3 - SUNSI Review of UFSAR, Rev. 21
ML21264A1352021-09-17017 September 2021
NRR E-mail Capture - Palo Verde 1, 2 and 3 - Acceptance Review of 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)
ML21237A0762021-08-25025 August 2021
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of RR-67, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection
ML21228A0082021-08-16016 August 2021
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of an LAR for Administrative Changes to Technical Specifications
ML21228A1042021-08-12012 August 2021
RR-67, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (EPID L-2021-LLR-0050) (Email)
ML21237A5172021-08-10010 August 2021
Email to PV Licensee and Palo Verde Nuclear Generating Station, Units 1, 2 and 3 - Notification of Inspection of the Licensees Implementation Industry Initiative Associated with the Open Phase Condition (NRC Bulletin 2012-01) and Request Fo
ML21160A1442021-06-0909 June 2021
NRR E-mail Capture - Palo Verde 1 and, 2 - Acceptance Review for Order Approving Transfers of Control of Licenses for Minority Interests Subject to Expiring Leases
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)
ML21146A3342021-05-14014 May 2021
ISFSI - Final Package for an Order Associated with Indirect Transfers of Control of Licenses from Pnm to Avangrid
ML21132A2372021-05-12012 May 2021
NRR E-mail Capture - Palo Verde 1, 2, and 3, and ISFSI - Final Package for an Order Associated with Indirect Transfers of Control of Licenses from Pnm to Avangrid
ML21103A3632021-04-13013 April 2021
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review for Indirect Transfer of Control of Licenses Pursuant to 10 CFR 50.80 and 10 CFR 72.50
ML21064A2372021-03-0303 March 2021
ISI Request for Information Rls
ML21053A0262021-02-22022 February 2021
NRR E-mail Capture - Palo Verde 1, 2 and 3 - Acceptance Review of 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)
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
ML20366A1682020-12-31031 December 2020
NRR E-mail Capture - Palo Verde 1, 2, and 3, and ISFSI - Acceptance Review of an Order Associated with Indirect Transfers of Control of Licenses
ML21005A2712020-12-29029 December 2020
102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054
ML20325A0392020-11-19019 November 2020
NRR E-mail Capture - Palo Verde 2 - Verbal Authorization of RR 66 to Extend Containment Tendon Inspection by One Year Based on 10 CFR 50.55a(Z)(2)
ML20316A0162020-11-0909 November 2020
NRR E-mail Capture - Palo Verde 2 - Acceptance Review of RR 66, Request Containment Post-Tensioning System Inspection One-Time by One Year Due to COVID-19 Pandemic
ML20295A4912020-10-21021 October 2020
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of LAR Associated with Adopting TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control
ML20265A0982020-09-21021 September 2020
NRR E-mail Capture - Palo Verde 1, 2, and 3 - Acceptance Review of License Amendment Associated with Making Necessary Administrative Changes to Technical Specifications
ML20108E9462020-04-16016 April 2020
NRR E-mail Capture - (External_Sender) Clarification to PVNGS Part 26 Exemption Request (ML20105A481)
ML20091K0752020-03-31031 March 2020
NRR E-mail Capture - Palo Verde 2 - Acceptance Review of RR 65, Request for Relief from RPV Bottom Mounted Instrumentation Nozzles and a Pressurizer Surge Line Weld Overlay Examination
ML20091M1992020-03-31031 March 2020
NRR E-mail Capture - Palo Verde 2 - Verbal Authorization of RR 65, Request for Relief from RPV Bottom Mounted Instrumentation Nozzles and a Pressurizer Surge Line Weld Overlay ISI Examinations
ML20050C9742020-02-19019 February 2020
NRR E-mail Capture - Palo Verde 1,2, and 3 - Framatome Htp Fuel LAR and Exemption Third Audit Summary (EPIDs L-2018-LLA-0194 and L-2018-LLE-0010)
2024-01-10
[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)
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2024-01-10
[Table view] |
Text
Lent, Susan From: Gibson, Lauren Sent: Wednesday, January 30, 20132:40 PM To: 'Robert. Roehler@aps.com'
Subject:
RAls for RR49 Reactor Vessel Head Flange Seal Leak Detection Piping (TAC Nos. MF0447, 8,9)
Attachments: MF0447 RAls.doc Rob, By letter dated December 19, 2012 (Agencywide Document Access and Management System (ADAMS)
Accession No. ML12361A256), Arizona Public Service Company (APS, the licensee) submitted "Reactor Pressure Vessel Head Flange Seal Leak Detection Piping - Relief Request No. 49" for U. S. Nuclear Regulatory Commission (NRC) review and authorization. The licensee has proposed an alternative to the system leakage test of reactor pressure vessel (RPV) flange leak-off line that is required by the American Society of Mechanical Engineers (ASIVIE) Boiler and Pressure Vessel Code (Code),Section XI, Table IWC 2500-1, Examination Category C-H, at Palo Verde Nuclear Generating Station (PVNGS), Units 1,2, and 3.
Specifically, instead of pressurizing the subject lines to the system leakage test pressure required by IWC-5221, the licensee proposes to pressurize the line using the static pressure head of the refueling water prior to performing a VT-2 visual examination. In order to complete our review, the staff requests the following additional information.
The Nuclear Regulatory Commission (NRC) staff has reviewed the submitted information and determined that the additional information identified in the enclosure is needed to complete its review.
On January 30, you confirmed a response date of February 22, 2013.
Thank you, Lauren Lauren K. Gibson Project Manager Columbia Generating Station Palo Verde Nuclear Generating Station Division of Operatillg Reactor Licensing U.S. Nuclear Regulatory Commission (301) 415-1056 1
REQUEST FOR ADDITIONAL INFORMATION REACTOR VESSEL HEAD FLANGE SEAL LEAK DETECTION PIPING - RELIEF REQUEST NO. 49 ARIZONA PUBLIC SERVICE COMPANY PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 DOCKET NOS. SO-S28, SO-S29, AND SO-S30 By letter dated December 19, 2012 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 12361A2S6), Arizona Public Service Company (APS, the licensee) submitted "Reactor Pressure Vessel Head Flange Seal Leak Detection Piping - Relief Request No. 49" for U. S. Nuclear Regulatory Commission (NRC) review and authorization. The licensee has proposed an alternative to the system leakage test of reactor pressure vessel (RPV) flange leak-off line that is required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, Table IWC-2S00-1, Examination Category C-H, at Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3.
Specifically, instead of pressurizing the subject lines to the system leakage test pressure required by IWC-S221, the licensee proposes to pressurize the line using the static pressure head of the refueling water prior to performing a VT-2 visual examination. In order to complete our review, the staff requests the following additional information.
- 1. What are the scheduled end dates for the PVNGS, Unit 1,2, and 3 third 10-year inservice inspection interval?
- 2. The proposed alternative is being submitted pursuant to Title 10 of the Code of Federal Regulations, Part SO (10 CFR SO), paragraph SSa(g)(S)(ii), revised inservice inspection program for a facility conflicts with the technical specification for the facility, but cites the provisions of 10 CFR SO.SSa(a)(3)(ii), hardship without a compensating increase in the level of quality and safety. Please confirm that the relief request is being submitted pursuant to 10 CFR SO.SSa(a)(3)(ii).
- 3. Provide a brief description of the operation of the RPV flange seal leak detection system, i.e., how the pressure in the leak-off line is measured and monitored, how the operators are alerted to a leakage condition and how they respond.
- a. If O-ring leakage trips the leak-off alarm and rapid depressurization of the leak-off line subsequently occurs, does the control room annunciator continue to show an indication?
- b. Are there other control room indications of O-ring leakage?
- 4. Provide a piping and instrumentation diagram (P&ID) and a piping isometric drawing showing the RPV flange seal leak detection piping.
S. What is the material of construction of the leak-off line?
ENCLOSURE
- 2
- 6. Describe PVNGS experience with degradation (corrosion, stress corrosion cracking, fatigue, etc.) of the RPV flange seal leak detection piping.
- 7. Potential O-ring leakage during service is detected with a pressure element in the leak off line. The proposed alternative would utilize the static fluid head of the refueling water to pressurize the leak-off line prior to a VT-2 examination.
- a. What is the fluid head pressure that exists in the line when the refueling cavity has been filled to its normal refueling water level?
- b. What is the trip pressure for the O-ring leakage alarm indication in the control room?
- 8. Discuss whether a system leakage test of the RPV flange seal leak detection piping could be performed at a pressure higher than that of the refueling water fluid head prior to removing the head at the beginning of the refueling outage. Describe any hardship associated with this sequence.
- 9. In order for a fluid leak in a pressurized line to be observed with a VT-2 examination, sufficient time must have elapsed between the time that the line was pressurized and the time that the examination is performed. Specify the minimum time between the time that the line is pressurized and the time that the VT-2 examination is performed for both uninsulated lines and insulated lines (as appropriate). Provide a technical justification based on the pressure in the leak-off line during the leakage test for the hold time.
