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MONTHYEARML15103A2882015-04-0909 April 2015 Presentation on Potential Relief Request About Pressure Boundary Leakage on Reactor Coolant Pump 2A Pipe Nozzle Project stage: Request ML15104A8102015-04-14014 April 2015 NRR E-mail Capture - Palo Verde, Unit 3 - Request for Information Regarding Pressure Boundary Leakage in RCP 2A Pressure Instrumentation Nozzle (MF6083) Project stage: RAI ML15110A4792015-04-15015 April 2015 NRR E-mail Capture - Palo Verde, Unit 3 - Information Regarding Pressure Boundary Leakage in Reactor Coolant Pump 2A Pressure Instrumentation Nozzle for April 15, 2015 Phone Call (MF6083) Project stage: Other ML15113A6362015-04-22022 April 2015 Acceptance of Relief Request 53 Project stage: Acceptance Review ML15113A4972015-04-23023 April 2015 Request for Additional Information Regarding Relief Request 53 Project stage: RAI 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 Project stage: Other ML15198A2422015-07-15015 July 2015 Transmittal of Updated Proprietary Documents for Relief Request 53 Project stage: Request ML15198A2242015-07-15015 July 2015 Transmittal of Non-Proprietary Documents for Relief Request 53 Project stage: Request ML15198A2262015-07-15015 July 2015 Attachment 3: Calculation CN-PAFM-15-20-NP, Rev. 2, Palo Verde Unit 3 RCS Cold Leg Alloy 600 Small Bore Nozzle Repair Transient Stress and Fracture Mechanics Evaluation for One Cycle Operation. Project stage: Request ML15198A2272015-07-15015 July 2015 Attachment 4: Calculation TR-FSE-15-2-NP, Rev. 1, Palo Verde Nuclear Generating Station Unit 3 Evaluation of Potential Loose Part - Reactor Coolant Pump Instrument Nozzle Weld Fragment. Project stage: Request ML15198A2252015-07-15015 July 2015 Attachment 2: Calculation CN-MRCDA-15-13-NP, Qualification of Palo Verde Unit 3 Reactor Coolant Pump Replacement Instrumentation Nozzle. Project stage: Request ML15209A6662015-08-10010 August 2015 Request for Withholding Information from Public Disclosure - 7/10/15 Affidavit Executed by J. Gresham, Westinghouse, Re Five Proprietary Documents in Support of Relief Request 53 - Approval of an Alternative to Flaw Removal (TAC No Project stage: Withholding Request Acceptance ML15238B6612015-09-15015 September 2015 Relief Request 53, Alternative to ASME Code Section XI Requirements Related to Flaw Removal Project stage: Other 2015-04-29
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Category:Request for Additional Information (RAI)
MONTHYEARML24297A6212024-10-22022 October 2024 Request for Additional Information Relief Request (RR) No. 72: Re-Submittal of RR-39/ASME Code X1 IWC-3420, IWA-3300 ML24257A1012024-09-11011 September 2024 Request for Additional Information License Renewal Commitment for AMP of Alloy 600 Components ML24143A1112024-05-20020 May 2024 Draft 2nd Round Request for RAIs Concerning LAR to Modify LCO for TS 3.5.2, LCO for TS 3.6.5, and Surveillance Requirements 3.5.1.2 and 3.5.2.2 for TS 3.5.1 and TS 3.5.2 ML24123A2002024-05-0101 May 2024 (E-Mail) Draft 2nd Round Request for Additional Information Concerning License Amendment Request to Modify Limiting Condition for Operation (LCO) for Technical Specification (TS) 3.5.2, LCO for TS 3.6.5, 3.5.1.2 and 3.5.2.2 for TS 3.5.1, a ML24114A2812024-04-19019 April 2024 Request for Additional Information (RAI-10150-R1) ML24011A1002024-01-10010 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) 2024-09-11
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REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 53 ALTERNATE REPAIR OF PRESSURE INSTRUMENTATION NOZZLE AT REACTOR COOLANT PUMP 2A PALO VERDE NUCLEAR GENERATING STATION, UNIT 3 (TAC NO. MF6083) ARIZONA PUBLIC SERVICE COMPANY DOCKET NUMBER 50-530 By letter dated April 17, 2015, Arizona Public Service Company (APS or the licensee) submitted Relief Request 53 regarding the repair of the differential pressure instrumentation nozzle on the suction side of the 2A reactor coolant pump at Palo Verde Nuclear Generating Station, Unit 3. To complete its review, the NRC staff requests the additional information (RAI) as follows: Letter dated April 17, 2015, American Society of Mechanical Engineers (ASME) Code,Section XI, Request for Approval of an Alternative to Flaw Removal - Relief Request 53, Non-Proprietary (Publically available) 1. Section 1of the relief request identifies the pressure instrument nozzle being classified as Examination Category B-P (Class 1 PWR Components Containing Alloy 600/82/182) and Code Item Number B15.205. However, in the ASME Code,Section XI, Table IWB-2500-1, Code Item number B15.205 does not belong to or match Examination Category B-P. Also, Class 1 pressure retaining dissimilar metal welds in vessel nozzles should be classified as Examination Category B-F, not B-P. Item Number B15.205 does appear in Table 1 of Code Case N-722-1, but not in the ASME Code. Clarify the exact Examination Category and Item Number of the pressure instrument nozzle and provide the reference. 2. The design of the half nozzle repair includes a gap of 0.06 inch between the remnant nozzle and the new nozzle. Discuss the calculations that were made to ensure that the 0.06 inch gap is sufficient for the thermal expansion of the remnant nozzle and new nozzle. If no calculations were performed, provide a justification. 3. Provide a piping isometric showing the locations and distances of pipe hangers and restraints along the pressure instrument line from the instrument nozzle attached to the reactor coolant pump to the first anchor. Attachment 3 APS Response to NRC Request for Additional Information (RAI), dated April 14, 2015 4. The licensee's response to NRC's RAI Question No. 3(c) did not address the frequency of the boric acid walkdown for the subject repaired instrument nozzle for the future inservice inspections. a. Discuss how often the repaired instrument nozzle will be examined in future inservice inspections.
b. After the repair, discuss under which Examination Category and Examination Item will the new J-groove weld be classified in accordance with the ASME Code,Section XI, Table IWB-2500-1. 5. In the PCI Quality Assurance Traveler on Page 12 of 18, Sequence Number 9.1.22 states that APS to perform liquid penetrant examination of all machined surfaces of the replacement nozzle. Sequence Number 9.1.25 instructs APS to perform liquid penetrant examination of weld preparation area on the casing of the reactor coolant pump. After a portion of the original nozzle is removed from the bore of the safe end, clarify whether the inside diameter surface of the bore will be examined by liquid penetrant testing prior to inserting the new Alloy 690 nozzle. If not, discuss how to ensure the bore contains no scratches or flaws. Letter dated April 17, 2015, Transmittal of Proprietary Documents for Relief Request 53, Proprietary Attachments (Non-public) Attachment 1 Westinghouse Document DAR-MRCDA-15-6-P, Rev. 1, Palo Verde Unit 3 RCS [Reactor Coolant System] Cold Leg Alloy 600 Small Bore Nozzle Repair 6. Page 8 states that the fatigue usage factor for the cold leg piping is W. Discuss whether a usage factor of W is calculated for the end of one cycle of operation or for 40 years of operation. Attachment 2 Westinghouse Calculation CN-MRCDA-15-13, Rev. 0, Qualification of Palo Verde Unit 3 Reactor Coolant Pump Replacement Instrumentation Nozzle 7. The licensee uses the stress analysis that Westinghouse performed for Plant X to apply to Palo Verde, Unit 3. Figure 4--groove weld at Palo Verde and the analyzed J-groove weld at Plant X. The J-groove weld at Plant X is located inside surface of the pipe whereas the new J-groove weld at Palo Verde is located at the outside surface of the safe end. The licensee stated that the impact of thermal and pressure transient loads will be less significant than those on the Plant X attachment weld. Discuss the impact of the different weld locations on all analyses and calculations involved in the repaired instrument nozzle at Palo Verde. 8. Clarify which results of Plant X analysis are applicable to the subject instrument nozzle and which results of Plant X analysis are not applicable. Clarify which analysis is performed using the plant-specific parameters from Palo Verde. 9. On Page 18, Table 4-2, shows that Fx and Fz have zero load for the normal condition, whereas for the faulted condition, Fx and Fz have 19 pounds (lbs) each. a. Confirm that the 19 lbs for the faulted condition is bounding for all faulted conditions including seismic loading. b. Clarify why Fx and Fz have zero load for the normal condition.
c. Discuss why the nozzle mechanical loads are so low considering that five mechanical loads are applied to the nozzle, as discussed on Page 13 and 14. 10. On Page 24, Table 5-6Attachment Weld Input Loads presents an axial load of 0.8 pound force on the new weld for the normal condition. Explain why the axial load is so low. Attachment 3 Westinghouse Calculation CN-PAFM-15-20, Rev. 2, Palo Verde Unit 3 RCS Cold Leg Alloy 600 Small Bore Nozzle Repair Transient Stress and Fracture Mechanics Evaluation for One Cycle Operation 11. Page 10 states that the corrosion allowance for the bore of the subject nozzle should be larger than the corrosion allowance (X inches) for the hot leg nozzles. a. Clarify why the cold leg corrosion allowance for the bore is larger than the corrosion allowance for the hot leg nozzles. b. It appears that the corrosion allowance is rather large such that the bore may not provide any friction to resist the nozzle ejection load. Discuss whether the new J-groove weld can support the entire nozzle ejection load without the support of the friction from the ID surface of the bore. 12. Page 15 states that the allowable flaw size evaluation performed for a hot leg nozzle repair would be conservatively representative for the Palo Verde Unit 3 RCP suction safe end instrumentation nozzle. Provide the allowable flaw size associated with the RCP suction safe end.