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| | number = ML12221A367 | | | number = ML12221A367 |
| | issue date = 08/08/2012 | | | issue date = 08/08/2012 |
| | title = Diablo Canyon Power Plant, Units 1 and 2 - Request for Additional Information Email, Request for Alternative No. RI-ISI-INT3 to ASME Code Requirements for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval (TAC ME7854 a | | | title = Request for Additional Information Email, Request for Alternative No. RI-ISI-INT3 to ASME Code Requirements for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval |
| | author name = Sebrosky J M | | | author name = Sebrosky J |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Soenen P R | | | addressee name = Soenen P |
| | addressee affiliation = Pacific Gas & Electric Co | | | addressee affiliation = Pacific Gas & Electric Co |
| | docket = 05000275, 05000323 | | | docket = 05000275, 05000323 |
| | license number = DPR-080, DPR-082 | | | license number = DPR-080, DPR-082 |
| | contact person = Sebrosky J M | | | contact person = Sebrosky J |
| | case reference number = TAC ME7854, TAC ME7855 | | | case reference number = TAC ME7854, TAC ME7855 |
| | document type = E-Mail | | | document type = E-Mail |
| | page count = 2 | | | page count = 2 |
| | project = TAC:ME7854, TAC:ME7855 | | | project = TAC:ME7854, TAC:ME7855 |
| | | stage = RAI |
| }} | | }} |
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| {{#Wiki_filter:From:Sebrosky, JosephTo:Soenen, Philippe RCc:"Baldwin, Thomas (DCPP)"; Hoffman, Keith; Patel, Jigar; Burkhardt, Janet; Chen, Qiao-LynnSubject:Request for Additional Information associated with relief request for risk-informed inservice inspection (ME7854,ME7855)Date:Wednesday, August 08, 2012 2:53:46 PMPhilippe, | | {{#Wiki_filter:From: Sebrosky, Joseph To: Soenen, Philippe R Cc: "Baldwin, Thomas (DCPP)"; Hoffman, Keith; Patel, Jigar; Burkhardt, Janet; Chen, Qiao-Lynn |
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| By letter dated January 20, 2012, (Agencywide Documents Access and ManagementSystem (ADAMS) Accession No. ML12025A084) Pacific Gas and Electric (PG&E)submitted for staff review and approval Relief Request RI-ISI-INT3-U1&2, which requestsauthorization to continue implementing a risk-informed inservice inspection (RI-ISI)program based on Electric Power Research Institute TR-112657 for American Society ofMechanical Engineers (ASME) Class 1 and 2 piping welds for the third 10-year inspectioninterval at the Diablo Canyon Power Plant Units 1 & 2 (DCPP). | | ==Subject:== |
| Based on a review of the submittal, the NRC staff has determined that the followingadditional information (RAI) is required in order to complete its review. The request foradditional information was discussed with Mr. Soenen on August 8, 2012. It was agreedthat a response to these RAIs would be provided by September 7, 2012. Should the NRCdetermine that this RAI is no longer necessary prior to the scheduled date, the request willbe withdrawn. If circumstances result in the need to revise the requested response date,please contact me at (301) 415-1132 or via e-mail at joseph.sebrosky@nrc.gov. The NRCstaff has determined that no security-related or proprietary information is contained herein.Sincerely, | | Request for Additional Information associated with relief request for risk-informed inservice inspection (ME7854, ME7855) |
| | Date: Wednesday, August 08, 2012 2:53:46 PM |
| | : Philippe, By letter dated January 20, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12025A084) Pacific Gas and Electric (PG&E) submitted for staff review and approval Relief Request RI-ISI-INT3-U1&2, which requests authorization to continue implementing a risk-informed inservice inspection (RI-ISI) program based on Electric Power Research Institute TR-112657 for American Society of Mechanical Engineers (ASME) Class 1 and 2 piping welds for the third 10-year inspection interval at the Diablo Canyon Power Plant Units 1 & 2 (DCPP). |
| | Based on a review of the submittal, the NRC staff has determined that the following additional information (RAI) is required in order to complete its review. The request for additional information was discussed with Mr. Soenen on August 8, 2012. It was agreed that a response to these RAIs would be provided by September 7, 2012. Should the NRC determine that this RAI is no longer necessary prior to the scheduled date, the request will be withdrawn. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1132 or via e-mail at joseph.sebrosky@nrc.gov. The NRC staff has determined that no security-related or proprietary information is contained herein. |
| | Sincerely, Joe Sebrosky REQUEST FOR ADDITIONAL INFORMATION Note: Questions 1 through 6 are from the piping and non-destructive examination branch, and question 7 is from the probabilistic risk assessment licensing branch |
| | : 1. The NRC issued rulemaking on June 21, 2011 which requires licensees to follow an augmented inservice inspection program in accordance with ASME Code Case N-770-1, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities, and limitations listed in Title 10 of Code of Federal Regulations 50.55a(g)(6)(ii)(F). In addition, the NRC held a public meeting to discuss the June rulemaking and the implementation of Code Case N-770-1 on July 12, 2011. |
| | Agencywide Document Access and Management System (ADAMS) accession number # ML112240818 documents the NRC summary of that meeting. The NRC staffs concern is that, the welds required to be examined in accordance with the augmented program required by 50.55a(g)(6)(ii)(F) should not be counted as exams selected to satisfy the RI-ISI program. Please describe how DCPP will address the requirements of the June 2011 rulemaking and ASME Code Case N-770-1 in implementing Relief Request RI-ISI-INT3-U1&2. |
| | : 2. Please describe how the proposed RI-ISI program will satisfy the requirements of |
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| Joe Sebrosky REQUEST FOR ADDITIONAL INFORMATION Note: Questions 1 through 6 are from the piping and non-destructive examination branch,and question 7 is from the probabilistic risk assessment licensing branch 1. The NRC issued rulemaking on June 21, 2011 which requires licensees to follow anaugmented inservice inspection program in accordance with ASME Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNSW86182 Weld Filler Material With or Without Application of Listed MitigationActivities," and limitations listed in Title 10 of Code of Federal Regulations50.55a(g)(6)(ii)(F). In addition, the NRC held a public meeting to discuss the Junerulemaking and the implementation of Code Case N-770-1 on July 12, 2011. Agencywide Document Access and Management System (ADAMS) accessionnumber # ML112240818 documents the NRC summary of that meeting. The NRCstaff's concern is that, the welds required to be examined in accordance with theaugmented program required by 50.55a(g)(6)(ii)(F) should not be counted asexams selected to satisfy the RI-ISI program. Please describe how DCPP willaddress the requirements of the June 2011 rulemaking and ASME Code Case N-770-1 in implementing Relief Request RI-ISI-INT3-U1&2. 2. Please describe how the proposed RI-ISI program will satisfy the requirements of IWB-2412 and IWC-2412 for percentage of examinations completed. 3. IWB-2420(a) and IWC-2420(a), "Successive Examinations" require that "thesequence of component examinations which was established during the firstinspection interval shall be repeated during each successive inspection interval, tothe extent practical." This requirement is to ensure components are examined on aonce per 10-year frequency to the extent practical. Please discuss how theproposed RI-ISI program satisfies this requirement. 4. The original RI-ISI program required 10% of the ASME Class 1 piping non-socketwelds, is this requirement retained by the 3rd interval RI-ISI program? TheAttachment 1-1 and Attachment 1-2 tables do not identify any ASME Section XIItem Numbers making it impossible for the NRC staff to determine if thisrequirement was retained. 5. The original RI-ISI program stated that RI-ISI examination locations were selectedsuch that >90% coverage is attainable. Was this requirement retained in theexamination locations selected for the proposed program? 6. As a living program the original RI-ISI program required a review of the program onan ASME period basis. Is this requirement retained in the proposed RI-ISIprogram? 7. Risk informed applications must address external events as specified in RegulatoryGuide 1.200 Revision 2. Please provide an assessment for how external events,including seismic events, at Diablo Canyon Power Plant affect the results of the riskimpact analysis for the third ten-year interval inservice inspection program plan.
| | IWB-2412 and IWC-2412 for percentage of examinations completed. |
| }} | | : 3. IWB-2420(a) and IWC-2420(a), Successive Examinations require that the sequence of component examinations which was established during the first inspection interval shall be repeated during each successive inspection interval, to the extent practical. This requirement is to ensure components are examined on a once per 10-year frequency to the extent practical. Please discuss how the proposed RI-ISI program satisfies this requirement. |
| | : 4. The original RI-ISI program required 10% of the ASME Class 1 piping non-socket welds, is this requirement retained by the 3 rd interval RI-ISI program? The Attachment 1-1 and Attachment 1-2 tables do not identify any ASME Section XI Item Numbers making it impossible for the NRC staff to determine if this requirement was retained. |
| | : 5. The original RI-ISI program stated that RI-ISI examination locations were selected such that >90% coverage is attainable. Was this requirement retained in the examination locations selected for the proposed program? |
| | : 6. As a living program the original RI-ISI program required a review of the program on an ASME period basis. Is this requirement retained in the proposed RI-ISI program? |
| | : 7. Risk informed applications must address external events as specified in Regulatory Guide 1.200 Revision 2. Please provide an assessment for how external events, including seismic events, at Diablo Canyon Power Plant affect the results of the risk impact analysis for the third ten-year interval inservice inspection program plan.}} |
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Category:E-Mail
MONTHYEARML24250A0542024-09-0606 September 2024 LRA - Requests for Additional Information - Set 1 - Email from Brian Harris to Adam Peck ML24250A0502024-09-0606 September 2024 NRR E-mail Capture - Acceptance Review Diablo Canyon Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML24235A2032024-08-22022 August 2024 OEDO-24-00083 - 10 CFR 2.206 - Diablo Canyon Units 1 and 2 Seismic - Final Determination e-mail - EPID L-2024-CRS-0000 ML24205A0622024-07-23023 July 2024 NRR E-mail Capture - Acceptance Review - Diablo Canyon Request for Approval to Extend the Alternative for Use of Full Structural Weld Overlay ML24187A1382024-07-0202 July 2024 License Renewal Environmental Review: Summary of June 27 Clarification Call Regarding Pg&Es Response to RCI AQN-3 ML24184C0422024-07-0202 July 2024 NRR E-mail Capture - Request for Additional Information Diablo Canyon 50.69 risk-informed Categorization ML24149A0832024-05-28028 May 2024 Acceptance Review: Diablo Canyon Request for Alternative Security Measures and Exemption for the Early Warning System ML24145A0612024-05-22022 May 2024 Written Limited Appearance Statement of Doris Nassiry ML24136A1622024-05-15015 May 2024 OEDO-24-00083 (E-Mail) 10 CFR 2.206 - Diablo Canyon Power Plant, Unit Nos. 1 and 2 Seismic - Initial Assessment ML24134A1902024-05-10010 May 2024 Written Limited Appearance Statement of Shelley Hamilton ML24134A1872024-05-10010 May 2024 Written Limited Appearance Statement of Charlene M. Woodcock ML24122C6702024-04-29029 April 2024 Request from NRC Review of a Draft EA for an Exemption for the Limerick Generating Station ML24095A3172024-04-0404 April 2024 NRR E-mail Capture - Acceptance Review Diablo Canyon Request to Revise Technical Specification 5.6.6 for Pressure and Temperature Limits Report ML24088A2382024-03-28028 March 2024 10 CFR 2.206 - Diablo Canyon Units 1 and 2 OEDO-24-00083 - Screen-in e-mail L-2024-CRS-0000 ML24058A1032024-03-0808 March 2024 OEDO-23-00350-NRR - Initial Assessment - 10 CFR 2.206 Petition from Mothers for Peace and Friends of the Earth Regarding Diablo Canyon ML24071A1762024-03-0707 March 2024 Email - (External Sender) NRC Proceeding on Diablo Canyon 50-275 and 50-323 LR-2 ML24067A0892024-03-0505 March 2024 Email Response from Diane Curran to Office of the Secretary, Assistant for Rulemaking and Adjudications, Russell Chazell ML24067A0902024-03-0505 March 2024 Email to Diane Curran from the Office of the Secretary, Assistant for Rulemaking and Adjudications, Russell Chazell ML24067A0882024-03-0404 March 2024 Email Hearing Request from San Luis Obispo Mothers for Peace, Friends of the Earth, and Environmental Working Group ML24060A0022024-02-28028 February 2024 (External Sender) Pre-Sub Mittal EWS Participants List E-mail ML24045A1972024-02-0606 February 2024 Tribal Consultation Request ML24033A3062024-02-0101 February 2024 Dcisc 2-1-2024 Email: Comments by Mr. Bruce Severance at This Mornings Public Meeting Re Scope of Review for DCPP License Extension ML23334A0912023-11-30030 November 2023 NRR E-mail Capture - Diablo Canyon 1 and 2 - Audit Questions for License Amendment Associated with TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23335A1012023-11-0606 November 2023 OEDO-23-00350-NRR - Screen-in Email - 10 CFR 2.206 Petition from Mothers for Peace and Change.Org Regarding Diablo Canyon ML23306A0422023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Diablo Canyon Request to Adopt 10 CFR 50.69, risk-informed Categorization and Treatment of SSCs ML23230A0702023-08-18018 August 2023 NRR E-mail Capture - Acceptance Review - Diablo Canyon Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b ML23165A2702023-06-14014 June 2023 NRR E-mail Capture - Acceptance Review - Diablo Canyon Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule ML23157A2392023-06-0505 June 2023 Limited Appearance Statement from Nina Babiarz in the Matter of the Diablo Canyon ISFSI License Renewal Application ML23096A1792023-04-0606 April 2023 NRR E-mail Capture - Request for Additional Information Diablo Canyon Exemption Request Regarding Senior Reactor Operator License Application ML23094A1032023-04-0404 April 2023 NRR E-mail Capture - Acceptance Review - Diablo Canyon Exemption Request Regarding Senior Reactor Operator License Application ML23076A0932023-03-16016 March 2023 16-2023 Email - Estimate of Spent Nuclear Fuel in Tons ML23067A0202023-03-0808 March 2023 NRR E-mail Capture - Diablo Canyon Nuclear Power Plant Evacuation Time Estimate Analysis Review ML23046A1042023-02-13013 February 2023 Transmittal Email, Diane Curran to Gibson, 2/13/23, Filing of Formal Opposition to PG&E Exemption Request ML23046A1132023-02-13013 February 2023 Transmittal Email, Paul Bessette to Gibson, 2/13/23, Filing of Formal Opposition to PG&E Exemption Request ML23052A2042023-01-10010 January 2023 E-mail from Paul Bessette Dated 01/10/2023 Regarding Diablo Canyon ML22326A1632022-11-21021 November 2022 Licensee Comment Email on Post-Shutdown Emergency Plan Amendment ML22266A0012022-09-22022 September 2022 (External Sender) E-Mail Diablo Canyon Power Plant, Unit Nos. 1 and 2 - Total Amount of Spent Nuclear Fuel Stored in Tons ML22241A1142022-08-29029 August 2022 NRR E-mail Capture - Acceptance Review - Diablo Canyon Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML22194A8872022-07-11011 July 2022 September 2022 Emergency Preparedness Exercise Inspection - Request for Information Email ML22187A2652022-07-0606 July 2022 NRR E-mail Capture - Request for Additional Information: Diablo Canyon Exemption Request for Part 73 force-on-force Training Due to COVID-19 ML22105A0702022-04-15015 April 2022 NRR E-mail Capture - Acceptance Review - Diablo Canyon Request to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections ML22090A0832022-03-31031 March 2022 NRR E-mail Capture - Acceptance Review - Diablo Canyon Request for Approval of a Certified Fuel Handler Training and Retraining Program ML22089A1672022-03-29029 March 2022 Email - Acknowledgement of NRC Receipt of Diablo Canyon ISFSI Renewal Application ML22087A0412022-03-25025 March 2022 NRR E-mail Capture - Acceptance Review - Diablo Canyon Request for Approval of Alternative Security Measures for Early Warning System ML22061A2192022-03-0202 March 2022 NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Changes to Emergency Plan for post-shutdown and Permanently Defueled Condition ML21323A0652021-11-19019 November 2021 NRR E-mail Capture - Acceptance Review - Diablo Canyon Revision of Emergency Plan for post-shutdown Condition ML21264A6722021-09-21021 September 2021 NRR E-mail Capture - Revised Schedule: Diablo Canyon Request to Revise Technical Specification to Reflect the Permanent Cessation of Reactor Operation ML21215A3432021-08-0303 August 2021 NRR E-mail Capture - Request for Additional Information - Diablo Canyon Request to Revise Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance ML21188A0382021-07-0707 July 2021 (External_Sender) DCPP Draft Emergency LAR - Asw ML21189A0662021-07-0707 July 2021 NRR E-mail Capture - Additional Draft Request for Additional Information - Diablo Canyon Emergency Amendment Request to Revise Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System 2024-09-06
[Table view] |
Text
From: Sebrosky, Joseph To: Soenen, Philippe R Cc: "Baldwin, Thomas (DCPP)"; Hoffman, Keith; Patel, Jigar; Burkhardt, Janet; Chen, Qiao-Lynn
Subject:
Request for Additional Information associated with relief request for risk-informed inservice inspection (ME7854, ME7855)
Date: Wednesday, August 08, 2012 2:53:46 PM
- Philippe, By letter dated January 20, 2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12025A084) Pacific Gas and Electric (PG&E) submitted for staff review and approval Relief Request RI-ISI-INT3-U1&2, which requests authorization to continue implementing a risk-informed inservice inspection (RI-ISI) program based on Electric Power Research Institute TR-112657 for American Society of Mechanical Engineers (ASME) Class 1 and 2 piping welds for the third 10-year inspection interval at the Diablo Canyon Power Plant Units 1 & 2 (DCPP).
Based on a review of the submittal, the NRC staff has determined that the following additional information (RAI) is required in order to complete its review. The request for additional information was discussed with Mr. Soenen on August 8, 2012. It was agreed that a response to these RAIs would be provided by September 7, 2012. Should the NRC determine that this RAI is no longer necessary prior to the scheduled date, the request will be withdrawn. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1132 or via e-mail at joseph.sebrosky@nrc.gov. The NRC staff has determined that no security-related or proprietary information is contained herein.
Sincerely, Joe Sebrosky REQUEST FOR ADDITIONAL INFORMATION Note: Questions 1 through 6 are from the piping and non-destructive examination branch, and question 7 is from the probabilistic risk assessment licensing branch
- 1. The NRC issued rulemaking on June 21, 2011 which requires licensees to follow an augmented inservice inspection program in accordance with ASME Code Case N-770-1, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities, and limitations listed in Title 10 of Code of Federal Regulations 50.55a(g)(6)(ii)(F). In addition, the NRC held a public meeting to discuss the June rulemaking and the implementation of Code Case N-770-1 on July 12, 2011.
Agencywide Document Access and Management System (ADAMS) accession number # ML112240818 documents the NRC summary of that meeting. The NRC staffs concern is that, the welds required to be examined in accordance with the augmented program required by 50.55a(g)(6)(ii)(F) should not be counted as exams selected to satisfy the RI-ISI program. Please describe how DCPP will address the requirements of the June 2011 rulemaking and ASME Code Case N-770-1 in implementing Relief Request RI-ISI-INT3-U1&2.
- 2. Please describe how the proposed RI-ISI program will satisfy the requirements of
IWB-2412 and IWC-2412 for percentage of examinations completed.
- 3. IWB-2420(a) and IWC-2420(a), Successive Examinations require that the sequence of component examinations which was established during the first inspection interval shall be repeated during each successive inspection interval, to the extent practical. This requirement is to ensure components are examined on a once per 10-year frequency to the extent practical. Please discuss how the proposed RI-ISI program satisfies this requirement.
- 4. The original RI-ISI program required 10% of the ASME Class 1 piping non-socket welds, is this requirement retained by the 3 rd interval RI-ISI program? The Attachment 1-1 and Attachment 1-2 tables do not identify any ASME Section XI Item Numbers making it impossible for the NRC staff to determine if this requirement was retained.
- 5. The original RI-ISI program stated that RI-ISI examination locations were selected such that >90% coverage is attainable. Was this requirement retained in the examination locations selected for the proposed program?
- 6. As a living program the original RI-ISI program required a review of the program on an ASME period basis. Is this requirement retained in the proposed RI-ISI program?
- 7. Risk informed applications must address external events as specified in Regulatory Guide 1.200 Revision 2. Please provide an assessment for how external events, including seismic events, at Diablo Canyon Power Plant affect the results of the risk impact analysis for the third ten-year interval inservice inspection program plan.