|
|---|
Category:Letter type:DCL
MONTHYEARDCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024
Nuclear Material Transaction Report for New Fuel
DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024
Nuclear Material Transaction Report for New Fuel
DCL-24-008, Schedule Considerations for Review of the DCPP License Renewal Application2024-01-17017 January 2024
Schedule Considerations for Review of the DCPP License Renewal Application
DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-01-15015 January 2024
Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023
Nuclear Material Transaction Report for New Fuel
DCL-23-122, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-14014 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
DCL-23-128, Emergency Plan Update2023-12-13013 December 2023
Emergency Plan Update
DCL-23-125, Core Operating Limits Report for Unit 1 Cycle 252023-12-0606 December 2023
Core Operating Limits Report for Unit 1 Cycle 25
DCL-23-121, Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System2023-11-16016 November 2023
Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System
DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023
License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System
DCL-23-118, License Renewal Application2023-11-0707 November 2023
License Renewal Application
DCL-2023-520, Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)2023-10-19019 October 2023
Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)
DCL-23-103, Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System2023-10-13013 October 2023
Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System
DCL-23-092, Material Status Report for the Period Ending August 31, 20232023-09-28028 September 2023
Material Status Report for the Period Ending August 31, 2023
DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-27027 September 2023
License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
DCL-23-083, Upcoming Meeting with Nuclear Security and Incident Response Staff2023-09-13013 September 2023
Upcoming Meeting with Nuclear Security and Incident Response Staff
DCL-23-078, Nuclear Material Transaction Report for New Fuel2023-09-0606 September 2023
Nuclear Material Transaction Report for New Fuel
DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application2023-08-16016 August 2023
Withdrawal of Request Regarding Senior Reactor Operator License Application
DCL-23-068, Nuclear Material Transaction Report for New Fuel2023-08-0909 August 2023
Nuclear Material Transaction Report for New Fuel
DCL-23-066, Nuclear Material Transaction Report for New Fuel2023-08-0303 August 2023
Nuclear Material Transaction Report for New Fuel
DCL-23-065, Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure2023-07-27027 July 2023
Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure
DCL-23-064, Nuclear Material Transaction Report for New Fuel2023-07-26026 July 2023
Nuclear Material Transaction Report for New Fuel
DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-07-13013 July 2023
License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
DCL-23-055, Nuclear Material Transaction Report for New Fuel2023-07-0606 July 2023
Nuclear Material Transaction Report for New Fuel
DCL-23-042, Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 02023-05-24024 May 2023
Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 0
DCL-23-032, Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program2023-05-22022 May 2023
Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program
DCL-23-041, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20222023-05-22022 May 2023
10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2022
DCL-23-038, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule2023-05-15015 May 2023
Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule
DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023
2022 Annual Nonradiological Environmental Operating Report
DCL-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023
2022 Annual Radiological Environmental Operating Report
DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023
2022 Annual Radioactive Effluent Release Report
DCL-2023-512, Submittal of Receiving Water Monitoring Program 2022 Annual Report2023-04-27027 April 2023
Submittal of Receiving Water Monitoring Program 2022 Annual Report
DCL-23-035, Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application2023-04-24024 April 2023
Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application
DCL-23-028, Technical Specification Bases, Revision 142023-04-24024 April 2023
Technical Specification Bases, Revision 14
DCL-2023-511, Report on Discharge Monitoring for the First Quarter of 20232023-04-20020 April 2023
Report on Discharge Monitoring for the First Quarter of 2023
DCL-23-031, Submittal of Annual Report of Occupational Radiation Exposure for 20222023-04-19019 April 2023
Submittal of Annual Report of Occupational Radiation Exposure for 2022
DCL-23-024, Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System2023-04-0404 April 2023
Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System
DCL-23-022, 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant2023-03-29029 March 2023
2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant
DCL-23-023, Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 22023-03-28028 March 2023
Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 2
DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update2023-03-23023 March 2023
Independent Spent Fuel Storage Installation, Emergency Plan Update
DCL-23-020, Responses to NRC Questions Regarding License Renewal Efforts2023-03-17017 March 2023
Responses to NRC Questions Regarding License Renewal Efforts
DCL-23-009, Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage2023-02-22022 February 2023
Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage
DCL-23-008, Request Regarding Senior Reactor Operator License Application2023-02-22022 February 2023
Request Regarding Senior Reactor Operator License Application
DCL-2023-503, Annual Sea Turtle Report2023-01-26026 January 2023
Annual Sea Turtle Report
DCL-2023-502, (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring2023-01-18018 January 2023
(DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring
DCL-22-091, Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage2022-12-20020 December 2022
Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage
DCL-22-089, Core Operating Limits Report for Unit 2 Cycle 242022-12-20020 December 2022
Core Operating Limits Report for Unit 2 Cycle 24
DCL-22-085, Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application2022-10-31031 October 2022
Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application
DCL-22-041, Site-Specific Decommissioning Cost Estimate, Revision 12022-10-12012 October 2022
Site-Specific Decommissioning Cost Estimate, Revision 1
DCL-22-042, Post-Shutdown Decommissioning Activities Report, Revision 12022-10-12012 October 2022
Post-Shutdown Decommissioning Activities Report, Revision 1
2024-01-29
[Table view] |
Text
Pacific Gas and Electric Company Barry S. Allen Diablo Canyon Power Plan t Site Vice President Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.4888 April 29, 2013 Internal: 691 .4888 Fax : 805.545.6445 PG&E Letter DCL-13-044 U.S. Nuclear Regulatory Commission 10 CFR 50.54(f)
ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
References:
- 1. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," dated March 12, 2012
- 2. Federal Register, Vol. 78, No. 38, Tuesday, February 26, 2013, pp.13097-13099
- 3. NEI letter to NRC, "Proposed Path Forward for NTTF Recommendation 2.1 :
Seismic Reevaluations," dated April 9, 2013
- 4. NRC letter, Endorsement of Electric Power Research Institute Final Draft Report 1025287, "Seismic Evaluation Guidance," dated February 15, 2012
- 5. Electric Power Research Institute (EPRI) Report No.1 025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," dated November 2012.
Dear Commissioners and Staff:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to Pacific Gas and Electric Company (PG&E). Reference 1, Enclosure 1 contains specific Requested Actions, Requested Information, and Required Responses associated with Recommendation 2.1 Seismic. Reference 1, Enclosure 1, Required Response 1 requires a 60-day response in which PG&E must submit: (1) its intent A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
m I &
Document Control Desk April 29, 2013 Page 2 PG&E Letter DCL-13-044 to follow the developed guidance or (2) an alternative approach, including acceptance criteria. In accordance with References 1 and 2, the 60-day responses are due to the NRC by April 29, 2013.
PG&E Letter DCL-12-060, "Pacific Gas and Electric Company's Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," dated June 7,2012, confirmed that PG&E will assess whether it can meet the submittal deadlines for the seismic hazard evaluation and seismic risk evaluation and submit its intention to follow the endorsed guidance or an alternative approach.
PG&E intends to respond to Reference 1, Enclosure 1 by following the approach described in Reference 3 on the schedule provided in Reference 3 with the following two clarifications:
(1) PG&E will perform the safe shutdown earthquake (SSE) to ground motion response spectrum (GMRS) comparison consistent with EPRI 3002000704, Section 2.2, footnote 1 (Reference 3, Attachment 1),
using the Diablo Canyon Power Plant (DCPP) double design earthquake (DOE) as the SSE. DCPP Updated Final Safety Analysis Report, Section 3.7.1.1 indicates that the DOE corresponds to the SSE, as described in 10 CFR 100, Appendix A.
(2) PG&E will develop the review-level ground motion (RLGM) in accordance with either Criteria 1 or 2 of EPRI 300200704, Section 4 (Reference 3, Attachment 1). For Criterion 1, PG&E will utilize the 5 percent damped free-field 1977 Hosgri earthquake (HE) spectrum as the baseline.
The 1977 HE is part of DCPP's design basis, previously reviewed and accepted by the NRC, and the spectrum shape is similar to the anticipated updated GMRS. The updated GMRS shape is expected to be similar to the 10-4 uniform hazard spectra, provided in Section 6.8.2 of PG&E Letter DCL-11-005, "Report on the Analysis of the Shoreline Fault Zone, Central Coastal California," dated January 7,2011. The ratio of the 1977 HE spectrum to the SSE (DOE) is 1.3 to 2.5 x SSE in the 1 to 10Hz frequency range and 1.9 x SSE at zero period acceleration. In order to develop RLGM, the 1977 HE spectrum will be scaled-up (if necessary) at each frequency to envelop the 5 percent damped updated GMRS, which is currently being developed in accordance with References 4 and 5.
The RLGM in-structure response spectra (ISRS) will be derived by scaling the 1977 HE ISRS based on the frequency-dependent ratio of the GMRS spectrum to the 1977 HE spectrum. The result will be a RLGM that envelops the updated GMRS. Therefore, the use of the 1977 HE for A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
__ Document Control Desk PG&E Letter DCL-13-044
~&~ April 29, 2013 I & Page 3 developing RLGM and in-structure RLGM seismic motion is appropriate for this beyond design basis, expedited evaluation process assessment.
PG&E is making a regulatory commitment (as defined by NEI 99-04) in the Enclosure of this letter. This letter includes no revisions to existing regulatory commitments.
If you have any questions, or require additional information, please contact Mr. Terence L. Grebel at (805) 545-4160.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on April 29, 2013.
Sincerely, B!.~~ $L---
Site Vice President dmfn/SAPN 50465913 Enclosure cc: Diablo Distribution cc:/enc: Thomas R. Hipschman, NRC, Senior Resident Inspector ArthurT. Howell, III, NRC Region IV Eric J. Leeds, NRC Director, Office of Nuclear Reactor Regulation James. T. Polickoski, NRR Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Enclosure PG&E Letter DCL-13-044 Page 1 of 1 Regulatory Commitments PG&E is making the following regulatory commitment (as defined by NEI 99-04) in this submittal:
Commitment Due Date PG&E intends to respond to Reference 1 , Enclosure 1 by Refer to following the approach described in Reference 3 on the Reference 3, schedule provided in Reference 3 with the following two Attachment 3 clarifications:
(1 ) PG&E will perform the safe shutdown earthquake (SSE) to ground motion response spectrum (GMRS) comparison consistent with EPRI 3002000704, Section 2.2, footnote 1 (Reference 3, Attachment 1), using the Diablo Canyon Power Plant (DCPP) double design earthquake (DOE) as the SSE.
(2) PG&E will develop the review-level ground motion (RLGM) in accordance with either Criteria 1 or 2 of EPRI 300200704, Section 4 (Reference 3, Attachment 1). For Criterion 1, PG&E will utilize the 5 percent damped free-field 1977 Hosgri earthquake (HE) spectrum as the baseline. The ratio of the 1977 HE spectrum to the SSE (DOE) is 1.3 to 2.5 x SSE in the 1 to 10Hz frequency range and 1.9 x SSE at zero period acceleration. In order to develop RLGM, the 1977 HE spectrum will be scaled-up (if necessary) at each frequency to envelop the 5 percent damped updated GMRS, which is currently being developed in accordance with References 4 and 5. The RLGM in-structure response spectra (ISRS) will be derived by scaling the 1977 HE ISRS based on the frequency-dependent ratio of the GMRS spectrum to the 1977 HE spectrum. The result will be a RLGM that envelops the updated GMRS.
