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| | issue date = 04/29/2013 | | | issue date = 04/29/2013 |
| | title = 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 | | | title = 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 |
| | author name = Allen B S | | | author name = Allen B |
| | author affiliation = Pacific Gas & Electric Co | | | author affiliation = Pacific Gas & Electric Co |
| | addressee name = | | | addressee name = |
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Category:Letter type:DCL
MONTHYEARDCL-24-087, License Renewal - Historic and Cultural Resources Reference Documents (Redacted)2024-09-12012 September 2024 License Renewal - Historic and Cultural Resources Reference Documents (Redacted) DCL-24-083, CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated2024-09-0909 September 2024 CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated DCL-24-078, Pre-Notice of Disbursement from Decommissioning Trust2024-09-0303 September 2024 Pre-Notice of Disbursement from Decommissioning Trust DCL-24-082, Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment2024-08-28028 August 2024 Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment DCL-24-077, Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident2024-08-15015 August 2024 Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident DCL-24-075, Response to Request for Additional Information for 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 React2024-08-0808 August 2024 Response to Request for Additional Information for 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 React DCL-24-070, License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2024-07-31031 July 2024 License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies DCL-24-071, Core Operating Limits Report for Unit 2 Cycle 252024-07-22022 July 2024 Core Operating Limits Report for Unit 2 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Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage2024-05-0808 May 2024 One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage DCL-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Radiological Environmental Operating Report DCL-24-047, 2023 Annual Non-radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Non-radiological Environmental Operating Report DCL-24-048, O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 20232024-04-30030 April 2024 O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 2023 DCL-24-027, 2023 Annual Radioactive Effluent Release Report2024-04-28028 April 2024 2023 Annual Radioactive Effluent Release Report DCL-24-045, Annual Report of Occupational Radiation Exposure for 20232024-04-24024 April 2024 Annual Report of Occupational Radiation Exposure for 2023 DCL-24-042, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-04-17017 April 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations DCL-24-022, Notification of Changes to Decommissioning Schedule2024-04-0202 April 2024 Notification of Changes to Decommissioning Schedule DCL-24-023, Revised Certification of Permanent Cessation of Power Operations2024-04-0202 April 2024 Revised Certification of Permanent Cessation of Power Operations DCL-24-031, Decommissioning Funding Report2024-03-27027 March 2024 Decommissioning Funding Report DCL-24-032, 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant2024-03-27027 March 2024 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant DCL-24-028, Request for Enforcement Discretion Regarding Compliance with Technical 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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 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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 2024-09-09
[Table view] |
Text
Pacific Gas and Electric Company April 29, 2 013 PG&E Letter DCL-13-044 B a rry S. Allen Site Vice President Diablo Canyon Power Plan t Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.4888 Internal:
691.4888 Fax: 805.545.6445 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike 10 CFR 50.54(f) 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
- Wolf Creek m Document Control Desk April 29, 2013 I & 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 April 29, 2013 I & Page 3 PG&E Letter DCL-13-044 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,
$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
- Wolf Creek 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.