ML13106A331
ML13106A331 | |
Person / Time | |
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Issue date: | 05/07/2013 |
From: | Leeds E Office of Nuclear Reactor Regulation |
To: | Joseph E Pollock Nuclear Energy Institute |
Regner L, NRR/JLD, 415-1906 | |
Shared Package | |
ML13114A949 | List: |
References | |
Download: ML13106A331 (28) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 7,2013 Mr. Joseph E. Pollock, Executive Director Nuclear Energy Institute 1776 I Street NW, Suite 400 Washington, DC 20006-3708
SUBJECT:
ELECTRIC POWER RESEARCH INSTITUTE FINAL DRAFT REPORT XXXXXX, "SEISMIC EVALUATION GUIDANCE: AUGMENTED APPROACH FOR THE RESOLUTION OF FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.1: SEISMIC," AS AN ACCEPTABLE ALTERNATIVE TO THE MARCH 12, 2012, INFORMATION REQUEST FOR SEISMIC REEVALUATIONS
Dear Mr. Pollock:
On behalf of the U.S. Nuclear Regulatory Commission (NRC), I am responding to the Nuclear 1
Energy Institute's (NEI's) letter of April 9, 2013. Your letter included a discussion of the update to the central and eastern United States (CEUS) ground motion model (GMM); an attached final draft of Electric Power Research Institute (EPRI) Report, "Seismic Evaluation Guidance:
Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic" (hereafter referred to as the EPRI Guidance); and attached proposed schedules accounting for the GMM update, implementation of the EPRI Guidance, and seismic resource limitations.
The NEI letter indicates that industry intends to supplement its use of the staff-endorsed "Seismic Evaluation Guidance: Screening Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic,,,2 with proposed interim actions, as detailed in the EPRI Guidance. The SPID guidance was the product of significant interaction between the NRC, NEI, EPRI, and other stakeholders at numerous public meetings to support licensee responses to Enclosure 1 ofthe March 12, 2012, information requese that was issued by the NRC pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.54(f) (the 50.54(f) letter). As with the SPID guidance, the NRC, NEI, EPRI, and other stakeholders have interacted in several public meetings since November 2012 to discuss the EPRI Guidance document.
The staff has determined that the EPRI Guidance will provide an important demonstration of seismic margin and expedite plant safety enhancements through evaluations and potential near-term modifications of certain core and containment cooling equipment while more comprehensive plant seismic risk evaluations are being performed. The NRC staff has also determined that the schedule modifications provided in the NEI's April 9, 2013, letter are Agencywide Documents Access and Management System (ADAMS) Accession No. ML13101A379.
The SPID guidance document is found in ADAMS under Accession No. ML12333A170. The staff endorsement letter for the SPID guidance is found in ADAMS under Accession No. ML12319A074.
The SO.S4(f) letter is available in ADAMS under Accession No. ML120S3A340.
J. Pollock -2 acceptable since the schedule accounts for seismic resource limitations, EPRI's completion of the update to the GMM for the CEUS, and implementation of the EPRI Guidance evaluations and modifications.
Ground Motion Model The SO.S4(f) letter requested that those licensees whose plants are located in the CEUS use NUREG-211S, "Central and Eastern United States Seismic Source Characterization for Nuclear Facilities," and the appropriate EPRI (2004, 2006) GMM to characterize the seismic hazard for their sites. 4 Subsequent to the issuance of the SO.S4(f) letter, industry informed the staff that it had undertaken a study and determined that the EPRI (2004, 2006) GMM should be updated. 5 In order to facilitate its eventual review of the updated EPRI GMM, the staff has interacted with NEI, EPRI, and other stakeholders in public meetings on industry's efforts to update the EPRI GMM.
By letter dated January 31, 2013,6 NEI transmitted the EPRI draft document, "Draft - EPRI (2004, 2006) Ground-Motion Model (GMM) Review Project" to the NRC, requesting review and approval by February 27,2013. For the update of its earlier GMM, EPRI used a significant amount of additional data, conducted field investigations, and used more recent methods than were previously available. In performing the GMM update, EPRI has also addressed the concerns of an independent peer review panel, which is an important part of the Senior Seismic Hazard Analysis Committee (SSHAC) guidelines (these guidelines are discussed in NRC's NUREG-2117, "Practical Implementation Guidelines for SSHAC Level 3 and 4 Hazard Studies").
Following a review of the NEI submittal, in a public meeting on February 28, 2013, 7 the staff expressed concern with EPRI's treatment of uncertainty and the level of documentation in the updated GMM. The staff formally documented these concerns by letter dated March 20, 2013. 8 Subsequently, in a public meeting on March 26, 2013,9 industry presented a revision of its updated EPRI GMM, which demonstrated significant progress towards addressing the staff's concerns with respect to the treatment of uncertainty. Industry also proposed a schedule, including further interactions with NRC staff, for completing the development and documentation of the updated EPRI GMM. In order to complete its update of the EPRI GMM and accompanying documentation, and to allow time for the development of site seismic hazard curves, industry proposed a six month delay from the schedule outlined in the SO.S4(f) letter for the submittal of the seismic hazard reevaluations for CEUS plants.
The staff agrees that updated models, methods, and data will provide licensees with the most current information in order to perform the seismic hazard evaluations requested by the SO.S4(f) letter. The NRC staff intends to complete its review of the industry's updated CEUS GMM by Licensees whose sites are located in the western United States (WUS) were asked to develop a probabilistic seismic hazard analysis consistent with the process used for new reactor licensing under 10 CFR Part 52, "Licenses, Certifications, and Approvals for Nuclear Power Plants."
By letter dated August 24, 2012, at ADAMS Accession No. ML12240A034, the industry notified staff of its intent to proceed with Phase 2 of the GMM update project.
The letter can be found in ADAMS at Accession No. ML13059A090.
The meeting summary and presentation materials can be found in the package in ADAMS at Accession No.
Ml13106A158.
The letter can be found in ADAMS at Accession No. Ml13078A029.
The meeting summary and presentation material can be found in the package in ADAMS at Accession No.
Ml13081A304.
J. Pollock - 3 August 30, 2013, if the industry submits the completed documentation of the updated model by June 30, 2013. If the staff is unable to approve the updated EPRI GMM by August 30, 2013, industry is expected to use the staff-approved EPRI (2004, 2006) GMM for the CEUS plant reevaluations.
EPRI Guidance The EPRI Guidance document provides licensees with additional guidance on the performance of an Expedited Seismic Evaluation Process. The Expedited Seismic Evaluation Process is a screening, evaluation, and equipment modification process to be conducted by licensees to provide additional seismic margin and expedite plant safety enhancements for certain core and containment cooling components while more detailed and comprehensive plant seismic risk evaluations are being performed.
The Expedited Seismic Evaluation Process focuses on the equipment needed to maintain or restore reactor and containment cooling during the initial phase of a severe external event causing an extended loss of all alternating current power as identified in Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design-Basis External Events.,,1o In response to the Order, NEI developed NEI12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide.,,11 The Expedited Seismic Evaluation Process identifies a subset of FLEX Phase 1 equipment for evaluation and potential modification. This subset of FLEX equipment is installed core and containment cooling equipment and connection points needed during an extended station blackout event.
In particular, the guidance describes a methodology for the evaluation of the seismic capacity of the equipment identified in the Expedited Seismic Evaluation Process. If the seismic capacity of the equipment is inadequate relative to the reevaluated seismic demand, then the guidance provides equipment modification criteria. These modifications will provide additional assurance regarding maintenance of core and containment cooling during beyond-design-basis seismic events. In accordance with the guidance, licensees will submit the results of the evaluations, including required equipment modifications and their implementation schedule, in an Expedited Seismic Evaluation Process report for review by the NRC staff. The letter states that CEUS licensees will submit the reports resulting from the Expedited Seismic Evaluation Process by December 2014 and complete non-outage-related Expedited Seismic Evaluation Process equipment modifications by December 2016. Similarly, the letter states that the western United States (WUS) licensees will submit Expedited Seismic Evaluation Process reports by January 2016 and complete non-outage-related Expedited Seismic Evaluation Process equipment modifications by June 2018.
After review of industry's proposed EPRI Guidance, the NRC staff believes that the evaluations and potential near-term equipment modifications associated with the Expedited Seismic Evaluation Process will provide an important demonstration of seismic margin and enhance plant safety while more detailed plant risk evaluations are being conducted by licensees. The 10 The Order is available in ADAMS under Accession No. ML12054A736.
11 The guidance is available in ADAMS under Accession No. ML12242A378.
J. Pollock -4 staff further concludes that the EPRI Guidance provides an appropriate methodology for licensees to implement and complete the Expedited Seismic Evaluation Process according to the schedule provided in the letter.
In accordance with the 50.54(f) letter, each licensee is to submit to the NRC its intention to follow the NRC-endorsed seismic reevaluation guidance (or SPID), or an alternative approach, 60 days after the issuance of the NRC-endorsed guidance. Licensees may use the EPRI Guidance, in addition to the SPID guidance, as an acceptable approach for responding to the information requested in Enclosure 1 of the 50.54(f) letter. Accordingly, the NRC staffs issuance of this letter endorsing the EPRI Guidance is not considered backfitting, as defined in 10 CFR 50.109(a)(1).
The NRC requests that EPRI publish a final version of the EPRI Guidance within one month of receipt of this letter. The final version of the EPRI Guidance should incorporate this letter between the title page and the first section, and EPRI should remove the draft markings from the document.
Schedule Modification As discussed above, the nuclear power industry has proposed two adjustments to the seismic hazard reevaluations at nuclear power plant sites: 1) to complete the update of the EPRI GMM for the CEUS, and 2) to implement the EPRI Guidance. These proposed changes affect the schedule outlined in the 50.54(f) letter.
First, the industry has requested additional time to complete the updated EPRI GMM project, including documentation and interactions with the NRC staff. The project documentation is scheduled to be submitted to the NRC on June 3, 2013. Pending approval by the staff, CEUS licensees will use the updated model to complete the site-specific seismic hazard evaluations specified in Enclosure 1 to the SPID guidance. Currently, the hazard submittals are requested by September 2013; however, the industry has requested to submit the hazard evaluations by March 31, 2014. The industry stated in its letter that it will not delay submittal of items 3.a.
"Description of Subsurface Materials and Properties," and 3.b. "Development of Base Case Profiles and Nonlinear Material Properties" of Section 4 of Enclosure 1 to the SPID guidance.
Licensees intend to submit these items in September 2013 for the staff's review. This will allow the staff to begin its review in accordance with the original schedule and complete a significant portion of the Section 4 review on time.
The staff finds that the schedule modifications discussed above for CEUS plants are acceptable because the updated GMM will provide the CEUS operating nuclear plant fleet with a model developed using the most recent data and methodologies available for their seismic hazard reevaluations. Additionally, the partial submittal in September 2013 will allow the staff to complete a portion of its review as originally scheduled by the 50.54(f) letter.
Second, the industry has requested modifications to the 50.54(f) letter schedule to allow for implementation of the Expedited Seismic Evaluation Process for those nuclear power plants where the reevaluated seismic hazard exceeds the plant's design basis. These schedule modifications allow for completion of the Expedited Seismic Evaluation Process for CEUS plants
J. Pollock - 5 by December 2016, if the equipment modifications do not require a plant shutdown to access equipment. 12 For WUS plants, the Expedited Seismic Evaluation Process modifications will be completed by June 2018, if the modifications do not require a plant shutdown to access equipment.
For plants requiring a seismic risk analysis, the 50.54(f) letter states that the staff will perform a prioritization for both the CEUS and WUS plants into two priority groups, and possibly a third, if needed. Under industry's proposed schedule, the higher priority CEUS plants will complete their risk evaluations by June 2017 (originally scheduled for October 2016). This delay is primarily due to the additional time needed to complete the EPRI GMM update project. The second group of CEUS plants will complete their risk evaluations by December 2019. This is about a two-year delay from the schedule specified in the 50.54(f) letter for the lower priority plants to complete their risk evaluations. Conversely, the letter proposes an earlier completion date of June 2017 for the risk evaluations for the higher priority WUS plants.
The staff finds that the schedule modifications discussed above for CEUS and WUS plants are acceptable, because the Expedited Seismic Evaluation Process provides for near-term seismic evaluations and expedited equipment modifications at the plants that will offer additional assurance that plants will operate safely during a beyond-design-basis seismic event.
Furthermore, the schedule modifications account for limited seismic resources available to both the NRC and the industry. The schedule modifications provide for completion of the higher priority CEUS plant risk evaluations by the end of June 2017, which is not a significant extension of the original 50. 54(f) letter schedule of October 2016. In addition, the schedule proposes an earlier completion date for the higher priority risk evaluations for the WUS plants.
The industry noted in its letter that if a large number of plants need to perform the risk evaluations, additional time may be needed which may extend the completion of some risk evaluations for a third tier of lower priority plants until December 2020. The NRC staff finds that the additional time to complete these lower priority plant risk evaluations is acceptable because limited seismic resources will likely impact the number of risk evaluations that can be completed by 2019.
Conclusion In conclusion, the staff has determined that the proposed EPRI Guidance and the schedule modifications described in the NEl's April 9, 2013, letter are acceptable since they provide for implementation of the expedited interim actions and near-term plant safety enhancements, as well as EPRl's completion of the update to the GMM for the CEUS. The industry proposal also provides a reasonable approach and schedule which accounts for the considerable seismic resources needed to complete the seismic reevaluations.
12 If outages are required, the plants are allowed two outages from the completion of the Expedited Seismic Evaluation Process report. which are to be submitted to the NRC staff for review by December 31,2014.
J. Pollock -6 If you or your staff have additional questions, please contact my office; alternatively, you can contact Mrs. Lisa Regner of my staff by phone at 301-415-1906, or bye-mail at Lisa. Regner@nrc.gov.
Sincerely,
- LE Office of Nuclear Reactor Regulation
Enclosure:
Federal Register Notice cc: See enclosed list Listserv
POWER REACTOR LICENSEES AND HOLDERS OF CONSTRUCTION PERMITS IN ACTIVE OR DEFERRED STATUS Arkansas Nuclear One Braidwood Station Entergy Operations, Inc. Exelon Generation Co., LLC Docket Nos. 50-313 and 50-368 Docket Nos. STN 50-456 and STN 50-457 License Nos. DPR-51 and NPF-6 License Nos. NPF-72 and NPF-77 Mr. Jeremy Browning Mr. Michael J. Pacillio Site Vice President Senior Vice President Entergy Operations, Inc. Exelon Generation Company, LLC Arkansas Nuclear One President and Chief Nuclear Office (CNO) 1448 S.R 333 Exelon Nuclear Russellville, AR 72802 4300 Winfield Road Warrenville, IL 60555 Beaver Valley Power Station First Energy Nuclear Operating Co. Browns Ferry Nuclear Plant Docket Nos. 50-334 and 50-412 Tennessee Valley Authority License Nos. DPR-66 and NPF-73 Docket Nos. 50-259, 50-260 and 50-296 License Nos. DPR-33, DPR-52 and DPR-68 Mr. Eric A. Larson Beaver Valley Power Station Mr. Joseph W. Shea P.O. Box 4, Route 168 Vice President, Nuclear licenSing Shippingport, PA 15077 Tennessee Valley Authority 1101 Market Street, EB 9W Bellefonte Nuclear Power Station Chattanooga, TN 37402*2801 Tennessee Valley Authority Docket Nos. 50-438 and 50-439 Brunswick Steam Electric Plant Construction Permit Nos. CPPR-122 and Carolina Power & Light Co.
CPPR-123 Docket Nos. 50-325 and 50-324 License Nos. DPR-71 and DPR-62 Mr. Michael D. Skaggs Senior Vice President, Nuclear Construction Mr. Michael J. Annacone Tennessee Valley Authority Vice President 6A Lookout Place Carolina Power & Light Company 1101 Market Street Brunswick Steam Electric Plant Chattanooga, TN 37402-2801 P.O. Box 10429 Southport, NC 28461
Byron Station Catawba Nuclear Station Exelon Generation Co., LLC Duke Energy Carolinas, LLC Docket Nos. STN 50-454 and STN 50-455 Docket Nos. 50-413 and 50-414 License Nos. NPF-37 and NPF-66 License Nos. NPF-35 and NPF-52 Mr. Michael J. Pacillio Mr. Kelvin Henderson Senior Vice President Site Vice President Exelon Generation Company, LLC Duke Energy Carolinas, LLC President and Chief Nuclear Office (CNO) Catawba Nuclear Station Exelon Nuclear 4800 Concord Road 4300 Winfield Road York, SC 29745 Warrenville, IL 60555 Clinton Power Station Callaway Plant Exelon Generation Co., LLC Union Electric Company Docket No. 50-461 Docket No. 50-483 License No. NPF-62 License No. NPF-30 Mr. Michael J. Pacilio Mr. Adam C. Heflin President and Chief Nuclear Officer Senior Vice President and Exelon Nuclear Chief Nuclear Officer Clinton Power Station Union Electric Company 4300 Winfield Road Ameren Missouri Warrenville, IL 60555 P.O. Box 620 Fulton, MO 65251 Columbia Generating Station Energy Northwest Calvert Cliffs Nuclear Power Plant Docket No. 50-397 Calvert Cliffs Nuclear Power Plant, LLC License No. NPF-21 Docket Nos. 50-317 and 50-318 License Nos. DPR-53 and DPR-69 Mr. Mark E. Reddemann Chief Executive Officer Mr. George H. Gellrich Energy Northwest Vice President MD 1023 Calvert Cliffs Nuclear Power Plant, LLC North Power Plant Loop Calvert Cliffs Nuclear Power Plant P.O. Box 968 1650 Calvert Cliffs Parkway Richland, WA 99352 Lusby, MD 20657-4702
- 3 Comanche Peak Nuclear Power Plant Diablo Canyon Power Plant Luminant Generation Co., LLC Pacific Gas & Electric Co.
Docket Nos. 50-445 and 50-446 Docket Nos. 50-275 and 50-323 License Nos. NPF-87 and NPF-89 License Nos. DPR-80 and DPR-82 Mr. Rafael Flores Mr. Edward D. Halpin Senior Vice President and Senior Vice President and Chief Nuclear Officer Chief Nuclear Officer Attn: Regulatory Affairs Pacific Gas and Electric Company Luminant Generation Company, LLC P.O. Box 56, P.O. Box 1002 Mail Code 104/6 Glen Rose, TX 76043 Avila Beach, CA 93424 Cooper Nuclear Station Donald C. Cook Nuclear Plant Nebraska Public Power District Indiana Michigan Power Company Docket No. 50-298 Docket Nos. 50-315 and 50-316 License No. DPR-46 License Nos. DPR-58 and DPR-74 Mr. Oscar A. Limpias Mr. Lawrence J. Weber Vice President Nuclear and Senior Vice President and Chief Nuclear Officer Chief Nuclear Officer Nebraska Public Power District Indiana Michigan Power Company 72676 648A Avenue Nuclear Generation Group P.O. Box 98 One Cook Place Brownville, NE 68321 Bridgman, MI49106 Crystal River Nuclear Generating Plant Dresden Nuclear Power Station Florida Power Corp. Exelon Generation Co., LLC Docket No. 50-302 Docket Nos. 50-237 and 50-249 License No. DPR-72 License Nos. DPR-19 and DPR-25 Terry Hobbs Mr. Michael J. Pacillio Decommissioning Director Senior Vice President Crystal River Nuclear Plant (NA2C) Exelon Generation Company, LLC 15760 West Power Line Street President and Chief Nuclear Office (CNO)
Crystal River, FL 34428-6708 Exelon Nuclear 4300 Winfield Road Davis-Besse Nuclear Power Station Warrenville, IL 60555 First Energy Nuclear Operating Co.
Docket No. 50-346 License No. NPF-3 Mr. Ray Lieb Site Vice President FirstEnergy Nuclear Operating Company c/o Davis-Besse NPS 5501 N. State Route 2 Oak Harbor, OH 43449-9760
- 4 Duane Arnold Energy Center Grand Gulf Nuclear Station NextEra Energy Duane Arnold, LLC Entergy Operations, Inc.
Docket No. 50-331 Docket No. 50-416 License No. DPR-49 License No. NPF-29 Mr. Rich Anderson Vice President, Operations Site Vice President Entergy Operations, Inc.
NextEra Energy Grand Gulf Nuclear Station Duane Arnold Energy Center P.O. Box 756 3277 DAEC Road Port Gibson, MS 39150 Palo, IA 52324-9785 H. B. Robinson Steam Electric Plant Edwin I. Hatch Nuclear Plant Carolina Power & Light Co.
Southern Nuclear Operating Co. Docket No. 50-261 Docket Nos. 50-321 and 50-366 License No. DPR-23 License Nos. DPR-57 and NPF-5 Mr. William R. Gideon Mr. C.R. Pierce Vice President Regulatory Affairs Director H.B. Robinson Steam Electric Plant Southern Nuclear Operating Co., Inc. Carolina Power & Light Company P.O. Box 1295/BI N B038 3581 West Entrance Road Birmingham, AL 35201-1295 Hartsville, SC 29550 Fermi Hope Creek Generating Station Detroit Edison Co. PSEG Nuclear, LLC Docket No. 50-341 Docket No. 50-354 License No. NPF-43 License No. NPF-57 Mr. Joseph H. Plona Mr. Thomas Joyce Senior Vice President and Chief Nuclear President and Chief Nuclear Officer Officer PSEG Nuclear LLC - N09 Detroit Edison Company P. O. Box 236, Fermi 2 - 210 NOC Hancocks Bridge, NJ 08038 6400 North Dixie Highway Newport, M I 48166 Indian Point Energy Center Entergy Nuclear Operations, Inc.
Fort Calhoun Station Docket Nos. 50-247 and 50-286 Omaha Public Power District License Nos. DPR-26 and DPR-64 Docket No. 50-285 License No. DPR-40 Vice President, Operations Entergy Nuclear Operations, Inc.
Mr. Louis CortopaSSi Indian Point Energy Center Vice President and Chief Nuclear Officer 450 Broadway, GSB Omaha Public Power District P.O. Box 249 Fort Calhoun Station Buchanan, NY 10511-0249 Mail Stop FC-2-4 9610 Power Lane Blair, NE 68008
- 5 James A FitzPatrick Nuclear Power Plant Limerick Generating Station Entergy Nuclear Operations, Inc. Exelon Generation Co., LLC Docket No. 50-333 Docket Nos. 50-352 and 50-353 License No. DPR-59 License Nos. NPF-39 and NPF-85 Site Vice President Mr. Michael J. Pacillio Entergy Nuclear Operations, Inc. Senior Vice President James A FitzPatrick Nuclear Power Plant Exelon Generation Company, LLC P.O. Box 110 President and Chief Nuclear Office (CNO)
Lycoming, NY 13093 Exelon Nuclear 4300 Winfield Road Joseph M. Farley Nuclear Plant Warrenville, IL 60555 Southern Nuclear Operating Co.
Docket Nos. 50-348 and 50-364 Millstone Nuclear Power Station License Nos. NPF-2 and NPF-8 Dominion Nuclear Connecticut, Inc.
Docket Nos. 50-336 and 50-423 Mr. C. R Pierce License Nos. DPR-65 and NPF-49 Regulatory Affairs Director Southern Nuclear Operating Co., Inc. Mr. David A Heacock P.O. Box 1295/Bin 038 President and Chief Nuclear Officer Birmingham, AL 35201-1295 Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center Kewaunee Power Station 5000 Dominion Boulevard Dominion Energy Kewaunee, Inc. Glen Allen, VA 23060-6711 Docket No. 50-305 License No. DPR-43 Monticello Nuclear Generating Plant Northern States Power Company Mr. David A Heacock Docket No. 50-263 President and Chief Nuclear Officer License No. DPR-22 Dominion Energy Kewaunee, Inc.
Innsbrook Technical Center Mr. Mark A Schimmel 5000 Dominion Boulevard Site Vice President Glen Allen, VA 23060-6711 Northern States Power Company - Minnesota Monticello Nuclear Generating Plant LaSalle County Station 2807 West County Road 75 Exelon Generation Co., LLC Monticello, MN 55362-9637 Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Nine Mile Point Nuclear Station Nine Mile Point Nuclear Station, LLC Mr. Michael J. Pacillio Docket Nos. 50-220 and 50-410 Senior Vice President License Nos. DPR-63 and I\IPF-69 Exelon Generation Company, LLC President and Chief Nuclear Office (CNO) Mr. Christopher Costanzo Exelon Nuclear Vice President Nine Mile Point 4300 Winfield Road Nine Mile Point Nuclear Station, LLC Warrenville, IL 60555 P.O. Box 63 Lycoming, NY 13093
- 6 North Anna Power Station Palo Verde Nuclear Generating Station Virginia Electric & Power Co. Arizona Public Service Company Docket Nos. 50-338 and 50-339 Docket Nos. STN 50-528, STN 50-529 and License Nos. NPF-4 and NPF-7 STN 50-530 License Nos. NPF-41, NPF-51 and NPF-74 Mr. David A. Heacock President and Chief Nuclear Officer Mr. Randall K. Edington Dominion Nuclear Executive Vice President Nuclear and Chief Innsbrook Technical Center Nuclear Officer 5000 Dominion Boulevard Arizona Public Service Co.
Glen Allen, VA 23060-6711 P.O. Box 52034, MS 7602 Phoenix, AZ 85072-2034 Oconee Nuclear Station Duke Energy Carolinas, LLC Peach Bottom Atomic Power Station Docket Nos. 50-269, 50-270 and 50-287 Exelon Generation Co., LLC License Nos. DPR-38, DPR-47 and DPR-55 Docket Nos. 50-277 and 50-278 License Nos. DPR-44 and DPR-56 Mr. Scott Batson Vice President, Oconee Nuclear Station Mr. Michael J. Pacillio Duke Energy Carolinas, LLC Senior Vice President 7800 Rochester Highway Exelon Generation Company, LLC Seneca, SC 29672 President and Chief Nuclear Office (CNO)
Exelon Nuclear Oyster Creek Nuclear Generating Station 4300 Winfield Road Exelon Generation Co., LLC Warrenville, IL 60555 Docket No. 50-219 License No. DPR-16 Perry Nuclear Power Plant FirstEnergy Nuclear Operating Co.
Mr. Michael J. Pacillio Docket No. 50-440 Senior Vice President License No. NPF-58 Exelon Generation Company, LLC President and Chief Nuclear Office (CNO) Mr. Vito A. Kaminskas Exelon Nuclear Site Vice President - Nuclear - Perry 4300 Winfield Road FirstEnergy Nuclear Operating Company Warrenville, IL 60555 Perry Nuclear Power Plant 10 Center Road, A290 Palisades Nuclear Plant Perry, OH 44081 Entergy Nuclear Operations, Inc.
Docket No. 50-255 License No. DPR-20 Vice President, Operations Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043
-7 Pilgrim Nuclear Power Station Unit No.1 R E. Ginna Nuclear Power Plant Entergy Nuclear Operations, Inc. RE. Ginna Nuclear Power Plant, LLC Docket No. 50-293 Docket No. 50-244 License No. DPR-35 License No. DPR-18 Mr. John Dent, Jr. Mr. Joseph E. Pacher Vice President and Site Vice President Vice President Entergy Nuclear Operations, Inc. RE. Ginna Nuclear Power Plant, LLC Pilgrim Nuclear Power Station RE. Ginna Nuclear Power Plant 600 Rocky Hill Road 1503 Lake Road Plymouth, MA 02360-5508 Ontario, NY 14519 Point Beach Nuclear Plant River Bend Station NextEra Energy Point Beach, LLC Entergy Operations, Inc.
Docket Nos. 50-266 and 50-301 Docket No. 50-458 License Nos. DPR-24 and DPR-27 License No. NPF-47 Mr. Larry Meyer Vice President, Operations Site Vice President Entergy Operations, Inc.
NextEra Energy Point Beach, LLC River Bend Station Point Beach Nuclear Plant, Units 1 & 2 5485 U.S. Highway 61 N 6610 Nuclear Road St. Francisville, LA 70775 Two Rivers, WI 54241-9516 Salem Nuclear Generating Station Prairie Island Nuclear Generating Plant PSEG Nuclear, LLC.
Northern States Power Co. Minnesota Docket Nos. 50-272 & 50-311 Docket Nos. 50-282 and 50-306 License Nos. DPR-70 and DPR-75 License Nos. DPR-42 and DPR-60 Mr. Thomas Joyce Mr. James E. Lynch President and Chief Nuclear Officer Site Vice President PSEG Nuclear LLC - N09 Northern States Power Company - Minnesota P.O. Box 236, Prairie Island Nuclear Generating Plant Hancocks Bridge, NJ 08038 1717 Wakonade Drive East Welch, MN 55089-9642 San Onofre Nuclear Generating Station Southern California Edison Company Quad Cities Nuclear Power Station Docket Nos. 50-361 and 50-362 Exelon Generation Co., LLC License Nos. NFP-10 and NFP-15 Docket Nos. 50-254 and 50-265 License Nos. DPR-29 and DPR-30 Mr. Peter T. Dietrich Senior Vice President and Mr. Michael J. Paciliio Chief Nuclear Officer Senior Vice President Southern California Edison Company Exelon Generation Company, LLC San Onofre Nuclear Generating Station President and Chief Nuclear Office (CNO) P.O. Box 128 Exelon Nuclear San Clemente, CA 92674-0128 4300 Winfield Road Warrenville, IL 60555
Seabrook Nuclear Plant St. Lucie Plant NextEra Energy Seabrook, LLC Florida Power & Light Co.
Docket No 50-443 Docket Nos. 50-335 and 50-389 License No. NFP-86 License Nos. DPR-67 and NPF-16 Mr. Kevin Walsh Mr. Mano Nazar Vice President, Seabrook Nuclear Plant Executive Vice President and clo Mr. Michael O'Keefe Chief Nuclear Officer NextEra Energy Seabrook, LLC NextEra Energy P.O. Box 300 P.O. Box 14000 Seabrook, NH 03874 700 Universe Boulevard Juno Beach, FL 33408-0420 Sequoyah Nuclear Plant Tennessee Valley Authority Surry Power Station Docket Nos. 50-327 and 50-328 Virginia Electric & Power Co.
License Nos. DPR-77 and DPR-79 Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 Mr. Joseph W. Shea Vice President, Nuclear Licensing Mr. David A. Heacock Tennessee Valley Authority President and Chief Nuclear Officer 1101 Market Street, LP 3D-C Dominion Nuclear Chattanooga, TN 37402-2801 Virginia Electric & Power Company Innsbrook Technical Center Shearon Harris Nuclear Power Plant 5000 Dominion Boulevard Carolina Power & Light Co. Glen Allen, VA 23060-6711 Docket No. 50-400 License No. NPF-63 Susquehanna Steam Electric Station PPL Susquehanna, LLC Mr. George T. Hamrick Docket Nos. 50-387 and 50-388 Vice President License Nos. NPF-14 and NPF-22 Carolina Power and Light Company Shearon Harris Nuclear Power Plant Mr. Timothy S. Rausch P.O. Box 165, Mail Zone 1 Senior Vice President and New Hill, NC 27562-0165 Chief Nuclear Officer PPL Susquehanna, LLC South Texas Project 769 Salem Boulevard STP Nuclear Operating Co. NUCSB3 Docket Nos. 50-498 and 50-499 Berwick, PA 18603-0467 License Nos. NPF-76 and NPF-80 Mr. Dennis L. Koehl President and CEO/CNO STP Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483
- 9 Three Mile Island, Unit 1 Vogtle Electric Generating Plant Exelon Nuclear Southern Nuclear Operating Co.
Docket No. 50-289 Docket Nos. 50-424 and 50-425 License No. DPR-50 License Nos. NPF-68 and NPF-81 Mr. Michael J. Pacillio Mr. C.R. Pierce Senior Vice President Regulatory Affairs Director Exelon Generation Company, LLC Southern Nuclear Operating Co., Inc.
President and Chief Nuclear Office (CNO) P.O. Box 1295/Bin 038 Exelon Nuclear Birmingham, AL 35201 4300 Winfield Road Warrenville, IL 60555 Waterford Steam Electric Station Entergy Operations, Inc.
Turkey Point Docket No. 50-382 Florida Power & Light Co. License No. NPF-38 Docket Nos. 50-250 and 50-251 License Nos. DPR-31 and DPR-41 Vice President, Operations Entergy Operations, Inc.
Mr. Mano Nazar Waterford Steam Electric Station, Unit 3 Executive Vice President and 17265 River Road Chief Nuclear Officer Killona, LA 70057-0751 NextEra Energy P.O. Box 14000 Watts Bar Nuclear Plant, Units 1 and 2 700 Universe Boulevard Watts Bar Nuclear Plant, Unit 1 Juno Beach, FL 33408-0420 Tennessee Valley Authority Docket No. 50-390 Vermont Yankee Nuclear Power Station License No. NPF-90 Entergy Nuclear Operations, Inc.
Docket No. 50-271 Watts Bar Nuclear Plant, Unit 2 License No. DPR-28 Tennessee Valley Authority Docket No. 50-391 Site Vice President, Operations Construction Permit No. CPPR No. 092 Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station Mr. Joseph W. Shea P.O. Box 250, Governor Hunt Road Chief Nuclear Officer and Executive Vice Vernon, VT 05354 President Tennessee Valley Authority Virgil C. Summer Nuclear Station 1101 Market Street South Carolina Electric & Gas Co. Chattanooga, TN 37402-2801 Docket No. 50-395 License No. NPF-12 Mr. Thomas D. Gatlin Vice President Nuclear Operations South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station Post Office Box 88, Mail Code 800 Jenkinsville, SC 29065
- 10 William B. McGuire Nuclear Station Duke Energy Carolinas, LLC Docket Nos. 50-369 and 50-370 License Nos. NPF-9 and NPF-17 Mr. Steven D. Capps Duke Energy Carolinas, LLC McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-8985 Wolf Creek Generating Station Wolf Creek Nuclear Operating Corp.
Docket No. 50-482 License No. NPF-42 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
[7590-01-P]
NUCLEAR REGULATORY COMMISSION
[NRC-2013-0038]
Electric Power Research Institute; Seismic Evaluation Guidance AGENCY: U.S. Nuclear Regulatory Commission.
ACTION: Endorsement letter; issuance.
SUMMARY
- The U.S. Nuclear Regulatory Commission (NRC) is issuing an endorsement letter of Electric Power Research Institute (EPRI) Report, "Seismic Evaluation Guidance: EPRI Guidance for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1:
Seismic," Draft Report, hereafter referred to as the EPRI Guidance. This EPRI Guidance provides additional information, to be used in combination with the staff-endorsed Screening Prioritization and Implementation Details (SPID) report 1 , on an acceptable strategy to implement interim actions in accordance with item (6) of the Requested Information in Enclosure 1 "Recommendation 2.1: Seismic," of the NRC staff's request for information (SO.S4(f) letter),
"Request for Information Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part SO.S4(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. In addition, in its April 9, 2013 letter, the Nuclear Energy Institute (!\lEI) requested modifications to the schedule The SPID report is available in the NRC's Agencywide Documents Access and Management System (ADAMS) under Accession No. ML12333A170. The staff endorsement letter for the SPID report is available in ADAMS under Accession No. ML12319A074.
The NElletter, with attachments, is available in ADAMS in a package with Accession No. ML13101A345.
established in the staffs 50.54(f) letter. The NRC staff has found the schedule modifications to be acceptable since they account for completion of the EPRI central and eastern United States (CEUS) ground motion model (GMM) update, completion of potential interim actions provided in the EPRI Guidance, and limited available seismic resources.
ADDRESSES: You may access information related to this document, which the NRC possesses and is publicly available, by searching on http://wwwregu/ations.gov under Docket ID NRC-2013-0038.
- Federal Rulemaking Web site: Go to http://wwwregu/ations.gov and search for Docket ID NRC-2013-0038. Address questions about NRC dockets to Carol Gallagher; telephone: 301-492-3668; e-mail: Carol.Gallagher@nrc.gov.
- NRC's Agencywide Documents Access and Management System (ADAMS):
You may access publicly-available documents online in the NRC Library at http://wwwnrc.aov/readina-rmladams.f7tm/. To begin the search, select "ADAMS Public Documents" and then select "Begin Web-based ADAMS Search." For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or bye-mail to PDRResources@nrc.qov. The NRC staffs endorsement letter of the EPRI Guidance is available under ADAMS Accession No. ML13106A331. The NRC staff's request for information dated March 12,2012, is available under ADAMS Accession No. ML12053A340.
- NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room 01-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
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FOR FURTHER INFORMATION CONTACT: Ms, Lisa M. Regner, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-1906; e-mail: Lisa.Regner@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background Information Pursuant to 10 CFR Part 50,54(f), the NRC issued a 50.54(f) letter dated March 12, 2012, regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident. 3 The NRC issued the 50.54(f) letter following the staff's evaluation of the earthquake and tsunami, and resulting nuclear accident, at the Fukushima Dai-ichi nuclear power plant in March 2011. Enclosure 1 to the 50.54(f) letter requests licensees and holders of construction permits under 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to reevaluate the seismic hazards at their sites using present-day NRC requirements and guidance, and to identify actions taken or planned to address plant-specific vulnerabilities associated with the updated seismic hazards.
Based on this information, the NRC staff will determine if additional regulatory actions are necessary to protect against the updated hazards.
By letter dated February 15, 2013, the NRC staff issued an endorsement letter, with clarifications, of EPRI-1025287, "Seismic Evaluation Guidance: Screening, Prioritization, and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," referred to as the SPID report. This SPID report describes The NTTF Report is available under ADAMS Accession No. ML111861807, The SO.S4(f) letter is available under ADAMS Accession No, ML12053A340,
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strategies for the screening, prioritization, and implementation of seismic risk evaluations that are acceptable to the NRC staff, and will assist nuclear power reactor licensees when responding to Enclosure 1 of the SO.S4(f) letter.
By letter dated April 9, 2013, the NEI submitted additional guidance to be used to supplement the SPID report for NRC endorsement. The letter also documented the industry's proposed plan to update the GMM for CELIS plants, and proposed modifications to the schedule for plant seismic reevaluations established in the SO.54(f) letter. The NEI letter, the EPRI Guidance, and additional attachments addressing proposed schedule changes are available in ADAMS under package Accession No. ML 13101 A34S.
II. Ground Motion Model The SO.S4(f) letter requested that the licensees whose plants are located in the CELIS use NUREG-211S, "Central and Eastern Llnited States [CELIS} Seismic Source Characterization for Nuclear Facilities" and the appropriate EPRI (2004, 2006) GMM to characterize the seismic hazard for their sites. The industry is currently completing a study to update the EPRI (2004, 2006) GMM based on current data and new ground motion prediction equations developed by seismic experts.
The NRC staff has interacted with NEI, EPRI, and other stakeholders in public meetings since November 2012, for status updates on industry's efforts to update the CELIS GMM. By letter dated January 31, 2013, the NEI transmitted the EPRI draft document, "Draft - EPRI (2004, 2006) Ground Motion Model (GMM) Review Project" to the NRC, requesting review and approval by February 27, 2013. For the update of its earlier GMM, EPRI used a significant amount of additional data, conducted field investigations, and used more recent methods than were previously available. In performing the GMM update, EPRI has also addressed the
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concerns of an independent peer review panel, which is an important part of the Senior Seismic Hazard Analysis Committee (SSHAC) guidelines (these guidelines are discussed in NRC's NUREG 2117, "Practical Implementation Guidelines for SSHAC Level 3 and 4 Hazard Studies").
Following a review of the NEI submittal, in a public meeting on February 28, 2013, the staff expressed concern with EPRI's treatment of uncertainty and the level of documentation in the proposed updated GMM. The staff formally documented these concerns by letter dated March 20, 2013.
Subsequently, in a public meeting on March 26, 2013, industry presented a revision of its updated EPRI GMM, which demonstrated significant progress toward addressing the staff's concerns with respect to the treatment of uncertainty. Industry also proposed a schedule, including further interactions with NRC staff, for completing the development and documentation of the updated EPRI GMM. In order to complete its update of the EPRI GMM and accompanying documentation, and to allow time for the development of site-specific seismic hazard curves, industry proposed a 6 month delay from the schedule outlined in the 50.54(f) letter for the submittal of the seismic hazard reevaluations for CEUS plants.
The staff agrees that updated models, methods, and data will provide licensees with the most current information in order to perform the seismic hazard evaluations requested by the 50.54(f) letter.
III. EPRI Guidance The EPRI Guidance document provides licensees with information on the performance of an Expedited Seismic Evaluation Process. The Expedited Seismic Evaluation Process is a screening, evaluation, and equipment modification process to be conducted by licensees to
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provide additional seismic margin and expedite plant safety enhancements while more detailed and comprehensive plant seismic risk evaluations are being performed.
The Expedited Seismic Evaluation Process evaluations would be conducted on plants with a new seismic hazard that exceeds their current seismic design basis, and necessary modifications would be made to certain core and containment cooling components used during the initial plant coping time following a severe external event. The letter states that CEUS licensees will complete non-outage-related Expedited Seismic Evaluation Process equipment modifications by December 2016. Western United States (WUS) licensees will complete non-outage-related Expedited Seismic Evaluation Process equipment modifications by June 2018.
After review of industry's proposed EPRI Guidance, the NRC staff believes that the evaluations and potential near-term equipment modifications associated with the Expedited Seismic Evaluation Process will provide an important demonstration of seismic margin and enhance plant safety while more detailed plant risk evaluations are being conducted by licensees. The staff further concludes that the seismic evaluation guidance for the EPRI Guidance provides an appropriate methodology for licensees to implement and complete the Expedited Seismic Evaluation Process according to the schedule provided in the letter.
IV. Schedule Modifications The NEI has proposed two adjustments to the seismic hazard reevaluations at nuclear power plant sites: (1) to complete the update of the EPRI GMM for the CEUS, and (2) to implement the EPRI Guidance. These proposed changes affect the schedule outlined in the 50.54(f) letter.
First, the industry has requested additional time to complete the updated EPRI GMM project, including documentation and interactions with the NRC staff. The project
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documentation is scheduled to be submitted to the NRC on June 3, 2013. Pending approval by the staff, the CEUS licensees will use the updated model to complete the site-specific seismic hazard reevaluations specified in Enclosure 1 to the SPID guidance. Currently, the hazard submittals are requested by September 2013; however, industry has requested to submit the hazard evaluations by March 31,2014. The industry stated in its letter that it will not delay submittal of items 3.a. "Description of Subsurface Materials and Properties," and 3.b.
"Development of Base Case Profiles and Nonlinear Material Properties" of Section 4 of to the SPI D guidance. Licensees intend to submit these items in September 2013 for the staff's review. This will allow the staff to begin its review in accordance with the original schedule and complete a significant portion of the Section 4 review on time.
The staff finds that the schedule modifications discussed above for CEUS plants are acceptable because the updated GMM will provide the CEUS operating nuclear plant fleet with a model developed using the most recent data and methodologies available for their seismic hazard reevaluations. Additionally, the partial submittal in September 2013 will allow the staff to complete a portion of its CEUS review as originally scheduled by the 50.54(f) letter.
Second, the industry has requested modifications to the 50.54(f) letter schedule to allow for implementation of the EPRI Guidance interim actions for those nuclear power plants where the reevaluated seismic hazard exceeds the plant's design basis. These schedule modifications allow for completion of Expedited Seismic Evaluation Process for CEUS plants by December 2016, if the modifications do not require a plant shutdown to access equipment. For WUS plants, the Expedited Seismic Evaluation Process modifications will be completed by June 2018, if the modifications do not require a plant shutdown to access equipment.
For plants requiring a seismic risk analysis (i.e., those with a reevaluated seismic hazard that exceeds the current seismic design basis), the 50.54(f) letter states that the staff will perform a prioritization for both the CEUS and WUS plants into two priority groups, and possibly
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a third, if needed. Under industry's proposed schedule, the higher priority CEUS plants will complete their risk evaluations by June 2017 (originally scheduled for October 2016). This delay is primarily due to the additional time needed to complete the EPRI GMM update project.
The second group of CEUS plants will complete their risk evaluations by December 2019. This is about a two-year delay from the schedule specified in the 50.54(f) letter for the lower priority plants to complete their risk evaluations. Conversely, the letter proposes an earlier completion date of June 2017 for the risk evaluations for the higher priority WUS plants.
The staff finds that the schedule modifications discussed above for CEUS and WUS nuclear power plants are acceptable, since the Expedited Seismic Evaluation Process provides for near-term seismic evaluations and expedited equipment modifications at the plants that will offer additional assurance that plants will operate safely during a beyond design basis seismic event. Furthermore, the schedule modifications account for limited seismic resources available to both the NRC and the industry. The schedule modifications provide for completion of the higher priority CEUS plant risk evaluations by the end of June 2017, which is not a significant extension of the original 50.54(f) letter schedule of October 2016. In addition, the schedule proposes an earlier completion date for the higher priority risk evaluations for the WUS plants.
V. Basis for Endorsement The NRC staff interacted with the stakeholders on development of the EPRI Guidance report with a focus on guidance on potential interim actions to be implemented for plants where the reevaluated seismic hazard exceeds the current seismic design basis. The EPRI Guidance report is the product of considerable interaction between the NRC, NEI, EPRI, and other
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stakeholders at five public meetings 4 over a 5-month period. These interactions and the insights gained from the meetings allowed for the development of this document in a very short time frame. The meetings helped develop the expectations for how licensees would perform potential interim actions after updating their seismic hazard information. At each meeting, the NRC staff provided its comments on the current version of the EPRI Guidance and discussed with stakeholders subsequent proposed revisions to the document. This iterative process, over several months, resulted in the final version of the document. The NRC staff's endorsement of the EPRI Guidance is based on this cumulative development process resulting from the interactions between stakeholders and the NRC staff. This is the same process employed successfully in the development of the SPID guidance.
The staff has determined that the EPRI Guidance will provide an important demonstration of seismic margin and enhanced plant safety through evaluations and potential near-term modifications of certain core and containment cooling equipment while more comprehensive plant seismic risk evaluations are being performed. The NRC staff also has determined that the schedule modifications provided in the NEI's April 9, 2013, letter are acceptable because the schedule accounts for seismic resource limitations, EPRl's completion of the update to the GMM for the CEUS, and implementation of the EPRI Guidance evaluations and actions.
VI. 8ackfitting and Issue Finality This endorsement letter does not constitute backfitting as defined in 10 CFR 50.109, "Backfitting" (the Back'fit Rule). This endorsement letter provides additional guidance on an
~ ...............
4 Public meetings were held on November 2 and 14 and December 13, 2012; and February 14 and March 26, 2013
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acceptable method for implementing the interim actions described in item (6) of the Requested Information in Enclosure 1, "Recommendation 2.1: Seismic," of the 50.54(f) letter. Licensees and construction permit holders may voluntarily use the guidance in the EPRI Guidance to comply with the requested interim action portion of the 50.54(f) letter. Methods, analyses, or solutions that differ from those described in the EPRI Guidance report may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative is acceptable.
VII. Congressional Review Act This endorsement letter is a rule as designated in the Congressional Review Act (5 U.S.C. 801-808). The Office of Management and Budget has found that this is a major rule in accordance with the Congressional Review Act.
Dated at Rockville, Maryland, this 7~ day of ~ 2013.
For the Nuclear Regulatory cIo'mmission 7
c/~~ 2j Eric J. L~ s, Director Office o(Nuciear Reactor Regulation
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J. Pollock -6 If you or your staff have additional questions, please contact my office; alternatively, you can contact Mrs. Lisa Regner of my staff by phone at 301-415-1906, or bye-mail at Lisa.Regner@nrc.gov.
Sincerely, Ira!
Eric J. Leeds, Director Office of Nuclear Reactor Regulation
Enclosure:
Federal Register Notice cc: See enclosed list Listserv DISTRIBUTION:
See next page ADAMS Accession No.: ML13114A949 (Pkg.); ML13106A331 (Letter); ML13109A594 (FRN1*via e-mail OFFICE LA: NRRIDORL* QTE* PM: NRR/,ILD/PMB NRO/DSEA* DD: NRO/DSEA*
NAME KGoldstein CHsu LRegner CMunson NChokshi DATE 05/01/2013 04/24/2013 04/19/2013 05/02/2013 05/02/2013 OFFICE D: NRRlDE* BC:NRR/JLD/PMB OGC* D: NRR/JLD* D: NRR NAME PHiland MMitcheli GMizuno DSkeen ELeeds DATE 04/29/2013 04/26/2013 05/02/2013 05/03/2013 05/07/2013 OFFICIAL RECORD COpy
Letter to Joseph E. Pollock from Eric J. Leeds dated May 7,2013
SUBJECT:
ELECTRIC POWER RESEARCH INSTITUTE FINAL DRAFT REPORT XXXXXX, "SEISMIC EVALUATION GUIDANCE: AUGMENTED APPROACH FOR THE RESOLUTION OF FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.1: SEISMIC" AS ACCEPTABLE ALTERNATIVE TO THE MARCH 12, 2012, INFORMATION REQUEST FOR SEISMIC REEVALUATIONS DISTRIBUTION:
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