ML14195A097
| ML14195A097 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/16/2014 |
| From: | Michael Balazik Japan Lessons-Learned Division |
| To: | Chris Adner Entergy Nuclear Operations |
| Balazik M, NRR/JLD, 415-2856 | |
| References | |
| Download: ML14195A097 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 16, 2014 Vice President, Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION ASSOCIATED WITH NEAR-TERM TASK FORCE RECOMMENDATION 2.1, SEISMIC HAZARD AND SCREENING REPORT
Dear Sir or Madam:
By letter dated March 31, 2014, to the Nuclear Regulatory Commission (NRC) (Agencywide Documents and Management System (ADAMS) Accession No. ML14090A243}, Entergy Operations, lnc.(Entergy), submitted for NRC review the Entergy Seismic Hazard and Screening Report, "Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident", for the James A. FitzPatrick Nuclear Power Plant (JAF).
The NRC staff has reviewed the information provided for JAF and has determined that additional information is required to complete the review. Enclosed is a request for additional information (RAI) related to the plant's Individual Plant Examination for External Events. As discussed with your staff during a recent phone call, the NRC staff requests that you respond no later than August 15, 2014.
If you have any questions related to the enclosed RAls or the requested submission date, please contact me at 301-415-2856 or via e-mail at Michaei.Balazik@nrc.gov.
Docket No. 50-333
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Sincerely,
~~rojc Hazards Management anch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION NEAR-TERM TASK FORCE RECOMMENDATION 2.1, SEISMIC HAZARD AND SCREENING REPORT ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Part 50 (10 CFR),
Section 50.54(f) (hereafter referred to as the 50.54 (f) letter) (Agencywide Document Access and Management System (ADAMS) Accession No. ML12053A340). The purpose of the request was to gather information concerning, in part, the seismic hazards at operating reactor sites and to enable the NRC staff to determine whether licenses should be modified, suspended, or revoked. To respond to the 50.54(f) letter, Entergy Nuclear Operations, Inc.
(Entergy, the licensee) committed to follow the Electric Power Research Institute (EPRI)
Report, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1:
Seismic," (ADAMS Accession No. ML12333A170) as supplemented by the EPRI Report, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.1: Seismic" (referred to as the Expedited Approach) (ADAMS Accession No. ML13102A142). Entergy submitted the re-evaluated seismic hazards (ADAMS Accession No. ML14090A243) for James A. FitzPatrick Nuclear Power Plant (JAF) in March 2014. The NRC staff conducted the screening and prioritization review of the submittal by assessing Entergy's screening evaluation and hazard analysis utilizing the endorsed SPID guidance. Accordingly, during the NRC screening and prioritization process, the staff identified that a determination could not be made and interactions with Entergy were needed to reach resolution. The staff identified JAF as a "conditional screen-in" for the purposes of prioritizing and conducting additional evaluations.
On May 9, 2014, the NRC staff issued a letter (ADAMS Accession No. ML14111A147) documenting the NRC staff's screening results.
In accordance with the SPID and Expedited Approach guidance, the re-evaluated seismic hazard determines if additional seismic risk evaluations are warranted for a plant. The SPID guidance provides criteria for a plant with ground motion response spectra (GMRS) above the safe shutdown earthquake, but bounded by the Individual Plant Examination for External Events (IPEEE) capacity spectrum. To use the IPEEE capacity spectrum to screen out of conducting a seismic risk evaluation, Entergy needed to demonstrate the adequacy of JAF's IPEEE evaluation by meeting the criteria in the SPID. If the IPEEE capacity is greater than the GMRS in the 1-10Hz range, the plant screens out of conducting a seismic risk.
The following additional information is requested to support the NRC's final screening determination for JAF based on IPEEE adequacy:
Enclosure
- 1. Appendix B of the seismic hazard screening report states that criteria in Table 2-3 from EPRI NP-6041 which is intended for use with structures designed as Seismic Category I structures was applied to the Seismic Category II turbine building as a basis for screening out the turbine building from the seismic margin analysis. Justifications provided for application of EPRI NP-6041 Table 2-3 in this manner include the use of lower damping values and other constraints used in the Operating Basis Earthquake (OBE) analysis of the turbine building.
- a. In the IPEEE, EPRI NP-6041 screening criteria intended for Seismic Category I structures was applied to the Seismic Category II turbine building. The turbine building, as a Seismic Category II structure, could have been designed using local building codes. The seismic performance of buildings designed using local building codes may differ significantly compared to buildings designed in accordance with NRC guidance for Seismic Category I structures. Due to these potential differences, similar design peak ground acceleration is not considered a sufficient justification for screening. Provide additional explanation to justify the application of the EPRI NP-6041 screening criteria intended for Seismic Category I structures as applied to the Seismic Category II turbine building.
- b. It is unclear in Appendix B what is meant by "constraints" used in the OBE analysis. Provide additional clarification and explanation on what is meant by constraints used in the OBE analysis and how that affects the design of the turbine building.
- c.
The damping value used in the OBE analysis was not clearly indicated. Describe what was the damping value used in the OBE analysis and why is it appropriate for your site.
- 2. The submitted IPEEE high confidence of a low probability of failure (HCLPF) Spectrum (IHS) is anchored to a peak ground acceleration of 0.22g. The anchor of 0.22g is dependent on block wall HCLPF values. Appendix B of the seismic hazard screening report notes that EPRI NP-6041 guidance was not followed exactly in the assessment of the HCLPF of the block walls in the IPEEE seismic margin assessment. Provide a description and basis of the reassessment of the HCLPF for the modified block walls that resulted in increasing the plant HCLPF to 0.22g. Specifically, did you deviate from the EPRI NP-6041 guidance in the development of the fragilities? And, if so, describe the implications of the deviations from that guidance.
- 3. Section 3.3 of Appendix B of the seismic hazard screening report states that "the full scope detailed review of relay chatter required in SPID (EPRI, 2013a) Section 3.3.1 has not been completed. The results of the review will be provided in a future submittal."
However, Section 4.2, High Frequency Screening (> 10 Hz), states that "above 10 Hz, the IHS exceeds the ground motion response spectra. Therefore, a High Frequency Confirmation will not be performed." Clarify this apparent contradiction as to whether they are the same or different reports and to confirm that a review of relay chatter will be submitted as stated in Section 3.3.
- concurrence via e-mail OFFICE NRR/JLD/JHMB/PM NRR/DORULPL 1-1/PM NRR/JLD/JHMB/LA NRR/JLD/JHMB/BC NAME MBalazik DPickett*
Slent SWhaley DATE 07/14/14 07/16/14 07/14/14 07/16/14