ML17026A001
| ML17026A001 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/30/2017 |
| From: | Steve Wyman Japan Lessons-Learned Division |
| To: | Sena P Public Service Enterprise Group |
| Wyman S, NRR/JLD 415-3041 | |
| References | |
| Download: ML17026A001 (4) | |
Text
Mr. Peter P. Sena, Ill President and Chief Nuclear Officer PSEG Nuclear LLC-N09 P.O. Box 236 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 30, 2017 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION-STAFF REVIEW OF MITIGATION STRATEGIES ASSESSMENT REPORT OF THE IMPACT OF THE REEVALUATED SEISMIC HAZARD DEVELOPED IN RESPONSE TO THE MARCH 12, 2012, 50.54(f) LETTER
Dear Mr. Sena:
The purpose of this letter is to provide the U.S. Nuclear Regulatory Commission's (NRC) assessment of the seismic hazard mitigation strategies assessment (MSA), as described in the December 12, 2016, letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16348A305), submitted by PSEG Nuclear LLC (PSEG, the licensee) for Hope Creek Generating Station (Hope Creek). The mitigation strategies assessment confirms that the licensee has adequately addressed the reevaluated seismic hazard within its mitigating strategies for beyond-design-basis external events.
BACKGROUND By letter dated March 12, 2012 (ADAMS Accession No. ML12053A340), the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The 50.54(f) letter was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested licensees reevaluate the seismic hazard using present-day methodologies and guidance. Concurrent with the reevaluation of seismic hazards, the NRC issued Order EA-12-049, "Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML12054A736). The order requires holders of operating power reactor licenses and construction permits issued under 10 CFR Part 50 to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling following a beyond-design-basis external event.
By "LR-N14-0035, PSEG Nuclear LLCs Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to [[CFR" contains a listed "[" character as part of the property label and has therefore been classified as invalid.)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.|letter dated March 28, 2014]] (ADAMS Accession No. ML14087A436), the licensee provided its reevaluated seismic hazard for Hope Creek in response to the 50.54(f) letter.
On December 10, 2015 (ADAMS Accession No. ML16005A621), the Nuclear Energy Institute (NEI) submitted Revision 2 to NEI 12-06, including guidance for conducting MSAs using the
P.Sena reevaluated hazard information. The NRG subsequently endorsed NEI 12-06, Revision 2, with exceptions, clarifications, and additions, in Japan Lessons-Learned Division (JLD) interim staff guidance (ISG) JLD-ISG-2012-01, Revision 1, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML15357A163).
MITIGATION STRATEGIES ASSESSMENT By letter dated February 29, 2016 (ADAMS Accession No. ML16049A609), the NRG staff documented its review of the licensee's reevaluated seismic hazard, also referred to as the mitigating strategies seismic hazard information. The staff confirmed the licensee's conclusion that its reevaluated seismic hazard is bounded by the safe shutdown earthquake (SSE) in the frequency ranges of 1 to 30 Hertz (Hz) and 40 to 100 Hz, but exceeds the SSE between 30 and 40 Hz, meriting a high frequency confirmation. In addition, the staff concluded that the Ground Motion Response Spectrum (GMRS) determined by the licensee adequately characterizes the reevaluated seismic hazard for the Hope Creek site.
By letter dated December 23, 2015 (ADAMS Accession No. ML15358A138), PSEG submitted a High Frequency Confirmation Report for Hope Creek. By letter dated February 18, 2016 (ADAMS Accession No. ML15364A544), the NRG staff confirmed the Hope Creek GMRS exceedance above the current design-basis is on the order of 1 O percent or less of the area under the SSE curve over the frequency range of exceedance and met the criterion described in Section 3.1.2, "Limited High Frequency Exceedance Screening," in Electric Power Research Institute (EPRI) Report 3002004396. The EPRI report concluded, and the staff agreed, that these types of minor exceedances over limited frequency ranges do not represent a significant high frequency concern. Therefore, the methodology used by the licensee is appropriate to disposition the GMRS exceedance above the current design-basis.
The licensee stated that the Hope Creek MSA was performed consistent with NEI 12-06, Revision 2. Appendix H of NEI 12-06, Revision 2, describes acceptable methods for demonstrating that the reevaluated seismic hazard is addressed within the Hope Creek mitigation strategies for beyond-design-basis external events. The NRC staff confirmed that the licensee's seismic hazard MSA is consistent with the guidance in Appendix H.4.2 of NEI 12-06, Revision 2, as endorsed, by JLD-ISG-2012-01, Revision 1. Therefore, the methodology used by the licensee is appropriate to perform an assessment of the mitigation strategies that addresses the reevaluated seismic hazard.
The NRC staff has reviewed the seismic hazard MSA for Hope Creek. The NRC staff concludes that sufficient information has been provided to demonstrate that the licensee's plans for the development and implementation of guidance and strategies under Order EA-12-049 appropriately address the reevaluated seismic hazard information stemming from the 50.54(f) letter.
P.Sena If you have any questions, please contact me at (301) 415-3041 or via e-mail at Stephen.Wyman@nrc.gov.
Sincerely,
,/
Stephen Wyman, B oject Manager Hazards Mana ent Branch Japan Lesson earned Division Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Distribution via Listserv
ML17026A001 OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NAME SWyman SLent DATE 1/25/17 1/26/17 SWyman, NRR BTitus, NRR EBowman, NRR GBowman, NRR NRR/JLD/JHMB/BC GBowman 1/26/17