ML20083F617
| ML20083F617 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/06/2020 |
| From: | Andrew Hon Plant Licensing Branch II |
| To: | Catherine Nolan Duke Energy Corp |
| Buckberg P | |
| References | |
| EPID L-2020-LLL-0000 | |
| Download: ML20083F617 (5) | |
Text
April 6, 2020 Mr. Christopher Nolan, Vice President Nuclear Regulatory Affairs, Policy &
Emergency Preparedness Duke Energy, LLC 526 South Church Street, EC-07C Charlotte, NC 28202
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 - CORRECTION TO AMENDMENT NO. 266 REGARDING ADOPTION OF 10 CFR 50.69, "RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS, AND COMPONENTS FOR NUCLEAR POWER REACTORS" (EPID L-2020-LLL-0000)
Dear Mr. Nolan:
On September 24, 2019, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 266 to Renewed Facility Operating License (RFOL) No. DPR-23 for the H. B. Robinson Steam Electric Plant, Unit No. 2 (Robinson) (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19205A289). The amendment adds a new license condition to the renewed facility operating license to permit the implementation of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.69, "Risk informed categorization and treatment of structures, systems and components for nuclear power reactors."
By letter dated January 21, 2020 (ADAMS Accession No. ML20021A136), Duke Energy Progress, LLC (the licensee) requested NRC approval of a correction to an error in Appendix B of RFOL DPR-23 that was introduced when Amendment No. 266 was issued. The erroneous text in Appendix B of RFOL DPR-23 implies that probabilistic risk assessment models are used to assess risk from high winds and external flood although screening using the individual plant examination of external events was actually used to assess risk from high winds and external flood. The licensee stated that the error had been inadvertently introduced during the processing of Amendment No. 266 and was neither addressed in the notice to the public nor reviewed by the NRC. Thus, the licensee stated that the typographical error falls within the scope of the guidance provided by SECY-96-238, Proposed Guidance for Correction of Technical Specification Typographical Errors, dated November 19, 1996 (Legacy ADAMS Accession No. 9611250030).
The NRC staff has confirmed that Amendment No. 266 for Robinson contained the error in Appendix B of RFOL DPR-23 as described above. Further, the NRC staff has determined that this error was inadvertently introduced and was not the subject of the amendment or the associated notice to the public. Therefore, consistent with NRC staff guidance dated
January 16, 1997 (ADAMS Accession No. ML103260096), based on the NRC's policy established by SECY-96-238, this error can be corrected by a letter to the licensee from the NRC staff.
Enclosed, please find the corrected Robinson RFOL page 2. This correction does not change any of the conclusions in the safety evaluation associated with Amendment No. 266.
If you have any questions regarding this matter, please contact me at (301) 415-8480 or by email at andrew.hon@nrc.gov.
Sincerely,
/RA/
Andrew Hon, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosure:
As stated cc: Listserv
Enclosure
APPENDIX B ADDITIONAL CONDITIONS HBRSEP, Unit No. 2 2
Amendment No. 266 date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.
(b)
The first performance of the periodic assessment of CRE habitability, TS 5.5.17.c.(ii), shall be within the next 9 months.
(c)
The first performance of the periodic measurement of CRE pressure, TS 5.5.17.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test.
266 Duke Energy is approved to implement 10 CFR 50.69 using the processes for categorization of Risk Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using: Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and internal fire; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2 and Class 3 SSCs and their associated supports; and the results of non PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards, i.e., seismic margin analysis (SMA) to evaluate seismic risk, and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009; as specified in Unit 2 License Amendment No. 266 dated September 24, 2019.
Upon implementation of Amendment No. 266.
ML20083F617 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC(A)
NAME PBuckberg BAbeywickrama UShoop DATE 03/24/2020 03/23/2020 03/31/2020 OFFICE NRR/DORL/LPL2-2/PM NAME AHon DATE 04/06/2020