RA-20-0088, Supplement to H.B Robinson Steam Electric Plant, Unit No. 2, Seismic Probabilistic Risk Assessment (SPRA) Submittal Enclosure Update - Public - Redacted
| ML20094K843 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/31/2020 |
| From: | Kapopoulos E Duke Energy Corp |
| To: | Office of Nuclear Reactor Regulation |
| Valentin-Olmeda M | |
| References | |
| RA-20-0088 | |
| Download: ML20094K843 (8) | |
Text
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE Ernest J. Kapopoulos, Jr.
H. B. Roanson Steam Electric Plant Unit 2
( ~ DUKE Site Vice President
~ ENERGY. Duke Energy 3581 West Entrance Road HartsviUe, SC 29550 o: 843.951.1701
- t. 843.951.1319 Emie.Kapopoulos@duke-energy.com Serial: RA-20-0088 10 CFR 50.4 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 H. B. Robinson Steam Electric Plant, Unit No. 2 Docket Number 50-261 Renewed Facility Operating License No. OPR-23
Subject:
Supplement to H.B. Robinson Steam Electric Plant, Unit No. 2, Seismic Probabilistic Risk Assessment (SPRA) Submittal - Enclosure Update
Reference:
Duke Energy Letter, H.B. Robinson Steam Electric Plant, Unit No. 2 - Seismic Probabilistic Risk Assessment (SPRA), Response to March 12, 2012, Request for Infonnation Regarding Recommendation 2. 1: Seismic, of the Near-Tenn Task Force Related to the Fukushima Dai-ichi Nuclear Power Plant Accident, dated December 12, 2019 Ladies and Gentlemen:
In a letter dated December 12, 2019 (i.e., Reference), Duke Energy Progress, LLC (Duke Energy), provided the seismic probabilistic risk assessment (SPRA) associated with the seismic hazard reevaluation for H. B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP).
The purpose of this submittal is to provide updated information to two tables included in the enclosure to the above submittal. The errors were administrative in nature, and do not affect the final SPRA results. Enclosure 1 to this letter contains the marked-up pages, and Endosure 2 contains the typed pages incorporating the corrections. The two pages provided are the only affected pages and serve as replacement pages to the same two pages in the referenced submittal.
There are no regulatory commitments associated with this letter.
Please address any comments or questions regarding this matter to Mr. Art Zaremba, Director - Nuclear Fleet Licensing, at (980) 373-2062.
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE U.S. Nudear Regulatory Commission Serial: RA-20-0088 Page 2 of 2 I declare, under penalty of perjury, that the foregoing is true and correct.
Executed on S [ M~ H , 2020.
Ernest J. Kapopoulos, Jr.
Site Vice President Endosures:
- 1. Revised Pages for Table 5.4-2 and Table 5.5-2 (Mark-Up)
- 2. Revised Pages for Table 5.4-2 and Table 5.5-2 (Typed) cc: L. Dudes, USNRC Regional Administrator, Region II M. Fannon, USNRC Sr. Resident Inspector - HBRSEP A. Hon, USNRC NRR Project Manager - HBRSEP OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEII - DO NOT RELEASE Enclosure 1 Revised Pages for Table 5.4-2 and Table 5.5-2 (Mark-Up)
(Total of 2 pages)
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE H. 8 . ROBINSON SEISMIC PROBABILISTIC RISK AsSESSMENT
SUMMARY
REPORT Table 5.4-2: Too 10 SCDF lmoortance Measures Ranked bv FV - Seismic Failures Median Fragility Component Description FV l3r l3u Failure Mode 2 Caoacltv tal Method2 Turbine Building RAB pounding induced cracking and SF-TB-CLASS POUND Class 3 - Pounding- 43.71% 0.28 0.13 0.25 splitting of the mezzanine floor slab sov induced cracking resulting in loss of structural integrity.
Failure of E DG-B pipe at RAB penetration.
Probability of failure at PGA:
SF-TK-DG-FOSTRG- DFOST Liquefaction-TNK_SETTLE Induced Settlement 12.57% NIA1 NIA NIA PGA(g) - Probability sov 0.265g - 0.388 0.325g - 0.569 0.582g - 0.887 0.7179- 0.966 Turbine Building SF-TB_C RANE Gantry Crane 11 .81% 0.29 0.21 0.24 Failure of A-frame anchor bolts sov Failure of AFW discharge piping where the 4 in. diameter pipe meets the 6x4 reducing elbow.
SF-TP-SDAFW- SDAFW Liquefaction- Probability of failure at PGA:
PMP_SETTLE Induced Settlement 7.01% NIA 1 NIA NIA PGA(g) - Probability sov 0.265g - 0.168 0.325g - 0.263 0.582g - 0.609 0.7179- 0.708
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OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE Page 59 of 198
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE H. B. ROBINSON SEISMIC PROBABILISTIC RISK AsSESSMENT
SUMMARY
REPORT Table 5.5-2: Top 10 SLERF Importance Measures Ranked by FV - Seismic Failures Median Fraglllty Component Description FV r ........,._, tn\ Pr Poi Failure Mode 2 Method2
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Failure of AFW discharge piping where the 4 in. diameter pipe meets the 6x4 reducing elbow.
SDAFW SF-TP-SDAFW- Probability of failure at PGA PMP_SETTLE Liquefaction- 4.19% NIA1 NIA NIA PGA(g) - Probability sov Induced Settlement 0.265g - 0.168 0.325g - 0.263 0.582g - 0.609 0.717g - 0.708 Reactor Auxiliary SF-RAB 2.74% 1.12 0.24 0.26 Flexural failure of piles. Rep.
Buildina Liquefaction-induced settlement failure at Intake Structure.
Underground Cable Probability of failure at PGA:
SF-TR-UG- Trays at Intake 2.45% NIA 1 NIA NIA PGA(g) - Probability Rep.
INTAKE_SETTLE Liquefaction-Induced Settlement 0.265g - 0.110 0.3259- 0.180 0.582g - 0.450 0.717g - 0.570 Page 74 of 198 OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEII - DO NOT RELEASE Enclosure 2 Revised Pages for Table 5.4-2 and Table 5.5-2 (Typed)
(Total of 2 pages)
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE H. 8. ROBINSON SEISMIC PROBABILISTIC RISK ASSESSMENT
SUMMARY
REPORT Table 5.4-2: Top 10 SCDF Importance Measures Ranked by FV - Seismic Failures Median Fraglllty Component Description FV Caoacltv la\ Pr Pu Failure Mode2 Method2 Turbine Building RAB pounding induced cracking and SF-TB-CLASS POUND Class 3 - Pounding- 43.71% 0.28 0.13 0.25 splitting of the mezzanine floor slab sov induced cracking resulting in loss of structural integrity.
Failure of EDG-B pipe at RAB penetration.
Probability of failure at PGA SF-TK-OG-FOSTRG- D FOST Liquefaction-TNK_SETTLE Induced Settlement 12.57% NIA 1 NIA NIA PGA(g) - Probability sov 0.265g - 0.388 0.325g - 0.569 0.582g - 0.887 0.717g - 0.966 Turbine Building SF-TB_CRANE Gantry Crane 11 .81% 0.29 0.21 0.24 Failure of A-frame anchor bolts sov Failure of AFW discharge piping where the 4 in. diameter pipe meets the 6x4 reducing elbow.
SF-TP-SDAFW- SDAFW Liquefaction- Probability of failure at PGA:
PMP_SETTLE Induced Settlement 7.01% NIA 1 NIA NIA PGA(g) - Probability sov 0.2659- 0.168 0.325g - 0.263 0.582g - 0.609 0.717g - 0.708
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Il Page 59 of 198 OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE
OFFICIAL USE ONLY-SECURITY RELATED INFORMATION CEIi - DO NOT RELEASE H. 8 . ROBINSON SEISMIC PROBABILISTIC RISK ASSESSMENT
SUMMARY
REPORT Table 5.5-2: Top 10 SLERF Importance Measures Ranked by FV - Seismic Failures Median Fraglllty Component Description FV 13r 13u Failure Mode 2 Canacltv ta\ Method2
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Failure of AFW discharge piping where the 4 in. diameter pipe meets the 6x4 reducing elbow.
SDAFW SF-TP-SDAFW- Probability of failure at PGA:
Liquefaction- 4 .19% NIA 1 NIA NIA sov PMP_SETILE PGA(g) - Probability Induced Setuement 0.265g - 0.168 0.325g - 0.263 0.582g - 0.609 0.717g - 0.708 Reactor Auxiliary SF-RAB 2.74% 1.12 0.24 0.26 Flexural failure of piles. Rep.
Building Liquefaction-induced setuement failure at Intake Structure.
Underground Cable Probability of failure at PGA:
SF-TR-UG- Trays at Intake 2.45% NIA1 NIA NIA PGA(g) - Probability Rep.
INTAKE_SETILE liquefaction-Induced Settlement 0.26Sg - 0.110 0.325g - 0.180 0.582g - 0.450 0.717g - 0.570 OFFICIAL USE ONLY-SECURITY RELATED INFORMATION Page 74 of 198 CEIi - DO NOT RELEASE