RA-21-0269, Response to Request for Additional Information Regarding Alternative Request to Utilize American Society of Mechanical Engineers (ASME) Code Case OMN-28

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Response to Request for Additional Information Regarding Alternative Request to Utilize American Society of Mechanical Engineers (ASME) Code Case OMN-28
ML21313A028
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 11/09/2021
From: Snider S
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-21-0269
Download: ML21313A028 (14)


Text

Steven M. Snider Vice President Oconee Nuclear Station Duke Energy ON01VP l 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3478 f: 864.873.4208 Steve.Snider@duke-energy.com Serial: RA-21-0269 10 CFR 50.55a November 9, 2021 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 OCONEE NUCLEAR STATION, UNIT NOS. 1, 2 AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 / RENEWED LICENSE NOS. DPR-38, DPR-47, AND DPR-55

SUBJECT:

Response to Request for Additional Information Regarding Alternative Request to Utilize American Society of Mechanical Engineers (ASME) Code Case OMN-28.

REFERENCES:

1. Duke Energy letter, Supplement to Relief Requests for Inservice Testing Plan - Sixth Interval, dated August 19, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21231A069)
2. NRC email, Oconee Nuclear Station, Units 1, 2, and 3 - Request for Additional Information RE: Alternative Request (ON-RPI-OMN-28) to use Code Case OMN-28 (EPID: L-2021-LLR-0054), dated September 30, 2021 (ADAMS Accession No. ML21273A049)

Ladies and Gentlemen:

By letter dated August 19, 2021 (Reference 1), Duke Energy Carolinas, LLC (Duke Energy) submitted alternative request ON-RPI-OMN-28 to the U.S. Nuclear Regulatory Commission (NRC). Specifically, Duke Energy requested NRC approval to utilize Code Case OMN-28 of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants (OM) Code, 2017 Edition for valves that fall under the appropriate category in the upcoming sixth ten-year Inservice Testing (IST) program interval for Oconee Nuclear Station (ONS), Units 1, 2, and 3.

By email dated September 30, 2021 (Reference 2) the NRC requested additional information to complete its review of alternative request ON-RPI-OMN-28. Enclosure 1 to this letter provides Duke Energys response to the request for additional information (RAI).

U.S. Nuclear Regulatory Commission RA-21-0269 Page 2 No new regulatory commitments have been made in this submittal. If you have additional questions, please contact Mr. Lee Grzeck, Manager (Acting) - Regulatory Affairs, at 980-373-1530.

Sincerely, Steven M. Snider Site Vice President Oconee Nuclear Station

Enclosures:

1. Response to Request for Additional Information cc:

L. Dudes, Regional Administrator USNRC Region II J. Nadel, USNRC Senior Resident Inspector - ONS S. A Williams, NRR Project Manager - ONS RA-21-0269 Page 1 Enclosure 1 Response to Request for Additional Information

U.S. Nuclear Regulatory Commission RA-21-0269 Page 2 NRC Request for Additional Information By a letter dated July 29, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21210A341), as supplemented by a letter dated August 19, 2021 (ADAMS Accession No. ML21231A069), Duke Energy Carolinas, LLC (Duke Energy, the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) Alternative Request ON-RPI-OMN-28 regarding certain inservice testing (IST) requirements of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, OM Code: Section IST (OM Code) for the IST Programs at Oconee Nuclear Stations, Units 1, 2, and 3 (Oconee) associated with the Sixth 10-Year IST Program interval.

Specifically, pursuant to subparagraph (1) in paragraph (z), Alternatives to codes and standards requirements, of Section 55a, Codes and standards, in Part 50, Domestic Licensing of Production and Utilization Facilities, in Title 10, Energy, of the Code of Federal Regulations (10 CFR 50.55a(z)(1)), the licensee requested to implement ASME OM Code Case OMN-28, Alternative Valve Position Verification Approach to Satisfy ISTC3700 for Valves Not Susceptible to StemDisk Separation, for certain valves at Oconee on the basis that the alternative provides an acceptable level of quality and safety.

The U.S. Nuclear Regulatory Commission staff has determined that additional information is needed as provided below. A clarification call to ensure mutual understanding was conducted on September 16, 2021.

Please respond within 45 days of the date of this e-mail.

RAI No. 1 Alternative Request ON-RPI-OMN-28 proposes that specific valves at Oconee deviate from the position verification requirements (referred to as PI requirements) of the ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants, Subsection ISTC, paragraph ISTC-3700, Position Verification Testing. Please provide the list of valves that is within the scope of Alternative Request ON-RPI-OMN-28. This information may be provided by submittal of the Sixth 10-Year IST Program Plan for Oconee, or by submittal of separate listing of valves with PI requirements for the Sixth 10-Year IST Program interval.

Duke Energy Response The tables below provide the list of valves that are within the scope of Alternative Request ON-RPI-OMN-28.

U.S. Nuclear Regulatory Commission RA-21-0269 Page 3 BS, BUILDING SPRAY (All Units)

Component ID 1BS-1 1BS-2 1BS-3 1BS-4 2BS-1 2BS-2 2BS-3 2BS-4 3BS-1 3BS-2 3BS-3 3BS-4 C, CONDENSATE (All Units)

Component ID 1C-156 1C-158 1C-160 1C-391 1C-903 1C-904 1C-906 1C-907 2C-156 2C-158 2C-160 2C-391 2C-903 2C-904 2C-906 2C-907 3C-156 3C-158 3C-160 3C-391 3C-903 3C-904 3C-906 3C-907

U.S. Nuclear Regulatory Commission RA-21-0269 Page 4 CF, CORE FLOOD SYSTEM (All Units)

Component ID 1CF-1 1CF-2 1CF-3 1CF-4 1CF-5 1CF-6 2CF-1 2CF-2 2CF-3 2CF-4 2CF-5 2CF-6 3CF-1 3CF-2 3CF-3 3CF-4 3CF-5 3CF-6 ESV, ESSENTIAL SIPHON VACUUM (All Units)

Component ID 1ESV-28 1ESV-29 2ESV-28 2ESV-29 3ESV-28 3ESV-29 FDW, FEEDWATER (Unit 1)

Component ID 1FDW-32 1FDW-35 1FDW-41 1FDW-44 1FDW-103 1FDW-104 1FDW-106 1FDW-108 1FDW-315 1FDW-316 1FDW-347 1FDW-368 1FDW-369 1FDW-372 1FDW-382

U.S. Nuclear Regulatory Commission RA-21-0269 Page 5 FDW, FEEDWATER (Unit 2)

Component ID 2FDW-32 2FDW-35 2FDW-41 2FDW-44 2FDW-103 2FDW-104 2FDW-106 2FDW-108 2FDW-315 2FDW-316 2FDW-347 2FDW-368 2FDW-369 2FDW-372 2FDW-382 FDW, FEEDWATER (Unit 3)

Component ID 3FDW-32 3FDW-35 3FDW-41 3FDW-44 3FDW-103 3FDW-104 3FDW-106 3FDW-108 3FDW-315 3FDW-316 3FDW-347 3FDW-368 3FDW-369 3FDW-372 3FDW-382 GWD, GASEOUS WASTE DISPOSAL (All Units)

Component ID 1GWD-17 2GWD-17 3GWD-17

U.S. Nuclear Regulatory Commission RA-21-0269 Page 6 HPI, HIGH PRESSURE INJECTION (Unit 1)

Component ID 1HP-23 1HP-24 1HP-25 1HP-26 1HP-27 1HP-98 1HP-115 1HP-139 1HP-140 1HP-398 1HP-409 1HP-410 1HP-939 1HP-940 HPI, HIGH PRESSURE INJECTION (Unit 2)

Component ID 2HP-23 2HP-24 2HP-25 2HP-26 2HP-27 2HP-98 2HP-115 2HP-139 2HP-140 2HP-398 2HP-409 2HP-410 2HP-939 2HP-940 HPI, HIGH PRESSURE INJECTION (Unit 3)

Component ID 3HP-23 3HP-24 3HP-25 3HP-26 3HP-27 3HP-98 3HP-115 3HP-139 3HP-140 3HP-398 3HP-409

U.S. Nuclear Regulatory Commission RA-21-0269 Page 7 3HP-410 3HP-939 3HP-940 LPI, LOW PRESSURE INJECTION (Unit 1)

Component ID 1LP-1 1LP-2 1LP-3 1LP-5 1LP-6 1LP-7 1LP-8 1LP-9 1LP-10 1LP-11 1LP-12 1LP-13 1LP-14 1LP-15 1LP-16 1LP-17 1LP-18 1LP-19 1LP-20 1LP-21 1LP-22 1LP-69 1LP-103 1LP-104 1LP-105 LPI, LOW PRESSURE INJECTION (Unit 2)

Component ID 2LP-1 2LP-2 2LP-3 2LP-5 2LP-6 2LP-7 2LP-8 2LP-9 2LP-10 2LP-11 2LP-12 2LP-13 2LP-14 2LP-15

U.S. Nuclear Regulatory Commission RA-21-0269 Page 8 2LP-16 2LP-17 2LP-18 2LP-19 2LP-20 2LP-21 2LP-22 2LP-69 2LP-103 2LP-104 LPI, LOW PRESSURE INJECTION (Unit 3)

Component ID 3LP-1 3LP-2 3LP-3 3LP-5 3LP-6 3LP-7 3LP-8 3LP-9 3LP-10 3LP-12 3LP-14 3LP-15 3LP-16 3LP-17 3LP-18 3LP-19 3LP-20 3LP-21 3LP-22 3LP-92 3LP-93 3LP-103 3LP-104 LPSW, LOW PRESSURE SERVICE WATER (Unit 0, Unit 1)

Component ID LPSW-1 LPSW-2 LPSW-3 1LPSW-4 1LPSW-5 1LPSW-6 1LPSW-15 1LPSW-16 1LPSW-18

U.S. Nuclear Regulatory Commission RA-21-0269 Page 9 1LPSW-19 1LPSW-21 1LPSW-22 1LPSW-24 1LPSW-139 1LPSW-1121 1LPSW-1122 1LPSW-1123 1LPSW-1124 1LPSW-1150 1LPSW-1151 LPSW, LOW PRESSURE SERVICE WATER (Unit 2)

Component ID 2LPSW-4 2LPSW-5 2LPSW-6 2LPSW-15 2LPSW-16 2LPSW-18 2LPSW-19 2LPSW-21 2LPSW-22 2LPSW-24 2LPSW-139 2LPSW-1121 2LPSW-1122 2LPSW-1123 2LPSW-1124 2LPSW-1150 2LPSW-1151 LPSW, LOW PRESSURE SERVICE WATER (Unit 3)

Component ID 3LPSW-4 3LPSW-5 3LPSW-6 3LPSW-15 3LPSW-16 3LPSW-18 3LPSW-19 3LPSW-21 3LPSW-22 3LPSW-24 3LPSW-120 3LPSW-123 3LPSW-139 3LPSW-1121

U.S. Nuclear Regulatory Commission RA-21-0269 Page 10 3LPSW-1122 3LPSW-1123 3LPSW-1124 3LPSW-1150 3LPSW-1151 MS, MAIN STEAM (Unit 1)

Component ID 1MS-17 1MS-24 1MS-26 1MS-33 1MS-35 1MS-36 1MS-76 1MS-79 1MS-82 1MS-84 1MS-93 1MS-102 1MS-103 1MS-104 1MS-105 MS, MAIN STEAM (Unit 2)

Component ID 2MS-17 2MS-24 2MS-26 2MS-33 2MS-35 2MS-36 2MS-76 2MS-79 2MS-82 2MS-84 2MS-93 2MS-102 2MS-103 2MS-104 2MS-105

U.S. Nuclear Regulatory Commission RA-21-0269 Page 11 MS, MAIN STEAM (Unit 3)

Component ID 3MS-17 3MS-24 3MS-26 3MS-33 3MS-35 3MS-36 3MS-76 3MS-79 3MS-82 3MS-84 3MS-93 3MS-102 3MS-103 3MS-104 3MS-105 PSW, PROTECTED SERVICE WATER (Unit 1, 2, 3)

Component ID PSW-14 1PSW-22 1PSW-23 1PSW-24 1PSW-25 1PSW-6 2PSW-22 2PSW-23 2PSW-24 2PSW-25 2PSW-6 3PSW-22 3PSW-23 3PSW-24 3PSW-25 3PSW-6 RCS, REACTOR COOLANT SYSTEM (Unit 1, 2, 3)

Component ID 1RC-1 1RC-4 1RC-155 1RC-156 1RC-157 1RC-158 1RC-159 1RC-160

U.S. Nuclear Regulatory Commission RA-21-0269 Page 12 1RC-162 1RC-163 2RC-1 2RC-4 2RC-155 2RC-156 2RC-157 2RC-158 2RC-159 2RC-160 2RC-162 2RC-163 3RC-1 3RC-4 3RC-155 3RC-156 3RC-157 3RC-158 3RC-159 3RC-160 3RC-162 3RC-163 SF, SPENT FUEL SYSTEM (Units 1, 2, 3)

Component ID SF-166 SF-167 3SF-166 3SF-167 SSW, SIPHON SEALING WATER (Units 1, 2, 3)

Component ID 1SSW-155 1SSW-156 1SSW-157 2SSW-155 2SSW-156 2SSW-157 3SSW-155 3SSW-156 3SSW-157 WL, TURBINE GENE COOLING WATER (Units 1, 2, 3)

Component ID K1WL-11 K2WL-11