ML19233A003
| ML19233A003 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/14/2019 |
| From: | Robert Kuntz Plant Licensing Branch III |
| To: | Kivi J Northern States Power Company, Minnesota |
| References | |
| L-2019-LLR-0055 | |
| Download: ML19233A003 (3) | |
Text
1 NRR-DRMAPEm Resource From:
Kuntz, Robert Sent:
Wednesday, August 14, 2019 9:45 AM To:
Kivi, Jeffrey L.
Cc:
Scott, Sara
Subject:
Request for Additional Information RE: Prairie Island Relief Requests 1-RR-10 and 2-RR-10 By letter dated June 13, 2019 (Agencywide Document Access and Management System (ADAMS) Accession No. ML19164A166), Northern States Power Company (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Table IWB-2500-1 for Category B-A and B-D examinations for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2 reactor pressure vessel (RPV) welds and nozzle welds.
The NRC staff has determined that additional information is required to complete its review. The following is a draft request for additional information (RAI). If clarification on the following draft RAI is required contact me to set up a teleconference. If no clarification is required this draft RAI will be considered an RAI and the NRC will expect a response within 30 days of this e-mail.
Robert Kuntz Senior Project Manager (Monticello and Prairie Island)
NRC/NRR/DORL/LPL3 (301)415-3733 DRAFT REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVE REQUESTS 1-RR-5-10 AND 2-RR-5-10 REGARDING FIFTH AND SIXTH TEN-YEAR INSERVICE INSPECTION PROGRAM INTERVALS NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NUMBERS 50-282 AND 50-306 EPID: L-2019-LLR-0055 By letter dated June 13, 2019 (Agencywide Document Access and Management System (ADAMS) Accession No. ML19164A166), Northern States Power Company (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Table IWB-2500-1 for Category B-A and B-D examinations for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2 reactor pressure vessel (RPV) welds and nozzle welds.
2 Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative to extend the fifth inservice inspection (ISI) interval at PINGP for Category B-A and B-D examinations so that the fifth ASME Code required examination can be performed in the current sixth ISI interval in 2033 and 2034 respectively on the basis that the alternative provides an acceptable level of quality and safety. The NRC staff reviewed the submittal and needs additional information to complete the review.
RAI-1
Tables 2 and 3 in Title 10 of Code of Federal Regulations Part 50.61a, Alternative fracture toughness requirements for protection against pressurized thermal shock events list maximum number of flaws depthwise for welds and plates (or forgings) of a generic RPV. However, Tables 2a and 2b of Alternative Requests 1-RR-5-10 and 2-RR-5-10 show different maximum number of weld and forging flaws for the PINGP, Units 1 and 2 RPV beltline, considering plant-specific RPV geometries. Please explain the differences and the manner in which the values in Tables 2a and 2b were derived (scaled).
Hearing Identifier:
NRR_DRMA Email Number:
186 Mail Envelope Properties (BYAPR09MB36561A1290DC9D7E5223464799AD0)
Subject:
Request for Additional Information RE: Prairie Island Relief Requests 1-RR-10 and 2-RR-10 Sent Date:
8/14/2019 9:44:56 AM Received Date:
8/14/2019 9:44:00 AM From:
Kuntz, Robert Created By:
Robert.Kuntz@nrc.gov Recipients:
"Scott, Sara" <Sara.Scott@xenuclear.com>
Tracking Status: None "Kivi, Jeffrey L." <Jeffrey.Kivi@xenuclear.com>
Tracking Status: None Post Office:
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