ML14356A073
| ML14356A073 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/18/2014 |
| From: | Scott Wall Plant Licensing Branch III |
| To: | James Anderson, Vincent D Northern States Power Co |
| Wall S | |
| References | |
| TAC MF4839, TAC MF4840 | |
| Download: ML14356A073 (3) | |
Text
1 NRR-PMDA-ECapture Resource From:
Wall, Scott Sent:
Thursday, December 18, 2014 3:45 PM To:
Anderson, Jon S.; Vincent, Dale M.
Cc:
Alley, David; Tsao, John; Pelton, David; Beltz, Terry; Willard, Bryan J.; Hammargren, Benjamin J.
Subject:
Prairie Island Nuclear Generating Plant, Units 1 and 2 - Requests for Additional Information Related to 10 CFR 50.55a Requests Associated with Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping (MF4839 and MF4840)
Attachments:
Prairie Island-RAIs for 10 CFR 50 55a Requests Associated with Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping (MF4839 and MF4840).pdf Mr. Anderson
By "L-PI-14-066, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS ([[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid.) - Shutdown|letter dated September 15, 2014]] (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML14258A073), as supplemented by letter dated October 20, 2014 (ADAMS Accession No. ML14293A458), Northern States Power Company (NSPM), a Minnesota Corporation, submitted relief requests for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The 10 CFR 50.55a requests numbered 1-RR-5-5, Revision 1, and 2-RR-5-5, Revision 1, are in support of the fifth ten-year interval for the PINGP, Units 1 and 2, lnservice Inspection Program.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by NSPM and has determined that additional information is needed to complete the review. On December 12, 2014, the NRC staff forwarded, via an electronic mail, a draft of the requests for additional information (RAIs) to the NSPM staff. The attachment to this electronic mail contains the finalized RAIs. On December 18, 2014, your staff agreed to response to the finalized RAIs no later than February 9, 2015.
Please note that review efforts on this task are being continued and further RAIs may develop.
Finally, please dont hesitate to contact me if you have any additional questions or concerns.
Sincerely,
ScottP.Wall,PMP,LSSBB,BSP SeniorProjectManager PlantLicensingBranchIII1 DivisionofOperatingReactorLicensing OfficeofNuclearReactorRegulation 301.415.2855 Scott.Wall@nrc.gov
Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATED TO SYSTEM LEAKAGE TEST OF SAFETY INJECTION ACCUMULATOR NITROGEN PIPING IN CONTAINMENT RELIEF REQUEST 1-RR-4-9 AND 2-RR-4-9 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated September 3, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14247A639), Northern States Power Company (NSPM, the licensee), doing business as Xcel Energy, submitted relief requests for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The 10 CFR 50.55a requests numbered 1-RR-4-9 and 2-RR-4-9 are in support of the fourth ten-year interval for the PINGP, Units 1 and 2, lnservice Inspection Program. The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by NSPM and has determined that additional information is needed to complete the review, as described in the attached request for additional information (RAIs).
RAI-RR-(4-9)-1: The licensee in Section 5 Proposed Alternative and Basis for Use of Enclosure to the relief request cited IWC-5210, IWA-5210, and IWC-5200 for which relief was requested and alternative was proposed. The requirements under IWC-5210, IWA-5210, or IWC-5200 have several sub-paragraphs.
Discuss specific subparagraph(s) of IWC-5210, IWA-5210, and IWC-5200 for which the relief was requested.
RAI-RR-(4-9)-2: American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code),Section XI, Table IWC-2500-1, Examination Category C-H, requires a system leakage test is performed according to IWC-5220 and a visual examination be performed according to IWA-5240 during each inspection period. IWC-5220 contains two subparagraphs, IWC-5221 and IWC-5222; and IWA-5240 contains four subparagraphs. Clarify whether the licensee is requesting relief from the ASME Code,Section XI, IWC-5220 and IWA-5240 in Table IWC-2500-1, Examination Category C-H. If yes, provide the specific subparagraphs in IWA-5240 and IWC-5220 the relief is requested. If no, provide justifications.
RAI-RR-(4-9)-3: The licensee submitted the relief requests pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(a)(3)(i). In accordance with 10 CFR 50.55a(a)(3)(i), the NRC staff authorizes a proposed alternative only if the alternative is equivalent in quality to the ASME Code requirement. Clarify how the licensees proposed alternative system leakage test is equivalent to the ASME Code,Section XI, IWC-5221 and IWA-5240 requirements and justify applicability of 10 CFR 50.55a(a)(3)(i).
RAI-RR-(4-9)-4: Provide the hardship(s) associated with the ASME Code,Section XI, required system leakage test of the safety injection (SI) accumulator nitrogen piping in containment. Hardship examples may include an as low as is reasonably achievable concern, creating excessive plant personnel hazards, and impact the plants Technical Specification requirement.
RAI-RR-(4-9)-5: Discuss leakage detection capabilities at the plant. Discuss any measure(s) that would be taken to monitor and identify leakage in an unlikely event of a through wall leak in the SI accumulator nitrogen piping in containment during normal operation.