ML13029A743
| ML13029A743 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/29/2013 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Meena Khanna Plant Licensing Branch 1 |
| Bamford P NRR/DORL/LPL1-2 301-415-2833 | |
| References | |
| TAC ME9510 | |
| Download: ML13029A743 (3) | |
Text
January 29, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Peter Bamford, Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST TO USE LATER ADDENDA OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE FOR OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS (TAC NO. ME9510)
The attached draft request for additional information (RAI) was transmitted by electronic transmission on January 29, 2013, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees proposal to use a specific portion of a later edition of the ASME Code For Operation And Maintenance Of Nuclear Power Plants that allows pump inservice testing reference values to be up to 90 percent of the test instrument range. The draft RAI is related to the licensees submittal dated September 10, 2012. The draft question was sent to ensure that it was understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-289
Enclosure:
As stated
January 29, 2013 MEMORANDUM TO: Meena Khanna, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM:
Peter Bamford, Project Manager /RA/
Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
THREE MILE ISLAND, UNIT NO. 1 - ELECTRONIC TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST TO USE LATER ADDENDA OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE FOR OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS (TAC NO. ME9510)
The attached draft request for additional information (RAI) was transmitted by electronic transmission on January 29, 2013, to Mr. Thomas Loomis, at Exelon Generation Company, LLC (Exelon, the licensee). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call (if needed) with Exelon in order to clarify the licensees proposal to use a specific portion of a later edition of the ASME Code For Operation And Maintenance Of Nuclear Power Plants that allows pump inservice testing reference values to be up to 90 percent of the test instrument range. The draft RAI is related to the licensees submittal dated September 10, 2012. The draft question was sent to ensure that it was understandable, the regulatory basis was clear, and to determine if the information was previously docketed. Additionally, review of the draft RAI would allow Exelon to evaluate and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not represent an NRC staff position.
Docket No. 50-289
Enclosure:
As stated DISTRIBUTION:
Public RidsNrrPMThreeMileIsland Resource LPL1-2 R/F Accession No.: ML13029A743
- via email OFFICE LPL1-2/PM EPTB/BC NAME PBamford AMcMurtray*
DATE 01/29/13 01/25/13 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT 1 REQUEST TO USE LATER ADDENDA OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE FOR OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS DOCKET NO. 50-289 By letter dated September 10, 2012 (Agencywide Documents Access and Management System Accession No. ML12254A177), Exelon Generation Company, LLC (Exelon, the licensee) submitted a request to use a provision of a later edition and addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). Specifically, the licensee proposed to use a specific portion of a later edition of the ASME OM Code that allows pump inservice testing (IST) reference values to be up to 90 percent of the test instrument range. This allowance was requested for all of the pumps in the IST program, but is specifically needed for the Boric Acid Injection Pumps. The U.S. Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
1.)
Paragraph 50.55a(f)(4)(iv) of Title 10 of the Code of Federal Regulations (10 CFR) allows the use of later ASME Code editions or addenda. As noted in NRC Regulatory Issue Summary 2004-12, Clarification on Use of Later Editions and Addenda to the ASME Code and Section XI, use of a specific portion of a later ASME Code edition and addenda is allowed provided that all requirements of respective editions or addenda are met. Since only a specific portion of a later ASME Code edition and addenda are to be used, the licensee is requested to address whether all related requirements of the respective editions and addenda will be met for the pumps that are the subject of this request.
Additionally, to avoid confusion with any potential future request, or revision to this request, the NRC requests that the licensee assign a specific number and title to the request.