ML18330A014

PRM-50-75 Email Status Update to Petitioner Dated November 15, 2018 ECCS Evaluation Models

ML18330A014
Person / Time
Issue date:	11/15/2018
From:	Dennis Andrukat Office of Nuclear Material Safety and Safeguards
To:	True D Nuclear Energy Institute
Dennis Andrukat 415-3561
References
NRC-2002-0018, PRM-50-75
Download: ML18330A014 (2)

Text

From: Andrukat, Dennis To: det@nei.org; arp@nei.org Cc: Beall, Robert

Subject:

Status Update for PRM-50-75 Date: Thursday, November 15, 2018 4:44:38 PM Mr. Doug True (for Mr. Anthony R. Pietrangelo) :

I am contacting you to provide a status update on the petition for rulemaking Mr. Anthony R. Pietrangelo submitted to the U.S. Nuclear Regulatory Commission (NRC), dated February 6, 2002, on behalf of the Nuclear Energy Institute (NEI). Mr. Pietrangelo requested that the NRC amend its regulations in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors, 10 CFR Part 50 Appendix A, General Design Criteria for Nuclear Power Plants and 10 CFR Part 50, Appendix K, ECCS Evaluation Models to allow the use of an alternative to the currently required double-ended rupture of the largest pipe in the reactor coolant system in emergency core cooling system (ECCS) evaluation models. Mr. Pietrangelo requested that the NRC revise applicable regulations to require adherence with current American Concrete Institute standards and American Society of Mechanical Engineers codes.

The NRC docketed Mr. Pietrangelo's letter as petition for rulemaking PRM-50-75, and the NRC published a notice of receipt in the Federal Register on April 8, 2002, (67 FR 16654).

The comment period closed on June 24, 2002. The agency received eighteen comment letters. As stated in the NRC letter dated October 15, 2008, the NRC determined that the issues raised in PRM-50-75 were appropriate for consideration and, in fact, the agency was considering them in the Risk-Informed Redefinition of Large Break Loss-of-Coolant Accident (LOCA) ECCS Requirements rulemaking (Docket ID: NRC-2004-0006). This rulemaking proposed revisions to the NRC regulations in 10 CFR Part 50 that address licensing of production and utilization facilities in which the issues raised by PRM-50-75 would be resolved. Substantive comments received on PRM-50-75 in response to the April 8, 2002, notice of receipt would be addressed as part of the Risk-Informed Redefinition of Large Break LOCA ECCS Requirements rulemaking.

However, on October 6, 2016, the NRC published a notice in the Federal Register (81 FR 69446) informing the public of the discontinuation of this rulemaking. In the notice, the NRC stated that PRM-50-75 would be addressed by alternative means and that the NRC will issue a separate Federal Register document to disposition PRM-50-75.

The status of PRM-50-75 can be found at the NRC Rules and Petition page at https://www.nrc.gov/reading-rm/doc-collections/rulemaking-ruleforum/active/PetitionIndex.html. At this Web site there is a link to a listing of all active NRC PRMs. You can monitor this site for status updates as they become available.

You can monitor the docket for your petition on the Federal rulemaking Web site,http://www.regulations.gov,by searching on Docket ID NRC-2002-0018. The Federal rulemaking Web site allows you to receive alerts when changes or additions occur in a docket folder. To subscribe: 1) navigate to the docket folder (NRC-2002-0018); 2) click the E-mail Alert link; and 3) enter your e-mail address and select how frequently you would like to receive e-mails (daily, weekly, or monthly).

Please feel free to contact me at Dennis.Andrukat@nrc.gov or (301) 415-3561 if you have questions or concerns.

Sincerely, Dennis Dennis Andrukat Project Manager Division of Rulemaking Office of Nuclear Material Safety and Safeguards 301-415-3561 Dennis.Andrukat@nrc.gov