ML22131A000

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PRM-50-122 - Email from C. Bladey, NRC to B. Magnuson Regarding Inquiry on Status of Petition Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors and Other Items Involving RG 1.183 and DG-13
ML22131A000
Person / Time
Issue date: 04/18/2022
From: Cindy Bladey
NRC/NMSS/DREFS/RASB
To: Magnuson B
- No Known Affiliation
Foli, Adakou
References
NRC-2020-0150, PRM-50-122
Download: ML22131A000 (2)


Text

From:

Bladey, Cindy To:

Brian Magnuson; Meighan, Sean; Wang, Weidong; Burkhart, Larry; Blumberg, Mark; Petti, David; Dickson, Elijah; Vasavada, Shilp; Jones, Steve; Parillo, John; Chang, Helen; Foli, Adakou; Berrios, Ilka; Firth, James; Burnell, Scott; Shepherd, Jill Cc:

Karen Gray; Jack Kolar; Stephani Ayers; Thad Guyer; Frank Newell

Subject:

RE: RE: ACRS Subcommittee Meeting - Regulatory Guide 1.183 (DG-1389) Alternative Radiological Source Terms for Evaluating Design Basis Accident at Nuclear Power Reactors - Inquiries Date:

Monday, April 18, 2022 12:00:31 PM Attachments:

image001.png Good Morning Mr. Magnuson, Im responding to your inquiry regarding the status of your petition for rulemaking, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, (PRM-50-122; NRC-2020-0150).

The NRC published in the Federal Register a notice of docketing with a request for public comment on your petition on August 24, 2020 (85 FR 52058). The NRC staff has reviewed the public comments, the merits of the petition, and past agency actions, and is in the process of preparing a recommendation to the Commission. The Commission will make and issue a final decision on your petition. Contact me if you have additional questions about the NRCs petition for rulemaking process.

Regards, Cindy Bladey

Cindy Bladey, Chief Regulatory Analysis and Rulemaking Support Branch U.S. Nuclear Regulatory Commission Division of Rulemaking, Environmental, and Financial Support Office of Nuclear Material Safety and Safeguards 11545 Rockville Pike Mail Stop: T04B72 Rockville, Maryland 20852-2738 301-415-3280

From: Brian Magnuson <magnuson28@msn.com>

Sent: Saturday, April 16, 2022 10:21 AM To: Meighan, Sean <Sean.Meighan@nrc.gov>; Wang, Weidong <Weidong.Wang@nrc.gov>;

Burkhart, Larry <Lawrence.Burkhart@nrc.gov>; Blumberg, Mark <Mark.Blumberg@nrc.gov>; Smith, Micheal <Micheal.Smith@nrc.gov>; Petti, David <David.Petti@nrc.gov>; Dickson, Elijah

<Elijah.Dickson@nrc.gov>; Vasavada, Shilp <Shilp.Vasavada@nrc.gov>; Jones, Steve

<Steve.Jones@nrc.gov>; Parillo, John <John.Parillo@nrc.gov>; Chang, Helen

<Helen.Chang@nrc.gov>; Bladey, Cindy <Cindy.Bladey@nrc.gov>; Foli, Adakou

<Adakou.Foli@nrc.gov>; Berrios, Ilka <Ilka.Berrios@nrc.gov>; Firth, James <James.Firth@nrc.gov>;

Burnell, Scott <Scott.Burnell@nrc.gov>; Shepherd, Jill <Jill.Shepherd@nrc.gov>; Shepherd, Jill

<Jill.Shepherd@nrc.gov>

Cc: Karen Gray <kareng@whistleblower.org>; Jack Kolar <jackk@whistleblower.org>; Stephani Ayers

<stephani@whistleblowerdefenders.com>; Thad Guyer <thad@guyerayers.com>; Frank Newell

<frank@loevy.com>

Subject:

[External_Sender] RE: ACRS Subcommittee Meeting - Regulatory Guide 1.183 (DG-1389)

Alternative Radiological Source Terms for Evaluating Design Basis Accident at Nuclear Power Reactors - Inquiries

April 16, 2022

Dear NRC Staff and ACRS Members:

Please let me know when the transcript of the March 16, 2022 meeting is available and all of my March 2022 public comments are posted in ADAMS.

Also, when should I expected documented responses to my December 2020 public comments?

Attached is NRC Regulatory Issue Summary 2001-19: Deficiencies in the Documentation of Design Basis Radiological Analyses Submitted in Conjunction with License Amendment Requests. Please recognize that it substantiates my March 28 public comments copied here.

Ironically, the design-basis contravention must deviate from design-basis, because even using the contravention, nuclear power plants cannot comply with GDC-19.

This is why RG 1.183 and DG-1389 lowers design-basis standards. They credit the use of non-safety related and non-seismically qualified systems and components that are not credited in design-basis analyses. Proffered inspections of non-safety related equipment (e.g., piping, condensers) do not satisfy legitimate design-basis analyses that can only credit safety-related equipment. RG-1389s seismically rugged is simply an artifice; legitimate design-basis seismic analyses refer to these components as seismically unqualified.

Additionally, please provide the current status of my 10 CFR 2.803 Petition for Rulemaking, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, (PRM-50-122; NRC 2020 0150).

Sincerely, Brian Magnuson

From: Brian Magnuson <magnuson28@msn.com>

Sent: Monday, March 28, 2022 10:30:07 PM To: Meighan, Sean <Sean.Meighan@nrc.gov>; weidong.wang@nrc.gov <Weidong.Wang@nrc.gov>;