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MONTHYEARML17061A1272017-02-0808 February 2017 Barry Quigley - Byron and Braidwood 2.206 Petition Regarding High Energy Line Break Project stage: Request ML17040A3042017-02-0808 February 2017 OEDO-17-00104 - Barry Quigley, Citizen, Email 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break Project stage: Request ML17040A3032017-02-0808 February 2017 OEDO-17-00104 - Barry Quigley, Citizen, Email 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break Project stage: Request ML17040A3022017-02-0808 February 2017 OEDO-17-00104 - Barry Quigley, Citizen, Email 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break Project stage: Request ML17040A3012017-02-0808 February 2017 OEDO-17-00104 - Barry Quigley, Citizen, Email 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break Project stage: Request ML17040A2992017-02-0808 February 2017, 17 July 2017, 24 April 2018 OEDO-17-00104 - Barry Quigley, Citizen, Email 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break Project stage: Request ML17027A2182017-03-0808 March 2017, 30 August 2017, 2 August 2018 OEDO-17-00070 - 2.206 Petition for Emergency Enforcement Action Per Chapter 10 Code of Federal Regulation Part 2.206 (10 CFR 2.206) at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Project stage: Request ML17111A7742017-04-13013 April 2017 Transcript of 2.206 Petition Review Board of April 13, 2017 Project stage: Request ML17174A7882017-06-22022 June 2017 OEDO-17-00070 - LTR from Paul Gunter to M. Banic Re. 2.206 Petition for Emergency Enforcement Action Per Chapter 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan Project stage: Other ML17163A0422017-06-22022 June 2017 OEDO-17-00135 - Response, David A. Lochbaum, Union of Concerned Scientists, 2.206 Petition - System One Solutions Event Notification (10 CFR Part 21) Project stage: Other ML17125A2452017-07-17017 July 2017 OEDO-17-00104 - Acknowledgement Letter for Barry Quigley, Citizen, E-mail 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break Project stage: Other ML17125A2472017-07-20020 July 2017 OEDO-17-00104 - FRN for Barry Quigley, Citizen, E-mail 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break Project stage: Other NRC-2017-0167, OEDO-17-00104 - FRN for Barry Quigley, Citizen, E-mail 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break2017-07-20020 July 2017 OEDO-17-00104 - FRN for Barry Quigley, Citizen, E-mail 2.206 Petition for Byron and Braidwood Units 1 & 2 High Energy Line Break Project stage: Other ML17198A3292017-08-30030 August 2017 OEDO-17-00070 - Acknowledgement Letter, Paul Gunter, Beyond Nuclear, Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Jap Project stage: Other 2017-06-22
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Category:2.206 Petition
MONTHYEARML20294A2402020-10-16016 October 2020 OEDO-20-00413 - 2.206 Petition-Beyond Nuclear - GE Mark I Hardened Vents ML17163A0422017-06-22022 June 2017 OEDO-17-00135 - Response, David A. Lochbaum, Union of Concerned Scientists, 2.206 Petition - System One Solutions Event Notification (10 CFR Part 21) ML17055C5832017-03-30030 March 2017 LTR-17-0038-1 - Final Rejection LTR - 2.206 Petition on the Issuance of Amendment Nos. 199 and 200, Revision to Technical Specification 3.8.1, AC (Alternative Current) Source - Operating ML17026A3092017-01-23023 January 2017 2.206 Petition on Palo Verde Nuclear Generating Station, Unit 3 - Issuance of Amendment Nos. 199 and 200 Revision to Technical Specification 3.8.1, AC Alternating Current Source-Operating ML11213A0302011-07-29029 July 2011 G20110563/EDATS: OEDO-2011-0535 - David Lochbaum Ltr. 2.206 - Boiling Water Reactors with Mark I and Mark II Containment Designs ML11192A2852011-07-0303 July 2011 G20110506/LTR-11-0402/EDATS: SECY-2011-0402 - Thomas Saporito 2.206 - Nebraska Public Power District and Cooper Nuclear Station, Et Al ML0836402012008-12-16016 December 2008 G20080864/EDATS: OEDO-2008-0949 - David Lochbaum Ltr Re 2.206 - Seismic Qualification Issues at DC Cook Unit 1 2020-10-16
[Table view] Category:Letter
MONTHYEARIR 05000298/20240032024-11-0505 November 2024 Integrated Inspection Report 05000298/2024003 IR 05000315/20240032024-10-31031 October 2024 Integrated Inspection Report 05000315/2024003 05000316/2024003 07200072/2024001 and Exercise of Enforcement Discretion ML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 ML24296B2152024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 03: Alternative Request Allowing Removal of the Lower Acceptance Criteria Threshold from Solenoid-Operated Valves ML24296B2142024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 02: Alternative Request Allowing Normally Closed Valves with a Safety Function to Close to Be Exercise Tested Once Per Refueling Cycle IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 AEP-NRC-2024-77, U2C28 Steam Generator Tube Inspection Report2024-10-21021 October 2024 U2C28 Steam Generator Tube Inspection Report ML24296B2172024-10-18018 October 2024 Submittal of Unit 1 Core Operating Limits Report, Revision 34, Unit 2 Core Operating Limits Report, Revision 26, and Unit 3 Core Operating Limits Report, Revision 3 ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 ML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report AEP-NRC-2024-80, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2024-10-15015 October 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask ML24285A2562024-10-11011 October 2024 License Renewal - Alloy 600 Management Program Plan Response to Request for Additional Information IR 07200044/20244012024-10-0808 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200044/2024401 ML24250A2052024-10-0808 October 2024 Issuance of Amendment No. 278 Regarding Revision to Technical Specification Table 3.3.2.1-1 and Transfer of Minimum Critical Power Ratio Values to Core Operating Limit Report ML24269A1542024-09-27027 September 2024 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed Life-of-Plant Alternatives for a Pressurizer Thermowell Nozzle Repair at Palo Verde Nuclear Generating Station, Unit 1 AEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 ML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) 05000316/LER-2024-002-01, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time ML24227A0822024-09-0303 September 2024 Summary of Regulatory Audit in Support of License Amendment Request to Modify the High Pressure Coolant Injection Low Flow Value IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000298/20240052024-08-22022 August 2024 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2024005) 05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-08-21021 August 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) ML24208A0612024-08-20020 August 2024 Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5 AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 IR 05000298/20240022024-07-25025 July 2024 Integrated Inspection Report 05000298/2024002 ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program 2024-09-09
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 22, 2017 Mr. David A Lochbaum Director, Nuclear Safety Project Union of Concerned Scientists P.O. Box 15316 Chattanooga, TN 37415
Dear Mr. Lochbaum:
I am responding to your e-mails dated February 22 and March 24, 2017, on behalf of the Union of Concerned Scientists (UCS), requesting that the U.S. Nuclear Regulatory Commission (NRC) issue Demands for Information (DFls) regarding the November 21, 2016, report, submitted to the NRC by System One Solutions, LLC in accordance with Title 10 of the Code of Federal Regulations (1 O CFR) Part 21 (the System One Part 21 report). You stated that UCS petitions the NRC to issue DFls pursuant to 10 CFR 2.204 to System One Solutions, LLC, AREVA NP, and the licensees for Cooper Nuclear Station, Donald C. Cook Nuclear Plant, and Palo Verde Nuclear Generating Station. You stated you are petitioning the NRC pursuant to 10 CFR 2.206, "Request for action under this subpart."
The NRC staff evaluated your request against the criteria in 10 CFR 2.206 and the guidance in Management Directive (MD) 8.11, "Review Process for 10 CFR 2.206 Petitions," to determine whether the request meets the criteria for review under 10 CFR 2.206. Based on our evaluation, we have determined that your petition does not meet the criteria for review under 10 CFR 2.206, in that it fails to provide facts that constitute the basis for the request, and requested an action that cannot be instituted pursuant to§ 2.202. Specifically, you stated that UCS has received information that calls into question the information in the System One Part 21 report. You further stated that UCS received information that indicated statements in the System One Part 21 report are inaccurate, but that UCS is unable to independently determine whether the information is accurate or not. You stated that the requested DFls will produce the records needed to fact-check the System One Part 21 report, and determine the source of any inaccuracies in the information reported to the NRC. Your petition also outlines additional actions USC may take, including additional enforcement actions it may request the NRC take, based on its review and determinations on information NRC obtains through the DFls and makes publically available.
Any person may request, pursuant to § 2.206, that the NRC institute a proceeding pursuant to
§ 2.202. Based on a § 2.206 request, the Commission may institute a proceeding pursuant to
§ 2.202 to modify, suspend, or revoke a license or to take such other action as may be proper only by serving on the licensee an order that must, in part, allege the violations with which the licensee is charged, or the potentially hazardous conditions or other facts deemed to be sufficient ground for the proposed action. For the NRC to accept a request submitted pursuant to § 2.206 for review, MD 8.11 specifies that the facts that constitute the basis for the request must be provided with the request, and must be credible and sufficient to warrant further inquiry.
For example, the NRC staff may determine that the information provided in a § 2.206 request is not sufficient to support issuance of an order pursuant to § 2.202, but may determine that the information is sufficient to warrant further inquiry through an inspection or, if the criteria in
D. Lochbaum 10 CFR 2.204 is met, through a DFI. As specified in 10 CFR 2.204, NRC may issue a DFI for the purpose of determining whether an order under 10 CFR 2.202 should be issued, or whether other actions should be taken. The NRC Enforcement Manual (available on the NRC Web site at http://www.nrc.gov/what-we-do/regulatory/enforcement/guidance.html) states, in part, that "A DFI is a significant action. It should be used only when it is likely that an inadequate response will result in an Order or other enforcement action."
Your request relies on DFls being issued to obtain facts that establish whether the System One Part 21 report contained inaccuracies that warrant taking additional action. Your request also does not provide supporting facts, such as the safety significance of the alleged inaccuracies in the System One Part 21 report, necessary for NRC to issue the DFls under§ 2.204, and to demonstrate that an inadequate response to such DFls would be sufficient ground for NRC to issue orders under§ 2.202 to require System One Solutions LLC, AREVA NP, and the licensees for Cooper, DC Cook, and Palo Verde to take additional action. Because your request does not provide facts that constitute a basis for issuing the requested DFls, and does not request an action that can be instituted through a proceeding pursuant to § 2.202, it is not appropriate for NRC to review the request under the 10 CFR 2.206 petition process.
The NRC takes seriously the providing of inaccurate information that could result in a safety issue or the NRC making a regulatory decision based on the inaccurate information. The NRC has a number of means to assess whether information submitted to it is materially inaccurate, and for determining what additional action, if any, is warranted regarding the inaccurate information. As such, your incoming letter will be referred to another NRC process for appropriate action. Receiving information about potential violations or safety concerns from the public is an important means for the NRC to identify and appropriately respond to such issues, and we appreciate you sharing your concerns and engaging in the regulatory process.
Sincerely,
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1 __ Jo~# ro~A'_
Douglas A. Broaddus, Chief Special Projects and Process Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc: Listserv
PKG ML17054C305 Incoming ML17054C313 and ML17086A340 Response Letter ML17163A042 *via
. e-ma1*1 OFFICE NRR/DORL/LSPB/PM NRR/DORL/LSPB/LAiT NRR/DORL/LSPB/LA NAME MBanic IBetts JBurkhardt DATE 06/15/2017 06/13/2017 06/14/2017 OFFICE OGC (NLO)* NRR/DORL/LSPB/BC NAME SKirkwood DBroaddus DATE 05/31/2017 06/22/2017