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MONTHYEARJAFP-10-0088, Submittal of Corrections to the 2004, 2005, 2006, 2007, and 2008 Annual Radioactive Effluent Release Reports2010-07-15015 July 2010 Submittal of Corrections to the 2004, 2005, 2006, 2007, and 2008 Annual Radioactive Effluent Release Reports Project stage: Request RA-10-040, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 20092010-09-24024 September 2010 Submittal of Revised Annual Radiological Groundwater Protection Program Report for 2009 Project stage: Request ML11056A0132011-02-28028 February 2011 Y020100294 - Compliance with Federal Regulation 10 CFR 50.9, Completeness and Accuracy of Information - Response Project stage: Other 2010-09-24
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Category:Letter
MONTHYEARIR 05000261/20240032024-10-30030 October 2024 Integrated Inspection Report 05000261/2024003 IR 07200015/20244012024-10-30030 October 2024 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200015/2024401 ML24303A2822024-10-29029 October 2024 License Termination Plan Supplemental Submittal for Technical Bases Documents JAFP-24-0055, Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation2024-10-29029 October 2024 Response to Request for Additional Information for License Amendment Request to Add Temporary Change to TS 3.3.2.1, Condition C, Control Rod Block Instrumentation IR 05000333/20240902024-10-29029 October 2024 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000333/2024090 IR 05000333/20244022024-10-28028 October 2024 Material Control and Accounting Program Inspection Report 05000333/2024402 (Cover Letter Only) ML24297A2182024-10-28028 October 2024 – NRC Operator License ML24276A1332024-10-17017 October 2024 Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes IR 05000261/20244022024-10-16016 October 2024 – Security Target Set Baseline Inspection Report 05000261/2024402 ML24282B0302024-10-11011 October 2024 Project Manager Assignment RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24284A1972024-10-10010 October 2024 Cover Letter Oyster Creek, License Termination Plan Acceptance Review ML24207A0192024-10-0909 October 2024 SE Addendum Related to the License Amendment No. 338 for Implementation of the Alternative Source Term (DPO-2021-001) ML24269A0462024-10-0404 October 2024 Cover Letter for Oyster Creek Nuclear Generating Station, License Amendment Request, License Termination Plan, Acceptance Review Request for Additional Information JAFP-24-0051, Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-0882024-10-0303 October 2024 Reply to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000333/2024011; EA-24-088 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24270A0742024-09-30030 September 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0134) - LTR ML24270A1452024-09-26026 September 2024 Notice of Enforcement Discretion for James A. Fitzpatrick Nuclear Power Plant JAFP-24-0047, License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software2024-09-25025 September 2024 License Amendment Request – Temporary Addition to TS 3.3.2.1 Condition C, Control Rod Block Instrumentation to Support Upgrade to Rod Worth Minimizer Software JAFP-24-0046, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation2024-09-25025 September 2024 Request for Enforcement Discretion for Technical Specification (TS) 3.3.2.1 Control Rod Block Instrumentation ML24274A0822024-09-25025 September 2024 Independent Spent Fuel Storage Installation Security Plan, Training Qualification Plan, Safeguards Contingency Plan, Revisions 1 and 2 JAFP-24-0045, Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2024-09-20020 September 2024 Supplemental Information for License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20240112024-09-19019 September 2024 Follow-up to Inspection Procedure 71153 Report 05000333/2024011 and Preliminary White Finding and Apparent Violation ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status JAFP-24-0044, Core Operating Limits Report Cycle 272024-09-16016 September 2024 Core Operating Limits Report Cycle 27 JAFP-24-0043, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2024-09-12012 September 2024 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues IR 05000261/20244012024-09-11011 September 2024 Security Baseline Inspection Report 05000261/2024401 IR 05000219/20240022024-09-0505 September 2024 – NRC Inspection Report 05000219/2024002 and 07200015/2024001 ML24165A0382024-09-0404 September 2024 Issuance of Amendment No. 356 Update Fuel Handling Accident Analysis 05000333/LER-2024-002, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation2024-09-0404 September 2024 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation IR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) IR 05000261/20240052024-08-22022 August 2024 Updated Inspection Plan for H.B. Robinson Steam Electric Plant - Report 05000261/2024005 05000333/LER-2024-001-01, EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket2024-08-21021 August 2024 EDG Lube Oil Check Valve Bonnet Cap Leak Due to Failed Gasket ML24169A2712024-08-14014 August 2024 – Issuance of Amendment No. 280 to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification 5.7, High Radiation Area ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24214A0372024-08-0101 August 2024 License Amendment Request to Revise Renewed Facility Operating License to Add License Condition 2.C.(18) to Include License Termination Plan Requirements IR 05000261/20240022024-08-0101 August 2024 Integrated Inspection Report 05000261/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test ML24179A1842024-07-23023 July 2024 June 20, 2024, Clarification Call on Preapplication Readiness Assessment of the Holtec Decommissioning International License Termination Plan IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 2024-09-05
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February 28, 2011 David Lochbaum Director, Nuclear Safety Project Union of Concerned Scientists Post Office Box 15316 Chattanooga, TN 37415
SUBJECT:
Response to your letter dated December 6, 2010, Compliance with Federal Regulation 10 CFR 50.9, Completeness and Accuracy of Information.
Mr. Lochbaum:
Thank you for your interest in potential 10 CFR 50.9 compliance issues. In your letter, you quoted three examples where you suggest that licensee documents violated 10 CFR 50.9, and that there were differences in how the NRC staff treated similar issues.
When revised or incorrect documents are received by the NRC they receive a review by staff to determine if additional assessments are necessary, based upon potential impacts to regulatory decisions. These expectations are part of the NRR technical qualification program. To reinforce our performance we will formalize 10 CFR 50.9 guidance in our review processes.
This will include ensuring that licensees take the appropriate actions in their corrective action processes.
For situations that require further review, our Office of the General Counsel has legal staff available for more in depth assessments of potential violations of 10 CFR 50.9, and how they should be handled.
We have reassessed the examples that you quoted, and believe that our original conclusions are still valid. A summary of each of the examples you quoted follows:
HB Robinson Nuclear Plant (ADAMS ML09170067), 10 CFR 50.9 violation In this example, the licensee provided inaccurate information that was used in part to determine a subsequent regulatory action. In the Notice of Violation it was stated that:
The third finding involves an NRC-identified apparent violation of 10 CFR 50.9(a), for which final severity level is to be determined, related to materially inaccurate information provided to the NRC in Licensee Event Report (LER) 05000261/2009-001. This information was material to NRC because it was used, in part, as the basis for determining whether the licensees response to the degraded condition was adequate and whether additional compensatory actions or NRC review would be necessary.
Thus this violation was material as it had an impact on a regulatory decision.
D. Lochbaum February 28, 2011 Fitzpatrick Revisions to their Annual Effluent Report (ADAMS ML101970366), no violation This document corrected an incorrect dose assessment factor that is used to calculate the potential radiological dose impact to the public from fission and activation gasses. Apparently a factor that was used in the licensees software was not correctly updated.
The NRC has described how licensees should make such changes to their effluent reports in Regulatory Guide 1.21. The licensee correctly followed the regulatory guide process for making such revisions. After the corrections, the revised values were two orders of magnitude below the licensees regulatory limits The conclusions from the assessment of this revision were:
- 1. The licensee did not deliberately state incorrect information.
- 2. No potential or actual regulatory decisions were affected.
- 3. The licensee followed the established regulatory process for revising their annual effluent report.
Oyster Creek to their Annual Effluent Report (ADAMS ML102950279), no violation The revision to this annual assessment report incorporated additional groundwater monitoring information that was not required by regulation or license condition. The additional information was provided voluntarily.
The conclusions from the assessment of this revision were:
- 1. The licensee chose to add additional information that was not required by regulations, thus the original document met regulatory expectations.
- 2. No potential or actual regulatory decisions were affected.
- 3. The licensee followed the established regulatory process for revising their annual effluent report.
Hopefully the explanations for these examples help your understanding of why one of these cases was treated as a violation, and the other two were not.
There is different NRC guidance for different document types. For example, the enforcement manual has guidance for situations when licensees report incorrect performance indicator information as this data is used in the reactor oversight process.
Sincerely,
/RA/
Frederick D. Brown, Director Division of Inspection and Regional Support Nuclear Regulatory Commission
D. Lochbaum February 28, 2011 Fitzpatrick Revisions to their Annual Effluent Report (ADAMS ML101970366), no violation This document corrected an incorrect dose assessment factor that is used to calculate the potential radiological dose impact to the public from fission and activation gasses. Apparently a factor that was used in the licensees software was not correctly updated.
The NRC has described how licensees should make such changes to their effluent reports in Regulatory Guide 1.21. The licensee correctly followed the regulatory guide process for making such revisions. After the corrections, the revised values were two orders of magnitude below the licensees regulatory limits The conclusions from the assessment of this revision were:
- 1. The licensee did not deliberately state incorrect information.
- 2. No potential or actual regulatory decisions were affected.
- 3. The licensee followed the established regulatory process for revising their annual effluent report.
Oyster Creek to their Annual Effluent Report (ADAMS ML102950279), no violation The revision to this annual assessment report incorporated additional groundwater monitoring information that was not required by regulation or license condition. The additional information was provided voluntarily.
The conclusions from the assessment of this revision were:
- 1. The licensee chose to add additional information that was not required by regulations, thus the original document met regulatory expectations.
- 2. No potential or actual regulatory decisions were affected.
- 3. The licensee followed the established regulatory process for revising their annual effluent report.
Hopefully the explanations for these examples help your understanding of why one of these cases was treated as a violation, and the other two were not.
There is different NRC guidance for different document types. For example, the enforcement manual has guidance for situations when licensees report incorrect performance indicator information as this data is used in the reactor oversight process.
Sincerely,
/RA/
Frederick D. Brown, Director Division of Inspection and Regional Support Nuclear Regulatory Commission DISTRIBUTION: Y020100294 RidsNRRMailRoom RidsNRROD ADAMS Accession #: ML11056A015; - Package; ML013610398 - Incoming; ML11056A013 - Letter OFFICE: NRR/DIRS/TA NRR/DIRS/D NAME: WBCartwright FDBrown DATE: 02/ 25 /11 02/ 28 /11 OFFICIAL RECORD COPY