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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML12187A044 + (Correction to Request for Relief 3lR-2 for Pressurizer Supports)
- ML121290597 + (Correction to Request for Withholding Information from Public Disclosure)
- ML12230A310 + (Correction to Requests for Additional Information for the Review of the Grand Gulf Nuclear Station License Renewal Application)
- NG-06-0329, Correction to Response to Apparent Violation in Office of Investigations Report No. 3-2004-033: EA-06-047 + (Correction to Response to Apparent Violation in Office of Investigations Report No. 3-2004-033: EA-06-047)
- ML021140666 + (Correction to Response to Backfit Claim Regarding NRC Inspection Report 50-313/01-06; 50-368/01-06)
- ML021140583 + (Correction to Response to Backfit Claim Re Inspection Report 50-313/01-06; 50-368/01-06)
- L-06-002, Correction to Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power + (Correction to Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power)
- ULNRC-06095, Correction to Response to NRC Request for Information Per 10CFR50.54(f) Re Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - 1.5 Year Responses + (Correction to Response to NRC Request for Information Per 10CFR50.54(f) Re Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - 1.5 Year Responses)
- ET 08-0033, Correction to Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application - Closure of the Metal Fatigue Analysis Open Items + (Correction to Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application - Closure of the Metal Fatigue Analysis Open Items)
- CNL-16-173, Correction to Response to Request for Additional Information Regarding Request to Revise Technical Specifications for Diesel Generator Completion Time Extension for Technical Specifications 3.8.1, AC Sources. + (Correction to Response to Request for Additional Information Regarding Request to Revise Technical Specifications for Diesel Generator Completion Time Extension for Technical Specifications 3.8.1, AC Sources.)
- CNL-22-104, Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 + (Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02)
- ML110670168 + (Correction to Response to Request for Additional Information for the Review of the PVNGS License Renewal Application (Lra), and LRA Amendment No. 30)
- ML021580155 + (Correction to Revision 33 to Wolf Creek Generating Station Physical Security Plan)
- ML13052A739 + (Correction to Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule)
- ML033000533 + (Correction to Risk-Informed Inservice Inspection Program Safety Evaluation)
- IR 05000293/1997099 + (Correction to SALP Rept 50-293/97-99.Page 2 of Subj Rept Corrected)
- ML20195C448 + (Correction to SE Supporting Amend 201 to License DPR-16. Corrected Page Shows Line Bars in Margin Indicating Areas of Change)
- ML20082S217 + (Correction to SE Supporting Amends 176 & 207 to Licenses DPR-71 & DPR-62,respectively,reflecting Removal of Condenser Offgas Monitor Alarm Setpoint Statement from SE)
- ML20198L300 + (Correction to SE Supporting Amends 223 & 199 to License DPR-53 & DPR-69 Re Rev to Error on Pages 1 & 5)
- ML17159A361 + (Correction to SE for Amend 174 to FOL NPF-14.Correction Due to Typos)
- ML20217K725 + (Correction to SE of Relief Request MC-R001 Re Qualification Requirements for non-destructive Exam Personnel Performing Containment Insp)
- ML20207B410 + (Correction to SECY-99-107, Potential Mod of Doe/Nrc MOU Due to Changes in Hanford Tank Waste Remediation Sys Privatization)
- ML20196G538 + (Correction to SER Acceping Amends to Added Limiting Condition for Operation,Trip Setpoints & SR for Residual Heat Removal Pump Trip on Refueling Water Storage Tank level-low)
- ML17354B102 + (Correction to SER Page 5 of SE & Page 6 of Ineel Technical Ltr Rept to Reflect Change of Word Then with Also, Submitted on 980817 in Response to Util 980409 Request Relief from Certain Requirements of ASME Code,Section XI)
- ML20236R288 + (Correction to SER Supporting Amends 203 & 233 to Licenses DPR-71 & DPR-62,respectively.Insert Page 42 (Safety Evaluation) & Page 9 of 51 (Table Rl))
- GNRO-2016/00050, Correction to Safety Analysis Report for Constant Pressure Power Uprate + (Correction to Safety Analysis Report for Constant Pressure Power Uprate)
- ML023290568 + (Correction to Safety Evaluation (SE) for Amendment No. 211)
- ML041190424 + (Correction to Safety Evaluation Associated with Relief Request No. RR 63 Regarding Risk-Informed Inservice Inspection Program)
- ML24024A020 + (Correction to Safety Evaluation Associated Wit Amendment No. 288 - Revision to Applicability Term for RCS Heat-Up and Cooldown Pressure-Temperature Limitations Figures)
- ML040930417 + (Correction to Safety Evaluation Associated with Issued Amendment)
- ML041200736 + (Correction to Safety Evaluation Associated with Issued Order)
- ML041360003 + (Correction to Safety Evaluation Associated with Issued Order)
- ML14365A093 + (Correction to Safety Evaluation Dated December 12, 2014, Regarding Amendment No. 249, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date)
- ML043270534 + (Correction to Safety Evaluation Dated October 28, 2004, Regarding Revision to Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan)
- ML043270474 + (Correction to Safety Evaluation Dated October 28, 2004, Regarding Revision to the Physical Security Plan, Training and Qualifications Plan, and Safeguards Contingency Plan)
- ML043270515 + (Correction to Safety Evaluation Dated October 28, 2004, Regarding Revision to the Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan)
- ML043280181 + (Correction to Safety Evaluation Dated October 28, 2004, Regarding Revisions to the Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan)
- ML11139A438 + (Correction to Safety Evaluation Inservice Inspection Program Alternative Issued Date June 24, 2009)
- ML25057A353 + (Correction to Safety Evaluation Issued for Request to Use Provisions from a Later Edition of ASME Code, Section XI (EPID-L-2024-LLR-0073))
- ML25080A307 + (Correction to Safety Evaluation Issued for Amendment Nos. 237, 237, 236, and 236)
- ML053500044 + (Correction to Safety Evaluation Issued in Amendment Nos. 183 and 185)
- ML13149A225 + (Correction to Safety Evaluation Page 60 (Redacted) for Amendment No. 188, Revise TSs to Reflect Installation of Digital GE-Hitachi Nuclear Measurement Analysis and Control Power Range Neutron Monitoring System)
- ML16139A164 + (Correction to Safety Evaluation Page for Amendment Nos. 279 and 275 Issuance of License Amendments Regarding Emergency Action Level Scheme Change)
- ML14106A383 + (Correction to Safety Evaluation Page, Relief Request No. 1/2E-1 for Containment Electrical Penetrations for the Third 10-Year Inservice Inspection Interval)
- ML18317A005 + (Correction to Safety Evaluation Pages 5 and 24 for Amendment No. 199 Dated November 27, 2006 Related to Alternative Source Term)
- ML13198A009 + (Correction to Safety Evaluation Pages 6-7 for Amendment No. 246, Revise the Updated Safety Analysis Report to Reflect Changes to Fuel Handling Accident Dose Calculation)
- ML12341A111 + (Correction to Safety Evaluation Pages Issued with Amendment No. 243 Dated 11/9/2012, Revise TS 2.0, Safety Limits, to Revise Safety Limit Minimum Critical Power Ratio Values of a Cycle-Specific Calculation)
- ML15022A416 + (Correction to Safety Evaluation Pages for Authorization of Relief from the Requirements of the ASME Code Extension of the Reactor Vessel Inservice Inspection Interval)
- ML15022A197 + (Correction to Safety Evaluation Pages for Amendment Nos. 180, 180, and 186 and 186 Clarification of Technical Specifications 3.3.1 and 3.3.2)
- ML062620299 + (Correction to Safety Evaluation Re Amendment No. 222)
- ML20216F492 + (Correction to Safety Evaluation Re Revised SG Tube Rapture Analysis)