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NRC Headquarters
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RIS 2005-31, Official Exhibit - Mandatory Hearing - AES000056-MA-BD01 - NRC Regulatory Issue Summary 2005-31, Control of Security-Related Sensitive Unclassified Non-Safeguards Information Handled by Individuals, Firms & Entities Subject to NRC Regula
RC-11-0104, License Amendment Request - LAR (10-03107) Proposed Change in Administrative Controls Section to Allow the Use of Westinghouse WCAP-12472-P-A, Addendum 1-A
BSEP 10-0133, Response to Additional Information Request Supporting License Amendment Requests for Addition of Analytical Methodology Topical Reports to Technical Specification 5.6.5 (NRC TAC Nos. ME3856, ME3857, ME3858, and ME3859)
L-2010-035, Submittal of License Amendment Request Regarding a Spent Fuel Pool Criticality Analysis Taking Credit for Boraflex
L-2009-249, Issuance of Amendment Regarding Spent Fuel Boraflex Remedy Supplement 3 to Request for a Change in Implementation Date
ULNRC-05620, Clarification Regarding Application of ASME Code Relief Request Approved for Callaway
Press Release-08-090, Nuclear Regulatory Commission Honors Employees on June 2 in Rockville, MD
GO2-05-196, Submittal of the Third Ten-Year Interval Inservice Inspection Program Plan and 10 CFR 50.55a Requests 3ISI-01 Through 3ISI-07
STC-19-050, STC Letter Notification of Public Meeting Re Response to Stakeholders on Issues Related T10 CFR 20 2002 Disposal in the Agreement States and RIS 2016-11
RIS 2016-11, September 6, 2019, Summary of Public Meeting Addressing Concerns Re Regulatory Issue Summary (RIS) 2016-11
HNP-05-130, Relief Requests No 2R1-016 Request for Relief from Inservice Inspection Requirements for Pressure Retaining Dissimilar Metal Welds and No 2R1-017 Request for Relief from Inservice Inspection Program Requirements for Reactor Vessel
LIC-05-0122, Relief Request for Use of Radiography Using Phosphor Imaging Plate
WM 05-0013, 10CFR50.55a Requests Regarding Implementation of ASME Section XI Requirements for Examination of the Reactor Pressure Vessel and Connecting Loop Piping Welds; 10CFR50.55a Requests 12R-29, 12R-30, 12R-31, and 12R-32
B17132, Forwards Responses to 980303 Questions Re Ability of Millstone Unit 1 to Meet TS Requirements Relating to SRV Setpoint Tolerances.List of Regulatory Commitments Contained within Ltr
B17695, Forwards Response to NRC 990204 RAI Re LBB Evaluation of Pressurizer Surge Piping.Response Discusses Loads,Fatigue & Fatigue Crack Growth Analysis That Were Part of Util Original 981109 Submittal
B17682, Responds to NRC Re Licensee Request for Review & Approval of LBB Methodology for Plant Pressurizer Surge Piping.Rev 0 to SIR-99-021, Evaluation of Stratification Loadings in LBB Analysis for Mnps,Unit 2 Surge Line, Encl
B17614, Informs That Util Reviewed Mnps,Unit 2 Independent Corrective Action Verification Program Rept,Issued 990112 by Parsons Group.Encl Response Addresses Findings & Recommendations Contained in Subject Rept
RC-96-0027, Forwards Revised Attachment Ii,Sections 3.4.3 & 5.0 & Safety Evaluation,Attachment IV to TS Change Request TSP 950001, Suppl 2 Re Plant Uprate
RC-97-0063, TS Change Request - TSP 97-02 to License NPF-12,charging mini-flow Header Isolation Motor Operated Valves
B15953, Submits Response to Request for Addl Info Re Porous Concrete sub-foundation.FSB Located on East Side of Reactor Containment Bldg & Two Foundation Structures
RC-96-0069, Submits Addl Info to Support Contention That Environ Effects of Plant Uprate Inconsequential.Uprate Will Increase Thermal Output of Plant by Approx 4.6 Percent,But Should Not Provide Any Adverse Impact to Surrounding Environ
RC-96-0072, Forwards Summaries & Conclusions for Evaluations Performed on SFP Cooling Subsys to Support Acceptability of SFP Peak Temps
RC-95-0212, Application for Amend to License NPF-12,consisting of Change Request 95-07 Re ECCS Pump Testing
RC-95-0299, Application for Amend to License NPF-12,consisting of Change Request 94-02,incorporating Revs to 10CFR20 Corrections of Bases 3/4 11-1
RC-95-0283, Application for Amend to License NPF-12,consisting of TS Change TSP 950010,allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days
RC-95-0184, Application for Amend to License NPF-12,consisting of TS Change Request 940007,removing Spec for MOVs Thermal Overload Protection & Bypass Devices (3/4.8.4.2) to Follow Guidance of Improved Westinghouse Standardized TS
RC-95-0258, Application for Amend to License NPF-12,consisting of Change Request 95-01,permitting VCSNS to Operate at Uprate Power Level of 2900 Mwt Core Power When Unit Restarted After Ninth Refueling Outage
RC-95-0226, Application for Amend to License NPF-12,consisting of Change Request TSP 940002,incorporating Revs to 10CFR20
RC-95-0174, Application for Amend to License NPF-12,consisting of TS Change Request TSP 950001,permitting Plant to Operate at Uprate Power Level of 2,900 Mwt Core Power.Proprietary Best Estimate Analysis... Encl.Analysis Withheld
RC-95-0218, Submits Notorization Suppl Re Circumferential Cracking of SG Tubes Per GL 95-03
RC-95-0215, Submits Rev to TS Change 95-02 Re PORVs & Block Valves
RC-95-0183, Requests Amend to License NPF-12,consisting of TS Change 95-09 Re TS 3/4.3.2 ESFAS Instrumentation,Sr 4.3.2.1 Being Revised to Exclude Requirement to Perform Slave Relay Test of 36 Containment Purge Supply & Exhaust Valves Quarterly
RC-95-0167, Application for Amend to License NPF-12,consisting of TS Change TSP 950002,revising TS 3/4.4.4 for Pressurizer PORVs to Follow Guidance of GL 90-06,GI 70 & Improved Westinghouse Standardized TS
RC-95-0145, Application for Amend to License NPF-12.Amend Would Revise SR 4.6.1.2 to Delete Schedular Requirements for Type a Testing
RC-95-0162, TS Change TSP 950006 to License NPF-12,requesting Amend to TS 3/4.6.2, Depressurization & Cooling Sys to Change Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs
RC-95-0149, Submits Notarization Suppl for Ltrs Dtd 950221,0306 & 0505
RC-95-0148, Forwards Rev 1 to Sce&G VC Summer Nuclear Station ASME Section XI Inservice Exam Manual for 2nd Insp Interval
RC-95-0084, Informs That Util Intends to Implement Formal Inductry Position on Severe Accident Mgt Approved by Nuclear Energy Inst Nuclear Strategic Issues Advisory Committee on 941104
RC-95-0058, Application for Amend to License NPF-12,requesting Discontinuation of Seismic Monitoring Network
RC-95-0046, Requests Discontinuation of Seismic Monitoring Network Around Plant,On Basis That Min Requirements of OL Condition 2.C (24) Have Been Satisfied
RC-95-0023, Provides Response to NRC Request for Addl Info Pertaining to Westinghouse Alloy 600 SG Mechanical Plugs
SECY-08-0147, Response to Utahs September 13,2018,Letter on NRC Recommendation for Site-Specific Performance Assessment for Depleted Uranium Penetrators
GO2-98-162, Requests Withdrawal of 980805 Proposed TS Amend,Modifying SR 3.8.4.7 to Allow Performance Discharge Test of SR 3.8.4.8 to Be Performed in Lieu of Battery Svc Test
ET 07-0016, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
ULNRC-04557, Issuance of Amendment 148, Reactor Trip System Instrumentation
RC-96-0117, Requests Return of Proprietary Westinghouse Rept, VCSNS Rsg/Uprating:Best Estimate Large Break LOCA Final Analysis Rept. NRC No Longer Needs to Review Best Estimate Methodology
SECY-21-0057, Enclosure - Stakeholder Engagement on the Very Low-Level Waste Scoping Study
RC-95-0252, Forwards Rev 7 to General Test Procedure (Gtp) GTP-301, IST of Pumps Second Ten Yr Interval, Incorporating Guidance from NUREG-1482 in Response to GL 89-04,Suppl 1
RC-95-0221, Suppl to TS Change TSP 950006 Re Compatibility W/Plant Operating Experience & Consistent W/Gl 93-05
RC-95-0185, Forwards Amend 95-02 to FSAR for VC Summer Nuclear Station, Per Telcon W/Berley Indicating That Previously Transmitted FSAR Amend 95-02 Destroyed
RC-95-0117, Provides Proposed Schedule for Sceg up-rate Licensing of Vsns W/Respect to Large Break LOCA Analyses