JAFP-17-0063, Sixth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
JAFP-16-0192, Fifth Six-Month Status Report in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order No. EA-13-109)
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3-i - 3.5A-4
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 1 of 9
L-03-127, Containment Conversion Pre-application Report
ST-HL-AE-1702, Forwards Comparison Between Plant Exceptions to Rev 1 to Reg Guide 1.75, Physical Separation & Test Repts for Similar Exceptions at Other Projects Re Use of Aluminum & Copper Sheathed Cable,Per SER (NUREG-0781),Open Item 9
JAFP-92-0598, Ja Fitzpatrick Nuclear Power Plant,Annual Summary of Changes,Tests & Experiments for 1991
L-2023-040, Response to Requests for Additional Information (Rals) and Requests for Confirmation of Information (Rc Ls) Following Regulatory Audit of Subsequent License Renewal Application
CNL-20-058, Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27)
B12136, Forwards Revised Pages to Attachments 2 & 3 of Re 10CFR50,App J Exemption Request Concerning Testing of Containment Isolation Valve in Reverse Direction & Addition of Penetration Requiring Schedular Exemption
VPN-027-99, Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2
05000260/LER-1988-004-02, :on 880701,low Reactor Water Level Signal Received by Reactor Protection Sys Resulting in ESF Initiation.Caused by Personnel Error.Sensing Lines Capped, Isolations Reset & Personnel Counseled
05000265/LER-1992-003, :on 900205,determined That Measured Leakage Rate of 528.6 Standard Cubic Feet Per Hr Exceeded TS for All Valves.Caused by Excessive Leakage of HPCI Steam Exhaust Check Valve.Valve Replaced
NSD-NRC-96-4815, Forwards Binder Tabs for Section of Background Info for AP600 Shutdown Emergency Response Guidelines SDF-0.1 & SGD-1 Through SDG-6 That Were Not Transmitted W/Rept
NPL-97-0073, Submits Documentation for NRC Review to Support Restart Issues as Identified on Unit 2 Startup Commitment List as Result from Discussions Conducted at 970131 NRC Wi Electric Senior Mgt Meeting
ND-18-0053, Request for License Amendment: Technical Specification Applicability Changes to Support Pressurizer Safety Valve Operability (LAR-18-004)
JAFP-17-0116, Seventh Six-Month Status Report for Phases 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of
GO2-81-183, Forwards Responses to Round 2 Questions from Containment Sys Branch.Responses Will Be Incorporated Into FSAR Amend within 4 Months.Ge Proprietary Figures Sent Under Separate Cover by
RS-14-072, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights
MNS-14-058, Inservice Inspection Report, End of Cycle 22 Refueling Outage
NL-16-115, Response to Request for Additional Information Regarding Review of Compliance with Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events,
NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years
L-PI-05-082, Request for Relief No. 21, for the Plant 3rd 10-Year Interval Inservice Inspection Program
BW050064, Eleventh Refueling Outage Steam Generator Inservice Inspection Summary Report
BW050007, Eleventh Refueling Outage Steam Generator Inservice Inspection Summary Report
RNP-RA/03-0074, Supplemental Information Regarding License Renewal Application
NL-04-1045, Response to NRC Questions Regarding the 2002 Unit 2 (2R9) and the 2003 Unit 1 (1R11) Steam Generator Tube Inspection Reports
L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ
W3P87-2060, Forwards Changes to QA Program (FSAR Section 17.2) Re Significant Transition at Facility from Const to Operations Phase Which Included Major Reorganization of Nuclear Operations Dept.Fee Paid