RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
CNL-16-010, Application to Modify Technical Specification 4.3.1.2, Fuel Storage Criticality (TS-508)
GNRO-2011/00076, License Amendment Request Criticality Safety Analysis and Technical Specification 4.3.1, Criticality
L-PI-11-075, Letter from Xcel Energy License Amendment Request for Spent Fuel Pool Criticality Changes
BSEP 06-0128, Request for License Amendments Regarding Fuel Design and Storage Requirements for Areva Np Fuel
1CAN070603, License Amendment Request to Support the Use of Metamic@ Polson Insert Assembles in the Spent Fuel Pool
LIC-06-0065, Closure of NRC TAC Issues for Fort Calhoun Station Unit No. 1
HNP-04-151, Technical Specification Bases Change: Undervoltage and Underfrequency - Reactor Coolant Pump Buses
NRC-98-0150, Forwards Response to NRC 981026 RAI Re Fermi 2 Conversion to Improved Std Ts.Responses Reflect Results of Series of Meetings Between Util & NRC
NRC-97-0105, Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms
NRC-98-0040, Application for Amend to License NPF-43,requesting to Allow one-time Extension of Surveillance Intervals to Delay Shutdown for Upcoming Sixth Refueling Outage (RFO6) Until 980904
RBG-44017, Requests Exemption to Criticality Accident Monitoring Requirements Stipulated in 10CFR70.24(a) Specifically for Areas Containing Incore Detectors & Unirradiated Fuel While Fuel Is Handled,Used or Stored Onsite
ULNRC-03873, Application for Amend to License NPF-30,revising TS Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr
U-600560, Summarizes Discussion W/Nrc Concluding That Repeat Manual Testing of Portions of Nuclear Safety Protection Sys Independent of self-test Sys Surveillance Test Functions Per Tech Spec 1.39 unnecessary.Marked-up Tech Spec Encl
ST-HL-AE-2715, Forwards Requested Addl Info Re Thermowell Mounted Rtds,In Response to 871218 Telcon.Response Revised to Clarify Effect of Change in RTD Time Response on Both Line Break Analyses
NL-22-0288, License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel
ELV-02942, Responds to Request for Addl Info for Changes for Tech Spec Re Removal of Resistance Temp Detector Bypass Loops
NL-22-0609, Response to NRC Requests for Information License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel
NL-05-014, Supporting Information for License Amendment Request Regarding Indian Point Unit 3 Stretch Power Uprate
BSEP-98-0174, Requests Exemption from Requirements of 10CFR70.24, Criticality Accident Requirements. Basis for Exemption Request Provided in Encl 1.List of Regulatory Commitments Contained in Ltr Provided in Encl 2
05000409/LER-1986-014, :on 860418,determined That During Discharge of 3,000 Gallon Waste Tank,Water from 4,500 Gallon Waste Tank Also Pumped.Caused by Open Suction Valve Leading to Operating Waste Transfer Pump.Valve Closed
05000366/LER-1988-014-01, :on 880427,surveillance Requirements Not Met Resulting in Condition Prohibited by Tech Spec.Caused by Procedural Inadequacy.Scheduling of Development of Permanent Procedure Revs Underway
1CAN100601, Supplement to License Amendment Request to Support Use of Metamic Poison Insert Assemblies in Spent Fuel Pool
05000366/LER-1988-002, :on 880219,surveillance Requirements of Tech Specs Not Met.Caused by Personnel Error.Special Purpose Procedures Developed & Surveillances Performed or Scheduled
05000382/LER-1997-005, :on 890715,failure to Perform Coolant Low Flow Trip Operating Bypass Surveillance Occurred.Caused by Failure to Implement Procedural Controls to Test Reactor Coolant Low Flow Bypass.Event Will Be Reviewed
05000354/LER-1995-033-01, :on 951114,TS Surveillance Requirement Implementation Deficiencies Occurred.Caused by Lack of Documentation of Annunciation for Previous Surveillances. SDV Bypass Logic Were Satisfactorily Tested
05000354/LER-1996-033, :on 951114,two Events Occurred Due to Identification of TS Surveillance Test Inadequacy.Caused by Ineffective Procedures.Tssip Review Will Be Completed
05000445/LER-1990-034, :on 900928,surveillance Missed for Channel Response Time Due to Personnel Error
1CAN040302, License Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.3
CNL-22-100, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)
HNP-99-094, Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration
05000397/LER-1993-010, :on 940304,24 Reportable Problems Identified by Failure of Procedures to Fully Implement.Cause Was Less than Adequate Barrier & Controls for Program Changes.Corrective Actions Include Procedure & TS Changes
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
LIC-06-0063, Exigent LAR, Deletion of Design Features Technical Specifications Redundant to 10 CFR 50.68, Criticality Accident Requirements
LIC-05-0075, Response to Request for Additional Information on the License Amendment Request, Revisions of Technical Specifications Table 1-1 and Section 4.0
LIC-04-0117, License Amendment Request, Revisions of Technical Specifications Table 1-1 and Section 4.0
NL-02-160, Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, & 5.0 of Improved TS
L-2024-188, Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis
GNRO-2011/00025, NET-287-01, Revision 1, BADGER Test Campaign at Grand Gulf Nuclear Station