NOC-AE-17003490, Changes to Emergency Plan and Implementing Procedure
RA-16-021, License Amendment Request for Proposed Changes to Technical Specifications Section 6.0 Administrative Controls for Permanently Defueled Condition
PLA-2407, Forwards Applications for Proposed Amends 63 & 17 to Licenses NPF-14 & NPF-22,respectively,revising Membership of Util Review Committee.Fee Paid
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 8 Through Chapter 10
RCF 10-03, Response to Request for Additional Information Regarding the Renewal of Facility Operating License
RA-10-050, Technical Specification Change Request No. 340, Proposed Revision to Appendix B Environmental Technical Specifications of the Facility Operating License
TMI-09-099, Submittal of Revision 12 of the Post-Defueling Monitored Storage Quality Assurance Plan
TMI-09-037, Supplement: Technical Specification Change Request No. 86 Deletion of Sections 6.5, Review and Audit
TMI-09-029, Supplement to License Amendment Request for: Oyster Creek Technical Specification Change Request No. 336, Three Mile Island Unit 1 Technical Specification Change Request No. 330, Deletion of Technical Specification Requirements for Review
2CAN100702, License Amendment Request, Technical Specification Changes Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process
W3F1-2007-0033, License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability
RC-05-0204, Response to NRC Questions Regarding Response to Generic Letter 96-06
W3F1-2004-0094, Revised Response to Waterford 3's Response Letter to Generic Letter 2003-01, Control Room Habitability
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate
W3F1-2003-0015, License Amendment Request NPF-38-247 Relocation & Modification of Technical Specifications 4.0.5 & 3/4.4.9 & Extension of Reactor Coolant Pump Flywheel Volumetric Examination Interval
NRC-93-0129, Forwards Rev 9 to Radiological Emergency Response Preparedness Plan. Rev Represents Changes Resulting from Implementation of Revised 10CFR20 Rule
NRC-95-0022, Forwards Rev 12 to Radiological Emergency Response Preparedness Plan (Rerp). Rev Result of 1994 Annual RERP Review,Including Rev of Emergency Response Organization
NRC-94-0107, Application for Amend to License NPF-43,proposing Changes to Administrative Controls Section of Ts,Consistent W/Guidance in NUREG-1433 & GL 93-07, Mod of Ts...For Emergency & Security Plans
NRC-94-0105, Forwards Rev 11 to Fermi 2 Radiological Emergency Response Preparedness Plan. Rev Represents Changes Resulting from Updating Fermi 2 Evacuation Time Estimate & Deleting Description of RERP Keycard Classes
NRC-95-0125, Forwards Rev 14 to Radiological Emergency Response Preparedness Plan. Rev Result of Updates to Ltrs of Agreement W/Offsite Support Agencies.Rev 13 Canceled
NRC-96-0039, Submits Rev 17 to RERP Incorporating NUMARC/NESP-007,rev 2, Methodology for Development of Emergency Action Levels
NRC-97-0038, Forwards Rev 19 to Radiological Emergency Response Preparedness (RERP) Plan. Changes Made in Rev Do Not Decrease Effectiveness of Plan as Supported by Encl 1, Effectiveness Review
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
BECO-88-121, Revised Application for Amend to License DPR-35,consisting of Proposed Change 88-15,updating Administrative Controls Section of Tech Specs to Conform to Current Nuclear Organization
B11621, Application to Amend Licenses DPR-61,DPR-21 & DPR-65, Revising Tech Spec Section 6.5 Re Fire Protection & Loss Prevention Program Audits & Clarifying Term Outside Firm. Fee Paid
RC-96-0121, Submits Rev 18 to Fermi 2 Radiological Emergency Response Preparedness Plan,Resulting from 1996 Annual RERP Plan Review
0CAN119205, Application for Amends to Licenses NPF-51 & NPF-6,revising Administrative Controls Sections of TS to Implement Technical Review & Control Process
FVY-83-121, Responds to NRC Re Violations Noted in IE Insp Rept 50-271/83-27.Corrective Actions:Setpoint for high-high Main Steam Line Radiation Instrument Trip Setting Reset to Less than Three Times Normal full-power Background
BVY-94-114, Responds to NRC Re Violation Noted in Insp Rept 50-271/94-20 on 940807-0917.Corrective Actions:Engineer Relieved from Further Duty & All Reactor & Computer Engineering Personnel Reinstructed on Overtime Requirements
BVY-90-126, Responds to NRC Re Violations,Deviation & Weaknesses Noted in Insp Rept 50-271/90-10 on 900813-1009. Corrective Actions:Procedure AP 0140 Reviewed & Evaluation Process for Equipment Qualification Will Be Reviewed
0CAN109002, Application for Amends to Licenses DPR-51 & NPF-6,revising Tech Spec Section 6.0, Administrative Controls, to Delete Specific Refs to Staff Positions & Plant Safety Committee Compositions
PY-CEI-NRR-0396, Rev 2 to Emergency Operating Procedure PAP-0507, Preparation Review Approval,Rev & Cancellation of Instructions
BVY-93-108, Responds to Violations Noted in Insp Rept 50-271/93-14. Corrective Actions:Nonconforming Matls Removed & Independent Insp of Remaining Scaffolding & Temporary Matls within Reactor Bldg Performed
NRC-95-0132, Forwards Rev 16 to Radiological Emergency Response Preparedness (RERP) Plan, Including Changes from Rev 15 to RERP Plan.Rev 15 Not Issued Separately.Rev 15 Implemented by Incorporating Encl Rev 16
NRC-93-0152, Forwards Rev 10 to Radiological Emergency Response Preparedness Plan. Rev Includes Changes That as of 940103, Implement Revised EPA, Manual of Protective Action Guides & Protective Actions for Nuclear Incidents, EPA 400-R-92-001
IA-97-166, Forwards SE Re Request to Establish Requirements for Audits of TS Subject to Provisions of App B to 10CFR50.Request Left Unsolved Pending Further NRC Review
3F0192-15, Forwards Rev 8 to Fire Protection Plan
NRC-96-0125, Forwards Addl Info on Proposed TS Change on Administrative Controls
IA-86-542, Requests Authorization to Issue Initial License for Dry Cask Storage of Spent Fuel Per 10CFR72 in Isfsi.License Should Be Granted
2CAN011301, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360
2CAN031602, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the Asme
L-82-185, Responds to NRC Re Violations Noted in IE Insp Repts 50-250/82-07 & 50-251/82-07.Corrective Actions:Maint Procedure 1207.1 Will Be Modified to Include Specific Impact Wrench Size & Torque Value Safe Operating Limits
FVY-82-133, Responds to NRC Re Violations Noted in IE Insp Rept 50-271/82-19.Corrective Actions:Fire Watch Personnel Reinstructed in Responsibilities.Fire Proof Kneeling Pads Constructed for Future Use
NRC-93-0126, Forwards Rev 8 to Radiological Emergency Response Preparedness Plan. Scope of Rev Primarily Changes Operating Organization in Figure B-1 & Position Titles in Table B-2
L-77-238, Letter Finding No Proprietary Information in Inspection Reports 05000250/1977012 and 05000251/1977012
LR-N980049, Forwards Rev 16 to Salem Generating Station UFSAR IAW Requirements of 10CFR50.71(e).Rev Contains Identified Text, Table & Figure Changes Required to Reflect Plant Configuration as of 970731
HNP-99-136, Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS
HNP-99-092, Application for Amend to License NPF-63,revising TS 6.5, Review & Audit, TS 6.8, Procedures & Program & TS 6.10, Record Retention
L-86-115, Responds to Violations Noted in Insp Repts 50-250/85-30 & 50-251/85-30.Corrective Actions:Operating Procedure OP 3204.1 Rewritten to Ensure Independent Verification That Four Breakers Locked Open Prior to Running RHR Pump
GO2-97-083, Forwards Audit 297-005, WNP-2 Emergency Preparedness Program. Three Problem Evaluation Requests & 10 Recommendations for Improvement Issued as Result of Audit Activities
GO2-92-258, Forwards Amend to License NPF-21,consisting of Proposed Change,Revising TS 6.0 to Change Composition of Plant Operations Committee & to Allow Implementation of Staff Reorganization Intended to Be Responsive to Plant Changes
GO2-89-146, Responds to NRC Re Violations Noted in Insp Rept 50-397/89-20.Corrective Action:Memo Placed in Training Audit File Notifying Lead Auditor to Include Listed Depts in Future Audits
GO2-87-294, Responds to NRC Re Violations Noted in Insp Rept 50-397/87-27.Corrective Actions:Overtime Control Directive Rev & Other Plant Procedures Review & Rev Planned.Full Compliance Expected by 880229
GO2-92-120, Responds to NRC Re Violations Noted in Insp Rept 50-397/92-03 on 920124-0308.Corrective Actions:Test Procedure PPM 8.3.230TP Revised to Require Drywell to Drywell Test Flow Path to Satisfy TS Requirements
2CAN121601, Response to Request for Additional Information License Amendment Request for Adoption of TSTF-545, TS Inservice Testing Program & Clarify SR Usage Rule Application to Section 5.5
W3F1-2009-0031, Technical Specification Bases Update to the NRC for the Period November 11, 2008 Through July 1, 2009
SBK-L-06063, License Amendment Request 06-01, Application to Eliminate License Condition 2.G Requiring Reporting of Violations of Section 2.C of the Operating License Using the Consolidated Line Item Improvement Process
NOC-AE-02001418, Changes to Emergency Plan Implementing Procedures