L-2017-139, License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply
L-2013-233, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
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 4 of 9
LR-N10-0015, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
LR-N09-0218, Unit 2 - License Amendment Request (LAR) S09-06 Revision to Technical Specification 4.0.5, Surveillance Requirements for Inservice Inspection and Testing of ASME Code Components
05000530/LER-1994-002-01, :on 940318,13 of 20 MSSVs Setpoints Found to Be Out of Tolerance.Most Valves Exhibited Seat Wear.Valves Replaced w/pre-tested Spares & Approval to Amend TS LCO 3.7.1.1,MSSV Setpoints Received
L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
HNP-07-005, Request for License Amendment to Relocate and Revise Technical Specifications Surveillance Requirement 4.0.5
SBK-L-06244, Submittal of Changes to Seabrook Station Technical Specification Bases
LR-N06-0051, Request for Amendment to Technical Specifications Maximum Allowable Power with Inoperable Steam Line Safety Valves
LR-N05-0031, Request for Change to Technical Specifications Removal of Performance Restrictions from Surveillance Requirements
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate
L-04-040, License Amendment Request Nos. 321 and 193, Modifying Technical Specification Requirements for Mode Change Limitations in Specifications 3.0.4 and 4.0.4 and the Associated Technical Specification Bases
L-2003-083, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4
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
L-2002-210, Proposed License Amendments Re Administrative Update of Technical Specifications, Section 4.4.1.1 - Appendix B
L-99-051, Provides Response to NRC Request to Maintain Change That Was Proposed to Be Deleted in LAR 214 & 81,submitted 980709.New Marked Up TS Pages Are Encl
B11608, Forwards Draft STS for three-loop Operation of Facility, Reflecting ANSI N510-1980 & Providing Addl Info Not Included in Original Submittal
W3F1-2016-0036, Application to Revise Technical Specifications to Adopt TSTF-545, Rev 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the ASME Code
L-2004-222, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.i.4
NOC-AE-04001668, License Amendment Request, Proposed Revision to Technical Specifications Regarding Mode Change Using the Consolidated Line Item Improvement Process
L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
05000336/LER-1986-008-02, :on 860920,6 of 16 Valves Failed Main Steam Safety Valve Simmer Test.Caused by Setpoint Drift.Increased Accuracy Pressure Gauges Used to Reduce Test Error & Spring & Ambient Temps Recorded
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
05000336/LER-1986-008, :on 860920,6 of 16 Valves Failed Main Steam Safety Valves Simmer Test Used to Verify Pressure Setpoint. Cause of Setpoint Drift Unknown.Increased Accuracy Pressure Gauges Used to Reduce Test Error
L-2006-264, Technical Specification Bases Control Program Periodic Record of Bases Changes TS 6.8.4.j.4
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
L-94-223, Forwards Revs to 940719 Proposed License Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1.1 & Associated Bases, Which Address Max Allowable Reactor Thermal Power Operation W/Inoperable Mssvs,Per Recent Conversation W/Nrc
05000315/LER-1998-054, :on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With
05000528/LER-1998-004, :on 980304,safety Valves as-found Pressures Out of Tolerance.Cause of Event Is Under Investigation.Three MSSVs & Psv Will Be Replaced W/Refurbished & Recertified Valves During Refueling Outage U1R7
05000529/LER-1993-002, :on 930518,determined That 15 of 20 MSSV & 4 of 4 Pressurizer Safety Valves as-found Relief Settings Out of Tolerence Limits.Valves Exhibited Seat Wear.Efforts to Enhance MSSV Setpoint Repeatability Continuing
LR-N16-0114, License Amendment Request 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 Using the Consolidated Line
L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-02-094, Technical Specifications Bases Change Submittal
L-2003-291, Technical Specification Bases Control Program, Periodic Report of Bases Changes, TS 6.8.4.j.4
AECM-83-0565, Forwards marked-up Proposed Changes to Tech Specs Per 821020 Confirmation of Action Ltr.Changes Intended to Enhance Clarity or Provide Consistency W/Plant Design & Operation. Justification for NSHC Encl
LR-N25-0015, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 2