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List of results

• TSTF-248  + (Revise Shutdown Margin Definition for Stuck Rod Exception)
• TSTF-535  + (Revise Shutdown Margin Definition to Address Advanced Fuel Designs)
• TSTF-435  + (Revise Steam Generator Requirements in ITS 3.4.5, 3.4.6, and 3.4.7)
• TSTF-499  + (Revise TS 3.4.3 Bases to Exclude the Pressurizer Surge Line from the P/T Limits)
• TSTF-128  + (Revise TSP Description)
• W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability  + (Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability)
• W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal  + (Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal)
• L-14-166, Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation  + (Revise Technical Specification 4.3.2, Spent Fuel Storage Pool Minimum Inadvertent Drainage Elevation)
• NL-19-1248, Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations - TSTF-51, SNC Response to NRC Request for Additional Information  + (Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations - TSTF-51, SNC Response to NRC Request for Additional Information)
• NL-18-1189, Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations- TSTF-51 and TSTF-471  + (Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations- TSTF-51 and TSTF-471)
• TSTF-363  + (Revise Topical Report References in ITS 5.6.5, Colr)
• TSTF-570  + (Revise Turbine Stop Valve and Turbine Control Valve Closure RPS Function Bases)
• TSTF-522  + (Revise Ventilation System Surveillance Requirements to Operate for 10 Hours PER Month)
• TSTF-038  + (Revise Visual Surveillance of Batteries to Specify Inspection is for Performance Degradation)
• TSTF-426  + (Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B and 6C)
• TSTF-301  + (Revise the 1 Hour Completion Time for Administrative Check of RCIC Operability)
• TSTF-031  + (Revise the 1.3 Examples to Match the BWR Standard)
• TSTF-050  + (Revise the 1.3 Examples to Match the CEOG Standard)
• TSTF-049  + (Revise the 1.4 Examples to Match the CEOG Standard)
• TSTF-026  + (Revise the Action for Minimum Temperature for Criticality to Match the Applicability)
• TSTF-025  + (Revise the Actions Terminology Regarding Qptr to Match the Actions Being Taken)
• TSTF-291  + (Revise the Applicability for the Intermediate Range Neutron Flux Specification)
• TSTF-293  + (Revise the Bases of the Source Range Neutron Flux Spec to Correctly Describe Required Actions)
• TSTF-092  + (Revise the Containment Purge and Exhaust SR to Exempt Valves That Are Locked, Sealed or Secured)
• TSTF-010  + (Revise the Control Rod Lcos Applicability from Mode 2 to Mode 2 with Keff>= 1.0)

• TSTF-268  + (Revise the Frequency of SR 3. 7.5.5, Afw/Efw Flow Path Verification)

• TSTF-565  + (Revise the LCO 3.0.2 and LCO 3.0.3 Bases)
• TSTF-165  + (Revise the LCO 3.0.5 Bases to Refer to Testing and Not SRS)
• ML18023A691  + (Revise the Pilgrim Emergency Plan to Address the Permanently Defueled Condition)
• TSTF-600  + (Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency)
• ML13240A320  + (Revise the Reactor Pressure Vessel Material Surveillance Capsule Withdrawal Schedule Due to License Renewal Amendment)
• ML17317A608  + (Revise the Reactor Pressure Vessel Material Surveillance Capsule Withdrawal Sechedule (CAC No. MF9075; EPID L-2016-LLL-0001))
• TSTF-008  + (Revise the SR 3.0.1 Bases to Allow Credit for Unplanned Events to Meet Any Surveillance)
• ML17137A159  + (Revise the Technical Specifications (Tss), Appendix a)
• ML19099A367  + (Revise the Technical Specifications for Permanent Extension of Types a and C Leak Rate Test Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency)
• TSTF-042  + (Revise the Wording of SR 3.0.2 to Be Consistent with the Other Nuregs)
• ML19290C369  + (Revised & Augmented List of Earthquake Intensities for Ks, 1867-1977)
• ML041180500  + (Revised (Revision 5) Davis-Besse IMC 0350 Oversight Panel Charter)
• ML050600423  + (Revised - 03/03/05 Notice of Meeting with Constellation Generation Group to Discuss NRCs Team Inspection Covering the Scoping and Aging Management Portions of Nine Mile Point Nuclear Stations Application for a Renewed License)
• IR 05000313/2023003  + (Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001)
• ML19182A188  + (Revised - Agenda 665th ACRS Full Committee Meeting, July 10-12, 2019)
• ML023310334  + (Revised - Braidwood Meeting Notice Letter to Licensee. Meeting to Start at 10:30 A.M. at Fossil Ridge Public Library)
• ML110480888  + (Revised - Browns Ferry Nuclear Power Plant - Operator Licensing Written Examination Approval 05000259/2011301, 05000260/2011301 and 05000296/2011301)
• ML063330486  + (Revised - Final Environmental Impact Statement Related to Construction of Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4 - March 1974)
• ML19218A073  + (Revised - NEIs Proposed Guidance for Section 1.8 of BTP 7-19)
• ML12073A162  + (Revised - Palisades Meeting Notice for End-of-Cycle Meeting)
• ML050750003  + (Revised - Pilgrim Annual Assessment Meeting Notice W/Nrc Slides)
• ML092720143  + (Revised - Political Activities)
• Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers  + (Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers)
• ML030640770  + (Revised 03/18/2003 Notice of Meeting with Entergy Nuclear Generation Company Re NRCs Annual Assessment of the Safety Performance at the Vermont Yankee Station)
• ML20199L143  + (Revised 1-OM-Index, Unit 1 Operations Dept OM Index)