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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML033500303  + (Withdrawal of Relief Request Related to Security Force Personnel Group Work-Hour Controls During Extended Allowed Outages)
• ML100120608  + (Withdrawal of Relief Request Related to Code Case N-729-1, Table 1)
• ML021690306  + (Withdrawal of Relief Request SP-1, Tac Nos. MB4763 & MB4764)
• ML090771305  + (Withdrawal of Relief Request SPT-006, Use of Code Case N-731 for the Fourth Interval ISI Program)
• ML101100467  + (Withdrawal of Relief Request Serial 09-MN-004)
• MNS-16-042, Withdrawal of Relief Request Serial No. 15-MN-002  + (Withdrawal of Relief Request Serial No. 15-MN-002)
• ML032731297  + (Withdrawal of Relief Request VR-12)
• ML14302A018  + (Withdrawal of Relief Request VRR-RBS-2014-2, ASME Code Case OMN-17 to Align Currently Installed Safety/Relief Valves to Requested Frequency)
• ML14049A290  + (Withdrawal of Relief Request W3-ISI-022, from ASME Code, Section XI Based on Code Case N-805 System Leakage Testing of Rv Head Flange O-Ring Leak Detection System, for the Third 10-year ISI Interval)
• NL-08-1080, Withdrawal of Relief Request for Indian Point, Unit 2, Regarding Inservice Testing Program Relief Request P-1 for Recirculation Pump Testing  + (Withdrawal of Relief Request for Indian Point, Unit 2, Regarding Inservice Testing Program Relief Request P-1 for Recirculation Pump Testing)
• ML20303A271  + (Withdrawal of Relief Request for Proposed Alternative to Supplemental Position Indication Testing Interval)
• ML081660002  + (Withdrawal of Relief Request for Temporary Non-Code Repair of Service Water Piping)
• ML092310081  + (Withdrawal of Relief Request for Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Alloy 82/182 Welds (ISIR-28))
• AEP-NRC-2009-62, Withdrawal of Relief Request for Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds (ISIR-28)  + (Withdrawal of Relief Request for Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds (ISIR-28))
• ML040280439  + (Withdrawal of Relief Request from Code Requirements for Low Pressure Safety Injection Pumps)
• ML053130082  + (Withdrawal of Relief Request from the Provisions of ASME Code XI, Relief Request 15 (TACs MC7770 and MC7771))
• NG-07-0270, Withdrawal of Relief Request to Allow Use of the Provisions of IWA-4132 for the Remainder of the Third 10-Year Inservice Inspection Interval and the Fourth Ten-Year Inservice Inspection Interval  + (Withdrawal of Relief Request to Allow Use of the Provisions of IWA-4132 for the Remainder of the Third 10-Year Inservice Inspection Interval and the Fourth Ten-Year Inservice Inspection Interval)
• ML043170470  + (Withdrawal of Relief Request to Extended Second Inservice Inspection Program 10-Year Interval)
• ML12219A329  + (Withdrawal of Relief Request to No. 3RR-19)
• ML072840015  + (Withdrawal of Relief Request to Use Alternative Ultrasonic Examination Method in Lieu of Radiography)
• ML080250305  + (Withdrawal of Relief Request to Use Code Case N-706)
• ML20105A378  + (Withdrawal of Relief Request to Use Code Case OMN-13)
• NG-07-0255, Withdrawal of Relief Request to Use the Provisions of Appendix Viii, Article VIII-4000, in the Evaluation of Changes in Maximum Cable Length for In-Service Inspection Examination Equipment  + (Withdrawal of Relief Request to Use the Provisions of Appendix Viii, Article VIII-4000, in the Evaluation of Changes in Maximum Cable Length for In-Service Inspection Examination Equipment)
• NOC-AE-03001544, Withdrawal of Relief Request, Request for Approval of an Alternative Approach for Containment Tendon Surveillances (RR-ENG-37).  + (Withdrawal of Relief Request, Request for Approval of an Alternative Approach for Containment Tendon Surveillances (RR-ENG-37).)
• ML032450235  + (Withdrawal of Relief Request, Request for Approval of an Alternative Approach for Containment Tendon Surveillances (RR-ENG-37))

• L-03-097, Withdrawal of Relief Requests  + (Withdrawal of Relief Requests)

• ML042790442  + (Withdrawal of Relief Requests - Request for Relief from ASME Section XI Code Requirements for Repair of Pressurizer Nozzle Penetrations)
• PLA-7092, Withdrawal of Relief Requests 1RR07 and 2RR07 for Third Ten-Year Interval Inservice Testing Program Plans for Susquehanna Ses (SSES) Unit 1 and Unit 2, PLA-7092  + (Withdrawal of Relief Requests 1RR07 and 2RR07 for Third Ten-Year Interval Inservice Testing Program Plans for Susquehanna Ses (SSES) Unit 1 and Unit 2, PLA-7092)
• ML043340429  + (Withdrawal of Relief Requests 2-ISI-22 and 3-ISI-18 Re Nondestructive Examination of Reactor Pressure Vessel Nozzle-to-Vessel Welds and Nozzle Blend Radii)
• ML071560416  + (Withdrawal of Relief Requests Associated with Pump Vibration (MD3253 Through MD3290))
• ML030520259  + (Withdrawal of Relief Requests CMP-16 & CMP-17 Alternative Repair Techniques)
• ML22110A123  + (Withdrawal of Relief Requests PR-09 and VR-07 (Epids: L 2021 Llr 0095 and L 2022 Llr 0021))
• CNRO-2004-00073, Withdrawal of Relief Requests RBS-ISI-001, RBS-ISI-002, and RBS-ISI-003  + (Withdrawal of Relief Requests RBS-ISI-001, RBS-ISI-002, and RBS-ISI-003)
• ML030860290  + (Withdrawal of Relief Requests to Support Alternative Repair Methods for Reactor Vessel Head Penetrations)
• L-2006-227, Withdrawal of Remote Shutdown and Post-Accident Monitoring Instrumentation TS Change  + (Withdrawal of Remote Shutdown and Post-Accident Monitoring Instrumentation TS Change)
• ML031560737  + (Withdrawal of Request - Implementation of Leak Before Break Technology)
• GO2-06-138, Withdrawal of Request 3ISI-01 for Plant  + (Withdrawal of Request 3ISI-01 for Plant)
• B19026, Withdrawal of Request RR-89-44 and RR-89-45 for Alternatives Allowing the Half-Nozzle Repair/Replacements in Alloy 600 Small Bore Nozzles  + (Withdrawal of Request RR-89-44 and RR-89-45 for Alternatives Allowing the Half-Nozzle Repair/Replacements in Alloy 600 Small Bore Nozzles)
• DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application  + (Withdrawal of Request Regarding Senior Reactor Operator License Application)
• ML082330141  + (Withdrawal of Request Related to NRC Approval of the Three Mile Island Joint Information Center (JIC) Relocation from Harrisburg to Coatesville, PA)
• ML050330262  + (Withdrawal of Request for Additional Information Regarding Response to Bulletin 2004-01)
• 1CAN061003, Withdrawal of Request for Alternative CEP-ISI-007 Pertaining to Application of Code Case N-663  + (Withdrawal of Request for Alternative CEP-ISI-007 Pertaining to Application of Code Case N-663)
• ML101750073  + (Withdrawal of Request for Alternative CEP-ISI-007)
• 2CAN011108, Withdrawal of Request for Alternative Pertaining to the Use of Code Case N-578  + (Withdrawal of Request for Alternative Pertaining to the Use of Code Case N-578)
• RBG-46947, Withdrawal of Request for Alternative RBS- ISI-012 - Request to Extend the Second ASME Inservice Inspection Interval  + (Withdrawal of Request for Alternative RBS- ISI-012 - Request to Extend the Second ASME Inservice Inspection Interval)
• RBG-47084, Withdrawal of Request for Alternative RBS-ISI-014 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections  + (Withdrawal of Request for Alternative RBS-ISI-014 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections)
• CNRO-2005-00030, Withdrawal of Request for Alternative RBS-PT-001  + (Withdrawal of Request for Alternative RBS-PT-001)
• ML112200390  + (Withdrawal of Request for Alternative Test Requirements for Large-Bore Hydraulic Snubbers)
• CNRO-2006-00037, Withdrawal of Request for Alternative W3-R&R-005  + (Withdrawal of Request for Alternative W3-R&R-005)
• ML062130121  + (Withdrawal of Request for Amendment)
• ML14051A103  + (Withdrawal of Request for Amendment to Eliminate the Use of the Term Core Aleration in the Technical Specifications)