Category:Code Relief or Alternative
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Category Used between: 31 May 2001 to 22 December 2025
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Agency
Pages in category "Code Relief or Alternative"
The following 200 pages are in this category, out of 2,675 total.
(previous page) (next page)1
- 1CAN041801, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period
- 1CAN071202, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period
2
- 2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
- 2CAN021002, Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps
- 2CAN071902, Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping
- 2CAN111101, Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-007
3
- 3F0309-06, Submittal of Relief Request 09-001-IT, Revision 0
- 3F0412-08, Relief Request (RR) 12-001-MX Revision 0, Approval to Use ASME Code Case N-791 for Containment Repair
- 3F0907-05, Relief Request 07-003-RR, Revision 1, and Response to Request for Additional Information
- 3F0912-08, Relief Request 11-001-MX, Revision 0, Commitment to Submit Alternate Surveillance Requirements Per 10 CFR 50.55a(a)(3)(i)
A
- AEP-NRC-2008-25, Use of Weld Inlays as an Alternative Repair Technique for Reactor Vessel Safe End-to-Primary Nozzle Alloy 82/182 Welds
- AEP-NRC-2009-26, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examination - Relief Request ISIR-30
- AEP-NRC-2009-52, Third and Fourth Ten-Year Interval Inservice Inspection Program Relief Request ISIR-31
- AEP-NRC-2011-23, Relief Requests for Limited Coverage Examinations Performed in the Third 10-Year Inspection Interval
- AEP-NRC-2015-31, Submittal of 10 Cer 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval
- AEP-NRC-2018-20, Request for Alternative from Volumetric/Surface Examination Frequency Requirement of ASME Code Case N-729-4, Request Number Isir 04-5, Revision 1
- AEP-NRC-2018-33, Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination
- AEP-NRC-2020-65, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-04
B
- B18946, Inservice Inspection Program Alternative Request RR-89-42 for the Inspection of Pressure-Retaining Surfaces of the Reactor Vessel Bottom Head Area
- BSEP 02-0175, Inservice Inspection Program Relief Request - Service Water System Piping Through-Wall Flaw
- BSEP 03-0069, Withdrawal of Inservice Inspection Program Relief Request for Service Water System Piping Non-Code Repair
- BSEP 05-0063, Relief Request VRR-15, Emergency Diesel Generator Service Water Check Valves
- BSEP 17-0104, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination
- BSEP 18-0040, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test
- BVY 05-071, Clarifications to Relief Request RI-01 Table
- BVY 07-017, Relief Request No. ISI-PT-01, Alternate Pressure Testing for Buried Piping Components, Fourth Inservice Inspection Interval
- BVY 13-018, Inservice Inspection Program for the Fifth Ten-Year Interval
- BYRON 2005-0132, Inservice Inspection Program Relief Request I3R-01
C
- CNL-14-139, Request for Alternative ISPT-03
- CNL-18-078, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Second Ten Year Interval Request for Relief for 1-ISI-21
- CNL-19-068, Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for
- CNL-22-081, Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12
- CNL-22-101, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01
- CNRO-2002-00001, Letter of Intent Re Proposed Alternatives to ASME Code Requirements
- CNRO-2002-00017, Proposed Alternative to ASME Code Requirements for Weld Repairs
- CNRO-2002-00053, Entergy Operations, Inc., Request to Use Alternate Testing Frequency for Inservice Testing Dated 11/22/2002
- CNRO-2002-00059, Request for Use of Non-ASME Code Repair to Standby Service Water Piping in Accordance with NRC Generic Letter 90-05
- CNRO-2003-00022, Relief, Proposed Alternatives to Requirements for Repairs Penetration Nozzles ASME Weld Repair and Examination Performed on Reactor Vessel Head
- CNRO-2003-00062, Request for Relief from ASME Section XI Volumetric Examination Requirements
- CNRO-2003-00063, Arkansas, Unit 1 - Requests for Relief from ASME Section XI Volumetric Examination Requirements
- CNRO-2004-00022, Arkansas Unit 1, Proposed Alternative to ASME Weld Examination Requirements for Repairs Performed on Reactor Vessel Head Penetration Nozzles
- CNRO-2004-00068, Requests for Alternative R&R-005 and R&R-006 - Review of NRC Safety Evaluation for Proprietary Information
- CNRO-2004-00073, Withdrawal of Relief Requests RBS-ISI-001, RBS-ISI-002, and RBS-ISI-003
- CNRO-2005-00036, Request for Alternative to 10 CFR 50.55a Examination Requirements of Category B1.11 Reactor Pressure Vessel Welds
- CNRO-2006-00010, Revised Request for Alternative to 10 CFR 50.55a Examination Requirements of Category B1.11 Reactor Pressure Vessel Welds
- CNRO-2006-00022, Arkansas, Unit 1 - Request for Alternative ANO1-PT-001, Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests
- CNRO-2006-00024, Request for Alternative ANO-ISI-005, Proposed Alternative to Extend the Third Inservice Inspection Interval for Reactor Vessel Inservice Examinations
- CNRO-2006-00025, Arkansas, Unit 1 - Request for Alternative ANO1-ISI-006, Proposed Alternative to Extend the Third Inservice Inspection Interval for Reactor Vessel Examination Category B-F Weld Examinations
- CNRO-2006-00041, Arkansas, Unit 1 - Request for Alternative ANO1-ISI-006, Proposed Alternative to Extend the Third Inservice Inspection Interval for Reactor Vessel Examination Category B-F Weld Examinations
- CNRO-2007-00027, Request for Alternative W3-ISI-004 Proposed Alternative to Second Interval ISI Examinations
- CNRO-2008-00035, Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 805
- CNRO-2009-00001, Relief Requests for Third 120 Month Inservice Inspection Interval
- CNRO-2009-00003, Letter from Entergy Response to Request for Additional Information Regarding Request ISI-2008-1 Use of Later ASME Section Xl Code Edition and Addenda for Repair and Replacement, Pressure Testing, and Non Destructive Examination Activ
- CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D
- CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1
- CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1
- CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
- CNS-15-062, Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2)
- CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing
- CP-200800927, (Cpnpp), Relief Request B-8 for Unit 1 Second 10 Year ISI Interval & B-6 for Unit 2 Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Reactor Vessel Hot & Cold Leg Nozzle Weld Examinations (Unit 1 Second Interval Start
- CP-200801132, Relief Request No. P-2 for the Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval)
- CP-200901227, Revision to Request for Relief to Extend the Unit 1 and 2 in Service Inspection Interval for the Reactor Vessel Weld Examination and Withdrawal of License Amendment Request 09-004 to Add License Condition for Submittal of ISI Informatio
- CP-201000890, Relief Request No. C-7 for the Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000)
- CP-201001544, Relief Request No. C-9 for the Second 10 Year Interval from 10 CFR 50.55a Inspection Requirements Due to Hardship (Second Interval Start Date: August 13, 2000)
- CP-201001546, Relief Request No. B-11 for the Second 10 Years ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000)
- CP-201201384, Response to Request for Additional Information for Relief Request No. E-1
- CP-201300003, Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010)
- CP-201500671, Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3
- CP-202000261, Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests
- CP-202000262, Snubber Testing and Snubber Visual Examinations Relief Request
- CPSES-200203345, Relief Requests A-3, A-4 Rev 1, & A-5 Rev 1 to the Inservice Inspection (ISI) from 1986 Edition of ASME Code, Section XI, No Addenda (Interval Start Date: August 13, 2000, Second Interval)
- CPSES-200203451, Relief Requests A-5 Rev 2 to the Unit 1 Inservice Inspection (ISI) from 1986 Edition of ASME Code, Section XI, No Addenda (Interval Start Date: August 13, 2000, Second Interval)
- CPSES-200203940, Relief Request B-3 for Second 10 Year ISI Interval from 10 CFR 50.55a Requirements for Class 1 the Repair/Replacement of CRDM Canopy Seal Weld (Interval Start Date: August 13, 2000, Second Interval)
- CPSES-200301005, Relief Request C-2 for the Second 10 Year ISI Interval for Unit 1 and C-7 for the First 10 Year ISI Interval for Unit 2 from 10 CFR 50.55a for the Purpose of Invoking Code Case N-562-1
- CPSES-200402110, Relief Request B-4 for the Second 10 Year ISI Interval for Unit 1 and B-1 for the Second 10 Year ISI Interval for Unit 2 from 10 CFR 50.55a for the Purpose of Invoking Code Case N-566-2, Corrective Action
- CPSES-200600636, Relief Request A-6 to the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 13, 2000, Second Interval)
- CPSES-200600994, Inservice Inspection Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 13, 2000, Second Interval)
D
- DCL-06-069, Residual Heat Removal Weld RB-119-11 - Flaw Analytical Evaluation Results
- DCL-07-032, Response to NRC Request for Additional Information Regarding ASME Section XI Inservice Inspection Program Relief Requests NDE-SLH U2 and NDE-LSL U2
- DCL-13-038, ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R18 to Allow Use of Alternative Depth Sizing Criteria
- DCL-15-075, Relief Request REP-SI - Supplement
- DCL-15-086, ASME Section XI Inservice Inspection Program Request for Relief PRS-3
- DCL-15-118, Response to NRC Request for Additional Information Regarding Relief Request FLIG-U1
E
- ET 02-0048, Supplemental Information for Inservice Inspection Program Alternative for Limited Examination on Feedwater Nozzle to Steam Generator Shell Weld, Relief Request L2R-23
- ET 05-0027, CFR 50.55a Request Number I2R-33 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds
- ET 06-0027, Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-34, I2R-35, and I2R-36
- ET 06-0029, CFR 50.55a Request, Use of Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-5222
- ET 12-0010, 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds
G
H
- HL-6261, Third 10-Year Interval Inservice Testing Program, Revision to Existing Relief Request RR-V-11
- HNP-05-128, Relief Request from Inservice Inspection Program No. 2R1-015 Alternative to ASME Code Section XI, IWA-4000 Requirements
- HNP-07-073, Withdrawal of the Relief Request from ASME Code Inservice Testing Requirements for the Second 10-Year Interval
- HNP-08-045, Second Ten-Year Interval Inservice Inspection Program-Final Documentation Including Requests for Relief in Accordance with 10 CFR 50.55a
- HNP-12-054, Relief Request I3R-09 Reactor Vessel Closure Head Nozzles Inservice Inspection Program - Third Interval
- HNP-12-060, Relief Request I3R-09 Reactor Vessel Closure Head Nozzle Repairs Inservice Inspection Program - Third Interval, Request for Additional Information Response
- HNP-12-133, Relief Request I3R-10 Spent Fuel Pool Cooling Piping, Request for Additional Information Response
J
- JAFP-02-0194, Proposed Revision of Relief Request VRR-06 for In-Service Testing Program
- JAFP-03-0111, Proposed Alternatives in Accordance with 10CFR50.55a(g)(6)(ii)(A)(5) and Relief from ASME Section XI Code Regarding Inspection of RPV Vertical Shell Welds Pursuant to 10 CFR 50.55a (g)(6)(i)
- JAFP-05-0105, Request for Approval of Relief Request No. RR-38, Proposed Alternative to Perform a Temporary Non-Code Repair in Accordance with 10 CFR 50.55a(a)(3)(ii)
- JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP
- JAFP-15-0122, Withdrawal of Application for Alternative Examination Requirements for James A. FitzPatrick Nuclear Power Plant Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241
- JAFP-18-0052, Proposed Alternative to Utilize Code Case N-879
- JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-880
- JAFP-18-0076, End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval
- JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds
- JPN-02-010, Relief Request RR-28, Revision 1 for the Third 10-Year Inservice Inspection Interval Program Plan
- JPN-02-011, Request for Relief RR-29, Third 10-Year Inservice Inspection Interval Program Plan
- JPN-03-020, Vermont Yankee Nuclear Power Station, Relief, Relief Request to Use ASME Code Case N-600
L
- L-02-023, Updated Interval (Second 10-Year Interval, Third Period and Third 10-Year Interval, First and Second Periods) Request for Relief No. RR-47 from 1989 ASME Code Requirements
- L-03-065, To Reply to Request for Additional Information Regarding Proposed Alternative Repair Methods for Reactor Vessel Head Penetrations
- L-06-042, Proposed Alternative to American Society of Mechanical Engineers Code Section XI Examination Requirements
- L-07-056, Requests Approval of Proposed Alternatives and Relief for Inservice Testing Program Ten-Year Update
- L-08-069, Impractical American Society of Mechanical Engineers Code Section XI Weld Examination Requirements (Request Nos. 1-TYP-3-RA-1, 1-TYP-3-RA-2, 1-TYP-3-RA-3)
- L-08-207, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inspection Period Extension Requirement
- L-08-347, Eight Separate In-Service Testing Program 10 CFR 50.55a Alternatives Requests in Support of the Third Ten-Year Interval
- L-08-362, Beaver, Units 1 and 2, Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Paragraph IWA-5244 Examination Requirements
- L-17-308, 10 CFR 50.55a Request for Alternate Reactor Vessel Nozzle Flaw Depth Sizing Criteria (Request 2-TYP-4-RVSE-2)
- L-17-317, Request to Extend Certain Reactor Vessel Inspections from 10 to 20 Years (Request 1-TYP-4-BN-01)
- L-19-107, Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements
- L-19-145, 10 CFR 50.55a Request in Support of the Fourth 10-Year Inservice Inspection (ISI) Interval
- L-20-060, CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency
- L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency
- L-20-117, 10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections
- L-20-118, CFR 50.55a Request Number SRR-1, Revision 0, Snubber Testing
- L-20-256, Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
- L-2002-044, Resubmittal of Code Relief Requests Nos. 30 & 31, Relief Request No. 30 Revised to Remove Reference to ASME Section IX, Paragraph QW-424
- L-2002-085, Alternative Examination for Reactor Pressure Vessel Nozzle Inner Radius Re-submittal of Relief Request No. 25
- L-2002-178, In-Service-Inspection Plan Unit 1 Third Ten-Year Interval & Unit 2 Second Ten-Year Interval Contingency Reactor Vessel Head Penetration Weld Repair and Flaw Evaluation Relief Requests
- L-2003-014, Inservice Inspection Program Second Ten-Year Interval Relief Request 35 Early Use of ASME Code Case N-533-1
- L-2003-063, ASME Section XI Relief Request No. 33, Alternative Requirements for Implementation of Appendix Viii, Supplement 10
- L-2003-116, In-Service-Inspection Plan Second Ten-Year Interval Relief Request 37
- L-2003-187, Relief Request 19 Risk-Informed Inservice Inspection Program
- L-2004-164, ASME Section Xl Relief Requests Nos. 34 and 35 Alternative Through-Wall Sizing Requirements and Alternative Ultrasonic Examination for Reactor Flange to Upper Shell Welds
- L-2007-144, Submittal of Fourth Ten-Year Interval In-Service-Test Program
- L-2007-195, Inservice Inspection Plan Fourth Ten-Year Interval Unit 1 Relief Request 1
- L-2010-001, Inservice Inspection Plan, Fourth Ten-Year Interval Relief Request No. 6
- L-2012-193, Concrete Containment Inservice Inspection Program, Exempt Tendon Inspection Relief Request No.7
- L-2012-381, Fourth Ten-Year Interval, Relief Request No. 10
- L-2017-050, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 5
- L-2017-112, Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 17, Revision 0
- L-2017-113, Inservice Inspection Plan, Fourth Ten-Year Interval Unit 1 Relief Request No. 16, Revision 0
- L-2017-121, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography
- L-2017-183, Fifth 10-Year Inservice Testing (IST) Program Interval Relief Requests PR-01 Through PR-06, and PR-09,
- L-2018-188, Inservice Inspection Plan - Fifth Ten-Year Interval Unit 1 Relief Request 6
- L-2020-002, Fifth 10-Year Inservice Inspection (ISI) Interval Relief Request (RR) 2 and St. Lucie Unit 2 Fourth 10-Year ISI Interval RR 5, Proposed Alternative for the Reactor Pressure Vessel (RPV) Bolting Examination Schedule Change Due .
- L-2020-160, Extension of St. Lucie Unit 2 RPV Welds from 10 to 20 Years
- L-2021-107, Fifth Ten-Year Inservice Inspection Interval Revised Relief Request Nos. 8 and 9 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(l), Extension of Inspection Interval for Turkey Point Units 3 and 4 Reactor Pressure
- L-21-047, 10 CFR 50.55a Request Numbers VR-3 and VR-5, Valve Testing Extension
- L-HU-05-028, ASME Section XI, ISI Request for Relief 21 & 22
- L-MT-03-001, Relief Request No. Pr 06 for Fourth 10-Year Inservice Testing Interval - High Pressure Coolant Injection Pump Testing
- L-MT-03-045, Request for Approval of Inservice Inspection Program Third 10-Year Interval Relief Request No. 17
- L-MT-03-048, Request for Authorization of Inservice Inspection Program Fourth 10-Year Interval Relief Request No. 8
- L-MT-05-074, Request to Use Subsequent Edition and Addenda of ASME Code for Inservice Testing
- L-MT-10-014, Request 10 CFR 50.55a Request 17: Extension of Permanent Relief from Volumetric Examination of Reactor Pressure Vessel Circumferential Shell Welds for the Renewed Operating License Term
- L-MT-15-083, 10 CFR 50.55a Request No. RR-010: Request for Approval of an Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection
- L-MT-18-023, 10 CFR 50.55a Request RR-012: Inservice Inspection Impracticality in Accordance with 10 CFR 50 .55a(g)(5)(iii) During the Fifth Ten-Year Interval
- L-PI-04-044, Request for Relief No. 20, Revision 0, for Units 1 & 2, 3rd Ten Year Inservice Inspection Interval
- L-PI-05-038, Withdrawal of 4th Ten-Year Inspection Interval Inservice Lnspection Program Relief Request No. 1-RR-4-1
- L-PI-14-117, Withdrawal of 10 CFR 50.55a Request RR-01 Associated with the Fifth Ten-Year Interval for the Inservice Test Program (TAC Nos. MF3928 and Mf 3929)
- L-PI-19-002, 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals for Prairie Island, Unit 1 and Unit 2
- LIC-02-0142, Relief Requests Pertaining to the Fort Calhoun Inservice Inspection (ISI) of the Reactor Pressure Vessel (RPV) for the Third Ten Year ISI Interval (1993-2003)
- LIC-03-0062, Relief Request Pertaining to Visual Inspection of Inaccessible Piping & Components
- LIC-04-0008, Relief Request Pertaining to Reactor Vessel Nozzle Inspections for the Third 10-Year Interval, Revision
- LIC-15-0066, Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds
- LIC-15-0086, Supplement to License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section III, 1980 Edition (No Addenda) as an Alternative to Current Code of Record
- LIC-15-0089, Submits Relief Requests Associated with the Fifth Inservice Testing Interval
- LIC-15-0114, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI
- LR-N04-0473, Relief Request SC-13-RR-A14 Synchronization of Salem Units 1 and 2 ISI Programs Ten-Year Inservice Inspection Intervals
- LR-N05-0446, ASME Code Relief Request Salem Units 1 and 2
- LR-N09-0126, Relief Requests to Extend the Inservice Interval for Reactor Vessel Weld Examination
- LR-N10-0380, Request for Authorization to Continue Using a Risk-Informed Inservice Inspection Alternative to the ASME Boiler and Pressure Vessel Code Section XI Requirements for Class 1 and 2 Piping
- LR-N12-0157, Submittal of Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval Code Edition
- LR-N18-0087, Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) Interval
- LR-N19-0083, Request for Relief S1-I4R-191 from Alloy 690 PWR Reactor Vessel Head Inspection Interval, Fourth 10-year Interval
- LR-N19-0084, Proposed Alternative for Examination of ASME Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections, Per Inservice Inspection Relief Request SC-I4R-192
- LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping