Category:Request for Code Relief or Alternative
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Category Used between: 5 August 2020 to 16 October 2025
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Agency
Pages in category "Request for Code Relief or Alternative"
The following 200 pages are in this category, out of 261 total.
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- 0CAN012502, Proposed Alternative ANO1-ISI-24-02 and ANO2-ISI-24-02 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds
- 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)
- 0CAN112001, Relief Request No. EN-20-RR-001, Revision 1 - Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in Class 2 and 3 Systems, Section XI, Div 1
- 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)
1
- 1CAN042102, Relief Request ANO1-ISI-026
- 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035
- 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)
- 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period
2
- 2CAN012302, Enclosure 2: Relief Request ANO2-RR-23-001
- 2CAN102102, Relief Request ANO2-R&R-012: Support the Repair of the Reactor Vessel Closure Head Penetration 46
- 2CAN112001, Request for Alternative to 10 CFR 50.55a(g)(6)(ii)(D) Examination Requirements - Relief Request ANO2-ISI-022
- 2CAN112103, Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46
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- CNL-20-077, Supplement to Watts Bar Nuclear Plant (WBN) Unit 1 - American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative IST-RR-8
- CNL-21-037, Request for Alternative, 21-ISI-1 Alternative Repair and Examination for Mid Canopy Seal Weld Replacement
- CNL-21-059, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-10
- CNL-21-081, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(b) and the Use of Case N-526
- CNL-22-002, Request for Relief from American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, in Accordance with 10 CFR 50.55a(g)(5)(iii) and 50.55a(g)(6) (BFN-2-ISI-003)
- CNL-22-009, Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In.
- CNL-22-024, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02
- CNL-22-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32
- CNL-22-049, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternatives RP-11 (SQN) and IST-RR-9 (WBN)
- CNL-22-079, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12
- CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval
- CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request
- CNL-24-072, Request for Alternative to Extend First Containment Inservice Inspection Interval
- CNL-25-033, Revision to Sequoyah Nuclear Plant, Units 1 and 2 American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02
- CNL-25-040, Tennessee Valley Authority - American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems, Section XI, Division 1, Request for Alternative
- CNL-25-060, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-03
- CNL-25-071, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-05
- CNL-25-103, Request for Exemptions from 10 CFR 50.55(a)(3)(iii) and 10 CFR 50.55a(y) for Adoption of Code Case OMN-31
- CP-202000431, Relief Request 1A4-1 Supplement - Reactor Vessel (Rv) Upper Head Examinations
- CP-202100143, (CPNPP) - Relief Request 1A4-3 for Continued Use of a Risk-Informed Process as an Alternative for the Selection of Class 1 and 2 Piping Welds for Unit 1 Inservice Inspection
- CP-202200041, (CPNPP) - Supplement to ASME OM Inservice Test Program Relief Request SNB-3, Snubber Inservice Program Third Interval Extension
- CP-202200276, (CPNPP) - Relief Request Application P-1, Inservice Testing (IST)
- CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality
- CP-202400358, Vistra Operations Company, LLC - Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section
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- DCL-24-066, Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL
- DCL-25-002, Proposed Alternative to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems, Section XI, Division 1
- DCL-25-011, ASME Section XI Inservice Inspection Program Request for Alternative NDE-RCSSE- 2R25 Use of Alternate Sizing Qualification Criteria Through a Protective Clad Layer
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- ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen
- ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components
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- L-2021-184, Relief Request Number 19 - Request for an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85
- L-2021-231, Relief Request Number 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety
- L-2022-035, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II
- L-2022-051, Fifth Ten-Year Inservice Inspection Interval Relief Request No. 10 Part-II, Supplement Information and Response to Request for Additional Information
- L-2022-079, Supplement to Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal.
- L-2023-034, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
- L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval
- L-2023-099, Pump Relief Request 10 (PR-10), One-Time Request for an Alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code for the Auxiliary Feedwater (AFW) 2C Pump
- L-2023-102, Relief Request PSL2-15-RR-01, Proposed Alternative to ASME Section XI Code Examination Requirements for Reactor Vessel Bottom Area and Piping in Covered Trenches
- L-2025-029, Relief Request (RR) 11 and 12, Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fifth Ten-Year Inservice Inspection Program Interval
- L-2025-058, Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160R1 Examination Schedule
- L-21-259, 10 CFR 50.55a Requests Number VR-10 and VR-11, Inservice Valve Testing
- L-21-280, 10 CFR 50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirements
- L-21-282, Proposed Inservice Inspection Alternative IR-063
- L-25-024, 10 CFR 50.55a Request BV-ISI-2025-01, Quench Spray Pinhole Leak
- L-MT-20-031, 10 CFR 50.55a Request No. RR-018, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
- L-MT-21-013, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval PR-04 (L-MT-21-013)
- L-MT-21-039, 10CFR50.55a Request Associated with the Sixth Inservice Testing Ten-Year Interval (L-MT-21-039)
- L-MT-21-040, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-01 (L-MT-21-040)
- L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)
- L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency
- L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program
- L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09
- L-PI-25-041, CFR 50.55a Request Nos. 1-RR-5-16 and 2-RR-5-16, Proposed Alternative to Conditions for Applying Code Case N-513-5, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping and Gate
- LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations
- LR-N22-0005, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs
- LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations
- LR-N24-0044, Relief Request VR-04
- LR-N25-0031, Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
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- ND-22-0199, Revision to Request for Alternative: Alternative Requirements for Inservice Test Interval Code Edition, Unit 4 (VEGP 3&4-IST-ALT-01R2)
- ND-22-0242, Request for Alternative: Alternative Requirements for Main Turbine System Valve Testing (VEGP 3&4-IST-ALT-02)
- NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement
- NL-24-0060, Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03)
- NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in
- NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)
- NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002
- NL-24-0421, Submittal of the Inservice Testing Program Alternative Requests and Relief Requests for Pumps and Valves - Sixth Ten-Year Interval
- NL-25-0045, Proposed Inservice Inspection Alternative FNP-ISI-ALT-2025-10 for Containment Unbonded Post-Tensioning System Inservice Inspection Requirements in Accordance with 10 CFR 50.55a(z)(1) (NL-25-0045)
- NL-25-0111, VEGP3-4-ISI-ALT-2025-01, Request for Use of a Later Edition of the ASME Section XI Boiler and Pressure Vessel Code for Inservice Inspection (NL-25-0111)
- NL-25-0152, Propoosed Inservice Alternative FNP-ISI-ALT-05-13 for Reactor Vessel Bottom Head Inspection
- NL-25-0313, Request for Authorization of Inservice Testing Alternative to ISTC-3700 and Inservice Testing Alternative to Adopt Code Case OMN-32
- NLS2021032, 10 CFR 50.55a Relief Request RI5-02, Revision 3, and RRS-01, Revision 1
- NMP1L3366, Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting
- NMP1L3454, Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps
- NMP1L3485, Proposed Alternative Associated with a Weld Overlay Repair to the Torus
- NMP1L3518, Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1
- NMP1L3519, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
- NMP1L3526, Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication
- NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
- NMP1L3612, Constellation Energy Generation, LLC - Relief Request for Alternative to Examination Category B-G-1, Item B6.20, Reactor Vessel Closure Stud Examinations
- NMP1L3645, Nine Point, Unit 1 - 90-Day Commitment Response - Relief Request 15R-12 Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Wield (32-W
- NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations
- NRC-25-0002, Submittal of Revised IST Valve Relief Request, VRR-003 Rev. 1, for the Fourth Ten Year Interval
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- PLA-7895, Relief Request 4RR-02, Revision 1 (PLA-7895)
- PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062
- PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval
- PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)
- PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)