Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing
Regulatory Guide 1.20# QUERYa09856f98a7b0c244770feea6620ee86
Regulatory Guide 1.20# QUERYdc150cfffe95a28996b7bd124cb14a26
Regulatory Guide 1.20# QUERY2f424dc36dc53148ebe16fe2b866f7dd
Regulatory Guide 1.20# QUERY6e8e6098e14870e6e2c4dfebdb64e5a9

Regulatory Guide 1.20# QUERY63d5ea34e6aa3a2e0bea4e8bf23559a9
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LR-N16-0119, Response to Request for Additional Information Regarding Review of Post-Extended Power Uprate Steam Dryer Stress Calculation Acoustic Circuit Model Software Error
CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates
NRC-15-0031, Response to NRC Request for Additional Information for the Review of the License Renewal Application - Sets 23, 24, and 26
L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan
L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE
GNRO-2012/00071, Response to Request for Additional Information (RAI) Dated June 5, 2012
NUREG-2123 Volume 2, Safety Evaluation Report Related to the License Renewal of Columbia Generating Station
NOC-AE-12002802, Response to Requests for Additional Information for the License Renewal Application, Aging Management Program, Set 13
L-MT-11-004, Extended Power Uprate: Replacement Steam Dryer - Initial Response to Request for Additional Information
NOC-AE-11002742, Response to Requests for Additional Information for the License Renewal Application
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 14, Initial Test Program
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 10.3 Through Section 15.1
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3.7.B.2-27 Through 3D-17
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 14 - Initial Test Program
NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 14
NL-15-169, NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 14.0 - Initial Test Program
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 14 - Initial Test Program
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
L-MT-10-072, Extended Power Uprate: Updates to Docketed Information
NRC 2010-0136, License Amendment Request 261 Extended Response to Request for Additional Information
NRC 2010-0063, License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information
LR-N08-0224, Attachment 6 - Hope Creek Final Stress Assessment of Hope Creek, Unit 1 Steam Dryer at 115% CLTP Conditions, C.D.I. Report No. 08-21NP, Revision 1
NLS2008097, Startup Test Report for Measurement Uncertainty Recapture Power Uprate
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 3.0 - Design of Structures, Components, Equipment, and Systems
RAIO-0418-59424, LLC Supplemental Response to NRC Request for Additional Information No. 185 (Erai No. 8963) on the NuScale Design Certification Application
RAIO-0218-58628, LLC - Response to NRC Request for Additional Information No. 296 (Erai No. 9231) on the NuScale Design Certification Application
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
RAIO-1218-63846, LLC Supplemental Response to NRC Request for Additional Information No. 340 (Erai No. 9358) on the NuScale Design Certification Application
RAIO-0518-59932, LLC - Submittal of Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the Design Certification Application
RAIO-0218-58728, LLC Supplemental Response to NRC Request for Additional Information No. 149 (Erai No. 8955) on the NuScale Design Certification Application
RAIO-0318-59292, LLC - Response to NRC Request for Additional Information No. 354 (Erai No. 9359) on the NuScale Design Certification Application
RAIO-0719-66436, LLC Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application
RAIO-0719-66435, LLC Response to NRC Request for Additional Information No. 194 (Erai No. 8884) on the NuScale Design Certification Application
ND-18-0709, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.03.07.1 (Index Number 78)
NL-20-0458, Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate
IA-92-296, NRC Staff Rept on Union of Concerned Scientists Petition for Emergency & Remedial Action
BSEP-98-0118, Forwards Summary of Results of Evaluations of Cracking Found on Bsep,Unit 1,jet Pump Riser Thermal Sleeve Extension to Elbow Welds.Evaluations Justify Unrestricted Operation for 24-month Fuel Cycle
NSD-NRC-97-5402, Summarizes Breaks That Need to Be Considered for AP600 as Result of LBB Evaluations Performed Re Pipe Rupture Analysis.Pipe Rupture LOCA Dynamic Transient Limiting Case Analysis,Encl
NSD-NRC-97-4989, Requests Responses to NRC Request for Addl Info & Updates of Status for Several Areas Being Reviewed by Ecgb & Emeb for AP600
RBG-21727, Informs That flow-induced Vibration Testing of Reactor Pressure Vessel Internals Conducted & Results Available in Preoperational Test Procedure 1-PT-50,per Util
NSD-NRC-96-4857, Forwards Responses to NRC Mechanical Engineering Branch Questions Including high-energy Line Break
ND-21-0956, ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.07.i (Index Number 78)
AECM-86-0054, Forwards Proprietary NEDC-31148P, Grand Gulf Unit 1,Reactor Internals Vibration Measurements... & EqDE-06-0286, Grand Gulf Unit 1 Reactor Internals..., Per Reg Guide 1.20 Requirements.Affidavit Encl.Repts Withheld (Ref 10CFR2.790)
ST-HL-AE-1296, Summarizes 850626 Meeting W/Nrc Mechanical Engineering Branch in Houston,Tx Re Mechanical Design.Encl Responses to FSAR Questions 210.18 Through 210.65 Will Be Incorporated Into FSAR Amend 50
NSD-NRC-96-4841, Submits Responses to 961003 Telcon Re NRC Mechanical Engineering Branch Questions Related to Qa,Reactor Vessel Internal Vibration,Crdms & Equipment Seismic Qualification
ET-NRC-93-3795, Forwards Responses to NRC RAIs on AP600 from Ltrs 920923, 1001 & 09.Remainder of RAIs Contained in NRC Ltrs of 920923 & 1001 Will Be Provided Prior to 930123
B11111, Forwards Response to Draft SER Open Items
RBG-16-672, Forwards Response to Draft SER Open Items Identified by NRC Mechanical Engineering Branch & Response to NRC Requesting Further Clarification on Design of Pipe/Component Supports
NRC-95-4405, Forwards Responses to NRC RAIs on AP600 from Ltrs of 940818 & 0902.Revs of Responses Previously Submitted Also Provided
NRC-94-4337, Forwards Responses to NRC Requests for Addl Info on AP600 from NRC Ltrs of 940429,0714,0818 & 0902.Responses Associated W/Nrc 940429 & 0714 Ltrs Complete
NRC-94-4184, Forwards Responses to NRC RAIs on AP600 from NRC 940316, 0419,29,0502,11,12,23 & 26 Ltrs.Revs of Responses Previously Submitted Also Provided,Completing Responses for NRC
NRC-94-4257, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs of 940415,29,0502,05,18,23,24,26 & 0608.Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
LD-93-012, Forwards Draft Sys 80+ Certified Design Descriptions & Associated ITAAC
LD-93-014, Forwards Addl Certified Design Descriptions & ITAAC for Sys 80+
PY-CEI-NRR-0394, Forwards Comments on Draft Ol,Proposed Items to Be Completed After Fuel Load & Updated Fsar,App 1B.NRC Evaluations & Conclusions Will Be Documented in Ssers 7 & 8
PY-CEI-NRR-0842, Forwards Proprietary NEDE-31567-P, Perry 1 Reactor Internals Vibration Measurements. Rept Withheld (Ref 10CFR2,790).Affidavit Encl
PY-CEI-NRR-0771, Forwards Reactor Internals Vibration Testing at Perry Unit 1, Preliminary Rept,Per Reg Guide 1.20
PY-CEI-NRR-0333, Forwards Proposed FSAR App 1B, License Commitments, Including Shift Operating Experience,Tmi Item I.G.1, Inservice Insp Program Reg Guide 1.97,per SER Commitments. Generic Conditions Not Included
LD-85-009, Forwards Proprietary & Nonproprietary Comprehensive Vibration Assessment Program for Palo Verde Nuclear Generating Station Unit 1 (Sys 80 Prototype),Evaluation of Predictions.... Proprietary Rept Withheld (Ref 10CFR2.790)
LD-92-021, Forwards Response to NRC 910806 & 1010 Requests for Addl Info,In Ref to Review of CESSAR Design Certification, Including Corresponding Revs
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
PY-CEI-NRR-1288, Forwards Proprietary NEDE-31567-P,addendum, Addendum to Perry 1 Reactor Internals Vibration Measurements (In-Core Guide Tube Fatigue Usage During Single Loop Operation). Encl Withheld (Ref 10CFR2.790)
ND-23-0588, ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.07.i (Index Number 78)
GO2-24-036, Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate
RS-24-116, Attachment: GE-Hitachi Affidavit / Pre-Application Meeting Presentation
NSD-NRC-97-5375, Forwards Response to 970625 RAI Re Listed RAIs & Dser Open Items on AP600 SSAR Chapter 14, Initial Test Program
NSD-NRC-98-5544, Forwards W Responses to Open Item Oits 5321/Q260.93 Re AP600 SSAR Chapter 14, Initial Test Program, Per 980107 Request
NSD-NRC-97-5133, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period 970416-0502,including Draft of SSAR Markup for LOOP Issue & Open Item Status
NSD-NRC-96-4772, Forwards Draft Rev to Section 14.2 of AP600 SSAR Addressing AP600 Initial Test Program
AECM-80-183, Submits Revised Responses Per Discussions at Mechanical Engineering Branch & Bnwl 800708-10 Meeting to Resolve Draft SER Open Items.Addl Info Will Be Provided by Separate Ltr
RAIO-1018-62201, LLC Supplemental Response to NRC Request for Additional Information No. 134 (Erai No. 8934) on the NuScale Design Certification Application
RAIO-0119-64103, LLC Supplemental Response to NRC Request for Additional Information No. 164 (Erai No. 8935) on the NuScale Design Certification Application
RAIO-0818-61633, LLC - Supplemental Response to NRC Request for Additional Information No. 128 (Erai No. 8966) on the NuScale Design Certification Application
RAIO-0818-61558, LLC Supplemental Response to NRC Request for Additional Information No. 110 (Erai No. 8932) on the NuScale Design Certification Application
RAIO-0618-60666, LLC - Response to NRC Request for Additional Information No 452 (Erai No. 9518) on the NuScale Design Certification Application
L-82-515, Confirms 821112 Telcon Agreement W/Util to Discontinue Hot Functional Testing of Reactor Vessel Internals Intended Solely to Increase Vibratory Cycles on Plant
LD-82-064, Forwards Proprietary & Nonproprietary Comprehensive Vibration Assessment Program for Prototype Sys 80 Reactor Internals,Palo Verde Nuclear Generating Station,Unit 1. Proprietary Version Withheld (Ref 10CFR2.790)
NRC-16-0014, Comments on the NRCs Safety Evaluation Report with Open Items Related to the License Renewal
L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report
NRC-15-0010, Response to NRC Request for Additional Information for the Review of License Renewal Application - Set 16
RAIO-0818-61360, LLC - Response to NRC Request for Additional Information No. 410 (Erai No. 9310) on the NuScale Design Certification Application
RAIO-1018-62208, LLC Supplemental Response to NRC Request for Additional Information No. 110 (Erai No. 8932) on the NuScale Design Certification Application
LR-N08-0199, Attachment 5 - C.D.I. Report.No. 08-29NP, Rev. 0, Final Stress Assessment of Hope Creek Unit 1 Steam Dryer at 111.5% CLTP Conditions
LR-N08-0033, CDI Report No. 07-17NP, Revision 4, Stress Assessment of Hope Creek Unit I Steam Dryer Based on Revision 4 Loads Model
LD-88-033, Forwards Response to NRC 880226 Request for Addl Info on Chapter 17 to Rev 4 to Topical Rept CENPD-210A, QA Program, Including Revs to C-E 871130 & 880411 Responses
AECM-88-0186, Application for Amend to License NPF-29,changing Tech Specs to Add Alternate DHR Sys.Fee Paid
PMNS20250694, Notice of pre-submittal Meeting Between Southern Nuclear Operating Company (Snc), General Electric (Ge), and NRC Regarding SNCs Proposed License Amendment Request (LAR) for an Extended Power Uprate (EPU) and a Steam Dryer Replacement