LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 7, Instrumentation and Controls
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
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, Chapter 1, Introduction and General Description of Plant
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 14.0 - Initial Test Program
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
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
NRC Generic Letter 79-05, Information Relating to Categorization of Recent Regulatory Guides by the Regulatory Requirements Review Committee
RAIO-0318-59292, LLC - Response to NRC Request for Additional Information No. 354 (Erai No. 9359) on the NuScale Design Certification Application
BECO-89-100, Submits Revised Plant Power Ascension Program as Previously Submitted by Util .Phase One Demonstration Proved Ability of Personnel,Procedure & Equipment to Accomplish Reactor Shutdown & Controlled Cooldown Outside Control Room
B12015, Forwards Changes to Initial Test Program,Per License Condition 2.C(10).Requirement for Reactor Trip Test at 50% Plateau & Ref to pseudo-ejected Rod Test Deleted & Note to Test 25 Added.Changes Will Be Included in FSAR Amend
RBG-23078, Forwards Description & Safety Evaluation of Changes to Initial Test Programs ST-13 & ST-30 Re NSSS Process Computer Performance & Control of Reactor Vessel Pressure & Water Level Outside Control Room,Respectively
ST-HL-AE-1458, Forwards Response to Draft SER & FSAR Items,Including Testing of Remote Shutdown Operation,Insp of New Fuel & Central Assemblies Upon Receipt & Physical Security Plan. Marked-up FSAR Pages Will Be Incorporated in FSAR Amend
NSD-NRC-96-4902, Forwards Response to Staff Comments on AP600 Test Program
NSD-NRC-96-4800, Forwards Responses to RAI & Open Items Contained in Nov 1994 Draft SER on AP600
ST-HL-AE-1186, Forwards Revised FSAR Chapter 14.2,including Preoperational & Initial Test Summaries & Associated Revised Responses to NRC Questions 423.1 - 423.35,for Review & Approval
RBG-16-356, Forwards Responses to Draft SER Open items,w/marked-up FSAR Pages.Changes Will Be Incorporated Into Next FSAR Amend
B10876, Forwards Responses to Agenda Items from 830626-28 Meetings W/Nrc & S&W in Boston,Ma Formalizing Commitments Made Orally at Meeting.Response to Addl Items Will Be Submitted by 831215.Info Will Be Incorporated Into FSAR Amend
NRC-94-4305, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs of 940429,0523,24,0615 & 0815. Responses Provided as Electronic Files Wordperfect 5.1 Format W/Kenyon Copy
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
TXX-9214, Forwards Advance FSAR Submittal Re Changes to Unit 2 Initial Startup Test Program.Changes Proposed as Result of Experience Gained in Performance of Unit 1 Initial Startup Program
TXX-9231, Responds to NRC 920622 Request for Addl Info Re Startup Testing Program.Draft Sections of Startup Testing Program Encl
LD-84-070, Forwards Proposed Changes to CESSAR Re Startup Testing for Review.Changes Currently in FSAR Change Process & Will Be Incorporated in CESSAR Amend 10
W3P84-1607, Suppls & Discusses R Beker Concerns Re Questions 640.17-22.FSAR Changes Which Will Be Implemented in Future Amend Per 10CFR50.71(e) Requirements
NSD-NRC-98-5609, Forwards Three Copies of W Response to Open Item (Oits) 6636/Q260.140F Re AP600 SSAR Chapter 14, Initial Test Program. Response to Open Item Includes Responses to Listed Dser Open Items of Same Ltr
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-98-5539, Forwards Westinghouse Responses to Five Open Items Re AP600 SSAR Chapter 14, Initial Test Program, as Requested in Ltr from Staff
B10909, Forwards Remaining Responses & Corresponding FSAR Changes to 640 Series Questions Not Forwarded by Util . Responses Will Be Formally Submitted Along W/Amend 5 by 831101
RBG-20-994, Forwards Addl Info Requested in a Schwencer to Wj Cahill Re Revs to FSAR Subsections.Revised FSAR Pages Supporting Revs Encl.Revs Will Be Included in Future FSAR Amend
GO2-86-104, Forwards Addl Info Re Fire Protection Program,Per 861020 Request,Including Rev 2 to Emergency Procedure 5.3.6, Reactor Pressure Vessel Flooding (Contingency)
GO2-81-564, Forwards Responses to SER Open Items Re Initial Test Program,To Be Incorporated Into Next FSAR Amend.Meeting to Resolve Disputed Open Items Suggested Prior to 810312 Safety Evaluation
L-83-324, Forwards Resolution of Item I.C Re Remote Shutdown Demonstration Prior to Initial Criticality,Per Region II Request.Item Closed.Requests Region II Be Notified of Concurrence Following Review