Periodic Testing of Protection System Actuation Functions
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W3F1-2017-0010, Response to NRC Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System (Esfas).
W3F1-2017-0018, Supplement to Response to RAI on License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System Subgroup Relays to Surveillance
W3F1-2016-0055, License Amendment Request to Revise Technical Specification 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Features Actuation System (ESFAS) Subgroup Relays to the Surveillance Frequency Control Program
W3F1-2017-0067, License Amendment Request to Remove Technical Specification 3/4.3.2 Table 4.3-2 Note 3 Exemption for Testing Relays K114, K305, and K313
LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation
CNL-14-107, Response to NRC Request for Additional Information Related to Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02)
NL-14-0635, License Amendment Request to Revise Technical Specifications Reactor Trip System Instrumentation
DCL-14-036, Response to Request for Additional Information on License Amendment Request for Digital Process Protection System Replacement
3F0413-03, Attachment C, Off-Site Dose Calculation Manual, Revision 34
CP-201201129, License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
1CAN051201, License Amendment Request New Technical Specification Governing ANO-1 Emergency Switchgear Room Chiller Trains
ULNRC-05654, Proposed Revision to Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, (License Amendment Request LDCN 09-0040)
NL-11-1057, License Amendment Request for Technical Specification Table 3.3.1-1
LR-N11-0122, Response to Request for Additional Information, License Amendment Request - Operation with Final Feedwater Temperature Reduction and Feedwater Heaters Out-of-Service
CP-201800115, License Amendment Request 17-001 Revision to Technical Specification 3.3.2. ESFAS Instrumentation
LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Appendices 9A and 9B Comparison
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 7
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
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 6 Through Chapter 7
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 15.2
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figure 7.6.5-1 (Sheet 1 of 2) Through Figure 8.3.1-1 (Sheet 4 of 34)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 11
DCL-16-011, Pacific Gas & Electric Co. Diablo Canyon Power Plant Units 1 & 2 Functional Requirements Specification Process Protection System (PPS) Replacement Nuclear Safety-Related,08-0015-SP-001, Rev. 9
NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System
NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 8.0 - Electric Power
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 7.0 - Instrumentation and Controls
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-i - 3.5A-4
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 7 - Instrument and Control Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 7 - Instrumentation and Control Systems
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 8.0 - Electric Power
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 7.0 - Instrumentation and Controls
DCL-12-069, Diablo Canyon, Units 1 and 2 - 08-0015-SP-001, Functional Requirements Specification, Revision 5, Attachment 2
NL-11-1812, Edwin I. Hatch, Unit 2 - 2011 Updated Final Safety Analysis Report, Revision 29, Chapter 6, Engineered Safety Features Through Chapter 7, Instrumentation and Control
ULNRC-05687, Application for Amendment to Technical Specification 3.3.2 Function 6.g Engineered Safety Feature Actuation System, Instrumentation: Auxiliary Feedwater Actuation on Trip of All Main Feedwater Pump (LDCN 10-0011)
TSTF-10-02, Transmittal of TSTF-521, Revision 0, Exclusion of Time Constants from Channel Operation Tests in Specifications 3.3.1 and 3.3.2
NL-09-1431, License Amendment Request for Technical Specification Table 3.3.1-1
ULNRC-05633, Revision of Technical Specification 3.3.9
ULNRC-05608, ULNRC-05608, Revision of Technical Specification 3.3.2 and 3.7.3 (License Amendment Request OL-1289)
CP-200900492, License Amendment Request (LAR) 09-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
NL-09-0154, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11, Reactor Coolant Pump Breaker Position
WM 09-0001, Response to NRC Request for Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
WM 09-0001, Wolf Creek - Response to NRC Request for Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
NOC-AE-08002378, License Amendment Request for Proposed One-time Exigent Change to Technical Specification 3.7.1.7, Main Feedwater System.
ULNRC-05494, Application for Amendment to Facility Operating License NPF-30 OL1283 - Revision of Technical Specifications 3.3, 3.7, and 3.8
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 7.0 - Instrumentation and Control Systems
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 7.0, Instrumentation and Controls
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
B10796, Provides Addl Info Re Util Request for Exemption from 10CFR50,App R Re Control Room Fire Per 830318 Meeting. Alternate Operator Actions Can Be Completed to Facilitate Safe Shutdown Following Fire in Control Boards
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
CPSES-200600591, (Cpses), Revision to Technical Specification 3.8.1, AC Sources Operating
ULNRC-06485, License Amendment Request to Revise Technical Specifications for Testing of Main Turbine Control Slave Relay (LDCN 18-0025)
SBK-L-18089, License Amendment Request 17-06, Change to the Technical Specification Requirements for Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation to Implement WCAP-14333 and WCAP-15376
NL-05-0237, Request to Revise Technical Specifications Reactor Trip System Instrumentation
CPSES-200500155, License Amendment Request (LAR) 04-015 Revision to Technical Specification 3.3.1 Reactor Trip System Instrumentation and 3.3.2 Engineered Safety Feature Actuation System Instrumentation (Esffas)
ET 17-0010, License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C)System
CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
ET 09-0018, Redacted Version of the Wolf Creek, License Amendment Request for Use of Fire-Resistive Electrical Cable
ET 09-0008, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
ET 06-0002, Revision to Technical Specification (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation
ET 06-0001, Revision to Technical Specification 5.5.8, Inservice Testing Program to Adopt Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-479, Revision 0
ULNRC-05071, Proposed Revisions to Technical Specification 3.7.3, Main Feed Water Isolation Valves to Add the Main Feed Water Regulating Valves and MFRV Bypass Valves and to Extend the MFRV Allowed Outage Time
CPSES-200402431, License Amendment Request 04-011, Revision to Technical Specification (TS 3.3.3) Post Accident Monitoring Instrumentation and 3.6.8 Hydrogen Recombiners
CPSES-200400606, License Amendment Request (LAR) (04-02) Revision to Technical Specification (TS) 3.3.2 Engineered Safety Features Actuation System (ESFAS) Instrumentation
DCL-04-013, License Amendment Request 03-17, Common Stars Amendment, Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
ULNRC-04929, Common Stars License Amendment Regarding Implementation of WCAP-14333 and WCAP-15379, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
DCL-03-101, Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report
WO 03-0059, Application for Amendment for Revision to Technical Specification 3.3.1, Reactor Trip System Instrumentation, and Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation (Common Stars License Amendment.)
DCL-03-016, License Amendment Request 03-02, Response Time Testing Elimination & Revision to TS 3.3.1, Reactor Trip System Instrumentation
DCL-03-011, License Amendment Request 03-01, Revision to TS 3.3.1, Reactor Trip System Instrumentation
ET 02-0029, Revision to Technical Specification Surveillance Requirements 3.3.1.2 and 3.3.1.3 Re Reactor Trip System Instrumentation
NOC-AE-02001333, License Amendment Request, Proposed Changes to Technical Specifications 3.7.1.5 & 3.7.1.7
CPSES-200200192, License Amendment Request 02-02 Re Revision to Technical Specification (TS) 3.7.3
ST-HL-AE-1518, Identifies Containment Sump Additive Tank Isolation & Vent Valves as Components Which Should Not Be Actuate Tested Per Reg Guide 1.22,Position D.4 Guidelines,In Response to Request from 850326-29 Review Meetings
NRC-97-0105, Application for Amend to License NPF-43,revising TS to Be Consistent W/Planned Replacement of Current Power Range Monitoring Portion of Existing Nms
ST-HL-AE-1386, Forwards Response to Draft SER or FSAR Items Q410.04,40.38, 211.21,211.38,440.78,10.27,311.03,222.8,440.44,Q430.120 & D.0.7-3 Concerning Motor Operator Valves & Diesel Generator Loading Table.Related Correspondence
L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions
L-87-155, Forwards Rept of Plant Changes/Mods,Including Summary of Safety Evaluation of Each Change,For Period Ending 861006, Per 10CFR50.59
L-88-050, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-348/88-26 & 50-364/88-26.Corrective Actions:Valve Closed, Sys Valve Alignment Check Performed,Lube Oil Strainer Inspected & Cleaned & Pump Restored to Operable Status
NLS8800078, Application for Amend to License DPR-46,revising Tech Specs to Add Operability & Surveillance Requirements for Alternate Shutdown Panels.Fee Paid
B12819, Responds to 880205 Request for Addl Info Re Reactor Protection Sys Upgrade.Meeting Arranged W/Nrc on 880210 at White Flint Ofcs.Util Maintains RPS Upgrade Meets 10CFR50.59 Requirements & Does Not Need Prior Approval
ST-HL-AE-1923, Requests That Encl Proposed Deletions & Changes to Specific Tech Specs Be Made in Final Proof & Review Tech Specs. Affected FSAR Pages Which Will Be Included as Part of FSAR Amend 58 Encl
ST-HL-AE-1490, Forwards Response to Draft Ser/Fsar Item D 8.3-6 Re Loads on Emergency buses.Marked-up FSAR Pages Will Be Included in Future FSAR Amend.Related Correspondence
U-600279, Forwards Response to 10CFR50.62 Requirements Re Reduction of ATWS Events for Light Water Cooled Nuclear Power Plants. Installation of ATWS Sys Complete.Tech Spec 3/4.1.5, Standby Liquid Control Sys, Will Be Revised
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
B11091, Forwards Addl Info Re Status & Formal Responses to 19 Draft SER Open Items,Per 840313 Review Meeting W/Instrumentation & Control Sys Branch.Responses Will Be Incorporated Into Future FSAR Amend
W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability
CP-202300096, License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements
PLA-4181, Forwards Description of Rev 47 Changes to FSAR for Sses.Most Current Rev of Design Drawings Incorporated in Rev 47 to Fsar.Fsar Encl
LD-89-107, Forwards Addl Info Re CESSAR-DC Chapter 7
PY-CEI-NRR-0307, Forwards Addl Info Re Reg Guide 1.118 & Performance of Surveillance Testing,Per 850705 Request.Proposed Change to FSAR Table 1.8-1 Also Encl
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
W3P83-2273, Forwards Response to NRC Requesting Review of ESF Actuation Sys Testing Commitments Against Provisions of IEEE-338 & Reg Guide 1.22.List of ESF Subgroup Relays Not Testable During Operation Encl
05000498/LER-1997-008, :on 970811,ESF Containment Spray Actuation Relays Slave Relay Test Were Not Fully Tested by Surveillance.Caused by Failure to Understand Expectations Re Documentation.Spray Pumps Verified Operable
05000327/LER-1986-013, :860403,discovered Inadequate Frequency of Testing of Esf.Caused by Personnel Failure to Write Instructions to Implement Tech Spec Surveillance Requirements
05000366/LER-1988-002, :on 880219,surveillance Requirements of Tech Specs Not Met.Caused by Personnel Error.Special Purpose Procedures Developed & Surveillances Performed or Scheduled
NSD-NRC-97-4947, Submits Refs & Changes for SSAR Chapter 7.Encl 1 Will Be Included in SSAR Rev 11.NRC Requested to Review Encl 2 & Provide Westinghouse W/Nrc Status for Item,Including 1052 & 1053 for Interlocks
LD-92-024, Forwards Response to NRC Request for Addl Info on Electrical Distribution Sys Design,In Ref to NRC Review of CESSAR
NRC-95-4526, Forwards Draft Markup of SSAR Section 7.3,incorporating Design Changes Occurred Since Original Issue of SSAR
LD-91-067, Forwards Response to NRC 910729 Request for Addl Info Re Engineering SSAR - Design Certification Covering IEEE Stds, Offsite Power Sys,Control Room Indication of Emergency Diesel Generator Operational Status & Dc Power Sys
LD-91-066, Forwards Response to NRC 910805 Request for Addl in on CESSAR Design Certification
05000443/LER-1994-002, :on 940210,determined Method for Performing Slave Relay Test Valve Did Not Satisfy Ts.Caused by Omission of Relevent Information from Surveillance Procedures. Procedures Revised
JPN-93-042, Forwards Application for Amend to License DPR-59,requesting Addition of Remote Shutdown Panel LCOs & Surveillance Requirements,Per GL 81-12, Fire Protection Rule
B10282, Forwards Safety Assessment Rept of SEP Topic VI-10.A,testing of Reactor Trip Sys & Esfs,Including Response Time Testing
A01825, Comments on NRC Evaluation of SEP Topic VI-7.A.3 Re ECCS Actuation Sys.Disagrees W/Nrc Conclusion Re Core Spray & LPCI Sys.Section D.4 of Reg Guide 1.22 Only Applies to Actuated Equipment Not Tested During Reactor Operation
AECM-80-225, Forwards Response to NRC Questions 031.56,031.71 & Revised Responses to Questions 031.38,031.54,031.60 & 031.75. Responses Will Be Incorporated Into Oct 1980 Amend to FSAR
ND-19-1129, Supplement to the Request for License Amendment Regarding Protection and Safety Monitoring System Surveillance Requirement Reduction Technical Specification .
HNP-94-053, Responds to NRC Re Violations Noted in Insp Rept 50-400/94-10.Corrective Actions:Review of Reg Guide 1.33,App A,Paragraph 3 Made to Check for Any Other Sys That Do Not Have Fill & Vent Procedure Steps
L-83-160, Forwards Suppl a to Independent Verification of Design & Const for St Lucie Unit 2 Nuclear Generating Station, Resolution of Discrepancies & Corrective Action Plans
L-83-199, Confirms Understanding of ESF Actuation Sys,(Esfas) Testing Per IEEE-338 & Reg Guide 1.22 Requirements,In Response to .All ESFAS Actuation Devices Tested During Shutdown Per FSAR & Tech Specs
L-87-147, Application for Amend to License NPF-16,revising Tech Spec 3/4 7.10, Snubbers, to Delete Snubber Listings,Per Generic Ltr 84-13.Evaluation of NSHC Encl.Fee Paid
L-88-164, Annual Rept Re Plant Changes/Mods Made Between 861006 & 871006
CP-201600216, License Amendment Request 16-001, Application to Revise Technical Specifications to Adopt TSF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing
RC-16-0043, License Amendment Request Technical Specification 3/4.7.1.2, Emergency Feedwater System
SBK-L-15025, NextEra Energy Seabrook, LLCs Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12
RC-15-0171, License Amendment Request - LAR-15-01424, Implementation of WCAP-15376-P-A, Revision 1 - Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times
BW140017, Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event
CP-201101663, License Amendment Request (LAR)11-003 for Adopting of TSTF-491, Rev. 2, Removal of the Main Steam and Main Feedwater Valve Isolation Time from Tech Specs Using Consolidated Line Item Improvement Process
ET 10-0010, License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps
ET 08-0039, Revision to TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, TS 3.7.2, Main Steam Isolation Valves (Msivs), and Addition of New TS 3.7.19, Secondary System Isolation Valves
WM 06-0033, Revision to Technical Specification (TS) 3.7.2, Main Steam Isolation Valves (Msivs), and TS 3.7.3, Main Feedwater Isolation Valves (Mfivs)
RC-05-0143, License Amendment Request - LAR 05-2926 Implementation of WCAP-14333-P-A, Rev. 1, Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times
ULNRC-04742, Revision to Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2
ET 02-0033, Revision to Technical Specification 3.1.6, Physics Tests Exceptions - Mode 2
TXX-0513, License Amendment Request - Revision to Technical Specification Surveillance Requirements 3.3.1.2 & 3.3.1.3, Reactor Trip System Instrumentation
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
NUREG-0821, Forwards Safety Evaluations of SEP Topics,Vols I-III,per App E of NUREG-0821, Integrated Plant Safety Assessment Rept for Re Ginna Nuclear Power Plant
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
LD-91-024, Responds to NRC Request for Addl Info Re Review of C-E SSAR
LD-95-011, Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page
CNL-25-083, Emergency Request for Amendment to Technical Specification – Reactor Trip System (RTS) Instrumentation Level Transmitter Inoperable (WBN-TS-25-08)