LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 13.5, Table 13.5-1, Administrative Procedure Topics

Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 13.5, Table 13.5-1, Administrative Procedure Topics

ML17046A544
Person / Time
Site:	Salem
Issue date:	01/30/2017
From:	Public Service Enterprise Group
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17046A230	List: LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.8-1 Through 3.8-56 LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 6.3-1A Through 6.3-4 LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 9.1-1 Through 9.1-9 LR-N17-0034, Redacted Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 5.5-1 Through 5.5-7 LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.2, Nearby Industrial, Transportation, and Military Facilities LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 3.6, Figure 3.6-1 Through Figure 3.6-30 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 15.3A, Generic Small Break Analysis LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3.6A, Description of Backdraft Damper LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3.9A, Bolted Connections for Linear Component Support 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 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 7A, Program Element Descriptions Resulting from the Implementation of the May 6, 1983 Order LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix a, TMI Lesson Learned LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 15, Figures 15.4-2 to 15.4-111 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 15, Section 15.5, Anticipated Transients Without Scram LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 17, Figures 17.2-1 to 17.2-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.2-1 to 4.2-25 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 to 4.3-35 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4-1 to 4.4-17 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.4.1 to 4.4-66d LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.5-1 to 4.5-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Section 4.5, Reload Analyses LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 4.3.1 to 4.3-61 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Sections 5.4.1 to 5.4-14 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.2-1 to 4.2-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.3-1 to 4.3-11 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.4-1 to 4.4-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 4, Tables 4.5-1 to 4.5-2 (Deleted) LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.1-1 to 5.1-13 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Figures 5.2-1 to 5.2-24 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 to 5.1-8 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.2.1 to 5.2-75 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.3.1 to 5.3-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Table 5.1-1, System Design and Operating Parameters LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Chapter 5, Tables 5.2-1 to 5.2-42 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 14.6-1 Through 14.6-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.1-1 Through 15.1-9 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.2-1 Through 15.2-46 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 15.3-1 Through 15.3-68 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.7.1 Through 3.7-13 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.9-1 Through 3.9-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3A-1 Through 3A-4 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 7.6-1 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 8.2-1 (Intentionally Deleted) and Figure 8.2-2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.2-1 to 10.2-4 Intentionally Deleted LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.3-1A Sheets 1 Through 6 of 6 Intentionally Deleted to 10.3-3, Sheets 1 & 2 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 10.4-1 Sheets 1 & 2 of 2, Intentionally Deleted to 10.4-19 LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.2-1A Sheets 1 Through 5 of 5 to 11.2-1B Intentionally Deleted LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.3-1A & B, Sheets 1, 2 & 3 of 3, Intentionally Deleted. Refer to Plant Drawings 205240 & 205340 in Dcrms LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 11.4-1 to 11.4-9 ... further results
References
LR-N17-0034
Download: ML17046A544 (5)

Text

TABLE 13.5-1 ADMINISTRATIVE PROCEDURE TOPICS

• Administration Program Description

• Supplemental Workforce Program Description

• Business Planning Process Description

• Management Process

• Project Evaluation and Authorization Process

• Budgeting Process Description

• Forecasting Process Description

• Salem/Peach Bottom Co-Owner Relationship

• Configuration Control Process Description

• Nonconforming Materials, Parts, Components

• Outsourcing Engineering Work Authorization Process

• Margin Management

• Configuration Management

• Chemistry Process Description

• Environmental Program

• Environmental Management System Process

• Chemical Management Process

• Emergency Preparedness Process Description

• Equipment Reliability Process Description

• PSEG New Hire Engineer Mentoring Program

• Equipment Reliability Program Description Note: This list consists of all of the active "description documents" (which correspond to the prior Nuclear Administrative Procedures (NAPs) which were the top-level procedures from our prior procedure system). It is a full-scale listing of the change from the old program to the new O.E.M. Program. This list represents all of the documents in alpha-numeric order without using the document numbers themselves, since the list is by TOPICS.

• Integrated Equipment Reliability Long Planning Process Description

• Material Degradation Program (MDMP)

• Regulatory Medical Testing Human Resources and Administration

• Exempt Overtime Human Resources and Administration 1 of 3 SGS-UFSAR Revision 25 October 26, 2010 TABLE 13-5-1 (Continued)

• Protected Activities and Selection Processes Human Resources Md Administration

• Change Management Human Performance Policy

• Technical Human Performance Process Description

• Nuclear Cyber Security Program Description

• Nuclear Wireless Regulatory Compliance Program Description

• Licensing Process Descriptions

• Process Description = Interface with Other Outside Agencies

• Reload Control Process Description

• Special Nuclear Material Control Process Description

• Quality Assurance Topical Report (QATR)

• Nuclear Oversight Audit Process Description

• Nuclear Oversight Performance Assessment Process Description

• Nuclear Oversight Vendor Audit (NOVA) Process Description

• Independent Inspection Process Description

• Independent Safety Engineering Function Process

• Conduct of Qperations Process Description

• Project Management

• Contractor Utilization

• Contractor Alliance Process

• Records Management (RM) Process Description

• Radiation Protection Process Description

• External Dose Control Program Description

• Internal Dose Control Program Description

• Respiratory Protection Program Description

• Radioactive Material Control Program Description 2 of 3 SGS-UFSAR Revision 25 October 26, 2010 TABLE 13-5-1 (Continued)

• High Radiation Area Program Description

• Radioactive Material/Waste Transportation/Disposal Program Description

• Radwaste Process Description

• Physical Protection Process Description

• Radioactive Contamination Control Program Description

• Program Description

• Radiological Instrumentation Program Description

• Radiological Posting and Labeling Program Description

• Fitness For Duty Process Description

• Access Authorization Process Description

• Training System Development Process Description

• Work Management Process Description 3 of 3 SGS-UFSAR Revision 25 October 26, 2010 TABLE 13.5-2 ABNORMAL OPERATING PROCEDURES

• Loss of Protective System Channels

• Acts of Nature

• Fire Protection System Activation -Plant Fires

• Fuel Cladding Failure

• Abnormal Release of Radioactivity ** Turbine Trip .,. Generator Load Reject ** Plant Chemistry Out-of Specification ** Condenser Tube Leakage ** Dropped Control Rod

• Failed Open Safety/Pressure Relief Valve ** Control Room Evacuation ** Loss Of Electrical Power {Blackout) -* Loss of Primary Containment Integrity .. Loss of Secondary Containment Integrity -* Loss of Circulating Water

• Loss of Condenser Vacuum (Hope Creek)

• Loss of Recirculation Pump or Flow (Hope Creek}

• Loss of Generator Stator Water Cooling ** Loss of Generator Seal Oil ** Loss of Service Air 1 of 2 SGS-UFSAR Revision 22 May 5, 2006 I I TABLE 13-5-2 (Continued)

• Loss of Instrument Air

• Loss of Shutdown Cooling

• Loss of Main Turbine Lube Oil

• l10SS of Reactor Auxiliary Cooling Water {Hope Creek)

• Loss of Safety and Turbine Auxiliary Cooling Water (Hope Creek)

• Rod Control System Malfunction ** Loss of Feedwater or Feedwater Control ** Service Water System Malfunction

• Reactor Pressure Control System Malfunction ** Reactor Vesse1 Level Control System Malfunction (Hope Creek} -* Neutron Monitoring System Malfunction -** Fuel Pool Cooling *** Fuel Pool Cleanup System Malfunction (Hope Creek) ,. Standby Liguid Control System Initiation (Hope Creek) 2 of 2 SGS-UFSAR Revision 22 May 5, 2006 I I