|
|
| Line 15: |
Line 15: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:NMPNS-2 TABLE 7.2-1 (CONT'D)LATI S DES 1$.Abbreviations used in table;AO-Air operated MO-Motor operated SO-Solenoid operated.RHR-Residual Heat Removal System LPCI-Low Pressure Coolant Injection System RCIC-Reactor Core Isolation Cooling System LPCS-Low Pressure Core Spray System HPCS-High Pressure Core Spray System~inal Dtt D~t'eactor vessel low water level (A scram will occur at this level also This i.s the higher of the two low water level signal)Reactor vessel low water level-(The reactor core isolation cooling system will be initiated at this level also.This is the lower of the two low water level signals.)High radiation-main steam line Line break-main steam line (high steam flow)Line break-main steam line (steam line high space temperature) | | {{#Wiki_filter:NMPNS-2 TABLE 7.2-1 (CONT'D) |
| High dry well pressure Reactor vessel low water level or high dry well pressure (core standby cooling systems will be started.)High reactor water level in startup mode Line break in cleanup system-high space temperature; high differential flow Line break in reactor core isolation coolinz system steam line to turbine (high steam line space temperature, high steam flow, or low steam line pressure)N Line break in residual heat removal system shutdown and head cooling (high space temperature) | | LATI S DES 1$ . Abbreviations used in table; ~inal will occur at this level D~t'eactor AO Air operated vessel low water level (A scram also This i.s the higher of the two low water level signal ) |
| Reactor high water level p+R S Low main steam line pressure at inlet to turbine (RUN mode only)Low condenser vacuum Low dry well pressure U High reactor vessel pressure-close residual heat removal-shutdown cooling valves and head cooling valves High temperature at outlet of'leanup system nonregenerative heat exchanger, high differential flow, high area temperatureS Standby liquid control system actuated High radiation, reactor building ventilation exhaust Remote manual switch from control room.(All regular Group A and Group B isolation valves will be capable of remote manual operation from the contxol room.)These are the isolation functions of the primary containment and reactor vessel isolation control system;other functions are given for informs,tion only.6of6}} | | MO Motor operated Reactor vessel low water level - (The reactor core isolation cooling system will be initiated at this level also. This is the lower of the two low water level signals.) |
| | SO Solenoid operated. |
| | High radiation - main steam line RHR - Residual Heat Removal System Dtt Line break main steam line (high steam flow) |
| | LPCI Low Pressure Coolant Injection System Line break main steam line (steam line high space temperature) |
| | RCIC - Reactor Core Isolation Cooling System High dry well pressure LPCS Low Pressure Core Spray System Reactor vessel low water level or high dry well pressure (core standby cooling systems will be started.) |
| | HPCS High Pressure Core Spray System High reactor water level in startup mode Line break in cleanup system high space temperature; high differential flow Line break in reactor core isolation coolinz system steam line to turbine (high steam line space temperature, high steam flow, or low steam line pressure) |
| | Line break in residual heat removal system shutdown and head cooling (high space temperature) |
| | N Reactor high water level p+ Low main steam line pressure at inlet to turbine (RUN mode only) |
| | R Low condenser vacuum S Low dry well pressure U High reactor vessel pressure close residual heat removal shutdown cooling valves and head cooling valves High temperature at outlet of'leanup system nonregenerative heat exchanger, high differential flow, high area temperatureS Standby liquid control system actuated High radiation, reactor building ventilation exhaust Remote manual switch from control room. (All regular Group A and Group B isolation valves will be capable of remote manual operation from the contxol room.) |
| | These are the isolation functions of the primary containment and reactor vessel isolation control system; other functions are given for informs,tion only. |
| | 6of6}} |
Latest revision as of 08:57, 30 October 2019
|
|---|
Category:Graphics incl Charts and Tables
MONTHYEARML22314A2262022-11-10010 November 2022
E-mail Dated 11/10/2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps
ML22292A1032022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2B, Tables 2B-8 Through 2B-38
ML22292A0982022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2B, Table 2B-35, Joint Distribution of Wing Direction and Speed
ML22292A0822022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 1, Figures 1.1-1 Thru 1.2-19 Sheet 2
ML22292A0732022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 02, Appendix 2B Table 2B-39
ML22292A0812022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 Through 4.6-9
ML22292A1382022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 18, Figures
ML22292A0852022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2B Table 2B-40 Thru 2B-55
ML22292A1302022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 17, Figures
ML22292A1082022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 3, Figures 3.2-1 Thru 3C.3-3
ML22292A1162022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2B, Table 2B-38, Joint Distribution of Wind Direction and Speed Location 100 Ft
ML22292A1052022-10-0505 October 2022
5 to Updated Final Safety Analysis Report, Chapter 2, Figures 2.5-110 Through 2H-42
NMP1L3339, R. E. Ginna Station - Constellation Energy Group, LLC: Notification of Change in Indirect Ownership2020-04-24024 April 2020
R. E. Ginna Station - Constellation Energy Group, LLC: Notification of Change in Indirect Ownership
ML18018A9652018-01-18018 January 2018
Nine Mile Point, Unit 1 - Equipment Qualification Program and Tables I - Equipment Qualification Reports and Table Ii - TMI Action Plan
ML18018A9612018-01-18018 January 2018
Preservice Inspection Plan
ML17037C6892017-02-0606 February 2017
Table 7.2-1, Process Pipelines Penetrating Primary Containment, 1 of 6
ML17037A6592017-02-0606 February 2017
Stratigraphic Correlation Chart Borings T-4-1 Through T-4-12, Plate 5-3
ML17037C6832017-02-0606 February 2017
Table 7.2-1, Isolation Signal Codes (Cont'D) 6 of 6
ML17037C5692017-02-0606 February 2017
Plate 5-10A - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-4-8 Through T-4-10
ML17037C5672017-02-0606 February 2017
Plate 5-10 - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-4-1 Through T-4-7
ML17037C6912017-02-0606 February 2017
Table 7.2-1 (Cont'D) 3 of 6
ML17037C5662017-02-0606 February 2017
Plate 5-9A - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-3-9 and T-3-10
ML17037C5652017-02-0606 February 2017
Plate 5-9 - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-3-1 Through T-3-8
ML17037C5642017-02-0606 February 2017
Plate 5-1 - Composite Site Stratigraphic Column
ML17037C5632017-02-0606 February 2017
Plate 4-10 - Cross Section CT-2 West Wall Cooling Tower Piping Trench
ML17037C5622017-02-0606 February 2017
Plate 4-9 - Geologic Plan View of Fault Cooling Tower Piping Trench
ML17037C5612017-02-0606 February 2017
Plate 1-2 - Composite Site Stratographic Column Showing Position of Overcome Borings in Relation to Site Stratigraphy
ML17037C7582017-02-0606 February 2017
Table 7.2-1 (Cont'D) 4 of 6
ML17037A6662017-02-0606 February 2017
Relative Pollen Percentages, Spores and Miscellaneous Microfossil Abundance, Plate 1-3
ML17037A6622017-02-0606 February 2017
Structural Comparison of Fault Zone in Boring Series T-3, Plate 5-11
ML17037A6582017-02-0606 February 2017
Stratigraphic Correlation Chart Borings T-3-1 Through T-3-10, Plate 5-2
ML17037A6632017-02-0606 February 2017
Structural Comparison of Fault Zone in Boring Series T-4, Plate 6-12
ML17037A7152017-02-0606 February 2017
Figure 6-3, Response Test Strip Chart for Unstable Condition.
ML17037A7012017-02-0606 February 2017
Table 7.2-1 (Continued)
ML17037C6922017-02-0606 February 2017
Table 7.2-1 (Cont'D) 4 of 6
ML17037C7592017-02-0606 February 2017
Table 7.2-1 (Cont'D) 6 of 6
ML17037C7792017-02-0606 February 2017
Table 7.2-1 Isolation Signal Codes(Cont'D) 6 of 6
ML17037C7822017-02-0606 February 2017
Table 7.2-1 Process Pipelines Penetrating Primary Containment 1 of 6
ML17037C7852017-02-0606 February 2017
Table 7.2-1 (Cont'D) 4 of 6
ML16056A1392016-03-11011 March 2016
Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
ML12138A1352012-05-0707 May 2012
Reactor Pressure Vessel Head Weld Flaw Evaluation - Response to NRC Request for Additional Information
ML12045A3892012-01-13013 January 2012
EPIP-EP-001, Attachment 1 EAL Matrix Unit 1, Page 1 of 2
ML12045A3962012-01-13013 January 2012
EPIP-EP-002, Attachment 1 EAL Matrix Unit 2, Page 2 of 2
ML12045A3942012-01-13013 January 2012
EPIP-EP-002, Attachment 1 EAL Matrix Unit 2, Page 1 of 2
ML12045A3932012-01-13013 January 2012
EPIP-EP-001, Attachment 1 EAL Matrix Unit 1, Page 2 of 2
ML12045A3922012-01-13013 January 2012
EPIP-EP-002, Attachment 1 EAL Matrix Unit 2, Page 1 of 2
ML12045A3912012-01-13013 January 2012
EPIP-EP-001, Attachment 1 EAL Matrix Unit 1, Page 2 of 2
ML12045A3902012-01-13013 January 2012
EPIP-EP-001, Attachment 1 EAL Matrix Unit 1, Page 1 of 2
ML12045A3872012-01-13013 January 2012
EPIP-EP-002, Attachment 1 EAL Matrix Unit 2, Page 2 of 2
ML0728203072007-10-11011 October 2007
Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists
2022-11-10
[Table view] |
Text
NMPNS-2 TABLE 7.2-1 (CONT'D)
LATI S DES 1$ . Abbreviations used in table; ~inal will occur at this level D~t'eactor AO Air operated vessel low water level (A scram also This i.s the higher of the two low water level signal )
MO Motor operated Reactor vessel low water level - (The reactor core isolation cooling system will be initiated at this level also. This is the lower of the two low water level signals.)
SO Solenoid operated.
High radiation - main steam line RHR - Residual Heat Removal System Dtt Line break main steam line (high steam flow)
LPCI Low Pressure Coolant Injection System Line break main steam line (steam line high space temperature)
RCIC - Reactor Core Isolation Cooling System High dry well pressure LPCS Low Pressure Core Spray System Reactor vessel low water level or high dry well pressure (core standby cooling systems will be started.)
HPCS High Pressure Core Spray System High reactor water level in startup mode Line break in cleanup system high space temperature; high differential flow Line break in reactor core isolation coolinz system steam line to turbine (high steam line space temperature, high steam flow, or low steam line pressure)
Line break in residual heat removal system shutdown and head cooling (high space temperature)
N Reactor high water level p+ Low main steam line pressure at inlet to turbine (RUN mode only)
R Low condenser vacuum S Low dry well pressure U High reactor vessel pressure close residual heat removal shutdown cooling valves and head cooling valves High temperature at outlet of'leanup system nonregenerative heat exchanger, high differential flow, high area temperatureS Standby liquid control system actuated High radiation, reactor building ventilation exhaust Remote manual switch from control room. (All regular Group A and Group B isolation valves will be capable of remote manual operation from the contxol room.)
These are the isolation functions of the primary containment and reactor vessel isolation control system; other functions are given for informs,tion only.
6of6
