ML17046A427

9 to Updated Final Safety Analysis Report, Tables 7.7-1 Through 7.7-6

ML17046A427
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, 9 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement 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, 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: ML17046A427 (7)

Text

1.

2.

3.

Rod.Stop Nuclear Overpower High AT Low Power TABLE 7.7-l ROD STOPS Actuation Signal 1/4 high power range nuclear flux or 1/2 high intermediate range nuclear flux 2/4 overpower AT or 2/4 overtetnperature AT Low turbine steamline inlet pressure Rod Motion Automatic and Manual Withdrawal Automatic and Manual Withdrawal Automatic Withdrawal Actuation of rod stop No. 2 above is accompanied by the initiation of turbine load reference reduction.

1 of 1 SGS-UFSAR Revision 21 December 6, 2004

TABLE 7. 7-2 OVERHEAD ANNUNCIATOR GROUPINGS The alarm groupings are as follows:

DISPLAY A ANNUNCIATOR TEST/TROUBLE ALARMS MISCELLANEOUS FIRE PROTECTION DISPLAY B MISCELLANEOUS WATER SYSTEMS VITAL DC VITAL INVERTERS MISCELLANEOUS ELECTRICAL SERVICE WATER DISPLAY C WASTE DISPOSAL LEAK DETECTION AUXILIARY COOLING CONTAINMENT DISPLAY D ECCS REACTOR COOLANT SYSTEM DISPLAY E CHEMICAL AND VOLUME CONTROL SYSTEM PRESSURIZER NUCLEAR INSTRUMENTATION SYSTEM ROO CONTROL DISPLAY F REACTOR TRIP SAFETY INJECTION TURBINE TRIP DISPLAY G MAIN STEAM TURBINE AND CONDENSER FEEDWATER TURBINE AUXILIARY COOLING SGS-UFSAR 1 of 2 Revision 17 october 16, 1998

DISPLAY H MAIN GENERATOR 25KV TRANSFORMERS DISPLAY J VITAL AC DIESEL GENERATORS GROUP BUSES DISPLAY K CIRCULATING WATER 13KV SYSTEM SOOKV SYSTEM SGS-UFSAR TABLE 7.7-2 (Cont.)

2 of 2 Revision 17 October 16, 1998

TABLE 7.7-3 SEISMIC MONITORING INSTRUMENTATION INSTRUMENTS AND SENSOR LOCATIONS

1.

Triaxial Time-History Accelographs

a.

Reactor containment, Elev. 81'

b.

Reactor Containment, Elev. 130'

c.

Auxiliary Building, Elev. 122'

2.

Triaxial Peak Accelographs

a.

Reactor Containment, Elev. 86'5"

b.

Reactor Containment, Elev. 136'3"

c.

Auxiliary Building, Elev. 122'5"

d.

Fuel Handling Building, Elev. 130' 1 of 1 SGS-UFSAR MEASUREMENT RANGE 0 -

0 -

0 -

0 -

0 -

0 -

0 -

lg lg lg lg lg lg 1g Revision 14 December 29, 1995

TABLE 7.7-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENTS AND SENSOR LOCATIONS

1.

a.

b.

c.

2.

a.

b.

c.

d.

M

=

SA R

=

NA Triaxial Time-History Accelographs Reactor containment, Elev. 81' Reactor Containment, Elev. 130' Auxiliary Building, Elev. 122' Triaxial Peak Accelographs Reactor Containment, Elev. 86'5" Reactor Containment, Elev. 136'3" Auxiliary Building, Elev. 122'5" Fuel Handling Building, Elev. 130' every 31 days every 6 months every 18 months not applicable Except seismic trigger 1 of 1 SGS-UFSAR CHANNEL CHECK M*

M*

M*

NA NA NA NA CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST R

R R

R R

R R

SA SA SA NA NA NA NA Revision 14 December 29, 1995

TABLE 7.7-5 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMENT

1.

Wind Speed

a.

Meteorological Tower

b.

Meteorological Tower

c.

Meteorological Tower

2.

Wind Direction

a.

Meteorological Tower

b.

Meteorological Tower

c.

Meteorological Tower

3.

Air Temperature - Delta T

a.

Meteorological Tower

b.

Meteorological Tower SGS-UFSAR LOCATION Nominal Elev.

Nominal Elev.

Nominal Elev.

Nominal Elev.

Nominal Elev.

Nominal Elev.

Nominal Elev.

Nominal Elev.

1 Of 1 33' 150' 300' 33' 150' 300' 150' - 33' 300' - 33' Revision 14 December 29, 1995

TABLE 7.7-6 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT

1.

Wind Speed

a.

Nominal Elev. 33'

b.

Nominal Elev. 150'

c.

Nominal Elev. 300'

2.

Wind Direction

a.

Nominal Elev. 33'

b.

Nominal Elev. 150'

c.

Nominal Elev. 300'

\\

3.

Air Temperature -

Delta T

a.

b.

D =

SA=

Nominal Elev.

Nominal Elev.

daily every 6 months SGS-UFSAR 150' - 33' 300' - 33' CHANNEL CHECK D

D D

D D

D D

D 1 of 1 CHANNEL CALIBRATION SA SA SA SA SA SA SA SA Revision 14 December 29, 1995