Text

Salem/Operations, S2.OP-AR.ZZ-0005(Q), Rev. 19, Overhead Annunciators Window E
	ML110060816
Person / Time
Site:	Salem
Issue date:	07/01/2010
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	LR-N10-0355 S2.OP-AR.ZZ-0005(Q), Rev 19
	Download: ML110060816 (66)
	v • d • e

PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR L.L.C.

SALEM/OPERATIONS S2.OP-AR.ZZ-0005(Q) REV. 19 OVERHEAD ANNUNCIATORS WINDOW E Biennial Review Performed: Yes ____ No ____ NA T DCP Packages and Affected Document Numbers incorporated into this revision: None The following OTSCs were incorporated into this revision: None REVISION

SUMMARY

OHA E-8 and E16, ROD INSERTION LIMIT LO and LO-LO:

[70110976]

C Step 3.9, changed to read; REFER to Technical Specifications 3.1.1.1 (Modes 1-4) and 3.1.3.5 (Modes 1-2). Added T/S references.

OHA E-13, SR HI FLUX AT S/D:

[70106166]

C Changed SETPOINT to 0.5 to 1.0 Decade above the SR Count Rate at Shutdown.

Set IAW SC.IC-DC.NIS-0003(Q). Reference 70102877, 70091991, and SC-NIS001-01.

OHA E-24, ROD DEV OR SEQ:

[70092606]

C Aligned SETPOINT Rod Deviation phraseology with information previously reviewed and approved in S1.OP-AR.ZZ-0005(Q) for consistency.

C Reformatted Step 3.1, the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months RPI and Group Demand Position readings are applicable at >85% RTP (Step 3.1.A) as well as #85% RTP (Step 3.1.B). Aligns with information previously reviewed and approved in S2.OP-DL.ZZ-0003(Q).

IMPLEMENTATION REQUIREMENTS Effective Date:

July 1, 2010 None

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 1 of 65 Rev. 19 OVERHEAD ANNUNCIATORS WINDOW E TABLE OF CONTENTS SECTION PAGE Table of Contents..................................................................... 1 Window E Overview.................................................................. 3 Text............................................................................... 4 WINDOW TITLE E-1 21 SEAL WTR INJ FLTR P HI.............................................. 4 E-2 POPS CH I ARM........................................................... 5 E-3 POPS CH II ARM.......................................................... 6 E-4 PZR LVL HI.............................................................. 7 E-5 SR DET VOLT TRBL....................................................... 8 E-6 IR DET VOLT LOSS........................................................ 9 E-7 PR DET VOLT LOSS...................................................... 10 E-8 ROD INSERT LMT LO..................................................... 11 E-9 22 SEAL WTR INJ FLTR )P HI............................................. 13 E-10 POPS CH I DISARM / 2PR6 CLSD........................................... 14 E-11 POPS CH II DISARM / 2PR7 CLSD.......................................... 15 E-12 PZR PRESS LO........................................................... 16 E-13 SR HI FLUX AT S/D....................................................... 18 E-14 IR N35 COMPEN VOLT LOSS.............................................. 20 E-15 PR HI RNG FLUX HI...................................................... 21 E-16 ROD INSERT LMT LO-LO................................................. 22 E-17 BA BATCH TK LVL LO................................................... 24 E-18 POPS CH I AUX AIR PRESS LO............................................. 25 E-19 POPS CH II AUX AIR PRESS LO............................................ 27 E-20 PZR HTR ON LVL HI...................................................... 29 E-21 SR HI FLUX AT S/D BLOCKED............................................. 31 E-22 IR N36 COMPEN VOLT LOSS.............................................. 32

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 2 of 65 Rev. 19 WINDOW TITLE PAGE E-23 PR LO RNG FLUX HI..................................................... 33 E-24 ROD DEV OR SEQ........................................................ 35 E-25 BA BATCH TK TEMP HI OR LO............................................ 37 E-26 2PR1 NOT FULL CLSD.................................................... 38 E-27 2PR2 NOT FULL CLSD.................................................... 39 E-28 PZR HTR ON PRESS LO................................................... 40 E-29 SR & IR TRIP BYP........................................................ 41 E-30 IR HI FLUX ROD WDRWL STOP........................................... 42 E-31 PR OVRPWR ROD STOP................................................... 43 E-32 ROD DRIVE PWR SPLY GND FAULT....................................... 44 E-33 SPARE.................................................................. 46 E-34 2PR1 CHANNEL UNSAFE................................................. 47 E-35 2PR2 CHANNEL UNSAFE................................................. 48 E-36 PZR HTR OFF LVL LO.................................................... 49 E-37 CH C SDM DECRNG...................................................... 51 E-38 UPPER SECT DEV ABV 50% PWR.......................................... 52 E-39 PR CH DEV.............................................................. 53 E-40 ROD BANK URGENT FAIL................................................ 54 E-41 LTDWN HX OUT TEMP HI................................................ 55 E-42 2PR1 1/2 TRIP............................................................ 57 E-43 2PR2 1/2 TRIP............................................................ 58 E-44 PZR SFTY VLV 2PR3 - 2PR5 NOT CLSD..................................... 59 E-45 CH D SDM DECRNG...................................................... 60 E-46 LOWER SECT DEV ABV 50% PWR......................................... 61 E-47 PR NEUT FLUX RATE HI.................................................. 62 E-48 ROD BOTTOM........................................................... 63 References......................................................................... 64

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 3 of 65 Rev. 19 1

21 SEAL WTR INJ FLTR P HI 2

POPS CH I ARM 3

POPS CH II ARM 4

PZR LVL HI 5

SR DET VOLT TRBL 6

IR DET VOLT LOSS 7

PR DET VOLT LOSS 8

ROD INSERT LMT LO 9

22 SEAL WTR INJ FLTR P HI 10 POPS CH I DISARM/

2PR6 CLSD 11 POPS CH II DISARM/

2PR7 CLSD 12 PZR PRESS LO 13 SR HI FLUX AT S/D 14 IR N35 COMPEN VOLT LOSS 15 PR HI RNG FLUX HI 16 ROD INSERT LMT LO-LO 17 BA BATCH TK LVL LO 18 POPS CH I AUX AIR PRESS LO 19 POPS CH II AUX AIR PRESS LO 20 PZR HTR ON LVL HI 21 SR HI FLUX AT S/D BLOCKED 22 IR N36 COMPEN VOLT LOSS 23 PR LO RNG FLUX HI 24 ROD DEV OR SEQ 25 BA BATCH TK TEMP HI OR LO 26 2PR1 NOT FULL CLSD 27 2PR2 NOT FULL CLSD 28 PZR HTR ON PRESS LO 29 SR & IR TRIP BYP 30 IR HI FLUX ROD WDRWL STOP 31 PR OVRPWR ROD STOP 32 ROD DRIVE PWR SPLY GND FAULT 33 34 2PR1 CHANNEL UNSAFE 35 2PR2 CHANNEL UNSAFE 36 PZR HTR OFF LVL LO 37 CH C SDM DECRNG 38 UPPER SECT DEV ABV 50% PWR 39 PR CH DEV 40 ROD BANK URGENT FAIL 41 LTDWN HX OUT TEMP HI 42 2PR1 1/2 TRIP 43 2PR2 1/2 TRIP 44 PZR SFTY VLV 2PR3-2PR5 NOT CLSD 45 CH D SDM DECRNG 46 LOWER SECT DEV ABV 50% PWR 47 PR NEUT FLUX RATE HI 48 ROD BOTTOM

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 4 of 65 Rev. 19 ALARM E-1 1

21 SEAL WTR INJ FLTR

)P HI DEVICES:

2PIC-189B SETPOINT:

$20 psid

1.0 CAUSE(S)

$20 psid across 21 Seal Injection Filter 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 ENSURE CVC System parameters are normal.

3.2 ENSURE 2CV71, CHG HDR PCV, and 2CV55, CENT CHG PMP FCV, are adjusted to maintain seal injection flow 6-10 gpm to each RCP.

3.3 SEND an Operator to check differential pressure locally at Elev. 84' Aux Building.

3.4 IF the alarm is valid, THEN:

A.

PLACE 22 Seal Injection Filter in service IAW S2.OP-SO.CVC-0001(Q), Charging, Letdown and Seal Injection.

B.

ENSURE the alarm clears.

C.

INITIATE SAP Notification to replace 21 Seal Injection Filter.

3.5 IF the alarm is not valid, THEN INITIATE SAP Notification to determine and correct the cause of alarm.

Page 1 of 1 E-1

References:

Dwg.

211562, 205328

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 5 of 65 Rev. 19 ALARM E-2 2

POPS CH I ARM DEVICES:

2TC-413C SETPOINT:

$312°F

1.0 CAUSE(S)

POPS Ch I is armed with Loop 21 WR T Cold $312°F 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 CONFIRM the alarm by observing RCS Temperature.

3.2 IF plant conditions require that POPS be armed, THEN REDUCE RCS Temperature to <312°F.

3.3 IF alarm is due to normal plant heatup, THEN ENSURE RHR is out of service and RH1 and RH2 are CLOSED, AND DISARM POPS Ch I by pressing OFF Push Button.

3.4 IF alarm is due to a malfunction, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

3.5 REFER to Technical Specifications.

Page 1 of 1 E-2

References:

Dwg.

244082

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 6 of 65 Rev. 19 ALARM E-3 3

POPS CH II ARM DEVICES:

2TC-423C SETPOINT:

$312°F

1.0 CAUSE(S)

POPS Ch II is armed with Loop 22 WR T Cold $312°F 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 CONFIRM the alarm by observing RCS Temperature.

3.2 IF plant conditions require that POPS be armed, THEN REDUCE RCS Temperature to <312°F.

3.3 IF alarm is due to normal plant heatup, THEN ENSURE RHR is out of service and RH1 and RH2 are CLOSED, AND DISARM POPS Ch II by pressing the OFF Push Button.

3.4 IF alarm is due to a malfunction, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

3.5 REFER to Technical Specifications.

Page 1 of 1 E-3

References:

Dwg.

224084

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 7 of 65 Rev. 19 ALARM E-4 4

PZR LVL HI DEVICES:

2LC459A, 2LC460A, 2LC461A SETPOINT:

$92%

1.0 CAUSE(S)

At least one channel of Pzr level $92%

2.0 AUTOMATIC ACTIONS:

NOTE 2-out-of-3 Channels will initiate a Reactor Trip $P-7.

None 3.0 OPERATOR ACTIONS:

3.1 IF a single instrument failure has occurred, THEN INITIATE S2.OP-AB.CVC-0001(Q), Loss of Charging, for applicability.

3.2 IF more than one channel indicates $92% and power is $P-7, THEN:

A.

TRIP Reactor.

B.

CONFIRM the Reactor Trip.

C.

GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

Page 1 of 1 E-4

References:

Dwg.

221055

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 8 of 65 Rev. 19 ALARM E-5 5

SR DET VOLT TRBL DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Any:

A.

SR channel deenergized with Turbine Power <15% (P-2)

B.

SR channel energized with Turbine Power $15% (P-2) 2.0 AUTOMATIC ACTIONS:

NOTE Source Range Channels will deenergize when 2 of 4 Power Range Channels reach P-10.

This alarm is blocked by P-2 when turbine power is >15%

AND will annunciate when turbine power <15%.

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to P-6 Block during Reactor Start-up, testing or maintenance, THEN no further action is required.

3.2 GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 1 of 1 E-5

References:

Dwg.

218914

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 9 of 65 Rev. 19 ALARM E-6 6

IR DET VOLT LOSS DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Loss of Detector voltage on IR Channel 2.0 AUTOMATIC ACTIONS:

NOTE If Reactor Power below P-10, Reactor Trip may occur.

None 3.0 OPERATOR ACTIONS:

3.1 IF alarm is due to testing or maintenance, THEN no further action is required.

3.2 IF a Reactor Trip occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.3 GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 1 of 1 E-6

References:

Dwg.

218914

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 10 of 65 Rev. 19 ALARM E-7 7

PR DET VOLT LOSS DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Loss of Detector Volts on PR channel 2.0 AUTOMATIC ACTIONS:

NOTE Loss of detector voltage may cause a Power Range Overpower Rod Stop.

Loss of 2-out-of-4 Power Ranges will result in Reactor Trip.

None 3.0 OPERATOR ACTIONS:

3.1 IF alarm is due to testing or maintenance, THEN no further action is required.

3.2 IF Reactor Trip occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.3 GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 1 of 1 E-7

References:

Dwg.

218914

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 11 of 65 Rev. 19 ALARM E-8 8

ROD INSERT LMT LO M

DEVICES:

2DC412A, 2DC422A, 2DC432A, 2DC442A SETPOINT:

10 steps from Rod Insertion limit

1.0 CAUSE(S)

One or more of Control Rod Banks (A, B, C, or D), within 10 steps of insertion limits 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 DETERMINE affected Rod Bank from Annunciator CRT:

CRT Point Description Rod Bank 502 Rod Insertion Limit Low (412)

Bank A 503 Rod Insertion Limit Low (422)

Bank B 504 Rod Insertion Limit Low (432)

Bank C 505 Rod Insertion Limit Low (442)

Bank D 3.2 ENSURE that Rods of applicable Bank are within +/- 12 steps of Group Demand Counter.

3.3 IF a Reactor Startup is in progress and the alarm is expected, THEN no further action is required.

3.4 IF alarm is due to surveillance testing pursuant to Technical Specification 4.1.3.1.2 IAW S2.OP-ST.RCS-0001(Q), Reactivity Control System - Rod Control Assemblies, THEN no further action is required.

(continued)

Page 1 of 2 E-8

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 12 of 65 Rev. 19 3.5 IF cause of alarm is a dropped rod, THEN GO TO S2.OP-AB.ROD-0002(Q), Dropped Rod.

3.6 IF cause of alarm is a misaligned rod, THEN GO TO S2.OP-AB.ROD-0001(Q), Immovable/Misaligned Rod.

NOTE The alarm will reset when the affected Rods are withdrawn at least 12 steps above Rod Insertion Limit.

3.7 COMMENCE Boron Addition to restore Rods to their normal band IAW S2.OP-SO.CVC-0006(Q), Boron Concentration Control.

3.8 IF the alarm is due to the Rod Insertion Limit Monitor or OHA being inoperable, THEN VERIFY individual Control Rod Positions every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months IAW S2.OP-DL.ZZ-0003(Q), Control Room Log - Modes 1-4. (T/S 4.1.3.5) 3.9 REFER to Technical Specifications 3.1.1.1 (Modes 1-4) and 3.1.3.5 (Modes 1-2).

Page 2 of 2 E-8

References:

Dwg.

220091

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 13 of 65 Rev. 19 ALARM E-9 9

22 SEAL WTR INJ FLTR

)P HI DEVICES:

2PIC-189A SETPOINT:

$20 psid

1.0 CAUSE(S)

$20 psid across 22 Seal Injection Filter 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 ENSURE the CVC System parameters are normal.

3.2 ENSURE 2CV71, CHG HDR PCV, and 2CV55, CENT CHG PMP FCV, are adjusted to maintain seal injection flow 6-10 gpm to each RCP.

3.3 SEND an Operator to check differential pressure locally at Elev. 84' Aux Building.

3.4 IF the alarm is valid, THEN:

A.

PLACE 21 Seal Injection Filter in service IAW S2.OP-SO.CVC-0001(Q), Charging, Letdown and Seal Injection.

B.

ENSURE the alarm clears.

C.

INITIATE SAP Notification to replace 22 Seal Injection Filter.

3.5 IF the alarm is not valid, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

Page 1 of 1 E-9

References:

Dwg.

211562, 205328

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 14 of 65 Rev. 19 ALARM E-10 10 POPS CH I DISARM/

2PR6 CLSD DEVICES:

2TC-413C SETPOINT:

312°F

1.0 CAUSE(S)

Either of following with RCS Loop 21 WR T Cold #312°F:

A.

POPS CH I disarmed B.

2PR6, PZR PWR OP RELIEF STOP V, closed 2.0 AUTOMATIC ACTIONS:

2.1 POPS CH I disarmed: Reinstates 2335 psig setpoint on 2PR1, PZR PWR OP RELIEF V.

2.2 2PR6 closed:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or plant evolutions, THEN no further action is required.

3.2 MONITOR RCS Temperature, POPS CH I, and 2PR6.

3.3 IF POPS CH I is disarmed with RCS Temperature #312°F, THEN:

A.

ESTABLISH RCS pressure <375 psig.

B.

ARM POPS CH I IAW S2.OP-SO.PZR-0004(Q),

Pressurizer Overpressure Protection Operation.

3.4 IF 2PR6 is closed, THEN OPEN 2PR6.

3.5 IF alarm is invalid, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

3.6 REFER to Technical Specifications.

Page 1 of 1 E-10

References:

Dwg.

244082 / 244083

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 15 of 65 Rev. 19 ALARM E-11 11 POPS CH II DISARM/

2PR7 CLSD DEVICES:

2TC-423C SETPOINT:

312°F

1.0 CAUSE(S)

Either of following with RCS Loop 22 WR T Cold #312°F:

A.

POPS CH II disarmed B.

2PR7, PZR PWR OP RELIEF STOP V, closed 2.0 AUTOMATIC ACTIONS:

2.1 POPS CH II disarmed: Reinstates 2335 psig setpoint on 2PR2, PZR PWR OP RELIEF V.

2.2 2PR7 closed:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or plant evolutions, THEN no further action is required.

3.2 MONITOR RCS Temperature, POPS CH II, and 2PR7.

3.3 IF POPS CH II is disarmed with RCS Temperature #312°F, THEN:

A.

ESTABLISH RCS pressure <375 psig.

B.

ARM POPS CH II IAW S2.OP-SO.PZR-0004(Q),

Pressurizer Overpressure Protection Operation.

3.4 IF 2PR7 is closed, THEN OPEN 2PR7.

3.5 IF the alarm is invalid, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

3.6 REFER to Technical Specifications.

Page 1 of 1 E-11

References:

Dwg.

244084 / 244085

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 16 of 65 Rev. 19 ALARM E-12 12 PZR PRESS LO M

DEVICES:

2PC-455D, 2PC-456D, 2PC-457D SETPOINT:

1765 psig

1.0 CAUSE(S)

One or more Pzr Pressure Channels #1765 psig 2.0 AUTOMATIC ACTIONS:

NOTE Low pressure on 2-out-of-3 Channels will initiate Safety Injection.

None 3.0 OPERATOR ACTIONS:

3.1 DETERMINE the affected Channel(s) from Annunciator CRT:

CRT Point Description 426 Pressurizer Pressure Low Channel I 427 Pressurizer Pressure Low Channel II 428 Pressurizer Pressure Low Channel III 3.2 IF a Reactor Trip or Safety Injection occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

(continued)

Page 1 of 2 E-12

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 17 of 65 Rev. 19 3.3 IF $2 channels indicate #1765 psig, THEN:

A.

Manually TRIP the Reactor AND INITIATE Safety Injection.

B.

GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.4 IF there is evidence of RCS leakage, (decreasing Pzr or VCT level),

THEN GO TO S2.OP-AB.RC-0001(Q), Reactor Coolant System Leak.

3.5 IF an actual RCS Pressure control problem exists, THEN GO TO S2.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

3.6 IF the alarm is due to testing, maintenance, or is normal for plant conditions, THEN no further action is required.

3.7 IF a single Pressurizer Channel is malfunctioning, THEN:

A.

INITIATE SAP Notification to determine the cause and repair affected channel.

B.

REMOVE malfunctioning channel from service IAW S2.OP-SO.RPS-0003(Q),

Placing Pressurizer Channel in Tripped Condition.

Page 2 of 2 E-12

References:

Dwg.

221055

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 18 of 65 Rev. 19 ALARM E-13 13 SR HI FLUX AT S/D DEVICES:

2NC31CX, 2NC32CX SETPOINT:

0.5 to 1.0 Decade above the SR Count Rate at Shutdown.

Set IAW SC.IC-DC.NIS-0003(Q).

1.0 CAUSE(S)

Source Range increasing by 0.5 to 1.0 Decade above background Source Range Level 2.0 AUTOMATIC ACTIONS:

The Containment Evacuation Horn sounds 3.0 OPERATOR ACTIONS:

3.1 CONFIRM the alarm by observing Source Range Counts.

3.2 IF the alarm is valid, THEN:

A.

STOP any core alteration in progress.

B.

IF Initial Core Loading of source bearing assembly and array of fuel is in progress, THEN NOTIFY Reactor Engineering to evaluate.

C.

IF a planned heatup or dilution is in progress, THEN CONTACT Reactor Engineering to confirm response.

(continued)

Page 1 of 2 E-13

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 19 of 65 Rev. 19 3.2 (continued)

D.

IF Step B or C is not in progress,

THEN, 1.

ANNOUNCE over the PA system: "The Source Range High Flux Alarm has sounded. Evacuate all personnel from Containment."

2.

SOUND the Containment Evacuation Horn by pressing the Evacuation Horn Test Push Button on 2RP2.

3.

VERIFY no dilution paths lined up and injecting.

4.

DETERMINE if Shutdown Margin requirements are satisfied.

5.

REFER to Technical Specifications.

3.3 IF alarm is due to spiking caused by welding or other electrical interference, THEN:

A.

ATTEMPT to locate and stop the activity.

B.

OBTAIN the key AND BLOCK the Containment Evacuation Horn.

Page 2 of 2 E-13

References:

Dwg.

218914, SC-NIS001-01, VTD 301156

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 20 of 65 Rev. 19 ALARM E-14 14 IR N35 COMPEN VOLT LOSS DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Loss of Compensating voltage on Intermediate Range Channel N35 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or maintenance, THEN no further action is required.

3.2 GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 1 of 1 E-14

References:

Dwg.

218914

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 21 of 65 Rev. 19 ALARM E-15 15 PR HI RNG FLUX HI DEVICES:

2NC41R, 2NC42R, 2NC43R, 2NC44R SETPOINT:

$109%

1.0 CAUSE(S)

PR High Range Channel at $109%

2.0 AUTOMATIC ACTIONS:

NOTE 2-out-of-4 PR High Flux Channel Trips will initiate Reactor Trip.

None 3.0 OPERATOR ACTIONS:

3.1 IF a Reactor Trip Occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.2 IF the alarm is due to a Control Rod Misalignment, OR two or more channels are $109%,

AND a Reactor Trip has not occurred, THEN:

A.

Manually TRIP the Reactor.

B.

GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.3 IF the alarm is due to testing or maintenance, THEN no further action is required.

3.4 IF the alarm is due to an instrument malfunction, THEN GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 1 of 1 E-15

References:

Dwg.

221052

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 22 of 65 Rev. 19 ALARM E-16 16 ROD INSERT LMT LO-LO M

DEVICES:

2DC412B, 2DC422B, 2DC432B, 2DC442B SETPOINT:

At Rod Insertion Limit

1.0 CAUSE(S)

One or more Control Rod Banks (A, B, C, or D), at insertion limit 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 DETERMINE the affected Rod Bank from Annunciator CRT:

CRT Point Description Rod Bank 506 Rod Insertion Limit Low-Low (412)

Bank A 507 Rod Insertion Limit Low-Low (422)

Bank B 508 Rod Insertion Limit Low-Low (432)

Bank C 509 Rod Insertion Limit Low-Low (442)

Bank D 3.2 ENSURE that all Rods of affected Bank are within +/-12 steps of Group Demand Counter.

3.3 IF a Reactor Startup is in progress and the alarm is expected, THEN no further action is required.

3.4 IF alarm is due to surveillance testing pursuant to Technical Specification 4.1.3.1.2 IAW S2.OP-ST.RCS-0001(Q), Reactivity Control System - Rod Control Assemblies, THEN no further action is required.

3.5 COMMENCE Emergency Boration IAW S2.OP-SO.CVC-0008(Q), Rapid Boration.

(continued)

Page 1 of 2 E-16

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 23 of 65 Rev. 19 3.6 IF the cause of the alarm is a dropped rod, THEN GO TO S2.OP-AB.ROD-0002(Q), Dropped Rod.

3.7 IF the cause of the alarm is a misaligned rod, THEN GO TO S2.OP-AB.ROD-0001(Q), Immovable/Misaligned Control Rods.

NOTE The alarm will reset when the affected rods are withdrawn at least 2 steps above the Rod Insertion Limit.

3.8 IF the alarm is due to the Rod Insertion Limit Monitor or OHA being inoperable, THEN VERIFY individual Control Rod Positions every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months IAW S2.OP-DL.ZZ-0003(Q), Control Room Readings - Modes 1-4 (T/S 4.1.3.5).

3.9 REFER to Technical Specifications 3.1.1.1 (Modes 1-4) and 3.1.3.5 (Modes 1-2).

Page 2 of 2 E-16

References:

Dwg.

220091

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 24 of 65 Rev. 19 ALARM E-17 17 BA BATCH TK LVL LO DEVICES:

2LIC-101 SETPOINT:

22%

1.0 CAUSE(S)

Boric Acid Batching Tank Level #22%

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to a Boric Acid Batch Transfer, THEN ENSURE the alarm clears when the transfer is complete.

3.2 IF the alarm is unexpected, THEN SEND an Operator to determine and correct the cause of the alarm.

Page 1 of 1 E-17

References:

Dwg.

218851

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 25 of 65 Rev. 19 ALARM E-18 18 POPS CH I AUX AIR PRESS LO DEVICES:

2PD-9862 SETPOINT:

90 psig

1.0 CAUSE(S)

Low air pressure on POPS Ch I Air Accumulator (2PR1) 2.0 AUTOMATIC ACTIONS:

NOTE This alarm indicates that a problem exists in the air supply for 2PR1, and allows time for corrective action.

The PORV Air System operates as follows:

1)

Redundant Air Supply Panel is designed to transfer Control Air supply to the alternate header at. 82 psig.

2)

If CA Supply pressure at the PORV drops to 85 psig, the Accumulator outlet solenoid will open and the Accumulators will begin to supply 2PR1. At this time, the Accumulators should still be charged to. 120 psig.

3)

As 2PR1 is cycled, the Accumulators begin to depressurize and, at 90 psig, cause this alarm. If the CA header repressurizes to $90 psig, the system will transfer back to the CA Header.

Based on calculations S-C-CA-MDC-1169 and S-C-CA-MEE-0433-01:

1)

A minimum initial accumulator pressure of 88 psig is needed to stroke the PORVs 100 cycles at LTOP condition (RCS temperature less than or equal to 312°F).

For inadvertent SI at power, the PORVs accumulators capacity provides for 220 strokes of the PORVs.

2)

A minimum air pressure of 77 psig is required to open a PORV under full flow conditions and 85 psig under static flow conditions.

None (Continued)

Page 1 of 2 E-18

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 26 of 65 Rev. 19 3.0 OPERATOR ACTIONS:

3.1 IF the Control Air Header A or B pressure drops to #88 psig, THEN manually START the Emergency Control Air Compressor.

3.2 IF a loss of Control Air is indicated, THEN GO TO S2.OP-AB.CA-0001(Q), Loss of Control Air.

3.3 IF a Containment entry is possible, THEN:

A.

CHECK for air system leaks.

B.

CHECK for proper operation of Redundant Air Supply Panel 700-2AB.

C.

PERFORM the valve lineup on the Accumulator air supply.

3.4 INITIATE SAP Notification to determine and correct the cause of the alarm.

3.5 REFER to Technical Specifications.

Page 2 of 2 E-18

References:

Dwg.

244083 / 205347

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 27 of 65 Rev. 19 ALARM E-19 19 POPS CH II AUX AIR PRESS LO DEVICES:

2PD-9863 SETPOINT:

90 psig

1.0 CAUSE(S)

Low air pressure on POPS Ch II Air Accumulator (2PR2) 2.0 AUTOMATIC ACTIONS:

NOTE This alarm indicates that a problem exists in the air supply for 2PR2, and allows time for corrective action.

The PORV Air System operates as follows:

1)

Redundant Air Supply Panel is designed to transfer Control Air supply to the alternate header at. 82 psig.

2)

If CA Supply pressure at the PORV drops to 85 psig, the Accumulator outlet solenoid will open and the Accumulators will begin to supply 2PR2. At this time, the Accumulators should still be charged to. 120 psig.

3)

As 2PR2 is cycled, the Accumulators begin to depressurize and, at 90 psig, cause this alarm. If the CA header repressurizes to $90 psig, the system will transfer back to the CA Header.

Based on calculations S-C-CA-MDC-1169 and S-C-CA-MEE-0433-01:

1)

A minimum initial accumulator pressure of 88 psig is needed to stroke the PORVs 100 cycles at LTOP condition (RCS temperature less than or equal to 312°F).

For inadvertent SI at power, the PORVs accumulators capacity provides for 220 strokes of the PORVs.

2)

A minimum air pressure of 77 psig is required to open a PORV under full flow conditions and 85 psig under static flow conditions.

None (Continued)

Page 1 of 2 E-19

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 28 of 65 Rev. 19 3.0 OPERATOR ACTIONS:

3.1 IF the Control Air Header A or B pressure drops to #88 psig, THEN manually START the Emergency Control Air Compressor.

3.2 IF a loss of Control Air is indicated, THEN GO TO S2.OP-AB.CA-0001(Q), Loss of Control Air.

3.3 IF a Containment entry is possible, THEN:

A.

CHECK for air system leaks.

B.

CHECK for proper operation of Redundant Air Supply Panel 700-2AC.

C.

PERFORM the valve lineup on the Accumulator air supply.

3.4 INITIATE SAP Notification to determine and correct the cause of the alarm.

3.5 REFER to Technical Specifications.

Page 2 of 2 E-19

References:

Dwg.

244085 / 205347

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 29 of 65 Rev. 19 ALARM E-20 20 PZR HTR ON LVL HI DEVICES:

2LC459-EX SETPOINT:

Computer generated 5% above program

1.0 CAUSE(S)

Pzr level $5% above program 2.0 AUTOMATIC ACTIONS:

Backup Heaters will energize (if in auto).

3.0 OPERATOR ACTIONS:

3.1 IF alarm is expected, THEN no further action is required.

3.2 CONFIRM pressurizer level is $5% above program as shown on Figure 1E-20.

3.3 IF an instrument failure exists, THEN:

A.

SELECT an operable channel for Control and Alarm.

B.

REFER to Technical Specifications.

C.

REMOVE the inoperable channel from service IAW S2.OP-SO.RPS-0003(Q),

Placing Pressurizer Channel in Tripped Condition.

D.

REFER to S2.OP-AB.CVC-0001(Q), Loss of Charging, for applicability.

3.4 IF pressurizer level is above the program value, THEN:

A.

REDUCE charging OR INCREASE letdown IAW S2.OP-SO.CVC-0001(Q),

Charging, Letdown and Seal Injection, to restore pressurizer level to program value of Figure 1E-20.

B.

MATCH TAVE to TREF.

(continued)

Page 1 of 2 E-20

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 30 of 65 Rev. 19 3.4 (continued)

C.

IF normal letdown cannot be placed in service, THEN PLACE Excess Letdown in service IAW S2.OP-SO.CVC-0003(Q), Excess Letdown Flow.

Page 2 of 2 E-20

References:

Dwg.

203347

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 31 of 65 Rev. 19 ALARM E-21 21 SR HI FLUX AT S/D BLOCKED DEVICES:

2PC-505CX SETPOINT:

15% Power (P-2)

1.0 CAUSE(S)

The SR channel "High Flux at Shutdown" switch is in the BLOCK position when below P-2 (15%).

2.0 AUTOMATIC ACTIONS:

NOTE The alarm should clear when Reactor Power is $15% (P-2).

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or normal plant evolutions, THEN no further action is required.

3.2 POSITION the High Flux at Shutdown switch as required by the applicable IOP.

3.3 IF the alarm is invalid, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

Page 1 of 1 E-21

References:

Dwg.

218914

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 32 of 65 Rev. 19 ALARM E-22 22 IR N36 COMPEN VOLT LOSS DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Loss of Compensating voltage on Intermediate Range Channel N36 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or maintenance, THEN no further action is required.

3.2 GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 1 of 1 E-22

References:

Dwg.

218914

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 33 of 65 Rev. 19 ALARM E-23 23 PR LO RNG FLUX HI DEVICES:

2NC41P, 2NC42P, 2NC43P, 2NC44P SETPOINT:

$25%

1.0 CAUSE(S)

Any PR Channel is $25% with:

Power <P-10 (10% power).

OR Power is >P-10 and the circuit is not manually blocked.

2.0 AUTOMATIC ACTIONS:

NOTE 2-out-of-4 Low Range High Flux Trips will initiate Reactor Trip.

None 3.0 OPERATOR ACTIONS:

3.1 IF a Reactor Trip has occurred, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.2 IF two channels are $25% and the circuit is not blocked, THEN:

A.

Manually TRIP the Reactor.

B.

GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

(continued)

Page 1 of 2 E-23

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 34 of 65 Rev. 19 3.3 IF the Low Range Flux trips should be blocked, AND only one channel is $25%,

THEN:

A.

REDUCE power to less than 25%.

B.

BLOCK the trips IAW applicable IOP.

3.4 IF the alarm is due to testing or maintenance, THEN no further action is required.

3.5 IF the alarm is due to a Rod Control System Malfunction, THEN GO TO the applicable procedure:

S2.OP-AB.ROD-0001(Q),

Immovable/Misaligned Control Rods S2.OP-AB.ROD-0002(Q), Dropped Rod S2.OP-AB.ROD-0003(Q), Continuous Rod Motion 3.6 IF the alarm is due to an instrument malfunction, THEN GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 2 of 2 E-23

References:

Dwg.

221052

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 35 of 65 Rev. 19 ALARM E-24 24 ROD DEV OR SEQ DEVICES: Plant Computer generated SETPOINT:

Rod Deviation:

$+/-12 steps from Bank Demand when Tcold $350°F and >85% RTP.

$+/-18 steps from Bank Demand when Tcold $350°F and #85% RTP.

$+/-24 steps from Bank Demand when Tcold <350°F

$+/-24 steps from Bank Demand anytime Rods are in motion.

$1 step from fully withdrawn for any Shutdown Rod Rod Sequence:

Out-of-Sequence

1.0 CAUSE(S)

1.1 Any deviation between an individual rod and its bank demand by:

A.

$+/-12 steps when Tcold is $350°F AND Rods are not in motion.

B.

$+/-24 steps when Tcold is <350°F.

C.

$+/-24 steps when Rods are in motion.

1.2 Any Shutdown Rod Off Top (not fully withdrawn) 1.3 Any Rod Bank Withdrawal Out-of-Sequence.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF Tcold is $350°F, AND Rods are not in motion, THEN A.

IF Rated Thermal Power is >85%,

THEN ENSURE all Rods are within +/-12 steps of the Group Demand Counter within one hour after rod motion.

(continued)

Page 1 of 2 E-24

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 36 of 65 Rev. 19 3.1 (continued)

B.

IF Rated Thermal Power is #85%,

THEN ENSURE all Rods are within +/-18 steps of the Group Demand Counter within one hour after rod motion.

C.

PERFORM the following every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months IAW S2.OP-DL.ZZ-0003(Q),

Control Room Log - Modes 1-4, until the alarm is clear.

1.

VERIFY Group Positions IAW T/S 4.1.3.1.1.

2.

COMPARE the Demand Position Indication and the Rod Position Indication IAW T/S 4.1.3.2.1.1.

3.2 IF Tcold is <350°F, THEN ENSURE all Rods are within +/-24 steps of the Group Demand Counter within one hour after rod motion.

3.3 IF Rods are in motion, THEN ENSURE all Rods are within +/-24 steps of the Group Demand Counter within one hour after rod motion.

3.4 IF the alarm is due to the Rod Deviation Monitor or OHA being inoperable, THEN PERFORM the following every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months IAW S2.OP-DL.ZZ-0003(Q),

Control Room Readings - Modes 1-4.

A.

VERIFY Group Positions IAW T/S 4.1.3.1.1.

B.

COMPARE the Demand Position Indication and the Rod Position Indication IAW T/S 4.1.3.2.1.1.

3.5 ENSURE proper Rod Withdrawal Sequence.

3.6 IF the cause of the alarm is a dropped rod, THEN GO TO S2.OP-AB.ROD-0002(Q), Dropped Rod.

3.7 IF the cause of the alarm is not a dropped rod, AND Rod Deviation is outside the allowed value for current plant conditions THEN GO TO S2.OP-AB.ROD-0001(Q), Immovable/Misaligned Control Rods.

Page 2 of 2 E-24

References:

Dwg. 203494

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 37 of 65 Rev. 19 ALARM E-25 25 BA BATCH TK TEMP HI OR LO DEVICES:

2TIC-100 SETPOINT:

Hi:

$165°F Lo:

125°F

1.0 CAUSE(S)

Boric Acid Batching Tank Temperature is $165°F or #125°F 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to a Boric Acid Tank transfer, THEN no further action is required.

3.2 IF the alarm is unexpected, THEN SEND an Operator to investigate.

3.3 INITIATE SAP Notification to correct the cause of the alarm.

Page 1 of 1 E-25

References:

Dwg.

218851

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 38 of 65 Rev. 19 ALARM E-26 26 2PR1 NOT FULL CLSD DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

2PR1, PZR PWR OP RELIEF V, is not fully closed.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF a Reactor Coolant System high pressure condition exists, THEN GO TO S2.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

3.2 IF the Reactor Coolant System pressure is normal and 2PR1 is leaking, (high tailpipe temperature, PRT level and temperature increasing),

THEN:

A.

CLOSE 2PR6, PZR PWR OP RELIEF STOP V.

B.

REFER to Technical Specifications.

3.3 IF the Reactor Coolant System pressure is normal, AND 2PR1 is not leaking, THEN INITIATE S2.OP-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance.

3.4 INITIATE SAP Notification to determine and correct cause of alarm.

Page 1 of 1 E-26

References:

Dwg.

244083

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 39 of 65 Rev. 19 ALARM E-27 27 2PR2 NOT FULL CLSD DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

2PR2, PZR PWR OP RELIEF V, is not fully closed.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF a Reactor Coolant System high pressure condition exists, THEN GO TO S2.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

3.2 IF the Reactor Coolant System pressure is normal and 2PR2 is leaking (high tailpipe temperature, PRT level and temperature increasing),

THEN:

A.

CLOSE 2PR7, PZR PWR OP RELIEF STOP V.

B.

REFER to Technical Specifications.

3.3 IF the Reactor Coolant System pressure is normal, AND 2PR2 is not leaking, THEN INITIATE S2.OP-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance.

3.4 INITIATE SAP Notification to determine and correct the cause of the alarm.

Page 1 of 1 E-27

References:

Dwg.

244085

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 40 of 65 Rev. 19 ALARM E-28 28 PZR HTR ON PRESS LO DEVICES:

2PC-455IX SETPOINT:

<9% MASTER PRESSURE CONTROL (PI-455D) OUTPUT (approximately 2210 psig compensated pressure)

1.0 CAUSE(S)

Pzr Pressure Control Channel is #2210 psig 2.0 AUTOMATIC ACTIONS:

Pzr Backup Heaters will energize (if in Auto).

3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or maintenance, THEN no further action is required.

3.2 IF the alarm is expected due to plant evolutions, THEN ENSURE pressure returns to normal, AND no further action is required.

3.3 IF there is evidence of RCS leakage, (decreasing Pzr or VCT level),

THEN GO TO S2.OP-AB.RC-0001(Q), Reactor Coolant System Leak.

3.4 GO TO S2.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

Page 1 of 1 E-28

References:

Dwg.

203347

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 41 of 65 Rev. 19 ALARM E-29 29 SR & IR TRIP BYP M

DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

One or more Channel Bypass switches in BYPASS (2/N31B, 2/N32B, 2/N35A, or 2/N36A) 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 DETERMINE the affected NI Channel from Annunciator CRT:

CRT Point Description 389 NIS Ch N31B Source Range Trip Bypass 390 NIS Ch N32B Source Range Trip Bypass 391 NIS Ch N35A Intermediate Range Trip Bypass 392 NIS Ch N36A Intermediate Range Trip Bypass 3.2 IF the alarm is due to testing or removing a channel from service, THEN no further action is required.

3.3 IF the alarm is unexpected, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

3.4 REFER to Technical Specifications.

Page 1 of 1 E-29

References:

Dwg.

221052

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 42 of 65 Rev. 19 ALARM E-30 30 IR HI FLUX ROD WDRWL STOP DEVICES:

2NC35EX, 2NC36EX SETPOINT:

$20% Power

1.0 CAUSE(S)

Any Intermediate Range Channel is $20% with the IR Rod Withdrawal Stop not blocked.

2.0 AUTOMATIC ACTIONS:

NOTE The Rod Withdrawal Stop is manually blocked when Reactor Power is above P-10, and is automatically reinstated when Reactor Power falls below P-10.

If an Intermediate Range channel reaches 25% before the Rod Withdrawal Stop is blocked, a Reactor Trip will occur.

Automatic or Manual Rod Withdrawal is prevented.

3.0 OPERATOR ACTIONS:

3.1 IF a Reactor Trip occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.2 REDUCE power to #20% Power.

3.3 IF the alarm is due to testing, THEN no further action is required.

3.4 IF there are indications of a malfunctioning IR channel, THEN GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 1 of 1 E-30

References:

Dwg.

218913

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 43 of 65 Rev. 19 ALARM E-31 31 PR OVRPWR ROD STOP DEVICES:

2NC41LX, 2NC42LX, 2NC43LX, 2NC44LX SETPOINT:

$103%

1.0 CAUSE(S)

Any Power Range Channel is $103%

2.0 AUTOMATIC ACTIONS:

Automatic or Manual Rod Withdrawal is blocked.

3.0 OPERATOR ACTIONS:

3.1 IF a Reactor Trip occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.2 REDUCE power to #100% Power.

3.3 IF the alarm is due to testing, THEN no further action is required.

3.4 IF there are indications of a malfunctioning PR channel, THEN GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

3.5 IF the alarm is due to Rod Control System Malfunction, THEN GO TO:

S2.OP-AB.ROD-0001(Q),

Immovable/Misaligned Control Rods S2.OP-AB.ROD-0002(Q), Dropped Rod S2.OP-AB.ROD-0003(Q), Continuous Rod Motion 3.6 IF power increases due to a Steam Leak, THEN GO TO S2.OP-AB.STM-0001(Q), Excessive Steam Flow.

Page 1 of 1 E-31

References:

Dwg.

218913

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 44 of 65 Rev. 19 ALARM E-32 32 ROD DRIVE PWR SPLY GND FAULT DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

A Ground Fault on 21 or 22 Rod Drive Generator 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF AT ANY TIME, a Reactor trip occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.2 ATTEMPT to reset the Ground Detection Relay on the face of #21 MG Set Control Panel by pressing the GND ALARM RESET Push Button.

NOTE There is one Ground Detection relay for both MG sets. It monitors the common neutral the MG sets share. If both MG sets are in operation, they must be removed from service one at a time to determine which MG is affected.

(continued)

Page 1 of 2 E-32

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 45 of 65 Rev. 19 3.3 IF the ground does not clear, THEN: at the direction of the SM/CRS, A.

REMOVE 21 Rod Drive Generator from service IAW S2.OP-SO.RCS-0001(Q), Rod Control System Operation.

B.

ATTEMPT to reset the Ground Detection Relay on the face of #21 MG Set Control Panel by pressing the GND ALARM RESET Push Button.

3.4 IF the ground does not clear, THEN, at the direction of the SM/CRS:

A.

RETURN 21 Rod Drive Generator to service IAW S2.OP-SO.RCS-0001(Q), Rod Control System Operation.

B.

REMOVE 22 Rod Drive Generator from service IAW S2.OP-SO.RCS-0001(Q), Rod Control System Operation.

C.

ATTEMPT to reset the ground Detection Relay on the face of 21 MG Set Control Panel by pressing the GND ALARM RESET Push Button.

3.5 INITIATE SAP Notification to determine and correct the cause of the alarm.

Page 2 of 2 E-32

References:

Dwg.

228452 / 228459

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 46 of 65 Rev. 19 ALARM E-33 33 DEVICES:

SETPOINT:

SPARE Page 1 of 1 E-33

References:

Dwg.

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 47 of 65 Rev. 19 ALARM E-34 34 2PR1 CHANNEL UNSAFE DEVICES:

2BS-455E, 2BS457E, 2CT-455, 2CT-457 SETPOINT:

N/A

1.0 CAUSE(S)

1.1 Bistable Test Switch 2BS-455E or 2BS-457E in TEST.

1.2 Channel Test Switch 2CT-455 or 2CT-457 in TEST.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

IF Unit is in Modes 1 - 3, THEN:

3.1 REFER to Technical Specification 3.4.5.

3.2 DIRECT Maintenance to ensure the following:

A.

Both 2BS-455E AND 2BS-457E are aligned to NORMAL.

B.

Both 2CT-455 AND 2CT-457 are aligned to NORMAL.

Page 1 of 1 E-34

References:

Dwg. 220066, 244083

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 48 of 65 Rev. 19 ALARM E-35 35 2PR2 CHANNEL UNSAFE DEVICES:

2BS-456E, 2BS-474B, 2CT-456, 2CT-474 SETPOINT:

N/A

1.0 CAUSE(S)

1.1 Test Switch 2BS-456E or 2BS-474B in TEST.

1.2 Channel Test Switch 2CT-456 or 2CT-474 in TEST.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

IF Unit is in Modes 1 - 3, THEN:

3.1 REFER to Technical Specification 3.4.5.

3.2 DIRECT Maintenance to ensure the following:

A.

Both 2BS-456E AND 2BS-474E are aligned to NORMAL.

B.

Both 2CT-456 AND 2CT-474 are aligned to NORMAL.

Page 1 of 1 E-35

References:

Dwg.

220068, 244085

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 49 of 65 Rev. 19 ALARM E-36 36 PZR HTR OFF LVL LO DEVICES:

2LC459C, 2LC460C SETPOINT:

17% level

1.0 CAUSE

Either Pressurizer Level Channel (Control or Alarm) #17%

2.0 AUTOMATIC ACTIONS:

2.1 Deenergizes Pressurizer Heaters.

2.2 Isolates Letdown:

(2CV3, 2CV4, and 2CV5 close)

(2CV2 closes from Control Channel signal)

(2CV277 closes from Alarm Channel signal) 3.0 OPERATOR ACTIONS:

3.1 VERIFY actual Pressurizer level.

3.2 ISOLATE Letdown AND DEENERGIZE Pressurizer Heaters.

3.3 IF a loss of Charging capability has occurred, THEN INITIATE S2.OP-AB.CVC-0001(Q), Loss of Charging.

3.4 IF a single instrument failure has occurred, THEN INITIATE S2.OP-AB.CVC-0001(Q), Loss of Charging, for applicability.

(continued)

Page 1 of 2 E-36

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 50 of 65 Rev. 19 3.5 IF actual Pressurizer level is #17%,

THEN:

A.

TAKE Charging to manual AND INCREASE charging to restore pressurizer level to >17%.

B.

IF there is indication of an RCS Leak, THEN GO TO S2.OP-AB.RC-0001(Q), RCS Leak.

C.

When Pressurizer level is >17%:

1.

PLACE Pressurizer Heaters in service as required.

2.

ESTABLISH Letdown IAW S2.OP-SO.CVC-0001(Q),

Charging, Letdown, and Seal Injection.

D.

RESTORE Pressurizer level to program band per Figure on next page.

E.

When Pressurizer level is restored to program, RETURN Charging to automatic or as directed by SM/CRS.

3.6 REFER to Technical Specifications.

Page 2 of 2 E-36

References:

Dwg.

203347 / 221060

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 51 of 65 Rev. 19 ALARM E-37 37 CH C SDM DECRNG DEVICES:

2XA-6562 SETPOINT:

Variable

1.0 CAUSE(S)

Increasing count rate on Source Range Channel C (Gamma Metrics) 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm occurs during Reactor Startup or Core Reload, AND the alarm is expected, THEN PRESS the ALARM SETPOINT RESET pushbutton for Channel C on 2RP1.

3.2 IF counts are elevated on both Source Range Channel C and D, THEN:

A.

NOTIFY the personnel in Containment of an increase in counts.

B.

PERFORM a Shutdown Margin Calculation to ensure minimum SDM requirements are met.

C.

REQUEST that Chemistry analyze RCS Boron concentration.

D.

EVALUATE the need for immediate boration, AND NOTIFY SM/CRS.

3.3 IF an instrument failure is suspected, THEN INITIATE SAP Notification to determine and correct the cause of alarm.

3.4 REFER to Technical Specifications.

Page 1 of 1 E-37

References:

Dwg.

601649 / PSBP 304198

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 52 of 65 Rev. 19 ALARM E-38 38 UPPER SECT DEV ABV 50% PWR DEVICES:

2NC50B SETPOINT:

Upper Section QPTR $1.02

1.0 CAUSE(S)

Upper Section QPTR is $1.02, (2% deviation), with Reactor Power above 50%

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or maintenance, THEN no further action is required.

3.2 IF there are indications of a Power Range Channel malfunction, THEN GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

3.3 IF there are indications of a Rod Control System Malfunction, THEN GO TO:

S2.OP-AB.ROD-0001(Q),

Immovable/Misaligned Control Rods.

S2.OP-AB.ROD-0002(Q), Dropped Rod.

3.4 PERFORM a Quadrant Power Tilt Ratio Calculation IAW S2.OP-ST.NIS-0002(Q), Power Distribution - Quadrant Power Tilt Ratio.

3.5 REFER to Technical Specifications.

3.6 NOTIFY Reactor Engineering of the alarm and the results of the QPTR calculation.

Page 1 of 1 E-38

References:

Dwg.

220459

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 53 of 65 Rev. 19 ALARM E-39 39 PR CH DEV DEVICES:

2NC46BX SETPOINT:

$+/-5% Deviation

1.0 CAUSE(S)

$+/-5% Deviation between two Power Range NI Channels 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or maintenance, THEN no further action is required.

3.2 IF the alarm due to an instrument malfunction, THEN GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

3.3 IF the alarm is due to a Rod Control System Malfunction, THEN GO TO:

S2.OP-AB.ROD-0001(Q),

Immovable/Misaligned Control Rods.

S2.OP-AB.ROD-0002(Q), Dropped Rod.

S2.OP-AB.ROD-0003(Q), Continuous Rod Motion.

3.4 INITIATE SAP Notification to determine and correct the cause of the alarm.

Page 1 of 1 E-39

References:

Dwg.

220460 / 218914

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 54 of 65 Rev. 19 ALARM E-40 40 ROD BANK URGENT FAIL DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Any:

Power Cabinet -

Regulation failure, Phase failure, Logic failure, Multiplex failure, or Loose circuit card Logic Cabinet -

Pulser failure, Slave Cycler Input failure, or Loose circuit card 2.0 AUTOMATIC ACTIONS:

All Rod Motion in Manual or Automatic is inhibited.

3.0 OPERATOR ACTIONS:

CAUTION Rod motion should not be attempted due to the possibility of dropping rods.

NOTE At the discretion of the SM/CRS, Maintenance should be contacted to collect as found data from the control rod logic and power cabinets prior to removing power from the cabinets.

When the Reactor Trip Breakers are opened, power to the rod control cabinets is removed and solid state indicator lights will extinguish. Not having this as found data will make it very difficult to identify the problem that caused the alarm.

GO TO S2.OP-AB.ROD-0001(Q), Immovable/Misaligned Control Rods.

Page 1 of 1 E-40

References:

Dwg.

223159

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 55 of 65 Rev. 19 ALARM E-41 41 LTDWN HX OUT TEMP HI DEVICES:

2TC-130C SETPOINT:

$136°F

1.0 CAUSE(S)

Letdown Heat Exchanger outlet temperature is $136°F 2.0 AUTOMATIC ACTIONS:

2CV21 will divert coolant directly to VCT.

3.0 OPERATOR ACTIONS:

3.1 IF 2CC71 is not controlling Letdown temperature at approximately 100°F, THEN PLACE 2CC71 in manual AND ADJUST Letdown temperature to.100°F.

NOTE 2CC71 fails closed on loss of power.

3.2 VERIFY 2CV21 indicates Mixed Bed diversion to VCT at 2CC2.

3.3 IF 2CC71 is closed, THEN:

A.

CHECK status of breaker 2ADC2AX7 (2CC113, 2CC215, & 2CC71 LETDOWN DISCHARGE VALVES; located in 2AADC 125VDC Distribution Cabinet).

B.

IF 2ADC2AX7 is tripped, THEN REFER TO SC.OP-DD.ZZ-0006(Z), Protective Circuit/Breaker Reset and Reclosure Policy.

3.4 IF 2CV18 is not controlling Letdown pressure at approximately 300 psig, THEN PLACE valve in manual AND ADJUST Letdown pressure to.300 psig.

(continued)

Page 1 of 2 E-41

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 56 of 65 Rev. 19 3.5 IF Letdown temperature or pressure cannot be controlled, THEN:

A.

ISOLATE Normal Letdown as follows:

1.

CLOSE following LTDWN ORIFICE ISOL Valves, as required:

2CV3, 45 GPM ORIFICE.

2CV4, 75 GPM ORIFICE.

2CV5, 75 GPM ORIFICE.

2.

CLOSE 2CV2, LTDWN LINE ISOL V.

3.

CLOSE 2CV277, LTDWN LINE ISOL V.

4.

CLOSE 2CV7, LTDWN HX INLET V.

B.

PLACE Excess Letdown in service IAW S2.OP-SO.CVC-0003(Q),

Excess Letdown Flow.

C.

IF reduced charging flow is required for PZR level control, THEN:

1.

IF a Centrifugal Charging Pump is in service.

THEN PLACE 2CA2015, CONTROL AIR SUPPLY TO CV55 BYPASS VALVE, in BYPASS.

2.

IF 23 Charging Pump is in service, THEN:

a.

TRANSFER to a Centrifugal Charging Pump IAW S2.OP-SO.CVC-0002(Q), Charging Pump Operation.

b.

ADJUST position of linkage for 23 Charging Pump to a lower position.

c.

TRANSFER to 23 Charging Pump IAW S2.OP-SO.CVC-0002(Q), Charging Pump Operation.

D.

NOTIFY Chemistry that the demineralizer is being bypassed.

3.6 IF the alarm is due to CC System Malfunction, THEN GO TO S2.OP-AB.CC-0001(Q), Component Cooling Abnormality.

3.7 IF the alarm is due to the loss of SW Header pressure, THEN GO TO S2.OP-AB.SW-0001(Q), Loss of Service Water Header Pressure.

3.8 INITIATE SAP Notification to determine and correct the cause of the alarm.

Page 2 of 2 E-41

References:

Dwg. 211594

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 57 of 65 Rev. 19 ALARM E-42 42 2PR1 1/2 TRIP DEVICES:

2PC-455A, 2PC-457A SETPOINT:

2335 psig

1.0 CAUSES

Pressurizer Pressure Channel I or Channel III $2335 psig.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF a Reactor Trip occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.2 CONFIRM alarm by observing Pressurizer pressure.

3.3 IF alarm is due to malfunction, THEN GO TO S2.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

Page 1 of 1 E-42

References:

Dwg. 244083

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 58 of 65 Rev. 19 ALARM E-43 43 2PR2 1/2 TRIP DEVICES:

2PC-456A, 2PC-474A SETPOINT:

2335 psig

1.0 CAUSES

Pressurizer Pressure Channel II or Channel IV $2335psig.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF a Reactor Trip occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.2 CONFIRM alarm by observing Pressurizer pressure.

3.3 IF alarm is due to malfunction, THEN REFER to Technical Specification 3.3.1.1.

Page 1 of 1 E-43

References:

Dwg.

244085

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 59 of 65 Rev. 19 ALARM E-44 44 PZR SFTY VLV 2PR3-2PR5 NOT CLSD DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

One or more Pzr Code Safety Valves are not fully closed.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 CONFIRM the alarm by observing individual tailpipe temperatures on 2CC2.

3.2 IF RCS pressure is normal and a Safety Valve leak is indicated, THEN GO TO S2.OP-AB.RC-0001(Q), Reactor Coolant System Leak.

3.3 IF RCS pressure is excessive, THEN:

A.

Manually TRIP the reactor.

B.

GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.4 IF no Safety Valve leakage is indicated, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

Page 1 of 1 E-44

References:

Dwg.

203464

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 60 of 65 Rev. 19 ALARM E-45 45 CH D SDM DECRNG DEVICES:

2XA-6563 SETPOINT:

Variable

1.0 CAUSE(S)

Increasing count rate on Source Range Channel D (Gamma Metrics) 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm occurs during Reactor Startup or Core Reload, AND the alarm is expected, THEN PRESS the ALARM SETPOINT RESET pushbutton for Channel D on 2RP1.

3.2 IF counts are elevated on both Source Range Channel C and D, THEN:

A.

NOTIFY the personnel in Containment of an increase in counts.

B.

PERFORM a Shutdown Margin Calculation to ensure minimum SDM requirements are met.

C.

REQUEST that Chemistry analyze RCS Boron concentration.

D.

EVALUATE the need for immediate boration, AND NOTIFY SM/CRS.

3.3 IF an instrument failure is suspected, THEN INITIATE SAP Notification to determine and correct the cause of the alarm.

3.4 REFER to Technical Specifications.

Page 1 of 1 E-45

References:

Dwg.

601649 / PSBP 304198

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 61 of 65 Rev. 19 ALARM E-46 46 LOWER SECT DEV ABV 50% PWR DEVICES:

2NC50D SETPOINT:

Lower Section QPTR $1.02

1.0 CAUSE(S)

Lower Section QPTR is $1.02, (2% deviation), with Reactor Power above 50%.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or maintenance, THEN no further action is required.

3.2 IF there are indications of a Power Range Channel malfunction, THEN GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

3.3 IF there are indications of a Rod Control System Malfunction, THEN GO TO:

S2.OP-AB.ROD-0001(Q),

Immovable/Misaligned Control Rods.

S2.OP-AB.ROD-0002(Q), Dropped Rod.

3.4 PERFORM a Quadrant Power Tilt Ratio Calculation IAW S2.OP-ST.NIS-0002(Q), Power Distribution - Quadrant Power Tilt Ratio.

3.5 REFER to Technical Specifications.

3.6 NOTIFY Reactor Engineering of the alarm and the results of the QPTR calculation.

Page 1 of 1 E-46

References:

Dwg.

220459

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 62 of 65 Rev. 19 ALARM E-47 47 PR NEUT FLUX RATE HI DEVICES:

Increasing:

2NC41U, 2NC42U, 2NC43U, 2NC44U Decreasing:

2NC41K, 2NC42K, 2NC43K, 2NC44K SETPOINT:

Increasing:

$+5% per 2 second change Decreasing:

Setpoint functionally defeated per DCP 80092664 / 80094424

1.0 CAUSE(S)

$+5% Change of Power in a 2 second period on any Power Range Channel 2.0 AUTOMATIC ACTIONS:

NOTE 2-of-4 High Flux Rates will trip reactor.

None 3.0 OPERATOR ACTIONS:

NOTE Hi Flux Rate Bistables must be reset at NIS Cabinets.

3.1 IF the alarm is due to testing, THEN no further action is required.

3.2 IF a Reactor Trip occurs, THEN GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.3 IF the alarm is due to a malfunction in a Power Range channel, THEN GO TO S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

3.4 IF there are indications of a Rod Control System Malfunction, THEN GO TO:

S2.OP-AB.ROD-0001(Q),

Immovable/Misaligned Control Rods.

S2.OP-AB.ROD-0002(Q), Dropped Rod.

Page 1 of 1 E-47

References:

Dwg.

221053

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 63 of 65 Rev. 19 ALARM E-48 48 ROD BOTTOM DEVICES:

Relays 57CR through 63CR in Rod Control Cabinets SETPOINT:

Any Shutdown Bank Rod:

<20 Steps Control Bank A Rod:

<20 Steps Control Bank B-D Rod:

<20 steps (with Gp Demand >35 steps)

1.0 CAUSE(S)

Any:

1.1 Shutdown Bank Rod:

<20 Steps 1.2 Control Bank A Rod:

<20 Steps 1.3 Control Bank B-D Rod:

<20 steps with the respective Group Demand >35 steps 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF the alarm is due to testing or a normal plant evolution, THEN no further action is required.

3.2 IF there are indications of a dropped rod, THEN GO TO S2.OP-AB.ROD-0002(Q), Dropped Rod.

3.3 IF there are indications of an IRPI failure, THEN GO TO S2.OP-AB.ROD-0004(Q), Rod Position Indication Failure.

Page 1 of 1 E-48

References:

Dwg.

226066

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 64 of 65 Rev. 19 OVERHEAD ANNUNCIATORS WINDOW E REFERENCES 1.0 Plant Documents:

1.1 Technical Specifications, Unit 2 1.2 Updated Final Safety Analysis Report 2.0 Reference Drawings:

2.1 203347, Pressurizer Heaters Schematic 2.2 203464, Pzr and PRT Valves & Temperatures 2.3 203494, Computer Wiring Diagram 2.4 205328, No. 2 Unit, Chemical & Volume Control Operation 2.5 211562, CVCS Schematic 2.6 211594, CVCS Schematic 2.7 218851, BA Batch Tank 2.8 218913, Rod Control Schematic 2.9 218914, Rod Control Schematic 2.10 220079, Pzr Overpressure Protection 2.11 220091, Rod Control Wiring Diagram 2.12 220459, PR Upper/Lower Section Deviation 2.13 220460, PR Deviation 2.14 221052, NI Trips/Alarms 2.15 221053, NI Trips/Alarms 2.16 221055, Pressurizer Pressure/Level Trips/Alarms 2.17 221060, Pressurizer Pressure/Level Trips/Alarms 2.18 223159, Rod Control System 2.19 224384, No.2 Unit Component Cooling System 2.20 226066, Rod Control System 2.21 228459, Rod Drive MG Sets 2.22 244082, Pzr Controls Schematic 2.23 244083, Pzr Controls Schematic 2.24 244084, Pzr Controls Schematic 2.25 244085, Pzr Controls Schematic 2.26 601649, Shutdown Monitor

3.0 PSBPs

3.1 304209, Westinghouse Precautions, Limitations, and Setpoints.

3.2 304198, Gamma-Metrics Model RCS-30 Shutdown Monitor Instruction Manual.

4.0 Other

4.1 DCP 2EC-3225, Boric Acid Concentration Reduction 4.2 DCP 2EC-3585, CCW Letdown Temperature Control Valve Modification 4.3 Calculations S-C-CA-MDC-1169 and S-C-CA-MEE-0433-01

S2.OP-AR.ZZ-0005(Q)

Salem 2 Page 65 of 65 Rev. 19 5.0 Cross

References:

5.1 2-EOP-TRIP-1, Reactor Trip or Safety Injection 5.2 SC.OP-DD.ZZ-0006(Z), Protective Circuit/Breaker Reset and Reclosure Policy 5.3 S2.OP-AB.CA-0001(Q), Loss of Control Air 5.4 S2.OP-AB.CC-0001(Q), Component Cooling Abnormality 5.5 S2.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions 5.6 S2.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction 5.7 S2.OP-AB.RC-0001(Q), Reactor Coolant System Leak 5.8 S2.OP-AB.ROD-0001(Q), Immovable/Misaligned Control Rods 5.9 S2.OP-AB.ROD-0002(Q), Dropped Rod 5.10 S2.OP-AB.ROD-0003(Q), Continuous Rod Motion 5.11 S2.OP-AB.ROD-0004(Q), Rod Position Indication Failure 5.12 S2.OP-AB.STM-0001(Q), Excessive Steam Flow 5.13 S2.OP-AB.SW-0001(Q), Loss of Service Water Header Pressure 5.14 S2.OP-DL.ZZ-0003(Q), Control Room Readings - Modes 1-4 5.15 S2.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection Flow 5.16 S2.OP-SO.CVC-0003(Q), Excess Letdown Flow 5.17 S2.OP-SO-CVC-0006(Q), Boron Concentration Control 5.18 S2.OP-SO.CVC-0008(Q), Rapid Boration 5.19 S2.OP-SO.PZR-0004(Q), Pressurizer Overpressure Protection Operation 5.20 S2.OP-SO.RCS-0001(Q), Rod Control System Operation 5.21 S2.OP-SO.RPS-0003(Q), Placing Pressurizer Channel in Tripped Condition 5.22 S2.OP-ST.NIS-0002(Q), Power Distribution - Quadrant Power Tilt Ratio 5.23 S2.OP-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance 5.24 S2.OP-ST.RCS-0001(Q), Reactivity Control System - Rod Control Assemblies 5.25 S2.OP-DL.ZZ-0003(Q), Control Room Log - Modes 1-4

ML110060816

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