Text

Salem/Operations, S1.OP-AR.ZZ-0005(Q), Rev. 17, Overhead Annunciators Window E
	ML110060582
Person / Time
Site:	Salem
Issue date:	07/01/2010
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	LR-N10-0355 S1.OP-AR.ZZ-0005(Q), Rev 17
	Download: ML110060582 (66)
	v • d • e

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

SALEM/OPERATIONS S1.OP-AR.ZZ-0005(Q) REV. 17 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 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 S1.OP-DL.ZZ-0003(Q).

IMPLEMENTATION REQUIREMENTS Effective Date:

July 1, 2010 None

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 1 of 65 Rev. 17 OVERHEAD ANNUNCIATORS WINDOW E TABLE OF CONTENTS SECTION PAGE Table of Contents..................................................................... 1 Window E Overview.................................................................. 3 Text............................................................................... 4 WINDOW TITLE E-1 11 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 12 SEAL WTR INJ FLTR P HI............................................. 13 E-10 POPS CH I DISARM / 1PR6 CLSD........................................... 14 E-11 POPS CH II DISARM / 1PR7 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

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 2 of 65 Rev. 17 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 1PR1 NOT FULL CLSD.................................................... 38 E-27 1PR2 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 1PR1 CHANNEL UNSAFE................................................. 47 E-35 1PR2 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 1PR1 1/2 TRIP............................................................ 57 E-43 1PR2 1/2 TRIP............................................................ 58 E-44 PZR SFTY VLV 1PR3 - 1PR5 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

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 3 of 65 Rev. 17 1

11 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

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

1PR6 CLSD 11 POPS CH II DISARM/

1PR7 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 1PR1 NOT FULL CLSD 27 1PR2 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 1PR1 CHANNEL UNSAFE 35 1PR2 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 1PR1 1/2 TRIP 43 1PR2 1/2 TRIP 44 PZR SFTY VLV 1PR3-1PR5 NOT CLSD 45 CH D SDM DECRNG 46 LOWER SECT DEV ABV 50% PWR 47 PR NEUT FLUX RATE HI 48 ROD BOTTOM

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 4 of 65 Rev. 17 ALARM E-1 1

11 SEAL WTR INJ FLTR P HI DEVICES:

1PIC-189B SETPOINT:

$20 psid

1.0 CAUSE(S)

$20 psid across Seal Injection Filter 11 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 ENSURE normal CVC System parameters.

3.2 ENSURE 1CV71 and 1CV55 are adjusted to maintain seal injection flow of 6-10 gpm to each RCP.

3.3 IF alarm is valid, THEN:

A.

PLACE 12 Seal Injection Filter in service IAW S1.OP-SO.CVC-0001(Q).

B.

ENSURE alarm clears.

C.

INITIATE SAP Notification to replace 11 Seal Water Injection Filter.

3.4 IF alarm is not valid, THEN NOTIFY Maintenance to determine and correct cause of alarm.

Page 1 of 1 E-1

References:

Dwg.

211562

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 5 of 65 Rev. 17 ALARM E-2 2

POPS CH I ARM DEVICES:

1TC-413C SETPOINT:

$312°F

1.0 CAUSE(S)

POPS Ch I armed with Loop 11 WR T Cold $312°F 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 CONFIRM alarm by observing RCS Temperature indication on console.

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

3.3 IF alarm is due to a 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 NOTIFY Maintenance to investigate and correct cause.

3.5 REFER to Technical Specifications.

Page 1 of 1 E-2

References:

Dwg.

241106

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 6 of 65 Rev. 17 ALARM E-3 3

POPS CH II ARM DEVICES:

1TC-423C SETPOINT:

$312°F

1.0 CAUSE(S)

POPS Ch II armed with Loop 12 WR T Cold $312°F 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 CONFIRM alarm by observing RCS Temperature indication on console.

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

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

3.4 IF alarm is due to a malfunction, THEN NOTIFY Maintenance to investigate and correct cause.

3.5 REFER to Technical Specifications.

Page 1 of 1 E-3

References:

Dwg.

242881

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 7 of 65 Rev. 17 ALARM E-4 4

PZR LVL HI DEVICES:

1LC459A, 1LC460A, 1LC461A 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 S1.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 1-EOP-TRIP-1, Reactor Trip or Safety Injection.

Page 1 of 1 E-4

References:

Dwg.

221055

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 8 of 65 Rev. 17 ALARM E-5 5

SR DET VOLT TRBL DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Either of following:

1.1 Either SR channel deenergized with Turbine Power <15% (P-2) 1.2 Either 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 alarm is due to P-6 Block during Reactor Start-up, testing or maintenance, THEN no further action is required.

3.2 GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunction.

Page 1 of 1 E-5

References:

Dwg.

218914

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 9 of 65 Rev. 17 ALARM E-6 6

IR DET VOLT LOSS DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Loss of Detector voltage on either IR Channel 2.0 AUTOMATIC ACTIONS:

NOTE If Reactor Power is below P-10, a 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 1-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.3 GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunction.

Page 1 of 1 E-6

References:

Dwg.

218914

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 10 of 65 Rev. 17 ALARM E-7 7

PR DET VOLT LOSS DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Loss of Detector Volts on one or more PR channels 2.0 AUTOMATIC ACTIONS:

NOTE Power Range Overpower Rod Stop may occur.

Loss of Power to 2-out-of-4 Power Ranges will result in a 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 a Reactor Trip occurs, THEN GO TO 1-EOP-TRIP-1, Reactor Trip or Safety Injection.

3.3 GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunction.

Page 1 of 1 E-7

References:

Dwg.

218914

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 11 of 65 Rev. 17 ALARM E-8 8

ROD INSERT LMT LO M

DEVICES:

1DC412A, 1DC422A, 1DC432A, 1DC442A 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 505 Rod Insertion Limit Low (411)

Bank A 506 Rod Insertion Limit Low (421)

Bank B 507 Rod Insertion Limit Low (431)

Bank C 508 Rod Insertion Limit Low (441)

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 S1.OP-ST.RCS-0001(Q), Reactivity Control System - Rod Control Assemblies, THEN no further action is required.

Page 1 of 2 E-8

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 12 of 65 Rev. 17 3.5 IF cause of alarm is a dropped rod, THEN GO TO S1.OP-AB.ROD-0002(Q), Dropped Rod.

3.6 IF cause of alarm is a misaligned rod, THEN GO TO S1.OP-AB.ROD-0001(Q), Immovable/Misaligned Rod.

NOTE This alarm will reset when affected Rods have been withdrawn at least 12 steps above Rod Insertion Limit.

3.7 COMMENCE Boron Addition to restore Rods to their normal band IAW S1.OP-SO.CVC-0006(Q), Boron Concentration Control.

3.8 IF 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 S1.OP-DL.ZZ-0003(Q), Control Room Readings - Modes 1-4.

(Technical Specification Surveillance 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

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 13 of 65 Rev. 17 ALARM E-9 9

12 SEAL WTR INJ FLTR P HI DEVICES:

1PIC-189A SETPOINT:

$20 psid

1.0 CAUSE(S)

$20 psid across Seal Injection Filter 12 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 ENSURE normal CVC System parameters.

3.2 ENSURE 1CV71 and 1CV55 are adjusted to maintain seal injection flow of 6-10 gpm to each RCP.

3.3 IF alarm is valid, THEN:

A.

PLACE 11 Seal Injection Filter in service IAW S1.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection Flow.

B.

ENSURE alarm clears.

C.

INITIATE SAP Notification to replace 12 Seal Water Injection Filter.

3.4 IF alarm is not valid, THEN NOTIFY Maintenance to determine and correct cause of alarm.

Page 1 of 1 E-9

References:

Dwg.

211562

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 14 of 65 Rev. 17 ALARM E-10 10 POPS CH I DISARM/

1PR6 CLSD DEVICES:

1TC-413A SETPOINT:

312°F

1.0 CAUSE(S)

Either of following with RCS Loop 11 WR T Cold #312°F:

1.1 POPS CH I disarmed 1.2 1PR6 closed 2.0 AUTOMATIC ACTIONS:

2.1 POPS CH I disarmed: Reinstates 2335 psig setpoint on 1PR1 2.2 1PR6 closed:

None 3.0 OPERATOR ACTIONS:

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

3.2 MONITOR status of RCS Temperature, POPS CH I, and 1PR6.

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 S1.OP-SO.PZR-0004(Q),

Pressurizer Overpressure Protection Operation.

3.4 IF 1PR6 is closed, THEN OPEN 1PR6.

3.5 IF alarm is invalid, THEN NOTIFY Maintenance to investigate and correct cause of alarm.

3.6 REFER to Technical Specifications.

Page 1 of 1 E-10

References:

Dwg.

241106 / 241107

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 15 of 65 Rev. 17 ALARM E-11 11 POPS CH II DISARM/

1PR7 CLSD DEVICES:

1TC-423C SETPOINT:

312°F

1.0 CAUSE(S)

Either of following with RCS Loop 12 WR T Cold #312°F:

1.1 POPS CH II disarmed 1.2 1PR7 closed 2.0 AUTOMATIC ACTIONS:

2.1 POPS CH II disarmed: Reinstates 2335 psig setpoint on 1PR2 2.2 1PR7 closed:

None 3.0 OPERATOR ACTIONS:

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

3.2 MONITOR status of RCS Temperature, POPS CH II, and 1PR7.

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 S1.OP-SO.PZR-0004(Q),

Pressurizer Overpressure Protection Operation.

3.4 IF 1PR7 is closed, THEN OPEN 1PR7.

3.5 IF alarm is invalid, THEN NOTIFY Maintenance to investigate and correct cause of alarm.

3.6 REFER to Technical Specifications.

Page 1 of 1 E-11

References:

Dwg.

242881 / 242882

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 16 of 65 Rev. 17 ALARM E-12 12 PZR PRESS LO M

DEVICES:

1PC-455D, 1PC-456D, 1PC-457D SETPOINT:

1765 psig

1.0 CAUSE(S)

One or more Channels of pressurizer pressure #1765 psig 2.0 AUTOMATIC ACTIONS:

NOTE 2-out-of-3 Channels will initiate a Safety Injection.

None 3.0 OPERATOR ACTIONS:

3.1 DETERMINE affected Channel(s) from Annunciator CRT:

CRT Point Description 426 Pressurizer Pressure Low Channel I (1PC-455D) 427 Pressurizer Pressure Low Channel II (1PC-456D) 428 Pressurizer Pressure Low Channel III (1PC-457D) 3.2 IF alarm is due to testing, maintenance, or is normal for plant conditions, THEN no further action is required.

Page 1 of 2 E-12

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 17 of 65 Rev. 17 3.3 IF a Reactor Trip or Safety Injection occurs, THEN GO TO 1-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 S1.OP-AB.RC-0001(Q), RCS Leak.

3.5 IF actual RCS Pressure control problem exists, THEN GO TO S1.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

3.6 IF a single Pressurizer Channel is malfunctioning, THEN:

A.

NOTIFY Maintenance to investigate and repair channel.

B.

REMOVE malfunctioning channel from service IAW S1.OP-SO.RPS-0003(Q),

Placing Pressurizer Channel In Tripped Condition.

Page 2 of 2 E-12

References:

Dwg.

221055

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 18 of 65 Rev. 17 ALARM E-13 13 SR HI FLUX AT S/D DEVICES:

1NC31C, 1NC32C 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)

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

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 on next page)

Page 1 of 2 E-13

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 19 of 65 Rev. 17 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 1RP2.

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

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 20 of 65 Rev. 17 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 alarm is due to testing or maintenance, THEN no further action is required.

3.2 GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunctions.

Page 1 of 1 E-14

References:

Dwg.

218914

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 21 of 65 Rev. 17 ALARM E-15 15 PR HI RNG FLUX HI DEVICES:

1NC41R, 1NC42R, 1NC43R, 1NC44R SETPOINT:

$109%

1.0 CAUSE(S)

One or more PR High Range Channels at $109%

2.0 AUTOMATIC ACTIONS:

NOTE 2-out-of-4 PR High Flux Channel Trips will cause a 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 alarm is due to a Control Rod Misalignment, OR two or more channels are $109%,

THEN:

A.

TRIP Reactor.

B.

CONFIRM the Reactor Trip.

C.

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

3.3 IF alarm is due to an instrument malfunction, THEN GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunction.

Page 1 of 1 E-15

References:

Dwg.221052

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 22 of 65 Rev. 17 ALARM E-16 16 ROD INSERT LMT LO-LO M

DEVICES:

1DC412B, 1DC422B, 1DC432B, 1DC442B SETPOINT:

At insertion limits

1.0 CAUSE(S)

One or more of Control Rod Banks (A, B, C, or D), at 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 509 Rod Insertion Limit Low-Low (411)

Bank A 510 Rod Insertion Limit Low-Low (421)

Bank B 511 Rod Insertion Limit Low-Low (431)

Bank C 512 Rod Insertion Limit Low-Low (441)

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 S1.OP-ST.RCS-0001(Q), Reactivity Control System - Rod Control Assemblies, THEN no further action is required.

3.5 COMMENCE Rapid Boration IAW S1.OP-SO.CVC-0008(Q), Rapid Boration.

Page 1 of 2 E-16

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 23 of 65 Rev. 17 3.6 IF cause of alarm is a dropped rod, THEN GO TO S1.OP-AB.ROD-0002(Q), Dropped Rod.

3.7 IF cause of alarm is a misaligned rod, THEN GO TO S1.OP-AB.ROD-0001(Q), Immovable/Misaligned Rod.

NOTE This alarm will reset when affected Rods have been withdrawn at least 2 steps above Rod Insertion Limit.

3.8 IF 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 S1.OP-DL.ZZ-0003(Q), Control Room Readings - Modes 1-4.

(Technical Specification Surveillance 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

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 24 of 65 Rev. 17 ALARM E-17 17 BA BATCH TK LVL LO DEVICES:

1LIC-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 alarm is due to Boric Acid Batch Transfer, THEN ENSURE alarm is cleared when transfer complete.

3.2 IF alarm is unexpected, THEN SEND an operator to investigate and correct cause of alarm.

Page 1 of 1 E-17

References:

Dwg.

218851

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 25 of 65 Rev. 17 ALARM E-18 18 POPS CH I AUX AIR PRESS LO DEVICES:

1PD-9862 SETPOINT:

90 psig

1.0 CAUSE(S)

Low air pressure on POPS Ch I Air Accumulator (1PR1) 2.0 AUTOMATIC ACTIONS:

NOTE This alarm indicates that a problem exists in the air supply for 1PR1, 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 1PR1.

At this time, the Accumulators should still be charged to.120 psig.

3)

As 1PR1 is cycled, the Accumulators begin to depressurize and, at 90 psig, cause this alarm. If the CA header pressurizes 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 #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

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 26 of 65 Rev. 17 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 S1.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 700-1AB.

C.

PERFORM a valve lineup on Accumulator air supply.

3.4 NOTIFY Maintenance to investigate and correct alarm.

3.5 REFER to Technical Specifications.

Page 2 of 2 E-18

References:

Dwg.

244083 / 205347 Sh 3

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 27 of 65 Rev. 17 ALARM E-19 19 POPS CH II AUX AIR PRESS LO DEVICES:

1PD-9863 SETPOINT:

90 psig

1.0 CAUSE(S)

Low air pressure on POPS Ch II Air Accumulator (1PR2) 2.0 AUTOMATIC ACTIONS:

NOTE This alarm indicates that a problem exists in the air supply for 1PR2, 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 1PR2. At this time, the Accumulators should still be charged to.120 psig.

3)

As 1PR2 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

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 28 of 65 Rev. 17 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 S1.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 700-1AC.

C.

PERFORM a valve lineup on Accumulator air supply.

3.4 NOTIFY Maintenance to investigate and correct alarm.

3.5 REFER to Technical Specifications.

Page 2 of 2 E-19

References:

Dwg.

244085 / 205347 Sh 3

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 29 of 65 Rev. 17 ALARM E-20 20 PZR HTR ON LVL HI DEVICES:

1LC459-EX SETPOINT:

Computer generated to be 5% above program

1.0 CAUSE(S)

Pressurizer level 5% or more 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 VERIFY that pressurizer level is 5% above program value as shown on Figure next page.

3.3 IF an instrument failure exists, THEN:

A.

SELECT an operable channel for Control and Alarm.

B.

REFER to Technical Specifications.

C.

REMOVE inoperable channel from service IAW S1.OP-SO.RPS-0003(Q),

Placing Pressurizer Channel in Tripped Condition.

D.

REFER to S1.OP-AB.CVC-0001(Q), Loss of Charging, for applicability.

3.4 IF actual pressurizer level is above program, THEN:

A.

REDUCE charging OR INCREASE letdown to restore pressurizer level to program value of Figure 1 below.

B.

MATCH TAVE to TREF.

(continued on next page)

Page 1 of 2 E-20

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 30 of 65 Rev. 17 3.4 (continued)

C.

IF normal letdown cannot be placed in service, THEN PLACE Excess Letdown in service IAW S1.OP-SO.CVC-0003(Q), Excess Letdown Flow.

Page 2 of 2 E-20

References:

Dwg.

203347

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 31 of 65 Rev. 17 ALARM E-21 21 SR HI FLUX AT S/D BLOCKED DEVICES:

1PC-505CX SETPOINT:

15% Power (P-2)

1.0 CAUSE(S)

Either channels' "High Flux at Shutdown" switch in BLOCK position when below P-2 (15%).

2.0 AUTOMATIC ACTIONS:

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

None 3.0 OPERATOR ACTIONS:

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

3.2 POSITION HIGH FLUX AT SHUTDOWN switch for both channels in position required by applicable IOP.

3.3 IF alarm is invalid, THEN DIRECT Maintenance to investigate and correct alarm.

Page 1 of 1 E-21

References:

Dwg.

218914

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 32 of 65 Rev. 17 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 N35 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

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

3.2 GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunctions.

Page 1 of 1 E-22

References:

Dwg.

218914

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 33 of 65 Rev. 17 ALARM E-23 23 PR LO RNG FLUX HI DEVICES:

1NC41P, 1NC42P, 1NC43P, 1NC44P SETPOINT:

$25%

1.0 CAUSE(S)

One or more PR Low Range Channels at $25% during either of following:

Power less than P-10 (10% power)

Power greater than P-10 and circuit not blocked 2.0 AUTOMATIC ACTIONS:

NOTE 2-out-of-4 Low Range High Flux Trips will initiate a 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 low range flux trips should be blocked, THEN:

A.

REDUCE power to less than 25%.

B.

BLOCK trips IAW appropriate IOP.

(Continued)

Page 1 of 2 E-23

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 34 of 65 Rev. 17 3.3 IF two or more channels are $25% AND circuit has not been blocked, THEN:

A.

TRIP Reactor.

B.

CONFIRM the Reactor Trip.

C.

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

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

S1.OP-AB.ROD-0001(Q), Immoveable/Misaligned Rod S1.OP-AB.ROD-0002(Q), Dropped Rod S1.OP-AB.ROD-0003(Q), Continuous Rod Motion 3.5 IF alarm is due to an instrument malfunction, THEN GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunction.

Page 2 of 2 E-23

References:

Dwg.

221052

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 35 of 65 Rev. 17 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 on next page)

Page 1 of 2 E-24

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 36 of 65 Rev. 17 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 S1.OP-DL.ZZ-0003(Q),

Control Room Readings - 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 S1.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 S1.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 S1.OP-AB.ROD-0001(Q), Immovable/Misaligned Control Rods.

Page 2 of 2 E-24

References:

Dwg. 221228

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 37 of 65 Rev. 17 ALARM E-25 25 BA BATCH TK TEMP HI OR LO DEVICES:

1TIC-100 SETPOINT:

Hi:

$165°F Lo:

125°F

1.0 CAUSE(S)

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

None 3.0 OPERATOR ACTIONS:

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

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

3.3 NOTIFY Maintenance to correct cause of alarm.

Page 1 of 1 E-25

References:

Dwg.

218851

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 38 of 65 Rev. 17 ALARM E-26 26 1PR1 NOT FULL CLSD DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

1PR1 not fully closed 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF a RCS high pressure condition exists, THEN GO TO S1.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

3.2 IF RCS pressure is normal and 1PR1 is leaking, (hi tailpipe temperature, etc), THEN:

A.

CLOSE 1PR6.

B.

REFER to Technical Specifications.

C.

NOTIFY Maintenance to investigate and correct cause.

3.3 IF RCS pressure is normal and 1PR1 is not leaking, THEN:

A.

INITIATE S1.OP-ST.RC-0008(Q), RCS Water Inventory Balance.

B.

NOTIFY Maintenance to investigate and correct cause of alarm.

Page 1 of 1 E-26

References:

Dwg.

244083

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 39 of 65 Rev. 17 ALARM E-27 27 1PR2 NOT FULL CLSD DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

1PR2 not fully closed 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 IF a RCS high pressure condition exists, THEN GO TO S1.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

3.2 IF RCS pressure is normal and 1PR2 is leaking, (hi tailpipe temperature, etc), THEN:

A.

CLOSE 1PR7.

B.

REFER to Technical Specifications.

C.

NOTIFY Maintenance to investigate and correct cause.

3.3 IF RCS pressure is normal and 1PR2 is not leaking, THEN:

A.

INITIATE S1.OP-ST.RC-0008(Q), RCS Water Inventory Balance.

B.

NOTIFY Maintenance to investigate and correct cause of alarm.

Page 1 of 1 E-27

References:

Dwg.

244085

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 40 of 65 Rev. 17 ALARM E-28 28 PZR HTR ON PRESS LO DEVICES:

1PC-455IX SETPOINT:

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

1.0 CAUSE(S)

Selected pressurizer pressure Control Channel #2210 psig 2.0 AUTOMATIC ACTIONS:

Backup Heaters will energize (if in auto).

3.0 OPERATOR ACTIONS:

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

3.2 IF alarm is expected due to plant evolutions, THEN VERIFY 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 S1.OP-AB.RC-0001(Q), RCS Leak.

3.4 GO TO S1.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

Page 1 of 1 E-28

References:

Dwg.

203347, 221060, 221061

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 41 of 65 Rev. 17 ALARM E-29 29 SR & IR TRIP BYP M

DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

One or more of Channel Bypass switches in BYPASS (1/N31B, 1/N32B, 1/N35A, 1/N36A).

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 DETERMINE 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 alarm is due to testing or removing a channel from service, THEN no further action is required.

3.3 IF alarm is unexpected, THEN NOTIFY Maintenance to investigate and correct.

3.4 REFER to Technical Specifications.

Page 1 of 1 E-29

References:

Dwg.

221052

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 42 of 65 Rev. 17 ALARM E-30 30 IR HI FLUX ROD WDRWL STOP DEVICES:

1NC35EX, 1NC36EX SETPOINT:

$20% Power

1.0 CAUSE(S)

Either Intermediate Range Channel $20% with IR Rod Withdrawal Stop not blocked.

2.0 AUTOMATIC ACTIONS:

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

If Intermediate Range reaches 25% before Rod Withdrawal Stop blocked, Reactor Trip will occur.

Inhibits Automatic or Manual Outward Rod motion.

3.0 OPERATOR ACTIONS:

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

3.2 ATTEMPT to lower power to #20% Power.

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

3.4 IF there is indication of a malfunctioning IR channel, THEN GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

Page 1 of 1 E-30

References:

Dwg.

218913

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 43 of 65 Rev. 17 ALARM E-31 31 PR OVRPWR ROD STOP DEVICES:

1NC41LX, 1NC42LX, 1NC43LX, 1NC44LX SETPOINT:

$103%

1.0 CAUSE(S)

Any Power Range Channel $103%

2.0 AUTOMATIC ACTIONS:

BLOCKS Automatic or Manual Rod Withdrawal 3.0 OPERATOR ACTIONS:

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

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

3.3 IF there is indication of a malfunctioning PR channel, THEN GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunctions.

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

S1.OP-AB.ROD-0001(Q), Immoveable/Misaligned Rod S1.OP-AB.ROD-0002(Q), Dropped Rod S1.OP-AB.ROD-0003(Q), Continuous Rod Motion 3.5 IF power increase is due to a Steam Leak, THEN GO TO S1.OP-AB.STM-0001(Q), Excessive Steam Flow.

3.6 REDUCE power to #100% Power.

Page 1 of 1 E-31

References:

Dwg.

218913

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 44 of 65 Rev. 17 ALARM E-32 32 ROD DRIVE PWR SPLY GND FAULT DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

Ground Fault on 11 or 12 Rod Drive Generator 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

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

3.2 ATTEMPT to reset Ground Detection Relay on face of 11 MG Set Control Panel.

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

(Continued)

Page 1 of 2 E-32

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 45 of 65 Rev. 17 3.3 IF ground does not clear, THEN at discretion of SM/CRS:

A.

REMOVE 11 Rod Drive Generator from service IAW S1.OP-SO.RCS-0001(Q), Rod Control System Operation.

B.

ATTEMPT to reset Ground Detection Relay on face of 11 MG Set Control Panel.

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

A.

RETURN 11 Rod Drive Generator to service IAW S1.OP-SO.RCS-0001(Q), Rod Control System Operation.

B.

REMOVE 12 Rod Drive Generator from service IAW S1.OP-SO.RCS-0001(Q), Rod Control System Operation.

C.

RESET ground Detection Relay on face of 11 MG Set Control Panel.

3.5 NOTIFY Maintenance to investigate and correct cause of alarm.

Page 2 of 2 E-32

References:

Dwg.

228452 / 228459

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 46 of 65 Rev. 17 ALARM E-33 33 DEVICES:

SETPOINT:

SPARE Page 1 of 1 E-33

References:

Dwg.

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 47 of 65 Rev. 17 ALARM E-34 34 1PR1 CHANNEL UNSAFE DEVICES:

1BS-455E, 1BS-457E, 1CT-455, 1CT-457 SETPOINT:

N/A

1.0 CAUSE(S)

1.1 Bistable Test Switch 1BS-455E or 1BS-457E in TEST.

1.2 Channel Test Switch 1CT-455 or 1CT-457 in TEST.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 DIRECT Maintenance to ensure:

A.

Both 1BS-455E AND 1BS-457E are aligned to NORMAL.

B.

Both 1CT-455 AND 1CT-457 are aligned to NORMAL.

3.2 IF Unit is in Modes 1 - 3, THEN REFER to Technical Specifications.

Page 1 of 1 E-34

References:

Dwg. 220066, 241107

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 48 of 65 Rev. 17 ALARM E-35 35 1PR2 CHANNEL UNSAFE DEVICES:

1BS-456E, 1BS-474B, 1CT-456, 1CT-474 SETPOINT:

N/A

1.0 CAUSE(S)

1.1 Test Switch 1BS-456E or 1BS-474B in TEST.

1.2 Channel Test Switch 1CT-456 or 1CT-474 in TEST.

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 DIRECT Maintenance to ensure:

A.

Both 1BS-456E AND 1BS-474B are aligned to NORMAL.

B.

Both 1CT-456 AND 1CT-474 are aligned to NORMAL.

3.2 IF Unit is in Modes 1 - 3, THEN REFER to Technical Specifications.

Page 1 of 1 E-35

References:

Dwg.

220068, 244082

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 49 of 65 Rev. 17 ALARM E-36 36 PZR HTR OFF LVL LO DEVICES:

1LC459C, 1LC460C 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:

(1CV3, 1CV4, and 1CV5 close)

(1CV2 closes from Control Channel signal)

(1CV277 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 S1.OP-AB.CVC-0001(Q), Loss of Charging.

3.4 IF a single instrument failure has occurred, THEN INITIATE S1.OP-AB.CVC-0001(Q), Loss of Charging, for applicability.

(continued)

Page 1 of 2 E-36

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 50 of 65 Rev. 17 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 S1.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 S1.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

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 51 of 65 Rev. 17 ALARM E-37 37 CH C SDM DECRNG DEVICES:

1XA-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 1RP1.

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

A.

NOTIFY personnel in Containment of increase in counts.

B.

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

C.

REQUEST Chemistry analyze RCS for Boron concentration.

D.

EVALUATE need for immediate boration of RCS AND NOTIFY SM/CRS.

3.3 IF an instrument failure is suspected, THEN NOTIFY Maintenance to investigate and repair cause of alarm.

3.4 REFER to Technical Specifications.

Page 1 of 1 E-37

References:

Dwg.

601526 / PSBP 304198

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 52 of 65 Rev. 17 ALARM E-38 38 UPPER SECT DEV ABV 50% PWR DEVICES:

1NC50B SETPOINT:

Upper Section QPTR $1.02

1.0 CAUSE

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

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

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

3.2 IF there is indication of a Power Range Channel malfunction, THEN GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunction.

3.3 IF there is indication of a Rod Control System Malfunction, THEN GO TO:

S1.OP-AB.ROD-0001(Q), Immoveable/Misaligned Rod S1.OP-AB.ROD-0002(Q), Dropped Rod 3.4 PERFORM a Quadrant Power Tilt Ratio Calculation IAW S1.OP-ST.NIS-0002(Q), Power Distribution - Quadrant Power Tilt Ratio.

3.5 REFER to Technical Specifications.

3.6 NOTIFY Reactor Engineering of alarm AND results of QPTR calculation.

Page 1 of 1 E-38

References:

Dwg.

220459

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 53 of 65 Rev. 17 ALARM E-39 39 PR CH DEV DEVICES:

1NC46BX SETPOINT:

$+/-5% Deviation

1.0 CAUSE

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

None 3.0 OPERATOR ACTIONS:

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

3.2 IF alarm is due to an instrument malfunction, THEN GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunction.

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

S1.OP-AB.ROD-0001(Q), Immoveable/Misaligned Rod S1.OP-AB.ROD-0002(Q), Dropped Rod S1.OP-AB.ROD-0003(Q), Continuous Rod Motion 3.4 NOTIFY Maintenance to investigate and correct cause of alarm.

Page 1 of 1 E-39

References:

Dwg.

220460 / 218914

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 54 of 65 Rev. 17 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 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 S1.OP-AB.ROD-0001(Q), Immoveable/Misaligned Rod.

Page 1 of 1 E-40

References:

Dwg.

223159

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 55 of 65 Rev. 17 ALARM E-41 41 LTDWN HX OUT TEMP HI DEVICES:

1TC-130C SETPOINT:

$136°F

1.0 CAUSE

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

Temperature Control Valve 1CV21 will divert coolant to VCT.

3.0 OPERATOR ACTIONS:

3.1 IF 1CC71 is not controlling Letdown temperature at approximately 100°F, THEN PLACE valve in manual AND ADJUST Letdown temperature to approximately 100°F.

NOTE 1CC71 fails closed on loss of power.

3.2 IF 1CC71 is closed, THEN:

A.

CHECK status of breaker 1ADC2AX7 (1CC113, 1CC215, & 1CC71 LETDOWN DISCHARGE VALVES; located in 1AADC 125VDC Distribution Cabinet).

B.

IF 1ADC2AX7 is tripped, THEN REFER TO SC.OP-DD.ZZ-0006(Z), Protective Circuit/Breaker Reset and Reclosure Policy.

3.3 IF 1CV18 is not controlling Letdown pressure at approximately 300 psig, THEN PLACE valve in manual AND ADJUST Letdown pressure to approximately 300 psig.

Page 1 of 2 E-41

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 56 of 65 Rev. 17 3.4 IF Letdown temperature or pressure cannot be controlled, THEN:

A.

ISOLATE Normal Letdown as follows:

1.

CLOSE following LTDWN ORIFICE ISOL Valves, as required:

1CV3, 45 GPM ORIFICE.

1CV4, 75 GPM ORIFICE.

1CV5, 75 GPM ORIFICE.

2.

CLOSE 1CV2, LTDWN LINE ISOL V.

3.

CLOSE 1CV277, LTDWN LINE ISOL V.

4.

CLOSE 1CV7, LTDWN HX INLET V.

B.

PLACE Excess Letdown in service IAW S1.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 1CA2015, CONTROL AIR SUPPLY TO CV55 BYPASS VALVE, in BYPASS.

2.

IF 13 Charging Pump is in service, THEN:

a.

TRANSFER to a Centrifugal Charging Pump IAW S1.OP-SO.CVC-0002(Q), Charging Pump Operation.

b.

ADJUST position of linkage for 13 Charging Pump to a lower position.

c.

TRANSFER to 13 Charging Pump IAW S1.OP-SO.CVC-0002(Q), Charging Pump Operation.

D.

NOTIFY Chemistry that the demineralizer is being bypassed.

3.5 IF alarm is due to a CC System Malfunction, THEN GO TO S1.OP-AB.CC-0001(Q), CC System Malfunction.

3.6 IF alarm is due to loss of SW Header pressure, THEN GO TO S1.OP-AB.SW-0001(Q), Loss of Service Water Header Pressure.

3.7 NOTIFY Maintenance to investigate and correct cause of alarm.

Page 2 of 2 E-41

References:

Dwg. 211594, 221408

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 57 of 65 Rev. 17 ALARM E-42 42 1PR1 1/2 TRIP DEVICES:

1PC-455A, 1PC-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 1-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 S1.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.

Page 1 of 1 E-42

References:

Dwg. 241107

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 58 of 65 Rev. 17 ALARM E-43 43 1PR2 1/2 TRIP DEVICES:

1PC-456A, 1PC-474C 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 1-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.

244082

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 59 of 65 Rev. 17 ALARM E-44 44 PZR SFTY VLV 1PR3-1PR5 NOT CLSD DEVICES:

N/A SETPOINT:

N/A

1.0 CAUSE(S)

One or more Pzr Code Safety Valves not fully closed 2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

3.1 CONFIRM alarm by observing individual tailpipe temperatures on 1CC2.

3.2 IF RCS pressure is normal and a safety valve leak is indicated, THEN GO TO S1.OP-AB.RC-0001(Q), RCS Leak.

3.3 IF actual RCS pressure is excessive, THEN:

A.

TRIP Reactor.

B.

CONFIRM the Reactor Trip.

C.

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

3.4 IF no Safety Valve leakage is indicated, THEN NOTIFY Maintenance to investigate and correct cause of alarm.

Page 1 of 1 E-44

References:

Dwg.

203464

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 60 of 65 Rev. 17 ALARM E-45 45 CH D SDM DECRNG DEVICES:

1XA-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 1RP1.

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

A.

NOTIFY personnel in Containment of increase in counts.

B.

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

C.

REQUEST Chemistry analyze RCS for Boron concentration.

D.

EVALUATE need for immediate boration of RCS and notify SM/CRS.

3.3 IF an instrument failure is suspected, THEN NOTIFY Maintenance to investigate and repair cause of alarm.

3.4 REFER to Technical Specifications.

Page 1 of 1 E-45

References:

Dwg.

601526 / PSBP 304198

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 61 of 65 Rev. 17 ALARM E-46 46 LOWER SECT DEV ABV 50% PWR DEVICES:

1NC-50D SETPOINT:

Lower Section QPTR $1.02

1.0 CAUSE

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

2.0 AUTOMATIC ACTIONS:

None 3.0 OPERATOR ACTIONS:

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

3.2 IF there is indication of a Power Range Channel malfunction, THEN GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrumentation System Malfunction.

3.3 IF there is indication of a Rod Control System Malfunction, THEN GO TO:

S1.OP-AB.ROD-0001(Q), Immoveable/Misaligned Rod S1.OP-AB.ROD-0002(Q), Dropped Rod 3.4 PERFORM a Quadrant Power Tilt Ratio Calculation IAW S1.OP-ST.NIS-0002(Q), Power Distribution - Quadrant Power Tilt Ratio.

3.5 REFER to Technical Specifications.

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

Page 1 of 1 E-46

References:

Dwg.

220459

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 62 of 65 Rev. 17 ALARM E-47 47 PR NEUT FLUX RATE HI DEVICES:

Increasing:

1NC41U, 1NC42U, 1NC43U, 1NC44U Decreasing:

1NC41K, 1NC42K, 1NC43K, 1NC44K SETPOINT:

Increasing:

$+5% change in any 2 second period Decreasing:

Setpoint functionally defeated per DCP 80092664 / 80094424

1.0 CAUSE

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

NOTE 2-out-of-4 High Flux Rates will Trip Reactor.

None 3.0 OPERATOR ACTIONS:

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

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

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

3.3 IF alarm is due to a malfunction in a Power Range channel, THEN GO TO S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunction.

3.4 IF there is indication of a Rod Control System Malfunction, THEN GO TO:

S1.OP-AB.ROD-0001(Q), Immoveable/Misaligned Rod S1.OP-AB.ROD-0002(Q), Dropped Rod Page 1 of 2 E-47

References:

Dwg.

221053

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 63 of 65 Rev. 17 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)

A potentially dropped rod as determined by any of following:

1.1 Any Shutdown Bank Rod:

<20 Steps 1.2 Control Bank A Rod:

<20 Steps 1.3 Control Bank B-D Rod:

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

None 3.0 OPERATOR ACTIONS:

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

3.2 IF there is indication of a dropped rod, THEN GO TO S1.OP-AB.ROD-0002(Q), Dropped Rod.

3.3 IF there is indication of an IRPI failure, THEN GO TO S1.OP-AB.ROD-0004(Q), RPI Failure.

Page 1 of 1 E-48

References:

Dwg.

226066

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 64 of 65 Rev. 17 OVERHEAD ANNUNCIATORS WINDOW E REFERENCES 1.0 Plant Documents:

1.1 Technical Specifications, Unit 1 1.2 Updated Final Safety Analysis Report

2.0 Commitments

None

3.0 Procedures

None 4.0 Reference Drawings:

4.1 203347, No. 1 & 2 Units, Pressurizer Heaters Schematic 4.2 203464, No. 1 & 2 Units, Pzr and PRT Valves & Temperatures 4.3 211562, No. 1 & 2 Units, CVCS Schematic 4.4 211594, No. 1 & 2 Units, CVCS Schematic 4.5 218851, No. 1 & 2 Units, BA Batch Tank 4.6 218913, No. 1 & 2 Units, Rod Control Schematic 4.7 218914, No. 1 & 2 Units, Rod Control Schematic 4.8 220066, No. 1 & 2 Units, Reactor Protection and Process Control Systems 4.9 220068, No. 1 & 2 Units, Reactor Protection and Process Control Systems 4.10 220079, No. 1 & 2 Units, Pzr Overpressure Protection 4.11 220091, No. 1 & 2 Units, Rod Control Wiring Diagram 4.12 220459, No. 1 & 2 Units, PR Upper/Lower Section Deviation 4.13 220460, No. 1 & 2 Units, PR Deviation 4.14 221052, No. 1 & 2 Units, NI Trips/Alarms 4.15 221053, No. 1 & 2 Units, NI Trips/Alarms 4.16 221055, No. 1 & 2 Units, Pressurizer Pressure/Level Trips/Alarms 4.17 221060, No. 1 & 2 Units, Pressurizer Pressure/Level Trips/Alarms 4.18 221061, No. 1 & 2 Units, Pressurizer Heater Control 4.19 221228, No. 1 Unit, Computer Wiring Diagram - Controls 4.20 221408, 1AADC 125 V.D.C. Distribution Cabinet 4.21 223159, No. 1 Unit, Rod Control System 4.22 226066, No. 1 & 2 Units, Rod Control System 4.23 228459, No. 1 & 2 Units, Rod Drive MG Sets 4.24 241106, No. 1 Unit, Pzr Controls Schematic 4.25 241107, No. 1 Unit, Pzr Controls Schematic 4.26 242881, No. 1 Unit, Pzr Controls Schematic 4.27 242882, No. 1 Unit, Pzr Controls Schematic 4.28 244082, No. 1 Unit, PORV Overpressure Prot System, Ch II 4.29 601526, No. 1 Unit, Shutdown Monitor

S1.OP-AR.ZZ-0005(Q)

Salem 1 Page 65 of 65 Rev. 17 OVERHEAD ANNUNCIATORS WINDOW E REFERENCES (Continued)

5.0 PSBPs

5.1 304198, Gamma-Metrics Model RCS-30 Shutdown Monitor Instruction Manual.

5.2 304209, Westinghouse Precautions, Limitations, and Setpoints for NSSS.

6.0 Other

6.1 Following Engineering Deficiencies:

DES 91-00729 on POPS Low Air press alarm (E-18/19)

DES 91-00727 on TIC-100, BA Batch Tk Temp alarm (E-25)

DES 91-00708 on PR Neutron Flux Rate Hi Alarm Setpoint (E-47) 6.2 Calculations S-C-CA-MDC-1169 and S-C-CA-MEE-0433-01 6.3 DCP 1EC-3696, PORV Control Circuitry Modification 7.0 Cross

References:

7.1 1-EOP-TRIP-1, Reactor Trip or Safety Injection 7.2 SC.OP-DD.ZZ-0006(Z), Protective Circuit/Breaker Reset and Reclosure Policy 7.3 S1.OP-AB.CA-0001(Q), Loss of Control Air 7.4 S1.OP-AB.CC-0001(Q), CC System Malfunction 7.5 S1.OP-AB.NIS-0001(Q), Nuclear Instrument System Malfunction 7.6 S1.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction 7.7 S1.OP-AB.RC-0001(Q), RCS Leak 7.8 S1.OP-AB.ROD-0002(Q), Dropped Rod 7.9 S1.OP-AB.ROD-0001(Q), Immovable/Misaligned Rod 7.10 S1.OP-AB.ROD-0003(Q), Continuous Rod Motion 7.11 S1.OP-AB.ROD-0004(Q), RPI Failure 7.12 S1.OP-AB.STM-0001(Q), Excessive Steam Flow 7.13 S1.OP-AB.SW-0001(Q), Loss of Service Water Header Pressure 7.14 S1.OP-DL.ZZ-0003(Q), Control Room Readings - Modes 1-4 7.15 S1.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection Flow 7.16 S1.OP-SO.CVC-0003(Q), Excess Letdown Flow 7.17 S1.OP-SO-CVC-0006(Q), Boron Concentration Control 7.18 S1.OP-SO.CVC-0008(Q), Rapid Boration 7.19 S1.OP-SO.PZR-0004(Q), Pzr Overpressure Protection Operation 7.20 S1.OP-ST.RC-0008(Q), RCS Water Inventory Balance 7.21 S1.OP-SO.RCS-0001(Q), Rod Control System Motor Generator Operation 7.22 S1.OP-SO.RPS-0003(Q), Placing Pressurizer Channel In Tripped Condition 7.23 S1.OP-ST.NIS-0002(Q), Quadrant Power Tilt Ratio 7.24 S1.RE-ST.ZZ-0002(Q), Shutdown Margin Calculation

ML110060582

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