LR-N10-0355, Hope Creek, HC.OP-AR.ZZ-0011(Q), Rev. 53, Overhead Annunciator Window Box C6

From kanterella
(Redirected from ML110050594)
Jump to navigation Jump to search
Hope Creek, HC.OP-AR.ZZ-0011(Q), Rev. 53, Overhead Annunciator Window Box C6
ML110050594
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 05/03/2010
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
References
LR-N10-0355 HC.OP-AR.ZZ-0011(Q), Rev. 53
Download: ML110050594 (76)
v • d • e


Text

Page 1 of 1

Packages and Affected Document Number s incorporated into this revision: CP No. CP Rev. AD No. Rev No. None The following OPEX were incorporated into this revision: None The following OTSCs were incorporated into this revision: None Changes Attachment B5 for the CRIDS replacement computer. This was evaluated in 80095687 and is editorial. (60082603-1000)

None

12345RSP/RSSRAD MONITORMN STM LINEREMOTEA-TAKEOVERCOMPUTERRADIATIONMUX SYSTEMTROUBLEHITROUBLEPage 2Page 4Page 5Page 6DLDMN STM LINEMN STM LINEVIB MONITORBOP/CRIDSB-SYSTEMRAD HI HIRADIATIONPNL B/CCOMPUTERALARM/TRBLOR INOPDOWNSCALEC374TROUBLEPage 7Page 19Page 20Page 21Page 22RADIATIONREACTORCRDSEISMIC MONSPDSC-MONITORINGCONTROL SYS HYDR UNITPNL C673SYSTEMALARM/TRBLINOPERATIVETEMP HITROUBLEPage 24Page 47Page 49Page 50Page 52ARPM/RBMRPISROD OUTCRDTHERMALD-FLOW REFINOPERATIVEMOTIONACCUMMONITOROFF NORMALBLOCKTROUBLEALARM/TRBLPage 56Page 57Page 59Page 64Page 65RBMRODCRD SCRAMRMCSE-UPSCALE ORDRIFTDISCH VOLDISPLAYSINOPERATIVENOT DRAINEDINOPPage 67Page 68Page 69Page 70RBMCRDRODCOMPUTER PTCOMPUTER PTF-DOWNSCALE SYSTEMOVERTRAVELRETURNINTROUBLETO NORMALALARMPage 71Page 72Page 73Page 74Page 75

1. IF plant control has been transferred outside the Main Control Room, a qualified operator has been dispatc hed to the Remote Shutdown Panel AND has implemented HC.OP-IO.ZZ-0008(Q); Shut down from Outside the Control Room.
2. IF plant control has not been transferr ed outside the Main Control Room, an operator to the RSP/Local Panel/MCC to determine why one OR more of the Transfer/Remote Control Switches have been taken out of the "normal operations" position.

D4828CH A REMOTE S/D PNL TAKE OVERControl of Channel A Class 1E

RHR, SACS and Fuel Pool

Cooling Equipment is transferred

to the Remote Shutdown Panel.D4829CH B REMOTE S/D PNL TAKE

OVERControl of Channel B Class 1E

RHR, RCIC, SSWS, Safety Relief

Valves, SACS, Chiller and Fuel

Pool Cooling Equipment is

transferred to the Remote

Shutdown Panel. E-6782-0, Sht. 1, 2 J-41-1, Sht. 13 J-43-1, Sht. 8 J-49-1, Sht. 2 J-11-1, Sht. 31 J-101-1, Sht. 5, 6, 11, 13 J-103-1, Sht. 5, 6, 7, 8 J-51-1, Sht. 24, 27, 28 J-53-1, Sht. 2 H-90-0, Sht. 2

D4830CH C REMOTE S/D PNL TAKE OVERControl of Channel C Class 1E

RBVS Equipment is transferred to

the RSP.D4831CH D REMOTE S/D PNL TAKE

OVERControl of Channel D Class 1E

RCIC, RBVS, RHR, SACS, SSWS

and Chiller Systems are

transferred to the Remote

Shutdown Panel.D4832NON-1E REMOTE S/D PNL

TAKEOVERControl of Reactor Recirc Pump

BP201 Discharge Valve

HV-F031B is transferred to the

RSP and the valve closes

IF open.D4833PSV-F013A&E CTRL TKOVR

AT C631ADS Valve(s) PSV-F013A

and/or F013E open from

Local Panel 10C631.D4834CH A MCC RSS TAKE OVERDivision 1 RHR, SACS and SSWS

Valve(s) are being controlled from

MCC(s) 10B212 (various cubicles)

and/or 10B451 Cubicle 012.D4835CH C MCC RSS TAKE OVERSACS Valve EG-HV-2496C is

being controlled from

MCC 10B232 Cubicle 142.D4836CH D MSS RSS TAKE OVERRHR Valve BC-HV-F015A is

being controlled from

MCC 10B481 Cubicle 062.

Various RMS COMPUTERS(RM-11)

1.

SM/CRS of alarm condition AND possible system shutdown.

2. a Notification [to Computer Group] to investigate AND take corrective alarm.

LOCALRM-11 1 & 2 CPUs Control Bldg.

El. 162' RMS Computer RoomNone DCP No. 4-HM-0653 DCP 80067994

abnormal procedure HC.OP-AB.RPV-0008(Q), Reactor Coolant Activity.

N/AHigh steam tunnel gamma radiation as detected from

RE-N006 (A, B, C, D) at a level of

1.5x normal full power background.Alarm only M-26-1, Sht. 1 J-26-0, Sht. 2 GEK-90300, Vol. IV, Part

All indications and non-control functions of the Circulating Water System may be affected by the terminal malfunction.

1.

an operator to the affected Multiplex Un it to determine which terminal has the malfunction.

2.

the SM/CRS to initiate corrective action.

3.

an operator at the Circulating Water Structure IF determined necessary.

D2426MUX AC676 POWER SUPPLY WARNINGAlarm onlyD2427MUX AC676 POWER SUPPLYTerminal station transfers to

standby operationD2428MUX AC676 DIRECTROL SYS

FAULTTerminal station transfers to

standby operationD2429MUX BC676 POWER SUPPLY

WARNINGAlarm onlyD2430MUX BC676 POWER SUPPLYTerminal station transfer to

standby operation.D2431MUX 0C536 POWER SUPPLY

WARNINGAlarm onlyD2432MUX 0C536 POWER SUPPLYTerminal station transfers to

standby operation J-108-0, Sht. 8 E-6797-0, Sht. 1 HC-118-02 Cutler-Hammer Directrol Multiplexer Technical Manual

Multiple Various

1.

DRYWELL NOBLE GAS module 1SK-RI-4991, DRYWELL COOLER CONDENSATE FLOW module 1SK-FI-4381 AND DRYWELL SUMP LEVEL module 1SK-LI-4930 on Panel 10C604 for ALERT/HIGH LED lit

OR OPERATE LED extinguished on active channels.

2. IF alarm is high radiation (HIGH LED lit on 1SK-RI4991)

Radiation Protection to obtain a grab sample.

3. IF alarm is downscale (OPERATE LED extinguished) power supply energized.
4.

SM/CRS of alarm condition.

1SK-RI-4991DRYWELL NOBLE GAS radiation HIGH LED lit

OR downscale OPERATE LED extinguishedNone1SK-FI-4381DRYWELL COOLER

CONDENSATE FLOW high flow

HIGH LED lit, downscale

OPERATE LED extinguished

OR total flow rate (Ch 3) HIGH LED litNone M-25-1, Sht. 1 M-26-1, Sht. 2 M-41-1, Sht. 1 M-43-1, Sht. 1 M-77-1 M-87-1, Sht. 2 J-25-0, Sht. 12 J-4025-0, Sht. 1, 2 E6795-0, Sht. 2 J-R 1000-0

1SK-LI-4930DRYWELL SUMP LEVEL Flow (high flow ALERT LED lit, Failure(OPERATE LED

extinguished) OR total flow rate (Ch 3) (ALERT LED lit)None

DRYWELL NOBLE GASRadiationHigh 5.0x10

-3 uC/ccDownscale N/A 1SK-RE4991High radiation from DrywellRad Monitoring Sample System (HIGH LED lit) or downscale (OPERATE LED extinguished)

None

1. IF alarm is high radiation (HIGH LED lit) other parameters for indication of leakage in Drywell (e.g. sumps, pressure, temperatures, etc.).

IF Drywell pressure is increasing to HC.OP-AB.CONT-0001(Q); Drywell Pressure.

2. IF source of leakage can be determined to isolate (e.g. backseat valve, etc.).
3.

radiation level trend on RM-11 for rate of increase.

4.

Radiation Protection to obtain a grab sample.

5.

SM/CRS of alarm condition.

1.Valve packing, piping,

OR flange leak from Main Steam, HPCI RCIC Steam, RWCU, Core

Spray, RHR

OR Recirc Valves - Alert1A.

any valves that are permissible to backseat.

to Tech. Spec. 3.4.3.2.1B.

SM/CRS to initiate corrective action.

2.Reactor Recirc Pump Seal leakage -

Alert2.

seal stage pressures AND flows for indication of leak.

SM/CRS to initiate corrective action.3.Reactor Coolant Pressure Boundary

leak - Alert3.

to Tech. Spec 3.4.3.2 for

Action Statement AND SM/CRS.4.Power failure - Downscale4.

power supply energized from 120VAC Distribution Panel 1DJ483 Bkr 21.5.Detector failure - Downscale5A.

to Tech. Spec. 3.4.3.1.5B.

SM/CRS to initiate corrective action.

DRYWELL COOLER CONDENSATE FLOWHigh 5 gpm Downscale N/A 1SK-FE-4381High flow through drain collections from Drywell coolers (HIGH LED) lit, or downscale (OPERATE LED extinguished)

None

1.

total flow from all Drywell Coolers on 1SK-FI-4381 Channel 3 (alarm point HIGH LED lit at 5 gpm). with Drywell Floor Drain Sump flow (unidentified leakage).

2.

other parameters for indication of leakage (e.g. sumps, Drywell pressure, temperatures, etc.).

IF Drywell pressure is increasing to HC.OP-AB.CONT-0001(Q); Drywell Pressure.

3. IF source of leakage can be determined to isolate (e.g. backseat valve, etc.).
4.

flow trend on RM-11.

5.

SM/CRS of alarm condition.

1.Valve packing, piping,

OR flange leak from Main Steam, HPCI & RCIC Steam, RWCU, Feedwater

OR Recirc Valves - Alert or High1A.

any valves that are permissible to backseat.

to Tech. Spec. 3.4.3.2.

2.Reactor Recirc Pump Seal leakage - Alert or High2A.

seal stage pressures AND flows for indication of leak.

SM/CRS to initiate corrective action.3.Reactor Coolant Pressure Boundary

leak - Alert or High3A.

to Tech. Spec. 3.4.3.2

for Action Statement AND SM/CRS.4.Chilled Water Cooling Coil OR piping leak (in Cooler) - Alert or High4A. over to opposite cooling coil

on the following (lower) Drywell Coolers:(a)1AVH212(b)1BVH212(c)1CVH212(d)1DVH2125.Power failure - Downscale5A.

power supply energized from 120VAC Distribution Panel 1DJ483

Bkr. 21.6.Instrument failure - Downscale6A.

to Tech. Spec. 3.4.3.1.6B.

SM/CRS to initiate corrective action.

DRYWELL COOLER CONDENSATE FLOWHigh 5 gpm Downscale N/A 1SK-FE4382High flow through drain collections from Drywell coolers (HIGH LED lit), or downscale (OPERATE LED extinguished)

None

1.

total flow from all Drywell Coolers on 1SK-FI-4381 Channel 3 (alarm point HIGH LED lit at 5 gpm). with Drywell Floor Drain Sump flow (unidentified leakage).

2.

other parameters for indication of leakage (e.g. sumps, Drywell pressure, temperatures, etc.).

IF Drywell pressure is increasing to HC.OP-AB.CONT-0001(Q); Drywell Pressure.

3. IF source of leakage can be determined to isolate (e.g. backseat valve, etc.).
4.

flow trend on RM-11.

5.

SM/CRS of alarm condition.

1.Valve packing, piping, OR flange leak from Main Steam, HPCI & RCIC Steam, RWCU, Feedwater

OR Recirc Valves - Alert or High1A.

any valves that are permissible to backseat.

to Tech. Spec. 3.4.3.2.

2.Reactor Recirc Pump Seal leakage -

Alert or High leak.2A.

seal stage pressures AND flows for indication of SM/CRS to initiate corrective action.3.Reactor Coolant Pressure

Boundary leak - Alert or High3A.

to Tech. Spec. 3.4.3.2

for Action Statement AND SM/CRS.4.Chilled Water Cooling Coil OR piping leak (in Cooler) - Alert or High4A. over to opposite cooling coil

on the following (upper) Drywell Coolers:(a)1EVH212(b)1FVH212(c)1GVH212(d)1HVH2125.Power failure - Downscale5A.

power supply energized from 120VAC Distribution Panel 1DJ483

Bkr. 21.6.Instrument failure - Downscale6A.

to Tech. Spec. 3.4.3.1.6B.

SM/CRS to initiate corrective action.

DRYWELL SUMP LEVEL FlowAlert 21.2 gpm Ex. Pump Runtime (6 min.)Downscale N/A 1SK-LT-4930High flow to Equipment Drain

Sump (ALERT LED lit)

OR downscale (OPERATE LED extinguished)

OR Excessive Pump Runtime.

None

1.

other parameters for indication of leakage (e.g. Drywell pressure, temperatur es, radiation level, etc.).

IF Drywell pressure is increasing to HC.OP-AB.CONT-0001(Q) Drywell Pressure.

2.

flow trend on RM-11.

3.

total Drywell Sumps flow on 1SK-LI-4930 Channel 3 (alarm point - ALERT LED lit at 20.5 gpm).

to Tech. Spec. 3.4.3.2 for Action Statement.

4.

to HC.OP-AB.CONT-0006(Q), Drywell Leakage.

5.

SM/CRS of alarm condition.

1.High inleakage to the Drywell Equipment Drain Sump - Alert or High.

Inputs are as follows:1A.

Recirc Pump Seal stage pressures

AND flows.(a)Reactor Recirc Seal staging flows1B.IF source of leakage can be determined,(b)Valve stem leakage (e.g. Recirc,

Main Steam)

IF possible.(c)Reactor Recirc vents and drains(d)Equipment vents and drains1C.

SM/CRS to initiate (e)Refuel Bellows drainscorrective action.(f)Containment Spray Header drains

2.Drywell Equipment Drain Sump Cooler leak - Alert or High2A.

Chilled Water System for inventory loss.2B. sump cooler.2C.

SM/CRS to initiate corrective action.3.Power failure - Downscale3.

power supply energized from 120VAC Distribution Panel 1DJ481 Bkr 19.4.Instrument failure - Downscale4A.

to Tech. Spec. 3.4.3.1.4B.

SM/CRS to initiate corrective action.

DRYWELL SUMP LEVEL FlowAlert 4.2 gpm

Rate of Rise - .918 gpm Ex. Pump Runtime (3 min.)

Downscale N/A 1SK-LT4931High flow to Floor Drain Sump (ALERT LED lit)

OR downscale (OPERATE LED ext.)

OR High Rate of Rise in one hours OR Excessive Pump Runtime.

None

1.

other parameters for indication of leakage (e.g. Drywell radiation, pressu re, temperatures, etc.).

IF Drywell pressure is increasing to HC.OP-AB.CONT-0001(Q)) Drywell Pressure.

2.

flow trend on RM-11.

3.

to Tech. Spec. 3.4.3.2 for Action Statement.

4.

to HC.OP-AB.CONT-0006(Q), Drywell Leakage.

5.

SM/CRS of alarm condition.

1A.

any valves that are permissible to backseat.

to Tech. Spec. 3.4.3.2.1B.1.Valve packing, piping, flange, cooler leak from Main Steam, HPCI & RCIC

Steam, RWCU, Feedwater Drywell

Coolers, Control Rod Drives, RACS, Chilled Water, Reactor Head vent, miscellaneous vents and drains, RHR, Core SprayIF source of leakage can be determined, IF possible.1C.

SM/CRS to initiate corrective action.

2.Containment Spray Header leaking - Alert or High2. RHR Containment Spray Valves are closed.3.Reactor Recirc Pump Seal

leakage - Alert or High3.

seal stage pressures AND flows for indication of leak.

SM/CRS to initiate corrective action.4.Reactor Coolant Pressure Boundary

leak - Alert or High4.

to Tech. Spec. 3.4.3.2

for Action Statement and SM/CRS.5.Chilled Water Cooling Coil leak on Drywell Cooler - Alert or High5. over to opposite coil.6.Power failure - Downscale6.

power supply energized from 120VAC Distribution Panel 1DJ481

Bkr. 19.7.Instrument failure - Downscale7A.

to Tech. Spec. 3.4.3.1.7B.

SM/CRS to initiate corrective action.

Variable D11-N006A

1. IF valid HI HI Main Steam Line Radiation levels exist the following:
a.

the Reactor by placing the Mode Switch to SHUTDOWN Position.

b. the Main Steam Isolation Valves AND Steam Line Drain Isolation Valves.

D2121MN STM LINE RAD HI-HI/INOP-W Reactor Coolant Sample Valve

SV-4310 closes

IF Channels W AND X are both in alarm Vacuum Pumps trip.D2122MN STM LINE RAD

HI-HI/INOP-XReactor Coolant Sample Valve

SV-4310 closes

IF Channels W AND X are both in alarm Vacuum Pumps trip.D2123MN STM LINE RAD

HI-HI/INOP-YReactor Coolant Sample

Valve SV-4311 closes

IF Channels Y AND Z are trippedD2124MN STM LINE RAD

HI-HI/INOP-ZReactor Coolant Sample

Valve SV-4311 closes

IF Channels Y AND Z are tripped. appropriate computer point

1.

operator to Panel H11-P635 AND H11-P636 to determine which of the main st eam line radiation monitors is downscale.

2.

to Technical Specifications 3/4.3.1 IF any monitor is suspected to be inoperable.

3.

SM/CRS of alarm condition AND permission to reset effected radiation monitor.

4.

SM/CRS initiate corrective action.

RIS K610ARadiation indication for Main Steam Line Radiation Monitor AAlarm onlyRIS K610BRadiation indication for Main

Steam Line Radiation Monitor BAlarm onlyRIS K610CRadiation indication for Main

Steam Line Radiation Monitor CAlarm onlyRIS K610DRadiation indication for Main

Steam Line Radiation Monitor DAlarm only J-26-0, Sht. 2 E-6796-0 M-26-1, Sht. 2 N1-D11-5, Sht. 1, Sht. 2, Sht. 3

Loss of power to Vibration Monitoring results in the inability to detect high vibration on the equipment associated with the effected panel(s).

SM/CRS initiate action to investigate t he Vibration Monitor Panel (BC or CC 374) generating the trouble alarm (power failure/fault).

D2358VIB MON PNL CH B POWER SUPPLY Alarm only D2359VIB MON PNL CH C POWER

SUPPLY Alarm only J-108-0, Sht. 7 E-6797-0, Sht. A J-700-42, Sht. 5, 8 J-700-43, Sht. 5, 8

FSAR 7.5.1.3.7.3 BP 980408063 BP 980507140

1. IF BOP problem, the SM/CRS of the malfunction AND I&C Department to initiate corrective action.
2. IF CRIDS problem, to OP-HC-103-102-1008, CRIDS System Failures Desktop Guide

N/AMalfunction of the On-Line OR Back-up Central System Unit (CSU) portion of the On-Line

Computer SystemIn the event of on-line CSU failure, the switch able busses are

released

AND the backup CSU will select the switch able busses

AND initialize in the on-line mode.

The AVAILABLE light on the

System Configuration Panel

(1AZ618) will extinguish

AND the NOT AVAILABLE light will illuminate for the failed CSU.C04 CRIDS failover Point will alarm if system fails over for any reason.

6 Line Stall Display indicates that viewer must be closed on affected screen.

J-108-0, Sht. 8 E-6797-0, Sht. 1 J-106-80, Sht. 1 J-106-82, Sht. 1

1. CRIDS failover 1A server health screen AND note of any stalls.

1B Real Time Comp Group at x7008. 2. 6 Line Stall 2A viewer. 2B using desktop icon.

2C notification.

Multiple Various 1. the appropriate RMS Module (Rm 23A) on Panel 10C604 to determine which radiation monitor(s) is in alarm and the condi tion downscale (OPERATE LED extinguished),

high (ALERT LED lit) or high high (HIGH LED lit).

2. automatic actions, if any, have occurred.

IF not initiate appropriate action(s) manually.

3.

to appropriate Attachment listed.

4.

SM/CRS of alarm condition.

1SP-RI-4873 Attachment C1-1North Plant Vent Rad Monitors (NPV RMS) Service Building

Elev. 137' Room 3582None1SP-RI-4875 Attachment C1-2South Plant Vent Rad Monitors (SPV RMS) Service Building

Elev. 155' Room 3602None1SP-RI-4811 Attachment C1-3Filtration, Recirculation, Ventilation

System Vent Rad Monitors (FRVSV RMS) Service Building

Elev. 155' Room 3601None0SP-RI-8817 Attachment C1-4Cooling Tower Blowdown Rad

Monitor (CTB RMS) Building 9

Elev. 102'None1SP-RI-4861 Attachment C1-5Liquid Radwaste Rad Monitor (LR RMS) Service and Radwaste

Bldg. Elev. 102', Radwaste Cont.

Rm. 3343Isolates HV-5377A&B appropriate Attachment.

DISPLAY/ KEYBOARD/

PRINTER CRT READOUT Attachment C1-6AOffgas System Rad Monitors (OG RMS)NoneNone Attachment C1-6BHIGH/LOW Offgas Sample FlowNone1SP-RY-4825A

1SP-RY-4825B Attachment C1-7Drywell Atmosphere Post Accident

Radiation Monitor (DAPA) DrywellRecorders RR4825A(B)

records values DISPLAY/ KEYBOARD/

PRINTER CRT READOUTReactor Auxiliaries Cooling

System Rad Monitor (RACS RMS)

Rx Bldg Elev. 77' Room 4209None Attachment C1-8DISPLAY/ KEYBOARD/

PRINTER CRT READOUTSafety Auxiliaries Cooling System Rad Monitors (SACS RMS)

Rx Bldg Elev. 102' Room 4307

and 4309None Attachment C1-9 appropriate Attachment.

3.08E + 03 uc/sec North Plant Vent RadMonitors (NPV RMS)

LOW -RE-4873BMID -RE-4873C2HI -RE-4873C1Continuously samples the effluent flow of the North Plant Vent via a

Wide Range Gas Monitoring

System

None

1. IF alarm is high effluent radiation (CH 4 HIGH LED lit on 1SP-RI4873 Panel 10C604),

to locate source.

2.

Radiation Protection of alarm condition.

3.

to HC.OP-AB.CONT-0004(Q), Radioactive Gaseous Release.

4. IF alarm is a monitor operate failure (OPER LED extinguished / CH 1 [Low Range]

and/or CH 4 [Eff. Level] green),

power supply energized and RM-11 status.

5.

to ODCM 3.3.7.11 for normal range or Tech Spec 3.3.7.5 for accident range.

6.

SM/CRS of alarm condition.

(continued on next page)

M-70-0, Sht. 2 E-0023-1, Sht. 3 M-79-0, Sht. 1 E-6796-0 M-92-0, Sht. 2 J-R 1000-0 M-26-1, Sht. 2, J-26-0, Sht. 3

1.High effluent radiation -1.

rad levels on the following to determine source

AND corrective action from the appropriate attachment: Offgas System -

to Attachment C1-61a.IF there are no increases in rad level on the above the following:1a(1).Solid Radwaste Exhaust gaseous high radiation

Solid Radwaste Exhaust HEPA

Filter (0AVH318 or 0BVH318)

break through or malfunction(1)Solid Radwaste Exhaust

SM/CRS AND over to stand by filter.

to ODCM 3.11.2.5.

Radiation Protection to investigate source of high radiation AND isolate. (2) Chemistry Laboratory Exhaust

gaseous high radiation

Chemistry Laboratory Exhaust

HEPA Filter (0AVH307 or

0BVH307)

break through or malfunction.(2)Chemistry Laboratory Exhaust

SM/CRS AND over to standby filter.

to ODCM 3.11.2.5.

Radiation Protection to investigate source of high radiation AND isolate.2.Power failure2.

power supply energized from 480 VAC MCC 10B323, Bkr 32.

3.Monitor/Detector failure3A.

to ODCM 3.3.7.11 for low range Action Statement.3B.

to Tech Spec 3.3.7.5 for mid

or high range Action Statement.3C.

SM/CRS of failure AND Tech Spec Action Statement.4.4A.

Radiation Protection.Process flow out of range during

severe weather conditions (i.e., large

and sudden changes in atmospheric

pressures, wind velocities and rain)4B.

alignment ANDoperation of ventilation and fans.4C.WHENstorm has passed, process flow has returned to normal.

3.08E + 02 uc/secSouth Plant Vent RadMonitors (SPV RMS)

LOW - RE-4875BMID - RE-4875C2HI - RE-4875C1Continuously samples the effluent flow of the South Plant Vent via a

Wide Range Gas Monitoring

System

None

1. IF alarm is high effluent radiation (CH 4 HIGH LED lit on 1SP-RI4875 Panel 10C604),

to locate source.

2.

Radiation Protection of alarm condition.

3.

to HC.OP-AB.CONT-0004(Q), Radioactive Gaseous Release.

4. IF alarm is a monitor operate failure (OPER LED extinguished

/ CH 1 [Low Range] and/or CH 4 [Eff. Level] green),

power supply energized and RM-11 status.

5.

to ODCM 3.3.7.11 for normal range or Te ch Spec 3.3.7.5 for accident range.

6.

SM/CRS of alarm condition.

Continued on next page

M-84-1, Sht. 16 M-26-1, Sht. 2 J-R 1000-0 J-26-0, Sht. 3 E-6796-0 E-0023-1, Sht. 3

1.High effluent radiation -1A.

rad levels on the following to determine source AND Corrective Action from the appropriate attachment: (1)Reactor Building Exhaust(2)Turbine Building Exhaust(3)Turbine Building Compartment Exhaust(4)Radwaste Area Exhaust 1B.IF there are no increases in rad levels on the above the following: (1)Mechanical Vacuum Pump discharge:

SM/CRS AND Mechanical Vacuum Pump from service. (2)Gland Seal Exhauster:

SM/CRS AND changing Main Turbine Sealing Steam to Auxiliary Steam

OR removing Turbine from service. (3)Decontamination Solution Evaporator

(00E301) Vent:

system from service IAW HC.OP-RW.HB-0003(Q); Chemical

Waste System Operations AND Vent Valve HV-F512.

1.High effluent radiation - (continued)(4)Service Area Exhaust:

Radiation Protection investigate to locate source of high radiation

AND isolate. 2.Power failure2.

power supply energized from 480 VAC MCC 10B313, Bkr 32. 3.Monitor/Detector failure3A.

to ODCM 3.3.7.11 for low range Action Statement. 3B.

to Tech Spec 3.3.7.5 for mid or high range Action Statement. 3C.

SM/CRS of failure AND Tech Spec Action Statement.

1.45E + 03 uc/secFiltration, Recirculation Ventilation System Vent Rad Monitors (FRVSV RMS) Continuous samples of the effluent flow from the FRVS via a Wide

Range Gas Monitoring SystemLOW - RE-4811AMID - RE-4811B2HI - RE-4811B1

None

1. IF alarm is high effluent radiation (CH 4 HIGH LED lit on 1SP-RI4811 Panel 10C604),

to locate source.

2.

Radiation Protection of alarm condition.

3.

to HC.OP-AB.CONT-0004(Q), Radioactive Gaseous Release.

4. IF alarm is a monitor operate failure (OPER LED extinguished

/ CH 1 [Low Range] and/or CH 4 [Eff. Level] green),

power supply energized and RM-11 status.

5.

to ODCM 3.3.7.11 for normal range or Tech Spec 3.3.7.5 for accident range.

6.

SM/CRS of alarm condition.

(continued on next page)

M-84-1, Sht. 16 M-26-1, Sht. 1 E-6796-0 E-0012-1, Sht. 3 J-R 1000-0 J-26-0, Sht. 3

1.High effluent radiation1A.

action required IAW HCGS Emergency Plan. 1B.

SM/CRS AND Radiation Protection. 2.Power failure2.

power supply energized from 120 VAC Distribution Panel 1DJ483, Bkr 23. 3.Monitor/Detector failure3A.

to ODCM 3.3.7.11 for low range Action Statement. 3B.

to Tech Spec 3.3.7.5 for mid or high range Action Statement. 3C.

SM/CRS of failure AND Tech Spec Action Statement.

Cooling Tower BlowdownRad Monitor (CTB RMS)

0SP-RE-8817Monitors a sample of the Cooling Tower Blowdown before it is

discharged to the river

None

1. IF alarm is high radiation (CH 1 HIGH LED lit on 0SP-RI-8817 Panel 10C604)

AND there is a Liquid Radwaste release in progress, terminating the release.

2.

Chemistry Department to obtain grab samples.

3.

Radiation Protection of alarm condition.

4. IF alarm is downscale (CH 1 OPERATE LED extinguished) power supply energized and RM-11 status.
5.

to ODCM 3.3.7.10 and 3.11.1.1.

6.

SM/CRS of alarm condition.

1.Liquid Radwaste release in progress - High alarm1.

0SP-RI-4861, LIQUID RADWASTE AND 1SK-RI-4991, COOL TOWER BLOWDOWN (RM-11).

IF both rad levels increased together, the Radwaste release. M-09-1, Sht. 1 M-11-1, Sht. 1 M-13-1 M-26-1, Sht. 2 M-33-0, Sht. 1 E-6796-0 E-0012-1, Sht. 3 J-R 1000-0 J-26-0, Sht. 3

  • Offsite Dose Calculation Manual (ODCM)

2.Contamination in Oil Separator 00S545 gravity draining to river2.

Radiation Protection to sample gravity drain (SX-8775).

V042 IF drain is source of radiation. 3.Contamination in SACS AND SACS Heat Exchanger leaked to Service Water System.3.

rad level on SACS RMS 1SP-RE4859A1 and B1.

IF high, SM/CRS AND further. 4.Contamination in RACS

AND Heat Exchanger leaked to Service Water System.4.

rad level on RACS RMS 1SP-RE2534.

IF high, SM/CRS AND further. 5.Power failure5.

power supply energized from 208/120VAC Distribution Panel 00Y517,

Bkr 1. 6.Detector failure6A.

to ODCM Table 3.3.7.10-1, Item 2a for Action Statement. 6B.

SM/CRS of failure.

Liquid Radwaste Rad Monitor (LR RMS)

  • Adjustable per ODCM0SP-RE-4861Monitors a sample of the LiquidRadwaste discharged to theCooling Tower blowdown line to river

Isolates HV-5377A&B on high high radiat ion (HIGH LED lit on 0SP-RI-4861, Panel 10C604 Bay 2).

1. IF alarm is high-high radiation (HIGH LED lit on 0SP-RI-4861), isolation.

IF isolation has not occurred, manually.

2.

Radiation Protection to obtain grab samples.

3.

to HC.OP-AR.SP-0001(Q), Radiation Monito ring System Alarm Response-RM-11.

4. IF alarm is Monitor loss of operate (OPERATE LED extinguished) power supply energized.
5.

to ODCM 3.3.7.10 and 3.11.1.3. 6. NJPDES Thermal Monitoring is affected IF Cause 5 or 6 exists.

7.

SM/CRS of alarm condition.

1.High effluent radiation (HIGH LED lit)1. isolation, IF not, HV-5377A&B. 2.Power failure2.

power supply energized from 120 VAC Distribution Bus 1DJ483, Bkr 12. M-63-0, Sht. 1 M-26-1, Sht. 2 E-6796-0 E-0012-1, Sht. 3 J-R 1000-0 J-26-0, Sht. 3

  • Offsite Dose Calculation Manual (ODCM)

4.Detector failure4A.

to ODCM Table 3.3.7.10-1 Item 1a for Action Statement. 4B.

SM/CRS of failure. 5.RM-80 Monitor (1SPRY-4861) failure5A.

to ODCM Table 3.3.7.10-1 Item 1a, 3a or 3b for Action Statements. 5B.

Chemistry for alternate flow monitoring IAW HC.CH-TI.ZZ-0003(Q).

5C.

SM/CRS of failure AND effect on NJPDES Thermal Monitoring System (1RFXY-11494).

5D.

I&C to repair instrument. 6.Loss of Process Flow on 0SPRY-4861 and/or loss of OPERATE on

Channel 4 of 0SPRI/RY-48616A.

to ODCM Table 3.3.7.10-1

Item 3b for Action Statement.6B.Same as 5B. 6C.Same as 5C.

6D.Same as 5D.

2.20E + 4 MR/hrOffgas System RadMonitors (OG RMS)

RE-N004ARE-N004BMonitors the offgas from a sample tap between the fourth and fifth

holdup pipes of the Offgas

System

None

1. IF alarm is high radiation, to HC.OP-AB.RPV-0008(Q) Reactor Coolant Activity.
2.

Radiation Protection of alarm condition.

3. IF alarm is Downscale, power supply energized.
4.

to Tech Spec 3.11.2.7.

5.

SM/CRS of alarm condition.

1.Fuel failure - high alarm1A.

to HC.OP-AB.RPV-0008(Q);

Reactor Coolant Activity.1B.

SM/CRS of possible fuel damage.2.Resin break through

OR air bubble from Condensate OR Reactor Water Cleanup Demineralizer2A.

to HC.OP-AB.RPV-0008(Q);

Reactor Coolant Activity.2B.

SM/CRS of problem. M-69-0, Sht. 1 E-6796-0 M-26-1, Sht. 2 J-R 1000-0 E-0012-1, Sht. 3 J-26-0, Sht. 3

3.Power failure3A.

power supply energized from 120 VAC Distribution Bus 1DJ483 Bkr 4. 3B.

to Tech Spec 4.11.2.7.1 AND 3.3.7.1.4.Detector failure4A.

to Tech Spec 4.11.2.7.1

AND 3.3.7.1.4B.

SM/CRS of failure.

Off Gas System Rad Monitors(OG RMS) Flow14.5 scfh (HIGH)6.0 scfh (LOW)

PDSHL-4851(B4)Monitors the flow through the Off Gas Rad Monitor Sample

System. (Normal flow is 10 scfh

as indicated on FI-4846 at local

Offgas Vial Sample

Panel 1NC367) A low off gas flow condition DOES NOT input to the RM-11. It only inputs to Overhead Annunciator C1. This alarm may be caused by an introduction of moisture into system on

initial startup.

None

1.

Radiation Protection of alarm condition.

2.

SM/CRS of alarm condition.

1.Sample flow - high1A.

I&C to adjust flow. 2.Sample flow - low2A.

I&C to adjust flow. 2B.

Sample Pump 10P397 running, power supply energized 0C335/J034. 3.Instrument failure3A.

to Tech Spec 4.11.2.7.1.3B.

SM/CRS of Action Statement.

High - 2.0E+2 R/HRDrywell Atmosphere Post-Accident Radiation

Monitor (DAPA) Monitors Drywell Radiation RE-4825A(B)

Radiation Recorders RR4825A

AND RR4825B on Panel 10C650C records values.

1.

SM/CRS of alarm condition.

2.

Radiation Protection of alarm condition.

3.

HC.OP-AB.RPV-0008(Q), Reactor Coolant Activity.

4. plant conditions against entry conditions for Emergency Operating procedure HC.OP-EO.ZZ-0103/4(Q), Reactor Building And Radioactive Release Control.
5.

to ECG Section 3.0.

1.Fuel Failure/LOCA has occurred.1A.

Emergency Operating procedure entry conditions AND SM/CRS enter appropriate EOP. 2.Instrument Failure OR check source has occurred.2A.

instrument.2B.

the SM/CRS initiate corrective action. 2C. compliance with Tech Spec 3.3.7.5.

FSAR table 7.5.1 M-26-1, Sht. 2 Tech Spec 3.3.7.5 M-26-1, Sht. 1 DKP data HC.IC-CC.SP-0042(Q)

9.00E-5 uCi/ccReactor Auxiliaries Cooling System Rad Monitor (RACS RMS) 1SP-RE-2534Monitors a sample from the discharge piping of the Reactor

Auxiliaries Cooling System

Pumps

None

1. IF alarm is high radiation try to determine source of radiation AND . (

RACS Head Tank level for leakage into RACS.)

2.

Chemistry Department to perform the following: [

] a. RACS to identify the source(s) of inleakage AND to identify the contaminants.

b. IF RACS sample indicates contaminants, SSW Systems
c. IF a release is in progress.
3. IF alarm is downscale power supply energized.
4.

to Tech Spec 3.3.7.1.

5.

SM/CRS of alarm condition.

1.Reactor Recirc Pump Seal Cooler intersystem leak - High alarm

[

]1A.

SM/CRS AND Reactor power. Recirc Pump from service

AND IAW HC.OP-SO.BB-0002(Q).

to Tech Spec 3.4.1.1 AND 3.4.1.3. M-13-0 J-26-0, Sht. 3 M-13-1 E-6796-0 E-0012-1, Sht. 3 J-R 1000-0

2.Reactor Water Cleanup Non-Regen Heat Exchanger inter-system leak -

High alarm

[

]2A.

SM/CRS AND Reactor Water Cleanup System from service

AND . 2B. compliance with sampling requirements of UFSAR Section 5.2.3.2.2.2. 3.Reactor Water Cleanup Pump Seal Cooler intersystem leak - High alarm.

[

]3A.

SM/CRS AND Cleanup Pump from service AND

. 4.The following are normally at lower pressure than the RACS

AND leakage would be from RACS.

IF RACS is shutdown leakage could be into RACS: 4A. system(s) from service

IAW appropriate Operating Procedure.(a)Feed Gas Cooler Condenser

HA 10E306 and HA 00E306(b)Waste Evaporator Condenser

HC 0AE303(c)Distillate Sub Cooler HC 00E380(d)Crystallizer Vapor Condenser

HC 00E379(e)Crystallizer Vent Gas Cooler

HC 00E378(f)Extruder Evaporators HC 0AP380

and HC 0BP380(g)Crystallizer Bottoms Tank Vent

Gas Cooler HC 00E381(h)Concentrated Waste Tanks

HB 0AT324 and HB 0BT324(i)Reactor Building Equipment Drain

Sumps HG AE211 and HG BE211

5.Power failure5.

power supply energized from 120 VAC Distribution Bus 1DJ483, Bkr 20.6.Detector failure6A.

to Tech Spec 3.3.7.1 for Action Statement.6B.

SM/CRS of failure AND Action Statement.

6.00E-5 uCi/ccSafety Auxiliaries Cooling System Rad Monitor (SACS RMS) 1SP-RE-4859A11SP-RE-4859B1Monitors at sample points downstream of RHR Heat

Exchangers A&B (BC AE205

and BC BE205)

None

1. IF alarm is high radiation AND a RHR Heat Exchanger is in service, the A OR B RHR Pump (IF RHR pressure is greater than SACS pressure). over to opposite (A OR B) SACS loop.

(

SACS Head Tank level for leakage into SACS.)

2.

Chemistry Department to perform the following: [

] a. the SACS to identify the source(s) of inleakage AND to identify the contaminants.

b. IF SACS sample indicates contaminants, SSW Systems
c. IF a release is in progress.
3. IF alarm is downscale power supply energized.
4.

to Tech Spec 3.3.7.1 and 3.4.9.1.

5.

SM/CRS of alarm condition.

M-11-1, Sht. 1 & 2 E-6796-0 M-26-1, Sht. 1 J-26-0, Sht. 3 E-0012-1, Sht. 3 J-R 1000-0

(continued on next page)

1.RHR A or B Heat Exchanger tube intersystem leak - High alarm.

[

]1A. RHR Pump A(B)

AND RHR Heat Exchanger.

to Tech Spec 3.4.9.1

AND SM/CRS of suspected tube leak. IF needed for Shutdown Cooling opposite loop in service.1B. over to opposite (A or B) SACS loop.

to Tech Spec 3.7.1.1.2.Fuel Pool Cooling Heat Exchanger tube intersystem leak - High alarm.

[

]2A. Heat Exchanger AND SM/CRS of suspected tube leak.2B. over to opposite (A or B) SACS loop.

to Tech Spec 3.7.1.1.3.RHR Pumps A or B Seal Cooler Heat Exchanger tube intersystem leak -

High alarm (very remote possibility)

[

]3A.

to Tech Spec 3.5.1

AND SM/CRS of possible need to inop RHR Pump.

RHR Pump A(B)

AND SACS Cooler.4.Containment Instrument gas Compressors A or B Cooler leak -

High alarm4A. to opposite compressor.

SM/CRS of cooler leak.5.Power failure5A.

power supply energized from 120 VAC Distribution Bus 1DJ483, Bkr 20 for 1SP RE 4859A1

OR 1BJ483, Bkr 12 for 1SP RE 4859B1.6.Detector failure6A.

to Tech Spec 3.3.7.1 for Action

Statement.6B.

SM/CRS of failure AND Action Statement.

1.

to HC.OP-AB.IC-0001(Q), Control Rod. 2. Before resetting Rod Drive Control System (RDCS) Analyzer Attachment C2-1 for LED information received.

C012RDCS INOPControl Rod INSERT and WITHDRAW function is INHIBITED with no

associated Control Rod withdrawal

overhead alarms.

N1-C11-1050-95, Sht. 26 E-6768-0, Sht. 1 GEK-90340A, Figure 4.2

55 0111159 1000051 0111043 0110039 0101135 0101027 0100015 0010111 0010047 0110123 0011119 0011007 0001103 0001031 01001YY Y 4 Y 3 Y 2 Y 1 Y 0 W 0 1 0 1 0 1 0 1 0 1 0 1 0 1 0 1 1 0 0 1 1 0 0 1 1 0 0 1 1 0 0 0 1 1 1 1 0 0 0 0 1 1 1 1 0 0 0 0 0 0 0 1 1 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 02 06 10 14 18 22 26 30 34 38 42 46 50 54 58 X 0 X 1 X 2 X 3 X 4 XXR601L701R602R604R605L610L609L608L702L703L704L611R606R512R511R510R509R701R702R703R704R508R603L113L112L111L110L201L202L203L108 L107L607R410R409R408R407R507L204L205L206L207L210L209L302L301L213L212 L211L106L706L415L506L505L509L508L507L504L507L502L501L408L409L410L411R211R210R209R202R215R214R213R212R208R207R206R205R204R203R106R105R104R103R102R101R114R113R112R111R110R107R108R109R304R305R306R307R308R309R310R311R312R313R314R315R316R303R302R201R612R611R610R609R608R505R115R501R502R503R504R706R705R607R301R710R709R708R707R406R506R405R404R403R402R401R319R318R317L603L105L104L103L102L101L602L401L303L402L601L307L304L316L414L707L708L709L710L711L308L309L310L311L305L306L413L412L317L315L403L314L404L313L312L405L406L407L208L606L604L605L511L416L510L109L705=16=16=15=14=13=12=11=10=9=8=7=6=5=4=3=2. Date/Time Operator Name Notification Number

250°F TRS-R018

1.

Cooling Water Flow at 63 gpm.

IF not, FIC-R600 as necessary. (DRIVE WATER PC STA) (10C651C)

Transient high temperatures condition (in alarm for < one hour) are acceptable. [

] 2. IF temperature remains in alarm for > one hour WITH no downward trend, the following:

Reliability Engineering of condition AND compensatory actions be initiated (i.e., notifying Reactor Engineering s hould temperature exceed 350°F).

HC.OP-DL.ZZ-0004(Q), Attachment 6 - CRD Mechanism High Temperature Log.

D3019CRD DISCHARGE WATER TEMPNone M-47-1, Sht. 2 80058502 GEK-90337 Nov. 1983 DCP No. 4-HM-0319 and 4-HC-0231

G.E. SIL 173

1.

an operator to Local Panel 10C673 to validate alarm AND reset in accordance with HC.OP-SO.SG-0001(Z).

2. Seismic Response Spectrum Annunciator (10C650C), AND on Attachment C4-1 the lamps that are illuminated.
3.

in accordance with HC.OP-SO.SG-0001(Q).

4.

I&C to retrieve the earthquake record IAW I&C procedure.

5.

procedure HC.OP-AB.MISC-0001(Q) Acts of Nature.

6.

cause AND severity of alarm to SM/CRS.

D3977SEISMIC TROUBLE ALARMAlarm Only J-108-0, Sht. 5 E-6797-0, Sht. 6 J-707-13, Sht. 1

DateTime:Performer WHEN completed, attachment to responsible System Engineer.

1. On the lower toolbar, the PROG button to bring up the NAP NAVIGATION display.
2.

the MC NAP ANNUNCIAT button to bri ng up the MC NAP ANNUNCIATOR display.

3.

the alarm points on the display (RED/YES)

T1403LOSS OF RTP MUX DATA LINKT1402LOSS OF RMS DATA LINKYDLCRIDSALRMLOSS OF CRIDS DATA LINKT1404UPS DATA LINKT1011SPDS CONTROLLER FAILUREEVCPROGBEPRI VALIDATION PROGRAM FAILUREMCCPROGBMISCELLANEOUS CALCULATION FAILURE

4.

SM/CRS refer to Section 11 of ECG for reporting requirements. 5. At the SM/CRS discretion, the Digital Systems Group PRIOR to rebooting the SPDS Computer AND them that one or both of the SPDS computers have failed.

6. IF multiple SPDS computers have failed during off-hours AND SPDS operation is necessary, THEN the computer using the appropriate guidance below. 7. A single computer fault not resulting in lo ss of data should not be r ebooted until the Digital Systems Group has been notified.

(continued on next page)

8.

a Notification identifying which computer has failed AND any additional information that may be pertinent. 9. On the lower toolbar, the TOP button to bring up the NAP NAVIGATION display.

10.

the DLS button under SYSTEM DIAGRAMS to bring up the SYSTEM STATUS display. 11. IF no drops are red or grey, Step 25. 12.

any drop icon that is red AND ACK DROP ALARM AND THEN CLR DROP ALARM.

13.

any drop icon that is red AND DROP DETAILS to see error message.

14. IF drops 1 and 51 remain failed THEN the SPDS Controllers have failed.
15. IF drops 129 and 130 remain failed THEN the SPDS computational servers have failed.
16. IF drops 179 and 180 remain failed THEN the data link servers have failed.
17. IF drop 160 remains failed THEN the SPDS historian has failed.
18. IF drops are gray on the SYSTEM STATUS display, THEN Network Communication has been lost. The most likely cause is SPDS switch failure
19. IF rebooting the SPDS equipment from 163' Elev Computer Room THEN in this step, otherwise, to Step 25.
20. IF neither drop 1 or 51 ar e green, but one is YELLOW THEN the power toggle switch on the controller that is not YELLOW.
21. IF neither drop 129 or 130 ar e green, but one is YELLOW THEN the power button on the com puter that is not YELLOW.
22. IF neither drop 179 or 180 ar e green, but one is YELLOW THEN the power button on the com puter that is not YELLOW.
23. IF drop 160 is not green, THEN the power button on drop 160 until drop 160 is de-energized one minute AND the power button until drop 160 is energized.

(continued on next page)

24. IF rebooting the equipment above did not pr ovide at least one green controller, computational server, data lin k server or historian, THEN a complex failure has occurred and will requi re Digital Systems Group direction.
25. IF there is at least one green controller, computat ional server, data link server or historian, AND the annunciator is still energized, THEN below. 26. On the lower toolbar, the TOP button to bring up the NAVIGATION display.
27.

which buttons underneath the SYSTEM DIAGRAMS window are red. 28. IF one or more RTP icons are red, THEN RTP communication has been lost or the prim ary data link server is inoperable.

the icon to obtain detail information on the failure.

29. IF the DLS RMS icon is red, THEN RMS communication has been lost or the primary data link server is inoperable.

the icon to obtain detailed information on the failure.

30. IF the DLS CRIDS icon is red, THEN CRIDS communication has been lost or the primary data link server is inoperable.

the icon to obtain detailed information on the failure.

31. IF the DLS UPS icon is red, THEN UPS data link communication has been lost or the UPS is not in a normal state.

the icon to obtain detailed information on the failure.

32. IF the RTP, DLS, CRIDS DLS RMS or DL S UPS buttons are not in alarm, THEN on the lower toolbar, the PROG BUTTON to bring up the NAP NAVIGATION display.
33.

the MC NAP ANNUNCIAT button to bri ng up the MC NAP ANNUNCIATOR display.

34.

the points in alarm on the display (RED/YES).

35. IF T1011 is in alarm, THEN the SPDS controllers drop 1 and 51 are inoperable.

IF rebooting drops 1 and 51does not restore the controller, THEN SPDS in inoperable.

(continued on next page)

36. IF EVCPROGB is in alarm, THEN the SPDS data validation program runni ng on the computational servers, drops 129 and 130 is inoperable.

IF rebooting drops 129 and 130 does not restore the alarm, THEN SPDS is inoperable.

37. IF MCCPROGB is in alarm, THEN the miscellaneous SPDS calculation program running on computational servers 129 or 130 is inoperable.

IF rebooting drop 129 and 130 does not restore the alarm, THEN SPDS Is inoperable J-108-0, Sht 8 E-6797-0, Sht 8 ECG 80059128

80067994

1.

Recirculation Pump loop flows AND IF high. 2.

the SM/CRS to initiate corrective action.

C028RECIRC FLOW UPSCALE OR INOPRod out motion blockC049RECIRC FLOW COMPAR

OUT LIMITSRod out motion block N1-C51-1080-25, Sht. 40 N1-C51-37-1 N0-C51-1 GEK 90341

1.

to HC.OP-AB.IC-0001(Q); Control Rod.

2. compliance with Technical Specification 3.1.3.7.
3. Attachment D2-1 by marking the illuminated LEDs.

completed attachment to Maintenance and Engineering

C070RPIS ALARMA Control Rod Motion Block will be initiated.

N1-C11-1050-95, Sht. 26 E-6768-0, Sht. 1 80046701

Date/Time Operator Name Notification Number

completed attachment to Maintenance and Engineering OT 08 16 24 32 4030201000220212421404443406463626 48382818FIODFO

1. correct control rod is being withdrawn.
2.

SM/CRS of alarm condition IF abnormal OR unexpected.

C048ROD OUT BLOCKRod withdrawal inhibited.C013ROD BLOCK-REFUEL MODERod withdrawal inhibited.

N1-C11-1050-95, Sht. 13, Sht, 14, Sht. 24, Sht. 26 N1-F15-E003-28, Sht. 1 N1-F13-E010-21, Sht. 2 DCP No. 4-HM-0643

ROD OUT BLOCK Various Rod Withdrawal Inhibited Various

Rod withdrawal inhibited.

specific cause.

1.APRM upscale1A.

IAW HC.OP-AR.ZZ-0009(Q), D4.2.APRM inoperable2A IAW HC.OP-AR.ZZ-0009(Q),

C4(C5)3.APRM downscale3A.

IAW HC.OP-AR.ZZ-0009(Q)

E44.IRM upscale4A.

IAW HC.OP-AR.ZZ-0009(Q),

D35.IRM downscale5A.

IAW.. HC.OP-AR.ZZ-0009(Q),

E36.IRM inoperable.6A.

IAW HC.OP-AR.ZZ-0009(Q),

C2(C3)7.IRM not full in.7A.

IRM(s).

8.SRM upscale8A.

IAW HC.OP-AR.ZZ-0009(Q), C1. 9.SRM downscale9A.

IAW HC.OP-AR.ZZ-0009(Q), E1 10.SRM inoperable10A.

IAW HC.OP-AR.ZZ-0009(Q), C1 11.SRM not full in11A.

SRM(s).

12.RBM upscale12A.

IAW HC.OP-AR.ZZ-0011(Q), E1 13.RBM downscale13A.

IAW HC.OP-AR.ZZ-0011(Q), F1 14.RBM inoperable14A.

IAW HC.OP-AR.ZZ-0011(Q), E1 15.Scram discharge volume high15A.

IAW HC.OP-AR.ZZ-0010(Q), B4 16.Scram discharge volume16A.

IAW HC.OP-AR.ZZ-0010(Q), C4 17.Recirculation flow upscale17A.

IAW HC.OP-AR.ZZ-0011(Q), D1 18.Recirculation flow downscale18A.

IAW HC.OP-AR.ZZ-0011(Q), D1 19.Recirculation Flow Comparator19A IAW HC.OP-AR.ZZ-0011(Q), D1 20.Rod Worth Minimizer System block20A.

to NSS Computer information

21.Rod Drive Control System block21A.

IAW HC.OP-AR.ZZ-0011(Q), C221B.

IAW HC.OP-AB.IC-0001(Q).22.Service Platform Fuel Bundle loaded22A.

Jib Crane (Refuel Mode).22B.

dummy plug AM 5

WHEN fuel is not being moved.23.Refueling Bridge Hoist loaded23A.

hoist (Refuel mode).24.Refueling Bridge Hoist down24A. hoist (Refuel mode).25.Refueling Bridge over core25A. Refueling Bridge from over core (Refuel or Startup mode).26.Mode Switch in SHUTDOWN26A. Mode Switch.27.Mode Switch in REFUEL27A. Mode Switch (One rod permissive).

ROD BLOCK-REFUEL MODE VariousRod Withdrawal Inhibited Various

Rod withdrawal inhibited.

specific cause.

1.Hoist loaded (Refuel Mode, control rod out)1A.

Hoist2.Grapple down or loaded. (Refuel

Mode, control rod out)2A.

Grapple OR Grapple.3.Platform over core.

(Refuel Mode, control rod out)3A. Platform from over core.

compliance with Technical Specification 3.1.3.5.

D5268CRD AccumulatorNone M-47-1, Sht. 1 J-47-0, Sht. 3

GE SIL 294

Various Various IF Wet Bulb is > 76°F and Relative Humidity is < 60% for 60 minutes, THEN the stay of permit for Cooling Tower Blowdow n Temperature is in effect.

1.

SM/CRS of alarm condition

2. the cause of the alarm at 10Z688 Thermal Monitor Display Computer (UECR)

AND to D5920/10Z688 for further actions.

3. IF desired by the SM/CRS, Shift Chemistry Supervisor of alarm AND potential NJPDES Permit violation.

D5920/10Z688 Station Net Heat Rate in MBTU/HR. (calculated value)None D5920/10Z688 Section 1D5920/10Z688 or 0SPRI-8817 or 1RFTR-11494 Pen No. 1Cooling Tower Blowdown Effluent Temperature YD BLDG # 9.

Element in OSPRY-8817 SystemNone

D5920/10Z688 Section 2D5920/10Z688 or 0EPTR-2440 or 1RFTR-11494 Pen No. 2Delaware River Influent Temperature Element in SSWS

IntakeNone

D5920/10Z688 Section 3

1RFTR(FR,XY) are located in cabinet 10Z655B (Elev. 163' - Upper Relay Rm). M-09-1 M-10-1, Shts 1, 2, 3 M-63-0 E-9010-1 E-9011-1 Shts 1, 2 E-9010-1 E-9011-1, Shts 1, 2 J-0611-0 80046890

D5920/10Z688 or or 0SPRI-4861 or 1RFFR-11494 Pen No. 1Cooling Tower Blowdown Effluent Flow Rate Across Basin Weir.

Element in Basin Weir transmitter

in 0SPRY-4861 SystemNone D5920/10Z688 Section 4D5920/10Z688 or 1DAFR-2218 Pens 1 & 2 or 1RFFR-11494 Pens 2 & 3Station Service Water flow rates Divisions A & B (Influent flows)None D5920/10Z688 Section 5D5920/10Z688 or 0SPRI-8817CTB RMS Fail Signal (Loss of Effluent Temp)°None D5920/10Z688 Section 6D5920/ 1RFXY-11494Loss of Power to Thermal Monitor 1RFXY-11494None D5920/10Z688 Section 7D5920/ 1RFXY-11494 Memory/Halt LightsLoss of Memory for Thermal Monitor 1RFXY-11494None D5920/10Z688 Section 8D5920/10Z688Loss of Power to Thermal Monitor Display System (10Z688)None D5920/10Z688 Section 9

1. correct control rod is being withdrawn.
2.

RBM SET-UP IF applicable.

C026EITHER RBM CHANNEL UPSCALERod motion blockC027EITHER RBM CHANNEL

INOPERATIVERod motion block N1-C51-1080-25, Sht. 47 N1-C51-1080-25, Sht. 48 N0-C51-1-2 GEK 90341

1. which control rod(s) is/are drifting by monitoring the full-core display.
2. IF it is determined that multiple cont rol rods have/are drifted/drifting, the Reactor AND HC.OP-AB.ZZ-0000(Q); Reactor Scram. [

] 3.

to Technical Specification 3/4.1.3 and 3/4.2 for applicab ility and statements.

4.

an OD-7 printout. [-] 5. Reactor thermal limits IAW Technical Specifications 3.2.1, 3.2.3, and 3.2.4.

6.

the On-Call Reactor Engineer IAW HC.RE-AP.ZZ-0101(Q);

Interim Reactor Operating Instructions. [

] 7.

the SM/CRS of alarm condition. 8. Using the Reactor Engineer's instructions AND HC.RE-IO.ZZ- 0001(Q), Core Operations Guidelines, the mispositioned control rod.

9. IF multiple rods have drifted, THEN the RE manager is informed. a coolant sample is taken and analyzed.

C078ROD DRIFT ALARMAlarm only M-46-1 CD-826A G.E. SIL 292 & SUP 1 M-47-1, Sht. 1 CD-760A G.E. SIL 310 J-3000-1, Sht. 12 CD-393B SOER 84-02R01 E-6768-0, Sht. 1 CD-270A NRC INFO 81-16 N1-C11-1050-95, Sht. 26 CD-434F G.E. SIL 471 & SUP 1 DCP No. 4-HM-0490 CD-574F INPO SER 14-89

3 gal LS-N013F, H

1.

to ensure all blue SCRAM lights on Rod and Detector Display are off.

2.

HV-F010/F180 AND HV-F011/F181 indicates OPEN. (10C651C)

D5269SCRAM DISCH VOLUME NOT DRAINEDNoneD5270SCRAM DISCH VOLUME

NOT DRAINEDNone M-47-0 Sht. 2 GEK-39469D March 1983 M-47-1 Sht. 1 J-47-0 Sht. 2 M-47-1 Sht. 1

INPO 80-06R09

1. control rod movement
2.

to HC.OP-AB.IC-0001(Q) Control Rod.

3.

the OD-7 displayto verify Control Rod Positions

4.

to Tech Specs: 3.1.3.

5, 3.1.3.7, and 3.1.4.1.

5.

Reactor Engineer, IF unplanned control rod movement has occurred.

D5922RMCS DISPLAYS INOPNone J-47-0, Sht. 3 PJ-200(Q)-2750 PJ-108-35, Sht. 1

PN1-C11-1050-0095 DCP 4EC-3192-2

1. a control rod withdrawal block has occurred.
2. which RBM Channel is in the downscale condition.
3.

to Technical Specificat ions 3.1.4.3 and 3.3.6.

4.

SM/CRS of alarm condition.

C025EITHER RBM CHANNEL DOWNSCALEControl Rod withdrawal block N1-C51-25, Sht. 33, Sht. 47, N1-C51-25, Sht. 48 GEK 90300 Volume IV, Part 1

1. charging water header pressure is being maintained.
2.

to Technical Specificati on 3.1.3.5 for applicability.

D2244CRD WATER PUMP A MOTORCRD Pump trip:D2246CRD WATER PUMP B MOTORa.OverloadD2248CRD PMP SUCT ISLN HV4005 OPFb.UndervoltageD2250CRD WATER PUMP A

SUCTION PRESSc.Low suction pressureD2252CRD WATER PUMP B

SUCTION PRESSD3017CRD DRIVE WATER FILTER DPD3018CRD WATER PUMP

SUCT FILTER DPN/ACRD ROD CHG WTR HDR

PRESS M-46-1 J-46-0, Sht. 2, Sht. 7 E-6420-0 E-6422-0 22A6249AC, Sht 7 N0-C11-42-(1)-9

1.

Nuclear Instrumentation for any s udden flux changes in the area of the uncoupled rod (potential for rod drop accident is present).

2.

to HC.OP-AB.IC-0001(Q); Control Rod.

C071ROD OVERTRAVELNone N1-C11-1050-95, Sht. 26 E-6768-0, Sht. 1

None

A2621MAIN TURBINE 1ST STAGE PRESSNoneA2925CHW CHILLER A MTR WINDING

TEMPNoneA2927CHW CHILLER B MTR WINDING

TEMPNoneA2929CHW CHILLER C MOTOR WDG

TEMPNoneA3016CRD ROD PILOT AIR HEADER

PRESSNoneA3063CHW CHILLER D MOTOR WDG

TEMPNoneD5562TSI PANEL TROUBLENoneD6001CRIDS BULK FAILURENone J-108-0, Sht. 12 E-6797-0, Sht. A DCP H-1-RJ-ECS-0035 AR 960424211 DCP 80078688

1. IF A3016 CRD ROD PILOT AIR HEADER PRESSis in AlarmTHEN the following:a.

an Operator to inspect for leaks of the Scram Air Header.

b.

to HC.OP-AB.COMP-0001(Q), Inst rument and/or Service Air.

2.

to the associated Digital Point/Indication response below.

A2621MAIN TURBINE 1ST STAGE PRESSNoneA2925CHW CHILLER A MTR WINDING

TEMPNoneA2927CHW CHILLER B MTR WINDING

TEMPNoneA2929CHW CHILLER C MOTOR WDG

TEMPNoneA3016CRD ROD PILOT AIR HEADER

PRESSNoneA3063CHW CHILLER D MOTOR WDG

TEMPNoneD5562TSI PANEL TROUBLENoneD6001CRIDS BULK FAILURE - CALL

DSGNone J-108-0, Sht. 12 E-6797-0, Sht. A AR 960424211 DCP H-1-RJ-ECS-0035 DCP 80078688 DCP 80078686 DCP 80078687

Retrieved from "https://kanterella.com/w/index.php?title=LR-N10-0355,_Hope_Creek,_HC.OP-AR.ZZ-0011(Q),_Rev._53,_Overhead_Annunciator_Window_Box_C6&oldid=955302"