ML20054J993

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Offnormal Event Procedure 05-1-02-III-5, Automatic Isolations,Safety-Related, Revision 12
ML20054J993
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 06/14/1982
From:
MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20054J949 List:
References
05-1-02-III-5, 5-1-2-III-5, NUDOCS 8206300279
Download: ML20054J993 (19)
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PLANT OPERATIONS MANUAL Volume 05 05-1-02-111-5 Section 02 Revision:

12 Date: 6-14-82 OFF-NORMAL EVENT PROCEDURE 9'

AUTOMATIC ISOLATIONS SAFETY RELATED

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Prepared:

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YM Reviewed:

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'uclear Plant Quality Superintehdent nical Review h

l' Approved:

Opergtions Superintend nt Concurrence:

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an't Pfant Man ger 0,,,lfy PSRC:

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'i""~ ~ L i s t o f E f f e c t iv e Page s : ^.~~~~ ' ~'~~ ~ '~

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Page:

l-18 List of TCN's Incorporated:

Revision TCN No.

10 None 11 None 12 None 8206300279 820625 PDR ADOCK 05000416 p

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'. D GULF NUCLEAR STATION OFF-NORMAL EVENT PROCT. DURE i

l

Title:

Automatic Isolations

[No.:

05-1-02-III-5 (Revision:

12 lPage:

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I 1.0 PURPOSE / DISCUSSION

}

1.1 The purpose of this procedure is to provide a method for assuring that system and building isolations have occurred and to provide guidance en priorities, cautions, and concerns with regard to restoring required i

systems to service.

1.2 This procedure may interface with the Emergency Plan and the Emergency

_ Procedures.

1.3 The objective of an automatic isolation is to provide protection against the onset and consequences of accidents involving the gross release of k.

radioactive materials from the containment or individual systems. When an isolation occurs the operator should ensure that a complete isolation has occurred and then determine which systems can safely be restored

}

while maintaining isolation integrity. The method for restoring systems I

will consist of performing a system shutdown and restart in accordance, with system operating instructions.

_ CAUTION g--

If an isolation occurs automatically, assume a true initiating event has.

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occurred unlers otherwise confirmed by at le as t two independent indications..'

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2.0 SYMPTOMS

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2.1 Any of the following annunciators:

2.1.1 CTMT & DRWL ISOL DIV..

1 OPER 2.1.2 CTMT & DRWL VENT ISOL DIV.

1(2) OPER O

f' 2.1.3 AUX BLDG ISOL DIV.

1(2) OPER l~~~~"~~^

~~ ~2.1.4 NSSS MANUAL ISOLATION'

~~

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..a CJtAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE i-l

Title:

Automatic Isolations lNo.:

05-1-02-111-5 1 Revision:

12 lPage:

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2.2 Alarms and/or indications that RCIC has isolated on one or more of the following:

steam line low pressure, steam line high flow, area high temperature, are high differential temperature, main steam line high or high dif ferential temperature, or high turbine exhaust diaphragm 1

pressure.

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~'

I 2.3 Alarms and/or indications that RWCU has isolated on one or more of the f

following:

reactor vessel low water level 2, high dif ferential flow, t

' area high temperature, are high differential temperature, main steam line tunnel high temperature, main steam line tunnel high dif ferential temperature, or SLC initiation.

2.4 Alarms and/or indications that RHR and LPCS test. lines have isolated on:

j high drywell pressure or reactor low level 1.

l

}

2.5 Alarms and/or indications that RHR shutdown cooling and head spray have isolated on:

reactor low level 3, high area temperature, high area dif ferential temperature, or reactor high pressure.

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4 2.6 Alarms and/or indications that containment cooling has isolated on:

f

--reactor-low level 2, hiy,h 'drJ9 ell pressure,,,orchigh radiation. +y 3

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2.7 Alarms and/or indications that auxiliary building has isolated on reactor low level 2 or high drywell pressure.

3.0 -AUTOMATIC ACTIONS

.7

.-.s.~-

3.1 All valves and/or dampers in.the. af fected systems or buildings close and, in many cases, the associated pumps and f ans trip.

t-4.0 IMMEDIATE OPERATOR ACTIONS I

4.1 Inform Shift Supervisor / Shift Superintendent.

~~4.2 If a release into the drywell, containuent, auxiliary building or turbine '

building is suspected, evacuate the affected building as necessary.

i 4.3 Verify the affected system (s) are, in fact, isolated and the associated pumps or fans are' tripped.

4.4 If a scram has occurred, refer to ONEP 05-1-02-1-1 for Reactor Scram.

5.0 SUBSEQUENT ACTIONS 5.1 Proceed to implement the Emergency Plan if directed by the Shif t Supervisor / Shift Superintendent.

5.2 If a radioactive release has occurred, notify the Radiation Control '

Section and refer to ONEP 05-1-02-II-3 for Offsite Gaseous Release.

_ n.

OFF-NORMAL EVENT PROCEDURE

, GRAND GULF NUCLEAR STATION l

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Title:

Automatic Isolations (No.:

05-1-02-111-5 l Revision:

12 iPage:

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5.3 Determine and correct the cause of the isolation.

s I

5.4 Restore unaf fected systems to service as follows:

j CAUTION o system should be restored to service before the cause of the isolation has been determined and the affected system is isolated. Verification of system integrity may be made by visual inspection of accessible areas I;

and/or observation of available Process Radiation Monitoring instrumentation and other available indications for inaccessible areas that the system is physically intact and operation of the system will not

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result in an uncontrolled release to the environment.

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l 5.4.1 Consult with the Health Physics Section prior to restoring ventilation to an area where a release may have occurred.

NOTE

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Suppression Pool Makeup will actuate if the Auxiliary Building

.i isolation is not--reeet-within 30 mingtes..,

5.4.2 Refer to SOI 04-1-01-M71-1, Containment and Drywell

~

l Instrumentation and _ Control, for resetting an automatic isolation.

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1 n NOTE l

lI The following sysiem restoration recommendations are not' to interfere with actual system operational. requirements imposed by other ONEP's or S01's.

These are only recommendations.

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5.4.3 If a Containment and/or Auxiliary Building isolation has occurred, the following systems should be restored first.

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_,.. NOTE 2.&

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t To re-open the Instrument Air Auxiliary Building Inboard Isolation j

valve (P53-F026A) after instrument air pressure in the Auxiliary Building is lost, first close the local instrument air header i

isolation valve that supplies air to the value actuator, then open f'

the accumulator outlet valve. Open P53-F026A from the Control Room, and when header pressure is restored, re-open the header i

l isolation valve and re-close the accumulator isolation valve.

j J

Instrument Air System (P53) a.

l b.

Containment Cooling System (M41)

Plant Service Water System (P44)

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Fire Protection (P64) (lP64-FA10A and B bypass valves may be used).

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dRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE Tigle: Automatic Isolations No.:

05-1-02-1Z 1-5 l Revision:

12 Page: 4 i

Plant Chilled Water System (P71) e.

NOTE The following Plant Service Water and Fire Protection System valves can be opened even if the Auxiliary Building isolation signal is not clear by taking the AUX BLDG ISO BYPSS DIV I and DIV II keylock switches to " bypass" on lH13-P870.

P44-Fil6 PSW RTN HDR FOR M/U/DISCH P44-Fil7 PSW RTN FDR FOR M/U/DISCH P44-Fil8 PSW DUMP TO DISCH BASIN P44-F119 PSW DUMP TO DISCH BASIN P44-F120 PSW SPLY HDR TO AUX BLDG P44-F121 PSW SPLY HDR TO AUX BLDG P44-F122 PS'MPLMR.TO TURB BI DG.c.

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P44-F123 PSW SPLY HDR TO TURB BLDG

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P64-F282A FIRE WATER SPLY HDR #1 TO AUX BLDG 2

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P64-F282B FIRE WATER SPLY HDR #1 TO AUX BLDG P64-F283A FIRE WATER SPLY HDR #2 TO AUX BLDG P64-F283B FIRE WATER SPLY HDR #2 TO AUX BLDG P64-F332A CO2 SPLY HDR ISOL TO AUX BLDG 4

P64-F332B CO2 SPLY HDR TO AUX BLDG NOTE The following valves may be reopened 30 seconds following

- an automatic isolation.

No bypass is required.

4 IP44-F053 PSW SPLY HDR TO CTMT IP44-F069 PSW RTN HDR FM CTMT IP44-F070 PSW RTN HDR FM CTMT

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IP44-F074 PSW SPLY HDR TO DRWL IP44-F076 PSW RTN HDR FM DRWL IP44-F077 PSW RTN HDR FM DRWL IP45-F273 AUX BLDG EQ/FL DR PMP BK TO SUPP POOL IP45-F27.4 AU,X BLDG EQ/FL DR PMP BK TO SUPP POOL

GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l

Title:

Automatic Isolations lNo.:

05-1-02-1I1-5 l Revision:

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5.4.4 Refer to the attached Automatic Isolation Checklist to aid in determining the af fected valves and systems.

I l

5.4.5 Restore the affected systems in accordance with appropriate SOI's.

I 5.5 If any system cannot be restored, evaluate the consequences to plant j

operations with that system (s) impaired.

i 5.6 With unaffected systems returned to service and the affected system (s) isolated, continue to operate in accordance with the appropriate 101.

5.7 Observe Technical Specification Sections 3.6.1.1 Primary Containment l

Integrity and 3.6.6.1 Secondary Containment Integrity.

1 AUTOMATIC ISOLATION CHECKLIST Main Steam Lines and Drains Group I j

Isolation Signals j

Reactor-vessel low water levv1'CTevel.1) -150.3%.r.

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Main Steam Line High Radiation 3.0 x Full Power Background Main Steam Line High Steam Flow 169,psid

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Main Steam Line High Space Tempeiature 180 *F t

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Low Main Condenser Vacuum 9" Hg.

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Low Main Steam Line Pressure (Run Mode Only) 849 psig I

Main Steam Tunnel Cooler Differential Temperature 80 *F Valves Closed

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ONE-0UT-OF-TWO-TWICE lH13-P601

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B21-F028A MSL A CTMT OTBD ISOL B21-F028B MSL B CTMT OTBD ISOL B21-F028C MSL C CTMT OTBD ISOL B21-F028D MSL D CTMT OTBD ISOL B21-F022A MSL A DRWL INBD ISOL B21-F022B MSL B DRWL INBD ISOL B21-F022C MSL C DRWL INBD ISOL B21-F022D MSL D DRWL INBD ISOL

GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l

Title:

Automatic Isolations (No.:

05-1-02-III-5 l Revision:

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AUTOMATIC ISOLATION CHECKLIST (continued)

B21-F019 INBD MSL DR OTBD DR VLV i

B21-F067A OTBD MSL A DR VLV B21-F067B OTBD MSL B DR VLV B21-F067C OTBD MSL C DR VLV i

B21-F067D OTBD MSL D DR VLV B21-F016 INBD MSL DR INBD DR VLV

.RHR to Radwaste Group II Isolation Signals

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Reactor Vessel Low Water Level (Level 3) 11.4" High drywell pressure 1.73 psig e

3 RHR Room High temperature 175 *F 3;-

RHR Room High Cooler Differential T5mperature 110 *F Valves Closed Division I.

1H13-P601 E12-F075A RHR HX A OTBD PROC SMPL VLV

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E12-F075B RHR HX B OTBD PROC SMPL VLV 7

E12-F040~

RHR TO RADWST OTBD SHUT 0FF VLV ~

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i E12-F037A RHR A TO CTMT POOL Division II E12-F060A RHR HX A INBD PROC SMPL VLV E12-F060B RHR HX' B INBD PROC SMPL VLV E12-F049 RHR TO RADWST INBD SHUT 0FF VLV

~

E12-F037B RHR B 10 CTMT POOL m

4

~ GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE I'

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Title:

Automatic Isolations No.:

05-1-02-111-5 l Revision:

12 lPage: 7 l

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f AUTOMATIC ISOLATION CHECKLIST (continued)

I i

RHR Shutdown Cooling and Head Spray Group III Isolation Signals Peactor Vessel Low Water Level (Level 3) 11.4" RER Room High Space Temperature 175 *F High Reactor Vessel Pressure 135 psig RHR Room High Cooler Dif ferential Temperature 110 *F Valves Closed i

Division I 1H13-P601 E12-F008-

.- -RHR SHUTDN CLG OTBD SUCT.VLV

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E12-F023 RHR B FLO TO HD SPR ~ ~

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E12-F053A RER A SHUTDN CLG RTN TO W Division II _ m.

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E12-F009 RHR SHUTDN CLG INBD SUCT VLV E12-F053B RHR B SHUTDN CLG RIN TO FW

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Steam Supply to RHR and RCIC (Group IV)

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Isolation Signals

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RCIC Low Steam Line Pressure 60 psig

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RCIC High Steam Line Space Temperature 190 *F RCIC High Steam Flow 145" H O 2

l High Main Steam Tunnel Cooler Differential Temperature 80 *F l

2 RCIC Turbine Exhaust diaphram High Pressure 10 psig RCIC High Room Cooler Dif ferential Temperature 130 *F RHR High Room Cooler Differential Temperature 110 *F

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hRAND.GULFNUCLEARSTATION OFF-NORMAL EVENT PROCEDURE l

Title:

Automatic Isolations lNo.:

05-1-02-III-5 1 Revision:

12 lPage: 8 l

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I AUTOMATIC ISOLATION CHECKLIST (continued)

Valves Closed Division I 1H13-P601 E51-F064 RCIC STM SPLY DRWL OTBD ISOL Division II E51-F063

~

RCIC STM SPLY DRWL INBD ISOL E51-F076 RCIC STM LINE WARMUP VLV

_RHR AND LPCS Test Line (GROUP V)

Isolation Signals m..~.-

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g Reactor Vessel Low Water Level (Level 1) -150.3"--

High Drywell Pressure 1.73 psig -

Valve Closed Division I 1H13-P601 E12-F011A RHR HX A DISCH 10 SUPP POOL E21-F012 LPCS TEST RTN TO SUPP POOL E12-F024A RHR A TEST RTN TO SUPP POOL Division II'~'~~~

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E12-F011B RHR HX B DISCH 10 SUPP POOL E12-F021 RHR C TEST RTN TO SUPP POOL E12-F024B RHR B TEST RTN TO SUPP POOL i

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L.

dRAND GULF NUCI

.t STATION OFF-NORMAL EVENT PROCEDURE l

Title:

Automstic Isolations lNo.:

05-1-02-III-5 IRevision:

12 lPage:

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l AUTOMATIC ISOLATION CHECKLIST (continued)

Containment and Drywell Isolation (Croup VI)

Isolation Signals Reactor Vessel Low Water Level (Level 2) -41.6" High Drywell Pressure 1.73 psig Valve Closed Division I lH13-P870 P53-F001 INST. AIR SUPPLY HDR. TO CTMT P53-F003 INST. AIR SPLY HDR P52-F105 SVC AIR SPLY HDR TO CTMT P71-F148 PCW RTN FM SMPL WTR CLRS/CTMT CLRS P71-F150 PCW SPLY ID SMPL WTR CLRS/CTMT CLRS.

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P21-F017 MU STR SPLY HDR TO CTMT' l..

P45-F096 DRWL CHEMWST SMP DISCH P45-F099 CTMT CHEMWST SMP DISCH P45-F003 DRWL FLOOR DR SMP DISCH P45-F062 CTMT FLOOR DR SMP DISCH

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P45-F0091'.

DRWL EQUIP DR SMP DISCH

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P45-F068 CTMT EQUIP DR SMP DISCH C36-F101 RWCU BKW RCV TK XFER 10 RADWST P60-F009 SPCU RTN FM CNDS PC FLTRS

.E61-F003A DRWL PURCE SPLY/ INITIAL VAC RLF E61-F005A POST LOCA VAC RLF A E61-F007 NORM VAC RLF CTMT OTBD ISOL P11-F075 CST kTR SPLY HDR TO CTMT P11-F130 REFUEL kTR XFER PMP SUCT FM SUPP POOL

dRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

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Title:

Automatic Isolations lNo.:

05-1-02-I11-5 IRevision:

12 lPage:

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AUTOMATIC ISOLATION CHECKLIST (continued)

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Division II

  • i P53-F007 INSTR AIR SPLY HDR TO DRWL 4

i P52-F195 SVC AIR SPLY HDR TO DRWL t

P71-F149 PCW RTN FM SMPL WTR CLRS/CTMT CLRS 4

4 P21-F018 MU WTR SPLY HDR 70. CTMT P45-F097 DRWL CHEMWST SMP DISCH P45-F098 CTMT CHEMWST SMP DISCH P45-F004 DRWL FLOOR'LR SMP DISCH P45-F061 CTMT FLOOR DR SMP DISCH i 1 9-P45-F067 CTMT EQUIP DR SMP DISCH E61-F003B DRWL PURGE SPLY/ INITIAL VAC RLF E61-F020 NROM VAC RLF CTMT INBD iSOL j

C36-F106 RWCU BKW RCV TK XFER TO RADWST P60-F010 SPCU RTN FM CNDS PC FLTRS Pll-F131 REFUEL WTR XFER PMP SUCT FM SUPP POOL T

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l Division I 1H13-P601 1

'C41-F028-FPCC RTN VLV CTMT OTBD ISOL r_

i I

C41-F029 CTMr FP DR CTMT OTBD ISOL G41-F044 CTMT FP DR CTMT INBD ISOL Division III E22-F023 RPCS TEST RTN TO SUPP POOL I

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..= -

GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l

Title:

Automatic Isolations lNo.:

05-1-02-111-5 IRevision:

12 lPage:

11 l l

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i AUTOMATIC ISOLATION CHECKLIST (continued) i Containment Cooling (Group VII)

Isolation Signals

'~"

Reactor Vessel Low Water (Level 2) -41.6" High Drywell Pressure 1,73 Containment and Drywell Ventilation Exhaust High Radiatiom 5 mR/hr Valves Closed Division I IH13-P870 M41-F0ll DRWL/CTMT SPLY AIR FM PURGE FANS M41-F015 DRWL PURGE SPLY FM CTMT CLG

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M41-F016 DRWL PURGE EXH 10 CTMT CLG M41-F035 CTMT CLG EXH 'IO CTMT VENT

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E61-F009 CTMT PURGE SPLY INL CIMT OTBD ISOL E61-F057 CTMT EXH FLTR TR INL CTMT OTBD ISOL Division II M41-F012 DRWL/CTMT SPLY AIR Di PURGE FANS

~

M41-F013 DRWL PURGE SPLY FM CTMT CLG I'" ~~ M41-F017[~

DRWL PURGE EXH 10 CTMT CLG

~ ~

5 -~.--

s M41-F034 CTMT CLG EXH 10 CTMT VENT.

E61-F010 CTMT PURGE SPLY INL CTMT INBD ISOL E61-F056 CTMT EXH FLTR TR INL CTMT INBD ISOL

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GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l

Title:

Automatic Isolations lNo.:

05-1-02-111-5 1 Revision:

12 lPage:

12 l 1

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l AUTOMATIC ISOLATION CHECKLIST (continued) i f

Reactor Water Cleanup (Group VIII) l Isolation Signals Reactor Vessel Low Water Level (Level 2) -41.6" 3

l Reactor Water Cleanup High Dif ferential Flow 79 gpm for 45 sec.

I i

Main Steam Line High Space Temperature 200 *F High Main Steam Tunnel Cooler Dif ferential Temperature 30 *F 4

Standby Liquid Control A or B Actuated l

Equipment Area Temperature - High RWCU HX Room 125 *F j

RWCU Pump Rocms 175 *F r#

RWCU Valve Nest Rooms 140 *F

.I RWCU Demin Rooms _

__._ 140 *F y, -RWCUrRec. Tank Room 140'*F.

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Equipment Area Diff. Temperature - High RWCU HX Room 66 *F j dS5 RWCU Pump Rooms ^

111 *F

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RWCU Valve Nest Rooms 71 "F

((1[.l.

RWCU Demin Rooms

,71 *F RWCU Rec. Tank Room

.. 71

  • F Valves Closed Division I lH13-P680

,t G33-F004 RWCU PMP SUCT CTMT OTBD ISOL i

~ ".' G33-F034~

i RWCU BLWDN CTMT OTBD ISOL l

G33-F039 RWCU RTN CTMT OTBD ISOL G33-F054 RWCU PMP DISCH CTMT OTBD ISOL 1H13-P870 l

G33-F250 RWCU SPLY 10 RWCU HXS 1

i G33-F252 RWCU HX RTN TO RWCU PMPS Division II 1H13-P680 G33-F001 RWCU PMP SUCT DRWL INBD ISOL G33-F028 RWCU BLWDN CIMT INBD ISOL I

G33-F040 RWCU RTN CTMT INBD ISOL G33-F053 RWCU PMP DISCH CTMT INBD ISOL

BRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

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Title:

Automatic Isolations lNo.:

05-1-02-III-5 IRevision:

12 lPage:

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J AUTOMATIC ISOLATION CH'ECXLIST (continued)

RCIC Exhaust Vacuum Breakers (Group IX)

Isolation Signals (need both signals)

High Drywell Pressure 1.73 psig RCIC Steam Line Low Pressure 60 psig Valves Closed

}-

)

Division I 1H13-P601 E51-F077 RCIC TURB EXH OTBD VAC BRKR Division II I

E51-F078 RCIC TURB EXH INBD VAC BRKR

~

. 4-Reactor Water Cleanup (Group X)

Isolation 3

Reactor Vessel Low Water Level (Level 2) -41.6"

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.... ~..

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Reactor Water Cleanup High Differential Flow 79 gpm for 45 sec Main Steam Line High Space' Temperature 180 *F cr' High Main Steam Tunnel Cooler Dif ferential Temperature 76 *F 4 ::

}f Standby Liquid Control A or B actuated Equipment Area Temperatu're - High "~' '

' ~~

~

~^

RWCU HX Room 125 *F RWCU Pump Rooms 175 *F RWCU Valve Nest Rooms 140 *F RWCU Demin Rooms 140 *F RWCU Rec. Tank Room 140 *F Equipment Area Diff. Temperature - High RWCU HX Room 66 *F RWCU Pump Rooms 111 *F RWCU Valve Nest Rooms 71 *F RWCU Demin Rooms 71 *F RWCU Rec Tank Room 71 *F Valves Closed G33-F251 RWCU SPLY TO RWCU HXS G33-F253' RWCU HX RTN TO RWCU PMPS

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GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

^

Title:

Automatic Isolations lNo.:

05-1-02-111-5 l Revision:

12 lPags:

14 l l

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I AUTOMATIC ISOLATION CHECKLIST (continued) q; i

, Reactor Sample Isolations Isolation Signals i

Reactor Vessel Low Water Level (Level 2) -41.6 I

Main Steam Line High Radiation 3.0 X Full Power Background l

Valves Closed 1

l Division I 1H13-P680 j

B33-F020 RW PROC SMPL DRWL OTBD ISOL I

Division II

,k j

B33-F919 RW PROC SMPL DRWL INBD ISOL

=

s I-Auxiliary Building Isolation Valves-Isolation Signals 7

22 Reactor Vessel Low Water Level (Level 2) -41.6" 2/

s High. Drywell Pressure 1.73 psig I

NOTE l

Standby Gas Treatment starts, Control Room HVAC Isolates, and Control Room Standby Fresh Air Unit starts.

-l

~~~

Valves' Closed

~~

~^~~~~

~~~

~

~

1 Division I lH13-P870 NOTE i

To reopen P53-F026A open the accumulator valve to supply air to the actuator.

j P53-F026A INSTR AIR SPLY HDR TO AUX BLDG PS2-221A SVC AIR SPLY HDR #1 TO AUX BLDG

~

P52-160A SVC AIR SPLY HDR #2 TO AUX BLDG B21-F113 MSL DR TO MN CNDSR t

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.~. _. _ _ _.

hRANDCULFNUCLEARSTATION OFF-NORMAL EVENT PROCEDURE l

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Title:

Automatic Isolations lNo.:

05-1-02-III-5 l Revision:

12 Page:

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AUTOMATIC ISOLATION CHECKLIST (continued)

Auxiliary Building Isolation Valves (Continued)

?44-F117 PSW RTN HDR FM MU/DISCH P44-F118 PSW DUMP TO DISCH BASIN P44-F121 PSW SPLY HDR 'IO AUX BLDG l

P44-F122 PSW.SPLY HDR TO TURB BLDG i

i P71-F300 PCW RTN FM DG RM CLRS i,

P71-F302 PCW SPLY 'IO DG RM CLRS P71-F304 PCW RTN HDR FM TURB BLDG

/

i 3

P71-F306 PCW SPLY HDR TO TURB BLDG j

3 N

l

~ P64-F282A FIRE WTR SPLY HDR #1 TO AUX BLDG

i..' ~

P64-F283 F FIRE WTR SPLY HDR #2 TO AUX BLDG

^

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..d.

= c

.. _ j.' P64-F332A CO2 SPLY HDR 'IO AUX BLDG l

P45-F158 AUX BLDG EQUIP DR SMP XFER 'IO RADWST 1

P45-F160 AUX BLDG FLOOR DR SMP XFER TO RADWST 1

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l !.... ~P60-F003 SPCU SPLY TO CNDS PC FLTRS

=.

P60-F008 SPCU RTN FM CNDS PC FLTRS l

l E12-F203 RHR SYS FLUSH TO LIQ RADWST l

l S

t i

  • GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l

Title:

Automatic Isolations lNo.:

05-1-02-111-5 l Revision:

12 iPage:

16 l l

l I

I I

I AUTOMATIC ISOLATION CHECKLIST (continued)

Auxiliary Building Isolation Valves (Continued)

G46-F253 FP BKW RCU TK XFER TO RADWST P66-F029A DOM WTR SPLY TO AUX BLDG P21-F024 MU WTR SPLY HDR TO AUX BLDG

{

G36-F108 RWCU BKW RCU TK XFER TO RADWST G33-F235 RWCU BLWDN TO MN CNDSR Pil-F062 CST WTR SPLY HDR TO AUX BLDG Pll-F064 HPCS/RCIC TEST RTN TO CST

/

Pil-F047 REFUEL WTR XFER PMP SUCT FM RWST

+

I P11 -F066 __ _

- _ RWST XFER TO CST _ _

Division II P53-F026B INSTR AIR SPLY HDR TO AUX BLDG

~

PS2-F221B SVC AIR SPLY HDR #1 TO AUX BLDG PS2-F160B SVC AIR SPLY HDR #2 TO AUX BLDG P44-F116 PSW RTN HDR FM MU/DISCH

~i P44-F119 PSW DUMP TO DISCH BASIN P44-F120 -

PSW SPLY HDR TO AUX BLDG P44-F123 PSW SPLY HDR TO TURB BLDG 98 e

9 e

QRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

1..

l

Title:

Automatic Isolations lNo.:

05-1-02-III-5 1 Revision:

12 ' Page:

17 l

_ _. 1 l

AUTOMATIC ISOLATION CHECKLIST (continued)

Auxiliary Building Isolation Valves (Continued)

P60-F004 SPCU SPLY 10 CNDS PC FLTRS P60-F007 SPCU RTN FM CNDS PC FLTRS P71-F301 PCW RTN FM DG RM CLRS P71-F303 PCW SPLY TO DG RM CLRS P71-F305 PCW RTN HDR FM TURB BLDG P71-F307 PCW SPLY HDR TO TURB BLDG P64-F282B FIRE WIR SPLY HDR #1 AUX BLDG

/

P64-F283B FIRE WTR SPLY HDR #2 AUX BLDG

- ~

4s t

P64-F332B CO2 SPLY HDR TO AUX BLDG

~

P45-F159 AUX BLDG EQUIP DR SMP XFER TO RADWST 4

3 P45-F161 AUX BLDG ' FLOOR DR ' SMP XFER TO RADWST P45-F163 ^

A'UX BI'5G CH5M 'WST SMP 'XF5R 70 ' RADWST E21-Fil4 MSL DRS TO MN CNDSR

'l G36-F109 RWCU BKW RCU IK XFER 70 RADWST

.. m

~. ' -

1 '.

(

G33-F234 RWCU BLWDN TO MN CNDSR Pil-F063 CST WTR SPLY HDR TO AUX BLDG i

Pll-F065 HPCS/RCIC TEST RTN 10 CST

.Pil-F061 REFUEL WTR XFER PMP SUCT Di RWST i

j Pil-F067 RWST XFER TO CST m.

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GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE l

Title:

Automatic Isolations

[No.:

05-1-02-111-5 laevision:

12 lPage:

18 l l

I I

I I

AUTOMATIC ISOLATION CHECKLIST (continued) i Auxiliary Building Ventilation Valves Reactor Vessel Low Water Level (Level 2) -41.6" High Drywell Pressure 1.73 psig Fuel Handling Area Vent Exhaust High Radiation 4 Mr/hr l

Fuel Pool Sweep Vent Exhaust High Radiation 35 Mr/hr Valves Closed Division I 1H13-P870 M41-F008 CTMT CLG 0/A INTK AUX BLDG INBD ISOL

/

M41-F036 CTMT CLG VENT EXH AUX BLDG INBD ISOL

l e-p.

T41-F007 AUX BLDG 0/A INTK AUX BLDG INBD ISOL T42-F004 FH AREA VENT EXH AUX BLd INBD ISOL T42-F011 FH AREA O/A INTK AUX BLDG INBD ISOL T42-F019 FP SWEEP O/A INTK AUX BLDG INBD ISOL Division II i

M41-F007 CTMT CLG 0/A INTK AUX BLDG OTBD ISOL M41-F037 CTMT CLG VENT EXH AUX BLDG OTBD ISOL t

i f

T41-F006 AUX BLDG 0/A INTK AUX BLDG OTBD ISOL T42-F003 FH AREA VENT EXH AUX BLDG OTBD ISOL T42-F012 FH AREA O/A INTK AUX BLDG OTBD ISOL ll T42-F020 FP SWEEP O/A INTK AUX BLDG OTBD ISOL 1-i e

~ _. -

_

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