ML20108A655

Emergency Operating Procedures Generation Package

ML20108A655
Person / Time
Site:	Quad Cities
Issue date:	10/30/1984
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20108A644	List: ML20108A642 ML20108A655
References
RTR-NUREG-0737, RTR-NUREG-737 PROC-841030-01, NUDOCS 8411150095
Download: ML20108A655 (89)

Text

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-ID/00090/ TABLE I ABBREVIATIONS i i Automatic Depressurization System ADS Average Power Range Monitor APRM Control Rod Drive CRD i 1 CS Core Spray Emergency Core Cooling System i ECCS l HCU Hydraulic Control Unit HPCI High Pressure Coolant Injection Heating, Ventilating and Air Conditioning HVAC Limiting Condition for Operation LCO LOCA Loss of Coolant Accident Low Pressure Coolant Injection LPCI Main Steenline Isolation Valve l MSIV l Ell-Ductility Transition Temperature NDTT Net Positive Suction Head NPSH Reactor-Core Isolation Cooling RCIC Residual Heat Removal l RXR { Reactor Protection System RPS Reactor Pressure Vessel RPV Reactor Weter Cleanup RWCU Rod Worth Minimizer RhEt Standy Gas Treatment SBCT Standby Liquid Control SBLC SORY Stuck Open Relief Valve Safety Relief Valve (Electromatic RJ11ef Valve SRV l-or Target Rock Safety - Relief Combination Valve) l (I-4) Rev. 1

This page intentionally left blank (I-5) Rev. 1 9395N

j ~ - i .w- . l OPERATOR PRECAUTIONS' ^ s General. I This~section-lists " Cautions" which are generally applicable at all~ times. CATUION #1. . Monitor-the' general state of the plant. -If an entry condition for.a-

procedure developed from the= Emergency Procedure Guidelines occurs, enter

- that procedure. When it.is determined that an emergency.no longer exists, enter-normal operating procedure. T CAUTION #2 1: I' Monitor RPV water. level and pressure and primary containment temperatures and. pressure from multiple indications. i CAUTION #3 If a safety function initiates automatically, assume a true initiating event has occurred unless otherwise confirmed by at least two independent indications. l - CAUTION #4 l l Whenever RHR is in the LPCI mode, inject through the heat exchangers as soon as possible. l l i l L 4 P l l p l (I-6) Rev. 1 + -, - -, _,.. .-e4, v 7 ,,,.~r,,,,--- .--a ,,.w., ww -.,%eg v w m y ,.,v,-,--...o_w-.._,,,,.--.ww_..,-%,.-_ - - - .a -..--

CAUTION #5 Suppression pool temperature is determined by QOS 1600-8. Drywell temperature is determined by QoS 1600-20. CAUTION 96 Whenever (temperature near the instrument reference leg vertical runs] exceeds the temperature in the table and the instrument reads below the indicated level in the table, the actual RPV water level may be anywhere below the elevation of the lower instrument tap. Indicated Temperature Level Instrument 169'F -37 in. Yarway Harrow Range (-60 to +60 in.) 170*F 63 in. GEMAC Upper 400 Range (-42 to 358 in.) 210*F -233 GHEMAC Lower 400 Range (-334 to 66 in.) 548'F -242 Yarway Lower Range (-234 to 66 in.) 548'F 44 GEMAC Narrow Range (0 to 60 in.) CAUTION 87 Yarway Level indicated levels are not reliable during rapid RPV depressurization below 500 psig. For these conditions, utilize the GEMAC to monitor RPV water level. s e i s O (I-7) Rev. 1

s i CAUTION #8 I This caution _ intentionally left blank. 1 l i I a f i 4 4 l i 7 l f i, l i I g 0 (I-8) Rev. 1 . ~

CAUTION #9 If signals of high suppression pool water level +5" (high level suction interlock) or low condensate storage tank water level 10,000 gal. (low level suction interlock) occur, confirm automatic transfer of, or manually transfer HPCI and RCIC suction from the condensate storage tank to the suppression pool. CAUTION #10 Do not secure or place an ECCS in MANUAL mode unless, by at least two independent indications, (1) misoperation in AUTOMATIC mode is confirmed, or (2) adequate core cooling is assured. If an ECCS is placed in MANUA'. mode, it will not initiate automatically. Make frequent checks of the initiating or controlling parameter. When manual operation is no longer required, restors the system to AUTOMATIC / STAND 3Y mode if possible. CAUTION #11 If a high drywell pressure ECCS initiation signal 2.0 psig (drya ll pressure which initiates ECCS) occurs or exists while depressurizing, 9 prevent injection from those CS and RHR-LPCI pumps not required to assure adequate core cooling prior to reaching their mawi== injection pressures. When the high drywell pressure ECCS initiation signal clears, restore CS and LPCI to AUTOMATIC / STANDBY mode. s f 9 (I-9) Rev. 1

CAUTION #12 Do not throttle NPCI or RCIC systems below 2200 rpm. CAUTION #13 Cooldown rates above 100*F/hr may be required to accomplish this step. CMTION #14 Do not depressurise the BFV below 100 psig unless motor driven pumps sufficient to maintain EFV water level are running and available for. injection. CADTION #15 Open SRVs in the following sequence if possible: 1. 203-35 3. 203-3E 5. 203-3A 2. 203-3C 4, 203-3D CAUTION #16 5 Bypassing low EPV water level ventilation system isolation and MSIV isolation interlecks may be required to accomplish this step. CAUTION #17 Cooldown rates abcVe 100*F/he may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive release to the environment. CMTION #18 If continuous LPCI operation is required to assure adequate core cooling, do not divert all RHR pumps from LPCI mode. bO (I-10) new. 1

^ i CAUTION #19 This caution intentionally left blank. CAUTION #20 This< caution intentionally loft blank. CAUTICE #21 Elevated suppression chamber pressure may trip the RCIC turbine on high awkmust pressure. CAUTION #22 Defeating isolation interlocks may be required to accomplish this step. CAUTION #23 ~ Do not initiate drywell sprays if suppression pool water level is above +48". S CAUTION #24 Bypassing high drywell pressure and low RPV water level secondary contairement HVAC isolation interlocks may be required to accomplish this step. CAUTIC3 #25 A rapid increase in injection-into the RPV may induce.a large power excursion and result in substantial core damage. s CAUTION #26 Large reactor power oscillations say be observed while executing this step. (I-ll) Rev. 1

.ID/0162A/ RPV CONTROL GUIDELINE []y q o ~ PURPOSE' The purpose of this guideline is to: , Maintain adequate' core cooling Shutdown the reactor, and Cool down the RPV to cold shutdown conditions temperature (100*F < RPV - water.. temperature < 212*F) ENTRY CONDITIONS I The entry conditions for this guideline are any'of the following:- RVP water level below +8 in. (low level scram setpoint) - RPV pressure above 1060 psig (high RPV pressure scram setpoint) Drywell pressure above 2.0 psig (high drywell pressure scram setpoint-A condition which requires MSIV isolation A condition which requires reactor scram, and reactor power above 3% (APRM downscale trip) or cannot be determined. OPERATOR ACTIONS i RC-1 If reactor scram has not been inititated, initiate reactor scram. 1 6 Irrespective of the entry condition, execute Steps RC/L, RCf P, and RC/Q concurrently. i i i l (RC-1) Rev. 1 l

~ -l h BC/LL -Monitor and control RPV water level, i RC/L-1 Confirm initiation of any of.the following: -Primary Containment Isolation ECCS l anergency diese1~ generator initiation i-Initiate any of these which should have-initiated but did not.- i i ( If while executing the following step: 4 Boron Injection is required,; eater [ procedure developed from CONTINGENCY #7]. l-l RPV water level cannot be determined BPV FLOODING IS j REQUIRED; ' enter - [ procedure developed from CONTINGENCY M]. i RPV Flooding is required, enter-[ procedure developed from l CONTINGENCY M]. i i BC/L-2 Restore and maintain RPV wate~r level c between +8 in (low level scram setpoint) - #9 and +48 in (high level trip setpoint)'

1. 10 with one or more of the following systems:

_EL, 5

Condensate /feedwater system 1100 - O peig (RPV pressure l range for system operation) i CBD system 1100 - O psig (RPV pressure range for system operation) RCIC system 1150 - 50 pois (RPV pressure range for system operation)

_G3, l

l l i. (RC-2) Rev. 1

I 1 l* HPCI system'1150 - 100 psig-(RPY pressure range for system-operation) CS system 325 - O psig (RPV pressure range for system operation) l ' LPCI system 325 - O pois (RPV pressure range for system operation) If RPV water level cannot be restored and maintained above ' 8 in..(low level scram setpoint), maintain RPV water level + above -143 in.' (top.of active fuel). If RPV water level can be maintained above -143 in. (top of active fuel)~and the ADS timer has initiated, prevent automatic RPV depressurization by resetting the ADS timer or by utilizing the ADS-IBMIBIT switch. 2 If RPV water level cannot be r.sintained above -143 in. j (top of active fusi), enter (procedure developed from l CONTINGENCY #1]. i 4 i If Alternate Shutdown Cooling is required enter I (procedure developed from CONTINGENCY #5]. s i RC/L-3 Proceed to cold shutdown in accordance with QGP 2-3. I f I l. l (RC-3) Rev. 1

T RC/P Nonitor and control RPV pressure. U If while executing the following steps: I Emergency RPV Depressurization is anticipated, rapidly depressurize the RPV with the main _fl],_ turbine bypass valves. Emergency RFV Depressurization or RPV Flooding is required-and less than 5 (number of SRVs. dedicated to ADS) SRVs are open, enter [ procedure developed from CONTINGENCY #2). RPV Flooding is required and 5 (number of SRVs dedicated to ADS) SRVs are open, enter [procedura developed from CONTINGENCY #6). RC/P-1 If any SRV is cycling, saitually open SRVs until RPV pressure drops to 935 peig (RPV pressure at which all turbine bypass valves are fully open). s 4 j l 1 i (RC-4) Rev. 1

G This page intentionally left blank. ? 0 (RC-5) Rev. 1

l 4 i 'I - f i If while executing the following steps: 3 '~ Boron Injection is required, and sne main condenser is available, and There has been no indication of gross fuel failure or steam [ line break, E j !h h OPen b6IVs to re-establish the main condenser as iL E %. a heat sink.

1. 16

, 1-

1. 1

r '

RC/P-2 Centrol RPV pressure below 115 psig (lowest SRV lifting pressure) with the main turbine bypass

1. 14 valves.

RPV pressure control may be augmented by one or more of the c2- ( following systems: , [. SRVs only when suppression pool water level is above -25 in.

1. 15 0-HPCI
2. 12 y; ;,

RCIC n e 1 m. h c ?_ f 'S _t a f '6 I -E E , 3- $+ (RC-6) Rev. 1 1

RWCU (recirculation mode) if'no boron'has been injected into the RPV. Main steam line drains. RWCU (blowdown mode) if no boron has been injected into the RPV. If-while executing the following steps the reactor is not shutdown, return to (Step RC/P-2). RC/P-3 When either: All control rods are inserted beyond position 04 (mmv4=n= suberitical banked withdrawal position), or 537 pounds (Cold SM tdown Boron Weight) of boron have been ~ injected into the RPV, or The reactor is shtdown and no boron has been injected into the RPV, O depressurize the RPY and maintain cooldown rate below 100*F/hr (RPV cooldown rate LCO)

1. 14. #17 RC/P-4 When the RHR sh tdown cooling interlocks clear, initiate the sh dtdown cooling mode of RHR.

_fl)_, O -(RC-7) Rev. I l

1 l s If the RHR shutdown cooling mode cannot be established and further cooldown is required, continue to cool down using one or more of the systems used for depressurization. If RPV cooldown is required but cannot be accompl.shed and all control rods are inserted beyond position 04 (maximum subcritical banked withdrawal position), ALTERNATE SHUTDOWN COOLING IS REQUIRED; enter procedure developed from CONTINGFNCY #5.- RC/P-5 Proceed to cold shutdown in accordance with QGP 2-1. RC/Q Monitor and control reactor power. If while executing the following steps: All control rods are inserted beyond position 04 (maximum subcritical banked withdrawal position), terminate boron injection and enter QGP 2-3. The reactor is shutdown and no boron has been injected into O the RPV, enter QGP 2-3. RC/Q-1 Verify the reactor mode switch in SHUTDONN. RC/Q-2 If the main turbine-generator is on-line and the MSIVs are open, confirm or initiate recirculation flow runback to minimum. RC/Q-3 If reactor power is above 3% (APRM downscale trip) or cannot be determined, trip the recirculation pumps. O (RC-8) Rev. 1 s', ;. ' .,.,e I[ J 'y 'k 5' *[b ' ',,,..f ' [ ,5 'e ,k9

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'[... .,1 k), .,j,i ' v, 4 ,8 i ',

2 Execute [ Steps RC/Q-4 and RC/Q-5] concurrently. RC/Q-4 If the reactor cannot be shutdown.before suppression pool temperature reaches 130*F _fl9_ (Boron Injection Initiation Temperature), BORON INJECTION IS REQUIRED; inject boron into the RPV teith SBLC and prevent autostic initiation of ADS. If boron cannot be injected with SLC, inject boron into the RPV by one or more of the following alternate methods: CRD RMCU Fosdwater HPCI O. RCIC Safe Shutdown F: map RC/Q-4.1 If boron is not being injected into the RPV by RWCU, confirm automatic isolation of or manually isolate s RMCU. RC/Q-4.2 Continue to inject boron until 537 pounds (Cold Shutdown Boron Weight) of boron have been injected into the RPV. RC/Q-4.3 Enter QCP 2-3. O

• O (RC-9) Rev. 1

I;. 'm RC/Q-5 Insert control rods as follows: RC/Q-5.1 If any scram valve is not open: D Remove: 590-175 A. C R and G at Panel 901-15(902-15) 590-175 B, D, F and H at Panel 901-17 (902-17) i (fuses which de-energize RPS scram solenoids) Close valva 0302-109 scram air header supply valve and open valves 0302-21A, 302-21B, 0302-21C, 302-21D When control rods are not moving inward: Replace: 590-175 A, C, E and G 590-175 B, D, F and H (fuses which demanergize RPS scram solenoids) Close Valves: C302-21A, 0302-21B, 0302-21C, 9?2-21D sad open valve 0302-109 RC/Q-5.2 Roset the reactor scram. If the reactor scram cannot be reset: I-R 1. Start both CRD pumps. M 2 If no CRD pump can be started, continue in this procedure at [ Step RC/Q-5.6.11 1 l E 3 j s k E 4 2 dl O M

== s ? (RC-10) Rev. 1 QY

.m .m i 2. Close valve 0301-25. HCU accumulator.~ charging; water header valve.' V 3. Rapidly insert control rods ] manually until the reactor scram

1. 20 can be reset.

4. Roset the reactor scram. 5. Open valve 0301-25 HCU accumulator' charging water header valve. RC/Q-5.3 If the scram discharge volume vent and drain valves are open, initiate a manual reactor scram. I 1. If' control rods moved inward, return to [ Step RC/Q-5.2].- 2. Reset the reactor scram. If the reactor scram cannot be reset,-continue in this procedure at [ Step RC/Q-5.5.1].

3.. Open the scram discharge volume. vent and drain valves.

BC/Q-5.4 Individually open the scram test switches for control rods.not inserted beyond position 04 (maximum suberitical banked withdrawal position). When a control rod is not. moving inward, close its. scram test switch. i i l l l i l~ l (RC-11) Rev.1 l i: E ,._,._._m.,,

RC/Q-5.5 Roset the reactor scram. O If the reactor scram cannot be reset: 1. Start both CRD pumps. If no CRD pump can be started, continue in this procedure at [ Step RC/Q-5.6.1]. 2. Close valve 0301-25 (HCU accumulator charging water header valve). RC/Q-5.6 Rapidly insert control rods manually until all control rods are inserted f20_ beyond position 04 (maximum subcritical banked withdrawal pos.i. tion). If any control rod cannot be inserted beyond position 04 (maximum suberitical banked withdrawal posit. ion): 1. Individually direct the effluent from valve 301-102 CRD withdraw line vent to a contained radweste drain and open valve 301-102 CRD withdraw line vent for each control rod not inserted beyond position 04 (maximum subcritical 9-; banked withdrawal position). 2. When a control rod is not moving inward, close valve 301-102 CRD withdraw line vent. 1 O i (RC-12) Rev. 1

ID/00119/ = (M PRIMARY CONTAIRMENT CONTROL GUIDELINE u) .g PURFOSE The purpose of this Fuideline is to: Maintain primary containment integrity, and Protect equipment in the primary containment. ENTRY CONDITIONS The entry conditions for this guideline are any of the following: Suppression' pool temperature above 95*F (most limiting suppression pool -temperature LCO) Drywell temperature above 180*F (maximum normal operating temperature) Drywell pressure above 2.0 psig (high drywell pressure scram setpoint) Suppression pool water level above +2 in. (maximum suppression pool water level LCO) ( Suppression pool water level below -2 in. (minimmm suppression pool water level LCO) OPERATOR ACTIONS Irrespective of the entry condition, execute [ Steps SP/T, DW/T, CN/T, PC/P and SP/L] concurrently. i N l' l (PC-1) Rev. 1 l' ~

k ~- SP/T : Monitor and control suppression pool temperature. s SP/T-1 Close all SORVs. If any SORV cannot be closed scram the reactor. v SP/T-2 When suppressiocc pool temperature exceeds 95'F. (most ll operat[,mj.7,ing suppression pool temperature ICO), available suppression pool cooling.

1. 18 l

SP/T-3 Before suppresti pool temperature. reaches 130*F-(Boron Injection Initiation Temperature)', scram the reactor. .l SP/T-4 If suppression pool temperature cannot be maintained $8 below the Heat Capacity Temperature Limit, maintain

1. 13 RPV pressure below the Limit.

$14 77/ .; y di Y / /4 y 9;, 'i y d Jf. h:yv@). f;; / i y d I u l l 1 l I (PC-2) Rev.1 y_,.._ _.,, ,_,_.,..m,

~ft RF . + l If suppression pool temperature and RPV pressure cannot be. restored and maintained below the Heat capacity Temperature m [e - Limit, EMERGENCY RPV DEPRESSURIATION IS REQUIRED; enter i procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure, f W/T, Monitor and control drywell temperature. ,a W/T-1. When average drywell temperature exceeds 180*F }' (drywell maximum normal operating temperature, L whichever is higher), operate available drywell l cooling. i Execute [ Steps W/T-2 and W/T-3] concurrently. W/T-2. If drywell temperature near the cold reference les instrument vertical runs reaches the RPV Saturation Temperature, RPY FLOODING IS REQUIRED; enter procedure developed from tha EPV Control Guideline at Step RC-1 and execute it concurrently with this procedure. H s s 1 e { l l (PC-3) Rev. 1 ~..

W/T-3' Before'drywell'. temperature reaches 1300*F'(drywell' design temperature) but only if suppression. chamber 4 temperature and drywell pressure are below the. 418 Drywell Spray Initiation Pressure Limit shut down recirculation pumps and drywell cooling fans and initiate drywell sprays. p i 4 l l i l If drywell temperature cannot be maintained below 300*F (drywell design temperature) EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this ~ ~ procedure. I o (PC-4) Rev.1

I t i t i i i e, i i f ' This page intentionally left blank. i g f 4 f j f I I 5 t I- \\ '( r l 1 0 1 l i 1 f i i {. J l A l' 8 I I l L (PC-5) Rev. 1

u ll PC/P Monitor and control primary containment-pressure.- PC/P-1 Operate systems, as required: Refer to QOP 1600-3 Post Accident Venting of Primary Contaitunent PC/P-2 Before suppression'chamoer pressure reaches 12.8 psig (suppression Chamber Spray

1. 8. #18' I

Initiation Pressure) and.if suppression pool water level is below 27 ft. 6 in. (elevation-of suppression pool-spray nozzles) initiate suppression pool sprays. PC/P-3 If suppression chasber pressure exceeds 12.8 psig (Suppression Chember Spray Initiation Pressure) _flg_ but only if suppression chamber temperature and. I drywell pressure are below the Drywell Spray Initiation l Pressure Limit, shut down recirculation pumps and drywell cooling fans and initiate drywell sprays. ~ t l s. 1 i i I l l O 3 (PC-6) Rev. 1

9 t -.s ~ This'page intentionally left blank. i i 4 i i I .l i 4 i i l l 1 i i i l I L i (PC 7) Rev. 1

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.If suppression pool water-level is below 27~ft. 6'in. l- = (elevation of suppression pool spray nozzles), initiate suppression pool sprays. v If suppression chamber temperature and drywell pressure are { b.elow the Drywell Spray Initiation Pressure Li.it shut down recirculation pumps and drywell cooling fans and initiate drywell sprays. 4 PC/P-7 If suppression chamber pressure exceeds the Primary Containment Pressure Limit, vent the primary

1. 22 containment in accordance with procedure for containment venting to reduce and maintain pressure below the Primary Containment Pressure Limit.

(PC-9) Rev. 1

' 4 4 f 1 This page intentionally'left blank. d i-I 4 4 t j i 1 l i l I l i t i i s i \\ I k i f I i 6 (PC-10) Rev. 1.

'SP/L-2s. SUPPRESSION POOL WATER LEVEL =BELOW'-2 in.-(minimum.' suppression. pool water. level LCO) \\ Maintain suppression pool water level above the Heat Capacity Level Limit. / 4 .i b i i I f. t I i i i i l l l l 1 l If suppression pool. water level cannot be maintained above the Heat Capacity Level' Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter procedure developed from.the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure. l (PC-ll) Rev. 1

ipu..rr.r. i SP/L SUPPRESSION POOL WATER LEVEL ABOVE + 2 in. (maximum suppression O pool water level LCO). Execute Steps SP/L-3.1 and SP/L-3.2 concurretly. SP/L-3.1. Maintain suppression pool water level below the Suppression Pool Load Limit. If suppression pool water level cannot be maintained below the Suppression

1. 13 Pool Load Limit, maintain RPV pressure
2. 14_

below the Limit. O (PC-12) Rev. 1

a If suppression-pool ~waterIlevel-and.RPV pressure' i L /"'J cannot be maintained below the Suppression Pool Load / v) Limit,but only if adegoate core cooling.is assured, \\s_ / terminate injection into the RPV from sources external to the primary. containment except from boron injection systems and CRD. If suppression _ pool water level and RPV' pressure l cannot be restored and maintained below the Suppression Pool Load Limit, EMERGENCI'RPV DEPRESSURIZATION IS REQUIRED;. enter' procedure-developed from the RPV_ Control Guideline.at Step RC-1 and execute it. concurrently with this procedure. SP/L-3.2 Before suppression pool. water level reaches 18 ft. (Elevation of bottom of Mark.I internal suppression chamber to drywell vacuum breakers less vacuum breaker. opening pressure in feet of water) but only ~ if adequate core cocling is assured, terminate injection into the RPV from sources external to the primary containment except from b7ron injection systems and CRD. s 1. When suppression pool water level reaches 18 ft.. elevation of bottom

1. 18

( of Mark I internal suppression A chamber to drywell. vacuum breakers less vacuum breaker opening pressure in feet of water) but only if suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit shut down recirculation pumps and drywell cooling fans and initiate drywell sprays. i l l I i I

(FC-13 ) Rev. 1 l

i ~ _.,.,. - ~

C ( s. 4 } s 2. If suppression pool water' level exceeds 18 ft. (elevation of $23 h bottom of Mark I internal suppression chamber to drywell vacuum breakers less vacuum breaker opening pressure in feet of water), contiue to operate, drywell sprays. 3. When primary containment water level reaches 92.5 ft. (Maximum Primary Containment Water Level Limit), terminate injection into the RPV.. from sources external to the primary containment ~ irreepective of whether adequate core cooling is assured. -i (PC-14) Rev.1 _____1_______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _o

i-ID/00120/ l '.. G ) SECONDARY CONTAIEMENT CONTROL GPIDELINE PUIPOSE The purpose of this guideline is to: i Protect equipment in the secondary containment, Limit radioactivity release to the. secondary containment, and either: Maintain secondary containment integrity, or-i Limit radioactivity release from the secondary containment. ENTRY CONDITIONS The entry conditions for this guideline are any of the following secondary containment conditions: Differential pressure at or above 0 in of water An area temperature above the maximum normal operating temperature- ,HVAC exhaust radiation level above the maximum normal operating radiation level An area radiation level above the maximum normal operating radiation i. level s A floor drain sump water level above the max 4. mum normal operating water level An area water level above the maximum normal operating water level L l s l (SC-1) Rev. 1 . - _. - _ = -. _. -,.. -. - -.

t . CPEBATOR' ACTIONS" If while executing the'following steps secondary containment HVAC exhaust radiation level exceeds-3 MR above background-(i.econdary containment HVAC isolation setpoint): I Confirm or manually initiate isolation of secondary containment HVAC, and . Confirm initiation of or manually initiate SBGT only when the space being evacuated is below 212*F. 4 - If while executing the following steps: Secondary containment HVAC isolates, and I . Secondary containment HVAC exhaust radiation level is below 3.MR above background (secondary containment HVAC isolation setpoint), restart secondary containment FVAC. k 4 Irrespective of the entry condition, execute Steps SC/T, SC/R,'and SC/L' ccncurrently. SC/T Monitor and control secondary containment temperatures. SC/T-1 Operate available area coolers. i l l-(SC-2) Rev. 1 l. z

U SC/T-2. Ifasecondary, containment HVAC-exh'aust-radiation > level is=below: (~~Ssf 3 MR above background (secondary containment HVAC isolationi /- setpoint) operate available secondary containment HVAC. k# SC/T-3 If.any area temperature' exceeds its maximum normal operating temperature, isolate. all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or-suppress a working fire. SC/T-4 If a primary system is discharging into an area, then before: any area temperature reaches - its maximum safe operatingL temperature, enter procedure developed from-the RPV Control Guideline at Step RC-1 and execute it concurrently with this . procedure. SC/T-5 If a primary system is discharging into an area and anl area temperature exceeds its maximum safe operating temperature in more'than one area, EMERGENCY RPV DEPRESSURIZATION IS' REQUIRED. SC/R Monitor and control secondary containment radiation levels. SC/R If any area radiation level exceeds its maximum normal operating radiation levtl, isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire. ( SC/R-2 If a primary system is discharging into an area, then before ~ any area radiation level reaches its maximum safe operating radiation level, enter procedure developed from the RPV Control Guideline at Step RC-1 and execute it concurrently with this procedure. l

\\p/

v (SC-3 ) - Rev. 1-

+ -t 1 SC/R-3/ IfLa primary; system is-discharging"into an area and an area ! ['~'\\ radiation level exceeds its maximum safe operating radiation A ) level -in more than one area, EMERGENCY RPV DEPRESSURIZATION IS b' REQUIRED. EC/L Monitor and control. secondary containment water levels. SC/L-1 If.any' floor drain 1 sump or area water. level is above its maximum normal operating water'-level, operate,available sump. pumps to restore;and maintain it below its maximum normal cPerating water level. If any floor drain-sump or area water level cannot be restored-and maintained below its. maximum normal operating water level, ' isolate all systems that are discharging water-into the sump or area except-systems required to shut down the reactor, assure adequate core cooling, or suppress a working fire. SC/L-2 If a primary system-is-discharging into an area, then before any floor drain sump or area water level reaches its maximum safe operating water level, enter procedure developed from the RPV Control Guideline at: Step'RC-1 and execute it concurrently with this procedure. 4 SC/L-3 If a primary system is discharging into an area and a floor drain sump or area water level exceeds its maximum safe 0Ferating water level in more than one area, EMERGENCY RPV ~ DEPRESSURIZATION IS REQUIRED. c l .i I l f (SC-4) Rev. 1 -. ~.

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ID/00130/ l RADI0 ACTIVITY RELEASE CONTROL GUIDELINE PMRPOSE The purpose of this guideline is to limit radioactivity release into areas -outside the primary and secondary containments. ENTRY CONDITIONS 1 The entry condition for this guideline is: 'Offsite radioactivity release rate above 10 times'the Technical Specification limit (release rate which requires an ALERT). OPERATOR ACTIONS Isolate all primary systems that are discharging ibto areas outside the RR-1 primary and secondary containments except systems required to assure adequate core cooling or shut. down the reactor. RR If offsite radioactivity release rate approaches or exceed 1 R/HR (release rate which requires a GENERAL ruracENCY) and a primary system l 1s discharging into an area outside the primary and secondary containments, runacINCY RPV.DO RESSURIZATION IS RRQUIRED; enter procedure developed from tha RPV Control Guideline at Ste'p RC-1 and execute it concurrently eith this procedure. l l / i r l (RR-1) Rev. 1 _ _ _,...w

3.- ID/00142/ v ,/. CONTINGENCY #1 \\ LEVEL RESTORATION If while executing the following steps: Boron Injection is required, enter procedure developed from CONTINGENCY

1. 7.

RPV water level cannot be determined RPV FLOODING IS REQUIRED; enter procedure developed from CONTINGENCY #6. RPV Flooding is required, enter procedure developed from CONTINGENCY #6. Cl-1 Inititate HPCI Cl-2 Line uP for injection and start pumps in 2 or more of the following injection subsystems: Safe Shutdown Pump RCIC-j LPCI V C3-A CS-B 1 l l s 's (Cl-1) Rev. 1 s L :.

9.. If less than 2 of the injection subsystems can be lined up, cosumance lining up as ar.ny of the following alternate injection subsystems as possible: Service water crosstie Fire system to Safe Shutdown Pump Interconnections with other units ECCS Jocky Fill SBLC (tist tank) SBLC (boron tank) Cl-3 Monitor RPV pressure and water level. Continue in this procedure at the step indicated in the following table. RPV PRESSURE REGION l 2 425 psig 100 psig HIGH INTERMEDLATE LOW IECREASING Cl-4 Cl-S Cl-6 DECREASING C1-7 Cl-8 1 (RPV pressure at which CS shutoff head is reached) 2 (HPCI low pressure isolation setpoint, whichever is higher) %".2 ^ If while executing the following steps: The RPV water level trend reverses or RPV pressure changes region, return to Step Cl-3. RPV water level drops below -59 in. (ADS initiation setpoint), prevent automatic initiation of ADS. O (Cl-2) Rev. 1

Cl-4 RPV WATER LEVEL INCREASING, RPV PRESSURE HIGH O Enter procedure developed from the RPV Control Guideline at (Step RC/L). Cl-5 RPV WATER LEVEL INCREASING, RPV PRESSURE INTERMEDIATE If HPCI and RCIC are not available and RPV pressure is increasing, EMERCENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure ia decreasing, enter -rocedure developed from the RPV Control Guideline at Step RC/L. If HPCI and RCIC are not available and RPV pressure is not increasing, enter procedure developed from the RPV Control Guideline at Step RC/L. Otherwise, when RPV water level reaches +8 in. (low level scram setpoint) ente.r procedure developed from the RPV Control Guideline at Step RC/L. Cl-6 RPV WATER 7.EVEL INCREASING, RPV PRESSURE LOW If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter procedure developed from the RPV Control Guideline at Step RC/L. Otherwise, enter procedure developed from the RPV Control Guideline at Step RC/L. 8 Cl-7 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH OR INTERMEDIATE If HPCI or RCIC is not operating, restart whichever is not operating. If no injection subsystem is lined up for injection with at least one pump running, start pumps in alternate injection subsystems which are lined up for injection. i O (Cl-3) Rev. 1

.. w When RPV water level drops to -143 in. (top of active fuel): 9 If no system, injection subsystou or alternate injection subsystem is lined up with at least one pump running, STRAM COOLING IS REQUIRED. When any system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, return to Step C1-3. Otherwise, EMERGENCY RP7 DEPRESSURIZATION:IS REQUIRED. When RPV water level is increasing or RPV pressure drops below 100 psig (HPCI low pressure isolation setpoint) return to Step C1-3. Cl-8 RPV WATER LEVEL DECREASING, RPV PRESSURE LOW If no LPCI or CS subsystem is operating, start pustys in alternate f ajection subsystems which are lined up for injection. If RPV pressure is increasing, EMERGENCY RPV DEPRESSURI2ATION IS REQUIRED. ~ When RPV water level drops to -143 in. (top of active fuel), enter procedure dSvaloped front CONTINGENCY #4. O 9 (Cl-4) Rev. 1

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i ID/00150/ ] (' l CONTINGENCY #2 V ammaussCY RPV DEPRESSURIZATICA f i l .C2-1 When either:

1. 13. #14 l

Boron Injection.is required and all injection'into-the RPV except from boron injection systems and CRD has been terminated-and prevented, or Boron Injection is not required, C2-1.1 This step left blank C2-1.2 If suppression pool water level is above 4 ft. 9 in. (elevation of top of SRV discharge device): Open all SRV's. C2-1.3 If less than 3 (Minimum Number of SRVs Required for Emergency Depressurization) SRVs are open _j,31_ and RPV pressure is--at least 50 psig (Minimum SRV Re-opening Pressure) above suppression chamber pressure, capidij depressUrize the RPV using one or l more of the following systans (use in order which will minimize radioactive release to the environment): s Main condenser Main steam line drains HPCI steam line RCIC steam line Head vent EMCU J f (C2-1) Rev. 1 ) . -.. _. _ _ -. -.__._ _.-.--..- _ -.. ___.._..,.._- _ _.-_.. ~. _..

i l 'J 4 i i ' If RPV_ Flooding is required, enter procedure developed from CONTINGENCY 96. l Enter procedure deve16 ped from the RPV' Control Guideline at Step RC/P-4. .C2-2. i 6 ? i I t t l ll. l, I (C2-2) Rev. 1 ~ -.

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~ .i CONTINGENCY ~#3 STEAM COOLING I I- - C3-1 l- .o If while. executing the following steps Emergency RPV repressurization:- is required or any system,Jinjection subsystem, or alternate; injection subsystem:is lined up for injection with at least one pump. running, enter procedure developed from CON *INGENCY.#2. 1-When RPV t;ater level drops to -240Lin. (Minimum Zero-Injection RPV Water Level) or'if RPV water level cannot be determined,.open one SRV... When=RPV pressure drops below 700 psig (Minimum Single SRV Steam' Cooling Pressure), enter procedure developed - from CONTINGENCY _ #2. i .I s i f 1 i t t i-l l I' I i H NN (C3-1) Rev. 3 - _ _ _,. _ _ _. _.. ~

ID/00170/ 9 CONTINCENCY #4 CORE COOLING WITHOUT LEVEL RESTORATION C4-1 Open all SRV's. _f.l.l C4-2 Operate Core Spray subsystems with suction from the suppression pool. When at least one core spray subsystem is operatins with suction front the suppression pool and RPV pressure is below 190 psig (RPV pressure for rated CS) terminate injection into the RPV from sources external to the primary containment. C4-3 When RPV water level is restored to -143 in. (top of active fuel) enter } procedure developed from the RPV Control Guideline at Step RC/L. s = 2 3 I = r 4 = G = 'i 9 5 (C4-1) Rev. 1 ss

ID/00180/ 9 CONTINGENCY #5 ALTERNATE SHUTDOWN COOLING C5-1 Initiate suppression pool cooling. CS-2 Close the RPV heed vents, MSIVs, main steam line drain valves, and HPCI and RCIC isolation valves. C5-3 Place the control switch for one (Minimum Number of SRVs Required fors Alternate Shutdown Cooling) SRV in the OPEN position. C5-4 Slowly raise RPV water level to establish a flow path through the open SRV back to the suppression pool. C5-5 Start one RKR pump with suction from the suppression pool. CS-6' Slowly increase LPCI injection into the RPV to the maximum. C5-6.1 If RPV pressure does not stabilize at least 54.4 psig (Minimum Alternate Shutdown Cooling HPV Pressure) above suppression chamber pressure, start another RHR pump. C5-6.2 If RPV pressure does not stabilize below 166 psig (Mav M m Alternate Shutdown Cooling RPV Pressure, open another SRV. C5.6-3 If the cooldown rate exceeds 100*F/hr (maximum RPV cooldown rate LCO) LPCI injection into ths RPV until the cooldown rate decreases below 100*F/hr (maximum RPV cooldown rate LCO) or RPV pressure decreases to within 50 psig (Minimum SRV Re-opening s Pressure) of suppression chamber pressure, whichever occurs first. C5-7. Control suppression pool temperature to maintain RPV water temperature 3 above 140*F (RPY NDTT). CS-8 Proceed to cold shutdown in accordance with procedure QGP 2-3 for cooldown to cold shutdown conditions. 2 1 I i = !O b (C5-1) Rev. 1

h ID/00190/ CONTINGENCY # 6 RPV FLOODING C6-1 If at least 3 (Minimum number of SRVs Required for Emergency Depressurization) SRVs can be opened, close the E*IVs, main steam line drain valves, HPCI and RCIC isolation valves. C6-2 If any control rod is not-inserted beyond position 04-(mawi= = suberitical bankM withdrawal position): C6-2.1 Terminate and prevent all injection into the BPV except from i -boron injection systems and CRD until RPV pressure is below the-Minimum Alternate RPV Flooding Pressure. 1 Minimum Alternate RPV Number.of open SRVs Flooding Pressure (psig) l_ 5 125 i 4 155 3 -- 210 2 320-If less than 2 (minimum number of SRVs for which the Minimum 's Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure) 3RVs can be opened, continue in this procedure. 4 ) l If while executing the following step, RPY water level'can be detemined and RPV Flooding is not required, enter procedure i developed from CONTINGENCY #7 and procedure developed from the RPV Control Guideline at Step RC/P-4 and execute these procedures concurrently. L (C6-1) Rev. 1 i

E i C6-2.2 Conmence and slowly increase injection into the RPV~ with the following systems until at least 2 (minimum

1. 25 number of SRVs for which the Mininnam Alternate RPV e

Flooding Pressure is below the lowest SRV lifting pressure) SRVs are open and RPV pressure is above the i Minimum Altornate RPV Flooding Pressure: Motor driven feedwater pumps [ Condensate pumps CRD LPCI Safe Shutdown Pump h If at least 2 (minimum number of~SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure) SRVs are not open or RPV pressure cannot be increased to abcVe the Minimum Alternate RPV Flooding Pressure, commence and slowly increase injection into the RPV with the following E systems until at least 2 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure) SRVs are c;en and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: CS LPCI I Safe Shutdown Pump RCCS Fill. Jockey Pump h C6-2.3 Maintain at least 2 (minimum number of SRVs for which the p Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure) SRVs open and RPV pressure above the Minimum s [ Alternate RPV Flooding Pressure by throttling injection. ? e ? I ^ (C6-2) Rev. 1 I

~ m C6-2.4 When: f All control rods are inserted beyond position 04 (maximum suberitical banked withdrawal position), or n 5 The reactor is shutdown and no bcron has been injected into the RPV, P continue in this procedure. [ C5-3 If RPV water level cannot be determined: R C6-3.1 Comumence and increase injection into the RPV with the following systems until at leat 3 (Minimum Raaber of SRVs Required for Emergency Depressurization) SRVs are open and RPY pressure is not decreasing and is at least 77 psig (Minimum RPV Flooding Pressure above suppression chamber presse.ie. Safa Shutdown Pump Motor driven feedwater pumps CS 7 LPCI Condensate pumps r CRD ECCS Jockey Pump SBLC (test tank) SBLC (boron tank) 5 C6-3.2 Maintain at least 3 (Minimum Number of SRVs Required for Emergency Depressurization) SRVs open and RPV pressure at least 77 psig (Minimum RPV Flooding Pressure) above suppression s [ chamber pressure by throttling injection. t a E tz = E [ s b. f b k (C6.3) Rev. 1

... ~... _ C6-4 If RPV water level can be determined, commence and increase injecticn 9 into the RPV with the following systems until RPV veter level is increaring: Safe Shutdown Pump Motor driven feedwater pumps CS LPCI Condensate pumps CRD RCCS Jockey Pump SBLC (test tank) SBLC (boron tank) C6-5 If RPY water level cannot be determined: C6-5.1 Fill all RPV water level instrur.entation reference columns. C6-5.2 Continue injecting water inLo the RPV until temperature near the cold reference les instrument vertical runs is below 212*F and RPV water level instrumentation is available. If while executing the following steps, RPV water level can be determined, continue in this procedure at Step C6-6. C6-5.3 If it can be determined that the RPV is filled or if RPV pressure is at least 77 psig (Minimum RPV Flooding Pressure) above suppression chamber pressure, terminate all injection s into the RPV and reduce RfV water level. C6-5.4 If RPV water level indicat8 a is not restored withing the F.axbuum Core Uncovery Tinh. .mit after commencing termination of injection into the RPV, return to Step C6-3. O (C6-4) Rev. 1

/ O This page intentionally left blank. O 9 (C6-5) Rev. 1

ID/0176A/ 1 CONTINGENCY #7 LEVEL / POWER CONTROL l t I If while executing the following steps RPV Flooding is required or RPV water -level cannot be determined.. control injection into the Egv to maintain reactor power above 8% (Reactor Flow Stagnation Power) but as low as practicable. However, if reactor power cannot be determined or maintained above 8% (Reactor Flow Stagnation Power), RPV FLOODIEG'IS REQUIRED; enter procedure developed from CONTIEGRECY #6. C7-1 If: l Reactor power is above 3% (APRM downscale trip) or cannot be determined, and Suppression pool temperature is_above 130*F.(Boron Injection Initiation Temperature), and Rither an SRV is open or opens or drywell pressure is above 2.0 psig (high drywell pressure scram setpoint) lower RPY water level by terminating and prevent all injection into the RPV except from boron injection (31_ systems and CBD until either: s Reactor power drops bowlow 3% (APRM downscale trip) or RPV water level reaches -143 in. (top of active fuel), or All SRVs remain closed and drywell pressure remains below 2.0 psig (high drywell pressure scram setpoint). (C7-1) Rev. 1 .-.-2.

If while executing the following steps Emergency RPV Depressurization is required, continue in this procedure at Step C7-2.1. If while executing the following step Reactor power is above 3% (APRM downscale trip) or cannot be determined, and RPV water level is above -143 in. (top of active fuel), and Suppression pool temperature is above 130*F (Boron Injection Initiation Temperature), and Either an SRV is open or opens or drywell pressure _is above 2.0 psig (high drywell pressure scram setpoint), return to Step C7-1. O C7-2 Maintain RPV water level either: 49, #10, #11, #25 If RPV water level was deliberately lowered in Step C7-1, at the level to which it was lowered, or If RPV water level was not deliberately lowered in Step C7-1, between +8 in. (lowlevelscramsetpoint')and+48in. (high level trip setpoint) with the following systems: Condensate /feedwater system 1100 - O psig (RPV pressure range for system operation) CRD system 1100 - O psig (RPV pressure range for system operation) Q (C7-2) Rev. 1

-RCIC system 1150 - 50 psig (RPV" pressure range for' (~ ( system operation) .#12. \\ HPCI system 1150 - 100 psig (RPV. pressure range for system operation) t .LPCI system 325 - O psig (RPV pressure range for system operation) If RPV water level'cannot be so maintained, maintain:RPV water.. level above -143 in.,(top of active fuel). If RPV water level cannot be maintained above -143 in..(top of. active fuel), numacENCY RPV DEPRESSURIATION IS REQUIRBD: C7-2.1 Terminate and prevent all injectiou into the BPV except from boron-injection systems and CBD until RPV pressure is below the Minirum Alternate RPV Flooding Pressure. t Minimum Alternate RPV k W r of open SRVs Flooding Presst. ire (psis) 5 125 4 155 3 ~ 210 2 320 s i If less than 2 (mirimum number of SRVs for which the Minimum Alternate RPV Floedicts Pressure is below the lowest SRV lifting presure) SEVs can be c,pened, continue in this procedure. l t i i (C7-3) Rev. 1 L,

M. C7-2.2 Commence and slowly increase injection into the RPV with the following systems to restore and maintain

1. 25 RPV water level above 143 in. (top of active fuel).

Condensate /feedwater system CRD RCIC HPCI LPCI Safe Shutdown Pump If RPV water level cannot be restored and maintained above -143 in. (top of active fuel), comunence and slowly increase injection into the RPV with the following systems to restore and maistain RPV water level above -143 in. (top of active fuel): CS LPCI Safe Shutdown Pump Jockey-Pump ~ If while executing the following step reactor power commences and continues to increase, return to Step C7-1. C7-3 When 266 pounds (Hot Shutdown Boron Weight) -f boron have been injected or all control rods are inserted beyond position 04 (mari= = suberitical banked withdrawal position), restore and naintain RPV water level between +8 in. (low level scram setpoint) and +48 in. (high level trip setpoint). O (C7-4) Rev. 1

Q . c) If RPV water level cannot be restored and maintained.above +8 in. (low level scram setpoint), maintain RPV water level above -143 in. (top of~ 0 active fuel). If RPV water level cannot be :aaintained above -143 in. (top of active fuel) EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; return to Step C7-2.1. If Alternate Shutdown Cooling is required, enter procedare developed from CONTINGENCY iS. C7-4 Proceed to cold shutdown in accordance with procedure QGP 2-3 for cooldown to cold shutdown conditions. O O (C7-5) Rev. 1

9 . rv ( t 4 7 l l i-i I QUAD-CITIES STATION EMERGENCY PROCEDURE WRITER'S GUIDELINE I I f i f i 1 t i r k I i t i I r b I l l F I ID/ TEMP-H I

~ 4 ATTACHMENT 2 m' f, ( LIST OF ABBREVIATIONS ADS - Automatic Depressurization-CRD - Control Rod Drive EHC - Electro-Hydraulic Control ERV -- Electromatic Relief Valve HPCI - High Pressure Coolant Injection HVAC - Heating, Ventilation, and Air Conditioning-LPCI - Lov Pressure Coolant Injection MSIV - Main Steam Isolation-Valve RBCCW - Reactor Building Closed Cooling Water RCIC - Reactor Core Isolation Cooling RPV - Reactor Pressure Vessel RWM - Rod Worth Minimizer RHR - Residual Heat Removal RPS - Reactor Protection System SBLC - Stand-by Liquid Control SGTS - Stand-by Gas Treatment System SRV - Safety / Relief Valve i SS? - Safe Shutdown Pump l s i TBCCW - Turbine Building Closed Cooling Water TIP - Transversing Incore Probe UPS - Uninterruptible Power Supply l i , (final) p n . _ _, _.~._. -.. _ _. _ _.. _ _ -

TABLE ~OF CONTENTS"

1.0 INTRODUCTION

1.1 Purpose 1.2 Scope 2.0~ PROCEDURE NETWORK 2.1 Procedure Category 2.2 Emergency Procedure Designation and Numbering 2.2.1 P*ocedure Designation 2.2.2 Procedure Numbering 2.2.3 Revision Numbering 3.0 FORMAT 3.1 Procedure Heading 3.2 Page Identification and Numbering 3.3 Instruction Step Numbering 3.4 Figure Numbering 3.5 Page Format 4.0 MECHANICS OF STYLE 4.1 Spelling 4.2 Vocabulary 4.3 Numerical Values 4.4 Units of Measurs 4.5 Abbreviations, Letter Symbols and Acronyms O

[. 4

f ;-

.) 1

s TABLE OF

CONTENTS ^(CON'T):

1 4.6 Capitalization-p ~ 4.6.1 Titles of an' Organizational Structure .4.6.2\\ Systems and Components ' T

4. 6.3 -. -Headings an'd' Subheadings f'

4.6.4 - Pfodes 'of Operation

4.6.5 Figures

4. 6. 6 ' Use of Logic Terms 4.7 Use of Underlining :

4. 8_

Listing of References i- '5.0 TERMINOLOGY J, r 5 '.1 Component Identification I (_ 5.2 Definition of Terms 5.3 Level of Detail + 5.4 Use of Cautionary Notes f 5.4 Description of Component Status i l l i .t I s. o i h ---..~,., -. n.,,-..--- - -.._..,.v._

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} ~ n- ,u ) - ~ ' '110?cINTRODUCTION< h-1'! PURPOSE. 1 1 ) . This writer's guide provides guidance that is' applicable:tolthe ' Emergency Operating Procedures at Quad-Cities' Station. I ts - purpo'se ' is to-provide administrative and technical guidance on the preparation- ~ of' function oriented Emergency ~ Operating-Procedures. 1.2 SCOPE-This writer's" guide only: applies. to those procedures ' contained in -Quad-Cities ~ Station GeneralEAbnormal Procedures Manual'(QGA)- - 2.0- PROCEDURE NETWORK ' 2.1 PROCEDURE' CATEGORY Within the procedure network, the major categorization of procedures is by the type of function addressed by the procedure. Emergency procedures are procedures which govern the' plant-operation during conditions of uncertainty ~and will~ return-the plant toza-safe and. stable condition. 2.2 EMERGENCY PROCEDURE ur:IGNATION AND NUMBERING 11i- -( L Each procedure will.be uniquely id.nt.fied. -The identification. l. permits easy administration of 'the process of procedure preparation, ' review, revision, distribution, and operator use. i 2.2.1 PROCEDURE DESIGNATION Designation of the emergeacy procedures will be QGA, Quad-Cities l General Abnormal Procedures. 2.2.2 PROCEDURE NUMBERING The emergency procedure numbering system is divided into l three main components: book, block, and the procedure. The-l book is designated by QGA. The block numbers start with 100 and are numbered consecutively for as many blocks as necessary. Example: 100, 200, 300,~etc. The procedure number'follows the block number and is also numbered consecutivel'y for as many procedures as necessary. Example: QCA 100-1 f Procedure Number Block Number Book. I l 1

3 7-

,Y -a,,,,.__-.-,__-.__a.-._._...___,.,---..,...-,-.,_.-___.--

s-a 'I -.= s 2.2.3 REVISION NUMBERING' ry - I .\\ -The revision number will appear on each page of'the procedure. .It will appear;in' the upper right hand corner of the page -l below the procedure number. i t-3.0 -FORMAT-3.1.. PROCEDURE HEADING 1 Every emergency procedure will:.have an, identification heading, on - page_1. The purpose of this heading is: (1) to identify the-procedure; -(2) to identify the' revision number; and'(3);to give the~ month and year of the' initiation of the revision. 3.2 PAGE IDENTIFICATION AND NUMBERING L Each page of the procedure will be identified by (1) the procedure number and revision number located _in the upper right-hand corner of the page and (2) the pages will be numbered sequentially at'the bottom of each page with the word (final) on the'last page. 3.3 INSTRUCTION STEP NUMBERING Instruction steps will be numbered and identified as follows: b A. k 1. a. (1) (a) i 3.4 FIGURE NUMBERING Figure: or tables that are not part of the main procedure but may be needed as reference material will be contained at the end of the block of procedures. The numbering will be the same as for the main procedures except that the figure or table number will be proceded by a "T". Example: QGA 300-T4 Figures or tables which are necessary to be part of the main procedure will be incorporated wherever needed in the procedure for convenient use. 3.5. PAGE FORMAT An example of page format is presented in ATTACEMENT 1. i i ! O-b

5 s. - us-m + ] i s ^ d ' " =, 4.0. MECHANICS'0FTSTYLE ~ M I i 'l j \\j;- -:4.1 ' SPELLING , ~ i _ Spelling should be consistant with modern usageh 1When a ch'oicefof- ~ spelling is offered.byfa dictionary, the firstLspelling.should'.be. -{ -used. .'4.2.-VOCABULARY m Words.used in-proceduresJshould' convey precise understanding'to thei trained. person. a.. Use: simple'words. ~ Simple words'are usually'short words offfew-syllables. 4 ' Simple words are general'ly common words. p -b. Use. common usage'if it makes the procedure. easier to understand.' i a c. Use words'which'are concrete'rather than vague, specific rather - -than. general, familiar:rather than' formal', precise rather.than ' -blanket. d. ' Define words that may be-understood.in-more-than one sense. Avoid using' verbs. that: are unfamiliar, vague,; or that can be: e. misinterpreted. f. Eliminate superfluous words. } g. The:use of shall, will, should, and may are as-follows: l 1. Shall-mandatory requirement. l 2. Will mandatory req irement. i l-3. Should - preferred or des ed method. Nonmand .o ry i 4. May a ce.ptable or wggested method. i h. System readiness or statur will.be denoted as follows. 1. Operable / operability. These worIs mean that a system, subsystem,l train,-component, or device-is capable'of performing its specified function. Implicit:in this definition should be the. assumption that all necessary l attendant instrumentation, controls, electrical ~ power sources, cooling or seal water, lubrication or other-auxiliary equipment that are required for.the system, rubsystem, train, component, o h vice to perform its function'are also capable of pc eming their related function. g r l- .2

7._- - g- -un w K. m) i {..~ ^ L 2.. ;0perating. -Thistword means:that!a' system,' subsystem,;

Jl\\1p}L train' component,;or' device _is.in operation and-is

performing c

~ '. j ,its specified function,'and that."out of service cards" or other. conditions do not prevent._it from maintaining-that ~ se rvice. '3.. Available; :This word means that'a system,Jsubsystem,. ~ . train,1 component, or device isioperable and can be used as ' desired. However, it;.need not-be operating. NOTE' If a system does-not fit one of the above.- s ' fo nsa l' de finitions - its use should not be'

• ed out if it can fuaction in aidegraded lu..e'of; operation.

1 1. Usel logic ~ terms-as follows: ~ 1. When attention does need:to be called to combinations of conditions, the word AND shall be placed between the description of each condition. The word AND shall' not-be used to-join more than three conditions. If more than.four conditions need to be' joined,'a list format shall be.used. ~s k,,, 2. The word OR'shall be used-when calling attention to alternative combinations of conditions. The use of.the word ~0R shall. always be in the inclusive sense. To specify the exclusive. "or" the following may,be used: either A OR B but not both. 3. When action steps are contingent upon certain conditions or combinations of conditions, the. step shall begin with j, the' words IF, IF NOT, or k' HEN followed by a description of l the condition or conditions (the antecident), a comma, the word THEN ~ followed by the action to be 'taken (the consequent). p 4. Use of IF NOT'should be-limited to those cases where the operator must respond to the'second of two possible conditions. IF should be used to specify the first condition. J. Avoid all-inclusive words unless the absolute meaning is real. l All inclusive -words include - never, all, L always, everyj and none. 4 r t: 4 / e e

u g ~ 4.3 NUMERICAI.' VALUES. Y

k

[ !The use of numerical values should be. consistent with the following rules: a. Arabic numerals should be used. b. For numbers less.than unity, the decimal point will oe precededL byla'zero. c. The - number of'significant - digits _ should be equal.to " the i number. of significant-digits contained in the acceptable tolerance.for the-measurement, except for common usage. d d. -Acceptable values should be specified such that addition and subtraction by the' user is avoided if possible. This can generally be-done by stating acceptance values as limits. Examples: 510*F maximum, 300 psig minimum, 580*F to 600*F 4.4 UNITS OF MEASURE t Units of measure are fixed by definition.by the National Bureau of Standards (NBS). Units of measure will be consistent'with NBS~ definitions. 4.5 ABBREVIATIONS, LETTER SYMBOLS,AND ACRONYMS The use of abbreviations should be limited to those which are common to a well trained licensed reactor operator. Abbreviations may be used where necessary to save time and space and where their meaning is unquestionably clear to the reader. A list of abbreviations is included in ATTACKMENT 2. Capitalization of abbreviations should be uniform. If the abbreviation is comprised of lower case letters, it should appear in lower case in a title or heading. The period should-be omitted in abbreviations except in cases where the omission would result in confusion. Acronyms are words formed by the initial letters of a name. Example: Ceco for Commonwealth Edison Company Letter symbols may be used to represent operations, quantities, elements, and' relations. The meaning of a symbol should be spelled out at the point of its first use or defined within the procedure or other standard source. I i . ~. -.

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) 7: - + ~~e Abbreviations, symbols, and acronyms should not be over-used. Their .f 'by: use should be for the benefit of the reader. They should be beneficial \\s. a. Saving reading time. b. Ensuring clarity when space is limited. c. Communicating mathematical ideas. 4.6 CAPITALIZATION; It.should be recognized that no one set of rules for. capitalization. can be universally applicable or.all encompassing. The~following 4 guidelines.will be applied in principle to areas not strictly defined. 4.6.1 ~ TITLES OF AN ORGANIZATIONAL STRUCTURE Staff positions and titles, when they refer to an individual with specific authority, duties, and responsibilities are capitalized. General categories or groups of people identified within the organizational structure are not capitalized. Examples: Station Superintendent Operating Engineer Shift Engineer l Reactor Operator electrician mechanic 4.6.2 SYSTEMS AND COMPONENTS The name of plant-system titles are capitalized. When the j word " system" is deleted from the title because of brevity and is understood because of context, the title is capitalized. When words from the title of a system are used and reference to that system is not intended, the words are not capitalized. Examples: Residual Heat Removal System The recirculating pump supplies... l 4.6.3 HEADINGS AND SUBHEADINGS I f First-level sentence headings will be placed in full capitals with an underscore, second-level sentence headings will be placed in full capitals without an underscore, and third-level i sentence headings will be placed in initial capitals without an underscore. s) l ! . ~ ~.

4.6.4. ~ MODES-OF OPERATION' .I J ~- i Modes of operation should be capitalized as they apply to a 'N specific configuration of the plant or of a system. Examples: ' Hot Standby Cold Shutdown Hot Shutdown : Refueling Outage 4.6.5 FIGURES - Capitalization should be used for references to-figures and. -titles of' figures within text' material. 4 Example: Refer to FIGURE 2 for... 4.6.6 USE OF LOGIC TERMS The logic term AND,'OR, NOT IF, WHEN, and THEN are often necessary to preciselv describe a set of conditions of-sequence of actions. When logic statements are used,-logic terms.will be highlighted so that all the contingencies are clear to the operator. Highlighting and emphasis will be achieved by using capitalization and underlining. All leters of the logic terms will be g capitalized. The use of AND and OR within the same logic \\~ statement will be avoided. When'AND and OR are used together, the logic-statement can be very ambigious. 7 4.7 USE OF UNDERLINING l Underlining will be used for emphasis. l 4.8 LISTING OF REFERENCES 1 Listing of references within the text of procedures should be minimzed. The concept of "each procedure stands alone infers that references are not necessary within procedural text. But, it is impractical-to blindly follow this concept. Listing of references within text of procedures are as follows: When the task required by a procedure is wholly governed by-a. another procedure, such other procedure should be referenced rather than repeating the instruction. l b. When the entire referenced procedure must be used to accomplish the task, only the procedure number need be referenced at the end of the step. Example:

1. Initiate shutdown cooling (QOP 1000-5).

When only several steps apply from the procedure to be referenced, c. such steps should be reiterated and the procedure should not be N. referenced. f L ! i: I L

,1 F -;-Hf c5.0 TERMINOLOGY 2 ) ,.L/ 5.1 COMPONENT IDENTIFICATION With' respect to identification of components, the following-rules ~ are established: a. Equipment, controls, and displays will be identified in operator- ' language-(common = usage) terms. These te.rms may not always match engraved names on panels but will be complete. b. When engraved names and numbers on panels and alarm windows are specifically the -item of concern -in the procedure, the engraving should'be quoted verbatim and emphasized by using all capitals. 5.2 DEFINITION OF TERMS-Terms.may be understood in more than one sense. It is important that the same term be used consistently in all' procedures which use the term. A-listing of terms and their definitions are provided in - ATTACHMENT 3. 5.3. LEVEL OF DETAIL-Too much detail should be avoided in the interest of being able to p effectively execute the instructions in a timely manner. The level I of detail required is the detail that a newly trained and licensed k _, operator would desire during an emergency condition. s 5.4 USE OF CAUTIONARY NOTES Cautionary notes can be considered in two fundamental categories: those that apply to the entire procedure and those that apply to a portion of the procedural content. Those that apply to the entire procedure are named PRECAUTIONS and are covered in operator training. ~ Those that apply to a portion of a procedure are named CAUTIONS and are placed immediately BEFORE that procedural content to which they. apply. This helps ensure that the procedure user' observes the caution before performing the step. It should be used instead of an instructional step. It should be used to denote a potential hazard to equipment or personnel associated with or consequent to the subsequent instructional steps. l i n-s__- i I l- : - ~ -., _ ~

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1 J5.5 -DESCRIPTION ~OF COMPONENT ^ STATUS' _ Y.M. Specific terminology should'be defined and adopted to. indicate . component. status. 'All procedures which refer to such status should' . use the adopted terminology. The following terms'and definitions are recommend'd. P . a'. ?In. Service /Out.of Service. This means that the component'is or 'not functioning within the plant mode of operation. b. -. Running / Shutdown..This-refers-to the conditions oftrotating; equipment'. c. On/Off. This should be used forisimple-equipment. Example: recorders, lights, and;it'.means that equipment is-or i is not being powered. d. - Racked In/ Racked'Out. This should be ' used. for p hysical statu's ~ of.switchgear and it means that the switchgear is available. E or not available to supply equipment. e. Energized /De-energized. This should be used to indicate status'- - of electrical' circuits, such as logic circuits and electrical' buses, and it means that the circuit is or is-not powered. ? 4 I 4 i t t 4 I e \\ F d f-t' F ,,,e. -,..,----,t. .,--.---,-w---w-,...,, ---.-..,,..#,.,,-,--,,,.,,._.-._m,..,--_ -...r-,..~,--

____..7..;.. - _.. _..., _.. _ _ ~ _ _ _ _. _ _ _ _. ~. _ _ _.... i l:z-' + 1 i t ATTACHMENT'1 6' i-

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QGA'100-1 l -~' Revision'1 January 1984' i j t [ Ma rgin - l'.' ' [ .I. ENTRY' CONDITIONS. -(heading al1. caps-and underlined) e c -A. THIS HEADING 'IS ALI.. CAPS NO UNDERLINE - l. B. l. C.- II. OPERATOR ACTIONS l f-A. I f f-1. IF -X' (start here with typing). THEN X. } a. (1) 4 i' (a) i-l f-o i I k .5 i l i-I I 9 i- (final) i . r i (-

3 T ATTACHMENT:3-j_q II )

As_- -

PROCEDURE'1ERMS AND THEIR DEFINITIONS \\ / VERB / TERM APPLICATION Allow To permit a stated condition to be achieved prior to ~ . proceeding, for-example, " allow discharge pressure;toi = stabilize". Check To perform a physical; action which achieves a result, such as " check lube oil level". CLOSE Opposite of open, for example: CLOSE VALVE 2001-833. Complete To accomplish specified procedural requirements. Establish To make arrangements. for a_ stated condition, for example: " establish communication with control room". INITIATE To cause an evolution to happen,-for example: INITIATE shutdown cooling. Inspect To measure, observe, or evaluate a feature or characteristic for comparison with specified limits; method of inspection should be included, for example: " visually inspect for leaks". OPEN To change the physical position of a mechanical. device, j such as valve or door to the fully open position. 4 RECORD To document specified condition or characteristic, for example: " RECORD discharge pressure". ^ SET To physically adjust to a specified value an adjustable feature, for example: " SET diesel speed to rpm". Shif t Supervisor This term is to include the Shift Engineer, the Shift Foreman, and the Station Control Room Engineer. START To energize an electro-mechanical device by manipulation of a start switch or button, for example: " START. . pump". STOP Opposite of start, for example: "STOP pump". THROTTLE To position a mechanical device to achieve the results required by the procedural step. TRIP To manually activate a semi-automatic feature, for ) example: " TRIP breaker. ) Ns_/ 1

,,. ~ -.. l.. - ATTAC}Df5NT:3 : PROCEDURE TERMS AND THEIR DEFINITIONS (CONTINUED) i i VERB / TERM APPLICATION i - ' VENT To perform a venting activity whose-complexity is within-the-skills of.the operator, for example: VENT,. . pumps". l VERIFY To ensure that a particular parameter _or equipment position is in the. desired condition. If it:is not;.it-shall be-placed to the desired condition. i. i 1 i i 4 5 t 4 1 1 i 1 j. i i - (final)

4...

ATTACHMENT 4:

QGA PROCEDURE _BE" m WN .100 REACTOR CONTROL 100-1-- ' Reactor' Level 100-2 . Reactor Pressure x 100-3 Reactor Power 200 PRIMARY CONTAINMENT CONTROL 4 200-1 Suppression: Pool Temperature n j 200 Dryvell Temperature i j 200-3 Containment Pressure i 1 200-4 Suppression Pool Level 1 4 L j ' 300 SECONDARY CONTAINMENT CONTROL I 300-1 Containment Radiation Level and Temperature i 300-2 Containment Water Levels t t J l 400 RADIOACTIVITY RELEASE CONTROL 1: 400-1 Radioactivity Release I ) i: i i l

D l l f i l QUAD-CITIES STATION PROGRAM FOR VERIFICATION AND VALIDATION OF EMERGENCY PROCEDURES 4 'I a l

_+ -p n it I.. VERIFICATION OBJECTIVES m Quad-Cities General _ Abnormal Procedure (QGA) verification objectives .[(j] are to confirm the QGAs. A. Accuras.Ay incorporate provisions of the Quad-Cities Technical Guidelines'. B. All written in compliance with the Quad-Cities Writers Guide. C. 'Present-a. level of ' detail enabling effective operator comprehension-and' response. D. . Utilize a language compatible to op'erator' training and experience.. E. Are compatible to plant equipment, controls, and indications regarding: 1. Equipment operation 2. Control / indication locaticas (with respect to procedure need) 3.- Nomenclature _ 4. Instrument unit of measure and readability II. VALIDATION OBJECTIVE j The objective of QCA validation is to determine that specified operations can be performed to manage the emergency condition. i s j III. VERIFICATION METHODS A. Desk-Top Reviews i The following desk-top reviews will be conducted for QCA verification. ( 1. Review of QGAs for compliance to the Technical Guidelines and compatibility to plant equipment, controls, and indications. 2. Review of QGAs for accuracy of plant-specific calculated parameters. 3. Review of QGAs for compliance to the Writers Guide for level of detail and language use. B. Control Room Walk-Through A walk through the Control Room will be used to verify level of detail and compatibility to equipment nomenclature, control / indication and instrument applicability. IV. VALIDATION METHODS A. Control Room walk-throughs by each rotating shift will demonstrate actions required by the QGAs can be related to equipment, controls, and indication. -

+

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3 4 B. Trcining' exsreises at ths Sir.ulator will bs used to dscenstrate ' and measure generic effectiveness = for' managing emergency-conditions. V.

DOCUMENTATION 1 -- V A.

Desk-Top Reviews Implementation of desk-top reviews will b'e documented by memorandum f or letter (accompanied by marked-p copies of procedures if f ' desireable). 4 B. Walk-Throughs 1. Control Room walk-throughs will be documented by checklist (Attachment 1). 2. Simulator exercises will be documented by checklist i (Attachment 2). } i 4 i t 9 i t' l 4 i 1 1 i t { 4 r l l I l t 2-

' + ~- h ;& A y, = ; s gf 3 m- ~ +: -e n:" ESRGENCY PROCEDURE 1 gf PLANT OPERATIONS WALK-TRROUGH~ CHECKLIST ,c -: 7' ~ ~ , PROCEDURE {NO. ~-DATE

z. List'anyl-step for.which: 2 s1.

Level of' detail is.< inadequate-or shoulu .be;revisedito. improve "how'to"Linstruction. 2.

Equipment':(pump, valve,'instrum nt, switch, i,

'etc.)'identificationfis incorrect or-omitted n 3 - when. identification'is required. i 0 i: l3. ~ Travel.from one location to another while complying with the procedures is impractical.. s;, p i' -4. An action is-required but no apparent-t l-. instrument, alare indicating light, etc. i monitors the effect of the action. l .~. t I 5: Installed instrumentation reads out in units i;, different than specified in'.the procedure. !i-!. t-I Comments-Signed Instructor 9 9 --Attachment I

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1

m ~ . = - fEMERGENCY PROCEDURE ~ i I v 'b ' GENERIC' SIMULATOR CHECKLIST. e ~ -Simulator-7% ' /\\ Transient ~ ~ ~ Procedure (s)'Used~

Date 1.

List any scep(s) resulting in.immediate' 4 ^ unexpected. simulator response.- Describe the unexpected response.- t -2. . List-any step (s)' that were difficult co perform in the necessary time interval. i j. Why? t 3. List any step (s) that were being performed l 1* -when management of the emergency was judged a failure. i What was the nature of the failure?' Rocommendations: P Signed: Instructor-( t l' Attachment-II .., _ _. -.. ~.. _.... _,. _ _. _ _ _. -... -.

Octob:r.1984 g QUAD CITIES STATION'DERGENCY OPERATING ^ n PROCEDURE TRAINING DESCRIPTION ' Introduction - Ther' general training format for each licensed operator will. involve three distinct phases. Phase one will involve formal classroom lectures, phase two will involve control ~ room and plant tours /walkdowns and phase three willarequire each licensM operator to demonstrate proficiency in the use of the E0P's at General Electric BWR Simulator in Morris, IL. Training Objectives-1. State, from memory, the entry conditions for Level Control, Containment Control and Reactivity Control. 2. Determine what conditions will allow departure from EOP's and subsequent use of normal operating procedures. 3. Identify control room instrumentation that monitor parameters for which EOP entry conditions are required. 4. Discuss alternate methods for shutting down the reactor. 5. Discuss flowpaths for initiation of alternate modes of shutdown Cooling.- 6. Given applicable graphs and parameters, determine whether limits defined by graphs in E0P's are being approached or exceeded. 7. Given parti::ular graphs, analyze the actions to be taken when parameters defined by the EOP graphs are exceeded. ( 8. Using the E0P's, simulate the operator's actions required to shutdown the reactor given a failure to scrse. 9. Discuss selected cautions using E0P's.

10. Using the EOP's, simulate the operators actions required to maintain adequate core cooling given a postulated transient with coincident equipment failure.

11. Using the EOP's simulate the operator's actions required to maintain primary or secondary containment parameters within limits.

e 1 1 e S

I TRevicica 1.. ~ .c Occ b r 1984 -i - g 112.i Demonstrate familiarity with SPDS/ EOF displays. as applicable. ' [h

13. Demonstrate ability to use'EOP's under accident conditions

while' operating at the Simulator facility.

t l. t EOF Training j '1. Classroom JQualifidd subject matter experts / instructors will

• use approved lesson plans to present the.EOP material to all licensed operators. Students will be given procedures, handouts

~

and flow charts for their use in analysing the~E0P's.' Generally, the E0P classroom training will address Logic terms'.. ~ use of general precautions, Procedure Specific precautions, Step [ Specific precautions, action verbs and special definitions.- Specifically, procedures'will be broken down step by step. Each series of steps will be explained in the text. The explanation will include reasons for taking the prescribed actions and how those actions are accomplished. l . 1 A formative oral evaluation will be conducted by the instructor at major steps in the procedures to ensure that. the trainees are j mastering'the material. Feedback on the procedures shall be col-lected from the students. This feedback will be considered fer l l changes to the lesson plan and appropriate comments will be forwarded to Operating Department procedure writers. t Classroom instruction will take approximately three days. A written-l examination will follow the classroom instruction. Additional i training will be required for satisfactory' class completion if the trainee scores below 70% on the written exam. i l 2. Control Room / Plant Walkdowns - approximately 8 hours will be devoted i by each licensed operator for the purpose of identifying all con-trol room instrumentation and plant equipment necessary for the effective implementation of the E0P's. Plant and Control room i ( j tours will be conducted under the direct supervision of a qualified I subject matter expert / instructor. I ~ i 3. Simulator - each licensed operator will epend three full days at the General Electric B.W.R. Simulator in Morris, IL to gain practice in i j the safe and effective implementation of the E0P's. These operators will be supervised by a qualified member of General Electric's or i Quad Cities Station's Training Staff. Any problems encountered . during simulation will be forwarded back to procedure writers for j resolution. Qualified training Staff members will perform evalua-tions of each licensed operators ability to implement the steps ( identified'in the E0P's. f s. 1. g - l j -w----,-m-,.-.,,5,----mmm-.y,..v,,-.-r--,,#mmy,m,,w, mew _, ,m,,m,-,.$.e-e,i.,n%,,,-,m,,,,m,-,..e --.d. 3,,,.m.w.. ~,..,.r-',-,,..,,..mm.. mm,,,.

October 1984 l t t Inctructional Techniques

• [

Instructor's guides with appropriate lesson plan material will be x f utilized during the classroom lecture format series. Student handouts / texts will be used as necessary. The number of students en-rolled in individual classroom sessions will be limited so as to Provide an optimum instructor to trainee retio and thereby provide maximum interaction. I Checklists will be used during control room / plant tours to aid in identifying all important instrumentation, controls and equipment. St=mntive evaluations will be used at the end of the classroom lecture and simulator training sessions. O V . (final) E. -}}