ML20093D156
| ML20093D156 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/08/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20093D155 | List: |
| References | |
| PROC-821208-02, NUDOCS 8410110125 | |
| Download: ML20093D156 (110) | |
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(l) PREPUBLICATION DRAFT EMERGENCY PROCEDURE GUIDELINES Revision-3I BWR 1 through 6 December 8, 1982 e
LASALLE COUNTY STATION EMERGENCY PROCEDURE GUIDELINE TECHNICAL GUIDELINE This Technical Guideline has been generated from revision 3I of the toergency Procedure Guideline. Any differences between revision 3I and
. revision 3 of the EPG has been designated by a letter in the margin.
Attachment A consists of a description of the change and the appropriate reason. Rach change is noted every time it appears throughout the Technical Guideline. . All parameters have been changed to comply with LSCS physical characteristics. The following systems are not installed at LaSalle and all references to them are-lined out without consnent.
- 1. IC
- 2. HPCI
- 3. Mk III containment
- 4. Heated Reference Legs
- 5. Mk I Containment
- 6. SPMS
~1. LPCS-B
i l Emergency Procedure Guidelines INTF!ODUCTION Cased on the various BWR system designs,-the following generic symptomatic cmergency procedure guidelines have been developed:
-RPV Control Guideline Primary Containment Control Guideline secondary Containment Control Guideline ; .. iloactivity Release Control Guideline The RPV control Guideline maintains adequate core cooling, shuts down the reactor, and cools down the RPV to cold shutdown conditions. This guideline
- is entered whenever low RPV water level, high RPV pressure, or high drywell pressure occurs, or whenever a condition which requires reactor scram exists and reactor power is above the APRM downscale trip or cannot be determined.
The primary Containment Control Guideline maintains primary containment - integrity and protects equipment in the primary containment. This guideline A is entered whenever suppression pool temperature, drywell temperature, containment temperature, drywell pressure, or suppression pool water level, is Ks 4 cbove its high operating limit or suppression pool water level is below its low operating limit. The Secondary Containment Control Guideline protects equipment in the secondary containment, limits radioactivity release to the secondary containment, and either maintains secondary containment integrity or limits radioactivity release from the secondary containment. This guideline is cntered whenever a secondary containment temperature, radiation level, or water level is above its maximum normal operating value or secondary containment differential pressure reaches zero. The Radioactivity Release Control Guideline limits radioactivity release into areas outside the primary and secondary containments. This guideline is entered whenever offsite radioactivity release rate is above that which requirc.s an Alert. l The entry conditions for these e:nergency procedure guidelines are symptomatic L of both emergencies and events which may degrade into emergencies. The ! guidelines'specify actions appropriate for both. Therefore, entry into procedures developed from these guidelines is not conclusive that an emergency has occurred.
, . Emergsney Procsdure Guida11nts Table I is a list of the abbreviations used in the guidelines.
Brackets [ ] enclose plant unique setpoints, design limits, pump shutoff pressures, etc., and parentheses ( ) within brackets indicate the source for the bracketed variable. Illustrated in these guidelines are variables for a typical BWR/4 or BWR/6 as appropriate. At various points throughout these guidelines, precautions are noted by the symbol: 5 The number within the box refers to a numbered " Caution" contained in the Operators Precautions section. These " Cautions" are brief and succinct red
- flags for the operator. The basis for each caution as well as for every step i is provided in Appendix B.
The emergency. procedure guidelines are generic to GE-BWR 1 through 6 designs in that they address all major systems which may be used to respond to an emergency. Because no specific plant includes all of the systems in these guidelines, the guidelines are applied to individual plants by deleting statements which are not applicable or by substituting equivalent systems where appropriate. For example, plants with no low pressure injection system will delete statements referring to LPCI, and plants with Low Pressure Core Flooding will substitute LPCF for LPCI. At various points within these guidelines, limits are specified beyond which certain actions are required. While conservative, these limits are derived from engineering analyses utilizing best-estimate (as opposed to licensing) models. Consequently, these limits are not as conservative as the limits specified in a plant's Technical Specifications. This is not to imply that operation beyond the Technical Specifications is recommended in an emergency. Rather, such operation may be required under certain degraded conditions in order to safely mitigate the consequences of those degraded conditions. The j - limits specified in the guidelines establish the boundaries within which i- continued safe operation of the plant can be assured. Therefore, conformance with the guidelines does not ensure strict conformance with a plant's Technical Specifications or other licensing bases. I l L em-- - --,-m e ,- -ne, , -- --,--+,na-- ,w.-e ..-g-.m ~, ,-.-,----,,,m__, e,-- - _ , r-,-,.w.,re,.v,ewae.vn, on-,,-n,,v,.e--w
1 Emergency Procedure Guidelines TABLE I EPG ABBREVIATIONS ADS - Automatic Depressurization System APRM - Average Power Range Monitor CRD - Control Rod Drive
' ECCS -
Emercency Core Colling System HCU - Hydraulic Control Unit M=CI - Mig 5 " :::ure C !:nt Injecti r HPCS - High Pressure Core Spray HVAC - Heating, Ventilating 'and Air Conditioning 10 !;;!; tier Cond:n;;r LCO - Limiting Condition for Operation LOCA - Loss of Collant Accident LPCI - Low Pressure Coolant Injection LPCS - Low Pressure Core Spray MSIV - Main Steamline Isolation Valves NDTT - Nil-Ductility Transition Temperature NPSH - Net Positive Suction Head RCIC - Reactor Core Isolation Cooling RHR - Residual Heat Removal RPS - Reactor Protection System RPV - Reactor Pressure Vessel RSCS. - Rod Sequence Control System RWCU - Reactor Water Cleanup SBGT - Standby Gas Treatment I-4 L
c
, Emergency Procedure Guidelines i
TABLE I(continued) SLC - Standby Li quid Control SORV - Stuck Open Relief Valve GF;;; Eper ::icr *::1 " Erup 9/str-
'SRV - Safety Relief Valve ,
9 O O O e
!-5
.,y---,- ---,w ,g-. , v..m,--,,, .-,....-..,,,,,,-,--cmn,
i l Emergency Procedure Guidelines OPERATOR PRECAUTIONS GENERAL l This section lists " Cautions" which are generally applicable at l c11 times. CAUTION #1 !
! Monitor the general state of the plant. If an entry I l condition for a Cprocedure developed from the Emergency i I Procedure Guidelines 3 occurs, enter that procedure. enter When !
I it is determined that an emergency no longer exists, I
! Enormal operating procedure 3. I
_______________________________________________________________ ~ CAUTION #2 l
! Monitor RPV water level and pressure and primary containment I
! temperatures and pressure from multiple indications. l l CAUTION #3 1 1 If a safety function initiates automatically, assume a true !
I initiating event has occurred unless otherwise confirmed by ! I at least two independent indications. I
! CAUTION #4 I t Whenever RHR is in the LPCI mode, inject through the heat !
I exchangers as soon as possible. t l CAUTION #5 i
! Suppression pool temperature is determined by Cprocedure f or i
! determining bulk suppression pool water temperature 3. t t Drywell temperature is determined by Cprocedure for !
I determining drywell atmosphere average temperature 3. I
! 0;nteir;;nt t: p retur: i: det:rtin d by Sprc :dar; fer I gx gI l Ceter-ining Merk !!! centeinnent e t.; ; ; p h e r e e,ece;. Iog
! t e.wp e c eim 0 .- . I I-6
Emergency Procedure Guidelines - i i l l CAUTION #6 1
!'Whenever Ctemperature near the instrument reference leg I I vertical runs 3 exceeds the temperature in the table and the !
I instrument reads below the indicated leve,1 in the table, the ! I actual RPV water level may'be anywhere below the elevation of I I the lower instrument tap. !
' I I Indicated See Atiackel
! Temocrature Level Instrument !
I I Cany 617 in. Shutdown Range Level ( 500 t in.)3 I I I l C107-F -107 in. de Range Leve (-150 to +60 in.)3 I i !
. I C310*F 19 in. Nar ang vel ( O to +60 in.)3 1 1
; C545*F in.' Fuel Zone Level (
500 in.)3 I g
, g i at in order of increasing temperature.'3 ~4 I Cheated referen instrument 3 in evels are not t i reliable _ during rapid RP rization below 500 psig. I I For- these ns, utilize oference leg i
! ins to monitor RPV water level. !
Rested c.bewee \ep not (wshWA., i s 9 14
/
0 e 1-7
/
. -,-...--.----m.--,_-_,.
.1 - ,
s e CAUTI010
- 6 !
Tfp)pfRA7t)ff INDICA 76D L f V f L. L EVfL IN3 7R u m ftvT ANY I4b in U-I SuurDowN RANGE aNy iso in 0-2.SHUTDow!v ARIUGE_ l80' l '?S in U-/ UPSE T RANGE j go* J g o in U-2 UPSET R A AJS E T .W r
Emergency Procedure Guidelines B CAUTION #8 I l NPSH requirements for pumps taking suction from t I I serve ression pool . I i su I I I 10 psig* I l I l................ I l . I I 240 + 5 psig . I I t................ I I I . I I Suppe sion t................ . I I Pool 220 + 0 psig I t . Temperatu e i . I I I (*F) ! ! I I I 2 + RHR NPS imit ! I *
- I I
g __+___ ___+___+___+..__ g 1 2 4 6 8 10 1
- 1. RHR mp Flow (X1000 gpm) i t
I I 10 p ig* I I
! i......... ........
I 2 + 5 psig . I I l............ ..... Suppress ~on : O psig : Poo 220 +................ . t
- Tempe ature . .
F) ! I 1
- I 200 + !
1 g 4 ____+-____+_____+_____ :
! 2 4 6 ! ! LPCS Fump Flow (X1000 gpm) I I
t I l
- uppression chamber pressure
! Suppression pool at normal water level I I-8
J h Emergency Procedure Guidelines f
! CAUTION #9 - + 3 m. I t If signals of high suppression pool water level C-tB-+2. 7 in. !
i (high level suctig interlock)3 or low condensate storage tank water level [4- N.*(low level suction interlock)3 accur, I I
- confirm automatic transfer of or manually transfe- lFC:, !
I HPCS, and RCIC suction from the condensate storage tank to i I the suppression pool. I SPECIFIC This section lists " Cautions" which are applicable at one or more cpecific points within the guidelines. Where a " Caution" is cpplicable, it is identified with the symbol I # t. t CAUTION #10 t
- Do not secure or place an ECCS in MANUAL mode unless, by at t
- least two independent indications, (1) misoperation in :
* - l AUTOMATIC mode is confirmed, or (2) adequate core cooling is !
l assured. If an ECCS is placed in MANUAL mode, it will not ! I initiate automatically.
- CAUTION #11 gg :
If a high drywell pressure ECCS initiation signal [Gre p si g :
- (drywell pressure which initiates ECCS)3 occurs or exists :
while depressuri-ing, prevent injection from those LPCS and :
! LPCI pumps not required to assure adequate core cooling prior :
- to reaching their maximum injection pressures.
l CAUTION #12 4 100 I Do not throttle HPG4- -e* RC IC turbine 4 below [GGM rpm
- (minimum turbine speed limit per turbine vendor manual)3.
! CAUTION #13
_Cooldown rates above [100*F/hr (RPV cooldown rate LCO)3 may :!
! be required to accomplish this step.
I-9
Emergency Procedure Guidelines t CAUTION #14 37 i
- Do not depressurize the RPV below C+00 psig (MF I ,c RCIC low I I pressure i solation setpoint, '
-.ich ver i : high;r)3 unless !
I motor dr iven pumps suf ficient to maintain RPV water level are ! I running and available for injection. I t CAUTION #15 l I Open SRVs in the following sequence if possible: [SRV i i opening sequence 3. I t CAUTION #16 I I Bypassing low RPV water level Eventilation system and3 MSIV t i isolation interlocks may be required to accomplish this step. l
! CAUTION #17 I l Cooldown rates above C100*F/hr (RPV cooldown rate LCO)3 may I
- be required to conserve RPV water inventory, protect primary I
- containment integrity, or limit radioactive release to the I i environment. -l
'r -
- CAUTION #1e :
! If- continuous LPCI operation of any RHR pump is required to I I assure adequate core cooling, do not divert that pump from t .
I the LPCI mode. t
! Me Aoto Teip, CAUTION #19 3d t I Cr 21-- -"+---Hc +Ha e- manually trip SLC pumps at COX (low I I level trip)3 in the SLC tank. .
I CAUTION #20 t i Defeating RSCS interlocks may be required to accomplish this t 1 step. I-10
- ,, -n- - - . . - - - - - - ----- ..- - - - - - - - -,,--e- ----~n,- --- .,-,.se-,,.,,-men..---.. -
[-- Emergency Procedure Guidelines t CAUTION #21 1 1 Elevated suppression chamber pressure may trip the RCIC 1
! turbine on high exhaust pressure. I
! CAUTION #22 i
! Defeating isolation interlocks may be required to accomplish !
I this step. I ________________________ tits _ sued ______________________________ l CAUTION #23 1
! Do not initia ell sprays if ton pool water I i level is above C17 ft. 2 vation of bottom of Mark I !
! internal sup r c amber to drywe breakers less !
aker opening pressure in feet of water) . t
! va
! CAUTION #24 :
i Bypassing high dryw' ell pressure and low RPV water level !
! secondary containment HVAC isolation interlocks may be t I required to accomplish this step. I
- CAUTION e25 -
! A rapid increase in injection into the RPV may induce a large !
! power excursion and result in substantial core damage.
- CAUTION #26 :
Large reactor power oscillations may be observed while :
- executing this step.
l i N r-21
Emergency Procedure Guidelines RPV CONTROL GUIDELINE PyRPOSE
-The purpose of this guideline is to:
o Maintain adequate core cooling, o Shut down the reactor, and 30 o Cool down the RPV to ld shutdown conditions (C+66*F < RPV water temperature < *F (cold shutdown conditions) 3) .
- ENTRY CONDITIONS The. entry conditions for this. guideline are any of the following:
Q.S o RPV water level below C+ i1 bin. (low l evel scram setpoint)3 no43 o RPV pressure above Ete+5 psig (high RPV pressure scram setpoint)3 t.69 o Drywell pressure above C9re psig (high drywell pressure scram setpoint)3 o A condition which requ1res reactor scram, and reactor power above C7% (APRM downscale trip)3 or cannot be determined 5*h OPERATOR ACTIONS 4 RC-1 If reactor scram has not been initiated, initiate reactor scram. of the entry conditions, execute CSteps RC/L, i
.: Irrespective l
- RC/P, and RC/03 concurrently.
RC-1
- ~- ~ , . - , - ..--,,-e
- n + , , - - - - - e. - - . - - , , , - . - - , . - - ~ - , - - - . - - - - - - - - , . - , - , , , , .-----,r- - - - - , , - - - , - - , , , . - - - , , , - , - - - .
Emergency Procedure Guidelines RC/L Monitor and control RPV water level. RC/L-1 Initiate each of the following which should have ((( initiated but did not: [,, o Isolation o ECCS Co Emergency diesel generator 3 i l If while executing the f ollowing step: ! i i t o Boron Injection is required or boron has been 1 enter Cprocedure developed I s
- injected into the RPV, I
I from CONTINGENCY #73. I i , I o RPV water level cannot be determined, RPV FLOODING I I IS REQUIREDI enter Cprocedure developed from i 1
! CONTINGENCY '#63.
I I
! o RPV Flooding is required, enter (procedure t developed from CONTINGENCY #63. I "I
RC/L-2 Restore and intain RPV water level between C+ i n.g(} ow level scram I #9 i setpoint)3 and C+ w in. (high level trip I #10 i setpoint)3 with one or more of the ! #11 i following systems: soTu o Condensate /feedwater system C+tte - O psig (RPV pressure range for system operation)3 so14 o~ CRD system C&444 - O psig (RPV pressure range for system operation)3 o RCIC system th 0-59 psig (RPV I #12 I pressure range for system operation)3 ----- 100 pri; '**" ; reeu e o ::^C: ;7;t;; l1110 ) range for system operation)3 ; 1014 o HPCS system C6444 - O psig (RPV pressure range i for system operation)3 qqo o LPCS system C+BE - O psig (RPV pressure range for system operation)3 I RC-2
1 Emergency Procedure Guidelines 2 40 o LPCI system CG66 - O psig (RPV pressure range for system operation)3 l If RPV water level c maintained above C+ d,qqnot be restored in. (low and level scram gy setpoint)3, maintain RPV water level above C-b64 in. (top of active fuel)3.
\bl If RPV water level can be maintained above C-F64 in. (top of active fuel)3 and the ADS timer has initiated, prevent automatic RPV depressurization by resetting the ADS timer.
l If gyRPV water level cannot be maintained above i I C-b64 in. (top of active fuel)3, enter Cprocedure I
! developed f rom CONTINGENCY #13. I
____________u______________________________________ t If Alternate Shutdown Colling is required, enter I I (procedure developed from CONTINGENCY #5.3 ! RC/L-3 When [ procedure for cooldown to cold shutdown conditions 3 is entered from CStep RC/P-53, proceed to cold shutdown in accordance with Cprocedure for cooldown to cold
- shutdown conditions 3.
RC-3
Emergency Procedure Guidelines RC/P Monitor and control RPV pressure. t*If while executing the following steps: I I I
. I o Emergency RPV Depressurization is ----- t I anticipated and Boron Injection is not I #13 I I I required, rapidly depressurize the RPV ----- 1 I with the main turbine bypass valves. I I I I o Emergency RPV Depressurization or RPV Flooding is !
I required and less than C7 (number of SRVs ! I dedicated to ADS)3 SRVs are open, enter Cprocedure ! I developed from CONTINGENCY #23. I t ! I o RPV Flooding is required and at least C7 (number i i of SRVs dedicated to ADS)3 SRVs are open, enter i Cprocedure developed from CONTINGENCY #63. I RC/P-1 If any SRV is cycling, initiete :C end man gily open SRVs until RPV pressure drops to C955 lsig (RPV pressure at which all turbine bypass valves are fully open)3. I 1 l I 1 RC-4
Emergency Procedure Guidelines t If while executing the following steps: I g Suppression pool l temperature cannot be ! -*S-t i l' o I maintained below the Heat Capacity I #13 I t
- t Temperature Limit, maintain RPV pressure t #14 I I I below the Limit. See A ttadsel ----- 'I t
197 + . I I
! . I I
188 + I i . Sup esion I . I I Poo I . t I Temperatur 60 + . I I ("F) eat . I I
. apacity . I I
t T erature . I I 122 + Limit . I I
- I I I
! 0 +----+----+------ -+--- I -
t 0 135 240 to t RPV Pressure (psig) ! i t t t I o Suppression pool water level cannot be ----- ! I maintained below the Suppression Pool Load ! #13 I I I Limit, maintain RPV pressure below the ! #14 I I
----- t the Limit. 5.. A u d .J
' "O + . t
! I
! I i .
! t i Suppres ' n i t i .
Pool ! ! I Water . ! I Level I ression i I (ft.) Poo ad . I
.I Limit I t . I t, --+--
i 12.5 +---------+------- 1 I O 400 0 t RPV Pressure (psig) I t I o Steam Cooling is required, enter [ procedure ! I developed from CONTINGENCY #33. I r _________________________________________________________ RC.5
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Emergency Procedure Guidelines t If while executing the following steps: I I I Boron Injection is required, and ! Io I r I The main condenser is available, and i I o I I to There has been no indication of gross fuel f ailure I i or steam line break, I t _____ g i open MSIVs to re-establish the main condenser I #16 I I
! as a heat sink.
1074 RC/P-2 Control RPV pressure below Et999 psig ----- (lowest SRV lifting pressure)3 with the t #14 I main turbine bypass valves. RPV pressure control may be augmented by one'or - more of the following systems:
; lC-o SRVs only when suppression pool water level is above W ft. 9-++. (elevation of top of SRV discharge device)3. If the ! #15 I continuous SRV pneumatic supply is or g becomes unavailable, place the control switch I
for each SRV in the CG699E3 position. AUTO _____ e ;TC; I #12 1 o RCIC o tother steam driven equipment) o RWCU (recircul ation mode) if no boron has been injected into the RPV. o Main steam line drains
. o RWCU (blowdown mode) if no boron has been injected into the RPV. Refer to tsampling procedures 3 prior to initiating blowdown.
RC,-b
~-
Emergency Procedure Guidelines while executing the following steps the reactor is ! l If I not shutdown, return to CStep RC/P-23. I RC/P-3 When either: o All control rods are inserted to or beyond g position CO6 (maximum subcritical banked withdrawal position)3, or 3o35p;_r.d;-(Cold
%\ Wome o C200 Shutdown Boron W.;W ,d 3 of boron have been injected into the RPV, or o The reactor is shutdown and no boron has been . injected into the RPV, _____
depressurize the RPV and maintain cooldown I #14 i rate below C100*F/hr (RPV cooldown rate 'l #17 1 LCO)3. If one or more SRVs are being used to depressurize the RPV and the continuous SRV pneumatic supply is or becomes unavailable, depressurize with sustained SRV opening. I RC/P-4 Wher the RHR shutdown cooling interlocks clear, initiate the shutdown cooling mode ! #18 1 of RHR. If the RHR shutdown cooling mode cannot be established and further cocidown is required, continue to cool down using one or more of the systems used f or depressurization. t If RPV cocidown is required but cannot be I t accomplished and all control rods are inserted to i I or beyond position CO6 (maximum suberitical ! I bani:ed wi thdrawl position)3, ALTERNATE SHUTDOWN t
- I COOLING IS REQUIREDI enter (procedure developed I I
I from CONTINGENCY #5.3. RC/P-5 Proceed to cold shutdown in accordance with l pre :d_r fer :::!d:x- t: Orld sh ut d ::--
;;r.d i t i er.; 2. L.(s P 2-1 NORM AL Uru tT S hu7 bow o RC-7
Emergency Procedure Guidelines f RC/Q Monitor and control reactor power.
! If while executing the following steps: I o All control rods are inserted to or beyond position g I CO6 (maximum subcritical banked withdrawal !
I position)3, terminate boron injection and enter I
! Cscram procedure 3.
- I l t I I o The reactor is shutdown and no boron has been i I injected into the RPV, enter Cscram procedure 3. I RC/Q-1 CConfirm or place the reactor mode switch in
. SHUTDOWN.3 RC/Q-2 If the main turbine-generator is on-line Cand the MSIVs are open3, confirm or inititate recirculation flow runback to minimum. RC/Q-3 If reactor power is above [f% (APRM downscale trip)3 or cannot be determined, trip the recirculation pumps.
! Execute CSteps RC/Q-4 and RC/Q-53 concurrently. I G
t RC-8
Emergency Procedure Guidelines RC/Q-4 If the reactor cannot be shutdown before UO, # suppression pool temperature reaches Cthe ----- I/ Baron Injection Initiation Temperature 3, I #19 I [TL BORON INJECTION IS REQUIREDI inject boron ----- into the RPV with SLC and prevent automatic initiation of ADS. l . I Boron i 130 + Injection I t...... Initiati i Suppression i . Tem ture i Pool 12 . I Temperature t . I (*F) ! . I 110 ......... ! i ! I i 100 +---+---+---+---+---+-- ! O 1 2 3 4 5 6 1 Reactor Power (%) t If boron cannot be injected with SLC, inject boron into the RPV by one or more of the following alternate methods: Co CRD 3 Co HPCS 3 Co RWCU 3 Lo Feedwater 3 4; .;- ; 3 Lo RCIC 3 Co Hydro pump 3 RC/Q-4.1 If boron is not being injected into the RPV by RWCU, confirm automatic isolation of or manually isolate RWCU. RC/Q-4.2 Continue to inject boron until C p-"ad= (Cold Shutdown Boron Weight)3 of boron have been injected into the RPV. RC/Q-4.3 Enter tscram procedure 3. RC-9 ___.,-..-_r.__,m-.,,__ _ , .,__.,_,,._m,. .--_-....,..,---,-...,_,~.,_,.,___y .._. - . . _ _ _ _ , , _ ,
Emergency Procedure Guidelines a RC/Q-5 Insert control rods as follows: RC/Q-5.1 If any scram valve is not open: o CRemove:
}H H11-P609 C71-F)4!rA, E C, G, H11-P611 C71-F B,F D,H Guses errtn Q.sk de-energize RPS scram solenoids)3.
C Lo3 F (a)I A 2cf- Su am Air _
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baJe< &epl y Np ad RFmoV6 2. " I,I,. '. .,f '."__ ,.' . _ G. __ Z...
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the Se. cam Me b.A*< Supply i;;r ar, ;ir h;;dar .;,,t v;1v;;2. - (. w e v- i(ycu-Doo6 When control rods.are not moving inward: o CReplace: H11-P609 C71-F18A,E C.G
'H11-P611 C71-F18B,F,D.H wh;ch (f uses wegh de-energize RPS scram solenoids)3.
IsosTAtt *be 3cce Aie. haAev c O!::: EC11 "^^" '::r:r cir 5::d:r i 5.pp)3 AWr 1(p)c 4 boof. awel. V^t ValV 32 :Fd ?OF E Cl INE 0; ; ~ ';- t ;"P P I^/ 09su s(s) r n ach Scram Aw- - Y.f. r #'?.#iI v., .. hsker3pph5kog. RC/O-5.2 Reset the reactor scram.
. s.<
If the reactor scram cannot be reset:
- 1. Start all CP.D pumps.
If no CRD pump can be started, continue in this procedure at [ Step RC/Q-5.6.13.
- 2. Close CC11-F034 (HCU accumulator charging water header valve)3.
t
- 3. Rapidly i nsert control rods manually until the reactor l #20 l l -----
scram can be reset. l i RC-10
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Emergency Procedure Guidelines s
- 4. Reset the reactor scram.
- 5. Open CC11-F034 (HCU accumulator charging water header valve)3.
RC/Q-5.3 Drain the scram discharge volume and , initiate a manual reactor scram.
- 1. If control rods moved inward, return to CStep RC/Q-5.23.
- 2. Reset the reactor scram.
If the reactor scram cannot be reset, continue in this procedure at CStep RC/Q-5.5.13.
~
- 3. Open the scram discharge volume vent and drain valves.
RC/Q-5.4 Individually open the scram test switches for control rods not inserted to or beyond position CO6 (maximum subcritical banked withdrawl position)3. When a control rod is not moving inward, close its scram test switch. . RC/O-5.5 Reset the reactor scram. If the reactor scram cannot be reset:
- 1. Start all CRD pumps.
If no CRD pump can be started, continue in this procedure at CStep RC/Q-5.6.13.
- 2. Close CC11-F034 (HCU accumulator charging water header valve)3.
RC-11 1
Emergency Procedur e Guidelines RC/Q-5.6 Rapidly insert control rods manually until all control rods are inserted to or beyond position I #20 1 CO6 (maximum subcritical banked ----- withdrawal position)3. If any control rod cannot be inserted to or beyond position CO6 (maximum suberitical banked withdrawl position)3:
- 1. Individually direct the s' Iuent from CC11-F102 (CRD withdraw line vent valve)3 to a contained radwaste drain and open CC11-F102 (CRD withdraw line vent valve)3 for each control rod not inserted to or beyond position CO6 (maximum subcritical banked withdrawal posi ti on) 3.
- 2. When a control rod is not moving .
inward, close its CC11-F102 (CRD withdraw line vent valve)3. e RC-12
- -- e s ----y- --- -- ew, , , , - - - - , ~ - , , r ,, ,-,, ,-- , --me- r --w - ,
Emergency Procedure Guidelines PRIMARY CONTAINMENT CONTROL GUIDELINE PURPOSE . The purpese of this guideline is to: o Maintain primary containment integrity, and a Protect equipment in the primary containment. ENTRY CONDITIONS The entry conditions f or this guideline are" any of the following:
\so o Suppression pool temperature above C45aF (most limiting' suppression pool temperature LCO)3 o Drywell temperature above C135*F (drywell temperature LCO or maximum normal operating temperature, whichever is higher)3 D2 e Cent ir; nt t; per:tur; ;b;v; :?O-F ' cant;;r;;nt t;,;p a r ;t ur :
11 LCC;3 ' e 1.68 Drywell pressure above [ Gee psig (htgh drywell pressure ! o scram setpoint)3 l + 3 66. o Suppression pool water level above [12 't. i in. (maximum suppression pool water level LCO)3 _4 5 in o Suppression pool water level below [12 't. 2 in. (minimum suppression pool water level LCO)3 l OPERATOR ACTIONS of the entry condi ti on. e>: ecu t e CSteps SP/T, Irrespective l l- DW/T. 45W9*, PC/P. SP/L,goncurrently. : : l PC-1 [ i
Emergency Procedure Guidelines r-SP/T Monitor and control suppression pool temperature. SP/T-1 C1cse all SORVs. If any SORV cannot be closed Cwithin 2 minutes (optional plant-specific time interval) 3, scram the reactor. SP/T-2 W gn suppression pool temperature exceeds i #18 I E M*F (most limiting suppression pool temperature LCO)3, operate available suppression pool cooling. Ilo*f SP/T-3 Before suppression pool temperature reaches [the Baron Injection Initiation Temperature 3, scram the reactor. ,
. I I I ", Boron i 130 + Injectio I Initfi on 1...... :
T perature ! Suppress I . Pool + 1 1 Temperature . .
! . I
("F)
+ ......... !
1
-+ 4 100 +---+---+---+---+---+
0 1 2 3 4 5 6 : Reacto:' Power (%) : O PC-2
l Emergency Procedure Guidelines l i I SP/T-4 If suppression pool temperature cannot be maintained below the Heat Capacity Temperature Limit, maintain RPV pressure i 1F4> ! below the Limitt enter Cprocedure developed I #13 I from the RPV Control Guideline 3 at [ Step i #14 1 RC-11 and execute it concurrently with this ----- I procedure. 3,, g g4, g,4 1 . J97 + . 188 + . Suppresio I , Pool ! . Temperature 16 . (*F) i eat . t Ca ity . I Tempe ure . 122 + Li mi t . I O +----+----+-------- --- 0 135 240 1090 RPV Pressure (psig) b If suppression pool temperature and RPV pressure
~
cannot be restored and maintained below the Heat Capacity Temperature Limit, EMERGENCY RPV . DEPRESSURIZATION IS REQUIRED. l 6 PC-3
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Emergency Procedure Guidelines DW/T Monitor and control drywell temperature. 3 ---- DW/T-1 When drywell temperature exceeds C135=F (drywell temperature LCO or maximum normal I #6 1 operating temperature, whichever is higher)3, ----
. operate available drywell cooling.
! Execute CSteps DW/T-2 and DW/T-33 concurrently. l DW/T-2 If drywell temperature En r th: :01d :fer:n::
Cup swd.<aths 3 ; gneg7=,eng ./ Or t i : 21 u-53 reaches the RPV
#'"T I * "" ^ ** " S Saturation Temperature, RPV FLOODING IS REQUIREDI wet twswu,k - enter.Cprocedure developed from the RPV Control Guideline 3 at CStep RC-13 and execute it concurrently with this procedure. Sea A \ ladhe1-I 550 + .
t . Temper ce ! . (*F) i . Enear cold ! . reference . . leg : instrument . . V Saturation vertical ! . T erature
- runs] :
217 +---__----_----------- 0 1000 RPV Pressure (psig) l I PC-4 i l l
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Emergency Frocedure Guidelines DW/T-3 Before drywell temperature reaches C340"F (maximum temperature at'which ADS qualified or drywell design temperature, whichever is l'ower)3 but only if Csuppression chamber temperature and drywell pressure are below the Drywell I ele i Spray Initiation Pressure Limit 3, Cshut ----- down recirculation pumps and drywell cooling fans and3 initiate drywell spr ays. C r ectr i c t i r.; f!: _ et: Cded*b'** CI ' E2P t 1:0 ther 720 ;; '9;x imum Ory ;11 Oprey Flow
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I O +----+----+----+----+--- 0 10 20 30 40 Drywell Pressure (psig) If drywell temperature cannot be maintained below C340=F (maximum temperature at which ADS qualifted . or drywell design temperature, whichever is lower)3, EMERGENCY RPV DEPRESSURIZATION IS I REQUIRED; enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC-13 and execute it concurrently with this procedure. 1 PC-5
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-M K TTT o " 9' l N/T Moni tor and contr.o1 containment temperature.
CN/T-1 When containment temperature exceeds C90=F --- r (containment temperature LCO) 3, operate I # I available containment cooling. - -- _________________________________________________ ____ i
! I owhile executing the following steps suppressic pool I
~
- sp ys have been initiated, when suppression . hamber i
- pre ure drops below 0 psig, terminate suppres on pool 1 i t w l1 spray . .
_______ _____________________________________ ___________ g CN/T-2 Bef re containment temperature reac s C185"F (con inment design temperature)3, ut only ----- if Cs pression chamber pressure 's above i #18 8 1.7 psi (Mark III Containment 5 ray ----- Initiati Pressure Limit)3, i tiate suppression pool spra . - CN/T-3 If containme temperature annot be maintained below C185"F ontainment esign temperatur,w)3, EMERGENCY RPV D PRESSURI TION IS REQUIREDI enter g' Cprocedure devel ed fr m the RPV Control' Guideline 3 at CSte R 13 and execute it concurfently with t procedure. CN/T-4 If containment tem era ure'Enear the cold reference - leg anstrument ve tical uns3 reaches the RPV Saturation Temp ature, V FLOODING IS REQUIRED. o 550 + . ~ L Tempe ature ! . ( F) En r cold : . r forence a .
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Emergency Procedure Guidelines PC/P Monitor and control primary containment pressure. PC/P-1 Operate Cthe following systems, as required: o Containment pressure control systems. Use containment pressure control system operating procedure.3 Co3 SBST Cand drywell purge 3, only when the temperature in the space being ----- evacuated is below C212"F (Maximum : #21 : Noncondensible Evacuation ----- Temperature)3. Use CSBGT and drywell purge operating proc =dures3.
, t _______________________________________________________ 3 :
C : If while executing the following steps suppr essi on : 3 C : pool sprays have been initiated,, when suppress, ion : 3 C : chamber pressure drops below O psig, terminate : 3 C suppression pool sprays. : 3 :
> C ------------------------------------------------------- 3 :
PC/P-2 Before suppressicn chamber pressure reaches Cthe
$. Agtm.ck.1 Pressure Suppression Pressure 3 C 17. ' p ri; st.s psig (Suppression Chamber Spray Initiation -----
Pressure >3, but enly t' t rup p r e::i cr 4F4F-: 52 pres ure i: Ob:v: 1.7 peig i #18 :
- C;ec k ::1 Ceateinment Opre7 Initiation -----
Freesure Limit!3 C suppres si on pool water level is below g dr-ftr. (elevation of suppression pool . spray no::g.g)3, mes initiate suppression pool sprays. e PC-7 _ _._.. . _ . _ _ _ _ . . . . . _ _ _ . ~ _
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Emergency Procedure Guidelines i PC/P-3 If suppression chamber pressure exceeds C 4 psig (Suppression Chamber Spray Initiation Pressure)3, but only if Csuppression chamber temperature and 5e a drywell pressure are below the Drywell ----- Attamkek Spray Initiation Pressure Limit 3, Eshut #18 I down recirculation pumps and drywell ----- cooling fans and3 initiate drywell sprays, Cr;;tricting fisw ret; t; 1;;; then 720 sp: 34 pc edc hte w ct , , g ,
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Suppression ' Chamber 200 + .. Temperature t . ("F t. 100 + 1 O +----+----+----+----+---- 0 10 20 30 40 Drywell Pressure (psig) PC/P-4 If suppression chamber pressure cannot be maintained below (the Pressure Suppression Pressure], EMERGENCY RPV DEPRESSURIZATION IS - REQUIRED. See A L Euck eck 1 56.0 + l Suppe sion : Chambe 42.5 + . Pressure- : . .
- (psig) 34.8 . ............
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