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 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, Ks containment temperature, drywell pressure, or suppression pool water level, is cbove its high operating limit or suppression pool water level is below its 4 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 continued safe operation of the plant can be assured. Therefore, conformance i-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 Automatic Depressurization System ADS Average Power Range Monitor APRM CRD Control Rod Drive ' ECCS Emercency Core Colling System Hydraulic Control Unit HCU M=CI Mig 5 " :::ure C !:nt Injecti r High Pressure Core Spray HPCS Heating, Ventilating 'and Air Conditioning HVAC 10 !;;!; tier Cond:n;;r LCO Limiting Condition for Operation Loss of Collant Accident LOCA Low Pressure Coolant Injection LPCI Low Pressure Core Spray LPCS Main Steamline Isolation Valves MSIV NDTT Nil-Ductility Transition Temperature Net Positive Suction Head NPSH RCIC Reactor Core Isolation Cooling RHR Residual Heat Removal Reactor Protection System RPS Reactor Pressure Vessel RPV Rod Sequence Control System RSCS. Reactor Water Cleanup RWCU Standby Gas Treatment SBGT I-4 L
c , Emergency Procedure Guidelines i TABLE I(continued) Standby Li quid Control SLC Stuck Open Relief Valve SORV GF;;; Eper ::icr *::1 " Erup 9/str-Safety Relief Valve 'SRV 9 O O O e !-5 .,y---,- ---,w ,g-. 4 v..m,--,,, .-,....-..,,,,,,-,--cmn, w,- www,,,,-,,,,,n,,-... - - -,, ,..n...m-.nm,-,- r.-~a,.c. ,,n...~,,
i Emergency Procedure Guidelines OPERATOR PRECAUTIONS GENERAL This section lists " Cautions" which are generally applicable at 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.
When ! I it is determined that an emergency no longer
- exists, enter I I
! Enormal operating procedure 3. 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 See Atiackel I Indicated ! 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 I 4 b 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 l CAUTION #8 I I serve NPSH requirements for pumps taking suction from t I I i su ression pool. I I I l 10 psig* I I l................ I I l I I 240 + 5 psig I I t................ I I I I I Suppe sion t................ I t Pool 220 + 0 psig I I Temperatu e i I I (*F) I I I I 2 + RHR NPS imit I I __+___ ___+___+___+..__ g g 2 4 6 8 10 1 1 1. RHR mp Flow (X1000 gpm) i t I I I 10 p ig* I i................. I 2 + 5 psig I I l............ Suppress ~on O psig Poo 220 +................ t Tempe ature 1 F) I I 1 200 + 4 ____+-____+_____+_____ g 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. ! (high level suctig interlock)3 or low condensate storage I i tank water level [4-N.*(low level suction interlock)3 accur, 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.
I l CAUTION #12 4 100 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 i t CAUTION #14 37
- 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 ! are ! I motor dr iven pumps suf ficient to maintain RPV water level 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 t I the LPCI mode. ! 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-
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[-- Emergency Procedure Guidelines t CAUTION #21 1 1 Elevated suppression chamber pressure may trip the RCIC 1 I ! turbine on high exhaust pressure. CAUTION #22 i ! Defeating isolation interlocks may be required to accomplish ! I I this step. ________________________ 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 ! ! va aker opening pressure in feet of water) t 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: Maintain adequate core cooling, o 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 RPV water level below C+ i1 bin. (low l evel scram setpoint)3 o 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. __________--_--_---___------__---__-__--------_-___---__ RC/L, .: Irrespective of the entry conditions, execute CSteps i 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 injected into the RPV, enter Cprocedure developed I s 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 CONTINGENCY '#63. 1 I I ! o RPV Flooding is
- required, enter (procedure t "I
developed from CONTINGENCY #63. 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 th 0-59 psig (RPV I #12 I o RCIC system pressure range for system operation)3 o
- ^C: ;7;t;; l1110 100 pri;
- reeu e
) 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 RC-2
1 Emergency Procedure Guidelines 2 40 o LPCI system CG66 - O psig (RPV pressure range for system operation)3 maintained above C+ d,qqnot be restored and If RPV water level c in. (low 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 RPV water level cannot be maintained above i gy 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 t I o Emergency RPV Depressurization is I anticipated and Boron Injection is not I #13 I I 1 I required, rapidly depressurize the RPV 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 ily g open SRVs until RPV pressure drops to C955 lsig (RPV pressure at which all turbine bypass valves are fully open)3. I 1 RC-4
Emergency Procedure Guidelines t If while executing the following steps: I g l' o Suppression pool l temperature cannot be -*S-t i I maintained below the Heat Capacity I #13 I t t Temperature Limit, maintain RPV pressure t #14 I I 'I I below the Limit. See A ttadsel t I 197 + I I I i 188 + I I Sup esion I I I Poo I t I Temperatur 60 + I I ("F) eat I apacity I I I t T erature I I 122 + Limit I I I I 0 +----+----+------ -+--- I t 0 135 240 to t i RPV Pressure (psig) 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 t "O + I i I t i i Suppres ' n i t I Pool 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 I t If while executing the following steps: I I Io Boron Injection is required, and I I I o The main condenser is available, and i I I to There has been no indication of gross fuel f ailure I i I t or steam line break, g I #16 I I i open MSIVs to re-establish the main condenser ! 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-SRVs only when suppression pool water level is o 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 I #12 1 e
- TC; o
RCIC tother steam driven equipment) o 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 l If while executing the following steps the reactor is ! 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 3o35 % \\ Wome C200 p;_r.d;-(Cold Shutdown Boron W.;W,d 3 of o 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 I SRV opening. 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 from CONTINGENCY #5.3. I 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 I l Cscram procedure 3. 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, I/# suppression pool temperature reaches Cthe 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 Q.sk Guses errtn de-energize RPS scram solenoids)3. C Lo3 F (a)I A 2cf-Su am Air a, baJe< &epl Np ad RFmoV6
- 2. " I,I,. '..,f '."__,.'. _ G. __ Z... ' '_ E. l. _. L.. i l ; ; A_ o_
y 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. c O!::: EC11 "^^" '::r:r cir 5::d:r i IsosTAtt *be 3cce Aie. haAev 5.pp)3 AWr 1(p)c 4 boof. awel. V^t ValV 32 :Fd ?OF E Cl INE I 0; ; ~ ';- t ;"P P ^/ 09su s(s) r n ach Scram Aw-Y.f. r #'?.#iI v., hsker3pph5kog. RC/O-5.2 Reset the reactor scram. If the reactor scram cannot be reset: . s.< 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. 3. Rapidly i nsert control rods t manually until the reactor l #20 l l scram can be reset. l i RC-10 .f' ,-e--, -, - - - - - - -, - -,, -, - - ----, ,w, -,---..,-,.-n, ,, - ~.,, - - - -, - -, - -. - - - - -
-a 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
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 OPERATOR ACTIONS Irrespective of the entry condi ti on. e>: ecu t e CSteps SP/T, 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 E M*F (most limiting suppression pool i #18 I 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 on 1...... Initfi Suppress I T perature 1 Pool + 1 Temperature ("F) I 1 + 100 +---+---+---+---+---+ -+ 4 0 1 2 3 4 5 6 Reacto:' Power (%) O PC-2
l Emergency Procedure Guidelines 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
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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 PC-4 i - 1
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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 Cded*b'** CI and3 initiate drywell spr ays. C r ectr i c t i r.; f!: _ et: E2P t 1:0 ther 720 ;; '9;x imum Ory ;11 Oprey Flow - Ret; Limit:3. Sea At 6b e d. 400 + t Drywell Spray i Initiation Pr sure 300 + Li Suppression Chamber 200 Temperature (*F) 1. 100 + 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 +y v --,.,.,,.v.,,.- ,_,m_,..,, __m, _,. _.,, _,..,, _ _ _
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s Emergency Procedure Guidelines \\ -M K TTT o " 9' N/T Moni tor and contr.o1 containment temperature. CN/T-1 When containment temperature exceeds C90=F (containment temperature LCO) 3, operate I # I r available containment cooling. i ! I owhile executing the following steps suppressic pool I
- sp ys have been initiated, when suppression. hamber i
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i w 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.
550 + ~ o L Tempe ature ( F) En r cold r forence a leg instrument RPV Satura ion vertical .i Temperatu e runs 3 s 212 +---------------------+ - L ( O ~ 100 RPV Pressure (psig) t I !2 PC-6 4 ~ ,4, ,,,,,,.a v, _,,,,,,,,,,,.amn, w wew. _.nn.,
l 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 :
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- psig, terminate : 3 C
suppression pool sprays.
- 3 3
C 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 , gg 400 + t Drywell Spray 1. Initiation Pressur 300 + Limit t 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 t I ssure Suppression essure O +----+---+------ 0 12.5 17 34.5 Primary Containment Wa Level (ft.) PC-8
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Emergency Procedure Guidelines o CIf suppression pool water level is below ipp 723 f t el. +4. b-bw..(elevation of suppression pool spray nozzles),3 initiate suppression pool sprays. o If Csuppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit 3, Eshut down recirculation pumps and drywell cooling fans and3 initiate drywell sprays tr;;trictir.g '!:e . Pa r C d c \\ A .% ce r t: t: 1 :: ther 72e gpr '":= i r.ur Dr,. :ri l Opce7 Tlea net: Limit)3. Se. All JLei 400 + t Drywell Spray i Initiation Press 300 + Limit t Suppression I Chamber 20 + Temperature (*F) 8. 00 + t t O +----+----+----+---- O to 20 30 40 Drywell Pressure (psig) N PC/P-7 If suppression chamber pr essure exceeds the Primary Containment Pressure Limit, vent the primary containment in accordance with
- #22 I
[ procedure for containment venting 3 to reduce and maintain pressure below the Primary Containment Pressure Limit. PC-10
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Emergency Procedure Guidelines L SP/L Monitor and control suppression pool water level. SP/L-1 Maintain suppression pool water level between C: 't?#E'ir.. (maximum suppression pool water level LCO)3 and C;; ft. 2 i n. -4 3 '" I~#B-1 (minimum suppression pool water level LCO)3. t #9 I Refer to Esampling procedure 3 prior to discharoing water. 00.ppr;;;ien pac! c : k r u p : :,- 5 : ..____m..a m.,. _,...,.. _ 12 9*M9 'ee beer initiated, v. int in uppr;;;isa peel "ete-level betur:r (22 't. ? in. (OrMO M' KIII +itieti e -etprint p!== =gg.m.iun geel...c l#=#l
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end Ca? ft. 22 in. '.7,i n i as; suppre;; ice p::1.-::t er - -lev;1 LCO' L - If suppression pool water-4 t' evel cannot be m maintained above C12 ft. 0 :n. (minimum suppression pool water level LCO)3, execute CStep SP/L-23. level cannot be If suppression pool water,$ i. (maximum suppression 't. maintained below Ci pool water level LCO)3 M2! ft. ? in. 00rMO bkk}}}[ initicti:P ::t p ri nt plu: suppr;;;;;n p;;; u;t;r 1v1 in:P ::: _;5 i :P
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Or-C sp;r;ti;n : 1 O N Lj if EF95 5 : 5 :r ini._i di, execute CStep SP/L-33. l c l t PC-11 -"-.-.---e- -,_,m...w.. ,,.m.,_,.
Emergency Procedure Guidelines v -4.5 in SP/L-2 SUPPRESSION POOL WATER LEVEL BELOW C12 't. 2. a. (minimum suppresion pool water level LCO)3 Maintain suppression pool water level above the Heat Capacity Level Limit. S e e AE(udne l. t 12'2" +. Heat Capaci Level L' t t Suppression i Pool Water 8'2" + Level I (ft.) 1 I t +-----------+------ 0 27 Two ("F) Where Twc = Heat Capacity Temperature Limit minus suppression pool temperature If suppression pool water level cannot be maintained above the Heat Capacity Level Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: enter Cprocedure developed from the RPV Control Guideline] at CStep RC-13 and e>:ecute i t concurrently with this procedure. O PC-12
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w Emergency Procedure Guidelines t +3in. SP/L-3 SUPPRESSION POOL WATER LEVEL ABOVE C12 ft. in. (maximum suppression pool water level LCO)3 " i. f 5 MS initiatie-retpcint p!v= -tC2! 't. - supp-errie pr:1 = t:r 1;; 1 incre;;; which r;; ult; ' cr 5"MS Op:r; tion); if OPMC h;; beca 1..itiated! SP/L-3.23 1 SP/L-T 1 ...u I E>: ecut e COtep=~ l I c oM. 1 SP/L-3.1, Maintain suppression pool water level below the Suppression Pool Load Limit. See A WA.L. 20 + I ~ I I Suppress' Pool Water Lev i Sup smion t.) 1 Pool Lo Limit 12.5 +---------+-----------+- O 400 1200 RPV Pressure (psig) If suppression pool water level cannot be maintained below the ! #13 : Suppression Pool Load Limit,
- #14 :
maintain RPV pressure below the Limit. If suppression pool water level and RPV pressure cannot be maintained below the Suppression Pool' Lead Limit but only if adequate core cooling is assured, terminate injection into the RPV f rom sources external to the primary containment except f rom boron injection systems and CRD. i PC-13
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Emergency Procedure Guidelines If suppression pool water level and RPV pressure cannot be restored and maintained below the Suppression Pool Load Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIREDI enter (procedure developed from RPV Control Guideline 3 at CStep RC-13 and execute it concurrently with this procedure. L-3.2 Before suppression / pool water lev reaches C17 ft. 2 in. (Maximum rimary tainment Water Level Li or eleva ' n of bottom of k I internal pqg7 suppressio ut amber drywell vacuum breakers less v m breaker opening ' O N Lg pressure in fe of r, whichever is lower)3 but nly if adequ core cooling s is assur terminate injectio to the RPV m sources external to the pr c ainment except from boron injection sy' stems and CRD. O e f PC-14
w l Emergency Procedure Guidelines MkI o N CY 1. When suppression pool water level reaches C17 ft. 2 in. (elevation f bottom of Mark 1 internal suppre sion chamber to drywell vacuum break rs t 1ess vacuum breaker opening pr ssure in Feet of water)3 but only i (suppression chamber temperature and drywell I #18 l-pressure are below the Drywell* Spray Initiation ressure Limit 3, Eshut down reci culation pumps and drywell cool'ng fans and3 initiate drywell spr s Crestricting flow rate to less t n 720 gpm (Maximum Drywell S ay Flow Rate imit)3. 400 + - I Drywell Spray Initiation Pressure 300 Limit Suppression y Chamber + Temperature ("F) 100 + f 0 +---
+----+----+----
O 10 20 30 40 Drywel Pressure (psig) If suppression pool wat r level exceeds C17. ft. 2 in. ( levation of bottom of Mark I internal suppressi on chanber to drywell vacuum breakers less vacuum breake I #23 : opening oressure in feet of water)3, continue to operate ywell H sprays Ebelow 720 gpm (Maximum Drywell Spray Flow Rate Limit)3. PC-15
Emergency Procedure Guidelines U-1 LO A - C M
- O I 3.
When primary containment water level [1 4. maximum Nimary ) g._._"reachest:IanfiinkinT] Water Level U-t g to C t b in el. Limit)3, terminate injection into the RPV from sources external to the primary containment irrespective of whether adequate core cooling is assured. h i l s 9 4 i PC-16 i. .,.... _........ _ _. _, _ - - _ _ _. _. _. _ - _. -... _ - -,,, ~... _
7 Emergency Procedure Guidelines SECONDARY CONTAINMENT CONTROL GUIDELINE ~. PURPOSE The purpose of this guideline is to: -o Protect equipment in the secondary containment, G Limit radioactivity release to the secondary containment, and either: o Maintain secondary containment integrity, or o Limit radioactivity release from the secondary containment. ENTRY CONDITIONS The entry conditions for this guideline are any of the following secondary containment conditions: o Differential pressure at or above o in. of water An area temperature above the maximum normal operating o temperature o A HVAC cooler dif f erential temperature above the maximum normal operating differential temperature o A HVAC exhaust radiation level above the maximum normal operating radiation level o An area radiation level above the maximum normal operating radiation level o A floor drain sump water level above the maximum normal operating water level o An area water level above the maximum normal operating water level SC-1
Emergency Procedure Guidelines OPERATOR ACTIONS ! If while executing the following steps secondary containment t t HVAC exhaust radiation level exceeds [PC mr/hr (secondary I lO t containment HVAC isolation setpoint) 3: I t o Confirm or manually initiate isolation of secondary I t containment HVAC, and I I I o -Confirm initiation of or manually initiate SBGT Conly i I when the space being evacuated i s below 212*F3. 1 1 If while executing the following steps: I Secondary containment HVAC isolates, and, I I o I t t o Secondary containment HVAC exhaust radiation level is ! g I oelow [E& mr/hr (secondary containment HVAC isolation I I t setpoint)3. t I restart secondary containment HVAC. 1 #24 8 8 1 t Irrespective of the entry condition, execute CSteps SC/T, t ! SC/R, and SC/LJ concurrently. t 4 4 SC-2 9 w -.-w e,--r n-w. -,-n- -e aw---
,o--,,-
w m,,v v- - - w
Emergency Procedure Guidelines ?' SC/T Monitor and control secondary containment temperatures. SC/T-1 Operate available area coolers. SC/T-2 If secondary contagnment HVAC exhaust radiation level is below C3d mr/hr (secondary containment HVAC isolation setpoint)3, operate available secondary containment HVAC. 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 int,o an area, then before any area temperature reaches its maximum safe operating temperature, enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC-13 and execute it concurrently with this procedure. SC/T-5 If a primary system is discharging into an area and an area temperature exceeds its maximum safe f"' operating temperature in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. l L l SC-3
Emergency Procedure Guidelines l SC/R Monitor and control secondary containment radiation levels. SC/R-1 If _ any area radiation level exceeds its maximum normal operating radiation level, i sol ate i 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 Cprocedure developed from the RPV Control Guideline 3 at CStep RC-13 and execute it concurrently with this procedure. SC/R-3 If a primary system is discharging into an area and an area radiation level exceeds its maximum safe operating radiation level in more than one area, EMERGENCY RPV DEPREESURIZATION IS REQUIRED. s e i SC-4 .. ~..
Emergency Procedure Guidelines SC/L-' Monitor and control secondary containment water levels. SC/L If any floor drain 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 operating 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 saf,e operating water level, enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC-13 and execute it concurrently with this procedure. SC/L-3 If a primary system is discharging into an area and a floor drain sump or area water level exceeds its maximum saf e operating water level in more than one area, EMERGENCY RPV DEPRESSURIZATION 75 REQUIRED. l i SC-5 . -... ~.... -..
.o Emergency Procedure Guidelines 1 1 TABLE 1 OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS I t MAX NORMALS I MAX SAFES I I SECONDARY CONTAINMENT I ALARM I OPERATING I OPERATING I I PARAMETER / LOCATION t i VALUE I VALUE I .g___________________________g_________g_____________g___________! ! DIFFERENTIAL PRESSURE IIN. WATERI IN. WATER I IN. WATER I I I I t CReactor Building / t t t I I outside air i O I t 3 I I CRefuel Floor /outside air i O t i 3 i ___________________________g_________g_____________g__________ "F 1 =F t
- F Se e ALL O *bt t
REA TEMPERATURE ~ g t g g g 1 CRW "A" pump room 158' i 130 t i 3 I CRWCU "B" pump room 158' 130 t i 3 1 t-CRWCU H room 158' at Hx. I 130 t 3 I I CRWCU Hx om 158' I I I disch-H. I 130 t t 3 I I CRWCU phase s room 158't 130 t t 3 1 CRWCU holding p mp room i 185 t 130 t t 3 I I I t I CNE Diagonal I 175 t 3 I I CSE Diagonal I 175 t 3 I I I I CHPCI room, area A 175 t t 3 I 1 CHPCI room, area B 3 1 l t CHPCI room, area C 75 3 I I t t I I I CTorus room, westwall 200 t t 3 I i CTorus room, eastwall -t 200 3 I t CTorus room, northwal 200 t t 3 : I CTorus room, southw t' 200 t 3 i I I 't CMain steam tunn 160 1 3 I I I I i ! CSE, Reactor 30 elev., I I t I area A I 200 t 3 I I CSE, Rea or 130 elev., i 200 t t 3 i area I I t i ! CNW iagonal. area A I 200 3 t ! C Diagonal, area B 200 1 3 I NW Diagonal, area C t 200 t I
- Typical values not available.
i SC-6 ~.
Afco Temp Max Normal Max S&fe Alcr:2 Steam Pipe Tunnel 1~16 212 130'F . RHR Equipment Room.1 206 212 120*F RHR Equipment. Room 2 206 212 120'F RCIC Pipe Route 206 212-190'F j RCIC Equipment Area 206 212 120'F RWCU Pump Room A 186 212 110'F RWCU Pump Room B 186 212 110*F RWCU Pump Room C 186 212 110*F RWCU Hx Room A 199 212 130*F RWCU Mx Room B 199 212 130'F 1 I -,,n=. .-----..-.-e,.---,-.--..-,,..,---,---.,-,n.,,. ,.n-.-
s. Emergency Procedure Guidelines es v-TABLE 1 OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS (Continued) _ ___._-________.58s_6 % _% b.-____-____ l-t I MAX NORMALS I-MAX SAFES t I SECONDARY CONTAINMENT I ALARM t OPERATING I OPERATING 't PARAMETER / LOCATION I I VALUE VALUE t __________________________I______ __!_____________!________ __t I -t AC COOLER DIFFERENTIAL I I t MPERATURE' t =JE t =F t F t I t-1 I I I CRWCU "A" Pump Room 75 I I 3 1 -t CRWCU " Pump Room t 75 I I 3 I I CRWCU Hx oom 158' at Hxs t 75 8 3 8 i CRWCU Hx om 158' disch. t I I ~ .I to Hotwel 75 t t 3 8 i CRWCU phase s arator i t I I room 158' t 75 8 3 8 t-CRWCU holding pu I I room 185' 8 75 t 3 1 t I I t t CNE diagonal I 50 t t 3 1 G ! CSE diagonal 50 3 1 I I I I !.I CHPCI Room, Cooler A 40 t 3
- CHPCI Room, Cooler B 3 :
I I I CNW Di agonal, Cooler A O 3 t-CNW Diagonal, Cooler B 1 4 I I J t 1 CNW Diagonal, Cooler C 40 t 3 3 -l. I I I I t 40 1 1 3 1 I CTorus. Room, NW 1.CTorus Room, West t 40 t t 3 8 I I I t ! [ Torus Rcom, NW 40 t t 3 I JI CTorus Room, Wes 40 t i 3 g I I I I CTorus Room, t 40 t t 3 I l.CTorus Room, est t 40 t i 3 i t I I t CTorus Ro m, NW t 40 t t 3 I t CTorus om, West i 40 1 3 i t I I t CMai Steam Tunnel, t 70 t t 3 C oler'A 1 C in Steam Tunnel, Cooler B t 70 ~
- Typical values.not.available.
SC-7 i.-,, - --.-_, .,.--,.v...,_-m,------,..w.--www ,,,wi. -.,.,.v,.. ,,my. .,m...,n,,,-y,-,.,,-.c.,4,.-+_--,.,-,,,,em.,,. ,..,m-,,.%.-,y..
Diff6rcntini T;mperctures Max Norn Max Safe Alcra op op Steam Pipe Tunnel 96 132 20*F RHR Equipment Room 1 126 132 20*F ) RHR Equipment Room 2 126 132 20*F RCIC Pipe Route 126 132 40'F RCIC Equipment Area 126 132 20'F RWCU Pump Room A 106 132 34'F RWCU Pump Room B 1,06 132 34*F RWCU Pump Room C 106 132 34*F RWCU Hx Room A 119 132 34'F RWCU Hx Room B 119 132 34*F -m-- -g-
g----
on------.--wwr,-, ,,-pw.---,p-.--.--w -+w,-,-...g,w_.- .,w--,yq_-y,-9w,,%-w94 --w ,-s--ew--- e-y --3--
Emergency Procedure Guidelines TABLE 1 OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS (Continued) I t MAX NORMALS I MAX SAFES I I SECONDARY CONTAINMENT I ALARM t OPERATING l OPERATING ! PARAMETER / LOCATION I I VALUE VALUE i p.,_---------------------_----__----g_----------_-g_--_---_--.; -t HVAC EXHAUST RADIATION I I t I LEVEL ABOVE I MR/HR MR/HR I MR/HR - t 1 CReactwe Building i JMr lo l 38 l, 3 l I C;f ;l F4eerRod M h k i 20 0 So I 3 8 t---------- --- h OSk%)I----l---------l-------------I Seg .I AREA RADIA ON LEVEL I MR/HR I MR/HR MR/HR I 8 A W k.L' [158' I Southeas Area i 15 I t 3 ! ! C150' Northeast rea i 15 t 3 I I C158' Northwest A ea i 15 1 3 I ! C130 Northeast Wo Area i 15 I I J l 1 C130' Southeast Work ea i 15 8 1 3 1 1 CDecontamination Pump i Equipment Room 20 t t 3 I CSouth CRD Hydraulic U' nit i 15 I 3't I CSpent Fuel Fool I I I t-Passageway 1p i t 3 i ! C185' Operating Floor 5 t 3 ! 3 : 1 C185' Sample Panel Area 1 I CCRD Repair Area 1 20 i 3 1 I C185' RWCU Control Panel t 1 Area 15 1 3 I CRCIC Equipment Area 20 t t 3 8 i CCRD Pump Room SW t 20 1 3 I I CRHR & Core Spray R m I i Northeast t 20 1 3 ! CRHR & Core Spra Room I t I Southeast 20 t i 3 ! ! CFuel Fool De n Panel Area 20 t t 3 I I l 1 t I t I I I I I i 1 I I i I I I I i I i i t i 1 i i I
- Typical values not available.
SC-B ,,--,e--.-._~.--e.-- -,.,e-+,- w--m,,,-.-ww--. ,----e.-- -wyr---.------,y ..mp,,--,-o,-,,,----,- =.w,--*- --m---%,----v--g----
ARM D18 Inst (PT) BQ EQ mr/hr ar/hr -MPL alarm Isol Service Bound Upscale max max mr/hr pr/hr Rad Rad Reading Normal Safe SBGT 820' E1. K602A 10" .RWCU Phase Sep K602B 10 2E6 E7 10* 108 102 RB Sample K6010 25 286 E7 108 250 108 (832) Station 10* 108 108 AB Cont. K6011 10 Purge RB HCU K601C 3.5 286 E7 108 35 350 Module N. RB HCU K601D 3.5 2B6 E7 108 35 350 Module S. TIP Room K602D 100 2E6 E7 108 108 108 TIP Drives K601E 7.5 286 E7 10' 75 750 CRD K601T 10 286 E7 10' 108 108 Storage & Repair W RHR Hx K602F 100 585 E7 10* los goa Rooms SE RHR Hx 602E 100 SES E7 10* 108 10* Rooms RCIC Room K602G 45 SE5 E7 108 450 4500 HPCS Room K601H 3.5 SES E7 108 35 350 MSL Tunnel K610A/D 3800 7500 686 E7 10'
Emergency Procedure Guidelines TABLE 1 OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS (Continued) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _d_e_s_ _A_ _N_ _c_. c_.d_ _ _ _ _ _ _ _ _ _ _ _ _ _ I MAX NORMALS I MAX SAFES I I CONDARY CONTAINMENT I ALARM OPERATING ! OPERATING I t-P RAMETER/ LOCATION I I VALUE I V UE I g__________________________g_________g_____________g__________g i FLOOR RAIN SUMP WATER I I I I I LEVEL i E t h t E t I I I
- CSump A (S E.
Diagonal) 47 1 1 3 I t CSump B (S. Diagonal) 1 52 I 3 I t--------------
l---------!--------- ---l-----------!
! AREA WATER LEV I E N t h I I I i i 1 CCRD Compartment t 7 I I 3 t I CRCIC Compartment 7 8 t 3 1 1 CRB NE Corner RM 7-t 3 I CRB SE Corner RM 7 1 I 3 I I CHPCI Compartment 7 1 3 I I CTorus Compartment NW I 7 1 3 1 1 CTerus Compartment NE 7 I I 3 I CTorus Compartment SE I l 3 1 ! CTorus Compartment SW I 7 t t 3 ! t I I t l t t I t I i t I l [ / I -I I I I i I 1 I I I i i I t I I t t I t i i t I i I I I I t I i I t I t I i
- Typical values not available.
SC-9
RB Batement watGr 10v210 Ht. from floor Area Limiting Component (Inches) NE RCIC Inst. rack elect. 25 conn. box SE RHR B&C Inst rack elect. 25 Conn box SW HPCS Suction P.S. 822-31 N015 & 14 NW .RHR A Inst. Rack Elect. 25 conn. box Raceway MSIV-LC elect, conn. 35 boxes
Emergency Procedure Guidelines RADIOACTIVITY RELEASE CONTROL GUIDELINE PURPOSE The purpose of this guideline is to limit radioactivity release into areas outside the primary and secondary containments. ENTRY CONDITIONS The entry condition for this guideline is: o Offsite radioactivity release rate above the offsite release rate which requires an Alert. ~ OPERATOR ACTIONS RR-1 Isolate all primary systems that are discharging into areas outside the primary and secondary containments except systems required to assure adequate core cooling or shut down the reactor. RR-2 If offsite radioactivity release rate approaches or exceeds the of f si te release rate which requires a General Emergency and a primary system is discharging into an area outside the primary and secondary containments, EMERGENCY RPV DEPRESSURIZATION IS REQUIREDs enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC-13 and execute it concurrently with this procedure. l i l O h RR-1
Emergency Procedure Guidelines n-CONTINGENCY 41 LEVEL RESTORATION 4 I If while executing the following steps: I f y C I o Boron Injection is required or boron has been injected i g" = I into the
- RPV, enter Cprocedura developed from I CONTINGENCY #73.
I I ! o RPV water level cannot be determined, RPV FLOODING IS I I REQUIRED 5 enter Cprocedure developed from CONTINGENCY I t
- 63.
I 1 i I o RPV Flooding is required, enter Cprocedure developed i I from CONTINGEN,CY #63. I a--------------------- C1-1 Initiete !C. C1-2 Line up for injection and start pumps in or more of the following injection subsystems: o Condensate o HPCS o LPCI-A o LPCI-B o LPCI-C o LPCS-A e L*CE-? If less than 2 of the injection subsystems can be lined up, commence lining up as many of the f ollowing alternate injection subsystems as possib1w: i to RHR service water crosstie 3 i Co Fire system 3 Co Interconnections with other units 3 to ECCS Leep-full systems 3 Co SLC (test tank) 3 Co SLC (boron tank) 3 C1-1
Emergency Procedure Guidelines l i i j i If while executing the following steps: I l t t I o The RPV water level trend reverses or RPV pressure I i l changes region, return to CStep C1-33. I j o RPV water level drops below C-hk6in. (ADS initiation I setpoint)3, prevent automatic initiation of ADS. I i g C1-3 Monitor RPV pressure and water level. Continue in this procedure at the step indicated in the following table. RPV PRESSURE REGIONg7 q% C4E5 psig38 C W psig3= t HIGH I INTERMEDIATE I LOW l t E I INCREASING I C1-4 I C1-5 I C1-6 I V E I DECREASING i C1-7 i C1-B I L
- (RPV pressure at which LPCS shutof f head is reached)
- (:TCI er RCIC low pressure isolation setpoint,. '.i c h ; v e r
- 1.,- w,u__s C1-4 R,PV WATER LEVEL INCREASING, RPV PRESSURE HIGH Enter Cprocedure developed from the RPV Control Guideline 3 ht CStep RC/L3.
C1-5 RPV WATER LEVEL INCREASING, RPV PRESSURE INTERMEDIATE RCIC e\\5ee not available and RPV pressure is If "^"' increasing. EMERGENCY RPV DEPRESSUR12ATION IS REQUIRED. When RPV pressure is decreasing, enter (procedure developed from the RPV Control Guideline 3 at CStep RC/L3. 15 If AT : ;r.: RCIC ene not available and RPV pressure is not increasing, enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC/L3. 12.S Otherwise, when RPV water level reaches C+NP in. (Iow level scram setpoint)3, enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC/L3. C1-2 .w-. .,..,..,,,..,w--.,..,,s ..,..-,,,n. ,,.._,,,-,g.
l Emergency Procedure Guidelines o C1-6 RPV WATER LEVEL INCREASING, RPV PRESSURE LOW If pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC/L3. Otherwise, enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC/L3. C1-7 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH OR INTERMEDIATE RCit. If lTC* - RCIC is not operating, restart which.er i: met 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. 161 When RPV water level drops to C-be4 in. (top of active fuel)3: o If no system, injection subsystem or alternate injection subsystem is lined up with at least one pump running. STEAM COOLING IS REQUIRED. When any system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, return to CStep C1-33. o Otherwise, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV water evel is increasing or RPV pressure drops below C psig ("""* -- RCIC l ow pressure isol ation setpoint. -hich:cc-it 'd;h .-)3, return to CStep C1-33. i l t C1-3 .. ~ _ _ _ _ _.. _. _.. _ _. _.. _ _ _ _ _ _ - _ _., _. - _ _. _ _ _ _ _ _.. -. _
) Emergency Procedure Guidelines 1 l C1-B RPV WATER LEVEL DECREASING, RPV PRESSURE LOW CIf no HPCS or LPCS subsystem is operating,3 start pumps in alternate injection subsystems which are lined up for injection. If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. ___________________________________g________(top of When RPV water level drops to C-k64 in. active I !! fuel)3, enter Cprocedure developed from CONTINGENCY #43. I D 9 0 I I l l I l C1-4 y ,,,..,..,_..-..m_._ ,s.,._ ,_-_.y.-r, ...._-...,,...,_4 ,....,..._7.
Emergency Procedure Guidelines 5 CONTINGENCY #2 EMERGENCY RPV DEPRESSURIZATION C2-1 When either: I #13 #14 i o Boron Injection is required and all injection into the RPV except from boron injection systems and CRD has been terminated and prevented, or o Boron Injection is not required, C2-1.1
- nitirt l0.
G C2-1.2 If suppression pool water level is above [a& ft. Jk-Gn. (elevation of top of SRV discharge device) 3: o Open all ADS valves. o If any ADS valve cannot be opened, open other SRVs until C7 (number of SRVs dedicated s to ADS)3 valves are open. C2-1.3 If less than C3 (Minimum Number of SRVs Required f or Emergency Depressurization) 3 SRVs are open Gend 7g, ,.t Rod EI'# d'~;;;"'O if "t '"""' 5^ ?2i; '"!Pi 2? ~~~~- -Ont ne ep;nin;
- rrra e? above suppression
! #22 1 MTs not tws%1 chamber pressure 3, rapidly depressurize the RPV using one or more of the following systems (use in order which will minimize radioactive release to the environment): o Main condenser o RHR (steam condensing mode) o COther steam driven equipment 3 o Main steam line drains ""C! :ter- !!n: o RCIC steam line o Head vent e C tui; ;i de c;nt C2-1
Emergency Procedure Guidelines 7 t If RPV Flooding is required, enter (procedure developed I I t from CONTINGENCY #63. C2-2 Enter Cprocedure developed from the RPV Control Guideline 3 at CStep RC/P-33. O e C2-2
Emergency Procedure Guidelines CONTINGENCY #3 STEAM COOLING C3-1* C:r'ir-initieti;r of IC. 1 If while executing this step Emergency RPV I I Depressurization is required or any
- system, injection i I
I subsystem, or alternate injection subsystem is lined up I I for injection with at least one pump
- running, enter !
I Cprocedure developed f rom CONTINGENCY #23. I If !C --ann & h= iaitict;d: 3.76 When RPV water level drops to C-291F in. (Minimum Zero-Injection RPV Water Level)3 or'if RPV water level cannot be determined, open one SRV. I When RPV pressure drops below C700 psig (Minimum Single ! I SRV Steam Cooling Pressure)3, enter Cprocedure developed I
- from CONTINGENCY #23.
I e C3-1
Emergency Procedure Guidelines CONTINGENCY #4 CORE COOLING WITHOUT LEVEL RESTORATION C4-1 Open all ADS valves. 1 #13 i If any ADS valve cannot be opened, open other SRVs until C7 (number of SRVs dedicated to ADS)] valves are open. C4-2 Operate HPCS and LPCS subsystems with suction from the suppression pool. When at least one core spray subsystem is operating with suct n from the suppression pool and RPV pressure is below CEte sig (RPV pressure for rated LPCS or.HPCS flow, whichever pressure is lower)3, terminate injection into the RPV from sources external to the primary containment. tbl C4-3 When RPV water level is restored to C->6+ in. (top of active fuel)3, enter Eprocedure developed from the RPV Control Guideline 3 at CStep RC/L3. I C4-1
Emergency Procedure Guidelines CONTINGENCY #5 ALTERNATE SHUTDOWN COOLING C5-1* Initiate suppression pool cooling. C5-2 Close the CRPV' head vents,3 MSIVs, main steam line drain valves, and HPG4-end RCIC isolation valves. Come%we (Minimum Number of SRVs C5-3 Place the control switch for Required for Alternate Shutdown Cooling)J SRVCs3 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 Terminate and prevent all injection into the RPV except from CRD. n C5-6 Start one LPCS or LPCI pump with suction from the suppression pool. C5-7 Slowly increase LPCS or LPCI injection into the RPV to the maximum. C5-7.1 If RPV pressure does not stabilize at least C94 7,f psig (Minimum Alternate Shutdown Cooling RPV Pressure)3 above suppression chamber pressure, start another LPCS or LPCI pump. its C5-7.2 If RPV pressure does not stabilize below C+99 psig (Ma>:imum Alternate Shutdown Cooling RPV Pressure) 3, open another SRV. C5-7.3 If the cooldown rate exceeds [100*F/hr (maximum RPV cool down rate LCO) 3, reduce LPCS or LPCI injection into the RPV until the cooldown rate decreases below C100*F/hr (maximum RPV cooldown rate LCO)3 Er ""Ypr:::.. J--.rrrrr tr within C0 p..q 7ayyt9ed !"i - i.. LR, 3. ep...i..; " r-u r' e' cr;; erri;r gggN vet e - O., pr....;:,
- .ich:ve- ^"" r : i. i ;t 1.
gg C5-8 Control suppression of temperature to maintain RPV water temperature above C F (RPV NDTT or head tensioning limit, whichever is higher)3. C5-9 Proceed to cold shutdown in accordance with Cprocedure for 3 cooldown to cold shutdown conditions 3. C5-1
a 8 Emergency Procedure Guidelines CONTINGENCY #6 RPV FLOODING If at least C3 (Minimum Number of SRVs Required for C6-1 Emergency Depressurization)3 SRVs can be opened or if HPCS motor driven feedwater pumps are available for orinjection, close the MSIVs, main steam line drain valves, IC, HPCI, RCIC and RHR steam condensing isolation valves. C6-2 If.any control rod is not inserted to or beyond position g CO6 (maximum subcritical banl:ed withrawal position)3: C6-2.1 Terminate and prevent all injection into the RPV except from boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure. i Minimum Alternate RPV I ! Number of open SRVs Flooding Pressure (psig)! _________g
- _______________________________________3\\&O C 7 or more t
++e t t I I C6 I M 3 2.19 i i C5 1 MG 3 A fs1 l I C4 GM 3 "h30 l 67 C3 GSO 3 %40 t ~ t 4M 3 f.r.5 C I C 1 I GAML 31942.96 l' 2 If less than [f (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)3 SRVCs3 can be opened, continue in thi s procedure. C6.-1 O
Emergency Procedure Guidelines l If while executing the f ollowing step, RPV water level i I can be determined and RPV Flooding is not required, I I enter Cprocedure developed from CONTINGENCY
- 73 and i I Cprocedure developed from the RPV Control Guideline 3 at i I CStep RC/P-43 and execute these procedures !
I concurrently. I =------------------------------------_ C6-2.2 Commence and slowly increase injection into the RPV with the following systems until at least [4'7-(minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is t #25 I below the lowest SRV lifting pressure)3 SRVCs3 are open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: o Motor driven feedwater ppmps o Condensate pumps o CRD to LPCI3 L If.at least C4 (minimum number of SRVs for which I the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lif ting pressure) 3 SRVCs3 are I not open or RPV pressure cannot be increased to above the Minimum Alternate RPV Flooding Pressure, commence and slowly increase injection into the RPV with the f ollowing systems until at least Dr1 (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)3 SRVCs3 are open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: o HPCS o LPCS to RHR service water crosstie 3 to Fire System 3 to Interconnections with other units 3 to ECCS keep-full systems 3 C6-2
Emergency Procedure Guidelines 1.- C6-2.3 Maintain at least CS (minimum number of SRVs for which the Minimum Alternate RPV Flooding Pressure is below the lowest SRV lifting pressure)3 SRVCs3 e open and RPV pressure above the Minimum Alternate RPV Flooding Pressure but as low as practicable by kf throttling injection. v C6-2.4 When* o All control rods are inserted to or beyond tw position C06 (maximum subcritical banked withdrawal position)3, or o The reactor is shutdown and no baron has been injected into the RPV, continue in this procedure. O e C6-3 =
i Emergency Procedure Guidelines i C6-3 If RPV water level cannot be determined: C6-3.1 Commence and increase injection into the RPV with the following systems until at least C3 (Minimum Number of SRVs Required for Emergency Depressurization) J SRVs are gpen and RPV pressure is not decreasing and is C77 5sig (Minimum RPV ( Flooding Pressure) 3 or more above suppression chamber pressure: o HPCS o Motor driven feedwater pumps o LPCS o LPCI o Condensate pumps a CRD to RHR service water crosstie 3 n-to Fire System 3 to Interconnections with other units 3 to ECCS keep-full systems 3 to SLC (test tank) 3 to SLC (boron tank) 3 C6-3.2 Maintain at least C3 (Minimum Number of SRVs Required for Emergency Depresgyrt:ation)3 SRVs open and RPV pressure at least C77 psig (Minimum RPV Flooding Pressure)3 above suppression chamber pressure but as low.as practicable by throttling injection. i C6-4
I Emergency Procedure Guidelines C6-4 If RPV water level can be determined, commence and increase injection into the RPV with the f ollowing systems until RPV water level is increasing: o HPCS o Motor driven feedwater pumps o LPCS o LPCI o Condensate pumps o CRD Co RHR service water crosstie 3 to Fire System 3 to Interconnections with other units 3 to ECCS keep-full systems 3 to SLC (test tank) 3 Co SLC (boron tank) 3 &w 0.1., % C6-5 If RPV water level cannot be determined: L..; U At i r.. i..o..t :. s C6-5.1 Continue injecting water into the RPV until Ctemperature near the cold reference leg instrument vertical runs 3 is below 212"F and RPV water level instrumentation is available. l l If while executing the following steps, RPV water level : I
- can be determined, continue in this procedure at CStep :
- C6-63.
C6-5.2 If it can be determined that th RPV is filled or j if RPV pressure is at least Ef? sig (Minimum RPV Flooding Pressure) 3 above suppression chamber pressure, terminate all injection into the RPV and reduce RPV water level. C6-5 y ,.m,
Emergency Procedure Guidelines C6-5.3 If RPV water level indication is not restored within the Maximum Core Uncnvery Time Limit after commencing termination of injection into the RPU, return to CStep C6-33. 3,, g guyh 40 + l Maximum Core Uncov 30 + Time Limi Core Uncovery 20 + Time (min.) 10 + l 1. 0 +--------+--,---+--------+ 1 min. 10 min. 1 hr. 10 hr. Time After Reactor Shutdown s-C6-6 When suppression chamber pressure can be maintained below the Primary Containment Design Pressure, enter Cprocedure developed from the RPV Control Guideline 3 at CSteps RC/L and RC/P-43 and execute these steps concurrently. i 56 +...... 4
- +
Suppression Chamber im y Containment Pressure ign Pressure (psig) 0 +----+--------+------ --- 0 12.5 34.5 Primary Containment Water Level (f t. ) C6-6 -e~---+---~ww.c-,- ,n-, __,__p,
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o. Emergency Procedure Guidelines CONTINGENCY #7 LEVEL / POWER CONTROL ________________-__-_-____-________--___--___---___--_-_----_- I I 1 If while-executing the following steps: I t I o RPV water level cannot be determined, RPV FLOODING IS I t-REQUIREDI enter Cprocedure developed from CONTINGENCY l ( I e t
- 63.
I I t o RPV Flooding is required, enter Cprocedure developed I t I t I from CONTINGENCY #63. C7 If: 5 o Reactor power is above C$% (APRM downscale trip)3 or cannot be determined, and 110* F o. Suppression pool temperature is above Cthe Boron . Injection Initiation Temperature 3, and I Bor t 130 + 1 - ction I l...... nitiation 'l Suppe i on Temperature J Pool 120 + Temperature ("F) I 110 + I t i 100 +---+---+---+---+- +---+ t O 1 2 3 4 5 t i Reactor Power (%) o' Either an RV is open or opens or drywell pressure is above C psig (high drywell pressure scram setpoint)3, j lower RPV water level by terminating and preventing all injection into the RPV except from boron ! #26 I injection systems and CRD until either: C7-1 ~ ~~ -,,,.r- _,,.,__p
Emergency Procedure Guidelines w o Reactor power drops below C% ( APRM downscale trip) 3, or -l4o o RPV water level reaches C-464 in. (Flow Stagnation Y Water Level)3, or o All SRVs,gmain closed and drywell pressure remains below C psig (high drywell pressure scram setpoint)3. t If while executing the following steps Emergency RPV ! ! Depressurization is required, continue in this procedure at ! I CStep C7-2.13. I 1 If while executing the following step: I I I S i o Reactor power is above C3% (APRM downscale trip)3 or I i cannot be determinkd, and I I t -gy L o RPV water level is above C-+64 in. (Flow Stagnation ! I Water Level)3, and I I to* F t t o Suppression pool temperature is above Cthe Boron ! I Injection Initiation Temperature 3, and i I I gg SRV is open or opens or drywell pressure is t I o Either I abcve CG e psig (high drywell pressure scram setpoint)3, ! I j I return to CStep C7-13. t O C7-2
Emergency Procedure Guidelines 5 C7-2 Maintain RPV water level either: I #9, #10, #11, #25 I If RPV water level was deliberately lowered in CStep o C7-13, at the level to which it was lowered, or i ) If.RPV water level was n,pg deliberately lowered in o CStep C7-13, betwq g C+ W in. (low level scram setpoint)3 and C+ M in. (high level trip setpoint)3, I with.the following systems: to76 o Condensate /feedwater system [ttte - O psig (RPV pressure range for system operation)3 toTL o CRD system Cbtto - O psig (RPV pressure range for system operrtion)3 to74 57 o RCIC system C+++4 - 50 psig (RPV pressure t #12 i range for system operation)3 Ew M7CI syete,i, [1110 - 100 peig 'RIV pre;;ur r er.; for 3 3 cyster Ope-stier}3 g 2Wo to LPCI system CSS 6 - O psig (RPV pressure range f or 3 3 C system operation)3 If RPV water level ca et be so maintained, maintain RPV water level above C-in. (top of active fuel)3 with these systems. i l I C7-3
e .o Emergency Procedure Guidelines 1%I If RPV water level cannot be maintained above C-k&4 in. (top of active fuel)3, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: C7-2.1 Terminate and prevent all injection into the RPV except from boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure. t Minimum Alternate RPV 1 1 Number of open SRVs t Flooding Pressure (psig)I t----------------------t--------------------------! C 7 or more 110 3 IVo 1 I t I I C6 1 135 3 2.t? I t i I I C5 . t 165 3 ACl I t t 210 3 330 t I C4 I t t 1 C3 1 280 3 446 t I y I t C2 1 430 3 445 I I I C 1 870 3 1442.94 z If less than C4'(minimum number of SRVs for which l the Minimum Alternate RPV Flooding Pressure is l below the lowest SRV lifting pressure)3 SRVCs3 can I be opened, continue in this procedure. C7-2.2 Commence and slowly increase injection into the RPV with the following systems to ! #25 I res ce and maintain RPV water level above C-in. (top of active fuel)3: o Condensate /feedwater system o CRD o RCIC Co HPCI 3 Co LPCI 3 l l l C7-4 ..,.,9.y.,_e.- ,,r.w-r.. ,,.~me,, ,%.-..,w=-.,,,.,,,.n,v. i,3-,,,.r%,-,,-,...--,,,m,,e-
e r Emergency Procedure Guidelines i If RPV water level e not be restored and maintained above C-in. (top of active fuel)3, commence and slowly increase injection into the RPV with the following syste to restore and maintain RPV-water level above C-in. (top of active fuel)3: o HPCS i o .LPCS Co RHR service water crosstie 3 Co Fire System 3 Co Interconnections with other units 3 to ECCS keep-full systems, 3 t If while executing the following step reactor power commences I and continues to increase, return to CStep C7-13. I WIS cyd, 9.b % C7-3 When C99+ pounds (Hot Shutdown Boron E g:.t) 3 of boron have been injected or all control rods are inserted to or beyond position CO6 (maximum suberitical banked withdrawal pog gion)3, restore and maintain RPV water 19791 between C+ ,i n. (l ow level scram setpoint)3 and C W an. (high level trip setpoint)3. 'y water level cannot be restored and maintained above If C+ in. - (low level scram setpoint)3, maintain RPV water M C-FM* i n. (top of active fuel)3. level above we If-RPV water level cannot be maintained above C-F64 in. (top of active fuel)3, EMERGENCY RPV DEPRESSURIZATION IS l REQUIREDI return to CStep C7-2.13. ! If Alternate Shutdown Cooling is
- required, enter !
I Cprocedure developed from CONTINGENCY #53. [ procedure for cooldown to cold shutdown conditions 3 C7-4 When is entered from Cprocedure developed from the RPV Control Guideline 3 at CStep RC/P-53, proceed to cold shutdown in accordance with Cprocedure for cooldown to cold shutdown conditions 3. C7-5 . -. -. -.. -. - - - ~,.. -. -...
4' W.. 't. ($ WRITER'S GUIDE FOR LASALLE GENERAL ABNORMAL (14A) SYMPTOM-BASED EMERGENCY PROCEDURES COMMONWEALTH EDISON COMPANY LASALLE COUNTY STATION ~ SEPTEMBER 19, 1984 4 a e&
'2 TABLE OF CONTENTS 'Section 1 INTRODUCTION 1.1 Purpose 1.2 Scope. Section 2 ROP DESIGNATION AND NUMBERING 2.1 Procedure Designation 2.2-Procedure Numbering l Section 3 FORMAT ~ 3.1 WA Sections 3.2 Procedure Heading and Page Identification 3.3 Instruction Step Numbering 3.4 Page Format '3.5 Type size Section 4 WRITING WA's 4.1 Writers Introduction 4.2 Relationship of LGA*3 to other procedures 4.3 Instructional Step Length and Content 4.4
- If/Then Logic-4.5 Cautions and Notes 4.6 Graphs Tables, and Attachments 4.7 Use of Underlining 4.8
. Referencing and Branching to Other Procedures 4.9 Component Identification 4.10 Units of Measure 4.11 Concurrent Actions / Overriding Instructions 4.12 Connectors (AND, OR) Lists 4.13 Checkoff Blanks 4.14 Capitalization 4.15 Unit Designation 4.16 Use of Verbs Table 1 - WA Acronym List Table 2 - Action Verb List I ., -. _. _. - - _ _.. _, -... - - - -..,. ~.... _., _.. - -, _. -.., _ _ _.. _... _ _, _....
Section 1 INTRODUCTION 1.1 PURPOSE The purpose of this procedure is to provide administrative and technical guidance on the preparation of LGA's. 1.2 SCOPE. This procedure applies to the writing of all of LaSa11e's symptom-based emergency procedures, LGA's. Section 2 80P DESIGNATION AND NUMBERING 2.1 Procedure Designation Designation of the emergency procedures will be WA - LaSalle General Abnormal. 2.2 Procedure Numbering o The emergency procedure numbering system is divided into two components - the procedure designator, LGA. and a serialized two digit number which identifies the WA. Example: LGA-01 o Tables that are part of the LGA's shall be labeled with the appropriate LGA number followed by "T" for table and a serialized one digit number. Example: LGA-T1 or WA-04-T1 Section 3 FORMAT B.1 LGA SECTIONS Rach WA shall be divided into four sections - A. PURPOSE - defines briefly the basic purpose for the procedure. B. ENTRY CONDITIONS - lists the entry conditions for the procedure. C. OPERATOR ACTIONS - the body of the procedure. D. REFERENCES - lists procedural references from the WA's. 3.2 PROCEDURE HEADING M PAGE IDENTIFICATION Bach page of the 14A'a: will be identified by the procedure number, the revision number, the revision date, and the page number. The pages will be numbered sequentially with the word " final" on the last page. Page 1 DOCUMENT ID 00691/
~ 3.3 INSTRUCTION STEP NUMBERING o Instruction stsps will be numbared and idsntified as follows: A. 1. 'a. (1) (a) o-When an instructional step that is a subordinate step appears on a different page than the governing step, the complete number shall be used at the start of the page. For example - step a. of the second step in Section A appears on a different page than step A.1.a. If this step heads the page, it shall be labelled step A.2.a instead of just a. 3.4 PAGE FORMAT' o. Margins shall be at-least 1 1/4" on the binding side and 1/2" on the other side. o. See the example below for proper alignment. Space 4 times after "If" and 2 spaces after "Then". f C. OPERATOR ACTIONS 1. I_f. X (start typing here) Then X 4. (1) (a) 3.5 -TYPE SIZE Use pitch 10 type size so that the procedure is readable under low light conditions. Section 4 WRITING IAA's 4.1 WRITER'S INTRODUCTION ~The IAA procedures exist as an aid to the operator to provide accurate, usable direction to his actions so that he may best cope with degraded conditions that have potential to threaten the plant and the public. The LGA -writer must keep this in mind whenever the 14A's are being drafted or revised. The IRA's are a tool for the operator and as such they must be usable by the operator. Of course technical content is extremely important; but exactitude in the technical content of a procedure is of little value if Page 2 DOCUMENT ID 00691/
'it is not writtsn in a mann2r that can be'undarstood and followed by an operetor during sccidsnt conditions. Tha LGA writer in tasksd with turning a tschnical documsnt (ie - Em3rgsncy Procedure Guidelints) into e functional operator's tool. To accomplish this goal he must approach this translation task from the operator's viewpoint. The writer has to ensure that the intent of the Technical Guideline is maintained, while at the same time the " usability" of the procedure is maximized.
- The guidance provided by this procedure will help maintain the clarity and consistency of the LGA's.
The rules set forth here are generally applicable throughout the procedure; however, there may be exceptions. If careful analysis reveals that a particular principle may not-be the best rule to use'for a certain circumstance, then that rule may be violated. Even though a rule may be bent to fit a special situation, it will only be intentionally violated when it promotes the overall effectiveness of the procedure. The major task for the 14A writer is not to produce a product with absolute engineering perfection; it is not to blindly follow the writing guidance contained in this guideline; but his task is to produce a procedure that can and will be used by the operator whenever the levels of plant safety are degraded. 4.2 kRLATIONSHIP O_E LGA's T_O OTHER PROCEDURES During normal large scale plant evolutions the plant's operation is - governed by the 14P's. More detailed, system-specific instructions for operation are provided by the LOP's. Alarm information is provided by the annunciator lan's. Instructions for testing equipment is provided by the - IDS's. Abnormal operating instructions for specific events are provided in the tak's. All of these operating procedures are used in conjunction with the others; sometimes more emphasis is placed on one type of procedure than another; other times a certain type of procedure may not even apply. 'The crux of the matter is that all of these operating procedures have the normal function of guiding the operation of the plant safely within the bounds of the license. Whenever conditions degrade to the point where the safety of the plant is diminished, entry into another type of procedure, the IAA,'is required. The LGA entry conditions do not necessarily indicate that an emergency exists but are degraded parameters which may lead to an emergency. When an LGA'is entered, it will be.the governing procedure. The operator will follow the directions given by the IRA. He will be using the other' station procedures to support the LGA direction. For example, the operator will still be responding to annunciators and the LOA annunciator procedures. He may be following instructions from an LGP or 144, yet he will still be in the IAA. When the 14A's are exited, the operator will return to the normal operating procedures or to special operating instructions written for recovery. 4.3 INSTRUCTIONAL STEP LENGTH AND CONTENT Instruction steps will be concise and precise. Conciseness denotes brevity; - preciseness means exactly defined. 'Thus, instructions should be short and exact. This is easily stated, but not so easily achieved. General rules to be used to meet these objectives are as follows: o Instructional steps should deal with only one idea. 4 Page 3 DOCUlWNT ID 00691/
o-Short, sicple santsnces should be umsd. .o compicx'ovolutions should be broken down into a series of simpler steps o -The action the operator takes should be clear. o Expected results of routine tasks should not be stated. o Operator actions should be related to observable plant parameters. When possible, avoid.using time as a key to operator actions. o Give the operator enough information to accomplish the task but j don't give him too much information to read. Don't clutter the procedure up with too much verbiage. There will be times when { identical series of steps will be repeated. Inclusion of these same steps at every point in the procedure would make the procedure . harder to follow. In these cases, the procedure will work better if the repeated steps appear at the back of the procedure book clearly identified with a tab. Whenever a conditional statement calls for taking the action, the operator will go to the tabbed section. When he has taken the required action, he will return to the procedure from which he came, o When a list of items requires actions to be taken in a specified ~ order, use the words "in the following order" or similar terms to identify the necessity of sequencing. Otherwise a listing would infer no specified order is required and leave the sequence up to the operator's judgement. 4.4 IF/THEN LOGIC o Whenever a condition appears in the procedure that will require prescribed operator action, the If/Then logic style should be used if it will make the procedure more clear. o The words "If" or "When" will normally precede the conditional statement. The word "Then" will precede the action statement. If, Then, and When shall be underlined when they are used to begin o conditional logic statements. o .The LGA's shall be written so that the If/Then logic is used l consistently. The procedure shall be constructed so that the l-operator will take the correct actions if he enters the procedure at the proper point and follows the logic given the following guidelines -- i l' "lF"- The operator reads the condition which follows. If the condition applies, he takes the action which follows in the related "Then" statement and goes on to the next procedural i step. If the condition does not apply, he does not have to l' even look at the "Then" statement, but continues on to the j next procedural step. l Page 4 i DOCUIENT ID 00691/ i
f "Then" - Th2 Ection statement which follows the "Then" will be taktn by the oparctor if the condition (tha "If" statement or the "When" statement) applies to the plant condition. If the conditional statement does not apply, the operator does not even have to read the action statement, but goes on to the next procedural l step. Even if the condition does apply and the . operator is performing or trying to perform the prescribed action, he should look ahead to see if the ensuing conditions apply. "When" - _The "When" statement is a special kind of "If" statement. "When" does the same thing as "If" except it. infers that the step may apply at a later time. "When" emphasizes that the operator should be looking for the associated condition and that the condition is likely to occur at a later time. When the associated condition does occur, the operator should take the action specified by the "Then" statement. The "If" statement technically does the same thing, "When" is used for emphasis, care should be taken not to overuse "When" to preserve its emphatic value, o The."If/Then" logic takes the operator from the entry conditions through the procedure until he exits the procedure or the "If" statements no longer apply. Generally, the further the operator 9ets into the procedure, the more degraded,the conditions are; hence the actions become more drastic. As the operator gets deeper into the procedure, he should not ignore the previous steps; he should still be taking actions those steps required. The operator should periodically go back through the previous "If" statements and ensure that if they apply, that he is taking the required actions. Conversely, the operator should not get stuck on an early step. He should look ahead in the procedure for conditions that might require more drastic actions. o Whenever practical, the "Then" statement should appear on the same page as the "If" statement. 4.5 CAUTIONS AND NOTES o Step specific cautions should precede the steps to which they apply. o Procedure specific cautions should precede the procedures to which they apply, o General Precautions should be included be included in a table at the front of the procedure. The General Precautions snould be stressed during training. o Notes should precede the steps to which they apply. Page 5 DOCUMENT ID 00691/
o CAUTIONS cnd NOTES ghall be emphtsizcd. Tha harding thall be all c:p2 cnd cantered ov2r th2 stctement. Tha hatding chall be
- underlined. The cautionary statement or note shall be conventionally typed using both upper and lower case letters to make it easier to read. The entire note or caution shall be enclosed by a box. See the example below:
i l l CAUTION Cooldown rates above 100'F/hr may be required to accomplish this step. o CAUTIONS and NOTES should not contain action steps. They should be informational or warning devises only. In rare cases a CAUTION or NOTE may have to contain an action or inferred action. This shall only be done after a very careful assessment of alternatives. o CAUTIONS and NOTES shall not be overused. If too many CAUTIONS or NOTES,are used the importance of the message may be diluted. Cautions may be minimized through training or by writing the information into the procedural step itself. o CAUTIONS and NOTES should appear in their entirity on a single page. Do not split CAUTIONS and NOTES between pages. o The step to which a step specific caution applies should appear on the same page as the caution. 4.6 GRAPHS. TABLES and ATTACHNENTS o Graphs, Tables, and Attachments should be easy to read and easy to use by the operators, o ' Units should be the same as those in the Control Room. o Graphs. Tables, and Attachments shall be labeled clearly. Graphs shall have a noun name and sequential. number. For example, IAA-03-G2, RPV Saturation Limit is the title of the second graph in 14A-03 and it defines the RPV Saturation Limit. o The use of graphs shall be minimized. When a single value can be used, it is better than using a graph. o Graphs will normally appear on the face adjacent page to where it is referenced in the text of the procedure. An exception may occur if an overriding Instruction applies to the same page that references a graph. When an overriding Instruction appears on the face adjacent page, the graph will be included on a foldout page. o. Where possible use a full page for the graphs. o The maximum number of divisions per inch for the axes of graphs should be 10. Page 6 DOCUMENT.ID 00691/
o .All numbers on tha grcphs should be at least 4 mm high. o All exas of tha graphs chall be clearly 1Ebeled and include the j units of measure. 4.7 USE OF UNDERLINING -o Underlining will be used for special emphasis. o The headings for " NOTE" and " CAUTION" shall be underlined. o Underlining shall be used to emphasize negatives. o Underlining s. hell be used to emphasize the logic terms, "If", "Then", and *When", o Underlining may be used.to emphasize connectors such as and or of when it will increase effectiveness. o Underlining may be used to emphasize other words in the procedure; however, the use of underlining should be limited so that the emphatic value is maintained. 4.8 REFERENCING AND BRANCHIW,TO OTHER PROCEDURES OR STEPS When the term " referencing" is used in connection with another procedure. it implies'that the referenced procedure will be used as a supplement to the procedure presently being used. o Referencing other sections, pages, or steps within other procedures can result in error. o Excessive forward and backward referencing within the same procedure can be confusing and can lead to skipping of steps, particularly since the referenced steps may not return the operator to the directing step. Also, important information preceding a referenced step can be missed. o If operators are required to use many procedures at the same time, there is a possibility that the referenced information may not be obtained and used or the exit point from the original procedure 4 might be forgotten. Important steps might be missed and operator delay might result. When the term " branching" is used in connection with another procedure, it signifies that the procedure being used is to be exited and the new procedure is to be used in its entirety. Branching is an acceptable method of entering another procedure and eliminates most of the problems associated with referencing. In determining whether to reference another part of the procedure for -instructions or to repeat the instructions within the procedure, consider the following factors: o If the referenced instructions can be repeated without greatly increasing the length of the procedure, repeat them. Page 7 DOCUMENT ID 00691/ .. ~.
o . Tabbing referenesd sactions too long to repeat would assist the operator in loccting tha information quickly. o If the procedure splits into two or more optional paths, references to other steps may be unaviodable. o-When multiple paths are taken from a single step, a matrix can be made that refers the operator to a procedure step tabbed with the same color as.the matrix box. Two types of procedure referencing are used in the 14A's, o one type of procedure referencing requires the operator to get out the referenced procedure, observe the precautions and limitations in the procedure, and to follow it step by step..When it is required that the operator follow the procedure this closely, he will be directed to take the action "h accordance with" the referenced procedure. An example of this kind of reference would be -- If Drywell pressure exceeds 45 psig AND Containment Radiation levels indicate 10CFR100 limits will not be exceeded Then VENT the Drywell through valve 1(2)VQO35, Drywell Vent / Purge Outlet Downstream Isolation to SBGTS in accordance with LOA-VP-03, Emergency Primary Containment Pressure Relief. In this case, if the conditional statements were satisfied, the operator would go to IDA-VP-03, follow the procedure through (even though he is still in the IDA) until he has vented the drywell M accordance with LOA-VP-03, then he would return to the 14A from which he came and find the correct steps to take next. o The other type of procedure referencing is just that - a reference. It is an aid to the operator giving him a reference for more detailed information on the task. This type of referencing is done by placing the referenced procedure in parentheses. For example -- When the RHR Shutdown Cooling interlocks clear her), INITIATE the Shutdown Cooling mode of RHR (LDP-RH-0~1) 4.9 COMPONENT IDENTIFICATION o Components identified in the 14A's shall be identified by common usage terms. The components shall be identified in the " language .of the operator." When confusion may be a problem, use the nameplate _ terminology on the control room labels. f Page 8 DOCUMNT ID 00691/
' Acronyms may be ussd in the WA*a but only whtn thsy are o univarsally undarstood by tha operators. A list of ccronyms used in the WA's'chall be,includsd in Table 1 of ths WA Writer's Guide. The Training Department shall be provided a copy of the Table 1 whenever the list is revised. 4.10 UNITS OF MEASURE l o Quantitative values should be stated within the range and accuracy of the instruments. An_ exception to this rule can be made when the common usage term does not fall within the accuracy of the instrumentation. An example of an exception would be the Tech Spec value for high drywel pressure, 1.69 psig. 1.69 psig is the setpoint the operators are trained on and is the casunon usage term for the high drywell pressure scram and isolation setpoint. 4.11 CONCURRENT ACTIONS / OVERRIDING INSTRUCTIONS o There may be events which will require the operators to be in more th'an one WA at the same time. Care must be taken to write the procedures such that the concurrent operator actions will not conflict. o There may (or may not) be instances where the operator continues past a conditional statement to subsequent procedural steps only to have the previous condition satisfied. When it is very important that the operator return insnediately to the previous step (ie - continuing with the later step may worsen the condition) and relying on the operator's memory or training is not feasible, then an " Overriding Instruction" is required. Overriding instructions shall appear on the face adjacent page to where it might apply. The overriding Instruction acts as a reminder to the operator that he needs to maintain awareness of the conditional statement in the instruction. 4.12 CONNECTORS (AND, OR) LISTS i o When a step contains more than three objects of an action, list them rather than imbedding them in a sentence. o When three or more conditions are associated with an action, list them separately ahead of the action statement. o When it is very important to connect two statements it may be best to separate the two statements vertically with AND emphasized by l capitals and underlining. For Example -- If the Suppression Pool water level can not be maintained below 26' 10" (+3") i AND adequate core cooling is assured l Then! TERMINATE injection into the reactor Page 9 DOCUMENT ID 00691/
'o -Whtn "cnds" cnd "orn" are sixtd care aust be taksn to snsure that th2 prepar combin:tions are undaretood. Usa of " ands" and " ors" is easiest to demonstrate by example. Assume there are three items A,B, and C. If we either wanted "A" or else both "B" and "C" it should be written: "A" O_R. .B" AND "C" If we wanted "A" and also wanted either "B" or "C" it should be written: "A" AND "B" OR "C" 4.13 CHECKOFF BLANKS o checkoff blanks shall be provided in the left hand margin adjacent to conditional statements were a check might help keep track of where the operator has been in the procedure. These checkoff blanks are not mandatory for the operator to complete, but are there for convenience if he thinks they will keep him on track. 4'14 CAPITALIZATION o conventional rules for capitalization shall be used except when special emphasis is warranted. o control Room indicator nameplate references shall be capitalized. o Action verbs shall be capitalized. o Acronyms shall be capitalized. o Words with a special meaning may be capitalized. An example would be NORMAL INJECTION SYSTEM. o Headings for procedure sections shall be capitalized. o Headings for CAUTIONS and NOTES shall be capitalized but the body shall use conventional upper and lower case letters. o connectors that-are used to vertically separate items shall be capitalized. _4.15 UNIT LESIGNATION Because of-the identical nature of the two units at LaSalle, the-procedures shall be written to provide guidance for both units. When equipment is identified by EPN, the unit one number shall be o listed first followed by the unit two number in parentheses. For 1 example -- "C1 HSE the RWCU isolation valves 1G33-F001(2G33-F001) and 1G33-F004(2G33-F004)." i Page 10 DOCUIENT ID 00691/ - _ _. - - - -.... - -.. ~ - -,. -,.. -.. - - -. -
o Whinivar cn op2rction21 difference b2twetn Units 1 cnd 2 cffcets th? emergincy procsdure, thtt difference shall be clearly cddresstd in the LGA. That difference shall be brought to the attention of the Training supervisor for inclusion in the LGA training. 4.16 USE OF VERBS o Verbs shall be used consistently throughout the LGA's. O REFER to TABLE 2. Action Verb List, for definitions of commonly used verbs, o If a verb is used in the WA procedure that takes on a special meaning, it should be included in TABLE 2. i i l DOCUMENT ID 00691/
TABLE 1 14A Acronym List ADS - Automatic Depressurization System CRD - Control Rod Drive CY' - Cycled Condensate BCCS - Emergency Core Cooling Sytem FW - Feedwater l GSEP - Ger.erating Stations Emergency Plan i HPCS - High Pressure Core Spray LGA - LaSalle General Abnormal LGP - LaSalle General Procedure Loh~- LaSalle' Operating Abnormal LPCI 1m Pressure Coolant Injection LPCS -' Low Pressure Core Spray MSIV - Main Steam Isolation Valve RCIC - Reactor Core Isolation Cooling RHR.- Residual Heat Removal RPV - Reactor Pressure Vessel RWCU - Reactor Water Cleanup SBGT - Standby Gas Treatment SBLC - Standby Liquid control SRV - Safety Relief Valve T.A.F. . Top of Active Fuel Page 12 DOCUMENT ID 00691/
TABLE 2 Action Varb Lint l Approach -lto continue on a trend such that a limit will be exceeded if more action is not taken to dampen the trend. Avoid - to take action to prevent something from occurring. Assure - to make certain. Check - to confirm that the desired condition or indication does exist change - to shift from one condition to another. Close - to change the physical position of a mechanical device to the CthSE position so that it prevents fluid flow or permits passage of electrical current. Continue - to maintain without interruption control - to regulate conditions such that a given parameter is maintained. Cooldown - to remove heat Decrease - DO NOT use the word " decrease". It may become confused with " increase". " Reduce" is a better word to use. Defeat - Prevent a specified action from occurring. Determine - to obtain definite first hand knowledge Depress - to push in an inward direction Depressurize - to reduc e pressure l l Divert - to change from one path to another. 1 Enter - Go to the referenced procedure. Follow the applicable steps of the reference procedure. Evacuate - to remove persons from a given area. l I Exceed - to surpass a given point. Exit - Leave this procedure. Go to referenced procedure. Increase - to make greater. Initiate - to start actions to achieve a given end. Isolate - to position a mechanical device to a position that will stop flow from one place to another. Maintain - to. keep in existing state. Page 13 DOCUIENT ID 00691/ i-
_= Monitor - to repastedly chsck iten of interest. Them item should be checked oftsn enough to notice significant changes. notify - to ensure that another person receives given information. Occur - to take place. Open - to change the physical position of a mechanical device to an unobstructive position that permits access or flow, or prevents passage of electrical current. Operate - to perform a manipulation or a series of manipulations such that a desired end is achieved. Perform - to carry out a prescribed action. Prevent - to take action to ensure that a given condition will not occur. Proceed - to go on to a desired state. Raise - to increase a parameter. Reach - to achieve a given level or magnitude. Reduce - to make smaller or decrease. Refer - to look to another source for guidance to accomplish a particular task. Restart - to reenergize a piece of equipment. Restore - to put back into original state. Return - to go back to a given point Reverse - to change direction Scram - to rapidly insert all control rods simultaneously. Shutdown - to Stop, to deenergize a piece of equipment. Stabilize - to hold steady start - to energize a piece of equipment. Terminate - to stop a function. Transfer - to switch from one place to another Trip - to activate a semi-automatic feature which will take a component out of its operating status. Vent - to permit a gas or a liquid confined under pressure to escape the confining volume. Verify - to check to ensure that the status of equipment / parameters is as indicated. If not, make it so. Page 14 DOCUMENT ID 00691/
(3) VALIDATION DESCRIPTION FOR LASALLE GENERAL ABNORMAL (LEA) SYMPTOM-BASED EMERGENCY PROCEDURES COMMONWEALTH EDISON COMPANY LASALLE COUNTY STATION SEPTEMBER 15, 1985 I r k I I i DOCUMENT ID 0554r/0008r
IRA VALIDATION PROGRAM .4 . PURPOSE A The purpose of the Emergency Operating Procedure Validation Program is to outline the, method used for determining that the actions specified in the 14A's can tse followed by Control Room Operators. to manage emergency conditions,in the plant.' p B.- REFERENCE 1. None. C. PREREOUISITES J A ', 1. None. 4 D. PRECAUTIONS 4! 1. None. E. LIMITATIONS'AND ACTION _S j 1. None. s F.. PROCEDURE y 1. Walk down the procedures at the plant to assure that the equipment , which is referenced is physically installed and usable as described in the procedures.
- ey
- Eguipment Piece Numbers are--accurate and v,isible on the equipment as shown in the procedures, b. Tools / Equipment which are required can be physically transported to necessary areas. 9 c. Equipment is. accessible when required. \\ 2. Waikdown tht; procedures using Shift Supervisors and NSO's at the BWR Cimulator to' assure understanding and usability of the procedures as written. i. 3. Comments accumulated from the walk-downs will be reviewed and incorporated in the procedures as deemed necessary. i .;) - v comments from operator training course are evaluated and incorporated 4. as deemed necessary. -n JM O. CNBCKLISTS 1. None. 4 H. TECHNICAL SPECIFICATION REFFRENCES 1. None. 3 s i 'i ' 'WI Dob M ID 0554r/0008r A.. m. ...U
'l (4) VERIFICATION DESCRIPTION FOR LASALLE GIDERAL ABNORMAL (14A) SYMPTOM-BASED EMERGENCY PROCEDURES COMMONWEALTH EDISON COMPANY LASALLE COUNTY STATION SEPTEMBER 15, 1984 l i i. l l
- DOCUMENT 205r/0004r
WA VERZFICATION e PURPOSE Assure that the new/ revised WA meets the guidelines established by the BWR Owners Group and that the revisions to the source documents have been properly reflected in the WA's. REFERENCES BOP Writers Guidelines 30P Technical Guidelines BOP Vdrification Guidelines; INPO-83-004 LIMITATIONS AND ACTIONS A Biannual review of the WA's will be conducted to assure that any changes in the source documents, Plant Systems, etc are reflected in the calculations and the procedures. Any changes to the W A's are not to affect the intent of the WA's verifiers will be chosen based on familiarity of the W A's as well as general plant knowledge. Licensed individuals are preferrable. PRECAUTIONS Changes to equipment, operating limits, experience data, etc. could affect calculations and/or validity of the procedures. PROCEDUR8 1. Obtain copies of the reference documents used in preparing / revising the particular Emergency Operating Procedure (LGA). 2. Review the reference documents to assure the most recent revisions were used, a. If the documents are not the latest revision or data is known to be outdated, inform the Office Supervisor and take necessary actions to up-date the documents, b. If more recent data could affect the calculations, have new calculations completed. Check the calculation sununary page to assure they were computed and reviewed by two people. c.- Calculations determining limiting parameters will be maintained ) in Central File. These calculations will be completed by one engineer and checked independently by a second engineer. This double check will be documented and maintained with the i calculations. j 1 DOCUMENT 205r/0004r
3. Riview the procedure for general written CorrECtniss format. e brcnching cnd gInirol understandibility cs outlintd in tha 1.aSalle Writers Guidelines (LWG's). 4 4. Conduct a step-by-step review of the procedure to assure it meets the requirements of the LaSalle Writers and Technical Guidelines. a. Entry Conditions and symptoms. b. Proper component / instrument identification c. Quantitative units with tolerances which are obtainable on Control Room and plant instruments. d. Equipment required is available for use (Modifications have not eliminated) e. Calculations to be done by operators have proper equations provided. f. Deficiency sheets documenting deviations from guidelines are provided and are adequately resolved. 5. Sign and Date the Verification completion Form and forward the procedure and verification package to the Procedure Manager for tracking. 6. The Procedure Manager records the procedure status and forwards to the Department Head.
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The Department Head reviews the package to assure resolutions to discrepancies and required actions from the verification process have been completed. He signs and dates the verification form and the on Site Revicw portion of LAP-820-2 and forwards to the next person on On Site Review. 8. When the Station Superintendent signs for Final Approval, he also signs the II,A Verification Approval. DOCUMENT 205r/0004r
Pagt of LGA VERIFICATION 14A NUMBER REVISION TITLE Scope of Verification: Rsference Documents A' signed Evaluator (s) LVG STEP DESCRIPTION ACCEPTABLE DISCREPANCY DATE/ INITIAL SHEET S l 2 Reference Document Review 3 Written Correctness Legibility Format Identification l l l i. DOCUMENT 205r/0004r l I
If,A VERIFICATION liiA PAGE of Stcp by Step Review j Stcp Written correctness Technical Correctness caution, or Acceptable Discrepancy Resolved Acceptable Discrepancy Resolved Note 8 Init/Date Number Date/ Initial Init/Date Number Date/ Initial DOCUMENT 205r/0004r
1EsA VERIFICATION Required Actions: i Conducted By / / / NAMES DATE Deficiences and Required Actions are adequately resolved and procedures are acceptable for use / DEPARTMENT HEAD DATE / SUPERINTENDENT DATE DOCUMENT 205r/0004r ... ~ - - -
1 Ji ( *$ 3 / r p. TRAINING DESCRIPTION FOR LASALLE GENERAL ABNORMAL (IAA) SYMPTOM-BASED EMERGENCY PROCEDURES ) COPMONWEALTH EDISON COMPANY LASALLE COUNTY STATION SEPTEMBER 15, 1984
? Trcining Description for LaSalle Genarol Abnormal (LGA) Symptom-bassd EmargEncy Procsdures - PORWARD - The following text describes the training process LaSalle Station plans to use for implementing a revision to the LGA's. It is important to realize that symptom-based emergency procedures are not new to the LaSalle licensed operator: LaSalle was the first plant to implement emergency procedures based upon the symptom-oriented Emergency Procedure Guidelines published by the BWR Owners Group. During 1981 LaSalle licensed personnel and license candidates were given one week of concentrated training on the new, symptom-oriented emergency procedures (LGA's). LaSalle Unit I has been safely operated using the upgraded LGA's since the operating license was received in April of 1982. Unit 2 has been safely operated throughout the startup test program using the LGA's. LGA training was included in the License Requalification Program in both 1983 and 1984. The LaSalle licensed operator has already been trained on, and is using the symptom-oriented procedures mandated by NURBG 0737. The guidelines on which the LGA's were based have been revised to incorporate reactivity control, secondary containment control, and radioactive release control. Consequently, the LGA procedures are being revised to reflect these changes. Since the reactivity control changes increase the complexity of the procedures, a significant training j effort is planned. The following text describes the training program which LaSalle plans to use to train licensed operators on the revised procedure. It should be noted that this training description is as we 1 plan it in September 1984. There may be content or structure changes to the program if these changes will further our goal towards safe and practical operations of the LaSalle County Units 1 and 2. INTRODUCTION The revised LGA training will consist of a Classroom Training session and ,~ a Practical Training session. The two sessions together should provide the trainee with the information necessary to obtain the objectives. The - training will be provided for RO and SRO licenseholders at LaSalle. The operating crew members shall receive the training before performing licensed shift duties under the revised procedures. LGA LEARNER OBJECTIVES State from memory the entry conditions for Level control, containment control, and Reactivity Control. Locate Control Room instrumentation that monitor parameters which are LGA entry conditions. j Determine when the LGA's may be exited to normal operating procedures. Discuss the basic flowpath for Alternate Shutdown Cooling. Given tne graph, discuss the basic reasons for taking actions when any of the parameters reach limits defined by graphs in the LGA's. DOCUMENT ID 00671/ l L'
Givin-th2 cppropriate graph and appropristo plcnt paramaters, datornint whether limita d2finsd by graphs in tha LGA's cre being approrchsd or exceeded. f Define any acronyms used in the LGA's. Discuss any instrumentation / procedure differences between U-1 and U-2 that impact upon the 14A's. Discuss the alternate methods for shutting down the reactor. Using the LGA's, simulate the operator's actions required to shutdown the ) reactor given a failure to scram. j Using the LGA's, simulate the operator's actions required to maintain adequate core cooilng given a postulated transient with coincident equipment failure. Discuss each General Precaution outlined in LGA-T1. Discuss selected Cautions using the LGA procedures. Using the LGA's, simulate the operator's actions required to maintain primary or secondary contanment parameters within limits. CLASSROOM TRAINING SESSION, Each licensed operator shall receive classroom training on the LGA's. This classroom training will be considered complete when the licensed operator scores 80% or above, on the written LGA examination. Additional training will be required if the trainee scores below 80% on the written examination. The test questions should reflect the intent of the LGA learner objectives. The classroom training session should take approximately three days. A typical day would be comprised of four hours of lecture, two hours of discussion and two hours of self study. Two hours will be allotted on the final day of training for the LGA examination. The student materials for the course shall include: l LGA Student Handout LGA procedure available for reference LGA Flowchart available for a graphic representation of procedural flowpath. l The LGA student handout will contain two major sections - an introductory section and a procedural step explanation section. l INTRODUCTION - Will include an overview of the revised procedural structure and a review of how to follow the LGA's. This introduction will encompass the following topics: - General Procedure Layout - Logic Terms l - Use of General Precautions DOCUMENT ID 00671/
.- U o of Stcp Spscific Crutions e - U;2 of Proceduro SpIcific Clutions - Action Verbs l - Special Definitions - Entry and Exit of the LGA's - Use of Accompanying Support Procedures PROCEDURAL STEP EXPLANATION - will cover each procedure and explain why operator actions are taken. This will be accomplished by dissecting the procedures into major subsections and explaining each evolution. PRACTICAL TRAINING Each licensed operator shall receive practical training on using the LGA's. The practical training will include a simulation of postulated transients which will require entry into each LGA. This training will normally be conducted on the LaSalle simulator. Two 4-hour shifts will be scheduled for LGA simulator training for each license holder. Under special circumstances, an actual control room walkthrough may be substituted for the simulator training to fulfill the practical training requirement. This special substitution must be approved by the Training Supervisor before it will be allowed. FEEDBACK LOOP Each trainee shall be provided with a feedback form as a means of collecting input from the license holders not only on the course but on the procedures themselves. This feedback will be considered for changes to the lesson plans and appropriate comments will be forwarded to the Operating Department procedure writers. DOCUMENT ID 00671/ -}}