ML20198J084
| ML20198J084 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/08/1986 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20198J081 | List: |
| References | |
| PROC-860108, NUDOCS 8601310174 | |
| Download: ML20198J084 (69) | |
Text
{{#Wiki_filter:} HOPE CREEK GENERATING STATION 9 PLANT SPECIFIC TECHNICAL GUIDELINES January 8, 1986 Revision 1 8601310174 860128 4 DR ADOCK 0500
OPERATOR PRECAUTIONS GENERAL This section lists " Cautions which are generally applicable at all times. CAUTION #1 Monitor the general state of the plant. If an entry condition for an Emergency Operating Procedure occurs, enter that procedure. i e CAUTION #2 Monitor RPV water level and pressure and primary containment temperatures and pressure from multiple indications. CAUTION #3 If a safety function initiates automatically, assume a true initiating event has occurred unless otherwise confirmed by at least two independent indications. CAUTION #4 Whenever RHR is in the LPCI mode, inject through the heat exchangers as soon as possible. 1
CAUTION #6 If drywell temperature exceeds 135*P use only channels A and B of the wide, narrow and upset RPV water level instruments. CAUTION #8 Observe NPSH requirements for pumps taking a suction on the suppression pool. CAUTION #9 If signals of high suppression pool water level (81 1/2 inches) or low condensate storage tank water level (3.6%) occur, confirm automatic transfer of or manually transfer HPCI and RCIC suction' from the condensate storage tank to the suppression pool. l SPECIFIC This section lists " cautions" which are applicable at one or more specific points within the guidelines. Where a " caution" is applicable, it is identified with the symbol #. CAUTION #10 Do not secure or place an ECCS in MANUAL mode unless, by at least two independent indications, (1) misoperation in AUTOMATIC mode is confirmed, or (2) adequate core cooling is assured. If an ECCS is placed in MANUAL mode, it will not initiate automatically. Make frequent checks of the initiating or controlling parameter. When manual operation is no longer required, restore the system to AUTOMATIC / STANDBY mode if possible. 2
CAUTION #11 If a high drywell pressure ECCS initiation signal 1.68 psig occurs or exists while depressurizing, prevent injection from those Core Spray and LPCI pumps not required to assure adequate core cooling prior to reaching their maximum injection pressures. When the high drywell pressure ECCS initiation signal clears, restore Core Spray and LPCI to AUTOMATIC / STANDBY mode. CAUTION #12 Do not throttle HPCI below 2500 rpm or RCIC below 2150 rpm. 1 t CAUTION #13 Cooldown rates above 100*F/hr may be required to accomplish this step. CAUTION #14 Do not depressurize the RPV below 100 psig unless motor driven pumps sufficient to maintain RPV water level are running and available for injection. CAUTION #15 Open SRVs in a sequence which will distribute heat uniformly throughout the suppression pool if possible. CAUTION #16 Bypassing low RPV water level MSIV isolation interlocks may be required to accomplish this step. 3
CAUTION #17 Cooldown rates above 100'F/hr may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive release to the environment. CAUTION #18 If continuous LPCI operation is required to assure adequate core cooling, do not divert all RIIR pumps from LPCI mode. CAUTION #19 Confirm automatic trip or manually trip SLC pumps at 325 gallons 3 e in the SLC tank. CAUTION #20 Defeating RSCS interlocks may be required to accomplish this step. CAUTION #21 Elevated suppression chamber pressure may trip the RCIC turbine on high exhaust pressure. CAUTION #22 Defeating isolation interlocks may be required to accomplish this step. 4
CAUTION #23 Do not initiate drywell sprays if suppression pool level is above ! 142.5 in. CAUTION #24 s Bypassing high drywell pressure and low RPV water level secondary containment HVAC isolation interlocks may be required to accomplish this step. CAUTION #25 A rapid increase in injection into the RPV may induce a large i t power excursion and result in substantial core damage. ' CAUTION #26 Large reactor power oscillations may be observed while executing this step. l i I 5
l I RPV CONTROL GUIDELINE i l PURPOSE The purpose of this guideline is to: o Maintain adequ&te core cooling, and o Shut down the reactor. ENTRY CONDITIONS The entry conditions for this guidelines are any of the following: o RPV water level Delow -38 inches or undetermined 2 o RPV pressure above 1037 psig o Drywell pressure above 1.68 psig o A condition which requires reactor scram, and reactor power above 5% or cannot be determined OPERATOR ACTIONS RC-1 If reactor scram has not been initiated, initiate reactor scram. Insert SRMs and IRMs l Irrespective of the entry condition, execute Steps RC/L, RC/P, and RC/O concurrently. I I 6
RC/L Monitor and control RPV water level. RC/L-1 Initiate each of the following which should have initiated, but dic' not: o Any Isolations o ECCS o Emergency diesel generator .
! l If while executing the following steps:
o Boron Injection is required or boron injection has been initiated into the RPV, enter OP-EO.ZZ-207(0) o RPV water level cannot be determined, RPV FLOODING IS REQUIRED; enter OP-EO.ZZ-202(Q) in preparation for RPV flooding o RPV Flooding is required, enter OP-EO.ZZ-206(0) I I 7
RC/L-2 Restore and maintain RPV water level between #9
+12.5 in. and +54 in. with one or more of the #10 following systems: #11 o Condensate system 720 - O psig o Feedwater system 1250 - 720 psig o CRD system 1500 - O psig o RCIC system 1250 - 65 psig #12 o HPCI system 1250 - 100 psig o Core Spray 380 - O psig o LPCI system 340 - O psig i e
s If RPV water level cannot be restored and maintained above +12.5 in., maintain RPV water level above top of active fuel. If RPV water level can be maintais.ed above top of active fuel and the ADS timer has initiated, prevent automatic RPV depressurization by resetting the ADS timer. l l If RPV water level cannot be maintained above top of active fuel, enter OP-EO.ZZ-201(Q) I l 8
RC/L-3 Restore and maintain RPV water level above above top of active fuel; return to noraml when possible, exit RC/L RC/P Monitor & Control RPV Pressure I l If while executing the following steps: o Emergency RPV Depressurization is #13 anticipated and Boron injection is not required, rapidly depressurize the RPV u s with the main turbine bypass valves. o Emergency RPV Depressurization or RPV Flooding is required and less than 5 SRVs are open, enter OP-EO.ZZ-202(0). o RPV Flooding is required and at least 5 SRVs are open, enter OP-SO.ZZ-206(Q). l I l o Restore Primary Containment Instrument Gas. 9
4 t RC/P-1 If any SRV is cycling, manually open SRVs until RPV pressure drops to 935 psig. l If while executing the following steps: o Suppression Pool temperature cannot be #8 maintained below the Heat Capacity #13 Temperature Limit, maintain RPV pressure #14 l below the Limit. o Suppression pool level cannot be
#13 l maintained below the Suppression Pool
#14 l Load Limit, maintain RPV pressure below l
the Limit. l o Steam Cooling is required, enter OP-EO.ZZ-203(Q) I I Maintain Condenser Vaccum 10
l l If while executing the following steps: o Boron injection is required, and o The main condenser is available, and o There has been no indication of gross fuel failure or steam line break, Then open MSIVs to re-establish the main #16 condenser as a heat sink. l l 1 RC/P-2 Control RPV pressure below 1037 psig with #14 o the main turbine bypass valves. RPV pressure control may be augmented by one or more of the following systems: o SRVs only when suppression pool level is #15 above 0 in. If the continuous SRV pneumatic supply is or becomes unavailable, place the control switch for each SRV in the (CLOSE) position a HPCI l#12 o RCIC o SJAE 11
4 o RFPT 4 o RWCU (recirculation mode) if no boron has been injected into the RPV. o Main steam line drains _ o RWCU (blowdown mode) is no boron has been i i injected into the RPV. Refer to sampling - procedures prior to initiating blowdown. f j RC/P-3 When either: i o All control rods are inserted to or beyond , position 02, or i o 690 pounds of boron have been injected into
'the RPV, or 7 o The reactor is shutdown and no boron has been injected into the RPV, Exit OP-EO.ZZ-101(Q) and Enter OP-EO.ZZ-099(0)
- RC/P-4 This step appears in the Post Scram Recovery Guidelines.
RC/P-5 This step appears in the Post Scram Recovery , Guidelines. 4 12
RC/O Monitor and ccntrol reactor power.
! l If while executing the following steps:
1 o All control rods are inserted to or beyond l , position 02, terminate boron injection and l exit RC/Q. l o The reactor is determined to be shutdown and no boron has been injected into the RPV, exit RC/Q. I J RC/Q-1 Confirm or place the reactor mode switch in SHUTDOWN. RC/Q-2 If the main turbine-generator is on-line, confirm or initiate recirculation flow runback to minimum. RC/Q-3 If reactor power is above 5% or cannot be determined, trip the recirculation pumps. I I ExecuteStepsRC/Q-4andRC/Q-5 concurrently.l 1 1 13
,, z _. _ __. . . . . _ ~ . _ ._ .. . ._..-.... . _.. _ - . . . ~ . _ . . . . . . _ . .
RC/Q-4 If the reactor cannot be shutdown before #19 i suppression pool temperature reaches 110*F. I ' BORON INJECTION IS REQUIRED; inject boron into l I the RPV with SLC and prevent automatic 1 initiation of ADS. I l If boron cannot be injected with SLC, inject boron into the RPV by one or both of the following alternate methods: ' o CRD ' o RWCU RC/Q-4.1 If boron is not being injected into the RPV by RWCU, confirm automatic isolation of or manually isolate RWCU. i
- RC/Q-4.2 Continue to inject boron until 690 pounds of boron have been injected into the RPV.
RC/Q-4.3 Exit RC/O ' l 1 l RC/Q-5 Insert control rods as follows: RC/Q-5.1 If any scram valve is not open: I I
- o De-energize the scram solenoids using ,
OP-EO.ZZ-302(O) , f 9 l 14
~ , - - - . , . -.-r, - . - - , - - , , . . -n... ,,., . ,--.--w
o Isolate and vent the scram air header usig OP-EO.22-306(0) When control rods are not moving inward; restore systems to normal RC/Q-5.2 Reset the reactor scram. If the reactor scram cannot be reset continue in this procedure at Step i RC/0-5.5. , i i RC/Q-5.3 Drain the scram discharge volume, i verify /cpen BF-V045 and initiate a manual reactor scram, <
- 1. If contrel rods moved ir; ward, return to ;
Step RC/0-5,2. ;
- 2. Reset the reacter scram.
i i If the reactor scram cannot be resot, continue in this procedure at Step RC/0-5.5. [
- 3. Open the scram discharge volume vent I and drain valves.
15
RC/0-5.4 Individually scram the control rods not inserted to or beyond position 02 using OP-EO.22-303(Q). When a control rod is not moving i nwa rd , terminate individual rod scram. RC/0-5.5 Manually insert control rods as follows, I l
, If while executing the following steps the Reactor Scram can be reset and ,
1 control rods moved ir; ward following the I last scram, reset theReactorScramandl return to Step RC/Q-5.3. . I l ? 4 i
- 1. Start all CRD pumps.
If no CRD pump can be' started, continue in this procedure at Step RC/O-5.5.4.
- 2. Close BF-V045 defeat RSCS and RWM. ,
r
- 3. Rapidly insert control rods manually. #20 I
i i 16 .
-_ _ ~
- 4. If any centrcl red cannot be inserted to or beyond position 02. Individually I
direct the effluent from the CRD withdraw line vent valve to a contained radwaste drain and open the CRD Withdrav line vent valve for that { Centrol Rod until it is cct moving l ! ir.vard. l k , l i ) l l i i ( 17
PRIMARY CONTAINMENT CONTROL GUIDELINE PURPOSE The purpose of this guideline is to: c Maintain primary containment integrity, and o Protect equipment in the primary ccntainment. ENTRY CONDITIONS The entry conditions for this guidelines are any of the follcwings o Suppression pool temperature above 95'F o Drywell temperature above 135*P o Drywell pressure above 1.68 psig o Suppression pool level above 78.5 inches 1 o Suppression pool level belcw 74.5 inches OPERATOR ACTIONS I l Irreepective of the entry condition, execute Steps SP/T, DW/T, lPC/P, and SP/L concurrently. l 1 l l l I 18 l I
SP/T Monitor and control suppression pool temperature. SP/T-1 Close all Stuck Open Relief Valves (SORV's) If any SORV cannot be closed within 2 minutes, scram the reactor. SP/T-2 When suppression pool temperature exceeds '#18 95*F, operate available suppression pool cooling. If at anytime a scram occurs before suppression pool temperature can be restored and maintained below 95'F, then perform OP-DL.Z2-026 Attachment 3G.
+
Before suppression pool temperature reaches 105*F, terminate testing of HPCI and RCIC and close any open SRVs. SP/T-3 Before suppression pool temperature reaches 110*F, scram the reactor. Maintain suppression pool temperature below 120*F, if Suppression pool temperature cannot be maintained below 120*F depressurize the reactor. If suppression pool temperature can be maintained below 120*F, return to below 95'F. 19
SP/T-4 If suppression pool temperature cannot be #8 ! maintained below the Heat Capacity Temperature #13 Limit, maintain RPV pressure below the Limit. l#14l If suppression pool temperature and RPV pressure cannot be maintained below the HCTL, Emergency Depressurization is required. Enter OP-EO.ZZ-202(O) and execute concurrently. I DW/T Monitor and control drywell temperature.
#6 DW/T-1 When drywell temperature exceeds 135'F, operate available drywell cooling.
If drywell air cooler inlet temperature cannot be maintained below 200*F then runback recirculation pumps, manually scram and enter 1 1 OP-CO.ZZ-100(0) and execute it concurrently with this procedure. DW/T-2 Incorporated into Caution #6 i 48' L#18 DW/T-3 Before drywell temperature reaches 340*F but #23 I only if suppression chamber temperature and suppression chamber pressure are below the Drywell Spray Initiation Pressure Limit, shut l
- down recirculation pumps and drywell ecoling <
i 1 ! fans and initiate drywell sprays at rated ficw I with one loop. 1 l 20
L If drywell temperature cannot be maintained below 340*F, EMERGENCY RPV DEPRESSURI2ATION IS REQUIRED; enter OP-EO.ZZ-202(O) and execute it i concurrently with this procedure.
- PC/P Monitor and control primary containment pressure. .
[ If drywell pressure can be maintained below 1.68 psig then return to Step PC/P. ! t PC/P-1 Operate the following systems, as required: , o Containment Atmosphere Control systems. , o FRVS, only when the temperature in the space #21 being evacuated is below 212*F. PC/P-2 Before suppression chamber pressure reaches l #8 14.8 psig, but only if suppression pool level #18 is below 180 in., initiate suppression chamber sprays. t PC/P-3 If suppression chamber pressure exceeds 14.8 #18 psig but only if suppression chamber ' temperature and suppression chamber pressure are below the Drywell Spray Initiation Pressure Limit, shut down recirculation pumps ; and drywell cooling f ans and initiate drywell sprays at rated flow with one loop. 21 L _ _ _ _ , _ . - _ _ - _ , -
PC/P-4 If suppression chamber pressure cannot be maintained below the Pressure Suppression Pressure, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. PC/P-5 If suppression chamber pressure cannot be maintained below 57.2 psig, RP'V FLOODING IS REQUIRED. PC/P-6 If suppression chamber pressure cannot be maintained below 65 psig, then irrespective of whether adequate core cooling is assured: If suppression pool level is below 180 inches initiate suppression chamber sprays. If suppression chamber temperature and suppression chamber pressure are below the Drywell Spray Initiation Pressure Limit, shutdown recirculation pumps and drywell cooling fans and initiate drywell sprays at rated flow with one loop. #22 PC/P-7 If suppression chamber pressure exceeds 65 psig then irrespective of the off-site Radioactivity Release Rate, vent the primary containment to reduce and maintain pressure below 65 psig. 22
SP/L' Monitor and control suppression pool level. 1 SP/L-1 Maintain suppression pool level between 74.5 #8,#9 in and 78.5 in. Refer to sampling procedure prior to discharging water. If suppression pool level cannot be maintained above 74.5 in., execute Step SP/L-2. If suppression pool level cannot be maintained below 78.5 in., execute Step SP/L-3. S P/ L-2 SUPPRESSION POOL LEVEL BELOW 74.5 in. Maintain suppression pool level above the Heat Capacity Level Limit. i If suppressigt &4- L level cannot be maintained above the n;<at G pacity Level Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter I OP-EO.22-202(O) and execute it concurrently with this procedure. f Maintain suppression pool level above 47 inches if suppression pool level cannot be maintained above 47 inches manually scram the Reactor and establish suppression chamber spray. 23
If the combination of suppression pool level and temperature cannot maintain NPSH for pumps taking a suction on the suppression pool, then line up and inject from systems which take a suction external to containment. Then secure all pumps that take a suction internal of containment. SP/L-3 SUPPRESSION POOL LEVEL ABOVE 78.5 in. l l Execute Steps SP/L-3.1 and SP/L-3.2 concurrently l ' l l SP/L-3.1 Maintain suppression pool level below the Suppress Pool Load Limit.
#13l If suppression pool level cannot be l#14 maintained below the Suppression Pool Load Limit, maintain RPV pressure below the Limit.
If suppression pool level and RPV pressure cannot be maintained below the Suppression Pool Load Limit but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron i injection systems and CRD. 24
1 If suppression pool level and RPV pressure cannot be maintained below the Suppression Pool Load Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter OP-EO.ZZ-202(0) and execute it concurrently with this procedure. S P/ L-3 . 2 Before suppression pool level reaches 142.5 in. but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron injection systems and CRD. l#18
- 1. When suppression pool level reaches 142.5 in. but only if suppression chamber temperature and suppression chamber pressure are below the Drywell Spray Initiation Pressure Limit shut down recirculation pumps and drywell cooling fans and initiate drywell sprays at rated flow with one loop. #23
- 2. If suppression pool level exceeds 142.5 in., continue to operate drywell sprays.
25
- 3. When primary containment water level reaches 93 ft., terminate injection into the RPV from sources external to the primary containment irrespective of whether adequate core cooling is assured.
l I 26
REACTOR BUILDING CONTROL GUIDELINE PURPOSE The purpose of this guideline is to: o Protect equipment in the Reactor Building, o Limit radioactivity release to the Reactor Building, and either: o Maintain Reactor Building integrity, or o Limit radioactivity release from the Reactor Building ENTRY CONDITIONS The entry conditions for this guideline are any of the following Reactor Building conditions: o Reactor Building differential pressure at or above 0 in. of water l o Reactor Building Temperature above Table 1 Column 1 o Reactor Building Local Radiation Monitor alarm o Reactor Building floor level above Table 2 Column 1 27
OPERATOR ACTIONS I I If while executing the f ollowing steps Reactor Building Ventilation exhaust radiation level exceeds 3 x 10-2 uci/cc: o Confirm or manually initiate isolation of Reactor Building Ventilation System, and o Confirm initiation of or manually initiate FRVS only when the space being evacuated is below 212*F.
- l. j I
I If while executing the following steps: o Reactor Building Ventilation System isolates, and o Reactor Building Ventilation exhaust radiation level is below 3 x 10-2 uci/cc l l Then restart Reactor Building Ventilation System #24 I I l Irrespective of the entry condition, execute Steps SC/T, SC/R, and SC/L concurrently. I I 28
3 SC/T Monitor and control Reactor Building temperatures. SC/T-1 Operate available area coolers. SC/T-2 If Reactor Building Ventilation exhaust radiation level is below 3 x 10-2 uci/cc operate available Reactor Building Ventilation fans. 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 fire. SC/T-4 If a primary system is discharging into an area, then before any area temperature reaches its maximum safe operating temperature, manually scram, enter OP-EO.ZZ-100(O) 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 operating tempera tu re in more than one area, EMERGENCY RPV DEPRESSURIZATION l IS REQUIRED. 29
If a fire is in progress and it is not under control, then continue fire suppression efforts. If a fire is in progress in an area and an
.\
area temperature exceeds its maximum safe l operating temperature in more than one area then Normal RPV depressurization is required. SC/R Monitor and control Reactor Building radiation levels. I SC/R-1 If any area radiation level exceeds its maximum normal operating radiation level, isolate all systems that are discharging into the area except systems required to shutdown the reactor, assure adequate core cooling, or suppress a fire. SC/R-2 If a primary system is discharging into an area, then before any area radiation level reaches 25 REM estimated dose for required area entry, manually scram enter OP-EO.ZZ-100(Q) and I execute concurrently with this procedure. SC/R-3 If a primary system is discharging into an area and an area radiation level exceeds 25 REM estimated dose for required area entry in more than one area, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. 30
SC/L Monitor and control Reactor Building water levels. SC/L-1 If any 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 area water level cannot be restored and maintained below its maximum normal operating water level, isolate all systems that are I j discharging water into the area except systems i required to shut down the reactor, assure adequate core cooling, or suppress a fire. SC/L-2 If a primary system is discharging into an area, then before any area water level reaches t-its maximum safe operating water level, manually scram enter OP-EO.ZZ-100(O) and execute it concurrently with this procedure. SC/L-3 If a primary system is discharging into an area and an area water level exceeds its maximum safe operating water level in more than one division, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. 31
TABLE 1 AREA DESCRIPTION COLUMN 1 COLUMN 2
& ROOM NUMBER Max Normal Op Temp Max Safe Op Temp CRD Pump Room Il5*F 140 F (4202)
RACS Pump Room (4209) ll5*F 140 F
& Hx Room (4211)
HPCI ll5*F 250*F (4111) Core Spray . Pump Rooms ll5*F 140*F A(4118) & C(4116) RHR Pump Rooms 115aF , 140*F A(4113 & C(4114) SACS 115 P 140*F A& C (4309) RCIC Pump Room 115*F 250*F (4110) Core Spray Pump Rooms ll5*F 140aF B(4104 & D(4105) RHR Pump Rooms ll5*F 140*F B ( 410 9) & D(4107) SACS ll5'F 140*F B& D (4307) I l l l 32
TABLE 2 AREA DESCRIPTION COLUMN 1 COLUMN 2
& ROOM NUMBER Max Normal Floor Max Safe Floor Level Level CRD Pump Room 4 1/2 inches (4202) 1 inch (25 min cont runtime) l RACS Pump Room (4209) 4 1/2 inches j
& Hx Room (4211) 1 inch (investigate)
D HPCI 4 1/2 inches I (4111) 1 inch (30 min Cont runtime) V I Core Spray Pump Rooms 4 1/2 inches S A(4118) & C(4116) 1 inch (15 min Cont runtime) I O RHR Pump Rooms 4 1/2 inches N A(4113 & C(4114) 1 inch (20 min Cont runtimo) SACS I 4 1/2 inches A& C (4309) 1 inch (investigate) D RCIC Pump Room 4 1/2 inches I (4110) 1 inch (17 min Cont runtime) V I Core Spray Pump Rooms 4 1/2 inches S B(4104) & D(4105) 1 inch (15 min Cont runtime) I O RilR Pump Rooms 4 1/2 inches N B ( 410 9) & D(4107) 1 inch (20 min Cont runtime) l II SACS 4 1/2 inches B& D (4307) 1 inch (investigate) l l l 33
RADIOACTIVITY RELEAS' CONTROL GUIDELINE PURPOSE The purpose of this guideline is to limit radioactivity release into areas outside the primary containment and Reactor Building. ENTRY CONDITIONS The entry conditions for this guideline is: o Offsite radioactivity release rate above the offsite release rate which requires an Alert. OPERATOR ACTIONS If testing or the radwaste area are the source of the release, then terminate the release and restore the radioactivity release rate below the Alert level. RR-1 Isolato all primary systems that are discharging into areas outside the primary containment and Reactor building except systems required to assure adequate core cooling or shut down the reactor. RR-2 If offsite radioactivity release rate approaches or exceeds the offsite release rate which requires a General Emergency and a primary systen. is discharging into an area outside the primary containment and Reactor building, EMERGENCY RPV DEPRESSURI2ATION IS REQUIRED; enter OP-EO.ZZ-202(0) and i execute it concurrently with this procedure. l Place MSIV sealing system in operation. 34
CONTINGENCY #1 LEVEL RESTORATION I I If while executing the following steps: o Baron Injection is required or boron injection has been initiated into the RPV, enter OP-EO.ZZ-207(Q) l o RPV water level cannot be determined, RPV FLOODING IS l REQUIRED; enter OP-EO.ZZ-202 in preparation for RPV flooding l o RPV flooding is required, enter OP-EO.ZZ-206(Q) I l Cl-2 Line up for injection and start pumps in 2 or more of the following injection subsystems: o Condensate o LPCI-A o LPCI-B o LPCI-C o LPCI-D o Core Spray - A o Core Spray - B 35
If less than 2 of the injection subsystems can be lined up, commence lining up as many of the following alternate injection subsystems as possible: o Service water o Fire system o ECCS keep-full systems o SLC Cl-3 Monitor RPV pressure and water level. Continue in this i procedure at the step indicated in the following table. RPV PRESSURE REGION (380 psig) (100 psig) l l l l HIGH l INTERMEDIATE LOW l RPV INCREASING Cl-4 Cl-5 Cl-6 l LEVEL I DECREASING Cl-7 Cl-8 l I l l 36
l If while executing the following steps: o The RPV water level trend reverses or RPV pressure changes region, return to Step Cl-3. o RPV water level drops below -129 in. , prevent automatic l l initiation of ADS. I l Cl-4 RPV WATER LEVEL INCREASING, RPV PRESSURE HIGH Enter OP-EO.ZZ-101(Q) at (Step RC/L) Cl-5 RPV WATER LEVEL INCREASING, RPV PRESSURE INTERMEDIATE If HPCI and RCIC are not available and RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is decreasing, enter OP-EO.ZZ-101(Q) at Step RC/L. If HPCI and RCIC are not available and RPV pressure is not increasing, enter OP-EO.22-101(Q) at step RC/L. L 37
Cl-6 RPV WATER LEVEL INCREASING, RPV PRESSURE LOW If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. When RPV pressure is f i decreasing, enter OP-EO.ZZ-101(Q) at Step RC/L. Oth e rw is e , enter OP-EO.ZZ-101(Q) at Step RC/L. Cl-7 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH OR I INTERMEDIATE If HPCI, RCIC or CRD is not operating, restart whichever is not operating. If no injection subsystem is lined up for injection with at least one pump running, start pumps in alternate injection subsystems which are lined up for injection. When RPV water level drops to Top of Active Puel: o If no injection subsystem or alternate injection j 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 Step Cl-3.
; o Otherwise, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED.
When RPV water level is increasing or RPV pressure drops i below 100 psig, return to Step Cl-3. 'l f 38
.- - _ . , _ . - . _ . . ~ _ , _ . - _ _ _ . . __r- . . , . . . , , __ _ ...._ ._ _ _ _ _ . . - . , _ . _ . _ _ . _ . . _ _ . . , ,. - . . _ _ _ _ _ , , _ _ , _ . .
Cl-8 RPV WATER LEVEL DECREASING, RPV PRESSURE LOW If no Core Spray injection subsystem is operating, start pumps in alternate injection subsystems which are lined up for injection. If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. 1 I l When RPV water level drops to top of active fuel enter OP-EO.ZZ-204(O) l I 39
CONTINGENCY #2 EMERGENCY RPV DEPRESSURIZATION If the reactor is not scrammed, then manual scram, enter OP-EO.ZZ-100(Q) and execute concurrently. C2-1 When either: 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, or o All rods are inserted to or beyond position 02. C2-1.2 If suppression pool water level is above 0 inches
#13, 14 o Open all ADS valves o If any ADS valve cannot be opened, open other SRVs until 5 valves are open.
40 ,
C2-1.3 If less than 3 SRVs are open and RPV pressure is at least 50 psig above suppression chamber pressure, rapidly depressurize the RPV using one or more of the following systems: #22 o Main condenser t o Main steam line drains o HPCI steam line o RCIC steam line o Head vent o RFPT o SJAS I I If RPV Plooding is required, enter OP-EO.ZZ-206(0)
- 1. I C2-2 Enter OP-EO.ZZ-101(Q) at Step RC/P-3 41
r CONTINGENCY #3 STEAM COOLING I I If while executing this step Emergency RPV Depressurization is required or any system, injection subsystem, or alternate injection subsystem is lined up for injection with at least one pump running, enter OP-EO.ZZ-202(O). 1 I When RPV dater level drops to -115.26 inches on the fuel zone indication or if RPV water level cannot be determined, open one SRV. I I I When RPV pressure drops below 700 psig enter OP-EO.ZZ-202(Q) I I 42
n CONTINGENCY #4 CORE COOLING WITHOUT LEVEL RESTORATION I I 4 If while executing the fo11ceing steps boron injection is a required or baron injection has been initiated into the RPV ( i enter OP-EO.22-207(0). I J C4-1 Open all ADS valves "413 i If any ADS valve cannot be opened, open other SRVs until 5 valves are open C4-2 Operate Core Spray subsystens with suction f rom the suppression pool. When at least one core spray subsystem is operating with suction from the suppression pool and RPV pressure is below 242 psig terminate injection into the RPV from sources external to the primary containment except CRD. Continue injection f rom all sources that take a suction internal to primary containment. C4-3 When RPV water level is restered to top of active fuel, OP-EO.ZZ-101(O), enter at Step RC/L 43
CONTINGENCY #5 ALTERNATE SHUTDOWN COOLING C5-1 Initiate suppression pool cooling. C5-2 Close the RPV head vents, MSIVs, main steam line drain valves, and HPCI and RCIC isolation valves. ! CS-3 Place the control switch for two SRVs in the OPEN position. i l l C5-4 Slowly raise RPV water level to establish a flow path through the open SRVs back to the suppression pool. Terminate and prevent all injection into the RPV except from CRD. C5-5 Start one CS Subsystem or one LPCI pump with suction from the suppression pool. C5-6 Slowly increase CS or LPCI injection into the RPV to the maximum. C5-6.1 If RPV pressure does not stabilize at least 50.2 psig above suppression chamber pressure, start another CS or LPCI pcmo. C5-6.2 If RPV pressure does not stabilize below 140 psig, open another SRV 44
C5-6.3 If the cocidown rate exceeds 100*F/b r, reduce CS or LPCI injection into the'RPV antil the cooldown rate decreases belcw 100*F/hr cr RPV pressure decreases to within 50 psig ef suppression chamber pressure, whichever occurs first. C5-7 Centrol suppression pool temperature to maintain RPV water temperature above 7 9'F C5-8 Proceed to cold shutdown in accordance with OP-IO.ZZ-004 45
CONTINGENCY #6 RPV FLOODING C6-1 If at least 3 SRVs can be opened close the MSIVs, main steam line drain valves, HPCI and RCIC isolation valves. C6-2 If any control rod is not inserted to or beyond position 02 C6-2.1 Terminate and prevent all injection into the RPV except f rota boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure. I I I
!N umber of open SRVs Minimum Alternate RPV Flooding Pressure (psig) 1 6
5 150 4 190 3 250 2 390 1 790 l- 1 I If less than 1 SRV can be opened, continue in this procedure. [ ] If whilo executing the f ollowing step, RPV water level can be 4 determined and RPV Flooding is not required, enter OP-EO.22-207(0) and OP-EO.22-101(0) at Stop RC/P-3 and l, execute theses procedures concurrently, ; _1 46
I C6-2.2 Commenee and slowly increase injection into the RPV with the following systems until at least 1 SRV is open and RPV pressure is above the Minimum Alternate RPV Flooding Pressures #25 o Condensate pumps o CRD If at least 1 SRV is not open or RPV pressure cannot be increased to above the Minimum Alternate RPV Plooding Pressure, commence and slowly increase injection into the RPV with the following systems until at least 1 SRV is open and RPV pressure is above the Minimum Alternate RPV Flooding Pressures o LPCI o Core Spray o Service water o Fire system o Condensato Transfer C6-2.3 Maintain at least 1 SRV open and RPV pressure above the Mininum Alternate RPV Flooding Pressure but as low as practicable by throttlino injection. C6-2.4 Whens o All control rods are inserted to or beyond position 02, or o The rwactor is determined to be shutdown and no baron has been injected into the RPV continuo in this procedure 47
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 3 SRVs are open and RPV pressure is not decreasing and is at least 70 psig above suppression chamber pressure. o Core Spray o LPCI o Condensate pumps o CRD o Service water o Fire Water o Condensate Transfer o SLC C6-3.2 Maintain at least 3 SRVs open and RPV pressure at least 70 psig above suppression chamber pressure but as low as practicable by throttling injection. C6-4 If RPV water level can be determined, commence and increase injection into the RPV with the following systems until RPV water level is increasing: o Core Spray o LPCI o Condensate pumps o CRD o Service water o Fire water o condensate Transfer o SLC 48
C6-5 If RPV water level cannot be determined: C6-S.1 Continue injecting water into the RPV until Drywell Temperature is below 212*P and RPV water level instrumentation is available. I I If while executing the following steps, RPV water level can be determined, continue in this procedure at Step C6-6. I I C6-5.2 If it can be determined that the RPV is filled or if RPV pressure is at least 70 psig above suppression chamber pressure, terminate all injection into the RPV and reduce RPV water level. C6-5.3 If RPV water level indication is not restored with the Maximum Core Uncovery Time Limit after commencing termination of injection into the RPV, return to Step C6-3. C6-6 When suppression chamber pressure can be maintained below the 57.2 psig enter OP-EO.ZZ-101(Q) at Steps RC/L and RC/P-4 and execute these steps concurrently. 49
r CONTINGENCY #7 LEVEL / POWER CONTROL I I If while executing the following step: o RPV water level cannot be determined, RPV Flooding is required; enter OP-EO.ZZ-202(Q) in preparation for RPV flooding. o RPV Flooding is required enter OP-EO.ZZ-206(Q) l I C7-1 If o Reactor power is above 5% or cannot be determined, and o Suppression chamber temperature is above 110*F, and o Either an SRV is open or opens or drywell pressure is above 1.68 psig, Then: if any MSIV is open, bypass low RPV water level Primary Containment Instrument Gas and MSIV isolation interlocks and restore the instrument gas to the containment, and Lower RPV water level by terminating and preventing all injection into the RPV except from boron injection systems and CRD until either:
#26 Reactor power drops below 5% or RPV water level reaches TAF or 50
All SRVs remain closed and drywell pressure remains below 1.68 psig I I If while executing the following steps Emergency RPV Depressurization is required, continue in this procedure at Step C7.2-1 I J l I If while executing the following steps: o Reactor power is above 5% or cannot be determined, and o RPV water level is above TAP and o Suppression pool temperature is above 110*P and l o Either an SRV is open or opens or drywell pressure is l above 1.68 pisg l return to step C7-1 l I C7-2 Maintain RPV water level either: # 9, #25 o If RPV water level was deliberately lowered in Step C7-1, at the level to which it was lowered, or o If RPV water level was not deliberately lowered in Step C7-1, between +12.5 in, and +54 in. with the following systems: o Condensate system 720-0 psig 51
o Feedwater system 1250-720 psig o CRD system 1500-0 psig o RCIC system 1250-65 psig #12 If RPV water level cannot be so maintained, maintain RPV water level above top of active fuel If RPV water level cannot be maintained above top of active fuel, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED: C7-2.1 Terminate and prevent all injection into the RPV except f rom boron injection systems and CRD until RPV pressure is below the Minimum Alternate RPV Flooding Pressure. I I I Number of open SRVs Minimum Alternate RPV Flooding l Pressure (psig) l t 5 150 4 190 3 250 2 390 1 790 l I I If less than 1 SRV can be opened, continue in this procedure. 52 L
C7-2.2 Commence and slowly increase injection into the RPV with the following systems until at least 1 SRV can be maintained open and RPV pressure can be maintained above minimum alternate RPV flooding pressure but as low as practicable by throttling injection to restore and maintain RPV water level above top of active fuel. #25 o Condensate /f eedwater system o CRD If RPV water level cannot be restored and maintained above top of active fuel, commence and slowly increase injection into the RPV with the following systems to restore and maintain RPV water level above top of active fuel. o LPCI #10, 11 o Core Spray o Service Water o Fire Water o Condensate Transfer l l If while executing the following steps reactor power commences and continues to increases, return to Step C7-1. l l I 53 l-
C7-3 When 371 pounds of boron have been injected or all control rods are inserted to or beyond position 02, restore and maintain RPV water level between +12.5 inches and +54 inches.
.If RPV water level cannot be restored and maintained above
+12.5 in., maintain RPV water level top of active fuel If RPV water level cannot be maintained above top of active fuel, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; return to Step C7-2.1.
C7-4 Enter OP-EO.ZZ-101(0) at step RC/P-3 I 54 i
SCRAM GUIDELINE PURPOSE The purpose of this guideline is to: o Provide operator response to a scram condition in which plant transient response is as anticipated for the existing condition ENTRY CONDITIONS The entry condition for this guideline is: Any scram condtion l l If while executing the following steps an entry condition for OP-EO.ZZ-101(O) exists, exit this procedure and enter OP-EO.ZZ-101(Q) l I S-1 Verify the scram S-2 Place the mode switch in SHUTDOWN l S-3 Insert SRMs and IRMs l S-4 When generator load is approximately 50 MWe trip the main turbine l l SS
S-5 Restore and maintain RPV water level between +12.5 in. 'and
+54 in, with one or more of the following systems: #10, #11 o Condensate 720-0 psig o Feedwater 1250-720 psig o CRD 1500-0 psig o kCIC 1250-65 psig # 9, #12 o HPCI 1250-100 psig o Core Spray 380-0 psig o LPCI 340-0 psig S-6 Control RPV pressure below 1037 psig S-7 Maintain Condbnser Vacuum S-8 Exit OP-EO.ZZ-100(Q) enter OP-EO. Z Z-99(0) 56
POST SCRAM RECOVERY GUIDELINE PURPOSE The purpose of this guideline is to: o Restore the plant to a normal shutdown condition, or o Cooldown the RPV to cold shutdown conditions l I If while executing the following steps: o RPV water level cannot be maintained above top of active fuel, or o RPV water level cannot be determined Then Enter OP-EO.ZZ-101(Q) I 1 I I If while executing the follcwing steps the reactor is not l shutdown, return to OP-EO.ZZ-101(Q) I I 57
o PSR-1 Restore and maintain RPV water level between +12.5 inches and +54 inches with one or more of the following systems: Condensate 720-0 psig Feedwater 1250-720 psig CRD 1500-0 psig RCIC 1250-65 psig # 9, #12 HPCI 1250-100 psig Core Spray 0-380 psig LPCI 0-340 psig PSR-2 If RPV water level cannot be restored and maintained above
+12.5 inches, maintain RPV water level above top of active fuel.
PSR-3 If all rods are inserted to or beyond position 02, then reset the scram, otherwise enter OP-CO.ZZ-101(Q) at Step RC/0-5 and execute concurrently. PSR-4 When conditions permit reset isolations PSR-5 If a recirculation pump can be restarted then start a recirculation pump, otherwise place Reactor Water Cleanup in service with 2 pumps and trip CRD pumps if not required for Rod insertion or level control. 58 e
PSR-6 If RPV temperature can be maintained to the right of the RPV pressurization curve, then maintain temperature to the right of the curve, otherwise maintain RPV pressure below the curve. PSR-7 If RPV depressurization is required, then depressurize the RPV and maintain cooldown rate below 100*F/hr, otherwise enter OP-IO.ZZ-002. PS R-8 When the RHR shutdown cooling interlocks clear, initiate the shutdown cooling mode of RHR. #18 If the RHR shutdown cooling mode cannot be established and f urther cooldown is required, continue to cool dcwn using one or more of the systems used for depressurization. l#9, #11, #12, 14, 415 If RPV cooldown is required but RHR shutdown cooling cannot be established and all control rods are inserted to or beyond position 02 enter OP-AB.ZZ-142, otherwise maintain pressure then enter OP-IO.ZZ-002. PSR-9 Proceed to cold shutdown in accordance with OP-IO.ZZ-004 J 59
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