ML17278A473: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 50: | Line 50: | ||
Exit this procedure and enter PPM 3.3.1, Reactor Scram.8.Insert control rods as follows: 1 8.1 If any scram valve is not open: a.Remove the f'ollowing RPS fuses: Fuse Location C72-F18A C72-F18C C72-F18E C72-F18G H13-P 609 H13-P 609 H13-P 609 H13-P609 C72-F188 C72>>F180 C72-F18F C72-F18H H13-P611 H13-P611 H13-P 611 H13-P611 b.Close scram air header supply valve CRO-Y-95 and open header vent valve CRD-V-64.c.When control rods are not moving inward: Replace RPS fuses Close CRD-V-64 Open CRD-V-95 8.2 Reset the reactor scram.If the reactor scram cannot be reset: a.Start both CRD pumps.If no CRD pump can be started, continue in this procedure at Step 8.6.b.Close HCU accumulator charging water header valve CRO-V-34.CAUTION Oef'eating RSCS interlocks may be required to accomplish this step.PROCKDURK NUMSKR 5.1.3 RKVISION NUMBKR PAOK NUMSKR RPV/Q 5.1.3-3 of'WP 999 R'I{9 99) c.Rapidly insert control rods manually until the reactor scram can be reset.If required, bypass the RWM and RSCS;bypass RSCS using individual CRD bypass switches at H13-P659.d.Reset the reactor scram.c.Open charging water valve CRD-V-34.8.3 If the scram discharge volume vent and drain valves are open, initiate a manual scram.a'.If'ontrol rods moved inward, return to Step 8.2.b.Reset the reactor scram.'f the scram cannot be reset, continue in this procedure at Step 8.5.a.c.Open the scram discharge volume vent and drain valves.8.4 Scram control rods from the KCUs: a.Establish communications between the HCUs and the Control Room.b.Individually open the scram test switches f'r control rods not inserted beyond position 06.c.Flhen a control rod is not moving inward, close its scram test switch.8.5 Reset the reactor scram.If'he reactor scram cannot be"reset.a.Start both CRD pumps.If'o CRD pump can be started, continue in this procedure at Step 8.6.b.Close HCU accumulator charging water header valve CRD-V-34.CAUTION Def'eating RSCS interlocks may be required to accomplish this step.C~Rapidly insert control rods manually until the reactor scram can be reset.If required, bypass the RNM and RSCS;bypass RSCS using individual CRD bypass switches at H13-P659.RPV/Q PROCEDURE NUMBKR 5.1.3 REVISION NUMBER~PAQK NUMBER 5.1.3-4 of'WP 99$Rl{9 99) 8.6 If any control rod cannot be inserted beyond position 06: a.Individually, direct the effluent from withdraw line vent valve CRD-V-102 to a contained liquid radwaste drain and open CRD-V-102. | Exit this procedure and enter PPM 3.3.1, Reactor Scram.8.Insert control rods as follows: 1 8.1 If any scram valve is not open: a.Remove the f'ollowing RPS fuses: Fuse Location C72-F18A C72-F18C C72-F18E C72-F18G H13-P 609 H13-P 609 H13-P 609 H13-P609 C72-F188 C72>>F180 C72-F18F C72-F18H H13-P611 H13-P611 H13-P 611 H13-P611 b.Close scram air header supply valve CRO-Y-95 and open header vent valve CRD-V-64.c.When control rods are not moving inward: Replace RPS fuses Close CRD-V-64 Open CRD-V-95 8.2 Reset the reactor scram.If the reactor scram cannot be reset: a.Start both CRD pumps.If no CRD pump can be started, continue in this procedure at Step 8.6.b.Close HCU accumulator charging water header valve CRO-V-34.CAUTION Oef'eating RSCS interlocks may be required to accomplish this step.PROCKDURK NUMSKR 5.1.3 RKVISION NUMBKR PAOK NUMSKR RPV/Q 5.1.3-3 of'WP 999 R'I{9 99) c.Rapidly insert control rods manually until the reactor scram can be reset.If required, bypass the RWM and RSCS;bypass RSCS using individual CRD bypass switches at H13-P659.d.Reset the reactor scram.c.Open charging water valve CRD-V-34.8.3 If the scram discharge volume vent and drain valves are open, initiate a manual scram.a'.If'ontrol rods moved inward, return to Step 8.2.b.Reset the reactor scram.'f the scram cannot be reset, continue in this procedure at Step 8.5.a.c.Open the scram discharge volume vent and drain valves.8.4 Scram control rods from the KCUs: a.Establish communications between the HCUs and the Control Room.b.Individually open the scram test switches f'r control rods not inserted beyond position 06.c.Flhen a control rod is not moving inward, close its scram test switch.8.5 Reset the reactor scram.If'he reactor scram cannot be"reset.a.Start both CRD pumps.If'o CRD pump can be started, continue in this procedure at Step 8.6.b.Close HCU accumulator charging water header valve CRD-V-34.CAUTION Def'eating RSCS interlocks may be required to accomplish this step.C~Rapidly insert control rods manually until the reactor scram can be reset.If required, bypass the RNM and RSCS;bypass RSCS using individual CRD bypass switches at H13-P659.RPV/Q PROCEDURE NUMBKR 5.1.3 REVISION NUMBER~PAQK NUMBER 5.1.3-4 of'WP 99$Rl{9 99) 8.6 If any control rod cannot be inserted beyond position 06: a.Individually, direct the effluent from withdraw line vent valve CRD-V-102 to a contained liquid radwaste drain and open CRD-V-102. | ||
b.When a control rod is not moving inward, close the associated CRD-V-102. | b.When a control rod is not moving inward, close the associated CRD-V-102. | ||
8.7 Inject boron using the RCIC System.a.Execute Step b and Step c concurrently. | |||
===8.7 Inject=== | |||
boron using the RCIC System.a.Execute Step b and Step c concurrently. | |||
If SLC-TK-1 level is less than 3000 gal., initiate Step d.b.With a Port-A-Band saw, grinder or cutting torch, cut the gooseneck from the open end of the RCIC suction line 2 in.standpipe on the 471 ft.elevation. | If SLC-TK-1 level is less than 3000 gal., initiate Step d.b.With a Port-A-Band saw, grinder or cutting torch, cut the gooseneck from the open end of the RCIC suction line 2 in.standpipe on the 471 ft.elevation. | ||
c.Connect SLC-TK-1 discharge to the RCIC suction standpipe. | c.Connect SLC-TK-1 discharge to the RCIC suction standpipe. | ||
| Line 99: | Line 101: | ||
d.Open RHR-V-106. | d.Open RHR-V-106. | ||
e.Monitor suppression pool level.Close RHR-V-106 when level is restored to 0 in.on CMS-LI-3 of'.4.If'uppression pool water level cannot be maintained above 30 ft.9-3/4 in., (-2-1/4 in on CMS-LR-3 or 4)proceed to Step 6.5.If suppression pool water level cannot be maintained below 31 ft, 1-3/4 in.(+1-3/4 in.on CMS-LR-3 or 4), proceed to steps 7 and 8 and execute those steps concurrently. | e.Monitor suppression pool level.Close RHR-V-106 when level is restored to 0 in.on CMS-LI-3 of'.4.If'uppression pool water level cannot be maintained above 30 ft.9-3/4 in., (-2-1/4 in on CMS-LR-3 or 4)proceed to Step 6.5.If suppression pool water level cannot be maintained below 31 ft, 1-3/4 in.(+1-3/4 in.on CMS-LR-3 or 4), proceed to steps 7 and 8 and execute those steps concurrently. | ||
RQCKDURK NUMBKR 5.2.4 WP$99 R1 I9 99)RKVISIQN NUMBKR I ACK NUMBKR SP/L 5.2.4-3 of 9 6.If suppression pool water level cannot be maintained above 30 ft.9-3/4 in.(-2-1/4 in.on NS-LR-3 or 4): 6.1.Maintain level above the Heat Capacity Level Limit HEAT CAPACITY LEVEL LIMIT 31 30 2S 25 27 25 Po 4 21 Po 20 17 15 0 5 10 15 20 25 30 35 40<T HO ('F)LIT~~HCTL MBIUS SUPPRESSION POOL TEMPERATURE I HEAT CAPACITY TEMPERATURE I IMIT 210 100 I 170 O 160 150 O.140 130 120 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 RPV PRESSURK (PSIQ)SP/L PROCEDURE NUMBER 5.2.4 REVISION NUMBER PAGE NUMBER 5.2.4.-4 of 9 WP 59a Rl (5 43) 6.2 If'evel cannot be maintained above the Heat Capacity Level Limit, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).Concur-rently, execute PPM 5.1.1, RPV Level Control (RPV/L)and PPM 5.1.3 Reactor Power Control (RPV/0).7.Maintain suppression pool water level below the Suppression Pool Load"~i""t.SUPPRESSiON POOL LOAD LlMlT 44 42 Ml 41 P 40 O 38 O 37 O 36 34 33 3'1 30 200 300 400 500 600 700 800 900 1000 1100 1200 APV PRESSURE (PSIG)SP/L PIIOCCDVRC NVMCCR 5.2.4 wf 4$I Rl (%441 RCVICIQN NLIMBCR PAQC NVMSCR 5.2.4-5 of' CAUTION Do not depressurize the RPY below 60 psig unless motor-driven pumps sufficient to maintain RPV water level are running and available for injection. | RQCKDURK NUMBKR 5.2.4 WP$99 R1 I9 99)RKVISIQN NUMBKR I ACK NUMBKR SP/L 5.2.4-3 of 9 6.If suppression pool water level cannot be maintained above 30 ft.9-3/4 in.(-2-1/4 in.on NS-LR-3 or 4): 6.1.Maintain level above the Heat Capacity Level Limit HEAT CAPACITY LEVEL LIMIT 31 30 2S 25 27 25 Po 4 21 Po 20 17 15 0 5 10 15 20 25 30 35 40<T HO ('F)LIT~~HCTL MBIUS SUPPRESSION POOL TEMPERATURE I HEAT CAPACITY TEMPERATURE I IMIT 210 100 I 170 O 160 150 O.140 130 120 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 RPV PRESSURK (PSIQ)SP/L PROCEDURE NUMBER 5.2.4 REVISION NUMBER PAGE NUMBER 5.2.4.-4 of 9 WP 59a Rl (5 43) | ||
===6.2 If'evel=== | |||
cannot be maintained above the Heat Capacity Level Limit, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).Concur-rently, execute PPM 5.1.1, RPV Level Control (RPV/L)and PPM 5.1.3 Reactor Power Control (RPV/0).7.Maintain suppression pool water level below the Suppression Pool Load"~i""t.SUPPRESSiON POOL LOAD LlMlT 44 42 Ml 41 P 40 O 38 O 37 O 36 34 33 3'1 30 200 300 400 500 600 700 800 900 1000 1100 1200 APV PRESSURE (PSIG)SP/L PIIOCCDVRC NVMCCR 5.2.4 wf 4$I Rl (%441 RCVICIQN NLIMBCR PAQC NVMSCR 5.2.4-5 of' CAUTION Do not depressurize the RPY below 60 psig unless motor-driven pumps sufficient to maintain RPV water level are running and available for injection. | |||
CAUTION Cooldown rates above 100oF/hr may be required to accanplish the following step.7.1 If'uppression pool water level cannot be maintained below the Suppression Pool Load Limit, maintain RPY pressure below the Limit.7.2 If suppression pool water 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 injection systems and CRO.SUPPRESSION POOL LOAD LIMIl46 44 42 41 39 O 38 O 37 3$w 35 34 33 32 31 30 200 300 400 500 600 700 600 900 1000 1100 1200 RPV PRESSURE (PSIG)PNQCCQVRC NVMBCR 5.2.4 RCVl31ON NVMBCI%PAQ4 NVMBKR SP/L 5.2.4-6 of 9 0 7.3 if suppression pool water level and RPV pressure cannot be restored and maintained below the Suppression Pool Load Limit, emergency RPV depressurization is required, enter PPM 5.1.2, RPV Pressure Control (RPV/P).Concurrently, execute PPM 5.1.1, RPV Level Control (RPV/L)and PPM 5.1.3 Reactor Power Control (RPY/Q).I'.Before suppression pool water level reaches the bottom of the drywell vacuum breakers (54 ft.6*in.), but only if adequate core cooling is assured, terminate injection into the RPV from sources external to the primary containment except from boron injection systems and CRD.PROCEDURE NUMBER 5.2.4 WP 599 Rl (9.99)REVISION NUMBER PACE NUMBER SP/L 5.2.4-7 of 9 CAUTION If'ontinuous LPCI operation is required t'o assure adequate core cooling, do not divert all RN pumps from LPCI mode.8.1 When suppression pool water level reaches the bottom of the drywell vacua breakers (54 f't.6 in.)but only if suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit: a.Stop recirculation pumps, drywell circulating fans and drywell cooling f'ans.b.Open drywell spray valves RHR-Y-168(A) and RHR-V-178(A). | CAUTION Cooldown rates above 100oF/hr may be required to accanplish the following step.7.1 If'uppression pool water level cannot be maintained below the Suppression Pool Load Limit, maintain RPY pressure below the Limit.7.2 If suppression pool water level and RPV pressure cannot be maintained below the Suppression Pool Load Limit, but only if adequate core cooling is assured, terminate'injection into the RPV from sources external to the primary containment except from boron injection systems and CRO.SUPPRESSION POOL LOAD LIMIl46 44 42 41 39 O 38 O 37 3$w 35 34 33 32 31 30 200 300 400 500 600 700 600 900 1000 1100 1200 RPV PRESSURE (PSIG)PNQCCQVRC NVMBCR 5.2.4 RCVl31ON NVMBCI%PAQ4 NVMBKR SP/L 5.2.4-6 of 9 0 7.3 if suppression pool water level and RPV pressure cannot be restored and maintained below the Suppression Pool Load Limit, emergency RPV depressurization is required, enter PPM 5.1.2, RPV Pressure Control (RPV/P).Concurrently, execute PPM 5.1.1, RPV Level Control (RPV/L)and PPM 5.1.3 Reactor Power Control (RPY/Q).I'.Before suppression pool water level reaches the bottom of the drywell vacuum breakers (54 ft.6*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.PROCEDURE NUMBER 5.2.4 WP 599 Rl (9.99)REVISION NUMBER PACE NUMBER SP/L 5.2.4-7 of 9 CAUTION If'ontinuous LPCI operation is required t'o assure adequate core cooling, do not divert all RN pumps from LPCI mode.8.1 When suppression pool water level reaches the bottom of the drywell vacua breakers (54 f't.6 in.)but only if suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit: a.Stop recirculation pumps, drywell circulating fans and drywell cooling f'ans.b.Open drywell spray valves RHR-Y-168(A) and RHR-V-178(A). | ||
Use a single spray header (header 8 if'ossible) | Use a single spray header (header 8 if'ossible) | ||
| Line 113: | Line 118: | ||
L.1 Operate available area, coolers.1.2 O'eactor Building HVAC exhaust plenum radiation level is below.13 mr/hr, operate available HVAC.1.3 If'ny area temperature exceeds its maximum normal operating temperature (Table 1), isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate cori cooling, or suppress a working f'ire.1.4 If a primary system is discharging into an area, then before an area temperature reaches its maximum safe operating temperature (Table 1), enter PPM 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure. | L.1 Operate available area, coolers.1.2 O'eactor Building HVAC exhaust plenum radiation level is below.13 mr/hr, operate available HVAC.1.3 If'ny area temperature exceeds its maximum normal operating temperature (Table 1), isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate cori cooling, or suppress a working f'ire.1.4 If a primary system is discharging into an area, then before an area temperature reaches its maximum safe operating temperature (Table 1), enter PPM 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure. | ||
0 1.5 If a primary system is discharging into an area, and an area temperature exceeds it maximum sai'e operating temperature in more than one area, emergency depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).PROCKDURK NUMBKR 5.2.5 WP$90 Rl[9%0)RKV IKION NUMSKR PaOK NUMKKR 5.2.5-2 of 6 2.Monitor and Control Secondary Containment Radiation Levels.2.1 If a primary system is discharging into an area, then bef'ore an area radiation level reaches the alarm level (Table 2), enter PFH, 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure. | 0 1.5 If a primary system is discharging into an area, and an area temperature exceeds it maximum sai'e operating temperature in more than one area, emergency depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).PROCKDURK NUMBKR 5.2.5 WP$90 Rl[9%0)RKV IKION NUMSKR PaOK NUMKKR 5.2.5-2 of 6 2.Monitor and Control Secondary Containment Radiation Levels.2.1 If a primary system is discharging into an area, then bef'ore an area radiation level reaches the alarm level (Table 2), enter PFH, 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure. | ||
2.2 If'ny area radiation level exceeds the alarm level, isolate all systems that are discharging into the area except systems required to shutdown the reactor, assure adequate core cooling or suppress a working f'ire.2.3 If'primary system is discharging into an area and an area radiation level exceeds the alarm level (Table 2)in more than one area, emergency RPV depressurization is required;enter FPM 5.1.2, RPV Pressure Control (RPV/P).3.Monitor and Control Secondary Containment Water Levels.3.1 If'ny f'loor drain sump water level is above the alarm level, operate available sunp pumps to restore and maintain the water level below the maximum normal operating water level.(Xf'ny f'loor drain sunup level cannot be restored and maintained below the alarm level, isolate all systems discharging water into the sump except systems required to shut down the reactor, assure adequate core cooling, or suppress a working f'ire.3.2 If a primary system is discharging into an area, and any water level reaches the Above Floor Level water level (Table 3), enter PPM 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure. | |||
3.3 If'primary system is discharging into an area and an area.water level exceeds the Maximum Saf'e Operating Level (Table 3)in more than one area, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).EOURE NUMBER REVISION NUMBER PAGE NUMBER 5.2.5 WP 990 RI I9%$)5.2.5-3 of 6 TABLE 1 Secondary Containment Temperature Control Location ILPCS P Room I IHPCS P Room I I CRD P Room I IRHR P Roce B I)Rial P Room A I IRCIC P Room I IDC MCC Room I!Steam Tunnel'l 5221 Elevation I IDiv.2 MCC Room I lRWCU P Room Div.1 MCC Room IRWCU HX Room I~SR-13/14 (H202 Anal)I IRf%HX Room'B l IFFC Puo Room I IRl%HX Room A I IMC-7B-B Room I IMC-8B-8 Room Alaxm OF 105 138 130 135 145/173 135/185 Maximum Normal Operating Value'F 104 104 120 104 120 104 104 Maximum Safe Operating Value'F 212 150 128 205 205 150 128 106 245 106 200 128 212 106"I I 106 I 0 PROCKOURK NUIHSKR 5.2.5 WP 595 R1 (5%5)RKVI5ION NUINSKR PAQK NUMSKR 5.2.5-4 of 6 0 TABLE 2 Secondary Containment Radiation Control Location Alarm (mr/hr)ARM-RIS-4 CRD HCUS East ARM-RIS-5 CRD HCUS West ARM-RIS-7 TSP Drive Room ARM-RIS-9 Rf+-P-2A Room ARM-RIS-10 Rl+-P-28 Room ARM-RIS-ll RN-P-2C Room ARM-RIS-12 RCIC-P-1 Room ARM-RIS>>13 HPCS-P-1 Room ARM-RIS-23 CRD P Room ARM-RIS>>24 I Rx 471.'est I I ARM~IS-m I Rx 471'E I I ARMWIS-P I Rx 501'NW 15 15 25 20 15 50 P KOURK NUMBKR 5.2.5 WP$99 RI (9&9)RKVISION NUMBKR PaaK NUMBKR 5.2.5-5 of 6 TABLE 3 Seconctary Containment Water Level Control Location.I LPCS P Room I I HPCS P Room I l RN Pum Room B I I RfR P Room A Above Floor Level Alarm (In.)Maximum Safe Operating Level (Inches Above Floor Level)69 I RCIC P Room I I RN P Room C I I CRD P Room 45 (+)EDR-R-5 alarm level at 420'9", f'loor level is 422'3".PROCEDURE NUMBER 5.2.5 WP$80 Rl{SWQ)REVISION NUMBKR PAOK NUMBER 5.2.5-6 of' UNCONTROLLED COPY WASKNGTON PUBLlC POWER SUPH Y SYSTEM PRQCCDVRC NVMCCR+5.2.6 4 MC NAMC PLANT PROCEDURES MANUAL%NP-2 AP QVCD DATC 06/13/85 5 EMERGENCY PROCE RES 5.0 PRECAUTIONS | ===2.2 If'ny=== | ||
area radiation level exceeds the alarm level, isolate all systems that are discharging into the area except systems required to shutdown the reactor, assure adequate core cooling or suppress a working f'ire.2.3 If'primary system is discharging into an area and an area radiation level exceeds the alarm level (Table 2)in more than one area, emergency RPV depressurization is required;enter FPM 5.1.2, RPV Pressure Control (RPV/P).3.Monitor and Control Secondary Containment Water Levels.3.1 If'ny f'loor drain sump water level is above the alarm level, operate available sunp pumps to restore and maintain the water level below the maximum normal operating water level.(Xf'ny f'loor drain sunup level cannot be restored and maintained below the alarm level, isolate all systems discharging water into the sump except systems required to shut down the reactor, assure adequate core cooling, or suppress a working f'ire.3.2 If a primary system is discharging into an area, and any water level reaches the Above Floor Level water level (Table 3), enter PPM 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure. | |||
===3.3 If'primary=== | |||
system is discharging into an area and an area.water level exceeds the Maximum Saf'e Operating Level (Table 3)in more than one area, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).EOURE NUMBER REVISION NUMBER PAGE NUMBER 5.2.5 WP 990 RI I9%$)5.2.5-3 of 6 TABLE 1 Secondary Containment Temperature Control Location ILPCS P Room I IHPCS P Room I I CRD P Room I IRHR P Roce B I)Rial P Room A I IRCIC P Room I IDC MCC Room I!Steam Tunnel'l 5221 Elevation I IDiv.2 MCC Room I lRWCU P Room Div.1 MCC Room IRWCU HX Room I~SR-13/14 (H202 Anal)I IRf%HX Room'B l IFFC Puo Room I IRl%HX Room A I IMC-7B-B Room I IMC-8B-8 Room Alaxm OF 105 138 130 135 145/173 135/185 Maximum Normal Operating Value'F 104 104 120 104 120 104 104 Maximum Safe Operating Value'F 212 150 128 205 205 150 128 106 245 106 200 128 212 106"I I 106 I 0 PROCKOURK NUIHSKR 5.2.5 WP 595 R1 (5%5)RKVI5ION NUINSKR PAQK NUMSKR 5.2.5-4 of 6 0 TABLE 2 Secondary Containment Radiation Control Location Alarm (mr/hr)ARM-RIS-4 CRD HCUS East ARM-RIS-5 CRD HCUS West ARM-RIS-7 TSP Drive Room ARM-RIS-9 Rf+-P-2A Room ARM-RIS-10 Rl+-P-28 Room ARM-RIS-ll RN-P-2C Room ARM-RIS-12 RCIC-P-1 Room ARM-RIS>>13 HPCS-P-1 Room ARM-RIS-23 CRD P Room ARM-RIS>>24 I Rx 471.'est I I ARM~IS-m I Rx 471'E I I ARMWIS-P I Rx 501'NW 15 15 25 20 15 50 P KOURK NUMBKR 5.2.5 WP$99 RI (9&9)RKVISION NUMBKR PaaK NUMBKR 5.2.5-5 of 6 TABLE 3 Seconctary Containment Water Level Control Location.I LPCS P Room I I HPCS P Room I l RN Pum Room B I I RfR P Room A Above Floor Level Alarm (In.)Maximum Safe Operating Level (Inches Above Floor Level)69 I RCIC P Room I I RN P Room C I I CRD P Room 45 (+)EDR-R-5 alarm level at 420'9", f'loor level is 422'3".PROCEDURE NUMBER 5.2.5 WP$80 Rl{SWQ)REVISION NUMBKR PAOK NUMBER 5.2.5-6 of' UNCONTROLLED COPY WASKNGTON PUBLlC POWER SUPH Y SYSTEM PRQCCDVRC NVMCCR+5.2.6 4 MC NAMC PLANT PROCEDURES MANUAL%NP-2 AP QVCD DATC 06/13/85 5 EMERGENCY PROCE RES 5.0 PRECAUTIONS | |||
+.2.6 RADIOACTIVITY RELEASE CONTROL 5.2.6.1 Purpose The purpose of'his procedure is to limit radioactivity release into areas outside the primary and secondary containments. | +.2.6 RADIOACTIVITY RELEASE CONTROL 5.2.6.1 Purpose The purpose of'his procedure is to limit radioactivity release into areas outside the primary and secondary containments. | ||
The entry condition for this procedure is: Offsite radioactivity release rate (determined by STA)above 1/2 mr/hr (Site Alert)5.2.6.5~~~0 erator Actions Isolate all primary systems that are discharging into areas outside the primary and secondary containments except those required to assure adequate core cooling or shutdown the reactor.2.If of'f'site radioactivity release rate approaches or exceeds 1 R/hr (General Emergency) and a primary system is discharging into an area outside the primary and secondary containments, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P)and execute concurrently with this procedure. | The entry condition for this procedure is: Offsite radioactivity release rate (determined by STA)above 1/2 mr/hr (Site Alert)5.2.6.5~~~0 erator Actions Isolate all primary systems that are discharging into areas outside the primary and secondary containments except those required to assure adequate core cooling or shutdown the reactor.2.If of'f'site radioactivity release rate approaches or exceeds 1 R/hr (General Emergency) and a primary system is discharging into an area outside the primary and secondary containments, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P)and execute concurrently with this procedure. | ||
| Line 134: | Line 143: | ||
CAUTION If the Condensate Supply System is valved to any ECCS injection subsystem, do not leave the connecting ECCS valve unattended and open.r I d.When RPV pressure decreases to 100 psig, valve the condensate supply system to that ECCS subsystem with an installed pipe spool by opening the related valve.1)LPCS (LPCS-V-25) 2)LPCI-A (RHR-V<<63A) 3)LPCI-B (RHR-V-63B) 4)LPCI-C (RHR-V-63C) e.When RPV water level is increasing or RPV pressure drops below 60 psig, return to Step 3 of this procedure. | CAUTION If the Condensate Supply System is valved to any ECCS injection subsystem, do not leave the connecting ECCS valve unattended and open.r I d.When RPV pressure decreases to 100 psig, valve the condensate supply system to that ECCS subsystem with an installed pipe spool by opening the related valve.1)LPCS (LPCS-V-25) 2)LPCI-A (RHR-V<<63A) 3)LPCI-B (RHR-V-63B) 4)LPCI-C (RHR-V-63C) e.When RPV water level is increasing or RPV pressure drops below 60 psig, return to Step 3 of this procedure. | ||
9.RPV Water Level Decreasing, RPY Pressure Low 9.1 If no HPCS or LPCS subsystem is operating, start pumps in alternate injection subsystems which are lined up f'r injection. | 9.RPV Water Level Decreasing, RPY Pressure Low 9.1 If no HPCS or LPCS subsystem is operating, start pumps in alternate injection subsystems which are lined up f'r injection. | ||
9.2 If'PV pressure is increasing, emergency RPV depressuri-zation is required.Enter PPM 5.3.2, Emergency Oepressur-ization and execute concurrently with this procedure. | |||
===9.2 If'PV=== | |||
pressure is increasing, emergency RPV depressuri-zation is required.Enter PPM 5.3.2, Emergency Oepressur-ization and execute concurrently with this procedure. | |||
CAUTION If the Condensate Supply System is valved to any ECCS injection subsystem, do not leave the connecting ECCS valve unattended and open.9.3 When RPV pressure decreases to 100 psig, valve the condensate supply system to that ECCS subsystem with an installed pipe spool by opening the related valve.1)LPCS (LPCS-V-25) 2)LPCI-A (RHR-V-63A) 3)LPCI-8 (RHR-V-63B) 4)LPCI-C (RHR-V-63C) | CAUTION If the Condensate Supply System is valved to any ECCS injection subsystem, do not leave the connecting ECCS valve unattended and open.9.3 When RPV pressure decreases to 100 psig, valve the condensate supply system to that ECCS subsystem with an installed pipe spool by opening the related valve.1)LPCS (LPCS-V-25) 2)LPCI-A (RHR-V-63A) 3)LPCI-8 (RHR-V-63B) 4)LPCI-C (RHR-V-63C) | ||
PROCKI3URK NUMBKR 5.3.1 WP 59~RI (3 l3)RKVISIQN NUMBKR PACK NUMBKR ,.C-LR 5.3.1-5 of 6 When RPV water level drops to-161 in.(TAF), exit this" procedure and enter contingent PPM 5.3.4, Core Cooling Without Level Restoration. | PROCKI3URK NUMBKR 5.3.1 WP 59~RI (3 l3)RKVISIQN NUMBKR PACK NUMBKR ,.C-LR 5.3.1-5 of 6 When RPV water level drops to-161 in.(TAF), exit this" procedure and enter contingent PPM 5.3.4, Core Cooling Without Level Restoration. | ||
| Line 152: | Line 163: | ||
CAUT10N Cooldown rates above 100oF/hr may be required to accomplish this step.1.Open all 7 AOS valves.2.If all AOS valves cannot be opened, open other SRVs until 7 valves are open.3.Operate HPCS and LPCS with suction from the suppression pool.When: a.Either HPCS or LPCS is operating with suction from the suppression pool and, b.RPV pressure is below 122 psig, Terminate injection into the RPV from sources external to the primary containment. | CAUT10N Cooldown rates above 100oF/hr may be required to accomplish this step.1.Open all 7 AOS valves.2.If all AOS valves cannot be opened, open other SRVs until 7 valves are open.3.Operate HPCS and LPCS with suction from the suppression pool.When: a.Either HPCS or LPCS is operating with suction from the suppression pool and, b.RPV pressure is below 122 psig, Terminate injection into the RPV from sources external to the primary containment. | ||
When RPV water level is restored to-161 in.(TAF), exit this procedure and enter PPM 5.1.1, RPV Level Control, (RPV/L)Step 6.C-W/0 LR URC NUMCCR 5.3.4 WP 407 RZ (I~)RCVl5lON NVMQCR AO NUMSCR 5.3.4-1 of' QMCQN78QII.I.EQ COPY WASKNGTON PUBLIC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 PRQCCQURC NUMCCR+5.3.5 OLU C NAMC ROVCO OATC 06/13/85 5 EMERGENCY PRO RES 5.3 EMERGENCY POROCEDURE CONTINGENCIES | When RPV water level is restored to-161 in.(TAF), exit this procedure and enter PPM 5.1.1, RPV Level Control, (RPV/L)Step 6.C-W/0 LR URC NUMCCR 5.3.4 WP 407 RZ (I~)RCVl5lON NVMQCR AO NUMSCR 5.3.4-1 of' QMCQN78QII.I.EQ COPY WASKNGTON PUBLIC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 PRQCCQURC NUMCCR+5.3.5 OLU C NAMC ROVCO OATC 06/13/85 5 EMERGENCY PRO RES 5.3 EMERGENCY POROCEDURE CONTINGENCIES | ||
+5.3.5 ALTERNATE SHJTDOWN COOLING (CONTINGENCY) l.Initiate'uppression pool cooling.2.Close: 2.1 RPV Head Vents MS-V-1 MS-V-2 2.2 MSIV'2.3 Main Steam Line Drains MS-V-16 MS-V-19 2.4 RCIC, Steam Isolation Valves RCIC-V-8 RCIC-V-63 RCIC-V-76 Place the control switch f'r 2 SRVs in the OPEN position.4.Slowly raise the RPV water level to establish a flow path through the open SRVs back to the suppression pool.5.Start LPCS or one RHR pump with suction from the suppression pool.'C-ASC URC NUMSCR 5.3.5@&457 RZ (SWQ)RCV<aaN NUMSCR AQ NUMS R 5.3.5-1 of 2 6.Slowly increase LPCS or RHR injection flow into the RPV to maximum.6.1 If RPV pressure does not stabilize at least 76 psig above suppression chamber pressure, start the LPCS or another RHR pump.6.2 If RPV pressure does not stablize below 120 psig,, open another SRV.6.3 If'he cooldown rate exceeds 100oF/hr, reduce LPCS or RHR injection into the RPV until the cooldown rate decreases below 100oF/hr.7.Control suppression pool temperature to maintain RPV water temperature above 80oF.8.Proceed to cold shutdown in accordance with PPM 3.2.1, Normal Shutdown to Cold Shutdown.PROCCQURC NVMBCR 5.3.5 WP.444 R4 (t&5)RKYI5ION NVMBCR PAOC NUMSCR C-ASC 5.3.5-2 of 2 UNt;GNTHGLLEG CGP Y WASKNGTON PUBLlC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 PROCCDURC NUMCCR+5.3.6 OLUMC NAMC A ROVCD DATC 06/13/85 5 EMERGENCY PROCEDURES 5.3 EMERGENCY PROCEDURE CONTINGENCIES | +5.3.5 ALTERNATE SHJTDOWN COOLING (CONTINGENCY) l.Initiate'uppression pool cooling.2.Close: 2.1 RPV Head Vents MS-V-1 MS-V-2 2.2 MSIV'2.3 Main Steam Line Drains MS-V-16 MS-V-19 2.4 RCIC, Steam Isolation Valves RCIC-V-8 RCIC-V-63 RCIC-V-76 Place the control switch f'r 2 SRVs in the OPEN position.4.Slowly raise the RPV water level to establish a flow path through the open SRVs back to the suppression pool.5.Start LPCS or one RHR pump with suction from the suppression pool.'C-ASC URC NUMSCR 5.3.5@&457 RZ (SWQ)RCV<aaN NUMSCR AQ NUMS R 5.3.5-1 of 2 6.Slowly increase LPCS or RHR injection flow into the RPV to maximum.6.1 If RPV pressure does not stabilize at least 76 psig above suppression chamber pressure, start the LPCS or another RHR pump.6.2 If RPV pressure does not stablize below 120 psig,, open another SRV.6.3 If'he cooldown rate exceeds 100oF/hr, reduce LPCS or RHR injection into the RPV until the cooldown rate decreases below 100oF/hr.7.Control suppression pool temperature to maintain RPV water temperature above 80oF.8.Proceed to cold shutdown in accordance with PPM 3.2.1, Normal Shutdown to Cold Shutdown.PROCCQURC NVMBCR 5.3.5 WP.444 R4 (t&5)RKYI5ION NVMBCR PAOC NUMSCR C-ASC 5.3.5-2 of 2 UNt;GNTHGLLEG CGP Y WASKNGTON PUBLlC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 PROCCDURC NUMCCR+5.3.6 OLUMC NAMC A ROVCD DATC 06/13/85 5 EMERGENCY PROCEDURES | ||
===5.3 EMERGENCY=== | |||
PROCEDURE CONTINGENCIES | |||
+5.3.6 RPV FLOODING (CONTINGENCY) 1.If at least 3 SRV's are open or if the O'CS pump is available for injection, close: a.MSIV's b.Main Steam Line Drains: c~MS-V-16 MS-V-19 RCIC Steam Isolation Valves: RCIC-V-8 RCIC-V-63 RCIC-V-76 C-FLD DURC NUMBCR 5.3.6 RCVISION NUMBCR AC NUMBCR 5.3.6-3.of 11 W~t7 RC (tent} | +5.3.6 RPV FLOODING (CONTINGENCY) 1.If at least 3 SRV's are open or if the O'CS pump is available for injection, close: a.MSIV's b.Main Steam Line Drains: c~MS-V-16 MS-V-19 RCIC Steam Isolation Valves: RCIC-V-8 RCIC-V-63 RCIC-V-76 C-FLD DURC NUMBCR 5.3.6 RCVISION NUMBCR AC NUMBCR 5.3.6-3.of 11 W~t7 RC (tent} | ||
2.If any control rod is not inserted beyond position 06: 2.1 Terminate and prevent all injection into the RPV except f'rom boron injection systems and CRD until RPY pressure i below the Minimum Alternate RPV Flooding Pressure.Nunber of open SRV's Minimum Alternate RPV Flooding Pressure (psig)7 or more 6 5 4 2 185 215 265 330 445 675 Even if'ess than 2 SRVs can be opened, continue in this procedure. | 2.If any control rod is not inserted beyond position 06: 2.1 Terminate and prevent all injection into the RPV except f'rom boron injection systems and CRD until RPY pressure i below the Minimum Alternate RPV Flooding Pressure.Nunber of open SRV's Minimum Alternate RPV Flooding Pressure (psig)7 or more 6 5 4 2 185 215 265 330 445 675 Even if'ess than 2 SRVs can be opened, continue in this procedure. | ||
| Line 163: | Line 177: | ||
6)Jog open RHR-V-538 while monitoring RPV pressure.7)Close RHR-V-688. | 6)Jog open RHR-V-538 while monitoring RPV pressure.7)Close RHR-V-688. | ||
d.Fire Water 90-0 psig 1)String fire hose from nearest outside hydrant to COND-P-2A. | d.Fire Water 90-0 psig 1)String fire hose from nearest outside hydrant to COND-P-2A. | ||
2)Attach hose to adaptor at COND-P-2A suction.3)Open hydrant and adaptor shutoi'f valves.C-FLD PROCKDURK NUMBKR 5.3.6 WP 59$Rl (t&5)RKVt5ION NUMBKR 1 PACK NUMBKR 5.3.6-4 of ll 2.4 Maintain at least 2 SRV's open and RPV pressure above the Minimum Alterate RPV Flooding Pressure by throttling injection. | 2)Attach hose to adaptor at COND-P-2A suction.3)Open hydrant and adaptor shutoi'f valves.C-FLD PROCKDURK NUMBKR 5.3.6 WP 59$Rl (t&5)RKVt5ION NUMBKR 1 PACK NUMBKR 5.3.6-4 of ll | ||
===2.4 Maintain=== | |||
at least 2 SRV's open and RPV pressure above the Minimum Alterate RPV Flooding Pressure by throttling injection. | |||
Number oi'pen SRyss Minimum Alternate RPV Flooding Pressure (psig)7 or more 6 5 4 3 2 185 215 265 330-445 675 2.5 When: a.All control rods are inserted beyond position 06 or, b.The reactor is shutdown and no boron has been injected into the RPV, continue in this procedure. | Number oi'pen SRyss Minimum Alternate RPV Flooding Pressure (psig)7 or more 6 5 4 3 2 185 215 265 330-445 675 2.5 When: a.All control rods are inserted beyond position 06 or, b.The reactor is shutdown and no boron has been injected into the RPV, continue in this procedure. | ||
URK NUMBER 5.3.6 WP 999 R I (9 99)REVISION NUMBER PAQK NUMBER 5.3.6-5 oi'l Ii'FV water level cannot be determined: | URK NUMBER 5.3.6 WP 999 R I (9 99)REVISION NUMBER PAQK NUMBER 5.3.6-5 oi'l Ii'FV water level cannot be determined: | ||
3.1 Commence and increase injection into the RPV with the following systems while verifying: | |||
===3.1 Commence=== | |||
and increase injection into the RPV with the following systems while verifying: | |||
a.At least 3 SRV's are open and, b.RPV pressure is not decreasing and, c.RPV pressure is at least 98 psig above suppression chamber pressure.d.HPCS e.CRD 1130-0 psig 1130-0 psig f.Condensate/Condensate Boosters 460-0 psig g.LPCS h.LPCI 360-0 psid 220-0 psid i.RHR Service Water-----.--160-0 psig 1)Use only if RHR-P-2B is inoperable 2)Verify, SW-P-1B operating 3)Open RHR-V-115 and RHR-V-116 4)Open RHR-V-42B I 5).Close RHR-V-68B j.SLC (test tank if OW-P-lA or OW-P-1B is operating) k.SLC (boron tank)3.2 Maintain at least 3 SRV's open and RPV pressure at least 98 psig above suppression chamber pressure by throttling i'njection. | a.At least 3 SRV's are open and, b.RPV pressure is not decreasing and, c.RPV pressure is at least 98 psig above suppression chamber pressure.d.HPCS e.CRD 1130-0 psig 1130-0 psig f.Condensate/Condensate Boosters 460-0 psig g.LPCS h.LPCI 360-0 psid 220-0 psid i.RHR Service Water-----.--160-0 psig 1)Use only if RHR-P-2B is inoperable 2)Verify, SW-P-1B operating 3)Open RHR-V-115 and RHR-V-116 4)Open RHR-V-42B I 5).Close RHR-V-68B j.SLC (test tank if OW-P-lA or OW-P-1B is operating) k.SLC (boron tank)3.2 Maintain at least 3 SRV's open and RPV pressure at least 98 psig above suppression chamber pressure by throttling i'njection. | ||
PROCCDURC NUMSKR 5.3.6 WP.$55 Rl IS&5)RKVISION NUMSCR PAQK NUMBCR C-FLO 5.3.6-6 of'l 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: | PROCCDURC NUMSKR 5.3.6 WP.$55 Rl IS&5)RKVISION NUMSCR PAQK NUMBCR C-FLO 5.3.6-6 of'l 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: | ||
| Line 172: | Line 191: | ||
2)Attach hose to adaptor at COND-P-2A suction.3)Open hydrant and adaptor shutoff valves.CCaURC NUMeCR 5.3.6 WP$99 R1 (9%3)RCVI5ION NUMSCR I aCC NUMeCR C-FLD 5.3.6-7 of ll h.ECCS Condensate Flush connections 40-0 psig 1)Install the removable pipe spool between the condensate supply system header and any one of the Yellowing ECCS injection subsystems | 2)Attach hose to adaptor at COND-P-2A suction.3)Open hydrant and adaptor shutoff valves.CCaURC NUMeCR 5.3.6 WP$99 R1 (9%3)RCVI5ION NUMSCR I aCC NUMeCR C-FLD 5.3.6-7 of ll h.ECCS Condensate Flush connections 40-0 psig 1)Install the removable pipe spool between the condensate supply system header and any one of the Yellowing ECCS injection subsystems | ||
~hsvin~Sobs stem Tie Valves LPCS LPCI-A LPCI-8 LPCI-C COND-V26/LPCS-Y-25 COND-V-36/RHR-V-63A COND-V-35/RHR-V-638 COND-V-37/RHR-V-63C 2)When RPV pressure is less than 100 psig and decreasing, open the Condensate/ECCS valves.associated with the installed spool.i.ECCS Keep Full Pumps------30-0 psig 1)HPCS-P-2 2)LPCS-P-2 3)SLC (test tank if DW-P-1A or k.SLC (boron tank)PRQCKDURK NUMSKR 5.3.6 WP 555 Rl (SiOQ)RKVISION NUMSKR PACK NUMSKR C-Ftg5.3.6-8.of ll 5.If RPV water level cannot be determined: | ~hsvin~Sobs stem Tie Valves LPCS LPCI-A LPCI-8 LPCI-C COND-V26/LPCS-Y-25 COND-V-36/RHR-V-63A COND-V-35/RHR-V-638 COND-V-37/RHR-V-63C 2)When RPV pressure is less than 100 psig and decreasing, open the Condensate/ECCS valves.associated with the installed spool.i.ECCS Keep Full Pumps------30-0 psig 1)HPCS-P-2 2)LPCS-P-2 3)SLC (test tank if DW-P-1A or k.SLC (boron tank)PRQCKDURK NUMSKR 5.3.6 WP 555 Rl (SiOQ)RKVISION NUMSKR PACK NUMSKR C-Ftg5.3.6-8.of ll 5.If RPV water level cannot be determined: | ||
5.1 Commence backfilling RPV level instrumentation reference columns using the IhC Shop Sprague pump or hand pumps.Zndicarcr/Reccrder | |||
===5.1 Commence=== | |||
backfilling RPV level instrumentation reference columns using the IhC Shop Sprague pump or hand pumps.Zndicarcr/Reccrder | |||
~ancae Transmitter Location MS-LR-615 MR-LI-610 MS-LR-623A MS-LR-6238 MS-LI-604 LI-606A LI-6068 LI-606C Fuel Fuel Wide Wide Wide Narrow Narrow Narrow CAUTION LITS-N044A LITS-N0448 LITS-N026A LITS-N026O LITS-N026C dPT-N004A dPT-NO048 dPT-N004C H22-P 010 H22-P009 H22-P004 H22-P026 H22-P005 H22-P004 H22-P027 H22-P005 Reference columns for the following instruments are located in the drywell.General CAUTION 86 is applicable. | ~ancae Transmitter Location MS-LR-615 MR-LI-610 MS-LR-623A MS-LR-6238 MS-LI-604 LI-606A LI-6068 LI-606C Fuel Fuel Wide Wide Wide Narrow Narrow Narrow CAUTION LITS-N044A LITS-N0448 LITS-N026A LITS-N026O LITS-N026C dPT-N004A dPT-NO048 dPT-N004C H22-P 010 H22-P009 H22-P004 H22-P026 H22-P005 H22-P004 H22-P027 H22-P005 Reference columns for the following instruments are located in the drywell.General CAUTION 86 is applicable. | ||
RFW-LR-608 MS-LI-605 Upset dPT-N017 Shutdown LT-N027 H22-P017 H22-P027 5.2 Continue injecting water into the RPV until water level.instrunentation is available. | RFW-LR-608 MS-LI-605 Upset dPT-N017 Shutdown LT-N027 H22-P017 H22-P027 5.2 Continue injecting water into the RPV until water level.instrunentation is available. | ||
| Line 189: | Line 210: | ||
STANDBY mode.C-PWR PROCCOURC NUMSCR 5.3.7 WP 444 RI (4&QI RCVISION NUMBCR PAQC NUMOCR 5.3.7-3 of 8 4.Maintain RPV water level at either: a.The level to which it was deliberately lowered in Step 2 or, b.Between+13.0 in.and+54.0 in.if'PV level was not deiiberately'owered with the following systems: a.CRD CAUTION 1130-0 psig Do not throttle the RCIC turbine be-low 1000 rpm.b.RCIC c.Condensate Booster Props 1130-60 psig 460-0 psig 1)Verify RFW-LIC-620 in MANUAL with OX output.2)Open RFW-V-117A, RFW-Y-117B and RFW-V-118. | STANDBY mode.C-PWR PROCCOURC NUMSCR 5.3.7 WP 444 RI (4&QI RCVISION NUMBCR PAQC NUMOCR 5.3.7-3 of 8 4.Maintain RPV water level at either: a.The level to which it was deliberately lowered in Step 2 or, b.Between+13.0 in.and+54.0 in.if'PV level was not deiiberately'owered with the following systems: a.CRD CAUTION 1130-0 psig Do not throttle the RCIC turbine be-low 1000 rpm.b.RCIC c.Condensate Booster Props 1130-60 psig 460-0 psig 1)Verify RFW-LIC-620 in MANUAL with OX output.2)Open RFW-V-117A, RFW-Y-117B and RFW-V-118. | ||
3)Close RFW-V-112A and RFW-V-112B. | 3)Close RFW-V-112A and RFW-V-112B. | ||
4)Start one each COND-P-1 and COND-P-2.5)Slowly open RFW-V-10 while monitoring RPV water level and power.4.1 If'PV water level cannot be maintained as required in Step 4, maintain RPV water level above-161 in.(TAF).4.2 If RPV water level cannot be maintained above-161 in.(TAF), emergency RPV depressurization is required;enter contingent PPM 5.3.2, Emergency RPV Depressurization and execute concurrently with this procedure through Step 4.6.C-PWR PROCKDURK NUMSKR 5.3.7 WP SPB Rl (SWQ)RKVISIQN NUMBKR PACK NUMSKR 4.3 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.'inimum Alternate RPV Number of open SRV's I Flooding Pressure (psig)7 or more 6 5 4 2 185 215 265 330 445 675 4A If'ess than 2 SRV's can be opened, continue in this procedure. | 4)Start one each COND-P-1 and COND-P-2.5)Slowly open RFW-V-10 while monitoring RPV water level and power.4.1 If'PV water level cannot be maintained as required in Step 4, maintain RPV water level above-161 in.(TAF).4.2 If RPV water level cannot be maintained above-161 in.(TAF), emergency RPV depressurization is required;enter contingent PPM 5.3.2, Emergency RPV Depressurization and execute concurrently with this procedure through Step 4.6.C-PWR PROCKDURK NUMSKR 5.3.7 WP SPB Rl (SWQ)RKVISIQN NUMBKR PACK NUMSKR | ||
4.5 Comence and~slowl increase injection into the RPV with the following systems to restore and maintain RPV water level above-161 in.(TAF).a~CRD 1130-0 psig.b.c~RCIC-1130-60 psig Condensate Booster Pumps 460-0 psig 1)Verify RFW-LIC-620 in MANUAL with OX output.2)Open RFW-V-117A, RFW-V-117B and RFW-V-118. | |||
===4.3 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.'inimum Alternate RPV Number of open SRV's I Flooding Pressure (psig)7 or more 6 5 4 2 185 215 265 330 445 675 4A If'ess than 2 SRV's can be opened, continue in this procedure. | |||
===4.5 Comence=== | |||
and~slowl increase injection into the RPV with the following systems to restore and maintain RPV water level above-161 in.(TAF).a~CRD 1130-0 psig.b.c~RCIC-1130-60 psig Condensate Booster Pumps 460-0 psig 1)Verify RFW-LIC-620 in MANUAL with OX output.2)Open RFW-V-117A, RFW-V-117B and RFW-V-118. | |||
3)Close RFW-V-112A and RFW-V-112B. | 3)Close RFW-V-112A and RFW-V-112B. | ||
4)Start at least one each COND-P-1 and COND-P-2.5)Slowly open RFW-V-10 while monitoring RPV level and power.C-FWR QCKQURK NUM SKR 5.3.7 WP.It5 Rt (5%5)RKVI5ION N VMSKR PAERK NUMSKR 5.3.7-5 of 8 CAUTION A rapid increase in injection inside the shroud may induce a large power excursion and result in substantial core damage.4.6 If RPV water level cannot be restored and maintained above-161 in.(TAF), ccnmenca and~slowl increase injection into the RPV with the f'ollowing systems to restore and maintain RPV water,level above-161 in.(TAF): as HPCS 1130-0 psig 1)Align HPCS.to take suction f'rom the suppression pool.2)At H13-P625, block open contacts 1-2 of E22A-K3.3)Verify HPCS-V-4 is closed.4)Start HPCS-P-l.5)Open HPCS-V-23. | 4)Start at least one each COND-P-1 and COND-P-2.5)Slowly open RFW-V-10 while monitoring RPV level and power.C-FWR QCKQURK NUM SKR 5.3.7 WP.It5 Rt (5%5)RKVI5ION N VMSKR PAERK NUMSKR 5.3.7-5 of 8 CAUTION A rapid increase in injection inside the shroud may induce a large power excursion and result in substantial core damage.4.6 If RPV water level cannot be restored and maintained above-161 in.(TAF), ccnmenca and~slowl increase injection into the RPV with the f'ollowing systems to restore and maintain RPV water,level above-161 in.(TAF): as HPCS 1130-0 psig 1)Align HPCS.to take suction f'rom the suppression pool.2)At H13-P625, block open contacts 1-2 of E22A-K3.3)Verify HPCS-V-4 is closed.4)Start HPCS-P-l.5)Open HPCS-V-23. | ||
Revision as of 15:48, 18 October 2018
| ML17278A473 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/01/1985 |
| From: | BAKER J W WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17278A471 | List: |
| References | |
| PROC-851101, NUDOCS 8511110269 | |
| Download: ML17278A473 (95) | |
Text
t uNCGMTRGLLEG CGPV PLANT PROCEDURES MANUAL SNP-2~'>>>O>69 85~>og@DOCK 050 F PDR WASKNGTON PUBLIC POWER SUPPLY SYSI'R4 PR4CCDVRC NVMCCR%5.0.0 4!UMC NAM a RDVCD DATC 06/13/85 5 EMERGENCY PROC RES 5.0 PRECAUTIONS
+5.0.0 EMERGENCY PROCEDURE GENERAL PRECAUTIONS The following Emergency Procedure Cautions are generally applicable at all times.CAUTION jP1 Use these Emergency Procedures with the Emergency Procedure Flow Chart.Observe the boxed requirements f'r exiting one procedure and entering another.CAUTION kQ.Monitor the general state of the plant.If fan entry condition f'r an Emergency Procedure occurs, enter that procedure.
When it is determined that an emergency no longer exists, return to normal plant operating procedures.
CAUTION P3 Monitor RPY water level and pressure and primary containment temperature and pressure from multiple indications.
CAUTION 84 If a safety f'unction initiates automatically, assume a true initiating event has occurred unless otherwise confirmed by at least two independent indications.
CAUTION 05 Whenever RHR is in the LPCI mode, inject through the heat exchangers as soon as possible.PRw RC NUMI5CR 5.0.0 RCVISIQN NUMCCR ACC NUMSCR 5.0.0-1 of'WP 417 RZ It<5)
CAUTION jj6 Whenever the following instruments read below the Limiting Level in the Table, the actual RPV water level may be anywhere below the elevation of the lower instrument tap.Instrument MS-LI-605, Shutdown RFW-LR-608, Upset Ran e 0-400 in.0-180 in.Limitin Level 197 in.160 in.CAUTION 07 D'PCS SUCTION SWITCHOVER SUPPRESSION POOL LEVEL HIGH or HPCS/RCIC SUC-TION SWITCHOVER CST LEVEL LOW alarms occur, confirm automatic transfer of or manually transfer HPCS and RCIC suction from the condensate storage tank to the suppression pool.RCIC suction will not auto transfer on high suppression pool level.CAUTION PP8 Notify the Shift Manager to classify any entry into these Emergency Proce-dures in accordance with PPM 13.1.1, Classifying The Emergency, and initi-ate the appropriate action plan.CAUTION 89 If during execution of these procedures, core damage is indicated and cooldown to cold shutdown is required, use PPM 5.3.5, Alternate Shutdown Cooling.PRQCKQURK NUMBKR 5.0.0 WP$9$R1 (9.9$)RKVISIQN NUMBKR PaCK NUMBKR 5.0.0-2 of 3 CAUTION 010 Observe NPSH requirements for pumps taking suction from the suppression pool.Zf core cooling is adequate, throttle pump flows to pressure NPSH.HPCS NPSH LIMIT RCIC NPSH LlMIT 10 Fald 14 44XI O>>QW 41~41 Q 240 210 210 4 d HPCS PUMP FLOW (x 1000 CPM)LPCS NPSH LIMIT 10 0 IIOC PUMP fLOW (x 100 CPM)RHR NPSH LIMIT-1~POO oE'g 220 gg 0~Ul 41 P I~l QN g 210 210 440 0 0 LPCS f UQP fLOW I x 1000 CPM)\0 d IIIIII PUMP FLOW]x 1000 CPM)+-Suppression Chamber Pressure (psig)Suppression Pool at Normal Level PROCEOVRE NUMBER 5.0.0 WP.590 R1 (9.02)REVISION NUMBER PACE NUMBER 5.0.0-3 of'
UNCGNTRGLLEG CGPY.WASHINGTON PUBLIC POWER SUPPLY SYSTEM PLAi tT PROCEDURES MANUAL%NP-2 PRQCCOVRC NVMCCR+5.0.1 QI M NAMC APPRQ CO OATC 03/14/84 5.0 II 5 0 EMERGENCY PROCEDURES PRECAUTIONS EMERGENCY OPERATING PROCEDURE FLOW.CHART The controlled copies of the"Energency Operating Procedure Flow Chart" are located in the Main Control Room, Technical Support Center and WNP-2 Simulator.
VRC NVMCCR 5.0.1 WP$01 RZ (SAQ)RCVI5lQN NUMSCR RCC NUMIICR 5.0.1-1 of'
MNCGNTHGILLEB CGPY WASKNC?QN PUBLlC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL WNP-2 PAOCCDURC NUMCCR+5.1.1 Ot MC NhM ROVCD DhTC 06/13/85 5 EMERGENCY PROC RES 5.1 RPV CONTROL+5.1.1 RPV LEVEL CONTROL (RPV/L)5.1.1.1~Pur oee The purpose of this procedure is to restore and maintain RPV water level within a satisf'actory range..1.1.~th d1 Entry conditions f'r this procedure are any of'he following:
1.RPV water level below+13.0 in., 2.RPV pressure above 1O37 psig, 3.Orywell pressure above le65 psig, 4.A condition which requires MSIV isolation, 5.A condition which requires reactor scram and reactor power is above 5X or cannot be determined.
.1.e""I l.If'eactor scram has not been initiated, initiate reactor scram.2.Place the reactor mode switch in SHUTDOWN.3.Irrespective of'he entry condition, execute this procedure concurrently with: a.PPM 5.1.2, RPV Pressure Control (RPV/P)b.PPM 5.1.3, Reactor Power Control (RPV/0)RPV/L.URC NUMSCR 5.1.1 ACVIC4ON NUMQCR hC NUMSCR 5.1.1-3.of 4'N&5$7 AZ (tWQ) 4.Monitor and control RPV water level using the following level instrunentation:
Indicator/Recorder MS-LR-615 MS-LI-610 MS-LR-623A MS-LR-6238 MS-LI-604 RFW-LI-606A-RFW-LI-6068 RFW-LI-606 C~Ran e Fuel Fuel Wide Wide Wide Narrow ,Narrow Narrow 5.Confirm initiation of any of the following:
a.MSIV Closure b.ECCS c.Emergency Oiesel Generators Initiate any of those which should have initiated but did not.If while executing Step 6: 1.Boron injection is required, exit this procedure and enter contingent PPM 5.3.7, Level/Power Control.2.RPV water level cannot be determined, exit this procedure and enter contingent, PPM 5.3.6, RPV Flooding.3.RPY Flooding is required, exit this procedure and enter contingent PPM 5.3.6, RPV Flooding.(3 CAUTION If HPCS SUCTION SWITCHOVER SUPP POOL LEVEL HIGH or HPCS (or RCIC)SUCTION SWITCHOVER CST LEVEL LOW alarms occur, confirm automatic transfer of or manually transfer HPCS and RCIC suction from the condensate storage tanks to the suppression pool.RCIC suction will not auto transfer on high suppression pool level.RPV/L PROCKOURK NUMCCR 5.1.1 WP SCI R'I (SWQ)RKVIIION NUMSKR PAOC NUMBKR 5.1.1-2 of 4 0 CAUTION 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 MAMJAL mode, it will not initiate auto-matically.
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.CAUTION If a high drywell pressure ECCS initia-tion signal (1.65 psig)occurs or exists while depressurizing, prevent injection from those LPCS and LPCI pumps not re-quired to assure adequate core cooling prior to reaching their maximum injection pressures.
When the high drywell pressure ECCS initiation signal clears, restore LPCS and LPCI to AUTOMATIC/STANDBY mode..6.Restore and maintain RPV water level between+13.0 in.and+54.5 in.with one or more of the following systems:~Sstem RPV Pressure Ran e a.Feedwater-----1130-160 psig b.CRD 1130-0 psig CAUTION Do not throttle the RCIC turbine below 1000 rpm.c.RCIC 1130-57 psig d.HPCS e.Condensate Booster f.LPCS g.LPCI-h.Condensate 1130-0 psig 460-0 psig 360-0 psig 220-0 psig 160-0 psigPROCKDURK NUMBKR 5.1.1 WP$9$Rl (9&9)RKVISIQN NUMBKR PAQK NUMBKR RPV/L 5.1.1-3 of 4 7.If'PV water level cannot be restored and maintained above+13.0 in.maintain RPV water level above-161 in.8.Ii'PV water level can be maintained above-161 in., (TAF)I prevent automatic RPV depressurization by inhibiting AOS.9.If'egraded core conditions exist, close f'eedwater block valves RFW-V-65A and RFW-V-65B within 20 minutes following cessation ofeedwater f'low.10.Ii'igh drywell pressure is indicated, manually initiate the MSLC System when the RPV has depressurized to 35 psig.Ref'er to PPM 2.2.6, Main Steam, Section B.If'PV water level cannot be maintained above-161 in., exit this procedure and enter PPM 5.3.1, Level Restoration.
I I If'lternate shutdown cooling is required, exit this I procedure and enter PPM 5.3.5, Alternate Shutdown l Cooling.l 11.Proceed to cold shutdown in accordance with PPM 3.2.1, Normal Shutdown to Cold Shutdown when level is restored to above+13.0 in.RPV/L PROCKDURK NUMBKR 5.1.1 WP.59$RI (9 9$)RKVI5ION NUMBKR PAQK NUMBKR 5.1.1-4 of 4 WASKNGTON PUBIC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 PRQCCOURC NUMCCR"5.1.2 AP5s VCQ PAVC 06/13/85 l UMC NAMC 5 EMERGENCY PRO RES 5.1 RPV CONTROL+5.1.2 RPV PRESSURE CONTROL (RPV/P)5.1.2.1 Purpose The purpose of'his procedure is to control pressure and cool down the RPV to cold shutdown conditions (100'F-200'F).5.1.2.2 Entr Conditions Entry conditions for this procedure are any of the f'ollowing:
1.RPV water level below+13.0 in., 2.RPV pressure above 1037 psig, 3.Drywell pressure above le65 psig, 4.A condition which requires MSIV isolation, 5.A condition which requires reactor scram and reactor power is above 5%or cannot be determined.
5.1.2.3, 0 erator Actions l.If reactor scram has not been initiated, initiate a reactor scram.2.Place the reactor mode switch in SHUTDOWN.Irrespective of'he entry condition, execute this procedure concurrently with: a.PPM 5.1.1, RPY Level Control (RPV/L)b.FPM 5.1.3, Reactor Power Control (RPV/Q)4.Monitor and control reactor pressure.URC NUMbCR RCVlQON NUMbCR Are NUMSCR Wt 50i RC ('SWQ)5.1.2-1 of' CAUTION Cooldown rates above 100'F/hr may be required to accomplish the following step.5.If'hile executing the f'ollowing steps emergency depressuriza-tion is anticipated, and boron injection is not required, rapidly depressurize the RPV with the'main turbine bypass valves.If while executing the f'ollowing steps: l.Emergency RPV depressurization or RPV f'looding is required and less than 7 p,"1""~p enter PPM 5.3.2, Emergency RPV Depressurization.
2.RPV f'looding is required and at least 7 enter FPM 5.3.6, RPV Flooding.6.If any SRV is cycling, manually open SRVs until RPV pressure drops to 930 psig.PROCEDURE NUMBER 5.1.2 REVISION NUMBER PACK NUM BKR RPV/P 5.1.2-2 or 8 WP 59$Rl (9 05)
CAUTION Cooldown rates above 100'F/hr may be required to accomplish the following step.Oo not depressurize the RPV below 60 psig unless motor driven.pumps sufficient to maintain RPV water level are running and available for injection.
7.If while executing the following steps: a.Suppression pool.-temperature cannot be maintained below the Heat Capacity Temperature Limit, maintain RPV pressure below the Limit.HEAT CAPACITY TEMPERATURE LIMIT C'00 p 190 I~o170 160 150 140 0 100 200 300 400 500 600 700 600 900 1000 1100 1200 HPV PRESSURE (PSIG)PROCKOURK NUMBKR 5.1.2 REVISION NUMBKR PAOK NUMBKR RPV/P 5.1.2-3 of 8 WP$94 R1 (9 CQ) b, Suppression pool water level cannot be maintained below the Suppression Pool Load Limit, maintain RPV pressure below the Limit.SUPPRESSION POOL LOAD LIMIT 46 45 44 42 g 40 39 O 38 O 37 O g 36 34 33 31 30 200 300 400 500 600 700 BOO 900 1000 1100 1200 RPV PRESSURE (PSIG)I I If'hile executing the f'ollowing steps, steam I cooling is required, exit this procedure and I enter PFM 5.3.3, Steam Cooling.PRQCKQVRK NUMBKR 5.1.2 RKVISIQN NVMBKR PACK NVMBKR RPV/P 5.1.2-4 of' III 8.If'hile executing the f'ollowing steps: o boron injection is required and o the main condenser is available, and o there has been no indication of'ross fuel failure or steam line break t open MSIVs'to re-establish the main condenser as a heat sink.CRUTlaR Bypassing RPY low water level MSIV iso-lation interlocks may be required to accomplish the following step.8.1 If'equired, bypass RPV low water level MSIV isolation interlocks by installing the f'ollowing jumpers: Location~Rela Contact H13&609 H13-P609 H13-P 611 H13-P611 KlA K1C K1B KlD 1-2 1-2 1-2 1-2 8.2 isolate and pressurize MS lines.a.Close or conf'irm MS drain line trap bypass/isolation valves closed: MS-V-71 MS-V-68 MS-V-69 MS-V-21 MS-Y-156 b.Open outboard MSIV's MS-V-28A MS-V-28B MS-V-28C MS-V-280 c.Open MS line drains to initiate inboard MSIV pressure equalization.
MS-V-16 MS-V-19 MS-V-20 PR OURE NUMBER 5.1.2 WP 5$$Rl (5 13)REVISION NUMBER PAC)E NUMBER RPV/P 5.1.2-5 of' d.Close SJAE Steam Supply Valves MS-V-110A MS-V-110B e.Close of'f'gas valves to save condenser vacuum 0 OG-V-125A OG-V-125B f.Close of'fgas preheater steam supply valves MS-V-115A MS-V-115B 8.3 When MS lines have repressurized and inboard MSIV differential pressure is 200 psid or less, open: MS-V-22A MS-V-22B MS-V-22C MS-V-22D 8.4 Return Air Removal and Offgas Systems to service.CAUTION Do not depressurize the RPV below 60 psig unless motor driven pumps suf'ficient to maintain RPV water level are running and available f'r injection.
9.Control RPV pressure below 1075 psig with the main turbine bypass valves.RPV pressure control may be augmented by one or more of the following systems: PROCEDURE NUMBER 5.3..2 REVISION NUMBKR PACK NUMBER RPV-P 5.1.2-6 of'WP 599 Rl t9 SS)
CAUTION The recommended SRV opening sequence is: 1.MS-RV-58 2.MS-RV-30 MS-RV-5C 4.MS-RV-4D 5.MS-RV-48 6.MS-RV-4A 7.MS-RV-4C 8.9.10.11.12.13.14.MS-RV-1A 15.MS-RV-28 16.MS-RV-1C 17.MS-RV-18 18.MS-RV-2C MS-RV-1D MS-RV-3C MS-RV-2D MS-RV-2A MS-RV-38 MS-RV-3A a.SRV's;only if'uppression pool water level is above 17'.D'he CIA System (including nitrogen backup bottles)is or becomes unavailable, depressurize with sustained SRV opening.b.RCIC c.SAE d.Sealing Steam e.RFW Turbines Off'as Preheaters g-.RWCU (recirculation through the heat exchanger) if'o boron has been injected into the RPV.h.Main steam line drains.Open MS-V-16, MS-V-19 and MS-V-21.RWCU (blowdown mode)if no boron has been injected into the RPV.Instruct the HP/Chemist to sample the RPV coolant in accordance with PPM 12.10.7, Post Accident Sampling and Analysis and report results to the Control Room prior to initiating blowdown.Do not blowdown if sample results indicate core damage.10.If'hile executing the f'ollowing steps, the reactor is not shutdown, return to Step 9 for RPV pressure control.PROCKOURK NUMBER 5.1.2 REVISION NUMBER PAGE NUMBER RPV/P 5.1.2-7 of'WP 599 Rl{9 49)
CAUTION Do not depressurize the RPV below 60 psig unless motor driven pumps sufficient to maintain RPV water level are running and available for injection.
CAUTION Cooldown rates above 100'F/hr may be required to conserve RPV water inventory, protect primary containment integrity, or limit radioactive release to the enviro-ment.11.When either: a.All control rods are inserted beyond position 06, or b.SLC-TK-1 or 2050 lb.of boric acid and 2130 lb.of borax in solution have been injected into the RPV, or c.The reactor is shutdown and no boron has been injected in the RPV, d.Oepressurize the RPV and maintain the cooldown rate below 100'F/hr.CAUTION If continuous LPCI operation is required to assure adequate core cooling, do not divert all RHR pumps from LPCI mode.12.When the RHR shutdown cooling interlocks clear, initiate the shutdown cooling mode of RHR.13.If the RHR shutdown cooling mode cannot be established and further cooldown is required, continue to cooldown using one or more of the systems used for depressurization (in Step 9).If RPY cooldown is required but cannot be accomplished and all control rods are in-serted beyond position 06, alternate shut-down cooling is required;exit this procedure and enter PPM 5.3.5, Alternate Shutdown Cooling.I 14.Proceed to cold shutdown in accordance with PPM 3.2.1, Normal Shutdown to Cold Shutdown.PROCKOURK NUMBKR 5.1.2 WP.SSS RI (4.44)RKVISION NUMBKR PAQK NUMBER RPV/P 5.1.2-8 of 8 UNCOIWlTHOI.I.Eg COPY WASHINGTON PUBLIC POMER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 lRQCCDURC NUMCCR+5.1.3 Ot UMC NAMC AFPROVCD OAT%06/13/85 5 EMERGENCY PRO ES 5.1 RPV CONTROL+5.1.3 REACTOR POWER CONTROL (RPV/Q)5.1.3.1~pur oee The purpose of this procedure is to control power and shutdown the reactor.Any condition which requires reactor scram and reactor power remains above 5X on the APRMs or cannot be determined.
1.D'uto scram has not been initiated, initiate manual scram.2.Place the reactor mode switch in SHUTDOWN.3.Execute this procedure concurrently with: a.PPM 5.1.1, RPV Level Control (RPV/L)b.PPM 5.1.2, RPV Pressure Control (RPV/P)4.Monitor and control reactor power.RPV/Q URC NUMSCR'.1.3 WII 407 RZ{tWt)RCVISIQN NUMSCR AO NUMSCR 5.1.3-1 of 9 If while executing the following steps: 1.All control rods are inserted beyond position 06, terminate boron injection exit this procedure and enter PPM 3.3.1, Reactor Scram.2.The reactor is shutdown and no boron has been injected into the RPV, exit this procedure and enter PFM 3.3.1, Reactor Scram.5.If the MSIV's are open and the T-G is on line, confirm or initiate recirculation FCV runback to minimum.6.If reactor power is above 5X after FCV runback or cannot be determined, trip the recirculation pumps to off.Execute Step 7 and Step 8 concurrently.
CAUTION Manually trip the SLC pumps when SLC-TK-1 level drops to 100 gal.0 7.If'he reactor cannot'e shutdown before suppression pool temperature reaches 110%, boron~in'ection is receuired; inject boron into the RPV with SLC and prevent automatic initiation of ADS.7.1 Monitor reactor power and SLC-TK-1 level.If boron cannot be injected into the RPV with SLC, perform: a.Step 8.7 if'CIC is operable, or b.Step 8.8 if'WCU is operable and RCIC is not.7.2 If boron is not being injected into the RPV by RWCU, confirm automatic'solation or manually isolate RWCU.7.3 Continue to inject boron until 2050 lb boric acid and 2130 lb borax in solution with 3000 gal.(minimum)of'ater have been injected into the RPV.RPV/0 PROCKOURK NUMBKR 5.1.3 RKVISION NUMBKR PAGK NUMBKR 5.1.3-2 of 9 WP 594 RI (9 4$)
Exit this procedure and enter PPM 3.3.1, Reactor Scram.8.Insert control rods as follows: 1 8.1 If any scram valve is not open: a.Remove the f'ollowing RPS fuses: Fuse Location C72-F18A C72-F18C C72-F18E C72-F18G H13-P 609 H13-P 609 H13-P 609 H13-P609 C72-F188 C72>>F180 C72-F18F C72-F18H H13-P611 H13-P611 H13-P 611 H13-P611 b.Close scram air header supply valve CRO-Y-95 and open header vent valve CRD-V-64.c.When control rods are not moving inward: Replace RPS fuses Close CRD-V-64 Open CRD-V-95 8.2 Reset the reactor scram.If the reactor scram cannot be reset: a.Start both CRD pumps.If no CRD pump can be started, continue in this procedure at Step 8.6.b.Close HCU accumulator charging water header valve CRO-V-34.CAUTION Oef'eating RSCS interlocks may be required to accomplish this step.PROCKDURK NUMSKR 5.1.3 RKVISION NUMBKR PAOK NUMSKR RPV/Q 5.1.3-3 of'WP 999 R'I{9 99) c.Rapidly insert control rods manually until the reactor scram can be reset.If required, bypass the RWM and RSCS;bypass RSCS using individual CRD bypass switches at H13-P659.d.Reset the reactor scram.c.Open charging water valve CRD-V-34.8.3 If the scram discharge volume vent and drain valves are open, initiate a manual scram.a'.If'ontrol rods moved inward, return to Step 8.2.b.Reset the reactor scram.'f the scram cannot be reset, continue in this procedure at Step 8.5.a.c.Open the scram discharge volume vent and drain valves.8.4 Scram control rods from the KCUs: a.Establish communications between the HCUs and the Control Room.b.Individually open the scram test switches f'r control rods not inserted beyond position 06.c.Flhen a control rod is not moving inward, close its scram test switch.8.5 Reset the reactor scram.If'he reactor scram cannot be"reset.a.Start both CRD pumps.If'o CRD pump can be started, continue in this procedure at Step 8.6.b.Close HCU accumulator charging water header valve CRD-V-34.CAUTION Def'eating RSCS interlocks may be required to accomplish this step.C~Rapidly insert control rods manually until the reactor scram can be reset.If required, bypass the RNM and RSCS;bypass RSCS using individual CRD bypass switches at H13-P659.RPV/Q PROCEDURE NUMBKR 5.1.3 REVISION NUMBER~PAQK NUMBER 5.1.3-4 of'WP 99$Rl{9 99) 8.6 If any control rod cannot be inserted beyond position 06: a.Individually, direct the effluent from withdraw line vent valve CRD-V-102 to a contained liquid radwaste drain and open CRD-V-102.
b.When a control rod is not moving inward, close the associated CRD-V-102.
8.7 Inject
boron using the RCIC System.a.Execute Step b and Step c concurrently.
If SLC-TK-1 level is less than 3000 gal., initiate Step d.b.With a Port-A-Band saw, grinder or cutting torch, cut the gooseneck from the open end of the RCIC suction line 2 in.standpipe on the 471 ft.elevation.
c.Connect SLC-TK-1 discharge to the RCIC suction standpipe.
1)Verify SLC-V-lA and SLC-V-lB closed.2)Remove either SLC-RV-29A or SLC-RV-29B.
3)Install a flanged hose adaptor to the mating discharge flange where the relief valve was removed.4)Attach a 5/8 in.hose to the adaptor, route through the Reactor Building acess well to the 471 ft.elevation and insert approximately 3 ft.into the open standpipe.
5)Remove the orifice from the flanged joint (RHR-P-2C room above the sump).Replace with a 2-inch 150-lb Style CG flexatallic gasket and tighten flange.d.Mix a sodium-pentaborate solution.1)Verify SLC-V-1A and SLC-V-1B closed.2)Add demineralized water to SLC-TK-1 in 1000 gal.quantities as required for a total tank volume of 3000 gal.minimum.3)Turn on the mixing air and mixing heater.4)Add 710 lb borax and 683 lb boric acid for each 1000 gal.of water added to SLC-TK-1.PROCKOURK NUMSKR 5.1.3 RKVISION NUMBKR PACiK NUMQKR RPV/Q 5.1.3-5 of 9 WP$$$R1 (S OS) e.Inject boron with RCIC.1)2)3)4)Close DW-V-159 or stop DW-P-lA and DW-P-lB.RCIC-V-10 must be open for SLC injection; if necessary, open the breaker at'C-Sl-1D then manually open RCIC-V-10.
Open either SLC-V-lA or SLC-V-lB.Operate the RCIC System as required by contingent PPM 5.3.7, Level/Power Control but with positive RPV injection.
lel8.8 Inject boron using the RWCU System.a., Perform Step b and Step c concurrently.
b.Backwash both RWCU demineralizers; refer to PPM 2.2.3, Reactor Water Cleanup System.c.Defeat RWCU isolation interlocks and restart RWCU pumps: 1)Defeat Interlocks:
~1 1~M, H13-P 622 H13-P623 H22B-K26 H22B-k27 3-4 3-4 CAUTION 7-8 7-8 RWCU-V-1 RWCU-V-4 All isolation functions of RWCU-V-1 and RWCU-V-4 have been defeated at Step c.l.2)'pen RWCU-V-1 and RWCU-V-4.3)Open RWCU-V-44.
4)Start both RWCU pumps.Jog closed RWCU-V-44 to maintain pump discharge pressure approximately 150 psig higher than RPV pressure.d.Confirm both RWCU demineralizers in SHUTDOWN: 1)At the RWCU demineralizer control panel, and for both demineralizers, confirm: a)SHUTDOWN lights illuminated.
b)All demineralizer vessel valves closed.'PRGCEOURK NUMBER 5.1.3 WP 550 RI (5 4$)REVISION NUMBKR PAGE NUMBER RPV/9.5.1.3-6 of 9 e.Modif'y demineralizer control'f'or boron injection.
1)At the RWCU demineralizer control panel, change the following timers to the indicated settings: N-52, N-53, N-54, N-55, N-56, N-57, N-58, N-59, N-60, N-61,~Prewash Backwash Drain-Fill and Wash----'-Rewash-Drain-Fill-Finish Fill Precoat Introduction-Precoat-0 min.-0-0--0-0-0-0 1/2--0 10 CAUTION Continuous Health Physics coverage is required at the RWCU precoat tank area f'r subsequent steps.Borate either demineralizer:
1)Verif'y the OMIT-RUN switch is turned to RUN.2)Depress the demineralizer PRECOAT pushbutton and af'ter approximately 1/2 minute, verify the precoat pump running with recirculation through the precoat tank.3)At approximately equal rates add 200 lb each of borax and boric acid to the precoat tank.4)Complete borax and boric acid addition to the precoat tank in 10 min.or terminate addition and proceed to Step g when the PRECOAT COMPLETE alarm is received.RPY/0 PROCEDURE NUMBER 5.1.3 REVISION NUMBER PAGE NUMBER J 5.1.3-7 of'WP 999 Rl[9 9$)
g.Place the borated demineralizer on-line.1)Turn the ISOLATE-OEISOLATE switch to DEISGLATE and observe the following valves open: Q, Influent Eg, Effluent 2)Depress the RETURN TO HOLD pushbutton and observe: 4)Hold pump starts Hold pump discharge valve H opens Precoat pump stops Close the following manual valves: RWCU-V-225, Vent RWCU-V-230, Air RWCU-V-233, Backwash out RWCU-V-234, Precoat and Wash RWCU-V-238, Precoat supply RWCU-V-239, Vent Set RWCU-FRC-74 to 130 gpm.5)Depress the FILTER pushbutton and observe demineralizer effluent valve FCV-E opens.h.Close RWCU-V-44.
0 Repeat Steps 8.6.f and 8.6.g to borate and place the second demineralizer on line.Reborate and return demineralizers to service: Depress the HOLD pushbutton; observe demineralizer outlet FCV-E, closes and hold pump starts.2)3)Turn the ISOLATE-DEISOLATE switch to ISOLATE;observe the following valves close: A8, Inlet Eg, Outlet Open manual isolation valves RWCU-V-234 and RWCU-V-238.
PROCEDURE NUMBER 5.1.3 WP 990 R1 t9 99)REVISION NUMBER PACK NUMBKR RPV/Q 5.1.3-8 of 9 4)Depress the BACKWASH pushbutton and observe the SHUTDOWN light illuminates.
5)Depress the demineralizer PRECOAT pushbutton and observe the precoat pump starts and recirculates through the precoat tank.6)At approximately equal rates, add 200 lb each of borax and boric acid to the precoat tank.Complete this addition in 10 min.or terminate and proceed to Step 8)when the PRECOAT COMPLETE ALARM is received.7)Confirm the PRECOAT COMPLETE alarm is illuminated.
8)Depress the the RETURN TO HOLD pushbutton and observe the hold pump starts and precoat pump stops.9)Close manual isolation valves RWCU-V-234 and RWCU-V-238.
10)Turn the ISOLATE-DEISOLATE switch to DEISOLATE and observe the following valves open: AB, Influent Al, Influent EB, Effluent ll)Depress the FILTER pushbutton and observe demineralizer effluent valve FCV-E opens.k.Repeat Steps 8.6.j until either: 1)All rods are inserted, or 2)2130 lb.of'orax and 2050 lb.of'oric acid have been injected into the RPV.I I Exit this procedure and enter PPM 3.3.1, I Reactor Scram.IPROCEDURE NUMBER 5.1.3 REVISION NUMBER PAGE NUMBER RPY/Q 5.1.3-9 of 9 WP OSI R1 (5&3)
NASEWGTQN PUBLLC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 PROCCDVRC NVMCCR"5.2.1 OL CNAMC APPROVCD DATC Os/13/85 EMERGENCY PRO RES 5.2 CONTAINMENT CONTROL+5.2el SUPPRESSION POOL TEMPERATURE CONTROL (SP/T)5.2.1.1~Pur eee The purpose of'his procedure is to maintain primary containment integrity by controlling suppression pool temperature.
~th-d'his procedure is entered whenever the suppression pool average water temperature is above 9OoF..l.e I 1.Monitor and control suppression pool temperature.
2.Irrespective of the entry condition, execute this procedure concurrently with: a.FPM 5.2.2, Drywell Temperature Control (DW/T)b.PPM 5.2.3, Primary Containment Pressure Control (PC/P)c.PPM 5.2.4, Suppression Pool Level Control (SP/L)Close any open SRV or scram the reactor within 2 minutes.CAUTION If'ontinuous LPCI operation is required to assure adequate core cooling, do not divert all RHR pumps f'rom LPCI mode.4.When suppression pool average temperature exceeds 90oF, operate available suppression pool cooling.SP/T DVRC NVMCCR 5.2.1 Wle St7 RC (tWQI RgVISION NVMI5CR PACC NVMCCR 5.2.1-1 of 3 5.-Before suppression pool temperature reaches llOoF, scram the reactor and place the mode switch in SHUTDOWN.CAUTION Do not depressurize the RPV below 60 psig unless motor driven pumps suff'icient to maintain RPV water level are running and available for injection.
CAUTION Cooldown rates above lOOoF/hr may be required to accomplish the f'ollowing step.CAUTION Observe NPSH requirements f'r pumps tak-ing suction f'rom the suppression pool.Refer to PPM 5.0.0.6-If'uppression pool temperature cannot be maintained below the Heat Capacity Temperature Limit, maintain RPV pressure below the Limit:.'r HEAT CAPAClTY TEMPERATURE I.lMlT 210 g 200 P-190 180 170 0 O~o 160 150 140 130 120 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 APV PAESSUAE (PSIG)PROCEDURE NUMSER 5.2.1 WP SSS RI (S.IQ)REVISION NUMBER PAGE NUMBER SP/T 5.2.1-2 of' 7.Ef suppression pool temperature and RPV.pressure cannot be restored and maintained below the Heat Capacity Temperature Limit, emergency RPV depressurization is required, enter PPM 5.1.2, RPV Pressure Control (RPV/P): Concurrently, execute PPM 5.1.1 RPV Level Control (RPV/L)and PPM 5.1.3, Reactor Power Control (RPV/Q).SP/T PROCEDURE NUMBER 5.2.1 REVISION NUMBER PAGE NUMBER 5.2.1-3 of 3 WP SSI Rl{5 SO) 0 UMCQNTRQLLED CQPY WASHINGTON PUBLIC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL WNP-2 tROCCDURC NUMCCR+5.2.2 OLAJMC NAMC APPROVCD DATC 06/13/86 5 EMERGENCY PRO RES 5.2 CONTAINMENT CONTROL"5.2.2 ORYWELL TEMPERATURE CONTROL (DW/T)5.2.2.1~Pur oee The purpose of this procedure is to maintain primary containment integrity and protect equipment in the primary containment.
This procedure is entered whenever the average drywell temperature is above 135'F or any local temperature is above 150'F.1.Monitor and control drywell temperature.
2.Irrespective
'oi'he entry conditions, execute this procedure concurrently with: a.FPM 5.2.1, Suppression Pool Temperature Control (SP/T)b.PPM 5.2.3, Primary Containment Pressure Control (PC/P)c.FPM 5.2.4, Suppression Pool Level Control (SP/L)3.If at any time RPV water level was below-161 inches and containment pressure is below 18 psig, initiate both CAC systems.Refer to PPM 2.3.3, Containment Atmosphere Control.OW/T URC NUMBCR 5.2.2 Wh4$1 R2 ($44)RCV IDION NUMBCR ACMIC NUMBCR 5.2.2-1 of 4 When average drywell temperature exceeds 135'F or any local temperature exce ds 150'F, operate available drywell cooling./NOTE Execute the following steps concurrently.
n 5.Xf drywell temperature reaches the RPV Saturation Temperature, RPV f'looding is requred;enter: a.PPM 5.1.1, RPV Level Control (RPV/L)b.PPH 5.1.2, RPV Pressure Control (RPV/P)and execute them concurrently with this procedure.
RPV SATURATloN TEMPERATURE 600 IK Q 360C 300 250 0I 100 2N 300 400 600 600 700 800, 900 1000 RPV PRESSURE (PSIG)PAOCKDURK NUMSKR 5.2.2 WP$9$RI{9~I')RKVISION NUMSKR PACK NUMSKR OW/T 5.2.2-2 of' CAUTIONIf continuous LPCI operation is required to assure adequate core cooling, do not divert all%R pumps from LPCI mode.6.Before dry'well temperature reaches 340'F, but only-if suppression chamber temperature and drywell pressure are below the Drywall Spray Initiation Pressure Limit: a.Stop RRC pumps, drywell circulating fans and drywell cooling fans.b.Open drywell spray valves RFR-V-16B(A) and RHR-V-17B(A).
Use a single spray header (header 8 if possible).
DRYVfELL SPRAY INITIATION PRESSURE LIMIT 250 240 8~>>P a.'<@pg": 220 0 K 200 1SO 160 R O 14O 5;+~ijgi";y~gF 120 100 15 20 25 30 35 40 45 50 SUPPRESSION CHAMSER PRESSURE (PSIG)~PRQCEOURC NUMSCR 3.2.2 W~tt R'I (~t)RKVltlON NUM OCR PAQC HUMOR OW/T 3.2.2-3 of 4 7.If drywell temperature cannot be maintained below 340'F, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure control (RPV/P).Concurrently, execute PPM 5.1.1, RPV Level Control (RPV/L)and PPM 5.1.3, Reactor Power Control (RPV/q).PROCKDURK NUMBKR 5.2.2 WP 99$R1 (9 99)RKVISION NUMBKR PACK NUMBKR OW/T 5.2.2-4 of 4 UNCGNTRGLLEG CQPY WASHINGTON PUBLIC POWER SUPPLY SYSTEM PLANT PROCEDURES i~JAL%NP-2 PROOCDURC NUMCCR+5i2+3 OL MC NAMC At OVCD OAl'C 06/13/85 5 EMERGENCY PROC ES 5.2 CONTAINMENT CONTROL+5.2.3 PRIMARY CONTAINMENT PRESSURE CONTROL (PC/P)5.2.5.1~Per oee The purpose of this procedure is to maintain primary containment integrity.
This procedure is entered whenever primary containment pressure exceeds le65 psig.2.Monitor and control primary containment pressure.Execute this procedure concurrently with: a.FPM 5.2.1, Suppression Pool Temperature Control (SP/T)b.PPM 5.2.2, Orywell Temperature Control (OW/T)c.PPM 5.2.4, Suppression Pool'evel Control (SP/L)CAUTION High suppression chamber pressure (25 psig)may trip the RCIC turbine on high exhaust pressure.3.Operate SBGT.Open drywell and suppression chamber 2-inch purge exhaust valves but only when the space being vented is below 212'F.Refer to PPM 2.3.1, Primary Containment Venting, Purging and Inerting, Sect:ion B.PC/P P URC NVMCCR 5.2.3 RKVtdlON NUMOCR AOC NVMBCR 5.2.3-1 of 8 WP OOI AZ itW) 4.If an RPV low level indication occurred or is present, manually initiate the MSLC System when the RPV has depressurized to 35 psig.Refer to PPM 2.2.6, Main Steam, Section B.5.If't any time, RPV water level was below-161 inches and containment pressure is below 18 psig, initiate both CAC systems.Refer to PPM 2.3., Containment Atmospheric Control.CAUTION Observe NPSH requirements for pumps tak-ing suction from the suppression pool.Refer to General Cautions 88, PPM 5.0.0.CAUTION If continuous LPCI operation is required to assure adequate core cooling, do not'ivert all RHR pumps from LPCI mode.6.Before suppression chamber pressure reaches 16.5 psig, but only if suppression pool water level is below the elevation of the spray header (53 ft.), initiate suppression pool sprays.PROCKDURK NUMBKR 5.2.3 RKVI5ION NUMBER PAGK NUMBKR PC/P 5.2.3-2 of'WP 990 Rt (9%5)
CAUTION If continuous LPCI operation is required to assure adequate core cooling, do not divert all Rl+t pumps from the LPCI mode.i l rr 7.If suppression chamber pressure exceeds 16.5 psig, but only if'uppression chamber temperature and drywell pressure are below the Orywell Spray Initiation Pressure Limit: a.Stop RRC puIIps, drywell circulating fans and drywell cooling f'ans.b.Open drywell spray valves RHR-V-168(A) and RHR-V-178(A).
Use a single spray header (header 8 if possible).
DRYNELL SPRAY INlTIATION PRESSURE LIMli 4"~oC g 220 200 180 5 g+160 140'8 cf~-W~W~~~,.g.Xi@i'20 15 20 25 30 35 40 45 50 SUPPRESSION CHAMBER PRESSURE (PSIG)PRQCKDURC RUMOUR 5.2.3 WP'ISO Rl IS~)RCVIOlCN NUMOKR PhQC NUMOCR PC/P 5.2.3-3 of' 8.Xf suppression chamber pressure cannot be maintained below the Pressure Suppression Pressure, emergency RPV depressurization is, required, enter PPM 5.1.2, RPV Pressure Control (RPV/P).Concurrently, execute PPM 5.1.1, RPV Level Control (RPV/L)an PPM 5.1.3>Reactor Power Control.PRESSURE SUPPRESSION PRESSURE 40 6 z O W 3020 20 30 40 50 PRIMARY CONTAINMENT WATER LEVEL.(FT.)CXI1W l1 PC/P PROCKDURK NUMSKR 5.2.3 WP SIII RI (9 43)RKVISION NUMSKR PAGK NUMSKR 5.2.3-4 of' 9.D'uppression chamber pressure cannot be maintained below the Primary Containment Design Pressure, RPV flooding is required, enter contingent PPM 5.3.6, RPY Flooding and execute concurrently with this procedure.
PRIMARY CONTAINMENT DESIGN PRESSURE i I 50 I 4 40 I 5 Q 00 Q 549 P5IQ 44 FT.10 0-10 20 00 40 50 60 PR04ARV CONTAINMEMT WATER LKVEL (FT.)PROCKOURK NUMSKR 5.2.3 WP 599 RI{9 9$)RKVISION NUMBKR PACK NUMSKR PC/P 5.2.3-5 of 8 10.D'uppression chamber pressure cannot be maintained below the Primary Containment Pressure Limit, PRIMARY, CONTAINMENT PRESSURE LIMIT 100 90 CD 5, 70 6 60 O 50 I I 98 PSIQ 29.92 FT.90 PSIQ 44 FT.0 10 20 30 40 50 60 70 SUPPRESSION CHAMBER IcVATER LEVEL (FT.)then irrespective of whether adequate core cooling is'ssured:
10.1 Xf suppression pool water level is below the elevation of'he spray header (53 ft.), initiate suppression pool sprays.PRQCCQURC NQMCCR 5.2.3 W~SI Rl{~)RCV!SION NLIMCCR IcA4C NVMCCR PC/P 5.2.3-6 of' 10.2 If suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit: 'RYWELL SPRAY INITIATION PRESSURE LtMIT" 240;K+?Pc8.4~4?~<<HgV ,":~>~e>.<o.~.<~
?<<><<py<<.)15 20 25 20 25 40 45 50 SUPPRESSION CHAMBER PRESSURB (PSIQ)a.Stop RRC, drywell circulating f'ans and drywell cooling f'ans.b.Open drywell spray valves RHR<<Y-16B(A) and RHR-V-17B(A).
Use a single spray header (header B if'ossible)
.PROCKQVRK NUMKCR 5.2.3 RKVtKION NUMOCR PACK NUMKCR pc/p 5.2.3-7 of 8 CAUTION Two-inch suppression chamber and drywell purge exhaust valve isolation interlocks are defeated by holding control switches to the OPEN position.D ll.If suppression chamber pressure exceeds the Primary Containment Pressure Limit, vent the primary containment through the 2-inch purge exhaust in accordance with PPM 2.3.1, Primary Containment Venting, Purging and Inerting, Section B to reduce and maintain pressure below the Primary Containment Pressure Limit,.PR/MARY CONTAINMENT PRESSURE LIMIT 100 U 90 g 80 5 m X 60 O 50 96 PSIQ 29.93 FT.90 PSI 44 FTe 0 10 20 30 40 50 60 70 SuPPRESSION CHAMBER WATER LEVEL (FT.)PRQCKOUNC NUMSCh 5.2.3 WF.49$Rl (9~)RCVISiON NUM4Ch PC/P g.2.3-8 of 8 NCQNTHGLLEG CGPY WASHBTGTON PUBLIC PQVSER SUPPLY SYSTEM PLANT PROCEDURES i~NUAL%NP-2 PRDCCDURC NUMCCR A DVCD DATC 06/13/85 DL MC NAMC 5.2 e EMERGENCY PROCE RES CONTAINMENT CONTROL 5.2.4.1~Pur oee The purpose of this procedure is to maintain primary containment integrity and protect equipment in the primary containment.
.*.This procedure is entered whenever suppression pool water level: 1.Goes above 31 ft.1-3/4 in.(+1-3/4 in.on CMS-LR-3 or 4)or, 2.5.2.4.3 Drops below 30 ft.9-3/4 in.(-2-1/4 in.on G45-LR-3 or 4).1.Monitor and control suppression pool level.2.Execute this procedure concurrently with: a.PPM 5.2.1, Suppression Pool Temperature Control (SP/T)b.PPM 5.2.2, Drywell Temperature Control.(DW/T)c.PPM 5.2.3, Primary Containment Pressure Control (PC/P)CAUTION Observe NPSH requirements f'r pumps taking suction from the suppression pool.Refer to PPM 5.0.0.SP/L URC NVMSCR 5.2.4 RCVImDN N VMSCR AQC NV MBCR 5.2.4-1 of 9 WP 507 RR (tWQi CAUTION If HPCS SUCTION SWITCHOVER SUPPRESSION POOL LEVEL HIGH or HPCS/RCIC SUCTION SWITCHOVER CST LEVEL LOW alarms occur, confirm automatic transfer of or manually transfer HPCS and RCIC suction from the condensate storage tank to the suppression pool.RCIC suction will not auto transfer on high suppression pool level.3.Maintain suppression pool water level between+1-3/4 in.and-2-1/4 in.on CMS-LR-3 or 4.3.1 Lower suppression pool level using RHR Loop 8: a.Operate RHR-P-28 b.Request the HP/Chemist sample RHR Loop B.Refer to PPM 12.10.1, Post Accident Sampling and Analysis.c.Request the Radwaste Control Operator to line up either the Waste Surge or Floor Drain Collector Tanks for reject from RHR.d.Confirm sample results permit discharge.
e.Open RHR-V-49 Open RHR-V-40 g.Monitor suppression pool level.Stop reject when level is lowered to 0 in.on CMS-LR-3 or 4.3.2 Raise suppression pool water level as follows: 3.2.1 If HPCS has not auto started: a.Verify HPCS suction from CST, HPCS-V-1, is open..b.With HPCS-P-1 operating, throttle open test valve HPCS-V-23.
3.2.2 If HPCS is not available:
a.Verify Reactor Building condensate supply header pressurized.
PROCEDURE NUMeER 5.2.4 WP 5$$Rl (9$3)REv>s<Ql$NUMeeR pacE nuMeER spn5.2.4-2 of 9 b.Install pipe spool between RHR-V-106 (RHR-P-2C suction piping)and COND-.V-28.
c.Open COND-V-28.
d.Open RHR-V-106.
e.Monitor suppression pool level.Close RHR-V-106 when level is restored to 0 in.on CMS-LI-3 of'.4.If'uppression pool water level cannot be maintained above 30 ft.9-3/4 in., (-2-1/4 in on CMS-LR-3 or 4)proceed to Step 6.5.If suppression pool water level cannot be maintained below 31 ft, 1-3/4 in.(+1-3/4 in.on CMS-LR-3 or 4), proceed to steps 7 and 8 and execute those steps concurrently.
RQCKDURK NUMBKR 5.2.4 WP$99 R1 I9 99)RKVISIQN NUMBKR I ACK NUMBKR SP/L 5.2.4-3 of 9 6.If suppression pool water level cannot be maintained above 30 ft.9-3/4 in.(-2-1/4 in.on NS-LR-3 or 4): 6.1.Maintain level above the Heat Capacity Level Limit HEAT CAPACITY LEVEL LIMIT 31 30 2S 25 27 25 Po 4 21 Po 20 17 15 0 5 10 15 20 25 30 35 40<T HO ('F)LIT~~HCTL MBIUS SUPPRESSION POOL TEMPERATURE I HEAT CAPACITY TEMPERATURE I IMIT 210 100 I 170 O 160 150 O.140 130 120 0 100 200 300 400 500 600 700 800 900 1000 1100 1200 RPV PRESSURK (PSIQ)SP/L PROCEDURE NUMBER 5.2.4 REVISION NUMBER PAGE NUMBER 5.2.4.-4 of 9 WP 59a Rl (5 43)
6.2 If'evel
cannot be maintained above the Heat Capacity Level Limit, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).Concur-rently, execute PPM 5.1.1, RPV Level Control (RPV/L)and PPM 5.1.3 Reactor Power Control (RPV/0).7.Maintain suppression pool water level below the Suppression Pool Load"~i""t.SUPPRESSiON POOL LOAD LlMlT 44 42 Ml 41 P 40 O 38 O 37 O 36 34 33 3'1 30 200 300 400 500 600 700 800 900 1000 1100 1200 APV PRESSURE (PSIG)SP/L PIIOCCDVRC NVMCCR 5.2.4 wf 4$I Rl (%441 RCVICIQN NLIMBCR PAQC NVMSCR 5.2.4-5 of' CAUTION Do not depressurize the RPY below 60 psig unless motor-driven pumps sufficient to maintain RPV water level are running and available for injection.
CAUTION Cooldown rates above 100oF/hr may be required to accanplish the following step.7.1 If'uppression pool water level cannot be maintained below the Suppression Pool Load Limit, maintain RPY pressure below the Limit.7.2 If suppression pool water 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 injection systems and CRO.SUPPRESSION POOL LOAD LIMIl46 44 42 41 39 O 38 O 37 3$w 35 34 33 32 31 30 200 300 400 500 600 700 600 900 1000 1100 1200 RPV PRESSURE (PSIG)PNQCCQVRC NVMBCR 5.2.4 RCVl31ON NVMBCI%PAQ4 NVMBKR SP/L 5.2.4-6 of 9 0 7.3 if suppression pool water level and RPV pressure cannot be restored and maintained below the Suppression Pool Load Limit, emergency RPV depressurization is required, enter PPM 5.1.2, RPV Pressure Control (RPV/P).Concurrently, execute PPM 5.1.1, RPV Level Control (RPV/L)and PPM 5.1.3 Reactor Power Control (RPY/Q).I'.Before suppression pool water level reaches the bottom of the drywell vacuum breakers (54 ft.6*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.PROCEDURE NUMBER 5.2.4 WP 599 Rl (9.99)REVISION NUMBER PACE NUMBER SP/L 5.2.4-7 of 9 CAUTION If'ontinuous LPCI operation is required t'o assure adequate core cooling, do not divert all RN pumps from LPCI mode.8.1 When suppression pool water level reaches the bottom of the drywell vacua breakers (54 f't.6 in.)but only if suppression chamber temperature and drywell pressure are below the Drywell Spray Initiation Pressure Limit: a.Stop recirculation pumps, drywell circulating fans and drywell cooling f'ans.b.Open drywell spray valves RHR-Y-168(A) and RHR-V-178(A).
Use a single spray header (header 8 if'ossible)
.ORYNELI SPRAY INITlATION PRESSURE LIMIT g'2D 200 W ill>'tao W 160 O 140 c+VI sigyn 4 15 2D 25 30 35 40 45 50 SUPPRESSlON CHAMBER PRESSURE (PSIG)RCVlllCN NVIIOCR PACK%NUN4CR SP/L 5.2.4-8 of 9 CAUTION Do not initiate drywell sprays if suppres-sion'pool water level is above the bottom of the drywell vacuum breakers (54 ft.6 in).8.2 lf suppression pool water level exceeds the bottom of the drywell vacuum breakers (54 ft.6 in.), continue to operate drywell sprays.8.3 When primary containment water level reaches the 551 ft.elevation, terminate injection into the RPV f'rom sources external to the primary containment irrespective of'hether adequate core cooling is assured.PROCKOVRK NUMBKR 5.2.4 WP.SSI RI IK I3)RKVISION NUMBKR PACK NUMBKR sp/L 5.2.4-9 of 9
UNCONTRQLLED COPY WASHINGTON PUBLIC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL VFNP-2 PRQCCOVRC NUMCCR+5.2.5 QL,UMC NAMC AP QVCD OATC 06/13/85'5 EMERCENCY FROCED RES 5.2 FRECAUTIONS
+5.2.5 SECONOARY CONTAINMENT CONTROL 5.2.5.1 Puzuase The purpose of this procedure is to: 1.Protect equipment in the secondary containment.
2.Limit radioactivity release to the secondary containment, and either: a.Maintain secondary containment integrity, or b.Limit radioactivity release from the secondary containment.
j j Entry conditions for this procedure are any of the following:
I 1.Secondary containment differential pressure at or above 0 in.of water.2.An area temperature (Table 1)above the maximum normal operating temperature.
A HVAC cooler differential temperature in the alarm state.4.A HVAC exhaust radiation level above the maximun normaL operating radiation level.5.An area radiation level (Table 2)above the maximum normal operating radiation level.6.An area water level (Table 3)above the alarm level.VRC NVMSCR 5.2.5 RCV IDION NV MOCR AQC NVMSCR 5.2.5-1 of 6 WP 407 RZ (tWt)
If, while executing the i'ollowing steps, Reactor Building HVAC exhaust plenum radiation level exceeds LS mr/hr: a.Conf'irm or manually initiate isolation of Reactor Building HVAC and, b.Conf'irm initiation of or manually initiate SBGT.NOTE: If', while executing the f'ollowing steps: a.Reactor Building HVAC isolates, and b.Reactor Building HVAC exhaust'radiation level is below l3 mr/hr, restart secondary containment HVAC.If'equired, jumper interlocks at individual equipment pieces;do not jasper high drywell or low RPV water level trips.Refer to E514, sheet 33.1.Monitor and Control Secondary Containment Temperatures.
L.1 Operate available area, coolers.1.2 O'eactor Building HVAC exhaust plenum radiation level is below.13 mr/hr, operate available HVAC.1.3 If'ny area temperature exceeds its maximum normal operating temperature (Table 1), isolate all systems that are discharging into the area except systems required to shut down the reactor, assure adequate cori cooling, or suppress a working f'ire.1.4 If a primary system is discharging into an area, then before an area temperature reaches its maximum safe operating temperature (Table 1), enter PPM 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure.
0 1.5 If a primary system is discharging into an area, and an area temperature exceeds it maximum sai'e operating temperature in more than one area, emergency depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).PROCKDURK NUMBKR 5.2.5 WP$90 Rl[9%0)RKV IKION NUMSKR PaOK NUMKKR 5.2.5-2 of 6 2.Monitor and Control Secondary Containment Radiation Levels.2.1 If a primary system is discharging into an area, then bef'ore an area radiation level reaches the alarm level (Table 2), enter PFH, 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure.
2.2 If'ny
area radiation level exceeds the alarm level, isolate all systems that are discharging into the area except systems required to shutdown the reactor, assure adequate core cooling or suppress a working f'ire.2.3 If'primary system is discharging into an area and an area radiation level exceeds the alarm level (Table 2)in more than one area, emergency RPV depressurization is required;enter FPM 5.1.2, RPV Pressure Control (RPV/P).3.Monitor and Control Secondary Containment Water Levels.3.1 If'ny f'loor drain sump water level is above the alarm level, operate available sunp pumps to restore and maintain the water level below the maximum normal operating water level.(Xf'ny f'loor drain sunup level cannot be restored and maintained below the alarm level, isolate all systems discharging water into the sump except systems required to shut down the reactor, assure adequate core cooling, or suppress a working f'ire.3.2 If a primary system is discharging into an area, and any water level reaches the Above Floor Level water level (Table 3), enter PPM 5.1.2, RPV Pressure Control (RPV/P), and execute concurrently with this procedure.
3.3 If'primary
system is discharging into an area and an area.water level exceeds the Maximum Saf'e Operating Level (Table 3)in more than one area, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P).EOURE NUMBER REVISION NUMBER PAGE NUMBER 5.2.5 WP 990 RI I9%$)5.2.5-3 of 6 TABLE 1 Secondary Containment Temperature Control Location ILPCS P Room I IHPCS P Room I I CRD P Room I IRHR P Roce B I)Rial P Room A I IRCIC P Room I IDC MCC Room I!Steam Tunnel'l 5221 Elevation I IDiv.2 MCC Room I lRWCU P Room Div.1 MCC Room IRWCU HX Room I~SR-13/14 (H202 Anal)I IRf%HX Room'B l IFFC Puo Room I IRl%HX Room A I IMC-7B-B Room I IMC-8B-8 Room Alaxm OF 105 138 130 135 145/173 135/185 Maximum Normal Operating Value'F 104 104 120 104 120 104 104 Maximum Safe Operating Value'F 212 150 128 205 205 150 128 106 245 106 200 128 212 106"I I 106 I 0 PROCKOURK NUIHSKR 5.2.5 WP 595 R1 (5%5)RKVI5ION NUINSKR PAQK NUMSKR 5.2.5-4 of 6 0 TABLE 2 Secondary Containment Radiation Control Location Alarm (mr/hr)ARM-RIS-4 CRD HCUS East ARM-RIS-5 CRD HCUS West ARM-RIS-7 TSP Drive Room ARM-RIS-9 Rf+-P-2A Room ARM-RIS-10 Rl+-P-28 Room ARM-RIS-ll RN-P-2C Room ARM-RIS-12 RCIC-P-1 Room ARM-RIS>>13 HPCS-P-1 Room ARM-RIS-23 CRD P Room ARM-RIS>>24 I Rx 471.'est I I ARM~IS-m I Rx 471'E I I ARMWIS-P I Rx 501'NW 15 15 25 20 15 50 P KOURK NUMBKR 5.2.5 WP$99 RI (9&9)RKVISION NUMBKR PaaK NUMBKR 5.2.5-5 of 6 TABLE 3 Seconctary Containment Water Level Control Location.I LPCS P Room I I HPCS P Room I l RN Pum Room B I I RfR P Room A Above Floor Level Alarm (In.)Maximum Safe Operating Level (Inches Above Floor Level)69 I RCIC P Room I I RN P Room C I I CRD P Room 45 (+)EDR-R-5 alarm level at 420'9", f'loor level is 422'3".PROCEDURE NUMBER 5.2.5 WP$80 Rl{SWQ)REVISION NUMBKR PAOK NUMBER 5.2.5-6 of' UNCONTROLLED COPY WASKNGTON PUBLlC POWER SUPH Y SYSTEM PRQCCDVRC NVMCCR+5.2.6 4 MC NAMC PLANT PROCEDURES MANUAL%NP-2 AP QVCD DATC 06/13/85 5 EMERGENCY PROCE RES 5.0 PRECAUTIONS
+.2.6 RADIOACTIVITY RELEASE CONTROL 5.2.6.1 Purpose The purpose of'his procedure is to limit radioactivity release into areas outside the primary and secondary containments.
The entry condition for this procedure is: Offsite radioactivity release rate (determined by STA)above 1/2 mr/hr (Site Alert)5.2.6.5~~~0 erator Actions Isolate all primary systems that are discharging into areas outside the primary and secondary containments except those required to assure adequate core cooling or shutdown the reactor.2.If of'f'site radioactivity release rate approaches or exceeds 1 R/hr (General Emergency) and a primary system is discharging into an area outside the primary and secondary containments, emergency RPV depressurization is required;enter PPM 5.1.2, RPV Pressure Control (RPV/P)and execute concurrently with this procedure.
P UAK NVMSCR 5.2.6 RCVI544N NUMICR PAQ NVMSCR 5.2.6-1 of'Wt Std RC (tgt) 0~P ll WGONTROLLEQ COPY PLANT PROCEDURES MANUAL%P-2 WASKNGTON PUBLIC POWER SUPPLY SYSTEM PRQCCQURC NVMBCR+5.3.1 Ql VMC HAMC A RQVCQ QATC 06/13/85 5.3 EMERGENCY PROC RES EMERGENCY PROCEDURE CONTINGENCIES
+5.3.1 LEVEL RESTORATION (CONTINGENCY)
If while executing the following steps: 1.Boron injection is required, exit this procedure and enter contingent PPM 5.3.7, Level/Power Control.2.RPV water level cannot be determined, RPV flooding is required;exit this procedure and enter contingent PPM 5.3.6, RPV Flooding.RPV flooding is required, exit this procedure and enter contingent PPM 5.3.6, RPV Flooding.1.Line up for injection and start pumps in 2 or more of the following injection subsystems:
a.Condensate
-Condensate Booster b.MPCS c.LPCI-A d.LPCI-B e.LPCI-C LPCS 2.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: C-LR V R C tlV M BCR 5.3.1 RCVIQQN RVMBCR PAQ tIVMBCR 5.3.1-1 of 6 WP St7 RB (SQS) 2.1 RHR Service Water Crosstie 2.2 Fire Water to Condensate Tie: a.String fire hose from nearest outside hydrant to COND-P-2A.
b.Attach hose to adapter at COND-P-2C suction.2.3 ECCS Condensate Flush Connections.
Install removable pipe spools between the Condensate Supply System and any one of the following ECCS injection subsystems having an inoperable pump.Open the related Condensate Supply Valve.a.LPCS (COND-V-26) b.LPCI-A (COm-V-36) c.LPCI-8 (COND-V-35) d.LPCI-C (COM3-V-37) 2.4 SLC (test tank)2.5'LC (boron tank)3.Monitor RPV pressure and water level.Continue in this procedure at the step indicated in the following Table: (360 psig)1 RPV Pressure Region (60 psig)2 HIGH INTERMEDIATE LOW Increasing V E I Decreasing LI 1(RPV pressure at which LPCS Shutoff head is reached.)2(RCIC low pressure isolation setpoint.)
PROCKDURK NUMSKR 5.3.1 WP IItl Rl{0 i'd)RKVISION NUMKKR PAERK NUMQKR 5.3.1-2 of 6 4.If while executing Steps 5 through 9: 4.1 The RPY water level trend reverses or changes region, return to Step 3.4.2 RPV water level drops below-129 in., inhibit AOS.5.RPV Water Level Increasing, RPV Pressure High Exit this procedure and enter PPM 5.1.1, RPV Level Control, (RPV/L)Step 3.Concurrently, execute PPM 5.1.2, RPV Pressure Control (RPV/P)Step 5.6.RPV Water Level Increasing, RPV Pressure Intermediate If RCIC is not available and RPV pressure is increasing, emergency RPV depressurization is required.Enter contingent PPM 5.3.2, Emergency RPV Oepressurization and execute concurrently with this procedure.
When RPV pressure is decreasing, exit this procedure and enter PPM 5.1.1, RPV Level Control (RPV/L)at Step 3.If RCIC is not available and RPV pressure is not increasing, exit this procedure and enter PPM 5.1.1, RPY Level Control (RPV/L)Step 3.I I When RPV water level reaches+13.0 inches, exit this I procedure and enter PPM 5.1.1, RPV Level Control (RPY/L)at Step 3.I OURK NUMBKR 5.3.1 RKVIBION NUMBKR 1 PAQK NUMBKR C-LR 5.3.1>>3 of 6 WP StS Rl (t&3) 7.RPV Water Level Increasing, RPV Pressure Low If'PV pressure is increasing, emergency RPV depressurization is required.Enter contingent PPM 5.3.2, Emergency RPV Depressurization and execute concurrently with this procedure.
When RPV pressure is decreasing, exit this procedure and enter PPM 5.1.1, RPV Level Control (RPV/L)at Step 3.If'PV pressure is not increasing, exit this procedure and enter PPM 5.1.1, Level Control (RPV/L)at Step 3.8.RPV Water Level Decreasing, RPV Pressure High or Intermediate 8.1 lf HPCS or RCIC is not operating, restart whichever is not operating.
8.2 If no injection subsystem is lined up f'r injection with at least one pump running start pumps in alternate injection subsystems which are lined up f'r injection.
8.3 When RPV water level drops to-161 in.(TAF):a 4 If'o system, injection subsystem or alternate injection subsystem is lined up with at least one pump running, steam cooling is required.Enter contingent PPM 5.3.3, Steam Cooling and execute concurrently with this procedure.
b.When any system, injection subsystem or alternate injection subsystem is lined up with least one pump running, return to Step 3 of this procedure.
c.When any source of'akeup water is available, emergency depressurization is required.Enter PPM 5.3.2, Emergency RPV Depressurization and execute concurrently with this procedure.
PROCKOURK NUMBKR 5.3.1 REVISION NUMBKR PACK NUMBKR 5.3.1-4 of 6 WP.$90 Rl I9 9S)
CAUTION If the Condensate Supply System is valved to any ECCS injection subsystem, do not leave the connecting ECCS valve unattended and open.r I d.When RPV pressure decreases to 100 psig, valve the condensate supply system to that ECCS subsystem with an installed pipe spool by opening the related valve.1)LPCS (LPCS-V-25) 2)LPCI-A (RHR-V<<63A) 3)LPCI-B (RHR-V-63B) 4)LPCI-C (RHR-V-63C) e.When RPV water level is increasing or RPV pressure drops below 60 psig, return to Step 3 of this procedure.
9.RPV Water Level Decreasing, RPY Pressure Low 9.1 If no HPCS or LPCS subsystem is operating, start pumps in alternate injection subsystems which are lined up f'r injection.
9.2 If'PV
pressure is increasing, emergency RPV depressuri-zation is required.Enter PPM 5.3.2, Emergency Oepressur-ization and execute concurrently with this procedure.
CAUTION If the Condensate Supply System is valved to any ECCS injection subsystem, do not leave the connecting ECCS valve unattended and open.9.3 When RPV pressure decreases to 100 psig, valve the condensate supply system to that ECCS subsystem with an installed pipe spool by opening the related valve.1)LPCS (LPCS-V-25) 2)LPCI-A (RHR-V-63A) 3)LPCI-8 (RHR-V-63B) 4)LPCI-C (RHR-V-63C)
PROCKI3URK NUMBKR 5.3.1 WP 59~RI (3 l3)RKVISIQN NUMBKR PACK NUMBKR ,.C-LR 5.3.1-5 of 6 When RPV water level drops to-161 in.(TAF), exit this" procedure and enter contingent PPM 5.3.4, Core Cooling Without Level Restoration.
PROCEOUAE NUMBKR 5.3.1 REVISION NUMBER PAGE NUMBER 5.3.1-6 of 6 WP 55~AI (8 53)
NCoe'aOL~ED t:OPY WASKNQTON PUBUC POWER SUPPLY SYSTEM PLANT PROCEDURES i~NUAL WNP-2 9RQCCDVRC NVMCCR+5.3.2 A PRDVCD ETC 06/13/85 I VM NAMC 5 EMERGENCY PRO RES 5.3 EMERGENCY PROCEDURE CONTINGENCIES
+5.3.2 EMERGENCY RPV DEPRESSURIZATION (CONTINGENCY)
CAUTION Cooldown rates above 100oF/hr may be required to accomplish this contingent procedure.
CAUTION Do not depressurize the RPV below 60 psig unless motor driven pumps suf'ficient to maintain RPV water level are running and available for injection.
1.When either: a.Boron injection is required and all injection into the RPV~exec t from boron in ection~aeterna and CRD has been terminated and prevente, or b.Boron injection is not required, 1.1 If suppression pool water level is above 17 f't.: a.Open all ADS valves.b.If'ny ADS valve cannot be opened, open other SRV's until 7 valves are open.CAUTION Defeating isolation interlocks may be required to accomplish the following step.C-ED URC NUMCCR 5.3.2 RCVISION NUMSCR Are NUMIICR 5.3.2-1 of 2 Wls$97 Rg (9WQ) 1.2 If less than 3 SRV's are open, rapidly depressurize the RPV using one or more of the following systems: a.Main Condenser D'equired, bypass RPV low water level MSIV and steam'line drain isolation interlocks by installing the following jumpers: Location H13-P609 H13-P 609 H13-P611'13-P611~Rela, Contact K1A.1-2 K1C 1-2 K1B 1-2'10 1-2 b.Main steam line drains.Open MS-V-16, MS-V-19 and MS-V-21 c.S3AE d., Sealing Steam e.RFW Turbines f'.Off Gas Preheaters'.
RWCU (recirculation through the heat exchanger) if no boron has been injected into the RPV.h.RWCU (blowdown mode)if no boron has been injected into the RPY.Instruct the HP/Chemist to sample the RPV coolant in accordance with PPM 12.10.7, Post Accident Sampling and Analysis and report results to the Control Room prior to initiating blowdown.Do not blowdown if'ample results indicate core damage.i.Head vents.Open MS-V-1 and NS-V-2 I I If RPV flooding is required, exit this I procedure and enter contingent PPM 5.3.6, I RPV Flooding.I Exit this procedure and enter PPM 5.1.2, RPV Pressure Control (RPV/P)Step 14.PRUCEOVRK NVMBKR 5.3.2 WP-SSIRl(B~N)
RKVlslQN NVMBKR PARK NVMBKR 5.3.2-2 of 2 DMCQNTRGLLEG CGPY PROCCOURC NUMCCR+5.3.3 OLAJMC NAMC WASKNGTON PUBLIC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 httROV 0 06/13/85 5 EMERGENCY PRO RES 5.3 EMERGENCY PROCEDURE CONTINGENCIES
+5.3.3 S'KAM COOLING (CONTINGENCY)
If while executing the following steps, emer-gency RPV depressurization is required or any system, injection subsystem or alternate in-jection subsystem is lined up with at least one pump running, exit this procedure and enter PPM 5.3.2, Emergency RPV Oepressurization.
ttthen RPV water level drops to-278 in.or if'PV.water level cannot be determined, open one SRV.I l When RPV pressure drops below 700 psig exit this I procedure and enter PPM 5.3.2, Emergency RPV l Depressurization.
I C-STM URc NUMscR 5.3.3 RCVI54ON NUMSCR AC NUM R 5.3.3-1 of 1 WMI7 RZ ($WQ) 0 WASKNGTON PUBUC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL WNP-2 PROCCDV RC NVMSCR+5.3.4 A ROVCD DATC 06/13/85~5 EMERGENCY PROC RES 5.3 EMERGENCY PROCEDURE CONTINGENCIES
+5.3.4 CCRE COOLING WITHOUT LEVEL RESTORATION (CONTINGENCY)
CAUT10N Cooldown rates above 100oF/hr may be required to accomplish this step.1.Open all 7 AOS valves.2.If all AOS valves cannot be opened, open other SRVs until 7 valves are open.3.Operate HPCS and LPCS with suction from the suppression pool.When: a.Either HPCS or LPCS is operating with suction from the suppression pool and, b.RPV pressure is below 122 psig, Terminate injection into the RPV from sources external to the primary containment.
When RPV water level is restored to-161 in.(TAF), exit this procedure and enter PPM 5.1.1, RPV Level Control, (RPV/L)Step 6.C-W/0 LR URC NUMCCR 5.3.4 WP 407 RZ (I~)RCVl5lON NVMQCR AO NUMSCR 5.3.4-1 of' QMCQN78QII.I.EQ COPY WASKNGTON PUBLIC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 PRQCCQURC NUMCCR+5.3.5 OLU C NAMC ROVCO OATC 06/13/85 5 EMERGENCY PRO RES 5.3 EMERGENCY POROCEDURE CONTINGENCIES
+5.3.5 ALTERNATE SHJTDOWN COOLING (CONTINGENCY) l.Initiate'uppression pool cooling.2.Close: 2.1 RPV Head Vents MS-V-1 MS-V-2 2.2 MSIV'2.3 Main Steam Line Drains MS-V-16 MS-V-19 2.4 RCIC, Steam Isolation Valves RCIC-V-8 RCIC-V-63 RCIC-V-76 Place the control switch f'r 2 SRVs in the OPEN position.4.Slowly raise the RPV water level to establish a flow path through the open SRVs back to the suppression pool.5.Start LPCS or one RHR pump with suction from the suppression pool.'C-ASC URC NUMSCR 5.3.5@&457 RZ (SWQ)RCV<aaN NUMSCR AQ NUMS R 5.3.5-1 of 2 6.Slowly increase LPCS or RHR injection flow into the RPV to maximum.6.1 If RPV pressure does not stabilize at least 76 psig above suppression chamber pressure, start the LPCS or another RHR pump.6.2 If RPV pressure does not stablize below 120 psig,, open another SRV.6.3 If'he cooldown rate exceeds 100oF/hr, reduce LPCS or RHR injection into the RPV until the cooldown rate decreases below 100oF/hr.7.Control suppression pool temperature to maintain RPV water temperature above 80oF.8.Proceed to cold shutdown in accordance with PPM 3.2.1, Normal Shutdown to Cold Shutdown.PROCCQURC NVMBCR 5.3.5 WP.444 R4 (t&5)RKYI5ION NVMBCR PAOC NUMSCR C-ASC 5.3.5-2 of 2 UNt;GNTHGLLEG CGP Y WASKNGTON PUBLlC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL%NP-2 PROCCDURC NUMCCR+5.3.6 OLUMC NAMC A ROVCD DATC 06/13/85 5 EMERGENCY PROCEDURES
5.3 EMERGENCY
PROCEDURE CONTINGENCIES
+5.3.6 RPV FLOODING (CONTINGENCY) 1.If at least 3 SRV's are open or if the O'CS pump is available for injection, close: a.MSIV's b.Main Steam Line Drains: c~MS-V-16 MS-V-19 RCIC Steam Isolation Valves: RCIC-V-8 RCIC-V-63 RCIC-V-76 C-FLD DURC NUMBCR 5.3.6 RCVISION NUMBCR AC NUMBCR 5.3.6-3.of 11 W~t7 RC (tent}
2.If any control rod is not inserted beyond position 06: 2.1 Terminate and prevent all injection into the RPV except f'rom boron injection systems and CRD until RPY pressure i below the Minimum Alternate RPV Flooding Pressure.Nunber of open SRV's Minimum Alternate RPV Flooding Pressure (psig)7 or more 6 5 4 2 185 215 265 330 445 675 Even if'ess than 2 SRVs can be opened, continue in this procedure.
If'hile executing the f'ollowing step, RPV water level can be determined and RPV flooding is not required, exit this procedure and enter: 1.PPM 5.3.7, Level/Power Control (Contingency) 2.PPM 5.1.2, RPV Pressure Control, (RPV/P)Step 12.and execute those procedures concurrently.
C-FLD PROCKOURK NUMBCR 5.3.6 WP 444 RI I4 4$)RCVISION NUMBKR PAOK NUMBCR 5.3.6-2 of ll CAUTION A rapid increase in injection into the RPV may induce a large power excursion and result in substantial core damage.2.2 Commence and slowly raise injection flow into the RPV with the following systems uhtil at least two SRV's are open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: a.CRO 1130-0 psig b.Condensate/Condensate Booster-----460-0 psig 1)Verify RFW-LIC-620 in MANUAL and RFW-FCV-10 closed.2)Open: RFW-V-117A RFW-V-1178 RFW-V-118 3)Close: RFW-V-112A RFW-'V-112B 4)Start't least one condensate pump and one condenstate booster pump.5)Slowly open RFW-FCV-10 while monitoring RPV pressure.6)If RFW-LIC-620 output exceeds 90K, verify RFW-FCV-15 is closed.7)Start another condensate/condensate booster pump.8)Jog RFW-V-109 open.CBOURK NUMBCR 5.3.6 RdVISION NUMBBR PAQB NUMBBR C-FLD 5.3.6-3 of ll WP.599 R I (9<9) 2.3 lf at least 2 SRV's are not open or RPV pressure cannot be increased above the Minimum Alternate RPV Flooding Pressure, commence and slowly raise injection i'low into the RPV with the following systems, until at least two SRVs ara open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: a~b.1130-0 psig 1)Align HPCS to take suction from the suppression pool.2)At H13-P625, block open contacts 1-2 oi'elay E22A-K3.3)Verify HPCS-V-4 is closed.4)Start HPCS-P-1.5)Open HPCS-V-23.
6)Open HPCS-V-4.7)Jog HPCS-V-23 closed while monitoring RPV pressure.-------360-0 psig C~Rl+Service Water 1)Use only ii'HR-P-28 is inoperable.
160-0 psig 2)Close RHR-V-428.
3)At H13-P623, block open contacts 9-10 oi'elay 822H-K 30.4)Verii'y SW-P-18 operating.
5)Open RHR-V-115 and RHR-V-116.
6)Jog open RHR-V-538 while monitoring RPV pressure.7)Close RHR-V-688.
d.Fire Water 90-0 psig 1)String fire hose from nearest outside hydrant to COND-P-2A.
2)Attach hose to adaptor at COND-P-2A suction.3)Open hydrant and adaptor shutoi'f valves.C-FLD PROCKDURK NUMBKR 5.3.6 WP 59$Rl (t&5)RKVt5ION NUMBKR 1 PACK NUMBKR 5.3.6-4 of ll
2.4 Maintain
at least 2 SRV's open and RPV pressure above the Minimum Alterate RPV Flooding Pressure by throttling injection.
Number oi'pen SRyss Minimum Alternate RPV Flooding Pressure (psig)7 or more 6 5 4 3 2 185 215 265 330-445 675 2.5 When: a.All control rods are inserted beyond position 06 or, b.The reactor is shutdown and no boron has been injected into the RPV, continue in this procedure.
URK NUMBER 5.3.6 WP 999 R I (9 99)REVISION NUMBER PAQK NUMBER 5.3.6-5 oi'l Ii'FV water level cannot be determined:
3.1 Commence
and increase injection into the RPV with the following systems while verifying:
a.At least 3 SRV's are open and, b.RPV pressure is not decreasing and, c.RPV pressure is at least 98 psig above suppression chamber pressure.d.HPCS e.CRD 1130-0 psig 1130-0 psig f.Condensate/Condensate Boosters 460-0 psig g.LPCS h.LPCI 360-0 psid 220-0 psid i.RHR Service Water-----.--160-0 psig 1)Use only if RHR-P-2B is inoperable 2)Verify, SW-P-1B operating 3)Open RHR-V-115 and RHR-V-116 4)Open RHR-V-42B I 5).Close RHR-V-68B j.SLC (test tank if OW-P-lA or OW-P-1B is operating) k.SLC (boron tank)3.2 Maintain at least 3 SRV's open and RPV pressure at least 98 psig above suppression chamber pressure by throttling i'njection.
PROCCDURC NUMSKR 5.3.6 WP.$55 Rl IS&5)RKVISION NUMSCR PAQK NUMBCR C-FLO 5.3.6-6 of'l 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:
a.HPCS b.CRD-1130-0 psig 1130-0 psig c.Condensate/Condensate Boosters 460-0 psig d.LPCS e.LPCI 360-0 psid 220-0 psid RHR Service Water-------160-0 psig 1)Use only if RHR-P-2B is inoperable 2)Verify SW-P-1B operating 3)Open RHR-V-115 and RHR-V-116 4)Open RHR-V-42B 5)Close RHR-V-68B g.Fire Water 90-0 psig 1)String fire hose from nearest outside hydrant to COND-P-2A.
2)Attach hose to adaptor at COND-P-2A suction.3)Open hydrant and adaptor shutoff valves.CCaURC NUMeCR 5.3.6 WP$99 R1 (9%3)RCVI5ION NUMSCR I aCC NUMeCR C-FLD 5.3.6-7 of ll h.ECCS Condensate Flush connections 40-0 psig 1)Install the removable pipe spool between the condensate supply system header and any one of the Yellowing ECCS injection subsystems
~hsvin~Sobs stem Tie Valves LPCS LPCI-A LPCI-8 LPCI-C COND-V26/LPCS-Y-25 COND-V-36/RHR-V-63A COND-V-35/RHR-V-638 COND-V-37/RHR-V-63C 2)When RPV pressure is less than 100 psig and decreasing, open the Condensate/ECCS valves.associated with the installed spool.i.ECCS Keep Full Pumps------30-0 psig 1)HPCS-P-2 2)LPCS-P-2 3)SLC (test tank if DW-P-1A or k.SLC (boron tank)PRQCKDURK NUMSKR 5.3.6 WP 555 Rl (SiOQ)RKVISION NUMSKR PACK NUMSKR C-Ftg5.3.6-8.of ll 5.If RPV water level cannot be determined:
5.1 Commence
backfilling RPV level instrumentation reference columns using the IhC Shop Sprague pump or hand pumps.Zndicarcr/Reccrder
~ancae Transmitter Location MS-LR-615 MR-LI-610 MS-LR-623A MS-LR-6238 MS-LI-604 LI-606A LI-6068 LI-606C Fuel Fuel Wide Wide Wide Narrow Narrow Narrow CAUTION LITS-N044A LITS-N0448 LITS-N026A LITS-N026O LITS-N026C dPT-N004A dPT-NO048 dPT-N004C H22-P 010 H22-P009 H22-P004 H22-P026 H22-P005 H22-P004 H22-P027 H22-P005 Reference columns for the following instruments are located in the drywell.General CAUTION 86 is applicable.
RFW-LR-608 MS-LI-605 Upset dPT-N017 Shutdown LT-N027 H22-P017 H22-P027 5.2 Continue injecting water into the RPV until water level.instrunentation is available.
5.3 If while executing the following steps, RPV water level can be determined, continue in this procedure at Step 6.5.4 Oetermine the RPV is filled by three or more of the following methods: a.RPV level indications upscale on fuel zone, wide range and narrow range channels.b.RPV skin temperature drop coincident to initiation of f'looding with sustained downward trend.c.SRV acoustic monitors on open SRVs indicate flow.d.SRV tailpipe temperature comparison indicates flow.e.Restart of'RC-P-lA or RRC-P-18 provides stable jet pump f'low indication.
PROCKDURK NUMSKR 5.3.6 WP 55$R'I (9 I5)RKVI5ION NUMSKR PAQK NUMSKR 5.3.6-9 of'l 5.5 If it can be determined that the RPV is filled or RPV pressure is at least 98 psig above suppression chamber pressure, terminate all injection into the RPV and reduc RPV water level Terminated Injection a.Open RPY head vents MS-V-l and MS-V-2.b.Confirm SRV's open.c.Open RHR-V-67 until approximately 6 additional inches of'tem have been exposed.d.Open RHR-V-8 and RHR-Y-9.e.Close RN-V-8, RHR-V-9, and Rf&>>V-67 when either level indication comes on scale or before exceeding the Maximum Core Uncoverv Time Limit.60 MAXIMUM CORE UNCOVERY TIME LIMIT r 50 I III 40 I, IC III 30 8 III IC CJ 20 x 10;10 1000 TIME AFTER REACTOR SHUTOOWN (MIN)5.6 If RPV water level indication is not restored within the Y termination of injection into the RPV, return to Step 3.PROCKDVRK NUMBER 5.3.6 WP$$~Rl (S~SS)REVISION NUMBER PACK IIUMBER C~D5.3.6-20 of ll 6.When suppression chamber pressure can be maintained below the Primary Containment Design Pressure, exit this procedure and enter: 1.PPM.5;1.1, RPV Level Control, (RPV/L)Step 6 and, 2.PPM 5.1.2, RPV Pressure Control, (RPV/P)Step 14 and execute those procedures concurrently.
C-FLD CKOURK NUMBKR RKVISION NUMBKR PAQK NUMBKR 5.3.6 WP.990 RI{9 43)
I uNCONTROLLEB COPY WASEGNGTON PUBLLC POWER SUPPLY SYSTEM PLANT PROCEDURES MANUAL V5P-2 PROCCDURC NUMSCR+5.3.7 Ol MC NAMC ROVCD DATC 06/13/85 5 EMERGENCY OCEDURES 5.3 EMERGENCY PROCEDURE CONTINGENCIES
+5.3.7 LEVEL/POWER CONTROL 1.If while executing the following steps, RPV flooding is required or RPV water level cannot be determined, control injection into the RPV to maintain reactor power above 8%but as low as practicable.
If reactor power cannot be determined or maintained above 8X, RPV flooding is required, enter contingent I PPM 5.3.6, RPV Flooding.I I C-PWR OURC NUMSCR 5.3.7 RKVISlON NUMSCR AC NUMBCR 5.3.7-1 of 8 WP 507 A2{'$42)
CAUTION Large reactor power oscillations may be observed while executing this step.2.If': a.Reactor power is above 5X or cannot be determined and, b.Suppression pool temperature is above 110oF and, c.Either an SRV is open or opens or drywell pressure is above 1.65 psig, Lower RPV water level by terminating and preventing all injection into the RPV except from boron injection systems and CRD until either: a.Reactor power drops below 5X or, b.RPV water level drops to-161 in.(TAF)or, c.All SRV's remain closed and drywell pressure remains below 1.65 psig.NOTE If'hile executing the f'ollowing steps, emergency RPV depressurization is re-quired, continue in.this procedure at Step 4.2.If'hile executing the f'allowing step:aO Reactor power is above 5X or cannot be determined and, b.RPV water level is above-161 in.(TAF)and, c~d.Suppression pool temperature is above 110oF and, Either an SRV is open or opens or drywell pressure is above 1.65 psig, return to Step 2.PROCKOURK NUMSKR 5.3.7 WP.594 R I (9i93)RKVI5ION NUMSKR PAGK NUMBKR C-PWR 5.3.7-2 of' CAUTION If HPCS SUCTION SWITCHOVER SUPPRESSION POOL HIGH or HFCS/RCIC SUCTION SWITCHOVER CST LEVEL LOW alarms occur, confirm automatic transfer of or manually transfer HPCS and RCIC suction from the condensate storage tank to the suppression pool.RCIC suction will not auto transfer on high suppression pool level.CAUTION Do not secure or place an ECCS in MANUAI mode unless by at least two independent indications:
1)misoperation in AUTO-MATIC mode is confirmed or 2)adequate core cooling is assured.If an ECCS is placed in MANUAL mode, it will not in-itiate autcmatically.
Make f requent checks of'he initiating or controlling parameter..
When manual operation is no longer required, restore the syst'm to AUTOMATIC/STANDBY mode ii'ossible.
CAUTION If a high drywell pressure ECCS initia-tion signal (1.65 psig)occurs or exists while depressurizing, prevent injection f'rom those LPCS and LPCI pumps not re-quired to assure adequate core cooling prior to reaching their maximum injec-tion pressures.
When the high drywell pressure ECCS initiation signal clears, restore LPCS and LPCI to AUTOMATIC/
STANDBY mode.C-PWR PROCCOURC NUMSCR 5.3.7 WP 444 RI (4&QI RCVISION NUMBCR PAQC NUMOCR 5.3.7-3 of 8 4.Maintain RPV water level at either: a.The level to which it was deliberately lowered in Step 2 or, b.Between+13.0 in.and+54.0 in.if'PV level was not deiiberately'owered with the following systems: a.CRD CAUTION 1130-0 psig Do not throttle the RCIC turbine be-low 1000 rpm.b.RCIC c.Condensate Booster Props 1130-60 psig 460-0 psig 1)Verify RFW-LIC-620 in MANUAL with OX output.2)Open RFW-V-117A, RFW-Y-117B and RFW-V-118.
3)Close RFW-V-112A and RFW-V-112B.
4)Start one each COND-P-1 and COND-P-2.5)Slowly open RFW-V-10 while monitoring RPV water level and power.4.1 If'PV water level cannot be maintained as required in Step 4, maintain RPV water level above-161 in.(TAF).4.2 If RPV water level cannot be maintained above-161 in.(TAF), emergency RPV depressurization is required;enter contingent PPM 5.3.2, Emergency RPV Depressurization and execute concurrently with this procedure through Step 4.6.C-PWR PROCKDURK NUMSKR 5.3.7 WP SPB Rl (SWQ)RKVISIQN NUMBKR PACK NUMSKR
4.3 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.'inimum Alternate RPV Number of open SRV's I Flooding Pressure (psig)7 or more 6 5 4 2 185 215 265 330 445 675 4A If'ess than 2 SRV's can be opened, continue in this procedure.
4.5 Comence
and~slowl increase injection into the RPV with the following systems to restore and maintain RPV water level above-161 in.(TAF).a~CRD 1130-0 psig.b.c~RCIC-1130-60 psig Condensate Booster Pumps 460-0 psig 1)Verify RFW-LIC-620 in MANUAL with OX output.2)Open RFW-V-117A, RFW-V-117B and RFW-V-118.
3)Close RFW-V-112A and RFW-V-112B.
4)Start at least one each COND-P-1 and COND-P-2.5)Slowly open RFW-V-10 while monitoring RPV level and power.C-FWR QCKQURK NUM SKR 5.3.7 WP.It5 Rt (5%5)RKVI5ION N VMSKR PAERK NUMSKR 5.3.7-5 of 8 CAUTION A rapid increase in injection inside the shroud may induce a large power excursion and result in substantial core damage.4.6 If RPV water level cannot be restored and maintained above-161 in.(TAF), ccnmenca and~slowl increase injection into the RPV with the f'ollowing systems to restore and maintain RPV water,level above-161 in.(TAF): as HPCS 1130-0 psig 1)Align HPCS.to take suction f'rom the suppression pool.2)At H13-P625, block open contacts 1-2 of E22A-K3.3)Verify HPCS-V-4 is closed.4)Start HPCS-P-l.5)Open HPCS-V-23.
6)Open HPCS-V-'4.
7)Mg closed HPCS-V-23 while monitoring RPV water level and power.b.LPCS c~RHR Service Water 360-0 psig 160-0 psig 1)Use only if RHR-P-28 is inoperable.
2)Verify SW-P-18 operating.
3)Block open contacs 9-10 of relay 822H-K30 at H13-P623 ii'HR interlocks have not cleared.4)Verify RHR-V-428 closed.5)Open RHR-V-115 and RHR-V-116.
6)Close RfR-V-688.
7)Jog open RHR-V-538 while monitoring RPV level and power.C-PWR PROCCDURC NUMSCR 5.3.7 WP.St%Rl I'$&l)RCVIGION NUMSCR PAOC NUMSCR 5.3.7-6 of 8 d.Fire Water 90-0 psig 1)String fire hose from nearest outside hydrant to COhG-P-2A.
2)Attach hose to adaptor at COND-P-2A suction.3)I, Open hydrant and adaptor shutoff valves.e.ECCS Condensatate Flush Connections 40-0 psig 1)Install the removable pipe spool between the Condensate Supply System header and any one of the I'allowing ECCS injection subsystems
~havin an inoperable punp:~Subs stem Tie Valves LPCS LPCI-A LPCI-8 LPCI-C COND-V-26/LPCS-V-25 COND-V-36/RHR-V-63A COND-V-35/RHR-V-638 COM3-V-37/Rf+-V-63C 2)When RPV pressure is less than 100 psig and decreasing open the tie valves associated with the installed pipe spool.f.ECCS Keep Full Systems------30-0 psig 1)HPCS-P-3 2)LPCS-P>>2 3)RfR-P-3 5.If'hile executing Step 6, reactor power coamences and continues to increase, return to Step 2.6.When 1230 lb.of boric acid and 1275 lb.of borax have been injected into the RPV or all control rods are inserted beyond position 06, restore and maintain RPV water level between+13.0 in.and+54.0 in.C-PWR PRQCKOURK NUMBKR 5.3.7 WPw$99 Rl (9%9)RKVISION NUMBKR PAQK NUMBKR 5.3.7-7 of 8 6.1 If RPV water level cannot be restored and maintained above+13.0 in., maintain RPV water level above-161 in.(TAF).6.2 If'PV water level cannot be maintained above-161 in.(TAF), emergency RPV depressurization is'equired, return to Step 4.2.If'lternate shutdown cooling is required, enter PPM 5.3.5, Alternate Shutdown Cooling.7.Proceed to Cold Shutdown in accordance with PPM 3.2.1, Normal Shutdown to Cold Shutdown.PRQCKDURK NUMBKR 5.3.7 REVISION NUMBKR PACK NUMBKR C-PWR5.3.7-8 of'WP SSI RI IS.Sl)