ML19351C994
| ML19351C994 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 10/02/1980 |
| From: | Parker W DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0694, RTR-NUREG-694 NUDOCS 8010080548 | |
| Download: ML19351C994 (74) | |
Text
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DUKE power COMPANY Powna Bun. nmo 422 SocTu Cannen StazzT, CKAa1.oTTz, N. C. asa4a wn.uu.' o. nan nen. .,n. October 2, 1980 Vect Pattictu? Ttttpuowt: Anta 7C4 57ca Peoouction 37 3-43e3 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation
, U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. B. J. Youngblood, Chief Licensing Projects 3 ranch No. 1 Re: McGuire Nuclear Station Docket Nos. 50-369 and 50-370
Dear Mr. Denton:
Attached are draft copies of the following McGuire emergency procedures for your review:
- 1) Secondary Line Rupture
- 2) Loss of'Feedwater These two emergency procedures in additt a to the three emergency procedures transmitted via my letter of September 16, 1980 complete the set of McGuire emergency procedures which require NRC review as specified in Item I.C.8 of NUREG-0694. These procedures have also been submitted to Westinghouse for their review as required by NUREG-0694 Item I.C.7. Satisfactory completion of both of these reviews is required prior to issuance-of a full power license. These procedures will remain in draft form until the results of both reviews have been transmitted to Duke Power Company.
The interim McGuire inadequate core cooling procedure is also attached. This procedure governs the use of the McGuire primary coolant saturation monitor and as such satisfies the fuel loading requirement for such a procedure, NUREG-0694 Item II.F.2.
Item I.C.1 of NUREG-0694 requires the analysis and development of procedural guidelines for inadequate core cooling situations. Mr. D. G. Eisenhut's letter of September 5,1980, which provided preliminary clarification of these requirements, stated that the analysis and guidelines should be submitted for NRC review by Jt' .an i, 1981. Subsequent to this submittal the NRC staff would review the analysis and guidelines and determine their acceptability by ;
July 1, 1981. Following NRC approval of the guidelines licensees would revise i their emergency procedures by December 31, 1981. 7
-$- )
THis DOCUMEllT C0tlTAltlS t (
8010080 P0OR QUAUTY PAGES
< ( .-
i Mr. Jarold R. Denton, Director October 2, 1980 Page Two The Westinghouse analysis of inadequate core cooling, WCAP 9753, WCAP 9754, and_WCAP 9744, has been submitted to the NRC for their review. These reports provide an analytical basis for subsequent Westinghouse development of guide-lines for the detection of and recovery from inadequate core cooling. These guidelines will be submitted for NRC review prior to January 1, 1981. Following NRC approval of these guidelines Duke will revise the McGuire inadequate core cooling procedure to assure consistency with the approved guidelines.
V y truly yours,
/
Q wl LJ . '
~
William O. Parker, Jr.
THH:scs Attachments l
l t
- 1 AP/1/A/
J
'2 .
t , DUKE POWER CCMPANY McGUIRE NUCLEAR STATION
- LOSS OF STEAM GENERATOR FEEDWATER 1.0 Symptoms 1.1 Main Feedwater Pump 1A and LB tripped (First Out).
1.2 Decreasing S/G 1evel and associated alarms.
1.3 S/G A, B, C, D Flo Mismatch to CF Flo Alert.
1.4 S/G A, B, C, D CF Flow < Stm. Flo alarm.
2.0 I= mediate Actions 2.1 Automatic 2.1.1 Reactor trip-turbine trip.
2.1.2 If 2/4 lo-lo level alarms in 1/4 S/G's or both CF pumps trips, CA pumps lA and 1B 172rt and feed S/G's.
2.1.3 If 2/4 lo-lo level in 2/4 S/G's, CA pump #1 starts and feeds S/G's.
2.2 Manual CAUTION: Inaccurate Pressurizer and S/G Level readings will occur during accident conditions involving breaks inside contain=ent. (This is caused by depressurization a::d/or reference leg heatup).
Refer to McGuire Data Book Tables through
. for correct conversions for actual level. Use backup instru=entation (i.e.: CA Flow, SM Pressure, NC Pressure and Wide Range Th, Tc).
2.2.1 Verify Reau;or Trip, if not tripped:
2.2.1.1 Manually trip reactor from Control Room.
2.2.1.2 If reactor trip has not yet occurred, i==ediately actuate Safety Injection and attemgt to manually insert control rods.
2.2.1.3 If reactor trip has not yet occurred, manually trip the M.G.
set breakers locally.
2.2.2 Verify Turbine Generator Trip, if not tripped:
2.2.2.1 Manually trip turbine from Control Room or locally at the turbine.
2.2.2.2 If turbine c-1p has not yet occurred, open the generator breakers, place the 2EH Control in =anual and close the Governor Valves in fast action.
2.2.2.3 If turbine trip has not yet occurred, stop and lockout the LH Pumps.
2.2.2.4 If turbine trip has not yet occurred, close the MSIVs.
- 2.2.3 Verify.CA flow from at least one train is being delivered to the S/G's. If not, manually operate pumps.
NOTE: DO NOT regulate CA flow until level indicates in the narrow r 11 ' range of > 0% (above U-tubes).
- , %s 2.2.4 Verify that heat is being removed from the reactor via the S/G's by noting the following:
2.2.4.1 Automatic steam dump to condenser is occurring.
2.2.4.2 NC Tave is decreasing towards programmed no-load temperature (557*F).
~ ~ "
NGTE: Atmospheric steam dump is blocked by a reactor trip.
Condenser dump by C-9 and/or P-12. If cooldown be-low 551*F is required the bypass interlocks must be used.
2.2.5 Ensure all required automatic actions occur.
3.0 Subsequent Actions CAUTION: Do not place systems in manual unless misoperation in automatic is apparent. If any system is placed in manual, make frequent checks for proper operation.
Initial /Date
/ 3.1 If any pressurizer PORV's open on high pressurizer pressure, ensure
. reseating at 2315 psig decreasing. If any pressurizer PORV does j not reseat, close its associated block valve.
/ 3.2 Annou:.ce occurence on plant paging system.
/ 3.3 Control CA Flow to all steam generators to obtain and maintain no-load water level 25 narrow range in each.
t NOTE: Monitor CA Condensate Storage Tank Level and Upper Surge Tank Lavel. CA suction will_ auto-swap to RN at 2.0 psig suction pressure.
/ 3.4 Place Steam Dump in " Pressure" mode and verify their operation to remove decay heat. If Steam Du=ps are not available, ensure operation of S/G FORV's and/or Steamline Safeties to remove de-cay heat. If any S/G PORV does not reseat below 1065 psig, close its associated isolation valve. If the PORV isolation valve cannot be closed or if any Steamline Safety fails open, r'efer to EP/1/A/-
5000/__ (Secondary Line Rupture) .
/ 3.5 If the CA pumps are not available and if the Main Feedwater Pumps cannot be restarted and if the Hoewell and Condensate bocster pu=ps are c?erating, depressuri:e the S/G's to 400 psig with the Steam Dumps and/or S/G FORV's and feed with the Hotwell and Condensate Booster Pumps.
. 3
. Initial /Date w
/ 3.6 In the event sufficient feedwater cannot be made available, refer
- to AP/1/A/ (Inadequate Core Cooling) for further actions.
/ 3.7 If 2 CBP's were running, trip one.
/ 3.8 Close or check closed the following valves to isolate feedwater to the S/G's:
ICF-26 (S/G LD FDW Cont. Isol.)
ICF-28 (S/G IC FDW Cont. Isol.)
1CF-30 (S/?- 13 FDW Cont. Isol.)
~ ~ ' ~ - " - ^ ^ - ~ ~ ~ ~ ~
1CF-35 (S/G LA FDW Cont. Isol.) -
1CF-137-A (S/G 1D FDW Cont. Isol. Bypass)
ICF-136-A (S/G IC FDW Cont. Isol. Bypass)
ICF-135-A (S/G 13 FDW Cont. Isol. Bypass) 1CF-136-A (S/G LA FDW Cont. Isol. Bypass) 1CF-129-B (S/G 1D CF to CA Nozzle Isol.)
ICF-128-B (S/G IC CF to CA Nozzle Isol.)
1CF-127-B (S/G 1B CF to CA Nozzle Isol.)
1CF-126-B (S/G LA CF to CA Nozzle Isol.)
1CF-150 (CF Tempering Flow to S/G 1A,13,1C, ID CA Nozzles)
/ 3.9 Determine cause for trip of CF pumps, CF valve isolation, valve
, malfunction, or other problems and take necessary corrective action.
/ 3.10 Reset feedwater isolation if it has occurred.
/ 3.11 Refer to EP/0/A/5000/31 (Notification of Unusual Events).
/ 3.12 If an ATWS Event has occurred or if cooldown is necessary, refer to OP/1/A/6100/02 (Controlling Procedure for Unit Shutdown) and take the Unit to cold shutdown.
/ 3.13 Refer to OP/1/A/6250/01 (Condensate and Feedwater System) for restart of Feedwater System.
I 1
1 1
. EP/1/A/5000/
P bi DUKE POWER COMPANY M r-
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. , k McGUIRE NUCLEAR STATION i / - ' h.'
- SECONDARY LINE RUPT M
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1.0 ' symptoms
{
F $.19bh- c'edine Pressure (one or all Steamlines) inment Humidity 1.3 Rapidly Changing NC System Tave 1.4 Steam Flow /Feedwater Flow Mismatch Alarm 1.5 High Containment Pressure Alarm.
1.6 Low S/G Water Level 1.7 High Containment Sump Level 2.0 Im=ediate Actions Refer to I==ediate Actions of EP/1/A/5000/__,(Immediate Actions and Diagnostics for a Safety Injection) if not already accomplished. l 3.0 Subsequent Actions Initial /Date
/ 3.1 All necessary I= mediate Actions of EP/1/A/5000/__ (I= mediate Actions and Diagnostics for a Safety Injection) have been per-formed.
. CAUTION: Inaccurate Pressurizer and S/G Leyel readings will occur during accident conditions involving breaks inside con-1 tainment. (This is caused by depressuri:ation and/or reference leg heatup). Refer to McGuire Data Book Tables l l
through for conversions for actual level. I Use backup instrumentation (i.e. : CA Flow, SM Pressure, NC Pressure ;rd Wide Range Th, Tc). l CAUTION: The diesels should not be operated at idle or minimum load for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the diesels are shut down, they should be prepared for restart.
CAUTICN: If the pressurizer Power Operator Relief Valves (PORV's) l open at any ti=e during this transient, verify that the l 1
valves reclose when RCS pressure drops below the FORV .
setpoint pressure. If any PCRV does not reclose, attempt l to isolate it using the appropriate backup isolation valve. If the PORV's do not reclose and cannot be isolated, go to EP/1/A/5000/__ (Loss of Reactor Coolant) .
/ 3.2 Stop all reactor coolant p":ss after ECCS pu=p operation has been verified and when the wide range reactor coolant pressure is at
=
- * ' . 93 Initial /Date
!buk
/ 3.2.1 G ose the Centrifugal Charging Pump miniflow isolation
- valves 1NV-151A (NV Pumps Recirculation) ano 1NV-150B (NV Pumps Recirculation) when the actual Rcactor Coolant System pressure drops to the calculated manual reactor coolant pump trip setpoint psig.
/ 3.2.2 Reopen the-Centrifugal Charging Pump miniflow isolation valves 1NV-151A (NV Pumps Recirculation) and 1NV-150B (NV Pumps Recirculation) should the wide range Reactor Coolant System pre'ssure subsequently rise to greater than 2000 psig.
/ 3.3 If component cooling water to the reactor coolant pumps is iso-lated on a containment pressure signal, all reactor coolant pumps shall be stopped within 5 minutes because of lose of motor bearing l cooling. l CAUTION: If the reactor coolant pu=ps are stopped, the seal in-1 jection flow should be maintained. 1
)
/ 3.4 Determine which steam generator (s) is affected by observing each j steamline pressure. A low steamline pressure compared to the other j loops denotes a faulted loop (s); terminate auxiliary feedwater to
. that depressurized or depressurizing steam generator (s).
NOTE: If all steam generators are depressurized or depressurizing the auxiliary feedwater flow must not be terminated to any steam generator until the faulted loop (s) is identified. I NOTE: If no loop has a low steamline pressure compared to the others and all steamlines have been isolated, determiae l l
if a break has occurred in the steamline, in the main feedline or in any piping system that connects with the secondary pressure boundary. If no indication of a break in the pressure boundary is found, go to Section 3.0 of
~
EP/1/A/5000/ _ (I= mediate Actions and Diagnostics for a Safety Injection) and re-evaluate the accident with par-ticular emphasis on the Loss of Reactor Coolant. If a leak from the secondary systems is found, continue to follow these instructions.
/ 3.4.1. If the water level in the non-faulted steam generator (s) is in the narrow range span, regulate the auxiliary feed-water flow to those steam generator (s) to maintain an in-dicated narrow range water level of =25%. If water level in-creases in an unexplained anner in one stea= generator, e
bV K
., )$.%qh Initial /Date d30 m ~3 go to EP/1/A/5000/__ (Steam Generator Tube Rupture.
. NOTE: Depress the Train "A" and Train "B" CA modulating valves resets in order to regulate flow to the steam generators.
/ 3.5 Monitor Refueling Water Storage Tank Level. If a low Refueling Water Storage Tank Level. (12'6"). is reached, refer to Section 4.0 to establish Cold Leg Recirculation.
/ 3.6 If Phase B containment isolation hts occurred and containment pressure is less than 3 psig, reset both trains of Phase B iso-lation and Train "A" and Train "B" Main Steam PORV resets if there is reasonable assurance that containment pressure will not again increase above 3 psig. Stop NS pumps LA and IB and close the following valves:
INS-32A (NS Pump 1A Disch. Containment Isol. Outside)
INS-29A (NS Pump 1A Disch. Containment Isc!. Outside)
INS-153 (NS Pump 13 Disch. Containment Isol. Outside)
LNS-12B (NS Pump 13 Disch. Containment Isol. Outside)
/ 3.7 Open:
1KC-338-B, (NC Pump Supply Header Pent. Isol. Outside) 1KC-424-B (NC Pump Return Header Pent. Inside Isol.)
LKC-425-A (NC Pump Return Header Pent. Outside Isol.)
1KC-230-A (Train LA to RB Non-Ess. Supply Hdr. Auto Isol.)
and 1KC-3-A (Reactor Bldg. Non-Ess. Return Auto Isol.)
and/or LKC-228-B (Train 13 to RB Non-Ess. Supply Hdr. Auto Isol.)
and 1KC-18-B (Reactor Bldg. Non-Ess. Return Auto Isol.)
/ 3.8 Open:
l 1RN-40-A (Non-Essential Header Supply 1A Isol.)
1RN-252-B (Non-Essential Header Supply to RB Pent. Outside Isol.)
1RN-253-A (Non-Essential Header Supply to RB Pent. Inside Isol.)
1RN-277-B (Non-Essential Return from RB Pent. Outsids Isol.)
1RN-276-A (Non-Essential Return from RB Pent. Insf ae Isol.) l
/ 3.9 Safety injection should be terminated IF,:
NOTE: The ccaditions given below for termination of safety injec-tion should be continuously monitored throughout this pro-cedure.
l l
l
. I
-4 Initicl/ Data *
/ 3.9.1 One vide range reactor coolant te=perature Tg as confirmed by one cota exit thermocouples, if available, is less than 350*F, AND Wide range reactor coolant pressure is greater than 700 psig and is stable or increasing AND Pressurizer water level is greater t'aan 20% of span and rising (heaters covered), AND The reactor coolant indicated subcooling is greater than
- F.
c.us fliary feedwater flow is isolated to all depressurized am generators and at least gpm is injected into the non-faulted steam generator (s) or indicated narrow range water level in at least one non-faulted steam gen-erator is greater than % level.
NOTE: If all wide range reactor coolant temperature indi-cators go above 350*F when attempting to satisfy the conditions of 3.9.1, initiate safety injection pu=p operation and continue operation until conditions of 3.9.2 or 3.9.3 (depending on containment indications) are satisfied.
NOTE: If all steam generators are depressuri:ed or depres-surizing, the safety injection flow must not be terminated until the faulted loop (s) is identified.
/ 3.9.1.1 Reset Safety Injection, D/G load Sequencers and Phase "A" Isolation. M
/ 3.9.2 If outside containment:
All vide range reactor coolant temperature TH "#" E#""U"#
than 350*F, AND Containment pressure, AND containment radiation, AND containment recirculation su=p levels cict not exhibit either abnor= ally high or increasing readings, AND Wide Range reactor coolant pressure is s. .e r than 2000 psig, and is stable or increasing, AND Pressurizer water level is greater than 20 percent of span, AND The reactor coolant indicated subcooling is greater than "F.
Auxiliary feedwater flow is isolated to all depressuri:ed steam generators and at least gpm is injected into
. 3 Initial / Deco the non-faulted steam generator (s) or indicated wide range water level in at least one non-faulted steam generator is above the top of the steam generator U-tubes (in the narrow range).
NOTE: If containment pressure, or containment radiation, or containment sump level exhibit either abnormally high or increasing readings when attempting to sat-isfy the conditions of 3.9.2, initiate safety in-jection pump operation and continue operation until the conditions of 3.9.3 are satisfied.
NOTE: If all steam generators are depressurized or depres-suring the safety injection flow must not be termi-nated until the faulted loops is identified. OR 3.9.2.1 Reset, Safety Injection, D/G Load Sequencers and Phase "A", Isolation.
/ 3.9.3 If inside containment:
All vide range reactor coolant temperature TH *
- E#** *#
than 350*F, Aht Containment pressure, OR containment radiatf.on, OR, con-tain=ent sump level exhibit either abnor= ally high or increasing readings, AND Wide range reactor coolant pressure is greater than 2000 psig, and is stable or increasing, AND Pressurizer water level is greater than 50% of span, AND The reactor coolant indicated subcooling is greater than
- F. I Auxiliary feedwater flow is isolated to all d pressuri:cd steam generators and at least gpm is injected in:o the non-faulted steam generator (s) or indicated carrow range water level in at least one non-faulted secas gen-erator is greater than % level.
NOTE: If all steam generators are depressurized or depres-suri:ing, the safety injection flow must not be ter-minated until the faulted loop (s) is identified.
/ 3.9.3.1 Reset Safety Injection, D/G Load Sequencers and Phase A Isolation.
/ 3.10 Stop any ECCS Pu=ps not needed for normal changing and reactor coolant pu=p seal injection flow.
,ge3*1' * ~ b ($ j Initial /Date RAM CAUTION: If wide range reactor coolant pressure decreases by 200
- pai or pressurizer water level decreases by 10 percent of span from che point of safety injection termination
' or the reactar coolant subcooling drops below *F, MANUALLY REINITIATE safety injection pump operation to maintain reactor coolant pressure and er=ssurizer level.
Go to Section 3.0 of EP/1/A/5000/__ (Immediate Actions and Diagnostics for a Safety Injection) to rediagnose the event.
Safety injection may be terminated after the restart when reactor coolant pressure is being controlled to the nominal value which existed when safety injection was initially terminated (T H1350*F) or to a value greater than or equal to 2000 psig (Tg >350*F) and when the re-actor coolant indicated subcooling is greater than
- F plus 15'F.
/ 3.11 If for any reason all reactor coolant pumps are tripped, ensure that core decay heat is being removed by natural circulation.
Refer to OP/0/A/6150/14 (Decay Heat Removal by natural circulation).
/- 3.12 Reset the control permissive for recirculation mode 1NI-184-3 and INI-185-A.
/ 3.13 Open: INV-150-B (Centrifugal Charging Pumps Recirc.)
1NV-151-A (Centrifugal Charging Pumps Recirc.)
/ 3.14 Throttle LNV-238 (Centrifugal Charging Pumps Disch. Control) as necessary to supply '8 gpm seal injection flow to each Reactor Coolant Pump.
/ 3.15 Close: 1NI-4-A (BIT Inlet Isolation)
INI-5-3 (BIT Inlet Isolation)
INI-9-A (3IT Discharge Isol.)
LNI-10-3 (BIT Discharge Isol.)
/ 3.16 Establish Instrument Air flow to contain=ent by opening:
NOTE: After opening each valve listed, allow the Instrument Air Header Pressure to stabilize before opening the next valve.
INV-129-B (Essential Supply from Tank "lA" Cont. Isol.)
INV-160-3 (Essential Supply frem Tank "13" Cont. Isol.)
INV-148-3 (Non-essential Upper Containment Supply Cont. Isol.)
1NV-150-3 (Non-essential Lower Contain=ent Supply Cont. Isol.)
INV-362-A (Instrument Air to Rx. 31dg. Annulus Isol.)
l
Initial / Data W
/ 3.17 Establish Component Cooling Water flow to the Auxiliary Building
- Non-essential header as follows:
Open the following valves:
1KC-1-A (Aux. Bldg. Non-ess. Return Auto Isol.)
1KC-2-B (Aux. Bldg. Non-ess. Return Auto Isol.)
Close the following valves:
1KC-56-A (ND HX 1A Auto Supply) 1KC-61-B (ND HX 13 Auto Supply)
As flow decreases, open:
1KC-50-A (Train LA to Aux. Bldg. Non-ess. Supply Edr. Auto Isol.)
1KC-53-B (Train 1B to Aux. Bldg. Non-ess. Supply Hdr. Auto Isol.)
/ 3.18 Establish Nuclear Service Water Flow to Auxiliary Building as follows:
Open:
1RN-42A (AB Non-Essential Supply Isol.)
1RN-63B (AB Non-Essential Return Isol.)
1RN-64A (AB Non-Essential Return Isol.)
/ 3.19 Align the Centrifugal Charging Pump to take a suction from the Volu=e Control Tank:
. Open: INV-141-A (Volume Control Tk. #1 Outlet Isolation)
INV-142-B (Volume Control Tk. #1 Outlet)
Close: INV-221-A (Centrifugal Charging Pu=p Suction from FW Syste=)
INV-222-B (Centrifugal Charging Pu=p Suction from FW Syste=)
/ 3.20 Establish Seal Water Return by opening!
INV-94-A (NC Pumps Seal Return Containment Isol. Inside)
INV-95-B (NC Pumpt Seal Return Contain=ent Isol. Cutside)
/ 3.21 Close IN/-241 (Regenerative HX #1 Tube Inlet Control)
/ 3.22 Open:
INV-244-A (Charging Line Containment Isol. Outside) 1NV-245-B (Charging Line Containment Isol. Outside)
/ 3.23 Establish the nor=al charging flow path by slowly throttling open 1NV-241 (Regenerative HX #1 Tube Inlet Control).
NOTE: As 1NV-241 is opened, adjust 1NV-238 as necessary to
=aintain Seal Injection Flow.
/ 3.24 Establish Letdown by opening in order as listed:
lVV-1-A (NC Letdown Isolation to Regenerative RX dl)
LNV-2-A (NC Letdown Isolation to Regenerative HX #1)
INV-7-B (Letdown Containment Isolation outside)
INV-459-A (High Pressure Letdown Centrol) NOTE: Open slowly.
?. 41" Initial /Date After letdown line is var =ed up, open NV-458-A (75 gpm Lerdown Orifice Outlet Containment Isol.) and/or NV-457-A (45 GPM Letdown Orifice Outlet Containment Isol.) and close INV-459-A (High Pressure Letdown Control).
/ 3.25 Verify 1NV-124 (Low Pressure Letdown Control) is modulating to maintain letdown' pressure at ~350 psig.
/ 3.26 Energize pressuriser heaters to maintain steam bubble.
/ 3.27 Verify that containment monitors lEMF-38 (Containment Particu-late-Low Range), lEMF-39 (Containment Gas-Low Ringe) and 1 EMF-40 (Containment Iodine-Low Range) are not in an alarm condition.
Reset the Containment Ventilation isolation signals.
/ 3.28 Notify Chemistry for sample of NC System Boron Concentration from the unaffected loop and verify shutdown margin per OP/0/A/6100/06 (Reactivity Balance Calculation).
/ 3.29 Monitor either the average temperature indication of core exit ther= occupies (if available) or all vide range reactor coolant temperatureHT t verify that NC temperature is at least 50*F ,
less than saturation temperature at NC indicated pressure.
If 50*F indicated subcooling is not present, then attempt to
. establish 50*F indicated subcooling by steam dump from the steam generators to the condenser or the at=osphere.
CAUTION: If steam dump is necessary, reduce the steam generator pressure to maintain a reactor coolant cooldown rate of no more than 50*F/Hr., consistent with plant makeup capability, until 50*F subcooling is established.
/ 3.30 Steam dump should be initiated in the following manner.
/ 3.30.1 Establish a flow path in at least one steamline in an in- l tact loop (if possible); g the main condenser is available ]
(C-9). Reset the main steam isolation and open MSIV l
bypass valves for unaffected S/G's and equalize pressure (
before opening main steam isolation valves. Open the l isolation valves for the unaffected steam generators.
Transfer the steam dump system to steam header pressure control. Set the steam header pressure control setpcint to the pressure in the intact steam generator (s) at the time safety injectica is ter=inated.
l l
i
. , w*
Initial /Date "
/ 3.30.2 IF_ all MSIV's are CLOSED an. nnot be reopened, the main condenser is not available, or the rupture is downstream of the steamline ie71ation valves, dump steam to the atmosphere from the intact loops using the steam generator power opercted relief valves.
See each steam generator power operated relief valve pressure control setpoint to the pressure in the intact steam generator (s) at the time safety injection is ter-minated. If 50*F indicated subcooling car'not be established i
or maintained, then MANUALLY REINITIATE SAFETY INJECTION.
Go to Section 3.0 of EP/1/A/5000/_ (Immediate Actions and Diagnostics for a Safety Injection) and re-evaluate the event.
/ 3.31 Perform a Reactivity Balance per OP/0/A/6100/06 (Reactivity Bal-ance Calculation) and verify shutdown margin equivalent to >l%_
AK/K at 200*F. If necessary, borate the NCS per OP/1/A/6150/09 (Boron Concentration Centrol).
/ 3.32 If stopped, start the NC Pump in the unaffected "A" or "B" Loop per OP/1/A/6150/02 (NC Pump Operation) for cooldown purposes.
/. 3.33 Begin cooldown and depressurization per OP/1/A/6100/02 (Controlling Procedure for Unit Shutdown), while keeping the affected S/G iso-lated.
/ 3.34 Refer to EP/0/A/5000/32 (Alert).
/ 3.35 If D/C is no longer required and has been runni..g >,1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, shutdown per OP/1/A/6350/02 (Diesel Generator).
/ 3.36 Realign the following for normal operation when desired:
NI per OP/1/A/6200/06 (Safety Inhetion System)
VC per OP/0/A/6450/ll (Control Room Air Conditioning and Ventilation';
VJ per OP/0/A/6450/14 (Computer Room Ventilation System)
BB per OP/1/A/6250/08 (Steam Generator Blowdown System) for un-affected generators only.
NV per OP/1/A/6200/01 (Chemical and Volume Control System)
PRT per OP/1/A/6200/01 (Chemical and Volume Control System)
NCDT.per OP/0/A/6500/01 (Liquid b*aste Recycle System)
KC per OP/1/A/6500/05 (Component Cooling 'Jacer System)
RN per CP/1/A/6400/06 (Nuclear Service 'Jacer System)
Contain=ent Ventilation per OP/1/A/6450/01 (Containment Ventilation)
KF per OP/1/A/6200/05 (Spent Fuel Cooling System)
NF pei OP/1/A/6200/lSA (Ice Condenser Refrigeration System) i
__.-.n
' i- *t .
- 2.L La 1 Initial / Data FW per OP/1/A/6200/14 (Refueling Water System)
VS to Contain=ent: Open IVS-12-3 (Station Air to Unit #1 Contain-ment Outside Isol.)
YM to Containment: Open lYM-ll5-3 (Containment Outside Isol.)
NM per OP/1/A/6200/ll (Nuclear Monitoring and Sampling System)
Start three control rod drive ventilation fans.
4.0 Cold Leg Recirculation
/ 4.1 If logic test on FWST level is in progress, notify I&E Department to place circuit back to normal.
/ 4.2 When the FWST level decreases to the low level alarm point (12'6")
but not earlier than 10 minutes af ter safety injection actuation, perform the following to establish containment sump, cold leg recirculation:
/ 4.2.1 Manually reset the Safety Injection signal and the Diesel Generator Load Sequencers and Phase A Isolation.
/ 4.2.2 Change Residual Heat Removal Pumps suction from the FWST to the Containment Recire. Sump:
NOTE: If manual swap of ND pumps suction is not accomplished prior to 8.0 ft. FWST Lvl., insure automatic swap
- occurs prior to reaching 7 ft. FWST Lvl.
/ 4.2.2.1 Open LNI-184 (Containment Sump Line 13 Isolation).
As it opens, verify the closing of LND-4 (NC Loop 3 to ND Pump 13 Containment Isol. Outside).
/ A.2.2.2 Open 1NI-lS5 (Containment Sump Line LA Isolation) .
As it opens, verify the closing of LND-19 (NC Loop 1C to ND Pump 1A Qontainment Isol. Outside).
NOTE: If FWST emergency to Level (0.9 f t.) is reached before change over to the recircu-lation sump is completed, secure all pumps taking suction en the FWST.
/ 4.2.3 Reinstate control power to 1FW-27 (FWST to ND Pump Isolation).
/ 4.2.4 Close:
1Fw-27 (FWST to ND Pump Isolation) 1ND-30 (ND HX 1A Outlet Crossover 31ock)
IND-15 (ND EX 13 Outlet Crossover Block)
. Initicl/D:ta wb
/ 4.2.5 Stop Contain=ent spray pu=ps lA and 13.
/ 4.2.6 Close INS-20 (NS Pump 1A Suction from RWST Block) .
/ 4.2.7 open 1NS-18 (NS Pump 1A Suction from Containment Sump Block).
/ 4.2.8 Open 1RN-134 (NS Heat Exchanger lA Supply Isolation).
/ 4.2.9 Start Containment Spray Pump 1A.
/ 4.2.10 Close INS-3 (NS Pump 13 Suction from RWST Block) .
/ 4.2.11 bpen 1NS-1 (NS Pump 13 Suction from Containment Sump Block).
/ 4.2.12 Open 1RN-235 (NS Heat Exchanger 1B Supply Isolation) .
~
/ 4.2.13 Start Containment Spray'~ Pump 13.
/ 4.2.14 Close:
INI-115 (Safety Inj. Pump 1A Miniflow Line Isol.)
INI-114 (Safety Inj. Pump 13 Miniflow Line Isol.)
/ 4.2.15 Reinstate control power to INI-147 (Safety Inj. Pumps Miniflow Edr. to RWST).
/ 4.2.16 Close 1NI-147 (Sfaety Inj. Pumps Miniflow Hdr. to RWST).
/ 4.2.17 Open 1NI-136 (ND HX 13 to Safety Inj. Pump 13) .
/ 4.2.18 Reinstate control power to 1NI-100 (RWST to Safety Inj.
Pumps).
/ 4.2.19 (Close 1NI-100 _(RWST to Safety Inj . Pumps) .
/ 4.2.20 Wait until the "FWST Lo-Lo Lv1" alarm (0.9') is received before proceeding to the next step.
/ 4.2.21 Open 1ND-58 (ND HX 1A Outlet to Centrifugal Charging Pumps lA and 1B Block).
/ 4.2.22 Open 1NI-332 and 1NI-333 (Safety Inj. Pump Suction Crossover from NV).
Open 1NI-334 (Safety Injection Pump Sucttion Crossover from NV Isol.)
/ 4.2.23 Close 1NV-221 and 1NV-222 (Centrifugal Charging Pu=ps Suction frc= N System).
/ 4.2.24 After one heur, if offsite power has not been interrupted, stop the Emergency Diesel Generators per OP/1/A/6350/02 (Diesel Generator).
/ 4.2.25 If a loss of offsite power occurs while in the Cold Leg Recirculation mode, refer to section 5.0 of this procedure.
/ 4.3 Notify Chemistry Department and HP Department to obtain ph sample of contain=en sump water.
fnitial/Date
/ 4.4 If contain=ent pressure increases to 13.0 psi following depletien
- of the ice in the ice condenser, align the Residual Heat Removal spray headers as follows:
/ 4.4.1 Verify that 1ND-30 (ND HX 1A Outlet Crossover Block) and 1ND-15 (ND HX 13 Outlet Crossover Block) are closed.
NOTE: Do not initiate ND System Spray until at least one hour after Safety Injection has been initiated.
/ 4.4.2 Reinstate power to the following valves:
1NI-173 (ND Edr. to NC Cold Leg Loops 1 and 2) '
1NI-178 (ND Edr. to NC Cold Leg Loops 3 and 4)
/ 4.4.3 Close 1NI-173 (ND Edr. to NC Cold Leg Loops 1 and 2)
/ 4.4.4 When 1NI-173 is fully closed, open 1NS-43 (ND Pump 1A Disch.
l to NS Nozzles Containment Isolation outside).
~
/ 4.4.5 Close 1NI-178 (ND Bdr. to NC Cold Leg Loops 3 and 4) .
/ 4.4.6 When 1NI-178 is fully closed, open INS-38 (ND Pump 1B Disch. to NS Nozzles Containment Isolation Outside).
/ 4.5 When containment pressure has decreased to an allowable level, the Residual Heat Removal Pumps discharge may be realigned to the Reactor i Coolant Sytem Cold Legs as follows:
/. 4.5.1 Close INS-43 (ND Pump 1A Disch. to NS Nozzles Containment l
Isolation Cutside).
/ 4.5.2 When INS-43 is fully closed, open 1NI-173 (ND Hdr. to NC Cold Leg Loops 1 and 2).
/ 4.5.3 Close 1N5-38 (ND Pump 13 Disch. to NS Nozzles Containment Isolation Outside).
/ 4.5.4 When INS-38 is fully closed, open 1NI-178 (ND Hdr. NC Cold Leg Loops 3 and 4).
NOTE: Cold Lag Recirculation Phase Monitor Light Config-uration. Group 2 and 4 completely lighted. Croups 1, 3, 5, 6, and 7 completely dark.
NOTE: Group 6 should be lighted during recirculation mode if Upper Head Injection has actuated and secured.
/ 4.6 Approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after the accident, realign the Safety Injection System for Hot Leg recirculation as follows:
/ 4.6.1 Reinstate power to the following valves:
1NI-173 (ND Edr. to NC Cold Leg Loops 1 and 2)
INI-178 (ND Edr. to NC Cold Leg Loops 3 and 4)
INI-183 (ND Edr. to NC Hot Legs Isolation) 1NI-lL (Safety Injection ?u=p 1A Hot Leg Injection Header Iso;
., %* _13_
g Initial /Date N INI-162 (Safety Injection Pu=ps Cold Leg Inj. Edr. Iso.) -
- INI-152 (Safety Inj. Pump 13 Hot Leg Inj. Hdr. Iso.)
/ 4.6.2 Close 1NI-173 (ND Edr. to NC Cold Leg Loop 1 and 2)
/ 4.6.3 open 1ND-30 (ND HX 1A Outlet Crossover Block)
/ 4.6.4 Open 1NI-183 (ND Hdr. to NC Hot Legs Isolation).
/ 4.6.5 Close 1NI-178 (ND Edr. to NC Cold Leg Loops 3 and 4)
/ 4.6.6 Open IND-15 (ND HI 13 Outlet Crossover Block)
/ 4.6.7 Stop Safety Injection Pump 1A.
~~
/ 4.6.8 Close 1NI-ll8 (Safety Inj. Pump 1A Cold Leg Inj. Line Iso.)
/ 4.6.9 Open 1NI-121 (Safety Inj . Pump 1A Hot Leg Inj . Header Iso-lation)
/ 4.6.10 Start Safety Injection Pump 1A and verify flow to the Reactor Coolant System through the Hot Leg Header.
/ 4.6.11 Stop Safety Injection Pump 13.
/ 4.6.12 Close:
1NI-162 (Safety Inj. Pumps Cold Leg Inj. Bdr. Isol.)
INI-150 (Safety Inj. Pump 13 Cold Leg Inj. Lines Isol.)
/ 4.6.13 Open 1NI-152.(Safety Inj. Pump 13 Hot Leg Inj. Header Isolation).
/ . 4.6.14 Start Safety Injection Ptmp 13 and verify flow to the Re-actor Coolant Syai.em through the Hot Leg Header. I NOTE: The Residual Heat Removal and Safety Injection pump I
are now aligned for Hot Leg recirculation.
NOTE: Monitor Light Configuration during Hot Leg Recirc-ulation. Groups 2, 4, 5, 6 compir te lighted. Groups 1, 3, 7 completely dark.
5.0 Recovery from Loss of Offsite Power While in Cold Leg Recirculation
/ 5.1 One minute after the loss of power occurred reset the Diesel Gen-erator Load Sequencers.
NOTE: Wait one minute before resetting to allow all loads to be sequenced on.
/ 5.2 Secure the following loads.
/ 5.2.1 Centrifugal Charging Pu=ps A and B.
/ 5.2.2 Pressurizer Backup Heaters.
/ 5.2.3 Baron Injection Tank Heaters.
1
- J ' . '
., . V.,f1 Initial /Date
/ 5.2.4 Boron Injection Recirculation Pumps A and 3 1
. / 5.2.5 Boric Acid Transfer Pumps
/ 5.2.6 Pipe Tunnel Booster Fans
/ 5.2.7 Control Rod Drive Vent Fans
/ 5.2.8 Lower containment Cooling Units
/ 5.2.9 Upper Containment Cooling Units
/ 5.2.10 Upper Containment Return Air Fans
/ 5.2.11 Incore Instrument Room Air Handling Units
/ 5.3 Restart the folic. ring loads in the sequence listed ('f they were operating prior to the loss of power).
NOTE: In order not to overload the Diesel Generato, start one load, then wait ~5 sec., check voltage, amperate and load on the Diesel Generator, then start the next load.
/ 5.3.1 Residual Heat Removal Pumps A and B.
/ 5.3.2 Safety Injection Pumps A and 3. l l
/ 5.3.3 Centrifugal Charging Pumps A and B. !
l
/ 5.3.4 Annulus Ventilation Fans A and B and verify proper operation per OP/1/A/6450/02 (Annulus Ventilation System).
. / 5.3.5 Annulus Ventiltion Preheaters A and B. l l
/. 5.3.6 Containment Air Return Fans A and 3. l
/ 5.3.7 Containment Spary Pu=ps A and 3.
/_ 5.3.8 Hydrogen Ski =aer Fans A and B.
/ 5.3.9 Start Spent Fuel Cooling Pump A or B if desired.
/ 5.4 Verify the proper operation of the following loads.
/ 5.4.1 Vital Battery Chargers EVCA, EVC3, EVCC, EVCD.
/ 5.4.2 Load Centers ELXA, ELXB, ELXC, ELXD.
/ 5.4.3 Power Panelboards EKA and EK3. l
/ 5.4.4 ND and NS Room Sump Pumps. l
/ 5.4.5 A/C System Switchgear Room Fans SGR-AHU-A, 3, C, and D.
/ 5.4.6 D/G A and 3 Auxiliaries.
/ 5.4.7 Blowers for the following DE Monitors. )
/ 5.4.7.1 DE-33 (Condenser Air Ejectors)
/ 5.4.7.2 DE-35, 36, and 37 (Unit Vent Particulate, Gas i and Iodine).
/ 5.4.7.3 DT-38, 39, and 40 (Contain=ent Particulate, Gas, and Iodine)
/ 5.4.7.4 DE-41 (Auxiliary 3u11 ding Ventilation) l i
'. Initicl/Dnto
/ 5.4.7.5 EMF-42 (Fuel Building Ventilation) i
/ 5.4.7.6 EMF-43A (Contrel Room Air Intake A)
/ 5.4.7.7 EdF-43B (Control Room Air Intake B)
/ 5.4.8 Auxiliary Building Filtered Exhaust Fans A and B.
./ 5.4.9 Comp. Cooling pumps Al, A2, B1 and B2.
/ 5.4.10 Nuclear Service Water Pumps A and B.
/ 5.4.11 Auxiliary Feedwater Pumps A and B.
/ 5.4.12 Control Area Air Conditioning System.
/ 5.4.13 Battery Room Exhaust Fans 1 and 2. -~~
/ 5.4.14 Ground Water Drainage System Pumps.
w
EP/1/A/5000/20 9
DUKE POWER COMPANY McGUIRE NUCLEAR STATION INADEQUATE CORE COOLING 1.0 Symptoms 1.1 Fluctuating NCP Amps.
1.2 NC Th (highest) temperature greater than Pzr. liquid space temperature.
1.3 "NCS Approaching Saturation Condition" alarm.
1.4 Th or Tc Wide Range, or Core Thermocouples indicate high temperature.
l.5 Reactor AT >60*F.
2.0 *Immediate Action -
2.1 Automatic 2.1.1 None 2.2 Manual CAUTION: Inaccurate Pressurizer and S/G Level readings will occur during accident conditions involving brea.s inside containment. (This is caused by depressurization and/cr reference leg heacup).
Refer to McGuire Data Book Curves _ ,
and curves for correct conversions for actual level. Use backup iustrumentation (i.e.: CA Flow, SM Pressure, NC Pressure and Wide Range Th, Tc).
2.2.1 Verify reactor is tripped, if not refer to Reactor Trip procedure (EP/1/A/5000/01).
2.2.2 Verify turbine is tripped, if not refer to Turbine Trip procedure (EP/1/A/5000/02).
2.2.3 Verify CA flow to the Steam Generators and levels are indicating '
in the narrow range.
2.2.4 Maintain NCS pressure above saturation for the hottest temperature in the NCS. Insure pressuvizer PORVs are closed.
2.2.5 Raise pressurizer level to greater than 50% and insure pressurizer 1
heaters are functioning. 1 2.2.6 Insure.both pressurizer spray valves are closed.
2.2.7 Verify that the Steam Generators are steaming to remove heat from NCS.
3.0 Subsecuent Action 3.1 Announce occurrence on paging system. 1 l
3.2 Refer to McGuire Data Book, Table 1.10 (Saturation Temperature vs. Pressure 1
I and determine degree of subcooling.
NOTE:
Tsat - Highest NC Temperature (Th, Tc or Ther=occuple reading) =
- F subcooled (for given pressure).
I
- _t - . _ _ - . , ._. m,wa, 3.3 Ifindicaticnscfinedsquntocaracoolingareprescnt, initista Snfaty
. Injacticn.
3.4 Refer to EP/1/A/5000/03 (Loss of Coolant) and OP/0/A/6150/04 (Decay Heat
! , Removal by Natural Circulation) to establish core cooling.
3.5 Refer to EP/0/A/5000/32 (Alert).
d w ee n# '
e i
e d
b i
e 4 #
- .t
= - . . . _ _ - - . . . .
EP/1/A/5000/ o DUE PCWER CCMPANY McGUIRE NUCLEAR STA!!ON IMMEDIATE ACTIONS AND DIAGNOSTICS FOR A SAFETY INJECTION 1.0 Symptoms 1.1 Low Pressurizer Pressure (1845 psig).
1.2 Low Pressurizar Level Ala m.
1.3 High Pressurizar Level Alarm.
1.4 High Containment Pressure Alarm.
1.5 High Containment Radiation (EMF 38, 39 or 40).
1.6 High Air Ejector Radiation (EMF 33).
1.7 High S/G Blowdown Radiation (EMF 34).
1.3 Steam Flow /Feedwa:ar Flow Mismatch Alarm.
1.9 Lacdown Isolation /?ressurizar Heaters Off Alarm.
1.10 Lcw-Low NC Sysces Tave (551 F).
1.11 High Containment Sump Level.
1.12 Low Steamline Pressure (one or all Steamlines).
1.13 Iow S/G Water Level.
1.14 Increasing S/G Water Level.
1.15 Rapidly Changing NC System Tave.
1.16 Increased Charging Flew.
1.17 High Steam Flow (one or all Steam 11nes).
1.18 High Containment Humidity.
1.19 High Conczinment Temperature.
1.20 Low Feedwater Pump Discharge Pressure.
1.21 Ice Condenser Doors Open. _
NOTE: The above symptoms are cypical of those which may arise while undergoing a Loss of Reactor Coolant, Loss of Secondary Coolant or Steam Generator Tube Rupture (one or nore sympccms may appear in any order).
2.0 Immediate .weton (Refer to Inclosure 1) 2.1 Auccmatic 2.1.1 Reactor Trip and Turbine Trip.
2.1. 2 Safecy Injection Actuation and Conta1= ment Phase "A" Isolation.
2.1.3 Vital bus voltages indicate that the busses are energi:ad and all intended loads are being powered.
2.1. 4 Teedwacar Isolation.
' l.3 CA ?u=ps s art and feed all steam generators.
1 l
.g.
l 2.1.6 NV, NI and ND Pumps start and the :nonitor lights indicate that the E/S Valves are in the proper safeguards position.
2.1.7 RN and KC Pumps start.
2.1.8 Containment Ventilation Isolation.
2.1.9 Containment Phase "3" Isolation and Containment Spray g Con-tainment Pressure is areater than 3.0 psig.
2.2 Manual 2.2.1 Ensure all required automatic actions occur.
2.2.2 Verify Reactor Trip, if not tripped:
2.2.2.1 M ually trip reactor from Control Room.
2.2.2.2 If reactor trip has not yet occurred, immediately actuate Safety Injection and attempt to manually insert control rods.
2.2.2.3 If reactor trip has not yet occurred, manually crip the M. G. set breakers locally.
2.2.3 Verify Turbine Generator Trip, if not tripped: 1 2.2.3.1 Mm==11y trip curbine from Control Room or locally at the turbine.
(
2.2.3.2 If turbine trip has not yet occurred, open the generator breakers, place the DER Control in manual j and close the Governor Valves in fast action.
. 2.2.3.3 If turbine trip has not yet occurred, stop and lock-out the LH Pumps.
2.2.3.4 If turbine trip has not yet occurred, close the MSIVs.
2.2.4 Verify Safety Injection flow from at least one train is being delivered to the NC System when the NC Pressure is below the shucoff head of the NV Pumps. If not, manually operate pumps.
2.2.5 Verify CA flow from at least one train is " ing delivered to the S/Gs. If not, manually operate pumps.
NOTE: DO NOT regulate CA flow until level indicates in the narrow range of > 0% (above "-cubes).
2.2.6 Verify that heat is being removed from the reactor via the S/Ge by noting the following:
2.2.6.1 Automatic steam dump to condenser is occurring.
2.2.6.2 NC Tave is decreasing c:varda programmed no-load temperature (337 7).
T NOTE: Atmospheric scesa dump is blocked by a Reactor Trip.
\,
Condenser dump is blocked by C-9 and/or F-12. If cooldown below $51*F Tave (P-12) is required the Sypass interlocks must be used.
3.0 Subsecuent Actions - Diagnostics (Refer to Enclosure 2).
CA!TIION: Inaccurate Pressuri:er and S/G Level readings will occur during accident conditions involving breaks inside containment. (This is caused by depressurization and/or reference leg heatup).
Refer to McGuire Data Book Tables through for correct conversations for actual level. Use backup instrumenta-tion (i.e.: CA Flow SM Pressure, NC Pressure and Wide Range Th. Tc).
Initial /Date
/ 3.1 If the NC pressure is low or decreasing in an uncontrolled manner, verify that:
321.1 All pressurizer spray line valves are closed and 3.1.2 All pressurizar PORVs are closed.
If not, manually close the valves from the Control Board. If the Pressurizar PCRV will not close, close its associated block valve.
/ 3.2 If the NC pressure is above the low pressure reactor trip set-point (1943 psig) AND is stable er, increasing, go to Step 3.3.
/ 3.3 Stop ALL NC Pumps after the NV pump operation has been veri-fied AND when the wide range NC pressure is at psig.
CAU~ICN: If IC to the NC pumps it isolated on Phase "3,"
ALL NC pumps should be stopped within 3 sinutes because of loss of motor-bearing cooling.
CAUTION: If the NC pumps are stopped, the seal injection flow should be maintained.
NOTE: Ihe conditions given above for stopping NC pumps should be continuously nonitored throughout this procedure.
/ *3.4 ,IJ_ EMF-33 (Air Ejector) or EMF-34 (S/G 3 lowdown Sa=ple) exhibit abnormally high readings AND containment pressure, contadnmant radiation (IMF 38, 39 or 40) and containment sump level exhibit normal readings, El go - I?/1/A/3000 (Steam Generscor Tube Fa11ura).
l
T 4 Initial /Date
'/ *3.5 IF_ the stan=1tne pressure is abnormally lower in one S/G than in the other S/Gs, TIH2: go to EP/1/A/5000/ (Secondary Line Rupture).
/ 3.6 p, containment pressure OR containment radiation (EMF 38, 39 or 40) OR containment sump levels exhibit either abnonnally high or increasing readings, THET go to EP/1/A/5000/
(Loss of Reactor Coolanc).
NOTE: For very small breaks inside containment, the contain-ment pressure increase will be very small and possibly not recognizable. For very small breaks the contain-ment sump level will increase very slowly and early in the transient may not indicate a level increase.
/ 3.7 IF,the F containment pressure, containment radiation (EMF 38, 39 or 40) AND containment sump level continue to exhibit stable readings in the normal pre-event range, THEN go to EP/1/A/5000/ (Secondary Line Rupcure).
- These stape may be interchanged.
/ 3.8 The Safety Injection Signal must be assumed to be non spurious
, until the following are exhibited:
/ 3.3.1 Normal readings for containment temperature, pressure, radiation (EMF 38, 39 or 40) and containment sump level AND
/ 3.8.2 Normal readings for Auxiliary Building Area Radt.acion Monitors and Auxiliary 3u11 ding 7entilation Radiation Monitor (EMF-41)
~
AND
/ 3.3.3 Normal readings for S/G 3 lowdown (EMF-34) and air ejector (EMF-33) radiation.
If .all of the symptoms 3.3.1, 3.3.2 and 3.3.3 are NOT =et, return to Step 3.3.
If all of the symptoms 3.3.1, 3.3.2 and 3.8.3 are set and when the following symptoms 3.3.4, 3.3.5, 3.3.6 and 3.3.7 l l
are exhibited:
/ 3.3.4 NC pressure > 2000 psig and increasing A'ID
/ 3.3.3 ?ressuri:er level > 25" level.
Initial /Date AND NOTE: Pressurizar level should trend with NC toeparature.
/ 3.8.6 The NC System indicated subcooling > 7 AND
/ 3.8.7 CA flow of at least gpa is injected into the S/Ga g indicate <'. narrow range level in at least one S/G > OT (above the U-tubes).
THEN
/ 3.8.8 Reset Safety Injection Phase "A" and the D/C load sequencer and stop the NI, ND and NV Pumps act required for nor:nal charging and NC pump seal injec-tion flow.
CAUTION: Automatic reinitiation of Safety Injection will not occur since the reactor trip breakers are not reset.
CAUTION: Subsequent to this Step, should loss of offsite power occur, :nanual Safety Injec-
, cion will be required to load the E/S equipment onto the D/G busses.
/ 3.9 Reset the Train "A" and Train "3" Modulating Valve Resets (Located on RN Panel).
/ 3.10 Reset the control permissive for recirculation =mde of 1NI-1843 and 1NI-185A.
/ 3.11 Open: INV-150B (NV Pumps Recirculation).
~
INV-151A (NV Pumps Racirculation).
/ 3.12 Throttle 1NV-238 (Charging Line Flow Control) as necessary to supply
- 8 3pm seal injectica flow and :naintain pressurizer level.
/ 3.13 Close: INI-4A (3. I. T. Inlet Isol. )
INI-5B (3. I. T. Inlet Isol. )
INI-9A (3. !. T. Disch. Isol. ) ,
1NI-103 (3. I. T. Disch. Isol. )
CAUTION: g NC pressure drops below 1345 psig g if pressurizer level drops below 10" g the NC subcooling drops below 7, MANUALI.? RE'NITIA*E SAr:..? IL*ECT!CN.
CAUTION: If the NV, NI and ND Ptamps are restarted once
, after termination, the NV pumps cannot be so-cured until the NC Pressure > 2200 psi or NC subcooling > F (15 F higher than 2
temperature for initial reset of safety injec-tion).
Initial /Dece
/ 3.14 Roset the CA Train "A" and Train "3" modulating valve resets to regulate flow to the S/Gs.
Control flow to maintain 25: level.
/ 3.15 Establish VI to the containment by opening:
NOTE: After opening each valve listed, allow the VI header pressure to stabilize before opening the next valve.
1VI-129B (A ESS Header Cont. Isol. OTSD).
171-160B (3 ESS Header Cont. Isol. OTSD).
- 171-148B (UPP Cont. Non ESS Edr. C/I OTSD).
LVI-1503 (L*4R Cont. Non ESS Edr. C/I OTSD).
LVI-362A (VI TO Annulus Vent Cont. Isol. ) .
/ 3.16 Notify Chemistry for sample of NC System 3eron Concentration and verify Shutdown Margin per I OP/0/A/6100/06 (Reactivity 3alance Calculation).
/ 3.17 Establish KC flow to the Auxiliary Su11 ding Non-Essential header As fallows:
Open the following valves:
j 1KC-1A (Trn. LA to A3 Non E s Rec. Isol.)
1KC-23 (Trn.13 to A3 Non _Ess Rec. Isol. )
Close the following valves:
1KC-56A (KC TO A ND HI)
IIC-813 (KC TO 3 ND HI)
As flow decreases, open:
1KC-50A (Trn 1A to A3 Non Ess Sup Isol.)
1KC-53B (Trn 13 to A3 Non ass Sup Isol.)
/ 3.18 _ Align the Centrifugal Charging Pump to take'A succion from the VCT:
Open: INV-141A (VC* Outlet Isolation)
INF-1423 (7C* Outlet Isolation) .
Close: INV-221A (NV ? umps Suct. 7:cm P4ST) 157-2023 (NV ? umps Suct. 7:tm T4ST)
. , =1I
- ,: . 7 i;'fd Initial / Deca
/ 3.19 Establish Seal Water Return by opening:
INV-94A (NC Pumps seal Ret. C/I !.nside) 137-95B (NC Pumps Seal Ret. C/ OTSD). ;
/ 3.20 Establish Nor:nal Charging as follows:
Close INV-241 (Regen. EI Tube Side Init CNTRL) i Open LNV-244A (Charging Line Cont. Isol. OTSD)
Open 137-2453 (Charging Line Cone. Isol. OTSD)
Slowly throttle open INV-241, as it is opened adjust 157-238 as necessary to maintain seal injection flow.
/ 3.21 Establish Letdown by opening:
INV-LA (NC L/D Isol. to Regen. HI)
INV-2A (NC L/D Isol. to Regen. HI)
INV-73 (Letdown Cont. Isol. Cutside)
Slowly throttle open INV-459A 9A L/D Orif. OTLT Cont. Isol) to warn the letdown line, after the letdown line is warmed open INV-458A (3 L/D Orif.
OTLT Cont. Isol) and/or INV-457A (C L/D orif. OTLT Cont. Isol.).
/. 3.22 Verify 1NV-124 (Letdown Press Control) is modulating ,
to maintain letdown pressure at 350 psig.
/ 3.23 Energi:e the pressurizer heaters to =aintain a steam bubble and pressurizar pressure.
/ 3.24 E after securing safety injection and transferring to normal pressurizer pressure and level control, the NC pressure does not drop below 1345 psig AND the pressurizar level remains above 10 AND the indicated NC subcooling > ?, THEN proceed to the following steps. If not, MANUALLY REINIT* ATE SAFE *'? I'UECTION and radiagnose plant conditions.
/ 3.25 Istablish RN flow to A * *fary 3u11 ding as fo11cvs:
Open: 1RN-42A (AS Non Ess Supply Isol) Coord. A-5 1RN-633 (A3 Non Ess Return Isol) Coord. -5 1RN-64A (A3 Non Ess Return Isol) Coord. C-5 13N-279B (A3 7ent Sys. Return : sol) Coord. M-5 1RN-199A (A3 Vent Sys. Return : sol) Coord. ?-5.
l 1
Y kf ~, Initial /Date
/ 3.25 Stop the R7 Ptssps.
/ 3.27 Perform a Reactivity Salance per CP/0/A/6100/06 (Reactivicf 3alance Calculacion) and verify Shut-down Margin equivalent to > l' 1K/K at 200 F. If necessary, borate the NC Syster per OP/1/A/6150/09 (Boron Concentracion Control).
/ 3.23 Return the following ventilacion systems to nor:nal par CP/1/A/6450/01 (Containment Ventilacion):
Containment Lower 7entilation Control Rod Drive 7encilation Incore Instrument Ventilation Containment Upper Ventilacion
/ 3.29 Secure the Diesel Generators per CP/1/A/6350/02 (Diesel Generators).
CAUTION: Do not allow the D/Gs to idle for :more than one hour.
/ 3.30 If desired, the P/D Charging Pump may be placed in operacion per OP/1/A/6200/01 (Chemical and Volume Control System).
/ 3.31 Realign RN as follows:
Open: 1RN-10A (Train 13 L:.I Supply) Coord. F-4 1RN-113 (Train 13 Il.I Supply) Coord. J-l Close: 1RN-95 (Train 13 SNSWP Supply) Coord. I-l Open: 1RN-283A (Train 13 Disch. to RC) Coord. 3-2 1RN-2843 (Train 13_D13ch. to RC) Coord. K-2 Close: 1RN-1523 (Train 13 Disch. SNSWP) Coord. I-2 Open: IRN-413 (Train 13 :o Non Ess Edr. Isol.)
Coord. I-4 1RN-43A (Train 13 :o Non Iss 3dr. Isol.)
Coord. F-2
/ 3.32 Realign IC as follows:
Open: 1KC-320A (NCDT HI Sup 3dr. Outside ! sol.)
1KC-3323 (NCDT HI Rec. 3dr. Inside Isol. )
1KC-333A (NCDT HI Re:. Edr. Outside : sol.)
1KC-4293 (R:c 31dg. Drain Edr. :sside : sol.)
1KC-430A (R:s 31dg. Drain Edr. Cucside Isol.)
l i
l
t l Initial /Date
'/ 3.33 Secure or.e train of IC per CP/1/A/6400/05 (Component Cooling 'Jacer Operat19n) vs. a desired.
/ 3.34 Realign NF as follows:
Open: INF-22SA (R3 Glycol Supply C/I OTSD) 1NF-2333 (R3 Glycol Return C/I USD)
INF-234A (R3 Glycol Return C/I OTSD)
/ 3.35 Realign the PRT as follows:
Open. INC-533 (N 2 c PRI Cont. Isol. OTSD)
INC-54A (N2 to PRT Cont. Isol. USD)
INC-56B (?RT Spray Cont. Isol. USD)
/ 3.36 Realign the NCDT as follows:
Open: Iki-13 (NCDT Pumps Disch. OTSD Isol.)
l'4L-7A (NCDT Pumpe Disch. INSD Isol.)
1%1-39A (NCDT 7ent Inside Isol.)
Iki-413 (NCDT Vent Cutside Isol.)
/ 3.37 Establish S/G Blowdown per OP/1/A/6250/08 (Steam Generator 31owdown System).
/ 3.38 Railisu the 3IT as follows:
Open: 1NI-23A (3IT Recire. Auto Isol.) i l
1NI-243 (3IT Recire. Auto '. sol.)
INI-41A (3IT Recire. Pmp Dis Auto 31k).
/ 3.39 Restart the BIT Racirc. Pumps. Energize the 3IT and BIT Surge Tank heaters.
/ 3.40 Initiate steps to return the BIT boron concentration to normal per C?/0/3/3400/13 (3oric Acid Addition to 3cron Injection). ~
/ 3.41 Rar.lign the Contai..sent
~
Floor and Equipment Sumps LA and 13 and the incott Instrument Sump as follows:
Open: 1%1 -641. (R3 Setp Pump Disch. INSD Isol.) l 1%1-653 (R3 Sump Pump Disch. OTSD Isol.)
/ 3.42 Realign the T4Si as follows: l Open: 174-33A (74ST to Recire. Pumps) 174-49B (T4ST to Racirt. Pumps)
/ 3.43 If necessary, refill the 74ST per CP/1/A/6 00/14 (Refuling ~4atar System).
/ 3.a4 Return K7 to normal operation per 0?/1/A/6 00/05 (Spent Fuel Cooling System).
l
h' Initial /Date
/ 3.45 Return VC/TC to sormal operation per OP/0/A/6450/11 (Control Area Ventilation / Chilled 'Jacer System).
/ 3.46 Return 7A to normal operation per CP/0/A/5450/03 (aim itary Building 7ent11ation System).
/ 3.47 Return Computer Roca Ventilation System to nor:nal operation per CP/0/3/6450/14.
/ 3.48 Reset to Auto VQ-6A and VQ-53.
/ 3.49 Roset Coneminment 7ent114 tion Isolation.
/ 3.50 Realign Primary Sampling System per CP/1/A/6200/11.
/ 3.51 Open iTM-115A (Containment Outside Isolation).
/ 3.52 Maintain a Hot Standby Condition and refer to Tach-nical Specifications to determine if further actions
- sust be taken.
_ / 3.53 Refer to EP/1/A/5000/ (Notification of Unusual Event).
I 1
I 1
J 1
l
c,
\ Enclonura 1 EP/1/A/5000/
UA3 AN AUTOMATIC EVALUATE NEED FOR REACTOR OR NO IF NO TRI? OCCURRED 7 TRIP -
~
RE* URN TO NOPJd.AL OPERATION
.fES YES Y v 7ERITI c MANUALLY IE TIATE REACTOR REACIOR TRIP TRI?
9 E7ALUATE NEED lHASACTCMATIC SI INITIATION NO FOR MANUAL F NO O
CCCURRED? SI INITIATICN l
9 _
YES I? TE q GO TO 4 -
.O s l i
b INIIIATZ l SAFEGUARDS SEQUENCE 1 Y
GO TO INCLOSURE 2 l
s l
3 .
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[ s races ENCLGEL*RE 1 V 2aGRMAL 7: ANT AND E:I-y VI2CaeENTAI. AND 2ACI*
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s./ IS RC3 *20C0 PSI (AND 3- ,
MANUALLY TRIP AL*j, .g IS EC AVAII.ABLE INC3EAIDIG AND P*A WATER
_ l nCr s m ace's :.Evt:.
- Pacc w .m x zAD b WATER LE7ZL AND INDICATED i T3s 203COCLDIG m3LANT 3PECIFICI l l
- O 'T AND ATW FLCW M NCN=
'h ?ACLTID 3/34 :R JOT?!O*!:rf NZ i 30 M LP/1/ A/ = NO CONTAIIDE.YT DCICA*- lAIIA s/21 5"IYII* N AI 'Z'A3I 3C00/ 3TTAM T ON "7m"M AND itION M OONCENSER AIA SJTC*CR TES
- DIERAT'J72 **,"SE /
' RADIAT:CN (EMF.33) :R TAI Aip2 V 3;;24 3G 3MWCCWW AACI- l AT CM (EMT-34) j )
lTERMINATI3I l
2 1 S/ sr Z TC 17/1/ Ar * :3 STEAM 78133CRE MWE3 gg i p gg .d 5000/ :453 cr *:8 ONE STIAM INERATCR ,845
. 75 .. ..R 72R WATER v'3 *HAN *N CTHERS7 YIS 3 EON h Y OOCT. ANTE ,J/I,,3ELOW 10% F 4PA:.-
P A INOICATE3 303COC*.:.% .
<ess **
NC sr 30 ASNCRMAL OR :::CREA3- ,
ING INOICAT::Ns IX:3T
'" ~ TCA: CONTA NMENT PRES = CONTRCL 01 TLOW *RANS-
' 83 , YT3 3;RE OR CON *AI:3'I!r TER TC NCRMAT., PZR 2PI3-l
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- 4**
- AACIATI;W fEMF=39. 39. SURE AND !Z7EL CONTML i or 4C) OR 00NTAI::MDr? ~
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MANUA* .7 I3ITIATI JAF3*T :::JEC**0N AE"':22:
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EP/1/A/5000/- 3/
W. DUKE PCWER COMPANY McGUIRE NUCLEAR STATICN LOSS OF REACTOR COOLANT 1.0 Symptoms 1.1 Rapid decrease in pressurizer pressure and level.
1.2 " Ice Condenser Doors Open" alarm.
1.3 Containment sump level increase.
1.4 Cone =dmaant camperature increase.
1.5 Containment pressure increase.
1.6 Containment humidity increase.
1.7 " EMF-38 Containment di Part Rad" alarm 1.8 "1!MF-39 Containment Hi Gas Rad" alarm 1.9 " EMF-40 Containment E1 Iod Rad" alarm 2.0 Immediate Actions Refer to := mediate Ac:1ons of I?/1/A/5000/_ (Im:nediate Actions and Diagnostics for a Safety Injectica) if not already accomplished.
3.0 Subsecuent Actices Initial /Date
/ 3.1 All necessary 1::nediate actions of EP/1/A/50CO/_ ( ==ediate Ac ions and Diagnostics for a Safety Injection) have been performed.
CAUTICN: Inaccurate Pressurizar and S/G Level readings vill cc ur during accident condi: ions involving breaks inside con-tainment. (This is caused by depressuri:a: ion and/or reference leg heatup). Refer to McGuire Data 3cok Tables through for correct conversions for actual level. Use backup instrgentation (i.e.: CA Flow, SM Pressure, NC Pressure and 'Jide Range Th. Tc) .
CAUTICN: Mcnitor FWST level closely. If 7WST level decreases rapi.". -
such t Mc the FWST low level alarm appears 'm' ent go to Step :.2.1.
NOTE: Verify that :he Pos: Accident Moni:oring (?AM) ins:: :=ents are opera:ing and recording these include: '4/R NC Presaura and temperature, SM pressure S/4" vater level, c:ntainment pressure, FWST level. *!pper Surge Tank level, Aux. Feedvater CST, and ?ressuri:e: level. I 1
CAUT:CN: The diasels shculd not be operated a: idle or -' '~u:s l load for note :han i heur. Of :he diesels are shut :own.
- hey should be prepared for restart.
Initial /Date ~ t i
/ 3.2 As the FWST level decraases due to safety injection flow, check '
l' that the contaiment sump level is increasing. If the sump level is not increasing re-evaluation of the symptoms in EP/1/A/5000/_,
(I:mandiate Actions and Diagnostics for a Safety Injection) must be done.
/ 3.3 Reset CA Modulating valves and control CA flow to che S/G's to maintain narrow range level. If narrow range level increams in an unexplained manner in one S/G, then go to IP/1/A/5000/_ (Steam Generator Tube Eupture) . l l
NOTE: Monitor CA Condensate Storage Tank level and Upper Surge !
Tank Level. CA suction will auto swap to RN at 2.0 psig f i
suction pressure.
/ 3.4 7erify all pressurizer PORV's are closed. Verify open status and power status to all PROV block valves.
CAUTION: If the pressurirer PCRV's open at any time during this transient, verify that the valves reclose when the pres-surizer pressure drops below- 2315 psig. If any PCR7 f ails l l
to close, close its associated block valve.
/ 3.5 Verify all ECCS components have assumed their safeguards status.
Manually align any that did not.
/ 3.5.1 During Upper Head Injections Groups 3 and 4 completely lighted, Groups 1, 2, 5, 5, and 7 completely dark.
/ 3.5.2 After Upper Head Injection Groups 3, 4, 5, and 6 completely lighted, Groups 1, 2, 5, and 7 completely dark.
/ 3.5.3 If either train of the 3CP ES7 Components nonitor lights in Groups 1 and 4 are our of sequence with the other lights in their respective group, the CAC must be interrogated to obtain a printout of misa11gned 30P ES7 Components.
/ 3.5.4 If the CAC is inoperable, perform 30P ES7 Components align-sents checklist, Enclosure .
/ 3.5.5 Perform the Post Accident Checklist, Enclosure .
NOTE: If the Phase "A" Cont 2f"mant Isolation Monitor lights arc also out of sequence, MANUAL *.T O!!!'A*E ?HASE A ISCLATICN.
/ 3.6 3afety Injection can be ter=inated if:
NC""!. : The conditions given below for car =inating 34facy Infecti:n should be continuously senicoted thr:ughout this procedure.
s aT s. 3-A .T Inicial/ Data t.h..-
3.6.1 NC pressure is greater than 2000 psig and increasing AND
/
/ 3.6.2 Pressurizer level is greater than 50% AND
/ 3.6.3 The NC indicated subcooling > 'T AND 1 _/ 3.6.4 CA flow is isolated to all depressurized S/G's and at
' east gym is injected into the non-faulted S/G's o_r, indicated narrow range level in at least one S/g of
> . Then:
/ 3.6.5 Raset Safety Injection Phase "A" and the D/G load sequencer and the NI, ND and NV pumps not required for normal charging and NC pump seal injection flow.
CAUTION: Automatic reinitiation of safety injection will 1
- not occur since the reactor trip breakars are not reset.
CAUTION: Subsequent to this step should loss of offsite power occur nanual safety injection will be re-quired to load the E/S equipment onto the D/G busses.
- / 3.7 Open
- INV-150B (NV Pumps Racirculation) 1NV-151A (NV Pumpa Recirculation)
/. 3.3 Throcele 1NV-238 (Charging Line Flow Control) as necessary to supply ~8 gpa seal injection flov and pressurizar level.
/ 3.9 Close: 1NI-4A (3IT Inlet Isol.)
131-53 (SIT Inlet Isol.)
1NI-9A (3IT Disch. Isol.)
INI-10B (SIT Disch. Isol.)
CAUTICN: If NC pressure drops below 1345 psig g if pressuri:er level drops below 10 g l ha NC subcooling drops below
'7, MANUALLY RE!'i!TIATE SAFETY INJECT!CN to estab-lish NC pressure and pressurizer level. Go to Step 3.1 in I?/1/A/5000/ _ (!madiate Actions and Diagnostics for a Safety Injection).
CAUTICN: If safecr injection is reinitiated after termination, the NV pumpa eannot be secured until the NC pressure >2 00 psig or 2 subcooling > '? (15'? higher than tem-parature for initial reset of safety injection).
/ 3.10 Establish 7! to che conta1= ment by opening:
NOTE: Af tar openir.g each valve listad, allow the VI header pres-sure to stabili:e before opuning the next valve.
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/ 3.11 2a:.si'.Ja I: !!aw c2 h.e w '.t -,y. mth- Yoe.r,6+4nt:.al usader -
As "slL:va .
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iC-IA (!=. lA :s A3 dest-7.se Sec. Imol.) i 1E-23 0:3.13 ;a M &aRi;a lar. Isol.) '
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c.:sa ha fan-- val:ma: . . .
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'E .36A (= to a 73 E 12-413 C:: :n 3 3D E.. .
.As *20w 1scr3ases, opos's..
1E-?CA (Tm. LA ca A3 1onH?ss' Sap. Iual.)12-523 (Tm.1.3 cm G 9to a.as Sep. !:d..) .
+ . .. -
/ 1.1: AM.;n the Cancrif. sal c:wstas Pomp c:a :also a anc-'m fr:a chs 7CT: '
cyan: '37-141a ("7C:*. Cariat- i=1-8 M 137-1423 t.CT Ost.*.at. Iaal.) .
I cisea: *TT-221A CRT Nase. .%ut. Fraa .'1EST) I 1.".7 '.223 Cr7 Piampe Sect Tr::ss ."*JST)
/ 3.1.3 f.s abl.ish smal ascar return hy cyanins; 137-74 C;c hans seal lat,. c/I Instae) 137-953 C5c huge seal lec, c/I CT:;D) 7
/
3.1x Istablish nor:sai starztes as falicus: .
- - c Clase 137-21 (2mgn E hae side ' sic. Catz1.)- [.
C;nn 137-I'44 ( Tarti.:t !.isa C.:as. Isol. 0"lllDi- '
Geen '.37-333 ('.".'*ars:g 'h Oat:. Iscl. CI:lD) '
Ilowly :::c la ven 137-141. as 1:.La apened adh.ac. 137- :3 7-as secassa:7 :o -=h" raal 1:2sc=.:an !!aur ._
/ 3.15 12tahl.125 laca.,.rn ';y = pani g: '
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';1 137-1.1 CfC L,'.) Isol. :s 14 ten. 3'I) l
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Initial /Date '
/ 3.16 Verify 1NV-124 (Letdown Press Control) is sodulating to main-tain letdown pressure at ~350 psig.
/ 3.17 Energize the pressurizar heaters to maintain a steam bubble and pressurizar pressure.
/ 3.18 After level in the non-faulted S/G's has been restored in the narrow range, regulate flow to the non-faulted S/G's to main-tain and indicated narrow range level.
NOTE: Monitor CA Condensate Storage Tank Level and Upper Surge i
Tank Level. CA suction vill auto sway to RN at 2.0 psig i l
suction pressure. !
/ 3.19 Monitor the core exic chee accupies (OAC and/or Incore Panel) or !
wide range Th to verify that NC temperature is at ; east 50*F sub- l cooled at present NC pressure. l 1
/ 3.19.1 If 50*? subcooling is not present, attempt to establish l l
50*F subcooling by use of condenser dumps. !
/ 3.19.2 If steam dump is necessary, reduce S/G pressure to main-tain a NC system cooldown rate of no more than 50*?/Er.,
consistent with makeup capability, until 50*F subcooling is established.
/. 3.19.3 If 50'r sue:coling cannot be established or maintained, then MANJUALLY REINITIATE SAFE"Y CUECTICN and go to Step 3.1 in EP/1/A/5000/__,(Immediate Ac:1ons and Diagnos-tics for a Safety Injectica) .
/ 3.20 If the conditions for terminating safety injection in Step 3.6 are not met, maintain necessary NV, NI and ND pumps in operation. If any E/S equipment is not operating, accompt to operate the equip-ment from the Control Room or locally. Initiate repairs if neces-sary.
/ 3.21 Stop all NC pumps af ter NV pump operatica has been verified and when the vide range NC pressure is at psig.
l
/ 3.21.1 Close the Centrifugal Charging Pump ninflicw isolation valves 1NV-151A (NV Pumps Recirculation) and Uiv-1503 (NV Pumps Recirculation) when the actual Reaccer Coolant systas pressure drops to the calculated manual reactor ecolant pump trip setpoint psig.
/ 3.21.0 Reopen the Castrifugal Charging pu=p niniflow isolation valves 1NV-131A (NV ?u=ps Recirculation) and 1NV-1503 (NV ?u=ps Recur:ulation) shculd :he vide range Reactor Cociant lystas pressure sub: quently rise to greater than 1
2000 psig.
l Initial /D .
>+
CAE!ICN: If KC to the NC pumps is isolated on Phase "B" all NC pumps should be stopped within 5 minutes because of loss of motor bearing cooling.
CAUTICN: If the NC pumps are stopped, the seal injection flow should be maintained.
NOTE: The conditions given above for stopping the NC pumpe should be continuously monitored throughout this procedure.
/ 3.22 If the NC possure quickly decreases below the S/G pressure, go to Step 3.32.
/ 3.23 Il the NC pressure slowly decreases or stabilizes above 1170 psig, the following additional actions should be taken to aid in :he cooldown and depressurization of the NC system:
/ 3.23.1 If :he main condenser is available (C-9), reset main steam isolation, MSIV Bypass and SM PORV's (if required due to Phase "3").
NOTE: Verify the MSIV Sypass Valve manual loaders are closed prior to resetting the MSIV Bypass Vivs.
/ 3.23.1.1 Slowly open the MSIV bypass valve (s) (if re-
- quired due to Phase "3"). If NC pressure is below 1955 psig (?-11) block :he steam line safety injec:1on in order to preven: main steam isolation during cooldown when S/G pres-sure decreases below 585 psig.
/ 3.23.1.2 Open the MSI7's (if required due to Phase "3")
and place the s:aam dump control in pressure mode to lower :he NC temperature and pressure.
/ 3.23.2 If the main condenser is not available (loss of C-9), re-set SM PROV's (if required due :o Phase "3") and dumo steam to atmosphere :o lower the NC :emperature and pres-sure.
CAUTICN: Reduce the S/G pressure to 970 psig and saintain a NC system cooldown rate of no. sore :han 50*7/Hr.,
consisten: wi:h nakeup capabiliry.
/ 3.24 If logic :est on T'4ST level is in progress, notify I5E Oeparrnent to place circuit back to nornal.
l Initial /Date
/ 3.25 If Phase 3 isolacisu occurs, the RV pumps must be stopped. The Reactor Coolant pumpe must be tripped within 5 minutes if not previously tripped.
NOTE: Verify Phase "3" isolacion and actuation of containment spary at 3 psig contslament pressure if not done previously.
/ 3.26 Verify proper operation of the Annulus Ventilation System (OP/1/A/6450/02).
/ 3.27 Verify Upper Head Injection Accumulator Tank discharge at 1240 psig and discharge isolation valves automatically close and gas after tank contents are discharged.
/ 3.28 Verify all four Cold Les Accumulators discharge between 400 and 450 psig.
/ 3.29 If the CAC is inoperable, perform 30P ES7 Components alignment checklist, Enclosure 5.1.
/ 3.30 Perform Post Accident Checklist, Enclosure 3.2.
/ 3.31 Refer to EP/0/A/5000/33 (Site Emergency).
3.32 *4 hen the T4ST level decreases to the lov level alarm point (12'6")
_ _/
but not earlier than 10 minutes af car safety injection actuation. l perform the following to establish containment sump, cold leg l
. recirculation:
/ 3.32.1 Change Residual Heat Removal Pumps suction from the T4ST )
to the Containment Rectre. Sump:
NOTE: If nanual swap of ND pumps suction is not accomp-11shed prior to S.0 f t. T4ST Lvl., insure automatic swap occurs prior to reaching 7 fc. FWST Lvl.
/ 3.32.1.1 Open INI-184 (Containment Sump Line 13 Isohtion) .
~
As it opens, verify the closing of IND-4 (NC *. cop 3 to ND P.mrp 13 Containment Isol. Outside).
/ 3.32.1.2 Open 1NI-135 (Containment Sump Line 1A ! solation).
As it opens, verify the closing of IND-19 (NC Loop 1C to ND ? ump 1A Containment ! sol. Cutside).
NOTE: If T4ST emergency to Level (0.9 ft.) is reached before change over :o the recirc-ulation su=p is completed, secure all pumps :aking suctica on :he T4ST.
/ 3.32.2 Reinstate control power to 174-27 (74ST to su pu=p :3e_
lation).
.g.
Initial Date
/ 3.32.3 Close:
1FW-27 (TJST to ND Pump IsoLstion)
MD-30 (ND HZ 1A Outlet Crossort: 31ock) 1ND-15 (ND HI 13 Outlet Crossover 31ock)
/ 3.32.4 Stop Containment spray pumps 1A and 13.
/ 3.32.5 Close INS-20 (NS Pump 1A Suction from RWST Block).
/ 3.32.6 Open D S-IS (NS Pump 1A Suction from Containment Sump Block).
/ 3.32.7 Open 1RN-134 (NS Heat Exchanger 1A Supply Isolation).
/ 3.32.8 Start Containment S., ray Pump 1A.
3.32.9 Close DS-3 (NS Pump 13 Suction from RWST 31ock).
_/
/ 3.32.10 Open 1NS-1 (NS Pump 13 Suction from Containment Sump 31ock).
/ 3.32.11 Cpen 1RN-235 (NS Heat Izchanger 13 Supply Isolation) .
/ 3.32.12 Start containment Spray Pump 13.
/ 3.32.13 Close: ;
1NI-115 (Safety Inj . Pump 1A Miniflow Line Isol.)
INI-114 (Safety Inj. Pump 13 Miniflev Line Isol.)
/ 3.32.14 Reinstate control power to 13I-147 (Safety Inj. Pumps Miniflow Edr. to RWST).
/ 3.32.15 Close 1NI-147 (Saiety Inj . Pumps Miniflow Edr. to RWST) .
/ 3.32.16 Open 1NI-135 (ND HI 13 to Safety Inj . Pump 13) .
/ 3.32.17 Reinstate control power to DI-100 (RWST to Safety Inj .
Puy s).
/ 3.32.13 Close 1NI-100 (RWST to Safety Inj. Pumps).
/ 3.32.19 Wait until the "r4ST Lo-Lo Lvi" alarm (0.9') is received before proceeding to the next step.
/ 3.32.20 OpenIND-58(NDHI1AduelettoCancrifugalCharging Pumps 1A and 13 31ock).
/ 3.32.21 Open 13I-332 and 1NI-333 (Saf acy Inj . Pump Suction Cross-over from NV).
Open 1NI-334 (Safety Injection Pump Suction Crossover fron :.V Isol.) .
/ 3.32.22 Close 1NV-221 and 1NV-202 (Cant:1 fugal Charging Pumps Su tion f cm FW System).
/ 3.32.23 Start Hydrogen Recombiners in accordance with OP/0/A/%30/1:
(Hydrogen Ski =mer, Cont. Air Return, Hydrogen Reco=biner and Hydrogen ? urge Syscam) when Hydrogen concentration Naches 2".
l
m ,
6
. ['
v6 I Initial / Data I
/ 3.32.24 After one hour, if offsite power has not been interrupted '
stop the Emergency Diesel Generators per CP/1/A/6350/02 (Diesel Generator).
/ 3.32.25 If a loss of offsite power occurs while in the Cold Leg Recirculation : node, refer to section 4.0 of this procedure. l
/ 3.33 Notify Chemistry Depart:nent and HP Department to obtain ph sample of concalament sump water and to begin periodic sampling of con-tain==nt for hydrogen concentration.
/ 3.34 If containment pressure increases to 13.0 psi following depletion i of the ice in the ice condenser, align the Residua', Heat Removal spray headers as follows: l
/ 3.34.1 verify that IND-30 (ND HI 1A Outlet Crossover Block) and 1ND-15 (ND HI 13 Outlet Crossover Block) are closed.
NOTE: Do not initiate ND System Spray until at least one hour after Safety Injection has been initiated.
/ 3.34.2 Reinstate power to the following valves:
1NI-173 (ND Edr. to NC Cold Leg Loops 1 and 2)
INI-178 (ND Edr. to NC Cold Lag Loops 3 and 4)
/ 3.34.3 Close 1NI-173 (ND Edr. to NC Cold Leg Loops 1 and 2) .
_/
- 3.34.4 When 1NI-173 is fully closed, open DIS-43 (ND ? ump la Disch. to NS Nozzles Containment Isolation cucside) .
/ 3.34.5 Close 1NI-178 (ND Edr. to NC Cold Leg Loops 3 and 4).
/ 3.34.6 'aten 1NI-178 is fully closed, open 1NS-38 (ND Pump 13 Disch. to NS No::les Conatisment Isolatica Cutside).
/ 3.35 '. ten containment pressure has decreased to an allowable level, the Residual Heat Removal Pumps discharge may be rtaligned to the Re-actor Coolant System Cold Legs as follows:
/ 3.35.1 Close INS-43 (ND Pump 1A Disch. to NS Nozzles Contaimnent Isolation Outside) .
/ 3.35.2 When DIS-43 is fully closed, open 1NI-173 (ND Edr. to NC Cold Leg Loops 1 and 2).
/ 3.35.3 Close DIS-38 (ND Pump 13 Disch. to NS Nozzles Contain:nent Isolation Cutside) .
/ 3.35.4 When DIS-38 is fully closed, open DII-173 (ND Hdr. NC Cold *.eg Loops 3 and 4).
NCTI: Cold '.eg Recirculation ?hase . Monitor *.ight Con-figuration. Orcup 3 and a :cepletely lighted.
Groups 1, 3. 5, i, and ' cupletely dark.
~
10 NOTE: Group 6 should be lighted during recirculation V mode if Upper Head Injection has actuated and secured.
/ 3.35.5 Start Hydrogen Purge System per CP/0/A/6450/10 (Hydrogen Skimmer Cont. Air Return, Hydrogen Racombiner and Hydrogen Purge System) if Hydrogen Concentration increases to 3.5%.
Reduce concentratiot. to <3% and realign.
/ 3.36 Approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> after the accident, realign the Safety Injection System for Hot Lag recirculation as follows:
/ 3.36.1 Reinstate power to the following vhlves:
1NI-173 (ND Edr. to NC Cold Les Loops 1 and 2) 1NI-178 (ND Edr. to NC Cold Lag Loopa 3 and 4)
INI-183 (ND Edr. to NC Hot Lage Isolation)
INI-121 (Safety Injection Pump 1A Hot Lag Injection Header Isol.)
1NI-162 (Safety Injection Pumps Cold Leg Inj. Edr. Iso.)
13I-152 (Safety Inj . Pump 13 Hot
- eg Inj . Edr. Iso.)
/ 3.36.2 Close 1NI-173 (ND Edr. to NC Cold Lag Loop 1 and 2).
/ 3.36.3 open IND-30 (ND HX 1A Cutlec Crossover Block) .
/ 3.36.4 Open 1NI-183 (ND Edr. to NC Hot Legs Isolation)
/ 3.36.5 Close 1NI-178 ND Edr. to NC Cold Lag Loops 3 and 4).
[ 3.36.6 Cpen IND-15 (ND HI 13 Cur.let Crossover Block)
/
3.36.7 Stop Safety Injection ? cmp 1A.
/ 3.36.8 Close 1NI-113 (Safety Injection LA Cold Leg Inj. Line Iso.)
/ 3.36.9 Cpen 1NI-121 (Safety Inj. Pump 1A Hot Lag Inj. Header Isolation).
/ 3.36.10 Start Safety Injection Pump 1A and verify flow to the Reactor Coolant System ehrough the Hot Leg Header.
/ 3.36.11 Stop Safety Injection Pump 13.
f_ 3.36.12 Cicee:
1NI-162 (Safety Inj. Pumps Cold Lag Inj . Edr. Isol.)
INI-150 (Safety Inj . Pump 13 Cold Lag Inj . Lines Isol.) i
/ 3.36.13 Open 1NI-152 (Safety Inj . Pump 13 Hot Lag Inj . Header Isolation).
/ 3.36.14 Start Safety Injection Pump 13 and verify fl:v to the Reactor Coolant Jystas through the Hot Lag Header.
NOTI: !?.e ReJidual Heat Re= oval and Saf acy Injection ?u==
are nav aligned for Hot Lag recirculati:n.
NCT2: Menitor Light Configuration furing Hot Lag Re:ir:-
ulation. ;rcups 2,J., 5, 6 c:mpletely lightad.
- 1 G: cups 1, 3, 7 ::=pleta dark. !
l l
l
.,,9 v Initial /Date
/ 3.37 Verify that when coatsdn=nc pressure decreases to less :han .25 pais containment spray pumps shutdown.
4.0 Recovery from Loss of offsite Power 'Aile in Cold Lag Recirculation
/ 4.1 One minute after the loss of power occurred reset :he Diesel Generator Load Sequencers.
NOTE: 'Jait one minute before resetting to allow all loads to be sequenced on.
/ 4.2 Secure the following loads.
/ 4.2.1 Centrifugal Charging Pumps A and 3.
/ 4.2.2 Pressurizer 3ackup Heaters
/ 4.2.3 3cron Injection Tank Heaters
/ 4.2.4 Soron Injection Racircula:1on Pumps A and 3
/ 4.2.5 Boric Acid Transfer Pumps
/ 4.2.6 Pipe Tunnel Sooster Fans
/ 4.2.7 Control Rod Drive Vent Fans l
/ 4.2.8 Lower Contmin=nt Cooling Units
/ 4.2.9 Upper Containment Cooling Uni:s
/ 4.2.10 Upper Containment Return Air Tans
/ 4.2.11 Incore Instrument Roca Air Handling Units
,/- 4.3 Restart the following loads in the sequence listed.
NOTE: In order not :o overload the Diesel Generator, start one load, then wait 'S sec., check voltage, amperate and load on the Diesel Generator, then start :he next load.
/ 1.3.1 Kasidual Heat Removal Pumps A and 3.
/ 4.3.2 Safety Injec:1on Pumps A and 3.
/ 4.3.3 Centrifugal Charging Pumps A and 3.
/ 4.3.4 Annulus Ventilation Fans A and 3, and verify proper opera: ion per CP/1/A/6450/02 (Annulus ventilation. System).
/ 4.3.5 Annulus 7entilation ? reheaters A and 3.
/ 4.3.6 Containment Air Return Tans A and 3.
/ 4.3.7 Containment Spray Pumps A and 3. I
/ 4.3.3 If the following vere operating prior to the loss of pcwer, restar: then.
/ 4.3.3.1 Hydrogen Reconbiners A and 3.
/ 4.3.3.2 Hydrogen Ski =er Fans A and 3.
/ 4.3.9 Star: Spent Fuel Cooling ?u=p A or 3 is desired.
1
g.
fR
\ .
Initial /Date
/ 4.4 7erify the proper operation of the following loads.
/ 4.4.1 Vital Battery Chargers E7CA, E7C3, EVCC, E7CD.
/ 4.4.2 Load Centers ELIA, ELIE, ELIC, ELID.
/ 4.4.3 Power Pane 1 boards IKA and EX3.
/ 4.4.4 ND and 285 Room Sump Pumps.
/ 4.4.5 A/C System Switchgear Room Fans SGR-AHU-A, 3, C, and D.
/ 4.4.6 D/G A and 5 Anw414meies.
/ 4.4.7 Blowers for the following EMF Monitors.
/ 4.4.7.1 EMF-33 (Condenser Air Ejector)
/ 4.4.7.2 EMF-35, 36, 37 (Unic Vent Particulate, Gas and Iodine)
/ 4.4.7.3 EMF-38, 39, and 40 (Containment Particulate, Gas and Iodine)
/ 4.4.7.4 EMF-41 (Auxiliary Building Ventilation)
/ 4.4.7.3 EMF-42 (Fuel Su11 ding 7entilation)
/ 4.4.7.6 EMF-43A (Control Room Air Intake A)
/ 4.4.7.7 EMF-43B (Control Room Air Intake 3)
/ 4.4.3 Auxiliary Building 711tered Exhaust Fans A and 3.
/ 4.4.9 Comp. Cooling pumps A1, A2, 31 and 32.
/ _
4.4.10 Nuclear Service 'Jacer Pumps A and 3.
/ 4.4.11 Auxiliary Teodwater Pumps A and 3.
/ 4.4.12 Control Area Air Conditicuing System
/ 4.4.13 Battery Room Exhaust Tans 1 and 2.
/ 4.4.14 Ground Water Drainage System Pumps.
5.0 Enclosures 3.1 30P ESF Components A11gnmenc Checklist 5.2 Post Accident Valve Checklist j
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EP/1/A/5000/ 32 McGUIRE NUCLEAR STATION STEAM GENERATOR TUBE RUPTURE 1.0 Symocoms 1.1 High Air Ejector Radiation (EMF-33) 1.2 High S/G Bicudown Radiation (EMF-34) 1.3 Steam Flow /Feedwater Flow Mismatch Alarm 1.4 Increasing S/G Water Level 1.5 Rapid decrease in Pressuri:er Pressure and Level 2.0 I:nmediate Action Refer to Immediate Actions of EP/1/A/5000/ _ (Immediate Actions and Diagnostics for a Safety Injection) if not already accomplished.
3.0 Subsequent Actions 3.1 All necessary 1:nmediate actions of EP/1/A/5000/_ (Immediate Actions and Diagnostics for a Safety Injection) have been perforned.
NOTE: If for any reason all reactor coolant pumps are tripped, ensure that core decay heat is being removed by natural circulation. Refer to OP/0/A/6150/14 (Decay Heat Removal by Natural Circulation).
NOTE: Make arrangements to sample containment atmosphere and steam generators to identify presence of abnornal radioactivity.
CAUTION: The diesels should not be operated at idle or nini=um load for -. ore than one hour. If the diesels are shut down, they should be prepared for restart.
3.2 Identify the faulted steam generator by one or note of the following nachods:
3.2.1 An unexpected rise in one steam generator water level with auxiliary feedwater flow reduced or stopped.
3.2.2 High radiation from any one steam generator blowdown line radiation monitor.
3.2.3 High radiation from any one steam generator, as determined by analysis or a sample.
NOTE: While identifying and isolating the faulted Steam Generator according to Steps 3.2 and 3.3, continua vich subsequent Steps 3.4 through 3.12.
3.3 When the faulted steam generator has been positively identified, then:
3.3.1 Stop all feedwater flow to the faulted steam generator (C7 andCA) . j 3.3.2 Close the sain steam isolation valve and check closed the =ain steam l isolation bypass valve associated vich the faultad steas generator.
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3.3.3 Verify the closure of the power operated relief valves associated
_ / 1 with the faulted steam generator. l JIE: If the main steam isolation valve or bypass valve associated with the faulted steam generator vill not close, then close the main attam isolation valves and bypass valves associated with non-facited steam generators and terminate all steam dumps to the condenser. Utilize the non-faulted steam generators' l power operated relief valves to maintain the reactor coolant !
system at approximately no-load conditions.
/
/
3.3.4 Trip the reactor coolant pump in the loop associated vich the faulted steam generator.
/ 3.3.5 Close the isolation valve in the steam line to the auxiliary feedwater pump assdciated with the faulted S/G. If the faulted Steam Generator is "3", unlock and close ISA-2 (Main Steam 13 to Aux. FDWPT Yo.1 Maintenance Isolation). If the affected Steam Generator is "C",
unlock and close 1SA-1 (Main Steam IC to Aux. ~~DWPT No. 1 Maintenance Isolacion).
/ 3.4 Verify that all pressurizar power operated tr'.ief valves are closed. Verify the open status and availability of power to all pressurizar power operated valve isolation valves.
/ 3.5 Stop all reactor coolant pumps af ter Centrifugal Charging Pump Operation has been verified and when the wide range reactor coolant pressure is at psig.
/_ 3.5.1 Close the Cantrifugal Charging Pump niniflow isolation valves 1NV-151A (NV Pumps Recirculation) and 1NV-150B (NV Pumps Recirculation) when the actual Reactor Coolant System pressure drops to the calculated nanual reactor coolant pump trip setpoint psig.
/ -
/ _ 3.5.2 Reapen the Centrifugal Charging Pump niniflow isolation valves INV-151A (NV Fumps Recirculation) and 1NV-150B (NV Pumps Recirculation) should the wide range Reactor Coolant System pressure subsequently rise to greater than 2000 psig.
_ / 3.6 If component cooling to the reactor coolant pumps is isolated on a con-tainment pressure signal, all reactor coolant pumps are to be stopped within 5 minutes because of less of notor bearing cooling.
CAUTICN: If reactor coolant pumps are stopped, the seal injection flow should be naistained.
NOTE: The conditions given above for stopping reactor coolant pu=ps should be continuously nonitored through Step 3.13 of this instruction.
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3.7 Verify all Emergency Core Cooling components have assumed their safeguards status. Manually align any that did not.
! '/ 3.7.1 During Upper Head Injections Groups 3 & 4 completely lighted, Groups 1, 2, 5, 6, and 7 completely dark.
/ 3.7.2 After Upper Head Injection Groups 3, 4, & 6 completed lighted, Groups 1, 2, 5, & 7 completely dark.
/ 3.7.3 If either train of the BOP ESF Components monitor lights in Group 1 and Group 4 are out of sequence with the other lights in their re-spective group, the OAC must be interrogated to obtain a printout of misaligned BOP ESF Components.
NOTE: If the Phase A Containment Isolation Monitor Lights are also out of sequence, manually initiate Phase A Contain= ant Isolation.
/ 3.7.4 If the OAC is inoperable, perform BCP ESF Components alignment checklist, Enclosure 4.1.
/ 3.8 If offsite power and the condenser (C-9) are available, open Main Steam Isolation bypass valves and any closed main steam line isolation valves except those on the faulted S/G to provide a flowpath to the condenser dump valves.
/ 3.9 Establish power sources necessary to operate at least one pressuriser power 4 operated relief valve, at least one steam generator power opverated relief valve, and charging and letdown flowpaths.
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/ 3.10 Manually stabilize the reactor coolant system (if not accomplished automatic- l ally) at approximately no-load temperature (557'F) by steam dump to the main condenser if offsite power and the condenser (C-9) are available. If offsite power or the condenser is not available, utilite the non-faulted :
steam generator power operated relief valves to stablize the reactor coolant system at approximately no-load temperature (557'F).
[ _ 3.11 Reset CA Modulating Valves and control auxniary feedwater flow to =aintain narrow range levels in the non-faulted steam generators.
NOTE: Monitor CA Condensate Storage Tank level and Upper Surge Unk level.
CA suction will auto-swap to RN at 2.0 psig suction pressure.
/ 3.12 If reactor coolant system pressure stabilizes above the Residual Heat Re-moval Pumps shutoff head (200 peig), manually reset Safety Injection, Phase A Isolation and the Diesel Generator load Sequencers so that safeguards equipment can be controlled by manual action. Stop the Residual Heat Removal Pump. Inst. Air Containment by opening:
17!-129B (A ESS Header cont. Isol. OTSD)
IV!-160B (3 ESS Header Cont. Isol. OTSD) 17!-362A (7 to Annulus 7ent Cont. Isol.)
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IvI-150B (Lwr. Cont. Non Ess Hdr. C/I OTSD) 17I-148B (Upp. Cont. Non Ess Hdr. C/I OTSD)
CAUTION: If tha reactor coolant system pressure decreases uncontrollably below the Residual Heat Removal pumps shut-off head, the pumps must be manually restarted to deliver fluid to the reactor cool-anc system.
CAfttION: Automatic reinitiation of safety injection will act occur since the reactor trip breakers are not reset.
CAUTION: Subsequent to this Step, should loss of offsite power occur, manual actica (e.g. , manual safety injection initiation) will be required to load the safeguards equipment onto the diesel powered emergency busses.
CAUTION: Do not proceed to Scpe 3.13 until the faulted steam generator has been identified and isolated.
Initial /Date
/ 3.12.1 Alizn the unaf"ectsd Steam Generators for nor=al blowdown per OP/1/3/6250/08 (Steam Generator 3 lowdown).
/ 3.13 After the faulted steam generator has been identified and isolated, begin a rapid cooldown of the reactor coolant system to 50*F below the no-load temperature (557*F) by use of the steem dump.
/. 3.13.1 If offsite power and the cendenser (C-9) are available, dump steam to the main condenser from the ncn-faulted steam generators by manual control of the steam header pressure controller.
/ 3.13.2 If offsite power is not available for the =ain condenser is not available, dump steam from the non-faulted steem gener-ators -drough the steam generator power operated relief
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valves.
/ 3.14 After the reactor coolant system temperature has been reduced to 50*? below the so-load temperature (557'?), if necessary begin a depressurization of the reactor coolant system to a value equal to the faulted steam generator steam pressure.
/ 3.14.1 Isolate all UHI Accumulator Discharge 7alves.
/ 3.14.2 If the RCP's are in service, use the pressuri:er spray to reduce the pressure.
/ 3.14.3 If offsite pcuer is not available, or the AC?'s are not in service open one pressurizer ?CRV :o decrease pressure.
NOTI: During subsequent controlled reactor coolant systes depressuri:atien, the reactor coolant systes pressure critarion for : ripping the reactor :colant pu=ps established in Step 3.3 OcES : rot A??L?.
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,:yk Initial / Data CAUTICN: Monitor containment indications to verify that a loss of reactor coolant other than the staan generator tube rupture is not in progress. If con-tainment sump level or a containment rample (if available at this time) are not in the normal pre-event range, further accident recovery must be directed according to J/ (Loss of Reactor Coolant, Step .
/ 3.15 As the reactor coolant system pressure decreases, due to the quenching of the steam by the pressurizar spary or due to the steam release through the pressurizar PORV, monitor the pressurizar water level indications and stop the depressurization operation:
/ 3.15.1 As soon as the reactor coolant system pressure decreases to a value equal to the faulted steam generator steam pressure.
/ 3.16 After the depressurization operation has been verified to have been terminated (using the pressurizar PORV stem-mounted position indicators or spary valve demand signal), continue to monitor the reactor coolant syscam pressure and the pressurizar water level.
/ 3.16.1 If the pressurizar water level continues to rise or r-mins
. nearly constant concurrent with a reactor coolant system pressure decrease, suspect leakage from the pressurizar steam space. Monitor the pressurizar relief tank (PRT) pressure, temperature and level to identify continusously increasing conditions. Close the PORV isolation valves if a reactor coolant leak to the PRT is identified. Monitor PRT conditions to verify PRT integrity.
~
CAUTION: If pressurizer relief tank integrity is lost, ab-nornal containment conditions could exist and may not be true indications of a continued loss of reactor coolant. If conditions of Step 3.16.1 per-sist after clorang the pressurizer ?OR7 isolation valves, further recovery sust be directed accord-ing to IP/ (Loss of Reactor Coolant)
Step . The conditions of Step 3.16.2 nust be satisfied before proceeding to Step 3.17.
/ 3.16.2 If the pressurizer water level subsequently continues to increase concurrent with a reactor coolant systen pressure increase, the safety injection flow is greater than the leak.
Initial /Date Then, stop all operating ECCS pumps not needed for nornal charging and reactor coolant pump seal injection flow when:
/ 3.16.2.1 Reactor coolant system pressure has increased by at least 200 psi (after shutting the spray valves or verified closure of the pressurizar PORVs) and
/ 3.16.2.2 An indicated water level has returned in the pressurizer, and
/ 3.16.2.3 The reactor coolant system indicated subcooling 3ASED CN '4IDE ENGE *EMPERATURE IN THE NON-FAULTED LOOPS OR THE CORE EXIT THEIQ10 COUPLES is greater than 'F.
CAUTION: Automatic reinitiation of safety in-jaccion will not occur since the reactor trip breakers are not reset.
NOTE: Following termination of safety injection, pressurizar pressure should decrease to a value equal to the faulted steam generator steam pressure.
/ 3.17 Re-establish charging flow to naintain the pecesurizer water level
. in the operating range (approxinately 25 percent indicated level) as follows:
CAUTION: If, during subsequent recovery actions, pressurizer water level cannot be raintained above 25 percent indicated level or the re tter coolant system indicated subcooling 3ASED CN 'JIDE ENGE TEMPERATURE IN THE NON-FAL1TED LCOPS OR *HE CORE EXIT THERMCCCUPLES cannot be naistained at l a value greater than ~ *? operate ECCS pumps as re-quired to re-establish pressurizer water level and sub- l cooling. If pressurizer water level and subcooling cannot be established by this method, MANUALLT RE!NITIATE SAFE"'?
IN.EC* ION, return to Step 3.14 and proceed with the in-struction from that point.
/ 3.17.1 Throttle LTT-238 (Charging Line Flow Control) as necessary to supply 'S gym seal injection flow.
/ 3.17.2 Close: 1NI-4A (3IT Inlet Isol.)
IN!-53 (3IT Inlet Isol.)
INI-9A (3IT Jisch. Isol.)
INI-103 (3I! Disch. Isol.)
. j
/ 3.17.3 Align the Centrifugal Charging Pump to take a suction
- from the VCT:
Open: INV-141A (VCT Cutlet Isolation)
LW-1423 (VCT Quclet Isol.)
Close: LW-221A (NV Pumps Suct. From FWST) 1NV-2223 (NV Pumps Suct. From FWST)
/ 3.17.4 Establish nornal charging as follows:
Close LW-241 (Regen. HI Tube Side Inlet Catri.)
Open: LW-244A (Charging Line Cont. Isol. OTSD) 157-2453 (Charging Line Cont. Isol. OTSD)
/ 3.17.5 Slowly throcria open LW-241 (Regen. EI Tube Side Inlet Catri.); as it is opened adjust LW-238 (Charging Line Flow Centrol) as necessary to -aatncain seal injection flow.
/ 3.18 Re-establish KC flow to the Auxiliary Building Non-Essential Header as follows:
Open: 1KC-IA (Trn. lA to AB Non Ess Ret Isol.)
IIC-23 (Trn. 13 to A3 Non Ess Ret Isol.)
Close: 1XC-56A (KC to A ND HI)
IIC-813 (KC to 3 ND ZI)
NOTE: Verify both ND Pumps are secured prior to closing 1KC-56 and 1KC-al.
As flow decreases, open:
1XC-50A (Trn. lA to A3 Non Ess Sys Isol.) ;
lIC-533 (Trn. 13 to A3 Non Ess Sys Isol.)
/ 3.19 Establish Seal Water Return by opening: ;
1h 7-94A (NC Pumps Seal Ret C/I Inside)
INV-953 (NC Pumps Seal Ret C/I OTSD) l
/ 3.20 Establish letdown by opening:
LW-1A (NC L/D Isol. to Regen HI)
LW-2A (NC L/D Isol. to Regen HI)
INV-73 (Letdown Cont. Isol. Outside)
Slowly throttle open 1NV-459A (A L/D Orif. OTLT Cont. Isol.) to vars the letdown line. Af ter the letdown line is var =ed, open 1.W-458A (3 L/D orif. OTLT Cont. Isol.) and/or LW-457A (c' L/D Orti. CTLT l Cont. Isol.).
/ 3.21 Verify LW-124 (t.acdova Press. Control) is nodulating to naintain lacdown prassure at '350 psig.
/ 3.22 Re-establish the use of the pressuri:er heaters to naistain the j
reactor coolant system pressure.
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/ 3.23 If offsite power has been restored, establish the required con-di:1ons for operation of a reactor cool.'nt pump and start the pump in a non-faulted loop (preferably in 'he loop connec:ed to the pressurizar, or if this is the faulted leop, in the other loop to which a spray line is connected) per C'/1/A/6150/02A (Reactor Coolant Pump Operation) . If all reactor coolant pun.ps are running, trip all but one reactor coolant pump so cs to maintain one pump operating in the loop connected to the pressurizer of if this is in the faulted loop, in the other loop to which a spray lina is connected.
/ 3.24 Refer to EP/0/A/5000/32 (Alert) .
CADTION: The following steps 3.25, 3.26, and 3.27 nust be per-for: red s%nicaneously. Failure to expedi:iously rsduce !
1 reactor cociant system pressure to a value equal to the faulted steam generator steam pressure once system cool-down is initiated could cause loss of pressuriaer level control.
/ 3.25 If offsite power is available, begin a controlled m oldown of the reactor coolant system at a race of about 30*F/hr by use of the steam dump to the nain condensers from the non-faul:ed steam gen-erators. Control the vacar levels in the steam generators :o nain-tain steam generator water level in the narrow ran;r,e span or in the viis range span at a. level sufficient :s assure that the U-
- uber. are covered.
If ot'fsite power is not available, dump steam from the non-faulted steam generators through the steam generator power operated relief valves to provide a controlled cooldown of the reactor coolant system at a race of about 50*F/hr.
/ 3.26 Simultaneous with :he cooldown using the non-faul:ed steam gener-acors, slowly decrease the faulted steam generator pressure by opening the bypass valva to the condenser (if available), or using the steam generator power operated relief valve.
/ 3.27 As pressure is reduced in thr faulted steam generator, control the reactor coolant pressure at a value approxinately aqual :o the steam pressure in :he faulted steam generator :o nini=1:e the leakage flow. Reac:or coolaat pressura con:rol should be accouplished by use of :he pressurizer heaters and action of one of the following:
'b Initial /p,g,
/ 3.27.1 Normal pressurizar spray (if an RCP is in service), o_r_
. / 3.27.2 Use of pressurizar auriMary spray (NV-21A (NV Spray to Pzr. Isol.) (if spray is heated by letdown through the regenerative heat exchanger), or
/ 3.27.3 3rief intermittant opening of one pressurizer PCRV.
NOTE: Maintain reactor coolant system temperature and pressure within the lim.a of the cooldown curves in the Data Book.
CAUT!CN: Safety injection should be reinitiated if n n-controlled reactor coolant system depressurization or an uncontrolled drop in pressurizar vacar lavel occurs during the cooldown process.
CAUTICN: If reactor coolant pressure control is accomplished by use of the pressurizar PCRV, continuously non-itor the PRT pressure, temperature and water level and take appropriate actions to verify and sain-tain PRT integrity. Verify pressurizar PORV clo-sare using the PORV stem-mountad position indi-cators and PRT conditions. If a reactor coolant leak to the PRT is identified, close ;N PCRV isolation valves. i
/ 3.28 'Aan the reactor coolant system pressure approaches the Cold ieg l Accumulator pressura, close the Cold Leg accumulator isolation valves.
/ 3.29 Start three upper and icwer contai" ment ventilation units.
/ 3.30 Raset the control permissive for recirculation seda 1NI-1843 and I
INI-185A. 1 l
/ 3.31 Rasat the contaimnant ventilation isolation signals.
/ 3.32 Notify Health Physics to datarmina activity released from the air ejectors and/or steam relief actuation.
/ 3.33 If gasacus release limits (10C7R-20, Appendix 3) have been ex-l caeded implement EP/0/A/5000/34 (General Inargency).
/ 3.34 Notify Chemistry to determine the extent of contamination to the secondary system. Refer to Technical Specifications (3.7.1.4) .
/ 3.35 Notify Chemistry to constantly scuitor NC System baron :encen-tration to ensura that dilution does not occur due to S/G draining into NC System.
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/ 3.36 Continue te cooldown and depressurizar the reactor coolant system and fault + steam generator until the reactor coolant hot b q camperatrys are below 350*7 in the non-faulted loops and the reactor coolant wide range pressure is less than 385 peig (do not collapse the pressurizar steam bubble).
/ 3.37 Place the residual heat removal system in operation using OP/1/A-6200/04 (Residual Haat Removal System).
NOTE: Throughout this cooldown procedure, maintain a steam bubble in the pressurizer. Solid water pressure control :nay not be effective.
/ 3.38 Coatinue -Jie plant cooldown in a normal mode excpet that after the RCP operation has been terninated, continue to si:nulcaneously con-trol the faulted steam generator steam pressure and reactor cool-anc pressure to sininize the leakage flow.
/ 3.39 '4 hen the reactor coolant system hot leg temperatures are reduced below 200*?, the pressure in :Se pressurizar say be reduced by using auxiliary spray until reactor coolant system pressure and l l
the faulted steam generator pressure equilibrate. ;
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