Text

Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling
	ML110050516
Person / Time
Site:	Salem, Hope Creek
Issue date:	06/24/2010
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	LR-N10-0355 HC.OP-AB.RPV-0009(Q), Rev 7
	Download: ML110050516 (64)
	v • d • e

RHR LOGIC A OUT OF SERVICE RHR LOGIC B OUT OF SERVICE RHR LOOP A TROUBLE RHR LOOP B TROUBLE RHR HX CLG WTR OUTLET TEMP HI COMPUTER PT IN ALARM APRM/RBM FLOW REF OFF NORMAL

Trip of RHR pump in Shutdown Cooling Isolation of Shutdown Cooling Flowpath Reduced or stopped RHR Shutdown Cooling flow to the Jet Pumps Lowering Core flow Rising Reactor coolant temperature/pressure Rising Recirc pump loop flow

TERMINATED Date/Time:

Procedures:

HC.OP-GP.SM-0001(Q), DEFEATING NSSSS ISOLATIONS FOR SHUTDOWN COOLING

Valves:

BC-HV-F008 SHUTDOWN COOL ING OUTBD ISOLATION BC-HV-F009 SHUTDOWN COOL ING INBD ISOLATION BC-HV-F015A RHR LOOP A RET TO RECIRC BC-HV-F015B RHR LOOP B RET TO RECIRC BC-HV-f006A RHR PMP A SUCT FROM RECIRC BC-HV-F006B RHR PMP B SUCT FROM RECIRC

Reactor Pressure > 82 psig The following valves cannot be opened from the Control Room OR their Remote Shutdown controls: HV-F008 HV-F009 HV-F015A HV-F015B Reactor Pressure > 82 psig OR Reactor Level < 12.5"

OR Loss of EITHER RPS Bus AND RSP Takeover Switches in NORMAL The following valves will isolate: HV-F008* HV-F009* HV-F015A* HV-F015B*

RHR Pump in Shutdown Cooling

AND Closure of ANY of the following: HV-F008 HV-F009 Associated HV-F006 RHR pump trips.

If GP.SM-0001 has been performed, these isolations are bypassed.

A. Loss of the RHR system prov iding Shutdown Cooling........................................................7 B. Alternate Loop of RHR is required to restore Shut down Cooling.........................................7 C. RHR S/D Cooling CANNOT be established wit hin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ...................................................

9 D. Loss of S/D Cooling AND RCS temp. < 200 o F AND RCS temp. is anticipated to reach 200 oF.................................................................9 E. Forced Circulation CANNOT be established using preferred RHR loops or Reactor Recirculation. 11 F. RWCU is required for Alter nate Decay Heat Removal......................................................11 G. Condensate Transfer is required for S/D cooling...............................................................13 H. RPV Temperature and Pressure CANNOT be maintained using Normal OR Alternate Decay Heat Remo val...................................................................................17

1. Fill and vent of the suction line should not be required for a spurious isolation provided action is taken to promptly restore the syst em and there is no reason to believe air has been introduced into the system. Procedures: HC.OP-SO.BC-0002, DECAY HEAT REMOVAL OPERATION Valves: BC-HV-F015A RHR LOOP A RET TO RECIRC BC-HV-F015B RHR LOOP B RET TO RECIRC BC-HV-F008 SHUTDOWN C OOLING OUTBD ISOLATION BC-HV-F009 SHUTDOWN C OOLING INBD ISOLATION 0.0001.0002.000 3.000 4.0005.000101001000100°F120°F140°F160°F180°F ** Represents initial starting temperature as listed in the Fi gure. Each line represents a different initial st arting temperature

___ A.1 IF below 200 o FTHEN the following:

___ a. time to reach 200 o F IAW Figure 1. ___ b. IF RCS temperature is expected to rise above 200 o F, THEN Condition D.

___ ___ A.2IF the SDC suction line isolates AND it is determined a fill and vent is required, THEN the following:___ PRIOR to establishing the suction flow path from the vessel,

& the suction line IAW Attachment 4 OR SO.BC-0002.

___ the need to implement Condition C (Suction line venting may take

more than one hour).

___ A.3 NSSSS is reset (SM)

___ A.4 HV-F008 and HV-F009 are OPEN. (if necessary, dispatch operators to operate manually).

] A.5Restore the tripped RHR pump as follows:

___ a. F015A(B).

___ b.

RHR Pump A(B). A. Loss of the RHR system providing Shutdown Cooling

Date/Time:

Estimated time RCS will reach 200F: ___ c. IMMEDIATELY F015A(B) to establish Shutdown Cooling flow between 3000 gpm and 10,000 gpm. B. Alternate Loop of RHR is required to restore

Shutdown Cooling Date/Time:

___ B.1 RHR loop A(B) in Shutdown Cooling IAW SO.BC-0002.

Procedures: HC.OP-SO.BB-0002, REACTOR RECIRCULATION SYSTEM OPERATION Valves: BB-HV-F001 REACTOR HEAD VENT DRW INBD ISLN BB-HV-F002 REACTOR HEAD VENT DRW OUTBD ISLN

PI-5824A 0 - 50 LOW RANGE REACTOR PRESS PI-5824B 0 - 50 LOW RANGE REACTOR PRESS PI-R605-C32 0 - 1200 REACTOR PRESSURE PR-R623A-B21 0 - 1500 PAMS PR-R623B-B21 0 - 1500 PAMS PI-3684A 0 - 1500 PAMS PI-3684B 0 - 1500 PAMS 1FDPISL-N658A-E41 0 - 200 HPCI TRIP UNIT 1FDPISL-N658E-E41 0 - 200 HPCI TRIP UNIT 1FDPISL-N658C-E41 0 - 200 HPCI TRIP UNIT 1FDPISL-N658G-E41 0 - 200 HPCI TRIP UNIT 1FCPISL-N658B-E51 0 - 200 RCIC TRIP UNIT 1FCPISL-N658F-E51 0 - 200 RCIC TRIP UNIT 1FCPISL-N658D-E51 0 - 200 RCIC TRIP UNIT 1FCPISL-N658H-E51 0 - 200 RCIC TRIP UNIT

___ C.1 Reactor Coolant temperature and pressure at least once per hour.

C. RHR S/D Cooling CANNOT be established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Date/Time:

___ C.2 forced circulation in the core utilizing Reactor Recirc IAW SO.BB-0002 OR an alternate method.

___ D.1 the need to establish Primary

AND Secondary Containment.

___ D.2 the following for indications of entry

into OPCON 3:

___ An increase in steam dome pressure could be indicative that boiling, to some degree, is

occurring in the Reactor Core. This

parameter should be monitored using the

redundant Reactor pressure indications given

in Table D.2, particularly those with the

lowest ranges such as Reactor Low Range

Pressure (0 - 50 psig on Panel 10C650A) or, the HPCI and RCIC trip units.

___ An increase in Reactor Head Vent temperature could be indicative of the onset

or verification of the presence of boiling in the

vessel. This temperature is monitored by

TE-N064 (when BB-HV-F001 and

BB-HV-F002 are open), and can be read on

the Control Room recorder B21-TRR614

point 24, Reactor Head Vent. D. Loss of S/D Cooling AND RCS temp. < 200 o F AND RCS temp. is anticipa

ted to reach 200 o F.

Date/Time:

___ An unexplained increase in Drywell leakage could be indicative of the presence of steam flow out of the vessel head and into the

Drywell. This parameter is monitored at RMS and includes primarily t he Drywell Equipment Drain flow, however, steaming into the

Equipment Drain Sump could also be

indicated by total Drywell leakage and

Drywell Cooler condensate flow, therefore, all of these points should be monitored for

unexplained increases.

2. IF in IO-0004, IO-0005, or IO-0009, the asso ciated attachment for "PLACING THE PLANT IN ALTERNATE DECAY HEAT REMOVAL MODE OF OPERATION" MAY identify an effective mode of Al ternate Decay Heat Removal.

Procedures: HC.OP-IO.ZZ-0004(Q) SHUTDOWN FROM RATED POWER TO COLD SHUTDOWN HC.OP-IO.ZZ-0005(Q) COLD SHUTDOWN TO REFUELING HC.OP-IO.ZZ-0009(Q) REFUELING OPERATION HC.OP-DL.ZZ-0026(Q) SURVEILLANCE LOG HC.OP-SO.EC-0001(Q) FUEL POOL COOLING AND CLEANUP SYSTEM HC.OP-SO.BG-0001(Q) REACTOR WATER CLEANUP SYSTEM OPERATION

Valves: 1-ED-V035 RWCU NRHX RACS RTN PLUG. (Rm 4504E).

___ ___ E.1 temperatures IAW DL-0026 s.

___ ___ E.2 RPV LVL 80 inches, BUT < 90 inches. ___ E.3IF RPV LVL reaches 90 inches, THEN the MSIV's.

___ E.4 T.S. cool down limits are not exceeded.

E.5 the following systems for alternate decay heat removal:

___ RWCU (Condition F)

___ "C" RHR (Attachment 2)

___ "D" RHR (Attachment 3)

___ Condensate Transfer (Condition G) E.6IF the vessel head is removed, AND the Reactor Cavity is flooded, THEN maximize Fuel Pool Cooling:

___ two Fuel Pool Cooling pumps are in service. (EC) E. Forced Circulation CANNOT be established using preferred

RHR loops or Reactor

Recirculation.

Date/Time:

___ SACS flow aligned through BOTH Fuel Pool Cooling heat exchangers.

___ F.1 RWCU is in service. (BG)

___ F.2 ED-V035. F. RWCU is required for Alternate Decay Heat Removal. ] Date/Time:

___ F.3 IF necessary, THEN Bypass the Regenerative heat exchanger to maximize decay heat removal. (BG)

Procedures: HC.OP-SO.AP-0001(Q) CONDENSATE TRANSFER SYSTEM OPERATION HC.OP-SO.BG-0001(Q) REACTOR WATER CLEANUP SYSTEM OPERATION

'A' RHR 1-AP-V044 (Rm. 4328) N/A BC-HV-F017A 'C' RHR 1-AP-V047 (Rm. 4328) N/A BC-HV-F017C 'B' RHR 1-AP-V056 (Rm 4322B) N/A BC-HV-F017B 'D' RHR 1-AP-V059 (Rm.

4322B) N/A BC-HV-F017D 'A' CORE SPRAY 1-AP-V041 (Rm. 4331) BE-HV-F004A BE-HV-F005A 'B' CORE SPRAY 1-AP-V062 (Rm.

4322B) BE-HV-F004B BE-HV-F005B HPCI 1-AP-V038 (Rm. 4331) N/A BJ-HV-8278 RCIC 1-AP-V052 (Rm. 4315) N/A BD-HV-F013

___ G.1 Condensate Transfer is in-service. (AP)

___ G.2 RWCU is in-service. (BG)

___ G.3 to Table G and align one of the following flowpaths to feed the vessel from

condensate transfer as follows: G.4 IF an RHR injection line will be used, THEN the following:

___ a. the desired loops INJECTION

VALVE listed in Table G.

___ b. OPEN the associated CS XFR DISCH ISLN listed in Table G to

obtain the desired injection rate. G.5 IF a Core Spray injection line will be used, THEN the following:

___ a. the desired loops OUTBD ISOL VLV listed in Table G.

___ b. the associated INJECTION

VALVE listed in Table G.

___ c.

the OUTBD ISOL VLV.

___ d. OPEN the associated CS XFR DISCH ISLN listed in Table G to

obtain the desired injection rate. G. Condensate Transfer is required for S/D cooling.

Date/Time:

3. Reactor pressure must be below the Low Pr essure Isolation setpoint for the system to prevent auto-closure of the injection valve. 4. Depressing the CLOSE push-button for HV-F 032A(B) will ensure the motor actuator is in the closed position and HV-F032A(B) remains closed.

Procedures: HC.OP-SO.BG-0001(Q) REACTOR WATER CLEANUP SYSTEM OPERATION

Valves:

AE-HV-F032A FW INLET CHECK VALVE AE-HV-F032B FW INLET CHECK VALVE AE-HV-F011A A FW SUPPLY LINE INBOARD ISOLATION VALVE AE-HV-F011B B FW SUPPLY LINE INBOARD ISOLATION VALVE

'A' RHR 1-AP-V044 (Rm. 4328) N/A BC-HV-F017A 'C' RHR 1-AP-V047 (Rm. 4328) N/A BC-HV-F017C 'B' RHR 1-AP-V056 (Rm 4322B) N/A BC-HV-F017B 'D' RHR 1-AP-V059 (Rm.

4322B) N/A BC-HV-F017D 'A' CORE SPRAY 1-AP-V041 (Rm. 4331) BE-HV-F004A BE-HV-F005A 'B' CORE SPRAY 1-AP-V062 (Rm.

4322B) BE-HV-F004B BE-HV-F005B HPCI 1-AP-V038 (Rm. 4331) N/A BJ-HV-8278 RCIC 1-AP-V052 (Rm. 4315) N/A BD-HV-F013

___ G.6 IF the RCIC injection line will be used, THEN the following:

___ ___ a.

reactor pressure < 64 psig

___ ___ b.

HV-F032B CLOSE Pb AND the HV-F032B is CLOSED. ___ c. HV-F011B is OPEN.

___ d. the NORM/BYPASS keylock switch for the HV-F013 in BYPASS.

___ e. the HV-F013.

___ f. OPEN the 1-AP-V052 to obtain the desired injection rate. G.7 IF the HPCI injection line will be used, THEN the following:

___ ___ a.

reactor pressure < 100 psig

___ ___ b.

HV-F032A CLOSE Pb AND the HV-F032A is CLOSED. ___ c. HV-F011A is OPEN.

___ d. the NORM/BYPASS keylock switch for the HV-8278 in BYPASS.

___ e. the HV-8278.

___ f. OPEN the 1-AP-V038 to obtain the desired injection rate. G. Condensate Transfer is required for S/D cooling.

___ G.8 RPV LVL using RWCU Blowdown. (BG)

5. The goal of the following steps is to estab lish water flow through two SRV's with at least a 50# d/p. It is desirable to maintain less than a 160# d/p across the SRV's to ensure a

single LPCI or Core Spray pump can deliver sufficient flow to remove decay heat. Any injection source may be used to flood the vessel, but it is desirable to use the torus as a

suction source for recirculation of water through the vessel and SRVs. This will prevent unnecessary water addition to the torus from outside sources.

Procedures: HC.OP-AB.ZZ-0001(Q) TRANSI ENT PLANT CONDITIONS.

Valves: BB-HV-F001 REACTOR HEAD VENT DRW INBD ISLN BB-HV-F002 REACTOR HEAD VENT DRW OUTBD ISLN BB-HV-F005 REACTOR HEAD VENT STM LINE A AB-HV-F016 CTMT INBD STM LINE DRAIN HDR ISLN OUTBOARD MOV AB-HV-F019 CTMT INBD STM LINE DRAIN HDR ISLN INBOARD MOV FD-HV-F002 HPCI STM INBD ISLN VLV FD-HV-F003 HPCI STM OUTBD ISLN VLV FD-HV-F100 HPCI STM WARMUP VLV FC-HV-F007 RCIC STM INBD ISLN VLV FC-HV-F008 RCIC STM OUTBD ISLN VLV FC-HV-F076 RCIC STM WARMUP VLV

___ ___ H.1 Suppression Pool Cooling IAW AB-0001.

___ H.2 the following Valves are closed.

___ RPV Head Vents.

___ MSIV's.

___ Main Steam Line Drain valves.

___ HPCI Steam Isolations.

___ RCIC Steam Isolations.

___ H.3 the control switches for two SRV's to OPEN (SRVs will not open until a

50# d/p is established).

___ H.4 RPV water level to establish a flow path through the OPEN

SRV's. ___ H.5 all injection into the RPV EXCEPT from CRD.

___ H.6 one Core Spray Subsystem or one LPCI Pump with suction from the

Suppression Pool.

___ H.7 Core Spray

OR LPCI injection into the RPV to maximum. ___ H.8 IF RPV pressure does not stabilize at least 50 psig above suppression chamber

pressure, OR two SRVs are NOT open, THEN and additional Core Spray Subsystem or LPCI pump AND continue to injection flow to establish stated conditions. ___ H.9 IF RPV pressure stabilizes at more than 160 psig above Suppression Chamber pressure, THEN another SRV. H. RPV Temperature and Pressure CANNOT be maintained using Normal OR Alternate Decay Heat Removal.

Date/Time:

___ H.10IF the cooldown rate exceeds 90°F/hr, THEN Core Spray or LPCI injection into the RPV UNTIL EITHER of the following occurs:

___ The cooldown rate drops below 90°F/hr. ___ RPV pressure decreases to within 50 psig of Suppression Chamber

pressure.

H. RPV Temperature and Pressure CANNOT be maintained using Normal OR Alternate Decay Heat Removal. ___ H.11 Suppression Pool temperature to maintain RPV water temperature above

79°F.

1.1 the entry Condition into the abnormal in the Comments Section. ___

1.2 in the comments section all systems affected by the implementation of this procedure AND restoration actions (i.e. restoration line ups) completed/required. ___

1.3 photocopies of any Hard Cards utilized as part of this procedure implementation to Attachment 1. ___

1.4 the Exit time for any applicable conditions and this abnormal are annotated in the comment section AND the Control Room Logs. ___ 1.5 completed Portions of this procedure AND Sections 1.0 and 2.0 of Attachment 1 to SM/CRS for approval and Record Retention. ___

_______________________________________________________________________ _______________________________________________________________________

_______________________________________________________________________

Completion of this attachment is annotated in the Control Room Logs:

Printed Name Signature Date/Time This procedure and Attachment 1 have been reviewed for completeness and accuracy. Entry/Exit conditions and all defic iencies, including corrective actions, are clearly recorded in the COMMENTS Section above. Printed Name Signature Date/Time 4.1 the following in accordance wit h RM-AA-101, Records Management Program: Procedure cover page Affected Conditions and Hard Cards performed Completion and Review section Attachment 1 Attachments 2, 3, 4 if used

Operation of the C to A Cross-Tie is restricted to conditions when reactor coolant temperature is < 300°F (67 psia).

To expedite the establishment of forced core circulation the sequential performance of the following instruction is subject to the discretion of the SM/CRS.

1.1 key for the 1-BC-HS-11496 Keylock Switch from Work Control key cabinet. ___

1.2 the Condensate Transfer System is in service, AND BC-HV-F015A is CLOSED. ___ 1.3 ECCS Jockey pump CP228 from service as follows:

1.3.1. AP-HV-2072 COND STOR & XFR SUPPLY TO RX BLDG is OPEN. ___ 1.3.2. IF required due to low RHR Loop A OR C pressure (D4373, D4397), 1-AP-V044 AND 1-AP-V047 CS Xfr to A And C RHR Pmp Dsch Isln . ___

1.3.3. 1-AP-V041 CS Xfr to A Core Spray Dsch. ___ 1.3.4. CP228 ECCS Jockey Pump. ___ 1.4 1BC-V203 ECCS Jock Pmp C Suct Vlv (Rm. 4114C). ___ 1.5 the following valves: HV-F004A RHR PMP A SUPP POOL SUCT MOV ___ HV-F004C RHR PMP C SUPP POOL SUCT MOV ___

1.6 the following valves are CLOSED: HV-F007A RHR PMP A MIN FL VLV. ___ HV-F007C RHR PMP C MIN FL VLV. ___

1.7 the following LPCI Injection Valves are CLOSED: HV-F017A RHR LOOP A LPCI INJ MOV ___ HV-F017C RHR LOOP C LPCI INJ MOV ___

1.8 the following valves: HV-F010A RHR LOOP C TEST RET MOV ___ HV-F024A RHR LOOP A TEST RET MOV ___ HV-F021A RHR LOOP A SPRAY ISLN MOV ___ HV-F027A RHR LOOP A SUPP CHAMBER SPRAY HDR ISLN MOV ___

1.9 Fully 1BC-V133 RHR Pmp C Suct Frm Recir Loop B (Rm 4227E). ___

1.10 IF the SDC suction line is NOT isolated, THEN the SDC suction line from the following until a solid stream of water is observed: 1.10.1. 1-BC-V284 AND 1-BC-V285 ___ 1.10.2. 1-BC-V165 AND 1-BC-V166 ___ 1.11 HV-F077 RECIRC LOOP B TO RHR SUP MAN VLV is open. ___ 1.12 IF the Shutdown Cooling suction line was isolated, THEN a fill and vent IAW HC.OP-SO.BC-0002(Q), Decay Heat Removal Operation. ___

1.13 the following valves are open: HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV ___ HV-F009 SHUTDOWN COOLIN G INBD ISLN MOV. ___ 1.14 AND 1BC-V571 RHR Cross-Tie Isolation Valve for C Loop BC-HV-11673. (Rm 4114A) ___ 1.15 IF Fill and Vent has been performed within 30 days on the A RHR Crosstie Isolation THEN

to Step 1.19. ___ 1.16 the following valves until a solid stream of water issues, THEN (Local): 1BC-V578 AND 1BC-V579 RHR Vent Valves (Rm. 4113A) ___ 1BC-V580 AND 1BC-V581 RHR Vent Valves (Rm. 4114A) ___ 1.17 1BC-V570 RHR Cross-Tie Isolation Valve for A Loop (Rm. 4113A) ___ 1.18 1BC-578 and 1BC-V579 RHR Vent Valves until a solid

stream of water issues, THEN (Rm. 4113A) ___

1.19 1BC-V570 RHR Cross-Tie Isolation Valve for A Loop (Rm. 4113A) ___

1.20 IF OPENED in Step 1.3.2, 1-AP-V044 AND 1-AP-V047 CS Xfr to A and C RHR Pmp Dsch Isln . ___

The interlock override will allow C RHR Pump to operate when the pump is aligned to the alternate suction from the RPV, when and if required.

In the cross-tie mode, C RHR Pump will not be automatically protect ed against the loss of

suction from the RPV.

1.21 At Panel 10C641 perform the following:

1.21.1.

the key obtained in Step 1.1 in the 1-BC-HS-11496 Keylock Switch. ___

1.21.2. the HV-F004C Valve/Pump C Interlock using the 1-BC-HS-11496 Keylock Switch. ___

1.21.3. in Control Room Narrative Log the position of the Keylock Switch. ___

1.22 IF during the cross-tie operation mode, the HV-F008 or HV-F009 close (e.g., on RPV Low Level 3 signal),

THEN IMMEDIATELY the C RHR Pump AND corrective action. ___

1.23 IF HV-F015A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV does NOT open immediately to establish flow, THEN the RHR Pump. ___

1.24 RHR PUMP CP202 and immediately HV-F015A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV until FI-R603C LOOP C FLOW indicates 3000 gpm. ___ AI-6358C PUMP C MOT AMPS. ___

flow of 3000 gpm for at least 10 minutes. ___

1.25 HV-F015A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV until FI-R603C LOOP C FLOW indicates 10,000 gpm OR 7000 gpm as required by plant conditions ( Caution). ___

1.26 the following Breakers OPEN AND Valves as listed IAW OP-AA-109, Safety Tagging Program: Breaker 52-232074 ECCS Jockey Pump CP228 ___ 1BC-V203 ECCS Jock Pmp C Suct Vlv (CLOSED) ___ Breaker 52-212031 HV-F004A RHR PMP A SUPP POOL SUCT MOV ___ Breaker 52-232031 HV-F004C RHR PMP C SUPP POOL SUCT MOV ___ Breaker 52-212041 HV-F007A RHR PMP A MIN FL VLV ___ Breaker 52-232041 HV-F007C RHR PMP C MIN FL VLV ___ Breaker 52-212052 HV-F017A RHR LOOP A LPCI INJ MOV ___ Breaker 52-232052 HV-F017C RHR LOOP C LPCI INJ MOV ___ Breaker 52-232044 HV-F010A RHR LOOP C TEST RET MOV ___ Breaker 52-212192 HV-F024A RHR LOOP A TEST RET MOV ___ Breaker 52-451062 HV-F021A RHR LOOP A SPRAY ISLN MOV ___ Breaker 52-212083 HV-F027A RHR LOOP A SUPP CHAMBER SPRAY HDR ISLN MOV ___ 1BC-V133 RHR Pmp C Suct Frm Recir Loop B (OPEN) ___

2.1 HV-F015A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV. ___ 2.2 WHEN the HV-F015A RHR LOOP A RET TO RECIRC LOOP A ISLN MOV is closed, THEN the C RHR Pump CP202. ___

2.3 IF required due to low RHR Loop A OR C pressure (D4373, D4397), 1-AP-V044 AND 1-AP-V047 CS Xfr to A And C RHR Pmp Dsch Isln . ___

2.4 1-BC-HS-11496 Keylock Switch from the OVERRIDE position. ___

2.4.1. the key from 1-BC-HS-11496 Keylock Switch AND the key to the Work Control key cabinet. ___ 2.4.2. in Control Room Narrative Log the position of the keylock switch. ___ 2.5 1BC-V570 RHR Cross-Tie Isolation Valve for A Loop (Rm. 4113A). ___ 2.6 AND 1BC-V571 RHR Cross-Tie Isolation Valve for C Loop BC-HV-11673. (Rm 4114A) ___ 2.7 tags from 1BC-V203 ECCS Jock Pmp C Suct Vlv (Rm. 4114C) AND valve. ___ 2.8 tags from 1BC-V133 RHR Pmp C Suc Frm Recir Loop B. (Rm 4227E) ___ 2.9 AND 1BC-V133 RHR Pmp C Suc Frm Recir Loop B (Rm 4227E) ___

2.10 the following valves: HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV ___ HV-F009 SHUTDOWN COOLING INBD ISLN MOV ___

2.11 the tags from the following valves: HV-F017A RHR LOOP A LPCI INJ MOV ___ HV-F017C RHR LOOP C LPCI INJ MOV ___ HV-F010A RHR LOOP C TEST RET MOV ___ HV-F024A RHR LOOP A TEST RET MOV ___ HV-F021A RHR LOOP A SPRAY ISLN MOV ___ HV-F027A RHR LOOP A SUPP CHAMBER SPRAY HDR ISLN MOV ___ 1BC-HV-F007A RHR PMP 1AP202 MIN FL BYP. ___ 1BC-HV-F007C RHR PMP 1CP202 MIN FL BYP. ___ 2.12 tags from HV-F004A AND HV-F004C RHR PMP SUPP POOL SUCT MOVs. ___

2.13 HV-F004A AND HV-F004C, RHR PMP SUPP POOL SUCT MOVs are OPEN. ___

2.14 ECCS Jockey pump CP228 to service as follows:

2.14.1. tags from Jockey Pump CP228. ___ 2.14.2.

CP228 ECCS Jockey Pump. ___ 2.14.3. 1-AP- V041 CS Xfr to A Core Spray Dsch. ___ 2.14.4. IF OPENED 1-AP-V044 AND 1-AP-V047 CS Xfr to A and C RHR Pmp Dsch Isln. ___ 2.15 system as plant conditions require. ___

Operation of the D to B Cross-Tie is restricted to conditions when reactor coolant temperature is < 300°F (67 psia).

To expedite the establishment of forced core circulation the sequential performance of the following instruction is subject to the discretion of the SM/CRS.

1.1 key to the 1-BC-HS-11682 Keylock Switch from Work Control key cabinet. ___

1.2 the Condensate Transfer System is in service AND BC-HV-F015B is CLOSED. ___ 1.3 ECCS Jockey pump DP228 from service as follows:

1.3.1. AP-HV-2072 COND STOR & XFR SUPPLY TO RX BLDG is OPEN. ___ 1.3.2. IF required due to low RHR Loop B OR D pressure (D4385, D4404), 1-AP-V056 AND 1-AP-V059 CS Xfr to B and D RHR Pmp Dsch Isln . ___

1.3.3. 1-AP- V062 CS Xfr to B Core Spray Dsch. ___ 1.3.4. DP228 ECCS Jockey Pump. ___ 1.4 1BC-V261 ECCS Jockey Pump D Suction Valve. ___ 1.5 the following valves: HV-F004B RHR PMP B SUPP POOL SUCT MOV ___ HV-F004D RHR PMP D SUPP POOL SUCT MOV ___

1.6 the following valves are CLOSED: HV-F007B RHR PUMP B MIN FLOW VLV ___ HV-F007D RHR PUMP D MIN FLOW VLV ___

1.7 the following LPCI Injection Valves are closed: HV-F017B RHR LOOP B LPCI INJ MOV ___ HV-F017D RHR LOOP D LPCI INJ MOV ___

1.8 the following valves: HV-F010B RHR LOOP D TEST RET MOV ___ HV-F024B RHR LOOP B TEST RET MOV ___ HV-F021B RHR LOOP B SPRAY ISLN MOV ___ HV-F027B RHR LOOP B SUPP CHAMBER SPRAY HDR ISLN MOV ___ 1.9 FULLY 1BC-V043 RHR Pmp D Suc Frm Recir Loop B (Rm. 4227D; Az 150 above catwalk) ___

1.10 IF the SDC suction line is NOT isolated, THEN the SDC suction line from the following until a solid stream of water is observed: 1.10.1. 1-BC-V284 AND 1-BC-V285 ___ 1.10.2. 1-BC-V165 AND 1-BC-V166 ___ 1.11 HV-F077 RECIRC LOOP B TO RHR SUP MAN VLV is OPEN. ___

1.12 IF the Shutdown Cooling suction line was isolated, THEN

a fill and vent IAW HC.OP-SO.BC-0002(Q), Decay Heat Removal Operation. ___

1.13 the following valves are open: HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV ___ HV-F009 SHUTDOWN COOLING INBD ISLN MOV. ___

1.14 AND 1BC-V601 RHR Crosstie Iso Vlv B LOOP BC-HV-11680 MOV (Rm. 4107A) ___ 1.15 IF a Fill and Vent has been performed within 30 days on the B RHR Crosstie Isolation THEN

to Step 1.19. ___ 1.16 the following valves until a solid stream of water issues, THEN (Local). 1BC-V610 and 1BC-V611 RHR B&D Loop X-Tie Vent Vlvs (Rm. 4107A) ___ 1BC-V608 and 1BC-V609 RHR B&D Loop X-Tie Vent Vlvs (Rm. 4107A) ___

1.17 1BC-V600 RHR X-Tie Iso Vlv Loops B&D. (Rm.

4107A) ___ 1.18 1BC-V608 and 1BC-V609 RHR B&D Loop X-Tie Vent Vlvs

until a solid stream of water issues, THEN (Rm. 4107A) ___

1.19 1BC-V600 RHR X-Tie Iso Vlv Loops B&D. (Rm. 4107A) ___ 1.20 IF OPENED in Step 1.3.2, 1-AP-V056 AND 1-AP-V059 CS Xfr to B and D RHR Pmp Dsch Isln . ___

The interlock override will allow D RHR Pump to operate when the pump is aligned to the alternate suction from the RPV, when and if required.

In the Cross-Tie mode, D RHR Pump will not be aut omatically protected against the loss of suction from the RPV.

1.21 the following at Panel 10C640:

1.21.1.

the key obtained in Step 1.1 in the 1-BC-HS-11682 Keylock Switch. ___

1.21.2. the HV-F004D Valve/Pump D Interlock using the 1-BC-HS-11682 Keylock Switch. ___

1.21.3. in Control Room Narrative Log the position of the Keylock Switch. ___

1.22 IF during the cross-tie operation mode, the HV-F008 or HV-F009 close (e.g., on RPV Low Level 3 signal),

THEN immediately the D RHR Pump AND corrective action. ___ 1.23 IF HV-F015B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV does not open immediately to establish flow, THEN the RHR Pump. ___

1.24 RHR PUMP DP202 and immediately HV-F015B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV UNTIL FI-R603D LOOP D FLOW indicates 3000 GPM. ___ AI-6358D PUMP D MOT AMPS. ___

flow of 3000 gpm for at least 10 minutes. ___

1.25 HV-F015B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV UNTIL FI-R603D LOOP D FLOW indicates 10,000 gpm OR 7000 gpm as required by plant conditions ( Caution). ___

1.26 the following Breakers OPEN AND Valves as listed IAW OP-AA-109, Safety Tagging Program: Breaker 52-242074 - Jockey Pump DP228 ___ 1BC-V261 - ECCS Jockey Pump D Suction Valve (CLOSED) ___ Breaker 52-222031 - HV-F004B RHR PMP B SUPP POOL SUCT ___ Breaker 52-242031 - HV-F004D RHR PMP D SUPP POOL SUCT ___ Breaker 52-222041 - HV-F007B RHR PUMP B MIN FLOW VLV ___ Breaker 52-242041 - HV-F007D RHR PUMP D MIN FLOW VLV ___ Breaker 52-222052 - HV-F017B RHR LOOP B LPCI INJ ___ Breaker 52-242052 - HV-F017D RHR LOOP D LPCI INJ ___ Breaker 52-242044 - HV-F010B RHR LOOP D TEST RET ___ Breaker 52-222063 - HV-F024B RHR LOOP B TEST RET ___ Breaker 52-222062 - HV-F021B RHR LOOP B SPRAY ISLN ___ Breaker 52-222083 - HV-F027B RHR LOOP B SUPP CHAMBER SPRAY HDR ISLN ___ 1BC-V043 - RHR Pmp D Suc Frm Recir Loop B (OPEN) ___

2.1 HV-F015B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV. ___ 2.2 WHEN the HV-F015B RHR LOOP B RET TO RECIRC LOOP B ISLN MOV is closed, THEN the D RHR Pump DP202. ___

2.3 IF required due to low RHR Loop B OR D pressure (D4385, D4404), 1-AP-V056 AND 1-AP-V059 CS Xfr to B and D RHR Pmp Dsch Isln ___ 2.4 1-BC-HS-11682 Keylock Switch from the OVERRIDE position. ___

2.4.1. the key from 1-BC-HS-11682 Keylock Switch AND to the Work Control key cabinet. ___ 2.4.2. in Control Room Narrative Log the position of the Keylock Switch. ___ 2.5 1BC-V600 RHR X-Tie Iso Vlv Loops B&D. (Rm. 4107A) ___ 2.6 AND 1BC-V601 RHR Crosstie Iso Vlv B LOOP BC-HV-11680 MOV (Rm. 4107A) ___

2.7 tags from 1BC-V261 ECCS Jockey Pmp D Suct Vlv (Rm. 4107D) AND valve. ___ 2.8 tags from 1BC-V043 RHR Pmp D Suc Frm Recir Loop B. (Rm. 4227D; Az 150 above catwalk) ___ 2.9 AND 1BC-V043 RHR Pmp D Suc Frm Recir Loop B. (Rm. 4227D; Az 150 above catwalk) ___

2.10 the following valves: HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV ___ HV-F009 SHUTDOWN COOLING INBD ISLN MOV ___

2.11 the tags from the following valves/breakers: HV-F017B RHR LOOP B LPCI INJ MOV ___ HV-F017D RHR LOOP D LPCI INJ MOV ___ HV-F010B RHR LOOP D TEST RET MOV ___ HV-F024B RHR LOOP B TEST RET MOV ___ HV-F021B RHR LOOP B SPRAY ISLN MOV ___ HV-F027B RHR LOOP B SUPP CHAMBER SPRAY HDR ISLN MOV ___ 1BC-HV-F007B RHR PMP 1BP202 MIN FL BYP. ___ 1BC-HV-F007D RHR PMP 1DP202 MIN FL BYP. ___ 2.12 tags from HV-F004B AND HV-F004D RHR PMP SUPP POOL SUCT MOV. ___

2.13 HV-F004B AND HV-F004D, RHR PMP SUPP POOL SUCT MOVs are OPEN. ___

2.14 ECCS Jockey pump DP228 to service as follows:

2.14.1. tags from Jockey Pump DP228. ___ 2.14.2.

DP228 ECCS Jockey Pump. ___ 2.14.3. 1-AP- V062 CS Xfr to B Core Spray Dsch. ___ 2.14.4. IF OPENED 1-AP-V056 AND 1-AP-V059 CS Xfr to B and D RHR Pmp Dsch Isln . ___ 2.15 system as plant conditions require. ___

1.1 1.1.1. RHR system was flushed and in service within the past 7 days. ___ 1.1.2. Reactor Coolant Temperature is < 200°F. ___ 1.1.3. IF an isolation condition was received, the cause of the isolation is clear. ___

1.2 1.2.1. prerequisites are complete. ___ 1.2.2. IF the BC-HV-F008 and BC-HV-F009 are closed, the following:

A. isolation condition is clear. ___

B.

NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM TRIP LOGIC A RESET

AND TRIP LOGIC D RESET PBs. ___ 1.2.3. the following valves are closed: BC-HV-F009 SHUTDOWN COOLING INBD ISLN MOV. ___ BC-HV-F008 SHUTDOWN COOLING OUTBD ISLN ___ BC-HV-F006A(B) RHR PMP A(B) SUCT FROM RECIRC ___ BC-HV-F015A(B) RHR LOOP A(B) RET TO RECIRC ___ BC-HV-F004A(B) A(B) RHR PMP SUPP POOL SUCT MOV. ___ BC-HV-F007A(B) RHR PMP A(B) MIN FLOW MOV ___ BC-HV-F024A(B) RHR LOOP A(B) TEST RET MOV ___ BC-HV-F040 RHR LOOP B DSCH TO LIQ RW ISLN MOV ___ BC-HV-F049 RHR LOOP B DSCH TO LIQ RW ISLN MOV. ___

1.2.4. BC-HV-F006A(B) RHR PMP A(B) SUCT FROM RECIRC ___

1.2.5. BC-HV-F008 SHUTDOWN COOLING OUTBD ISLN MOV Keylock Switch HS-11495 in the ARMED position

(10B242 Bkr 242082). ___ 1.2.6. BC-HV-F008 SHUTDOWN COOLING OUTBD ISLN ___ The Condensate Transfer header pressure should be controlled while completing Step 1.2.7 thru 1.2.8.F by using only 1 Condensate Transfer Jockey pump. Condensate usage should be minimized during this period thru coordination with potential condensate users (i.e.,

Chemistry, Radwaste, Operations etc.).

1.2.7.

the following Condensate Storage and Transfer pumps and Refueling Water Pump in STOP (Local Panel

00C113): (Refueling Water Pump hand-switch is a spring

return to normal switch)

A. HS-2061A CNDS TRANSFER PUMP 0AP155 MOTOR ___

B. HS-2061B CNDS TRANSFER PUMP 0BP155 MOTOR ___

C. HS-2063A OR B CNDS JKY XFR PUMP 0B(A)P156 MOTOR (whichever Jky Pmp is NOT in lead on

HSS-2063) ___

D. HS-2054A-2 REFUEL WATER PUMP 0AP157 ___

1.2.8. IF there is any reason to believe the SDC Suction header was drained OR voided, the following: IF pressure control valve is not able to main tain pressure at 140 psig, throttle 1-AP-V017 condensate transfer pressure control inlet isolation valve to maintain 140 psig.

A.

PIC-2044A CNDS XFR PUMPS DISCHARGE PRESS controller to ~ 140 psig (Local Panel 00C113) ___

B.

AND 1-AP-V048 COND STOR &

XFR TO RHR B SUCT HDR FILL & FLUSH ISLN VLV (local). ___

C.

AND SLOWLY 1-BC-V191 Cond Stor & Xfr to Recirc Suct. ___

D. the Shutdown Cooling Suction piping for a minimum of 5 minutes using the following valves: 1-BC-V165, Recirc Loop B to RHR Vnt Isln (North Pipe Chase) ___ 1-BC-V166, Recirc Loop B to RHR Vnt (North Pipe Chase) ___

E. the following vent valves are returned to their required positions:

1-BC-V165 CLOSED AND LOCKED ___ 1-BC-V166 CLOSED ___

F. AND 1-BC-V191 ___ G. AND 1-AP-V048 (local) ___ 1.2.9. BC-HV-F009 SHUTDOWN COOLING INBD ISLN MOV. ___

1.2.10.

the A(B)P202 RHR PUMP AND IMMEDIATELY BC-HV-F015A(B) RHR LOOP A(B) RET TO RECIRC UNTIL FI-R603A(B) or FR-R608A(B) -

CRIDS A3137(A3139), LOOP A(B) FLOW indicates " 3000

gpm. [CD-133B, CD-177E] ___ 1.2.11.

1-AP-V017. ___ 1.2.12. AI-6358A(B) PUMP A(B) MOT AMPS. ___ 1.2.13.

RHR Loop in shutdown cooling at " 3000 gpm as indicated on FI-R603A(B) or FR-R608A(B) -

CRIDS A3137(A3139), LOOP A(B) FLOW, for " 3 minutes. ___ 1.2.14. WHEN conditions of Step 1.2.13 have been satisfied, THEN ,

the following:

A. BC-HV-F015A(B) RHR LOOP A(B) RET TO

RECIRC UNTIL FI-R603A(B) or FR-R608A(B) -

CRIDS A3137(A3139), LOOP A(B) FLOW indicates required flow. ___

Adds Step 1.10 to Attachments 2 and 3 to vent prior to placing decay heat removal in service. This was reviewed in the DCP and is editorial. (80097565-0220) Adds / moves Steps 2.13 and 2.14 on A ttachments 2 and 3 to ensure the RHR pump suctions are open and restore the ECCS jockey pumps to service. (70093469-0020) Adds Step A.3 to ensure NSSSS is reset. (70105939-0010)

LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling

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LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling

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