Text

Salem/Operations, S2.OP-AB.RHR-0001(Q), Rev. 17, Loss of Rhr
	ML110060779
Person / Time
Site:	Salem
Issue date:	03/12/2008
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
References
	LR-N10-0355 S2.OP-AB.RHR-0001(Q), Rev 17
	Download: ML110060779 (114)
	v • d • e

{{#Wiki_filter:PSEG Internal Use Only PSEG NUCLEAR L.L.C. SALEM/OPERATIONS S2.0P-AB.RHR-0001(Q) - REV. 17 LOSS OFRHR Biennial Review Performed: Yes No L Page 1 ofl Change Package(s) and Affected Document Number(s) incorporated into this revision: None The following OTSC(s) were incorporated into this Revision: None REVISION

SUMMARY

The following changes were incorporated into this revision: Revised procedure to reflect instal1ation of a Equipment Hatch Ventilation Bruner (EHVB). to be utilized in lieu of the Outage Equipment Hatch (OEH). This change is being incorporated to support replacement of the Steam Generators IA W DCP 80083522, and is consistent with guidance delineated in Engineering Calculation S-2-RC-MDC-2151, Containment Closure in Modes 5 and 6 During Steam* Generator Replacement. Utilization ofthe Equipment Hatch Ventilation Barrier (EHVB) to fulfill the requirements for Containment Closure is only allowed during Refueling Outage 2R16 in order to support replacement of the Steam Generators IA W S-2-RC-MDC-21S1, Containment Closure in Modes 5 and 6 During SG Replacement. Affected steps and attachments include; Step 3.32, CAS 4.0 and 6.0, Attachment 14, and Technical Basis Document for Attachment 4 and 14. [80094905-01701 IMPLEMENTATION REQUIREMENTS Effective Date: O~ l'2../ZOO:> None

S2.0P-AB.RHR-0001(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure IA W S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable Attaclunent:

, Steam Generator Reflux Cooling

+ 0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%, THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND. Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures if RHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 1 of 100 [C0330] [C03S4] Rev. 17

82.0 P-AB,RHR~OOOI (Q) LOSSOFRHR 1.0 ENTRY CONDITIONS DATE: TIME: -- 1.1 Any indication of loss or reduction in RHR System cooling. 2.0 IMMEDIATE ACTIONS 2.1 None 3.0 SUBSEQUENT ACTIONS 3.1 INITIATE Attachment 1, Continuous Action Summary. 3.2 IF the RCS is vented to the Contairunent atmosphere with the Containment Equipment hatch OPEN AND at least two RCS loops are fi11ed with associated SG's available, THEN CLOSE the vent path prior to Core Boil. (Refer to Attachment 4) NOTE 0% Pressurizer Level Cold Cal. indication corresponds to 108.92 ft. elevation, when the RCS is filled and vented. 3.3 Is ReS aligned for operation <101 ft. elevation (Reduced Inventory)? YES NO--> I GO TO Step 3.5 V 3.4 GO TO S2.0P~AB.RHR~0002(Q), Loss ofRHR at Reduced Inventory. 3.5 Is the loss ofRHR due to a mechanical failure or loss of electrical power to the in-service RHR Pump? YES ) NO--> GO TO Step 3.7 V 3.6 GO TO Step 3.50 Salem 2 Page 2 of 100 Time Time Time Rev. 17

S2.0P-AB.RHR-OOOl(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alann annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss of RCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Themlocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 3 of 100 [C0330J [C03S4} Rev. 17

S2.0P-AB~RHR-OOOl(Q) 3.7 CHECK RHR cooling availability as follows: A. Is any RHR pump running? YES I NO--> GO TO Step 3.9 Time V NOTE 0% Pressurizer Level Cold Cal. indication corresponds to 108.92 ft. elevation when the ReS is filled and vented. 3.8 Salem 2 B. Is ReS level >97.5 ft elevation AND stable OR rising consistent with YES 1 V C. D. YES I V current RCS makeup (Charging, SI) in progress AND no excessive indication ofRCS leakage? NO--> GO TO Step 3.8 REDUCE RHRflowto 1500 -1800 gpm. Are RHR Pumps cavitating or gas bound as indicated by any of the following? + RHR motor amps low or oscillating + RHR flow low or oscillating + Report of abnonnal noise or pump damage + RHR discharge pressure fluctuating + RHR Suction pressure fluctuating NO--> GO TO Step. 3.54 Time Time STOP running RHR Pumps. [C0354] Page 4 of 100 Rev. 17 .1

S2.0P~AB.RHR-OOOl (Q) SELECTED CAS ITEMS* IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

.., Steam Generator Reflux Cooling .. 0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alann annunciates AND Containment Sump level exceeds 62%, THEN ALIGN intact RHR train( s) to Contaimnent Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss of RCS inventory occurs AND AttacIunent 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thennocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0p*AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 5 of 100 [C0330] [C0354] Rev. 17

S2.0P-AB.RHR-OOOl(Q) 3.9 PERFORM the following: STOP 2 RHR Letdown Booster Pump ISOLATE Sampling activities ISOLATE Nonna} Letdown to CVCS ISOLATE Excess Letdown ISOLATE RHRLetdown to CVCS TERMINATE any known maintenance or testing in progress 3.10 DETERMINE time to core boiling using Attachment 4, Time To Reach Boiling After Loss ofRHR OR Attachment 5, Heatup Rate For Loss OfRHR Cooling, as applicable. 3.11 Is RCS level >97.5 ft elevation AND stable OR rising consistent with current RCS makeup (Charging, S1) AND no excessive indication ofRCS Leakage? YES I NO--> GO TO Step 3.34 V 3.12 Does the time to core boiling allow adequate time for normal restoration AND local venting ofRHR System? YES I NO--> GO TO Step 3.20 V 3.13 Is any RHR Pump available as indicated by all of the following? Power available to at least one RHR Pump RHR Suction and Discharge valves open

2RHl (RHR COMMON SUCTION VALVE)
2RH2 (RHR COMMON SUCTION VALVE)
RH4 (PUMP SUCTION VALVE)
SJ49 (RHR COLD LEG ISOLATION VALVE)

Component Cooling available to RHR System (step continued on next page) Salem 2 Page 6 of 100 Time Time [C0329] Rev. 17

S2.0P-AB,RHR-OOOl CQ) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOICQ), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

.., Steam Generator Reflux Cooling .. 0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%, THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TI1vfE a loss of RCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Them10couple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 7 or100 [C0330] [C03S4] Rev. 17

82.oP-AB.RHR-OOOl(Q) 3.13 (continued) Service Water System available as heat sink YES NO--> GO TO Step 3.30 I V CAUTION Venting the RHR system may cause a reduction in ReS level requiring more makeup flow rate. Any opening in the ReS boundary could result in release of high temperature fluids, radioactive water, or gases to Con.tainment. Opening 2SJ69 aligns the RWST to RHR and may result in RCS level rise. 3.14 VENT RHR Pumps and piping as follows: A. ISO LATE RHR Suction from RCS by closing 2RH2 OR 2RH 1. (2RH2 is preferred, 2RHl is a backup) B. IF air supplies to 21RH18 and 22RH18 are isolated, THEN ALIGN air to 21RH18 and 22RH18 as follows: OPEN 21RH18-AlS, LOCAL AlS TO 21RH18 OPEN 22RH18-AlS. LOCAL AlS TO 22RH18 C. THROTTLE OR CLOSE 21RH18, 22RH18, and 2RH20 as required to control RCS inventory. D. ENSURE 2RP41ockout switch for 2SJ69, RHR SUCTION FROM RWST, in VALVE OPERABLE. (Control Room) E. OPEN 2SJ69, RHR SUCTION FROM RWST. (Control Room) (continued on next page) Salem 2 Page 8 oflOO Time [C0329] [C0658] Rev. I?

S2.0P-AB.RHR-0001(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-0001(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown "IF AT ANY TIME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 QR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thennocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 9 of100 [C0330] [C0354] Rev. 17

S2.0P-AB.RHR-OOOl(Q) 3.14 (continued) F. Send Operators to PERFORM the following:

1.

OPEN 2RH81 AND 2RH82, RHR Suction Line second high point vent, until steady stream of water flows (mechanical penetration area 78 1 elevation).

2.

IF the bioshield area inside containment is accessible, THEN OPEN 2RH68 AND 2RH69, RHR Suction Line first high point vent, until steady stream of water flows.

3.

MONITOR RHR Pump in preparation for pump start. O. CLOSE 2SJ69, RHR Suction From RWST. H. OPEN 2RHl AND 2RH2, RHR Suction from ReS.

1.

Notify Operator in RHR Pump area to MONITOR the pump for abnormal conditions after the pump is started. J. RAISE* makeup flow to RCS to prevent level drop as voids collapse. CAUTION Changes in ReS pressure or voiding In the Reactor Coolant System may result in inaccuracies in Res level indication. Lower flow rates when starting RHR Pumps are preferable to limit initial sudden cooldown and to minimize level loss caused b coUa sin voids. 3.15 START one RHR Pump as follows: Salem 2 IF alternate RHR Loop is aligned for BCCS, THEN PERFORM Attachment 2, Aligning RHR Loop From BCCS To Shutdown Cooling. IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling. Page 10 oflOO Rev. 17

S2.0P-AB.RHR-OOOl(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Contaimnent Closure lAW S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown IF AT ANY T1ME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Swnp IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB,LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 11 oflOO [C0330] [C0354] Rev. 17

s2.OP-AB.RHR-OOOI (Q) 3.16 Notify local Operator to PERFORM observation at RHR Pumps: No abnormal noise No seal damage No RHR suction pressure oscillations NOTE 0% Pressurizer Level Cold Cal. indication corresponds to 108.92 ft. elevation, when the RCS is filled and vented. 3.17 Is RHR System normal as indicated by ALL of the following? ReS level- >97.5 ft. elevation AND stable OR rising RHR flow - stable between 1800 AND 3000 gpm ReS temperature - stable or lowering Component Cooling available to RHR System Service Water available as heat sink No local indication ofRHR Pump damage YES I NO--> GO TO Step 3.30 V 3.18 IF an alternate decay heat removal method is established. THEN SECURE the alternate decay heat removal method lAW the Attachment in effect. 3.19 GO TO Section 4.0. Salem 2 Page 12 oft 00 Time Time Rev. 17

S 2.0 P-AB.RHR-OOOI (Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.OP-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME R WST LO Level Alarm annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Contaimnent Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures if RHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 13 of 100 [C0330] [C0354) Rev. 17

S2.0P-AB.RHR-OOOl(Q) 3.20 CONTINUE CAUTION IF adequate time is not available to locally vent RHR Pumps, THEN the fastest way to restore RHR flow is to recover level in the ReS and sw'eep entrained air from the system by operating the system at a relatively high flow rate. 3.21 IS ReS level> 101 ft.? YES NO--> GO TO Step 3.30 I V 3.22 Send an Operator to locally MONITOR RHR Pump while starting. 3.23 START one RHR Pump at full flow as follows: 1F alternate RHR Loop is aligned for BeeS, THEN PERFORM Attachment 2, Aligning RHR Loop From BCeS To Shutdown Cooling. IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling. 3.24 Notify local Operator to PERFORM observation at RHR Pumps: No abnormal noise No seal damage No RHR suction pressure oscillations Time Salem 2 Page 14 of 100 Rev. 17

s2.0 P~AB.RHR-OOOI (Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, --r THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown

+ IF AT ANY TIME RWST LO Level Alann annunciates AND Containment Sump level exceeds 62%, THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13; Cold Leg Re9irculation. + IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one ofthe following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service. CONTROL injection flow to result in lowering Core Exit Themlocouple temperatures if RHR is not available. IF in Mode 4; THEN GO TO S2.0P-AB.LOCA-OOOl (Q); Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 15 oflOO [C0330] IC0354] Rev. 17

s2.OP-AB.RHR-OOOl (Q) 3.25 Is RHR System normal as indicated by ALL of the following? RHR Pumps - at least one running RCS Level- >101 ft. elevation AND stable OR rising RHR Flow - stabilized> 1500 gpm + ReS Temperature - stable or lowering + No local indication of RHR Pump damage YES I NO--> GO TO Step 3.30 V 3.26 ADJUST appropriate RH18 to establish RHR flow as required between 1800 and 3000 gpm to result in stable or lowering Core Exit Thermocouple temperatures. 3.27 STABILIZE ReS level >101 ft., as determined by the SM/CRS. 3.28 IF an alternate decay heat removal method is established, THEN SECURE the alternate decay heat removal method IA W the Attachment in effect. 3.29 GO TO Section 4.0. 3.30 STOP any running RHR Pumps. Salem 2 Page 16 oflOO Time Time Rev. 17

S2,OP-AB,RHR-0001(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-0001(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alann annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures if RHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-0001(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 17 of 100 [C0330] [C0354] Rev. 17

3.31 CONTINUE CAUTION Only Borated water should be added to the RCS to maintain adequate Shutdown Margin. Any opening in the RCS boundary could result in release of high temperature fluids, radioactive water, or gases to Containment. 3.32 INITIATE ~ ofthe alternate methods of decay heat removal:

. Hot Leg Injection (Feed & Bleed ~ Preferred method ifRCS NOT intact or Loops NOT filled AND core exit TCs ;::200°F)

[Attachment 7 is NOT applicable if Attachment 14 has been initiated]

. Cold Leg Injection (Feed & Bleed ~ Preferred Method if Core Exit TCs < 2000P)

[Attachment 8 is NOT applicable if Attachment 14 has been initiated]

, Stearn Generator Reflux Cooling (RCS depressurized AND no other means of decay heat removal is available)
0, Forced Flow Or Natural Circulation Cooldown (RCS intact and filled to greater than 0% in the Pressurizer with Loops filled)
1, Cooling the RCS with Spent Fuel Pool (Reactor Vessel Head Removed) 3.33 NOTIFY 8M/CRS to refer to the following:

Event Classification Guide NOTE [C0609] The ReS may be substituted for one RHR Loop lAW Tech Spec 3.4.1.4#~ provided the following conditions exist: The RCS is filled and vented lAW S2.0P~SO.RC-0003(Q) or S2.0P-SO.RC-0002(Q), with RCS pressure maintained >100 psig. At least two steam generator water levels are mainta[ned ~9% narrow range indication with an Auxiliary Feedwater supply and a vent path available. RVLlS is monitored at least once per shift lAW S2.0P-DL.ZZ~0002(Q). Technical Specifications Salem 2 Page 18 of100 Rev. 17

S2.0P-AB,RHR-OOOl(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump LAW Attachment 13, Cold Leg Recirculation. JF AT ANY TIME a loss of ReS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available. JF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 19 of 100 [C0330} [C03S4J Rev. 17

S2.0P-AB.RHR~000l(Q) 3.34 Is there indication ofRCS leakage as indicated by any of the following? [C03S4} Level rise in the RWST [C0631] Level drop in RCS prior to initiation of alternate decay heat removal methods More frequent Containment Sump pump operation OHA C-26, 21 RHR SUMP OVERFLO alann OHA C-34, 22 RHR SUMP OVERFLO alarm RHR MIDLOOP SYS TRBL OHA D-47 (if installed) Reduced Inventory Instrumentation indicating ReS level loss (RVLIS or Mid-Loop, ifin service) YES NO--> GO TO Step 3.50 I Time V 3.35 ISOLATE RHR as follows: [C0354] A. CLOSE 2RHl AND 2RH2, RHR Common Suction Valves [C0658] B. PLACE 2RP410ckout switch for 21SJ49 AND 22SJ49, RHR Discharge to Cold Leg Valves in VALVE OPERABLE C. CLOSE 21SJ49 AND 22SJ49, RHR Discharge to Cold Leg Valves. D. Send an Operator to ENSURE 2RH21 is fully CLOSED AND LOCKED. [C0631] Salem 2 Page 20 of 100 Rev. 17

s2.OP-AB.RHR-0001 (Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

Attac1unent 9, Steam Generator Reflux Cooling

0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment l3, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 21 of 100 [C0330] [C03S4] Rev. 17

S2.0P"AB.RHR-OOOl(Q) 3.36 Has the isolation ofRHR stopped the leak in ReS as indicated by any of the following? ReS level rising at a faster rate + Containment or RHR sumps pumping less frequently YES I GO TO Step 3.46 NO--> V 3.37 Send Operators to LOCATE AND ISOLATE the leak from RHR System. NOTE If possible, the leak should be isolated from the ReS and the other train of RHR. This will allow lacin one train of RHR back in service. 3.38 Is either train ofRHR available for shutdown cooling? NO I YES--> GO TO Step 3.42 V 3.39 CONTINUE OR INITIATE decay heat removal using alternate methods IA W Step 3.32 until RHR System is repaired and restored to service. 3.40 WHBN RHR System is restored to service, Salem 2 THEN: A. INITIATE recovery from alternate decay heat removal method selected IA W attachment in effect. B. PLACE an RHR loop in service as follows: IF alternate RHR Loop is aligned for BeeS, THEN PERFORM Attachment 2, Aligning RHR Loop From BeCS To Shutdown Cooling. OR IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling.

e.

GO TO Section 4.0. Page 22 of 100 Time Time Time Rev. 17

S2.0P~AB.RHR~OOOl(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure IA W S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling Attaclunent 10, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME R WST LO Level Almm mIDunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 23 of 100 [C0330] [C0354] Rev. 17

S2.0PMAB.RHR-OOOl(Q) 3.41 Does available RHR Pump require venting? NO I YES--> GO TO Step 3.47 V 3.42 RESTORE RHR as follows: A. OPEN 2RHl AND 2RH2~ RHR Common Suction Valves B. OPEN 218J49 AND 22SJ49, RHR Discharge to Cold Leg Valves. C. PLACE 2RP410ckout switch for 21SJ49 AND 22SJ49~ RHR DISCHARGE TO COLD LEG VALVEs in LOCKED OUT. 3.43 PLACE one RHR Loop in service as follows: IF alternate RHR Loop is aligned for BCCS, THEN PERFORM Attachment 2, Aligning RHR Loop From ECCS To Shutdown Cooling. IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling. 3.44 SECURE alternate decay heat removal method selected IA W attachment in effect. 3.45 GO TO Section 4.0. 3.46 LOCATE AND ISOLATE leakage from the RCS~ paying particular attention to locations of known maintenance or testing activities. Salem 2 Page 24 of 100 Time [C0354] Time Rev. 17

IQIH 82.0 P-AB. RHR-OOOI (Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6~ THEN INITIATE Containment Closure lAW S2.OP-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

.., Steam Generator Reflux Cooling

0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME R WST LO Level Alarm annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.OP-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 25 of 1 00 [C0330] [C0354] Rev. 17

S2.0P-AB.RHR-OOOl(Q) 3.47 When RCS leakage is stopped, becomes controllable OR otherwise contained, RESTORE RHR as follows: CAUTION Venting the RHR System may cause a reduction in RCS level requiring more makeup flowrate. Any opening in the RCS boundary could result in release of high temperature fluids, radioactive water, or gases to Containment. Opening 2SJ69 aligns the RWST to RHR and may result in RCS level rise. A. VENT RHR Pumps and piping as follows:

1.

CLOSE 2RH2 OR 2RHI. (2RH2 is preferred, 2RHI is a backup)

2.

IF air supplies to 21 RH18 and 22RH18 are isolated, THEN ALIGN air to 21RH18 and 22RH18 as follows: OP*EN 21RH18 wAlS, LOCAL A/S TO 21RH18 OPEN 22RH18-AlS, LOCAL A/S TO 22RH18

3.

THROTTLE OR CLOSE 21RH18, 22RH18. and 2RH20 as required to control ReS inventory. [C0329] [C0658]

4.

PLACE 2RP410ckout switch for 2SJ69, RHR SUCTION FROM RWST, in VALVE OPERABLE. (Control Room) Salem 2

5.

OPEN 2SJ69, RHR SUCTION FROM RWST. (Control Room)

6.

Send Operators to PERFORM the following:

a.

OPEN 2RH81 AND 2RH82, RHR Suction Line second high point vent, until steady stream of water flows (mechanical penetration area 78' elevation).

b.

IF the bioshield area inside containment is accessible, THEN OPEN 2RH68 AND 2RH69, RHR Suction Line first high point vent. until steady stream ofwater flows.

c.

MONITOR RIIR Pump in preparation for pump start. (continued on next page) Page 26 of 100 Rev. 17

S2.0P-AB.RHR-0001(Q) SELECTED CAS ITEMS + IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2. OP-AB.CONT-OOO 1 (Q), Containment Closure. + IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

+, Steam Generator Reflux Cooling + 0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME R WST LO Level Alann annunciates AND Containment Sump level exceeds 62%, THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: + IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, + CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available, IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 27 of 100 [C0330] [C0354] Rev. 17

S2.0P-AB.RHR-OOOl(Q) 3.47 (continued)

7.

ESTABLISH RCS level >97.5 f1. elevation as determined by the CRS.

8.

CLOSE 2SJ69, RHR Suction From RWST.

9.

OPEN 2RHI AND 2RH2, RHR Suction from RCS. CAUTION Changes in RCS pressure or voiding in the Reactor Core may result in inaccuracies in ReS level indication. Lower flow rates when starting RHR Pumps are preferable to limit initial sudden cooldown and to minimize fevelloss caused by collapsing voids. Operating at low RHR System fJowrates greatly reduces the risk of air entrainment (vortexing). Salem 2 B. OPEN 218J49 AND 22SJ49, RHR Discharge To Cold Leg Valves. C. Notify Operator in RHR Pump area to MONITOR the pump for abnormal conditions after the pump is started. D. RAISE makeup flow to RCS to prevent level drop as voids collapse. E. START one RHR Pump as follows: IF alternate RHR Loop is aligned for BCCS, THEN PERFORM Attachment 2, Aligning RHR Loop From ECeS To Shutdown Cooling. IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling. F. Notify local Operator to PERFORM observation at RHR Pumps: No abnonnal noise No seal damage (continued on nextpage) Page 28 of 100 Rev. 17

S2.0P-AB.RHR-OOOl (Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure IAW S2.0P-AB.CONT-000ICQ), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable Attacrunent: +, Steam Generator Reflux Cooling

0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alann annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thennocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 29 of 100 [C0330] [C0354] Rev. 17

S2.0P-AB.RHR-OOOl(Q) 3.47 (continued) G. Is RHR System normal as indicated by ALL ofthe fotiowing? ReS Level- >97.5 ft. elevation AND stable OR rising RHR Flow - stable between 1800 and 3 000 gpm RCS Temperature - stable or lowering Component Cooling available to RHR System Service Water available as heat sink No local indication ofRHR Pump damage. YES I NO--> GO to Step 3,50 Time V 3.48 IF an alternate decay heat removal method is established, THEN SECURE the alternate decay heat removal method lAW the attachment in effect. 3.49 GO TO Section 4.0. Time 3.50 Is a heat sink available for Residual Heat Removal? Component Cooling to RHR System Service Water to Component Cooling System Time YES I NO--> GO TO Step 3.62 V 3.51 Is an RHRLoop available? Time YES I NO--> RETURN TO Step 3.31 V Salem 2 Page 30 of 100 Rev. 17

S2.0P-AB.RHR-OOOl(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure IA W S2.0P-AB.CONT-0001(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures if RHR is not available. IF in Mode 4, THEN GO TO S2.0P-AB,LOCA-0001(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 31 oflOO [C0330] [C0354] Rev. 17

S2.0P-AB.RHR-0001(Q) 3.52 PLACE the alternate RHR Loop in service: IF alternate RHR Loop is aligned for EeeS, THEN PERFORM Attachment 2, Aligning RHR Loop From EeeS To Shutdown Cooling. IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling. 3.53 Is RHR in service? YES I NO--> RETURN TO Step 3.7 V 3.54 Is a heat sink available for Residual Heat Removal? Component Cooling to RHR System Service Water to Component Cooling System YES I NO--> GO TO Step 3.62 V 3.55 Is RHR flow stable? NO I YES--> GO TO Step 3.68 V 3.56 ATTEMPT to stabilize RHR flow between 1800 and 3000 gpm as follows: THROTTLE the appropriate RH18 valve: 21RH18, RHR Flow Control Valve 22RH18. RHR Flow Control Valve THROTTLE 2RH20, RHR HX BYF ASS VAL VB Salem 2 Page 32 oflOO Time Time Time Rev. 17

S2.0P~AB.RHR~OOOl(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

.., Steam Generator Reflux Cooling .. 0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%, THEN ALIGN intact RHR trainCs) to Containment Sump IA W Attaclnnent 13, Cold Leg Recirculation. IF AT ANY TIME a loss of RCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2.0P~AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 33 of 100 [C0330] [C0354] Rev. 17

3.57 ADJUST Component Cooling flow to RHR Heat Exchangers between 4000 and 4200 gpm. 3.58 Is RHR flow stable? YES I NO--> RETURN TO Step 3.7 V 3.59 Is RHR System normal as indicated by ALL of the following? RHR Pumps - at least one running RCS Level- >97.5 ft. elevation AND stable OR rising RHR Flow - stable between 1800 and 3000 gpm ReS Temperature - stable or lowering No local indication ofRHR Pmnp damage YES I NO--> GO TO Step 3.62 V 3.60 IF an alternate decay heat removal method is established, Time Time THEN SECURE the alternate decay heat removal method IA W the attachment in effect. 3.61 GO TO Section 4.0. Time 3.62 Is Component Cooling available to RHR as indicated by the following? + 21 RHR Heat Exchanger flow + 22 RHR Heat Exchanger flow RHR PUMPS CCW FLOW LO alarm clear (2CC2) Time NO I YES--> GO TO Step 3.65 V Salem 2* Page 34 of 100 Rev. 17

S2,OP-AB.RHR-OOOl(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q), Containment Closure. IF AT ANY TIME a complete loss of aU vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alam1 annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump lAW Attachment 13, Cold Leg Recirculation. IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available. + IF in Mode 4, THEN GO TO S2.0P-AB.LOCA-OOOl(Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet Salem 2 Page 35 of 100 [C0330] [C03S4] Rev. 17

S2.0P-AB.RHR-OOOl(Q) 3.63 INITIATE S2.0P-AB.CC-000l(Q), Component Cooling Abnom1ality. 3.64 When Component Cooling is restored, ADJUST Component Cooling flow to RHR components lAW S2.0P-SO.CC-OOOl(Q), Component Cooling System NOlmal Operation. 3.65 Is Service Water available as an ultimate heat sink for RHR cooling? NO j YES--> GO TO Step 3.68 V 3.66 INITIATE S2.0P-AB.SW-OOOl (Q), Loss of Service Water Header Pressure. 3.67 When Service Water System is returned to service: A. RETURN RHR to normal operation IA W S2.0P-SO.RHR-0001(Q), fuitiating RHR. B. RESTORE normal cooling (Service Water) to plant components lAW Attachment 12, Alternate Cooling Water, Step 8.0. 3.68 Is RHR System normal as indicated by ALL ofthe following? + RHR Pumps - at least one running + RCS level- >97.5 ft. elevation AND stable OR rising consistent with current RCS makeup AND no excessive indication ofRCS Leakage. + RHR flow - stable between 1800 and 3000 gpm + ReS temperature - stable or lowering NO YES--> GO TO Section 4.0 I V 3.69 RETURN TO Step 3.7 for symptom rediagnosis or as directed by the CRS. Salem 2 Page 36 of 100 Time Time Rev. 17

S2.0P-AB.RHR-OOOl(Q) SELECTED CAS ITEMS IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl (Q), Containment Closure. IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown IF AT ANY TIME RWST LO Level Alarm annunciates AND Containment Sump level exceeds 62%,

THEN ALIGN intact RHR train(s) to Containment Sump IA W Attachment 13, Cold Leg Recirculation, IF AT ANY TIME a loss ofRCS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: IF in Mode 5 OR 6, THEN START Safety Injection and Charging Pumps as required: AND: CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thermocouple temperatures ifRHR is not available. IF in Mode 4, THEN GO TO S2,OP-AB,LOCA-OOOl (Q), Shutdown LOCA. Refer to Exhibit 1 for Briefing Sheet SaJem 2 Page 37 of 100 [C0330] [C0354] Rev. 17

S2.0P-AB.RHR-0001(Q) 4.0 COMPLETION AND REVIEW 4.1 EXPLAIN Entry Condition in Comments Section of Attachment 15. 4.2 COMPLETE Attachment 15, Sections 1.0 and 2.0, AND FORWARD this procedure to the SM/CRS for review and approval. 4.3 SM/CRS PERFORM the following: Salem 2 A. REVIEW this procedure with Attachments 1 through 14 for completeness and accuracy. B. COMPLETE Attachment 15, Section 3.0. C. FORWARD completed procedure to Operations Staff. END OF PROCEDURE Page 38 of 100 Rev. 17

S2.0P-AB.RHR-OOOl(Q) ATTACHMENT 1 (Page 1 of2) CONTINUOUS ACTION

SUMMARY

1,0 IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2,OP-AB.CONT-0001(Q), Containment Closure, 2.0 IF AT ANY TIME a complete loss of all vital buses occurs, THEN PERFORM the applicable

Attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown 3.0 IF AT ANY TIME the Loss ofRHR cooling is due to a loss of Service Water or Component Cooling as a heat sink, THEN concurrently CONNECT hoses AND ALIGN alternate water sources to available equipment IA W Attachment 12, Alternate Cooling Water.

AND PERFORM the applicable attachment:

, Steam Generator Reflux Cooling
0, Forced Flow or Natural Circulation Cooldown 4.0 IF credit is being taken for the Equipment Hatch Ventilation Barrier (EHVB) to provide Containment Closure prior to filling the cavity to> 125' 6 t1 THEN Immediately INITIATE Attachment 14, 2R16 COLD LEG INJECTION (Prior to Filling Cavity to> 125' 6tt).

5,0 IF AT ANY TIME RWST LO Level Alarm arumnciates AND Containment Sump level exceeds 62%, Salem 2 THEN ALIGN intact RHR train(s) to Containment Sump IA W Attaclunent 13, Cold Leg Recirculation. Page 39 of 100 [C0330] Rev. 17

S2.0P~AB.RHR.OOOl(Q) ATTACHMENT 1 (Page 2 of2) CONTINUOUS ACTION

SUMMARY

NOTES Violation of Technical Specification 3.5.3 requires notifications lAW ECG. 0% Pressurizer Level Cold Cal. indication corresponds to 108.92 ft. elevation when the ReS is filled and vented. CAUTION Extreme care and judgement should be utilized in using more than one Charging or Safety Injection Pump. if the size of the leak is misjudged t use of high head pumps could cause a cold overpressurization accident. At low temperatures, use of high head pumps should be deliberate. 6.0 IF AT ANY TIME a loss of ReS inventory occurs AND Attachment 14 has NOT been initiated (2R16), THEN PERFORM one of the following: Salem 2 A. IF in Mode 5 or 6, THEN START Safety Injection and Charging Pumps as required ~ CONTROL Pressurizer level between 5% and 50% while maintaining RHR System in service, CONTROL injection flow to result in lowering Core Exit Thennocouple temperatures ifRHR is not available. B. IF in Mode 4, THEN GO TO S2.0P"AB.LOCA~OOOl(Q), Shutdown LOCA. Page 40 of 100 [C0354] Rev. 17

s2.0 P-AB.RHR-OOOI CQ) ATTACHMENT 2 (Page 1 of 2) ALIGNING RRR LOOP FROM ECCS TO SHUTDOWN COOLING 1.0 IF placing RHR Loop 21 in service, THEN: A. ENSURE RHR Loop 21 is aligned for BeCS injection. B. PLACE 21RH29, RHR PUMP MINIMUM FLOW VALVE in AUTO. C. Locally: OPEN 21RH12, RHR HX BYPASS ISOLATION VALVE OPEN 21RH17, RHRLETDOWN ISOLATION VALVE OPEN 21RH18-A/S, RHRLETDOWNISOLATION VALVE AIR SUPPLY Salem 2 D. In the Control Room: CLOSE 21RH18, RHRPUMP FLOW CONTROL VALVE CLOSE 22RH18, RHR PUMP FLOW CONTROL VALVE CLOSE 2RH20, RHR HX BYPASS CLOSE 22CC 16, RHR HX COMPONENT COOL OUT VALVE OPEN 21 CC16, RHR HX COMPONENT COOL OUT VALVE E. START 21 RHR Pump. F. OPERATE 21RH18 AND 2RH20, to maintain stable RHR flow to the Reactor Coolant System. Page 41 ofl 00 Rev. 17

s2.OP~AB.RHR~OOOI (Q) ATTACHMENT 2 (Page 2 of2) ALIGNING RHR LOOP FROM.ECCS TO SHUTDOWN COOLING 2.0 IF placing RHR Loop 22 in service~ THEN: A. ENSURE RHR Loop 22 is aligned for ECCS injection. B. PLACE 22RH29, RHR PUMP MINIMUM FLOW VALVE in AUTO. C. Locally: OPEN 22RH12, RHR HX BYPASS ISOLATION VALVE OPEN 22RH17, RHR LETDOWN ISOLATION VALVE OPEN 22RIIl 8~NS~ RHR LETDOWN ISOLATION VALVE AIR SUPPLY D. In the Control Room: CLOSE 22RH18, RHR PUMP FLOW CONTROL VALVE CLOSE 21RH18, RHRPUMP FLOW CONTROL VALVE CLOSE 2RH20, RHR HX BYPASS CLOSE 21 CC16, RHR HX COMPONENT COOL OUT VALVE OPEN 22CC16, RHR HX COMPONENT COOL OUT VALVE E. START 22 RHR Pump. F. OPERATE 22RH18 and 2RH20, to maintain stable RHR flow to the Reactor Coolant System. 3.0 RETURN to procedure step in effect. Salem 2 Page 42 of 100 Rev. 17

s2.0 P-AB.RHR~OOOI (Q) ATTACHMENT 3 (Page I of 1) ALIGNING RHR LOOP FOR SHUTDOWN COOLING 1.0 IF placing RHR Loop 21 in service, THEN: A. PLACE 21 RH29, RHR PUMP MINIMUM FLOW VALVE in AUTO. E. CLOSE 21RH18, RHRPUMP FLOW CONTROL VALVE. C. CLOSE 22RH18, RHRPUMP FLOW CONTROL VALVE. D. CLOSE 2RH20, RHR HX BYPASS. E. CLOSE 22CC16, RHR HX COMPONENT COOL OUT VALVE. F. OPEN 21 CC 16, RHR HX COMPONENT COOL OUT VALVE. O. START 21 RHR Pump. H. OPERATE 21RH18 AND 2RH20, to maintain stable RHR flow to the Reactor Coolant System. 2.0 IF placing RHR Loop 22 in service, THEN: A. PLACE 22RH29, RHR PUMP MINIMUM FLOW VALVE in AUTO. E. CLOSE 22RH18, RHR PUMP FLOW CONTROL VALVE. C. CLOSE 21RH18, RHR PUMP FLOW CONTROL VALVE. D. CLOSE 2RH20, RHR HX BYPASS. E. CLOSE 21 CC 16, RHR HX COMPONENT COOL OUT VALVE. F. OPEN 22CC 16, RHR HX COMPONENT COOL OUT VALVE. G. START 22 RHR Pump. H. OPERATE 22RH18 AND 2RH20, to maintain stable RHR flow to the Reactor Coolant System. 3.0 RETURN to procedure step in effect. Salem 2 Page 43 of 100 Rev.17

1600 ATTACHMENT 4 (page 1 of 14) Time To Saturation Before Core Offload - Cavity Flooded Elav. 128.6 ft At Various Initial ReS Temperatures S2.0P-AB.RHR-0001(Q) ~- --of - -- -J- -- --~ --- - --.:..---~--- -~----~----~----j-- --j--- --+- --l--- - --~-- - ---I -- - -~-- --f-- --~ ----!-----!- ---+---~--- +--+-- -- +---\\- ---f----'- ---1--- - j - - --~ - - - -" - - -j- __ 60°F 1400 1~~~~~~~~~~~~~~~~~~~~~~~;f~;;+/-;;;;+/-~~;;~~~~~~~~~~~ _70°F __ 80°F 1200 t-~-t--r-T--r-i--r-i--t-1--r-~-+-i--T-~-t~--t-~~~--+-~~~--+-~~~~+=~~-=~+/-:==~. __90°F .E 1000 __ 100°F g __ 110°F .2 e 800 __ 120°F ~ --1WF o 600 --140"F Q> § ~ ~-- --. -.1-----, --150 F 400 ---;---------:----~----c-~~:;.c:_:;z:..:.-d __ 160°F 200 ~ lu+ Ii **1 IllfTTfnrLLlu):::;:u,m[m:uu;m:;;;c-3 =::::: CORE Salem 2 o ~f--~~-+--~~-+--~~-+~~+-~~--+-~-+--~~-+--~+--+--~+-~~--+-~----7-~-+--~~-+--~~-+--~ o 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Time After Shutdown (days) NOTE Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core --190"F TIC OR HOT LEG T3I/21 HOTLEG 122/22 HOT LEG T46 J 23 HOT LEG TI4/24 HOT LEG Dl2 KI2 11 H4 COMPUTER POINT TOO31A/T0419A TO022A / T0439A T0046A I T0459A T0014A I T0479A Page 44 of 100 Rev. 17

120 110 100 90 Ii) 80 2 ::.

<:: §. 70 t::

~ 60 l!!

s 50 (J) 0 I-eI>

40 E i= 30 20 10 0 0 CORE Salem 2 S2.0P-AB.RHR-000l(Q) ATTACHMENT 4 (Page 2 of 14) Time To Saturation Before Core Offload AtWater Elev. 10% PZR Level At Various Initial RCS Temperatures Iii I '11 1_ I, _ I I ~~~' --i i~~*----.;: I 1--J:=I=::::j=:h=-+----4=-+/-:: -... --'----' .....---~ 1 1 --i-..*. -:. -~-=~=--:-::~:'-.::::-:-:-=---.-.. -. ----~-.. -~ ---r---.----------- 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Tim e After Shutdown (days) NOTE __ 60°F __ 70°F

80°F

- - - 90°F 100°F

--110*F __ 120°F __ 130°F __ 140°F __ 150°F __ 160°F __ 170°F --190*F Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core TIC OR HOT LEG I T31/21 HOT LEG T22/22 HOT LEG T46 I 23 HOT LEG T14 / 24 HOT LEG D12 K12 J) H4 I COMPUTER POINT T0031A / T0419A T0022A / T0439A T0046A i T0459A TOO)4A! T0479A --.. -.-~-.-- Page 45 of 100 Rev. 17

110 100 90 80 J

I 70

..E g e 60 g E

I Ii>

50 CI) 0 I-(I) 40 .§ I-30 20 10 0 ATTACHMENT 4 (page 3 of 14) S2.0P-AB.RHR...oOOl(Q) Time To Saturation Before Core Offload AtWater Elev.103.5 ft At Various Initial RCS Temperatures --BO°F I ~~~-4-~+-~-+~~+-~-+~-~~~-4-~4-~~~~~~~i --70"F -80'F I i I'

'---~-=---~ -

gO°F

'~;

~;,;,~ i ! I 1 I L----I I I -, ! __ 100°F I I i r ~-1100F I, I I

,: ;, j

--120*F ,I ~ Ii I !4 I i -' I --130'F --140°F 11i::nQ~ --160°F ___,*180°F --190'F o 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 2021 22 2324 25 2627 2829 30 31 32 33 34 35 36 37 38 39 40 Time After Shutdown (days) NOTE Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core I I TIC OR HOT LEG DI/21 HOT LEG T22/22 HOT LEG T46 f 23 HOT LEG T14 f 24 HOT LEG CORE DI2 K12 J1 H4 COMPUTER POINT TOO31A/T0419A TOO22A J T0439A TO046A I T0459A T0014A I T0479A Salem 2 Page 46 of 100 Rev. 17

100 95 90 85 80 75 '0 70 .l!! 65 60 55 S e 50 a 45 CI) o* 40 35 E i= 30 25 20 15 10 5 0 CORE S2.0P-AB.RHR-OOOl(Q) ATTACHMENT 4 (page 4 of 14) Time To Saturation Before Core Offload At Water Elev.101 ft At Various Initial RCS Temperatures i 1 i i 1 I I I n-n-r--; fi-:-:--r-'-:-T-T---'i"---~---T---;--;-'-----"-'............ I I I Ii' i ! ' . ', I: [i .. :p i I I i II iii 'I i i '11*-1 iii iil_j\\~~-i J.....-1 ~--,

d I

.1 i .I. I I i ~~! J--i-------r--: IL--?""l I.~ I I 1........1------ i i ____ 1_ ~ ..J.---"\\ I ....d::=r_L .... 1 . ~___._J i~~ ~i ,----------=:1 I :::t==i=t,, I I;~~ '~~~~~':I-~ ,,, I~ ~~m~~I~1 i:.. ~ ~~~+/-=c:+=+-~. +--+- : I

:-::L-i :: :!: i I i

I.; :. :.: ::

,--: ---~; ~i¥Bmm~!~ ~ I l' 1 ~ ~ l I ! 1 i --;----,-- J I .:.t=.:+. -4 L-+--.-f o 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 2324 25 26 27 28 29 3D 31 32 33 34 35 36 37 38 39 40 Tim e After Shutdown (days) NOTE Use the highest reading Core Exit Thermocouple OR Hot leg Temperature to determine the starting temperature for the Reference Core __ 60°F __ 70°F --BO°F __ 90°F __ 100°F --110"F --120°F __ 130°F __ 140°F __ 150°F __ 160°F --170"F

180°F

__ 190°F TIC OR HOT LEG T31 /21 HOT LEG T22/22 HOT LEG T46/23 HOT LEG T14 / 24 HOT LEG D12 K12 11 H4 COMPUTER POINT TOO31AfT0419A T0022A f T0439A T0046A I T0459A TOOI4A / T0479A Salem 2 Page 47 of 100 Rev. 17

65 60 55 50 Ci) 45 S

l

'" 40 I c 35 0 ~ ~ 30 (/J 0 25 I-(I) E i= 20 15 10 5 0 I I I t S2.0P-AB.RHR-0001(Q) ATTACHMENT 4 (page 5 of 14) Time To Saturation Before Core Offload At Water Elev. 97 ft At Various Jni~ial ReS Temperatures I I f -- -r ---r---r---' I 1 ~ "T~~, i~ I ~!I~*iiJ ~ll_~1 I'**~** : -i--i -,---- ~ r-I .L I -I J ---~1 i

1

~ 1 I 1 1 11 I. __ t. .. j J __ GO°F --70°F __ 80°F __ 90°F __ 100°F __ 110°F __ 120°F __ 130°F __ 140°F __ 150°F __ 160°F --170°F __ 180°F o 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Time After Shutdown (days) NOTE Use the highest reading Core Exit Thennocouple OR Hot Leg Temperature to detennine the starting temperature for the Reference Core TIC OR HOT LEG 131/21 HOT LEG T22/22 HOT LEG T46f23 HOT LEG Tl4 I 24 HOT LEG CORE D12 K12 11 H4 COMPUTER POINT TOO31AfT0419A TO022A f T0439A T0046A ! T0459A TO014A I T0479A I Salem 2 Page 48 of 100 Rev. 17

......... Ir"r.tW"E.......-<>0 ~~<=:.. .... 1I(Jt0'_o 910_0 ~1(Ir_O IIG:JOr_lO !!S:O...-o.-'-IIlJ~-'-.<:)Io"'" 5"_':' <.......... )0 0 ~~--

21O"_1IDI

____ o "'_00 00_00 ATTACHMENT 4 (page 6 of 14) TIME TO REACH CORE BOILING AFTER LOSS OF RHR (BEFORE REFUELING 40 TO 100 DAYS) ~ -~ v s2.OP-AB.RHR-OOOI (Q) ~ I~ ~- "foo C:-gr-_.. ".,. ___________ ""1-..00 ~ g w-"" ~'I(]I'_O 00 .so_'IDI 8:Il10_0 -WII[JI'O_O ..... ~-=-_4:tI -.-li....... ~ ~~.- ~ .........-c:CCII...::JIo.............. <~~::. NOTE Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core TJC OR HOT LEG TIl /21 HOT LEG T22! 22 HOT LEG T46 /23 HOT LEG T14!24 HOT LEG CORE Dl2 KI2 Jl H4 COMPUTER POINT T0031A I T0419A T0022A I T0439A T0046A / T0459A TOOl4A/T0479A Salem 2 Page 49 of 100 Rev. 17

c 'E 550.00 I ~ 500.00 -h-to 450.001- ~ ATTACHMENT 4 (page 7 of 14) TIME TO REACH CORE BOILING AFTER LOSS OF RHR (BEFORE REFUELING 100 TO 1000 DAYS) HUR ("F/min) s2.OP-AB.RHR-OOOI (Q) ~ 400.00 +---~ __ ~ ________ ~ ______ +-______ ~ ______ ~~ ______ +-____ ~~ ______ -1 ______ ~,1.1o 1.00 350.00 c 0.90 :§

300.00

.~ ~8o ~ '0 co Q I-25lHIO (I) E i= 200.00 150.00 100.00 50.00 -r"-..r' - ~ ~ t.. _:;--J~'-- ~ I ~~-I~ -~ V ..\\.-~.. ~ ~ oI!!".. "~-..,.. -.. ~- -- "'" - - 0.70 ~ Co = 0.00 15 ~

r:

0.50 0.40 0.30 " ** t--... __ _ 0.20 0.10 0.00 ! 0.00 10[J 200 300 400 500 1300 700 800 SOD 1000 Days Shutdown (D~) Salem 2 Page 50 of 100 Rev. 17

2200 2000 1800 1600 !l 1400 I: I c: 1200 .'il ~ -= 1000 UJ f!- 800 II> E i= 600 400 200 0 CORE t::::: :::L:: ::: -T------ ATTACHMENT 4 (page 8 of 14) Time To Saturation After Core Offload - Cavity Flooded Elev. 128.6 ft At Various Initial Res Temperatures 82.OP-AB.RHR-OOOI (Q) __ 60°F --70"F __ BOeF __ gO°F __ 100°F f _____ 1---------1----- ____ ~----- ___ ~ _______. __ ~-- _______ ~ ________ -l---------j ____ +/----.:-::-::;_~_=--__ ~ _____ ~_.:-=-== _~ ___ -=-I--;:=;: ____ ~ __ --=----i----,......c-. _ _ __ . _ =---'='" __ ~ -- 110°F --120"F __ 130°F __ 140°F __ 150°F --160"F __ 170°F --190"F __ 180°F "h--i~L-

-:--::r::~:-: ~i~~~~~~~:~F:~-~-~-i~~::-:-~: ~::~::H:: ::::::: :-::::-:-F:: ____.---_ ___ __ _______, _

-~~ 0 2 4 6 B 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 Time After Shutdown (days) NOTE Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core TIC OR HOT LEG TIl 121 HOT LEG T22 J 22 HOT LEG T46 / 23 HOT LEG T14! 24 HOT LEG Dl2 K12 J1 H4 COMPUTER POINT T0031A I T0419A T0022A / T0439A T0046A / T0459A T0014A / T0479A 0 ** _ _ ~ Salem 2 Page 51 of 100 Rev. 17

180 170 160 150 140 130 Ii) J.l 120

110

~ J:: 100 0 "" f! 90 .a 80 <II Cf.J 0 70 too Q> 60 E j:: 50 40 30 20 10 0 I _I. ~ i l 1 !~ ATTACHMENT 4 (page 9 of 14) S2.0P-AB.RHR-000l(Q) Time To Saturation After Core Offload At Water Elev. 1.0% PZR Level At Various Initial ReS Temperatures -I' ---1

-- -'--r I

I I __ ~ If! i --+-t1 i .l--t--tJ I ~ [:_~i: t ! IT T ;~ l.-+---r--i 1~1 L--d--+/-:C .. ~, ~:., ~-~ f ~ ~~ ~ '~-1 t ~~1_ .. '_.H~.-.- - 4 I i I j __ 60°F __ 70°F __ 80°F __ 90°F --100*F --110'F __ 120°F __ 130°F --140"F __ 150°F fi J __ HO°F --180'F . -~'---' __ 190°F o 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 2526 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Time After Shutdown (days) NOTE Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core TIC OR HOT LEG 131/21 HOT LEG T22/22 HOT LEG T46 /23 HOT LEG T14 124 HOT LEG CORE D12 K12 11 H4 COMPUTER POINT T0031 A I T0419A T0022A ! T0439A T0046A ! T0459A TO014A I T0479A Salem 2 Page 52 of 100 Rev.!7

.e c I 0 f!

l 1d r/}

0 I- <l> E i= 160 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 S2.0P-AB.RHR-000l(Q) ATTACHMENT 4 (Page 10 of 14) Time To Saturation After Core Offload At Water Elev. 103.5 ft At Various Initial ReS Temperatures i I If! ~H**--l---I-- ". ----'-, -::=-=>>. I I --.l I III IIIIIIIIII~~ .d I ~ .-J..----'I ~~~~I~I~~~~*~~~~Tt~~~~~ I ~:--i I [ i ~~~~~~~~~~~~~=+~~~~~~=-~T-! -=--""="'---_.j I ~l J-~~~~~~~~~~~~~4=r+/-~~~~=t~~~. -I . -j I i --

~----------------1 o

2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Time After Shutdown (days) NOTE Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core __ 60°F __ 70°F -_._.-. 80 ° F __ gO°F __ 100°F __ 110°F . __ 120°F __ 130°F --140"F ---150"F __ 160°F __ 170°F __ 180°F __ 190°F TIC OR HOT LEG T3I/21 HOT LEG TI2/22 HOT LEG T46 123 HOT LEG T14/ 24 HOT LEG CORE D12 K12 11 H4 COMPUTER POINT TOO3JA/T0419A T0022A I T0439A T0046A I T0459A T0014A / T0479A Salem 2 Page 53 of 100 Rev. 17

150 140 130 120 110 "iii <II 100 c g 90 c 0 80 ~

I 70

'Iii rn 0 I-50 E 50 j.:: 40 30 20 10 0 CORE I I I i I I t ATTACHMENT 4 (page 11 of 14) Time To Saturation After Core Offload At Water Elev.101 ft At Various Initial ReS Temperatures I S2.0P-AB.RHR-0001(Q) !l~ ~.. __ 60°F __ 70°F --BO°F I '4 __ gO°F i-+-:--~;;=-i-="f--b"";"'4=""'-b~~==::;::=-+-~,,;.-~~~ ~ 1 00 of --{

-t-i=~-i~~+-~~~-4~~~~~~~~J-~~~-L-~~~~~! --110°F

__ 120°F --130'F Ii ~ -=pr: ~I'-"~ I I~I ~~. ~I~I~I;I~ __ 140°F '--! __ 150°F i "i -r--~~----'--; --; __ 160°F __ 170°F ~~-+-~'I' ~. ~ I i i f 1 --180'F ~ j i ~ It I L o 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 2324 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Time After Shutdown (days) NOTE Use the highest reading Cafe Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core -*-190*F TIC OR HOT LEG T31 /21 HOT LEG TI2 / 22 HOT LEG T46 /23 HOT LEG Tl4 124 HOT LEG DI2 KI2 JI H4 COMPUTER POINT TOO31A/T0419A T0022A / T0439A T0046A I T0459A TOOl4A/T0479A Salem 2 Page 54 of 100 Rev. 17

100 95 90 85 80 75 70 !!l 65 ~ t:: §. 60 t: 55 0 ;; 50 i'! 45 ~ 40 II> 35 S 30 25 20 15 10 5 0 CORE ATTACHMENT 4 (page 12 of 14) Time To Saturation After Core Offload At Water Elev. 97 ft At Various Initial RCS Temperatures S2.0P-AB.RHR-0001(Q) '-'i 1 1'-: --I ]---r---r-r-r-~L. 1 ~L--:-CLJ_ . T---:-'r-'"[' -. -,. T----.-,--'-------,--.-, t==t:=Jc~+==+=++-+-+--+~-~r_t--t_t_t_I~=t=t=t=l-j----*I* ~_~ -~60°F -r 1- -+ I i i ...l i '--~~-~-+-+----4 j- -i~-T i -=""' --1

f

-~70*F _~80°F __ gO°F __ 100°F __ 110°F __ 120°F __ 130°F -~140°F __ 160°F __ 170°F __ 180°F .. j __ 190°F o 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Time After Shutdown {days} NOTE Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core TIC OR HOT LEG T31/21 HOT LEG T22 122 HOT LEG T46 /23 HOT LEG T14 / 24 HOT LEG Dl2 K12 Jl H4 COMPUTER POINT T003IA IT0419A T0022A I T0439A T0046A ! T0459 A TOOI4A I T0479A ~----- -~- -~-- Salem 2 Page 55 of 100 Rev. 17

CORE Salem 2 '1.... 0 '120 "100 TIME TO 80 REACH SATURATION (MIN) 60 40 20 0.0 S2.0P-AB.RHR-000l(Q) ATTACHMENT 4 (page 13 of 14) TIME TO REACH CORE BOILING AFTER LOSS OF RHR (AFTER REFUELING 40 TO 100 DAYS) --~ ~ ~ ~ / ,..-----~ ...,.- 1-- -~' '100" F "l40"F 0.0 20 40 60 80 '100 Ti.-ne after shutdo........ (days) NOTE I "120 Use the highest reading Core Exit Thermocouple OR Hot Leg Temperature to determine the starting temperature for the Reference Core I TIC OR HOT LEG T31/21 HOT LEG T22/22 HOT LEG T46/23 HOT LEG T141 24 HOT LEG D12 K12 J1 H4 COMPUTER POINT TOO31A/T0419A T0022A f T0439A T0046A I T0459A TOO14A/T0479A Page 56 of 100 Rev. 17

800.00 ~ 750.00 700.00 650.00 500.00 550.00 "\\.. ..-.. 500.00 s:: §. 450.00 ~ g 400.00 0... Q) 350.00 E j:: 300.00 250.00 200.00 150.00 100.00 !o'" /' l,./ __ ~ r V'- 5O.OD 0.00 1 DO 200 Salem 2 ATTACHMENT 4 (page 14 of 14) TIME TO REACH CORE BOILING AFTER LOSS OF RHR (AFTER REFUELING 100 TO 1000 DAYS) I I I --TIS (100 oF) -TIB (140 OF) HUR rF/min) ~ ~

7

.F / /" ~ / ~~... /' V ,.,-~ V ~"r /' ~ -.. S2.0P-AB.RHR-0001(Q) 1.[ID -~ ~- 0.90 ./'" V - 0.80 0.70 ~,- r-- s.: 0.60 : Q) 0.50 ~ 0.. ~ 0.40 ~

I:

0.30 0.20 - 0.10 300 400 500 500 100 800 900 0.00 1000 Days Shutdown (Days) Page 57 of 100 Rev. 17

S2.0P-AB.RHR-0001(Q) ATTACHMENT 5 (page 1 of5) HEATUP RATE FOR LOSS OF RHR COOLING Heat Up Rate Before and After Core Reload Cavity Flooded

I I I

I I I ii, I II II I I 1.3 i i i I ! ii' 1.2 I I I I I I I I I I I I I I I I I I I i ! .. L~. __, __ J 1 1 j I I [ I I I [ I I I I I I I I I II!! i' ! I I I i 1.0 I I I I I I i I I !

s-i II !!

1-I I I ii E 0.9 'I I I . I, ~ I 'I ! I I' -; 0.8

i i i I

I I ,T ,- I! I S f ill I!; .... 07 I I i ; ' I ~. j I I ! ! 1; 0.6 \\! I ,[ I i : ~ \\ ! I !I il I i-;-- 05 \\1 [ 1 \\~ j I I 'I 'I 0.4 Ii" I ._~_. _, \\1 "-,j ~ I I I 0.3 J}.. ~ I I i i i ![ '+-1.: I !---r--+-: I Ii I I ~! I 02 ! ! i i i I ~ I 0.1 i i i i ---.----. -- Before Offload I I I T I I I -After Offload 0.0 I I I I: I o 1 2 3 4 5 6 7 8 9 10 11 12 13 1415 16 17 18 192021 222324 252627 28 29 30 31 32 33 3435 363738 3940 Time After Shutdown (days) Salem 2 Page 58 of 100 Rev. 17

25 24 23 t-=f=H=' I ~tJ --- L 22 I J 21 i.. I .1 20 19 I i I I I 1 I I 18 I [I

I r 17

'E 16

15 i "

I ~ 14 'i ~ 'I: I .$ 13-~-, '-\\- "I I r n:: 12 I C. i 1 i I

> 11

~ '~ ~I I II ' II I I ~ \\11 i II ! 6 I r--I 5 ~H?0t-4 I I I r o Iii i '1'1-+ o 1 234 567 8 9 Salem 2 S2.0P-AB.RHR-0001(Q) i ATTACHMENT 5 (page 2 ofS) HEATUP RATE FOR LOSS OF RHR COOLING Heat up Rate Betore ancl Atter Core Reload At 10"/oPZR Level I I I I I ..1 r .J J J I 'I I --i-Iii 1 i! I I I I I I l I I I --1, -~ I 10 11 12 1314 15 16 17 18 19 2021 22232425 262728293031 323334353637 383940 Time After Shutdown (rla=l Page 59 of 100 -- Before Offload -- After Offload Rev. 17

S2.0P-AB.RHR-000l(Q) ATTACHMENT 5 (page 3 ofS) HEATUP RATE FOR LOSS OF RHR COOLING Heat Up Rate Before and After Core Re load At Elev. 103.5 ft 25r-1i~~~-r1l~~~:-1I-'~-r-r'-~:-~1!-,-,-.~'-'-.-r-~~----~~~ 24 I : I . i 23 1 1 --;----[ 1 22 i I j I 21 i I Iii! 20 i I I I I 1 I I 19 I I I I I I 18 i l l I !: i I I "1---'--., - --I 17 I I ' j

-=- 16

--~- ii j' i-:-~] E 15 I I ~ 14 i ' I I . -.. -----'---..;----1

13

-j i f --1 c G ' , l ~ 12 I I I ' j §" 11 r I I i----~--i 1iI10 I I i II

---1 Cb l

I 1 J: 9 \\! i I j Iii. i I 8 I I ill T T 7 \\i i ! ! I 6 U\\.!. I l: i I 5 \\1" t i I I 4},. ill I. I ,1 3 ~ -r-f-L i I j i i -"""'-'----1 2 I T=J==h I t .~ 1 i .-.. - - -i o I I I t ! o 1 2 3 4 5 6 7 8 9 10 11 1213 14 1516 17 18 192021 22232425262728293031 323334353637 383940 Time After Shutdown (davs) Salem 2 Page 60 of 100 --Before Offload --After Offload Rev. 17

$ 13

. 12

3" 11 iii 10 GI

t:

9 8 7 6 5 4 3 2 1 0 S2.0P-AB.RHR-000l(Q) ATTACHMENTS (page 4 ofS) HEATUP RATE FOR LOSS OF RHR COOLING Heat Up Rate Before and After Core Reload At Elev.101 ft I j I l - I - - - - - - - ! ~ f 1-iJ~1 I I I I I I I I I I I I I ,------,-~--.--~,~-'----l I __ !_I \\i I I I i I I i I I I I I I 1 1 I -1 I 1 [--:- i 1 - '--~--1 ~~~:s....,...l--'--l-...:...-_l__+---i--L-'---+-'--_I_+____;..--_i_+_--L_+-f_+_-L_+_1-~_;__~~-!__r__r_~_t--.. -~ -l +--~'*"=-~~:::p:,,~d___+_--'---'---+_+_~-+--+-_+_-+---+--+---i-_+_-i-+_-'-+_-,----I--_,---:--...;-- -'--i 1 1--+ 1 J --;---+--~~--_!_--'-~____,c---- l... ---I-----I---i-012345678 9 10111213141516171819202122232425262728293031323334353637383940 Time After Shutdown (days) -- Before Offload --After Offload Salem 2 Page 61 of 100 Rev. 17

25 24 23 22 21 20 19 18 17 C 16 ~ 15 t 14 S 13 ~ 12

3' 11 iii 10 Q)

I:

9 8 7 6 5 4 3 2 1 0 i \\ -L J I 'L I I ATTACHMENT 5 (page 5 of 5) BEATUP RATE FOR LOSS OF RHR COOLING Heat Up Rate Before and After Core Reload At Elev. 97 ft 1 J I J S2.0P-AB.RHR-000l(Q) i I I i I I I I I I I I I I I I I I I I i I I I Fl n TI I I i-r=1 r---.J ,---- I ~ I~ LJ I Ii

c.

I. i -- Before Offload .1 --After Offload 1 o 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 3637 38 39 40 Time After Shutdown (davs) Salem 2 Page 62 of 100 Rev. 17

S2.0P-AB.RHR-000l(Q) ATTACHMENT 6 (l>age 1 of2) MAKEUP RATE REQUIRED TO REFILL Res AFTER LOSS OF RI-IR Make Up Flow Before Core Offload N. Various Injection Temperatures 3200T=~~~~T=T=~~~~~~~~~~~~~~~~-,-'-'-r-r~-'-'~~~----------- &. 2,000

1

{ C) 1,800 o 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 2021 22 23 24 25 26 27 28 29 30 31 32 3334 35 36 37 38 39 40 Time After Shutdown (days) Salem 2 Page 63 of 100 _100°F _gO°F _80°F Rev. 17

2,400 2,200 2,000 1,800 1,600 e-

a.

S 1,400 3:: 0 u: 1,200 0.. ~ 1,000 CG

5 800 600 400 200 0

S2.0P-AB.RHR-OOOl(Q) ATTACHMENT 6 (page 2 of2) ~UPRATEREQUnmDTOREmLLRCSAFTERLOSSOFRHR Make Up Flow Mer Core Offload IV. Various Injection Temperatures

l:::I::::F: ::::1~::I:~:F:i:::r:~1~:~ :::+4:::::::::!:::::~:::r:::T~:~::::l::r::: ::+=::[:=+:::I::::1::::1::::j:::+:: i::4:::r~~::::tJ:::~::::f::~:::::1

r::::!:=:::::::,:::: ::::t:::t=f:: :::t:: ::::j::::J::::::::+::: :::: :::: ::::,::+:::t::::~:::: ::::1:::: :::: ::::l::::!:::T::r:j::::L::!::::J::::~::::~::':r::!:::::(::1 iinlil:nI!n!:iJI:;;jn;r!;iiiitin!~~ri!i:l:~ninl!ni:I;;iiIlli,L'}!

i::_f:t:I:: :::::--:1::: ::::!::.]::..j::::j.. **** *= *** :-: ** ~.: ** -+::i: *** ~.n. :! *** !..t:.:: **, ** **i:nl.l**.~.-f; *** t=

Inri r r r l I I o 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 2021 22 23 24 25 26 27 28 29 30 31 32 3334 35 36 37 38 39 40 lime After Shutdown (days) _100°F _gO°F _80°F Salem 2 Page 64 of 100 Rev. 17

ATTACHMENT 7 (Page 1 of 5) S2.0P-AB.RHR-0001(Q) HOT LEG INJECTION (preferred method RCS ~ 200 0 P) C0354 CAUTION Only Borated water should be added to the RCS to maintain adequate Shutdown Margin. Any opening in the ReS boundary could result in release of high temperature fluids, radioactive water, or gases to Containment. Violation of Technical Specification 3.5.3 requires notifications lAW ECG. 1.0 MAKEUP to the ReS as follows: Salem 2 A. OPEN 2SJ30, Suction from RWST. B. IF BOTH Safety Injection Pumps are tagged, THEN send an Operator to RELEASE breaker for one Safety Injection Pump. C. PLACE 2RP4 Lockout Switch for the appropriate SJ 40, SAFETY INJECTION HEADER STOP VALVE, in VALVE OPERABLE. D. OPEN appropriate SJ40 valve, Safety Injection Header Stop Valve. E. START the selected Safety Injection Pump. F. CONTINUE feeding RCS at maximwn rate until ONE of the following occurs: RHR is restored. Flow from any RCS opening is adequate to result in lowering Core Exit Thermocouple temperatures. G. When any of the above conditions are satisfied, CONTROL injection flow by locally throttling the appropriate S1 PUMP DISCH VALVE, 21 SJ35 or 22SJ35, to minimize flow to Containment while maintaining Core Exit Thermocouples stable or lowering (SI Pump room, 84' elevation). H. IF Core Exit Thermocouples are not available, THEN MAINTAIN injection flow determined in Attachment 6, Makeup Rate Required To Refill RCS After Loss Of RHR. Page 65 of 100 Rev. 17

S2.0P-AB.RHR-OOOl(Q) ATTACHMENT 7 (Page 2 of5) HOT LEG INJECTION 2.0 INFORM Containment personnel that high temperature fluids, contamination, and airborne activity will exist at any RCS openings. 3.0 IF Service Water is available, THEN START all available CFCUs in slow speed to minimize Containment pressure rise. 4.0 ALIGN bleed path by perfonning ONE of the following: A. VERIFY a 0.5 ft2 or greater hot leg vent path exists: (circle path verified) All Pressurizer Safety Valves removed Pressurizer Manway removed Vent path determined by System Manager B. OPEN the following valves: 2PRl, Pressurizer PORV, and 2PR6, Block Valve for 2PRl 2PR2, Pressurizer PORV, and 2PR7, Block Valve for 2PR2

Reactor Head Vent Solenoid Valves:

2RC40 2RC41 2RC42 2RC43 5.0 CONTROL Safety Injection Pump flow rate to maintain Core Exit Thermocouple temperature stable or lowering by locally throttling the appropriate SI PUMP DISCH VALVE, 21SJ35 or 22SJ35. 6.0 MAINTAIN feed and bleed of the RCS until RHR is restored or other methods of decay heat removal are utilized. Salem 2 Page 66 of 100 [C0329] Rev. 17

82.OP~AB.RHR-OOOI (Q) ATTACHMENT 7 (Page 3 of 5) HOT LEG INJECTION 7.0 When RHR becomes available, THEN RETURN RHR to service IA W the following: A. IF the RHR system requires venting THEN VENT RHR Pumps and piping: CAUTION Venting the RHR system may cause a reduction in RCS fevel requiring more makeup flowrate. Any opening in the ReS boundary could result in release of high temperature fluids, radioactive water, or gases to Containment. Opening 2SJ69 aligns the RWST to RHR and may result in ReS level rise.

1.

ISOLATE RHR Suction from RCS, CLOSE 2RHI OR 2RR2, RHR Suction from RCS (2RH2 is prefened, 2RHI is backup).

2.

ENSURE 2RP4 lockout switch for 2SJ69, RHR SUCTION FROM RWST, in VALVE OPERABLE. (Control Room)

3.

OPEN 2SJ69, RRR SUCTION FROM RWST.

4.

Send operator to: [C0329] [C0658]

a.

OPEN 2RH81 AND 2RH82, RHR Suction Line second high point vent, until steady stream of water flows (mechanical penetration area 78' elevation).

b.

IF the bioshield area inside containment is accessible, THEN OPEN 2RR68 AND 2RH69, RHR Suction Line first high point vent, until steady stream of water flows.

5.

SEND an Operator to the RHR Pump Room in preparation for pump start. (step continued on next page) Salem 2 Page 67 of 100 Rev.!7

ATTACHMENT 7 (Page 4 of5) HOT LEG INJECTION S2.0P-AB.RHR-0001(Q) 7.A (continued)

6.

CLOSE 2SJ69, RHR Suction From RWST.

7.

OPEN 2RHl AND 2RH2, RHR Suction from RCS.

8.

Notify Operator in RHR Pump area to MONITOR the pump for abnormal conditions after the pump is started. B. IF the RRR system requires alignment, THEN START one RHR Pump as follows: IF alternate RHR Loop is aligned for ECCS, THEN PERFORM Attachment 2, Aligning RHR Loop From BCCS To Shutdown Cooling. IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attaclunent 3, Aligning RHR Loop For Shutdown Cooling, C. IF RRR System is ready for normal operation, THEN RETURN to service IA W S2.0P-SO.RHR-OOOl(Q), Initiating RHR. 8.0 When RHR is restored, REMOVE Hot Leg Injection from service as follows: A. STOP any running Safety Injection Pumps. B. CLOSE HOT LEG DISCHARGE valves: 21SJ40 22SJ40 C. PLACE 2RP4 Lockout Switch for 28J3 0, R WST TO 81 SUCTION VAL VB, in VALVE OPERABLE. (Continued on next page) Salem 2 Page 68 of 100 Rev. 17

8.0 (continued) ATTACHMENT 7 (Page 5 ofS) HOT LEG INJECTION D. CLOSE 2S130, Suction From RWST. s2.OP-AB.RHR-OOOI CQ) E. ENSURE the SI PUMP DISCH V ALVEs are Fully Open: 21SJ35 22S135 9.0 CLOSE the Reactor Head Vent Solenoid Valves: 2RC40 2RC41 2RC42 2RC43 10.0 RETURN to procedure step in effect. Salem 2 Page 69 of 100 Rev. 17

S2.0P~AB.RHR-0001(Q) ATTACHMENT 8 (page 1 of7) COLD LEG INJECTION (preferred method RCS < 200°F) CAUTION + Only Borated water should be added to the RCS to maintain adequate Shutdown Margin. + Any opening in the ReS boundary could result in release of high temperature fluids, radioactive water, or gases to Containment. + Violation of Technical Specification 3.5.3 requires notifications lAW ECG. 1.0 MAKEUP to the RCS as follows: A. IF the BIT flowpath AND a Charging Pump is available, THEN ALIGN feed path to the RCS as follows:

1.

OPEN RWST outlet to Charging Pumps: 28J1 2SJ2

2.

CLOSE VCT outlet to Charging Pumps: 2CV40 2CV41

3.

IF both Centrifugal Charging Pumps are tagged out, THEN send Operator to RELEASE breaker for one Centrifugal Charging Pump. CAUTION When the PS25 is the vent path, maximum flow of <300 gpm is required when steam generator nozzle dams are installed. This may be controlled by throttling the pump discharge valve. Salem 2

4.

START the designated available Charging Pump AND FEED at maximum rate by aligning the following valves in the Cold Leg Injection flow path: OPEN BIT INLET: 28J4 or 28J5 OPEN BIT OUTLET: 28J1Z or 28J13 CLOSE Charging Discharge Isolation Valves: 2CV68 OR2CV69 Page 70 of 100 Rev. 17

ATTACHMENT 8 (Page 2 of 7) COLD LEG INJECTION S 2.0 P~AB.RHR-OOOI (Q) 1.0 (continued) B. IF BIT flowpath and Charging Pump is NOT available, AND a Safety Injection Pump with a Cold Leg Injection path is available, THEN ALIGN feed path to the RCS as follows:

1.

ENSURE OPEN RWST TO SI PUMP valves: + PLACE 2RP410ckout switch in VALVE OPERATE AND OPEN 2SJ30 + 21SJ33 OR 22SJ33 associated with the available SI Pump 28J67 AND 2SJ68, SI PMP RECIRC VALVES

2.

IF both Safety fujection Pumps are tagged out, THEN send Operator to RELEASE breaker for one Safety Injection Pumps. CAUTION When the PS25 is the vent path, maximum flow of <300 gpm is required when steam generator nozzle dams are installed. This may be controlled by throttling the pump discharge valve. Salem 2

3.

START the designated available Safety Injection Pump AND FEED at maximum rate by aligning the following valves in the Cold Leg Injection flow path: OPEN 21SJ134 OR 22SJ134 associated with the available SI Pump PLACE 2RP4 lockout switch in VALVE OPERATE AND OPEN 2SJl35 CLOSE 28J67 AND 2SJ68, SI PMP RECIRC VALVES C. CONTINUE feeding ReS at maximum rate until one of the following occurs:

1.

RHR is restored.

2.

Pressurizer level is ~50% cold calibration.

3.

Flow from any RCS opening is adequate to result in lowering Core Exit Thermocouple temperatures. Page 71 of 100 Rev. 17

S2.0P-AB.RHR-OOOl(Q) ATTACHMENT 8 (Page 3 of7) COLD LEG INJECTION D. When any of the above conditions in Step I.e are satisfied: CONTROL injection flow by using nonnal charging to minimize flow to containment while maintaining Core Exit Thermocouples stable or lowering. CYCLE BIT isolation valves to control flow to the Res: BIT INLET: 2SJ4 OR 2SJ5 BIT OUTLET: 2SJ12 OR 2SJ13 OR OPEN 2SJ67 AND 2SJ68, SI PMP RECIRC VALVES valves AND CYCLE 2SJ135 to control flow to the RCS. E. IF Core Exit Thennocouples are NOT available, THEN MAINTAIN injection flow determined in Attachment 6, Makeup Rate Required to Refill Res After Loss ofRHR. 2.0 INFORM Containment personnel that high temperature fluids, contamination, and airborne activity will exist at any RCS openings. 3.0 IF Service Water is available, THEN START all available CFCUs in slow speed to minimize Containment pressure rise. (continued on next page) Salem 2 Page 72 of 100 Rev. 17

S2.0P-AB.RHR-0001(Q) ATTACHMENT 8 (Page 4 of7) COLD LEG INJECTION 4.0 ALIGN bleed path by perfOlming ONE of the following: A. VERIFY a 0.5 ft2 or greater hot leg vent path exists: (circle path verified) All Pressurizer Safety Valves removed Pressurizer Manway removed Vent path determined by System Manager B. OPEN the following valves: 2PR1, Pressurizer PORV, AND 2PR6, Block Valve for 2PRl 2PR2, Pressurizer PORV, AND 2PR7, Block Valve for 2PR2

Reactor Head Vent Solenoid Valves:

2RC40 2RC41 2RC42 2RC43 5.0 MAINTAIN feed and bleed ofthe RCS until RHR is restored or other methods of decay heat removal are utilized. Salem 2 Page 73 of 100 [C03291 Rev. 17

s2.OP~AB.RHR~OOOl (Q) ATTACHMENT 8 (Page 5 of7) COLD LEG INJECTION 6.0 When RHR becomes available, THEN RETURN RHR to service lAW the following; A. IF the RHR system requires venting THEN VENT RHR Pumps and piping; CAUTION + Venting the RHR system may cause a reduction in ReS level requiring more makeup flowrate. + Any opening in the ReS boundary could result in release of high temperature fluids, radioactive water, or gases to Containment. + Opening 2SJ69 aligns the RWST to RHR and may result in RCS level rise.

1.

ISOLATE RHR Suction from RCS, CLOSE 2RHl OR 2RH2, RHR Suction from RCS (2RH2 is preferred, 2RHI is backup),

2.

ENSURE 2RP410ckout switch for 2SJ69, RHR SUCTION FROM RWST, in VALVE OPERABLE.

3.

OPEN 2SJ69, RHR SUCTION PROM RWST.

4.

Send operator to: [C0329} [C06581

a.

OPEN 2RH81 AND 2RH82, RHR Suction Line second high point vent, until steady stream of water flows (mechanical penetration area 78' elevation).

b.

IF the bioshield area inside containment is accessible, THEN OPEN 2RH68 AND 2RH69, RHR Suction Line first high point vent, until steady stream of water flows.

5.

SEND an Operator to the RHR Pump Room in preparation for pump start.

6.

CLOSE 2SJ69, RHR Suction From RWST. (step continued on next page) Salem 2 Page 74 of 100 Rev. 17

S2.0P-AB.RHR-OOOl(Q) ATTACHMENT 8 (Page 6 of7) COLD LEG INJECTION 6, 4.A (continued)

7.

OPEN 2RHI AND 2RH2, RHR Suction from ReS.

8.

Notify Operator in RHR Pump area to MONITOR the pump for abnormal con,clitions after the pump is started. B. IF the RHR system requires alignment, THEN START one RHR Pump as follows: IF alternate RHR Loop is aligned for EeeS, THEN PERFORM Attachment 2, Aligning RHR Loop From BCCS To Shutdown Cooling. IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown'Cooling. C. IF RHR System is ready for normal operation, THEN RETURN to service JAW S2.0P-SO.RHR-0001(Q), Initiating RHR. 7.0 WHEN RHR is restored, REMOVE Cold Leg Injection from service as follows: A. STOP any running Charging Pumps OR Safety Injection Pumps. B. CLOSE Charging Header OR Safety Injection Header Stop Valves for Cold Leg Injection: 2SJ4, INLET TO BIT 2SJ5, INLET TO BIT 2SJ12, BIT OUTLET + 2SJ13, BIT OUTLET 21SJ134 AND 22SJ134, SI Pump Discharge to Cold Leg 2SJl35, SI Pump Discharge to Cold Leg (step continued on next page) Salem 2 Page 75 of 100 Rev. 17

ATTACHMENT 8 (Page 7 of7) COLD LEG INJECTION 7,5.0 (continued) C. OPEN VCT Outlet to Charging Pumps: 2CV40 2CV41 D. CLOSE RWST Outlet to Charging Pumps: 2SJ1 28J2 E. OPEN Charging Discharge Isolation Valves: 2CV68 2CV69 8.0 CLOSE Reactor Head Vent Solenoid Valves: 2RC40

2RC41 2RC42
2RC43 9.0 RETURN to procedure step in effect.

Salem 2 Page 76 of 100 S2.0P-AB.RHR-OOOl(Q) Rev. 17

S2.0P-AB.RHR~OOOl(Q) ATTACHMENT 9 (Page 1 of 5) STEAM GENERATOR REFLUX COOLING NOTE Motor operated valves may need to be manually operated. CAUTION Only Borated water should be added to the ReS to maintain adequate Shutdown Margin. Any opening in the ReS boundary could result in release of radioactive water or gases to Containment. 1.0 ALIGN the RWST to gravity feed the RCS using one of the following methods: Salem 2 A. RWST To RHR Suction (Preferred) OR

1.

PLACE 2RP41ockout switch for 2SJ69, RHR Suction From RWST in VAL VB OPERABLE.

2.

OPEN 2SJ69, RHR Suction From RWST. B. Throttle OPEN 2RH21 to allow flow through RH19s and SJ49s. OR C. RWSTToHotLeg:

1.

CLOSE RHR HX DISCH X-CONN valves: 21RH19 22RH19 2RH20

2.

PLACE 2RP4 lockout switch for 2RH26, HOT LEG ISO VALVE in VALVE OPERABLE.

3.

OPEN 2RH26, HOT LEG ISO VALVE.

4.

Throttle OPEN 2RH21, RHR TO RWST STOP VALVE. Page 77 of 1 00 Rev. 17

S2.0PMAB.RHRM0001(Q) ATTACHMENT 9 (Page 2 of 5) STEAM GENERATOR REFLUX COOLING NOTE To maintain ReS pressure low enough for gravity feed from RWST, at least two Steam Generators must be available as heat sinks using reflux cooling. 2.0 ENSURE at least two Steam Generators are aligned for heat sink using reflux cooling as follows: Steam Generator nozzle dams removed Primary and secondary manways and hand holes installed Steam Generator contains water or can be filled 3.0 FEED available Steam Generators to maintain wide range level >77% using Auxiliary Feedwater System OR Condensate System. 4.0 REMOVE decay heat by performing one of the following: OPERATE the appropriate MSlOs to maintain Core Exit Thennocouples stable or lowering. DRAIN the Steam Generators as required to maintain level <95% wide range. 5.0 NOTIFY Containment personnel that high temperature fluids, contamination, and airborne activity will exist at any Res openings. 6.0 IF Service Water is available, THEN START all available CFCUs in slow speed to minimize Containment pressure rise. 7.0 OPEN Reactor Head Vent Solenoid Valves: 2RC40 2RC42 Salem 2 2RC41 .' 2RC43 Page 78 of 100 [C03291 Rev. 17

S2.0P-AB,RHR-0001(Q) ATTACHMENT 9 (Page 3 of 5) STEAM GENERATOR REFLUX COOLING 8.0 MAINTAIN reflux cooling of the RCS until RHR is restored or other methods of decay heat removal are utilized. 9.0 When RHR becomes available, THEN RETURN RHR to service as follows: A. IF the RHR system requires venting THEN VENT RHR Pumps and piping: CAUTION Venting the RHR system may cause a reduction in RCS fevel requiring more makeup flowrate. Any opening in the RCS boundary could result in release of high temperature fluids, radioactive water, or gases to Containment. Opening 2SJ69 aligns the RWST to RHR and may result in ReS fevel rise.

1.

ISOLATE RHR Suction from ReS, CLOSE 2RHI OR 2RH2, RHR Suction from ReS (2RH2 is preferred, 2RHI is backup).

2.

ENSURE 2RP41ockout switch for 2SJ69, RHR SUCTION FROM RWST, in VALVE OPERABLE.

3.

OPEN 2SJ69, RHR SUCTION FROM RWST.

4.

Send operator to: [C0329] [C0658}

a.

OPEN 2RH81 AND 2RH82, RHR Suction Line second high point vent, until steady stream of water flows (mechanical penetration area 78' elevation).

b.

IF the bioshield area inside containment is accessible, THEN OPEN 2RH68 AND 2RH69, RHR Suction Line first high point vent, until steady stream of water flows. (step continued on next page) Salem 2 Page 79 of 100 Rev. 17

S2.0P-AB.RHR~OOOl(Q) 9.0 (Continued) ATTACHMENT 9 (Page 4 ofS) STEAM GENERATOR REFLUX COOLING

5.

SEND an Operator to the RHR Pump Room in preparation for pump start.

6.

CLOSE 2SJ69, RHR Suction From RWST.

7.

OPEN 2RH1 AND 2RH2, RHR Suction from RCS.

8.

Notify Operator in RHR Pump area to MONITOR the pump for abnormal conditions after the pump is started. B. IF the RHR system requires alignment, THEN START one RHR Pump as follows: IF alternate RHR Loop is aligned for ECCS, THEN PERFORM Attachment 2, Aligning RHR Loop From ECCS To Shutdown Cooling. IF alternate RHR Loop is aligned for Shutdown Cooling, THEN PERFORM Attachment 3, Aligning RHR Loop For Shutdown Cooling. C. IF RHR System is ready for normal operation, THEN RETURN to service IA W S2.0P~SO.RHR-OOOl (Q), Initiating RHR. 10.0 When RHR is restored, SECURE Gravity Feed Path as follows: A. CLOSE 2SJ69, RHR Suction From RWST. B. CLOSE the following valves, if aligned for gravity feed: 2RH21,RHR TO RWST STOP VALVE 2RH26, HOT LEG ISOLATION VALVE C. ENSURE 21RH19 and 22RH19 valves are OPEN. Salem 2 Page 80 of 100 Rev. 17

S2.0P-AB,RHR-OOOl(Q) ATTACHMENT 9 (Page 5 of 5) STEAM GENERATOR REFLUX COOLING 11,0 CLOSE Reactor Head Vent Solenoid Valves: + 2RC40 2RC42

2RC41
2RC43 12.0 RESTORE Steam Generator level to the level directed by the SM/CRS AND INITIATE securing the feeding and draining of Steam Generators LAW appropriate procedures.

13.0 CLOSE any MS 1 as NOT required for decay heat removal, as directed by the SMICRS. 14.0 RETURN to procedure step in effect. Salem 2 Page 81 of 100 Rev. 17

S2.0P-AB.RHR-0001(Q) ATTACHMENT 10 (Page 1 of 1) FORCED FLOW OR NATURAL CIRCULATION COOLDOWN 1.0 FEED available Steam Generators to maintain wide range level >77% using Auxiliary Feedwater System or Condensate System. 2.0 REMOVE reactor decay heat by performing one of the following: OPERATE the appropriate MSIOs to maintain Core Exit Thermocouples stable or lowering. DRAIN Steam Generators as required to maintain level <95% wide range. 3.0 IF forced flow cooling ofthe RCS is desired, THEN OPERATE Reactor Coolant Pumps lAW S2.0P-SO.RC-OOOl(Q), Reactor Coolant Pump Operation. 4.0 IF Natural Circulation Cooldown is desired, THEN VERIFY Natural Circulation by maintaining the following parameters: ReS subcooling based on Core Exit Thermocouples >oop Core Exit Thermocouples stable or lowering + Steam Generator pressures stable or lowering RCS Hot Leg temperatures stable or lowering ReS Cold Leg temperatures at saturation temperature for Steam Generator pressure 5.0 CONTINUE RCS cooling using Steam Generators until RHR System is restored. OPERATE the appropriate MSIOs to maintain Core Exit Thermocouples stable or lowering. DRAIN the Steam Generators as required to maintain level <95% wide range. 6.0 RETURN to procedure step in effect. Salem 2 Page 82 of 100 Rev. 17

82.OP-AB.RHR-OOOI (Q) ATTACHMENT 11 (Page 1 of 1) COOLING THE ReS WITH SPENT FUEL POOL NOTE Cooling RCS with Spent Fuel Pool is available only when the Reactor Head is removed. CAUTION Only Borated water should be added to the RCS to maintain adequate Shutdown Margin. 1.0 IF the Fuel Transfer Tube Blank Flange is installed, THEN REMOVE the Fuel Transfer Tube Blank Flange. 2.0 INITIATE flooding the Refueling Cavity IA W S2.0P-SO.SF-0003(Q), Filling the Reactor Refueling Cavity. 3,0 RAISE cooling of the Spent Fuel Pool to maximum IA W S2.0P.SO.SF-0002(Q), Spent Fuel Cooling Operation. 4.0 RAISE Reactor Refueling Cavity Filtering and Purification flow to maximum IA W S2.0P*SO.SF-0005(Q), Refueling Water Purification System Operation. 5.0 SEND an Operator to the Fuel Transfer Tube Gate Valve. 6.0 When Reactor Cavity AND Spent Fuel Pool1evels are equalized at ~23 fl. water level, OPEN the Fuel Transfer Tube Gate Valve. 7.0 INFORM Containment personnel that contamination and airborne activity will exist at any RCS openings. 8.0 IF Service Water is available, THEN START all available CFCUs in slow speed to minimize Containment pressure rise. 9.0 MAINTAIN Spent Fuel Pool Cooling of the RCS until RHR is restored or other methods of decay heat removal are utilized. 10.0 When RHR is restored~ RETURN Spent Fuel Pool Cooling to normal operation lAW S2.0P-SO,SF-0002(Q), Spent Fuel Cooling System Operation. 11.0 RETURN to procedure step in effect. Salem 2 Page 83 of 100 Rev. 17

S2.0P~AB.RHR~OOOl(Q) ATTACHMENT 12 (Page 1 of 6) ALTERNATE COOLING WATER 1.0 Prior to aligning the alternate cooling water supply, STOP the affected pump normally cooled by Service Water. NOTE DM cooling supply hoses-are to be furnished with double check valves. DM cooling discharge hoses are to be directed to the closest available floor drain and securely fastened to prevent hoses from comin dislod ed from the drain. 2.0 INSTALL Demineralized Water supply hoses with double check valves between the applicable DR Header Connection Valves: Component Connected From Connected To Initials 21 RHR PUMP MECH SEAL HEAT EXCH 2DR47 SUPPLY HOSE (21 RHRHx Rm. 21CC22 E1. 55') 21 RHR PUMP MECH SEAL HEAT EXCH 21CC220 DISCHARGE HOSE (21 RHR Valve Floor Drain Rm, E1. 55') 22 RHR PUMP MECH SEAL HEAT EXCH 2DR48 SUPPLY HOSE (22 RHR HX Rm, 22CC22 EI. 55') 22 RHRPUMPMECRSEAL HEAT EXCH 22CC220 DISCHARGE HOSE (22 RHR Valve Floor Drain Rm, El. 55') 21 & 22 CRG PUMPS MECH SEAL HX & 2DR39 GLAND COOLER SUPPLY HOSE (By CS Tank, 2CC106 E1. 84') 21 CHG PUMP MECH SEAL HX & GLAND 2CC239 Floor Drain COOLER DISCHARGE HOSE 22 CHG PUMP MECH SEAL HX & GLAND 2CC231 Floor Drain COOLER DISCHARGE HOSE 22 CHG PUMP LUBE OIL COOLER & GEAR 2DR38 OIL COOLER SUPPLY HOSE (Cone Hold Tank 2SW201 Area. El. 84") Salem 2 Page 84 of 100 Rev. 17

S2.0P-AB.RHR-OOOl(Q) ATTACHMENT 12 (Page 2 of 6) ALTERNATE COOLING WATER Component Connected From 22 CHG PU;vrF LUBE OIL COOLER & GEAR OIL 22SW961 COOLER DISCHARGE HOSE 22 SAFETY INJECTION PUMP LUBE OIL 2DR36 COOLER SUPPLY HOSE (CCHX Corr, El.84') 22 SAFETY INJECTION PUMP LUBE OIL 2SW166 COOLER DISCHARGE HOSE 21 CHG PUMP LUBE OIL COOLER & GEAR OIL 2DR38 COOLER SUPPLY HOSE (Cone Hold Tank Area, E1. 84 ") 21 CHG PUMP LUBE OIL COOLER & GEAR OIL 21SW952 COOLER DISCHARGE HOSE 21 SAFETY INJECTION PUMP LUBE OIL 2DR36 COOLER SUPPLY HOSE (CCHXCorr, E1. 84') 21 SAFETY INJECTION PUMP LUBE OIL 2SW172 COOLER DISCHARGE HOSE Connected To Initials Floor Drain 2SW165 Floor Drain 2SW187 Floor Drain 2SW171 Floor Drain 3.0 CROSS-TIE the Component Cooling System Header to supply 21 and 22 Safety Injection Pump Seal Water Heat Exchanger by removing lock AND opening 2CC318, CC Cross-Tie Valve. Salem 2 Page 85 of 100 Rev. 17

S2.0P-AB.RHR-0001(Q) ATTACHMENT 12 (Page 3 of 6) ALTERNATE COOLING WATER 4.0 REPOSITION valves as required to run pumps, from the normal cooling position to the alternate cooling position as shown: NORMAL COOLING ALTERNATE COMPONENT POSITION COOLING POSITION 21 Charging Pump Lube Oil Cooler & Gear Oil Cooler 2DR38, DR Header Hose Connection Closed Open 21SW956, SW Inlet Valve Open Closed 21SW955, SW Outlet Valve Open Closed 2SW187, SW Inlet Drain Closed Open 21SW952, SW Outlet Drain Closed Open 22 Charging Pump Lube Oil Cooler & Gear Oil Cooler 2DR38, DR Header Hose Connection Closed Open 22SW960, SW Inlet Valve Open Closed 22SW959, SW Outlet Valve Open Closed 2SW201, SW Inlet Drain Closed Open 22SW961, SW Outlet Drain Closed Open 21 Safety Injection Pump Lube Oil Cooler 2DR36, DM Supply Valve Closed Open 2SW160, Inlet to Cooler Locked Open Closed . 2SW220, Outlet fonn Cooler Open Closed 2SW171, Inlet Drain Closed Open 2SWl72, Outlet Vent Closed Open 2SW513, SI Pmp Rm Clr SW Inlet Valve Open Closed Salem 2 Page 86 of 100 Rev. 17

S2.0P-AB,RHR-0001(Q) ATTACHMENT 12 (Page 4 of 6) ALTERNATE COOLING WATER COMPONENT NORMAL COOLING ALTERNATE COOLING POSITION POSITION 22 Safety Injection Pump Lube Oil Cooler 2DR36, DM Supply Valve Closed Open 2SW162, Inlet to Cooler Locked Open Closed 2SW181, Outlet form Cooler Open Closed 2SW165, Inlet Drain Closed Open 2SW166, Outlet Vent Closed Open 21 RHR Pump Mechanical Seal Heat Exchanger 2DR47, DR HEADER HOSE Closed Open CONNECTION Valve 21CC21, CC hl1et Valve Open Closed 21 CC23, CC Outlet Valve Open Closed 21CC42, CC Inlet Drain Closed Open 21 CC220, CC Outlet Drain Closed Open 22 RHR Pump Mechanical Seal Heat Exchanger 2DR48, DR HEADER HOSE Closed Open CONNECTION Valve 22CC21, CC Inlet Valve Open Closed 22CC23, CC Outlet Valve Open C10sed 22CC22, CC Inlet Drain Closed Open 22CC220, CC Outlet Drain Closed Open Salem 2 Page 87 of 100 Rev. 17

s2.OP~AB.RHR~OOOI (Q) ATTACHMENT 12 (Page 5 of 6) ALTERNATE COOLING WATER COMPONENT NORMAL COOLING ALTERNATE COOLING POSITION POSITION 21 Charging Pump Mechanical Seal Heat Exchanger & Gland Cooler 2DR39, DR Header Hose Closed Open Connection 2CC318, CC Cross~tie Valve Locked Closed Open 2CC 1 OS, CC Inlet Valve Open Open 2CC107, CC Outlet Valve Open Closed 2CC97, CC Inlet Valve Open Closed 2CC214, CC Header Outlet Open Closed 2CC106, CC Inlet Drain Closed Open 2CC239, CC Outlet Drain Closed Open 22 Charging Pump Mechanical Seal Heat Exchanger & Gland Cooler 2DR39, DR Header Hose Closed Open Connection 2CC318, CC Cross~tie Valve Locked Closed Open 2CC319, CC Inlet Valve Open Closed 2CCI03, CC Outlet Valve Open Closed 2CC97, CC Inlet Valve Open Closed 2CCI05, CC Inlet Valve Open Open 2CCI07, CC Outlet Valve Open Closed 2CC214, CC Header Outlet Open Closed 2CCI06, CC Inlet Drain Closed Open 2CC231, CC Outlet Drain Closed Open Salem 2 Page 88 of 100 Rev. 17

s2.OP-AB.RHR-OOOI (Q) ATTACHMENT 12 (Page 6 of 6) ALTERNATE COOLING WATER 5.0 INSTALL AND OPERATE fans in the following pump rooms for additional cooling as required: I PUMP ROOM I NUMBER OF FANS REQUIRED I Component Cooling Water Pump 2 Residual Heat Removal Pumps 2 Contairunent Spray Pumps 1 Safety Injection Pumps 1 Charging Pumps 1 Spent Fuel Pool Cooling Pumps 1 6.0 CLOSE the following balancing dampers between the Auxiliary Building Ventilation System and the RHR area and 21 & 22 Smnp Tank Pumps. A. 2VHE728 (Elev 55 RHR Valve Room) B. 2VHE731 (Aux Bldg Sump Tk Rm) 7.0 RETURN to Procedure Step 3.7 to remove decay heat until Service Water is restored. 8.0 WhenService Water is restored: A. REPOSITION valves on components aligned for alternate cooling to the nonnal cooling position, unless directed by S2.0P-SO.SW-0002(Q) or S2.0P-SO.SW-0003(Q). B. Direct a second Operator to PERFORM an Independent Verification on valves or components repositioned to the "NORMAL COOLING POSITION". Salem 2 C. REMOVE alternate cooling and drain hoses installed for alternate cooling and return to storage, unless directed by S2.0P-SO.SW-0002(Q) OR S2.0P"SO.SW"0003(Q). D. REMOVE portable fans installed in pwnp rooms and return to storage, unless required by another procedure. E. RETURN Auxiliary Building Ventilation System balancing dampers to normal position. 2VHE728 (Elev 55 RHR Valve Room) 2VHE731 (Aux Bldg 8mnp Tk RIn) Page 89 of 100 Rev. 17

ATTACHMENT 13 (Page 1 of2) COLD LEG RECIRCULATION 1.0 IF an intact RHR Train is available, THEN: A. s2.OP-AB.RHR-OOOl (Q) VERIFY Containment Sump level ~62%. (adequate water supply for Cold Leg Recirculation) [C0354] Salem 2 B. CLOSE 2RH21, RHR to RWST Stop Valve. C. ALIGN intact RHR train to Containment Sump as follows:

1.

PLACE 2RP4 lockout switch for 2S169, RHR Suction From RWST in VALVE OPERABLE.

2.

CLOSE 28J69, RHR Suction From RWST.

3.

CLOSE RH4, RHR Pump Suction Valve, on intact RHR Train.

4.

OPEN 8J44, CONT SUMP SUeT VALVE. on intact RHR train.

5.

PLACE 2RP410ckout switch for SJ49, RHR Discharge to Cold Legs, on intact RHR train in VAL VB OPERABLE.

6.

OPEN SJ49, RHR Discharge to Cold Legs, on intact RHR train.

7.

CLOSE RHI8, RHR HX Flow Control Valve, on intact RHR train.

8.

CLOSE 2RH20, RHR HX Bypass Control valve.

9.

ENSURE applicable RH29, RHR PUMP MINIMUM FLOW VALVE in AUTO.

10.

START intact RHR Pump to transfer to Cold Leg Recirculation.

11.

IF Hot Leg Injection is in service, THEN:

a.

STO P any running Safety Inj ection Pumps.

b.

CLOSE 218J40 AND 22SJ40, HOT LEG DISCHARGE valves. Page 90 of 100 Rev. 17

S2.0P-AB.RHR-0001(Q) ATTACHMENT 13 (Page 2 of2) COLD LEG RECIRCULATION

12.

IF Cold Leg Injection is in service, THEN:

a.

STOP any running Charging Pumps.

b.

CLOSE Charging Header Stop Valves for Cold Leg Injection:

28J4, Inlet to BIT
28J5, Inlet to BIT

+ 28J 12, BIT Outlet

28J13, BIT Outlet

13.

OPEN CV68 and CV69, Charging Discharge Isolation Valves.

14.

THROTTLE the following valves to control RCS level: Applicable RH18 for intact RHR train 2RH20, RHR HX Bypass Control valve

15.

RETURN to procedure step in effect. 2.0 IF an intact RHR Train is NOT available, THEN: Salem 2 A. ESTABLISH an alternate decay heat removal method:

, Steam Generator Reflux Cooling (RCS depressurized and RCPs NOT available)
0, Forced Flow Or Natural Circulation Cooldown (RCS intact and filled to >0% in the Pressurizer) 1, Cooling the RC8 with Spent Fuel Pool (Reactor Vessel Head Removed)

B. SECURE Hot Leg injection. C. SECURE Cold Leg injection. D. RETURN to procedure step in effect. Page 91 of 100 Rev. 17

s2.OP-AB.RHR-0001 (Q) ATTACHMENT 14 (Page 1 of 6) 2R16 COLD LEG INJECTION (Prior to Filling Cavity to > 125' 6") NOTE One Airlock should remain open until notified by Maintenance that the Equipment Hatch Ventilation Barrier (EHVB) is closed. 1.0 CLOSE the following valves: 2VC1, CONT PURGE SUPPLY ISOL VLV 2VC2. CONT PURGE SUPPLY ISOL VLV (as applicable) 2VC3, CONT PURGE EXHAUST ISOL VLV (as applicable) 2VC4, CONT PURGE EXHAUST ISOL VLV Salem 2 Page 92 of 100 Rev. 17

s2.OP~AB.RHR~OOOI (Q) ATTACHMENT 14 (Page 2 of6) 2R16 COLD LEG INJECTION (Prior to Filling Cavity to> 125' 6") CAUTION + Only Borated water should be added to the RCS to maintain adequate Shutdown Margin. + Any opening in the RCS boundary could result in release of high temperature fluids, radioactive water, or gases to Containment. + Violation of Technical Specification 3.5.3 requires notifications lAW ECG. 2.0 MAKEUP to the RCS as follows: A. 1F the BIT flowpath AND a Charging Pump is available, THEN ALIGN feed path to the RCS as follows:

1.

OPEN RWST outlet to Charging Pumps: 28J1 28J2

2.

CLOSE VCT outlet to Charging Pumps: 2CV40 2CV41

3.

IF both Centrifugal Charging Pumps are tagged out, THEN send Operator to RELEASE breaker for one Centrifugal Charging Pump. C0354

4.

ST ART the designated available Charging Pump AND FEED at maximum rate (> 520 gpm) by aligning the following valves in the Cold Leg Injection flow path: OPEN BIT INLET: 28J4 AND 2SJ5 OPEN BIT OUTLET: 2S112 AND 2SJ13 CLOSE Charging Discharge Isolation Valves: 2CV68 OR 2CV69 CLOSE Charging Pump Miniflow Valves: 2CV139 AND 2CV140 (step continued on next page) Salem 2 Page 93 of 100 Rev.!7

ATTACHMENT 14 (Page 3 of 6) 2R16 COLD LEG INJECTION (Prior to Filling Cavity to> 125 t 6 1t ) 2.0 (continued) B. bE BIT flowpath and Charging Pump is NOT available~ AND a Safety Injection Pump with a Cold Leg Injection path is available~ THEN ALIGN feed path to the RCS as follows:

1.

ENSURE OPEN RWST TO 81 PUMP valves: PLACE 2RP41ockout switch in VALVE OPERATE AND OPEN 2S]30 218J33 OR 228J33 associated with the available SI Pump 2SJ67 AND 2SJ68, SI PMP RECIRC VALVES

2.

IF both Safety Injection Pumps are tagged out, THEN send Operator to RELEASE breaker for one Safety Injection Pump.

3.

START the designated available Safety Injection Pump AND FEED at maximum rate (> 520 gpm) by aligning the following valves in the Cold Leg Injection flow path: OPEN 21 SJ134 OR 22SJ134 associated with the available 8I Ptunp PLACE 2RP4 lockout switch in V ALVE OPERATE AND OPEN 281135 CLOSE 28J67 AND 2SJ68, 81 PMP RECIRC VALVES C. OPEN the following valves: + 2PRl 2PR2 + 2PR6 2PR7 (step continued on next page) Salem 2 Page 94 of 100 Rev. 17

S2.0P~AB.RHR~OOOl(Q) ATTACHMENT 14 (Page 4 of 6) 2R16 COLD LEG INJECTION (Prior to Filling Cavity to > 125' 6") 2.0 (continued) D. OPERATE at least 2 CFCU's in HIGH SPEED with a Service Water Flow of ~ 2500 gpm, as required, to maintain Containment Differential Pressure < 0.5 psid. E. CONTINUE feeding RCS at maximum rate until one ofthe following occurs: 1, RHR is restored.

2.

The Inner Equipment Hatch is installed with a minimum of four bolts. F. When any of the above conditions in Step 2.E are satisfied: CONTROL injection flow by using normal charging to minimize flow to contairunent while maintaining Core Exit Thermocouples stable or lowering. CYCLE BIT isolation valves to control flow to the RCS: BIT INLET: 28J4 OR 2SJ5 BIT OUTLET: 2SJ12 OR 2SJl3 OPEN 2SJ67 AND 28J68, S1 PMP RECIRC VALVES valves AND CYCLE 2SJ135 to control flow to the RCS. G. IF. Core Exit Thermocouples are NOT available, THEN MAINTAIN injection flow detennined in Attachment 6, Makeup Rate Required to Refill ReS After Loss ofRHR. 3.0 INFORM Containment personnel that high temperature fluids, contamination, and airborne activity will exist at any ReS openings. Salem 2 Page 95 of 100 Rev. 17

S2.0P~AB.RHR-0001(Q) ATTACHMENT 14 (Page 5 of 6) 2R16 COLD LEG INJECTION (Prior to Filling Cavity to> 125' 6 11 ) 4.0 When RHR becomes available, THEN RETURN RHR to service IA W the following: A. IF the RHR system requires venting THEN VENT RHR Pumps and piping: [C0329] CAUTION + Venting the RHR system may cause a reduction in ReS level requiring more makeup flowrate. + Any opening in the RCS boundary could result in release of high tempera.ture fluids, radioactive water, or gases to Containment. + Opening 2SJ69 aligns the RWST to RHR and may result in RCS level rise.

1.

ISOLATE RHR Suction from RCS, CLOSE 2RHl OR 2RH2, RHR Suction from RCS (2RH2 is preferred, 2RHI is backup).

2.

ENSURE 2RP4lockout switch for 2SJ69, RHR SUCTION FROM RWST, in VALVE OPERABLE.

3.

OPEN 2SJ69, RHR SUCTION FROM RWST.

4.

Send operator to: [C0658]

a.

OPEN 2RH81 AND 2RH82, RHR Suction Line second high point vent, until steady stream of water flows (mechanical penetration Salem 2 area 78' elevation).

h.

IF the bioshield area inside containment is accessible, THEN OPEN 2RH68 AND 2RH69, RHR Suction Line first high point vent, until steady stream of water flows.

5.

SEND an Operator to the RHR Pump Room in preparation for pump start.

6.

CLOSE 2SJ69, RHR Suction From RWST.

7.

OPEN 2RHI AND 2RH2, RHR Suction from ReS.

8.

Notify Operator in RHR Pump area to MONITOR the pump for abnormal conditions after the pump is started. B. START one RHR Pump IA W Attachment 3, Aligning RHR Loop For Shutdown Cooling. Page 96 of 100 Rev. 17

5.0 6.0 Salem 2 S2.0P-AB,RHR-0001(Q) ATTACHMENT 14 (Page 6 of 6) 2R16 COLD LEG INJECTION (Prior to Filling Cavity to > 125' 6") WHEN RHR is restored, REMOVE Cold Leg Injection from service as follows: A. STOP any running Charging Pumps OR Safety Injection Pumps. B. CLOSE Charging Header OR Safety Injection Header Stop Valves for Cold Leg Inj ection:

2SJ4, INLET TO BIT 2SJ 5, INLET TO BIT
2SJ12, BIT OUTLET
2SJ13, BIT OUTLET
21SJ134 AND 22SJ134, SIPump Discharge to Cold Leg 2SJ135, SI Pump Discharge to Cold Leg C.

OPEN VCT Outlet to Charging Pumps:

2CV40
2CV41 D.

CLOSE RWST Outlet to Charging Pumps:

2SJI
2SJ2 E.

OPEN Charging Discharge Isolation Valves: 2CV68

2CV69 2CV139 AND 2CV140, Charging Pump Miniflow Valves RETURN to procedure step in effect.

Page 97 of 100 Rev. 17

S2.0P-AB.RHR-OOOl(Q) ATTACHMENT 15 (Page 1 of 2) COMPLETION SIGN*OFF SHEET 1.0 COMMENTS (Include procedure deficiencies and corrective actions. Attach additional pages as necessalY.) SaJem 2 Page 98 of 100 Rev. 17

s2.OP-AB.RHR-OOOl (Q) 2.0 SIGNATURES Print ATTACHMENT 15 (Page 2 of 2) COMPLETION SIGN-OFF SHEET Initials Signature 3.0 SM/CRS FINAL REVIEW AND APPROVAL Date This procedure with Attachments 1-15 is reviewed for completeness and accuracy. Entry conditions and an deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section or this attachment. Signature: _______________ _ Date: __ _ SM/CRS Salem 2 Page 99 of 100 Rev. 17

S2.0P-AB.RHR-OOOl(Q) EXHIBIT 1 (Page 1 of 1) BRIEFING SHEET NOTE The following items are a list of potential topics which should be covered during the briefing at SM/CRS discretion.

1.

SAFETY If sending Operators to inspect for suspected leaks, OBTAIN Radiation Protection support, due to possible elevated radiation levels.

2.

TECHNICAL SPECIFICATIONS and ECGs If in Mode 4. REFER to TS 3.5.3 and 3.4.1.3 Ifin Mode 5, REFER to TS 3.4.1.4 Ifin Mode 6 or Defueled, REFER to TS 3.9.8.1 and 3.9.8,2

3.

PARAMETERS TO BE MONITORED RHR flow, RWST level, CETs and Pressurizer level Containment and Auxiliary Building radiation levels 4~ SOURCES OF LEAKAGE Particular attention should be given to components which have on-going maintenance activities or have been recently operated, tagged for maintenance or had valve alignments performed.

5.

CONTINGENCIES Brief most likely success path to restore core cooling. (Consider Attachment 4, Time to Reach Core Boiling) Restoration of normal RHR cooling - Attachment 2, Aligning RHR Loop From ECCS to Shutdown Cooling. No power available - Attachment 9, Steam Generator Reflux Cooling, or Attachment 10, Forced Flow or Natural Circ Cooldown. If CETs >200°F and RCS not intact - Attachment 7, Hot Leg Inj ection. IfCETs <200°F - Attachment 8, Cold Leg Injection. ReS intact and >0% Pressurizer level - Attachment 10, Forced Flow or Natural Circ Cooldown. Reactor Head removed - Attachment 11, Cooling the RCS with the Spent Fuel Pool. Salem 2 If the RWST level drops to 15.2', cold leg recirculation will be aligned IA W 3, Cold Leg Recirculation. Page 100 of 100 Rev. 17

LOSS OFRHR TECHNICAL BASES DOCUMENT s2.OP-AB.RHR-OOOI (Q)

1.0 REFERENCES

1.1 Technical Documents Salem 2 A. Salem Generating Station Updated Final Safety Analysis Report:

1.

Section 5, Chapter 5.5, Component and Subsystem Design

2.

Section 6, Chapter 6.3, Emergency Core Cooling Systems

3.

Section 7, Chapter 7.4, Systems Required for Safe Shutdown

4.

Section 15, Chapter 15.1, Condition I Faults, Nonnal Operation and Operational Transients

5.

Section 15, Chapter 15.2, Condition II Faults, Faults of Moderate Frequency

6.

Section 15, Chapter 15.3, Condition III Faults, Infrequent Faults

7.

Section 15, Chapter 15.4, Condition N Faults, Limiting Faults B. Salem Generating Station Technical Specifications Unit 2:

1.

3.5.3, Minimum ECCS Subsystem

2.

3.4.1.3, Reactor Coolant System

3.

3.4.1.4, Reactor Coolant System

4.

3.9.8.1, Refueling-Coolant Circulation

5.

3.9.8.2, Refueling-Low Water Level C. Configuration Baseline Documentation:

1.

DE-CB.RHR-0030(Q), Residual Heat Removal System D. Technical/Engineering Letters:

1.

Salem Generating Station Licensee Event Reports:

a. NSO LER-83-066, Closure of2RHl

b. NSO LER 89-019-00, Nitrogen Injection Into RCS Causes Gas Binding of RHRPumps

c. NSO LER-89-021, Overpressurization ofRHR Piping

d. NSO LER-89~022, RHR Cold Leg Discharge Valves Not Meeting Single-Failure Criteria

2.

NSO NLR~189215-01, NRC Corrective Action Plan for Loss ofRHR at Salem 1 per inspection 50-272/89-17 [C0329]

3.

NRC Inspection Report 50-272/89-17, Loss ofRHR Event on May 20, 1989

4.

Letter from L.K. MILLER, General Manager-Salem Operations, to all station employees, dated May 22, 1989

5.

Letter from J.M. Zupko, Jr., General Manager QA and Nuclear Safety Review: Special Investigation into the Loss OfRHR Event of May 20, 1989, to Vice President and Chief Nuclear Officer

6.

Supervisory Letter SL-37, Salem Primary Systems Loss of Decay Heat Removal, from General Manager to all Supervisors, dated April 2, 1990

7.

S-C-RHR-MEE-0390, 12-21-89, RHR Venting and Addition of New Vent Valves on RHR Suction Piping Page 1 of 13 Rev. 17

S2.0P-AB.RHR~OOOl(Q)

8.

WCAP-11916, 7-88, Loss ofRHR Cooling While the RCS is Partially Filled

9.

PSE-86-532, Westinghouse letter to PSE&G, ECCS Performance During Mode 4 Operation, April 9, 1986 E. Event Classification Guide, Section 4, Loss of Decay Heat Removal F. Westinghouse Emergency Response Guidelines, Executive Volume, Technical Specification Violations G. DCP 2EC-3316, Package I-Containment Sump Level Setpoint Modification, Calculation SC-WDOOI-Ol H. Calculation SC-CNOOI-Ol, Salem Unit 1&2 Steam Generator Level Trip, Alarm, Ind & Rec (Narrow Range)

1.

Calculation SC-CN003-01, Salem Unit 1&2 Steam Generator Level Trip, Alarm, Ind & Rec (Wide Range) J. S-2-RHR-MDC-2074, Time to Boil Reactor Vessel with a Loss ofRHR K. NUMARC 91-06, Guidelines for Industry Actions to Assess Shutdown Management. 1.2 Procedures A. S2.0P~SO.AF-OOOl(Q), Auxiliary Feedwater System Operation B. S2.0P-SO.CC-OOOl(Q), Component Cooling System Normal Operation C. S2.0P-SO.CN~OOOl(Z), Placing Feed and Condensate Systems in Operation D. S2.0P-SO.RC-0001(Q), Reactor Coolant Pump Operation E. S2.0P*SO.RC*0005(Q), Draining The Reactor Coolant System To i= 101 Pt Elevation F. S2.0P-SO.RC-0006(Q), Draining the Reactor Coolant System G. S2.0P-SO.RHR-OOOl(Q), Initiating RHR H. S2.0P-SO.SF -0002(Q), Spent Fuel Cooling Operation

1.

S2.0P-SO.SF-0003(Q), Filling the Reactor Refueling Cavity J. S2.0P~SO.SF-0005(Q), Refueling Water Purification Operation K. S2.0P~AB.CONT-OOOl(Q), Containment Closure L. S2.0P~AB.CC-OOOl(Q), Component Cooling Abnormality M. S2.0P~AB.RCS-OOOl(Q), Small RCS Leak N. S2.0P~AB.RHR-0002(Q). Loss ofRHR at Reduced Inventory O. S2.0P~IO.ZZ-0006(Q), Hot Standby To Cold Shutdown P. SC.OP~DL.ZZ~0027(Q), Log Supplement Q. 2-EOP-LOCA-3, Transfer to Cold Leg Recirculation 1.3 Drawin2s A. 205332, Residual Heat Removal B. 205331, Component Cooling C. 205333, Spent Fuel Cooling Salem 2 Page 2 of 13 Rev. 17

S2.0P~AB.RHR~OOOl(Q) 1.4 Conformance Documents A. C0329, NLR-189215-01, Task 0004, add steps to restore RHR to operability inAOP B. C0329, NLR-189215~01, Task 0005, recommend use of additional vent paths inAOP C. C0329, NLR~189215-01, Task 0006, revise AOP for additional vent paths D. C0329, NLR-189215-01, Task 0007, required reference to this letter in AOP references E. C0330, NRC GL 88-17~Fl, Task 0005, develop procedures for Containment Closure F. C0354, Westsalepse-86-532, BCCS Performance During Mode 4 Operations, Shutdown LOCA G. C0631, INPO OE 7261, Reactor Coolant System Draindown At WolfCreek H. C0658, AR # 970110263, Response to GL 89-10 1.5 Industry Concerns Salem 2 A. NRC Generic Letter 87-12, Loss of Decay Heat Removal B. NRC Generic Letter 88-17, Loss of Decay Heat Removal C. NUREG 1269, Loss of Residual Heat Removal System Diablo Canyon Unit 2 D. NUREG 1410, Loss of Vital AC Power and the Residual Heat Removal System During Mid-Loop Operations at Vo gtle Unit 1 on March 20, 1990 E. NRC Bulletin 80-12, Decay Heat Removal System Inoperability F. NRC INFO 87-23, Loss of Decay Heat Removal Function at PWRs With Partially Drained Reactor Coolant Systems G. NRC INFO 89~67, Loss of Residual Heat Removal System Caused by Accumulator Nitrogen Injection H. Westinghouse Owners Group Abnormal Response Guideline (WOG-ARG-l), Loss ofRHR While Operating at Mid~Loop Conditions, Rev.O, March 15, 1990 I. INPO SOER 85-4, Loss or Degradation ofRHR Capability in PWRs J. INPO SOER 88-3, Losses ofRHR With Reduced Reactor Vessel Water Level atPWRs K. NSAC-52, Residual Heat Removal Experience Review and Safety Analysis, Pressurized Water Reactors, January 1983 A. Calculation S-C-RHR~NDC-1619, Time To Boil Curve Extension For Loss Of Residual Heat Removal B. PSBP-324187, Salem RCS Pressurization Studies for Shutdown Configurations with the PS25 Spray Valve Bonnet Removed as a Vent Path Page 3 of13 Rev.I7

S2.0P~AB.RHR~OOOl(Q) 2.0 DISCUSSION 2.1 This procedure provides the direction necessary for shutdown plant operation with RHR malfunctions. It is the intent of this discussion to provide the reasoning behind the logic and flowpath of the procedure. It is not intended to provide additional direction to the procedure. 2.2 Entry Conditions ~ Entry conditions are based on the Operator recognizing a malfunction in the RHR System. Salem 2 The symptoms available to the Operator are as follows: + Indications ofRHR Pump Trip + 2CCI Alarm DISCHARGE HIGH PRESSURE + Unexpected drop in RCS level with RHR in service as indicated by Overhead Alann indicating less than 97.5 ft.: + OHA-D47, RHR MIDLOOP SYS TRBL + Unexpected drop in Reactor Vessel level as indicated by Reduced Inventory Instrumentation (RVLIS and Mid-Loop). + Unexpected rise in Core Exit temperature indicated by the Plant Computer points: + T0014A, Reactor Core location H4 + T0022A, Reactor Core location K12 + T0031A, Reactor Core location D12 + T0046A, Reactor Core location J1 RHR Sump alanns: + OHA C~26, 21 RHR SUMP OVERFLO

OHA C-34, 22 RHR SUMP OVERFLO

+ Indication of RHR Pumps cavitating or air bound: Flow oscillations Motor amps fluctuating Excessive pump noise RHR discharge pressure fluctuating More 'frequent operation of Containment Sump Pumps Unexpected drop in VCT level as indicated on the Plant Computer points L0112A or L0114A Page 4 of 13 Rev. 17

s2.OP-AB.RHR-OOOI CQ) 2.3 Immediate Actions - None 2.4 Subsequent Actions - Salem 2 Step 3.1 directs initiation of Attachment 1, Continuous Action Summary, which is evaluated in conjunction with perfonnance of this procedure. Step 3.2 addresses isolating the RCS vent path if the Containment Equipment Hatch is open. The closure ofthe vent path must be completed prior to Core Boiling. When the RCS is vented to the Containment, Salem's interpretation ofNUMARC 91-06 requires that either the RCS is made Intact prior to the time to core boiling should RHR be lost (applicable when the RCS loops are filled and two or more Stearn Generators are available as a heat sink for Natural Circulation. Heat sink means the Steam Generators have a feed make-up sources available, Secondary water level above the V-tubes, and a Steam Generator vent path) OR Containment Closure is established prior to time to Core boiling should a Loss ofRHR occur. (Containment Closure in this statement only applies the Equipment Hatch and the Personnel Air Locks, and 2VCl through 2VC6; Containment Closure of all the other penetrations required prior to Core Vncovery and is established IA W S2.0P-AB.CONT -0001 (Q). Step 3.3 detennines ifthe unique situation of MidwLoop operations exists because of the different requirements associated with those plant conditions. For a Loss ofRHR during reduced RCS inventory conditions, the Operator is directed to S2.0P-AB.RHR-0002(Q), Loss OfRER At Reduced Inventory. Step 3.5 and 3.7 questions for pump problems. If problem is a result of a loss of electric power, then the Operator is directed to steps which establish a heat sink. If the problem is a result of mechanical problems, then the Operator is directed to steps which will return the RHR system to service or establishes an alternate heat sink. If a pump was not affected then the Operator is directed to check for RHR System capability and directed to steps which check for RHR heat sink problems. If the running pump is cavitating, the other RHR pump will also cavitate if started. If the running pump is affected, flow is throttled and RCS level is raised, to attempt to stabilize the RHR System. If this returns the system to normal, the Operator is directed to close out the procedure. If a loop is not available for cooling, the Operator continues and attempts to restore the lost loop, while providing alternate cooling methods (hot leg injection, cold leg injection, etc.). Ifinitial indications are RHR Pump cavitation or gas binding, action is taken to raise ReS level and flow is reduced to the minimum value of 1500 to 1800 gpm in an attempt to restore stable flow and reduce cavitationlvortexing. Less than 1500 gpm can result in excessive vibration from the pump. This method has been shown to be effective by Westinghouse analysis. The RCS level indication is normally via RVLIS. At this point pressurizer level is still on scale which is greater than 108 ft. In S2.0P-SO.RC-0005(Q), the RCS reduced inventory log is required to be maintained lAW SC.OP-DL.ZZ-0027(Q), Attachment 1) Reduced RCS Inventory Log, whenever RCS level is below PZR level indication (104 ft.). This requires RVLIS reading in feet every hour and a tygon tube reading every 4 hours. RVLIS will only be used in the RefuelinglReduced Inventory Mode in S2.0P*SO.RC*0005(Q) and/or the tygon tube which indicates in foot increments. Page 5 orB Rev.!7

Salem 2 S2.0P-AB.RHR~OOOl(Q) If raising level ot reducing flow does not stop cavitation or gas binding, RHR Pmnps are stopped and the time to core boiling is determined using one of the curves in Attachments 4 or 5, Time To Reach Core Boiling After Loss OfRHR, which accounts for decay heat loads before and after refueling following shutdown. Using this information, it is decided if adequate time exists to vent the RHR System to attempt restoration ofRHR by the nonnal means. This method requires a Containment entry by operations personnel to vent RHR Pumps and suction piping which has the potential to be a lengthy process. Iftime is available, the Operator is directed to attempt to rapidly restore RHR flow if plant conditions are conducive to RHR Pump operation. Whenever an attempt is made to restart an idle RHR Pump, RCS level is verified as being adequate, power availability is checked, proper operation of a heat sink is confirmed, and the system is verified free of air or other gases. Industry experience has shown the possibility exists of gases other than air or steam can accumulate in the low pressure or high elevation area ofRHR piping, notably Nitrogen, due to Safety Injection Accumulator addition or gases leaving solution. When these conditions are satisfied, the RHR Pump is started at low flow to minimize thennal shock and rapid RCS level loss due to sudden void collapse. If the time to saturation is very short the operator is directed to sweep air from the RHR System as addressed in Westinghouse Owners Group Abnormal Response Guideline ARG~ 1. Flow is then restored to the normal operating value between 1800 and 3000 gpm, determined by the flow required to stabilize Core Exit Thermocouple temperatures, and if all parameters are normal, the procedure is exited. Alternate methods of decay heat removal are detennined, the entry conditions of the Emergency Plan are checked in the Event Classification Guide, and appropriate Technical Specifications are reviewed to insure operating license compliance. Stability ofRCS level is checked to determine if a loss of inventory is occurring. Direction is given to isolate all ReS drain paths. Ifleakage is indicated, RHR is isolated to detennine leak location. If RHR leakage is the reason for the malfunction, it is detennined if an intact train of RHR still exists: if so, the intact train is returned to service after leak isolation or repair is completed. Leakage from the RCS outside the RHR boundaries are located and isolated while alternate methods of decay heat removal continue. In the event RHR Pumps are operating but a problem exists with flow or ReS temperature, the RHR flow control valve is checked or the standby RHR Pump with its redundant flow control valve is operated, to correct flow problems. RCS temperature problems are corrected by ensuring proper operation of the Component Cooling System and the required Service Water System. The procedure is then exited, or if the malfunction is not yet corrected, the Operator is directed to Step 3.1 for symptom rediagnosis. Page 6 of 13 Rev. 17

S2.0P-AB.RHR-OOOl(Q) In the event an altemate method of decay heat removal is required, attachments are provided to cool the Reactor Core while Operators continue attempts to restore RHR. Plant conditions and system configuration may require the implementation of one or more of these attachments. DUling performance of the Attachments, leak isolation and RHR restoration is continued. Cooling by Component Cooling and Service Water are checked to evaluate additional cooling problems. If Component Cooling or Service Water availability of cooling is challenged, the Operator is directed to initiate S2.0P-AB,CC-OOOl(Q), Component Cooling Abnormality or S2.0P*AB.SW-OOOICQ), Loss Of Service Water Header Pressure. If the procedure is completed and RHR System is NOT considered normal by flow, temperature and RCS level the Operator is directed to return to Step 3.1 for symptom rediagnosis. Attachments included with this procedure are as follows: Salem 2 ATTACHMENT 1 - CONTINUOUS ACTION

SUMMARY

The Operator is notified that if power is lost to all RHR pumps and makeup sources, Steam Generator Cooling is still available. If a complete loss of heat sink has occurred, the Operator is directed to perform Attachment 12, Altemate Cooling Water, to provide cooling to pumps necessary for decay heat removal. Direction to perform S2.0P~AB.CONT-OOOl(Q), Containment Closure, ifin Mode 5 or 6 is provided. Two hours is allotted to complete this verification and should be initiated as soon as recognized to complete this procedure in a timely manner. Direction to start Safety Injection and Charging pumps as required to control Pressurizer level and core exit thennocouple temperatures. This provides additional guidance for keeping the core covered and cooled, to allow Operator action as soon as the need is recognized prior to starting other pumps in the body of the procedure. ATTACHMENT 2 AND 3 - ALIGNING RHR LOOP FROM ECCS TO SHUTDOWN COOLING I ALIGNING RHR LOOP FOR SHUTDOWN COOLING These attachments provide instructions to place an available RHR Loop in service. provides guidance ifthe alternate RHR Loop is aligned for BCCS injection. Attachment 3 provides guidance if the alternate RHR Loop is aligned for shutdown cooling. These attachments provide guidance from S2.0P-SO.RHR-OOOl(Q), Initiating RHR. This infonnation is in this procedure to align the RHR Loop in a timely manner to avoiding the reference to an additional procedure, S2.0P-SO.RHR-OOOl(Q). Page 7 of 13 Rev. 17

Salem 2 ATTACHMENT 4 - TIME TO REACH CORE BOILING AFTER LOSS OF RHR Curves depicting the time available before saturation temperature is reached in the Reactor core. An RCS level of 101 1 elevation is selected since any volume of water in the Pressurizer will not provide any additional time to boiling in the actual core regions. Any volume of water in the Pressurizer is important in time to core uncovery, but not in time to core boiling. This level results in curves which are conservative but not unnecessarily so. Additional curves provide the time to boil and heatup rate expected for a loss of RHR so that an accurate assessment of time to core boiling can be made. These curves project heatup from 1 up to 1000 days after shutdown. Hot Leg Temperature maybe used in place of CETs when CETs are not available (i.e. Reactor Head removed, CETs disconnected etc.). For 2R16 to support Steam Generator Replacement, Engineering Calculation S~2~RC-MDC-2151, Containment Closure in Modes 5 and 6 During SO Replacement, was developed to allow use of an Equipment Hatch Ventilation Barrier (EHVB). This calculation takes credit for Operator actions taken lAW Attachment 14 of this procedure. When the actions specified in Attachment 14 are adhered to following a Loss of Shutdown Cooling, the time to core boil is calculated to be at least 70 minutes. If the Operator actions of Attachment 14 are NOT taken, the curves provided within this procedure are still valid for calculating time to boil. ATTACHMENT 5. HEATUP RATE FOR LOSS OF RHR COOLING provides the heatup rate expected for a loss ofRHR so that an accurate calculation oftime to core boiling can be made in the event the RCS is at some initial temperature other than that depicted in the curves of Attachment 4. ATTACHMENT 6 -MAKEUP RATE REQUIRED TO REFILL RCS AFTER LOSS OFRHR Depicts the makeup flow rate required to adequately cool the Reactor core and refill the RCS after a loss ofRHR. This is the flowrate necessary to result in lowering Core Exit Thermocouple temperature in a feed and bleed scenario. ATTACHMENT 7

HOT LEG INJECTION Hot Leg Injection is the preferred method when the RCS temperature is greater than or equal to 200 0P for restoring RCS inventory lost due to leakage, as it ensures flow through the core in all conditions. Openings in any RCS Hot Leg will provide an adequate vent path to prevent pressurization of the RCS which could inhibit flow to the core. If a hot leg vent path does not already exist, Pressurizer PORVs are opened to provide the desired bleed path. Hot leg injection can provide adequate core cooling at lower flow rates than cold leg injection, since natural circulation within the core promotes mixing ofthe coolant.

Page 8 of 13 Rev. 17

Salem 2 S2.0P~AB.RHR-OOOl(Q) Decay heat removal is accomplished by Feed and Bleed of the RCS: Borated water is pumped into the RCS using a Safety Injection Pump aligned to RCS hot legs, taking suction from the RWST. Design minimum flow of the Safety Injection Pump is 400 gpm. Maximum flow to the RCS is maintained until one of the following conditions ]s satisfied: A. RHR is restored B. Flow from RCS opening is adequate to result in lowering Core Exit Thennocouple temperatures The bases of these conditions is as follows: RHR is restored, normal shutdown operation is resumed and procedure is exited. Flow from RCS openings is adequate to result in lowering Core Exit Them10couple temperatures. This determines that decay heat removal is adequate and core will remain covered. In the event Core Exit Thennocouples are not available, injection flow is maintained IA W Attachment 6, Makeup Rate Required to Refill RCS After Loss of RHR. Decay heat removal is accomplished by Feed and Bleed of the RCS. Borated water is pumped into the RCS using a Safety Injection Pmnp aligned to RCS hot legs, taking suction from the RWST. lfthe RCS is boiling, the use of hot leg level and pressurizer level may not provide an accurate indicator of inventolJ' in the ReS. To avoid frequent starting and stopping of Safety Injection Pumps, the appropriate SJ35 valve is throttled to obtain the flow rates addressed above. Minimum flow recirculation is maintained at all times to the Safety Injection Pumps, therefore throttling discharge flow is acceptable and within UFSAR analysis. Heat is removed from the Containment by operation of all available Containment Fan Cooling Units (CFCUs) in slow speed, which is the UFSAR analyzed accident configuration, which also insures Containment or RCS pressure rises are minimized. A note informs the Operator that ifthe RCS is intact, the possibility of starting a Reactor Coolant Pump to provide forced flow through the Reactor Core should be considered. RCS feed flow is adjusted to exceed boil off rate or to stabilize level while maintaining Core Exit Thennocouples stable or lowering, A bleed path is aligned from the Pressurizer to the PR T, and ultimately to the Containment Sump. The Reactor Head is vented to remove any bubble which may have foooed, and to provide additional vent path. Attempts to correct primary system leakage continue and when accomplished, RHR is restored and the procedure is exited. Page 9 orl3 Rev. 17

Salem 2 82.OP-AB.RHR-OOOl (Q) ATTACHMENT 8 - COLD LEG INJECTION Decay heat removal is accomplished by feed and bleed ofthe RCS. Cold Leg Injection is the preferred method when the RCS temperature is less than 200oP. Borated water is charged into the RCS using a Charging Pump or Safety Injection Pump aligned to RCS cold legs taking suction fi'om the RWST. If any opening exists in any RCS Cold Leg, flow may not reach the Reactor Core unless Cold Leg Injection is initiated before any RCS pressurization due to boiling. Failure of a Steam Generator Nozzle Dam or removal of a Cold Leg Steam Generator Manway, with no Hot Leg vent path on the same loop could result in core uncovery within several minutes after boiling starts due to Hot Leg pressurization. As a result of these concerns, Salem Generating Station has incorporated several practices to minimize the possibility of this event occurring: A. Hot side Steam Generator Manways are removed first and installed last. B. Cold side Steam Generator Manways are installed first and removed last. These precautions ensure that if Cold Leg Injection is required, a Cold Leg opening does not exist without an adequate Hot Leg vent path on the same loop. Maximum makeup flow is maintained as described in the bases for Hot Leg Injection. The design minimum flowrate of the Charging Pumps is 460 gpml well above the flow required to remove core heat in the conditions addressed in this procedure. Heat is removed from the Containment by operation of all available CFCUs in slow speed (UFSAR analyzed)which also insures Containment or RCS pressure rises are minimized. A note informs the Operator that if the ReS is intact, the possibility of starting a Reactor Coolant Pump to provide forced flow through the Reactor Core should be considered. RCS feed flow is adjusted to exceed boil off rate or to stabilize level while maintaining Core Exit Thermocouples stable or lowering. A Bleed path is aligned from the Pressurizer to the PRT and ultimately to the Containment Sump. The Reactor Head is vented to remove any bubble which may have fanned and to provide an additional vent path. Attempts to correct primary system leakage continue and when accomplished, RHR is restored and the procedure is exited. Conditional steps are included which return RHR to service. Conditional steps are included which provide instructions for venting and/or aligning the system. Page 10 of13 Rev. 17

Salem 2 82.OP-AB.RHR-OOOI (Q) ATTACHMENT 9 - STEAM GENERATOR REFLUX COOLING In the event the ReS is at or near atmospheric pressure, the RWST is available to provide a borated water source to the ReS. This method is of particular importance when electrical power is not available for other methods of decay heat removal. Westinghouse Owners Group analysis has shown that the phenomena known as reflux cooling will adequately remove decay heat if at least two Steam Generators are available as a secondary heat sink. RCS pressure at or near atmospheric is most conducive to the initiation of this phenomena. Steam in the RCS piping will condense in the relatively cold Steam Generator tubes and "fall back" to the loops and flow to the Reactor Core due to density differences. As temperature rises, RCS pressure rises also, but it has been found through analysis that pressures up to the 20 psig range tend to improve this phenomena once established at lower pressures. Once the secondary side of the Steam Generators reach saturation, continued heat removal can be accomplished by feed and bleed or steaming of the Steam Generator. Feedwater is provided to the Steam Generators for decay heat removal by the Condensate System or the Auxiliary Feedwater System. Heat removal from the Steam Generators is accomplished by operation of the Main Steam Power Relief Valves (MSlOs), or by feed and bleed of the Steam Generator secondary side while maintaining wide range level in the 77% to 95% range. This range was selected based on the following: A. Wide range level is accurate at low ReS temperatures (Cold Calibrated) B. 77% WR will ensures Steam Generator tubes remain covered to provide the maximum heat transfer rate from the RCS for all temperature ranges. C. 95% is selected as the maximum to provide the Operator with an adequate operating margin without going "off-scale high" or passing water through MSIOs or to the Main Steam piping. Heat removal from the Containment is especially critical in this decay heat removal mode since any excessive pressure rise with any openings in the RCS pressure boundary could disrupt flow from the RWST, and reduce heat transfer to the secondary water in the Steam Generators. A more complete explanation of this phenomena can be found in the Westinghouse Owners Group Abnormal Response Guideline. Heat is removed from the Containment by operation of all available CFCUs in slow speed (UFSAR analyzed) which also insures Containment or RCS pressure rises are minimized. Conditional steps are included which return RHR to service. Conditional steps are included which provide instructions for venting and/or aligning the system. Page 11 of13 Rev. 17

Salem 2 S2.0P-AB.RHR-0001(Q) ATTACHMENT 10 - FORCED FLOW OR NATURAL CIRCULATION COOLDOWN In the event the ReS is filled, cooldown by steaming the Steam Generators will stop any heatup of the RCS. IfRCS pressure is adequate to satisfy RCP seal differential pressure requirements, RCPs are operated lAW the normal Operating Procedure. If a natural circulation cooldown is required, the Operator is provided with parameters to maintain to ensure natural circulation heat removal is occurring. Once decay heat removal from the RCS is stabilized, Operators are dispatched to locate and isolate the source ofRCS leakage. When leak isolation is completed, RHR is restored and procedure is exited. ATTACHMENT 11 - COOLING THE RCS WITH SPENT FUEL POOL If the Reactor Vessel head is removed, the Operator is directed to initiate flooding of the Reactor Cavity until water levei is equalized with the Spent Fuel Pool level. The Reactor Cavity is cross connected to the Spent Fuel Pool and decay heat is removed by raising Reactor Cavity Filtering and Purification flow to maximum and Operating the Spent Fuel Pool Cooling System as required to stabilize or reduce RCS temperature. Heat is removed from the Containment by operation of all available CFCUs which also insures Containment pressure rise is minimized. When RHR becomes available, it is restored to service and the procedure is exited. ATTACHMENT 12 - ALTERNATE COOLING WATER This attachment is provided to direct the Operator to align alternate cooling water to pumps and components used throughout this procedure. Failure to do so can lead to failure of components necessary for alternate decay heat removal. If the failure is a loss of Service Water, decay heat is transferred to Component Cooling and then to the Spent Fuel Pool since CC temperature will eventually exceed SFP temperature on extended loss ofRHR casualties. Loss of Component Cooling will require initiating one of the specified means of alternate decay heat removal. Since alternate cooling water cannot be provided to Safety Injection Pump Seal Water Heat Exchangers when BOTH trains ofCC are lost, decay heat removal by cold leg injection or Steam Generators would be preferred in this very unique case. Page 12 of13 Rev. 17

Salem 2 s2.OP-AB.RHR-OOOI (Q) ATTACHMENT 13 - COLD LEG RECIRCULA TrON This attachment provides direction for alignment ofRHR pump suction to Containment Sump as described in 2-EOP-LOCA-3, Transfer to Cold Leg Recirculation. As discussed in Westinghouse background documents, this provides long tem1 decay heat removal. This attachment is referred to in Attachment 1, when RWST LO Level Alarm actuates (15.24 ft) and Containment Sump level indication reaches 62% This has been determined to be the level necessary to provide adequate Net Positive Suction Head for RHR Pumps taking a suction on the Containment Sump. ATTACHMENT 14 - 2R16 COLD LEG INJECTION (Prior to Filling Cavity to > 125' 6") For 2R16 to support Steam Generator Replacement, Engineering Calculation S-2-RC-MDC-21S1, Containment Closure in Modes 5 and 6 During SG Replacement, was developed to allow use of an Equipment Hatch Ventilation Barrier (EHVB). This calculation takes credit for Operator actions taken IA W Attachment 14 of this procedure. When the actions specified in Attaclunent 14 are adhered to following a Loss of Shutdown Cooling, the time to core boil is calculated to be at least 70 minutes. If the Operator actions of Attachment 14 are NOT taken, the curves provided within this procedure are still valid for calculating time to boil. 4 implements the requirements of S-2-RC-MDC-21S1, Containment Closure in Modes 5 and 6 During SO Replacement, and is to be utilized when a Loss of Shutdown Cooling occurs during 2R16 prior to filling the Refueling Cavity to> 125' 6", END OF DOCUMENT Page 13 of13 Rev. 17}}

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