ML20085E426
| ML20085E426 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 05/31/1995 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20085E403 | List: |
| References | |
| PROC-950531, NUDOCS 9506160533 | |
| Download: ML20085E426 (249) | |
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AP600 Emergency Response Guidelines Revision 0 May 31,1995 Westinghouse Electric Corporation Energy Systems Business Unit i Advanced Technology Business Area P.O. Box 355 l Pittsburgh, PA 15230 0
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AP600 O
EMERGENCY RESPONSE GUIDELINES 1
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1 OPTIMAL RECOVERY GUIDELINES l
STATUS TREES l O
FUNCTION RESTORATION GUIDELINES i
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AP600 O suenouxcv asseosse ouinetixes OPTIMAL RECOVERY GUIDELINES AE-0: Reactor Trip or Safety Injection AES-0.1: Reactor Trip Response AES-0.2: Natural Circulation Cooldown AE ' ass of Reactor or Secondary Coolant AES-1.1: Passive Safety Systems Termination AES-1.2: Post LOCA Cooldown and Depressurization AE-2: Faulted Steam Generator Isolation AE-3: Steam Generator Tube Rupture i AECA-1.1: LOCA Outside Containment O
STATUS TREES ,
AF-0.1 Suberiticality AF-0.2 Core Cooling j AF-0.3 Heat Sink )
AF-0.4 Integrity l AF-0.5 Containment AF-0.6 Inventory i
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AP600 EMERGENCY RESPONSE GUIDELINES h FUNCTION RESTORATION GUIDELINES AFR-S.1: Response to Nuclear Power Generation /ATWS AFR-S.2: Response to Loss of Core Shutdown AFR-C.1: Response to Inadequate Core Cooling AFR-C.2: Response to Degraded Core Cooling ,
AFR-C.3: Response to Saturated Core Cooling AFR-H.1: Response to Loss of Secondary Heat Sink AFR-H.2: Response to Steam Generator Overpressure AFR-H.3: Response to Steam Generator High Level AFR-H.4: Response to Loss of Normal Steam Release Capabilities AFR-H.5: Response to Steam Generator Low Level AFR-P.1:
AFR-P.2:
Response to Imminent Pressurized Thermal Shock Condition Response to Anticipated Pressurized Thennal Shock Condition h
AFR-Z.1: Response to High Containment Pressure AFR-Z.2: Response to Containment Flooding AFR-Z.3: Response to High Containment Radiation Level AFR-Z.4: Response to Low Containment Pressure AFR-I.1: Response to High Pressurizer Level AFR-I.2: Response to Low Pressurizer Level AFR-I.3: Response to Voids in Reactor Vessel i
FOOTNOTE DEFINITIONS ii I
l AP600 EMERGENCY RESPONSE GUIDELINES Statement of Intent The AP600 Emergency Response Guidelines (ERGS) provide functional guidelines for terminating i accidents and transients that affect plant safety. Emergency Operating Procedures (EOPs) will be !
i developed using the functional guidelines from the ERGS in a presentation philosophy that directs the operating staff to provide timely implementation. The EOPs and their presentation may not resemble the ERGS, but will accomplish the functional guidance provided. The use of historical terminology in the ERGS (Ex.: " status trees") does not imply any specific form of detailed implementation, therefore no constraints are placed on the MMIS design because of their use. The ERGS do not specify the complete degree of automated plant response nor the degree of user control over the pace of wnrking through the accident respona The task allocation between the man and the computer to do inis will i be decided when designing the features of the Man-Machine Interface System (MMIS). The format and features of the EOPs and their presentation will be determined by the Human Factors Engineering ,
(HFE)/MMIS design process. This process includes the development of EOPs, development of '
functional requirements and design basis for the computerized procedure system, man-in-the-loop prototype / concept i sting, workload analysis, detailed design of hardware and software and the final i
life verification and validation.
The ERGS are formatted such that the plant functional guidelines within each ERG are represented by O #e-se<ea. seia-r cea stees. u aer e cs 8 ia ii e stee. -ser er aisti ci c'ie s.<eeee ses. a'er indications are specified. These specific actions, responses, and reference to indications are provided to reflect the potential actions and responses needed to meet the functional guideline for the AP600 design. During the development of the AP600 MMIS design and Emergency Operating Procedures (EOPs) it may be shown that not every distinct action, response, or indication identified in the ERGS is required to meet the higher level functional guideline. Additionally, the extent of main control room automation versus manual operator action will also be a consideration in the achievement of the high ,
level functional guideline. .
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! AE-0 1
Reactor Trip or Safety Injection b
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AE-0 REACTOR TRIP OR SAFETY INJECTION Rev. 0 5/31/95 A. PURPOSE This guideline provides actions to verify proper esponse of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection, to assess plant conditions, and to identify the appropriate recovery guideline.
B.* SYMPTOMS OR ENTRY CONDITIONS
- 1) The following are symptoms that require a reactor trip, if one has not occurred:
- a. Source range high neutron flux (interlocked with P6)
- b. Intermediate range high neutron flux (interlocked with P10)
- c. Power range high neutron flux - low setpoint (interlocked with P10)
- d. Power range high neutron flux - high setpoint
- e. Power range high positive flux rate
- f. Overtemperature delta-T
- g. Overpower delta-T
- h. Low pressurizer pressure (interlocked with P10)
(Q j 1. Low reactcr coolant cold leg flow (interlocked one loop out of four with P8 9d two loops out of four with P10)
- j. Low reactor coolant pump speed (interlocked with P10)
- k. Reactor coolant pump bearing water high temperature (interlocked one loop out of four with P8 and two loops out of four with P10)
- 1. High pressurizer pressure
- m. High pressurizer water level (interlocked with P10)
- n. Low SG level - narrow ran
- p. ADS actuation signal
- q. Safety injection actuation signal
- r. CMT actuation signal
- t. Low pressurizer level (DAS) )
- 2) The following are symptoms of a reactor trip:
- a. Any reactor trip alarm
- b. Rapid decrease in neutron level indicated by nuclear instrumentation
- c. All shutdown and control rods are fully inserted O
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Number Title Rev./Date AE-0 REACTOR TRIP OR SAFETY INJECTION Rev. 0 5/31/95 SYMPTOMS OR ENTRY CONDITIONS (continued)
- 3) The following are symptoms that require a reactor trip and safety injection, if one has not occurred:
- a. Low pressurizer pressure
- b. Hi-1 containment pressure
- c. Low compensated steam line pressure
- d. Low-3 cold leg temperature
- e. Manual
- 4) The following are symptoms of a reactor trip and safety injection:
- a. Any SI alarm
- b. CMT injection valves open
- c. PRHR isolation valves open O
All reactor trip parameters, safety injection parameters and alarms listed in the symptoms or entry conditions are preliminary and are subject to change to be consistent with the AP600 PMS and DAS design.
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Number Title Rev./Date tN AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. 0
- (,_,)c 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE
- Steps 1 through 3 are IWfEDIATE ACTION steps.
t
- Foldout page should be open.
1 Verify Reactor Trip: Manually trip reactor. If reactor will HQI trip IHEN 90 to e All control rods - INSERTED AFR-S.1, AP600 RESPONSE TO NUCLEAR POWER GENERATION /ATWS, e Reactor trip and bypass Step 1.
breakers - OPEN ,
1 e Neutron flux - DECREASING 2 Verify Turbine Trip: Manually trip turbine.
. All turbine stop valves -
CLOSED
() 3 Check If SI Is Actuated: Check if SI is required. IE SI is required, IHE8 manually actuate.
[ Include additional AP600 details in E0Ps] If SI is HQI required,181H go to ,
AES-0.1. AP600 REACTOR TRIP '
RESPONSE, Step 1. i 4 Verify Main FW Isolation: Manually close valves as necessary. ,
e Main flow control valves - l CLOSED 1 l
e Main FW 1 solation valves - '
CLOSED
]
5 Verify SG Blowdown Isolation: Manually close valves as necessary.
SG blowdown isolation valves - CLOSED O
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Number Title Rev./Date AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. 0
, 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Verify Containment Isolation:
! a. Containment isolation - a. Manually actuate containment l
ACTUATED isolation.
- b. Containment isolation b. Manually close valves.
valves - CLOSED 7 Verify CMT Actuated: Actuate CMT initiation. If valves will HQI open, It[G manually open e CMT injection valves - OPEN valves as necessary.
8 Verify PRHR Actuated: Actuate PRHR Initiation. IE valves will ROI open, IH G e Verify PRHR isolation valves - manually open valves as OPEN necessary.
9 Verify All RCPs Tripped Manually trip RCPs.
O 10 Check If Main Steamlines Should Be Isolated:
- a. Check if any of the a. Go to Step 11.
following signals have occurred:
. Low steam line pressure
-OR-e Low-2 RCS Tavg
-OR-e Hi-1 containment pressure
- b. Verify main steamline b. Manually close valves. !
isolation and bypass !
valves - CLOSED !
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Number Title Rev./Date AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. 0
)~ 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Verify Passive Containment Verify PCS initiated. If EI,
, Cooling Not Required: It[G manually initiate.
, Containment pressure - HAS REMAINED LfiS THAN (P01) PSIG e Containment temperature - LESS THAN (T03)
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Number Title Rev./Date AE-0 APf,00 REACTOR TRIP OR SAFE 1Y INJECTION Rev. 0 5/31/95 STEP ACTION /EXPF.CTED RESPONSE RESPONSE NOT OBTAINED L
12 Check RCS Temperatures: H temperature less than (T04) F and decreasing, M :
- RCS cold Icg temperatures -
STABLE AT OR TRENDING T0 a) Stop dumping steam.
(T04) F b) E cooldown continues, E control total feed flow.
Maintain total feed flow greater than (F01) gpm until narrow range level greater than (LO3)% [(LO4)% for adverse containment] in at least one SG.
c) E cooldown continues, E close main steamline isolation and bypass valves.
d) E cooldown continues and both SFM in operation and narrow range level greater than (LO3)% [(LO4 containment] in at )%
leastfor oneadverse
[ Include additional AP600 details in E0Ps]
E temperature greater than (T04) F and increasing, M:
. Dump steam to condenser.
-0R-e Dump steam using SG PORVs.
-OR-e Initiate PRHR.
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l Number Title Rev./Date p, AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. O Q 5/31/95 i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
13 Verify Power to ECS AC Busses: l
- b. AC busses - ALL ENERGIZED b. Try to restore power to deenergized ac busses.
NOTE
- It may be necessary to block the Low-3 RCS Tcold to restart SFW pumps.
14 Verify SFW Pumps Running Manually start pumps.
l 15 Verify Total SFW Flow - GREATER E SG narrow range level greater
[N THAN (F01) GPM than (LO3)% [(LO4)% for adverse containment] in any SG, M control feed flow to maintain !
narrow range level. j H narrow range level less than (LO3)% [(LO4 containment])% in all for SGs,adverse M
manually start SFW pumps and align valves as necessary. E SFW flow greater than (F01) gpm can l E be established, M initiate PRHR.
E PRHR can E be initiated, M 90 to AFR-H.1, AP600 RESPONSE TO LOSS OF RCS HEAT SINK, Step 1.
16 Verify SFW Valve Alignment - Manually align valves as PROPER SHUTDOWN ALIGNMENT necessary.
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Number Title Rev./Date AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. 0 5/31/95 STEP i
ACTION / EXPECTED RESPONSE ; RESPONSE NOT OBTAINED CAUTION If adverse containment conditions exist, RCS makeup should be operated in manual to maintain pressurizer level.
17 Check RCS Makeup Status:
- a. PRZR level - GREATER THAN a. Verify one makeup pump (LO5)% [(L23 running. E EI, IBEN CONTAINMENT])% FOR ADVERSE manually start one makeup pump.
- b. PRZR level - LESS THAN b. Verify all makeup pumps (LO6)% [(L31 stopped. E HQI, IllEN CONTAINMENT])% FOR ADVERSE manually stop all makeup pumps.
18 Verify SWS System Operation:
- b. Verify proper valve b. Manually align valves as alignment: necessary.
[ Include additional AP600 details in E0Ps]
19 Verify CCS System Operation:
- b. Verify proper valve b. Manually align valves as alignment: necessary.
[ Include additional AP600 details in E0Ps]
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Number Title Rev./Date (S AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. O C/ 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Verify VWS System Operation:
- a. VWS pumps - AT LE/.ST ONE a. Start VWS pumps as RUNNING necessary,
- b. Verify proper valve b. Manually align valves as alignment necessary.
[ Include additional AP600 details in E0Ps]
21 Verify Containment Fan Coolers - Manually start fan coolers.
RUNNING 22 Check If SG Secondary Pressure Boundaries Are Intact:
(')
(_/
- a. Check pressures in all SGs - a. Go to AE-2, AP600 FAULTED STEAM GENERATOR ISOLATION, e NO SG PRESSURE DECREASING Step 1.
IN AN UNCONTROLLED MANNER e NO SG COMPLETELY DEPRESSURIZED 23 Check If SG Tubes Are Intact: Go to AE-3, AP600 STEAM GENERATOR TUBE RUPTURE, Step 1.
. Condenser air ejector radiation - NORMAL e SG blowdown radiation - NORMAL 24 Check If RCS Is Intact: Go to AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
e Containment radiation - NORMAL e Containment pressure - NORMAL e Containment level - NORMAL O
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Number Title Rev./Date AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check If Passive Safety Systems should Be Terminated:
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- a. RCS subcooling based on core a. Go to Step 27.
exit TCs - GREATER THAN (S01) F l b. RCS heat sink: b. Jf neither condition satisfied,1113 go to e Total feed flow to SGs - Step 27. l GREATER THAN (F01) GPM
-OR-e Narrow range level in at least one SG - GREATER THAN (LO3)%
-OR-e PRHR - OPERATING
- d. PRZR level - GREATER THAN d. Go to Step 27.
(LO5)%
26 Go To AES 1.1, AP600 PASSIVE SAFETY SYSTEMS TERMINATION, Step 1 27 Initiate Monitoring Of Critical Safety Function Status Trees O
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Number Title Rev./Date AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION. Rev. 0
.t 5/31/95 STEP. ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED. -l I
CAUTION If the Deaerator Storage Tank level decreases to less than (LO8), the SFW pump suction should be transferred to the CST. ;
i 28 Check SG Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow THAN (LO3)% greater than (F01) gpm until narrow range level greater than (LO3)% in at least one.
SG.
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- b. Control feed flow to b. IE narrow range level in any ;
maintain narrow range level SG continues to increase in between (LO3)% and 50% an uncontrolled manner, JEEN !
go to AE-3, AP600 STEAM l GENERATOR TUBE RUPTURE, Step 1.
29 Check Secondary Radiation - Go to AE-3, AP600 STEAM GENERATOR NORMAL TUBE RUPTURE, Step 1.
[ Include additional AP600 details !
in E0Ps] i i
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Number Title Rev./Date AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. 0 5/31/95 i l
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED .
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30 Check If ADS Should Be Actuated: l
- a. CHT level - LESS THAN (L01)% a. H RCS hot leg level indication greater than ,
(L32), M go to Step 31. l E RDI, E manually i actuate ADS. l l
- b. Verify first stage ADS b. Manually open valves as isolation valves - OPEN necessary.
- c. Check second stage ADS c. M (T01) seconds have valves - OPEN elapsed from first stage ADS signal, M verify second stage ADS valves open. E HQI, M manually open second stage ADS valves as necessary.
- d. Check third stage ADS d. M (T02) seconds have valves - OPEN elapsed from second stage ADS signal, M verify third stage ADS valves open.
IE fiDI, E manually open third stage ADS valves as necessary.
- e. Align RNS to inject into RCS
- f. Go to AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
31 Check Auxiliary Building Evaluate cause of abnormal Radiation - NORMAL conditions. E the cause is a loss of RCS inventory outside containment, M go to AECA-1.1, AP600 LOCA OUTSIDE CONTAINMENT, Step 1.
l 32 Reset SI 33 Reset Containment Isolation O
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Number Title Rev./Date !
,tG AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. 0 V 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ,
34 Establish Following Support Systems Into Containment:
e Instrument Air e VWS e CCS 35 Check If Diesel Generators Should Be Stopped:
- a. Verify ECS ac buss 2s - a. Try to restore offsite power I ENERGIZED BY OFFSITE POWER to ECS ac busses. If offsite ,
power can fiDI be restored, '
IliEff load the following equipment on ac busses:
O [IncludeadditionalAP600 details in E0Ps]
- b. Stop any unloaded diesel generator and place in standby 36 Check If PRHR Should Be Isolated
- a. Check the following: a. Go to Step 37.
. SFW - IN OPERATION e Narrow range level in at i least one SG - GREATER THAN (LO3)%
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- b. Close PRHR isolation valves 37 Return To Step 12
- END - l Page 13 of 14
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Number Title Rev./Date AE-0 AP600 REACTOR TRIP OR SAFETY INJECTION Rev. 0 5/31/95 f
l FOOTNOTES i
Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline. I I
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AES-0.1 Reactor Trip Response O
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AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. O D) 5/31/95 A. PURPOSE This guideline provides the necessary instructions to stabilize and control the plant following a reactor trip without a safety injection. .
i B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 3 when SI is neither actuated nor required.
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Number Title Rev./Date AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If Si actuation occurs during this guideline, AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, should be performed.
NOTE Foldout page should be open.
1 Check RCS Temperatures - IE temperature less than (T04) F e RCS AVERAGE TEMPERATURE STABLE AT OR TRENDING T0 (T04) F IF a) Stop dumping steam.
ANY RCP RUNNING b) IE cooldown continues. IllEN
-0R- control total feed flow.
Maintain total feed flow e RCS COLD LEG TEMPERATURES greater than (F01) gpm until STABLE AT OR TRENDING TO narrow range level greater i (T04) F IF NO RCP RUNNING than (LO3)% in at least one l SG. I c) lE cooldown continues, IBEN close main steamline isolation and bypass valves, d) If cooldown continues and both SFW in operation and narrow range level greater than (LO3)% in at least one SG, IllEH isolate PRHR.
[ Include additional AP600 details in E0Ps]
IF temperature greater than (T04) F and increasing, IliEN:
e Dump steam to condenser.
-0R-e Dump steam using SG PORVs.
-0R-e Initiate PRHR.
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Number Title Rey,/Date AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. O I 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Verify All ECS AC Busses - Try to restore offsite power to ENERGIZED BY OFFSITE POWER ECS ac busses. E offsite power -
can HQI be restored, M load the following equipment on ac busses:
[ Include additional AP600 details in E0Ps]
3 Check FW Status: ,
- a. Check RCS average a. Continue with Step 3c. E temperatures - LESS THAN temperature less than (T08) F (T08) F, IHEN do Step 3b and c.
- b. Verify main FW flow control b. Manually close valves, valves - CLOSED
- c. Verify feed flow to SGs c. Establish feed flow to the SGs using SFW. E SFW HQI available AND SG narrow ,
range level less than (L36)%, IBEN verify PRHR '
actuated. E HQI, IHEN manually actuate PRHR. ;
i 4 Verify All Control Rods Fully H two or more control rods HQI Inserted fully inserted, IHEN immediately borate (B01) ppm for each control rod not fully inserted.
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Number Title Rev./Date AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check RCS Makeup Status:
- a. PRZR level - GREATER THAN a. Verify one makeup pump (L37)% running. H HQI, E manually start one makeup pump,
- b. PRZR level - LESS THAN b. Verify all makeup pumps
('.38)% stopped. If HQI, E manually stop all makeup pumps.
- c. Operate makeup and letdown as necessary to maintain PRZR level - BETWEEN (L37)%
AND (L38)%
6 Check CMT Status:
- a. PRZR level - GREATER THAN a. Verify CMT injection valves (L17)% open. If HQI, M manually open valves. Continue with Step 7. M PRZR level l Greater than (L17)%, M do Step 6b.
- b. Verify CMT injection b. Manually close valves.
valves - CLOSED l
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I Number Title Rev./Date
'pV AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. 0 5/31/95 [
f STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check PRZR Pressure Control: ;
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Go to AE-0, AP600 REACTOR ;
TRIP OR SAFETY INJECTION, Step 4. '
- b. Pressure - STABLE AT OR b. E pressure less than (P12) '
TREhDING T0 (P12) PSIG psig and decreasing, M :
I) Verify PRZR spray valves closed. H N01, M manually close. E valve (s) can HQI be ,
closed, IHfH close PRZR ,
spray valve (s) block valve. E valve (s) can -
NOI be closed, E stop RCP(s) spray valve supply)ing (s . failed
- 2) Verify PRZR heaters on.
H NQI, IHEN manually turn on.
E(P12 p)ressure PSIG and greater than increasing, IHEN:
- 1) Verify PRZR heaters- off.
H NQI, IHEN manually turn off.
- 2) Control pressure using nomal PRZR spray. E nomal spray HQI available IHEN use auxiliary spray.
O Page 5 of 9
Number Title Rev./Date AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- If the Deaerator Storage Tank level decreases to less than (LO8), the SFW pump suction should be transferred to the CST.
8 Check SG Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow THAN (LO3)% greater than (F01) gpm until narrow range level greater than (LO3)% in at least one SG.
- b. Control feed flow to b. E narrow range level in any maintain narrow range level intact SG continues to between (LO3)% and 50% increase, IllEN stop feed to that SG.
9 Transfer Condenser Steam Dump To H condenser 110.I available, IliEN Pressure Control Mode use SG PORVs.
NOTE RCPs 1A and 18 should be run to provide normal PRZR spray.
10 Check RCP Status - AT LEAST TWO Try to start RCPs IA and IB:
RUNNING
- a. Establish conditions for starting RCPs:
[ Include additional AP600 details in E0Ps].
- b. Start RCPs IA and 18. E no RCP can be started IllEN refer to ATTACHMENT A to verify natural circulation. E natural circulation 1101 verified, IllEN increase dumping steam.
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Number Title Rev./Date t Q AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. O h 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED I
11 Check If Source Range Detectors Should Be Energized:
- a. Check intemediate range a. Continue with Step 12. luiEN flux - LESS THAN (V02) flux less than V02), IllEN do Steps lib an c.
- b. Verify source range b. Manually energize source detectors - ENERGIZED range detectors.
12 Shut Down Unnecessary Plant Equipment:
[ Include additional AP600 details in E0Ps]
13 Maintain Stable Plant Conditions:
. PRZR pressure - AT (P12) PSIG e PRZR level - BETWEEN (L37)%
AND (L38)%
. SG narrow range levels -
BETWEEN (LO3)% AND 50% !
e RCS average temperature - AT -
(T04) F l 1
14 Determine If Natural Circulation !
Cooldown Is Required:
- a. Criteria - MET a. Go to appropriate plant
[ Include additional AP600 details in E0Ps]
i
- b. Go to AES-0.2, AP600 NATURAL i CIRCULATION C00LDOWN, Step 1
- END - 1 O i Page 7 of 9
Number Title Rev./Date AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. 0 5/31/95 ATTACHMENT A The following conditions support or indicate natural circulation flow:
e RCS subcooling based on core exit TCs - GREATER THAN (501) F e SG pressures - STABLE OR DECREASING e RCS hot leg temperatures - STABLE OR DECREASING e Core exit TCs - STABLE OR DECREASING e RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE O
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e Number Title Rev./Date O AES-0.1 AP600 REACTOR TRIP RESPONSE Rev. 0 5/31/95 i i
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FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted '
parameters used in this guideline. ,
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AES-0.2 '
Natural Circulation Cooldown ;
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I Number Title Rev./Date j AES-0.2 g
} AP600 NATURAL CIRCULATION C00LDOWN Rev. 0 5/31/95 j A. PURPOSE This guideline provide: actions to perform a natural circulation RCS cooldown and depressurization to cold shutdown, with no accident in progress, under i requirements that will preclude any upper head void formation.
- 8. SYMPTDMS OR ENTRY CONDITIONS This guideline is entered from-
- 1) AES-0.1, AP600 REACTOR TRIP RESPONSE, Step 14, when it has been determined that a natural circulation cooldown is required.
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Page 1 of 9
Number Title Rev./Date AES-0.2 AP600 NATURAL CIRCULATION C00LDOWN Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If SI actuation occurs during this guideline, AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, should be performed.
NOTE
- Foldout page should be open.
- RCPs 1A and 18 should be run to provide normal PRZR spray.
- If conditions can be established for starting an RCP during this guideline, Step 1 should be repeated.
1 Try To Restart At Least One RC":
- a. Establish conditions for a. Go to Step 2.
starting RCPs:
[ Include additional AP600 details in E0Ps]
- b. Start at least one RCP b. Go to Step 2.
- c. Go to appropriate plant procedure [ Include additional AP600 details in E0Ps]
2 Borate RCS To Cold Shutdown Boron Concentration 3 Verify Cold Shutdown RCS Boron Return to Step 2.
Concentration By Sampling:
[ Include additional AP600 details in E0Ps]
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Number Title Rev./Date AES-0.2 Rev. 0 (pf AP600 NATURAL CIRCULATION C00LDOWN 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check RCS Makeup Control System: Adjust controls as necessary.
- a. Makeup set for greater than or equal to cold shutdown ;
boron concentration
- b. Makeup set for automatic control 5 Verify All CRDM Fans - RUNNING Start all fans. 4 CAUTION If the Deaerator Storage Tank level decreases to less than (LO8), the SFW pump suction should be transferred to the CST.
6 Initiate RCS Cooldown To Cold Shutdown:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN (T09) F/HR
If PORVs HQI available, IliEff use PRHR.
- c. Maintain SG narrow range c. Control feed flow as level - AT (L19)% necessary.
- d. Maintain RCS temperature and l ressure - WITHIN LIMITS OF p(C01) 7 Check RCS Hot Leg Temperatures - Return to Step 6. 1 i LESS THAN 550 F 8 Depressurize RCS To (P13) PSIG:
- a. Check letdown - IN SERVICE a. Try to establish letdown.
- b. Use auxiliary spray b. Use one set of first stage PRZR ADS valves.
Page 3 of 9
Number Title Rev./Date AES-0.2 AP600 NATURAL CIRCULATION C00LDOWN Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION SI actuation PRZR circuits pressure will automatically increases to greater than (unblock P14) psig.if 9 Block SI Actuation:
. Low steam pressure e Low T-cold e Low PRZR pressure 10 Maintain Following RCS Conditions:
e RCS pressure - AT (P13) PSIG
- PRZR level - AT (LI8)%
e Cooldown rate in RCS cold legs - LESS THAN (T09) F/HR e RCS temperature and pressure -
WITHIN LIMITS OF (C01) 11 Monitor RCS Cooldown:
. Core exit TCs - DECREASING e RCS hot leg temperatures -
DECREASING e RCS subcooling based on core exit TCs - INCREASING l
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Nanber Title Rev./Date AES-0.2 AP600 NATURAL CIRCULATION C00LDOWN Rev. O Os 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Initiate RCS Depressurization:
- a. Check CRDM fans - ALL a. Perform the following (S06)
RUNNING actions. Go to Step 12c.
GREATER THAN (S07) F
- c. Use auxiliary spray c. Use one set of first stage PRZR ADS valves.
13 Continue RCS Cooldown And Depressurization:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN (T09) F/HR r
- b. Maintain subcooling b. Stop depressurization and requirements of Step 12 reestablish subcooling.
- c. Maintain RCS temperature and ressure - WITHIN LIMITS OF p(C01) 14 Verify Steam Void In Reactor Repressurize RCS within limits of Vessel Does Not Exist: (C01) to collapse potential voids :
in system and continue cooldown.
- PRZR level - NO UNEXPECTED LARGE VARIATIONS i
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Page 5 of 9
Number Title Rev./Date AES-0.2 AP600 NATURAL CIRCULATION C00LDOWN Rev. 0 5/31/90 l
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l l
l 15 Check If SI Accumulators Should Be Isolated:
- a. Criteria - MET a. Continue with Step 16. Et1B requirements met,1110 do
[ Include additional AP600 Step 15b.
details in E0Ps]
i
- b. Check power to isolation b. Restore power to isolation valves - AVAILABLE valves.
- c. Close both SI accumulator l l isolation valves 16 Maintain Letdown Flow 17 Check If RNS Can Be Placed In Service:
- a. RCS temperature - LESS THAN a. Return to Step 13.
(T06) F
- b. RCS pressure - LESS THAN b. Return to Step 13.
(P08) PSIG
- c. Place RNS in service using
[ Include additional AP600 details in E0Ps]
l 18 Continue RCS Cooldown To Cold Shutdown O
Page 6 of 9
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i Ntmiber Title Rev./Date f ~~ AES-0.2 AP600 NATURAL CIRCULATION C00LDOWN Rev. 0
( 5/31/95 STEP ACTION #57.PECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Depressurizing the RCS before the entire RCS is less than 2001= may result in void fonnation in the RCS.
19 Continue Cooldown Of Inactive Portion Of RCS:
. Cool upper head region using CRDM fans e Cool SG U-tubes by dumping steam from all SGs 20 Determine If RCS Depressurization Is Permitted:
Return to Step 18.
~
- b. Go to appropriate plant procedure
- END -
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Number Title Rev./Date AES-0.2 AP600 NATURAL CIRCULATION C00LDOWN Rev. 0 5/31/95 FOLDOUT AE-0 SERIES GUIDELINES
- 1. SI ACTUATION CRITERIA Actuate SI and go to AE-0, REACTOR TRIP OR SAFETY INJECTION, Step 1, if E1IHEB condition listed below occurs:
. RCS subcooling based on core exit TCs - LESS THAN (S01) F [(S02) F FOR ADVERSE CONTAINMENT]
PRZR level - CANNOT BE MAINTAINED GREATER THAN (LO5)% [(L23)% FOR ADVERSECONTAINMENT]
- 2. RED PATH
SUMMARY
- a. SUBCRITICALITY - Nuclear power greater than S%.
- b. CORE COOLING - Core exit TCs greater than 1200 F
- c. HEAT SINK - Narrow range level in all SGs less than (LO3)%[(LO4)% FOR ADVERSE CONTAINMENT] MD total feedwater flow less than (F01) gpm MD PRHR not in service
- d. INTEGRITY - Cold leg temperature decrease greater than 100 F in last 60 minutes MD RCS cold leg temperature less than (T14) F
- e. CONTAINMENT - Containment pressure greater than (P21) PSIG
- 3. SFW SUPPLY SWITCH 0VER CRITERION Switch to CST if deaerator storage tank level decreases to less than (LO8).
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Number Title Rev /Date AES-0.2 AP600 NATURAL CIRCULATION C00LD0WN Rev. 0 l 5/31/95 !
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FOOTNOTES i Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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AE-1 Loss of Reactor or Secondary Coolant O I l
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l Number Title Rev./Date AE-1 AP600 LOSS OF REACTOR OR SECONDARY C0OLANT Rev. 0 l 5/31/95 h
A. PURPOSE l This guideline provides actions to recover from a loss of reactor or secondary coolant. !
B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from:
- 1) AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 24, with any of'the ;
following symptoms: high containment radiation, high containment pressure, ,
or high containment level.
I +
- 2) AES-1.1, AP600 PASSIVE SAFETY SYSTEMS TERMINATION, Step 4 and Step 22, and AFR-I.2, AP600 RESPONSE TO LOW PRESSURIZER LEVEL, Step 4, if SI has to be reinitiated. !
- 3) AE-2, AP600 FAULTED STEAM GENERATOR ISOLATION, Step 6, after identification and isolation of a faulted SG.
O 4) AECA-1.1, AP600 LOCA OUTSIDE CONTAINMENT, Step 2, after actions to isolate a LOCA outside containment have been taken.
l
- 5) AFR-C.1, AP600 RESPONSE TO INADEQUATE CORE COOLING, Step 17 and Step 25, and :
AFR-C.2, AP600 RESPONSE TO DEGRADED CORE COOLING, Step 15, after core ;
cooling has been re-established. l
- 6) AFR-H.1, AP600 RESPONSE TO LOSS OF HEAT SINK, Step 2, if RCS pressure is less than all non-faulted SG(s) pressure. {
i
- 7) AFR-H.1, AP600 RESPONSE TO LOSS OF HEAT SINK, Step 16, after ADS has been actuated.
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Page 1 of 10 l
Naber Title Rev./Date AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE
- Foldout page should be open.
1 Check If Any SGs Are Faulted:
e NO SG PRESSURE DECREASING IN AN UNC014 TROLLED MANNER e Steamlines.
. NO SG COMPLETELY e Feedlines.
DEPRESSURIZED JE NQI, IEEN go to AE-2, AF600 FAULTED STEAM GENERATOR ISOLATION, Step 1.
CAUTION
- If the Deaerator Storage Tank level decreases to less than (LO8), the SFW pump suction should be transferred to the CST.
2 Check Intact SG Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow THAN (LO3)% [(LO4)% FOR greater than (F01) gpm until ADVERSE CONTAINMENT] narrow range level greater than (LO3)% [(LO4)% for adverse containment] in at least one SG.
- b. Control feed flow to b. If narrow range level in any maintain narrow ran e level SG continues to increase in between (LO3)% [(L0 )% for an uncontrolled manner, IHEN adverse containment and 50% go to AE-3, AP600 STEAM GENERATOR TUBE RUPTURE, Step 1.
3 Check Secondary Radiation - Go to AE-3, AP600 STEAM GENERATOR NORMAL TUBE RUPTURE, Step 1.
[ Include additional AP600 details in E0Ps]
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.. - _ ~ . . . - - .. . - - - - _ . . .
Number Title Rev./Date AE-1 Rev. 0 O AP600 LOSS OF REACTOR OR SECONDARY COOLANT 5/31/95 .
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
If adverse containment conditions exist, RCS makeup CAUTION should be operated in manual to maintain pressurizer ,
level. .
i 4 Check RCS Makeup Status l
- a. PRZR level - GREATER THAN a. Verify one makeup pump !
(L05)%[(L23)% FOR ADVERSE running. IE EI, IBEN CONTAINMENT] manually start one makeup pump. IE level continues to decrease or cannot be restored. IBEN start second makeup pump.
- b. PRZR level - LESS THAN b. Verify all makeup pumps (LO6)%[(L31 stopped. IE EI, IEEN CONTAINMENT;?%FORADVERSE manually stop all makeup pumps.
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Number T1 tie Rev./Date AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT Rev. 0 5/31/95 STFP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check If Passive Safety Systems Should Be Terminated:
- a. RCS subcooling based on core a. Go to Step 7.
exit TCs - GREATER THAN (501) F [( 2) F FOR ADVERSE CONTAINMENT
- b. RCS heat sink: b. If neither condition satisfied, JBEH go to
. Total feed flow to intact Step 7.
SGs - GREATER THAN (F01)
GPM
-0R-
. Narrow range level in at least one intact SG -
GREATER THAN (LO3)%
[(LO4)% FOR ADVERSE C0lTAINMENT]
-OR- i e PRHR - IN OPERATION l
INCREASING
- d. PRZR level - GREATER THAN d. Go to Step 7.
(LO5)% [(L2 )% FOR ADVERSE CONTAINMENT l 6 Go To AES-1.1, AP600 PASSIVE ,
+
SAFETY SYSTEMS TERMINATION, Step !
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Page 4 of 10
Number Title Rev./Date N AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT Rev. 0 1 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
7 Check If ADS Should Be Actuated:
- a. CMT level - LESS THAN (L01)% a. E RCS hot leg level indication reater than (L32) [(L33 % FOR ADVERSE CONTAINMENT , ItiEN 90 to .
Step 8. IE ROI, ItiEN l manually actuate ADS.
l b. Verify first stage ADS b. Manually open valves as ,
isolation valves - OPEN necessary. I
- signal, IHEN verify second I stage ADS valves open. If HQI, IHEN manually open second stage ADS valves as necessary.
- d. Check third stage ADS d. WtiEN (T02) seconds have valves - OPEN elapsed from second stage ADS signal, IHEN verify third stage ADS valves open.
If HQI, ItiEN manually open third stage ADS valves as necessary.
- e. Align RNS to inject into RCS l
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Number T1 tie Rev./Date AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT Rev. O l 5/31/95 ;
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check If Passive Containment Cooling Should Be Stopped:
- a. Passive containment a. Go to Step 9.
cooling - OPERATING 1
- b. Containment pressure - LESS b. Continue with Step 9. WiiEN l THAN (P10) PSIG containment pressure less I than (P10) psig, IHEN do '
Steps 8c and d.
- c. Reset passive containment ;
cooling signal l 1
- d. Stop passive containment cooling and place in standby:
[ Include additional AP600 details in E0Ps]
9 Check RCS And SG Pressures: Return to Step 1.
1 e Check pressure in all SGs - l STABLE OR INCREASING l l
e Check RCS pressure - STABLE OR !
DECREASING 10 Check If Diesel Generators Should Be Stopped
- a. Verify ECS ac busses - a. Try to restore offsite power l ENERGIZED BY OFFSITE POWER to ECS ac busses. IE offsite power can HQI be restored, IHEN load the following equipment on ac busses:
[ Include additional AP600 details in E0Ps]
- b. Stop any unloaded diesel generator and place in ,
standby 1 Page 6 of 10 l
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.. Number Title Rev./Date p)
(
AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT Rev. 0 5/31/95 :
i l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 Initiate Evaluation Of Plant !
Status: :
- a. Check auxiliary building a. Try to identify and isolate radiation - NORNAL 1eakage:
i
[ Include additional AP600 [IncludeadditionalAP600 l details in E0Ps] details in E0Ps]
IE the cause is a loss of RCS inventory outside l containment, IHEN go to AECA-1.1, AP600 LOCA OUTSIDE '
CONTAINMENT, Step 1.
- b. Obtain samples: <
[IncludeadditionalAP600 details in E0Ps]
- c. Evaluate plant equipment: '
[ Include additional AP600 details in E0Ps]
- d. Start additional plant i equipment to assist in ,
recovery
[ Include additional AP600 l details in E0Ps] ,
i 12 Check If RCS Cooldown And ,
Depressurization Is Required: i
(P03) PSIG [(P04) PSIG FOR (F02) gpm. IHEN 90 to ,
ADVERSE CONTAINMENT] Step 13. i i
ACTUATED
- c. Go to AES-1.2 AP600 POST LOCA C00LDOWN AND l DEPRESSURIZATION Step 1. !
O l Page 7 of 10 -!
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I Number Title Rev./Date l AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT Rev. 0 l 5/31/95 l l
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED )
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13 Check If Fourth Stage ADS Should l Be Actuated: l l
- a. CMT level - LESS THAN (L10)% a. Perfonn the following:
- 1) If CMT level decreases to less than (L10)%, IHEN do Steps 13b and c.
- 2) If P,CS hot leg level I indication decreases to less than (L32) [(L33)%
FOR ADVERSE CONTAINMENT],
IHEN manually actuate fourth stage ADS and do Steps 13b and c.
- 3) Continue with Step 14.
- b. Verify fourth stage ADS b. Manually open valves as isolation valves - OPEN necessary.
- c. Verify IRWST injection c. Manually open valves as isolation valves - OPEN necessary.
14 Check IRWST Level:
- a. IRWST level - LESS THEN a. Continue with Step 15. MtiEN (L11)% IRWST level less than (L11)%, IHEN do Step 14b.
- b. Verify containment sump b. Manually align valves as recirculation valves - OPEN necessary.
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l Number Title Rev./Date l p AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT Rev. O !
\.) 5/31/95 l
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If SI Accumulators should Be Isolated: !
- a. Reset SI if necessary I
- b. At least two RCS hot leg b. Continue with Step 16. IniEli i temperature channels - LESS at least two RCS hot leg l THAN (T05) F temperatures less than (T05) F, IllEti do Steps 15c and d.
1' I
- c. Check power to isolation c. Restore power to isolation valves - AVAILABLE valves.
- d. Close both SI accumulator d. Vent any unisolated isolation valves accumulators.
16 Check If Intact SGs Should Be Depressurized To RCS Pressure:
- a. RCS pressure - LESS THAN a. Go to Step 17.
INTACT SG PRESSURES
[ Include additional AP600 feed flow to a SG with high details in E0Ps] radioactivity,
- c. Dump steam to condenser from c. Dump steam using intact SG )
intact SGs until SG pressure PORVs until SG pressure less l less than RCS pressure than RCS pressure.
17 Determine If Reactor Vessel Head Should Be Vented 18 Evaluate Long Term Plant Status ,
- END -
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_ ___ _ _ _ _ _ _ _ _ _ _ _ . i
Number Title Rev./Date AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT Rev. 0 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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Page 10 of 10
O AES-1.1 Passive Safety Systems Termination lO
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i Number Title Rev./Date j Q AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. 0 5/31/95 l
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A. PURPOSE This guideline provides the necessary instructions to tenninate safety injection and stabilize plant conditions.
B. SYMPTOMS OR ENTRY CONDITIONS ;
This guideline is entered from AE-0, REACTOR TRIP OR SAFETY INJECTION, Step 26, and AE-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 6, when specified tennination criteria are satisfied, fe O
Page 1 of 9
Number Title Rev.,9 ate AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Foldout page should be open.
1 Reset SI 2 Reset Containment Isolation 3 Close CHT Injection Valves 4 Verify CMT Injection Not Required:
- a. RCS subcooling based on core a. Perform the following:
exit TLs - GREATER THAN (501) F [(S02 1) Manually open CMT CONTAINMENT] ) F FOR ADVERSE injection valves.
- 2) Go to AE-1. AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- b. PRZR level - GREATER THAN b. Perfom the following:
(LO5)% [(L23 CONTAINMENT])% FOR ADVERSE a) Manually open CMT injection valves. j b) G0 to AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
O Page 2 of 9
l Number Title Rev./Date 1
~
g AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. O ;
j 5/31/95 ,
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
^
CAUTION If adverse containment conditions exist, RCS makeup should be operated in manual to maintain pressurizer level.
5 Check RCS Makeup Status:
, a. PRZR level - GREATER THAN a. Verify one makeup pump running. IE 1101 ItiEti CONTAINMENT.}i(LO5)%[(L23 % FOR manually ADVERSE start one makeup pump.
- b. PRZR level - LESS THAN b. Verify all makeup pumps (LO6)%[(L31)% FOR ADVERSE stopped. IE fiOI, ItiEtl CONTAINMENT] manually stop all makeup !
pumps.
- c. Operate makeup and letdown 4 as necessary to maintain PRZR level - BETWEEN (LO5)%
AND (LO6)%[BETWEEN (L23)%
O AND (L31)% FOR ADVERSE CONTAINMENT]
6 Check If PRNR Should Be Isolated
- a. Check the following: a. Go to Step 7.
- SFW - IN OPERATION i i
e Narrow range level in at t least one SG - GREATER THAN (LO3)% [(LO4)% FOR ADVERSE CONTAINMENT] i
- b. Close PRHR isolation valves 7 Realign Other Components To Pre-SI Configuration: ,
- a. [ Include additional AP600 details in E0Ps]
O -
Page 3 of 9 f
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Number Title Rev./Date AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Check if Passive Containment Cooling Should Be Stopped:
- a. Passive containment a. Go to Step 9.
cooling - OPERATING
- b. Containment pressure - LESS b. Continue with Step 9. MIEli THAN (P10) PSIG containment pressure less than (P10) psig, IllEN do Steps ac and d.
- c. Reset passive containment cooling signal
- d. Stop passive containment cooling and place in standby:
[ Include additional AP600 details in E0Ps]
9 Verify All Control Rods Fully E two or more control rods 1i01 Inserted fully inserted, IllEN immediately borate (B01) ppm for each control rod not fully inserted.
10 Check RCS Makeup Control System: Adjust controls as necessary
- b. Makeup set for automatic control 11 Transfer Condenser Steam Dump To H condenser 1f01 available,111EN .
Pressure Control Mode use SG PORVs. l 12 Check RCS Hot Leg Temperature - Control steam dump and total feed STABLE flow as necessary to stabilize i RCS temperatures.
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Page 4 of 9 I
Number Title Rev./Date l AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. O !
C' 5/31/95 l l
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Control PRZR Pressure:
- a. Check letdown - IN SERVICE a. Try to establish letdown.
- b. Maintain pressure stable using PRZR heaters and PRZR r auxiliary spray as necessary CAUTION
- If the Deaerator Storage Tank level decreases to less than (LOB), the SFW pump suction should be transferred to the CST.
14 Check Intact SG Levels:
- a. Narrow ran e level - GREATER a. Maintain total feed flow THAN (LO3) [(LO4)%FOR greater than (F01) gpm until ADVERSE CONTAINMENT] narrow ran e level greater than (LO3) [(LO4)% for O adverse containment] in at least one SG.
- b. Control feed flow to b. If narrow range level in any maintain narrow ran e level SG continues to increase, i between (LO3)% [(LO )% for IliEN stop feed flow to that adverse containment and 50% SG.
i 15 Check RCP Cooling: Establish normal cooling to RCP(s). Refer to [ Include e RCP'CCS flow - NORMAL additional AP600 details in e RCP temperature (s) - NORMAL 16 Verify All ECS AC Busses - Try to restore offsite power to ;
ENERGIZED BY OFFSITE POWER ECS ac busses. IE offsite power can NQLbe restored. IllEN load i the following equipment on ac emergency busses:
[ Include additional AP600 details in E0Ps]
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Number Title Rev./Date AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE RCPs 1A and 1B should be run to provide normal PRZR spray.
17 Check RCP Status - AT LEAST TWO Try to start RCPs 1A and IB:
RUNNING
- a. Establish conditions for starting RCPs:
[ Include additional AP600 details in E0Ps]
- b. Start RCPs 1A and IB. If no RCP can be started. IHEN refer to ATTACHMENT A to verify natural circulation. If natural circulation HQI verified. IHEH increase dumping steam from intact SGs.
18 Check If Source Range Detectors should Be Energized:
- a. Check intermediate range a. Continue with Step 19. WHEN flux - LESS THAN (V02) flux less than (V02), IHE3 do Steps 18b and c.
- b. Verify source range b. Manually energize source detectors - ENERGIZED range detectors.
19 Check If Diesel Generators should Be Stopped:
POWER
- b. Stop any unloaded diesel generator and place in standby O
Page 6 of 9 l
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Naber Title Rev./Date AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. 0 p/
y 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Shut Down Unnecessary Plant Equipment:
[ Include additional AP600 details in E0Ps]
21 Maintain Plant Conditions -
STABLE l e PRZR pressure e PRZR level e RCS temperatures e Intact SG levels 22 Verify CNT Injection Not O Required:
- a. RCS subcooling based on core a. Perform the following:
exit TCs - GREATER THAN (501) F [( 2) F FOR ADVERSE 1) Manually open CMT CONTAINMENT injection valves.
- 2) Go to AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- b. PRZR level - GREATER THAN b. Perform the following: <
(LOS)% [(L23 CONTAINMENT])% FOR ADVERSE a) Manually ope 1 CMT injection valves. ,
b) Go to AE-1, AP600 LOSS OF l REACTOR OR SECONDARY COOLANT, Step 1.
23 Go To Appropriate Plant Procedure
- END -
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Number Title Rev./Date AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. 0 5/31/95 ATTACHMENT A The following conditions support or indicate natural circulation flow:
RCS subcooling based on core exit TCs - GREATER THAN (S01) F [(S02) F FOR ADVERSE CONTAINMENT]
= RCS hot leg temperatures - STABLE OR DECREASING Core exit TCs - STABLE OR DECREASING e RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE O
O Page 8 of 9
+
Number Title Rev./Date ;
, f( AES-1.1 AP600 PASSIVE SAFETY SYSTEMS TERMINATION Rev. 0 5/31/95 I
FOOTNOTES I
Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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AES-1.2 l
Post LOCA Cooldown and Depressurization O
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Rev./Date Number Title '
O AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. 0 5/31/95 i
A. PURPOSE This guideline provides actions to cool down and depressurize the RCS to cold shutdown conditions following a loss of reactor coolant inventory.
B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 12 when RCS pressure is greater than the RNS cut-in pressure and ADS is not actuated.
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O Page 1 of 15
Number Title Rev./Date l AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. O I 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Foldout page should be open.
1 Verify All ECS AC Busses - Try to restore offsite power to ENERGIZED BY OFFSITE POWER ECS ac busses. IE offsite power can HOI be restored, M load the following equipment on ac busses:
[ Include additional AP600 details in E0Ps]
CAUTION
- If IRWST level decreases to less than (L11), RNS alignment to the containment sump should be veri fled.
- If adverse containment conditions exist, RCS makeup should be operated in manual to maintain pressurizer level.
2 Check RCS Makeup Status
- a. PRZR level - GREATER THAN a. Verify one makeup pump (LO5)%[(L23 % FOR ADVERSE runnin . If HQI, M CONTAINMENT manual y start one makeup purrp. IF. level continues to decrease or cannot be restored, M start second makeup pump.
- b. PRZR level - LESS THAN b. Verify all makeup pumps (LO6)%[(L31)% FOR ADVERSE stopped. IE EDI, M CONTAINMENT] manually stop all makeup pumps.
- c. Operate makeup and letdown as necessary to maintain PRZR level - BETWEEN (LOS)%
AND (LO6)%[BETWEEN (L23)%
AND (L31)% FOR ADVERSE ,
CONTAINMENT] :
O'!
Page 2 of 15 j
Number Title Rev./Date l D AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check If PRHR Should Be Isolated
- a. Check the following: a. Go to Step 4. .
I l e SFW - IN OPERATION e Narrow range level in at least one SG - GREATER THAN (LO3)% [(LO4)% FOR ADVERSE CONTAINMENT] ,
l
- b. Close PRHR isolation valves CAUTION
- If the Deaerator Storage Tank level decreases to less than (LOB), the SFW pump suction should be transferred to the CST.
4 Check Intact SG Levels: i
- a. Narrow ran e level - GREATER a. Maintain total feed flow THAN (LO3) [(LO4)% FOR greater than (F01) gpm until ADVERSE CONTAINMENT] narrow range level greater than (LO3)% [(LO4)% for adverse containment] in at least one SG.
- b. Control feed flow to b. IE narrow range level in any maintain narrow ran e level SG continues to increase in between (LO3)% [(L0 )% for an uncontrolled manner, IRS adverse containment and 50% go to AE-3, AP600 STEAM GENERATOR TUBE RUPTURE, Step 1.
I i
O l Page 3 of 15
Number Title Rev./Date AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE
- Low steamline pressure SI and low T-cold SI should be blocked when PRZR pressure decreases to less than (P06) psig.
- After the low steamline pressure SI signal is blocked, main steamline isolation will occur if the high steam pressure rate setpoint is exceeded.
- Shutdown margin should be monitored during RCS cooldown.
5 Initiate RCS Cooldown To Cold Shutdown:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100 F/HR
- c. Use RNS if in service
- d. Use PRHR as necessary 6 Turn All PRZR Heaters OFF O
Page 4 of 15
Number Title Rev./Date AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. O j 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSIAINED CAUTION
- Voiding may occur in the RCS during RCS depressurization. This will result in a rapidly increasing PRZR level.
- Cycling of the PRZR ADS valves should be minimized.
7 Depressurize RCS To Refill PRZR:
- a. Use auxiliary spray a. Use one set of first stage PRZR ADS valves.
- b. PRZR level - GREATER THAN b. Continue with Step 8. When (LO7)% [(LO9 level greater than (LO7)%
CONTAINMENT])% FOR ADVERSE
[(LO9)% for adverse containment] . TliEN do Step 7c.
- c. Stop RCS depressurization O
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Number Title Rev./Date AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. O i 5/31/95 l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l 8 Check If ADS Should Be Actuated:
- a. CMT level - LESS THAN (L01)% a. E RCS hot leg level indication greater than (L32) [(L33 CONTAINMENT;)%FORADVERSE
, M go to Step 9. E E E manually actuate ADS. I
- b. Verify first stage ADS b. Manually open valves as isolation valves - OPEN necessary.
- c. Check second stage ADS c. M (T01) seconds have valves - OPEN elapsed from first stage ADS signal, M verify second stage ADS valves open. E E , M manually open second stage ADS valves as necessary,
- d. Check third stage ADS d. M ( 02) seconds have valves - OPEN elapsed from second stage ADS signal, M verify third stage ADS valves open.
E E , E manually open third stage ADS valves as necessary.
- e. Align RNS to inject into RCS
- f. Go to Step 10 I
O Page 6 of 15 l
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Number Title Rev./Date
/" AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. 0
( 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check If CMT Injection Should Be Isolated:
- a. ADS - NOT ACTUATED a. Go to Step 10.
- b. RCS subcooling based on core b. Go to Step 10.
exit TCs - GREATER THAN (501) F [(S02 CONTAINMENT] ) F FOR ADVERSE
- c. PRZR level - GREATER THAN c. Go to Step 10.
(LOS)% [(L23 CONTAINMENT])% FOR ADVERSE l
- d. Close CMT injection valves 10 Verify CMT Injection Not Required:
]
(S01) F [(S02) F FOR ADVERSE CONTAINMENT]
- b. PRZR level - GREATER THAN b. Manually open CMT injection (LOS)% [(L2 )% FOR ADVERSE valves.
CONTAINMENT 11 Check RCP Cooling: Establish normal cooling to RCP(s). Refer to [ Include
. RCP CCS flow - NORMAL additional AP600 details in e RCP temperature (s) - NORMAL I
!o j
Page 7 of 15
Number Title Rev./Date AES-1.2 AP600 POST LOCA COOLDOWN AND DEPRESSURIZATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE RCPs 1A and 18 should be run to provide nonval PRZR spray.
12 Check If RCPs Shocid Be Started:
Go to Step 13.
- b. RCS subcooling based on core b. Go to Step 13.
exit TCs - GREATER THAN (S01) F [(S 2) F FOR ADVERSE CONTAINMENT
- c. PRZR level - GREATER THAN c. Return to Step 7.
(LO7)% [(LO )% FOR ADVERSE CONTAINMENT
- 1) Establish conditions for to verify natural starting RCPs: circulation. If natural circulation NDI verified,
[ Include additional AP600 IBEH increase dumping steam, details in E0Ps]
- 2) Start RCPs O
Page 8 of 15 I l
Number Title Rev./Date
('s AES-1.2 AP600 POST LOCA C00LD0WN AND DEPRESSURIZATION Rev. 0
'() 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- Voiding may occur in the RCS during RCS depressurization. This will result in a rapidly increasing PRZR level.
- Cycling of the PRZR ADS valves should be minimized.
- If CMT injection is necessary to maintain PRZR level, RNS pumps should be started to inject into the RCS when RCS pressure is less then (P03) [(PO4)%
FOR ADVERSE CONTAINMENT]
13 Depressurize RCS To Minimize RCS Subcooling:
- a. Use nonnal PRZR spray a. Use auxiliary spray. If auxiliary spray HQI available, IHEN use one set of first stage PRZR ADS valves.
O V b. Turn on PRZR heaters as necessary
- c. Depressurize RCS until EITHER of the following conditions satisfied:
e PRZR level - GREATER THAN (L13)% [(L14)% FOR ADVERSE CONTAINMENT]
-0R-
. RCS subcooling based on core exit TCs - LESS THAN (503) F [(SO4) F FOR ADVERSE CONTAINMENT]
14 Verify Adequate Shutdown Marg'n:
- a. Sample RCS
- b. Shutdown margin - ADEQUATE b. Borate as necessary.
O Page 9 of 15
Number Title Rev./Date AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Check If SI Accumulators Should Be Isolated:
- a. RCS subcooling based on core a. E both RCS hot leg exit TCs - GREATER THAN temperatures less than (S01) F [(S02 (T05) F, IllEN go to CONTAINMENT] ) F FOR ADVERSE Step 15c. E fiQI, IllEN go to Step 16.
- b. PRZR level - GREATER THAN b. Return to Step 7.
(LO7)% [(LO )% FOR ADVERSE CONTAINMENT
- c. Check power to isolation c. Restore power to isolation valves - AVAILABLE valves.
- d. Close all SI accumulator d. Vent any unisolated isolation valves accumulators.
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Page 10 of 15
Number- Tltle Rev./Date AES-1.2 AP600 POST.LOCA C00LD0WN AND DEPRESSURIZATION Rev. 0
( 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check If Diesel Generators should Be Stopped:
i
- a. Verify ECS ac busses - a. Try to restore offsite power i
ENERGIZED BY OFFSITE POWER to ECS ac busses. 1E offsite power can HQI be restored, M loadthe following equipment on ac busses:
[ Include additional AP600 details in E0Ps]
- b. Stop any unloaded diesel generator and place in standby 17 Check If Passive Containment Cooling Should Be Stopped:
- a. Passive containment a. Go to Step 18.
O cooling - OPERATING l
- b. Containment pressure - LESS b. Continue with Step 18. M THAN (P10) PSIG containment pressure less than (P10) psig, E do Steps 17c and d.
- c. Reset passive containment I cooling signal
- d. Stop passive containment cooling and place in standby:
(IncludeadditionalAP600 details in E0Ps]
18 Check If Source Range Detectors Should Be Energized:
- a. Check intermediate range a. Continue with Step 19. M e
flux - LESS THAN (V02) flux less than (V02), M do Steps 18b and c.
- b. Verify source range b. Manually energize source detectors - ENERGIZED range detectors.
Page 11 of 15
Number Title Rev./Date AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 Shut Down Unnecessary Plant Equipment:
[ Include additional AP600 details in E0Ps]
20 Check If RCP(s) Must Be Stopped:
THAN (P07)PSIG pressure - GREATER
[ Additional steps related to normal AP600 cooldown will be placed after Step 20]
21 Check If RNS Can Be Placed In Service:
- a. Check the following: a. Go to Step 22.
. RCS temperatures - LESS THAN (T06)*F [(107)] F FOR ADVERSE CONTAINMENT e RCS pressure - LESS THAN (P08) PSIG [(P09) PSIG FOR ADVERSE CONTAINMENT]
- b. Determine if RNS should be placed in service in accordance with [ Include additional AP600 details in E0Ps]
l l 22 Check RCS Temperatures - LESS Return to Step 2.
l THAN 200 F 23 Evaluate Long Term Plant Status And Maintain Cold Shutdown Conditions l
l
- END -
O Page 12 of 15
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, Nurber Title Rev./Date !
AES-1.2 Rev. O AP600 POST LOCA C00LD0WN AND DEPRESSURIZATION !
5/31/95 4 I
ATTACHMENT A l The following conditions support or indicate natural circulation flow: '
RCS subcooling based on core exit TCs - GREATER THAN (Sol) F [(S02)*F FOR i ADVERSE CONTAINMENT] !
SG pressures - STABLE OR DECREASING i RCS hot leg temperatures - STABLE OR DECREASING i i
Core exit TCs - STABLE OR DECREASING ;
RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE O
O .
Page 13 of 15
l Number Title Rev./Date AES-1.2 AP500 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. 0 5/31/95 FOLDOUT FOR AE-1 SERIES GUIDELINES
- 1. CMT INJECTION CRITERIA Open CMT injection valves if EITHER condition listed below occurs:
. RCS subcooling based on core exit TCs - LESS THAN (S01) F [(S02) F FOR ADVERSE CONTAINMENT]
PRZR level - CANNOT BE MAINTAINED GREATER THAN (LO5)% [(L23)% FOR ADVERSE CONTAINMENT]
- 2. RED PATH
SUMMARY
- a. SUBCRITICALITY - Nuclear power greater than S%.
- b. CORE COOLING - Core exit TCs greater than 1200 F
- c. HEAT SINK - Narrow range level in all SGs less than (LO3)%[(LO4)% FOR ADVERSE CONTAINMENT] AND total feedwater flow less than (F01) gpm AND PRHR not in service
- d. INTEGRITY - Cold leg temperature decrease greater than 100 F in last 60 minutes AND RCS cold leg temperature less than W
(T14) F
- e. CONTAINMENT - Containment pressure greater than (P21) PSIG
- 3. SECONDARY INTEGRITY CRITERIA Go to AE-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, if any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated.
- 4. AE-3 TRANSITION CRITERIA Go to AE-3, STEAM GENERATOR TUBE RUPTURE, Step 1, if any SG level increases in an uncontrolled manner or any SG has abnormal radiation.
- 5. SFW SUPPLY SWITCHOVER CRITERION Switch to CST if deaerator storage tank level decreases to less than (LO8).
O Page 14 of 15
l Number Title Rev./Date O AES-1.2 AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION Rev. 0 5/31/95 i
FOOTNOTES f i
Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline. i i
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Page 15 of 15 i
v , - ,--w..
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AE-2
- Faulted Steam Generator Isolation O
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f Number Title Rev./Date
- ( AE-2 AP600 FAULTED STEAM GENERATOR ISOLATION Rev. 0 5/31/95 F
A. PURPOSE This guideline provides actions to identify and isolate a faulted steam generator.
B. SYMPT 0MS OR ENTRY CONDITIONS This guideline is entered from:
- 1) AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 22, with the following symptoms:
- a. Any SG pressure decreasing in an uncontrolled manner.
- b. Any SG completely depressurized.
- 2) AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1 and AE-3, AP600 STEAM GENERATOR TUBE RUPTURE, Step 5, with the following symptoms and/or conditions:
(% a. Any SG pressure decreasing in an uncontrolled manner.
- b. Any SG completely depressurized,
- c. Faulted SG isolation not verified.
I
- 3) AFR-H.5, AP600 RESPONSE TO STEAM GENERATOR LOW LEVEL, Step 3, when the affected SG is identified as faulted.
- 4) Other guidelines whenever a faulted SG is identified.
l Page 1 of 4 )
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Number Title Rev./Date AE-2 AP600 FAULTED STEAM GENERATOR ISOLATION Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown.
1 Check Main Steamline Isolation Manually close valves.
And Bypass Valves Of Affected SG(s) - CLOSED 2 Identify Faulted SG(s):
- a. Check pressures in all SGs - a. Search for initiating break:
e ANY SG PRESSURE e Main steamlines.
DECREASING IN AN UNCONTROLLED MANNER e Main feedlines.
-OR- e Other secondary piping.
. ANY SG COMPLETELY Go to Step 4.
DEPRESSURIZED Page 2 of 4 i l
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Number Title Rev./Date A AE-2 AP600 FAULTED STEAM GENERATOR ISOLATION Rev. 0
'() 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- If both SGs are faulted and PRHR is not available, at least (F04) gpm feed flow should be maintained to the SG that will be used for RCS cooldown.
3 Isolate Faulted SG(s): Manually close valves. IE valves can HQI be closed, JBEN dispatch
. Isolate main feedline operator to locally close valves or block valves.
. Isolate SFW pump flow e Verify SG PORVs - CLOSED e Verify SG blowdown isolation valves - CLOSED e Isolate other secondary
- piping:
's/ [ Include additional AP600 details in E0Ps]
4 Check Deaerator Storage Tank Switch SFW pump suction to the Level - GREATER THAN (LO8) CST.
S Check Secondary Radiation:
- a. Request periodic activity samples of all SGs:
[ Include additional AP600 details in E0Ps]
- b. Check unisolated secondary radiation monitors
- c. Secondary radiation - NORMAL c. Go to AE-3, AF600 STEAM GENERATOR TUBE RUPTURE, Step 1.
6 Go to AE-1 AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1 b - END -
Page 3 of 4
Number Title Rev,/Date AE-2 AP600 FAULTED STEAM GENERATOR ISOLATION Rev. 0 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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Page 4 of 4
O AE-3 I
Steam Generator Tube Rupture l 1
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,s Number T1 tie Rev./Cate
(' ) AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 A. PURPOSE This guideline provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture.
B. SYMPTOMS OR ENTRY CONDITIONS Thir guideline is entered from:
- 1) AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 23 when condenser air ejector radiation or SG blowdown radiation is abnormal.
- 2) AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 29, AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 3, AE-2, AP600 FAULTED STEAM GENERATOR ISOLATION, Step 5, and AFR-H.3, AP600 RESPONSE TO STEAM GENERATOR HIGH LEVEL, Step 7, when secondary radiation is abnormal.
- 3) AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 28, AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 2,
('T AES-I.2, AP600 POST LOCA C00LDOWN AND DEPRESSURIZATION, Step 4, when a SG
'q ,/ narrow range level increases in an uncontrolled manner.
- 4) AE-1 series foldout page whenever any SG level increases in an uncontrolled manner or any SG has abnormal radiation.
A Page 1 of 22
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I Number Title Rev./Date l AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 l 5/31/95 ;
I STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l
NOTE
- Foldout page should be open.
- Personnel should be available for sampling during this guideline.
1 Identify Ruptured SG(s): Continue with Ste WilEN ruptured SG(ps 4 through 8 s) identified, e Unexpected increase in any SG IllEN do Steps 2 and 3 narrow range level
-0R-
. High radiation from any SG sample
-0R-
. High radiation from any SG steamline
-OR-
. High radiation from any SG blowdown line:
[ Include additional AP600 details in E0Ps]
O Page 2 of 22
i Number Title Rev./Date
(N3 AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0
( j' 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If PRHR is not available, one SG should be maintained available for RCS cooldown.
2 Isolate Flow From Ruptured SG(s):
- b. Check ruptured SG(s) PORV - b. MfiEN ruptured SG pressure CLOSED less than (P05) psig, IEEE verify SG PORV closed. IE RQI closed, IHEN place PORV controller in manual and close PORV. IE PORV can RQI be closed, JHEN close PORV block valve.
- c. b c. Manually close valve (s).
Verify valve (s) from lowdown isolation ruptured (A) SG(s) - CLOSED
- d. Close ruptured SG(s) main d. Perfom the following:
steamline isolation and bypass valves 1) Close remaining main steamline isolation and bypass valves.
- 2) Verify following valves closed.
[ Include additional AP600 details in E0Ps].
- 3) Use intact SG PORV for steam dump lE the ruptured SG can HQI be isolated from the intact SG,.IREN PRHR should be used for cooldown actions in this guideline.
- e. [ Include additional AP600 details in E0Ps]
('M N
Page 3 of 22
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 '
5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless needed for RCS cooldown.
3 Check Ruptured SG(s) Level:
- a. Narrow range level - a. Maintain feed flow to ruptured GREATER THAN (LO3)% SG until level greater than
[(LO4)% FOR ADVERSE (LO3)% [(LO4)% for adverse CONTAINMENT] containment]. Continue with Step 4. }uiEE ruptured SG level greater than (LO3)% [(LO4)% for adverse containment], JBf3 stop feed flow to ruptured SG(s).
- b. Stop feed flow to ruptured SG(s)
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Page 4 of 22 l
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Number Title Rev./Date r AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. O
{w) 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- If IRWST level decreases to less than (L11), RNS alignment to the containment sump should be veri fled.
- If adverse containment conditions exist, RCS makeup should be operated in manual to maintain pressurizer level.
4 Check RCS Makeup Status
- a. PRZR level - GREATER THAN a. Verify one makeup pump (LO5)%[(L23)% FOR ADVERSE running. E HQI, IllEN CONTAINMENT.I manually start one makeup pump. E level continues to decrease or cannot be '
restored, IHEN start second makeup pump,
- b. PRZR level - LESS THAN b. Verify all makeup pumps r (LO6)%[(L31)% FOR ADVERSE stopped. E HM, IllEH
(]y CONTAINMENT] manually stop all makeup pumps.
- c. Operate makeup and letdown as necessary to maintain PRZR level - BETWEEN (LO5)%
AND (LO6)%[BETWEEN (L23)%
AND (L31)% FOR ADVERSE !
CONTAINMENT]
5 Check If SGs Are Not Faulted. i
. NO SG PRESSURE DECREASING RCS cooldown IN AN UNCONTROLLED MANNER l e Steamlines. i e NO SG COMPLETELY DEPRESSURIZED . Feedlines.
E EDI, IllEN go to AE-2, AP600 FAULTED STEAM GENERATOR ISOLAT!0N, Step 1.
A]
G Page 5 of 22
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check If PRHR Should Be Isolated
' heck the following: a. Go to Step 7.
. SFW - IN OPERATION e Narrow range level in at least one SG - GREATER THAN (LO3)% [(LO4)% FOR ADVERSE CONTAINMENT]
- b. Close PRHR isolation valves CAUTION
- If the Deaerator Storage Tank level decreases to less than (LO8), the SFW pump suction should be transferred to the CST.
7 Check Intact SG Levels:
- a. Narrow ran e level - GREATER a. Maintain total feed flow THAN (LO3) [(LO4)% FOR greater than (F01) gpm until ADVERSE CONTAINMENT] narrow range level greater than (LO3)% [(LO4)% for adverse containment] in at least one SG.
- b. Control feed flow to b. IE narrow range level in any maintain narrow range level intact SG continues to between (LO3)% [(LO4 increase in an uncontrolled adverse containment])% and 50% for manner, IllEE return to Step 1.
8 Verify All ECS AC Busses - Try to restore offsite power to ENERGIZED BY OFFSITE POWER ECS ac busses. If offsite power can 1101 be restored, IllEN load the following equipment on ac busses:
[ Include additional AP600 details in E0Ps]
O Page 6 of 22
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 O 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l:
CAUTION Isolation of the ruptured SG from the intact SG to be used for RCS cooldown should be canpleted by closing the main steamline isolation and bypass valves for the ruptured SG or for the intact SG before continuing to Step 9, unless a ruptured SG is needed for RCS cooldown or the cooldown will be performed using PRHR.
9 Check If RCS Cooldown Rate Should <
Be Maximized
- a. Check the following: a. If neither condition satisfied, IliEN 90 to e Ruptured SG pressure - Step 10.
DECREASING
-0R-e RCS subcooling based on +
core exit TCs - LESS THAN '
O (S01) F [(S02) F FOR ADVERSE CONTAINMENT]
-OR-e CMT level - DECREASING l
t
- b. Maximize RCS cooldown rate 801 exceeding the Tech Spec l' limit i
i I
Page 7 of 22
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION RCS and ruptured SG(s) pressures must be maintained less than the ruptured SG(s) PORV setpoint.
NOTE
- Low steamline pressure SI and low T-cold SI should be blocked when PRZR pressure decreases to less than (P06) psig.
- After the low steamline pressure SI signal is I blocked, main steamline isolation will occur if the i high steam pressure rate setpoint is exceeded.
- Shutdown margin should be monitored during RCS cooldown.
l
- Since ruptured SG(s) may continue to depressurize to 1 less than the minimum RCS pressure necessary for
! continued RCP operation, cooldown to cold shutdown should not be delayed.
10 Initiate RCS Cooldown To Cold Shutdown:
- a. Maintain cooldown rate in j RCS cold legs - LESS THAN 100 F/HR I
l
I
- c. Use RNS if in service l d. Use PRHR as necessary 11 Turn All PRZR Heaters OFF I
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i Number Title Rev./Date l D AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. O I 5/31/95 l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l CAUTION
- Voiding may occur in the RCS during RCS depressurization. This will result in a rapidly increasing PRZR level. ,
- Cycling of the PRZR ADS valves should be minimized.
12 Depressurize RCS To Refill PRZR: l l'
- a. Use auxiliary spray a. Use one set of first stage PRZR ADS valves.
- b. PRZR level - GREATER THAN b. Continue with Step 13. When !
(LO7)% [(LO9 level greater than (LO7)% j CONTAINMENT])% FOR ADVERSE
[(LO9)% for adverse containment], IlifE do Step 12c.
t
- c. Stop RCS depressurization O
)
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O Page 9 of 22 i
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check If ADS Should Be Actuated:
- a. CMT level - LESS THAN (L01)% a. H RCS hot leg level indication reater than (L32) {(L33 % FOR ADVERSE CONTAINMENT , M go to Step 14. E 1101, M manually actuate ADS.
- b. Verify first stage ADS b. Manually open valves as isolation valves - OPEN necEssary.
- c. Check second stage ADS c. M (T01) seconds have valves - OPEN elapsed from first stage ADS signal, M verify second stage ADS valves open. E HQI, M manually open second stage ADS valves as necessary.
- d. Check third stage ADS d. M (102) seconds have valves - OPEN elapsed from second stage ADS signal, M verify third stage ADS valves open.
E fiQI, M manually open third stage ADS valves as necessary.
- e. Align RNS to inject into RCS
- f. Go to Step 15 O
Page 10 of 22 i
Number Title Rev./Date '
J r] AE-3 AP600 STEAM GENEllATOR TUBE RUPTURE Rev. 0 V
5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If CMT Injection should Be Isolated: >
- a. ADS - NOT ACTUATED a. Go to Step 15. !
- b. RCS subcooling based on core b. Go to Step 15.
exit TCs - GREATER THAN (S01)*F [(502 CONTAINMENT] ) F FOR ADVERSE ,
- c. PRZR level - GREATER THAN c. Go to step 15.
(LO5)% [(L23 CONTAINMENT])% FOR ADVERSE l
i
- d. Close CMT injection valves .
15 Verify CMT Injection Not ;
Required:
- a. RCS subcooling based on core a. Manually open CMT injection ,
exit TCs - GREATER THAN valves.
(S01) F [(502 CONTAINMENT] ) F FOR ADVERSE .
- b. PRZR level - GREATER THAN b. Manually open CMT injection (L05)% [(L2 )4 FOR ADVERSE valves.
CONTAINMENT -
l l
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Page 11 of 22
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 1
1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Initiate Evaluation Of Plant Status:
- a. Check auxiliary building a. Try to identify and isolate radiation - NORMAL leakage:
[ Include additional AP600 [ Include additional AP600 details in E0Ps] details in E0Ps]
- b. Obtain samples:
[ Include additional AP600 details in E0Ps]
- c. Evaluate plant equipment:
[ Include additional AP600 details in E0Ps]
- d. Start additional plant equipment to assist in recovery:
[ Include additional AP600 details in E0Ps]
17 Check RCP Cooling: Establish normal cooling to RCP(s). Refer to [ Include e RCP CCS flow - NORMAL additional AP600 details in i
~
e RCP temperature (s) - NORMAL O
Page 12 of 22
l Number Title 6 v./Date AE-3 Rev. 0 (q-f AP600 STEAM GENERATOR TUBE RUPTURE 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Inadvertent criticality may occur following any natural circulation or PRHR cooldown if the first RCP started is in the ruptured loop.
NOTE RCPs 1A and 1B should be run to provide normal PRZR spray.
18 Check If RCPs Should Be Started:
Go to Step 19.
- b. RCS subcooling based on core b. Go to Step 19.
exit TCs - GREATER THAN (S01) F [(S02 CONTAINMENT] ) F FOR ADVERSE
- c. PRZR level GREATER THAN c. Return to Step 12.
(LO7)% [(L0 )% FOR ADVERSE CONTAINMENT
- 1) Establish conditions for to verify natural starting RCPs: circulation. E natural circulation NOI verified,
[ Include additional AP600 M increase dumping steam details in E0Ps] from intact SG.
- 2) Start RCPs O
Page 13 of 22
7.
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- Voiding may occur in the RCS during RCS depressurization. This will result in a rapidly increasing PRZR level.
- Cycling of the PRZR ADS valves should be minimized.
1
- If CMT injection is necessary to maintain PRZR level, RNS pumps should be started to inject into l the RCS when RCS pressure is less then (P03) [(PO4)k FOR ADVERSE CONTAINMENT]
l 19 Depressurize RCS To Minimize RCS l
Subcooling:
I a. Use nonnal PRZR spray a. Use auxiliary spray. If auxiliary spray EDI available, IH G use one set '
of first stage PRZR ADS valves,
- b. Turn on PRZR heaters as necessary l
i l
Step continued on next page O
Page 14 of 22
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 -
- (, 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ,
- c. Depressurize RCS until EITHER of the following conditions satisfied:
-0R-e RCS pressure - EQUAL TO RUPTURED SG PRESSURE IF BACKFILL NOT DESIRED
-OR-e PRZR level - GREATER THAN (L13)% [(L14)% FOR ADVERSE CONTAINMENT]
() .
~ ~
RCS subcooling based on core exit TCs - LESS THAN !
(S03) F [(SO4) F FOR '
ADVERSE CONTAINMENT]
20 Check If Diesel Generators Should Be Stopped:
- a. Verify ECS ac busses - a. Try to restore offsite power ENERGIZED BY OFFSITE POWER to ECS ac busses. If offsite power can HQI be restored, ;
IHfH load the following equipment on ac busses: '
[ Include additional AP600 details in E0Ps]
- b. Stop any unloaded diesel generator and place in standby 1 O
Page 15 of 22 1
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 Check If Passive Containment Cooling Should Be Stopped:
- a. Passive containment a. Go to Step 22.
cooling - OPERATING
- b. Containment pressure - LESS b. Continue with Step 22. BBEN THAN (P10) PSIG containment pressure less than (P10) psig IllEN do Steps 21c and d.
- c. Reset passive containment cooling signal
- d. Stop passive containment cooling and place in standby:
[ Include additional AP600 details in E0Ps]
22 Minimize Secondary System Contamination:
[ Include additional AP600 details in E0Ps]
23 Turn On PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured SG(s) Pressure 24 Verify Adequate Shutdown Margin:
- a. Sample ruptured SG(s) ,
- b. Sample RCS
- c. Shutdown margin - ADEQUATE c. Borate as necessary.
l Ol Page 16 of 22
Number Title Rev./Date p AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. O Q 5/.11/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 Check If SI Accumulators should Be Isolated:
- a. RCS subcooling based on core a. If both RCS hot leg exit TCs - GREATER THAN temperatures less than (501) F [(S02 (T05) F,1118 go to CONTAINMENT] ) F FOR ADVERSE Step 25c. lE EQI,1118 go to Step 26.
- b. PRZR level - GREATER THAN b. Return to Step 12.
(LO7)% [(L0 )% FOR ADVERSE CONTAINMENT
- c. Check power to isolation c. Restore power to isolation valves - AVAILABLE valves.
- d. Close all SI accumulator d. Vent any unisolated isolation valves accumulators.
26 Check If Source Range Detectors Should Be Energized:
- a. Check intermediate range a. Continue with Step 27. lul8 flux - LESS THAN (V02) flux less than (V02),1118 do Steps 26b and c.
- b. Verify source range b. Manually energize source detectors - ENERGIZED range detectors.
27 Shut Down Unnecessary Plant Equipment:
[ Include additional AP600 details in E0Ps]
28 Check If RCP(s) Must Be Stopped:
THAN (P07)PSIG pressure - GREATER O
Page 17 of 22
Naber Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- Steam should not be released from a ruptured SG f f water may exist in its steamline.
- Ruptured SG pressure may decrease rapidly when steam is released.
- Voiding may occur in the RCS during RCS depressurization. This may result in a rapidly increasing PRZR level.
29 Check If Ruptured SG Pressure Should Be Reduced:
- a. Ruptured SG pressure - a. Go to Step 30.
GREATER THAN RCS PRESSURE
- b. Perform the following:
- Decrease RCS makeup and increase letdown to initiate backfill
-OR-
. Initiate blowdown from i rupturedSG(s)
-OR-e Dump)
SG(s steam from ruptured
- c. Check RCS - LESS c. Go to Step 30. l THAN (P08) pressure' PSIG [(P09) PSIG l FOR ADVERSE CONTAINMENT]
l
- d. Stop ruptured SG !
depressurization O
Page 18 of 22
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. O i h(% 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED <
L CAUTION
- Feed flow should not be established to any ruptured SG which is also faulted unless needed for RCS cooldown.
30 Check Ruptured SG(s) Narrow Range Refill ruptured SG to (Lif)%
Level - GREATER THAN (LO3)% [(L16)% for adverse containment]
[(LO4)% FOR ADVERSE CONTAINMENT] using feed flow. If either of the following conditions occurs. IllEN stop feed flow to ruptured SG:
e Ruptured SG pressure decreases in an uncontrolled manner.
-OR-e Ruptured SG pressure increases to (P05) psig.
31 Check If RNS Can Be Placed In Service:
- a. Check the following: a. Return to Step 10.
. RCS temperatures - LESS THAN (T06) F [(T07) F FOR ADVERSE CONTAINMENT]
e RCS pressure - LESS THAN (P08) PSIG [(P09) PSIG FORADVERSECONTAINMENT]
- b. Determine if RNS should be placed in service in accordance with [ Include additional AP600 details in E0Ps]
32 Check RCS Temperatures - LESS Return to Step 10.
THAN 200 F 1
33 Evaluate Long Term Plant Status. I And Maintain Cold Shutdown Conditions )
- END -
Page 19 of 22 l
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Number Title Rev./Date I AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. O S/31/95 ATTACHMENT A The following conditions support or indicate natural circulation flow:
RCS subcooling based on core exit TCs - GREATER THAN (501) F [(S02) F FOR ADVERSE CONTAINMENT]
SG pressures - STABLE OR DECREASING RCS hot leg temperatures - STABLE OR DECREASING Core exit TCs - STABLE OR DECREASING RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE O
O Page 20 of 22
Number Title Rev./Date O AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. 0 5/31/95 FOLD 0VT FOR AE-3 GUIDELINE
- 1. CMT INJECTION CRITERIA Open CMT injection valves if 111BEB condition listed below occurs:
e RCS subcooling based on core exit TCs - LESS THAN (S01) F [(S02) F FOR ADVERSE CONTAINMENT]
e PRZR level - CANNOT BE MAINTAINED GREATER THAN (LO5)% [(L23)% FOR ADVERSE CONTAINMENT] !
1
- 2. RED PATH
SUMMARY
l
- a. SUBCRITICALITY - Nuclear power greater than 5%.
- b. CORE COOLING - Core exit TCs greater than 1200 F )
- c. HEAT SINK - Narrow range level in all SGs less than (LO3)%[(LO4)% FOR ADVERSE CONTAINMENT] MD total feedwater flow less than (F01) gpm MD PRHR not in service e d. INTEGRITY - Cold leg temperature decrease greater than 100 F in last 60 minutes MQ RCS cold leg temperature less than (T14) F
- e. CONTAINMENT - Cc,ntainment pressure greater than (P21) PSIG
- 3. SECONDARY INTEGRITY CRITERIA Go to AE-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, if any SG pressure is decreasing in an uncontrolled manner or has completely depressurized, and has not been isolated.
- 4. MULTIPLE TUBE RUPTURE CRITERIA Return to AE-3, STEAM GENERATOR TUBE RUPTURE, Step 1, if any intact SG level increases in an uncontrolled manner or any intact SG has abnormal radiation.
- 5. SFW SUPPLY SWITCHOVER CRITERION Switch to CST if deaerator storage tank level decreases to less than (LO8).
O Page 21 of 22
Number Title Rev./Date AE-3 AP600 STEAM GENERATOR TUBE RUPTURE Rev. O 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
O O
Page 22 of 22
0 1
l l I AECA-1.1 l l
LOCA Outside Containment O
O
,f%, Number Title Rev./Date i AECA-1.1 AP600 LOCA OUTSIDE CONTAINMENT Rev. 0 ,
5/31/95 j l
l A. PURPOSE This guideline provides actions to identify and isolate a LOCA outside containment.
B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from:
')
. AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 31, on abnormal radiation in the auxiliary building due to a loss of RCS inventory outside containment.
- 2) AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 12, if it is determined that the cause of abnormal radiation is due to a loss of RCS inventory outside containment.
O v
O Page 1 of 3 ,
Number Title Rev./Date AECA-1.1 AP600 LOCA OUTSIDE CONTAINMENT Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Try To Identify And Isolate Break:
- a. Sequentially operate the i following valves and monitor 1
for an RCS pressure increase: ,
! 1) RNS suction and return l lines connected to RCS.
- 2) [ Include additional AP600 details in E0Ps]
2 Check If Break Is Isotated:
- a. RCS pressure - INCREASING a. Dispatch personal to mix boric acid solution for makeup pumps.
- b. Go to AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
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- END -
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ a
I e humber Title Rev./Date AECA-1.1 Rev. 0 AP600 LOCA OUTSIDE CONTAINMENT 5/31/95 l
)
1 i
FOOTNOTES l
NONE USED IN THIS GUIDELINE ,
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Page 3 Of 3
O I
AF-0.1 Suberiticality O
e O
Number:
Title:
Rev. Issue /Date:
O' AF-0.1 SUBCRITICALITY Rev.0 5/31/95 GO TO AFR-S.1 NO R-S1 POWER RANGE
""~
g LESS THAN 5%
YES
-S 2 INTERMEDIATE NO RANGE SUR -
RANGE SUR ZERO OR MORE NEGATIVE YES NEGATIVE THAN -0.2 DPM YES O I CSF SAT O
SOURCE l
RANGE ENERGlZED YES i
~8 2 9
SOURCE NO RANGE SUR ZERO OR NEGATIVE YES AT O
_ J
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l l AF-0.2 I
Core Cooling O I i
1 l
O J
Number:
Title:
Rev. Issue /Date: ~
AF-0.2 CORE COOLING Rev.O 5/31/95 FR-C.1 CORE EXIT TCs LESS -
THAN 1200*F CO TO AFR-C.2 CORE EXIT O TCs LESS TH AN (T13)*F YES W
. . . q =.
SUBCOOLING NO BASED ON CORE EXIT TCs GREATER THAN YES (S01)*F [S02)*F SIT l
O .
i
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O !
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AF-0.3 l Heat Sink O
l O
J l
(] Number:
Title:
Rev. Issue /Date:
O A F-0.3 HEAT SINK Rev.0 l 5/31/95 1 AFR-H 1
! PRHR IN SERVICE -
TOTAL O
FEEDWATER YES
- FLOW TO SGs -
GREATER THAN YES I (F01) GPM e e o e e e @3:3 PRESSURE IN NO NARROW RANGE BOTH SGs NO ~
LEVEL IN AT LESS THAN
OOO R-H.3 8
NARROW NO RANGE LEVEL IN BOTH SGs LESS THAN YES (L12)%
e o e e@J:2 O
PRESSURE IN BOTH SGs -
LESS THAN (P19) PSIG YES R-H$
NARROW NO RANGE LEVEL IN BOTH SGs GREATER THAN (Lo3)% [(LO4)%) YES CSF O '
l O
AF-0.4 Integrity ,
1 i
O O
I
/ Number:
Title:
Rev. Issue /Date:
A F-0.4 INTEGRITY Rev.O 5/31/95 E
a, 5
O T1 T2 ,
COLD LEG TEMPERATURE : l AFR-P1 ALL RCS PRESSURE M G To
- COLD LEG AFR-P.1 TEMPERATURES -
POINTS TO RIGHT OF YES UMIT A ALL RCS Go To NO gg COLD LEG FR-P.2 TEMPERATURES - G GREATER THAN A (T14)*F YES O p ALL RCS COLD LEG TEMPERATURES -
NO GREATER THAN DECREASE IN NO (T15)*F YES ALL RCS COLD
+ LEGS LESS -
THAN 100*F IN F THE LAST 60 YES MINUTES ,
Go To AFR-P.1 i ALL RCS NO COLD LEG TEMPERATURES GREATER THAN 1 RCS PRESSURE NO (T14)*F YES LESS THAN '
COLD - y OVERPRESSURE 9 Go To UMIT YES gg j FR-P.2 ;
RCS NO TEMPERATURE _ i GREATER THAN CSF i 716)*F YES I SAT O\ I CSF SAT l
O l
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AF-0.5 Containment O
O
Number:
Title:
Rev. Issue /Date:
O' A F-0.5 CONTAINMENT Rev.0 5/31/95 GO TO AFR-Z.1 CONTAINMENT NO I l AFn-z1
. PRESSURE _
g LESS THAN (P21) PSIG YES I
CONTAINMENT PRESSURE NO LESS THAN ~
(P01) PSIG m Go To YES O
CONTAINMENT O LEVEL LESS THAN (L34)
YES 0=
CONTAINMENT NO RADIATION LESS THAN (R02) YES
- Q=
CONTAINMENT NO PRESSURE GREATER THAN (P22)PSIG YES 1
l CSF f '
lO I
SAT 1
l 4
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1 AF-0.6 Inventory O
O l
Number:
Title:
Rev. Issue /Date:
{ Rev.O A F-0.6 INVENTORY 5/31/9 5 9 9 9 99 e '
AFR-1.3 PRESSURIZER LEVEL NO BEHAVIOR _
INDICATES Rx UPPER HEAD YES FULL PRESSURIZER
- LEVEL LESS -
THAN (L24)%
o . . . . . . . .@=
l PRESSURIZER NO LEVEL 1 GREATER THAN )
(LO5)% YES l
l e o e e @ f,.', !
PRESSURIZER LEVEL NO BEHAVIOR -
INDICATES Rx UPPER HEAD YES FULL 1
l
O I
l AFR-S.1 l Response to Nuclear Power Generation /ATWS O
l
\
O
Number Title Rev./Date 0
, AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. O 5/31/95 l
_ A. PURPOSE This guideline provides actions to add negative reactivity to a core which is observed to be critical when expected to be shut down.
I B. SYMPTOMS OR LNti.if CONDITIONS i
This guideline is entered from:
- 1) AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 1, when reactor trip is not verified and manual reactor trip is not effective.
- 2) AF-0.1, SUBCRITICALITY Critical Safety Function Status Tree on either a RED or ORANGE condition.
1
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Page 1 of 7
l l
l Number Title Rev./Date I AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. O ;
5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Steps 1 and 2 are IMMEDIATE ACTION steps.
1 Verify Reactor Trip: Manually trip reactor. IE reactor will not trip, IHEN manually
. All control rods - INSERTED insert control rods. ,
l e Reactor trip and bypass i breakers - OPEN e Neutron flux - DECREASING 2 Verify Turbine Trip: Manually trip turbine. If turbine will EQI trip, IHEN e All turbine stop valves - manually run back turbine. IE CLOSED turbine can HQI be run back, IHEN close main steamline isolation and bypass valves.
3 Check If PRHR Should Be Actuated
- a. Check the following: a. If neither condition satisfied, IEEH go to e SG wide range level - LESS Step 4.
THAN (L35)%
- OR -
- Both of the following e SG narrow range level -
LESS THEN (L36)%
- AND-e SFW flow - LESS THAN (F05) gpm
- OR - )
e RCS hot leg temperature l
- GREATER THAN (T17) F
manually open valves as i necessary.
4 Page 2 of 7 l I
l Number Title Rev./Date AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. 0 O' 5/31/95 STEP- ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check SFW Pumps'- RUNNING Manually start pumps.
'5 Initiate Boration of RCS:
- a. Open CNT injection valves
- b. Trip all RCPs I I
- d. Control RCS makeup flow and letdown as necessary to borate the RCS CAUTION If an SI signal exists or occurs, the insnediate actions of AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION should be perfonned while continuing with this guideline.
! 6 Check If The Following Trips Have Occurred:
- a. Reactor trip a. Dispatch operator to locally j trip reactor:
[ Include additional AP600 details in E0Ps]
- b. Turbine trip b. Dispatch operator to locally l trip turbine:
l
[ Include additional AP600 details in E0Ps]
O Page 3 of 7
. . . . .. - __ _ _ __ __u
Number Title Rev./Date AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If the Deaerator Storage Tank level decreases to less than (LOB), the SFW pump suction should be transferred to the CST.
7 Check SG Level:
- a. Narrow range level in at a. Perform the following:
least one SG - GREATER THAN (LO3)% [(LO4 1) Verify total feed flow CONTAINMENT])% FOR ADVERSE greater than (F03) gpm.
H HQI, I118 manually start SFW pumps and align valves as necessary.
- 2) Maintain total feed flow greater than (F03) gpm until narrow range level greater than (LO3)%
[(LO4)% for adverse containment) in at least one SG.
- b. Coni.rol feed flow to maintain narrow ran e level between (LO3)% [(L0 )% for ad',erse containment and SM.
8 Verify All Dilution Paths - Manually isolate dilution paths.
ISOLATED
[ Include additional AP600 details in E0Ps]
O Page 4 of 7
Ntaber Title Rev./Date
/' AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check For Reactivity Insertion Stop any controlled cooldown and From Uncontrolled RCS Cooldown: go to Step 14.
- RCS temperatures - DECREASING i IN AN UNCONTROLLED MANNER
-OR- i e Any SG pressure - DECREASING I IN AN UNCONTROLLED MANNER 10 Check Main Steamline Isolation Manually close valves.
And Bypass Valves - CLOSED i
11 Identify Faulted SG(s):
- a. Check a. Go to Step 14.
(% SG(s) pressures in all
. ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
-0R-e ANY SG COMPLETELY DEPRESSURIZED CAUTION
- If both SGs are faulted and PRHR is not available, at least (F04) gpm feed flow should be maintained to :
the SG that will be used for RCS cooldown.
12 Isolate Faulted SG(s): Manually close valves or block valves. If valves can ROI be e Isolate main feedline closed,1112 dispatch operator to locally close valves or block e Isolate SFW flow valves.
. Verify SG PORVs - CLOSED Page ; of 7
I Number iitie Rev./Date
,/ AFR-5.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. O ;
5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check SFW Pumps - RUNNING Manually start pumps. i 5 Initiate Boration of RCS:
- a. Open CMT injection valves
- b. Trip all RCPs
- d. Control RCS makeup flow and letdown as necessary to borate the RCS CAUTION if an SI signal exists or occurs, the imediate actions of AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION should be performed while continuing with this guideline.
6 Check If The Following Trips Have Occurred:
- a. Reactor trip a. Dispatch operator to locally trip reactor:
[ Include additional AP600 i details in E0Ps] l
)
- b. Turbine trip b. Dispatch operator to locally trip turbine:
[ Include additional AP600 details in E0Ps]
O ~
Page 3 of 7
- _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ a
Number Title Rev./Date AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If the Deaerator Storage Tank level decreases to less than (LO8), the SFW pump suction should be transferred to the CST.
7 Check SG Level:
- a. Narrow range level in at a. Perform the following:
least one SG - GREATER THAN (LO3)% [(LO4 1) Verify total feed flow CONTAINMENT])% FOR ADVERSE greater than (F03) gpm.
IE HDI, IllEN manually start SFW pumps and align valves as necessary.
- 2) Maintain total feed flow greater than (F03) gpm until narrow range level greater than (LO3)%
[(LO4)% for adverse containment] in at least one SG.
- b. Control feed flow to maintain narrow ran e level between (LO3)% [(LO )% for adverse containment and 50%.
8 Verify All Dilution Paths - Manually isolate dilution paths.
ISOLATED
[ Include additional AP600 details inE0Ps]
O Page 4 of 7
i Number Title Rev./Date AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. 0 '
/ 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Check For Reactivity Insertion Stop any controlled cooldown and l From Uncontrolled RCS Cooldown: go to Step 14.
e RCS temperatures - DECREASING IN AN UNCONTROLLED MANNER
-0R-e Any SG pressure - DECREASING IN AN UNCONTROLLED MANNER 10 Check Main Steamline Isolation Manually close valves.
And Bypass Valves - CLOSED 11 Identify Faulted SG(s):
- a. Check a. Go to Step 14.
SG(s) pressures in all e ANY SG PRESSURZ DECREASING IN AN UNCONTROLLED MANNER
-0R-e ANY SG COMPLETELY DEPRESSURIZED CAUTION
- If both SGs are faulted and PRHR is not available, at least (F04) gpm feed flow should be maintained to the SG that will be used for RCS cooldown.
12 Isolate Faulted SG(s): Manually close valves or block valves. IE valves can HDI be
. Isolate main feedline closed, IliEN dispatch operator to locally close valves or block e Isolate SFW flow valves.
O i Page S of 7 1
Number Title Rev./Date AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Check Core Exit TCs - LESS THAN IF core exit TCs greater than 1200 F 1200 F and increasing, THEN go to SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE, Step 1.
14 Yerify Reactor Subcritical: Continue to borate. If boration RQI available,1118 allow RCS to
- a. Power range channels - LESS heat up. Perform actions of other THAN 5% Function Restoration Guidelines in effect which do not cool down
- b. Intermediate range channels - or otherwise add positive NEGATIVE STARTUP RATE reactivity to the core. Return to Step 5.
CAUTION Boration should continue to obtain adequate shutdown margin during subsequent actions.
15 Return to Guideline And Step In Effect
- END -
O Page 6 of 7
Number Title Rey,/Date O AFR-S.1 AP600 RESPONSE TO NUCLEAR POWER GENERATION - ATWS Rev. 0 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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Page 7 of 7
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l AFR-S.2 Response to Loss of Core Shutdown O
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Number Title Rev./Date AFR-S.2 AP600 RESPONSE TO LOSS OF CORE SHUTDOWN Rev. 0 l 5/31/95
)
l A. PURPOSE I
{ This guideline provides actions to restore the core to an adequate shutdown condition.
B. SYMPT 0MS OR ENTRY CONDITIONS This guideline is entered from AF-0.1, SUBCRITICALITY Critical Safety Function Status Tree, on either YELLOW condition.
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Page 1 of 3
Number Title Rev./Date AFR-S.2 AP600 RESPONSE TO LOSS OF CORE SHUTDOWN Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Check Intermediate Range Flux:
- a. Flux - LESS THAN (V02) a. IE flux decreasing, IEEti continue to monitor flux.
WHEti flux less than (V02),
JBEti do Steps Ib and c.
E flux fiQI decreasing, IBfti check intermediate range channels for undercompensation. If undercompensated, IEEli manually energize source range detectors. If fiQI undercompensated, IBfti borate RCS until flux less than (V02).
- b. Verify source range b. Manually energize source detectors - ENERGIZED range detectors.
O 2 Check Source Range Channels - Borate until source range startup ZERO OR NEGATIVE STARTUP RATE rate is negative or zero.
CAUTION Baration should continue to obtain adequate shutdown margin during subsequent actions.
3 Return To Guideline And Step In Effect ;
l
- END -
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F Number Title '
's AFR-S.2 AP600 RESPONSE TO LOSS OF CORE SHUTDOWN ReE'O 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted paraneeters used in this guideline.
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Page 3 of 3
O .
AFR-C.1 Response to Inadequate Core Cooling i
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A" Number Ti11e Rev./Date
',. Iy '. AFR-C.I' AP600 RESPONSE T0 INADEQUATE CORE COOLING Rev.'O 5/31/95' A. PURPOSE This guideline provides actions to restore core cooling. :
B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AF-0.2, CORE COOLING Critical Safety Function i Status Tree, on a RED condition.
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. Page 1 of 10 '
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N aber Title Rev./Date AFR-C.1 AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Verify CMT Actuated: Actuate CMT initiation. If valves will ROI open, IHW manually open
. CMT injection valves - OPEN valves as necessary.
2 Verify All RCPs Tripped Manually trip RCPs.
3 Start All RCS Makeup Pumps 4 Check RCP Support Conditions - Try to establish support AVAILABLE conditions.
[ Include additional AP600 details in E0Ps]
5 Check SI Accumulator Isolation Valve Status:
- a. Power to isolation valves - a. Restore power to isolation AVAILABLE valves.
- b. Isolation valves - OPEN b. Open isolation valves unless closed after accumulator discharge.
6 Check Core Exit TCs:
- a. Core Exit TCs - LESS THAN a. Go to Step 7.
1200 F
- b. Return to guideline and step in effect I
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l Number Title Rev./Date I O AFR-C.1 AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. O ;
5/31/95 l I
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If IRWST level decreases to less than ,'L11), RNS alignment to the containment sump should be vertfled. ,
7 Depressurize RCS To Inject IRWST: [
- a. Actuate ADS i
- b. Verify first stage ADS b. Manually open valves as isolation valves - OPEN necessary. !
- c. Check second stage ADS c. M (T01) seconds have i valves - OPEN elapsed from first stage ADS l signal, M verify second ;
stage ADS valves open. E fiQI, M manually open r second stage ADS valves as necessary, i
- d. Check third stage ADS d. M (T02) seconds have valves - OPEN elapsed from second stage t ADS signal, M verify :
third stage ADS valves open. t E fiQI, M manually open i third stage ADS valves as l necessary.
- e. Align RNS to inject into RCS e. 1E RNS injection into RCS can fiQI be established, M actuate fourth stage ADS.
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Number Tit'- Rev./Date AFR-C.1 AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE This guideline should be continued while obtaining hydrogen sample in Step 8.
8 Check Containment Hydrogen Concentration:
- a. Obtain a hydrogen concentration measurement:
[ Include additional AP600 details in E0Ps]
- b. Hydrogen concentration - b. Determine if additional LESS THAN 0.5% IN DRY AIR recovery actions are necessary. Go to Step 9.
- a. Core Exit TCs - LESS THAN a. If decreasing, ItiEN return 1200 F to Step 1. If N91, IllEN go to Step 10.
- b. Return to guideline and step in effect i
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Number Title Rev./Date
,] AFR-C.1 AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. 0
/ 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- If the Deaerator Storage Tank level decreases to less than (LJ8), the SFW pump suctton should be transferred to the CST.
- A faulted or ruptured SG should not be used in subsequent steps unless PRHR is not available and no intact SG is available.
10 Check Intact SG Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow THAN (LO3)% [(LO4)% FOR greater than (F01) gpm until ADVERSE CONTAINMENT] narrow range level greater than (LO3)% [(LO4)% for adverse containment] in at least one SG. If total feed flow greater than (F01) gpm can HDI be established, JH G continue attempts to o
establish a heat sink in at Cy least one SG and go to Step
- 17. OBSERVE NOTE PRIOR TO STEP 17.
- b. Control feed flow to maintain narrow range level between (LO3)% [(L0 )% for adverse containment and 50%
Page 5 of 10
e Number Title Rev./Date !
AFR-C.1 AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. O i 5/31/95 l
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE
- Partial uncovery of SG tubes is acceptable in the following steps.
- After the low steamline pressure Si signal is blocked, main steamline isolation will occur if the high steam pressure rate setpoint is exceeded.
11 Depressurize All Intact SGs To (P15) PSIG:
- b. Check SG pressures - LESS b. E SG pressure decreasing, THAN (P15) PSIG IliEli return to Step 10. E 1101, IllEtj verify PRHR actuated and go to Step 17.
OBSERVE NOTE PRIOR TO STEP 17.
- c. Check RCS hot leg c. E RCS hot leg temperatures temperatures - AT LEAST TWO decreasing, IliEti return to LESS THAN (T05)"F Step 10. E fiDI, IllEtj verify PRHR actuated AtiD go to Step
- 17. OBSERVE NOTE PRIOR TO STEP 17.
- d. Stop SG depressurization 12 Check If SI Accumulators Should Be Isolated:
- a. At least two RCS hot leg a. Go to Step 17. OBSERVE NOTE temperatures - LESS THAN PRIOR TO STEP 17.
(T05) F
- b. Close all SI accumulator b. Vent any unisolated isolation valves accumulator.
O Page 6 of 10
Number Title Rev./Date AFR-C.1 O AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 Depressurize All Intact SGs To Atmospheric Pressure: $
f a. Dump steam to condenser at a. Dump steam at maximum rate i l maximum rate using SG PORVs. IE steam can NOT be dumped, IllEN verify PRHR actuated AND go to Step
- 17. OBSERVE NOTE PRIOR TO STEP 17.
14 Verify RNS Flow Continue efforts to establish RNS flow. If core exit TCs less than 1200 F, IliEN return to Step 13.
If fiDI. IllEN 90 to Step 17.
OBSERVE NOTE PRIOR TO STEP 17.
15 Check Core Cooling:
- a. Core exit TCs - LESS THAN a. Go to Step 17. OBSERVE NOTE 1200 F PRIOR TO STEP 17.
- b. At least two RCS hot leg b. Return to Step 13.
temgeratures - LESS THAN l
350 F l
l c. RCS hot leg level indication c. Return to Step 13.
l - GREATER THAN (L32)%[( 33)%
FOR ADVERSE CONTAINMENT l 16 Go To AE-1, AP600 LOSS OF R:,CTOR OR SECONDARY COOLANT, Step 13 O
Page 7 of 10
Number Title Rev./Date AFR-C.1 AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Nonmal conditions are desired but not required for starting the RCPs.
17 Check If RCPs Should Be Started:
- a. Core exit TCs - GREATER THAN a. Go to Step 18.
1200 F
- b. Check if an idle RCS cooling b. Perform the following:
loop is available:
- 1. Open all other vent paths e Narrow range SG level - to containment.
GREATER THAN (LO3)%
[(LO4)% FOR ADVERSE 2. Go to Step 18.
CONTAINMENT]
e RCP in associated loop -
AVAILABLE AND NOT OPERATING
- d. Return to Step 17a.
18 Check Core Exit TCs - LESS THAN If core exit temperatures 1200 F decreasing, IBEH return to Step 17. If core exit temperatures increasitig and RCPs running in all available RCS cooling loops, IBEN go to SACRG-1, SEVERE ACCIDENT CONTROL CONTROL ROOM GUIDELINE INITIAL RESPONSE, Step 1.
19 Try to Depressurize The RCS By Try to locally depressurize SGs Cooling Down With PRHR to atmospheric pressure.
1 Page 8 of 10 1
Number Title Rev./Date
(~g AFR-C.1 AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. 0
() 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 20 Check If SI Accumulators Should Be Isolated:
- a. RNS flow indicators - AT a. Return to Step 19.
LEAST INTERMITTENT FLOW
- b. Close all SI accumulator b. Vent any unisolated isolation valves accumulator.
21 Check If RCPs should Be Stopped:
- a. At least two RCS hot leg a. Go to Step 23.
temperatures - LESS THAN 350 F
- b. Stop all RCPs 22 Verify RNS Flow Perform the following:
(v]
- a. Continue efforts to establish RNS flow.
- b. Actuate fourth stage ADS.
- c. Verify IRWST injection isolation valves open. If M I, 1118 manually open valves.
23 Check Core Cooling: Return to Step 17.
GREATER THAN (L32)% :(L33)% FOR ADVERSE CONTAINMENT' e At least two RCS hot leg I temperatures - LESS THAN 350 F i 24 Go To AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 13
-^T
- END -
Page 9 of 10
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Humber Title Rev./Date AFR-C.1 AP600 RESPONSE TO INADEQUATE CORE COOLING Rev. 0 5/31/95 FOOTNOTES I
Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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O AFR-C.2 Response to Degraded Core Cooling O
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Number 11tle Rev./Date
.O AFR-C.2 AP600 RESPONSE TO DEGRADED CORE COOLING Rev. 0 5/31/95 ,
A. PURPOSE This guideline provides actions to restore adequate core cooling.
i B. SYMPTOMS OR ENTRY CONDITIONS (
This guideline is entered from AF-0.2, CORE COOLING Critical Safety Function i Status Tree, on an ORANGE condition.
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1 Number Title Rev./Date AFR-C.2 AP600 RESPONSE TO DEGRADED CORE COOLING Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Verify CMT Actuated: Actuate CMT initiation. If valves will HQI open IBEN manually open
. CMT injection valves - OPEN valves as necessary.
CAUTION Symptoms for AFR-C.1, AP600 RESPONSE TO INADEQUATE CORE COOLING should be closely monitored during subsequent steps.
2 Verify All RCPs Tripped Manually trip RCPs.
CAUTION If adverse containment conditions exist, RCS makeup should be operated in manual to maintain pressurizer level.
3 Check RCS Makeur 'tatus:
- a. PRZR 1evel - GREATER THAN a. Start all makeup pumps.
(L05)%[(L23 % FOR ADVERSE CONTAINMENT
- b. PRZR level - LESS THAN b. Verify all makeup pumps (LO6)%[(L31)% FOR ADVERSE stopped. If NDI, IHEN CONTAINMENT] manually stop all makeup pumps.
4 Check Core Cooling:
- a. Core Exit TCs - LESS THAN a. IE decreasing IBIN return to (T13) F Step 1. If HQI, IBIN go to Step 5.
- b. Return to guideline and step in effect.
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Number Title Rev./Date AFR-C.2 AP600 RESPONSE TO DEGRADED CORE COOLING Rev. 0
/"]
-(/ 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check SI Accumulator Isolation '
Yalve Status:
- a. Power to isolation valves - a. Restore power to isolation AVAILABLE valves,
- b. Isolation valves - OPEN b. Open isolation valves unless. ;
closed after accumulator discharge.
CAUTION If IRWST level decreases to less than (L11), RNS alignment to the containment sump should be vertfled.
6 Depressurize RCS To Inject IRWST:
- a. Actuate ADS
- b. Verify first stage ADS b. Manually open valves as isolation valves - OPEN necessary.
- c. Check second stage ADS c. M (T01) seconds have valves - OPEN elapsed from first stage ADS signal, M verify second stage ADS valves open. E
- HQI, E manually open ,
second stage ADS valves as necessary.
- d. Check third stage ADS d. M (T02) seconds have valves - OPEN elapsed from second stage ADS signal, M verify third stage ADS valves open.
H N01, M manually open third stage ADS valves as necessary. '
- e. Align RNS to inject into RCS e. E RNS injection into RCS can H01 be established, M actuate fourth stage ADS. l O
Page 3 of 7
Number Title Rev./Date AFR-C.2 AP600 RESPONSE TO DEGRADED CORE COOLING Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check Core Cooling:
- a. Core Exit TCs - LESS THAN a. E decreasing M return to (T13) F Step 1. E E01, M go to Step 8.
- b. RCS hot leg level indication b. E increasing, M return
- GREATER THAN (L32)%[(L33)% to Step 1. H E01, M 90 FOR ADVERSE CONTAINMENT] to Step 8.
- c. Return to guideline and step in effect.
CAUTION
- If the Deaerator Storage Tank level decreases to less than (LO8), the SFW pump suction should be transferred to the CST.
- A faulted or ruptured SG should not be used in subsequent steps unless PRHR is not available and no intact SG is available.
8 Check Intact SG Levels:
- a. Narrow range level - GREATER a. Maintain total feed flow THAN (LO3)% [(LO4)% FOR greater than (F01) gpm until ADVERSE CONTAINMENT] narrow range level greater than (LO3)% [(LO4)% for adverse containment] in at least one SG.
- b. Control feed flow to maintain narrow range level between (LO3)% [(LO4)% for adverse containment] and 50%
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l Number ittle Rev./Date AFR-C.2 AP600 RESPONSE TO DEGRADED CORE COOLING Rev. 0 i s,
s 5/31/95 i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION The following step will cause accumulator injection which may cause a red path condition in AF-0.4, INTEGRITY Status Tree. This guideline should be -
completed before transition to AFR-P.1, AP600 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK.
NOTE After the low steamline pressure SI signal is blocked, main steamline isolation will occur if the high steam pressure rate setpoint is exceeded.
9 Depressurize All Intact SGs To (P15) PSIG:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100 F/HR
- b. Dump steam to condenser b. Manually or locally dump steam from SGs:
O
(,) e Use PORV. l
- OR -
e [ Include additional AP600 details in E0Ps] . l 1
- c. Check SG pressures - LESS c. Return to Step 8.
THAN (PIS) PSIG j
- d. Stop SG depressurization i
10 Check RNS Pumps - RUNNING Start pumps as necessary, i 11 Check If SI Accumulators should ;
Be Isolated.
i
- a. At least two RCS hot leg a. Go to Step 12.
temperatures - LESS THAN.
(TOS) F
- b. Close all SI accumulator b. Vent any unisolated isolation valves accumulator.
O Page 5 of 7
Number Title Rev./Date AFR-C.2 AP600 RESPONSE TO DEGRADED CORE COOLING Rev. O l 5/31/95 I
i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Depressurize All Intact SGs To Atmospheric Pressure:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100 F/HR
- b. Dump steam to condenser b. Manually or locally dump steam from SGs:
e Use PORV.
- OR -
e [ Include additional AP600 details in E0Ps].
13 Verify RNS Flow Perform the following:
- a. Continue efforts to establish RNS flow.
- b. Actuate fourth stage ADS.
- c. Verify IRWST injection isolation valves open. If MI, IllEU manually open valves.
14 Check Core Cooling: Return to Step 12.
. Core Exit TCs - LESS THAN (T13) F e RCS hot leg level indication -
GREATER THAN (L32)%,:(L33)% FOR ADVERSE CONTAINMENT.
. At least two RCS hot leg temperatures - LESS THAN 350 F 15 Go to AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 13
- END -
Page 6 of 7 l
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I Number Title
- AFR-C.2 AP600 RESPONSE TO DEGRADED CORE COOLING Re 0
's) -- l 5/31/95
\
FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted .
parameters used in this guideline.
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O AFR-C.3 Response to Saturated Core Cooling O
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a Number Title Rev./Date 4
[T AFR-C.3 AP600 RESPONSE TO SATURATED CORE COOLING Rev. O i 5/31/95 A. PURPOSE ,
i This guideline provides actions to restore subcooled core cooling. i i
4
- 8. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AF-0.2, CORE COOLING Critical Safety Function '
Status Tree, on a YELLOW condition. '
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Number Title Rev./Date AFR-C.3 AP600 RESPONSE TO SATURATED CORE COOLING Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Check RNS System - HAS NOT BEEN Go to [ Include additional AP600 PLACED IN SERVICE FOR SHUTDOWN details in E0Ps] .
COOLING 2 Verify CMT Actuated: Actuate CMT initiation. lE valves will HQI open, JBEN manually open
. CMT injection valves - OPEN valves as necessary.
3 Verify All RCPs Tripped Manually trip RCPs.
CAUTION If adverse containment conditions exist, RCS makeup should be operated in manual to maintain pressurizer level.
4 Check RCS Makeup Status:
- a. PRZR level - GREATER THAN a. Start all makeup pumps.
(L05)%[(L23)% FOR ADVERSE CONTAINMENT] ,
l
- b. PRZR level - LESS THAN b. Verify all makeup pumps !
(LO6)%[(L31)% FOR ADVERSE stopped. If HQI, IliEU l CONTAINMENT] manually stop all makeup pumps.
l 5 Return To Guideline And Step In Effect
- END -
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.. . ..m . . . .-. _ . _ . . __. .- .
t Number Title Rev./Date AFR-C.3 AP600 RESPONSE TO SATURATED CORE COOLING Rev. 0 5/31/95 !
FOOTNOTES l
Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline. {
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O AFR-H.1 Response to Loss of Secondary Heat Sink O
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i Number Title Rev./Date AFR-H.1 AP600 RESPONSE TO LOSS OF HEAT SINK Rev. 0 :
5/31/95 !
A. PURPOSE i This guideline provides actions to respond to a loss of heat sink in all steam generators.
B. SYMPTDMS OR ENTRY CONDITIONS l i
This guideline is entered from: ;
- 1) AE-0, AP600 REACTOR TRIP OR SAFETY INJECTION, Step 15, when minimum SFW flow .
is not verified AND narrow range level in all SGs is less than (LO3)% :
[(LO4)% FOR ADVERSE CONTAINMENT] AND PRHR can not be initiated. ;
- 2) AF-0.3, HEAT SINK Critical Safety Function Status Tree on a RED condition.
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Number Title Rev./Date AFR-H.1 AP600 RESPONSE TO LOSS OF HEAT SINK Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Try To Establish PRHR Flow:
- a. Actuate PRHR initiation
- b. Verify PRHR isolation b. Manually open valves as valves - OPEN necessary.
- c. Verify PRHR flow c. Manually open valves as necessary. IE PRHR flow can NOT be established, IBfd go to Step 2.
- d. Return to guideline and step in effect CAUTION
- If total feed flow is less than (F01) gpm due to operator action to control RCS temperature, this guideline should not be performed.
2 Check If Secondary Heat Sink Is Required:
- a. RCS pressure - GREATER THAN a. Go to AE-1, AP600 LOSS OF ANY NON-FAULTED SG PRESSURE REACTOR OR SECONDARY COOLANT, Step 1.
- b. RCS temperature - GREATER b. Try to place normal RNS l l THAN (T06) F [(T07) F FOR System in service to cool ADVERSE CONTAINMENT] RCS while continuing in this guideline. Refer to [ Include additional AP600 details in E0Ps]. If adequate cooling with normal RNS System established, IEEN return to guideline and step in effect.
O Page 2 of 9
Number Title Rev./Date
( 's AFR-H.1 AP600 RESPONSE TO LOSS OF HEAT SINK Rev. 0
(,,) 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION
- If parameter (V04) [(V05) for adverse containment]
is exceeded due to loss of secondary heat sink, Step 9 should be imediately initiated for feed and bleed cooldown.
- If the Deaerator Storage Tank level decreases to less than (LOB), the SFW pump suctton should be transferred to the CST.
3 Try To Establish SFW Flow To At least One SG:
- a. Check control room indications for cause of SFW failure:
. Deaerator storage tank level e SFW pump power supply V e SFW valve alignment e Low-2 RCS Tcold SFW isolation e High-2 SG NR level SFW isolation
- b. Try to restore SFW flow
- c. Check total flow to SGs - c. Dispatch operator to locally GREATER THAN (F01) GPM restore SFW flow. Go to Step 4.
- d. Return to guideline and step in effect -
.. 1 Page 3 of 9
Number Title Rev./Date AFR-H.1 AP600 RESPONSE TO LOSS OF HEAT SINK Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Try To Establish Main FW Flow To At least One SG
- a. Check Condensate System - IN a. Try to place Condensate SERVICE System in service. E ROI, IBEH go to Step 8.
- b. Check FW isolation valves - b. Perform the following:
OPEN
- 1) Reset S1 if necessary.
- 2) Reset FW isolation.
- 3) Open FW isolation valves.
E no FW isolation valve can be opened, JJ1EN go to Step 8.
- c. Establish Main FW flow: c. Go to Step 6.
[ Include additional AP600 details in E0Ps]
5 Check SG Levels:
- a. Narrow range level in at a. IE feed flow to at least one least one SG - GREATER THAN SG verified, IREN maintain (LO3)% [(LO4)% FOR ADVERSE flow to restore narrow range CONTAINMENT] level to greater than (LO3)%
[(LO4)% for adverse containment] . IE N01 verified, IllEH go to Step 6.
- b. Return to guideline and step in effect O
Page 4 of 9
. _~_ . . .
i Number Title Rev./Date AFR-H.1 AP600 RESPONSE TO LOSS OF HEAT SINK Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPGNSE RESPONSE NOT OBTAINED CAUTION Following block of automatic Si actuation, manual SI actuation may be required if conditions degrade.
6 Try To Establish Feed Flow From Condensate System:
- a. Depressurize RCS to less than (P06) PSIG:
- 1) Use normal spray 1) Use auxiliary spray. lE auxiliary spray E available, JBEN use one set of first stage PRZR ADS valves.
- b. Block SI signals:
e Low Steamlire Pressure SI e Low PRZR Pressure SI e Low T-cold SI
- c. Depressurize at least one SG to less than (P20) PSIG:
- 1) Dump steam to condenser 1) Manually or locally dump at maximum rate steam from SGs: ,
e Use PORV.
-0R-e [Includeadditional AP600 details in E0Ps].
If E . J1iEN go to Step 8.
- d. Establish condensate flow: d. Go to Step 8.
(includeadditionalAP600 details in E0Ps]
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Number Title Rev./Date AFR-H.1 AP600 RESPONSE TO LOSS OF HEAT SINK Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Check SG Levels:
- a. Narrow range level in at a. lf feed flow to at least one least one SG - GREATER THAN SG verified,1[iEN maintain (LO3)% [(LO4 flow to restore narrow range CONTAINMENT])% FOR ADVERSE level to greater than (LO3)%
[(LO4)% for adverse containment] . If N01 verified, ItiEN go to Step 8.
- b. Return to guideline and step in effect 8 Check For Loss Of Secondary Heat Sink:
- a. Parameter (V04) [(V05) for a. Return to Step 1.
adverse containment]
EXCEEDED CAUTION Steps 9 through 12 must be performed quickly in order to establish RCS heat removal by RCS feed and bleed.
9 Actuate SI 10 Verify CMT Actuated: Actuate CMT initiation. IE valves will HQI open, IliEN manually open e CMT injection valves - OPEN valves as necessary.
11 Verify All RCPs Tripped Manually trip RCPs.
O Page 6 of 9
Number Title Rev./Date
,e ~s AFR-H.1 AP600 RESPONSE TO LOSS OF HEAT SINK Rev. 0 (ji 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If IRWST level decreases to less than (L11), RNS alignme,1t to the containment sump should be verified.
12 Establish RCS Bleed Path:
- a. Actuate ADS
- b. Verify first stage ADS b. Manually open valves as isolation valves - OPEN necessary.
- c. Check second stage ADS c. WHEN (Tol) seconds have valves - OPEN elapsed from first stage ADS signal, IEEB verify second stage ADS valves open. If HQI, IHEN manually open second stage ADS valves as necessary.
- d. Check third stage ADS d. WHEB (T02) seconds have fT valves - OPEN elapsed from second stage V ADS signal, IHEN verify third stage ADS valves open.
IE HQI, IHEN manually open third stage ADS valves as ;
necessary. ;
- e. Align RNS to inject into RCS e. If RNS injection into RCS i can HQI be established, IHEN l actuate fourth stage ADS. '
13 Perform Steps 1 Through 11 Of l E-0, REACTOR TRIP OR SAFETY INJECTION While Continuing With This Guideline 1
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Number Title Rev./Date Af t-H.1 AP600 RESPONSE TO LOSS OF HEAT SINK Rev. 0 5/31/95 STEP f ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If adverse containment conditions exist, RCS makeup should be operated in manual to maintain pressurizer level.
14 Check RCS Makeup Status:
- a. PRZR level - GREATER THAN a. Verify one mai:eup pump (105)%[(L23)% FOR ADVERSE running. If Mjl, IBfB CONTAINMENT] manually start one makeup pump. If level continues to decrease or cannot be restored, IliEN stcrt second makeup pump.
- b. PRZR level - LESS THAN b. Verify all makeup pumps (LO6)%[(L31)% FOR ADVERSE stopped. If N01, IllEN CONTAINMENT] manually stop all makeup pumps.
CAUTION
- If containment pressure increases to greater than (Pol), containment spray should be verifled.
15 Continue Attempts To Establish Secondary Heat Sink In At least One SG:
. SFW flow
. Main FW flow e Condensate flow
. Other low pressure flow 16 Go To AE-1, AP600 LOSS OF REACTOP, OR SECONDARY COOLANT, Step 13
- END -
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Number Title Rev./Date 1
[ AFR-H.1 AP600 RESPONSE TO LOSS OF SECONDARY HEAT SINK Rev. 0 5/31/95 l l
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FOOTNOTES ,
l Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline. ;
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i AFR-H.2 l 1
Response to Steam Generator Overpressure l O
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m- Number 11tle Rev./Date AFR-H.2 AP600 RESPONSE TO STEAM GENERATOR OVERPRESSURE Rev. 0 5/31/95 i
i A. PURPOSE This guideline provides actions for an overpressure condition affecting either steam generator where pressure has increased above the highest safety valve setpoint.
B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AF-0.3, HEAT SINK Critical Safety function Status Tree on a YELLOW condition. ,
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Page 1 of 5
Number Title Rev./Date AFR-H.2 AP600 RESPONSE TO STEAM GENERATOR OVERPRESSURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Throughout this guideline, "affected" refers to either SG in which pressure is greater than (P18) psig 1 Identify Affected SG(s):
2 Verify FW Isolation To Affected Manually close valves.
SG(s):
- a. Flow control valves - CLOSED
- b. FW isolation valves - CLOSED 3 Check Affected SG(s) Narrow Range Go to AFR-H.3, AP600 RESPONSE TO Level - LESS THAN (L27)% [(L28)% STEAM GENERATOR HIGH LEVEL, FOR ADVERSE CONTAINMENT] Step 1.
CAUTION If affected SG narrow range level increases to greater than (L27)% [(L28)% for adverse containment], steam should not be released from the affected SG(s).
4 Try To Dump Steam From The Go to Step 6.
Affected SG(s):
e Steam Dump System
-OR- 1 e Main steamline isolation l Lypass valves
-OR-e [ Include additional AP600 details in E0Ps]
Page 2 of 5
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Number Title Rev./Date AFR-H.2 AP600 RESPONSE TO STEAM GENERATOR OVERPRESSURE Rev. 0 O _
5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check Affected SG(s) Pressure:
- a. Pressure - DECREASING a. Go to Step 6. I
- b. Pressure - LESS THAN (P18) b. Return to Step 3. !
- d. Return to guideline and step !
in effect i CAUTION SFW flow should remain isolated to affected SG(s) until a steam release path is established. ,
6 Isolate SFW Flow To Affected SG(s) 7 Check RCS Hot Leg Temperatures - Cool down RCS to less than '
LESS THAN (TIO) F [(Til) F FOR (TIO) F [(T11) F for adverse ADVERSE CONTAINMENT] containment] by dumpin steam from the unaffected SG s).
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Number Title Rev./Date AFR-H.2 AP600 RESPONSE TO STEAM GENERATOR OVERPRESSURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Continue Attempts To Manually Or Locally Dump Steam From Affected SG(s):
. Steam Dump System
-OR-
. Main steamline isolation i bypass valves j
-OR-e [ Include additional AP600 l details in E0Ps]
9 Return To Guideline And Step In O1l Effect
- END -
O Page 4 of 5
J n Number Title . Rev./Date J( AFR-H.2 -AP600 RESPONSE TO STEAM GENERATOR OVERPRESSURE Rev. 0 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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O AFR-H.3 Response to Steam Generator High Level O
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Number Title Rev./Date
-* AFR-H.3 AP600 RESPONSE TO STEAM GENERATOR HIGH LEVEL Rev. 0 j-5/31/95 3
i A. PURPOSE This guideline provides actions to respond to a steam generator high level !
condition and to address the steam generator overfill concern. ;
- 8. SYMPTOMS OR ENTRY CONDITIONS !
This guideline is entered from: .
- 1) AF-0.3, HEAT SINK Critical Safety Function Status Tree on a YELLOW ,
condition, and !
- 2) AFR-H.2, AP600 RESPONSE TO STEAM GENERATOR OVERPRESSURE, Step 3, if the !
affected SG narrow range level is high. .
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Number Title Rev./Date AFR-H.3 AP600 RESPONSE TO STEAM GENERATOR HIGH LEVEL Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If SG narrow range level has increased to greater than (L27)% [(L28)% for adverse containment] an evaluation should be made for SG overfill considerations. Steam should not be released from any SG with level greater than (L27)% [(L28)% for adverse containment] prior to overfi11 evaluation.
NOTE Throughout this guideline, "affected" refers to either SG in which narrow range level is greater than (L12)%.
1 Identify Affected SG(s):
- a. Narrow range level - GREATER a. If less than (L12)% in all THAN (L12)% SGs, IllEN return to guideline and step in effect.
2 Verify FW Isolation:
- a. Main FW pumps - STOPPED a. Manually stop pumps.
- b. Flow control valves - CLOSED b. Manually close valves.
- c. Feedwater isolation valves - c. Manually close valves.
CLOSED 3 Isolate SFW Flow To Affected SG(s)
O Page 2 of 4
Number Title Rev./Date
(~'N AFR-H.3 AP600 RESPONSE TO STEAM GENERATOR HIGH LEVEL Rev. 0
(,) 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check Affected SG(s) Level:
- a. Narrow range level - LESS a. Go to Step 5.
THAN (L27)% [(L28)% FOR ADVERSE CONTAINMENT]
- b. Narrow range level - b. Go to Step 5.
DECREASING
- c. Control SFW flow to maintain narrow range level between (LO3)% [(LO4)% for adverse containment] and 50%
- d. Return to guideline and step in effect 5 Adjust Affected SG(s) PORY
/O Controller Setpoint To (P05) PSIG
()
6 Close Affected SG(s) Main Steamline Isolation and Bypass Valves 7 Check Affected SG(s) Radiation - IE AE-3 guideline is in effect, NORMAL 1REN return to guideline and step in effect. If H01. IllEN go to
[ Include additional AP600 details AE-3 AP600 STEAM GENERATOR TUBE in E0Ps] RUPTURE, Step 1.
8 Establish Blowdown From Affected SG(s):
[ Include additional AP600 details in E0Ps]
9 Return To Guideline And Step In Effect rm
) - END -
Page 3 of 4 i
Number Title Rev./Date AFR-H.3 AP600 RESPONSE TO STEAM GENERATOR HIGH LEVEL Rev. 0 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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1 AFR-H.4 Response to Loss of Normal Steam l Release Cap i
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f Number Title Rev./Date O AFR-H.4 AP600 RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES Rev. 0 5/31/95 l
l A. PURPOSE This guideline provides actions to respond to a failure of the steam generator power operated relief valves (PORVs) and condenser dump valves.
B. PURPOSE .
This guideline is entered from AF-0.3, HEAT SINK Critical Safety ranction Status Tree on a YELLOW condition. ,
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Number Title Rev./Date AFR-H.4 AP600 RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If affected SG(s) narrow range level increases to greater than (L27)4 [(L28)% for adverse containment ,
steam should not be released from the affected SG(s .
NOTE Throughout this guideline, "affected" refers to either SG in which pressure is greater than (P19) psig.
1 Try To Restore Normal Steam Release Capability Of Affected SG(s):
-0R-e Condenser steam dump
-OR-
- [ Include additional AP600 details in E0Ps]
2 Check SG Pressures - LESS THAN Manually or locally dump steam (P19) PSIG from SG(s with pressure greater than (P19 psig.
3 Return To Guideline And Step In Effect
- END -
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- Number Title Rev./Date AFR-H.4 Rev. O
'l-\'n)- AP600 P.ESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES 5/31/95 t
FOOTNOTES l Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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AFR-H.5 l Response to Steam Generator Low Level l O ,
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Number Title Rev./Date AFR-H.S AP600 RESPONSE TO STEAM GENERATOR LOW LEVEL Rev. O Os g 5/31/95 A. PURPOSE i This guideline provides actions to respond to a steam generator low level !
condition. ;
B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AF-0.3 HEAT SINK Critical Safety Function Status ,
Tree on a YELLOW condition. !
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Number Title Rev./Date i AFR-H.S AP600 RESPONSE TO STEAM GENERATOR LOW LEVEL Rev. 0 l 5/31/95 i l
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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
l CAUTION Steam releases from affected SG(s) should be minimized.
1 NOTE Throughout this guideline, "affected" refers to either SG in which narrow range level is less than (LO3)%
[(LO4)% for adverse containment].
1 Identify Affected SG(s): 1
- a. Narrow range level - LESS a. Return to guideline and step THAN (LO3)% [(LO4)% FOR in effect.
ADVERSE CONTAINMENT]
l 2 Verify Blowdown Isolation Valves Manually close valves.
From Affected SG(s) - CLOSED CAUTION SFW flow should not be established to a faulted SG that has been isolated unless needed for RCS cooldown.
3 Check If Affected SG(s) Not Faulted:
- a. Check pressure in affected a. E affected SG(s) previously SG(s) - identified as faulted, M return to guideline and step e NOT DECREASING IN AN in effect. E HQI, M go UNCONTROLLED MANNER to AE-2, AP600 FAULTED STEAM GENERATOR ISOLATION, Step 1.
. NOT COMPLETELY DEPRESSURIZED 4 Check SFW Flow To Affected E affected SG(s) wide range SG(s) - GREATER THAN (F04) GPM level greater than (L29)% [(L30)%
for adverse containment], M establish SFW flow as necessary to refill affected SG(s).
E affected SG(s) wide range level less than (L29)% ,:(L30)%
for adverse containment , E establish SFW flow to affected SG(s) at a rate not to exceed 100 gpm per SG.
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, I Number Title Rev./Date Rev. 0 O AFR-H.5 AP600 RESPONSE TO STEAM GENERATOR LOW LEVEL 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Continue Filling Affected SG(s)
Until Narrow Range Level Greater Than (LO3)% [(LO4)% For Adverse Containment]
6 Return To Guideline And Step In Effect !
- END -
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Number Title Rev./Date AFR-H.5 AP600 RESPONSE TO STEAM GENERATOR LOW LEVEL Rev. 0 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used.in this guideline.
0 9
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O AFR-P.1 l
Response to Imminent Pressure Thermal l Shock Condition l O
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AFR-P.1 AP600 RESPONSE TO IP911NENT PRESSURIZED THERMAL SHOCK Rev. 0 CONDITION 5/31/95 i
A. PURPOSE This guideline provides acticas to avoid, or limit, thermal shock or pressurized thermal shock to the reactor pressure vessel, or overpressure conditions at low temperature. -
i B. SYMPTOMS OR ENTRY CONDITIONS <
This guideline is entered from AF-0.4, INTEGRITY Critical Safety Function ~ Status Tree on a RED or either ORANGE condition.
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Number Title Rev./Date AFR-P.1 AP600 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Rev. O CONDITION 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE A faulted SG is either SG that is depressurizing in an uncontrolled manner or is completely depressurized.
1 Check RCS Cold Leg Temperatures - Try to stop RCS cooldown:
STABLE OR INCREASING
- b. Verify condenser steam dump valves closed.
- c. If both SFW in operation and narrow range level greater than (LO3)% [(LO4)% for adverse containment] in at least one SG, IHEN isolate PRHR.
- d. If normal RNS in service, INEN stop any cooldown from RNS.
- e. Control feed flow to non-faulted SG(s) to stop RCS cooldown. Maintain total feed flow greater than (F01) gpm until narrow range level greater than (LO3)% [(LO4)%
for adverse containment] in at least one non-faulted SG.
- f. Minimize cooldown from faulted SG(s):
- 1) Verify main steamline isolation and bypass valves closed for each faulted SG.
- 3) If any SG HQI faulted, IHEN isolate all feedwater to faulted SG(s) unless necessary for RCS temperature control. If a faulted SG is necessary for RCS temperature control,(M flow at F04)control feed gpm to that SG.
Page 2 of 9
Number Title Rev./Date
'p AFR-P.1 AP600 RESPONSE TO I M INENT PRESSURIZED THERMAL SHOCK Rev. 0 ys CONDITION 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If adverse cor'tainment conditions exist, RCS makeup should be operated in manual to maintain pressurizer level.
2 Check RCS Makeup Status
- a. PRZR level GREATER THAN a. Verify one makeup pump (LO5)% [(L2 )% FOR ADVERSE running. IE MQI, ItiG CONTAINMENT manually start one makeup pump. IE level continues to decrease or cannot be restored,111@ start second makeup pump.
- b. PRZR level - LESS THAN b. Verify all makeup pumps (LO6)% [(L31 stopped. If HQI,1115 CONTAINMENT])% FOR ADVERSE manually stop all makeup pumps.
3 Check If CMT Injection Should Be Isolated:
- a. ADS - NOT ACTUATED a. Go to Step 4.
- b. RCS subcooling based on core b. Go to Step 4.
exit TCs GREATER THAN (S01) F CONTAINME[ TS 2) F FOR ADVERSE
- r. PRZR level - GREATER THAN c. Go to Step 4.
(LO5)% [(L2 )% FOR ADVERSE CONTAINMENT
- d. Reset SI
- e. Close CMT injection valves O
Page 3 of 9
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Number Title Rev./Date AFR-P.1 AP600 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Rev. O CONDITION 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Verify CMT Injection Not Required:
- a. RCS subcooling based on core a. Manually'open CMT injection exit TCs - GREATER THAN valves and go to Step 14.
(501) F [(S02 CONTAINMENT] )"F FOR ADVERSE
- b. PRZR level - GREATER THAN b. Manually open CMT injection (LO5)% [(L23 valves CONTAINMENT])% FOR ADVERSE 5 Check RCS Hot Leg Temperatures - If increasing, ljif3 control feed STABLE flow and steam dump as necessary to establish stable RCS hot leg temperat ures ,11 dec reasi ng ,111EB verify actions of Step 1 have been performed before continuing with this guideline.
6 Check If SI Accumulators Should Be Isolated:
- a. RCS subcooling based on core a. Return to Step 4.
exit TCs - GREATER THAN (S01) F [(502) F FOR ADVERSE CONTAINMENT]
- b. Check power to isolation b. Restore power to isolation valves - AVAILABLE valves.
- c. Close all SI accumulator c. Vent any unisolated isolation valves accumulator.
O Page 4 of 9
Number Title Rev./Date em AFR-P.1 AP600 RESPONSE TO IW4INENT PRESSURIZED THERMAL SHOCK Rev. O Q CONDITION 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 De ressurize RCS To Decrease RCS I Su cooling:
- a. Use auxiliary spray a. Use one set of first stage PRZR ADS valves.
- b. Depressurize RCS until either of the following conditions satisfied:
. RCS subcooling based on core exit TCs - LESS THAN (S03) F [(SO4) F FOR ADVERSE CONTAINMENT]
-0R-e PRZR level - GREATER THAN (L13)% [(L14)% FOR ADVERSECONTAINMENT)
- c. Stop RCS depressurization CAUTION An increase in RCS pressure may result in excessive reactor vessel stress. RCS pressure and temperature should be maintained stable while performing subsequent steps in this guideline.
8 Check PRZR Level - GREATER THAN Try to restore level with makeup (L22)% [(L25 while maintaining stable RCS CONTAINMENT])% FOR ADVERSE pressure. IE level can H0I be restored, JEEN go to step 13.
9 Check RCS Makeup Control System: Adjust controls as necessary.
- a. Makeup control system set for cold shutdown boron concentration
- b. Makeup set for automatic control i
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l Number Title Rev./Date AFR-P.1 AP600 RL'sPONSE TO IM4INENT PRESSURIZED THERMAL SHOCK Rev. O CONDITION 5/31/95 I
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED !
i 10 Check If Letdown Should Be Established:
- a. PRZR level - GREATER THAN a. Go to Step 11.
(LO6)% [(L31 CONTAINMENT])% FOR ADVERSE
- b. Establish letdown: b. Establish reactor head vent i flow. !
[ Include additional AP600 details in E0Ps] [ Include additional AP600 ,
details in E0Ps]
11 Check PP.IR Level - LESS THAN Control makeup and letdown as (L13)% [(L14)% FOR ADVERSE necessary.
CONTAINMENT]
12 Control PRZR Pressure:
- a. Maintain pressure stable a. Use one set of first stage using PRZR heaters and PRZR ADS valves.
auxiliary spray as necessary 13 Check RCS Subcooling Based On Use auxiliary spray for any Core Exit TCs - LESS THAN (503) F further depressurization. Return
[(504) F FOR ADVERSE CONTAINMENT] to Step 7b.
IE HQI, IHEN return to Step 7a.
O Page 6 of 9
Number Title Rev./Date AFR-P.1 AP600 RESPONSE TO IMINENT PRESSURIZED THERMAL SHOCK Rev. 0
(* CONDITION 5/31/95
(
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Determine If RCS Temperature Soak
- Is Required
- a. Cooldown rate in RCS cold a. Go to Step 15. !
legs - GREATER THAN 100 F IN ANY 60 MINUTE PERIOD
- b. Perform all of the following:
- 1) Do not cool down RCS until temperature has been stable for (T12) hours
- 2) Do not increase RCS pressure during that time
- 3) Perform actions of other guidelines in effect O which do not cool down or increase RCS pressure until the RCS temperature soak has been completed
- 4) RCS cooldown is perTnitted after (T12) hours
- 5) Maintain RCS pressure and cold leg temperature within the limits of Figure AFRP1-1
- 6) Maintain cooldown rate in RCS cold legs less than 50 F in any 60 minute period 15 Return To Guideline And Step In Effect
- END -
O Page 7 of 9
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Number Title Rev./Date AFR-P.1 AP600 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Rev. O CONDITION 5/31/95 FIGURE AFRP-1, POST SOAK C00LDOWN LIMIT i
i 2,400 I
l 2,000 -
EXAMPLE 1,800 -
ONLY e
j a 1,200 -
.cermm e h; "l% "
$ COOLDOWN
!E 8
5 800 -
400 -
0 '
j 0 100 200 300 400 500 600 RCS COLD LEG TEMPERATURE (DEG F) l I
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_ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ - - _ - . . - . _ - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .J
. . . . .. .-. _. . . -- - .. - . - _ _ . _ . . . - - . ~ . - - .
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( Number Title Rev./Date .
I AFR-P.1 AP600 RESPONSE TO I M INENT PRESSURIZED THERMAL SHOCK Rev. O !
CONDITION 5/31/95 i i
i FOOTNOTES i
Refer to FOOTNOTE DEFINITION Document for a description of all footnoted l parameters used in this guideline.
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AFR-P.2 Response to Anticipated Pressure Thermal Shock Condition O
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Number Title Rev./Date
!O AFR-P.2 AP600 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK Rev. O i CONDITION 5/31/95 i
A. PURPOSE ,
This guideline provides actions to respond to a limited overcooling condition or '
to an overpressure condition at low temperature. j B. SYMPTOMS OR ENTRY CONDITIONS !
This guideline is entered from AF-0.4, INTEGRITY Critical Safety Function Status ,
Tree on either YELLOW condition. ,.
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Number Title Rev./Date AFR-P.2 AP600 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK Rev. O CONDITION 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE A faulted SG is either SG that is depressurizing in an uncontrolled manner or is completely depressurized.
1 Check RCS Cold Leg Temperatures - Try to stop RCS cooldown:
STABLE OR INCREASING
- b. Verify condenser steam dump valves closed.
- c. E both SFW in operation and narrow range level greater than (LO3)% [(LO4)% for adverse containment] in at least one SG, M isolate PRHR.
- d. E normal RNS in service, M stop any cooldown from RNS.
r Contiol feed flow to non-faulte ir SG(s) to stop RCS cnM j;wn. Maintain total feed flow greater than (F01) gpm until narrow range level greater than (LO3)% [(LO4)%
for adverse containment] in at least one non-faulted SG.
- f. Minimize cooldown from faulted SG(s):
- 1) Verify main steamline isolation and bypass valves closed for each faulted SG.
- 3) E any SG N01 faulted, M isolate all feedwater to faulted SG(s) unless necessary for RCS temperature control. E a faulted SG is necessary for RCS temperature control,(IHEN flow at F04) gpm control feed to that SG.
Page 2 of 5
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Number Title Rev./Date AFR-P.2 AP600 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK Rev. O O CONDITION 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 1
1 2 Check RCS Pressure - WITHIN TECH Decrease RCS pressure to within 4 SPEC PRESSURE-TEMPERATURE LIMITS tech spec limits using auxiliary '
FOR 100 F/HR C00LDOWN RATE spray. If auxiliary spray HDI :
available, IllEN use one set of first stage PRZR ADS valves.
3 Determine If Additional RCS Cooldown Restrictions Are Required:
- a. Cooldown rate in RCS cold a. Additional cooldown legs - GREATER THAN 100 F IN restrictions are not ANY 60 MINUTE PERIOD required. Go to Step 4.
- b. RCS cooldown is permitted with the following restrictions:
- 1) Maintain RCS pressure and cold leg temperatures O within the limits of Figure AFRP2-1
- 2) Maintain cooldown rate in RCS cold legs less than 100 F in any 60 minute period 4 Return To Guideline And Step In Effect
- END -
b
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Number Title Rev./Date AFR-P.2 AP600 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK Rev. O CONDITION 5/31/95 f1GURE AFRP-2. C00LDOWN LIMII 2,400 r 2,000 -
EXAMPLE ONLY g 1,600 -
Ui E
W ACCEPTABLE REG:ON w 1,200 --
roa COOLDOWN E
8 5 800 -
400 -
0 '
O 100 200 300 400 500 600 RCS COLD LEG TEMPERATURE (DEG F)
O Page 4 of 5
I Number Title Rev./Date AFR-P.2 Rev. 0
-AP600 RESPONSE TO ANTICIPATED PRESSURIZED THERMAL SHOCK CONDITION 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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O AFR-Z.1 Response to High Containment Pressure O ,
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j "g Number Title Rev./Date (g AFR-Z.1 AP600 RESPONSE TO HIGH CONTAINMENT PRESSURE Rev. 0 5/31/95 A. PURPOSE This guideline provides actions to respond to a high containment pressure.
B. SYMPTOMS OR ENTRY CONDITIONS f This guideline is entered from AF-0.5, CONTAINMENT Critical Safety Function l- Status Tree on a RED or ORANGE condition.
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Number Title Rev./Date AFR-Z.1 AP600 RESPONSE TO HIGH CONTAINMENT PRESSURE Rev. O !
5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED j 1 Verify Containment Isolation if flow path HQI necessary, IHEN Valves - CLOSED close valves.
2 Check If Passive Containment Cooling Is Required: :
1
- a. Check the following: a. Return to guideline and step in effect.
. Containment pressure -
HAS INCREASED TO GREATER THAN (P01) PSIG
- OR -
e Containment temperature -
GREATER THAN (103)
- b. Verify PCCWST injection b. Manually open valves.
valves - OPEN 3 Verify Containment Fan Coolers - Manually start fan coolers.
RUNNING 4 Verify Main Steamline Isolation Manually close valves.
And Bypass Valves - CLOSED Page 2 of 5
_ - . _ _ _ _ . _ . . .. _ __ ~ _ _ ._ _ _ m. _ ._ . . _ . _ _
i Number Title Rev./Date s AFR-Z.1 AP600 RESPONSE TO HIGH CONTAINMENT PRESSURE Rev. 0 5/31/95 l i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED :
i i
CAUTION
e if both SGs are faulted and PRHR is not available, at least (F04) gpm feed flow should be maintained to the SG that will be used for RCS cooldown. '
5 Check If Feed Flow Should Be I Isolated To Any SG.
- a. Check pressures in all SGs - a. Go to Step 6. [
e ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER
-OR- !
. ANY SG COMPLETELY DEPRESSURIZED O b. Isolate feed flow to affected SG:
i
- Main FW
. Sm 1 l
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Number Title Rev./Date AFR-Z.1 AP600 RESPONSE TO HIGH CONTAINMENT PRESSURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check Containment Hydrogen Concentration:
AVAILABLE
[ Include additional AP600 details in E0Ps]
Continue with Step 8. WHEN hydrogen concentration measurement available, IHEN do Step 6b.
- b. Hydrogen concentration - b. Determine if additional LESS THAN 0.5% IN DRY AIR recovery actions are necessary. Go to Step 7.
- c. Go to Step 8 7 Periodically Obtain A Hydrogen Concentration Measurement 8 Return To Guideline And Step In Effect
- END - ,
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i Number Title Rev,/Date
/ AFR-Z.1 AP600 RESPONSE TO HIGH CONTAINMENT PRESSURE Rev. 0 :
5/31/95 i
FOOTNOTES [
L Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline. ;
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Nf AFR-Z.2 Response to Containment Flooding ;
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Number Title Rev./Date AFR-Z.2 AP600 RESPONSE TO CONTAINMENT FLOODING Rev. 0 5/31/95 A. PURPOSE This guideline provides actions to respond to containment flooding.
B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AF-0.5, CONTAINMENT Critical Safety Function Status Tree on an ORANGE condition. '
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Number Title Rev./Date AFR-Z.2 AP600 RESPONSE TO CONTAINMENT FLOODING Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Try To Identify Unexpected Source Of Water To Containment:
- CCS e VWS e Demineralized water
. [ Include additional AP600 details in E0Ps]
2 Check Containment Water Activity Level:
[ Include additional AP600 details in E0Ps]
3 Determine If Any Additional '
Actions Are Necessary 4 Return To Guideline And Step In Effect
- END -
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o __ . _.. . . . _ . . _ .- _ . - . . . , _ _ _ . . _ _ _ . . _ _ . . _ .._
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Number Title. Rev./Date O AFR-Z.2 AP600 RESPONSE TO CONTAINMENT FLOODING Rev. 0 5/31/95 :
FOOTNOTES .
NONE USED IN THIS GUIDELINE l l
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AFR-Z.3 Response to High Containment
. Radiation Level O F O
Number Title Rev./Date
( AFR-Z.3 AP600 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL Rev. 0 5/31/95 A. PURPOSE This guideline provides actions to respond to high containment radiation level.
B. SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AF-0.5, CONTAINMENT Critical Safety Function Status Tree on a YELLOW condition.
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Number Title Rev./Date AFR-Z.3 AP600 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL Rev. 0 5/31/95 $
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Verify Containment Ventilation Isolation:
- a. Containment exhaust a. Go to Step 2.
radiation - GREATER THAN (R01)
- b. Verify containment supply b. Manually close dampers.
and exhaust air dampers -
CLOSED 2 Check Containment Radiation:
- a. Containment radiation - LESS a. Verify the following:
THAN (R02)
- 1) RNS IRWST suction line isolation valve closed.
If HQI,1118 manually close valve. h
- 2) WLS containment sump pump discharge isolation valve closed. If EQI. IliB manually close valve.
3 Determine If Any Additional Actions Are Necessary 4 Return To Guideline And Step In Effect
- END -
Page 2 of 3
--..- = .- - - - - .. .. - . . . . .-
1 Number Title Rev,/Date AFR-Z.3 AP600 RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL Rev. 0 j
5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline. ,
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Response to Low Containment Pressure ,
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Number T1 tie ~ Rev./Date
- AFR-Z.4 'AP600 RESPONSE TO LOW CONTAINMENT PRESSURE Rev. 0 5/31/95 A. PURPOSE This guideline provides actions to respond to a low containment pressure.
B. SYMPTOMS OR ENTRY CONDITIONS This guideline in entered from AF-0.5, CONTAINMENT Critical Safety Function Status Tree on a YELLOW condition.
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Number Title Rev./Date AFR-Z.4 AP600 RESPONSE TO LOW CONTAINMENT PRESSURE Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Determine If Containment Pressure Should Be Increased By Adding Outside Air 2 Return To Guideline And Step In Effect I
- END -
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73 Nurrber Title Rev./Date AFR-Z.4 Rev. 0
(] AP600 RESPONSE TO LOW CONTAINMENT PRESSURE 5/31/95 ;
i FOOTNOTES NONE USED IN THIS GUIDELINE O
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Page 3 of 3
O AFR-I.1 Response to High Pressurizer Level l
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.. .. -. _. .. . . . . - --. . . ~ . . -- - . -
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Number Title . Rev./Date l AFR-I.1 AP600 RESPONSE TO HIGH PRESSURIZER LEVEL Rev. 0 :
5/31/95 !
t i
I A. PURPOSE [
This guideline provides actions to respond to a high pressurizer level. !
B. SYMPTOMS OR ENTRY CONDITIONS !
l This guideline is entered from AF-0.6,' INVENTORY Critical Safety Function Status l Tree on a YELLOW condition. l
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Number Title Rev./Date AFR-I.1 AP600 RESPONSE TO HIGH PRESSURIZER LEVEL Rev. 0 ,
5/31/95 l I
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Check CMT Injection Valves - ALL Return to guideline and step in !
CLOSED effect.
CAUTION Makeup and letdown flows should be carefully controlled to avoid sudden RCS pressure changes since the PRZR may be water solid. ,
2 Check RCS Makeup Status:
- a. RCS makeup - IN SERVICE a. Start one makeup pump.
3 Check Letdown - IN SERVICE Establish letdown:
[ Include additional AP600 details in E0Ps] .
4 If letdown can HQI be I established, It1B establish l reactor head vent flow.
[ Include additional AP600 details in E0Ps] .
4 Check PRZR Pressure:
- a. Pressure - LESS THAN (P02) a. Control makeup and letdown PSIG as necessary to decrease PRZR pressure to less than (P02) psig.
5 Turn On PRZR Heaters l
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Number Title Rev./Date p AFR-I.1 AP600 RESPONSE TO HIGH PRESSURIZER LEVEL Rev. O V 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
+
6 Check PRZR Spray Valves:
- a. Normal spray ilves - CLOSED a. Manually close spray valves.
E valve (s) can HDI be closed, IHEN close PRZR E valve (s)(can HQI bespray valve s) bl closed IllEN stop RCP(s) supplying failed spray valve (s).
- b. Auxiliary spray valve - b. Manually close auxiliary CLOSED spray valve. E valve can H01 be closed, ItiEN open i normal RCS makeup line. ,
7 Control Makeup And Letdown As Necessary To Maintain RCS Pressure Stable 8 Check PRZR Level ' LESS THAN Return to Step 7.
(L24)% ;
9 Return To Guideline And Step In Effect
- END -
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Number Title Rev./Date AFR-I.1 AP600 RESPONSE TO HIGH PRESSURIZER LEVEL Rev. 0 5/31/95 FOOTNOTES Refer to FOOTNOTE DEFINITION Document for a description of all footnoted parameters used in this guideline.
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AFR-I.2 Response to Low Pressurizer Level l O
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~. - . . - - . .-. - , . . . . -. . = . . - -
t Number Title Rev./Date f AFR.".2 AP600 RESPONSE TO LOW PRESSURIZER LEVEL Rev. 0 l 5/31/95 i
A. PURPOSE This guideline provides actions to respond to a low pressurizer level.
B.
SYMPTOMS OR ENTRY CONDITIONS This guideline is entered from AF-0.6, INVENTORY Critical Safety Function Status !
Tree on a YELLOW condition.
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Number Title Rev./Date AFR-I.2 AP600 RESPONSE TO LOW PRESSURIZER LEVEL Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 Check CMT Injection Valves - ALL Return to guideline and step in CLOSED effect.
2 Verify Letdown - ISOLATED Manually isolate letdown.
3 Verify One Makeup Pump - RUNNING Manually start one makeup pump.
E level continues to decrease or cannot be restored,1118 start second makeup pump.
4 Increase RCS Makeup Flow To E makeup flow at maximum IllG Restore PRZR Level open CMT injection valves. IE PRZR level can NJJ be restored, 1118 go to AE-1, AP600 LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
5 Check PRZR Level:
- a. Level - INCREASING a. Return to Step 4.
- b. Level - GREATER THAN (L22)% b. Return to Step Sa.
6 Turn On PRZR Heaters As Necessary 7 Return To Guideline And Step In Effect
- END -
O Page 2 of 3
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Rev./Date i A -I.2 AP600 RESPONSE TO LOW PRESSURIZER LEVEL RV N5 FOOTNOTES I,
Refer to FOOTNOTE DEFINITION Document for. a description of all footnoted :
parameters used in this guideline. '
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. . . - - _- . - - - - .-- -___--- ._ - -1
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o l AFR-I.3 Response to Voids in Reactor Vessel f
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Number Title Rev./Date !
.g AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR VESSEL Rev. 0 ,
5/31/95 i
A. PURPOSE This guideline provides actions to respond to voids in the reactor vessel head. ;
B. SYMPTOMS OR ENTRY CONDITIONS ;
This guideline is entered from AF-0.6, INVENTORY Critical Safety Function Status Tree on a YELLOW condition.
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Number Title Rev./Date AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR VESSEL Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONFT RESPONSE NOT OBTAINED CAUTION If a controlled natural circulation cooldown is in progress and a void in the reactor vessel upper head is expected, this guideline should not be performed.
1 Check CMT Injection Valves - ALL Return to guideline and step in CLOSED effect. i l
l 2 Establish Stable RCS Conditions: j i
- a. PRZR level - STABLE AND a. Control RCS makeup and BETWEEN 40% AND 60% letdown as necessary.
- b. RCS pressure - STABLE b. Turn on PRZR heaters and use j normal PRZR spray as I necessary. If normal spray HDI available, JE B use auxiliary spray.
- c. RCS hot leg temperatures - c. Dump steam as necessary.
STABLE 3 Check RCPs - ALL STOPPED Go to Step 10.
4 Check If RCS Pressure Should Be (
Increased:
- a. Pressure - AT LEAST 100 PSI a. Go to Step 7.
LESS THAN TECH SPEC LIMIT
- b. Pressure - LESS THAN (P16) b. Go to Step 7.
PSIG [(Pl7) PSIG FOR ADVERSE CONTAINMENT]
- c. Turn on PRZR heaters to increase RCS pressure 50 psi 5 Control RCS Makeup And Letdown As Necessary To Maintain PRZR Level Greater Than (L22)% [(L25)% For Adverse Containment]
O Page 2 of 10
Idumber Title Rev./Date AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR VESSEL Rev. 0 O 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
6 Check If Reactor Head Is Full:
- a. PRZR level behavior - a. Go to Step 7.
INDICATES REACTOR VESSEL HEAD FULL
- b. Turn off PRZR heaters as necessary to stabilize RCS j pressure.
- c. Return to guideline and step in effect NOTE RCPs lA and 1B should be run to provide normal PRZR spray. ,
t 7 Try To Start At Least One RCP:
(') a. Establish the following a. If conditions can H01 be
(/ conditions prior to RCP start:
established, IllEN go to Step 10.
. PRZR level - GREATER THAN (L20)% [(L26)% FOR ,
ADVERSE CONTAINMENT]
e RCS subcooling based on '
core exit TCs - (S05) F
[(SIO) F FOR ADVERSE CONTAINMENT]
e [ Include additional AP600 ,
details in E0Ps] -
SATISFIED
- b. Start at least one RCP 8 Check PRZR Level Behavior - Go to Step 10.
INDICATES REACTOR HEAD FULL 9 Go To Step 19 O
Page 3 of 10
Number Title Rev./Date AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR VESSEL Rev. 0 5/31/95 )
1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Obtain Containment Hydrogen Concentration Measurement:
[ Include additional AP600 details in E0Ps]
CAUTION Following block of automatic Si attuation, manual 51 actuation may be required if conditions degrade.
11 Check If Low PRZR Pressure SI Can Be Blocked:
- a. PRZR pressure - LESS THAN a. Decrease PRZR pressure to (P13) PSIG less than (P13) psig using nonnal PRZR spray. If normal spray M01 available, IBEN use auxiliary spray.
- a. PRZR level - STABLE AND a. Control makeup and letdown BETWEEN 40% AND 60% as necessary.
- b. RCS pressure - STABLE b. Turn on PRZR heaters and use normal PRZR spray as necessary. If normal spray HQI available, IBEN use auxiliary spray.
- c. RCS subcooling based on core c. Dump steam as necessary.
exit TCs - GREATER THAN (S08) F [(509) F FOR ADVERSE CONTAINMENT]
- d. RCS hot leg temperatures - d. Dump steam as necessary.
STABLE O
Page 4 of 10
Number Title Rev./Date A AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR VESSEL Rev. O Q 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ,
14 Prepare Containment For Reactor Vessel Venting: ,
- a. Isolate containment:
[ Include additional AP600 details in E0Ps]
- b. Start containment air circulation equipment: i
[ Include additional AP600 details in E0Ps]
15 Determine Maximum Allowable Venting Time: ;
i
concentration - LESS THAN 3's concentration:
O IN DRY AIR
[ Include additional AP600 details in E0Ps] ,
- b. Refer to ATTACHMENT A to detennine maximum venting time j Page 5 of 10 I
humber Title Rev./Date AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR VESSEL Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Review Reactor Vessel Venting Termination Criteria:
e RCS subcooling based on core exit TCs - LESS THAN (501)'F
[(S02) F FOR ADVERSE CONTAINMENT]
-OR-PRZR level - LESS THAN (L22)%
[(L25)% FOR ADVERSE CONTAINMENT]
-OR-
. RCS pressure - DECREASES BY 200 PSI
-OR-
- Venting time - GREATER THAN MAXIMUM TIME CALCULATED IN STEP 15
-OR-
. PRZR level behavior -
INDICATES REACTOR HEAD FULL CAUTION Venting should be stopped if any venting termination criterion in Step 16 is exceeded.
17 Vent Reactor Vessel:
- a. Open both valves in one vent a. 1E either valve fails to path open in one vent path, lHEN i close both valves and open i valves in second path. ;
- b. Any venting termination b. Continue venting. WHEN any criterion - EXCEEDED venting termination criterion is exceeded, IBEN do Steps 17c, 18, 19, 20.
- c. Close all vent valves O
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Number Title Rev./Date AFR-I.3 O AP600 RESPONSE TO YOIDS IN REACTOR VESSEL Rev. 0 5/31/95 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 Check PRZR Level Behavior - Increase RCS pressure to value INDICATES REACTOR HEAD FULt. recorded in Step 12. Return to Step 10.
19 Check PRZR Level - STABLE Control makeup and letdown as necessary.
20 Return To Guideline And Step In Effect
- END - .
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l Number Title Rev./Date AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR VESSEL Rev. 0 5/31/95 ,
figure FRI3-1. HYDROGEN F10W RATE VS. RCS PRESSURE Hydrogen Flow Rate (SCFM) 6,000 i
l 5,000 :
EXAMPLE 4,000 H ONLY 3,000 2,000 h 1,000
/
' '"'J""d---
0 0 400 800 1,200 1,600 2,000 RCS PRESSURE (PSIG)
O Page 8 of 10
n Number ' i tle Rev./Date
( ) AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR VESSEL Rev. 0
\/
g i/31/95 8
ATTACHMENT A INSTRUCTIONS FOR DETERMINING VENTING TIME
- 1. Determine Containment Volume at STP = A P 492 degrees R A= (V03) x ------------ x -----_--_----------
14.7 psia T where: P (psia) = Containment pressure (psig) + 14.7 T (degrees R) = Containment temperature (degrees F) + 460
- 2. Determine Maximum Hydrogen volume that can be vented = B (3. 0?s - Containment Hydrogen Concentration) x A B= -_________-__---_______ ---_-_-_--_______-___-__ -___
100's
! )
s~~'/
- a. Check RCS pressure.
- b. Using Figure FRI3-1, read hydrogen flow rate.
- 4. Calculate maximum venting time.
B Maximum venting time = -----
C r\
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Page 9 of 10
i Number Title Rev./Date l AFR-I.3 AP600 RESPONSE TO VOIDS IN REACTOR YESSEL Rev. O I 5/31/95 l l
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FOOTNOTES I
Refer to FOOTNOTE DEFINITION Document for a description of all footnoted !
parameters used in this guideline.
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Nmber Title Rev./Date O FOOTNOTES AP600 FOOTNOTE DEFINITIONS Rev. 0 5/31/95 I
A. PURPOSE This document contains the definitions for all the footnotes used within the AP600 Emergency Response Guidelines.
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Number iltle Rev./Date FOOTNOTES AP600 FOOTNOTE DEFINITIONS Rev. 0 5/31/95 MASTER FOOTNOTE INDEX B01 Boration requirement for stuck tod C01 Tech Spec limit for natural circulation cooldown rate F01 FW flow to remove decay heat at 10 minutes F02 Minimum detectable RNS flow F03 Required feed flow for ATWS analysis F04 Minimum detectable SG feed flow F05 SFW Cow setpoint for PRHR actuation LOI CMT low level ADS actuation LO2 IRWST low-I-vel LO3 SG level above U-tubes for norrnal containment conditions LO4 SG level above U-tubes for adverse containment conditions LO5 PRZR low level setpoint for starting RCS makeup for normal containment conditions LO6 PRZR high level setpoint for stoppmg RCS makeup for normal containment conditions LO7 PRZR leveljust on span for normal containment conditions LOS Low deaerator storage tank level requiring switchover to CST LO9 PRZR level just on span for adverse contamment conditions LIO CMT fourth stage ADS actuation setpoint LIi 1RWST level for transferring RNS to containment sump L12 Hi-2 SG narrow range level Ll3 PRZR hi 'h level value for normal containment conditions Ll4 PRZR hi 'h level value for adverse containment conditions L15 Hi-2 SG narrow range level minus 5W margin for normal containment conditions Ll6 Hi-2 SG narrow range level minus 5% margin for adverse containment conditions Ll7 PRZR level for CMT actuation for normal containment conditions LiS PRZR no-load level value L19 SG no-load level L20 PRZR level to accommodate upper head void collapse L21 PRZR level for CMT actuation for adverse containment conditions L22 PRZR level for letdown isolation for normal containment conditions L23 PRZR low level setpoint for starting RCS makeup for adverse containment conditions L24 PRZR high level reactor trip setpoint L25 PRZR level for letdown isolation for adverse containment conditions L26 PRZR level to accommodate upper head void collapse for adverse containment conditions L27 SG nanow range level at the tmoer tap for normal containment conditions L2h SG narrow range level at the uppe tap for adverse containment conditions L29 SG wide range level just on span foi normal containment conditions L30 SG wide range level just on span for adverse containment conditions L31 PRZR high level setpoint for stopping RCS makeup for adverse containment conditions L32 RCS hot leg level greater than bottom of hot legs for normal containment conditions L33 RCS hot leg level greater than bottom of hot legs for adverse containment conditions i L34 Containment water level just below flood level i L35 SG wide range level setpoint for PRHR actuation L36 SG narrow range level setpoint for PRHR actuation L37 PRZR post-trip no-load mmimum level setpoint for starting RCS makeup j L38 PRZR post-trip no-load maximum level for stopping RCS makeup Page 2 of 4 l
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Number Title Rev./Date FOOTNOTES AP600 FOOTNOTE DEFINITIONS Rev. 0 ,
( 5/31/95 Pol Containment PCS actuation pressure P02 PRZR spray valve closure setpoint P03 RNS shutoff head pressure for normal containment conditions PO4 RNS shutoff head pressure for adverse containment conditions POS Normal SG PORV controller setpoint just below safety valve setpoint ;
P06 PRZR permissive to allow block of S1 P07 Minimum RCS pressure to run RCPs P08 Normal RNS cut-in pressure for RCS cooling for normal containment conditions ,
P09 Normal RNS cut-in pressure for RCS cooling for adverse containment conditions PIO Containment pressure to terminate PCS Pl1 Low PRZR pressure Si setpoint .
P12 PRZR normal operating pressure Pl3 PRZR permissive to allow block of Si minus 50 psi Pl4 PRZR pressure at which SI unblocks P15 SG pressure prior to accumulator nitrogen injection P16 Saturation pressure, corresponding to full power RCS hot leg temperature for normal ;
contamment conditions Pl7 Saturation pressure corresponding to full power RCS hot leg temperature for adverse containment conditions Pl8 SG pressure for highest steamline safety valve P19 SG pressure for lowest steamline safety valve P20 Shutoff head pressure of condensate pumps P21 Containment design pressure P22 Containment pressure indicative of an underpressure concern ROI Containment ventilation radiation isolation setpoint R02 Containment High-2 radiation isolation setpoint -
l S01 Minimum RCS subcooling for normal containment conditions SO2 Minimum RCS subcooling for adverse containment conditions S03 Minimum RCS subcoolin for normal containment conditions plus 10*F margin .
SO4 Minimum RCS subcoolin for adverse containment conditions plus 10*F margin SOS RCS subcooling to accommodate upper head void collapse for normal containment conditions l S06 RCS subcooling requirements for RCS depressurization without all CRDM fans '
S07 RCS sutrooling requirements for RCS depressurization with all CRDM fans S08 Minimum RCS subcoolin for normal containment conditions plus 50*F margin SO9 Minimum RCS subcoolin for adverse containment conditions plus 50*F margin S10 RCS subcooling to accommodate upper head void collapse for adverse containment conditions Page 3 of 4 l
Number Title Rev./Date FOOTNOTES AP600 FOOTNOTE DEFINITIONS Rev. 0 5/31/95 T01 Time delay for second stage ADS actuation T02 Time delay for third stage ADS actuation T03 liigh containment temperature T04 No-load RCS temperature TO5 Hot leg saturation temperature to minimize nitrogen injection once accumulators empty T06 Normal RiiR cut-in temperature for normal containment conditions T07 Normal R11R cut-in temperature for adverse containment conditions TOS RCS low average temperature T09 Maximum cooldown rate for natural circulation cooldown T10 Saturation temperature of lowest steamline safety valve for normal containment conditions Tl1 Saturation temperature of lowest steamline safety valve for adverse containment conditions T12 Required soak time Tl3 670 F plus errors for adverse containment concitions or 700 F whichever is higher T14 Integrity curve temperature Tl T15 Inteprity curve temperature T2 T16 RCS temperature setpoint to place cold overpressure protection in sersice Tl7 RCS hot leg temperature for PRilR actuation Vol liydrogen recombiner operability limit V02 Intennediate range permissive to block source range high flux trip (P-6)
V03 Containment voleme in cubic feet V04 Bleed and feed criteria for normal containment conditions V05 Bleed and feed criteria for adverse containment conditions
-END-O Page 4 of 4