ML100470564
| ML100470564 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/02/2010 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML100470564 (385) | |
Text
{{#Wiki_filter:Appendix D 0 Scenario Outline Form ES-D-1 2009 NRC EXAMINATION Facility: Catawba Nuclear Station Scenario No.: 1 Op-Test No.: 20090-1 2009 D-1 SNAP 141 Examiners: Operators:
- Unit 1 is recovering from a reactor trip 2 days ago
- Conditioned power level is 100%
- EFPD is 252-5 days
- Boron Concentration is 1929 ppm
- Your crew has stabilized the plant in Mode 2 at 1 x 10-88 amps and critical data gathering has been completed
- IA/61 00 001 (Controlling Procedure for Unit Startup), Enclosure 4.1, Unit Startup is in OP/1 IN61 progress and has been completed through step 2.166
- Increase power to 1% per OP/1/A/61 OP/1/N61 001001 Event Malf. No. Event Event No. Type* Description 1 RO R Increase power to 1%
2 RO I IIR N35 Loss of high voltage failure/re-zero failurelre-zero SUR SRO TS 3 BOP C KC pump 1B2 trips, 1B1 will not start SRO TS 4 BOP C Loss of offsite power to 1B essential trainl 1RN-292B fails to open SRO TS 5 BOP C NC system leak (DeS) SRO TS 6 RO C Loss of normal feed to S/Gs I 1A CA pump fails to autostart 7 ALL M Steam line break on 1A S/G Additional Failures 1BB-56A fails to auto close 1A NO ND pump fails to autostart
*(N)ormal, (R )eactivity, (R)eactivity, (I)nstrument, (C)omponent, (C)om ponent, (M)ajor
SIMULATOR SETUP Reset to 10-8 amps BOL snap Roll Charts Clear EHC alarm and any OACI 1.47 bypass alarms Sign off OP/1/A/61 OP/1 IA/61 001001 enclosure 4.1 thru step 2.166 (students start at 2.167) MALFUNCTIONS, REMOTES, and OVERRIDES Malfunction # Description Value Event Ramp Delay Trigger ANN-AD11-B03 TRANSFORMER A TROUBLE ON ANN-AD11-E03 TRANSFORMER B TROUBLE ON LOA-CA015 CA66B - CA PMP #1 DISCH TO S/G A 0 22 120 300 ISOL VLV LOA-NV078 SEAL WATER LOW FLOW LCL ACKN 21 180 REFLASH ACK (AD7,C4) MAL-CA004A FAILURE OF CA PUMP A TO START AUTO MAL-DG007B DIG 1B OUTPUT BREAKER FAILURE OPEN MAL-ENB009A LOSS OF IIR CH 35 HI VOL T 2 MAL-NC013B NC COLD LEG BLEAK 0.22 5 MAL-ND001A ND PUMP A FAILURE AUTO MAL-SM008A STM LINE BRK OUTSIDE 4.125E6 7 CO NTAINMENT LOOP A CONTAINMENT OVR-EP051D ETB NORM FDR FRM ATD TRIP PB ON 4 OVR-FWP018C CFPT 1A MOP 1A1 AUTO PB OFF 6 OVR-FWP019C CFPT 1A MOP 1A2 AUTO PB OFF OVR-KC016C PMP B1 ON PB OFF OVR-KC018D PMP B2 OFF PB ON 3 VLV-RN033A RN292B DSL GEN B HTX INLET ISOL VLV FAIL AUTO ACTIONS VLV-SG007A BB56A S/G 1A1A BLDN CONT CO NT ISOL INSIDE FAIL AUTO ACTIONS
EVENT TRIGGERS (other than manual) Event Trigger I Description NONE CRITICAL TASKS (See attached documentation) E-O H - Manually start at least one low-head ECCS pump before transition out of E-O. E-O 0 - Close containment isolation valves such that at least one valve is closed on each critical phase A penetration before the end of the scenario. E-2 A - Isolate the faulted S/G before transition out of E-2. QUALITATIVE ATTRIBUTES Required Actual Total malfunctions 5-8 8 Malfunctions after EOP entry 1-2 2 Abnormal events 2-4 5 Major transients 1-2 1 entered/requiring substantive actions EOPs enteredlrequiring 1-2 2 EOP contingencies requiring substantive actions 0-2 0 Critical tasks 2-3 3 REFERENCES OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 revision 217DCS AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation System) revision 024DCS AP/1/A/5500/021 (Loss of Component Cooling) revision 036DCS AP/1/A/5500/007 (Loss of Normal Power) revision 057 AP/1/A/5500/010 AP/1 /A/5500/01 0 (Reactor Coolant Leak) revision 051 DCS AP/1/A/5500/006 (Loss of S/G Feedwater) revision 039 EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) revision 036 EP/1/A/5000/E-2 (Faulted Steam Generator Isolation) revision 012 EP/1/A/5000/ES-1.1 (Safety Injection Termination) revision 025 OTHER NOTES AND INSTRUCTIONS NOTE: The following steps are GUIDELINES. The NRC lead examiner will direct timing of events unless otherwise noted. NOTE: Any groups or individuals (IAE, Rx Grp, RP, SOC, SWM) that are called to IIR a problem or for simple notification of a problem, repeat back the information they provide unless otherwise noted. NOTE: Any operators dispatched should repeat back information provided. Call back items are listed below when necessary for the scenario.
Event 1 -Increase
- Increase power to 1 1%
This event will be entered once the crew has taken turnover and evaluated plant conditions. Anytime after a stable positive startup rate is achieved, the next event can be started. Event 2 - IfRIIR N35 Loss of high voltage failure. SRO Technical Specification Initiating Cue: 1 AD-2, C/1, N35 failed to bottom of scale 1AD-2, When AP/1/A/5500/016 AP/1/A155001016 is completed, and the SRO has completed consulting Technical Specifications, the next event can be inserted TS - 3.3.1 Item 4 Condition F Event 3 - KC pump 1B2 trips. 1B1 will not start. SRO Technical Specification Initiating Cues:
- 1AD-6, C/1 - C/4, D/1 - D/4, E/1 - E/4 and others When AP/1/A/5500/021 AP/1/A155001021 is completed and the SRO has completed consulting Technical Specifications, the next event can be inserted.
If an operator is dispatched to checkout 1A2 KC pump and breaker, after a few minutes state "nothing abnormal was noted". TS - 3.7.7 Condition A Event 4 - Loss of offsite power to 1B essential train/1 RN-292B fails to open. SRO Technical Specification Initiating Cue: Multiple electrical alarms on 1AD-11, UV status lights for 1ETB on 1SI-14 When operator is dispatched to manually open 1RN-292B, after 3 minutes call back and state "1RN-292B cannot be opened". When called by the crew to open 1EDF-F01 F and load shed 1ETB, RUN SCHEDULE Load_Shed_1 ETB.sch (under Operations folder). Call back when schedule is complete and state: "1 B DIG Load sequencer has been de-energized and 1ETB has been load shed per Enclosure 9. No lockout relay targets are picked up." When step 22 of AP/1/A/5500/007 AP/1/A155001007 case 2 is completed and the SRO has completed consulting Technical Specifications, the next event can be inserted. TS - 3.4.9 Condition B 3.8.1 Conditions A, B, D, F 3.8.9 Condition A 3.7.8 Condition A
Event S - NC system leak. SRO Technical Specification Initiating Cue: 1AD-13, Al7, F/5 When a leakage rate has been determined, and step 11 of AP/1/Al5500/010 is completed and the SRO has completed consulting Technical Specifications, the next event can be inserted. If annunciator for seal water low flow comes in and directed by the crew, insert EVENT 21. Call back when alarm is cleared and state "Seal water low flow has been locally acknowledged." TS - 3.4.13 Condition A, 3.6.4 Condition A, SLC 16.7-9 Condition A,B Event 6 - Loss of normal feed to S/Gs/1A CA pump fails to autostart Initiating cue: 1AD-1 Al6 and 1AD-5 Al1, Al4 When step 5 of AP/1/Al5500/006 AP/11A15500/006 is read, the next event should be inserted. This will begin the major event. Event 7 - Steam line break on 1A S/G Initiating cue: 1AD-3, 1AD-3, Al1 This is the major event. Additional failures
- 1BB-56A fails to auto close
- 1A ND pump fails to autostart In E-2 Step 7.c.3) RNO, when dispatched to close 1 1CA-66B, CA-66B, insert EVENT 22.
Call back when 1CA-668 is closed and state "1CA-668 is closed." In E-2, Step1 O.c if asked to sample S/Gs for activity state "I will sample Unit 1 S/Gs for activity Step10.c and report the results back in about an hour." In E-2, Step 1O.c if asked to frisk cation columns for activity state "I will frisk Unit 1 cation columns for activity and report back the results in a few minutes. Call back in S minutes and state "Unit 1 cation columns indicate no abnormal activity." Scenario End Point ANYTIME AFTER NV SII FLOWPATH IS ISOLATED PER STEP 9 of EP/1/S000/ES-1.1.
CREW INFORMATION
- Unit 1 is recovering from a reactor trip 2 days ago
- Conditioned power level is 100%
- EFPD is 25 days
- Boron Concentration is 1929 ppm 8
- Your crew has stabilized the plant in Mode 2 at 1 x 10-8 amps and critical data gathering has been completed
- OP/1/A/61 OP/1/Al6100 00 001 (Controlling Procedure for Unit Startup), Enclosure 4.1, Unit Startup is in progress and has been completed through step 2.166
- Increase power to 1% per OP/1/A/61 001001 OP/1/Al61 00/001
Duke Energy Procedure No. Catawba Nuclear Station OP/I/N6 100100 1 OP/I/A/61001001 Revision No. Controlling Procedure For Unit Startup 217 Des Electronic Reference No. Continuous Use CNOO5FK3 CN005FK3 CD
OP!l/A/6100/001 Page 2 of7 Controlling Procedure For Unit Startup
- 1. Purpose 1.1 To outline the steps necessary to take the plant from cold shutdown to 15% full power.
1.2 To provide a procedure for startup from any shutdown condition.
- 2. Limits and Precautions 2.1 This procedure is Reactivity Management related because it controls activities that can affect core reactivity by changing boron concentration, temperature, steam flow, and power level. (R.M.)
2.2 The following Limits and Precautions are Reactivity Management related: (R.M.) 2.2.1 2.2.2 Overlap between the source and intermediate ranges and between intermediate and the power ranges shall NOT be less than 1 decade. 2.2.3 During Modes 1 & & 2 and prior to diluting for ECB, the PZR boron concentration shall be within +/- 50 ppm of the NC System boron concentration. During Modes 3, 4,5,6, 4, 5, 6, or No Mode, PZR boron concentration is NOT required to be maintained relative to the NC System provided the following conditions are met:
- PZR outflow can be verified
- NC System boron concentration> 100 ppm over the required r-equired SDM 2.2.4 With the reactor critical at low power, steam withdrawal from the S/Gs may be used only for auxiliary uses (i.e., warm steam lines, operate air ejectors, supply gland steam, some turbine warming) or for controlling heatup rate via the steam dumping system. Use caution to ensure the steam drain is slow.
2.2.5 Ensure reactivity management guidance outlined in SOMP 01-02 (Reactivity Management) is followed during reactor startup and power operation.
A*[[*****P*R*E*\lf5*0**~~f*st*E*P-§-**wr[L ALL PREVIOUS STEPS WILL BE BE SIGNED OFF AND ARE NOT Enclosure 4.1 INCLUDED HERE. OP/IIA161 001001 OP/I/A/61001001 Unit Startup Page 50 of66 2.166 Ensure Steps 2.137 - 2.139 have been completed to ensure automatic steam dump control has been established. N e);rE: 1. ~()l1ttQl~g,9::wiJli,gl"a~~l~~~;liI!1lTN O:r~~ceed'th~)erffpqJ.:iITYfod;.~ithdtawaJ lirij'lt~isp'~~lfJce<I. in:'u:ii11[Pll,~1IE;;P}~,'~egtm~g,l:a~
- 3. ]he",thrQ:J]lijJ,g pr!It,\~AlliQyp4~~:reg¥alve;i.l;tffep~the othyrS4lli:bMPI!"~§:tte;g,valves.
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~~b§i~feabgX~.llie*:.})OAH:dti~:tQlai?Osi,fi1}l~.:,l£1mQ~~:R~I¢i'if\) UJ1it'Pn:~2R;*P{It);"
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.~~,; FheA~pprQ~Slhirig:;tlie PO~H, as~tllip fat~I<lf~'~Q:i.tdpffiis rec()mmfip'Cle4Wi12j.~}
r~corij'rij'.end~!tha(llil,s rat~NOT~beex~~Q~'Qlil1til,thetiifljirie* i~ip1aceg ori~lhi~1l~~sqr:vtr:
- QJ -02);~c{Rl£1~)
Will pull rods to have a positive stable S/U raTel rate - - 2.167 2.167~r~l;tse,~@act9~~Ow~fl~o l%~ (R*M*) Per L&P 0.5 is limit. See L&P. I _ _ 2.168 Begin reviewing the items listed in Step 2.176 so that Unit 1 will NOT enter Mode 1 until all substeps of2.176 are signed off. - - 2.169 IF necessary, continue heatup to no load T T-AVG
-AVG (S57°F).
(557°F). - - 2.170 Increase S/G b10wdown blowdown flowrate as recommended by Secondary Chemistry for S/G chemistry control and within guidelines ofOP/l/A/62501008 ofOPIlIAl62501008 (Steam Generator Blowdown). (R.M.) Person making recommendation recommendation'---_ _ _ _ _ _ _ _ _ __ _ _ 2.171 Coordinate with Chemistry to determine when blowdown b10wdown flowrate can be subsequently reduced.
Initiating Cue: 1AD-2, C/1, N35 failed to bottom of scale
CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/A155001016 1 of 14 Rev 24 DC~ A. Purpose
- To verify the proper response in the event of a nuclear instrumentation malfunction.
B. Symptoms Case I. Source Range Malfunction
- Indication lost or erratic
- 1AD-2, D/1 "SIR HI VOLTAGE FAILURE" - LIT
- 1AD-2, D/3 "SIR HI FLUX LEVEL AT SHUTDOWN" - LIT
- 1AD-2, D/4 "SIR HI FLUX LEVEL AT SHUTDOWN" - LIT.
Case II. Audio Count Rate Malfunction
- Audible count rate lost.
Case III. Intermediate Range Malfunction
- Indi¢c}tion IRS! or ett.3'tic
**llJqi'~~ti&lJ!il@§t.*&r~,{it~ll~
lIlJ
.~*1~~,tgi~l:,IIIlil~lI1i!IlY'P[]1fi~§i&;l~:lIl1§!!n[]!'Wi 1AR"2,G/1"IlRhIJWOLTI-iGE q:~IEURl;":"
- 1AD-2, C/2 "I/R COMPENSATING VOLTAGE FAILURE" - LIT
- 1AD-2, C/3 "I/R "IIR HI FLUX LEVEL ROD STOP" - LIT
- SIR failure to re-energize during shutdown.
Case IV. Power Range Malfunction
- Indication lost or erratic
- 1AD-2, Al1 "P/R HI NEUTRON FLUX RATE ALERT" - LIT
- 1AD-2, Al2 "P/R HI NEUTRON FLUX LO SETPOINT ALERT" - LIT
- 1AD-2, Al3 "P/R HI NEUTRON FLUX HI SETPOINT ALERT" - LIT
- 1AD-2, 8/3 "COMPARATOR P/R CHANNEL DEVIATION" - LIT
- 1AD-2, 8/5 "P/R HI VOLTAGE FAILURE" - LIT
- 1AD-2, E/8 "OVER POWER ROD STOP" - LIT
CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/A/5500/016 8 of 14 Case III DC~ Rev 24 OCt Intermediate Range Malfunction ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED c. C. Operator Actions
- 1. Vefiff0teact9r;i*p()~~t:~I?~B5~1UEB'TI1AN
- 10%.
~ Will insert rods to achieve a SUR of 0
_ Adjust turbine load to maintain T-Avg at T-Ref.
- 3. i'U;I@:IUm[a:I~,ul~I]~U~,'slJi!~~ll:ij
~ldeJ1tiffflffe,j:;t~~jVRcbann~I;;
I~_ .>f\r~Q,q R0 .'iliII'i\lg:35' OR
- N-36.
4 ~~~IJ~i~ff~~g91~1~~gt~~~:r:~IIIR~ililllI1U!~:1 4..,6Jtheaffect~q Il~;idtaW~t~i!pgt!~lnth:g: lillg~!,!'lg'; f6l1QWing: _ f:=tI1!I~c$ll!i!~i"I,.§'liEljjifRI P::'$Witchl~~i
@ffeqt~qchEIn:hel' i\1BYRASS"f b~ Verififh~':'LE\fE":lJil,F1~X!?'&§S~' Hgpt Q:D . t~e.aff¢ct~g"UfV:J'[§Wiji:i~l!)~rj.:
RO I _ 0. yeriff'AD-2,Cf4;'~:Nn:§;XiSIAlR;2~,11R T.~IP {t;3YP~§S" -:LIJ. I
CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/A/SSOOI016 AP/1/N55001016 9 of 14 Case III Rev 24 DC~ Intermediate Range Malfunction ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8. 9 .'oelerIX!H1~<al1,d,¢orre9ts¢aP"§~tt>f1W~! malfUnclion;' 1O.§jh,sure ~olX!pl!<!\j1£:e:will:J};J~ch
- 10. SR~C 3.3;1 ITEM 4 Condition F (Reactor Trip§t~tetn (RI§)
Instrumentati~fin:
- 11. pmlflll'_lIi._fj,~
11.Qet~rlX!iQe' reqqit~~hotifiqk:ltiorn~: __*fI:!IIB It;'REFER. ....,~. . TOij.!i:(Q/AlSOOQ/001, one INone
~41III
( Classificatidb'91Emer:9?ncy) _ ~) REFER TO:RI7/0/~/SQQP1(t1~::KI'flIi@;' N()tifi<.:qtiohRequir~roqgJs ).
- 12. NQtiMJi~~~tgr,~f9Up:Fngil1~~f()f
.occ(Jrr~i1ce:
O~UJTION Inst1:lJlingJ1Bfqsesl::~i,~blianyP/iji;ch~j1n~11~D9pe~a~I~R'§f in 'a.lrippe(f;
- cqrrtf!Ji9n';;:tn~ytesmt~nr a'reactor!trip ;'Qn,P/R,,~tgt!rtfip dll~:ito', voltag~r
$pi~~~.:
- 13. WHENJh~;~ff~:Cted Ilij;~haQn~Hi~
ir~pairedr~mHENen~urejj;IA§;t:~tqrn~;;ttie
~liann~l to ~'eOlic~}i ENe!:
Initiating Cues: 1AO-6, C/1 - C/4, 0/1 - 0/4, E/1 - E/4 1AO-20, Al1 and 1AO-21, Al1 and others
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A/5500/021 AP/1/N55001021 1 of 39 Rev 36 DC~ A. Purpose
- To verify proper response in the event of a loss of Component Cooling.
B. Symptoms
- 1AD-10, Al1 "KC SURGE TANK A LO-LO LEVEL" - LIT
- 1AD-10, Al2 "KC SURGE TANK B LO-LO LEVEL" - LIT
- 1AD-9, FI5 F/5 "KC TRAIN A SINGLE PUMP RUNOUT" - LIT
- 1AD-9, F/6 "KC TRAIN B SINGLE PUMP RUNOUT" - LIT
- 1AD-9, F/7 "KC TRAIN A TWO PUMP RUNOUT" - LIT
- FIB "KC TRAIN B TWO PUMP RUNOUT" - LIT 1AD-9, F/8
- High temperature alarms on components supplied by KC System.
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/N55001021 2 of 39 DC~ Rev 36 DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions BOP DOES THIS PROCEDURE C~llJ.mIC1l~f
.CJS:llJfTION\F::iillit~ to. re§lQre tiQ;putDP .
jlThi!i:~illif:C~,~~Cll§J~2C~lli~\I!'RYmB;;(§~::t!.S~~[i,lIg!i~ii!1(1Ulll~m,ml1gaEi1i~ijl(5g2I1Hgl!~Ci~~
~eal~~()oli:Qg¥jq;;;therni~Ibar[i~rco()Ji!ig :6'r::NV seal}!iij~ctio!;l'w;~JhiD\~QtDiI1uJ~§4'Wi!1 q~Y$~d~:tDage'IQ,;thE~f!JC pIlJii'tp**seals
§galliU:m~:£tign~~ittllnl~'g:imi!tiYtg~lW,i!I~ln~g'1'ii!1il:maglll:12J\tlJ1Y£';Q;A,nm'Bj§gaU~,
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'8.~tfqrmltJt~,fQII()w;Ir1,:g:
_ {!~~ Stattfiit.!e""sl ()d~ltsPpuOO:p.
- b. IF no KC pump can be started, THEN 1 B 1 KC pump will not start and the perform the following:
crew will have to start an A train pump. This will require action in _ 1) IF SII has actuated on either unit, Step 14. THEN GO TO Step 4. CAUTION YO can only supply one Unit's NV pump at a time. _ 2) Determine which unit will receive alternate NV pump cooling from YD. _ 3) IF Unit 2 selected to receive YD cooling to 2A NV pump, THEN GO TO Step 4. (RNO continued on next page)
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A155001021 APf1fAl5500f021 3 of 39 DCE Rev 36 DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (Continued)
- NV pumps may be started without regard to cooling water alignment.
- Operating NV Pump will reach high temperature conditions in approximately 15 minutes with no cooling water.
_ 4) Dispatch operator to align YD cooling to NV pump 1A. REFER TO Enclosure 4 (Alternate Cooling To NV Pump 1A). _ 5) Maximize NV pump run time. REFER TO Enclosure 7 (Maximize NV Pump Run Time). _ 6) IF AT ANY TIME an SII Sfl occurs on either unit, THEN notify dispatched operator to realign NV Pump 1A 1A cooling to normal. REFER TO Enclosure 4 (Alternate Cooling To NV Pump 1A). _ 7) GO TO Step 4.
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A/55001021 AP/1/Al5500/021 of39 4 of 39 DC~ Rev 36 DCt ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IF KC flow unavailable to letdown HX, THEN isolate letdown as follows: _ *.,1AQ;1,F/3 "lil='POl)! HX019T;L!=T'}:I1
'fEtv1P!'~A~iPARK{: a. Ensure the following valves - CLOSED:
- 1NV NV-1-1 OA (Letdn Orif 1B Otlt Cant Isol)
- 1 1NV-11A NV-11A (Letdn Orif 1C 1C Otlt Cant 1501)
Isol)
- 1NV-13A NV-13A (Letdn (Letd n Orif 1A 1A Otlt Cant Isol).
- b. Control charging to stabilize Pzr level at If LIT, will go to RNa, But will program level while maintaining seal NOT do actions because one KC injection flow.
pump will be on already.
- c. Ensure 1NV-153A (Letdn Hx Otlt 3-Way Vlv)
VI v) - ALIGNED TO VCT.
- d. Ensure 1NV-172A (3-Way Divert To VCT-RHT) - ALIGNED TO RHT.
- e. Ensure VCT makeup -IN AUTOMATIC
- f. WHEN time and manpower permit, AP/1/A/55001012 THEN REFER TO AP/1/Al5500/012 (Loss Of Charging Or Letdown).
- g. IF AT ANY TIME the following conditions exist:
- VCT level - LESS THAN 23%
- PZR level - GREATER THAN 85%
AND INCREASING. _ THEN GO TO Enclosure 8 (Rx Trip Sequence).
- h. GO TO Step 6.
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/11A155001021 AP/1/Al5500/021 50f39 5 of 39 DC~ Rev 36 DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. 'IF)~~~NY:TIME 1AD.~.z, F/:n~tLETQN: I-:I~
Ql.HL:;E[ HI TI;MP" ,L:I:n:;rHENlg~rt§~m Stepll~RNO. _ GO TO Step 8.
- 7. '!§la,fli;D~mqn,~lt~gIIR,9mRr§JIlj~§
§t~rliijUgitiob~I.KGp,~mp(§jnCis _ IF KC pump(s) damaged by fire, THEN lQ:~r:@:§:§Jl~rYjiit§?I§,gRRIMil~:nY!IiIi'J2~9§il
\tlec@;[~CitYt~:r§9PpIYi!ilI1Y '~~n9aqs' notify IAE to repair cables to pumps fR,r~ii@DJlY{.iij':;~:~bGi~~:I?
'pr~,$i@;glly.'.in:s¢tvice;y needed for recovery. REFER TO IP/11A13890/027A (Fire Damage Control IP/1/A13890/027A Procedure).
Perform the following: _ *.~1\D';?O, Al1jflKC SU),~RLylt;J~RFL~~ a. Ensure the following valves - OPEN:
~p l;-JCp~gps l~~u - DJ¥F.K
- 1KC-425A (NC Pumps Ret Hdr Cont
_ .~51AD-4i1..l'~tKQ!§)URg!iY HQg::FLOWi Isol) fO NQ;F,?,!e~~~np~1rfJPA~~1
- 1KC-3388 (NC Pumps Sup Hdr Cont Isol) 1501)
- 1KC-4248 (NC Pumps Ret Hdr Cont Isol).
(RNO continued on next page)
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A155001021 AP/1/A/55001021 60f39 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (Continued)
- b. IF AT ANY TIME any of the following conditions are met:
- Time since loss of KC - GREATER THAN 10 MINUTES OR
_
- Any NC pump trip criteria from Enclosure 1 (Foldout Page) is met THEN perform the following:
- 1) IF letdown is isolated, THEN:
a) Ensure NV pump suction aligned to FWST as follows: _ (1) 1NV-252A (NV Pumps Suct From FWST) - OPEN _ (2) 1NV-2538 (NV Pumps Suct From FWST) - OPEN _ (3) 1NV-188A (VCT Otlt Isol)- CLOSED _ (4) 1NV-1898 (VCT Otlt Isol)- CLOSED. _ b) WHEN Reactor is tripped, THEN attempt to establish and maintain a slow cooldown as required to maintain PZR level. _ 2) Ensure steam dumps - IN PRESSURE MODE. _ 3) Ensure the Reactor - TRIPPED. (RNO continued on next page)
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A/55001021 AP/1/A/5500/021 7 of 39 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (Continued)
- 4) WHEN reactor power less than 5%,
THEN perform the following: _ a) Trip all NC pumps. _ b) Ensure the normal spray valve associated with the tripped NC pump(s) - IN MANUAL AND CLOSED. _ 5) Secure any dilutions in progress.
- 6) IF the reactor trip breakers were closed, THEN perform one of the following while continuing with this procedure as time and conditions allow:
_ .* IF above P-11, THEN GO TO EP/1/A/5000/E-O (Reactor Trip Or Safety Injection). OR
- IF below P-11, THEN GO TO AP/1/A/55001005 (Reactor Trip AP/1/A/5500/005 Or Inadvertent S/I Below P-11).
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/N55001021 8 of39 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. Y~i'ify. KC~v~II~I>I~'Rj's:fpllpW;§~'
- a. 4'eri:fyfg~,fplJq,wliJgTfaifi Ai,,~~
*Il!Ql1,,;e§~~jjJial he~aer i~Qlatioh';yal\f~~1
<@I1!RNf The KC non-essential header valves can be
.1;~C-23Q!~S~(Rxe!Qg NQLl",:Ess~\ltdr' reopened when the I§'QJ) appropriate train's level switch is reset. This
- 1)~Qj3A {~1;l?lcf9~pb~~§~:R~nli;tdr should occur between Isol} 40% and 48% KC surge tank level.
*.1~~i:qgf\Jf\QgelggNQ'd~§?xl;!g:Gi IsgJ) a. WHEN OAC alarm C1 D2215 (KC Train A Low-Low Level Surge Tank Isol) is
* ' x*'*BI""*g*'*
1K*"~::~:"m,\1"il,,,<,"E;c; 1""2'1'/\ '/1VU "u <..~~~
*:*.. o*n** I::;,,'s'" R"e" t :erd'"r'"
".,-,/7,>~'B,...'*U. ~., ,.<ttJ, <: "NOT ACTUATED", THEN ensure the Is~J;n affected valve(s) are open.
- b. V~rI:fy.the fg!r,pWing!:lr9in:'i~tKC Iloi\~essent!~l heacf,eriso'~ti()nVal\lesd P~I~N: The KC non-essential header valves can be
* :1*1}(}fgg~B *. (~:.,13I.cfgiNpn;g§:§}Jqrj reopened when the
.I.son appropriate train's level switch is reset. This
- 1.KC-'18B
) ......
- d B\f:RX>BUir;"Nbrl-:l2:Ss
' ....... ",**Qt... ,.... ;,", Ret;fldt:: '",. . . ,'" ,,' should occur between I~pl) 40% and 48% KC surge tank level.
* *1I}Ctggl?{f\ti*~BldgjN6ri-:p§~ Hdt
~1~9J) b. WHEN OAC alarm C1D2214 (KC Train B Low-Low Level Surge Tank Isol) is
_ .11i~*?J~Y{f\iigIBlggINqQ2§§§*'~g,HEf9fii "NOT ACTUATED", THEN ensure the 1591). affected valve(s) are open.
- c. ;~ta~r;t adcfiJiqi'Jal~CpLlnip(s)Jls'j c. IF KC pump(s) damaged by fire, THEN
(!j~q~$~~!Y;iltb§p~ply,;gQ;Y ,KQjQJ;td$' notify IAE to repair cables to pumps fitt~s~tjJl~4'1ll.*sgt!j'~§;j needed for recovery. REFER TO IP/1/N38901027A (Fire Damage Control none will none will be be needed needed Procedure). Procedure).
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/N55001021 9 of 39 90f39 Rev 36 DC!: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1O.
- 10. ii~~ri~~u'~Q,$i!ijli~:~~n~I,L~I~I~,:QPfm'~li~~j
'\!erjfY~C sufge;tali~;jle'lel$flofJ'iJala~J
~~Ilpw~l;:
fc:)II()Ws~. _ at fMeriff*;t;)~tgill.ISJ><'~ytg~*tar5l5jH~yel§:\::50$.., a. Perform the following: 2~?tP;Ati@lfilTA~gwEtij
- 1) Dispatch operator to initiate makeup to surge tank(s) by opening the appropriate valve( s):
valve(s): _ . 1KC-107 (1A KC Surge Tank YM M/U) (AB-601, PP-59, Rm 500) OR _ . 1KC-111 1KC-111 (1B (1 B KC Surge Tank YM M/U) (AB-601, PP-59, Rm 500). _ 2) Dispatch operators to locate and isolate KC System leakage. _ 3) WHEN the affected KC surge tank(s) level is greater than or equal to 90%, THEN notify dispatched operator to secure makeup. _ 4) GO TO Step 11.
- 11. Verify at least one KC surge tank above Perform the following:
10-10 level as follows:
- a. Verify the following:
_ . 1AD-10, N1 "KC SURGE TANK A LO-LO LEVEL" - DARK _ 1) Both Unit 1 RN Essential Headers - PRESSURIZED. OR _ 2) IF only one RN Essential Header is
- 1AD-10, N2 "KC SURGE TANK B pressurized, THEN use it for surge LO-LO LEVEL" - DARK. tank makeup.
_ 3) IF AT ANY TIME the RN Essential Header being used for makeup becomes depressurized, THEN notify dispatched operator to secure makeup from RN. (RNO continued on next page)
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/11Al55001021 AP/11A155001021 10 of 39 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 11. (Continued)
Preference should be given to the surge tank with the highest stable level and available pumps.
- b. Dispatch operator to makeup to available train of KC from YM and RN.
REFER TO Enclosure 5 (Surge Tank Makeup).
- c. Dispatch operators to locate and isolate KC System leakage.
- d. Notify Chemistry of RN makeup to KC System.
- e. WHEN the KC surge tank level is above the 10-10 level setpoint, THEN:
_ 1) Ensure the KC pumps on the affected train - ON. (RNO continued on next page)
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A/55001021 AP/1/A/5500/021 11 of 39 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 11. (Continued)
The KC non-essential header valves can be reopened when the appropriate train's level switch is reset. This should occur between 40% and 48% KC surge tank level.
- 2) Open the non-essential header isolation valves for the affected train as follows:
- Train A:
- 1KC-230A (Rx Bldg Non-Ess Hdr Isol)
- 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol)
- 1KC-50A (Aux Bldg Non-Ess Hdr Isol)
- 1KC-1A (Aux Bldg Non-Ess Ret Hdr Isol).
OR
- Train B:
- 1KC-228B (Rx Bldg Non-Ess Hdr Isol)
- 1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol)
- 1KC-53B (Aux(Au x Bldg Non-Ess Hdr Isol)
- 1KC-2B (Aux(Au x Bldg Non-Ess Ret Hdr Isol).
- f. WHEN one train's non-essential header isolation valves are opened, THEN perform Steps 12 through 13.
(RNO continued on next page)
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A/55001021 AP/1/N5500/021 12 of 39 Rev 36 DC~ DCE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 11. (Continued)
_ g. GO TO Step 14.
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A1SS00/021 AP/1/A/55001021 13 of 39 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. Verify 1AD-10, Al1 "Ke SURGE TANK A Perform the following:
LO-LO LEVEL" - DARK.
- a. Ensure the following valves - CLOSED:
- 1KC-230A (Rx Bldg Non-Ess Hdr 1501)
Isol)
- 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol)
KC-50A (Aux Bldg Non-Ess Hdr
- 1KC-SOA 1501)
Isol) 1KC-1A (Aux Bldg Non-Ess Ret Hdr
- 1KC-1A Isol).
- b. Ensure both Train B KC pumps - ON.
- c. IF KC Surge Tank 1A level continues to empty, THEN:
decrease OR is empty.
- 1) Ensure the following Train B essential equipment - IN SERVICE AS NEEDED:
- NV Pump 1B
- NI Pump 1B
- NO Pump 1B ND
- NO Hx 1B ND
- CA Pump 1B
- NS Pump 1B
- KF Pump 1B.
- 2) Ensure the following Train A essential equipment - OFF:
- NV Pump 1A
- NI Pump 1A
- NO Pump 1A ND
- CA Pump 1A
- NS Pump 1A
- KF Pump 1A.
_ pumps--
- 3) Ensure both Train A KC pumps OFF.
_ 4) Locate and isolate leak on Train A essential header.
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A/55001021 AP/1/A/5500/021 14 of 39 DC~ Rev 36 DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. Verify 1AD-10, Al2 "Ke "KC SURGE TANK B Perform the following:
LO-LO LEVEL" - DARK.
- a. Ensure the following valves - CLOSED:
- 1KC-228B (Rx Bldg Non-Ess Hdr Isol)
- 1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol)
- 1KC-53B (Aux Bldg Non-Ess Hdr Isol)
- 1KC-2B (Aux Bldg Non-Ess Ret Hdr 1501).
Isol).
- b. Ensure both Train A KC pumps - ON.
- c. IF KC Surge Tank 1B level continues to decrease OR is empty, THEN:
- 1) Ensure the following Train A essential equipment - IN SERVICE AS NEEDED:
- NV Pump 1A
- NI Pump 1A
- NO Pump 1A
- NO Hx 1A
- CA Pump 1A
- NS Pump 1A
- KF Pump 1A.
- 2) Ensure the following Train B essential equipment - OFF:
- NV Pump 1B
- NIPump1B NI Pump 1B
- NO Pump 1B
- CA Pump 1B
- NS Pump 1B
- KF Pump 1B.
_ 3) Ensure both Train B KC pumps - OFF. _ 4) Locate and isolate leak on Train B essential header.
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A/5500/021 15 of 39 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED This will require a swap of the switches so A train is in TEMP mode and B train is in MINIFLOW mode
- 15. iDe,tgiin!lt~;~pdcorig(:;t ca(f~e 6fjoss'!(if t~C.;
.!§;D§!lt~lig9WRI1~D;§~'1ill~11I1D:~QRl1i;l~
16 .§nsu't~l;cQmpll~n~e Wittib~RRr::9pri~tE!
- 1n~gpl!I;§p~:§§;m:{l!,II§,~I~gl~!iI,I~li;gggl§,ggji J~cb * *~J,l~:(:;s at1p§~I~,ctg(jL,li~~l1s~~,
\~gWWi,lw'§DI§Jm;;:D;9;li!l;
,gonlnliHii~ntslMaQu~l:
TS 3.7.7 Condition A _~, SL;Q;16.9-9{J:?QratiQ!iltl'Sysf&Xf1s: ~:crrrip$J;: SqJl!gowp}, _ ::' :SI!~Ji;~q;~7~ ,Q (BQt~tion~£stem~\
... ".a:rin'lililm
- C fI.
"",9 .!;Lv"",PS)O . . . . Petal~n
. ",' .9)
*3;5;2.(c~CS;J~Operalin"*'\
"",." ..."." " ,.,.91.
*:, 3,5;~ii~(ECCS;~:$hlJt"own)
_:,0 '~,:~i!i{C()m~jnrn~J)t Spray System) _ ii ;;3,;(;5 (At;i~lialN"F:;;g@g\Nal~:ri(I:\R&'V}) (System)' _ ;~(,' (3,7':}l~1(Comp()nent~90Iing!Watet'(CCW)
,Ss*e'ln).;;
.Y,.~,,,...
None iRBI7E3'R:IIm;~,Ii~~~~iIi!J!*~lli!l:i~l~ _
- tREFERTa'R,f'I.Q1A1:§QQO/OlIm 1~,"I~§~ili~~ZigJI~tE3iiD~.r;:e!l;!l?~li (Cla$,slfit!atiq)JPf.EOie'rIje(;;cy)'
_ :~:li '~E3filE3R*'I1t';)':L~elli!l~l~g*ggZ,gi~i§;i~fim<!)
~I?R;ER Ta;l'P/O!E3,/5QQQI,013J~RO'
.*N~Ji!i~ti~111~eqYI[emen,1§)~.
- 1. III&IIWI.II*.III.III'#IgilL,I"'.,Q"IIIII.,.,.'., .*.. "*. ,.11:1"1,,!
;irst§tifi<mtlf:)tfl'meCilrerneo'fs 1
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/N5500/021 AP/1/A/5500/021 16 of 39 DC~ Rev 36 DCt ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _ .* Notify Radiation Protection that a potential unmonitored release may have occurred.
- Notify Station Management to evaluate a KC Hx to RN leak.
- 19. V~~'fy~~~,surgelflii}{s}j~veJ(~~'folloW'~;~, _ RETURN TO Step 9.
_ ** '1IIM Great'J~!5
<><>'", . ':'i11/1ari
* *.... 50P~'!
lllla'.'..,,1'.
- 20. trJilillllfl'lMgW'GlIIIII'IRiIl?'firl
_*_* Return .KC .. . .ton6[h1~11 puOOps' .mm~ operi,mfJfl. lilillill.J REFER TOPPl1 * * */~U?;~QP/OOo IIBlltrU
~~
(G9[1poqef1tCQonD9M(i§t~tjj$,~,g~eOO'!1
- Return NV Pump 1A to normal cooling as applicable. REFER TO Enclosure 4 (Alternate Cooling To NV Pump 1A).
Perform the following:
.1 A!j):t,if~@IiLg;r~N H,X
_ * .."IIB T;EMF1i:1i Q>,l,\R~i ma'0WiiltSTHI
..... a. IF letdown isolated, THEN refer to AP/1/N5500/012 (Loss Of Charging AP/1/A/5500/012 Or Letdown).
. . .H/3"~O"fHFT;;Efy1P"
_ *it .1AD-7, .WMllllllltI.1BlI -J!l'iR~i
- b. Do not continue in this procedure until Step 21 conditions are met.
CNS LOSS OF COMPONENT COOLING PAGE NO. AP/1/A/5500/021 AP/1/Al5500/021 17 of 39 DC~ Rev 36 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. En&\,It~VCT Clnc;rl~J~t~wl1 pat,b :~ligned a$
- follo~§:~i
- p. m1;tU~,sirfta to align:it9Mlii[~I.lmp,§JJqltonsto VCT~1tb¢n;perforrri~;t~:~!{gllowing1f 1)Oper;rt[le;if6UowiI19 y~!ves:
1NV-~,§J;1~:(YCT 0JIUspl)
.1 t\iV-9;:89l3(1(M9TOtltlls9i).
_*~ID
... a"'lm*. . . .
- 2) .Q!Qseth,~::itQIIQWing v?IV:~~:
_ .'h ';1NV-2j~?A (m\!:PUm2~Suct From, tfWSJl: b,: WHENt'i!\!:sllctionaligij~d tQVQjjf, THEN mgrriEmtar:i1yj)lac~1 NMf1iil~f¥j (~;"WY;?yJPi\lert1oM~T-R!j\n~!~ii~lj~
*~MQ]l~!ip:Q~itjOn*.,qn~:f;$lurf:jlifR,:;Ui~lYTzO".
- 23. D,~I!irm.ii1~*lcillglt~(Olzplantt§fatus.
RETURN TOp.tQcedurg in affect,~J
Duke Energy Procedure No. Catawba Nuclear Station 1 AP/I/A/5500/007 API IAl5500/007 Loss of Normal Power Revision No. 057 Electronic Reference No. CN005CEB Continuous Use PERFORMANCE I
- * * * * * * * *
- UNCONTROLLED FOR PRINT * * * * * * * * * *
(ISSUED) - PDF Format Initiating Cue: Multiple electrical alarms on 1AO-11, 1AD-11, UV status lights for 1ETB on 1SI-14 1SI-14
CNS LOSS OF NORMAL POWER PAGE NO. AP/1/A155001007 AP/1/N55001007 2 of 154 Revision 57 Case II. Loss of All Power to an Essential Train:
- 1ETA de-energized
** }ET6~~g¥~b~[gl~~d*
** .~Qspf(3lii:~fm'gll~1Rpera{l;'g com.poneQts sappIlEi~;frbn1,@Jf~9!~q~dsf
- Affected DIG - OFF
{.>%f1~cted:P/G bre~E~.r- Q'~~N
- Affected sequencer not loading essential loads.
Case III is normally entered from Case I or II. If both 1ETA and 1 ETB are powered 1ETB from Unit 2 and Unit 1 offsite power only is lost then Case III may be entered directly. Case III. Loss Of All 6.9KV Busses
- Case I (Loss of Normal Power to an Essential Train), Step 12
- Case II (Loss of All Power to an Essential Train), Step 22
- 1AD-11, F/4 "ZONE G LOCKOUT TRIP" - LIT
- Loss Of Switchyard
- Swgr Tie Bkrs Closed status lights (1 SI-14) - LIT
- Emergency lighting - LIT
- Numerous transformer trouble annunciators 1AD LIT
* "DRPI BONB ON EMERG POWER" (1SI-3) (1 SI-3) - LIT
- DRPI indication - DARK
- 1SA-5 failed open.
CNS LOSS OF NORMAL POWER PAGE NO. AP/1/A/5500/007 20 of 154 Case II Revision 57 Vjs$'()fAIHpovJe6Joan**.Esse.btiarW*P1Jl11~ C. Operator Actions 1.
- 2. zv~H{si~.~h~~\~~~~nti~!;,loaCls'fPowgi:~dfrq;g,
~h~'~g!z~(j;l~~j)l as'/19I1owsJ
- a. . uniri{p) - 1~.f$ERVI9~A~] a. Manually start pump(s).
EE>/
- b. *ftC~Unip(§) -JN$I~RVIQgAS b. Perform the following:
~ljJ~:~DEo..
_ 1) Manually start pump(s). _ 2) Ensure KC Hx outlet mode switches
- PROPERLY ALIGNED.
- c. c. REFER TO AP/1/A/5500/012 (Loss of Charging or Letdown).
- d. Apump'is r~quir~~'Y' .malJ,tam'*S/G
'rS,~l[f-IENj~m~rlU"" ....(tJl~rriP~*
- e. REFER TO OP/0/A/6450/011 (Control Room Area Ventilation/Chilled Water System).
- 3. _ IF CA Pump #1 is required to maintain S/G levels, THEN start CA Pump #1.
The crew should not RESET CA to
- 4. secure the CAPT. The CAPT will secure automatically when CA is RESET in step 12. Otherwise an
- 5. _overspeed condition could result if it is started later due to steam trapped in the line The D/G DIG IS running, but the output breaker will not close. Also the cooling water valve will not open DIG will be secured and the D/G eventually.
CNS LOSS OF NORMAL POWER PAGE NO. AP/1/AJ55001007 AP/1 I Al55001007 21 of 154 Case II Revision 57 Loss of All Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED RESPDNSE
- 6. p:~tLormtbef~l1owin:gi19rtfle:affected
[)/q~i
- DIG 1A:
- a. Depress and hold the DIG "OFF" pushbutton.
- b. Dispatch operator to open 1EDE-F01 F (Diesel Generator Load Sequencer Panel 1DGLSA) (AB-577, BB-46, Rm 496).
- c. WHEN 1EDE-F01 F (Diesel Generator Load Sequencer Panel 1DGLSA) is open, THEN release the DIG "OFF" pushbutton.
OR
"'@IGft~~::
_l,~;l<~tf tj:' ,Dispatch qReratd~ to opEf~) 1EQF-F01F (Dj~s~IGC?lJe(a~qi~o~a . S¢quel) Pal1~1 1DGl,(SB}{i,B-560,
~,B:'4'<. ~7?);
7. _ . REFER TO Enclosure 8 (Manual Load Shed Of 1ETA) OR
**~~ii~l~~flfrOSg~.'~9 (fi§HualCfj,:dad'
CNS LOSS OF NORMAL POWER PAGE NO. AP/1/A15500/007 AP/1/AJ5500/007 22 of 154 Case II Revision 57 Loss of All Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. _ REFER TO AP/O/AlS500/020 AP/OIAl5500/020 (Loss of Nuclear Service Water).
9. 0 .:V~tLt~~lfstafq~asf2fJ9ws:j 110.
- a. sJl-!HAsAcTUAJi~Q:t;
- ' .. , ,'"< ~', ">" c "\""""-',
a.
- b. GO TO Step 12.
CNS LOSS OF NORMAL POWER PAGE NO. AP/1/A155001007 AP/1/A/55001007 23 of 154 Case II Revision 57 Loss of All Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11.
- a. _,*i. . . . .
- b. At least one NO pump - ON. b. REFER TO AP/1/A155001019 AP/1/A/55001019 (Loss of Residual Heat Removal System).
- c. 1 1AD-11, Kl3 "4KV BIO BUS FTA AO-11, K/3 c. Perform the following:
VOLTAGE LO" - DARK. Both NO Hx Bypass valves fail closed on loss of 1LXI (1FTA). (1 FTA). 1} IF NO Pump 1A is operating in Residual Heat Removal Mode, THEN perform the following: _ a} Place the "PWR DISCON FOR OISCON fOR 1N1173A" 1NI173A" in "THROT". _ b} Throttle 1NI-173A (NO Hdr 1A To Cold Legs C&O)C&D) to stabilize NC temperature. _ c} WHEN 1AD-11, 1AO-11, K/3Kl3 "4KV BIO BUS FTA VOLTAGE LO" dark, THEN return 1NI-173A to normal alignment. 2} IF NO Pump 1B is operating in Residual Heat Removal Mode, THEN perform the following: _ a} Place the "PWR OISCON DISCON FOR fOR 1N1178B" in "THROT". 1N1178B" _ b} Throttle 1NI-178B (NO Hdr 1B To Cold Legs A&B) to stabilize NC temperature. _ c} WHEN 1AD-11, 1AO-11, K/3"4KVB/O Kl3 "4KV BIO BUS FTA VOLTAGE LO" dark, THEN return 1 NI-178B to normal alignment.
CNS LOSS OF NORMAL POWER PAGE NO. AP/1/A155001007 AP/1/A/5500/007 24 of 154 Case II Revision 57 Loss of All Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12. 13.Q4II~W:U~jGtf'Jvels;~~~JgJlsw~;' 13. _~; VEirl!ygFftgw ~t\1AjNTIilrNIN~J§lIAI?~61 a. Perform the following: S/Gt&VEL~; _ 1}
- 1) REFER TO Enclosure 16 (S/G Level Control).
_ 2} GO TO Step 14. 2) b. pl¢lion tcftake iQ,ipfG: c.
CNS LOSS OF NORMAL POWER PAGE NO. AP/1/A155001007 AP/1/A/5500/007 25 of 154 Case II Revision 57 Loss of All Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 14. To prevent overpressurizing the condenser perform the following:
- a. Dispatch operator to close the following valves:
SA-22 (Main Steam To CSAE) 1SA-22
- 1 (TB 1-594, 1M-32)
- 1SA-27 (Aux Steam To CSAE)
(TB-594, 1M-27).
- b. WHEN notified by dispatched operator that the SA supplies are closed, THEN perform the following:
_ 1) Open "COND A-B-C VAC BKR VLVS".
- 2) IF power not available to operate "COND A-B-C VAC BKRVLVS",
BKR VLVS", THEN dispatch operator to open the following valves:
- 1CM-368 (1A Main Cond Shell Vacuum Bkr) (TB-600,1 F-26)
(Ladder needed) 1CM-369 (1B
- 1CM-369 (1 B Main Cond Shell Vacuum Bkr) (TB-603, 1F-24)
(Ladder needed)
- 1CM-370 (1 C Main Cond Shell Vacuum Bkr) (TB-605, 1F-22)
(Ladder needed). _ 3) WHEN time permits, THEN dispatch operator to complete breaking condenser vacuum. REFER TO OP/1/B/63001006 OP/1/B/6300/006 (Main Vacuum). _ 4) Shutdown steam seals. REFER TO OP/1/B/63001005 OP/1/B/6300/005 (Steam Seal System).
CNS LOSS OF NORMAL POWER PAGE NO. AP/1/A/55001007 AP/1/AJ55001007 26 of 154 Case" Revision 57 Loss of All Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 15. CgntrdlJ.~h:~igibg'm~~'!~:jlB~s1'
_a;j1;'~'~1 arglqgflo~f~ssJij115; _ ;~!"'~~9jI0'tt .Ctl~~$ir9'*fC**.Yj*..as***~,~ses~~~tg\ mcmllamzt: . ~ve . rp9I§J:naQ . 16.
- a. a. Perform the following:
_ 1) Attempt to restore letdown. REFER TO AP/1/A/55001012 AP/1/AJ55001012 (Loss of Charging or Letdown). _ 2) WHEN normal letdown has been established, THEN place additional letdown orifice in service as necessary to control Pzr level. _ 3) GO TO Step 17.
- b. place! ao!f/tlQU/a'i'net(lowri 6nific ser'{i9~as q~c~S$~.toco~iroir l~vet 17.
- 18. _ REFER TO AP/OIAl5500/022 (Loss of Instrument Air).
19.
.... ' t CNS LOSS OF NORMAL POWER PAGE NO. AP/1/A155001007 AP/1/A/5500/007 27 of 154 Case" Revision 57 Loss of All Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 20. _ *~.;1*f!.~(Pr~§:s.ufiier) .T8 3.4.9 Condition B _ * ::?~t~'>~I~:;S;PlJrces -Operatiog) T8 3.8.1 Condition A, B, D, 0, and F T8 3.8.9 Condition A _ ,.e<,\3lli8i,2(~Q;I:SJ~~r~p - ShutdoWD) T8 3.7.8 Condition A _.II:tIIIBI" {bC'S1...._ _....fR,__ _ ;Slh'38 4
~;':.~. . . . ;
f )f:*>': Qg,~~~~~ 0 perq.t@J[ll~L ili,)CC _ l.3.S:P'* (D.C$(~urce?~§hqt~!:>Wri~j II. 3.6.7 . .Wili5ijMl)
'<lrivertf£(§'~'Opera~ing}i Gl)3.8.8 (l6vert~rs-:$QotdowD,)
__._I.iil . .**. .~ __ . _Dis!ribq~iQn:*~ystems~:i.~p~rating);
*~03.8.9.( * *' . .IM_81
_ ~;i\~~.::S*~1 o~{bJ;?tril)ution. Sy$te.il1~~.- s~:t)!Jt90Wljlih
- 21. Det~lTilirie:rtfiuirednotiii:catiQns:
...... c.' c* '.: q .:.:.*..~*."d.*U' .. ....<<..." ........ c .UN.*.
~: c'":-,R,:,,,E,,-F=E~R _TO_c R,~7:Qt.w5000/0~1 (qq~§ifica!iQl1;~fEmergenqy) dtRP/O~B{~09P{013 (NR~f QIi:tYB.~9'fllr~m~,nt?;).
_ WHEN time and manpower permit, THEN perform applicable portions of Case III. Case III (Loss Of All 6.9KV REFER TO Case'" Busses). 23*'t>:hn~t;~92Qt'ri~*~ in:t~.i,~pr()ced:p,l*e.Oti:til 23.
,!!j'e f()lI()winga!:~* s~ti.s'fied: rEXTEVENT INEXTEVENT
_
- The status of all lockout targets have been determined
- Station management has approved power restoration to the affected bus.
Initiating Cue: 1AD-13, All, F/5 LEAK IS approximately 30 gpm
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/Al5500/010 2 of 154 Rev 51 DC~ Case II. NC System Leak:
- Cn:Wgihg'~fJow inCl[catioo;iINCREASlfi],c.;
- 1I:zrlevel ;;;.RJ:::PRg~.f:?JN~l
- Pzr pressure - DECREASING
- Any of the following EMF indications - INCREASING OR IN ALARM:
- EMF-41 (Aux Bldg Ventilation)
- 1EMF-38 (Containment Particulate)
- 1EMF-39 (Containment Gas)
- 1EMF-46A (Component Cooling Train A)
- 1EMF-46B (Component Cooling Train B).
- Containment floor and equipment sump level(s) - INCREASING.
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/N55001010 AP/1/N5500/010 54 of 154 Case II Rev 51 DC~ NC System Leak ACTION/EXPECTED RESPONSE RESPDNSE NOT OBTAINED
RESPONSE
C. Operator Actions IBOPP DOES THESE ACTIONS
- 3. Ensure containment integrity as required:
- a. IF leak known to be in Auxiliary Building, THEN GO TO Step 4.
- b. Initiate Containment Closure.
- c. Initiate additional action as required to ensure Containment Equipment Hatch -
CLOSED.
- d. Initiate additional action as required to ensure Containment Air Locks -
CLOSED. aa..rv1aintcI!tJ,,!chC!(gihg .{lpW 'les~]hail) 180GPM~ b ,. M.*ahuall '.tt'?;~'o'ttle*******.~t~'.'V'"29A:E(NWPm'*
. ..,Y,,,SHJ( .J.~. *,m'* ., .. P .s A&I~;PA§J!!l:(jFIQ,W.91rtIJJo'*§J~bl!jtei:;Pzr:.
Je~~[' PZR level will wi" still be _ c. IF Pzr level is stable OR increasing, decreasing and the crew THEN GO TO Step 5. wi" have to reduce will (RNO continued on next page) letdown.
CNS REACTOR COOLANT LEAK PAGE NO. AP/1 /A/5500/01 0 AP/1/N55001010 55 of 154 Case II Rev 51 DCS DC~ NC System Leak ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
- d. IF'P;z(I&;~~Td~f(nii:lJll$mtq~@E~ase; THEN:
- 1) Req~~£~tdowQflowJ9 45:~PM as follows::
!I.III a) IF 1 r;;J}/:JOA (Letdo Orif;,S Otlt
=.I.I.I,..
CooIIspJ}open. THEN Jperform a) the foHQ~iJ19: . _ (1) (1) s M!=ll1lJ§lly ..cont~QJJ NVt-:'t;48 (It~R'tQlf,'r~ss y,gQtr()l)t2 e§tc3pH§J1JetdQ~Q' *1 pr~M~t:e
'!BIE+~
beNileeg';375 '-::~:(;)O
~~
~J'Uem-1lI!I 7 RS:JB'l\
h~ _ (2) 1hr9tt1e1 NV-81f9 {letdo' FI9w,VarO(it:~trl) fbXl~;Mi~ GpM ;letdoWnJfI9w. _ (3) WHEN 45GPMletQ'1Wn
-("i *
;f1ow~§tabnsheq. TBEN iadjusht~~:;l~§(.b~m:ln L Press Q9:htftol);;fQ}!)1ainJ§,{f;!,
letdown~r~ssy[~~:at 3!5QPSIG. _ (4) ,WHENIe,td6w,n pre§:§,bfe is stable~t~2:~,QPSI(2rTHEN; place tf>!~![a:'~8 (J+/-:~Jdn J:.:>tess QQ:gtt91}:iQi~~;utOi (RNO continued on next page)
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/A/5500/010 AP/1/A15500/010 56 of 154 Case II DC~ Rev 51 OCt NC System Leak ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued) b) IF 1 NV-13A (Letdn Orif 1A Otlt Cant Isol) open, THEN perform Cont the following:
_ (1) Manually control 1NV-148 (Letdn Press Control) to establish letdown pressure between 150 - 200 PSIG. _ (2) Open 1NV-11A (Letdn Orif 1C Otlt Cant Cont Isol). _ (3) Adjust 1NV-148 (Letdn Press Control) to establish letdown pressure between 375 - 400 PSIG. _ (4) Close 1NV-13A (Letdn Orif 1A Otlt Cont Cant Isol). _ 1 NV-148 (Letdn (5) Adjust 1NV-148 Press Control) to maintain letdown pressure at 350 PSIG. _ (6) WHEN letdown pressure is stable at 350 PSIG, THEN place 1 NV-148 (Letdn 1NV-148 Press Control) in auto.
- 2) IF Pzr level continues to decrease, THEN ensure the following valves closed:
- 1NV-10A (Letdn Orif 18 1B Otlt Cont Cant Isol)
- 11NV-11A NV-11A (Letdn Orif 1C Otlt Cant Cont Isol)
- 1NV-13A (Letdn Orif 1A Otlt ContCant Isol).
(RNO continued on next page)
CNS REACTOR COOLANT LEAK PAGE NO. AP/11A155001010 AP/1/A155001010 57 of 154 Case II Rev 51 DC:: NC System Leak ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
- 4) IF Pzr level continues to decrease OR cannot be maintained greater than 4%, THEN:
a) IF in Modes 1, 2, or 3 with CLAs in service, THEN perform the following: _ (1) Manually trip the reactor. _ (2) WHEN reactor trip verified, THEN manually initiate S/I. _ (3) EP/11A15000/E-O GO TO EP/1/A15000/E-O (Reactor Trip Or Safety Injection). _ b) IF in Mode 3 with CLAs isolated OR in Mode 4, THEN GO TO AP/11A155001027 AP/1/A155001027 (Shutdown LOCA). _ c) IF in Mode 5, THEN GO TO AP/1/A155001019 (Loss of AP/11A155001019 Residual Heat Removal System).
- 5. If AT;!ANYTIME;pzrD,~,<~ld~~tea$e,s in*
!~J)*~ne9ntr:Qll¢dll1qJj'fler* or~annQ.t..l)e l1latn!~iQe~igteatetJhan )4~lo~THENGO.
TOSteRj;4~i
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/N55001010 58 of 154 Case II Rev 51 DeE DC~ NC System Leak ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6.\fEff:i:ty;,pzrINC:pt~~~Y1::@<',~JIB~~QIN~ Perform the following: l;o()R§l~Bl.,l;i~IP~:§lggp; PRESSVRpi a. IF Pzr level is greater than 17%, THEN ensure Pzr heaters on as required.
- b. Ensure Pzr spray valves - CLOSED.
- c. Ensure all Pzr PORVs - CLOSED.
- d. IF any Pzr PORV is leaking or has not reseated, THEN close its associated Pzr PORV isolation valve.
- e. IF Pzr/NC pressure is decreasing in an uncontrolled manner, THEN:
- 1) IF in Mode 1, 2 or 3 with CLAs in service, THEN:
_ a) Manually initiate S/I. _ b) GO TO EP/1/N5000/E-O (Reactor Trip Or Safety Injection). _ 2) IF in Mode 3 with CLAs isolated OR in Mode 4, THEN GO TO AP/1/N55001027 (Shutdown LOCA). _ 3) IF in Mode 5, THEN GO TO AP/1/N55001019 (Loss of Residual Heat Removal System). 7 .DI§J)~lctf~PR~~i\t9~r§)~u)})~Qgte.(rt~} i~;6IateNC:§ys~~tnl~aE** 8.il§giw;Rlg'R~:II;~U(gi~!M§t§mliR§,I~tJi:tj~i
- 8. \(eritypr<;>R~rY9lY9i~Y~teffjJQPetaliJ:)ri.;
'Er@osllrJf14 (Qoritrg);
t~Ii.I?*Ii~:lmCi>!Ii!'iilg§PC:@llldl:'~~tgptlgU
;REf.ERTO
*e:p:Q,'tn,\~entil'*tibfl~ystenl:Yeriijqjitio:n)~.
111IQmll§!'itn~l~g!'i'i§Mlt@m}il@liYiltigp)~'!
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/N55001010 59 of 154 Case II Rev 51 DCl: NC System Leak ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. ifF 'Ai1*~NYTrM E 1AQ7?, ..II1.*!VCr[<J'!l-V~,~i dE~i"j~N~DiII\llB;:'Jam,~~iJ!tlllj'11&"\g;IlImj1e~IIJ' This wont happen.
#ifli!rfj;l.:~le11lis\T*t;lIiNi!.n§n:lti~ln,,~:mn;j§!~§I!,~m alatm~ll-IT, TflEN* ali,gn':~~tR,Ymg,i§ycni5m
;lgIQ~':ii~i,mj'~J!I:leUgll~;!
tQ thegW§TWa§~§llqVl~~i
- a. Open 1NV-2S2A NV-252A (NV Pumps Suct From FWST).
- b. Open 1NV-253B (NV Pumps Suet From FWST).
- c. Close 1NV-188A (VCT Otlt Isol).
- d. Close 1NV-189B (VCT (VCTOtltOtlt Isol).
- e. IF Reactor trip breakers are closed, THBN perform the following:
THEN _ 1) Continue concurrent use of this procedure for the NC leak. _ 2) Manually trip the reactor. _ 3) IF Unit was in Mode 3 below 1955 PSIG, THEN THBN GO TO AP/1/N5500/005 (Reactor Trip or AP/1/N55001005 Inadvertent S/I Below P-11). _ 4) GO TO EP/1/N5000/E-O (Reactor Trip Or Safety Injection).
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/A155001010 60 of 154 llIIr.'P Qase'111ih Rev 51 DC~
~
N~§:£~§,tf;lm Utgk ACHON/EXPECTED*RES'PONSE ;RESPONSE NOT oBlA:I NED;
- 1O.
- 10. ;Q~!~rmiJl~N""ite:~l<z@t~.Qy,:aJry;,qf{th f611Q:W.jt;i§ W~lhoa~:
_ .* _~ Cbfl1par~;charging:fI6w;~Iild * *IIII1IIID-Wi&l. letdown flg;w Leak size is approximately 30 gpm aM _*tm~.""'" aM _*.~181
* .M6iiitorOACI~9ihlC1PO.f):76(GrossN9 System Le$RI,Rl;lte, Ten Mih Run A,{9):f 11 11.. _1I,.I~JllrJilm
.E:t1~U r~p~Q.rtlPIi,:u]p~;iVfU!:tlappt9?X'~J~.)
.J~.1JQIIUiI_
tI:~~h SP~*Q~ :andf§jl~cje:~flJl~~g~~~@\ TS 3.4.13 Condition A
.CommI~m~n:tsiM~lIliin*
. . . .JEIfIR. .' TS 3.6.4 Condition AA
_......."4'........
- 3.4A RCSL<):6ps-Mod Els.;l and 2 SLC 16.7-9 Condition A, B
;~. 3.4,5.;RCSf'l3oo
.......... ". . ' . df..~ Ps::'Mode13i
_ .: ~;4.12 LbwTelj1'peratureOyerpresS!Jr~ Protection ,(LTOP) Sys;tElDl
;~~i:3'4131ft*gCS 'Q. **:erati A nafil2eaKcf* i)::
<.,I**. *....* w\' hi*. ...*.... .I;>.,,,,,,.. """':*"'* ," .. " . . * '. 9
~1 3,f4!J(~ (RCI§;lP(El§~ji!te l~olqtjpti~alR:~
m!~i\LEla,~$gEl) (~~§:§;;(Seal IIjj~dtiof:lFlow) EVENT 6 can begin here. here . _ * " 3.~,3.Gontalninent l~oI~tl9n
*_r~.1!IJMf'iE_.
- ~**;3'1li:~1:{Sed6nda
.. ',,+'.'. *h,* \ .;;"; "" . J]f
.' SI!@'?"*6.7:1'97
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,**Sh'e'ific*:Piefivrr
,.,.~ ..........
a, Y Snutc1([Wf:l.fS
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Va,!£!g$;
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7
,."".t' {l(. ....., ,,,.,, Y/.l:'
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~~M, Y'stem};:
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/A155001010 AP/1/N5500/010 143 of 154 Enclosure 14 - Page 1 of 3 Rev 51 DC~ Control Room Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. V~[ity9netraiQ91'ttlE!folloyvihg Perform the following:
eqiJi~~m~pt'§,ln]pper,I;\UQn: '
- a. Shift operating VCIYC trains. REFER
_ ~;\ t£~~~f;mJ~r} TO Enclosure 15 (Shifting Operating _ * 'CR, AlfU;;!:~,1'; VCIYC Train).
.. OW\AIiW::1 It:CRAPFT~t; b. IF no train can be properly aligned, THEN dispatch operator and IAE/Maintenance to restore at least one train of VCIYC. REFER TO the following:
OP/OIAl64501011 (Control Room _ .* OP/OIN6450/011 Ventiiation/Chilied Water Area Ventiiation/Chilled System) EM/OIAl52001001 (Troubleshooting _ .* EM/OIN5200/001 Cause For Improper Operation of VCIYC System).
- 2. Verity th~\1;pllowirigrarif:i)q)ilpiCltofs) IF chlorine odor is detected in the PA~,K::, Control Room, THEN perform the following based on the status of given
_
- ilAD":1~1~8c!2!JI:ii!JiJj)1HNTPlKE~r alarms:
QI:'iLORINE1~i!j
- a. IF detectors on both unit intakes are in
- 1AQ-,18.I?!,~~*,*UNIT .tJNTAKE;HI alarm, THEN:
.CHJ;;g;>RIN~,1 B"
- 1) Ensure the following VC intake
- 11'11\41.
l'f}"'G'0d.-. 8
' , 1J 78mllNIT*2 'INPUfiE HI'
,.Jtd":~ ',.,V c/c.c~ , ,~\¥<>, ~ dampers - CLOSED:
CIj[I!f§)RI N1=iZA".
- 1VC-58 (CRA Filt Inlet)
- 1AD-113; E/8":UNIT;2~IJS!JAKE,HI
- 1VC-6A (CRA Filt Inlet)
C/dLQR1 N§,;,2B",
- 2VC-58 (CRA Filt Inlet)
- 2VC-6A (CRA Filt Inlet).
_ 2) GO TO Step 4. (RNO continued on next page)
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/A/5500/010 AP/1/Al5500/010 144 of 154 Enclosure 14 - Page 2 of 3 Rev 51 DC~ Control Room Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. {Continued)
(Continued)
- b. IF Unit 1 intake HI chlorine detector(s) in alarm, THEN:
- 1) Ensure the following VC dampers -
CLOSED: _ . 1VC-58 (CRA Filt Inlet) _ . 1VC-6A (CRA Filt Inlet).
- 2) Ensure the following dampers -
OPEN: _ .* 2VC-58 (CRA Filt Inlet) _
- 2VC-6A (CRA Filt Inlet).
_ 3) GO TO Step 4.
- c. IF Unit 2 intake Hi chlorine detector(s) in alarm, THEN:
1)) Ensure the following VC dampers - 1 CLOSED: _ .* 2VC-58 (CRA Filt Inlet) _
- 2VC-6A (CRA Filt Inlet).
dampers -
- 2) Ensure the following dampers-OPEN:
_ . 1VC-58 (CRA Filt Inlet) _ . 1VC-6A (CRA Filt Inlet). _ 3) GO TO Step 4. _e 1~C-~I?I(Qij1\ FiJf:llnl~!}) _ .1VC*,QA{Q~Fl!Hln!~t)\ _ .2VC~pB{Qf:Rif~lHltllet) _ .'g'lQi6A{ORi::Eilt Inlet).
CNS REACTOR COOLANT LEAK PAGE NO. AP/1/N55001010 145 of 154 Enclosure 14 - Page 3 of 3 Rev 51 DC~ OC~ Control Room Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED R£SPONSENOT 4.~epeafthisenJ~,IQst.ireOhtll notifiedljpy 4.
§J~tiQnlVl~nage,:mtmt as follQws:
°li il: Anytil:heV~!yCr~I~t~g2iftlhlJ,rj~i~tbrs 1AO':18act:qale.
oe;:
1AO-1 Al6 Initiating cue: 1AD-1 A/6 and 1AD-5 1AO-5 Al1, A/1, Al4 A/4
CNS LOSS OF S/G FEEDWATER PAGE NO. AP/11N55001006 AP/1/N55001006 1 of 20 Rev 40 DC~ A. Purpose
- To verify proper response to a loss of feedwater supply to the S/Gs.
- To verify proper response to a loss of normal supply of auxiliary feedwater.
B. ~mptoms Symptoms CasEf"I.Lq§gPf:;q= Su ppIYT9~S/Gs!:<
* ,cfBT AandB~:~;rtRI<P:PEDi
- 1AD-3, C/6 "CF ISOL TRN A" - LIT
- 1AD-3, D/6 "CF ISOL TRN B" - LIT
- Any S/G 10 level alert alarm on 1AD LIT
- Any S/G flow mismatch 10 CF flow alarm on 1AD LIT.
Case II. Loss Of Normal CA Supply:
- Any CA Auto Start
- 1AD-5, H/4 "CACST LO LEVEL" - LIT
- 1AD-8, B/1 "UST LO LEVEL" - LIT.
CNS LOSS OF S/G FEEDWATER PAGE NO. AP/11A155001006 AP/1/A/55001006 2 of20 2of20 Case I DC~ Rev 40 DCl: Loss of CF Supply To S/Gs ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. QRerator QQerator Actions
-0 yerifY!lr~ctctO[:;p:OVler;;4E§S TH~N 5%~. IF AT ANY TIME all CF supply to S/G(s) lost, THEN perform the following:
IRO
- a. Manually trip reactor.
- b. GO TO EP/11A15000/E-0 EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection).
IRO J 2*v:gftifY~Jt~fG'tlElJilev~lci'e:g"flllJtiP§ IF 214 S/G N/R levels on anyone S/G are Ul(,ID::~4Jt;;:DARK;; greater than 83%, THEN:
- a. Verify all Feedwater Isolation status lights (1SI-5) - LIT.
- b. IF any Feedwater Isolation status light is not lit, THEN:
_ 1) Manually initiate Feedwater Isolation. _ 2) IF proper status light indication is not obtained, THEN manually close affected valve(s). 3**i{~j~i~llgliJ,Il!~lllgr1lllf'~B§II:J~Bjl:mIN}
- 3. Ve[ifY.;t()tal?;~A fIQ"",,¥GREATER .ItlAN 4~OGPJ\llt:
',§jg:i~Rml'
,{5,';:' ManUaUyangJr;GAyglve(s~}t:is:lrequir~gj toesta~!i$b:'I~£V::i CAPT #1 should have been secured already and 1A CA pump feeds AlB S/Gs since B train has no 1B CA pump feeds C/D S/Gs power and A CA pump CAPT feeds all S/Gs autostart is failed, they will start A CA manually.
CNS LOSS OF S/G FEEDWATER PAGE NO. AP/1/A155001006 AP/1/A/55001006 30f20 3 of 20 Case I Rev 40 DC~ Loss of CF Supply To S/Gs ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. II1II. . . . . . . .,1_
_ fa';; 6l~""'RA1III _ B ~V§t!fY~lI:i:$IG NfRley~t~!;:- GRI;~llI~B; a. Maintain total feed flow greater than _fL li~~N,* ** 11;1;%' 450 GPM to intact S/Gs until at least one S/G N/R level greater than 11 %. _ b.1 ,WHEN at 1~~~~rb~rie"§(G; ~Leil~,v,elis gteqter tt:lar11~'.1 %,THENIt[[<;!m~feeQ
,flbW to,mairitai(:l~;c!1I~9f;GiN1R l~yels tQetwee:[]
- 11;°{qI'i&n°4;~r
- 5. MAJOR EVENT WILL BE INSERTED WHEN THIS STEP IS READ
- 6. Ensure compliance with appropriate Tech Specs and SLCs:
- 3.3.2 (ESFAS Instrumentation)
- 3.7.5 (Auxiliary Feedwater System)
- SLC 16-7.1 (AMSAC).
- 7. Determine required notifications:
- REFER TO RP/O/A/50001001 RP/0IAl50001001 (Classification Of Emergency)
RP/0/B/50001013 (NRC
- REFER TO RP/O/S/50001013 Notification Requirements).
- 8. Determine and correct cause of loss of CF supply.
- 9. Verify at least one CF Pump* Pump - ON. _ Perform a hot restart of one CF Pump.
REFER TO OP/1/A16250/001 OP/lIAl6250/001 (Condensate and Feedwater System).
MAJOR EVENT START Initiating cue: 1AD-3, AJ1
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1 I A/SOOO/E-O EP/1/A/5000/E-O 1 of 61 DC~ Rev 36 DCE A. Purpose This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of all Reactor Trips and 5/1 above P-11, valid 5/1 below P-11 and to assess plant conditions, and to identify the appropriate recovery procedure.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-0 2 of61 of 61 DC~ Rev 36 DeE B. Symptoms or Entry Conditions
- 1. The following conditions are symptoms that require a Reactor Trip:
- 1 of 2 SIR channels - GREATER THAN 105 CPS WHILE BELOW P-6
- 1 of 2 IIR channels - GREATER THAN 25% FULL POWER AMPS EQUIVALENT WHILE BELOW P-10
- 2 of 4 P/R channels - GREATER THAN 25% FULL POWER WHILE BELOW P-10
- 2 of 4 P/R channels - GREATER THAN 109% FULL POWER
- 2 of 4 P/R channels - +5% FULL POWER IN 2 SECONDS
- 2 of 4 loop LlTs OPLlT SETPOINT ilTs - GREATER THAN THE OPilT
- 2 of 4 loop LlTs ilTs - GREATER THAN THE OTilT OTLlT SETPOINT
- 2 of 4 Pzr pressure channels - GREATER THAN 2385 PSIG
- 2 of 4 Pzr pressure channels - LESS THAN 1945 PSIG WHILE ABOVE P-7
- 2 of 3 Pzr level channels - GREATER THAN 92% WHILE ABOVE P-7
- 2 of 4 S/G N/R level channels on 1 of 4 S/Gs - LESS THAN LO-LO SETPOINT
- 2 of 4 NC pump buses - LESS THAN 77% OF NORMAL VOLTAGE (5082 VOLTS) WHILE ABOVE P-7
- 2 of 4 NC pump buses - LESS THAN 56 HERTZ WHILE ABOVE P-7
- 2 of 3 NC flow channels on 2 of 4 NC loops - LESS THAN 90% OF LOOP MINIMUM MEASURED FLOW WHILE ABOVE P-7 AND BELOW P-8
- 2 of 3 NC flow channels on 1 of 4 NC loops - LESS THAN 90% OF LOOP MINIMUM MEASURED FLOW WHILE ABOVE P-8
- 4 of 4 turbine stop valves - CLOSED WHILE ABOVE P-9
- 2 of 4 turbine stop valves EHC pressure - LESS THAN 550 PSIG WHILE ABOVE P-9
- 1 of 2 SII trains - ACTUATED
- 2 of 2 SSPS trains - GENERAL WARNING ALARM.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/A15000/E-O 3 of 61 30f61 DeS Rev 36 DC!:
- 2. The following are symptoms of a Reactor Trip:
- Any Reactor Trip annunciator - LIT
- Neutron level - RAPIDLY DECREASING
- Rod bottom lights - LIT.
- 3. The following are symptoms that require a Reactor Trip and SII:
5":
- 2 of 4 Pzr pressure channels - LESS THAN 1845 PSIG
- 2 of 3 containment pressure channels - GREATER THAN 1.2 PSIG.
- 4. 5/1:
The following are symptoms of a Reactor Trip and S/I:
- Any SII Reactor Trip annunciator - LIT
- NV, NI, and ND pumps - ON
* "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT
- E/S EIS Load Sequencer Actuated status lights (1SI-14) - LIT.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O 40f61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- c. Operator Actions C. RO DOES THIS PAGE 0:~erifY,Re,~cfO~TriP: Perform the following:
_~h All r()q!QQtt()!l!J';light~l:~LlI a. Manually trip r.eactor. reactor. _ .t\J1 re~~1Qr~,trip'~'QO Q~RaSSjd2JeakttCs b. IF reactor will not trip, THEN
;QPEN" concu rrently:
concurrently: _
- fLR arii'g:~~FP§)~:ESE.f\,§JJ2J:G) EP/1/A/5000/F-O (Critical
- Implement EP/1/A/SOOO/F-O Safety Function Status Trees) .
- GO TO EP/1/A/5000/FR-S.1 EP/1/A/SOOO/FR-S.1 (Response To Nuclear Power Generation/ATWS).
o _
\TeriM~urbi!1~Trip;j
*5H:JLJr~I!i\~,;~!Op~¥,gIY§§:;:~P!1Q§f2[t Perform the following:
- a. Manually trip the turbine.
- b. IF turbine will not trip, THEN:
_ 1) Depress the "MANUAL" pushbutton on the turbine control panel. _ 2) Rapidly unload turbine by simultaneously depressing the "CONTROL VALVE LOWER" and "FAST RATE" pushbuttons.
- 3) IF turbine will not runback, THEN close:
- All MSIVs
_
- All MSIV bypass valves.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/A15000/E-O 50f61 Rev 36 DC:: I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED -0 Verify 1I;JAl~'tltF1e'i['B -E,NERGI~sp* _0Sl~nifY?,I~'mllIDi;t:i;§rniall:E~,I:ERml£§~l i?eriorm fh~l121@tt"'mg;:1 R~II:~m'~~~ltIUIW;mg~;l BOP DOES ILlV" LI,V'ES THIS PAGE a. IF 1ETA AND 1ETB are de-energized, THEN GO TO EP/1/A15000/ECA-O.O EP/1/A/5000/ECA-O.O 1ETB is NOT (Loss Of All AC Power). energized
- b. WHEN time(!!I¢ws,~THEN!fattempt to; t~stot~"Pdwe'"rnQ:.:Qe!!!~rt~:rgi,2I~J1f, s,Witct)fH~~rwQil~lgo:lilJihqii;)~rWith.tl1i,s
;p(ocedt.lt@:REF:ER{:!fo.
API11~l2!5PO/OQ["(1:.9~s'gl'f>l(mnal\
""XX "P",ower)\;:'
o
@Sl,g[ifY§r,ilj!n~!!!!!\@,§I\ii,~fgli;tI'.
Verify Sll;is1ii4f(j~~gp:
~fil=lr=:~i~'~i{~~~i~i'liE~mu,~!li'l
- a. "SAij:ETY1tbJ~J:[~il110N'~CTUA:TED" a. Perform the following:
- a. stat4:~I:lig hti(~S11,;i3 }~~LIT.
- 1) Verify conditions requiring S/I:
1} _ . Pzr pressure - LESS THAN 1845 PSIG OR _
- Containment pressure -
GREATER THAN 1.2 PSIG. _ 2) 2} IF S/I is required, THEN manually initiate S/I.
- 3) IF S/I is not required, THEN 3}
concu rrently: concurrently:
- Implement EP/1/A15000/F-O EP/1/A/5000/F-O (Critical Safety Function Status Trees) .
- GO TO EP/1/A15000/ES-O.1 EP/1/A/5000/ES-O.1 (Reactor Trip Response).
- b. Bqth;;g~§J't~?Q;$;~q Y$'r:!cerCl9tJl~ted b. Manually initiate S/I.
stal4~( JJgl1ts;~U~!~1~1:~J,3:,I;[F;2 They may choose to manually initiate S/I but the B sequencer breaker was opened previously and this step will not accomplish anything.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/N5000/E-O EP/1/N5000/E-0 6 of 61 60f61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED lmi~l~l1mlii~II,ell(!iiCg(JillqliJi:~~IIgii:§~:! 7..~~telInirtefEfguiied)notifi~Clti6ri§::
~,f RERERTO.R!?!QIA'1:S000/~D,~i RIZ&lI3R;illi@;li!i%¥llm~lli¥lllllll;!lli~ii i~gl~§~:iIi~~!i~%lJilllf;lf:;p!!i!llEitg§ii~'S!~r i,(Classitig~tidJi'~fEn;i~rg~ny~g' Perform the following:
- a. Manually initiate Feedwater Isolation.
- b. IF proper status light indication is not obtained, THEN manually close valves.
1 IBOP 1 99. jl~r:!IliliJj~§gll!i:Qgiila'J1mg,iill~§RI~ligiii
;ye~if¥lij,h~§E(~ C9Ptainm~l1tls:Qlatio')j 1(§\t~U![~l!:~liiJgJJ,g~§;~
*stC,lt!l~:i~~;,fo"UQW~.~1
- a. 'P5a~etit~.'l~gS;!=jT"lights\;"Q481S~* _ a. Manually initiate Phase A Isolation.
- b. MOrlitqrJjgJilr~a l1el*~t6IiR;lPptfli~l!lts'*,;; 'pi' tJV)~I}])~IIY~IgQ}f¥~ly~§li}
LII.; ICRITICAL TASK I 1BB-56A has failed to close and B train BB valve is not closed
- 10. tl~li,fllptgp~DiiBaa~§j'~;lag[gat[Q'iim§;
(\lce,ItlY~prQP~fiPb{t$~4BCl,c;U.atiQn,iClS} due to loss of power, so there is IBOP I folloWs: ifCl!lq~§:; a direct path from containment. a;c Cont9il1meQ~'ipres~:~u~t:.:t;I~Q a. Perform the following: RI:?MAI NEP:tEpS~~ffiAtil~gPS.I~;). This time may be used later to determine when to align ND Aux spray. _ 1) Record approximate time of reactor trip. _ 2) Verify NS pumps -INDICATING FLOW. _ 3) IF flow is not indicated, lIiHEN THEN manually initiate Phase B Isolation for affected train(s). (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O 7 of 61 Rev 36 DC~ ACTIONIEXPECTED ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (Continued)
- 4) Verify Phase B 8 Isolation has actuated as follows:
_ a) Phase B 8 Isolation "RESET" lights - DARK. _ b) IF Phase B 8 Isolation "RESET" lights are lit, THEN manually initiate Phase B 8 Isolation. c) Verify following monitor light panel lights - LIT:
- Group 1 Sp lights
- Group 5 Sp lights
- Group 5 St lights Ll11 and Ll12.
_ d) IF monitor light panel not in correct alignment, THEN ensure correct alignment. e) IF NS pump(s) did not start, THEN perform the following for the affected train(s): _ (1) Reset ECCS. _ (2) Reset DIG load sequencer. _ (3) Manually start affected NS pump. _ (4) IF AT ANY TIME a B/O 8/0 occurs, THEN restart SII equipment previously on. _ 5) Stop all NC pumps. _ 6) Maintain seal injection flow. _ 7) Energize H2 igniters. (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/N5000/E-0 8 of 61 8of61 DC~ Rev 36 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (Continued)
- 8) Dispatch operator to perform the following:
_ a) Secure all ice condenser air handling units. REFER TO Enclosure 13 (Securing All Ice Condenser Air Handling Units). _ b) Place containment H2 analyzers in service. REFER TO OP/1/N6450101 OP/1/N6450/01 0 (Containment Hydrogen Control Systems). _ 9) WHEN 9 minutes has elapsed, THEN verify proper VX system operation. REFER TO Enclosure 7 (VX System Operation). _10) GO TO Step 11. b..IF All;ANYtffIME ~Qntairif;jjl:~OFg1f§~$Pt~) b el<9~~p~'"3* ~:§IG~hile ih}tl}is pr@,g~au~g~ THEN perf<5[r11~~§p1 O,~: 11 . 'v~rfi'fp'rop~t;PN:p>>1I1p'~f§bjS;A§ f()(Igws:.
- a. MotQ~)priY¢li:::<!~\ip:t!mpS;ilt~N!} a. Perform the following for the affected train(s):
_ 1) Reset ECCS. No B train power so should not go to RNO. _ 2) Reset DIG load sequencer. _ 3) Manually start affected motor driven CA pump. _ 4) IF AT ANY TIME a BIO B/O occurs, THEN restart SII S/I equipment previously on.
- b. 3:;$/~j:NLl~)lg~el§J\\lG.B~~L§~;lJJ!l\NJ;,
11%/;
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O 9 of 61 Rev 36 DC~ ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED
;f.~rt'Qttn* tH~1;I~l!()wlfl0g1{ot'i~tfecf~{;I
- '1~Jn(sl; 1A NDNO pump a; ResetfGCS;;"
must be b. :R§seHgl7,'§3Io~dj,~Au~J1l~r. manually started. CRITICAL TASK! t:;;l\J)gbuC!l!y,1;'91fit1i~!jfe@1¢@;1p(:n:np:, dv: 'tFA1f,ANY;TIME~~. 8/qG,gclJr~1THEN' fe$1l;lI:r$I!!9vl'l1iptl"ie,hfp'reviously . q"8. 1I~limliU;~;@J2:1ltmp§;;1,mjl~f1Il} Perform the following for affected train(s): No B 8 train power so should not go to RNO. a. Reset ECCS.
- b. Reset DIG load sequencer.
- c. Manually start affected pump.
- d. IF AT ANY TIME a 8/0 BIO occurs, THEN restart SII equipment previously on.
- 14. Perform the following:
- a. IF any Unit 2 RN pump is off, THEN No B 8 train power so manually start affected pump(s).
should not go to RNO. 1B RN has no power, but 18 b. IF any Unit 1 RN pump is off, THEN perform the following for affected 28 2B is running. train(s):): train(s _ 1) Reset ECCS. _ 2) Reset DIG load sequencer. _ 3) Manually start affected pump. _ 4) IF AT ANY TIME a 8/0 BIO occurs, THEN restart SII equipment previously on. IBOP 15*I~jjifll:Rilli~;f'Y'gHUliliggJI§Y~tgm~
- 15. vg~~fYrp!i,Qg~:t'Y~PIUitiof\~yste.m$
pgi¥fttili'gl!ii;I§11§IJI!!I:' op~ratiQll~~~*'JpJJ$1W~;. _ !~, .~Efjf::R;lI'O'I~ltl~!qsII!JE!~tkY:~iilJil§ti()1)
~E:~E:j~~ill1*fi),!III~lm~~1~~illl"l~l~~~llli!!J!9m
!~~~!grn~:~~fil~ti90l~'
$9;$t¢ITfVerif\@§ti6n)J
_ * ,tJdtitMiUnit2,~6p~rqJ9rt()p~N§fm'
~*tl@19Sur~9{ORP()§iteUIi:Ujil¥entn~tioh .
V~li@~t!qflM
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11A15000/E-0 EP/1/A/SOOO/E-0 10 of 61 DC~ Rev 36 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 16. y~ti~@lIf§IG!pre~'~ures/GREi~~MrE:I~; "~jDJJ PerfpIfll thelfgUdWil1g:
IRO TfiAN7J!5';P~I~~ II
-~
;a., _ _f()J1owing Ve'tifylb,e
~:: IAIF:MSIWs
,lII\Il1Elt~
- .~:A:i)~MSivb"ErS's:6valves
' * *ml.mii.md*A-'~~"-_
. ",A:,
Valve'$':" Ct.;~SED:
, , ' : yp "'". . . ,,",,.,.:...
- AIIl§LG PORVs>
- b. IF any valve is open, THEN:
_ 1) Manually initiate Main Steam Isolation. _ 2) IF any valve is still open, THEN manually close valve. 17. r:::-::-:::::--, EWMt'MflilJlllbilWiiflWlJ IBOP I r::::'IB-=-O=-p-'1 _ a. '. . . . . . . . . . . .IJIIIItl7IJ a. Manually start NV pump(s) and align valves.
- b. Perform the following:
_ 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN.
- 2) IF ND pump miniflow valve(s) cannot be opened, THEN perform the following for affected train(s):
_ a) Reset ECCS. _ b) Reset DIG load sequencer. _ c) Stop ND pump. _ d) IF AT ANY TIME a BIO occurs, THEN restart SII S/I equipment previously on. _ e) IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart the ND pump. _ 3) GO TO Step 18.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 11 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. (Continued)
_ c. Manually start NI pump(s) and align valves. IBOP I
- d. NC pressu($I\.J;~STH~N 28qPSIGr IJtBf~.
_ 1) _lmlllllllllltJllttlJ..-_ E;ii$Cffe"£'iJD'pijm'fJ';tTjrRjflow}:~plvf¥'oh op&[aiing NO pl(rT),R{ s!~~- :Q1ill=N;e IRIlYMlJlfJD1IGIIIJIBI
- 2) IF the NO ND pump miniflow valve(s) valve{s) cannot be opened.
opened, THEN perform the following for affected train(s): _ a) Reset ECCS. _ b) Reset DIG load sequencer. _ c) Stop NO ND pump. _ d) IF AT ANY TIME a BIO occurs. occurs, THEN restart SII equipment previously on. _ e) IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner. manner, THEN restart the NO ND pump.
- e. ND NO pumps -INDICATING
- INDICATING FLOW TO e. Manually start NO ND pump(s) and align C-LEGS. valves.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP/1/A/5000/E-0 120f61 12of61 DC~ Rev 36 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 18. (;ontrgl i~(GI~Velsas foll§ws:
a.' VerifyJotaF~Aflow- GRi::!\TJ=RTHAN a. Perform the following:
.4QO ~P:M.
_ 1) IF N/R level in all S/Gs is less than 11 % (29% ACC), THEN manually start CA pumps and ensure correct Flow may be less than 450 gpm due to valve alignment. operator action.
- 2) IF N/R level in all S/Gs is less than 11 % (29% ACC) AND feed flow greater than 450 GPM cannot be established, THEN concurrently:
EP/1/A1S000/F-0 _ .* Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees) Trees).. EP/1/A15000/FR-H.1
- GO TO EP/1/A/5000/FR-H.1 (Response To Loss Of Secondary Heat Sink).
- b. ,WHENatl~9~tlone S/G:N/RleveL;i§'
greater than')1 % {29%ACC),THBNr th rqttleJee,g flovvtQ:r:n?:jbtail];:~lt§/G
~/~I~Y*~.I$ petweg!1;~:~ 1.~ {2,~%;ii~,9C)
~~ngi;50%;;
V~.tifYall ;CAi~ph~tion yalves:- OPEN. _ Manually open valve(s).
- 20. _ Manually align equipment.
IBOP I .._IEID NOTE* Encl9suret~I(NCTemp~ratu[eQpnlc~l} shall.r~Q1~J.n i(;11eff§~!jlJDJiJ sgQ~ggu~tiI\ procedQm~proyJd~,Jtlt~~mattYeftNqi~f~mpe,r(3JI1I~Im¥nlC~kg:ti'i~mtce1; _ ~1,IC9I}t,rqt~CI~e:mR§l~tlJre: .REIi:ERTO IRO I EI)~lo§iyre 4;(ri,Q~1f~mperatu'rEt CQptrolJ~
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 13 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. VgDfI~ezrPORY ari.d ;pzr sptclYV~{ve\
'~~fiifM!BfijIR~B~itti~jmiD§ml:I~]!I~;!jl~1 IBOP I 1§!llY§ 1 11§,J(gllg:!l§lli
$~j:)JY~ji.S foHC)W$:
- a. IF Pzr pressure is less than 2315 PSIG, THEN:
_ 1) Manually close Pzr PORV(s). _ 2) IF any Pzr PORV cannot be closed, THEN close its isolation valve.
- 3) IF any Pzr PORV cannot be closed OR isolated, THEN perform the following:
_ a) Energize H2 igniters. b) Dispatch operator to perform the following: _ (1) Secure all ice condenser air handling units. REFER TO Enclosure 13 (Securing All Ice Condenser Air Handling Units). _ (2) Place containment H2 analyzers in service. REFER TO OP/1/A164501010 OP/1/A/6450/010 (Containment Hydrogen Control Systems). (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP/1/A/5000/E-O 14 of 61 DC~ Rev 36 DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. (Continued) c} IF both the following conditions c) exist,
- Containment pressure -
GREATER THAN 1 PSIG
- Containment pressure - HAS REMAINED LESS THAN 3 PSIG
_ THEN start one VX fan. REFER TO Enclosure 5 (VX Fan Manual Start). d) d} Concurrently: EP/1/A15000/F-0
- Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).
EP/1/A15000/E-1
- GO TO EP/1/A/5000/E-1 (Loss Of Reactor Or Secondary Coolant).
- b. IF Pzr pressure is less than 2260 PSIG, THEN:
_ 1) valve(s}. 1} Manually close spray valve(s). 2) 2} IF spray valve(s) valve(s} cannot be closed, THEN: _ a} Stop NC pumps 1Aand a) 1A and 1B. 1B. _ b) b} IF NC pressure continues to decrease, THEN stop third NC pump as required. 9;~!;,Jga~fQJ1~Pt[;BO R¥!,r~ol?HIl!t yalve,:- c. IF power is available, THEN open one
- (jj?Ji~N; Pzr PORV isolation valve unless it was closed to isolate an open Pzr PORV.
~ _ \g3. \f~rifyN,C§ubS?2'gling<l;)as~,il'onCP'rEi e~iJ IF any NV OR NI pump is on, THEN:
- rlG,$N§REATt;.~TH~*.Q~f~
- a. Ensure all NC pumps - OFF.
- b. Maintain seal injection flow.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11Al5000/E-O EP/1/N5000/E-O 15 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 24. ~~rify majnst~!i!lnlilJ~~ ar~+ft1~lpt~§ IF press tire ir'l'TaUY S/Gisde~reas'l,lgJrt fQUQ,Vis: <i,fI!Jn~Qlll!Qlled,:mann~r OR;<;JDY SIG;,is!
depies'S'j.Tri~~c;I, ',THEN.lR~rforri1lthe
~f :,l\lIlliS/Gi1:
".~'* *"~* * *II'II'III':~
r ssiJf',:'R,'ST:ABLEOR
'" """"v' llillir:t,~,,~ ",' ~,s, '8,'_ following:
~
_ ' ,v ' 1t:J()D~,E~§HNJ3
- a. IF both the following conditions exist,
-.~~~-
11, ALL SIGs'~I?.RESSURIZl+/-p. _ .* Containment pressure - GREATER THAN 1 PSIG _ .* Containment pressure - HAS REMAINED LESS THAN 3 PSIG _ THEN manually start one VX fan. REFER TO Enclosure 5 (VX Fan Manual Start).
- b. _1MIIfD CoricLirr~r}t!y:
*..I."'.t
_ ~: Impl§Jn~ot EPWIN50aO/F-O (QritR:al _*~
" , ' , ;z.;:'j~:;"'l Tree~)~:
Saf~!y',i!f:llJncti9$t$J$t,us
- 25. Verify S/G tubes are intact as follows: IF any EMF trip 1 light is lit OR any S/G level is increasing in an uncontrolled
- Verify the following EMF trip 1 lights- manner, THEN concurrently:
DARK: EP/1/A15000/F-O (Critical _ . Implement EP/1/N5000/F-O
- 1EMF-33 (Condenser Air Ejector Safety Function Status Trees).
Exhaust) EP/1/A15000/E-3 (Steam _ . GO TO EP/1/N5000/E-3
- 1EMF-26 (Steamline 1A) Generator Tube Rupture).
1EMF-27 (Steamline 1B)
- 1EMF-27 1B)
- 1EMF-28 (Steamline 1C)
- 1EMF-29 (Steamline 1D). D) .
- All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/N5000/E-0 320f61 32 of 61 Enclosure 1 - Page 1 of 1 Rev 36 DC~ Foldout Page
- 1. IF any S/G(s) suspected ruptured, THEN perform the following:
- WHEN the following conditions met:
- Total CA flow - GREATER THAN 450 GPM AND
- All intact S/G(s) N/R level - GREATER THAN 11 %(29% ACC)
THEN throttle feed flow to ruptured S/G(s) to maintain ruptured S/G(s) N/R level between 11 %(29% ACC) and 39%.
- 2. NC Pump Trip Criteria:
- IF the following conditions are satisfied, THEN trip all NC pumps while maintaining seal injection flow:
- At least one NVor NV or NI pump - ON
- NC subcooling based on core exit TICs - LESS THAN OR EQUAL TO O°F. OaF.
- 3. CA Suction Source Switchover Criteria:
- IF either of the following annunciators are lit, THEN REFER TO AP/1/N55001006 (Loss of S/G Feedwater):
- 1AD-5, H/4 "CACST LO LEVEL" OR 1AD-8, 8/1
- 1AD-8, B/1 "UST LO LEVEL".
- 4. Position Criteria for 1NV*2028 NV-202B and 1NV*203A NV-203A (NV Pumps A&8 1501):
A&B Recirc Isol):
- IF NC pressure is less than 1500 PSIG AND NV SII flowpath is aligned, THEN close 1NV-202B NV-2028 and 1NV-203A.
- IF NC pressure is greater than 2000 PSIG, THEN open 1NV-202BNV-2028 and 1NV-203A.
- 5. Cold Leg Recirc Switchover Criterion:
- IF FWST level decreases to 37% (1AD-9, 0/8 "FWST 2/4 LO LEVEL" lit), AND an S/I SII has occurred, THEN GO TO EP/1/N5000/ES-1.3 (Transfer To Cold Leg Recirculation).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/Al5000/E-O 33 of 61 Enclosure 2 - Page 1 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. BOP DOES THIS ENCLOSURE
- 18. Verify one tr,?ipof thelolloWiQg; II a. Perform the following:
equipmenti§,:;m}qperatiop: _ 1) 1} Shift operating VCIYC trains. REFER TO Enclosure 6 (Shifting Operating VCIYC Train). 2) 2} IF no train can be properly aligned. aligned, THEN dispatch operator and IAE/Maintenance to restore at least one train of VCIYC. REFER TO the following: _ .* OP/O/AI6450/011 OP/O/A/64501011 (Control Room Area Ventilation/Chilled Ventiiation/Chilied Water System)
- EM/O/Al5200/001 EM/O/A/52001001 (Troubleshooting Cause For Improper Operation of VCIYC System).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/SOOO/E-O 34 of 61 Enclosure 2 - Page 2 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. (Continued)
- b. ~~f;Ify theTQIJQwing filprtQ§;;~:pARK: b. IF chlorine odor is detected in the Control Room, THEN perform the
.;1A@,,18, ;~aj*Pli!fl~wJ1~lf)1;r&~~'~I.* following based on the status of given GI:rI~.Qgl~§l!~l\i; alarms:
- 11S~2~J3;,:~§f{11itSLNlm'1IIINill~,~g!;ie 1) IF detectors on both unit intakes are Gti!JtQl~lNEll~' in alarm, THEN:
_ *'4P~i~~I~D1Qi;WN[T~;tNTI\I}EHJ; a) Ensure the following VC intake iQ§{!.i.QlllNJ;~'* dampers - CLOSED: _ * £1~Q5~~;lE18t"~NITj~INTAKEHJ;
- 1VC-S8 1VC-S8 (CRA Filt Inlet)
Ql1L1.QgJNE~~B~ .
- 1VC-6A (CRA Filt Inlet)
- 2VC-S8 (CRA Filt Inlet)
- 2VC-6A (CRA Filt Inlet).
_ b) GO TO Step 1.d.
- 2) IF Unit 1 intake HI chlorine detector(s) in alarm, THEN:
a) Ensure the following VC dampers - CLOSED: _ . 1VC-S8 (CRA Filt Inlet) _ . 1VC-6A (CRA Filt Inlet). b) Ensure the following dampers - OPEN: _
- 2VC-S8 (CRA Filt Inlet)
_
- 2VC-6A (CRA Filt Inlet).
_ c) GO TO Step 1.d. (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/A15000/E-O 35 of 61 Enclosure 2 - Page 3 of 7 Rev 36 DC~ DCS Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. (Continued)
- 3) IF Unit 2 intake Hi chlorine detector(s) in alarm, THEN:
a) Ensure the following VC dampers - CLOSED: _
- 2VC-58 (CRA Filt Inlet)
_
- 2VC-6A (CRA Filt Inlet).
b) Ensure the following dampers - OPEN: _ . 1VC-58 (CRA Filt Inlet) _ . 1VC-6A (CRA Filt Inlet). _ c) GO TO Step 1.d.
- c. !;Dsgfe the fPII9wijjQI,IC ,cf~Q:fpe~§ -
\QflpN:
_~} :~}{Q7§12,,(CRI1iifnu q!,~t) _~' jYQt6~j(GRI1~fjlrlIi.!~t) _ 4J2\(:~Jpe(QRI11ffjlt I.!lll~t) _. 2'l:@7p~(Q,RI1t*~![t;lriil~t)* d .RJ~p~arSt~j!ltof tbis:enctq:SureY!,lj11il, o'Qtified I:>Y~§fatiQn)managemenras
,;fgIlQ~?:i
_ - Atfjl~Ff§~lP~~I~V.~IY;~BiLbg)llJ~§; QB _ ;.Lt;tX.tl;lime VC/YC
"., ..,.Y...*.....,..... ..... u.
relatea annl.lnCiatots u. pr1I~~~~Ja,J;IG!yClte~
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/Al5000/E-O EP/1/A15000/E-O 36 of 61 Enclosure 2 - Page 4 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. .EnsureprQj:>,~tV'A'{S~.m,gtp ?§R,~raUpnas" fQU9VfS:)
B train VA is powered from Unit 2 w~:I?U~JJrEftn~;\toU6W(!{lg JanS't"'OFf;j and therefore is unaffected by the
~~§UXFtA 1B train blackout.
* "A:ElUXF '1B\
-~ .Ensut~}lA.SjY~l~mIUt~r iSlill setyiceas
'follows~
;t 1ABF:":":[DL12
...".............&.1
'.... g'V,Vlf,.'
'\ ....FHter. A.8 ass .
" ....,yp, Darf:j:tt§[s,) i~;j~~!.o9§~P
.. 1A~&i!::)~9;~~9 (MAfilte.~J3 Bypass'
.. *;ers).
Da*rQJ? .,., ~~CJiOSEP d, "~., ,
- A§PXF-1A
* ~EtFXFJI3.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 37 of 61 Enclosure 2 - Page 5 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. tl;~iji~I'iill,ii:~I'fl.g!!I§I~~l~:mlI?R~r~Ji§:Q.,~~I!
V,¢rifyp,oR:~liVE[~ystEHij'fPperati()Qas follows~\ f§U§il~~l
- a. a. Manually start fan{s).
b. b.Afll'\ulus pr~§~~:U[~1!irE3E~mE;EN b. Perform the following:
-1:,4;;IN. WG~~Q~l.8Jtii!;?!~Pii~
- 1) IF annulus pressure is more positive than -1.4 in. WC, THEN:
a) Verify flow indicated on the This will be correct for A train, following indications: no power to B train.
* "VE 1A1A FLOW TO STACK"
* "VE 1B FLOW TO STACK".
b) IF flow is not indicated, THEN dispatch operator to verify status of the following dampers based on their local indication or their operating piston rods being extended 4" to 6":
- 1AVS-D-2 1AVS-D-2 (VE A Trn Recirc Damp) (AB-603, JJ-51, Rm 500) - CLOSED
- 1AVS-D-7 (VE B Trn Recirc Damp) (AB-603, HH-52, Rm 500) - CLOSED
- 1AVS-D-3 (VE A Trn Exh Damp) (AB-603, JJ-52, Rm 500) - OPEN
- 1AVS-D-8 (VE B Trn Exh Damp) (AB-603, HH-52, Rm 500) - OPEN.
_ c) Consult plant engineering staff and notify IAEIMaintenance IAE/Maintenance to troubleshoot and repair. REFER TO EM/1/A152001002 (Troubleshooting Cause For VE System Hi/lo Pressure). _ d) GO TO Step 3.c. (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 38 of 61 Enclosure 2 - Page 6 of 7 DC~ Rev 36 DC::: Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued)
- 2) IF annulus pressure is more negative than -1.8 in. WC, THEN:
_ a) Determine which VE train indicates highest discharge flow to stack. _ b) Within 2 hours, ensure VE train that indicates highest discharge flow to stack is secured. _ c) Consult plant engineering staff and notify IAE/Maintenance to troubleshoot and repair. REFER TO EM/1/A/5200/002 EM/1/A152001002 (Troubleshooting Cause For VE System Hillo HilLa Pressure).
- c. ti~peal§t~p;z3.beY¢lY.3Qlmint.it~s *iIliltI!:'
i9Rfif~Q:b~t~lation,'manag~.meht
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/Al5000/E-O EP/1/NSOOO/E-O 39 of 61 Enclosure 2 - Page 7 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. Record time ventilation systems are verified on following table:
TIME SYSTEM INITIALS (VC. (VC, VE)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 41 of61 Enclosure 4 - Page 1 of 4 Rev 36 DC~ NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Perform the following: IRO DOES THIS ENCLOSURE E~CLOSURE a. Use NC T -Colds to determine NC I temperature as required in subsequent steps.
- b. GO TO Step 4.
2..lJ§:el:Jj,i,T-Avator;:lg}errtlifje 2 lm~gll,m;i,t:nl~gBI;tqi'~glgrming6i} Nq t(:im'B~{~~lurg~§;r(:i~lt~dr~~II!ji§UP§ggP'~p')
~~rtlP:~JalurEl~~ rec:nUredl(} 'sUbs~quetlt J§tgB.§1 slElA§'f;
,31, !IF!II!:A:\1l11~bJ.1l*.\1lIfv1EI6!:11IByrol?§l~r~IIU;l?g(:i~~)
.IFA1J:~ANY.TIME.N~~PuOlP~lFlrettippedl:;
,THENspse NeT-Colas to,g~temlif'le Net
\maENIU~g;;lSIi:;;iFIQQI~JI*'tq::lI':U~,grm~p~6Q~
;lg;ml?~t~ti;jrltJiI~§rltg.Yirltl:lii.n';!§y§§~gygiill;
;tertlp!f~~turei~s reqIiirer;:linsubs~quent step~Y
;Illtg~f~i 4 .;V~Uifillg,ll!}ltl!Q~iilli,gi:iLq;Uq~i<<!j§;
- NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.
OR
- NC temperature - TRENDING TO 55rF.
- 5. Continue to monitor NC temperature.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O 42 of 61 Enclosure 4 - Page 2 of 4 Rev 36 DC~ NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. Do not continue in this enclosure until one of the following occurs:
- NC temperature - GREATER THAN 557°F AND INCREASING IN AN 55]oF UNCONTROLLED MANNER.
OR
- NC temperature - GREATER THAN 55]oF 557°F AND STABLE.
OR
- NC temperature - LESS THAN 55]oF AND DECREASING IN AN 55rF UNCONTROLLED MANNER.
- 7. tY~~i;fi{~G,temp~ratl:lfe -LESSIJ:;IAN Perform the following:
552';I?~Pl~ECREA.S[Nq~!
- a. IF NC temperature is greater than 55]oF AND increasing, THEN stabilize 55rF NC temperature at 55rF 55]oF as follows:
- 1) IF steam dumps are available, THEN use steam dumps.
- 2) IF steam dumps are not available, THEN use S/G PORVs.
- b. IF the following conditions exist:
- NC temperature is greater than 55]oF and stable 55rF
- Time and manpower is available, THEN stabilize NC temperature at 55]oF as follows:
55rF
- 1) IF steam dumps are available, THEN use steam dumps.
- 2) IF steam dumps are not available, THEN use S/G PORVs.
- c. GO TO Step 9.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 43 of 61 430f61 Enclosure 4 - Page 3 of 4 DC~ Rev 36 DC:: NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 88. tA<<~'mpt. tostoplbg,;;NC B s coqUiQwn as fgllows:
.......... '. '. jlmste~i"~<f a.EnsureT '£. ....I11,Y.!IlP .. s.2;~~LOSED u
.d~. .. . .
- b. IF any S/G PORV cannot be closed, valve..
THEN close its isolation valve
- c. ~~'iiS;l.Jr~1j~~G*blowd.9wlil~Jo)~ isolated~
d..q;JQ~"~';th'~ fqUowing Y~lves:.
* ;'~1J~,M~T1A{SlG 1AOtitHdr BldWn fPYJ.;}
.. *"1SM2 7El8;RS/G :1 BOtltHdr BldWn.
CIY)
~\ ;1;SMFl{9A (S{G1()'~UIJ Hdrl?!(;!WD:
PlY>>)
** ~ c":'1
}":I; -n" D'(S7f~Wif'D "Oflt 'LJ'~ i'B'I'l'I"'*ww*
c Pir" ~:~f:t1Rji . /:,; ~+/-l~~t. c"i" " Y!,i\~ ~;; ,ywn:
- .. SAil eN};
C lie. [)epr~,ss,a!1(fnpld "SIYBEFORE$,EAT L!RN;L~~Cl;jpSE" PuS.llPutton (1 MG..~(). t9 C'~~Er;Uje ~CmOwirjg¥£lIy~s:.
~, ii1'SMf4:1.($top VJy'i1f,1E3,efqr~I!Seat Drn}
.1:SM;;~4 (Stop VlytJ,2, ,l3efore Se~l
'O,rn);
,;~" t~~.MA~'X~t9P0Vly;;f/;Bfa:~f&ifeiiJq;E:l.at Dm)
* . ' 1pM.J~~lStop "':lv~:i~E:lf()re;Se. at Om}.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 44 of 61 Enclosure 4 - Page 4 of 4 Rev 36 DC~ NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (Continued) f*r.* . . ._ fJ,:ST088Et;>":!';
- f. Verify NO'cq<;>190wn .... ff.. .n::*. cooldowncontiriues,THEN >:throttle lt~~g,jfl.i~;as follows:' . '~~. ' "...
- 1) 'IF~~/G'f\JI;!!tl~x?! i.s 1e$§:tpan.t~1.~\%
(29°(o ACG):':irJJ~n:~/G's~tjfHEN;
&[lrtg~I~/t~.~9j!UQ~ft()' gCIi1~)(,e tl1~j folloWing::
- Maiolah tota.lf§g.o .tlowli9reates; thc:il't.4~O GPM.'
- 2) WHEN~/Rlev~Usgr~<:it¢:fthgD 11 % {29% AC.~tln a!~'~§$ton~ ${@~'
THEN throttlef~e:ct JIC5W;rurther to.
?ql1ie~~i~he!qII9~lri9:; . .
~iMiriiniize cqQ:,lQ9wr1
- Maintain: at least oneS/QiIN/R' level gfeat~Jthan 11%
(29% ACC). .. (3) 1Fc9.olgqwncoQUm:Qes, THEN c!~~e theifQ.IIQl&iQg.yahfe~~i
. ~
~""All MSIVs.
.. AII*MSIY. bypassyalves.
9..CQntif,1J!~il\!pxpeijfQfrP1 the .acti9jj~6J this., 9 erjc*IQ§i,m~~ast;~q-UiredtoeQ.~ijre*oneof the following:
- NC temperature - STABLE AT LESS THAN OR EQUAL TO 557°F.
OR
- NC temperature - TRENDING TO 557°F. 55rF.
Duke Power Company Procedure No. Catawba Nuclear Station EP/I/A/sooo/E-2 Faulted Steam Generator Isolation Revision No. 012 Electronic Reference No. CP0094CZ Continuous Use PERFORMANCE I
- * * * * * * * *
- UNCONTROLLED FOR PRINT * * * * * * * * * *
(ISSUED) - PDF Format 16
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/N5000/E-2 1 of 21 Revision 12 A. Purpose This procedure provides actions to identify and isolate a faulted S/G. B. Symptoms or Entry Conditions This procedure is entered from:
- a. EP/1/A15000/E-O EP/1/N5000/E-O (Reactor Trip Or Safety Injection), Step 24, with the following symptoms:
- 1) Any S/G pressure decreasing in an uncontrolled manner.
- 2) Any S/G completely depressurized.
- b. EP/1/A15000/E-1 EP/1/N5000/E-1 (Loss Of Reactor Or Secondary Coolant), Step 2, EP/1/A15000/ECA-3.1 EP/1/N5000/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired), Step 11, EP/1/A15000/ECA-3.2 EP/1/N5000/ECA-3.2 (SGTR With Loss Of Reactor Coolant - Saturated Recovery Desired), Step 5 with the following symptoms and/or conditions:
- 1) Any S/G pressure decreasing in an uncontrolled manner.
- 2) Any S/G completely depressurized.
- 3) Faulted S/G isolation not verified.
- c. EP/1/N5000/FR-H.5 (Response To Steam Generator Low Level), Step 4, when the EP/1/A15000/FR-H.5 affected S/G is identified as faulted.
- d. Foldout page of other procedures whenever a faulted S/G is identified.
- e. EP/1/A15000/ECA-2.1 EP/1/N5000/ECA-2.1 (Uncontrolled Depressurization Of All Steam Generators),
Enclosure 1 (Foldout Page), if any S/G pressure increases.
eNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A/5000/E-2 2 of 21 20f21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions 1. 2. 3. 1RQl3. Vgtlfytti~,fQIIQ,~lgg .¥:c,!IYesl?:(;L()~EP: _ Manually close valve(s).
~
=: ,::}~gt~~~YR:?~§;~Var~~s.
- 4. _ IF all S/Gs are faulted, THEN GO TO EP/1/A15000/ECA-2.1 (Uncontrolled EJ Depressurization Of All Steam Generators).
IRQ I 5. . ild~t1lti'~~iflftbf~dlSfGf~~!'~sfdnows:
.tit *Y. ' k ' h ". \.7"....... " " , Perform the following:
_
- VerifyjfanySl<:?;'pr~~sU(~;?DE¢gEA§ING a. Dispatch operators to search for INANUNC()NTg(];)Lll;J)Ml:\~NER initiating break at the following locations:
!~QR,f
- Main steamlines
*
- Main feedlines
_
- Other secondary piping.
_ b. GO TO Step 8.
- 6. Maintain one S/G available for NC System cooldown cool down in subsequent steps.
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/N5000/E-2 EP/1/A/5000/E-2 30f21 3 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 77..'I,~ot/r~,anfaqhed'slG{sY:~~fdnqWs:
~:is/G'lA:
EJ- _!!ii~;~ii~. a. Perform the following: _ 1) Manually close valve(s).
- 2) IF 1CA-185 (S/G 1A CA Nozz Tempering Isol) cannot be closed, THEN:
a) Manually close the following valves:
- 1 CF-1 00 (S/G CA Nozz 1CF-100 Tempering Ctrl)
- 1CF-156 (8yp Valve For 1CF-100).
b) IF 1CF-100 OR 1CF-156 cannot be manually closed, THEN dispatch operator to close the affected valve(s):
- 1CF-100 (S/G CA Nozz Tempering Ctrl) (T8-580, 1H-33) (Ladder needed)
- 1 CF-156 (8yp Valve For 1CF-156 1CF-100) 1CF-1 00) (T8-577, 1H-33)
(Ladder needed).
- b. b. Perform the following:
_ 1) Manually close S/G PORV.
- 2) IF S/G PORV cannot be closed, THEN:
_ a) Manually close S/G PORV isolation valve. _ b) IF S/G PORV isolation valve cannot be closed, THEN dispatch operator to close the valve.
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/N5000/E-2 4 of 21 40f21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- c. Close the following valves:
_1) _ 1) Dispatch operator to close 1SM-77A (S/G 1A Otlt Hdr Bldwn CN) (DH-583, FF-GG, 43-44, Rm 591). _ 2) 2) Perform the following: _ a) Close 1CA-60 (CA Pump 1A Flow To S/G 1A). _ b) Dispatch operator to close 1CA-62A (CA Pmp A Disch To S/G 1A Isol) (DH-587, DD-EE, 44-45, Rm 591). _ 3) ~f i~lforrn,lhe j8nowing: _ ~r Cl.ose1C;A-64(CA Pumpfjt1 Flgw IQi3fG.1A) . _ *PHij~~~P'* .. &~efgtor to.close
. t~,A Pmp1 QJsch,~~Q
'SI Is~I~;(Df-!p5~4.DR;-I3~*;*
44- .* ril:591).~ d. This should already have been done in E-O but will be done here if not. CRITICAL TASK!!!
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/A/5000/E-2 5 of 21 50f21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
IRQ I - 2)
- 2) ~~~~y~~~.{S/Gr<<'1~*Bf~Wij:i~on~ 2) Perform the following:
_ a) Manually close valve. b) IF valve will not close AND 1BB-56A is open, THEN No power last known position was perform the following: closed _ (1) Ensure "S/G A BLDWN BLOWN FLOW CTRL"- FLOWCTRL"- CLOSED. (2) Dispatch operators to ensure the following valves - CLOSED: _ .* 1 BB-148B (S/G 1A 1BB-148B Bldwn Cont Isol Byp) (DH-580, EE-FF, 44-45, Rm 591) _ .* 1 BB-81 (1A S/G 1BB-81 Blowdown Penetration Valve Test Isol) (DH-583, EE-FF, 44, Rm 591).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A/5000/E-2 6of21 6 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
_ 3) ),,~BJ5iB(S/G 1AiSldwn:gont'f~ol 3) 'gIB@tQ1!t~I';fbI\D~ri9::l
\~J§!lfl
- ;pJi'!fQ18'nlJ~lly~Clbs~?yalv~ )
No power last known position was OPEN b 5tlii:\yalv6 will notclose,AND\ 1BB-56A should 1IBB:-5()Ats oper;iil~:rHEN"" already be per;!'orm' th$ following: closed but if not _ (1) ,Ensdre i "S/G?'!l('S8bWlx,f' this RNO will be ;FLO\~lhTRL~1 _ i . . i. .;d done. CLO~il;,Q. . (2). {DispafbQloper~tor~ to'
- t~~e!{~~~~~g .
- 1138-57
.~~~~g8~ti> -~lf" Skip to page 18, steps in between are for isolating other S/Gs that may be faulted, but none are in this case. i&t~-4Q!~~m 59,;~)
_ iffi*S'i~B'4B111~'1A,§£G* .
. SIQwdown H~Yietration v~~~:':[e~q§~1) ..... .
(DJ"h:583,iEI;-'PF. 44 iji Rm591).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/A/5000/E-2 70f21 7 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- S/G 1B:
- a. Verify S/G 1B Feedwater Isolation a. Perform the following:
status light (1 SI-5) - LIT. _ 1) Manually close valve(s).
- 2) IF 1CA-186 (S/G 1 1BB CA Nozz Tempering Isol) cannot be closed, THEN:
a) Manually close the following valves:
- 11CF-100 CF-1 00 (S/G CA Nozz Tempering Ctrl)
- 1CF-156 (Byp Valve For 1CF-100).
b) IF 1CF-100 OR 1CF-156 cannot be manually closed, THEN dispatch operator to close the affected valve(s):
- 1CF-100 (S/G CA Nozz Tempering Ctrl) (TB-580, 1H-33) (Ladder needed)
- 1CF-156 (Byp Valve For 1CF-100) (TB-577, 1 1H-33)
H-33) (Ladder needed).
- b. Verify S/G 1B PORV - CLOSED. b. Perform the following:
_ 1) Manually close S/G PORV.
- 2) IF S/G PORV cannot be closed, THEN:
_ a) Manually close S/G PORV isolation valve. _ b) IF S/G PORV isolation valve cannot be closed, THEN dispatch operator to close the valve.
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/A/5000/E-2 8 of 21 80f21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- c. Close the following valves:
_ 1) 1SM-76B (S/G 1B Otlt Hdr Bldwn _ 1) Dispatch operator to close CN). 1SM-76B (S/G 1B Otlt Hdr Bldwn CN) (DH-583, FF-53, Rm 572). _ 2) 1CA-58A (CA Pmp A Disch To 2) Perform the following: S/G 1B Isol). _ a) Close 1CA-56 (CA Pump 1A 1B). Flow To S/G 1B). _ b) Dispatch operator to close 1CA-58A (CA Pmp A Disch To S/G 1B Isol) (DH-586, DD-EE, 52-53, Rm 572). _ 3) 1CA-54B (CA Pmp 1 Disch To 3) Perform the following: S/G 1B Isol). _ a) Close 1CA-52 1CA-52 (CA Pump #1 Flow To S/G 1 B). 1B). _ b) Dispatch operator to close 1CA-54B 1CA-54B (CA Pmp 1 Disch To S/G 1B Isol) (DH-584, DD-EE, 52-53, Rm 572).
- d. Verify CA Pump 1A or 1B-1B - d. IF CA Pump #1 is the only source of AVAILABLE. feedwater, THEN perform the following:
_ 1) Maintain steam flow to the CAPT from at least one S/G. _ 2) IF desired to isolate steam supply to CA Pump #1 from 1B S/G, THEN GO TO Step 7.e. _ 3) GO TO Step 7.f.
- e. Dispatch operator to unlock and e. Dispatch operator to unlock and close 11SA-1 SA-1 (1B (1 B S/G Main Steam to close 1SA-3 (1 B S/G Mai n Steam to CAPT Maintenance Isol) (DH-624, CAPT Stop Check) (AB-551, DD-53, FF-53, Rm 572) (Breakaway lock Rm 217) (Breakaway lock installed).
installed).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A/5000/E-2 9 of 21 90f21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- f. Verify the following blowdown isolation valves - CLOSED:
_ 1) 1BB-19A (S/G 1B Bldwn Cont Isol _ 1) Manually close valve. Insd). _ 2) 1BB-150B 1BB-150B (S/G 1B 1B Bldwn Cont 2) Perform the following: Isol Byp). _ a) Manually close valve. b) IF valve will not close AND 1BB-19A is open, THEN perform the following: _ (1) Ensure "S/G B BLDWN FLOW CTRL"- CLOSED. (2) Dispatch operators to ensure the following valves - CLOSED:
- 1 BB-150B (S/G 1B 1BB-150B 1B Bldwn Cont Isol Byp)
(DH-580, FF, 52-53, Rm 572)
- 1BB-83 (1 B S/G Blowdown Penetration Valve Test Isol)
(DH-580, FF-53, Rm 572).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/11A/5000/E-2 10 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
_ 3) 1BB-21 B {S/G 1B Bldwn Cont Isol 3} 3) Perform the following: 3} Otsd). Otsd}. _ a) a} Manually close valve. b) b} IF valve will not close AND 1BB-19A is open, THEN perform the following: _ (1) Ensure "S/G B BLDWN FLOW CTRL"- CLOSED. (2) Dispatch operators to ensure the following valves - CLOSED:
- 1BB-21B (S/G 1B Bldwn Cont Isol Otsd)
(DH-580, FF, 52-53, Rm 572)
- 1BB-83 (1 B S/G Blowdown Penetration Valve Test Isol)
(DH-580, FF-53, Rm 572).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/A/5000/E-2 11 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- S/G 1C:
- a. Verify S/G 1C Feedwater Isolation a. Perform the following:
status light (1SI-5) - LIT. _ 1) Manually close valve(s).
- 2) IF 1CA-187 (S/G 1C 1CA-187 1C CA Nozz Tempering Isol) cannot be closed, THEN:
a) Manually close the following valves: _ .* 1CF-1 00 (S/G CA Nozz Tempering Ctrl) _ .* 11CF-156 CF-156 (Byp Valve For 1CF-100). b) IF 1CF-100 OR 1CF-156 cannot be manually closed, THEN dispatch operator to close the affected valve(s): _ .* 1CF-100 (S/G CA Nozz Tempering Ctrl) (TB-580, 1H-33) (Ladder needed)
- 11CF-156 CF-156 (Byp Valve For 1CF-100) (TB-577, 1 1CF-100)(TB-577, 1H-33)
H-33) (Ladder needed).
- b. Verify S/G 1C PORV - CLOSED. b. Perform the following:
_ 1) Manually close S/G PORV.
- 2) IF S/G PORV cannot be closed, THEN:
_ a) Manually close S/G PORV isolation valve. _ b) IF S/G PORV isolation valve cannot be closed, THEN dispatch operator to close the valve.
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/A/5000/E-2 12 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- c. Close the following valves:
_ 1) 1SM-75A (S/G 1C Otlt Hdr Bldwn _ 1) Dispatch operator to close CN). 1SM-75A (S/G 1C Otlt Hdr Bldwn CN) (DH-580, GG, 52-53, Rm 572). _ 2) 1CA-46B (CA Pmp B Disch To 2) Perform the following: S/G 1C Isol). _ a) Close 1CA-44 (CA Pump 1B Flow To S/G 1 C). 1C). _ b) Dispatch operator to close 1CA-46B (CA Pmp B Disch To S/G 1C Isol) (DH-586, DD, DO, 53-54, Rm 572). _ 3) 1CA-50A (CA Pmp 1 Disch To 3) Perform the following: S/G 1C Isol). _ a) Close 1CA-48 (CA Pump #1 Flow To S/G 1 C). 1C). _ b) Dispatch operator to close 1CA-50A (CA Pmp 1 Disch To 1CA-50A S/G 1C Isol) (DH-584, EE-53, Rm 572).
- d. Verify CA Pump 1A or 1B - d. IF CA Pump #1 is the only source of AVAILABLE. feed water, THEN perform the feedwater, following:
_ 1) Maintain steam flow to the CAPT from at least one S/G. _ 2) IF desired to isolate steam supply to CA Pump #1 from 1 1C C S/G, THEN GO TO Step 7.e. _ 3) GO TO Step 7.f.
- e. Dispatch operator to unlock and e. Dispatch operator to unlock and close 1SA-4 (1C S/G Main Steam to close 1SA-6 (1C S/G Main Steam to CAPT Maintenance Isol) (DH-624, CAPT Stop Check) (AB-551, DO-53, DD-53, FF-53, Rm 572) (Breakaway lock Rm 217) (Breakaway lock installed) installed). (Ladder needed).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/A/5000/E-2 13 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- f. Verify the following blowdown isolation valves - CLOSED:
_ 1) 1BB-60A (S/G 1C Bldwn Cont Isol _ 1) Manually close valve. Insd). _ 1BB-149B (S/G 1C Bldwn Cont
- 2) 1BB-149B 2) Perform the following:
Isol Byp). IsoI8yp). _ a) Manually close valve. b) IF valve will not close AND 1BB-60A is open, THEN perform the following: _ (1) Ensure "S/G C BLDWN FLOW CTRL"- CLOSED. (2) Dispatch operators to ensure the following valves - CLOSED: 1BB-149B (S/G 1C
- 1BB-1498 Bldwn Cont Isol Byp)
(DH-578, FF-GG, 52, Rm 572)
- 1BB-82' (1 C S/G Blowdown Penetration Valve Test Isol)
(DH-583, FF-53, Rm 572).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/Al5000/E-2 14 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
_ 3}
- 3) 1BB-u1B 1B8-61 8 (S/G 1C 1C Bldwn Cont Isol 1501 3}
- 3) Perform the following:
Otsd). _ a) Manually close valve. a} b} IF valve will not close AND b) 1BB-60A is open, THEN 1BB-60A perform the following: _ (1) BLOWN Ensure "S/G C BLDWN FLOW CTRL"- FLOWCTRL"- CLOSED. (2) Dispatch operators to ensure the following valves - CLOSED:
- 1 BB-61 B (S/G 1C 1BB-61B 1501 Otsd)
Bldwn Cont Isol (DH-578, FF-GG, 52, Rm 572) 1BB-82 (1 C S/G
- 188-82 Blowdown Penetration 1501)
Valve Test Isol} (DH-583, FF-53, Rm 572).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/A/5000/E-2 15 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- S/G 1 D:
1D:
- a. Verify S/G 1D Feedwater Isolation a. Perform the following:
status light (1SI-5) - LIT. _ 1) Manually close valve(s).
- 2) IF 1CA-188 (S/G 1D CA Nozz Tempering Isol) cannot be closed, THEN:
a) Manually close the following valves:
- 1CF-1 00 (S/G CA Nozz Tempering Ctrl)
_ .* 1CF-156 (Syp (Byp Valve For 1CF-100). b) IF 1CF-100 OR 1CF-156 cannot be manually closed, THEN dispatch operator to close the affected valve(s): 1CF-1 00 (S/G CA Nozz
- 1CF-100 Tempering Ctrl) (TB-580, (TS-580, 1H-33) (Ladder needed)
- 11CF-156 CF-156 (Syp (Byp Valve For 1CF-1 00) (TB-577, 1CF-100) (TS-577, 1 H-33) 1H-33)
(Ladder needed).
- b. Verify S/G 1D PORV - CLOSED. b. Perform the following:
_ 1) Manually close S/G PORV.
- 2) IF S/G PORV cannot be closed, THEN:
_ a) Manually close S/G PORV isolation valve. _ b) IF S/G PORV isolation valve cannot be closed, THEN dispatch operator to close the valve.
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/N5000/E-2 EP/1/A/5000/E-2 16 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- c. Close the following valves:
_ 1) 1 SM-74B (S/G 1 1SM-74B D Otlt Hdr Bldwn 1D _ 1) Dispatch operator to close CN). 1SM-74B 1SM-74B (S/G 1 1DD Otlt Hdr Bldwn CN) (DH-583, FF-GG, 44-45, Rm 591 ). _ 2) 1CA-42B (CA Pmp B Disch To 2) Perform the following: S/G 1D Isol). _ a) Close 11CA-40 CA-40 (CA Pump 1 1B B Flow To S/G 1D). _ b) Dispatch operator to close 1CA-42B (CA Pmp B Disch To S/G 1D Isol) (DH-586, DD-EE, 43-44, Rm 591). _ 3) 1CA-38A (CA Pmp 1 Disch To 3) Perform the following: S/G 1D Isol). _ a) Close 1CA-36 (CA Pump #1 Flow To S/G 1D). _ b) Dispatch operator to close 1CA-38A 1CA-38A (CA Pmp 1 Disch To S/G 1D Isol) (DH-584, DD-EE, 43-44, Rm 591).
- d. Verify the following blowdown isolation valves - CLOSED:
_ 1) 1BB-8A (S/G 1D Bldwn Cont Isol _ 1) Manually close valve. Insd).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/11A15000/E-2 EP/1/A/5000/E-2 17 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
_ 1BB-147B (S/G 1D 81dwn
- 2) 188-1478 Bldwn Cont 2) Perform the following:
Isol Byp). Isol8yp). _ a) Manually close valve. b) IF valve will not close AND 1 BB-8A is open, THEN 188-8A perform the following: _ (1) Ensure "S/G D 8LDWN BLDWN FLOW CTRL"- FLOWCTRL"- CLOSED. (2) Dispatch operators to ensure the following valves - CLOSED: 1BB-147B (S/G 1D
- 188-1478 Bldwn Cont Isol 8yp) 81dwn Byp)
(DH-582, EE-FF, 44, Rm 591)
- 1 BB-80 (1 D S/G 188-80 Blowdown Penetration 810wdown Valve Test Isol)
(DH-583,EE-FF,44, Rm 591).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/Al5000/E-2 18 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
_ 3) 1BB-1 OB (S/G 1D Bldwn Cont 1501 Isol 3) Perform the following: Otsd). _ a) Manually close valve. b) IF valve will not close AND 1BB-8A is open, THEN perform the following: _ (1) Ensure "S/G D BLDWN FLOW CTRL"- CLOSED. (2) Dispatch operators to ensure the following valves - CLOSED: _ .* 1BB-10B (S/G 1D Bldwn Cont Isol Otsd) (DH-582, EE-FF, 44, Rm 591) _ .* 1BB-80 1BB-80 (1D (1 D S/G Blowdown Penetration Valve Test 1501) Isol) (DH-583,EE-FF,44, Rm 591). 8. IRO I
- 9. _ REFER TO AP/1/A15500/006 (Loss of S/G
~ Feedwater).
-1......' - -
eNS CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A15000/E-2 EP/1/A/5000/E-2 19 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. Verif9se~pna~rY. *radiafion)\i~~"noml~ii~~i fO,llg~§:
EJI _.&11_,1&1_ ,BOP \&.t~iis~~~lb~1fQnQ~iDg silg hai~~LRE~I::I*::i __1.,,- _ t1);XpHa.s~IA, C()rlfaI~l'l1~J1t,ISQi~:!rQn~ _ 2): GASy~tem VaJve;"~glJtr()j _ 3) KG NCiNI Ni\.1 St ~Id(lg:ifs. _ *bB?;.:l\lignall SIG:$ forchernistry sampmig~J; I'
'c~ji!i;Rerforrn at l~af)i6ne of.thefollowing':i'
_ '*,.Notjfy Gb~rpistryto:p~r,iodicaUy
. sample ~11 T§/Gs for aqlivity.
OR
.{NdJi{Y JRR to peri9'~;ic~IIY!i~is~1~Jr
. :¢?tLdh: ~pl~mn~ ferenB:ptivi~.
d .;:ifMeVfy;t,~~;IQ,if&Mhg)!;MF t~jPli;flights.~ d. GO TO EP/1/A15000/E-3 EP/1/A/5000/E-3 (Steam
;IJARK.:> Generator Tube Rupture).
- 1EMF~i9 (StearplinW:t~.A),
_ 4; 1~M!t~~Z;(§f~cfmlIDe;j;f3r
;;lt~;EME;g28; (;$I~*a";;;'lin'e
~;: *. ; ***..**..* ,';'
-_ . 1EMF~~g"i(Steamlil)efb)~
i" :w~"""",,;,,m... e.y~rl{y:tg~rS/G(§)lruJ,!~i'ji:I.NS;U;5;E; e.
;~9N[~It)!i\.1F;Nif ;:
1C)*.1
;~~ii:t%B:~q;yesf RP to;perfdrrri'th~,;!(qflowi~g~.
_1) _ 1) 1'v1(:UJj~or the ~r~~:tof th,~/ste9.rpf~4IJ} fqri~~diation *. ,
- f. f. Perform the following:
_ 1) Notify station management to evaluate S/G(s) activity results. _ 2) IF S/G(s) activity indicate a SGTR, EP/1/A/5000/E-3 THEN GO TO EP/1/A15000/E-3 (Steam Generator Tube Rupture).
eNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/N5000/E-2 EP/1/A/5000/E-2 20 of 21 Revision 12 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11. a <~QQ~liDgi!?~,~~q!n'\:qQi;~l~xitf/~s a. GO TO Step 12 12.. A'TIE,£~ TH,~tJO~F;, . RO/SOP RO/BOP
- b. 'Iler~y .secongafY:lhefitgir1!< agfg!Jpws:, b. GO TO Step 12.
_ .'N/B:t(~veal~afl~§st (>n~.\inta ,. NW:"JG';;i1
.GRgl:\TBH1TH~~;;1,1 %{29%/"J OR
*'~9~~81~:Yi1V~5~~~Wf@*§t' c.
- c. ~~~;~I~~~STA§J4E &R' c. GO TO Step 12.
- d. P~rIi¥~ef- G.B:EAtt:2f~TH1\N11ftPJ d. GO TO Step 12.
(gPO(crACC); 1
- e. Termination criteria should be met and the crew should transition to ES-1.1.
- 12. EP/11A15000/E-1 (Loss Of GO TO EP/1/Al5000/E-1 Reactor Or Secondary Coolant).
CNS FAULTED STEAM GENERATOR ISOLATION PAGE NO. EP/1/A/5000/E-2 EP/1/A15000/E-2 21 of 21 Enclosure 1 - Page 1 of 1 Revision 12 Foldout Page
- 1. Cold Leg Recirc Switchover Criterion:
(1AD-9, 0/8 "FWST 2/4 LO LEVEL" lit), THEN GO TO _ .* IF FWST level decreases to 37% (1AO-9, EP/1/A/5000/ES-1.3 (Transfer To Cold Leg Recirculation). EP/1/A15000/ES-1.3
- 2. Position Criteria for 1NV-202B and 1NV-203A (NV Pumps A&B Recirc Isol): 1501):
_ .* IF NC pressure is less than 1500 PSIG AND NV SII flowpath is aligned, THEN close 1NV-202B and 1NV-203A.
- IF NC pressure is greater than 2000 PSIG, THEN open 1NV-202B and 1NV-203A.
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/NSOOO/ES-1.1 1 of of76 76 Rev 2SDCS Rev2SDCS A. Purpose This procedure provides the necessary instructions to terminate Safety Injection and stabilize plant conditions. B. Symptoms or Entry Conditions This procedure is entered from:
- a. EP/1/NSOOO/E-O (Reactor Trip Or Safety Injection), Step 27, EP/1/NSOOO/E-1 (Loss Of Reactor Or Secondary Coolant), Step 7, and EP/1/NSOOO/E-2 (Faulted Steam Generator Isolation), Step 11 when specified termination criteria are satisfied.
- b. EP/1/NSOOO/FR-H.1 (Response To Loss Of Secondary Heat Sink), Step 48, after secondary heat sink has been re-established and S/I SII has been terminated.
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A15000/ES-1.1 EP/1/A/5000/ES-1.1 20f76 2 of 76 Rev 25DCS 25DGS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED c. C. Operator Actions Z"ErislJre SfF~l~ESEn' B. EGCS;' a. Perform the following: _ 1) IF either reactor trip breaker is closed, THEN dispatch operator to open Unit 1 reactor trip breakers. _ 2) Concurrently implement Enclosure 6 (ECGS Master Reset) while (ECCS continuing in this procedure.
- b. Dispatch operator to open the affected sequencer(s) control power breaker:
- 1EDE-F01 F (Diesel Generator Load Sequencer Panel 1DGLSA) (AB-577, BB-46, Rm 496)
- 1EDF-F01 F (Diesel Generator Load Sequencer Panel 1DGLSB) (AB-560, BB-46, Rm 372).
- c. 1H£~m'lANY TIME a B/Q,:sg:curs, THEN; restarfS!1 eqqjpment ptt~;Viously,pn~
.IIRT.DDlllliiJWllllmmu
- E,JJ§{I~,~lc1he :toUoWirig]~potaiijme:fi~}
. . .1J&iJllill_ _.
!sola1ion;;!Jgl)al,$iil;~ESET:
- Phase A
.; *Phase.B.
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A/5000/ES-1.1 30f76 3 of 76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Est.ablishVtJo:icOlltainm~ntas foUqW~: Perform the following: ISOpl _ * \*"$liICe 1VI
*cv 7B'Y'l:/I'r7' t I"~p'I')' - OPC'N
',,":,714~\),t,,,j~on dli.' a. Align N2 to the Pzr PORVs by opening the following valves:
- 1NI-438A (Emer N2 From CLA A To 1NC-34A)
- 1 NI-439B (Emer N2 From CLA B To 1NC-32B).
- b. IF VI pressure is less than 85 PSIG, THEN dispatch operator to ensure proper VI compressor operation.
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A/5000/ES-1.1 4 of76 40f76 Rev 250CS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ISOp/5.
- a. Cbht~iJ1(nel11J~:r~~~:Wre. t:ffl~§ EXC§~{~F(i>;i91:~§;!{s.~;
- b. Verify the following valves - OPEN: b. Perform the following:
- 1FW-27A (NO Pump 1A Suct From _ 1) WHEN containment pressure is less FWST) than 1 PSIG, THEN perform Steps 5.d through 5.f.
FW-55B (NO Pump 18
- 1FW-558 1B Suct From FWST). _ 2) GO TO Step 6.
- c. Containment pressure - LESS THAN c. Perform the following:
2.4 PSIG. _ 1) WHEN containment pressure is less than 2.4 PSIG, THEN perform Step 5. _ 2) GO TO Step 6.
- d. Reset NS.
- e. Stop NS pumps.
- f. Close the following valves:
- 1NS-29A (NS Spray Hdr 1A Cant Cont Isol)
- 1NS-32A (NS Spray Hdr 1A Cant Cont Isol)
- 1NS-15B (NS Spray Hdr 1B Cont Cant Isol)
- 11NS-12B NS-12B (NS Spray Hdr 18 1B Cant Cont Isol).
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A15000/ES-1.1 EP/1/A/5000/ES-1.1 5 of 76 50f76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. yerifY'NC pre~~Yre -'~;rAB:!,:iE:g.g' Perform the following:
iINCREA~Jt4,p*, ~ a. Ensure Pzr spray valves - CLOSED.
- b. IF NC pressure continues to decrease, EP/1/A15000/ES-1.2 THEN GO TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization ).
B. In subsequent steps, control room ISOpl control is lost for the following valves and local operation will be required:
- 1NV-294 (NV Pmps A&B Disch Flow Ctrl)
- 1NV-309 (Seal Water Injection Flow).
- 9. Isoli!t~\~V~tJ?fl6wp~th as(ollow~7ij,
=-:::-=-1 ~ a: !,¥UrmY&\tg:~f9I1qW!mgv~1V:es"';QgEN= a. IF NV pump suctions are aligned for Cold Leg Recirc, THEN: _ ;;1 11'i1M,7~§2N;{m'¥(EIt.img,$,,$uQtEr()m FWS;;F) _ 1) Close 1NV-309 (Seal Water Injection Flow). _ *** i)1J}lV-2q313{NViBampsi~l.k;t IJrqfft f't!$]}s 2) IF control of 1NV-309 is lost from the control room, THEN dispatch operator with radio to perform the following: _ NV-308 (Seal Wtr Inj a) Close 1 NV-30B Flow Ctrl Isol) (AB-554, JJ-54, Rm 233) (Ladder needed). _ b) Throttle 1NV-311 (Seal Wtr Inj Flow Ctrl Byp) (AB-555, JJ-54, Rm 233) to control seal injection flow as required in subsequent steps.
- 3) Open the following valves:
- 1NV-312A (Chrg Line Cant Cont Isol)
- 1NV-314B (Chrg Line CantCont Isol).
(RNO continued on next page)
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A15000/ES-1.1 EP/11A15000/ES-1.1 60f76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (Continued)
NV-312A OR 1 NV-314B cannot
- 4) IF 1NV-312AOR opened, THEN dispatch operator be opened.
valve(s). REFER to open affected valve{s). enclosure(s) for TO the following enclosure{s) affected valve(s):
- Enclosure 8 (locally NV-312A)
Open 1NV-312A)
- Enclosure 10 (locally Open 1 NV-314B).
_ 5) Do not continue in this procedure until 1NV-312A and 1NV-314B are open. _ 6) IF NC pressure is greater than PSIG, THEN throttle 1NV-309 1950 PSIG. 1NV-309 or 1 NV-311 to 50% open. _ 7) Open 1NV-294 (NV Pmps A&B _7) Disch Flow Ctrl).
- 8) IF control of 1NV-294 is lost from room, THEN:
the control room. _ a) Place the controller for 1NV-294 in the 100% demand position. _ b) Dispatch operator with a radio to throttle 1NV-295 (NV Pmps A & Ctrllsol) B Disch Ctrl (AB-551, Isol) (AB-551. JJ-55, Rm 231) to control JJ-55. charging flow as required in subsequent steps.
- 9) Close the following valves:
_ . 1NI-9A (NV Pmp C/l Inj Isol) 1 NI-1 OB (NV Pmp C/l Inj Isol). _ . 1NI-10B (RNO continued on next page)
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A15000/ES-1.1 70f76 7 of 76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (Continued)
- 10) IF 1 NI-9A OR 1 NI-1 OB cannot be closed, THEN dispatch operator to close affected valve{s). REFER TO the following enclosure(s) for affected valve(s):
- Enclosure 7 (Locally Close 1NI-9A)
- Enclosure 9 (Locally Close 1NI-10B).
- 11) Throttle charging and seal injection to maintain the following:
- Charging line flow between 60 GPM and 180 GPM
- NC pump seal injection flow.
_ 12) GO TO Step 11.
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/11A15000/ES-1.1 EP/1/A/5000/ES-1.1 80f76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (Continued) b.~eri6~:m)e~fbncm*'fr~'\lalves'~:CDHEN
- b. " ,JY, h~~ ,,~,,',' I g",~,~"""",~, " ': b. Perform the following:
* ~1f)JV"4Q~A (N)Z*PumpJ A&Bigecirc _ valve{s) .
- 1) Open affected valve{s).
!§Pl)
_ 2) IF 1NV-203A AND 1NV-2Q2B are
.1 m~:-202:~{NV:jErnps;f\~B R~~ir9 open, THEN GO TO Step 9.c.
IsQD*
- 3) Dispatch operator to open affected valve(s):
_ .* 1NV-203A (NV Pumps A&B IF 1NV-203A was closed earlier due to low Recirc Isol) (AB-554, HH-JJ, NC system pressure per enclosure 1 of E-O, 54-55, Rm 231) (Ladder needed) or E-2 they will go to the RNO and open it.
- 1NV-202B (NV Pmps A&B Recirc Isol) (AB-554, HH-JJ, 54-55, Rm 231) (Ladder needed).
_ 4) Close 1NV-309 (Seal Water Injection Flow).
- 5) IF control of 1NV-309 is lost from the control room, THEN dispatch operator with radio to perform the following:
_ a) Close 1NV-308 (Seal Wtr Inj Flow Ctrl Isol) (AB-554, JJ-54, Rm 233) (Ladder needed). _ b) Throttle 1NV-311 (Seal Wtr Inj Flow Ctrl Byp) (AB-555, JJ-54, Rm 233) to control seal injection flow as required in subsequent steps.
- 6) Open the following valves:
- 1NV-312A (Chrg Line Cont Isol) 1NV-314B (Chrg Line Cont Isol).
- 1NV-314B (RNO continued on next page)
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A15000/ES-1.1 EP/1/A/5000/ES-1.1 90f76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (Continued)
- 7) IF 1NV-312AOR NV-312A OR 1 NV-3148 NV-314B cannot be opened, THEN dispatch operator to open affected valve{s).
valve(s). REFER TO the following enclosure(s) for affected valve(s):
- Enclosure 8 (locally Open 1NV -312A)
NV-312A)
- Enclosure 10 (locally Open 1NV-314B).
NV-3148). _ 8) Do not continue in this procedure until 1NV-312A and 1NV-314B NV-3148 are open. _ 9) IF NC pressure is greater than 1950 PSIG, THEN throttle 1NV-309 or 1 NV-311 to 50% open. _ 10) Open 1NV-294 (NV Pmps A&8 A&B Disch Flow Ctrl).
- 11) IF control of 1NV-294 is lost from the control room, THEN:
_ a) Place the controller for 1 NV-294 in the 100% demand position. _ b) Dispatch operator with a radio to throttle 1NV-295 (NV Pmps A&B 8 Disch Ctrllsol) Ctrl Isol) (AB-551, (A8-551 , JJ-55, Rm 231231)) to control charging flow as required in subsequent steps.
- 12) Close the following valves:
- 1 NI-9A (NV Pmp C/l Inj Isol)1501)
OB (NV Pmp C/l Inj Isol).
- 1NI-1 08 1501).
(RNO continued on next page)
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A/5000/ES-1.1 10 of 76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (Continued)
- 13) IF 1NI-9A OR 1NI-1 OB cannot be closed, THEN dispatch operator to close affected valve(s). REFER TO the following enclosure(s) for affected valve(s):
- Enclosure 7 (Locally Close 1 NI-9A)
- Enclosure 9 (Locally Close 1 NI-1 OB).
1NI-10B).
- 14) Throttle charging and seal injection to maintain the following:
- Charging line flow between 60 GPM and 180 GPM
- NC pump seal injection flow.
_ 15) WHEN 1NV-203A AND 1NV-202B are opened, THEN charging flow may be reduced below 60 GPM. _ 16) GO TO Step 11. c. c.Q!O:§~ th&~fondW1X~g vaIV§s: c. Dispatch operator to close affected valve(s). REFER TO the following enclosure(s) for affected valve(s):
- Enclosure 7 (Locally Close 1NI-9A)
- Enclosure 9 (Locally Close 1NI-10B).
SCENARIO MAY BE TERMINATED ANYTIME AFTER THIS STEP
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A/5000/ES-1.1 11 of 76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1O. \§~~iiJ?U~lrcn~tging'a~ifol~qW~: a.,Vetin~ /'" " "))!,&1~", ""', ',~1 '" ,9",;;Valves"'l%
':1, all"on?'"'~fC)no'W;in "'" J"" "',
- a. IF all the valves are closed, THEN OPEN~ perform the following:
_ * "1NVm4'~'(NG'P~;S'TS
","\,'0"';"1> ,"",:(,;mp;:,,,£" ~e," JIPP """" r'~"t; _ 1) Open 1NV-309 (Seal Water C(1rT'{sol,).
""""[l,","",,,, Injection Flow).
_ t~ if1N\l~5:5A,
."'"5""",,,,'",,", ( NGIBm
""," p"mSeal'B.u"
,",", "" "',,, pp,y 'I""" _ 2) IF control of 1NV-309 (Seal Water
~()l'it;I§'Qn Injection Flow) is lost from the control room, THEN dispatch
_
- f11IN\I.";(3(3&(NC;;~rhp G$eal p"l.1pply operator with radio to open 1NV-311 gpnt;I~~O (Seal Wtr Inj Flow Ctrl Byp)
(AB-555, JJ-54, Rm 233).
- ltl1V-:7'Z!~(NCBrhp Dpeal§l.1pply
~Orlt ;IsQ!j: 3) Open the following valves:
_ . 1NV-312A (Chrg Line Cont Isol) 1501) _ . 1NV-314B (Chrg Line Cont Isol). 1501).
- 4) IF 1NV-312AOR NV-312A OR 1 NV-314B cannot be opened, THEN dispatch operator to open affected valve(s). REFER TO the following enclosure(s) for affected valve(s):
valve{s):
- Enclosure 8 (Locally Open 1NV-312A)
NV-312A)
- Enclosure 10 (Locally Open 1NV-314B).
_ 5) Throttle 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to maintain charging flow less than 180 GPM.
- 6) IF 1NV-294 cannot be operated from the control room, THEN:
_ a) Place the controller for 1NV-294 in the 100% demand position. _ b) Dispatch operator with a radio to throttle 1NV-295 {NV(NV Pmps A & B Disch Ctrllsol) Ctrl Isol) (AB-551, JJ-55, Rm 231) to maintain charging line flow less than 180 GPM. (RNO continued on next page)
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/Al5000/ES-1.1 EP/1/A/5000/ES-1.1 12 of 76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (Continued)
_ 7) GO TO Step 11.
- b. n~J;irQttt~;%~;t)!V"?~4J,f{NV;ilgOlpS;&~S<Di~fh b. Perform the following:
;FIQwCm5'f:pr 34&~Pty1J9~argirj@jlina*
fIQ~. _ 1) Place the controller for 1NV-294 in the 100% demand position. _ 2) Dispatch operator with a radio to throttle 1NV-295 (NV Pmps A & &B Ctrl Isol) (AB-551, JJ-55, Rm Disch Ctrllsol) 231) for 32 GPM charging line flow. _ 3) Throttle 1NV-295 to control charging flow as required in subsequent steps.
- c. c:;lq$e1 N,\f~~09(S,~al W?J~rlrij~j3ti9n c. Dispatch operator with radio to perform 1?19l¥)* the following:
_ 1) Close 1NV-308 (Seal Wtr Inj Flow Ctrl Isol) (AB-554, JJ-54, Rm 233) Ctrllsol) (Ladder needed). _ 2) Throttle 1NV-311 (Seal Wtr Inj Flow Ctrl Byp) (AB-555, JJ-54, Rm 233) to maintain 32 GPM seal water flow in subsequent steps.
- d. d. Dispatch operator to open affected valve(s). REFER TO the following
- 1b1V-:312~{c;bJg'UfleContl~9,O enclosure(s) for affected valve(s):
.1~\f:::3h1S (QmJ@ l;iq¢<CQnt;lgol):
- Enclosure 8 (Locally Open 1NV-312A)
- Enclosure 10 (Locally Open 1NV-314B).
- e. VerifY,.1NV:{~09:7;:l\BLE*T.O'BE e. GO TO Step 10.g.
OPf;RA1f;PFJ~~ty1 JJ-f~CQt:{f:ROL aQ.QMi
- f. PJJ;l,~g~;~}N~~~@;~~ti'~Qtq:
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A15000/ES-1.1 EP/1/A/SOOO/ES-1.1 13 of 76 Rev 2SDCS 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1O. (~Qntih4~~1 g,:perfbYmth~followJD9:
- MaiD~ail11f~bA~rgi,tJ9;JI()w,J,~~? ftl;;l,Ji\l 1~Q~<?PM~
'~.: Mainlainl~21(3PM j,".',,,,~>,>,., .., ",~ ,
tsea[(water~nQW;
.'"., .J)=flM."'>""'~~N:N">."<>."'''' > , ,&~"',,~
- a. ~~QJr91. Q!rargiIjg::llow¥tQ~rfj:aIO:!§)fj:B,?,;tl l~¥~J.*§~~I;,jJg~.
b..'~~rif:Y.!P~9J~yel{£1P1J~{?l:::E.~~.Ii!. b b. Perform the following:
!NCf~J~t'-&I~<?*
_ 1) IF any S/G is faulted, THEN do not continue until faulted S/G depressurization stops OR Pzr level can be maintained stable or increasing.
- 2) IF no S/G is faulted OR Pzr level continues to decrease after faulted S/G depressurization stops, THEN perform the following:
a) Open the following valves:
- 1 NI-9A (NV Pmp C/l Inj Isol)
_ . 1NI-10B (NV Pmp C/l Inj Isol). b) Close the following valves:
- 1NV-312A (Chrg Line Cont Isol)
- 1NV-314B (Chrg Line Cont Isol).
_ c) GO TO EP/1/A15000/ES-1.2 EP/1/A/SOOO/ES-1.2 (Post lOCA Cooldown And Oepressu rization). Depressurization).
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/A/SOOO/ES-1.1 14 of 76 25DCS Rev 2SDCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12.il~lj~:~~iOl!Ulgi1l§';i~l~i:lilt!l~q'§I~'lIlINl
- 12. Y~rjfycon~itipnsi~te m~;tto stoPfNI~
!Rglirl'§i~§i::fgIIR~§;;i PtlmR§,~i:;,fgJlpws!;
- a. Vgrity thefQ!J()wing¢9J'ldil,pTIs\<{[~ a. Perform the following:
sat!~ried: _ 1) IF any S/G is faulted, THEN do not continue until faulted S/G depressurization stops OR criteria for stopping NI pumps is met. _ 2) IF no S/G is faulted OR conditions for stopping NI pumps cannot be satisfied after faulted S/G depressurization stops, THEN GO TO EP/1/A/5000/ES-1.2 EP/1/A/SOOO/ES-1.2 (Post LOCA Cooldown And Depressurization). b.
- 13. (Ensur~",aU NDRijijip(llJtW,itlf§,y;~{iqtt
~UgQ~n:l:to FVV§~Ti:'STQepI:D3'
CNS SAFETY INJECTION TERMINATION PAGE NO. EP/1/N5000/ES-1.1 15 of 76 Rev 25DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- a. lNg~~,Q9oQ,linm~aSe(ll'Q",Qcore¢,xi~T/C~ a. Perform the following:
-~1~,E~IF~T~At"JO~IJ~
_ 1) Manually start S/I pumps and align valves as necessary to restore NC subcooling. _ 2) GO TO EP/1/N5000/E-1 (Loss Of Reactor Or Secondary Coolant).
- b. Pz(l~yel'- GligAl;"lFI3TI-I.~N'~}1% b. Perform the following:
(20o;4'ACC )}: _ 1) Control charging flow to restore Pzr level to greater than 11 % (20% ACC).
- 2) IF Pzr level cannot be maintained greater than 11 % (20% ACC),
THEN: _ a) Manually start SII S/I pumps and align valves as necessary to restore Pzr level. _ b) GO TO EP/1/N5000/E-1 (Loss Of Reactor Or Secondary Coolant).
Appendix D Scenario Outline Form ES-D-1 2009 NRC EXAMINATION Facility: Catawba Nuclear Station Scenario No.: 2a- Op-Test No.: 2009 D-1 SNAP 142 Examiners: Operators: Initial Conditions:
- 100% power
- EFPD = =25 days
- Boron Concentration is 1348 ppm Turnover:
- 1CFP5600 (1 D S/G Narrow Range Level Ch #2) failed 2 hours ago. IAE repairs are in progress and estimated to take 4 hours. All TSAIL entries have been made.
- Reduce power to 87% for control valve movement test to be done by the next shift per OP/1/A/61 001003 (Controlling Procedure for Unit Operation), Enclosure 4.3, Unit Operation Between 85% and 100% Power.
Event Malf. No. Event Event No. Type* Description 1 BOP N Borate for power decrease (DCS) 2 RO R !rods as necessary Power reduction using turbine in auto lrods 3 SRO TS 1B S/G WR level fails low (TS call only) 4 BOP C RN Strainer 1A high DIP, backflush does not operate SRO TS 5 RO C Generator voltage regulator fails voltage low 6 RO C Loss of condenser vacuuml reduce load with turbine in manual 7 BOP C PZR Spray valve 1NC-27 fails open with no manual control SRO TS 8 ALL M Tube rupture on 1A S/G Additional Failures Failure of automatic feedwater (CF) (OF) isolation Failure of 1NI-9 1NI-1 0 to automatically position 1NI-9 and 1NI-10 S/G PORV 1SV-19 fails open
*(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
SIMULATOR SETUP Reset to 100% BOL snap Roll Charts Provide a boration/dilution plan Clear EHC alarm and any OACI 1.47 bypass alarms Sign off OP/1/A/61 001003 enclosure 4.3 thru step 2.13 (students start at 2.14) MALFUNCTIONS. REMOTES. and OVERRIDES Malfunction # Description Value Event Ramp Delay Trigger MAL-IPE003B PZR SPRAY VLV NC-27 FAIL, NO 100 7 60 MAN CTRL MAL-ISE007A AUTO CF ISOL SIGNAL TRN A BLOCK MAL-ISE007B AUTO CF ISOL SIGNAL TRN B BLOCK MAL-MT003 LOSS OF CONDENSER VACUUM 0 11 300 (VLV LEAK) MAL-MT003 LOSS OF CONDENSER VACUUM 25 6 (VLV LEAK) MAL-MT010 GLAND STEAM REGULATOR 0 15 15 FAILURE (TL3) MAL-MT012 EXTRACTION STEAM SEAL 0 15 15 REGULATOR FAILURE (TL 10) I \ MAL-RN002A RN STRNER 1A HI DIP 0 12 5 MAL-RN002A RN STRNER 1A HI DIP 100 4 60 MAL-RN002A RN STRNER 1A HI DIP 0 14 5 Del in 1 MAL-RN002A RN STRNER 1A HI DIP 100 10 60 MAL-SG001A S/G A TUBE LEAK 650 8 MAL-SM002A S/G PORV SV19 FAILURE 100 9 5 OVR-EGB004C VOLTAGE ADJUST RAISE PB OFF 5 OVR-EBG004C VOLTAGE ADJUST RAISE PB OFF 13 Del in 1 OVR-EGB004D VOLTAGE ADJUST LOWER PB ON 5 Del in 8 VLV-NI001A NI9A B.I.T. DISCHARGE ISOL VLV FAIL AUTO ACTIONS VLV-NI002A NI10B B.I.T. DISCHARGE ISOL VLV FAIL AUTO ACTIONS VLV-RN061F VLV-RN061 F RN30A RN STRAINER A BCKWASH 0 ISOL FAIL TO POSITION XMT-SG016 LCF_5600 S/G 1D N/R LVL CH2 TO 0 DCS/MCB/OAC (CFAA5600) XMT-SG094 XCF_5620 S/G B W/R LVL CH 2 TO 0 3 DCS/OAC (CFAA5620)
XMT-MT011 PTL_5000 TURBINE SEAL STEAM 3.2 HEADER PRESS MTR XMT-MT011 PTL_5000 TURBINE SEAL STEAM 0 15 15 Del in HEADER PRESS MTR 2 EVENT TRIGGERS (other than manual) Event Description Trigger 9 jpplp4(1) I jpplp4(2) (Reactor Trip either train)
-<Reactor 10 jpplsia I jpplsib (Safety Injection either train) 11 rtlh004>0.035 & & x01 d047m>1.1 (TL4 not closed and Steam Seal Header Pressure> 1.1 psig) 12 X11 i038f X11i038f pump off button depressed)
(1A RN pump 13 X01i135m (Voltage Regulator in manual) 14 X11 i038f & & jpplsib &
& !jpplsia (1A RN pump off button depressed and B SI and no A SI) 15 SMSS < 1165 (MW less than 1165)
( CRITICAL TASKS (See attached documentation) E-O 1- Establish flow from at least one high-head ECCS pump before transition out of E-O. feedwater E-3 A - Isolate feed water flow into and steam flow from the ruptured S/G before a transition to ECA-3.1 occurs. QUALITATIVE ATTRIBUTES Required Actual Total malfunctions 5-8 8 Malfunctions after EOP entry 1-2 3 Abnormal events 2-4 4 Major transients 1-2 1 entered/requiring substantive actions EOPs enteredlrequiring 1-2 1 EOP contingencies requiring substantive actions 0-2 0 Critical tasks 2-3 2 REFERENCES
OP/11A161501009 (Boron Concentration Control) revision 068DCS OP/11A161 001003 (Controlling Procedure for Unit Operation), Enclosure 4.3 revision 106DCS OP/1/B/63001001 (Turbine Generator) revision 091 AP/0IAl55001020 AP/OIAl55001020 (Loss of Nuclear Service Water) revision 037DCS AP/11A155001037 (Generator Voltage and Electric Grid Disturbances) revision 000 AP/11A155001011 (Pressurizer Pressure Anomalies) revision 022DCS AP/11A155001023 (Loss of Condenser Vacuum) revision 018 EP/11A15000/E-0 (Reactor Trip or Safety Injection) revision 036DCS EP/11A15000/E-3 (Steam Generator Tube Rupture) revision 034DCS OP/0IAl64001006C OP/OIAl64001006C (Nuclear Service Water) revision 266 NOTES AND INSTRUCTIONS NOTE: The following steps are GUIDELINES. The NRC lead examiner will direct timing of events unless otherwise noted. NOTE: Any groups or individuals (IAE, RxGrp, RP, SOC, SWM) that are called to I/R IIR a problem or for simple notification of a problem, repeat back the information they provide unless otherwise noted. NOTE: Any operators dispatched should repeat back information provided. Call back items are listed below when necessary for the scenario. Event 1 - Borate for power decrease This event will be entered once the crew has taken turnover and evaluated plant conditions. ( When the first boration batch has been completed, the next event can be started. Event 2 - Power reduction using turbine/rods as necessary When turbine power has been reduced by 3-5 MW, the next event can be inserted. Event 3 --1B1B S/G WR level fails low, SRO Technical Specification Initiating Cues:
- 1AD-2 alarms F/10 (DCS alarm screen shows actual alarm)
TS 3.3.3 Item 21, Conditions A, C Event 4 - RN Strainer 1A high D/P, DIP, backflush does not operate, SRO Technical Specification Initiating Cues: Al1,, Al2, Al5, C/2 1AD-12 alarms Al1
- 1AD-12 When AP/0/Al55001020 AP/OIAl55001020 is completed and the SRO has completed consulting Technical Specifications, the next event can be inserted.
TS 3.7.8 Condition A If asked to check out RN pump 1A 1A and/or breaker state, after 10 minutes state "Nothing
unusual was noted." If asked to check on RN pump 1B following the state, state "It appears to be operating normally." Event 5 - Generator voltage regulator fails voltage low Initiating Cues:
- OAC alarm C1A0567 (Unit 1 Generator Volts) - LO At Step 17, when the SOC is contacted for guidance on adjusting generator voltage state "Adjust voltage per the Voltage Schedule".
AP/1/A/55001037 is reached, the next event can be entered. When step 18 of AP/1/A15500/037 Event 6 - Loss of condenser vacuum Initiating Cues:
- 1AD1, F/7
- OAC alarm C1A0734 (Condenser C absolute backpressure)
- Turbine MW decreasing When load has been reduced to -1165 per AP/1AP/1/A/55001023, I A15500/023, TL pressure will fail to 0 per EVENT 15. Once the crew begins adjusting 1TL TL-4,
-4, EVENT 11 will trigger which will make the leak smaller and go away completely after a few minutes so that vacuum recovers.
( Event 7 - PZR Spray valve 1NC-27 fails intermediate with no manual control NOTE: If the spray valve failure is not dealt with quickly, the reactor will trip and in that case, EVENT 8 should be immediately triggered. Initiating Cues:
- 1AD-6, F/8 FIB
- OAC alarm C1 L4455 (Normal Pressurizer Spray Flow Activated)
When AP/1/A15500/011 AP/1/A/55001011 is completed and the SRO has completed consulting Technical Specifications, the next event can be inserted. This will begin the major event. TS - 3.4.1 Condition A (based on NC pressure at the time)
Event 8 - Tube rupture on 1A S/G Initiating Cues:
- 1RAD-1, 8/1, 8/4, E/5
- 1RAD-3, E/5 This is the major event.
Additional failures
- Failure of automatic feedwater (CF) isolation
- Failure of 1NI-9 and 1NI-1 0 to automatically position
- S/G PORV 1SV-19 fails open Scenario End Point ANYTIME AFTER SAFETY INJECTION IS TERMINATED PER EP/1/A1S000/E*3 EP/1/A1SOOO/E*3 Step 2S.c.
j,
CREW TURNOVER INFORMATION Initial Conditions:
- 100% power
- EFPD =25 days
- Boron Concentration is 1348 ppm Turnover:
- 1CFP5600 (10 (1 D S/G Narrow Range Level Ch #2) failed 2 hours ago. IAE repairs are in progress and estimated to take 4 hours. All TSAIL entries have been made.
- Reduce power to 87% for control valve movement test to be done by the next shift per OP/1/A/61 001003 00/003 (Controlling Procedure for Unit Operation), Enclosure 4.3, Unit Operation Between 85% and 100%100% Power.
(
OP/l!A/6150/009 OP!l/A/6150/009 Page 2 of4 Boron Concentration Control
- 1. Purpose To describe the operation of the Boron Concentration Control System.
- 2. Limits and Precautions 2.1 This procedure is Reactivity Management related because it controls activities that can affect core reactivity by changing boron concentration. (R.M.)
2.2 The following Limits and Precautions are Reactivity Management related: (R.M.) 2.2.1 When changing the boron concentration of the NC System, closely monitor the following for expected indication:
- Rod motion Rodmotion
- T-AVG
- Nuclear instrumentation 2.2.2 When performing dilutions at or near 100% power, batch additions to the VCT (instead of continuous dilution at low flow rates) are the preferred method. {PIP C99-0587}
2.2.3 If the NC System is filled and vented and the boron concentration is being reduced in the NC System, at least one NC pump shall be in operation, recirculating the NC System. {PIP C99-2510} 2.2.4 If the boron concentration is being increased in the NC System, at least one NC pump or one ND pump shall be in operation, recirculating the NC System. 2.2.5 Following an increase or decrease of the NC System boron concentration of
~ 50 ppm, pressurizer spray shall be operated to equalize the boron concentration throughout the system.
2.2.6 When the reactor is subcritica1 subcritical and dilution is in progress, if the Nuclear Instrumentation increases by a factor of two, secure the operation immediately and evaluate the cause. 2.2.7 If the unit has operated continuously for several months, significant Boron 10 depletion may have occurred. The effective boron concentration of the NC System may be lower than indicated by Chemistry samples. NC temperature shall be carefully monitored following VCT makeup. 2.3 During continuous dilution operations, sample the NC System H2 concentration every evelY eight hours.
OP/l!A/61501009 OP/l!A/6150/009 Page 3 of4 2.4 When manually operating any motor operated valve, minimize the torque applied to the handwheel. 2.5 After manual operation, maintenance or packing adjustment of any motor operated safety related valve, it shall be cycled electrically to ensure reliable automatic operation. 2.6 With the "NC MAKEUP MODE SELECT" switch in the "DILUTE" position, the makeup flow rate is limited by letdown flow, the VCT spray nozzle, and VCT pressure. The maximum expected makeup flow rate is approximately 95 gpm. 2.7 With the "NC MAKEUP MODE SELECT" switch in the "ALTERNATE DILUTE" position, the maximum expected makeup flow rate is approximately 130 gpm. 2.8 With BAT boron concentration greater than or equal to 7200 ppm, it is recommended that only manual makeup be performed when the NC System boron concentration is
~1300 ppm. Automatic or manual makeup can be used when NC System boron concentration is < 1300 ppm. {PIP 03-7305}
2.9 With BAT boron concentration less than 7200 ppm, it is recommended that only manual makeup be performed when the NC System boron concentration is:::: is::: 1250 ppm. Automatic or manual makeup can be used when NC System boron concentration is
< 1250 ppm. {PIP 03-7305}
- 3. Procedure Refer to Section 4 (Enclosures).
- 4. Enclosures 4.1 Automatic Makeup 4.2 4.3 Dilution 4.4 Alternate Dilution 4.5 Manual Operation Of The Makeup Controls 4.6 Operation Of The Boric Acid Transfer Pumps In Miniflow 4.7 Placing Boric Acid Tank #2 In Service For Unit #1 4.8 Valve Checklist 4.9 Rapid Boration
BOP DOES THIS Enclosure 4.2 OP;1/A/6150/009 Boration Page 1 of3
- 1. Initial Conditions o 1.1 1.2l 11: .*1) IF;j'nM{ide*.1;!W2,~11~f.if~;~t~acti;¥~~m@.agelll~fttjgQIlfrQl$Y~taoli§h¢q;~fSQMBimz:02.
(R~~(;tix~lY' M~Ilagerii~ht)}7*(~*M~J oOl;~\ V e~Jf5f,:§Yf&Qt~i!p!g;IM9~'l!l,ll~i~~ix~1:a.bI~ t~i~~gety~the f$i~c{pf:~Qglant!i!i,ifu1u,pe<:l duringtJ;te pI~l1n~Kl1ll1pt~tl~11~R~~t10t1':':
- 2. Procedure
~;()TE:*** *'fp.is:~~~lQsut~;iWiU"~Ii~cttei9tiMi.t£;&Qflthe~m:~l;!lQ:!d'i$:~hk~t~f6i'§;!~¢$~~'!tedimporta4t lB' B-¢acgIrit£ MahiIgelll~llt Pkt)the\Wq~llne§:bfN,~l'},1304!5(B:e~¢!ivi~ Man~ement). ,IR.MJ o 2:1 2.2 o ilNY,i~?~[l\ eml\XiferPmfiToijI6h<.let;yCtrl) 01 NY";.'tS6A(I31Aijlenc1¢tO tlt1;pVCl1>Otlt) o 2.3 o 2.4 o 2.5 2.6 'IFiID~.QI§Ild~~it~ A~t\fllfQ~jii!lJtoiji~119malS'ill,.pperl.I2n91g~ure 4H (AlltQmati!{,:t¥al<eqp), recqrd th~;(§et1?!lllIirf;[f!the9'iD;ttgn~f*:t:~t!if!~";.2J~8FtijlFii&fefrrriniff,g1:§l@i1:@Jii~nt';I, ,.*,1gplJl' o 2.7 o 2.8 o 2.9
Enclosure 4.2 OP;1fAf6150/o09 OP!lfAf6150f009 Boration Page 2 of3 2.10 D INV-;g~,~.5\ (iI3Y5\\l~t:y!;)jl,11:l5 ~rI31~~Q~rJJtrJ) D JNV~\i$f12'\~(l3fA';Blel1fl§:I~iOt~t1(9>V~~~jQtW D 2.12 2.13 WHEN.;tIi~fg:e~Y<:l.;Y{lumeqfbqiig~c.iC:\is;f:~l!:~ll'~P;:o~tlIe;tmit~acid~at~tli:coUfif~t~ensqi;¢) the1({I!QwjiIg iYa,~\@$,a9se:;{:R*M;)\ D .1~~23.~5\JBI2'\;)~fer P:w TO\BlenQ~X;; CtI!~ D ti~~I~'~~(B/~\Blend:eK~OtltW:P vCrOtIt)l NH:rE:~ ':Ifadai,tiQna:~;J?'Qf~tio~'(§:Fill.lj~[*Petfg.e4§ve~*t1t~~~ot.fiS~'9t!t!.(~~~tliff,'fl;ushmg*themaK~p.p. line j$Nm"E?t~9;Q}:llm~utiedJ; 2.14 IF desired, flush the makeup line as follows: Flushing should not be 2.14.1 Open the following valves: desired at this time. D INV-242A (RMWST To BfA Blender Ctrl) INV-186A (BfA Blender Otlt To VCT Otlt) D 1NV-186A D 2.14.2 Ensure one reactor makeup water pump is in "ON". 2.14.3 WHEN ~ 20 gallons of makeup water have been flushed through the makeup line, close the following valves: D INV-242A (RMWST To BfA Blender Ctrl) D INV-186A (BfA Blender Otlt To VCT Otlt) 2.14.4 Place the following valve control switches in "AUTO": D INV-242A (RMWST To BfA Blender Ctrl) D INV-186A (BfA Blender Otlt To VCT Otlt) 2.14.5 IF NOT required for current plant operation, place the reactor makeup water pump started in Step 2.14.2 in "AUTO".
Enclosure 4.2 OP/l!A/6150/009 OP;l/A/6150/009 Boration Page 3 of3 Page30f3 2.15 2.15.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup). OR 2.15.2 oD 2.15.2.1 ~ps,urej,th~;i:¢ql1tl~11~tI:9rfa~~~8~;(J3/A\~fst[l?ar)' Tmf3Ll,l;1qerl:Ctt,zl~: i§~:§e! tQ'~li"~'1¥~~1!~il'ecJirrg~p.;inl;~!~R)~I?;~!i(~~;.M:~J o 2.15.2.2 D oD 2.15.2.3 P;li~'l@,~it~&;~~W'&Q;tfrRo:p:l;1~;Wi@iitb @'~uSTI\9;{TII
;pil~~iti!!:~m~Mi'J 2.16 Do NOT file this enclosure in the Control Copy folder of this procedure.
OP/l!A/6100/003 OPll/A/61 001003 PageZ2 of4 Page Controlling Procedure For Unit Operation
- 1. Purpose To describe the operation of the unit between approximately 15% and 100% tull power.
- 2. Limits and Precautions 2.1 This procedure is Reactivity Management relared related because it controls activities that can effect core reactivity by the following: (R.M.)
- Control rod movement
- Turbine load changes
- Feedwater manipulations
- Reactor power changes 2.2 The following Limits and Precautions are Reactivity Management related: (R.M.)
2.2.1 Before returning reactor control to automatic, T-AVG shall be within +/- 1°F of T-REF. 2.2.2 Do NOT exceed rod insertion limits or temporary rod withdrawal limits. 2.2.3 Automatic control rod withdrawal is blocked when Control Bank D ~ 200 steps withdrawn. 2.2.4 The difference in boron concentration between the PZR and NC System is desired to be maintained within +/- 50 ppm. 2.2.5 Axial Flux Difference (AFD) shall be maintained within the allowable limits as defined in the ROD manual at all power levels above 50% reactor power. (Tech Spec 3.2.3) 2.2.6 During a power change, other indications of reactor power shall be observed along with power range and secondary thermal power indications to aid in determining the reactor power level. Using indications like turbine impulse
~Ts, and others may help in detecting the pressure, CF flow rate, NC loop ~Ts, miscalibration of a nuclear instrument.
2.3 In the event of an inadvertent power reduction, it is recommended that the power level NOT be increased until an investigation has been conducted and corrective action taken.
OP/l!Al61 OP!l/A/61 00/003 Page 3 of4 2.4 If reactor control is in manual, maintain T-AVG within +/- 2°F ofT-REF to prevent receiving "T-REF/T-AUCT HIILO" alarm. 2.5 Whenever there is a thermal power change greater than or equal to 15% rated thermal power within a one hour period: (OAC point CIL4790 C1L4790 in alarm)
- Notify Chemistry to take an isotopic analysis for iodine within 2 to 6 hours following the last power change that is greater than or equal to 15% rated thermal power within a one hour period. (T.S. SR 3.4.16.2)
- When thermal power has stabilized, notify Radiation Protection to sample and analyze gaseous effluents. (S.L.C. 16.11-6) 2.6 S/G blowdown flowrate shall NOT exceed a maximum of200 GPM per S/G.
2.7 After a thermal power change when plant conditions stabilize, 1EMF-39 setpoints shall lEMF-39 setpointsshall be adjusted so the Trip 2 setpoint is set at three times the containment activity and Trip 1 setpoint is set at 70% of Trip 2 setpoint. 2.8 If the RC System condenser inlet temperature drops to less than or equal to 60°F when 5SOF when the Rx is critical, the system the Rx is shutdown or less than or equal to 55°F system shall be configured as follows:
- One RC pump running (throttled).
- One tower inlet isolated.
- All three riser bypasses open.
2.9 CIK0628 (CF Flow Venturi Correction Factor) shall be reset to 1.0 when OAC point C1K0628 either of the following conditions are met:
- A step load change such as a load rejection greater than 10% rated thermal power,
- A ramp load change of greater than 15% rated thermal power in a one hour period.
2.10 When the unit is engaged in a power maneuver resulting in a mismatch between OAC point C1P138S CIP1385 (Reactor Thermal Power, Best) and any excore power channel in excess of2% refer to Tech Spec Basis for SR 3.3.1.2. 2.11 The insertion of Control Bank D will affect mismatch between OAC point C1P1385 CIP1385 (Reactor Thermal Power, Best) and the excore power range channels. This is due to shielding of the power range detectors by Control Bank D. Therefore, refer to Tech Spec Basis for SR 3.3.1.2 when mismatch between Reactor Thermal Power (Best Estimate) and the excore power range channels shall be observed to be exceeding 2%. 2.12 The Reactor Engineering Group normally provides information for planned power maneuvers. The OAC xenon predict program can be used to help anticipate dilution and boration requirements. {PIP C99-0587}
OP/l!A/61 00/003 OP/l!Al6100/003 Page 4 of4 2.13 The Steamline N-16 Radiation Monitors (EMF-71, 72, 73, 74) become inaccurate at power levels below 40% due to inaccuracies in the algorithm used to calculate the output of these monitors. {PIP 99-3980} 2.14 It is recommended that Primary Chemistry be notified prior to all significant boric acid additions or dilutions to the NC System such that proper pH control may be maintained. Normal boric acid additions and dilutions should be communicated at the Control Room {PIP C-01-66S} shift briefing. {PIP C-01-665} 2.15 In accordance with INPO best practices when personnel are accessing areas that could experience significant dose rate changes resulting from increasing power, Operations shall maintain Reactor power steady or decreasing.
- 3. Procedure Refer to Section 4 (Enclosures).
- 4. Enclosures 4.1 Power Increase 4.2 Power Decrease 4.4 T-AVG T-AVG Coastdown 4.4.1 T -AVG Coastdown Data T-AVG 4.4.2 Adjustment OfDCS Of DeS ACCEPTED VALUE For T AVG A VG 4.4.3 T-AVG Coastdown Tracking Data (Phase 1 and Phase 2)
T-AVG 4.5 Power Escalation Guideline
Enclosure 4.3 OPIl!A/61 001003 Unit Operation Between 85% and 100% Power Page 3 of6 NOTE: The intent of the following step is to have a more controlled final approach to 100% power. 2.9 WHEN at 99.5% reactor power on CIP1385 CUI Reactor Thermal Power Best), perform the C1P1385 (Ul following: 2.9.1 HOLD power escalation for at least 10 minutes to allow for Xenon and AFD oscillations to be seen. 2.9.2 WHEN at least 10 minutes have elapsed,continue elapsed, continue the power increase. CAUTION: Alternate indications of reactor power shall be monitored to verify reactor power level and help prevent NI miscalibration.
- - 2.10 At 100% thermal power (3411 MWt), compare OAC heat balance point C1P1385 CIP1385 (Reactor Thermal Power, Best) with nuclear instrumentation.
2.11 IF this power increase is from Mode 3, notify Secondary Chemistry to perform a primary to PTIl/B/46001028 (Determination of Steam Generator secondary leak rate calculation per PT/l/B/46001028 Tube Leak Rate for Unit 1) within 24 hours of reaching 100% power. (NSD 513) Person notified ----------------------------
- - 2.12 r:S-::"T~A-::"R=T,........,
-IF required, notify IAE to adjust nuclear instrumentation per Model W10 #00874628.
START Person notified HERE lTl'llmIC." 1.:J:;h~ \~i~li§I'Jj~1ioper@i!lg<<~tt~OO~lp§~~Il~ ,T'lt~.;following.§teps red4ge'poweito~~S,~:
*IJ6wer.
1:~j~'lll[1fJhl ill 2.13 IFtliisisKi'f~1\'YG'Co;:t,stQ()\vJ!~?iPfiintam T~~'Yih~:,2:,Id:!miMgk~I11Wf?tlorPhas~'S 2 at!~
~~clo~llfe4 .4;1::
N/A SROSRO 2i!:14'IF shtill~~.qtilglle,IAj;[eqh.Sp~giI~nsllrethe*)NR~'liasp~eh l}otiti'e4per these 2
*R~l4l~f:5@*O~(Pl~£;(NR~!:Uoti'tiQa:~QJlJt~4!!ire1p.eiits); steps
Enclosure 4.3 OP/liAl61 001003 OP/l!Al6100/003 Unit Operation Between 85% and 100% Power Page 4 of6
;Nq;rE~ The procedY,t~,m~Y conti1.1lle whHeperfonning St~117.15I 2 . 15 is 1_ _ 2.15.1 Declare 1EMF-48 lEMF-48 inoperable.
12.15 N/A 2.15.2 Close 1NM-26B INM-26B (Hot Leg Smpl Smp1 Heir Hdr Cont Isol). Iso1). Record time 2.15.3 Notify NotifY Primary Chemistry and RP Shift that 1EMF-48 lEMF-48 has been isolated: RP Shift person notified. notified____________________ Primary Chemistry person notified. ___________________ notified'----_ ________ __
,NOTE::.! .QUring a l}-~yG. Coast4pwn "'hei,i,:'!a;lturQitj~!l§a4reductibli\:bi~~~a;mptessure jn~:rease ($.~fe!y valve testmg,);;is requesf¢d wit~:t,h'!<iWrb!tje;:co1:ltfOFvalV~s.2a)§i9rt:4@~r wide:open,.the 10g\i!j
<lycrease ",nUNOT belilIea.r withtKa!tve r.~f~f¢1.1ce (demaUdJ:l!1em-~:~~e. 1:his is4ue toJlj:e .flow characteri~tic':()f the turbine coritto,~y~~I"es:lJA'Qa4:i~ncreaseldecte~~.::isJinear "1@;deman\:!
increase!d~crease fr9~!!:lppr9ifimatelyaO% '\!:t>',~q~::ta1"e refel~enc~~ijAFD osc;ill~tions sh;bultl be expeCted. (07-~$299\ 2.16 CAUTION: CAUTI ON: I.. Wen $e IltUt{~~:eng~:ged iff ~RPw¢~tmaU~J,i"tyr.:resulting!tji:t mismatc../,lbe~~~n q~c; pg~nt,.G;~gil3,"8,~m.\ea:9rQr.Theiilif~IPq;wet,?B~~n,and any ex:core po",et:~~hanti~rin
'i~X:~e.§~ilQf::~%;re~~~> t5<*Tech Sp{¢9Ba'sis for~:g>$.3.1.2,~,
2t * * . .indic~tions Alternate ()fre#it'9:rPQ~~.h~# be monitor~i4:to
'. . ."!I.IIIII.II.IEl'1lIllJL an4m~lp pr~},;;~Ii:t NIWJ~~cal:!b,t<!t!q!l~
_.Will*!*,MWlllll
*'I'.....
. . . . y~rify reactdrt:>ow~r Jev~J' 1IIIJIIII
- - 2.18 'IF ~n:pw¢t;,;Q~er&'l!I:~¥:.oflfiiDxethan. gQ% *. reactor.poW1~tis pl~pIiyg~. issg~;~'i4,~I'>>'l~'
#9IT~1A6'28%J~9;~JAEIo prevent theiml§ma!sh .q.e~yeil 'OAGij.e~IQal~~,pI'iilct 2.18 is C IP 1385:(R:eaCtorTh;efmal&pw~iriJ:3¢s!ft~Wlg.rany.~xcore pow~r'~ha;D~I:exce~4illg 2%J; N/A
Enclosure 4.3 OP/l!A/61 001003 OPIl!A161001003 Unit Operation Between 85% and 100% Power Page 5 of6 NOTE: :1',@fi,~ followU!g ntilig(;l1eiliist]:y ~~mples~~RMlfig;t~qtie$tY120 days to refueling G4~misttylQ¢fsoJl;;ilp.tifi~g '*if' f, ,j"lj{.;I,~)J;!* 2.21 NOTE: 2.22 IF shutting down for an outage where condenser vacuum will be broken, at approximately 85% turbine power (~1 (~1003 003 MWe) complete the Heater Vent Orifice Return to Service Valve Alignment enclosure of OP/l/B/62501004 (Feedwater Heaters, Vents, Drains and Bleed ofOPIlIB162501004 System).
OP!l/B/63 00/00 1 OP/l!B/6300/001 Page 2 of5 Turbine Generator
- 1. Purpose To describe the proper method for operating the Turbine-Generator.
- 2. Limits and Precautions 2.1 This procedure is Reactivity Management related because it controls activities that can effect reactivity. (R.M.)
2.2 Low load operation limits: 2.2.1 The unit can be operated continuously at low loads when exhaust hood temperature is < 175°F. The load shall, however, be increased slowly until the temperature decreases below 125°F before increasing load at normal rate (Multipoint Recorder on 1MC3). IMC3). 2.2.2 Limit turbine/generator operation below 5% load to 1 hour to prevent moisture erosion unless directed by the Turbine Engineer for testing 2.2.3 Motoring of the unit is to be avoided. 2.2.4 Excessive use of the exhaust hood sprays shall be avoided to prevent accelerated blade erosion. 2.3 Journal bearings shall NOT be operated with metal temperatures above 250°F (OAC Turbine Bearings graphic (TGBRG)). 2.4 Lube oil cooler discharge temperatures shall be lOO°F to 120°F when at rated speed. 2.5 The lube oil temperature rise shall NOT exceed SO°F 50°F on the main bearings and 45°F on the thrust bearing. 2.6 Under no conditions shall the thrust bearing be operated above 190 0 P metal temperature 190°F (OAC Turbine Bearings graphic (TGBRG)). 2.7 Never allow a hot rotor to stand without rolling. If and when a hot rotor was allowed to stand still, when possible rotate the shaft 180° and allow to stand still again for one-half the time it first stood still, and then put the turbine on turning gear. 2.8 The minimum allowed cold gas temperature is 86°P 86°F for operation. The maximum cold gas temperature is 122°F. (OAC points CIA0522C1AOS22 (Cold Gas from Hydrogen Cooler Turbine End) and C1A0528 CIA0528 (Cold Gas from Hydrogen Cooler Exciter End), Main Generator graphic (MAINGEN)).
OPI l!B/63 00100 00/00 1 Page 3 of5 2.9 Do NOT exceed the load, hydrogen pressure, and power factor limits per the Unit One Revised Data Book Figure 43. 2.10 If the limits of the Unit One Revised Data Book Figure 43 (Generator Capability Curves) are exceeded, the Turbine Generator shall be tripped. 2.11 The generator shall NOT be operated without excitation. If the generator is operated without field, the unit shall be immediately tripped off the line and shutdown for inspection. 2.12 Following a trip-out due to differential phase relays, both the armature and field windings shall be meggered and inspected before attempting to resynchronize. 2.13 Do NOT allow turbine generator speed to exceed 2000 rpm on overspeed tests. 2.14 The turbine shall NOT be operated with condenser vacuum less than 24.3 inches Hg. 2.15 The maximum differential pressure between adjacent LP shell pressures shall NOT exceed 2.0 inches Hg. (main condenser vacuum gauges on 1MC13, IMC13, OAC points C1P1669 (DIP between A & B Condensers) and C1P1670 (DIP between B & C Condensers) or Main Condenser graphic (CMCOND)). 2.16 Do NOT hold the turbine at speeds < 800 rpm for more than 5 minutes. 2.17 When steam seals are on the turbine, the steam packing exhauster shall be operating, and the turbine shall be on turning gear. The turbine may be taken off gear with steam seals established with concurrence from the Turbine Engineer. 2.18 When a condition arises that is serious enough to make a reduction in speed necessary, it shall be initiated by selecting "MANUAL" and "CONTROL VALVE LOWER" or by tripping the turbine. 2.19 Temperature of the LH System reservoir shall be 2: 90°F prior to turbine start (OAC ofthe point C1A0188 (LH TEMP)). 2.20 A sudden downward trend on an LP turbine's lower extraction temperature shall be investigated as a possible indication of water induction into the turbine. This is indicated on the recorder on the rear of 1MC8 labeled "TURBINE WATER DETECTION", using any of the LP 8th stage lower temperatures. 2.21 The time the turbine generator is on turning gear shall be kept to a minimum to prevent the buildup of copper dust in the generator coil slots. 2.22 When system is in "EMERG MANUAL" runbacks and limit circuits may NOT be available. 2.23 Control rods shall NOT exceed rod withdrawal limits. Prior to changing power, refer to Reactor Operating Data Book, Temporary Control Rod Withdrawal Limits.
OP!l/B/63 00/00 1 OP/I/B/63001001 Page 4 of5 2.24 A "LOAD RATE" > "6.2 MWIMIN" shall NOT be used during nonnalload normal load changes. 2.25 The main turbine oil temperature limit of 80 to 90°F shall be maintained when the turbine is on the turning gear. 2.26 Differential temperature between adjacent exhaust hoods shall NOT exceed 30°F unless evaluated and approved by the responsible engineer (Turbine Generator System Expert). (OAC points C1P1667 (A & B Exhaust Hoods Metal Delta Temp) and C1P1668 (B & C Exhaust Hoods Metal Delta Temp) or Main Condenser graphic (CMCOND)). 2.27 During turbine acceleration, the heat up rate of the first stage bowl inner surface (OAC C1P1283 (First Stage Metal Temp Rate)) shall be < 150°FIhr. Point ClP1283 2.28 During turbine acceleration, the rate of change of the reheat steam temperature (OAC points C1P1287 to C1P1292 (CIV No.1 (to 6) Inlet Temp Rate) or Turbine Generator graphic (TG)) shall be < 125°Flhr. 2.29 Any deviations from this procedure that could affect steam admission rates shall require an engineering evaluation to be perfonned performed which specifically addresses partial arc admission. 2.30 The 6.9KV Switchgear Automatic Fast Transfer Switches are placed in the ENABLE position whenever the generator breakers are closed and in the DEFEAT position whenever the generator breakers are open. If an auto autoswap swap of the tie breaker occurs when in the DEFEAT position, equipment being supplied by the 6.9KV Switchgear is more likely to trip than when the switch in ENABLE. {PIP 98-4093, PIP 9S-3589} 98-3589} 2.31 Feedback loops shall NOT be taken in/out of service during turbine control valve movement. Following turbine control valve movement, DEHC shall be allowed to stabilize prior to placing feedback loops in/out of service to prevent unexpected load changes. (PIP 03-5660) 2.32 The Main Turbine OIU Work Station has the capability to perfonn perform control functions for the Main Turbine, including tripping and resetting of the turbine. If a control function window is inadvertently selected while manipulating the Main Turbine OIU Work Station, the window shall be closed to prevent actuation of the control function. 2.33 The Main Turbine shall NOT be run more than 3 hours at 1800 lSOO RPM, no load, unless directed by the Turbine Engineer for testing. 2.34 The Excitation System can affect the functioning of heart pacemakers. Personnel with pacemaker devices shall NOT enter the AVR enclosurelbuilding enclosure/building during operation or testing. If the AVR A VR enclosurelbuilding is NOT installed, personnel with pacemaker devices shall remain at least 20 feet away from the AVR during operation or testing. 2.35 Failure to confinn confirm steam isolation to the turbine prior to opening the generator breaker may result in destructive overspeed of the steam turbine power train. {PIP C-08-501S} C-08-50l8}
opil IB/63 00100 1 OP/1/B/63001001 Page:;5 of5 Page
- 3. Procedure Refer to Section 4 (Enclosures).
- 4. Enclosures 4.1 Turbine Generator Startup 4.2 4.2J"gad C4~gm~f 4.3 Transfer Turbine From Auto Control To Manual Control And Transfer Turbine From Manual Control To Auto Control 4.4 Turbine Generator Shutdown 4.5 Placing (Removing) Core Monitor And Pyrolysate Collector In (From) Service 4.6 Valve Checklist 4.7 Generator Operating Limits 4.8 Turbine Generator Roll Computer Points 4.9 Lamp Verification 4.10 Operation of Turbine TSI Panel 4.11 Reboot of the Main Turbine OIU OIV Computer 4.12 OIU Computer Alarm Switch That Drives the "EHC Fault Transfer of the Main Turbine OIV Annunciator" 4.13 Voltage Regulator Operation From Control Room 4.14 UI Gen Voltage Reg Local Control Panel Voltage Regulator Operation From VI
Enclosure 4.2 OP/liB/63001001 OP/l!B/6300/001 Load Changing Page 3 of4 D 2.1.2.7 Verify new load target appears on Target Display. D 2.1.2.8 Select "GO" and verify it illuminates to start load increase. START HERE D 2.1.2.9 S/G blowdown changes shall be coordinated with Secondary Chemistry. 2.2.1 D 2.2.1.1 D D v~t~~;
.. aly;~li D ow:raws~haU 1>y~djust~g;to obffiifim(~ljh!1in
~oltl'flte.*Ip~d.
~IFC~;;ffill ..... ~lga;;liliJOgiMWEj&~~erif§~*r~M::33 t i(~tri;.;YW#4
Enclosure 4.2 OP/l!B/6300100 OP/l!B/63 00100 1 Load Changing Page 4 of4 2'. l!fnit ()]J,eRea~~qr;Opeigting~~!~, S~glioIl.!i\1sha,11bereferredto f6rallowl1;~r~,ramp raf~~i! 2.2.2 o 2.2.t!f D S~Ieyt n£Q~D R4TE'iatl4.veri~ifr~~1Iiritlat~s. o 2.2.2;g. D rnpu(!hed~§'!f~d IOl!4rate"i* D'i:2.t!3> D Selecf':EN'l1R" an~y~ritMir~:LQ~ ~TE "g9ysdi4~ D'~}2 .2:114: D o i2;~2.4.!§;: D O :.';;"12.16 D i~*"~ *... ~'::.-,,:'
'S' IeGti!:
'e . 'wEN' ,yu:R'*'cn .! '\\i"> ;~\l&)FT'A*R****'***G**E*T"f*;<j:f'* k
......*.. 4'. an,'ii!,tNen"~l!0:l,.' ; }\:;.goe&GH.at'.
D VYuft*neW:lb'ad ~aiget apBearsO~!Ta'rg~t ni~ptay. D s:el~~I:'l~lm'!;~4~'¥:~HfYt~!rtluffitl;!~t~~t1Q~~s~tri*IQad4~.~reas~: . D .' .* ~i&h~~g~~$§j\iH;;B~0~Q,'~&~~~t~Q4W4tlilS:y¢~l)dq~ry\ 2.3 Do NOT file this enclosure in the Control Copy folder of this procedure.
SCENARIO 2 EVENT 3 DATA - 1B SIG W/R level fails low INITIATING CUE: 1AD-2 alarms F/10 (DCS alarm screen shows actual alarm) There is no procedural action for this event; it is a TS call for the SRO only. TS 3.3.3 Item 21, Conditions A, C
Initiating Cues:
- e1AD-12 1AD-12 alarms Al1, Al2, Al5, C/2 ALL STEPS PERFORMED PERfORMED BY BOP
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP101Al55001020 AP/OIN55001020 1 of 52 Rev 37 DC~ A. Purpose
- To verify proper response in the event of a loss 1055 of RN train or normal suction.
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP/OIAl55001020 AP 101N55001020 2 of 52 2of52 Rev 37 DC~ B. Symptoms
*e Case I. Loss of RN Train:
elAP-12"i~j~()f 2A,P~12l;Al1*"RIj. PU.MIi. Alffg1QWM1ZL01!;ti~IT e iA!i~12iWgor 2J\Q*:12.~2 "RN: ESS:E;NTIJ\~HDRAPRESS:URq~*;-.I,.O"~;L1T
*e 1AD-12, Al4 N4 or 2AD-12, Al4 N4 "RN PUMP B FLOW HI/LO" - LIT e 11.JV.r::\So12 N51Dw~"/l2An:1"'2: N'5'wRN:!if'1c"SSENTIALlI:4DR
.~~ g~ .. ~} . J :" fut ...Hi~, . ~t~<;.,>. ", .. '" -.,.-,<<.,,>./1~;: .' 1,." .. , : ... )Jf. . fr4;~,u*. c B::oRES*S.:1z1DPfj:...
L"O* ':311.iIT' H X;~{t-,~.. . :... :"",'d/",E},'"-#:R..:.,.,: .'.C ":.;.)t~~,< o c en :1AP~12, C/2::QC?AQ~,~;;;GZ~~~fU'~"liI'y1P ,*~I3T~[NE;R**tWJJUBll!?;;tL.J:ill
*e 1AD-12, C/5 or 2AD-12, C/5 "RN PMP B STRAINER HI DIP" - LIT
*e RN PUMP 1A or 1B - TRIPPED
*e RN PUMP 2A or 2B - TRIPPED.
*e Case II. Loss of RN Pit Level:
*e 1AD-12, B/2 "RN PIT A SCREEN HI DIP" - LIT
*e 1AD-12, B/5 "RN PIT B SCREEN HI DIP" - LIT
*e 1AD-12, B/1 or 2AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL - LO" - LIT
*e 1AD-12, B/4 or 2AD-12, B/4 "RN PUMP INTAKE PIT B LEVEL - LO" - LIT
*e 1AD-12, E/2 or 2AD-12, E/2 "RN PIT A SWAP TO SNSWP" - LIT
*e 1AD-12, E/5 or 2AD-12, E/5 "RN PIT B SWAP TO SNSWP" - LIT.
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP/O/A/55001020 3 of 52 Case I Rev 37 DeS DC:: Loss of RN Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- c. Operator Actions 2.
3 .YErtjff~~~I1;(p't~e ratil}gRNilPUr11P ti!et{§rmlllg:::t91IoWitig:, f,fJ§£tla~g~,tI9W ~ GR:I;ATER: Tij~tJ~I§O(), I)GeM~~ aa.*§!Qp::atlW~t;:J.*,pt;(ro*w{$)ti91Jfeql,llred t9: Any alternate RN Pump :$rtpRQtU~¥§!em,.Q9~r,~lig'il~ can be started.
- b. *J;QJ?JJ~¢;t!il'~:1toUoW:i1:l9t§~m.tprrval~esto!
Should secure 1A RN :laRE;lT*'@!f'L~l~t: pump due to another pump running.
- 1rt,\Rf;,I?'~!t(8,:r:~n:~~&llPitii:~'~I~or'Frpm Lakg~)
{i; 1Rt9,;~B {ij,~pIHIE'JfA I.§o I, Frq@;i' LaK~"
*. ****~RN~511&{~N P{ffi{ PIt J;3:":tsol, i?roDi Lak¢l
;~ .1R~~§~)!{~,;f:iW~i~Plll~~:1§01 FrQoi L'k'lt a ~7,'f c.Ef1~lHi~'itheJ9HowiQgres~~tItial be~¢Jer i~Qlg@hv~IYes fdr{reqqIt~d tmir1s~
@gl;~:
_ . ~.* ,q~!g~t!3f:~r{RNilPfdr,l1~iSURQly;;"soJ} _ '~**'1R.tN.§69~J8,:NHqnB§upplYl$Ql9\ _ I~+ 2R~:i()7A (B'NHd'iJ2A .sURpl~\tsoD} _ .~gN-().lil?T:(RNBdr ~B StlppJYil~61). (RNO continued on next page)
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP/OIAJ55001020 AP/O/ Al5500/020 4 of 52 Case I Rev 37 DC~ Loss of RN Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued) d.;RitslJr~lttJ.e fOIJowing};RN tol~L di~Q!;lqrggr%~alv§;~:; ~!ltgN:;
_ e111t-J-849.e ($1~lipflR~;';Di$9h[p:~B.L:
$Ys);
ei. Ensut~ onijQf th~fbllowing RL disch~rge va.lves -;,QPENil OR _e .1R!2::62{ij.N Sy$fDisch'To RCTFfqC;:B)F {i~j §!Jl§~retb~fpUo}Vii!fg .st~ljQn. RN gJ,§pt1*?(9e:ltl.~ag~r:~rQssover.~alves .-
!~~~f'iI:)
_;~'*:lRti;!..:~,A; (~l~tibri RNDisQIDbjdr X"Q.tY~r) _ e1RN-5~~{Station RNJ;)isclj:;.ijId(
.~"'QVE:}rJtl (RNO continued on next page)
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP/OIAl5500/020 AP/O/ AJ55001020 5 of 52 Case I Rev 37 DeEDeS Loss of RN Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued)
- g. IF~*,ier oftllie;foH6Wj@g~pnditic;i!l$l1jis ittl§t;l*
Conditions do not require these _ . RN cannot be aligned to the lake lsteps. jsteps. _ . No flow indicated on operating RN pump(s). THEN align RN to SNSWP as follows: _ 1) Align valves for RN swap to SNSWP. REFER TO Enclosure 2 (RN Valve Alignment for RN Swap to SNSWP). _ 2) IF WL discharge in progress, THEN coordinate with Radwaste Chemistry to secure all controlled WL discharges. _ 3) IF any RN chemical addition is in progress, THEN have Chemistry secure it. _ 4) WHEN corrective action has been taken, THEN restore RN to normal alignment. REFER TO Enclosure 3 (Returning RN alignment To Normal After Transfer To SNSWP). This alarm was in , but tl;l;~' Y~rify th~iQ!!dwi!1g:alarm§]eDARK:', should be off if 1A RN pump was secured _ **iI~ifllilIIZi1~!~Il~~:~;~!Ji~r~m,g!,~E~:
'1 A4lif~iT~l?liigt)JPM~jf\$;"fRl\IN£:R t~FRmfti t\IU:I~IIII!!li earlier.
- 1AD-12, C/5 "RN PMP B STRAINER Backwash will not DIP" HI D/P" operate in any case.
- 2AD-12, C/2 "RN PMP A STRAINER HI DIP"
- 2AD-12, CIS CI5 "RN PMP B STRAINER HI DIP".
- i. I Farly ,bf;ll[e;;pr~tlli!us alsltmslit, TItiEN L
man UGI,l,ly ;b:~l5lm§itm aft:~~f~d strpi!'!:~l'i REFERlKllQ'~R[Q/AJE.m,qqZPQQJ~ (N4pl~~tlPer¥:t@gtYV<3~,f~J"{§Y$'~1'!'! )J
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP/OIAl55001020 AP/O/A/55001020 6 of 52 Case I Rev 37 DC:: DC~ Loss of RN Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. V~(ify e~'<<b.()JiEfr~.t[!lg~N/f)urtlp Perform the following:
dI§j~ttargetllgW.; t:'I;§S' THAI'1,23,QPO
.G~M; CAUTION Closing of the RN supply x-over isolation valves may result in the momentary isolation of an essential header.
NOTE Isolating the Unit 1 or 2 non-essential header will result in loss of cooling supply to the following unit related equipment:
- VA Supply Vent Units
- VF Supply Vent Unit.
- a. Ensure the following RN supply X-Over isolation valves - CLOSED:
- 1RN-47A 1RN-4 7A (RN Supply X-Over Isol)
- 1RN-48B (RN Supply X-Over Isol)
- 2RN-47A (RN Supply X-Over Isol)
- 2RN-48B (RN Supply X-Over Isol).
- b. IF flow is returning to normal, THEN GO TO Step 5.
- c. IF flow is still excessive, THEN:
_ 1) Ensure both RN pump(s) on the affected train - OFF. _ 2) Dispatch operators to locate any piping leaks. REFER TO AP/OIAl5500/030 (Plant Flooding). AP/O/A/55001030
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP/O/A/5500/020 AP/O/A/55001020 7 of 52 Case I Rev 37 DC~ Loss of RN Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6.I§jjs:qr~IBi:9;B~tl@Ugh~JlU~I~ii!§f!BNlt§lt~li, 6.Ettsur¢~pn)peri@lignm~ntpfRJ5J~tQU<;@i IIXs:!'~s:,I§U§~s:';:' H>t~).asfgJJpw,~:.
- a. Shift KC train in service as needed.
REFER TO:
- OP/1/A/6400/005 OP/1/A/64001005 (Component Cooling Water System)
OP/2/A/6400/005 (Component
- OP/2/A/64001005 Cooling Water System).
b. Perform the following:
- a. Do not exceed 4650 GPM through an NS Hx.
- b. Align RN flow through NS Hx(s) as needed to increase each operating RN pump's discharge flow to greater than 8,600 GPM. REFER TO OP/0/A/64001006F (Nuclear Service OP/O/A/64001006F Water System Flush Procedure).
- 8. tY~~r'j~fRNi~Y~!,*~LE J"9:'ALL,:;UNIT Dispatch operator to locally remove any l' 2\,N D, q~I,:r<<~\P1GISk D/G(s) without a cooling water supply from standby readiness. REFER TO:
OP/1/A163501002 (Diesel Generator
- OP/1/AI6350/002 Operation)
OP/2/A/6350/002 (Diesel Generator
- OP/2/A/63501002 Operation ).
Operation). _ VCNC to operating RN train. Align VCIYC REFER TO OP/O/Al6450/011 (Control _
- V~l!b~VC1Y~)';AL!~:NED~~.} Room Area Ventilation/Chilled Water q!i~~TIf)l,~RN,:illRAIN;1 System).
_ *'~tjM¥C<i~bll1~~~RUJ~~INGi
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP/O/A/55001020 AP/0/AJ5500/020 8 of 52 Case I Rev 37 DCS DC~ Loss of RN Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 110. O. Q~tertni'r1'Q,~ndIsorrect,:cati~,~~of IQ~~;ot R.NlJrai 11,;1 TS 3.7.8 Condition A 11. 11 . iSl)~:PT:ji{:~,9tn~Jjali~~}rWittr~pPJQR"atl:r leii§:g)]~,;j~~m~Ji,ilii~~;EiJl'jJ!lDni1~illillg'i i:;ecl1T§J)ecs~nd' Ilt:g,gl~f;lg:~§";~iigI~glg~lgg~J,&!ggf11gg1 ~~lect~d:,Licen§ee Cotnm'itnlents,Mariu.c:lI:
;~pmm:!lm~JjI~lji.Mfit1J;Jfi.l:
.' SLCJ 6.7-6 (BN*Di§;9harge
;lristr'ui:n~ritatiQQ)
* *8;6.5(Contairl"~'*ent'XMi<TerfreratJjre)'
.... '. "."" ., ...W. ""~" ...."... j:> . . .'....,e*
- 3 . ...~6.6 *.*(CQritain1:Yi'eriPS'ta:iS;'stem)*;
. .... ,., . . ' .....,.,. ..... .~.... Y". 'il* "w.*
_ *.*~ ,6.17:l!I~Qnt?iMmet}t\~~,v@;tI!3jectjQn} tWale~§y~tei:n J~VI,~:s?)
.' 3.7 :$.(Auxma'~IFee,~lNate~%(AF\II{j Syst~i:n)
.' ~;j7,71{Cbi:nponentlCooIJrtg W?Wr{C~~)
t§~§!~Q:1J
.*~. 3, lnp {ConJrqll3qorn Are~Vel1tilation
&yst~fll {c8AVS)1 ...
~'~~7.:n. (QprrtrQJt8!lQm'~l¢;?~lt!inedW,~I~~
!;~y~temJl~~~W$'~!
_-;' 3~~;t{A.C.~.Qurce§;s~;0p~tatingl _I~ @~;~()~;.~~i$qo~c&~::,§E(LJ~dqlNri) .
. . :~:~. np/f:iIAl'
*;; ,,'REFE'°irO Q:~g .,,?,
'~Ot;i"'JI)IYr1!}
"M,~~",.J;{~ ~&~<J.'
(Cla$$ification:l9>f E'm~fgea:9Y)
.. R~Q6RIIiJ'(JI~,~lq~\~llm~~liiUI;I!limJiI!
RE~ERTOlRF=>/Ql~/500QLP1~\{~~Q
,;t;igtifiqFltiQ'1!~~991t&Q:l~!Jt§)r Il~~t~f:t~~ti~D'I!B§g!lill~§tI~DI§III'
CNS LOSS OF NUCLEAR SERVICE WATER PAGE NO. AP/O/A/55001020 9 of 52 Case I Rev 37 DC~ Loss of RN Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 14. Det~tmiheii'kJj'g:l~tm. plarttl~~qJds,~
RElrURNi~TO,pro,¢g~Jlr~!~ffe.Gt,s
Duke Energy Procedure No. Catawba Nuclear Station 1 AP/I/A/5500/037 API IA/5500/037 Generator Voltage and Electric Grid Disturbances Revision No. 000 Electronic Reference No. CP00965X Continuous Use PERFORMANCE I
- UNCONTROLLEDFORPRrnT**********
(ISSUED) - PDF Format
GENERATOR VOLTAGE AND ELECTRIC GRID CNS PAGE NO. DISTURBANCES AP/1/A/5500/037 AP/1/N5500/037 2of20 Revision 0 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED B. Symptoms
- Ca~e 1~I?!"U?ml~f~~n1l~tqr;1;QJ;;GrJfj,:rqJlm~:~
- 1AD-11, Kl6 "230 KV Switchyard Voltage LO" - LIT
- 1AD-1, C/4 "GEN Excitation Limiter Active" - LIT
- OAC point C1 E1795 (230KV Y BUS VOLTS) - IN ALARM LO
- OAC point C1E1797 (230KV R BUS VOLTS) -IN ALARM LO
- OAC point C1A0567 (Unit 1 Generator Volts) -IN ALARM HI
~,' O,A.G~pointC1~95671~(,~i:lit'fm;:G~h~~:tQ'&~Q1ts);~TtilB!-A~M*!-q)
- OAC point C1A1631 (Unit 1 Generator MEGAVARS) - IN ALARM HI
- OAC point C1A1631 (Unit 1 Generator MEGAVARS) - IN ALARM LO
- Generator voltage and MVARs fluctuating
- Generator Capability Curve Exceeded
- TCC notification that "Real Time Contingency Analysis" (RTCA) indicates Switchyard voltage would NOT be adequate if the unit should trip.
- Case II Abnormal Generator or Grid Frequency:
- OAC point C1A0561 (Generator Frequency) - IN ALARM LO
- OAC point C1 E1794 (230KV Y BUS Frequency) - Indicated Frequency less than 59.8 Hz
- OAC point C1 E1796 (230KV R BUS Frequency) - Indicated Frequency less than 59.8 Hz
- SOC or TCC notification of Grid frequency disturbances
- 1AD-1, D/6 "EHC System Fault" (EHC Alarm Panel input indicates Generator Frequency Correction activated) - LIT.
GENERATOR VOLTAGE AND ELECTRIC GRID CNS PAGE NO. DISTURBANCES AP/1/A155001037 AP/1/A/55001037 40f20 4of20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- c. Operator Actions C.
- 1. Perform the following:
D Shared systems (RN, VC, YC, VA) require an operable normal power source to be operable.
- a. IF notified by TCC that degraded switch yard (grid) voltage conditions exist, THEN ensure compliance with the following Tech Specs. REFER TO PT/1/A143501002C PT/1/A/43501002C (Available Power Source Operability Check).
- 3.8.1 (AC Sources - Operating)
- 3.7.8 (Nuclear Service Water System (NSWS)
- 3.7.10 (Control Room Area (CRAVS))
Ventilation System (CRA VS))
- 3.7.11 (Control Room Area Chilled Water System (CRACWS))
- 3.7.12 (Auxiliary Building Filtered Ventilation System ABFVS)).
- b. RETURN TO procedure and step in effect.
2. D RO GENCAP will not be exceeded.
GENERATOR VOLTAGE AND ELECTRIC GRID CNS PAGE NO. DISTURBANCES AP/1/A/5500/037 50f20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. Adjust Generator MVARs to operate Perform the following:
within Generator Capability Curve limits as follows: a. IF voltage regulator in "AUTO", THEN perform the following: _ . Depress "LOWER" on the VOLTAGE ADJUST to reduce lagging MVARs _ 1) Place voltage regulator in MANUAL. _ 2) Adjust MVARs to within the GENERATOR CAPABILITY CURVE
- Depress "RAISE" on the VOLTAGE limits.
ADJUST to reduce leading MVARs.
- b. IF unable to maintain MVARs within Generator Capability Curve limits, THEN remove generator from service as follows:
- 1) IF reactor power greater than or 1) equal to 69%, THEN perform the following:
_ a) Trip reactor. _ b) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection).
- 2) IF reactor power less than 69%,
THEN perform the following: _ a) Trip turbine. _ b) GO TO AP/1/A/5500/002 (Turbine Generator Trip).
- 4. Notify RES Engineer to evaluate generator abnormal operating conditions.
GENERATOR VOLTAGE AND ELECTRIC GRID CNS PAGE NO. DISTURBANCES AP/1/A155001037 60f20 6of20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Tfie;T(jC\~'ReaITfme ,<!bhting' .c/>ina1Y"(RfC~)' prQgram di3t~rmil'les if the Un~(*,i~l h.l~~~; adeqi~i~l~ S~i!,C~i .~Rlta :~:i.!pble f()~lt~:9G§lgqdstQnoWingi;a
.lJnIt Tnp Wlth,SafetYi:JDJectlon a ,'N'." t,pn.
- 5. R~i1()rm th~!jif();llowirig:l
_ a.',J:TCC l1asnot report($
'ii,'dications,THEN notit CJo. :rnOnitor "RICA" and *teport resu <,itoCQQtrol RO No info received from :Room Supe'fvI$or.
TCC b. :IF!:ATANYTIMETCCrepOrtstffla't
~>--A" indi ',siCNS' switchy~'~¥{
,'ge would';'T be. adequ~t~l{if th~)
it should trip; THEN GO TOt~tep 6} _ C:!:~'bbserve.N()teprior*tdr§tep 17:il~hd ~~) TO Step'17;'
- 6. Record time TCC "RTCA" indicated CNS switchyard (grid) voltage NOT adequate.
- 7. Start 2 hour timer from time TCC "RTCA" indicated CNS switchyard (grid) voltage NOT adequate.
GENERATOR VOLTAGE AND ELECTRIC ELECTRICGRIDGRID CNS PAGE NO. DISTURBANCES AP/1/A/5500/037 AP/1/N55001037 7of20 70f20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED When TCC "RTCA" indicates switchyard voltage would NOT be adequate if the unit trips, the following conditions exist:
- Both trains of offsite (normal) power are inoperable.
- Both ECCS trains are in an unanalyzed condition and inoperable.
- Shared systems (RN, VC, YC, VA) that require an operable normal power source, are inoperable.
- 8. Perform Tech Spec assessment as follows:
- a. Ensure compliance with the following Tech Specs due to both trains of the following systems inoperable:
- 3.8.1 (AC Sources - Operating)
- 3.5.2 (ECCS - Operating)
- 3.7.8 (Nuclear Service Water System (NSWS))
(NSWS>>
- 3.7.10 (Control Room Area Ventilation System (CRA VS))
(CRAVS>>
- 3.7.11 (Control Room Area Chilled (CRACWS))
Water System (CRACWS>>
- 3.7.12 (Auxiliary Building Filtered Ventilation System ABFVS)).
ABFVS>>.
- b. Ensure compliance with Tech Spec 3.0.3 due to both trains of ECCS, RN, VC, YC, VA inoperable.
- 9. Notify Regulatory Compliance to pursue licensing options due to loss of normal power source operability to shared systems.
GENERATOR VOLTAGE AND ELECTRIC GRID CNS PAGE NO. DISTURBANCES AP/1/Al5500/037 80f20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED The TCC/SOC response to a degraded grid voltage condition may restore voltage to adequate status within one hour.
- 10. Activate the TSC as follows:
- a. Verify TCC expects switchyard (grid) a. Perform the following:
voltage restoration to adeq uate status in less than one hour. _ 1) Activate the TSC. REFER TO RP/0/B/5000/027 (Augmentation of Shift Utilizing the Emergency Response Organization without Emergency Declaration) _ 2) Observe Note prior to Step 11 and GO TO Step 11.
- b. Evaluate activating the TSC. REFER TO RP/0/B/5000/027 (Augmentation of Shift Utilizing the Emergency Response Organization without Emergency Declaration)
NOTE The degraded switchyard (grid) voltage condition places ECCS in an unanalyzed condition reportable per 10CFR50. 72(b)(3)(ii). 72(b )(3)(ii).
- 11. Determine required notifications:
- REFER TO RP/0/Al5000/001 (Classification Of Emergency)
- REFER TO RP/0/B/5000/013 (NRC Notification Requirements).
- 12. Evaluate the following:
- Stopping in progress surveillance testing.
- Stopping in progress maintenance activities.
- Returning systems to normal/functional status.
GENERATOR VOLTAGE AND ELECTRIC GRID CNS PAGE NO. DISTURBANCES 111AJ55001037 AP/1/N55001037 AP 9 of 20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED The SOCITCC is allowed 2 hours to restore switchyard (grid) voltage to adequate. The 2 hour time limit may be adjusted based on OSM assessment of plant or grid conditions.
- 13. Do not continue in this procedure until one of the following conditions exist:
- 2 hours have elapsed since TCC "RTCA" indicated switchyard voltage NOT adequate.
OR
- Notification from TCC that "RTCA" indicates switchyard voltage would be adequate should the unit trip.
OR
- OSM adjust 2 hour time limit based on assessment of plant conditions
GENERATOR VOLTAGE AND ELECTRIC GRID CNS PAGE NO. DISTURBANCES AP/1/A/5500/037 AP/1/N55001037 10 of 20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 14. Verify TCC reported that "RTCA" Perform the following:
indicates switchyard voltage would be adequate should the unit trip.
- The jumpers bypass the 4160 degraded voltage 5 second time delay relay.
- If an S/I occurs with the jumpers installed, the 4160V incoming breakers trip open when LOCA Sequencer actuates. The D/Gs DIGs will supply power.
SP~C to install jumpers per
- a. Notify SPOC AM/1/A/51 00/008 (4Kv Essential Power AM/1/N51 001008 (EPC) System Degraded Voltage Logic.
When jumpers are installed offsite power and shared systems remain inoperable until "RTCA" indicates switchyard voltage is adequate should the unit trip.
- b. WHEN jumpers installed per AM/1/A/51 00/008 (4Kv Essential Power AM/1/N51 001008 (EPC) System Degraded Voltage Logic, THEN Unit 1 exits L.C.O. 3.0.3 due to both trains of ECCS inoperable Tech Spec 3.5.2.
- 15. Do not continue in this procedure until TCC reports that "RTCA" indicates switchyard voltage would be adequate should the unit trip.
GENERATOR VOLTAGE AND ELECTRIC GRID CNS PAGE NO. DISTURBANCES AP/1/A155001037 AP/1/AJ55001037 11 of 20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 16. WHEN TeeTCC reports "RTCA" "RTeA" indicates switchyard voltage has been returned to adequate should the unit trip, THEN petiorm perform the following:
- a. IF jumpers installed, THEN notify SPOC to rem'ove jumpers per, AM/1/AJ5100100B (4Kv Essential Power AM/1/A15100100B (EPC) System Degraded Voltage Logic.
- b. Evaluate exiting the following Tech Spec LCO actions:
- 3.B.1.(AC Sources - Operating)
- 3.5.2 (ECCS - Operating)
- 3.7.B (Nuclear Service Water System (NSWS))
(NSWS>>
- 3.7.10 (Control Room Area Ventilation System (CRAVS))
(CRAVS>>
- 3.7 3.7.11.(Control
.11.(Control Room Area Chilled Water System (CRACWS))
(CRACWS>>
- 3.7.12 (Auxiliary Building Filtered Ventilation System ABFVS)).
ABFVS>>. _
- Tech Spec LCO 3.0.3.
- c. Notify Regulatory Compliance of Tech Spec LCO action status.
GENERATOR GENERATOR VOLTAGE AND ELECTRICGRID ELECTRIC GRID CNS PAGE NO. DISTURBANCES AP/1/AJ5500/037 AP/11A155001037 12 of 20 Case I Revision 0 Abnormal Generator or Grid Voltage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
.B.
d~;~~~~::~~!~t~htaj~~J?t:~~Orin 17. '-R:-::O:--'
'foIlQWs;:j OR When the SOC is called, The crew will be told to adjust generator according to the voltage voltage aocording schedule.
- 18. ;M1'henSOCITGC~e(ifies s~~tdhYard(gr(~)*
;~bltage ad~qtiat~)and reliable, THEN' RETURN. TO;procedur'~~!ep in eJf~gtl
Duke Energy Procedure No. Catawba Nuclear Station 1 API IA/SSOO/023 IA/5500/023 Loss of Condenser Vacuum Revision No. 018 Electronic Reference No. CNOOSCER CN005CER Continuous Use PERFORMANCE I
- UNCONTROLLEDFORPruNT**********
(ISSUED) - PDF Format Initiating Cues:
- 1AD1, F/7
- OAC alarm C1A0734 (Condenser C absolute backpressure)
- Turbine MW decreasing
CNS LOSS OF CONDENSER VACUUM PAGE NO. AP/1 I Al55001023 AP/11 1 of 15 Revision 18 A. Purpose
- To verify proper response in the event of a loss of condenser vacuum.
B. Symptoms
- Condenser vacuum indication - DECREASING
- Hotwell temperature - INCREASING
- 1AD-1, F/7 "CONDENSER LO VACUUM" - LIT
- FIB "EXH HOOD HI TEMP (PRE-TRIP)" - LIT 1AD-1, F/8
- 1AD-5, Al4 "CFPT A LO EXHAUST VACUUM" - LIT
- 1AD-5, C/4 "CFPT B LO EXHAUST VACUUM" - LIT
- OAC point C1P1493 (Unit 1 C1&C2 Average RC Inlet Temp) -IN ALARM HI.
CNS LOSS OF CONDENSER VACUUM PAGE NO. AP/11A155001023 AP/1/A155001023 2 of 15 Revision 18 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- c. Operator Actions C.
1.
- 2. Decrease *.
turbine
. ' d','W* ..**
load.as required to
<stabilize vaculiQ!lf's follqW~:
.aJj:i;LIFWPid po~~r reducti()n~,r~q!-!i(ed, tHEN perfcWnJlie, fono\'Xing~j NOTE *irif*iM~:~'ruALl rtlq:g,e;~\tbe conmjryalves~r~capabfg~of~~IEtt?yel.wi(hid 3 min\!J~s~:
_ 1>>'3;Select '\t0~NUAL" a~~liCONTROL Crew should stay in this AP at this VALVE[~PWERIf toteduce turpine load asirequired. Itime. time. _ 2) REFER TO AP/flNS500lhbg*
.{f$~pi~:jDownl~I2~~r)~"N'" .
_ ,:,~ )G$f;:Q$tgR;l~~
- b. Perform the appropriate controlling procedure to reduce power:
_ . OP/11A161 OP/1/Al61 001003 (Controlling Procedure For Unit Operation) OR OP/1/A161 001002 (Controlling
- OP/11A161 Procedure For Unit Shutdown).
CNS LOSS OF CONDENSER VACUUM PAGE NO. AP/1/AJ55001023 3 of 15 Revision 18 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3.
- 3. <~eIify proper~C Sysffrh}foper~ttQflJi<a§l fQU,c>\Vs:
- a. a. Perform the following:
_ 1}
- 1) Start additional cooling tower fans as necessary to maintain condenser inlet temperature less than gO°F.
REFER TO OP/1/B/64001001A (Condenser Circulating Water System). _ 2) Start additional RC pump(s} 2} pump(s) as necessary to maintain condenser inlet temperature less than gO°F. REFER TO OP/1/B/64001001A (Condenser Circulating Water System).
- b. b. IF cooling tower level is low, THEN perform the following:
_ 1} Ensure 1RL-853
- 1) 1RL-853 (Train A RL To RC Makeup Control) (1MC-13)-
(1 MC-13) - RESTORING NORMAL COOLING TOWER LEVEL. 2) 2} IF 1RL-853 is not maintaining cooling tower level, THEN perform the following: _ a) Contact Environmental a} Chemistry to secure cooling tower blowdown. _ b) b} Throttle open 1RL-855 (Train A M/U Valve Bypass) RL To RC MlU (1 MC-13) to maintain cooling (1MC-13) tower level. _ c) c} Start additional RL pumps as needed. REFER TO OP/O/B/64001003 (Low Pressure Service Water System).
CNS LOSS OF CONDENSER VACUUM PAGE NO. AP/1/A/55001023 AP/1/N55001023 4 of 15 Revision 18 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. Perform the following:
- a. Adjust 1AS-2 (Main Stm To Aux Steam) setpoint to maintain AS header pressure 165 PSIG.
- b. IF 1AS-2 will not control in automatic, THEN manually adjust 1AS-2 to maintain AS header pressure 165 PSIG.
- c. IF 1AS-2 is functional, THEN GO TO Step 5.
CAUTION Aligning the Unit 2 AS system to supply Unit 1 AS headers may cause small reactivity changes on Unit 2.
- d. IF Unit 2 available to supply Unit 1 AS header, THEN perform the following:
_ 1) Adjust 2AS-2 (Main Stm To Aux Stm) to maintain AS header pressure 165 PSIG.
- 2) Dispatch operator to align Unit 2 AS as follows:
_ a) Ensure 1AS-33 (Unit 1 AS Hdr Isol) (TB-590, 1M-26) - OPEN. _ b) Open 1AS-59 (Unit 2 AS Hdr Isol) (TB-584, 2N-26). _ 3) WHEN 1AS-59 is open, THEN slowly close 1AS-2 (Main Stm To Aux Steam).
CNS LOSS OF CONDENSER VACUUM PAGE NO. AP/1/AJ55001023 AP/1/A/5500/023 5 of 15 Revision 18 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED EJ5.5.
- a. a. GO TO Step 7.
=i{\j~I~1i;l:t~li~t~;~]~lll~71TiD:~iil~
b.
- c. c. GO TO Step 6 RNO.
CNS LOSS OF CONDENSER VACUUM PAGE NO. AP/1/A/55001023 AP/1 I Al55001023 6 of 15 Revision 18 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6.
, le~~~i~~~i~tlow"~~~~~: 'g~~sur~1~TL~9tStea.J}iSeareackfogt, .. .'
qri'loade( . Reg¥~lvell~>paifi~IIYlp~h .byi pe!1prrriingatl~~st oQlof t6e fbJIQ~Qg;J _ . Verify 1TL-3 (Steam Seal Reg Valve)- Valve) - *.~t5s.erv~ljfldjr
, '~(.;.~ c '. i)'f",c'.'~~.> c
\nC~ti9ri~t'f1 tC-91 NOT CLOSED ~\q§ition9s,}fol .~,
OR _ ~.~\:."gb$~:~~}dQ:1\IID1§t~*$£iJ'~eall:i~a~gi~;
\R[e~§L!r~~
- Verify both the following:
.i{§'#S1lSeaJ R~g)
- Unit 1 - ON LINE. ">c'" eJ~lIpwjng,
,:g!1
- 1TL-10 (E Bleed Steam Seal Reg Valve) - NOT CLOSED. _ *,.~.team .s~?npr~§srure:rGRl;{%t~R t8AN9:IPSJG~n
@m
- Coordinate local observation of 1TL-9 position as follows:
- a. Dispatch operator to locally observe 1TL-9 (Steam Seal Packing Unloader Reg Valve) (TB-594, 1G-31).
- b. Throttle open 1TL-4 (Stm Seal Reg Byp) until one of the following conditions are met:
_ . Steam seal pressure - GREATER THAN 6 PSIG. OR
- Dispatched operator reports 1TL-9
- NOT CLOSED.
CNS LOSS OF CONDENSER VACUUM PAGE NO. AP/1/A/55001023 AP/1/N55001023 7 of 15 Revision 18 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE S,ta~ing; a~a;~r~:~~~~l~;.~jI9tors o~7v~uiiru,q~~~, wlfE;i;l,~f~m9feY~~~1ll When. bl9fi By tf#JTlP~Lf,!Jqf~£:'$rtlJe}:[easo(lJQr 105A,tQ[ Y~,cuum: 7. ,BOP 1_ a. a. Perform the following: 1)
- 1) IF additional air removal will increase vacuum, THEN perform the following:
Depending on how closely they monitor vacuum, they a) Dispatch operators to perform may dispatch operators the following: here becasuse the trend doesnt immediately reverse _ .* Align main vacuum pump(s) for service. REFER TO on TL restoration Enclosure 4 (Placing Main Vacuum Pumps in Service) .
- Align idle set of CSAE jet(s) for service. REFER TO OP/1/S/63001006 OP/1/B/63001006 (Main Vacuum).
_ b) WHEN condenser vacuum decreases to less than 24 in. Hg., THEN align main vacuum pump{s) to the condenser. pump(s) REFER TO Enclosure 4 (Placing Main Vacuum Pumps in Service). _ 2) GO TO Step 8. b.IFATANY,lJl~El9Pnd~t\~~~;vasug
- b. .
decre,<;\s~$;':THEN Dbserye Not~:! .' St~R~7:::?np peryornilS~e~i 7.;' ..
- 8. Eil!gr~pr9per;: qp~rWiqnlloftP:Syst~n,:.i REFERTO oPllO/i3/6250J011 . '{Vacoum:
Pri l11irig Sy~.t~m)*:* "
CNS LOSS OF CONDENSER VACUUM PAGE NO. AP/11A15500/023 AP/1/A/55001023 8 of 15 Revision 18 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. pI!;p~lqhpf$e:~,pr(s) to'*V,~rIfy*prqpet?~~al The crew may not dispatch operators if i!~l:lOU9h flows.: ~REFERT(y~r;Dg'g~ure2 they are confident they know that they (Verification q!:~eal:E!Q""sl~, . .... understand where the issue is and have aken actions to mitigate it.
taken 10. 11. NONE j@~'RP/OjAJ5boO/b01
.~'ipr(Of Emerg'ency) - :!.!j~~i!t~~~:~~'~~~~~~l; ~INR~i 13.
14.
Initiating Cues: FIB 1AD-6, F/8
- 1AO-6,
- OAC alarm C1 L4455 (Normal Pressurizer Spray Flow Activated)
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/Al55001011 AP/1/A155001011 1 of 9 Rev 22 DC~ A. Purpose To ensure proper response in the event of abnormal Pressurizer pressure, assess plant conditions, and identify the appropriate steps for the following cases: Case I Pressurizer Pressure Decreasing Case II Pressurizer Pressure Increasing. B. Symptoms Case I. Pressurizer Pressure Decreasing:
- 1AD-6, E/10 "PZR PORV DISCH HI TEMP" - LIT
- 1AD-6, E/11 "PZR SAFETY DISCHARGE HI TEMP" - LIT
- 1AD-6, F/8 "PZR LO PRESS CONTROL" - LIT
- 1AD-6, Al8 "PZR HI PRESS ALERT" - LIT
- All Pzr heaters - ENERGIZED
- 1AD-6, D/11 "PZR LO PRESS PORV NC34 BLOCKED" - LIT
- 1AD-6, D/10 "PZR LO PRESS PORV NC32 & & 36 BLOCKED" - LIT
- Pressurizer pressure less than 2235 PSIG and decreasing Case II. Pressurizer Pressure Increasing:
- 1AD-6, D/8 "PZR LO PRESS ALERT" - LIT
- 1AD-6, C/8 "PZR HI PRESS DEV CONTROL" - LIT
- 1AD-6, B/8 "PZR HI PRESS" - LIT
- Pressurizer pressure greater than 2235 PSIG and increasing
- All Pzr heaters - ENERGIZED.
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A/55001011 AP/1/A15500/011 2of9 Case I DC~ Rev 22 DCt Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions BOP DOES THIS PAGE Perform the following:
- a. Manually close Pzr PORV(s).
- b. IF any Pzr PORV cannot be closed, THEN:
_ 1) Close the affected PORV(s) isolation valve.
- 2) IF the Pzr PORV isolation valve cannot be closed, THEN perform the following:
_ a) IF in Mode 3 with CLAs isolated OR in Mode 4, THEN GO TO AP/1/A/55001027 AP/1/A15500/027 (Shutdown LOCA). _ b) Trip reactor. _ c) WHEN reactor tripped OR SII setpoint reached, THEN ensure SII initiated. _ EP/1/A15000/E-O d) GO TO EP/1/A/5000/E-O (Reactor Trip Or Safety Injection).
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A/5500/011 30f9 3 of 9 Case I Rev 22 DeSDC~ Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED BOP DOES THIS PAGE IBOP Pet!9,fm t!l~tollgwing; _~: (N1~ltY~lly'~!glQ,~~t;gft§qteQ~li~51;:1yal.l{e(s r b §}'i~1 fi'i:i;fff~Ql~tJ JmraYv'§lyg(s) Will nOtqlose,t
~I~~'~p§rf()rm;:'([~U61Iow[i\ig:
thg,Cont~QI :Room i.!!i'~iIi\~f:I¥itlill\llejfl;i~i;i&kgDl~g!!ig;gm i13¥)1f;jATljl.NYIINlE*
~;mp~mili§gi';g~t~Emitl~§i;ll;i~~*m:!E~~~~g~)
\~l!Jp¢tvisord~t§rmine~thClr~'reacto~i
'fmmi§lt~!1.tl.lif~gfifJ1J;1l:N;:
i~f!p.i~rgqui{ed~trHEN: _ @'ij1rip'reCl~9@ _ i~I:}J WIiENtiA~Qtorp<'ft¥er!~s~i'than 9.%;: THEN~§tpp NmHylnps1A It is possible that the crew may feel a need to :aog,J§t, trip the reactor and SI or it may occur _ c};.GOTOEP/1YN50QQt1?'-O automatically if the crew is slow to respond. (ReClC?torTrip!fQr St;lfe,'ty In any event, the SGTR will occur on Rx trip, Injection). whether the trip is manual or an automatic trip occurs. 2) ;$'~tg~~tifiAII.;,;~[QSgD" fo(aff?pted
.Spr?Y;i~glVg(§>>l):podg,i,§~lects~tch:
_ * 'iUJ'llC"'gZtI;ZRt~E:RA'{ '\ILY*
;MODQi§J;rCEGJ8
* "1 NC-29 PZR SPRAY SPRAYVLV VLV MODE SELECT".
_ 3)IFiNqprgssur~i!§l;:~t~!;1!~:Z0R ingt§asing,THENiGO:y:a~$tep 3; (RNO continued on next page)
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A155001011 AP/1/A/55001011 4 of 9 40f9 Case I Rev 22 DC~ Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (Continued)
{Continued) BOP DOES THIS PAGE IBOP
- 4) IF NC pressure continues to decrease, THEN:
a) IF in Modes 1 or 2, THEN: _ (1) Trip reactor. _ (2) WHEN reactor power less than 5%, THEN stop NC Pumps 1A 1A and 1B. _ (3) EP/1/A/5000/E-O GO TO EP/1/A15000/E-O (Reactor Trip or Safety Injection). _ b) Stop NC Pumps 1Aand 1A and 1 B. 1B. _ c) IF NC pressure continues to decrease, THEN stop additional NC pumps as required. _ d) REFER TO AP/1/A155001004 AP/1/A/55001004 (Loss of Reactor Coolant Pump). _ IF Pzr pressure is less than 2220 PSIG, THEN ensure all Pzr heaters are energized.
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A/55001011 AP/1/A155001011 50f9 Case I Rev 22 DC~ Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED RO DOES THIS PAGE IRO Positrx~,tre:~Q:th~!fYJls;i:in~~lif~glqiJri()g:~arri1'nGr~~~~,Jij'NGl~,tessCire:l;whiqljlniaYQause autgj~to'QlitiS~jj(il§fjf~
- 5. V~L!1Y;,N~~fRt~~sur~~STJi;f3LE OR _ IF pressure continues to decrease, THEN INq~~Ji;§JN(31J REFER TO AP/11A15500/010 (Reactor Coolant Leak).
- 6. ,WHEN iNCpre~:~i..Jre J§§~~ijL~L;THENi.'
- SI~oilJze unitti,3:t;?pplqptiat~Bpbwer.i;le:ver~
..i~~jJ.j;st theJqJJ5winga,sleqLHted \q Q\~iQtainJ~~vg witt;)jri'1 °pitqf T -Ret'
~!~!-fJo\f~!i\lll' 7.
- 7. ;"F:<le~ttpressijre:chcuil,!iH~iledJ
'1:IE:JII!BllJip~g§:§!:!!I'tg::'§tl!,!,tI:n~l;mUggllil1fl1Ef'l' IlPHEN perform following:
- a. Verify "P-11 PZR S/I SII BLOCK a. Ensure compliance with Tech Spec PERMISSIVE" status light (1SI-18) in 3.3.2 (Engineered Safety Features required state for unit conditions. Actuation System (ESFAS)
Instrumentation) Instrumentation)..
- b. Notify IAE to fail following bistables for affected channel per Model WIO
#00874531. Bistables shall be tripped within 72 hours:
- Pzr low pressure S/I SII
- OT Delta T
- Pzr high pressure Reactor Trip
- Pzr low pressure Reactor Trip.
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A/55001011 6of9 Case I DC~ Rev 22 DCS Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8.l;nsure\9Qmp!iJ~fl~~Wifl'f~pprQ~~riat~)
- 8. ,l§n~i.fti~ig§m,BliJiill~J~itili!l\ppti~p:{i~!~Ij t1l~,§f:t;§p,~,@;§'~!i T~.9h .SR,~,~~':;:
_ * ~R~;1[;~~a!'?1or Tripj§jlsternR~T~>>) JJi!slr!!:!:rnffhtatjpJl) _ .: ~i~t~:: (Engine~t~p~aJ~!Y;;ff'~?llJe~~; Actg~tionSY§I~itl.c(§§P:~§); IIis1e~rn~I1tp1i~!1)i _;' 3.3.3r(!?q:sr~cqiQE[~lM@lIj~dtiff9*.(P:~M)) InstnJitl¢iJiiaiioJJ!)} TS - 3.4.1 Condition A (based on NC pressure at the time) _'i'i ;3.3.4:(g~itlq!gt§J:IOldqWp"Sysl~ri1) _ .3.4 ~1 JRQP;'l3~,f~§.~ure;)'f:i!fnpei'all:lrei;alJd F low !2~pattJ;lt~ll1rori1;~QCleC!.t~i!?oili{ig {DNI;Hl~ifnits)J _ .' 3*4A;,{RCS*~t?pp$-lt)tlrPij?I::~;~1 i§:Wf,fg} _~'~1~J),\t8{~p;Qb()ps-.MrPDE'r9) _ '. *3 wf*)'6 1ror:'S*0iLoop**s'i:;<M* OD*6,*.<4*
~:"::r..., "{~~\.'i'. ~:,. .. ..... "..,::~,:~.' 'cc ' * * :." * * ~:L
. f)'
_ .*3A.9rat¢~sti@it1(4J _ .3A:1:Q(Pres§:Yf:i:zer§lfjl~ty;~a\'Z¢§)! _ ." il4:~n(l::>t~~slJrizgnp9Wet:Qperct!~d lfiR§lief@~~~IV~s. W.G1RVsJJ _ *:;****3.4.13 {RCS~(::r:'etatior:)"ILeaV:B
........ ' """;F!,, ........ #.s .... ,. . ..r~. 9L e ';/
_ ;~, ,jg~lg'mlli"ig:l'~§n§lIgrm~!pl~iUlli!i.f§J~)\ D;~l~t1P:il1elQhg t~r:lljplant~l~tUs,. RE:fflI!!JR""'lllmliIIIB{~,~~l"'lt~il@It~,g!~\ REWURN TG)!pro~Eil::lure in ~Jfect.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O 1 of 61 Rev 36 DC~ A. Purpose This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of all Reactor Trips and 8/15/1 above P-11, P*11, 5/1 below P-11 valid 8/1 P*11 and to assess plant conditions, and to identify the appropriate recovery procedure.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-0 EP/11A15000/E-0 20f61 2 of 61 Rev 36 DC~ B. Symptoms or Entry Conditions
- 1. The following conditions are symptoms that require a Reactor Trip:
- 1 of 2 SIR channels - GREATER THAN 105 CPS WHILE BELOW P-6
- 1 of 2 IIR I/R channels - GREATER THAN 25% FULL POWER AMPS EQUIVALENT WHILE BELOW P-10
- 2 of 4 P/R channels - GREATER THAN 25% FULL POWER WHILE BELOW P-10
- 2 of 4 P/R channels - GREATER THAN 109% FULL POWER
- 2 of 4 P/R channels - +5% FULL POWER IN 2 SECONDS
- 2 of 4 loop ~Ts OP~T SETPOINT ilTs - GREATER THAN THE OPilT
~Ts - GREATER THAN THE OTilT
- 2 of 4 loop ilTs OT~T SETPOINT
- 2 of 4 Pzr pressure channels - GREATER THAN 2385 PSIG
- 2 of 4 Pzr pressure channels - LESS THAN 1945 PSIG WHILE ABOVE P-7
- 2 of 3 Pzr level channels - GREATER THAN 92% WHILE ABOVE P-7
- 2 of 4 S/G N/R level channels on 1 of 4 S/Gs - LESS THAN LO-LO SETPOINT
- 2 of 4 NC pump buses - LESS THAN 77% OF NORMAL VOLTAGE (5082 VOLTS) WHILE ABOVE P-7
- 2 of 4 NC pump buses - LESS THAN 56 HERTZ WHILE ABOVE P-7
- 2 of 3 NC flow channels on 2 of 4 NC loops - LESS THAN 90% OF LOOP MINIMUM MEASURED FLOW WHILE ABOVE P-7 AND BELOW P-8
- 2 of 3 NC flow channels on 1 of 4 NC loops - LESS THAN 90% OF LOOP MINIMUM MEASURED FLOW WHILE ABOVE P-8
- 4 of 4 turbine stop valves - CLOSED WHILE ABOVE P-9
- 2 of 4 turbine stop valves EHC pressure - LESS THAN 550 PSIG WHILE ABOVE P-9
- 1 of 2 S/I trains - ACTUATED
- 2 of 2 SSPS trains - GENERAL WARNING ALARM.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 30f61 3 of 61 Rev 36 DC~
- 2. The following are symptoms of a Reactor Trip:
- Any Reactor Trip annunciator - LIT
- Neutron level - RAPIDLY DECREASING
- Rod bottom lights lig hts - LIT.
- 3. The following are symptoms that require a Reactor Trip and 5/1: 811:
- 2 of 4 Pzr pressure channels - LESS THAN 1845 PSIG
- 2 of 3 containment pressure channels - GREATER THAN 1.2 PSIG.
- 4. The following are symptoms of a Reactor Trip and 5/1:
8/1:
- Any S/I SII Reactor Trip annunciator - LIT
- NV, NI, and NO ND pumps - ON
* "SAFETY INJECTION ACTUATED" status light (1SI-13) -LIT - LIT
- EIS E/S Load Sequencer Actuated status lights (1SI-14) -LIT.
- LIT.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/AlSOOO/E-O 4 of 61 40f61 Rev 36 DCEDC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- c. Operator Actions C.
IRO IRO DOES THIS PAGE
- 1. .W,
_sD:_~~tQf:ii_ Perform the following: _ J~mldJI&PQtt~mUTl~". _ .' ',,IIJ!I~.fqfjrr.ijp!;fjml~~~!(~!iijf'
- a. Manually trip reactor.
- b. IF reactor will not trip, THEN
- I
~~.n concurrently:
EP/1/A15000/F-O (Critical
- Implement EP/1/AlSOOO/F-O Safety Function Status Trees) .
EP/1/A15000/FR-S.1
- GO TO EP/1/AlSOOO/FR-S.1 (Response To Nuclear Power Generation/ATWS).
._------ Perform the following:
- a. Manually trip the turbine.
- b. IF turbine will not trip, THEN:
_ 1) Depress the "MANUAL" pushbutton on the turbine control panel. _ 2) Rapidly unload turbine by simultaneously depressing the "CONTROL VALVE LOWER" and push buttons.
"FAST RATE" pushbuttons.
- 3) IF turbine will not runback, THEN close:
- All MSIVs
_ .* All MSIV bypass valves.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O 50f61 5 of 61 Rev 36 DC~ DC~ I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED -0 :,..tEr.alll,~J~::~£it,UiRG~"~R) Perform the following:
- a. IF 1ETA AND 1ETB are de-energized, IBOP DOES THIS PAGE THEN GO TO EP/1/A15000/ECA-O.O (Loss Of All AC Power).
- b. WHEN time allows, THEN attempt to restore power to de-energized switchgear while continuing with this procedure. REFER TO AP/1/A15500/007 (Loss of Normal AP/1/A155001007 Power).
- a. a. Perform the following:
- 1) Verify conditions requiring S/I:
S/I should have _ _ .*. Pzr pressure - LESS THAN 1845 PSIG already been actuated, but if not, OR it will be done here, per RNa. _ . Containment pressure - GREATER THAN 1.2 PSIG. _ 2) IF S/I is required, THEN manually S/I. initiate SIlo
- 3) IF S/I is not required, THEN concurrently:
- Implement EP/1/A15000/F-O (Critical Safety Function Status Trees).
Trees) .
- GO TO EP/1/A15000/ES-O.1
- b. WI PI ,. (Reactor Trip Response).
- b. Manually initiate S/I.
SIlo 6.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 60f61 6 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7..P'tl"'Cr!Q~~"tiQ1i(il~'!Cjfi~J 7
-,.,.====
_ . iIllFeRGtmfHPII.tlIO/llJ§<'
- 11Il~§lICCiICl OfIJJiI.~IIf) 8.
-====--
.;REEElI\1m:f8i{QJ'/~O.l.ao" NtifrWti~"hVD~iii'" JtS:)<.:
q . . ~~.Jlt!i\!.Miisnl!l~~rn~i.M.<
<'W
. :t1 CRITICAL TASK IICRITICAL TASK
~:,lI1 ======
~ {.im~mY~II¥i;Jgillit~eil,qRt§jtl\f§_!~iI i_iQJ{~(§tm<t~;:,IJg~~IuttrMtiffII$'.
~~f~Io§¢1?JMEB~J1!4~lQlllt:ir...
9. IBOP I IBOP
- a. Manually initiate Phase A Isolation.
- b. b. Manually align valves.
~O.
~
-- a. Perform the following:
NOTE This time may be used later to determine when to align ND Aux spray. _ 1) Record approximate time of reactor trip. _ 2) Verify NS pumps -INDICATING
- INDICATING FLOW.
_ 3) IF flow is not indicated, THEN manually initiate Phase B Isolation for affected train(s). (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O 70f61 7 of 61 DC~ Rev 36 DC!: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (Continued)
- 4) Verify Phase B Isolation has actuated as follows:
_a) a) Phase B Isolation "RESET" lights - DARK. _ b) IF Phase B Isolation "RESET" lights are lit, THEN manually initiate Phase B Isolation. c) Verify following monitor light panel lights - LIT:
- Group 1 Sp lights
- Group 5 Sp lights
- Group 5 St lights U11 and U12.
_d)d) IF monitor light panel not in correct alignment, THEN ensure correct alignment. e) IF NS pump(s) did not start, THEN perform the following for the affected train(s): _ (1) Reset ECCS. _ (2) Reset DIG load sequencer. _ (3) Manually start affected NS pump. _ (4) IF AT ANY TIME a B/O occurs, THEN restart SII equipment previously on. _ 5) Stop all NC pumps. _ 6) Maintain seal injection flow. _ 7) Energize H2 igniters. (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EPI1IA15000/E-0 EP/1/A/5000/E-0 80f61 8 of 61 DC~ Rev 36 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (Continued)
- 8) Dispatch operator to perform the following:
_ a) Secure all ice condenser air handling units. REFER TO Enclosure 13 (Securing All Ice Condenser Air Handling Units). _ b) Place containment H2 analyzers in service. REFER OP/1/A164501010 TO OP/1IA/645010 10 (Containment Hydrogen Control Systems). _ 9) WHEN 9 minutes has elapsed, THEN verify proper VX system operation. REFER TO Enclosure 7 (VX System Operation). _10) GO TO Step 11. b. IBOP I
- 1. ¥~r,(.P:t.f~\QRin!ml\llIf";.$I@l.\!,§1
- a. _ _ _ _ _ __
a*~()t<¥~,tIrlhtl.~~li\il!l. a. Perform the following for the affected train(s): _ 1) Reset ECCS. _ 2) Reset DIG load sequencer. _ 3) Manually start affected motor driven CApump. CA pump. _ 4) IF AT ANY TIME a BIO occurs, b.,,_______ SII equipment THEN restart S/I previously on.
- b. Ensure CA Pump #1 - RUNNING.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O 9 of 61 90f61 Rev 36 DC~ ACTIONIEXPECTED RESPONSE ACTION/EXPECTED RESPONSE NOT OBTAINED
- 12. Perform the following for affected train(s):
IBOP I -:<I. :-iEEE
- a. Reset ECCS .
- b. Reset DIG load sequencer.
- c. Manually start affected pump.
- d. IF AT ANY TIME a 8/0 BIO occurs, THEN IBOP I restart 5/1 SII equipment previously on.
- 13. v,ti1f6I,r,~~;;'~Il~;!f~1Ij Perform the following for affected train(s):
- a. Reset ECCS.
- b. Reset DIG load sequencer.
- c. Manually start affected pump.
IBOP I d. IF AT ANY TIME a 8/0 BIO occurs, THEN 5/1 equipment previously on. restart SII J] I P II,' m 14.V","~Yijll;\UIjI~lll:cl.ug."pYln" 14. Pf(~i)
'I' Perform the following:
- a. IF any Unit 2 RN pump is off, THEN manually start affected pump(s).
Grew may reset EGGS and b. IF any Unit 1 RN pump is off, THEN DIG sequencers to secure perform the following for affected RN pump 1A 1A since it train(s): restarts on the SII S/I and it still _ 1) Reset ECCS. has Hi DIP. _ 2) Reset DIG load sequencer. _ 3) Manually start affected pump. _ 4) IF AT ANY TIME a 8/0 BIO occurs, THEN restart 5/1 SII equipment IBOP I previously on. 15.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-0 EP/1/A15000/E-0 10 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 16. Perform the following:
EJ a. Verify the following valves - CLOSED:
=.
All All All MSIVs MSIV bypass valves SIG PORVs.
- b. IF any valve is open, THEN:
_ 1) Manually initiate Main Steam Isolation. _ 2) IF any valve is still open, THEN manually close valve. IBOP 17. I _ _ _* _ _ __ 17. aa.f\~\'§f£If:J~W:':"lll'IJ,j~~T.S;f;"LiQrt:
. . . . . . . . . . . . . . . . .. _ a. Manually start NV pump(s) and align valves.
- b. _ _ _ _ _ _ _ __ b. _ _ _ __
- b. NP::Q03,8:q;A:;7:I~§~1i!lillll~'1J1fPI.ti b. "lllll<2\tmilt11ll1l1_i
_ 1l E.rEf'If'lp.*Jl~I!J~j;fiflllllt{ VIlg~;:p~) pp(r~tlllg;_I!~~ltif;Q\Pql 1NI-9A and 1NI-10B do not automatically position and the BOP should note and manually open these valves.
*2, '1Iillllllill.lm!lllil.IIII~II~t~!
':iimlli,!:l~ill~iMllll.'.~llirn!.~.lii.II.I;
';.II"OOI!II.!II!II'~I;llllllm~~III~t~~!
CRITICAL TASK to open at least one of these _ a) Reset ECCS. valves! _ b) Reset DIG load sequencer. _ c) Stop ND NO pump. _ d) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on. _ e) IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart the NO pump. _3).~ _ __
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11A15000/E-O EP/1/A/5000/E-O 11 of 61 Rev 36 DC~ DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. (Continued)
- c. *_ . ._ _ __
_ c. Manually start NI pump(s) and align IBOpr valves.
- d. _ _ _ __
_d. . . . . . . . . . . . . . .. _1)=====_
- 2) IF the NOND pump miniflow valve(s) cannot be opened, THEN perform the following for affected train(s):
_ a) Reset ECCS. _ b) Reset DIG load sequencer. _ c) Stop NOND pump. _ d) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on. _ e) IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart the NO ND pump. _ 3).11 II ,
- e. NO ND pumps -INDICATING
- INDICATING FLOW TO e. Manually start NO ND pump(s) and align C-LEGS. valves.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP/1/A/5000/E-0 12 of 61 Rev 36 DCE DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 18. Coijl'~I;$l.".II.I%;'~Up"
- a. y:~tif!J9t~f.;~A1T:1pw~It?~~lf1R'[~rt a. Perform the following:
4~(!)l~1;Mt _ 1) IF N/R level in all S/Gs is less than 11 % (29% ACC), THEN manually start CA pumps and ensure correct valve alignment.
- 2) IF N/R level in all S/Gs is less than 11 % (29% ACC) AND feed flow greater than 450 GPM cannot be established, THEN concurrently:
_ . Implement EP/1/A/5000/F-0 EP/1/A15000/F-0 (Critical Safety Function Status Trees) Trees)..
- GO TO EP/1/A/5000/FR-H.1 EP/1/A15000/FR-H.1 (Response To Loss Of Secondary Heat Sink).
b.
- 19. _ Manually open valve(s). valve(s}.
I IBOP \BOP 20.
!*IIII~====II_ _ Manually align equipment.
r:-:lf~1:-:'N":':'I--:::9~A-a-n-:d:-1:-:'N":':'I--:1-=-O-=B-a-re-st:":"!'iII:-c-:-lo-s-e-:d-,t~h-ey-w='1i11 20 Manually align equipment. BOP '1I IIBOP i If 1NI-9A and 1NI-1 OB are still closed, they will be opened based on this RNO RNO.. 1111 iiil 'I II iii EM
- 111111
- 21. B_
E] EJ
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11A15000/E-O EP/1/A/5000/E-O 13 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. illlitWIlr e.~rlij:t\It;p.~I:If'Y~~I'"
;~~r.:f,t.jf.j 1-**a::.]I;~fI~.E;J,ItV'I~aI2D) a. IF Pzr pressure is less than 2315 PSIG, IBOP IBOP I THEN:
_ 1) Manually close Pzr PORV(s). _ 2) IF any Pzr PORV cannot be closed, THEN close its isolation valve.
- 3) IF any Pzr PORV cannot be closed OR isolated, THEN perform the following:
_ a) Energize H2 igniters. b) Dispatch operator to perform the following: _ (1) Secure all ice condenser air handling units. REFER TO Enclosure 13 (Securing All Ice Condenser Air Handling Units). _ (2) Place containment H2 analyzers in service. REFER TO OP/1IAl6450/0 OP/1/A/6450/01010 (Containment Hydrogen Control Systems). (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP/1/A/5000/E-0 14 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. (Continued) c) IF both the following conditions exist,
_ .* Containment pressure - GREATER THAN 1 PSIG
- Containment pressure - HAS REMAINED LESS THAN 3 PSIG
_ THEN start one VX fan. REFER TO Enclosure 5 (VX Fan Manual Start). d) Concurrently: EP/1/A15000/F-0
- Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).
EP/1/A/5000/E-1
- GO TO EP/1/A15000/E-1 (Loss Of Reactor Or Secondary Coolant).
IBOPJ. I'IIIIIIII"II"""II'I"IIII'I'!III'.". b. IF Pzr pressure is less than 2260 PSIG, THEN: _ 1) Manually close spray valve(s).
- 2) IF spray valve(s) cannot be closed, THEN:
_ a) Stop NC pumps 1A and 1B. _ b) IF NC pressure continues to decrease, THEN stop third NC pump as required.
- c. c. IF power is available, THEN open one Pzr PORV isolation valve unless it was closed to isolate an open Pzr PORV.
IBOP I
- 23. IF any NV OR NI pump is on, THEN:
- a. Ensure all NC pumps - OFF.
- b. Maintain seal injection flow.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1 I A/5000/E-O 15 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSEII RESPONSF,; RESPONSE NOT OBTAINED
- 24. IF pressure in any S/G is decreasing in IBOP I an uncontrolled manner OR any S/G is depressurized, THEN perform the following:
.----- If the crew does not note the
- a. IF both the following conditions exist,
_ . Containment pressure - GREATER THAN 1 PSIG _ . Containment pressure - HAS 1A S/G PORVopen,PORV open, they REMAINED LESS THAN 3 PSIG may transition to E-2 to isolate the PORV and THEN _ THEN manually start one VX fan. go to E-3. If they note it, REFER TO Enclosure 5 (YX (VX Fan they will likely have closed Manual Start). the block valve by this point
- b. Concurrently:
and will continue in E-O. _ . Implement EPI1IA15000/F-O EP/1/A/5000/F-O (Critical Safety Function Status Trees). _ . GO TO EP/1/A15000/E-2 EP/1/A/5000/E-2 (Faulted Steam Generator Isolation).
"'Vlri,fl#S/D
~
+.~Htar'jriifMcl\a't;folllwsl:
IBJ~'I., BOP ,":"" ,~~u,,' ,M,,~"ik'='~ ~~" "",,,,,1,,,,,,,, ",'",",'
.~JVifflfli'Ut"eta'!tJ9iliNfFf>'tlipj'\ll~rglYn I.I.I,IIIJ,.IIIIIIIIIIIIIIII" lJ~RJ<:1
_ _ _I I _ ~g til1iIi1,Fi.:;tt~.Ti.1\1Iij"8 ii. *
- _-lla'lill
'lllil!JlUltl "it llflC!:'II';;JlE";D'61"t:Q';iS'~'1'I""1&l ifiJ\iY,
- \,;~~!f.:I*~U;:*::*,.. ".Llt~~.SfMf:e",r,~~R'S!n/P
- 1EMF-27 (Steamline 18) 1B)
- 1EMF-28 (Steam (Steamline line 1C)
- 1 EMF-29 (Steamline 1D).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP/1/NSOOO/E-0 32 of 61 Enclosure 1 - Page 1 of 1 Rev 36 DC~ Foldout Page 1. 1 JF"':'>"~,'S'~'l"~~:~li.F 11M'-ii¥_j~'i.a1ilMi1TIEtf"':';"~""" *'*;'*1Oi"'*~n~Uliw_
........,any.,.!~.lfiij~~h\!.iIi!_,__Jf;~{~:
it ~""", WIEli:ttle;fi5rrblii~\ x;* .~U,TJl.W\pbtif; __ .,, . . ., ..... ,.\nB.tl!!ll'IR~~k* j.,
,1J!ii!I\tF' If
**~~;l:Q.m:t,;.~J.~,_J:~c!!'{* .AD
.1 ~9f8~I.I!~:tU1ll1~tI~~f;RIH~.~fl'ij
,AtIlt
.) i~lllht,Q.,~IG"llifllRil~l~':;**.;B,IlA:Jje""1;'f/6,{~11ll"
.!.J.I.B!.1"g1ttl"'~¥'i',~, ' .*... "... ,.~, "M!fil., ".~%,\;$' ).'"
TLlm:kI.;.1tdf"'++I&;;*'KiSd;,ffQwf(5)1MiItj~Cf:f5/G< to ,m';;u~\I'tureBfSt~!KlAI;>>rm~'~~2iem
~!la_ir,IiIiP"",,,,,,,,,,., .....,\_L\,:'h'Ald!Sfu14"fi!WR!"';,"!li17i~\L".,
1:1 ft{_,t(fl;r~nq~,,~ar.
- 2. NC Pump Trip Criteria:
- IF the following conditions are satisfied, THEN trip all NC pumps while maintaining seal injection flow:
- At least one NV or NI pump - ON
- NC subcooling based on core exit TICs - LESS THAN OR EQUAL TO O°F. OaF.
- 3. CA Suction Source Switchover Criteria:
- IF either of the following annunciators are lit, THEN REFER TO AP/1/NSSOOI006 AP/1/A15500/006 (Loss of S/G Feedwater):
1AD-S, H/4 "CACST LO LEVEL"
- 1AD-5, OR
- 1AD-8, B/1 "UST LO LEVEL".
- 4. Position Criteria for 1 NV-202B and 1NV-203A (NV Pumps A&B Recirc Isol):
- IF NC pressure is less than 1S00 1500 PSIG AND NV SII S/I flowpath is aligned, THEN close 1NV-202B and 1NV-203A.
- IF NC pressure is greater than 2000 PSIG, THEN open 1NV-202B and 1NV-203A.
S.
- 5. Cold Leg Recirc Switch Switchover over Criterion:
- IF FWST level decreases to 37% (1AD-9, D/8 "FWST 2/4 LO LEVEL" lit), AND an S/I SII has occurred, THEN GO TO EP/1/NSOOO/ES-1.3 EP/1/A15000/ES-1.3 (Transfer To Cold Leg Recirculation).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11A15000/E-O EP/1/Al5000/E-O 33 of 61 Enclosure 2 - Page 1 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. IBOP DOES THIS ENCLOSURE I
- j
- a. Perform the following:
_ 1) Shift operating VCIYC trains.
--=-1-iiii
.v 1 REFER TO Enclosure 6 (Shifting Operating VCIYC Train).
- 2) IF no train can be properly aligned, THEN dispatch operator and IAE/Maintenance to restore at least one train of VCIYC. REFER TO the following:
_ .- OP/OIAl6450/011 _ OP/O/Al6450/011 (Control Room Area Ventiiation/Chilied Ventilation/Chilled Water System)
-* EM/O/Al5200/001 EM/OIAl5200/001 (Troubleshooting Cause For Improper Operation of VCIYC System).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/SOOO/E-O EP/11A15000/E-O 34 of 61 Enclosure 2 - Page 2 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE I. RESPONSE NOT OBTAINED
- 1. (Continued)
.==
ilili
- b. 'l~fif!'~~;if~lfMrt{;E~J"'~~~ b. IF chlorine odor is detected in the Control Room, THEN perform the
_ .:~PfQlfl;~&!:\'mIIIJ U\fr~.~IIHI following based on the status of given _. ._=-....
~ijlll>lll~~1ta' leil-lal_~IT;,"'IIIIf",II<ElI'HI alarms:
1)
- 1) IF detectors on both unit intakes are
.=.
==....-
CtlL,<lRllHIEI'g
,:1~'&, :~1a:;.II.,2)11.~;IFi
- Clilll>illf;~~
1e1l.BI8JIl~\1J11.2.;1tJ:'~~.I,'j in alarm, THEN: a) Ensure the following VC intake dampers - CLOSED: 1VC-58 1VC-S8 (CRA Filt Inlet) CI1U.I1RUf*Et~lI~ _ .* 1VC-6A (CRA Filt Inlet) _ .* 2VC-58 2VC-S8 (CRA Filt Inlet) _ .* 2VC-6A (CRA Filt Inlet). _ b) GO TO Step 1.d.
- 2) IF Unit 1 intake HI chlorine detector(s) in alarm, THEN:
a) Ensure the following VC dampers - CLOSED: _ . 1VC-58 1VC-S8 (CRA Filt Inlet) _ . 1VC-6A (CRA Filt Inlet). b) Ensure the following dampers - OPEN: _ . 2VC-58 2VC-S8 (CRA Filt Inlet) _ . 2VC-6A (CRA Filt Inlet). _ c) GO TO Step 1.d. (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A1S000/E-O 35 of 61 3S Enclosure 2 - Page 3 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. (Continued)
- 3) IF Unit 2 intake Hi chlorine detector(s) in alarm, THEN:
a) Ensure the following VC dampers - CLOSED: _ . 2VC-S8 2VC-58 (CRA Filt Inlet) _ . 2VC-6A (CRA Filt Inlet). dampers - b) Ensure the following dampers-OPEN: _ . 1VC-S8 1VC-58 (CRA Filt Inlet) _ . 1VC-6A (CRA Filt Inlet). _ c) GO TO Step 1.d. c.
-IF d;~~~ <~,.;:,
iRDn&atiSte1li'<1)t)ff
~~.. h.,.', jOi;\.
*f19!m~~!:~y:*§t@t~@'* *~.:1~
t91!~~~l' Kls
\~',eC,.wjhi"' ~ ftl diWct*i!!iPSlI~t;
~,f',.. .H:~~M;;;i'.~hU!
_*"1 _ ilv ~~fe;,~.~'Y~!f:f:"Q~; 1111 !!i iii 9 lIB
- *1111 11111111 111.111111
* 'II
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/A15000/E-O 36 of 61 Enclosure 2 - Page 4 of 7 DC~ Rev 36 DCS Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. E;pjl~l.q.r,N,I,~y~.(itI.:~aqqma f"lr:.:-~
Jl""gJ . . ll''k
*\sI1,~.!IHC9JJ(j)W,. . .t\l1~f!'1=:'
=-'I *
-:;~:~~tii:~j
" I Glj fErlslJt4fWAj7S?ste~m!I:~.l!!dil.\1:t~i!i.:J"~"'\
-1,.I!lIiili~IIIIIIIIIiiiiIlIlIiiii"
... " .,,,, ..*.. , .. ,'Y,,, *.
fQIlq~1 IrUV1M!i'f'_lYQ?".
-===-----
_ \~~i1:~~fill~,1;~.:illa:Filf~r:A B9P§~j
-==---
O~mJref§)i;~s'~eO~'Q
.~;] ;:tt\BJf~Jl7§?J8l';;.~(mfl:!lti~ia, avp~1
..._---- *1¥;ittrtR&@:~t~;;_.1I
* "'1niiiffiia*1th'!id;Ei'\fllwrii\11;.rllijl:l!1O~'"
,~,!&Jf~t:~);*'~lil~Jx<> /MhU~'.kM;~J1JM:;\~t<%v"Mk~!'?*
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/SOOO/E-0 EP/1/A1S000/E-0 37 of 61 Enclosure 2 - Page S of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3lti";ioFi1lliI"lllr'iRiiO.rI\JIE*S0s*"~d!ifM;N~ew'W;~I*'O*'**'.n'Ta'a;., 3...et.**"",.iPH'!'" ~'i}L., .. ~..L~H " *.".!.~~......"" .....,~ 2fQ:IIQM;} _ \j~j ,ifJ;*lt.llllDlNl a. Manually start fan(s).
- b. !~g'nl,J!.q~:pr$'~~~t~*~.~.~.!i. b. Perform the following:
i.i1t4'.IN~W~\.'l{~);::i1,;a\t.~ WIll
- 1) IF annulus pressure is more positive than -1.4 in. WC, THEN:
a) Verify flow indicated on the following indications:
- JIVE "VE 11A A FLOW TO STACK" JIVE 1B FLOW TO STACK".
* "VE b) IF flow is not indicated, THEN dispatch operator to verify status of the following dampers based on their local indication or their operating piston rods being extended 4" to 6":
1AVS-D-2 (VE A Trn Recirc
- 1AVS-D-2 Damp) (AB-603, JJ-S1, Rm SOO) - CLOSED
- 1 AVS-D-7 (VE B Trn Recirc 1AVS-D-7 Damp) (AB-603, HH-S2, Rm SOO) - CLOSED 1AVS-D-3 (VE A Trn Exh
- 1AVS-D-3 Damp) (AB-603, JJ-S2, Rm SOO) - OPEN
- 1 AVS-D-8 (VE B Trn Exh 1AVS-D-8 Damp) (AB-603, HH-S2, Rm SOO) - OPEN.
_ c) Consult plant engineering staff _c) and notify IAE/Maintenance to troubleshoot and repair. REFER TO EM/1/A/S2001002 EM/1/A1S2001002 (Troubleshooting Cause For VE System Hillo HilLo Pressure). _d) GO TO Step 3.c. (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/11A15000/E-O 38 of 61 Enclosure 2 - Page 6 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued)
- 2) IF annulus pressure is more negative than -1.8 in. WC, THEN:
_ a) Determine which VE train indicates highest discharge flow to stack. _ b) Within 2 hours, ensure VE train that indicates highest discharge flow to stack is secured. _ c) Consult plant engineering staff and notify IAE/Maintenance to troubleshoot and repair. REFER TO EM/11A152001002 EM/1/A152001002 (Troubleshooting Cause For VE System Hi/lo Hillo Pressure). c.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11A15000/E-0 EP/1/A/SOOO/E-O 40 of 61 Enclosure 3 - Page 1 of 1 DC~ Rev 36 DC!: Opposite Unit Ventilation Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. Ensure proper Unit 2 VA System operation as follows:
- Ensure the following fans - OFF:
- ABUXF-2A
- ABUXF-2B.
- Ensure VA System filter is in service as follows:
_ . 2ABF-D-12 & 19 (VA Filter A Bypass Dampers) - CLOSED _ . 2ABF-D-5 2ABF-D-S & 20 (VA Filter B Bypass Dampers) - CLOSED.
- Ensure the following fans - ON:
- ABFXF-2A
- ABFXF-2B.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11A/SOOO/E-O EP/1/Al5000/E-O Enclosure 4 - Page 1 1 of 4 41 of 61 61 Rev 36 DC~ NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1.
- Perform the following:
- a. Use NC T -Colds to determine NC IRO DOES THIS ENCLOSURE I temperature as required in subsequent steps.
- b. GO TO Step 4.
2.
- I 3.
.-=====--
44*Ytl.AfI'};.I:~lefllIIIIII~}
. GO TO Step 7.7.
* '.:t~I1III~1t11~\~III's.f:Ii~**IiIlItA_
T"9fifi~tm~.aa1'Fi~.** all "PII ,,!!
*~} \.~.,t$.ralfmli.>+IIf~.mK~.~Ri!!bfil Ii II 5.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1 I A/5000/E-O 42 of 61 Enclosure 4 - Page 2 of 4 DC~ Rev 36 DCS NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6.
- NC temperature - GREATER THAN 55rF AND INCREASING IN AN UNCONTROLLED MANNER.
OR
- NC temperature - GREATER THAN 557°F AND STABLE.
OR
- NC temperature - LESS THAN 55rF AND DECREASING IN AN UNCONTROLLED MANNER.
- 7. Verify NC temperature*
temperature - LESS THAN Perform the following: 557°F AND DECREASING.
- a. IF NC temperature is greater than 55rF AND increasing, THEN stabilize NC temperature at 55rF 557°F as follows:
- 1) IF steam dumps are available, THEN use steam dumps.
- 2) IF steam dumps are not available, THEN use SIG PORVs.
- b. IF the following conditions exist:
- NC temperature is greater than 55rF and stable
- Time and manpower is available, THEN stabilize NC temperature at 557°F as follows:
55rF
- 1) IF steam dumps are available, THEN use steam dumps.
- 2) IF steam dumps are not available, THEN use SIG PORVs.
- c. GO TO Step 9.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/N5000/E-O 43 of 61 Enclosure 4 - Page 3 of 4 Rev 36 DC~ NC Temperature Control ACTIONIEXPECTED ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. Attempt to stop the NC cooldown as follows:
- a. Ensure all steam dumps - CLOSED.
- b. Ensure all S/G PORVs - CLOSED. b. IF any S/G PORV cannot be closed, THEN close its isolation valve.
- c. Ensure S/G blowdown is isolated.
- d. Close the following valves:
- 1SM-77A (S/G 1A Otlt Hdr Bldwn CN)
- 1 SM-76B (S/G 1B 1SM-76B 1B Otlt Hdr Bldwn CN)
- 1SM-75A (S/G 1C Otlt Hdr Bldwn CN)
- 1SM-74B (S/G 1 1D D Otlt Hdr Bldwn CN).
- e. Depress and hold "SN BEFORE SEAT DRN" "CLOSE" pushbutton (1 MC-3) to close the following valves:
- 1SM-41 (Stop Vlv #1 Before Seat Drn) 1SM-44 (Stop Vlv #2 Before Seat
- 1SM-44 Drn)
- 1 SM-43 (Stop Vlv #3 Before Seat 1SM-43 Drn)
- 1SM-42 (Stop Vlv #4 Before Seat Drn).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/11A/5000/E-O 44 of 61 Enclosure 4 - Page 4 of 4 Rev 36 DC~ NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (Continued)
- f. Verify NC cooldown - STOPPED. f. IF cooldown continues, THEN throttle feed flow as follows:
- 1) IF S/G N/R level is less than 11 %
(29% ACC) in all S/G's, THEN throttle feed flow to achieve the following:
- Minimize cooldown
- Maintain total feed flow greater than 450 GPM.
- 2) WHEN N/R level is greater than 11 % (29% ACC) in at least one S/G, THEN throttle feed flow further to achieve the following:
- Minimize cooldown
- Maintain at least one S/G N/R level greater than 11 %
(29% ACC).
- 3) IF cooldown continues, THEN close the following valves:
- All MSIVs
- All MSIV bypass valves.
- 9. Continue to perform the actions of this enclosure as required to ensure one of the following:
- NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.
OR
- NC temperature - TRENDING TO 55rF.
rfj;) ({j;) CNS EP/1/A/5000IE-3 EP/1/N5000/E-3
\, --
STEAM GENERATOR TUBE RUPTURE PAGE NO. 1 of 110 Rev 34 DC~ A. Purpose This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture. B. Symptoms or Entry Conditions This procedure is entered from: EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection), Step 25, when condenser air ejector
- a. EP/1/N5000/E-0 radiation, S/G blowdown radiation or steamline radiation is abnormal.
EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection), Step 30, EP/1/N5000/E-1
- b. EP/1/N5000/E-0 EP/1/A/5000/E-1 (Loss Of EP/1/A/5000/E-2 (Faulted Steam Generator Reactor Or Secondary Coolant), Step 5, EP/1/N5000/E-2 Isolation), Step 10, EP/1/A/5000/ECA-2.1 EP/1/N5000/ECA-2.1 (Uncontrolled Depressurization Of All Steam Generators), Step 7, and EP/1/A/5000/FR-H.3 EP/1/N5000/FR-H.3 (Response To Steam Generator High Level), Step 8, when secondary radiation is abnormal.
EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection), Step 29, EP/1/A/5000/E-1
- c. EP/1/N5000/E-0 EP/1/N5000/E-1 (Loss Of EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Reactor Or Secondary Coolant), Step 4, EP/1/N5000/ES-1.2 EP/1/A/5000/ES-3.1 (Post - SGTR Cooldown Using Backfill),
Depressurization), Step 10, EP/1/N5000/ES-3.1 Step 6, EP/1/A/5000/ES-3.2 EP/1/N5000/ES-3.2 (Post - SGTR Cooldown Using Blowdown), Step 6, EP/1/A/5000/ES-3.3 (Post - SGTR Cooldown Using Steam Dump), Step 8, EP/1/N5000/ES-3.3 EP/1/A/5000/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery EP/1/N5000/ECA-3.1 EP/1/A/5000/ECA-3.2 (SGTR With Loss Of Reactor Coolant-Desired), Step 12, and EP/1/N5000/ECA-3.2 Coolant - Saturated Recovery Desired), Step 6, when a S/G N/R level increases in an uncontrolled manner.
- d. Any foldout page that has E-3 transition criteria whenever any S/G level increases in an uncontrolled manner or any S/G has abnormal radiation.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 EP/1/A15000/E-3 2 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- c. Operator Actions
- 2. Identifyruptur~'~'SlG(s)~s fon§~~; Perform the following:
IRO *. OR
...Jl**..
i$IG!eve'-:;IN~~E~SIl'JGINf~,bl
. . . .,IffIPII'IJJJ...
UNCONIR.OJ.LED MAt)J.N~R¥*
*BIllllll
- a. WHEN ruptured S/G(s) is identified, THEN perform Steps 3 through 9.
- b. GO TO Step 10.
_ . RP determines ruptured S/G by frisking the cation columns in the CT lab. OR
- The foUowi ng'§:NfI['!~r:ip)i;~ 'ligQt~ .E,:1::ljf:1
- 1i3MP-g6 :(qtearTIline t~~1 Crew may ask RP to frisk CAT EMF-27 (Steamline 1B)
- 1EMP-27 COLUMNS to get confirmation of
- 1EMF-28 EMP-28 (Steamline 1C) leak. This takes about 5 minutes.
Sampling takes about 1 hour. EMF-29 (Steamline 1 D).
- 1EMP-29 OR
- IF S/G Sampling is required to identify ruptured S/G(s), THEN:
- a. Ensure the following signals -
RESET: _ 1) Phase A Containment Isolations. _ 2) CA System valve control. _ 3) KC NC NI NM St signals.
- b. Align all S/Gs for Chemistry sampling.
- c. Notify Chemistry to sample all S/Gs for activity.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/Al5000/E-3 EP/1/A/5000/E-3 3 of 110 DC~ Rev 34 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. :1~:l"imllllg~§J*11§tigmiilJ~~J:i~Z~!llj VifrifY'!iilleqst'oneiQtacfS1G'.f' Maintain one S/G available for NC
- AVAIl:AI3.l:EFgJ~.Nq.§YS-':~M
- ~I~JJ!!~!!I.§!fim!ili~J~i!~Il§ll§M System cooldown in subsequent steps.
~If)tI;!llittliiN; POOLDOWN.
4. EJ _ 1) IEf;j~y~~e,§rtllR!!rl:gcH!SlG(s)4P?PBY."
- J~[~~§q?
The PORV block valve may ili!I!1EI!!:~ already have been isolated _ 2) iIFtI!R~Ufeg:t{?L{3(S)*PO~'\Y~'wur;nQf' already have been isolated - 2) :glos~t~iTHE!f.llfnafJually QIg>$~ If not it will be closed here. jegptO'G~d ~%GXs) :fi*Q;>RV::liMlation CRITICAL TASK! vaN~: _ 3) IF ruptured S/G(s) PORV isolation valve will not manually close, THEN dispatch operator to close ruptured S/G(s) PORV isolation valve.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/A/5000/E-3 4 of 110 DC~ Rev 34 OCl: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
- b. Verify SIG(s>>)1 B and::~C - JNTACT .. b. Perform the following:
_ 1} IF both motor driven CA pumps 1) available, THEN close the "CAPT TRIP TN CTRL". _ 2) IF CA Pump #1 is the only source of 2} feedwater, THEN maintain steam flow to the CAPT from at least one S/G. 3}
- 3) IF S/G 1B is ruptured, THEN:
_ a} a) Dispatch two operators to unlock and close 1 SA-1 (1B 1SA-1 (1 B S/G Main Steam to CAPT Maintenance Isol) (DH-624, (OH-624, FF-53, Rm 572) (Breakaway lock installed). _ b) b} IF 1SA-1 cannot be closed, THEN dispatch two operators to unlock and close 1 1SA-3 SA-3 (1 B S/G Main Steam to CAPT Stop
~O-53, Rm Check) (AB-551, DO-53, 217) (Breakaway lock installed).
4}
- 4) IF S/G 11CC is ruptured, THEN:
_ a) Dispatch two operators to unlock a} and close 1 SA-4 (1C 1SA-4 (1 C S/G Main Steam to CAPT Maintenance Isol) (DH-624, (OH-624, FF-53, Rm 572) (Breakaway lock installed). _ b} IF 1SA-4 cannot be closed, b) THEN dispatch two operators to unlock and close 1SA-6 (1 C S/G Main Steam to CAPT Stop Check) (AB-551, DO-53, Rm 217) (Breakaway lock installed) (Ladder needed). _ 5}
- 5) WHEN the ruptured S/G steam supply to CA Pump #1 is isolated, THEN open the "CAPT TRIP TN CTRL".
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/A/5000/E-3 5 of 110 Rev 34 DC~ DC!: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
EJ c. I§QJ;ate bloV(d9Wn ~nll~~e,~,fn~pr?:U~:lpQ;al! rUP1!J red *S/~J~1';a~lfp,lt9Yl?:'
- Sl~i1A:
_ 1 )\;~!i::rse1;i1$MilZI~f{(qfG1~iOtlVJf:t9r _ 1) Dispatch operator to close Bl(!wt1'CN~~ 1SM-77A (S/G 1A Otlt Hdr Bldwn
*.*.,.'".~;,.,,1. I~RITICAL TASK CRITICAL TASK J CN) (DH-583, FF-GG, 43-44, Rm 591).
591 ).
- 2) t~er:ity;th)~1tgllowiQg' blo~q.9'11n
\i~Q!1;!Ji9J1Ycilv~s7}~LOS ED:
_ :~); 11;;~BtQpA (Sf~,1A~U~WllC9nt _ a) Manually close valve. tl~QI}lll~d) .** _ b )l§~i~;i!f~~if(§i~J~"H]dYlt1 b) Perform the following: c:****f'fl**** 'lilB~"J!V Cq.I;U;,~q.x .,YP4,~ _ (1) Manually close valve. (2) IF valve will not close AN D 1 BB-56A is open, AND THEN perform the following:
- 1. Ensure "SfG "S/G A BLOWN BLDWN FLOW CTRL" - CLOSED.
- 2. Dispatch operators to ensure the following valves - CLOSED:
- 1BB-148B (SfG(S/G 1A Bldwn Cont Isol Byp) (DH-580, EE-FF, 44-45, Rm 591) 591 )
- 1BB-81 (1A SfG S/G Blowdown Penetration Valve Test Isol) (DH-583, EE-FF, 44, Rm 591 ).
591).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/11A15000/E-3 6 of 110 DC~ Rev 34 DeS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
_ c)1.BI:B~;>;r:!? .(SfG*t~~~I¢W:i\ qi?:Qt c) Perform the following: J~.oll@t§:g)~: _ (1) Manually close valve. (2) IF valve will not close AND 1 BB-56A is open, 1BB-56A THEN perform the following:
- 1. Ensure "S/G A BLDWN FLOW CTRL" - CLOSED.
- 2. Dispatch operators to ensure the following valves - CLOSED:
- 1BB-57B (S/G 1A 1A Bldwn Cont Isol Otsd) (DH-580, EE-FF, 44-45, Rm 591) 1BB-81 (1A S/G
- 1BB-81 Blowdown Penetration Valve Test Isol) (DH-583, EE-FF, 44, Rm 591).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1// A/5000/E-3 EP/1 7 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
- S/G 1B:
_ 1) Close 1SM-76B 1SM-76B (S/G 1B1B Otlt Hdr _ 1) Dispatch operator to close Bldwn CN). 1SM-76B (S/G 1B Otlt Hdr Bldwn CN) (DH-583, FF-53, Rm 572).
- 2) Verify the following blowdown isolation valves - CLOSED:
_ 1BB-19A (S/G 1B a) 1BB-19A(S/G 1B Bldwn Cont _ a) Manually close valve. Isollnsd). _ b) 1BB-150B (S/G 1B Bldwn b) Perform the following: Cont Isol Byp). _ (1) Manually close valve. (2) IF valve will not close AND 1 BB-19A is open, THEN perform the following:
- 1. Ensure "S/G B BLOWN FLOW CTRL" - CLOSED.
- 2. Dispatch operators to ensure the following valves - CLOSED:
- 1BB-150B (S/G 1B Bldwn Cont Isol Byp) (DH-580, FF, 52-53, Rm 572)
- 1BB-83 (1 B S/G Blowdown Penetration Valve Test Isol) (DH-580, FF-53, Rm 572).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 8 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
_ c) 1BB-21 B (S/G 1B Bldwn Cont c) Perform the following: IsoIOtsd). _ (1) Manually close valve. (2) IF valve will not close AND 1 BB-19A is open, 1BB-19A THEN perform the following:
- 1. Ensure "S/G B BLDWN FLOW CTRL" - CLOSED.
- 2. Dispatch operators to ensure the following valves - CLOSED:
1BB-21B (S/G 1B
- 1BB-21B(S/G1B Bldwn Cont Isol Otsd) (DH-580, FF, 52-53, Rm 572)
- 1BB-83 (1 B S/G Blowdown Penetration Valve 1501) (DH-580, Test Isol)
FF-53, Rm 572).
CNS STEAM GENERATOR GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 9 of 110 DC~ Rev 34 DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
- S/G 1C:
_ 1) Close 1SM-75A (S/G 1C Otlt Hdr _ 1) Dispatch operator to close Bldwn CN). 1SM-75A 1 SM-75A (S/G 1C 1C Otlt Hdr Bldwn CN) (DH-580, GG, 52-53, Rm 572).
- 2) Verify the following blowdown isolation valves - CLOSED:
_ a) 1BB-60A (S/G 1C Bldwn Cont _ a) Manually close valve. Isollnsd). _ b) 1BB-149B (S/G 1C Bldwn b) Perform the following: Cont Isol Byp). _ (1) Manually close valve. (2) IF valve will not close AND 1 BB-60A is open, THEN perform the following:
- 1. Ensure "S/G C BLDWN FLOW CTRL" - CLOSED.
- 2. Dispatch operators to ensure the following valves - CLOSED:
- 1BB-149B (S/G 1C Bldwn Cont Iso IsolI Byp) (DH-578, FF-GG, 52, Rm 572)
*.1BB-82(1CS/G 1BB-82 (1 C S/G Blowdown Penetration Valve Test Isol) (DH-583, FF-53, Rm 572).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/N5000/E-3 EP/1/A/5000/E-3 10 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
_ c} c) 1BB-61B (S/G 1C Bldwn Cont c) Perform the following: c} IsoIOtsd). _ (1) Manually close valve. (2) IF valve will not close AND 1BB-60A is open, THEN perform the following:
- 1. Ensure "S/G C BLDWN FLOW CTRL" - CLOSED.
- 2. Dispatch operators to ensure the following valves - CLOSED:
- 1BB-61B(S/G1C 1BB-61B (S/G 1C Bldwn Cont Isol Otsd} (DH-578, Otsd)
FF-GG, 52, Rm 572)
- 1BB-82 (1C S/G Blowdown Penetration Valve Test Isol) (DH-583, FF-53, Rm 572).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/N5000/E-3 11 of 110 Rev 34 DC!:: OCt ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
- S/G 10:
1D: _ 1) Close 1SM-74B 1SM-74B (S/G 101D Otlt Hdr _ 1) Dispatch operator to close Bldwn CN). 1SM-74B 1SM-74B (S/G 10 1D Otlt Hdr Bldwn CN) (DH-583, FF-GG, 44-45, Rm 591 ).
- 2) Verify the following blowdown isolation valves - CLOSED:
_ a) 1BB-8A (S/G 10 1D Bldwn Cont _ a) Manually close valve. Isollnsd). _ b) 1BB-147B (S/G 10 1D Bldwn b) Perform the following: Cont Isol Byp). _ (1) Manually close valve. (2) IF valve will not close AND 1BB-8A is open, THEN perform the following:
- 1. Ensure "S/G D 0 BLOWN BLDWN FLOW CTRL" - CLOSED.
- 2. Dispatch operators to ensure the following valves - CLOSED:
- 1BB-147B (S/G 1D Bldwn Cont Isol Byp) (DH-582, EE-FF, 44, Rm 591)
- 1BB-80 (1 D S/G Blowdown Penetration Valve Test Isol)
(DH-583,EE-FF, 44, Rm 591).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/A/5000/E-3 12 of 110 120f110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. (Continued)
_ c) BB-1 OB (S/G 1 c} 11BB-10B 1DD Bldwn Cont c} c) Perform the following: IsoIOtsd). _ (1) Manually close valve. (2) IF valve will not close AND 1 BB-8A is open, 1BB-8A THEN perform the following:
- 1. Ensure "S/G D BLDWN FLOW CTRL" - CLOSED.
- 2. Dispatch operators to ensure the following valves - CLOSED:
- 11BB-10B(S/G1D BB-10B (S/G 1D Bldwn Cont Isol1501 Otsd}
Otsd) (DH-582, EE-FF, 44, Rm 591) _ .* 1BB-80 1BB-80 (1D(1 D S/G Blowdown Penetration Valve Test Isol} 1501) (DH-583,EE-FF, 44, Rm 591).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/N5000/E-3 EP/1/A15000/E-3 130f110 13 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. Perform the following:
- a. Close the following valves on remaining S/Gs:
CLOSING 1SM-7 is a
!CLOSING
!,..,.n,T'CAL CRITICAL TASKTASK I
=.
- MSIV
_ . MSIV bypass valve.
- b. Place steam dump control in manual and lower controller output to 0%.
- c. Place "STEAM DUMP SELECT" switch in pressure mode.
- d. Transfer turbine steam seal supply to AS as follows:
_ 1) Open 1TL-8 (Aux Stm To Stm Seal Reg). _ 2) Close 1TL-2 (Main Stm To Stm Seal Reg).
- e. Ensure the following turbine SN before seat drain valves - CLOSED:
- 1SM-41 (Stop Vlv #1 Before Seat Drn)
Dm)
- 1SM-44 (Stop Vlv #2 Before Seat Drn)
Dm)
- 1SM-43 (Stop Vlv #3 Before Seat Drn)
Dm)
- 1SM-42 (Stop Vlv #4 Before Seat Drn).
Dm).
- f. Close 1AS-1 (SM To AS Inlet).
- g. Ensure the following valves - CLOSED:
- 1HM-1 (MSRH 1A&1 B SSRH Stm Source)
- 1HM-2 (MSRH 1C&1D SSRH Stm Source).
(RNO continued on next page)
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A1S000/E-3 EP/1/A/SOOO/E-3 14of110 140f110 Rev 34 DC~ DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED S. (Continued)
- h. Dispatch operator to isolate steam flow from all ruptured S/G(s). REFER TO Enclosure 2 (Locally Isolating Steam Flow From Ruptured S/G(s>>.
- i. WHEN cool down is initiated in cooldown subsequent steps, steps. THEN use intact S/G(s) PORV for steam dump.
_ j. IF at least one intact S/G cannot be isolated from all ruptured S/G(s), S/G(s). THEN EP/1/A1S000/ECA-3.1 (SGTR GO TO EP/1/A/SOOO/ECA-3.1 With Loss Of Reactor Coolant-Coolant - Subcooled Recovery Desired). 6. a._ CQhfrbr'rqA'turgd)$l,§X§r'levela,$"fO,II,Pw~;;:
- a. Verify ruptur~d S/G(s) NfR;;!¢v$J ,-'
GRg~TER)GJjAN11 %J4~;o~ ACC).,
- a. Perform the following:
_ 1) IF any ruptured S/G is also faulted. faulted, THEN do not establish feed flow to the ruptured S/G unless needed for NC System cooldown.
- 2) IF any ruptured S/G(s) is not faulted OR is required for cooldown, cooldown. THEN:
_ a) Establish and maintain feed flow to affected S/G(s). _ b) WHEN affected S/G(s) N/R level greater than 11 % (29% ACC). ACC), THEN perform Steps 6.b and 6.c. _ 3) GO TO Step 7.
CNS TUBE RUPTURE STEAM GENERATOR TU8E PAGE NO. EP/1/A15000/E-3 15 of 110 150f110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. (Continued)
- b. Iso.I~!~ feep ,flQw *10 alrF:i1ptur~p S;;g3{§)}
asSlfQ'Ui[>ws;;
'!~J '$I,{:?:.~1A:
_8 1) Perform the following: 1CA-60 (CA Pump 1A _ a) Close 1CA-60 Flow To S/G 1A). CLOSING BOTH THESE VALVES IS CRITICAL _ b) Dispatch operator with 14" valve wrench to close 1CA-62A (CA Pmp A Disch To S/G 1A Isol) (DH-587, DD-EE, 44-45, Rm 591). _ 2) :Clos~ 1GA-6.6B(CAPr;tip1.. .!!i~Q.g. 2) Perform the following: To S/G ;1.¥\ 1~9I); _ a) Close 1CA-64 (CA Pump #1 Flow To S/G 1A). _ b) Dispatch operator with 14" valve wrench to close 1CA-66B (CA Pmp 1 Disch To 1CA-668 S/G 1A Isol) (DH-584, DD-EE, 44-45, Rm 591) .
- S/G 18: 1B:
_ 1) Close 1CA-58A (CA Pmp A Disch 1) Perform the following: To S/G 18 1B Isol). _ a) Close 1CA-56 (CA Pump 1A 1B). Flow To S/G 18). _ b) Dispatch operator with 14" valve wrench to close 1CA-58A (CA Pmp A Disch 1B Isol) (DH-586, To S/G 18 DD-EE, 52-53, Rm 572).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 16 of 110 DC~ Rev 34 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. (Continued)
_ 2) Close 1CA-54B (CA Pmp 1 Disch 2) Perform the following: To S/G 1B Isol). _ a) Close 1CA-52 (CA Pump #1 Flow To S/G 1B). _ b) Dispatch operator with 14" valve wrench to close 1CA-54B (CA Pmp 1 Disch To S/G 1B Isol) (DH-584, DD-EE, 52-53, Rm 572) .
- S/G 1C:
_ 1) Close 1CA-46B (CA Pmp B Disch 1) Perform the following: To S/G 1C Isol). _ 1CA-44 (CA Pump 1B a) Close 1CA-44 1B Flow To S/G 1 C). 1C). _ b) Dispatch operator with 14" valve wrench to close 1CA-46B (CA Pmp B Disch To S/G 1C Isol) (DH-586, DD, 53-54, Rm 572). _ 2) Close 1CA-50A (CA Pmp 1 Disch 2) Perform the following: To S/G 1C Isol). _ a) Close 1CA-48 (CA Pump #1 1C). Flow To S/G 1C). _ b) Dispatch operator with 14" valve wrench to close 1CA-50A (CA Pmp 1 Disch To S/G 11C C Isol) (DH-584, EE-53, Rm 572) .
- S/G 1D:
_ 1) Close 1CA-42B (CA Pmp B Disch 1) Perform the following: To S/G 1D Isol). _ a) Close 1CA-40 1CA-40 (CA Pump 1B 1B Flow To S/G 1 D). _ b) Dispatch operator with 14" valve wrench to close 1CA-42B (CA Pmp B Disch To S/G 1D Isol) (DH-586, DD-EE, 43-44, Rm 591).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/A/5000/E-3 170f110 17 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. (Continued)
_ 2) Close 1CA-38A (CA Pmp 1 Disch 2) Perform the following: To S/G 1D Isol). _ a) Close 1CA-36 (CA Pump #1 Flow To S/G 1D). _ b) Dispatch operator with 14" valve wrench to close 1CA-38A (CA Pmp 1 Disch To 1CA-38A S/G 1D Isol) (DH-584, DD-EE, 43-44, Rm 591). c. CAUTION NC T -Cold indication in T-Cold the ruptured loop may cause an invalid Integrity Status Tree condition. _ Disregard NC T-Cold indication in the ruptured loop, until directed by this EP or until this EP is exited. IBOP BOP 8 1 . _8., D~Rtess EGGS .$t¢'am. pr~s$qr~l tt'tlMDCK*;;J~J.IshqgttoI"lS;i c.r )Mainti;fnJ::':~C~lpfEisslire'le~~.JhJth 1955 R$lGli!-I§Illg gbe.bf tb~f911?;?'Wiiig:: _ ;;'l~trsp(aY OR
- Pzr PORV.
CNS STEAM GENERA GENERATOR TOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 EP/1/Al5000/E-3 18 of 110 180f110 DC~ Rev 34 DC!: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- NC .pu(riRltcipcriteiia. base<fi9liHNC subcooling1:qoes hofaR~l:yaft~r:i.stC3rtin9 <;i controll~.d 1~Q.old9wn::
*:~i Affel';'lhEmbWlstear'nline'i
@"".,Jt ,. ....... ,~. "'." '. .,.xQ.."ressure
. .. . mai/'i1steam
........ .",,,. , , '. is6r"tion
.R,. . ., sig.hal
>~t~C3(ri:~ls'p'Cl,tiohl~i!l oC'?b!f.if;the high st~a(ri pressq~~;rate setp9intis exceeded ..
" isblocKed;N'!aln II mm~BYm"'F1_
_a*~".W!i. a. GO TO EP/1/Al5000/ECA-3.1 EP/1/A/5000/ECA-3.1 (SGTR gIlJar'iDlI_llIl&fIIIIJmI With Loss Of Reactor Coolant - Subcooled Recovery Desired).
- b. .G)~te:r(riin~):requiredaC§re eXit Jemper?tlJf;~ from th~&tC3blef;p:~ld~:
LOWEST Target temperature RUPTURED S/G PRESSURE CORE EXIT EX IT TICs could be lower (PSIG) (OF) depending on speed going through the EQUAL TO OR GREATER 532 (512 ACC) THAN 1200 procedure and when 1A S/G PORV is 11'100 gil' 119'9 :520 . ( 50?F:'ACC ) isolated. isolated . 1000 -- 1099 507 (489 ACC) 900 - 999 494 (476 ACC) 800 -- 899 479 (461 ACC) 700 -- 799 462 (445 ACC) 600 - 699 442 (426 ACC) 500 -- 599 420 (405 ACC) ACe) 400 -- 499 392 (379 ACC) ACe) 320 -- 399 364 (352 ACC)
CNS GENERATOR STEAM GENERA TOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/Al5000/E-3 19 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (Continued)
- c. ,gfis:greri:.rpt!;lL~d $t9(~) i§plated li§/
to!lo)1s:
- 1) ,~erifytl:te~IbII<;>~iJ~~l~~Iye§lQi1~I!} 1) Ensure the following valves on at nip!yt~G!i§&@J§)~f?UtU$Ernr~ least one intact S/G - CLOSED:
'ii MtSI\1
- MSIV
_ **.'t*;;~}a~~/
- MSIV bypass valve.
- 2) IF ruptured S/G(s) pressure is less than 1090 PSIG, THEN perform the following:
These valves should already _ a) Ensure S/G PORV on ruptured
.previously have been closed. S/G(s) - CLOSED OR ISOLATED.
b) IF S/G PORV on ruptured S/G(s) not closed or isolated, THEN: _ (1) Ensure operator dispatched to close ruptured S/G(s) PORV isolation valve. (2) Do not continue until affected S/G PORV(s):
- Isolated OR
- Determined to be unisolable.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/11A/SOOO/E-3 20 of 110 Rev 34 DC~ DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (Continued)
- 3) IF S/G 1B OR 1C ruptured, THEN 3) Perform the following:
verify one of the following CAPT steam supply valves - CLOSED: _ a) Ensure operator dispatched to isolate CAPT steam supply from
* "CAPT TRIP TN CTRL" the ruptured S/G.
OR b) Do not continue until affected CAPT steam supply:
- Manual isolation valve on the affected S/G.
- Isolated OR
- Determined to be unisolable.
EJd.~
- d. ~}llerifyJIi~~condeJts~r is::a¥ailC\pl~fff§: d. GO TO Step 9.g RNO.
follpWsy _ .-...m....._ .......
* "C-9 CON~ AVAILABI£i:2' FOR SIM 11"~Q
*DLJMP" status light (1pl-18) - LIT
;M§:1;V2Niihtact$(G(q,},~'ORi:2~:1
_ ** l1""'lIl'BimllllllllD
- e. :;V~r,!f~il§te:~:rjl d4rjlpS,:;~ I N;,!~R,E$SURE
'M,()pB *e. PI~'~steam dCimpsinptessur~ttnbd~,
a,s"fbllowS: _ \1) PI~;@:j;~,~STMPLJMPGTRL~'J'V'1!N
~latidnihmii!t1:~0§!ji
_ 2>:l:rvtanually:~!JjusfffSTrvt~JJM!7:'CTR.L*' MIA station outpt.ittEfl:Q1atch ~ii% 'STM DUMP DEM&hlQl;i:;(il~MP5~f1 t _ 3) 3)WHEN~lUp!,Jto.nth~"qI1rvt; DLJMBf: IGTRl"<M~~$tatIdn is egllmtothe iP~.STMI,}>,UMP PEM~f:'l[9t:
/.,j SMPB'2n~::~;~f;THEN"
\'' .',,' ,}4"h._._ _ P'la'l)8t1he
,,_,b'jy .
t~t~ClmauljAsirfpress,U:~~!fuqg~; f.WHEN.~P;" 2'j![~:;'LOTAV~it:'smtus Iigt1il; f. (1SI-18)18 lit,lfHEN PlaCe the steClJ11 dump int§rIQck' bypas~li$WitCl1e§iQ;il1;J?YP rNT~!<.;'
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 EP/1/A15000/E-3 21 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPON~E NOT OBTAINED
RESPONSE
- 9. (Continued)
_ g. IDEiff(:1i;Steam1lti
-g. N'", ,~~",' " ,w' '
(xf~CIehser ffomintact (;)","" ,',,', '" '"" EJI IRO
- g. Perform the following:
SlG(~~\~1:[jjlaximumyt~~~ 'kbJle' att~rnpf,itlXfl;~o avgjg, a '~§ir)!;$te,~m _ 1) Dump steam from all intact S/G(s) at Isol?tioh;, maximum rate with S/G PORV(-s). PORV(s). _ 2) IF any intact S/G PORV cannot be opened from the control room, THEN dispatch operator(s) to dump steam at maximum rate from intact IF a Main Steam Isolation occurs, the S/G(s) PORV. REFER TO PORVS on intact S/Gs will be used Enclosure 3 (Local Operation of per the RNO. S/G PORVs). PORV-s).
- 3) IF operator(s) were dispatched to S/G PORV(s), THEN:
_ a) Obtain sound powered phone from storage box on rear wall of control room. _ b) Connect sound powered phone to jack on 1MC-11. _ c) Monitor sound powered phone for communication from the Doghouse(s). Doghouse{s).
- 4) IF no intact S/G is available for NC System cooldown, THEN contact station management to determine which of the following to perform:
- Use faulted S/G OR EP/1/A/5000/ECA-3.1
- GO TO EP/1/A15000/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired).
_ 5) GO TO Step 9.h.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/Al5000/E-3 EP/1/A/5000/E-3 22 of 110 DC~ Rev 34 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 9. (Continued)
IBOP I "~i]i~~~~:~I~ft~~I~~~r~i==:'I"'~!mPK![~)l
- h. *\f;~f!fym9jn:;~m:l.~ntIt~QJ,9tiQb'tJ!PCK~~!;
~-=:--! h. stafq§iIJglJt$l(t§I;:;1!~,):jfILI3?~1
- h. Perform the following:
- 1) Depressurize NC System to less than 1955 PSIG using one of the following:
_ . Pzr spray OR
- Pzr PORV.
- 2) WHEN "P-11 PZR SII S/I BLOCK PERMISSIVE" status light (1SI-18) is lit, THEN:
_ a) Depress ECCS steam pressure "BLOCK" push buttons. _ b) Verify main steam isolation blocked status lights (1SI-13)- LIT. _ 3) Maintain NC pressure less than 1955 PSIG.
- i. WHENcor~~~ifT~P§lEi'ti:l.l@§J;)t\j§J:t:
r~g);JiredJgttiperatU~g~S1"Hr::N;st1bmt~j
~!~~,~~I!,Jlj~Csles~lnal1t~qitjre:g Jgttipgt§lqt~,
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/N5000/E-3 23 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1O.
- 10. C()ntro.lill~(:1~7~;~Jeyelsl~~follo~s:~
(mJIe!1~SllSlfl!lPm a.,,~~
- a. __
*ye~if~rI'iJZ~.~level;jn:anintc[¢t~/Gs:"~
- gRJ;~ATE~FHAWi;~,1.%i:{4~%;bCC).:
emE"'_~
- a. Perform the following:
IBOP I _ 1) Maintain total feed flow greater than 450 GPM to intact S/Gs until at least one intact S/G N/R level greater than 11 % (29% ACC).
- 2) IF total 'feed feed flow greater than 450 GPM cannot be established, THEN contact station management for guidance to establish feed flow from one of the following alternate sources:
** CF CF
** CMCM
_
- Alternate low pressure water source.
- b. '1,OY6ttJ§, ie~Cli!pw\1!q!;rnainJ:aih' all intaGt:: b. IF N/R level in any intact S/G continues 8lG N/Rile~~]s between 16% to increase in an uncontrolled manner, (290/0 ACC)tand50%.;* THEN:
_ 1) Stop NC system cooldown. _ 2) RETURN TO Step 1.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 24 of 110 Rev 34 DC!: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- a. Dispatch operator to restore power to affected Pzr PORV isolation valve(s):
- 1EMXD-F02C (PORV Isol Motor (1NC31B))
(1 NC31 B)) (AB-560, BB-50, Rm 372)
- 1EMXC-F03C (Pressurizer Power Operated Relief Isol. Valve 1NC33A)
(AB-577, BB-50, Rm 496)
- 1EMXD-F05A (PORV Isol Motor (1 NC35B)) (AB-560, BB-50, Rm 372).
- b. b. IF Pzr pressure is less than 2315 PSIG, THEN:
_ 1) Manually close Pzr PORV(s). _ 2) IF any Pzr PORV cannot be closed, THEN close its isolation valve. _ 3) IF Pzr PORV cannot be closed OR isolated, THEN GO TO EP/1/A/5000/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired).
- c. c. Open one Pzr PORV isolation valve unless it was closed to isolate an open Pzr PORV.
- d. lProp¢Plg:C#!;
_ _!:h!!!! d .IF<~T AN¥IlTIME'a:P~r1J70R\1:pp~,g~~< 9U:~';tqltHgfl1pr§~:§!,l rEt;;~bile. iI11t![I? lTHEm~:pgl~tmtb~IQJIQWing:' _In WFlI?~;g4'tj;~tl~l?!~!ti{td~~~J~~?~]~}to 1~$§Ill!i3;gf~;a~1~1g;~;I~;:;{f;1:f EN4gJ'jSQre' tb:§t"a]v£gl9s~§~;pf:is i'§dlat$.d:
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 25 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12..EnsJfte:~llltiJ~~g'SI;;"P: 12
- a. ECG§~'i a. Perform the following:
_ 1) IF either reactor trip breaker is closed, THEN dispatch operator to open Unit 1 reactor trip breakers. _ 2) Concurrently implement Enclosure 12 (ECCS Master Reset) while continuing in this procedure.
- b. b. Dispatch operator to open the affected sequencer(s) control power breaker:
- 1EDE-F01 F (Diesel Generator Load Sequencer Panel 1DGLSA) (AB-577, BB-46, Rm 496)
- 1EDF-F01 F (Diesel Generator Load Sequencer Panel 1DGLSB) (AB-560, BB-46, Rm 372).
c.
*En1iyt~th~}f()Jrowi~g.col)t~lifimerit i~,QI.~tiofiJ~jgQ}lr~,~;1i~ES,f;;,I:)
iiii Phase~ _ *.' Pt;ta,§EfB: 1;tl~* E~tflb,lislj.~ll9 C.QtJtail1m~!1f a~,!91J(.)Y{;§J Perform the following: i BOP I _.* El"lsUtg;\1Y'1+:t;~§:i(YIl~Qf"ir;I$,£:)li~,~~~QR,I;r5J:~* a. Align N2 to the Pzr PORVs by opening the following valves:
- V¢dfy:YI]Rr~~$,,1lr&>::~~!;Jt.,IE;"tIIj~N 85 RSle;'i
- 1NI-438A (Emer N2 From CLA A To 1NC-34A)
- 1 NI-439B (Emer N2 From CLA B To 1NC-32B).
- b. IF VI pressure is less than 85 PSIG, THEN dispatch operator to ensure proper VI compressor operation.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/N5000/E-3 EP/1/A/5000/E-3 26 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Y~rifY ctU~ri<:lllg~f,QPd'P~t~1illg'ND pYinps. ~~1IQUpW~I _all ~tl~asrg!i~NDpgOip -.Q~ .. a. GO TO Step 15.e.
- b. *~g.rJfYNP p'uXtlP( s~1~:W~ti6!l'!!&~ALU:SNED' b. GO TO Step 16.
TYl~F;WST.
- c. c. GO TO Step 16.
- d. StoP'~Q.pump\sJ'~ith.s~c1iQo'laligll~:GU toF\l¥h~I;~'
- e. IF. ATA:NYFTnVIe:.N~~iQt§s~*l!C§ decrea~~.s;J9'*le~s}th~llf28~~~G'BI~ .*;!g*§:@
uncQnttQn~grfiq:Dn~.~ii\[H EN~t¢stI3TIt~lR: P4m:R$;~ _ Do not continue in this procedure until ruptured SIG(s) S/G(s) identified. 17 . '..er**I~,,*.n~IC."'S
¥. "s......
.y ..l~ .... ,., .. Yc...*.te.'m**'I]!.c.66.iJ.*.Cl6w.*nl~"".....
M, d *. *.*.*** ........U%* . *
. . T.*sh6u*IA%he
..'I;!,"~.,.
$topp~~:,
a*%)l$fify CQt~i'El?<it T(~~1YL~§S TH~N a, :po not~()ntihg.~.irll!Jlis Pt'o,pgcl;lJr~uhtil tt}E:@LJlgJ;@*TEf\'1~.~RA]IJRE; . core e*itTIC~:tijte'i!~l?stl'lan'fe:ql!ired temp~rator§.j: Crew will hold here until they meet temperature requirements from the Table on page 18.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 EP/1/N5000/E-3 27 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 18. 'rl;erify'f:4.Rlure,Q:§t,G'(ll* Ri~s~:qr,giJsi~Q]J:et~tJ
;~~cifYii~{!RtgC~~Ji:§fi§II~IIIIIIR!I§§D~lt(§l),lDl!gcl I
I""R--~O-::--""" ~_ 1i;J?Qt):J~Jt~~~\t()n§~s: EJ operatQr at&lJirgRt,l\lt~p~lG,(iS) pre$~ure;' a. Perform the following:
~'[\&I?Le:;~R
":"";"I¥A~r'lttiHJti('INF}H INQ.REASING, I~i:",
_1) 1) Ensure ruptured S/G(s) isolated.
- E~L:.:: ~, ~.\~I ::::~l REFER TO Steps 3 through 6.
_ 2) IF ru .. ~.~~ :::, ,.,,~~~~J i: less is less than intact S/G{s) used for cooldown, THEN GO TO EP/1/N5000/ECA-3.1 (SGTR With EP/1/A/5000/ECA-3.1 Loss Of Reactor Coolant - Subcooled Recovery Desired).
- 3) IF AT ANY TIME DIP between ruptured S/G(s) and intact S/G(s) used for cooldown is less than 250 PSIG, THEN:
- Maintain total NC System cooldown less than 100°F in an hour
- Dump steam from intact S/Gs to maintain intact S/G pressures 250 PSIG below ruptured S/G(s) pressure.
_ 4) IF intact S/G(s) used for cooldown can not be maintained at least 250 PSIG below the pressure of the ruptured S/G(s), THEN GO TO EP/1/N5000/ECA-3.1 (SGTR With EP/1/A/5000/ECA-3.1 Loss Of Reactor Coolant - Subcooled Recovery Desired). _ 5) GO TO Step 19.
- b. IFATANYmIMEri.i'R:tLJ;t:~:gz~Sl@l$j) pl~§sure i§\Q~cr~~~~Jiig~,Oi.le'in~Jbfs.
p~<?~e.d ur&,iTH ENEp'eITorJiijjSte.p:','8. _ IF NC subcooling cannot be promptly restored to greater than 20°F, THEN GO TO EP/1/A15000/ECA-3.1 EP/1/A15000/ECA*3.1 (SGTR With Loss Of Reactor Coolant* Coolant - Subcooled Recovery Desired).
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/A/5000/E-3 28 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 20. itlep~gi~lJrize'f::ICSY~I~fJlL!§ll:!g RpR~
lIJ£p~~§~g~i~e;ltbl~i§¥§,lgmI;g§,'jJli:fli1Sj
$'praYr:l§/fQllo~~J!
§'P;G@¥;~§i;;;lQ.I.f.QW.§Jll
_ a) ;yerifM\lQotm~:IJ;i~1~$pr~~!1I()WiJ a. GO TO Step 21.
~8YAJg~8!!F~
- b. 'iZg£!f98~mlever,:".E.ESS.:n"IAN;~6.% b. Observe Caution prior to Step 23 and
,.,('7;3 0.)Z .' AC.r))
... 1 **:fO .....~. GO TO Step 23.
c. c*~~r>:te$suri?;~:NC qyl;;.tem\With ri~XimLlri'
~ll?Uable sp@y;
~UIF;,,:r ANYtirlME g.Qlj[191tli$;;st~P;i(m.§L91 This is a judgement call about tbe' f:pJlowing¢.9riditiq:~se~j~ts:* going to step 21 based on
_ .* ; :Spray vat~~sare\!Q.ote1f~ctiv§:'!ifi; whether the SRO thinks
*r~duci.ngl:NCpr~§$*ute sprays are "effective" and what he feels is "approaching 83%".
(PRJ _ ~1. 'HtiloJieti S/G{"')
. . P ...................... .§ N RleveUisi..
. . . . ****;*:achir(7B3% ,'(82% ACC}.
aPJ~[@..........9""d....... ..... ' . '.", _ THE3NGOT1~lil$feRr'4J.*,j e*Q,g1(liot cpntiriUe u.(;1J1Iat 1$f!§fori~ptt5'~) fpll~]viQg;;gpnditiori$':satisf:ied: _ ~{; .NO s~pcpoliog~baseClpn;c~reexit T/Ci)j;;{bt*jr;:E§~Il\'H8r.giP~F GR. _ ~ i.i~~r le~eII:- G8.l;lKTER ::rRAN7!5% f{?i~.7fil8~Gl' OR
.' Bg!11J;)f.rtQ~Yf,gJIPWig:tl*;;
_ It', NYPt~sslJre\l;!: I?gS~:]f;iAr;yj RLJij"lI1JRE.~:$[G{s)JeRES§,.l:JRpi ANDl
'~z'r' le' 'e*f,.tl.'.14(3'* [;:U;;1\\.-r;;crRF'1i.t,J A N* +tldfOZ
.*,. :,. c!i!, ' v '<~~{ ~,;; '.. li}:Jt4~;I~\~ ;j .~; ~{~~t:::\ " .jjJ.~~;
. r~.::
+20%b.~GJ,
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 29 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 20. (Continued) f.f.C'Qse'1@J~JbIl6wjpg v~lve(s):
- 1) IF spray valve(s) will not close, THEN:
_ a) Stop NC pumps 1Aand 1B. _ b) IF NC pressure continues to decrease, THEN stop third NC pump as required. _ 2) 1it\iJY;;.;37~\1~\7,ti'§gllRJYT6H,?;rAuXj 2) Ensure one of the following valves - S,'pr~Y)~ CLOSED: _ . 1NV-312A (Chrg Line Cant Isol) OR
- 1NV-314B (Chrg Line Cant Isol).
- 21. Depressurize NC System using Pzr PORV as follows:
- a. Verify at least one Pzr PORV-PORV - a. Establish NV aux spray as follows:
AVAilABLE. _ 1) Ensure at least one NI pump - ON. This step will be used if the crew _ 2) Ensure at least one NV pump - ON. determines that a PORV will be used to reduce NC pressure in 3) Ensure the following NV pump addition to a spray valve. miniflow valves - OPEN:
- 1NV-203A (NV Pumps A&B Recirc Isol)
- 1NV-202B (NV Pmps A&B Recirc Isol).
- 4) Close the following valves:
_ . 1NI-9A (NV Pmp C/l Inj Isol) _. 1 NI-1 OB (NV Pmp C/l Inj Isol). 1NI-10B (RNO continued on next page)
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1 I A/5000/E-3 EP/1/A/5000/E-3 30 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 21. (Continued)
_ 5) Manually throttle 1NV-294 (NV Pmps A&B Disch Flow Ctrl) for 32 GPM charging line flow. _ 6) Manually close 1NV-309 (Seal Water Injection Flow).
- 7) Open the following valves:
NV-312A (Chrg Line Cont lsol)
- 1 NV-312A(Chrg
- 1NV-314B (Chrg Line Cont Isol).
_ 8) Place 1NV-309 in auto.
- 9) Ensure the following valves -
CLOSED: _ .* 1NC-27 (pzr Spray Ctrl Frm Loop A)
- 1NC-29 (pzr Spray Ctrl Frm Loop B)
- 1NV-39A (NV Supply To Loop D Isol)
- 1NV-32B (NV Supply To Loop A Isol).
_ 10) Maintain charging flow less than 180 GPM. _ 11) Throttle 1NV-37A (NV Supply To Pzr Aux Spray) and charging flow as required. _ 12) RETURN TO Step 20.e.
- b. Verify Pzr level - LESS THAN 76% b. Observe Caution prior to Step 23 and (73% ACC). GO TO Step 23.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/A/5000/E-3 31 of 110 310f110 Rev 34 DC:: DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 21. (Continued)
- c. Open one Pzr PORV. c. Perform the following:
- 1) Align N2 to the Pzr PORVs by opening the following valves:
- 1NI-438A (Emer N2 From CLA A To 1NC-34A)
- 1NI-439B (Emer N2 From CLA B To 1NC-32B).
_ 2) Open one Pzr PORV.
- d. Do not continue until at least one of the following conditions satisfied:
_ . NC subcooling based on core exit TICs - LESS THAN OaF OR
- Pzr level - GREATER THAN 76%
(73% ACC) OR
- Both of the following:
_ . NC pressure - LESS THAN RUPTURED S/G(s) PRESSURE AND
- Pzr level-level - GREATER THAN 11 11% %
(20% ACC).
- e. Close Pzr PORV. e. Close Pzr PORV isolation valve.
- f. Close Pzr spray valve(s). f. IF spray valve(s) valve{s) will not close, THEN:
_ 1) Stop NC pumps 1Aand 1B. _ 2) IF NC pressure continues to decrease, THEN stop third NC pump as required.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/N5000/E-3 EP/1/A/SOOO/E-3 32 of 110 Rev 34 DC~ DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 22. Verify NC pressure - INCREASING. Perform the following:
- a. Close Pzr PORV isolation valve.
- b. IF pressure continues to decrease, THEN perform the following:
- 1) Monitor the following conditions for indication of leakage from the Pzr PORV:
- PRT pressure
- Pzr Relief Valve Temp.
_ EP/1/N5000/ECA-3.1
- 2) GO TO EP/1/A/SOOO/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired).
ICAI)lm[mNl§ZI;iJpg~~mg§ll~lI!!!iJj~l§,~jllil!!§lIl;~,mln;J~1i;Q,n"j~!7;il~ti~\~:~~]I~'i;iI'l?li§~1;lQijjlli'J;~~M~nlt igzfiw"'i,aglg~ll~gRlg;I!~~jli§lm:l§'!l EP/1/N5000/ECA-3.1 (SGTR
- a. GO TO EP/1/A/SOOO/ECA-3.1 With Loss Of Reactor Coolant -
Subcooled Recovery Desired).
- b. ~Y:¢Fif¥~~~qdtid~I)i~l1ea~ $J.bk as JdUows: EP/1/N5000/ECA-3.1 (SGTR
- b. GO TO EP/1/A/SOOO/ECA-3.1 With Loss Of Reactor CoolantCoolant--
_ . N[f\yJg""el;jr:rf?tJlei!:~Jipt].~::riQt~etSlfJ,N Subcooled Recovery Desired).
*GgEATE:g'rr:hf/~.J'~;J'lWJI<<'~~Cl9**4.~~1)
_ ~il. m~tC3J{ggd'f1q~lavailaP:J~";JoS/GJ~r:) Bf\E:4rr:~RlIjAN.4§q*iG.PM~i
- c. EP/1/N5000/ECA-3.1 (SGTR
- c. GO TO EP/1/A/SOOO/ECA-3.1 With Loss Of Reactor Coolant -
Subcooled Recovery Desired).
- d. ~P:?"!¢Y~l~:g;RE:ATER. rr:WAN .11;9& d. RETURN TO Step 7.
t(?o;%r£l?~J ~.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/A/5000/E-3 33 of 110 DC~ Rev 34 DeE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24.~top1§ZI pumps~~s f6I1Q~)Ns;:
- a. StoR¥M!J~uJIjp~,~~ a. Perform the following:
- 1) IF NI Pump 1A failed to trip, THEN perform the following:
a) Ensure the following valves-valves - OPEN:
- 1NI-115A (NI Pump 1A 1501)
Miniflow Isol)
- 1NI-147B (NI Pump Miniflow 1501).
Hdr To FWST Isol). b) WHEN miniflow path aligned, THEN ensure the following valves - CLOSED:
- 11NI-121A(NI NI-121A (NI Pump 1A To H-Legs B&C)
- 11NI-118A(NI NI-118A (NI Pump 1AC-Leg 1A C-Leg Inj Isol).
_ c) Dispatch operator to locally trip 1ETA#11 1 ETA#11 (1A NI Pump Motor) (AB-577, AA-49, Rm 496). (RNO continued on next page)
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/11A15000/E-3 EP/1/A/5000/E-3 34 of 110 340f110 DC~ Rev 34 DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 24. (Continued)
- 2) IF NI Pump 1B failed to trip, THEN perform the following:
a) Ensure the following valves - OPEN:
- 1NI-144A 1NI-144A(NI(NI Pump 1B Miniflow Isol) 1501)
- 1NI-147B (NI Pump Miniflow Hdr To FWST Isol).
b) WHEN miniflow path aligned, THEN ensure the following valves - CLOSED:
- 1NI-150B (NI Pump 1B C-Leg Inj Isol) 1501)
- 1 NI-152B (NI Pump 1B To H-Legs A&D).
_ c) Dispatch operator to locally trip 1ETB#11 (1 B NI Pump Motor) (AB-560, AA-49, Rm 372). b.
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A15000/E-3 EP/1/A/5000/E-3 35 of 110 DC~ Rev 34 DCE ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 25. I~.g!~te ~~SnfflQ.Ylp,~lfl:~s",,f&n9ws~
IBOP I a. ~&Jify]hEiIpliowitlgValYf1s -OR-EN: a. IF NV pump suctions are aligned for Cold Leg Recirc, THEN perform the
*,1~fiJV"'252A~\(NVI?~mps£§uctf;tbm following:
R;W$T) _ 1} GO TO Enclosure 10 (Establish 1) Charging With NV Miniflow Isolated). _ 2}
- 2) GO TO Step 27.
- b. Perform the following:
.1f'i~72,(f~'Al(NY'e4mp~~~,I?R§~it~ 1} Dispatch operator to open affected 1) 15<51]\ valve(s}:
valve(s):
- N*w)'2'
- 1. ..*,¥ '02'BSlMYT.'P*'T'*W"'Pl\o"swR" *'*c':* "'.
....:;",Al:!/I1Y.*l,iAIJlP§;;~? :," .~<J~P
- 1NV-203A (NV Pumps A&B Is~n~ Recirc Isol) (AB-554, HH-JJ, 54-55, Rm 231) (Ladder needed)
- 1 NV-202B (NV Pmps A&B Recirc Isol) (AB-554, HH-JJ, 54-55, Rm 231) (Ladder needed).
_ 2}
- 2) GO TO Enclosure 10 (Establish Charging With NV Miniflow Isolated).
_ 3} WHEN 1 NV-203A AND 1NV-202B 3) are opened, THEN charging flow may be reduced below 60 GPM. _ 4} GO TO Step 27. 4)
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/5000/E-3 36 of 110 Rev 34 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 25. (Continued)
IBOP I c. c. Perform the following:
- 1) Dispatch operator to close the affected valve(s). REFER TO the following enclosure(s) for the affected valve(s):
- Enclosure 13 (Locally Close 1Nl-9A)
SCENARIO MAY BE TERMINATED
- Enclosure 15 (Locally HERER Close 1NI-10B).
NI-1 OB).
- 2) IF NC pump seal cooling is established from KC flow to thermal barrier, THEN perform the following:
_ a) Ensure all NC pumps - OFF. _ b) Stop NV Pumps. _ 1NI-9A AND 1NI-10B are c) WHEN 1NI-9AAND closed, THEN restore NV pump to service. REFER TO Enclosure 9 (NV Pump Restart). d) Ensure the following valves - OPEN:
- 1NI-115A (NI Pump 1A Miniflow Isol)
- 11NI-144A(NI NI-144A (NI Pump 1 1B B
Miniflow Isol)
- 1NI-147B (NI Pump Miniflow Hdr To FWST Isol).
(RNO continued on next page)
CNS STEAM GENERATOR TUBE RUPTURE PAGE NO. EP/1/A/SOOO/E-3 62 of 110 Enclosure 1 - Page 1 of 2 Rev 34 DC~ Foldout Page
- 1. NC Pump Trip Criteria:
- IF the following conditions are satisfied, THEN trip all NC pumps while maintaining seal injection flow:
- At least one NV or NI pump - ON
- NC subcooling based on core exit TICs - LESS THAN OR EQUAL TO OaF.
- 2. Position Criteria for 1NV-202B and 1NV-203A (NV Pumps A&B Recirc Isol): 1501):
- IF NC pressure is less than 1S00 PSIG AND NV S/I flowpath is aligned, THEN close 1NV-202B and 1NV-203A.
- IF NC pressure is greater than 2000 PSIG, THEN open 1NV-202B and 1NV-203A.
- 3. S/I 5/1 Reinitiation Criteria:
- IF NC subcooling based on core exit TICs is less than OaF OR Pzr level cannot be maintained greater than 11 % (20% ACC), THEN:
- a. Manually start S/I pumps and align valves as necessary to restore subcooling and Pzr level.
- b. IF S/I reinitiation occurs after Section C. (Operator Actions), Step 24, THEN GO TO EP/1/A/SOOO/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired).
- 4. Secondary Integrity Criteria:
- IF pressure in any unisolated S/G is decreasing in an uncontrolled manner OR any unisolated S/G has completely depressurized, THEN GO TO EP/1/A/SOOO/E-2 (Faulted Steam Generator Isolation) unless needed for NC System cooldown.
S. Cold Leg Recirc Switchover Criterion:
- IF FWST level decreases to 37% (1AD-9, 0/8 "FWST 2/4 LO LEVEL" lit), THEN GO TO EP/1/A/SOOO/ES-1.3 (Transfer To Cold Leg Recirculation).
CNS GENERATOR STEAM GENERA TOR TUBE RUPTURE PAGE NO. EP/11A15000/E-3 EP/1/A/5000/E-3 63 of 110 Enclosure 1 - Page 2 of 2 Rev 34 DC~ DC:: Foldout Page
- 6. CA Suction Source Switchover Criteria:
- IF either of the following annunciators are lit, THEN REFER TO API1/A15500/006 AP/1/A/5500/006 (Loss of S/G Feedwater):
_ .* 1AD-5, H/4 "CACST LO LEVEL" OR _ .* 1AD-8, B/1 "UST LO LEVEL".
- 7. Multiple Tube Rupture Criteria:
- IF level in any intact S/G increases in an uncontrolled manner OR any intact S/G indicates abnormal radiation, THEN:
- a. Stop any operator controlled cooldown and depressurization in progress.
- b. RETURN TO EP/11A15000/E-3 EP/1/A/5000/E-3 (Steam Generator Tube Rupture), Step 1.
Appendix D 0 Scenario Outline Form ES-D-1 2009 NRC EXAMINATION Facility: Catawba Nuclear Station Scenario No.: Op-Test No.: 20090-1 2009 D-1 SNAP 143 Examiners: Operators: Initial Conditions:
- 75% power
- EFPD =450 days
- Boron Concentration is 208 ppm Turnover:
- 1A D/G was placed in Maintenance Mode and red tagged 2 hours ago for PMs and is expected back in 6 hours.
- 1CFP5600 (10 (1 D S/G Narrow Range Level Ch #2) failed 2 hours ago. IAE repairs are in progress and estimated to take 4 hours. All TSAIL entries have been made.
- Increase power to 100% at 5% an hour per OP/1/Al61 00/003 (Controlling Procedure for Unit Operation), Enclosure 4.1, Power Increase.
Event Malf. No. Event Event No. Type* Description 1 BOP N Dilute for power increase (DCS) 2 RO R Increase power to 100% 3 BOP I P/R N44A failure SRO TS 4 RO C Loss of 1A CF pump/ no auto rod motion 5 BOP C PORV open does not fully reclose, can be blocked SRO TS 6 RO C 1CF-55 (0(D CF Reg Valve) auto control fails/manual control available SRO TS 7 ALL M Large Break LOCAl Loss of emergency coolant recirculation Additional Failures Auto S/I train A & B fails to auto actuate 1NI-184B 1N 1-184B fails closed 1A essential train loss of power
*(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (C)om ponent, (M)ajor
SIMULATOR SETUP Reset to a 75% power EOL snap Roll Charts boration/dilution plan Provide a borationldilution Clear EHC alarm and any OACI 1.47 bypass alarms Sign off OP/1/A/61 001003 enclosure 4.1 thru step 2.52 (students start at 2.53) MALFUNCTIONS. REMOTES. and OVERRIDES Malfunction # Description Value Event Ramp Delay Trigger LOA-CNT002 H2 ANALYZERS BOTH 24 600 MAL-ENB011G MAL -ENB011 G P/R DETECTOR 44A FAILURE 100 3 MAL-EQB003A LOSS OF DIG 1A 1A SEQUENCER 21 300 CTRL CTRLPWRPWR MAL-IRX009 RODS FAIL TO MOVE AUTO 4 MAL-ISE002A AUTO SI TRN A FAILS TO ACTUATE MAL-ISE002B MAL -ISE002B AUTO SI TRN B FAILS TO ACTUATE MAL-NC013C NC COLD LEG C LEAK 27.5 8 MAL-OV0691 B NCDJ5167 NC-34A DEMAND ALARM 5 OPEN fail to NORMAUALARM MAL-SLlM22_04 1CFSS5060: CF55 FCV D 0 Raise Button 6 1 Output Pushbutton fail to position Depressed Del in 6 OVR-DG015B DIG 1B MAINT MODE PB (11/378) ON INITIATE PB OVR-DG047 *DG-PNL** MAINTENANCE MODE
*DG-PNL ON PB BLACK PB OVR-DG048A *DG-PNL** MODE SEL 2 POS
*DG-PNL ON LOCKOUT RELAY SW TRIP POS OVR-EP029D ETA NORM FDR FOR FRM ATC TRIP ON 9 10 PB OVR-FWP012C CFPT 1A TRIP & & RESET TRIP PB ON 4 OVR-FWP015C CFPT 1B TRIP & & RESET TRIP PB ON 7 VLV-NC006C NC33A PZR PORV ISOL VLV 23 300 FAILPWR VLV-NC007F NC34A PZR PORV FAIL TO 0.25 12 1 POSITION VLV-NC007F NC34A PZR PORV FAIL TO 1 5 1 POSITION VLV-NI037F NI184B CNMT SUMP LINE 1B 0 ISOL (STEM) FAIL TO POSITION VLV-NI037F NI184B CNMT SUMP LINE 1B 1 22 300 300 ISOL (STEM) FAIL TO POSITION XMT-SG013 LCF_5580 S/G 1 10 D N/R LVL CH4 100 6 TO DCS/MCB/OAC (CFAA5580)
XMT-SG016 LCF_5600 S/G 1 10 D N/R LVL CH2 0 TO DCS/MCB/OAC (CFAA5600)
EVENT TRIGGERS (other than manual) Event Description Trigger TriQQer 8 Reactor trip either train [ jpplp4(1) I jpplp4(2) ] 9 x11 i357F (TRUE when 1B NO pump is secured) 12 X1 Oi1 03c (TRUE when 1NC-34A is taken to the close position) CRITICAL TASKS (See attached documentation) E-O 0 - Manually actuate at least one train of SIS-actuated safeguards before any of the following:
- Transition to any E-1 series, E-2 series, or E-3 series procedure or transition to any FRG
- Completion of Step 5.a of ES-0.1 ES-1.3 A - Transfer to cold leg recirculation and establish ECCS recirculation flow that at least meets the assumptions of plant specific LOCA analyses.*
- Per Technical Specification 3.5.2 basis background section:
"Per The EGGS consists of three separate subsystems: centrifugal charging (high head), safety injection (SI) (intermediate head), and residual heat removal (RHR) (low head). Each subsystem consists of two redundant, 100% capacity trains. The EGGS accumulators and the RWST are also part of the EGGS, but are not considered part of an EGGS flow path as described by this LGO. The EGGS flow paths consist of piping, valves, heat exchangers, and pumps such that water from the RWST can be injected into the RGS following the accidents described in this LGO. The major components of each subsystem are the centrifugal charging pumps, the RHR pumps, heat exchangers, and the SI pumps. Each of the three subsystems consists of two 100% capacity trains that are interconnected and redundant such that either train is capable of supplying 100% of the flow required to mitigate the accident consequences. This interconnecting and redundant subsystem design provides the operators with the ability to utilize components from opposite oppOSite trains to achieve the required 100% flow to the core. Critical steps are denoted on the Instructor guide. QUALITATIVE ATTRIBUTES Required Re_quired Actual Total malfunctions 5-8 8 Malfunctions after EOP entry 1-2 3 Abnormal events 2-4 4 Major transients 1-2 1 entered/requirinQ substantive actions EOPs entered/requiring 1-2 2 continQencies requiring EOP contingencies reQuirinQ substantive actions 0-2 1 Critical tasks 2-3 2
REFERENCES OP/1/A/6150/009 (Boron Concentration Control) revision 068DCS OP/1/A/61501009 OP/1/A/61 00/003 001003 (Controlling Procedure for Unit Operation), Enclosure 4.1 revision 106DCS OP/1/B/63001001 (Turbine Generator) revision 091 OP/1/B/6300/001 AP/1/A/55001016 (Malfunction of Nuclear Instrumentation System) revision 023 AP/1/A/5500/016 AP/1/A/55001011 (Pressurizer Pressure Anomalies) revision 022DCS AP/1/A/5500/011 AP/1/A/55001003 (Load Rejection) revision 036 AP/1/A/5500/003 EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) revision 036DCS EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) revision 023 EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) revision 021 EP/1/A/5000/ECA-1.1 (Loss of Emergency Coolant Recirculation) revision 31 DCS OTHER NOTES AND INSTRUCTIONS NOTE: The following steps are GUIDELINES. The NRC lead examiner will direct timing of events unless otherwise noted. NOTE: Any groups or Individuals (IAE, RxGrp, RP, SOC, SWM) that are called to IIR a problem or for simple notification of a problem, repeat back the Information they provide unless otherwise noted. NOTE: Any operators dispatched should repeat back Information provided. Call back Items are listed below when necessary for the scenario. Event 1 - Dilute for power Increase This event will be entered once the crew has taken turnover and evaluated plant conditions. When the first dilution batch has been completed, the next event can be started. Event 2 -Increase power to 100% This event will be entered once the crew has taken turnover and evaluated plant conditions. When turbine power has increased by 3-5 MW, the next event can be started. Event 3 - P/R N44A failure. SRO Technical Specification Initiating Cues:
- 1AD-2, A/3, A/8, B/8, C/8 Et8 El8 and others OTDTIOPDT channel in trip per Step 5, reply:
When SPOC is notified to place OTDT/OPDT "Place Channel 4 of OPDT and OTDT In trip condition per Model W/O 00874531." When AP/1/A/5500/016 AP/1/A/55001016 is completed, and the SRO has completed consulting Technical Specifications, the next event can be inserted. TS - 3.3.1 Items 2a, 2b, 3, 6, 7, 16b, 16c, 16d, 16e Conditions D, E, R, S
Event 4 - Loss of 1A CF pumpl no auto rod motion Initiating Cues:
- Al1, A/4 1AD-5, A/1, Al4
- 1AD-1,F/4 AP/1/A/55001003 is completed, the next event can be inserted.
When AP/11A155001003 TS - 3.1.6 Condition A (IF Control Rods are at Lo-Lo insertion limit) Event 5 - PORV open does not fully reclose. can be blocked. SRO Technical Specification Initiating Cue:
- 1AD-6 C/12, El10, F-8 AP/1/A/55001011 is complete and the SRO has completed consulting Technical Specifications, When AP/11A155001011 the next event can be inserted.
If an operator is dispatched to remove power from 1NC-33A, Insert EVENT 23. When EVENT 23 Is activated, state "Power has been removed from 1NC-33A". TS - 3.4.11 Condition B TS - 3.4.1 Condition A (based on NC pressure at the time) Event 6 - 1CF-55 (D CF Reg Valve) auto control falls/manual control available Initiating Cues:
- 1AD-4 D/4, 1AD-2 F/9 When 1D S/G level has been stabilized in manual and the SRO has completed consulting Technical Specifications, the next event can be inserted. This will begin the major event.
TS - 3.3.1 Item 13 Condition E TS - 3.3.2 Item 5.a.(2) Condition J, Item S.b.(2) 5.b.(2) Condition D, Item 6.b Condition D TS - 3.0.3 (due to two channels OOS) TS - 3.3.3 Item 10 Condition B Event 7 - Large Break LOCAl Loss of emergency coolant recirculation When the second feed pump is tripped, the T/G will trip on AMSAC, but because they reactor is <69% power, it will not trip automatically. The crew will manually trip the reactor based on the immediate actions of AP/06 (trip when >5% power and loss of all feedwater) This begins the major event. EP/1/A150001E5-1.3 without ever NOTE: Depending on student reading speed, they could enter EP/1/A15000/ES-1.3 EP/1/A15000/E-1. going to EPI1IA15000/E-1. Additional failures
- Auto S/I train A && B fails to auto actuate
- 1NI-184B fails closed
- 1A essential train loss of power
In E-O, RNO Step 10.a.8).a) and b) when an operator is dispatched to secure ice condenser air handling units and place H2 analyzers in service, Insert EVENT 24. Call back when the analyzers are In in service and state: "Both Unit 1 H2 Analyzers are In in service." NOTE: At kickout from E-O, SUBCRITICALITY is RED due to N44 failure. NC INTEGRITY is RED or ORANGE due to cooldown of loops during a LB LOCA. NC INTEGRITY is VALID and the crew should transition briefly to EP/1/NSOOO/FR-P.1 EP/1/A/5000/FR-P.1 but kick back out to E-1 due to flow to the NC cold legs. HEAT SINK could also be in RED due to operator action but should not be entered on that basis. In E-1 Step 4, if asked to sample S/Gs for activity state "I will sample Unit 1 S/Gs SlGs for activity and report the results back In in about an hour." In E-1 Step 4, if asked to frisk cation columns for activity state "I will frisk Unit 1 cation columns for activity and report back the results In a few minutes. Call back In 5 minutes and state "Unit 1 cation columns Indicateindicate no abnormal activity." In ES-1.3 Step 4.b RNO, when dispatched to remove power from 1EDE-F01 F, Insert EVENT 21. Call back when the breaker Is open and state "1 EDE-F01 F Is open." In ES-1.3 Step S.a.2).c).(2), 5.a.2).c).(2), RNO when dispatched to manually open 1NI-184B, 1NI-184B, Insert EVENT 22. Call back when the valve reaches full open and state "1 NI-184B Is open." Scenario End Point sn AFTER VERIFICATION OF PROPER S/I FLOW PER STEP 5.1 of EP/1/5000lES-1.3. EP/1/5000/ES-1.3.
CREW TURNOVER INFORMATION Initial Conditions:
- 75% power
* =
EFPD = 450 days
- Boron Concentration is 208 ppm Turnover:
- 1A DIG was placed in Maintenance Mode and red tagged 2 hours ago for PMs and is expected back in 6 hours.
- 1CFP5600 (1 D S/G Narrow Range Level Ch #2) failed 2 hours ago. IAE repairs are in progress and estimated to take 4 hours. All TSAIL entries have been made.
- Increase power to 100% at 5% an hour per OP/1/A/61 00/003 001003 (ContrOlling Procedure for Unit Operation), Enclosure 4.1, Power Increase.
OP/liAl6150/009 Page 2 of4 Boron Concentration Control
- 1. Purpose To describe the operation of the Boron Concentration Control System.
- 2. Limits and Precautions 2.1 This procedure is Reactivity Management related because it controls activities that can affect core reactivity by changing boron concentration. (R.M.)
2.2 The following Limits and Precautions are Reactivity Management related: (R.M.) 2.2.1 When changing the boron concentration of the NC System, closely monitor the following for expected indication:
- Rodmotion
- T-AVG
- Nuclear instrumentation 2.2.2 When performing dilutions at or near 100% power, batch additions to the VCT (instead of continuous dilution at low flow rates) are the preferr-ed preferred method. {PIP C99-0587}
2.2.3 If the NC System is filled and vented and the boron concentration is being reduced in the NC System, at least one NC pump shall be in operation, recirculating the NC System. {PIP C99-2510} 2.2.4 If the boron concentration is being increased in the NC System, at least one NC pump or one ND pump shall be in operation, recirculating the NC System. 2.2.5 Following an increase or decrease of the NC System boron concentration of 2: 50 ppm, pressurizer spray shall be operated to equalize the boron concentration throughout the system. 2.2.6 When the reactor is subcritical sub critical and dilution is in progress, if the Nuclear Instrumentation increases by a factor of two, secure the operation immediately and evaluate the cause. 2.2.7 If the unit has operated continuously for several months, significant Boron 10 depletion may have occurred. The effective boron concentration of the NC System may be lower than indicated by Chemistry samples. NC temperature shall be carefully monitored following VCT makeup. 2.3 During continuous dilution operations, sample the NC System H2 concentration every eight hours.
OP/l!Al6150/009 Page 3 of4 2.4 When manually operating any motor operated valve, minimize the torque applied to the handwheel. 2.5 After manual operation, maintenance or packing adjustment of any motor operated safety related valve, it shall be cycled electrically to ensure reliable automatic operation. 2.6 With the "NC MAKEUP MODE SELECT" switch in the "DILUTE" position, the makeup flow rate is limited by letdown flow, the VCTspray nozzle, and VCT pressure. The maximum expected makeup flow rate is approximately 95 gpm. 2.7 With the "NC MAKEUP MODE SELECT" switch in the "ALTERNATE DILUTE" position, the maximum expected makeup flow rate is approximately 130 gpm. 2.8 With BAT boron concentration greater than or equal to 7200 ppm, it is recommended that only manual makeup be performed when the NC System boron concentration is
~1300 ppm. Automatic or manual makeup can be used when NC System boron
;::..1300 concentration is < 1300 ppm. {PIP 03-7305}
2.9 With BAT boron concentration less than 7200 ppm, it is recommended that only manual makeup be performed when the NC System boron concentration is 2: 2:. 1250 ppm. Automatic or manual makeup can be used when NC -System ~ystem boron concentration is
< 1250 ppm. {PIP 03-730S}
03-7305}
- 3. Procedure Refer to Section 4 (Enclosures).
- 4. Enclosures 4.1 Automatic Makeup 4.2 Boration 4.3~ Dill.ltid!jj 4.4 Alternate Dilution 4.5 Manual Operation Of The Makeup Controls 4.6 Operation Of The Boric Acid Transfer Pumps In Miniflow 4.7 Placing Boric Acid Tank #2 In Service For Unit #1 4.8 Valve Checklist 4.9 Rapid Boration
All steps performed by BOP Enclosure 4.3 OP!lIA/61501009 OP/I/A/6150/009 Dilution Page 1 of3 o j~~2i; Hll;;i.!i'Mt>de..Hi.or~,.~ti$:ur~;JP~~acti,yitY~:fuat,j,'ggeIti~its:coiitt:Ql~:;;esllibli$.~9-~r..$P~ij OJ ~Q.~
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- 2. Procedure 1--
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Enclosure 4.3 OP/l!A/6150/009 OP/1!A/6150/009 Dilution Page 2 of3 2.9 IF ATAN:¥.lUME it is desired to divert letdown to the RHT manually operate 1NV-172A (3-Way Divert To VCT-RHT) as follows: NOT DESIRED o 2.9.1 INV-I72A (3-Way Divert To VCT-RHT) to the Place the control switch for 1NV-172A "RHT" position. oD 2.9.2 Ensure VCT level is monitored continuously while diverting to the RHT. RBT. o D 2.9.3 WHEN desired VCT level is reached return INV -InA (3-Way Divert To VCT-INV-l72A RHT) to "AUTO". NOTE: If necessary, dilution can be manually secured at any time by placing the "NC MAKEUP Ifnecessary, CONTROL" switch to the "STOP" position. o 2.10 2.11 2.12 2.13 .WHEN\the des~~~dvolwne ofreactbr m~~~up?w4tteti:~,il~~a:cl1~poiijit~!j1gIillm:~Kellpibatch lPoM~~rltnsl¢f!.the* fbllpwi;t'l,g'valv~s.clog~~I(~t~'b 2.14 2.14.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup). OR 2.14 .2IFm~kellP£g,t.th~i1te,yiplt~:!.;dOri~~'t)l!:att[~J~'f!£¢~Pl1l?l~$ANDltl1.1fs~l~lP~a$* 2.14.2 ipteY!~lJ:§J~i~Jigti~1I'p~~;Eli§I5?1qr~'~Htl:~I~u::t:gxnatt~IYf~¢jl:p),.p~gormlqf':;rollo~illg: D ,g¥~!ilJ?3 tfJf;1fjl~J!*1'\l~f.$i'1~V~~(?@:J&;r~g)l.$l%;s~it§;n*.t,~1iljel'~r~i"*
\P:9~!FiQi, . (:g.;M!d\
Enclosure 4.3 OP/l!Al6150/009 Dilution Page 3 of3 2.15 Do NOT file this enclosure in the Control Copy folder of this procedure.
OP/l!Al61 00/003 OP/I/A/6100/003 Page 2 of4 Controlling Procedure For Unit Operation
- 1. Purpose of the unit between approximately 1'5%
To describe the operation ofthe 15% and 100% full power.
- 2. Limits and Precautions 2.1 This procedure is Reactivity Management related because it controls activities that can effect core reactivity by the following: (R.M.)
- Control rod movement
- Turbine load changes
- Feedwater manipulations
- Reactor power changes 2.2 The following Limits and Precautions are Reactivity Management related: (R.M.)
2.2.1 Before returning reactor control to automatic, T-AVG shall be within +/- 1°F of T-REF. 2.2.2 Do NOT exceed rod insertion limits or temporary rod withdrawal limits. 2.2.3 Bank D ~ 200 Automatic control rod withdrawal is blocked when Control Bank: steps withdrawn. 2.2.4 The difference in boron concentration between the PZR and NC System is desired to be maintained within +/- 50 ppm. 2.2.5 Axial Flux Difference (AFD) shall be maintained within the allowable limits as defined in the ROD manual at all power levels above 50% reactor power. (Tech Spec 3.2.3) 2.2.6 During a power change, other indications of reactor power shall be observed along with power range and secondary thermal power indications to aid in determining the reactor power level. Using indications like turbine impulse pressure, CF flow rate, NC loop /)"DoTs, Ts, and others may help in detecting the miscalibration of a nuclear instrument. 2.3 In the event of an inadvertent power reduction, it is recommended that the power level increased until an investigation has been conducted and corrective NOT be increased conective action taken.
OP/l!A/6100/003 OP!l/A/6100/003 Page 3 of4 2.4 lfreactor If reactor control is in manual, maintain T-AVG within +/- 2°F ofT-REF to prevent receiving "T-REF/T-AUCT HIILO" alarm. 2.5 Whenever there is a thermal power change greater than or equal to 15% rated thermal power within a one hour period: (OAC point CIL4790 C1L4790 in alarm) Notify Chemistry to take an isotopic analysis for iodine within 2 to 6 hours following
- NotifY the last power change that is greater than or equal to 15% rated thermal power within a one hour period. (T.S. SR 3.4.16.2)
- When thenna1 thermal power has stabilized, notifY notify Radiation Protection to sample and analyze gaseous effluents. (S.L.C.
(S.L.e. 16.11-6) 2.6 S/G blowdown blowdoVlll flowrate shall NOT exceed a maximum of200 of 200 GPM per S/G. 2.7 After a thermal power change when plant conditions stabilize, 1EMF-39 setpoints shall be adjusted so the Trip 2 setpoint is set at three times the containment activity and Trip 1 setpoint is set at 70% of Trip 2 setpoint. 2.8 lfthe If the RC System condenser inlet temperature drops to less than or equal to 60°F when the Rx is shutdown or less than or equal to 55°F when the Rx is critical, the system shall be configured as follows:
- One RC pump running (throttled).
- One tower inlet isolated.
- All three riser bypasses open.
2.9 OAC point C1K0628 CIK0628 (CF Flow Venturi Correction Factor) shall be reset to 1.0 when either of the following conditions are met:
- A step load change such as a load rejection greater than 10% rated thermal power,
- A ramp load change of greater than 15% rated thermal power in a one hour period.
2.10 When the unit is engaged in a power maneuver resulting in a mismatch between OAC point C1P1385 (Reactor Thermal Power, Best) and any excore power channel in excess of2% refer to Tech Spec Basis for SR 3.3.1.2. 2.11 The insertion of Control Bank D will affect mismatch between OAC point C1P1385 (Reactor Thermal Power, Best) and the excore power range channels. This is due to shielding of the power range detectors by Control Bank D. Therefore, refer to Tech Spec Basis for SR 3.3.1.2 when mismatch between Reactor Thermal Power (Best Estimate) and the excore power range channels shall be observed to be exceeding 2%. 2.12 The Reactor Engineering Group normally provides information for planned power maneuvers. The OAC xenon predict program can be used to help anticipate dilution and boration requirements. {PIP C99-0587}
OP/l!A/61 001003 OP/I/A/61 00/003 Page 4 of4 2.13 The Steamline N-16 Radiation Monitors (EMF-71, 72, 73, 74) become inaccurate at power levels below 40% due to inaccuracies in the algorithm used to calculate the output of these monitors. {PIP 99-3980} 2.14 It is recommended that Primary Chemistry be notified prior to all significant boric acid additions or dilutions to the NC System 'Such such that proper pH control may be maintained. Normal boric acid additions and dilutions should be communicated at the Control Room shift briefing. {PIP C-O 1-665} 2.15 In accordance with INPO best practices when personnel are accessing areas that could experience significant dose rate changes resulting from increasing power, Operations shall maintain Reactor power steady or decreasing.
- 3. Procedure Refer to Section 4 (Enclosures).
- 4. Enclosures 4.2 Power Decrease 4.3 Unit Operation Between 85% and 100% Power 4.4 T-AVG Coastdown 4.4.1 T-AVG T-AVG Coastdown Data 4.4.2 Adjustment OfDCS ACCEPTED VALUE For T A AVG VG 4.4.3 T-AVG Coastdown Tracking Data (Phase 1 and Phase 2) 4.5 Power Escalation Guideline
Enclosure 4.1 1001003 OP/l!Al6100/003 OP/l!Al6 Power Increase Page 15 of 15 - - 2.50 IF required due to Generator/Automatic Voltage Regulator (AVR) testing at approximately 75% turbine power (~885 MWe), perform the following: 2.50.1 IF performing Generator/Automatic Voltage Regulator (A (AVR) VR) testing, HOLD until Generator/A VR personnel are ready for Operations to continue with Unit 1 Increase. power increase. oD 2.50.2 Once notified by A VR personnel that AVR testing is complete, at this power, begin power increase. Person making notification'--_ notification._ _ _ __ ____ _______ CAUTION: Alternate indications of reactor power shall be monitored to verify reactor power level and help prevent NI miscalibration. 2.51 At 75% reactor power, compare OAC heat balance point CIP1385 (Reactor Thermal Thelmal Power, Best) to nuclear instrumentation. - - 2.52 IF required, notify lAE IAE to adjust nuclear instrumentation per Model W/O #00874628. Person notified CAUTION: Failure to perform the following step as written may result in lifting the AS Header relief valve. NOTE: OAC Graphics CF Pump Details, CFPMPIA and CFPMPlB, CFPMPIB, shall be referred to while swapping steam supplies for CFPTs. - - 2.5 2.'533 1\1IIIII1III: . . ._ ". . . . . . . .Y;'petfofni i~~::;~ppro~trn.qt¢l5*:;8~~itu,rhiI1e::Pdwef;!(1Ji:024MWe .... . ._ _..,"'* th~ifollowil1gWlii1e;~P:~\iring iCE ( urn ." ;§~e~eaiIs;riiainta'ill'ed: .
"'P . .P.li(,,*
.m..,* ,,*..*-. . . . . . . IAII All steps to here complete. No steps signed off here ... .. .
oD 2.53.1 Slowly open ISP-3 lSP-3 (SC To CFPT lA & IB) (TB-640, IG-24). lG-24). o D 2.53.2 253.2 Adjust setpoint of lAS-2 (Main Stm To Aux Stm) to 125 psig. o 2.'53.3 D 2.53.3 Slowly close lAS-12 (AS To CFPT Isol). oD 2.53.4 253.4 IF Unit 1 and Unit 2 AS headers are cross-tied, adjust setpoint of2AS-2 of 2AS-2 (Main Stm To Aux Stm) to maintain the desired AS header pressure. 2.54 IF a temporary PC was installed at the local MSR Panel for placing the MSR's in service, remove the Pc. PC. 2.55 2.S5 IF desired to increase turbine power to greater than 85%, .go go to Enclosure 4.3 (Unit Operation Between 85% and 100% Power). 2.56 File this enclosure in the Control Copy folder of this procedure.
OP/l!B/6300/001 Page 2 of5 Turbine Generator
- 1. Purpose To describe the proper method for operating the Turbine-Generator.
- 2. Limits and Precautions 2.1 This procedure is Reactivity Management related because it controls activities that can effect reactivity. (R.M.)
2.2 Low load operation limits: 2.2.1 The unit can be operated continuously at low loads when exhaust hood temperature is < 175°P. The load shall, however, be increased slowly until the temperature decreases below 125°P before increasing load at normal rate (Multipoint Recorder on 1MC3). IMC3). 2.2.2 Limit turbine/generator operation below S% 5% load to 1 hour to prevent moisture erosion unless directed by the Turbine Engineer for testing 2.2.3 Motoring of the unit is to be avoided. 2.2.4 Excessive use of the exhaust hood sprays shall be avoided to prevent accelerated blade erosion. 2.3 Journal bearings shall NOT be operated with metal temperatures above 250°F (OAC Turbine Bearings graphic (TGBRG)). 2.4 Lube oil cooler discharge temperatures shall be lOO°F to 120 00 P when at rated speed. 2.5 The lube oil temperature rise shall NOT exceed SOop on the main bearings and 4SoP 45°P on the thrust bearing. 2.6 Under no conditions shall the thrust bearing be operated above 19000 P metal temperature (OAC Turbine Bearings graphic (TGBRG)). 2.7 Never allow a hot rotor to stand without rolling. If and when a hot rotor was allowed to stand still, when possible rotate the shaft 180° and allow to stand still again for one-half the time it first stood still, and then put the turbine on turning gear. 2.8 The minimum allowed cold gas temperature is 86°P for operation. The maximum cold gas temperature is 122°P. (OAC points CIA0522C1AOS22 (Cold Gas from Hydrogen Cooler Turbine End) and C1A0528 CIA0528 (Cold Gas from Hydrogen Cooler Exciter End), Main Generator graphic (MAINGEN)).
OP/l!B/63 00100 1 OP/I/B/63 Page 3 of5 2.9 Do NOT exceed the load, hydrogen pressure, and power factor limits per the Unit One Revised Data Book Figure 43. 2.10 Ifthe If the limits of the Unit One Revised Data Book Figur-e Figure 43 (Generator Capability Curves) are exceeded, the Turbine Generator shall be tripped. 2.11 The generator shall NOT be operated without excitation. If the generator is operated without field, the unit shall be immediately tripped off the line and shutdown for inspection. 2.12 Following a trip-out due to differential phase relays, both the armature and field windings shall be meggered and inspected before attempting to resynchronize. 2.13 Do NOT allow turbine generator speed to ex-ceed ex.c;eed 2000 rpm on overspeed tests. 2.14 The turbine shall NOT be operated with condenser vacuum less than 24.3 inches Hg. 2.15 The maximum differential pressure between adjacent LP shell pressures shall NOT exceed 2.0 inches Hg. (main condenser vacuum gauges on 1MC13, OAC points C1P1669 (DIP between A & B Condensers) and C1P1670 (DIP between B & C Condensers) or Main Condenser graphic (CMCOND)). 2.16 Do NOT hold the turbine at speeds < 800 rpm for more than 5 minutes. 2.17 When steam seals are on the turbine, the steam packing exhauster shall be operating, and the turbine shall be on turning gear. The turbine may be taken off gear with steam seals established with concurrence from the Turbine Engineer. 2.18 When a condition arises that is serious enough to make a reduction in speed necessary, it shall be initiated by selecting "MANUAL" and "CONTROL VALVE LOWER" or by tripping the turbine. 2.19 Temperature of the LH System reservoir shall be ~ 90°F prior to turbine start (OAC ofthe point C1A0188 (LH TEMP)). 2.20 A sudden downward trend on an LP turbine's lower extraction temperature shall be investigated as a possible indication of water induction into the turbine. This is indicated on the recorder on the rear of 1MC8 labeled "TURBINE WATER DETECTION", using any of the LP 8th stage lower temperatures. 2.21 The time the turbine generator is on turning gear shall be kept to a minimum to prevent the buildup of copper dust in the generator coil slots. 2.22 When system is in "EMERG MANUAL" runbacks and limit circuits may NOT be available. 2.23 Control rods shall NOT exceed rod withdrawal limits. Prior to changing power, refer to Reactor Operating Data Book, Temporary Control Rod Withdrawal Limits.
OP;l/B/63 00/00 1 OP/l!B/6300/001 Page 4 of5 2.24 A "LOAD RATE" > "6.2 MW/MIN" shall NOT be used during nonnalload changes. 2.25 The main turbine oil temperature limit of 80 to 90°F shall be maintained when the turbine is on the turning gear. 2.26 Differential temperature between adjacent exhaust hoods shall NOT exceed 30°F unless evaluated and approved by the responsible engineer (Turbine Generator System Expert). (OAC points CIP1667 C1P1667 (A & B Exhaust Hoods Metal Delta Temp) and C1P1668 CIP1668 (B & C Exhaust Hoods Metal Delta Temp) or Main Condenser graphic (CMCOND)). 2.27 During turbine acceleration, the heat up rate of the first stage bowl inner surface (OAC CIP1283 (First Stage Metal Temp Rate)) shall be < 150°Flhr. Point C1P1283 150°Fihr. 2.28 During turbine acceleration, the rate of change of the reheat steam temperature (OAC points CIP1287 C1P1287 to CIP1292 C1P1292 (CIV No.1 (to 6) Inlet Temp Rate) or Turbine Generator 125°F/hr. graphic (TG)) shall be < 125°Flhr. 2.29 Any deviations from this procedure that could affect steam admission rates shall require an engineering evaluation to be perfonned which specifically addresses partial arc admission. 2.30 The 6.9KV Switchgear Automatic Fast Transfer Switches are placed in the ENABLE position whenever the generator breakers are closed and in the DEFEAT position whenever the generator breakers are open. If an autoswap auto swap of the tie breaker occurs when in the DEFEAT position, equipment being supplied by the 6.9KV Switchgear is more likely to trip than when the switch in ENABLE. {PIP 98-4093, PIP 98-3589} 2.31 Feedback loops shall NOT be taken in/out of service during turbine control valve movement. Following turbine control valve movement, DEHC shall be allowed to stabilize prior to placing feedback loops in/out of service to prevent unexpected load changes. (PIP 03-5660) 2.32 The Main Turbine OIU Work Station has the capability to perfonn control functions for the Main Turbine, including tripping and resetting of the turbine. If a control function window is inadvertently selected while manipulating the Main Turbine OIU Work Station, the window shall be closed to prevent actuation of the control function. 2.33 The Main Turbine shall NOT be run more than 3 hours at 1800 RPM, no load, unless directed by the Turbine Engineer for testing. 2.34 The Excitation System can affect the functioning of heart pacemakers. Personnel with pacemaker devices shall NOT enter the AVR enclosure/building during operation or testing. If the A VR enclosurelbuilding is NOT installed, personnel with pacemaker AVR devices shall remain at least 20 feet away from the A VR during operation or testing. AVR 2.35 Failure to confinn steam isolation to the turbine prior to opening the generator breaker may result in destructive overspeed of the steam turbine power train. {PIP C-08-S0 18} C-08-5018}
OP/l!B/6300100 OP/l!B/630010011 Page 5 of5
- 3. Procedure Refer to Section 4 (Enclosures).
- 4. Enclosures 4.1 Turbine Generator Startup 4.2 Load Changing 4.3 Transfer Turbine From Auto Control To Manual Control And Transfer Turbine From Manual Control To Auto Control 4.4 Turbine Generator Shutdown 4.5 Placing (Removing) Core Monitor And Pyrolysate Collector In (From) Service 4.6 Valve Checklist 4.7 Generator Operating Limits 4.8 Turbine Generator Roll Computer Points 4.9 Lamp Verification 4.10 Operation of Turbine TSI Panel 4.11 Reboot of the Main Turbine OID OIU Computer 4.12 Transfer of the Main Turbine OID OIU Computer Alarm Switch That Drives the "EHC Fault Annunciator" 4.13 Voltage Regulator Operation From Control Room 4.14 Ul Gen Voltage Reg Local Control Panel Voltage Regulator Operation From VI
Enclosure 4.2 OP/l!B/63 00100 00/00 1 Load Changing Page 2 of4 o D 2.1.1.6 Verify the following valves close at 15% of full load (181 MW, 105 psig Turbine Impulse Pressure):
- ISM-21 (Ctrl Vlv #2 Stm Lead Dm) lSM-21 DID)
- ISM-29 (Ctrl Vlv #1 Stm Lead Dm) lSM-29 DID) 2.1.1.7 WHEN CV3 comes off of its fully closed 'Seat seat (65% of full load, 783 MW), verify lSM-25 ISM-25 (Ctrl Vlv #3 Stm Lead Dm) DID) closes.
2.1.1.8 WHEN CV4 comes off of its fully closed seat (92% of full load, 1109 MW), verify 1SM-33 ISM-33 (Ctrl Vlv #4 Stm Lead Dm) DID) closes. o D 2.1.1.9 S/G blowdown flowrates shall be adjusted to obtain maximum blowdown for the appropriate load.
;.' '~~~;%ti1Jil~,~iil~stag~'rql.'lfSh¢!l fl' (T~t,~lfie ~\ir~I"1~~t~A~11 T~@P)) ~3S0°
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- 3. lJnit One;Reactq~ bpe~tingData~~"ec~ion2'r4shalr~~ re(~5'&t ~2. for , al;>le rai1Jp
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Enclosure 4.2 OP/l!B/6300/001 OP/l!B/63 00/00 1 Load Changing Page 3 of of44 oD 2.1.2.7 ~~ti{)(\~ffY2iq,!diJarg~t*app,y,ar~. on\T:~rgdtI~i,sP~Y~ o ';~~'l~;i:8 o ?1.2'~j SY6blj()~qhaIlg~~ sh~~I1Je aoo[dina!~d':ffYi,in£$ycotia~nY* Ghe~l UTI 0 N :"fiie'lBact:1jJ.~~roget'pressure al1.d~oW8r1factqi'limitspertheUnit One ReVis~d Data Book CAUTION: CA Eigfiry 4j.§1l~1l Not be ex;geedeq; 2.2 IF decreasing turbine generator load, perform perfonn the following: 2.2.1 Decrease turbine generator load within the following limitations: oD 2.2.1.1 Rate of change of First-Stage Bowl Inner Surface Temperature shall NOT exceed lS0°Flhr IS0°Flhr (OAC point C1P1283 CIP1283 (First Stage Metal Temp Rate)). oD 2.2.1.2 OAC point C1Al140 CIA1140 (Turbine Lower Inner Shell Temp) vs. Percent Steam Flow (OAC point CIP1588 C1P1588 (Design Total Main Steam Flow, Measured (%)) shall be maintained above and to the left of curve in the Unit One OAC Databook "Load-Changing Recommendations". oD 2.2.1.3 Control valve casing difference, OAC point CIA0961 C1A0961 (Turb Valve Chest Inner Surface Metal Temp) minus CIA0967 C1A0967 (Turb Valve Chest Outer Surface Metal Temp), shall NOT exceed curve "Allowable Temp Difference on Control Valve Casing" in the Unit 1 OAC Databook. oD 2.2.1.4 S/G blowdown flowrates shall be adjusted to obtain maximum blowdown for the appropriate load. 2.2.1.5 IF CV4 fully closes (92% of full load, 1109 MWE), verify 1SM-33 ISM-33 (Ctrl Vlv #4 Stm Strn Lead Dm) opens. 2.2.1.6 IF CV3 fully closes (65% of full load, 783 MWE), verify 1SM-25 ISM-25 (Ctrl Vlv #3 Stm Lead Dm) opens.
Initiating Cues:
- 1AD-2, Al3, N8, B/8, C/8 E/8 and others N3, Al8,
CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/A155001016 AP/1/N55001016 1 of 14 Rev 24 DC~ A. Purpose
- To verify the proper response in the event of a nuclear instrumentation malfunction.
B. Symptoms Case I. Source Range Malfunction
- Indication lost or erratic
- D/1 "SIR HI VOLTAGE FAILURE" - LIT 1AD-2, D/1"S/R
- 1AD-2, D/3 "SIR HI FLUX LEVEL AT SHUTDOWN" - LIT
- 1AD-2, D/4 "SIR HI FLUX LEVEL AT SHUTDOWN" - LIT.
Case II. Audio Count Rate Malfunction
- Audible count rate lost.
Case III. Intermediate Range Malfunction
- Indication lost or erratic
- 1AD-2, C/1 "IIR HI VOLTAGE FAILURE" - LIT
- 1AD-2, C/2 "IIR COMPENSATING VOLTAGE FAILURE" - LIT
- 1AD-2, C/3 "IIR "I/R HI FLUX LEVEL ROD STOP" - LIT
- SIR failure to re-energize during shutdown.
- Indication lost or erratic
- 1AD-2, N1"P/R Al1 "P/R HI NEUTRON FLUX RATE ALERT" - LIT
- 1AD-2, N2 Al2 "P/R HI NEUTRON FLUX LO SETPOINT ALERT" - LIT
- 1AD-2, N3 Al3 "P/R HI NEUTRON FLUX HI SETPOINT ALERT" - LIT
- 1AD-2, 8/3 "COMPARATOR P/R CHANNEL DEVIATION" - LIT
- 1AD-2, 8/5 "P/R HI VOLTAGE FAILURE" - LIT
- 1AD-2, E/8 "OVER POWER ROD STOP" - LIT
CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/A/55001016 AP/11Al5500/0 16 10 of 14 Case IV Rev 24 DCl: DC!: Power Range Malfunction ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED C. Operator Actions IRO DOES THIS PAGE _@ BIWIIllIIlTcftD1Ili* * *MlIPII _@'VerifyaurOdmotion:':§TPPPED. _ IF unwarranted rod motion is occurring, THEN place "CRD BANK SELECT" to manual.
- 2. VgrUYiiii1 ~Q,~~?RE(8"P~B.PPWE:FROD _ Adjust Turbine load to maintain T-Avg T -Avg at
§[(Jii],-D~~.( T-Ref.
- N-41 OR
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- N-43 OR
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CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/A/5500/016 11 of 14 Case IV Rev 24 DC~ Power Range Malfunction ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. B~,Ig;[iD]!11ii~1{QJI~,~illg'i@gII~ii~I~)j\ttl~1 e~,rtQ[rn~!Ii~+lpllbWbjg °aQ:lIbrt$l~rthg J~i~:Q:~II~n~Qy°$:.
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CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/Al5500/016 AP/11A155001016 12 of 14 Case IV Rev 24 DC~ Power Range Malfunction ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED BOP DOES THIS PAGE EXCEPT LAST STEP (~~D~~d~fgi~~)ttle ~ffg:ctedqlJanner\;;ts, fqllpw~i
- a. ;ij~Jnov~JlJe:pon.Rgl POWlrfuse:i?l'flI' (l?qvy'er**RG1riY/?Ai:lt?wer.
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- b. Requ¢,§I~p~;@$M iQUJaintair):jt.he cootitPIJ:rP;pwt?~ifm:§l§" un~~~d:1I§:~ontrol;:
- c. ye~ifythe. a!f~aed'R2:\Y~tJ3,aiIlge. c. Remove the instrument power fuses at
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nR~f*: -~ve at adjust turbine load to maintain T -Ave T-Ref.
CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/A155001016 AP/1/Al5500/016 13 of 14 Case IV Rev 24 DCE DCS Power Range Malfunction ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 13. WElI3~~tii!,~lL~il!il!i"i,Ii:)Q:fj1iI.R~f~I~NmJ WHEN 1~~1l~~twjtijfll'1°fjq~jn~~f;ANDj
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CNS MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM PAGE NO. AP/1/A/55001016 Enclosure 1 1 - Page 1 1 of 11 14 of 14 Rev 24 DC~ P/R Bistables That Must Be Tripped
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- P;8
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;~t EIT'§Jlre itJJ@J!gJ(CJWiiJg gj~t~ble,§;;tor ttig;;fiffe:ptedcha(ujetar:~ placg'~*in. tb~~!;ripp~~~¢ol1gitiQn W!!biri;1;~. ijggrsr il;:!li:~gj'~lllll~liiilgl~9~ill§lij,~ID~[g,§111§1IIbg'!Dlt¢q~¢~IIRDi;HJ,~IX~j'g'illjtil!llti~lll!lQg,lgiiG§i!ligili§nRiilijini
'l'11!!,HI§g,r~l%
Initiating Cues:
- 1AD-5, AJ1, AJ4
- 1AD-1, F/4 Turbine load decreasing
CNS LOAD REJECTION PAGE NO. AP/11A155001003 AP/1/A/5500/003 1 of 36 Rev 36 DC~ A. Purpose
- To verify proper response in the event of a Load Rjection with Unit Tie Switchyard PCBs closed and the switchyard is available.
CASE II Switchyard Not Available:
- To verify proper response in the event of a Load Rejection with all Unit Tie Switchyard PCBs open and/or the switchyard is not available, with the Unit carrying it's in-house loads.
CNS LOAD REJECTION PAGE NO. AP/1/A155001003 AP/1/A/55001003 2of36 Rev 36 DC~ B.Syinptoms
~~~SE I ;tSwitcliY~rdAvaiiaple:
S,<<jt§"~yard ene(giz~~¥AND. anY'S,WitchyarClHUlitTie 'P~l?clos~'QjAND:
* . . . . . .I'iIIIBJr-11MP'IIIII!8
- _ i l. . . .tl. . .m*DJI~illflllllI
." . . . .JINIL.)U...,....",.,..'l~ypl.l)
"C-77'\jlJ;;Q~.PQijt:@~PiU:\J'lt!':!~GQN
.~. ' ...,_~fI!Mfm~._
DDUMl1j~statiJ~llighn( 1~1;:18). . t0ri;llli: JrC~7B:t~Q~S 9fT:. r::QA;P)11~\I}.u!\AJMOSpU~f'*~statUsli~t '(lSI-18[~lililT{
."'IM' .U,..-. $
CASE" CASE II Switchyard Not Available: Switchyard not available AND:
- 1AD-1, F/4 "TURB RUNBACK INITIATED" - LIT
- Turbine Generator megawatt output - RAPIDLY DECREASING
* "C-7A LOSS OF LOAD INTLK COND DUMP" status light (1SI-18) - LIT * "C-7B LOSS OF LOAD INTLK ATMOS DUMP" status light (1SI-18) - LIT
- Condenser or atmospheric steam dump valves - OPEN
- Control rods - STEPPING IN.
CNS LOAD REJECTION PAGE NO. AP/1/Al5500/003 AP/1/A/5500/003 30f36 3 of36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- c. Operator Actions IRO DOES THIS PAGE
-0 i~~rifYr~gl]§lg:~!I',~flg,I:'1I6§1~J;il!§I.~~I.~. Verify
~",JlQM,lm~m,~)
~l.rIPM,6Ij~U tt1rlilp~!19ijd;" DeggEA&It,lGJN Perform the following:
- a. Select "MANUAL" on turbine control panel.
- b. Depress "CONTROL VALVES LOWER" pushbutton and reduce turbine load as required.
o
\;;;;,I ~.,"efJ:fy~Fro
.'.' /;£1% p,et teactotres arise:
" ..'" . . "v...*** P... ,.',,,4,. . _ ilRim[*l\y;glili§:;:"g'ij~~~irl§~lll,d,
~~~~Q;[f7tj~RTBEN
* *§":i,llllfiigQ:iri*
JR{iT+~y,gji~'gt:¢~ter tI)Cl,!1*1.5~f:'ffiiglJer. mClIj,pallyiDsertj~onlt§1 1,!J:~!'njmiligfili!mllII:(glm~!lY~I!~.ii',lii§gllpQnln~I' _ leCd'1r:ol
...,.,ll~", rodsi+;"IN,"A1JTO"At:413
.....'<'..... ,,' . , .M"" .. ;fQ:qst;'E(~ireqlfif~;d tom",intain:;i!,tAvg WiUnn iiQ;g§'1lJ,i~t!liqY:ir~Sj~~lrm~U"Jai!lJIn~l!ygIWiIJli",
.$Jf.§;/iPINGJN i:,Qfltm'Rifl)
,:t:~Fof;r'Reff lid,:DE'
_ .; "R/~$ttgpl((jljJlux, ~(:l9CRqASI NGf Rods fail to work in AUTO I
- 3. Verify plqJl~t:~~~i!m!d urti'RJ op~~Cltionc)~:
~irj!~!Jlt;gJliiril§~~ili!lgYmRJQJlir~~i6Qi'~§J
',fQllows'D}
- foUows:t
~. ¥Cerify T ~Re,f!iristrl.!1iieiJtaliQiidl a. IF T-Avg Coastdown is in progress,
- AYAILA~J~J=~ THEN determine T-Ref from table.
REFER TO Enclosure 4 (T-Ref Value RunbacklPower Reduction). Following RunbackiPower
- b. "C-:~l:~ONDrA,V~IIJA:J~lf.E6PIi:[$I:M; b. Perform the following:
- DUMp"*statMf:ligtil.(1'61~:1~J~I~I';~:
_ 1) Manually operate S/G PORVs as necessary to maintain T -Avg at T-Ref. _ 2) GO TO Step 4.
CNS LOAD REJECTION PAGE NO. AP/1 / Al5500/003 AP/1/Al5500/003 40f36 4of36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued)
IRO DOES THIS PAGE I
- c. c. IF steam dump valves are closed AND T-Avg is 3°F greater than T-Ref, THEN:
* "Q~7,'A\!+q~~(~~fJ2G~P INT~I< CONQ D lJM~I:1l§!clltJ§inght(:1§1-18)~;"LrT. _ 1) Place "STM DUMP CTRL" in manual.
_ 2) Adjust "STM DUMP CTRL" to 0% demand. _ 3) Place the steam dumps in pressure mode. _ 4) Manually operate condenser steam dump valves to maintain T-Avg at T-Ref. _ 5) IF steam dump valves fail to operate, THEN dump steam as necessary from available S/G PORVs to maintain T-Avg at T-Ref.
- d. d. Perform the following:
_ 1) Place "STM DUMP CTRL" in manual. _ 2) Adjust "STM DUMP CTRL" to 0% demand. _ 3) Place the steam dumps in pressure mode. _ 4) Manually operate condenser steam dump valves to maintain T-Avg at T-Ref. _ 5) IF steam dump valves fail to operate, THEN dump steam as necessary from available S/G PORVs to maintain T-Avg at T-Ref.
CNS LOAD REJECTION PAGE NO. AP/1/A/55001003 AP/11A155001003 50f36 Case I DC~ Rev 36 DCE Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. BOPP DOES THIS PAGE
- a. IF Pzr pressure is less than 2315 PSIG, THEN:
_ 1) Manually close Pzr PORV(s). _ 2) IF any Pzr PORV cannot be closed, THEN close its isolation valve.
- 3) IF Pzr PORV isolation valve cannot be closed, THEN:
_ a) Trip reactor. _ b) GO TO EP/11A15000/E-0 EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection).
- b. IF Pzr pressure is less than 2260 PSIG, THEN:
_ 1) Manually close the affected spray valve(s). _ 2) REFER TO AP/11A155001011 AP/1/A/55001011 (Pressurizer Pressure Anomalies). _ b;; ~~~iW:t;t6'~qtqrpoW¢t:G8I::AIEg'TPili1i1J b. GO TO Step 6. (Q§21d! P~I.9g:l'O JI3,EtEVEfilill c~t, fVefifCml"n'dbiholwellrufn
. . d.
'(5) FOR V@,~,8.J"".'Yd'.' ."".H""P,." c. Manually start standby hotwell pump(s) as necessary.
- d. Manually start standby condensate booster pump(s) as necessary.
CNS LOAD REJECTION PAGE NO. AP/1/A155001003 AP/1/N55001003 6 of 36 Case I DC~ Rev 36 OCt Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED U fi36Pl6. Veri~j~!le f()UbwiQgige{'1Efr~to1CJ,ratms,~1 PARt(1,: _ Ensure turbine generator load - REDUCED TO APPROXIMATELY 48% AND THE ALARM CLEARS. _. 1AD-111~Cf1\,'G,ENIiKR A OVER i~JJRRE;~iRr: _~; ,'~~P"'~t<<~*tfh1<"~,E:t\J';*f?KR,Hr'VEIl'
~EJF\fR.l;f);Ili':~
IIRol?* R0 I 7 .V'et:ifV~~/G.I¢9~ls*~t@~~1~llgat~a,~; Perform the following: f91IcjIN§.;
- a. Ensure feedwater regulating valves -
_
- AfI'SZl3 loW:levelglert:~larrTl§K:1AQ7ffk;l MODULATING TO CONTROL S/G DAR~ LEVELS AT PROGRAM SETPOINT.
- b. IF any S/G(s) N/R level is decreasing in an uncontrolled manner, THEN:
_ 1) Trip reactor. _ 2) GO TO EP/1/A15000IE-O EP/1/N50001E-O (Reactor Trip Or Safety Injection).
CNS LOAD REJECTION PAGE NO. AP/1/A/55001003 70f36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IRol a. Perform the following:
- a. Place "CRD BANKSELECT"-switch -IN MANUAL.
- b. Maintain control rods above insertion limits.
- c. Operate control rods to stabilize reactor power between 6%-10%.
- d. IF AT ANY TIME reactor power is less than or equal to 5%, THEN perform the following:
_ 1} Ensure turbine - TRIPPED. _ 2} Concurrently insert control rods to shutdown the reactor. REFER TO OP/1/A/6150100a OP/1 IA/61501008 (Rod Control). _ 3} GO TO AP/1/A/55001002 (Turbine Generator Trip).
- e. GO TO Step 10.
RO
- 9. IFAI'~NYTIMEr~~ptorp()~etis)EiSS thf,lo<ot;;iequ.~lto.,20%;THENperf9rm S~eR1QsRNg;
_ Adjust 1AS-2 (Main Stm To Aux Steam) as required to maintain AS header pressure between 140 PSIG and 150 PSIG. ~_ 11. Calculating boron for this is an ADMIN JPM on this exam. If they start to do it, then the next event should begin and the TS can be reviewed during followup. Nll>I1][t:9t En);JQ~y:!;gJ~.(B§qi#hsettion Uhii'l'~()rilllQrm)
CNS LOAD REJECTION PAGE NO. AP/1/A/55001003 8 of 36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED lRo RO l 13. 13 . P~ljprm (b~foIlQWihgI a':~ i,J~ft!il~)lfj£l:QI~~¢l<]~rg§ltl!D;'aa isl~~s.J~b.~ri 3~o/&;i"fAEN11 _ 1) WHEN time and personnel permit, THEN perform applicable steps of OP/1/A/61 001003 (Controlling Procedure For Unit Operation). _ 2) Do not continue in this procedure until reactor power is less than 30%. _ 3) WHEN reactor power is less than 30%, THEN GO TO Step 14. b..VIlHEfllj!IIJ~!~R:r:!Ct'!!pqri,t~r!(r:gn~!~~~t~:qg~Fi b WHENJheat2Jlfip'pr{§,tetllnb:aG.ktarget laagi~!II:(~a¢n~g]lTHBN!;! 10adisreach~q}THEN: _ 11Stabilizeuriit atlQurrent.pow¢r leV:~I~ _ ~.9} \W~intaltj~co{lJ~O:! rogs ab()v~, ij1*Sel1i.dh71Imit~..
.$) AdjIisIltfjgIQlld~i.h9,;'a~.**r'eq~ir'{¥g;;to maintainijt~yg'~itfliri1 °F6f 1!1':Ref:
{Turi:>!t(ejoad
;~ContfQI rods
-_ '!i~ .j0ci'fcil;i;conMntratiOh.
H;'V~7>.A.M>.dJl;..'. ',',:,'hAh'> ,','... ,A{,.>'Ah~".*
- 14. Verify the "RESET" light on "AMSAC "AM SAC Perform the following:
FOR CF VALVES" switch - DARK.
- a. IF turbine impulse pressure is less than 190 PSIG, THEN notify IAE to correct the cause of the AMSAC failure to deactivate.
- b. Depress the "BYPASS" pushbutton on "AM SAC FOR CF VALVES" switch.
- c. WHEN 2 minutes has elapsed, THEN verify "RESET" light on "AMSAC "AM SAC FOR CF VALVES" switch has remained dark.
CNS LOAD REJECTION PAGE NO. AP/1/A/55001003 AP/1/A/5500/003 90f36 9 of 36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED When separated from the grid the turbine reverts to speed control. Perform the following:
- a. IF both generator PCBs are open, THEN ensure main turbine speed -
MAINTAINED BETWEEN 1792 AND 1807 RPM.
- b. IF the turbine generator is separated from the grid, THEN:
_ 1) Ensure main turbine speed - MAINTAINED BETWEEN 1792 AND 1807 RPM. _ 2) Ensure main generator voltage - MAINTAINED BETWEEN 20.9 KV AND 23.1 KV.
- c. IF load rejection caused by loss of main busline 1A or 1B, 1B, THEN:
- 1) Notify Transmission Control Center (TCC), using one of the following methods, to investigate and repair cause of the loss of busline:
- 704-382-9403
- 704-382-9404
- 704-399-9744
- 704-382-4413 (System Operating Center).
_ 2) WHEN notified by TCC that the affected busline is ready to be re energized, THEN restore power to the affected busline. REFER TO Enclosure 1 (Offsite Power Restoration ).
- 16. A~UI~tP:9~?t~tfClct~ffas Il~I::es~arY..
.*REFER mJiU!1iJ~l1i!li~vi$.~QjDClt!l,:.I?O()1s:
.F:;igl.lr~. 4~j
CNS LOAD REJECTION PAGE NO. AP/1/A/55001003 10 of 36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. WHEN1lhe apRrQ"lJ,~l~l;,lInJj;a:~k'JFf:g~l, J,9aq.~;tti~!;:tl~'9f~REN1)
_ *... :StabiTig:~lQtl,itatappropf:I~l.eP9werrev~!. _. i~g!ti~i;tlli"qQfitrol rqd$aoqY,e in~ertron
;lrtlIlt§": .
~**t\'rJll~tthe foIJQWi,n9ka~;tecjtilf;¢dto m?ii 6t[3in T-!\yglWitllitilq F[~~r~*Rgft
~*., TOlbine lo.\:iQi
.:. '.C9]'ltrol r09h~~
- Boroll Gori¢gt[ttEliii>.Q,:
1.8. N.()lifypysteml:.Q]~~rijlIbgQibf,@.(~OC)j
*q$i)j9l!.he req~i~patql1~tJ~I~PDOn~;pf
;c'iltretitiunit~ta:tijs.
1.9~ D.~lermil'O~i~iIq cqt~~ct caUse9f.IOad Q@~g[mUig!ti'al~nngg~g~g§@!mllg'a(lli Load rejection caused by loss
~gjgglIgU~;
(~jectiol1: of CF pump.
CNS LOAD REJECTION PAGE NO. AP/1/A/55001003 AP/1/A155001003 11 of 36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 20. S!lytdQwrfunn!¥~~s~l'N4RJjibtl~quiRm,~I1~
IBOP 1~§If:Qlt(?\yS:
\a)' Re$t9~~.9~~Arl~.\CFas. tfpllbW~;
_ 3} Shutdown one CF pump as necessary. REFER TO OP/1/A/62501001 OP/1/A162501001 (Condensate and Feedwater System). _ 4} Shutdown excess Condensate Booster Pumps. REFER TO OP/1/A/62501001 OP/1/A162501001 (Condensate and Feedwater System). _ 5} Shutdown excess Hotwell Pumps. REFER TO OP/1/A/62501001 OP/1/A162501001 (Condensate and Feedwater System). b. 41..8i~s~t$1~am dijm;p '~~!i~j;~.§f6UP\V~:; 0 IR I _9;\ 'M~rlwr~§,q!6f PQ\y~(':§J~E?ltE:il a. Perform the following: _ 1} WHEN reactor power is stable, THEN perform Steps 21.b through 21.g. _ 2} GO TO Step 22.
CNS LOAD REJECTION PAGE NO. AP/1/A155001003 AP/1/A/5500/003 12 of 36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 21. (Continued) IRQ does this page
- b. veftfyst&~ftDduhipyalv?s - IN. b. Perform the following:
"I:7f>.V:G" MGQE.
- 1) IF using S/G PORVs, THEN:
_ a) WHEN T-Avg is within 1°F of T-Ref AND stable, THEN close S/G PORVs. _ b) GO TO Step 21.d.
- 2) WHEN T-Avg is within 1°F ofT-Ref AND stable, THEN:
_ a) Ensure steam dumps - CLOSED. _ b) Perform Steps 21.d through 21.g. _ 3) GO TO Step 22.
- c. c. Perform the following:
_ 1) WHEN steam dump valves are closed, THEN perform Steps 21.d through 21.g. _ 2) GO TO Step 22. _ d. ,~e~,~tstg;l;3!ndqmp Vq!y:~S.
'., e I Y';"'$ke.'ff e,.Ii Vrif.~~'~m g,.*,".9! J?......9 ht
*.. Q'lIBwiii'is:r"Jl1iti
*. ;h.., ..... §
{1SI~~~J:~ Dl\~lS.: _ ~" ~{;-7 A.[:;9SS.QF[OA@INTJi:.KCG~C) PYMPii _ 2JJi ~~~}13,l,.;QS$\QFLQ(\PJNJJi:.K
'l\TMQ$,:P;Q4MP:!:~'
_ g. IF steam dumps are in "T-AVG" mode, THEN place "STM DUMP CTRL" in auto.
CNS LOAD REJECTION PAGE NO. AP/1/N5500/003 13 of 36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Transfer feed flow to CA nozzles. REFER TO Enclosure 2 (Transferring Feed Flow From CF To CA Nozzles). IBOP
- 23. ~e~i,fYl~A ptdTlPs - QfF"~
il\i~iU1,1'~iRmm'i}~i91~,til,Ei~ Perform the following: Periorm
- a. WHEN CA is no longer needed to feed S/G(s), THEN shutdown the CA System S/G(s},
following the automatic start and return CA System to standby readiness. REFER TO OP/1/N6250/002 (Auxiliary Feedwater System).
- b. Re-establish S/G blowdown. REFER TO OP/1/N6250/008 (Steam Generator Slowdown).
~RO
- 24. 'lerifYJreac~()r::p()WetZl:l1an9~Y~'IG~§;~TE~
I;I1~N(Q~I:QVALTQj15%[~.:A 1!{1:lI.~1J~**
.~,r;g'J~p.
- 25. NotiU1, the following sections to take Notify Depending on how far they appropriate samples:
reduce power, this step may
- Radiation Protection to sample and apply and they will do step 25.
analyze gaseous effluents. REFER TO Selected Licensee Commitments Manual, Section 16.11-6.
- Primary Chemistry to sample for isotopic analysis of iodine. REFER TO Tech Specs 3.4.16 (Sample must be taken between 2 hours and 6 hours following last power change greater than or equal to 15% rated thermal power within a 1 hour period).
- 26. er1~J.I~~iC()I11PU~t1ce fiUfi' apBr()pri,m~)
l~,g~,m~§ii!~~mi}Lii~ij~ii~iilg'~R:m,tgi}il,,~jgl TS 3.1.6 Condition A (if rods are below llt~~g11IR,i'§~~ {r1!elj"f~peC$t.i LoLo insertion limits.) _ .~~).;t(~1i1l'4t9wt1~girgjJ~J{$PM~i))
.3.1.6 faDtfftbl'tBarnkH;'S'ertillln:m:'its"
. '. .L.A".**..*..** ".. " ..*....**!l.IL~~. ..*.*. A .**. JLl. ",,./.
CNS LOAD REJECTION PAGE NO. AP/1/A/55001003 AP/1/N55001003 14 of 36 Case I Rev 36 DC~ Switchyard Available ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 27. :N9J!fy ReactorGroup'~'ngineer o{'
o§,§~rrence~ _ g:§:i Det&':[m1:!le'tR:rigite~d?fant sIJl~,~~
,RETtiJRN\lT0;rpP/1lAlI§I~g!l/Q,Q3
\n~c?:ntrQllitlg ~roce;~PtB!lqflUni~
~Qpera~jor).
Initiating Cue:
- 1AO-6 C/12, E/10, F-8 NC Pressure decreasing
CNS eNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/AJ55001011 1 of 9 Rev 22 DC~ A. Purpose To ensure proper response in the event of abnormal Pressurizer pressure, assess plant conditions, and identify the appropriate steps for the following cases: Case I Pressurizer Pressure Decreasing Case II Pressurizer Pressure Increasing. B. Symptoms L
.1:J\D-Bt;jZ6;~1 O\~RZg po.av OJ$:~H ;;t;;IUW£;'MI?"~f:~rr
'. 1~~~~;;;E,:/U*~R~RSAiETY;DI~~1;V:\lK~I3HU{.E3MIi?,'c\- LIT e .1~OiqtIT:~a\*B41~;.l.i;o.;fl:RESSiQo.~TRJ~L" ;'::U;lf e* \1:J\Q16;;AJB:\\I?;l:RlliIJiSf;?Rl;SS:J\trRTl'FLiT:
fi Allpzr b~aterS"I2NER~JZED
- 1~P7§;;p7iUnf~R Lo.YiRl2§~iPql3V~N~34'~l:;OC~ED" -t,;F
.. :t~P;2,:~Dl19 3l'f.?i~l;l~}ifi\R§~$;;P0RVtt'JC32j'&36Bl9Gts:EP:;;::LlT .~; ;f)re~surizerpress:;qr¢; leS~l1thaQ22g51P~!G~~nQ. d~~a.~jig Case II. Pressurizer Pressure Increasing:
- 1AD-6, D/8 "PZR LO PRESS ALERT" - LIT
- 1AD-6, C/8 "PZR HI PRESS DEV CONTROL" - LIT
- 1AD-6, B/8 "PZR HI PRESS" - LIT
- Pressurizer pressure greater than 2235 PSIG and increasing
- All Pzr heaters - ENERGIZED.
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A/5500/011 2of9 Case I DC~ Rev 22 DeE Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED c. C. Operator Actions IsOp BOP a.
- b. ifF ah~{'pzr PQ~')l:"caDfi"Qrb~9Jt2,sedt),
PORV will stick before it gets .'IT'HEN;ii full closed. _ 1) Clo§~li~h~:af(til~tepPORV(~>>) isqU:UIg.Q¥:t!,llgt;
- 2) IF the Pzr PORV isolation valve cannot be closed, THEN perform the following:
_ a) IF in Mode 3 with CLAs isolated OR in Mode 4, THEN GO TO AP/1/A/5500/027 (Shutdown LOCA). _ b) Trip reactor. _ c) WHEN reactor tripped OR S/I setpoint reached, THEN ensure S/I initiated. _ d) GO TO EP/1/A/5000/E-O (Reactor Trip Or Safety Injection).
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A/55001011 AP/1/A15500/011 30f9 Case I Rev 22 DC~ Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED _ 2. ~D.I"'IIBII 2.~y:~rify Pzrsp~i:ayvalve(sl *)<;LOSEQ,;$ Perform the following:
- a. Manually close affected spray valve(s).
valve{s). IBOP
- b. IF affected spray valve(s) valve{s) will not close, THEN perform the following:
- 1) IF AT ANY TIME the Control Room Supervisor determines that a reactor trip is required, THEN:
_ a) Trip reactor. _ b) WHEN reactor power less than 5%, THEN stop NC Pumps 1A and 1B. 18. _ EP/1/A/5000/E-O c) GO TO EP/1/A15000/E-O (Reactor Trip Or Safety Injection).
- 2) Select "FAIL CLOSED" for affected spray valve(s) mode select switch:
* "1 NC-27 PZR SPRAY VLV MODE SELECT"
* "1 NC-29 PZR SPRAY VLV MODE SELECT".
_ 3) IF NC pressure is stable OR increasing, THEN GO TO Step 3. (RNO continued on next page)
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A155001011 40f9 4 of 9 Case I Rev 22 DC~ Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (Continued)
- 4) IF NC pressure continues to decrease, THEN:
a) IF in Modes 1 or 2, THEN: _ (1) Trip reactor. _ (2) WHEN reactor power less than 5%, THEN stop NC Pumps 1A and 1B. _ (3) GO TO EP/1/A15000/E-O (Reactor Trip or Safety Injection). _ b) Stop NC Pumps 1A and 1 B. _ c) IF NC pressure continues to decrease, THEN stop additional NC pumps as required. _ d) REFER TO AP/1/A155001004 (Loss of Reactor Coolant Pump). _ IF Pzr pressure is less than 2220 PSIG, THEN ensure all Pzr heaters are energized. IBOP
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/11A155001011 AP/1/A/5500/011 50f9 5 of 9 Case I Rev 22 DC:: DC~ Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED N<J'IlB NOTE Positive. rC?ag!i£:ityiSltj;)s~:tted!QiJtiQgK?riti[~aseiftJ~cpr~ssur:~whicn\rnaY'(lause; aut()rocLiiIl)~$KttiQtli* _ IF pressure continues to decrease, THEN AP/11A15500/01 0 (Reactor REFER TO AP/11A15500/010 Coolant Leak). BOP _ * $'aO:jliz~)jott at appr()prial~;ffJbw~'r';I~ye];'\
~: :l\J;!lqi'stJt1&KfollqWimgas reqUitedt~
@aiDtaif(\illt~yg!@!Jhin:FRtof T~Rij.f:
_ . . . . . T ur;Qltte"Jo§~!
= .,'1 CootrQlfo'gS;i
**~BQrO(1con~:1)lJra,tiph,
- 7. ,:'I.Ii,!!~'!6i!llIBtg§,§,'(!!t@!!!~J!~'!Jh@lt~i!g<1i~liPlEN'
;li;~.!Bz{;\pt~~,~.ure¢ltannel f~i!edJ~]HEN perform following:
- a. Verify "P-11 PZR SII S/I BLOCK a. Ensure compliance with Tech Spec PERMISSIVE" status light (1SI-18) (1 SI-18) in 3.3.2 (Engineered Safety Features required state for unit conditions. Actuation System (ESFAS) nstru mentation).
IInstrumentation).
- b. Notify IAE to fail following bistables for affected channel per Model W/O W10
#00874531. Bistables shall be tripped within 72 hours:
- Pzr low pressure S/I
- OT Delta T
- Pzr high pressure Reactor Trip
- Pzr low pressure Reactor Trip.
CNS PRESSURIZER PRESSURE ANOMALIES PAGE NO. AP/1/A15500/011 AP/1/A/5500/011 6of9 Case I Rev 22 DC~ Pressurizer Pressure Decreasing ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. E!1s(frel;(:o:l:Qplianc~"WJ!,l;if;~pprQR:Ci,~!e, T:¢ch Spec~~ TS 3.4.11 Condition B
* @;~3: 1:(B.eactQji,Trip Syst~m (RTS) fli1§lt!:Jrngntatidn );
TS 3.4.1 Condition A (based on NC pressure at the time) _:~" 3.3Y4:i(R~mdJeSMQ,t,(:jqW,ri SSl§te'hl)) _ Jli 3f4.1itl~C~:~pressure:j;I1:T(~rnP~1~mre.~ndJ flo~;;De:J?;;(fitur:eErom'N Cipl~at~:t1ibmng (D:ti~)tt:rnit~) _ It~,~~~ (R~S;:Loog~~MODqR, 1;ii~iid 2) _ * ;~;~4j'5i{RCS Ltflf9PS::: MODE1~)
. . . . .t.rIIBIIII~WIII
_ *.';:3A.6,(RG9>Loop~~;N1QP>EE~} _*IBIIIJl
~
-_ (~> ;?~;!1P
~!ii~;4.9 K~t~s,"§:~r'J~er;y
(~res~urj~erSafeMVa!ves) _II9.
-.~
_ *. @54: 11 (Pre?stirizer P9W~Ji;Operat¢<;i; _ _~.J) ReliefVgl~$~
, 3,4i~'~:B
,~",P:~:>> ~
(ReStO,,;, (PORVs}),: 0'e""['6+j'o' nar;'I)'0a'
""",.'< .,~.*>,>t~h<< .. ~J\.
Determinelpngterm,planf,statll?
- c.
- 17a""g""'e)',"
L~~,>>"'<>, ~c c RETURN rnl procegil!¢:~.ri ef{~£f~;t
SCENARIO 3 EVENT 6 DATA lAD-4 D/4 1AD-2 INITIATING CUE: 1AD-4 lAD-2 F/9 There was a Case 3 of AP/1/A/5500/00G AP/l/A/5500/006 but it was deleted as a result of ofthe the DCS modification. There is no specific procedural guidance for this failure, other than OMP 1-8, step 7.2.C guidance which states:
"When process control, process protection or safety signals are generated in response to valid plant conditions and equipment fails to automatically position, then a licensed operator is expected to properly position the equipment."
Crew is expected to manually control valve 1Cf-55 SI<5 lCf-55 to prevent a low S/G level reactor trip or a high S/G level T/G trip based on 1D lD S/G level. Once they have control and the SRO has consulted Technical Specifications, the Major Event will begin. TS 3.3.1, Item 13.e ( 5.a.{2} Condition J, Item 5.b.{2} Condition D, Item G.b 3.3.2 Item 5.a.{2) 6.b Condition D 3.3.3 Item 10 Conditions B, D, 33.3 \I 0, F, alid II "Yt:- j?t:.- 3.0.3 {due to two failed channels}
2nd CF Pump TRIPS. Containment pressure increasing NOTE: LOCA occurs on Rx Trip.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O 1 of 61 Rev 36 DC~ A. Purpose This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of all Reactor Trips and S/I5/1 above P-11, valid S/I 511 below P-11 and to assess plant conditions, and to identify the appropriate recovery procedure.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-0 2 of61 of 61 Rev 36 DC~ B. Symptoms or Entry Conditions
- 1. The following conditions are symptoms that require a Reactor Trip:
- 1 of 2 SIR channels - GREATER THAN 105 CPS WHILE BELOW P-6
- 1 of 2 I/R channels - GREATER THAN 25% FULL POWER AMPS EQUIVALENT WHILE BELOW P-10
- 2 of 4 P/R channels - GREATER THAN 25% FULL POWER WHILE BELOW P-10
- 2 of 4 P/R channels - GREATER THAN 109% FULL POWER
- 2 of 4 P/R channels - +5% FULL POWER IN 2 SECONDS
- 2 of 4 loop ~Ts - GREATER THAN THE OP~T SETPOINT
- 2 of41oop ~Ts -GREATER of 4 loop ~Ts - GREATER THAN THE OT ~T SETPOINT OT~T
- 2 of 4 Pzr pressure channels - GREATER THAN 2385 PSIG
- 2 of 4 Pzr pressure channels - LESS THAN 1945 PSIG WHILE ABOVE P-7
- 2 of 3 Pzr level channels - GREATER THAN 92% WHILE ABOVE P-7
- 2 of 4 S/G N/R level channels on 1 of 4 S/Gs - LESS THAN LO-LO SETPOINT
- 2 of 4 NC pump buses - LESS THAN 77% OF NORMAL VOLTAGE (5082 VOLTS) WHILE ABOVE P-7
- 2 of 4 NC pump buses - LESS THAN 56 HERTZ WHILE ABOVE P-7
- 2 of 3 NC flow channels on 2 of 4 NC loops - LESS THAN 90% OF LOOP MINIMUM MEASURED FLOW WHILE ABOVE P-7 AND BELOW P-8
- 2 of 3 NC flow channels on 1 of 4 NC loops - LESS THAN 90% OF LOOP MINIMUM MEASURED FLOW WHILE ABOVE P-8
- 4 of 4 turbine stop valves - CLOSED WHILE ABOVE P-9
- 2 of 4 turbine stop valves EHC pressure - LESS THAN 550 PSIG WHILE ABOVE P-9
- 1 of 2 S/I SII trains - ACTUATED
- 2 of 2 SSPS trains - GENERAL WARNING ALARM.
CNS REACTOR TRIP OR SAFETY SAfETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1 I A/5000/E-O 30f61 Rev 36 DC~
- 2. The following are symptoms of a Reactor Trip:
- Any Reactor Trip annunciator - LIT
- Neutron level - RAPIDLY DECREASING
- Rod bottom lights - LIT.
- 3. The following are symptoms that require a Reactor Trip and 5/1:
- 2 of 4 Pzr pressure channels - LESS THAN 1845 PSIG
- 2 of 3 containment pressure channels - GREATER THAN 1.2 PSIG.
- 4. The following are symptoms of a Reactor Trip and 5/1:
- Any SII Reactor Trip annunciator - LIT
- NV, NI, and ND pumps - ON
* "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT
- E/S Load Sequencer Actuated status lights (1SI-14) - LIT.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP!1!Al5000!E-O 4 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions RO DOES THIS PAGE IRO 1.
@ 'MerifY Fi~iict91i~lljp,: Perform the following:
_
- All roC:JpotI,om;llflfs\!§,¥~!f\crTli a. Manually trip reactor.
_ * 'AUreaqtqr~lrip~ltQPypa'~'§!:>.raa1iers-: b. IF reactor will not trip, THEN
'OPE~} concurrently:
_ .f1HIRanj~§iiPE,~;iJ;?\§IN~.' EP/1/A/5000IF-O (Critical
- Implement EP!1!Al5000!F-O Safety Function Status Trees) .
- GO TO EP!1!Al5000!FR-S.1 EP/1/A/5000/FR-S.1 (Response To Nuclear Power GenerationlATWS).
Generation! G) V~i;!fY~lurbi'1g;rrjp: Perform the following: _ * 'AII!t~rpi,QJ~tf~JppYflI¥esc~J2.9SEq; a. Manually trip the turbine.
- b. IF turbine will not trip, THEN:
_ 1) Depress the "MANUAL" pushbutton on the turbine control panel. _ 2) Rapidly unload turbine by simultaneously depressing the "CONTROL VALVE LOWER" and "FAST RATE" pushbuttons.
- 3) IF turbine will not runback, THEN close:
- All MSIVs
_
- All MSIV bypass valves.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1 IA/SOOO/E-O S of61 50f61 DC~ Rev 36 DC!: I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED -0 Perform the following:
- a. IF 1ETA AND 1ETB are de-energized, BOP DOES THEN GO TO EP/1/A15000/ECA-O.O EP/1/A/5000/ECA-O.O (Loss Of All AC Power).
THIS PAGE
- b. WHEN time allows, THEN attempt to restore power to de-energized switchgear while continuing with this procedure. REFER TO AP/1/A15500/007 (Loss of Normal AP/1/A/5S001007 Power).
0..,...*- _ a. 1. . . . .~1IIJ!!' a. !~~rtQrm the f6I1dWig:g:
~
;t) VerifyconqiiiQiisreqllirjng S/!~
_ .' Pzr pressure -.LE§STH~N:
.1. 84.~.gSIG Auto SII is blocked on both channels. Manual initiation Q;R' required.
CRITICAL TASK! _*....**iiMM.. tIIIS. . . .~1 _R _ 2) . ... IF;'l'~lI* ,~::i'~quired}jTHEN 1lIIIitf.li'. .ma.nually) ijtg.itiat~ SIL 1IU111P1 3} IF S/I is not required, THEN 3) concurrently: _ .* Implement EP/1/A15000/F-O EP/1/A/SOOO/F-O (Critical Safety Function Status Trees) Trees)..
- GO TO EP/1/A15000IES-O.1 EP/1/A/SOOOIES-O.1 (Reactor Trip Response).
- b. B6th E/S IQa~~~~quen:¢~r actuated. b. Manually initiate S/I.
st?tl.J~l.ight§ C~St'*J:4} IlIff.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/A15000/E-O 6 of61 of 61 DC~ Rev 36 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
~, REF BB,1il1(;),'iRP/07A1500Dl001" (ClassiU~~ti,!:>rl~\f\,I~rtJerg@ncy)'
* ; ~REFERliF(;)iRP!Q@/500QIQ13 (NBC
*hl6ti.m::.;3tiQQ\~equr@J1ents1*
- 8. Perform the following:
- a. Manually initiate Feedwater Isolation.
- b. IF proper status light indication is not obtained, THEN manually close valves.
IBOpl
- 9. .Vjfrift:'8hai;e'"AlContalhtrienOJ$6Jc:ltiot\'
sf5!tiI~~:~sfqU9WS:. a. a.~JJase;lI*:fi.ESETI'*ligh!~r~*DARK. a. Manually initiate Phase A Isolation.
- b. MOQitG:e:Pigh1p~Ji~I.G;ifg:~P;.5§JligtIt~ b. Manually align valves.
LIT;. v~ti~~prqp~r(Pha~eJB *a.ctl.laf.iQn~fu~} 10 .I~g~im~e!IS!P~t'lgflg~~I,~!,gpIIUIIgill!l~~i! fdnos:~... li!lg!~§!~f
...., ~. .
- a. Ccjnt~IDm.~r1t~llt;g§:§Ql~i;:(HA§; a.
RE;~INEQ~lE;§S;~lltil~t§I 311~1G~ iROTE: Thi~~lirne .rnc:i*~:bell~gd r~1ert04~teffriine\ (~tl!;~n 19;:~Ugn NQAlix'
~B[~yJ;
_ ,?I'M~rify~l)I§.11purnm)* ;;:IN[}I~ATING FLQ¥\li _ !~,)J jll3ifIR~~'nqt!'l;nJjit~Ji!, THEN
'!!:i~laU~I.IY?injXi~t~Pq~~ .B!solation f6t;~If~ct~(Htt~iQ{ s'f' (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A1S000/E-O 7of61 7 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE ACTIONIEXPECTED RESPONSE NOT OBTAINED
- 10. (Continued)
BO
- 4) \~erify Ph gse:'&lUS:9Iation h~s
~JrNated(,~~Jdlli~§}
_ aI, 1l!f:hC\s~'l§;lsdlaIip'ijl?l!tRE$ET"
--_e Ug,bts':;PARK;
_ b) mPIi~se BIS6l?:!!~n"RESET" Ji§bts are lit, THEN':rjjanuat!y iqitjg~e Phase B Isdla,tion, c) Vefityfollowingr:tl9hitqr 1Ig111\ panelligbts - LIT: _*~11
- Gfoupl Sp lights
_*~I. d)
- Gt9uP 5 Sp Iigl1J$:
_*.~fI"""
-@X,:oup 5SrUg'hts U11.a,)ll:g I1Zil 2.
,j!,v, e) e) . . . . " . . ._
IFNSpUrop{S) _*
- did hotstaJiM THEN perform the following for IiflBDperform the affected train(s):
_ (1) Reset ECCS. _ (2) Reset DIG load sequencer. _ (3) Manually start affected NS pump. _ (4) IF AT ANY TIME a BIO occurs, THEN restart SII
,..i,.
equipment previously on. _ S) M * *
- _6) MaiQt~jn,sealinj~ction
- 6) . . . . . . .. . tlpW.
7)~ne~gl?:e\H2 _ 7) 1IIIIlI
. . . . . .igQU¢rs,,;:
(RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/N5000/E-O EP/1/A/5000/E-0 8 of 61 DC~ Rev 36 DCS ACTION/EXPECTED ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (Continued) 8 )qJ§J?iit~!'J;QQgrgJor~fctl?J~rfo1itii,tli61 fdfloW\D9'~
_ 9) ~WHEN~~~rrllrj!;Jtes"ha~~elap~~g} THEN1~~tifY:iprqper'0~ sy§t~m op~ratidn,:.REFERTO En~1psLJci;:l7 i(V~~~;~§~Entl~~R~t?!ti(),Q.1)*
- b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this procedure, THEN perform Step 10.a.
V,erity prcrp~r C~~puWp~~ta:fl,l,$ a~i'1:9UoW~'; 11.IM~ti'f#'R;figRG;r~~iR;Iilm'J.lm~J~IR~;~~!ll:gI19WB:; 11.
- a. M~lor driv@ll CApuiup§~liON~? a. Perform the following for the affected train(s):
_ 1) Reset ECCS. _ 2) Reset D/G DIG load sequencer. _ 3) Manually start affected motor driven CA pump. _ 4) IF AT ANY TIME a B/O BIO occurs, THEN restart S/I SII equipment previously on. b.;3 $JG N/R1foYels 7~GR:E;ATERllmAN b. Ensure CA Pump #1 - RUNNING.
;~,1,~('o;
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O 90f61 9 of 61 DC~ Rev 36 DC:: ACTION/EXPECTED RESPONSE ACTIONIEXPECTED RESPONSE NOT OBTAINED
- 12. ~erifyallof tlJ.@JoU6)f,£ingS£lpum'i>s
- ON.: Perform the following for affected train{s):
BOP DOES a. R.eset ECCS. THIS PAGE
- b. Reset DIG load sequencer.
- c. Manually start affected pump.
- d. IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.
Perform the following for affected train{s):
- a. Reset ECCS.
- b. Reset DIG load sequencer.
- c. Manually start affected pump.
- d. IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.
14 14.* .V,er*.fy;a*
.. .' . 11***tJ**
. . n**.t [if.' ~.raT*n* d ,1:I."n*****'12* :R.:.:r*.. . um'" ..*5***.*.*'.
......... ".. ...PI P . . "J? Perform the following:
~PN,
- a. IF any Unit 2 RN pump is off, THEN manually start affected pump(s).
- b. IF any Unit 1 RN pump is off, THEN perform the following for affected train(s):
_ 1) Reset ECCS. _ 2) Reset DIG load sequencer. _ 3) Manually start affected pump. _ 4) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on. 15 . V~)Yi"".f!"'rh"Y*iyehlilaU6niSystems 1*.:JJtQt!.@Ji:.................... ........ .~..*......**..i<._.. oB~r.atiQ:mIi5ifQJr6W~; _
- REFI3R;~TO*~lilI~los(:IJ~:2{y(£tJma!!qn\
Sys!~rnVeriij~tio~ _ Ii 'NollP';Unmez:Q'
""'N').'i.. . . . . . . . Pefalor ......... to}erfol':
..J? ......OJ'. .*;
.g:{;!Q'Q~i.JrEl~~!l(QpP&l:liteg;Jg'it y~I)lJilqUQri
- ~~rifit§ljpQal
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP/1/A/5000/E-O 10 of 61 DC~ Rev 36 DCS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 16. i~erifYialrSfGpr~ssures:':;GRE~TE;R: Perform the following:
TIifAN .775 PSlg,~;
- a. Verify the following valves - CLOSED:
- All MSIVs
_
- All MSIV bypass valves
- All S/G PORVs.
- b. IF any valve is open, THEN:
_ 1) Manually initiate Main Steam Isolation. _ 2) IF any valve is still open, THEN manually close valve. RO 17. ll.~""IIB1IfJI1lIIIIDIL~ _ a. '1lJrB"l?f.III1B~ a. Manually start NV pump(s) and align valves.
- b. Perform the following:
_ 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN.
- 2) IF ND pump miniflow valve(s) cannot be opened, THEN perform the following for affected train(s):
_ a) Reset ECCS. _ b) Reset D/GDIG load sequencer. _ c) Stop ND pump. _ d) IF AT ANY TIME a B/O BIO occurs, THEN restart S/I SII equipment previously on. _ e) IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart the ND pump. _ 3) GO TO Step 18.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O 11 of 61 DC~ Rev 36 OCt ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 17. (Continued)
IBOP 1_ I _ c.c.~rp!:rftlpglINDJ~ATINC? FLOW.: c. Manually start NI pump{s) pump(s) and align valves.
- d. d. Perform the following:
_ 1) Ensure ND NO pump miniflow valve on operating ND NO pump{s) pump(s) - OPEN.
- 2) IF the NDNO pump miniflow valve(s) cannot be opened, THEN perform the following for affected train{s):
_ a) Reset ECCS. _ DIG load sequencer. b) Reset O/G _ c) Stop NDNO pump. _ d) IF AT ANY TIME a B/O BIO occurs, THEN restart S/I equipment previously on. _ e) IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart the ND NO pump. _ 3) GO TO Step 18. IBOP
- e. ;NRiiPumps'J.]NDI~~m:INGrlffi!;:;PWiJP. e. Manually start NO pump{s) and align ND pump(s) g:lli~GS"j valves.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11A15000/E-0 EP/1/A/5000/E-0 12 of 61 Rev 36 DC:: AGH,ONf:EXPECT'£D1{E~PONSE " _ ,:~p ~ialLW119J~IJCAftQW..:.{~REI\Tiij~JJ'i~J5J a. Perform the following:
~t50~PM:}
Isop _ 1) IF N/R level in all S/Gs is less than 11 % (29% ACC), THEN manually start CA pumps and ensure correct valve alignment.
- 2) IF N/R level in all S/Gs is less than 11 % (29% ACC) AND feed flow greater than 450 GPM cannot be established, THEN concurrently:
- Implement EP/11A15000/F-0 EP/1/A/5000/F-0 (Critical Safety Function Status Trees).
Trees) .
- GO TO EP/1/A/5000/FR-H.1 EP/11A15000/FR-H.1 (Response To Loss Of Secondary Heat Sink).
- b. Wt:lEN*<::lt,lf:}ast;Qi1eS/G+N/RI.~¥eli$;
tlr~1<::ltel}ltbsio;t~*9(,~.~r2~.?4.i~~Cljl~rH.E:N tnr9ttl§lfe~~Jlowrt9 n:'falEt§irl§,lIt;~/~ NfR Iglg'~.t;t~tW~~ni;1;1°~ (2.~%~~C,~iJ: and9'~'Phi< Isop IBOP
- 19. yeri.fyl~JI,gAi~91'\tiQn va{2es .. QPEN.
1,~~irf~lii@,~U9~I,ii§gl~tig[li~I~~§.HI~egM~ _ Manually open valve(s). valve{s). <="Is-=-o-=-p--'1 IBOP I 20 20.. Verify SII:~qlliRro~nt:~§ta(lJs:I~~~eg 'Of;i' "MgrtIYI§r,I,II:GIt;illw~oti!II~~tlll§;I~~I,@!;[IIi(gD: _ Manually align equipment. irooni.t.9r*ligtU,~:~pelilN'PRQrER'
;IWQ[lilg~iUglnD:@I[l@lll~,'le~me,gil
IUI~MWgHm~!
'AlIG,f!MENT~
NO"fE EIJGlg~I1r,e,'4(~PjleQ;lg:era~ti[;~::(C()Dt[91) ~11~JI.r~Dta.injQe,ffect9:rltil*S,u!;>~~queot:.
,pro~@.Qj;),t¢§~*Q!£tvig§.~Ut~rQ9!i!,g.N.Qjftl*mR~[~lYr.g~~.QQ1CQ[giJiQC;'!t:lC¢*
IRo 2"- IC<mtrpl?NC leXnpe'ra,lure. REFER;l\O EJj(:liP$,lJre4(~CT~roper~ture Con,trQ!p
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/A15000/E-O 13 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- a. IP~1~;~]p~~,$,1~ltei~J~$$lli1~h 2315 PSIG, THEN: '
_ /1) M?n.ual,!Y~losee¢r, P<qRV( s). Should already have isolated a PORV per AP/11 earlier. May :2,) IF~DY. P~i:,ppRlit~~~nI19t bei¢lqpect;.: not perfrom RNO even though THENcld~~Mls isgl?tiofilv:aJ)C~;~; PORV is still open, since it IS 3} IF any Pzr PORV cannot be closed 3) isolated. OR isolated, THEN perform the following: _ a) Energize H2 igniters. a} b) b} Dispatch operator to perform the following: _ (1) Secure all ice condenser air handling units. REFER TO Enclosure 13 (Securing All Ice Condenser Air Handling Units). _ (2) Place containment H2 analyzers in service. REFER TO OP/1 IAl6450!O 10 OP/1/A/6450/010 (Containment Hydrogen Control Systems). (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP 111A/5000/E-0 14 of 61 DC~ Rev 36 DCE AClI ON/EX PECPEO RES PON St\¥k
- 22. (Continued) c) IF both the following conditions exist,
- Containment pressure -
GREATER THAN 1 PSIG
- Containment pressure - HAS REMAINED LESS THAN 3 PSIG
_ THEN start one VX fan. REFER TO Enclosure 5 (VX Fan Manual Start). d) Concurrently:
- Implement EP/1/A15000/F-0 EP/1/A/5000/F-0 (Critical Safety Function Status Trees).
- GO TO EP/1/A15000/E-1 EP/1/A/5000/E-1 (Loss Of Reactor Or Secondary Coolant).
- b. IF Pzr pressure is less than 2260 PSIG, THEN:
IBOP _ 1) Manually close spray valve(s).
- 2) IF spray valve(s) cannot be closed, THEN:
_ a) Stop NC pumps 1A and 18. 1B. _ b) IF NC pressure continues to decrease, THEN stop third NC pump as required. Isop IBOP c.:Atle~sfI9r'f~; P~r'POg~'i~J;?I~JioJi!:X$lvell
- c. c. IF power is available, THEN open one OPi::N; Pzr PORV isolation valve unless it was closed to isolate an open Pzr PORV.
IRO I
- 23. \Ii~Dh~); :§*Y""cQQr,v')b"""
*. ',Fi.' N..C;' ""b': d" ',W .*".... .*Hi**,*""t "lltigl~fl~rgliii,iyl§,gg~li:lg'!I§,~~~iigii'!glll§niimll!li rQg'~,,§2~ ... gn;:~or&{~~1 tm\l;l~;YlJ9MOR;ft!lrPJtQJ;p.i$**on, THEN':'
T/~~l"'GR~~1FpR'lH~N ':O,~Ii~: NC Pumps may have been _ {~',6m§'urei:~Wt\l{3.11ump~-. qfF, previously tripped based on loss of support 'ii. if\.1aint~mse,atli;1j~]:~'tiAttflow.: equipment due to Sp
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O 15 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 ffl:@fiiW'i!m~"i;l,§~~llmliDIIIi"fi@i'!![Ql;i21!:i~§jI 24..'letifY;mainst~'timliQI~"(~;iQ,tij£J:a~;, IF pressure in any S/G is decreasing in I'--~-O--' llllp1&~~\f f6l1owsj) an uncontrolled manner OR any S/G is IRa depressurized, THEN perform the _ * ~11$/~lpfe§sut@:§lSTA§LE og following: JjJC~~,qlJ~G'
- a. IF both the following conditions exist,
*;tXI#JtSj~,~~~JRRES,$QJ3JZS'Q;
- Containment pressure - GREATER THAN 1 PSIG
- Containment pressure - HAS REMAINED LESS THAN 3 PSIG
_ THEN manually start one VX fan. REFER TO Enclosure 5 (VX Fan Manual Start).
- b. Concurrently:
- Implement EP/1/A/5000/F-O (Critical Safety Function Status Trees).
- GO TO EP/1/A/5000/E-2 (Faulted Steam Generator Isolation).
Isop IF any EMF trip 1 light is lit OR any S/G level is increasing in an uncontrolled manner, THEN concurrently:
- Implement EP/1/A/5000/F-O (Critical
_
- J~MF-33I~oi'rd~r:f~:~rrA:ir~j@GfQC Safety Function Status Trees)
Trees)..
~§i<f,laust)
- GO TO EP/1/A/5000/E-3 (Steam
_ * ':eME£2,§~(§t~~tnl!n~:,;1A) Generator Tube Rupture).
- 1, EN11?~g:r'{~t,~atnliJl~;i~Jn:
f~ 1EMJ~i2,?'lt~~~~,[:hlitj¢l~J
- 1BMF-29KSfearoliije1~,)J
_ .~! ~ll$KG;;!~&~lsd§1f.1?L",§;9R It:J:RE.t\,~lJ:&Gl;I~},Q~NIRQ4~R i,MAN~E:,Jil'
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/SOOO/E-O EP/1/Al5000/E-O 16 of 61 Rev 36 DCE DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26. Isop a. Vetify~tQ¢;tc)lJmlgN~f~u mptJb~rmfir a. P~rfottD :lhetcml{5,Wirig: barrr~~i:§lgfi;rn~::;::~ARK:'
~tlsri~~f{!1t}@LM,g,I'le>f6r4he af:f~ktea; Je' 1~~j;~',~/1,"N,qP A,T;t{;lFRM~l.1;l !t!!~;p utDt¥(~H:1~~lQSJ::D:
B~RR!E:R KqG,!;JTLET;:;P1J1L
- fli9Yi"" _ ,.;~ i1I\el~fJ4,A.(MC Pump<1ATher'm}
f3Q.n~tJl) _'. '**;~,,!,\P':6';Fl~~\"Nqp'112* TI;:H;~MAJ.,:* e..t\RRIE:ffl!,.~q 'G~4JjgET11-1!1Z~'Q' fiLOW;! _ !1i'rI1Kq~$64J3 (N,Gj=?ump 113 Themf fBatOllt) _ {~ il[~D-6;E:1,:~JilNGP[qtH*HE,~M.t\L: _ ':"i i1K<:>34:,~A {Nq:fE?l:Imp1 qTh~rm il3l\RRIERllSq\Q\QJ'Ifi::iE:!;:IIILQ BarQt!U fiJ!.OW". _ ~;; ~1KC;;4t~13 (N~:;E9mp1 r>Tf"\erm _ }4 ),1 ~D':6i,EJ4~"Nqm;:p1lti:!FRMAb iBar<:>tIt).
- 13l\RRI,ERiKC Qt:JTLET"P1!!LQ' fUi.9W'!,1 2) IF the valve for the affected NC pump will not close, THEN perform the following:
_ a) Trip all NC pumps. (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A1S000/E-O EP/1/A/SOOO/E-O 17 of 61 Rev 36 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 26. (Continued) b) Perform the following:
_ (1) Dispatch operator with radio to standby at 1KC-42SA (NC Pumps Ret Hdr Cont 1501) (AB-S88, Cant Isol) GG-S2, Rm 419) (Ladder needed). _ (2) Close 1KC-42SA (NC Pumps Ret Hdr Cont Cant Isol) from Control Room. _ (3) IF 1KC-42SA (NC Pumps Ret Hdr Cont Cant Isol) will not close completely from Control Room, THEN have operator locally close 1KC-42SA (NC Pumps Ret Hdr Cont Cant Isol) (AB-S88, GG-S2, Rm 419). _ (4) WHEN 1KC-42SA (NC Pumps Ret Hdr Cant 1501) Cont Isol) has been closed, THEN close 1KC-424B (NC Pumps Ret Hdr Cant Cont Isol). _ (S) WHEN 1KC-42SA (NC Pumps Ret Hdr Cant Cont Isol) is closed, THEN notify the dispatched operator to return. (6) Close the following valves:
- 1KC-338B (NC Pumps Sup Hdr Cont Cant Isol)
- 1KC-430A (Rx Bldg Drn Cant Isol)
Hdr Cont
- 1KC-429B (Rx Bldg Drn Hdr Cont Cant Isol).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP/1/A/SOOO/E-0 18of61 18 of 61 Rev 36 DC~ ACTIONIEXPECTED ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 26. (Continued)
- b. VefifS1;NC sx~t~hlU§t{lli1~ct:MJfPllo\\§: b };~: PefformJtlJ:~&f611()wiJ~g:
- C601§inm~Q!E,QIessfiit~- LE$~ TH&N _ 1) ;~:mi!igi.~~lI1IT!~1;1!!~fli;jlilr~I!1 1)EnFlrgii,¥;H2igtm~rs.
- 1. e~;lb?,~~
2)~§~mm~~~~m:~lm~m~~~i~*
- 2) Dispatch1Qperal9r!()'p~1;fQfttUhe
_ .* IF normal off-site power is available, Jol.l~wingt THEN verifY verify containment pressure less than 0.3 PSIG. _ a) ~~gue~:~ll iq? cqri9~H§~r ~ir t;!§pdlinglWlil$1 :REFER TOl
- Containment high range EMFs - t,titi2Iq$tJrEF13 (Sepuril1g All. Ice LESS THAN 3 RlHR: .~~ild~W~~D,&jCtt:~ta!ldljng*l}**J;Uts ):
_ . 1EMF-53A (Containment Trn A) _ b) "ti;I~¢e'coD~airitn~ht H2 <;iMlyzer§ _ . 1EMF-538 EMF-S38 (Containment Trn 8). {mi;§?r\?i,§~~REF,6RTO lPf:?11/M'~~:gQl~i~:t~qQtaif;\lDent*
- Containment EMF trip 1 lights- 'ii,),Y Jog?~;.:on r;SI ;, Yst*
H(r"';~X31'1!6 ems,::
"i\'
DARK:
- 3) IF both the following conditions
- 1EMF-38 (Containment exist, Particulate)
- 1EMF-39 (Containment Gas)
- Containment pressure -
GREATER THAN 1 PSIG
* ~pntainri1~[itstImplev&l;;;l~'1l~I3[E:
- Containment pressure - HAS REMAINED LESS THAN 3 PSIG
_ THEN manually start one VX fan. REFER TO Enclosure S 5 (VX Fan Manual Start). 4 ) QQ'i~\1trel"lf!~~)
* ~r;lJrplerQ~Df'Eel~ilm~QQQi=~,O
( CritiQC?rSaf~t!tf:Lln~tiQtl~fatug; Tm¢§l*
- GOTO EP/1 Im5QOOI!=~ 1 {Loss Qf~~;~ptQtPr'SepqI199r;y:
i~P()[§Dt}~j
- 27. Verify 511 termination criteria as follows:
- a. NC subcooling based on core exit TICs a. GO TO Step 28.
- GREATER THAN OaF.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 32 of 61 Enclosure 1 - Page 1 of 1 DC~ Rev 36 DC:: Foldout Page
- 1. IF any S/G(s) suspected ruptured, THEN perform the following:
- WHEN the following conditions met:
- Total CA flow - GREATER THAN 450 GPM AND
- All intact S/G(s) S/G{s) N/R level- level - GREATER THAN 11%{29% 11 %{29% ACC)
THEN throttle feed flow to ruptured S/G(s) S/G{s) to maintain ruptured S/G(s) S/G{s) N/R level between 11 %(29% ACC) and 39%.
- 2. NC Pump Trip Criteria:
- IF the following conditions are satisfied, THEN trip all NC pumps while maintaining seal injection flow:
- At least one NVor NV or NI pump - ON
- NC subcooling based on core exit TICs - LESS THAN OR EQUAL TO O°F. OaF.
- 3. CA Suction Source Switchover Criteria:
- IF either of the following annunciators are lit, THEN REFER TO AP/1/A15S001006 AP/1/A155001006 (Loss of S/G Feedwater):
1AD-S, H/4 "CACST LO LEVEL"
- 1AD-5, OR
- 1AD-8, 8/1 B/1 "UST LO LEVEL".
!l,> P9~j!I~t(:Gritf(ri~fgt:*1 NV.-2Q26**an*gi~~~v~gP~~[IN~{11?0Y.lliRB~8r.~R.ecir~J§ol):.
'~'ilEi:NC;
~"'.'h P.
.* U.,
. 'ressure
..... ,.. ....is;lesstha'ilil150mPSTGiANDNViSlJ:.flow*
,.. ...... ath
. . """'*.'" A.,,,.,,,. , _..**. ,.,*.c.c"u.*... .. P.... .'is alig..
........ 'oed THENGI.(j)'se 1 _._
.. _ ~".,."". 1Nv.::202B\
'. h." ... .
'atj(f1*~y:~gQ~A.;
~~"JFNC
~,.".P "r'essurelis/reate~thaJj:2:000PSIG
..d.* %, . g v."" £;;' ....... M . ..*.*.
THEN 0 P'enT~1NV@Y>;I)\~Ba7d
' , - - ... ",,* ...iT"iiY=*. ,.*.*. ..JJ.,1NV-2,@'3A.
5. S. Cold Leg Recirc Switchover Criterion:
- IF FWST level decreases to 37% (1AD-9, D/8 "FWST 2/4 LO LEVEL" lit), AND an S/I SII has occurred, THEN GO TO EP/1/A15000/ES-1.3 EP/1/A1S000/ES-1.3 (Transfer To Cold Leg Recirculation).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O 330f61 33 of 61 Enclosure 2 - Page 1 of 7 DC~ Rev 36 DeE Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED BOP DOES THIS ENCLOSU IBOP ENCLOSURE
@:; 'jI E?t~fY bij;eX(rain'ljfitheJgllowing'j a. Perform the following:
eQl1ljpmelitjs.in op.~ratiQrr: _ 1) Shift operating VCIYC trains.
* ';y,;C,chiUe:ti GR';AHU~~J' C,B:A~HgJ,E1 CB:A'PfH~£)
REFER TO Enclosure 6 (Shifting Operating VCIYC Train).
- 2) IF no train can be properly aligned, THEN dispatch operator and IAE/Maintenance to restore at least one train of VCIYC. REFER TO the following:
- OP/OIAl64501011 OP/O/A16450/011 (Control Room Ventilation/Chilled Water Area Ventiiation/Chilied System)
- EM/O/A15200/001 EM/OIAl52001001 (Troubleshooting Cause For Improper Operation of VCIYC System).
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/SOOO/E-O EP/1/A/5000/E-O 34 of 61 Enclosure 2 - Page 2 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. (Continued) b.~er4fy
- b. thefoUgyving;;glarrrl's - DJ\~K; b. IF chlorine odor is detected in the Control Room, THEN perform the
_ *~*AD"J8J IN,8,7;1Jf)!,tn'1~I~mAl(fjj~fili following based on the status of given Cl-:tt,.~~I.~§I1:AJ: alarms:
- 1J\IM::rWr~I,~J\il1JNJ::r:"'Ii~!I\JTAt}e:AIJ" 1) IF detectors on both unit intakes are CIrfJ,109 iINB'11BY
,.,i\,. ,~;i:'~~~",J.4~""".,,, /,' ',. ,:-:;t;,,;
in alarm, THEN:
* .1ADlJl~1 pr8~;~N[l7~~N]A~EHJ a) Ensure the following VC intake Cf:lt;~*~INE~'* dampers - CLOSED:
_ *j1 AQ:::,,\a,:n~El"I2INIT2IN:r:A~EtH _ .* 1VC-S8 1VC-58 (CRA Filt Inlet) iPti!U,~.RINE4Br* _ .* 1VC-6A (CRA Filt Inlet) _
- 2VC-S8 2VC-58 (CRA Filt Inlet)
_ .* 2VC-6A (CRA Filt Inlet). _ b) GO TO Step 1.d.
- 2) IF Unit 1 intake HI chlorine detector(s) in alarm, THEN:
a) Ensure the following VC dampers - CLOSED: _ . 1VC-58 1VC-S8 (CRA Filt Inlet) _ . 1VC-6A (CRA Filt Inlet). b) Ensure the following dampers - OPEN: _ . 2VC-58 2VC-S8 (CRA Filt Inlet) _ . 2VC-6A (CRA Filt Inlet). _ c) GO TO Step 1.d. (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/N5000/E-O EPI1IN5000/E-O 35 of 61 Enclosure 2 - Page 3 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. (Continued)
- 3) IF Unit 2 intake Hi chlorine detector(s) in alarm, THEN:
a) Ensure the following VC dampers - CLOSED: _ . 2VC-58 (CRA Filt Inlet) _ .* 2VC-6A (CRA Filt Inlet). b) Ensure the following dampers-OPEN: _ . 1VC-58 (CRA Filt Inlet) _ . 1VC-6A (CRA Filt Inlet). _ c) GO TO Step 1.d. c.J;:n~:!ltelti~f()lJqWing ve ;;g,§J;ljper~:!;~' Q:8~t)I: _ ;;'41 VC-58 (C~fHtlnlet) _ e 1VC:'6AJC~
- =i--i>i'i-i J iMi' i FHtlnlet)
"i@i'i"'i*ilalll"
_ * *~VQ:5E3ICRAfji.lliJIlIet)
-_ *'4V Ce9A{CRA FiI!~1il1!eth d~y filll)1P"f_"I._~
~eR~et1~J~P.1 qfthis/ehQl§,$ur~Crntii.
ri!Qtifi~d'5y $ta:ti9jjtnanag~'Ctlent as folloWs:. _ *IIBIJJItIIIleI. . . .+B _ ir AnY timelYCIYCrelalgaannu!,)pjators
~,
6n1.!~p; 118'actg.~l~.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/Al5000/E-O 36 of 61 Enclosure 2 - Page 4 of 7 Rev 36 DCE DC!: Ventilation System Verification ACTION/EXPECTED RfSPONSE RESPONSE NOT OBTAINED
- 2. ~p;n$ur~~prog~r:?Y'A Syst~n1iOp~f:~n'Qn,,~s o
f9 U WS:
*"IfDJIIIIJ.....
.~n~ure. the. follo~il'\@rf~ms.~'.'~fF:
':11§n~t1f~:¥~~$ystetn!J!JJ~;!IJ~jll~erVic~ ::(s]
*eIl!allllWRIIIIIaII."!Mi lIIBJa fQIJQwsl*
.1A;~f':PH12 & tQ.(VA filtef;:~'~!RqM P9tnP.~fr;~l ".CLOSE:!:}
- . 1AI3f::~t~~ 20(Vt. f'J,I~erI3<I3i~?I?:~~~l Q~:uli'p~fSI';" CEQSSliU
- '~:, EQsqt~'lt;l,l3~followingsf~ns17;QN:
*8IBII:lItllllBl.
_ * ...-p, W '1V1II
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-0 EP/1/A/5000/E-0 37 of 61 Enclosure 2 - Page 5 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 .~EffjijM{Br6'p~t'lY~SY~le,lndR,eratiQh;as
!f9IJ~W~~
at VE;f~J5$'; Q,ti:/:' a. Manually start fan{s}. fan(s).
- b. Annt!l!:!::;;:Rt~§~l~Ite1':1?t;~fV£;gI:-1b b. Perform the following:
,1341 ti\l!1W.9ANm,,.1.8JIN. 'Wf!+l 1
1}) IF annulus pressure is more positive than -1.4 in. WC, THEN: a) a} Verify flow indicated on the following indications:
* "VE 1A FLOW TO STACK"
* "VE 18 FLOW TO STACK".
b} IF flow is not indicated, THEN b) dispatch operator to verify status of the following dampers based on their local indication or their operating piston rods being extended 4" to 6":
- 1AVS-D-2 (VE A Trn Recirc Damp) (AB-603, JJ-51 , Rm 500) - CLOSED
- 1AVS-D-7 1AVS-D-7 (VE B Trn Recirc Damp) (AB-603, HH-52, Rm 500) - CLOSED
- 1AVS-D-3 (VE A Trn Exh Damp) (AB-603, JJ-52, JJ-S2, Rm 500) - OPEN
- 1AVS-D-8 (VE B Trn Exh Damp) (AB-603, HH-52, Rm 500) - OPEN.
_ c) c} Consult plant engineering staff and notify IAE/Maintenance to troubleshoot and repair. REFER EM/1/A152001002 TO EM/1/A/5200/002 (Troubleshooting Cause For VE HilLo Pressure). System Hillo _ d} GO TO Step 3.c. d) (RNO continued on next page)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/N5000/E-O EP/1/A/5000/E-O 38 of 61 Enclosure 2 - Page 6 of 7 Rev 36 DC~ Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued)
- 2) IF annulus pressure is more negative than -1.8 in. WC, THEN:
_ a) Determine which VE train indicates highest discharge flow to stack. _ b) Within 2 hours, ensure VE train that indicates highest discharge flow to stack is secured. _ c) Consult plant engineering staff and notify IAE/Maintenance to troubleshoot and repair. REFER TO EM/1/A/5200/002 EM/1/N5200/002 (Troubleshooting Cause For VE System Hillo Pressure).
- c. tRep;~atSf@l:r3.b eve'w:3Q~tlil1DLit~§J!lflltil, ngl{ti~cl.QYl~J~tion(tn~riaggmeht.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/11INSOOO/E-O EP/1 39 of 61 Enclosure 2 - Page 7 of 7 DC~ Rev 36 DeS Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. Record time ventilation systems are verified on following table:
TIME SYSTEM INITIALS eve, (V(, VE)
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/N5000/E-O 41 of 61 Enclosure 4 - Page 1 of 4 Rev 36 DCl: NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
,J~,(;!IjQtm ttiEijic:>lIoViiJ;l9;;
- ~.; Q$eitiCllJ~,~olasllt01del~nTiif:ie~gJ IRO DOES THIS ENCLOSURE t¢mJt~ral(jr~/as. req]lirea,';ir sO~s~qQ~ht step§~
- 2. Use NC T-Avg to determine NC temperature as required in subsequent steps.
- 3. IF AT ANY TIME NC pumps are tripped, THEN use NC T -Colds to determine NC T-Colds temperature as required in subsequent steps steps..
*. ' iNC. teEip~rar!;li(§i?~,J;'A§~1E~~J-I;$PJ TI-iA~}PRE~t:JAL :m~;\9,§G;~~§i P~j
** ltil~i~'mrpe(?Jl"J~ittrREtilIdING:,:rO 557:Fi
- 5. Continue to monitor NC temperature.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/N5000/E-O 42 of 61 Enclosure 4 - Page 2 of 4 Rev 36 DC~ NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 6. Do not continue in this enclosure until one of the following occurs:
- NC temperature - GREATER THAN 55rF AND INCREASING IN AN UNCONTROLLED MANNER.
OR
- NC temperature - GREATER THAN 55rF AND STABLE.
OR
- NC temperature - LESS THAN 557°F AND DECREASING IN AN 55rF UNCONTROLLED MANNER.
7.~cetjTh"it'i{C tertJper~'9re*- LE:SS THlSt'f Perform the following: {§~~Z'gll] A.'N [LI:)~CRijlSS ING,}'
- a. IF NC temperature is greater than 55rF AND increasing, THEN stabilize NC temperature at 55rF 557°F as follows:
- 1) IF steam dumps are available, THEN use steam dumps.
- 2) IF steam dumps are not available, THEN use S/G PORVs.
- b. IF the following conditions exist:
- NC temperature is greater than 55rF 557°F and stable
- Time and manpower is available, THEN stabilize NC temperature at 55rF as follows:
- 1) IF steam dumps are available, THEN use steam dumps.
- 2) IF steam dumps are not available, THEN use S/G PORVs.
- c. GO TO Step 9.
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A15000/E-O EP/1/A/5000/E-O 43 of 61 430f61 Enclosure 4 - Page 3 of 4 Rev 36 DC~ NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. t~tt~ffipf'to1~~9P ttr~,;~~ 1:;6oldoytn\~~
f9 I10yt$: a.,I=f\$ure atI:S!§l!nldumpSd: CLOSEO).~ b.BJisyce.qll §/GJ;QJ~Vs -iCg;OSED, b. IF any S/G PORV cannot be closed, THEN close its isolation valve. cc.. g.. iEQ:;>ur~ ~~C?jQIQ~g~l!rt;is.
.....,.1IIMIi (jIO~@,~tQ~ :fbUqWii1gya,I~t:i§~.
- **;1.
-1,l?M:Hl\
1it-w CN~ h"",
~ _~
is61~led.
;* . .(S/;G{?I~,Gt!Lt!qt~~ldwn
"'Ll w~~
~. :;1jpMt?§J? (SfQ}1B;:i:~mHClr1lEUowh
-IU'": ,
..*....,*=
ifiI C{;j/;)}
.., """"~
_I ..I_l".
.' 01~§Nb-i'1~l~*(§(C?:'1'Qt~Jlt::;!zId j'*;Bldwp*
n1i!J~:
- ~ 1 SM..?48~§{Q:~D OtltHdr BldWn}
CN).
~lDepressI~.r1d, hglg;~\~{;j/;:BE!i@RE~l?EAfr
- P[}tJ" "OI;lQ~;gtRuslh1itiltton}(i~MC-3) t~
.Q!g~~: 'l1;eJfqllbWi.n'g*v~We~:
~t:1~M-41,{Qtop Vlv #1LB'efor~;,$eat Drn)
.1 §M~4 !($tog. \{'~ #21fiH:}fo~~;~eat Drn~;
- l~ ';1l?M"'43 ,(§lop'VJv #3.,eefore:$eat.
Ofn)
'd . 7L.*.sr"*
!. ,1:SM:'A2:(' ::X1Iv;~71 Hlor":WS'at
,9P:%~..;p:;m- e", EL.e Qrn) ..
CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO. EP/1/A/5000/E-O EP/1/Al5000/E-O 44 of 61 44of61 Enclosure 4 - Page 4 of 4 Rev 36 DC~ NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (Continued)
- f. Y~rif~~Nt;;~eba:lqpWrjv:S[(JPPE~! f. IF copld:QWl;!)}cc>ntinpes;THENtbrottle feed Jlowrft§:ifollow~~
- 1) 'IF§IG.N(R1i!,~ve!iii§stes~tth~!l1;1,m%'
(2~i~AC~>>!'i'!a':9ni§1~'s~'THEN~
*thto~l~.J~g,ilQW't~I~J;f:tieve.l/;l~
i;!gllg)N(r'j.9?
":l' 'Miffirijlzgl§gl~Jg~\wi!l
'
- lN1~i'\ltgih JqJ§Lfe.e."~t:!I()W'lgrEgat~t
,thab.i2l-50}@~tM~
2)WHEN,i;N/Rle.y?ti.si:gt1~fite'fth,anj t~MJ%;(?J3%,l\Gr;}ifi'~Ie:~§i bDe':$IG;
'iJiHENlthrottlefeed fIB\W:fllrrther to
\e:Ql}i~~~:.the:fPUP~I:r;t~.i)~" C.'0 ,
l'}iN!lttjwi~~c;bblciow
- iN!t;:iiht9Jriaf le~$f oQfJS/~tf;\lZ,R
'I~vel greateftnan1~'%'
(29%ACC);
~). '1FX9Q9fqQWQ)§gJilllhges,'Tfi ENc!Q§eJ i:tb;~..t9IIQwjQg)~}llg~§::
i~i AIlJiiMSf'1:s% c* 'd ,,~.:t .. ,'., ,,~h~' it .AIIMSI~Zbyp<ifss valyesi'
- 9. ~,<?QJil1ue.:tope[fo,th~ aeti().n,~,of ttlJl~
fi~,!it~Q:Y~:!ltg:R,glifgnmltt!~~§tign,$ji:91:itt!,'i~: j~D~lg§1Qlg;iI§'i!t~lglfg(;l:'tg,;I,d~glglllgii:igj!:lf'
- e,tt~I()s:tJre.as;req41t~d tq'f,@.nsote';iolJ~;<?,f itt!,gl~f9:IU1!{id'g~:,
;tij~1f()1J6wiilg
~\ NCtem~e't'at!iir~Y;;'Sl~BLE1iiAT
~"'A.' P,'Si[';Uc cc >>-~"'~',';M:.P. ,,:j,,/ / C AwK*,**c _
Lffi6S
., ..~~ A" ,
iill!lfI~N:Q~U;qW~!lKQ;,5'57:i5*,
,QR i~iN~terhper~tLlre.;,;[REI}!!lING;D:P 'ti.571~E"
RESPONSE TO IMMINENT PRESSURIZED THERMAL CNS PAGE NO. SHOCK CONDITION EP/1/A15000/FR-P EP/1 .1
/ A/5000/FR-P.1 1 of 55 Rev 18 DC~
A. Purpose This procedure provides actions to avoid, or limit, thermal shock or pressurized thermal shock to the reactor pressure vessel, or overpressure conditions at low temperature. B. Symptoms or Entry Conditions This procedure is entered from EP/1/AlSOOO/F-O EP/1/A15000/F-O (Critical Safety Function Status Trees) (REACTOR COOLANT INTEGRITY) on a RED or either ORANGE condition. May be entered due to REO RED or ORANGE path due to Tcolds falling after LOCA and cold injection. Path IS valid, but procedure recognizes a LOCA in step one (based on NO flow to CLs) and kicks back to procedure and step in effect.
RESPONSE TO IMMINENT PRESSURIZED THERMAL CNS PAGE NO. SHOCK CONDITION EP/1/Al5000/FR-P.1 EP/1 /A/5000/FR-P.1 2of55 DC~ Rev 18 DC:: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions NDf.l¢lw~pC:-Legsi§ligrgat~tlhah IF::iN~!:([QWlQi'j!~zL.~g§i~lg"t~~:fj~tlill:i~'ii! _ IF 6I~. GPM.THENRETURNb]:O{PLOCEil~J.lre i§2l5;*lieM;"iI'lE:N;RE'URti.lI(mCll)1~1?;tQA~!~mt@;
!~n~li§fgf.f::'n.~f'!'~"§l; antf.step'.in effect;
- 2. Monitor Enclosure 1 (Foldout Page).
- 3. Verify all NC i-Colds T-Colds - SiABLE STABLE OR Attempt to stop NC System cool down as cooldown INCREASING. follows:
- a. Ensure all S/G PORVs - CLOSED.
- b. IF any S/G PORV cannot be closed, TI'IEN THEN close its isolation valve.
- c. Ensure all steam dump valves -
CLOSED.
- d. IF ND is in RHR mode, il'lEN THEN stop any cooldown from ND System.
- e. Identify faulted S/G(s) as follows:
_
- Any S/G pressure - DECREASING IN AN UNCONTROLLED MANNER OR
_
- Any S/G - DEPRESSURIZED.
(RNO continued on next page)
Duke Energy Procedure No. Catawba Nuclear Station EP/I/A/5000/E-1 Loss of Reactor or Secondary Coolant Revision No. 023 Electronic Reference No. CP0094CP Continuous Use PERFORMANCE I
- UNCONTROLLEDFORPruNT**********
(ISSUED) - PDF Format At some point in this procedure, fWST level will drop to 37% and they IAt will transition to ES-1.3
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A15000/E-1 EP/1/N5000/E-1 1 of 29 Revision 23 A. Purpose This procedure provides actions to recover from a loss of reactor or secondary coolant. B. Symptoms or Entry Conditions This procedure is entered from:
- a. EP/1/A15000/E-O EP/1/A15000/FR-H.1 EP/1/N5000/E-O (Reactor Trip Or Safety Injection), Step 22, and EP/1/N5000/FR-H.1 EP/1/A15000/FR-H.1 (Response To Loss Of Secondary Heat Sink), Step 41 and EP/1/N5000/FR-H.1 (Response To Loss Of Secondary Heat Sink), Step 43 when a Pzr PORV is stuck open and its isolation valve cannot be closed.
EP/1/A15000/E-O (Reactor Trip Or Safety Injection), Step 26, with any of the following
- b. EP/1/N5000/E-O symptoms: high containment radiation, high containment pressure, or high containment recirculation sump level.
EP/1/A15000/E-O (Reactor Trip Or Safety Injection), Step 36, EP/1/N5000/ECA-2.1
- c. EP/1/N5000/E-O EP/1/A15000/ECA-2.1 (Uncontrolled Depressurization Of All Steam Generators), Step 8 and EP/1/N5000/FR-H.1 EP/1/A15000/FR-H.1 (Response To Loss Of Secondary Heat Sink), Step 46, when NC pressure is less than the shutoff head pressure of the NOND pumps.
EP/1/A15000/ES-1.1 (Safety Injection Termination), Step 14 and EP/1/N5000/ES-1.1
- d. EP/1/N5000/ES-1.1 EP/1/A15000/ES-1.1 (Safety Injection Termination), Step 33, and EP/1/A15000/FR-1.2 EP/1/N5000/FR-1.2 (Response To Low Pressurizer Level), Step 8, if S/I has to be reinitiated.
EP/1/A15000/E-2 (Faulted Steam Generator Isolation), Step 12, after identification and
- e. EP/1/N5000/E-2 isolation of a faulted S/G.
- f. EP/1/A15000/ECA-O.2 (Loss Of All AC Power Recovery With S/I EP/1/N5000/ECA-O.2 SII Required), Step 15, after normal injection mode conditions are established.
EP/1/A15000/ECA-1.2 (LOCA Outside Containment), Step 3, when a LOCA outside
- g. EP/1/N5000/ECA-1.2 containment is isolated.
EP/1/A15000/FR-C.1 (Response To
- h. EP/1/N5000/FR-C.1 Inadequate Core Cooling), Step 21 and EP/1/N5000/FR-C.1 EP/1/A15000/FR-C.1 (Response To Inadequate Core Cooling), Step 31, and EP/1/A15000/FR-C.2 (Response To EP/1/N5000/FR-C.2 Degraded Core Cooling), Step 24, after core cooling has been established.
- i. EP/1/A15000/FR-H.1 (Response To Loss Of Secondary Heat Sink), Step 39, after EP/1/N5000/FR-H.1 secondary heat sink has been re-established and all Pzr PORVs are closed.
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A/5000/E-1 EP/1 1A/5000/E-1 20f29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions 1.
- 2. VerifYlm~iQ. s~~~m!iQ(f~'~t~!iii!gQl~~' IF pressure in any S/G is decreasing in fpllows.;!) an uncontrolled manner OR any S/G is depressurized, THEN:
_ . ~fI S/Gt~c~~~llt~I$T~ILE~R1 INPR~~SlNJ3 a. IF any faulted S/G{s) feedlines OR steamlines are not isolated, THEN: _ .~IIS/d§:jlE1gJ;§~t1Rl~.~~. _ 1) IF EP/1/A/5000/E-2 (Faulted Steam Generator Isolation) has been performed for the affected S/G, THEN GO TO Step 2 RNO b. _ 2) GO TO EP/1/A/5000/E-2 (Faulted Steam Generator Isolation).
- b. IF the affected S/G(s) is faulted outside containment, THEN request RP to perform the following:
_ 1) Monitor the area of the steam fault for radiation. _ 2) Notify the control room of any abnormal radiation conditions.
- 3. ,Qontrql.*iQfattf:§Z~JJ~yel§1i~~!Q'lgW§:;
- a. "Xl .'*N/RI~gert a. Maintain total feed flow greater than a*~jjgR.1THA .. 450 GPM until at least one intact S/G N/R level is greater than 11 %
NIR (29% ACC).
- b. lntaqf b. IF N/R level any S/G continues to increase in an uncontrolled manner, THEN GO TO EP/1/A/5000/E-3 (Steam Generator Tube Rupture).
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. E P/1/A/5000/E-1 EP/1/A15000/E-1 30f29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
,X(~ti.... .~concf~fY;f~~.(~!iQI1/i§l:!.~r.;n~l~'I~ll
,folio' a, ..* EnsQL~lm,~{f6n@~T:ng $jghals;~rlRESET~1'
_ ~.]}.;.l?Il~~IJ\ 'c6nt~lqm~llt[s()laU~l)s _12J}:;¢.A.~y~fe.m vaIV~,{ii;;()r1tr*~U _ ~Jfi~C NC1~nt:Jr\A~§t$lg~1!$;' _'f)'~f:~~H£l'h aIlSJ~s,fOr:g~~QJi~ll&s~rnpljd.g~
*~r});fl~.Ii9rmat!~~stoQ~.ciftti~~foIlQ~IIQg.~;
_ ;~\11IptifY**S!1s~~j~t~l@f*s*~.rillJl~4~J1{§r<$§ tQracbv,ty~t
'~:lil?
l~lfNbnf"'p toJri$kall calibncpji.lmns~
.. 'fO yj:
.lCj{ V~rl{~zt~~ifQJIQ~i.Og;,~fvrF?]trip~~lIigms};fi EP/1/A15000/E-3 (Steam
- d. GO TO EP/1/A/5000/E-3 DAg;K: Generator Tube Rupture) .
- ** (~EMF:i.33.>(Condenser~ff;E'
~tigm:§ID ........... ?EL J~ctorl
_ . 1ij~fe:ig6{~i~~mllhe;;iA) _ \;:!j(~tgMi=~2~.;~;S:t~aml1:'li~:1.§:~; _ !ltr1~MR)~g?"(SteX3{miine1l~)\ _ ."1 ijMgc:~~,*(~~1:m!in.Ei§J:D);i
- e. e. Perform the following:
_ 1) Notify station management to evaluate S/G{s) activity results. _ 2) IF S/G(s) activity indicate a SGTR, THEN GO TO EP/1/A15000/E-3 EP/1/A/5000/E-3 (Steam Generator Tube Rupture).
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A/5000/E-1 40f29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5'~~~~;!~~f~~vs,:gdli!21'~~iboV~~IV~: 5.
- a. \1,i~ert\g,~1'IPif;;~ORV£I§91atiohk&alv~§,4" a. Dispatch operator to restore power to
'~~~JL~Bl!i!=. valve{s):
affected Pzr PORV isolation valve{s}:
- 1EMXD-F02C (PORV Isol Motor (1 NC31 B)) (AB-560, BB-50, Rm 372)
- 1EMXC-F03C (Pressurizer Power Operated Relief Isol. Valve 1NC33A)
(AB-577, BB-50, Rm 496)
- 1EMXD-F05A (PORV Isol 1501 Motor (1 NC35B))
NC35B)} (AB-560, BB-50, Rm 372).
- b. b.
b.lF- ~~r)pt:~§rtt~liS,ii1es~th~b:~3t5~~~IQ1 THEN:: _ 1")*: 'Ma'f~~:ny~IQse R~I:F;qJ~i{s).: _ :12) IF~ny pir POR~icanQ9t:beclos'~(n THENclpseitsisolatiQ:O\"alv~.
- c. c. Open one Pzr PORV isolation valve unless it was closed to isolate an open Pzr PORV.
d.
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A15000/E-1 EP/1/A/5000/E-1 50f29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6. a.
- b. Verify secondary heat sink as follows: 6.f.
- b. GO TO Step 6.f.
- N/R level in at least one intact S/G -
GREATER THAN 11% 11 % (29% ACC) OR
- Total feed flow to all intact S/Gs-GREATER THAN 450 GPM.
- c. NC pressure - STABLE OR c. GO TO Step 6.f.
INCREASING.
- d. Pzr level - GREATER THAN 11 % d. Perform the following:
(20% ACC). _1)1) IF NC pressure is increasing AND normal Pzr spray is available, THEN attempt to stabilize NC pressure using normal Pzr spray. _ 2) GO TO Step 6.f.
- e. GO TO EP/1/A15000/ES-1.1 EP/1/A/5000/ES-1.1 (Safety Injection Termination).
- f. MonttorSllterminat[oFFCr1le'riI3Y<.REFE*Ri
~ti~t~§c~re*2{§/'Termlnatiob<
_ g. IF AT ANY TIME SII te~mination criteria S/I ter,mination is met while in this procedure, THEN RETURN TO Step 6. 7.
- a. a. Perform the following:
_ 1) IF AT ANY TIME an NS pump(s) starts while in this procedure, THEN perform Step 7. _ 2) GO TO Step 8.
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A15000/E-1 EP/1/A/5000/E-1 6of29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
ISOp I b*Verlf~.J1:~fQfl9WIogv~i\j~!;~QP~mi!
- b. b. Perform the following:
_ * ~1.f:rif!"~1~(~:tJlPurrtP,,;1Al~$~£~~;fPgm: _ 1) IF NS pump(s) have previously f~W~n} been stopped more than once, THEN GO TO Step 8. _ ~;il'1FW /5$I3.(NQ>f,?ump'1 BS'~9t* ff9:1D 5WSn> _ 2) WHEN containment pressure is less than 1 PSIG, THEN perform Steps 7.e through 7.h. _ 3) GO TO Step 8.
- c. Coni!aj~men~JRres~fe - G"Ess>rHAN c. .Ped()tm~f1~:ffoll()Wiflg:
2A~~fG; _ .1) .* **\IIIHE~'~bntainmei1t'l~tessur~i~les§
;1bang.4<*P~I.~iTHEr-.liperfqnn}
;$1¢p~t?
_ ?~I!lGO:Tb~~'~i@J
- d. Verify operating NS pump{s) - HAVE d. IF NS pump{s) has previously been REMAINED RUNNING SINCE INITIAL stopped, THEN GO TO Step 8.
PHASE B SIGNAL.
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A/5000/E-1 70f29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 7. (Continued)
- e. Ensure SII - RESET:
_ 1) ECCS. 1) Perform the following: _ a) IF either reactor trip breaker is closed, THEN dispatch operator to open Unit 1 reactor trip breakers. _ b) WHEN trip breakers open, THEN reset ECCS. _ 2) DIG load sequencers. 2) Dispatch operator to open the affected sequencer(s) control power breaker:
- 1EDE-F01 F (Diesel Generator Load Sequencer Panel 1DGLSA)
(AB-577, BB-46, Rm 496)
- 1EDF-F01 F (Diesel Generator Load Sequencer Panel 1DGLSB)
(AB-560, BB-46, Rm 372). _ 3) IF AT ANY TIME a B/O occurs, THEN restart SII equipment previously on.
- f. Reset NS.
_ g. Stop NS pumps.
- h. Close the following valves:
- 1NS-29A (NS Spray Hdr 1 A Cont 1A Isol)
- 1NS-32A (NS Spray Hdr 1A Cont Isol)
- 1NS-1SB (NS Spray Hdr 1B Cont Isol)
- 1NS-12B 1NS-12B (NS Spray Hdr 1B 1B Cont Isol).
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A/5000/E-1 EP/11A15000/E-1 80f29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8. a.
- b. NC pressure - STABLE OR b. GO TO Step 9.
INCREASING.
- c. At least one ND pump - ON. c. GO TO Step 8.h.
- d. ND pumps suction - ALIGNED TO d. GO TO Step 9.
FWST.
- e. Verify FWST level- GREATER THAN e. Perform the following:
45%.
- 1) IF AT ANY TIME the following conditions exist:
_
- Any ND pump(s) operating with flow - LESS THAN 1000 GPM TO THE LOOPS
- KC to the associated ND HX -
ISOLATED, _ THEN stop the affected ND pump(s) within 3 hours. _ 2) GO TO Step 9.
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A15000/E-1 EP/1/N50001E-1 90f29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 8. (Continued)
- f. Ensure S/I SII - RESET:
_ 1) ECCS. 1) Perform the following: _ a) IF either reactor trip breaker is closed, THEN dispatch operator to open Unit 1 reactor trip breakers. _ b) WHEN trip breakers open, THEN reset ECCS. _ 2) DIG load sequencers. 2) Dispatch operator to open the affected sequencer(s) control power breaker:
- 1EDE-F01 F (Diesel Generator 1DGLSA)
Load Sequencer Panel 1DGLSA) (AB-577, BB-46, Rm 496)
- 1EDF-F01 F (Diesel Generator Load Sequencer Panel 1DGlSB) 1DGlSB)
(AB-560, BB-46, Rm 372). _ 3) IF AT ANY TIME a B/O occurs, S/I equipment THEN restart SII previously on. _ ND pumps.
- g. Stop NO
- h. IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart ND NO pumps.
- 9. Verify NC and S/G pressures as follows:
- a. All SIG S/G pressures - STABlE OR a. IF SIG S/G pressure is decreasing due to a INCREASING. S/G, THEN RETURN TO Step 1.
faulted SIG,
- b. NC pressure - STABLE OR b. RETURN TO Step 1.
DECREASING.
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A15000/E-1 E P111A/5000/E-1 10 of 29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10. ISOpl
- a. iAl'lellst1q~Ql D7$J~ oN. a. GO TO Step 11.
- b. ;;y~[lty'1EW~!is eli'ergized;by.off$iie b. Perform the following:
ipgwrasTgOJ~WS: _ 1) Attempt to restore offsite power to 1}
* !i\~/G1A &~~TQ~J~JAI';-QPf;N; affected switchgear. REFER TO AP/1/A155001007 AP/1/A/55001007 (Loss of Normal
** 1§[~r;i;Erig!B(§I~J~\t:S> Power).
_ 2} GO TO Step 10.d. 2) c.
- d. .1EJJ~3i§en~rgizedl!bfoffs,ite d. Perform the following:
raS~Q'llow§l _ 1) 1} Attempt to restore offsite power to
**~d7@~4;~!k!I?J~~l:tpE~!r~!QR:E:N! affected switchgear. REFER TO AP/1/A155001007 AP/1/A/55001007 (Loss of Normal
- 1~Aft&g~riE:g~ltgp!! Power).
_2) _ 2} IF 1ETA is energized from offsite power, THEN GO TO Step 10J. _ 3) 3} GO TO Step 11. e.
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A/5000/E-1 EP/1/A/SOOO/E-1 11 of 29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 10. (Continued)
ISOPI f. EnSUtel$jht.~t!~ET: 1) _1) c::f§ds'l
~",'>..;".cl~"",t 1) Perform the following:
_ a) IF either reactor trip breaker is closed, THEN dispatch operator to open Unit 1 reactor trip breakers. _ b) WHEN trip breakers open, THEN reset ECCS.
- 2) Dispatch operator to open the affected sequencer(s) control power breaker:
- 1EDE-F01 F (Diesel Generator Load Sequencer Panel 1DGLSA)
(AB-S77, BB-46, Rm 496) (AB-577,
- 1EDF-F01 F (Diesel Generator Panel1DGLSB)
Load Sequencer Panel 1DGLSB) (AB-S60, BB-46, Rm 372). (AB-560, _ 3)if~T~NYTIN,lE'a'AZ\~;bccur§r 3) THEN ~~st(3.r'ti:S71' eqi,lipment pr~yigll'§IYRUI .. ,. ., Depending on reader speed, FWST may be at 37% by this point. If not they will continue in this procedure until then and transition per Enclosure 1.
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A15000/E-1 EP/1/Al5000/E-1 12 of 29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
,0tJt~i,~~on\~lnmeht~fi~ilCQ:hc~'Fttr~ii8:n i~~ f~'fI~W~( ,,' .'",','" ..,., " '. ,
at Ensure, operatpr has be'~:o!~ispatchelJ to secure a""" condens~)t;'?ir:handltgg
'units .. REF' , 0 Enclbsure:;3'
;i!SecuEing,AIf'I'ondenser:A.ir
'fl~,ndfthg}~hi~s' j, *. , '.' ' ' ' ,
- b. Perform the following:
_ 1) Dispatch operator to place 1} containment H2 analyzers in service. REFER TO OP/1/A164501010 (Containment OP/1/Al6450/010 Hydrogen Control System). _ 2) WHEN H2 analyzers are in 2} service, THEN perform Steps 11.c through 11.e. _ 3) GO TO Step 12. 3}
- c. Verify,.col1t.~inmElQ~H£J;icOncentrl~iqtl:,,,:, c. Perform the following:
LE$$,,{WHAN6%,. _ 1) Obtain recommendation from 1} station management for method to reduce H2 concentration. _ 2} GO TO Step 12. 2)
- d. d. Dispatch operator to place H2 recombiners in service. REFER TO OP/1/A164501010 OP/1/Al6450/010 (Containment Hydrogen Control System).
- e. WHEN.theJb~condenser'air haci(j
~flitl?,~re,;off AN I?LH!i~k~o@~rt:ra~iQ less than;6%,THEN~n~tgize the ignib~r§;H:MC-7),
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A15000/E-1 EP/1/A/SOOO/E-1 13 of 29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12.lniiijt~!eyal uati!Rn~f\plant*.stl!tq~,..~s 12. f,p'.II.oVl(~ti ISOpl
- a. VeJft¥i~/1~jst~Q1;s3:~\l9NEQ1~~B;: a. GO TO Step 12.-c.
12.c. IN4EC::'flQN MODE
- b. VerifyCola,l:,~gRe9Itq,68pability as follows:
_1) _ 1) GO TO EP/1/A15000/ECA-1.1 EP/1/A/SOOO/ECA-1.1 (Loss Of Emergency Coolant Recirculation).
- 2) 2) Perform the following:
- IF power cannot be verified to minimum number of valves required to perform the following:
- Transfer one train of ND to the containment sump
- Establish ND flow from containment sump to one train of NV and NI pumps.
_ THEN GO TO EP/1/A15000/ECA-1.1 EP/1/A/SOOO/ECA-1.1 (Loss Of Emergency Coolant Recirculation).
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A15000IE-1 EP/1/A/5000/E-1 14 of 29 Revision 23 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 12. (Continued)
- 3) 3) IF power cannot be verified to minimum number of valves required to isolate NI pump miniflow, THEN
- perform the following:
*
- Attempt to restore power to miniflow isolation valve(s)
- Have operator standing by to locally close the required valve:
- 1NI-147B (NI Miniflow Hdr To FWST Isol) (AB-548, HH-JJ, 53-54, Rm 234)
- 1NI-115A (NI Pump 1A Miniflow Isol) (AB-549, GG-HH, 53-54, Rm 235)
- 1NI-144A (NI Pump 1B Miniflow Isol) (AB-548, HH-JJ, 53-54, Rm 234).
4)
- 4) .. _ 4) WHEN criteria for establishing Cold Leg Recirc are met, THEN manual alignment to containment sump will
- be required.
- c. Verify auxiliary building radiation is c. Evaluate cause of abnormal conditions normal as follows: as follows:
- EMF-41 (Au (Auxx Bldg Ventilation) trip 1 _ 1) Monitor OAC EMF alarms, OAC VA light - DARK Graphic, and area monitor EMFs to determine location of activity activity..
- All area monitor EMF trip 1 lights-DARK. _ 2) Dispatch operator to locate potential leak.
_ 3) IF cause of alarm is LOCA outside containment, THEN GO TO EP/1/A15000/ECA-1.2 (LOCA EP/1/A/5000/ECA-1.2 Outside Containment).
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/A/5000/E-1 EP/1/A15000/E-1 24 of 29 Enclosure 1 - Page 1 of 2 Revision 23 Foldout Page
- 1. NC Pump Trip Criteria:
- IF the following conditions are satisfied, THEN trip all NC pumps while maintaining seal injection flow:
NV or NI pump - ON
- At least one NVor
- NC subcooling based on core exit TICs - LESS THAN OR EQUAL TO O°F.
- 2. 5/1 Reinitiation Criteria:
- IF NC subcooling based on core exit TICs is less than O°F OR Pzr level cannot be maintained greater than 11 % (20% ACC), THEN manually start S/I pumps and align valves as required to restore subcooling and Pzr level.
- 3. Secondary Integrity Criteria:
- IF pressure in any un isolated S/G is decreasing in an uncontrolled manner OR any un isolated S/G is completely depressurized, THEN GO TO EP/1/A/5000/E-2 EP/1/A15000/E-2 (Faulted Steam Generator Isolation).
- 4. SGTR Transition Criteria:
- IF level in any S/G is increasing in an uncontrolled manner OR any S/G has abnormal radiation, THEN:
- a. Manually start S/I pumps and align valves.
- b. GO TO EP/1/A/5000/E-3 EP/1/A15000/E-3 (Steam Generator Tube Rupture).
- 5. ,~pld ,l.:gg:Recl~q<SwiJ~H6V<<rf)1Crft~t!Qn':
-<~/ . *.~.;.:fia~.*2tffih.'.1.,. ",' .7,pl~*"fjvv,~If214~~IX~Vi=l2il*:litJr.tfj'EN(§fj1fC!)*i
, \ .. "",' ..~. .eg~~Qir~QI~tion).
CNS LOSS OF REACTOR OR SECONDARY COOLANT PAGE NO. EP/1/N5000/E-1 E P111A/5000/E-1 25 of 29 Enclosure 1 - Page 2 of 2 Revision 23 Foldout Page
- 6. CA Suction Source Switchover Criteria:
- IF either of the following annunciators are lit, THEN REFER TO AP/1/N5500/006 AP/1/A/55001006 (Loss of S/G Feedwater):
_ . 1AD-5, H/4 "CACST LO LEVEL" OR
- 1AD-8, B/1 "UST LO LEVEL".
- 7. Position Criteria for 1NV-202B and 1NV-203A (NV Pumps A&B Recirc Isol): 1501):
- IF NC pressure is less than 1500 PSIG AND NV S/I SII flowpath is aligned, THEN close 1NV-202B and 1NV-203A
- IF NC pressure is greater than 2000 PSIG, THEN open 1NV-202B and 1NV-203A.
- 8. Loss of Emergency Coolant Recirculation Criteria:
- IF emergency coolant recirculation has been established and is subsequently lost, THEN GO TO EP/1/N5000/ECA-1.1 EP/1/A/5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation).
Duke Energy Procedure No. Catawba Nuclear Station EP/I/A/soOO/ES-1.3 Transfer to Cold Leg Recirculation Revision No. 021 Electronic Reference No. CP0094CV Continuous Use PERFORMANCE JI
- UNCONTROLLEDFORPRrnT**********
(ISSUED) - PDF Format
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/N5000/ES-1.3 EP/1/A/5000/ES-1.3 1 of 38 Revision 21 A. Purpose This procedure provides the necessary instructions for transferring the safety injection system and containment spray system to the recirculation mode. B. Symptoms or Entry Conditions This procedure is entered from:
- a. EP/1/N5000/E-1 EP/1/A/5000/E-1 (Loss Of Reactor Or Secondary Coolant), Step 14, on low FWST level.
- b. EP/1/N5000/ECA-2.1 EP/1/A/5000/ECA-2.1 (Uncontrolled Depressurization Of All Steam Generators), Step 10, on low FWST level.
- c. Other procedures whenever FWST level reaches the switch over setpoint.
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 EP/1/N5000/ES-1.3 2of38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions _ . a,,'djii_.i.lgewillrtJlfJiiltlJ1JIDIB I I . _ _1111_1811111"* *, . iN0fI: 2~j {~Jet~ Perform the following:
<~hn
- a. Ensure S/I - RESET:
_1)1) ECCS. _ 2) DIG load sequencers. sequencers .
** '1AD-211~J?,!:~i"CQNT,"§:(;JMP ft n,;
lEVEL",>3;3 _ 3) IF AT ANY TIME a BIO occurs, THEN restart S/I equipment previously on.
- b. Ensure the following valves - CLOSED:
- 1FW-27A (NO(ND Pump 1A Suct From FWST)
- 1FW-55B (NO(ND Pump 1B Suct From FWST).
(RNO continued on next page)
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 3 of 38 30f38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (Continued)
- c. IF valve(s) valve{s) will not close, THEN:
_ pump{s).
- 1) Stop associated ND pump(s).
- 2) Depress the following "DEFEAT" pushbutton{s) pushbutton(s) for the affected train(s):
* "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A"
* "C-LEG RECIR FWST TO CONT SUMP SWAP TRN B". 8".
_ pump{s)
- 3) Close the associated ND pump(s) containment sump suction valve(s).
- d. IF FWST level less than 37% due to FWST puncture, THEN RETURN TO procedure and step in effect.
- e. IF both NS pumps are off, THEN GO TO Step 2 RNO g.
- f. IF either of the following annunciators are lit:
- 1AD-20, B/2 8/2 "CO NT. SUMP LEVEL "CONT.
>2.5 fi" OR
_ . 1AD-21, B/2 8/2 "CO NT. SUMP LEVEL
>2.5 fi",
_ THEN GO TO Step 3. (RNO continued on next page)
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/N5000/ES-1.3 4of38 4 of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (Continued)
- g. IF all of the following conditions met:
- FWST level - LESS THAN 8%
- NC temperature - GREATER THAN 200°F
- Containment Spray - PREVIOUSLY IN SERVICE
- Indicated containment sump level -
GREATER THAN 0.5 FT. _ THEN GO TO Step 3.
- h. IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect.
- i. IF both "CO NT. SUMP LEVEL >3.3 fi" annunciators on 1AD-20 and 1AD-21 dark, THEN stop all pumps taking suction from the containment sump.
_ j. GOTO GO TO EP/1/N5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation).
- 3. _ Establish KC flow to affected NO Hx(s).
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/N5000/ES-1.3 5 of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4.E,hlgl~'S/f'!'RI;SET: 4.
- a. e'dG'$; a. Perform the following:
_ 1) IF either reactor trip breaker is closed, THEN dispatch operator to open Unit 1 reactor trip breakers. _ 2) WHEN trip breakers open, THEN reset ECCS.
- b. b. Dispatch operator to open the affected sequencer(s) control power breaker:
- 1EDE-F01 F (Diesel Generator Load Sequencer Panel 1DGLSA) (AB-577, BB-46, Rm 496)
- 1EDF-F01 F (Diesel Generator Load Sequencer Panel 1DGLSB) (AB-560, BB-46, Rm 372).
c.
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 6 of 38 6of38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. ~lign,.~lt"~Y~!~m (or1i~cil'q~~JpiIOw!i:
IBOP/5.
- a. VefifY*f9II()J~1?l~:.y,R+f¥ft~h~J:~E~: a. iR~rforro.;'he (~,(gWin~~ij 1tiJ]~;'i~11RYr;nP11~;lIfItt~~'; _ "~::f~;'i;MqiJ~a.IJy;.()p~l1~faffeG\}d**.,,~i~I§J.~:*
'Sy_.
~};giIF:vaI¥~{s)WI!(~'botopen,.tHEN*:*
_ qf stQPtheNDiP9mp(s}a§~odiat~cj) wif60i~ close~i~ontatllmenl suryp1 suc:tioh**valv~:<~) .. b) Close;;,th~' as~~pi,;lteqJNq. 1NI-184B will NOT be open. 10 seconds pump(slsuc(i~fl.valve .frOIn* the,: after they secure the pump, there will be a FWS1) loss of all essential power to A train. "A" train power to essential equipment will not
- 1FW-27A (NO Pump 1ASuct 1A Suet be restored for the remainder of the From FWST) scenario.
- 1FW;.55BjND PlJmp~Jf3$u9t I?J9m FVYST).
(RNO continued on next page)
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A1S000/ES-1.3 EP/1/A/SOOO/ES-1.3 7of38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED S. (Continued) Wi{ENtheNd:' yalv~,from the J ;;IS TH13Nmerform the fOlio >' : (1 (1)) Att,ep1p,tJ,o,m, 8,; YO~,~l
'be':aff~qt~~ co ";i.,, me'n~)
s'ump sLiqt!!iirryar~~(s)., _ .* 1 1NI-18SA NI-185A (NO Pump 1A Cont Sump Suct)Suet) (2) }IF affect tai~fuent sump, su~!~~:wiU ~Bf
,qp~J'\:;~L- sp'gt~htWgi:
qp~faforsto operl!~the'
<i\lfectedvalve(s);!: '
- 1 NI-18SA (NO Pump 1A 1NI-18SA Cont Sump Suct)
(AB-S4S, EE-FF, S2-S3, 52-S3, Rm 217)
** ,1 NI-184B(~ijiPumpi1 B, Once they call, it will take 10 minutes to get 'Gont Sump'$!!Ict) the valve open, 5 to get there and 5 to open. (AS-54;>;, Efu'.CGGj5i~$3.
Rm 21i()Jj
- 3) IF both containment sump suction valves are closed, THEN:
Both valves are NOT closed. 1NI-185A 1NI-185A is open _ a) IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect. _ b) GO TO EP/1/A1S000/ECA-1.1 EP/1/A/SOOO/ECA-1.1 (Loss Of Emergency Coolant Recirculation).
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000IES-1.3 EP/1/A/5000/ES-1.3 8 of 38 8of38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (Continued)
IBOpl b.
- b. VeflfY'fpllo\VfD9~Y~r'g~:,t,gb~~J?tD: b. Perform the following:
* ~frf1:Q;,:Roroli!lA,§g~lFraro. _ 1) Manually close affected valve{s) valve(s)..
- 2) IF valve(s) will not close, THEN:
_ a) Stop associated ND pump(s). pump{s).
"DEFEAT" b) Depress the following "DEFEA Til pushbutton(s) for the affected train(s):
* "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A"
* "C-LEG RECIR FWST TO CONT SUMP SWAP TRN 8".
_ c) Close the associated ND pump(s) containment sump suction valve(s). d) IF both containment sump suction valves are closed, THEN: _ (1) IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect. _ (2) GOTO EP/1/A/5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation).
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 90f38 9 of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (Continued)
IsOpl c. c.*\Z~:rlf~{~Q:gqffl*p~iL ON: c*p~Jj~lm~rli~'follo\YIVg : c. _ 1 );§Iart;:NfQlpump(~)\Mth.§Hctioh al!gnedtqah OI\~hiCohf~(Qment There should be no valid RED or sli'mp suql!Q:n*v;a:li~k ORANGE paths that need to be implemented so the crew should go to ECA-1.1. There may be an ORANGE/RED path on NC Integrity which IS valid, but should have been previously addressed. _ .b)~~~~.~i~~lAl5000(g*GA*1.1}i
- (EQ.sqorEfne(g~)':l~y:qQqI9mt J~ecii"cuI9tior))l
- d. Isolate NI pump miniflow as follows:
_ 1) Verify NC pressure - LESS THAN 1) Perform the following: 1620 PSIG. _ a) Stop NI pumps. _ b) WHEN pressure is less than 1620 PSIG, THEN start NI pumps.
- 2) Close the following valves:
- 1 NI-115A (NI Pump 1A Miniflow 1NI-115A Isol)
- 1NI-144A (NI Pump 1B Miniflow Isol).
_ 3) Place "PWR DISCON FOR 1NI-147B" switch in "ENABLE". _ 4) Close 1NI-147B 1NI-147B (NI Pump Miniflow Hdr To FWST Isol).
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A15000/ES-1.3 20 of 38 Enclosure 1 - Page 1 of 1 Revision 21 Foldout Page
- 1. SII Reinitiation Criteria:
5/1
- IF NC subcooling based on core exit TICs is less than OaF OR Pzr level cannot be maintained greater than 11 % (20% ACC), THEN manually start S/I SII pumps and align valves as required to restore subcooling and Pzr level.
2.
.lilFSt (0110
- ia>.IF>aij ~Mnare:cr@'Rr:orane
.........*~ff:~q!rt. >~th P"
..... '-.. '-.". . . .".%g . 'P"'" rocg(:fure
........ is'in.effeOl"jt
. h.*...... "., .*.d ..~...:fENRElf'URNliI0,
- ... - ' "P..roceCture
........... ~~ ..in
- 3. Loss Of FWST Supply To ECCS Pumps:
- IF FWST level decreases to less than 11 %, THEN stop NS pumps taking suction from the FWST.
- IF FWST level decreases to less than 5%, THEN stop all pumps taking suction from the FWST.
J~) (je--) CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/1/N5000/ECA-1.1 EP/1/A/5000/ECA-1.1 1 of 83 Rev 31-DC~ A. Purpose This procedure provides actions to restore emergency coolant recirculation capability, to delay depletion of the FWST by adding makeup and reducing outflow, and to depressurize the NC System to minimize break flow. B. Symptoms or Entry Conditions This procedure is entered from:
- a. EP/1/N5000/E-1 EP/1/A/5000/E-1 (Loss Of Reactor Or Secondary Coolant), Step 12, when Cold Leg Recirc capability cannot be verified.
EP/1/NSOOO/ES-1.2 (Post LOCA Cooldown
- b. EP/1/A/5000/ES-1.2 Cool down And Depressurization), Step 5, when Cold Leg Recirc capability cannot be verified.
- c. EP/1/N5000/ES-1.3 (Transfer To Cold Leg Recirculation), Step 5, when at least one EP/1/A/5000/ES-1.3 flowpath from the sump cannot be established or maintained.
- d. EP/1/N5000/ECA-1.2 EP/1/A/5000/ECA-1.2 (LOCA Outside Containment), Step 3, when a LOCA outside containment cannot be isolated.
CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/1/A/5000/ECA-1.1 20f83 Rev 31 OC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions
- a. yerif~'~lIi;~imtf"l~'JQJlowiriglptim'Q$ a. ,4E;;pow~r;is av§llabl$'!:tm"trr~ffte'ct~lfi;
'BR4!pP~~ij'iii§~.¥l~lJ~~.I@;;!!!~lji!m~i3!{Sl~U~:Ql J\VA!~B~WTG;1;1E O~{;RAIJ;P FROM (~ssehtiJ=!lfbus,(§J~~iTHENj dispatch 1~§§f:l!iW!~!ili6!il~~§~'ii'imt:tfjf'4'i d is patch rHEf,QoJ;~JI8oLi.00ty1i operator and maintenance to determine and correct cause of pump failure.
_
- N!l2J'I),J)!'01P$; REFER TO EM/1/A/52001005
_. N\7P9rng:§ (Troubleshooting Cause For NO, NI, or _ * ,Nlptifnp*1 NV Pump(s) Failing to Start).
- b. iM'~rJfY. th~.f0'11(jyY1f1g1Wi:llvE{~J b. E'?rfq~&fYf;lb~ffQllqVv'ii)g:
.J\WJ\I~f2I,;J;:TQ. §~i;OPqW\TE:VJ~\FROrv1l ifHI; COhl.l'RQLlBOOty1!;, 1) i'IFpJ)W~t;i115 lJe>travail§ble, THEN di~g?tGhigP~rfl'tClrJq~~osureitl1e
~< 1N.*.I;;*1857xlNO'liPufn't1AC*"t
. . .* . \...k .** * . * " ". *.
Slim"P
'<~"' Re.,... 0 .*....
foIl6Wing'plea,Kers:~feql@§:ed::' s\jct)\
- 1 1EMXA-R080 EMXA-R080 (NO Pump 1A
* ~.:NI-184§'n~D ~ymp1J3i@of11.:3hiJrip; Suction From Containment Sump
.~J,Jqt).; Valve 1N1185A) 1N1185A) (AB-577, FF-54, Rm 478)
May not do this RNO since the power loss
- 1 EMXB-F01 C (NO Pump 1 1EMXB-F01C B 1B is beyond just those Suction From Containment Sump breakers. Valve 1N1184B) (AB-560, FF-56, Rm 330).
(RNO continued on next page)
CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/1/A/5000/ECA-1.1 3 of 83 Rev 31 OC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued)
- 2) IFg12SYercaJi\qgf p~re~tore:altq:~t;
~qsrpr;f~I,val~~lDR valve gan:ndrbe
!qp~S;~!~g'fr:Qgj21l:le. CO(lirol roQ,m,.
iJ'HEN}} _ a) IF NO Pump 1A is available, THEN dispatch two operators to standby to open 1NI-185A (NO Pump 1A Cont Sump Suct) Suet) (AB-545, EE-FF, 52-53, Rm 217). This should already have been _ b) IF NQ,i=lV!l1P,\1 !:3is:?v::itlai:)le;;! done in ES-1.3 THEN;Qi.~pafc!'i'~6.qR~ra.tqt§j,to* standt>y:t() opet1r'1~11>l1~~41?'1(i~P PU!l11?1'B ContStigjp"~ucl! (AE?f945, FF~G{3,.52~93; RID 2~7;;},t, c )WHlEN~fl(fastoo~' of tt:1~ 4£i!lQWltil:g* ;;L.fe
.* OR
~.s:
_~:1~p':'.g1. B/27G,@NT.§,UMI? IlI::Y~!!f . ~2~§;t!i _ THEN0t1aye~I§Pc1tchedJ5p~rat6i op~paffect~!l;*alve(s ).
CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/11A1S000/ECA-1.1 EP/1/A/SOOO/ECA-1.1 4 of 83 Rev 31 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued)
- c. ~§lifY c6nt~inrneht surnRI~v~1 c. IF NC inventory lost outside
*aq~q*lJatea~toIlOYi§,; containment, THEN GO TO Step 4.
_ FJ':: ij~~[)j~~111[3J~**~!;Ori!rtii~UM~J.-E3YsE3 L
!~2;RJl";i*LJJ.:
OR
- All of the following:
- FWST level - LESS THAN 8%
- NC temperature - GREATER THAN 200°F
- Containment Spray -
PREVIOUSLY IN SERVICE
- Indicated containment sump level -
GREATER THAN O.S FT.
CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/1/A/5000/ECA-1.1 EP/1/N5000/ECA-1.1 5 of 83 DC~ Rev 31 DeS ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 3. (Continued)
{Continued) ISOp 1_ d.&:efifyCqlqLegRecirCQf:1pabiUty- d. ;Peijc)fmtfi~lfollbWi~g: RESl"OREP~
- 1) GqDtin4~)fatternpts to restorerecirg caR~binMi~s follpy{s:
- 2) WH~N'etng[g~f:iQY coolgnlfe~m::
Likely NOT restored at this time C?pl}1:)jli.tY:'I§~resU?t~q.qllting:ttt!~ and should continue. Transition !ptQ~~~JJr§,j'}rHEN!fi back to ES-1.3 will be per this a) IF transfer to Cold Leg Recirc is step or Enclosure 1 guidance. required, THEN perform the following: (1) Ensure the following valves
- OPEN:
- 1NS-29A (NS Spray Hdr 1501) 1A Cont Isol)
- 1 NS-32A (NS Spray Hdr 1501) 1A Cont Isol)
- 1NS-15B NS-158 (NS Spray Hdr 1501) 1B Cont Isol) 18
- 1NS-12B NS-128 (NS Spray Hdr 1501).
1B Cont Isol). 18 _ (2) GOTO EP/1/A/5000/ES-1.3 EP/1/N5000IES-1.3 (Transfer To Cold Leg Recirculation ). _ b) RETURN TO procedure and step in effect.
- e. RETURN TO procedure and step in effect.
CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/11A1S000/ECA-1.1 EP/11A/5000/ECA-1.1 60f83 6 of 83 Rev 31 DeS DC!: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IBOP 144.. . a._ t;hs,-!re a. BCQ~; 5fr~RI;§E;T:
- a. Perform the following:
_ 1) IF either reactor trip breaker is closed, THEN dispatch operator to open Unit 1 reactor trip breakers. _ 2) WHEN trip breakers open, THEN reset ECCS.
- b. Dispatch operator to open the affected sequencer(s) control power breaker:
- 1EDE-F01 F (Diesel Generator Load (AB-577, Sequencer Panel 1DGLSA) (AB-S77, BB-46, Rm 496)
- 1EDF-F01 F (Diesel Generator Load Sequencer Panel 1DGLSB) (AB-S60, (AB-560, BB-46, Rm 372).
c. c.IFAT~ANYS:J:IME:aBlq:occu,*J,IflEN restart.S/I ~q~uiprn~Qtpt@viousl~~mJi
- 5. pgpt[~~tt(~tiQE,fE:AT'~I)U~Jijy~on~()Jj IBOP I tli~1'(9Up~jifgs~i~~I1~s;
'.' ":C-LEG *Rt;QIRFWSTTOCONTSU~P SWAeJ~N1!~A"
* '~C:'LE~;k?:~E~I~!~1j:J";o, CO{l!lmJSUMIj p~Ae?;:rgJ)ll;~;~ii 1---.1
- 6. ~IJIIII1fi(.'tqJm.'_
~~ ~jMl1El"'1JIaB
_al _ FW$Tlgy~P" GRt;8Jj~~Frti8tl",~$i;11 a. GO TO Step 33. b.IFAIfANY1nME~B~§l!~vell§J!:e$'s
- tha~n'~%1;THEN GO'\;fO 9t~p,t3~:'
CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/1/Al5000/ECA-1.1 EP/1/A/5000/ECA-1.1 7of83 7 of 83 Rev 31 DC~ ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
,~. V~ftify fQI!Qwing NS<Jil!imp'~,s\Jq~i6Q.~plves' a. GO TO Step 10 10..
- OPEN:;
- 1NS-:20Al(NS,Pumj:) '1A Sqct;tf(Qm F;WST)'
- l~jNS;;~B (NSd:)ump 1BSuct Ft9m FW,pljH b.O~termin~h't:imbet\pfNS:ip:umps itegpicgQ,:llrQ,Q1.lt1e.wlgllowiQQ)able:
FWST LEVEL CONTAINMENT P RESSU Rf (PSIG) PRESSURE NS PUMPS REQUIRED REQU I RED GREATER THAN 15 2
'G R'EA'T!!ER
~~
THAN
~1iA'lNl BETWEEN 10 AND 15 1
~ 5%
LESS'THAN}I'O
~lJll'l~ ~ 0 LESS THAN 5% N/A 0 c.
c.Y~rifY the n!ll.mp~Wbf N~pumpsi~>n EOUALTQ1INJ9M8ERfjSf;:OljIRijQ?:
~i.I*".i*11)
Vprify",ct,j~ri,~ltQ,~1i9m;NS!~fbt:r~J;ifcas _ "ip~ ManY,allS1t~p~rate t)I,S pumps t~quJJE~d,;QJi,+tilJ:)I¢ qQoy~; IWili Will secure the 1B NS pump. as flD _ fbnpv<~::' _ a.. Ahy a . .NS ..pump
. .-:*ON.,
- b. Verify at least one of the following b. Perform the following:
annunciators - LIT: _ 1) WHEN at least one "CONT. SUMP _ . 1AD-20, 8/3 "CONT. SUMP LEVEL LEVEL >3.3 ft" annunciator is LIT,
>3.3 ft" THEN GO TO Step 8.c.
OR _ 2) GO TO Step 9. _ .* 1AD-21, 8/3 "CONT. SUMP LEVEL
- >3.3 ft".
- c. Align NS for recirc. REFER TO Enclosure 3 (Aligning NS for Recirculation ).
Recirculation).
CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/1/Al5000/ECA-1.1 EP/1/A/5000/ECA-1.1 8 of 83 80f83 Rev.31 DC~ Rev31 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- a. p~tf~llftli~tLgf01!~~ingi
_ 1) Ens'eJre;'NS Tfaio!,jA. - .RESET." 2)CI()sethe _ - i l. . . foll6wing'vab7es: _It 1 ~!3-2~U\{t'-:I;§~pray Hd(11ACorit Is()!) _ fi .
;,:1 N§;:3;?tl%(N,§~Spray
. . . . .BIfII1lIHdrttlA
- !sC?I~~{
J?~rt()L{l11;tfie.
*:b. QlllII .. lIIIDII tQILQl&ilig:'
. . .Cont . .D
_'1).EnsQ£@}N,~,;!i'r~if:1~~[~;RE~!;:T!ii
*. . . . . .11. . .
- 2) Clos&"the.~f911~WibQt[Xc;3Iy'~~:
-1 NS-158 (t:1JS IS91)
~praY:;lidr18 Cool
- '\i' (1NS~:t2BJNS,s (" Hd:
.. : "";...... *....'L:.......,,,,..P.i3Y 1Qi C"l
., .... J:hi: on 1$01).
Ii.
- c. IFATi:ANY?iTIME.NS pumps are
'~!QQPed;'Qrtstafte.a;'THEN: .
Depending on reader speed 1 NI-184B 1NI-184B _ e \~risuue':'~?sQc,!p:!edNS T\t~l@j;i: should be open by this time and the RE~gT* crew would go back to ES-1.3 per
- enclosure 1 guidance or previous WHENITHEN step (3.d.2) RNO).
- 10. Initi.ate ITl~Reufito!FW~J~,REFiERTO Qet1ZAI,~20010.14.(Reflieling*lJI{cjJer
§ysttil1l)~:
CNS LOSS OF EMERGENCY COOLANT RECIRCULATION PAGE NO. EP/1/A/5000/ECA-1.1 52 of 83 Enclosure 1 - Page 1 of 1 Rev 31 DC~ Foldout Page
- 1. Emergency Coolant Recirc Capability Restoration:
.:WHEN~melgent!y>coolaot.recircPqpgbilitY~i,sr~t6J:~~i:I!JriQ:gJbJs;pr'Q:g~J!ui'~tfFHENt:
- ~l JF4r~f:isf!ilr ~oGqtg Leg!B~cir{}1~:t~g~lr¢~ti3}THENi,Q~)fgf:m}!fil!¢~t911()WiOg:
1~ Ensur~';tfle !pll&,wiQg1'l~lQ;g~"~@:Iil;N::) _ b. RETURN TO procedure and step in effect.
- 2. ECCS Suction Source Monitoring Criteria:
- IF the suction source is lost to any ECCS OR NS pump, THEN stop the affected pump.
- IF FWST level decreases to less than 5%, THEN stop all pumps taking suction from the FWST.
- IF both "CO NT. SUMP LEVEL >2.5 ft" fi" annunciators on 1AD-20 and 1AD-21 dark, THEN stop all pumps taking suction from the containment sump.
- 3. CA Suction Source Switchover Criteria:
AP/1/A/55001006 (Loss of S/G
- IF either of the following annunciators are lit, THEN REFER TO AP/1/A/5500/006 Feedwater):
_ . 1AD-5, H/4 "CACST LO LEVEL" OR
- 1AD-8, 8/1 "UST LO LEVEL".
......l.l ItV )
Duke Energy Procedure No. Catawba Nuclear Station EP/IIAlSOOO/ES-1.3 EP/IIAl5000/ES-1.3 Transfer to Cold Leg Recirculation Revision No. 021 Electronic Reference No. CP0094CV Continuous Use PERFORMANCE I
**********UNCONTROLLEDFORPRrnT**********
(ISSUED) - PDF Format
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A15000/ES-1.3 EP/11A1S000/ES-1.3 1 of 38 Revision 21 A. Purpose This procedure provides the necessary instructions for transferring the safety injection system and containment spray system to the recirculation mode. B. Symptoms or Entry Conditions This procedure is entered from:
- a. EP/1/A15000/E-1 EP/11A1S000/E-1 (Loss Of Reactor Or Secondary Coolant), Step 14, on low FWST level.
- b. EP/1/A15000/ECA-2.1 EP/11A1S000/ECA-2.1 (Uncontrolled Depressurization Of All Steam Generators), Step 10, on low FWST level.
- c. Other procedures whenever FWST level reaches the switchover switch over setpoint.
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A1S000/ES-1.3 EP/1/A/SOOO/ES-1.3 20f38 2 of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. C. Operator Operator ActionsActions ISOp BOP DOES DOES ALL ALL THESE THESE ACTIONS ACTIONS 1.M<>D;nO'f\~gnGlbs:~re.t (Fcintouf Page). CAtJ~I(j)N S/I recr.'~gp:rittig,lrfl~19~~C Sys~~ro.:;!rol.lst b~;itrl~intain~gat all time$.
....* -_1.11 NOTE
_111'**
'~\Ste
'. '. R '5.'.2~mr8('t:"h
,"W S9Sh6(!JldHe;'**
.*.9 . ,.'... . W' ,'.'
. . . . .11_ _ _ 18 J? erfo~~ertt:l(~itffioutkieYrg'(.
¥lj!:t~i\'" ' ..;.1 ""." . :l'dY..
2: :~~~m~~~~lt~r3i~tflfhe*tQllqWing; Perform the following:
- a. Ensure SII - RESET:
_ * ,:1ADi20,13/3;~~Pd'f>JJt.~uMIi:i.!ij,~EL >3.3 f{n _1) ECCS.
- .QR _ 2) DIG load sequencers.
_ *.1Ab-21:!BY3~ "CONT/S(:¥J,MPLE9EH:;:~3.3
",' 'd>>,'VJ", <<,., ~ , ~' ~,,~~>> c', '."S,',',,->!'> >""",> >>v >
_ 3) IF AT ANY TIME a 8/0 occurs,
~ft:i~T THEN restart SII S/I equipment previously on.
- b. Ensure the following valves - CLOSED:
- 1FW-27A FW-27 A (NO Pump 1A 1A Suet Suct From FWST)
- 1FW-SS8 (NO Pump 18 Suct From FWST).
(RNO continued on next page)
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 30f38 Revision 21 ACTION/EXPECTED RESPONSE RESPDNSE NOT OBTAINED
- 2. (Continued)
- c. IF valve{s) valve(s) will not close, THEN:
_ 1) Stop associated NO ND pump(s). pump{s).
- 2) Depress the following "DEFEAT" pushbutton(s) for the affected train(s):
* "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A"
* "C-LEG RECIR FWST TO CONT SUMP SWAP TRN 8".
_ 3) Close the associated NO ND pump(s) containment sump suction valve(s).
- d. IF FWST level less than 37% due to FWST puncture, THEN RETURN TO procedure and step in effect.
- e. IF both NS pumps are off, THEN GO TO Step 2 RNO g.
- f. IF either of the following annunciators are lit:
- 1AD-20, 8/2 "CONT. SUMP LEVEL
>2.5 fi" OR
_ . 1AD-21, 8/2 "CONT. SUMP LEVEL
>2.5 fi",
_ THEN GO TO Step 3. (RNO continued on next page)
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/SOOO/ES-1.3 EP/1/A1S000/ES-1.3 4of38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 2. (Continued)
- g. IF all of the following conditions met:
- FWST level - LESS THAN 8%
- NC temperature - GREATER THAN 200°F
- Containment Spray - PREVIOUSLY IN SERVICE
- Indicated containment sump level -
GREATER THAN O.S FT. _ THEN GO TO Step 3.
- h. IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect.
- i. IF both "CO NT. SUMP LEVEL >3.3 fi" annunciators on 1AD-20 and 1AD-21 dark, THEN stop all pumps taking suction from the containment sump.
_ j. EP/1/A/SOOO/ECA-1.1 (Loss GO TO EP/1/A1S000/ECA-1.1 Of Emergency Coolant Recirculation).
- 3. _ Establish KC flow to affected NO Hx(s).
B train only. No power to A train.
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A1S000/ES-1.3 S of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 4. ED;~~re ~~i~;I{ESEml
- a. i§~~S. a. Perform the following:
_ 1) IF either reactor trip breaker is closed, THEN dispatch operator to open Unit 1 reactor trip breakers. _ 2) WHEN trip breakers open, THEN reset ECCS.
- b. b. Dispatch operator to open the affected sequencer(s) control power breaker:
- 1EDE-F01 F (Diesel Generator Load Sequencer Panel 1DGLSA) (AB-S77, BB-46, Rm 496)
- 1EDF-F01 F (Diesel Generator Load Sequencer Panel 1DGLSB) (AB-S60, BB-46, Rm 372).
- c. mA!t.ANYdIME>~hB/6q96ursi~HEf'j'l
;~~~t~tt$'lJ~;equipment pt~viouslybn,; ...
CNS TRANSFER TO COLD COLO LEG RECIRCULATION PAGE NO. EP/1/A/SOOO/ES-1.3 EP/1/A/5000/ES-1.3 6of38 6 of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED S.
- 5. AIi~ni[§m;sy,~ltnn:f()ri~reclrp,,~ fcill~~~lE*
a .it:~mtyf611;d\kllng v~l~~~.;QPE;~:;!: a. Perform the following:
**11NI~185~i;(NQ~Ymgl1~I(Jq;rit*SYrnp _ 1) Manually open affected valve(s) valve(s)..
SqGD
- 2) IF valve{s) valve(s) will not open, THEN:
1 ~r¥11:8~BJ'&[)£PQmpIlI BCcWltSul11g.
- ** .S~P~J""*' J,,"" ........*" . . .... .'. "
_ a) Stop the NDNO pump(s) associated with a closed containment sump suction valve(s). b) Close the associated ND NO pump(s) suction valve from the FWST:
- 1FW-27A (NO (ND Pump 1A Suct From FWST)
FW-SSB (NO
- 1FW-55B (ND Pump 1B Suct From FWST).
(RNO continued on next page)
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A15000/ES-1.3 7 of 38 70f38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (Continued) pump(s)suction c) WHEN the ND pump(s)'Suction valve from the FWST is closed, THEN perform the following:
(1) Attempt to manually open the affected containment sump suction valve(s). valve(s) .
- 1NI-185A(NDPump1A 1NI-185A (ND Pump 1A Cont Sump Suct)
- 1 NI-184B (ND Pump 1 1NI-184B B 1B Suct).
Cont Sump Suet). (2) IF affected containment sump suction valve will not open, THEN dispatch two operators to open the affected valve(s): affeeted
- 1NI-185A (ND Pump 1A Cont Sump Suet)
Suct) (AB-545, EE-FF, 52-53, Rm 217)
- 1 NI-184B (ND Pump 1 1NI-184B B 1B Cont Sump Suct)
(AB-545, FF-GG, 52-53, Rm 217).
- 3) IF both containment sump suction valves are closed, THEN:
_ a) IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect. _ b) GO TO EP/1/A15000/ECA-1.1 (Loss Of Emergency Coolant Recirculation Recirculation).).
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/NSOOO/ES-1.3 EP/1/A/5000/ES-1.3 8of38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (Continued)
S. b.Vg@fy
- b. foIl8~ltlgvarY.~s ~ .QLO$![~,j b. Perform the following:
.1&YV
* -27AiNl,:;)tffltJ;mp,~~'f81S~.r;ttrhQili) _ 1) Manually close affected valve(s) valve(s)..
F~{3:n)
- 2) IF valve{s) will not close, THEN:
* ;~.~~~I3XBt~I.PiJmp;i1 B;§UGl Fro*itl'
_ a) Stop associated ND pump(s). b) Depress the following "DEFEAT" pushbutton{s) pushbutton(s) for the affected train{s): train(s):
* "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A"
* "C-LEG RECIR FWST TO CONT SUMP SWAP TRN B". S".
_ c) Close the associated ND ND pump(s) containment sump suction valve(s). d) IF both containment sump suction valves are closed, THEN: _ (1) IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect. _ (2) GOTO GO TO EP/1/NSOOO/ECA-1.1 EP/1/A/5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation).
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/SOOO/ES-1.3 EP/1/N5000/ES-1.3 90f38 9 of 38 Revision 21 ACTION/EXPECTED RfSPONSE RESPONSE RESPONSE NOT OBTAINfD OBTAINED
- 5. (Continued)
S.
- c. Y~rify NO'pumpsi\QN. c. iPerf~r,hl th(!f; foHqWI!5g:
_1) _ 1) S19Xt ND\pump{s) Wit!J!~~tiQ!1 alig'(1ed tQ'9n Qpen co'ntainm~mt Should start 1B NO pump at this ,:?ur:nl? suc;tibn va,lYe; time. CRITICAL TASK! 2) IF no ND pump can be started OR no ND train can be aligned for recirc, THEN: _ a) IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect. _ b) GO TO EP/1/A/SOOO/ECA-1.1 EP/1/N5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation). Recirculation ).
- d. 'lsolqt~NI. P:k1mp'mrfittldw*~*sfdll.§.:/
_1) _ 1) sterifxf~C'pr~§~iiref'~'E:S$.JBA~{ 1) Perform the following:
,:620;e~IG,:
_ a) Stop NI pumps. _ b) WHEN pressure is less than 1620 PSIG, THEN start NI pumps.
- 2) ,~lQ$(ITile Jg!lqwing,;¥alve§.f No "A" train power power..
_ .*';\';~\$14~!i~f{~li~8;mpl!1~1~lo:[fgw 1 NI*~'44A(NI/PuITl'Af"
- ** ~I.§oli~ 13 .* MIFilfI6v/t
......,. ,. .."P ..,.. ........
- ,~)*'t~1~it~1~~~Q1~?EN~~Lgl'~ . CRITICAL STEP due to potential for release of radioactivity to environment.
CNS TRANSFER TO COLD lEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 EP/1/A15000/ES-1.3 10 of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (Continued)
- e. t¢i9s~\t6eJpll()wlhg valy~s:
.'. p?3~A'(ND ifr:ain bl)' ........1A:,Hot l.3:e'}';lo*
,.."QA No power to 1ND-32A and 1NV-203A.
- f. Perform the following:
_ 1) IF 1NI-9A (NV Pmp C/l Inj Isol) _ .* 1~\7~gQ~!lt~Y*.Bgrop*s~~:R~qi;~~ AND 1NI-10B (NV Pmp C/l Inj Isol) IsqO; are closed, THEN maintain charging flow greater than 60 GPM. OR
- 2) Close the following valves:
*.1~V~202Bff(NVR@!!'~J',A;~S~B~ci~~
I:S91)~
- 1NV-203A (NV Pumps A&B Recirc Isol)
- 1NV-202B (NV Pmps A&B Recirc Isol).
g.
~~J~,pqmp SuclXEOveit}
']J);
~~~r~~B{NII?:LlfTI~§U~t:J:rQ;m 111NI-333B NI-333B is CRITICAL TASK 3Y Qp§'Ji\!fR~~;t2!(gWjng,&?lve§X 1NP7~~~;(NQ :S;1!ppl~t0:'~M.~IMj NL8mps) 6B(ND $t.tpply Tpl~l -136B is CRITICAL TASK 1NI-136B
.i:4.~.d;*i* ....... .
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 11 of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (Continued) h.
- h. .I!:ft~lfl"iff,t\ilf~"p.
_2) _ 2) _ 2) Dispatch operator to close 1NI-100B 1NI-100B (NI Pmps Suct From FWST) (AB-552, HH-JJ, 53-54, Rm 234). 3) _III It is Critical that 1N 1-1 OOB and NI-1
'" "IV 1.u.1\I 'l£:'lA be closed from the 25.2f-
-~-,
control boards and an operator be NV-252A dispatched to close 1NV-2S2A _III (which has no power). Ref DBD for Nl system. NI NOTE: The scenario ends on the next page. b) IF 1NV-253B (NV Pumps Suct From FWST) cannot be closed, THEN dispatch operator to perform the following: _ (1) Open 1EMXJ-R03A (NV Pump Suction From FWST NV253B)) (AB-560, Motor (1 NV253B>> GG-56, Rm 330). _ (2) Close 1NV-253B (NV Pumps Suct From FWST) (AB-554, HH-JJ, 53-54, Rm 234) (Ladder needed).
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 12 of 38 Revision 21 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 5. (Continued)
- i. V~tif~prop~'~edft9JI()W;'~s* fonOws: i. IF any S/I pump on without a suction flowpath, THEN stop the affected
_ .* IfN,~i!,~]I~liQW"i~J~JPI~~TIN(3,.FLO':!:K pump(s). _ **;DJI4~\gmp~:IliaL~J~JJ5A1dN,~i=l,..Q':!:K THE SCENARIO CAN BE _ * {flb;RUmpS;t'l)J~19.K!1liIN~1E~Q':!:Ki:: TERMINATED AT THIS POINT.
- 6. WHEN FWST level decreases to 11 %
(1AD-9, Et8 "FWST LO-LO LEVEL" alarm lit), THEN perform the following:
- a. Stop NS Pumps.
Aligning NS for Recirc is JPM and should not
- b. Align NS for recirc. REFER TO be allowed during this scenario.
Enclosure 2 (Aligning NS for Recirculation).
- 7. IF any NS pump in service with suction NS pumps (if running) are aligned to FWST, THEN perform the secured per Enclosure 1 when following: FWST reaches 11 % level.
- a. Ensure appropriate operator is in possession of Enclosure 2 (Aligning NS for Recirculation).
- b. Designate operator to ensure NS pumps immediately secured when FWST level decreases to 11 % OR 1AD-9, E/8El8 "FWST LO-LO LEVEL" alarm lit.
- c. IF time and manpower permit, THEN notify designated operator to review Enclosure 2 (Aligning NS for Recirculation) for current plant conditions.
CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO. EP/1/A/5000/ES-1.3 20 of 38 Enclosure 1 - Page 1 of 1 Revision 21 Foldout Page
- 1. SII Reinitiation Criteria:
- IF NC subcooling based on core exit TICs is less than OaF OR Pzr level cannot be maintained greater than 11 % (20% ACC), THEN manually start SII pumps and align valves as required to restore subcooling and Pzr level.
- 2. Loss Of Emergency Coolant Recirculation:
- IF Step 5 has been completed AND recirc flow is subsequently lost, THEN perform the following:
- a. IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect.
- b. GO TO EP/1/A/5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation).
- 3. Loss Of FWST Supply To ECCS Pumps:
- IF FWST level decreases to less than 11 %, THEN stop NS pumps taking suction from the FWST.
- IF FWST level decreases to less than 5%, THEN stop all pumps taking suction from the FWST.}}