ML20056D396
| ML20056D396 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/16/1993 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17310A512 | List: |
| References | |
| 41EP-1R004, 41EP-1R4, NUDOCS 9308130110 | |
| Download: ML20056D396 (234) | |
Text
{{#Wiki_filter:. . - . - . . . 41EP-1ROO4 Revision 00.07 PVNGS Page 1 of 87 Total 234 ,,, EXCESS STEAM DEMAND E8 5 E8 o-on so om ou OlUECTIVE moo 88 t104 W PJ "TI m This procedure provides the operator actions which must be accomplished to mitigate the effects of an excess steam demand. The actions in this procedure are necessary to ensure that the plant is placed in a safe, stable condition. 'Ihe goal O L. , ',d_
^ * .,
I of this procedure is to establish SDC cntry conditions. _ Z n O m E, i O
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EXCESS STEAM I)EM ANI) 41 El'- 111004 Revision 00.04 PVNGS Page 3 of 87 Total 234 1.0 ENTITY CONDITIONS (cont.) 1.2 IF all of the entry corn'itions f or an excess sicani denianti exist, TlliiN pc forni both of the following: Direct the primary operator to GO TO l'xcess Sicain Dernand,41EP-lROO4, Appendix A, Primary Operator Actions, beginning with Step 3.1. ] 3 Direct the secondary operator to GO TO Excess Sicain Deinand,41EP-1ROO4, Appcialix II, Secondary Operator Actions, beginning with Step 3.1. p "TI O 1.3 IF all of the entry conditions for an excess steam dennand do NOT cxist, D T!!!iM direct the team to G01O Emergency Operations,41EP-lE001, beginning at the entry to the Safety Function g Flowcharts. p
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41 E P- 1 R 004 Revision 00.04 PVNGS Page d of 87 Total 234 EXCESS STEAM DIGI AND i'RS ACI'lONS CRS DETAILS i 2.0 IGIERGENCY N(T!'IFICATi()N ANI) S UI'I'O R T Ensure that the event is being classified in accordance with the Direct an SRO or emergency coordinator (lualified person to 2.1 CONCURRENTLY PERFORM Emergency Classification, n Emergency Plan. EPIP.02, beginning with Step 4.0. O~ 33 Infonn an STA of the (, cess steam demand. Z 2.2 "T1 O Direct the STA to PERFORM Einergency Operations, 33 2.3 WilliN the STA arrives in the control room, TlIEN direct him to m initor safety function status and plant 41EP-lEOOi, Appendix S, STA Responsibilitics, beginning ate the entry to the STA SFFC. 3> paramercrs, -1
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Continue in this pincedure. O Z O Z r-
EXCESS STEAM I)EM ANI) 41 E P- 111004 Revision 00.04 PVNGS Page 5 of 87 Total 234 f.]1S ACTIONS CRS DETAILS l 2.0 IG1EltGENCY NOTIFICATION ANI) SUI' PORT (cont.) ___ ________ ____._____________.________________________________------NOTE---------------------------------------------------------------------------- After a thermal power change that exceeds 15% within a i hour period, Tech Spec 3.4.7 requires that the RCS be sampled for the m Do,e Equivalent 1-131. O g
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24 Direct Chemistry to per fonn all of the following: Z T Sampic both steam generator het legs for activity. O
*Il PERFORM Primary Sampling Instructions. 3" 740P-9SS01, to sample the RCS for boron concentration. >
--I m
PERFORM Reactor Coolant System Specific Activity ] Surveillance Test,74ST-9RCO2. between 2 and 6 hours 7 after the trip. O PERFORM Operaticn of the Post Accident Sampling Z System,740P-ISS02, beginning with Step 4.1, to place the l'~ 4 PASS in service.
EXCICSS STEAM I)EM ANI) 4 I ICP- 1 IR 004 Revision 00.04 PVNGS Page 6 of 87 Total 234 CRS ACTIONS CRS DETA!LS 3.0 l',VI:NT C()NTR()l, 3.1 Ensure that an MSIS has actuated. T 3.2 Ensure that the secont:arv operator aligns luth steam generators O
"U for hot leg sampling. -
Z
~m 3.3 Infonn Chemistry of the statos of systems needed to suppoit if the nuclear cooling water system is NOT operating. O sampling. TilEN RCS and steam generator samples can not be drawn. 3 5
jf the nonnal chilled water system is NOT operating. 3> DR NAN-SO5 is de-energized, d TiiEN infonn Chemistry to use attemate sample cooling for stcaro generator samples and 1%SS for RCS samples. .g O Z r-
14',XCESS STEM,1 I)l01 A NI) 41 El'-I R 0 0 4 Revision 00.(M PVNGS Page 7 of 87 Total 234 CRS ACflONS_ CRS DETAILS 3.0 EVI;NT CONTRt G. (root.)
- 3. l IF, at any time during this pr o<;cdure, pressurizer picssure is below the safety injecnon setprint. n TilliN cnsure that all of the following conditions exist: O~
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_. A SI AS and a CI AS lu.s actuaicd. Z "T1 No more than 1 RCP i. operating in each loop. O Sec IIPSI Delivery Curve, on the control board. I Acceptable IIPSI flow is established to the RCS. 3 SESS indicates that the safety injection components are in their >
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actuated condition. O SESS indicates that the containment isolation valves are closed. Check that une of the following conditions exists: g SESS indicates that at least I containment isolation valve i 0 each automatically isolated penetration is closed. Z r-The valves in any open penetrations have been overridden 4 open as required by plant conditions.
EXCESS STEA AI DEM AND 41 EI'- 111004 Revision 00.04 PVNGS Page 8 of 87 Total 234
.CKL\CI'lONS CRS DETAILS 3.0 EVENT CONTROi, (cont.)
CA UTION T Maximizing the charging and safety injection flows may canse the pressurizer to overfi'l, which in turn may cause an RCS pressure O excursion upon RCS heatnp. Throttling or terminating flows may be necessary to prevent overfilling the pressurizer. D Z 3.5 IF a SIAS and a CIAS have actuated, T IllEt! continue in this pmcedure. IE 1191 TlIEN GO TO Step 3. I6 in this procedure. 5 l -4 i b Z , O. l Z i r-i -< I 1 h
EXCESS STEAM I)IGi ANI) 41 EP- 1 It 004 Revision O(UM PVNGS Page 9 of 87 Total 234 C R S A C I'l O N S CRS DETAILS 3.0 1:VI:NT CONTitOL (cont.) C A UTIO N m Running the saf ety injection pumps on miniflow for lont;cr than I hour may cause pump damage due to overheating. O 33 C A UTION Z T llaving only I llPSI injection valve per train in a throttled position will minimize crosion damage, s: 3.6 IE all of the llPSI thmttle criteria have been met, Check that all of the following IIPSI throttle criteria are met:
- -TilliN direct the primary operator to throttle llPSI, while mainUining the 1 IPSI th'rottle criteria. RCS subcooling is above the minimum subcooling limit. O See Nomial Containment RCS Pfr Limits [Ilarsh .Z Containment RCS P/r Limitsj, on the control board. O Z
RVLMS indicates that the RVUll level is at least 16% r Pressurizer level is being maintained above 337c[40701 At least I steam generator has a level above 2% !!37ol WR and is maintaining RCS heat removal.
v EXCESS STEAM DEM AND 41 E P-1 R 004 Revision O(UM PVNGS Page 10 of 87 Total 234 l 1:RS ACTIONS CRS DETAILS 3.0 EVI:NT CONTROI. (cont.) 3.7 Stcp5 3.7 and 3.3 - PC may be thmtlling flPSI. m O 3.9 IF tmth of the followin : conditions exist: y IIPSI train A has been throttled. Z T-
@t IIPSI injection valves are closed. O -
3 TilEN direct the primary openitor to override and stop IIPSI g pump A. p
.i 3.10 IE hit lof the following conditions exist:
IIPSI train 13 has been throttled. O Z
-All 4 IIPSI injection valves are closed. r-TIIEN direct the primaiy operator to override and stop llPSI pump II.
3.11 IF all of the llPSI throtric criteria can NOT be maintained. TilEN cusure that all cf the following conditions exist:
- 1. t\H availabic 1 IPSI pumps are running.
- 2. All of the llPSI throttle valves are fully open.
- 3. Acceptable IIPSI flow is established to the RCS. See IIPSI Delivery Curve, on the control board.
41EP-1R004 Revision 00.07 PVNGS Page i1 of 87 Total 234 EXCESS STEAM DEM AND CRS DETAILS
.CRS_ACrl_QfiS_
3.0 EVENT CONTROL (cont.) _ . ..___ .___......___....._____......_....__..........____..__..._...--NOTE----------------------------- - - - - - - - While in Mode 3 with pressurizer pressure greater than 1837 psia [1620 - 2047 psia), the corrtet position of the LPSI throttic valves must be y verified within 4 hrs following the completion of each valve stroking operation per Tech Spec Surveillance Requirements 4.5.2.g. O 3.12 lE a SI AS has actuated, 7 AND_ pressurizer Pressure is grea!cr than 260 psia [300 psial and m stable or increasing, O THEN perfonn d of the following: D E
- 1. Direct the primary cocrator stop all operating LPSI pumps. p
- 2. Direct the primary operator close all the LPSI injection valves.
.1 O
- 3. Ensure that the position verification LCO requirements are Calculate the time 4 hours after the LPSI throttle valves are closed. Z met within 4 hours after the LPSI injection valves have Time that the LPSI throttic valves are closed.
O been closed. r-
+ 4 hours
= time.
3.13 JE pressurizer pressurt can jiqI' be maintained above 260 psia [300 psia],TIIEN perfonn all of the following:
- 1. Dirret the primary operator start a(( of the available LPSI pumps.
- 2. Direct the primary operator open !v_th of the LPSI injection velves for _any.cf the LPSI pumps that are running.
- 3. Ensure that acceptab!c LPSI flow is established to the RCS. See LPSI Delivery Curve, on the control bean!.
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I. (cont.) . ____ __ _-.____________________________.______..______-N()TE.-------_------_-------------_----_--_---_----__-----_----------__--_----
m Stabilizing Tc prevents an uncontrolled picssuriter level increase which coukt result in possible solid plant operations or lifting ofO the pressurizer safety valves. m 2 3.16 IE pressurizer pressure reaches 2300 psia [2150 psial, T TilEN perform both of the following: O 2 Ensure that the primary operator maintains pressurizer pressure S below 2300 psia [2150 psial. 3> Enstne that the secondary operator stabilizes Tc in the loop with d O the highest pressure steam generator. Z O 3.17 Steps 3.17 tuul 3.13 - 50 is stabilizing Tc in the loop with the highest pressure srcarn generator. ( 3.19 l'O is maintaining pressuri:crpressurc less than 2300 psia (2150 psia].
41 EI'-I R 004 Revision 00.04 PVNGS Page 14 of 87 Total 234 EXCESS STEA A1 1)ESI ANI) CRS ACTIONS CRS DETAILS 3.0 EVENT CONTROI. (cont.) 3.20 if, at any time dining :his piocedure,;nty of the following conditions c.xist: 7
.O Minimum RCS nibcooling is NOT acceptabic. See Nonnal Containment RCS P/r Limits [Ilarsh Containment y RCS P/r Limits], on the contial board.
Z . RCP NPSli is NOT acceptable. See RCP NPSil Curve, on the control board. m O CSAS actuates. T E~ TiiEN cnsure that the primary operator stops al.1 of the operating >
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RCPs. - O, 3.21 IF any RCPs are runni ig, AND RCP annunciator windows are in alann for running RCPs. O TilEN direct the,primar'y operator to evaluate guy RCP Z r"" annunciator window that is in alarm. -<
41 E P- 1 It 004 Revision 00.01 PVNGS Page 15 of 87 Total 234 EXCMSS STEAM I)EMANI) CRS ACTIONS CRS DETAILS 3.0 EVENT CONTROL. (cont.) Evaluate the itWT level and charging system status and GO TO Perfonn the decision table below: 3.22 the applicable Step in this procedure. n O O RWT level below or approaching 73% RWT level below or approaching 20% l_ RWT Icvel stable ;I and above 73% " T1 O No charging pump SFP level above No charging pump - g CIIN-ilV-536 CllB-V327 SFP level above alann setpoint suction paths availabic alami setpoint suction paths availableg CRS chooses to ClIA t01 and PCN-V215 CRS chooses to stop charging PCN-V215 stop charging d CilN-UV-501 0 CII A-V755 ~
'-7 CilN-V144 CllN-V144 CllA-P01 CilB-P01 and 0 CilB-V756 ,
, g ClIll-Pol r CilE-Pol CIIE-P01 and CilN-IIV-532 CIIN-IIV-532 .
CllE-V757 CIIA-P01 CIIA-P01 Cllti-Pol CIIB-Pol CilE-P01 CiiE-P01 GO TO Sicp 3.26 GO TO Step 3.25 GO TO Step 3.26 GO TO Step 3.23 GO TO Step 3.24 GO TO Step 3.25 in this procedure. in this procedure. 'in this procedure. . in this procedure. in this procedure. in this procedure.
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. _ . s EXCESS STEAM 1)EMANI) 41 E P- 1 It 004 Revision 00.04 PVNOS Page 17 of 87 Total 234 CRS ACTIONS CRS DEFAILS
.\ . it I?.Vl{NT CONTROL, (cont.)
3.25 IF the RWT level is NOT sunicient for charging ptunp operation, AND charging pump suction must be maintained. n TilliN perform both of the following: O "U
- l. Direct the primary operator to transfer charging pump Z -
suction to the SIT.
"n
- 2. GO TO Step 3.27 in this pmcedure.
O "O 3 3.26 IE the CRS chooses to stop charging. )> Oil charging pump suction can NOT be tnaintained, _-i TlIEN direct the primary operator to perfonn both of the O following: g Isolate RCP seat blecdorr. O Z I'~ Place all of the charging pumps in PULL TO LOCK. -< 3.27 Direct the secondary operator to align instnanent air to the containment. 3.28 IE nuclear cooling water is in service, AND pressurizer level is gicater than 33% [40(7el, TilEN direct the primary operator to open the letdown containment isolation valves. 3.29 IE the letdown containment isolation valves arc open, TilliN direct the primary operator to restore letdown.
. - ~ . . . . - ._- -- - -
4 I EI'-I 1(004 Revision 00.01 PVNGS Page 18 cf 87 Total 234 EXCESS STEAM I)IGIANI) CRS DETAILS fRS A_CTIONS 3.0 EVENT CONTROI, (cont.)
.. ..........................._................._.__.............-NOTE----------------------------------------------------------------------------
"T1 An excess stearn demand may affect both steam generators. When both steam generators are affected, the least affected is considered intact. The most affected ste:un generator is considered to be f:ndted. The faulted steam generator will have lower pressure and Icvel than O "O
the intact stemn generator. _.__. ..____ ...___..________...___-...____...__.____..._.____...__... NOTE-------------------------------------------------------------------------- E "r1 O Before the fanited steam generator dries out,its RCS loop Tc will l'e the lowest. After the faulted steam generator dries out,its RCS loop "U Tc will t c the highest. 3 3.30 Ensure that the secondary operator identifics the steam generator Evaluate all of the parameters in the table below for each steam d that is faulted. generator te identify the faulted steam generator: .O Z Parameter S.tc_a.m Generator i Steam Generator 2 O,, I-Lowest steam generator pressure .. Lowest RCS loop Tc (before steam generator dryout) Ilighest RCS loop Tc (following steam generator dryout) Lowest steam generator level Record the faulted steam generator .
v 41 EP-IltOO4 Revision 00.04 PVNGS Page 19 0f 87 Total 234 EXCESS STEAM DEM AND CRS DETAILS fRS ACTIONS 3.0 EVENT CONTROL. (cont.) _ _______________...___________....______________-____________---NOTE-----------_-------------------------------_-.-------------------------_--- An excess steam demand may af feet both steam generators. When both steam generators are affected, the Icast affected is considered n intact. The most affected steam pencrator is considered to be faulted.The faulted steam generator will have lower pressure and level than O m the intact steam generator. Z T1 3.31 Direct the secondary operator to isolate the faulted steam O generator. 3 5 Evaluate the parameters in the table below for the intact steam 3> 3.32 WilEN the faulted steam generator has been isolated, --j TlIEN ensure that theisolated steam generator is the faulted generator to ensure that the faulted steam generator is isolated: g steam generator. 2 Steam Ocncrator i Steam Generator 2 O Parameter .- I Pressure is stabilized or , recovering in the intact steam generator Level is stabilized or recovering in the intact steam generator Tc is stabilized or recovering in the intact RCS loop
4 I EI'-I ROO4 Revision 00.04 PVNGS Page 20 of 87 Total 234 EXCESS STEAM DIG 1 AND C R S A U i'l O N S CRS DETAILS 3.0 EVENT CONTRUi. (cont.) 3.33 IJf] the diagnosis was cenect and the f aulted steam genciator has 71 been isolated. O TIIIM GO TO Step 3.36 in this procedure. "U IF NOT,TIIIM direct the secondary operator to perform ;11!of Z the following: "T1
- 1. Restore the steam generator that was incorrectly isolated.
5
- 2. Isolate the steam f.cncrator that was incorrectly diagnosed >
as being intact. --i
- 3. Record the faulted steam generator. Steam generator faulted . O' Z
'O 3.34 50 may be restoring the incorrectly isolated stcain gencrator.
I"" 3.35 SO may bc isolating the stcom generator that was considcred intact.
EXCESS STEAM DEMAND 41 E P-1 R 004 Revision 00.m l'VNGS Page 21 of 87 Total 234
!HS ACI'lONS CitS DETAILS 3.0 EVENT CONTitol, (ctmt.)
............................................._.._.....__...._.........--NGTE-...-----------------------------------------------------------------------
Ispiipment that has bcen overridden will retptire manual restoration should conditions degrade to the point where automatic actuation n should take place. O ___. ..................___ ..____......___............... __...__.....__...... __..____ .._____.._.._ ...... .___._-_ ....______________ ._____.-_____ ..__________ g
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3.36 Direct the primary operator to check that containment pressure is Z less than 8.5 psig. . "T1 O o 3.37 IE a CS AS has actuated. K AND the containment pressure is icss than 7.0 psig, > TilEN direct the prima,y operator to override and stop CS. d O Z-3.38 IE the CS pumps were placed in override, AND the containment pressure increases to 8.5 psig, O TilEN direct the primary operator to re-initiate CS. Z r-3.39 1E a CS AS has actuated. Ti1EN direct the secondary operator to stop 1t1! of the containment fa ns.
41 El'-1 R004 Revision 00.01 PVNGS Page 22 of 87 Total 234 EXCESS STEAM I)EM ANI) CRS ACI'lONS_ CRS DETAILS 3.0 EVENT CONTR()l, (cont.) 3.10 WilliN reactor power has decreased to 2 x 10+%, "T1 TilliN perform both of the following: _O Calculate the time I hour after the reactor tripped. "U
- l. l(nsure that, within I hour of the reactor trip, both of the -
startup channel high neutron flux alarms are operable. Time of the reactor trip (from the Z T CRS Safety Function Flowchart) O
+1 hour: .0
= hours. 5 3>
.d
- 2. Direct the primary operator to CONCURRENTLY PliRFORM Ikiron Dilution Alarm Channel Check, O-Attaciunent A-3 to the Primary Operator Actions. Z O
Continue in this procedure. g t-* Direct an STA or a reactor operator, other than the primary or 3.41 11] informed that the channel check indicates an inoperable neutron flux alarm, secondary operator, to PERFORM Startup Channel liigh TilEN ensure that the LCO action requirements are met. Neutron Flux Alarm Inoperable 3.1.2.7, 41ST-lZZ24, beginning with Step L1. 3.42 lE less than 4 RCPs are running, TilEN cnsure that the primary operator places the pressurizer spray valves in M ANU AL 3.13 l'O may he perfanning Spray Valve Actuarian Data Shect.
~ - - .
v EXCICSS STEAM DEM AND 41EP-1 ROO4 Itevision 00.07 PVNGS Page 23 of 87 Total 234 C!1S ACTIONji DRS DIsrAILS 3.0 EVENT CONTitOL (cont.)
.....................................................................-----f4OTE-------------------------------=- ------- ------------
Stabilizing Tc prevents an uncontmiled pressurizer level increase which could msult in possible solid plant operations or lifting of the pressurizer safety valves. r1 O II 3.44 .III the faulted steam geremtoris above 2% [13%) WR level. - AND the condenser is available, 2 T TilEt! direct the secondary operator to align the faulted steam generator for high rate blowdown to the condenser. O 7 E
.i O
Z O Z r- -we- ,e - ev_-- +- --
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. w EXCESS STEAM I)EM ANI) 41 E P-1 R 004 Revision 00.04 PVNGS Page 24 of 87 Total 234 i:R5 ACilONS CRS DETAILS 3.0 EVI:NT C()NTitt)', (cont.)
3.45 IF the ADVs or AFA-P01 are being used, r1 Tillitiinfonu Radiation Piotection and the RMS technician of the steam release. O 33 IF both of the following 13.8 kV buses me de-energized: Z-3A6 TI O N AN-SO I. '33 s N A N-SO2. Ti!EN direct an operator to CONCURRENTLY PERFORM
-j Emergency Operations. 41EP-lEOui, Appentlix V, o Preparing For and Restoring Offsite l'ower, beginning with z Step 1.1. O Z
3.47 Check that aji Section 3.0 steps have been addressed. Q
5 w 41 E I'- I R 0 0 <l Revision 00.04 PVNGS Page 25 of 87 Total 234 EXCESS STEAM I)EMANI) CRS ACTIONS CRS DETAILS 1.0 Pl> ANT STATUS POINT i? -tivity Control is satisfied, Check that the conditions from at least 1 of the columns,in the 4.1 TilliN continue in this procedure. table below, are met: T1
-O IF NOT,TilEN direct the team to GO TO Emergency 3"I Operations,41EP-lEOOI, beginning at the entry to the 2 Safciv Function Flowcharts.
- 71 O
All CliAs are inserted 11 oration rate is greater than 40 gpm . Reactor power is less than 10-4% h..- Adequate shutdown margin is established . RCS boron concentration is greater than 2150 ppm C) e. C) Reactor power is decreasing Reactor power is decreasing Reactor power is decreasing 7 - r Reactor power is constant <
l i j %' l
.i ' P- 1 R 004 Revision 00.(M PVNGS Page 26 of 87 Total 234 I(XCESS STEAM DEM AND i
CRS del' AILS CRS M7110NS d 4.0 Pl.A NT STATUS l'OINT (cont.) Check that all of the following criteria are rnet: 4.2 IE Maintenance of Vital Auxiliaries is satisfied, n Till!N continue in this procedure. Main turbine is tripped. O IF NOT, Tlll!N direct 'he team to GO TO Einergency x Generator output breakers are open. Operations,4111P-11!O01, beginning at the entry to the Z Safety Function Flowcharts. All of the buses in at least 1 train in the table below,:tre "TI cnergized: O llus Train A Train B > 1 4.16 kV HUS PBA-503 PBB-SO4 5 2 ' 120 Vac IlUSES PNA-D25 PNB-D26 O PNC-D27 PND-D28 2: r PKA'-M41 PKU-M42 125 Vdc UUSES PKC-M43 PKD-M44
41 El'- l it O O 4 Revision 00.01 PVNGS Pagc 27 0f 87 Total 234 EXCESS STEAni DIGI ANI) CRS ACTIONS CRS DETAILS 4.0 l'i, ANT ST ATUS l'OINT (cont.) Check that aji of the criteria are met for the existing pressurizer 4.3 !!j RCS Picsstne and inventory Control are satisfied, TilF.N continue in this procedure. Icvel condition listed in the table below: , m O IF NOT, Till!N direct the team to GO TO Emer gency y Operations,41EP-il!OOl. bc< Jinning at the entry to the Z Safety Function Flowcharts. "T1 0
~
Pressurizer icvel below 10 % 125 %1 3 _ Pressurizer level between 10 and 70% 125 - 74%1 5 RCS subcooling is acceptable. RVLMS indicates that the Outlet Plenum level is aQ- > least 21%. i _ See Nonnal Containment RCS P/r Limits y lilarsh Containment RCS P/r Limitsi, on IIPSI flow is acceptabic. - , the c.ontrol boani. #~ See IIPSI Delivery Curve on the control board. O bill availabic charging pumps are running. 2 RVLMS indicates that the Outlet Plenum level r ' is at least 21%. ~ Charging and Ictdown, as available, are restoring pressurizer Icvel. At least 1 of the following conditions is met: ilPSI flow is acceptable. See IIPSI Delivery Curve on the control board. IIPSI throttle criteria have been met.
41 El'- 1 R 004 Revision 00.04 PVNGS Page 28 of 87 Total 234 EXCESS STEAM 1)EM AN1) CRS DETAILS ('RS MTION.S 4.0 l'i, ANT STATUS :'OINT (cont.) A. Calculate RCS operating loop AT. Th P 4.4 lE Ileat Removal is satisfied. TlIEN continue in this procedme. c P T IF NOT.TilliN direct the team to GO TO Emergency O ____ Operations. 41!!!'-11iO01. beginning at the entry to the = RCS operating loop AT T p Saf ety 1 unction Ilowcharts B. Check that all of the critcria are met for the existing RCP Z condition listed in the table below: m O
-3 At least 1 RCP runnine -
No RCPs runnine b.= RCS loop AT is less then 10'F [17"Fl. RCS loop ATis less than 57 F [74 Fl. 4 REP CET temperature is less than 600 F [610'Fl. O RCS Te is less than ' 70 F [358 Fl. c. RCS Tc is stable or decreasing. REP CET temperature is stable or decreasing. O Z r-C. Check that the intact steam generator meets the criteria for the-< existing level condition listed in the table below: 2 Steam Generators Available 1 Steam Generator Available - SG WR_ Level Enough now to maintain the steam generator Enough flow tr naintain the steam generator Above 72% 1787cl WR Icvel between ,2 and 80% [78 - 847cj WR level between 72 and 80% [78 - 84%) WR Between 2 and 72% At least 250 gpm or 0.14 x 106 lb/hr At least 500 gpm or 0.28 x 106 lb/hr fccdwater flow feedwater How i 13 - 787cl WR Between 250 and 1500 gpm or between Between 500 and 1500 gpm or between Below 2% i137cl WR 0.14 x 106 lb/hr and 0.83 x 106 lb/hr 0.28 x 106 lb/hr and 0.83 x 106 lb/hr
4 I E P- 1 It 004 Revision 00.04 PVNGS Page 29 of 87 Total 234 EXCESS STEAM DIG 1 AND CRS ACTIONS CRS DETAILS 4.0 l'I, ANT STATUS "OINT (cont.) Check that ;til of the following criteria are met: 4.5 lij Containment integri:y is satisned, TilEN continue in this pmcedure. m At least i of the following pressure criteria is met: O 11 NOT, TilliN dircct .hc tearn to GO TO Emergency x Containment pressure is less than 3.0 psig. _ Operations,41EP-iliOOl, beginning at the entry to the Z Safety Function Flowcharts. CIAS has actuated. m O None of the following available containment radiation % monitors are in ALERT or 111G11 alann: E RU-l or alternate. RU- 148. -j O R U -16. R U- 149. g RU- 17. O Z None of the following available steam plant radiation F 4 monitors are in ALERT or 111G11 alann: RU- 139. RU-140. RU-141. One of the following conditions is met: No ALERT or 111G11 alann on RU-4 or RU-5. Chemistry sampics indicate no increased steam generator tube leakage.
4 I EP-I R004 Revision 00.04 PVNGS Page 30 of 87 Total 234 EXCESS STEAM DEM AND CRS DETAILS [RS ACTIONS 4.0 Pl. ANT STATUS l'OINT (cont.) Check that at least I of the following containment pressure criteria 1.6 IE Containment Atnnnpherie ('onnel is satisfied, TilEN continue in this pn*cetinie, is met: 71 O IF NOT, TilEN direct the team to GO TO Emergency Containment pressure is less than 8.5 psig. m Operations,41HP-liiOOi, beginning at the entry to the At least 1 CS header is delivering at least 3525 gpm. Z Safety Function I lowcharts. r1 O m 3
--i O
Z O Z r-
w I 41 El'- 1 R 004 Revision 00.01 PVNGS Page 31 of 87 Total 234 IGCESS STEAM I)EM ANI) CRS ACTIONS CRS DETAILS 5.0 l'I. ANT STAlllLIZATION 5.1 PO anal 50 arc l>cginning their normal response ta new abtrms. r1. O CAUTION D Oveniding an AFAS and thmitling now when the steam generator levelis below 27o [13%] WR may result in a loss of heat removal. "T1 Z O.
..................._...................................................... NOTE---.-~.---------------.--_-------------------------------------~~--------- p AFW valves that are in ovenide will not auto actuate. Operator action will be required to maintain the steam generator icvels.
_...__._ ...._.. ..______. .___. .....___..._______ ._______..-._____-__....___ ..____...____._____.-__ .. . ______.-____ --i Establi.sh the minimum required feedwater flow to the intact stcan6 5.2 IE an AFAS has actuated, TIIEN perfonninth of the following: generator as listed in the tabic below: g Ensure that the intact s: cam generatorlevel is being O
- 1. Z maintained. I-'
-G SG WR Level Flow Required Above 72% [7870] WR Enough flow to maintain the steam generator level between 72 and 80% (78 - 8470l WR.
Between 2 and 72% At least 500 gpm or 0.28 x 106 lb/hr feedwater How 113 - 7870] WR
- AFAS actuated and not throttled Below 27o [137o] WR Between 500 and 1500 gpm or between 0.28 and 0.83 x 106 lb/hr
- 2. GO TO Step 5.10 in this procedure.
41 EP-111004 Revision 00.04 PVNGS Page 32 of 87 Total 234 EXCESS STEAM I)EMANI) CRS DETAILS ClEM TlONS 5.0 Pl.A NT ST Allit,17, ATION (cont.) li' an AFAS has NO [ actuated, livaluate the tabic below and direct the secondary operator to GO 5.3 TilEN direct the secondary operator to ensure that an auxiliary TO the appropriate step to ensure that an auxiliary feed pump is y feed pump is placed in service. placed in service: g 71 Stait-up Auxiliary Feedwater Essential Electric Driven Essential Steam Driven Z Pump, AFN-P01 Auxiliary Fcedwatcr Pump, Auxiliary Fcedwater Pump, T1 AFB-P01 AFA-P01 O
- D
- G Direct the secondary operator Direct the secondary operator Direct the secondary operator :>
to GO TO Step 5.4 in his to GO TO Step 5.5 in his ;-j - to GO TO Step 5.7 in his procedure, to start AFN-Pol. procedure, to start AFB-Pol. procedure, to start AFA-POI. O Z O 2 5.4 Steps 3.4 aml 5.5 - SO may be placing an essential AFW pump in scrvice. Q 5.6 lE Essential Steam Driven Auxiliary Fecdwater Pump, AFA-P01, has been started, TlIEN infonn Radiation Protection and the RMS technician of the steam release. 5.7 Steps 5.7 through 5.9 - 50 may be placing the startup AFW plung in service.
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41 El'-I R O O4 Revision 00.04 PVNGS Page 34 cf 87 Total 234 EXCESS STEAM I)EM ANI) CRS DETAILS CRS A('TIONS 5.0 l'i, ANT STAlllll7.\ TION (cont.) _C2\ UTIO N 71 O Overriding an AFAS and throttling flow when the steam generator level is below 2% (i3%) WR may rcsch in a loss of heat removal. 33
.............................._....................................... NOTE.--------------------------------.-------.--------.-----.----------
O Al W valves that are in oveiride will not auto actuate. Operator action will be required to maintain the steam generator Icvels. 23 Establish the required feedwater flow to the intact steam gen
- 5.13 WilEN AFW has been restored to the intact steam generator, -
- TilEN direct the secondary operator to maintain the intact as listed in the table below:
O steam generator level between 72 and 80% l78 - 84%l. Z Continue in this procedure- O-SG WR Level Flow Required - y r' Above 72% [78%l WR Enough flow to maintain the steam generator .< level between 72 and 80% [78 - 84%J WR. Iletwecn 2 and 72% At least 500 gpm or 0.28 x 106 lb/hr feedwater flow [13 78%) WR Delow 2% {l3%) WR
- AFAS actuated and not throttled Betwecn 500 and 1500 gpm or between 0.28 and 0.83 x 106 lb/hr
41 EP-111004 Revision 00.04 PVNGS l' age 35 of 87 Total 234 EXCESS STEAM DEM ANI) CRS DETAILS URS ACIIONS 5.0 l'I, ANT STAllii lZ.\ TION (cont.) 5.11 Direct the primary opetator to place the hydrogen analyzers ir m service. O 23 5.15 l'O is rccorclin : the tirne the hyciro;;cn analyzers secre piaccelin Z Setrire. m O 5.16 IF a CSAS has occurred, S TilEN ensure Ilic prinnry' operator isolates blecdof f flow. >
-1 5.17 Direct the primary operator to maintain pressitrizer level Ittween O 10 an<l 707c 125 - 7<1%l anti trending to between 33 and 53% z
[40- 5070). O Z 5.18 Direct the secondary operator to stop the heater drain pumps. Q 4 - - . + mm w, - w ww --
41 E P- 1 R 004 Revision 00.01 PVNGS Page 36 of 37 Total 234 EXCESS STEAM DEM ANI) CRS DETAILS CRS ACTIONS 5.0 l'I. ANT STAllli IZ ATION (cont.) 5.19 IF all of the following conditions exist:
"T1 Establishing conting to the containtnent is desired. O l'lant cooling water is available.
"_U Z
y Nuclear cooling water is available. O At least I nonnal chiller is availabic. g 3 Containment pressure is below 7.0 psig. >
'IIIEtj direct the secondary operator to establish cooling to the d
containment. O Z O 5.20 Lil the NC water containment isolation valves are open. Z Tl.lEti direct the secondary operator to override and stait at least I'" l CEDM ACU. -< 5.2 i Step 5.21 and 5.22 - 50 may be sterting contaimncnt nonnal ACUS and a normal chiller. 5.23 Dirn t the secondary operator to align an auxiliary steam supply. 5.24 IE auxiliary steam is being supplied fiom the cross-tic header, TlIEN direct the secondary operator to shift gland seal fmm main steam to aur.iliary steam. . 5.25 Direct the secondary operator to restore gland seal to the main turbine.
- - . _-- . _ . . - _ . _ . . ~_
n mO2 Z MO % 5>1 O Z O Z r<- I t M n e Re m 4 Oh t n 3 F ia 2 Rt o t n _ l a E4 o v t o P - Y A C , T t h 7 Ln s r 8 Te a f . Nm l I o k Eh [ s 7 c Rc a 3 S o Rt t h imdr c L I s UtA i t A l C La P a T a m Nt e ro
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R e nh t A poS t ta n r e C Z ioi cig a er . M ot i n ptabe g pe y a e I A L r r o r n olb E i t a d pp em ye r prd i w ya r t ap T l A nOp o i t a lo mec S T c e yE i imOo r y e c l o i r c S pcR F pa S s c eny r . eny ee S T h ea1 ht er hh E t gd . go t t N t r n 1 tc r t t n C A c e e op e e n e ci eh X L i mcet r e r mv r iit E P DESS iDEIn Dw 6 7 8 2 2 2 5 5 5 0 5
u.. EXCESS STEAM DIGI AND 41 EI'-l R OO4 Revision 00.01 PVNGS Page 38 of 87 Total 234
,HS AgiONS CRS DETAILS 5.0 l'I, A NT ST Al?II,1Z ATIG N (cont.)
5.29 .lF the containment pressure incicases, A. Evaluate the containment pressure on Iall of the following: Tlliiti ensure that the containment pressure is being controlled. m IICA-PI-351 A. IICC-PI-351 C. O IICD-PI-351 D. 3 IICB-PI-351 B. E T B. Direct the primary operator to perfonn the operator actions in the table below, after evaluating the highest valid containmen pressure: Ind' ated Containment Pressure Oncrator Actions .. 4 Above 3 psig Ensure that a SI AS and a CIAS have actuated. Itetween 3 and 8.5 psig Ensure that wie of the following conditions exists: o7
- 1. At ! cast 2 containment air handling units and at j; least 1 CEDM fan are in service. .
- 2. At least 1 CS header is delivering at least 3525 ppm.
Above 8.5 psig Ensure that a CSAS has actuated with all of the following conditions met:
- 1. At least 1 CS header is delivering at least 3525 gpm.
- 2. The hydrogen analyzers are operating.
- 3. All RCPs are stopped.
5.30 Check that all Section 5.0 steps have been addressed.
41 EP-I R O O4 Revision 00.04 PVNGS Pagc 39 0f 87 Total 234 EXCESS STEAM DEMAND CRS DETAILS CRS ACTIONS 6.0 l'i, ANT STATUS i>OINT Chcck that the conditions from at least 1 of the columns,in the 6.1 lij Reactivity Contiof i; satisfied, table below, are met: 31 TilliN continue in this procedute. O y IF NOT, TIIEN direct the team to GO TO ICinergency Opci ations,411?P-ll.001, beginning at the entry to the Z Safet.y Function Flowcharts. "T1 0 3,1 Iloration rate is greater than 40 gpni Reactor power is less than 10-d% g All CEAs arc inser ted Adequate shutdown margin is established RCS baron concentration is greater than 2150 ppm O c . O Reactor power is decreasing Reactor power is decreasing st . Reactor power is decreasing I Reactor power is constant < . .. . -. - .. . . - . . . - . -. , .-. . ~ . - - . - -. -.
41 E P-1 It 004 Revision 00.04 l'VNGS Page 40 of 87 Total 234 EXCESS STEAM DESI ANI) CRS DETAILS CRS ACTIONS 6.0 Pl,A NT STATUS l'OINT (cont.) Check that all of the buscs in at Icast I train in the table below, are 6.2 111 Maintenance of Vit.,1 Auxiliaries is satisGed, m TlliiN continue in thi:. procedure. cuergized: , O D3 IF NOT,TIIEN direc: the Icam to GO TO Emergency Train B Bus Train A : Operations 411!P-il!OOl, beginning at the entry to the d-Safety Function Flowtharts, PBB-SO4 M 4.16 kV BUS PBA-S03 O 120 Vac BUSES PNA-D25 PNibD26 23 1.
..PNC-D27 PND-D28 >i, 125 Vdc BUSES PKA-M41 PKB-M42 6 Z
PKC-M43 PKD-M44 O E r-
m.. PVNGS Page 4I of 87 Total 234 EXCESS STEA Al 1)ESIANI) 41 El'-1 It 004 Revision 00.02 CRS DL~ RAILS CRS ACTIONS 6.0 l'i, ANT ST ATUS l'OINT (cont.) Check that all of the criteria are met for the existing pressurizer 6.3 lj' RCS Pressure and Inventory Control are satisfied, level condition listed in the table below: m Tlll(N_ continue in this prnedute. O D JF NOT, TilEN direct the team to GO TO Emergency ._ Operations,41EP-lEOol, beginning at the entry to the Z Safety Function Flowchatts. T U
"Il Pressurizer level below 1070125701 Pressurizer level between 10 and 707c l25 - 747o1 _ 5; RCS subcooling is acceptabic. RVLMS indicates that the Outlet Plenum level is -ak l
~
least 211 Sec Nonual Containment RCS Pff Linn_ lilarsh Containment RCS P/r Limitsi, on the control IIPSI flow is acceptabic. 6-, board. Sec IIPSI Delivery Curve on the control board. C ' RVLMS indicates that the Outlet Plenum level All availabic charging pumps are running. 2l is at least 211 r Charging and letdown, as availabic, are restoring pressurizer Icvel. At least 1 of the following conditions is met: ilPSI flow is acceptable. Sec IlPSI Delivery Curve on the control board. IIPSI throttle criteria have been met.
41 El'- 1 R 004 Revision (X).01 PVNGS Page 42 of 87 Total 234 EXCESS STEAM DEM AND CRS ACTIONS CRS DETAILS 6.0 l'la\NT STATilS l'OINT (cont.) A. Calculate RCS operating loop AT. Th F 6sl IF ileat Remova! is satisfied. Till!N continue in this preecdure.
- T'- "F m IF NOT,TlIEN direct the team to GO TO Emergency O Operalions,4111P-1 EODI. beginning at the entry to the = RCS operating loop AT F 0 Safety F, unction Flowcharts.
II. Check that all of the criteria are met for the existing RCP k condition listed in the table below: T O JJ At leastl ILChunnine No RCPuunnine g RCS loop AT is less than 57"F [74 F). __RCS loop AT is less than 10F [17 F]. { REP CET temperature is less than 600 F [610 Fl. RCS Te is less than 570 F 1558 Fl.
~
RCS Tc is stable or decreasing. REP CLT temperature is stable or decreasing. O 2.' r" C. Check that the intact steam generator meets pfl of the criteria -< for the existing level condition listed in the table below: SG WR Level 2 Steam Generators Available 1 Steam Generator Available Above 72% 178%) WR Enough flow to maintain the steam generator Enough flow to maintain the steam generator level between 72 and 80% l78 - 84%} WR Icvel between 72 and 80% [78 - 84%l WR lictween 2 and 72% At least 250 gpm or 0.14 x 106 lb/hr At least 500 gpm or 0.28 x 106 lb/hr [13 - 78%) WR reedwater flow feedwater flow Below 2% l13%) WR Between 250 and 1500 ppm or betwccn lletween 500 and 1500 gpm or between 0.14 x 106 lb/hr and 0.83 x 106 lb/hr 0.28 x 106 lb/hr and 0.83 x 106 lb/hr
v 41 El'- 1 R 004 Revision 00.04 PVNGS Page 43 of 87 Total 234 EXCESS STEAM 1)EM ANI) CRS DisFAILS GRS ACTIONS 6.0 Pl, ANT STATUS POINT (cont.) Check that at least 1 of the following pressure criteria is met: 6.5 11 containment isolation criteria for Containment Integrity is 'm satisIied, Containment pressure is less than 3.0 psig. O
'llIEN continue in this procedme. Jl IF NOT,TilEN direct the team to GO TO Emergency CI AS has actuated.
Z-Operations,41 EP-lEOOl, beginning at the entry to the Il O Safety Function Flowcharts. o ' A. Evaluate any alann on ;all of the following containment g 6.6 E containment radiatien monitors criteria for Containment radiation monitors that are in service: p intepity is satisfied, y TilliM continue in thir procedure, RU-l or alternate. RU-148. - O IF NOT.TilEN direct the team to GO TO Emergency _ RU- 16. RU- 149. Z Operations,41EP-liiOOi, beginning at the entry to the O Safety Function Flowcharts. RU- 17. , c r-- 11 . Check that none of the containment radiation monitors were evaluated have ALERT or Il!GII alamis: RU-l or alternate. RU- 148. RU- 16. RU-149. R U- 17. C. E no containment radiation monitors are available. Qil the CRS suspects that the containment radiation monitor indications are not correct, TllEN direct Chemistry to sample the containment atmosphere.
~
4 i EP-I R 004 Revision 00.01 PVNGS Page 44 of 87 Total 234 EXCESS STEAM I)EM AND CRS ACTIONS CRS DETAILS 6.0 l'i, A NT STATUS l'OINT (cont.) 6.7 E steam plant radiation monitors criteria for Containment A. Evaluate ;uty alann on ;11 1 of the following steam plant intepity is satisfied, radiation monitors that ate in service: m Tilliti continue in thie procedute. O R U- 139. RU- 140. R U- 141. 0 E NOT.TilEN direct the team to GO TO Emergency Z Operations,41EP-lEOOl. beginning at the entry to the R U- 4. RU-5.
~T1 Safety 1:nnetion Howcharis O B. Check that none of the steam plant radiation monitors that 3 were evaluated have ALERT or 111G11 alanns: E 3>
RU- 139. RU- 140. RU-141. d O RU-4. RU-5. z O C. E no sicam plant radiation monitors are available, Z Qll the CRS suspects that the steam plant radiation monitor Q indications are not correct, TilEN direct Chemistry to sample the steam generators.
i i a mO7 gmOxE>1 O - Z O Z r<- r i te r c . 4 er m 3 p 2 u g s s la t e r 5 o p 2 5 T t ig 3 - n t 7 e s s 8 m p a - r 0 n 5 le . ia 8 t a 5 t 4 S n n g e L o a ,n g a IA c g ht n e P T n s v s E i w e ,h . e D l l o i s d . S s t i lo f e r
,i r _
C e u s e - ht s d S e a f r e G o p h N 1 t n S V t s e C l' a m 1 le n t s 1 t a ia a 0 t e t a n l 0 0 ht o t n C A kt: . io ce ~ i s h em _ v Ci s t e I 4 . O O t l I l' E e yh 1 ct 4 no et gy d, r r et G e men F, e is t h a s Ot
) s Tt a
) S .
i l Oe Gi nn I t N n o N O o t r o n A I c n , ore t i I T ( Cud mge Gl ( A T N ic e r c t ab e ,s
) S eo l t heOa I r I
R O h r p p t Oh C P e M oi t E: w t . mh e1 A S J t r i'l
- o Ai n t .
E t diF l T T t e Nin l S A nu !d o T en ll ,it S mit sc S io nn iTnn S T . iou E N ta c Tt F . C nN oE Ortny - A, C l Neepf a G I I l Fl Ii F I OS S. 6 0 6
v r 41 El'- 1 R 0 04 Revision 00.01 PVNGS Page 46 of 87 Tota! 234 EXCESS STEAM 1)lG1 ANI) CRS DETAILS CRS ACTIONS 7.0 SYSTEM ENIIANCEMENT 7.1 WIIliN plant conditions and personnel availability pennit n addressing locked in alanns without adversely affecting the plant O recovery, D TilEN direct an operator to perfonn both of the following, as - tiine pennits: Z T
- l. Review all hrked in alanns.
~
O
~D
- 2. Ensure that the appropriate alarm response actions have S been taken. 3>
_--I Continue in this procedure. O Z
- 7. 2- li' otbite power has been lost, O AND has been restored to the stanup transfonners, Z TilFN direct an operator to PERFORM Einergency . F Operations,4111P-lEOOi, Appendix V, l'reparing For and 4 Restoring Offsite Power, beginning with Step 2.1.
7.3 If at least 2 RCPs are running, TlIEN GO TO Step 7.12 in this procedure.
EXCESS STEAM I)EM ANI) 41 E P-1 It 004 Revision 00.04 PVNGS Page 47 of 87 Total 234 CRS ACTIONS CRS DETAILS 7.0 SYSTEM ENil ANCEMENT (cont.) C A UTION
. ri Major seal failure may occur if the RCPs are restarted after gitltel of the following conditions: O l . Scal injection and cooling water were lost for longer than 20 minutes. U
- 2. Seal bicedof f was not stopped within 1 minute of the loss of cooling water and seal injection. -
RCPs should not be started if either of these conditions has occurred, except to prevent core damage. Z TI O 7.4 IF the RCP seal operating limits have NOT been exceeded, Check that both of the following conditions exist: 5 lillitdecssary to run an RCP to prevent core damage, TilEN continue in this procedure. Seal injection and nuclear cooling water have been > interrupted to the RCP seals for less than 20 minutes. d IF NOT, TilEN GO TO Step 7.12 in this procedure. O Seal bleedoff was stopped within 1 minute of the start Z of the event. -O Z r-
+-
(T *1 W q
41 EP-l itOO4 Revision 00.04 PVNGS Page 48 cf 87 Total 234 EXCESS STEAM DIGI AND CRS DETAILS CRS ACilONS 7.0 SYSTl31 ENII ANCEMENT (cont.) 1 CAUTION T Operating RCP combinations of pumps I A and 2B, or pumps IB and 2A may cause RCP bearing damage. O y i
--------------------------------------------------------------------.--NOTY--------------------------------------
g 1 RCP operating in each loop is the optimal pump configuration to be used during emergency or recovery operations, ] if started, the preferred combinations are pumps 1 A and 2A, or pumps 1B and 2B. Check that allof the following conditions exist: 3> 7.5 Check that the plant conditions and equipment will support RCP --i
~
operahon. RCS subcooling is acceptable. O' Pressurizer pressure is above the NPSil limits. O At least I steam generator is maintaining RCS heat removalZ and has a level maintained above 2% [13%] WR. r-Power is availabic from NAN-SOI or NAN-SO2. Cooling water to the RCPs is in service. Check that at icast I of the following conditions exists: RVLMS indicates that the RVUII Icvel is 100% and pressurizer level is being maintained at or above 33% [40%). RVLMS indicates that the RVUll Icvel is 67% and pressurizer level is being maintained at or above 66% (81%I.
% moef i
41 E P- 1 It 004 Revision 00.01 PVNGS l' age 49 of 87 Total 234 EXCESS STEAM 1)EM ANI)
.CitS DETAILS CRS ACTIONS 7.0 SYSTESI ENII ANCESlENT (cont.)
7.6 if the plant conditions and equipment will NOT support RCP r1 opeiation. O Till(N GO'IO Step 7.12 in this procedure. 33 Ensure that allof the following prcrcquisites exist for cach RCP Z lij plant conditions and equipincut will support RCP operation, 'T1 7.7 Till!N direct the primary opera:or to establish the picrcquisites to be started: O. for statting RCPs. 3 Seal injection is in service. E 3> Seal blecdoffis in service. --I The oil lid pump has been running for 7 minutes. O TURll & GEN AUX TRIP & LO RELAY, G5/186R-1 an
~!
When star ting RCPs, a pressurizer level drop due to RCS void collapse and contraction may occur. A loss of pressurizer level control inay result in a loss of RCP NPSil and RCS subcooling. RCP and fuel damage may occur if the RCPs and the RCS O Z operate in this condition. O
.--.--....... Z.
................._..................................................... NOTE-------------------..---.------.-------.--.-- g I RCP operating in each loop is the optimal pump connguration to be used during emergency or recovery operations, if 2 RCPs are to b st;uted, the preferred combinations are pumps 1 A and 2A,or pumps 1B and 2B. .
7.10 WilEN the prerequisites for starting RCPs are established, TIIEN perform both of the following:
- 1. Infonn the other units that an RCP will be started and will affect dicscl generator operation.
- 2. Direct the primary operator to start 1 RCP.
V: 4 I E P-I R 001 Revision 00.04 PVNGS Page 51 of 87 Total 234 EXCESS STEAM DIG 1 AND CRS DETAILS GS ACTIONS 7.0 SYSTEM EN11 ANCEMI:NT (cont.)
. .. ______..__...-_____.__..._.___......__......_____...____.-_-N()TE-------------.-------------------_----_----------____-__--------------____
1 RCP operating in cach loop is the nptimal pump conf ~guration to be used during emergency or recovery operations. If'.1 cps are to be m statted, the preferred combinations are pumps 1 A and 2A, or pumps 1B and 2n. O "U Z
- 7. I I If only i RCP is running, 1 TilEN perfonn all of the followin"a: ---
O-
- 1. Infonn the other units that an RCP will be started and will f= '
alfcct dicscl generator operation. >
- 2. I'nsure that the RCS pressure and temperature are stable.
d O
- 3. Direct the primary operator to start a second RCP, Z l'referably 1 in the opposite loop O Z
r-7.12 IInsure that pressurizer icvel is between 10 and 70% [25 74%l < and is trending to between 33 and 53'70140 - 50%).
w 41 E P- 111004 Revision 00.04 PVNGS Page 52 of 87 Total 234 EXCESS STEAM DIGl ANI) CRS Dl? FAILS CRS ACTIONS 7.0 SYSTESI ENil ANf'EAIENT (cont.)
--.-----.-----------_------..--..--.--_--.-_-------------------NOTE--------------------------------------------------------------------------
Safety injection now into :Lc hot and zold legs will cause RCS Th and Tc to read lower temperatures than actually exist. m
------------------------.------------- g 33 Check that ;11.1 of the following conditions exist:
- 7. I 3 IF no RCPs are runnim;, Z TiiEN check that the conditions for natural circulation exist in the RCS loop ATis less than 57 F {74 F). m RCS toop with the intact steam generator. O Th P 33 E
- Tc P
= RCS loop AT T O Z
Th and Tc are constant or decreasing. O Z RCS subcooling is acceptabic. r"" See Normal Containment RCS Pfr Limits {Ilarsh -< Containment RCS P/r Limits], on the control board. The AT between RCS loop Th and REP CET temperature is less than 10 F(15 F.l. RCS loop Th 'P
- REP CET temperature T
= AT . __ P
s, 41 E P-I lt O O4 Revision 00.01 PVNGS Pagc 53 of 87 Total 234 EXCESS STEAM I)EM AND ('RS ACTIONS CRS DETAILS 7.0 SYSTEM ENII AN('EMENT (cont.) 7.11 IF no RCPs are runnin;;, AND natural circulation conditions do NOT exist, y Ti!Et! direct the team to(iO TO Emergency Operations, O 41EP-lE001, beginning at the entry to the Salcty Function 7) Flowcharts. Z m Check that the proper c<luipment has actuated for n actuated Direct an operator (s) to CONCURRENTLY PERFORM the O 7.15 37 safety signals. referenced appendix of Emergency Operations, 41 EP-l EOOl, for m safety signals that have actuated: E i Actuated Safety Sinnal Appendix 6 CSAS Appendix K, Verification of CSAS, beginning with Step 1.1 O SIAS Appendix G, Verification of SIAS, beginning with Step 1.1 Z " I" CIAS Appendix II, Verification of CIAS, beginning with Step 1.1 AFAS Appendix I, Verification of AFAS, beginning with Step I.1
..M S IS Appendix J, Verification of MSIS, beginning with Step I.I
=___ _ ____. -_-_- __-. . . - - -- --. . .. . . _. .
EXCESS STMAM I)EM ANI) 41 EP-1 R 004 Itevision 00.01 PVNGS Page 54 of 87 Total 234 Cl(S ACTIONS CRS I)ETAlt.S 7.0 SYSTICSI ENil ANCisSIENT (cimt.) 7.16 Check that the containment pressure is less than 7.0 psig, as IE a CSAS has actuateti. TilEN check that the CS AS reset criteria are met. indicated on all of the following available indicators: r1 O IICA-PI-351 A. "U IICB-PI-351B. U "T1 IICC-PI-351 C. O x IICD-PI-351D. S 3>
-l 7.17 IE a SI AS has actuated, Check that both of the following criteria are met: O TIIEN check that the SI AS reset criteria are met. z llPSI pumps are stopped.
O Containment pressure is less than 3.0 psig. Z
mO32 nZmO3E3 doz OZr<- i 2 - e r - a - s r _ 4 to n 3 i 2 n l o - a t t u % o n T : g i o t t 7 c is a 8 n p f i 0 ida o e r r 5 3 - a t n 5 S a n e e e L a g I ir ht m a A te s n P T I i r c s i a T e tn D g n l s o: e S i cn t R i w e r gna a n C o u inl a r e ll s S f o s e wI oI l t a r . G e p lloI G r o
. . 8 9 N ht t n
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EXCESS STEMi DEMAND 41 El'-1 It 004 Revision 00.0 : PVNGS Page 56 of 87 Total 234 1:RS ACTION!i CRS DETAILS 7.0 SYSTESI ENil ANCE AIENT (cont.) 7.19 IF the safety signal reset eriteria are satisfied, Direct the operators to CONCURRENTLY PERFORM the Till!N direct an operator to reset the safety signals and restore referenced appendix of Ernergency Operations, r etjuipment to standby. 41EP-1EOOl, for;1ny safety signals that have actuated and have O inct the safety signal reset criteria: "U dA Actuated Safety Sicnal Appendix 9 O CSAS Appendix Q, Resetting CSAS, beginning with Step 1.1 _k 5. SIAS Appendix M, Rer, citing SIAS, beginning with Step 1.1 3 ~ 1 CIAS Appendix N, Rcsetting CI AS, beginning with Step 1.1 6 2 O 7.20 IF a CS AS has actuate l. f Tillit{ continue in this pnxetinic. < IF NOI TIlEN GO TO Step 7.24 in this procetluic.
ili M P-I R 004 Revision 00.04 PVNGS Page 57 of 87 Total 234 EXCl?SS STEAM I)iCM ANI) CRS ACTIONS CRS DETAILS 7.0 SYSTES1 ENII ANCESlENT (cont.) 7.21 Place the hydrogen recombiners in service: T
- 1. linsure that at least I hydrogen recombiner is installed. IE the recombiner is NOT installed, .
O TIIEN direct hicchanical hiaintenance to PERFORh1 Ilydrogen U Recombiner Installation And Removal, 31h1T-911P01, beginning with Step 1.1. Z m O Direct an operator to PERFORN1 at least 1 oi the following U
- 2. Ilj the containment hydrogen is between 0.5 and 2Mo, 3 TIIEN place at least I hydrogen recombiner in service.
sections in Containment Ilydrogen Control And Ilydrogen Purge Exhaust System, 410P-lilP02: 3>
--I
~
Hegin with Step 4.1 for Train A Ilydrogen Recombiner. O Hegin with Step 8.1 for Train B llydrogen Recombiner. 2 O Z r-
41 EP- 1 R 004 Revision 00.04 PVNGS Page 58 of 87 Total 234 EXCESS STEAM DIGI AND CRS DETAILS OJS ACI'lONS. 7.0 SYSTEi\1 ENil ANCEMENT (ennt.) 7.22 E the containment hydrogen increases to 2.8% or ;;rcater, A. Ensure that the hydrogen purge unit is installed. AND the erncigency coonlinator concurs, m Till:N place the hydrogen purge unit in service. B. Direct an operator to PERFORM at least 1 of the following O sections in Containment Ilydrogen Control And x Ilydrogen Purge Exhaust System, 410P-IIIP02: - Z Begin with Step 6.1 for Train A Ilydrogen Purge Exhaust.T O Begin with Step 10.1 forTrain B Ilydrogen Purge % Exhaust. 5
- 3>
-i
~
7.23 E all of the following conditions exist: Direct an operator to PERFORM the following sections in O Containment flydrogen Control And Ilydrogen Purge g Containment hydrogen removal is in progress. Exhaust System, 4IOP-illP02: l O Begin with Step 5.1 for Train A Ilydiogen Recombiner.. Z Containment hydro;;en decreases to less than 0.5%. r-Begin with Step 9.1 forTrain B llydrogen Recombiner. The TSC concurs that containment hydrogen will not increase to greater than 0.5%. l Begin with Step 7.1 for Train A Ilydrogen Purge Exhaust. TilliN remove both of the following from service: Begin with Step 11.1 for Train B Ilydrogen Purge Ilydrogen recombiners. __ Exhaust. __ liydrogen purge system. 7.24 Check that a_ll Section 7.0 steps have been addressed.
t
%.w' PVNGS Page 59 or 87 Total 234 EXCESS STEAM 1)EM ANI) 4110 P- 1 R 004 Revision 00.0-1 l
CRS DETAILS CRS ACTIONS l 8.0 Pi, ANT STATUS POINT Check that the conditions from at least 1 or the columns,in the 8.1 IE Reactivity Contml is satisfied, table below, are met: 71 TilEN continue in this piocedure. O ! l "U .l l IF NOT, TIIEN direct the team to GO TO Emergency - Operations,41EP-1EOOi, beginning at the entry to the 2 ' Safety Function Flowcharts. 'T1 O l Horation rate is greater than 40 gpm . Reactor power is less than 10-470 b! All CEAs are inserted :5 ,
- Adequate shutdown margin is established _
RCS boron concentration is greater than 2150 ppm O. l 4. O Reactor power is decreasing Reactor power is decreasing 7 Reactor power is decicasing E ' w,' Reactor power is constant
PVNGS Page 60 of 87 Total 234 EXCESS STEAM DEM ANI) 41 El'- 1 R 004 Revision 00.04 CRS DETAILS _CRS ACTIONS S.0 PI,A NT ST ATUS l'OINT (cont.) Check that ;111 of the buses in at least I train in the table below, are 8.2 til Maintenance of Vital Auxili:uies is satisfied, energized: y T1liiN continue in this procedure, O 3) IF NOT, TilEN direct the team to GO TO Emergency Train A Train 11 . Bus ___ Operations,411iP-lEOOi, beginning at the entry to the Z Safety Function Flowcharts. PBA-503 PBB-SO4 91 4.16 kV BUS O PNA-D25 PNB-D26 J1 120 Vac BUSES -. PNC-D27 PND-D28 5 1 125 Vdc BUSES PKA-M41 PKB-M42 {j PKC-M43 PKD-M44 O 4 F
41 E P-1It O O 4 Revision 00.04 PVNGS Page 61 of 87 Total 234 EXCMSS STEAM DEMAND CRS DETAILS CRS ACTIONS S.O PLANT STATIJS "OINT (cont.) Check that ;111 of the criteria are met for the existing pressurir.cr 8.3 E RCS Pressure and tuventory Control are satisfied, m Till!N continue in this procedure. level condition listed in the tabic below: O p E NOT, TilEN direci the team to GO TO Emergency - Operations,411!P-lEOOi, beginning at the entry to the Z Safety Function Flowcharts. m O Pressurizer level below 10% (25%1 Pressurizer level between 10 and 70% 125 - 74%1 [5 . RCS subcooling is acceptable. RVLMS indicates that the Outlet Plenum level is ab least 21% j See Nonoal Containment RCS P/r Limits lilarsh Containment RCS P/r Limitsi, on the control O board. IIPSI flow is acceptable. z See llPSI Delivery Curve on the control board. O RVLMS indicates that the Ontlet Plenum level e - All availab!c charging pumps are running, r is at least 21% Charging and letdown, as available, are restoring pressurizer level. At least I of the following conditions is met: IIPSI Ilow is acceptabic. See IIPSI Delivery Curve on the control board. IIPSI throttic criteria have been met. .-_ - .-, . . - . - .. --- .- . . ~ - . . . . . - . . . - - . -
41 E P- 1 R 004 Revision 00.04 PvNGS Page 62 of 87 Total 234 EXCESS STEAM DIG 1 ANI) CRS ACTIONS CRS DETAILS S.O l'I, ANT STATUS l'OINT (cmit.) A. Calcul.ite RCS operating loop AT. Th "U 8.4 IF llent Removal is satisfied. TilEN continue in this procedu:c.
- Tc "U m IF NOT.TilEN direct the team to GO TO Emergency Operalions. 41EP-liiOUI. beginning; at the entry to tihe = RCS operating loop AT *F Safety 1, unction Flowchar ts.
B. Check that all of the criteria are met for the existing RCP 2 m condition listed in the table below: O n. At least 1 RCP runninn No RCPs runnine 5 RCS loop AT is less than 10'F [17 F]. RCS k>op ATisless than 57 F[74 Fl. REP CET temperature is less than 6(XFF [610'Fl. O Z RCS Tc is less than 570'F 1558 Fl. RCS Tc is stable or decreasing. REP CET temperature is stable or decreasing. O 2 P C. Check that the intact steam generator meets gl.1 of the criteria -< for the existing level condition listed in the table below: 2 Steam Generators Available 1 Steam Generator Available SG WR Level Enough flow to maintain the steam generator Enough flow to maintain the steam generator Above 72% 178%) WR Icvel between 72 and 80% [78 - 84%] WR level between 72 and 80% l78 - 84'7c} WR At least 250 gpm er 0.14 x 106 lb/hr At least 500 gpm or 0.28 x 106 lb/hr lletween 2 and 72% feedwater How feedwater How i 13 - 78%l WR Between 250 and 1500 gpm or between Between 500 and 1500 gpm or between 11clow 2r7c 113%) WR 0.14 x 106 lb/hr and 0.83 x 106 lb/hr 0.28 x 106 lb/hr and 0.83 x 106 lb/hr
41 E P-l itOO4 Revision 00.04 PVNGS Pagc 63 cf 87 Total 234 EXCESS STEAM DEM ANI) CRS DETAILS CRS ACTIONS. 8.0 Pl. ANT STATUS POINT f cont.) Check that at least 1 of the following pressure criteria is met: 8.5 lE containment isolation critena for Containment Integrity is m satisfied, Containment pressure is less than 3.0 psig. O Tl fly continue in this prtredute. D CI AS has actuated. IE NOT,TilEN direct the team to GO TO Etnergency z Operations. 41 EP-liiOOl, beginning at the entry to the m Safety Function lilowchaits O x A. Evaluate any alann on ;di of the following containment g 8.6 .lE containment radiaticn monitors criteria for Containment radiation monitors that arc in service: p Integrity is satisfied, q TlIEN continue ir this pnredure. RU-l or alternate. R U- 148. - O IF NOT.TilEN direct the team to GO TO Emergencv R U- 16. R U- 149. Z Operntions,4iliP-IEGOI. beginning at the entry to lite O Safety Function Flowcharts. RU- 17. Z r-IL Check that none of the containment radiation monitors that were evaluated have ALERT or IllGII alanns: RU-1 or alternate. RU-148. R U- 16. R U- 149. RU- 17. C. .!E no containment radiation monitors are available, OR the CRS suspects that the containment radiation monitor indications are not correct, TlIEN direct Chemistry to sample the containment atmosphere. _ . . _ __ _ _ . _ . _ . . . ~ _ _ _ . _ . _ _ _ . _ _ - _ _. . . _ .-. _ _ . _, , ._ ___ _ _ . - _ - - - _ . _ _ .__
Page 61 of 87 Total 234 EXCESS STEAM I)EM ANI) 41 El'-1 R 004 Revision 00.04 PVNGS CRS DETAILS CRS ACTIONS S.0 Pl, ANT STATUS l'OINT (cont.) A. Evaluate am alann on all of the foHowing steam plant S.7 lij meam plant radiation n'onitors criteria for Containment radiation monitors that are in service: y Integrity is satisfied, O Tlll.iti continue in this paredure. RU- 139. RU- 140. RU- 141. y IF NOT, TilEN direct the team to GO TO Emergency RU-4. R U-5. z- _ Operations,41 EP-lEOOl, beginning at the entry to the m-Safety Function Flowcharts, O IL Check that pone of the steam plant radiation monitors that "U were evaluated have ALERT or lilGil alanns: g 3> RU - 139. RU- 140. RU-141. _
-i O
RU 4. R U-5. g O C. 1F no steam plant radiation monitors are availabic, 2 OR the CRS suspects that the steam plant radiation monitor4F mdications are not correct, TIIEN direct Chemistry to sample the steam generators.
41 El'- 11(004 Revision 00.04 PVNGS Page 65 of 37 Total 234 EXCESS STEAM DEM AND CRS DETAILS CRS ACTIONS S.0 Pl, ANT STATUS POINT (cont.) Check that at least I of the following containment pressure criteria 8.8 IF Containment Atmospheric Controlis satisfied, Tlll!N continue in this pmcedure. is met: ri O IF NOT,TilEN direct the team to GO TO Emergency Containment pressure is less than 8.5 psig. m Operations,411iP-111001, beginning at the entry to the Z Safety Function Flowcharts. At least 1 CS header is delivering at least 3525 gpm. m O m Check that at least I of the following containment hydrogen 3-concentration criteria is met: 3>
. ..I.
CS has not actuated. O Z livdrogen concentration is less than 0.51 O Both of the following conditions are met: Z r-Ilydrogen concentration is between 0.5 and 2.8% 4 A hydrogen recombiner is being placed in operation or is operating. The hydrogen purge system is operating.
. _ . _ _ _ . , _ _ _ ~ . _ _ . . . _ . _ . . _
- u. ,
41 l':l'- 1 I(004 Revision 00.04 PVNGS Page 66 of 87 Total 234 EXCESS STEAM DEM ANI) CRS ACTIONS CRS DETAILS 9.0 PI, ANT COOL,DOWN 9.1 IF the diesel generatoa are innning, Direct an operator to PERFORM Diesel Generator AND are NOT required to supply eithcr of the followine buses: Operations Afler ESFAS Actuations, 4 i AO-17752, m beginning with Step 1.1. O
.p PB A-S03.
PBil-SO4. Z m TilEN shut down any unloaded diesel generator. O 33 E _................................_.................................-NOTE---------------------------------------------------------------------- >
-1
~
The STA completes Shutriawn Margin,72ST-1 RXO9 during the perfonnance of the STA Safety Function Flowchart. Credited boron O concentration is detennined in 72ST-IRXO9 and takes credit for xenon reactivity. The target boron concentration is detennined in 7 Attachincut S-2 to the STA's appendix. It is the limiting boron concentration required during the RCS cooldown. O Z I~ 9.2 Detennine the credited RCS boron concentration and the target A. Record the credited RCS boron concentration. 4 RCS boron concentration for the coohlown to 350'F [338 Fj. Refer to 72ST-lRXO9, Shutdown Margin. Credited RCS boron concentration ppm B. Direct the STA to PERFORM Einergency Operations, 41EP-lEOOi, Appendix S, STA Responsibilities, Attachment S-2, Boration During Cooldown Worksheet. C. Record the target RCS boron concentration required for the RCS cooklown. Refer to Attachment S-2. Target RCS boron concentration ppm
41 EP-I R OO4 Revision OO.04 PVNGS Pagc 67 of 87 Total 234 EXCESS STEAM DEM AND CRS ACTIONS CRS DETAILS 9.0 Pl, ANT COOi,DOWN 9.3 IE the credited RCS baron concentration is less than the target RCS boron concentration, m TilEN direct the STA to evahrate the difTerence and determine g whether the makeup during the cooldown will provide adequate D boration. Z 11 lE the credited RCS boron concentration is less than the target Refer to Emergency Operations, 41EP-1E001, O 9A 23 RCS boron concentration, Appendix S, STA Responsibilitics, Attachment S-2, AND the STA hagtennined that adequate boration will NOT 13 oration During Cooldown Workshect. K occur during the couldown, 3> Direct the primary operator to borate to the required baron -l TIIEM borate the RCS by the amount specified as the Required Horation on the lloration During Cooldown Worksheet. concentration. ] Z WilEN any of the following conditions are met: O 9.5 Z The credited RCS lxaron concentration is greater than the r 4 target RCS boron concentration. The STA has detennined that adequate boration will occur during the cochlown. The required boration is complete. t Pressurizer level approaches 80'70174%l nnd letdown is isolated. TilEN continue in Ihis procedure. l l 9.0 SO is performing RCS and Pressuriter Cooldown Log. l
s.. 41 E P- 1It 004 Revision 00.04 PVNGS Page 68 of 87 Total 234 EXCESS STEAM DEM ANI) CRS DETAILS CRS ACflONS 9.0 l't, ANT COOL >DOWN (cont.) 9.7 Jij the MSIVs on the intac: steam generator can NQIbe opened, y TilliN GO TO Step 9.12 in this procedure. O x 9.8 1.E the condenser is availabic, 2 AND steaming to the condenser is desired, TilliN direct the secondary operator to bypass and open the O-MSIVs on the intact steam generator. x K Steps 9.9 and 9.11 - 50 may be opening the MSIVs. 9.9 . l. 9.12 IF all of the following conditions exist: Z O Pressurizer pressure approaches the low pressure pretrip Z setpoint. I"" The pretrip alarm, LO P7R PRESS CII PRE-TRIP, actuates. SI AS is NOT actuated. TIIEN perform hqth t of the following:
- 1. Ensure that the pressure reduction is due to deliberate actions.
- 2. Direct the secondary operator to maintain the automatic Pressurizer Pressort - Low setpoint below pressurizer pressure.
EXCESS STEAM I)EM AND 4I El'-I R004 Revision 00.04 PVNGS Page 69 of 87 Total 234 CRS ACTIONS CRS DETAILS 9.0 Pl. ANT CODI,00WN (cont.) Evaluate the method of RCS depressurization. Evaluate the n,cthod of RCS depressurization by performing the 9.13 following decision table and direct the primary operator to GO TGn the applicabic step in this procedure for RCS depressurization to O between 350 and 395 psia [280 and 330 psia]; p d. Auxiliary Spray Main Spray { Jl
- PRESSURIZER AUX SPRAY VLV, CllA-IIV-205 3',
RCP1A >
- PRESSURIZER AUX SPRAY VLV, CIIB IIV-203 -
l RCP 111 h I i: 2 or more charging pumps running No charging pumps running I charging pump running GO TO Step 9.17 . : GO TO Step 9.14 GO TO Step 9.15 GO TO Step 9.16 in this procedure. in this procedure. in this procedure. in this procedure.
"T O ~n. Z l . 1 r OU ' K >}-OZ OZr4
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- m EXCESS STEAM DEM AND 41 EP-I R OO4 Revision 00.04 PVNGS Page 71 of 87 Total 234 CRS ACTIONS CRS DETAILS ,
9.0 PLANT COOi,DOWN (cont.)
.......__..___...__.............___........____...................-----NOTE-.-------------------.-----.---_------.---------------------.------.----.--
The maximum allowed RCS cooldown rate is 100*F/hr,in accordance with Tech Spec 3.4.8.1. The maximum allowed pressurizer y cooldown rate is 200F/hr, in accordance with Tech Spec 3.4.8.2. O
.................................__.......__.__._.....___........_....-NOTE----.------------------------------------------ - ---------
Z Step 9.26 provides the action that the operator should take if the RCS becomes over cooled during the cooldown that follows n Step 9.30. O 0 K See Normal Containment RCS P/T Limits [Ilarsh Containment yi, 9.26 IE the cooldown rate exceeds 100"F/hr. RCS P/r Limitsi, on the control board. -{ TlllM direct the secondary operator to reduce the cooldown rate to Icss than 100'F/hr, while maintaining the RCS P/r limits. '3 Z.
..........____.....__....._____....____.................__.__....... NOTE----------------------------------------------------------------------- O Z-Step 9.27 provides the action that the operator should take if the RCS becomes oversubcooled during the cooldown that follows r-Step 9.30 .-_....__
x..... a_.._..................._.......-.._............. - .... ....... ...... ..... ....... _ 9.27 IE the RCS becomes oversubcooled, A. Direct the primary operator to CONCURRENTLY TilEN ensure that the primary operator depressurizes the plant PERFORM Spray Valve Actuation Data Sheet, using main or auxiliary spray to restote pressurizer pressure to Attachment A-4 to the Primcry Operator Actions. within the acceptable region. B. See Nonnal Containment RCS P/T Limits [1larsh Containment RCS P/r Limits), on the contml board. __ _ _ .._ _ _u_. - _ _ _ . _ - . _ . .
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4 I E P-I 11004 Revision 00.04 PVNGS Page 73 of 87 Total 234 EXCESS STEAM DEM AND CRS DETAILS CRS ACTIONS 9.0 PI, ANT COOI,DOWN (cont.) 9.32 Maintain pressurizer Icvel between 10 and 70'7o [25 - 74'11 and trending to between 33 and 53% 140 - 50'Tol. y O See Nonnal Containment RCS P/F Limits [Ilarsh Containtncnt 9.33 Maintain pressurizer pressure within the acceptable region throughout the cooldown. RCS P/F Limitsj, on the control board. y "Tl Direct the primary operator to CONCURRENTLY PERFORM - O Spray Valve Actuation Data Shect, Attachment A-4 to the y Primary Operator Actions. g
-l 9.3 ! Maintain the intact srcam generator level between 50 and 70'1 NR throughout the coohlown.
O Z-r- 1 f-i l l l
. - . - - . _ - - . . -. . - - - , . . - . . = . . . . .. . . - - . -- . . . . . . . . . - . . .. . - . . . . . _ . - . . ~
w 41 EP-1 R 004 Revision 00.04 PVNGS Page 74 of 87 Total 234 EXCESS STEAM DEM ANI) CRS DETAILS CRS ACTIONS 9.0 P1, ANT COOLDOWN (cont.) 9.35 WilEN pressuri7.cr pressure is less than 1000 psia [1000 psia), T AND ictdown is in service. O Till!N ensure that the primary operator aligns the standby g letdown control valve. ~ z Continue in this proccJure. m O m __ _9. 3 6 WIiEN pressurizer pressure is less than 1000 psia [1000 tisial, g AND Ictdown is in service, e p Tlliiti ensure that the primary operator aligns the standby H backpressure control valve. O Continue in this procedure. O Z 9.37 WIIEN pressurizer pressure is less than 750 psia 1860 psia), r TilliN direct the primary operator to depressurize the SITS to -< between 300 and 310 psig. Continue in this procedure. 9.38 WilEN pressurizer pressure is less than 410 psia [390 psia}. AND RCS This less than 350 F [338'F), TilEN direct the primary operator to isolate the SITS. Centinue in this procedure.
v i 41 EP-1 RO O 4 Revision 00.04 PVNGS Page 75 0f 87 Total 234 EXCESS STEAM DEM AND CRS DETAILS FRS ACTIONS 9.0 PLANT COOi.,DOWN (cont.)
................................................_....................... NOTE-------------------------------------------------------------------------
Voiding in the RCS may be indicated by a_ny of the following indications. parameter changes, or trends: y O
! . Letdown now is greater than the charging flow. D
- 2. Pressurizer level is increasing significantly more than expected while operating pressurizer spray. 2 m
- 3. Pressuri7er level is decreasing significantly more than expected while operating pressurizer heaters.
O "U E
- 4. The RVLMS indicatesless than 100% RVUlllevel. >
- 5. HJTC unheated thermocouple temperature indicates saturated conditions in the RVUll. j O
- 6. The RCS cannot be depressurized. .... .......
7
...................................................... ....... .................................... ... ...... ....... .............. O Z
9.39 LE RCS voiding prevents RCS depressurization, r-TilEN_ PERFORM Emergency Operations,41EP-1E001, ~< Appendix A, RCS Void Detennination and Control, beginning with Step 1.1. RETURN TO Step 9.40 in this procedure.
m 41 EP-I R O O4 Revision 00.01 PVNGS Page 76 cf 87 Total 234 EXCESS STEAM DEMAND CRS DEFAILS
.CRS ACTIONS 9.0 PLANT COOLI)()WN (cont.)
Ensure that SDC system entry conditions are established. Ensure that itJ1of the following conditions exist: 9.40 m Pressurizer level is being maintained greater than 33% O [40%). m RCS subcooling is acceptable. 2 See Nonnal Containment RCS Pfr Limits [Ilarsh -T Containment RCS Pfr Limits], on the control board. 'O M , Pressurizer pressure is less than 395 psia [330 psia}. E RCS This less than 350 F [338 FJ. --j O
' Z 9.41 Check that ;i!! Section 9.0 steps have been addressed. O Z-r-
I l l i
- =y ,c. g. a + .- _w. , -
41 El'- I R004 Revision 00.01 PVNGS Page 7'l of 87 Total 234 EXCESS STEAM I)lGI ANI) __ CRS DETAILS CRS ACT!ONci 10.0 l'i, ANT STATUS POINT Check that the conditions frotn at least I of the cohnnns,in the 10.1 IF Reactivity Control is satisfied, TlIEN continue in this procedure. tabic below, are inct: m O IF NOT, TIIEN direct the team to GO TO Einergency ' 3 Operntions,41EP-lLO01, beginning at the entry to the Safety Function Flowcharts. f.
"Tl' O
All CEAs are inserted 13 oration rate is greater than 40 gpm . Reactor power is less than 104o I 3l Adequate shutdown margin is established ) , i RCS boron concentration is greater than 2150 ppm { 2: Reactor power is decreasing Reactor power is decreasing C Reactor power is decreasing 2
- Reactor power is constant C M,
m 41 EP-1 ROO4 Revision 00.04 PVNGS Page 78 of 87 Total 234 EXCESS STEAM DEM AND CRS ACTIONS CRS DETAILS 10.0 Pi, ANT STATUS POINT (cont.) Check that all of the buses in at least I train in the table below, are 10.2 lij Main:enance of Vital Auxiliaries is satisfied, TlIEN continue in this procedure. cnergized: IF NOT,TilEN direct the team to GO TO Emergency Train B Operations,41EP-l EOOl. beginning at the entry to the Bus Train A _, Safety Function Flowcharts. g 4.16 kV BUS PBA-503 PBB-504 ,1 0-
- 120 Vac BUSES PNA-D25 PNB-D26 )
.PNC-D27 PND-D28 jl i
125 Vdc BUSES PKA-M41 PKB-M42 O PKC-M43 PKD-M44 E O Z t-g y- , -w. --en a e :=, - ~e ---.-- w=-w c w --
41 E P-I R OO4 Revision 00D1 PVNGS Page 79 ef 87 Total 234 EXCESS STEAM DID1AND CRS ACTIONS CRS DETAILS 10.0 P1, ANT STATUS POINT (cont.) IF RCS Pressure and Inventory Control are satisfied, Check that all of the criteria are met for the existing pressurizer 10.3 TilliN continue in this procedure. level condition listed in the table below y O IE NOT, Tl fliN direct the team to GO 'l O Emergency y Operations,41 EP-1EOut. beginning at the entry to the Z Safety Function Flowchaits. "T1 U Pressurizer Icvel below 107o [257o1 I Ptessurizer level between 10 and 70% [25 - 74701
' El RCS subcooling is acceptable. RVLMS indicates that the Outlet Plenum level is-af l
Sec Nonnal Containment RCS Pfr Limits [Ilarsh Icast 217o. Containment RCS P/r Limits], on the control IIPSI flow is acceptable. { board. # See llPSI Delivery Curve on the control board. O RVLMS indicates that the Outlet Plenum level Z All available charging pumps are running. is at least 2170. r Charging and letdown, as availabic, are restoring pressurizer level. At least I of the following conditions is met: 1 IPSI flow h acceptable. See IIPSI Delivery Curve on the control board. IIPSI throttle criteria have been met.
w w 41 El'- 1 R 004 Revision 00.04 PVNGS Page 80 of 87 Total 234 EXCESS STEAM DEM AND CRS ACTIONS CRS DETAILS 10.0 l'l, ANT STATilS POINT (cont.) A. Calculate RCS operating loop AT. Th cF 10.4 IF Ilcat Removal is satisfied, TlliiN continue in this procedure.
~ C T IF NOT, Till3N direct the team to GO TO Emergency Operations,4IEP-1EOOl, beginning at the entry to the = RCS operating loop AT F n Safety Function Flowcharts.
B. Check that all of the criteria are met for the existing RCP 2 m condition listed in the table below: O a) At least i RCP running No RCPs runnine g RCS loop AT is less than 10'F l17 Fl. RCS leap AT is less than 57 F [74 Fl. REP CET temperatum is less than 600'F [610 Fl. O RCS Tc is less than 570 F [558 F]. e. RCS Te is stable or decreasing. REP CET temperature is stable or decreasing. () 2" r-C. Check that the intact steam generator meets all of the criteria -< for the existing level condition listed in the tabic below: 2 Steam Generators Avaital2_c 1 1 Steam Generator Available SG WR Level Enough flow to maintain the steam generator Enough flow to maintain the steam generator Above 72% [78%] WR level between 72 and 80% 178 - 84%] WR level between 72 and 80% [78 - 84%l WR Between 2 and 72% At least 250 gpm or 0.14 x 106 lb/hr At least 500 gpm or 0.28 x 106 lbMir feedwater flow feedwater flow i13 - 78%] WR Between 250 and 1500 gpm or between Between 500 and 1500 gpm or between Below 2% {13%l WR 0.14 x 106 lb/hr and 0.83 x 106 lbMir 0.28 x 106 lbMir and 0.83 x 106 lbMir
41 El'- 1 R 004 Revision 00.01 PVNGS Page 81 of 87 Total 234 EXCESS STEAM I)EM ANI) CRS DETAILS CRS ACTIONS 10.0 l'i, ANT STATUS POINT (ennt.) Check ihat at least 1 of the following pressure criteria is met: 10.5 lij etmtainment isolatien criteria for Containment Integrity is n satisfied, . Containment pressure is less than 3.0 psig. O TlIEN continue in this proccdure. 3 IF NOT, TlIEN direct the team to GO TO Entergency CI AS has actuated. Z Operations. 41EP-liiOOl, beginning at the entry to the n Safety Function Flowtharts. O x A. Evaluate any alann on allof the following containment g 10.6 IE containment radiation monitors criteria for Containment radiation monitors that are in service: p Integrity is satisfied. q TilEN continue in this prwedure. RU-l or alternate. RU- 148. - O IF NOT.TIIEN direct the team to GO TO Emergency R U- 16. RU-149. Z Operntions. 41 EP-lEOOI. beginnint; at the entry to tiie O Safety Function Flowcharts. P U- 17. Z r-B. Check that nnn_c_of e the containment radiation monitors that were evaluated have ALERT or ll!GII alanns: RU-l or alternate. RU- 148. RU- 16. RU-149. RU- 17. C. If no containment radiation monitors are availabic, QIl the CRS suspects that the containment radiation monitor indications are not correct, TilEN direct Chemistry to sampic the containment atmosphere. _ _ __ _ _ __ __ ~~ __ __ . . _ _ _ --
a 4 I El'-1 R004 Revision 00.04 PVNGS Page 82 of 87 Total 234 EXCESS STEAM 1)EM AND CRS ACTIONS CRS DETAILS 10.0 P1, ANT STATUS POINT (cont.) 10,7 A. Evaluate;my alann on al!of the following steam plant IE steam plant radiation monitors criteria for Containment Integrity is satisfied, radiation monitors that arc in service: m TIII:N continue in thir procedine. O R U- 139. RU- 140. RU- 141. 0 IF NOL TIIEN direct the team to GO TO Emergency Z RU-4. R U-5. Operntions,41EP-lE001, beginning at the entry to the 'T Safety Function Flowcharts. O Z B. Check that n_qn_c of the steam plant radiation monitors that were evaluated have ALERT or 111G11 alanns: 5 RU-139. RU-140. RU- 141. "j o R U-4. RU-5. z O C. IF no steam plant radiation monitors are available, 2 511 the CRS suspects that the steam plant radiation monitor Q indications are not correct, TlIEN direct Chemistry to sampic the steam generators.
, ,n ,- - , - - m ,a,, ,.
w e- -
, , , , w - - , , - - , - .,,
41 El'-1 It0 04 Revision oo.ca PvNGS Page 83 of 87 Total 234 EXCESS STEAM I)EM ANI) CitS DisrAILS CRS ACTIONS 10.0 l'i, ANT STATUS POINT (cont.) Check that at least 1 of the following containment pressure criteria 10.8 lE Containment Atmmphcric Controlis satisfied, TilliN continue in this prccedure. is met: y O Containtuent picssure is less than 8.5 psig. y lij NOT.TlIEN direct the team to GO TO Emergency _ Operations,41EP-lEODI, beginning at the entry to the g Safety Function Flowcharts. At least 1 CS header is delivering at least 3525 gpm. n O
.n Check that at least 1 of the following containment hydrogen g concentration cnteria is inct: )
-1 CS has not actuated O 2
llydrogen concentrmion is less than 0.5%. O 130th of the following conditions arc inet: Z r Ilydrogen concentration is between 0.5 and 2.8% -< A hydrogen recombiner is being placed in operation or is operating. The hydrogen purge system is operating.
41 EP-I R 004 Revision 00.01 PVNGS Page 84 of 87 Total 234 EXCESS STEAM DEM AND CRS DETAILS CRS ACIIONS I1.0 Pit ()CEI)UltE EXIT Ensure that M of the following have been recorded: 11.1 Ensu:c that the equipinent log entrics have been made in the contiol room lo"n. Source of fcedwater. O RCP status. z l.ecdwater pump status, m O m-Ensure that the event c!assification has been logged in the unit Ensure that g of the following have been recorded: g-11.2 p log. Time the event was classified. y . O Event classincation. Z Time the event tenninated. O Z r-
a w 41 El'- 1 R 004 Revision 00.(M PVNGS Page 85 of 87 Total 234 EXCESS STEASi DEMAND CRS ACTIONS CRS DETAILS I1.0 PROCEDUltE EX:T (cont.)
...______._______.___________.._________.__._________________________--NOTE--------------------------------------------------------------------------
The following list of LCOs is not inclusive. Ensme that any of the reactivity control systems Tech Spec LCOs Ensure that atly applicable LCOs have been complied wi i 1.3 that were entered have been complied with and that the LCO cntered: ,, s:atus is entered in the unit log. Z Shutdown margin is adequate with all of the CEAs insertedh Refer to Tech Spec 3.1.1.1. O 23 Shutdown margin is adequate with any CEA withdrawn. g w Refer to Tech Spec 3.1.1.1. p
-i Charcing pumps arc operable.
Refer to Tech Spec 3.1.2.4. O Z O Z r-
PVNGS Page 86 of 87 Total 234 EXCESS STEAM I)EM ANI) 41 El'-1 R O O4 Revision 00.01 CRS DETAILS CRS ACTIONS I l .0 PROCEDURE EXIT (cont.)
. . . . . . . . . . . .........................................................---NOTE-------.-----------------------------------------------------------
The following list of LCOs is not inclusive.
... ............................ .......................................................................... ...--..- ...--.---..............--........-- ....... 'T1 A. Ensure that an applicable LCOs have been complied with O 11.4 Ensme that .a_ny Tech Spec LCOs that were entered have been and entered:
"Il complied with and that the LCO status is entered in the unit log. -
RCS loops are operabic. Z Refer to Tech Spec 3.4.1.2. rt O Each steam generator is operabic. I Refer to Tech Spec 3.4.4, and surveillance g
~
requirement 4.4.4.3.c.4. >
--i ECCS train A subsystems are operabic.
Refer to Section XI Valve Stroke Timing & O 2-Position Indication Verification - Mode 1 Thru 6
- Safety Injection A Train ECCS Throttle Valveso -
. 73ST-IXIll, and Tech Spec 3.5.2. g r-ECCS train B subsystems are operabic. Refer to Section -<
XI Valve Stroke Timing & Position Indication Verification - Mode 1 Thru 6 - Safety Injection 11 Train ECCS Throttle Valves,73ST-IXIl2, and Tech Spec 3.5.2. Chemistry is in specification. Refer to Tech Spec 3.4.6. Identify ECCS conditional requirements that plant conditions have incurred and comp!cte a TSCCR for those items. Refer to Tech Spec 3.5.3, Action b. B. Evaluate for any other LCOs that may have been entered.
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41 E P-1 It 004 Revision 00.01 PVNGS Page 87 of 87 Total 234 EXCESS STEAM 1)EMAN1) CRS DETAILS CAS ACTIONS 11.0 PitoCEDUltE EXIT (cont.) 11.5 IE Spray Valve Actuation Data Shect, Attaclunent A-4 to the l'riinary Operator Actions, or RCS and Pressurizer Coo!down n Log. Attaclunent 11-3 to the Secondary Operator Actions, was O y used, Til!!N ensure that the lata in the attaciunents is being transferred j into ItCS and Pressurizer ileatup and Cooldown Itates, Z I m 40ST-9RC01. .O x GO TO Ilot Standby to Cold Shutdown Mode 3 to E 11.6 Mode 5,410P-lz7It), beginning witti Step 4.1. >
-i O
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,a 41 EP-l llOO4 Itevision 00.04 PVNGS Appendix A Page 1 of 74 Total 234 EXCESS STEAM DIG 1AND 71 O
I Z l'IllM AltY OPEllATOlt ACTIONS -] I E OlUECTIVE -. O Z This appendix provides the primary operator actions which must be accomplished after an excess steam demand. O T actions in this pmcedure are necessary to ensure that the plant is placed in a safe, stabic condition. The goal of this 7 pr ocedure is to establish SDC entry conditions. r""
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m .s EXCESS STEASi I)ESI ANI) 41 EP- 1 It 004 Revision 00.04 PVNGS Appendix A Page 3 of 74 Total 234 PRIMARY Ol'l!R ATOR Afl^lONS PRIM ARY OPl!RATOR DETAILS 3.0 EVENT CONTROI.
.T .1 S0 is ensuring an hiS!S.
"T1 3.2 50 is aligning ly2 tit srcam generatorsfor hot leg sampic.
0 3.3 CRS may inform Chemistry to use alternate sampic cooling methocis. 9 N If, at ;wv time during this procedure, pressurizer pressure is E 3A below the safety injection setpoint, TilEN cnsure that all of the following conditions exist: O A SI AS and a CIAS have acttnted. Z O No more than i RCP is operating in cach loop. 7 I-Acceptable llPSI flow is established to the RCS. Sec IIPSI Delivery Curve, on'the contml board. < SESS indicates that the safety injection components are in their actuated condition. SESS indicates that the containment isolation valves are closed. Check that one of the following conditions exists: SESS indicates that at least I containment isolation valve in cach automatically isolated penetration is closed. The valves in any open penetrations have been overridden open as required by plant conditions.
l EXCESS STEAM I)EM ANI) 41 E P-111004 Revision 00D1 PVNGS Appendix A Page 4 of 74 Total 234 l PRIMARY OPliR ATOR ACrlONS PRih1 ARY OPERATOR DETAILS 3.0 EVENT CONTRO*, (cont.) CAUTION T Maximiting the charging and safety injection flows may cause the pressurizer to overfill, which in turn may cause an RCS pressure O cxcursion upon RCS heatup. Thrcttling or tenninating flows may be necessary to prevent overfilling the pressurizer. 33 Z 3.5 11! a SI AS and a CIAS have actuated, m TilliN continue in this appendix. O
'33 IF NQT, TilEN GO TO Step 3.16 in this appendix. g
--i
- 3.6 Ensure that all of the following IIPSI throttle criteria are met: O RCS subcooling is above the minimum subcooling limit. See Nonnal Containment RCS P/r Limits [Ilarsh Containment Z RCS P/r Limits), on the control board. O Z
RVI.MS indicates that the RVUII level is at least 16"c. r-Pressurizer level is being inaintained above 337c [40%). At least I steam generator has a level above 27c 113701 WR and is maintaining RCS heat renmval.
EXCESS STEAM DIG.I ANI) 41 El'-i lt O O 4 Revision 00.04 PVNGS Appendix A Page 5 0f 74 Total 234 PRIMARY OPERATOR ACrlONS PRIMARY OPERATOR DETAILS 3.0 EVENT CONTROI, (cont.) CAUTION llaving only 1 IIPSI injection valve per train in a throuled position will minimize crosion damage. m O ti 3.7 IE the CRS has directed, Override and throttle closed the llPSIIIEADER A TO RC LOOP-AND all of the llPSI throttle criteria have been met, VLVs,1 valve at a time: TilEN override and throttle llPSI A Dow, while maintaining the IIPSI IlEADER A TO RC LOOP 1 A VLV, SIA-IIS-637. O IIPSI throttle criteria. 3 ilPSiIlEADER A TO RC LOOP IB VLV, SI A-IIS-647. IIPSI IIEADER A TO RC LOOP 2A VLV, SIA-IIS-617. - O llPSI IlEADER A TO RC LOOP 2B VLV, SI A-IIS-627. Z O Z IE the CRS has directed, Override and throttle closed the llPSI IIEADER B TO RC LOOPg-- 3.8 AND aU of the IIPSI throttle criteria have been met, VLVs, I valve at a time: -< TilEN override and throttle 11 PSI B flow, while maintaining the IIPSI IIEADER B TO RC LOOP 1 A VLV, SIB-IIS-636. llPSI throttle criteria. IIPSI IIEADER B TO RC LOOP IB VLV, SIB-HS-646. IIPSIIIEADER B TO RC LOOP 2A VLV, SIB-IIS-616. IIPSI IIEADER B TO RC LOOP 2B VLV, SIB-IIS-626.
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v EXCESS STEAM I)EM AND 41 El'- 111004 Revision 00.01 PvNGS Appendix A Page 7 of 74 Total 234 PRlhlARY Ol'IiRNIOR ACI'lONS PRihlARY OPERATOR DETAILS 3.0 EVENT CONTROL (cont.) 3.1 i tilpil of the IIPSI throale criteria can NOT be maintained, TlII!N ensure that 91 1 of the following conditions exist:
"11
- 1. Inform the CRS that the llPSI throttle criteria are not met. O 33
- 2. M! availabic IIPSI pumps are running. g
- 3. N!af the IIPSI throtoc valves are fnlly open.
]
- 4. Acceptable llPSI now is established to the RCS. Sec llPSI Delivery' Curve, on the control board.
E 8' > 3.12 IF all of the following conditions exist: A. Override and stop both LPSI pumps: d O The CRS has directed. LPSI PUMP A, SIA-llS-3. Z A SIAS has actuated. LPSI PUMP B, SIB-IIS-4 Pressurizer pressure is greater than 260 psia [300 psial and stable or increasing. B. Override and close all of the LPSI injection valves: k TilEN perform both of the following: LPSI IIEADER A TO RC LOOP 1 A, SIA-IIS-635. Stop all operating LPSI pumps. LPSI IIEADER A TO RC LOOP 1B, SI A-IIS-645. Close ill! LPSI injection vales. LPSI IIEADER H TO RC LOOP 2A, SIB-IIS-615. LPSI IIEADER B TO RC LOOP 2B, SIB-IIS-625.
EXCESS STEAM DEMAND 41EP-1 R004 Revision 00.07 i PVNGS Appendix A Page 8 of 74 Total 234 PRIMARY OPUSATHR ACTIONS PRIMARY OPERATOR DETAILS 3.0 EVENT CONTROL (cont.) 3.13 IE pressurizer pressure can NOT be maintained above 260 psia LPSI ilEADER A TO RC LOOP 1 A, SIA-IIS-635. [300 psial, TIIEN perfonn all of the following: LPSI IIEADER A TO RC LOOP 1B, SIA-IIS-645. "T1
- 1. Start all of the avaliable LPSI pumps. O LPSI IIEADER B TO RC LOOP 2A, SIB-IIS-615. "U
- 2. Open both of the LPSI injection valves for any of the LPSI pumps that are running. LPSI IIEADER B TO RC LOOP 2B, SIB-IIS-625. k "Tl
- 3. Ensure that acceptable LPSI flow is established to the RCS. See LPSI Delivery Curve, on the control boani. O D
3.14 IE the CRS has directed, Direct an auxiliary operator to override and close all of the E AND at any time during this procedure, a SIAS is actuated, following breakers, I at a time: >
'IllEN energize all of the following electrical panels, I at a time: d O
NIIN-M 19. 480V MCC E-NIIN-M19,1-E-PGA-L35D2, located in g class switchgear room A. O NIIN-M20. 480V-MCC E-NIIN-M20,1-E-PGB-L36D2, located in Z class switchgear room B. Q NIIN-M71. 480 V MCC 1-E-NIIN-M71,1-E-PGA-L33B3, located in class switchgear room A. NIIN-M72. 480V MCC E-NHN-M72,1-E-PGB-L34B3, located in class switchgear room B. Essential lighting panel QBN-D90. MAIN ESSENTIAL LIGIITING PANEL E-QBN-D90, 1-E-PGB-L36D4, located in class switchgear room B. Ess'ential lighting panel QBN-D91. MAIN ESSENTIAL LIGIITING PANEL E-QBN-D91, 1-E-PGA-L35D3, located in class switchgear room A.
PVNGS Appendix A Pagc 9 of 74 Total 234 41 E P-I R OO4 Revision 00.04 EXCESS STEAM 1)EMANI) PRIM ARY OPERATOR DEFAILS PRIMARY OPERATOR ACI'lONS 3.0 IWENT CONTROL, (cont.) 3.15 50 is checkingJhr steans genenitor drycnti conditions. 71 O 3.16 Maintain pressuri7er pressure l'ss than 2300 psia [2150 psial.
"_U Z
3.17 Steps 3.17 and 3.13 - SO is stabilizing Tc in the loop with the highest pressure steam gencrator. x E 3.19 lil, at any n time (luring this procedure, any auxiliary spray valve d will be opened, OR any main spray valve will be opened with any RCI' stopped, O TilliN CONCURRiiN'lLY PERFORM Spray Valve Actuation 2 Data Shect, Attaclunent A-4 to this appendix. O Z r-
w EXCESS STEASI 1)ESI ANI) 41 EI'-I 11004 Revision 00.04 PVNGS Appendix A Page 10 of 74 Total 234 PRIMARU1Pl!RATOR ACI'lONS PRIM ARY OPERATOR DETAILS 3.0 EVENT CONTRO!, (cont.) 3.20 IE, at any time during this pnxedure, any of the following conditions exist: m Minimum RCS subcooling is NOT acceptable. See Nonnal Containment RCS P/r Limits [Ilarsh Containment O RCS lYr 1.imits], on the control board. p RCP NPSil is NOT acceptable. See RCP NPSil Curve, on the control board. k m O CS AS actuates. "U TlIEN stop all of the operating RCPs. E 3>
-i O
Z O Z r-
m_ v 41 E P-1 R O O4 Revision 00.01 PVNGS Appendix A Page i1 of 74 Total 234 EXCESS STEAM DEMAND PRINIARY OPliRATOR ACIIONS PRlhl ARY OPER ATOR DETAILS 3.0 EVENT CONTROI, (ennt.) IF all of the following conditions exist: Refer to tie alann response procedure indicated in the table below 3.21 to evaluate ;my alanning RCP annunciator windows. T The CRS has directed. O Any RCPs are sunning. - RCP annunciatt r windows are in alann for the running h g R C Ps.
'D TilliN evaluate the alann. g i
Alann response procedure -- Annunciator window O Panel UO3A Alarrn Responses 2: RCP SEAL SYS TRBL (3 All A) O Panel 1103A Alarm Responses 2: RCP SEAL INJ FLOW I11-111 OR LO (3A11B) r " PancI Il03A Alarm Responses -; ____RCP SEAL INJ TEMP ill-lll OR LO-LO (3 Al2A) RCP CONT BLEED-OFF PRESS III-III (3A 12B) Panci B03A Alarm' Responses RCP TRBL (4 A02A,4 A03 A,4 A04 A,4 A05 A) Panel 804A Alarrn Responses RCP LO NCW FLOW (4D01 A,4D01B,4D02A,4D02B) Panel 1104D Alarrn Responses RCP LO NCW FLOW (4E01 A,4E01B,4E02A,4E020) Panel H04E Alarm Responses
_ v EXCESS STEASI DESIAND 41 E P-i llO O4 Revision 00.04 PVNGS Appendix A Page 12 0f 74 Total 231 PRIN1ARY UPERATOR ACTIONS PRih1 ARY OPERATOR DETAH4 3.0 EVENT CONTROL, (coni.)
..............__............______........__.........._...............-NOTE---------------.-.--------------.-------------------------------------
The CRS also perfonns this decision table.
..... __..___. _______.___. ____....______........ ____ ...-_..........__ ..___......__ ..._________.......-- _ .___--- ........_______ ..__________............. r O
3.22 Evaluate the RWT level and charging system status and GO TO Perfonn the decision table below: 0 the applicable step in this appendix. Z m RWl' level stable RWT level below or approaching 73% RWT level below or approaching 20% O D and above 73%
- M 3=
CilN-ilV-536 CilB-V327 SFP level above No charging pump SFP level above No charging pump q alann setpoint suction paths avai able alann setpoint suction paths availab!g CRS chooses to CRS chooses to 2 CilN-UV-501 CII A-Pol and PCN-V215 stop charging PCN_V215 stop charging () CII A-V755 n CllA-Pol CilB-Pol and CilN-Vl44 CilN-V144 C ' Cllli-V756 CllB-P01 CllE-P01 and CIIE-P01 CIIE-V757 CilN-ilV-532 CilN-IIV-532 CIIA-P01 CII A-P01 CilB-Pol CilB-Pol ClIE-P01 CIIE-P01 GO TO Step 3.23 GO TO Step 3.24 GO TO Step 3.25 GO TO Step 3.26 GO TO Step 3.25 GO TO Step 3.26 in this appendix. in this appendix. in this appendix. in this appendix. in this appendix. in this appendix.
a 41EP-1ROO4 Revision 00.07 PVNGS Appendix A Page 13 0f 74 Total 234 EXCESS STEAM DEMAND PRIMARY OPERATOR ACTIONS PRIMARY OPERATOR DETAILS-3.0 EVENT CONTROL (cont.) A. Stop griy operating BAMPs. 3.23 .lJ3 the CRS has directed. AND the RWTlevelis stable above 73%, M TilEN perform hqth of the following: B. IE power is available, O 'i TIIEN perfonn all of the following: 3
- 1. Transfer the charging pump suction from the VCr to
- a. Open RWT GRAVITY FEED TO CilRG PMPS b
SUCr VLV, CIIN-IIS-536. ]
- 2. GO TO Step 3.28 la this appendix.
- b. Close VOLUME CONTROLTANK OUTLET VLV, : 3 '
CIIN-IIS-501. E
- c. Start the charging pumps as necessary. .d
, O Z C. LE power is NOT availabic, O 311CEliperform;illof the following: 7
- a. Ensure that a Radiation Protection technician accompanies the operator to perfonn the area surveys.
k
- b. Direct an auxiliary operator to manually align leh of the following valves:
a) Open RWT GRAVITY FEED TO CIIRG PMPS SUCT VLV, CIIE-IIV-536, located in the BAMP room, on the 70 ft elevation. b) Close VOLUME CONTROLTANK OUTLET, C11N-UV-501, located in the auxiliary building . on the 115 ft elevation. c) - Start the charging pumps as necessary.
EXCESS STEAM DEMAND 41 El>- 1 It 0 04 Revision 00.01 PVNGS Appendix A Page 14 of 74 Total 234 PRIN1/\RY OPERATOR AillONS PRIMARY OPERATOR DETAILS 3.0 EVENT CONTROI, (cont.) 3.24 IF the CRS has directed, A. Ensure that a Radiation Protection technician accompanics the ANi] the RWT level is below or approaching 737c, operator to perform the area surveys.
"T1 TilEN perform both of the following:
B. Direct an auxiliary operator to align the valves in Charging O
- 1. Transfer charging pump suction to the bottom of the RWT, Pump Suction from the RWT, Attachment A-1 to this 33 through RWT TO Cil ARGING PUMPS SUCTION, appendix.
Z Ci lB-V 32~7 T C. Start the charging pumps as necessary. O
- 2. GO TO Step 3.28 in this appendix. *Il
- 67 g 3.25 IF all of the fo: lowing conditions exist: A. Ensure that a Radiation Protection technician ac operator to perfonn the area surveys.
The CRS has directed. O B. Direct an auxiliary operator to align the valves in Charging Z The RWT level is NOT sufficient for charging pump Pump Suction from the SFP, Attachment A-2 to this appendix. O operation. 7 Charging pump suction must be maintained. C. Close RFL WATER TANK TO B AM PUMPS SUCT VLV,k
- CLIN-IIS-532.
TilEN perfonn both of the following: D. Open RWT GRAVITY FEED TO CilRG PMPS SUcr
- 1. Transfer charging pump suction to the SFP. VLV, CIIN-ilS-536.
- 2. GO TO Step 3.28 in this appendix. E. Close VOLUME CONTROL TANK OUTLET VLV, CilN-liS-501.
F. Start the charging pumps as necessary. l l- _ - _ _ - - - - _ _ _ _ _ - _ - - - ._
EXCESS STEAM DEM AND 41 E P-1 It 004 Revision 00.0 ! PVNGS Appendix A Page 15 of 74 Total 2.t! PRINl ARY Ol'El.(ATOR ACI'lONS PRIMARY OPERATOR DETAILS 3.0 EVENT CONTROL, (ennt.) IF the CRS has directed, Perfonn aji of the following to place gH of the charging pumps in 3.26 AND charging pump suction can NOT be maintained, PULL TO LOCK: ri TlIEN perform both of the following: Ensure that OUTSIDE CNTMT ISOL VLV, I A A-IIS-2, O is open. 'U Isolate RCP seal bleedoff. Place all of the charging pumps in PULL TO LOCK. Isolate seal bleedoff by closing al.1of the following valves: RCP CONT IlLEED-OFF llDR TO VCr ISOL O 3 VLV, Cil A-IIS-506. 3 RCP CONT BLEED-OFF IIDR TO VCT ISOL M VLV, CilB-llS-505. d O RCP CONT llLEED-OFF IIDR RELIEF VLV Z ISOL, CII A-IIS-507. g Place all of the charging pump handswitches in PULL TO 2 LOCK: < CilARGING PUMP 1, CIIA-IIS-216. CllARGING PUMP 3. CIIA-IIS-218A. CilARGING PUMP 3, Cilll-11S-218. CIIARGING PUMP 2, CilB-IIS-217.
41 EP-1 ROO4 Revision 00.04 PVNGS Appendix A Page 16 of 74 Total 234 EXCESS STEAM DEMAND PRIM ARY OPERATOR DETAILS PRIMARYSPERATOR ACTIONS 3.0 EVENT CONTROL (cont.) 3.27 50 is aligning instntment air to the ccmtainment. 11 A. Ensure that IErDOWN B ACKPRESSURE CONTROL, O 3.28 IEitl!of the following conditions exist: CilN-PIC-201, is in manual with 100% output. 3 The CRS has directed. B. Ensure that LEVEL SETPOINT CONTROL, RCN-LIC-11(Z instrument air is aligned to the containment. is in manual with 0% output. ] 2 Nuclear cooling water is in service. C. Ensure that the selected letdown control valve is closed, as E indicated by green lights above LETDOWN CONTROL ! Pressurizer level is greater than 33% 1,10%]. V ALVE LV-110P/l 10Q SELECTOR, CIIN-IIS-110-1. D. Override and open ;111 of the following valves: O TilliN open the letdown containment isolation valves. Z LETDOWN TO REGEN IIX ISOL VLV, CilB-flS-515. O LETDOWN TO REGEN IlX ISOL VLV, CII A-IIS-516. 2 REGEN IlX OUTLET ISOLATION VLV, CilB-llS-523<.
41 El'- 111004 Revision 00.01 PVNGS Appendix A Page 17 of 74 Total 234 EXCESS STEAS1 DEM ANI) PRIM ARY OPERATOR DETAILS PRIM.'.RY Ol'ER ATOR AC1'lONS 3.0 EVENT CONTROL (cont.) IE the CRS has directed, A. Calculate the time 22 minutes after letdown was isolated. 3.29 AND the letdown containment isolation valves have been opened, Time of SIAS m TilEN restore Ictdown flow. O
+ 22 m.m p
= time. --
m O B. IE letdown has been isolated longer than 22 minutes, D TIIETI perfomi both of the following: E
- a. Open LETDOWN CONTROL VALVES BYPASS, ~--i CilN-ilS-526, to allow a 4 minute wannup. O Close LETDOWN CONTROL VALVES BYPASS, 2
b. CIIN-IIS-526. O Z r-4 C. Raise the output on RCN-LIC-110 to place the letdown control valves in the intennediate position to establish flow. D. Lower the output on CIIN-PIC-201 to establish 450 psig backpressure. E. Place CilN-PIC-201 in AUTO. F. Adjust the output on RCN-LIC-110 to establish the desired flow. G. Balance and place RCN-LIC-110 in LOCAL / AUTO.
w
%j EXCESS STEAM 1)EM ANI) 41 EI'-I R 0 04 Revision 00.04 PVNGS Appendix A Page 18 of 74 Total 234 PRIMARY OPER ATOR ACl'lONS PRIMARY OPERATOR DETAILS 3.0 EVENT CONTROL, (cont.)
3.30 Steps 3.30 through 3.33 - 50 is icientifying amt isolating the affccretisteam generator. T O
......--......-.-.....---.._.....-...-_....-....-................--NOTE----------------------------------------------------------------------------- D
~
Etluipment that ha< been overridtlen will rettuire manual restoration should conditions degrade to the point where automatic actuation Z T should take place.
--.--....... O 23 Jf the CRS hiis directed, Check that the pressure is less than 8.5 psig, on ;111 of the availabl<3 3.36 TilEN check that containment pressure is less than 8.5 psig. CONTAINMENT PRESSURE indicators listed below: >
H-IICA-PI-351 A. 6 IICB-PI-351 B. O IICC-PI-351 C. Z r~' N~ ilCD-PI-351 D. _ - .. _ _ . . - - = - . . . .- , .. ,
h v 41EP-lROO4 Revision 00.05 PVNGS Appendix A Page 19 0f 74 Total 234 EXCESS STEAM DEMAND PRIM ARY OPERATOR DETAILS PRIMARY OPERATOR ACTIONS 3.0 EVENT CONTROL (cont.) IF all of the following conditions exist: A. Perfonn ho_th of the following to stop A train CS: 3.37 Override and close CNTMT SPRAY A DSCII TO SPRAY rl He CRS has directed. llDR I VLV, SI A-IIS-672. O m A CSAS has actuated. Ovenide and stop CONTAINMENT SPRAY PMP A, - SI A-IIS-5. Z Containment pressure is less than 7.0 psig. "fl O TilliN stop containment spray. "U B. Perfonn both of the following to stop B train CS: E 3> Override and close CNTMT SPRAY B DSCII TO SP llDR 2 VLV, SIB-IIS-671. O Z Override and stop CONTAINMENT SPRAY PMP 11, O SIB-IIS-6. Z r-
=<
i --% - - _ -----------_-_--_--,--,._--a +- - - -s u- *- w - a v m ,c-
__ v EXCESS STEAM I)EM ANI) 41 EP-1It 004 Revision 00.04 PVNGS Appendix A Page 20 of 74 Total 234 PRIMARY OPERATOR ACFIONS PRIM ARY OPERATOR DETAILS 3.0 EVENT CONTROI. (cont.) 3.38 IF all of the following conditions exist: The CRS has directed. 7 O The CS pumps were placed in override, y Containment pressure is greater than or equal to 8.5 psig. 2 r1 TIIEN re-initiate lx)th trains of CS. O E 3.39 50 nray be stopping ali of the containmentfans. p _-I O 3.40 WilEN the CRS has directed, Z AND reactor power has decreased to 2 x 10-Wo. O TilEN CONCURRENTLY PERFORM Boron Dilution Alann Z Channel Check, Attachment A-3 to this appendix. r-Continue in this appendix. 3.4 I CRS may be ensuring that the LCO action requirements are met.
EXCESS STEA Al 1)ESI ANI) 41 El'- 1 It 004 Revision 00.04 PVNGS Appendix A Page 21 of 7, Total 234 l'RIMARY Ol'ERATOR ACTIONS l' RIM ARY OPERATOR DETAi'd 3.0 EVENT CONTROL. (cont.) IF less than <! RCPs are runnin't, Perform ;tJ1 of the following to place PRE' SURE SPR AY 3.42 TilEN place the PRESSURE S!'R AY CONTROL, CONTROL, RCN-PIK-100,in manual: TI RCN-PIK-100, in manual. Adjust the manual signal of PRF3SURE SPR AY O CONTROL, RCN-l'IK-100, u<.ng the thumbwhcci to .0 match the automatic signal. Z Select M ANUAL on PRESF URE SPRAY CONTROL, T RCN-PIK- 100. O 33 Reduce the setpoint of PRESSURE SPRAY CONTROL, 5 RCN-PIK-100, to 0. >
-1 Infomi the CRS and secondary operator that PRESSURE O SPR AY CONTROL, RCN-PIK-100,is in manual controlZ O
~
Z t-i t
EXCESS STEAM DEM AND 41 EP-1 RO O4 Revision O(MM PVNGS e ppendix A Page 22 of 74 Total 234 PRIMARY OPERATOR ACIIONS Y PRI,1\RY OPERATOR DETAILS 3.0 EVENT CONTROL > (cont.) 3A3 If, at itnv time during this procedure,imy auxiliarf spray valve will be opened. OR any main spray valve will be opened with any RCP stopped, m TilEN CONCURREN ILY PERFORM Spray Valve Actuation O Data Sheet, Attachment A-4 to this appendix. 3 Z Step 3 A4 - So inay be aligning blowdownfor the m 3.44 O faultedsteam gcnerator. 33 E CRS may be informing Radiation l'rotection and the RalS y 3.45 4 technician of the stcam release. O E 3.46 CRS may be directing an operator to restore offsite power. O Z Check that all Section 3.0 steps have been addressed. r* 3.47 -<
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s._.- 41EP-1ROO4 Revision 00.04 PVNGS Appendix A Page 24 of 74 Total 234 EXCESS STEAM DEMAND PRIMARY OPERATOR ACTIONS PRIMARY OPERAT OR DETAILS 5.0 PLANT STAlllLl7,ATION 5.1 11cgin a nonnal response to new alanns. m 5.2 50 niay be ccmtrolling the steam generator level. O 33 5.3 Steps 5.3 through 5.9 - 50 rnay be restoring AFW to the stcant 5 m gencrator. O 33 5.10 Steps 5.10 through 5.12 - 50 is ensuring that the inainfccchvater g prun;>s are tripped. p
. ..I.
5.13 S0 inay be controlling the stcant generator level. O Z I-
g D g 4 rO; 5 1O:M)>j i
- 3~ - O- Zk _
3 L e 2 O . l b la : S , A u t w I S D o o o Y V I t r T l e L L S I n 4 b P V I o . e S - m m 7 l L B f b B P m o S a O I o 5 L I t e M SI I
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a E f o S A h t t P D s Y N i e s n S A w e A R u B L n r O t u r B o o x T l e O i t t i d A o z y R M is r o n c T E o e R ht l a N T p ta r p E n S e p P o A O E. p A b C Y 7 o O n S Y y Y i s n2. e - L L r S R n pS O A ia G A o oII R N l i x it d - T 8. N M c nB A u V I a a P N- e a R e eI OS n P P I h a ht dI CI t 1 f o i , r rV nB e t c e t cn. en 0 e 1 l. vL pP le ir a 0 0 a OV OI I S Dl a n n n i o f o e i s r e i m v P T e L R c O b'u 4 S , 0 I S A o r Y V 9 0 L L S I t n t I P V I o - S - m 1 L A
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I O T tcn ee eI OS l h n a r u y A r ig idI Cl t l a Y Z tc t cn d M d or nV n eA e e n A R A 1, l sd ay e vL OV pP OI I le S e ig Da r c o r a e E M i l h h p ht T 11 l A Se Rh i ht s e m S 1 l' T C e t it S ec n e S h a i h S t l p e E T u t N N N n dr C A. li l li it n o c X l i l i o e E P WT C R 4 5 1 1 5 5 0 5
EXCESS STEA Ai I)IGIANI) 4 i El'- 1 It 0 04 Revision 00.01 PVNGS Appendix A Page 26 of 74 Total 234 PRIRNRY OPER ATOR ACTIONS PRISI ARY OPERATOR DETAILS 5.0 l'LANT STAllil,IZATION (cont.) 5.16 IF all of the following conditions exist: E power is available to the SEAL 13LEEDOl;F FROM RCP VLVs, The CRS has directed. TIIEN close ;t il the following valves: n O CS AS has occurred. RCN-1IS-430. p Seal injection is being supplied to the RCPs. RCN-IIS-431. Z ri TilEN ensure that RCt' seal bleedoff now is isolated to prevent RCN-ilS-432. O 3 vver-pressurizing the RDT. E RCN-IIS-433. E NOT, TilEN, perform 1313 3 of the following: d O A. Ensure that OUTSIDE CNTMT ISOL VLV, I A A-IIS-2, is z open. B. Close all of the following valves: 2 RCP CONT BLEED-OFF IIDR TO VCT ISOL VLV, Cll A-IIS-506. RCP CONT BLEED-OFF IlDR TO VCr ISOL VLV. CIIB-I1S-505. RCP CONT HLEED-OFF llDR RELIEF VLV ISOL, Cil A-IIS-507.
EXCESS STEAM I)EMANI) 41 El'-1 R004 Revision 00.04 PVNGS Appendix A Page 27 of 74 Total 234 PRIMARY OPER ATOR ACTM)liS PRIM ARY OPERATOR DETAILS 5.0 l'l> ANT STAltli,iZ ATION (cont.) 5.17 WIIEN the CRS has directed, TlliiN maintain pressurizer level between 10 and 707c ri [25 - 74%l and trending to between 33 and 5370 (40 - 507cl. O 3 Continue in this appendix Z 5.13 50 is stotyring the hea:cr drain prunps. x 5 5.19 Steps 5.19 throngh 5.22 - 50 rnay be restoring normal containment ACUS and a normal chiller. Q. O 5.23 Steps 5.23 and 5.25 - SO is aligning ainiliary steam to supply Z glandscal. 9 Z r-5.26 50 is performing Secondary Equipment Shutdown Checklist. 4 5.27 IF the CRS has directed, TIIEN CONCURRENTLY PERFORM Emergency Operations,41EP-lEOOI. Appendix F, Water Inventory Record, beginning with Step 1.1. l \
i
.,_ v l
i f EXCESS STEAM DEAI AND 41 El'- 1 It 004 Revision oo.oa PvNGS Appendix A Page 28 of 74 Total 234 l' RIM ARY Ol'ERNIUR ACTIONS PRIM ARY OPERATOR DETAILS l l 5.0 l'i, A NT STAl!Il#/,ATION (cont.) C_A UTION Following an RCS coohlown, an overpressurization of the itCS may result in a pressurized thermal shock. ] x 5.28 WilliN the CRS has directed, CONCURRENTLY PERFORM Spray Valve Actuation Data Sheet, Allachment A-4 to this appendix. 2n TilEN maintain pressurizer pressure within the acceptahic region by use of amof the following: O See Nomial Containment RCS P/r Limits [Ilarsh Containment x Pressurizer heaters and spray. RCS P/r Limits), on the control board. g 3> Charging and letdown. -4 Throttling of the lil'SI valves Continue in this appen<lix O Z r M mm__ . __________.______.____m.__.____m -- , e e
~
IGCESS STEASI DESIANI) 41 E P-l ltOO4 Revision oo.oa PvNGS Appendix A Page 29 0f 74 Total 23-1 PRlhlARY OPl!RATOR ACIIONS PRIN1 ARY OPERATOR DETAILS 5.0 Pl, ANT STAlill,IZ ATION (cont.) 5.29 Ensure that tc; containment pressure is being controlled. A. Evaluate the containment pressum on a_Ilof the following: IICA-PI-35i A. IICC-PI-35 i C. ri O l lCll-PI-351 B. IICD-PI-351D. W Z II. IF the CRS has directed, T TilEN perform the operator actions in the table below, after O evaluating the highest valid containment pressurc: 3 E' Indicated Containment Pressure Oncrator Actions Q> Ainvc 3 psig Ensure that a SI AS and a CI AS have actuated. O Z Between 3 and 8.5 psig Ensure that ofte of the following conditions exists: g
- 1. At least 2 containment air handling units and at 3 least 1 CEDM fan arc in service. k
- 2. At least 1 CS header is delivering at least 3525 gpm.
Above 8.5 psig Ensure that a CS AS has actuated with gl] of the following conditions met:
- 1. At least i CS header is delivering at least 3525 gpm.
- 2. The hydrogen analyzers are operating.
- 3. AIJ RCPs are stopped.
5.30 Check that itti Section 5.0 steps have been addressed.
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EXCESS STEAA1 I)EAIAND 41 El'- 1 It 004 Revision 00.04 PVNGS Appendix A Page 32 of 74 Total 234 PRlhiARY OPERATOR ACIIONS PRih1 ARY OPERATOR DETAILS 7.0 SYSTESI ENII ANCESIENT (cont.) C A UTION hlajor seal faihire may occur if the RCPs are restarted after either of the following conditions: 71
- 1. Seal injection and cooling water were lost for longer than 20 minutes. O
- 2. Seal bleedoff was not stopped within 1 minute of the loss of cooling water and sealinjection. 33 RCPs should not be started if either of these conditions has occurred, except to prevent core damage. -
Z 71 7.4 IF the RCP seal opera:ing limits have NOT been execeded, Check that both of the following conditions exist: iM it is necessary to mn an RCP to prevent core damage, 5 TIIEN continue in this procedure.' Seal injection and nuclear cooling water have been interrupted to the RCP seals for less than 20 minutes. > IE MH, TilEN GO TO Step 7.12 in this appendix. d __ Seal bleedoff was stopped within 1 minute of the stan O' of the event. Z O Z r-
EXCESS STEAhi 1)EM ANI) 41 El'- 111004 Revision cont PVNGS Appendix A Page 33 of 74 Total 234 PRIMARY _QHiR ATOR ACf!ONS PRIM ARY OPERATOR DETAll S 7.0 SYSTEM ENilANCESIENT (cont.) CAUTION Operating RCP combinations of pumps 1 A and 2B,or pumps IB and 2A may cause RCP bearing damage. r1 O 33 ____________________________________________________-___.._______________.440TE---------------------------------------------------------------------------- Z I RCP operating in cach lo,p is the optimal pump configuration to be used during emergency or recovery operations. If 2 RCPs are to bc ___________.?-.'.___.._'.-___________.___________________________________..____..__.._______.. O x 7.5 Check that the plant conditions and equipment will support RCP Check that a_1_I of the following conditions exist: E operation. > y CSAS has not actuated. - RCS subcooling is acceptabic. O Z Pressurizer pressure is above the NPSII limits. O At least I steam generator is maintaining RCS heat removaZ and has a level maintained above 2% l13%] WR. F Power is available from NAN-S01 or NAN-SO2. Nuclear cooling water low flow alarms are clear. ! Check that at least 1 of the following conditions exists: i RVLMS indicates that the RVUll level is 100% and pressurizer level is being maintained at or above 33% l [40%). l l RVI.MS indicates that the RVUll Icvel is 67% and I pres mrizer level is being maintained at or above 6U7o (81%).
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EXCESS STEAM DEM AND 41 E P-1 It 004 Revision 00.04 PVNGS Appendix A Page 35 of 74 Total 234 PRIN1 AR Y Ol'l!R ATOR ACTIONS PRIMARY OPERATOR DETAILS 7.0 SYSTEM ENil ANCEMENT (cont.) 7.7 IE plant conditions and equipment will support RCP operation, TilEN establish all of the following ptercquisites for each RCP to be started: m O Seal injection is in service. m Seal bicedoff is in service. Ensure that the seal blecdoff flow is between 1 and 3 gpm. 2 m The oil lift pump has been rutming for 7 minutes. Start the oil lift pump (s) and allow them to run for 7 minutes O before starting the RCP(s) to be started. 3 TURB & GEN AUX TRIP & LO RELAY,G5/186R-1 and Cabinet 1-E-M AN-C01 is located in the back panel area of the E G3/l86R-2, on MAN-C01, are reset. control room. The RCP handswitch o'i B04 is in the normal AFTER STOP, O green Gagged, position. Z RCP Speed Switch Trip Relay 214 SLOW SPEED AL is reset. Direct an onerator to CONCURRENTLY PERFORM Relav O Resetting,40DP-00P02, beginning with Step 1.1, to reset the 2 RCP Breaker 286 UO Relay is reset. actuated devices. Q Electrical support panels are energized.- Dnc of the following conditions is met: E-NNN-D15 alann window ICl2B (NNYS1)is clear, or local breakers 52-D1525 for RCP 1 A and 52-D1526 for RCP 1 B are checked closed. E-NNN-D15 is located in the south corridor of the turbine building,100 ft elevation. E-NNN-D16 alann window ICl2B (NNYS2) is clear, or k> cal breakers 52-D1625 for RCP 2A and 52-D1626 for RCP 2B are checked closed. E-NNN-D16 is located in the north corridor of the auxiliary bui! ding,120 ft elevation.
1 O ~3 gs.10 3 .>i6- Z g 2 5rC ~
~
4 w 3 2 o le lat b s s s s s s s o l e e e e e e e e T b a s n n s s n s n s n s n s n 4 t e r o o o o o o o 7 e u p p p p p p p _ f h : d s s s s s s s 0 S t n w e e e e e e e e L c R R R R R R R 6 I io o 3 A de dn r p e T t i m m m m m m m g a E aw c r e s n r a r a r a r a r a r a r a P D id o o l l l l l l l A R nt p A A A A A A A i ia s x O ec e A A A A A D E idn T r n u u r 3 3 3 3 4 4 4 A de n m 0 0 0 0 0 0 0 e R c a n r a B 1 1 l I 1 1 1 1 5 1 l I p E l p A P O mP p A l e l e c l e l e e l e e C n n n n n n n Y sR a a a a a a a R n g P P P P P P P S A o pi n G s i N M I em r V R a P P ml r a 4 la a yn )
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. I I C i L L L T L ad D A n o w A A A N B N N c n R c o E E E O R O s e N O
( d in S S S C T L l O. Pp Cp A T T w P P P P P P P R sa M A N r C C C C C C C gi R E o R R R R R R R h E E t a int 1 t n D l' O 3 icn r a i E t s2 Y C u - r 1 M R N n n - f o7 A A A a s p e E M l P tet T I i N C ' iS s S R R iO u l E y qT S n c S I S a _ rO e E e rG E t a p C T lu eN S a hE X Y v t i Ei E S E IT X. 9 7 7 0 7
.. v EXCESS STEAM DEMAND 41 EP-1 ROO4 Revision 00.04 PVNGS Appendix A Page 37 of 74 Total 234 PRIMARY OPERATOR ACI' IONS PRIMARY OPERATOR DETAILS 7.0 SYSTESI ENIIANCESIENT (cont.)
C A UTION T When starting RCPs, a pressuri7er level drop due to RCS void collapse and contraction may occur. A loss of pressurizer level control may result in a loss of RCP NPSil and RCS subcooling. RCP and fuel damage may occur if the RCPs and the RCS O-3 operate in this condition. -
= Z m
---------------~---------------------------------------------------------NOTE------------------------------- -- ------- -- -----
O 2 1 RCP operating in cach loop is the optimal pump configuration to be used during emergency or recovery operations. If 2 RCPs are to be g started, the preferred combinations are pumps 1 A and 2A, or pumps 1B and 2B. p q _ 7.10 IF the CRS has directed 1 RCP to be started, O TilEN perfonn all of the following: Z O
- 1. Place CIIARGING LINE TO RC LOOP 2A DP z CONTROL, CIIN-PDIC-240, in M ANU AL. r-
- 2. Start all of the available charging pumps.
- 3. Place CilN-PDIC-240 in AUTO.
- 4. Start 1 RCP.
l
- 5. Ensure proper RCP operation. Ensure that both of the following conditions exist:
Motor amperage stabilizes between 360 and 500 amps. i NPSil is acceptable for RCP operation. See RCP NPSil Curve, on the control board.
._ v EXCESS STMAM 1)IG1 ANI) 41 El'- 1 It 004 Revision 00.01 PVNGS Appendix A Page 38 of 74 Total 234 PRIMARY OPERATOR ACTIONS PRIMARY OPERATOR DEFAILS 7.0 SYSTESI ENil ANCEMENT (cont.)
________________________.____..______________________________--------NOTE-------------------------------------------------------------------------- 1 RCP operating in cach loop is the optimal pump configuration to be used during emergency or recovery operations. If 2 RCPs are to Ix' started, the preferred combinations are pumps 1 A and 2A, or pumps 1B and 2B. m _____________ _____________________________________..__________________.__________._______________________ ___________.__________________________________________- O
- D 7.11 IF the CRS has directed a second RCP to be started, TilEN peiform both of the following:
Z m Statt a second RCP, preferably 1 in the opposite loop. O
- 1. "U Ensure that both of the following conditions exist: E
- 2. Ensure proper RCP operation. - >
Motor amperage stabilizes between 360 and 500 amps. ""j O NPSil is acceptable for RCP operation. 2 See RCP NPSil Curve, on the control board. O Z 7.12 Ensure that pressurizer level is between 10 and 70% [25 - 74%) and is trending to between 33 and 53% [40 - 30%). k 7.13 Steps 7.13 and 7.14 - 50 may be checkin): natural circulation conditions. 7.15 IE the CRS has directed, TIIEN CONCURRENTLY PERFORM the referenced appendix for a verification that the celuipment responded correctly for ayn actuated safety signals.
EXCESS STEAM I)EM ANI) 41 EP-1 It 004 Revision 00.04 PVNGS Appendix A Page 39 of 74 Total 234 l'RIN1ARY OPER ATOR ACIIONS PRIM ARY OPERATOR DETAILS 7.0 SYSTEM ENil ANCEMENT (cont.) 7.16 Steps 7.16 through 7.l3 - CRS nury he checking the safety signal reset criteria. T O 7.19 E the CRS has directed, y AND the safety signal reset criteria are met, , , , , , TilEN CONCURRENTLY PERFORM the referenced appendix Z. for ;tny actuated safety signals and restore equipment to standby. m O m 7.20 E a CSAS has actuated, g p, TIIEN continue in this appendix.
. ..I E NOT, TilEN GO TO Step 7.24 in this appendix. O Z
E the CRS has directed, A. Ensure that at least I hydrogen recombiner is installed. O 7.21 2 AND the containment hydrogen is between 0.5 and 2.W7c, TIIEN place at least I hydrogen recombiner in service. B. Dittet an operator to PERFORM at least 1 of the following r-sections in Containment llydrogen Control And "< Ilydrogen Purge Exhaust System, 410P-lilP02: Begin with Step 4.1 for Train A Ilydrogen Recombiner. Begin with Step 8.1 for Train B Ilydrogen Recombiner. l I' l
l 41 E P-111004 Rcvision 00.04 PVNOS Appendix A Page 40 of 74 Total 2.01 EXCESS STEAS1 1)ES1 ANI) l'RIMARY OPERATOR DETAILS l_' RIM ARY OPER ATOR ACI'!ONS 7.0 SYSTEM ENil ANCEMENT (cont.) A. Ensure that the hydrogen purge unit is installed. 7.22 If the CRS has directoJ, AND the containment hydrogen increases to 2.870 or greater, y
- 11. Direct an operator to PERFORM at least 1 of the following TlIEN place the hydrogen purge unit in service. sections in Containment Ilydrogen Control And O Ilydregen Purge Exhaust System, 410P-lllP02: D
~
Begin with Step 6.1 for Train A Ilydrogen Purge Exhaust. Z T llegin with Step 10.1 for Train B llydrogen Purge O 33 Exhaust. E Direct an operator to PERFORM the following sections in H
~"
7.23 IF all of the following conditions exist: Containment Ilydrogen Control And Ilydrogen Purge O Exhaust System, 4IOP-lilP02: 7 The CRS has directed. Begin with Step 5.1 for Train A Ilydrogen Recombiner. O Containment hydrogen removal is in progress. Z F Begin with Step 9.1 forTrain B Ilydrogen Recombiner. -< Containment hydrogen decreases to less than 0.51 The TSC concurs that containment hydrogen will not Begin with Step 7.1 forTrain A Ilydrogen Purge Exhaust. increase to greater than 0.51 Begin with Step 11.1 for Train B llydrogen Purge TilEN remove both of the fellowing from service: Exhaust. Ilydrogen recombiners. Ilydrogen purge system. 7.24 Check that all Section 7.0 steps have been addressed.
tom 2mOmK> DOZ OZr<- t _ t. 2 l t a o T
- 4 7
f o S 1 L I 4 A e T g I E D A R x O i T d n A e R p p E P A O Y S R G A N M V IR P P 4 0 0 0 n o is i v e R 4 O O t i l P E 1 4 , 3, d e N t s O l e u i q C e r A s D R a N O s r A e T te I A m GI E R T N a r a D l' O I p O t n M Y ' l a R l p A A S E M U f o T I T S R A R S P T S C S e S T ht E N m C A, r o X I f n E P I 1 8. 0 8
wi EXCESS STEAM 1)EM ANI) 41 EP-I R004 Revision 00.04 PVNGS Appendix A Page 42 of 74 Total 234 PRIMARY OPERATOR ACI' IONS PRIM ARY OPER ATOR DETAILS 9.0 PLANT COOL,DOWN 9.1 CRS may be directing an cy>erator to unload and shut down the dicsci generators. T O Steps 9.2 and 9.3 - The CRS is determining the credited RCS 11 9.2 .- horon concentration and the target RCS baron concentrationfor Z the cooldown to 350*F [333"F]. Tl O 23 IP all of the following conditions exist: 9.4 E The CRS has directed. H
~
The the credited RCS Imron concentration is less than the g target RCS boron concentration. g O The STA has determined that adequate lx> ration will NOT Z occur during the cooldown. r THEN borate the RCS by the amount specified as the Required Boration on the Boration During Cooldown Worksheet.
EXCESS STEAM DEMAND 41 EP-I R OO4 Revision 00.04 PVNGS Appendix A Page 43 0f 74 Total 234 PRINIARY OPERATOR ACMONS PRIN1 ARY OPERATOR DETAILS 9.0 l'I. ANT COOL.1)OWN (cont.) 9.5 WIiEN ;my of the following conditions are met: The credited RCS boron concentration is greater than the m target RCS boren concentration. O 33 The STA has deiennined that adequate boration will occur - during the couldown. Z T The required boration is complete. O 33 Pressurizer level approaches 80701747c] and letdown is E isolated. 3>
..4 TilEN continue in this appendix. O Z
9.6 SO is perfonning RCS and Pressurizer Cooldown Log. O r-9.7 Steps 9.7 through 9.11 - 50 may be opening the MSIVs. 9.12 SO may be resetting the automatic Pressuri:ct Pressure - Low setpoint. i l i i l
- v v EXCESS STEAS1 DESIAND 41 EP-1 R 004 Revision (X).04 PVNGS Appendix A Page 44 of 74 Total 234 '
PRIMARY OPERATOR ACTIONS PRIMARY OPERATOR DETAILS 9.0 PI, ANT COOI.DOWN (cont.)
...................................................................-------NOTE-------------------------------------------- - - - - - - - - . . - - - - - - - - - .
r The CRS also performs the decision table in step 9.13 m O '. 9.13 Evaluate the method of RCS depressurization. Evaluate the method of RCS depressurization by perfonning the . 23 , following decision table and GO TO the applicable step in this - appendix: 2 m 3.
' Main Spray Auxiliary Spray D E
s>
-RCP1A
- PRESSURIZER AUX SPRAY VLV, CIIA-IIV-205 d 3
.RCP1B
- PRESSURIZER AUX SPRAY VLV, CilB.IIV-203 g 3
' E 2 or more charging pumps running No charging pumps running I charging pump mnning } .
^
GO TO Step 9.14 GO TO Step 9.15 GO TO Step 9.16 GO TO Step 9.17 ' in this appendix. in this appendix. in this appendix. in this appendix. I 1 w _ _ _ _ _ .u__ _________ _ _. __ __. _ . _ _ _ _ _ . . _ . . , .-. _ . . _ . . . . . - . . . - . . _ _ . . _ ,
- -- s l
EXCESS STEAM DEMANI) 41 E P- 111004 Revision 00.04 PVNGS Appendix A Page 45 of 74 Total 234 l l PRIM ARY OPER ATOR ACTIONS PRIM ARY OPERNIOR DETAILS 9.0 l'I, ANT COOL,DOWN (cont.) 9.14 IF all of the following conditions exist:
'llic CRS has directed. m O
Pressurizer pressure is above 395 psia 1330 psial. D RCP 1 A or IB is running. Z T TilEN perfonn all of the following: O 33
- 1. Maintain minimum acceptable RCS subcooling. See Nonnal Containment RCS Pfr Limits [Ilarsh Containment E RCS P/F Limits], on the control board. 3>
-4
- 2. Maintain acceptable RCP NPSil. Sec RCP NPSil Curve, on the control board. 3 Z
- 3. Begin a depressurization of the RCS to between CONCURRENTLY PERFORM Spray Valve Actuation Data 350 and 395 psia [180 and 330 psial, using main spray. Sheet, Attachment A-4 to this appendix. O Z
- 4. GO TO Step 9.25 in this appendix. Q
a .- v EXCESS STEAM I)EM ANI) 41 El'- 1 It 004 Revision 00.04 PVNGS Appendix A Page 46 of 74 Total 234 PRIMARY OPER ATOR ACI'lONS PRih1 ARY OPERATOR DETAJLS 9.0 l'i, ANT COOi,DOWN (cont.) 9.15 11;all of the fo!!owing cenditions exist: The CRS has directed. m O l'rcssurizer pressure is above 395 psia 1330 psial. m At least 2 charging pumps are running. Z m TlIEN perfonn all of the following: O "U
- l. Maintain minimum acceptable RCS subcooling. See Nonnal Containment RCS P/r Limits [Ilarsh Containment E RCS P/r Limits], on the contml board. >
~
4
- 2. Ilegin a depressurization of the RCS to between A. CONCURRENTLY PERFORM Spray Valve Actuation DataO 350 and 395 psia 1280 and 330 psial, using auxiliary spray. Sheet, Attachment A-4 to this appendix. g B. Open at least 1 of the following valves: O Z
PRESSURIZER AUX SPRAY VLV, CilA-IIS-205. Q PRESSURIZER AUX SPRAY VLV, CIIB-IIS-203.
- 3. GO TO Step 9.25 in this appendix.
EXCESS STEAM I)RSI ANI) 41 E P-l it O O4 Revision 00.04 PVNGS Appendix A Page 47 0f 74 Total 234 PRIM ARY Ol'ERATOR ACI'lONS PRIM ARY OPER ATOR DETAILS 9.0 l'I. ANT COOI,1)OWN (cont.) 9.16 11;all of the following cond;tions exist: The CRS has directed. "T1 O Pressurizer pressure is above 395 psia 1330 psial. "D No charging pumps are running. Z "T1 TIIEN perform both of the following: O Isolate the RCP seal injection flowpath. Close nnq of the following valves to isolate the RCP seal injectiotM 1. flow path: >
.d RCP SEAL INJ SPLY llDR ISOL VLV, CilB-IIS-255. O Z
SEAL INJECTION IIX INLET VLV, CIIN-IIS-231P. g 2
- 2. Start at least I ch.,rging pump.
EXCESS STEAM DEMAND 41 E P-1 R 004 Revision 00.04 PVNGS Appendix A Page 48 of 74 Total 234 PRIMARY OPERATOR ACflONS PRIM ARY OPERATOR DETAILS 9.0 Pl> ANT COOLDOWN (cont.) 9.17 IF all of the following conditions exist: The CRS has directed. m O Pressurizer pressure is above 395 psia 1330 psial. I) Only I charging pump is running. Z m Additional charging pumps are available. O 23 TlIEN perfonn allof the following: 3
- 1. Start a second charging pump. A. Place CIIN-PDIC-240 in MANUAL. _-I O
B. Start a second charging pump. g C. Place CllN-PDIC-240 in AUTO. O Z r-
- 2. Maintain minimum acceptable RCS subcooling. See Normal Containment RCS P/r Limits [Ilarsh Containment -<
RCS P/r Limits], on the control board.
- 3. Begin a depressurization of the RCS to between A. CONCURRENTLY PERFORM Spray Valve Actuation Data 350 and 395 psia [280 and 330 psial, using auxiliary spray. Sheet, Attachment A-4 to this appendix.
B. Open at least 1 of the following valves: PRESSUR17ER AUX SPRAY VLV, CilA-IIS-205. PRESSURIZER AUX SPRAY VLV, CIIB-IIS-203. 4 GO TO Step 9.25 in this appendix.
EXCESS STEAM DEM ANI) 41 EP-1 R004 Revision 00.04 PvNGS Appendix A Page 49 of 74 Total 234 PRIMARY OPliRNIUR ACI'lONS PRihl ARY OPliRATOR DETAILS 9.0 l'l, ANT COOL,DOWN (cont.)
........................................................................NOTV------.----------------------------..-------------..-----..--------..--
Actuation of auxiliary spray with I charging pump running will cause a reductir,n or loss of scal injection flow.
................................................................. .................................................................................... ........... m O
9.18 JE the additional charging pumps couhl NOT be started, "I) AND only I charging pump is running, Z TilEN perfonn all of the following: m Close all of the following RCP bicedoff valves: O
- 1. Isolate RCP blecdoff flow. 'D RCP CONT BLEED-OFF IIDR TO VCT ISOL VLV, E-CIIB-1IS.505. 3>
-i
~
RCP CONT BLEED-OFF IIDR TO VCT ISOL VLV, O CII A-IIS-506. g RCP CONT ULEED-OFF IIDR RELIEF VLV ISOL, O CII A-IIS-507. Z I"
- 2. Maintain acceptable RCS subcooling. See Nonnal Containment RCS P/r Limits [Ilarsh Containment RCS IYr Limits], on the control board.
s
- 3. Depressurize the RCS to between 350 and 395 psia A. CONCURRENTLY PERFORM Spray Valve Actuation Data
[280 and 330 psial, using auxiliary spray. Shect, Attachment A-4 to this appendix. B. Open at least i of the following valves: PRESSURIZER AUX SPRAY VLV, CilA-IIS-205. PRESSURIZER AUX SPRAY VLV, CllB-IIS-203.
- .v EXCESS STEAM DESI AND 41 E P-i lt O O4 Revision 00.04 PVNGS Appendix A Pagc 50 0f 74 Total 234 PRIM ARY OPER ATOR ACTIONS PRIM ARY OPERATOR DIfi' AILS 9.0 l'LANT COOI,1)OWN (cont.)
........................................................................... NOTE-----------..---.---------.---------------...-....-----...-----.--..------
Steps 9.19 through 9.21 establish seal injection with all of the seal injection flow controllers energized, after using auxiliary spray.
.................................................................................................................................................................. m O
A. Check that at least 1 of the follo"?! ;, vai cs is closed: 9.19 E the RCP sealinjection flow path is isolated, "D AND all of the seat injection flow controllers are energized, - TilEN close the seal injection control valves from the control RCP SEAL INJ SPLY llDR ISOL VLV, CIIB-11S-255. Z "T1 room to prepare for establishing seal injection. SEAL INJECTION IlX INLET VLV, CIIN-IIS-231P. O E NOT, TilEN GO TO Step 9.22 in this appendix. "U E B. Close all of the RCP SEAL INJECI' ION FLOW CONTROL 3> valves by setting them to maximum output in the MAN --I position: O Z CIIN-FiC-241. O CIIN-FIC-242. Z r CIIN-FIC-243. CIIN-FiC-244.
EXCESS STEAM DEMANI) 41 El'- 1 It 004 Revision 00.04 PVNGS Appendix A Page 51 of 74 Total 234 l' RIM ARY Ol'ER ATOR ACTIONS PRIM ARY OPERATOR DETAILS 9.0 PLANT COOL,DOWN (cont.) _____________________.______._____.._________________..._________________-NOTE---------------------------------------------------------------------------- Steps 9.19 through 9.21 establish seat injection with all of the seal injection flow controllers energized, after using auxiliary spray. m
....._____________________....______.._________________.________.__________NOTiG--------_-_-_---_--------____--__---_-__------___--__-_--.____.-_-__----- O
- o The RCP seal outlet cooldown rate limit is 50'Fhnin. _
___.______.________________ .. ______.___________ __.__________ ___..._____________________________________________________________________________.____ Z m 9.20 IF all of the RCP seal injection flow control valves are closed, O 3 TlIEN perfonn M of the following to establish seal injection flow to.allof_the RCPs;_ E' Ensure that RCP SEAL INJ SPLY llDR ISOL VLV, -i 1. CIIB-flS-255, is open. O Z
- 2. Ensure that SEAL INJECTION ilX INLET VLV, CIIN-IIS-231P, is open.
O Z
- 3. Lower the output on ClIARGING LINE TO RC LOOP 2A Monitor M of the following RCP SEAL INJECTION FLOW G DP CONTROL, CilN-PDIC-240, until 120 psid is indicated CONTROL indicators:
on CLIN-PDIC-240, or until a leakage of 0.2 gpm is-indicated on each flow indicator. CilN-FIC-241. CIIN-FIC-242. CilN-FIC-243. CIIN-FIC-244. l
l EXCESS STEASI DESIAND d i EP-I I{ O 04 Revision 00D1 PVNGS Appendix A Pagc 52 cf 74 Total 234 PRINIARY OPERATOR ACflONS PRIMARY OPERATOR DETAILS 9.0 PLANT COOL.1)OWN (cont.)
.... ...................................................................... NOTE---------------------------------------------------------------------------
Steps 9.19 through 9.21 establish seal injection with all of the scal injection flow controllers energized, after using auxiliary spray.
................................................................... .............................................................................................. m O
9.21 IF RCP scal injection flow was established, Check the seal outlet temperatures using M of the following H04 D AND the seal outlet temperatures have stabilized, indicators: - TilEN perfonn all of the following: Z I A SEAL I OUTLET, TF-157. T
- 1. Throttle open each RCP seal injection flow control valve to O
IB SEAL 1 OUTLET,1T-167. 3 establish greater than 6.6 1;pm seal flow to each RCP. 3 2A SEAL 1 OUTLET,TT-177. 3>
--{
~
2B SEAL 1 OUTLET,1T-187. O Z Balance and place M of the RCP SEAL INJECTION FLOW O
- 2. Select the controllers to AUTO. 2 CONTROL valves in AUTO: r-CLIN-FIC-241.
CIIN-FIC-242. Clin-FIC-243. CIIN-FIC-244,
- 3. GO TO Step 9.25 in this appendix.
.. n EXCESS STEAM DEM ANI) 41 E P-1 R 004 Revision 00.04 PVNGS Appendix A Page 53 of 74 Total 234 l'RlM ARY_QPliRATOR ACI'lONS PRIM ARY OPliRATOR DETAILS 9.0 PLANT COOLDOWN (cont.)
_______________________.________.________________..__......_------------MOTE---------------------------------------------------------------------------- Steps 9.22 through 9.24 establish seal injection with I or more seal injection flow controllers de-energized, after using auxiliary spray. _.____________ ..__________.._______________ __________________________ . __.______ ...____ .____..__.. .....__________________ ......... _______.... .........._- 71 O IF the RCP seal injection flow path is isolated, Check that at least 1 of the following valves is closed: "U 9.22 AND ;t ilof the seal injection flow controllers are NOT cncrgized, TilEN perform all of the following: RCP SEAL INJ SPLY IIDR ISOL VLV, CilB-IIS-255. SEAL INJECTION llX INLET VLV, CilN-IIS-231P. s
- 1. Ensure that instrument air is aligned to the containment. Ensure that OUTSIDE CNTMT ISOL VLV, IA A-IIS-2, is open.
O
- 2. Direct an auxiliary operator to close SEAL INJ. IlX OUT., CilN-V836 is located in the auxiliary building i10 ft valve Z CilN-V836. galleiy. O Z
- 3. Ensure that ;aB cncrgized seal injection flow control valves Open the energized RCP SEAL INJECTION FLOW CONTROL p am fully open. valves by setting them to minimum output in the MAN position: <
CllN-FIC-241. CilN.FIC-242. CIIN-FIC-243. CllN-FIC-244.
. w v EXCESS STEAM DEMAND 41 E P- 111004 Rcvision 00.04 PVNGS Appendix A Page 54 of 74 Total 234 PRIMAILY OPERATOR ACIIONS PRIMARY OPERATOR DETAILS 9.0 P1, ANT COOLDOWN (cont.)
_____________________.____._______________._____________.._________________ NOTE------------------------------------------------------------------------ Steps 9.22 through 9.24 establish sealinjection with 1 or more seal injection flow controllers de-energized, after using auxiliary spray. O 9.23 IP all of the RCP seal injection flow control valves are NOT g energized. AND RCP seal injection is nceded, Z TlIEN align seal injection by performing all of the following: M O
- 1. Open RCP SEAL INJ SPLY llDR ISOL VLV, CilB-IIS-255. 33 E-
- 2. Open SEAL INJECTION IIX INLET VLV, CHN-IIS-231P.
--I
- 3. Lower the output on CIIARGING LINE TO RC LOOP 2A DP CONTROL, CIIN-PDIC-240, until 120 psid is indicated
{~ g on CilN-PDIC-240. O-Z r-
. m v I
EXCESS STEAM I)lG1 AND 4 I I?P-I R 004 Revision 00.04 PVNGS Appendix A Page 55 of 74 Total 234 PRIMARY OPERATOR ACIIONS PRIMARY OPERATOR DETAILS 9.0 Pi, ANT COOLDOWN (coni.)
.......................... ................. ................--......-----NOTE---------------------------------------------------------------------------
Steps 9.22 through 9.24 eMablish seal injection with 1 or more seal injection flow controllers de-energized, after using auxiliary spray. r1
.............................---............................--.....---NOTE.-.--------.----------------------------------------------------.----..--. O 3
The RCP seal outlet cooldown rate limit is 50F/ min.
. .............. ___.............................. ..._........._........_______.....___...____..________________. ..__.._.__..___. ....... ___..........__....... 2 ri 9.24 IP all of the RCP seal injection now control valves are NOT CIIN-V836 is located in the auxiliary building 110 ft valve O gallery.
3 energized, AND RCP seal injection has been aligned, S TilEN direct an auxiliary operator to throttle open SEAL INJ. A. Check :he RCP seal outlet temperatures using all of the > IIX OUT., CIIN-V836. following B04 indicators: d O l A SEAL I OUTLET, TI-157. Z lB SEAL 1 OUTLET,TI-167. O Z 2A SEAL 1 OUTLET, TI-177. k 2B SEAL 1 OUTLET, TI-187. B. WIIEN a temperature decrease is noted on the RCP seal outlet temperatures, TIIEN direct the auxiliary operator to stop opening CilN-V836. C. WilEN the RCP seal outlet temperatures have stabilized, TlIEN direct the auxiliary operator to fully open CIIN-V836.
- m. v EXCESS STEAM I)EM ANI) 41 EP-I ROO4 Revision 00.04 PVNGS Appendix A Pagc 56 cf 74 Total 234 PRIM ARY OPF;R ATOR ACI'lONS PRIM ARY OPERATOR DETAILS 9.0 P1, ANT CODI,1)OWN (cont.)
___.____.________.._________...________.._________________..___________.NOTIC-.---------_--------------.--------------------------------------------._--- RCP cooling water can be supplied cither from nuclear cooling water or essential cooling water.
...___..__.__________________________....._..___.__ _________________...___________ ___________________ _____________ ......_____________________. ____....__..... m O
9.25 lE RCP seal injection is established. Open ;tl! of the following valves: "U AND cooling water is r.upplied to the RCPs, Till!N cstablish seal bleedoff flow from ;41 of the RCPs. RCP CONT BLEED-OFF IIDR TO VCT ISOL VLV, 2 ClIB-1IS-505. T O RCP CONT IlLEED-OFF IIDR TO VCT ISOL VLV, ~U E ClIA-1IS-506. RCP CONT BLEED-OFF IIDR RELIEF VLV ISOL, d Cl I A-1 IS-507. O Z Open ;til of the following SEAL BLEEDOFF FROM RCP VLVs: RCN-IIS-430. k RCN-IIS-431. RCN-IIS-432. RCN-IIS-433. _ _ _ _ - ._. _ , . ~ . . . ..
. . v EXCESS STEAM DEMAND 41 EP-1ROO4 Revision 00.04 PVNGS Appendix A Page 57 ef 74 Total 234 PRIMARY OPERATOR ACITONS PRIMARY OPERATOR DETAIM 9.0 PLANT COOLDOWN (cont.)
9.26 CRS is ensuring that the cooldown rate does not excccd 100'FIhr. n
..................... ............ .................. ...................N o y y.............................. ..... - ....._ .......
O.n Step 9.27 provides the action that the operator should take if the RCS becomes oversubcooled during the cooldown that follows 5n Step 9.30. O 0 9.27 JE the RCS becomes oversubcooled, during the cooldown that A. CONCURRENTLY PERFORM spray Valve g follows Step 9.30, Actuation Data Sheet, Attachment A.4 to the y TilEN depressurize the RCS to restore pressurizer pressure to Primary Operator Actions. --I within the acceptable region. 13 . See Nonnal Containment RCS P/r Limits [11arsh
]
Containment RCS Limits), on the control board. 2 O Z r- _. - . . w-
. , w EXCESS STEAM I)EM ANI) 41 El'-lit O O4 Revision 00.04 PVNGS Appendix A Pagc 58 0f 74 Total 234 PRIM ARY OPER ATOR ACTIONS PRIMARY OPERATOR DETAILS 9.0 Pi, ANT COOL,1)OWN (cont.)
9.23 Steps 9.23 thrortph 9.30 - 50 is Marting a plant cooldown to below 350 *F (333'Fl. m O 9.3 i CRS rnay he infonning Radiation Pratection and the Rots g technician qf the stcorn relcasc. , Z m 9.32 Maintain pressurizer level between 10 and 70% [25 - 74%] and O trending to between 33 and 53% [40 - 50%). 'D E 9.33 Maintain pressurizer pressure within the acceptable region See Nonnal Containment RCS Pfr Limits [Ilarsh Containment -i throughout the cooldown. RCS P/r Limitsj, on the control board. O CONCURRENTLY PERFORM Spray Valve Actuation Data Z Shect, Attacliment A-4 to the Primary Operator Actions. O Z r-9.34 50 is inaintaining the stcain generator levels. A
.. v v IGCESS STEAM 1)IG1 ANI) 41 El'- 111004 Revision 00.04 PVNGS Appendix A Page 59 of 74 Total 234 l' RIM ARY OPERATOR ACTIONS PRIM ARY OPERATOR DETAILS 9.0 l'1, ANT COOI DOWN (cont.)
9.35 WIIEN pressurizer pressure is ! css than 1000 psia [1000 psial, A. Direct an auxiliary operator to open ene n of the following AND letdown is in service, LETDOWN CONTROL VALVE INLET VALVES: TilEN align the standby letdown control valve. T CilN-V341 for CllN-LV-110P. CllN-V341 is located in O Continue in this appendix. the letdown control valve gallery, on the 110 ft elevation. 'U CilN-V343 for CIIN-LV-110Q. CLIN-V343 is located 2 outsidc the letdown heat exchanger room, on the 100 ft clevation. O 7 K II . Select DOTil with the LETDOWN CONTROL VALVE D LV-110P/l 10Q SELECTOR, CLIN-1IS-110 1, on 1103. d O C. Direct an auxiliary operator to open gne of the following Z LETDOWN CONTROL VALVE OUTLET VALVES: O CIIN-V342 for CilN-LV-110P. CilN-V342 is loca the letdown control valve gallery, on the 110 ft elevation. < CllN-V340 for CIIN-LV-110Q. CIIN-V340 is located outside the letdown heat exchanger room, on the 100 ft clevation.
1ey + EXCESS STEASI I)ESI ANI) 41 E I'-l 11004 Revision 00.04 PVNGS Appendix A Page 60 of 74 Total 231 l'RIN1ARY Ol'ERATOR ACTIONS PRIMARY OPERATOR DETAILS 9.0 l'I, ANT COOI.DOWN (cont.) 9.36 WilEN pressuri7er pressure is less than 1000 psia (1000 psial, A. Direct an auxiliary operator to open one of the following AND letdown is in service, 13 ACKPRESSURE CONTROL VALVE INLET VALVES: TilEN align the standby backpressure control valve. r1 CIIN-V347 for CIIN-PV-201Q. CilN-V347 is located O Continue in this appendix. outside the letdown heat exchanger mom, on the 100 ft "U clevation. - Z CilN-V348 for CIIN-PV-20lP. CllN-V348 is located in T the letdown control valve gallery, on the 110 ft elevation. O
'D E
II . Select ilOTil with the IErDOWN B ACK-PRESS VLV 3> PV-20 l P/201Q SELECTOR, CilN-IIS-201, on 1103. d O C. Direct an auxiliary operator to open _om of the following Z B ACKPRESSURE CONTROL VALVE OU'lLET VALVES: O CLIN-V349 for CilN-PV-201Q. CIIN-V349 is located 2 outside the letdown heat exchanger room, on the 100 ft clevation. k CIIN-V350 for CIIN-PV-20lP. CIIN-V350 is located in the letdown control valve gallery, on the 110 ft elevation.
EXCESS STEAM I)EMANI) 41 El'- 1 R OO4 Revision 00.04 PVNGS Appendix A Page 61 of 74 Total 234 l'RIN1 ARY OPERNIUR ACI' IONS PRlh1 ARY OPER ATOR DETAILS 9.0 Pl, ANT C()OI 1)()WN (cont.) 9.37 Will!N the CRS has directed. A. Energize o_nc of following SIT VENT VALVE POWER ANI2 pressurizer pressure is less than 750 psia 1860 psial. SUPPLY Switches: TilEN depressurize the SITS to between 300 and 310 psig. n Train B Train A Continue in this appendix. ~ SIB-IIS-18A SI A-llS-17A g 71 O 11 . Depressurize all of the SITS in the table below to between
~
300 and 310 psig, using the SAFETY INJECTION TANK E VENT VALVES in the energi7cd train: Train B Train A O SIT 7 1A SIB-llS-633 A SI A-IIS-607A O Z 18 SIB-IIS-643A SI A-IIS-608 A r" 2A SIB-IIS-613A SIA-IIS-605A 2 11 SIB-IIS-623 A SIA-IIS-606A C. De-energize the energized SIT VENT VALVE POWER SUPPLY: Train B Train A SIB-llS-18A SI A-IIS-17A
.. ~,
EXCESS STEAM DEMAND 41 El'- 1 R 004 Revision 00.04 PVNGS Appendix A Page 62 of 74 Total 234 PRIM ARY OPERATOR ACflONS PRIMARY OPERATOR DETAILS 9.0 Pl, ANT COOL,DOWN (cont.) 9.38 WilEN all of the following conditions exist: The CRS has directed. n O Pressurizer pressure is less than 410 psia 1390 psia). g
~
RCS This less than 350 F1338 Fl. Z
*n TilEN perfonn both of the following to isolate the SITS: O "U
- l. Direct an auxiliary operator to unlock and close the supply Direct an auxiliary operator to PERFORM SIT isolation Valve E breakers to.all of the SITisolation valves. Power Alignment, Attachment A-5 to this appendix. 3>
-i O
- 2. Close an of the SIT isolation valves. Close all of the SIT isolation valves: 7 Continue in this appendix.
SIT I A OUTLET TO RC LOOP 1 A VLV, SIA-IIS-634. O Z SIT IB OUTLETTO RC LOOP 1B VLV, SIA-IIS-644. Q SIT 2A OUTLET TO RC LOOP 2A VLV, SIB-IIS-614. SIT 2B OUTLET TO RC LOOP 2B VLV, SIB-IIS-624.
~
_ .. s_,. . EXCESS STEAM I)EM ANI) 41 E l'- 111004 Revision 00.04 PVNGS Appendix A Page 62 of 74 Total 234 PRIMARY Ol'ER ATOR ACflONS PRIMARY OPERATOR DETAILS 9.0 PI, ANT COOI,DOWN (cont.) 9.38 W!!EN all of the followinc conditions exist: The CRS has directed. m O Pressurizer pressure is Icss than 410 psia [390 psial. "X3 Z RCS Th is less than 350'F 1338"Fl. T TilEN perfonn both of the following to isolate the SITS:
- 1. Direct an auxiliary operator to unlock and close the supply Direct an auxiliary operator to PERFORM SIT lsolation Valve S _
breakers to allof the SIT isolation valves. Power Alignment, Attachment A-5 to this appendix. O
- 2. Close all of the SIT isolation valves. Close all of the SITisolation valves: 2 Continue in this appendix. SIT I A OUTLETTO RC LOOP 1 A VLV, SI A-IIS-634.
SIT IB OUTLETTO RC LOOP IB VLV, SIA-IIS-644. k SIT 2A OUTLETTO RC LOOP 2A VLV, SIB-IIS-614. SIT 2B OUTLETTO RC LOOP 2B VLV, SIB-IIS-624.
EXCESS STEAM DEM AND 41 E P-l R O O4 Revision 00.04 PVNGS Appendix A Pagc 63 0f 74 Total 234 PRIMARY OPERNIUR ACI'lONS PRIM ARY OPERATOR DETAILS 9.0 P1, ANT COOI,DOWN (cont.) ______________________________________________________________.._________-NOTE-------------------------------------------------------------------------__ Voiding in the RCS may be indicated by a_ny of the following indications, parameter changes, or trends: m
- 1. Letdown flow is greater than the charging flow. O 33
- 2. Pressurizer level is increasing significantly more than expected while operating pressurizer spray. -
Z
- 3. Pressuri7er level is decreasing significantly more than expected while operating pressurizer heaters. T O
- 4. The RVLMS indicates less than 100% RVUll level.
3 E
- 5. 1 UTC unheated thermocouple temperature indicates saturated conditions in the RVUll. >
.. I -
- 6. The RCS cannot be depressurized. O g
9.39 IE RCS voiding prevents RCS depressurization, O TilEN PERFORM Emergency Operations,41EP-lEOOl, 2 Appendix A, RCS Void Detemiination and Control, beginning Q with Step 1.1. RETURN TO Step 9.40 in this appendix. _ - . - - - -- - e- + - , - -- _ - -4
_; v EXCESS STEAM DEM AND 41 EP-1 It 004 Revision 00.04 PVNGS Appendix A Page 64 of 74 Total 234 PRIMARY OPERATOR ACI'lONS PRIMARY OPERATOR DETAILS 9.0 PLANT COOLI)OWN (cont.) 9.40 Ensure that all of the fellowing SDC system entry conditions exist: m Pressurizer level is being maintained greater than 337o [407cl. O 33 RCS subcooling is acceptable. See Normal Containment RCS Pfr Limits [ Harsh Containment - RCS P/r Limits], on the control board. Z T O Pressurizer pressure is less than 395 psia [330 psial. 33 3 RCS Thi sless than 353 F[338 F]. > d 9.4 i Check that all Section 9.0 steps have been addressed. O Z O Z r-
4 mom _ZmOxE> DOZ OZr<- 3 2 l a to . T 4 7 - f o S 5 L I 6 A e T tg E i l D A R . x O i T d n A e R . p E p P A O Y S R G A N MI V R P > l 4 0 0 0 n - o is i v e R 4 , 0 0 t I -- 1 l E 1 4 S d e N t s IO e u I q C e r A s D R a N O s r e A T t M A w; R T n E i l N n a D l' O I p - O t n Y M R l' lp a A A S
] f E M l o
T I T S S R
> A R l
T C S S e S T ht E N n C A, n o X 1 f n . E l' I
. 1 0
1 0 0 1
EXCESS Sl'EAM I)IGI ANI) 41 EI'- 11(004 Revision 00.01 PVNGS Appendix A Page 66 of 74 Total 234 PRIM ARY OPER ATOR ACl'lONS PRIMARY OPERNIDR DETAILS i 1.0 PROCEDURE EXIT II.I Steps 1I.I through iI.4 - CRS is ensuring that all administrative requit entents are inct.
"T1 O
11.5 IE Spray Valve Actuation Data Shect, Attachment A.4 to this "D appendix, was used, TilEN ensure that the data in the attachment is being transferred Z "T1 into 1(CS and Pressurizer lleatup and Couldown Rates, 40ST-9RC01. O a g 11.6 GO TO the procedure selected by the CRS. 35
--I
. O Z
END OF PROCEDURE O Z r-
, m.
EXCESS STEAM DEM AND 41 El'- 1 It 004 Revision 00.04 PVNGS Appendix A Page 67 of 74 Total 234 ACrlONS DETAllS ATTACilMENT A-1 Charging l' ump Suction from the RWT Page1 of1 A- 1.1 Open RWT TO CliARGING PUMPS SUCTION, CilB-V327. CilB-V327 is located in the cast mechanica! piping penetration room,70 ft cicvation southwest corner.
]
x A-1.2 Open CIIARGING PUMP A ALTERNATE SUCTION, CilA-V755 is located in the A charging pump ante room. y CII A-V755. m O I A-1.3 Close CilARGING PUMP A SUCTION, CllA-V316. CIIA-V316 is located in the A charging pump ante room. g
-1 A-1 A Open CIIARGING PUMP B A11rERNATE SUCTION, Cilll-V756 is located in the B charging pump ante room.
O. CllB-V756. Z O A-l.5 Close CIIARGING PUMP B SUCIION, CIIB-V319. CilB-V319 is located in the B charging pump ante room. z r-A-1.6 Open CilARGING PUMP E ALTERNATE SUCFION, CIIE-V757 is located in the E charging pump ante room. CIIE-V757. A-1.7 Close CilARGING PUMP E SUCTION, CllE-V322. CIIE-V322 is located in the E charging pump ante room. A-1.8 Infomi the control room that this attachment is complete. END OF ATTACilMENT
EXCESS STEAM DEM AND 41 E P-1 It 004 Revision 00.04 PVNGS Appendix A Page 68 of 74 Total 234 AC1'lONS DETAILS ATTACllMENT A-2 Chaiging Pump Suction from the SFP Page1of1 A-2.1 Align RWT TO B AM PUMPS SUCr VLV, Cilli-IIV-532, for A. Unlock the CilE-IIV-532 handwheel in accordance with nonnal operation. Locked Valve, lireaker, And Component Control, T 40AC-07ZO6. CilE-1IV-532 is located in the BAMP room. O 23 B. Turn the CilE-IIV-532 handwheel clockwise /close until the g pomter mdicates neutral. 7 O C. Unlock and open INSTRUMENT AIR TO CllE-IIV-532, 1 AN-V252, in accordance with Locked Valve, lircaker,3 g-And Component Control,40AC-0Z7.06. IAN-V252 is p located on the west wall in the BAMP room. q O A-2.2 Open both of the following valves: Z O SFP TO BAMP ISOLATION VALVE, CilN-V144. CIIN V144 is located in the B AMP room. g r" SFP TO BAMP ISOLATION V ALVE, PCN-V215. PCN-V215 is located in the fuct building,115 ft elevation, on thew: nonh wall of the heat exchanger area. A-2.3 Record IAN-V252 and CilE-IIV-532 handwhcci pointer positions in Locked Valve, lireaker, And Component Control, 40AC-0ZZ06 A-2.4 Infonn the control room that this attachment is complete. ENI) OF ATTACilMENT m.-_m- -am .._. ----._m.-__ _ _. 9_+* "
- t 9'
. . v EXCESS STEAM I)EMANI) 41 E P-111004 Revision 00.04 PVNGS Appendix A Page 69 of 74 Total 234 ACflONS DETAILS ATTACilMENT A.3 Bonin Dilution Alann Channel Check Page1of4
.......__.........._.....___......._......____............___._....._...... NOTE-----------------------------------------------------.--.----..----.--------
This attaciunent satisfies surveitlance requirenients 4.1;2.7.a.2.a and 4.1.2.7.a.2.b for their initial perfonnance. T O
"U
__ A-3.1 Place the startup channel instrunients in service. A. Select the S-U ClIAN position with both Channels I and 2 g CONTROI/STARTUP CilANNEL SELECTOR switches, y SEN-IIS-5A and SEN-llS-6A, on B04. O 33 B. Ensure that the METER SELECT pushbutton is in the g START UP position on both of the NUCLEAR y INSTRUMENTATION START-UP AND CONTROL g DRAWERS. - O C. Press the IIV PERMIT /IIV ON button on both of the Z NUCLEAR INSTRUMENTATION START-UP AND O CONTROL DRAWERS. g r"
EXCESS STEAM DEMAND 41 EP-1ROO4 Revision 00.04 PVNGS Appendix A Page 70 cf 74 Total 234 ACTIONS DETAILS ATTACIIMENT A-3 Boron Dilution Alann Channel Check (cont.) Page 2 of 4 _____ NOTE ---------- ----- If only 1 channel is availabl.: a deviation comparison is not possible. For this case a qualitative assessment of channel behavior is T performed on the remaining channel. O _________________-- ______________________ ___________ _____________ ________________ ______ ._______________ "D Perfonu the columns below for each channel: A-3.2 Perfonn a channel check on the staitup channels. a Startuo Channel 2 a Startun Channel 1 g Record Channel I count rate: cps. Record Charmel 2 count rate: cps. Calculate the instrument voltage corresponding to Channel 1 Calculate the instrument voltage corresponding to Channel 2 O' count rate: count rate: 2 Vdc. 3 V I= 2 Log (channel 1 reading in cps) =_ Vdc. V2 = 2 Log (channel 2 readiag in cps) = g Ilighest Vdc reading Vdc - Lowest Vdc reading Vdc = AVdc Vdc Acceptance Criteria: AVdc is less than or equal to 0.8 Vdc A-3.3 IE AVdc is greater than 0.8, TilEN infonn the CRS that the acceptance criteria has not been met, which indicates an inoperable startup channel.
EXCESS STEAM DEMAND 41 EP-1 RO O4 Revision 00.04 PVNGS Appendix A Page 71 of 74 Total 234 ACTIONS DETAILS Page 3 of 4 ATTACIIMENT A-3 lloron Dilution Alann Channel Check (cont.)
........................................................................----NOTE--------------------------------------------
If only I channelis available a deviation comparison is not possible. For this case a qualitative assessment of channel behavior is T performed on the remaining channel. ... .......... O m A-3.4 Perfonn a channel check on the baron dilution alarms. Per on e colmiins o v or each channel at the miscellaneous g m J Channel IJSEN-N1-005 Channel IJSEN-NI-006 U S Press the RESET pushbutton to reset the alann. Press the RESET pushbutton to reset the alann. f Ensure that the FLUX / SET POINT pushbutton is selected to Ensure that the FLUX / SET POINT pushbutton is selected to d FLUX. O FLUX. Z Ensure that the digital display is not flashing. Ensure that the digital display is not flashing. g (Acceptance Criteria is the display not flashing.) (Acceptance Criteria is the display not flashing.) 7 Ensure that the decimal point is flashing. Ensure that the decimal point is flashing. (Acceptance Criteria is the decimal indicator Gashing at
]
(Acceptance Criteria is the decimal indicator flashing at about I flash per second.) about I flash per second.) Record flux reading: Vdc Record flux reading: Vdc Vdc Lowest flux reading Vdc = AVdc Vdc Ilighest flux reading Acceptance Criteria: AVdc is less than or equal to 0.8 Vdc A-3.5 IE AVdc is greater than 0.8, TIIEN infonn the CRS that the acceptance ciiteria has not been met. which indicates an inoperable boron dilution alamt
4
.Z Ow5>i.Oz
- . OZk 3
2 . l a t o T 4 4 s. 7 f f o o 4 2 e e 7 g e a i m g P T a P A id x b n lA e ' I p A p E I e e e n t a i m .u S D T 1 G N V P M M l s X ( a e e t n i t :a a o i I n D D i is v e
)
R l i a 4 i t 0 ) i n 0 1 tn o ( _. 1 ( c 1
- k c
P e h E C . 1 l 4 e n ) n a o er e r e r h n t u e
/ tt tt -
C t s e a a a u w n n n n l o ( y i g i g i g a e e S S S b n lA n o
) n o I
o it e N 3 it a lcr A 3 g l i u mi C D m M g g f n ? T E - n ( o i t t e N D g r o s e m E . H t e a M M c n i r l l A la t e C E l i i r A T e v C r o T S 3- r u e r e is T A s c n w v A S e r ht a e e F S T t p : i v p O E N t e y e u n c b r S C E o c e t D - c d c f N X M R e A e n n a i h E E l l ht e n tp S
/t C 6 f o e c s A 3 e
r r c s e T - A P A A T A A
EXCESS STEASI I)ESI ANI) 4 I El'- 1 It 004 Revision 00.01 PVNGS Aprendix A l' age 73 of 74 Total 231 ATI'ACll All':NT A-4 Spray Valve Actuation I)ata Sheet Page1ofI l'ressurizer Main Spray Cycle Log Pressurizer Auxiliary Spray Cycle Log Cycle Time SPR AY LOOP SI'R AY LOOP Pressurizer loitial Cycle Time REGENERATIVE Pressurizer Initial Number IA 1 11 TEMPERATURE Number IlX OUTLET TEMPERATURE TEMPliRNTURE TE-101 TE-103 TE-101 Tli-101 T1 RCN-TI- 103
- RCN-TI-103* RCN-TI-101 CIIN-TI-229' RCN-TI-101 0
- D i 1 lZ
~ii 2 2 0
;U 3 3 3 4 a .
-{
'5 '5 0
- Z 6 6 0 lZ-7 7 l 8 8 9 9 10 10 11 11 12 12
- For operations in the manual mode with less than 4 pump.s n"m; - Log spray line temperature before spray valves are opened.
log spray line temperature before the spray valves are opened.
EXCESS STEAM DEMAND 41 EP- 111004 Revisian b ).04 PVNGS Appendix A Page 74 of 74 Total 234 MTIONS DETAILS ATTACllMENT A-5 SIT isolation Valve Power Alignment Page1 ofI ____ A - 5.1 Energize the SIT isolaiion valves. Unlock and select ON with aji of the SIT isolation valve supply y breakers listed in the table below,in accordance with 1,ocked O Valve, lireaker, And Component Control, 40AC-07.7.06: g 7 Breaker Location U~1 O SAFETY INJECTION TANK 3 ISOL VLV J-SI A-UV-634.1-LPHA-M3316 Electrical Penetration Room A, ;3 Auxiliary Building,120 ft level M BACK-UP BREAKER i OR M3316, #1-E-P1I A-M3316A p
- 1 S AFliTY INJECTION TANK 4 ISOL VLV J-SIA-UV-644,1-E-Pila-M3318 Electrical Penetration Room A, O d-Auxiliary Building,120 ft level BACK-UP BREAKER FOR M3318, #1-E-Pila-M3334 O 2
r - Electrical Penetration Room B, - S AFETY INJECTION TANK 1 ISOL VLV J-SIB-UV-614, #1-E-PilB-M3619 Auxiliary Building,100 ft level B ACK-UP BREAKER FOR M3619,1-E-PIIB-M3641 A SAFETY INJECrlON TANK 2 ISOL VLV J-Sill-UV-624, #1-E-PIIB-M3618 Electrical Pcnctration Room B, Auxiliary Building,100 ft level BACK-UP BREAKER FOR M3618,1-E-PIIB-M3M1 END OF ATTACllMENT
EXCESS STEAM DEMAND 41 E P- 1 I(O O4 Revision 00.0-2 PVNGS' Appendix B Page 1 of 61 Total 2.34 m O m Z SECONDARY OPEllATOlt ACTIONS [ x E Oll.IECTIVE O This appendix proviiles the secondary operator actions which must be accomplished after an excess steam demand. The Z actions in this procedure are necessary to ensure that the plant is placed in a safe, stable condition. The goal of this procedure is to establish SDC entry conditions. O g F
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m EXCESS STEAM DEM ANI) 41 E P-1 It 004 Revision 00.01 PVNGS Appendix B Page 4 of 61 Total 231 3.0 ICVENT CONTitOI, (cont.) 3.15 lij all of the following comlitions exist: Steam generator level is below 2'To [13%] WR. Steam generator pressure is decreasing. "Tl O Tc is approaching Th. 33 TIIEN infonn the CRS that a steam generator is approaching dryout conditions. O 33 3.16 Stabilize Tc in the loop with the highest pressure steam generator using ADVs. q O 3.17 Align at least i ADV frr>m the steam generator with the highest Perfonn the actions in the table below to align at least 1 ADV fronZ pressure for operation. the steam generator with the highest pressure for operation: O
'Z l
SG 1 LINE 1 ISOL SG 1 LINE 2 ISOL SG 2 LINE 1 ISOL SG 2 LINE 2 ISOL ' ACTION VLV. SGA-IIV-184 VLV. SGB-IIV-178 VLV. SGB-IIV-185 VLV. SG A-IIV-179 A. Lower ADV VALVE CONTROL SGA-IllC-184 A SGB-IIIC-178A SGB-IIIC-185A SGA-IIIC-179A outputs to minimum. B. Select OPEN PERM on SGA-flS-184A SGB-IIS-178A SGB-ilS-185A SGA-IIS-179A both ADV permissives. SGC-IIS-184B SGD-IIS-178B SGD-IIS-185B SGC-IIS-179B
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s,, 'g48 EXCESS STEAM I)EMAND 41 EP-1 ROO4 Revision oo.m PVNGS Appendix B Page 7 of 61 Total 231 3.0 EVENT C()NTR()L (cont.) ________.____.......__..___...___.....________________.______......N()TE----------------------------------------------------------------------------- An excess steam demand may affect both steam generators. When both steam generntors are affected, the least affected is considered intact. The most affected steam generator is considered to be faulted. The faulted steam generator will have lower pressure and level than the intact steam generator, m __________...._.._____...._........________.............___.....___----N()TE------------------------------_--_----------------------------------------- O D Before the faulted steam generatordries out,its RCS loop Tc will be the lowest. After the faulted steam generator dries out, its RCS loop 5 Tc will be the highest. m _____________________.__.._______________. ______.____._____________._________________.. _... ......___. _____________________. .__..... _.. ____________________- O Ja 3.30 identify the steam generator that is faulted. Evaluate n!! of the parameters in the tabic below for each steam E generator to identify the faulted steam generator: )>
- _{
O Parameter Steam Generator 1 Steam Generator 2 - g Lowest steam generator pressure O Lowest RCS loop Te (before steam genciator dryout) Q liighest RCS loop Tc (following steam generator dryout) Lowest steam generator level Record the faulted steam generator .
EXCESS STEA AI I)EM ANI) 41 E P- 1 It 004 Revision 00.04 PVNGS Appendix B Page 8 of 61 Total 2_Lt 3.0 EVENT CONTROL. (con:.) ___._________________________________________._____.----------------------NOTE--------------------------------------------------------------------------- An excess steam demand may af fect both steam generators. When both steam generators are affected, the least affected is considered intact. The most affected steam generator is considered to be faulted. The faulted steam generator will have lower pressure and level than the intact steam generator. ________________________________... _________________ _________________________________________.._____________ ___________________________________________________ T O 3.31 WIIEN the CRS has directed, Ensure that allof the following valves in the tab:e below for the 3 TlIEN isolate the faulted steam generator. faulted steam generator are closed: g m Steam Generator i Steam Generator 2 O y S SG 1 Line 1 ADV, SGA.IIV-184 SG 21.ine 1 ADV, SGB-IIV-185 g
-1 SG 1 Line 2 ADV, SGB-11V-178 SG 2 Line 2 ADV, SGA-IIV-179 -
O AFW TO SG 1 DOWNSTREAM VLV, AFC-IIS-36A ARY TO SG 2 DOWNSTREAM VLV, AFA IIS-37A Z AUX FWTO SG 1 DOWNSTREAM VLV, AFB-IIS-34A . AUX FW TO SG 2 DOWNSTREAM VLV, AFB-IIS-35A g O SG 1 STM SPLY TO PMP, SGA-IIS-134 A SG 2 STM SPLY TO PMP, SGA-IIS-138A < SG 1 COLD LEG ISOL VLV, SGN-IIS-41 SG 2 COLD LEG ISOL VLV, SGN-IIS-44 (Blowdown isolation) (Blowdown Isolation) SG 1 IlOT LEG ISOL VLV, SGN-IIS-43 SG 2 IlOT LEG ISOL VLV, SGN-IIS-42 (Blowdown isolation) (Blowdown Isolation)
EXCESS STEAM I)EMANI) 4 i E P- 1 It 004 Revision OuO ! PVNGS Appendix B Page 9 of 61 Total 234 3.0 EVENT CONTROL. (coni.)
.-_--.._....--....----.....--....------._-----..................------NOTE----------------------------------------------------------------------------
An excess steam demand may atfcct both steam generators. When both steam generators are affected, the icast affected is considered intact.The most affected steam generator is considered to be faulted. The faulted steam generator will have lower pressure and level than the intact steam generator. y m 3.32 Ensure that the isolated steam generator is the fauhed steam Evaluate the parameters in the table below for the intact steam generator. generator to ensure that the faulted steam generator is isolated: y T O Parameter Steam Generator 1 Steam Generator 2 D R Pressure is stabilized or d recovering in the intact y steam generator
]
Level is stabilized or E recovering in the intact O steam generator Z Tc is stabilized or recovering in the intact RCS loop
- -__.a-.._ .-ma- L - - _'- __ e+ . ye= M e 4 ,m_, y
_ . . . ..z. . _ . . . ~ _ ~ ~ ~ . , ~ , - , e v' EXCESS STEAM DEMAND 41 E P- 111004 Revision 00D1 PVNGS Appendix B Page 10 of 61 Total 234 3.0 EVENT CONTROL. (cont.) 3.33 E the diagnosis was correct and the faulted steam generator has tren isolated, TlIEN GO TO Step 3.36 in this appendix. m 3.34 E the faulted steam generator has NOT been isolated, Restore all of the following valves in the table below for the steamO TlIEN restore the steam generator that was incorrectly isolated. generator that was incorrectly isolated to the required position for T plant conditions: g m Steam Generator i 3 Steam Generator 2 m SG 1 Line 1 ADV, SGA-IIV-184 SG 2 Line 1 ADV, SGB-llV-185 S f y. SG 1 Line 2 ADV, SGB-IIV-178 SG 2 Line 2 ADV, SGA-IIS-179 -- O AFW TO SG 1 DOWNSTREAM VLV, AFC-IIS-36A AFW TO SG 2 DOWNSTREAM VLV, AFA-IIS-37A :Z O AUX FWTO SG 1 DOWNSTREAM VLV, AFB-llS-34A AUX FW TO SG 2 DOWNSTREAM VLV, AFB-IIS-35A g SG 1 STM SPLY TO PMP, SGA-IIS-134A SG 2 STM SPLY TO PMP, SGA-IIS-138A < SG 1 COLD LEG ISOL VLV, SGN-ilS-41 SG 2 COLD LEG ISOL VLV, SGN-IIS-44 (Blowdown Isolation) (Blowdown isolation) SG 1 IlOT LEG ISOL VLV, SGN ilS-43 SG 2 IlOT LEG ISOL VLV, SGN-IIS-42
- (Blowdown Isolation) (Blowdown isolation) i
v EXCESS STEAM DEMAND 41 E P-11t 004 Revision 00.04 PVNGS Appendix B Page 11 of 61 Total 234 3.0 EVEN'l' CONTROL (cont.) 3.35 Isolate the steam generator that was inconectly diagnosed as Ensure that a_Il of the fo!!owing valves in the table below for the being intact. faulted steatn generator are closed: Steam Generator i Steam Generator 2
]
SG 2 Line 1 ADV, SGB-IIV-185 U SG 1 Line 1 ADV),SGA-IIV-184 {; SG 1 Line 2 ADV, SGB-IIV-178 SG 2 Line 2 ADV, SG A-IIV-179 bh AFW TO SG 2 DOWNSTREAM VLV, AFA-IIS-37A O AFW TO SG 1 DOWNSTREAM VLV, AFC-IIS-36A - n
=
AUX FW TO SG 1 DOWNSTREAM VLV. AFB-IIS-34A AUX FW TO SG 2 DOWNSTREAM VLV, AFB-IIS-35A ![ SG 1 STM SPLY TO PMP, SGA-IIS-134 A SG 2 STM SPLY TO PMP, SGA-IIS-138A - O SG 1 COLD LEG ISOL VLV, SGN-ilS-41 SG 2 COLD LEG ISOL VLV, SGN-I-IS-44 Z (Blowdown Isolation) (Blowdown isolation) g 7 SG 1 IlOT LEG ISOL VLV, SGN-IIS-43 SG 2 IlOT LEG ISOL VLV, SGN-IIS-42 i:< (Blowdown Isolation) (Blowdown Isolation) - t l 336 Steps 336 throtagh 338 - PO rnay be stopping CS. I 1
EXCESS STEAM I)EMAND 41 El'-I R 004 Revision 00.04 PVNGS Appendix B Page 12 of 61 Total 234 3.0 EVENT CONTR()l, (cont.) 3.39 IE the CRS has directed, A. Scicct STOP with 3 of the following fan switches: AND a CS AS has actuated. TIIEN ensure that ;all of the containment fans are stopped. PRZR NORM AL CLG FAN A,IICN-ilS-354 PRZR NORMAL CLG FAN B, IICN-ilS-355. 'g REAC CAVITY CLG FAN A,IICN-IIS-58. _ REAC CAVITY CLG FAN C,IICN-ilS-60. z n O REAC CAVITY CLG FAN B,llCN-IIS-59. U REAC CAVITY CLG FAN D, IICN-IIS-61. 3 p, B. Place d of the following fan switches in PULL TO LOCK: CNTMT NORMAL ACU FAN A,IICA-IIS-11. O Z CNTMT NORMAL ACU FAN C,ilCA-IIS-13. I-- CNTMT NORMAL ACU FAN B,IICB-IIS-12. CNTMT NORMAL ACU FAN D,llCB-IIS-14 CEDM ACU FANS A/C,IICA-IIS-49. CEDM ACU FANS B/D,llCB-IIS-50.
_ m v EXCESS STEAhl DEh1AND 41 E P-111004 Itevision 00 04 PVNGS Appendix B Page 13 of 61 Total 234 3.0 1;VI:NT CONTitOi, (cont.) 3.40 PC is performing Hor,:n Dilution Alarm Charmcl Check. 3.4 I CRS may be ensuring that the LCO action requirements are met. m O a 3.42 Steps 3.42 and 3.43 - PO may be c:ontrolling the pressurizer spray valves. 2 m O-D E
-1 O.
Z O Z r-
EXCESS STEAM I)EMANI) 41 EP-1 R OO4 Revision 00.01 PVNGS Appendix B Page 14 of 61 Total 234 3.0 EVENT CONTitol, (cont.) 3.<t d if the CRS has directed. A. PliRFORM the appropriate attachment to reduce the inventory TlliiN align the fauhed ste nn generator for high rate blowdown in the faulted steam generator: to the condenser. Steam Generator 1 Level Reduction Checklist, Attachment B-1 to this appendix. T O Steam Generator 2 Level Reduction Checklist, 3 Attachinent B-2 to this appendix. g B. Return to Step 3.47. [ 3.45 CRS inay be informing Radiation Protection and the RMS y technician of the steam relcase. y
-i 3.46 CRS may be directing an operator to restore oJJsite power.
.O Z
3.47 Check that aji Section 3.0 steps have been addressed. O Z r-
mO2 ZmO3E2 DOZ OZr<- 1 . 3 - _ 1 3 _ 2 _ l _ ta _ o _ T _ 1 6 f o 5 1 e g a P 1 1 i x d n ep p A S G N . V P 4 0 0 0 n o is i v e R 4 0 0 ( _ 1
- 1 .
P E 1 4 d . te s e u t t e r s D a N s r _ A e te M T m E N a r a D I p O t n M l' lap A S E U f o T T S S A R T C S S e S T ht E N m C A, ro X l f n E P I 1 _ 4. 0 _ 4
v EXCESS STEAM DEMAND 41 E P-1 ROO4 Revision 00.04 PVNGS Appendix B Page 16 of 61 Total 234 5.0 Pl, ANT STAltli,1ZATION 5.1 Begin a nonnal response to new alanns. CAUTION m
-O-Overriding an AFAS and thronling Cow when the steam generator level is below 27o [13%] WR may result in a loss of heat removal. g Z
______..___________._____._____________________---------NOTE--- =----_ -------- _ ------ . _ _ _ _ _ T AFW valves that are in override will not auto actuate. Operator action will be required to maintain the steam generator levels. O D E 5.2 IF an AFAS has actuated, y AND at least 1 steam generator level is above 270113%) WR, i TilEN perfonn all of the following: 3 Override and adjust all of the valves to the intact steam generator 2
- 1. Override and adjust the ARV valves to establish the intact steam generator level between 72 and 807o 178 - 847oJ WR. in the table below: O Z
Essential Steam Driven Auxiliary Feedwater Pump Essential Electric Driven Auxiliary Feedwater Pumo k AFW TO SG 1 UPSTREAM VLV, AFA-IIS-32A AUX FW TO SG 1 UPSTREAM VLV, AFB-IIS-30A ARV TO SG 2 UPSTREAM VLV, AFC-IIS-33A AUX FW TO SG 2 UPSTREAM VLV, AFB-IIS-31 A ARV TO SG 1 DOWNSTREAM VLV, AFC-IIS-36A AUX FW TO SG 1 DOWNSTREAM VLV, AFB-IIS-34A AFWTO SG 2 DOWNSTREAM VLV, AFA-IIS-37A AUX FW TO SG 2 DOWNSTREAM VLV, AFB-IIS-35A
- 2. Ensure that the intact steam generator level is being maintained.
- 3. GO TO Step 5.10 in this appendix.
EXCESS STEAM DEMAND 41 E P-1 It 004 Revision 00.01 PVNGS Appendix 13 Page 17 of 61 Total 234 5.0 l'I. ANT STAltII,17. ATION (cont.)
..................__.............__._....................._...... NOTE-------------------------------------------------------------------------_
The CRS alw, perfonos the decision table below. The CRS will direct which AFW pump to place in service. ri 5.3 WIIEN the CRS has directed, Evaluate the table bclow and GO TO the appropriate step to ensurcO AND an AFAS has NOT actuated, that an auxiliary feed pump is placed in service: D TlIEN ensure that an asixiliary feed pump is placed in service. Z T1 Start-up Auxiliary Feedwater Essential Electric Driven Essential Steam Driven ' 3 Pump, AFN-P01 Auxiliary Feedwater Pump, Auxiliary Feedwater Pump, 33 AFH-Pol AFA-P01 3
-l WilEN the CRS has directed, WilEN__ the CRS has directed, TlIEN GO TO Step 5.4 in this WilliN the CRS has directed, TIIEN GO TO Step 5.5 in this 3
T!!EN GO TO Step 5.7 in this 2 appendix to start AFN-POI. appendix to start AFil-P01. appendix to start AFA-POI. ' 3 Z r-T .__
-- +
. ~ s m
EXCESS STEAM DEMAND 41 El'-l R O O4 Revision 00.04 PVNGS Appendix B Page 18 of 61 Total 234 5.0 l'I,A NT STAllll,IZ ATI()N (cont.)
........................................................................-N()YE-----------------------------------------------------------------------------
~1 he essential electric driven and start-up AFW pumps discharge pressure alanns are expected to alann at full auxiliary feed flow.
5.4 lij the CRS has directed to place Essential Electric Driven Record the intact steam generator . 7 Auxiliary Feedwater Pomp, AFil-P01, in service to the intact O steam generator, y TilEN perfonn all ofinc following: _ Z
- l. Start ESS ELECTRIC AUX FEED PUMP, AFB-IIS-10. n O
- 2. Open the AFW downstream valve to the intact steam Open the valve to the intact steam generator: ti generator. g AUX FW TO SG 1 DOWNSTREAM VLV, AFB-1IS-34A.)
--I AUX FW TO SG 2 DOWNSTREAM VLV, AFB-IIS-35A.-
O Z
- 3. Jog open the AFW upstream valve to the intact steam A. Jog open the valve to the intact steam generator: O generator to establish a feedwater flow rate of at least Z 500 gpm. AUX FW TO SG 1 UPSTREAM VLV, AFB-IIS-30A. I--
I AUX FW TO SG 2 UPSTREAM VLV, AFB-IIS-31 A. B. Ensure that feed flow is established to the intact steam generator. C. Establish a steam generator level between 72 and 80% [78 - 84%] WR. D. Limit the pump amps to 151 amps.
- 4. GO TO Step 5.10 in this appendix.
s - EXCESS STEAM DEMAND 4 I E P-I R 004 Revision (XMM PVNGS Aprendix 11 Page 19 of 61 Total 234 5.0 Pl. ANT ST Allll.lZATION (cont.) 5.5 lij directed by the CRS to place Essential Steam Driven Auxiliary Record the intact steam generator Feedwater Pump, AFA-IUl. in service to the intact steam generator. TlIEN perform all of the following: ri
- 1. Start the pump. Open the steam supply from the intact steam generator: .O 23 SG 1 STM SPLY TO PMP, SGA-IIS-134A. -
Z SG 2 STM SPLY TO PMP, SGA-IIS-138A. [ x
- 2. Open the AFW downstream valve to the intact steam Open the valve to the intact steam generator: 5
' generator.
M AFW TO SG 1 DOWNSTREAM VLV, AFC-IIS-36A. d o AFW TO SG 2 DOWNSTREAM VLV, AFA-IIS-37A. Z O
- 3. Jeg open the AFW upstream valve to the intact steam A. Jog open the valve to the intact steam generator: f generator to establish a feedwater flow rate of at least 4 500 gpm. ~ AFW TO SG 1 UPSTREAM VLV, AFA-IIS-32A.
AFW TO SG 2 UPSTREAM VLV, AFC-IIS-33A. B. Ensure that feed flow is established to the intact steam
- generator.
l C. Establish a steam generator Icvel between 72 and 80% ( [78 - 84%J WR.
- 4. GO TO Step 5.10 in this appendix.
t 6
EXCESS STEAM I)EM ANI) 41 El'- 1 It 004 Revision 00.0-1 PVNGS Appendix B Page 20 of 61 Total 234 5.0 l'LA NT STAltil.17,.\ TION (cont.) 5.6 CRS may be informine Rattiation l'rviccti<nt and the RMS technician of the stewn ielcase.
..._______.....______..__._________.____.________......______.....__.--NOTE------------------------------------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
]
The essential electric driven and start t.o AFW pumps discharge pressure alarms are expected to alarm at full auxiliary feed flow. x. g 11 5.7 IF directed by the CRS to start Start-up At xiliary Feedwater Record the intact steam generator O Pump, AFN-P01, m TilEN perform both of the following: g 3>
- 1. Open the suction valves. Open both of the following valves: y PMP SUCT FllOM CST VLV, CTA-IIS-1. O Z
PMP SUCT FROM CST VLV, CFA-IIS-4. O Z r-
- 2. Ensure that the downcomer isolation valves are open to the Ensure that both of the following DOWNCOMER ISOL VLVs arc-<
intact steam generator. open to the intact steam generator: Steam Generator 1 Steam Generator 2 SGA-IIS-172 SGA-IIS-175 SGB-IIS-130 SGB-IIS-135
~. w EXCESS STEAM DEMAND 41 E P-I 1(004 Revision 00.04 PVNGS Appendix 11 Page 21 of 61 Total 234 5.0 Pl, ANT STAlill.17, ATit )N (cont.)
5.8 IE Start-up Auxiliary Feedwater Pump, AFN-l'01,is being placed in service, TilEN perfonn allof the following:
- 1. Jog open the feed' vater isolation bypass valve to 10% open Jog open gne of the following valves to the intact steam generator T to the intact steam generator. to 10% open: O 33 SG ! FW ISOL llYPASS VLV, SGN-IIS-Il43. -
Z SG 2 FW ISOL BYPASS VLV, SGN-ilS-Il45. ' O 22
- 2. Close the downcomer feedwater regulating block valves. Close both of the following valves: E SG 1 FW ISOL 11 LOCK VLV, SGN-ilS-1142. d O
SG 2 FW ISOL IlLOCK VLV, SGN-ilS-Il44. Z
- 3. Start S/U Aux Fced Pump, AFA-IIS-II. O g
F
wg EXCESS STEAM DEMANI) 4I EP-1 R004 Rcvision 00.04 PVNGS Appendix B Page 22 of 6i Total 234 5.0 PLANT STAlllLIZATION (cont.) 't 5.9 Transfer feed from the main feed ptnups to Stait-up Auxiliary Feedwater Pump, AFN-P01:
- 1. Lower the speed cf the iunning main feed pumps to below A. Select MANUAL with both of the following:
1000 tpm. "TI FWPT A MANUAL / AUTO SELECT, FTN-IIS-99. O 33 FWPT B MANUAL / AUTO SELECT, FTN-IIS-100. 2 ri B. Lower each turbine speed to below 1000 rpm by turning eachO of the following manual speed control pots counterch>ckwise:33 FEEDWATER PUMPTURB A MANUALSPEED E CONTROL, FTN-IIS-53. FEEDWATER PUMPTURB B MANUAL SPEED O CONTROL, FTN-IIS-54. Z O
- 2. Adjust the feedwater isolation bypass valve to establish an A. Adjust the valve to the intact SG: Z AFW flow of at least 0.28 x 106 lb/hr to the intact steam I""
SG 1 FW ISOL BYPASS VLV, SGN-ilS-Il43. "< generator. SG 2 FW ISOL BYPASS VLV, SGN-IIS-1145. B. Ensure that feed flow is established to the intact steam generator. C. Establish a steam generator level between 72 and 80% [78 - 84%) WR.
- 3. GO TO Step 5.11 in this appendix.
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EXCESS STEAM I)EM ANI) 41 EP-1 It 004 Revision 00.01 PVNGS Appendix B Page 26 of 61 Total 234 5.0 PI, ANT STAltll,1ZATION kont.) C A UTION Overriding an AFAS and tinottling flow when the steam generator level is below 2% l13%I WR may result in a loss of heat removal. ri -
.........................................................................---NOTV----------------------------------------------------------------------------- O~
3 AFW valves that are in override will not auto actuate. Operator action will be required to maintain the steam generator levels. -E m O 5.13 WilEN the CRS has directed, Establish the required feedwater flow to the intact steam generatorm AND AFW has been restored to the intact steam generator, as listed in the table below: g TilEN maintain the intact steam generator level between p 72 and 80% 178 84%) WR. y Continue in this procedure. O SG WR Level Flow Reauired 2 O Above 72% l787o1 WR Enough flow to maintain the steam generator Z level between 72 and 80% [78 - 84'7o] WR F" Between 2 and 727c At least 500 gpm or 0.28 x 106 lb/hr [13 - 78%) WR feedwater flow Below 2% [13%] WR . AFAS actuated and not throttled Between 500 and 1500 gpm or between 0.28 and 0.83 x 10 6 lb/hr I l l l
. u. w EXCESS STEAM DEMAND d i EP-I ROO4 Revision 00,04 PVNGS Appendix B Page 27 of 61 Total 234 5.0 l'i, ANT STAllit.17.ATI()N (cont.)
5.11 Steps 3.14 and 5.15 - !'O is placing the hydrogen analy:crs in service. 5.16 PO may be ensuring that RCP scal blecdoffjlme is isolated. "r1 9
.I3 '
5.17 PO may be controlling pressurizer levcl. 3 m 5.18 WIIEN the CRS has directed, A. Stop toth of the heater drain pumps: TilEN stop the heater drain pumps. IIEATER DRAIN PUMP A, EDN-HS-505. E Continue in this appendix. > llEATER DRAIN PUMP B, EDN-ilS-506. d o Z O Z r-
~ -
EXCESS STEAM DEMAND 41 El'- 1 R 004 Revision 00.04 PVNGS Appendix B Page 28 of 61 Total 234 5.0 l'l, ANT STAllll.lZATION (cont.) 5.19 E;ill of the following conditions exist: Override and open ;il l of the following valves : The CRS has directed. CilW RETURN llDR OUTSIDE CNTMT ISOL VLV, WCA-IIS-62. Plant cooling water is available. T CilW RETURN llDR INSIDE CNTMT ISOL VLv, O Nuclear cooling water is available. WCB-IIS-61. 3 At least I nonnal chiller is available. CilW SUPPLY llDR OUTSIDE CNTMT ISOL VLV, b WCB-llS-63. Containment spray is NOT spraying. Containment p: essure is below 7.0 psig. Override and open a._l]of the following valves: TilEN open the chill water containment isolation valves and the NCW CNTMT UPSTREAM SPLY ISOL VLV, d NC water containment isolation valves. NCB-1IS-401. O Z NCW CNTMT DOWNSTREAM RETURN ISOL VLV, g NCA-IIS-402. 7 NCW CNTMT UPSTREAM RETURN ISOL VLV, NCB-IIS-403. k
EXCESS STEASI 1)ESIANI) 41 E P- 111004 Revision 00.04 PVNGS Appendix B Page 29 of 61 Total 234 5.0 Pl, ANT ST AllII,17, ATit)N (cont.) l 5.20 WilliN the CRS h::s directed, Ovenide and start one of the following: AND the NC water containment isolation valves are open, TIII!N ensure that at least I CEDM ACU is started. CEDM ACU FANS A/C,ilCA-IIS-49. Continue in this appendix. CEDM ACU FANS B/D,ilCB-IIS-50. T O
- D 5.21 IF the chill water containment isolation valves have been opened, Override and start 2 fans from the same train in the table below: -
TIIEN ensure that 2 containment ACU fans are running in the 2 same train. g
- 3 Train A Train B CNTMT NORMAL ACU FAN A.IICA-IIS-Il CNTMT NORMAL ACU FAN B,IICB-IIS-12 d O
CNTMT NORMAL ACU FAN C,IICA-IIS-13 CNYMT NORM AL ACU FAN D,IICB-IIS-14 Z O Z r-
_ s_. v-EXCESS STEASI I)ESI ANI) 41 E P-l it OO4 Revision 00.04 PVNGS Appendix B Pagc 30 0f 61 Total 234 5.0 l'LANT STAllli.17ATION (cont.) 5.22 If the CRS has direcicd, AND no chillers are operating after ventilation was restored, TilliN perfann allof the following:
- 1. Check that at least 1 plant cooling water pump is oncrating. T O
- 2. Check that at least I nuclear cooling water puinp is %
operating. {
- 3. Start a nonnal chiller. A. Start 2 of the following chillers by placing the con rol switch to STOP and then to START: 3 NORM CIILR B/ CIRC PMP B, WCN-IIS-2A.
NORM CilLR C/ CIRC PMP C, WCN-IIS-3A. d o NORM CIIW PMP & CIILR-E02 CONT, WCN-IIS-4A. Z NORM CIILR A/ CIRC PMP A, WCN-ilS-1 A O g r*
D Z10i:>4.O . Z O 7 r<- t r U n - - 4 n 3 i : s y , 2 nl E l ta mp p V . o luus L 3
- 4. 5 T o A 9 9 9 r e
1 cm ea V 0 V 0 V-0 V- d a 6 ht te N - e f s O N N N h o f oy I G G G e 1 ea r v- T S S S it 3 ni A , , , s e oil lo. L E E E s g x n O V V V o P a nu na S u S L L L c r B fdo r I R A A A t n r e d e E V V V e r ix et pce a D T T T r u d c E E E c n ol e I A e p t r s I E L L L e oeh c I N N N ht r it- I
~ A t I I I at f r s E R R R o l
L_ e pgn s I E E E o T- t s oil C r S C C C i n S y a U U U u G S .5 N : o. r O1 D D D r e i iw l R0 E E E h V xo CV R R R P ul to a be n e e e eN et . s s s 4 n e pS o l o l o h n t e al 0 t b OA lC C C nm n n 0 ca 0 e r f og ie i n Dh nl a o t I is i . v A B e . R 4 1 4 0 0 V - 0 N t S
- I E A
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E E I n b D D N o is n A A - c ia A ( m E E - a M l I I M N I l.t e i E E _ E ( < s I I I tc y T T D T cr e a S S x A i ri l S . S J M Z id x i O 5 1 O n e A 1, s u a a R0 R p E i l ht CV C p a l a e - e T l A Sh Rt sN oS s o is - S T Cre l l ht CA C S S ht e us i n S n e E T N N e u N n C E E it A. l n X I i I l o E l' W T C 3 2 5 0 . 5
EXCESS STEASi DEhl AND 4 i E P- 111004 Revision 00.04 PVNGS Appendix B Page 32 of 61 Total 234 5.0 l'i, ANT STAlill,IZATION (cont.) 5.24 E the CRS has direc'cd. A. Ensure that AUX STEAM TO GLAND SEAL RGLTR VLV, AND auxiliary steam is being supplied from the cross-tic header, GSN-ilS-14 is open. TIIEN shift gland seal from main steam to auxiliary steam. B. Ensure that M AIN STEAM TO GLAND SEAL RGLTR VLV, GSN-ilS-5 is closed. m O C. Check that steam pressure is 3 to 5 psig, on GLAND STEAMD SEAL SUPPLY PRESSURE, GSN-PI-3. - Z m 5.25 WilEN the CRS has directed, O TilEN align gland sca' to the main turbine. Continue in this appendix. O 5.26 E the CRS has directed, - Z TilEN CONCURRENTLMuiRFORM Emergency O Operations,41EP-lE001, Appendix E, Secondary 7 Equipment Shutdown Checklist, beginning with Step 1.1. p 5.27 PO rnay be perforrning Water inventory Record. 5.23 PO may he controlling pressurizerpressure. 5.29 PO is checking the containment pressure. 5.30 Check that all Section 5.0 steps have been addressed.
1Om _ZrODE> DOZ OZr<- i T 4 . 3 2 l a to T 1 _ 6 f o - 3 3 e g P a _ B x id n e p p A S G N v P a 0 0 0 n o is i v t e I 4 0 0 1 1 1 l' E 1 4 d. t e s c u y e r
) s I a N s r -
I A te e S n E T r a
) N r a
1 I p 1 O t l' n. S : lp A S E U f o T I N S - S t T iC S S e S T ht E N m C A, r o X l f n E l' i 1
- 6. _
0 _ 6 _
v EXCESS STEAM DEM ANI) 41 E P-l R OO4 Revision 00.04 PVNGS Appendix B Page 34 cf 61 Total 234 7.0 SYSTESI ENilANCESIENT 7.1 CRS is directing an operatar :o chec!r all locked in alarnts. 7.2 CRS may be directing an operator to restore of(site power. ri O 7.3 PO and CRS may be going to Step 7.12 in their procedurcs. 'D Z M 7.4 CRS inay be checking the RCI' seals. O 2 Steps 7.5 through 7.11 - PO rnay be starting the RCPs. S 7.5
~
d 7.12 l'O is checking pressurizer level. O Z O Z r-
.. m. v EXCESS STEAM DEMANI) 4 I E P- 1 It 004 Revision 00.0 t PVNGS Appendix B Page 35 of 61 Total 2.u 7.0 SYSTEAl ENil ANCEAIENT (cont.)
___..._____.__.._____________.....___________________-------------NOTE------------------------------------------------------------------------ Safety injection flow into the hot and cold legs will cause RCS Thand Tc to read lower temperatures than actually exist. 7.13 lij no RCI's are runnirg, Check that all of the fo!!owing conditions exist: m TilEN check that all of the following conditions for natural O circulation exist in at least 1 RCS loop with the intact steam RCS loop AT is less than 57 F [74 FJ. "O generator. Th P 2 "T1 O
- Tc T "I3 E
= RCS loop AT T >
-i Th and Tc are constant or decreasing.
3 RCS subcooling is acceptable. 2 See Nonnal Containment RCS Pfr Limits Illarsh O Containment RCS Pfr Limits], on the control board. Z r-The AT between RCS loop Th and REP CET temperature is4 less than 10'Fil5 FJ. RCS loop Th T
- REP CET temperature T
=AT T
w EXCESS STRAM I)EM ANI) 41 El'-1 It 004 Revision 00.01 PVNGS Appendix B Page 36 of 61 Total 234 7.0 SYSTEAl ENil ANCESIENT (cont.) 7.14 E no RCPs are running, AND natural circulation conditions do NOT exist, TIII!N inform the CRS. r1 7.15 If the CRS has directed, O TilliN CONCURRENTLY PERFORh1 the referenced appendix 33 for a verification that the equipment responded correctly for _any actuated safety signals. Z ri O N 7.16 Steps 7.16 through 7.18 - CRS ma} be checking the safety signal
' reset criteria.
5
--I.
7.19 jf the CRS has directed. O AND the safety signal reset criteria are met, 2 TilEN CONCURRENTLY PERFORh1 the referenet i appendix g for am actuated safety signals and restore equipment to standby. 7 r"" 7.20 CRS may be going to Step 7.24 of his procedure. 7.2 i Steps 7.21 through 7.23 - l'O may be controlling the containment hydrogen concentration. 7.24 Check that all Section 7.0 steps have been addressed.
7Om Z7Ox3>4- OZ 1 . 1 . OZr<- 4 3 2 l a to T 1 - 6 f o 7 3 e g a P B x id n e p p A S G N V P 4 0 R ( n o is i v ., e R 4 0 . 0 1 - 1 1 P E 1 4 d te s _ e u q er D s a N s r A 1 te e - G T m a r I N a D I p O t n l P r o a _ lp A S E U f o - T T S S A R T C S S c S T lt i E N n C A, n o X 1 f n . E l' I _ 1
- 8. .
0 S lt i{. t
_ s_- w EXCESS STEAM I)EM ANI) 4 I I? P-111004 Revision 00.04 PVNGS Appendix B Page 38 of 61 Total 234 9.0 Pl. ANT COOL,1)()WN 9.1 CRS may be dirccting an operator to unload and. shut d<nen the dieselgencrators. 9.2 Steps 9.2 and 9.3 - The CRS is determining the credited RCS m baron concentration and the target RCS baron concentrationfor O 3 the cooldown to 350"Fl338'FJ. _ Z T 9.4 PO rnay be horating the RCS to the required baron concentration. O m 5 9.5 WilEN_;my of the following conditions are met: > The credited RCS boron concentration is greater than the d target RCS boron concentration. O Z The STA has detennined that adequate boration will occur O during the cooldown. 7 r The required beration is complete. < Pressurizer level approaches 80% [74%] and letdown is isolated. TIIEN continue in this appendix.
EXCESS STEAM DEMANI) 41 E P- 1 RO O4 Revision 00.04 PVNGS Appendix B Page 39 of 61 Total 234 9.0 Pl ANT COOi,1)OWN (cont.)
................................................__.....__.........---NOTY.---------------------------------------------------------------------------
The maximum allowed RCS cooldown rate is 100'F/iir, in accordance with Tecli Spec 3.4.8.1. The maximum allowed pressurizer couldown rate is 200'F/hr, in accordance with Tecli Spec 3.4.8.2.
*n 9.6 Reconi the RCS and pressurizer cooldown rates. CONCURRENTLY PERFORM RCS and Pressurizer Cooldown O Log, Attaclunent 11-3 to this appendix. 33 Z
~"
9.7 IE the MSIVs on the intact steam generator can NOT be opened, g TilEN GO TO Step 9.12 in this appendix. 7
- :g
.-4 O-
- Z
~ O
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" - - OZ OZr4.
4 . 3 r 2 2 o 4 l a ta 2-r to e S T n I I Se . - 1 S gS 2 . . N - 6 f AmS pas r o 0 3 5 4-T o YteM t a 4 - S M 0 r 8 S , . 4 Bs e t e n 0 I I I I S e Vch e V - N V g at - N L a I t f Sno G E G G V P M hele i m G S S B a S , , N et v h rl e e S S R x t V V i t ot S L D d ef f L n e s oE0 V V T p lcV2 :s A p e v N N E A t oL1 Aeh 1 l a R R S rVt r o v D D E o g R S t aNm r o t a r 8 4 n M M O G eor e 0 i T T F pI f n V- w S S E N oTs e lo N B V yA ve G E l o N r G M V P aLl m S f e M S il Oa i v a e ht R R 4 0 xS e uI s S t T T B ale h f o S S R 0 nAt ll P N J t 0 U D T n t aUs a o cNse e s is i eAc r c lo v e iDMA C R 4 0 0t t I c
- 1 t a
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,gt o s si nl it e Va o la v IS osV o l a
D M gI t i s v N ) nS la in heiM u a A t n w n d r t oe a M o c nl el h m e E ( pf otd s in D o en s l N oh u t t o a p y m~ a W e ~ M O S foa R r b t s A D. Cho rue t Vr o I n E t i e s Sa a I h b s Men r _ T O t n er e e m e S O ynp ht b fo e h g S C t e S d rh eet r
- em s s T t c peozt oae o E N e rN ia r lCts l
C C A iE d l a e X L l un qe . E P fiT I eg 1 2 8 9 0 9
~ .. -
EXCESS STEAM DEAIAND 4 i EP-1 ROO4 Revision 00.04 PVNGS Appendix B Page di of 61 Total 231 9.0 l'LANT COOL,DOWN (cont.) 9.9 IF directed by the CRS to open the MSIVs, TilEN pufenn both of the following to equalize the pressure around the MSIVs on the intact steam generator:
- 1. Override and open the MSIV bypass valve on the intact steam generator.
Open the MSIV BYPASS ISOL VLV solenoids in the tabl below, on the intact steam generator:
'.O 7
Z Steam Generator 1 Steam Generator 2 m O SG A-UY-169A SGB-UY-183B 33 3 SGB-UY-169B SG A-UY-183A y
.1 O
- 2. Equalize the pressure across the MSIVs. Direct an auxiliary operator to throttle open the MSIV BYPASS 2 MANUAL ISOLATION VALVE that was closed in Step 9.8 O alvve.
Z r""
g 4 TO3-O 7 E>d O Z O Z r<- - 3 N N: 2 E E l P P a O t o e O T W W g ht o g 1 N O O - y m 6 E L L f
,P S S o rO o o 2 o t s
t s 4 e t aW e . . e . . g r eO h c A 8 h c A 8 a nL t 0 0 t O 0 P i 7 7 i S 8 eS g w 1 1 w I 1 B o s - - s - - x mt ag g S l S I g S I S I n n I r id en i l I
- i I
n t s i w A B w A B e p t co w o G G l o G G ll S S p al l o S lo S info t A f , , f , , e V V e V V ee h h ht I S I S ht S I I S = t S f f G t f is o o M M o M M N 1 ht I 1 1 1 2 2 t t V r o s a E E s a E E P tob le N N le N N a r n I I I I
==
en t a L L t a L L 4 0 n ef o e e 0 gr c c a a 0 np:e l l P n i s P io aN c V t t sl E I is S v fi M iT e m R 4 0 e 0 R 1 P E s
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4 ,I V sS 1,V M I rS1 toMr a o r et a eh r - nt e ed n gne D nug N r ar on ea r
)
A tn a tsde M u t n zes t E ( oie D deula h t N
~
st n t W s a e e M O ps ya o [ A D, b hd n E l ee r a T O r a us e S O s sd i S C Vrer I pe r S S T l e v o E N bht N - e C A, hD ! l X t N l 1XTi l 3 E l 1 1 0 m 9 0 9
.. m -
ICXCESS STEAM I)EMANI) 41 El'- 111004 Revision 00.04 PVNGS Appendix B Page 43 of 61 Total 234 9.0 l'l, ANT C()()l,1)()WN (cont.) 9.11 E the MSIVs are bypassed on steam generator 2, E steam generator 2 is the intact steam generator, AND the pressure has c(jualized around the MSIVs, TilEN perfomi tyth of the following to SLOW OPEN the TilEN ovenide and open the steam generator 2 MSIVs. MSIVs: Place at least I of the following switches to SLOW OPEN:1 O LINE I MSIV, SGA-IIS-171 A. T LINE 1 MSIV, SGB-IIS-171B. O Place at least 1 of the following switches to SLOW OPEN:7
- LINE 2 MSIV, SGA-IIS-181 A.
LINE 2 MSIV, SGB-IIS-181B. d O Z 9.12 E the CRS has directed, A. Press the LO P7R PRESS SETPOINT RESET for pil 4 O AND the pressure reduction is due to deliberate actions, channels on B05 to lower the automatic Pressurizer g TilEN maintain the automatic Pressurizer Pressure - Low Pressure - Low setpoint. g setpoint below pressurizer pressure. -<; B. Ensure that the pretrip alarm, LO PZR PRESS Cil PRE-TRIP, is clear.
~ . __.
EXCESS STEAM DIR,I ANI) 41 El'-iltOO4 Revision 00.04 PVNGS Appendix B Page 44 of 61 Total 234 9.0 PLANT C()()l,1)()WN (ennt.) 9.13 Steps 9.13 through 9.!3 - PO may be depressuri:ing the RCS. 9.19 Steps 4.19 through 9.25 - PC may be restoring scalinjection and
'TI seal hicedolT. O M ,
_ _ _ _.N ()T E-- _ -- --------------------_------ ----------------= Z 11 The maximum allowed RCS cocidown rate is 10(FF/hr, in accordance with Tech Spec 3.4.8.1. The maximum allowed pressurizer g cooldown rate is 200 F/hr, in accordance with Tech Spec 3.4.8.2. 3 ___..______________..__._________..._______________.__.__________________---N()TE-------------------------------------- E p
-i Step 9.26 provides the action that the operator should take if the cooldown rate is exceeded during the cooldown that follows Step 9.30.
__ _______ ____._______...______._______________________._____________ _._______________.... __--__. . _____..________________- - ___---- O Z 9.26 l_F the RCS cooldown rate exceeds 10(FF/hr, during the See Normal Containment RCS P/r Limits,[Ilarsh Containment O cooldown that follows Step 9.30, RCS P/r Limits) on the control board. 7 TIIEN reduce the cooldown rate to less than 100'F/hr, while g maintaining the RCS P/r limits. < 9.27 CRS is ensuring that the RCS is not oversubcooled.
- - , - +- e m-+ -. em-e- t _
EXCESS STEAM I)lGIANI) 41 E P-1 It 004 Revision oo.oa PvNGS Appendix 11 Page 45 of 61 Total 2M 9.0 Pl, ANT C()OI,1)OWN (cont.)
...............................__..................._......_.........NOTV---------...----------------------------------------------------------------
The maximum allowed RCS cooldown rate is 100T/hr, in accordance with Tech Spec 3.4.8.1. The maximum allowed pressurizer couldown rate is 200T/hr, in accctdance with Tech Spec 3.4.8.2. m
._...................._............._...._____...._._____..____.------NOTE----------------------------------------------------------------------------
If any RCPs are operating, use RCS Th to detennine the cooldown endpoint.lf no RCPs are operating, use REP CET to determine the y cooldown endpoint. m
......_____..... .................____.._....________ ___________________... ___...__.. ......._____ ..______ ._..________......_ . _ ___. ______..___.....----- O
- D 9.28 JE the CRS has directml, g AND the SBCS is available, y TIIEN use the SilCS to begin a controlled plant couldown to an y.
RCS Th of below 350T [338Tl. O-Continue in this procedure. 2 O Z r-
EXCESS STEAM DEM AND 41 E P-1 It 004 Revision 00.04 PVNGS Appendix B Page 46 of 61 Total 234 9.0 P1, ANT CODI.DOWN (cont.)
~ ------------------ ---- ---- ----- --------------- -------.-----------NOTV.----------------------------------------------------------------------------.
The maximum allowed RCS couldewn rate is 100'F/hr, in accordance with Tech Spec 3.4.8.1. The maximum allowed pressurizer couldown rate is 200 F/hr, in accordance with Tech Spec 3.4.8.2.
-----.------.--.----------.--------------------.------_....--------.---NOTE-----------------------------------------------------------------------------
]
If any RCI's arc operating, use RCS Thto detennine the cooldown endpoint.lf no RCPs are operating, use REP CET to detennine the - cooldown endpoint. g m O 9.29 JE the CRS has directed, Perfonn the actions in the table below to align at least 1 ADV frong AND the SBCS is NEl' available, the intact steam generator for operation: g TIIEN align at least 1 ADV from the intact steam generator for y operation. --l O r SG 1 LINE I ISOL SG 1 LINE 2 ISOL SG 2 LINE 1 ISOL SG 2 LINE 2 ISOL *- ACflON VLV. SG A-IIV-184 V LV. S_9 B-l lV- 178 VLV. SG B-IIV-185 V LV. SG A-I IV- 179 0 Z - A. Lower ADV VALVE CONTROL SGA-IllC-184 A SGB-IllC-178 A SGB-IllC-185A SGA-IllC-179A t outputs to minimum.
~
4 B. Select OPEN PERM on SGA-1IS-184A SGB-IIS-178A SGB-IIS-185A SGA-IIS-179A both ADV permissives. SGC-IIS-1848 SGD-IIS-178B SGD-IIS-185B SGC-IIS-179B
EXCESS STEASi DESI AND 4 i E l'- 111004 Revision 00.01 PVNGS Appendix 11 Page 47 of 61 Total 231 9.0 l'i, A NT C()()l,1)()WN tennt.)
. ... . .... . . . . .. .. _ .. .......__......_..N()TV---------------------.---------------------------------------------
The maximum allowed RCS couldown rate is 100'F/hr, in acconlance with Tech Spec 3.4.8.1. The maximum allowed pressurizer couldown rate is 200'F/hr. in accoidance with Tech Spec .1.4.8.2. m 9.30 A. Sct the demand for each selected ADV to at least 307c, with O IE the CRS has directe 1 TlIEN open the selected ADVs to cool down to an RCS Th of the thumbwhcci on the ADV VALVE CONTROL 33 below 350"F [338 Fl. Z II. Check that cach selected ADV is moving toward open. m C. WIIEN the position approaches 2070 open, O TilEN adjust the demand with the thumbwhcci to control thc 3 RCS cooldown. E 3> i 9.3 I CRS may he informing Radiation l'rotection arul the RMS O technician <{the steam release. Z O Steps 9.32 and U33 - l'O is controlling pressuriter Icrel and E 9.32 prCs%Ille. 4
I TOx GmOyE OZ OZr<-- L. . 2 l t a o T . 1 - 6 f o 8 4 e g a P B x id n e p p A . S G . N V P M U( O n o is i v e R 4 0 0 T s R I m 1 d S l .
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EXCESS STEASt I)Eh! ANI) 41 E P- 111004 llevision 00.04 PVNGS Appendix B Page 50 of 61 Total 234 ' i 1.0 l'lWCEI)llitE EXIT I 1.1 Sicps I1.1 thiottyh 11.4 - CRS is ensuring tirat all administrative requircincnts ate inct. T1 I 1.5 IE RCS and Pressurizer Cooldown 1.og, Attachinent 18-3 to this appendix, was used. O TilEN ensure that the data in the attachment is being transferred 3 into IICS anil Pressurizer lleatup and Cooldown Rates, 2 40ST-9RC01. m O 11.6 GO TO the procedure selected by the CRS. _.i. ENI) OF PROCEI)URE O Z O Z r-L- . _ . - _ ___m ___-__m__-____.-____n__ -- *-&m _ - - ws_s- w e. . - , ,_y .< W
EXCESS STEASI 1)ESI AND 41 E P- 111004 Revision 00.04 PVNGS Appendix B Page 51 of 61 Total 234 ACIIONS DETAILS ATTACIIMENT lt-I Steam Generator i Level Reduction Checklist Page 1 of 4
.._....._......._._...............________.._...___............._.._.... NOTE----------.------------------------.-----._--.-------.-------.-----._-.--
T This attachment uses 111G11 RATE blowdown to the main condenser for level reduction. O ___....______....__.....___...________..._______...._______________________________________________________...._________.___________._______.-_______...__________ x; B- 1.1 Override and open both of the following valves: Z "T1 SG 1 COMMON UPSTR ISOL VLV, SGA-IIS-500P. O 33 SG 1 COMMON DNSTR ISOL VLV, SGB-llS-500Q. E 3>
-l
~
__.______......_____...._____._________..-_.._...._____.......______..__.-NOTE----_----..----------------------------------------------------------------- O Z
. ......__.-_.. [S I.SSS)_5._S .)_)$[. . _$ ____Y $. $50___
_S_ __S._S?._S. _I S $ [_"). .. s S. $$_!S____S_[___ $__ ..$_S$$I[._ $ _E$.__ ______ O Z B-1.2 If steam generator blowdown can NOT be unisolated, TilEN perfonn both of the following: Ensure that both of the following valves are closed: k SG 1 COMMON UPSTR ISOL VLV, SG A-11S-500P Ensure the steam generator blowdown containment isolation valves are closed. SG 1 COMMON DNSTR ISOL VLV, SGB-IIS-500Q GO TO step 3.47
+ w T
EXCESS STEAN DEM AND 41 EP-1 ROO4 Revision 00.04 PVNGS Appendix B Page 52 of 61 Total 234 ACIIONS DETAILS ATTACIIMENT 11-I Steam Generator 1 1.evel Reduction Checklist (cont.) Page 2 of 4 B-1.3 Direct an auxiliary operator to ensure that both of the following valves are open, to send water to the condenser: m O SG 1 tilGli RATE 11 LOWDOWN TO CONDENSER, 2} SC-IIV-18C OUTLET, SCN-V088. Z
~~ SG 1 ABNORh1 AL l! LOWDOWN TO CONDENSER, T SC-Ilv-18R, OUTI.ET, SCN-V071. O 33 5
11-1.4 Select OFF with the SG 1 PATil' SELECTOR val.VES, 3> S CN-IIS- 1. -j o Z 11- 1.5 Ensure that at Icast I of the following valves art open: O SG 1 COLD LEG ISOL VLV, SGN-ilS-41. Z r-SG 1 IlOT LEG ISOL VLV, SGN-ilS-43. l-
m EXCESS STEAM DEM AND 41 EP-1 ROO4 Revision 00.04 PVNGS Appendix 13 Page 53 of 61 Total 234
&CI'lONS DETAILS ATTACilSIENT 11-1 Ste.im Generator i 1.crel Reduction Checkli:;t (cent.) Pagc 3 of 4 11-1.6 Select lilGil R ATE on SG 1 R ATE SEl.ECTOR VALVES, m SCN-ilS- 1 S. O 23 13-1.7 Select COND with the SG 1 PATil SELECTOR VALVES, Z SCN-llS-l. .m O
21 11-1.8 IF all of the following conditions are met: E Steam generater level is below 2% i 13%] WR. -j
. O Steam generator pressure is decreas.mg. g Te is approaching Th. O Z
TlIEN inionn the CRS that steam generator i is approaching { dryout cond,tions. i fl-1.9 IF the CRS has directed, TilEN stabilize Tc with steam generator 2.
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EXCESS STEAM DiGIANI) 41 E P.I ltO O4 Revision 00.04 PVNGS Appendix B Page 57 of 61 Total 234 ACl~lONS DETAILS ATTACllMENT 11-2 Steam Generator 21 evel Reduction Checklist (cont.) Page 3 of 4 11-2.6 Select iIIGII R ATE on SG 2 R ATil Stil.ECTOR VALVliS, m S CN -1 IS- 19. O m 11-2.7 Select COND with the SG 2 PATil SELECIOR VALVliS, Z SCN-1IS-2. T O m 112.8 IP all of the following conditions are met: E Steam generato: level is below 2% l13%] WR. d O Steam generator pressure is decreasing. Z Te is approach;ng Th. TIIEN infomi the CRS that steam generator 2 is approaching dryout conditions. k 13-2.9 1E the CRS '.as directed, TilEN stabilize Tc with steam generator 1. -u~ +-..a+ - - - - - -- v - m w - g ,e ,n , e~- ,,
mO3J ZmO3E)>jOz - OZG 4 3 2 l a . to T
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)
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EXCESS STEAM DEMANI) 41 EP-I R004 Rcvision 00.04 PVNGS Appendix B Page 59 of 61 Total 234 , ATTACllMENT 11-3 RCS and Pressurizer Cooidown log Page 1 of 3 Instructions RCS Cooldown Data Pressuriz.cr Cooldown Data
...___...__________________ NOTE------------------------------- Time RCS Cooldown Pressurir.er Cooldown Temperature Rate TEM PER ATURE Rate
~
The PMS demand typer may be used to obtain the RCS - RCA-TI-l 15 TE-101 1
+ , . . ,
and P7R temperatures at the required 15 minute intervals. 1 RCN-TI-101 ___RCB-TI- 125 n REPCET *
- 1. Use the colder of RCA-TI-l15 or RCB-TI-125 during Row w am 1 Nm 2 forced circulation. (a)
~' <
- @{F !"1 0
- 2. Use the REP CET temperature from QSPDS, page 211, (b) 3
- =
during natural circulation. (c) D,
- 3. Place a check mark next to the instrument selected,in the . 2 space provided. Use the same instrument for all readings. (d) O Z
- 4. The PMS points, RCTl15 and RCT125, may be used to (c) r) make a PMS operator log.
(f) k r -
- 5. Record the present time in the first blank box under -
C the time column in Row a. (g)
- 6. Record the RCS temperature for the present time in the (h) first blank box under the RCS Temperature column in Row a. (i)
(i)
...____..._________....__-----NOTE------------------------
(k) The instructions are continued on the next page. (1) _
- Do not exceed an RCS AT of 25"F. ** Do not exceed a PZR ATof 50*F.
EXCESS STEAN DEMAND 41 El'- 1 R O O4 Revision 00.04 PVNGS Appendix B Page 60 of 61 Total 234 ATTACl1 A1ENT 11-3 RCS anil Pressurizer Coohlown 1.og (cont.) Page 2 er 3 Inst ructioils RCS Cooldown Data Pressurizer Coohlmvn Data -
- 7. Record the PZR temperature for the present time in the Time RCS Cooldown Pressurizer Couldown Orst blank box under the Pr(ssurizer Temperature Temperature Rate TEM PER ATURE Rate column in Row a.
- ____ RCA-TI-l 15 TE-101 RCS AT* PZR AT**
- 8. W1IEN 15 ininutes has elapsed since Step 1 above, i.
_ __ RCB-TI-125 RCN-TI-101 ;n TlIEN repeat Steps 5 - 7 for Row b.
; __ REP CEI ,_
Row
^
- s o?
.; 8 8
(m)
...__.__........._____......-NOTE------------------------------ :
(n) in,. An RCS AT of >25 F or a PZR AT of >50"F for 4 consecutive 15 minute intervals will exceed the limits (o) y of Tech Specs 3.4.8.1 and 3.4.8.2. (P) 9 4
...______________________...-NOTE--------------------------
((l) O Be sure to preserve the sign of the number. A positive ;t number indicates cooldown and a negative number (r) r indicates heatup.
..._____. _____.. ..___________.___..___________...___...___ ___.. _ (s)
- 9. Subtract Row b from Row a for the RCS Temperature (t) column. Record the difference under the RCS AT column.
(u) __...._________.._____.._____. NOTE---------------------------- (v) The instructions are continued on the next page. __________________ _______ ._____.______________________________...__ (w) (x)
- Do not exceed an RCS AT of 25 F. ** Do not execed a PZR AT of 50'F.
EXCESS STEAM DEMAND 41 E P-1 It OO4 Revision 00.04 PVNGS Appendix 11 Page 61 of 61 Total 234 ATTACilMENT 11-3 RCS and Pressuriier Cooldown 1.og (cont.) Page 3 of 3 Instructions RCS Couldown Data Pressurizer Cooldown Datn ____________________._.____---NOTE---------------------_-------- Tinic It C S Cooldown Pressurizer Cooldown Temperature Rate TEM PER ATURE Rate He sure to preserve the sign of the number. A positive
~
RCA-TI-l 15 TE-101 T number indicates cooldown and a negative number ^.- 0- C
- RCB-TI- 125 RCN-TI-101 0
indicates heatup. Z REP CET s, . Row m- ' gm t m J' T
- 10. Subtract Row b from Row a inr the Pressurizer Temper dure column. Record the difference under the (y) M?
]%
g PZR AT column. (z) :.
.=
- 11. Continue to record the RCS and pressuri7er temperatures (aa) h3 at 15 minute intervals. For each set of temperatures. - J record the respective differences in the proper AT columns. (bb) O 4
___________________.________ NOTE------------------------------ (cc) o Z - An RCS AT of >25 F or a PZR AT of >50'F for 4 (dd) r consecutive 15 minute intervals will exceed the limits Tech Specs 3.4.8.1 and 3.4.8.2. (ee) (ff)
- 12. Infonn the CRS anytime that the RCS and pressurizer temperature 15 minute AT calculation exceeds the RCS (gg)
AT of >25 F or the pressurizer AT of >50*F. (hh) (ii) (ii)
- Do not exceed an RCS AT of 25 F. ** Do not exceed a PZR AT of 50 F.
)
EOO I k l E'"O F4 Il a A *T* f #% k t #% a 'a 1.s v w.s eain w a aI WBn 3 3 %F I W1iE I 41EP-1'I(UUL PVNGS Revision 00.04 ' EXCESS STEAM DEMAND i
~ Appendix C Page 1 of 12 Total 234 :;
Shift Supervisor Overview - h - l Section 1 . Entry Conditions Section 2 Emergency notifications and support , Section 3 Stabilize the plant as much as possible during the excess' steam demand event. MSIS actuation and verification. SIAS actuation and verification. HPSI, LPSI, & CS stop and throttle criteria.. .l RCP trip criteria. Swap charging pump suctions. . Letdown restoration. Faulted SG isolation. , LOOP actions
' Section 4 Safety function status checks.
Section 5 Stabilize the plant. I SG level control. Maintain pressurizer pressure. R
- Aux. steam to gland seal system.
Depressurize RCS. , Containment pressure control. . Section 6 Safety function status checks. . Section 7 Stabilize the plant. Restore offsite power if available. , t Restart of RCPs if possible. . Reset and verify safety signals that have actuated. Hydrogen control. Section 8 Safety function status checks. l Section 9 Plant cooldown. Transfers vital busses from DG(s) to offsite power if possible. , Open MSIVs on intact SG. . Plant cooldown. l Establish shutdown cooling Section 10 ! Safety function status checks. -l Section 11 Procedure Exit and Administrative Requirements 1
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CADIhfCAD Rf A TI A kt A kte u
~
EXCESS STEAM DE55 ND ~/I'E'IE itOdd" ' PVNGS Revision 00.04 Shift Supervisor Overview Appendix C Page 2 of 12 Total 29 4 Section 1 Steps 1.1 thru 1.3 Entry Conditions i Section 2 Emergency Steps 2.1 thru 2.4 Notifications l' Section 3 Event Control if Ensure MSIS Step 3.1 v 6 Align SGs for hot leg sampling Step 3.2
!f
*IF below 1837 psia ensure the following:
SIAS Actions SIAS, CIAS, only 2 RCPs running, Step 3.d adequate HPSI and LPSI flow I Is there a SIAS actuation?- GO TO 3.16 r NO to contmue event control YES [ Monitor for HPSI. LPSI stop and tho ole - S'"Es 3 h 'rr' ' 18 SG Dry-Out Controt Tc/RCS piemuie inacase v Continued on next page
\
FOR INFnQ IUI ATinM AMI V EXCESS STEAM DEMAND - ' 41EP-1ROO4 PVNGS Revision 00.04 s 1 Shift Supervisor Overview Appendix C Page 3 of 12 Total 234 - .f Section 3 continued from previous page j
;i u !
If SIAS, actuation energize
, 31,p 3,74 appropriate electncal panels . -t u _,
r Monitor for SG dryout, 1 Control RCS temperature and Steps 3.15 tluu 3.19 - pressure v : t RCP Tri RCP trip criteria Steps 3.20 and 3.21 Criten.a E , Swap CH , Swap CH pump suction Steps 3.22 tluu 3.26 j Pump Suction to RWT or SFP, or Pull to Lock v i Establish IA to containment Step 3.27 ; i i
" If ossible restore letdown Steps 3.28 and 3.29.-
k"es 0 ion P o l SG Isolation Determine faulted SG Step 3.30 j o v i { Isolate Faulted SG Step 3.31 -. . 1 Ensure correct SG isohueil' Step ,13: h Continued on next page l l
.u , _
E O Q lh.II" O D ER A T f A hl A
' ' ~
hti~V ' EXCESS STEAM D5MANN ' ' 4iNE iO0 PVNGS. Revision 00.04 Sitift Supervisor Overview Appendix C Page 4 of 12 Tota 1234 ) Section 3 continued from previous page Is correct GO TO,3.36 SG isolated? YES to contmue plant stabilization NO v Isolate the correct SG Steps 3.34 and 3.35 u CS Stop CS stop criteria Steps 3.36 thm 3.38 Criteria n If CS AS. stop all containment fans ,, Step a.09 h Startup channel checks Steps 3.40 and 3.41 v Place spray valves in manual Step 3.42 4 Ifleak not isolated, align affeeted SG blowdown to Step 3.14 - condenser I _ _, LOOP If there is also a Loor Ste 3 d6 Actions Concunently Perloim EU App. V i J f Continued on next page
FOR INFORMATION ONI Y EXCESS STEAM DEMAND 41EP-1ROO4 PVNGSi Revision 00.04
- Shift Supervisor Overview Appendix C Page 5 of 12 Tota 1234 1
Section 3 continued from previous page v l Steps 4.1 thru 4.6 ' af y Function Status Checks n : I l
- Section 5 Plant Stabilization f .
SG Control SG 1evel control Steps 5.2 thru 5.13) Stop mam feed pumps u H2Monitors Place H2 monitors in
, Steps 5.14 and 5.15 service I
RCP Bleedoff If CSAS, isolate bleedoff . Step 5.17.. q t 4 Maintain pressurizerlevel . Step 5.18 ~ T v Stop heater drain pumps , ' Step 5.19 -l { ! Steps 5.20 and_5.22 Es ablish containment cooling. i ! I .. *
'I b
Continued on next page ,
"OR !NFORM ^T!OPJ OPJ' Y EXCESS STEAM DEMAND - 41EP-1ROO4 PVNGS- Revision 00.04 Shift Supervisor Overview Appendix C Page 6 of 12 Total 234 )
Section 5 continued from previous page , t v Supply Aux Steam from main steam Gland Seal or Aux Steam Cross-tie, Steps 5.23 thru 5.25 Supply gland seal from aux. steam v Secondary Equipment Shutdown Step 5.26 Checklist k Water Inventory Record Step 5.27 h Maintain pressurizer pressure
, Step 5.28 within Pfr lunits v
Control containment pressure Step 5.29 v teps il thm 6.8 F nction Status Checks i Section 7 System Enhancement , 4 Restore Offsite If available restore offsite power Step 7.2 . Povrer Continued on next page
- = . .= . . , . . . _ . ,
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. . .. .... .. ....m. . . . . . . . ...
EXCESS STEAM DEMAND ~ 41EP-1ROO4. PVNGS Revision 00.04 'i Shift Supervisor Overview Appendix C - Page 7 of 12 Totd 234 , I' : Section 7 continued from previous page ! t
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l Are two RCPs running? GO TO 7.12 ; YES to continue
. plant stabilization NO ,
RCP Restart If ossible P RCP restart - Steps 7.4 thru 7.11 i A Natural Circulation Natural Circulation criteria Steps 7.13 and 7.14 6 v , ESF ESF actuation verification and Steps 7.15 thru 7.19 .i Actuation reset : 1
'i is .
CSAS actuated . GO TO 7.24 , NO to continue; , SFSCs YES f ; i
. Continued'on next page
. - .. ___. _ . _U
r FOR 'NFORM.^T!ON ON!.Y EXCESS STEAM DEMAND 41EP-IROO4 -PVNGS Revision 00.04 Shift Supervisor Overview Appendix C Page 8 of 12 Total 234 Section 7 continued from previous page e Hydrogen Step 7.21 Hydrogen recombiners Control v If > 3.5% hydrogen, . s,.a,,,, Step Hydrogen purge v IF not needed, secure Step 7.23 hydrogen purge and recombm.ers v Section 8 Steps 8.1 thru S.8 Safety Function Status Checks u Section 9 Plant Cooldown v Transfer Vital Tnuisfer vital buses from DGs to Busses to Offsite offsite power if possible 3 Pg-Power i Y RCS Boration Detemiin shutdown margin, Steps 9.2 thru 9.5 RCS boration if required v Continued on next page
CAD Ikf E AD ES A TI A kt A ktt' V ' EXCESS STEAM D55I$ii ~5i$iO/IiO'0T' 'PVNGS. Revision 00.04 - A Shift Supervisor Overview . Appendix C Page 9 of 12 Total 234 Section 9 continued from previous page . 1 i v .; v Can ! MSIVs on intact GO TO 9.12 t SG be opened? NO to continue plant cooldown
' 'ES :
e v If condenser cve.ilable, Steps 9.8 thru 9.11:' ' open MSIVs o -G Plant Cooldown using SBCS system Steps 9.12 thru 9.34 .: Cooldown or ADVs, Depressunze the RCS t 1r ; Depressurize and isolate' SITS . Steps 9.37 and 9.38' v , Void RCS void elimination . Step 9.39 Elimination lI Shutdown Check Shutdown Cooling Step 9.40-Cooling enny conditions e Sectinn lo ~ steps in ;f. ,30.8- ! Safciy Fonction Sinim:' lreic
]
I Section 11 Steps 11.1 thm 11.5 Procedure Exit ; I
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FOR !NFORMAT!ON ONLY EXCESS STEAM DEMAND 41EP-1ROO4 PVNGS Revision 00.04 Shift Supervisor Overview Appendix C Page 10 of 12 To'a! 234 . 1 1 ) l Safety Function Status Check Acceptance Criteria Reactivity Control: Check that the conditions from one of the columns below are met: All CEAs are insened Boration rate is greater Reactor power is less than 10~4 7c . than 40 gpm. Adequate shutdown margin is established. Reactor power is Reactor power is RCS boron concentration is greater than decreasing decreasing 2150 ppm. Reactor power is decreasing. Reactor power is constant. Maintenance of Vital Auxiliaries: Check that all of the following criteria are met: Main turbine is tripped. Generctor output breakers are open. , All of the buses in at least one train from the table below are energized. Train A Train B 4.16 kV BUS PBA-S03 PBB-SO4 120 Vac BUSES PNA-D25 PNB-D26 PNC-D27 PND-D28 125 Vdc BUSES PKA-M41 PKB-M42 PKC-M43 PKD-M44 RCS Pressure and Inventory Control: 1 Check that all of the following criteria are met for the existing pressurizer level condition: Pressurizer level between 10 and 707c [25 - 747c] RCS suhrooling is acceptable. See Nomial Containment RC3 r Limits, on the c..nt o,1 b .:o.1 II I:m h < ..m en,,,-m to "; l' T 1. nuie:
- control board i.
RVildS indicaten that the l'VI til level r picatei than 21'h Charging and letdown. as available. are restoring pressurizer imi. 1 1
r: p i r= A n s t e r-e n a m a =r e n a s n amn u
.l EXCESS STEAM DEN 1AWd ~"1$iCINO 4 W 'PVNGS- Revisica 00.04 Shift Supervisor Overview Appendix C Page 11 of 12. Total 234 l
[ .l Safety Function Status. Check Acceptance Criteria Ensure that HPSI meets pnq of the following: HPSI flow is acceptable. See HPSI Delivery Curve, on the control ~ board. ! HPSI throttle criteria have been met. Pressurizerlevel below 10% [25%] .) RVLMS indicates that the RVUH level is greater than 21%. , HPSI flow is acceptable. See HPSI Delivery Curve, on the control board. All available charging pumps are running. IIcat Removal:
, A. Calculate RCS operating loop AT. Th *F ,
-Tc *F ~
l I
= RCS operating loop AT *F {
B. Check that all of the criteria are met for the existing RCP condition listed -) in the table below: i At least 1 RCP runninc: No RCPs mnninr: RCS loop AT is less than 10*F [17'F]. RCS loop AT is less than 57*F [74*F]. ; RCS Tcis less than 570*F [558'F]. REP CET temperature is less than 600*F [608*F]. RCS Teis stable or decreasing. REP CET temperature is stable or ; decreasing. ; C. Check that the intact steam generator meets all of the criteria for the ecist-ing level condition listed in the table below SG WR Level 2 Steam Generators Available 1 Steam Generator Available ; Above 72% Enough flow to maintain the steam gen- Enough flow to maintain the steam gen, [78%]WR erator level between 72 and 80% [78- erator level between 72 and 80% [78 - 84%] WR 84%] WR Between 2 At least 250 gpm or U.le ID" 11'llu tre'l 6 lemt "" ht'm m 0.2h %hr feed-and 72% water flow watei flow -! [l3 78%]WR ' l
- Below Between 250 and 1500 gpm or between - Between 500 and 1500 gpm or between- 2 2%[13%]WR 0.14x106 lb/hr and 0.83x106 lb/hr 0.28x106 lb/hr and 0.83x106 ib/hr 4
C A D I Al t" A t3 RE A *rf A kl A kil V EXCESS STEAM DEMAND - 41EP-1ROO4 PVNGS Revision 00.04
. Shift Supervisor Overview Appendix C . Page 12 of 12 Total 234 -
.). !
Safety Function Status Check Acceptance Criteria Containment Integrity: Check that all of the following criteria are met: ; i At least one of the following pressure criteria is met: l r Containment pressure is less than 3.0 ps_ig. ; CIAS has actuated. j None of the following containment radiation monitors are in ALERT or , HIGH alann: l RU-l or alternate RU-16 RU-17 RU-148 RU-149 None of the following steam plant radiation monitors are in ALERT or l
' HIGH alarm:
RU-139 l RU-140 ,
/
RU-141 _QE of the following conditions is met: No ALERT or HIGH alarm on RU-4 or RU-5. I Chemistry samples indicate no increased steam generator tube.. leakage. Containment Mr..ospheric Control: Check that at least 1 of the following containment pressure criteria is met: Containment pressure is less than 8.5 psig. , At least I containment spray header is delivering at least 3525 gpm. q l
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FOR INFORMATION ONLY PROCEDURE ACTION COVER SHEET PROGDURE NO-. REV# DDC-PV Contact f or Decimal Revision No. 41EP-1ROO4 00.07 Ed$4#'$P"6' 3 Dh
. PROCLDUKE TIll E
) Excess Steam Demand DESCRIPDON OF ACDON:
TYPE OF CPS (page 11) PO (page 8) step 3.13 - Changed step to include opening both LPSI injection PROCEDURE ACDON Valves tor any running Ll'bll' ump. DECDdAL REVISION CPS (page 23) step 3.44 - Reworded the step so the condition relies on SG level. REVISION PO, page 13, step 3.23 - Added step to stop any operating BAMPs if charging pump suction is , tn ho thrnuch C'H m APPROVED PROCEDURE ACnON NEW PROCEDURE PREPAna ay. Ex1 STA: UNffS AHtCTED: LNTENT 01ANGE: CANCELLADON Rick Timmons 5861 7665 One R YES NO TEMPORARY APPROVAL SIGNATURES mer.r to s ction s.4) "" = "'P7 "Id" "*P"'an77 aPr=4 proceaure actson un the omgnedydup box immediasety upon complesion. (PRINT) MEMBER PIRIT SUPERVISORY frIAf7 (9.ep 3 (2.3) SIGNATURE DATE Total Number of Pages for the Temporarily Approved Procedure Actwa 3 (PRINT) ASSISTANTISHIFT SUPERVISOR (SRo)(Step 8 4 2 9, s]GNMURE DATE
- 1. A CATS DATABASE SEARCH IS REQUIRED FOR ALL PROCEDURE ACTIONS IN ACCORDANCE %TITI 90GB.OCQ01, COhBi!TMENT ACTION TRACKLNG SYSTEM - CATS. (CATS search is not required for clencat or admmistrative actions)
- 2. IF Tills IS AN IN1T.N7 QlANGE PROCEDURE ACDON,THEN PERFORM A 10CFR$0.59 SCREENLNG AhT) EVALUAT10N PER 93AC.ONS01.
k i Procedure Action Package Documents (Refer to Section 3.2.1.3)
- 1. NOPC (1), CATS search (15), V&V Requirements Checklist (1), Comment Forms (0), Procedure Pages 1, la,11, lla,23,23a, App A Page 8. Sa,13,13a.
\,
lotal Pages 'lurned Over to DDC (include PAC) (Technica1 Reviewer Only) 2, y Ou O(CHCL $ sj &' ha lS 5 PRINI TECHNICALREVIEWT.n [/ SIGNATURE
'DATE (hrer to Section 3.2.91 g/g PRINT Q A CONCURRE. 'CE (PR and AC only) SIGNA 2VRE DATE John Dennis PRLNT
/[ ,e,,7 LEAIi MANAG SIGNA 2VRE 4[f
/ 1) ATE (nerer to section 3.2.10 ;
f
.TOhn Dennis /[* f x ; 2_,,y d/,y (nerer to section 3.2.11) l PRINT liOCUMENT APPftOVER ElGNATURE / #
DATE [p -((-
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E!!,ctm Date,irrequ ted f 1 PV216-08NR (8 921 01AC-0AP02 l s
ENCLOSURE 3 t
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SAFETY ASSESSMENT OF THE OPERATION OF j UNITS 1 AND 3 WITH RESPECT TO THE UNIT 2 SGTR EVENT Table 2.1.6-2 Sequence of Events for a Main Stearn Line Break With 3 Induced Double Ended Guillotine Tube Failures Time (sec) iEvent 10 3 U-Tubes fail (double ended guillotine breaks) 20 SIAS, HPSI injection 27 Pressurizer empties 28 AFAS on SG#2 (locked out) 1810 Operator initiates auxiliary feedwater (one pump) to intact steam generator 1920 Operator throttles HPSI ~50% to reduce pressure - all throttle criteria met 2410 Operator begins a controlled cooldown plant with the intact SG and opens pres- - sunzer vent path. Steaming rate, venting and feed rate to the intact SG are peri-odically adjusted to maintain desired conditions. 4380 Shutdown cooling entry conditions reached 6430 Level recovered in faulted steam generator to 4.0 feet above tube sheet 18,850 Level recovered in faulted steam generator to above U-tubes, ft. 28,800 Transient Ended Seouence of Events and Systems Oneration At 0.0 seconds, a MSLB occurs on SG#2. 'Ihe reactor trip and MSIS occur appmximately 3 seconds later due to low SG pressure and the MSIVs close, isolating 3 of the 4 main steam lines. At 10 seconds,3 double ended guillotine tube ruptures are assumed to occur in SG#2. At ~20 seconds, a SIAS occurs. At ~28 seconds an AFAS occurs on the faulted generator, but auxiliary feedwater flow is locked out due to low pressure in the faulted generator. The faulted generator essentially boils dry at ~200 seconds, but the RCS continues to cool down due to boil off of the leakage. At ~1300 seconds, primary pressure rebounds to a maximum of 1156 psia, at which time HPSI flow essentially matches the leak rate and RCS makeup due to liquid contraction effects. Subcooling continues to increase due to the ongoing cooldown. At ~30 minutes, operators begin steaming and feeding the intact generator at a nominal rate of 650 gpm (only one auxiliary feedwater pump is assumed to be available). At 32 minutes, operators are assumed to throttle safety injection flow due to high pressurizer level and subcooling margin. At 40 minutes the operators open the pressurizer vent to aid depressurization (both auxiliary and main spray are assumed to be unavailable) and increase steaming from the intact generator to establish and maintain a controlled cooldown per the Technical Specification cooldown limits. At approximately 73 minutes, RCS temperature and pressure are within the shutdown cooling system entry conditions (350 F,400 psia). Nevenheless, for purposes of conservatively determining offsite dose, all cooling is assumed to continue via the steam generators for 8 hours. This analysis assumes that the shutdown cooling (SDC) system will be placed in service within 2 l hours of reaching entry conditions, and that the RCS will 1e at cold shutdown conditions 4 hours after the SDC is placed in service. Hence, this event would be over within 8 hours. 23 l
SAFETY ASSESSMENT OF THE OPERATION OF UNITS 1 AND 3 WITH RESPECT TO THE UNIT 2 SGTR EVENT
- 1 (i.e., no partitioning) for the flashed portion of the leak, and for bulk boiling when liquid levels are less than 4.0 feet above the tube sheet.
- 10 for bulk boiling when liquid levels are 4.0 feet above the tube sheet.
- 100 for bulk boiling when liquid levels are above the U-tubes.
4 3 0 3
- 6) The atmospheric dispersion factors are 3.1 x 10 sec/m and 5.1 x 10 sec/m for the Exclusion Area Boundary (EAB) and low Population Zone (LPZ), respectively.
- 7) Doses due to the initial activity present in the faulted generator are included in the SRP dose calculations, but are negligible for evaluating realistic dose consequences, or SRP dose consequences with reduced primary activities.
The above assumptions account for all the activity in the faulted generator due to the initial dryout, and do not credit any partitioning effects until a steam / liquid interface is reestablished. No credit is taken for plateout effects in the faulted generator. It should be noted, however, that ~50% of the iodine released from the RCS is assumed to plateout inside containment in LOCA events. Given the surface area inside the generators, a similar plateout effect would be expected for this event, which would significantly reduce dose consequences. The dose consequences for the MSLB with induced leakage equivalent to 3 DEG tube breaks are given in Table 2.1.6-4 Table 2.1.6-4 Summary of Off-Site Dose Conse*quences Incorporating CEPAC 'IYansient Results for a l Main Steam Line Break With Induced Leakage Equivalent to 3 DEG 'Ibbe Breaks
? Dose Consequencesj iGIS Cases,REMf iPIS Cases,' REM:
Applicable Limits,10CFR100 300 300 2 Hour EAB, SRP Assumptions 374 1360 2 Hour EAB, Realistic Assumptions" 23 28 2 Hour EAB, SRP Assumptions with realistic 225 272 initial activities (0.6 and 12 pCi/gm) 8 Hour LPZ, SRP Assumptions 119 253 8 Hour LPZ, Realistic Assumptions" 5 4 8 Hour 172,, SRP Assumptions with realistic 72 51 initial activities (0.6 and 12 Ci/gm)
- a. 0.6 and 12 pCi/gm for GIS and PIS initial activities. Realistic def and X/Q values.
The transient results noted above were also used to evaluate the control room 8 hour GIS and PIS doses by ratioing the dose consequences by the appropriate atmospheric dispersion factors and incorporating a protection factor of 95 for the control room essential air handling system. 26 i
SAFETY ASSESSMENT OF THE OPERATION OF UNITS 1 AND 3 WITH RESPECT TO THE UNIT 2 SGTR EVENT i Corresponding doses for a MSLB with 2 DEG tube failures were also determined. The resulting [ dose consequences are summarized on Table-2.1.6-5: Table 2.1.6-5 Summary of Control Room Dose Consequences Based On CEPAC Transient Results for a Main Steam Line Break With Induced Leakage Equivalent to 2 and 3 DEG 'Ibbe Breaks Dose Consequences GIS Cases, REM PIS Cases,~ REM l Applicable Limits,10CFR100 30 30 l Number of Tubes Assumed to Fail 2 3 2 3 l 8 Hour LPZ, SRP Assumptions 35 49 68 103 l 8 Hour LPZ, SRP Assumptions with realistic 21 29 14 21 l initial activities (0.6 and 12 pCi/gm) For comparison purposes, the PIS doses for the MSLB with 2 and 3 DEG tube mptures are depicted on Figure 2.1.5-1 (designated "s" and "j" on figure). 2.1.7 Dose Consequence Conclusions Based on the dose consequences described above, the offsite doses for a MSLB with induced tube leakage greater than the analyzed value of 1.0 gpm can be limited to within the specified acceptance criteria (10CFR100 limits for off-site doses and 30 REM thyroid for control room doses) by [ administratively restricting the PVNGS primary activity to the limits shown on Table 2.1.7-1. Table 2.1.7-1 Primary Activity Limits to Ensure Dose Consequences For a MSLB With Induced Tube Failures Remain Within 10CFR100 Limits
-Tech Spec 2 Administrative :
- Parameters . . ; g; Primary Activity, Steady State, Ci/gm 1.0 0.6 Primary Activity, Spiked, pCi/gm 60 12 These administrative limits justify continued operation of PVNGS Units I and 3 until the scheduled refueling outages.
In addition, the results presented herein demonstrate that pressurizer power operated relief valves are not required to ensure acceptable dose consequences. The HPSI flows assumed in the ana!ysis are PVNGS specific. Maximum safety injection rates were assumed in order to maximize leak rates, and hence dose. I i l l l l 27 l
L i i i i e P P f ENCLOSURE 5 . I e a
. 1 SAFETY ASSESSMENT OF THE OPERATION OF UNITS 1 AND 3 WITH RESPECTTO THE UNIT 2 SGTR EVENT Supplemental Information:
FOR MSLB+SGTR CASES-AVG. 2 AND 8 HOUR. LEA.K RATES ARE: l I Average GPM for-Intervals j 2 Hours 8 Hours i MSLB + 1 DEG TUBE 352 -- ci
;l MSLB + 2 DEG TUBES 635 393 i MSLB + 3 DEG TUBES 821 507 j
.i MSLB + 4 DEG TUBES 988 --
i 1 and 4 DEG tube transients were run for 2 hour intervals only. to l evaluate 2 hour doses. , s l t i i i i
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L 0 k i 1 5 6 3 i, 9 4 o ENCLOSURE 6 i b M 1 x f
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Steam Generator Resin Intrusion When resin was discovered on Unit 2 steam generators' (SG) can decks, an intensive data review was initiated to determine if there were any indications of when the intrusion (s) occurred. This review was conducted of all three units data and encompassed a time - frame from approximately January 1987 through May of this year. The review revealed no potential instances in Units 1 or 3. . However, the review did confirm resin intrusions in Unit 2 on two separate occasions. Both involved condensate demineralizers. The first was revealed by maintenance records that show that the underdrain seal for condensate demineralizer vessel "B" needed repair in July of 1991. The other involved condensate demineralizer vessel "E". Resin intrusion from this event was discovered 4 'anuary 1992 when sulfate was detected at levels greater the O ppb. The subsequent inspection at the time founc8 i failure of c, 4
.esin retention screen in vessel "E". Chapter V. A. 3 of the Unit 2 S'.eam Generator Tube Rupture Analysis Report ;
submitted to the NRC on July 18, 1993, describes condensate demineralizer retention element problems discovered during the current Unit 2 outage. ( As a consequence of these findings, all three units' SG hideout return data was reviewed for the years 1991 through 1993. Unit Two exhibited the highest average return of sulfate, averaging 84 grams (Unit One - 53 grams, Unit Three - 37 grams). Sulfate residual is consistent with resin intrusion as it is a by-product of cation resin decomposition. Numercus indications were available to implicate resin intrusion in these two events, some evident and recognized at the time (such as the vessel"E" retention screen failure and others revealed as an ' "after the fact" review (such as in the case of the vessel"B" retention screen failure). The 1992 vessel"E" failure was evident by the follouing indications: ,
- a. Elevated sulfate levels in Unit 2 SGs.
- b. Decreased sample flow and pressure from vessel"E".
- c. Sample line filters for vessel"E" plugged.
- d. Sample line filter for condensate demineralizer influent contained resin.
The 1991 vessel"B" failure wac evident, after the fact by the following indications:
- a. Less gallons throughput using this vessel.
- b. Higher effluent conductivity when this vessel was in service,
- c. Difficulty achieving acceptable conductivity when performing pre-service rinses (prior to placing vessel in service).
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- d. Resin beads were discovered on corrosion product sample filters installed at the time on the SG blowdown sample.
Based on these indications there have been no resin intrusions in Unit One or Three. It should be noted that at the time resin was discovered on corrosion product sample filters, Unit Two was the only unit with the capability as this was a pilot study performed at the unit to characterize and quantify the transport of corrosion products. Since then all units have had on-line corrosion product monitoring installed that continuously monitors SG blowdown, feedwater and condensate demineralizer influent and effluent. While it is not their designed intent, the monitors employ a filter that will reveal resin fines, as well as whole beads, thus providing greater monitoring capability in all units. , Additionally, resin traps are installed immediately downstream of the condensate demineralizer vessels and designed to catch any resin from a retention screen failure. These are equipped with differential pressure gauges that would reveal any catastrophic failure by remote alarm indication in the Control Room. It should be noted, however, that in neither of Unit Two's events was the intrusion apparently of great enough magnitude to initiate such an alarm. On July 19, 1993, suspected resin fines were discovered in Unit 3's corrosion product sample filters (CRDR #330317). Initial indications implicate a resin charge that may have contained more resin " fines" than normal. Regardless, resin fine intrusion is expected to some degree. EPRI document NP-4521, Resin and Ionics Leakaae from Condensate Polishers with and without Inert Resin. April 1986, estimates annual resin leakage range from 38 to 235 pounds. This leakage is primarily in the form of fines. While this is recognized by the industry, Palo Verde is currently developing a program to quantify resin intrusion and, where possible, mitigate it. 1 1 l l
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