ML20236T224
| ML20236T224 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/20/1987 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20236T206 | List: |
| References | |
| PROC-871120-01, NUDOCS 8712010085 | |
| Download: ML20236T224 (131) | |
Text
{{#Wiki_filter:A T T A C IL*iE N T 2 T O BECO LETTER 87-185 APPENDICES TO THE PILGRIM NUCLEAR POWER STATION PLANT-SPECIFIC TECHNICAL GUIDELINES 9 e i I FOR NFORMA"l0N proaggstsq;p 0!i.Y F
The enclosed appendices-document the process,followed in developing'the-Pilgrim Nuclear. Power Station (PNPS)' Plant-Specific Technical Guidelines (PSTGs) from the BWROG Generic Emergency Procedure Guidelines (EPGs) Rev. 4 version. APPENDIX A: MARKUP OF GENERIC EPGs The PNPS PSTGs are based on Draft Revision 4AF of the BWR'0wners'-Group Emergency Procedure Guidelines (EPGs). In developing the PSTGs, the generic EPGs were modified as required to correctly reflect the configuration, function, and operating characteristics of the structures, systems and components at Pilgrim. This appendix documents those modifications by illustrating tne changes made by providing a marked-up copy of the original generic-based BWROG EPGs. APPENDIX B: DIFFERENCES BETWEEN GENERIC EPGs AND PSTGs This appendix contains discussions of the technical byses for differences between the generic EPGs and the PNPS PSTGs where the basis is not evident or of significant change from the text of the respective statement. For example, no basis discussion is provided to address,a modification of the EPGs which simply inserts the Pilgrim-specific value of a trip setpoint or the name (or acronym) of a system. However, where major changes have taken place full explanation and basis is given. L
l APPENDIX A : MARKUP OF GENERIC EPGs 1 1 1 i
Acc,narm.W,_itc4crA..d - . . . _ _ . _ _ POWM_m.,_ S7;4770d , o un unnne unuur - 1 PL AA/~r .S~Pr.TC/ffC 725~M/V/M/-- ruro
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l kt q Prepared for the - < BWR OWNERS' GRO ' s Emergen ocedures Committee , 1 an Gener - ectric Company tions Engincedng,Inc. 5 Cunner Avenue 39650 . .rty Street, Suite 400 San Jose, CA 95125 Fremo 94538 l 1 x J 1 I I
l y9tV R $ P/p ci$c. Nc/in/Y btAkelrdc4 OEI h " dcrt .Sg*300 0 5 ::gency " cred"r= Wihlinc & LIST OF EFFECTIVE PAGES Nf fb*t Y Y hc.-khc4_ /h /W/ ccndrb W blg -h?fo V (Ense new Enen new Rase w] GL, y, Title 4AF PC-1 'E4M SC-1 T yi 4AF PC-2 4AE SC-2 .4AE 4 /I-l 4Z PC-3 4AE SC-3 4AD lil. [I-2 4AE PC-4 4AE SC-4 4AD g ,g 1
' I-3 I-4 4Af 6Z PC-5 PC-6 4A 4AE.
SC-5 SC-6 4AD 4W rt t-3 I-5 4AD PC-7 4AE SC-7 4AD' t - 4. ( )tI-6 4AD PC-8 4AE SC-8 4AD l-f I-7 4AC PC-9 4AE SC-9 4AD t-b l I-8 4Z PC-10 4AE RR-1 4AD Z -I 4AD j PC-ll 4AE Cl-1 4AE [~f (I-9 I-10 4Z PC-12 4AE Cl-2 4AE l y.g RC-1 RC-2 4M 4AE PC-13 PC-14 4AE 4AE Cl-3 Cl-4 4AE 4AP 4 l yg RC-3 4AD PC-15 4AE C2-1 4AE l y-y RC-4 4AD PC-16 4AE 2-2 4AE [ID'I l RC-5 4AD PC-17 4AE C3-l\ 4AF l 3-i RC-6 4AD PC-18 4AE C4-1) 4AE IO~
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l 3 RC-7 4AD PC-19 4AE C4-2 4AE 3-4 RC-8 4AE ' PC-20 4AE C4-3 4AF I~+
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T-7 @ RC-9 4AE PC-21 4AE C4-4 4A y-f RC-10 4AD PC-22 4AE C4-5 4 10-6 , 3 ') RC-ll 4AE PC-23 4AE C4-6 4E H-( 3.go RC- 12 4AE C4-7 _j AE li.c 3.l RC-13 4AE C4-8 4AE I t-I y-iz, RC-14 4AE 4.( C4-9 4AE h-4 RC-15 4AE 4,7 p.j C5-ll 4AE s t -s-RC-16 4AE g.g C5-2 4AD t i-(, RC-17 i 4AE 4 -1 C5-3 4AD 4 #r 3 ~8 C5-4 4AD IDI 4 -5 F-f C5-5 4AE ' E IN 4.g 6.T C5-6 4AD 4 ,,) f.f C5-7 4AE A-l C6-1 4AE A- Z. 4 -f I-7 C6-2 4AE A-3 4A f-8 C6-3 4AE A-t f~i C6-4 4AD 4-(o 4 -l( 6-l A-7
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) l A SECWW .4 kg wik hI ed on the various BWR system designs, the following generic d ksym omatic emergency-procedure guidelines have been devel : 1
! RPV Control Guideline o Primary Containment Control Guide e I 41 o condary Containment Control deline
{ o Ra activity Release Contro Guideline Tha RPV Control Guideli maintains a uate core cooling, shuts l h- down the reactor, and cool e conditions. own th V to cold shutdokn This guideline i en red whenever low RPV water 1 level, high RPV pressure, or hi
,R . whnnever a condition which r ire drywell pressure occurs, or reactor scram exists and hi g' reactor-power is above the RM down le trip or cannot be determined.
y' The Primary Contains t Control Guideline ma tains primary containment integr y and protects equipment i he primary s containment with espect to the consequences of a mechanistic ll 3vants except e consequences of hydrogen generatio na ll , Mark III con inment. This guideline is entered whene ll ' l suppressio pool temperature, drywell temperature, conta ent gg tempera re, drywell pressure, suppression pool water level, or prim containment hydrogen concentration is above its high I
-2 e o ating limit nr munoremmion nool water level is below its low
. parating limit.I Cupp;;;;i: pbel*,, rywell. - ' ---' '--^a=
- ll y determining bulk'suppreerice perl r:ter +== para ll rywel
&nr&/ =3 d ll
- q. atmosphere average temperatur g : 3 "=r6 -
. u .- s . . .......u-----~--
IIIO:::tri--- ^"4 /9w&ll , ---- aa...,.s yg,.a , ,,, g iIN U . K Wir y r N."JCJ'. x Y.F4 %',C f 1 C e Leer. "my Cuni.ain=nt s,unh ui uu16eline protects equipmen n\ N the e 46 secondaryndary containment, limits radioactivity inment, and either maintains steconreleasecontainment} Lntegrity or lim
- ontainment. This gu radioactivity release fr e is enter e secondary enever a secondary "
8 i :ontainment temperature, ra evel, or water level is above
.ts maximum normal operat value econdary containment differential pressu eaches zero.
A
"'ha Radio vity Release Control Guideline limits onctivity delea nto areas outside the primary and secondary )
goo ainments. This guideline is entered whenever offsite l
.s { radioactivity release rate is above that which requires an Aler .j di L M Revisio M g 1-#
- - _ _ _ . 1
Replacement paraq1gphs: Incert A Th:se Plant-Specific Technical Guidelines (PSTGs) have been dsveloped based on Draf t Revision 4AF of the generic BWR Owners' Group Emergency Procedure Guidelines and the design cf structures
~cnd systems at the Pilgrim Nuclear Power Station (PNPS). The PSTGs are comprised of the following:
o Operator Precautions (Section 2) o RPV Control Guideline (Section 3) o Primary Containment Control Guideline (Section 4) o Secondary Containment Control Guideline (section 5) o Radioactivity Release Control Guideline (Section 6) o Contingency #1 - Alternate Level Control (Section 7) o Contingency 42 - Emergency RPV Depressurization (Section 8) o Contingency #3 - Steam Cooling (Section 9) o Contingency f4 - RPV Flooding (Section 10) o Contingency #5 - Level / Power Control (Section 11) l o Contingency #6 - Primary Containment Flooding I (Section 12) Insert B L ' Brackets ( ) enclose plant-specific procedure references and step numbers which are determined coincident with the development of the plant-specific EOPs. Parenthesis ( ) enclose statements identifying the source of a plant-specific numerical value. Where multiple sources apply, that which corresponds to (and thus ultimately defines) the value shown is highlighted by boldface print. l l w_ - _ .
N
'OEI Document 8390-4 Emergency Procedure Guidelines e /M.R u/
et . P S r b s. \' Table als a list of the abbreviations used in the oge&deMeest._ Br [ ] enclose plant unique setpoints, design limits, pum ' rhutoff pr etc., and parentheses ( ) withi . indicate the source. acket . . Illustrated in these guidelines are var t; ri c 1 BWR/4 or BWR/6 as A appropriate. :W e basis for a brackete -v..i:5'= E curve I is not from the text, a description of its basis is wy - l mM in Annendix A. f l At various points throughout these ;"idelin operator .I precautions are noted by the symbol: pf7 g i ei The' number.wi hin
. . Se.c the M boxZ-refers to a numbered " Caution",, g jf contained i the Oper:ts; r;;;;.;ti :: :::tk d -These " Cautions" are brief and succinct red flags for. the. cperator. ll mergency procedure guidelines are generic to GE-BWR 1 throug signs in that they address all major systems may be used t 1 ond to an emergency except used to mitigate the conseg a of the gener hydrogen in a Mark.III containment. Be the systems in these e
ne cific plant includes all of. he guidelines are applied to -{l l individual pl deleting state s which are not applicable I-5 or.by su uting equivalent systems w appropriate. For exa , plants with no low pressure inject stem will delete' o ements referring to LPCI, and plants with_ Low saure Core [ looding will substitute LPCF for LPCI.. N l l' l I I/ I-2 Draft Revision 4AE
OEI Document 8390-4 Emergency Procedt a Guidelines
)
i fpHPs W" 1 At variousLpo Lnts within these gri'ali... , limits are~specified bayond which certain actions are' require ~c. While conservative,
.thase-limits'< re derived:from engineering analyses utilizing bast-estimate (as. opposed to licensing) models. Consequently, thase' limits re generally not as conservative as the limits ( , specified irg : ;12;t PTechnical Specifications. This is not to !
imply that operation.beyond the Technical Specifications is a recommended in any emergency. Rather, such operation is required _ I and is now permitted under certain degraded conditions in order 1 to. safely mitigate the consequences of those degraded conditions. The limits specified in the -guid:line@e_stablish the boundaries within 'which continued safe operation of the plant -can be v fSTGar assured. Therefore, conformance withot
-1M 'he= gnde44ee415oes not ensure strict conformance with "
Technicpl Specification or other licensing bases. PS-6s C I u c.ed ures c b e h e d F A At' other points within thesef,gu9-lhe ni defeating safety system l interlocks and initiation logic is specified. This is also i required-in order to safely mitigate the consequences of degraded I conditions, and it is generally specified only when conditions i exist for which the interlock or logic was not designed. 1 Bypassing other interlocks may also be required due to instrument i failure, etc., but these interlocks cannot be identified in ll cdvance and are therefore not specified in the4;uid:lin;;"- ll J ff66 3 The entry conditions for theae :::rgenci p::::d::: guid:line',are symptomatic of both'emergene s and events which may degrade into emergencies. The gede&4*eF specify actions appropriate for both. Therefore, entry into procedures developed from these/STGs
-" is not conclusive that an emergency has occurr Each procedure developed from these ? Or;; 07 p::::d::'% l
-;eid:lin:0 is entered whenever any of its entry conditions I occurs, irrespective of whether that procedure has already been I j ontered or'is presently being executed. The procedure is exited I and h one__the of theoperator returnsspecified exit. conditions to non-emergency in the procedure astisrIe9por>it is determined that an emergency no longer exists.
procedures is when lh l l citi. % For examtfle,^ the procedure developed f rom the RFV Control l Guideline specifies cooldown to cold shutdown conditions by i various methods and exit after the shutdown cooling interlocks I have cleared, but entry into this procedure does not require any l
.cooldown if it can be determined that an emergency no longer i j exists prior to establishing the conditions required to commence 1 3 the cooldown as specified in the procedure. After a procedure 1 (
f- developed from these guidelin
- as been entered, subsequent l J clearing of all entry condition for that procedure is not, by 1 itself, conclusive that an emer ncy no longer exists. I PSTGs I-3 Draft Revision 4AA
l OEI Document 8390-4 Emergency Procedure Guidelines I J PG T6.c Procedures developed from thesgs--a gency precedur guid: liner"- l cpecify symptomatic operator actions which will maintain the I rcactor plant in a safe condition and optimize plant response and I margin to safety irrespective of the initiating event. However, l ) for certain specific events (e.g., earthquake, tornado, blackout, l l or fire), emergency response and recovery can be further enhanced l by additional auxiliary event-specific operator actions which may I g . 1 b3 provided in supplemental event-specific procedures intended i for use in conjunction with the symptomatic procedures. As with ll cetions specified in any other procedure intended for use with ll the symptomatic procedures, these event-specific operator actions ll must not contradict or subvert the symptomatic operator actions l specified in the symptomatic procedures and must not result in l loss or unavailability of equipment the operation of which is I cpecified in these procedures. I i I-4 Draft Revision 4Z
, OEI. Document 8390-4 Emergency Procedure Guidelines TABLE -l cyPSTts EP& ABBREVIATIONS 3
Y 4 ADS. - Automatic Depressurization System
.t APRM - Average Power Range Monitor ARI -
Alternatfa.,RodInskrtion ll lh f. 3 ces Rp g,g,32 Control Rod Drive 5,, c, , , DilaffMS4.c "T'M
~
3T Emergency Core N oling System y ECC h - Q t Il
'- y HPCI - High Pressure Coolant Injection
,i .D1-us w
~. - _O_Y. _ I. .b%.P. . _e
, .. . .y.,_ . .., ,
3, gI 4VA8fl+[ Heating tilati,A$indAirCOnditie-i"f, o g i a. -
"- ~I~n cA
? 01- ~ = C:nd:===.1 4 IC G CO L 8I Limiting Condition for Operation L av el I n S
- c.* #*
- ll LPCI - Low Pressure Coolant Injection
,L.- R Lr s.v. ed. R e.c.o M,,_ e- .,,,
e% _ . n.... M - M n t on a yA - A o + Ay//Ak
/ 1~i NPSH - Net Positive Suction Head M d. -
M o r +W.r t gg o"lation No) ling NCI I ke$cto#r"Chfe Residual Heat Removal RHR - rm - Ravel W 'ess Per m** A
,RPS Reactor Protection System
]N . ) RPV - Reactor Pressure Vessel R5C5 ";J Swsucuve Control Syste.. ( - Q I Reactor Water Cleanup ,- 'RWCU - X {, RWM - Rod Worth Minimizer i SBGT - Standby Gas Treatment 4 g N I-5 Draft Revision 4AD i
\
i OEI Document 8390-4 Emergency Procedure Guidelines
.g.
TABLE T (continued) t PSTC-> ABE RtirVI ATI oN5 f B QLC Standby Liquid Control OEMO - Suppressive rovi rankeup 5 1 tc; % f E. - 6,etAnd SRV - Safety Relief Valve SW ~
$h Svice LO&
s.w - - Eh . T B c.0 A.) - , T J big 3M(d(N 0301ck CooliNI W TlP - C C Oi-8 t r unvec .a. I n u o, e. f%k A [W 1u.sd (wsd .hs4d f -{0.vo, k 1
~
'417/f A[ a '
~ -
BcAu [u. 4 K0 beff Oz A- b wc l-1
)
l l 1 I l 1 i l I-6 Draft Revision 4AD j l l l E__ -- -- .
f &w ff\:: N}/W-$ ec.::: :n .f r .-e. a .e N c.Arort
- errer: emen : - -
SEC ~7"7W 7 OPERATOR PRECAUTIONS This sectivu lictr " cautions" which are ao 51; ei. vue or.more' specific points withi R ne o '":1 ' --a . W ere a " Caution" is } appli , is identified with the symb l CAUTION 81 lJ% _ .4 - -i l-. An RPV water level-instrument may be used to determine RPV.I 1 J water level only when all the';following conditions are I l. l satisfied for.that instrument: '
'l i I .
I I , l 1. The temperatures near all the instrument runs are below.I: l' l I theRPVSaturationTemperaturg(p' g ij -I j
;i I I I I 547 + .
I l . I l -i L l Temperatu l . I i ! I' ( F) . .I i 1 near I i l l ' instrument . l l l - run i RPV ration l ll 4
- 1. l. Tempera e l - ll l -
1 I I I l- l l l 212 +----------------+------ l l l 0 1000 l i RPV Pressure (psic) l l i l l- . I I l 2.- For each of the instruments in the following table, the i i l instrument reads above the Minimum Indicated Level or the l l l l- temperatures near all the instrument reference leg l l vertical runs are below the Maximum Run Temperature. l
, t' Maximum Ru Minimum ' Al l I Temperature (gF) Indicat l .
l l Instrument aa fin.) DW Runs RB Runs in.) l . I I l l 1 l [ Fuel Zone -317~ 76 -305 ) l l q 1.1/yl %
%jl l g A gg- M -0. e Revision :
Replaceae'nt paracraphs:
'Incert C Instrument Maximum Run (Number) Temperature (OF) Indicated !
{Rance~(in.)} DW Runs RB Runs _, Level (in.) i. Fordwater Control A NA NA 0.0 (LI 640-29A) {0 to +60) F$tdwater Control B NA NA' O.0 (LI 640-29B) {0 to +60) Wide Range A NA 314 -263.5
.(LI 106A)
(LR 1001-650A) (-277.5 to +22.5) Wide Range B NA 324 -267.9 (LI .106B)
- (LR 1001-650B)
(-277.5 to +22.5)
)
l 1
OEI Document 8390-4 Emergency Procedure Guidelines RLrAA C 6"- O>t7-H l 3. - For each of'the following instruments, the nstrument l ll l reads above the Minimum Indicated Level assoc ated with l ll l the highest temperature near an instrument ference leg l ll 1 vertical runt I ll I I II
- a. Narrow Range (0 to 60 in.) M ] I ll ll
~
l [ Highest Drywell Run Minimum ] l [ Temperature (oF) Between Indicated 1. ll l [ Lgy gigh Level fin.) ] l ll 1 [ ] l ll l [ - 286 0 ) l ll l [ 86 350 ) l ll l [ 3 450 4 ] l ll l [. 450 550 26 ] l ll ll
- b. Wide Range (-150 to +60 in.)
! 1 41 '
l [ ] l 11 l [ ] I 11 l [ Bighest Drywell Minimum ] l ll l l [ Temperature (oF) w n Indicated ] l ll 1 I [ Lay High Level fin.) ] l l l [ ] I l l 1 - 128 -150 ] l ll 1 l [ 128 250 -140 ] l ll l [ 250 350 -131 ] l ll l [ 3 450 120 ] ! ll 4
/50 550 -
7 l l l [ ] 1 ll l [ c. S tdown Range (-17 to +383 in.) ] l ll 1 [ ] l ll l [ Highest Drywell Run Minimum ] l ll l [ Temperature (oF) Between Indicated 1 11 l [ LQM High Level (in.) l ll fl I l l [ 150 150 250 10 23
]
]
)
l I 1l ll ll [ 250 350 41 ] l l [ 350 450 65 ) l
! [ 450 550 on l l a
________________________________________________________-4 _ ______ m______________________--_ - - - - l CAUTION 82 /l
'l [ Heated reference leg . may not be used t(I l g 1 determine RPV vel during ra de pressurization l l
- __5 ________*.__________________________________________ ___'
I-8 Draft Revision 4Z
Replacement paraaraohs: 2
. Insert D
- a. Narrow Range A.{-50 to +50 in.)
l (LI 263-100A) 1 (LR 1001-604A) l . ) Highest Reactor Building Minimum Run Temperature (gF) Between Indicated Low Hich Level (in.) 186 -50 187- 200 -49.2 201 250 -45.5 251 300 -41.3 301 350 -36.4 l l 1 l b. . Narrow Range B (-50 to +50 in.) l (LI 263-100B) (LR 1001-604B) Highest Reactor Building Minimum Run' Temperature (gF) Between Indicated Low Hiah Level (in.) 181 -50 182 200 -48.8 201 250 -44.9 251 300 -40.4 301 350 -35.3 l
CEI Document 8390-4 Emergency Procedure Guidelines l
+ur bike, beleW Tl8' r p h 'in* % %
- 4- we W u.
spes&_ t w a (ac + a c k w a.. , s a f o r. _ A) l Operating HPCIA or RCIC turbines below l22L 4 rpm (minimum l l 1 turbine speed limit per turbine vendor manual) may result in l l l unstable system operation and equipment damage., I l l Elevated 3 : pp;;;:10. Ch:dr pressure may trip the RCIC l l turbine on high exhaust pressure. l l CAUTION 85 l l If PCS is taking suction from the suppression pool dI l.suppr ion pool temperature exceeds the HPCS Pump PSH I Limit,-t pump may be damaged and.become inoperable. I i l I {l' I I I l HPCS Pump NPSh Limi l l I I I I I I I I I 24 +. . . . . . . 10 psig* I I I I I I I . . . I l
! Suppression l. . . 5 psig l l z_3 l Pool 220 + l l l Temperature l . . . l l l (OF) 1. . . O psig l l l l l 1 I 200 + l l l l l l +____+ ___+____+_ _+___ l l l 0 2 4 6 l l l HPCS Pump Flow (X100 pm) l l l l
- Suppression amber overpressure l l l}
l .
' CAUTION 46 l l 0
l Cool own rates above [100 F/hr (RPV cooldown rate LCO)] ay.I l be required to accomplish this step. l w_ > T I-9 Draft Revision 4AD I l ______________ ____ a
1 l CEI Document 8390-4 Emergency Procedure Guidelines 1
.__..____.____ __..._______- - - _.g ._..___________.......___
l A rapid increase'in injection into the RPV may induce a large l
'l power excursion and result in substantial core damage. l )
___________ _______________.___...__.______ __...___ __________ q 1
)
l l I i 1 l j 1 1 l i I-10 Draft Revision 4Z .l l l l
fM/ .S P/d-S O
- O E I M : r :..t
- 2 0 0 ,p e c e Nc- &cAmk 6u!W Emetgeavy Fwmedc: Cuidelir.cc %
1 i
.SC= C 770d ~S RPV CONTROL GUIDELINE PURPOSE j The purpose of this guideline is to:
1 o Maintain adequate core cooling, - o Shut down the reactor, and 0 o CooldowntheRPVtocoldshutdownconditions(1100r,hPV water temperature 12 F (cold shutdown conditions) ).* ENTRY CONDITIONS The entry conditions for this guideline are any of the following:
*\ RPVu A o RPV water level below -{+1dg+in. (low3 1evel scram setpoint) o g/lo8f RPV pressure above -{l003 psig (high RPV pressure scram setpoint) P o Drywell pressure above hsig (high drywell pressure scram setpoint)$ 0 -
I o A condition which requires reactor scram, and reactor power
.above %
(APRM downscale trig) Q cannot be determined se+poid O_PERATOR ACTIONS RC-1 If reactor scram has not been initiated, initiate reactor scram. l Irrespective of the entry conditions, execute [ Steps RC/L, l l RC/P, and RC/Q) concurrently. l l 1 l
' EC b evision M 3-d i
{ _ _ _ - - _ - _ _ i
i
@EI Document 8390-4'- Emergency Procedure Guidelines j l
___{82j l l
#1 RC/L Monitor and control RPV water level. l l g
l RC/L-1 Initiate each of the following which should have l . initiated but did not: l ) o Isolation ) 1 o ECCS Emergency diesel generator l i If while executing the following step: I o Any control rod cannot be dete ined to be l l inserted to or beyond position )02 f (Maximum l l l Suberitical Banked Withdrawal Posit:.on)Q) and it l ll l has not been determined that the reactor will I ll ; I remain shutdown under all conditions without l ll ' I boron, enter [ procedure developed from l ll l Contingency #5). l l l l 1 o RPV water level cannot be determined, enter l l I [ procedure developed from Contingency #4]. l l f !
\
f k ( L % _ . ) RC-2 Draft Revision 4AE
OEI Document 8390-4 Emergency Procedure Guidelines
~
J
.F4q -r$ 2 ll.
[ l -If l containment whil: :::: tir., water -level 'and the f;'.; wing
;;ppresei;;
- t-$ e rimary l
. ..: 2 2 4l ll
,,L %
g[ . l pressure ~cannot be maintained b low the Maximum Primary
.l Containment ,W ater Level. Limitg then irrespective: of l l
.l l 3 - 2.
3 [s'/ M
- l whether adequate core cooling is assured terminate i lI
-l injection into the RPV'from sources external to the ll f[?
l l primary containment until primary containment water) and eupprec ien ch;;b f7 pressure .can be l Ii ll ( I level l maintained below the Maximum Primary Containment Water'l ll N Level Limit. l Il l l l Maximum Primary 1 -l ! l l Containment ll l l l Water Level Limit l ll l 1......... I ll l 1 . l ll 4 l Primary . I-- -H l Containment . I IL l Water Level . I l l I (feet) I . l l 1 I . I I I l l 1 1 I I . l l l l +_______________________ l l l l 1 ll Suppression Chamber Pressure (psig) l _____________________________________.___________________ l c low gev wn RC/L-2 Restore and m tain RPV water level between low level scram setpoint or shutdown ll
+J-f+4Pinp (V water lI igh level interlock, whichever cooling 3RP higher) Pand -{+1H$ in. level trip setpoint) ll withoneormoreg+fthe@(f_ollowingsystems:
M f o Condensate /feedwater e-*e.4*rs Fa.a.Aw M f i o CRD l C. o RCIC with suction from-theec^= d neate N stars;* I t:r'9_ defeating low RFV pressure ------ l isolation interlocks end -m-- h i Jn -M2-- I #If
.-u s m . E.
I ll3-3 eupp .ggien 73:1 _
-l
*r=aef:: legi& if necessary. I o HPCI with suction from theA+cn CST22:St.f ---a,- l 4ter:;; LenkS defeating high I fri lI >
eupp::aaien pe d pater level suction - *- l transfer logic if ecessary. l fo r+ 1 RC-3 Draft Revision 4AD I
-@EI Document 8390-4 Emergency Procedure Guidelines l'
o S; control and maintain pump flos 1 45 ll les han [the HPCS Vortex Limit]. - - l l , 4+ l l l HPCS Vortex . l ) Limit . l
'3 + . l l . I Suppression l . l 34 l Pool 2+ . l j Water Level . l {
(feet) l l 1+ l 1 I l l l 0 +----+----+----+----+---- I 0 2- 4 6 8 l-HPCS Pump Flow (X1000 gpm) l 1 l RC-4 Draft Revision 4AD l l
@EI Document 8390-4 Emergency Procedure Guidelines (Fgwuz. b o CS; control and maintain p mp flow le s l than the M CS Pump NPSH Limit /and e S l Vortex Limit*@ f p w- 4D. l r 0 l LPCS Pump NPSH Limit l 1 r l l.................. I 240 + . 10 ps
- l l.................. l l .5 sig i supp ssion -l l Poo 220 +.................. l Temperat e l . O psig l l
l
+__ __+___ _+_____+_____
/l i
0 2 4 6 LPCS P p Flow (X1000 gpm) l
- Suppression ambe overpressure 1 8 l l 1 1 I l i 6+ LPCS Vortex L it i i i
l 1 Suppres ion l l Po 4+ . . I Wate Level l. . . I eet) l l 2+ l i i i l i I ; O +-----+-----+-----+----- I l 0 2 4 6 l LPCS Pump Flow (X1000 gpm) l i I RC-5 Draft Revision 4AD
OEI Document 8390-4 Emergency Procedure Guidelines [t. m EA d o LPC ,with injection through the heat exc ngers as soon as possible; control and maintain pump flow less than the RHR Pump NPS lh t l Limit3and g e RHR Vortex Limi l "Ji" 7 ump r7F5if Limit l................ l l . I 240 + . 10 ps
- 1 l................ l l . I o Suppr sion l................ . psig l /
Pool 220 + . If Temperatur l 20 psig ( F) l /l l ! 200 + 1 1 I
+___+ __+_ +___+___+_.._ l 0 2 4 6 8 10 l RHR Pum low (X1000 gpm) l I
- Suppression c amber o rpressure 1 8 l l
l RHR Vortex Lim . l 6+ l l l . l Suppres on l . 1 Poo 4+ . I wate Level 1...... I eet) l l 2+ 1 1 I I I O +---+---+---+---+---+--- l 0 2 4 6 8 10 l RHR Pump Flow (X1000 gpm) If RPV water leve cahnot $e Eestored and/~ S b # l maintained abov (lowl~ level scram setpoint I or shutdown coolincu water level interlock, ll whichever is higher) , maintain RPV water level ll above F-15$ 1n. (top of active fuel) % l
- \ t.b . 3 L
RC-6 Draft Revision 4AD
i i I OEI Document 8390-4 Emergency Procedure Guidelines RPV water level control may be augmented by one or l 1 more of the follow ng systems: l o S5w c on +1e. .1. R R R, l [e nun _
- _ieg g;t;; ;;;;;;;; y _R ,,
l o C.t h LJ.:*% wes s +. 44 4. R 4 R. l [o Fire 'yet-= WA cossMel le RRR } S- l l'
!e Ta& arcana ^eti::: with ether unit: ) -E l l
b ECCS~ e keep-full cyct: d' -f g r - em rum . u i e a cro ssA:di k .s stc.
- lI 1 moes+ L '.6 w ea 6,.r.4 cM"W u A Tr @g j i
{e "" h02:n tank 1 Rl 4 o t .L(snsJr Tr&) mschtsk. 4e Ec e s 9 % 6 se. l l If RPV water level can be maint ined above
-/ t G. 5 g !-lS f in. (top of active fuel) and the ADS timer has initiated, prevent automatic RPV depressurization by reaetting the ADS timer.
1 If RPV water level cannot be maintained above l J l--l M in. (top of active fuel)$f enter [ procedure l ; gzt,.yl; i developed from contingency #1] . l l i RC/L-3 When precr' foi vvuldeWn t: : 1d hutdetn b l r <^ - Jane b s:: entered from [ Step RC/P-5], proceed l
/ .to cold shutdown in accorda'nce wit y{p:ccedure f:: R (
l na^1dern t^ : ld chutdern 00 fitians. s 1 t ( ! Pm c.e Lu 2 . s . s-} "w s.id s4 4 ; FO N cA RC-7 Draft Revision 4AD
+
OEI Document.8390-4 . Emergency Procedure Guidelines-RC/P Monitor and control RPV pressure. L . L l If while executing the following steps: l . l l-L lo A hish drywell' pressure ECCS initiation signal l l L l (Mtfpsig - . (drywell' pressure which initiat es l l l 'ECCS) )1 exists,. prevent' injection from those-bd5S l
~
l l and LPCI pumps not required to ; assure adequate l l l core cooling prior-to~depressurizing below their-l l l maximum injection pressures. l l l .. l lo Emergency'RPV Depressurization is anticipated and l l either l position 940?. (Maximum ---- l l. l l Withdrawal Position)$'Subcritical' l1llBanke determined that the reactor will remain or it has been ii l #6 i l l l shutdown under all conditions without boron, --- l- ll l rapidly-depressurize the RPV with the main turbine l (,passya}yes +4a, ,, L ,Jg g pg ,,gm ,4 l . c pa l lo Emergency RPE Depressurization is required and g l l less than M 4,(number of SRVs dedicated to- ADS)@ l l SRVs ~are open, enter [ procedure developed from l l Contingency #2]. l l . l , Io RPV water level cannot be determined and less than l l ! l -Fp24(number ofSRVsdedicatedtoADS)(PSRVs are-l l l f f, I ope #, enter [ procedure developed from l l. L l- Contingency #2]. , I l 1 l-lo RPV water level cannot be determined and at least l l l 44*((numbe r of SRVs dedicated to ADS)gA SRVs are l j l open, enter (procedure developed from l l Contingency 44). l l
~
RC/P-1 If any SRV is cycling,-initi;te IC :.~maY ly open SRVs until RPV pressure drops to 19 3-6 (RPV pressure at which all. turbine bypas alves . arefullyopen)@yE- 9to 1 I RC-8 Draft Revision 4AE 1
CBI Document 8390-4 Emergency Procedure Guidelines j
% lrre.s ach-We N 1 re. s ig RPV mlSevn v4 l If while executing the following st s:
I
. To eu.4 wA44 y ilf_._.
Io 3 Suppsc :10r pc.. temp rature cannot be 1 I maintained below the Heat Capacity l #6 II I l Temperature Limi -- 1 I l- below the Limit.
,fmain[tainRPV)
Pg47 pressure ! i i . I l 227 & i .
. Heat Capacity I /
n l l pression l i Temperat t
'/
l 1 l . l l Tempgra e . l l ( F) + . l l . I I I I I I I l l l l +_+______________ _____ l 1 l 0 75 1090 i RPV Pressure (paig) I h l o Merricr.p:f~waterlevelcannotbe ---- 1 l# lI f ]J I [ I maintained below the SRV Tail Pipe Level Limitj,3 maintain RPV presspre below the Limi t . A '$m' 5 -(*c+&*- % l
" 5 4*j APV webs MD 1
l l l . i 1 20.0 + . I l l SRV Tail Pipe ll l l Level Lim I ll l 8, ession l . l l Poo l l l Water l . I I Level . I I (ft l . I I I . I I I . I l 12.5 +------+------------ +- l 0 400 12 l
, l RPV Pressure (psig)
I i I I Io Steam Cooling is required, enter [ procedure l l l developed from Contingency #3]. I l J L RC-9 Draft Revision 4AE j I ______-_a
CEI' Document 8390 Emergency Procedure Guidelines i l If while executing the following steps: l I I 1 Io Bornn Injection is requirede and l I i lc The main condenser is available, and l l l lo There'has been no indication of gross fuel failure I l or steam line break, I l l open MSIVs, bypassing pn:;;;ti: Syster :no low p RPV l l l l' water level isolation interlocks if necessary, to re- 1 l37 1 establish the main condenser as a heat sink. I l i i i RC-10 Draft Revision 4AD
@EI Document 8390-4 Emergency Procedure Guidelines RC/P-2 Stabilize RPV pressure at a pressure below l gg,5k!10.;7 psig (high RPV pressure scram setpoint) with I the main turbine bypass valves.
RPV pressure control may be augmented by one or more of the following systems: g - o SRVs only when ::ppressi:n pee swater level is above {4 ft. P in (elev:ti:n *- top of SRV discharge device)g,.; open SRVs in the following l sequence if possibles -!M P c " "'"^"l
^S,% Bj A (SRV opening sequence) @ if the continuous l SRV pneumatic supply is or becomes unavailable, ;
place the control switch for each SRV in the l
--[C1,00E ;P AUTO 7 position. I
- c. s U I o HPCI with sucti n from the cendaneate- !#Ig,l I 4.F 4 W. .4. c a w eet** ll stcrig; tanko te . +,e s-< Fa, l.
te.n swe.+ (F ea ussy, __ __ l o RCIC with suction from the 14
- F--#
f( l 1
-s t c r a g e t;n'0._.,
, c 8"G -
ll
- a !ni-her stear drien ; uip . nth-o RWCU (recirculation mode), bypassing l
- [regener:tiv; heat each nger: :nd - l .
filter /demineralizers and, if necessary, I defeating fy,C and other isolation interlocks. l J 6 ' o Main steam line drains o RWCU (blowdown mode) if no boron has been injected into the RPV; refer to -[: rpling8 ~ l
-precedurer? prior to initiating blowdown.
4 Pro u.% s.7.s', Ye.% q c.>0I A Sq l:3,oeq,JAq j u e. c. 2 + a , , - . l l f \ RC-11 Draft Revision 4AE I
--_-_-_-____--w
1 !
.OEI Document 8390-4 Emergency Procedure Guidelines l
l If while executing the following steps the reactor is l l not shutdown, return to [ Step RC/P-2). l , ________________________________________________________. J RC/P-3 When eithers l o All contr pl rods are inserted to or beyond ll position p2 (Maximum l Withdrawa(. Position)$i~Suberitical or Banked l l o It has been determined that the reactor will ll l l remain shutdown under all conditions without ll boron, or
- ll ;
o fids (Cold Shutdown Boron Weight) f boron have been injected into the RPV, or o The reactor is shutdown and no boron has been injected into the RPV, i depressurige the RPV and maintain cooldow rate l belojw100 F/hr (RPV cooldown rate LCO) . l l If one or more SRVs are being used to depressurize l the RPV and the continuous SRV pneumatic supply is l or becomes unavailable, depressurize with sustained l SRV opening. l RC/P-4 When the shutdown cooling RPV pressure interlock l clears, initiate shutdown cooling $fsing only those i RHR pumps not required to maintain RPV water level J, 4-3 above-44df i . (nr? =te: 101 Pshutdowncooling)W**AtVN interlock y operation in the LPCI mode f wa 8PY \ If shutdown cooling cannot be established and l 3.g3 further3 oo down is required, continue to cool down using one or more of the systems used for depressurization. 1 i l 1 l I RC-12 Draft Revision 4AE ,
l I GEI Document 8390-4 Emergency Procedure Guidelines ' RC/P-5 When either: ll f o All control rods are inserted to or beyond ll position 9 02 (Maximum Suberitical Banked l-Withdrawal Position) f or l o It has been determined that the reactor will ll remain shutdown under all conditions without ll boron, or ll o [ou s (Cold Shutdown Boron Weight) f ll boron have been injected into the RPV, proceed to cold shutdown in accordance with
-! procedure f:: ce;10:un t ;;10 shutdewa -
eenditier.: } .CL l P r o c. e M z . t. s ') Conk flad.
$b ou>n hr-e- ho at eA. . '
l RC-13 Draft Revision 4AE
1 OEI Document 8390-4 Emergency Procedure Guidelines r P A= z.1.e, h6 L~ . " RC/Q Monitor and control reactor power. l If while executing the following steps: l l l lo All control rods are inserted to or beyo a posi: ion l 11 l g,J@02 (Maximum Subcritical Banked Withdrowal 'l l l Position) @ terminate boron injection and eLter l l l -!::r:r p:c:Od:::lC_ l a l l l-o It has been determined that the reacto will emain l ll
.1 shutdown under all conditions wi hout boron, l ll 1 terminate boron injection and enterA -!ecr~d _1 ll l preced' ara!D l ll l 1 lo The reactor is shutdown an o boron has been l l injected into the RPV, enter {rcr:r preced fn].GL l RC/Q-1 honfirmorplacethereactormodeswitchin SHUTDOWN.@JL If ARI has not initiated, initiate ARI. l fRC/Q-2 RC/Q-3 If the main turb MSIVs are openOf"ine-generator confirm or initiate is on-line (and the recirculation flow runback to minimum. I RC/Q-4 If [ct r wer is above $ (APRM downscale tri @forcannotbedetermined,tripthe rec rculation pumps.
; nC/O E Tf ART han not initinted. in4&4me. m _ ]S l Execute [ Steps RC/Q-6 and RC/Q-7] concurrently. l l
l i l
. 1 I
i RC-14 Draft Revision 4AE
CEI. Document 8390-4 Emergency Procedure Guidelines rfV'f RC/Q- [Defore -"ppr :;ien pe;
.Jors M Temperature re ,e s e l Boron Injection Initiation Temperature 4 ut only if l the reactor cannot be shut down, BORON INJECTION IS l REQUIRED; inject boron into the RPV with (LC and prevent automatic initiation of ADS. )
140 + l l l Boron l j 130 + Inject i l l...... In ion l { Suppression emperature l ) Pool 120 + . l l Temperature . l ( F) l l 110 + ... . . . . l' l l l l 100 +---+---+---+---+---+--- l 0 1 2 3 4 5 Reactor Power (%) l v's A RvJ C.R. If boron cannot be injected with p C, inject boron __ into the RPV 11a-enava --a -ya On: 4 r er e.;re of th l fo;110:i:;; L _ D [o CRD [ HPCS ] [o RWCU
/
] [ '
[o dwater ] [o HPC ] [ RCIC ] o Hydro pu ] 1 l l
.. \ '
.l s 1q l j ;c %. ,
!*^ k- RC-15 Draft Revision 4AE l
, 1
- d. . ! _ . _ _ . _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
OEI Document 8390-4 Emergency Procedure Guidelines rm il A 146.d v M ZI ( W.4- 58cc. + d w A ' I t e.v d. G - un + t.,4 s si. c _______________________ ___.r=c__mr_nA_____ i l If while executing the following steps SLC tank l l water l-level level . drops tojlet ' low GLC t:nt trip)!9 l manually trip the SLC pumps. confirm automatic trip
- ste Al of or l lh l
l l l ___________________7_______ l RC/Q .1 If boron is not being injected into the 3 RPV by RWCU and RWCU is not isolated, ll bypass -!::; ner:tiv; heat ;;;ch:ng::s "
% filter +ha./demineralizers.
RWCR Ih ll . 4 Continue to inject boron until-9808 -#88 9 F.2 RC/Q F pounds (Cold Shutdown Boron Weight)@^of boron have been injected into the RPV. RC/Q- 3 Enter-!seram p enn an ce3C, 6 A f r o e.e k . 2 , (. (oj I c M fcr A - l I
)
1 1 RC-16 Draft Revision 4AE
~
6EI Document 8390-4 Emergency Procedure Guidelines. RC/Q- Inserttcontrol rods as follows: l RC/Q .1 Reset ARI, defeating ARI logic trips if l necessary. l RC/Q- Insert control rods with one or more of l G the following methods: 1 I i o .De-energize scram solenoids l
- l L o Vent the' scram air header .l 1
o Reset the scram, defeating RPS logic l trips if necessary, drain the scram l discharge volume, and initiate.a l manual scram l . I I o Open individual scram test switches l I o Increase CRD cooling water .l differential pressure 1 o Drive control rods, defeating 2000 ;;.8- Q RWM interlocks if necessary l l o Vent control rod drive overpiston I volumes l RC-17 Draft Revision 4AE
p g p_g W J . _ Tpe e , G '7 Te c A m L A 6mlalk
^ : 0 ; r:st e3an-4 rmergency pr;;;3;r; nia,11,,,, " - -
i Sc=C 770W Y ! i PRIMARY CONTAINMENT CONTROL GUIDELINE j { i. PURPOSE l . The purpose of this guideline is to: o Maintain primary containment integrity, and l o Protect equipment in the primary containment. ; l ENTRY CONDITIONS The entry conditiohs for this guideline are an of the following: o [ enppreerior g pry = r peo temperature above-!?5 pai-%emperature LCO)% (most limiting o Drywelltemperatureabove-{135f[kr 11 temperature LCO r maximum normal operating temperature, whichever is higher) un t9py-4nmone e mnormenra ahnve 0ron e (;;ntainreen; t;;p; rat;. % ree):
- o Drywell pressure above ghs(g (high drywell pressure '
scram setpoint)@ "-
'o h fhpre: sic [ ool water level above-[12 ft. . (maximum
,,suppresci ool water level LCO)$ A-o h- N ppr:ssien pov water level below-!12 ft. n (minimum g-ruppraceinn p^ _ water level LCO)(Lc_
o Primary containment hydr I hydrogen 3 alarm setpoint) ken concentration above d e h gh, I L o n c % k ,- N con t-g OPERATOR ACTIONS l Irrespective of the entry condition, execute [ Steps SP/T, l l DW/T, @ PC/P., SP/L, and PC/H] concurrently. l l k i ! WY -Draf vision l 4-#
CBI Document.8390 Emergency Procedure Guidelines 80T SP/T Monitor and control - ppseesien pee. mperature below I l05 ?A most limitin h --- usingavailablesupprhpreeeim. yvvA emperature LCO l ion pool cooling. I When ;;ppseeeie.. p;;y f oc u w itic I
. te rature cannot be maintained ll below l05 .?,(most limitingneupp::::i:: p;;f-temperature l LCO)fI go*p l l
SP/T-1 erate all available suppression pool cooling l using only those RHR pumps not required to assure l. l adequate core cooling by continuous operation in I theLPCImodef l Before-: ppr:::i:n peedF temperature
/o r u w h rea hes- he I SP/T-2 l Boron Injection Initiation Temperatur , enter l
[ procedure developed from the RPV Con rol
-(Fi ga<O Guideline] at [ Step RC-1]'and execute it concurrently with this procedure. I 1.0 e l l l Boron l 13 0 + Inject l...... Ini ion l Suppression l . mperature l Pool 120 .. l Temperature l . l (OF) . I 10 + ........ l l l l 1 loo +___+___+ __+___+ __+-__ l 0 1 2 3 4 5 l Reactor Power (%)
i-l } l PC-2 Draft Revision 4AE
'OEI Document 8390-4 Emergency Procedure Guidelines l l
9 l
-$
- c 4 Wh SP/T-3 Whengeuppr:::ica p^^ . temperature and RPV pressure l cannot be maintained below the Beat Capacity l EMERGENCX RPV DEPRESSURIZATION Temperature IS REQUIRED. Limigg( Figorn r> l l .
l. 227 + . Heat Capacity l Temperature Suppre on Limit J2--- Pool l l
-q,-
i Temperature . ( F) 165 + . I I I
+-+--------------+-- ---
0 75 1090 RPV Pressure (psig) 1 iY l 1 l j i PC-3 Draft Revision 4AE
'CEI Document 8390-4 Emergency Procedure Guidelines DW/T Monitor and control drywell temperature below-{1 0 -5 f'j st'F l (drywell temperature LCO or maximum normal operating I temperature, whichever is higher)$ using available drywell I cooling. l l
l ---- ll l Ist'{Whendrywelltemperaturecannotbemaintainedbelow 0 r:35 . (drywell temperature LCO or maximum n rmal l #1 l l operating temperature, whichever is higher) : ---- I l DW/T-1 Operate all available drywell coolinqg defeating'- l l 4.g ir:1stien inter 10:h: if nc::::;ryC_. ll l l l If while executing the following steps drywell sprays l l l have initiated and drywell pressure drops below l l_G JJ"been (high drywell pressure scram setpoint)dT,* ll psig l l terminate drywell sprays. l l l
&% *jes\*P DW/T-2 Before drywell temper u e reaches-!240 .A(maximum _
temperature at whic ADS hualified or drywell hic ever is lower)Opbut only design if-!::pprc temperature,$
- icn p;; water level is below il? f tf_. l fg3;giin. (01:v;tica ;f bottom of internal euppreeried'- l
*"*d#charb:? to drywell vacuum breakers less vac_yum breaker opening pressure in feet of water) Vand$
l i drywell temperature and pressur are within tHE's 13 Drywell Spray Initiation Limit %utdown @t recirculation pumps and drywel cooling fans and$ a- y (P) 1 initiatedrywellsprays$$usingonlythoseRHRpumps i not required to assure adequate core cooling by l continuous operation in the LPCI mode $f l 597 + . I l . Drywell Spray i l Initiation l . . Lim l Drywell . l Temperature 338 + .............. ( F) l l l I I i 100 ++--+-----+---------+-- ; I 3 11 29 60 l Drywell Pressure (psig) j l PC-4 Draft Revision 4AE
l OEI Document 8390-4 Emergency Procedure Guidelines l t.1i'P DW/T-3 When dr ell temperature cannot be maintained below l I l200FA(maximumtemperatureatwhichADSfhualified 4., l or dryf @well designRPV temperature, whicheverISis ) lower) EMERGENCY DEPRESSURIZATION l REQUIRED; enter [ procedure developed from the RPV Control Guideline) at [ Step RC-1] and execute it concurrently with this procedure. 11 . i i 1 l l l l PC-5 Draft Revision 4AE
CEI' Document 8390-4' ' Emergency ~ Procedure Guidelines CN/ Monitor and control containment temperature below [900F ntainment temperature LCO)], using available containmen I coo g. l I When con inment temperature cannot be maintained ---- ll below [900 (containment temperature LCO)] ' l 41 l l CN/T-1 Operate 11 available containment cool g. I l l If while executing e following step suppression pool I l l sprays have been in lated and ppression. chamber i 1 I pressure drops below [ 0 psig ( gh drywell pressure l l l scram setpoint)], termina sup ession pool sprays. l -l l CN/T-2 Before containment mper ure reaches [185 F ED, ' (containment desi tempera re)], but only if suppression cha er pressure above [2.0 psig I (Mark III Con inment Spray Ini ation Pressure Limit)], in late suppression poo sprays using l l only thos R pumps not required t assure l l adequat core cooling by continuous o ration in I the LP mode. I CN/T-3 Wh containment temperature cannot be main ained l low [1850 F~(containment design temperature , EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; en r [ procedure developed from the RPV Control i Guideline) at [ Step RC-1] and execute it concurrently with this procedure. l ll i N l 1 I J l . I l Mark III containment only PC-6 Draft Revision 4AE
l l j 1 i i OEI Document 8390-4 Emergency Procedure Guidelines 1 1
.PC/P Monitor and control primary containment pressure l r #3M psig (high drywell pressure scram setpoint) @below sing the I felleeing ry t:::" 4 (:N. b +w M Af % spheric. t.e,A/ th.
v Containment pressure control systems; use
!cnn ainment pressure control syst _a ing i procedure . I o and drywell purge]; use [SBGT an I drywell purge operating procedures 1. ,/
When primary containment pressure cannot be maintainedf ll below -tBvf3 psig (high drywell pressure scram setpoint)S: l t.s-l l If while executing the following stepsfsuppYessionf I l ) l sprays have been initiated andA suppression ehrrbes l l l pressure drops below -fBrG*psig (high drywell pressure I i l scram setpoint)$f terminate suppression pee (3 sprays. I i ____________________________ _(______________g
, m . ___ l J s- !
PC/P-1 Before nz<ww pp :::icn cheE?eed' pressure reachesar4thdE-l presonre e upproreinn nr.ennr.3 [17 ' prig u.ogs Suppression Chamber Spray Initiation Pressure)$7C- . d (but only if-!euppreeslen charb : ie Ob:J:-<-- I 2.0 p;ig p- y::::::iati;R,"E Init ~j,4~4 Precrure Limit}P--!:upprecci:n p(MarkIIICenttinrentOpkfwaterlevelis\.p.c 0 , I yggy elows-24 ft. 5 in?-( 1 ;;tica ;S suppression A s,f ! sp nozzles)it-initiate suppression spra o assure I padequatecoreusing only those RHR pumps not required oling by continuous operation in I the LPCI mode . I i 1 1 1 l I 1 i PC-7 Draft Revision 4AE
CEI Document.8390-4 Emergency Procedure Guidelines ' l l If while executing the following steps drywell sprays l I drops below l
.lhave$Ppsigbeen liiNt (high initiated drywelland drywell pressure scram setpoint)$7ll pressure l l terminate drywell sprays. l l
' l or+ sta PC/P-2 Whena+ruppre;;ien ch::b:P pr s u r e e x c e e d s ,II . o g r.ig l
'17.4 psit (Suppression Ch .ber Spray Initiation Pressure)fbut only IL.
if '3'$*n.reerien O '*Y level is below --{l7 rp (el;;;ti p^dfwaterO O % bottom l of internal supprc;;ien ch;;.befato drywell vacuum i breakers less v,qcuum breaker opening pressure in I g feet of water) f and fdrywell temperature and l [p,bcgto)~pressurearewithintheDrywellSprayInitiation Limiy, Oshut down# recirculation pumps and drywell I l cooling fans and@ initiate drywell sprays @using l i only those RHR pumps not required to assure i adequate cor oling by continuous operation in i the LPCI mod . l 597 + . l l l . Drywell Spray l Initiation l . . Li l ) Drywel l . I l Temperature + .............. ( F) l.
~ I l !
I l 100 ++--+-----+----- ---+--- I 3 11 29 0 l Drywell Pressure (ps ) ;
~~~ __ N l l
l l l PC-8 Draft Revision 4AE
CEI Document.8390-4 Emergency' Procedure Guidelines When n4 PC/P-3 _a. %ppree.ivu v;.embe$ pressure cannot be [Fi8"'#th I maintained below the Pressure Suppression Pressurg, l EMERGENCY RPV DEPRESSURIZATION IS REQUIRED s l l l Pressure Suppressio l Pressure Suppress l Chamber + . - l Pressure . l (psig) + . .......... 1 . l . l . I . o +--+-----+----+---- --- 0 Primary Containment Wate Level (ft.) ; l l 1 l l PC-9 Draft Revision 4AE
CEI Document 8390-4 Emergency Procedure Guidelines M b r~w BeforeAcuppr:seien ch::b; y > PC/P-4 . pressure aches $the l Primary Containment Pressure Limi then l irrespectiveoftheoffsiteradioadbivityrelease l Og rate, vent the primary containment, defeating isolation interlocks if n cessary, to reduce and l I maintainjpress e below t e Primary Containment l Pressure Limi as follows: l I I I l l Primary Containme Pressure L M l [
+..... l Suppress l . l Chamber ............... I Pressure 1 i
(psig) l l ! l l i I l l l l l 0 +----+---+------------- l
- Primary Containment W&ter l l l Level (ft.)
^
l 44 c 4 l o If supp::: icn per Pwater level is below l 3l0y -!25 ft. "' in . (cl:vetivu c' Lid- bottom of thep% supprerrien ch::b;0 vent) , vent thef* % l suppreerien ch::b;;" in accordance with I g pree:dur fer pric.:. , cz,nttiaman* "entin;;) C I 4o c L. o If pupp::::ica p :T-water level is at or above l y/0 l20 ft.-3.in. (elev:tien O' th6' bottom of the-+ert4-
^
ruppra==4a" ch::be Q vent) or if the34er
-ruppreerien ch: Ribe't_,canno be vented, vent the l a l drywell in accordance with (precedure f:F- I g prit :y 00ntain= nt 7:nting h l r e c C. 8- - C
\]
A9 ' LLJot. L%em c Dh { Lok , PC-10 Draft Revision 4AE l __ ---
l
)
OEI Document 8390 Emergency Procedure Guidelines 1 i ___. - i [ -5 Whensuppressionchamberpressureexceeds[e ] M ) [ rimary Containment Pressure Limit], then l [ i spective of the offsite radioactivity re se ] l [ rate whether adequate core cooling is sured,] l l [ vent the imary containment, defeat isolation ] l l [ interlocks necessary, to reduc and maintain' ] l ' l [ pressure below he Primary C ainment Pressure ] l l [ Limit) as follows: ) l l [ ] I [ o If suppression oo ter level is below ] l [ [26 ft. 9i (elevati of the bottom of ] l [ the supp ssion chamber v )], vent the ] l 4, j i [ suppr sion chamber in accor ce with ] l J l [ [p edure for primary containm venting). ] l [ ] I 1 [ o If suppression pool water level is at r ] l l [ above [26 ft. 9 in. (elevation of the b om ] l [ of the suppression chamber vent)] or if th ] l l [ suppression chamber cannot be vented, vent l ! [ the drywell in accordance with [ procedure , I for primary containment venting]. ] ~ 4ee w \ PC/P- When/; ppression chambe.ypressure cannot be l mainta ned below $t.he Primary Containment Pressure l (( g) LimiA , then irrespective of whether adequate core coolang is assured: J kors i l j 1
\
6 o U 30Ig .,If u.: ppr::cien S water level is below l l . in. p::(cicvetien et suppression g I spray nozzles),Qnitiate suppression Pee 7-[ Add.f sprays. o 4?
- res s i ca p;;.Vwater level is below i)Ifp ;upp?in.
u, ft. (010 :ti n c. bottom of internalMl 3
- pprecrien ch::be" to drywell vacuum breakers i less vacuug bre ker opening pressure in feet i of water)QTan rywell temperature and l ,
pressure are withinythe Drywell Spray '
/ /0 -
Initiation Limij, fshut down recire lation I pumps and drywell cooling fans an initiate (h{. drywell sprays. ! , ! I ! i PC-ll Draft Revision 4AE l _ -. _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ __
1 I OBI Document 8390-4 Emergency Procedure Guidelines SP/L. Monitor and controlgurysession yvvi-water level. hcA l l If while executing the following steps Primary l l' l Containment . Flooding is required, enter [ procedure l l l developed from Contingency #6). l l SP/L-lnglaintain cupprerri^a water level g tween 12 (maximum uppreeri:.. pee awater lev LCO) and [f'. Pl12 in. ft 41n. (minimum rupprecrien p;;.jl4 l water level LCO)h merefer to {ee...pling precedureN l i prior to
=e.::p w5:discharging
- : ;: :: t e wate e sp e O
- r. ,!:upp::;eie..
e] c__. pe?1 l gss . , S has been initiated, maintain su press 1 pool wat between [23 n..(SPMS initiation setpo n u pression pool wa er PMS operation O. level incre ch results. 11 in. (minimum suppreso ter
~
l 9- IL7 l Ifa:;ppres; ion peel water leve cannot be maintained above-{12 fL. ( m i n i m u m s u p p r a = = 4 ^ = S--- g 7-p;;P water level LCO) $xecute e$ n. [ Step SP/L-2]. TV If . ppreerien peel > water _le_ve_ Y r 89 y cannot be j (maximum suppreeric. #--- j
' c"d i
)maintainedbelow[12ft.'41n.pe:PwaterlevelLCO)f:!??f
!niti; tic: 00tpcint p 9in-
- pp;;eeien p;;1*;2ter l
-1:;;l 1,m..;;; which :::;1'4 f;;; ""E ep::: tion:)g _
- 'if S".".S h;e been inii.imed, , execute [ Step SP/L-3] . j 1
\ l
~
PC-12 Draft Revision 4AE
1
@EI Document 8390-4 Emergency Procedure Guidelines 1 1
l l T C (L d S Iz.7 SP/L-2 AGUFFTCOGIO:; TOOI WATER LEVEL BELOW-[12 fL. D in. (minimum e"pprerrica p :"gwater level LCO) % ! 4* rw '
--- -------------------------- --_ -- y
, 1 Execui.c l S t a n =__ SP .. and SP/L-2.2] l l -
)
[-l concurrenti l ]' l j 1
------ ----..------------------------ ----- , 1) 4c M
/ '/L-2.1 SP Maintain supprc: i n p $ water leve' . l above the Heat Capacity Level Limig.7 Fi p i g {
l Heat Chpacit
)
12'2" + j
- l. Level L j
. l .
Suppr ion i . j , l Pool l . Water B "+ ....... Level (ft.) l { l l l l {
+------------ --+------
/_\T HC I }
Where /_\.T Heat Capacity Temperature { ; Limit minN =uppression s pool temperature ' If zuppr:: ler. 704AYatN level cannot be g(5 maintained above the Heat Capacity Level Limi , EMERGENCY RPV DEPRESSURIZATION IS b REQU RED; enter [ procedure developed from the RPV Control Guideline] at [ Step RC-1] and execute it concurrently with this procedure. 4e r*4-- SP/L-2.2 Maintain zuppre::i n p:Ch water level I i above 10 ft. ,, in. (-51 l of the HPCI ex aust) h :tien of t E top l If zupprrrrien(3' d Nterb~L - level cannot be i l maintainedaboyh!Sft. fin. ( c l e : t i e r. - l l f thf top of the HPCI exhaust) 7 secure l j HPCI irrespective of whether adequate l core cooling is assured. l
. PC-13 Draft Revision 4AE
_--_____-____-__A
l i i 1 OEI Document 8390-4 Emergency Procedure Guidelines , i 1 94ewa SP/L-3 -SUFFRESSIO; 70v91 y 0 2. K SATER LEVEL ABOVE i tEO i
-[12 f t.
(maximum cuppre len prob ater level LCO)% 4-G i (I23 fh- 9 in- (CDuc initi&Livu senpuini pine ~'# - - i ruppr:::icn peel
- eater leu =1 in"raaaa which rann1&= 4L__,
f rer SFA5 vpet. Lien)] if CPMc b=? b: n iniLI.Lud)
-_____-------_-_-__-_....._-_____..._______.. ... i l Execute [ Steps SP/L-3.1, SP/L-3.2, and l l l SP/L-3.3) concurrently. l 1 1
1 1 I 1 ( 1 l 1 I l I 1 I I l l i I l 1 1 i 1 PC-14 Draft Revision 4AE I l
s OEI Document 8390-4 Emergency Procedure Guidelines SP/L-3.1 Maintain JS cvA
$suppre::icn p;;.lYwater level below the SRV Tail Pipe Level Limig. (F '-~* [l}
l . l . 20.0 + . SRV Pipe Suppres n l l l . evel Limit Mll Pool Wate . el l . (ft.) l . l . I
,,- 12.5 +------+------------- -
0 400 120 (_ RPV Pressure (psig) > b4f 8 If,eup> pre::ica p;;f' water level cannot be [334 ust 9)\/ maintained below the SRV Tail Pipe Level ll 6 LimiQ, enter [ procedure developed from I the RPV Control Guideline] at [ Step RC-1] l and execute it concurrently with this l procedure. (Fcb-~t G)I If3:wppr;;;ien poc.ywater leve and RPV ; 1 pressure cannot be maintained below the SRV Tail Pipe Level Limit, ut only if ll adequate core cooling is assured, terminate injection into the RPV from sources external to the primary , containment except from boron injection j systems and CRD. 44 r ua If :uppraerica 3 pee.Juwater level and RPV pressure cannot be restored and maintained below the SRV Tail Pipe Level ll Limih, EMERGENCY RPV DEPRESSURIZATION IS REQU D. l Oy) i l
)
i l PC-15 Draft Eevision 4AE l
- - - - - - - - - l
l 1 CEI Document 8390-4. Emergency Procedure Guidelines l l Je i SP/L-3.2 pp --ic: p::f" water level Maintaina::ruA- l Igg ~ below il7 ft. Rhin. (elev tion -f' bottom l of internal ::pprc :ic; ~ c5--he_hg 4, % l drywell vacuum breakers less vacuum l breaker o l water) % pening pressure in feet of 1 A,. IS 3 l Ifacupprerrien p::d water leve cannot be l maintained below-ll? ft. ff n. (elevetien' l o#" bottom of internal rupprerrien c5--':fL l d 466gtodrywellvacuumbreakerslessvacuum l breaker pening pressure in feet of I water) : l I o Terminate drywell sprays. l l o If adequate core cooling is assured, l terminate injection into the RPV l from sources external to the primary l containment except from boron l injection systems and CRD. l SP/L-3. 3 Maintain primary containment water level l below the Maximum Primary C(ntainment l WaterLevelLimig.(F*{644 53 l
\~
l Maximum Primary l Containment l l Water Level Limit l ,f___ l......... l/
. I Primary l l Containment l . I Water Level l . , l (feet) . l I I l . l l . I
+_______________________
- Styptwooisu Chembs. Es ::: : (pcid L l l If primary containment water level cannot l be maintained below the Maximum Primary s Containment Water Level Limigi terminate injection into the RPV from sources 14
'W E) external to the primary containment l l' irrespective of whether adequate core l cooling is assured. l PC-16 Draft Revision 4AE
OBI Document 8390-4 Emergency Procedure Guidelines pr % a.cg to % 4n1 % s M PC/H Monitor and controlphydrogen and oxygen concentrations. l l _________________________________________________________ l-1 If while executing the following steps: l l 1 l l lo The hydrogen or oxygen monitoring system is or l l becomes sample the- drywell and l
'l l
! 3 supp::eeis. unavailable,for
- h- '.. hydrogen and oxygere dee l
- ':200 rith !:srpling prec=dere' c l lh l
Drywell or Suppr ::ien 0h:.250 #" hydrogen
. concentration cannot be determined to be below 6% l l l a drywell- orTeury.e.. ion dan "-- oxygen l l concentration cannot be determined to be below 5%, I l-EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter I l.
g [ procedure- developed from the RPV Control l l l Guideline) at [ Step RC-1] and execute it l l l concurrently with this procedurer recur = in'L I l p:::::t Op:::. Lip vi hd : ;en =iving syntama aatl l 4~9 l rece-M er: :.. .u w irrespective of the offsite l l l radioactivity release rate, vent and purge the l l l containment in accordance with [ Steps l l l (primary PC/H-1 1' through a .4] until drywell and l l l g ruppr=== inn a"-"e QhycIrogen concentrations can be l' l l determined to be below 6% or drywell and l l l a= pp::::ic; ch :brdoxygen concentrations can be l l l determined to be below 5%. l l _________________________________________________________ l l 1,::t I/II enn+-m i nmenta . nn1[PC-17 Draft Revision 4AE
i
' OEI Doculment 8390-4 Emergency Procedure Guidelines :
" . I
". l
/ .OY y
N 4e r +4-3 g. PC/H-1 When drywell oracuppreerien 7..;;be[ hydrogen . l )
% concentration reaches [0. % (minimum detectable l )
hydrogen concentration)$t but only if the offsite ll j
, radioactivity release rate is expected to remain l
) d below the offsite release rate LCO, vent and purge ll the primary containment, defeating isolation
. pre drywell andA
~
inte_rlocks if necessary, to res pp::;sion ch:;5;Jore and maintain hydrogen l l l j l l concentrations-below-l0.%p(minimumdetectable hydrogen concentration)d) as ollows: 1 1 n( $ E t .o V. l <T .___________________________________ ,.___________ l If while executing the following steps the l l l s i
%? l offsite radioactivity release rate reaches the l ll \
5
% l offsite release rate LCO, isolate the primary l ll ) *A l I containment vent and purge. l l Qq g. _________________________________________________ i i
PC/B-1.1 3 fer te (re pling p :::fure]Ps l L 4er g /4o c + l . i
, PC/H-1.2 If 4;ppr:;;i;n p;;$ waterflevel is below l, { i A '
25 ft.-$1n. (eleveti- of th" bottom of I\ 1k - pg (he t cu <} 1% N( l \ ,p g arg{pree:ppierrica ch::b;dvent)$f vent upp ;eicu cha;t:0 in accordance with
- L e f;; pri-ary m a h=en"L.,
^ l it
'f,
,kk
- ti29 1 ./orud I lg Ne a e ,
q If g%upp ee.c..j c;;, ater level ef at th?or I,' q t w(div:tien Ik
'k t T/O-bottom above-!25 ft. a in.
of the cuppreerien che Le y vent)] l , i d Ard or if tneAcuppre::icn chidmcannot be !
' l s
vented, vent the drywell in accordance l g ; with [precedur; f;r prin:ry containaeu O
., l ventir;]f_. 4T lt
, 4,. a Io PC/H-1.3 If the suppreccion Ohn' ;Qor drywell can at 4 be vented:
l N.f D % o If drywell oxygen concentration is ( I 6 below 5%, initiate and maximize the i drywell nitrogen purge flow. I Lk o If drywell oxygen concentration is not below 5%, initiate and maximize I l ,h 1 the drywell air purge flow. I l I1ey _Z ___________________________________________________
.] Execute [ Steps PC/H-2 and PC/H-3] concurrently.
I lh l h !/II cent:in;;nt; On1 [ PC-18 Draft Revision 4AE
CEI Document 8390-4 ' Emergency Procedure GuiCelines
.s H-2 Monitor and contro; nyarogen and oxygen i concentrations in the drywell. ll H-2.1 When drywell hydrogen concentration reaches [1% (minimum hydrogen lk l
t concentration for recombiner ration ot f 1 inimum detectable hydrogen I c centration, whichever higher)] but l on1 if drywell hydroge concentration is l below 6% (maximum hyd gen concentration l q for tec .biner opera on or 6%, whichever l l is lower) or dryw 1 oxygen I concentrate .is elow [5% (maximum i oxygen concen tion for recombiner I operation or % whichever is lower)], l place hydr en re ombiners in service ! I h taking s tion dir tly on the drywell l and ope te the dryw 1 hydrogen mixing I syste I l < PC/H-2.2 Wh drywell hydrogen con entration l' < aches [6% (maximum hydro n I concentration for recombiner peration or l 6%, whichever is lower)] and ywell- 1 oxygen concentration reaches [5 (maximum l oxygen concentration for recombi r I operrtion or 5%, whichever is low )], I secure any hydrogen recombiner taki I suction on the drywell. l
. I PC/H-2.3 Continue in this procedure at [ Step -
l PC/H-4]. l
)
t f 1 : 4ed I/II centaine;nt; =l % PC-19 Draft Revision 4AE
@EI Document 8390-4 Emergency Procedure Guidelines P -3 Monitor and control hydroger, and oxygen concentrations in the suppr$ssion chamber. l I
B-3.1 When suppression chamber hydrogen 1.{ concentration reaches [1% (minimum I
. hydrogen concentra?. ion for recombin 1 operation or minimum detectable by rogen I concentration, whichever is high )] but ly if suppression chamber h rd i gen I c centration is below'[6% (ma imum j hyd gen concentration for r ombiner I opera on or.6%, whichever lower)] or- I suppre ion chamber oxygen concentration- l is below 5% (maximum oxy en l concentra on for recom ner operation or 1 5%, whichev r is lower , place hydrogen l I recombiners servic taking suction i directly on th sup ession chamber. l l l l
If no. hydrogen re mbiner can be placed I ction directly cut the in service takin4 suppression ch ber- ut only if the If I drywell hydro n conc tration'is below l 4.g f6% (maximu ydrogen c ncentration for l
. recombiner peration or %, whichever is I lower)) o drywell oxygen concentration I is below [5% (maximum oxyge l
.concent ation for recombiner operation or 1 5t, w chever is lower)], pla e hydrogen l-reco iners in service taking etion l
. ind ectly on the suppression c mber by I wa of the drywell. l l
PC/M-3.2 hen suppression chamber hydrogen I concentration reaches [6% (maximum I hydrogen concentration for recombine I operation or 6%, whichever is Icwer)) and I suppression chamber oxygen concentrate n l reaches [5% (maximum oxygen concentrat n I for recombiner operation or 5%, whichev r I is lower)], secure all hydrogen i L recombiners taking suction directly on l I the suppression chamber. l L__ , l
' Mark I/!! ;;r.tein=="&= nni, PC-20 Draft Revision 4AE
3 i CBI Document'8390-4 Emergency Procedure-Guidelines I When drywell orAsapp 4*t w ;;;i;; che...Le.yhyd PC/H- gen- l t concentration reaches 64 and drywell org l ehambef oxygen concentration is above 5%, l EMERGENCY.RPV DEPRESSUR1EATION IS REQUIRED; enter i . i [ procedure developed from the RPV Control l i Guidelinel at [ Step RC-13 and execute it l concurrently with this procedure; -:::::: hydre;e-- l 4_g3 21:4 9 eye *- e ::E irrespective of the offsite l radioactivity release rate, vent and purge the' l I primary containment, defeating isolation interlocks 1 if necessary, to restore and maintain drywell and,*r4
;;ppr;;:le ch=-'rt_ hydrogen concentrations below i 6% or drywell and Orpp::::ien cM ' =3 oxygen I concentrations below 5% as follows: l {
- l. 1 l
# executing the l
/,fF l f' uppr e-ian while following pr:l"or drywell sprays have been l steps l l I
j p1l initiated ands l l I 1 lo Toc
# ; p p; is i e;. che&L.:1 pressure drops
_ below l I l l l WJ1?si setpoint) , (high drywell terminate pressure scram l pee 5- l l l sprays. suppressiones ,A Q lo Drywell pressure drops below -[-ih4ffsi l setpoint)$g l l l (high drywell pressure scram fl i
- 1. terminate drywell sprays. l l i.
PC/H-[.1 pew IfA_upprecrien p;;" water level is below I l. 7- -I:0 ft. (.poodt., spray nozzles) N initiateviin. Suppression ^) l ; (01;;"ie;. l ~3;o y _ suppression M ' sprays g sing only those l RHR pumps not required to assure adequate l core cooling y continuous operation in I i the LPCI mode . l 1 l l \ l
- l. l E .5 ga aew l
OEI Document 8390-4 Emergency Procedure Guidelines J 1
*t T
hr4 Iferuppr-y rien pec. water level is below I
& PC/H-%.2 hh I f o g{20 ft. Ein. (elev;ti:n Of th?. bottom of htsbe A vent)], vent the I
I r i the36b Q f r# Mppr,[prc::dar; fei y&1=&2 centel.uum a
~
ppreseien:rien chambe Rin accordance with I I
-venti d * - l l
te r u Iffouppreerian ". water level is at or i 2 aboveri!20 ft. fin. (cl:v:ti n ;f th S l n
*%q 7 fo~ bott6m of the cupprerrien s ;hanhen vent)] I g geg4fy if Ine gsppr;;;ica cheabefLcannot be 1 vented, vent the drywell in accordance l
@ with4!pr..__ucs d ure
. ,ece far pr 4 = ry ann & a i nman& l l
PC/H- 3 If the suppr:esien ch:rbe* rirywellcan be vented, initiate and maximize the I drywell purge4 flog.(44 en %Aro 4 . g. I PC/H-[.4 If -4p y c Auppre icn peel water level is below l J * -l17 ft. ?nin. (elev: tier ^* bottom of j ,4er.La._ , , .P' f internal ~supprerrier ch::b:^_,4to drywell i
- 183 o ] vacuumbreakerslessvacuumbreakehrnd[
opening pressure in feet of water) l i ( drywell temperature and pressure are I hG within th Drywell Spray Initiation ut down recircu ation pumps and l i T LimiQ nitiate !
/0) drywell coolingpns $usingand
[' drywell sprays pumps not required to assure adequate on y those RHR core cooling by continuous operation in l I I l the LPCI mod 7 I v ' 597 + . I l , Drywell Spr y' Init on
/l i l
I . . imit i Drywell l I
.............. l Temperature 338 +
( F) l l . I l I I I I I I 100 ++--+-----+--------- 1 J 3 11 29 60 l I ( Drywell Pressure (psig) , l m Mark I/II containments o g PC-22 Draft Revision 4AE l t l l
1 6 .!
]'
ORI Document 8390-4' Emergency Procedure Guidelines I chr- Y hydrogen hr4 PC/H- -When drywell or ~ D :::i: l J concentration cannot be restored and_maint nd l below 6% and drywell or ::pp::::i: chtrbt.goxygen I concentration cannot be restored and maintained l below 5%, then irrespective of whether adequate I core cooling is assured: I ) _________________________________________________ g l If while executing the following- steps l I I I suppression M or d ywell sprays have been'l l ! l initiated and: c, a4 l l l %a ch_;.b; ? pressure drops l I , l o A p- i;; below l l j l g,~5 N ::p::si g (high drywell pressure scram l l 1 l setpoint)gF, terminate suppression 3 gMM48 l l l sprays.- c kel . I o Drywell pressure drops below 43,4[*fsi I (high drywell pressure scram setpoint) l l I terminate drywell sprays. l l i _4- 4cem I PC/H-5.1 Ifg"ppreeri:n pee [ water lep l is below 'l 1;; ' ppression, 44 JJy"p!:' ft. C in. (:- eek. spray nozzles) [ica ;f initiate I suppression poch sprays. I PC/H- 2 If krereierpe??waterlevelisbelow 7 J17 ft. S in. ( ' ----" --
- bottom of I f anternal : ppreerirr chrr;;4 to drywell MO {
jg3 { vacuumbreakerslessvacuumDreakehrnd[ opening pressure in feet of water) drywell temperature and pressure are
'l i l
within h Drywell Spray Initiation l ut down recirculation pumps and l ((< . N)\ C Limig,l drywel cooling fans andf initiate l drywell sprays. I l l I l snark +/II centeinr rte e ly" PC-23 Draft Revision 4AE
MPs Me f-S c<We. p sea,,,'jc Gul% l On Mer rt 2000 t " er;ency ? 00:32:: Cuideliner s h S& C WOW [ SECONDARY CONTAINMENT CONTROL GUIDELINE ! 1 I
)
PURPOSE The' purpose of this guideline is to: i o Protect equipment in the secondary containment, o Limit radioactivity release to the secondary containment, and either: ) o Maintain secondary containment integrity, or o Limit radioactivity release from the secondary containment. ENTRY CONDITIONS i The entry conditions for this guideline are any of the following secondary containment conditions: o Differential pressure at or above 0 in, of water o An area temperature abqve the maximum normal operating temperature, (%44 r-/) o A fiVAde c N1er diff;;;ntidtemperature above the max (mum normal operating diff;;;ntief4emperature,C.7d/e T-*-> Rsu.:fmpildl% 71o y# o 3 A ;;VAw exhaust radiation 4evel above r t maximum normal operating radiation level) w V Q.va%f o Anarearadiationlevelabove)themaximumnormaloperating radiation level,(*ndle_ f - 3'
# ejet f. /m.on N M y f (tw n S eer 6_I 9 4 Afloordrainsumpwaterlevelabovethe(maximumnormal a
hu *p. A operating,Flee water t drMlevel) F 4 o An area water level above the maximum normal operating water level ( g g g.- _ Revision M S' ~W
ORI. Document 8390-4 Emergency Procedure Guidelines OPERATOR ACTIONS (g[ Ok l If while executing the following stepsa cecendary ::nt:in;;n6 l l . ::VAC'-. exhaust radiation level exceeds .4408, mr/hr (secondary l* l containment-EVAdLisolation setpoint)$f- t6 5 rA m II. H+.V
, I hi r- M v s/,,
lo Confirm or manually initiate gisolatio% W
- f :_ce ft:A l i ,xat;in :nt ::VA% and r aa.c. b k wit M g l l H+V secchy %duA M l lo Confirm initi;.ti:n for manually initiate SBOT. l ll A...
efer %.... I If while executing the foll wing steps: l H+ j le:4ce_ery I l lo 6@c-..t:f.;;nt "VA",. isolates, and, l I t I lo , .$ec$...+..h : y(:0Qt::in;;.at
- . . . ::"AC'. exhaust radiation level is l l below mr/hr (secondary containment ':
438,Q hA 44 f /.13 HW h?f:"-6 e d
- Misolation lea setpo ,
I l restart n eerender" centeiu-um EVmi. defeating high drywell l l l l(pressure l nd low RPV water level isolation interlocks if l l l'necessary. l l l Irrespective of the entry condition, execute [ Steps SC/T, l
,1 SC/R, and.SC/L] concurrently.
l t-C-S W S .C Q. c o Lo NAi & s' s 0 l n N o n l SC-2 Draft Revision 4AE l
k ;%O ,
.r l
~
x ., y
.p, '*N '
p ,3 OBI Document 8390-4 Emergency',?rocedure Guidelines
],.
) twhm w & m d WutA.
J. (y+*fCr 4 *J+Aa4G- m f"I) kL
. ,\ .
r dnitor and contro recondary containment temperatures. V "b #** (T80IC d 3 SC/r tf's 3 ~ t
)
. < Sp/T-1 tm .d.cf allable' Area cooler '.
-AL s t: U oje.M ?:p p:,.. ' 2 SC/T-2 rIf ........., . ...Mm.gs ;UUMAexhaust TRdiation n e#4. 1
{,
~
level is below'-Hkf/mr/hr HVACisolationsetpoint),)gyperatea secondary cont'ainment' h e . .' O[-
- I+' p g.eeeendary cent:i..;;.d. ::"A . ro a b %,hd'l ableI d' V A ,.
Nm d! w"p$ SC/T-3 cau k :3 L:tAins. M V-When jnexceedd area'femperatur its maximum g ,.anormal- ll 3. operatJng temperatur , isolate all ---- l' I systems (that'are discharging into the 1y[i.01lq l W ---- ,!!/ < _ area except systems: required to shut l'
/ down the reactor, assure adequate core cooling, or 3 suppress'a fire. l
, 4 s s .s < 1 g,
s \.I l' Execute [ Steps SC/T-4 and SC/T-5] concurrently. l ll
*M- .
3 , ll-ll r t,,, y .
'N ' SC/T-4 It'apdmarysystemisdischargingintosecondary I containment: k ; s
$le S-l SC/T-4.1 Before hiny area temperature reaches its ll b ' ) ,4 7 1, maximuQ safe operating temperatur , enter- ll
[ptbceditre;6eveloped from the RPV Control ill
-' Guidelirid'[ Et [ Step RC-1] and execute it
,2 T ll t concurrently with this procedure. ll' 4
.. ./ ll ll SC/T-4.2 When an' area temperature exceeds-it x\ ' maximum sa'fe operating temperaturegin ll
.more than one area, EMERGENCY RPV ll DEPRESSURIZATION IS REQUIRED. ll SC/T-5 When an area temperature exceeds its maximum safe ll operating t,emperature3 1n more than one ares, shut ll ll i down the reactor.
4
?
., ~ ;
o jt e ar I,* '
\
x ( ,
} e
;lj ,'
5 1 ; '- -l. f.. !a. .f .. 1
./
\ SC-3 ' Draft Revision 4AD
)
s A f' j' _j p( s% 1
'OEI-Document 8390-4 ; Emergency Procedure Guidelines SC/R Monitor and control secondary containment radiption levels.
LT*4 ta s -x SC/R-1 When an area radiation level exce sitsmaximum) normal operating radiation.leve isolate all systems that are discharging in the area except systems required to shut down the reactor, assure adequate core cooling, or suppress .
- a. fire. l ll l Execute [ Steps SC/R-2 and SC/R-3] concurrently. l ll ll ll SC/R-2 If a primary system is discharging into secondary l containment: ll 11 SC/R-2.1 Before any area. radiation level. reaches ll its_ maximum safe operating radiation ll leveh enter [ procedure developed from ll the RPV Control Guideline) at [ Step RC-1] ll and execute it concurrently with this ll procedure. ll
. ll SC/R-2.2 When an area radiation level exceeds its ll maximum safe operating radiation level ll in more than one area, EMERGENCY RPV ll DEPRESSURIEATION IS REQUIRED. ll SC/R-3 When an area radiation level exceeds its maximum ll safe operating radiation level in more than one l ll area, shut down the reactor. ll
[ f2 0 d SC-4 Draft Revision 4AD
OEI Document 8390-4 Emergency Procedure Guidelines
& c e et c. $ b r &!Y' SC/L Monitor and c ntrol secondary containment water levels.
SC/L-1 Wheg floordrainsumporMeawaterlevelis aboveitsmaximumnormaloperatingwaterleve\,[7M/efl operate available sump pumps to restore and 6,# maintain it below its maximum normal operating water level. N If a c 4 La. e ea,cMet. b a (8 floordrainsumporta[eiwater W evel cannot L8 A,
- g. S>f) beoperating restored and maintained Tselow its maximum normal water leve), isolate all systems that are discharging water into the sump or area except systems required to shut down the reactor, assure adequate core cooling, or suppress a fire. l
_________________________________________________________ lj , i Execute [ Steps SC/L-2 and SC/L-3] concurrently. l ll l _________________________________________________________ ll ll SC/L-2 If a primary system is discharging into secondary l containment: ll 11 SC/L-2.1 Before any area water level reaches its ll maximum safe operating water leve , enter ll [ procedure developed from the RP . Control ll Guideline] at [ Step RC-1] and exe ute it ll concurrently with this procedure. Il ll SC/L-2.2 When an area water level exceeds its ll maximum safe operating water level in il more than one area, EMERGENCY RPV ll DEPRESSURIZATION IS REQUIRED. ll SC/L-3 When an area water level exceeds its maximum safe 'l operating water levelgin more than one area, shut ll down the reactor ll m I h EY
'I l
4 SC-5 Draft Revision 4AD I
@EI Document 8390-4 Emergency Procedure Guidelines fEi L Ace ~ -
I . TABLE 1 kl/ 7~M f OPERATING VALUES OF SECONDARY CONTAINMENT PARAMETERS
~
___________________________ ___________________________________ (2[b[) 1 MAX NORMAL l MAX SAFE l l l SECONDARY CONTAINMENT PARAMETER l OPERATING l OPERAT G l 'l l I VALUE l VA E l l_____ _______________________________+_____________+___ ______l MPERATURE 0 0 _g 1 AREA I _E l ,,, I I l [RWCU "A" ump room 158' l 130 1 215 ] l ll' l [RWCU "B" p p. room 158' l 130 l 215 ] l ll l [RWCU Ex room 158' at Exs I 130 l 215 ] l ll l [RWCU Ex room- 8' at discharge to l' I i l hotwell l 0 l 215 ] l l l [RWCU phase separ or room 158' l 30 l 215 ) l l l [RWCU holding pump om 185' l 130 1 215 ) l I i l 1 l l [NE Diagonal 175 1 214 ] l ll l [SE Diagonal l 175 l 214 ] l l l l l l l l [HPCI room, area A i 175 l 214 ] l l l l [HPCI room, area B l 175 l 214 ] I l l l [HPCI room, area C l 175 1 214 ) I l l l l l l l [ Torus room, westwall l 175 l 214 ] I l l l [ Torus room, eastwall . 175 l 214 ] l l l l [ Torus room, northwall l 175 l 214 ) l l l l [ Torus room, southwall i 175 l 214 ) I i l i I I i 1 [ Main steam tunnel l 00 1 215 ) l l l l . l l l l [SE, Reactor 130' area A i 15 1 214 ) l l l l-[SE, Reactor 13 ' area B l 150 l 214 ) l l j l l l l
/ I [NW Diagonal area A I 175 1 310 ) I ll l [NW Diagona , area B l 175 l 310 ) l ll l [NW Diagon , area C l 175 310 ] l ll l l l 1 l l l l l l 1 I I I I I ti I
i I I l I I I l l l l l 1 I I I i l l i SC-6 uraft MeVision 4W o
PNPS Plant-Specific Technical. Guidelines lMCEA r e TABLE 5-1 ./ SECONDARY CONTAINMENT AREA MAXIMUM TEMPERATURES l l MAX NORMAL l MAX SAFE. I 1 AREA l OPERATING l OPERATING l. l- l VALUE I VALUE I l_____________________________________+.____________+___________l 1 1 I I I I l l l l 1 RWCU filter area - 74' Elev. I 105 1 120 1 1 RWCU holding pump area - 74' Elev. l. 105 l 120 l l l 1 I l RWCU backwash tank area - 51' Elev, i 105 1 214 l 1.RWCU "A" pump area - 51' Elev. I 105 1 213 I I I l I i- l RWCU "B" pump area - 51' Elev. l. 105 1 213 I I RWCU heat exchanger area - 51' Elev.I 105 1 215 l 1 1 I l l RWCU piping mezzanine area 1 105 1 238 i 1 36' Elev. I I j l i I I l l RCIC torus piping area l 105 1 258- 1 i RCIC turbine area 1. 105 1 130 l I I I I i RCIC piping area - 23' Elev. I 105 1 224 l 1 (TIP room) l I l l I I 1 l Main steam tunnel area 1 105 1 289 . I I 1 l l HPCI torus piping _ area. I 105 1 258 I l'HPCI turbine area 1 105 l 130 l i I I I l HPCI piping area - 23' Elev. I 105 1 309 l l ("B" RHR valve room) l l l 1 1 I 1 l RHR "B" and "0" pump area l 105 l 130 l l 1 1 I I l l RHR "A" and "C" pump area l 105 l 130 1 1 1 I i 1 RWCU & RHR piping area - 23' Elev. I 105 1 251 1 1 ("A" RHR valve room) l 1 1
-l. I 1 I i RHR S.E. pipewell area i 105 1 224 1 1 I I I i RHR. piping area - 80' Elev. I 105 l 120 l I (Fuel pool heat exchanger area) 1 l l 1 1 I I 5-6 Revision 3
^
OEI Document 8390-4' Emergency Procedure Guidelines
~
fG~$A Di= O RATING VALUES OF SECONDARY CONTAINMENT PARAMETERS (Continue 1: l
~SEC DARY CONTAINMENT PARAMETER.
-l. max NORMAL
.l OPERATING 1
l l-l
-l i
- l. l VALUE l 1
l____________________________________+_____________l-l HVAC COOL R DIFFERENTIAL l l-.TEMPERATUR l O _f l O -. l. I. 1-[RWCU."A" pu l [RWCU~"B" pump room 158' room 158' I l l 75 75
] l
] l
/ 1:l l [RWCU Hx room 1 8' at Exs .l 7 ] l -l l [RWCU-Hx room 15 ' at discharge to l l, I hotwell. . I 75 ) l l l [RWCU phase separa r room 158' l' 75 ] l l l [RWCU holding pump om_185' l 75 ] l l l I I l [ Torus. room, NW A -
50 ) l l' I [ Torus room,. west A l '50 ) l l l . l l l [ Torus room, NW B 1 50 ] l l I: [ Torus room, west B. l 50 ] I I i l . l
.I-[Tdrus room, NW C l 50 ) l I l-[ Torus room, west C l 50 ) l l 1 . l l l [ Torus room, NW D l 50 ) I l-I [ Torus room, west D '
50 ) l l l- 1 l' I l l I I I I l l l' 1 I I I I
- 1. I I I I I l- 1 1 1 l l
- l. I I
, I I I l- 1 1 I I I I I I I I I I i l
/ -
SC-7
]
Draft Revision 4AD LL _ _ _ _ .
PNPSfPlant-Specific' Technical Guidelines
//f.$ EA f-i
~ TABLE 5-2 SECONDARY CONTAINMENT'H&V C00LER' MAXIMUM TEMPERATURES.
l l MAX NORMAL- l l COOLER l OPERATING il i I VALUE I I l (Panel C-6';) I _____________________________________+______________l 1 1 E i l- 1 I l HPCI compartment i 100 l' l I I i RHR A quadrant l- 100 I l l l l RHR B quadrant i 100 l 1 1 l l CRD quadrant' l 100- 1. I I I I RCIC quadrant i 100 l l l l 1 1 I i j S_, R. ,,1.n s
I OEI Document 8390-4 Emergency Procedure Guidelines fc-TLA C E i M/ 7W i TABLE 1
' OPERA G VALUES OF SECONDARY CONTAINMENT PARAMETERS (Continued) l l MAX NORMAL I MAX SA I I Q i l SECONDAR CONTAINMENT PARAMETER -l OPERATING l OPERA NG I l l 'l i VALUE I V UE l k l____________________________________+_____________+__________l-l~ l HVAC EXHAUST RA TION LEVEL l HE/HB l ;
l- 1 I I t
! [ Reactor building l 50 ] NA l l l [ Refuel'. floor 1 50 1 NA l l l_______________________ ____________l__________ __l___________l l' AREA RADIATION LEVEL l MR/H I BB/JB l I . l l l l [158' southeast' area 1 0 1 1250 ] l' l l [158' northeast area 1 50 l 1250 ) I l l [158' northwest area l 50 1 1250 ] l l l l l l l [130' northeast. work area 1 50 1 1250 ] l l l [130 southwest work area 50 l 1250 ) l l l l l l [ Decontamination pump & equipmen l l l l room l 50 l 1250 ] l l I [ South CRD hydraulic units. l 50 l 1250 ] l l
l [ Spent fuel pool passageway l 50 l 1250 ) l I l l l i l [185' operating floor l 5 l 1250 ] l l l-[185' sample. panel area l 50 I '1250 ) l ll l l [185' RWCU control pane area 1 50 1 1250 ] 1 l' I I I I
.1 [ Fuel pool demin pan area l 50 l 1250 ] l l l [CRD repair area 1- 50 1250 ] l' l [RCIC equipment a a l 50 1 1250.] l ll{
l [CRD pump room l 50 l 1250 ) I. I i 1. I 'l l [RHR 6 core s ay room northeast i 50 1 1250 ) l l l [RHR & core ray room southeast i 150 1 250 ] I l 1 I I l l 1 1 I I I I I l 1 I I l l I I I ) I I i l l l l l l l 1 , , I I I _ _____________________________________________________________ l L SC-8 Draft Revisio L--_____--__--_.
PNPS Plant-Specific Technical Guidelines
/WSWAJ &
TABLE 5-3 SECONDARY CONTAINMENT AREA MAXIMUM RADIATION. LEVELS
- l. l MAX NORMAL -l MAX SAFE 1 l AREA- 1 OPERATING l OPERATING l l I VALUE l VALUE 1 l_____________________________________+_____________+___________g l H&V EXHAUST RADIATION LEVEL l I !
! I I I l Reactor building l 710 cps l NA i 1 Refuel floor I 16 mR/hr i NA 1 l_____________________________________+_____________+___________i l- ! mR/hr- I mR/hr i I I I !
l N.W. equipment space /HPCI pump room 1 20 1 1000 1 l 17'6" Elev. I I l' i 1 1 1 1 CRD pump room - 17'6" Elev. I 20 1 1000 l I I I I I RCIC pump room - 17'6" Elev. I 22 l 1000 l 1 1 I l l S.E. equipment space - 17'6" Elev. I 350 1 1000 l
- 1. . 1 I I I CRD HCU west area - 23' Elev. I 300 l 1000 l I I I
. CRD HCU east area - 23' Elev. I 300 1 1000 l I I I I i RB west area - 51' Elev. I 5 l 1000 l l l l l l RB east a rea - 51' Elev. I 8 l 1000 l I I I i 1 North storage and laydown area 1 28 l 1000 l 1 74'3" Elev. 1 I i 1 1 I I l Fuel pool cooling pump /hx area 1 60 1 1000 l I 74'3" Elev. 1 l l l l l l 1 SBLC pump area - 91'3" Elev. l 5 1 1000 l l I I i i Skimmer surge tank area 1 40 1 1000 l 1 91'3" Elev. I l I
- 1. I I l 58 Revision 3
'CEI-' Document 8390-4 Emergency Procedure Guidelines gci~~M C E .
W/7W TABLE 1 ~ OP TING VALUES OF, SECONDARY CONTAINMENT PARAMETERS (Continued) I I MAX NORMAL I MAX S E,A f
'i SECO RY' CONTAINMENT PARAMETER l' OPERATING l OPE TING I I I VALUE I ALUE I 1 _--.._____ .------_______--.__-_-_-+_---_______-_+- ______--_I I. FLOOR DRAIN MP WATER LEVEL l & I l l l l l l [ Sump A (NE dia nal) l 47 i NA I II 1.[ Sump B (NW diago 1) 1 52 ) i NA I l1 l_____--___-_-______ --- -_-_________+-_----_ ___-+___-______-1 1 AREA WATER LEVEL l l & I I I I i 1 [CRD compartment . l 7 l 260 ] l l l [RCIC compartment i 7' I 22 ] I I I . l I 'l I [RB NE corner room 7 l 14 ] I I I [RB SE corner room I 7 l 15 ] I I I I I I l [HPCI compartment I 7 l 14 ] l l l l l l l [ Torus compartment NW 'l 7 I 11 ] I I I [ Torus compartment NE 7 l 11 ] l l l [ Torus compartment SE 7 I 11 ] l l l [ Torus compartment SW I 7 I 11 ] l l l' I I I I I I I I i i l a
i I I I I I I I i 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
- -_-----_----_---__--_------_-__---__------___----_----___-- . l f( SC-9 Draft Revision 4AD j
PNPS Pl' ant-Spec 1fic Technical Guidelines a-
/ W S 5 k 7~~ N
. TABLE 5-4 SECONDARY, CONTAINMENT SUMP / AREA NAXIMUM WATER LEVELS l l MAX NORMAL-- l MAX SAFE 1 l SUMP / AREA l- OPERATING l OPERATING 1 I .I .VALUE I VALUE 1 l___________________________________+_____________+_____________g
.I I I i l SUMP l- 1 I I I I I
-1, Reactor building floor drain i1 inch on 1 NA l 1 l HPCI pump- ! . -l l l room' floor i l 1 -l 1 'l-
.l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ + _ _ _ _ _ _ _ _ _ _ _ + _ _ _ _ _ _ _ _ _ _ _ _ _ :-
l' I Inches ! Inches I I- - ARE A l(above floor)l(above floor)l l' i 1 I I I N.W. quadrant i 1 1 6 l l l 1 1 l S.E. quadrant i 1 1 6 1 l ! I i 1 HPCI compartment I 1 .l. 6- 1 I I I l' I S.W. quadrant i 1 1 6 1 1 I I I l CRD quadrant' i 1 1 6 I l- 1 I l-l~ Re.1 1.n S ) S_,
f/V P S P/W- e ciWe 22cAmY &wYNdco O=I 0:: r:nt S380-4 F==r;=nny pracad"re G"idelinar - SE C 770 d (o RADIOACTIVITY RELEASE CONTROL GUIDELINE PURPOSE The purpose of this guideline is to limit radioactivity release into areas outside the primary and secondary containments. ENTRY CONDITJ,QLS The entry condition for this guideline is: S o Offsite radioactivity release rate above the offsite release l c P-- rate which requires an Alert. l OPERATOR ACTIONS H+Y i l If whileexecutingthefollowingstepsturbinebuigdinga I is shutdown -!er-iecleted dse to high restart l l l turbine b u i l d i n g n i"1.*.C , f;f;; ting rediction] i=01stien inter~'ecke 1 18,,, I l 1 se;;;; rye l g g O,.- I i RR-1 Isolate all primary systems that are discharging into areas outside the primary and secondary containments except systems required to assure adequate core cooling or shut down the reactor. RR-2 When offsite radioactivity release rate approaches or ll exceeds the offsite release rate which requires a General l Emergency but only if a primary system is discharging into il an area outside the primary and secondary containments, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter [ procedure developed from the RPV Control Guideline) at [ Step RC-1] and execute it concurrently with this procedure. (o - # C aR-1 M Revisionf W l w___-___
fWf$ ffp$ . dce & Mi ht< thbAee 0"I 0;Or:2t O OO O Emerger.cy Trecedure 0010011..0S A SC~ C/90W f 4 g CONTINGENCY fl - Q ALTERNATE LEVEL CONTROL l l If'while executing the following steps: 1 1 l lo Any control rod canno e determined to be inserted to I l i or' beyond position- 02 (Maximum Subcritical Banked l l l Withdrawal Position)@ and it has not been determined l ll l that the reactor' will remain shutdown under all l ll l conditions without boron, enter (procedure developed I ll l from Contingency #5]. l I i lo RPV water level cannot be determined, enter [ procedure l l l developed from Contingency 64]. l l 1 l l lo RPV _ water level is increasing, enter (procedure l l [ developed from the RPV Control Guideline) at'l l 1 [ Step RC/L]. /,v 4 PV l l l lo RPV water level drops below i-l L41n. p' fT w m /cveX (ADS, initiation l l l l setpoint)], prevent automatic initiation of ADS. l l ) _______________________________________________________________ l
&0 PA . .. .
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\
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~s 7-W i T1-1' tief Lbevision 4A : O-l C _ _ _ _ _ ___-_____ _
C3IDocumentg390_4' Emergency Procedure Guidelines D (f of MM _____________________ ________________________________________ g l If "hil eaecutin- h fell ^"in; st p- p,rimary containment l lj
" h = "^ e pressure l water level and """-~ ~4^" cannot be / c #.,
I maintained below he Maximum Primary Containment Water Levely V"I I /i Limi then irrespective of whether adequate core cooling is l "l
/ l assu a terminate injection into the RPV from- sources l l
, gj external to the primary containment until primary containment l l 8
.I water level and s"ppr00:icn ch::b: A pressure can be l l <
l maintained below the^gaximum Primary Containment Water Level l l { v l Limit. +'"*- l. l/
, \' \ l Maximum Primary lI l- l Containment l l ;
i 1. Water Level Limit i l I l......... .I l l l . I I l Prim l . I l l l Containmen l . l l l Water Level . I 1 l (feet) l . I l l l . l l l l . I I I I . I I l +__________________ ___ l l l l 1 l Suppression Chamber Pressure (psig l l t__________________________________________________________ l1 l 01-1 Initict: IC.f k l Cl-2 Draft Revision 4AE I
@BI Document 8390-4 Emergency Procedure Guidelines Cl- Line up for injection, start pumps, and irrespective of l l pump NPSH and vortex limits, increase injection flow to the l-maximum with 2 or more of the following injection' l subsystems:
o Condensate n unen s o LPCI-f3yith injection through the heat exchanger as l soon dfi possible. l o LPCI-1Qtith injection through the heat' exchanger as I soon-a3 possible. l
- a LPCI-C with inj::tian thronah the best ::chen3e e.- ( l g ovuu es g::ible.'" .l o S-A o S-B o
If less than 2 of the injection subsystems can be lined up, J commence lining up as.many of the following alternate > injection subsystems as possible: o S5W c.e e s s H A 4. A.H 4 1 nun : .;;;; ;;t;; g;;;ti: y I e c 4 g WaA c.e e ss+4cA 4. A HA Wo Fire yete # W,A, cassMI. 4e (LH R. 4 8--
- l; Inter;;nn;;tivum wii.h eth;r anite ]R
%o ECCSgeep-{ulleyetem .} e
-l CLC (teet tauk) l C 2
__La SLC (beren innk) ] %
- be m m er. b S b Y h Y c r-oss Neh k sate _ ( +c t + .wJ<. a bo m d !
h M. l y-- M E'C.C C b* l l l la c. ) l 1 Cl-3 Draft Revision 4AE
'CBI Document-8390-4; Emergency Procedure Guidelines f If_RPV. pressure is above l1f psig (highest RPV pressure l Cl-3 5 at which the shutoff head of.a low-water-qualitu alternate- l injectionsubsystem(excluding (LC)isreached)/f- l
~ _____________________ .ar_____*__________________________ i l If while executin the followingisteps RPV pressure l l lL drops below-f46 ps g (highest RPV pressure at which the I ~
l .- l' shutoff head.of a low-water-quality alte nate injection l l
- l. subsystem (excludinggLC)(is reached) , continue _ in' l l llthis procedure at,[Steptcl-0]. Il
-_________________________JiL_A _______________ ___________ [
Cl- 1 If'no injection subsystem is lined up for injection ! L' with at least one pump running, start pumps in alternate. injection subsystems which.are lined up for injection. jL t r.Gr.3 Cl-3.2 When RPV wate level-drops to [-15 8A in. (top of l 5- ' active fuel) : o If any system, injection. subsystem or I alternate injection subsystem is lined up with l at least'one pump running, EMERGENCY RPV l DEPRESSURIZATION IS REQUIRED. I o If no system, injection subsystem or alternate injection subsystem is lined up with at least . one pump running, STEAM COOLING IS REQUIRED. .l , Cl- When RPV pressure drops.'below [skg(highestRPV l 3 pressure at.which the shutoff head of a low-water-quality A l alternate ~' injection subsystem (excluding (LC) is reached)@: - l i Cl- 1 Line up for injection, start pumps, and I i ' irrespective of pump NPSH and vortex limits, l increase injection flow to the maximum with all I systems and injection subsystems. I J. nt61 l Cl-4.2 When RPV water level drops to [-1 ein. (top of l 3 active fuel)(f EMERGENCY RPV DEPRESSURIZATION IS -l REQUIRED; 1;.ne up for injection, start pumps, Aand l increase injection flow to the maximum with eH , I f' alternate injection subsystem p ** [essi6/4. p7l
- t r. 6 . 7 l IfRPVwaterlevelcannojtberestoredand a l maintained above--l I dxTn. (top of active fuel)F, l PRIMARY CONTAINMENT FLOODING IS REQUIRED; enter l ,
[ procedure developed from Contingency 46]. 1 ! I Cl-4 Draft Revision 4AE I
f ?S .Pld-Sp cb Nc m Y b M e h e b d e.g ney n: n t aten_4 mm.vg. y n;;;;;ra cui;;11,:: os S &778W 8
- CONTINGENCY #2 -
EMERGENCY RPV DEPRESSURIZATION
'C2-1 When either: I #2 # l l
_______ g o Any control rod can o be determined to be inserted to I or beyond position 2 (Maximum Suberitical Banked l WithdrawalPosition}} and it has not been determined ll that the reactor wil. remain shutdown under all ll conditions without boron and all injection into the ll RPV except from boron injection systems, CRD, and RCIC ll has been terminated and prevented, or o All. control rods are inserted to or beyond position ll 02 (Maximum Suberitical Banked Withdrawal Position)(,A ) l or it has been determined that the reactor will rema:.n ll. shutdown under all conditions without boron, ll z .s-C2-1.1 If a i h drywell pressure ECCS initiation signal l ( 3 ps g (drive 11 pressure which initiates e 1 exists, prevent injection from those M CS l ECCS) and LPC h)I pumps not required to assure adequate core l cooling. I C2 1.2 Initist: IC8 lh C2-1. If suppression pool water level is above-!f ft P - l 8 in. ( top of SRV discharge device)
% -2.
e4 ppen all ADS valves. RVs ica to A M ves are op au.the
~~, ate ,-
s+..m ~asY w J
-ca-ae M Revisio M 84
OEI Document 8390-4 Emergency Procedure Guidelines C2-1. If less than 3 (Minimum Number of SRVs Require b l j5 for Emergency Depressurization)$#SRVs are open Gand RPV pressure is at least 50 psig (Minimum SRV Re- l opening Pressure) above cupprecrien chn 'm[x4+r**- pressure 7, rapidly depressurize the RPV, defeating l isolation interlocks if necessary, using one or i ! more of the following: l o Main cond0n:Ot 3 Ywe W v 6 f e4A
- P_9P ' te:r ;;ndencing =;d. %
- i
-0 [Other : tear drieen eggiprent]EL~
\
o Main steam line drains i o BPCI steam line o RCIC steam line o fhadvent l 1 \ l - e IC tube e4de venkr~3 l l If RPV water level cannot be determined, enter [ procedure l l l developed from Contingency 94]. l l C2-2 When either: 1 I ll
~
o All control rods are inserted to'or beyond positi,jo 02
-(Maximum Suberitical Banked Withdrawal Position)&, or l l
o- It has been determined that the reactor will remain ll H shutdown under all conditions without boron, or ll o -GS8do#hlds(ColdShutdownBoronWeight) u of boron have been injected into the RPV, or l ; I o The reactor is shutdown and no boron has been injected l , into the RPV, 1 4 i enter [ procedure developed from the RPV Control Guideline] at [ Step RC/P-4). l C2-2 Draft Revision 4AE
Cct h k Y nt hurkkkg fkfb f/wh
-0 51-- h w ; L t 03 90 -4 Ext: ;ncy Precad"r= ""idelin== 4 ,
1 I I SECWDW 9 CONTINGENCY 43 - ) STEAM COOLING I ll _ C3 i Cenfir- initiction of M 9-i ___________________________________________________________ l l If while executing this step Emergency RPV l l l Depressurization is required, RPV water level'cannot be l l l determined, or any system, injection subsys tein, or l l l alternate injection subsystem is lined up for injection I l with at least one pump running, enter [ procedure ! I developed from Contingency #2]. . l C. 5 - f initi ted igpen RPV water level drops to ll
=l 20% in. (Minimum Zero-Injection RPV Water Level) enter ll
[ proc dure developed from Contingency #2]. l Ib 8. 3 4 l l E
--C3-1 -Or:ff Revisiog M L_______._______
fk $ h$ c hh. a m hw 0"I-Bou _..t 9 3 ^^ -- t E...O r y 44,y "recc:'ure Cuidelin0bt Secnod/O CONTINGENCY #4 - RPV FLOODING l ) _______________________________________________________________ l l If while executing the following steps RPV water level can be l l l determined: l l l l l lo If any control rod canno be determined to be inserted l ll l to or beyond positio 02 (Maximum Suberitical Banked l l
'l Withdrawal Position and it has not been determined l ll l l that the reactor will remain shutdown under all I ll l conditions without boron, enter [ procedure developed l ll l from Contingency $5] and [ procedure developed from the l l l RPV Control Guideline] at [ Step RC/P-4] and execute l l l l these procedures concurrently. l l l' l l lo .:f all control rods are inserted to or beyond positio l ll l )02 (Maximum Subcritical Banked Withdrawal Positionf or l ll i l it has been determined that the reactor will remain i ll
[ l shutdown under all conditions without boron, ente'r ! ll l [ procedure developed from the RPV Control Guideline] at l l l [ Steps RC/L and RC/P-4) and execute these steps l l l concurrently. l l _______________________________________________________________ l l e,- - ( i ( l ( k e ~ _ _ _ f l c.;-i R mo b evisio M } 1 0 ~.** l l
OEI Document 8390-4 Emergency Procedure Guidelines (F
& 4e e 1
l If whi e executing the following steps primary containment I ll l water evel and euppre-=ian W 9 % pressure cannot be l l ) (< l I.maint ned below the Maximum Primary Containment Water Level l l .0 i Limi , then irrespective of whether adequate cors cooling is l l l assu d terminate injection into the RPV from sources l l l external to_the primary containment until primary containment l l ) I water level and =ppressica ch =befapressure can be l l 4 l maintained below the Maximum Primary Contah ment ** Water Level I l l Limit. 1 1 I i Maximum Primary
.j i l l l Containment l q l
l' I Water Level Limit l......... l l l l [ l l . I Primary l l l l Containment . l l l Water Level . l l l (feet l . l l l 1 . l l l 1 . l 1 l l . l l l +_______________________ l l l l l Suppression Chamber Pressure (psig) l l ' _______________________________________________________________ i C4-1 If any control rod nnot be determined to be inserted to I or beyond position 2 (Maximum Suberitical Banked l and it has not been determined that ll Withdrawal the reactor will Position rema ')in shutdown under all conditions ll without boron, flood the RPV as follows: ll _________________________________________________________ l 1 l If while executing the following steps either 11-l ll 1 2l ll l control rods are inserted to or beyond positio 1 (Maximum Suberitical Banked Withdrawal Position r it l ll l has been determined that the reactor will remain f ll l shutdown under all conditions without boron but RPV i ll l water level cannot be determined, continue in this l l 'I 1 i procedure at [ Step C4-2]. l l l j l l l C4-2 Draft Revision 4AE l u __ _ _ _ _.___
OEI Document 8390-4 Emergency Procedure Guidelines C4-1.1 Terminate and prevent all injection into the RPV except from boron injection systems and CRD until RPV. pressure is below the Minimum Alternate RPV Flooding Pressure. l l Minimum Alternate RPV l l Number of open SRVs i Flooding Pressure (psig)l g l_____ ________________l__________________ .______ 7 or more l 110 ) '
'l '
l (6 l
.I 135 ] }l {l l
l l l- 165 i l/l i l 74 l /86.lo 210 }A - l l l l l l [3 i l r +r.s 2so-f=- l l 1 l 1 [2 l 376 0 -400 ; - l l _ _ [1 _ _ _ _ _ _ . _ _ _ _ _ _766 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _7_ . If less than 1 (minimum number of'SRVs for which l the Minimum ternate RPV Flooding Pressure i belowthelowestSRVliftingpressure)(SRVs)can l be opened, continue in this procedure. C4-1.2 If at least (Minimum Number of SRVs Required for l Emergency Depressurization) SRVs can be opened, l close the MSIVs, main steam line drain valves, and
-ECf2.RCIC, nn d "'" :t e a valves.
e"#0nrinik. isolation lh t I 1 Shw f/w l l 1 l 1 l C4-3 Draft Revision 4AE l
= ___ _ __________ _ _ _ a
OEI Document 8390-4 Emergency Procedure Guidelines C4-1.3 Commence and, irrespective of pump NPSH and vortex l limits, slowly increase injection intq the RPV with l the following systems until at leact {l -- g l (minimum number of SRVs for which the l #$l l Minimum Alternate RPV Flooding Pressure is -- - l below the lowest SRV lifting pressure)7 SRV - 1 l open and RPV pressure is above the Minimum Alternate RPV Flooding Pressure: o Lt.es drive.9. feedwater pumps, defeating high l RPV water leveT,$=^1 34^n ia_te rlechs. if I necessary. l P 4-n, p t og ic l o Condensate pumps + l o CRD LPC ith injection through the heat l exch@ angers as soon as possible. ] ]g If less than (minimum number of SRVs for which ll the Minimum Alternate RPV Flooding Pressure below the lowest SRV lifting pressure) f SRV open or RPV pressure cannot be increased to ve is(f ll y I the Minimum Alternate RPV Flooding Pressure, commence and, irrespective of pump NPSH and vortex l limits, slowly increase injection into2 the RPV with I the following systems until at least $1 (minimum I number of SRVs for which the Minimum Alternate RPV Flooding P,[ essure ij below the lowest SRV lifting pressure)dTSRV h 61s fopen and RPV pressure is I above the Minimum Alternate RPV Flooding Pressure: 0 HPCS, def0 ting high ",,","nwater 10701 iOO10 tic. l 4 . 4. m , u, - 4c - , - . l30-5 a c c o ssl5 'Y-lc ANk rn eue --->--..._-.-u- , s~
'Nkin'c."r DikaX YI'N4
'i Mo d;"4{Oystes Fire %:A cr o sef 'cA
- M2 h lc is:terc0""00ti0n; With other Unite ](
ECCSgeep-fullsystenst -} # - 0on$hsh Te c. c o cc h sk. 4 G~d C.C C4-4 Draft Revision 4AE
OEI' Document 8390-4 Emergency Procedure Guidelines FAIN AAY W7~AtW#&W f.R.e c AtWG H ASQWATA _______________ _______ ___________________________ ll l If.less than (mi um number of SRVs.for which l ll l the Minimum Alte ate RPV Flooding Pressure i ll l belg(wp the lowes SRV lifting pressure) @ SR ll l isgr open or V pressure cannot be increased ol ll above the Minimum Alternate RPV Flooding l ll l-Pressure,j enter [ procedure developed from l 1 Contingency #6] and (procedure developed from the l llll 10-6 l RPV Control Guideline] at (Step RC/P-4) ' and l ll l execute these procedures concurrently. l ll ___________________________________________________ ll C4-1.4 When.at least (minimum number of SRVs for which l the Minimum Alternate RPV Flooding , Pressure-is below the lowest SRV lifting pressure)$aSRV isFj ll open'and_RPV pressure is above the Minimum l Alternate RPV Floodin Pressure, control injection i to maintain at least (minimum number.of SRVs for I which the Minimum Alternate RPV Flooding tressure is below the lowest SRV lifting pressure) fSRV l open and RPV pressure above the Minimum Alternate
~
i RPV Flooding Pressure but as low as practicable. l C4-1.5 When all ontrol rods are inserted to or beyond l position 2 (Maximum Suberitical Banked Withdrawal l Position); or it has been determined that the ll reactor w:.11 remain shutdown under all conditions ll without boron, continue in this procedure. ll C4-2 If at least (Minimum Number of SRVs Required for Emergency Depressurization)f SRVs can be opened or if a l
' ::700 er ;;ter dr44ed feedwater pump is available for l injection, close the MSIVs, main steam line drain valves,
- nd ICE,RCIC .nd .""" stes c^rdencing isolation valves. l 10-1 54-m lh b C4-5 Draft Revision 4AE
OEI Document 8390-4 Emergency Procedure Guidelines
)
u C4-3 Flcod the.RPV as follows: l .] l C4-3.1 Commence and, irrespective of pump NPSH and. vortex l ! limits, increase injection into the RPV with the l ! following systems until at least9 3:(Minimum Number J of SRVs Required for Emergency,Depressurization) % ] SRVs are o n and RPV pressure is not decreasin and is psig (Minimum RPV Flooding Pressure) or. l more abovegTrip::::i n ch-S%Sressure: l l
.% ]
- 700, 0.GeLii.3 Livia RF v-
,_m .,_u_ ,, _ _ _ . , . . . .
aeter level 1-^1stic m 8-lh i H 7.eter hi::n Yf.eedwater pumps, defeating high o ! l , ,, RPV water level,'-^'=^ '-'^ ' ~ k= if
'necessary. P M + r y (
- p c- l o S o LPCgwith injection through the heat 'I exclfangers as soon as possible. IO 4 y
o Condensate pumps . o CRD o SS V c.r e st I-d M 1- RRS I ){ 0 '"J:" C.t 4;;;; p WIicea tt4 weLere costM cic;[-ti: 4e' @HA No Fire Syst^-*- W M c-M stM4. 4e MA t A- _ !c Intercennecti;n; with viLes unite ]% ECCS keep-full cy t;;.e" a s t- 4-- l0 L> _ e CLC b em sk (teet e.nN "s's.ua)A s Wb "T't-e_s # f% c-r-e ssfrd ,lo S8l C-
- l: CLC (beren t: h) } %
_o__ _ _Cu _ _ d.h _ _ _s __4_ _ ___ _ _ _ _ _ _"T_____________________ r-@_ _ _ _ _ _c. r e e.t h k / 4iis; c c_ t l If less than [ (Minimum Number of SRVs Required l ll l for Emergency Depressurization)f SRV s re open l ll l or RPV a l ll
. f it?8 psig pressure cannot be maintaine(MinimumRPVFloodingPressu
[ procedure l above l ll
;;esi;n :h--M i pressure, enter 3 l
} /o developed. from Contingency 6 and (procedure l ll l 801 J l developed from the RPV Control 3uideline] at l ll i l [ Step RC/P-4] and execute t e procedures l ll i l concurrently. l ll C4-6 RcxMW6 Draft Revision 4AE f.[ 8l-WfAc% j _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ - . _ _ . _ _ . a
OEI Document 8390-4 Emergency Procedure Guidelines C4-3.2 When at least 3 (Minimum Number of S Vs Required l for Emergency pressurization) SRV s O re open l and RPV pressure can be maintained at least M ^ 62.-ll psig (Minimum RPV Flooding Pressure) @ bove l O'" 2upp::;elvu 3 Geisr^ pressure, control injection'to i maintain at leasF-d3 (Minimum Number of SRVs Required for Emergency and RPV pressure Dep @psig at least3 pressurization (Minimum RPV @ RVs open l Flooding Pressure)Labovei;uppseesier. ch :b,%. g4cc u l pressurebutaslowaspr{cticable. I 6 2. i
.f I
( s
, 1
.i i
1
..s C4-7 Draft Revision 4AE
_( $. CEI Document ~I390-4 Emergency Procedure Guidelines C4 When: l
. l o' .
RPV water level' instrumentation 2N wStm is availablef.and-levLE kMcL - d ll o Temperature sl ear the M rleference leg inats.umente,. l 0 ' verticalrunsQrebelow212F,and ~ l o RPV pressure has remai ed'at least p g (Minimum' RPV Flooding Pressure) boveL rupp ::;i0n ch--59t; g+8% pressure for at least khe-MinimumCoreFlooding l Interval b , * , l'
- l. ( l
.. . 1 I
[ l Number of 1 ' Minimum Core Flooding I ] l Interval (min) ,i l /1 t 1 ) 1 di----jlopen:SRVs- .-_--_ --...------+-----------------------..---l j
! j [
6 I i
- 1! l )
'I I <_ 5 / 16 1 1 fl.- '
. [ l ~4 47<-- G, t. 9 1 1 l-
@ [ l 3 1 -sar- 3 o7 . g, I I
-------------------------------------------------- . l y.
l<
- TerminateJ411 injection into the RPV and reduce RPV water i level until=RPV water level indication is restore -
l. ot(. F.*4
.o (4- 1 If RPV water level indication is rest %redwitinthe l Maximum core Uncovery Time Limit /after conanencing -I termination of injection'into the RPV, return to [ Step, ,l C4-3.1]. ^
, I
) .>
80 + l Maximum Core Uncover [ l 60 + Time Limit
, /
l . Core l v Uncovery 40 . Time l . r (min.) . . 0+ . p I . 7 i. !' O +-------+--------+- -----+-- ; 10 min. I hr. 10 hr. 00 hr. Time Af ter 7.eactor Shut n
)
0 < C4-8'.,f t'. Draft Revision 4AE L F 'e, 3 f .r - ! _. . 1 . >
OEI. Document 8390-4 Emergency Procedure Guidelines i C4-5 Enter (procedure developed from the RPV Control Guideline] l ' at [ Steps RC/L and RC/P-4] and execute these steps 1 concurrently. i I' 1 I 1 . h A l-o I.
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CQJ4TINGENCY 45 j Lgy.g/ POWER CONTROL a ___- ... __-____-__ __.,_____-__...___ --_-__ __ _________-----_
. l If while fxecutinanthe following steps: l l
~f" l U ;. N f 4 l l lo RPV ' uter level cannot Mitdetermined, enter [ procedure l l. I devel geS lf rom Contingenop t 4] . l l l
& l- l lo All. cion' trol rods are intarted to or beyond positi M2 l ll
'l (Maximum. CabcrStical Banhed Withdrawal Position r it l ll 1 has been determined that the, reactor will ' remain l ll l shutdown under all Nonditionn wfthout boron, enter i ll l [ procedure develope.i.'from the F2V Control Guideline] at l l
[ Step RC/L]". {( z_) !
/ lo Primary containment water / level' and,; pp :ssic,ii cham'eec9 t~ l l l pressure cannot be maintained.below the Maximum Primary l l . l > Containment Water Ltvel Limik, then irrespective of l l
,l I, whether adequate- core. coolihg is ' assured terminate l l 4 y Ninjection s , J.nto $he RPV from sources External to the l l 4 1
- primary. containment rimary containment ' water l l eI until uma?ew y' pressure can be maintained l l level anda@supersagina 9 .1 below the s.ximundPrimary Cor:tainment Water Level Lin.it. I 1 k
i Mc M l l i naxh'nUE Primary ^ l i b( 1
- l l
Containment Water Level Limit i
,i l......... - l l l l . l l l J Primary I . l
'f,) dont ainment I . I i p 'l Water. Level '0 W . l I l (f5et) ll . l l
. l l . l l
, l I . l l l . I l l
pl____ ________..-______. N. l l
. Suppres s ion.JNhnmho r Dronenra (pgj g} \
l l _____________________________.,._______________________________ l > .C4-1 Prevent automatic initiation of ADS. l c . ) M evision M M -* e- _ _ _ _ _ _
GEI Document 8390-4 Emergency Procedure Guidelines-
'C542 If t- {
(.sof* o Reactor power is above 34 (APRM downscale trig r cannot be determined, and Tara w @ ,h o - 0 ppr ::ica p;;S temperature is ve Gthe Boron l Injection Initiation Temperatur and- l
%)
2.u v ff I l l Boron 130 + Injecti i l...... I on l Suppression emperature ! Pool 120 + . I Temperature . l ( F) l l 110 + .. .... l l l l l 100 +---+---+---+---+---+--- l 0 1 2 3 4 5 l Reactor Power (t) .i
..o Either SRV is open or opens or drywell pressure is above setpoint .0 psigN g(high ,g- drywell pressure scram Then: l
.o If any MSIV is open, bypass low RPV water level I prer sti _yeteaenEMSIVisolationinterlockg,*nd
'arter: th: p;:r stie : pply lt: the raa+=4a== ] ; ="d9 -
o Lower.RPV water level, irrespective of any consequent I reactor power'or RPV water level oscillations, by ll
. terminating and preventing all injection into the RPV except from boron injection systems and CRD until eithers o Reactor power drops below (APRM downscale tri)Mor EfpCt N k - l L 6. J o RPV wafer level reaches i 16#Ain. (top of active ll fuel)$for ll o All SRVs remain closed and drywell pressure remains below 43, psig (high drywell pressure scramsetpoint)f.{st.5-c5-2 Draft Revision 4AD
03I Document 8390-4 Emergency Procedure Guidelines l If while executing the following steps Emergency RPV l l Depressurization is required, continue in this procedure at l l [ Step C5-3.1]. l l If while executing the following step: Ml lo Reactor power is above h (APRM downscale tri ) or l cannot be determined, and l l i t6.7 l l o- RPV water level is above [in. (top of active l l] l fuel)$7 and I il l rom wA p ,1A temperature
/- l lo Oppr ::ien is above Fthe Boron l l l Injection Initiation Temperature @f and l l l ^(Fe d ) l lo Either an SRV is open or opens or drywell pressure is l l above -{-3,4 psig (high drywell_ pressure scram setpoint)f,4-l l z.s l l return to [ Step C5-2]. l l
C5-3 Maintain'RPV water level eithers lt l l
- / C'6 .1 ----
l o 'If RPV water level was deliberately lowered in [ Step C5-2), between- A n. (Minimum Steam Cooling RPV ll WaterLevel)Qn!-2M d the level to which it was lowered, ll or g g/Di - z.s. 3 o If RPV water level asnothiberatelyloweredin [ Step C5-2], betwe n ' 10,Ain. (top of active fuel)] ll and -f+54 in. (,highelevel trip setpoint)$/*-
++8 r-ssc^ae Feab4 with the following systems:
o Condensate /feedwater l i o CRD l C55 l
.. o RCIC with suction from the sendeneete"- ------
l ters; t: P.t defeating low RPV pressure l $[# 3'- J-l l isolation interlocks :nd high :spprc;;ien" - l p^01 er*ar 101:1 ;setion tr ::f:r 1;;iq if necessary. l i C5-3 Draft Revision 4AD
--___.________.__m_. _
CEI Document 8390-4 Emergency Procedure Guidelines C_G TJ
'b[ HPCI with suction from the ::nd::::t;'-
-6^--- '- '* defeating high suppression pool l #
l ]
')k l ll
, [ water level suction transfer logic if ----
l
@ necessary. M] l LPCK) tith; injection through the heat exchangers as
[ soofas possible; control and maintainfpump flow ] l [ 'less than the RHR Pump NPSH Limit,and Sthe RHR ] Vortex Limit,. ,. ( p, p. d SL) ' ] KHK Fump nrC:! '#"I* '
</ l i................ ,
- i. 1 . ] ,
240 + . 10 psig* ] l [ 1................ l l eppression 1................ . 5 psig !i A [ ool 220 + . ] [ Temp ature l . O psig l [ ( l -] l [ l ] l [ 00 + ] l [ l ] l [ ___+___+ __+___+___ ___ j l [ 0 2 4 6 8 10 ] l
-[ RHR mp Flow ( 000 gpm) ] l
[ ] I
~[ -* Suppression chanb erpressure ). 1
[ ] l [ 8+ ] l [ l ] l [ l R Vortex L it . ] l [- 6+ . ] l [ l . ] [ Suppression . ] [ Pool + . ]. l{ l [ Water Level l...... ] l [ (feet) l ] l [ 2+ ] l [ l ] I [ l ] 1 [ 0 +---+---+---+---+---+--- ] I [ 0 2 4 6 8 10 ) l [ RHR Pump Flow (X1000 gpm) l L ___ C5-4 Draft Revision 4AD
CEI Document 8390-4 Emergency Procedure Guidelines SPV wO If RPV water level was ot deliberately lowered in [ Step l.
% ,yC5-2]j and RPV water 1 el cannot be maintained above: I o l - l' in. (top of ac Q s$."$ m and etweek l 20P in. ( ve fuel)f7 nimum Steammaintain Coolin RPV RPV water Water level A lI Level)y f+!HPin. (high,eveltripsetpoint) . l
++6 reac.4er F. 4s4 -if6 7 If'RPVwaterlevelcannotbebaYtainedabove-!-2^81n. l (Minimum Steam Cooling RPV Water Level) $ EMERGENCY-RPV l.
DEPRESSURIZATION IS REQUIRED: C5-3.1 Terminate and prevent all injection into the RPV except from boron injection systems, CRD, and RCIC ll until RPV pressure is below the Minimum Alternate RPV Flooding Pressure. l l Minimum Alternate RPV' l l Number of open SRVs i Flooding Pressure (psig)l l______________________i__________________________ 4-l Q or more I I 110 ] _ 4 Q l [6 135 ) l l l l l
}M !
1 I)I l .P 4 i /8c4 41a M l l l l l [3 I E fr.B ann u2 l l l [2 l 3 76 0 nn 3o l l d i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __?!12_"_ _ _a_ _' "_ _ l If less than (minimum number of SRVs for which I the Minimum Alternate RPV Flooding Pressure s below the lowest SRV lifting pressure) (SRV a can I be opened, continue in this procedure. W I I i C5-5 Draft Revision 4AE _ _ _ - _ _ _ _ \
(EBI DocumentL 8390-4 Emergency Procedure Guidelines
'C5-3.2 Commence and, irrespective of pump NPSH and vortex l limits,-slowly increase injection into the -- y l RPV_with the following systems to restory l $$l l
l (top of active fuel) 7 andmaintainRPVwaterlevelabovel15).in. . g 9, y l
-o Condensate /feedwater l o CRD o
CST RCIC with suction from theAccrf;n;et.e .:.v..pt l tinLdefeating low RPV pressure isolation interlocks and high :q;reerier c.y . _ l g g .g,
-lecel ="etina tran:fe: 1:;i"-if necessary. l
) HPCI with suction from the eendenstit # N
[ _:t :: t: h,C, defeating high -"ppr w A l- [ g M w;:ter a level suction transfer logic if ) l [ necessary. ] l [o LPC:Pj)with injection .through the heat ] g.3 J exc1 rangers as soon as possible.
- t z 4.7 If RPV water lev annot be restored and ll maintained abov v l'4" in . (top of active fuel) , i!
restore'and maintain RPV water level above A.ll l-20$in. (Minimum Steam Cooling RPV Water' Level)$. ll
-in 2 -
IfRPVwaterlevehannotberestoredand maintained aboveA' 2 0 in. (Minimum steam Cooling ll RPV Water Level)$i'~ commence and, irrespective of ll pump NPSH and vortex limits,' slowly increase I injection into the RPV with the following systems to restore and maintain'RPV water level above 3 l 20R in.-(Minimum Steam Cooling RPV Water Level) ll e uFCo b l
- I
, e.e.ss & $ Ao R A & \
% 24 " Vide :" ThWd% a. 1*
o Fir Sy:t:^ WM ceersM/.4e ##8
-- !; Int::;;nn : tion: aith ;th:: ; nit: ; E _
ECCS keep-full mystir.". }.- 52__ v._ r._ 0 (.M ck L.M & W . 41. c, v trNcb b &WS C5-6 - Draft Revision 4AD
'OEI. Document-8390-4 Emergency Procedure Guidelines
.(
______S__b _. T ll l If RPV water level annot be restored and!l ll l maintained'above-i-ledin. (Minimum' Steam Cooling ~l ll l RPV- Water ~ Level) h enter [ procedure developed l -ll l from Contingency #6]. I- ll 11-5
- l 5V 3 f.6 / / *Q M /Ae4 L C5-3.3 .When water level can be mainta ne above l 006 n. (Minimum Eteam Cooling RPV Water Level) [ 1l return to [ Step C5-3]. l
)
_____________________________________________________________Ql If 'while executing the following -step reactor, power l 1 l
; l' commences'and continues to increase, return to [ Step C5-2]..l }
j Fl A y.7o,r _ iM. ns. R PV j. l , 05-4 Wh n pounds ( t Shutdown Boron Weight)7 of boron ]- hav en injecte restore and maintain RPV water. level ] -l [ between4-{+3M in. o level scram set oint nd ] l [
-f+%gin . jhigh glevel rip setpoint ]' l
[ ++ - v' w e tas - ] l-If RPV wa Y I O N [ ot be restored and aintained ] l [ above e n. (low evel scram setpoint) , mainta n.RPV ] l [ water level above -I 104 in. (top of active fuel) . ]. .I [
' - 8 M '8 g _ sci,.3 ] l
[ If RPV. water level cannot be maintained above-i-10,Ain. ] l [ (top of active fuel)$f EMERGENCY RPV DEPRESSURIZATION IS -l
' REQUIRED; return to [ Step C5-3.1]. J]/ l I
'C5-5 Whe nlp:: + ft: 00:1drun t: ;;10 ehut0;wr. :;nditi:n:N l s entered from [ procedure developed from the RPV Control !
Guideline) at [ Step RC/P-5], proceed to cold shutdown in l
./ accordance with -lprer:dar: f:: -vidum t.e celd ; hate::: t o__
/l : ditiaa=]
?
l
~
Proce k 2.l. 5
}
" (.'odroflad b doa/W % owg C5-7 Draft Revision 4AE
/4/PS
- a: me r: t 2300 4
/=V&&cdi W<AdddmEh E :rgency Precee re cuid:line <
SEC,7/dg /E CONTINGENCY f 6 --~ l PRIMARY CONTAINMENT FLOODING l l l l i l If while executing the following steps:_____________________________________________ FI N E- l ll l 4e% I il lo Primary containment water level nd a ppre 10n th::b 34 ll l' pressure cannot be maintained b ow the Maximum Primary l l l Containment Water Level Limih, then irrespective of l l l whether adequate core cooling is assured terminate l l l injection into the RPV from sources external to the l l l primary containment until primary containment water i l i level and smppre :ica ch::b:$ pressure can be maintained l l l l below the[+ *c Maximum 4 Primary Containment Water Level Limit. lmll l l Maximum Primary l l l containment l l l Water Level Limit l l 1......... fl l l l . l l l Primary l l l l Containment . l l l Water Level . l l l (feet) I . I l l l . l I I l . l l l l . l 1 l +____________________ _ l l l l l Suppression Chamber Pressure (psig l l, l
! ~i i lo RPV water level can be restored and maintained above l ll l -tzhh l ly?" in. (top of active fuel) # enter [ procedure l Il .
from the RPV Control Guideline] at [ Step l ll I developed l RC/L). l ll _______________________________________________________________ l
- c5-1 Ir 4 + 4 -t e er:=O - !@
l l i evision
/ 2-#
0]I Document 8390-4 Emergency Procedure Guidelines C6- Operate the following systems: l l \
)
c EPCS-vith suction fre; th; 00ndenrate eterage +=n' A l t- z then availableT<-- l o ; operate one with suction from the,C G 7- l condene=':e eterage *=nWf^r fire syster]Ponly when the 1 other d 5S is operating with suction from the,-terw . I
-;;ppreerinn nnn1 o l 1
o Condensate /feedwater l 1
-o CRD l cGT RCIC with suction from the^ce"6eaea*= c&nrage tan A l
o I only, defeating low RPV pressure isolation interlocks ll
=ad Mgh suppr===ien peel veter le"el suction tr nefest 4e vik if necessary. ll a y I
l o LPCI'with suction from sources external to the primary l containment O nly.]'i' reeible.lC l 1 o S.S kl scessw ? J ./o A H A e l _!:0 PPR ser" ice :ter cre : tic W l Ci +f W4 seesrNeA ./s ANA l [o Fire yrt:' #4 @phd 4 gg N l 1
-!c Intercenneewivu= w1 Ll4 v iim. Unit: N l ECCSkeep-{ullcyster? - --}--E-I v
f e n+har nri - ma -ru centai r:nt fill cyst;;; j "% l j l
/ 1 O (.ewh &c c rp N o 6cei -ReA % c sr.4.m & Pc Z 4% ,
1 I cW L l . l l i l I l C6-2 Draft Revision 4AE 1
i CEI Document 8390-4 Emergency Procedure Guidelines nF+ C6-When primary. containment water level reachesA420 ft. 2 in5L l (elsvation of ih&' bottom of the lowest recirculation l i piping)ff'then irrespective'of.the offsite radioactivity I release rate vent the RPV, defeating isolation igterlocks l ! if necessary, until RPV water level reaches-l-lo gin. (top ll of active fuel)d(gith one or more of the followingT -ito.7 l l 1
- c fi ced ve .t ,alves$_. l l
o MSIVs l I o Main steam line drains l l o- HPCI steam line l I o .RCIC steam line l Oi-s I
-c Ic tub: cide ve..L. E- l
' e PJm# l l
) C6-3 Draft Revision 4AE
OEI Document 8390-4 Emergency Procedure Guidelines (o ? . T F 5 C6- When primary containment water level reaches ^' ' ' = 4 ae ll (ele /:tien ^*-top of active fuel) # maintain 493 ft. primary 5 ! # - ' ' ^-ll^ '" l I containment water level between top of active fuel) % nd the Maximum Primary
- Containment ll Water Level Limitawith the following systems taking suction ll fromsourcesextegaltotheprimarycontainmentonlywhen ll required ( Fi 7--}
l
- ., ,e o & ll ll o [eedwatercondensate ll 1I o CRD 1l 1I o LPCI ll l1
- u. . a - m, o i b [$}A)~N[$f f NW h $ ll
= [ """ eetvive weter
}& Il o
C-lH M 'r*"h5:"ti-E*'L Fire syst^r WA co suh4 2 4 4A @ Il ll l1
-! : Inter :nnectica rith other unit: !A II ECCS heep ' full e= te=r "
M Il 11
-!e other pri- ry centain ent fill ayeten: )% i1 0 (ohn s& G c ce .r/ Nik k G~CC C Cor - H i h feek Q g C C Y b fl0 C-[ j
///thiNt 86W bAC-4 1
i C6-4 Draft Revision 4AD l
l APPENDIX B DIFFERENCES BETWEEN GENERIC EPGs AND PSTGs
)
l )
1 PSTG APPENDIX B TABLE OF CONTENTS Title Page B- , 1 EPG/PSTG General Modifications . . .. . . . . . . . . . . . . 2 PSTG Section 1 - Introduction'. . . . . . . . . . . . . . 4 PSTG Section 2 - Operator Precautions . . . . . . . . . . 7 PSTG Section 3 - RPV Control Guideline . . .. . . . . . 8 PSTG Section 4 - Primary Containment Control Guideline . . . .. . . . . . . . . .. . 12 PSTG Section 5 . Secondary Containment Control
. Guideline . . .. . . . . . . . . . . . 17 1
-PSTG Section 6 - Radioactivity Release Control Guideline . . . . . . . . . . . . . . . 19:
PSTG Section Contingency 41' (Alternate Level Control) . . . . . . . 20 PSTG Section. 8 - Contingency #2 (Emergency RPV Depressurization) . . . . 22 PSTG Section 9 - Contingency 13 (Steam Cooling) . . . . . 24 ) P!*G Section 10 - Contingency #4 (RPV Flooding) . . . . . 25 3
,JPG Section 11 - Contingency 45 (Level / Power Control) . . 27 !
PSTG Section 12 - Contingency #6 (Primary Containment Flooding) . . . . . 29 I i Page B1 of 31 Revision 3 ; - - - = _ _ - _ _
EPG/PSTG GENERAL MODIFICATIONS This section contains general modifications which appeared frequently during the Emergency Procedure Guideline (EPG) to Plant-Specific Technical Guideline (PSTG) development process. Since these modifications are minor and not of a technical nature, they have been included in this section rather than referenced at every location in which they occur.
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CRANGE: All figures have been relocated. i BASIS:- Placement of miniature figures within steps whenever they are referenced causes spacial constraints and is not necessary. Removing the figures from the main body of the PSTGs and grouping them as an attachment at the back of the document accomplishes three things: 1) the figures are grouped together allowing the user to remove and consult them while reviewing the PSTGs; and, 2) the figures can be of much larger scale, thus allowing for more precise interpolation; and, 3) the bulk of the document can be reduced.
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( ) I CHANGE: The word " elevation" has been deleted as a descriptive reference in steps identifying suppression pool (torus) and drywell/ primary containment water level instrument values. BASIS: The sample plant used to calculate the numerical values illustrated in the EPGs has the same reference zero point for plant elevation, suppression pool (torus), and ] drywell water level instrumentation. Since Pilgrim's l plant elevation is not the same as the water level d instrument zero reference, inclusion of the word L " elevation" is not technically correct and has therefore been deleted.
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Page B2 of 31 Revision 3 l
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CHANGE: The words " suppression chamber" and " suppression pool" have been replaced by the word " torus." BASIS: This.is the correct plant-specific terminology. Note: The only. exceptions are when plant-specific terminology '(i.e. , suppression chamber sprays and suppression pool cooling) dictates using the original EPG wording.
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l CHANGE: Portions of qualifiers for monitored plant parameters have been modified. BASIS: This is to provide further clarification for monitored plant parameters and consistency among these qualifiers.
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) Page B3 of 31 Revision 3 _ _ _ _ _ _ _ - - - - - _ _ _ _ _ _ _ _ _ _ . _ __ _ _ _ ._. _ _ l
PSTG SECTION 1 - INTRODUCTION
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EPG Page I-1 CHANGE: A majority -of the first three paragraphs have been deleted from the Introduction and replaced with i different wording. BASIS: The intent and entry conditions of the RPV Control and Primary Containment Control Guidelines have been deleted here because they appear in the respective individual guidelines.
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EPG Page I-1 CHANGE: 1. The phrases "and containment" and "and Mark III containment atmosphere average temperature" have been deleted from the latter part of the third paragraph.
- 2. Also in the latter part of the third paragraph, the procedural reference for determining bulk suppression pool temperature has been modified.
BASIS: 1. These phrases are applicable to Mark III contain-ments only; Pilgrim has a Mark I containment. Some conjunctions and punctuation changes have been incorporated for clarity.
- 2. Separating drywell and suppression pool (torus) temperature references is necessary since drywell bulk average temperature is determined by procedure and suppression pool (torus) temperature is indicated directly.
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\ l l l l i Page B4 of 31 Revision 3
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EPG Page I-1 CHANGE: The fourth and fifth paragraphs have been deleted from the Introduction and replaced with other wording. BASIS: The intent and entry conditions of Secondary Containment Control and Radioactivity Release Control Guidelines have been deleted here because they appear in.the respective individual guidelines.
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-EPG Page I-1
' CHANGE: .The.following sentence has been added to-the
Introduction:
"Unless specified otherwise, torus water level values are referenced to the instrument zero of.the wide range torus water level instrument and primary containment water level values are referenced to plant elevation."
BASIS: Placement of this sentence in the Introduction alleviates the need to insert similar wording in numerous locations where. torus and primary containment water levels are referenced later in the PSTGs.
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EPG Page I-2 CHANGE: The last paragraph has been deleted. BASIS: This paragraph is an instruction outlining the methodology to follow when converting _the EPGs from the generic form to plant-specific technical guidelines. In the context of the PSTGs, this instruction is not required. L
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- Page B5 of 31 Revision 3 1
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4 EPG Pages I-3 and'I-4 CHANGE: In numerous locations " emergency-procedure guidelines" or similar wording has been-replaced by the abbreviation "PSTG."
' BASIS:~ .This change is required to achieve consistency within the context of the document.
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EPG Page.I-3 CHANGE: The second sentence of the last paragraph has been slightly modified .(i.e., the word "either" has been deleted and the word "when" has been added). BASIS: This -correct's an EPG grammatical error.
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EPG Pages I-5 and I-6
- CRANGE: Table I-has been modified.
BASIS: Applicable plant-specific abbreviations have been incorporated and.non-applicable generic abbreviations have been deleted. e
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1 PSTG SECTION 2 - OPERATOP. PRECAUTIONS l
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(] )' EPG Page I-7 l CHANGE: The first paragraph of the Operator Precaution Section has been deleted. BASIS: An introduction to the information presented in this section and an explanation of how a caution is l identified are already included in Section I of the PSTGs, and therefore need not be repeated. l
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EPG Page I-9 i CHANGE: Caution 2 has been deleted. a BASIS: Pilgrim has no heated reference leg RPV water level instruments; therefore, the information presented in this caution does not apply.
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EPG Page I-9 CHANGE: Caution 5 has been deleted. BASIS: Pilgrim has no HPCS; therefore, the information presented in this caution does not apply.
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l l EPG Page I-9 CHANGE: Caution #6 has been deleted. BASIS: The information presented in this caution has been { incorporated in applicable steps (i.e., RC/P overrides d and EPG Step C2-1.3).
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Page B7 of 31 Revision 3
l PSTG SECTION '3 - RPV CONTROL GUIDELINE
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EPG Page RC-1 CHANGE: In the Purpose section, the conditions that describe , cold shutdown have been changed. BASIS: The plant-specific definition of cold shutdown for Pilgrim has no low temperature limit, and the upper bound includes 212 F.
================================================================= i EPG Page RC-3 CHANGE: The override statement on EPG Page RC-3 has been incorporated in the same box with the override statement thac is located on EPG Page RC-2.
BASIS: Although spacial limitations do not allow this override statement to fit on the previous page of the EPGs, it applies to the same step as the override statement on EPG Page RC-2. Locating the Maximum. Primary Containment Water Level Limit figure at the back of the PSTGs in an attachment and referencing the respective figure number alleviates the need to separate this override statement from the previous one.
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EPG Page RC-3 CHANGE: In Step RC/L-2, the phrase "and high suppression pool water level suction transfer logic" has been deleted from bulleted item addressing RCIC. BASIS: The RCIC system at Pilgrim has no high suppression pool water level suction transfer logic; therefore, this portion of the statement does not apply.
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Page B8 of 31 Revision 3
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.EPG'Page RC-4 i'
, i' CHANGE:- LIn' Step _'RC/L-2, information regarding HPCS has been-deleted.
BASIS: ' Pilgrim has no HPCS; therefore, this information does not apply.
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'EPG Page RC CHANGE: In Step RC/L-2, a comma.has been inserted between the words "LPCI" and "with."
BASIS: 'This' change reflects.the intent that LPCI'be permitted whether or not injection'through the heat exchangers can. i be achieved.
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EPG Pages RC-8 and RC-11 CHANGE: In Step RC/P-1, the words." initiate IC and" have been deleted.- In: Step RC/P-2, the first item in the list (i.e., IC) has been deleted. BASIS: Pilgrim has no isolation condenser ~(IC); therefore, instructions regarding the use of: this component do not apply.
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i EPG Page RC-10 l CHANGE: The words " pneumatic system and" have been deleted. BASIS: At Pilgrim the pneumatic supply to the MSIVs does not automatically isolate on a low RPV water level signal; E therefore, any direction to bypass such an interlock is l unnecessary. [' -================================================================= I-Page B9 of 31 Revision 3
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EPG Page RC-11 (}h () 1 1 CHANGE: In Step RC/P-2, the following phrase has been deleted: j "o [Other steam driven equipment)" q
. BASIS:' Pilgrim has no steam driven equipment other than that ;
already listed.
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9 EPG Pages RC-11 and RC-16 I CHANGE: In Steps RC/P-2 and RC/Q-6.1, the phrase identifying the l RWCU regenerative heat exchangers has been deleted. { BASIS: At Pilgrim the RWCU system is not configured _with a bypass path around,the RWCU regenerative heat exchangers; therefore, the direction to bypass the heat exchangers does not apply.
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h EPG Page RC-12 CHANGE: In the last paragraph of Step RC/P-4, the abbreviation "RPV" has been inserted. BASIS: "RPV" has been inserted to clarify the term "cooldown."
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EPG Page RC-14 CHANGE: Step RC/Q-5 has been deleted. BASIS: This step appears in either of two locations (Steps RC/O-2 and RC/Q-5) in'the RPV power control section of the guideline depending on whether or not ARI initiation causes a trip of the reactor recirculation pumps. ARI initiation does not cause a recirculation pump trip at Pilgrim; therefore~, placement of this instruction at
. Step RC/Q-2 is correct.
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EPG Page RC-16 CHANGE: In the override statement, the words " confirm automatic trip of or" have.been deleted and the qualifier for the tank water level value has been modified. BASIS: The SBLC pumps at Pilgrim do not have an automatic trip;;
.therefore, statements referring to an automatic pump trip do not apply. !
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h EPG Page RC-17 CHANGE: In' Step RC/Q-7.2, the words "RSCS and" have been deleted. BASIS: Pilgrim has no RSCS; therefore, the direction to bypass interlocks associated with RSCS does not apply. ,
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I l [ Page B11 of 31 Revision 3 L
PSTG SECTION 4 - PRIMARY CONTAINMENT CONTROL GUIDELINE .
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( ) EPG Pages PC-1 and PC-6 CRANGE: The Containment Temperature Entry Condition and all CN/T steps have been deleted. BASIS: The containment temperature entry condition and operator actions only apply to those plants with Mark III containments.
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i EPG Page PC-4 CBANGE: In Step DW/T-1, the phrase " defeating isolation interlocks if necessary" has been deleted. BASIS: The drywell coolers at Pilgrim have no isolation interlocks; therefore, instructions to defeat such interlocks do not apply.
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EPG Pages PC-4 and PC-5 CRANGE: In Steps DW/T-2 and DW/T-3, the word "is" has been inserted between " ADS" and " qualified." BASIS: This corrects an EPG typographical error. !
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EPG Page PC-7
.CBANGE: In Step PC/P-1, the following bracketed terms have been deleted:
" Pressure Suppression Pressure"
" Mark III Containment Spray Initiation Pressure Limit" BASIS: Within the context of this step, each of these terms are applicable only.to plants with a Mark III containment; Pilgrim has a Mark I containment.
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b EPG Page PC-11 CHANGE: Step PC/P-5 has been deleted. BASIS: Step PC/P-5 is only applicable to plants where using a specific-pathway for venting the primary containment might threaten continued adequate core cooling. Pilgrim has no such vent path; therefore, the instructions of this step do not apply.
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EPG Pages PC-12 and PC-14 1 CHANGE: In Steps SP/L-1 and SP/L-3, the references to SPMS have been deleted. I BASIS: Pilgrim has no SPMS; therefore, instructions regarding l operation of this system do not apply. ;
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Page B13 of 31 Revision 3
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Q===========================================================n== tac. x :n EPG Page'PC-13 CHANGE: The override statement has been deleted. 7 v ;
' BASIS: Concurrent execution'of Steps SP/L-2.1 and'SP/L-2.2 is only-intended for plants with a HPCI exhaust elevation above the lowest torus water level of the Heat Capacity Level Limit (downcommer opening elevation) . At Pilgrim the HPCI exhaust elevation is not above the lowest torus water'1evel of the HCLL; therefore, instructions i regarding concurrent execution do not' apply. ' i i
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EPG Page PC-17 CHANGE: .The phrase "in accordance with (sampling procedure]" has been deleted. BASIS: A plant-specific procedure for. sampling for hydrogen and oxygen does not currently exist. The instruction to
" sample" the.drywell and torus is deemed to provide (
adequate direction. a
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( f) EPG Page PC-17 CHAN'GE: In the override statement, the ph' rase " secure and ,
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prevent operation of hydrogen mixing systems and 1 recombiners and" has been deleted. j l BASIS: Pilgrim has no hydrogen mixing systems or recombiners; i therefore, instructions regarding operation of these I systems do not apply. ,
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EPG Page PC-10 (4[0) CHANGE: Step PC/H-1.1 has been reconfigure. BASIS: The additional wording correctly reflects instructions contained in the referenced procedure (i.e., Procedure 5.7.3.2, "Drywell Atmospheric Sampling , Transport, and Analysen Under Emergency Conditiono').
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EPG Page PC-18 CHANGE: The override statement directing concurrent execution i of Steps PC/H-2 and PC/H-3 has been deleted. BASIS: Steps PC/H-2 and PC/H-3 aret'not applicable at Pilgrim (refer to change 4-9 and 4-12); therefore, this override statement is not required.
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( ) EPG Pages PC-19 and PC-20 ;. CHANGE: Steps PC/H-2 and PC/H-3 have been deleted. BASIS: See change 4-9.
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(f f) EPG Page PC-21 > CHANGE: In Step PC/H-4 (PSTG Step PC/H-2), the following phrase has been deleted: l "secu re hydrogen mixing rcy;tems , and" BASIS: See change 4-9. 1 ( m u = = = = =r:en = = = = = = = = = = = = = = = = = = = = = = =2,= = =.= = = = = = u = = = = = = = = = = = = = = = = = = = = = = l 1 a i i Page B15 of 31 Revision 3 l l l u_________ _ .
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mammmmmmazummmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmas mmmmmmmmmmmmmansamm _EPG Page PC-22 CHANGE: In Step PC/H-4.3 (PSTG Step PC/H-2.3), the.following phrase has been added:
"(air or nitrogen)"
BASIS: Since-no drywell purge gas is specified,-this parenthetical phrase has been~added to avoid possible confusion.
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1 Page B16 of 3I Revision 3
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" ' .'PSTG SECTION ti -3ECO!DARY CONTAINMENT CONTROL GUIDELINE
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EPG Pati,ps'$b-1 and SC-5 >
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t' y y . . CHANGE:. The Floor Drain Sump Water Level- Entry Condition - A and- Step SC/L-1 terminology has been changed to specify
" reactor bul.I.$1n; l g," %
.g , y At Pilgrim alliteactor building floor drains are routed-.
' ~)EASIS:
A' to a single sump; therefore', associate 6 wording reflects
- this configu' ration.
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EPG ages'SC-2ankSC-3 CHMGEs The phrase "segondary containment' HVAC" has been replaced with " refuel floor" BASIS: hhe 4 only ventilation exhaustiradiation monitbr' with an isolation function foq(the secondary containment at _ l Pilgrim is from the refuel T1oor; therefore, associated wording reflect:; !this c' configuration. 1 x
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- g p EPG Page SC-3' 'j i
CHANGE: The following phrase has~been adued to Step SC/T-1:
" Control secondary containment area temperatures below maximum normal 1 opezating values (Table-5-1) using"
, g ? ..
BASIS: Step SC/T-1 in.its.,EPG form does not direct operation f within:any specific bounds. The revised' step specifies
'j ', appropriate values (i.e., normal operating) below which s the operator should control secondary containment temper-
- j. .I ature. Thid approach is also consistent with the other a
=J two parallel steps r$(SC/R and SC/Wfof this guideline. I j
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'EPG Pages'SC-6 thru SC-9
. CHANGE: The' title for Table 1, " Operating Values of Secondary Containment Parameters" has been altered.
BASIS: To enable more precise reference.to,the secondary containment parameters, the EPG table has been modified and divided'into 4. separate tables as follows: Table.5-1: Secondary Containment Area Maximum Temperatures . . Table 5-2: Secondary _ Containment Cooler Maximum Temperatures Table 5-3: Secondary Containment Area Maximum Radiation Levels Table 5-4: Secondary Containment Sump / Area Maximum Water Levels
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i 1 l f ; i [ Page B18 of 31 Revision 3
l PSTG SECTION 6 - RADIOACTIVITY RELEASE CONTROL GUIDELINE
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EPG Page RR-1 CHANGE: In the override statement, the following phrases have been deleted:
- a. "Ior isolated due to high radiation)"
- b. " defeating isolation interlocks if necessary."
BASIS: At Pilgrim, the turbine building H&V system does not automatically isolate on a high radiation signal; therefore, any reference to such an isolation is unnecessary.
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Page B19 of 31 Revision 3
PSTG SECTION 7 - CONTINGENCY ll (ALTERNATE LEVEL CONTROL)
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EPG Page'Cl-2 CHANGE: The override statement has been incorporated with the override statement on EPG Page Cl-1. BASIS: Although spacial limitations do not allow this override statement to fit on the previous page of the EPGs, it applies to the same steps as the override statement on EPG Page C1. Locating the Maximum Primary Containment Water Level. Limit figure at the back of the PSTGs in an attachment and referencing the respective figure number alleviates the need to physically separate this override statement.
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EPG Pages Cl-2 and Cl-3 CHANGE: Step Cl-1 has been deleted. In Step Cl-2 (PSTG Step Cl-1), the second injection subsystem (HPCS) and the fifth injection subsystem (LPCI-C) have been deleted. BASIS: Pilgrim does not have any of the above components / subsystems (i .e . , IC , HPCS , and. LPCI-C) ; therefore, instructions regarding use or operation of these components / subsystems do not apply.
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EPG Page Cl-3 CHANGE: In Step Cl-2 (PSTG Step Cl-1) , a comma nas been placed between "LPCI-A (B)" and "with." BASIS: This change reflects the intent that LPCI-A and LPCI-B be permitted whether or not injection through the heat exchangers can be achieved.
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Page B20 of 31 Revision 3
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EPG Page Cl-4
. CHANGE:-.In Step Cl-4.2 (PSTG Step C1-3.2), the. word "all" has been replaced with "as many", and the words "as possible" have been inserted after " subsystems."
BASIS: Alternate injection subsystem configurations at Pilgrim
.do not allow "all" subsystems to be aligned to the RPV at the same. time;'therefore, the wording "as many ... as possible" reflects the correct configuration.
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Page B21 of 31 Revision 3 q i
PSTG SBCTION 8 - CONTINGENCY 8 2 (EMERGENCY RPV DEPRESSURIEATION) 1:
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EPG Page C2-1 CHANGE: Step C2-1.2'has been deleted. BASIS: Pilgrim does not have an IC; therefore, instructions regarding'use of this component do not apply.
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EPG Page C2-1 CHANGE: In Step C2-1.3 (PSTG Step C2-1.2), the following instruction has been deleted:
"o If any ADS valve cannot be opened, open other SRVs until [7 (number of SRVs dedicated to ADS)] valves are open."
and the format of the step has been reconfigure accordingly. BASIS: At Pilgrim, the number of SRVs operated by the ADS' logic is the same as the total number of SRVs; therefore, the instruction to open additional SRVs does not apply.
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EPG Page C2-2 CHANGE: In Step C2-1.4 (PSTG Step C2-1.3), " Main condenser" has been changed to " Main turbine bypass valves." BASIS:- This step directs RPV depressurization through the use of different paths. Although the main condenser is a heat sink for RPV depressurization, the actual path is
.via the main turbine bypass valves; terminology has been modified accordingly.
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Page B22 of 31 Revision 3
l J l EPG'Page C2-2 CHANGE: In Step C2-1.4-(PSTG Step C2-1.3), the following depressurization paths.have been deleted:
"o. RHR-(steam condensing mode)"
"o [Other steam driven equipment]"
"o IC' tube side vent"
~
BASIS: Pilgrim does.not have an IC and does not use the steam condensing mode-of.RHR. Additionally, Pilgrim has no I steam driven. equipment other than that already'11sted. Therefore, instructions regarding use of these depressurization paths do not apply.
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i Page B23 of 31 Revision 3
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*e PSTG SECTION 9:- CONTINGENCY #3 (STEAM COOLING) -
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EPG Page C3-1 CHANGE: In Step _C3-1, instructions pertaining to IC have been deleted. BASIS: Pilgrim has no IC;.therefore, instructions regarding use of this component do not apply.
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l l l l 4 I Page B24 of 31 Revision 3
PSTG SECTION 10 - CONTINGENCY $4 (RPV FLOODING)
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EPG Pages C4-3 and C4-5 CHANGE: In Steps C4-1.2 and C4-2, "IC" and "RHR steam condensing" have been deleted. BASIS: Pilgrim does not have an IC and does not use the steam condensing mode of RHR; therefore, instructions regarding use of these components / systems do not apply.
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a Pages C4-3 and C4-5 CHANGE: In Steps C4-1.2 and C4-2, " steam line" has been inserted between "RCIC" and " isolation valves." BASIS: The " steam line" terminology has been inserted to clarify the fact that no RPV injection flowpath valves need be isolated, only steam.
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Pages C4-4 and C4-6 CHANGE: In Steps C4-1.3 and C4-3.1, the bulleted item pertaining to the feedwater pumps has been changed as follows:
- a. " Motor driven" has been deleted.
- b. The phrase " isolation interlocks" has been replaced with " pump trip logic."
BASIS: All Pilgrim feedwater pumps are motor driven; therefore, reference to such is not necessary. The terminology
" pump trip logic" correctly reflects the applicability i to motor driven feedwater pumps (vs. isolation j interlocks for steam driven feedwater pumps).
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) Page B25 of 31 Revision 3
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EPG Pages C4-4 and C4-6' CHANGE: In Steps C4-l.3 and C4-3.1, a comma has been inserted between."LPCI" and "with." BASIS: This change reflects the intent that LPCI be permitted whether or~not injection through the heat exchangers can be achieved.
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h EPG Pages C4-4 and C4-6 ECHANGE: .In' Steps C4-1.3 and.C4-3.1, HPCS has been deleted from the list.of systems. BASIS: ' Pilgrim has no HPCS; therefore, instructions regarding operation of this system do not apply.
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EPG Pages C4-5 and C4-6 CHANGE: In the override statements, the phrase " PRIMARY CONTAINMENT FLOODING IS REQUIRED" has been inserted. BASIS:' .This phrase has been inserted to facilitate exiting the
-' Suppression Pool Water Level Control Guideline from the override statement on EPG Page PC-12.
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e L Page B26 of 31 Revision 3
PSTG- SECTION 11 - CONTINGENCY #5 (LEVEL / POWER CONTROL)
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EPG Page C5-2 CHANGE: In Step C5-2, references to " pneumatic system" or
" pneumatic supply" have been deleted. l I
BASIS: The Pilgrim pneumatic supply to the MSIVs does not ' automatically isolate on a low RPV water level signal; therefore, any direction to bypass such an interlock or restore supply is unnecessary.
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h EPG Pages C5-3 and C5-6 CHANGE: In Steps C5-3 and C5-3.2, the phrase "and high suppression pool water level suction transfer logic" has been deleted from the. bulleted item addressing RCIC. BASIS: The RCIC system at Pilgrim has no high suppression pool water level suction transfer logic; therefore, this portion of the statement does not apply.
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EPG Pages C5-4 and C5-6 CHANGE: In Steps C5-3 and C5-3.2, a comma has been inserted between "LPCI" and "with." BASIS: This change reflects the intent that LPCI be permitted
. whether or not injection through the heat exchangers can be achieved.
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4 Page B27 of 31 Revision 3
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EPG Page C5-6 CHANGE: In Step C5-3.2, HPCS has been deleted from the list of injectic systems. BASIS: . Pilgrim has no HPCS; .therefore, instructions regarding operation of this system do not apply.
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EPG Page C5-7 CHANGE: In the override statement, the phrase " PRIMARY CONTAINMENT FLOODING IS REQUIRED" has been inserted. BASIS: This phrase has been inserted to facilitate exiting the Suppression Pool Water Level Control Guideline from the override statement on EPG Page PC-12.
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EPG Page C5-7 CHANGE: In Step'C5-4, the phrase "into the RPV" has been j inserted between " injected," and " restore." BASIS: This phrase has been added to alleviate any doubt that the boron is injected into the RPV and not any other location.
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Page B28 of 31 Revision 3 j
PSTG SECTION 12 - CONTINGENCY 96 (PRIMARY CONTAINMENT . FLOODING)
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EPG Page'C6-1 .. CHANGE:- Step C6-1 has been deleted. EBASIS: Pilg rim 'has no SPMS; therefore, instructions regarding
-operation.of'this system do not apply. =================================================================
EPG Pages C6-2 and C6-4 " CHANGE:. In Steps C6-2 and C6-4 (PSTG Steps C6-1 and C6-3), HPCS has been deleted from the list of systems. BASIS: Pilgrim has no HPCS; therefore,' instructions regarding operation of this system do not apply.
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EPG Page C6-2 ' CHANGE: In Step C6-2'(PSTG Step C6-1), the phrase "and high suppression pool water level suction transfer logic" has been deleted from the bulleted item addressing RCIC. l BASIS: The RCIC system at Pilgrim has no high suppression pool water level suction transfer logic; therefore, this portion of the statement.does not apply.
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l l Page B29 of 31 Revision 3
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EPG Page C6-2 CHANGE: In Step C6-2 (PSTG Step C6-1), .the phrase "if possible" has been deleted from the bulleted item addressing LPCI. BASIS: The phrase "if possible" only applies to plants where LPCI injects inside the core shroud. At Pilgrim, LPCI injects outside the shroud; therefore, the word "only" applies to the use of LPCI rather than "if possible."
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EPG Page C6-3 CHANGE: In Step C6-3 (PSTG Step C6-2), the following vent paths have been deleted:
"o Flood vent valves" "o IC tube side vents" "o RHR" BASIS: Pilgrim has no flood vent valves or IC, and RHR is not a viable vent path; therefore, any instructions regarding use of these vent paths do not apply.
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l ( EPG Page C6-4 CHANGE: In Step C6-4 (PSTG Step C6-3), the wording "feedwater/ condensate" has been transposed. BASIS: -Using " condensate /feedwater" rather than "feedwater/ condensate" is consistent with listings found elsewhere in the EPGs/PSTGs.
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EPG Page C6-4 CHANGE: In Step C6-4 (PSTG Step C6-3), Head Spray has been deleted from~the list of systems. BASIS: At Pilgrim, the Head Spray system is integral with the;flowpath of.the listed f111' systems'crosstied to RHR (i.e., SSW, City Water, and Fire Water);-therefore, it is not appropriate to list it separately.
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b I Page B31 of 31 Revision 3}}