ML24192A138

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Energy Northwest, Emergency Preparedness Procedures
ML24192A138
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Issue date: 06/27/2024
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Document Control Desk, Office of Nuclear Reactor Regulation
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DISTRIBUTION - VOLUME 13 - EMERGENCY PREPAREDNESS PROCEDURES Page 3 of 3 Distribution Date: 06/27/24 Filed By: _______________ Prepared by:

Procedure Number Revision Procedure Number Revision Procedure Number ' Revision 13.1.1 050 I

TO: ENERGY NORTHWEST EXTERNAL CONTROLLED COPY PROCEDURE HOLDERS The following documents have been revised and are to be inserted into your controlled copy manual and the superseded revisions removed and destroyed. No receipt acknowledgement is required for the listed document(s).

Should you have questions on this distribution please contact Alan Page, Records, and Information at (509)377-8595 or atpage@energy northwest.com.

I I EXTERNAL DISTRIBUTION I Coov# Location,! Procedures 26 ReQion IV - US Nuclear Regulatory Commission All 52 State of Washington, Military Department All 55 Federal Emergency Management Aoencv (FEMA) All II 57 Benton County - Department of Emergency Management All

~ -

87 Document Control Desk NRC - All f " --

142 Hanford EOC/SMT All 164 Oregon State Department of Enerov All 223 Franklin County Emergency Management All "

224 WashinQton State Department of Health - Office of Radiation Protection All

/)i45

///lrK

& PPM 13.1.1 and is printed in color, single sided, on 11 " x 17" paper, folded, 3-hole punched, stapled on top and distributed by Document Control. All ERO Positional-Specific Binder procedures are stapled.

% Contact Security - All Security Procedures go to the sec fo r signature NOTE: Distribution of the PPM 13. 1. 1 wall flow charts are controlled by PPM 13.1. 1 A and distribution is performed by EP. Updated 01/18/2024 GENERAL EMERGENCY I SITE AREA EMERr CY I ALERT I UNUSUAL EVENT

Prok,t,ged 1o.. of d o tfaile W'i d II onske AC powf/1' to eme rgency LOH of d otr.ite I nd Iii o n tite AC poWl!t lo emergency b lAM LoH ol II b u l one AC po Wl!I' 1ource to emergency b USff Lon of d o tfl.lte AC po - i::ap bitity to emergency b-

,.,... lo, 15miM1110 1 lon ger for 15mlnute.orlonger fo115minu1111o r long er

MG 1. 1 I 1 I 2 I 3 I I I i MS1. 1 I 1 I 2 I 3 I I I i MA1.1 I 1 i 2 I 3 I I I i MU1.1 I 1 I 2 I 3 I I I i Loss of fill offsite AND fill o n site AC powe r ca pa b ility to Loss o f fill offsite and fill onsite AC po wer ca pabi lity to AC powe r capa bility, Table 2, to em ergency buses S M-7 Loss of fill o ffsite AC powe r capability, T a ble 2, to emergency emer gency buses SM-7 and S M-8 emergen cy b uses S M-7 an d SM-8 for GE 15 min. (Note 1) a n d SM-8 reduce d to a single power source for GE 15 m in. b uses SM-7 an d S M-8 for GE 15 m in. { Nole 1)

AND EITHER : (Note 1)

Resto rat ion of emergency bus SM-7 or SM-8 AND tional single power source fa ilure 'Nill resuh in a 1 in LT 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> isnfillikely (Note 1) t£r:J._ add i LOH o f OR loss of ill AC power to SAFETY SYSTE M S Emetg enc ) RPV level c a nn o t be restored and ma intained Tab le 2 AC Po w er Sou rce s AC Pow er GT - 166in-. -

LOH of !I em ergen cy AC and vil*I DC power SOtJftH fo1 Offslte 15mlnule1orlonger Startup TransfOfmer TR-S

MG1.2 I 1 I 2 I 3 i I I i Backup Transformer TR-B Loss o f.ill offsite AND ~ o n site AC power ca pa b ility lo Backfeed 500 KV power through a lready em ergen cy b uses S M-7 and SM-8 fo r GE 15 m in. (Note 1) Main T ra nsfo rmers (if gned in modes 4, 5, def on ly)

I-AND a li Ind icated vottage is LT 108 voe on b21b. 125 voe buses loH of l!I vital DC powe 1 for 15 mil'IUl:es Of loll{ler On slte 2 DP-S1-1 and DP-51 -2 tor GE 15 min. (Note 1) DG1 MS2.1 I 1 I 2 I 3 I I I i

Lo ss of... DG2 *-LT 108 voe on~ 125 voe buses Main Ge n erato r via TR-N1/N2 VltalDC Indicated vohage is Power DP-S1-1 a n d DP-S1 -2 lor GE 15 min. (Nole 1)

UNPLA NN ED 1011 of Contro l Roo m lndic1tioo1 lor 15 m in utes or U NPLANNED loHofControl Room lndie.tion, for 15mITTutesor longerwilhaalgnifleant!Tan sientinprogreH lon ger

MA J.1 I 1 I 2 I 3 I I I i MUJ.1 I 1 I 2 I 3 I I I i 3 An UNPLANNED event results in the inabi lity to monitor one An UNPLANNEq event results in the inability to m onitor o r m o re Ta b le 10 pa rameters from within the Cont rol R oo m o n e or more T abfe 10 pa ra m eters from within the Contro l LoHof....... for GE 15 m in. (N ote 1) Room for GE 15 min. (Note 1)

Con trol AND Room /j[Jy_ Table 11 trans ient event in prog ress Ind ica tions

Tati,e 10 Safety Syste m Para m eters

Reactor powe r Reaeto1 eoolent aetivffy greater than Technica l Spec1t'lcatlon Tati,e 5. *lowablemwls Plan t Slnlctures Conta in in g S f* Shutdown Sys l~s or. RPVle v el Co mp o nent s RPV pressure MU4.1 I 1 I 2 I 3 I I I i Primary contai n ment pressu re SJAE CONDSR OU TLET RAD HI-H I a larm (P602) 4..... 467' elVita l portions o f evation vital the Rad Waste/Con tro l Buildin g:. island. Wetwe ll level

R CS Wet.ve il tempe ratu re Ac tivity 87 " elevation cable spreadin g room - MU4.2 I 1 I 2 I 3 I I I I Ma in Contro l Room and vertical cable ch.se I 525' elevation HVAC a rea Ta ti,e 11 Tra n sient Events Coolant activity GT 0.2 µCi/gm dose equivalent 1-131

Re a ctor Building Vital portions o f the Turbine Building. Reacto r scram RCS leak 1g1 for 15 minute* ot lonoer Runbaci< GT 25% therma l reader -

M DEH pres&ure switches. RPS witches on turbine lhrotde valves. power MUS.1 I 1 I

5 Turbine Building ventilation radiation monitors. ECCS injection OR

.... Ma in steam line piping up to MS-V-1 46 a n d the first stop va lves. The rma l power osc illat ions GT 10% (2) RCS ident ified lea kag e GT 25 gpm for GE 15 mi n.

R CS Standby Service Water Pump Houses OR lukage ocation outside Diesel Generator Building (3) Leak a ge from the RCS to a lcont a inment GT 25 g pm for GE 15 min.

(Note 1)

lnabl litytoahutdOWl'lthereaetoreauslngaehalenge toRP'v' Auto ma tic: or ma n ua l.u am fails lo I hu t down the reae io r, an d AUloma tln s!MtI e or ma n ua l scram falls lo.tiut down the rHdor w a ter level or RCS hea t remova l subl equ en1m an uI laction Itak en1 1the reai;tori;ontrolwa reQ2lsu ei;eu.flAlnshuttin g down lhereaetor

MS6.1 I 1 I 2 I I I I i MA6.1 I 1 I 2 I I I I i MU6.1 I 1 I 2 I I I I i An automatic OR manua l scram fails lo shut down the Ari automatic OR manua l scra m fails to shut dO'Nn the An automatic OR manua l scram did !!.Q! shut dO'Ml the reactor reader reader 6... AND AND AND ei!! actions to shut down the reader a re n.Ql successfu l as Manua l scra m actions taken a t the reactor cont ro l conso le A subsequent automatic scram OR manua l RPS indicated by reactor power GT 5% (mo d e switch in shutdown, manual push butto n s or AR I) are taken at the reactor contr o l conso le (mode switch in sc ra m act ion Failure ANO E ITHER: !!Q! successful in shutting down the reactor as Indicated b y shutdown, manua l push buttons or ARI) is successfu l in Tati,e, Co mm unicatio n Method* RPV level 0Illlii!t be restored and mainta ined reactor power GT 5% (Nole 8) shutting d O'M'l the reactor a s ind icated by reactor power above - 186 in. or 0Drull be d etermined LE 5% (APR M downsca le) (Nole 8)

OR

- Syste m O n slte OR O NR C W\\/V tem pe ra tu re a nd R PV pressure~ b e m aintained be low lhe HCTL Plant Publ ic Address (PA) System X loll of d lll"l91te or offsile i;ommunieationI e.pabiltiel P1ant Te lephone System X X MU7.1 I 2 3

e 4 onslte comm u nic atio n met hods 7 Plan t Radio Sy stem O peration s and X ( 1) Lo ss o r i!!J T b lSecurity Channe ls....... OR loss or (2) Loss o f i.11 Tab le 4 ORO communication methods Com m. Offsite caR ing capability from the X X Co ntrol R o om via direct telepho ne OR (3) Loss of fill Tab le 4 NRC commun icatio n methods long distance ca lling capabl llty on X X the commercia l pho n e sys tem Hazudou1 even! alleetlng a SA FE TY SYSTE M n eeded fOI' the current°"eratlr'igmode

MA8.1 I 1 I 2 I 3 I I I i The occur rence of~ Table 8 haza rdous event Tabfe 8 Hazar dou s Events AND Even t damag e has ca u sed in dica tion s o r deg rade d 8 -. Seismic eve n t performanc e on one train of a SAFETY SYSTE M n eed ed for the cu rrent operating mode Haza rdo u s - Internal or external FLOOD ING event AND EITHER' -

Event High winds Event damage has caused indications of de graded A ffecting. T omado strike performance to a secon d tra in of a SAFETY SYSTE M Sa fety. FIRE n eeded for the current o pera ting mode Sy stem s EXP LOS ION O R

. Volcanic ash fa llout Event da m age has resu lted in V ISIBLE DAMAGE to a

. Other events with similar hazard current operat isecond train of a SAFETY SYSTEM needed for the characteristics as determined by the Sh ift (Notes 9, 10) ng mode

Manager

FG 1.1 I 1 I 2 I 3 I I I i FS1.1 I 1 I 2 I 3 I I I i FA1.1 I 1 I 2 i 3 I I I i I F Los s of.iWY t'NO bar riers Loss or potential loss of.6!lk'. loss or ~ potentia l loss o f...

Fission Produ c t AN D ~ two b arriera (Ta ble F-1) EITHER Fue l Clad or RCS bar rier rd barrier (T abl e F-1 ) (Table F-1)

Bar rier Deg rada tion Loss or potential loss o f the thi I

Table F-1 Fission Product Barrier Threshold Matrix FC - Fuel Clad Barr ier RCS - Reactor Coolan t System Barrier PC - Conta i-nment Barrier

Loss Potential Los s Loss Potential Los s Lo ss Po tential L oss

A RPV level 0llllQl be restored and RP V level~ be restored and RPV W ater Level or cannot be determined. or~ b e de termined. SAG entry requ ired mai n tained GT -161 In. mainta ined GT - 161 in........ SAG entry requ ired

UN ISOLABLE break in 2!!..X of the UN ISOLABLE primary system leakage UN ISOLABLE primary system leaka~

fo llowi ng : that resuhs in exceeding EI THER: that results in exceeding E ITHER :

  • Main Steam Une RB area tem perature alarm leve l RB area m a ximum safe o peratin g B.....,_
  • RWCU (EDP Table 23 ) temperature (EDP Table 23 ) -* RC IC Steam Line

RC S leak R a te

  • Feedwater OR OR O R RB area rad iat ion alarm level RB area max imum safe operating Emergency RPV Depressurization is (EDP Table 24) rad iation (EDP Table 24) requ ired

PC pressure GT 45 psig I

UNPLANNED rapid drop in PC pressure OR sts inside PC fo llowing PC pressure rise Explosive mixtu re ex i C........ PC pressu re GT 1. 68 pslg due to RCS "°"" OR (H2 GE 6% and 0 2GE 5% ) ea kage OR PC Con d itions l PC pressu re response n21 consistent v.-ith LOCA conditions WiN temperature and RPV pressure cannot be ma inta ined below !he

HCTL

Co n tain ment Radiatio n Mo n ito r C MS-R IS-27E or C MS-R 1S-27 F Containment Radiation Mon itor D reading GT 3,600 Rfhr Containment Radiation Monitor C MS-R IS-27E Of CMS-RIS-2 7F PC Rad f..... CMS-RIS-2 7E or CMS-RIS-27F... -DR reading GT 70 R/hr read ing GT 14,000 Rfhr RCS A c tivity Primary coo lant activity GT 300 µCi/gm Dose Equivalent 1-131

UN ISOLAB LE d irect downs tream E pathway to the environment exists after PC Integrity or........ -... PC iso lation signa l.....

Bypa ss O R

Intent iona l PC venting per EOPs

F ~ condit ion in the o pin ion of the !!:!f:J.. condition in the o pinion o f the 6!J:i. condition in the opinion o f the 6!J:i. co nd ition in the opinion o f the ~ con d ition In the opinion o f the &J:i condition in the o pinion o f the that indicates Emergen c y Emergency Director that indicates loss Em ergency Director that indica tes Emergency Director that indicates loss Emergency Director that Indicates Emergency Director that indicates lou Emergency Director oss of the Containment Director of the fuel clad barrier potential loss of the Fue l Clad barr ier of the RCS barrier potent ial loss of the R CS barr ier of the Con ta inment barr ier potent ia l l Judgm ent barrier

13.1.1 Rev. 50 CLASS IFYING THE EMERGENCY Modes: I 1 I I 2 I I 3 HOT CONDITIONS I ENERGY 6/27/2024 NORTHWEST Pow er Operations Startup Hot Shutdown (RCS GT 200°F)

GENERAL EMERGENCY SITE AREA EMERC. ::,y ALERT UNUSUAL EVENT

LCM of RPV i1W911fory affading full did lnfeWttY Wllh Lou of RPV irwet1ory lffeding core decly hell l'llfflD\\11 1 Slgnillc:anl INa o r RP V inv.rwory UntJlannad '"9 of RPV lrwentory -

  • c.onl 111M1ent chale nged _...,

CU1. 1 rl -,,- ~,- ~,-.~ r, - 5~rl -,I RPV levef LT -161 in. for GE 30 min. { Note 1) (1) CONTAIN MENT CLOSURE n.Q1 established ( 1) Loss of RPV Inventory as indicated by RPV level { 1) UNPLANNED loss o f rea ctor coo lant results in RPV level AN D ANO LT -50 in. less than a required lower limit for GE 15 min. (Note 1)

&Jy_ o f the following ind ica tio n s of contai n ment cha llenge : RPV level LT -129 in. OR OR

  • CONTAINMENT CLOSURE !!Q! established (Note 6) OR (2) RPV level~ be monitored for GE 15 min. { Note 1 ) {2) RPV level ~ be mon itored AND AND
  • Explosive mixture inside PC (H2 GE 6% and 0 2 GE 5%) (2) CONTAINMENT CLOSURE established UNPLANNED increase in ruiY Tabl e 1 sump or pool levels
  • UNPLANNED rise in PC J)fessure AND UNPLANNED inc rea se in.l!lY. Table 1 sump or poo l due to a loss of RP V inventory
  • RB area radiation GT.M!}'. Maximum Safe Opera ting level RPV level LT -161 in. levels due to a loss o f RPV inventory (EOP Ta ble 24) 1 RPV level cannot be monitored for GE 30 min. (Note 1) RPV level cannot be monitored for GE 30 min. (Note 1)

AND AND - Table 1 Su mps/Pool RPV Core uncovery is indicate d b y filri of the follo\\Mng : Co re u ncovery Is indicated by !!Ji'. o f the follo'lling:

L oYol

  • UNPLANNED wetwe ll level rise GT 2 inches
  • UNPLANNED wet\\1/ell level rise GT 2 inches t!J1_ valid Hi-Hi level alarm on R-1 Ta ble 2 AC Powe r Sources
  • VALID indlcatioo of RB room fiooding as identified by
  • VAL ID Indication of RB ro o m flooding as identified by throul71 R-5 sumps,...

high level alarms (EDP Table 25) high level alarms (EOP Table 25) EOR GE 25G PM Offslte

  • Observation o f UNISOLABLE RCS leakage outs ide
  • Observation of UNISOLABLE RCS leakage outside FOR GE 10GPM Startup Transformer TR..S plimary containment of sufficient magnitude to Ind icate primary containment of sufficient magnitude to indicate core uncovery core uncovery Wet\\1/ell level rise I Backup Transformer TR-8 AND Observation of UN ISOLABLE RCS Backfeed 500 KV power thro u i;, Main leakage Tr,rsformers (if already a lign ed in

&ill'. of the following indications of containmen t cha a enge : modes 4, 5, def on ly )

  • CONTAINMENT CLOSURE !lQ! established (Note 6) --- Ons lte

, Exp losive mixtu re inside PC (H2 GE 6% and 0 2 GE 5%)

  • UNPLANNED rise in PC pressure DG1
  • RB area radiation GT fil1:t Maximum Safe Operating level 0(32 (EOP Table 24) u.Jn Generato r via TR-N1fN2

Losa o f ii oltsile,nd ii onall e AC power to emergency buse s Lou o f II bl.tone AC porr,,<er sowce 10 emergency buses fot 15 fc,r 15minutnor longer mtn lfnor lqer

CU 2.1 [I ::J1c::J1:::::::1:I* : :::1 : s~:::::1 ;;:o e;]F:]I 2 Loss of fill offsite and ill onsite AC power capabi lity to AC powe r capabf l~y, Tab le 2, to em ergen c y b uses SM-7 Loal of emergency buses SM-7 and SM-8 for GE 15 min. (Note 1) and SM-8 reduced to a single pov,oer source for GE 15 m in.

Em

  • g onci (Note 1)

C AC Power AND Cold SDI &Jy addition al single power sour ce fa ilure IMN result in a loss Rol uol of ill AC po'Ner tOi SAFETY SYSTEMS Sy stem Matfunct. Inability 10 ma lnca ln plant in cold shutdCIWn UN PLANNED lnc:rease In RCS t-,nper 1ture l

Ta ble 7 R CS Reheat Dur ation Threshokl1 3 If an RCS heat remonl 1yst1m is in ope,atlon 'Mlhin this UNPLANNED increase In RCS temperature to GT 20o *F UNPLANNED Incre ase in RCS temperature to GT 2oo*F time frame and RCS temperature is being reduced !he EAL for GT Table 7 duration (No te 1)

R CS lsDmappiCilble OR Temp. UNPLANNED R PV pressure increase GT 10 psig cuJ.2 LI _..., lc.- __. l_~ l--"-*-'-1 ~s'-,_l _..., 1 RC S Statu s Co ntainm ent Hea t-up Closu re Status Dur a tion Loss of fill RCS temperature and RPV water level ind ication lor GE 15 min. (Note 1)

Intact NIA 60 min.

  • 4 establ!shed 20 m in. *

~intact CU4. 1 [ ( j j -4 j 5 j j Lo n ol 021 established O m in. Indicated voltage Lr 108 voe on~ 125 voe buses Vl talDC DP-81-1 and DP-61-2 for GE 15 min. (Note 1)

  • -* Loss of d ~* or offue oommunlcatlona capa blllies

Table4 Communication Method s CU S.1 [ I I j 4' j 5 j DEF I 5 Loss of e!1 Tab le l onsite communication methods Sys te m On slte ORO NRC OR Loos of Loss or ill Table 4' ORO communication methods COfflm. Plant Public Address (PA} System X DR Plant Telephone Sys tem Loss of fill Table 4' NR G communication methods

Plant Rad io System Operations and X Haz ardou s event a n ec;tjng a SAFETY SYS TEM needed for the Security Channels anent operabng mode

Ta ble I Haza rdou s Eve n ts CA6, 1 lc.-__....)c.-__.l_~ I--"-* _._I....e.5 _,_I _ _, I Offsite calling capability from !he X - The occurrence o f w Tab le 8 hazardous event Control Room via direct telephone

  • SelSmic even t AND
  • Interna l or externa l FLOOD ING event Even t damage has caused indications o f degra d ed 6 Long distance cal ling capabi lity o n High 'llinds performance on one train of a SAFETY SYSTEM needed fOI' Hazard ou s the commercia l phone system the curre nt operating mode Events Tornado strike ANO EITHER
  • A-no...... F IRE Event damage has caused indications of degraded Sys tems EXPLOS ION performance to a seco nd train of a SAFETY SYSTEM needed for the cu rrent o pera ting mode Vo lcanic as h fa llout OR other events with similar hazard Event damage has resu lted in V ISIBLE DAMAGE to a characteristics as determined by the Shift second train of a SAFETY SYSTEM needed for !he Manager current operating mode (Notes 9, 10)

Ii

13.1.1 Rev. 50 CLASS IFYING THE EMERGENCY Modes: ~I _4 ~11 5 11 DEF I ENERGY 6/2712024

C o ld Shu tdown R efue ling Defueled NORTHWEST COLD CONDITIONS (RCS :S 200°F)

GENERAL EMERGENCY SITE AREA EMERGL. _..;y I ALERT UNUSUAL EVENT

  • R elHH of g*N-radloeciivlty rnul:ing in off&ile doN gr.lier ReleHe of gNeou. radloadivlly '"'-'ting in offwte dne gfHler RelHn o l gHeous or lquid rw.di!MctMry rHUlting In oW.1141 RelH.. of PMOUI or liqukt radio*cOvtty gr**rer lh*n 2 timH lt.n 1,000 mrem TEOE o r 5.000mrem lhyroid COE lhan 100 mrem TEOE OI' 500 nwem thyroid COE dote gre.ter than 10 m rem TEDE o r SO rnram thyroid COE the 00CM.,....s for 60 minutes or longer

R G1.1 I 1 I 2 I 3 I 4 I 5 [ DEF j RS 1. 1 I 1 I 2 I 3 I 4 j S f DEF I RA 1.1 I 1 I 2 [ 3 I 4 I 5 I DE F ) RU 1.1 ! 1 I 2 I 3 I 4 I 5 I DEF I

( 1) Reading on fil1i'. Table 3 effluent radiation mo n itor (1) Re a ding on ~Table 3 effluent radiation monitor (1) Read ing on i.QY. Tab le 3 effluen t rad iation monito r (1) Reading on filll Table 3 effluent radiation m onitor GT co lumn "G ENERAL" for GE 15 min. GT column " SAE" for GE 15 min. GT co lumn " ALERT' ' lor GE 15 min. GT co lumn "UE" for GE 60 m in.

OR OR OR OR (2) Dose assessmenl us ing adua l meteoro logy indicates (2) Dose assessment using actua l meteorology (2 ) Dose assessment using actual meteoro logy indicates (2) Sample analyses for a gaseous or liquid release doses GT 1,000 mrem TEDE or GT 5000 mrem thyroid indicates doses GT 100 mrem TEDE or GT 500 doses GT 10 mrem TEDE or GT 50 mrem thyroid COE indica tes a concentration or release rate > 2 )( ODCM COE at or beyond the SITE BOUNDARY m rem thy roid COE at or beyond the SITE at o r be y ond the S IT E BOUNDARY ~mits for GE 6Q min.

(Notes 1, 2, 3, 4) BOUNDARY (Notes 1, 2, 3, 4) (Notes 1, 2, 3)

(Notes 1, 2, 3, 4)

RA 1. 2 I 1 I 2 I 3 I 4 I 5 I DE F I 1 RG 1.2 I 1 I 2 I 3 I 4 5 I DEF I R S 1.2 I 1 I 2 I 3 I 4 5 I DEF I An aly sis of a liquid effluent sam ple indicates a concen tra tion Rad Field survey resuhs indicate EITHER of the fo llowing at or Fiekl survey resuhs Ind icate EIT HER of the follOINing at or or release rate that would resu lt in doses GT 10 mrem TEOE Efflu ent beyond the SITE BOUNDARY. beyond the S ITE BOUNDARY : or GT 50 mrem thyro id COE at or beyond the SITE

  • Closed window dose rates GT 1,000 mR/hr
  • C los ed window dose rates GT 100 mR/h r e)(pected BOUNDARY for 60 min. of e)(posUre (Notes 1, 2) expected to continue for GE 60 m in. lo continue for GE 60 min. RA1.3 I 1 I 2 j 3 I 4 j 5 I DEF I
  • Analyses of field survey samples in dicate thyroid
  • Ana lyses of fiekl survey samp les indicate thyroid COE GT 5,000 m rem for 60 m in. of inha lation. COE GT 500 m rem for 60 m in. of inhalat ion. Field survey resu hs Ind icate EITHER o f the foMowing at or (Notes 1, 2) (Notes 1, 2) beyond the SITE BOUNDARY :
  • Closed win dow dose ra tes GT 10 mR/hr expected to co nt in ue for GE 60 m in.
  • An alyses of field surve y samp les ind icate thyroid COE GT 50 mrem for 60 m in. o f Inha lation.

R (Notes 1, 2)

Abnofm Sp.nt fuel poo1 i.ve1 cannot be rn!Ofed ro M 6enl !he lop of !he Spenl ~I poal levsl 81 rha lop ol lhe fuel ra ck, Signit\\elnl lowe ring o l wat er level a bove, or da mag e to, Rad II.let racks 101 50 mirues or longer lmidlatedl'uel Levels RG2.1 ! 1 I 2 I 3 I

  • I 5 I DEF I RS2.1 j 1 I 2 I 3 I 4 I 5 I DEF I RA2.1 I 1 I 2 I 3 I 4 I 5 I DEF I RU 2.1 j 1 I 2 I 3 I 4 ) 5 I DEF I I

Rad Spent fue l poo l level cannot be restored to a t lea st 0.5 ft lowe ring o f spent fuel poo l level lo 0.5 ft Uncovery of irradiated fuel in the R EFUE LI NG PATHWAY U NPLANNED wa ter level drop in the REFUE LING PATHW AY Effluen t for GE 60 min. (No te 1) as in dicated by E ITHER o f the fo llowi n g:

RA2.2 I 1 I 2 I 3 I 4 I 5 I DEF I

  • SF P level LE 22.3 ft 2 Damage to Irrad iated fue l resu lting in a release of e SF P low level a larm Ta b6e 3 Effluen t Moni tor Class ification Threshold s ra d ioactivity ANO Irradiated - ANO UNPLANNED rise in area radiation levels as indicated by fil!Y Fuel Even t - Release Poin t Moni tor Gene ra l SAE A lert LIE High a larm on iQY of the followi n g radiation monitors
  • o f the fo llowing radiation monitors PRM-RE*11 J.OSUIJIIC!fec
  • ARM-R IS-1 Reactor Building Fue l Pool Area
  • ARM -R IS-1 Reactor Building Fuel Poo l Area
  • ARM-R IS-2 Reactor Buildin g Fue l Pooi Area ARM-R IS-~ Reactor Building Fue l Poo l Area

. Reactor Building Exheur.l PR M*RE*12 2.82E*1 l,ICl/cc

  • ARM-R IS-34 Reactor Building E levation 606 ARM-R I S-3,4 Reactor Building Elevat ion 606

, PR M*RE*1J 7.50E+02 µCl/cc 7.50E +1 µCl/c c

  • REA-R IS-609A-D R)( Bldg Ve n t i 1--T,- rt>-I, -, -.,-,. -,, -,,-,-,,-"'-, +------+--- --!-- -----+----!---- ~ TEA*RI S*13 8.35E-02 µCllcc 8.JSE-OJµCllcc 8.35E-04µ Cilcc 4.22E-05iJCilcc RA2.3 I 1 I 2 I 3 I 4 I 5 I D EF j

Cl Re dwH te Buildin g *RIS*14 J.45E-01 µCl/cc 3.45E-02µCl/cc 3.45E-03 µCi/cc 3.98E -04 1,10/cc Lowering of spent fue l poo l lev el to 10 ft [.,.

'\\ Eirhau.t \\I\\IEA RedwH leEffluent FDR-R IS-606 2XH I-H lalerm Rad iation level, lhet IMPEDE

  • cc;:MS lo equipme nt n etnsa-y to r normal punt ope retione, cooldown or el-MdOWl'I

! TSWEMluerit TSW-R IS-5 3.00E-05 µCl,'cc 3 J Seivk:11Wa1erProcneA Sw.R IS-604 1.00E+Ol cps RAJ.1 ! 1 I 2 I 3 I 4 I 5 I DEF I A,ea Seivk:e Water ProceH B SW -RI S-605 1.00E*02cps (1) Dose rates GT 15 mRhir in Control Room R a d iation (ARM-R IS-19) or CAS (by survey)

Levels OR I (2) An UN PLANNED event resu lts In radiation leve ls tha t prohibit or IM PEDE access to ifil'. Tab le 9 T abte 9 Sale Opera tion & Shutdown Room s/Areas roo m s or areas (Note 5) j

- Room/Area Damag e to I k>llded CH k CO NFINEMENT BOU NDAR Y Modes Applicability L--------- ~ :::R::;W:::,::6::7-:R::-,...,::-::-,::.. :::c::~:::*::,;-;,R::,-::=::l;;:R;;HR;::-ffu:::oh:::to::;:RW-:;::~-;,,:::,J:r- -:---- *..,_ -l-________________.) EU1.1 ~I ___ st_o cc,agc,c *c..c.Ope= **cclicc.on.c*'----'

Damage to a loaded canister (MPC) CONF INEMENT E 1 RW 467 Vita l Island (RH R*V -9 disconnect) BOUNDARY as indicated by measured dose rates on a RB 422' B RHR Pump Rm (loca l pu mp temperatures) loaded ove rpa ck GT EITHER :

ISFSI Con fln em enl RB 454 ' B RHR Pum p Rm (o pera te RHR-V--65B) None 20 m rem/h (ga m ma + neu tron) o n the to p of the Bound *ry ove rpack

100 m remi1lr (gamma+ neut ron) on the side of the ove rpack, excluding in let and out let duds HOSTILE ACTION v.ithln the PROTECTED AREA HOSTILE ACTION within the OWNER CONTROLLED AREA or Con.rmed SECUR ITY CONDITION or lhre1I 1irbOl'nelllKklhr111twilhiri30minutee

HS1.1 I 1 I 2 I 3 I 4 j 5 I DEF I HA1.1 I 1 ) 2 I 3 ) 4 I 5 I DEF I HU 1.1 I 1 I 2 I 3 I 4 I 5 I DEF I A HOS TI LE ACTION is occurri n g or has occurred within ( 1) A HOST ILE ACTION is occur ring or has occurred (1) A SECUR ITY CONDIT ION tha t does~ Invo lve a the PR OTEC T ED AREA as reported b y the Secu rity within the Olf.lNER CONTROLL ED AREA as reported HOST ILE ACTIO N as repo rted by the Security Sergean t o r Security Lieu ten a n t b y the Sec u rity Se rgeant o r Sec urity Lieu tenan t Sergea n t or Sec u rity lieuten a n t 1 OR OR Security (2) A validated notification from N RC o r an aircraft attack (2) Notification o f a credible security threat directed at the threat within 30 min. of the site site OR (3) A v alidated notification from the NRC providing in formatio n o l an a ircraft threat

Seiamlc eve GT OBE levels 2 'se~A6~MA8.1 f~ o ~iai,;; - j HU2.1 I 1 j 2 I 3 I 4 I 5 \\ DEF I S~smlc I upgrade to an Alert b ased on degraded Seismic event G Opera ting Bas is Earthquake (QBE) as L_ _ _ _ _ __ _ safety system performance or damage j Event indicated by H13. 851.S1.5-1 (OPERAT ING BAS IS EARTHQUAKE I :,CCEEDED ) activa ted Notes

1 The Emergency Directo r shou ld dec la re the event HUJ.1 I 1 j 2 I J ) 4 j 5 j DEF )

prom ptly upo n determ in in g that time limit has been ( 1) A tornado stri~e within the PROTEC T ED AREA exceeded. or will likely be exceeded OR 2 If a n ongoing release is de tected and the release start (2) Volcanic ash r llout requiring plant shutdown time is unknown, assume that the release duration has exceeded the specified time Nmit 3 If the effluent now past an effluent monitor is known to HUJ. 2 I 1 H 2 I 3 I

  • I 5 I DEF I 3 have stopped. indicating that the relea se path ts isolated, 1 the effluent monitor reading is no lo n ge r VALID for ~:~e~~:~°:n:a~o 1r:i,:;~,~~:ria:a~ ;10~~:~do~ :u:~~n;~o Natura l or classification pu rposes SYSTEM compo ent needed for !he current operating mode Tech. 4 T he pre-ca lcu la ted effluent monitor va lues presented in Haza rd EAls RA1.1, RS1. 1 a nd RG1. 1 sho uld b e use d for HU J,J DEF emergency classification assessmen ts un til the resu lts (1) Movement of ersonne l within the PRO TECTED AREA is from a dose as sessment us ing actua l met eo ro logy are IMPEDED due to a n orfsite eve n t in volvin g hazardous avai lable materials (e.g., an offsite chem ica l spill, 618-11 event or 5 lf the equipment in the listed room o r a rea was a lready to)(ic gas releas e)

Inoperable o r out-of -service before the event occurred, OR then no eme rgency c lassification is wa rranted (2) A hazardous event that resuhs in Otl-Site conditions 6 If CONTA INMENT CLOSURE is re-estab lished prior to sufficient to proh ib it the plant staff from a ccessing the site exceeding the JO.m inute time limit, d eclaration of a via persona l ve hic les (No te 7)

Ge n era l Emerge n cy Is n ot required 7 This EAL does no t a pply to routin e traffic impedimen ts _,_ FIREpolenll*"ydegradingthelevelor u letyoflhepl1nt such as fog, snow, Ic e, o r vehicle bre a kdowns or T able 5 accide n ts Plan t Struc ture1 Co n tainin g Sa fe Sh u tdo wn Sys tem s o r 8 A manua l scram action is any operator action, o r set ol Co mp o n ents HU 4.1 I 1 I 2 I 3 I 4 I 5 I DEF I actions, wh ich causes the control rods to be rapidly A F IRE is nm exti,guished within 15 min. of.any: of the Inserted into the core, and does no t include manua lly Vita l portions of the Rid W ste !Con trol Building: fo llOINing FIRE detedion indications (Note 1):

driving in control rods or im plementa tion of boron in jection 46T elevationvit*lisland

  • Report from the field (i.e., visua l observation) strategies
  • Rece iJ;i of multiple (more than 1) fire alarms or 9 If the a ffected SAFETY SY STEM train was a lready 487 elevation ca ble spreading room indications H in opera ble or o u t o f service before the hazar d ous event Main Contro l Room a n d verticet cab le c hase
  • Field verificatioo o f a single fire a la rm occurre d, !h en em ergen c y classificatio n is n o t war ra n1 ed 525' eleva tion HVAC area ANO Haza rds The FI RE is loca ~ed within ~ Ta ble 5 a rea 10 If the hazar d o u s even t only resu lted in V ISIBLE Reector Building DAMAGE, with no indications o f deg raded performance Vita l portion& ol lhe TUrbiFlll Bu ilding HU4.2 I 1 j 2 I 3 I 4 I 5 I DEF I to at least one train of a SAFETY SYSTEM, then this OEH pres.sure s'Mtches Rece ipt of a single lire a larm (i.e., !!Q other ind ication s of a 4 eme rgency classification Is not warranted RPS switches on lurblne thro ttle vatves FIRE)

Fire ANO M1in steam ~ne 11di11ion mon itors The fire a larm is,xlicaling a FIRE within am Table 5 area Turbine Building ventilation radiation monitors AND Main &tea m Hne pipin g Up to MS*V-146 a nd the first stop va lves The e)(istence of fl FIRE is nQ! verified within 30 min. of a lar m receipt (Note 1)

Sta ndby Service W a ter Pump Houses Diesel Gene tato, Building HU 4. 3 I 1 I 2 I 3 I 4 I 5 j DEF I (1) A FIRE within the ISFS l or plant PROTEC T ED AREA !lQ1 e)(!1ngui&hed 'Mlhin 60 min. of the in itial report, alarm or indication (Note 1)

OR (2) A FIRE within the ISFS I or plant PROTECTED AREA that Table 9 Safe Opera tion & Sh utdow n Rooms/A reas requires firefighting support by an offsite fire response agency to e)C\\Jngu ish

Roo m /Area Modes Applicabi lity G11eoua releHe IMPEDING 1cce11 to eqlipmenl necea.arv for n orma l plant operations, coo ldown or ehutdown RW 467' Radwute Con tro l Roo m (RHR flush to RW tank s) 5 RW 467 Vital I sland (RHR -V-9 disconnect) HAS, 1 I 1 I 2 I 3 I 4 I 5 I D EF I I Hazard o u& RB 422' B RHR PI.MTip Rm (loca l pump temper*bJres) Release of a to)(ic, cor rosive, a sphyxi a nt or flammable gas Gases RB 45'4 ' B RHR Pum p Rm (o perate RHR*V--65B ) into i.QY. T able 9 rooms or are a s ANO Entry Into the room or area is prohibited or IMPEDED (Note 5)

tnab~~ to conlrot e key u fety rundion rrom OU!llde the Conlrol Con lrol Room ev1cuatio" re,ulting in tranaler of plant contro l lo

    • ~ allemaleloc1Uo"8

HS6. 1 I 1 I 2 I 3 I 4 I 5 I HA6.1 j 1 I 2 I 3 I 4 I 5 I DEF I An event has resulted in plant control being tra ns ferred from An even t has resu lted in plant con tro l be ing trans ferred 6 the Control Room to the Remote Shutdown Pane l or from the Co n trol Room to the R emote Shutdown Pane l or Control Altern at e Remote Shutdown Pane l An:emate Remote Shutd o \\Nl1 Pa nel Room ANO Ev acuation Control of ill of the follOINing key safety funct ions Is Q21 reestablished within 15 min. {Note 1 )*

  • Reactivity (Modes 1 and 2 on ly )
  • R PV water level
  • R CS heat remova l

Other conditions ex istlr,g which In the Judgment of lhe Emergen cy Other condition, ulstir,g which In the judgm erit of the Emergency Other condi tlona e1dstlng which in the Judgmnnt ol lhe Othef condlllo"e ex itr.tlng which In lhe Judgment ol !he Director warrant declaration o f Gel'lllral Emergency Directorwarrentdedarallono fSlteAreaEmergency Emerg en cyOireclorwa rrantdec larat ionof *nA lert Eme,vency Director warrant declaration o f I UE

HG7.1 I 1 I 2 I 3 I 4 [ 5 I DEF I HS7.1 I 1 I 2 I 3 I 4 I 5 I D EF I HA7. 1 ! 1 I 2 I 3 I 4 I 5 I DEF I HU7.1 I 1 j 2 I 3 I 4 I 5 I DEF I Other conditions exist which, In the judgment of the Other conditions exist wh ich, In the judgment of the Other cond itions exist wh ich, in the judgment of the Other conditions e)(ist 'Nhich, in the judgment of the Emergency Director, indica te tha t events a, e in progress or Emergency Director, ind icate that events are in progress or Emergency Director, indicate tha t eve n ts are in progress or Emergency Director, indicate that events are in progress or have occurred which invotve actual or IMM INENT have occurred IM'lich invotve adua l or likely major fa ilu res of have occurred which involve an actua l or potentia l have occurred v.t',ich In dicate a po tential degradation of the 7 substant ial co re deg rada tion or melting 'Mth potentia l for plant functions needed for protection of the public or substantial degradation of the level of safety of the plant or level of safety ol the plant o r ind icate a secu rity threat to loss of cont a inment integrity o r HOST ILE ACT ION that HOST ILE ACT ION that resu lts in intentiona l damage or a security even! that involves prob abl e life threaten ing risk facility protection has been in itiated. No releases of Judgme nt results in an act ua l loss o f ph ysica l con tro l of the facility. m a licio u s a ds, (1) towa rd site pe rso n n el or equipm en t that to site pe rso nn el or damage to site eq uipm ent because of radioactive materia l requirin g o ffsite response o r monitorin g R elea ses c an be rea so nably ex pected to e)(cee d EPA cou ld lead to the likely failure of o r, (2) tha t prevent effective HOST ILE ACT ION. Any re leases ar e ex pected to be lim ited ar e ell:pected u n iess fu rther deg ra dation of SAFETY Pro tective Actio n Gu ideline e)(pos ur e lev els o ffsite for m o re acc ess to equ ipm ent ne ed ed fo r the pro tection o l the pu blic. to sm a ll fractio n s o f the EPA Protective Action Guid eline SYSTE MS occ u s.

tha n the im me d iate site area. An y releases are not expec ted to resu lt in expos u re levels ex pos ur e levels.

wh ich exceed EPA Protective Action Guideline exposu re levels be y ond the SITE BOUNDARY.

13.1.1 Rev. 50 CLA S SIFY ING THE EMERGEN CY Modes:.___1 __.II..__ _2 __.II..__ _3 __.I.._I _4 __,II.._ _5 __,I I DEF ENERGY 6/2712024

Power Operations Startup Hot Shutd o wn Co ld ShutdD'NT1 Refu eling Oefueled NORTHWEST ALL CONDITIONS l

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