ML100670507

Actual Handouts to Applications (Folder 3)

ML100670507
Person / Time
Site:	Millstone
Issue date:	01/15/2010
From:	D'Antonio J M Operations Branch I
To:	Dominion Nuclear Connecticut
Hansell S
Shared Package
ML092400035	List: IR 05000336/2010301 ML100220055 ML100470870 ML100470905 ML100470918 ML100610136 ML100670496 ML100670507 ML101160391
References
50-336/10-301, TAC U01799, FOIA/PA-2011-0115 50-336/10-301
Download: ML100670507 (4)

Text

RE-G-03 Page 1 of 1 MP2-20-01 Rapid Down Power Reactivity Plans RWST -1 pump RWST -2 pump BAST -1 %/min 90% 0 RE-G-04 SA 880 gals SA flow 44 gpm CEA pos -180 steps RE-G-05 SA 880 gals SA flow 88 gpm CEA pos -180 steps RE-G-06 SA 204 gals SA flow 20 gpm C EA pos -180 steps Time -20 min. Time -10 min. Time -10 min. Rate -30%/hr Rate -60%/hr Rate -60%/hr 70% (No CEAs) I RE-G-07 SA 2458 gals SA flow 44 gpm CEA pos -180 steps RE-G-08 SA 2640 gals SA flow 88 gpm CEA pos -180 steps RE-G-09 SA 606 gals SA flow 20 gpm C EA pos -180 steps Time -56 min. Time -30 min. Time -30 min. Rate -32%/hr Rate -60%/hr Rate -60%/hr I 55% I* 15% 0 RE-G-10 SA 3080 gals SA flow 44 gpm CEA pos -154 steps RE-G-11 SA 3315 gals SA flow 88 gpm C EA pos -154 steps RE-G-12 SA 720 gals SA flow 18 gpm CEA pos -154 steps Time -70 min. Time -38 min. Tinle -40 min. Rate -39%/hr RE-G-13 SA 4400 gals SA flow 44 gpm CEA pos -140 steps Rate -71%/hr RE-G-14 SA 5120 gals SA flow 88 gpm CEA pos -140 steps Rate -68%/hr RE-G-15 SA 1100 gals SA flow 16 gpm C EA pos -140 steps Time -100 min. Time -58 min. Time -80 min. Rate -51 %/hr Rate -88%/hr Rate -64%/hr 90% 0 70% I (No CEAs) I I 55%

• 15% 0 RE-G-03 MP2-20-01 Rapid Down Power Reactivity Plans RWST -1 pump RWST -2 pump RE-G-04 RE-G-05 SA vol-880 gals SA vol-880 gals SA flow -44 gpm SA flow -88 gpm CEA pos -180 steps CEA pos -180 steps Time -20 min. Time -10 min. Rate -30%/hr Rate -60%/hr RE-G-07 RE-G-08 SA vol-2458 gals SA vol-2640 gals SA flow -44 gpm SA flow -88 gpm CEA pos -180 steps CEA pos -180 steps Time -56 min. Time -30 min. Rate -32%/hr Rate -60%/hr RE-G-10 RE-G-11 SA vol-3080 gals SA vol-3315 gals SA flow -44 gpm SA flow -88 gpm CEA pos -154 steps C EA pos -154 steps Time -70 min. Time -38 min. Rate -39%/hr Rate -71 %/hr RE-G-13 RE-G-14 SA vol-4400 gals SA vol-5120 gals SA flow -44 gpm SA flow -88 gpm CEA pos -140 steps CEA pos -140 steps Time -100 min. Time -58 min. Rate -51 %/hr Rate -88%/hr Page 1 of 1 BAST -1 %/min RE-G-06 SA vol-204 gals SA flow -20 gpm C EA pos -180 steps Time -10 min. Rate -60%/hr RE-G-09 SA vol-606 gals SA flow -20 gpm C EA pos -180 steps Time -30 min. Rate -60%/hr RE-G-12 SA vol-720 gals SA flow -18 gpm CEA pos -154 steps Tinle -40 min. Rate -68%/hr RE-G-15 SA vol-1100 gals SA flow -16 gpm C EA pos -140 steps Time -80 min. Rate -64%/hr 8/6/08 MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS APPROVAL EFFECTIVE DATE SITE AREA EMERGENCY GENERAL EMERGENCY ALPHA CHARLIE-TWO o ALERT CHARLIE-ONE o UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE BARRIER I LOSS OF COLD S I D FUNCTION I I Mode 5, 6 Loss of Shutdown Cooling> 15 Minutes Refuel Water Level < 35 Ft., 61nUncontrolled RCS Temperature Increase>

IO' F RCS Boron Concentration

< Minimum Required r EU; I IREFUEUSPENT FUEL POOL LEVELl ""--M-od-e-6-,-0--'

1Uncontrolled Spent Fuel Pool Water Level Decrease Loss of Cooling Suction Uncontrolled Refuel Pool Water Level Decrease Containment Evacuation 81'ill All Spent Fuel Assemblies in Storage I LOSS OF I Mode 1,2,3,4 Loss of Most (75%) MCB Annunciators>

15 Minutes /lli.Q SPDS ICC Instrumentation I LOSS OF COMMUNICATIONS I I Mode ALL ,. Loss of ALL Onsite Electronic Communications Methods 2Loss of ALL Electronic Communications Methods Government I SHUTDOWN LCO EXCEEDED I I Mode 1, 2, 3, 4 I NOTE: When two or more EALs apply, always choose the EAl of the highest incident classification; also always read fr o m top to bottom in each category Unit NOT Brought To Required Mode Within Applicable LCO Statement Time fur > ""."'. . . '. """ , *'V*...III ..... *

' SO'mJiVhr .. I I Mode ALL OFFSITE DOSE 1MP2 Kaman Vent M onitor (RM-8 Isa) Reading 0.02 f'Cl/cc for> 15 Minute s 2MP2 WRGM Site Stack Effluent Activity (R M-8169) Read2.. 1 f'Ci/cc for> 15 M in3MSL Mon itor (RM-4299NB

/C) Read ing 0.03 R lfor> 15 M i4M easured Plume Dose Rate Onsite 5 for> 15 M5Rad Assessmenl Determines Integrated Dose L 0.005 Rem TEDE OR 2.. 0.025 Rem CDE EfIIuentMonltCirs In*AllrmORUnDIeMed.

UnmonIIored or

...ANDDELTMWO PolItulilCoc:fe Urn'" as Datetm/ned from EP I-fOAP06, PAfIs." IaHIad .

ALERT CHARLIE-ONE Events are in process or have occurred wh i ch Involve an actua l or potential substantial degradation of Ihe level of safety of the plant or a secur i ty event t hat i nvolves probable Hfe threatening risk to site personnel o r damage to site equipment because of Intentional malicious dedicated efforts of a hosUie act. Any releases are expected to be limited to small fractions of the E PA Protective Action Guideline exposure leve ls. UNUSUAL EVENT " DELTA-TWO Events are in process or have occurred which i ndicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

MP-26-EPI-FAP06-002 Revision 006 Page 1 of 3 I FUEL CLAD OR RCS BARRIER I I Mode 1, 2, 3, 4 See Bar r i er Fa ilure Reference Table I BA2 II STEAM LINE BREAK II Mode 1, 2, 3, 4 U nisolable Steam U ne Bre ak O utside CTMT Mode 1, 2, 3, 4 LOU GtVa!llP on l DC 1i.Ai8a201A.AIiIlmtB

>' 15 Min" STATION BLACKOUT Mode 5, 6, 0 I I Loss of Voltage on Bu ses 24C AND 24D > 15 Min utes I PA2 I I SINGLE AC POWER SOURCE I I Mode 1, 2,AD On l y One AC Power Source A vailable to Supply Bus es 24C 24D > 15 M i nute s Su ch That L oss of Th at P ow er Sourc e W o uld R esult in a Sta tio n Blackout (U nit 3 Buses 34NB CANNOT be C redited unless already aligned to U nit 2 Bus 24C I or 24D) I AUTOMATIC RX TRIP FAILURE I I Mode 1, 2 Fa il ure of Automatic Reactor Trip Manual Trip Was Success f ul I INABILITY TO MAINTAIN COLD SID I I Mode 5, 6 1Un controlled R C S Tem pe rature Increase > 10'F That Resu lts in RCS Temperat ure > 200' F 2. Inadve rtent Cr iticality boss OF ANNUNC-IA-T-O-R-SIT-RA-N-S-IE-N'i Mode 1, 2, 3, 4 Lo ss of Most (75%) MCB A n n unciato r s> 15 Minutes 8t1Q EITHER of the Following:

Significant Transient in LOSS of SP DS AN.O.ICC InstrumentatioII CTMT BARRIER Mode 1, 2, 3, 4 See Barrier Failure Reference Table I RCS LEAKAGE I I Mode 1, 2, 3, 4 1 Pressure Boundary Leakage> 10 GPM Unidentified Leakage> 10 GPM Identified Leakage> 25 GPM Primary to Secondary Leakage > 25 GPM §] I FUEL CLAD DEGRADATION I I Mode ALL 1 RCS Activity>

60 I1Ci/gm 1-131 DEQ Dose Rate at One Foot from Un pressurized Sample .2:. 2 mRlhr l LOSS OF OFFSITE POWER I I Mode ALL Loss of all OFFSITE power to buses 24C AND 24D for > 15 Minutes. jPU2l LOSS OF DC I I Mode 5, 6 Loss of Voltage on DC Buses 201 A AND 201 B > 15 Minutes MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS 7/29/08 APPROVAL DATE GENERAL EMERGENCY ALPHA BARRIER FAILURE I FUEL CLAD OR RCS BARRIER I 1 Mode 1 , 2, 3, 4 See Bar r i e r F ailure Reference T able 1 BA2 1 ,-I __ S_TE_A_M_Ll_NE_B_REA_K_----'11 Mode 1 , 2 , 3, 4 U nis o lable Ste am U ne Br eak O ut s ide CTMT 1-1 ___ C_T_M_T_B_A_R_RI_E_R

__ --'II Mode 1 , 2 , 3, 4 See Barrier Failure Reference Table [§J 1-1 ___ R_C;.,.S;.,.L_EA_KA_G_E

__ ----II I Mode 1 , 2, 3, 4 1 . Pressure Boundary Leakage> 10 GPM 2. Unidentified Leakage> 10 GPM 3. Identified Leakage> 25 GPM 4. Primary to Secondary Leakage >25 GPM 1 FUEL CLAD DEGRADATION 1 1,--_M_Od_e_A_L_L_-,. 1. RCS Activity> 60 I-lC i/gm 1-131 DEQ 2. Dose Rate at One Foot from Un pressurized RCS Sample .2:. 2 mR/hr/ml SITE AREA EMERGENCY CHARLIE-TWO o ALERT CHARLIE-ONE 1-1 _--=-ST.:.,:.A.:.,:.T.:.,:IO:..:.N;..;B;;.:LA:....:..;:,C.:..:KO;;:..U;;:..T:.-----II I Mode 5, 6 , 0 Loss o f V ol ta ge o n B u s es 2 4 C 240 >15 M i n u te s I PA2 I I SINGLE AC POWER SOURCE I 1 Mode 1, 2, 3, 4 O n ly O n e AC P o w er Source A va ilable to S uppl y Bu s e s 24C M!!UQ.B 24 0> 15 M i n u te s Su ch Th at L o ss of T hat P o w e r Sourc e W o uld R e s ult in a St atio n Blac ko ut (U nit 3 Buses 3 4 N B CANN O T be C r edi t e d un l es s already align ed to U nit 2 Bus 2 4C I or 240) I LOSS OF OFFSITE POWER 1 1 Mode ALL Loss of all OFFSITE power to buses 24C AND 240 for > 15 Minutes. fPu2lLI ___ LO_S_S_O_F_D_C

__ ---'I 1 Mode 5 , 6 Loss of Voltage on DC Buses 201 A AND 201 B > 15 Minutes I AUTOMATIC RX TRIP FAILURE 1 1 Mode 1 , 2 Fa il ure of Aulomatic Reactor Trip 8NQ M anual Trip W as Suocess f ul 1 INABILITY TO MAINTAIN COLD S I D I 1 Mode 5, 6 1 , Un contro ll e d R C S Tem pe rature Increase> 10' F That Res u lt s in R C STemperat ure > 200'F 2. I na d vertent C r iticalit y OF ANNUNCIATORSfTRANSIEN]

Mode 1 , 2 , 3 , 4 Lo ss of M ost (75%) M C B Ann u n ciato r s> 1 5 M inutes EITHE R of the Follow i n g: Significan t Transien t in P rogress L OSS of S PDS AMl I CC Instrumentati o n 1 LOSS OF COLD S I D FUNCTION I Mode 5, 6 1. Loss of Shutdown Cooling> 15 Minutes Illi.Q Refuel Pool Water Level < 35 Ft., 6 tn. 2. Uncontrolled RCS Temperature I ncrease> 10" F 3. RCS Boro n Concentration

< Minimum Required IREFUEUSPENT FUEL POOL LEVELl r-1-M-od-e ,-0--' 1. Uncontrolled Spent Fuel Pool Water Level Decrease Causing Loss of Cooling Suction Flow 2. Uncontrolled Refuel Pool Water Level Decrease Requiring Containment Evacuation 81iQ All Spent Fuet Assemblies in Safe Storage Locations

-I LOSS OF ANNUNCIATORS I I Mode 1,2,3,4 1 Loss of Most (75%) MCB Ann u nciators> 15 Minutes /lli.Q SPDS Q8 ICC Instrumentation Available I LOSS OF COMMUNICATIONS 1 1 Mode ALL 1. Loss of ALL Onsite Electronic Communications Methods 2. Loss of ALL Electron i c Communications Methods With Government Agencies NOTE: When two or more EALs apply, always choose the EAL o f the highest in ci d e nt cla s sification; also always read fr o m top to bottom i n each categ o ry. 1 SHUTDOWN LCO EXCEEDED 1 I Mode 1, 2, 3, 4 I Un i t NOT Brought To Requ i red Mode Within Applicable LCO Action Statement Time Limits o UNUSUAL EVENT DELTA-TWO Mode ALL 1. M P2 Kaman Vent M on i tor (RM-8 1 68) Re a d i ng 0.02 for> 15 M i nutes 2. M P2 WR G M Site Stack Effluent Act i v i ty (R M-8169) R eading 2..1 for> 15 M i nu t es 3. M Sl M on i tor (RM-4299N B/C) Read i ng 0.03 R/hr 10( > 15 M i nu t es 4. M eas ur ed P l ume Dos e R a te Ons i le 5 mR/hr fo r > 15 M inutes 5. Rad Assessm en t Determines tntegrated D ose Offs i te 2.. 0.005 Rem T EDE OR 2.. 0.025 Re m CDE Thyro i d L..-......;U;.,.N_P_LA_N_N_E_D_R_EL

_E_A..;.S_E_

..... 1 I Mode ALL 8/6/08 EFFECTIVE DATE D UNUSUAL EVENT DELTA-ONE CHARLIE-ONE Eve n ts are in process or have occur r ed wh i ch involve an aClua l 0( poten ti al substantial degradation of the l evel of safety of the plant or a secur it y event t hat i nvolves probab l e life threaten ng r i sk to s i te personnel o r damage to site equ i pment because of I ntent i onal malicious ded i cated efforts o f a hosWe act. Any re l eases are expected to be lim i ted 10 smalilractions o f the EPA PrOlective Act i on Guideline exposure levels. UNUSUAL EVENT DELTA-TWO OR DELTA-ONE Events are in process or have occurred which i ndicate a potential degradation of the level of safety of the plant or indicate a se c urity threat to facility protection. No releases of radioactive material requiring offsite response or monitoring are expected untess funher degradation of safety systems occurs. 2 Millstone MP-26-EPI-FAP06-002 Revision 006 Page 1 of 3 '.

MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS SITE AREA EMERGENCY GENERAL EMERGENCY ALPHA CHARLIE-TWO D ALERT CHARLIE-ONE o UNUSUAL EVENT DELTA-TWO UNUSUAL EVENT DELTA-ONE

=**I SPENT FUEL ASSEMBLY DAMAGE I I Mode ALL 1Spent Fuel is Exposed from O pen Ve ss el , C avit y , or SF AND Spent Fuel Has D e c ayed L 3 0 Day2Fuel Handling A CCident C ausing D amage 10 S pent Fuel , Ind ica ted by Fuel Building O R Containmen t Radiation M onito r s Increasing I RA2 1 1 PLANT RADIATION 1 1 Mode ALL 1Ra dia t ion R eadings> 1 5 mR/hr in C ontrol Room O R Central Al a rm S tatio n QB Secondary Alarm S t ation 2R adiation R eading> 5 R/hr in Areas Requir in g Access Safe ShRAD MONITORS I 1 Mode ALL 1Uncontrolled Refuel Pool Water Level Decrease AND Rad Levels Require Evacuation o f CTMT or Spent Fuel Pool Area 2Unexpected Area Rad Monitor Reading Offscale High > 1000 Times Normal A'n ..I I 1 SECURITY EVENT Mode ALL Security Events as determined for Station Safeguards Contingency Plan and reponed by Security Shift Supervis i on , (Addresses events that I nvolve A ctual or Potential Substantial degradation 10 the level of safety 01 the p l ant) 2A noti ficat ion from t he site security force that an armed attackexptosr-e attack , airliner I mpact, or other HOSTILE A CT10N occurring or has occurred w i thin the OCA3A vaHdated notification from the N RC of an airliner attack threat le ss Ihan 30 minutes a w ay. I TA2 1 1 DESTRUCTIVE PHENOMENA 1 1 Mode ALL 1. Seismic E ven t > 0.09g ZPA 2, Onslte Sustained Windspeed

> 90 MPH 3 , V isible D amage to Structures o r Equipmenl AtiQ A ffecting Safe Shutdown Vessel or Vehicle Collision 8NQ Affecting Safe Shutdow n 5Missiles Affecting Safe Shutdown 6Flooding Affecting Safe Shutdow n 1 SECURITY EVENT 1 1 Mode ALL 1Security Eve n ts as delermined for Stat i on Safeguards Cont i ngency P l an and reported by Security Shift Superv i sion. (Addresses events that involve Potential degradat i on in the le v el of safety of Ihe plan!.) A credible s i te specific s'ecur i ty thre a t notific*alion. A validated notificat i on from the NRC providing information of aircraft 1 DESTRUCTIVE PHENOMENA 1 " Mode ALL 1Seismic Activity Detected Per AOP-2562, Eanhquake 2Report by Plant Personnel of Tornado Striking Within Prote ct ed Area 3Visible Damage to Structures or Equipment Within the Protected Area I CONTROL ROOM EVACUATION I Mode ALL C ont rol Room Evacuation I nitiated 1 GA2 1 I FIRE/EXPLOSION 1 1 Fi r e or Explosion Affecting Safe S h utdown A rea 8tiQ Damage to S tru ctures QB E quipment In dicated I GA3 1 1 TOXIC/FLAMMABLE GASES I I Mode ALL Ufe T hreaten in g T oxic G as es QB Rammable G a s Concentrations a s Id entified in C-OP 2 00.5 , " O il , Hazardous M aterial. H azardous W aste and M i xed Waste C onti ngency P lan" Aff ecting A reas for S afe Shutdow n I FIRE 1 I Mode ALL Fire in Bui l ding OR Areas Adjacenl to Areas Needed for Shutdown NOT Extinguished Within 15 M i nutes of Notificalion Verifica t ion of Control Room 2Fire-Affecting a Loaded ISFSI-eonfinement Boundary NOT Ex1 i nguished Within 15 Minutes of Not i fication , 1 GU2 1 1 TOXIC/FLAMMABLE GASES 1 1 Mode ALL t Life Threatening Toxic Gases QB Flammable Gas Concenlrat i ons Identified in C-OP 200.5 , " Oil , Hazardous Malerial, Hazardous and Mi x ed Waste Contingency Plan " AffeCling Normal Notification 0 1 a N ea r*Si te Release That May-Require Evacuation I 1 JUDGEMENT Mode ALL Any Condit ion F or Which J udgement Indicates T ha t Safety Systems M a y Be Degraded 8MQ Wh ich Requires Emergency Response Organizat i on Staffing I I JUDGEMENT Mode ALL Any Condition For Which Judgement Indicates Degradation in the Level of Safety of the ALERT -I CHARLIE-ONE Events are In prooess or have occurred which i nvolve an a.otual or potenlia l substantial degradation of the leve l 01 safety of th e plant or a secur i ty event that In volves probable Ilfe threatening risk to s i le personnel or damage to site equipment because of I ntentiona l malicious dedicate d effons of a host ile act. Any releases are expecled to be l i mited to small fractions of Ihe EPA Protective Action GUideline exposure levels. UNUSUAL EVENT I' D ELT A-TWO OR DELTA-ONE Events are in process or have occurred which indicate a potential degrad a tion of the le v el of safety of the plant or indicale a security threal to facility prole c ti o n. No releases of rad i oactive mater i al requiring offsite response or monitoring are expected unless further degradatio n of safety systems occurs , Onsrte Sustained Winds peed > 75 MPH 5ExplOSion Within the Protected Area Turbine Failure Caus i ng Observable Casing Damage Vessel or Vehicle Collision With Structures OR Equipment Required AREAS OF CONCERN FOR SAFE SHUTDOWN Control Room Cable Vaults Turbine Building Penetration Areas RBCCW Rooms Diesel Generator Room Charging Pump Cubicles Switchyard Switchgear Rooms Intake Structure Switchgear Area Coolant Tanks Area Containment DC Equipment and Battery Rooms Safety Injection Pump 2 for Safe Shutd o wn or a loaded ISFSI Confinement Boundary 8 , Flood Level > 19 Feet Mean Sea Level 9Flooding in Areas Containing Safe Shutdown Equipment Millstone MP-26-EPI-FAP06-002 Revision 006 Page 2 of 3 MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS GENERAL EMERGENCY ALPHA I SPENT FUEL ASSEMBLY DAMAGE I I Mode ALL 1. Spen t Fu el is Exposed fro m O pen V e s s el , C a v i t y , o r SF Pool AN D Spent Fuel H as D e c a yed L 3 0 Da ys 2. Fuel H andl i n g A CCident C ausing D amage to S pent F ue l , I nd i cate d by Fuel B ui l ding O R C o nt ainmen t Radiation M o n ito r s I ncrea s in g I RA2 I .... 1 __

I Mode ALL 1 , R a di a t ion R eadin g s> 1 5 m R/h r in C on t rol Room O R C e nt ral Al a rm S tat i o n QB S eco n d ary Al arm S t ation 2. R adiation R ead i ng> 5 R/hr i n Areas R equiring A ccess f o r Safe S hutdo w n ,-I ___ R_A_D_M_O_N_IT_O_R_S

__ --'I I Mode ALL 1. Uncontrolled Refuel Pool Water Level Decrease AND Rad Levels Require Evacuation of CTMT or Spent Fuel Pool Area 2. Unexpected Area Rad Monitor Reading Offscale High OR > 1000 Times Normal Reading SITE AREA EMERGENCY CHARLIE-TWO D ALERT CHARLIE-ONE IL....-__

I Mode ALL Security Events a s determ i ned l or Station Sa f eguards Cont i nge n cy Plan and reported by Se c urity Shift Supervis i on. (Addresses events that I nvo l ve A o t ual o r Potent i a l Subs t an t i al degradat i o n t o t h e lev el o f safely of th e p l ant ,) 2. A notificat i o n from t he s i te s e c u r i ty for ce that an a rmed an ack , exp l osive anack , a i rliner I mpact , or other H OSTILE A C TI O N Is occurr i ng or has occurred with i n the OCA. 3. A validated nOlificat i on from th e N RC or an air li ner attac k th re at le ss than 30 m i nute s a w ay_ I TA2 I I DESTRUCTIVE PHENOMENA I I Mode ALL 1. Seismic E ven t > 0.0 9 g ZPA 2. On sile S ustained W in ds p ee d > 90 MPH 3. V isible D amage to S tr uctures o r E q u i p me n t A ff ecting Sa f e S h utdo wn 4. Vesse l or Vehicle ColliSio n flliQ Affecting Sa f e Shutdo w n 5. Missi l es Aff ecting Sa f e Shu t down 6. Flooding Affecting Sa f e Shutdow n .... __ S_E;....C_U_R_ITY_E_V;...E_NT

__ --JI I Mode ALL 1. Security Events as determined for Stat i on Safeguards Cont i ngency Plan and reported by Se c urity Shift Superv i sion. (Addresse s events that involve Potentia l degradation in the le v el of safety of the plant.) 2. A cre di ble site specifi c s'ecurily t hre a t notific*ation. 3. A val i dated notificat i on from the NRC pr o viding information of an aircraft threat. I DESTRUCTIVE PHENOMENA II Mode ALL 1. Seismi c Activity Detected P e r AOP*2562. Eanhquake

2. Repon by P l a n t Personnel of Tornado Striking Within Prot e c t ed Area 3. Visible Damage to Stru c tures or Equipment Within the Protected Area 4. Onsile Sustained Winds peed > 75 MPH FIRE/GASES GS1 CONTRO L ROOM EVACUATION Mode ALL U,m: from P*fttt Co10 OF N1 NOt W1tI1In is Min,,* After CQfIQ'Ql Room I CONTROL ROOM EVACUATION I Mode ALL C on t rol Roo m Evac u ation I n i t iated I GA2 I .... 1 ___

I Mode ALL Fir e or Explosion A ffectin g Safe S h utdown A rea 8tfQ D amage to S t r u c t ures QB E qu i p m e nt In dicated I GA3 I I TOXIC/FLAMMABLE GASES I I Mode ALL Uf e T hr eat en i n g T o x ic G as es QB Ramm ab l e G a s Con ce nt r atio n s a s Id en ti fi ed i n C-OP 2 0 0.5 , *O il , Hazardous M ate r ial. H aza r dous W ast e and M i x ed Was t e C onti ngency P l a n" A ff ec t i ng A reas f o r S a f e S hu t do w n ________

______

1. Fire in Bui l ding OR Areas Ad j acent to Area s Needed for Safe Shutdown NOT Extinguished W i thin 15 Minutes of Notification QB Verifica t ion of Control Room Alarms 2;-Fire AtteC1ing a Loaded ISFSI-eontinement Boundary NOT Ext i nguished Within 15 Minutes of Not i fication. I GU2 I I TOXIC/FLAMMABLE GASES I I Mode ALL 1. Life Threatening Toxic Gases QB Flammable Gas Concentrat i ons as Identified in C-OP 200.5. " Oil , Hazardou s Material.

Hazardous Waste and Mixed Waste Contingency Plan" Affecting Normal Operat i on 2. Notification of a N ear-S ite Release That May-Require Evacuation o UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE JUDGEMENT IL....-__ J:....:U;....;;D;....;;G-=E;...M;.::E;.,..N;...T

__ --JI I Mode ALL A ny C ondit i on F or Whic h J udgement I ndica te s T hat S afety Systems M a y Be D egraded 8NQ W h i ch Require s E m e rg ency Resp o n se Org a n izat i o n Staffing .... 1 ___

__ --'I I Mode ALL Any Condition For Which Judgement Indicates Potential Degradation in the Level of Safety of the Plant ALERT CHARLIE-ONE Eve n ts are I n process or ha ve occurred which I nvo l v e an a.otua l or potent i a l substant i al d egr ad a t i on o f the l e v el o f sa fe ty of t he plant or a secur i ty event that In volves probab l e li f e threaten i ng ri sk to s i te p e rsonnel or damage to site eqU i pment because of I ntentiona l malic i ous ded i cate d e f forts of a hos til e ac t. Any r eleases are expected to be l i m i ted 10 small fractions o f Ihe EPA Protective Act/on Gu i deline expos u re l ev el s. UNUSUAL EVENT DELTA-TWO OR DELTA-ONE Events are in process or have occurred which indicate a potential degradation of the le v el of safety of the pl a nt or indicate a security threat to facility protect i on. No releases of rad io active mater i al requiring offsite response or m o nitoring are expected unless further degradati o n of safety systems occurs. 5. ExplOSion Within the Protected Area AREAS OF CONCERN FOR SAFE SHUTDOWN 2 6. Turbine Failure Caus i ng Observable Casing Damage 7. Vess e l or Vehicle Collision With Structures OR Equipmen t Required for Safe Shutd o wn or a loaded ISFSI Confinement Boundary 8. Flood Level> 19 Feet Mean Sea Le v el 9. Flooding in Areas Containing Safe Shutdown Equipment Control Room Cable Vaults Turbine Building Penetration Areas RBCCW Rooms Diesel Generator Room Charging Pump Cubicles Switchyard Switchgear Rooms Intake Structure Switchgear Area Coolant Tanks Area Containment DC Equipment and Battery Rooms Safety Injection Pump Rooms Millstone MP-26-EPI-FAP06-002 Revision 006 Page 2 of 3 MILLSTONE 2 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE IMMINENT -No Turnaround in Safety System Performance is Expected AND Escalation to General Emergency Conditions Will Occur Within 2 Hours INDICATORS FUEL CLAD BARRIER RCSBARRIER CTMT BARRIER SAFETY FUNCTION STATUS/ FUNCTIONAL RECOVERY I FCB1 I I LOSS I Not Applicable I POTENTIAL LOSS I 0 No RCS Heat Remo v al Via Steam Generators Alli2 Once Through Cooling NOT Effective AND Shutdown Cooling System Is NOT In Service I RCB1 I I LOSS I Not Applicable I POTENTIAL LOSS I 0 Uncontrolled RCS Cooldown AND RCS Pressure-Temperature To the Left Of the PTS Limit 200°F Subcooling Maximum Curve 0 No RCS Heat Removal Via Steam Generators Alli2 Once Through Cooling NOT Effecti v e AND Shutdown Cooling System Is NOT In Service CORE EXITTC TEMPERATURES I FCB2 I I LOSS I Core Exit Thermocouple Readings > 1300 O F I POTENTIAL LOSS I 0 Core Exit Thermocouple Readings > 800 OF I RCB2 I I LOSS I RCS Subcooling

< 30°F I POTENTIAL LOSS I Not Applicable I CNB1 I I LOSS I Not Applicable I POTENTIAL LOSS I Core Exit TC Temperature Readings > 1300°F Alli2 Do NOT Decrease Within 15 Minutes PRESSURE I RCB3 I I LOSS I Not Applicable I POTENTIAL LOSS I 0 Uncontrolled RCS Pressure Decrease and Increasing Containment Radiation Monitors I CNB2 I I LOSS I [iJ Rapid Unexplained CTMT Pressure Decrease L Following Initial Increase [iJ No CTMT Pressure Increase When Expectation Exists I POTENTIAL LOSS I o CTMT Pressure > 10 PSIG Increasing AND No Containment Spray Pump o CTMT H2 Concentration 4% COOLANT LEAKAGE I RCB4 I I LOSS I [iJ Reactor Coolant Leak > CVCS Capacity AND Entry Into EOP-2534, Steam Generator Tube Rupture or EOP 2540, Functional Recovery , to Address Steam Generator Tube Rupture I POTENTIAL LOSS I 0 Reactor Coolant Leak> CVCS Capacity AND Entry Into EOP-2525, Standard Post Trip Actions 0 Reactor Coolant Leak Rate CVCS Capacity At::ill EITHER of the following: . Entry Into EOP 2534, Steam Generator Tube Rupture . Entry Into EOP 2540, Functional Recovery , to Address Steam Generator Tube Rupture I C NB3 1 I LOSS I Primary to Secondary

> Tech Spec Limits and EITHER exists:

• Nonisolable Steam Release from Affected S/G to environment. . Prolonged Release From Affected S/G to Environment When Used for Cooldown. (see basis for description of prolonged release) Failure of BOTH Isolation Valves AND a Pathway to the Environment Exists I POTENTIAL LOSS I o Entry Into EOP-2532 , Loss of Primary Coolant, AND Leakage Exists Outside CTMT Requiring Local Isolation RADIATION I FCB3 I I LOSS I RM -8240/8241 Reading > 300 R/hr RM -8240/8241 Reading> 5 R/hr Without RCS Release InsideCTMT At Least 5% Fuel Clad Damage As Determined By Core Damage Estimate [JJ Dose Rate at One Foot from Unpressurized RCS Sample 28 mR/hr/ml I POTENTIAL LOSS I Not Applicable I RCB5 I I LOSS I [iJ RM-8240/8241 Reading > 5 R/hr Without Fuel Clad Barrier Loss I POTENTIAL LOSS I Not Applicable I CNB4 I I LOSS I Offsite Dose Plume Rate 10-6 Times RM-8240/8241 Reading if Release is to CTMT I POTENTIAL LOSS I o RM-8240/8241 Reading> 1 , 200 R/hr o At-beast *20% Fllel Clad Damage As Determined By Core Damage Estimate WATER LEVEL I FCB4 I I LOSS I Not Applicable I POTENTIAL LOSS I 0 RVLMS Reading = 0% with OPERABLE #8 string (NA if no OPERABLE #8 strinq) --I CNB51 I LOSS I No CTMT Sump Level Increase When Expectation Exists -I P9TENTIAL LOSS I Not Applicable JUDGEMENT , I FCB5 I Any Condition For Which Judgement Indicates Loss or Potential Loss of Fuel Clad Barrier Due to: . Imminent Barrier Degradation Based On Current Safety System Performance . Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate

-I RCB6 I Any Condition For Which Judgement Indicates Loss or Potential Loss of RCS Barrier Due to: . Imminent Barrier Degradation Based On Current Safety System Performance . Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate I CNB61 Any Condition For Which Judgement Indicates Loss or Potential Loss of CTMT Barrier Due to: . Imminent Barrier Degradation Based On Current Safety . System Performance Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate MORE THAN THREE BARRIERS ONE BARRIER AFFECTED 3/3 YES TWO BARRIERS ONLY ONE BARRIER AFFECTED ALERT ONE CLAD RCS CTMT 2 UNUSUAL EVENT DELTA-ONE MP-26-EPI-FAP06-002 Revision 006 Page 3 of 3 Millstone 2/3 MILLSTONE 2 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE IMMINENT -No TUrnaround in Safety System Performance is Expected AND Escalation to General Emergency Conditions Will Occur Within 2 Hours INDICATORS FUEL CLAD BARRIER RCSBARRIER I FCB1 I I LOSS I I RCB1 I I LOSS I SAFETY FUNCTION Not Applicable Not Applicable STATUS/ I POTENTIAL LOSS I I I FUNCTIONAL POTENTIAL LOSS 0 Uncontrolled RCS Cooldown AND RCS Pressure-Temperature To RECOVERY the Left Of the PTS Limit 200°F Sub c ooling Maximum CUNe 0 No RCS Heat Remo v al Via Steam Generators 8NQ Once Through Cooling NOT Effective AND Shutdown Cooling 0 No RCS Heat Removal Via Steam Generators 8NQ Once Through System Is NOT In SeNice Cooling NOT Effecti v e AND Shutdown Cooling System Is NOT In SeNice I FCB2 I I LOSS I I RCB2 I I LOSS I CORE EXITTC [I] Core Exit Thermocouple Readings> 1300 O F [I] RCS Subcooling

< 30°F TEMPERATURES I POTENTIAL LOSS I I POTENTIAL LOSS I 0 Core Exit Thermocouple Readings> 800 OF Not Applicable I RCB3 I I LOSS I Not Applicable I POTENTIAL LOSS I PRESSURE 0 Uncontrolled RCS Pressure Decrease and Increasing Containment Radiation Monitors I RCB4 I I LOSS I [iJ Reactor Coolant Leak> CVCS Capacity AND Entry Into EOP-2534, Steam Generator Tube Rupture or EOP 2540, Functional Recovery , to Address Steam Generator Tube Rupture COOLANT I POTENTIAL LOSS I LEAKAGE 0 Reactor Coolant Leak> CVCS Capacity AND Entry Into EOP-2525, Standard Post Trip Actions 0 Reactor Coolant Leak Rate CVCS Capacity N[l EITHER of the following: . Entry Into EOP 2534, Steam Generator Tube Rupture . Entry Into EOP 2540, Functional Recovery , to Address Steam Generator Tube Rupture I FCB3 I I LOSS I I RCB5 I I LOSS I [I] RM-8240/8241 Reading> 300 R/hr [iJ RM-8240/8241 Reading> 5 R/hr Without Fuel Clad [I] RM-8240/8241 Reading> 5 R/hrWithout RCS Release Barrier Loss InsideCTMT

--[I] At Least 5% Fuel Clad Damage As Determined By Core RADIATION Damage Estimate I POTENTIAL LOSS I [I] Dose Rate at One Foot from Unpressurized RCS Sample 28 mR/hr/ml Not Applicable I POTENTIAL LOSS I Not Applicable I FCB4 I I LOSS I WATER Not Applicable I I LEVEL POTENTIAL LOSS 0 RVLMS Reading = 0% with OPERABLE #8 string (NA if no OPERABLE #8 strinq) I FCB5 I I RCB6 I Any Condition For Which Judgement Indicates Loss or Potential Any Condition For Which Judgement Indicates Loss or Potential Loss of Fuel Clad Barrier Due to: Loss of RCS Barrier Due to: JUDGEMENT . Imminent Barrier Degradation Based On Current Safety . Imminent Barrier Degradation Based On Current Safety System Performance System Performance . Degraded Fission Barrier Monitoring Capability Making . Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate Barrier Status Indeterminate CTMT BARRIER I CNB1 I I LOSS I Not Applicable I POTENTIAL LOSS I Core Exit TC Temperature Readings >1300°F 8NQ Do NOT Decrease Within 15 Minutes I CNB2 I I LOSS I [iJ Rapid Unexplained CTMT Pressure Decrease Following Initial Increase [iJ No CTMT Pressure Increase When Expectation Exists I POTENTIAL LOSS I o CTMT Pressure> 10 PSIG 6NQ Increasing AND No Containment Spray Pump o CTMT H2 Concentration 4% I C NB3 1 I LOSS I [I] Primary to Secondary> Tech Spec Limits and EITHER exists:

• Nonisolable Steam Release from Affected S/G to environment. . Prolonged Release From Affected S/G to Environment When Used for Cooldown. (see basis for description of prolonged release) [I] Failure of BOTH Isolation Valves AND a Pathway to the Environment Exists I POTENTIAL LOSS I o Entry Into EOP-2532 , Loss of Primary Coolant, AND Leakage Exists Outside CTMT Requiring Local Isolation I CNB4 I I LOSS I [I] Offsite Dose Plume Rate 10-6 Times RM-8240/8241 Reading if Release is to CTMT I POTENTIAL LOSS I o RM-8240/8241 Reading> 1,200 R/hr o At-beast -20% Fuel Clad Damage As DetefRlined By Core Damage Estimate I CNB5 I I LOSS I [I] No CTMT Sump Level Increase When Expectation Exists I POTENTIAL LOSS I Not Applicable I CNB6 I Any Condition For Which Judgement Indicates Loss or Potential Loss of CTMT Barrier Due to: . Imminent Barrier Degradation Based On Current Safety . System Performance Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate 1-THREE BARRIERS 3/3 YES TWO BARRIERS 2/3 MORE THAN ONE BARRIER AFFECTED ONLY ONE BARRIER AFFECTED CLAD RCS 2 Millstone ALERT ONE UNUSUAL EVENT DELTA-ONE MP-26-EPI-FAP06-002 Revision 006 Page 3 of 3