ML100670507

Actual Handouts to Applications (Folder 3)

ML100670507
Person / Time
Site:	Millstone
Issue date:	01/15/2010
From:	D'Antonio J 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 vol 880 gals SA flow 44 gpm CEA pos - 180 steps RE-G-05 SA vol 880 gals SA flow 88 gpm CEA pos - 180 steps RE-G-06 SA vol 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 vol 2458 gals SA flow 44 gpm CEA pos - 180 steps RE-G-08 SA vol 2640 gals SA flow 88 gpm CEA pos - 180 steps RE-G-09 SA vol 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 vol 3080 gals SA flow 44 gpm CEA pos - 154 steps RE-G-11 SA vol 3315 gals SA flow 88 gpm C EA pos - 154 steps RE-G-12 SA vol 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 vol 4400 gals SA flow 44 gpm CEA pos - 140 steps Rate - 71%/hr RE-G-14 SA vol 5120 gals SA flow 88 gpm CEA pos - 140 steps Rate - 68%/hr RE-G-15 SA vol 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

7/29/08 8/6/08 MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS APPROVAL DATE 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 FAILURE

~ I LOSS OF COLD SID FUNCTION I I Mode 5, 6

1.

Loss of Shutdown Cooling> 15 Minutes ~ Refuel Pool Water Level < 35 Ft., 61n.

2.

Uncontrolled RCS Temperature Increase> IO' F

3.

RCS Boron Concentration < Minimum Required rEU; I IREFUEUSPENT FUEL POOL LEVELl

""--M-od-e-6-,-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 81'ill All Spent Fuel Assemblies in Safe Storage Locations

~

I LOSS OF ANNUNCIATO~ I Mode 1,2,3,4 Loss of Most (75%) MCB Annunciators> 15 Minutes /lli.Q SPDS Q8 ICC Instrumentation Available

~ I LOSS OF COMMUNICATIONS I I Mode ALL Loss of ALL Onsite Electronic Communications Methods

2. Loss of ALL Electronic Communications Methods With Government Agencies

~

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 from top to bottom in each category Unit NOT Brought To Required Mode Within Applicable LCO Action Statement Time Limits fur >

_~_~-nilu-81ai)~

'O~fOt. Ji,'t5*JiIIffiiIIS ~~.., " "."'.

~9!e~~,~a~ '~

""", *'V*...III.....

• ~

. \\JrJ.Q~,AaIe:on.ne ' SO'mJiVhr

~,,1j~~- '.

~

.s; NlA*~,~_fanld_Qffaft8

. ~ ~.~~_EOR~'Uiefiem'COI!~

~ I I I Mode ALL OFFSITE DOSE

1. MP2 Kaman Vent Monitor (RM-8Isa) Reading ~ 0.02 f'Cl/cc for> 15 Minutes

2. MP2 WRGM Site Stack Effluent Activity (RM-8169) Reading 2.. 1 f'Ci/cc for> 15 Minutes

3. MSL Monitor (RM-4299NB/C) Reading ~ 0.03 Rlhr for> 15 Minutes 4.

Measured Plume Dose Rate Onsite ~ 5 mAthr for> 15 Minutes

5. Rad Assessmenl Determines Integrated Dose Offsite L 0.005 Rem TEDE OR 2.. 0.025 Rem CDE Thyroid EfIIuentMonltCirs In*AllrmORUnDIeMed. UnmonIIored or

~Qffallaa...ANDDELTMWO PolItulilCoc:fe Urn'"

as Datetm/ned from EPI-fOAP06, "~and PAfIs."

IaHIad Nota: e.,aitUlonlto,.bIIoaIa.ReII8te~SeIpoInt

~_~.eo~""AlHiatIlJ1iIIIh.~

NDT~

ALERT CHARLIE-ONE Events are in process or have occurred which Involve an actual or potential substantial degradation of Ihe level of safety of the plant or a security event that involves probable Hfe threatening risk to site personnel or 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 EPA Protective Action Guideline exposure levels.

UNUSUAL EVENT DELTA-TWO OR DELTA-ONE Events are in process or have occurred which indicate 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. 2 Millstone 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 Barrier Failure Reference Table I BA2 II STEAM LINE BREAK II Mode 1, 2, 3, 4 Unisolable Steam Une Break Outside CTMT Mode 1, 2, 3, 4 LOU GtVa!llP onlDC 1i.Ai8a201A.AIiIlmtB >' 15 Min"

~

STATION BLACKOUT Mode 5, 6, 0 II Loss of Voltage on Buses 24C AND 24D > 15 Minutes I PA2 I I SINGLE AC POWER SOURCE I I Mode 1, 2,AD Only One AC Power Source Available to Supply Buses 24C

~ 24D > 15 Minutes Such That Loss of That Power Source Would Result in a Station Blackout (Unit 3 Buses 34NB CANNOT be Credited unless already aligned to Unit 2 Bus 24C I or 24D)

~ I AUTOMATIC RX TRIP FAILURE I I Mode 1, 2 Failure of Automatic Reactor Trip ~ Manual Trip Was Successful

~

I INABILITY TO MAINTAIN COLD SID I I Mode 5, 6

1. Uncontrolled RCS Temperature Increase > 10'F That Results in RCS Temperature > 200' F

2.

Inadvertent Criticality

~ boss OF ANNUNC-IA-T-O-R-SIT-RA-N-S-IE-N'i Mode 1, 2, 3, 4 Loss of Most (75%) MCB Annunciators> 15 Minutes 8t1Q EITHER of the Following:

Significant Transient in Progress LOSS of SPDS AN.O.ICC Instrumentation

~ I II 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

2. Unidentified Leakage> 10 GPM

3. Identified Leakage> 25 GPM

4. Primary to Secondary Leakage > 25 GPM

§] I FUEL CLAD DEGRADATION I I Mode ALL 1. RCS Activity> 60 I1Ci/gm 1-131 DEQ

2. Dose Rate at One Foot from Unpressurized RCS Sample.2:. 2 mRlhrl ml

~ 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 Barrier Failure Reference Table 1 BA2 1,-I __

S_TE_A_M_Ll_NE_B_REA_K_----'11 Mode 1, 2, 3, 4 Unisolable Steam Une Break Outside 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-lCi/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 of Voltage on Buses 24C ~

240 > 15 Minutes I PA2 I I SINGLE AC POWER SOURCE I 1 Mode 1, 2, 3, 4 Only One AC Power Source Available to Supply Buses 24C M!!UQ.B 240 > 15 Minutes Such That Loss of That Power Source Would Result in a Station Blackout (Unit 3 Buses 34N B CANNOT be Credited unless already aligned to Unit 2 Bus 24C 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 Failure of Aulomatic Reactor Trip 8NQ Manual Trip Was Suocessful

~

1 INABILITY TO MAINTAIN COLD SID I 1 Mode 5, 6 1,

Uncontrolled RCS Temperature Increase > 10' F That Results in RCSTemperature > 200' F

2.

Inadvertent Criticality

~

~OSS OF ANNUNCIATORSfTRANSIEN]

Mode 1, 2, 3, 4 Loss of Most (75%) MCB Annunciators > 15 Minutes EITHER of the Following:

Significant Transient in Progress LOSS of SPDS AMl ICC Instrumentation

~

1 LOSS OF COLD SID 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 Increase> 10"F

3.

RCS Boron Concentration < Minimum Required

[~J IREFUEUSPENT FUEL POOL LEVELl r-1-M-od-e-6-,-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 Annunciators > 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 Electronic Communications Methods With Government Agencies NOTE: When two or more EALs apply, always choose the EAL of the highest incident classification; also always read from top to bottom in each category.

~

1 SHUTDOWN LCO EXCEEDED 1 I Mode 1, 2, 3, 4 I Unit NOT Brought To Required Mode Within Applicable LCO Action Statement Time Limits o UNUSUAL EVENT DELTA-TWO Mode ALL

1.

MP2 Kaman Vent Monitor (RM-8168) Reading ~ 0.02 ~C l/cc for > 15 Minutes

2.

MP2 WRGM Site Stack Effluent Activity (RM-8169) Reading 2..1 ~Ci/cc for > 15 Minutes

3.

MSl Monitor (RM-4299NB/C) Reading ~ 0.03 R/hr 10( > 15 Minutes 4.

Measured Plume Dose Rate Onsile ~ 5 mR/hr for > 15 Minutes

5.

Rad Assessment Determines tntegrated Dose Offsite 2.. 0.005 Rem TEDE OR 2.. 0.025 Rem CDE Thyroid 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 Events are in process or have occurred which involve an aClual 0(

potential substantial degradation of the level of safety of the plant or a security event that involves probable life threaten ng risk to site personnel or damage to site equipment because of Intentional malicious dedicated efforts of a hosWe act. Any releases are expected to be limited 10 smalilractions of the EPA PrOlective Action Guideline exposure levels.

UNUSUAL EVENT DELTA-TWO OR DELTA-ONE Events are in process or have occurred which indicate 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 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 FIRE/GASES JUDGEMENT

=**~t;mrt'Sp'rf,~t'lY~;~ :eQ1H

~penn~w 'HjS ~1(!~ :$OJ)a,.

Q1r~" ~,,Eiti6lritled

~ ISPENT FUEL ASSEMBLY DAMAGE I I Mode ALL 1, Spent Fuel is Exposed from Open Vessel, Cavity, or SF Pool AND Spent Fuel Has Decayed L 30 Days

2. Fuel Handling ACCident Causing Damage 10 Spent Fuel, Indicated by Fuel Building OR Containment Radiation Monitors Increasing I RA2 1 1 PLANT RADIATION 1 1 Mode ALL 1, Radiation Readings> 15 mR/hr in Control Room OR Central Alarm Station QB Secondary Alarm Station 2, Radiation Reading> 5 R/hr in Areas Requiring Access for Safe Shutdown

~

RAD MONITORS I 1 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 A'n.._~*~,~.t8.o~~tbtt *~"*~

~~;=:cr.rm:~u.=.~QN1t

~ I I 1 SECURITY EVENT Mode ALL Security Events as determined for Station Safeguards Contingency Plan and reponed by Security Shift Supervision, (Addresses events that Involve Actual or Potential Substantial degradation 10 the level of safety 01 the plant)

2. A notification from the site security force that an armed attack, exptosr-e attack, airliner Impact, or other HOSTILE ACT10N Is occurring or has occurred within the OCA.

3. A vaHdated notification from the NRC of an airliner attack threat less Ihan 30 minutes away.

I TA2 1 1 DESTRUCTIVE PHENOMENA 1 1 Mode ALL

1.

Seismic Event > 0.09g ZPA 2,

Onslte Sustained Windspeed > 90 MPH 3,

Visible Damage to Structures or Equipmenl AtiQ Affecting Safe Shutdown

4. Vessel or Vehicle Collision 8NQ Affecting Safe Shutdown

5. Missiles Affecting Safe Shutdown

6. Flooding Affecting Safe Shutdown

~ 1 SECURITY EVENT 1 1 Mode ALL 1, Security Events as delermined for Station Safeguards Contingency Plan and reported by Security Shift Supervision. (Addresses events that involve Potential degradation in the level of safety of Ihe plan!.)

2.

A credible site specific s'ecurity threat notific*alion.

3, A validated notification from the NRC providing information of an aircraft threat.

~

1 DESTRUCTIVE PHENOMENA 1 "

Mode ALL 1, Seismic Activity Detected Per AOP-2562, Eanhquake

2. Report by Plant Personnel of Tornado Striking Within Protected Area

3. Visible Damage to Structures or Equipment Within the Protected Area

~ I CONTROL ROOM EVACUATION I Mode ALL Control Room Evacuation Initiated 1GA2 1 I FIRE/EXPLOSION 1 1 ModeALL~

Fire or Explosion Affecting Safe Shutdown Area 8tiQ Damage to Structures QB Equipment Indicated I GA3 1 1 TOXIC/FLAMMABLE GASES I I Mode ALL Ufe Threatening Toxic Gases QB Rammable Gas Concentrations as Identified in C - OP 200.5, "Oil, Hazardous Material. Hazardous Waste and Mixed Waste Contingency Plan" Affecting Areas for Safe Shutdown

~ I FIRE 1 I Mode ALL

1.

Fire in Building OR Areas Adjacenl to Areas Needed for Safe Shutdown NOT Extinguished Within 15 Minutes of Notificalion QB Verification of Control Room Alarms 2:- Fire-Affecting a Loaded ISFSI-eonfinement Boundary NOT Ex1inguished Within 15 Minutes of Notification, 1GU2 1 1 TOXIC/FLAMMABLE GASES 1 1 Mode ALL t, Life Threatening Toxic Gases QB Flammable Gas Concenlrations as Identified in C-OP 200.5, "Oil, Hazardous Malerial, Hazardous Waste and Mixed Waste Contingency Plan " AffeCling Normal Operation

2. Notification 01 a Near*Site Release That May-Require Evacuation

~ I I 1 JUDGEMENT Mode ALL Any Condition For Which Judgement Indicates That Safety Systems May Be Degraded 8MQ Which Requires Emergency Response Organization Staffing

~ I I I JUDGEMENT Mode ALL Any Condition For Which Judgement Indicates Potential Degradation in the Level of Safety of the Plant ALERT

- I CHARLIE-ONE Events are In prooess or have occurred which involve an a.otual or potenlial substantial degradation of the level 01 safety of the plant or a security event that Involves probable Ilfe threatening risk to sile personnel or damage to site equipment because of Intentional malicious dedicated effons of a hostile act. Any releases are expecled to be limited to small fractions of Ihe EPA Protective Action GUideline exposure levels.

UNUSUAL EVENT I'

DELTA-TWO OR DELTA-ONE Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicale a security threal to facility prolection. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs,

4.

Onsrte Sustained Winds peed > 75 MPH

5. ExplOSion Within the Protected Area

6.

Turbine Failure Causing Observable Casing Damage

7.

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 Rooms 2

for Safe Shutdown or a loaded ISFSI Confinement Boundary 8,

Flood Level > 19 Feet Mean Sea Level

9. Flooding 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.

Spent Fuel is Exposed from Open Vessel, Cavity, or SF Pool AND Spent Fuel Has Decayed L 30 Days

2.

Fuel Handling ACCident Causing Damage to Spent Fuel, Indicated by Fuel Building OR Containment Radiation Monitors Increasing I RA2 I....

1 __

P_LA:....;;".N_T_R_

AD;.,..I;.,..AT;.,..I..;;,.O;.,..N_----'

I Mode ALL 1,

Radiation Readings > 15 mR/hr in Control Room OR Central Alarm Station QB Secondary Alarm Station

2.

Radiation Reading> 5 R/hr in Areas Requiring Access for Safe Shutdown

~

,-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....-__

S:;.;E:;.;C;....;;U_R;...ITY--=E;...V..::.EN;...T~_--II I

Mode ALL Security Events as determined lor Station Safeguards Contingency Plan and reported by Security Shift Supervision. (Addresses events that Involve Aotual or Potential Substantial degradation to the level of safely of the plant,)

2.

A notification from the site security force that an armed anack, explosive anack, airliner Impact, or other HOSTILE ACTION Is occurring or has occurred within the OCA.

3.

A validated nOlification from the NRC or an airliner attack threat less than 30 minutes away_

I TA2 I I DESTRUCTIVE PHENOMENA I I Mode ALL

1.

Seismic Event > 0.09g ZPA

2.

Onsile Sustained Winds peed > 90 MPH

3.

Visible Damage to Structures or Equipment Affecting Safe Shutdown

4.

Vessel or Vehicle ColliSion flliQ Affecting Safe Shutdown

5.

Missiles Affecting Safe Shutdown

6.

Flooding Affecting Safe Shutdown

~I S_E;....C_U_R_ITY_E_V;...E_NT __

--JI I

Mode ALL

1.

Security Events as determined for Station Safeguards Contingency Plan and reported by Security Shift Supervision. (Addresses events that involve Potential degradation in the level of safety of the plant.)

2.

A credible site specific s'ecurily threat notific*ation.

3.

A validated notification from the NRC providing information of an aircraft threat.

~

I DESTRUCTIVE PHENOMENA II Mode ALL

1.

Seismic Activity Detected Per AOP*2562. Eanhquake

2.

Repon by Plant Personnel of Tornado Striking Within Protected Area

3.

Visible Damage to Structures or Equipment Within the Protected Area

4.

Onsile Sustained Winds peed > 75 MPH FIRE/GASES GS1 CONTROL ROOM EVACUATION Mode ALL U,m: C~

from HO~$hUt(lOWr\\ P*fttt Co10 OF N1 NOt ~nshed W1tI1In is Min,,* After CQfIQ'Ql Room

~

~

I CONTROL ROOM EVACUATION I Mode ALL Control Room Evacuation Initiated I GA2 I....

1 ___

FI;....R.;;;;;E/-=E.....;.

XP;....L:....:O.....;.S;....IO;...N~_--II I

Mode ALL Fire or Explosion Affecting Safe Shutdown Area 8tfQ Damage to Struc tures QB Equipment Indicated I GA3 I I TOXIC/FLAMMABLE GASES I I Mode ALL Ufe Threatening Toxic Gases QB Rammable Gas Concentrations as Identified in C-OP 200.5,

• Oil, Hazardous Material. Hazardous Waste and Mixed Waste Contingency Plan" Affecting Areas for Safe Shutdown

~

~I ________

F_IR~E ______ ~I 1L-_M_o_de_A_L_L~

1.

Fire in Building OR Areas Adjacent to Areas Needed for Safe Shutdown NOT Extinguished Within 15 Minutes of Notification QB Verification of Control Room Alarms 2;-

Fire AtteC1ing a Loaded ISFSI-eontinement Boundary NOT Extinguished Within 15 Minutes of Notification.

I GU2 I I TOXIC/FLAMMABLE GASES I I Mode ALL

1.

Life Threatening Toxic Gases QB Flammable Gas Concentrations as Identified in C-OP 200.5. "Oil, Hazardous Material. Hazardous Waste and Mixed Waste Contingency Plan" Affecting Normal Operation

2. Notification of a Near-Site 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 Any Condition For Which Judgement Indicates That Safety Systems May Be Degraded 8NQ Which Requires Emergency Response Organization Staffing

~

1 ___

J_U_D.....;.G_E_M~E_N_T __

--'I I Mode ALL Any Condition For Which Judgement Indicates Potential Degradation in the Level of Safety of the Plant ALERT CHARLIE-ONE Events are In process or have occurred which Involve an a.otual or potential substantial degradation of the level of safety of the plant or a security event that Involves probable life threatening risk to site personnel or damage to site eqUipment because of Intentional malicious dedicated efforts of a hostile act. Any releases are expected to be limited 10 small fractions of Ihe EPA Protective Act/on Guideline exposure levels.

UNUSUAL EVENT DELTA-TWO OR DELTA-ONE Events are in process or have occurred which indicate 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.

5.

ExplOSion Within the Protected Area AREAS OF CONCERN FOR SAFE SHUTDOWN 2

6.

Turbine Failure Causing Observable Casing Damage

7.

Vessel or Vehicle Collision With Structures OR Equipment Required for Safe Shutdown or a loaded ISFSI Confinement Boundary

8.

Flood Level > 19 Feet Mean Sea Level

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 Removal 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 Effective AND Shutdown Cooling System Is NOT In Service CORE EXITTC TEMPERATURES I FCB2 I I LOSS I

~

Core Exit Thermocouple Readings > 1300 OF 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 CNB3 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 I~----------------~

MORE THAN THREE BARRIERS ONE BARRIER AFFECTED 3/3 YES TWO BARRIERS ONLY ONE BARRIER AFFECTED ALERT CHARUE ONE CLAD RCS CTMT 2

UNUSUAL EVENT DELTA-ONE MP 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 Subcooling Maximum CUNe 0

No RCS Heat Removal 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 Effective 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 OF

[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 CNB3 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-r---------------------------~

THREE BARRIERS 3/3 YES TWO BARRIERS 2/3 MORE THAN ONE BARRIER AFFECTED ONLY ONE BARRIER AFFECTED CLAD RCS 2

Millstone ALERT CHARUE-ONE UNUSUAL EVENT DELTA-ONE MP EPI-FAP06-002 Revision 006 Page 3 of 3