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 RE-G-04 RE-G-05 RE-G-06 SA vol-vol 880 gals SA vol-vol 880 gals SA vol-vol 204 gals 90% SA flow - 44 gpm SA flow - 88 gpm SA flow - 20 gpm CEA pos - 180 steps CEA pos - 180 steps C EA pos - 180 steps Time - 20 min. Time - 10 min. Time - 10 min.

0 Rate - 30%/hr Rate - 60%/hr Rate - 60%/hr RE-G-07 RE-G-08 RE-G-09 70% SA vol-vol 2458 gals SA vol-vol 2640 gals SA vol-vol 606 gals SA flow - 44 gpm SA flow - 88 gpm SA flow - 20 gpm I (No CEAs) CEA pos - 180 steps CEA pos - 180 steps C EA pos - 180 steps I

Time - 56 min. Time - 30 min. Time - 30 min.

I Rate - 32%/hr Rate - 60%/hr Rate - 60%/hr I

RE-G-10 RE-G-11 RE-G-12 SA vol-vol 3080 gals SA vol-vol 3315 gals SA vol-vol 720 gals 55% SA flow - 44 gpm SA flow - 88 gpm SA flow - 18 gpm CEA pos - 154 steps C EA pos - 154 steps CEA pos - 154 steps I

Time - 70 min. Time - 38 min. Tinle - 40 min.

Rate - 39%/hr 71 %/hr Rate - 71%/hr Rate - 68%/hr RE-G-13 RE-G-14 RE-G-15 SA vol-vol 4400 gals SA vol-vol 5120 gals SA vol-vol 1100 gals 15% SA flow - 44 gpm SA flow - 88 gpm SA flow - 16 gpm CEA pos - 140 steps CEA pos - 140 steps C EA pos - 140 steps 0 Time - 100 min. min. Time - 58 min. Time - 80 min.

Rate - 51 %/hr Rate - 88%/hr 64 % /hr Rate - 64%/hr

7/29/08 8/6/08 MILLSTONE UNIT 2 EMERGENCY ACTION LEVELS APPROVAL DATE EFFECTIVE DATE GENERAL EMERGENCY ALPHA SITE AREA EMERGENCY CHARLIE-TWO o ALERT CHARLIE-ONE o UNUSUAL EVENT DELTA-TWO D UNUSUAL EVENT DELTA-ONE BARRIER FAILURE fur >

_~_~-nilu-81ai)~

Mode 1, 2, 3, 4 ' O~fOt. Ji,'t5*JiIIffiiIIS ~~.., " "."' . . . '.

LOU GtVa!llP onlDC 1i.Ai8a201A.AIiIlmtB >' 15 Min" ~9!e~~,~a~'

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

~

• ~.\JrJ.Q~,AaIe:on.ne ' SO'mJiVhr

~ ,,1j~~- '. ~

.s; NlA*~,~_fanld_Qffaft8

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

~I I FUEL CLAD OR RCS BARRIER I I1 Mode 1, 2, 3, 4 ~ STATION BLACKOUT II 1-1_--=-ST.:.,:.A.:.,:.T.:.,:IO:..:.N;..;B;;.:LA:....:..;:,C.:..:KO;;:..U;;:..T:.-----II I 6, 0 Mode 5, 6, ~ I AUTOMATIC RX TRIP FAILURE I1 I1 Mode 1, 2 ~ I OFFSITE DOSE II Mode ALL ALERT Automatic Reactor Trip 8NQ Failure of Aulomatic ~ Manual Trip Was Suocessful Successful 1. MP2 Kaman Vent Monitor (RM-8Isa) (RM - 8168) Reading ~ 0.02 f'Cl/cc

~C l/cc CHARLIE - ONE CHARLIE-See Barrier Failure Reference Table Loss ofo f Voltage on o n Bu Buses ses 24C ~ AND 240 24D > 15 Minutes for>

for > 15 Minutes Events are in process or have occurred which

~ I INABILITY TO MAINTAIN COLD SID 1 SID 1II Mode 5, 6 2. MP2 WRGM Site Stack Effluent Activity (RM- 8169) Reading Involve involve an actuaaClua l 0(or potential substantial II PA2 I I SINGLE AC POWER SOURCE II I1 Mode 1, 2,AD 2, 3, 4 1.

1, Uncontrolled RCS Temperature Increase > 10' 10' F That Resu Results lts ~Ci/cc for 2.. 11 f'Ci/cc for> > 15 Minutes degradation of Ihe the level of safety of the plant or a security event that involves probable Hfe life I1 BA2 II1 , - I_ _ STEAM LINE BREAK S_TE_A_M_Ll_NE_B_REA_K_----'11 II Mode 1, 2, 3, 4 O nly On

~ 24D M!!UQ.B On e AC Pow ly One Power er Source Available to Supply Buses 24C 240 > 15 Minutes Such That Loss of That Power 2.

in RCS RCSTemperature Temperature > 200 ' F Inadvertent Criticality

3. MSl Monitor (RM-4299NB/C) Reading ~ 0.03 R/hr MSL for>

10( > 15 Minutes Rlhr threaten ng risk to site personnel or damage to site threatening equipment because of Intentional malicious Uniso lable Steam U ne Break O utside CTMT Unisolable Source Would Result in a Station Blackout (Unit 3 Buses 34NB CANNOT be Credite or 240) 24D)

Credited d unless already aligned to Unit 2 Bus 24C 34N B I ~ ~OSS

~ boss OF OF ANNUNCIATORSfTRANSIEN]

ANNUNC-IA-T-O-R-SIT-RA-N-S-IE-N'i Loss of Most (75%) MCB Annunciators Annunciators>

Mode 1, Mode 1, 2, 2, 3,

> 15 Minutes 8t1Q EITHER of 3, 44 4. Measured Plume Dose Rate Onsile for>

for > 15 Minutes Onsite ~ 5 mR/hr mAthr dedicated efforts of a hosWe hosUie act. Any releases are expected to be limited 10to smalilractions small fractions of the EPA Protective Action Guideline exposure levels.

PrOlective the Following:

Following : 5. Rad Assessment Assessmenl Determines Integrated tntegrated Dose Offsite 2.. 0.005 Rem TEDE OR 2.. 0.025 Rem CDE Thyroid L

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

~ I1-1_ _ _CTMT BARRIER _ _--'II C_T_M_T_B_A_R_RI_E_R II Mode 1, 2, 3, 4 ~ I LOSS OF OFFSITE POWER 1 I 1I Mode ALL ~ I1 LOSS OF COLD SID FUNCTION I I Mode 5, 6 1I L..-......;U;.,.N_P_LA_N_N_E_D_R_EL_E_A..;.S_E_..... Mode ALL UNUSUAL EVENT

1. Loss of Shutdown Cooling> 15 Minutes Illi.Q ~ Refuel Pool "'.

See Barrier Failure Reference Table Loss of all OFFSITE power to buses 24C AND 240 24D for Water Level < 35 Ft., 661n.

tn . EfIIuentMonltCirs In*AllrmORUnDIeMed. UnmonIIored or DELTA- TWO DELTA-TWO

> 15 Minutes Minutes.. 2.

2. Uncontrolled RCS Temperature Increase> 10" IO' F ~Qffallaa. . . ANDDELTMWO PolItulilCoc:fe Urn'"

~

[§J I1-1_ _ _RCS _ _----III I 3.

3. RCS Boron Concentration < Minimum Required as Datetm/ned from EPI-fOAP06, "~and PAfIs."

IaHIad . OR 1.

R_C;.,.S;.,.L_EA_KA_G_E LEAKAGE Pressure Boundary Leakage> 10 GPM Mode 1, 2, 3, 4 jPU2l fPu2lLI_ _ _ LOSS LO_S_S_O_F_D_C OF DC_ _---'I I I1 Mode 5,5, 6 r

[~J EU; I IREFUEUSPENT FUEL POOL LEVELl ""--M-od-e-6-,-0--'

r-1-M-od-e ,-0--'

Nota: e.,aitUlonlto,.bIIoaIa . ReII8te~SeIpoInt DELTA-ONE Events are in process or have occurred which

2. Unidentified Leakage> 10 GPM Loss of Voltage on DC Buses 201 A AND 201 B > 15 Minutes 1. Uncontrolled Spent Fuel Pool Water Level Decrease Causing ~_ ~.eo~""AlHiatIlJ1iIIIh .~ indicate a potential degradation of the level of safety

3. Identified Leakage> 25 GPM Loss of Cooling Suction Flow NDT~ of the plant or indicate a security threat to facility

2. Uncontrolled Refuel Pool Water Level Decrease Requiring protection. No releases of radioactive material

4. Primary to Secondary Leakage >25 > 25 GPM requiring offsite response or monitoring are Containment Evacuation 81iQ81'ill All Spent Fuel Fuet Assemblies in Safe

§~ ] I1 FUEL CLAD DEGRADATION I I 1,--_M_Od_e_A_L_L_-,.

1 Mode ALL Storage Locations expected untess unless funher systems occurs.

further degradation of safety

- ~ II ANNUNCIATO~I LOSS OF ANNUNCIATORS I Mode 1,2,3,4 1 2

1..

1 I1Ci/gm 1-131 DEQ Activity > 60 I-lCi/gm RCS Activity>

2. Dose Rate at One Foot from Un pressurized RCS Loss of Most (75%) MCB Annunciators Annunciators> > 15 Minutes /lli.Q SPDS Q8 ICC Instrumentation Available Sample .2:. 2 mRlhrl mR/hr/ml ml

~ I LOSS OF COMMUNICATIONS I1 I1 Mode ALL Millstone 1.

,. Loss of ALL Onsite Electronic Communications Methods 2.

2. Loss of ALL Electronic Communications Methods With Government Agencies

~ 1 I SHUTDOWN LCO EXCEEDED I1 I Mode 1, 2, 3, 4 II MP-26-EPI-FAP06-002 Revision 006 NOTE: When two or more EALs apply, always choose the EAL EAl of the highest inci dent classification; also always read from top to bottom in each category incident categ ory. Unit NOT Brought To Requ Required ired Mode Within Applicable LCO Action Statement Time Limits Page 1 of 3

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

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

~penn~w'HjS ~1(!~:$OJ)a,.

A'n. ._~*~,~.t8.o~~tbtt*~"*~

~~;=:cr.rm:~u.=.~QN1t GS1 CONTROL ROOM EVACUATION U,m: C~ from HO~$hUt(lOWr\ P*fttt Co10 OF N1 NOt ~nshed W1tI1In is Min,,* After CQfIQ'Ql Room

~

Mode ALL Q1r~" ~,, Eiti6lritled

~ II SPENT FUEL ASSEMBLY DAMAGE II II Mode ALL ~ IIL....-_ _SECURITY EVENT I S:;.;E:;.;C;....;;U_R;...ITY--=E;...V..::.EN;...T~_--II 1I Mode ALL ~ II CONTROL ROOM EVACUATION II Mode ALL ~ IIL....-_ _JUDGEMENT J:....:U;....;;D;....;;G-=E;...M;.::E;.,..N;...T_ _--JI I 1 I Mode ALL ALERT - I Security Events as determined for lor Station Safeguards Contingency 1.

1, Spent Fu el is Exposed from Open Vessel, Fuel Vessel , Cav ity, or SF Pool Cavity, Cont rol Room Evacuation In Control itiated Initiated Any Condition For Which Judgement J udgement Indicates That Safety CHARLIE-ONE Plan and reported reponed by Security Shift Supervision. Supervision , (Addresses events AN D Spent Fuel Has Decayed AND De cayed L 30 Days Aotual or Potential Substantial degradation 10 that Involve Actual to the level of Systems May Be Degraded 8NQ 8MQ Which Requires Em ergency Emergency Events are In prooess process or have occurred which

2. Fuel Handling Handl in g ACCident Causing Damage 10 to Spent Fuel, 2.

safely safety of 01 the plant,)

plant)

A notification from the site security force that an armed attack, anack, 1I GA2 1I 1.... FI;....R.;;;;;E/-=E..XP;....L:....:O.....;.S;....IO;...N~_--II I _ _ _FIRE/EXPLOSION . ;. 1 1I ModeALL~

Mode ALL Respo n se Organizatio Response Organization n Staffing Involve an a.otual or potential involve degradation of the level of potenlial substantial 01 safety of the plant or a Indicated by Fuel Building OR Containment Radiation Mo nitors Monitors Increasing explosive exptosr-e anackattack,, airliner Impact, or other HOSTILE ACTI ON Is ACT10N security event that Involves probable Ilfe life occurring or has occurred within the OCA. Fi re or Explosion Affecting Safe Shutdown Area 8tfQ Fire 8tiQ Damage threatening risk to sile site personnel or damage to site II RA2 1I 11...._ _PLANT P_LA:....;;".N_T_RADIATION R_

AD;.,..I;.,..AT;.,..I..;;,.O;.,..N_----'
1 1I Mode ALL 3. vaHdated notification A validated nOlification from the NRC or than 30 minutes away.

Ihan away_

of an airliner attack threat less Struc tures QB Equipm to Structures Equipment ent In dicated eqUipment because of Intentional malicious equipment efforts of a hostile act. Any releases are dedicated effons 1, Radiation Reading Readings> s > 15 m R/h r in Control Room OR C mR/hr entral Central II TA2 1 I 1 I DESTRUCTIVE PHENOMENA 1I 1I Mode ALL II GA3 1 I 1 I TOXIC/FLAMMABLE GASES II II Mode ALL expected expecled to be limited 10 Protective Action to small fractions of Ihe EPA Act/on GUideline Guideline exposure levels.

Alarm Stat ion Statio n QB Secondary Alarm Station Ufe Threatening Toxic Gases QB Rammable Rammabl e Gas Concentrations 2 ., Radiation Reading> 5 R/ R/hr hr in Areas Requirin g Access fo forr 1. Seismic Event > 0.09g ZPA as Id entified in C - OP 200.5 , *"Oil, Identified Oil, Hazardous Material. Hazardous Safe Shutdown 2,

2. Onsile Sustained Windspeed Onslte Winds peed > 90 MPH Waste and Mixed M ixed Waste Conti ngency Plan" Affecting Areas for 33,. Visible Damage to Structures or Equipmenl Eq uipment AtiQ Affecting Safe Shutdow n Safe Shutdown Shutdown 44.. Vessel or Vehicle ColliSionCollision 8NQ flliQ Affecting Safe Shutdown

5. Missiles Affecting Safe Shutdown

6. Flooding Affecting Safe Shutdown

~ ,-I_ _ _R MONITORS_ _--'II

_A_D_M_O_N_IT_O_R_S RAD I1 Mode ALL ~ 1...._ _SECURITY

~I S_E;....C_U_R_ITY_E_V;...E_NT EVENT _ _--JI1 1 I Mode ALL ~ I~I________FIRE F_IR~E______~I1 I1L-_M_o_de_A_L_L~ Mode ALL ~ J_U_D.....;.G_E_M~E_N_T_ _--'II I I1...._ _ _JUDGEMENT Mode ALL UNUSUAL EVENT 1.

1, Security Events Eve nts as determined delermined for Station Safeguards Contingency 1. Fire in Bui lding OR Areas Adjacent Adjacenl to Areas Areas Needed for Safe Any Condition For Which Judgement Indicates Potential

1. Uncontrolled Refuel Pool Water Level Decrease AND Rad Plan and reported by Security Shift Supervision. (Addresses (Addresses events Shutdown NOT Extinguished Within 15 Minutes of Notification Notificalion QB Degradation in the Level of Safety of the Plant I' DELTA-TWO Levels Require Evacuation of CTMT or Spent Fuel Pool Area that involve Potential degradation in the level of safety of Ihe the plan!.)

plant.) Verification of Control Room Alarms 2;- Fire 2:- AtteC1ing a Loaded ISFSI-eontinement Fire-Affecting ISFSI-eonfinement Boundary NOT OR

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

2. Unexpected Area Rad Monitor Reading Offscale High OR Extinguished Ex1inguished Within 15 Minutes of Notification ., DELTA-ONE

> 1000 Times Normal Reading 3.

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

1I GU2 1 1I I TOXIC/FLAMMABLE GASES I1 1I Mode ALL Events are in process or have occurred which indicate a potential degradation of the level of safety

~ 1I DESTRUCTIVE PHENOMENA 1I I " Mode ALL 1.

t, Life Threatening Toxic Gases QB Flammable Gas Concentrations Concenlrations as indicate a security threal of the plant or indicale threat to facility protect ion . No releases of rad ioactive material prolection.

1.

1, Seismic Activity Detected Per AOP*2562. AOP-2562, Eanhquake Identified in C-OP C- OP 200.5.200.5, "Oil, Hazardous Material. Malerial, Hazardous Waste requiring offsite response or monitoring are

2. Repon by Plant Personnel of Tornado Striking Within Protected Area Report and Mixed Waste Contingency Plan " Affecting AffeCling Normal Operation expected unless further degradation of safety

3. Visible Damage to Structures or Equipment Within the Protected Area 2. Notification 01 of a Near-Site Near*Site Release That May-Require Evacuation systems occurs.

occurs, 2

4. Onsrte Sustained Winds peed > 75 MPH Onsile

5. ExplOSion Within the Protected Area AREAS OF CONCERN FOR SAFE SHUTDOWN

6. Turbine Failure Caus ing Observable Casing Damage Control Room Switchgear Rooms

7. Vessel or Vehicle Collision With Structures OR Equipment Required Cable Vaults for Safe Shutdown or a loaded ISFSI Confinement Boundary Intake Structure Millstone Turbine Building Switchgear Area 8.

8, Flood Level > 19 Feet Mean Sea Level Penetration Areas Coolant Tanks Area 9.

9. Flooding in Areas Containing Safe Shutdown Equipment RBCCW Rooms Containment Diesel Generator Room DC Equipment and Battery Rooms Charging Pump Cubicles MP-26-EPI-FAP06-002 Safety Injection Pump Rooms Switchyard Revision 006 Page 2 of 3

MILLSTONE 2 EMERGENCY ACTION LEVELS BARRIER FAILURE REFERENCE TABLE IMMINENT - No TUrnaround Turnaround in Safety System Performance is Expected AND Escalation to General Emergency Conditions Will Occur Within 2 Hours r---------------------------~

I~----------------~

INDICATORS FUEL CLAD BARRIER RCSBARRIER CTMT BARRIER THREE BARRIERS MORE THAN I FCB1 I I LOSS I I RCB1 I I LOSS I ONE BARRIER SAFETY FUNCTION Not Applicable Not Applicable AFFECTED STATUS/ I POTENTIAL LOSS I FUNCTIONAL II POTENTIAL LOSS I Uncontrolled RCS Cooldown AND RCS Pressure-Temperature To RECOVERY 0 the Left Of the PTS Limit 200° F Subcooling Maximum Curve CUNe 0 No RCS Heat Removal Via Steam Generators 8NQ Alli2 Once Through Cooling NOT Effective AND Shutdown Cooling No RCS Heat Removal Via Steam Generators 8NQ Alli2 Once Through System Is NOT In SeNice Service 0 Cooling NOT Effective AND Shutdown Cooling System Is NOT In Service SeNice I FCB2 I I LOSS I I RCB2 I I LOSS I I CNB1 I I LOSS I 3/3 CORE EXITTC Not Applicable

~

Core Exit Thermocouple Readings > 1300 OF TEMPERATURES [I] ~

[I] RCS Subcooling < 30 ° F I POTENTIAL LOSS I I POTENTIAL LOSS I I POTENTIAL LOSS I ~ Core Exit TC Temperature Readings > 1300°F 8NQ Alli2 Do 0 Core Exit Thermocouple Readings > 800 OF Not Applicable NOT Decrease Within 15 Minutes II RCB3 I I LOSS I I CNB2 I I LOSS I Not Applicable [iJ Rapid Unexplained CTMT Pressure Decrease YES L Following Initial Increase PRESSURE I POTENTIAL LOSS I [iJ No CTMT Pressure Increase When Expectation Exists I POTENTIAL LOSS I 0 Uncontrolled RCS Pressure Decrease and Increasing Containment Radiation Monitors o CTMT Pressure > 10 PSIG 6NQ AND No Containment Spray Pump

~ Increasing o CTMT H2 Concentration ~ 4% TWO BARRIERS I RCB4 I I LOSS I I C NB3 1 1 I LOSS I

[iJ Reactor Coolant Leak > CVCS Capacity AND Entry Into [I]

~ Primary to Secondary > Tech Spec Limits and EITHER exists:

EOP-2534, Steam Generator Tube Rupture or EOP 2540,

• Nonisolable Steam Release from Affected S/G to environment.

Functional Recovery, to Address Steam Generator Tube Rupture I POTENTIAL LOSS I . Prolonged Release From Affected S/G to Environment When Used for Cooldown . (see basis for description of COOLANT prolonged release)

LEAKAGE 0 Reactor Coolant Leak> CVCS Capacity AND Entry Into EOP-2525, Standard Post Trip Actions [I] Failure of BOTH Isolation Valves AND a Pathway to the

~

Environment Exists 0 Reactor Coolant Leak Rate ~ CVCS Capacity At::ill of the following:

N[l EITHER I POTENTIAL LOSS I

.. Entry Into EOP 2534, Steam Generator Tube Rupture Entry Into EOP 2540, Functional Recovery, to Address Steam Generator Tube Rupture o Entry Into EOP-2532, Loss of Primary Coolant, AND Leakage Exists Outside CTMT Requiring Local Isolation 2/3 I FCB3 I I LOSS I I RCB5 I I LOSS I I CNB4 I I LOSS I

~

[I] RM -8240/8241 Reading > 300 R/hr

[iJ RM-8240/8241 Reading > 5 R/hr Without Fuel Clad [I]

~ Offsite Dose Plume Rate ~ 10- 6 Times RM-8240/8241

~

[I] RM-8240/8241 RM -8240/8241 Reading> 5 R/hrWithout R/hr Without RCS Release Barrier Loss Reading if Release is to CTMT ONLY ONE BARRIER AFFECTED InsideCTMT --

~

[I] At Least 5% Fuel Clad Damage As Determined By Core I POTENTIAL LOSS I RADIATION

[JJ Damage Estimate I POTENTIAL LOSS I ALERT

[I] Dose Rate at One Foot from Unpressurized RCS Sample

~ 28 mR/hr/ml Not Applicable o RM-8240/8241 Reading>

Reading > 1,200 R/hr II POTENTIAL LOSS I o At-beast -20%

• 20% Fllel Damage Estimate Fuel Clad Damage As Determined DetefRlined By Core CHARUE-CHARUE Not Applicable ONE I FCB4 I I LOSS I Not Applicable CNB51I I CNB5 I LOSS I CLAD RCS CTMT WATER [I]

~ No CTMT Sump Level Increase When Expectation Exists LEVEL I POTENTIAL LOSS I POTENTIAL LOSS I I P9TENTIAL 0

2

- - 1-UNUSUAL RVLMS Reading = 0% with OPERABLE #8 string (NA if no OPERABLE #8 strinq) Not Applicable EVENT I FCB5 I I RCB6 I IAny CNB61I CNB6 Any Condition For Which Judgement Indicates Loss or Potential Any Condition For Which Judgement Indicates Loss or Potential Condition For Which Judgement Indicates Loss or Potential DELTA-ONE JUDGEMENT .

Loss of Fuel Clad Barrier Due to:

to :

Loss of RCS Barrier Due to :

Loss of CTMT Barrier Due to:

Millstone Imminent Barrier Degradation Based On Current Safety Imminent Barrier Degradation Based On Current Safety Imminent Barrier Degradation Based On Current Safety

. System Performance Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate

. System Performance Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate

. System Performance Degraded Fission Barrier Monitoring Capability Making Barrier Status Indeterminate MP EPI-FAP06-002 Revision 006 Page 3 of 3

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