ML112030734

Draft - Outlines (Folder 2)

ML112030734
Person / Time
Site:	Millstone
Issue date:	06/27/2011
From:	NRC Region 1
To:
JACKSON D RGN-I/DRS/OB/610-337-5306
Shared Package
ML110030662	List: IR 05000423/2011302 ML111860296 ML112030663 ML112030719 ML112030734 ML112030746 ML112030794 ML112030812 ML112030862 ML112031001 ML112490411
References
TAC U01832
Download: ML112030734 (21)

Text

ES-401 PWR Examination Outline Form ES401-2 th Facility: Millstone 3 Date of Exam: July 18 , 2011 RO K/A Category Points SRO-Only Points Tier l.

Group K 1

K 2

KIilllIA 3 1 A

2 A

3 A

4 G

• Total A2 G* Total Emergency & 1 , 1 2 4 3 3 18 3 3 6 Abnormal Plant Evolutions 2 1 1 N/A 2 2 N/A 2 9 2 2 4 Tier 6 2 3 6 ~.

-) 5 27 5 5 10 Totals

2. 1 5 2 1 5 0 1 4 -)

~. 2 3 3 28 3 2 5 Plant Systems 2 0 0 2 2 3 1 0 1 0 0 1 10 2 1 3 Tier 5 2 3 7 3 2 4 3 2 3 4 38 5 3 8 Totals

3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 2 l2T- 2 4 10 2 2 1 2 7

Note: I. Ensure that at least two topics from every applicable KJ A category are sampled within each tier ofthe RO and SRO-only outlines (i. c., cxcept for onc category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KJ A category shan not be lcss than two).

2. Thc point total for eaeh group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D ofES-40l for guidance regarding the elimination of inappropriate KJ A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting as second topic for any system or evolution.

5. Absent a plant-specific priority, only those KJAs having an importance rating (IR) of2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KJ A categories.

7.

• The generic (G) KJAs in Tiers 1 and 2 shan be selected from Section 2 ofthe KJA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b of ES-401 for the applicable KJAs.

8. On the following pages, enter the KJ A numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KJ A catalog, and enter the KJ A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO seli~ctions to KJAs that are linked to 10CFR55.43.

ES-401 2 Form ES-401-2

• ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - TIer IIGroup 1 (RO)

ElAPE#IN,molS,fcty Function K

1 I.-~3 2 G KIA Topic(,) IR #

000007 Reactor Trip 1 Knowledge ofthe reasons for the actions in 4.0/4.6 1 Stabilization - Recovery 1 1 :theEOP 000008 Pressurizer Vapor 6 Ability to operate and/or monitor control of 3.6/3.6 2 Space Accident 1 3 Pzr level reak LOCA 1 4 Ability to operate/monitor CVCS 3.7/3.5 3 3

000011 Large Break LOCA 1 2  :

Knowledge of the interrelations between 3 pumps and a large break LOCA 000015/17 RCP Malfunctions 1 Ability to determine/interpret the cause of 3.0/3.5 5 14 RCP failure 000022 Loss of Reactor 2 Ability to determine/interpret Charging Pump 3.2/3.7 6 Coolant Makeup / 2 problems 000025 Loss ofRHR System / 1 Knowledge ofthe operational implications of 3.9/4.3 7 4 a loss ofRHRS during all modes of operation 000026 Loss of Component 2.4.49 Ability to perform actions without reference 4.6/4.4 8 Cooling Water /8 to procedures requiring immediate operation of system components and controls 29 ATWS /1 2.4.35 Knowledge oflocal auxiliary operator tasks 3.8/4.0 9 and the resultant operational effects am Gen. Tube 2.2.37 Ability to determine operability and/or 3.6/4.6 10 availability of safety related equipment 000054 Loss of Main 2 Knowledge ofthe operational implications of 3.6/4.2

/4 the effects of feed introduction on a dry SG ackout 16 2 Knowledge of the reasons for the actions 4.3/4.6 contained in the EOP 000057 Loss of Vital AC Elec. 1 Ability to operate and/or monitor manual 3.7/3.7 13 Inst. Bus /6 inverter swapping 000058 Loss of DC Power 16 1 Knowledge of the operational implications of 2.8/3.1 14 t=quipmentlin,trumen"tion 000062 Loss of Nuclear 3 mine/interpret valve lineup to 2.6/2.9 15 Service Water 14 .. h portion of system bypassed

~f Instrument Ai< 1 .::

Ability to operate and/or monitor remote 2.7/2.5 16 manual loaders fSecondary 1 Knowledge of ops implication of components, 3.8/4.1 17 capacity, function of emergency systems

• 000077 Generator Voltage and 1 Knowledge of the operational implications of 3.3/3.5 18 Electric Grid Disturbances I 6 definition of volts, watts, amps, V ARs, power factor KIA Category Totals: 5 I 2 4 3 3 Group Point Total:

ES-401 2 Fonn ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (SRO)

E/APE # I Name / Safety K K K A A G KtA Topic(s) IR #

Function 1 2 3 I 2 000015117 RCP Malfunctions 7" Ability to determinelinterpret calculation of 2.9 76

/4 , ....... flow in loop with stopped RCP 000022 Loss of Reactor ... 2.4.6 Knowledge ofEOP mitigation strategies 4.7 77 Coolant Makeup / 2 ....

000038 Steam Gen. Tube 7 Ability to determinelinterpret plant conditions 4.8 78 Rupture 13 trom survey of control room indications 000058 Loss of DC Power 15 2.4.8 Knowledge of how AOPs are used in 4.5 79 conjunction with EOPs W/E11 Loss of Emergency I, Ability to determine/interpret facility 4.2 80

, Coolant Recire. I 4 conditions and selection of appropriate procedure W1E0S Inadequate Heat . . . 2.4.47 Ability to diagnose and recognize trends 4.2 81 Transfer- Loss of Secondary .....

utilizing appropriate control room reference Heat Sink 14 !i X material KIA Category Totals: 0 10 0 0 3 3 Group Point Total: 6

ES-401 3 Fonn ES-401 PWR Examination Outline Fonn ES-401-2 Emergency and Abnonnal Plant Evolutions - Tier l/Group 2 (RO)

E/APE # / Name / Safety K K K A A G

.' KIA Topic(s) IR #

Function 1 2 3 1 2 000005 Inoperable/Stuck 2 I ...... Knowledge of operational implication of 3.113.9 19 Control Rod / 1 .. flux tilt 000024 Emergency 4 .'

2.612.5 20 Boration /1  : ... Knowledge of the interrelations between emergency boration and pumps 3.8/4.3 21 000033 Loss of 2A20 Knowledge of operational implications of i

I' Intennediate Range NI I 7

• EOP warnings, cautions, and notes 000036 Fuel Handling 2 Ability to operate andlor monitor ARM 3.113.5 22

. Accident / 8 .... system W IE 14 Loss of CTMT 2 I*. 3.3/3.8 23 Ability to determine/interpret adherence to Integrity I 5 . '., appropriate procedures W IE 13 Steam Generator 3 > ***** Knowledge ofthe reasons for manipulation 3.2/3.4 24 Over-pressure 1 4 ....... ........... of controls to obtain desired results WIE 16 High Containment 2.4.31.. Knowledge of annunciators, indications, or 4.2/4.1 25 Radiation I 9 ... response procedures W IE03 Post LOCA 3 ....

'.' Ability to operate andlor monitor for desired 3.7/4.1 26 Cooldown Depress. 14 .... operating results W/E08 RCS Overcooling 1 3.4/4.2 27 PTS!4 .... .. Ability to determine/interpret selection of appropriate procedures KIA Category Point Totals: I ! I 1 2 2 2 Group Point Total: 9

-2 ES-401 PWR Examination Outline Fonn ES-401-2 Emergency and Abnonnal Plant Evolutions - Tier I1Group 2 (SRO)

E/APE#/Name/Safety Function

~ K 2

K 3

AA.

1 ~ .***..

(J KIA Topic(s) IR #

000076 High Reactor Coolant 2 ... Ability to determine/interpret 3.4 82 Activity /9 1< < corrective actions for high fission I. ..... product activity W/E 13 Steam Generator Over- 2;2:40 Ability to apply Technical 4.7 83 pressure /4 Specifications for a system Site Specific Instrument Failure ..*... 2:1.23 Ability to perfonn specific system 4.4 84 Response AOP 3571 / 7 and integrated plant procedures during all modes of operation Site Specific Loss of All AC X Ability to determine/interpret Site 85 Recovery with the SBO Diesel *** selection/adherence to appropriate ECA-0.3/6 ....... procedure KIA Category Point Totals: 2 12. Group Point Total: 4

ES-401 4 Form ES-401-2 ES-40l PWR Examination Outline Fonn ES-4OJ-2 Plant Systems - Tier 2/Group 1 fRO)

System # / Name K K K K K K A A A A in. KIA Topic(s) IR #

I 2 3 4 5 6 1 2 3 4 i .....

003 Reactor 10 ** Predict and/or monitor changes in 2.512.7 28 Coolant Pump I,,<<. .

RCP Standpipe level associated with 0 ontrols 004 Chemical 7 Predict impact/mitigate isolation of 3.4/3.7 29 and Volume ....... letdown/makeup Control ......... ....

005 Residual Heat Removal 3

i.<.

Knowledge of power supplies to RCS pressure boundary MOVs 2.712.8 30 006 Emergency 2.4049 Ability to perfonn without 4.6/4.4 31 Core Cooling I reference immediate actions 007 Pressurizer 1 .'. Physical connections/cause-effect 2.9/3.1 32 Relief/Quench I* between PRT and CTMT System Tank 007 Pressurizer I .... Design feature and/or interlock that 2.6/2.9 33 Relief/Quench provides for PRT cooling Tank 008 Component 8 Predict impact/mitigate the 2.5/2.7 34 I Cooling Water ... . shutting ofthc letdown cooler isolation valves

, 008 Component 8 Ability to monitor automatic 3.6/3.7 35 j Cooling Water operation due to SIS I 010 Pressurizer

• Pressure Control 8 Physical connections/cause-effect 3.2/3.5 36 between PZR PCS and PZR LCS I 2.4.4 4.5/4.7 37

• 012 Reactor Ability to recognize entry Protection conditions for EOPs/AOPs 013 Engineered 1 Knowledge of the effect ofa loss 2.7/3.1 38 Safety Features or malfunction of detectors on Actuation ESFAS 022 Containment 3 Predict and/or monitor changes in 3.1/3.4 39 Cooling Containment humidity due to operating controls 026 Containment 1 Knowledge of the effect ofa loss 3.9/4.1 40 Spray or malfunction of CSS on the Ctmt

..... Cooling System 026 Containment 6 Predict and/or monitor changes in 2.7/3.0 41 Spray Ctmt Spray Pump cooling associated with operating controls 039 Main and 7 lity to manually operate and/or 2.8/2.9 42 Reheat Steam nitor steam dump valves

ES-401 4 Form ES-401-2

~ ES-401 PWR Examination Outline Fonn ES-401-2 Plant Systems Tier 2/Group I (RO) Continued System # / Name K K K K K K A A A A KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 ",'c,'

059 Main 4 Physical connections/cause 3.4/3.4 43 Feedwater effect between MFW and Steam Generator Water Level Control 061 Auxiliary/ 8 Knowledge of design features or 2.7/2.9 44 Emergency ""

interlocks which provide for Feedwater ",

, AFW recirculation 062AC 5 Ability to monitor automatic 3.5/3.6 45 Electrical ', .. ,' operation, including safety-Distribution related indicators and controls 062AC i 2.4.11 Knowledge of abnonnal 4.0/4.2 46 condition procedures Electrical Distribution 063 DC 3

'.' . '.' Physical connections/cause 2.9/3.5 47 Electrical .' effect between DC System and Distribution battery charger and battery 063 DC 2 Knowledge of design features or 2.9/3.2 48 Electrical interlocks which provide for Distribution breaker interlocks and cross-ties 064 Emergency 1 Physical connections/cause 4.1/4.4 49 Diesel Generator effect between EDG and AC 064 Emergency 10 ...... 3.3/3.4 50 Ability to manually operate Diesel Generator andlor monitor need forlconsequences of manual load shedding on safeguards bus 073 Process 1 Predict andlor monitor changes 3.2/3.5 51 Radiation in radiation levels associated Monitoring with operating controls 076 Service 8 Knowledge of power supplies 3.113.3 52 Water for ESF-actuated MOVs 076 Service 6 '.

Knowledge of design features or 2.8/3.2 53 Water interlocks which provide for Service Water train separation 078 Instrument I

'.,. Knowledge of design features or 2.7/2.9 54 Air I ','

interlocks which provide for manual/auto transfer of control 103 Containment 3 Ability to manually operate 2.7/2.7 55 andlor monitor ESF slave relays KIA Category 5 2 0 I 4 2 2 3 3 Group Point Total: 28 115 1 Point Totals:

4 Form ES-401-2 ES-401 PWR Examination Outline Fonn ES-401-2 Plant S "stems - Tier 2/Group I SRO)

I System # I Name K K K K K K A A A A KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 .. )

004 Chemical and Volume 28 Predict impact/mitigate 4.3 86 Control  ; .;". ..;............ depressurizing RCS

, while hot 005 Residual Heat Removal 3 .;. Predict impact/mitigate 3.1 87 RHRPump

.. malfunction 013 Engineered Safety 2;2.39 Knowledge ofless than 4.5 88 Features Actuation

.  ;.... >i or equal to one hour Tech Spec action statements for systems 059 Main Feedwater 2.4:4 Ability to recognize 4.7 89 I I*****. entry conditions for

< I EOPs/AOPs 078 Instrument Air 1 Predict impact/mitigate 2.9 90 I;

air dryer and filter

... malfunctions KIA Category Point Totals

0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5

.;./.!

ES-401 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Group 2 (RO)

System # I Name I [5 K K K K K K A A Ai A ******* KJA Topic(s) IR #

1 2 3 4 5 6 I 2 3 ,4 011 Pressurizer Level 4 1,<. > Knowledge of the effect on 3.113.1 56 Control PLC of a loss or malfunction

".,.,' '...' of pressurizer level controllers 015 Nuclear 2.*2044 Ability to interpret control 4.2/4.4 57 Instrumentation I room indications and understand how operator

• • • • • • • actions affect system and plant

.c I> .,<

016 Non-nuclear 6 **'i' .

Knowledge ofthe effect of a 3.5/3.7 58 Instrumentation ..

loss or malfunction ofNNI will have on AFW 027 Containment 1 .. Knowledge of operational 3.113.4 59 Iodine Removal  ; implications of the purpose of

'. charcoal filters 029 Containment Purge 3 Knowledge of design features 3.2/3.5 60

...... or interlocks which provide for automatic purge isolation 035 Steam Generator 1 Knowledge of the effect ofa . 4.4/4.6 61 I

loss or malfunction ofSGS on the RCS 072 Area Radiation 1 ..... Knowledge of operational 2.7/3.0 62 Monitoring implications of radiation I

! , theory, including sources, type, effects i 079 Station Air 1 Predict impact/mitigate cross- 2.9/3.2 63

.. I connection with lAS 086 Fire Protection 3 Knowledge of the operational 3.1/3.4 64 I*', implications of water spray on I

electrical components Site Specific AMSAC x Knowledge of AMSAC design Site 65 I features or interlocks KJA Category Point 0 10 2 2 3 I 0 1 0 0 1 Group Point Total: 10 Totals: I ' .. >

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems Tier 2/Group 2 (SRO)

• *m~* * ;:*~*.

System # / Name K K K K K K A '8, A A KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 017 In-core 3.5 Temperature Monitor 1:. + Predict impact/mitigate thermocouple open/short 91 circuits 035 Steam Generator 1 ******L/ ........

Predict impact/mitigate impact 4.6 92 on SGS of faulted or ruptured

' . / SGs Site Specific AMSAC 2.4.47 Ability to diagnose and 4.2 93 h

recognize trends utilizing appropriate control room reference material

. ' i.

KIA Category Point Totals:

0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Fonn ES-401-3 Facility: Millstone Unit 3 Date of Exam:

Category KiA # Topic RO SRO-Only 1R # 1R #

2.1.8 Ability to coordinate personnel activities outside the control room 3.4/4.1 66 Ability to locate control room switches, controls, and indications,

l. 2.1.31 4.6/4.3 67 and to determine they "Vll"""] reflect the: desired plant lineup Ability to interpret and execute procedure steps Conduct of . 2.1.20 4.6 94 Operations 2.1.41 Knowledge of the H;til~ingprocess 3.7 95 Subtotal 2 2 Knowledge of the process for making changes to procedures

2. 2.2.6 3.0/3.6 68 Equipment 2.2.l4 Knowledge of the process for controlling equipment configuration or 3.9/4.3 69 status Knowledge of conditions and limitations in the facility license Control 2.2.38 4.5 96 Knowledge ofless than or equal to one hour Tech Spec action 2.2.39 4.5 97 statements for systerrts Subtotal 2 Ability to use radiation monitoring systems, such as fixed radiation

3. 2.3.5 2.9/2.9 70 monitors and alarms, portable survey instruments, personnel monitoring equij.J. ;;Ill, etc.

Radiation 2.3.12 Knowledge of radiological safety principlt~s pertaining to licensed 3.2/3.7 71 operator duties, such as containment entry, fuel handling, access to locked hiph-nuii:!tion areas, ali2nill!? filters, etc.

Control Ability to control radiation releases 2.3.11 4.3 98 Subtotal 2 1

4. 2.4.4 Ability to l' i7P entry conditions for EOPs! AOPs 4.5/4.7 72 Emergency 2.4.19 Knowledge ofEOP layout, 1>J1I1Uo1::., and icons 3.4/4.1 73 Procedures/ 2.4.20 Knowledge of operational implications of EOP warnings, cautions, 3.8/4.3 74 and notes.

Plan 2.4.47 Ability to diagnose and recognize trends utilizing appropriate control 4.2/4.2 75 room reference material 2.4.6 Knowledge ofEOP mitigation strategies i

I 4.7 99 Knowledge ofthe bases for prioritizing emergency procedure I 2.4.23 4.4 100 imnlementation during "'l1J"'O"'l1"J Vlwuuw>

Subtotal 4 2 II Tier 3 Point Total 10 7

ES-401 Record of Rejected KJAs Fonn ES-40 1-4 Tier I Randomly Reason for Rejection Group Selected KJ A 2/1 061.K4.14 N/A Millstone 3. No interlocks for Aux Feedwater Isolation at Millstone 3 211 026.Al.04 Over-sample of monitoring/predicting Containment humidity. Also selected in 022.A2.03 2/1 078.K4.02 Over-sample of interlock for swap-over of service air to instrument air. Also selected in 079.A2.01 2/1 012.GEN.2.4.3 Generic KIA to identify post-accident instruments is NIA for the RPS system, which is used with the reactor trip breakers closed (pre-accident conditions) l 3/1 GEN.2.1.34 Knowledge of primary/secondary chemistry limits. Rejection recommended by Ops Rep.

Not conducive to discriminating RO level question Ii 3/2 GEN.2.2.21 Identity pre-post maintenance test requirements: not part of RO job function III SRO APE.022.GEN.2.4.21 Generic KIA to evaluate safety function is Nt A for loss of makeup AOP 111 SRO WIE05.GEN.2.2.39 Over-sample of <1 hour Tech Specs for SRO. Also, NI A for loss of heat sink accident 21l SRO 004.A2.09 Over-sample of actions for high RCS activity. Also selected in APE.076. A2.02 ES-401, Page 27 of33

ES-301 Administrative Topics Outline Form ES-30 1-1 Facility: Millstone 3 Date of Examination: 7/11 - 7/15/11 Examination Level: ROW SRoD Operating Test Number: 2K11 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Determine QPTR, Analyze Results and Make Recommendations.

Conduct of Operations D,S KIA 2.1.19 (Ability to use plant computer to evaluate system or RO A.1.1 component status) KIA Rating: 3.9/3.8 Perform a Shutdown Margin for MODE 3 with One Stuck Control Rod: Xe Correction Required.

Conduct of Operations M,R 2.1.37 (Knowledge of procedures, guidelines associated with RO A.1.2 reactivity management) KiA Rating: 4.3/4.6 Perform a Manual RCS Leakage Calculation.

Equipment Control N,S KIA 2.2.12 (Knowledge of surveillance procedures)

KiA Rating: 3.714.1 ROA.2 P,R Actions and Expected Response for RMS Equipment failure Alarms.

Radiation Control KIA 2.3.5 (Ability to use radiation monitoring systems, such as ROA.3 fixed radiation monitors .... ) KiA Rating: 2.9/2.9 i

Emergency Procedures I Plan Ie:

• 1\ E*

retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( .:::. 3 for ROs; .:::. 4 for SROs & RO retakes)

(N)ew or {M)odified from bank ( ~ 1)

(P)revious 2 exams ( < 1; randomly selected)

ES-301, Page 22 of 27 NUREG-1021, Rev 9, Supp 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone 3 Date of Examination: 7/11 - 7/15/11 Examination Level: ROO SRO[i] Operating Test Number: 2K11 Administrative Topic Type Describe activity to be performed (see Note) Code*

Administrative Requirements for Shift Manning Activities - Working Hour Limitations.

Conduct of Operations M,R KIA 2.1.5 (Ability to use procedures related to shift staffing .... )

SRO A.1.1 KiA Rating: 2.9/3.9 Review a Surveillance for RCS Leakage, Analyze Results and Take Appropriate Action.

Conduct of Operations N,R KIA 2.1.7 (Ability to evaluate plant performance and make SRO A.1.2 operational juclgements .... ) KiA Rating: 4.4/4.7 Perform an Operability Determination.

Equipment Control N,R KIA 2.2.37 (Ability to determine operability and/or availability of safety related equipment) KiA Rating: 3.6/4.6 SRO A.2 Evaluation of an Unplanned Gaseous Release.

Radiation Control N,R KIA 2.3.11 (Ability to control radiation releases)

KiA Rating: 3.8/4.3 SRO A.3 Emergency Plan Classification and Protective Action Recommendation for a General Emergency.

Emergency Procedures I Plan P,D,R KIA 2.4.41 12.4.44 (Knowledge of emergency action level SRO A.4 thresholds, classification / PARs) KiA Rating: 2.9/4.6 ; 2.4/4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom

{D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes)

(N)ew or {M)odified from bank ( ~ 1)

(P)revious 2 exams ( <: 1; randomly selected)

ES-301, Page 22 of 27 NUREG-1021, Rev 9, Supp 1

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 3 Date of Examination: 7/11/11 Exam Level: RO ~ SRO-I D SRO-U D Operating Test No.: 2K11 Rev 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. S.1 I Align Safety Grade Boration Path M, A, E, S 1 - 004 KIA Number: APE: 024 AA1.17; KIA Rating: 3.9/3.9

b. S.2 / Respond to an Inadvertent Containment Isolation Phase 'A' N,E,EN,S 2 - 013 KIA Number: 013 A4.02; KIA Rating: 4.3/4.4

c. S.3 I Perform an RCS Bleed and Feed per FR-H.1 D,A,E,S 3 - 010 KIA Number: EPE: EOS - EA1.1; KIA Rating: 4.1/4.0

d. S.4 I Lineup RHR System in the Injection Mode (RCS Leak) D,A, E,S,L 4.1 - 005 KIA Number: EPE: 009 - EA1.13; KIA Rating: 4.41 4.4

e. S.5 I SGTR Cooldown Using Atmospheric Steam Relief or Bypass 0, E,S 4.2-041 valves KIA Number: EPE: 038 - EA1.16; KIA Rating: 4.4/4.3

f. S.6 I Respond to High Containment Pressure M, A, E, EN, 5 - 026 KIA Number: EPE: E14-EA1.1; KIA Rating: 3.7/3.7 S

g. S.7 I Energize SBO Auxiliaries with the SBO Diesel N,E,S 6 - 062 KIA Number: 062 A1.01; KIA Rating: 3.4/3.8

h. S.8 I Auxiliary Building South Floor Area Fire M,A,E,S 7 - 012 KIA Number: APE: 067 AA2.16; KIA Ratin~:J: 3.3/4.0 In-Plant Systems@ (3 for RO); (3 for SRO-i); (3 or 2 for SRO-U)

i. P.1 I Establish Service Water to Train "B" Control Building Chilled M, E 4.2 - 076 Water Cross Tie KIA Number: 076 K1.19; KIA Rating: 3.6/3.7

j. P.2 / Primary PEO Actions on a Control Room Evacuation P,D,E,R 6 - 062 KIA Number: APE: 068 AA1.14; KIA Rating: 4.2/4.4

k. P.3 / Spent Fuel Pool emergency Makeup 0, A, E, R 8 - 033 KIA Number: 033 A2.03; KIA Rating: 3.1/3.S

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO I SRO-II SRO-U (A)lternate path 4-6 14-6 I 2-3 (C)ontrol room (D)irect from bank <9/ ~81 ~4 (E)mergency or abnormal in-plant ~11 >1/ ~1 (EN}gineered safety feature - /- / ~ 1 (control room system)

(L)ow-Power I Shutdown >11 ~11 ~1 (N)ew or (M)odified from bank including 1(A) ~21 ~21 ~1 (P)revious 2 exams ~ 3/ ~ 3 I ~ 2 (randomly selected)

(R)CA >11 ~11 ~1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 3 Date of Examination: 7111/11 Exam Level: RO D SRO-I LiJ SRO-U D Operating Test No.: 2K11 Rev 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title Type Code* Safety Function

a. S.1/ Align Safety Grade Boration Path M,A,E,S 1 - 004

b. S.2 / Respond to an Inadvertent Containment Isolation Phase 'A' N,E,EN,S 2.- 013

c. S.3 / Perform an RCS Bleed and Feed per FR-H.1 D,A,E,S 3 - 010

d. SA / Lineup RHR System in the Injection Mode (RCS Leak) D,A,E,S,L 4.1 - 005

e. S.61 Respond to High Containment Pressure M,A, EN, 5 - 026 S

f. S.7/ Energize SBO Auxiliaries with the SBO Diesel N,E,S 6 - 062

g. S.8 / Auxiliary Building South Floor Area Fire M,A,E,S 7 - 012 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 fOl' SRO-U)

h. P.1 1 Establish Service Water to Train "B" Control Building Chilled M, E 4.2 - 076 Water Cross Tie

i. P.21 Primary PEO Actions on a Control Room Evacuation P,D,E,R 6 - 062

j. P.31 Spent Fuel Pool emergency Makeup D A, E, R 8 - 033

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-II SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D}irect from bank :5.91 ~81 ~4 (E)mergency or abnormal in-plant ~11 >11 >1 (EN)gineered safety feature - I - I ~ 1 (control room system)

(L)ow-Power 1 Shutdown ~11 ~11 ~1 (N)ew or (M)odified from bank including 1(A) ~21 ~21 ~1 (P)revious 2 exams :5. 3 I ~ 3 I :5. 2 (randomly selected)

(R)CA ~1/~1/~1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 3 Date of Examination: 7/11/11 Exam Level: RO D SRO-I D SRO-U LiJ Operating Test No.: 2K11 Rev 2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title Type Code* Safety Function

a. S.1 I Align Safety Grade Boration Path M,A,E,S 1 - 004

b. SAl Lineup RHR System in the Injection Mode (RCS Leak) D,A,E,S,L 4.1 - 005

c. S.6/ Respond to High Containment Pressure M,A, EN, 5 - 026 S

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

d. P.1 / Establish Service Water to Train "B" Control Building Chilled M,E 4.2 - 076 Water Cross Tie

e. P.21 Primary PEO Actions on a Control Room Evacuation P,D,E,R 6 - 062

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety I functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 14-6 1 2-3 (C)ontrol room (D)irect from bank :5.91:5.8/:5. 4 (E)mergency or abnormal in-plant ~11 ~11 ~1 (EN)gineered safety feature - 1 1 ~ 1 (control room system)

(L)ow-Power I Shutdown >1/~1/>1 (N)ew or (M)odified from bank including 1(A)  ?,.2/?,.2/?,.1 (P)revious 2 exams :5. 3 1 :5. 3 1 :5. 2 (randomly selected)

(R)CA ~11 >1/?,.1 (S)imulator ES-301, Page 23 of 27

Appendix 0 Scenario Outline Form ES-D-1 Facility: Millstone 3 - Scenario No.: 2K11 NRC-01 Op-Test No.: 2K11 Examiners: Operators:

Initial Conditions: IC-18, 100% Power, Middle of life, Eguilibrium Xe.

Turnover:

The I2lant is at 100% 120wer and at the middle of life. The "Au TPCCW l2uml2 is out of service for oil rel2lacement Event Malf. No Event Event No. Type* Description 1 'B' MD AFW pump oil leak. (Tech Spec entry) 2 RX10A I (RO) Controlling channel of PZR level fails just below setpoint. (AOP 3571) 3 I MS11A I (BOP) 'A' SG pressure channel failure. (3MSS-PT20A)

(Annunciator response, AOP 3571) 4 FW01 R (RO) Loss of condenser vacuum and procedurally directed R (SRO) rapid down power (5%/min). Vacuum will stabilize.

N (BOP) (AOP 3559, AOP 3575) 5 ED04C C (RO) Loss of emergency bus 34C. (AOP 3577)

C (BOP) 6 RC02D M (ALL) Small break LOCA inside CTMT. Requires Reactor Trip and Safety Injectio,!. (AOP 3555) 7 TC03 C (BOP) Turbine fails to trip automatically or manually, and requires a turbine runback.

8 S107A1B C (RO) SIH pumps fail to auto-start.

9 FW19 M (ALL) Loss of Secondary Heat Sink. TD AFW pump trips, lA' MD AFW pump deenergized due 'to loss of bus 34C,

'B' MD AFW pump in PTL due to no oil. (success path will be to establish Main Feed)

• (N)ormal, (R )eactivity, (I )nstrument, (C)omponent, (M)ajor AppendiX D, Page 38 of 39

Appendix 0 Scenario OutlinE! Form ES-D-1 Facility: Millstone 3 Scenario No.: 2K11 NRC-02 Op-Test No.: 2K11 Examiners: Operators:

Initial Conditions: IC-18. 100% Power. Middle of life. Equilibrium Xe.

Turnover:

The I2lant is at 100% 120wer and at middle of life. The "Alf EDG is out of service for I2lanned maintenance.

Event Malf. Event Event No. No Type* Description 1 RX05D I (RO) Loop 4 Tavg fails high (loop 4 narrow range Thot).

(AOP 3571) ... _

2 RX12G I (BOP) 'C' steam generator level channel (controlling) fails low.

(AOP 3571) 3 SG03B R(RO) * 'B' SG Tube Leak (AOP 3576), and subsequent R (SRO) procedurally required rapid downpower. (3%/min).

N (BOP) (AOP 3576, AOP 3575}

4 MS01B M (ALL) 'B' main steam line break in CTMT. Requires Reactor Trip and Safety Injection.

5 RP10AlB C (RO) Automatic and IVIB7 manual reactor trip switch fail.

RP09B Successful manual reactor trie Mf?4.

6 RP08A1B C (BOP) Main Steamline Isolation fails to automatically actuate.

7 RP11E C (RO) Several HPSI components fail to respond to a Safety ~

Injection signal.

8 SG01B M (ALL) Hot, dry '8' SG results in a SGTR. Faulted, ruptured I il SG.

I

• (N)ormal, (R )eactivity, (I}nstrument, (C)omponent, (M)ajor Appendix 0, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Millstone 3 Scenario No.: 2K11 NRC-04 (sQare) Op-Test No.: 2K11 Examiners: Opemtors:

Initial Conditions: IC-OB (modified}, 7% 120wer, Beginning of Life, No Xe.

Turnover:

The crew will take the shift with reactor 120wer stable and just having entered MODE 1 (reactor 120wer 7%), following a reactor startul2 by the I2revious shift. This is the initial Qlant startuQ from a refueling outage. OP 3203, Plant Startu{2 is in I2rogress.

Event Malf. Event Event No. No Type* Description 1 R (RO) Power increase to place the Main Turbine online using R (SRO) OP 3203, Plant Startup. (Section 4.3)

N (BOP) 2 NI11 P-10 Permissive failure results in a termination of the startup and Tech Spec 3.0.3 entry.

3 SW01C C (RO) 'C' Service Water Pump trip. (Annunciator response) 4 NI09B I (BOP) Power Range Nuclear Instrument (NI) Channel 42 Lower Detector fails high requiring FRV Bypass valve controllers to be placed in manual. i 5 RC25B C (RO) 'B' RCP high shaft vibration requiring an immediate C (BOP) shutdown of the affected RCP. (Annunciator response,

• AOP 3554) 6 ED01 Loss of offsite power. 'A' Emergency Diesel Generator EG13A C (BOP) (EDG) fails to automatically start and must be manually RP11M started from MB8. BOP must manually close the 'A' and 'B' EDG output breakers.

7 CV13B M (ALL) Small break LOCA inside CTMT (catastrophic loss of RC02B 'B' RCP seal package). Safety Injection required.

8 RP07A1B C (RO) Safety Injection fails to automatically actuate.

9 RP11L C (BOP) Feedwater Isolation fails to automatically actuate.

10 RC02C C (RO) Large break LOCA inside CTMT. CDA fails to auto-RP06A1B actuate.

• (N)ormal, (R )eactivity. (I )nstrument. (C)omponent, (M)ajor Appendix D, Page :~B of 39