ML112030812

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Final Outlines (Folder 3)
ML112030812
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/01/2011
From:
NRC Region 1
To:
JACKSON D RGN-I/DRS/OB/610-337-5306
Shared Package
ML110030662 List:
References
TAC U01832
Download: ML112030812 (21)
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Text

PWR Examination Outline Form ES-401-2

,y: Millstone 3 Date of Exam: July 18th , 2011 RO KIA Category Points SRO-Only Points Tier Group A2 G* Total IK!KIKIKIK:K!A A/A!A G I

I . 1 2 3 . 4 1 5 61 2 ~ 3 I 4

  • 1 Total. I
1. I I 5 11 I Emergency &  ! 1 2 !4 3 ,3 18 3 3 6 Abnormal I 1 Plant 1 Evolutions 2 1 1 1 11 I N/A j2 2 N/A 2 9 ,

2 2 4 Tier I I , I6 Totals 16 2 13 5 I 5 27 5 5 10 I I I I

2. II 1 /5 2 11 5 0 1 ! 4 12 2 I

3 '3 28 3 2 5 Plant ,

Systems I 2 10 0 2 '2 i 3 11 I0 I 1 10 0 1 l 10 2 1 3 I

Tier 1 5 2 3 7 13 2 I 4 I3 I2 3 4 I 38  !

5 3 8 I Totals 1 1 1 1 1

3. Generic Knowledge and 1 2 I1 3 4 I

I 1 2 3 1

Abilities Categories 1

I 4 I I

10 7 2 2 2 4 2 I 1 2 I 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i. e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2. The point total for each 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 2S 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; operational1y important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Sc:ction D of ES-401 for guidance regarding the elimination of inappropriate KIA 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.

S. Absent a plant-specific priority, only those KlAs 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 topies for Tiers 1 and 2 from the shaded systems and KIA categories.
7. '" The generic (G) KI As in Tiers 1 and 2 shall be selected from Seetion 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b of ES-40 1 for the applicable KI As.
8. On the following pages, enter the KIA 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and 1 point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10CFR55.43.

ES-401 2 Form ES-401-2

, ES-401 PWR Examination Outline Fonn ES-40l-2 Emergency and Abnormal Plant Evolutions - Tier I/Group 1 (RO)

I

!IK,K I I E/APE # 1 Name 1 Safety K' A AG KIA Topic(s) IR #

Function 1 2 3 1 2 000007 Reactor Trip 1 Knowledge of the reasons for the actions in 4.0/4.6 1 Stabilization - Recovery 1 I the EOP 000008 Pressurizer Vapor 6 Ability to operate and/or monitor control of 3.6/3.6 2 Space Accident / 3 Pzr level 000009 Small Break LOCA I 4 Ability to operate/monitor CVCS 3.7/3.5 3 3

000011 Large Break LOCA / 2 Knowledge of the interrelations between 2.6/2.7 4 3 pumps and a large break LOCA 000015/17 RCP Malfunctions 1 Ability to determine/interpret the cause of 3.0/3.5 15

/4 RCP failure 000022 Loss of Reactor 2 Ability to detennine/interpret Charging Pump 3.2/3.7 *6 Coolant Makeu~/2 problems 000025 Loss of RHR System I 1 Knowledge of the operational implications of 3.9/4.3 7 4 a loss of ERRS during all modes of operation

, 000026 Loss of Component 2.4.49 Ability to perfonn actions without reference ' 4.6/4.4 8 Cooling Water I 8 to procedures requiring immediate operation i

of system components and controls I i 000029 ATWS / 1 2.4.35 , Knowledge of local auxiliary operator tasks I 3.8/4.0 9 and the resultant operational effects i 000038 Steam Gen. Tube 2.2.37 Ability to determine operability and/or I 3.6/4.6 10 Rupture /3 availabilitJ:: of safetJ:: related eguiEment 000054 Loss of Main 2 Knowledge of the operational implications of 3.6/4.2 11 Feedwater / 4 the effects of feed introduction on a dry SG 000055 Station Blackout / 6 2 Knowledge of the reasons for the actions 4.3/4.6 12 '

contained in the EOP 000057 Loss of Vital AC Elec. 1 Ability to operate and/or monitor manua:! 3.7/3.7 13 Inst. Bus / 6 inverter swapping ,

000058 Loss of DC Power /6 1 Knowledge of the operational implications of 2.8/3.1 14 battery charger equipment/instrumentation 000062 Loss of Nuclear 3 Ability to detennine/interpret valve lineup to 2.6/2.9 15 Service Water / 4 restart SWS with portion of system bypassed 000065 Loss of Instrument Air 1 Ability to operate and/or monitor remote 2.7/2.5 16

/8 manual loaders W/E05 Loss of Secondary 1 Knowledge of ops implication of components, 3.8/4.1 17 Heat Sink / 4 capacity, function of emergency systems 000077 Generator Voltage and 1 Knowledge ofthe operational implications of 3.3/3.5 18 Electric Grid Disturbances / 6 definition of volts, watts, amps, VARs, power factor KIA Category Totals: 5 1 2 4 3 3 Group Point Total: 18

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

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

Function 1 2 3 1 2 000015/17 RCP Malfunctions 7 Ability to determine/interpret 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 determine/interpret plant conditions 4.8 78 Rupture /3 from survey of control room indications 000058 Loss of DC Power /5 2.4.8 Knowledge of how AOPs are used in 4.5 79 coniunction with EOPs W/E11 Loss of Emergency 1 Ability to determine/interpret facility 4.2 80 Coolant Recirc. /4 conditions and selection of appropriate procedure WIE05 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 /4 material KIA Category Totals: 0 0 0 0 3 3 Group Point Total: 6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emer,gency and Abnormal Plant Evolutions - Tier lIGroup 2 (RO)

E/APE # / Name / Safety K. K K A A G KIA Topic(s) IR #

I Function 1 2 3 1 2 000005 Inoperable/Stuck 2 Knowledg'~ of operational implication of 3.l/3.9 19 Control Rod / I flux tilt 000024 Emergency 4 Knowledge of the interrelations between 2.6/2.5 20 Boration 11 emergency boration and EumEs 000033 Loss of 2.4.20 Knowledgl~ of operational implications of 3.8/4.3 21 Intermediate Range NI / 7 EOP warnings, cautions, and notes i 2 Ability to operate andlor monitor ARM 3.113.5

  • 22 IE36 Fuel Handling ident /8 system

. W/E14 Loss ofCTMT 2 Ability to determine/interpret adherence to 3.3/3.S 23 i Integrity I 5 appropriate proeedures WIE 13 Stearn Generator 3 Knowledge of the reasons for manipulation 3.2/3.4 24 Over-pressure I 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 WIE03 Post LOCA 3 Ability to operate andlor monitor for desired 3.7/4.1 26 Cool down Depress. 14 operating results WIEOS RCS Overcooling 1 Ability to determine/interpret selection of 3.4/4.2 27 PTS/4 appropriat<: procedures KIA Category Point Totals: I I I 2 2 12 Group Point Total: 9

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier lIGroup 2 (SRO) i E/APE # / Name / Safety *K K K A A G KIA Topic(s) IR #

Function 2 3 1 2 11 000076 High Reactor Coolant 2 Ability to determine/interpret 3.4 82 i

. Activity / 9 corrective actions for high fission product activity W/E 13 Steam Generator Over- 2.2.40 Ability to apply Technical 4.7 83

. pressure / 4 Specifications for a system I Site Specific Instrument Failure 2.1.23 Ability to perform specific system 4.4 84 i Response AOP 3571/7 and integrated plant procedures during all modes of oQ.eration Site Specific Loss of All AC X Ability to determine/interpret Site 85 Reeovery with the SBO Diesel selection/adherence to appropriate ECA-0.3 /6 procedure KIA Category Point Totals: 2 2 Group Point Total: 4

ES-401 4 Form ES-401-2 I ES-401 PWR Examination Outline Form ES-40l-2 Plant Systems - Tier 2/Group 1 (RO)

III I I System # / Name K ,K KKK K A A A A I* G KiA Topic(s) IR I #

1 2 3 4 5 6 I 234 003 Reactor 10 Predict andJor monitor changes in : 2.512.7 28 Coolant Pump RCP Standpipe level associated I with operating controls 004 Chemical 7 . Predict impact/mitigate isolation of I 3.4/3.7 and Volume I letdown/makeup I Control I 005 Residual 3 Heat Removal I 006 Emergency 2.4.49 i Ability to perform without 4.6/4.4 31

. Core Cooling i , reference immediate actions 007 Pressurizer Physical connections/cause-effel~t 2.9/3.1 32  !

Relief/Quench I between PRT and CTMT System I Tank I I 007 Pressurizer I I I Design feature andJor interlock that 2.6/2.9 33 Relief/Quench i provides for PRT cooling  !

Tank I 008 Component 8 I Predi.ct impact/mitigate the 2.5/2.7 34 Cooling Water

  • shuttmg of the letdown cooler

! isolation valves 008 Component 8 Ability to monitor automatic 3.6/3.7 35 Cooling Water operation due to SIS 01 0 Pressurizer 8 Physical connections/cause-effect 3.2/3.5 36 Pressure Control I between PZR PCS and PZR LCS 012 Reactor 2.4.4 Ability to recognize entry 4.5/4.7 37 Protection conditions for EOPs/AOPs 013 Engineered Knowledge of the effect of a loss I 2.7/3.1 I 38 Safety Features or malfunction of detectors on i Actuation I I ESFAS I 022 Containment I 3 Predict andJor monitor changes in 3.1/3.4 Cooling 026 Containment I' i 2

1 I

1 Containment humidity due to operating controls Knowledge ofthe effect of a loss I 4.2/4.3 40 I Spray I . 4)r ~alfsunction ofCSS on the 1r-______t--+_+--+_+--+_+-::---+_+-~-+--_l_~ec~l~rc~ R pray System,"'-_ _ _._-+___-+_-IJ 026 Containment' I 6 Predict andJor monitor changes in 2.7/3.0 41 Spray I* ,i I I Ctmt Spray Pump cooling I associated with operat=in.:o;;lg;c.;c:.,.:o:,.::n::.:tr:.;:o;:,.:is:...-.+-_ _--!f----1i 039 Main and ,. i ,. ,. II 7 I* Ability to manually operate and/or 2.812.9 . 42 Reheat Steam I monitor steam dump valves Rev. 1

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) Continued

. I  ! I#

System # 1 Name K K K KIK K A I A A A G KIA Topic(s) IR 1 2 3 4 i 5 6 i 1 12 3 4 i 059 Main 4 Physical connections/cause- 3.4/3.4 143 Feedwater effect between MFW and Steam I

I 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 i 5 Ability to monitor automatic 3.5/3.6 45 Electrical Distribution I operation, including safety-related indicators and controls I I i I I 062AC 2.4.l1 Knowledge of abnormal I 4.0/4.2 .46 Electrical condition procedures i

Distribution 063 DC 3 Physical connections/cause- . 2.9/3.5 i 47 II Electrical i effect between DC System and

  • Distribution 063 DC 2 i I I , I battery charger and battery I 2.9/3.2 I i i Knowledge of design features or i 48 Electrical interlocks which provide for Distribution I

breaker interlocks and cross-ties 064 Emergency 1 Physical connectionslcause- 4.1/4.4 49

. Diesel Generator effect between EDG and AC 064 Emergency 10 Ability to manually operate 3.3/3.4 50 Diesel Generator I and/or monitor need i i for/consequences of manual load i I I shedding on safeguards bus I 073 Process 1 Predict and/or monitor changes 3.2/3.5 51 I I Radiation in radiation levels associated i

Monitoring I with operating controls I

076 Service I

Knowledge of power supplies 3.1/3.3 52 8 I Water for ESF-actuated MOVs 076 Service 6 Knowledge of design features or 2.8/3.2 53 Water I i interlocks which provide for 1

i I Service Water train separation 2.7/2.9 54 078 Instrument Knowledge of design features or

. Air interlocks which provide for i

I manual/auto transfer of control 103 Containment

! 3 Ability to manually operate 2.7/2.7 55 i and/or monitor ESF slave relays i KIA Category 5 2 1I5 0 14 2 2 3 3 Group Point Total: 28 Point Totals:

1 11

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

System # / Name K K K K K K A A A A G 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 or equal to one hour Tech Spec action statements for systems 059 Main Feedwater 2.4.4 Ability to recognize 4.7 89 entry conditions for EOPs/AOPs 078 Instrument Air 1 Predict impact/mitigate 2.9 90 air dryer and filter malfunctions KIA Category Point Totals: 0 0 0 0 0 0 0 3 0 10 2 Group Point Total: 5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/0roup 2 (RO)

System # 1 Name K K K K K K A A A A 0 KIA Topic(s) IR #

1 2 13 4 5 6 1 2 3 4 oII Pressurizer Level 4 Knowledge of the effect on 3.113.1 56 Control PLC of a loss or malfunction of pressurizer level controllers 015 Nuclear 2.2.44 Ability to interpret control 4.2/4.4 57 Instrumentation room indications and understand how operator actions affect ~stem and plant 016 Non-nuclear 6 Knowledge of the 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 loss or malfunction ofSOS on the RCS 072 Area Radiation 1 Knowledge of operational 2.7/3.0 62 Monitoring implications of radiation theory, including sources, type, effects 079 Station Air 1 Predict impact/mitigate cross- 2.9/3.2 63 connection with lAS 086 Fire Protection 4 Knowledge of the operational 2.9/3.5 64 implications of hazards to personnel from fire type and methods of protection Site Specific AMSAC x Knowledge of AMSAC design Site 65 features or interlocks KIA Category Point Totals:

0 0 2 2 3 TEo ° 1 Oroup Point Total: 10 Rev. 1

5 Form E8-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/0roup 2 (SRO)

System # / Name K K K K K K A A A A 0 KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 017 In-core 1 Predict impact/mitigate 3.5 91 Temperature Monitor thermocouple open/short circuits 035 Steam Generator 1 Predict impact/mitigate impact 4.6 92 on SOS of faulted or ruptured SGs Site Specific AMSAC 2.4.47 Ability to diagnose and 4.2 93 recognize trends utilizing appropriate control room reference material KIA Category Point 0 0 0 0 0 0 0 2 0 0 1 Group Point Total:

Totals:

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

Category KJA# Topic IR Rod :o-o~1 Ability to coordinate personnel activities outside the control room 2.1.8 I 3.4/4.1 66

1. 2.1.31 Ability to locate control room switches, controls, and indications, 4.6/4.3 67 and to determine they correctly reflect the desired plant lineup Conduct of 2.1.20 Ability to interpret and execute procedure steps 4.6 94 Operations 2.1.41 Knowledge of the refueling PIVvl;;M 3.7 95 2.

Subtotal 2.2.6 Knowledge of the process for making changes to procedures ~ 3.0/3.6 68 2

Equipment 2.2.14 Knowledge ofthe process for controlling equipment configuration or 3.9/4.3 69 status Control 2.2.38 Knowledge of conditions and limitations in the facility license 4.5 96 Knowledge ofless than or equal to one hour Teeh Spec action 2.2.39 4.5 97 statements for :SYMI;;IW; Subtotal Ability to use radiation monitoring systems, such as fixed radiation

~ 2

3. 2.3.5 2.9/2.9 70 monitors and alarms, portable survey instruments, personnel monitoring 1;;'1' . etc.

Radiation 2.3.12 Knowledge of radiological safety principles pertaining to licensed 3.2/3.7 71 operator duties, such as containment entry, fuel handling, access to locked hirth. A:

  • areas, aligning filters, etc.

Control Ability to control radiation releases 4.3 98 12.3.11 4.

Emergency Subtotal 2.4.4 2.4.1 Ability to recognize entry conditions for EOPs/ AOPs Knowledge of EOP entry conditions and immediate action steps Knowledge of operational implications of EOP warnings, cautions,

~2 4.5/4.7 4.6/4.8 72 73

  • 1 Procedures/ 2.4.20 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 4.7 99 Knowledge of the bases for prioritizing emergency procedure 2.4.23 4.4 100 imnlementation during 1;;11,,,,S". vpl;;rations Subtotal er 3 Point Total Rev. 1 I: 4 10 2

7

Fonn ES-40 1-4 Tier I Randomly Reason for Rejection Group Selected KJ A 211 061.K4.14 N/A Millstone 3. No interlocks for Aux Feedwater Isolation at Millstone 3 2/1 026.A1.04 Over-sample ofmonitoring/predicting Containment humidity. Also selectcd 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

211 012.GEN.2.4.3 Generic KIA to identify post-accident instruments is NI A for the RPS system, which is used with the reactor trip breakers closed (pre-accident conditions) 211 026.K3.01 Effect ofCSS malfunction on CCS. N/A Millstone 3. CCS trips on CTMT depressurization signal without input from CSS. Rejection directed by NRC Chief Examiner.

2/2 086.KS.03 Effect of water spray on electrical equipment. Rejection directed by NRC Chief Examiner. Not conducive to discriminating question 3/1 GEN.2.1.34 Knowledge of primary/secondary chemistry limits. Rejection recommended by Ops Rep.

Not conducive to discriminating RO level question 3/2 GEN.2.2.21 Identify pre-post maintenance test requirements: not eart of RO job function

3/4 GEN.2.4.19 Knowledge ofEOP Symbols. Rejection directed by NRC Chief Examiner. Not conducive to discriminating question III SRO APE.022. GEN.2.4 .21 Generic KIA to evaluate safety function is NI A for loss of makeup AOP 111 SRO WIEOS.GEN.2.2.39 Over-sample of <1 hour Tech Specs f.Jr SRO. Also, N/A for loss of heat sink accident 2/1 SRO 004.A2.09 Over-sample of actions for high RCS activity. Also selected in APE.076. A2.02 I

ES-401, Page 27 of33 Rev. 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone 3 Date of Examination: 7/11-7/15/11 Examination Level: RO 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 Ftating: 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 I 4.6 Perform a Manual RCS Leakage Calculation.

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

KfA Rating: 3.7 I 4.1 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 .... ) KfA Rating: 2.9/2.9 Emergency Procedures 1 Plan 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; randomIY;:>vlv,",,,::;J)

ES-301, Page 22 of 27 NUREG-1 021, 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 SROCi] Operating Test Number: 2K11 Administrative Topic Type Describe activity to be performed (see Note) Code*

Administrative Requirements for Shift Mannin';J 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 judgements .... ) KJA Rating: 4.4 / 4.7

_UeJ't,.M.~t. fl<'lllL ~ LC-rL(J6>7'hj Ph&::1effiJ:: .7?r~7.~bil~etermination ~

( A,

  • I.  !'lC.il\ .p.Mefl.c-L very ,;)60 *"

Equipment Control N,R ~~7 ~,A.eilif" ta ej'etsFFRiRQ Q~9Fiilbilit¥ aodlo[ all~ility of sa~ I elated equil'meftl~ 1<1+\ r;;!Elljf'l~r 'i Q I 4.6 SRO A.2 1<',4- Ge" Z.2./8 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 I PARs) KJA 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 retakinq 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-30 1, Page 22 of 27 Dr~i"-4~ P41(~J JfI41 \vc Jei~~ ,f. t...",< -/-I- ps~s~/e q,YI$"vt~J~"- ;/-""""'$ ..JM'i'vlI)-k,...,l.

~ ::rf" ~ r~rJ<t(..e.JJ d nolJ "dVe..,4~ ~ho.jj.,o-le~ cJ."""'7i ~ ~ w-t..... ~ tJ s 7(,,/1, NUREG-1021, Rev 9, Supp 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 i

Facility: Millstone Unit 3 Date of Examination: 7/11/11 Exam Level: RO liJ SRO-I D SRO-U D Operating Test No.: 2'K11 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 / 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/ Perform an RCS Bleed and Feed per FR-H.1 D, A, E, S 3 - 010 i

KiA Number: EPE: EOS - EA 1.1; KiA Rating: 4.1 14.0

d. SAl 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: 4.4/4.4
e. S.5 I SGTR Cooldown Using Atmospheric Steam Relief or Bypass 0, S 4.2 041 valves KiA Number: EPE: 038 - EA1.16; KiA Rating: 4.4/4.3 i
f. S.6/ Respond to High Containment Pressure M,A, EN, 5 - 026 KiA Number: EPE: E14-EA1.1; KiA Rating: 3.7/3.7 S
g. S.7/ Energize SBO Auxiliaries with the SBO Diesel N, S 6 - 062 KiA Number: 062 A 1.01; KiA Rating: 3.4/3.8
h. S.81 Auxiliary Building South Floor Area Fire M,A,E,S 7 - 012 KiA Number: APE: 067 AA2.16; KiA Rating: 3.3/4.0 In-Plant Systems@ (3 for RO); {3 for SRO-Il; (3 or 2 for SRO-U)

P.1 I Establlsn ;:)el Vlv~

t i.

WatArJ~- it:::

vy Tr"";'" UM" y V I III VI oUIiOing Chilled KiA Number: 076 K1.19; KiA Rating: 3.67"':r.7-----...

M, E 4.2 - 076 I i

j. P.21 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.31 Spent Fuel Pool emergency Makeup D, A, E, R 8 - 033 KiA Number: 033 A2.03; KiA Rating: 3.1 13.5

@ 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.

+ RI Re"",,,ove Servi,e \vll.~ c..,b', de 5<J-.p5 Frv-. 5eV'Vi" ~

tA 2. '1. "3 S- 3.~/Lf.O Drijill.' 'JP11 f'leerJ~J n b<- n (J1 4 t<:J cJ'-'<.. ~ fb~t;r.1 Q '--fr'N\:x (A~..JoJ 1c,

...pplicQ.",.t-s. hJ fYV.~hli\y tJ6T1i1.t;..., ouf ~~'" v""I"'f.5) c<<v.sta.J hy ~""'c" f~.,r-

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 I 4-6 1 2-3 (C)ontrol room (D)irect from bank <91 :5;81 :5;4

{E)mergency or abnormal in-plant .:::,11 >1/;:::1 (EN)gineered safety feature - I I;::: 1 (control room system)

(L)ow-Power / Shutdown .:::,1/,2:1/;:::1 (N)ew or (M)odified from bank including 1(A) >2/,2:2/>1 (P)revious 2 exams :5; 3 1 ~ 3 1 :5; 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: 7/11/11 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 I Align Safety Grade Boration Path M,A, E,S 1 - 004 II h ~ ? / Respond to an Inadvertent Containment Isolation Phase 'A' N, E,EN,S 2 - 013 II ':t I Perform an RCS Bleed and Feed per FR-H.1 D,A, E, S 3 - 010 II I Lineup RHR System in the Injection Mode (RCS Leak) D,A,E,S,L 4.1 - 005
e. S.6 I Respond to High Containment Pressure M, A. E, EN, 5 - 026 S
f. S.7 I Energize SBO Auxiliaries with the SBO Diesel N, E,S 6- 062 n ~ R I Auxiliary Buildinq South Floor Area Fire M, A. E, S I 7 - 012

~

'"'. s@ (3 for RO): (3 for SRO-I); (3 or 2 for SRO-U)

h. P.1 / Establish Service Water to Train "B" Control Building Chilled M,E 4.2 - 076 Water Cross Tie
i. P.2/ Primary PEa Actions on a Control Room Evacuation P,D,E, R 6 - 062
j. P.3 / 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 I SRO-I / SRO-U (A)lternate path 4-6 1 4-61 2-3 (C)ontrol room (D)irect from bank  ::::.91 ::::.81 ::::.4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - /- I ~ 1 (control room system)

(L)ow-Power / Shutdown .:::1/.:::1/~1 (N)ew or (M)odified from bank including 1(A) ~2/':::2/~1 (P)revious 2 exams .::: 3 / .::: 3 I ::::. 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.: 2Kt1 Rev 2 II 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 1 Align Safety Grade Boration Path M,A,E,S 1 - 004
b. S.41 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, E, 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.2! 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 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-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room

{D)irect from bank -:5,9/ -:5,81 <4 (E)mergency or abnormal in-plant ~1/~1/>1 (EN)gineered safety feature - I- / ~ 1 (control room system)

(L)ow-Power I Shutdown >1/>1/~1 (N)ew or (M)odified from bank including 1(A) ~21 ~2/'=::1 (P)revious 2 exams < 3 I -:5, 31 < 2 (randomly selected)

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

Appendix D 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 Qlant is at 100% Qower and at the middle of life. The "A" TPCCW QumQ is out of service for oil reQlacement.

Event Malf. No Event Event No. Type* Description 1 'B' MO AFW pump oil leak. (Tech Spec entry) 2 RX10A I (RO) Controlling channel of PZR level fails just below setpoint. (AOP 3571 ) (Tech Spec entry) 3 MS11A I (BOP) 'A' SG Atmospheric Relief Valve pressure channel fails high. (3MSS-PT20A) (Annunciator response, AOP 3571) 4 FW01 R (RO) Loss of condenser vacuum and procedurally directed R (SRO) rapid downpower (5%/min). Vacuum will stabilize.

N (BOP) (AOP 3559, AOP 3575) 5 ED04C C (RO) Loss of emergency bus 34C. (AOP 3577) (Tech Spec C (BOP) entry) 6 RC02D M (ALL) Small break LOCA (220 gpm) inside CTMT. Requires Reactor Trip and Safety Injection. (AOP 3555) 7 TC03 C (BOP) Turbine fails to trip automatically or manually, and MS12D requires a turbine runback.

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

9 FW19 M (ALL) Loss of Secondary Heat Sink. TO AFW pump trips, 'i\'

MD AFW pump deenergized due to loss of bus 34C,

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

  • (N)ormal, (R)eactivity, I)nstrument, (C)omponent, {M}ajor Page 78 of 80

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

Initial Conditions: IC-1B, 100% Power, Middle of life, Eguilibrium Xe.

Turnover:

The Qlant is at 100% Qower and at middle of life. The "A" EDG is out of service for Qlanned 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) (Tech Spec entry) 2 . RX12G I (BOP) 'C' steam generator level channel (controlling) fails low.

(AOP 3571) (Tech Spec entry) 3 SG03B R (RO) 'B' SG Tube Leak (410 gpd), and subsequent R (SRO) procedurally required rapid downpower. (3%/min).

N (BOP) (AOP 3576, AOP 3575) (Tech Spec entry) 4 MS01B M (ALL) 'B' main steam line break in CTMT. Requires Reactor Trip and Safety Injection.

5 RP10AlB C (RO) Automatic and MB7 manual reactor trip switch fail.

RP09B Successful manual reactor trip MB4.

6 RPOBAIB C (BOP) Main Steam line Isolation fails to automaticall):, actuate.

7 I RP11E C (RO) Several HPSI components fail to respond to a Safety In[ection siQnal.

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

  • N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 72 of 74

Appendix 0 Scenario Outline Form ES-D-"

FactTty [  ! S tone 3 M'II S cenar'o

[ No'.. 2K11 NRC-04 Op-Test No'.. 2K11 Examiners: Operators:

-~~-".

Initial Conditions: le-08 (modified}, 7% gower, Beginning of Life, No Xe.

Turnover:

The crew will take the shift with reactor Qower stable and just having entered MODE 1 (reactor Qower 7%1. following a reactor startuQ by the grevious shift. This is the initial gIant startuQ from a refueling outage. OP 3203, Plant StartuQ is in Qrogress.

, Event Malf. Event Event 1 N1o~ No Type'" Description Power increase to place the Main Turbine online using R (RO)

I I R (SRO) OP 3203, Plant Startup. (Section 4.3)

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

! 3 SW01C C (RO) 'C' Service Water Pump trip. (Annunciator response)~-

(TechSe.ec entry) ___

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. (Tech Seec entry2 5 i RC25B C{RO) 'B' RCP high shaft vibration requiring an immediate I C (BOP) shutdown of the affected Rep. (Annunciator response, AOP35~ ____

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

7 I CV13B M (ALL) Small break LOCA inside CTMT (catastrophic loss of

. RC02B 'B' RCP seal package). Safety Injection re-.9uired .

8 . RP07NB* C (RO) Safety Injection fails to automatically actuate.

.9 RP11L ClBOP) Feedwater 's.(Jlation fails to automatically actuate .

10 RC02C C (RO) Large break LOCA inside CTMT. COA fails to auto RP06NB I actuate. .~---

'" Normal, (R)eactivity, I)nstrument, (C)omponent, (M)ajor

- ~~

Lesson

Title:

Large Break LOCA Page 56 of 58

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