ML18074A366

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Final Outlines (Folder 3)
ML18074A366
Person / Time
Site: Millstone Dominion icon.png
Issue date: 11/27/2017
From: Peter Presby
Operations Branch I
To:
Dominion Energy Nuclear Connecticut
Shared Package
ML17094A469 List:
References
CAC U01946
Download: ML18074A366 (17)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone Unit 3 Date of Exam: December 4, 2017 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

1 3

3 3

3 3

3 18 3

3 6

Emergency and Abnormal Plant 2

1 1

2 N/A 2

2 N/A 1

9 2

2 4

Evolutions Tier Totals 4

4 5

5 5

4 27 5

5 10 1

2 3

2 3

3 2

3 3

1 3

3 28 3

2 5

2.

Plant 2

1 1

0 1

1 1

1 1

1 1

1 10 2

1 3

Systems Tier Totals 3

4 2

4 4

3 4

4 2

4 4

38 5

3 8

3. Generic Knowledge and Abilities 1

2 3

4 10 i

2 3

4 7

Categories 3

2 2

3 1

2 2

2 Note: 1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

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 25 points.

3.

Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b 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 a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those Kl As having an importance rating (IR) of 2.5 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 K/A categories.

7.

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.

8.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' I Rs 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 a category 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 K/A catalog and enter the K/A numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic KIAs These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 2

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

E/APE # / Name I Safety Function K1 K2 K3 A1 A2 G*

KIA Topic(s)

IR 000007 (EPE 7; BW E02&E10; CE E02) 5 Decay power as a function of time 3.3/3.8 1 Reactor Trip, Stabilization, Recovery/ 1 000008 (APE 8) Pressurizer Vapor Space 8

PRT level pressure and temperature 3.8/3.8 2 Accident/ 3 000009 (EPE 9) Small Break LOCA / 3 21 Actions contained in EOP for small break 4.2/4.5 3 LOCA/leak 000011 (EPE 11) Laroe Break LOCA / 3 11 Conditions for throttlino or stoppino HPI 3.9/4.3 4 000015 (APE 15) Reactor Coolant Pump 1

Cause of RCP failure 3.0/3.5 5 Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant 4

Reason for changing from manual to,3utomatic 2.9/3.0 6 Makeup/ 2 control of charging flow valve controller 000025 (APE 25) Loss of Residual Heat 3

LPI pumps 3.4/3.3 7 Removal System I 4 000026 (APE 26) Loss of Component 2.1.27 Knowledge of system purpose and or function. 3.9/4.0 8 Coolino Water/ 8 000027 (APE 27) Pressurizer Pressure 3

Controllers and positioners 2.6/2.8 9 Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient 6

Breakers, relays, and disconnects.

2.9/3.1 10 Without Scram / 1 000038 (EPE 38) Steam Generator Tube 2

Leak rate vs. pressure drop 3.2/3.5 11 Rupture/ 3 000054 (APE 54; CE E06) Loss of Main 4

Actions contained in EOPs for loss of MFW 4.4/4.6 12 Feedwater /4 000056 (APE 56) Loss of Offsite Power I 6 20 AFW flow indicator 3.9/4.1 13 000057 (APE 57) Loss of Vital AC 2.2.37 Ability to determine operability and/or 3.6/4.6 14 Instrument Bus/ 6 availability of safety related equipment.

The conditions that will initiate the automatic 000062 (APE 62) Loss of Nuclear Service 1

opening and closing of the SWS isolation 3.2/3.5 15 Water I 4 valves to the nuclear service water coolers 000065 (APE 65) Loss of Instrument Air/ 8 4

Emergency air comoressor 3.5/3.4 16 (BW E04; W E05) Inadequate Heat 2

Facility's heat removal systems, including 3.9/4.2 17 primary coolant, emergency coolant. the decay Transfer-Loss of Secondary Heat Sink/ 4 heat removal systems and relations between the proper operation of these systems to the operation of the facility.

000040 (APE 40; BW E05; CE E05; W E12) 2.4.3 Knowledge of local auxiliary operator tasks 3.8/4.0 18 during emergency and the resultant Steam Line Rupture-Excessive Heat operational effects Transfer/ 4 000008 (APE 8) Pressurizer Vapor Space 2.4.46 Ability to verify that the alarms are consistent 4.2 76 Accident/ 3 with the plant conditions.

000025 (APE 25) Loss of Residual Heat 4

Location and isolability of leaks 3.6 77 Removal System / 4 000056 (APE 56) Loss of Offsite Power/ 6 2.4.50 Ability to verify system alarm setpoints and 4.0 78 operate controls identified in the alarm response manual.

000038 (EPE 38) Steam Generator Tube 2

Existence of an SIG tube rupture and its 4.8 79 Rupture/ 3 potential consequences

ES-401 3

Form ES-401-2 2.4.20 Knowledge of operational implications of EOP 4.3 80 (W E04) LOCA Outside Containment/ 3 waminas. cautions and notes.

1 Facility conditions and selection of appropriate 4.4 81 (BW E04; W E05) Inadequate Heat procedures during abnormal and emergency Transfer-Loss of Secondary Heat Sink/ 4 operations.

KIA Cateaorv Totals:

3 3

3 3

3/3 3/3 Grouo Point Total:

18/6

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-4 Emeroencv and Abnormal Plant Evolutions-Tier 1/Grouo 2 RO/SRO)

E/APE # / Name/ Safety Function K1 K2 K3 A1 A2 G*

KIA Topic(s)

IR AOP 3571, Instrument Failure Response 2

Ability to operate and/or 3.3/3.6 19 monitor the following as they apply to an instrument failure response: operating behavior characteristics of the facilitv 000036 (APE 36; BW/A08) Fuel-Handling Incidents/ 8 3

Guidance contained in EOP 3.7/4.1 20 for fuel handlino incident 000059 (APE 59) Accidental Liquid Radwaste Release/ 9 2.1.7 Ability to evaluate plant 4.4/4.7 21 performance and make operational judgments based on operating characteristics, reactor behavior and instrument i nteroretation..

AOP 3550, Turbine Trip 2

Ability to operate and/or 3.3/3.6 22 monitor the following as they apply to a turbine trip:

operating behavior characteristics of the facility.

(W E01 & E02) Rediagnosis & SI Termination/ 3 1

Components and functions 3.4/3.9 23 of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

(BW E08; W E03) LOCA Cooldown-Depressurization / 4 2

Adherence to appropriate 3.5/4.1 24 procedures and operation within the limitations in the facility's license and amendments.

(W E13) Steam Generator Overpressure/ 4 2

Normal, abnormal and 2.9/3.3 25 emergency operating procedures associated with (Steam Generator Overpressure).

000069 (APE 69; W E14) Loss of Containment Integrity/ 5 1

Components, capacity, and 3.3/3.6 26 function of emergency svstems.

(W E16) High Containment Radiation /9 2

Adherence to appropriate 3.0/3.3 27 procedures and operation within the limitations in the facility's license and amendments.

000001 (APE 1) Continuous Rod Withdrawal / 1 5

Uncontrolled rod withdrawal, 4.6 82 from available indications 000076 (APE 76) High Reactor Coolant Activity I 9 2.4.41 Knowledge of the emergency 4.6 83 action level thresholds and classifications.

(BW EOS; W E03) LOCA Cooldown-Depressurization / 4 1

Facility conditions and 4.2 84 selection of appropriate procedures during abnormal and emeroency operations.

000069 (APE 69: W E14) Loss of Containment Integrity/ 5 2.4.21 Knowledge of the 4.6 85 parameters and logic used to assess the status of safety functions IK/A Category Point Totals:

I 1 I 1 12 12 1212 !112 I Group Point Total:

I 1914 I

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S,stems-Tier 2/Group 1 (RO/SRO)

System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

KIA Topic(s)

IR 003 (SF4P RCP) Reactor Coolant 7

RCS temperature and pressure 3.4/3.4 28 Pump Effects of RCP shutdown on T-ave.,

003 (SF4P RCP) Reactor Coolant 3

including the reason for the unreliability 3.1/3.5 29 Pump of T-ave. in the shutdown loop 004 (SF1; SF2 CVCS) Chemical and 31 Purpose of flow path around boric acid 3.0/3.4 30 Volume Control storage tank 005 (SF4P RHR) Residual Heat 2

Modes of operation 3.2/3.5 31 Removal 006 (SF2; SF3 ECCS) Emergency 2

Valve operators for accumulators 2.5/2.9 32 Core Coolinq 007 (SF5 PRTS) Pressurizer 1

Quench tank cooling 2.6/2.9 33 Relief/Quench Tank 008 (SF8 CCW) Component Cooling 2.1.23 Ability to perform specific system and 4.3/4.4 34 integrated plant procedures during all Water modes of plant operation.

008 (SF8 CCW) Component Cooling 2.1.31 Ability to locate control room switches, 4.6/4.3 35 controls and indications and to Water determine that they are correctly reflectinq the desired plant lineup.

01 O (SF3 PZR PCS) Pressurizer 1

PZR heaters 3.0/3.4 36 Pressure Control 012 (SF? RPS) Reactor Protection 1

Trip setpoint adjustment 2.9/3.4 37 012 (SF? RPS) Reactor Protection 1

DNB 3.3/3.8 38 013 (SF2 ESFAS) Engineered 1

ESFAS/safeguards equipment control 3.6/3.8 39 Safety Features Actuation 013 (SF2 ESFAS) Engineered 1

Sensors and detectors 2.7/3.1 40 Safety Features Actuation 022 (SF5 CCS) Containment Cooling 1

Containment equipment subject to 2.9/3.2 41 damage by high or low temperature, humidity and pressure 026 (SF5 CSS) Containment Spray 5

Containment spray reset switches 3.5/3.5 42 039 (SF4S MSS) Main and Reheat 5

Increasing steam demand, its 3.3/3.6 43 relationship to increases in reactor Steam power 039 (SF4S MSS) Main and Reheat 7

Reactor building isolation 3.4/3.7 44 Steam 059 (SF4S MFW) Main Feedwater 7

Feed Pump speed, including normal 2.5/2.6 45 control speed for ICS 061 (SF4S AFW) 1 Controllers and positioners 2.5/2.8 46 Auxiliarv/Emerqency Feedwater 062 (SF6 ED AC) AC Electrical 4

Local operation of breakers 2.6/2.7 47 Distribution 062 (SF6 ED AC) AC Electrical 2

ED/G 4.1/4.4 48 Distribution 063 (SF6 ED DC) DC Electrical 2

AC electrical system 2.7/3.2 49 Distribution 064 (SF6 EDG) Emergency Diesel 1

Local and remote operation of the 4.0/4.3 50 ED/G Generator

ES-401 6

Form ES-401-2 073 (SF7 PRM) Process Radiation 2

Detector failure 2.7/3.2 51 Monitoring 076 (SF4S SW) Service Water 2.2.37 Ability to determine operability and/or 3.6/4.6 52 availability of safety related equipment 078 (SF8 IAS) Instrument Air 1

Air pressure 3.1/3.2 53 103 (SF5 CNT) Containment 5

Emergency containment entrv 2.9/3.9 54 103 (SF5 CNT) Containment 2

Loss of containment integrity under 3.8/4.2 55 normal operations 005 (SF4P RHR) Residual Heat 2

Pressure transient protection during 3.7 86 Removal cold shutdown 008 (SF8 CCW) Component Cooling 2.1.30 Ability to locate and operate 4.0 87 Water components. including local controls.

039 (SF4S MSS) Main and Reheat 1

Flow paths of steam during a LOCA 3.2 88 Steam 062 (SF6 ED AC) AC Electrical Consequence of paralleling out-of-89 15 phase/mismatch in volts 3.2 Distribution 063 (SF6 ED DC) DC Electrical 2.4.20 Knowledge of operational implications 4.3 90 Distribution of EOP warnings, cautions and notes.

~

'"'-*nt Totals:

2 3

2 3

3 2

3 3/3 1 3 3/2 Group Point Total:

28/5

ES-401 7

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

System# I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A G*

KIA Topic(s)

IR 4

002 (SF2; SF4P RCS) Reactor 7

Pumps 2.5/2.8 56 Coolant 015 (SF7 NI) Nuclear 1

NIS channels, components and 3.3/3.7 57 Instrumentation interconnections 016 (SF? NNI) Nonnuclear 1

Separation of control and protection 2.7/2.8 58 Instrumentation circuits 033 (SF8 SFPCS) Spent Fuel Pool 2

Radiation monitoring systems 2.8/3.3 59 Coolino 034 (SF8 FHS) Fuel-Handling 1

Radiation levels 3.3/3.7 60 Equipment 035 (SF 4P SG) Steam Generator 1

S/G water level control 4.0/3.9 61 071 (SF9 WGS) Waste Gas 2.4.46 Ability to verify that the alarms are 4.2/4.2 62 Disposal consistent with the plant conditions.

072 (SF7 ARM) Area Radiation 1

Containment ventilation isolation 3.3/3.6 63 Monitorinq 001 (SF1 CRDS) Control Rod Drive 5

NIS and RPS 4.5/4.4 64 086 Fire Protection 2

Low FPS header pressure 3.0/3.3 65 028 (SF5 HRPS) Hydrogen 2.4.30 Knowledge of events related to system 4.1 91 Recombiner and Purge Control operations/status that must be reported lo internal organizations or outside aqencies.

011 (SF2 PZR LCS) Pressurizer 4

Loss of one, two or three charging 3.7 92 Level Control pumps 079 (SF1 RPI) Rod Position 4

Misaligned rod 3.9 93 Indication KIA Category Point Totals:

1 1

0 1

1 1

1 1/2 1 1 1/1 Group Point Total:

~

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility:

Date of Exam:

Category K/A#

Topic RO SRO-only IR IR 2.1.15 Knowledge of administrative requirements for temporary 2.7/3.4 66 management directives such as standing orders, night orders, Operations memos, etc.

2.1.29 Knowledge of how to conduct system lineups, such as valves, 4.1/4.0 67

1. Conduct of breakers, switches, etc.

Operations 2.1.20 Ability to interpret and execute procedure steps.

4.6/4.6 68 2.1.5 Ability to use procedures related to shift staffing, such as 3.9 94 minimum crew complement, overtime limitations, etc.

Subtotal 3

1 2.2.42 Ability to recognize system parameters that are entry level 3.9/4.6 69 conditions for Technical Soecifications 2.2.44 Ability to interpret control room indications to verify the status 4.2/4.4 70 and operation of a system, and understand how operator actions and directives affect plant and system conditions

2. Equipment Control Ability to determine Technical Specification Mode of Operation 2.2.35 4.5 95 2.2.7 Knowledge of the process for conducting special or infrequent 3.6 96 tests Subtotal 2

2 2.3.11 Ability to control radiation releases.

3.8/4.3 71 2.3.14 Knowledge of radiation or contamination hazards that may 3.4/3.8 72 arise during normal, abnormal, or emergency conditions or activities.

3. Radiation Control 2.3.15 Knowledge of radiation monitoring systems 3.1 97 2.3.5 Ability to use radiation monitoring systems 2.9 98 Subtotal 2

2 2.4.1 Knowledge of EOP entry conditions and immediate action 4.6/4.8 73 steps.

2.4.32 Knowledge of operator response to loss of all annunciators.

3.6/4.0 74 2.4.4 Ability to recognize abnormal indications for system operating 4.5/4.7 75 parameters which are entry-level conditions for emergency and

4. Emergency abnormal operatinq procedures.

Procedures/Plan 2.4.29 Knowledge of the emergency plan.

4.4 99 2.4.40 Knowledge of the SRO's responsibilities in emergency plan 4.5 100 implementation.

Subtotal 3

2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/ As Form ES-401-4 Tier/

Randomly Reason for Rejection Group Selected KIA 1/2 Rejected Emergency and Abnormal Plant Evolutions associated with Babcock and Wilcox (BW) and Combustion Engineering (CE) reactors - Millstone Unit 3 is a Westinqhouse design.

2/1 Rejected 025 (SF5 ICE) Ice Condenser - Millstone Unit 3 does not have an ice condenser installed.

2/1 Rejected 053 (SF1; SF4P ICS*) Integrated Control - Millstone Unit 3 does not have ICS. This topic has no operational significance but similar topics are covered in MSRs.

2/2 Rejected in part 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control - Millstone Unit 3 has no hydrogen recombiner, but does have purge control.

1 /1 G2.2.39 -

Question #14: The E/APE for this KIA statement is Loss of Knowledge of less Vital AC Instrument Bus. There are no less than one hour than one hour technical specification actions to be taken. Randomly technical reselected 2.2.37.

specification action statements for systems.

3 G2.1.17 - Ability Question #67: This KIA is considered oversampled since this to make accurate, will be tested extensively during the operating test.

clear, and concise Randomly reselected 2.1.29.

verbal reports.

3 G2.1.27-Question #68: Cannot write an operationally valid question Knowledge of without a specific system assigned to this KIA. Randomly system purpose reselected 2.1.20.

and or function.

1/2 Question #19: The licensee requested to add 8 items to the Tier 1, Group 2 list of E/APEs to be available for random selection in accordance with ES-401 Attachment 1. AOP 3571, "Instrument Failure Response," was randomly selected as Question 19.

1/2 Question #22: The licensee added 8 items to the Tier 1, Group 2 list of E/APEs to be available for random selection in accordance with ES-401 Attachment 1. AOP 3550, "Turbine Trip," was randomly selected as Question 22.

1 /1 EPE.009.K3.03 Question #3: Questions on this topic would be considered LOD1 - knowledge of reasons for tripping the reactor during a SBLOCA. Randomly reselected K3.21.

1/1 APE.065.A2.02 Question #79: IAS flow readings - there are no IAS flow readings at Millstone Unit 3. Randomly reselected 038 Steam Generator Tube Rupture, A2.02.

ES-401 Record of Rejected K/ As Form ES-401-4 1/2 APE.001.A2.02 Question #82: Position of emergency borate valve on continuous rod withdrawal. Millstone Unit 3 does not emergency borate on a rod withdrawal event. Randomly reselected A2.05.

2/1 064.A4.04 Question #50: Manually operator/monitor remote diesel air compressor switch. Millstone Unit 3 has only a local air compressor switch. Randomly reselected A4.01.

2/1 005.K4.01 Question #31: RHR design feature for overpressure mitigation system. This tests the same concept as Question

  1. 86. Randomly reselected K4.02 2/1 010.K2.02 Question #36: Power supply to spray valve controller. This overlaps with question #39 and #57 for control power *type questions. Randomly reselected K2.01.

2/2 035.A3.02 Question #61: SGS monitor auto operations of MAD valves.

Millstone Unit 3 has no MAD valves. Randomly reselected A3.01.

2/2 079.K1.01 Question #64: service air instrument air physical connections. Air systems are oversampled (see questions 16, 53, 64, 79, 93). Randomly reselected new topic and KIA due to oversampling. Randomly reselected 001 Control Rod Drive, K1.05.

2/2 071.A2.08 Question #92: Waste Gas Disposal: Millstone Unit 3 has no waste gas procedural actions associated with meteorological changes outside of E-Plan PARS, which is already being tested on the Operating Test. Randomly reselected 011 Pressurizer Level Control, A2.04.

2/2 079.A2.01 Question #93: Service air cross-connect with instrument air.

This overlaps with air pressure in question #53. Randomly reselected 014 Rod Position Indication, A2.04 3/1 G2.1.38 Question #94: Knowledge of the station's requirements for verbal communications when implementing procedures. Not SRO level and already being tested on the Operating Exam.

Randomly reselected G2.1.5.

3 G2.3.5 Question #72: Ability to use radiation monitoring systems.

Cannot write an operationally valid question above LOD1.

Randomly reselected G2.3.14

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Millstone 3 Date of Examination:

12/2/17 - 12/8/17 Examination Level: RO

~ SRO D Operating Test Number:

2017 NRC Administrative Topic (see Note)

Type Describe activity to be performed Code*

D,R Determine RCS Leakrate, and Determine if the Leakrate Conduct of Operations is within Limits.

KA: GEN.2.1.7 4.4 / 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

M,R Calculate a dilution without the PPC Conduct of Operations KA: GEN.2.1.43 4.1 / 4.3 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

D,P,S Perform AC Electrical Source Inoperability Equipment Control Surveillance Requirements.

KA: GEN.2.2.12 3.7/4.1 Knowledge of surveillance procedures.

N,R Determine Dose Limits Under Changing Plant Radiation Control Conditions KA: GEN.2.3.4 3.2 I 3.7 Knowledge of radiation exposure limits under normal or emergency conditions.

Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:5 3 for ROs; :5 4 for SROs and RO retakes)

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

(P)revious 2 exams (:5 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Millstone 3 Date of Examination:

12/2/17 - 12/8/17 Examination Level: RO D SRO

~

Operating Test Number:

2017 NRC Administrative Topic (see Note)

Type Code*

Describe activity to be performed N,R Determine Effects on Calorimetric of Removing Conduct of Operations Instruments from Service, and Determine Required Actions KA: GEN.2.1.7 4.4 I 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

N,R Check Refueling Admin Requirements Conduct of Operations KA: GEN. 2.1.40 2.8 I 3.9 Knowledge of refueling administrative requirements.

D,R Complete a Shutdown Safety Assessment Checklist Equipment Control KA: GEN. 2.2.18 2.6 I 3.9 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

D,R Evaluation of an Unplanned Gaseous Release Radiation Control KA: GEN. 2.3.11 3.8 I 4.3 Ability to control radiation releases.

D,P.R Emergency Plan Classification and PAR Emergency Plan KA: GEN. 2.4.44 2.4 I 4.4 Knowledge of emergency plan protective action recommendations.

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; s 4 for SROs and RO retakes)

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

(P)revious 2 exams (s 1, randomly selected)

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

Millstone 3 Date of Examination:

12/2/17 - 12/8/17 Exam Level: RO L8]

SRO-I D SRO-U D Operating Test Number:

2017 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Safety Code*

Function

a. Initiate Immediate Boration (004.A2.14 3.813.9)

D,S,E,A 1

b. Establish Feed and Bleed Cooling of the RCS (W/E05.EK2.2 3.91 4.2)

N,S, E,A 2

C. Depressurize the RCS During a SG Tube Rupture (EPE.038.EA1.04 4.3/4.1)

D,S, E,A 3

d. Shifting the RHR System During Single Loop Operation (005.A4.01 3.613.4)

D,S,L 4 primary

e. Shift to SG Feedwater Flow Control Valves (059.A4.032.91 2.9)

N,S 4 secondary

f.

Manual CIA (103.A2.03 3.513.8)

D, P, S, 5

E,EN,A

g. Test Start The "B" EOG From MB8 (064.A4.06 3.913.9)

D,S 6

h. Starting Control Building Ventilation on Filtered Outside Air (0?1.A2.09 3.o 13.5)

D,S, E 9

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

Establishing Charging Pump Cooling (076.A2.01 3.5 I 3.7)

D,R,E 4 secondary

j.

Energizing MCC 32-3T following CDA (062.A2.01 3.4 I 3.9)

M, E,A 6

k. Align "C" CCW Pump and Heat Exchanger to the "A" Train D,P, R,E 8

(008.A2.01 3.3 / 3.6)

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

  • Type Codes Criteria for R /SR0-1/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank
5 9/:5 8/:5 4 (E)mergency or abnormal in-plant

~1/~1/~1 (EN)gineered safety feature

~ 1/~ 1/~ 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

5 3/:5 3/:5 2 (randomly selected)

(R)CA

~1/~1/~1 (S)imulator

ES-301 Control Room/In-Plant systems Outline Form ES-301-2 Facility:

Millstone 3 Date of Examination:

12/2/17 - 12/8/17 Exam Level: RO D SRO-I ~ SRO-U D Operating Test Number:

2017 NRC Rev 1 Control Room Systems:* 8 tor RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Safety Code*

Function

a. Initiate Immediate Boration (004.A2.14 3.813.9)

D,S, E,A 1

b. Establish Feed and Bleed Cooling of the RCS (W/E05.EK2.2 3.91 4.2)

N,S, E,A 2

C. De pressurize the RCS During a SG Tube Rupture (EPE.038.EA 1.04 4.31 4.1)

D,S, E,A 3

d. Shifting the RHR System During Single Loop Operation (005.M.01 3.613.4)

D,S,L 4 primary

e.
f.

Manual CIA (103.A2.03 3.5 / 3.8)

D, P, S, 5

E,EN,A

g. Test Start The "B" EOG From MBB (064.A4.06 3.913.9)

D,S 6

h. Starting Control Building Ventilation on Filtered Outside Air (011.A2.09 3.o 13.5) D,S, E 9

In-Plant Systems:* 3 tor RO, 3 tor SRO-I, and 3 or 2 tor SRO-U

i.

Establishing Charging Pump Cooling (076.A2.01 3.51 3.7)

D,R,E 4 secondary

j.

Energizing MCC 32-3T following CDA (062.A2.01 3.41 3.9)

M,E,A 6

k. Align "C" CCW Pump and Heat Exchanger to the "A" Train (008.A2.01 3.313.6)

D,P, R,E 8

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

  • Type Codes Criteria for R /SR0-1/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank
5 9/:5 8/:5 4 (E)mergency or abnormal in-plant

.::1/.::1/.::1 (EN)gineered safety feature

.:: 1/.:: 1/.:: 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

5 3/:5 3/:5 2 (randomly selected)

(R)CA

.::1/.::1/.::1 (S)imulator

ES-301 Control Room/In-Plant systems Outline Form ES-301-2 Facility:

Millstone 3 Date of Examination:

12/2/17 - 12/8/17 Exam Level: ROD SRO-I D SRO-U ~

Operating Test Number:

2017 NRG Rev 1 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Safety Code*

Function

a.
b. Establish Feed and Bleed Cooling of the RCS (W/Eos.EK2.2 3.91 4.2)

N,S, E,A 2

C.

d. Shifting the RHR System During Single Loop Operation (oos.M.01 3.613.4)

D,S,L 4 primary

e.
f.

Manual CIA (103.A2.03 3.5 / 3.8)

D, P, S, E, 5

EN,A

g.
h.

In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.
j.

Energizing MCC 32-3T following CDA (062.A2.01 3.41 3.9)

M,E,A 6

k. Align "C" CCW Pump and Heat Exchanger to the "A" Train (ooa.A2.01 3.3/ 3.6)

D, P, R,E 8

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

  • Type Codes Criteria for R /SR0-1/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank

$ 9/$ 8/$ 4 (E)mergency or abnormal in-plant

~ 1/~ 1/~ 1 (EN)gineered safety feature

~ 1/~ 1/~ 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 s 3/S 3/S 2 (randomly selected)

(R)CA

~1/~1/~1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Millstone 3 Scenario No.: 2K17 NRC-01(Rev 1)

Op-Test No.:

2K17 Examiners:

Operators:

Initial Conditions: IC-18, 100% Power, Middle of life, Equilibrium Xe Turnover: The plant is at 100% power and at middle of life. The 'A' EDG is out of service for planned maintenance.

Critical Tasks:

1. Manually actuate at least one train of SIS-actuated safeguards before transition out of E-
0. (CT-2)
2. Establish 530 Gpm AFW flow to the SGs before transition out of E-0. (CT-4)
3. Establish at least one train of quench spray flow prior to RWST reaching 520k gallons (CT-3)
4. Manually trip RCP's (CT-16).

Event No.

Malf.

Event Event No Type*

Description 1

RX09A I (RO)

Controlling channel of PZR pressure (3RCS*PT 455) fails high. (AOP 3571) (Tech Spec entry) 2 RX16A I (RO)

Turbine Impulse pressure instrument (3MSS-PT505) fails I (BOP) low. (AOP 3571) (Tech Spec entry) 3 CV13C R (SRO)

'C' RCP seal degradation. Rapid Downpower (1 %/min) to CV14C R (RO) take the unit offline. (Annunciator Response, AOP 3575)

N (BOP) 4 CV13C

'C' RCP seal continues to degrade, resulting in high seal CV14C leakoff and a procedurally required reactor trip.

(Annunciator Response) 5 RC03C M (All)

Small break LOCA inside CTMT (catastrophic loss of 'C' RCP seal package).

6 RP07A/B C (RO)

Safety Injection fails to automatically actuate.

7 FW20 C (BOP)

AFW pumps fail to auto start.

8 RP06A/B C (RO)

Large break LOCA inside CTMT. CDA fails to automatically RPD10004 C (BOP) or manually actuate. (FR-Z.1)

RPDl0006 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor D-41

Appendix D Scenario Outline Form ES-D-1 Facility: Millstone 3 Scenario No.: 2K17 NRC-02 (Rev 1)

Op-Test No.:

2K17 Examiners:

Operators:

Initial Conditions: IC-160, 79% Power, Middle of life, Equilibrium Xe Turnover: The crew will take the shift with reactor power at 79%. The plant is being returned to service following a refueling outage. The crew is to stabilize reactor power at 79% while Reactor Engineering performs EN 31015 "Power Ascension Testing of Millstone Unit 3". The 'C' CCP heat exchanger is out of service for tube leak repair. The 'D' SWP is out of service for corrective maintenance.

Critical Tasks:

1. Manually trip the reactor from the control room with either Main board trip switch or by opening 32B and 32N supply breakers before completing Step 1 of E-0. (CT-1)
2. Isolate the faulted SG(s) before transition out of E-2. (CT-17)

Event Malf.

Event Event No.

No Type*

Description 1

RX12M I (BOP)

'A' steam generator level transmitter (3FWS-L T551) fails low (AOP 3581 / AOP 3571 ). {Tech Spec entry) 2 SG03C R (SRO)

"C' SG Tube Leak (460 gpd), and subsequent R (RO) procedurally required rapid downpower. (3%/min). (AOP N (BOP) 3576, AOP 3575) (Tech Spec entry) 3 MS01C M (ALL)

'C' main steamline break in CTMT. Requires reactor trip and safety injection.

4 RP10A/B C (RO)

Automatic and MB7 manual reactor trip switch fail.

RP09B Successful manual reactor trip MB4.

5 RP11E C (RO)

Multiple HPSI components fail to automatically actuate.

6 RP11K C (RO)

CTMT Isolation Phase 'A' fails to automatically actuate.

7 SG01C M (ALL)

Hot, dry 'C' SG results in a SGTR. Faulted, ruptured SG.

(ECA-3.1)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor D-41

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