ML18074A363
| ML18074A363 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/23/2017 |
| From: | Peter Presby Operations Branch I |
| To: | Dominion Energy Nuclear Connecticut |
| Shared Package | |
| ML17094A469 | List: |
| References | |
| CAC U01946 | |
| Download: ML18074A363 (10) | |
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 1
2 3
4 7
Categories 3
2 2
3 1
2 2
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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each K/A 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 NRG 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 KIA 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 Kl As.
- 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 KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to Kl As that are linked to 1 O CFR 55.43.
G* Generic K/As 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 Fo Emergency and Abnormal Plant Evolutions-Tier 1/Group 1 (RO/SRO)
E/APE #/Name/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 3
Reactor trip and safety initiation 4.1/4.4 3 000011 (EPE 11 l Larqe Break LOCA / 3 11 Conditions for throttlinq or stoppinq 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 automatic 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 Cooling Water/ 8 000027 (APE 27) Pressurizer Pressure 3
Controllers and positioners 2.6/2.8 9 Control Svstem 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 / 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
Emerqency air compressor 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 I 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 Oftsite Power/ 6 2.4.50 Ability to verify system alarm setpoints and 4.0 78 operate controls identified in the alarm response manual.
000065 (APE 65) Loss of Instrument Air/ 8 2
Relationship of flow readings to system 2.6 79 operation (W E04) LOCA Outside Containment/ 3 2.4.20.
Knowledge of operational implications of EOP 4.3 80 warninos, cautions and notes.
ES-401 3
Form ES-401-2 Facility conditions and selection of appropriate 4.4 81 (BW E04; W E05) Inadequate Heat 1
procedures during abnormal and emergency Transfer-Loss of Secondary Heat Sink/ 4 operations.
KIA Cateaorv Totals:
3 3
3 3
3/3 3/3 Group Point Total:
18/6
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emerqencv and Abnormal Plant Evolutions-Tier 1/Group 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 handlina 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 interpretation.
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.
(SW 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, abnonmal and 2.9/3.3 25 emergency operating procedures associated with (Steam Generator Overoressure \\.
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 2
Position of emergency 4.2 82 boration valve 000076 (APE 76) High Reactor Coolant Activity/ 9 2.4.41 Knowledge of the emergency 4.6 83 action level thresholds and classifications.
(BW E08; W E03) LOCA Cooldown-Depressurization / 4 1
Facility conditions and 4.2 84 selection of appropriate procedures during abnormal and emeraencv 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 I 212 1112 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/Grou J 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 storaae tank 005 (SF4P RHR) Residual Heat 1
Overpressure mitigation system 3.0/3.2 31 Removal 006 (SF2; SF3 ECCS) Emergency 2
Valve operators for accumulators 2.5/2.9 32 Core Coolina 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 reflecting the desired plant lineup.
010 (SF3 PZR PCS) Pressurizer 2
Controller for PZR spray valve 2.5/2.7 36 Pressure Control 012 (SF7 RPS) Reactor Protection 1
Trip setpoint adjustment 2.9/3.4 37 012 (SF7 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 Auxiliary/Emeraency 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 EOG) Emergency Diesel 4
Remote operation of the air 3.2/3.2 50 Generator compressor switch (different modes)
ES-401 6
Form ES-401-2 073 (SF? PRM) Process Radiation 2
Detector failure 2.7/3.2 51 Monitorinq 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
Emerqency containment entry 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 components. including local controls.
Water 039 (SF4S MSS) Main and Reheat 1
Flow paths of steam during a LOCA 3.2 88 Steam 062 (SF6 ED AC) AC Electrical 15 Consequence of paralleling out-of-3.2 89 Distribution phase/mismatch in volts 063 (SF6 ED DC) DC Electrical 2.4.20 Knowledge of operational implications 4.3 90 of EOP warnings, cautions and notes.
Distribution KIA Category Point 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 ES-401 PWR Examination Outline Form ES-401-2 Plant S,stems-Tier 2/Group 2 (RO/SRO)
System #/Name K1 K2 K3 K4 KS K6 A1 A2 A3 A G*
KIA Topic(s)
JR 4
002 (SF2; SF4P RCS) Reactor 7
Pumps 2.5/2.8 56 Coolant 015 (SF? 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 Coolina 034 (SF8 FHS) Fuel-Handling 1
Radiation levels 3.3/3.7 60 Eauipment 035 (SF 4P SG) Steam Generator 2
MAD valves 3.7/3.5 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 (SF? ARM) Area Radiation 1
Containment ventilation isolation 3.3/3.6 63 Monitorina 079 (SF8 SAS**) Station Air 1
IAS 3.0/3.1 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 to internal organizations or outside agencies.
071 (SF9 WGS) Waste Gas 8
Meteorological changes 2.8 92 Disposal 079 (SF8 SAS**) Station Air 1
Cross-connection with IAS 3.2 93 IK/A Catego~ Point Totals:
I 1 I 1 lo I 1 I 1 I 1 I 1 I 112 I 1 I 1 I 111 I Grau[! Point Total:
I I 1013 I
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 breakers, switches, etc.
- 1. Conduct of Operations 2.1.20 Ability to interpret and execute procedure steps.
4.6/4.6 68 2.i.38 Knowledge of the stations requirements for verbal 3.8 94 communication when implementinq procedures Subtotal 3
1 2.2.42 Ability to recognize system parameters that are entry level 3.9/4.6 69 conditions for Technical Specifications 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 2.3.5 Ability to use radiation monitoring systems 2.9/2.9 72
- 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 operating 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 Kl 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 desiqn.
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 siqnificance 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.