ML033140066
| ML033140066 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/25/2003 |
| From: | Wilson M Dominion Nuclear Connecticut |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-336/03-302 | |
| Download: ML033140066 (12) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Note:
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- 2.
I
- 3.
- 4.
- 5.
6.*
I 7
- 8.
i
- 9.
Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the Tier Totals in each K/A category shall not be less than two). Refer to Section D.l.c for additional guidance regarding SRO sampling.
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 +I 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.
Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the categoryhier.
The generic (G) WAS 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. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) 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; summarize all the SRO-only knowledge and non-A2 applicable categories in the columns labeled K and A.
Use duplicate pages for RO and SRO-only exams.
For Tier 3, enter the KIA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
LOUT2K3-ES-40 1 -2&3-Post-NRC-Review.doc
ES-401 Emergency and P EIAPE # I Name I Safety Function K K K P 1
2 3
1 000007 (BW/E02&EIO; CEIEO2) Reactor Trip - Stabilization - Recovery I 1 000008 Pressurizer Vapor Space Accident I 3 000009 Small Break LOCA / 3 00001 1 Large Break LOCA I 3 000015/17 RCP Malfunctions I 4 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pressure Control System Malfunction I 3 000029 ATWS I 1 000038 Steam Gen. Tube Rupture I 3 000040 (BWIEOS; CEIE05; WIE12)
Steam Line Rupture - Excessive Heat Transfer I 4 000054 (CE/EO6) Loss of Main Feedwater I4 000057 Loss of Vital AC Inst. Bus I 6 I I I I 000058 Loss of DC Power I 6 000062 Loss of Nuclear Svc Water I4 000065 Loss of Instrument Air I 8 WA Category Totals PWR Examination Outline Form ES-401-2 al Plant Evolutions -Tier l/Group 1 (RaSROB G
WA Topic(s)
IR AA2.02; Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: Charging pump problems.
2.1.33; Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
AA2.02; Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The cause of possible CCW loss.
2.2.22; Knowledge of limiting conditions for operations and safety limits.
X X
3.7 4.0 -
3.6 -
4.1 -
system operationslstatus should be reported to outside agencies. The use of a question in this category will conflict AA2.06; Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: AC instrument bus alarms for the inverter and alternate power source.
2.1.2; Knowledge of operator responsibilities during all modes of operation.
X 3.7 -
4.0 -
X I 2.1.32; Ability to explain and apply all system limits and I 3.8 4 I Group Point Total:
LOUT2K3-ES-40 1 -2&3-Post-NRC-Review.doc
Form ES-401-2 ination Outline -
ES-401 Emergency a EIAPE # I Name I Safety Function itions - Tier IIGroup 2 (R&R@
WA Topic(s) 000001 Continuous Rod Withdrawal I 1 Deselected based on NRC Examiner Feedback 000005 InoperableIStuck Control Rod / 1 000024 Emergency Boration I 1 000028 Pressurizer Level Malfunction I 2 AA2.10; Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Whether the automatic mode for PZR level is functioning improperly, necessity to shift to manual modes.
2.2.22; Knowledge of limiting conditions for operations and safety limits.
000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI I 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak I 3 000051 Loss of Condenser Vacuum I 4 4.0 1
2.4.49; Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
000059 Accidental Liquid RadWaste Rel. I 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms I 7 000067 Plant fire on site I 9 3.7 2.2.25; DESELECTED. Knowledge of bases in technical bases for limiting conditions for operation and safety limits. Deselected. There are NO Technical Specifications associated with a fire on site. Unit 2 Technical Requirements Manual addresses this.
WA Reselected based on NRC Examiner feedback.
2.4.49; Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
System K/A reselected to 051, Loss of Condenser Vacuum, based on NRC Examiner Feedback. KIA randomly selected moved to System # 051.
1 000068 (BW/AO6) Control Room Evac. I 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (WIE06&E07) Inad. Core Cooling I 4
II ES-401 Emergency and K
E/APE # / Name / Safety Function I
BW/EO9, CE/A13, W/E09&E10 Natural Circ. I 4 BW/E13&E14 EOP Rules and Enclosures CE/AI 1, W/E08 RCS Overcooling - PTS I 4 CE/A16 Excess RCS Leakage 12 CE/EO9 Functional Recovery CEIEO9 Functional Recovery WA Category Point Totals:
PWR Examination Outline n
Form ES-401-2 itions -Tier I/Group 2 ( R a R O 9 WA Topic(s)
Not applicable to Millstone 2 2.1.33; DESELECTED. Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications. The Functional Recovery procedures at Millstone 2 do NOT specifically address technical specifications.
Reselected based on NRC feedback.
2.1.14; Knowledge of system status which require the notification of plant personnel.
4.0 3.3 -
Group Point Total:
1
II II ES-401 System # / Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 008 Component Cooling Water 013 Engineered Safety Features Actuation 026 Containment Spray 039 Main and Reheat Steam 056 Condensate 059 Main Feedwater 061 AuxiliarylEmergency Feedwater I
062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 103 Containment c K/A Cate o Point Totals:
PWR Examination Outline--
Form ES-401-2 11 Group 1 (R6SRO1)
G WA Topic(s)
IR
- 1 I
I I1 4 4 3 -
x 2 2
Deselected based on NRC feedback.
A2.01; Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions: LOCA Not applicable to Millstone 2 X
2.4.49; Ability to perform without reference to 4.0 1
procedures those actions that require immediate operation of system components and controls.
I I
I II 2.4.4; Ability to recognize abnormal indications for 4.3 1
system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
2 1 Group Point Total:
1 3
1 LO UT2 K3-ES-40 1 -2&3-Post-N RC-Review.doc
ES-401 System # I Name 001 Control Rod Drive 002 Reactor Coolant 01 1 Pressurizer Level Control 014 Rod Position Indication 01 5 Nuclear Instrumentation 016 Non-nuclear Instrumentation 01 7 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Point Totals:
PWR Examination Out Form ES-401-2 Not applicable to Millstone 2 X
A2.03; Ability to (a) predict the impacts of the 4.0 1
following malfunctions or operations on the Fuel Handling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions: Mispositioned Fuel Element.
I 1
1 Group Point Total:
2 Grayed out rows are not applicable to Millstone Unit Two (CE designed plant)
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-C me Unit WA #
2.1.2 2.1.25 Date of Exam: 09/19/03 Topic Knowledge of operator responsibilities during all modes of operation.
Reselected, based on NRC feedback, to KIA 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.
Subtotal 2.2.25 2.2.14 I Facility: Mills Category
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Conduct of 0 pera t ions
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Equipment Control
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Radiation Control
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Emergency Procedures
/ Plan Tier 3 Target Point Total Reselected per NRC guidance due to close proximity of knowledge requirement to selected WA 2.2.14. New K/A 2.2.25 Knowledge of bases in technical specification for limiting conditions for operations and safety limits.
Knowledge of the process for making configuration changes.
Su btotai 2.3.1 1 Subtotal Ability to control radiation releases.
2.4.9 Knowledge of low power / shutdown implications in accident (e.g.
LOCA or loss of RHR) mitigation strategies.
2.4.25 Subtotal Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
RO I
SRC IR 4.0 -
24 3.7 -
3.9 1 -
1 1
2 1
1 1
1 -
2
ES-401 Record of Rejected WAS Form ES-401-4 Tier I Group 1 /I 1 /2 1 12 112 112 211 G
G G
G Randomly Selected KIA 2.4.30 2.2.25 2.1.33 2.1.I4 2.4.49 2.1.25 331n 2.2.25 Reason for Rejection 000054 (CEIEO6) Loss of Main Feedwater / 4; The use of a question in this category will conflict with a previously selected JPM.
Randomly reselected E/APE#000065 Loss of Instrument Air 1 8,
KIA 2.1 -32.
000067 Plant fire on site 19; There are NO Technical Specifications associated with a fire on site. Unit 2 Technical Requirements Manual addresses this. Randomly reselected K/A 2.4.49.
Reselected based on NRC Examiner comments CE/E09 Functional Recovery; The Functional Recovery procedures at Millstone 2 do NOT specifically address technical specifications.
Randomly reselected WA 2.1.14.
Reselected based on NRC Examiner comments 000003 Dropped Control Rod I 1 ; Knowledge of system status criteria which require the notification of plant personnel Deselected based on NRC Examiner Feedback 000051 Loss of Condenser Vacuum 14; Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
System K/A reselected to 051, Loss of Condenser Vacuum, based on NRC Examiner Feedback. WA randomly selected moved to System # 051.
007 ?
r c
C Deselected, based on NRC feedback, to 2.1.25.
Reselected, based on NRC feedback, to K/A 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.
Reselected per NRC guidance due to close proximity of knowledge requirement to selected K/A 2.2.14. New K/A 2.2.25 Knowledge of bases in technical specification for limiting conditions for operations and safety limits.
LO UT2 K3-ES-40 1 Post-N RC-Com men ts
ES-301 Transient and Event Checklist Form ES-301-5 3
2 9
5 7
3,8 1,6 OPERATING TEST NO.: 1 4
Type 1
Type 0
3 5
Major 1
Instructions: (1)
(2) 4, 8 5,7 6
5,6 7
(3)
Minimum Number I
- I N/A I N/A I N/A I N/A I
I I
I 2*
2 2, 3 1,
I :: I I
14.8 Enter the operating test number and Form ES-301-D-1 event numbers for each evolution type.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. *Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a one-for-one basis.
Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.
Author:
NRC Reviewer:
NUREG-I 021, Draft Revision 9 26 of 27
Appendix D Scenario Outline Form ES-D-7 CVOGC W DO3 RC04 RC12A RCllA RP07 ED02 RP-4A-D Facility:
MP2 Scenario No.: ES03LU1 Op-Test No.: 1 C
I c, R C
R, M Examiners:
0 pe rato rs :
Initial Conditions: 28% power, MOL, 1175 ppm Boron, Forcing PZR Sprays, 2 Charging Pumps operating, SGBD @ 25 gprn per SG, 24E aligned to 24D, TDAFP 00s for bearing replacement, B Charging Pump out to prevent auto start which may lift discharge reliefs.
Turnover: 28% power and holding for turnover. Shutdown three days ago for repair to small unisolable steam leak in the Turbine Building. MOL, 1175 ppm Boron, blend ratio is 3.5:1, Forcinq PZR Sprays, 2 charging Pumps operating, A MFP in operation, Group 7 CEAs @ 152 steps, SGBD @ 25 gpm per SG, 24E aligned to 24D, TDAFP 00s for bearinq replacement, in TSAS 3.7.1.2.a and TRM II, 3.0, item 2, B Charging Pump out to prevent auto start which may lift discharge reliefs. In TRM 7.1 -1, Table 7.1.1-1 Item B, Action 1 and 2. No other equipment 00s and no surveillance in progress or due.
Event No.
1 2
3 4
5 6
7 8
FW20B Fw30 I S I05A s104c Event Description Failure of the Letdown Backpressure Controller.
CTMT Sump level transmitter fails to zero.
35 gpm RCS leak in CTMT requiring a rapid downpower.
Oil leak in A RCP A
RCP seizes and trips; results in failure of TCBs to open (ATWS). Successful manual reactor trip using CEDM MG output breakers. Loss of offsite power during the reactor trip.
Degraded A AFW Pump and failure of B AFW Pump to start results in loss of all feedwater.
Small break LOCA immediately after reactor trip Degraded A HPSl Pump and trip of C HPSl results in less than required SI flow.
I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 10212, Draft Revision 9 40 Of 41
Appendix D Scenario Outline Form ES-D-1 Facility:
MP2 Scenario No.: ES03LU2 Op-Test No.: 2 Examiners:
Operators:
Initial Conditions: 100% power, MOL, Eq. Xe., 821 ppm Boron, SGBD @ 25 gpm per SG, 24E aligned to 24D, B Charging Pump out to prevent auto start which may lift discharge reliefs.
Turnover: 100% power, MOL, Eq. Xe., 821 ppm Boron, blend ratio: 6.3:l SGBD @- 25 gpm per SG, 24E aligned to 24D, B Charging Pump out to prevent auto start which may lift discharge reliefs. in TRM 7.1.I, Table 7.1.I-1 Item B, Action 1 and
- 2. No other equipment 00s and no surveillance in progress or due.
I 1 Event Malf.
No.
Event DescriPtion Event C
TY Pe*
The Main Feedwater Flow transmitter fails low RX1 OC RXGB S103A TC04 RP28D, E, H TCOGA - D I
C I
Channel Y Reactor Regulating System failure.
All 4 main control valves close requiring a reactor trip.
RCS temperature and pressure rise and reactor fails to automatically trip on high RCS pressure (ATWS). Successful manual reactor trip using manual push buttons.
Loss of offsite power during the reactor trip.
A DG output breaker fails to close resulting in the loss of one complete facility.
ED02 EG08A RCOSA M
Pressurizer safety valve sticks open after the trip resulting in a LOCA.
SG02B M
Steam Generator Tube Rupture in #2 Steam Generator after the trb.
SWOIC C
Loss of C Service Water Pump results in loss of cooling to the running Diesel Generator (only source of power).
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor NUREG 10212, Draft Revision 9 40 of 41
ES-30 1 Simulator Scenario Quality Checklist Form ES-30 1-4 i
L Facility: Mi 11 S. t (.,tu 2
Date of Exam: 9/22/03 ScenarioNumbers: / I Z I Ope!
QUALITATIVE ATTRl B UTES the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the eve in the minimum number of transients and events ting Test No.:
Initials 25 of 27 NUREG-I 021, Draft Revision 9