NTD-16-051, Draft Outlines (Facility Letter Dtd. - 9/12/2016 (Folder 2)
| ML17109A361 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/12/2016 |
| From: | D'Antonio J Operations Branch I |
| To: | Mog M Public Service Enterprise Group |
| Shared Package | |
| ML16076A441 | List: |
| References | |
| NTD-16-051, U01930 | |
| Download: ML17109A361 (25) | |
Text
Mr. Joseph D 'Antonio Chief Examiner Division of Reactor Safety US Nuclear Regulatory Commission 2100 Renaissance Blvd King of Prussia, PA. 19406 NTD-16-051 September 12, 2016
Dear Mr. D 'Antonio,
Enclosed is our proposed outline for the initial license examination to be conducted for Salem candidates during a two-week period beginning on December 12, 2015. These materials should be withheld from public disclosure until after the examinations are complete.
The exam includes RO and SRO-I applicants.
Forms included with this package are:
- Form ES-201-2, Examination Outline Quality Checklist.
- Form ES-301-1, (2 pages) Administrative Topics Outline.
- Form ES-301-2, (2 pages) Control Room Systems I In-Plant System Outline.
- Form ES-301-6, (2 pages) Competencies Checklist
- Form ES-D-1, (5 pages), Appendix D, Scenario Outline.
- Forms ES-401-2, PWR Examination Outline, and ES-401-3, Generic Knowledge and Abilities Outline: Separate forms are completed for the RO and SRO sections of the examinations.
- Form ES-401-4, Record of Rejected K/As The written exam outlines were developed using the Westinghouse PWROG Outline Generation Software.
Safety Function 5: Containment Integrity, System 025 Ice Condenser System was suppressed during outline development.
This suppression was submitted and approved by the NRC for previous Salem exams. If you have any questions concerning this letter, please contact me at 856-339-1929, or the Lead Exam Author, Gerry Gauding, at 856-339-1554.
e ES-401 PWR Examination Outline Form ES-401-2 Facilit)l:
Salem Printed: 09/14/2016 Date Of Exam: 12/19/2016 RO KIA 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 0 0 0 Emergenc, 2 2 2 2 2 1 0 9 0 0 0 & N/A N/A Abnormal Tier Plant Evolutions Totals 5 5 5 5 4 3 27 0 0 0 1 3 2 3 3 ,., 2 3 2 2 ,., 2 28 0 0 0 2. .) .) 2 1 1 1 1 1 1 1 1 1 1 0 10 0 I 0 0 0 Plant Systems Tier 4 3 4 4 4 3 4 3 3 4 2 38 0 0 0 Totals 3. Generic Knowledge And 1 2 3 4 1 2 3 4 10 0 Abilities Categories 3 2 2 3 0 0 0 0 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 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section 0.1.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 K/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 KIA categories.
7.* The generic (G) KIAs 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 0.1.b of ES-401 for the applicable K/As. 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (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 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 point totals(#)
on Form ES-401-3.
Limit SRO selections to KIAs that are linked to 10 CFR 55.43. 09/14/2016 10:01:26 am PWR RO Examination Outline Printed: 09114/2016 Facility:
Salem ES-401 Emergency and Abnormal Plant Evolutions
-Tier 1 I Group 1 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000007 Reactor Trip -Stabilization
-x EK2.02 -Breakers, relays and 2.6 l Recovery I 1 disconnects 000009 Small Break LOCA I 3 x 2.4.18 -Knowledge of the specific 3.3 1 bases for EOPs. 000011 Large Break LOCA I 3 x EA2.03 -Consequences of managing 3.7 1 LOCA with loss of CCW 000015/000017 RCP Malfunctions I 4 x AK2.10 -RCP indicators and controls 2.8* 1 000022 Loss of Rx Coolant Makeup I 2 x AKl.03 -Relationship between 3.0 l charging flow and PZR level 000025 Loss of RHR System I 4 x 2.4.46 -Ability to verify that the alarms 4.2 1 are consistent with the plant conditions.
000026 Loss of Component Cooling Water I x AK3.02 -The automatic actions 3.6 l 8 (alignments) within the CCWS resulting from the actuation of the ESF AS 000027 Pressurizer Pressure Control System x AK3.03 -Actions contained in EOP for 3.7 l Malfunction I 3 PZR PCS malfunction 000029 A TWS I 1 x EK2.06 -Breakers, relays, and 2.9* l disconnects 000038 Steam Gen. Tube Rupture I 3 x EA 1.44 -Level operating limits for 3.4* 1 S/Gs 000040 Steam Line Rupture -Excessive x AKl.02 -Leak rate versus pressure 3.2 1 Heat Transfer I 4 change 000054 Loss of Main Feedwater I 4 x 2.4.45 -Ability to prioritize and 4.1 1 interpret the significance of each annunciator or alarm. 000055 Station Blackout I 6 x EA2.03 -Actions necessary to restore 3.9 1 power 000056 Loss of Off-site Power I 6 x AA2.03 -Operational status of safety 3.8 1 injection pump 000057 Loss of Vital AC Inst. Bus I 6 x AA 1.06 -Manual control of 3.5 1 components for which automatic control is lost W/E04 LOCA Outside Containment I 3 x EA 1.1 -Components, and functions of 4.0 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 09/14/2016 10:00:58 am PWR RO Examination Outline Printed: 09/14/2016 Facility:
Salem ES-401 Emergency and Abnormal Plant Evolutions
-Tier 1 I Group 1 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points W/E05 Inadequate Heat Transfer -Loss of x EK3. I -Facility operating 3.4 I Secondary Heat Sink I 4 characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics W/El 1 Loss of Emergency Coolant Recirc. I x EKl.2 -Normal, abnormal and 3.6 1 4 emergency operating procedures associated with Loss of Emergency Coolant Recirculation KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18 09/14/2016 10:00:58 am 2 PWR RO Examination Outline Printed: 09/14/2016 Facility:
Salem ES -401 Emergency and Abnormal Plant Evolutions
-Tier 1 I Group 2 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000001 Continuous Rod Withdrawal I 1 x AA2.02 -Position of emergency 4.2 1 boration valve 000003 Dropped Control Rod I 1 x AK.2.05 -Control rod drive power 2.5 1 supplies and logic circuits 000024 Emergency Boration I 1 x AK3.02 -Actions contained in EOP for 4.2 1 emergency boration 000033 Loss ofintermediate Range NI I 7 x AAl.02 -Level trip bypass 3.0 1 000037 Steam Generator Tube Leak I 3 x AAl.06 -Main steam line rad monitor 3.8* 1 meters 000074 Inad. Core Cooling I 4 x EK.2.02 -PORV 3.9 1 W /E08 RCS Overcooling
-PTS I 4 x EKl. l -Components, capacity, and 3.5 1 function of emergency systems W/EIO Natural Circ. I 4 x EK3 .3 -Manipulation of controls 3.4 1 required to obtain desired operating results during abnormal, and emergency situations W/E14 Loss ofCTMT Integrity I 5 x EKl.2 -Normal, abnormal and 3.2 1 emergency operating procedures associated with High Containment Pressure Kl A Category Totals: 2 2 2 2 1 0 Group Point Total: 9 09/14/2016 10:01 :03 am PWR RO Examination Outline Printed: 09/14/2016 Facility:
Salem ES-401 Plant Systems -Tier 2 I Group 1 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump x 2.2.22 -Knowledge of 4.0 1 limiting conditions for operations and safety limits. 004 Chemical and Volume Control x K5.26 -Relationship 3.1 1 between VCT pressure and NPSH for charging pumps 004 Chemical and Volume Control x K4.04-Manual/automatic 3.2 1 transfers of control 005 Residual Heat Removal x A 1.02 -RHR flow rate 3.3 1 006 Emergency Core Cooling x K3.0l -RCS 4.1
- 1 006 Emergency Core Cooling x Al.17 -ECCS flow rate 4.2 1 007 Pressurizer Relief/Quench x A4.04 -PZR vent valve 2.6* 1 Tank 008 Component Cooling Water x K4.01 -Automatic start of 3.1 1 standby pump 010 Pressurizer Pressure Control x A2.02 -Spray valve failures 3.9 1 012 Reactor Protection x Al.01-Trip setpoint 2.9* 1 adjustment 013 Engineered Safety Features x K2.0l -ESFAS/safeguards 3.6* 1 Actuation equipment control 022 Containment Cooling x Kl.01-SWS/cooling 3.5 1 system 022 Containment Cooling x A3.01 -Initiation of 4.1 1 safeguards mode of operation 026 Containment Spray x A4.05 -Containment spray 3.S 1 reset switches 026 Containment Spray x A3.0l -Pump starts and 4.3 1 correct MOY positioning 039 Main and Reheat Steam x KS.08-Effect of steam 3.6 1 removal on reactivity OS9 Main Feedwater x A2.01 -Feedwater actuation 3.4* 1 of AFW system OS9 Main Feedwater x Kl.OS -RCS 3.1
- 1 061 Auxiliary/Emergency x KS.OS -Feed line voiding 2.7 1 Feedwater and water hammer 061 Auxiliary/Emergency x K6.01 -Controllers and 2.S 1 Feedwater positioners 062 AC Electrical Distribution x K3.02 -ED/G 4.1 1 063 DC Electrical Distribution x K3.02 -Components using 3.S I DC control power 064 Emergency Diesel Generator x K6.07 -Air receivers 2.7 1 064 Emergency Diesel Generator x Kl.03 -Diesel fuel oil 3.6 1 supply system 073 Process Radiation Monitoring x 2.1.32 -Ability to explain 3.8 1 and apply system limits and 09/14/2016 10:01:09 am PWR RO Examination Outline Printed: 09/14/2016 Facility:
Salem ES -401 Plant Systems -Tier 2 I Group 1 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points precautions.
076 Service Water x K4.02 -Automatic start 2.9 1 features associated with SWS pump controls 078 Instrument Air x K2.02 -Emergency air 3.3* I compressor I 03 Containment x A4.04 -Phase A and phase 3.5* I B resets KIA Category Totals: 3 2 3 3 3 2 3 2 2 3 2 Group Point Total: 28 09/14/2016 10:01:09 am 2 PWR RO Examination Outline Printed: 09/14/2016 Facility:
Salem ES-401 Plant Systems -Tier 2 I Group 2 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 011 Pressurizer Level Control x A4.05 -Letdown flow 3.2 1 controller 015 Nuclear Instrumentation x A2.02 -Faulty or erratic 3.1 1 operation of detectors or compensating components 028 Hydrogen Recombiner and x K.2.01 -Hydrogen 2.5* 1 Purge Control recombiners 033 Spent Fuel Pool Cooling x Kl.05 -RWST 2.7* 1 034 Fuel Handling Equipment x A3.02 -Load limits 2.5* 1 035 Steam Generator x Al.QI-S/G wide and 3.6 1 narrow range level during startup, shutdown, and normal operations 045 Main Turbine Generator x K3.0l -Remainder of the 2.9 1 plant 068 Liquid Radwaste x K6. l 0 -Radiation monitors 2.5 1 079 Station Air x K4.01 -Cross-connect with 2.9 1 IAS 086 Fire Protection x K5.04 -Hazards to 2.9 1 personne 1 as a result of fire type and methods of protection Kl A Category Totals: 1 1 1 1 1 1 1 I 1 1 0 Group Point Total: 10 09/14/2016 10:01 :15 am Facility:
Salem Generic Cate2ory Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan 09/14/2016 10:01:20 am Generic Knowledge and Abilities Outline (Tier 3) PWR RO Examination Outline Printed: 09/14/2016 Form ES-401-3 KA Topic 2.1.l Knowledge of conduct of operations 3.8 1 requirements.
2.1.2 Knowledge
of operator responsibilities during all 4.1 1 modes of plant operation.
2.1.40 Knowledge of refueling administrative 2.8 1 requirements.
Category Total: 3 2.2.35 Ability to determine Technical Specification 3.6 1 Mode of Operation.
2.2.39 Knowledge of less than or equal to one hour 3.9 1 Technical Specification action statements for systems. Category Total: 2 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergency conditions.
2.3.13 Knowledge of radiological safety procedures 3.4 1 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Category Total: 2 2.4.4 Ability to recognize abnormal indications for 4.5 1 system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
2.4.11 Knowledge of abnormal condition procedures.
4.0 I 2.4.32 Knowledge of operator response to loss of all 3.6 1 annunciators.
Category Total: 3 Generic Total: 10 ES-401 PWR Examination Outline Form ES-401-2 Facilit)l:
Salem Printed: 09/14/2016 Date Of Exam: 12/19/2016 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total 1. 1 0 0 0 0 0 0 0 3 3 6 Emergency 2 0 0 0 0 0 0 0 2 2 4 & N/A N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions
- 2. 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2 0 0 0 0 0 0 0 0 0 0 0 0 0 I 2 1 ,., .) Plant Systems Tier 0 0 0 0 0 0 Totals 0 0 0 0 0 0 5 3 8 3. Generic Knowledge And 1 2 3 4 1 2 3 4 0 7 Abilities Categories 0 0 0 0 2 2 1 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 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.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 KIAs 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 KIA categories.
7.* The generic (G) KIAs 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 KIAs. 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (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 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 point totals(#)
on Form ES-401-3.
Limit SRO selections to KIAs that are linked to 10 CFR 55.43. 09/14/2016 8:15:01 am PWR SRO Examination Outline Printed: 0911412016 Facility:
Salem ES-401 Emergency and Abnormal Plant Evolutions
-Tier 1 I Group 1 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000007 Reactor Trip -Stabilization
-x EA2.02 -Proper actions to be taken if 4.6 1 Recovery I I the automatic safety functions have not taken place 000015/000017 RCP Malfunctions I 4 x 2.2.37 -Ability to determine operability 4.6 1 and/or availability of safety related equipment.
000029 ATWS I 1 x 2.2.44 -Ability to interpret control 4.4 I room indications to verify the status and operation of a system, and understand
... how operator actions and directives affect plant and system conditions.
000065 Loss oflnstrument Air I 8 x 2.1.42 -Knowledge of new and spent 3.4 I fuel movement procedures.
W IE 11 Loss of Emergency Coolant Recirc. I x EA2.2 -Adherence to appropriate 4.2 1 4 procedures and operation within the limitations in the facility's license and amendments W/El2 -Steam Line Rupture -Excessive x EA2. l -Facility conditions and 4.0 1 Heat Transfer I 4 selection of appropriate procedures during abnormal and emergency operations Kl A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 09/14/2016 8:14:33 am PWR SRO Examination Outline Printed: 09/14/2016 Facility:
Salem ES-401 Emergency and Abnormal Plant Evolutions
-Tier 1 I Group 2 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 000037 Steam Generator Tube Leak I 3 x AA2.l 4 -Actions to be taken if S/G 4.4 1 goes solid and water enters steam lines 000069 Loss of CTMT Integrity I 5 x 2.4.41 -Knowledge of the emergency 4.6 1 action level thresholds and classifications.
W/E03 LOCA Cooldown -Depress. I 4 x EA2. l -Facility conditions and 4.2 1 selection of appropriate procedures during abnormal and emergency operations W/E08 RCS Overcooling
-PTS I 4 x 2.4.6 -Knowledge ofEOP mitigation 4.7 1 strategies.
Kl A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 09/14/2016 8:14:40 am PWR SRO Examination Outline Printed: 0911412016 Facility:
Salem ES-401 Plant Systems -Tier 2 I Group 1 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points 006 Emergency Core Cooling x A2. I 2 -Conditions 4.8 I requiring actuation of ECCS 061 Auxiliary/Emergency x A2.07 -Air or MOY failure 3.5 1 Feedwater 064 Emergency Diesel Generator x 2.2.40 -Ability to apply 4.7 1 Technical Specifications for a system. 076 Service Water x A2.0l -Loss ofSWS 3.7* 1 103 Containment x 2.1.23 -Ability to perform 4.4 1 specific system and integrated plant procedures during all modes of plant operation.
KIA Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 09/14/2016 8:14:45 am PWR SRO Examination Outline Printed: 09/14/2016 Facility:
Salem ES-401 Plant Systems -Tier 2 I Group 2 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 002 Reactor Coolant x 2.2.25 -Knowledge of the 4.2 I bases in Technical Specifications for limiting conditions for operations and safety limits. 034 Fuel Handling Equipment x A2.01 -Dropped fuel 4.4 1 element 056 Condensate x A2.04 -Loss of condensate 2.8* I pumps Kl A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 09/14/2016 8:14:50 am Generic Knowledge and Abilities Outline (Tier 3) PWR SRO Examination Outline Printed: 09/14/2016 Facility:
Salem Form ES-401-3 Generic Category KA Topic Conduct of Operations 2.1.35 Knowledge of the fuel-handling responsibilities 3.9 1 ofSROs. 2.1.36 Knowledge of procedures and limitations 4.1 1 involved in core alterations.
Category Total: 2 Equipment Control 2.2.22 Knowledge of limiting conditions for operations 4.7 1 and safety limits. 2.2.37 Ability to determine operability and/or 4.6 1 availability of safety related equipment.
Category Total: 2 Radiation Control 2.3.11 Ability to control radiation releases.
4.3 1 Category Total: 1 Emergency Procedures/Plan
2.4.4 Ability
to recognize abnormal indications for 4.7 1 system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
2.4.9 Knowledge
oflow power /shutdown implications 4.2 1 in accident (e.g. LOCA or loss ofRHR) mitigation strategies.
Category Total: 2 Generic Total: 7 09/14/2016 8:14:56 am ES-401 Tier/Group Randomly Selected Kl A RO 111 003 2.4.40 RO 111 015 AK3.04 ROl/1 025 2.2.6 ROl/1 038 EK3.07 RO 111 055 2.1.21 RO 111 055 2.4.39 ROl/1 065 2.4.25 RO 111 077 AKl.01 RO 112 003 AK2.03 RO 1/2 59 2.4.17 RO 112 076 2.1.6 RO 112 El32.1.1 R02/1 005 2.1.5 R02/1 010 A4.02 R02/1 059 2.4.41 R02/1 064 Kl.05 R02/2 011 Kl.05 R02/2 041 K4.18 SRO 111 007 2.3.11 SROl/1 024 2.1.34 SRO 111 Ell 2.1.41 SRO 112 E16 2.2.35 R ----d of Reiected K/As Salem 15-01 NRC E -------Reason for Rejection (ES-401, D.1.b) Salem does not have power-to-flow limits (ES-401, D.1.b) Salem does not have RCS loop isolation valves (ES-401, D.l.b) (ES-401, D.1.b) (ES-401, D.1.b) A definition doesn't have operational implications Salem does not have a metroscope (ES-401, D.1.b) (ES-401, D.1.b) (ES-401, D.1.b) (ES-401, D.1.b) Sampled on CERT exam EAL Threshold levels not RO required knowledge Oversampling ofEDG air start system (064 K6.07 also on this exam) Salem does not have a reactor regulating system SDS does not provide for Turbine Trip (ES-401, D.1.b) (ES-401, D.1.b) (ES-401, D.l.b) (ES-401, D.1.b) Pagelof 2 ES-401, Page 44 of 50 F ------ES-401-4 ES-401 SRO 2/1 013 2.1.5 SRO 2/1 064 2.4.44 SRO 2/1 103 2.1.40 SRO 2/2 075 2.2.21 SRO 2/2 072 2.4.32 (ES-401, D.1.b) (ES-401, D.1.b) (ES-401, D.1.b) (ES-401, D.1.b) (ES-401, D.1.b) Record of Reiected K/As Salem 15-01 NRC E 2 ES-401 , Page 44 of 50 ------F ----ES-401-4 Reasoning for keeping SRO Kl A 000065, Loss of Instrument Air, 2.1.42 -"Knowledge of new and spent fuel movement procedures" on SRO exam outline. ES-401.D.1.b does not contain Kl A 2.1.42 in the list of generic Kl As from which the Tier 1 and Tier 2 topics may be selected.
However, NUREG-1122 does indicate that Generic KIA 2.1.42 is associated with CFR55.43.7, with an importance rating of 3.4. Since the Loss of Instrument Air topic can be directly tied to Generic Kl A and a question written at the SRO level as described in lOCFR Part 55.43 (7) "Fuel handling facilities and procedures.", this KIA was left in exam outline.
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
SALEM Date of Examination:
12/12/16 Examination Level:
- RO SRO Operating Test Number: 15-01 NRC Administrative Type Describe activity to be performed Topic (See Note) Code* Conduct of R,M,P Calculate leakrate into containment sump. Operations 2.1.25 Calculate Shutdown Margin Conduct of R,M 2.1.43 Ability to use procedures to determine the effects on reactivity of plant Operations changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. Perform ST.CVC-010 Borated Water Sources (Simulator)
Equipment Control S,M 2.2.37 Ability to determine operability and/or availability of safety related equipment.
Perform radiation dose calculation and determine if any Dose Limit will be Radiation Control R,D exceeded.
2.3.4 Knowledge
of radiation exposure limits under normal and emergency conditions.
Emergency N/A Procedures I 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 5 are required.
- Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, for ROs; for SROs & RO retakes) (N)ew or (M)odified from bank (_:::1) (P)revious 2 exams randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
SALEM Date of Examination:
12/12/16 Examination Level: RO
- SRO Operating Test Number: 15-01 NRC Administrative Type Describe activity to be performed Topic (See Note) Code* Conduct of R,M Review a completed surveillance to demonstrate Operability of 21 CFCU Operations 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. Conduct of Direct Actions for Spent Fuel Movement (Determine work which would require Operations R,D suspension of Fuel Movement) 2.1.42 Knowledge of new and spent fuel movement procedures.
Equipment Control R,M Review completed Shutdown Margin calculation.
2.2.12 Knowledge of surveillance procedures Determine required actions upon Radioactive Effluent Monitor failure Radiation Control R,D 2.3.11 Ability to control radiation releases Emergency S,M,P Classify Emergency I Non-Emergency Events, and complete the ICMF. Procedures I Plan 2.4.29 Knowledge of the Emergency 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 5 are required.
- Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (.'.::,3 for ROs; .'.::,4 for SROs & RO retakes) (N)ew or (M)odified from bank (_:::1) (P)revious 2 exams (.'.::,1; randomly selected)
ES-301 Control Room Systems/In-Plant System Outline Form ES-301-2 Facility:
SALEM Date of Examination:
12/12/16 Exam Level: SRO-I SRO-U Operating Test No.: 15-01 NRC 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) Perform control rod operability verification A,D,S 1 b) Perform Actions for Containment Sump blockage A,N,EN, L,S 2 c) Isolate ECCS Accumulators in TRIP-6 A,D,L,S 3 d) Respond to a Loss of Secondary Heat Sink (Initiate Bleed and Feed using Rx Head Vent Valves) A,D,L,P,S 4 (pri) e) TCAF a Loss of All Service Water A,M, S 4 (sec) f) Adjust PRZ Relief Tank (PRT) Level and Pressure D,S 5 g) Energize 4KV vital bus from Station Power during restoration from LOPA D,L,S 6 h) Respond to a Loss of Control Air A,D,S 8 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i) Transfer PZR BU heaters to emergency power source during a LOOP D,E,L,P 3 j) Perform AFW Back leakage test N,R 4 (sec) k) Start and Synchronize an EOG D,R 6 @ 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 I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank I 4 (E)mergency or abnormal in-plant I 1 1 (EN)gineered safety feature -I -I 1 (control room system) (L)ow-Power I Shutdown I I (N)ew or (M)odified from bank including 1 (A) I 2 1 (P)revious 2 exams 3 3 2 (randomly selected) (R)CA I 1/ 1 (S)imulator ES-301 Control Room Systems/In-Plant System Outline Form ES-301-2 Facility:
SALEM Date of Examination:
12/12/16 Exam Level : RO llsRo-111 SRO-U Operating Test No.: 15-01 NRC 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) Perform control rod operability verification A,D,S 1 b) Perform Actions for Containment Sump blockage A,N,EN, L,S 2 c) Isolate ECCS Accumulators in TRIP-6 A,D,L,S 3 d) Respond to a Loss of Secondary Heat Sink (Initiate Bleed and Feed using Rx Head Vent Valves) A,D,P,S 4 (pri) e) TCAF a Loss of All Service Water A,M, S 4 (sec) f) Adjust PRZ Relief Tank (PRT) Level and Pressure D,S 5 g) h) Respond to a Loss of Control Air A,D,S 8 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i) Transfer PZR BU heaters to emergency power source during a LOOP D,E,P 3 j) Perform AFW Back leakage test N,R 4 (sec) k) Start and Synchronize an EOG D,R 6 @ 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 I SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irect from bank I 4 (E)mergency or abnormal in-plant .::: 1 I _::: 1 I_::: 1 (EN)gineered safety feature -I -I _::: 1 (control room system) (L)ow-Power I Shutdown _:::1 I _:::1 I _:::1 (N)ew or (M)odified from bank including 1 (A) _:::2 I _::: 2 I_::: 1 (P)revious 2 exams 3 3 2 (randomly selected) (R)CA .::: 1 I .::: 1 / .::: 1 (S)imulator Appendix D Scenario Outline Form ES-D-1 Facility:
SALEM 1 & 2 Scenario No.: ESG-1 Op-Test No.: 15-01 NRC Examiners:
Operators:
Initial Conditions:
100% power, MOL. PZR Pressure Channel Ill is selected for Control. Turnover:
Maintain current power. Event Malf. No. Event Type* Event No. Description 1 PR0017A I Controlling PZR level channel fails low (TS) ALL 2 RC0002 c RCS leak (TS) ALL 3 RC0002 M Small Break LOCA ALL 4 RP0342 c High Head ECCS isolation valves fail to open RP0343 CRS/RO 5 CB09A DI c SEC fails to reset KCB09ASE CRS/PO RP318E1 6 RP318E2 c All AFW pumps fail to start AF0353A CRS/PO AF0353B 7 RC0002 c SBLOCA escalation after entering SI Termination procedure CRS/RO * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Facility:
SALEM 1 & 2 Scenario No.: ESG-2 Op-Test No.: 15-01 NRG Examiners:
Operators:
Initial Conditions:
89.4% power, MOL. Xenon is building in at 25 pcm/hour.
2C EOG Jacket Water heater is C/T after failing yesterday.
Turnover:
Power is reduced in preparation for performing Main Turbine Valve testing later in shift. Maintain current power. Event Malf. No. Event Type* Event No. Description 1 AN0266 c 2C EOG Pre-lube pump failure (TS) CRS 2 CN0117C c 23 Condensate pump trip CRS/PO R 3 CRS/RO Down power N PO 4 SG0078A c SGTL (TS) ALL 5 SG0078A M SGTR ALL 6 RC0003C c 23 RCP trip during cooldown RC0003A ALL 7 VL0123 c PZR PORV fails to shut during RCS depressurization CRS/RO * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Facility:
SALEM 1 & 2 Scenario No.: ESG-3 Op-Test No.: 15-01 NRG Examiners:
Operators:
Initial Conditions:
1x10-8 Amps during startup at BOL. 25 CFCU CIT. 23 Charging pump CIT. Turnover:
Raise power to 2%. Event Malf. No. Event Event No. Type* Description 1 PR0016A I Controlling PZR Pressure Instrument fails high (TS) CRS/RO 2 RD0267 c Dropped control rod (TS) CRS/RO 3 MS0090Ar21 M Steam Rupture in containment on 21 SG during rod ALL insertion RP0277A RP0277B 4 MS0092E c ALL MSIVs fail to shut MS0092F ALL MS0092G MS0092H 5 AF0181A c 21 AFW pump trip CRS/PO 6 RP318L 1 c Containment Spray pumps fail to start RP318L2 ALL Appendix D, Page 38 of 39