ML081770483
| ML081770483 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/08/2008 |
| From: | Peal R Susquehanna |
| To: | Caruso J Operations Branch I |
| Caruso J | |
| Shared Package | |
| ML080390056 | List: |
| References | |
| 50-387/08-302, 50-388/08-302, PLA 006366 | |
| Download: ML081770483 (15) | |
Text
Susquehanna Learning Center 769 Salem Boulevard Berwick, PA 18603-0467 570-542-3353 TM May 8,2008 Mr. John Caruso USNRC Chief Examiner USNRC Region 1 475 Allendale Road King of Prussia, PA 19406-1 41 5 Susquehanna Learning Center Examination Outline PLA 006366 File A1 4-1 3D Mr. Caruso:
Enclosed for your review and approval are the Updated Examination Materials for the PPL Susquehanna, LLC Initial Licensed Operator Examination scheduled on May 16,2008. These materials support the 2008 NRC Written RO Exam, a written retest exam for three [3] RO candidates. These materials are submitted in accordance with NUREG 1021, Operator Licensing Examination Standards for Power Reactors, Revision 9 Supp.1. The following materials are enclosed:
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0 Form ES-201-3, Examination Security Agreement (Up to Date Copy)
Form ES-401-6, Written Examination Quality Checklist - Rev. 0 (Signed)
RO Written Outline (Rev. 5 dated 5/2/08)
- Form ES-401-1, BWR Examination Outline - RO - Rev. 5
- Form ES-401-3, Generic Knowledge and Abilities Outline Tier 3-RO - Rev. 5 Form ES-401-4, Record of Rejected WAS - Rev. 5 Memo with the summary of changes to the exam since the draft submittal.
Hardcopy of all new or revised exam items with new references attached by question.
Electronic copy of the entire exam submittal in MS Word on the enclosed CD-Rom.
0 0
0 0
Modifications to the previously submitted outlines were made as a result of feedback received following NRC review and comments. Following incorporation of the NRC Comments, the entire exam was revalidated with only editorial comments, documented in the summary above.
PLA-006366 File A1 4-1 3D We request that these materials be withheld from public disclosure until after the completion of the examination. If you have any questions, please feel free to contact me at 570-542-31 26 or Chris Michaels at 570-542-1 891.
The above materials have been reviewed for Safeguards Material content. None of these materials are deemed to be Safeguards Material.
Manager-Nuclear Training
Response
No
Enclosures:
Listed cc:
R. M. Fry R. R. Sgarro Ops Letter File Nuc Records-Site cm 45 day cover letter C M/R M P/nl k
ES-401 Written Examination Outline
- acility:
SSES 2008 RO Exam Date of Exam:
511 612008 Vote:
- 1.
- 2.
- 3.
- 4.
5.
- 6.
7.*
- 8.
- 9.
Ensure that at least two topics from every applicable WA 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 WA category shall not be less than two).
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 f l 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.
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 that are not included on the outline should be added. Refer to section D. 1.b of ES-401, for guidance regarding elimination of inappropriate WA statements.
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.
Absent a plant specific priority, only those WAS 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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the WA 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 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. 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.
For Tier 3, select topics from Section 2 of the WA Catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selectionsto WAS that are linked to 10CFR55.43 Susquehanna 2008 RO Written Outline Rev. 5
ES-401 2
Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 X
X EKI.01 - Knowledge of the operational implications of the following concepts to HIGH DRYWELL 295024 High Drywell Pressure 5
4.1 39 295021 Loss of Shutdown zooling I 4 3.6 -
3.3 40 41 295004 Partial or Total Loss of I C Pwr 16 X
29503 1 Reactor Low Water Level I 2 42 295003 Partial or Complete Loss of AC I 6 43 between REACTOR R LEVEL and the COMPONENT COOLING WATER :
Placing standby heat exchanger in SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR 29503 1 Reactor Low Water Level 1 2 44 -
45 29501 8 Partial or Total Loss of ccw I 8 46 41 600000 Plant Fire On-site I 8 295005 Main Turbine Generator Trip I 3 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown I 1 48 I UNKNOWN : CRD hydraulics systems I I
I AAl.02 - Ability to operate and/or I
monitor the following as they apply to 295019 Partial or Total Loss of Inst. Air I 8 49
ES-401 2
Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 I
I 295026 Suppression Pool High Water Temp. 1 5 295025 High Reactor Pressure /
3 I 295023 Refueling Acc Cooling Mode 1 8 295030 Low Suppression Pool Water Level / 5 295028 High Drywell Temperature / 5 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295016 Control Room Abandonment 17 700000 Generator Voltage and Electric Grid Disturbances 295004 Partial or Total Loss of DCPwr/6 3
Group Point Total:
ES-401 3
Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EKl.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH CONTAINMENT HYDROGEN CONCENTRATIONS: Containment 295002 Loss of Main Condenser Vac 1 3 SSURE : HPCI:
295007 High Reactor Pressure 295015 Incomplete SCRAM I
ES-401 4
SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-401-1 stem # / Name 400000 Component Cooling Water 206000 HPCI 300000 Instrument Air I 2 15004 Source Range Monitor I 2 12000 RPS 262001 AC Electrical Distribution 262002 UPS (AC/DC)
CCWS will have on the INJECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Turbine and pump lubrication: BWR-2.9 3.0 1 -
2 I
I 2,3,4 I
I I K4.02 - Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following:
3.0 GE MONITOR Fuel thermal time PCI: INJECTION MODE T SPECIFIC) : Keep fill monitor changes in parameters associated with operating the U T R R U P T A B L E P O W E R 1 2.5 1 8
SUPPLY (A.C./D.C.) controls including: Motor generator ou uts 2.8 2.7 3 -
4 5
ES-40 1 4
SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-401-1 I
263000 DC Electrical Distribution I 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 21 1000 SLC 21 5005 APRM / LPRM monitor changes in parameters associated with operating the D.C.
ELECTRICAL DISTRIBUTION impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMNUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abn cond or ops. Nuclear impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ;
and (b) based on those predictions, use procedures to correct, control, or mitigate the SYSTEM including: Primary automatic operations of the RELIEFEAFETY VALVES I
I I I Plant-Specific I A3.08 - Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including: Control rod block 2.5 3.3 3.1 3.7 3.6 -
4.1 -
3.7
ES-401 4
Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 2 12000 RPS 259002 Reactor Water Level Control 205000 Shutdown Cooling 209001 LPCS 264000 EDGs 261 000 SGTS 259002 Reactor Water Level Control 203000 RHWLPCI: Injection Mode 264000 EDGs I monitoring system I K1.02 - Knowledge of the physical connections andlor cause-effect relationships between REACTOR WATER following concepts as they apply to RHWLPCI: INJECTION MODE (PLANT SPECIFIC) :
I Core cooling methods I K1.04 - Knowledge of the physical connections andor cause-effect relationships between EMERGENCY GENERATORS (DIESEUJET) and the following: Emergency
ES-401 4
SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-401-1 System # I Name PRESSURE CORE SPRAY 209001 LPCS SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following: Reactor water level 205000 Shutdown Cooling rc 3.2 26
ES-401 5
SSES 2008 RO Written Exam Written Examination Outline Plant Systems -Tier 2 Group 2 Form ES-401-1 K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the RECIRCULATION SYSTEM :
Component cooling water 202001 Recirculation 1 systems I K2.02 - Knowledge of electrical I I
286000 Fire Protection 2.9 -
28 -
ower supplies to the following:
cause-effect relationships between ROD WORTH MINIMIZER SYSTEM (RWM)
(PLANT SPECIFIC) and the and/or interlocks which provide for the following: Recirculation 3.4 29 20 1006 RWM 259001 Reactor Feedwater 3.5 30 impacts of the following on the REACTOR FEEDWATER SYSTEM ; and (b) based on to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of 259001 Reactor Feedwater Y
physical connections and/or cause-effect relationships between NUCLEAR BOILER INSTRUMENTATION and the following: Reactor protection 3.9 32 21 6000 Nuclear Boiler Inst.
I system I AI.07 - Ability to predict and/or I I
1 monitor changes in parameters associated with operating the REACTOR CONDENSATE SYSTEM controls including:
Svstem lineuo 256000 Reactor Condensate 3.1 33 2.9 216000 Nuclear Boiler Inst.
monitor changes in parameters associated with operating the NUCLEAR BOILER INSTRUMENTATION controls including: Removing or returning a sensor (transmitter) to service
ES-401 5
SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 Form ES-401-1 27 1000 Off-gas 234000 Fuel Handling Equipment 230000 RHWLPCI:
Torus/Pool Spray Mode WA Category Totals:
1 2 1 1 1 0 A3.02 - Ability to monitor impacts of the following on the REACTOWTURBTNE PRESSURE REGULATING SYSTEM ; and (b) based on those predictions, use procedures I
I procedures.
I I
I A2.09 - Ability to (a) predict the I
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 KIA #
-acility:
Topic SSES 2008 RO Written Exam Date:
5/16/2008 Category I.
- onduct I f Operations
- 2.
Equipment Control
- 3.
Radiation Control
- 4.
Emergency Procedures /
Plan
~,
I Ability to direct personnel activities inside the control 2.1.20 I Ability to interpret and execute procedure steps.
2.1.41 2.1.34 Knowledge of the refueling process.
Knowledge of primary and secondary plant chemistry limits.
Subtotal Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, coordination with the transmission system operator.
Knowledge of the proccss for conducting special or infrcqucnt tests.
2'2'1 2.2.7 Subtotal Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Knowledge of radiation exposure limits under normal or emergency conditions.
2'3' l2 2'3'4 Subtotal Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, AOP's and SAMGs.
2.4.16 2.4.42 Knowlcdgc of emergency response facilities.
Subtotal Tier 3 Point Total SRO-Only
- 2.6 I 73 I
ES-401 2 1 2 Record of Rejected KIAs 201004 / K3.01 Form ES-401-4 3 1 2 2 1 2 2 1 2 2 1 2 2 1 2 Randomly TierGroup I Selected WA I
G2 / 2.2.23 task above the level which would make a discriminating question for an RO. Randomly replaced with 2.1.41.
(Q #3 1) This WA topic has limited operational validity for RO applicants. Randomly replaced with 259001 A2.04.
(Q #3 1) Oversampled Condensate System. This KIA topic has limited operational validity for RO applicants. Randomly replaced with 259001 A2.04.
(Q #32) Essential Power used for RBM Operator Display Assembly ODA only with limited operational impact. Randomly replaced with 2 16000 K1.O 1.
(Q #27) Over sampled K1 in Tier Group 2. Randomly replaced 286000 K507 256000 / K2.01 215002 / K6.03 223001 K117 with 272000 K6.02.
Reason for Rejection I
I (n
- nversampled K1 in Tier Group 1. Randomly replaced IO K5.01.
,,v,,&,,
I,iere is no direct system interrelationship between (Q #54) KA for High Offsite Release Rate with Generic 2.2.38 raises this to the SRO level, making it difficult to write a discriminating question at the RO level. Randomly replaced with 295028 G2.4.6.
(Q #2) Concept too basic to write a discriminating question related to the subject WA. Randomly replaced with 295002 K1.02.
(Q #lo) Duplicate KA for nuclear Instrument detector position.
Deselected the IRM, retained the SRM WA. Randomly replaced with 212000 K5.01.
(Q #20) At Susquehanna, the APRM back panel meters, switches and indicator lights are in the Lower Relay Room, not the control room with limited operational impact due to the recent PRNMS modification. Randomly replaced with 215005 A3.08.
(Q #29) Current plant procedure has this system bypassed in startup and shutdown, only used for indication following reactor scram. RSCS has limited use at SSES and has been removed 295038 22*38 1 1 1 211 21 1000 / K1.07 211 2 15003 / K5.03 239002 /K106 2 1 1 2 1 1 215005 / A4.03 (Q #lo) Oversampled K1 in Tier Group 1. Randomly replaced with 212000 K5.01.
(Q #27) There is no direct system interrelationship between 2 1 2 2 1 2 2 1 2 2 1 2 from TS and TRM. Randomly replaced with 201006 K1.02.
(Q #69) The KA to track Technical Specification LCO is a SRO 272000 / K6.02 Radiation Monitoring and DC power. Randomly ieplaced with 202001 K6.02.
(Q #30) Concept too basic to write a discriminating question on this design feature. Randomly replaced with 259001 K4.11.
(Q #28) Very similar to WA on power supply to Core Spray pumps. Oversampled ECCS power supplies. Randomly reselected with WA 286000 K2.02.
(Q #34) Oversampled Reactor Feedwater and for the RFP trip, question in this area would be too simplistic per telecon with Chief Examiner. Randomly replaced with WA 216000 A1.02.
239001 K4*04 233000 / K2.02 25900 1 / A2.0 1 Page 1 of 2
ES-401 Record of Rejected WAS Form ES-401-4 (Q #58) Duplicate to Question #63, similar WA with only difference between Scram and Incomplete Scram. Randomly replaced with WA 295004 AA2.04.
(Q #59) Very narrow scope of containment isolations that have any effect on reactivity control. Randomly replaced with WA 50000 EK1.O1.
111 295006 / AA2.02 112 295020 / AK1.02 (Q #26) This WA overlaps with similar WAS randomly selected on the EPE/APE section of the exam, e.g., Questions 5 1, 61.
Randomly replaced with 20900 1 K3.O 1.
(Q #42) This concept overlaps with existing WA in Question 54 related to High Drywell Temperature. Randomly replaced with 211 212000 / K3.09 111 295028 / EK2.01 WA 29503 1 EA2.01.
(Q #19) Oversampled 259002 Feedwater Water Level Control (FWLC) in Tier 2. Randomly reselected WA 21 1000 A4.05.
(Q#26) Oversampled 209001 LPCS system in Tier 2 Group 1.
Randomly reselected WA 205000 K3.02.
259002 A4*02 209001 K301 211 211 Page 2 of 2