ML081770483

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Final Examination Outlines (Folder 3)
ML081770483
Person / Time
Site: Susquehanna  Talen Energy icon.png
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)
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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 19406-1415 Susquehanna Learning Center Examination Outline PLA 006366 File A14-13D 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:

0 Form ES-201-3, Examination Security Agreement (Up to Date Copy) 0 Form ES-401-6, Written Examination Quality Checklist - Rev. 0 (Signed) 0 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 0 Form ES-401-4, Record of Rejected WAS - Rev. 5 0 Memo with the summary of changes to the exam since the draft submittal.

0 Hardcopy of all new or revised exam items with new references attached by question.

0 Electronic copy of the entire exam submittal in MS Word on the enclosed CD-Rom.

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 A14-13D 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 570-542-3126 or Chris Michaels at 570-542-1891.

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 CM/R MP/nlk

ES-401 Written Examination Outline

acility: SSES 2008 RO Exam Date of Exam: 511612008 Vote: 1. 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).
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 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.
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 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.
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 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.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* 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

8. 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. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. 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 EKI.01 - Knowledge of the operational implications of the following concepts 295024 High Drywell Pressure X to HIGH DRYWELL 4.1 39 5

295021 Loss of Shutdown X 3.6 40 zooling I 4 295004 Partial or Total Loss of X 3.3 41 I C Pwr 16 29503 1 Reactor Low Water 42 Level I 2 295003 Partial or Complete 43 Loss of AC I 6 between REACTOR 29503 1 Reactor Low Water R LEVEL and the 44 Level 1 2 29501 8 Partial or Total Loss of 45 ccw I 8 COMPONENT COOLING WATER :

Placing standby heat exchanger in 600000 Plant Fire On-site I 8 46 295005 Main Turbine 41 Generator Trip I 3 295037 SCRAM Conditions Present and Reactor Power SCRAM CONDITION PRESENT 48 Above APRM Downscale or AND REACTOR POWER ABOVE Unknown I 1 APRM DOWNSCALE OR 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 49 Inst. Air I 8

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 1 7 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 295007 High Reactor Pressure SSURE : HPCI:

295015 Incomplete SCRAM I

ES-401 4 Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 stem # / Name 400000 Component Cooling Water CCWS will have on the 2.9 1 INJECTION SYSTEM design 206000 HPCI feature(s) and/or interlocks which 3.0 2 provide for the following: Turbine and pump lubrication: BWR-I I 2,3,4 - I I I K4.02 - Knowledge of (INSTRUMENT AIR SYSTEM) 300000 Instrument Air design feature(s) and or interlocks 3.0 3 which provide for the following:

I 2 15004 Source Range Monitor GE MONITOR 2.8 4 I

2 12000 RPS 2.7 5

Fuel thermal time 262001 AC Electrical Distribution PCI: INJECTION MODE 11 T SPECIFIC) : Keep fill monitor changes in parameters associated with operating the 262002 UPS (AC/DC) UTRRUPTABLEPOWER 2.5 8 SUPPLY (A.C./D.C.) controls including: Motor generator ou uts

ES-401 4 Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 I

263000 DC Electrical monitor changes in parameters associated with operating the D.C. 2.5 Distribution ELECTRICAL DISTRIBUTION I223002 PCIS/Nuclear Steam Supply Shutoff 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 3.3 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 3.1 predictions, use procedures to correct, control, or mitigate the 3.7 SYSTEM including: Primary automatic operations of the 239002 SRVs RELIEFEAFETY VALVES 3.6 21 1000 SLC I I 4.1 I I Plant-Specific -

I A3.08 - Ability to monitor automatic operations of the AVERAGE POWER RANGE 21 5005 APRM / LPRM MONITOR/LOCAL POWER 3.7 RANGE MONITOR SYSTEM including: Control rod block

ES-401 4 Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 2 12000 RPS I monitoring system I K1.02 - Knowledge of the physical connections andlor cause- effect relationships 259002 Reactor Water Level between REACTOR WATER Control 205000 Shutdown Cooling 209001 LPCS 264000 EDGs 261 000 SGTS 259002 Reactor Water Level Control 203000 RHWLPCI: Injection following concepts as they apply Mode to RHWLPCI: INJECTION MODE (PLANT SPECIFIC) :

I Core cooling methods I K1.04 - Knowledge of the physical connections andor cause- effect relationships 264000 EDGs between EMERGENCY GENERATORS (DIESEUJET) and the following: Emergency

rc ES-401 4 Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 System # I Name PRESSURE CORE SPRAY 209001 LPCS SHUTDOWN COOLING 205000 Shutdown Cooling SYSTEM (RHR SHUTDOWN 3.2 26 COOLING MODE) will have on following: Reactor water level

ES-401 5 Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Plant Systems -Tier 2 Group 2 K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the 202001 Recirculation RECIRCULATION SYSTEM :

Component cooling water 286000 Fire Protection I

1 I

systems K2.02 - Knowledge of electrical ower supplies to the following:

I 2.9 28 cause- effect relationships between ROD WORTH 20 1006 RWM MINIMIZER SYSTEM (RWM) 3.4 29 (PLANT SPECIFIC) and the 259001 Reactor Feedwater 3.5 30 and/or interlocks which provide for the following: Recirculation impacts of the following on the REACTOR FEEDWATER SYSTEM ; and (b) based on 259001 Reactor Feedwater to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of Y

physical connections and/or cause- effect relationships 21 6000 Nuclear Boiler Inst. between NUCLEAR BOILER 3.9 32 INSTRUMENTATION and the following: Reactor protection I

I I

system AI .07 - Ability to predict and/or monitor changes in parameters I 1 associated with operating the 3.1 33 256000 Reactor Condensate REACTOR CONDENSATE SYSTEM controls including:

Svstem lineuo -

monitor changes in parameters associated with operating the 216000 Nuclear Boiler Inst. NUCLEAR BOILER 2.9 INSTRUMENTATION controls including: Removing or returning a sensor (transmitter) to service

ES-401 5 Form ES-401-1 SSES 2008 RO Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 A3.02 - Ability to monitor 27 1000 Off-gas 234000 Fuel Handling Equipment 230000 RHWLPCI:

Torus/Pool Spray Mode I I procedures. I I I A2.09 - Ability to (a) predict the I impacts of the following on the REACTOWTURBTNE PRESSURE REGULATING SYSTEM ; and (b) based on those predictions, use procedures WA Category Totals: 121110

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

-acility: SSES 2008 RO Written Exam Date: 5/16/2008 SRO-Only Category KIA # Topic

~ , I Ability to direct personnel activities inside the control I.

onduct 2.1.20 I Ability to interpret and execute procedure steps.

I f Operations 2.1.41 Knowledge of the refueling process.

Knowledge of primary and secondary plant chemistry 2.1.34 limits.

Subtotal Knowledge of the process for managing maintenance activities during power operations, such as risk

2. 2'2'1 assessments, work prioritization, coordination with the Equipment transmission system operator.

Control Knowledge of the proccss for conducting special or 2.2.7 infrcqucnt tests.

Subtotal Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as containment entry

3. 2'3' l 2 requirements, fuel handling responsibilities, access to Radiation locked high-radiation areas, aligning filters, etc.

Control Knowledge of radiation exposure limits under normal or 2'3'4 emergency conditions.

Subtotal

4. Knowledge of EOP implementation hierarchy and Emergency 2.4.16 coordination with other support procedures or guidelines Procedures / such as, operating procedures, AOP's and SAMGs.

Plan 2.4.42 Knowlcdgc of emergency response facilities. 2.6 I 73 I Subtotal Tier 3 Point Total

ES-401 Record of Rejected KIAs Form ES-401-4 TierGroup I Randomly Selected WA I Reason for Rejection (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 111 295038 22*38 discriminating question at the RO level. Randomly replaced with 295028 G2.4.6.

(Q #2) Concept too basic to write a discriminating question 211 21 1000 / K1.07 related to the subject WA. Randomly replaced with 295002 K1.02.

(Q #lo) Duplicate KA for nuclear Instrument detector position.

211 2 15003 / K5.03 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 211 215005 / A4.03 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 212 201004 / K3.01 scram. RSCS has limited use at SSES and has been removed from TS and TRM. Randomly replaced with 201006 K1.02.

(Q #69) The KA to track Technical Specification LCO is a SRO 312 G2 / 2.2.23 task above the level which would make a discriminating question for an RO. Randomly replaced with 2.1.41.

212 286000 K507 (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 212 256000 / K2.01 limited operational validity for RO applicants. Randomly replaced with 259001 A2.04.

(Q #32) Essential Power used for RBM Operator Display 212 215002 / K6.03 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 212 223001 K117 with 272000 K6.02.

I (Q

  • I (n #lo) nversampled Oversampled K1 in Tier Group 1. Randomly replaced 211 239002 /K106 with 212000 IO K5.01.

, ,v ,,&,,There (Q #27) I ,iere is no direct system interrelationship between 212 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 212 239001 K4*04 this design feature. Randomly replaced with 259001 K4.11.

(Q #28) Very similar to WA on power supply to Core Spray 212 233000 / K2.02 pumps. Oversampled ECCS power supplies. Randomly reselected with WA 286000 K2.02.

(Q #34) Oversampled Reactor Feedwater and for the RFP trip, 212 25900 1 / A2.0 1 question in this area would be too simplistic per telecon with Chief Examiner. Randomly replaced with WA 216000 A1.02.

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ES-401 Record of Rejected WAS Form ES-401-4 (Q #58) Duplicate to Question #63, similar WA with only 111 295006 / AA2.02 difference between Scram and Incomplete Scram. Randomly replaced with WA 295004 AA2.04.

(Q #59) Very narrow scope of containment isolations that have 112 295020 / AK1.02 any effect on reactivity control. Randomly replaced with WA 50000 EK1.O1.

(Q #26) This WA overlaps with similar WAS randomly selected 211 212000 / K3.09 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 54 111 295028 / EK2.01 related to High Drywell Temperature. Randomly replaced with WA 29503 1 EA2.01.

211 259002 A4*02 (Q #19) Oversampled 259002 Feedwater Water Level Control (FWLC) in Tier 2. Randomly reselected WA 21 1000 A4.05.

211 209001 K301 (Q#26) Oversampled 209001 LPCS system in Tier 2 Group 1.

Randomly reselected WA 205000 K3.02.

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