ML022970271
| ML022970271 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/05/2002 |
| From: | Michaels C Exelon Nuclear |
| To: | Bissett P NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-277/02-302, 50-278/02-302 50-277/02-302, 50-278/02-302 | |
| Download: ML022970271 (30) | |
Text
To:
Paul Bissett, NRC Chief Examiner From: Chris Michaels, Peach Bottom Exam Author
?/7'o &
CC:
Phil Nielsen, MAROG Exam Development Coordinator Date: 9/5/2002 Re:
Initial License Exam NRC review comments for 9/23/02 Peach Bottom Exam.
The revised Peach Bottom Exam for administration the week of 23 September 2002 is attached. The following exam comments were addressed in response to the Peach Bottom NRC Exam preparation and reviews during the week of 26 August 2002.
Wriften Exam Comment Summary
- 1. Question ID#9 (ROISRO#9) Comment: Editorial comment for the word Operable which is capitalized.
Response: The word "Operable" is capitalized in Peach Bottom procedures to denote the reference to Technical Specifications. The word is sometimes written in full caps i.e.,
"OPERABLE". Either is acceptable.
Agreed Resolution: No change is required.
- 2. Question ID#13 (ROISRO#13) Comment: Periods missing in stem.
Response: Corrected editorial comment as discussed.
- 3. Question ID#22 (ROISRO#22) Comment: Periods missing in stem and write outthe time "15 minutes" as fifteen (15) minutes.
Response: Corrected as discussed.
- 4. Question ID#27 (ROISRO#27) Comment: Add the word "the" to expected response.
Response: Corrected as discussed.
- 5. Question ID#32 (ROISRO#32) Comment: Two possible answers.
Response: Agree with comment and changed stem to add a qualifier to rule out one choice.
Agreed Resolution: Changed stem to "...and choose the FIRST required course of action".
- 6. Question ID#35 (ROISRO#35) Comment: Capitalize the word "after" to draw attention to the time sequence.
Response: Corrected as discussed to "AFTER the first ten minutes".
- 7. Question ID#44 (RO/SRO#44) Comment: Grammatically awkward statement in bullets.
Response: Statement is consistent with local vernacular but changed to be easier to read. Sentence changed to "...was started on the drywell and now reads..."in both bullets 4 and 5.
- 8. Question ID#49 (ROISRO#49) Comment: In the e bullet, the word "Air made Choice
'C' implausible.
Response: Agree with comment.
Agreed Resolution: Deleted the word "All" from the 6e bullet. All Choices now plausible.
- 9. Question ID#53 (ROISRO#53) Comment: In Choice 'D', add the word "in".
Response: Corrected as discussed to add the word.
- 10. Question ID#54 (ROISRO#54) Comment: In 4th bullet, word "pumps" appears to be missing.
Response: Corrected as discussed and added "...pumps..." to enhance statement.
- 11. Question ID#55 (ROISRO#55) Comment: In stem, is "...operated at rated power' acceptable or should it be operating?
Response: Corrected and stem changed to "...operating at rated power"to enhance sentence.
- 12. Question ID#60 (RO/SRO#60) Comment: Opening statement in stem is grammatically awkward.
Response: Agree and corrected as discussed to "Unit 3 was operating at full power when... The following conditions currently exist:'
- 13. Question ID#61 (RO/SRO#61) Comment: Question seems awkward with the location of "next".
Response: Corrected as discussed to "...which area is investigated NEXT as the source of the high radiation."
- 14. Question ID#66 (ROISRO#66) Comment: Could we add "heatup rate" to Choice 'D'to identify the LCO of concern.
Response: Corrected as discussed and added the phrase "heatup rate"to both Choices
'C' and 'D' to clarify the limits and balance both statements.
- 15. Question ID#67 (RO/SRO#67) Comment: Two true/false pairs since the ol level is out of spec.
Response: We understand the comment and although this was a previously approved NRC question from Aug 2001, agree the question should be revised.
Agreed Resolution: Corrected the stem to remove part I of the question and focus the question on the logging action. Answer options have been modified to be consistent with the revised question. This revision significantly improves the question quality and provides direct K/A applicability.
- 16. Question ID#84 (RO#84) Comment: Inconsistent use of procedure title in this question as compared to other questions.
Response: Corrected as discussed to format the procedure number and title consistently.
- 17. Question ID#91 (RO#91) Comment: In stem, appears that the word "in" is missing.
Response: Corrected as discussed to "...was placed in Torus Cooling in accordance with..."
- 18. Question ID#92 (RO#92) Comment: Bullet 3 doesn't read correctly and adding the procedure requirement would provide stem focus.
Response: Corrected as discussed. Bullet 3 now reads "...is in alarm." and question includes procedure "...in accordance with SO..."
Page 2 of 5
- 19. Question ID#94 (RO#94) Comment: Statement not consistent with prior questions.
Response: Corrected as discussed to read "Which one of the following statements is correct?"
- 20. Question ID#95 (RO#95) Comment: Choice A(2) doesn't specify the type of isolation.
Response: Corrected as discussed to add the words "...Group I isolation."and added "Reactor Building"to choice 'B(2)' to balance distractors.
- 21. Question ID#96 (RO#96) Comment: Grammatically awkward and need to add words "if any".
Response: Corrected as discussed to "...which one of the following manual actions, if any, is required in accordance with..."
- 22. Question ID#97 (RO#97) Comment: There is duplication in the question and statement can be simplified.
Response: Corrected as discussed. Statement changed to "Throttle open the:"
- 23. Question ID#98 (RO#98) Comment: Use of capitalization in Choices not consistent.
Response: Corrected as discussed. Word capitalization changed to be consistent with other questions in the exam.
- 24. Question ID#102 (SRO#77) Comment: Delete the word "and" in Choice 'C'. The words "to monitor" seem redundant.
Response: Corrected as discussed to delete "and" and "to monitor" in the choices.
- 25. Question ID#103 (SRO#78) Comment: Enhancing the justification statements would improve the apparent relevance of the question as SRO only.
Response: Corrected as discussed to enhance the justifications to include the required knowledge of the Tech Spec bases.
- 26. Question ID#108 (SRO#83) Comment: Could we reword the question to focus on Tech Spec Action. Is the phrase "most limiting" acceptable at Peach Bottom?
Response: Stem corrected and revised to "...select the MOST RESTRICTIVE Tech Spec Action (TSA)?
- 27. Question ID#1 19 (SRO#94) Comment: Need to focus the stem to prevent multiple correct answers.
Response: Agree that stem could be focused but believe there is only one correct answer.
Agreed Resolution: Revised the opening statement for the choices to "RP-AA-460 "Controls for High and Very High Radiation Areas" permits entry into the High Radiation Area during a transient provided that the Operator:"
- 28. Question ID#122 (SRO#97) Comment: Stem needs to ask what actions, if any, are required.
Response: Corrected as discussed. Question revised to "...and what additional actions, if any, are required?"
Page 3 of 5
System JPM Comment Summary JPM#3: Main Steam Recovery from a Group I Isolation Minor change to procedure reference on page 7.
JPM#7; Low CRD Scram Air Header Pressure Added Cue to Step #8 "Monitoring Scram Air headerpressure and it is below 80 psig."
JPM#10: Closing a Stuck Open MSIV For the Examiner, added information regarding fuse locations inside the panel.
Revised Steps 9 and 10 so that the operator in the field does not need to direct RO actions in the control room. Step 9 now states that the operator will determine that Section 4.1 was not successful, that Section 4.2 cannot be performed and that Section 4.3 will be required to close the MSIVs.
Added a Cue in Step 9 that the RO has completed Steps 4.3.1 throuli 4.3.3 and to direct the operator to continue in the procedure starting at Step 4.3.4.
Step 10 revised to state that the operator will go to the Unit 3 Recirc MG Set Room to perform Step 4.3.4.
Admin JPM Comment Summary RO Admin#3:
Revise the Task Initiating Cue to state: "The Control Room Supervisor directs you to use P&lDs to determine the impact of the damaged PS0246B on the ESW pumps, ECW pump and ECW Pump Discharge valve (MO-0841) during an automatic Diesel Generator start."
SRO Admin#1:
Correct the footers of the Attachments 1,2 and 3 so the examiner knows wliat attachments are to be provided to the candidate.
SRO Admin#2:
Revise the Cue on page 6 that identifies the JPM Attachment 3 as the procedure RE C-01 Appendix 7 Attachment 1.
SRO Admin#3:
Revise the Task Initiating Cue to: "The attached clearance request for the 'A' Service Water Booster Pump has just been prepared for emergent work. The Shift Manager directs you, the Work Execution Center (WEC) Supervisor, to review and approve the clearance request for immediate application and inform the Control Room Supervisor (CRS) when complete."
Page 4 of 5
Dynamic Scenario Comment Summary Scenario #1 Event#2:
"* Corrected error from 24 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
"* Added Cue to state "If needed, as Shift Manager, prompt the crewto place the RPS Channel in trip in accordance with GP-25 App 1."
Scenario #2 Event #1:
Prior to removing Reactor Feedpump, override off the Hotwell Level High alarm to prevent unnecessary distraction from the normal operating event.
Scenario #3 Event #2:
Trouble alarm did not flash as expected. Discussed the response with Simulator Support and alarm window is a simulation problem to be corrected as soon as possible. Lead Examiner determined that alarm window problem is minor and would have little impad, if any on scenario.
Page 5 of 5
ES-401 BWR RO Examination Outline Facility:
Peach Bottom Atomic Power Station Exam Date: 09/23/2002 Printed: 09/05/2002 Form ES-401-2 Exam Level: RO Group K/A Category Points K1 K2 K3 K4 K5 K6 1
2 3
3
- 1.
Emergency 2
4 6
3 Abnormal Plant 3
1 1
1 Evolutions Totals 7
10 7
Tier
- 2.
Plant Systems 2
2 3
2 3
3 Al 2
5 1
8 2
A2 A3 A4 2
0 0
2 3
2 3
G 1
0 2
3 Point Point Total 13 19 4
36 28 2
2 2
2 2
2 1
2 2
1 2
1 19 3
0 0
1 1
0 1
0 0
0 1
0 4
Tier Totals 4
4 6
5 5
5 4
5 3
6 4
51 Cat I Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge And Abilities 3
4 3
3 13 Note:
- 1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.
- 2. Actual point totals must match those specified in the table.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category tier.
I Tier I
Pea Bottom Atomic Power Stat BWR RO mination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.
Points 295005 Main Turbine Generator Trip / 3 X
AA1.04 - Main generator controls 2.7 1
295006 SCRAM / I X
AK3.03 - Reactor pressure response 3.8 1
295007 High Reactor Pressure / 3 X
AK2.06 - PCIS/NSSSS: Plant-Specific 3.5 1
295009 Low Reactor Water Level / 2 X
AK2.04 - Reactor water cleanup 2.6 1
295015 Incomplete SCRAM / 1 X
AK3.01 - Bypassing rod insertion blocks 3.4 1
295015 Incomplete SCRAM / 1 X
AK2.04 - RPS 4.0 1
295024 High Drywell Pressure / 5 X
EA1.03 - LPCS: Plant-Specific 4.0 1
295025 High Reactor Pressure / 3 X
EKI.02 - Reactor vessel integrity 4.1 1
295031 Reactor Low Water Level / 2 X
EK 1.03 - Water level effects on reactor power 3.7 1
295031 Reactor Low Water Level / 2 X
EA2.01 - Reactor water level 4.6*
1 295037 SCRAM Condition Present and Reactor Power Above X 2.1.27 - Knowledge of system purpose and/or function.
2.8 1
APRM Downscale or Unknown / I 500000 High Containment Hydrogen Concentration / 5 X
EK3.07 - Operation of drywell vent 3.1 1
500000 High Containment Hydrogen Concentration / 5 X
EA2.01 - Hydrogen monitoring system availability 3.1 1
K/A Category Totals:
2 Facility:
ES - 401 Printed:
09/05/2(
3 3
2 2
1 Group Point Total:
13 I
BWR RO ý mination Outline Pe(., 3ottom Atomic Power Stat Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 2 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 295001 Partial or Complete Loss of Forced Core Flow X
AA1.07 - Nuclear boiler instrumentation system 3.1 1
Circulation / 1 295002 Loss of Main Condenser Vacuum / 3 X
AK3.03 - Reactor feedpump turbine trip: Plant-Specific 3.3 1
295003 Partial or Complete Loss of A.C. Power / 6 X
AK2.01 - Station batteries 3.2 1
295003 Partial or Complete Loss of A.C. Power / 6 X
AA 1.02 - Emergency generators 4.2*
1 295008 High Reactor Water Level / 2 X
AK2.08 - Main turbine: Plant-Specific 3.4 1
295012 High Drywell Temperature / 5 X
AA1.01 - Drywell ventilation system 3.5 1
295013 High Suppression Pool Temperature / 5 X
AK1.03 - Localized heating 3.0 1
295016 Control Room Abandonment / 7 X
AK3.01 - Reactor SCRAM 4.1*
1 295017 High Off-Site Release Rate / 9 X 2.4.4 - Ability to recognize abnormal indications for 4.0 1
system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
295017 High Off-Site Release Rate / 9 X
AK2.09 - Condenser air removal system: Plant-Specific 2.8 1
295018 Partial or Complete Loss of Component Cooling X
AK1.01 - Effects on component/system operations 3.5 1
Water / 8 295019 Partial or Complete Loss of Instrument Air / 8 X
AK3.02 - Standby air compressor operation 3.5 1
295022 Loss of CRD Pumps / I X
AAI.02 - RPS 3.6 1
295029 High Suppression Pool Water Level / 5 X
EK2.08 - Drywell/suppression chamber ventilation 2.6 1
I Facility:
ES - 401 Printed:
09/05/2(
ll*nrm Eq-dfl 1-9.
Facility:
Pe(
3ottom Atomic Power Stat ES - 401 BWR RO (
mination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 K/A Category Totals:
4 6
3 5
0 1
Group Point Total:
19 2
Form ES-401-2 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 295030 Low Suppression Pool Water Level / 5 X
EK1.02 - Pump NPSH 3.5 1
295030 Low Suppression Pool Water Level / 5 X
EA1.06 - Condensate storage and transfer (make-up to 3.4 1
the suppression pool): Plant-Specific 295033 High Secondary Containment Area Radiation Levels /
X EK2.02 - Process radiation monitoring system 3.8 1
9 295038 High Off-Site Release Rate / 9 X
EK2.01 - Radwaste 3.1 1
600000 Plant Fire On Site / 8 X
AK1.02 - Fire Fighting 2.9 1
Printed:
09/05/7(
Facility:
Pe(. Bottom Atomic Power Stat ES - 401 BWR RO (
mination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / Group 3 K/A Category Totals:
1 1
1 1
0 0
Group Point Total:
E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 295021 Loss of Shutdown Cooling / 4 X
AK1.04 - Natural circulation 3.6 1
295023 Refueling Accidents / 8 X
AA1.04 - Radiation monitoring equipment 3.4 1
295035 Secondary Containment High Differential Pressure / 5 X
EK2.04 - Blow-out panels: Plant-Specific 3.3 1
295036 Secondary Containment High Sump/Area Water X
EK3.01 - Emergency depressurization 2.6 1
Level / 5 Form ES-401-2 4
1 Printed:
09/05/7(
F Facility:
Peach Bottom Atomic Power Stat
- dill Printed:
09/0/
-12 BWR RO Eý ination Outline Plant Systems - Tier 2 / Groun 1
- Form ES-401-2 Sys/Ev #
System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 201001 Control Rod Drive Hydraulic System /
X K5.02 - Flow indication 2.6 1
1 201002 Reactor Manual Control System / 1 X
K4.01 - Detection of sequence timer 2.7 1
malfunction 201002 Reactor Manual Control System / I X
K6.01 - Select matrix power 2.5 1
202002 Recirculation Flow Control System /I X
K5.01 - Fluid coupling: BWR-3, 4 2.8 1
203000 RHR/LPCI: Injection Mode (Plant X
K2.03 - Initiation logic 2.7*
1 Specific) / 2 206000 High Pressure Coolant Injection X 2.1.23 - Ability to perform specific system and 3.9 1
System / 2 integrated plant procedures during different modes of plant operation.
211000 Standby Liquid Control System! I X
K1.06 - Reactor vessel 3.7 1
211000 Standby Liquid Control System! I X
K3.01 - tAbility to shutdown the reactor in 4.3' 1
certain conditions 212000 Reactor Protection System / 7 X
A4.09 - SCRAM instrument volume level 3.9 215005 Average Power Range Monitor/Local X
K3.01 - RPS 4.0 1
Power Range Monitor System / 7 215005 Average Power Range Monitor/Local X
K4.08 - Sampling of overall core power in each 2.7 1
Power Range Monitor System / 7 APRM (accomplished through LPRM assignments and symmetrical rod patterns) 1
c Peach Bottom Atomic Power Stat BWR RO Eý ination Outline Plant Systems - Tier 2 / GrouD 1 Printed:
09/0 t 12 Sys/Ev#
System/Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 216000 Nuclear Boiler Instrumentation / 7 X
A2.14 - Recirculation flow: Design-Specific 2.9 1
217000 Reactor Core Isolation Cooling X
K5.04 - Testable check valve operation 2.6 1
System (RCIC) / 2 1
1 1_1_1_1_1 217000 Reactor Core Isolation Cooling X
K 1.01 - Condensate storage and transfer system 3.5 1
System (RCIC) / 2 218000 Automatic Depressurization System /
X 2.4.49 - Ability to perform without reference to 4.0 1
3 procedures those actions that require immediate operation of system components and controls.
223001 Primary Containment System and X
A1.01 - Drywell temperature 3.5 1
Auxiliaries / 5 223001 Primary Containment System and X
A4.05 - Containment/drywell oxygen 3.6 1
Auxiliaries / 5 concentration 223002 Primary Containment Isolation X
A2.06 - Containment instrumentation failures 3.0 1
System/Nuclear Steam Supply Shut-Off / 5 223002 Primary Containment Isolation X
K3.04 - Reactor building radiation level 3.4 1
System/Nuclear Steam Supply Shut-Off/ 5 239002 Relief/Safety Valves / 3 X
K2.01 - SRV solenoids 2.8*
1 239002 Relief/Safety Valves /3 X
A2.01 - Stuck open vacuum breakers 3.0 1
259001 Reactor Feedwater System / 2 X 2.1.27 - Knowledge of system purpose and/or 2.8 1
I function.
2 Facility:
ES - 401 Form FS-4fll-*
Peach Bottom Atomic Power Stat Printed:
09/0 t
ination Outline Plant Systems - Tier 2 / Group 1 K/A Category Totals:
2 2
3 2
3 3
2 3
2 3
3 Group Point Total:
Facility:
ES - 401 Sys/Ev#
System/Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 259002 Reactor Water Level Control System /
X K6.04 - Reactor feedwater flow input 3.1 1
2 259002 Reactor Water Level Control System /
X A3.03 - Changes in main steam flow 3.2 1
2 261000 Standby Gas Treatment System / 9 X
A4.01 - tOff-site release levels: Plant-Specific 3.2*
1 261000 Standby Gas Treatment System / 9 X
A3.03 - Valve operation 3.0 1
264000 Emergency Generators (Diesel/Jet) / 6 X
K6.02 - Fuel oil pumps 3.6 1
264000 Emergency Generators (Diesel/Jet) / 6 X
A 1.09 - Maintaining minimum load on 3.0 1
emergency generator (to prevent reverse power) 28 3
Form E*q-4fll-2
(
Peach Bottom Atomic Power Stat BWR RO E(
iination Outline Plant Systems - Tier 2 / Group 2 Printed:
09/0' f
)2 Sys/Ev#
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 201006 Rod Worth Minimizer System (RWM)
X K6.02 - Reactor water level control input:
2.9 1
(Plant Specific) / 7 P-Spec(Not-BWR6) 204000 Reactor Water Cleanup System / 2 X
A3.06 - Lights and alarms 3.1 1
204000 Reactor Water Cleanup System / 2 X
K3.01 - Reactor water quality 3.2 1
205000 Shutdown Cooling System (RHR X
K2.02 - Motor operated valves 2.5*
1 Shutdown Cooling Mode) / 4 1
205000 Shutdown Cooling System (RHR X
A1.02 - SDC/RHR pump flow 3.3 Shutdown Cooling Mode) / 4 215002 Rod Block Monitor System / 7 X 2.4.31 - Knowledge of annunciators alarms and 3.3 indications, and use of the response instructions.
219000 RHR/LPCI: Torus/Suppression Pool X
A4.02 - Valve lineup 3.7*
1 Cooling Mode / 5 219000 RHR/LPCI: Torus/Suppression Pool X
K5.01 - System venting 2.6 1
Cooling Mode / 5 226001 RHR/LPCI: Containment Spray X
K4.12 - Prevention of inadvertent containment 2.9 1
System Mode / 5 spray activation 230000 RHR/LPCI: Torus/Suppression Pool X
A1.04 - System flow 3.2*
1 Spray Mode / 5 239001 Main and Reheat Steam System / 3 X
K4.01 - Automatic isolation of steam lines 3.8 245000 Main Turbine Generator and Auxiliary X
K3.02 - Reactor pressure 3.9 1
Systems / 4 Facility:
Peach Bottom Atomic Power Stat K/A Category Totals:
2 2
2 2
.ination Outline Plant Systems - Tier 2 / GrouD 2 1
2 2
1 Printed:
09/0*
12 Sys/Ev #
System / Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 256000 Reactor Condensate System / 2 X
K2.01 - System pumps 2.7*
1 262002 Uninterruptable Power Supply X
K1.08 - Containment isolation system:
2.9 1
(A.C./D.C.) / 6 Plant-Specific 272000 Radiation Monitoring System / 7 X
A2.06 - Downscale trips 2.8 1
290001 Secondary Containment / 5 X
KI.02 - Primary containment system:
3.4 1
Plant-Specific 290001 Secondary Containment / 5 X
A2.05 - High area temperature 3.1 1
300000 Instrument Air System (IAS) / 8 X
K5.13 - Filters 2.9 1
400000 Component Cooling Water System X
A4.01 - CCW indications and control 3.1 1
(CCWS) / 8 1
1 1
1 1
2 1
Group Point Total:
19 2
Facility:
C Facility:
Peach Bottom Atomic Power Stat ES - 401 BWR RO E(
ination Outline Plant Systems - Tier 2 / Group 3 Printed:
09/05( T 2
Sys/Ev#
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 215001 Traversing In-Core Probe / 7 X
K6.04 - Primary containment isolation system:
3.1 1
Mark-I&II(Not-BWRI) 233000 Fuel Pool Cooling and Clean-up / 9 X
A4.06 - System temperature 2.5*
1 234000 Fuel Handling Equipment / 8 X
K3.04 - tcore modifications/alterations 2.9 1
290002 Reactor Vessel Internals / 5 X
K4.01 - 2/3 core coverage following a DBA 3.7 1
1_
1_1_1_1_1_1_1LOCA K/A Category Totals:
0 0
1 1
0 1
0 0
0 1
0 Group Point Total:
4 Form ES-401-2
Generic Knowledge and Abilities Outline (Tier 3)
E BWR RO Examination Outline Printed: 09/05/2002(
Form ES-401-5 Imp.
Points KA Topic Conduct of Operations 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating 3.7 1
characteristics, reactor behavior, and instrument interpretation.
2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports.
2.9 1
2.1.29 Knowledge of how to conduct and verify valve lineups.
3.4 1
Category Total:
3 Equipment Control 2.2.2 Ability to manipulate the console controls as required to operate the facility between 4.0 1
shutdown and designated power levels.
2.2.11 Knowledge of the process for controlling temporary changes.
2.5 1
2.2.22 Knowledge of limiting conditions for operations and safety limits.
3.4 1
2.2.34 Knowledge of the process for determining the internal and external effects on core 2.8 1
reactivity.
I Category Total:
4 Radiation Control 2.3.11 Ability to control radiation releases.
2.7 1
2.3.9 Knowledge of the process for performing a containment purge.
2.5 1
2.3.2 Knowledge of facility ALARA program.
2.5 1
Category Total:
3 Emergency Plan 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support 3.0 1
procedures.
2.4.43 Knowledge of emergency communications systems and techniques.
2.8 1
2.4.25 Knowledge of fire protection procedures.
2.9 1
Category Total:
Generic Total:
3 13 C
Facility:
Peach Bottom Atomic Power Stat Generic Category KA I
ES-401 BWR SRO Examination Outline Facility:
Peach Bottom Atomic Power Station Exam Date: 09/23/2002 Printed: 09/05/2002 Form ES-401 -1 Exam Level:
SRO Tier Group K/A Category Points K1 K2 K3 K4 K5 K6
- 1.
1 4
5 4
Emergency 2
3 3
3 Abnormal Plant Tier Evolutions Totals 7
8 7
- 2.
Plant Systems 2
2 2
2 2
2 Al 4
2 6
2 A2 5
3 8
2 A3 A4 2
2 G
4 3
7 3
Point Total 26 17 43 23 2
1 1
2 1
1 2
1 1
1 0
2 13 3
0 1
0 1
0 1
0 0
0 0
1 4
Tier Totals 3
4 4
4 3
5 3
3 3
2 6
40 Cat I Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge And Abilities 4
5 4
4 17 Note:
- 1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.
- 2. Actual point totals must match those specified in the table.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category tier.
I
imination Outline Printed:
09/05/2(
Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-1 E/APE #
E/APE Name / Safety Function Ki K2 K3 Al A2 G KA Topic Imp.
Points 295003 Partial or Complete Loss of A.C. Power / 6 X
AK2.01 - Station batteries 3.2 1
295003 Partial or Complete Loss of A.C. Power / 6 X
AA1.02 - Emergency generators 4.3*
1 295006 SCRAM / 1 X
AK3.03 - Reactor pressure response 3.9*
1 295007 High Reactor Pressure / 3 X
AA2.02 - Reactor power 4.1
- 1 295007 High Reactor Pressure / 3 X
AK2.06 - PCIS/NSSSS: Plant-Specific 3.7 1
295009 Low Reactor Water Level / 2 X
AK2.04 - Reactor water cleanup 2.6 1
295010 High Drywell Pressure / 5 X
AA2.03 - Drywell radiation levels 3.6 1
295010 High Drywell Pressure / 5 X 2.1.14 - Knowledge of system status criteria which 3.3 1
require the notification of plant personnel.
295013 High Suppression Pool Temperature / 5 X 2.2.22 - Knowledge of limiting conditions for operations 4.1 1
and safety limits.
295013 High Suppression Pool Temperature / 5 X
AK1.03 - Localized heating 3.3 1
295015 Incomplete SCRAM / I X
AK3.01 - Bypassing rod insertion blocks 3.7 1
295016 Control Room Abandonment / 7 X
AK3.01 - Reactor SCRAM 4.2*
1 295017 High Off-Site Release Rate / 9 X 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.
295017 High Off-Site Release Rate / 9 X
AK2.09 - Condenser air removal system: Plant-Specific 2.9 1
Facility:
ES - 401 I
mination Outline Printed:
09/05/2 (
Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 1 Form ES-401 -1 E/APE #
E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp.
Points 295023 Refueling Accidents / 8 X
AA1.04 - Radiation monitoring equipment 3.7 1
295024 High Drywell Pressure / 5 X
EAI.03 - LPCS: Plant-Specific 3.9 1
295025 High Reactor Pressure / 3 X 2.2.22 - Knowledge of limiting conditions for operations 4.1 1
and safety limits.
295025 High Reactor Pressure / 3 X
EK1.02 - Reactor vessel integrity 4.2 1
295026 Suppression Pool High Water Temperature / 5 X
EA2.03 - Reactor pressure 4.0 1
295030 Low Suppression Pool Water Level / 5 X
EK1.02 - Pump NPSH 3.8 1
295030 Low Suppression Pool Water Level / 5 X
EA1.06 - Condensate storage and transfer (make-up to 3.4 1
the suppression pool): Plant-Specific 295031 Reactor Low Water Level / 2 X
EK1.03 - Water level effects on reactor power 4.1 1
295031 Reactor Low Water Level / 2 X
EA2.01 - Reactor water level 4.6*
1 295038 High Off-Site Release Rate / 9 X
EK2.01 - Radwaste 3.4 1
500000 High Containment Hydrogen Concentration / 5 X
EK3.07 - Operation of drywell vent 3.7 1
500000 High Containment Hydrogen Concentration / 5 X
EA2.01 - Hydrogen monitoring system availability 3.5 1
K/A Category Totals:
4 5
4 4
Facility:
ES - 401 5
Group Point Total:
26 4
(
Peat.._ J*ottom Atomic Power Stat BWR SRO (
mination Outline Printed:
09/05/2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-1 E/APE #
E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp.
Points 295002 Loss of Main Condenser Vacuum / 3 X
AK3.03 - Reactor feedpump turbine trip: Plant-Specific 3.3 1
295008 High Reactor Water Level / 2 X
AK2.08 - Main turbine: Plant-Specific 3.5 1
295012 High Drywell Temperature/ 5 X
AA1.01 - Drywell ventilation system 3.6 1
295018 Partial or Complete Loss of Component Cooling X
AKI.01 - Effects on component/system operations 3.6 1
Water / 8 295019 Partial or Complete Loss of Instrument Air / 8 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.
295019 Partial or Complete Loss of Instrument Air / 8 X
AK3.02 - Standby air compressor operation 3.4 1
295020 Inadvertent Containment Isolation / 5 X
AA2.05 - Reactor water level 3.6 1
295021 Loss of Shutdown Cooling / 4 X
AK1.04 - Natural circulation 3.7 1
295022 Loss of CRD Pumps / 1 X
AA1.02 - RPS 3.6 1
295028 High Drywell Temperature / 5 X 2.1.32 - Ability to explain and apply system limits and 3.8 1
precautions.
295029 High Suppression Pool Water Level / 5 X
EK2.08 - Drywell/suppression chamber ventilation 2.9 1
295032 High Secondary Containment Area Temperature / 5 X
EA2.02 - Equipment operability 3.5 1
295032 High Secondary Containment Area Temperature / 5 X 2.1.14 - Knowledge of system status criteria which 3.3 1
require the notification of plant personnel.
295033 High Secondary Containment Area Radiation Levels X
EK2.02 - Process radiation monitoring system 4.1 1
9 Facility:
ES - 401
PeL 3ottom Atomic Power Stat BWR SRO (
imination Outline Emergency and Abnormal Plant Evolutions - Tier 1 / GrouD 2 Printed:
09/05/2(
Form ES-401-1 K/A Category Totals:
3 3
3 2
3 3
Group Point Total:
Facility:
ES - 401 E/APE #
E/APE Name / Safety Function KK1 K2 K3 Al A2 G KA Topic Imp.
Points 295034 Secondary Containment Ventilation High Radiation /
X EA2.01 - Ventilation radiation levels 4.2 1
9 295036 Secondary Containment High Sump/Area Water X
EK3.01 - Emergency depressurization 2.8 1
Level / 5 600000 Plant Fire On Site / 8 X
AK1.02 - Fire Fighting 3.1 1
17
(
Facility:
Peach Bottom Atomic Power Stat ES - 401 BWR SRO E(
ination Outline Plant Systems - Tier 2 / Group 1 Printed:
09/05(
'2 Form ES-401-1 Sys/Ev #
System / Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 202002 Recirculation Flow Control System / 1 X 2.1.33 - Ability to recognize indications for 4.0 1
system operating parameters which are entry-level conditions for technical specifications.
202002 Recirculation Flow Control System / 1 X
K5.01 - Fluid coupling: BWR-3, 4 2.8 1
203000 RHRILPCI: Injection Mode (Plant X 2.1.33 - Ability to recognize indications for 4.0 1
Specific) / 2 system operating parameters which are entry-level conditions for technical specifications.
203000 RHR/LPCI: Injection Mode (Plant X
K2.03 - Initiation logic 2.9*
1 Specific) / 2 211000 Standby Liquid Control System /1 X
K3.01 - tAbility to shutdown the reactor in 4.4*
1 certain conditions 211000 Standby Liquid Control System /1 X
K1.06 - Reactor vessel 3.7 1
212000 Reactor Protection System / 7 X
A4.09 - SCRAM instrument volume level 3.8 1
215005 Average Power Range Monitor/Local X
K3.01 - RPS 4.0 1
Power Range Monitor System / 7 215005 Average Power Range Monitor/Local X
K4.08 - Sampling of overall core power in each 3.1 1
Power Range Monitor System / 7 APRM (accomplished through LPRM assignments and symmetrical rod patterns) 216000 Nuclear Boiler Instrumentation / 7 X
A2.14 - Recirculation flow: Design-Specific 2.9 1
Peach Bottom Atomic Power Stat BWR SRO E(
iination Outline Plant Systems - Tier 2 / Group I Printed:
09/05( 1'2 Form ES-401-1 Sys/Ev #
System / Evolution Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp.
Points 217000 Reactor Core Isolation Cooling X
K5.04 - Testable check valve operation 2.7 1
System (RCIC) / 2 223001 Primary Containment System and X
A1.01 - Drywell temperature 3.6 1
Auxiliaries / 5 223001 Primary Containment System and X
A4.05 - Containment/drywell oxygen 3.6 1
Auxiliaries / 5 concentration 223002 Primary Containment Isolation X
A2.06 - Containment instrumentation failures 3.2 1
System/Nuclear Steam Supply Shut-Off / 5 226001 RHR/LPCI: Containment Spray X
K4.12 - Prevention of inadvertent containment 2.9 1
System Mode / 5 spray activation 239002 Relief/Safety Valves / 3 X
K2.01 - SRV solenoids 3.2*
1 239002 Relief/Safety Valves / 3 X 2.2.25 - Knowledge of bases in technical 3.7 1
specifications for limiting conditions for operations and safety limits.
259002 Reactor Water Level Control System /
X K6.04 - Reactor feedwater flow input 3.1 1
2 259002 Reactor Water Level Control System /
X A3.03 - Changes in main steam flow 3.2 1
2 261000 Standby Gas Treatment System / 9 X
A3.03 - Valve operation 2.9 1
264000 Emergency Generators (Diesel/Jet) / 6 X
K6.02 - Fuel oil pumps 3.6 1
Facility:
ES - 401
Facility:
Peach Bottom Atomic Power Stat ES - 401 Printed:
09/05(
iination Outline Plant Systems - Tier 2 / Group 1 K/A Category Totals:
2 2
2 2
2 2
2 2
2 2
3 Group Point Total:
23 Sys/Ev #
System / Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 264000 Emergency Generators (Diesel/Jet) / 6 X
A 1.09 - Maintaining minimum load on 3.1 1
emergency generator (to prevent reverse power) 290001 Secondary Containment / 5 X
K 1.02 - Primary containment system:
3.6 1
Plant-Specific Form ES-401-1
(
Peach Bottom Atomic Power Stat Printed:
09/05(
iination Outline Plant Systems - Tier 2 / Group 2 Sys/Ev#
System / Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp.
Points 201002 Reactor Manual Control System / 1 X
K4.01 - Detection of sequence timer 2.7 1
malfunction 201002 Reactor Manual Control System / 1 X
K6.01 - Select matrix power 2.6 1
201006 Rod Worth Minimizer System (RWM)
X K6.02 - Reactor water level control input:
2.9 1
(Plant Specific) / 7 P-Spec(Not-BWR6) 204000 Reactor Water Cleanup System / 2 X
A3.06 - Lights and alarms 3.1 1
205000 Shutdown Cooling System (RHR X
A1.02 - SDC/RHR pump flow 3.2 1
Shutdown Cooling Mode) / 4 205000 Shutdown Cooling System (RHR X
K2.02 - Motor operated valves 2.7*
1 Shutdown Cooling Mode) / 4 214000 Rod Position Information System / 7 X 2.4.6 - Knowledge symptom based EOP 4.0 mitigation strategies.
234000 Fuel Handling Equipment / 8 X
K3.04 - tcore modifications/alterations 3.8 1
245000 Main Turbine Generator and Auxiliary X
K3.02 - Reactor pressure 4.0 1
Systems / 4 259001 Reactor Feedwater System / 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.
262002 Uninterruptable Power Supply X
K1.08 - Containment isolation system:
3.1 1
1 (A.C./D.C.) / 6 Plant-Specific Facility:
(
Facility:
Peach Bottom Atomic Power Stat ES - 401 Printed:
09/05(
)2 BWR SRO Ei iination Outline Plant Systems - Tier 2 / Groun 2 Form ES-401-1 K/A Category Totals:
1 1
2 1
1 2
1 1
1 0
2 Group Point Total:
13 Sys/Ev #
System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 272000 Radiation Monitoring System / 7 X
A2.06 - Downscale trips 2.9 1
300000 Instrument Air System (JAS) / 8 X
K5.13 - Filters 2.9 1
/
Facility:
Peach Bottom Atomic Power Stat ES - 401 BWR SRO i iination Outline Plant Systems - Tier 2 I Croun 3 Printed:
09/05( T 2
F~nrm ]F.-dfl1..1 K/A Category Totals:
0 1
0 1
0 1
0 0
0 0
1 Sys/Ev #
System /.Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 215001 Traversing In-Core Probe / 7 X
K6.04 - Primary containment isolation system:
3.4 1
Mark-I&II(Not-BWR1) 256000 Reactor Condensate System / 2 X
K2.01 - System pumps 2.8 1
288000 Plant Ventilation Systems / 9 X 2.4.6 - Knowledge symptom based EOP 4.0 1
1_ _
1__ 1mitigation strategies.
1 290002 Reactor Vessel Internals /
X K4.01 - 2/3 core coverage following a DBA 3.9 1
LOCA Group Point Total:
4
Generic Knowledge and Abilities Outline (Tier 3)
(
BWR SRO Examination Outline Printed: 09/05/2002 (
Form ES-401-5 Imp.
Points KA Topic Conduct of Operations 2.1.32 Ability to explain and apply system limits and precautions.
3.8 1
2.1.13 Knowledge of facility requirements for controlling vital / controlled access.
2.9 1
2.1.7 Ability to evaluate plant performance and make operational judgments based on operating 4.4 1
characteristics, reactor behavior, and instrument interpretation.
2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports.
3.0 1
Category Total:
4 Equipment Control 2.2.29 Knowledge of SRO fuel handling responsibilities.
3.8 1
2.2.21 Knowledge of pre and post maintenance operability requirements.
3.5 1
2.2.2 Ability to manipulate the console controls as required to operate the facility between 3.5 1
shutdown and designated power levels.
2.2.11 Knowledge of the process for controlling temporary changes.
3.4*
1 2.2.22 Knowledge of limiting conditions for operations and safety limits.
4.1 1
Category Total:
5 Radiation Control 2.3.6 Knowledge of the requirements for reviewing and approving release permits.
3.1 1
2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 3.3 1
personnel exposure.
2.3.11 Ability to control radiation releases.
3.2 1
2.3.9 Knowledge of the process for performing a containment purge.
3.4 1
Category Total:
Facility:
Peach Bottom Atomic Power Stat Generic Category KA
(
4 I
(
Facility:
Peach Bottom Atomic Power Stat Generic Category KA Generic Knowledge and Abilities Outline (Tier 3)
S BWR SRO Examination Outline Printed: 09/05/2002 (
Form ES-401-5 Imp.
Points KA Topic Category Total:
Generic Total:
4 17 2
Emergency Plan 2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.
2.8 1
2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support 4.0 1
procedures.
2.4.43 Knowledge of emergency communications systems and techniques.
3.5 1
2.4.25 Knowledge of fire protection procedures.
3.4 1