ML062930215
| ML062930215 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/11/2006 |
| From: | Todd Fish Operations Branch I |
| To: | Exelon Generation Co |
| Sykes, Marvin D. | |
| References | |
| ES-401-1 | |
| Download: ML062930215 (17) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 Facilitv:
Limerick Generating Station Printed: 09/11/2006 Date Of Exam:
10/23/2006 Note:
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7."
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Ensure that at least two topics from every KIA category are sampled within each tier of the RO and SRO-only outlines (Le., 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 +I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
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 ES401, Attachment 2, for guidance regarding the 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) WAS in Tiers I and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.
On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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. Use duplicate pages for RO and SRO-only exams.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to Note: This form deviates from theNUFEG-1021 Form ES-401-1 by the addition ofthe K and A column under the SRO Only Points. This allows sampling all Fuel Handling System KAs as required by ES-401.
1
Facility:
Limerick Generating Station ES - 401 Emergency and EIAPE # I Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC Pwr 116 295004 Partial or Complete Loss of DC Pwr L
I 295005 Main Turbine Generator Trip / 3 I 295006 SCRAM / 1 295016 Control Room Abandonment / 7 I 295018 Partial or Total Loss of CCW / 8 295019 Partial or Total Loss of Instrument Air18 I 295021 Loss of Shutdown Cooling / 4 1
295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water Temp. / 5 I 295028 High Drywell Temperature / 5 295030 Low Suppression Pool: Wtr Lvl / 5 I
I 29503 1 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1
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295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown/ 1 I 295038 High Off-Site Release Rate / 9 600000 Plant Fire On Site / 8 BWR RO Examination Outline Printed: 09/11/2006
)normal Plant Evolutions - Tier 1 / Group 1 (RO I SRO)
Form ES-401-1 Ti
2.8 Total
1
BWR RO Examination Outline Printed: 09/11/2006 Facility:
Limerick Generating Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO)
Form ES-401-1 K1 X
I E/AF'E # / Name / Safety Function K2 X
1 1
1 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295015 Incomplete SCRAM / 1 295020 Inadvertent Cont. Isolation / 5 & 7 I-295033 High Secondary Containment Area Radiation Levels / 9 PO0000 High CTMT Hydrogen Conc. / 5 K/A Category Totals:
1
BWR RO Examination Outline Facility:
Limerick Generating Station 212000 Rps 212000 RPS 215003 IRM ES - 401 I
I X
203000 RHWLPCI: Injection I
I x 205000 Shutdown Cooling I
I
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206000 HPCI l
l 209001 LPCS I
I 209001 LPCS l l 211000 SLC I
I 212000 Rps 212000 RPS
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215003 IRM 2 15004 Source Range Monitor 2 15005 APWLPRM 217000 RCIC I
I I
I 2 17000 RCIC 21 8000 ADS 223002 PCISkJuclear Steam 239002 SRVs 259002 Reactor Water Level Control l l 261000 SGTS I
I 26200 1 AC Electrical Distribution 262002 UPS (AC/DC)
Printed: 0911 1/2006 Form ES-401-1 14 I I G KATopic K6.02 - D.C. electrical K3.02 - ADS logic K5.03 - Changing detector X I 1 A4.04 - Manually initiated operation: Plant-Specific 1
BWR RO Examination Outline Facility:
Limerick Generating Station Printed: 09/11/2006 2
BWR RO Examination Outline Facility:
Limerick Generating Station Printed: 09/11/2006 Plant Systems - Tier 2 / Group 2 (RO / SRO)
Form ES-401-1
<S - 401 SysfEvol # I Name I
I 201002 RMCS 201 006 RWM I 202001 Recirculation 204000 RWCU
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215002 FU3M 216000 Nuclear Boiler Inst.
223001 Primary CTMT and Aux.
230000 RHR/LPCI: Torus/Pool Snrav Mode 245000 Main Turbine GeneratodAux I x 256000 Reactor Condensate I
259001 Reactor Feedwater 290003 Control Room HVAC II WA Category Totals:
1
Generic Knowledge and Abilities Outline (Tier 3)
BWR RO Examination Outline Printed: 094 1/2006 Ability to perform pre-startup procedures for the 3.7 facility, including operating those controls associated with plant equipment that could affect reactivity.
Knowledge of the process for controlling Knowledge of tagging and clearance procedures.
2.5 temporary changes.
3.6 Facility
Limerick Generating Station Form ES-401-3 1
1 1
Catepory ToDic IR Conduct of Operations I
2.1.3 Knowledge of shift turnover practices.
I 3.0 1
1 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system 01 component status.
2.1.29 Knowledge of how to conduct and verify valve lineups.
Category Total:
3 Equipment Control 2.2.1 2.2.11 2.2.13 Category Total:
3 -
1 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Radiation Control 2.5 2.3.4 2.3.1 1 Ability to control radiation releases.
2.7 1
Categorv Total:
2 3.7 Emergency Plan 2.4.21 2.4.46 Knowledge of the parameters and logic used to assess the status of safety functions including:
1.Reactivity control 2.Core cooling and heat removal 3.Reactor coolant system integrity
- 4. Containment conditions 5.Radioactivitv release control.
1 3.5 Ability to verify that the alarms are consistent with the plant conditions.
Category Total:
1 2
Generic Total:
10
Limerick ILT05-1 ES-401 Record of Rejected WAS Form ES-401-4 essentially the same as another already on the exam.(215002 K2.03 RBM, electrical power supplies to APRM channels). Substituted another K3 in its I
/ I 1 / I 1 / I 1 /I 295016 2.2.25 295023 2.1.27 295031 EA2.01 295038 EKI.03 600000 2.4.6 10 A4.14 place.
Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.
Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a Competent and non-competent operator.
Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator and WA corresponds to a task that is N/A for RO's.
Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator and generic WA refers to EOP mitigation strategy, while the cateaorv is an AOP.
' non-competent operator.
Redrawn with the approval of the lead examiner due to KIA overlap with another WA already included on this portion of the exam.
Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.
Redrawn with the approvat of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator. Also a loss of ECS room cooling has no effect on LPCl because LGS is analyzed for loss of room cooling.
Redrawn with the approval of the lead examiner due to WA overlap with a JPM.
Redrawn with the approval of the lead examiner due to A3 not applicable to SRO exam, deselected due to a known deficiency in the software.
ES-401, Page 27 of 33
Limerick ILT05-1 ES-401 ReFord of Rejected WAS Form ES-401-4
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1295030 EA2.02 295031 2.1.6 112 295007 2.2.25 SRO EXAM Redrawn with the approval of the lead examiner due to WA overlap with questions on the RO portion of the exam.
Redrawn with the approval of the lead examiner due the lack of concepts that would meet the WA and still distinguish between a competent and non-competent operator.
Redrawn with the approval of the lead examiner due to WA overlap with questions on the RO-portion of the exam.
Redrawn with the approval of the lead examiner due to WA overlap with questions on the R O portion of the exam.
Redrawn with the approval of the lead examiner due to WA overlap with questions on the RO portion of the exam.
Redrawn with the approval of the lead examiner due to WA overlap with questions on the RO portion of the exam.
ES-301 Administrative To Dics Outline Form ES-301-I Facility: Limerick Examination Level: RO SRO 0 Date of Examination: 10/23/06 Operating Test Number: ILT05-1 Administrative Topic Type (See Note)
Code*
Conduct of Operations Conduct of Operations Equipment Control N, R Radiation Control p, R Emergency Plan N, R Describe activity to be performed Administration Actions on a Thermal Limit Violation Review Main, Turbine Bypass Valve Exercising ST Calculate Stay Time Fire Alarm in Invertor Room (CE 254')
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 & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (L I)
(P)revious 2 exams (r 1; randomly selected)
ES 301, Page 22 of 27
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Examination Level: RO SRO Administrative Topic (See Note)
Equipment Control r
Emergency Plan Type Code*
N, R P, R Date of Examination: 10/23/06 Operating Test Number: ILTO5-1 Describe activity to be performed
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Determination of Adequate Shift Staffing Administrative Actions on a Thermal Limit Violation Review Main Turbine Bypass Valve Exercising S.T Calculate Stay Time ERP Classification and Reporting (Plane Crash)
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 & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (1
- 1)
(P)revious 2 exams (5 1 ; randomly selected)
ES 301, Page 22 of 27
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Limerick Exam Level: RO 1x1 SRO-I 0 SRO-U 0 Date of Examination: 10/23/06 Operating Test Number: ILT05-1 Control Room Systems* (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Safety I
I Function
- a. Reactor Recirc/Start MG Set - High Vibration
- b. Remove 1 C RFP From Service to Standby AI L, p, s 1
D, s 2
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- c. Control Room Vent High Radiation Isolation Reset
- d. Manually Initiate Core Spray (Initiation Pushbutton Fails)
A, Nl s 4
- e. Restore RECW, DWCW, PClG D, s 5
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. Place Alternate CRD Flow Control Valve In Service I
All RO and SRO-l 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 Type Codes Criteria for RO / SRO-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27
ES-301 Control RoomhPlant Systems Outline Form ES-301-2 Facility: Limerick Exam Level: RO SRO-I SRO-U 0 Date of Examination: 10123106 Operating Test Number: ILT05-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including I ESF)
System J JPM Title Safety I
I Function
- a. Reactor RecircIStart MG Set - High Vibration
- b. Remove I C RFP From Service to Standby
- c. Control Room Vent High Radiation Isolation Reset
- d. Manually Initiate Core Spray (Initiation Pushbutton Fails)
D, S 2
Dl s 9
A, N, S 4
A, N, S 6
- f. Scram Reset A1 Dl s 7
- g. Placing Alternate TECW Pump in Service
- h.
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
I D, E, R l 8
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety
- Type Codes Criteria for RO / SRO-I I SRO-U
- A)lternate path
- C)ontrol room
- D)irect from bank
- E)mergency or abnormal in-plant
- L)ow-Power I Shutdown
- N)ew or (M)odified from bank including 1 (A) 1P)revious 2 exams
,R)CA
'S)imulator 4-6 / 4-6 I 2-3 ES-301, Page 23 of 27
ES-301 Control Room/ln-Plant Svstems Outline Form ES-301-2 Facility: Limerick Exam Level: RO 0 SRO-I c] SRO-U Date of Examination: 10123106 Operating Test Number: ILT05-1
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IrControl Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Safety 1
1 Function 1 a. Reactor RecircIStart MG Set - High Vibration I A, L, P, S I 1
11 b. DG Fast Start From Control Room (ESW fails to start)
I A, N S 1
6
/I c. Control Room Vent High Radiation Isolation Reset ( FSF)
- d.
- e.
- h.
Implant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. MSIV -1 29" Bypass (T-221)
- k.
I I
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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams
( W A (S)imulator Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27
Appendix D Scenario Outline Form ES-D-I Event Malf.
Event Type*
I MV1238B I (RO/ CRS) 2 MED263D I (PRO/ CRS) 3 MAD1 47E C (ROICRS) 4 MRR441 C (ALL) 5 MFW252B M (ALL) 6 MHP449 C (PRO/ CRS) 7 MCR412A C (RO/CRS) 8 MSL559 C (RO/ CRS)
No.
No.
Facility: Limerick Scenario No.: J-Op-Test No.: ILTO5-I Event Description "1 B Narrow Range Level Transmitter fails downscale c%C)
D14 Bus Overcurrent/Loss of D14 Bus ( 7 ' ~ s SRV "L" fails open mechanically Coolant leakage in drywell "B" Feedwater line rupture inside Primary Containment HPCl Turbine Trip
" I A CRD Pump Trip SLC pipe rupture Examiners:
Operators:
Initial Conditions: 100% power. RCIC is out of service for bearing replacement. Regulatory actions log entry has been made. Estimated time of repair is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Turnover: Maintain 100% power. Continue repairs on RCIC.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-I Malf.
Event Type*
No.
MV1234A I (RO/CRS)
MCN078C C (ALL)
N/A R (RO)
MRR435A C (PRO/CRS)
MRP029D M (ALL)
MRP407C MRR435B C (PRO/ CRS)
MSLl97 C (RO/CRS)
Facility: Limerick Event Description A RPV Pressure Transmitter (RPS) Fails High (Ts\\
IC Condensate Pump trips Insert control rods to exit Restricted Region IA Recirc Pump trips ATWS - B RPS fails to trip, both RRCS channels fail to initiate ARI SLC Squib Valve Failure to Fire 1 B Recirc Pump trips (x 5\\
Scenario No.: 2 Op-Test No.: ILT05-I Examiners:
Operators:
Initial Conditions: 95% power recovering from a planned down power to perform a rod pattern adjustment.
Turnover: 95% power. Rod pattern adjustment is complete. Raise power to 100%.
Event No.
1 2
3 4
5 6
7 APPENDIX D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Event No.
I 2
3 4
5 6
7 8
Facility: Limerick Scenario No.: 3 Op-Test No.: ILTO5-I Malf.
Event Type*
Event No.
Description N/A R (RO/CRS)
Continue to Withdraw Control Rods MSR214F I (RO/CRS)
IRM channel "F" fails upscale (.Ts\\
MED282A I (ALL)
Loss of Division 1 DC VlCl14A C (RO/CRS)
"?A" CRD Pump high vibration MRR441 C (ALL)
Coolant leakage in drywell MMS067 M (ALL)
Steam leak in drywell MCSI 83D MRP029C C (RO/CRS)
"A" RPS failure to scram (TS\\
I C (PRO/CRS) "I D" Core Spray fails to auto start Examiners:
Operators:
Initial Conditions: 5% power with startup in progress. "IA" SRM is inoperable and bypassed.
Turnover: 5% power - continue with startup IAW GP-2 APPENDIX D, Page 38 of 39