ML051720123
| ML051720123 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/31/2005 |
| From: | Melodee Jensen Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML051610145 | List: |
| References | |
| 50-254/05-301, 50-265/05-301 | |
| Download: ML051720123 (28) | |
Text
OUTLINE SUBMITTAL AND NRC COMMENT FOR THE QUAD CITIES INITIAL EXAMINATION - MAY 2005
SVP-04-108 December 20,2004 Regional Administrator, Region Ill U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 21 0 Lisle, IL 60532-4352 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Submittal of Integrated Initial License Training Examination Outlines Enclosed are the examination outlines that support the Initial License Examination scheduled for May 2, 2005 through May 9, 2005 at Quad Cities Station.
This submittal includes all appropriate Examination Standard forms and outlines in accordance with NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9.
In accordance with NUREG-1021, Revision 9, Section ES-201, Initial Operator Licensing Examination Process, please ensure that these materials are withheld from public disclosure until after the examinations are complete.
Should you have any questions concerning this letter, please contact Mr. W. J. Beck, Regulatory Assurance Manager, at (309)-227-2800. For questions concerning examination outlines, please contact Mark Jensen at (309)-227-3438 or Mike Kaufman at (309)-227-4173.
Respectfully, Timothy J. Tulon Site Vice President Quad Cities Nuclear Power Station DEC 2 1 2CW
December 20,2004 U.S. Nuclear Regulatory Commission Page 2
Enclosures:
(Hand delivered to Nicholas A. Valos, Chief Examiner, NRC Region 111)
Examination Security Agreement - Form ES-201-3 Administrative Topics Outline (RO) - Form ES-301-1 Administrative Topics Outline (SRO) - Form ES-301-1 Control Roomh-Plant Systems Outline (RO) - Form ES-301-2 Control Roodln-Plant Systems Outline (SRO) - Form ES-301-2 BWR Examination Outline (RO & SRO) - Forms ES-401-1 and ES-401-3 Record of Rejected WAS - Form ES-401-4 Scenario Outlines (4) - Forms ES-D-1 Completed Checklist:
Examination Outline Quality Checklist - Form ES-201-2 Transient and Event Checklist - Form ES-301-5 Competencies Checklist - Form ES-301-6 cc:
Chief, Operations Branch - NRC Region I l l (without attachments)
NRC Senior Resident Inspector - Quad Cities Station (without attachments)
L L
ES-201 Examination Outline Quality Checklist Form ES-201-2 Item
- 1.
W R
I T
T E
N 2
S I
M U
L A
T 0
R 3
w I
T 4
G E
N E
R A
L Date of Examination:
L Inltl:
Task Descriptron a
b a
b Assess whether the outline was systematically and randomly prepared in accordance with Section D 1 of ES-401 and whether all K/A categories are appropriately sampled c Assess whether the outline over-emphasizes any systems, evolutions. or generic topics Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 b a t s w Y
d Assess whether the justifications for deselected or rejected K/A statements are appropriate a Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specificabons. and major transients L
w w b Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants audit test(s) and scenarios will not be repeated on subsequent days mL c To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
a Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
J(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed J (2) task repetition from the last two NRC examinations is within the limits specified on the form d (3) no tasks are duplicated from the applicants audit test(s)
J (4) the number of new or modified tasks meets or exceeds the minimums specified on the form
/ (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the mb &J among the safety functions as specified on the form P
form I
I b Verify that the administrative outline meets the criteria specified on Form ES-301-1 (1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified J (3) no more than one task is repeated from the last two NRC licensing examinations FD i t c
& b a @
c Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.
a Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropria!e exam section
$ 4 9
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
- c. Ensure that WA importance ratings (except for plant-specific priorities) are at least 2.5.
i!
e Check the entire exam for balance of coverage.
,Cr,ec6 :G, A.:pl!ca;i2r:
and overiap among exam hections.
f. Assess.w-!f?thzr.tpe.
yay filsthe-a-p~oo~a~ioblevel (RO or SRO!
a Author b Facility Reviewer (*)
c NRC Chief Examiner (8)
ES 201-2, Page 25 of 27
-~
ES-301 Ad mi nistrative Topics Out1 i ne Form ES-301-1 Facility: Quad Cities Examination Level:
Date of Examination: 05/02/2005 Operating Test Number:
1 Administrative Topic (See Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code*
Describe activity to be performed N, S Perform Control Room Actions to assemble the fire brigade. 2.1.16 N, S Perform Electrical Distribution Surveillance for loss of two offsite lines. 2.1.31 N
Determine proper isolation points to allow an RBCCW pump to be taken Out Of Service for Maintenance. 2.2.13 D
Review a survey map and determine allowable stay time. 2.3.2 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless Type Codes & Criteria: (C)ontrol room they are retaking only the administrative topics, when 5 are required.
(D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (2 1)
(P)revious 2 exams (5 1; randomly selected) 5 ES 301-1, Page 22 of 27
ES-301 Ad mini st rat ive Toei cs Outline Form ES-301-1 Facility: Quad Cities Examination Level: SRO Date of Examination: 05/02/2005 Operating Test Number:
1 Administrative Topic (See Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code*
N N,
D M
Describe activity to be performed Initiate Fire Impairment that requires compensatory actions. 2.1.25
~
Review Mode Change Checklist. 2.1.12 Review Temporary Change Package to determine if it can be accepted for Operation. 2.2.1 1 Review survey map and determine stay times. 2.3.2 Determine EAL classification and fill out NARS form.
2.4.41 VOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless Type Codes & Criteria: (C)ontrol room they are retaking only the administrative topics, when 5 are required.
(D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (2 1)
(P)revious 2 exams (5 1; randomly selected)
ES 301 -1, Page 22 of 27
ES-301 Control Roomh-Plant Systems Outline Form ES-301-2 Facility: Quad Cities Exam Level:
Date of Examination: 05/02/2005 Operating Test Number:
1 Control Room Svstems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Code*
Safety Function
- a. Bypass all Reactor Scram Signals. 295015.AK2.04 D, S 1
- b. Inject SSMP to U2 with Normal Feed (14-1) unavailable. A2.04*
A, L, M, S 2
- c. Start HPCl in pressure control mode with spurious isolation.
- d. Start Shutdown Cooling with pump trip. 205000.A2.06
- e. Vent the Primary Containment with the Hardened Vent. 295010.AA1.05 A, L, M, S 3
A, L, N, S 4
D, L, S 5
A, D, S 6
295025.EA1.04
- f. Shutdown EDG with early trip. 264000.A2.02
- g. Perform post maintenance test on Fuel Pool Radiation Monitor with a
- h. Shutdown Standby Gas Treatment with failure of heater to trip.
~
N, S 7
A, D, S 9
failure of the trip signal. 272000.A1.02 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i. Align SSMP Room Cooler to Alternate Cooling (Fire Main).
D, E, P, R 8
D, L, R, E 2
D. E 1
295018.AA1.01
- j. Inject SBLC Test Tank to RPV. 295031.EA1.08
@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in
- Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA
[S)imulator e control room.
Criteria for RO / SRO-I / SRO-U 4-61 4-6 12-3
< 9 / ( 8 1 1 4
> 1 / )1
/,1
> 1 I 21 121
> 2 / ) 2 121
< 3 I 5 3
/ (2 (randomly selected)
>1 I 21 121 ES-301, page 23 of 27
ES-301 Control Roomh-Plant Svstems Outline Form ES-301-2 Facility: Quad Cities Exam Level: SRO-I Date of Examination: 05/02/2005 Operating Test Number:
1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title 1 Typecode*
- a. Bypass all Reactor Scram Signals. 295015.AK2.04 D, S, L
- b. Inject SSMP to U2 with Normal Feed (14-1) unavailable. A2.04*
A, L, M, S
- c. Start HPCl in pressure control mode with spurious isolation.
- d. Start Shutdown Cooling with pump trip. 205000.A2.06
- e. Vent the Primary Containment with the Hardened Vent. 295010.AA1.05 A, L, M, S A, L, N, S D, L, S 295025.EA1.04
- f. Shutdown EDG with early trip. 264000.A2.02
- g. Perform post maintenance test on Fuel Pool Radiation Monitor with a
- h.
A, D, S N, S failure of the trip signal. 272000.A1.02 Safety Function 1
2 3
4 5
6 7
Implant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i. Align SSMP Room Cooler to Alternate Cooling (Fire Main).
D, E, P, R 8
D, L, R, E 2
D, E 1
2950'l8.AA1.01
- j. Inject SBLC Test Tank to RPV. 295031.EA1.08
@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested if
- Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant
&)ow-Power (N)ew or (M)odified from bank including I(A)
(P)revious 2 exams (S)imulator e control room.
Criteria for RO / SRO-I / SRO-U 4-6 / 4-6 12-3
( a 1 2 4
> I / >I 121
> 1 I >I
/>1
> 2 1 2 2 111 c 3 / 5 3 I52 (randomly selected)
>I /
21 121 ES-301, page 23 of 27
u ES-301 Transient and Event Checklist Form ES-301-5 Facility: Quad Cities Date of Exam: 5/2/05 Operating Test Number: 1 A
Scenarios Crew Position Instructions:
M I
- 1.
Circle the a plicant level and enter the o eratin test number and Form ES-D-1 event numbers for each event are not ap Icable for RO applicants. R8s muspsetve in both the "at-the-controls (ATC)" and "balance-of-plant YiOP) positions; Pnstant SROs must do one scenario, including at least two instrument or component (VC) malfunctions and one major transient, in the ATC position.
Reactivity manipulations may be conducted under nor*mal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D.
instrument or component malfunctions on a I-for-I basis.
- e. TS
- 2.
Reactivity and normal evolutions may be replaced with additional
- 3.
Whenever practical,,both instrument and component malfunctions should be included; only those that require verifiable actions tha provide insight to the applicant's competence count toward the minimum requirement.
Author:
NRC Reviewer:
L L
Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No: I Op-Test No: 1 Examiners:
Operators:
Initial Conditions: 80 MWe. Reactor startup is in progress. Containment inerting is in progress.
Turnover: The plant is operating at 80 MWe with a reactor startup in progress. The 1-0640-296, B narrow range RPV level instrument is 00s reading downscale. The 1 B EHC pump and HPCI are 00s. IRM #I5 is bypassed. The crew is to transfer auxiliary power per QCGP 1-1 and continue the reactor startup. BPO has been notified of the power transfer.
Event Malfunction Event Event 1
Transfer Auxiliary Power 2
Increase power with control rods 3
4 5
6 7
8 nml l a I --
K U I D n nm08c rdOl r 4 rcl3 I SRO ia04a rrl l a ALL I
1 APRM drift with RBM 7 rod block C, T Uncoupled control rod C, T C
M M
Steam leak in RCIC. Group V isolation fails to actuate Recoverable loss of instrument air Circulating water rupture under the hotwell Leak in the A recirc suction / TAF blowdown (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
Appendix D Scenario Outline Form ES-D-1
SUMMARY
The plant is operating at approximately 80 MWe with a reactor startup in progress. Drywell inerting is in progress. The 1-0640-298, B narrow range RPV level instrument is 00s reading downscale. The 3 EHC pump and HPCl are 00s. IRM # I 5 is bypassed.
The crew will assume the shift with orders to transfer auxiliary power (BOP-N) and continue the startup by pulling control rods (RO-R). During control rod withdrawal APRM #3 will drift high causing RBM #7 to enable and cause a rod out block (RO-I). After the APRM and/or RBM is bypassed a control rod will come uncouple at position 48 (RO-C, SRO-T). Actions to recouple the control rod will fail and it will be fully inserted.
An operator will report from the field that he felt vibrations in the plant and the seismograph has actuated.
A steam leak will develop in RClC and the group V isolation will not actuate requiring the operator to isolate it manually (BOP-C, SRO-T).
A recoverable loss of instrument air will occur. The operator will start standby instrument and service air compressors (BOP-C). The NLO will be able to isolate the leak.
A rupture of the circulating water piping and subsequent flooding of the condensate pit will require the crew to scram the reactor and secure the condensate and feed pumps (M-All).
After the scram a leak in the A recirc suction header will develop. The crew will be unable to control level above the top of active fuel requiring a blowdown (M-All). RPV level will be recovered using low-pressure ECCS pumps.
The scenario will be terminated when primary containment parameters are lowering and RPV level is in a band of 0 - 48.
CRITICAL TASKS:
Critical task #I Critical task #2:
Appendix D Scenario Outline Form ES-D-1
~~
Facility: Quad Cities Scenario No:
2 Op-Test No: 1 Examiners:
Operators:
Initial Conditions: Full power, holding load. Torus cooling on.
Turnover: The plant is holding load at rated reactor power. The 1 B TBCCW pump and GCB 3-4 are 00s. @One control rod is inoperable and 00s on the RWM. Torus cooling is on A loop following a planned RClC run. The RClC run has been completed and the crew is to secure Torus cooling first thing this shift.
Number 3
I rd19 4
rm02m aoti1754012b 5
loi107503bl loi107503b2 6
mc08
- rp04a, rd05r 7
rd 13a and b, 8
crOl and 2
- rdl4a, dihslO590303 9
!nt Event le*
N Secure Torus cooling Condensate pump tripkecirc runback, BOP reset runback Loss of the A RWM Refuel floor rad monitor fails upscale Standby Gas Treatment starts with a failure or the heater Recoverable loss of main condenser vacuum, load drop Loss of A RPS, 5 rods scram in requiring an immediate reactor scram Delayed slow scram / gross fuel failure Pipe rupture at scram discharge volume / QGA 300 blowdown due to 2 max safe rads I
T M
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
@Which control rod cannot be determined until the new core load and rod pattern are in place in the Simulator.
Appendix D Scenario Outline Form ES-D-1
SUMMARY
The plant will be holding load at rated conditions. The 1 B Turbine Building Closed Cooling Water (TBCCW) pump and Gas Circuit Breaker (GCB) 3-4 will be 00s. 1 inoperable control rod will be 00s on the Rod Worth Minimizer (RWM). APRM #I will be bypassed. Torus cooling will be on A loop.
The crew will take the shift with orders to secure torus cooling which was running for an RClC surveillance that has been completed (BOP-N). After Torus cooling has been secured the B condensate pump will trip causing a reactor recirc runback.
After the operator resets the recirc runback signal (BOP-C) the A RWM will fail. The crew will swap to the B RWM and take the previously 00s control rod back 00s (RO-I).
One of the refuel floor radiation monitors will fail upscale causing the reactor building vents to isolate and standby gas treatment (SGT) to autostart (SRO-T). The B SGT heater will not start (SRO-T). The operator will manually start A SGT and secure B (BOP-C).
A recoverable loss of vacuum will occur causing the need for a load drop (RO-R). The NLO dispatched will refill the loop seal on the turbine vacuum breaker and vacuum will return to normal.
A loss of A RPS will occur and 5 rods will scram in requiring an immediate reactor scram (RO-C).
When the scram is inserted a SDV blockage will cause the rods to insert at a slower than normal rate resulting in gross fuel element failure (M-All). The piping will rupture at the scram discharge volume and the crew will blowdown due to 2 areas above max safe rads.
The scenario will be terminated when all 5 ADS valves are open and RPV pressure is dropping.
CRITICAL TASKS:
Critical task #I:
Critical task #2:
Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No:
3 Op-Test No: 1 Examiners:
Operators:
Initial Conditions: 92% power, holding load Turnover: The plant is holding load at 92% reactor power. The 10263-298, S narrow range level instrument, is 00s reading downscale. The 1 S TBCCW pump and HPCl are 00s. APRM #I is bypassed. Continue to hold load.
Event Malfunction Event Event 7
1 2
rd04r C, T Control rod drifts out 3 notches 3
dihs156041a BOP C
Gland Steam Exhauster trip 4
ed02 SRO T
Loss of Reserve Aux Transformer 12 dihsl1401 la,
- BOP, cs05a SRO minimum flow valve to open A core spray pump autostart with a failure of the Ro SRO ano9017e12, lohs 1 5604 1 a4 5
N/A RO R
Load drop with recirc flow 6
N/A BOP N
Secure reactor feed pump and condensate pump RPV level indicator fails upscale requiring manual level control 7
rrl5a RO rp05a and b, Inadvertent Group I isolation and subsequent break in B 8
ms05b main steam line ALL 9
dihsl1001s17a ALL M
Unable to spray DW, DW coolers trip, PSP blowdown I
pco 1 dihsl100126b rrl7a-d, rr20a and b 10 rrl9a-d, ALL M
Loss of all RPV level indication, RPV flooding (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec
Appendix D Scenario Outline Form ES-D-1
SUMMARY
The plant is holding load at 92% power. The 1-0640-29B, B narrow range RPV level instrument is 00s reading downscale. The 1 B TBCCW pump and HPCl are 00s. APRM # I is bypassed.
When the crew assumes the shift the A core spray pump will autostart but its minimum flow valve will fail to open. The operator will secure the pump (BOP-C, SRO-T). A control rod will drift out 3 notches and will be inserted using the QCOA (RO-C, SRO-T). The on line gland sealing steam exhauster will trip requiring the other to be placed in service (BOP-C).
A loss of Reserve Aux Transformer 12 will occur (SRO-T). A load drop to less than 2511 MWth will be performed (RO-R) and 1 RFP and 1 condensate pump will be secured (BOP-N).
The other narrow range RPV level instrument will fail upscale causing the operator to take manual control of feedwater (RO-I).
An inadvertent Group I isolation will cause a steam leak in the drywell M-All). Drywell sprays will be unavailable and the drywell coolers will not restart. The crew will blowdown due to the inability to stay within the PSP curve or maintain DW temperature (M-All).
When saturation conditions are met all RPV level instruments will become unavailable and the crew will flood the RPV (M-All).
The scenario will be terminated when the crew identifies indications that the RPV is flooded to the main steam lines.
CRITICAL TASKS:
Critical task #I:
Critical task #2:
Scenario Outline Form ES-D-1 Appendix D Event Malfunction NIA I
Number No.
Event Event Type*
Description BOP I N Swap reactor feed pumps I
Scenario No:
4 Op-Test No: 1 0 pera tors:
Zacility: Quad Cities
- xaminers:
2 rd07a
- cu03, rplOa and b 3
4 fwl4c
- rr06a, rr07a 5
- sw02, 6
mcOl,
mc04 7
rd13 a and b n
- tcOl,
- I Initial Conditions: 80% power, 2 RFPs on.
C, T C, T A CRD pump trip Leak in the RWCU room, Group Ill fails to actuate RU 9
SRO SRO Bop C, R Heater tube leak, load drop RO RO C
A reactor recirc pump seal failure ALL M
Intake structure blockage, loss of circ water 1/2 core hydraulic ATWS ALL ALL M
Turbine trip with no bypass valves M
Turnover: The plant is holding load at 80% reactor power. The 1 B EHC pump and GCB 3-4 are 00s. IRM # 15 is bypassed. The crew is to start I C RFP from Bus 12 and secure 1 B RFP first thing this shift.
I I
I 0
I tc09 a
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (Wajor, (T)ech Spec
Appendix D Scenario Outline Form ES-D-1 SU M MARY :
The plant is holding load at 80% power. 2 RFPs and 3 Condensate pumps are running. 18 EHC pump and GCB 3-4 are 00s. IRM #I5 is bypassed.
The crew will take the shift with orders to swap RFPs (BOP-N). After the RFP swap the A CRD pump will trip requiring the B to be started (RO-C, SRO-TS).
A leak will develop in the RWCU system and the Group Ill will fail to actuate on high room temperature (BOP-C). The BOP will manually isolate it.
A tube leak in the A3 low-pressure heater will cause the bypass to open and the number 3 string to isolate. The RO will drop load and the BOP will close the heater string bypass (RO-R, BOP-C)
The A reactor recirc pump seals will fail causing DW pressure to rise. The RO will trip and isolate the pump (RO-C).
While actions are being taken to recover from the loss of a recirc pump there will be a blockage at the intake structure tripping the circulating water pumps requiring a scram (M-All). A half core hydraulic ATWS will occur (M-All). During the ATWS condenser vacuum will be lost requiring pressure control with ADS valves.
The scenario will be terminated when the actions of QCOP 0300-28 have been taken, Torus cooling is on and reactor pressure is under control with ADS valves CRITICAL TASKS:
Critical task #I:
Critical task #2:
ES-401 BWR Examination Outline FORM ES-401-1 W
- 1.
Emergency &
Abnormal
- 2. u Plant Systems
~~
-acility Name: Quad Cities Date of Exam: May 2 - 9, 2005 I
'I I
I
- 3. Generic Knowledge and Abilities Categories RO KIA Ce 3
3 4
4 egory Points SRO-Only Points A
A I A Total A2 G*
Total 2
3 4
3 3
20 3
4 7
1 NIA 1
7 2
1 3
Jete: 1.
- 2.
- 3.
- 4.
- 5.
- 6.
7.'
- 8.
- 9.
Ensure that at least two topics from every applicable 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 KIA 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. Thl 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 tha 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 ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
Select topics from as many systems and evolutions as possible; sample every system or evolution in thc 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 bt 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 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topic5 must be relevant to the applicable evolution or system.
On the following pages, enter the KIA 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-onl!
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 selections to WAS that are linked to 10 CFR 55.43.
ES-401, Page 16 of 33
ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (RO)
K K
E/APE # I Name / Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Trip I 3 I
0 1
295006 SCRAM I 1 L-JI 0
3 295016 Control Room Abandonment / 7 29501 8 Partial or Total Loss of CCW / 8 0
7 295019 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling I4 295023 Refueling Acc / 8 295024 High Drywell Pressure I 5 L
0 2
295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. I 5 295027 High Containment Temperature I 5 0
1 600000 Plant Fire On Site / 8 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl / 5 295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 0
1 295038 High Off-site Release Rate I 9 3 I 4 I 3 f 3 IGroup Point Total I
20 1
K/A Category Totals.
3 4
ES-401, Page 17 of 33
ES-401 3
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401.
ES-401, Page 18 of 33
ES-401 4
Form ES-401-1 llES401 BWR Examination Outline Plant Systems - Tier 2IGroup 1 (RO)
Form ES-401 ES-401, Page 19 of 33
ES-401-1 5
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401 Plant Svstems - Tier 2/Grouo 2 fRO)
ES-401, Page 20 of 33
ES-401 2
Form ES-401-I ES-401 BWR Examination Outline Form ES-401-Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (SRO)
~
ES-401, Page 17 of 33
ES-401 3
Form ES-401-1 Form ES-401 BW R Examination Outline w
Orywell temperature 295014 Inadvertent Reactivity Addition / 1 ES-401, Page 18 of 33
BWR Examination Outline Form ES-401-ES-401 ES-401, Page 19 of 33
ES-401 5
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401 Plant Svstems - Tier 2IGrou~ 2 (SRO)
ES-401, Page 20 of 33
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 ES-401, Page 26 of 33
QUAD CITIES MAY 2005 INITIAL LICENSE EXAM OUTLINE COMMENTS
- 1.
Source Comment Resolution Dynamic The SRO should get credit for the Events in a Comment incorporated.
Simulator scenario (not just some).
Scenarios