ML051240372
| ML051240372 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/07/2005 |
| From: | Ross J Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML050900103 | List: |
| References | |
| 50-373/05-301, 50-374/05-301 50-373/05-301, 50-374/05-301 | |
| Download: ML051240372 (24) | |
Text
EXAMINATION OUTLINE SUBMITTAL AND NRC COMMENTS FOR THE LASALLE INITIAL EXAMINATION - MARCH 2005
Outline Submittal LaSalle County Station 2005 Initial Examination
~
Exelan,..
txelon Cenerdtioq Company, LLC LaSaIle County Statlor-w w w exeloncorp corn Nuclear 2601 N o r t h 21 Road f M a ~ ~ e i l l leL s61341-9757 November 8, 2004 United States Nuclear Regulatory Commission Attention: Regional Administrator, Region Ill 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-1Iand NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Submittal of Initial Operator Licensing Examination Outline Enclosed are the examination outlines supporting the Initial License Examination scheduled for the week of March 7, 2005, at LaSalle County Station. This submittal includes all applicable Examination Standard forms and outlines in accordance with NUREG-1021, Operator Licensing Examination Standards, 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 Terrence W. Simpkin at (815) 415-2800. For questions concerning examination materials, please contact John E. Ross at (815) 415-2276.
Respectfully, George P. Barnes Site Vice President LaSalle County Station
Enclosures:
(Hand delivered to 6. Palagi, Chief Examiner, NRC Region 111) cc: NRC Senior Resident Inspector - LaSalle County Station (Without enclosures)
c ES-201 Examination Outline Quality Checklist Form ES-201-2 lnitia Item Task Description a b '
- 1. a. Venfy that the outline(s) fit(s) the appropriate model. in accordance with ES401. L Mv
~~~ ~~
- b. Assess whether the outline was systematically and randomly prepared in accordance with '.
Section D . l 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.
v
- d. Assess whether the justifications for deselected or rejected WA statements are appropriate. '
2 a. Using Form ES-301-5. verify that the proposed scenario sets cover the required number of normal evolutions. instrument and component failures. technical specifications, S and major transients. w M b. Assess whether there are enough scenario sets (and spares) to test the projected number U and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity. and ensure that each applicant can be tested using Hw A at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days.
T 0
c . To the extent possible, assess whether the outline(s) conform(s) with the qualiative R and quantitative criteria specified on Form ES-3014 and described in Appendix D. Hn
~~~~ ~~ ~~
- 3. a. Venfy that the systems walk-through outline meets the criteria speafied on Form ES-301-2:
W (1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as speufied on the form .
c I T
(2) task repetition from the hst two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test@)
(4) the number of new or modifiedtasks meets or exceeds the minimunsspechd on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria Nn, on the form.
- b. Venfy that the administrative outline meets the Criteria s p e a k d on Form ES-301-1:
(1) the tasks are distributed among the topics as specmed on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the bst two NRC licensing examinations
- c. Determine if there are enough different outlines to test the p r o w e d number and mix of applicants and ensure that no items are duplicated on subsequent days.
- 4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
E N c. Ensure that WA importance ratings (except for plant-specific priorities)are at least 2.5.
E
- d. Check for duplication and overlap among exam sections.
A e. Check the entire exam for balance of coverage.
L '
- a. Author ,&
- b. Facility Reviewer r) I W
- c. NRC Chief Examiner (#) -1
- d. NRC Supervisor 2 w-12 do('
Note: # Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
b ES-201,Page 25 of 27
ES-30 1 Administrative Topics Outline F o ~ E S - 3 01- 1 Facility: LaSalle County Station Date of Examination: 03/07/2005 Examination Level: SRO Operating Test Number: 2003-01 Administrative Topic Type (See Note) Code* Describe activity to be performed Create and Place an Equipment Status Tag (EST) on the Main Steam Line (MSL) Radiation Monitor Conduct of Operations M Recorder 2.1.15 2.313.0 Review A New Case Core Performance Log and Report findings to the Shift Manager Conduct of Operations P (Similar to previous NRC Exam item.) 2.1.25 2.8/3.1 Review Completed Surveillance and Determine any Action Requirements Equipment Control D 2.2.12 2.613.0 Given a Radiation Survey Map, Determine Correct Area Posting Requirements Radiation control N 2.3.1 2.213.0 Determine Reportability Requirements per EP-AA- 1 14, for a Shutdown Required By Technical Specifications Emergency Plan D 2.4.30 2.213.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
(N)ew or (Mkdified from bank (2 1)
(P)revious 2 exams (I 1; randomly selected)
(S)imulator ES-30 1, Page 22 of 27
ES-301 Control Room/ln-Plant Svstem Outline Form ES-301-2 Facility: LaSalle Countv Station Date of Examination: 03/07/2005 Examination Level: SRO (see NOTE at bottom of page) Operating Test Number: 2003-01 Control Room Systems * (8 for RO, 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title
- a. Downshift RR Pumps to Slow Speed with One Pump Tripping to Off I Code**
A, D, S Safety Function 1
I 202001
- b. Initiate RClC for Level Control with Failure of 1E51-FO46to Automatically A, E, N, S 2 217000 I
Open
the Unit Supervisor
- d. Shutdown High Pressure Core Spray (HPCS) After an Automatic Initiation with High Drywell Pressure Present N, L, S 4 209002 I
- e. Start Containment Spray with a Failure of the Second Valve to Open I k4, E, L, N, 5 226001 I f.
g.
Perform LOS-DG-M3 (16 DG) with a Loss of the SAT Reset a Half-Scram with a Blown Group Scram Fuse 6
264000 7
I 2 12000
- i. In-Plant Actions to Lineup Cycled Condensate (CY) to Low Pressure 1 D, E, L, R 2 Coolant Injection (LPCI) for Vessel lniection 203000
- j. Hydraulically Isolate an Inoperable Control Rod Drive (CRD) Hydraulic 1 Control Unit (HCU) 201001
- k. Locally Start the OA VE Charcoal Filter N, R 9 290003
- 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 the control room.
- Twe Codes I Criteria for RO / SRO-I / SRO-U I (A)ltemate path 4-6 / 4-6 /' 2-3 (C)ontrol room (D)irect from bank 59 / 58 114 (E)mergency or abnormal in-plant 21 / 21 121 (L)ow-Power 21 / 21 / 21 (N)ew or (M)odified from bank including I(A) 22 f 22 f 21 (P)revious 2 exams 1 3 / < 3 / 1 2 (randomly selected)
(R)CA 21 / 2 1 / 2 1 (S)imulator NOTE: SRO-I will perform all 10 JPMs and SRO-U will perform the following five JPMs: d. (ESF), e., f., i.,
and j.
ES-301, Page 23 of 27
ES-301 Transient and Event Checklist Form ES-301-5 Instructions:
- 1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event p;TS are not ap licable for RO applicants. ROs must serve in both the at-the-controls (ATC) and L
balance-of- lant ( OP) positions; Instant SROs must do one scenario, including at least two instrument or component &C) malfbnctions and one major transient, in the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. *Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirement.
NOTE: Can use any one o Author:
NRC Reviewer:
/
ES-301, Page 26 of 27
- ES401 BWR Examination Outline FORM ES-401-1
- acility Name: LaSalle County Station Date of Exam: March 07, 2005 Jote: 1. Ensure that at least two topics from every applicable K/A 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 KIA 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 *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.
- 3. 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 KIA 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 KIA categories.
7: The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.
- 8. 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-only exams.
- 9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the KIA 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 2 Form ES-401-1 11ES-401 BWR Examination Outline Form ES-401-II Emergency and Abnorn I Plant Evolutions - Tier l1Group 1 (RO)
E/APE # I Name I Safety Function A G KIA Topias) IR 2
95001 Partial or Complete Loss of Forced Natural arculatm 35 Core Flow Circulation I1 & 4 0
295003 Partial or Complete Loss of AC 16 D C eledncalloads 34
/ 6
</
295004 Partial or Total Loss of DC Pwr I6 0
3 II R e d w SCRAM Plarn-Spec#~:
I 1 I
id 31 295005 Main Turbine Generator Trip I 3 v
0 2 I IRPS 3.6 1
))295006 SCRAM I1 Reactor water level response C M r o l rod posrtim 38.4? 2 2
O' .3 295016 Control Room Abandonment I7 m l d y to expram a d ap;thl system lrnits and pecautms 34 2 2 0
295018 Partial or Total Loss of CCW I8 .- Effeds on cnmponen(lsystem operatmi 35 J
0 295019 Partial or Total Loss of lnst Air I 8 Offgas system 28
> 6 295021 LOSS of Shutdown Cooling 14 Feeding and W i n g reactor vessel 33
\J I
0 295023 Refueling Acc I8 Fuel pool cwlmg and cleanup system 29
!,.' 2 295024 High Drywell Pressure I 5 fi I 4.2 95025 High Reactor Pressure I 3 I lSuPPRESSED 1 R e a d a walw bwl ndlcalm 36 95030 Low Suppression Pool Wtr Lvl I 5 NPSH czuwdaratms for ECCS pumps 35 r -
0 295031 Reactor Low Water Level I 2 I 1 7,. Anernate njectl~nsystems Plant-rpecrfc 38 1 8 295037 SCRAM Condition Present and Power 1
' Reactorpower 42 Above APRM Downscale or UnknownI 1
.1 7 1 00000 Plant Fire On Site I 8 satus mtena which require the notification Fire Classlfmtms by type I 25 25
... (IWA Category Totals: 1 4 1 3 1 4 1 3 3 3 Group Point Total ES-401, Page 17 of 33
ES-401 3 Form ES-401-1 BWR Examination Outline F o ES-401-
~
ES-401,Page 18 of 33
ES-401 4 Form ES-401-1 ES-401. Page 19 of 33
ES-401-1 5 Form ES-401-1 IIES-401 BWR ExaminationOutline Form ES-401-ES-401,Page 20 of 33
ES-401 2 Form ES-4 BWR Examination Outline Form ES-401-Ememencv and Abnormal Plant Evolutions Tier l/GrouD . 1 ISRO)
K K EIAPE # IName / Safety Function A A G WA Topic@) IR 1 2 295001 Partial or Complete Loss of Forced Core Flow Circulation I1 8 4 04, Abtlity to recognize abnormal indicabonsfor system 295003 Partial or Complete Loss operating parameterswhtch are entry-level condibons 43 o4 for emergency and abnormal operating procedures 295004 Partial or Total Loss of DC y&, Extent of partial or complete loss of D C power 39
.-7/
I 295005 Main Turbine Generator Trip I 3 Ib95006 SCRAM I 1 II 295016 Control Room Abandonment I 7
!@I, Knowledge of bases in technical speaficabons for limiting condibonsfor operations and safety limb I 37 1
295018 Partial or Total Loss of CCW I8 0 295019 Partial or Total Loss of Inst. Air / 8 0 295021 Loss of Shutdown Cooling I 4 95023 Refueling Acc I8 1p95024 High Drywell Pressure I5 5026 Suppression Pool High Water I: T-jI O4 IReactorvesselmetal temperature Ability to recognize abnormal indications for system operabng parameterswhich are entry-level condibons for emergency and abnormal operabng procedures I 3.3 43 1
1 0
0 0
95027 High Containment Temperature / 5 0 95028 High Drywell Temperature I5 1 0
Readorpower 42 1 2
5037 SCRAM Condibon Present and Power 95038 High Off-site Release Rate I 9 WA Category Totals: 0 0 0 3 4 Group Point Total:
ES-401, Page 17 of 33
ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline FOIWIES-401-Emergency and Abnormal Plant Evolutions - Tier llGroup 2 (SRO)
IR #
0 0
0 2.9 1 4 1 0
0 0
a 0
0 0
0 0
0 3.4 1 0
0 0
0 K/A Category Totals 0 0 0 0 1 2 Group Point Total L-I' 1 1 1 1 I I I ES-401, Page 18 of 33
ES-401 4 Form ES-401-1 ES-40 1 BWR Examination Outline F o ES-401-
~
ES-401, Page 19 of 33
ES-401 5 Form ES-401-1 ES401 - BWR Examination Outline Plant Svstems - Tier Z/GrouD 2 (SRO)
ES-401, Page 20 of 33
ES-401 Generic Knowledge and Abilities Outline (Tier 3) F o ES-401-3
~
[Facility Nan 3:LaSalle County Station Date of Exam:March 07, 2005 RO SRC Category WA # Topic IR # IR l.
1 0 2.1 . 01 ~ n o w ~ of g tonduct e d operations requaements 3.7 1 38 Abillty to locate control mom switches. controls and mdidions and to determne that they y; 12. ' 31 are ax~actlyrefledmg Ihe desired plant lneup 4.2 1 3.9
--I 2
I 1 / / I 3.8 1 Conduct of 1 Abillty to locate and operate components. lncludng local m t r o l s 3.9 3.4 Operations -. -
7.
1 2.1.
- 2. -
Equipment 1 Controt- $$
--/
---_ ~2.2.20 9
I Knowledge ofthe process for managtng bwbleshootmgadivflles 1 2
- 3. 2.3. 10 IAbillty to pertarm procedures to reduce e x c e s w levels d radialon and guard aganst personnel exposure I 2.9 I 1 I 3.3 Radiation Control *'/
r
.- I 2.9 2 4. 01 of EOP entry conditions and nnmediateadm steps - , 4.3 1 4.6 Knowledge of RO tasks performedwtwde the man m r o l room durng emergency 2.4. 34 operatlw i d w t n g system eeography and system nplicatiw 3.8 1 3.6 d me bases fa pn0rltuu-q safety f v l d m s dunng abmnnaUemerpency 2.4. 22 3 4 1 oo8(81ms 2.4. 40 \ Knavlsdeed the SROs responubibtlesn emergency plan nplementatm 2.3 4 P .., l 1 2.4.
' .- 2 ,y , If 5 I 2.4.
ES-401,Page 26 of 33 k
J'
Examiners: Operators:
Initial Conditions:
0 Ramping to full power following a unit startup 0 Rated Rod Line with core flow at -85 Mlbmhour Turnover:
0 Continue the power ramp per the QNEs request L
Event Malf. Event Event No. No. Type* Description
(N) SRO Supervises crew activities
, 2. kln24bnm (C) BOP RCIC Drain Pot Failure ro5 63 (C) SRO Technical Specification Determination
- 3. mrd280 (C) RO CRD Pump trips/Start standby CRD pump SRO Directs actions per the annunciator and normal procedures
(I) SRO Technical Specification Determination
(M) SRO Automatic Scram Failure, manual scram works. LGA Entry Conditions
- (Nbrmal, (R)eactivity, (I)nstruement, (C)omponent, (M)ajor Transient Page 1 o f 2
Narrative Summary NRC Scenario-01:
Event Description
- 1. Initial conditions have the plant completing a startup, LGP-3-1 is in progress. Power is approximately 93% RTP. The examinees are directed to continue ramping power to 100% using Reactor Recirculation Flow Control Valves.
- 2. The RCIC drain pot high level alarm will annunciate. The examinees will recognize that the drain bypass valve 1E5 1-F054 has automatically opened. Following the annunciator procedure, when the high level alarm does NOT clear, they will have to close the RCIC Trip and Throttle Valve lE51-F360. This will render the RCIC system inoperable and the Unit Supervisor will have to make a Technical Specification determination.
- 3. The running CRD Pump will trip. Per the annunciator procedure, the NSO will verify that Charging Water Pressure is greater than 500 psig, and then start the standby CRD pump, and follow up with normal operating procedure.
- 4. An instrument line reference leg will rupture in the reactor building.
Among other indications, this will cause the 1A RR Pump Low Differential Temperature timer will initiate. By procedure, the NSO will bypass this timer. The Unit Supervisor will have to make another Technical Specification determination.
- 5. For this event a Reactor Recirculation line will break causing LOCA conditions in the Drywell. Automatic RPS Scram will fail however manual actions to scram will be successful. The Unit Supervisor will enter the EOPs and take actions to control Reactor Water Level and Drywell Pressure. The MDRFP trips shortly after starting. Bus 143 trips on overcurrent. RCIC is not available from an earlier event. This will require a blowdown for level control.
Termination The scenario can be terminated when the examinees have FWV and Containment parameters stable and under control.
Critical Steps:
- 1. Manually scram the reactor when automatic setpoint is exceeded.
- 2. Perform a blowdown per the EOPs when level cannot be restored and maintained above -1 50 inches.
Page 2 of 2
Facility: LaSalle County Station Scenario No.: Scenario-02 Op Test No.: 2003-01 NRC Exam Examiners: Operators:
Initial Conditions:
Ramping to full power following a unit startup 0 Full power with flow backed off to -85 Mlbmhour Turnover:
0 Start the 1 B CRD, shutdown 1A CRD for oil change 0 Continue the power ramp to 100% power per the QNE Event Malf. Event Event No. No. Type* Description I. NIA (N) RO Swap running CRD pumps
'v 2. rO60 1 Low ADS Bottle Bank Nitrogen Pressure Technical Specification Determination
- 3. various 1B TDRFP Seal Injection Pump trips and standby fails to start overrides 4.
5.
zc 1 1025 k6k07wt8 (C)
(C)
I1R O I1 RO CRD Accumulator Trouble Alarm (low pressure)
SRO Technical specification Determination Loss of4160 vac Bus 141X (C) SRO
- 6. NIA Reduced of Heater Drain Pump Forward
~ ~ ~~~
- 7. mrc033 Recirculation loop rupture - LOCA conditions in the Drywell
~~
- (N)ormal, (R)eactiv (C) SRO Page 1 of 2
Narrative Summary NRC Scenario-02:
W Event Description
- 1. This event is a normal swap of the running CRD pump (from 1A to 1B) per the procedure.
- 2. Drywell pneumatic trouble alarm is received, an NLO is send to investigate. The NLO reports back to the control room that the South Bottle bank pressure is actually below the alarm setpoint. The Unit Supervisor is expected to make a Technical Specification determination.
- 3. The running TDRFP Seal Injection Pump will trip and the standby pump will fail to automatically start. The NSO will take actions per the annunciator procedure.
- 4. Next a CRD HCU Accumulator will alarm. The examinees are expected to dispatch an NLO to the effected HCU. The NLO reports that the accumulator has low pressure. The Unit Supervisor is expected to declare the accumulator inoperable and make a Technical Specification determination.
- 5. Bus 141X will trip. This causes loss of two Heater Drain pumps. The NSO is expected to start the standby Heater Drain pump.
- 6. The examinees are expected to enter LOA-HD- 101 and reduce power. If this is not done before Heater Drain Tank level increases to 9-feet the HD Flushing valves will open and the Feedwater Pumps will trip on low suction pressure.
- 7. Next a LOCA will develop in the Drywell. The event is entered when directed by the lead examiner or immediately if the reactor automatically scrams due to loss of Feedwater. The examinees are expected to enter the EOP based on RPV Level and Containment Pressure.
The examinees are expected to enter LGA-0 10 and LGA-NB-0 1 and take actions to shutdown the reactor. When the first fuse is pulled rods will start to move however the SDV will fill and they will have to reset the scram, drain the SDV and re-scram reactor to get rods to go full-in.
Termination Scenario can be terminated when the examinees have RPV and Containment parameters stable and under control.
Critical Steps:
- 1. Reduce power per the abnormal operating procedure to prevent a loss of Feedwater and resulting scram following loss of 141X.
- 2. Use multiple methods per EOP Support procedure to insert control rods during an ATWS.
Page 2 of 2
Facility: LaSalle Countv Station Scenario No.: Scenario-03 Op Test No.: 2003-01 NRC Exam Examiners: Operators:
I Initial Conditions:
0 Startup in progress per LGP 1 0 Ready to roll the main turbine Reactor Power is GO%
Turnover:
Continue to pull rods per the sequence package Event Malf. Event Event No. No. Type* Description
- 1. NIA (R) RO Continue pulling control rods per the sequence package W) SRO
- 2. Stuck control rod, moves after increasing Drive Water pressure
- 4. Failure of 1C VR Fuel Pool Exhaust Radiation Monitor upscale Technical Specification Determination
- 5. Off-Gassuction rupture and loss of vacuum and manual scram, 3 (M) SRO stuck rods (ATWS), manually drive rods in mrd218 mrd213
Narrative Summary NRC Scenario-03:
Event Description
- 1. The RO will continue to pull control rods per the startup sequence package.
- 2. One control rod is discovered to be stuck. Several attempts to free the rod using the normal operating procedure (LOP) will fail. The LOP will direct the operator to take actions per the abnormal operating procedure. When drive water pressure is increased sufficiently, the rod will free itself. And the startup can continue.
- 3. While pulling a control rod one of its RPIS reed switches will fail at the final withdrawal position. The crew will take actions per the abnormal operating procedure and the SRO will make a Technical Specification determination.
- 4. One of the four Reactor Building Ventilation Fuel Pool Exhaust Radiation Monitors fails upscale. This will cause an annunciator to alarm in the control room. The Unit Supervisor is expected to make a Technical Specification determination.
- 5. A rupture in the Off-Gas 2ndStage Air Ejector line will cause a slow loss of vacuum. The crew will have time to dispatch operators to look for air leakage into the main condenser. The size of the leak continues to increase until the crew is forced to manually scram the reactor. When the reactor is scrammed, 3 control rods will stick full-out rendering a low power ATWS.
The RO will be able to close the Drive Water Pressure control valve and then manually drive the three control rods full-in.
- 6. Next a steam leak LOCA will develop with a containment bypass path.
Termination The scenario can be terminated when the examinees have RPV and Containment Parameters stable and under control.
Critical Steps:
- 1. Initiate Suppression Chamber Sprays and Drywell Sprays to control containment parameters
- 2. Use EOP Support Procedures to insert control rods following the scram.
Page 2 of 2
COMMENTS ON LASALLE 2005 EXAMINATION OUTLINE Outline Section Comment and Resolution Comment: Be sure that the JPM covering review of a Core Performance Log is clearly different than that given in the previous exam.
Resolution: Different initial conditions will be used and different parameters will be out of specification.
Admin Topics Comment: Be sure that the JPM covering review of a completed surveillance is safety significant.
Resolution: JPM required identification of an inop RClC system.
System JPMs Comment: Be sure there or no JPMs with only one critical task, and be sure there is safety significance to each JPM.
Resolution: To be verified during on site validation.
Written Exam Discussed how random selection of KAs was done.
Resolution: KA selection was random I Written Exam Discussed not over using 2 out of 2 twice type of question.
Resolution: Will be evaluated during written exam review.