ML042950318
| ML042950318 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/16/2004 |
| From: | Bost D Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML042540508 | List: |
| References | |
| 50-237/04-301, 50-249/04-301 50-237/04-301, 50-249/04-301 | |
| Download: ML042950318 (26) | |
Text
EXAMINATION OUTLINE SUBMITTAL FOR THE DRESDEN INITIAL EXAMINATION - AUGUST 2004
Exelon Generation Company, LLC www.exeloncorp.com Nuclear Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 April 5, 2004 SVPLTR 04-001 1 U. S. Nuclear Regulatory Commission Region I l l ATTN: Operator Licensing Branch 801 Warrenville Road Lisle, IL 60532-4351 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 Docket Nos. 50-237 and 50-249
Subject:
Submittal of Initial Operator Licensing Examination Outlines Enclosed are the examination outlines supporting the Initial License Examination at Dresden Nuclear Power Station. The examinations are scheduled for the week of August 16, 2004.
This submittal includes all appropriate Examination Standard forms and outlines in accordance with Draft Revision 9 of NUREG-I 021, Operator Licensing Examination Standards.
in accordance with NUREG 1021, Draft 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 Jeff Hansen, Regulatory Assurance Manager, at 81 5-41 6-2800. For questions concerning examination outlines, please contact Shannon Frey at 815-416-2406.
Respectfully, Dresden Nuclear Power Station
Enclosures:
(Hand delivered to Chief Examiner, NRC Region 111)
Examination Security Agreements (Form ES-201-3)
Administrative Topics Outline (Form ES-301-1)
Control Roomlln-Plant Systems Outline (Form ES-301-2)
BWR Examination Outline (Forms ES-401-1)
Generic Knowledge and Abilities Outline (Tier 3) (Form ES-401-3)
Scenario Outline (Form ES-D-1)
Record of Rejected WAS (Form ES-401-4)
Examination Outline Quality Checklist (Form ES-201-2)
Transient and Event Checklist (Form ES-301-5) cc:
(without attachments)
Chief, NRC Operator Licensing Branch NRC Senior Resident Inspector - Dresden Nuclear Power Station
ES-20 1 Examination Outline Quality Checklist Form ES-20 I
-2
- 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.
- 3.
- a. Verifvthat:
L (1) the kutline(s) contain(s) the required number of control room and in-plant tasks, P
W I
T (2) no more than 30% of the test material is repeated from the last NRC examination, (4) no more than 80% of any operating test is taken directly from the licensees exam banks.
-)[(3)*
no tasks are duplicated from the applicants audit test(s), and (2) one task is conducted in a low-power or shutdown condition,
~
- a. Author J. Facility Reviewer (*)
- . NRC Chief Examiner
- Independent NRC Reviewer initial items in Column c chief examiner concurrence required.
UREG-1021, Draft Revision 9 LEBV 5, U
Facility: Dresden Examination Level (circle one): RO Date of Examination: 811 612004 Operating Test Number: ILT 03-1 Administrative (see Note)
Conduct of Operations Conduct of Operations Equipment Control 3adiation Control Zmergency Plan Describe activity to be performed JPM: Authorization of Overtime IAW GL 82-12 Requirements WA: 2.1.4, 2.3 I 3.4 REF: LS-AA-119, LS-AA-119 Att. 1 JPM: Initiate a Firewatch WA: 2.1.8, 3.8 I 3.6 REF: OP-MW-201-007 JPM: Verify U3 EDG Surveillance
.(/A:
2.2.12, 3.0 13.4 REF: DOS 6600-01 JPM: CCSW Activity Calculation Verification VA: 2.3.11, 2.713.2 IEF: DOS 1500-08 IPM: Complete a NARS Form and make the required notifications
?EF: EP-AA-174 WA: 2.4.38,2.2 14.0 NUREG-1021, Draft Revision 9 22 of 27 IRC O u t l i n e S u b m i t t a l Copy
ES-301 Control Room/ln-Plant System Outline Form ES-30 I -2 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
Date of Examination: 8/16/2004 Type Safety Code*
Function System / JPM Title
- a. Recirculation System - Startup of 2nd Recirc Pump w/ Failure of D, A, S, L (I)
Reactivity Discharge Valve to Open.
DOP 0202-01; K/A: 202001 A4.01, 3.7 / 3.7 Control (2)
Reactor Watei Inventory
- b. Reactor Water Cleanup System - Reject Primary Water Via N, s, L RWCU System Following a Group 3-Isolation.
DOP 1200-02; MA: 204000 A4.03, 3.2 / 3.1 Control (3)
Reactor Pressure Control
- c. HPCl - Manually Start HPCl for Pressure Control D, s, L DOA 2300-02; WA: 206000 A4.06, 4.3 / 4.3 (5)
Containment Integrity
- d. LPCl - Perform LPCl System Operability Test with Torus D, A, s Available, Pump Trips.
DOP 1500-03; WA: 219000 A4.01, 3.8 / 3.7
- e. AC Electrical Distribution - Transfer Auxiliary Power to TR-22 D, A, S, L (6)
Electrical from TR-21, TR-22 to Bus 23 ACB fails to close.
DOP 6500-01; KIA: 262001 A4.04, 3.6 / 3.7 N, s (7)
D, A, s, L (9)
Instrumentation DOS 0700-08; WA: 215005 A4.05, 3.4 / 3.4
- g. Standby Gas Treatment System - SBGT Post Maintenance Radioactivity Release Testing with receipt of an Auto Initiation Signal.
DOP 7500-01; WA: 261000 A2.10, 3.1 / 3.2
- h.
In-Plant System (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i. Control Rod Drive Hydraulic System - Vent the U3 Scram Air M, R (1)
Reactivity Header to Perform an Alternate Insertion of Control Rods.
- j. D.C. Electrical Distribution - Restore Unit 2 125 VDC Battety DEOP 500-5; WA: 201001 K4.04, 3.6 / 3.6 Control D
(6)
Electrical System to Operable Following a failure of One or More Battery Buses.
DOP 6900-08: WA: 263000 A4.01. 3.3 / 3.5 D, A (7)
- k. Reactor Protection System - Supply U3 RPS Bus B From RPS Instrumentation MG 3A with MG Failure to Start Initially.
DOP 0500-03; WA: 212000 A2.02, 3.7 / 3.9 Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol 23 of 27 NUKEG-1021, Draft Revision 9
?C O u t 1 l n e S u b m i t t a l Co
_I
Applicant Evolution Minimum Scenario Number 1
2 1
3 I
4 I
Type Type Number RO Instructions: (1)
(2)
Enter the o erating test number and Form ES-D-1 event numbers for Reactivit manipulations may be conducted under normal or controlled Section C.2.a of A pendix D.
- Reactivity and normal evolutions may be for-one basis.
be include ; only those that require verifiable actions that provide insi ht each evolu P ion type.
abnorma Y conditions (refer to Section D.5.d) but must be significant per replaced with addi P ional instrument or component malfunctions on a one-(3)
Whenever ractical, both instrument and component malfunctions should etence count toward the minimum requiremen!!
c f Author:
NRC Reviewer:
I p./ 7-
' L.
NUREG-1021, Draft Revision 9 24 of 26
3-401 BWR Examination Outline FORM ES-401-1
=acility Name: Dresden Date of Exam: 8/16/2004 Jote: 1.
- 2.
- 3.
- 4.
- 5.
6.*
- 7.
- 8.
- 9.
Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the Tier Totals in each WA category shall not be less than two). Refer to Section D. 1.c for additional guidance regarding SRO sampling.
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.
Select topics from many systems and evolutions; avoid selecting more than two KIA topics from a given system or evolution unless they relate to plant-specific priorities.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the categoryhier.
The generic (G) KlAs in Tiers I and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.
For Tier 3, enter the KIA numbers, descriptions, importance ratings, and point totals on Form Refer to ES-401,, for guidance regarding the elimination of inappropriate WA statements.
REG-1021, Draft Revision 9 IRC O u t l i n e S u b m i t t a l C O P Y
-d
w I
I :
295001 Partial or Complete Loss of Forced II Core Flow Circulation / 1 & 4 ES-401 BWR Examination Outline Form ES-40 Emergency and Abnormal Plant Evolutions - Tier IIGroup 1 (RO)
K K
/APE #I Name I Safety Function Ir 295003 Partial or Complete Loss of AC 16 0
1 0 I 295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 3.2 3.5; 3.7 3.6 4
3.4 2.8 2.5
~
95004 Partial or Total Loss of DC Pwr I 6 1
0 2
1 1
1 1
1 295005 Main Turbine Generator Trip I 3 01.3 3
Ability to recognize indications b r system operating parameters which are entry-level condilions for technical specifications.
I I 295019 Partial or Total Loss of Inst. Air I 8 3
295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc Cooling Mode I 8
- _I-Breakers. relays. and disconnects 4
3 3 Group Point Total:
295024 High Drywell Pressure I 5 I
,. -J
-\\:%
95025 High Reactor Pressure 13 I
KIA Category Totals:
2 5
295026 Suppression Pool High Water 295027 High Containment Temperature I5 It I
1 I
I I I 1k95028 High Drywell Temperature 15 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level 12 95037 SCRAM Condition Present and Power bow APRM Downscale or Unknown / 1 295038 High Off-site Release Rate I 9 lfsOO000 Plant Fire On Site I 8 I I I ISystems necessary to assure safe plant shutdown 1
1 1
1 Turbine valve position Knowledge of system purpose andlor function.
I I l i l I I I IRemote shuldown panel: Plant-Specific Backup air system supply: Plant-Specific O
l I
I I
1 ContainmenV d w e l l temperature kl I I 0 4. ~
Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
I I I
/Pressure effects on reactor water level I
I I
ISuppression chamber pressure: Mark-l&ll Suppressed RPV flooding: ADS 0
0 2
5 1 7 I I (ECCS systems (NPSH considerations): Plankspecific Reactor power I
I I
I I I I (Meteorological effects on off-sile release 3.3 I 1 z 3.5 NUREG-1 021, Draft Revision 9 18 of 34 R C O u t l i n e S u b m i t t a l Copy
._I_-
95029 High Suppression Pool Wtr Lvl / 5 Reactor SCRAM
-1021, Draft Revision 9
?C O u t l i n e S u b m i t t a l COPY
t i
206000 HPCl 207000 Isolation (Emergency)
Condenser 1(ES-401
~~
209001 LPCS 209002 HPCS 21 1000 SLC 11 ElAPE # I Name I Safety Function 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 11203000 RHRILPCI: Injection
~
~~
262002 UPS (ACIDC) 263000 DC Electrical Distribution 264000 EDGs 1
p O
Shutdown Cooling Mode 212000 RPS +--
215003 IRM 112~5004 Source Range Monitor
(~15005 APRM I LPRM 217000 RClC
"-7 259002 Reactor Water Level Control 261 000 SGTS 262001 AC Electrical Distribution 300000 Instrument Air I1 400000 Component Cooling Water K/A Category Totals:
NUREG-I 021, Draft Revision 9 4RC O u t l i n e S u b m i t t a l Copy BWR Examination Outline
~
~~
Form ES-401-41 20 of 34
21 of 34 NRC O u t l i n e S u b m i t t a l C O P Y NUREG-1021, Draft Revision 9
ES-401 Emerger E/APE # I Name I Safety Function 295001 Partial or Complete Loss of Forced I Core Flow Circulation I 1 & 4 I
295003 Partial or Complete Loss of AC I 6 II
~~~
~~
~
295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip I 3 0
1 295006 SCRAM I 1 295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc Cooling Mode I 8 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. 1 5 295027 High Containment Temperature I 5 295028 High Drywell Temperature I5
~
~~
295030 Low Suppression Pool Wtr Lvl / 5 295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / 8 I
1 K/A Category Totals:
1 i W-1 BWR Examination Outline and Abnormal Plant Evolutions - Tier 1IGrouo 1 (SRO)
Form ES-401.
NUREG-1021, Draft Revision 9 18 of 34 URC O u t l i n e S u b m i t t a l C o p y
I-
/ -.
.pbpi
'L/
95002 Loss of Main Condenser Vac J 3 295022 Loss of CRD Pumps I 1 E-b i 'L-NUREG-1021, Draft Revision 9 I R C O u t l i n e S u b m i t t a l C o p y
/Po' I,
BWR Examination Outline Form ES-40' CSJ - -- I-----
ElAPE # f Name f Safety Function
- I 203000 RHRILPCI: Injection
/PO5000 Shutdown Cooling Mode 21 1000 SLC I
I Plant Systems - Tier 2/Group 1 (SRO)
NUREG-1021, Draft Revision 9 JRC o u t l i n e s u b r n ~ t t a i c o p y 20 of 34
JRC O u t l i n e S u b m i t t a l C o p y
3C O u t I i ne S u b m i t t a I C o p y
Facility: Dresden Scenario No: ILT-N-1 Op-Test No: ILT 03-1 Examiners:
Operators:
Event No.
1
?
3 1
1 j
I Malfunction Event Event Number Type*
Description None C
SRo Vacuum breaker stuck approximately 20% open.
NSO NSO NSO RODLOGDI C
SRO Control Rod Begins to drift in.
RDPPATRP C
SRO 2A CRD Pump is making a grinding noise, must swap.
N IASPOT I
SRO APRM 5 Fails Upscale. Bypass and Reset Half Scram.
121 Small Leak in Drywell.
2B CRD pump trips on low suction pressure and RDPPBTRP M
Accumulator alarms begin to come in.
RODST Several control rods remain withdrawn. The leak in 122 drywell gets worse.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor RC O u t l i n e S u b m i t t a l C o p y
ILT-N-L§CENARIO OVERVIEW L..
L/
Scenario Obiective Evaluate the crew's ability to control the plant during a condition requiring Emergency Depressurization.
Narrative Summary:
- 1. Unit is in Mode I at -95% power, operating per BPO.
- 2.
The following equipment is 00s:
- a. 2B Stator Cooling Pump
- b. IRM16
- 3. LCOs:
- a. None
- 4. Scenario Description At shift turnover, the team is informed of a Torus to Drywell vacuum breaker that has failed DOS 1600-9 and is stuck approximately 20% open. The team begins a plant shutdown.
Control rod H-01 will begin drifting in.
A report comes into the Main Control Room that the 2B CRD pump is making a loud grinding noise. The NSO will swap CRD pumps, placing 2A CRD pump in service.
APRM Channel 5 fails upscale. The NSO will bypass_the_APRM and Reset the half scram.
A small steam leak upstream of the restrictors occurs. The Team will begin to execute the DOA for slow leak.
The running CRD pump trips on low suction pressure and accumulator alarms begin to come in. When the Team scrams three rods stay out. The CRD pump can be restarted after an NLO swaps suction filters to drive in rods. The steam leak will get worse and pressurize the containment, forcing an Emergency Depressurization.
-8. -.-
Scenario Run Time:
60 min.
Scenario Events:
Event 1 - Torus to Drywell Vacuum Breaker Fails Open At shift turnover, the team is informed of a Torus to Drywell vacuum breaker that has failed DOS 1600-9 and is stuck approximately 20% open. Attempts by the team to close the valve are unsuccessful. The team begins a plant shutdown.
Malfunctions Required:
Torus/DAN vacuum breaker failed 20% open Note: This malfunction does NOT count quantitatively due to occurring before turnover.
Success Path:
~ R C o u t 1 ne s u ~ r n i t t a l C O D Y
sew L
Control rod H-01 will begin drifting in.
Malfunctions Required:
e Rod H-01 Drifts In Success Path:
o 0
Executes DOA 0300-05, Inoperable or Failed CRDs.
Executes DOA 0300-12, Mispositioned CRD.
Event 3 - CRD Pump Swap A report comes into the Main Control Room that the 2B CRD pump is making a loud grinding noise. The NSO will swap CRD pumps, placing 2A CRD pump in service.
Malfunctions Required: 1 Success Path:
e CRD pump trip if NSO does not swap pumps in a timely manner.
NSO swaps running CRD pumps.
L Event 4 - APRM 5 Fails Upscale APRM Channel 5 fails upscale.
Malfunctions Required: 1 Success Path:
e Bypass APRM Channel 5 o
-7 APRM Channel 5 Fails Upscale Performs DOP 0500-07, Manual Half Scram Reset Event 5 - Slow Leak A small steam leak upstream of the restrictors occurs.
Malfunctions required: 1 Success path:
Small steam leak before restrictors.
Performs DOA 0040-01, Slow Leak NRC o u t ~
~ n e s u b r n i t t a i C O P Y
~
__I
Event 6 - Runninq CRD Pump Trips on Low Suction Shortly after the CRD pump trips, the team receives an accumulator trouble alarm. Shortly after the initial alarms others come in at odd times until a total of 8 accumulator alarms are in. The Operators should scram after the first accumulator alarm is received.
Malfunctions required: 2 Numerous accumulator alarms Success Path:
e Scram, perform DGP 2-3
<*/
&i das*u,~w Trip of 2A CRD pump Event 7 - Reactor Fails to scram and Pressurizes the containment forcinq an Emerqency Dewessurization As the steam leak propagates, the failed open vacuum breaker will prevent proper condensation of the steam and consequently, Torus and Drywell pressures will rapidly rise.
Malfunctions required: 3 0
Large steam leak after restrictors Severaf control rods remain withdrawn.
Success Path:
I-0 Performs DEOP 400-02, Emergency Depressurization.
bi NSO drives in withdrawn control rods.
NRC O u t 1 i n e S u b m \\ t t a l c o p y
-E.+
Fa Ex Inii Tu 1
None cility: Dresden Scenario No: ILT-N-2 Op-Test No: ILT 03-1 aminers:
Operators:
NSO R
SRO tial Conditions: Rx Power - 15%, 2B Stator Cooling Pump OOS, IRM 16 00s.
rnover: Continue with startup per DGP 1-1.
2 3
4 NSO DORC13DO C
SRO ANSO SER1222 s
SRO RODK08AT C
SRo 5
5 7
NSO RLLMLS 1
SRO RRMASLI F RRMASLZF AI!
RDHLDEGA RDHLVFPA Event Description Raise power with rods Control rod double notches while withdrawing control rods LPCl system low pressure alarm Accumulator alarm due to low pressure FWLC setpoint drifts high Recirc pump seal failure All rods do not go in
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC O u t l i n e S u b m i t t a l C O P Y
ILT-N-2 SCENARIO OVERVIEW Evaluate Operator actions during ATWS Narrative Summary:
- 1. Unit is at -15% power. Continue with startup per DGP 1-1.
- 2. The following equipment is 00s:
- a. 28 Stator Cooling Pump
- b. IRM 16
- 3. LCOs:
- a. None
- 4. Scenario Description The Team increases reactor power by withdrawing control rods per DOP 0400-01, and DGP 01-01.
The Team recognizes and responds to a control rod that double notches. The Team will insert the control rod to its target position.
A LPCl System low-pressure alarm is received and the SRO must review Tech Specs and declare the loop INOP until the system is vented.
An accumulator alarm comes up due to low pressure. The SRO will reference Tech Specs and The Team recognizes and responds to a failure of the automatic mode of the FWLC system by taking FWLC to manual.
The 2A recirc pump seal fails and begins to pressurize the drywell, the suction valve will not close due to being shorted out from the leak and the Team will be forced to scram.
When the Team scrams the reactor, all the rods do not go in initially. Repeated scram resets will be successful in getting the rods to go in.
. i - - _.__=
= -_--.
declare the acc-umulator INOP.
L,<+.
Scenario Run Time:
60 min.
Scenario Events:
Event 1 - Raise Dower bv withdrawinq control rods The Team increases reactor power by withdrawing control rods per DOP 0400-01, and DGP 01-
- 01.
Malfunctions required:
0 0
Success Path:
0 Control rods pulled per applicable procedures.
NRC O u t l i n e S u b m i t t a l C o p y
..... ~.
~
~
The Team recognizes and responds to a control rod that double notches. The Team will insert he control rod to its target position.
Malfunctions Required:
e Control rod double notches.
Success Path:
e The control rod is moved to its target position.
Event 3 - LPCl System Low Pressure Alarm A LPCl System low-pressure alarm is received and the SRO must declare the loop INOP until the system is vented.
Malfunctions Required: 1 e
LPCl System low-pressure alarm.
Success Path:
e SRO declares the system INOP until it is vented.
L 7
Event 4 -Accumulator Alarm An accumulator alarm comes up due to a faulty instrument in the field.
Malfunctions required: 1 e
Accumulator alarm.
Success path:
References Tech Spec and declares the accumulator INOP.
Event 5 - Failure of the FWLC Auto Mode The Team recognizes and responds to a failure of the automatic mode of the FWLC system.
Malfunctions Required: 1 e
FWLC setpoint drift Success Path:
Takes manual control of the FWLC system.
NRC O u t l i n e S u b m i t t a l C O P Y
.-___CL c
The 2A recirc pump seal fails and begins to pressurize the drywell, the suction valve will not close due to being shorted out from the leak.
Malfunctions required: 3 Recirc pump seal failures.
Success Path:
0 Suction valve fails to close.
Scram prior to drywell reaching 2.0 psig.
Event 7 - ATWS When the Team scrams the reactor, all the rods do not go in initially. Repeated scram resets will be successful in getting the rods to go in.
Malfunctions required: I 0
Partial CRD hydraulic lock Success Path:
0 Manually drives control rods, performs repeated scram resets per DEOP 500-1.
w NRC O u t l i n e S u b m i t t a l C o p y