ML042950318

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Examination Outline Submittal for the Dresden Initial Examination - August 2004
ML042950318
Person / Time
Site: Dresden  Constellation icon.png
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)
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Text

EXAMINATION OUTLINE SUBMITTAL FOR THE DRESDEN INITIAL EXAMINATION AUGUST 2004

Exelon Generation Company, LLC Dresden Nuclear Power Station www.exeloncorp.com Nuclear 6500 North Dresden Road Morris, IL 60450-9765 April 5, 2004 SVPLTR 04-0011 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 815-416-2800. 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-201 Examination Outline Quality Checklist Form ES-20I-2

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4and 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 (2) no more than 30% of the test material is repeatedfrom the last NRC examination, I -)[(3)* no tasks are duplicated from the applicants audit test(s), and T (4) no more than 80% of any operating test is taken directly from the licensees exam banks.

(2) one task is conducted in a low-power or shutdown condition, ~

a. Author J. Facility Reviewer (*)
. NRC Chief Examiner
  1. IndependentNRC Reviewer initial items in Column cchief examiner concurrence required.

UREG-1021, Draft Revision 9 LEBV 5,

U

Facility: Dresden Date of Examination: 811612004 Examination Level (circle one): RO Administrative Describe activity to be performed Operating Test Number: ILT 03-1 (see Note)

JPM: Authorization of Overtime IAW GL 82-12 Requirements REF: LS-AA-119, LS-AA-119 Att. 1 Conduct of Operations WA: 2.1.4, 2.3 I 3.4 JPM: Initiate a Firewatch REF: OP-MW-201-007 Conduct of Operations WA: 2.1.8, 3.8 I 3.6 JPM:Verify U3 EDG Surveillance REF: DOS 6600-01 Equipment Control

.(/A: 2.2.12, 3.0 13.4 JPM: CCSW Activity Calculation Verification IEF: DOS 1500-08 3adiation Control VA: 2.3.11, 2.713.2 IPM: Complete a NARS Form and make the required notifications Zmergency Plan ?EF: EP-AA-174 WA: 2.4.38,2.2 14.0 NUREG-1021, Draft Revision 9 22 of 27 IRC Outline Submittal Copy ES-301 Control Room/ln-Plant System Outline Form ES-30I -2 Date of Examination: 8/16/2004 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Safety Code* Function

a. Recirculation System - Startup of 2nd Recirc Pump w/ Failure of D,A, S, L (I)

Discharge Valve to Open. Reactivity DOP 0202-01; K/A: 202001 A4.01, 3.7 / 3.7 Control

b. Reactor Water Cleanup System - Reject Primary Water Via N, s, L (2)

RWCU System Following a Group 3-Isolation. Reactor Watei Inventory DOP 1200-02; MA: 204000 A4.03, 3.2 / 3.1 Control

c. HPCl - Manually Start HPCl for Pressure Control D,s, L (3)

DOA 2300-02; WA: 206000 A4.06, 4.3 / 4.3 Reactor Pressure Control

d. LPCl - Perform LPCl System Operability Test with Torus D, A, s (5)

Available, Pump Trips. Containment Integrity 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) from TR-21, TR-22 to Bus 23 ACB fails to close. Electrical DOP 6500-01; KIA: 262001 A4.04, 3.6 / 3.7
f. APRM / LPRM - Bypass an LPRM. N, s (7)

DOS 0700-08; WA: 215005 A4.05, 3.4 / 3.4 Instrumentation

g. Standby Gas Treatment System - SBGT Post Maintenance D,A, s, L (9)

Testing with receipt of an Auto Initiation Signal. Radioactivity DOP 7500-01; WA: 261000 A2.10, 3.1 / 3.2 Release 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)

Header to Perform an Alternate Insertion of Control Rods. Reactivity DEOP 500-5; WA: 201001 K4.04, 3.6 / 3.6 Control

j. D.C. Electrical Distribution - Restore Unit 2 125 VDC Battety D (6)

System to Operable Following a failure of One or More Battery Buses. Electrical DOP 6900-08: WA: 263000 A4.01. 3.3 / 3.5

k. Reactor Protection System - Supply U3 RPS Bus B From RPS D, A (7)

MG 3A with MG Failure to Start Initially. Instrumentation 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 Out1 lne Submittal Co

_ I

Applicant Evolution Minimum Scenario Number I Type Type Number 1 2 1 3 I 4 RO Instructions: (1) Enter the o erating test number and Form ES-D-1 event numbers for P

each evolu ion type.

Reactivit manipulations may be conducted under normal or controlled (2)

Y abnorma conditions (refer to Section D.5.d) but must be significant per Section C.2.a of A pendix D.

  • Reactivity and normal evolutions may be P

replaced with addi ional instrument or component malfunctions on a one-for-one basis.

(3) Whenever ractical, both instrument and component malfunctions should cf be include ; only those that require verifiable actions that provide insi ht etence count toward the minimum requiremen!!

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. 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.

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. 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.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the categoryhier.

6.* The generic (G) KlAs in Tiers Iand 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.

7. 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.
8. For Tier 3, enter the KIA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9. Refer to ES-401,Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

REG-1021, Draft Revision 9 IRC Outline Submittal COPY

- -d

ES-401 BWR Examination Outline Form ES-40 Emergency and Abnormal Plant Evolutions - Tier IIGroup 1 (RO) w Ir

/APE # I Name I Safety Function K

, K I 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 I I:

295003 Partial or Complete Loss of AC 1 6

~

95004 Partial or Total Loss of DC Pwr I 6 I I 1 1 I

1 ISystems necessary to assure safe plant shutdown 1

295005 Main Turbine Generator Trip I 3 Turbine valve position I I lil Knowledgeof system purpose andlor function.

I I I z

0 295016 Control Room Abandonment I 7 IRemote shuldown panel: Plant-Specific 1

0 295018 Partial or Total Loss of CCW I 8 I

295019 Partial or Total Loss of Inst. Air I 8 II 1 O l I I I Backup air system supply: Plant-Specific 3.3 I 1 295021 Loss of Shutdown Cooling I 4 kl I IContainmenV d w e l l temperature 295023 Refueling Acc Cooling Mode I 8

- _ I-

,. -J I 295024 High Drywell Pressure I 5 04.~ Ability to recognizeabnormal indications for system operating parameters which are entry-level conditions for emergencyand abnormal operating procedures.

95025 High Reactor Pressure 13 I I I /Pressure effects on reactor water level 3.5 295026 Suppression Pool High Water I I I ISuppression chamber pressure: Mark-l&ll 3.2 1 295027 High Containment Temperature I5 Suppressed 0 It I I

1 I 0 0 1k95028 High Drywell Temperature 1 5 I I 2 5 RPV flooding: ADS 3.5;3.7 2 295030 Low Suppression Pool Wtr Lvl I 5 1 7I I (ECCS systems (NPSH considerations): Plankspecific 3.6 1 295031 Reactor Low Water Level 1 2 Reactor power 4 1 I I I I 95037 SCRAM Condition Present and Power 01.3 Ability to recognize indicationsb r system operating parameters b o w APRM Downscale or Unknown / 1 which are entry-levelcondilions for technical specifications. 3.4 1 3

295038 High Off-site Release Rate I 9 I I I (Meteorologicaleffects on off-sile release 2.8 1 lfsOO000 Plant Fire On Site I 8 Breakers. relays. and disconnects 2.5 1 I

-\ KIA Category Totals: 2 5 3 4 3 3 Group Point Total:

NUREG-1 021, Draft Revision 9 18 of 34 RC Outline 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 Outline Submittal COPY

t ~ ~~ i 1(ES-401 BWR Examination Outline Form ES-401-41 1 ElAPE # I Name I Safety Function 11203000 RHRILPCI: Injection 1 p O Shutdown Cooling Mode 206000 HPCl 207000 Isolation (Emergency)

Condenser

~~

209001 LPCS

+--

209002 HPCS 21 1000 SLC 212000 RPS 215003 IRM 112~5004Source Range Monitor

(~15005 APRM I LPRM 217000 RClC

" - 7 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution

~ ~~

262002 UPS (ACIDC) 263000 DC Electrical Distribution 264000 EDGs 1I300000 Instrument Air 400000 Component Cooling Water K/A Category Totals:

NUREG-I 021, Draft Revision 9 20 of 34 4RC Outline Submittal Copy

21 of 34 NUREG-1021, Draft Revision 9 NRC Outline Submittal COPY

ES-401 BWR Examination Outline Form ES-401.

Emerger and Abnormal Plant Evolutions - Tier 1IGrouo 1 (SRO)

E/APE # I Name I Safety Function I 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 I 295003 Partial or Complete Loss of AC I 6

~~~ ~~ ~

I 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip I 3 0

295006 SCRAM I 1 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 NUREG-1021, Draft Revision 9 18 of 34 URC Outline Submittal Copy

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 IRC O u t l i n e Submittal Copy

I,

/Po' BWR Examination Outline Form ES-40' I-----

Plant Systems - Tier 2/Group 1 (SRO)

CSJ --- ElAPE # f Name f Safety Function

- I 203000 RHRILPCI: Injection

/PO5000 Shutdown Cooling Mode I211000 SLC I

NUREG-1021, Draft Revision 9 20 of 34 JRC o u t l i n e s u b r n ~ t t a ic o p y

JRC Outline S u b m i t t a l Copy 3C Out I i ne S u b m i t t a I Copy Facility: Dresden Scenario No: ILT-N-1 Op-Test No: ILT 03-1 Examiners: Operators:

Event Malfunction Event Event No. Number Type* Description 1 None C SRo Vacuum breaker stuck approximately 20% open.

NSO

? RODLOGDI C SRO Control Rod Begins to drift in.

NSO 3 RDPPATRP C SRO 2A CRD Pump is making a grinding noise, must swap.

NSO 1 NIASPOT I SRO APRM 5 Fails Upscale. Bypass and Reset Half Scram.

1 121 Small Leak in Drywell.

2B CRD pump trips on low suction pressure and j

RDPPBTRP M Accumulator alarms begin to come in.

I RODST Several control rods remain withdrawn. The leak in 122 drywell gets worse.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor RC Outline Submittal Copy

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 Iat -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_APRMand Reset the half scram.

-8. -.- 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.

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 Co 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 Executes DOA 0300-05, Inoperable or Failed CRDs.

0 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 CRD pump trip if NSO does not swap pumps in a timely manner.

Success Path:

e NSO swaps running CRD pumps.

L - Event 4 - APRM 5 Fails Upscale

-7 APRM Channel 5 fails upscale.

Malfunctions Required: 1 APRM Channel 5 Fails Upscale Success Path:

e Bypass APRM Channel 5 o Performs DOP 0500-07, Manual Half Scram Reset Event 5 - Slow Leak A small steam leak upstream of the restrictors occurs.

Malfunctions required: 1 Small steam leak before restrictors.

Success path:

Performs DOA 0040-01, Slow Leak NRC o u t ~ n e subrnittai COPY

- ~ __I

<*/ d a s

  • u , ~ w

&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

e Scram, perform DGP 2-3 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 -

NRC O u t 1 ine S u b m \ t t a l copy

- E .+

Facility: Dresden Scenario No: ILT-N-2 Op-Test No: ILT 03-1 Examiners: Operators:

Iniitial Conditions: Rx Power - 15%, 2B Stator Cooling Pump OOS, IRM 16 00s.

Turnover: Continue with startup per DGP 1-1.

Event Description NSO 1 None R SRO Raise power with rods NSO Control rod double notches while withdrawing control 2 DORC13DO C SRO rods ANSO 3 SER1222 s SRO LPCl system low pressure alarm 4 RODK08AT C SRo Accumulator alarm due to low pressure NSO 5 RLLMLS 1 SRO FWLC setpoint drifts high RRMASLI F 5 Recirc pump seal failure RRMASLZF AI!

RDHLDEGA 7 All rods do not go in RDHLVFPA

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Outline Submittal COPY

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

--- .... i - - _.__== declare the acc-umulator INOP.

L,<+. 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.

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 Outline Submittal Copy

. . . . . ~ .. .,_ . . ~ ~ . . .. .,..

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 Outline Submittal COPY

.-- - .-___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.

Suction valve fails to close.

Success Path:

0 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 Outline Submittal Copy

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