ML081720153

Examination Outline Submittal and Comments for the Dresden Initial Examination - March 2008

ML081720153
Person / Time
Site:	Dresden
Issue date:	03/03/2008
From:	Mcneil D NRC/RGN-III/DRS/OLB
To:	Exelon Generation Co
Shared Package
ML081010290	List: ML081720153 ML081720174 ML081720186 ML081720211 ML081720217 ML081720224 ML081720228 ML081720231 ML081720234 ML081780151
References
50-237/08-301, 50-249/08-301
Download: ML081720153 (27)

Text

EXAMINATION OUTLINE SUBMITTAL AND COMMENTS FOR THE DRESDEN INITIAL EXAMINATION - MARCH 2008

Exelon Generation Company, LLC www.exelonrorp.com Dresden Nuclear Power Station 6500 North Dresden Road Nuclear Morris. it 60450-976s October 17,2007 SVPLTR 07-0048 Regional Administrator, Region Ill U. S. Nuclear Regulatory Commission 2443 Warrenville Road Lisle, IL 60532-4352 Dresden Nuclear Power Station, Units 2 and 3 Renewed 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 weeks of March 3, 2008 through March 14, 2008.

This submittal includes all appropriate 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 Mr. Jim Ellis, Regulatory Assurance Manager, at 815-416-2800. For questions concerning examination outlines, please contact Mr. Frank Ferrero at 815-416-2620.

Respectfully, Danny Bost Site Vice President Dresden Nuclear Power Station

Enclosures:

(Hand delivered to Chief Examiner Region 111)

Examination Security Agreements (Form ES-201-3)

Administrative Topics Outline (Form ES-301-1)

Control Room/ln-Plant Systems Outline (Form ES-301-2)

BWR Examination Outline LForms

~~~ -~ES-401-1)

~~~ ~~~~

Generic Knowledge and Abilities Outline (Tier 3) (Form ES-401-3)

Scenario Outlines (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 enclosures)

Chief, NRC Operator Licensing Branch NRC Senior Resident Inspector - Dresden Nuclear Power Station

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility Dresden Date of Examination: 3/3 /o 8 Item Task Description

- 1 - 1 - I

1. a. Verify that the outline(s) fit@) the appropriate model, in accordance with ES-401 ti-

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I T

0 Assess whelher me OJtline was Syslematica y and random y prepared In accoraance ulth Sect.on D 1 of ES-401 and whetner all K A categor es are appropriately Samp ed T-&z rc b+.

T c Assess whether me OJtline over-emphasizes any systems evo JtiOnS or gener c lopcs 3-E N d Assess wether me fustit cations for dese ecled 0: re,ected K A stalements are appropriale a Usmg Form ES-301.5 verify that the propose0 scenario sets cover me reqdired n-mber

2. of normal evolLt ons, nstrdment and component fad,res. lecnnica specit cations.

and ma,or trans ents S

I b. Assess whether there are enough scenario sets (and spares) to test the projected number M and mix of applicants in accordance with the expected crew composition and rotation schedule U without compromising exam integrity and ensure that each applicant can be tested using L at least one new or significantly modified scenario, that no scenarios are duplicated A from the applicants'audit test(s). and scenarios will not be repeated on subsequent days.

T 0

R 3.

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15) the nLmber 01 alternate patn. low-power emergency. and RCA tas6s meet the cr terla on tne form 0-Verity thal !he admin strat ve OJlllne meets the cr ter a specif ea on Form ES-301-1 b

,1,I the i a . ~ ~~ ~~ ~~ ~ ~ ~ ~~~~~~~.~~

~ .OISlribvted ammo lhe tooics as soec t ea on me form s are

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/Ab (2) at east one task s new or signif canny modif eo 13, no more man one task IS repealed from tne as1 two NRC I cens ng examinations c Determ ne f there are enouah dinerent outlines to test tne pro ecled number ana m x I s-I. .//I1 hn 4.

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a. Author - /c-Date 03

b. Facility Reviewer r) 0 c. NRC Chief Examiner (#)

d. NRC Supewisor NOTE: # Independent NRC Reviewer initial items in Column "c"; chief examiner concurrence required.

ES-201, Page 25 of 27

ES-201 Examination Security Agreement F o ES-201-3

~

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 3hheh4t !&  ?

date of my signature. I agree that I will not knowinglydivulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct. evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and I authorized by the NRC (e.g.. acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical securily measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellationof the examinations and/or an enforcementaction against me or the facility licensee. I will immediatelyreport to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any informationconcerning the NRC licensingexaminations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, Idid not instruct, evaluate, or provide performancefeedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBILIW SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE 1.-

2. da1. 301J-I mr& rO c b t 3 2 A d klz.. H&P/

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3. J O ~ - P - - l L - ,

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ES-201, P j26 Of 27 i

ES-301 Administrative Topics Outline Form ES-301-1

acility: Dresden Date of Examination: 3/3/08 ixamination Level: RO SRO [7 Operating Test Number: 2008-301 Administrative Topic Type Describe activity to be performed (See Note) Code' Verify Off-Site Power Sources Available Conduct of Operations Generic.2.1.31 Verify Acceptance Criteria met for the Acoustic Monitor Conduct of Operations Based on Test Results Generic2 1.25 Verify Reversal of Diesel Generator Cooling Water Flow Equipment Control N, S Generic.2.2.12 CCSW Activity Calculation Radiation Control D, P, S Generic.2.3.11 Emergency Plan rlOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (21)

(P)revious 2 exams (5 1; randomly selected)

~~~ ~~ ~

ES 301,Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1

acility: Dresden Date of Examination: 3/3/08 ixamination Level: RO 0 SRO Operating Test Number: 2008-301 Administrative Topic TYPe Describe activity to be performed (See Note) Code' Review Oft-Site Power Sources Available Paperwork Conduct of Operations Generic2 1.31 Reportability Determination Conduct of Operations Generic.2.1.1 Verify SBLC Tank Heater Surveillance Equipment Control Generic.2.2.12 CCSW Activity Calculation Radiation Control Generic.2.3.11 Determine Emergency Classification Emergency Plan N, S Generic.2.4.38 UOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

' Type Codes 8 Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank 1)

(P)revious 2 exams (51; randomly selected)

ES 301,Page 22 of 27

ES-301 Control Roomfin-Plant Systems Outline Form ES-301-2 Facility: Dresden Date of Examination: 3/3/06 Exam Level: RO [XI SRO-I 0 SRO-U 0 Operating Test Number: 2008-301 Control Room Systems" (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System IJPM Title Safety Type Code' Function

a. Injection of SBLC System (211000.A4.08) (A,D,P.SI 1

b. Start and Secure a Reactor Feed Pump (259001.A4.02) 1 A,N.S I 2

c. Perform an Emergency Depressurization(218000.A4.01) I A,D,S 1 3

d. Shutdown The Isolation Condenser (207000.A4.05) D, S 4

e. Verify Spurious Group 3 Isolation (223002.A4.01) A, D, L, S 5

f. Crosstie Bus 23-1 and Bus 33-1 (262001.A4.01) N, S 6

g. Drive TIP Detectors to Isolation Position (215001.A4.03) (A,D,P,SI 7

h. Start SBGT System (261000.A4.02) 1 D,L,S I 9

i. Locally Pull ARI Fuses to Reset ATWSIARI Circuit (295037.EA1.03) D, E 1

1. Manual Fill of Unit 2 EDG Day Tank (Gsneric.2.1.30) D. R 6

k. Valve in Control Room Emergency Breathing Air Supply (600000.A2.10) D 8 overlap those tested in the control room.

"Type Codes Criteria for RO ISRO-I I SRO-U

~ ~~ ~ ~ ~

(A)lternate path 4-6 I 4-6 I 2-3 (C)ontrolroom (D)irect from bank -

c 9 1 58 1 5 4 (E)mergencyor abnormal in-plant ,11 21 1 2 1 (L)ow-PowerI Shutdown -

> l I >1 / > 1 (N)ew or (M)odified from bank including 1(A) -

>2/ 22 1 2 1 (P)revious2 exams -

c 3 15 3 I 5 2 (randomly selected)

[R)CA -

> 1 1 >1 I >1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Roodn-Plant Systems Outline Form ES-301-2 Facility: Dresden Date of Examination: 3/3/08 Exam Level: RO [7 SRO-I SRO-U 0 Operating Test Number: 2008-301 Control Room Systems" (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Safety Type Code' Function

a. Injection of SBLC System (211000.A4.08) A, D, P , S 1

b. Start and Secure a Reactor Feed Pump (259001.A4.02) 1 A.N,S 1 2 C.

d. Shutdown The Isolation Condenser (207000.A4.05) D, S 4

e. Verify Spurious Group 3 Isolation (223002.A4.01) A, D, L, S 5 I. Crosstie Bus 23-1 and Bus 33-1 (262001.A4.01)

g. Drive TIP Detectors to Isolation Position (215001.A4.03) (A,D,P,Sl 7

h. Start SBGT System (261000.A4.02) I D,L,S 1 9 In-Plant Systems" (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Locally Pull ARI Fuses to Reset ATWS/ARI Circuit (295037.EA1.03) D, E 1

i. Manual Fill of Unit 2 EDG Day Tank (Generic.2.1.30) D, R 6

k. Valve in Control Room Emergency Breathing Air Supply (600000.A2.10) D 8

@ All RO and SRO-I control room (and in-plant)systems must be different and sewe different safety functions: all 5 SRO-Usystems must serve different safety functions; in-plant systems and functions may overlap those tested in the control rwrn

'Type Codes Criteria for RO ISRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank <91 <a 1 5 4 (E)mergencyor abnormal in-plant -

> I / >I/ > I (L)ow-Power IShutdown -

> 1 1 >1 1 2 1 (N)ew or (M)odified from bank including 1(A) -

>2/ 22 121 (P)revious 2 exams -< 3 15 3 I5 2 (randomly selected)

(R)CA -

> 1 / >1 1 2 1 (S)imulator ES-301, Page 23 of 27

tS-301 Transient and tvent Checklist Form ES-301-5 resden Date of Exam: 3/3/08 Operating Test Number: 2008-301 M

L I I N C I A M N U T

MU f

RO SRO-l 0

SRO-1 0

0 E?

SRO-I 1 1 1 Edd)

SRO-1 4

2 4

2 2

1 0

0 2 2 RO 1 ! 1 ! 0 0

L.

F\

8 SRO-t 0

RO 0

SRO-I 0

SRO-1

-lnstru 0 2 2

1. Check the a licant level and enter the operating test number and Form ES-D-I event numbers lor each event ty e f8 are not ap licable for RO applicants. ROs must serve ,n both the -at.the-controls (ATC) and ,baknie-of-plant (B8P) positions Instant SROs must do one Fenar.0, including at. least two instrument or component (IC) malfunctions and one major transient. in the ATC position

2. Reactivit manipulations may be conducted under normal or controlledabnormal conditions (refer to Section 8.5.d) bul must be signlficanl per Section C.2.a 01 Appendix D. *) Reactivity and normal evolutions may be replaced with additional instrument or component mahnctions on a 1-for-I basis.

3. Whenever practical. both instrument and component malfunctions should be included; only those that require verifiable actions that provide tnsight to the applicants competence count toward the minmlrm requ#rementsspecified for the applicants license level in the right-nand collrmns.

ES-301, Page 26 of 27

ES-401 BWR Examination Outline FORM ES-401-1 Plant 2 1 1 1 1 1 2 1 1 1 1 1 12 0 1 2 3 Systems Tier Totals 3 3 3 4 3 5 3 3 4 3 4 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 2 2 3 2 2 1 2 ES-401. Page 16 of 33

ES-401 2 Form ES-401-1 Form ES-401 95003 Partial or Complete Loss of AC 1 6 95025 High Reactor Pressure 1 3 95028 High Drywell Temperature / 5 Reactor water level mea~urement 95031 Reactor Low Water Level I2 ES-401, Page 17 of 33

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ES-401 3 FoKES-401-1 BWR Examination Outline Fom ES-401 ES-401,Page 18 of 33

ES-401 4 Form ES-401-1

ES-401-1 5 Form ES-401-1 IES-401 BWR Examination Outline Form E S X L.

86000 Fire Pratectbn ES-401, Page 20 of 33

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401 95030 Low Suppression Pool Wtr Lvl / 5 95038 High Off-site Release Rate / 9 ES-401,Page 17 of 33

ES-401 3 Form ES-401-1 ES.401 BWR Examination Outline Form ES-401.

Emergency and Abnormal Plant Evolutions. Tier llGroup 7 (SRO)

K K K A  !& ,;,,,:

WAPE # I Name I Safety Function , ~ .:,'Yfi8-.-Q..' WA Topk(s) IR P 95002 Loss of Main Condenser Vac I 3 5007 High Reactor Pressure 1 3 95008 High Reactor Water Level 17 95010 High Drywell Pressure 15 95011 High Containment Temp 15 5012 High Drywell Temperature 15 I I o 95013 High Suppression Pool Temp. 15 95014 inadvertent Reactivity Addition / 1 95015 Incomplete SCRAM I 1 95017 High Off-site Release Rate I 9 5020 inadvertentCont. isolation 1 5 8 7 95022 Loss of CRD Pumps I 1 95029 High Suppression Pool Wtr Lvl 1 5 95032 High Secondary Containment Area 95033High Secondary Containment Area adiation Levels I 9 795034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High Differential Pressure 15 795036 Secondary Containment High SumplArea Water Level I5 t t I l t l L l 0

0 0

00000 High CTMT Hydrogen Conc. 15 A Category Totals:

ES-401, Page 18 of 33

ES-401 4 Form ES-401-1 II IIIII OOooO Instrument Air

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ES-401, Page 19 of 33

ES-401 5 Form ES-401-1 ES-401 EWR Examination Outline Form ES-401 I I I I I I I I I I I I I I "

01005 RClS I 0 02001 Recimlamn 02002 ReCirwlatOn Flow Control 04000 RWCU 14000 RPlS

)b15001 Traversing In-core Probe Ib15002 RBM I l l 39001 Main and Reheat Steam I I 11 I I 1 0 39003 MSlV Leakage Control 1 1 1 I 0 45000 Main Tu*ine Gen. I AUX.

56000 Reactor Condsn~ate 59001 Reactor Feedwater 68000 uadwasta 72000 Radialon Monlfoting I I I I I I I I:a I I I I I o 88000 Phot veotilamo 90001 Secondary CTMT L.

ES-401, Page 20 of 33

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 acility Name:Dresden Date of Exam:3/3/08 Category WA# Topic RO I SRO-Only I R I # I I R I #

ES-401, Page 26 of 33

ES-401 Record of Rejected WAS Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected W A None rejectedfrom outline generation.

I I I 1

I II II I t I t I I I ES-401,Page 27 of 33

Appendix D Scenario Outline Form ES-D-1

=acility: Dresden Scenario No: ILT-N-1 Op-Test No: 2008-301

xaminers: Operators:

nitial Conditions: Rx Power 2%.

rUrnOVer: Continue with Unit startup per DGP 1-1 Event Malf.

+

Raise power using Control Rods RDFAILG2 c [ :2g [ RPlS Failure For Rod G-02 '

C :1:y I Instrument Air Compressor Trip / Start Standby 4 I Nlll2POT

' I NSo SRO I IRM channel fails upscale I ADS3BSD ADS3BBN C 1 SRO 1 Target Rock Bellows Failure C 1 yz: 1 Core Spray System Develops Low Keep Fill Pressure I RODST 122

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec call

Appendix D Scenario Outline Form ES-D-1 P

Eacility: Dresden Scenario No: ILT-N-2 Op-Test No: 2008-301

-zxaminers: Operators:

nitial Conditions: Rx Power 75%.

rurnover: Reduce power with Recirc flow per DGP 3-1, to accommodate TSO request.

Reduce power with Recirc flow CRD Flow Controller Fails Low SER1589 ANSO U2 Emergency Diesel Genyrator Inoperable due to 3 SER0710 T18 SRO cooling water pump failure HPlNlT 1 II ANSO SRO Spurious HPCI Initiation 5 1 RDPPATRP 1 1 C NSO SRO CRD Pump Trip Spurious ERV Opening 7 I H33/H34 I M I TEAM I Loss of Feedwater Causing a Manual Scram Loss of level indication /Flooding

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)ech Spec call

Appendix D Scenario Outline Form ES-D-1 Examiners: Operators:

I Initial Conditions: Rx Power 90%

Turnover: Swap RBCCW Pumps, maintain loa ,181 TSO I action, Event

!EL ANSO Swap RBCCW pumps SRO NSO SRO Control Rod Begins to drift in

-- ANSO SRO Drywell to Torus differential pressure controller failure NSO Master Recirc Flow Controller fails downscale SRO ANSO 2A circ water pump trip SRO Loss of Main Condenser Vacuum Causing a Manual TEAM Scram TEAM Lowering Torus level from ECCS suction line break

__=

OPERATING TEST JPMS ADMIN

1. Verify Acceptance Criteria Met for the Acoustic Monitor Based on Test Results The 2007 exam outline had a JPM by the same title. Other than a change in the WA, what other modifications will be made to make this JPM different?

Modified the components that must be identified with out of specification readings.

2. Verify Reversal of Emergency Diesel Generator Cooling Water Flow The 2007 exam outline had a JPM by the same title, but the 2008 exam list this as a NEW JPM.

The same WA has been used on the last three exams for Admin JPMS.

This doesnt appear to be a random selection.

WA (Generic 2.2.12)remained the same but JPM was replaced with Verify HPCl Discharge Line Temperature Monitoring Calculation.

3. CCSW Activity Calculation A JPM by the same title has appeared on the 2006 and 2004 exams.

This doesnt appear to be a random selection.

No changes were made.

4. Determine Emergency Classification This same JPM, with minor variations, has appeared on the last three exams.

JPM was changed to include completion of NARS form

CONTROL ROOMllN-PLANT SYSTEMS

1. "Start SBGT" The last three exams have involved operation of operation of SBGT.

Suggest finding a different system for this safety function.

JPM was replaced with "Align Charcoal Adsorber Filters in Parallel Mode of Operation [Off Gas System]

2. "Valve in Control Room Emergency Breathing Air" Used in the 2006 exam under a different WA and Safety Function There doesn't appear to be a direct tie between the WA and the JPM WA was changed to reflect applicability to Safety Function.

3. "Manual Fill of the Unit 2 EDG Day Tank A generic WA is listed for this JPM. Isn't there a system specific WA?

JPM was replaced with "Manual Fill of the Unit 3 EDG Day Tank, was written with alternate path and included a system specific WA.

SIMULATOR SCNARIOS SCENARIO 1

1. RPlS malfunction has been used on last two exams. Recommend replacing with some other rod control malfunction (e.g., rod withdrawal beyond banklprogram position.

Evenffmalfunction was replaced with "Control Rod Drive Overtravel"

2. Target Rock Bellows failure used on last exam. There are minimal response actions for the BOP operator.

Evenffmalfunction were eliminated.

SCENARIO 2 (renumbered as scenario 3)

1. Spurious HPCl Initiation was used on 2006 exam. Recommend replacing HPCl failure during performance of a pump surveillance (e.g., pump failure to generate enough flow, HPCl line break due to water hammer, or min flow fail fails open etc)

Evenffmalfunction replaced with HPCl isolation failure.

2. What is the cause for failure of level indicators? Is there a reasonable common cause?

Evenffmalfunctionsmodified by notification (initial condition) of possible circuit card manufacturing defect.

3. Spurious ERV opening was also used in 2006 exam.

Evenffmalfunction eliminated.

SCENARIO 3 (renumbered as scenario 2) 1, Loss of Circ WaterlLoss of Vacuum has been used on last two exams.

Recommend initiating loss of vacuum in another manner (e.g., tube plugging.

screen clogging, tube failures)

EvenWmalfunction changed to Cribhouse intake clogging

2. Might be able to tie in a reactivity manipulation (controlled downpower) with degrading plant conditions.

No change made, but will evaluate during validation.

WRITTEN EXAM No Comments