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 6500 North Dresden Road Morris. it 60450-976s Dresden Nuclear Power Station Nuclear 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 81 5-41 6-2800. 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

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ES-401-1)

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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

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

are OISlribvted ammo lhe tooics as soec t ea on me form b

Facility Dresden Date of Examination: 3/3 /o 8 0 -

/ A b Item -

1.

W R

I T

T E

N -

2.

S I

M U

L A

T 0

R -

3.

W

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4.

G E

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R A

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Task Description 1

1 I

ti-

a.

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

. ? ~

rc b+.

T-&z 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 Assess whether me OJtline over-emphasizes any systems evo JtiOnS or gener c lopcs Assess wether me fustit cations for dese ecled 0: re,ected K A stalements are appropriale Usmg Form ES-301.5 verify that the propose0 scenario sets cover me reqdired n-mber of normal evolLt ons, nstrdment and component fad,res.

lecnnica specit cations.

and ma,or trans ents 3-c d

a

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.

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I (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 Determ ne f there are enouah dinerent outlines to test tne pro ecled number ana m x c

I s-I..//I1 hn Date

a. Author

- /c-0 3

b. Facility Reviewer r) 0 - 1 5 -

c. NRC Chief Examiner (#)

d. NRC Supewisor NOTE:

1. 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

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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 3hh 4 ?&!the date of my signature. I agree that I will not knowingly divulge 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 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 cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report 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 information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

I PRINTED NAME JOB TITLE I RESPONSIBILIW SIGNATURE (1)

DATE SIGNATURE (2)

DATE NOTE 1.-

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4 4.-RkpFl/

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9

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

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3.

J O ~ - P - - l L -,

'OT('5 ES-201, P j26 Of 27 i

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

acility: Dresden ixamination Level: RO SRO [7 Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code' N, S D, P, S Date of Examination: 3/3/08 Operating Test Number: 2008-301 Describe activity to be performed Verify Off-Site Power Sources Available Generic.2.1.31 Verify Acceptance Criteria met for the Acoustic Monitor Based on Test Results Generic2 1.25 Verify Reversal of Diesel Generator Cooling Water Flow Generic.2.2.12 CCSW Activity Calculation Generic.2.3.11 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 (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)

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ES 301, Page 22 of 27

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

acility: Dresden ixamination Level: RO 0 SRO Date of Examination: 3/3/08 Operating Test Number: 2008-301 Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TYPe Code' N, S Describe activity to be performed Review Oft-Site Power Sources Available Paperwork Generic2 1.31 Reportability Determination Generic.2.1.1 Verify SBLC Tank Heater Surveillance Generic.2.2.12 CCSW Activity Calculation Generic.2.3.11 Determine Emergency Classification 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 (5 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (P)revious 2 exams (5 1; randomly selected)

1)

ES 301, Page 22 of 27

ES-301 Control Roomfin-Plant Systems Outline Form ES-301-2 System I JPM Title Facility: Dresden Exam Level: RO [XI SRO-I 0 SRO-U 0 Safety Type Code' Function Date of Examination: 3/3/06 Operating Test Number: 2008-301

d. Shutdown The Isolation Condenser (207000.A4.05)

e. Verify Spurious Group 3 Isolation (223002.A4.01)

f. Crosstie Bus 23-1 and Bus 33-1 (262001.A4.01)

Control Room Systems" (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

D, S 4

A, D, L, S 5

N, S 6

i. Locally Pull ARI Fuses to Reset ATWSIARI Circuit (295037.EA1.03)

a. Injection of SBLC System (21 1000.A4.08)

( A, D, P. S I 1

D, E 1

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

2

1.

Manual Fill of Unit 2 EDG Day Tank (Gsneric.2.1.30)

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

c. Perform an Emergency Depressurization (218000.A4.01)

I A,D,S 1

3 D. R 6

D 8

g. Drive TIP Detectors to Isolation Position (215001.A4.03)

( A, D, P, S I 7

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

9 overlap those tested in the control room.

"Type Codes

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(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams

[R)CA (S)imulator Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2-3 c 9 1 58 1 5 4

,11 2 1 1 2 1

> l I >1 / > 1

> 2 / 2 2 1 2 1

> 1 1 >1 I >1 c 3 15 3 I 5 2 (randomly selected)

ES-301, Page 23 of 27

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

Safety Type Code' Function A, D, P, S 1

System I JPM Title

a. Injection of SBLC System (211000.A4.08)

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, S l 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

8

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

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

'Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2-3

< 9 1 < a 1 5 4

> I / >I />I

> 1 1 >1 1 2 1

> 2 / 2 2 1 2 1

> 1 / >1 1 2 1

< 3 15 3 I 5 2 (randomly selected)

ES-301, Page 23 of 27

tS-301 Transient and tvent Checklist Form ES-301-5 L.

L I C

A N

T RO SRO-l SRO-1 0

0 E?

Edd)

SRO-I SRO-1 0

0 RO F\\

SRO-t 0

0 0

RO SRO-I SRO lnstru resden Date of Exam: 3/3/08 Operating Test Number: 2008-301 M

I N I M

U M U f 0

1 1

1 4

4 2

2 2

1 0

2 2

1 1

0 8

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 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.

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#rements specified for the applicants license level in the right-nand collrmns.

2.

3.

ES-301, Page 26 of 27

ES-401 BWR Examination Outline FORM ES-401-1 Plant Systems 2

1 1

1 1

1 2

1 1

1 1

1 12 0

1 2

3 Tier Totals 3 3 3 4 3 5 3 3 4 3 4 38 4

4 8

ES-401. Page 16 of 33 1

3

3. Generic Knowledge and Abilities Categories 2

3 4

1 2

3 4

2 2

3 2

2 1

2 10 7

ES-401 2

Form ES-401-1 Form ES-401 95003 Partial or Complete Loss of AC 16 95025 High Reactor Pressure 13 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

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.:,'Yfi8-.-Q..'

WA Topk(s)

IR P

95002 Loss of Main Condenser Vac I 3 5007 High Reactor Pressure 13 95008 High Reactor Water Level 17 95010 High Drywell Pressure 15 9501 1 High Containment Temp 15 5012 High Drywell Temperature 15 I

I o 95013 High Suppression Pool Temp. 15 9501 4 inadvertent Reactivity Addition / 1 95015 Incomplete SCRAM I 1 95017 High Off-site Release Rate I 9 5020 inadvertent Cont. isolation 1 5 8 7 95022 Loss of CRD Pumps I 1 95029 High Suppression Pool Wtr Lvl 15 95032 High Secondary Containment Area 95033 High 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 I 5

I l

t l

L l

t t 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 I I I I I I I 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

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I 01005 RClS 0

I 02001 Recimlamn 02002 ReCirwlatOn Flow Control 04000 RWCU 14000 RPlS Ib15002 RBM I l l

)b15001 Traversing In-core Probe 39001 Main and Reheat Steam 39003 MSlV Leakage Control 1 1 1 I I 11 I I 1 0

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 W A #

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 Group Randomly Selected W A Reason for Rejection None rejected from outline generation.

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ES-401, Page 27 of 33

Scenario Outline Form ES-D-1 Appendix D

=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.

RDFAILG2 +

4 I Nlll2POT ADS3BSD I ADS3BBN I

RODST 122 Raise power using Control Rods c [ :2g

[ RPlS Failure For Rod G-02 '

C 1 y::

I Instrument Air Compressor Trip / Start Standby NSo IRM channel fails upscale

' I SRO I C 1 SRO 1 Target Rock Bellows Failure C 1 yz: 1 Core Spray System Develops Low Keep Fill Pressure

• (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 3

SER0710 T18 ANSO SRO U2 Emergency Diesel Genyrator Inoperable due to cooling water pump failure ANSO HPlNlT 1 I I SRO NSO 5

1 RDPPATRP 1 C 1 SRO Spurious HPCI Initiation 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:

Initial Conditions: Rx Power - 90%

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

!EL ANSO SRO NSO SRO ANSO SRO NSO SRO -

ANSO SRO TEAM TEAM

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action, Event Swap RBCCW pumps Control Rod Begins to drift in Drywell to Torus differential pressure controller failure Master Recirc Flow Controller fails downscale 2A circ water pump trip Loss of Main Condenser Vacuum Causing a Manual Scram 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.

A JPM by the same title has appeared on the 2006 and 2004 exams.

This doesnt appear to be a random selection.

3. CCSW Activity Calculation 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" 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.

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 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?

Evenffmalfunctions modified 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