Text

Outline Submittal for the Point Beach Initial Examination - September 2003
	ML033030026
Person / Time
Site:	Point Beach
Issue date:	09/29/2003
From:	Short P; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
References
	50-266/03-301, 50-301/03-301
	Download: ML033030026 (35)
	v • d • e

OUTLINE SUBMITTAL FOR THE POINT BEACH INITIAL EXAMINATION - SEPT 2083

ES-201 Examination Preparation Checklist Form ES-201-1 1 Facility: Point Beach Date of Examination: 09/29 - 10/03/03 11 Examinations Developed by: [ Facility] / NRC (circle one) 1 Target Date* I Task Description/ Reference

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Chief Examiners Initials

-180 1. Examination administration date confirmed (C.l .a; C.2.a & b) *4J zii

-120 2. NRC examiners and facility contact assigned (C.l .d; C.2.e) &J 43

-120 3. Facility contact briefed on security & other requirements (C.2.c) aut3 &??

-120 4. Corporate notification letter sent (C.2.d) 1 [-go] 1 [5. Reference material due (C.l .e; C.3.c)l 1I -75 1 Integrated examination outline(s) due (C.l .e

6. & f; C.3.d)

-70 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)

-45 8. Proposed examinations, supporting documentation, and reference materials due (C.l .e, f, g & h; C.3.d)

-30 9. Preliminary license applications due (C.l .I; C.2.g; ES-202) l -14

10. Final license applications due and assignment sheet prepared (C.l .I; C.2.g; ES-202)

11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

12. Examinations reviewed with facility licensee (C.l .j; C.2.f & h; C.3.g)

)I -7

13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

/I -7

14. Final applications reviewed; assignment sheet updated; waiver letters sent (C.2.g, ES-204)

15. Proctoring/writtenexam administration guidelines reviewed with

-7 facility licensee and authorization granted to give written exams (if applicable) (C.3.k)

16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

Target dates are keyed to the examination date identified in the corporate notification letter.

They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[ ] Applies only to examinations prepared by the NRC.

23 of 25 NUREG-1021, Draft Revision 9

NMC Committed to Nuclear Excellence Point Beach Nuclear Plant

/ Operated by Nuclear Management Company, LLC NRC 2003-0057 June 25,2003 Mr. Roger D. Lanksbury, Chief Operations Branch Division of Reactor Safety U. S. Nuclear Regulatory Commission Region Ill 801 Warrenville Road Lisle, IL 60532-4351

Dear Mr. Lanksbury:

POINT BEACH NUCLEAR PLANT INITIAL OPERATOR LICENSING EXAMINATION OUTLINES In response to your letter dated May 15, 2003, enclosed are the initial operator licensing examination outlines. As confirmed with your staff, the examinations are scheduled for the week of September 29, 2003. As noted in your letter dated June 9, 2003, which confirmed a telephone conversation on May 27, 2003, between Mr. Bielby of your staff and Mr. Sizemore, our Training Supervisor; the examination is being prepared based on the guidelines in Revision 9 of NUREG-I 021.

NUREG 1021 physical security requirements state that the enclosed examination materials shall be withheld from public disclosure until after the examination is complete.

Please contact Mr. Phil Short at 920/755-6125 if you have questions regarding the examination outlines or require additional information.

CWWkmd Enclosures 6590 Nuclear Road Two Rivers, Wisconsin 54241 Telephone: 920.755.2321

NRC 2003-0057 Page 2 bcc w/oe: C.Sizemore P.A. Short File

Initials Item Task DescriDtion a b* c#

1.

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a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

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b. Assess whether the outline was systematically and randomly prepared in accordance with R Section D.l of ES-401 and whether all WA categories are appropriately sampled. fl4d I

T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

T E

d. Assess whether the justifications for deselected or rejected WA statements are appropriate.

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a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal

2. evolutions, instrument failures, and major transients. p3B

b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of S applicants in accordance with the expected crew composition and rotation schedule without compromising I exam integrity; ensure each applicant can be tested using at least one new or significantly modified M scenario, that no scenarios are duplicated from the applicants audit test(s)*, and scenarios will not be reDeated on subseauent davs. p- %llL/

l 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.

W

/

T

a. Author

b. Facility /Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Supervisor Note:

Not applicable for NRC-developed examinations.

Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

NUREG 1021, Draft Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Point Beach Nuclear Plant Date of Examination: 9/29-10/3/03 Examination Level: RO Operating Test Number: 2003301 Administrative Topic Describe activity to be performed:

(see Note)

Conduct a Control Board Walk-down for Shift Turnover Conduct of Operations /

(identify ALL abnormal items using Turnover Checklist, similar to last Shift Turnover NRC exam, with varied items).

Conduct of Operations /

Plant Parameter Perform a Pressurizer Heater Input Test Calculation (new P M ) .

Verification Equipment Control /

Review a Tag Series for adequacy (similar to 2000 NRC Exam).

Tagging & Clearances I( Radiation Radiation Control /

Exposure I Perform a stay-time calculation (new JPM).

Limits NOTE: 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, NUREG- 1021, Draft Revision 9

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ES-301 Administrative Topics Outline Form ES-301-1 Facility: Point Beach Nuclear Plant Date of Examination: 9/29-10/3/03 Examination Level: SRO Operating Test Number: 2003301 Administrative Topic Describe activity to be performed:

Conduct a Control Board Walk-down for Shift Turnover Conduct of Operations /

(identify ALL abnormal items using Turnover Checklist, similar to last Shift Turnover NRC exam, with varied items).

Conduct of Operations /

Plant Parameter Perform a Pressurizer Heater Input Test Calculation (new JPM).

Verification Equipment Control /

Review a Tag Series for adequacy (similar to 2000 NRC Exam).

Tagging & Clearances Radiation Control /

Knowledge of Radiation Evaluate an Emergency Dose Extension (new JPM).

Exposure Limits Emergency Plan /

Emergency Action Make an Emergency Plan Classification (includes PARS, new JPM).

Levels and Classifications NOTE: 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.

NUREG- 1021,Draft Revision 9

ES-301 Control R o o m - P l a n t Systems Outline Form ES-301-2 Facility: Point Beach Nuclear Plant Date of Examination: 9/29-10/3/03 Exam Level : RO Operating Test No: 2003301 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

I I System / JPM Title Code* 1 Function Safety 1 a. Control Rod Drive System / Respond To Uncontrolled Rod Motion.

1 b. Chemical & Volume Control System / Manually Makeup To TheVCT.

(1 c. Emergency Core Cooling System / Fill An Accumulator Gas Space.

ir

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d. Reactor Coolant Pump System / Start A Reactor Coolant Pump (last NRC exam)

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e. Auxiliary Feedwater System / Raise Steam Generator Level 4

4 Using Auxiliary Feedwater N, s, L, A (secondary) 1 f. Containment spray system / Secure Containment Spray Nuclear Instrument To Service 11 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) I I

i. Pressurizer Level Control System / Locally Operate A Charging 2

I j . A. C. Electrical Distribution / Align Alternate AC Power To A Residual Heat Removal Pump.

~~~

6

/ Use The Spent Fuel Pool Cooling 8

System To Re-flood The RHR System Suction.

Type Codes: (D)irect from bank, (M)odified from bank, m e w , (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NUREG- 1021 Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Point Beach Nuclear Plant Date of Examination: 9129-10/3/03 Exam Level : SRO-I Operating Test No: 2003301 11 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Safety System I JPM Title Code* Function (1 a. Control Rod Drive System I Respond To Uncontrolled Rod Motion.

1 b. Chemical & Volume Control System I Manually Makeup To TheVCT.

1 c. Emergency Core Cooling System I Fill An Accumulator Gas Space.

1 d. Reactor Coolant Pump System I Start A Reactor Coolant Pump (last m c exam)

I e. Auxiliary Feedwater System I Raise Steam Generator Level Using Auxiliary Feedwater N, s, L, A 4

(secondary) l f. Containment Spray System I Secure Containment Spray 5 l g. Emergency Diesel Generators I Respond To An Emergency Diesel Generator Failure To Load 6

1 h. NIA NIA I NIA I

1I In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. Pressurizer Level Control System I Locally Operate A Charging pump 5fF I j. A. C. Electrical Distribution I Align Alternate AC Power To A Residual Heat Removal Pump.

I k. Spent Fuel Pool Cooling / Use The Spent Fuel Pool Cooling System To Re-flood The RHR System Suction.

Type Codes: (D)irect from bank, (M)odified from bank, m e w , (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

" R E G - 1021, Draft Revision 9

1 AppendixD Scenario Outline FormES-D-1 I I Facility: Point Beach Scenario No.: 1 OP-Test No.: 2003301 I Examiners: Operators:

I Initial Conditions: Unit 1 is at 100% Power. MOL, equilibrium xenon conditions. Unit 2 is at 100% Power.

Turnover: G-02 EDG is out of service for annual maintenance. It was taken 00s 2 days ago, and is expected to be returned to service in 3 days. G-01 EDG is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW 01-35A.

1P-2C Charging Pump is out of service due to a failed motor bearing. The failure occurred 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago and has been tagged out for repair.

1P-15A Safety Iniection Pump has just been tagged out (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago) due to high vibration that was identified during In-service Testing. The pump is not available.

Today is Sunday, present clock time is real time. A normal shift complement is available with exception of the 3'd SRO. An RP Tech is on-site along with two mechanics who are working on the diesel. A maintenance crew has iust been called in for 1P-15A.

1 The objective of the shift is to maintain stable plant conditions.

Event Malf. Event Event No. No. Type* Description 1 Service Water Pump Trip.

SRO I-RO 2 Controlling Pressurizer Pressure channel PT-43 1 fails high.

SRO I - Ro SRO I 1P-2A Charging Pump belt failure.

I 4 I I I - All I Turbine First Stage Pressure Transmitter PT-485 fails low.

5 M - All RCS Leak develops to SBLOCA, requiring reactor trip.

6 C - All Reactor trip breakers fail to open - (ATWS).

7 Safety Injection Pump 1P-15B fails to start.

SRO

Oormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG- 1021, Draft Revision 9

1 AppendixD Scenario Outline FormES-D-1 I Facility: Point Beach Scenario No.: 2 OP-Test No.: 2003301 Examiners: Operators:

Initial Conditions: Unit 1 is at 75% power. Power was reduced apvroximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ago at the request of the Power System Suvervisor. Xenon is building in slightly. Unit 2 is at 100% Power.

Turnover: G-02 EDG is out of service for annual maintenance. It was taken 00s 2 davs ago, and is expected to be returned to service in 3 davs. G-01 EDG is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.

1P-2C Charging Pump is out of service due to a failed motor bearing. The failure occurred 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago and has been tagged out for repair.

1P-15A Safety Iniection Pump has just been tamed out (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago) due to high vibration that was identified during scheduled In-service Testing. The pumv is not available.

Today is Sunday. present clock time is real time. A normal shift complement is available with excevtion of the 31d SRO. An RP Tech is on-site along with two mechanics who are working on the diesel. A maintenance crew has just been called in for 1P-15A.

The obiective of the shift is to maintain stable dant conditions until the Power System Supervisor requests power be returned to 100%.

Power reduction initiated due to tube leak.

8 1 1 M- ALL 1 Steam Leak develops on Steam Generator B 9 Steam Generator B Sample valve fails to isolate.

SRO (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 02 1, Draft Revision 9

ES-401 PWR Examination Outline Form ES-401-2 Facility: Point Beach Nuclear Plant Date of Exam: Sep 29,2003 Note: 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.l .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 WA 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) 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. 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 KIA 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 WA 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 KIA statements.

Page 1 of 13

i PWR Examination Outline ES-401 Form ES-401-2 Emergency a I Abnoi ;-Tier I/Group 1 (RO/SRO) - -

E/APE # / Name / Safety Function WA Topic(s) IR #

2.4.31 Knowledge of annunciators 000007 (BW/E02&EI0; CE/E02) Reactor 1 alarms and indications, and use of 3.3 Trip - Stabilization - Recovery / 1 the response instructions 008.AK3.03 Knowledge of the reasons for the following responses as they apply to the Pressurizer 000008 Pressurizer Vapor Space Vapor Space Accident (Relief Valve 4.1 Accident (Relief Valve Stuck Open) / 3 Stuck Open): Actions contained in EOP for PZR vapor space accident /

LOCA 009.EA2.34 Ability to determine or interpret the following as they apply to 000009 Small Break LOCA / 3 3.6 a small break LOCA: Conditions for throttling or stopping HPI Y

011.EK2.02 Knowledge of the 000011 Large Break LOCA I 3 interrelations between Large Break 2.6 LOCA and the following: Pumps 015.AK3.02 Knowledge of the reasons for the following responses as they apply to the Reactor Coolant 000015/17 RCP Malfunctions / 4 3.0 Pump Malfunctions (Loss of RC Flow): CCW lineup and flow oaths to RCP'oil coolers ' -

022.AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Reactor 000022 Loss of Rx Coolant Makeup / 2 Coolant Pump Makeup: Actions 3.5 contained in SOPS and EOPs for RCPs. loss of makeuo, loss of charging, and abnormal charging -

025.AK1.01 Knowledge of the operational implications of the following concepts as they apply to 000025 Loss of RHR System I 4 3.9 Loss of Residual Heat Removal System: Loss of RHRS during all modes of operation 026.AK3.02 Knowledae of the reasons for the following responses as they apply to the Loss of 000026 Loss of Component Cooling Component Cooling Water: The 3.6 8 Water / 8 automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 027.AK1.01 Knowledge of the operational implications of the 000027 Pressurizer Pressure Control following concepts as they apply to 3.1 9 System Malfunction I 3 Pressurizer Pressure Control Malfunctions: Definition of saturation temperature 000029 ATWS / 1 038.EA2.17 Abilitv to determine or 000038 Steam Gen. Tube Rupture I 3 interpret the folloihng as they apply to 3.8 10 a SGTR: RCP restart criteria 040.AA2.05 Ability to determine and 000040 (BW/E05; CE/EO5; W/E12) interpret the following as they apply to Steam Line Rupture - Excessive Heat 4.1 11 the Steam Line Rupture: When Transfer / 4 ESFAS systems may be secured -

Page 2 of 13

EIAPE # I Name I Safety Function

I WA Topic(s) 054.AA2.05 Ability to determine and interpret the following as they apply to 000054 (CEIEOG) Loss of Main the Loss of Main Feedwater (MFW): 3.5 12 Feedwater14 Status of MFW pumps, regulating and I stop valves 000055 Station Blackout I 6 056.AA1.31 Ability to operate andlor monitor the following as they apply to 000056 Loss of Off-site Power I 6 3.3 13 the Loss of Offsite Power: PZR heater group control switches 2.4.31 Knowledge of annunciators 000062 Loss of Nuclear Svc Water I 4 alarms and indications, and use of 3.3 14 the response instructions 065.AK3.03 Knowledge of the reasons for the following responses as they apply to the Loss of 000065 Loss of Instrument Air I 8 2.9 15 Instrument Air: Knowing effects on plant operation of isolating certain equipment from instrument air W/E04.EKI .3 Knowledge of the operational implications-of the following concepts as they apply to the (LOCA Outside Containment):

WIE04 LOCA Outside Containment I 3 X 3.5 16 Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Outside Containment)

W/EI 1.EKI .3 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant WIEI 1 Loss of Emergency Coolant X Recirculation): Annunciators and 3.6 17 Recirc. 1 4 conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recirculation)

WIE05.EA1.1 Ability to operate andlor monitor the following as they apply to the (Loss of Secondary Heat BWlE04; W/E05 Inadequate Heat Sink): Components, and functions of Transfer - Loss of Secondary Heat 4.1 18 control and safety systems, including Sink 14 instrumentation, signals, interlocks, failure modes, and automatic and manual features -

-I--

WA Category Totals: 14 ~

Group Point Total:

Page 3 of 13

PWR Examination Outline ES-401 Emeraencv and Abnormal Plant Evolutions -Tier I/Group 2 (RO/SRO)

" I I

Form ES-401-2 ElAPE#/ Name I Safety Function K 1

K 2

K 3

A 1

A 2

G WA Topic(s) I IR #

001.AKI .08 Knowledge of the operational implications of the 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod I1 Ix1 I I I1 1I following concepts as they apply to Continuous Rod Withdrawal: Control 19 interpret they following as they apply 000005 InoperablelStuck Control Rod I 1 X to the InoperablelStuck Control Rod: 3.5 20 Reauired actions if more than one rod is stuck or inoperable.

024.AK2.04 Knowledge of the 000024 Emergency Boration / 1 interrelations betweenthe Emergency I 2.6 21 000033 Loss of Intermediate Range NI / 7 II/llIx system and integrated plant procedures during all modes of plant 22 reasons for the following responses 000069 (WIE14) Loss of Containment as they apply to the Loss of X 3.8 23 Integrity / 5 Containment Integrity: Guidance contained in EOP for loss of 000074 (W/E06&E07) Inadequate Core 1 Cooling / 4 monitor the following as they apply to 000076 High Reactor Coolant Activity I 9 X 3.2 24 the High Reactor Coolant Activity:

Failed fuel-monitoring equipment I I I I I WIE02.EA2.1 Ability to determine and

\NIEOI & E02 Rediagnosis & SI / / I l l I interpret they following as they apply to the (SI Termination): Facility 3.3 25 lllll' rermination 13 conditions and selection of appropriate procedures during abnormal and emergency operations.

W/EI3.EA1.2 Ability to operate andlor monitor the following as they WE13 Steam Generator 3ver-pressure / 4 I I I Ixl I I I I I apply to the (Steam Generator Overpressure): Operating behavior

-characteristics of the facility 3.0 26 Page 4 of 13

interpret the following as they apply to BWIE08; W/E03 LOCA Cooldown and the (LOCA Cooldown and Depressurization/ 4 X Depressurization): Adherence to 3.5 27 appropriate procedures and operation within the limitations in the facilitys Page 5 of 13

PWR Examination Outline ES-401 ;row 1 (RO/SROI Form ES-401-System # I Name WA Topic@)

003.K3.01 Knowledge of the effect that a loss or malfunction of the 3.7 28 DO3 Reactor Coolant Pump RCPS will have on the followinn: -

RCS 003.A3.01 Ability to monitor automatic operation of the RCPS, 3.3 29 including: Seal injection flow 004.K6.31 Knowledge of the effect of a loss or malfunction on the 304 Chemical and Volume Control following CVCS components: 3.1 30 Seal injection system and limits on flow range -

005.K2.01 Knowledge of bus 105 Residual Heat Removal power supplies to the following: 3.0 31 RHR pumps 006.K6.18 Knowledge of the effect 306 Emergency Core Cooling of a loss or malfunction on the 3.6 32 following will have on the ECCS:

Subcookg margin indicators 007.K1.01 Knowledge of the IO7 Pressurizer Relief/Quench physical connections and/or rank cause-effect relationships between 2.9 33 the PRTS and the following systems: Containment system 008.A1.04 Ability to predict and/or monitor changes in parameters (to 108 Component Cooling Water prevent exceeding design limits) 3.1 34 associated with operating the CCSW controls including: - Surge tank level - -

010.K6.04 Knowledge of the effect of a loss or malfunction of the 2.9 35 following will have on the PZR

)I0 Pressurizer Pressure Control PCS: PRT - -

010.A4.03 Ability to manually operate and/or monitor in the 4.0 36 control room: PORV and block valves 012.A2.06 Abilitv to (a) DrediCt the impacts of the fhowhg' malfunctions or operations on the RPS: and (b) based on those 112 Reactor Protection predictions, use procedures to 4.4 37 correct, control, or mitigate the consequences of those malfunctions or operations:

Failure of RPS signal to trip the reactor 2.4.4 Ability to recognize abnormal 113 Engineered Safety Features indications for system operating rctuation parameters which are entry-level 4.0 38 conditions for emergency and abnormal operating procedures 122 Containment Cooling 2.1.27 Knowledge of system purpose and/or function

' * . X 125 Ice Condenser

,a I) >L Page 6 of 13

I PWR Examination Outline ES-401 Form ES-401-2 Plant (stems -Tier 2/Gr( D 1 (RO/SRO) =

System # / Name WA Topic(s) IR #

026.A3.01 Ability to monitor automatic operation of the CSS, 026 Containment Spray 4.3 40 including: Pump starts and correct MOV positioning -

039.K1.07 Knowledge of the physical connections and/or cause-effect relationships between 3.4 41 the MRSS and the following 039 Main and Reheat Steam systems: AFW 039.K3.06 Knowledge of the effect that a loss or malfunction of the 2.8 42 MRSS will have on the following:

SDS __

056.K1.03 Knowledge of the physical connections and/or cause-effect relationships between 2.6 43 the Condensate System and the following systems: MFW 056.A2.04 Ability to (a) predict the impacts of the following 056 Condensate malfunctions or operations on the Condensate System: and (b) based on those predictions, use 2.6 44 procedures to correct, control, or mitigate the consequences of those malfunctions or oDerations:

Loss of condensate pumps -

059.K1.02 Knowledge of the physical connections and/or 059 Main Feedwater cause-effect relationships between 3.4 45 the MFW and the following systems: AFW system 061.K5.02 Knowledge of the operational implications of the following concepts as they apply to 3.2 46 061 Auxiliary/Emergency the AFW: Decay heat sources Feedwater and magnitude 2.2.22 Knowledge of limiting conditions for operations a i d 3.4 47 safety limits 062.A3.01 Ability to monitor automatic operation of the AC 062 AC Electrical Distribution 3.0 48 distribution system, including:

Vital AC bus amperage 063.A3.01 Abilitv to monitor automatic operation of the DC 063 DC Electrical Distribution electrical system, including: 2.7 49 Meters, annunciators, dials, recorders, and indicating lights 064.K4.02 Knowledge of ED/G system design feature(s) andlor 064 Emergency Diesel Generator interlock(s) which provide for the 3.9 50 following: Trips for ED/G while operating (normal or emergency) 073.K5.01 Knowledge of the operational implications as they apply to concepts as they apply to 073 Process Radiation Monitoring 2.5 51 the PRM system: Radiation theory, including sources, types, units, and effects -

Page 7 of 13

ES-401 I PWR Examination Outline Plant Svstems - Tic I

(RO/SRO) Form ES-401-2 System # I Name WA Topic(s) #

076.K1.08 Knowledge of the physical connections and/or 076 Service Water cause-effect relationships between 3.5 52 the SWS and the following systems: RHR system 078.K2.01 Knowledge of bus 078 Instrument Air power supplies to the following: 2.7 53 Instrument air compressor 103.K3.01 Knowledge of the effect that a loss or malfunction of the containment system will have on 3.3 54 the following: Loss of containment integrity under shutdown conditions -

103.A2.04 Ability to (a) predict the 103 Containment impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use 3.5 55 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Containment evacuation (including recognition of the alarm) -

(/A Category Point Totals: Group Point Total: 28 Page 8 of 13

PWR Examination Outline Form ES-401-2 ts-401 Plant Sy: 'ier 2 (RO/SRO)

I 1 I I I Svstem # / Name I4 KI 4 KI WA Topic@) #

2.4.6 Knowledqe of symptom 002 Reactor Coolant I I I 1 I based EOP mitigation strategies 56 011.A2.06 Ability to (a) predict the impacts of the fckowing.

malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to 57 correct, control, or mitigate the consequences of those malfunctions or operations:

Inadvertent PZR spray actuation 014.K4.03 Knowledge of RPlS design feature(s) and/or 3.2 58 interlock(s) which provide for the following: Rod bottom lights 015.Kz.01 Knowledge of bus power supplies to the following: 3.3 59 NIS channels, components, and interconnections 016.A4.02 Ability to manually operate and/or monitor in the 2.7 60 control room: Recorders impacts of the following-malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those 033 Spent Fuel Pool Cooling predictions, use procedures to 3.1 61 correct, control, or mitigate the consequences of those malfunctions or operations:

Abnormal spent fuel pool water I I I I I level or loss of water.level impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures H

045 Main Turbine Generator 2.7 62 to correct, control, or mitigate the consequences of those malfunctions or operations:

Malfunction of electrohydraulic control Page 9 of 13

PWR Examination Outline ES-401 Plant Svstems - Tier 2/Gr ID 2 (RO/SRO\

~- - I I Form ES-401-:

System # / Name WA Topic(s) #

055 Condenser Air Removal 068.A4.04 Abilitv to manuallv 068 Liquid Radwaste operate and/or monitor in the 63 control room: Automatic isolation 071.A1.06 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 071 Waste Gas Disposal associated with Waste Gas 64 Disposal System operating the controls including: Ventilation svstem 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086.A2.04 Ability to (a) predict the impacts of the following malfunctions or operations of the Fire Protection System; and (b) 386 Fire Protection based on those predictions, use 65 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure to actuate the FPS when required, resulting in fire damage VA Category Point Totals: Group Point Total: 10 Page 10 of 13

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

I I Form ES-401-3 Facilitv: Point Beach Nuclear Plant I Date of Exam: Sep 29,2003 I SRO-Only Category WA # Topic IR #

Ability to recognize indications for system 2.1.33 operating parameters which are entry-level 3.4 66 conditions for technical specifications Ability to make accurate, clear and concise 2.1 .I7 3.5 67 verbal reports 1.

Conduct of Operations Subtotal 2 Knowledge of limiting conditions for 2m2'22 3.4 68 operations and safety limits 2.2.33 Knowledge of control rod programming 2.5 69

2. 2.2.27 Knowledge of the refueling process 2.6 70 Equipment Control I I I Subtotal 3 Knowledge of 10 CFR: 20 and related facility 2'3'1 2.6 71 radiation control requirements Knowledge of radiation exposure limits and 2.3.4 contamination control, incjuding permissible 2.5 72 levels in excess of those authorized 3.

Radiation 2.3.1 I Ability to control radiation releases 2.7 73 Cont roI Page 11 of 13

ES-401 Generic Knowledge and Abilities Outline (Tier 3) I Form ES-401-3 Facility: Point Beach Nuclear Plant Date of Exam: Sep 29,2003 RO SRO-0 nly KIA # Topic IR # IR #

Knowledge of annunciators alarms and 2.4.31 indications, and use of the response 3.3 74 instructions Knowledge of low power I shutdown 2.4.9 implications in accident (e.g. LOCA or loss of 3.3 75

4. RHR) mitigation strategies Emergency 1 Procedures I Plan Tier 3 Point Total 1 10 I Page 12 of 13

ES-401 Record of Rejected WAS Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected WA Fundamentals question - Selected AK3.03 No K2s selected for tier 1 - Selected EK2.02 111 ~0000261K1 No K I statements - Selected AK3.01 AK3.01 NIA to PBNP - Selected AK3.02 1I1 000062 I K2 No K2 statements - Selected G2.4.31 000001 I I2 SRO level knowledge - Selected AKI .08 AK3.02 II2 000024 I K3 No K2s selected for tier 1 - Selected AK2.04 211 022 I K5 WA 2.5 - Selected G2.1.27 211 056 I A I All WAs < 2.5 - Selected K1.03 211 059 I K5 All WAS < 2.5 - Selected K1.02 211 062 I K6 All WAS < 2.5 - Selected A3.01 1 ,211 1078lA2 WA < 2.5 - Selected K2.01 I/ 212 10141K6 All WAs < 2.5 - Selected K4.03 1 212 I 0161K6 WA < 2.5 - Selected A4.02 1 212 I 0451 K2 All WAS < 2.5 - Selected A2.17 1 212 I 0681A1 All WAs < 2.5 - Selected A4.02 I 2 12.2.11 SRO level knowledge - Selected 2.2.27 3 3 12.3.8 WA 2.5 - Selected 2.3.1 3 3 12.3.5 WA < 2.5 - Selected 2.3.3 2.3.3 KIA 2.5 - Selected 2.3.4 3 3 12.3.7 WA < 2.5 - Selected 2.3.1 I 1 3 I 4 12.4.37 WA < 2.5 - Selected 2.4.31

~~~

3 4 12.4.28 WA < 2.5 - Selected 2.4.9 Page 13 of 13

f ES-401 PWR Examination Outline Form ES-40 1-2 Facility: Point Beach Nuclear Plant Date of Exam: Sep 29,2003 II Plant Systems - - - - - - - - - _ - - - - - - -

Tier 5 3 3 2 2 3 2 7 4 3 4 38 0 3 1 2 6 Totals Note: 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.l .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 WA 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) WAS in Tiers Iand 2 shall be selected from Section 2 of the WA 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 WA 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 WA 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.

Page 1 of 11

ES-401 Emergency an1 irmal PI I

EIAPE # I Name I Safety Function I! KJA Topic(s) 2.4.30 Knowledge of which events I I R I #f 000007 (BW/E02&E10; CElE02) Reactor related to system operationslstatus 3.6 1/76 should be reported to outside 000009 Small Break LOCA I 3 000011 Large Break LOCA I 3 ~~ 7 000015117 RCP Malfunctions 14 I 000022 Loss of Rx Coolant Makeup 12 I 000027 Pressurizer Pressure Control System Malfunction I 3 interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: PZR heater 3.6 1 3/78 000038 Steam Gen. Tube Rupture 1 3 reasons for the following responses as they apply to the SGTR: Criteria I I4.5 4/79 Transfer 1 4 000054 (CEIEO6) Loss of Main Feedwater 14 .

000055 Station Blackout 16 1 interpret the following as they apply to a Station Blackout: Actions necessary I I 4.7 5/80 000056 Loss of Off-site Power I 6 I--

000062 Loss of Nuclear Svc Water 1 4 1 000065 Loss of Instrument Air 1 8 interpret the following as they apply to WlE04 LOCA Outside Containment I 3 the (LOCA Outside Containment):

4.2 6181 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments 1 WIEll.EA2.2 Ability to determine and I interpret the following as they apply to WlEl1 Loss of Emergency Coolant the (Loss of Emergency Coolant Recirc. 1 4 Recirculation): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments Page 2 of 11

Page3of11 WlEl6.EA2.2 Ability to determine and interpret the following as they apply to WlE16 High Containment Radiation I9 the (High Containment Radiation):

Adherence to appropriate procedures 3.3 and operation within the limitations in Page 4 of 11

PWR Examination Outline ES-401 Form ES-401-2 Emeraencv and Abnormal Plant Evolutions -Tier I/GrouD 2 (ROISRO)

I

" I . I E/APE # / Name / Safety Function K K K A G WA Topic(s) IR #

1 2 3 2 reasons for the following responses as they apply to the (Natural Circulation Operations): RO or SRO BW/EO9; CE/A13; W/ E10 Natural Circ. / function within the control room team X

4 as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and 2 I 0 I GrouD Point Total: 1 5 Page 5 of 11

ES-401 I PWR Examination Outline Plant vstems - Tic I

1 (ROISRO)

~- - I I

I Form ES-401-2

=

I System # / Name WA Topic(s) #

003 Reactor Coolant Pump monitor changes in parameters (to prevent exceeding design limits) 004 Chemical and Volume Control 13/88 associated with operating the CVCS controls including: Letdown and charging flows 2.2.25 Knowledge and bases in technical specifications for limiting 005 Residual Heat Removal 3.7 14/89 conditions for operations and safetv limits 006 Emergency Core Cooling 007 Pressurizer ReliefIQuench Tank 008.A2.09 Ability to la) predict the impacts of the fdllowhg '

malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the 008 Component Cooling Water 2.8 15/90 consequences of those malfunctions or operations:

Results of excessive exit temperature from the letdown cooler, includina the temperature

~~~

effects on /on-&change resins 010 Pressurizer Pressure Control 012 Reactor Protection 313 Engineered Safety Features 4ctuation 322 Containment Cooling 026.A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 326 Containment Spray 4.2 1 6/91 associated with operating the CSS controls including: Containment 339 Main and Reheat Steam 356 Condensate 359 Main Feedwater 361 AuxiliaryIEmergency Feedwater 362 AC Electrical Distribution 363 DC Electrical Distribution 164 Emergency Diesel Generator 173 Process Radiation Monitoring 176 Service Water

~

Page6of11

-~

Page 7 of 11

ES-401 ~

Form ES-401-3 Facility: Poi t Beach Nuclear Plant I Date of Exam: Sep 29,2003 Category WA #

I Topic I

LRO 1 SRO-Only I

I I IR Ability to locate and use procedures and 2.1.5 directives related to shift staffing and activities.

Ability to direct personnel activities inside the I 3*4 I l9jg4 2.1.9 control room 1.

Conduct of Operations Subtotal Knowledge of limiting conditions for 2'2'22 operations and safety limits.

2.2.24 Ability to analyze the effects of maintenance activities on LCO status.

I 3.8 1 22/97 2.

Equipment Control Subtotal Knowledge of the process for performing a 2.3.9 containment purge I

3.

Radiation Control Subtotal Page 9 of 11

ES-40 1 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 I

Knowledge of general guidelines for EOP 2.4.14 3.9 24/99 flowchart use.

Knowledge of EOP implementation hierarchy 251 2.4.16 and coordination with other support 4*0 100

4. procedures Emergency Procedures ISubtotal 2 1 Tier 3 Point Total 1 7 Page 10 of I 1

ES-401 Record of Rejected WAS Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected WA 1 111 1 000007 I K2 I Not SRO only - Selected K1 1 Not SRO only - Selected G2.4.30 1 'I1 1I1 ooool 'Io1 K2 000027 I K I Not SRO only - Selected G2.1.I Not SRO only - Selected A I 2

AI Not SRO only - Selected K2 K2 Not SRO only - Selected AA2.10 1I1 000038 I A I Not SRO only - Selected EK3.09

/ 111 1 WlE04 I K1 1 Not SRO only - Selected A I AI Not SRO only - Selected EA2.2 000005 I

'I2 Previously selected in RO outline, selected AKI .02 AA2.03 000060 I

'I2 Not SRO only - Selected AK3.01 AK3.04 211 005 I K5 Not SRO only - Selected K1 K1 Not SRO only - Selected G2.2.25 211 008 I K5 All WAS 2.5 - Selected K6 K6 All WAS 2.5 - Selected A2.09 212 011 / A 3 Not SRO only - Selected K5 K5 Not SRO only - Selected A I .04 3 3 12.3.4 Previously selected in RO outline - Selected 2.3.1 2.3.1 Previously selected in RO outline - Selected 2.3.9 4 4 12.4.2 Not SRO only - selected 2.4.14 Page I 1 of I 1

ML033030026

Text

Dear Mr. Lanksbury:

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