ML051320277

Draft - Outlines (Facility Ltr Dated 12/09/2004) (Folder 2)

ML051320277
Person / Time
Site:	Beaver Valley
Issue date:	12/09/2004
From:	Hynes C, Wooley T FirstEnergy Nuclear Operating Co
To:	Barr S, Conte R NRC/RGN-I/DRS/OSB
Conte R
References
Download: ML051320277 (36)

Text

L Memorandum To: Mr. Stephen Barr, US From: Thomas Wooley Date: 12/9/04 Re: BVPS Unit 1 NRC Exam Outline Enclosed, for your review and approval is the outline for the FENOC BVPS Unit 1 NRC Exam scheduled to be administered in February 2005. This submittal satisfies the requirements of NUREG- 1021, Operator Licensing Examination Standards for Power Reactors Rev. 9.

We request that these materials be withheld from public disclosure until after completion of the examination.

If you have any questions or require further information, please call iiie at (724) 682-5723.

o r Mr. Chris Hynes at (724) 682-575 1.

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: BVPS-1 Date of Examination: 2/28

___ 005 Itern Task Description - -

a C#

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

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

I

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. JGA T d. Assess whether the justifications for deselected or rejected K/A statements are JGA T appropriate.

E

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number JGA of normal evolutions, instrument and component failures, technical specifications, and major transients.

b. Assess whether there are enough scenario sets (and spares) to test the projected JGA 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.

T c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and JGA 0 quantitative criteria specified on Form ES-301-4 and described in Appendix 0.

R ps 3 a. Verify that systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks, JGA w distributed among the safety functions as specified on the form

/

T (2) task repetition from the last two NRC examinations is within the limits specified on JGA the form, (3)' no tasks are duplicated from the applicants' audit test@) JGA (4) the number of alternate path, low-power, emergency and RCA tasks meet the JGA criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1 (1) the tasks are distributed among the topics as specified on the form JGA (2) at least one task is new or significantly modified JGA 1 (3) no more than one task is repeated from the last two NRC licensing examinations JGA

c. Determine if there are enough different outlines to test the projected number and mix of JGA applicants and ensure that no items are duplicated on subsequent days.

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in JGA the appropriate exam section.

G b. Assess whether the 10CFR 55.41143 and 55.45 sampling is appropriate. JGA E

N I c. Ensure that WA importance ratings (except for plant-specific priorities) are at least 2.5 JGA E d. Check for duplication and overlap among exam sections. JGA R

e. Check the entire exam for balance of coverage. JGA A

L f. Assess whether the exam fits the appropriate job level (RO or SRO). JGA Printed Name / Signature Date 3.

3 Author Facility Reviewer (*)

Joseph G. Arsenault . 11/23/2004

NRC Chief Examiner (#)

c ,

W' j NRC Supervisor VOTE # Independent NRC reviewer initial items in Column "c". chief examiner concurrence required NUREG-1021, Revision 9

BVPS Units 1 and 2 2005 NRC Initial License Written Examination Written Examination Outline Methodology The written examination outline was developed using a proprietary electronic random outline generator developed by Western Technical Services, Inc.

The software was designed to provide a written examination outline in accordance with the criteria contained in NUREG-1021, Revision 9.

The application was developed using Visual Basic code, relying on a true random function based on the PC system clock. The random generator selects topics in a Microsoft Access Database containing Revision 2 of the PWR K&A catalogue. The selected data is then written to a separate data table. The process for selection of topics is similar to the guidance in ES-401,Attachment 1.

The attached outline report and plant specific suppression profile (not used for BVPS) report are written directly from the data tables created by the software. Electronic copies of the data tables are on file.

The process used to develop the outlines is as follows:

For Tier 1 and Tier 2 generic items, only the items required to be included in accordance with ES-401, Attachment 2 are included in the generation process.

The BVPS plant suppression profile lists all suppressed topics, either at the Topic level (System/EPE) or at the statement level. These items were suppressed prior to the electronic generation process. ltems suppressed for the BVPS-I exam only included system 025 (Ice Condenser) and Generic topics 2.2.3 and 2.2.4 (Multi-Unit) This document intended to serve as plant suppression profile due to the small number of suppressed items.

Outline is generated for all topics with KA importance 22.5.

0 25 SRO topics are randomly selected from Tier 1 AA2 and required generic items, Tier 2 A2 and required generic items, and Tier 3 generic items (All with ties to 10CFR55.43). 75 RO topics are randomly selected to complete the outline, 100 topics total.

The exam report generated lists the topic (Question) number in the far right column. RO topics are numbered 1-75, and SRO topics are numbered 76-100 The SRO topics are written in red ink for ease of identification.

ltems that are rejected after the initial generation process are automatically placed on the rejected items page. The software tracks whether items are added manually or by random generation, and a report of outline modification may be generated.

Disposition of any item randomly selected but not included in the outline is documented and included.

ES-401 PWR Examination Outline Form ES-401-2 1I Facility: BVPS-I Date of Exam: 2/28/2005 I I RO WA Category Points I SRO-Only Points G* I Total 1 3 1 5 3 2 1 0 4 4 4 1 28 3 2 1 5 2.

Plant 2 2 1 1 1 0 1 2 0 1 0 1 10 1 Systems Tier Totals 5 2 6 4 2 2 2 4 5 4 2 38 4 4 1 8

3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3141 7 2 3 2 3 2 2 1121 Note: 1. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two).

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 *Ifrom 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. Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified: operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding elimination of inappropriate WA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.' The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.

8. 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. Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the WA Catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10CFR55.43 NUREG-1021 Revision 9 1

X EP ZP

~

CP L'Z X OP P'&

ii Ixl 6C q-zi z-COPS pj L-s "9 lops3

Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Number K/A Topi&)

Imp. Q#

038 I Steam Gen. Tube Rupture I 3 I 1 EA1.16 4bility to operate and monitor the following as they apply to a SGTR: SIG atmospheric relief valve and secondary PORV controllers and indicators Ability to determine and interpret the following as they 4.4 46 040 I Steam Line Rupture - Excessive Heat Transfer I 4 AA2.05 apply to the Steam Line Rupture: When ESFAS systems 4.1 47 may be secured Ability to operate and I or monitor the following as they 054 I Loss of Main Feedwater I 4 AA1.04 apply to the Loss of Main Feedwater (MFW): HPI, under 4.4 48 total feedwater loss conditions Knowledge of the operational implications of the following 055 I Station Blackout I 6 EK1.02 concepts as they apply to the Station Blackout : Natural 4.1 49 circulation cooling Ability to operate and I or monitor the following as they 056 I Loss of Off-site Power I 6 AA1.10 apply to the Loss of Offsite Power: AuxiliaryIemergency 4.3 50 feedwater pump (motor driven)

Ability to determine and interpret the following as they 057 I Loss of Vital AC Inst. Bus I6 AA2.04 apply to the Loss of Vital AC Instrument Bus: ESF system 3.7 51 panel alarm annunciators and channel status indicators Ability to operate and I or monitor the following as they 058 I Loss of DC Power I 6 AA1.01 apply to the Loss of DC Power: Cross-tie of the affected 3.4 52 dc bus with the alternate supply Ability to determine and interpret the following as they 062 ILoss of Nuclear Svc. Water I 4 AA2.01 apply to the Loss of Nudear Service Water: Location of a 2.9 53 leak in the CCWS Ability to determine and interpret the following as they apply to the (LOCA Outside Containment) Facility EO4 I LOCA Outside Containment I 3 I I EA2.1 conditions and selection of appropriate procedures during abnormal and emergency operations.

Knowledge of the reasons for the following responses as 3.4 54 E05 I Inadequate Heat Transfer Loss of Secondary EK3.2 they apply to the (Loss of Secondary Heat Sink) Normal, 3.7 55 Heat Sink I 4 abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).

lX Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency E l 1 ILoss of Emergency Coolant Recirc. I4 EK1.3 Coolant Recirculation)Annunciators and conditions 3.6 56 indicating signals, and remedial actions assodated with the (Loss of Emergency Coolant Recirculation).

I I KIA Category Point Totals: I 013 I 3 Group Point Total: I 18/6 NUREG-1021 Revision 9 3

P 9 L'E X P I S l d - BU!l-JaAO S 3 t l I803 z9 8's X 19 'E E'

6'1 X 8s E'Z X LS E' 56 C t P8 OP r

1 I-COPS. Od OkS3

I ES-40 t . .s-1 Fa S-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 T --

E/APE # / Name Safety Function A1 1 A2 1 Number 1 K/A Topic(s) Imp. Q#

Knowledge of the interrelationsbetween the (Steam Generator Overpressure) and the following: Components.

E13 I Steam Generator Over-pressure I4 EK2.1 and functions of control and safety systems, including 3.0 64 instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Conduct of Operations: Ability to locate and operate E16 / High Containment Radiation / 9 2.1.30 3.9 65 components, including local controls.

I K/A Category Point TOM: 1 112 Group PointTotal: I 914 NUREG-1021 Revision 9 5

IS40 Fo! S-401-2 L. s-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 1 System #/Name

- - Number A3 A4 1 ImD.

2 1 .ii 4 0 4 1 ASility t o ( , 3 ) ;)I<?(JI~:I tlw \II~~),~~of: \ the S ~OIIWWIV~ 171~1 function5 or opitiatioiis o r the hlRSS ,drl(l (!I) !i.iseti or1 predictions. use procedures to correct t C O ~ l t I 0 or A2 05 36 rnitigate the consequences of those malf!inctions or operations lricreasirig steam demand. its relationship to iricreases 111 reactor power Knowledge of the operational implications of the 003 Reactor Coolant Pump K5.02 following concepts as they apply to the RCPS: Effects 2.8 of RCP coastdown on RCS parameters 003 Reactor Coolant Pump K3.02 Knowledgeof the effect that a lass or malfunction of the RCPS will have on the following: SIG I 3.5 2

004 Chemical and Volume Control X A4.12 Ability to manually operate and/or monitor in the control room: Boration/dilution batch control 1 3.8 3

Ability to manually operate andlor monitor in the control 005 Residual Heat Removal room: Controls and indication for closed cooling water 3.1 4 Knowledge of the effect that a loss or malfunction of the 005 Residual Heat Removal 3.7

~

Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based 006 Emergency Core Cooling A2.11 on those predictions, use procedures to correct, control, 4.0 or mitigate the consequences of those malfunctions or operations: Rupture of ECCS header

- ~~ ~~ ~~

007 Pressurizer RelieflQuench Tank A4.01 Ability to manually operate and/or monitor in the control room: PRT spray supply valve I 2.7 NUREG-1021 Revision 9

ES4C L .IS-?

Fd 3-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 1 System #/Name I G IKl1K2IK3 K4 K5

~~

K/A T o o i c -

Ability to (a) predict the impacts of the following Imp. Q#

malfunctions or operations on the CCWS, and (b) based 008 Component Cooling Water on those predictions, use procedures to correct. control, 3.2 8 or mitigate the consequences of those malfunctions or operations: Highnow surge tank level Knowledge of the operational implications of the following concepts as the apply to the PZR PCS:

010 Pressurizer Pressure Control X 3.5 9 Determination of condition of fluid in PZR. using steam tables Knowledge of the effect of a loss of malfunction of the 012 Reactor Protection 2.7 10 following will have on the RPS: Sensors and detectors 013 Engineered Safety Features Ability to manually operate and/or monitor in the control room: ESFAS-initiated equipment which fails to actuate 4.5 11 Actuation Knowledge of CCS design feature@)and/or interlock(s) 022 Containment Coding X which provide for the following: Cooling of containment 2.5 12 penetrations Knowledge of the physical connections and/or cause-022 Containment Cooling X effect relationships between the CCS and the following 3.7 13 systems: SEC/remote monitoring systems Conduct of Operations: Ability to perform s p e c k 026 Containment Spray system and integrated plant procedures during all 3.9 14 modes of plant operation.

Knowledgeof the effect that a loss or malfunction of the 039 Main and Reheat Steam MRSS will have on the following: RCS 3.6 15 Knowledgeof the physical connections and/or cause-039 Main and Reheat Steam effect relationships between the MRSS and the following 2.7 16 systems: MFW Ability to monitor automatic operation of the MFW, 059 Main Feedwater 2.9 17 including: Programmed levels of the S/G Knowledge of MFW design feature@)and/or interlo&(s) 059 Main Feedwater X which provide for the following: Automatic trips for MFW 3.1

- Pumps 061 AuxiliaryEmergency Knowledgeof the physical connections and/or cause-Feedwater effect relationships between the AFW and the following 3.6 systems: Emergency water source 061 AuxiliaryEmergency Ability to monitor automatic operation of the AFW, Feedwater 4.0 including: RCS coddown during AFW operations NUREG-1021 Revision 9 7

I ES-4C t .si FC 1-Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 1 out-of-phaselmismatch in volts Knowledge of the effect that a loss or malfunction of the 22 063 DC Electrical Distribution X K301 3.7 dc electrical system will have on the following: EDlG Knowledgeof EDlG system design feature@)and/or 064 Emergency Diesel Generator X K4.02 inter-lock(s) which provide for the following: Trips for 3.9 23 EDlG while operating (normal or emergency)

Ability to monitor automatic operation of the EDlG 064 Emergency Diesel Generator X A3.05 system, including: Operation of the governor control of 2.8 24 frequency and voltage control in parallel operation Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) 073 Process Radiation Monitoring X A2.02 based on those predictions, use procedures to correct, 2.7 25 control, or mitigate the consequences of those malfunctions or operations: Detector failure Knowledge of bus power supplies to the following: 2.7 26 076 Service Water X K2,0, Service water Knowledge of the effect that a loss or malfunction of the 078 Instrument Air X K3.02 IAS will have on the following: Systems having 3.4 27 pneumatic valves and controls Ability to monitor automatic operation of the containment 3.9 28 103 Containment X A3.0, system, including: Containment isolation WA Category Point Totals: 1 / 2 3 1 5 3 2 1 0 4 1 3 4 4 Group Point Total: 28/5 NUREG-1021 Revision 9 8

6 LE E'Z X 9E 9'E X ri I 8L' LM X

LZL'Z I I 1 x 1

~

ZE P'E LO' LV X LE Z'E X

cc os P 2 i-i 7 x L'c

Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 2 System #/Name I G I K1 I K2 I K3 I K4 I K5 I K6 I A1 1 A2 I A3 I A4 I Number I WA Topics Knowledge of the physical connections andlor cause-effect relationships between the circulating water 075 Circulating Water X K1.02 2.9 system and the following systems: Liquid radwaste discharge WA Category Point Totals: 112 2 1 1 1 I 0 I 1 I 2 I 011 I 1 I 0 I GroupPointTotal: I NUREG-1021 Revision 9 10

Facility: BVPS-1 Date of Exam: 2/28/2005 RO Category WA # Topic 2 1 20 Abililv to t>xtcutc proc,c,ciiirt. strps Knowlr.ci:jr> of .;)stern statti5 critrria whirh l4 reqiiirc' Ihc notific ,qtion of I m n t iwrsonnrl

1. Knowledge of conduct of operations 2.1 3.7 Conduct of requirements.

3perations Ability to obtain and interpret station reference 2.1.25 materials such as graphs, monographs, and 2.8 67 tables which contain performance data.

Subtotal Knowlcdge of new and spent fuel movement 28 procedures Knowledqe of limiting conditions for operations 22 and safety limits 2.2.12 Knowledge of surveillance procedures. 3.0 68 Knowledge of bases in technical specifications 2.2.25 for limiting conditions for operations and safety 2.5 69 2.

Equipment Control limits. - -

Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage 2'2.30 3.5 70 facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

3.

Subtotal 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against

-F 2.9 I 71 qadiation Control personnel exposure.

2.3.1 1 Ability to control radiation releases.

~~

Subtotal 1.

Zmergency 2.4.29 Knowledge of the emergency plan.

'rocedures I Plan Knowledge of operational implications of EOP 2'4'20 warnings, cautions, and notes.

Ability to interpret control room indications to verify the status and operation of system, and 2'4'48 3.5 75 understand how operator actions and directives affect plant and system conditions.

rier 3 Point Total 1 7 NUREG-I 021 Revision 9 11

I Tier I Randomly Reason for Rejection Group Selected KIA I 1I 1 I 057 AA2.09 I The subject KIA isn't relevant at the subject facility.

I 112 I 001 AA1.04 I The subject KIA isn't relevant at the subject facility.

112 003 AK2.03 The subject KIA isn't relevant at the subject facility.

2/1 012 K6.11 The subject KIA isn't relevant at the subject facility.

212 033 2.4.6 The subject KIA isn't relevant at the subject facility.

The subject KIA's importance rating isn't equal to or greater than 2.5 for the 211 059 K4.14 license level of the proposed examination, and there isn't a site-specific priority that justifies keeping the KIA, if its importance rating is below 2.5.

2/1 061 K1.10 The subject K/A isn't relevant at the subject facility.

The subject WA's importance rating isn't equal to or greater than 2.5 for the 3 G2.2.9 license level of the proposed examination, and there isn't a site-specific priority that justifies keeping the KIA, if its importance rating is below 2.5.

lil 027 2 4.49 The subject KIA isn't relevant at the subject facility It isn't possible to prepare a psychometrically sound question related to the 111 062 2.1.14 su biect K/A It isn't possible to prepare a psychometrically sound question related to the 1 2 067 AA2 11 sub ect 1/1 062 2 1 23 I Random selection of replacement K A was a duplicate topic G2 4 29 Duplicate of K A already selected K A deleted because 3 topics selected for Generic Section 2 Replaced with G2 l7 2.4.4.

NUREG-1021 Revision 9 12

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: BVPS-1 Date of Exam: 2/28\05 Scenario 112 1314 Operating Test No.: NRC Numbers:

QUALITATIVE ATTRIBUTES Initials a b'

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of JGA service, but it does not cue the operators into expected events.

~

2. The scenarios consist mostly of related events. JGA

3. Each event description consists of the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptomslcues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario JGA without a credible preceding incident such as a seismic event.

5. The events are valid with reaard to Dhvsics and thermodvnamics. JGA

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain JGA complete evaluation results commensurate with the scenario objectives.

7. If time compression techniques are used, the scenario summary clearly so indicates. Operators NIA have sufficient time to carry out expected activities without undue time constraints. Cues are given.

8. The simulator modeling is not altered. JGA

9. The scenarios have been validated. Pursuant to IOCFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

~ ~~~~~~ -

IO. Every operator will be evaluated using at least one new or significantly modified scenario. All other JGA scenarios have been altered in accordance with Section D.5 of ES-301.

11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit JGA the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number of transients and events JGA SDecified on Form ES-301-5 (submit the form with the simulator scenarios).

JGA TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO; SEE SECTION D.5.d) Actual Attributes 1 2 3 4

1. Total malfunctions (5-8) 6 6 6 6 -JGA

2. Malfunctions after EOP entry (1-2) 1 2 1 2 1 3 1 1 JGA

3. Abnormal events (2-4) 3 3 2 4 JGA

4. Major transients (1-2) 1 1 2 1 JGA

5. EOPs enteredlrequiring substantive actions (1-2) 2 2 2 2 JGA

6. EOP contingencies requiring substantive actions (0-2) I 1 1 0 1 0 1 0 JGA

7. Critical tasks (2-3) 2 2 3 2 JGA NUREG-1021, Revision 9

2005 BVPS-1 Initial License Examination Outline Submittal PSA Considerations The scenarios developed for the 2005 BVPS-1 NRC license examination were constructed in consideration of the BVPS-1 Plant Specific Analysis. (PSA)

Each scenario considered one or more of the following 3 factors:

1. Contribution to CDF by sequence type

2. Contribution to CDF by initiator

3. Contribution to CDF by system Component or instrument failures were chosen based upon the importance of the system to CDF. River Water, Auxiliary Feedwater, and Electrical Distribution failures throughout the scenarios will all increase the likelihood of core damage in accordance with the BVPS-1 PSA. Instrument failures affecting the operation of control systems such as Pressurizer Pressure Control and CVCS are also part of important event sequences.

Major transients were developed based upon either sequence type or initiator.

Each of the Major events developed for the BVPS-1 scenarios were selected for their importance either as an initiator (Loss of Feedwater, ATWS), or by sequence type (LOCA, SGTR, MSLB). The events were designed to place the crew in a position to evaluate the performance of operator actions important to the PSA.

For the JPM examination, one new JPM was developed to evaluate important operator actions contributing to CDF:

Actions for SI Termination (Top 10 action #1)

The remaining JPMs were selected or developed with consideration of the importance of the system or evolution that the task is performed on.

ES-301 Transient and Event Checklist Form ES-301-5 F acility BVPS- 1 Date of Exam: 2/28/2005 Operating Test No : NRC Scenarios E

V E 1 2 3 4 N T M T 0 1 CREW POSITION CREW POSITION CREW POSITION CREW POSITION T A I Y L M P

E RX NOR SROI-I I/C MAJ TS RX NOR SROI-2 I/C MAJ TS RX NOR SROI-3 IIC MAJ TS RX NOR SROU-I I/C MAJ Instructions' 1 Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type, TS dit) not applicable for RO applicants. ROs must service in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)"

positions; Instant SROs must do one scenario, including at least two instrument or component ( I E ) malfunctions and one major transient, in the ATC position.

2 RedCtiVity manipulations may be conducted under normal or controlledabnormal conditions (refer to Section D 5 d) but must be significant per Section C 2 a of Appendix D Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis 3 Whenever practical, both instru ent and component malfunctions should be included only those that require verifiable

- 5.

actions that Drovide insioht to th amlicant's

,, comnetence count toward the minimum reouirement Author umw NRC Reviewer:

NUREG 1021 Revision 9

ES-301 Transient and Event Checklist Form ES-301-5 I

Facility: BVPS-I Date of Exam: 2/28/2005 Operating Test No NRC A Scenarios P

P L

I C

A CREW POSITION CREW POSITION CREW POSITION N

T c

S A B S A B S A B R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 1

I 15.9 I I I I I I NOR I I I 1 I/C I I 1 I I I I I I 1

5,9 7

1 NOR I I NUREG 1021 Revision 9

ES-301 Competencies Checklist Form ES-301-6 1 Facility: BVPS-1 Date of Examination: 2/28/2005 Operating Test No. NRC n

._- APPLICANTS I ATC BOP Competencies SCENARIO SCENARIO SCENARIO InterpreVDiagnose Events and Conditions 1 '22 134 57 7 1

245 2

259 345 7

3 4 156 Comply With and 123 1-7 124 157 135 12 Use Procedures (1) 46 7 9 7 124 159 135 125 7 7 124 125 134 125 57 79 57 67 NA NA NA NA NA NA NA NA Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

Only applicable to SROs.

Instructions:

Circle the applicants' license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Author:

NRC Reviewer: &-

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: BVPS-1 0 ate of Exam inat ion: 2/28/2005 Examination Level RO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

2.1.25 Ability to obtain and interpret station reference Conduct of Operations materials such as graphs, monographs, and tables which contain performance data (2.8)

N JPM: Perform RCS Cooldown Verification 2.1.23 Ability to perform specific system and Conduct of Operations integrated plant procedures during all modes of plant operation (3.9)

M JPM: Perform an ECP Calculation 2.2.13 Knowledge of Tagging and Clearance Equipment Control Procedures (3.6)

M JPM: Review a Tagging Request 2.3.2 Knowledge of facility ALARA program (2.5)

Radiation Control N

JPM: Determine Maximum Allowable Stay Time 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.

• Type Codes & Criteria: (C)ontrol room (D)irect from bank I( 3 for ROs; I for 4 for SROs & RO retakes)

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

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

(S)imuIato r NUREG-1021, Revision 9

Administrative Topics Outline Task Summary Ala Given a set of plant conditions and a required RCS cooldown, the applicant will be required to determine the cooldown rate and acceptability within specified limits. This is a new JPM.

A1 b Given plant conditions prior to a reactor startup, the applicant will be required to calculate the estimated critical boron concentration. This is a modified bank JPM. A variation of this JPM was performed on the 2001 NRC examination.

A2 Given a tagging request, the applicant will be required to perform a review and identify errors contained within the tagging order. This is a modified bank JPM. A variation of this JPM was performed on the 2001 NRC examination.

A3 Given a task to perform in the RCA, the applicant will be required to select the appropriate RWP, evaluate the RWP and a survey map, and determine maximum stay time in the work area. This is a new JPM.

NUREG-1021, Revision 9

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

-acility. BVPS-1 Date of Examination, 2/28/2005 Examination Level SRO Operating Test Number: NRC Administrative Topic TY Pe Describe activity to be performed (see Note) Code*

2.1.12 Ability to apply Technical Specifications for a Sonduct of Operations system (4.0)

D JPM: Determine Action Required For Failed AC Sources Surveillance 2.1.23 Ability to perform specific system and

onduct of Operations integrated plant procedures during all modes of plant operation (4.0)

M JPM: Review an ECP Calculation 2.2.13 Knowledge of Tagging and Clearance Equ i pment Cont roI Procedures (3.8)

M JPM: Approve a Tagging Request 2.3.8 Knowledge of the process for performing a Radiation Control planned Gaseous Radioactive release (3.2)

N JPM: Review a Gaseous Waste Discharge Authorization 2.4.40 Knowledge of SROs responsibilities in Emergency Plan emergency plan implementation (4.0)

N JPM: Terminate an Emergency Classification 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, Revision 9

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

• Type Codes & Criteria: (C)ontrol room (D)irect from bank (I3 for ROs; I for 4 for SROs & RO retakes)

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

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

(S)imulator NUREG-1021. Revision 9

Administrative Topics Outline Task Summary A1 a The applicant will be required to identify procedural errors and determine the required Technical Specification actions for a failed surveillance test. This is a bank JPM. This JPM was performed on the 2002 NRC examination.

A1 b Given plant conditions prior to a reactor startup, the applicant will be required to calculate the boron concentration required for reactor startup. This is a modified bank JPM. A variation of this JPM was performed on the 2001 NRC examination.

A2 Given a tagging request, the applicant will be required to perform a review and identify errors contained within the tagging order. This is a modified bank JPM. A variation of this JPM was performed on the 2001 NRC examination.

A3 The applicant will be required to review a gaseous waste discharge release permit containing errors that must be identified and corrected prior to approval. This is a new JPM.

A4 The applicant will be given conditions during performance of Emergency Director duties that allow the termination of an emergency classification. The conditions of this JPM are based on a Unit 2 Unusual Event as documented in LER 2-000-03. This is a new JPM.

NUREG-1021, Revision 9

ES-301 Control Room/ln-Plant Svstems Outline Form ES-301-2

'acility: BVPS-1 Date of Examination: 2/28/2005 fxam Level : RO / SRO(I) SRO(U) Operating Test No.: NRC

ontrol Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Type Safety JPM # System JPM Title Code' Function 00 1 Raise Reactor Power to Amps SI NSAL 1 Rod Control

~~ ~~

52 E02 Perform SI Termination IA W ES-1.1 NSAE 3 SI Termination s3 Ern Post LOCA C/D Isolate SI Accumulators During a LOCA NSA E 4P and Depressurization s4 04 1 Initiate Natural Circulation Cooldown DASE 45 Steam Dump 103 s5 Manually Actuate CIB DSAEP 5 Containment S6 064 Synchronize and Load E D 0 No. 2 DS 6 EDG s7 015 Remove Power Range Instrument From Service DS 7 NIS S8 004 Perform Manual Makeup to the VCT DS 2 cvcs In-Plant Systems (3 for RO: 3 for SRO-I; 3 or 2 for SRO-U) 028 P1 Locally Startup a Containment Hydrogen Analyzer DER 5 HRPS P2 061 Reset TDAFW Pump Trip Throttle Valve DR 45 AFW P3 062 BV-1 Actions to Establish Station Blackout Cross-Tie to Unit 2 DE 6 AC Distribution All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

NUREG-1021, Revision 9

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Type Codes Criteria for RO / SRO-I I SRO-U 91 31 4 abnormal in-plant I / l i 1 11 l i 1 ew or (M)odified from bank including 1(A) 2 1 21 1 (P)revious 2 exams 3/ 3/ 2 (randomly selected)

NUREG-1021, Revision 9

Control Room/ln-Plant Systems Outline Task Summarv s1 The applicant will raise reactor power using control rods to approach criticality. Source Range High Flux Trips must be blocked, and power indication switched to Intermediate Range channels. The alternate path of this task will be based on continuous rod motion in the OUT direction. The applicant will be required to trip the reactor based on AOP guidance. This is a new JPM.

s2 SI Termination will be performed requiring the applicant to align normal RCS makeup flowpaths and secure ECCS equipment. The alternate path of this task will require the applicant to diagnose the inability to maintain RCS inventory and based on either EOP or Foldout page guidance, realign the BIT and re-establish HHSl flow. This is a new JPM.

s3 The applicant will be placed in the EOP network during a Post-LOCA Cooldown and Depressurization. The task is to isolate SI accumulators so that RCS depressurization may continue. The alternate path of this task is to vent one SI accumulator to containment once it is determined that it cannot be isolated. This is a new JPM.

s4 The applicant will initiate an RCS cooldown IAW ES-0.2 during natural circulation conditions. The alternate path of this task is to initiate cooldown using the Residual Heat Release Valve after diagnosing the failure of condenser steam dump valves. This is a bank JPM.

s5 The applicant will be required to verify Containment Isolation Phase B (CIB) actuation.

The alternate path of this task is to manually realign equipment required by CIB after determining that it did not actuate either automatically, or manually. This is a bank JPM.

This task was performed on the 2001 NRC examination.

S6 The applicant will synchronize EDG No. 2 to its emergency bus and raise load on the EDG.

s7 The applicant will perform the action to remove a power range NI channel from service S8 The applicant will manually establish makeup to t h e VCT. This is a bank JPM.

P1 The applicant will locally start a containment hydrogen analyzer. This is a bank JPM that will require entry into the Radiation Control Area (RCA).

P2 The applicant will be required to reset the turbine driven auxiliary feedwater pump trip/throttle valve. This is a bank JPM.

P3 The applicant will perform actions to restore emergency AC power using the station blackout cross-tie to Unit 2. This is a bank JPM.

NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: BVPS-1 Scenario No.: 1 OpTest No.: NRC Examiners: Candidates: CRS RO PO Initial Conditions: BOL, 100% power.

1CH-P-1C, HHSVCharging Pump 00s.

PCV-1RC-456 PORV leakage. MOV-1RC-536, Block Valve closed with power maintained.

Flood warnings from heavy rains.

Maintenance investigating 1WR-P-1A, River Water Pump abnormal vibrationhoise.

Turnover: Initiate power reduction to 75% for waterbox cleaning.

Critical Tasks: FR-S.l .C, Initiate RCS Boration and/or insert RCCAs E-2.A, Isolate Faulted SG Event No.

1 Malf. No. 1 Event Type*

Event Description 1 Power Reduction For Waterbox Cleaning 2 TUR15 (C) ALL Turbine Control Valve Failure (Load Rejection)

(TS) US 3 PRS08E (I) RO, US Pressurizer Pressure Transmitter Fails High (TS) US 4 MSS16E (I) PO, us SG Pressure Transmitter Fails Low (TS) US 5 TURO1 1 Turbine Trip - Steam Dump Failure. Reactor Trip required.

MSS07A 6

7 I CRF12A CRF12B MSS12A I (C) RO, US (C) PO, US Auto and Manual Reactor Trip Failure One SG Atmospheric Dump Valve Fails Partially Open (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 1 The crew will assume the shift at 100% power with instructions to reduce load to 75% for waterbox cleaning.

A turbine load rejection will occur due to a turbine valve position limiter failure requiring the crew to stabilize the plant by matching Tave and Tref and resetting condenser steam dump valves.

After Technical Specifications have been addressed and the plant is stable, Pressurizer Pressure Channel PT-445 will fail high slowly requiring the RO to take manual control of Pressurizer heaters, spray valves, and PORVs. The Unit Supervisor will then address applicable Technical Specifications.

When RCS pressure is stable, SG pressure transmitter PT-485 will fail low causing the steam flow signal to its associated main feedwater control valve to fail low. The PO will take manual control of the affected valve to prevent RPS actuation on SG low-low level.

When SG level is under control and Technical Specifications have been addressed, a turbine trip will occur with a steam dump failure requiring a reactor trip.

Upon reactor trip, the reactor trip breakers will not open automatically or manually. The RO must insert rods and initiate emergency boration. The Unit Supervisor will direct crew response in accordance with the ATWS Functional Recovery procedure.

A faulted SG develops due to a stuck open SG atmospheric dump valve requiring transition to E-2 to isolate the faulted SG. The scenario is terminated upon completion of E-2, or upon transition to ES-1.l.

EOP Flow Path: E-0, FR-S.1, E-0, E-2

Appendix D Scenario Outline Form ES-D-1 Facility: BVPS-1 Scenario No.: 2 Op Test No.: NRC Examiners: Candidates: CRS RO PO Initial Conditions: MOL, 53% Power.

1CH-P-1C, HHSVCharging Pump is 00s.

PCV-1RC-456 PORV leakage. MOV-1RC-536, Block Valve is closed with power maintained.

Flood warnings from heavy rains.

Maintenance investigating 1WR-P-1A, River Water Pump abnormal vi b ration/noise.

Turnover: Reduce power to take the unit off-line due to circulating water intake clogging.

Critical Tasks: E-0.1, Start Train 6 HHSKharging Pump E-1.C, Stop RCPS

~

Event Malf. No. Event Type Event Description 1 (R) RO Reduce Power (N) PO, US (TS) US SG Level Transmitter Fails High (TS) US Train A(No. 1) EDG Failure (C)RO, US Letdown Pressure Control Valve Fails Closed In Auto (C) PO, US SG AFRV Controller Fails Closed In Auto (C) RO, US RCS Leak 7 RCSOZA (M) ALL SBLOCA 8 IN H40 Train B HHSVCharging Pump Auto Start Failure 9 SlSl OA (C) PO AFW Start Failure (Auto SI Failure Train A)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 2 The crew will assume the shift at 53% power with directions to reduce power to take the unit offline due to circulating water intake clogging.

As power is being reduced, a SG B level transmitter will fail high requiring the Unit Supervisor to refer to Technical Specifications.

When the Unit Supervisor has reviewed Technical Specifications, a control power breaker will inadvertently open making the No. 1 Emergency Diesel Generator inoperable. This failure provides the Unit Supervisor with an additional Technical Specification referral and sets up required actions post-trip.

When Technical Specifications have been addressed, the letdown pressure control valve will fail closed requiring the RO to take manual control to restore letdown flow.

When letdown is restored, SG Amain feedwater control valve will fail closed in automatic, requiring the PO to take manual control to stabilize SG level.

When SG level is stabilized, an RCS leak will develop. When the Unit Supervisor refers to Technical Specifications, the leak will degrade into a SBLOCA requiring a reactor trip and safety injection actuation by the crew.

The Train B HHSVCharging Pump will fail to automatically start and must be started manually. RCPs must be tripped when criteria is met due to the LOCA. ESF Train A components must be started manually by the operators.

The scenario may be terminated upon entry to ES-1.2, Post LOCA Cooldown And Depressurization, or when RCS cooldown is initiated.

EOP Flow path: E-0, E-1, ES-1.2

Appendix D Scenario Outline Form ES-D-1 Iacility : BVPS-1 Scenario No.: 3 OpTest No.: NRC

!xaminers: Candidates: CRS RO PO nitiai Conditions: MOL, 25% power.

PCV-1RC-456, PORV 456 Leakage. MOV-1RC-536, Block Valve closed with power maintained Flood watch remains in effect.

Tumover: Raise power to 100% after a trip due to loss of all circulating water.

Zriticai Tasks: E-O.F, Initiate Feedwater Flow with MDAFW E-3.A, isolate Ruptured SG E-0.0, Initiate CIA Event Malf . No. Event No. Type* Event Description 1 (R) RO Raise Power (N) PO, US 2 AUXlOA (C) RO,US Train A River Water Pump Trips. (Backup pump must be (TS) US manually started.)

3 EPS04E (C) ALL Loss of 4KV Bus 1AE. No. 1 EDG Fails to Auto Start.

INH53 (TS) US 4 RNM01A (M)ALL MFW Pump A Degradationnrip. Reactor Trip.

EPS11A No. 1 EDG Failure 5 INH33 (C) PO MDAFW Train 6Pump Auto Start Failure INH36 TDAFW Pump Auto Start Failure INH20 6 1 INH21 RCS03B I (M)ALL SG B SGTR (when AFW is initiated).

7 iNH49 (C) PO CIA Fails To Automatically Actuate (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 3 1-The crew will assume the shift at approximately 25% power with instructions to raise power to 100%.

After initiation of the power increase, the running river water pump will trip. The backup pump will not start automatically and must be started manually by the RO.

When Technical Specifications have been addressed, 4KV Emergency Bus 1 AE will be de-energized and the crew must manually start No. 1 EDG and reinitiate charging flow.

The Unit Supervisor will refer to Technical Specifications.

When the plant is stable, the running main feedwater pump will trip requiring a reactor trip. The No. 1 EDG will fail de-energizing 4KV Bus 1AE. The Train B MDAFW pump and the TDAFW pump will fail to automatically start requiring manual start by the operator.

When transition is made to ES-0.1 and A M pumps have been started, a SGTR will develop requiring SI initiation. CIA valves will not automatically close requiring manual closure by the PO while performing Attachment 1-K, Verification of Automatic Actions.

The scenario is terminated when the ruptured SG is isolated in E-3 and the crew has commenced an RCS cooldown.

EOP Flow Path: E-0, ES-0.1, E-0, E-3

Appendix D Scenario Outline F O WES-D-1

~

FaciIity : BVPS-1 Scenario No.: 4 Op Test No.: NRC Examiners: Candidates: CRS RO PO Initial Conditions: MOL, 75% power.

PCV-1RC-456, PORV 456 leakage. MOV-1RC-536, Block Valve closed with power maintained.

River level has receded. Flood watch cancelled on last shift 1WR-P-1A, River Water Pump 00s.

Turnover: Continue raising power to 100%.

Critical Tasks: E-2.A, Close MSlVs Terminate ECCS prior to water relief through PORVs Event Malf. No. Event No. Type* Event Description 1 FWM01B (C) PO, US Main Feedwater Pump (FW-P-1B) Trip 2 (R) RO Rapid Load Reduction (N)PO, US 3 CRF04BV (C) RO, US Control Rod K-6 Drops (Reactor does not trip.)

(TS) US 4 X07A090P (C) RO, US Pressurizer Master Pressure Controller Output Fails High (TS) US 5 FWM14F (I) PO, US SG C Feedwater Flow Transmitter Fails High FWM07C (M) ALL SG CFeedwater Reg Valve failure (Unrecoverable).

Reactor Trip Required.

7 MSS02B (C) PO Main Steam Break Downstream of MSIVs MSIVs Fail To Close Automatically (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 4 The crew will assume the shift with instructions to raise power to 100%.

A main feedwater pump will trip requiring the crew to initiate a rapid load reduction. After the load reduction, one control rod will drop requiring action to realign and the Unit Supervisor to refer to Technical Specifications.

After the plant is stabilized, the Pressurizer master pressure controller output will fail high requiring the RO to take action to manually control Pressurizer pressure with backup heaters and spray valves. The Unit Supervisor will refer to Technical Specifications.

When Pressurizer pressure is returned to program, a SG feed flow transmitter failure will require the PO to take manual control of the affected SG main feedwater control valve.

When the affected SG level is under control, an unrecoverable main feedwater control valve failure will require a reactor trip.

Upon reactor trip, a steam break will develop downstream of the MSIVs. SI will actuate; however, main steam line isolation will not occur automatically.

The steam line break will be terminated after manual actuation of main steamline isolation by the PO.

The scenario may be terminated when the crew stops HHSl pumps in ES-1.1 EOP Flow Path: E-0, ES-0.1, E-0, ES-1.1