ML071230730

Examination Outline Submittal and NRC Comments for the Monticello Initial Examination - February 2007

ML071230730
Person / Time
Site:	Monticello
Issue date:	05/03/2007
From:	Valos N NRC/RGN-III/DRS/OLB
To:
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ML070660508	List: ML071230730 ML071230735 ML071230739 ML071230740 ML071230743 ML071230745 ML071230748 ML071230773
References
50-263/07-301
Download: ML071230730 (28)

Text

EXAMINATION OUTLINE SUBMITTAL AND NRC COMMENTS FOR THE MONTICELLO INITIAL EXAMINATION - FEBRUARY 2007 Monticello Nuclear Generatina Plant Operated by Nuclear Management Company, LLC Committed to Nuclear Excellence b November 1 , 2006 L-MT-06-067 10 CFR Part 55.40 Regional Administrator, Region Ill US Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attention: Nick Valos Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Examination Outlines For the Initial Licensing Examination to Be Conducted the Week of Februaw 12,2007 Reference 1

NUREG 1021, Operator Licensing Examination Standards for Power Reactors, Revision 9 In accordance with the requirements of 10 CFR 55.40(b) (4), a power reactor facility licensee must receive NRC approval of their proposed written examination and operating tests. Further, 1 OCFR55.40 (a) requires that examinations meet the requirements of Reference

1. Therefore, enclosed for your review are the proposed examination outlines for the initial license examinations for our operator license applicants.

L In accordance with 10CFR 55.49, "Integrity of Examinations and Tests" and Reference 1 , Section ES-201 , Attachment 1 , "Examination Security and Integrity Guidelines,"

the Nuclear Management Company, LLC requests that the enclosed materials be withheld from public disclosure until after the examinations are complete.

The proposed examination outlines were prepared per the guidelines of Reference 1, sections ES-301 and ES-401. Proposed outlines have been prepared to support development, by the NMC, of examinations for four (4) Reactor Operator (RO) license candidates, one (1) Senior Reactor Operator (SRO) - Upgrade license candidate and four (4) SRO - Instant license candidates.

Enclosed are the following specific items for your review. Form ES-201-2, Examination Outline Quality Checklist Form QF-1071-01, NMC Master Security Agreement Form ES-301-1, Administrative Topics Outline RO 2807 West County Road 75 0 Monticello, Minnesota 55362-9637 Telephone:

763.295.51 51 e Fax: 763.295.1454 USNRC Page 2 Form ES-301-1 , Administrative Topics Outline SRO Form ES-301-2, Control Room/ln-Plant Systems Outline RO Form ES-301-2, Control Room/ln-Plant Systems Outline SRO - I Form ES-301-2, Control Room/ln-Plant Systems Outline SRO - U Form ES-D-1 , Scenario Outline (for scenarios 1, 2, and 3) Form ES-301-5, Transient and Event Checklist (Crews 1,2, and 3) Form ES-401-1, BWR Examination Outline Form ES-401-3, Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-4, Record of Rejected WAS Form MNGP 2007 ILT NRC Written Exam Outline Random and Systematic Process / Audit Exam Methodology L This letter makes no new commitments and no revisions to existing commitments.

Nuclear Management Company, LLC Enclosures cc: Administrator, Region 111, USNRC (w/o attachments) Project Manager, Monticello, USNRC (w/o attachments) Resident Inspector, Monticello, USNRC (w/o attachments)

- I ES-201 Examination Outline Quality Checklist Form ES-201 R I Facility:

Date of Examination:

b. Assess whether the outline was systematically and randomly prepared in accordance with Section 0.1 of ES-401 and whether all WA categories are appropriately sampled.

c. Assess whether the outline overemphasizes any systems, evolutions, or generic topics.

qM Item 1 E' N 2. S I M U L A T 0 R - Task Description IWlN 1. I a. Verify that the outline@)

fit(s) the appropriate model, in accordance with ES-401. d. Assess whether the justifications for deselected or rejected WA statements are appropriate. a. Using Form ES-301-5. verify that the proposed scenario sets cover the required number 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 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@). and that scenarios will not be repeated on subsequent days.

c. To the extent possible. assess whether the outline@) conform(s) with the qualitative and quantitative criteria specified on Form ES-3014 and described in Appendix 0. 0' o/ Y 3. w I T a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain@)

the required number of control room and implant tasks distributed among the safety functions as specified on the form (2) task repetition kcin the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s) (4) the number of new OT modified tasks meets OT exceeds the minimuns speufied on the form (5) the number of alternate path, low-power.

emergency, and RCA tasks meet the 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 (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

b. Y d P Y 'W d. Check for duolication and ovedar, amona exam sections.

Q Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. c. ~~ I e. Check the entire exam for balance of coveraae. ~ ~~ 1 f. Assess whether the exam fits the amrooriate iob level (RO or SRO). a Author b Facility Reviewer y) c NRC Chief Examiner

(#) d NRC Supervisor 9 Or i c ,- --+ V Note: # Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.

ES-201, Page 25 of 27 ES-301 Administrative Topics Outline Form ES-301-1 I Facility: Monticello Nuclear Generating Plant Date of Examination:

2/12/07 Exam Level:

RO SRO 0 I Administrative Topic (see Note) Conduct of Operations Conduct of Operations *Type Codes

& Criteria:

t I TY Pe Code* S, N MNGP-07 Operating Test Number:

Describe activity to be performed Bulk DNV Temperature Manual Calculation 2.4.47 3.4 JPM-001 Control Room Shift Turnover Checklist 2.1.3 3.0 JPM-3139-001 Daily Jet Pump Operability Check Test 01 33 2.2.12 3.0 JPM-0133-001 High Radiation Area Entry 2.3.10 2.9 J PM-4 AWI-08.04.06-002 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required. (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (13 for ROs; 14 for SROs & RO retakes) (N)ew or (M)odified from bank (21) (P)revious 2 exams (11; randomly selected)

ES-301 Administrative Topics Out1 ine Form ES-301-1 I Date of Examination:

211 2/07 Iacility: Monticello Nuclear Generating Plant Exam Level: RO 0 SRO [XI Administrative Topic (see Note) Sonduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code* S, N R. M MNGP-07 Operating Test Number:

Describe activity to be performed Bulk DMI Temperature Manual Calculation 2.4.47 3.7 JPM-001 Determine Shift Staffing 2.1.4 3.4 JPM Owl-01.06-003 Review Daily Jet Pump Operability Check Test 01 33 2.2.12 3.4 High Radiation Area Entry 2.3.10 3.3 J PM-4 Awl-08.04.06-002 Protective Action Recommendation 2.4.44 4.0 JPM-A-2-204-004 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required. *Type Codes

& Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 14 for SROs & RO retakes) (N)ew or (M)odified from bank (21) (P)revious 2 exams (11; randomly selected)

I ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 I 2112107 Facility: Monticello Nuclear Generating Plant Date of Examination: Exam Level:

RO sR0-l 0 s~0-u 0 Operating Test No.: MNGP-07 1 Control Room Systems@

(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) ___ System 1 JPM Title JPM-C.4-B.Ol.03.C-004, PERFORM THE REACTOR

a. SCRAM FUNCTIONAL TEST 0010

/ ROD DRIFT

/SCRAM N, A, S 1 201003.A2.03 3.413.7 JPM-B.06.05.06-001, REACTOR FEED PUMPS COLD

b. STARTUP N, S, L 2 259001 .A4.02 3.913.7 JPM-B.03.03-002, PERFORM SRV OPERABILITY AND c' POSITION INDICATION CHECK IAW TEST 01 12 D, A, S, L 3 239002.A4.01 4.414.4 d' 217000.A4.04 3.613.6 e' CHAMBER VACUUM BREAKER LEAKAGE N, A, S 4 N, A, S 5 JPM-B.02.03-009, MANUAL INITIATION OF RClC JPM-B.04.02-006, DRYWELL TO SUPPRESSION OPERATIONAL CHECK 223001 .A3.02 3.413.4 JPM-B.09.08-001, MANUALLY START NO. 11 EDG f. (CONTROL ROOM ACTIONS)

P, s 6 264000.A4.04 3.713.7 JPM-B.05.11-001, PERFORM THE SERVICE WATER

g. EFFLUENT MONITOR FUNCTIONAL TEST D, S 7 h. STANDBY LINEUP D, S 9 272000.A4.02 3.013.0 JPM-B.04.02-002, RESTORE SBGT TO A NORMAL 261000.A3.01 3.313.2 In-Plant Systems@

(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) . I. JPM-B.08.01.02-05-001, TRANSFER EDG COOLING FROM EDG-ESW TO SERVICE WATER 295018.AA1.01 3.313.4 COMPRESSORS FOR MAIN AIR SUPPLY TO OUTBOARD MSIVS . JPM-B.02.04-03, STARTUP OF AIR DRIVEN 239001 .K1.12 2.512.6 , JPM-C.5-3101-002, DEPRESSURIZE THE SCRAM AIR K' @ HEADER LOCALLY PER C.5-3101, PART B 295037.EA1.03 4.114.1 All RO and SRO-I control room (and in-plant) systems must be different and serve 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 room.

N,R I 4

• Type Codes Criteria for RO I SRO-I I SRO-U (A)Iternate path 4-6 14-6 I 2-3 (C)ontrol room (D)irect from bank 19 I <a I 14 (E)mergency or abnormal in-plant 21 I21 I21 (L)ow-Power I Shutdown 21 /21/21 (N)ew or (M)odified from bank including 1(A) 22 122 I21 (P)revious 2 exams 13 113 112 (randomly selected) (R)CA 21 / 21 I21 (S)imulator ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 ] I Facility: Monticello Nuclear Generating Plant Date of Examination:

2/12/07 I Exam Level: RO 0 SRO-l SRO-u 0 Operating Test No.: MNGP-07 I Control Room Systems* (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title I Safety Type 'Ode* Function JPM-C.4-6.01.03.C-004, PERFORM THE REACTOR a' SCRAM FUNCTIONAL TEST 0010

/ ROD DRIFT

/ SCRAM N, A, s 1 b' POSITION INDICATION CHECK IAW TEST 01 12 D, A, s, L 3 201003.A2.03 3.413.7 JPM-6.03.03-002, PERFORM SRV OPERABILITY AND 239002.A4.01 4.414.4 c. 217000.A4.04 3.6/3.6 d' CHAMBER VACUUM BREAKER LEAKAGE N, A, s 4 JPM-6.02.03-009, MANUAL INITIATION OF RClC JPM-B.04.02-006, DRYWELL TO SUPPRESSION OPERATIONAL CHECK 223001 .A3.02 3.4/3.4 JPM-6.09.08-001, MANUALLY START NO. 11 EDG e. CONTROL ROOM ACTIONS1 264000.A4.04 3.713.7 JPM-6.05.11-001, PERFORM THE SERVICE WATER f' EFFLUENT MONITOR FUNCTIONAL TEST D, S 7 272000.A4.02 3.0l3.0 JPM-B.04.02-002, RESTORE SBGT TO A NORMAL g' STANDBY LINEUP D, S 9 I 261000.A3.01 3.313.2 I I In-Plant Systems@

(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U) ' JPM-6.08.01.02-05-001, TRANSFER EDG COOLING FROM D 8 1. EDG-ESW TO SERVICE WATER 2950 18.AA1.0 1 3.3l3.4 COMPRESSORS FOR MAIN AIR SUPPLY TO OUTBOARD MSIVS JPM-6.02.04-03, STARTUP OF AIR DRIVEN N, R 4 J' 239001.K1.12 2.512.6 HEADER LOCALLY PER (2.5-3101, PART B JPM-C.5-3101-002, DEPRESSURIZE THE SCRAM AIR D, R, E 1 k. 295037.EA1.03 4.114.1 All RO and SRO-I control room (and in-plant) systems must be different and serve 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 room.

@

• Type Codes I Criteria for RO I SRO-I / SRO-u (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power

/ Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (RFA (S)im ulator 4-6 14-6 I 2-3 19 I <a I 54 21 I21 127 21 / 21 I21 22 I 22 I 21 13 / 13 112 (randomly selected) 21 I21 I21 ES-301. Paae 23 of 27 ES-301 Control Roomh-Plant Systems Outline Form ES-301-2 I 211 2107 -acility:

Monticello Nuclear Generating Plant Date of Examination:

ixam Level: RO 0 sRO-1 0 sR0-u Operating Test No.: MNGP-07 2ontrol Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) Safety Type 'Ode* Function System I JPM Title JPM-C.4-B.Ol.03.C-004, PERFORM THE REACTOR a' SCRAM FUNCTIONAL TEST 0010 I ROD DRIFT I SCRAM N, A, S 1 b. POSITION INDICATION CHECK IAW TEST 01 12 D, A, S, L 3 c' STANDBY LINEUP D, s 9 201003.A2.03 3.413.7 JPM-B.03.03-002, PERFORM SRV OPERABILITY AND 239002.A4.01 4.414.4 JPM-B.04.02-002, RESTORE SBGT TO A NORMAL 261000.A3.01 3.313.2 I I h. In-Plant Systems@ (8 for RO); (7 for SRO-I);

(2 or 3 for SRO-U) . JPM-B.09.08-008, NO. 11 EDG OPERATION WITHOUT D, E 6 I. DIVISION 1 BAlTERY 295004.AA1.02 3.814.1 COMPRESSORS FOR MAIN AIR SUPPLY TO OUTBOARD MSIVS 239001 .K1.12 2.512.6 JPM-B.02.04-03, STARTUP OF AIR DRIVEN N, R 4 J. k. @ All RO and SRO-I control room (and in-plant) systems must be different and serve 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 room. *Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 14-6 12-3 (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 (C)ontrol room (D)irect from bank 19 I18 114 21 I21 121 21 121 I21 22 I 22 I 21 13 I13 I4 (randomly selected) 21 I21 I21 ES-301, Page 23 of 27 Appendix D Scenario Outline Form ES-D-1 13 Facility:

MNGP Scenario No.: NRC-01 Op-Test No.: MNGP-07 Examiners: Operators:

Turnover: Perform Test 0008 MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST. Event No. 1 - 7 Initial Conditions:

100% reactor power with RClC inoperable due to planned maintenance on the tritdthrottle valve. Test 0008 MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST is scheduled to be performed.

I5 2 I6 Malf. No. MSOGA CH07B AP07 TU03G TU03H SWOlA FW20A RROlA Event Tvm* C (BOP) M (ALL) M (ALL) M (ALL) C (BOP) Event Description Perform Test 0008 MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST. The

'A' Outboard MSIV will fail to close when required by test resulting in an ITS LCO. CRD Flow Control Valve Fails Closed. The STBY FCV will be placed in service when High CRD Temperature annunciator alarms. Inadvertent ADS timer actuation.

ADS taken to inhibit. ITS LCO Main Turbine Vibrations, lower reactor power to lower / stabilize vibrations.

RBCCW system degradation.

RBCCW Pump Trip. Standby pump fails to auto start.

Loss of Air to 'A' Feed Reg. Valve.

FRV Lockup and recovery. Recirc line break inside primary containment.

Scram. Unable to spray DAW. EOP 1 100 entry (RPV Control).

EOP 1200 entry (Primary Containment Control). EOP 2002 entry (Blowdown)

Failure of 1 ADS SRV to open * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Facility:

MNGP Scenario No.: NRC-02 Op-Test No.: MNGP-07 Examiners: Operators:

I I Initial Conditions:

89% reactor power. Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES, is scheduled to be completed.

I Turnover:

Complete Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES and return to 100% power. Event No. 1 - - 2 3 - Malf. No. TCO6B - - CH08A TC05A RR02C PP06 RR07 RR08 PP05A PP05C CH16 Event Type* N (BOP) R (RO) C (BOP) (SW M (ALL) Event Description ComDlete Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES The #2 Turbine Bypass Valve will not open as required by the test resulting in an ITS LCO. 11 CRD Pump trip. Start 12 CRD pump. EPR Oscillations and placing the MPR in control. RPV press inst fails upscale, half scram fails to be initiated. ITS LCO. 12 Recirc pump motor bearing temp and vibrations high and subsequent shutdown of pump. ITS LCO. Group 1 isolation, ATWS EOP-2007 (Failure to Scram) entry. All rods inserted, EOP-1100 (RPV Control) entry and RPV parameter recovery I * (N)ormal, (R)eactivity, (I)nstrument, (C)ornponent, (M)ajor Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Event No. 1 2 3 4 5 6 7 Facility:

MNGP Scenario No.: NRC-03 OpTest No.: MNGP-07 Malf. No. CH02 N/A SL02A N113D FW15B HPOl RU07 Examiners: Operators:

Initial Conditions: Reactor power is -95% with APRM 2 inoperable.

Event Type* c (RO) N (BOP) I (RO) M (ALL) Event Description Withdraw control rod with raised drive pressure. Perform Test 0255-03-IA-1-1, CORE SPRAY LOOP A QUARTERLY PUMP AND VALVE TESTS. SBLC Squib Valve Loss of Continuity ITS LCO APRM 4 Fails Upscale. Bypass APRM and reset half scram. 12 RFP bearing high temperature, shutdown 12 RFP. Lower reactor power to support removal of 12 RFP. HPCl inadvertent initiation and shutdown.

HPCl will be inoperable.

ITS LCO. RWCU Leak, un-isolable, EOP-1300 Entry, Scram Blowdown, EOP 2002 Entry. I * (N)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39 Facilitv:

MNGP Date of Exam: 02/12/2007 RO WA Category Points SRO-Only Points A2 G* Total Tier Group K K K K 1 K 1 K A A A I A G 1234561234*

Total 1. 1 343 33 4 20 4 3 7 Emergency at Abnormal Plant Tier Evolutions Totals 2 111 N/A 2 1 N/A 1 7 2 1 3 454 54 5 27 6 4 10 1 2123222343 2 26 3 2 5 Plant 2 11211111111 12 2 1 3 2. 3. Generic Knowledge and Abilities Categories Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. Ensure that at least two topics from every 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). 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 k1 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. Systems/evolutions 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 the elimination of inappropriate WA statements. 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. Absent a plant-specific priority, only those WAS 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.

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

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 10 CFR 55.43. ES-401, Page 16 of 33 Form ES401-1 295018 Partial or Total Loss of CCW / 8 EK1.07 Shutdown margin ES-401, Page 17 OF 33 c:\2007 It nrc exam\nrc fons\75 day submittal\fam es-401-1 bwr examination outline.doc ES-401 3 Fo~ ES-401-1 ES-401 Bt Emergency and Abnom E/APE # / Name / Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 8 4 295003 Partial or Complete Loss of AC I6 295004 Partial or Total Loss of DC Pwr I6 295005 Main Turbine Generator Trip

/ 3 295006 SCRAM I 1 295016 Control Room Abandonment

/ 7 29501 8 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I8 I I I 295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc I 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure I3 295026 Suppression Pool High Water Temp. / 5 295027 High Containment Temperature I5 295028 High Drywell Temperature I 5 111 111 295030 Low Suppression Pool Wtr Lvl I5 Ill 295031 Reactor Low Water Level I2 !I1 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate

/ 9 I Ill 600000 Plant Fire On Site I8 ! Examination Outline Plant Evolutions - Tier l/Group 1 (RO Form ES-40 1 WA Topic@) IR

1. M2.02 Reactor power I pressure I and level 4.3 1 2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during emer enc o rations. 2.2.13 Knowledge of tagging and clearance rocedures AA2.05 Entry conditions of emergency plan 4.6 1 Y EA2.01 Reactor Dressure 4.2 1 x EA2.02 Suppression pool level 3.9 1 N/A MNGP N/A N/A 2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status 3,0 , X - - 0 4 3 Group Point Total: 7 c:\2007 dl nrc exarn\nrc forms\75 day wbm~l\rOrm es-401-1 twr examinaton wtline.doc 1014/2006 9 16 AM ES-401 BWR Examination Outline FM ES-401-: Emergency and Abnormal Plant Evolutions - Tier l/Group 2 E/APE # / Name / Safety Function K K K'A A KIA Topic(s) IR # 12312 295002 Loss of Main Condenser Vac

/ 3 295007 High Reactor Pressure I3 295008 High Reactor Water Level 12 295009 Low Reactor Water Level I2 295010 High Drywell Pressure I5 29501 1 High Containment Temp / 5 295012 High Drywell Temperature 15 X 'I 295034 Secondary Containment K/A Category Point Totals U1.03 RPS 3.4 I 1 U2.03 RWCU blowdown flow 2.9 ~ 1 I U/A MNGP 1 N/A/ NIA 2.4.8 Knowledge of how the event based emergency

/ sbnormal operating procedures are used in conjunction I 3.0 ~ 1 ~ith the symptom based EOPs 1 9K1.05 Fuel thermal limits 3.7 1 4K2.08 Neutron monltonng System 3.6 1 I AK3.05 Reactor water level response EA1.04 SBGT/ FRVS 4.2 I 1 I 1 , I Grow Point Total:

17 ES-401, Page 18 of 33 ES-401 BWR Examination Outline Form ES-401-I Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO E/APE # / Name / Safety Function c:\2W7 lit nrc exarn\nrc fwms\75 day submittal\fm es-401-1 bwr examinati outline.doc b 10/4/2006 9: 16 AM ES-401 Form ES-401-3 System #I Name - I/ 21 2000 RPS x 1x 215003 IRM x- 215004 Source Range Monitor X 215005 APRM

/ LPRM I ~ X I I 217000 RClC - 218000 ADS

~ XI 223002 PClSINuclear Steam Supply Shutoff I/ l X 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS X i 262001 AC Electrical Distribution I I,,; X I 1 262002 UPS (ACIDC) 263000 DC Electncal Distribution 264000 EDGs I 300000 Instrument Air 400000 Component Cooling Water ~~ II K/A Category Point Totals K/A Topic@) IR

1. K2.02 Vafves 1 2.5 1 1 K3.02 Reactor water level , 3.2 ~ 1 N/A MNGP I N/A ~ N/A K5.01 Indicationsof pump cavitation 1 2.6 i 1 N/A MNGP K6.03 A C power K4.07 RWCU isolation A1.09 Individual relay status I 2.7 I ~5.02 Specific logic arrangements I 3.3 j ' A2.04 Up scale or down Scale trips 1 3.7 1 1 A3.03 RPSstatus I 1 1 A4.03 APRM back panel switches, meters and indicabng lights A2.07 Recirc flow channels flow 3.2 mismatch 2.1.24 Ability to obtain and interpret 2.8 I stabon eledncal and mechanical 1 drawinqs K1.02 Low pressure core spray 4.0 1 2.9 1 K1.11 Containment atmosphere sampling 1 ~ K3.03 Ability to rapidly depressurize

' 4.3 the reactor K4.10 Three element control 3.4 1 1 A4.07 System flow 3.1 A1.07 SBGT train temperature i 2.8 K6.01 D.C. power 3.1 1 A2.01 Under voltage

~ A2.01 Grounds A3.01 Meters, dials, recorders, alarm% and indicating lights A3.04 Operation of the govenor control system on frequency and voltaqe control A4.01 Pressure gauges 2.1.28 Knowledge of the purpose and function of major system components and controls 2.6 1 1 2.8 3.2 I '1 3.1 I 3.2 1 Group Point Total I 26 ES-401, Page 19 of 33 ES-401 BWR Examination Outline Plant Systems - Tier 2/Group 1 (R0d;;;;;j)

Form ES401-I System # / Name 239002 SRVS I 263000 DC Electrical Distnbution 264000 EDGs 300000 Instrument Air enerator I1 -- 400000 Component Cooling Water I , ! WA Category Point Totals ES401 BWR Examination 0 Plant Systems - Tier Z/Group ES-401- System # / Name K K K KIK K A A 11/213/415/6/112 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment I 239001 Main and Reheat Steam 239003 MSlV Leakage Control 241000 Reactornurbine Pressure Regulator 245000 Main Turbine Gen I Aux - 256000 Reactor Condensate 259001 Reactor Feedwater I 11 1 WA Topic(s) , IR 1 K3.01 Ability to move control rods K4.05 Rod position indication N/A MNGP N/A MNGP I K5.02 Feedback signals I 1 +H I 1 I I +H K6.04 APRM reference channel I 2.8 ~ I I A1.02 Containment/drywell temperature I 3.4 3.1 A2.02 Loss of refueling platform air system N/A MNGP X A3.01 Turbine tnp 3.6 x A4.03 Hotwell level controls 3.2 2.2.2 Ability to manipulate the console controls as required to operate the facility 4,0 between shutdown and designated power levels X TI system 3.6 j K1.09 Pnmary containment isolabon I TH m.04 Control room pressure I 2.8 1 WA Category Point Totals:

11:1/2j1j111 11 11 P ES-401, Page 20 of 33 1 11 11 I Group Point Total ! 1; ES-401 9 Form ES-401-1 FOrm ES401- 0 ES-401 BWR Examinabon Outline Plant Systems - Tier 2/Group 2 (RO SRO) 286000 Fire Prot K/A Category Point Totals c:\2007 ik nK exam\nK fums\75 dav submittal\fam es-401-1 bwr examinatan wtline.doc 10/412006 9.16 AM

--__ Facilitv:

MNGP Date of Exam: 0211 a2007 ~ Category 1. Conduct of Operations

2. Equipment Control 3. Radiation Control 4. Emergency Procedures I Plan Topic 2.1.20 I Ability to execute procedure steps 2.1.32 I Abilitv to exDlain and amlv svstem limits and Drtautions I 3.4 I 11 I 2.8 1 Ability to obtain and interpret station reference materials such as graphs / monographs

/ and tables which contain performance data 2.1 .25 2.1.4 Knowledge of shift staffing requirements 3.4 1 I 3 1 Subtotal 2.2.27 ' Knowledge of the refwling process 2.6 1 2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4 1 3.7 1 2.2.25 2.2.24 Ability to analyze the affect of maintenance activities on LCO status 3.8 1 Knowledge of bases in tech specs for limiting conditions for operations and safety limits I I I I 2 2 Subtotal 2.5 1 2.6 1 Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized Knowledge of 10 CFR: 20 and related facility radiation conbol requirements

2. 3-4 2.3.1 2.3.11 Ability to control radiation releases 3.2 1 3.0 1 Knowledge of 10 CFR: 20 and related facility radiation control 2.3.1 requirements Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33 ES-301 Transient and Event Checklist Form ES-301-5 Facility:

MNGP Date of Exam: 2/12/07 Operating Test No: M N GP-07 Scenarios E V E N T T Y P E RX 1 2 I 3 4 T 0 CREW CREW T POSITION POSITION A A BL TO CP M I N I M U CREW CREW POSITION 1 POSITION - S R 0 RO El' 0 SRO-I SRO-U NOR I/C MAJ 0 Fila RO TS RX NOR I/C SRO-I 0 0 SRO-U MAJ TS RO 0 0 SRO-I SRO-U RO RX NOR I/C MAJ TS RX 0 0 SRO-U 0 SRO-I Instructions:

NOR I/C MAJ TS - 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type:

TS are not applicable for RO applicants.

ROs must serve 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 (VC) malfunctions and one major transient, in the ATC position. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. r) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

2. 3. ES-301. Paae 26 of 27 ES-301 Transient and Event Checklist Form ES-301-5 Facility:

MNGP Date of Exam: 2/12/07 Operating Test No: MNGP-07 Instructions:

Scenarios 2 3 4 CREW CREW CREW POSITION POSITION POSITION - S R 0 A T C -gqyTgqT 0 oc B 0 P - 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type: TS are not applicable for RO applicants. ROs must serve 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 (IC) malfunctions and one major transient, in the ATC position.

Reactivity manipulations may be conducted under normal or controlled abnormal 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. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns. 2. 3. ES-301. Paae 26 of 27 ES-301 Transient and Event Checklist FOITII ES-301-5 Facility:

MNGP Date of Exam: 2/12/07 Operating Test No: MNGP-07 Scenarios E v E N T T Y P E RX NOR 3 &I POSITION A i M I N I M U CREW CREW POSITION 1 POSITION CREW POSITION CPOC - B 0 P - S R 0 - S R 0 - S R 0 A T C RO Qq SRO-I I I I I II I I/C MAJ 0 SRO-U 0 0 RO TS RX NOR I/C SRO-I SRO-U m3 0 0 EIq 0 0 RO SRO-I SRO-U RO SRO-I MAJ TS RX NOR I/C MAJ TS RX NOR I/C MAJ 0 SRO-U TS - Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type: TS are not applicable for RO applicants.

ROs must serve 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 (VC) malfunctions and one major transient, in the ATC position. Reactivity manipulations may be conducted under normal or controlled abnormal 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-I basis. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns. 2. 3.

MONTICELLO 2007 INITIAL LICENSE EXAM OPERATING OUTLINE COMMENTS

1. 1. - 2. Source Admin JPM-001 Control Room JPM-B.04.02-002 Comment There is no WA listed associated with Section 2.1 of the WA catalog. Admin JPMs associated with Conduct of Operations are required to have a WA from Section 2.1 of the WA catalog. NOTE: This comment applies to both the RO and SRO outlines.

~~ The Importance Ratings for the ROlSRO should be listed as 3.2l3.3 instead of 3.313.2. - NOTE: This comment applies to the RO, SRO-I, and SRO-U outlines.

Resolution Comment incorporated.

The WA for the JPM was changed to 2.1.25. Comment incorporated.