ML071230730

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Examination Outline Submittal and NRC Comments for the Monticello Initial Examination - February 2007
ML071230730
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/03/2007
From: Valos N
NRC/RGN-III/DRS/OLB
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ML070660508 List:
References
50-263/07-301
Download: ML071230730 (28)
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Text

EXAMINATION OUTLINE SUBMITTAL AND NRC COMMENTS FOR THE MONTICELLO INITIAL EXAMINATION - FEBRUARY 2007

Monticello Nuclear Generatina Plant Committed to Nuclear Excellence Operated by Nuclear Management Company, LLC 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 L operating tests. Further, 10CFR55.40 (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.

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 L

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 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-201-2 Facility: Date of Examination:

Item 1 Task Description

1. I a. Verify that the outline@)fit(s) the appropriate model, in accordance with ES-401. IWlN R b. Assess whether the outline was systematically and randomly prepared in accordance with I 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.

q M E '

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

0

2. 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.

S and major transients.

o/

I M b. Assess whether there are enough scenario sets (and spares) to test the projected number U 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 L

A at least one new or significantly modified scenario, that no scenarios are duplicated Y T from the applicants' audit test@).and that scenarios will not be repeated on subsequent days.

0 c. To the extent possible. assess whether the outline@)conform(s) with the qualitative R and quantitative criteria specified on Form ES-3014 and described in Appendix 0.

3. 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 w distributed among the safety functions as specified on the form I (2) task repetition kcin the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants' audit test(s) Y (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 d (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. P
b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. Y
c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. ' W
d. Check for duolication and ovedar, amona exam sections.

~~

Q I e. Check the entire exam for balance of coveraae.

~ ~~

1 f. Assess whether the exam fits the amrooriate iob level (ROor 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 Operating Test Number:

MNGP-07 I

Administrative Topic TYPe Describe activity to be performed (see Note) Code*

Bulk DNV Temperature Manual Calculation Conduct of Operations JPM-001 2.4.47 3.4 Control Room Shift Turnover Checklist Conduct of Operations JPM-3139-001 2.1.3 3.0 Daily Jet Pump Operability Check Test 0133 JPM-0133-001 S, N 2.2.12 3.0 High Radiation Area Entry JPM-4 AWI-08.04.06-002 2.3.10 2.9 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.

t *Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (13 for ROs; 14 for SROs & RO retakes)

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

(P)revious 2 exams (11; randomly selected)

ES-301 Administrative Topics Out1ine Form ES-301-1 I Iacility: Monticello Nuclear Generating Plant Date of Examination: 2112/07 Exam Level: RO 0 SRO [XI Operating Test Number:

MNGP-07 Administrative Topic TYPe Describe activity to be performed (see Note) Code*

Bulk DMI Temperature Manual Calculation Sonduct of Operations JPM-001 2.4.47 3.7 Determine Shift Staffing Conduct of Operations JPM Owl-01.06-003 2.1.4 3.4 Review Daily Jet Pump Operability Check Test Equipment Control S,N 0133 2.2.12 3.4 High Radiation Area Entry Radiation Control R. M J PM-4 Awl-08.04.06-002 2.3.10 3.3 Protective Action Recommendation Emergency Plan JPM-A-2-204-004 2.4.44 4.0 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 (53for 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 Facility: Monticello Nuclear Generating Plant Date of Examination: 2112107 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 0112 D, A, S, L 3 239002.A4.01 4.414.4 JPM-B.02.03-009, MANUAL INITIATION OF RClC N, A, S 4 d' 217000.A4.04 3.613.6 JPM-B.04.02-006, DRYWELL TO SUPPRESSION e' CHAMBER VACUUM BREAKER LEAKAGE N, A, S 5 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 272000.A4.02 3.013.0 JPM-B.04.02-002, RESTORE SBGT TO A NORMAL
h. STANDBY LINEUP D, S 9 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

. JPM-B.02.04-03, STARTUP OF AIR DRIVEN COMPRESSORS FOR MAIN AIR SUPPLY TO OUTBOARD MSIVS 239001.K1.12 2.512.6 N,R I 4

, JPM-C.5-3101-002, DEPRESSURIZETHE 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.

  • 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 I14 (E)mergency or abnormal in-plant 21 I 2 1 I 2 1 (L)ow-Power I Shutdown 21 / 2 1 / 2 1 (N)ew or (M)odified from bank including 1(A) 22 122 I 2 1 (P)revious 2 exams 13 113 112 (randomly selected)

(R)CA 21 / 21 I 2 1 (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)

I System / JPM Title JPM-C.4-6.01.03.C-004, PERFORM THE REACTOR Type 'Ode*

Safety Function a' SCRAM FUNCTIONAL TEST 0010 / ROD DRIFT / SCRAM N, A, s 1 201003.A2.03 3.413.7 JPM-6.03.03-002, PERFORM SRV OPERABILITY AND b' POSITION INDICATION CHECK IAW TEST 01 12 D, A, s, L 3 239002.A4.01 4.414.4 JPM-6.02.03-009, MANUAL INITIATION OF RClC

c. 217000.A4.04 3.6/3.6 N, A, s 4 JPM-B.04.02-006, DRYWELL TO SUPPRESSION d' CHAMBER VACUUM BREAKER LEAKAGE 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) 1.

JPM-6.08.01.02-05-001, TRANSFER EDG COOLING FROM D 8 EDG-ESW TO SERVICE WATER 2950 18.AA1.01 3.3l3.4 JPM-6.02.04-03, STARTUP OF AIR DRIVEN N, R 4 J' COMPRESSORS FOR MAIN AIR SUPPLY TO OUTBOARD MSIVS 239001.K1.12 2.512.6

k. JPM-C.5-3101-002, DEPRESSURIZETHE SCRAM AIR D, R, E 1 HEADER LOCALLY PER (2.5-3101, 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.

  • Type Codes I Criteria for RO I SRO-I / SRO-u (A)lternate path 4-614-6I 2-3 (C)ontrol room (D)irect from bank 19 I <a I 54 (E)mergency or abnormal in-plant 21 I 2 1 127 (L)ow-Power / Shutdown 21 / 21 I 2 1 (N)ew or (M)odified from bank including 1(A) 22 I 22 I 21 (P)revious 2 exams 13 / 13 112 (randomly selected)

(RFA 21 I 2 1 I 2 1 (S)imulator ES-301. Paae 23 of 27

ES-301 Control Roomh-Plant Systems Outline Form ES-301-2 I

-acility: Monticello Nuclear Generating Plant Date of Examination: 2112107 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 System I JPM Title Type Ode*

Function 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 201003.A2.03 3.413.7 JPM-B.03.03-002, PERFORM SRV OPERABILITY AND

b. POSITION INDICATION CHECK IAW TEST 0112 D, A, S,L 3 239002.A4.01 4.414.4 JPM-B.04.02-002, RESTORE SBGT TO A NORMAL c STANDBY LINEUP D, s 9 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)

.I. JPM-B.09.08-008, NO. 11 EDG OPERATION WITHOUT D, E 6 DIVISION 1 BAlTERY 295004.AA1.02 3.814.1 JPM-B.02.04-03, STARTUP OF AIR DRIVEN N, R 4 J. COMPRESSORS FOR MAIN AIR SUPPLY TO OUTBOARD MSIVS 239001.K1.12 2.512.6 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 (C)ontrol room (D)irect from bank 19 I 1 8 1 1 4 (E)mergency or abnormal in-plant 21 I 2 1 121 (L)ow-Power I Shutdown 21 121 I21 (N)ew or (M)odified from bank including 1(A) 22 I 22 I 21 (P)revious 2 exams 13 I 1 3 I 4 (randomly selected)

(R)CA 21 I 2 1 I 2 1 (S)imulator ES-301,Page 23 of 27

Appendix D Scenario Outline Form ES-D-1 Facility: MNGP Scenario No.: NRC-01 Op-Test No.: MNGP-07 Examiners: Operators:

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.

Turnover:

-Perform Test 0008 MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST.

Event Malf. Event Event 7

No. No. Tvm* Description 1 MSOGA 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.

2 CH07B CRD Flow Control Valve Fails Closed. The STBY FCV will be placed in service when High CRD Temperature annunciator alarms.

13 AP07 Inadvertent ADS timer actuation. ADS taken to inhibit.

ITS LCO TU03G Main Turbine Vibrations, lower reactor power to lower /

TU03H stabilize vibrations.

I5 SWOlA C (BOP) RBCCW system degradation. RBCCW Pump Trip.

Standby pump fails to auto start.

I6 FW20A Loss of Air to A Feed Reg. Valve. FRV Lockup and recovery.

RROlA M (ALL) Recirc line break inside primary containment.

Scram. Unable to spray DAW.

M (ALL) EOP 1100 entry (RPV Control).

M (ALL) EOP 1200 entry (Primary Containment Control).

EOP 2002 entry (Blowdown)

C (BOP) 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 II Facility: MNGP Scenario No.: NRC-02 Op-Test No.: MNGP-07 Examiners: Operators:

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

Turnover:

Complete Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES and return to 100% power.

Event Malf. Event Event

--1 No. No.

TCO6B Type*

N (BOP)

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.

2 CH08A 11 CRD Pump trip. Start 12 CRD pump.

3 TC05A EPR Oscillations and placing the MPR in control.

RR02C RPV press inst fails upscale, half scram fails to be initiated.

PP06 ITS LCO.

RR07 R (RO) 12 Recirc pump motor bearing temp and vibrations RR08 C (BOP) high and subsequent shutdown of pump.

(SW ITS LCO.

PP05A M (ALL) Group 1 isolation, ATWS EOP-2007 (Failure to Scram)

PP05C entry.

CH16 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 Facility: MNGP Scenario No.: NRC-03 OpTest No.: MNGP-07 Examiners: Operators:

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

Event Malf. Event Event No. No. Type* Description 1 CH02 c (RO) Withdraw control rod with raised drive pressure.

2 N/A N (BOP) Perform Test 0255-03-IA-1-1, CORE SPRAY LOOP A QUARTERLY PUMP AND VALVE TESTS.

3 SL02A SBLC Squib Valve Loss of Continuity ITS LCO 4 N113D I (RO) APRM 4 Fails Upscale. Bypass APRM and reset half scram.

5 FW15B 12 RFP bearing high temperature, shutdown 12 RFP.

Lower reactor power to support removal of 12 RFP.

6 HPOl HPCl inadvertent initiation and shutdown. HPCl will be inoperable.

ITS LCO.

7 RU07 M (ALL) 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 Tier Group K 1

K 2

K 3

1 1 K K K A A A A G 4 5 6 1 2 3 4

  • I Total A2 G* Total
1. 1 3 4 3 3 3 4 20 4 3 7 Emergency at 2 1 1 1 N/A 2 1 N/A 1 7 2 1 3 Abnormal Plant Tier Evolutions Totals 4 5 4 5 4 5 27 6 4 10 1 2 1 2 3 2 2 2 3 4 3 2 26 3 2 5 2.

Plant 2 1 1 2 1 1 1 1 1 1 1 1 12 2 1 3

3. Generic Knowledge and Abilities Categories Note: 1. 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).
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 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.
3. 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.
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 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.
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 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 I t nrc exam\nrc fons\75 day submittal\fam es-401-1bwr examination outline.doc

ES-401 3 F o ES-401-1

~

ES-401 Bt ! Examination Outline Form ES-40 1- 1 E/APE # / Name / Safety Function Emergency and Abnom Plant Evolutions - Tier l/Group 1(RO WA Topic@) IR #

295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 8 4 295003 Partial or Complete Loss of AC I6 M 2 . 0 2 Reactor power Ipressure Iand level 4.3 1 295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Trip / 3 295006 SCRAM I 1 2.4.23 Knowledge of the bases for prioritizing 295016 Control Room Abandonment / 7 emergency procedure implementation during emer enc o rations.

295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I8 I I I 2.2.13 Knowledge of tagging and clearance rocedures 295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc I 8 AA2.05 Entry conditions of emergency plan 4.6 1 295024 High Drywell Pressure / 5 295025 High Reactor Pressure I 3 Y EA2.01 Reactor Dressure 4.2 1 295026 Suppression Pool High Water x EA2.02 Suppression pool level 3.9 1 Temp. / 5 295027 High Containment Temperature I 5 N/A MNGP N/A N/A 295028 High Drywell Temperature I 5 X

2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or 3,0 ,

1 1 1 component status 1 1 1 295030 Low Suppression Pool Wtr Lvl I 5 I l l 295031 Reactor Low Water Level I 2

! I 1 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 I l I

l 600000 Plant Fire On Site I 8 0 4 3 Group Point Total: 7 c:\2007 d l nrc exarn\nrc forms\75 day wbm~l\rOrmes-401-1twr examinaton wtline.doc 1014/2006 9 16 AM

ES-401 BWR Examination Outline F M 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 #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 X U1.03 RPS 3.4 I 1 295007 High Reactor Pressure I 3 I U2.03 RWCU blowdown flow 2.9 1 295008 High Reactor Water Level 12 ~

295009 Low Reactor Water Level I 2 I 295010 High Drywell Pressure I 5 29501 1 High Containment Temp / 5 U/A MNGP 1 N/A/ NIA 2.4.8 Knowledge of how the event based emergency /

295012 High Drywell Temperature 1 5 sbnormal operating procedures are used in conjunction I 3.0 ~ 1

~ i t the h 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 295034 Secondary Containment I

1 I

K/A Category Point Totals Grow Point Total: 1 7 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 b c:\2W7 lit nrc exarn\nrc fwms\75 day submittal\fm es-401-1 bwr examinati outline.doc 10/4/20069:16 AM

ES-401 Form ES-401-3 K/A Topic@) IR #

System # I Name 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 I / A1.09 Individual relay status I 2.7 I 11 212000 RPS 1x x - ~ 5 . 0 2Specific logic arrangements I 3.3 j '

215003 IRM 215004 Source Range Monitor 215005 APRM / LPRM I x-X A2.04 Up scale or down Scale trips A3.03 RPSstatus A4.03 APRM back panel switches, I

1 3.7 1 1 meters and indicabng lights

~ X A2.07 Recirc flow channels flow 3.2 I

mismatch I 2.1.24 Ability to obtain and interpret 2.8 I 217000 RClC stabon eledncal and mechanical 1

- drawinqs K1.02 Low pressure core spray 4.0 1 218000 ADS ~ XI I / K1.11 Containment atmosphere 2.9 1 223002 PClSINuclear Steam Supply Shutoff l sampling 1 ~

K3.03 Ability to rapidly depressurize ' 4.3 X

239002 SRVs the reactor K4.10 Three element control 3.4 1 1 259002 Reactor Water Level Control A4.07 System flow 3.1 X A1.07 SBGT train temperature 2.8 261000 SGTS i i K6.01 D.C. power 3.1 1 262001 AC Electrical Distribution I I , , X ;

262002 UPS (ACIDC)

I A2.01 Under voltage 2.6 1 1 1 A2.01 Grounds 263000 DC Electncal Distribution

~

2.8 A3.01 Meters, dials, recorders, alarm% 3.2 I and indicating lights A3.04 Operation of the govenor 264000 EDGs control system on frequency and ' 1 voltaqe control 3.1 I A4.01 Pressure gauges 300000 Instrument Air I 2.1.28 Knowledge of the purpose and

~~

400000 Component Cooling Water function of major system components 3.2 1 I I and controls K/A Category Point Totals Group Point Total I 26 ES-401, Page 19 of 33

ES-401 BWR Examination Outline Form ES401-I Plant Systems - Tier 2/Group 1(R0d;;;;;j)

System # / Name 239002 SRVS 263000 DC Electrical Distnbution I

264000 EDGs enerator I 1 --

300000 Instrument Air 400000 Component Cooling Water I WA Category Point Totals

ES401 BWR Examination 0 ES-401-Plant Systems - Tier Z/Group K K K KIK K A A WA Topic(s) , IR System # / Name 11/213/415/6/112 1 K3.01 Ability to move control rods K4.05 Rod position indication N/A MNGP N/A MNGP I K5.02 Feedback signals

+H I 1

I 1

I

+H K6.04 APRM reference channel I

I 2.8

~ I I A1.02 Containment/drywell temperature I 3.4 233000 Fuel Pool Cooling/Cleanup A2.02 Loss of refueling platform air 3.1 234000 Fuel Handling Equipment system IT I 239001 Main and Reheat Steam N/A MNGP 239003 MSlV Leakage Control 241000 Reactornurbine Pressure Regulator X A3.01 Turbine tnp 3.6 245000 Main Turbine Gen I Aux x A4.03 Hotwell level controls 3.2 256000

- Reactor Condensate 2.2.2 Ability to manipulate the console 259001 Reactor Feedwater controls as required to operate the facility X 4,0 I between shutdown and designated power 1 1 1 levels K1.09 Pnmary containment isolabon system 3.6 j TH I

m.04 Control room pressure I 2.8 1 P

WA Category Point Totals: 11:1/2j1j111 11 1 1 1 1 11 I Group Point Total  ! 1; ES-401, Page 20 of 33

ES-401 9 Form ES-401-1 ES-401 BWR Examinabon Outline FOrm ES401-0 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 A M

Facilitv: MNGP

~

Date of Exam: 0211a2007 Category 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 1 1 I Ability to obtain and interpret station reference materials such as

1. 2.1.25 graphs / monographs / and tables which contain performance data 2.8 1 Conduct of 2.1.4 Knowledge of shift staffing requirements 3.4 1 Operations I

Subtotal 3 1 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 Knowledge of bases in tech specs for limiting conditions for 3.7 1

2. 2.2.25 operations and safety limits Equipment 2.2.24 Ability to analyze the affect of maintenance activities on LCO status 3.8 1 Control I I I I Subtotal 2 2 Knowledge of radiation exposure limits and contamination control /

2.3-4 including permissible levels in excess of those authorized 2.5 1 Knowledge of 10 CFR: 20 and related facility radiation conbol 2.3.1 requirements 2.6 1

3. 2.3.11 Ability to control radiation releases 3.2 1 Radiation Knowledge of 10 CFR: 20 and related facility radiation control 3.0 1 Control 2.3.1 requirements 4.

Emergency Procedures I Plan 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:

MNGP-07 E Scenarios V

E N

1 I 2 3 4 T 0

M I

T T

S CREW POSITION 1 CREW POSITION CREW POSITION CREW POSITION A B T

A L

N M

I Y R T O U P 0 C P E

RO RX El' NOR SRO-I I/C 0

SRO-U MAJ 0 TS RO RX Fila NOR SRO-I I/C 0

SRO-U MAJ 0 TS RO RX 0 NOR SRO-I I/C 0

SRO-U MAJ TS RO RX 0 NOR SRO-I I/C 0

SRO-U MAJ 0

Instructions:

-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.
2. 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.
3. 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.

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 Scenarios 2 3 4 CREW CREW CREW

-gqyTgqT

- POSITION POSITION POSITION S A B R T 0 o c 0 0 C P 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 (IC) malfunctions and one major transient, in the ATC position.
2. 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.
3. 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.

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 E Scenarios v

E N

T T

S CREW POSITION 1 CREW POSITION -

S 3

CREW POSITION A

B

&I S

POSITION i A

M N

M I

I Y R R T 0 R U P 0 C P O C 0 C P 0 E

RO RX I I I I Q q NOR I I I SRO-I I/C 0

SRO-U MAJ 0 TS RO RX 0 NOR SRO-I I/C m 3 SRO-U MAJ 0 TS RO RX 0 NOR SRO-I I/C EIq SRO-U MAJ 0 TS RO RX 0 NOR SRO-I I/C 0

SRO-U MAJ Instructions:

-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.
2. 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.
3. 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.

MONTICELLO 2007 INITIAL LICENSE EXAM OPERATING OUTLINE COMMENTS

  1. Source Comment Resolution
1. Admin JPM-001 There is no WA listed associatedwith Section 2.1 of Comment incorporated.

the WA catalog. Admin JPMs associatedwith The WA for the JPM was Conduct of Operations are required to have a WA changed to 2.1.25.

from Section 2.1 of the WA catalog.

NOTE: This comment applies to both the RO and SRO outlines.

- ~~

2. Control Room The Importance Ratings for the ROlSRO should be Comment incorporated.

JPM-B.04.02-002 listed as 3.2l3.3instead of 3.313.2.

NOTE: This comment applies to the RO, SRO-I, and SRO-U outlines.

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