ML071230735

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Final Outlines for the Monticello Initial Examination February 2007
ML071230735
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/03/2007
From: Valos N
NRC/RGN-III/DRS/OLB
To:
Shared Package
ML070660508 List:
References
50-263/07-301
Download: ML071230735 (11)
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Text

FINAL OUTLINES FOR THE MONTICELLO INITIAL EXAMINATION FEBRUARY 2007

ES-301 Administrative Topics Outline Form ES-301-1 I Facility: Monticello Nuclear Generating Plant Date of Examination: 2112107 I

Exam Level: RO SRO 0 Operating Test Number: MNGP-07 I Administrative Topic Code*

Describe activity to be performed I

Bulk DMI Temperature Manual Calculation Conduct of Operations JPM-001 2.1.25 2.8 Control Room Shift Turnover Checklist I

Conduct of Operations JPM-3139-001 2.1.3 3.0 Daily Jet Pump Operability Check Test 0133 JPM-0133-001 Equipment Control 2.2.12 3.0 High Radiation Area Entry Radiation Control R, M JPM-4 AWI-08.04.06-002 2.3.10 2.9 Emergency Plan 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 (13for ROs; 14 for SROs & RO retakes)

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

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

ES-301, Page 22 of 27

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

Facility: Monticello Nuclear Generating Plant Date of Examination: 2112/07 Exam Level: RO 0 SRO [XI Operating Test Number:

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

Bulk DMI Temperature Manual Calculation Conduct of Operations JPM-001 2.1.25 3.1 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 0133 2.2.12 3.4 High Radiation Area Entry Radiation Control JPM-4 Awl-08.04.06-002 2.3.10 3.3 Protective Act ion Recommendation R. D 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 (13for ROs; 14 for SROs & RO retakes)

(N)ew or (M)odified from bank (11)

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

I I

ES-301 Control Roomh-Plant Systems Outline F o ES-301-2

~ I Facility: Monticello Nuclear Generating Plant Date of Examination: 2/12/07 Exam Level: RO sR0-l 0 sR0-u 0 Operating Test No.: MNGP-07 Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function JPM-C.4-B.Ol.03.C-004, PERFORM THE REACTOR a' SCRAM FUNCTIONAL TEST 0010 / ROD DRIFT / SCRAM N. A. S I I -

1 201003.A2.03 3.4/3.7

c. JPM-6.06.05.06-001, REACTOR FEED PUMPS COLD

"' STARTUP N, s, L 2 259001.A4.02 3.9/3.7 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 4.4/4.4 JPM-B.02.03-009, MANUAL INITIATION OF RClC

d. 217000.A4.04 3.6/3.6 N, A, S 4 JPM-B.04.02-006, DRYWELL TO SUPPRESSION e' CHAMBER VACUUM BREAKER LEAKAGE N, A, S 5 OPERATIONAL CHECK 223001.A3.02 3.4/3.4 JPM-B.09.08-001, MANUALLY START NO. 11 EDG f' (CONTROL ROOM ACTIONS) P. s I -

6 264000.A4.04 3.7/3.7 I

JPM-B.05.11-001, PERFORM THE SERVICE WATER y' EFFLUENT MONITOR FUNCTIONALTEST D, s 7 272000.A4.02 3.0/3.0 JPM-B.04.02-002, RESTORE SBGT TO A NORMAL h' STANDBY LINEUP D, s 9 261000.A3.01 3.Z3.3 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) 1.. JPM-B.O8.01.02-O5-001, TRANSFER EDG COOLING FROM D 8 EDG-ESW TO SERVICE WATER 295018.AA1.01 3.3/3.4

. JPM-B.02.04-03, STARTUP OF AIR DRIVEN COMPRESSORS FOR MAIN AIR SUPPLY TO OUTBOARD MSIVS N, R 4 239001.K1.12 2.5/2.6 JPM-C.5-3101-002, DEPRESSURIZETHE SCRAM AIR D, R, E 1 k'

HEADER LOCALLY PER C.5-3101, PART B 295037.EA1.03 4.V4.1

@ 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.

ES-301, Page 23 of 27

  • Type Codes Criteriafor RO I SRO-I I SRO-U (A)lternate path 4-6 14-6 I 2-3 (C)ontrol room (D)irect from bank 19 I Sa I a (E)mergency or abnormal in-plant 21 I21 I 2 1 (L)ow-Power I Shutdown 21 I 2 1 I 2 1 (N)ew or (M)odified from bank including 1(A) 22 I 2 2 I 2 1 (P)revious 2 exams 13 I <3 1 1 2 (randomly selected)

(R)CA 21 I 2 1 I21 Wimulator

ES-301 Control Roomh-Plant Systems Outline Form ES-301-2 I Facility: Monticello Nuclear Generating Plant Date of Examination: 2/12/07 Exam Level: RO 0 ~ ~ 0 - 1sR0-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-B.Ol.03.C-004, PERFORM THE REACTOR a' SCRAM FUNCTIONAL TEST 0010 / ROD DRIFT / SCRAM N, A, s 1 201003.A2.03 3.4/3.7 I I b.

JPM-B.03.03-002, PERFORM SRV OPERABILITY AND

'. POSITION INDICATION CHECK IAW TEST 01 12 D, A, S, L 3 239002.A4.01 4.4/4.4 JPM-B.02.03-009, MANUAL INITIATION OF RClC N, A, s 4 d' 217000.A4.04 3.6j3.6 JPM-B.04.02-006, DRYWELL TO SUPPRESSION e' CHAMBER VACUUM BREAKER LEAKAGE N, A, S 5 OPERATIONAL CHECK 223001.A3.02 3.4/3.4 JPM-B.09.08-001, MANUALLY START NO. 11 EDG f' (CONTROL ROOM ACTIONS) P, s 6 264000.A4.04 3.7/3.7 JPM-B.05.11-001, PERFORM THE SERVICE WATER g' EFFLUENT MONITOR FUNCTIONALTEST 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 26 1000.A3.01 3.2l3.3 In-Plant Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

~

I . JPM-B.08.01.02-05-001,TRANSFER EDG COOLING FROM EDG-ESW TO SERVICE WATER 295018.AA1.01 3.3/3.4 D 8 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.U2.6 k' JPM-C.5-3101-002, DEPRESSURIZETHE SCRAM AIR D, R, E 1 HEADER LOCALLY PER C.5-3101, PART B 295037.EA1.03 4.1/4.1

@ 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 Criteriafor RO I SRO-I I SRO-U (A)lternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank 19 1 Sa 1 14 (E)mergency or abnormal in-plant 21 I21 121 (L)ow-Power I Shutdown 21 I 2 1 I 2 1 (N)ew or (M)odified from bank including 1(A) 22/22/21 (P)revious 2 exams 13 1 1 3 1 1 2 (randomly selected)

(R)CA 21 I 2 1 I 2 1 (S)imulator

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

acility: Monticello Nuclear Generating Plant Date of Examination: 2112/07
ontrol Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

I I System I JPM Title JPM-C.4-B.Ol.03.C-004, PERFORM THE REACTOR SCRAM FUNCTIONAL TEST 0010 I ROD DRIFT I SCRAM N,A, S 1 201003.A2.03 3.413.7 3.

JPM-B.03.03-002, PERFORM SRV OPERABILITY AND

e. POSITION INDICATION CHECK IAW TEST 01 12 D, A, S, L 3 239002.A4.01 4.414.4 9.

JPM-B.04.02-002, RESTORE SBGT TO A NORMAL h STANDBY LINEUP D, S 9 261000.A3.01 3.Z3.3 n-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 I 2-3 (C)ontrol room (D)irect from bank 19 I 58 I 14 (E)mergency or abnormal in-plant 21 I 2 1 121 (L)ow-Power I Shutdown r l 121 I 2 1 (N)ew or (M)odified from bank including 1(A) 22 122 I 21 (P)revious 2 exams 13 113 1 1 2 (randomly selected)

(R)CA 21 I 2 1 I 2 1 (S)imulator

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

Examiners: Operators:

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

Event Malf. Event Event No. No. Type* Description 1 MSOGA N (BOP) Perform Test 0008 MAIN STEAM LINE ISOLATION (SRO) VALVE CLOSURE SCRAM TEST. The 'A' Outboard MSlV 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.

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

ITS LCO 4 TU03G Main Turbine Vibrations, lower reactor power to lower /

TU03H stabilize vibrations.

5 SWOlA RBCCW system degradation. RBCCW Pump Trip.

Standby pump fails to auto start.

6 RN20A Loss of Air to 'A' Feed Reg. Valve. FRV Lockup and recovery.

7 MS04A M (ALL) Steam line break inside primary containment.

MS04B Scram. Unable to spray DNV.

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

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

EOP 2002 entry (Blowdown) 8 S054- C (BOP) Failure of D ADS SRV to open 01 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:

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

Event MaIf. Event Event No. No. Type* Description 1 TCOGB N (BOP) Complete Test OSP-TRB-0570, EXERCISE MAIN PRO) TURBINE BYPASS VALVES The #2 Turbine Bypass Valve will not open as required by the test resulting in an ITS LCO.

2 CH08A C (RO) 11 CRD Pump trip. Start 12 CRD pump.

3 TC05A I (BOP) EPR Oscillations and placing the MPR in control.

4 RR02C I(R0) RPV press inst fails upscale, half scram fails to be initiated.

PP06 (SRO) ITS LCO.

5 MS09 C (BOP) 11 Steam Packing Exhauster trip, start standby blower.

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

(SRO) ITS LCO.

7 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 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

Amendix D Scenario Outline Form ES-D-1 Facility: MNGP Scenario No.: NRC-03a Op-Test No.: MNGP-07 Examiners: Operators:

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

Turnover:

Withdraw control rod 26-27 to position 08 and then perform Test 0255-03-IA-1-1, CORE SPRAY LOOP A QUARTERLY PUMP AND VALVE TESTS.

Event Description Withdraw control rod with raised drive pressure.

1-1

, r- - v t n w CRI v W D

-C rccrc J Event Deleted ]

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.

HPCI inadvertent initiation and shutdown. HPCI will be inoperable.

ITS LCO.

RWCU Leak, un-isolable, EOP-1300 Entry, Scram Blowdown, EOP 2002 Entry.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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