ML071230735

Final Outlines for the Monticello Initial Examination February 2007

ML071230735
Person / Time
Site:	Monticello
Issue date:	05/03/2007
From:	Valos N NRC/RGN-III/DRS/OLB
To:
Shared Package
ML070660508	List: ML071230730 ML071230735 ML071230739 ML071230740 ML071230743 ML071230745 ML071230748 ML071230773
References
50-263/07-301
Download: ML071230735 (11)

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:

211 2107 I Exam Level: RO SRO 0 Operating Test Number:

MNGP-07 I Administrative Topic Code* Conduct of Operations I Conduct of Operations Equipment Control Radiation Control R, M Emergency Plan I Describe activity to be performed Bulk DMI Temperature Manual Calculation 2.1.25 2.8 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 JPM-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. *Type Codes

& Criteria:

' (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, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 ] Date of Examination:

211 2/07 Facility: Monticello Nuclear Generating Plant Exam Level:

RO 0 SRO [XI Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control TY Pe Code* R. D MNGP-07 Operating Test Number: Describe activity to be performed Bulk DMI Temperature Manual Calculation 2.1.25 3.1 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 Act ion Recommend at ion 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 (13 for ROs; 14 for SROs & RO retakes) (N)ew or (M)odified from bank (11) (P)revious 2 exams (11; randomly selected)

II I ES-301 Control Roomh-Plant Systems Outline Fo~ 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) System / JPM Title Type Code*

Safety Function ES-301, Page 23 of 27 JPM-C.4-B.Ol.03.C-004, PERFORM THE REACTOR a' SCRAM FUNCTIONAL TEST 0010 / ROD DRIFT

/ SCRAM N. A. S 1 I I- 201003.A2.03 3.4/3.7 c. JPM-6.06.05.06-001, REACTOR FEED PUMPS COLD "' STARTUP N, s, L 2 c' POSITION INDICATION CHECK IAW TEST 01 12 D, A, S, L 3 259001 .A4.02 3.9/3.7 JPM-B.03.03-002, PERFORM SRV OPERABILITY AND 239002.A4.01 4.4/4.4 d. 21 7000.A4.04 3.6/3.6 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 3.4/3.4 JPM-B.09.08-001, MANUALLY START NO.

11 EDG f' (CONTROL ROOM ACTIONS) P.

s 6 I- 264000.A4.04 3.7/3.7 I JPM-B.05.11-001, PERFORM THE SERVICE WATER y' EFFLUENT MONITOR FUNCTIONAL TEST 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 EDG-ESW TO SERVICE WATER JPM-B.02.04-03, STARTUP OF AIR DRIVEN 295018.AA1.01 3.3/3.4 COMPRESSORS FOR MAIN AIR SUPPLY TO OUTBOARD MSIVS 239001.K1.12 2.5/2.6 HEADER LOCALLY PER C.5-3101, PART B 295037.EA1.03 4.V4.1 N, R . D, R, E JPM-C.5-3101-002, DEPRESSURIZE THE SCRAM AIR k' 8 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 4-6 14-6 I 2-3 (A)lternate path (D)irect from bank (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 Wimulator (C)ontrol room 19 I Sa I a 21 I21 I21 21 I21 I21 22 I22 I21 13 I <3 112 (randomly selected) 21 I21 I21 ES-301 Control Roomh-Plant Systems Outline Form ES-301-2 I 2/12/07 Facility: Monticello Nuclear Generating Plant Date of Examination: Exam Level:

RO 0 ~~0-1 sR0-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 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.A4.0 1 4.4/4.4 d' 217000.A4.04 3.6j3.6 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 3.4/3.4 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 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 26 1 000.A3.0 1 3.2l3.3 In-Plant Systems@ (8 for RO);

(7 for SRO-I);

(2 or 3 for SRO-U)

D ~ 8 4 . JPM-B.08.01.02-05-001, TRANSFER EDG COOLING FROM I 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 239001.K1.12 2.U2.6 JPM-C.5-3101-002, DEPRESSURIZE THE SCRAM AIR 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. N, R J' D, R, E k' @ 1

• Type Codes (A)lternate path (C)ontrol room (D)irect from bank (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 Criteriafor RO I SRO-I I SRO-U 4-6 14-6 12-3 19 1 Sa 1 14 21 I21 121 21 I21 I21 22/22/21 13 113 112 (randomly selected) 21 I21 I21 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 I 211 2/07 :acility: Monticello Nuclear Generating Plant Date of Examination:

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 201003.A2.03 3.413.7 N, A, S 1 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 9 261 000.A3.01 3.Z3.3 n-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 4-6 14-6 I 2-3 19 I 58 I 14 21 I21 121 rl 121 I21 22 122 I 21 13 113 112 (randomly selected) 21 I21 I21 (A)lternate path (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 Appendix D Scenario Outline Form ES-D-1 Event No. 1 2 3 4 5 Facility:

MNGP Scenario No.: NRC-01 Op-Test No.: MNGP-07 Malf. No. MSOGA CH07B AP07 TU03G TU03H SWOlA Examiners: Operators:

I 6 7 8 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.

RN20A MS04A MS04B S054- 01 Event Type* N (BOP) (SRO) M (ALL) M (ALL) M (ALL) C (BOP) Event Description Perform Test 0008 MAIN STEAM LINE ISOLATION VALVE CLOSURE SCRAM TEST.

The 'A' Outboard MSlV 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.

Steam line break inside primary containment.

Scram. Unable to spray DNV. EOP 1100 entry (RPV Control).

EOP 1200 entry (Primary Containment Control).

EOP 2002 entry (Blowdown)

Failure of D ADS SRV to open Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Event Ma If. Event No. No. Type* 1 TCOGB N (BOP) PRO) 2 CH08A C (RO) 3 TC05A I (BOP) 4 RR02C I(R0) PP06 (SRO) 5 MS09 C (BOP) 6 RR07 R (RO) (SRO) RR08 C (BOP) 7 PP05A M(ALL) PP05C CH16 (N)ormal, (R)eactivity, (I)nstrument, Facility:

MNGP Scenario No.: NRC-02 Op-Test No.: MNGP-07 Event Description Complete Test OSP-TRB-0570, EXERCISE MAIN TURBINE BYPASS VALVES The

1. 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. 11 Steam Packing Exhauster trip, start standby blower. 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 (C)omponent, (M)ajor Examiners: Operators: Initial Conditions:

89% reactor power. Test OSP-TRB-0570.

EXERCISE MAIN TURBINE BYPASS VALVES, is scheduled to be completed.

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-vtnw ,- CRI v D-WC 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