ML20212H319
| ML20212H319 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/16/1999 |
| From: | Brion A NORTHERN STATES POWER CO. |
| To: | NRC |
| Shared Package | |
| ML20212H208 | List: |
| References | |
| NUDOCS 9910010036 | |
| Download: ML20212H319 (275) | |
Text
.6, Northem States Power Montice50NucieerGenerating Plant LTh'% con, Enc $oYn*EsYe2 1
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July 16,1999 US Nuclear Regulatory Commission 801 Warrenville Road l Lisle IL 605324351 C/O Ronald Bailey
Dear Mr. Bailey:
This materialis for the Official use of Ronald Bailey.
l IT IS TO BE OPENED BY THE ADDRESSEE ONLY ---
Enclosed is the August 1999 Monticello RO Exam Package, included are the revised outlines.
All changes are in blue font. The remaining ES-301 forms are also included. For the actual exam l package we have sent a copy of the written exam and handout package that the applicants will be !
given for the exam. Also included is the written exam answer key with justifications and reference material stapled with each question. For the JPMs we have the revised outline, the JPM and the two questions for each JPM. For the Admin JPMs we have two JPMs and six questions along with the revised outline. For the simulator exam we have the ES-301 forms and the four scenarios included.
If there is anything else that you need or have questions on please let me know. I will call Monday or Tuesday to ensure that you received the exam package and the complete reference package. '
As per NUREG 1021 please withhold these materials from public disclosure until after the i examination is complete. The exam is currently scheduled from August 23,1999 to August 27,1999.
Sincerely,
. M Anthony F. Bron SeniorTechnicalInstructor 9910010036 990927 PDR ADOCK 05000263 V PDR i
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INITIAL SUBMITTAL OF THE OPERATING TEST FOR THE MONTICELLO EXAMINATION - THE WEEK OF AUGUST 23,1999
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us,mi i INITIAL SUBMITTAL OF THE ADMINISTRATIVE JPMS FOR THE
- MONTICELLO EXAMINATION - THE WEEK OF AUGUST 23,1999
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l ES-301 Administrative Topics Outline Form ES-301-1 Facility:,_Monticello Nuclear Generating Plant _.Date of Examination:,_8/23/1999 _
Examination Level (circle one): RO / SRO O mrating Test Number 1 Administrative Topic / Subject Describe method of evaluation:
- 2. TWO Administrative Questions Startup Cautions / N'otes for RO Responsibilities 1 (Administrative Question) !
Reactor plant startup requirements j
_ ~.-i C.1 Flexibility in performing Procedure Steps 9
(Administrative Question)
Refueling interlocks (Administrative Question) l l
Fuel Handling Foreign Material Exclusion (Administrative Question)
I 1 Administrative JPM; Determine if Work Order (WO) i A.2 Familiarity with the use of P&lDs isolation is adequate.
1 Administrative JPM; Determine radiation protection i A.3
**" '" E '#8#' **
Radiation Work Permits (RWP) assignment involving the isolation of a HCU.
I Non-Duty reporting requirements (Administrative Question)
Emergency Action Levels and A.4 lassMons Classification Recommendation to Shift Management (Administrative Question) i
a;mann Administrative-JPMs and l Administrative Questions
MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-Q-001 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 "9Rt Ouestion:
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A Reactor startup is in progress with Reactor power on the SRMs. An illness has forced one of the duty PEO's to go home. You have been called over from the training center to fill the vacant position,
~-
in addition to the required shift turnover, what additional administrative requirements must be satisfied prior to assuming the duty? - -- =- - '- -
Answer:
Section 111 (CAUTIONS AND NOTES FOR REACTOR CRITICALITY AND HEATUP) of C.1 must be reviewed prior to assuming licensed operator duty.
Reference:
C.1 (STARTUP), pg 6 of 63 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-002 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 l
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Ouestion: I A reactor startup is in progress during the summer and steps in C.1 (STARTUP) are l complete through step C.1.V.C (Reactor Pressurization to 150 psig). The Turbine Building APEO calls the Control Room and requests permission to start the Isophase bus duct cooling blower. This step is not required until Turbine Generator startup portion of C.1.
is placing Isophase Bus duct cooling in service at this time allowable and why? --
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Answer:
l Yes. C.1 allows reasonable flexibility in the sequence of steps, provided:
- 1. Steps are not omitted.
- 2. Steps are performed in the manner prescribed.
- 3. Ste as that are called for at or prior to reaching specific operating conditions are per ormed before passing beyond these conditions.
i
Reference:
C.1 (STARTUP), pg 4 of 63 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-003 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 4 ,
Question:
o During refuel operations control rods must be withdrawn to position 48 to facilitate unloading of a core cell for control rod replacement.
How can multiple control rods be positioned to 48 when Reactor Manual Control System is interlocked such that when in " Refuel Mode" only one rod may be withdrawn past position 007 - - -
Answer:
After a control rod is withdrawn to position 48, the refueling interlock for the control rod withdrawn is bypassed.
Reference:
D.2-05, pg. 27 of 58 1/cmb
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\ MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-004 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 l Page 1 of 1 1
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,1 Question: l l
While changing tools on the monorail crane you inadvertently drop an adjustable wrench in the fuel pool. I What are your responsibilities in this situation?
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Answer: l l
Note where i,t comes to rest and notify the Refuel Coordinator, Shift Supervisor, or Supt.
Nuclear Engineenng l
Reference:
D.2-05, pg.15 of 58 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWl-04.04.01 -0(5 TITLE: ISOLATION OF NO.11 FUEL POOL PUMP Revision 0 Page 1 of 4 i SRO: SRO/RO: X SRO/RO/NLO: NLO:
Plant
Reference:
P&lD M-135,4 AWi-04.04.01 (EQUIPMENT ISOLATION)
Task Standard: Verify Adequate isolation for Maintenance Activities on No.11 Fuel Pool Pump.
K/A
Reference:
Generic K/A Task No: 2.2.13 Rating RO/SRO: 3.6/3.8 Recent Events: None Probabilistic Risk Assessment Human Error:
Monticello Specific Task List
Reference:
METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 10 Min Simulator: Normal:
Alternate Maximum Time to Complete: 20 Min In-Plant: Path: X l
Other: X Time Critical: Yes X No Prepared By:
d 4 h [. /4 9 g //oj Date:
7-/f9Z/
Reviewed By: Date: yL/-9f Shift Supv/ Shift Mgr5 view By:
/J 4 /rt. k. Ark //.3 Date: 7-/% 7f 4
Approved By: (Supt Ops Trng) Date: 7 g. p v
3087 (DOCUMENT CHANGE. HOLD, AND COMMENT FORM) incorporated' Resp Supv: OTRNG l Assoc Ref: MTCP-3.32 lSR: N Frea: 0 yrs ARMS: JPM4 awl 441001 l Doc Type: 8505 l Admin inrbals: Date:
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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWl-04.04.01 -001 TITLE: ISOLATION OF NO.11 FUEL POOL PUMP Revision 0
~
Page 2 of 4 MatiEEEEWEEffe9EAN9PJ]SEMP& Emit 3HREEIRBSEMEh14 Initial Conditions:
No.12 Fuel Pool Cooling Pump in service.
Initiating Cues:
The SS directs you to review the attached isolation for maintenance on No.11 Fuel Pool Cpoling Pump. Maintenance will be repacking the pump. Determine whether the iso ation provides adequate protection for maintenance workers who will be work-ing on the pump.
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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWi-04.04.01 -001 TITLE: ISOLATION OF NO.11 FUEL POOL PUMP Revision 0
! Page 3 of 4 PERFORMANCE INFORMATION Eigggeg7ggaggpygyt e33g gyjjilyggggSfagagg1lggggggyggg l STEP 1 Standard:
Locates P&lD M-135. Locates a controlled copy of P&lD M-135.
STEP 2 Standard:
Reviews isolation by comparing it to Reviews isolation by comparing it to P&lD M-135.
P&lD M-135. The operator may reference 4 AWi-04.04.01 Correct valve position and proper use of (EQUIPMENT ISOLATION) for instruction son re-viewing isolations. (Not critical portion of Stan-l HOLD and SECURE Cards should be verified. dard.)
Cue: None Comments: None
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STEP 3 Standard:
l Identifies that Valve PC-52-1 is not in- Critical portion of the Standard is the identification j cluded on the isolation, of PC-52 not included on the isolation. j Cue: None Comments: None STEP 4 Standard:
Notifies SS of review findings. Notifies SS that PC-52-1 should be included on isolation.
Cue: None Comments: None STEP 5 Standard:
l lNFORM EVALUATOR THAT THE TASK HAS BEEN COMPLETED.
Cue: None Comments: DO NOT PROMPT!
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MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWl 04.04.01.oot TITLE: ISOLATION OF NO.11 FUEL POOL PUMP Revision 0 Page 4 of 4 l
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Initial Conditions:
No.12 Fuel Pool Cooling Pump is in service.
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llIcolstionLId:L99-80224.v1 ..
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Status: DRAFT
Title:
- 11 FUEL POOL COOLING' PUMP PACKING REPLACEMENT l Asrc Wrk Doc:. Oid: 132917 Icolated For:"SAWATZKE B
, Pr:p3 red by:
l Reviswed-by:
l-Equipment Isolated: .
Equipment: P-7A,- 11 FUEL POOL ~ COOLING & CLEANUP PUMP-
' System: FPC.- Fuel Pool Cooling and Cleanup
. Location: Bldg: REACTOR BLDG Floor:- 1001' ~ ' ELEVATION '
Room: :RX-BLDG.1001'~FP SKIMMER TK RM Remarks: 985 LEVEL.
_ Idolction Instructions:
?Rsotoration' Instructions:-
..;Tcgs?---------------------------- -------------------------------------------
.Tcg:.1 Type: SECURE Size: SMALL- IV: Y. Status: NEW Equipments-42-3302/CS-1,- 11 FPCC PUMP (LOCAL)-
Alt Id:'B3302/CS-1 l . System: FPC Fuel' Pool' Cooling and Cleanup--
l Location: Bldg: REACTOR BLDG Floor: -985 ELEVATION:
Room: 'RX' BLDG 985' FUEL POOL'HX-RM, Remarks: PANEL C Tag' Pos:.STOP Norm Pos: START
- R: marks:
CSDS: ,
aIV:- Yes:
Holds:--
SAWATZKE B I Tug:.2 Type: SECURE Size: SMALL IV: Y Status: NEW
-Equipment: 42-3302/CS-2, 11 FPCC PUMP Alt'Id:.~B3302/CS-2 ..
i
. System:'FPC - Fuel Pool Cooling'and Cleanup Location: Bldg: ; RAD WASTE BLDG Floor: 935' ELEVATION
. Room: RW 935' CONTROL ROOM..
Remarks:-PANEL'C Tcg Pos: OFF
. Norm Pos: ON '
R2 marks:'
l E CSDS:
l IV: Yes:
. Holds:. ..
SAWATZKE'B-Tcg: 3 . Type: JHOLD- . Size: LARGE IV: Y Status: NEW
- Equipment
- -B3302, P-7A, 11 FUEL POOL COOLING PUMP- 480V SUPPLY
' System:~480 - 480 V Station: Auxiliary
F,x LocOtilon: Bldg: TURBINE BLDG.
Floor: 911' ELEVATION Room: TURB BLDG 911' EAST Remarks: MCC-133A Tc.g 'Pos: OPEN-Norm'Pos: CLOSED Remarks:
CSDS:
.IV: Yes:-
Holds:
SAWATZKE B o
Ttg 4 .Typei HOLD Size: LARGE IV: Y Status: NEW Equipment: PC-3-1, 11 FPCC PUMP SUCTION
. System: FPC - Fuel Pool Cooling and Cleanup' Location: Bldg:' REACTOR BLDG Floor: 985' ELEVATION Room: RX BLDG 98C' FUEL POOL-HX RM Remarks:
Ttg Pos: CLOSED Norm Pos: OPEN Remarks: ,
CSDS:
- IV: Yes:
-Holds:
SAWATZKE B Tug: 5 Type: HOLD . Size: LARGE IV: Y Status: NEW Equipment: PC-5-1, 11 FPCC PUMP DISCHARGE System: FPC - Fuel Pool Cooling and Cleanup Location: Bldg: REACTOR BLDG Floor: 985' ELEVATION Room: RX BLDG 985' FUEL POOL HX RM Remarks:
Tcg Pos: CLOSED Nonn Pos: OPEN R; marks:
\
CSDS: '
IV: Yes:
Holds:
SAWATZKE B
.Tcg: 6 13Pe: HOLD Size: LARGE IV: Y Status: NEW Equipment: PC-46-1, 11 FPCC PUMP CASING DRAIN System: FPC - Fuel Pool Cooling and Cleanup
. Location: Bldg: REACTOR BLDG Floor: 985' ELEVATION i Room: RX BLDG 985' FUEL POOL HX RM Remarks:
l Trg Pos: OPEN l Norm Pos: CLOSED -
R2 marks:
g:
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. CSDS:-
'.IV: Yos:
Holds:
SAWATZKE B <
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.Tcg: 7 Type: HOLD' Size: LARGE IV: Y Status: NEW Equipment: PC-45-1, 11 FPCC PUMP SUCTION DRAIN i System: FPC - Fuel Pool Cooling and Cleanup Location: Bldg: REACTOR BLDG Floor: -985' ELEVATION Room: RX BLDG 985' FUEL POOL HX RM Remarks: !
l Tag Pos: OPEN Norm'Pos: CLOSED Remarks:
CSDS:
IV: Yes:
- Holds: <
SAWATZKE B 1
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NH-36256 l REnows U AS-BUILT:
RD4 SED TO RER.ECT REAUGNED FUEL POOL 2000NG SYSTEW TO RHA SYSTEM SPOOL PIECE
,,,,y, PER DRR: WO-96-0168 E ,,,,.a., l Cl DWN: RHH 8-27-96
_ Cg eL _ s-27-** E FILWED 9-4-96 r1 r1 r1 r1 ut A5-8UILT:
h,, ki, ka i k RO4 SED TO RER.ECT a
AS FOUND CON 0m0N IN ACCORtANCE MTH SRI 92-025 CORRECTED ,
a a a a y PC-31 LOCATION &
gasyg,o 9 DRR: WO-97-0164 sau.aon ratous h'/ G RHH 11-19-97 yaco jjr i'i CHd: JTL 11-12+97 en s sei a 2r or '.J00: +
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Y RATING PW u.c i l o CLIAN-UP SYSTEM P & ID THERN STATES POWER COWPANT N WNE l & A8 Wmrams NH-36256 6 1 1
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MONTICELLO NUCLEAR GENERATING PLANT 4 AWi-04.04.01 TITLE: EQUIPMENT ISOLATION Revision 15 Page 13 of 34 4.3.8 The isolation preparer SHALL indicate completion of isolation preparation by one of the following:
A. Using the " Signatures" function under the " Iso" menu in the HSC System and then selecting " Prepared By...".
B. Signing the Prepared By blank on Form 3063-1.
4.3.9 The isolation scheme SHALL be reviewed by a knowledgeable individual other than the isolation preparer (isolation reviewer).
_ 4.3.10 The isolation reviewer should use controlled prints or other definitive
_ _ anttcurt. ant. documentation to verify. completeness,and adequacy ofJhe isolation line-up for the isolations intended purpose.
4.3.11 The isolation reviewer should ensure that the isolation provides adequate instruction for venting, draining, or grounding for the isolations intended purpose.
4.3.12 The isolation reviewer SHALL indicate completion of a satisfactory review by one of the following:
i A. Using the " Signatures" function under the " Iso" menu and then selecting " Reviewed By...".
B. Signing the Reviewed By blank on Form 3063-1.
4.3.13 If the isolation is associated with a WO, then the WO preparer should attach Form 3063-1 or a copy of the isolation from the HSC System, to the WO for submittal to the WO Coordinator. _
4.3.14 If the isolation is associated with a Work Procedure, Design Change Procedure, or OCD, the procedure preparer should provide a copy of the isolation from the HSC System in addition to the isolation table
_ format in the procedure.
4.3.15 If the isolation is not associated with a work document, but is drafted using the " HOLD and SECURE Card Book" then a copy of the HSC isolation should be provided to the Shift Supervisor's Office when desired to be installed.
4.4 Approval and Authorization for Installation of Isolations 4.4.1 If the isolation is associated with a Work Procedure or OCD, the Shift Supv SHALL verify that the HSC System isolation instructions agree with isolation instructions provided with the work procedure or OCD. If the instructions do not agree, then the instructions of the OC Reviewed Work Document or OCD SHALL be followed and the HSC instructions should be updated to agree.
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MONTICELLO NUCLEAR GENERATING PLANT JPM-RWP-31 001 TITLE: DETERMINE RADIATION PROTECTION Revision 0 REQUIREMENTS Page 1 of 4 SRO: SRO/RO: X SRO/RO/NLO: NLO:
i l Plant
Reference:
RWP 31 Task Standard: Determine radiation protection requirements and projected whole body exposure for isolation of an HCU.
i-- - - K/A
Reference:
Generic K/A . -- - . Task No: - 2a10-- Rating RO/SRO: 2.9/3.3 -
Recent Events: None 1
Probabilistic Risk Assessment Human Error: ,
1 Monticello Specific Task List
Reference:
METHOD OF TESTING TIME FOR COMPLETION Estimated Tme to Complete: 10 Min Simulator: Normal: X Alternate Maximum Eme to Complete: 20 Min In-Plant: X Path:
Tme Critical: Yes X No l l l
Prepared By: Q Date: 7_ fgp I Reviewed By:
1[3 Date: p g.pp Shift Supv/ Shift Mgr Review B[/M /t1 Date: 7-/w ?)
Approved By: (Supt Ops Trng) Date: yy.pp v
N:, :n . iMe;f; op ., ), 4 ,
3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated-Resp supv: OTRNG l Assoc Ref MTCP-3.32 IsR: N Frea: 0 yrs ARMS: JPMRWP31001 l Doc Type: 8505 l Admin initials: Date:
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MONTICELLO NUCLEAR GENERATING PLANT JPM-RWP-31 -001 TITLE: DETERMINE RADIATION PROTECTION Revision 0 REQUIREMENTS Page 2 of 4 E d filESTf B EEd! 5 3} l S IR P 5 f @ i G if3 M P y y E J y g g j
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Initial Conditions: )
HCU 14-23 required to be isolated for accumulator changeout.
Initiating Cues:
Determine the appropriate RWP, RWP requirements and expected exposure for isola-tion of HCU 14-23. System draining is not required at this time. Expected time to ;
complete isolation is one half (1/2) hour . -
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r MONTICELLO NUCLEAR GENERATING PLANT JPM-RWP-31 -001 TITLE: DETERMINE RADIATION PROTECTION Revision 0 REQUIREMENTS Page 3 of 4 PERFORMANCE INFORMATION Mif#hharigeWblepthfeW - ' . , i ' '. . ~ die 5. ' '
STEP 1 Standard:
Determine and locate RWP 31 as the 1. Determines area is RWP No. 31 from Rx.
applicable radiation work permit. Bldg 935' floor drawing located at Access Control log-in area.
STEP 2 Standard:
Review RWP No. 31 for clothing require- 2. Reviews RWP No. 31 and determines the ments. following:
- a. Class 2 protective clothing.
_. b. Reaching over barrier is acceptable for this RWP.
Cue: None Comments: None STEP 3 Standard:
Review RWP No. 31 and determines General area mrem /hr is 1.5-10.
pp sure.
Expected exposure should be .75 - 5 mrem.
Cue: None Comments: None STEP 4 Standard:
INFORM EVALUATOR THAT THE TASK HAS BEEN COMPLETED.
Cue: None Comments: DO NOT PROMPT!
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MONTICELLO NUCLEAR GENERATING PLANT JPM-RWP-39 -001 TITLE: DETERMINE RADIATION PROTECTION Revis'on 0 l REQUIREMENTS Page 4 of 4 l
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HCU 14-23 required to be isolated for accumulator changeout.
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l Monticallo Nuclear Gen 2 rating Plant RWP Num 1 Rev 16 RADIATION WORK PEEMIT 12/15/9a 10:15
- a Work Location All Non-Contaminated, Non-High Radiation and Non-Neutrtn 2ad;ati
- n Areas within the Restricted Area.
Description of Work l General entry to perform tasks which are passive in nature, as defined in 4 AW: 08.04.05, Radiological Work Control. Other work only as authorited by the Radiation Protection Coordinator.
o Radiological Conditions Location Contact General Area Smearable mrem /hr mrem /hr dpm/100cm2 RX,TS,RW and Recom 31dgs G/A .
.2-90 100 Admin Eldg Hot Lab, & H&V Rm .2-2.5 100 Access Control .2-2.5 100 Cond Storage Tanks Basin -- - - - - - - - -
.2-3-- 000 ~
Admin,Recom,RW,RX,D/G Roofs .2-30 _00 TB Roof .2 10 Requirements E:cposure Monitoring TLD Electronic Dosimeter - Alarm points 100 mrem /hr and 50 mrem.
Entries to the following areas for less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per day do not l require electronic dosimeters:
- 1) Turbine & Reacter 31dgs Railroad Says,
- 2) Other posted areas outside the power block which are governed under this RWP.
r-- '=s to Access C:ntrol or .he Het Lab under this RWP do nc: requirs electrcnic dosimeter use.
Other Approval from the Radiation Protection Coordinator SHALL be obtained prier to climbing to the upper levels (above 8') of any floor or accessing areas off of stairways in the Reactor or Rad Waste Buildings except in the case of using permanently installed ladders or platforms that are NOT posted as Contaminated Areas.
When using installed ladders, platforms, or stairways DO NOT access arcas beyond the installed ladder, platform or stairway without contact _ng the Radiation Protection Coordinator for additional surveys.
Observe the dose rate maps posted insthe plant for more precise information on dose rates in areas you will be entering.
l Ccnvas gloves should be worn when handling or transpor;ing c:cis. ,,
[ scaffolding, or other equipment that may have a: :ne :: e zee.. aps:ce j a C:ntaminated Area. Additionally coveralls sh: Cd ce w rn 4:,tne tools, scaffolding, or other equipment may : me in cents:: wt:n your body.
1 - 59613
+
Rev 6 RADIATI ON WORK PERMIT 09/11/97 14:45
~
Work Location 935 Reactor - Tip Cubicle Description of Work General entry by Radiation Protection personnel to perform routine surveys and surveillances. Other work only as authorized by the Radiation Protection Coordinator.
Radiological Conditions Location Contact General Area Smearable mrem /hr mrem /hr dpm/100cm2 TIP Cubicle 2-10 50,000 TIP Shields and Tubing 160 60-80 Shielded Cave in Hallway 400 200 Shielded Cart in Hallway 300 140
_- _ Requirements ,
Exposure Monitoring TLD Electronic Dosimeter - Alarm points 250 mrem /hr and 100 mrem High Radiation Area Dose Rate Meter Contaminated Area Class 2 Protective Clothino Required for activities in which parts of your body other than your hands or feet may come in contact with surfaces in the work area.
Class'l Protective Clothina Required for activities in which no parts of your body other than your hands or feet may come in contact with surfaces in the work area.
Other All entries to this area with an ALNOR dose alarm set point above 100 mrem require specific Gen Supt Rad Serv approval prior to the entry.
I All entries to this area other than those listed in the Description of Work section SHALL be approved by the Radiation Protection Coordinator 10U) your supervisor prior to each specific entry.
Prior to each entry the crew leadperson is to verify with the RPC that Gecure cards in the name of the RPC have been placed such that the 6 TIP detectors are held in their shields for the duration of the entry t and that ARM A-13 is reading less than 100 mrem /hr.
Dose rates on the TIP Tubing and Shields as well as the shielded caves in the hallway are higher than surrounding general area dose rates.
Maintain as much distance as reasonably possible from these areas.
i I
_- 01073 h, _ . . . . . . _ _. .. ., . _ . _ . . . . _ _ _ . _ . . ._
Monticallo Nuclear Generating Plant RWP Num 31
, Rev 4 RADIATION WORK PERMIT 11/04/97 12:30 Work Location 935 Reactor - East and West CRD Accumulator Banks I l
l Description of Work !
Gsneral entry to perform valving operations, instrument work or routine surveillances or other tasks which are passive in nature, as defined I in 4 AWI 08.04.05, Radiological Work Control. Other work only as authorized by the Radiation Protection Cordinator.
Radiological Conditions Location Contact General Area Smearable mrem /hr mrem /hr dpm/100cm2 Enst and West Accumulator Banks 1.5-10 1,000 l Overhead areas above banks 120 10 1 Requirements l
Exposure Monitoring TLD '
I Electronic Dosimeter - Alarm points 50 mrem /hr and 50 mrem Contaminated Area Class 2 Protective Clothing Required for activities in which parts of your body other than your hands or feet may come in contact with surfaces in the work area.
Class 1 Protective Clothing Required for activities in which no parts of your body other than your l hands or feet may come in contact with surfaces in the work area. '
Surgeon's gloves may be worn in place of rubber gloves for activities that require manual dexterity.
R3 aching over barriers is acceptable under this RWP. Adequate protective clothing in this case consists of rubber gloves and liners. If any parts of your arms or upper body may come in contact with contaminated surfaces then coveralls SHALL also be worn. Immediately dispose of all protective clothing in the nearest protective clothing receptacle after the work is complete.
Other System SHALL NOT be opened unless a RPS is in attendance. Crew 1Gadperson notify the RPC at Ext 1135. Excluded from this requirement tre instrument connections and valve caps.
When tool carts are required, use only tool carts labeled as potentially contaminated. Notify the RPC for follow-up smears on carts, tools, and work areas immediately after job completion.
- 71878 -
l Montic;11o NuclEtr Genersting Plant RWP Num 65 Rev 4 RADIATION WORK PERMIT 04/03/98 12:00 l l
Work Location i 1
935 Reactor - CRD Rebuild l Description of Work G2neral entry to perform tasks which are passive in nature, as defined i in 4 AWI 08.04.05, Radiological Work Control. Other work as !
cuthorized by the Radiation Protection Coordinator.
Radiological Conditions Location Contact General Area Smearable mrem /hr mrem /hr dpm/100cm2 CRD Rebuild Area General Area 100 6-60 40,000 High Radiation Area Around Drives 450 30-150 120,000 i N
~~ ~ ^' '
Requirements ~- '-
Exposure Monitoring l
TLD l Electronic Dosimeter - Alarm points 150 mrem /hr and 50 mrem High Radiation Area Rsview dose rates listed above prior to High Radiation Area entry.
Contaminated Area C1 mss 3 Protective Clothing Minimum requirements for entry.
Other NO ENTRY allowed to this area under this RWP when Control Rod Drives cro being rebuilt.
- 50550
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MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-005 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1
, a b
Question:
o A truck rollover on the freeway has resulted in an ammonia concentration of >50 ppm over a large area of the plant protected area.
How would you classify this emergency?
Answer:
Alert, Guideline 16.
1
Reference:
A.2-101, pg 31 of 54 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-006 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 i Page 1 of 1 ;
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l Question:
While attempting to fill a vacant shift, the individual on the phone states he had consumed an alcoholic beverage earlier in the day.
How much time since consumption of the alcoholic beverage must pass before the individual can report to work? __ _. _
_ _ ._ _ q Answer:
5 Hours i
Reference:
FFD Handbook A.2-106, pg. 5 of 20 ;
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INITIAL SUBMITTAL OF THE WALKTHROUGH JPMS FOR THE ,
MONTICELLO EXAMINATION - THE WEEK OF AUGUST 23,1999 a-
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l \ ES-301 Individu:1 Walk-thr ugh TCct Outlins Form ES-301-2 Facility: Monticello Nuclear Generating Plant Week of Examination: 8/23/1999 l
Examination Level: RO Operating Test Number: 1 System / JPM Title / Type Safety Planned Follow-up Questions:
Codes
- Function K/AIG // Importance // Description i
- 1. 202001/ Start #11 Recire Pump / a. K4.02 / 3.1/ Adequate recirculation pump NPSH (M)(A)(S)(L) I
- b. A3.09 / 3.3 / MG set trip: Plant-Specific
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(D)(S) 2 l
- b. K3.01/ 3.2 / Reactor water quality
- 3. 223002 / Open MSIVs following a a. K4.04 / 3.2 / Automatic bypassing of selected isolations !
Group Iisolation 5 during specified plant conditions (D)(S)(L)
- b. K4.06 / 3.4 / Once initiated, system reset requires deliberate operator action _
- 4. 209001/ Perform a Core Spray test a. K6.05 / 2.8 / Loss of ECCS room cooler (s)
(M)(S)(A) 4
- b. K4.04 / 3.0 / Line Break Detection
- 5. 295003 / Restore LC 103 from a. AA1.01/ 3.7 / A.C. Electrical Distribution System.
LC-104 6 (D)(S)(L)(A)
- b. 2.2.13 / 3.6 / Knowledge of Tagging and Clearance l Procedures. I
- 6. 271000 / Recombiner Train a. 2.1.32 / 3.4 / Ability to explain and apply system limits and Switching 9 precautions. ,
(D)(S) l
- b. A3.01/ 3.3 / Automatic system isolations
- 7. 241000 / Synchronize the a. K1.01/ 3.8 / Reactor power Turbine / Generator to the Grid 3 (D)(S)(L)
- b. K3.02 / 4.2 / Reactor pressure
- 8. 201003 / Isolate a HCU a. A2.03 / 3.4 / Drifting rod I
(D)(P)
- b. K5.05 / 3.0 / Reverse power effect
- a. 295031 EA1.08 / 3.8 / Alternate injection Systems
- 9. 286000 / Use of Alternate injection systems for RPV Makeup, 8 (Firewater crosstie).
(N)(P)
- b. A1.05 / 3.2 / System lineups
- a. 2.1.28 / 3.2 / Knowledge of the purpose and function of major
7 (D)(P)
- b. A4.12 / 3.9 / Close/open SCRAM instrument volume vent and/or drain valves
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator (L)ow-Power,(P)lant,(R)CA l/ntc/mif L. _
Monticello Nuclear Generating Plant :
August 1999 RO Exam ;
Plantand - -
Sirnulator JPMs and !
Questions .
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lMONTICELLO NUCLEAR GENERATING PLANT . JPM-B.1.4-004
! TITLE: START NO.11 RECIRC PUMP Revision 0 l Page 1 of 7
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SRO: SRO/RO: X SRO/RO/NLO: NLO:
Plant
Reference:
B.1.4-05.02, Rev 8 Task Standard: Complete STEPS 1 through 6 of B.1.4-05.02 for Starting No.11 Recirc Pump Only 1
K/A
Reference:
202001- - Task No: A4.01 - Rating RO/SRO: 3.7/3.7 --H Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
CR202.009 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 10 Min Simulator: X Normal:
Alternate Maximum Time to Complete: 20 Min in-Plant: Path: X Time Critical: Yes X No Prepared By: gatv/-f1f Date: 7. g_py Reviewed By: Date: 7 gy pp v
Shift Supv/ Shift Mgr Review By: M /If % Date: j-jy-Sp h
Approved By: j (Supt Ops Trng) Date:
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3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated-Reso supv: OTRNG ( Assoc Ref MTCP.3.32 lsR: N Frea: 0 yrs ARMS: JPMB14004 l Doc Type: 8505 l Admin inrtials: Date:
1/cmb
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MONTICELLO NUCLEAR GENERATING PLANT JPM B.1.4-004 TITLE: START NO.11 RECIRC PUMP Revision 0 Page 2 of 7 l 2SIONN535!@EIMdjffgyyggQg3M SET-Upj}'3pd@Qggy.}gggy Simulator Setup:
Initialize to an 10 that has the Reactor shutdown and all rods are IN. Reactor water level should be above 30". Place the CRD System in service and align plant systems such that the operator may enter Ops Manual B.1.4-05.02 for performance of this JPM.
MO-2-53A Closed MO-2-43A Open Insert RR08A (NO.11 RECIRC PUMP MOTOR HI VIBRATION) during MG Set "A" Lube Oil temperature adjustment Step No.11 of JPM.
Initial Conditions: - '~ ~~ ~' '~
A Reactor startup is planned for next shift. All control rods are fully inserted and reac-tor water levelis above 30".
Initiating Cues: -
The Shift Supv directs you to start No.11 Recirculation Pump, in accordance with the procedure.
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.4-004 TITLE: START NO.11 RECIRC PUMP Revision 0 j Page 3 of 7 l PERFORMANCE INFORMATION l lggggPyfgrgjaneggjectivejfjQQ EgggjiggStandardj3ggjggggg STEP 1 Standard: j Locates procedure and verifies all pre- Locates appropriate procedure, step, and verifies l requisites are met, all necessary prerequisites are completed.
l Cue: 1 Bus 11 is being supplied from 2R Transformer, operator verifies knife switch 4 in Panel C-31 is closed. l Comments:
Procedure B.1.4-05.02.
STEP 2 (Procedure STEP 1) Standard:
Complete Form 2114 (Prestart Checklist None
- Reactor Recirc System).
Cue:
Form 2114 is complete for the Reactor Recirc System.
Comments: None 4 STEP 3 (Procedure STEP 2a) Standard:
Verify the following for start of 11 Recire Closes or verifies closed MO-2-53A.
pump:
Cue: None Valve MO-2-53A,11 RECIRC PUMP Comments' DISCHARGE CLOSED.
Verification is performed by observing the green
" closed" indicating light on.
STEP 4 (Procedure STEP 2b) Standard:
Valve MO-2-43A,11 RECIRC PUMP Opens or verifies open MO-2-43A.
SUCTION OPEN.
Cue: None Comments:
Verification is performed by observing the red "open" indicating light on.
STEP 5 (Procedure STEP 2c) Standard:
Position Indicator 2-184-22A reads Verifies that No.11 Recirc pump Position Indicator approximateiy 2.55 (2.45 - 2.65) for 11 2-184-22A reads approx 2.55.
Recirc Pump.
Cue: None Comments: None 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.4-004 TITLE: START NO.11 RECIRC PUMP Revision 0 Page 4 of 7 l E E[iYEL D,o(maggg g et,ije g y,g @h;jlQQggSgndardjXQPyggy.g STEP 6 (Procedure STEP 2d) Standard:
Scoop tube lock is reset for 11 Recirc Verifies alarm C04-C-05 is not in the alarm condi-pump. tion.
Cue: None
, Comments: None STEP 7 (Procedure STEP 2e) Standard:
The recirculation system annunciation Verifies no abnormal or unexpected annunciators on Panel C-04 is normal for 11 Recirc are in the alarm condition.
pump.
_ . _ _ _ . _ . _ _ _ Cue: .None _
Comments: None STEP 8 (Procedure STEP 2f) Standard:
Valve AO-2-2-11 A,11 RECIRC PMP Verifies green light on.
SEAL LEAKOFF is CLOSED as indi-cated on C-04 (green light on). Cue None Comments: None STEP 9 "C" (Procedure STEP 3) Standard:
NOTE: The RECIRC PUMP Places #11 Recirc M/G set drive motor DISCHARGE valve must be at tandswitch (2A-S1 A) to the START position least 20-25% open within 66 momentarily.
seconds of M/G set start or a (Non Critical cortion of Standard) trip will occur. 20-25% open corresponds to a 6-8 second Verifies pump start by the following:
Ith the valve gn*tro" sign -
- 1. MG Set Drive Motor light indication changes from green to red, Place 11 MG Set drive motor control AND switch to START and observe: 2. Generator speed peaks at a point between 30
- a. Generator speed peaks and 100% s aeed, as indicated on meter Si 2-184-16A, 3 ump Speed.
between 80 to 100% speed g (because field generator breaker is OPEN). 3. Generator field breaker closes about 6
- b. Generator field breaker seconds after the drive motor breaker is CLOSED approximately 6 closed, as indicated by the indicating light changing from green to red, seconds after dnve motor AND breaker is CLOSED
- 4. After the field breaker closes, enerator
- c. Generator speed lowers to about 40% speed and then speed slowly decreases to 40 speed and ;
lowers to minimum speed. then lowers to minimum. '
Cue: None )
Comments: None 1/cmb
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.4-004 ,
TITLE: START NO.11 RECIRC PUMP Revision 0 !
Page 5 of 7 I ggyypppgancg;O,ygytiv,ejjjjg Qigjgdggglgtpidgrdjgjiggo gg ,
STEP 10 "C" (Procedure STEP 4) Standard:
WHEN ten (10) seconds has passed Opens #11 recirc pump discharge valve by hold-after MG Set start, ing handswitch 2A-S7A, CW to the OPEN posi-THEN OPEN MO-2-53A,11 RECIRC tion, until the valve position indication changes PUMP DISCHARGE, from green to red.
AND observe the following:
(Non-Critical portion of Standard)
- a. Loop flow rises to 6500 GPM.
- 1. Performs required observations and
- b. Pump speed remains constant. verifications:
- c. Jet pump flow rises to 20% of a. Loop Flow - 6500 GPM on F1-2-159A.
rated (6 x 106 lb/hr).
- b. Pum speed rema!ns constant - - - -
- d. Pump Current - 50 (Normal for SI 84-16A.
25% speed)
- c. Jet Pump Flow - Flow on F1-2-3-928 is
- e. Pumo Volts - 900 (Normal for dependent on plant condition.
25% speed)
- d. Pump Amps - 50 on 2-184-22A
- f. Drive Motor Amps - 150 (Normal for 25% speed) e. Pump Volts - 900 on 2-184-23A.
- g. Valve AO-2-2-11 A,11 RECIRC f. Drive Motor Amps - 150 on 2- 184-24A.
PMP SEAL LEAKOFF is OPEN g. Seal Leakoff Block valve light indication, as indicated on Panel C-04 SV-2-2-11 A, is no longer lit.
(green light off).
Cue: None Comments: None STEP 11 (Procedure STEP 5) Standard:
NOTE: The pumps will be Calls APEO to monitor temperature and adjust it operated at minimum as necessary to maintain 100*F.
speed until reactor power is increased to Cue: I approximately 60% by Outlet of lube oil heat exchanger is 100*F.
control rod withdrawal per Ops. Manual C.1 (Startup Comments: None Procedure). I Monitor and adjust service water at 11 MG Set oil cooler to maintain lube oil temperature at approximately 100*F leaving the cooler.
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.4-004 TITLE: START NO.11 RECIRC PUMP Revision 0
{
Page 6 of 7
& N.P,:fo p jng @)jQ fg[Q [fjygQQ[QQfffQ$gQnjajffj[f,5gjggyjgjg STEP 12 "C" (Procedure STEP 0 ) Standard:
NOTE TO SIMULATOR OPERATOR: Operator Actions: C.6-4-B-25 (RECIRC PUMP AFTER RO calls APEO to I adjust / monitor oil temperature, 1. Operator monitors Recirc pump motor activate RR08A (RECIRC PUMP vibration and temperatures on TR-2-2-31 on MOTOR "A" til VIBRATION) C-21 and SPDS.
- 1. Monitor "A" Pump Motor 2. Operator dispatches Rx Bldg APEO to the temperatures and vibration via Recirc MG Set Room to:
SPDS and TR-2-2-31 (C-21), a. Determine Recirc pump motor vibrations
~
- 2. Dispatch an operator to the Recirc on VM-5603 MG Set Room to determine "A"
' - ~
Cue'-
Recirc Pump Motor vibration as indicated on local indicator When candidate dispatches APEO to MG Set VM-5603. Room, inform him vibration on No.11 pump motor
- 3. E "A" Recirc Pump Motor vibration remains at or above 3 mils, to$e n a l
THEN trip "A" Recirc MG Set per 3. Operator determines vibrations are high and B.1.4-05 ( CTOR trips A Recirc MG Set per B.01.04-05. l
- a. ps e motor breaker with HS OPE TO)
- 4. E"A" Recirc Pump Motor vibration b. Closes discharge valve with HS V-2-53A.
drops below 3 mils, j THEN perform the following: 4. Notifies the following:
- a. RESET vibration annunciator by a. Shift Supervision ,
depressing "A" Recirc Pump b. System Engineer Vibration Monitor Reset pushbutton on C-04. Comments: None
- b. Continue monitoring "A" Recirc Pump Motor vibration and beanng temperatures.
- 5. Notify the following: !
- a. Shift Supervision I
- b. System Engineer STEP 13 I INFORM CANDIDATE THAT JPM IS COMPLETE. l (Pre-approved prompt)
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MONTICELLO NUCLEAR GENERATING PLANT J PM.B.1.4-004 TITLE: START NO.11 RECIRC PUMP Revision 0 l Page 7 of 7 !
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Initial Conditions:
A Reactor startup is planned for next shift. All control rods are fully inserted and reac-tor water level is above 30".
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l 4-B-25 lI RECIRC PUMP MTR A WINDOW NUMBER
\" HI VIBRATION SETPOINT ACTUATING DEVICE i 3 mils after 5 Sec TD VM-5602 in Recirc MG Room 1 o l
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CONFIRMATORY INDICATIONS A Recirc Pump motor vibration Indicated by VM-5602 in Recirc MG Room and on SPDS. l l I AUTOMATIC ACTIONS INITIATED None I (3 l
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' OPERATOR ACTIONS 1
I 1. Monitor A Pump Motor temperatures and vibration via SPDS and TR-2-2-31 l -
(C-21),
- 2. Dispatch an operator to the Recirc MG Set Room to determine A Recirc Pump Motor vibration as indicated on local indicator VM-5603.
- 3. LE A Recirc Pump Motor vibration remains at or above 3 mils, THEN tria A Recirc MG Set per B.1.4-05 (REACTOR RECIRCULATION -
SYSTEk - SYSTEM OPERATION).
l 4. IE A Recirc Pump Motor vibration drops below 3 mils, THEN perform the following:
- a. RESET vibration annunciator by depressing A Recirc Pump Vibration Monitor Reset pushbuttcn on C-04,
- b. Continue monitoring A Recirc Pump Motor vibration and bearing l emperatures.
- 5. Notify the following:
- a. Shift Supervision
- b. System Engineer lLJ O) l C.6-004-B-25 Page 1 of 2 Rev. 1
1 l Question #: JPM-B.I.4-004-Q1 Point Value: 1.0 Time (Minutes): NA l CLOSED BOOK /NO REFERENCE MATERIAL ALLOWED.
During normal system operation, what are eight (8) conditions that will trip the Recirc Generator Drive Motor breaker?
i Answer: (Any 8 of 10)
- 1. Control Switch to Stop 6) Pump Suction valve <90% open
- 2. Drive motor bus undervoltage 7)
- Pump disch. valve <20-25% open i
- 3. Low lube oil press (6 sec. Delay) 8) Low-Low waterlevel(-47 inches)
- 4. Lube oil high high temperature 9) Auto initiation of LPCI
- 5. Gen Lockout relay tripped 10) Auto transfer ofstation aux
- 66 sec. Time delay on pump start. ,
l l
i Reference (s): B.I.4-02, pg.12 and 13 of 14 K/A
Reference:
A3.09 Task Number: 202001 i Rating: RO 3.3 l
j
r-4 Candidate's Response to JPM-B.I.4-004-Q1 o
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l Question #: JPM B.I.4-004-Q2 - Point Value: 1.0 Time (Minutes): NA l {
While operating at 75% power, what effect will a loss of feedwater have on the Recire System? (Assume Reactor water level does not decrease below -20 inches on the safeguards.) i l
i Answer:
i When feedwater flow decreases to <20% for 15 seconds, the Recire GM sets will automatically runback to minimum speed of 30%.
~ . --
Reference (s): B.5.8-01, pg. 4 of 5 K/A
Reference:
K4.02 Task Number: 202001 Rating RO: 3.1 l i
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Candidate's Response to JPM-B.I.4-004-Q2 i
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM Revision 5 Page 1 of G MREEMEEGEBRER SRO: SRO/RO: X SRO/RO/NLO: NLO:
Plant
Reference:
B.2.2-05.D.1, Rev 14 Task Standard: Place RWCU System in Service with No.11 RWCU Pump and 11 RWCU Filter /Demineralizer in Service _
K/A
Reference:
204000 Task No.: A2.04 Rating RO/SRO: 2.7/2.9 Recent Events: None Probabilistic Risk Assessment Human Error: None -
Monticello Specific Task List
Reference:
CR204.003 METHOD OF TESTING TIME FOR COMPLETION ~
Estimated Time to Complete: 10 Min Simulator: X Normal:
l Alternat- Maximum Time to Complete: 20 Min I In-Plant: Path. X Time Critical: Yes X No Prepared By: g < Date:
ppg Reviewed By: Q3 7 Date: /,- 9 -?9 l Shift Supv/ Shift Mgr Review By: Date: ffg Approved By:
v
[ (Supt Ops Trng) Date: 4_ p pp 4
i
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a ... . .?' -
. Fo; ftjki'15 U* E(:'id F ~ e~ *% - ---
I 13087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated- #n6 l Resp Supv: OTRNG l Assoc Ref: MTCP-3.32 lsR: N Frea: 0 yrs ARMS: JPMB22001 l Doc Type: 8505 l Admin initials: MVA Date: If flo/fN'
~ L/
1/cmb -
l AGONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 i T!TLE: STARTUP THE RWCU SYSTi M Revision 5 l Page 2 of 5 i l
$N? W $$$iUli$$$ $ $ $ U='z,Ph21%[Q 1U Qj g gifLf'fQ*Q Simulator Setup:
Initialize to 'ny 10 with the Reactor shutdown, <212*F and RWCU out of service. 1 RWC') syuma sould be unisolated with both pumps off.
Insert the followin IOS to cause a failure of No.11 RWCU pump to start: S26-02 (A520P28-26), Di ital Value to OFF, INSERT.
Initial Conditions:
The Reactor is Shutdown and Reactor coolant temperature is <212*F. Preparation for a plant startup are in progress. The RWCU system is ready for operation. The No.
12flWCU Filter is being backwashed and wilt be putinseTvice later -
The RWCU pumps and heat excilangers are filled and vented. RBCCW and Instru-ment Air are operating properly.
Initiating Cues:
The Shift Supv directs you to place RWCU system in service by performing STEPS 12 through 14 of the RWCU system startup procedure B.2.2-05.D.1. Use No.11 RWCU pump and No.11 Filter.
All required steps prior to STEP 12 have been successfully completed. -
1/cmb z
1 MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM . Revision 5 Page 3 of 5 PERFORMANCE INFORMATION '
3@l,PirforniahcE'O6]gige]jgg? gggg[g"{thyggdyggggy STEP 1 Standard:
Locate procedure B.2.2-05 D.1., Startup Locates appropriate procedure and steps.
of 11 or 12 Reactor Water Cleanup Sys-tem. Cue: None Comments: None l l
STEP 2 "C" (Procedure STEP 12) Standard:
CAUTION Attempts to start 11 RWCU pump using ;
_. STEP 13 must be performed immedit HS-12A-SS, realizes pump does not start. Noti- !
ately following STEP 12. fies. Shift Supv' (N n- r al n an ad Start a Reactor Water Cleanup pump l using the PLmp A or Pump B switch for Operator should observe the following: I the desired pump.
- 1. Pump run iridication does not change from green to t ed. l
- 2. CLEANUP PUMP DISCH pressure as indicated on PI-12-131 does not increase.
Cue: -
Shift Supv notifies operator that investigative and corrective actions will be started and to use the 12 pump.
Comments: !
Do NOT give cue if operator does not notify the Shift Supv.
STEP 3 "C" (Procedure STEP 12) Standard:
CAUTION Starts 12 RWCU pump using HS-12A-S6.
STEP 13 must be performed immedi- (Non-Critical portion of Standard)
Gtely following STEP 12.
Operator should observe the following:
Start a reactor water cleanup purnp using the Pump A or Pump B switch for 1. Pump run indication changes from green to the desired pump. md.
- 2. CLEANUP PUMP DISCH pressure as indicated on PI-12-131 increases.
Cue: None Comments: None 1/cmb
b MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM . Revision 5 Page 4 of 5 MS$$ Ilk.p{Qg @ gygggfjtg g g j g . g g .i g Sts53 rd g dg.pyg gepp g g y STEP 4 "C" (Procedure STEP 13) Standard:
NOTE 1: The AIR-TO-LOCK- Directs the Radwaste APEO to slowly OPEN GAUGE will indicate CV-12-4-15A.
alve sta to ope (Non-Critical cortion of Standard)
NOTE 2: At flow >35 gpm the Operator should observe the following:
HOLDING PUMP will trip 1. C04-B-21, CLEAN UP FILTER DEMIN and AO-12-4-37A will FAILURE clears.
close.
- 2. FILTER A FLOW as indicated on F1-12-141 A Slowly open Filter Demin T-202A Outlet, . increases. - -
CV-12-4-15A, by turning the regulator knob at the 11 RWCU Filter T-202A Flow Cue:
Control, FIC-12-4-97A, on Panel C82. CV-12-4-15A is open.
Comments:
The RWCU pump has no minimum flow protec-tion. If this step is not performed, pump damage will occur.
Simulator operator places No.11 RWCU F/D in -
service.
STEP 5 (Procedure STEP 14) Standard:
Increase the flow through the filter /de- Directs the Radwaste Operator to increase flow min to 70 gpm using FIC-12-4-97A. on No.11 F/D to 70 gpm.
(Non-Critical portion of Standard)
Operator should observe that FILTER A FLOW as indicated on F1-12-141 A increases to =70 gpm.
Cue: None Comments:
Simulator Operator increases flow on No.11 RWCU F/D to 70 gpm (=72%). It is allowable to put the cleanup up to 85 gpm maximum on one filter.
STEPG Standard:
INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-l TASK HAS BEEN COMPLETED. pleted.
Cue: None Comments: DO NOT PROMPT!
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM Revision 5 '
Page 5 of 5 l
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T CANDIDATESICQPJBISA (,yg?g-g initial Conditions:
The Reactor is Shutdown and Reactor coolant temperature is <212*F. Preparation for -
a plant startup are in progress. The RWCU system is ready for operation. The No.
12 RWCU Filter is being backwashed and will be put in service later.
The RWCU pumps and heat exchangers are filled and vented. RBCCW and Instre-ment Air are operating properly.
SvMINEORM3TEIEEVACUgORiWEENKO_UJEfAVJdCO_MPEETEDKHEiT6SE! ! JIM I/cmb
l Question #: JPM-B.2.2-001-Q1 Point Value: 1.0 Time (Minute @ NA l During a Reactor Startup a Group I occurs from 30% power and water level has swelled to +58". The Shift Supervisor requests that RWCU be placed in service with MO-2399 closed, allowing all flow to be routed to the condenser. With a scram signal still present and a CRD pump in service, will Reactor level increase or decrease when minimum dump flow is established? (Assume Reactor pressure is 750 psig and very slowly decreasing.)
Answer:
Increase. The CRD system is injecting approximately 100 gpm. The maximum blow.
down limit with all flow routed to the condenser is 79 gpm.
Reference (s): B.2.2-05, pg 40 of 71 i K/A
Reference:
A4.03 Task Number: 204000 Rating RO: 3.2 i
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1 Candidate's Response to JPM-B.2.2-001.Q1 o
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Question #: JPM-B.2.2-001-Q2 Point Value: 1.0 Time (Minutes): NA l l
l Scon after returning No. I 1 RWCU filter to service, Reactor conductivity increases to the l point where significant damage could occur over a short period of time. How long do
- you have to reduce conductivity to an acceptable value and what requirement is associated if this time limit is not met?
Answer:
If the parameter is not reduced to below the action level within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then initiate an orderly plant shutdown and cold shutdown achieved within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
- .~ , .. . . . - ..
Reference (s): C.2-05, pg.14 of 20 K/A
Reference:
K3.01 Task Ntunber: 204000 Rating RO: 3.2
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I Candidate's Response to JPM-B.2.2-001-Q2 o
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l 1 l-MONTICELLO NUCLEAR GENERATING PLANT JPM B.2.4 001 j TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 )
GROUP l ISOLATION Page 1 of 11 1
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> *? A % S I i L
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$bM2 dim @iEhili?6IddQld&2I5hpB@B!!BEREOplM$' f5 min MidiiE!Eidh$M i hk
~W SRO: SRO/RO: X SRO/RO/NLO: NLO:
1 1
Plant
Reference:
B.2.4-05.H.1, Rev 14 Task Standard: Open the MSIVs following a Group i isolation K/A
Reference:
239001 - - - - Task No.E A4.01 Rating RO/SRO: 4.2/4.0 - -- -~ !
Recent Events: None Probabilistic Risk Assessment Human Error: None .
Monticello Specific Task List
Reference:
CR239.003 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 15 Min Simulator: X Normal: X Alternate Maximum Time to Complete: 30 Min in Plant: Path:
Time Criticai: Yes X No Prepared By: gd M Date: y-/y pf Reviewed By: - Date: 7-/y 0p 7 Shift Supv/ Shift Mgr Review By: // M fvl Date: y- /y-Ff Approved By: gh (Supt Ops Trng) Date: 7-fy.gg 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated-Resp supv: OTRNG l Assoc Ref: MTCP 3.32 IsR: N Frea: 0 yrs ARMS: JPMB24001 l Doc Type: 8505 l Admin initials: Date:
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 2 of 11
!!MfAMASMiFi2Mi31si!MOU3{JJM]ETgggggggggg{gggfggggg I Simulator Setup:
Initialize to any IC which places the Reactor at power and insert malfunctions PPOSA and PP05B to create a spurious Group I Isolation. Clear the malfunctions, place the Reactor mode switch to the SHUTDOWN position and reset all annunciators. Verify all EOP entry conditions are clear.
Initial Conditions:
The Reactor is in a hot shutdown condition following a Reactor Scram due to a spuri-ous Group I isolation. The initiating signal for the spurious Group I was determined and corrected. The Main Steam Lines are still hot.
.,_ initiating Ques-The Shift Supv directs you to re-open the MSIVs per Ops Manual B.2.4-05 procedure, Steps 1 through 13. Another operator will perforc. Step 14.
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 3 of 11 PERFORMANCE INFORMATION
[yjggj!ggdogmangeJge,ctigeggjgy ggggg$@yyjytagyarppg[gfgggyjggg STEP 1 Standard:
Locate procedure B.2.4-05.H.1, "Open- Locates appropriate procedure and determines ing MSIVs Following a Group I isola- status.
tion", and reviews precautions, limita-Cue *-
tions, and preyequisites.
- 1. {
Outboard MSIV air pressure is 270 psig. >
- 2. Main Condenser and auxiliaries are available for service.
Comments: None
' ~
' ~
STEP 2
~~
(Procedure STEP 1)~ Stindard:
Verify the following: 1. Verifies that the initiating signal for the Group I
- a. Initiatin gnal for i e Group 1 isolation has cleared b monitoring I parameters,and given fnitial conditions.
- 2. Operator should verify annunciators 5-A-44,
- b. 1E Group 1 isolat. ion caused by one of the following: Group 1 CHAN A TRIP and 5 A-52, Group l l
' CHAN B TRIP are reset.
- 1) TemperatureSteam Cue:
Tunnel High None j
- 2) Main Steam Line High Flow mmen s: None
- 3) Main Steam Line Low Pressure THEN confirmation made that main steam line break has not occurred.
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l MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 l
GROUP I ISOLATION Page 4 of 11
$DgjgPgrformapcepgeg}iveigg Engglggg5jtar[dard Mygygggy STEP 3 "C" (Procedure STEP 2) Standard:
Reset the Group I isolation by perform- 1. Places HS 16A-S1 A for A0-2-80A to CLOSE, ing the following: AND
- b. RESET Group i isolation by 3. Places HS 16A-S1C for AO 2-800 to CLOSE, depressing pushbuttons AND 16A-S32A and 16A-S328, Main 4. Places HS 16A-S1D for AO-2-80D to CLOSE, Steam isolation Reset -Inboard AND and Outboard, respectively
. (Ranel C-03)._ 5. Places HS_16A-S2A for AO 2-86A to CLOSE, 3 AND 1
- 9. Resets Group 1 isolation by depressing pushbutton 16A-S32A, AND
- 10. Depresses pushbutton 16A-S32B.
(Non-Critical nortion of Standard)
Operator should observe the following:
- 1. All MSIVs closed by observing light indications, AND
- 2. Group i reset by observing white l'ght i
indicators above pushbutton 16A-S32A lit, AND
- 3. White light indicators above pushbutton 16A-S328 lit.
Cue: None Comments: None STEP 4 (Procedure STEP 3a) Standard:
Isolate steam usage downstream of the 1. Places No.11 Recombiner Train Selector MSIVs by performing the following: Switch TSS-A to SHUTDOWN, AND
- a. Place both recombiner trains in 2. Places No.12 Recombiner Train Selector SHUTDOWN. Switch TSS-B to SHUTDOWN.
Cue: None Comments: None l/cmb l
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 5 of 11 ggggge@gnanggbjgctlyegg; c jig ggsj7dgggy,gtandydfgggggg3 STEP 5 (Procedure STEP 3b) Standard:
Place both SJAE steam su 3 ply pressure 1. CLOSES CV-1242 using 11 SJAE E-2A controllers in MANUAL anc CLOSE the PRESS controller by taking controller to following steam supply valves: MANUAL and turntg control knob to closed p sWon, A@
- a. CV-1242
- 2. CLOSES CV-1243 using 12 SJAE E-28
- b. CV-1243 PRESS controller by taking controller to MANUAL and turning control knob to closed position.
Cue: None
~ --
l Comments.
The controller must be turned CW to close valve.
STEP 6 (Procedure STEP 3c) Standard:
l_ CLOSE the _following: Closes MO-104'S using HS-1045,6N_DQ
- a. Md-1045, Steam Seal Reg (Non-Critical nortion of Standard) 1 Feed Valve
- 1. Verifies MO-1046 is closed.
- b. MO-104 Steam Seal Reg
- 2. Operator should observe valve position YP indicating lights changing from red to green.
Cue: None Comments: None STEP 7 - (Procedure STEP 3d) Standard:
CLOSE the following main steam line 1. Verifies MO-2565 CLOSED, M drain valves:
- 2. Verifies MO-1739 CLOSED, M
- 1. MO-2565, Steam Line Drain Orifice
- 3. Verifies MO-1617 CLOSED,6NQ Bypass
- 2. MO-1739, Turbine Steam Bypass e es m000 GOSED, M Ndr Drain 5. Verifies MO 1180 CLOSED, ANQ
- 3. MO-1617, Deaerating Steam Supply 6. Verifies MO-1181 CLOSED,6NQ
- 4. MO-4000, Main Hdr Press Equalizer 7. Verifies MO-1182 CLOSED,6_N_Q N Drain 8. Verifies MO-1183 CLOSED.
- 5. MO-1180, Main Stop Valve SV-1 Drain (Non-Critical nortion of Standard)
- 6. O,181, Main Stop Valve SV-2 [ tor should observe valve position indicating
- 7. MO-1182, Main Stop Valve SV-3 Cue: None Drain Comments: None
- 8. MO-1183, Main Stop Valve SV-4 Drain l/cmb i
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 1 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP IISOLATION Page 6 of 11 ggggeppnytangpbj9ct!yg4;g ( g gg g g g g g gtayuiard yy g g ;; g g g STEP 8 (Procedure STEP 4) Standard:
CLOSE Turbine Bypass Valves. Closes Turbine Bypass Valves.
l (Non-Critical portion of Standard)
Operator should observe valve position indication. l Cue: None l l Comments: None STEP 9 (Procedure STEP 5) Standard:
l Perform the following: Operator verifies air supply pressure by checking ~
computer point AIR 100. ~ ~ ~
- a. Verify main air supply pressure is 255-285 psig. Cue:
- b. IE main air supply pressure is Air pressure reading is 270 psig.
above 285 psig, THEN vent per Ops Manual Comments Section B.2.4-05.G.4, S ecial Simulator computer point may be unavailable, Procedures - Relieving h therefore the operator must be provided with the Pressure in the Main Ai upply reading. Procedure B.2.4-05.G.4 is not required to Outboard MS'Vs, prior to because air pressure did not exceed 285 psig.
opening the outboard MSIVs.
STEP 10 "C" (Procedure STEP 6) Standard:
CAUTION Operator opens Outboard MSIVs using HS-16A-S2A, AND HS-16A-S28, AND Operation of an Outboard MSIV with HS-16A-820, and HS-16A-S2D.
main air supply 3ressure above 295 psig may result n actuator damage. (Non-Critical portion of Standard)
Open each Outboard MSIV, AO-2-86A Operator should observe valve position indicating through D, as follows: lights change from green to red.
- a. Depress and hold TEST Cue: None pushbutton.
i Comments: None
- b. PLACE handswitch to AUTO /
l OPEN.
- c. Intermittently release and depress TEST pushbutton at approximately 1/2 second -
intervals to jog open MSIV.
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP iISOLATION Page 7 of 11 pgg{Pyrfgjmanjpyge,c{ivejg(g g p p ygg g g ![S[aj!yaf g Jp{g g g g g g STEP 11 (Procedure STEP 7) Standard:
CLOSE MO-2564, Steam Line Drain Closes MO-2564 using HS 16A-S35.
Downstream MSIVs.
(Non-Critical cortion of Standard)
Operator should observe valve position indicating lights change from red to green.
Cue:
Text Comments: None STEP 12 'C" (Procedure STEP 8) Standard:
~~ ~'
~ ' ~ ~ ~
OPEN inboard and outboard Main 1. Opens MO-2373 using HS 16A-S5, AND Steam Drain isolation Valves: 2. Opens MO-2374 using HS 16A-S6.
- a. MO-2373 (Non-Critica! c'ortion of Standa_rd)
- b. MO-2374 Operator should observe all valve position indicat-ing lights change from green to red.
Cue: None Comments: None STEP 13 "C" (Procedure STEP 9) Standard:
Perform the following: Opens MO-2564 using HS-16A-S35.
- a. OPEN Outer Steam Line Drain (Non-Critical cortion of Standard) 4, to pressurize aro d Si s Operator should observe the following:
- b. IE hot shutdown condition has 1. Valve position indicating lights change from been long enough to allow green to red.
steam lines downstream of 2. Annunciators 5-A-33, MAIN STEAM LINE MSIVs to cool down. LOW PRESS CH A and 5-A-34 MAIN STEAM THEN control warming rate by LINE LOW PRESS CH B reset.
opening and closing MO-2564 intermittently. Cue: None Comments:
The steam lines are hot.
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 8 of 11 O
WlA:W$E*$$5*,n,cfy,b,)ejt,i,yey,ggy G y }lg gfiq Q gStap h rd y g g g g g STEP 14 (Procedure STEP 10) Standard: None NOTE: The computer point Cue:
AIR 100 alarms and If operator asks for readings of AIR 100, state that ze s of t me 3ressure the main air pressure.is 270 psig, s above main a r pressure Comments: None pe athon a'bo e 2 psig Procedure 0255-07-IA-1 is not required to be per-may be determined by for,med as main air pressure did not exceed 295 referring to AIR 100. psig.
if an Outboard MSIV actuator has been
- operated above main air pressure of 295
~ ~
asig, verify operability by performing
'rocedure 0255-07-IA-1 on affected out-board MSIV(s).
STEP 15 "C" (Procedure STEP 11) Standard:
CAUTION 1. At <100 psid, de resses the TEST pushbutton I" " ^
A water hrmmer could occur if inboard MSIVs are opened at differen. 2. Places HS-16A-S1C in AUTO /OPEN, AN_Q.
tial pressures >100 psid. 3. Intermittently releases and depresses TEST WHEN pressure difference between aushbutton at approximately 1/2 second main steam lines and reactor is s 100 nistvals to Jog the first MSIV open.
N OPEN inboard MSIV AO-2-800 ~
as follows: Operator should observe the following:
- a. Depress and hold the TEST 1. The 100 psid can be determined by using pushbutton. Pl-4274 for MSL pressure and any Reactor pressure indicator.
- b. PLACE handswitch in AUTO /OPEN. .
- 2. Valve position indicating lights change from green to red.
- c. Intermittently release and depress TEST pushbutton at 3. Valve position indication on Primary approximately 1/2 second Containment Mimic Board on C-03, changes intervals to jog open MSIV. from green to red.
Cue: None Comments: None 1
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1 MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 9 of 11 d$h3$E'd.oJJpangeggpctgeggjgy; ~@gj:pg@gStaydardjggi;ygiggjpg STEP 16 (Procedure STEP 12) Standard:
NOTE: Inboard MSIVs "A", "B", and Operator opens inboard MSIV:
"D" may not open until 1. AO-2-80A using HS-16A-S1 A, AND i differential pressure across l valves is less than 2. AO-2-80B using HS-16A-S1B, AND appmximately 77 psid. 3. AO-2-80D using HS-16A-S1 D.
OPEN the following inboard MSIVs: Cue: None
- a. AO-2-80A Comments: None
- b. AO-2-80B
' ~ ~ ~
'c. AO-2-80D l
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1 i MONTICELLO NUCLEAR GENERATING PLANT
_ JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 :
GROUP IISOLATION Page 10 of 11
@@iN?d!fgtmanJgoggt!yegsggg [g-ggggggggtanyag@ygingjgggg l STEP 17 (Procedure STEP 13) Standard:
CAUTION l
Steam seal relief valves will start to lift at a seal steam pressure of 20 psig.
NOTE: A Control Room alarm will annunciate at a seal steam 4 pressure of 1.5 psig. l Place seal steam in service by perform-ing the foNowing: '
- 1. Operator throttles open MO-1046 and control
- 1. Throttle Open MO-1046 (STEAM steam seal pressure at 4 psig.
SEAL REGULATOR BYPASS VALVE), as required to control 2. Operator mainta. ins steam seal header steam seal header pressure at 3ressure at 4 psic by opening MO-1047 approx. 4 psig. . F pressure is > 5 psig, or opening MO 1046 F pressure is < 3 psig.
- 2. Maintain steam seal header pressure at approx. 4 psig. Comments: None
- a. E steam seal header pressure is >5 psig, THEN open MO-1047 (STEAM SEAL REGULATOR UNLOADING VALVE) to unload excess steam.
- b. E steam seal header pressure is < 3 psig, THEN OPEN MO-1046 to increase steam '
seal header pressure.
STEP 18 Standard:
INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted.
Cue: None Comments: DO NOT PROMPT!
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP l ISOLATION Page 11 of 11 1
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5 M N M M 31583937 M $33k W R -
Initial Conditions:
The Reactor is in a hot shutdown condition following a Reactor Scram due to a spuri-ous Group I isolation. The initiating signal for the spurious Group I was determined and corrected. The Main Steam IJnes are still hot.
M.351UFSBM}JHREVgy,6TppffMEgy_OMti&ygpSMB[plE, REM,6 1/cmb
I l Question'#: JPM-B.2.4-001-Ql . Point Value: 1.0 Time (Minutes): NA l While pertonning logic testing, an inadvertent Group I occurs with the ; lant at 100%
poiver. C.4-A instructs the operator to reset the reactor scram as soon as possible.- What must be done to reset the scram under these conditions?
Answer:
Reduce Reactor pressure to <600 psig or open the MSIVs. 1 1
~
l Reference (s): B.5.6-06, pg 8 of 17, Figure 6 '
K/A
Reference:
K4.04 Task Number: 223002 Rating RO: 3.2 I
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Candidate's Response to JPM.B.2 4 001.Q1 1
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I -# T l Question #: JPM-B.2.4-001-Q2 Point Value: 1.0 Time (Minutes): NA l What effect will a loss of Y-80 have on the Group I logic and what operator action is required when power is restored? -
Answer:
Loss of Y-80 will de-energize the white MSIV AC outboard solenoid power indicating light on C-04.
When power is restored, then momentarilyjumper from M3 to T1 on relay 16A-K68 on
~- - ~ ~ ~ ~ ' '
C-03. -
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Reference (s): B.5.6-06, pg.11 of 12; B.S.6-06, pg 16 of 17, Figure 14; C.4-B.9.13.G, pg 3 of 13 K/A
Reference:
K4.06 Task Number: 223002 Rating RO: 3.4 1
l e
r Candidate's Response to JFM-B.2.4-001-Q2 i
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~, MONTICELLO NUCLEAR GENERATING PLANT J PM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 1 of 8
~
Y ?Y dBMIEW!fbhbbbk&&M8Eb bbbbEhbh SRO: SRO/RO: X SRO/RO/NLO: NLO: _
Plant
Reference:
Core Spray System Tests No. 0255-03-IA-1, Rev 25 Task Standard: Perform STEPS 5-10,12-13, and 15-21 of Core Spray Systems Tests No.
0255-03-IA-1 K/A
Reference:
209001 - - - -- Task No.: A1.02- Rating RO/SRO: 3.2/3.4-A .6 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
CR209.007 CR209.018 NL209.003 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 20 Min Simulator: X Normal:
Alternate Maximum Time to Complete: 40 Min l In-Plant: Path: X l Time Critical: Yes X No Prepared By: /dul- /V1 Date: 7-- f y. 9)
Reviewed By: Date: 7-/c;/- $p Shift Supv/ Shift Mgr Reviewh Moul- /Mo Date: /- /y- 9 7 Approved By: (Supt Ops Trng) Date: 7-/V fp 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:
Resp Supv- CTRNG l Assoc Ref MTCP-3.32 lsR: N '
Frea: 0 yrs ARMS: JPMB31005 l Doc Type: 8505 l Admin inrtials: Date:
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01-005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 2 of 8 g ggjgggy@jQgggggg gfy@pggS,E EPgg g g gggg g g g g g g;g Simulator Setup: l Initialize to any IC that places the plant at 100% power with the Core Spray system operable.
Digital flow indication for CS is NOT selected to CS.
Fill out4255-03-IA-1 as follows: -
- Sign Shift Supv approval.
- Reason for performing: Other _X e Write in Comments, " Perform STEPS 5-10,12-13, and 15-21 for PMT."
~' ~ ~'
-"- ~ ~ - ~ '
- N/Kall~other stb ~psin procedurs.
- Trip No.11 Core Spray Pump when JPM Step No.12 is complete. (CS01 A)
Initial Conditions:
The plant is at 100% power. Maintenance has just been completed on the No.11 Core Spray pump.
Initiating Cues.
The Shift Supv directs you to perform selected portions of the Core Spray System Tests No. 0255-03-IA.
Provide bosrator with a copy of Test.
Provide operator with stopwatch. (Simulated calibration date.)
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 3 of 8 .
PERFORMANCE INFORMATION E M E09A"1"la,,gg g g yt!geTg p Q pggggyylggStanyargsyf3,gglggg STEP 1 (Procedure STEP 5) Standard:
Verify that a suction pressure of 2 3 1. Directs Reactor Building APEO to read pump psig and a discharge pressure of 2 30 suction pressure from local indicator psig exist. Record the indicated values PI-14-36A, from the following instruments: AND
- a. PI-14-36A,11 CS PUMP 2. Verifies that pump discharge pressure is 2 30 SUCTION PRESSURE. psig on PI-14-48A.
psig. Cue:
- b. PI-14-48A, DIVISION 1 CS Reactor Building APEO reports that PI-14-36A PUMP PRESSURE- indicates 5 psig.
psig. l Comments: None STEP 2 "C" (Procedure STEP 6) Standard: !
CAUTION: Starts 11 Core Spray pump by momentarily plac- l ing control switch HS-14A-SSA in START. l Do not start pump if system is not pressurized, as damage could result (Non-Critical portion of Standard) i
" " P "
g an un i le i e. Operator should observe the following.
START P-208A,11 CORE SPRAY 1. Pump run indication changes from green to l red.
PUMP (Breaker 152-505).
- 2. Pump discharge pressure as indicated on l PI-14-48A, increases to ~360 psig. '
- 3. Annunciator C03-A-41, AC INTERLOCK, alarms. l Cue: None Comments: None j 1
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01-005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 4 of 8
[jgg;gggprfogancpJggcgyejygg ggpigjgj{ggygSMndajdg[iggggg STEP 3 "C" (Procedure STEP 7) Standard:
NOTE: Establishing flow verifies 1. Selects CS for readout.
the pump's check valve CS-9-1 has opened. 2. Throttles n MO-1749 using handswitch HS-14A-S4A until FI-7189 indicates the Slowly OPEN MO-1749,11 CORE appropriate mV value, SPRAY TEST *LINE TO TORUS, until AND F1-7189, CS LOOP A FLOW, indicates 10.01 - 10.13 mV. Record mV reading
- 3. Records mV reading, AND and hour and minute. Reference value: 4. Records Hr/ Min reading.
3080 gpm (10.07).
(Non-Critical cortion of Standard)
__ m mV _. -
Operator should observe the following.
Hr/ Min 1. Valve position indication changes to dual indication (green and red) from green only.
- 2. System flow as indicated on F1-14-50A, increases to =3080 gpm.
- 3. Pump discharge pressure as indicated on PI-14-48A decreases to =300 psig.
- 4. Records Hr/ Min.
Cue: None Comments: None STEP 4 (Procedure STEP 8) Standard:
Verify the pump has run at least 2 min. 1. Verifies that the pump runs for at least 2 utes, at the rec;uired flow before pro- minutes, caeding record hour and minute. AND Hr/ Min 2. Records hour and minute.
Cue: None Comments:
Evaluator ma of this JPM. y shorten run time for performance STEP 5 "C" (Procedure STEP 9) Standard:
Record dischar e 3ressure indicated on Records ump discharge pressure from PI-14-48A, CS U VIP 11 DISCHARGE PI-14-48 PRESSURE.
Cue: None Comments: None psig
>279 psig 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 5 of 8 EidEE850l!3aycepggtijegggy (([gy{$gggg$Jian_da dyf{gggg3 STEP 6 "C" (Procedure STEP 10) Standard:
Record pump suction pressure as indi- Calls APEO and asks for pump suction reading, cated on local indicator PI-14-36A, CS records reading.
PUMP 11 SUCTION PRESSURE.
Cue:
Pump suction pressure 4 psig.
Comments: None STEP 7 "C" (Procedure STEP 12) Standard:
Calculate the differential pressure by Records the proper values and determines the
~
Aubtractirig pump sucjon pressure fr.om. D P. . __ _ ___- .. . .
pump discharge pressure.
Cue: None Discharge Press Suction Press FETtT Comments: None STEP 8 "C" (Procedure STEP 13) Standard:
NOTE: Required Action Ran e 1. Determines AP in the acceptable range, AND p requirem nt which 2. Irdtials the appropriate line.
are more restrictive than Cue: None Section XI requirements. Comments: None Initial the appropriate line to indicate the range in which the differential pressure of P-208A,11 CORE SPRAY PUMP, falls. The reference value is 297 PSID.
Acceptable 276 to 327 PSID:
Rec uired Action < 276 and > 327 PSI 3:
- a. IE the value is in the Required Action range, THEN notify the Shift Supervisor.
STEP 9 (Procedure STEP 15) Standard:
Conduct vibration measurements of Operator notifies en P-208A. Record data on Appendix 1. vibration analysis. gineering staff to complete Attach the vibration analysis results to >
the test. Cue:
Vibration tests are complete. Readings are acceptable.
Comments: None 1/cmb
F l
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 6 of 8 l
% KJgeggggnyeJ M Q$1p y;M Q @jyfjggggjgjStagdaggggy[gyg[3g STEP 10 (Procedure STEP 16) Standard:
Initial the appropriate line to Indicate the Operator initials Acceptable Range, range in which the vibration values for P-208A fall. Cue: None Acceptable Range: Comments: None o
Alert Range:
Required Action Range:
- a. lE any value is in the Alert or Required Action range, THEN notify the Shift- ---- - - - -- ----
Supervisor.
STEP 11 (Procedure STEP 17) Standard:
Perform the following: Records voltage on bus 15 from V4K104,
- a. Record 15 bus voltage from (Nekcontacts APEO to obtain motor amps from computer point 15 BUS VOLTAGE (V4K104). Cue:
15 bus voltage Volts. Motor amps are 75,74,75.
- b. Record P-208A motor amps Comments: None from breaker 152-505 (Turbine Bldg, El 911, 4KV area).
Motor Amps:
1 2 3 STEP 12 (Procedure STEP 18) Standard:
Fully OPEN MO-1749. Fully opens MO-1749 using HS 14A-S4A.
NOTE: Activate Malf CS01 A Cue: None (CORE SPRAY PUMP Comments: None OVERLOAD) when MO-1749 is Full Open.
l/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01-005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 7 of 8 M uyf39janpekOyjgypgjj;[5Q P
(QfgjllLygfygfQJanfQdjQ}gjgjggyyp STEP 13 Standard: No.11 Core Sorav Overload Alarm Reviews ARP 3-A-14 (CORE SPRAY PUMP NO. 3-A-14 11 OL/ MAN-OVRD)
- 1. Determines pump overload has 1. Dispatches Turb Operator to check Core occurred. Spray Breaker 152-505.
- 2. Isolate No.11 Core Spray per Cue:
B.03.01 -05.E.2 APEO reports ACB 152-505 relay flags indicate
- a. Place 14A-S5A, No.11 Core overcurrent.
Sp a Pu p o rolswitch
- 2. Isolates No.11 Core Spray, Pump per ULL-TO-L CK position. - B.03.01 -05.E.2.
- b. Place 14A-S1 A, MO-1753 Div i a. Places HS 14A-55A in PTL.
CS Injection inboard control b. Place HS 14A-51 A to Close and verifies switch, in the CLOSE position. Red Light goes out and Green Light
- c. Place 14A-S16A, MO-1751 Div i comes on.
CS Injection Bypass keylocked c. Places HS 14A-516A to Bypass. switch in the BYPASS position,
- d. Places HS 14A-52A to Close and verifies 4A- M 1751 vICS Red Light goes out and Green Light injection Outboard, in the comes on.
CLOSE position, e. Declares No.11 Core Spray INOP. I
- d. Declare No.11 Core Spray f. Notifies Shift Supervisor.
Inoperable.
- g. Notifies System Engineer.
- e. Notify Shift supervisor.
- f. Notify System Engineer.
STEP 14 INFORM CANDIDATE THAT THE JPM IS COMPLETE. ' I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01-005 l TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 8 of 8 o l l
.. . . . . . . - - _ . . _ ~. .. _ _ . . _ . . . , _ _ _
.__.j I
g
~
; 1. ' . +ls@.,1; :~;3.L.i.':4 7:/9&CANDIDA3SjCgPggfg J l Initial Conditions: 1 The alant is operating at 100% power. Maintenance has just been completed on the No. 1 Core Spray Pump.
Mjf@MtJMM.AA.UATOR@l!EgkYOUREf0Jg_WM6S .n.- :. , l/cmb
c . MONTICELLO NUCLEAR GENERATING PLANT 0255-03-th-1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 1 of 14 0255-03-IA-1 CORE SPRAY SYSTEM VALVE OPERABILITY TEST 0255-03-111 CORE SPRAY SYSTEM PUMP OPERABILIT/ TEST _ . REVIEW AND APPROVALS Prepared By: Ug Sg. Reviewed By:pg g,% OC Review Req'd: YES OC Meeting Number: _7,#7 $ . Date:y-25 a 7 OC Results Review Req'd: NO A, f[/ Date: 03/22/78 Approved By: V((M Date:S 7Jf- V7 O REVIEW AND APPRWAL OF ACTIVITIES DATE
~ Shift SupV Appr6vTio Cb7dmence: Twary TimerTwectny smwy - - -
Operator: Completed By Shift Supervisor: Completion CS System Engineer: Reviewed By PCT System Engineer: Section XI IST Coord: OC Results Reviewed at Meeting Number: Not Required , 03/22/78 COMMENTS Pe h s o , s - /o ,. /2 - /.3 ,_ a e s - o / A r emr l n~ l l I I WO(S) ISSUED YES NO NUMBER (S)
'- FORfADMINISTR'ATIVE!DSE ONLYMWZQWhiFyjMIIST rehtC A%h 3087 (DOCUMENT CHANGE HOLD, AND COMMENT FORM) incorporated:- 9 YY W l Reso Supv: SSSE l Assoc Ref: B.3.1 l '. rlSR: Y 'Freo: a yrs _
ARMS: 0255031A1 l Doc Type: 4030 l Admin Initials: \ LfL DateQElbM loe, SIMULATOR USE ONLT
1 MONTICELLO NUCLEAR GENERATING PLANT - 0255-03-th.1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 2 of 14 PURPOSE The purpose of this test is to demonstrate Core Spray System pump and valve operability. Tech Specs 4.5.A and 4.15.B require ump and valve testing in accordance with Sect on XI of the ASME Boiler and Pressure ssel Code. The A and B RHR Room ECCS Sump Pumps, P-88A, B, C, D, are run each c uarter to verify operpbility. If any aump fails to run, the Shift Supervisor and the Liquid ladwaste System Engineer SHAli be notified. The Loop A and Loop B Core Spray System Leakage Check Procedures 1203-1 and 1203-2 should be completed once each refuel cycle concurrently with this test. -- --Core Spray pump suction pressure is recorde6wherHhe-pumps are idle andwhen the-- aumps are running. Calculating the difference between the two pressures provides an I ndication of the suction line pressure drop and ECCS suction strainer performance. ECCS suction strainer performance is monitored to meet NRC Commitment M95024A. REFERENCES
- 1. Tech Specs 3.5/4.5 and 3.15/4.15
- 2. Ops Man B.3.1 (CORE SPRAY)
- 3. P&lD M-122 (NH-36248)
- 4. Calculation No. CA-90-007
- 5. Procedure 1376 (RHR AND CORE SPRAY PUMP MOTORS OIL SAMPLING)
- 6. 4 awl-09.04.01 (INSERVICE TESTING PROGRAM IMPLEMENTATION)
- 7. EWi-09.04.01 (INSERVICE TESTING PROGRAM)
PERSONNEL Operator (s) Engineer Associate (Vibration Readings) EQUIPMENT Calibrated Stopwatch (XT - ) Radio Handsets as required i I/jao
MONTICELLO NUCLEAR GENERATING PLANT 0255-03-lA-1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 3 of 14 PRECAUTIONS
- 1. Test conditions specified in procedure steps identified with an asterisk (*) must be satisfied to meet Tech Spec. If one of these steps cannot be satisfactorily completed, notify the Shift Supervisor.
- 2. Steps identified with an X contain acceptance criteria that is established to prove the '
operational readiness of pumps and valves in the Inservice Testing Program. If the I step can not be satisfactorily completed or the measured value is outside the acceptable range, the Shift Supervisor must be immediately notified. The Shift Supervisor must complete Form 3107 (INSERVICE TEST DEVIATION FROM ACCEPTANCE CRITERIA SHIFT SUPERVISOR'S IMMEDIATE ACTION) which initiates the corrective action process and documents the operability determination. The stroke timing acceptance criteria for a power operated valve will include a time exceeds a limitin(g stroke time, the valve must be declared inoperableLi! immediately. If the measured value is outside the acceptable band but does not exceed an LST, the valve must be retested and the Shift Supervisor immediately i notified. If the second stroke time is acceptable, the valve is considered operable. If l the second stroke is still outside the acceptance band but does not exceed an LST, l the valve may be considered operable with adequate justification. In either case, a i Form 3108 (PUMPNALVE/ INSTRUMENT RECORD OF CORRECTIVE ACTION) is completed by the System Engineer to document the corrective action. I Values measured for pump testing will fallinto one of three ranges: Acceptable, Alert, or Required Action. When a measured value is in the Alert Range, the pump 1 is considered operab e and the Shift Supervisor is immediately notified. When a measured value is in the Required Action range, the pump must be declared inoperable. In either case, a Form 3108 is completed by the System Engineer to document the corre1ive action.
- 3. Procedure steps identified with an E SHALL be satisfactorily completed to meet equipment qualification requirements. If one of these steps cannot be satisfactorily l completed, notify the System Engineer. I
- 4. CST-103-1 and CST-104-1 are exercise tested for Section XI as a pair. If they fail to meet the acceptance criteria, both valves SHALL be declared ino 3erable and both valves require corrective action. This is a requirement of CS-1, w1ich is a relief request in REFERENCE 7. ;
- 5. Procedure steps identified with a $ SHALL be satisfactorily completed to meet NRC commitments. if one of these steps cannot be satisfactorily completed, contact the l System Engineer. !
^
1/jao
1 MONTICELLO NUCLEAR GENERATING PLANT - - 0255 03.lg.1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 4 of 14
- 6. This procedure is written to satisfy prescriptive Code requirements on how pum a and l valve operating data is obtained. A change should not be rnade to the technica '
content of a step unless it has been verified to have no effect on the plant's compliance with Code requirements or the effects have been addressed. For ; example, a temporary change to take the pump discharge pressure measurement l from a different instrument would not be acceptable without an evaluation. ! REASON FOR PERFORMING PROCEDURE Check One
- 1. Quarterly pump and valve surveillance required by Tech Spec 4.5.A and 4.15.B. Satisfies requirement 0255-03-IA-1 and 0255-03-111.
Complete all steps. Complete in conjunction with: -- - - - - -- --4 0255-03-IIB (CORE SPRAY SYSTEM FUNCTIONAL PRESSURE TEST) YES NO 1203-1 (SYSTEMS LEAKAGE CHECK PROCEDURE "A" LOOP CORE SPRAY SYSTEM) or 1203-2 (SYSTEMS LEAKAGE CHECK PROCEDURE "B" LOOP CORE SPRAY SYSTEM) YES NO Procedure 1376 (RHR AND CORE SPRAY PUMP MOTORS OIL SAMPLING) YES NO
- 2. Verification of 12 Core Spray System Operability in conjunction with Test 0419-2 (ASDS CORE SPRAY AND 14 EMERGENCY SW SYSTEM FUNCTIONAL TEST). Complete STEPS 27 through 35, STEPS 43 through 46, STEPS 48 through 51.
- 3. Other - Specify in COMMENTS section. Note any requirements satisfied. X, PREREQUISITES None PROCEDURE Initial STEP 1 Declare 11 Core Spray inoperable, and enter LCO for j Technical Specification 3.5.A.3.a. g/4 E X STEP 2 CLOSE MO-1751,11 CS INJECTION OUTBOARD ISOL, AND record closing time. (LST 13 Sec) l CLOSE Sec /
(7-11 Sec) p/d I/jao
MONTICELLO NUCLEAR GENERATING PLANT -. - 0255-03-lh-1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 5 of 14 E X STEP 3 Cycle MO-1741,11 CORE SPRAY PUMP TORUS l SUCTION, AND record closing and opening times. (LST 65 Sec in OPEN direction). l CLOSE._"/+ Sec OPEN N4 Sec (42 '57 Sec) (42-57 Sec) Y STEP 4 Verify annunciator 3-A-54 (CORE SPRAY SUCT VLV 1741 CLOSED) resets. #/A STEP 5 Verify that a suction pressure of 23 PSIG and a discharge pressure of 230 PSIG exist. Record the indicated values from-tho4ellowing4astruments-
- a. PI-14-36A,11 CS PUMP SUCTION PRESSURE.
PSIG
- b. PI-14-48A, DIVISION 1 CS PUMP PRESSURE PSIG ,_
- 77l-[.jQ."fi].+;}g :
j'dH[i]h. 4 f f)((;j.}ly.~gl Do not start pump if system is not pressurized, as damage could result from suddenly fil!!ng and pressurizing an unfilled pipe. STEP 6 START P-208A,11 CORE SPRAY PUMP (Breaker 152-505). NOTE: Establishing flow verifies the pump's check valve CS-9-1 has opened. E*X STEP 7 Slowly'OPEN MO-1749,11 CORE SPRAY TEST LINE TO TORUS, until F1-7189, CS LOOP A FLOW, indicates 10.01 - 10.13 mV. Record mV reading and hour and minute. Reference value: 3080 GPM (10.07 mV). mV HR/ MIN
.X STEP 8 Verify the pump has run at least 2 minutes at the required flow before proceeding, record hour and minute.
HR MIN
- STEP 9 Record discharge pressure indicated on PI-14-48A, CS PUMP 11 DISCHARGE PRESSURE. PSIG
>279 PSIG STEP 10 Record pump suction pressure as indicated on local l indicator PI-14-36A, CS PUMP 11 SUCTION PRESSURE.
PSIG 1/jao
F' i . MONTICELLO NUCLEAR GENERATING PLANT 0255-03-fh-1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 6 of 14 _ X STEP 11 Verify proper operation of check valves CST-103-1 and CST-104-1 by observing and recording the pressure as ind ted on PI-7324, COND SERV-CS LOOP A FILL. PSIG
- s 160 PSIG #/A l STEP 12 Calculate differential pressure by subtracting pump suction l pressure from pump discharge pressure.
Discharge Pressure Suction Pressure NOTE: Required Action Range (low) is based on Tech Spec requirements
- - - - - - which are more rostrictive than Section XI requirements..--._ - _ _. ... _ .,
X STEP 13 Initial the appropriate line to indicate the range in which the differential pressure of P-208A,11 CORE SPRAY PUMP, falls. The reference value is 297 PSID. . Acceptable 276 to 327 PSID: Required Action <276 and >327 PSID:
- a. IE the value is in the Required Action range, ItiEN notify the Shift Supervisor. l
$ STEP 14 Calculate suction line pressure drop by subtracting running i pump suction pressure from idle pump suction pressure.
#l& - ^'lk = ^'/A PSiD y/6 idle Pressure Running Pressure STEP 15 Conduct vibration measurements of P-208A. Record data l on Appendix 1. Attach the vibration analysis results to the test.
X STEP 16 initial the appropriate line to indicate the range in which the vibration values for P-208A fall. Acceptable Range: Alert Range: Required Action Range: i
- a. lE any value is in the Alert or Required Action range, THEN notify the Shift Supentisor l 1/jao
p , l ! . j MONTICELLO NUCLEAR GENERATING PLANT - . 0255 03.lA.1 } TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 7 of 14 STEP 17 Perform the following: !
. a. Record 15 bus volta VOLTAGE (V4K104)ge from computer point 15 BUS 1
15 bus voltage Volts
- b. Record P-208A motor Amps fcom breaker 152-505.
(Turbine Bldg., El 911,4 KV Area) Motor Amps: 1 2 3 E STEP 18 Fully OPEN MO-1749. E X STEP 19 CLOSE MO-1749, l j AND record closing time (LST 23 Sec). ] CLOSE Sec (15-20 Sec) STEP 20 STOP P-208A,11 CORE SPRAY PUMP. STEP 21 - Verify annunciator 3-A-41 (AC INTERLOCK) resets. NOTE: This step may be performed concurrently with the remainder of the procedure. NA if a sample is not required. E STEP 22 If required, perform Procedure 1376 for P-208A. #!A E X STEP 23 Cycle MO-1753,11 CS INJECTION INBOAR'D ISOL, l A_NQ record opening and closing times. (LST 10 Sec in OPEN direction, LST 13 Sec in CLOSE direction). OPEN Sec CLOSE Sec j (7-10 Sec) (7-11 Sec) y/A E X STEP 24 OPEN MO-1751, l A_N_Q record opening time. (LST 10 Sec) OPEN Sec (7-10 Sec) y/ 4 j l I/jao - L _
4 MONTICELLO NUCLEAR GENERATING PLANT - - 0 2 5 5 0 3 .l g .9 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 8 of 14 STEP 25 in the A RHR Room, run the following ECCS Sump Pumps without water for about 30 seconds by placing the local handswitch to RUN then return the handswitch to AUTO.
- a. P-88A (Breaker B-3349) 14-
- b. P-888 (Breaker B 3350) o STEP 26 JE all 11 Core Spray components are operable and MO-1741 and MO-1751 are in the OPEN position, TILFJideclare 11 Core Spray perable, A_!iQ exit LCO for Technical S ecification 3.5.A.3.a.
^' -
STEP 27 ' Declare 12 C6fe Spray inoperabte and enter L-CO for --- - Technical Specification 3.5.A.,3.a. E X STEP 28 CLOSE MO-1752,12 CS INJECTION OUTBOARD ISOL, l AND record closing time. (LST 13 Sec).' CLOSE #/4 Sec (7-11 Sec)
. E X STEP 29 Cycle MO-1742,12 CORE SPRAY PUMP TORUS l SUCTION, A_ liq record closing and opening time. (LST 65 Sec in the OPEN direction)
CLOSE d'/A Sec OPEN "S+ Sec (42 57 Sec) (42-57 Sec) STEP 30 Verify annunciator 3-B-46 (CORE SPRAY SUCT VLV 1742 CLOSED) resets. STEP 31 Verify that a suctic: pressure of 23 PSIG and a discharge pressure of130 PSIG exist. Record the indicated values from the following instruments:
- a. PI-14-36B,12 CS PUMP SUCTION PRESSURE.
"/* PSIG v
- b. PI-1 488, DIV St N 2 CS PUMP PRESSURE g 1/jao m
j
MONTICELLO NUCLEAR GENERATING PLANT - - 0255-03-IA-1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 9 of 14
-l ( ; \ @yjfftygg"~ATNG gggR$jgg&
- Do not start pump if system is not pressurized as damage could result from suddenly filling and pressurizing an unfilled pipe.
STEP 32 START P-208B,12 CORE SPRAY PUMP (Breaker A/l# 152-605). NOTE: Establishing flow verifies that the pump's check valve, CS-9-2 has opened. E*X STEP 33 Slowly OPEN MO-1750,12 CORE SPRAY TEST LINE TO l
-~
~ TORUS, until F1-7188, CS LOOP B FLOW, indicates 10.01 - -
and hour and minute. 10.13 mV.value: Reference Record 3080mV GPMreading (10.07 mV),
"/A- mV "/A HR/ MIN X STEP 34 Verify the pump has run at least 2 minutes at the required flow before proceeding, record hour and minute.
N/A HR MIN
^ STEP 35 Record discharge pressure indicated on PI-14-488, CS PUMP 12 DISCHARGE PRESSURE., "/d- PSIG
> 279 PSIG STEP 36 Record pump suction pressure as indicated on local l indicato;A-PI-14-368, CS PUMP 12 SUCTION PRESSURE.
"/ PSIG STEP 37 Calculate the differential pressure by subtracting the pump l suction pressure from pump discharge pressure.
#l+ -
#l+ = "l* PSID Discharge Pressure Suction Pressure NOTE: Required Action range (low)is based on Tech Spec requirements, which are more restrictive than Section XI requirements.
X STEP 38 Initial the appropriate line to indicate the' range in which the differential pressure of P-208B,12 CORE SPRAY PUMP, falls. The reference value is 288 PSID Acceptable 276 to 317 PSID: "/+ l Required Action <276 and >317 PSID: d' / +- s/ !
- a. !
lE THENthe notify valuetheis Shift in the Required Action range, Supervisor. d' /4- v//t/ I 1/jao t i
n MONTICELLO NUCLEAR GENERATING PLANT - - 0255-03.lA.s TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 10 of 14 i
$ STEP 39 Calculate suction line pressure drop by subtracting running pump suction pressure from idle pump suction presure.
N& - "lA- = "lA- PSID p/4
- l' Idle Pressure Running Pressure STEP 40 Conduct vibration nieasurement of P-208B. Record data on l l
, Appendix 2. Attach the vibration analysis results to the test.
X STEP 41 Initial the appropriate line to indicate the range in which the , vibration values for P-208B fall. l _ Acceptable Range:
#/M- _ _ ___ _
Alert Range: "/4-Required Action Range: #/A
- 1
- a. IE any value is in the Alert or Required Action range, i THEN notify the Shift Supervisor. #/+
STEP 42 Perform the following:
- a. Record 16 bus voltage from computer point 16 BUS VOLTAGE (V4K 105).
16 bus voltage #[s4- Volts
- b. Record P-208B motor Amps from breaker 152-605.
(Turbine Bldg, El 931,4KV Area). Mntor Amps: 1 M2 #/t?- 3 #/A E STEP 43 Fully OPEN MO-1750. E X STEP 44 CLOSE MO-1750, l ANR record closing time. (LST 21 Sec). CLOSE #/rf- Sec (14-19 Sec) i STEP 45 STOP P-208B,12 CORE SPRAY PUMP. v_ STEP 46 Verify annunciator 3-A-41 (AC INTERLOCK) resets. #/r4 Ifjao
I
$3NTICELLO NUCLEAR GENERATING PLANT .
0255-03.lA.1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 11 of 14 NOTE: This may be performed concurrently with the remainder of the procedure. NA if a sample is not required. E STEP 47 If required, perform Procedure 1376 for P-208B. #/A
\
E M STEP 48 Cycle MO-1754,12 CS INJECTION INBOARD ISOL, l AND record opening and closing times. (LST 10 Sec in OPEN direction, LST 13 Sec in CLOSE direction). OPEN #/A- Sec CLOSE #/A Sec (7-10 Sec) (7-11 Sec) E X STEP 49- OPEN MO-1752,
---[
M record opening time. (LST 10 Sec) OPEN #/A- Sec (7-10 Sec) STEP 50 In the B RHR Room, run the followi ECCS Sump Pumps without water for about 30 seconds placing the local handswitch to RUN then return the h ndswitch to AUTO:
- a. P-88C (Breaker B-4349)
- b. P-88D (Breaker B-4350)
STEP 51 1E all 12 Core S 3 ray components are operable and MO-1742 and MO-1752 are in the OPEN position, *j THEN declare 12 Core Spray erable, M exit LCO for Technical S cification 3.5.A.3.a. #/A l/jao
e 55NTICELLO NUCLEAR GENERATING Pi ANT - . 0255 03.lg.3 , TITLE: CORE SPRAY SYSTEM TESTS Revision 25 l Page 12 of 14 Appendix 1 Vibration Measurements Pump 11 Core Sorav Pumo P-208A Vibration measurements are to be taken using an IRD Vibrational Analyzer with magnetic pickup at the yellow numbered points on the pump and motor. Record vibration velocity in In/Sec. Motor or Pump Location 1 2 3 ) Pickup Orientation- -- A- H -V- - H- V- H- -V -- - - - - - , Velocity In/Sec Acceptable Range <0.325 <0.325 <0.325 <0.325 <0.325 <0.325 <0.325 Alert Range 0.325 0.325 0.325 0.325 0.325 0.325 0.325 to to to to to to to 0.70 0.70 0.70 0.70 0.70 0.70 0.70 Required Action >0.70 >0.70 >0.70 >0.70 >0.70 >0.70 >0.70 A = Axial H = E/W V = N/S Nomina 1 Vibration Reference Values . I Bearino 1 Bearino 2 Bearino 3
..1 ,
VA= 0.14 Vs = 0.20 Vs = 0.19 Motor Vy = 0.20 ~'2 Vs = 0.28 Vv = 0.21 Vv = 0.28
---3 Pump initial Record Vibration Analyzer Serial No.
Data Taker Data Recorder 1/jao
l l MONTICELLO NUCLEAR GENERATING PLANT - - 0255-03.lA 1 j TITLE: CORE SPRAY SYSTEM TESTS Revision 25 I Page 13 of 14 Appendix 2 Vibration Measurements l l Pump 12 Core Sorav Pumo P-208B Vibration measurements are to be taken using an IRD Vibrational Analyzer with magnetic alckup at the yellow numbered points on the pump and motor. Record vibration velocity n In/Sec. Motor or Pump Location 1 2 3 Pickup ~- Orientation
~~
~=A -- H ---- V- ll - V -- --H - V - --
Velocity ,
/
In/Sec Acceptable Range <0.300 ' <0.325 <0.325 <0.325 <0.325 <0.325 <0.325 j Alert Range .' O.300 0.325 0.325 0.325 0.325 0.325 0.325 to to to to to to to 0.70 0.70 0.70 0.70 0.70 0.70 0.70 Required Action >0.70 >0.70 >0.70 >0.70 >0.70 >0.70 >0.70 A = Axia! H = E/W V = N/S Nominal Vibration Reference Values Bearina 1 Bearina 2 Bearina 3
---1 ;
VA= 0.12 Vs = 0.20 Vs = 0.23 Motor i
..2 Vs = 0.22 Vv = 0.15 Vy = 0.18 Vy = 0.20 ..3 Pump Initial ,
Record Vibration Analyzer Serial No. Data Taker Data Recorder 1/jao
r MONTICELLO NUCLEAR GENERATING PLANT - - 0255 03.lA.1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 Page 14 of 14 l I BASES The GE SAFER /GESTR-LCCA analysis requires that a Core Spray pump be capable of I delivering 2800 GPM against a reactor pressure of 130 PSI greater than containment pressure to be considered operable. This requirement is satisfied by meeting the i enveloping criteria of an indicated pump discharge pressure of 279 PSIG at an indicated l flow of 3064 GPM.' These values include allowance for instrument error (Calculation No. 90-007,) and the tee box Modification (940060). l The 160 PSIG limit for PI-7324 confirms CST-103-1 and CST-104-1 are not stuck wide open. At a pump discharge pressure of about 275 PSIG, pressure in the Core Spray system at the pressurizing station will be greater than 160 PSIG. The pressurizing station pressure is checked immediately after pump start in case the pressurizing station
- pressure control valve leaks.-This would gradually pressurize the CST side of the station - ,
to CST pressure when the check valve closed due to Core Spray system operation. Unless otherwise noted in this procedure, the bases for acceptance criteria in steps identified by an "X" is contained in the System Engineer's Section XI file. The content of these files, including how the acceptance criteria is calculated, is governed by 4 awl-09.04.01 (INSERVICE TESTING PROGRAM IMPLEMENTATION). The aurpose of recording bus voltage and pump motor Amps is for future trending, if neet ed, by the Plant Life Extension group. Quarterly readings are Judged to be an adequate frequency. ' Core Spray is declared inoperable during this test since MO-1751/MO-1752, the outboard injection valves, are susceptible to pressure locking when closed (in the event of a rapid reactor depressurization), see Generic Letter 95-07 assessment. Core Spray is declared inoperable whenever MO-1749 or MO-1750 is open. The existing motor operator logic does not provide for disc closure on torque when given an auto close signal. Since full closure capability is not assumed unless the valve closes on torque, the valves cannot be relied upon to prevent diversion of flow when they auto close. The idle pump suction and discharge pressures of 3 PSIG and 30 PSIG, respectively, are specified as prestart minimum values. These values are based on the approximate normal indicated values. This verification is intended to ensure that damage to the pump and piping does not occur from abnormal conditions. l ifjaa < l
L -- , l Question #: JPM-B.3.1-005-Ql Point Value: 1.0 Time (Minutes): NA l 0 A leak in RHR Room "A" has required the closing of SW-115 and SW-114. What effect does this have on plant operations? - 1
- 1 Answer:
With loss of room cooling, Division I Core Sp y and RHR pumps must be declared inoperable. Reference (s): B.3.1-05, pg 3 of 19, B.3.4-05, pg 4 of 67
)
-K/A
Reference:
K6.05 Task Number: 209001 Rating RO: , 2.8 i t l I r l L-..
Candidate's Response to JPM-B.3.1-005-Q1 l 9 I
F1 pstion #: JPM-B.3.1-005-Q2 Point Value: 1.0 Time (Minutes): NA l Given the following plant conditions: e Reactor S/D in progress. e "A" Loop RHR placed in' Shutdown Cooling Mode. e Reactorlevel 55 inches. The reactor building APEO reports to the Control Room and informs the lead operator that the Core Spray dP readings are out of spec (indicating -30" water column). The lead informs him that this condition is normal for these plant conditions. Do you concur with the lead's assessment and why? Answer: Yes. The increase in water density and changing core flow conditions in the Reactor result in Core Spray nozzle high dP alarms during S/U and S/D. Reference (s): ARP C.6-3-A-13 K/A
Reference:
K4.04 Task Number: 209001 Rating RO: 3.0 l 1 I I l l
I-Candidate's Response to JPM-DJ.1-005-Q2 l o
--m em- e '"" PW W me o, ,
I -
.* MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-07-002 TITLE: RESTORE LC-103 FROM LC-104 Revision 1
, Page 1 of 5
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" % y[g$$fS!$NIdEdITES$)1 R TUSS ##~ 3NdIS@AENSh$ty@s%i EtiME g iD G Bf R E l
@Ei$$idAWS45% @d e s sJMe$SG8Ehid6 MEN E 1 SRO: SRO/RO: X SRO/RO/NLO: NLO:
Plant Referer)ce: E.4-07, Rev 0 I 4 Task Standard: Restore LC-103 from LC-104 l i
.. K/A
Reference:
295003 .__ __ _ Task.No.: AA1.01-_ __ ._. Rating RO/SRO: 3.7/3.8 - - - - - - - - Recent Events: None Probabilistic Risk Assessment liuman Error: "ACB309409Y" Monticello Specific Task List
Reference:
CR262.024 i SS333.038 ! METHOD OF TESTING TIME FOR COMPLETION Simulator: X Normal: Alternate Maximum Time to Complete: 12 Min in-Plant: Path: X Time Critical: Yes X No Prepared By:g [g. Date: Reviewed By: g[MA Date: /i/S0/97 8 shift Supv/ Shift Mgr Review By: g, Date: 7 g._9g Approved By: g7g r (Supt Ops Trng) Date: /__g._ff _ ..~..., _ ... n.... - - - - ~ 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated- l >WA Reso suov- s ops TR l Assoc Ref: MTCP-3.32 ISR Il Frea 0, vrs - ARMS: JPME407002 l Doc Type: 8505 l Admin Initials: /Vv Date: / /'//'/X 1/mif
~~ MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-07-002 TITLE: RESTORE LC-103 FROM LC-104 Revision 1 Page 2 of 5 7t N E 5bYd:N} E FI$$55$ N $.#5h SMh W NMEN E N E $Y M EN $ $d N OIN $f Simulator Setup: Initiate a Station LONOP with a failure of 11 EDG to start. Perform C 4-A, appiicable C.4s and EOPs as necessary. Perform C.4-B.9.02.3 up to Step 12. Recover Reactor water level using RCIC. l LLQ'@: Override Sync Switch for ACB 52-309 to OFF position. initial Conditions: A LONOP occurred about 45 minutes ago. C.4-B.9.02.8 (LOSS OF NORMAL OFF-SITE POWER) had been performed up to Step 2. No.12 EDG is running, supplying 16 Bus and LC-104. No.11 EDG failed to start and 15 Bus is dead. Reactor water levelis being maintained using RCIC. -- -' initiating Cues: The Shift Supervisor directs you to restore LC-103 and LC-104 using procedure E.4-07. Ste as 1 and 2 have been performed. You are to perform Ste as 3 through 9 to energize LC-103, the remaining steps will be performed by an outpl ant operator at a later time. 1/mif
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MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-07-002 l TITLE: RESTORE LC-103 FROM LC-104 Revision 1 l , Page 3 of 5 PERFORMANCE INFORMATION M@!pl@yicpgl{Mj{g[4gffj gygjfjjjy,gg@jg{Qga!)]fjg{gj{gg[yg((g STEP 1 "C" (Procedure STEP 3) Standard: Place 52-305/CS,11 Serv Water Pum a Places CS 52-305, for 11 SW pump in NORMAL P-102A, in the NORMAL AFTER STO R AFTER STOP position AND observes white light position, - is out. l ANQ verify wtste standby light is out. Cue: None l Comments: None STEP 2 "C" (Procedure STEP 4) Standard: ) Place 52-301/CS,103 LOAD CTR SEC Trips 52-301 ACB,103 LC SEC ACB. ACB-52-301, to TRIP. ~ Cue': None-Comments: None STEP 3 "C" (Procedure STEP 5) Standard: , Verify 103/104 LC BUS TIE ACB-52-309 Verifies or opens ACB-52-309,103/104 LC Bus is OPEN. Te. Cue: None Comments: None . STEP 4 "C" (Procedure STEP 6) Standard: Place 52-409/CS,103/104 LC BUS TIE Closes ACB-52-409,103/104 LC Bus Tie. ACB-52-409, to CLOSE. Cue: None Comments: None I/mif
(
.- MONTICELLO NUCLEAR GENERATING PLANT JPM-E 4-07-002 TITLE: RESTORE LC-103 FROM LC-104 Revision 1 Page 4 of 5 l jggggyjMajcypp,jgt[Q2[gj]jg {Jggjgggjl{p{y}jSgnyaf{ggg$gggyg[
STEP 5 "C" (Procedure STEP 7 ) Standard: Place 52-309/SS, SYNC 103/104 LC Places 52-309/SS to ON; sync for 103/104 LC
,7US TIE ACB-52-309, to ON. Bus Tie.
(Non-Critical portion of Standard) Operator may note the sync circuit meters do not respond. Cue: None Comments: 52-309/SS does not work properly and will remain OFF. STEP 6 "C" (Procedure STEP 8) Standard: ROTE: ACB-52-309 will not CLOSE Operator notifies Shift Supervisor'of abnormal re-unless ACB-52-409 is sponse. CLOSED. ' (Non-Critical oortion of Standard) Place 52-309/CS,103/104 LC BUS TIE Operator may attempt to close 52-309 ACB, ACB-52-309, to CLOSE. 103/104 LC Bus Tie. Cue: As Shift Supv state that you will issue a WO and
. notify the appropriate people.
Comments: 52-309 will not close thus 103 LC will not become energized. PRE-APPROVED PROMPT Terminate this JPM after the candidate has notified the Shift Supv of the inability to complete the task. l/mit l
i
. MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-07-002 TITLE: RESTORE LC-103 FROM LC-104 Revision 1 l
. Page 5 of 5 l
i lI o
- Q$$pidQ@,M;if'higggND,lDJTEjSiC,03 S jg'gpfgg{gggggg initial Conditions:
A LONOP occurred about 45 minutes ago. C.4-B.9.02.B (LOSS OF NORMAL OFF-SITE POWER) had been performed up to Step 2. No.12 EDG is running, supplying - 16 Bus and LC-104. No.11 EDG failed to start and 15 Bus is dead. Reactor water levelis being maintained using RCIC. J; f.;di.; 1 N,gO,,g[(NEEy$JL ATPO3_WHE,NJOUjgAJEjCpMPfETEDKH,Jt n4SJgj!1$$$@ l l/mif ]
7... E e i l Question #: JPM-E.4-07-002-Ql Point Value: 1.0 Time (Minutes): NA l 1 i What is the source of power to MCC-133B at the present time? l 1
' Answer: <
Energized from LC-104 through MCC-143B. ! i i l i
' Reference (s): ' B.09.07-02, pg 4 of 8 )
K/A
Reference:
295003 i Task Number: AA1.01 l Rating RO: 3.7 { i i i l l 1
r l Candidate's Response to JPM-E.4-07-002 Q1 o I l I l l J 1 I 1 i
rx 9 1 l fj Question #: JPM-E.4-07-002-Q2 Point Value: 1.0 Time (Minutes): NA l During a plant outage with refueling in progress, the SS directs you to rack out the 480 V breaker for #12 Service Water pump. The isolation directs you to rack the breaker to the DISCONNECT position. What concern is there with this isolation request? i
- Answer:
The breaker must be removed from the room due to seismic concerns if racking it to disconnect or the breaker must be racked to TEST only to maintain its seismic
. qualifications.
Reference (s): B.09.07-05, pg 26 of 69 K/A
Reference:
295003 Task Number: 2.2.13 Rating RO: 3.6 i I 1 l 4 l I I i I
l I Candidate's Response to JPM-E.4-07-002-Q2 I i 1
)
i l 1 l I i
1
' MONTICELLO NUCLEAR GENERATING PLANT JPM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 1 of 8 fw;~m c6
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+ " ' -au.p::::n.; -n .m,enws. %wJerw l u ..Jf\ .; ' W t
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SRO: SRO/RO: X SRO/RO/NLO: NLO: Plant
Reference:
B.7.2.1-05.02, Rev 4 Task Standard: Place "A" Off-Gas Recombiner in OPERATE and "B" Off-Gas Recombiner in FULL STEAM FLOW K/A_
Reference:
. . _ . -271000 Task No.: A4.09 Rating RO/SRO: 3.3/3.2
~
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~~ -~"
~
A1.01 3.371f ~~ Recent Events: None Probabilistic Risk Assessment Human Error: "GRECTRNAY" Monticello Specific Task List
Reference:
CR271.012 METHOD OF TESTING TIME FOR COMPLETION
~
Simulator: X Normal: X Alternate Maximum Time to Complete: 30 Min in-Plant: Path: Time Critical: Yes .X No Prepared By: QQf Date: ;2. ff-99 Reviewed By: g Date: g,fg,99 Shift Supv/ Shift Mgr Review By: g Date: g .f g Approved By:
] (Supf0ps Trng) Date: g_g-pp 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated: //At Reso supv: OTRNG l Assoc Ref MTCP-3.32 ls54; N Frea: 0 yrs ARMS: JPMB721001 l Doc Type: 8505 l Admin Inttials: (";[,./ Date:/MGo7/'/9 1/mif
1
.' MONTICELLO NUCLEAR GENERATING PLANT JPM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5
. Page 2 of 8 PgMjSEgggygggggg Simulator Setup:
Initialize to any at, power IC. Ensure "A" Off-Gas Recombiner is in STANDBY and "B" l Off-Gas Recombiner is in OPERATE. j initial Conditions: The plapt is operating at 100E "B" Off-Gas Recombiner is in OPERATE. "A" Off-Gas Recombiner is in STANDBY. HWC is not in service. Vacuum is slowly decreas-ing (1 in Hg every 30 minutes) and the Shift Supv believes the problem to be the "B" recombiner, initiating Cues: ;
- I Shift Supv directs you to switch recombiner treins by plaom' g "A"-Off-Oss Reeembiner- --
in OPERATE and B" Off-Gas Recombiner in FULL STEAM FLOW. 1/mif
.' MONTICELLO NUCLEAR GENERATING PLANT J PM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5
. Page 3 of 8 PERFORMANCE INFORMATION M@ggppfst@M -
gdf@jgy3g7g{gyg STEP 1 Standard: Locates procedure B7.2.1-05.02.B.2, Locates appropriate procedure. Recombiner Train Switching Cue: None Comments: None i STEP 2 (Procedure STEP 1) Standard: i lE Shift Supervisor rec,uests, None THEN lower HWC hyc rogen injection to 8 CFM, Cue'- OR perform procedure B.2.6-05.F, Hy- HWC has been shutdown IAW B.2.6-05.F. i drogen Water Chemistry Shutdown. Comments: None HWC is not in service as per the Initiating Cues. STEP 3 (Procedure STEP 2) Standard: IE"A" Recombiner Train is in high steam Verifies that "A" Recombiner is in STANDBY. flow THEN advance to Step 4. Cue: None Comments: None STEP 4 "C" (Procedure STEP 3a) Standard: Increase the dilution steam flow to 6700 Places TSS-A in FULL STEAM FLOW. sihr W: (Non-Critical cortion of Standard) Placing TSS-A in FULL STEAM FLOW. Operator should observe steam flow increasing on FR-7508A. Cue: None Comments: None I/mif L
~ MONTICELLO NUCLEAR GENERATING PLANT J PM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 4 of 8 g e g f f p M g c3 M MM5dME3igurM&l%% STEP 5 (Procedure STEP 3b) Standard: Adjust setpoint of PIC-7497A OG TR-A 1. Verifies steam pressure above 260 psig STM PRESS CNTRL at or above 260 AND psig as required to achieve 6700lbs/hr
- 2. Verifies steam flow on FR-7508A about 6700 steam flow as indicated on FR-7508A lb/hr' OGHU TR A ED OUTLT FLOW / PRESS (C-252B).
- 3. If operator adjusts setpoint on PIC-7497A it should be done by the following:
- a. Pushes A/M button to "M" position
- b. Adjusts knob f or desired flow / pressure
- c. Pushes A/M button to "A" position _. _ __ ,;
Cue: None Comments: None STEP 6 "C" (Procedure STEP 4) Standard: ; Place HS-7575A AIR SUPPLEMENT Places HS-7575A to OPERATE /OPEN. SV-7575A to OPERATE /OPEN. Cue: None Comments: None l STEP 7 (Procedure STEP 5) Standard: l Adjust FC-7576A DILUTION AIR CON- Adjusts FC-7576A to approximately 5 scfm. ! TROLLER to approximately 5 scfm. Cue: None Comments: None STEP 8 (Procedure STEP 6) Standard: ! N_OTE: It is important that FY-7491 A 1. Verifies FY-7491 A is in MANUAL and FY7491B are not AND simultaneouslyin AUTO orin 2. MANUAL mode of control for Verifies FY-7491 A has zero output. ; more than a couple of Cue: None minutes or Train Low Inlet Comments: Nona ' pressure may result. Verify FY-7491 A, OGHU TR A OG INLT FLW AUCTIONEER is in MANUAL with ! zero output. l I/mif l l l
MONTICELLO NUCLEAR GENERATING PLANT J PM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 5 of 8 M P, g Q p g e3 G M ;agg ,p{g STEP 9 "C" (Procedure STEP 7) Standard: Place FY-7491B, OGHU TR B INLT FLW Places FY-7491B in MANUAL using the manual / AUCTIONEER in MANUAL. auto selector switch. Cue: None Comments: None STEP 10 "C" (Procedure STEP 8) Standard: NOTE: While performing the Places TSS-A in OPERATE. tollow, ng step, both FCV-7489A and FCV-7489B (Non-Critical cortion of Standard) . . . _ . ._ WlJI be OPEN.- Operator should observe PI-7495 for pressure- - - -4 Place TSS-A, TRAIN SELECTOR SW transients. TRAIN A in the OPERATE aosition. Cue: None 6.N_Q bserve PI-7495, OG iU MN IN-LET LINE PRESSURE Comments: None AND TI-7514A, OGHU TR A PREHEAT-ER OUTLET TEMP. STEP 11 "C" (Procedure STEP 9) Standard: lE PI-7495 pressure changes rapich if PI-7495 changes rapidly OR if TI-7514A de- . QB TI-7514A temperature decreado; creases below 320*F, places TSS-A in FULL STM below 320'F, FLOW. THEN place TSS-A, TRAIN SELECTOR ' SW TRAIN A to the FULL STM FLOW Cue. . None i position. Comments: None STEP 12 "C" (Procedure STEP 10) Standard: l Slowly increase flow of FY-7491 A, 1. Slowly increases Oh-Gas flow using OGHU TR A OG INLT FLW AUC- FY-7491 A open pushbutton, TIONEER. AND lE"A" Train trips while being started, 2. IF "A" Train trips, balances "B" Train inlet THEN balance B Train inlet pressure pressure by adjusting PC-7478B or PC-7479B from PC-74788, OGHU TR B INLET OG ESS C setpoint untillow in t7e green band AND p _y4 "I t Gas Controller, OGHU TR B INLET OG hces"B y491 B' U '
)
PRESS CNTRL by adjusting the setpoint so the needle is k,w in green band, (Non-Critical portion of Standard) l ANQ place the inlet TR BGas INLT Controller'AUC-FY-74918, OGHU FLW Operator should observe Off-Gas flow . increasing l TIONEER in the AUTO position. on FR-7492A. Cue: None l Comments: None I 1/mlf 1
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5
, Page 6 of 8 Md6fillialEiPA_b]iic~tl~y'eM yf.? 7 p .7Stshd {d F - Q g g STEP 13 (Procedure STEP 11) Standard:
Maintain total off- as flow approximately Maintains off-gas flow constant by sl.o,wly decreas-constant by slowl decreasing output of ing the output of FY-7491B to zero using the FY-74918, OGHU TR A OG INLT FLW CLOSE pushbutton. AUCTIONEER, to zero. (Non-Critical nortion of Standard) Operator should observe flow decreasing on FR-74928. Cue: None Comments: None STEP 14 "C" (Procedure STEP 12) Stalidsrd. CAUTION: 1. Balances PC-7478A OR PC-7479A using the OPEN or CLOSE pushbuttons for FY-7479A, Must balance low in the green band until FY-7491 A is low in the green band or controller will respond erratically AND ' upon placing FY-7491 A in AUTO.
- 2. Places FY-7491 A in the AUTO 3osition using NOTE: PC-7479A is the preferred the Manual / Auto Selector switc1.
controller. Cue: None i Balance PC-7478A, OGHU TR A INLET OG PRESS CNTRL, QB PC-7479A, Comments: None . OGHU TR A INLET OG PRESS CNTRL, ANQ alace FY-7491 A, OGHU TR A OG INLT :LW AUCTIONEER in the AUTO position. I STEP 15 (Procedure STEP 13) Standard: Slowly adjust PC-7478A, OGHU TR A Slowly adjusts in service PC-7478A INLET OG PRESS CNTRL QB PC-7479A until setpoint is 11.8 to 12.2 PSIA. QB PC-7479A, OGHU TR A INLET OG PRESS CNTRL setpoi.. , to 12 PSIA. Cue None Comments: None STEP 16 "C" (Procedure STEP 14) Standard: i Place TSS-B, TRAIN SELECTOR SW Places TSS-B in the FULL STM FLOW position. TRAIN B, in the FULL STM FLOW posi-tion. Cue: None Comments: None 1 i I/mif j
, MONTICELLO NUCLEAR GENERATING PLANT J PM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5
. Page 7 of 8 M Q g f e g s 5tiv~e " T i MSgd,a~jdg"ggggyfd STEP 17 "C" (Procedure STEP 15) Standard:
NOTE: Desired dilution air can be Sets FC-7576A to approximately 1.0 scfm. obtained from the System Cue: None Engineer. Comments: Adjust FC-7576A to the desired air injec- Inform operator to set flow rate at 1.0 scfm. tion rate. STEP 18 (Procedure STEP 16) Standard: Locally verify flow indicated by F1-7794A Instructs APEO to verify local flow is the same as OGHU TR A DILUTION AIR FLOW is setpoint at controller FC-7576A. rpproximately the same as setpoint of FC-7576A. Cue. Flow is verified to be the same as setpoint. Comments: None STEP 19 (Procedure STEP 17) Standard: None Return HWC to previous injection rates Cue: 3er O s Man Section B.2.6-05.D, HY-HWC is being placed service IAW Ops. Man.
)RO EN WATER CHEMISTRY - SYS- B.2*6-05*D*
TEM OPERATION. Comments: None ! STEP 20 Standard: INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted. Cue: None Comments: DO NOT PROMPT! l l j l/mlf l l
, MONTICELLO NUCLEAR GENERATING PLANT JPM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 8 of 8 { l l I 1 I _ _ _ _ _ _ . _ _ . _ _ _ _ . . _ _ . ..........._.._...__......_.-___._.-_-m initial Conditions: The plant is operating at 100%. "B" Off-Gas Recombiner is in OPERATE. "A" Off-Gas Recombiner is in STANDBY. HWC is not in service. Vacuum is slowly decreas- . l ing (1 in Hg every 30 minutes) and the Shift Supv believes the problem to be the "B" l recombiner. I MNEQBMKhst:.vasuATOERWHENb0QOlH&VE3QOMPJ:.t:a ~ t?~ ASM l I/mif
1 L h . f , .-l Question #: JPM-B.7.2.1-001-Ql Point Value: 1.0 Time (Minutes): NA. l
- During performance of steps in C.1 (STARTUP) you are directed to place both recombiner trains in service. Currently, the following plant conditions exist:
e 50% power e Off-gas flowis r.ormal i e Reactor went critical on May 19th at 1730 e Generatorload is 310 Mwe e Two recombinersin smice When directed to remove one of the recombiners from service, which of the two should be removed? . 1 i J Answer: '
-"A" recombiner. During the months of May, June, and July, "B" recombiner is preferred to be in " operate".
Reference (s): B.7.2.1-05, pg 6 of 9 K/A
Reference:
2.1.32 Task Number: 271000 l- Rating RO: 3.4 l l 1 l l ! I ! (c
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r
)
1 Candidate's Response to JPM-B.7.2.1-001 QI-i l 1 o , l 1 l I l l I i l l d
4 l Question #:: JPM-B.7.2.1-001-Q2 Point Value: 1.0 Time (Minutes): NA l With "B" recombiner in " operate", what efrect would there be on the oft-gas compressor if a 4% hydrogen trip occurred on the "A" recombiner outlet analyzers? ' Answer: No effect. 4% trips are bypassed if the associated train is not in " operate". Reference (s): B.7.2.1-02, pg 21 of 23 K/A
Reference:
- , A3a1 - ----- - - - - - - - Task Number: 271000 Rating RO: 3.3
I Candidate's Response to JPM-B.7.2.1-001-Q2 l 9 I 1 l e 4 L.._
MONTICELLO NUCLEAR GENERATING PLANT JPM-O,1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 1 of 10
?
SRO: SRO/RO: X SRO/RO/NLO: NLO: Plant
Reference:
C.1, Rev 23 Task Standard: Synchronize Main Generator to the Grid and pick up minimum initial load. K/A
Reference:
- 245000 -
--Task-No.:- A4.02 -- - Rating-RO/SRO:4.1/2.9 -
Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
CR245.005 I METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 15 Min Simulator: X Normal: X Alternate Maximum Time to Complete: 30 Min in-Plant: Path: Time Critical: Yes X No 1 Prepared By: M M VVL Date: 7-o/ - 9) l
\
Reviewed By: j Date: 7_fy pp ; Shift SupV/ Shift Mgr Review By: M Date: 7_ g_9p Approved By: gg - (Supt Ops Trng) Date: 7_j y gp l l l l 1 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated-R_ esp Supv: OTRNG l Assoc Ret MTCP-3.32 lSR: N Frea: 0 yrs ARMS: JPMC1002 l Doc Type: 8505 l Admin initials: Date: I 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 2 of 10 l SyyygiMXjQ EQ$3pf@ks?TfJPM yETrUipglf@@ W@Qq4ggggggy Simulator Setup: Initialize to any IC with the Turbine speed at 1800 rpm and ready for loading. Load limit at 90%, speed / load changer adjusted for about 1800 rpm, Voltage Regulator at i minimum. Initial Conditio,ns: Reactor is in RUN at about 15% power with one and one-half bypass valves open. The Main Generator is rolling at approximately 1800 rpm ready for synchronization. , No abnormal conditions exist. The startup checklist is complete through G-19. I initialing Cues: The Shift Supv-directsyou to synchronize Main Generator to the grid and pickup mini- - mum load in accordance with the Startup Procedure C.1, Section VI.C. 1 l/cmb
l MONTICELLO NUCLEAR GENERATING PLANT JPM-C.1-002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 3 of 10 PERFORMANCE INFORMATION
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STEP 1 Standard: Locate Section VI.C in the C.1 Startup Locates appropriate section of procedure. Procedure (Turbine-Generator Synchro-nization and Loading). Cue.. None Comments: None STEP 2 "C" (Procedure STEP C.1) Standard: NOTE: The Main Generator Field 1. Closes the main generator field breaker by ACB (field breaker) will placing the MAIN GENERATOR FIELD ACB trip if No.1 Main switch (241/CS) to close _ __. Generator Kilovolts AtLD (generator voltage) is not
>5KV within 30 seconds of 2. If necessary, uses MANUAL VOLTAGE closing the field beaker.
ADJUST to raise generator voltage above With the Turbine at approximately 1800 SKV. rpm CLOSE the MAIN GENERATOR (Non-Critical portion of Standard) FIELD ACB AND verify the breaker indicates Operator should verify the field breaker indicates CLOSED closed by observing MAIN GENERATOR FIELD THEN use the MANUAL VOLTAGE AD- ACB red light is on. 1 JUST to increase No.1 MAIN GENERA-TOR KILOVOLTS to slightly greater than Cue: None 5 KV. Comments: None l/cmb
f ' l l~ MONTICELLO NUCLEAR GENERATING PLANT JPM-C.1 -002 l ! TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 l WITH OUTPUT GRD Page 4 of 10 l
$5I61NIIOS'10E5"$595}?.cypeyggf gggg/$iggj$Stangardf,3}gfgggg STEP 3 "C" (Procedure STEP C.2) Standard:
CAUTION: 1. Uses MANUAL VOLTAGE ADJUST to raise Generator voltage to 22 as KV (CS-70) l Never exceed 23.1 KV when increas-ing voltage as indicated on No.1 indicated on NO.1 MAIN GENERATOR KILOVOLTS meter. Main Generator* Kilovolts meter (C-08). (Non-Critical portion of Standard) CAUTION: 2. Verifies all three phases are at 22 KV by selecting A-B, B-C, and C-A positions on the
>1000 Field Amps to obtain 20 KV as Indicated on No.1 Main Generator PHASE VOLTAGE SELECT SWITCH (VS1).
. _. Field Amps and No.1 Main Generator Cue: None Kilovolts meters on C-08 may cause Comments: generator damage.
- 1. Voltage adjusts to 20 KV with less than 1000 NOTE: The voltage Regulator field current amps so there is no need to take should be adjusted slowly alternate actions a.1)-4),
due to rheostat overtravel. Use the MANUAL VOLTAGE ADJUST to raise No.1 Main Generator Kilovolts to ap 3roximately 22 KV. l 6.b2 monitor on all three phases for the following condition:
- a. JE more than 1000 Field Amperes is necessary to obtain 20 KV, THEN perform the following:
- 1) Reduce Generator Voltage to about 10 KV using the MANUAL VOLTAGE l ADJUST
- 2) OPEN the Generator Field l breaker 1
- 3) Notify Plant Technical staff
- 4) Notify System Dis 3atch of the delay to load t1e Generator I
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MONTICELLO NUCLEAR GENERATING PLANT JPM-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 5 of 10 iMEBe!!olm8nc69bipctivgspjg gjggggggsanprdgggggggg STEP 4 "C" (Procedure STEP C.3) Standard: Start the amplidyne by placing the REG. 1. Places REGULATOR TRANSFER switch ULATOR TRANSFER switch (C-08) to (243/CS) to TEST position. the TEST position, AND perform the fol- 2. lowing: Uses the REGULATOR VOLTAGE ADJUST switch (CS 90) adjust the NO.1 MAIN
- a. Verify red light ON. GENERATOR AMPLIDYNE VOLTAGE meter to zero 20 volts.
NOTE: If breaker 2123 is not racked (Non-Critical portion of Standard) in or its disconnect switch is not closed, the amplidyne 1. Operator should request local inspection of motor will not start; however, the amplidyne. the red lightwittte'ON.
- 2. Operator should verify red light is on.
- b. Perform a localinspection of the Cue:
Amplidyne. APEO reports that local inspection of the ampli-c.
- g. e REG E D e dyne reveals no abnormal conc'itions.
No.1 MAIN GENERATOR Comments: AMPLIDYNE VOLTAGE meter The adjusting of the amplidyne in this ste 3 is to (C-08). verify it operates properly. It will need to de read-justed at a later step. STEP 5 (Procedure STEP C.4) Standard: NOTE: Placing the LC-107/LC-108 Verifies switching on LC-107/LC-108 is not taking synch select switch in ON place. will affect C-08 synchroscope. Cue: Verify the LC-107/LC-108 synch select Synch switch is not being used. switch is in OFF. Comments: Operator may call APEO to verify. STEP 6 "C" (Procedure. STEP C.5) Standard: Inserts SYNC SWITCH handle and turns on syn-Turn (8N4SS ON or the 8N5SS synchronizing) on C-08 for oneswitch of chronizing switch (8N4/SS or 8N5/SS) for either the Generator Output Breakers, MAIN GENERATOR BREAKER No.1 GCB 8N4 AND observe the following: gr MAIN GENERATOR BREAKER No. 2 GCB 8NS.
- a. Synchronizing pointer is moving.
(Non-Critical portion of Standard)
- b. Synchronizing Voltmeters and sensing lights are activated. Operator should verify synchronizing pointer is moving and synchronizing voltmeters and sensing lights are activated.
Cue: None Comments: None I/cmb
M5NTICELLO NUCLEAR GENERATING PLANT JPM-C.1 -002 TITLE: SYNCHRONIZE TURBlNE GENERATOR Revision 5 l WITH OUTPUT GRID Page 6 of 10
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STEP 7 "C" (Procedure STEP C.6) Standard: l' i Use SPEED LOAD CHANGER to adjust Uses SPEED LOAD CHANGER handswitch on l the Generator speed until clockwise syn- C-07 to adjust Generator speed so that clockwise i chronous pointer rotation of one revolu- rotation is established on the synchroscope. tion 'n 30 to 120 seconds is established. Cue: None Comments: None I STEP 8 "C" (Procedure STEP C.7) Standard: CAUTION Uses MANUAL VOLTAGE ADJUST (CS-70 to match INCOMING VOLTAGE to RUNNING) V Generator voltage is_ limited to a. max- A6"' imum of 23.1 KV and a minimum of 20.9 KV as indicated on No.1 Main Cue: None Generator Kilovolt meter (C-08). Comments: None l NOTE: Incoming voltage . Indicates generator voltage. Use MANUAL VOLTAGE ADJUST con-trol switch to adjust incoming Voltage to match Running Voltage. STEP 9 "C" (Procedure STEP C.8) Standard: l Repeat STEPS C.6 and C.7, until both if necessary, continue to adjust voltage and speed conditions are met, until voltages are approximately the same and synchroscope is rotating once every 30 to 120 seconds. Cue: None Comments: None STEP 10 (Procedure STEP C.9) Standard: Allow the synchroscope to make at least Allows synchroscope to complete a minimum of twn com 3lete revolutions to verify that two revolutions. the sync 1roscope is operating properly. Cue: None Comments: None l . I 1/cmb l L
f . MONTICELLO NUCLEAR GENERATING TS LANT JPM-C.1-002 l TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 ! WITH OUTPUT GRID Page 7 of 10 l ((f@g@pgmanc3ppecygegggg gg@$fijg74St,apday,dyglggggl,jg STEP 11 "C" (Procedure STEP C.10) Standard: I WHEN the synchroscope pointer is in 1. Closes selected Main Generator output I the Green Band, breaker by placing its control switch THEN perform the following to load the (G8N4/CS or G8N5/CS) to CLOSE for about 1 generator: second while the synchroscope pointer is in
- a. CLOSE the selected Main grgn band, Generator Output Breaker (8N4 j or 8N5) by firmly placing its 2. Uses SPEED LOAD CHANGER handswitch 4 control switch to CLOSE, for on CO7 to increase Generator load to about approximately 1 second. 20-40 MWE. f
- 1) 1Ethe breaker does not (Non-Critical cortion of StandardL._ - _. . -
close on the first attempt, THEN reset the breaker Operator should: control switch and the alarm 1. Verify phase to phase voltages and phase to by placing the selected phase currents are approximately equal. I h h in the N;aker p ost io 2. Turn off synchroscope by placing 8N4/SS or i AND return to STEP 5 8N5/SS to OFF and remove handle from ) above, switch, AND
- 2) th r does not 5e o t be 3. ct p ropriate entries be made in Control attem at, THEN DO NOT reset the 4. Directs NAPEO to inspect No.1 Gen breaker and the alarm, Transformer and 345 KV disconnects for AND notify System abnormal conditions.
Engineer. Cue:
- b. Use SPEED LOAD CHANGER
- 1. Appropriate log entries have been made.
to immediately pick up 5% load (about 30 MWE). 2. If the breaker @es not close on the second
- c. Verify phase to phase voltages' attempt, when t,he system engineer is notified, l AND phase to phase currents jtksuY essfntinue to attempt closing breaker are approximately equal.
- d. Turn OFF the synchroscope and 3. The No.1 Gen Transformer and '345 KV remove handle from switch, disconnects appear normal.
- e. Log in the Control Room Log. Comments:
- f. Locally inspect the No.1 If the breaker does not close, the operator should Generator Transformer area and follow through with the procedure guidance.
345 KV disconnects to verify no i abnormal conditions such as arcing, smoke, etc. I 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 8 of 10 IEESU@'!!prrnancgppjpgti?e{fgd3 gqggjgggSganda,rdygggggll;74g STEP 12 "C" (Procedure STEP C.11) Standard: Turn ON the synchronizing switch for the Inserts SYNC SWITCH handle and turns on syn-open Main Generator Output Breaker, chronizing switch (8N4/SS or SN5/SS) for remain-and observe the following: ing Generator output breaker,
- a. Incoming and Running (Non-Critical nortion of Standard) voltmbters are matched Operator should verify the following:
- b. Synchroscope indicated frequency is matched 1. SYNCHRONIZING INCOMING VOLTAG~.
and SYNCHRONIZING RUNNING VOLTAGE meters are matched. 2c SYNCHRONIZING meter is pointed straight-up and is not rotating. Cue: None Comments: None 1 1/cmb L_.
j- MONTICELLO NUCLEAR GENERATING PLANT JPM-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 l WITH OUTPUT GRID Page 9 of 10 l l (( gig gggggnpgnyejp p y ie M M [ M g gj g gSja @ yrd @ g g gj g gfg g STEP 13 "C" (Procedure STEP C.12) Standard: CLOSE the selected Main Generator Closes selected Main Generator output breaker Output Breaker, by firmly placing its con- by placing its control switch (G8N4/CS or trol switch to CLOSE. G8N5/CS) to CLOSE.
- a. Ethe breaker does not close on (Non-Critical oortion of Standard)
I reset he breaker control 1. Verifies phase to phase voltages and phase I switch and the alarm by placing currents are approximately equal. the selected breaker control to 2. Turns off synchroscope by placing 8N4/SS or the TRIP position, 8N5/SS to OFF and removes handle from AND attempt to close the switch, breaker again.
- 3. Directs appropriate entries be made on
- b. E the breaker does not close on control room log.
E do re et the breaker 4. Notifies System Dispatch and the alarm, Cue: AND notify system engineer.
- 1. Appropriate log entries have been made.
- c. Verify phase to phase voltages AND phase carrents are 2. System Dispatch has been notified.
approximately equal. Comments: None
- d. Turn OFF the synchroscope and remove handle from switch,
- e. Log in the Control Room Log.
- f. Notify System Dispatch.
STEP 14 Standard: INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted. Cue: None Comments: DO NOT PROMPT! l l l
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MONTICELLO NUCLEAR GENERATING PLANT JPM-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 10 of 10 i
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i M i$ SELDO?$$0k M Initial Conditions: Reactor is in RUN at about 15% power with one and one-half bypass valves open. The Main Generator is rolling at approximately 1800 rpm ready for synchronization. No abnormal conditions exist. The startup checklist is complete through G-19. 5isi.iyWJNiiiDSMNHliSEygpA10,RjyH,jENgpy]j8XliSCpyg@&DJHiialTASKllM; l I/cmb L
l Question #: JPM-C.1-002-Ql Point Value:1.0 Time (Minutes): NA l If Reactor pressure is increased from 1000 to 1010 psig with the pressure regulator, what effect will this have on Reactor power?
- Answer:
. A power increase of approximately 3 Mwt.
Reference (s): B.S.9-05, pg 3 of 10 -~~ K/A
Reference:
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Task Number: 241000 Rating RO: 3.8 s I t l l
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g i. Candidate's Response to JPM-C.1-002-Q1 o h ,g 0 1 I i i
4 MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-003 TITLE: ISOLATE A HCU Revision 4 Page 1 of 7
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3 ;;_rgo3g - y y e y A s g {;s{ g ga g lf g ~ - SRO: SRO/RO:. SRO/RO/NLO: X NLO: Plant Refererx:e: B.1.3-05, Rev 7 Task Standard: Isolate CRD 22-51 for HCU accumulator removal. K/A
Reference:
- Generic -
-Task-Ne+-2d.30- Rating RO/SRO: 3.9/3.4- - -- -
Recent Events: None Probabilistic Risk Assessment Human Error: None , Monticello Specific Task List
Reference:
CR201.036 NL201.010 METHOD OF TESTING TIME FOR COMPLETION Estimated Eme to Complete: 15 Min Simulator: Normal: X Alternate Maximum Eme to Complete: 30 Min in-Plant: X Path: Time Critical: Yes X No Prepared By: W%{ Date: 2-Y-77 Reviewed By: Mg_ _ Date: gr[91 Shift Supv/ Shift Mgr Review By: [gj7g Date: 37,7 9 Approved By: _jg (Supt Ops Trng) Date: y g g ll3087 (DOCUMENT CHANGE. HOLD. AND COMMENT FORM) incorporated: h l Resp Supv: OTRNG l Assoc Ref MTCP-3.32 lSR: N Frea: 0 yrs l ARMS: JPMB13003 l Doc Type: 8505 l Admin Initials: (p) Date: rQi9s:L/tf 1/mif
I
'. MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-003 TITLE: ISOLATE A HCU Revision 4 )
Page 2 of 7 l N EItSgggggAyggggfgj Plant Setup: None Initial Conditions: CRD 22-51 is currently at position 48 and requires replacement of the accumulator. The CRD will remain at position 48 during performance of this maintenance. The 1 Nuclear Engineer has verified that the SDM is in conformance with Tech Specs. The l requirements of Tech Spec 3.3.D.1 will not be violated if this action is taken. No.11 CRD pump is in service. Initiating Cues:
----- Shift Supv directs you to perform " Hydraulic Control Unit-Isolation" per B.1.3-05 for - - - -
I HCU 22-51. All necessary tools will be provided to the operator. l The isolation cards will be hung by other operators. Venting of N2 will be performed by other operators per B.1.3-05. ALL OPERATOR ACTIONS ARE TO BE SIMULATEDI SIMULATE ALL STEPS EXCEPT STEP 14. j 1 l 1 i 1/mlf
4 MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-003 TITLE: ISOLATE A HCU Revision 4
. Page 3 of 7 PERFORMANCE INFORMATION QPjpo}m]h}cgje~cg y { - t Q S_t,ssdW(d s y _ j g STEP 1 Standard:
l Locates 3rocedure B.1.3-05 Locates correct procedure. (HYDRAJLIC CONTROL UNIT ISOLA-Cue. TION).
# Provide operator with a copy of procedure. If re-guested, RWP is as locally posted. Manipula-tions are to be SIMULATED, therefor (e, specific RWP requirements should not be needed.
Comments: None STEP 2 "C" (Procedure STEP 1) Standard: - CAUTION Operator verifies that cooling water pressure has I een a sd accodngly, You must first close CRD-101 before closing CRD-102 or CRD-112. Simi- Cue: . larly, when opening these valves valves CRD-102 and CRD-112 mu'st be No HCUs are currently isolated. open prior to opening valve CRD-101. Comments: None A reactor scram will result in damage to the CRD If it should occur with valve CRD-101 open and valve ~ CRD-102 or CRD-112 closed. If two (2) or more HCUs are currently isolated, THEN adjust cooling water flow down-ward from its nominal value of 48-50 m by 0.40 gpm for each HCU current-isolated or being isolated. STEP 3 "C" (Procedure STEP 2) Standard: Close CRD-101, HCU Drive-insert Riser Closes CRD-101 by turning valve handwheel CW. Isol. Cue: CRD-101 valve stem moves IN; valve meets resistance and is tight. Comments: None STEP 4 "C" (Procedure STEP 3) Standard: Close CRD-102, HCU Drive-Withdraw Closes CRD-102 by turning valve handwheel CW. Riser Isol. Cue: CRD-102 valve stem moves IN; valve meets resistance and is tight. Comments: None 1/mif
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-003 TITLE: ISOLATE A HCU Revision 4 Page 4 of 7 i MPEr(olnlancKQ$isitM. M St Ed.aT STEP 5 "C" (Procedure GTEP 4) Standard: ! Close CRD-113, HCU Accumulator Closes CRD-113 by turning valve handwheel CW. Charging Water Riser Isol. Cue: CRD-113 valve stem moves IN; valve meets resis-tance and is tight. Comments: None STEP 6 "C" (Procedure STEP 5) Standard: With a hose connected from CRD-107 to Removes plug at CRD-107. Connects drain a bucket or drain, slowly open CRD-107, header hose to C.RD-107. Slowly opens CRD-107 < HCU Accumulator Water Drain, to dis- using CCW motion. charge the water accumulator pressure. Cue:
- 1. CRD-107 valve stem moves OUT.
- 2. Flow can be seen and heard through tubing for a few minutes.
Comments: None STEP 7 "C" (Procedure STEP 6) Standard: . Close CRD-112, HCU Scram Discharge Closes CRD-112 by turning valve handwheel CW. Riser Isol. Cue: CRD-112 stem moves IN; valve meets resistance and is tight. Comments: None STEP 8 "C" (Procedure STEP 7) Standard: Close CRD-104, HCU Cooling Water Closes CRD-104 by turning valve handwheel CW. Riser Isol. Cue: CRD-104 stem rnoves IN; valve meets resistance and is tight. Comments: None STEP 9 "C" (Procedure STEP 8) Standard: Close CRD-103, HCU Drive Water Riser Closes CRD-103 by turning valve handwheel CW. Isol. Cue: CRD-103 stem moves IN; valve meets resistance and is tight. Comments: None I/mif
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-003 TITLE: ISOLATE A HCU Revision 4 Page 5 of 7 MPJticitrnancWQtilectM M S Ld I I STEP 10 "C" -(Procedure STEP 9) Standard: Close CRD-105, HCU Exhaust Water Closes CRD-105 by turning valve handwheel CW Riser isol. Cue: CRD-105 stem moves IN; valve meets resistance
, and is tight.
Comments: None STEP 11 "C" (Procedure STEP 10) Standard: Close CRD-116, HCU Scram Pilot Air Closes CRD-116 by rotating handle 90'. Isol. . Cue: ~~ CRD-116 handle turns CW and is 90* from its original position. Comments: None STEP 12 "C" (Procedure STEP 11) Standard: De-energize the two scram pilot air Locates appropriate SCRAM SOLENOID FUSE valves, SV-117 and SV-118, by pulling PANEL at north end of CRD Bank 2. Simulates the two appro ariate fuses at the SCRAM removing fuses 117 and 118 for CRD 22-51. - SOLENOID PJSE PANEL. Cue: The fuses for CRD 22-51 are removed. Comments: Do not allow the operator to open fuse panels. STEP 13 "C" (Procedure STEP 12) Standard: Electrically disarm the directional control Disconnects Amphenol plugs for solenoid valves valves by removing the Amphenol plugs SV-120 through SV-123 by turning connector connected to the following solenoic. CCW. valves: Cue:
- a. SV-120 Amphenol plugs for solenoid valves SV-120
- b. SV-121 through SV-123 rotate CCW and are removed.
l c SV-122 Comments: None
- d. SV-123 l
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-003 TITLE: ISOLATE A HCU Revision 4 Page 6 of 7 MiddpianMO61e6flyM S'falidaTM STEP 14 (Procedure STEP 13) Standard: Tape t'oth ends of the connections to Tapes the exposed surfaces of all four Amphenol keep contact surfaces clean. plugs and the solenoids. Cue: Exposed surfaces are covered. Comments: None STEP 15 (Procedure STEP 14) Standard: Monitor CRD system flow and raise by- Monitors system flow and adjusts CRD-169 if pass flow using CRD 169, CRD Pump ricoded. Byaass Pressure Reducing / Flow Control Va ve to maintain total pump flow. cue- . CRD system flow is normal. Comments: None STEP 16 Standard: INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted. Cue: None - Comments: DO NOT PROMPT! l/mif
'. MONTICELLO NUCLEAR GENERATING DLANT JPM-B.1.3-003 TITLE: ISOLATE A riCU Revision 4
. Page 7 of 7 o
.: ' D Di e s; - /
Initial Conditions: CRD 22-51 is currently at position 48 and requires replacement of the accumulator. The CRD will remain at position 48 during performance of this maintenance. The - Nuclear Engineer has verified that the SDM is in conformance with Tech Specs. The requirements of Tech Spec 3.3.D.1 will not be violated if this action is taken. No.11 CRD pump is in service. MEnBuinimirisdualEfidWSEllbCDDBAVJEC%$iiimi e.gserrgg l ( I I/mif
i l , I l l ) [ ' l Question #: JPM-B.I.3-003-Q1 Point Value:1.0 Time (Minutes): NA l If alarm 5-A-27 activates and a control rod is slowly inserting from position 48 to 00,
._ what would be the most likely cause of failure?
Answer: Scram valve 126 or 127 leaking. Reference (s): B.I.3-05, pg 61 of 69
' K/A
Reference:
201003 Task Number: A2.03 Rating RO: 3.4 i I l l l i l l.
Candidate's Response to JPM-B.I.3-003-Q1 1 l i e f l
l Question #: JPM-B.I.3-003-Q2 Point Value: 1.0 Time { Minutes): NA l While operating at 90% power, a rod group at position 32 is withdrawn to position 48. Following the control rod withdrawals, Reactor power is indicating 89%. Why? -
. Answer:
A small decrease in power due to an inverse power response from the rod movement can
; be observed between 88% and 100% power for control rods withdrawn below the core midplane.
Reference (s): C.2-01, pg 9 of 15 K/A
Reference:
K5.05 Task Number: 201003' Rating RO: 3.0 r N .. . . ..
. i Candidate's Response to JPM-B.I.3-003-Q2 '
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MONTICELLO NUCLEAR GENERATING PLANT JPM-C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 FOR RPV MAKEUP Page 1 of 5
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Plant
Reference:
C.5-3203, Part D, Rev 1 Task Standard: Simulate Using Fire Water Cross-tie to LPCI K/A
Reference:
Generic _ _ Task No.: 9 1.23 _ _ Rating RO/SRO: 3.9/4.0 - Recent Events: None Probabilistic Risk Assessment Human Error: "WVHINXTIEY" Monticello Specific Task List
Reference:
CR314.016 NL314.004 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 10 Min Simulator: Normal: X Alternate Maximum Ime to Complete: 20 Min , in-Plant: X Path: Time Critical: Yes X No Prepared By: // d /Fl Date: 7-/y-9f Reviewed By: sg Date: 7-y_. p 7 Shift Supv/ Shift Mgr Review By: //M rVI Date: 7-/ y- 7) Approved By: Q (Supt Ops Trng) Date: 7_/y. p p 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated: Resp supv- OTRNG l Assoc Ref: MTCP-3.32 lsR: N Freq: 0 yrs ARMS: JPMC53203001 l Doc Type: 8505 l Admin Intbals: Date: 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 l FOR RPV MAKEUP Page 2 of 5 R$f2Eh%5Effgggygggggggggy;S,MPfggggQg[ggjggg'fpgjgyyy[ggy Plant Setup: None-Initial Conditions: I The plant is in an emergency condition requiring the use of Alternate injection Sys- l tems for RPV Makeup. The Diesel Fire Pump is operating, RHRSW is not supplying RHR, and plans are to inject through the Fire Water cross-tie to LPCI using the A loop of RHR. Initiating Cues: The Shift Supv orders you to lineup the fire water system for LPCI Injection per , C.5-3203. Complete in plant stepa-only.- ----- -
-H ALL OPERATOR ACTIONS ARE TO BE SIMULATED!
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I MONTICELLO NUCLEAR GENERATING PLANT JPM-C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 l FOR RPV MAKEUP Page 3 of 5 1 PERFORMANCE INFORMATION NIdjPepfgynyp@ppyejp3l2jfy g jg g gg g g g g Slaj ga(dgy g ggg g gg g g STEP 1 Standard: Locate procedure C.5-3203 (USE OF Locates appropriate procedure. ALTERNATE SYSTEMS FOR RPV Cue. . j MAKEUP) PART D.
, Provide operator with a copy of procedure.
Comments: Inform operator not to open EOP file drawer. STEP 2 "C" (Procedure STEP 1) Standard:
. .- CLOSE RHRSW-13, EMER INJECTION Closes RHRSW-13. ,
LEAKAGE TEST. I Cue: RHRSW-13 moves in clockwise direction, stem lowers, meeta resistance and is tight. Comments: None STEP 3 (Procedure STEP 2) Standard: ! Verify CLOSED RHRSW-12, EMER Verifies RHRSW-12 closed. l lNJECTION VIA 11 LOOP. Cue: I
- 1. RHRSW-12 when attempt to move clockwise, l meets resistance and is tight.
- 2. Report from the Control Room that Procedure STEP 3 is completed: MO-2020, MO-2006, MO-2021, and MO-2007 are verified closed.
Comments: None STEP 4 "C" (Procedure STEP 3) Standard: Verify Closed the following valves: Cal!c Control Room to verify valves are closed.
- 1. MO-2020 (RHR "A" DW SPRAY Cue:
OUTBOARD) The following valves have been verified closed:
- 2. MO-2006 RHR "A" DISCHARGE
- 1. MO-2020 TO TORUS (-OUTBOARD)
- 3. 2. MO-2006 MO-2021 (RHR "B" DW SPRAY OUTBOARD) 3. MO-2021
- 4. MO-2007 4. MO-2007 TO TORUS (RHR "B" DISCHARGE
-OUTBOARD) 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 FOR RPV MAKEUP Page 4 of 5 Eiggleggrgancgpggtgy;gg gtjfggiiggjiglfryppyidaidgggggggggy STEP 5 "C" (Procedure STEP 4) Standard: OPEN the following valves: 1. Opens RHRSW-46, AND
- a. RHRSW-46 (EMERG INJECT 2. Opens RHRSW-14.
VIA DIESEL FIRE PUMP) (Non-Critical portion of Standard) i
- b. R EMER INJECTION Informs Control Room STEP 4 is complete.
Cue: RHRS\N-46 and RHRSW-14 handwheels move in i the counterclockwise direction, stem rises, meets ' resistance and are tight. Comments: None STEP 6 Standard: INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted. Cue: None Comments: DO NOT PROMPT! l I l/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 FOR RPV MAKEUP Page 5 of 5 o I g g ggpfgjC g gig g ESyJ Kg(({j $ $i@$$fl[g}d}l$l$3%j M D Initial Conditions: The plant is in an emer tems for RPV Makeup.gency condition requiring the use of Alternate inject RHR, and plans are to inject through the Fire Water cross-tie to LPCI using the loop of RHR. 55YbW.A.JQ3MMggyOQggggp9,@,f[E.,ggggEJbAS,$! M l l l/cmb
1 l Question #: JPM-C.5-3203-001-Q1 Point Value: 1.0 Time (Minutes): NA Besides Diesel fire pump injection, what other systems can be used to inject through MO-2012 and MO-20147 Answer:
- 1. - RHRSW
- 2. Condensate service through the pressurizing station.
Reference (s): C.5-3203, pg 2 K/A
Reference:
A1.05 Task Number: 286000 Rating RO: 3.2
f , l l Candidate's Response to JPM-C.5-3203-001-Q1 f l 1 l 1 I j l ( 9 I 1 l
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l Question #: JPM-C.5-3203-002-Q2 Point Value: 1.0 Time (Minutes): NA l During an emergency, the SS directs you to line-up and inject with RHRSW pump No. L 11, the only available pump. When opening the LPCI injection valves, wlmt is the maximum flow that can be placed on the pump without causing damage? l Answer: 6000 gpm. tW + ' y se * % + s* he, Reference (s): B.08.01.03-05, pg 4 of 27 K/A
Reference:
EA1.08
- Task Number: 295031 Rating RO: 3.8 1
)
1 Candidate's Response to JPM-C.5-3203-002-Q2 1 i l l l 8 l l
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5 l l l 1 I l I 1 1 I i r
I AfCNTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 I TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS - Page 1 of 6 th " = . 2: Y y- " .~ .
- m=-
17 ; -= = u % %
?;_.y: n . n g y @ BEIE A U RC7T@.
{y ~ ' ;' r J:; - -@B 9 [ L:T ;- ; ; .9 , SRO: SRO/RO: SRO/RO/NLO: X NLO: Plant
Reference:
B.9.12-05.D.1, Rev 4 1 Task Standard: Startup the No.11 RPS MG Set l 1 K/A
Reference:
2.1 - Task No.: 2.1.30 Rating RO/SRO: 3.9/3.4 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
NL212.003 , METHOD OF TESTING TIME FOR COMPLETION Estimated Eme to Complete: 10 Min - Simulator: Normal: X ! Alternate Maximum Eme to Complete: 20 Min in-Plant: X Path: Time Critical: Yes X No Prepared By: g g Date: pg Reviewed By: g Date: f/3/pg Shift Supv/ Shift Mgr Review By: f v Date: Qgg - Approved By: g,pg (Supt Ops Trng) Date: p_g 97 l l r:@i 4TN% . TI i :@34 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated- N Rrso sopv- OTRNG l Assoc Ret MTCP-3.32 _ lSR: N Frea: 0 yrs ARMS: JPMB912001 l Doc Type: 8505 l Admin initials: V Date:(39 / ell% I/mif
4 MONTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS - Page 2 of 6 4 . ur s er iOP1; ;
.. . ..;_ 'i. _7 .
.g ; . . ..- :. , <g ;jc.f. .
Plant Setup: None Initial Conditions:
' Reactor is in cold :,hutdown with a Refuel Outage in progress. "A" RPS is de-ener-gized awaiting restoration of No.11 RPS MG set which has just been released by the electricians following PM completion. MG Set Supply Breaker (BKR-1107) is already closed. CB1 A is closed and CB2A is open in Cable Spreading room.
Initiating Cues: The_ Shift Supv directs you to startup,No.11 RPS MG Set and place it on RPS Bus A. ,_ _ ALL OPERATOR ACTIONS ARE TO BE SIMULATED! e i I/mif
( l- If!ONTICELLO NUCLEA 1 GENERATING FLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 l MOTOR GENERATORS - Page 3 of 6 PERFORMANCE INFORMATION gl@ornfarice10.b]bEM . . . . . . . . . : ~ta c a r . t . :1 7 A" % STEP 1 Standard: l Locate procedure B.9.12-05.D.1., "MG Locates appropriate procedure. Set Startup". Cue: Provide operator with a copy of procedure. Comments: None 4 STEP 2 "C" (Procedure STEP 1) Standard: Place OFF-ON switch at MG set control Turns the No.11 RX PROTECTION M-G SET
. _ . . panel ON, . __ OFF-ON switch. clockwise to the ON position. .._._ . -_
(Non-Critical portion of Standard)
- 1. Operator should remove access cover from No.11 RX PROTECTION M-G SET control panel to allow access to controls.
- 2. O )erator should observe that the red POWER O 9 light is lit.
Cue: The cover plate is removed and the red POWi!R
^
ON light is lit. Comments: None , STEP 3 "C" (Procedure STEP 2) Standard: Press drive motor START button. Momentarily depresses No.11 RX PROTECTION 1 M-G SET START pushbutton. Cue: Motor has started and is coming up to speed. Comments: None STEP 4 (Procedure STEP 3) Standard: Verify drive motor starts. Verifies drive motor has started. (Non-Critical nortion of Standard) Operator should observe local volt meters. Cue: Drive motor is running. AC VOLYS meter indica-tion is increasing. Comments: None I/mif
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS - Page 4 of 6 STEP 5 (Procedure STEP 4) Standard: If necessary, press drive motor START Verifies voltage is indicated on AC VOLTS meter. button again to establish generator voit-
. ge.
Cue: If operator requests, AC VOLTS meter is reading
, 121 VAC.
Comments: None STEP 6 "C" (Procedure STEP 6) Standard: ! CLOSE generator output breaker, CB. Closes the No.11 RX PROTECTION M-G SET GENERATOR OUTPUT breaker by pushingJt up . ward to the ON position. (Non-Critical nortion of Standard) Operator should, verify the red POWER IN light on EPA-153 is lit. Cue: The white line on the GENERATOR OUTPUT breaker is exposed, and the red POWER IN light on EPA-153 is lit. - Comments: None i I/mif
e MONTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS - Page 5 of 6 MJttormainceIObTeetM.MS'tWdili'M STEP 7 "C" (Procedure STEP 6) Standard: To reset and close the output breakers 1. Closes EPA-153 output breaker by pushing it on the EPA units associated with each down to reset the breaker then upward to the MG Set, perform the following in the or- ON position. der written:
- 2. Closes EPA-154 output breaker by pushing it
- a. IE starting up MG Set A, down to reset the breaker then upward to the THE_N_ CLOSE breaker on ON position.
CL SE breaker on (Non-Critical cortion of Standard) EPA-154. 1. Upon closing the output breaker for EPA-153,
- b. IE startin MG Set B, the operator should verify:
THEN CLO E breaker on a. The red POWER OUT light on EPA-153 is EPA-156, lit AN_DD CLOSE breaker on AND
. EPA-175.
- b. The red POWER IN light on EPA-154 is lit.
- 2. Upon closing the output breaker for EPA-154, The operator should verify the red POWER OUT light on EPA-154 is lit.
Cue:
~
- 1. When the operator looks at EPA prior to operat;'g it, tell them the breaker is in the middle position.
- 2. The red POWER OUT light is lit on EPA-153 and the red POWER IN light is lit on EPA-154.
- 3. The red POWER OUT light is lit on EPA-154.
Comments: None STEP 8 (Procedure STEP 7) Standard: None To reset and close the output breakers Cue: None on the EPA units associated with the al- Comments: ternate source, perform the following in the order written: The operator should determine it is not necessary 1
- a. to complete this step of the procedure due to initi-
. CLOSE breaker on EPA-157. ating cue. <
- b. CLOSE breaker on EPA-158.
STEP 9 Standard: INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted. Cue: None Comments: DO NOT PROMPT! l I/mif
o MONTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS . Page 6 of 6
.- o tt'E 'B v': :6? . ;
^ _'
Initial Conditions: Reactor is in cold shutdown with a Refuel Outage in progress. "A" RPS is de-ener-gized awaiting restoration of No.11 RPS MG set which has just been released by the - electricians following PM completion. MG Set Supply Breaker (BKR-1107) is already closed. CB1 A is closed and CB2A is open in Cable Spreading room. j I'EJTjfFh War 75 7FiRT ~ ~
- mff '
I l Question #: JPM-B.9.12-001-Ql Point Value: 1.0 - Time (Minutes): NA l l - Blockage in the East SDV results in increasing water level in the SDV. SDV water level reaches the point that relays 5AKIC on panel C-15 and SAKID on panel C-17 de-energize. What is the status of the Reactor Protection System?
- Answer:
Full scram due to trip on both "A" RPS and "B" RPS for SDV high level.
' Reference (s): B.5.604 --
K/A '
Reference:
212000 Task Number: A4.12 Rating RO: 3.9 l 4 l.
p , 1 l Candidate's Response to JPM-B.9.12-001-Q1 l l l r l l 1 l [ i
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l Question #: JPM-B.9.12-002-Q2 Point Value: 1.0 Time (Minutes): NA l 1 . An inadvertent opening of 52-307 results in an auto close of 52-209. The length of time for this evolution was approximately .5 seconds. What is the status of the RPS bus ifpower was supplied through CBI A and during the event? - y Answer: Both RPS busses will remain energized. The flywheel on MG Set A will retain voltage for up to 2 seconds. Reference (s): B.9.12-02, pg 3 of 5 K/A
Reference:
2.1.28 Task Number: 212000 Rating RO: 3.2
r-Candidate's Response to JPM-B.9.12-001-Q2 o l I i I i i i
INITIAL SUBMITTAL OF THE SCENARIOS FOR THE MONTICELLO EXAMINATION - THE WEEK OF AUGUST 23,1999 l l i
Monticello Nuclear Generating Plant August 1999 RO Exam I Simulator Exam l
i 9 [-l ,. I I 4 Attached are the Revised scenario outlines. Changes are highlighted in blue. I l 1
r 1 Scenario Outline
. Simulator Scenario 1, "ATWS with SBLC Injection Required"
. Removed RFP discharge pressure gauge failure and replaced with Main i Generator H2 cooler controller failure.
l . Only one bearing fails on main turbine vs. three.
. Simulator Scenario 2, "SORV with Tailpipe Break and Failure of DW Spray"
. Re-titled scenario to more accurately reflect events.
. Changed Sample pump trip to component failure vs. instrument failure.
. Simulator Scenario 3, " Steam Leak in Secondary Containment with a Loss of High Pressure injection" The following changes to scenario to shorten the length.
. Start at 90% vs.100% power (10% power drop vs. 20% power drop)
. Torus cooling will be in service at beginning of scenario. (For RCIC test)
- RCIC operability vs. monthly test (correction)
. Simulator Scenario 4 (Spare) " Loss of Normal Feedwater with Low Power ATWS" No changes Attached are forms ES-D-1 outlining the scenario events.
i 2
. Simulator Scenario 1, "ATWS with SBLC Injection Required" Facility: Scenano BWR Op-Test No.: 1 Monticello No.: 1 Examiners: Operators: RO Brady BOP Caeperson '
Objectives: To evaluate the applicants' ability to start a reactor feedwater pump during plant start-up conditions; increase reactor power using control rods; identify and respond to an SRV bellows leak; to enter and perform EOP for ATWS requiring SBLC injection; to implement contingency for attemate control insertion. Initial Conditions: IC-171; approximately 50% reactor power during start-up following a maintenance outage; *B" CRD flow control valve is out of service due to a ruptured diaphragm. Turnover Continue with reactor start-up by placing #12 RFP in service. Increase power per C.1 Start-up and Nuclear ennineer guidance. Event No. Malf. No. Event Type
- Event Description 1 N/A N(BOP) Start #12 RFP law B-manual procedure B.6.5-05.
Generator H2 cooler controller fails in auto requiring 2 A004P1-S f(BOP) manual control of H2 cooling valve. Increase reactor power using control rods per C.1 3 N/A R(RO) and Nuclear Eng,neer guidance. i 4 M42-01 l(RO) SBLC tank level indicator fails downscale. Bellows leak on "A" SRV requiring response law 5 APO4A C(BOP) Annunciator response procedure C.6.3-A-17. 6 TUO4D C(BOP) f;",rbine bearing 4 high tamp leading to vibration Turbine trip and reactor scram with only a few rods CH16 inserted; Turbine casing will be penetrated CH19 M(Both) resulting in loss of condenser vacuum necessitating 7 A24 C(Both) closure of the MSIVs MC03 CV-19A CRD FCV fails closed preventing rod 8 CH07B C(RO) insertion using CRD hydraulics. 9 MS02B C(BOP) "B" outboard MSIV will fail to close. RHR torus cooling will be required to control torus 10 A510P5-15 l(BOP) temp. DP indication for #11 RHR heat exchanger will fail downscale. 11 RHRSW pump fails to start when given a start 11 A520P30 C(BOP) ;
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 3 )
l l i
q Simulator Scenario 2, "SORV with Tailpipe Break and Failure of DW Spray
- i Facility: Scenan BWR Op-Test No.: 1 Monticello No.: 2 l Examiners: Operators: RO Eigen BOP Brady Obiectives: To evaluate the applicants' ability to; reduce reactor power using recire pump speed control; perform MSIV exercise test; respond per AOPs to a loss of an essential MCC, leaking SRV, and SRV failed open; implement EOP actions on increasing drywell temperature and pressure escalating to conditions requiring a emergency RPV depressurization.
Initial Conditions: IC-172; 100% reactor power; #11 SW pump is taggd out of service for j packing replacement. i Tumover Reduce power to 90% per C.2 Power Operations for monthly MSIV testing. Event No. Malf.No. Event Type
- Event Description 1 N/A R(RO) decrease power to 90%
RW trouble alarm due to sample tank pump trip 2 C05A49 C(RO) following completion of release to CSTs
#3 APRM recorder fails as is at 95% indicated 3 POS I(RO) power requiring notification of l&C to correct condition.
4 A510P07-11 f(BOP) #11 Recire pump speed indication fails as is i 5 N/A- N(BOP) MSIV exercise testing law surveillance 0160. ? MCC-142A ground resulting in feeder breaker trip ED75 6 C(BOP) to MCC 142. Pressure control transfers from EPR to MPR as a result of this failure.
"F" SRV begins to leak requiring monitoring of SRV 7 AP03F C(BOP) temp recorder, execution of ARP C.6-3-A-9., and execution of AOP C.4.B.3.3.B "F" SRV fails open with broken tailpipe. Rx scram
[C0 F at 2# drywell including a spurious group one S34-01 8 M(Both) isolation when reactor pressure decreases to 840 S34-02 psig. S34-03 S34-04 Drywell spray valve MO-2022 failed closed. This combined with the loss of power to the Div 2 drywell spray valves inhibits DW spray capability. 9 A520P31 C(BOP) This will result in DW pressure increasing to a point , requiring RPV emergency depressurization per l EOPs. l "C" SRV fails closed when RPV emergency l depressurization is required. Power is : 10 A520P30 C(BOP) subsequently restored to MCC 142 allowing DW ! spray to begin. .
* (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor 4
l
Simulator Scenario 3, " Steam Leak in Secondary Containment with a Loss of High Pressure injection" Facility: Scenan BWR Op-Test No.: = 1 Monticello No.: 3 Examiners: Operators RO = Casperson BOP = Eigen Objectives: To evaluate the applicants' ability to; complete'RCIC surveillance; reduce reactor power using recirc pump speed control and control rods; respond to a control rod drifting fror.1 the core; respond to loss of high pressure feed and implement EOPs on low reactor water level and high secondary containment radiation; complete an RPV emergency depressurization including level restoration with low pressure pumps. Initial Conditions: IC-173; 90% reactor power; RCIC operability testing in progress for post maintenance testing. The valve timing portion of the surveillance test is complete. Tumover: Complete the RCIC monthly testing. Vibrations on #11 condensate pump have been increasing slowly (not yet at the alarm point). Power was reduced to 90% last shift to determine the effects on the pump vibration. OC is meeting to discuss further course of action regarding the increasing vibration. B loop of RHR is in Torus Cooling. Event No. M alf. N o. Event Type
- Event Description 1 N/A N(BOP) Complete RCIC monthly surveillance test.
2 A510P06-08 f(BOP) RCIC RPM gauge fails downscale Power reduction is requested from OC due to an increasing vibration trend on #11 condensate 3 N/A R(RO) pump. Power should be reduced to 80% using recirc speed control and then four rods need to be inserted per the Nuclear engineer. Rod drift out of core with at failure of the rod drift CH01 C(RO) light and the rod drift alarm. Recovery of the 4 C05A27 inadvertent rod withdrawal requires hydraulic BAS 43P30 l(RO) isolation at pos,i tion 00. 5 FWO3B C(BOP) #12 condensate pump breaker trip
#11 condensate pump trip on high vibration 6 FWO3A C(BOP) resuiting in a reactor scram at +9 inches. All control rods willinsert.
At -48 inches or when RCIC is manually started, RC07 the RCIC steam line will break in the RCIC room RC08 and will fail to isolate. HPCI will start at trip on high 7 A520P30 M(Both) exhaust pressure. Entry into EOPs for water level A520P28 and Secondary Containment radiation will be HPO3 required. 2 off-scale high radiation indications will require a 8 N/A M(Both) emergency RPV depressurization per EOPs 9 A520P29 C(BOP) Division one RHR pump will fail to start
* (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor 5 .
i e Simulator Scenario 4 " Loss of Normal Feedwater with Low Power ATWS" Facility: Scenari Monticello MR No.: 4 Op-Test No.: 1 Examiners: Operate 3: Spare Obiectives: To evaluate the applicants' ability to; operate the EDG; increase reactor power using recirc pump speed control; respond per AOPs to a loss of an RBCCW pump, and a trip of a recirc and RFP pump on a loss of #12 4160 bus; implement EOP actions on decreasing reactor water level with an A1WS condition; manually control HPCI. Ja%I Con'$lSDE: IC-174, 70% reactor power; #11 EDG in service for post maintenance testing. #11 service water pump is out of service for packing replacement. Turnover: Complete EDG surveillance test then increase reactor power to 80% per C.2 Power Operations and Nuclear engineer guidance. Hold at 80% per Nuclear engineer. Event No. Malf. No. Event Type
- Event Description
" Drywell cam trouble alarm due to filter paper failing 1 C04B22' C(BOP) to advance. 2 N/A N(BOP)' Complete surveillance test for #11 EDG "C" MSL flow indicator falis downscale requiring 3 A510P7 l(BOP) l&C response 4 N/A R(RO) Increase reactor power to 80% Trip of #11 RBCCW pump with failure of #12 pump SWO1A to auto start. #12 will start when given a start 5 A531P27-01. C(BOP) signal.
#12 4kv bus ground resulting in a trip of #12 6 ED05B C(BOP) reactor feed pump and #12 recirc pump.
Spurious trip of #11 reactor feed pump causes a reactor scram at +9 inches. All rods do not insert 7 I^ } requiring EOP ATWS entry. Control rods will drift 6 M B th) into core when increased cooling water flow is applied. HPCI controller will fail in automatic. HPCI will 8 A510P6 i(BOP) function with the controller in manual.
* (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor s
6
MONTICELLO NUCLEAR GENERATING PLANT lNIT-OP TEST 01 TITLE: ATWS WITH SBLC INJECTION REQUIRED Revision 0 Page 1 of 13
/
Prepared By: gg Date: ppg Validated By: [hh Date: % 9, /W) Reviewed By: A g 4k ' Date: q T4 gg Approved By: ~ Date: 7_ /p - f p ATTACHMENTS 1. Form 3139 (CONTROL ROOM SHIFT TURNOVER CHECKLIST) 2. Form 3140 (SHIFT SUPERVISORS OFFICE TURNOVER CHECKLIST) PRAINPUT
- 1. Initiating Event:
Turbine trip due to vibration.
- 2. Accident Class:
Class IV - Accident sequences involving failure to scram leading to a high pressure cha!!enge to containment resulting from power generation into the containment.
- 3. Human Errors / Equivalent:
e LSLCINJECY Failure to inject SBLC - e UH Failure to control reactor level during an ATWS e RLOTORCLGY Failure to initiate Torus Coomig e PSMSABCDXY Failure to manually initiate ATWS
- 1. SCENARIO
SUMMARY
A. Scenario Descriotion
- 1. Initial Conditions The unit is in the process of starting up with power about 50%. No.12 RFP will be started. Rods will be withdrawn to reach the 100% rod pattern. *B" CRD FCV has a ruptured diaphragm and is out of service.
~
- 2. Scenario Events
- a. No.12 RFP will be started per C.1 (REACTOR STARTUP) and B.06.05-05.02.
- b. Reactor power increase with control rods per Nuclear Engineering request and C.2 (POWER OPERATIONS).
1/cmb
i l MONTICELLO NUCLEAR GENERATING PLANT l NIT-OP-TEST 01 TITLE: ATWS WITH SBLC INJECTION REQUIRED Revision 0 i Page 2 of 13 I
- c. SBLC Tank Level Indicator Fails Downscale. l.
- d. SRV Bellows Leak Alarm requiring ARP actions to determine operability. I l
- e. No. 4 Turbine Bearing temperature will start to increase. Vibration on No. 4 I Bearing will also increase until the Turbine Vibration High Alarm comes in.
Operator Action to unload the Turbine may slow the vibration increase,
- f. Vibration will slowly increase until the Turbine trip point is reached. At this point, ,
whether a SCRAM is inserted manually or the turbine trip causes the scram, full rod i insertion will not occur.
- g. Turbine vibration will continue to increase, resulting in Turbine blading failure and casing penetration. Air in-leakare will rapidly increase and vacuum will begin dropping and the condenser willbe lost as a heat sink. A report will be made that l the Turbine Building Operator heard a loud bang and then heard a leak from either ;
the Turbine operating floor or the hot side (he/she can't tell), no steam is visible. At l this point, the SRVs will be lifting due to the low power ATWS and the Torus will be l the heat sink.
- h. The loss of CRD "A" FCV and failure of MO 3-20 will prevent rod insertion. Even with both loops of RHR in Torus Cooling, the Torus temperature will continue to increase slowly, requiring SBLC injection and entry into Level / Power control.
- 3. Termination Cues
- a. Reactor !
injected, andpower, as indicated plant conditions bycontrol. are under the APRMs, is less than 3%, SBLC has b ' NOTE: Stable plant conditions are not possible in a reasonable amount of time. i B. Scenario Objectives 1
- 1. Evaluate ability to Start an RFP during a Plant Startup and increase Reactor power using controrrods.
- 2. Increase Rx power per C.1 and Nuclear Engineer instructions.
, 3. Identify and respond to instrument malfunction, H2 CLG-1589 Controller. t
- 4. Increasing Turbine bearing vibration could lead to potential Turbine damage in addition to a reactor scram and must be responded to promptly.
- 5. Loss of condenser vacuum could lead to loss of the heat sink for the reactor and must be responded to promptly.
- 6. A SCRAM with failure of all rods to fully insert is a situation which could quickly jeopardize Primary Containment integrity if immediate actions to mitigate are not taken.
- 7. Increasing Torus temperature has a high potential for damage to the containment and must be responded to promptly.
- 8. During followup actions after the scram, the operator should identifv the failure of an Outboard MSIV to close. Also, an RHRSW pump will fail to start when given a start signal. Verification of redundant isolation and use of redundant pumps will be required .
to complete required actions 1/cmb
F YM p Q42?ELLO NUCLEAR GENERATING PLANT INIT-OP-TEST 01 TITLE'. ATWS WITH SBLC INJECTION REQUIRED Revision 0 Page 3 of 13 l
- 11. SCENARIO CREATION A. Initial Conditions
- 1. 1C-171 B. Manual Settina Summarv
- 1. Hang SECURE Card on "B" CRD FCV.
C. Event Triaaer
- 1. None D. Procedures /Surveillances i
- 1. None l l
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r R; vision 0 MONTICELLO NUCLEAR GENERATING PLANT Page 13 of 13 l SHIFT TURNOVER INFORMATION Ble unit is currently at 50% power during a Startup following a maintenance outage. "B" CRD Flow Control Valve is out-of-service due to a ruptured diaphragm. Continue with the Reactor Startup by placing No.12 RFP in service. Increase power per C.1 i (STARTUP) and Nuclear Engineer guidance. ! Within the next half hour, the Nuclear Engineer will provide a list of required control rod moves to , l retum the plant to 100% power. The plans for this shift are to continue with the Startup.
"B* CRD FCV air operator ruptured a diaphragm last shift and is currently tagged out and the valve operator is disassembled. "B" FCV should be back sometime next shift.
l l MONTICELLO SIMULATOR USE ONLY L l INSTRUCTIONS FOR: CONTROL ROD WITHDRAWALTO 100% ROD PATTERN Increase Reactor power by withdrawing control rods to 100% rod pattern.
- 1. Withdraw the following control reds from position 12 to position 36:
14 - 23 38 - 31
'22 - 36 ,
30 - 39 i 14 - 31 38 - 23 _ 30 - 23 22 - 31
- 2. Withdraw the following rods from position 4 to position 12:
22 - 31 30 - 23 30 - 31 22 - 23
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! MONTICELLO NUCLEAR GENERATING PLANT 3139 i TITLE: CONTROL ROOM SHIFT TURNOVER CHECKLIST Revision 23 Page 1 of 2 l Shift Manager: TRAINS'Jt Date: rn A e a s'ar- Shift: o yo a - /9 oo Completed By- y d g %. Reviewed By: Shift Supv.: d w. ,t LPEO: w,e e PEO: 2 gv ( Omen: Mode Switch Shutdown Startup k N9 Refuel MWT Core Thermal Power 5 Nominal 1775 MWT Core Flow 5 57.6 + 1 (inst error) x 10'Lb/Hr 4./ ~/ f x 1OC lb/Hr Core /Rx Dp 518.6 /5 27 PSID r.X / ~7. O PSID Rx Pressure 5100r + 20 PSIG 93O PSIG Rx Level +30 to +40 INCHES Indicated 3.5 INCHES , Torus Level -2" to +2" O INCHES f RCPDp 5143 PSID /5 / /_5 PSID Steam Flow 5 7.20 + .25 (Inst Error) x 10'Lb/Hr .2./3 xi0' Lb/Hr FW Flow < 7.20 + .25 X 10*Lb/Hr 3.// x)0' Lb/Hr
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Controller System Sw. Pos. Mode /SP/Outout Alarms Valve Une-Uo i 11 D Gen /h.rl o N/A C N/A N/A N/A 12D Gen ADS "A", "C", "D" N/A N/A V' N/A N/A SRV Low-Low Set C-03 *E" "G", *H" DIV 11 Low-Low Set Logic Auto /Byp N/A N/A "A" RHR AJn N/A OK "A" RHRSW _ p % / J20 /O )
"A" Core Spray N/A HPCI N/A A.Mc / f S~ l ICO "B" RHR /4vh N/A "B" RHRSW oFA /*" / 40 / O "B" Core Spray M N/A RCIC N/A MN / f 0 / loo "A" SBGT 4h p / 40 / O g "B"SBGT p p / 40 /o f SBLC n# N/A CKT Cont ind nl/
"A" EFT Qum.W7 N/A l
"B" EFT yh)1/Jfb/ N/A n;nonepqweg g p wegemf3w:mm;ggrs:g; gun.mgaa:gri Source Supplying: 1R 1AR EDGs is a Manual 2R/1R Transfe utred prior to taking generator off line? Yes
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3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: 99-/4'70 0 ADM,,lh)ST3A OPER l SR:/\ le Frea: 0 )vts. _ Reso Suov- OPER W/M l Assoc Ref: STONI'- a ARMS- 3139 "IDocTvoe: 407C I Admin initialsd W Date%MW M/clii O ' .s ,11 3 i + 6 r* ? i Q t O *.1!' ,
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MONTICELLO NUCLEAR GENERATING PLANT 3140 TITLE: SHIFT SUPERVISORS OFFICE TURNOVER Revision 14 CHECKLIST Page 2 of 2 Shift Mgr: rwa m.Wr, Shift Supv: rw . .w . c (Circle items where applicable) j Completed By: wn Date: xxxx Shift: 0700-1900
- 1. Unit status: Powerlevel - 50 #7o MWT E'/S MWE o 73
- 2. Any Surveillance Tests in progress now?
if YES, Numbers: YES k
- 3. List Suweillance Tests scheduled for next shift: ,
Numbers: 1216-1.
- 4. Any infrequent Test or Evolution (as defined in 4 AWi-04.05.07) in progress? YES NO If YES, state Test or Evolution if YES, on-coming Shift Manager SHALL ensure that on-coming crew is briefed by the Senior Line Manager responsible for the Test or Evolution, prior to tumover using the same Form 3560 that was used for the previous crew.
- 5. Any limiting conditions for operation? YES (List,if YES) a.
b.
- 6. System deviations from normal during shift:
- a. cRO e u n B ireta4J Je J,w d n rep,v.
b. c. d. e. f. _ 7. Any new memos or instructions issued? YES k (if YES, then list or attach copy) a. b.
- 8. On-coming shift review the following and sign below:
- a. Shift tumover checklist f. WRAs/OCDs in progress
- b. Equipment status sheet g. Shift Supv log
- c. Active jumper /byass log h. Controlled key log
- d. Night order book i. SS/SM controlled key rings received
- e. New memos / instructions Shift Manager: Date:
Shift Supewisor: Date: t/ pdc 't 1.;t'ra
i
+ .
MONTICELLO NUCLEAR GENERATING PLANT l NIT-OP-TEST 02 { TITLE: SORV WITH TAILPIPE BREAK AND Revision 0 FAILURE OF DW SPRAY Page 1 of 16
. /
Prepared By: Date: 7jy . y Validated By: g gg Date: y j z _ cyy 1 I Reviewed By: y jg Date: 7 g-g9 Approved By: Date:
} 7 -f y p p y - -
AITACHMENTS
- 1. Form 3139 (CONTROL ROOM SHIFT TURNOVER CHECKLIST)
- 2. Form 3140 (SHIFT SUPERVISORS OFFICE TURNOVER CHECKLIST)
PRA INPUT
- 1. Initiating Event:
Stuck Open Relief Valve
- 2. Accident Class:
Class 1118 - Accident sequences initiated or resulting in small or med um LOCAs for which the Reactor is not depressurized.
- 3. Human Errors / Equivalent:
~
RLODWSPRAY -. Failure to spray the Drywell - XRPVBLDWNY - ~ Failure to spray the Containment
- 1. SCENARIO
SUMMARY
A. Scenario Descriotion
- 1. Initial Conditions The unit is operating at full power with No.11 SW Pump out-of-service.
, 2. Scenario Events
- a. Reduce Rx power to 90% for MSIV monthly test,
- b. APRM No. 3 Recorder Fails as is at 95% power. 4 l
- c. No.11 Recirc Speed Indication is Failed as is,
- d. A ground will develop in MCC-142A. The crew must verify proper MPR operation and LCO requirements.
l I/cmb l t
MONTICELLO NUCLEAR GENERATING PLANT INIT-OP-TEST 02 TITLE: SORV WITH TAILPIPE BREAK AND Revision 0 FAILURE OF DW SPRAY Page 2 of 16 l l
- e. During this period, SRV-F will begin leaking and a tailpipe break in the Torus will l
release the energy above the suppression pool. DW pressure will slowly rise as the leak continues to increase.
- f. A SCRAM will occur at 2 psig and Division I Torus Sprays will be placed in-service.
As Drywell temperature increases, the leaking SRV will fail Full Open.
]
- g. At 12 psig DW sprays will be attempted and Division I MO-2022 will fail to open, along with Division 2 due to loss of MCC-142A preventing Drywell spray. Drywell temperature and pressure will continue to increase.
- h. The failure of the mode switch in RUN will result in a Group I isolation as pressure drops below 840 psig preventing rapid depressurization through the bypass valves.
Before drywell pressure exceeds the DW pressure limit (-27 psig), a blowdown will be required. I
- i. When the 3 ADS valves are given an open signal, "C" SRV will not open, requiring the opening of a different SRV.
J. Successful operation of Drywell sprays will be allowed after emergency l depressurization has been initiated following restoration of MCC-142A. Drywell I and Torus sprays must be secured before negative containment pressures are l sustained.
- 3. Termination Cues
- a. Emergency Depressurization initiated,
- b. Drywell pressure under control. _
- c. Prior to crew entering RPV flooding.
Elli: Stable plant conditions are not possible in a reasonable amount of time. B. Scene,rio Objecthres:
- 1. Reduce Reactor power using recirc and recognize Failed APRM Recorder and Failed Recirc Speed Indicator.
- 2. Perform MSIV Exercise Test.
- 3. Paspond to a 1.oss of MCC-142A l 4. Respond to an SRV leak.
- 5. Respond to a Stuck Open SRV with a broken tailpipe.
- 6. Emergency depressurize the Reactor due to high Drywell pressure and respond to an SRV that Falls to OPEN.
I/cmb
l MONTICELLO NUCLEAR GENERATING PLANT l NIT-OP-TEST 02 TITLE: SORV WITH TAILPIPE BREAK AND Revision 0 FAILURE OF DW SPRAY Page 3 of 16 l l
- 11. SCENARIO CREATION 1
A. Initial Conditions
- 1. 1C-172 B. Manual Settina Summarv
- 1. Place a SECURE Card on No.11 SW Pump Handswitch.
C. Event Triaaer
- 1. None D. Procedures /Surveillances
- 1. 0160 (MSIV EXERCISE TEST)
=
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MONTICELLO NUCLEAR GENERATING PLANT Revision 0 Page 16 of 16 SHIFT TURNOVER INFORMATION The plant is at 100% power. The No.11 SW Pump is tagged out-cf-service for packing replacement. A Reactor power reduction to 90% is scheduled to allow MSIV exercise testing per surveillance No. 0160. i l I I/cmb ! I
l a2 I l 1 MONTICELLO NUCLEAR GENERATING PLANT 3140 TITLE: SHIFT SUPERVISORS OFFICE TURNOVER ~ Revision 14 CHECKLIST Page 2 of 2 Shift Mgr: 7 7P rol n Q c Shift Supv: mWWr / (Circle items where applicable)
/
Completed By: v( Date: yx Shift: 0700-1900
- 1. Unit status: Power level /60 % MWT / 7 S S' MWE [a62 /
- 2. Any Surveillance Tests in progress now?
If YES, Numbers: YES [
- 3. List Surveillance Tests scheduled for next shift:
Numbers: 1216-1. 6 /6 O MC/ c/ 2%etc/M
- 4. Any infrequent Test or Evolution (as defined in 4 AWi-04.05.0h) in YES progress?
If YES, state Test or Evolution if YES, on-coming Shift Manager SHALL ensure that on-coming crew is briefed by the Senior Line Manager responsible for the Test or Evolution, prior to tumover using the same Form 3560 that was used for the previous crew.
- 5. Any limiting conditions for operation? YES (List,if YES) ,
a. b.
- 6. System deviations from normal during shift:
- a. #M .s~w nvy ocr 4 facNg res/ wen.eu L
- b. l
- c. _
- d. ,
e.
- f. ~
- 7. Any new memos or instructions issued? YES (if YES, then list or attach copy) a.
b.
- 8. On-coming shift review the following and sign below:
- a. Shift tumover checklist f. WRAs/OCDs in progress
- b. Equipment status sheet g. Shift Supv log
- c. Active jumper /byass log h. Controlled key log
- d. Night order book i. SS/SM controlled key rings received
- e. New memos / instructions Shift Manager: Date:
Shift Supervisor: Date: , 1/ pdc
i" ~
- .2. l MONTICELLO NUCLEAR GENERATING PLANT 3139 i TITLE: CONTROL ROOM SHIFT TURNOVER CHECKLIST Revision 23 1
Page 1 of 2 Shift Manager: TR A1a(W c _ Date: 7TRhJW 0 Shift: C70 0 - /90 0 Compleiad By- // Reviewed By Shift Supv.: X< LPEO: y/ PEO: 24 Others: Mode Switch Shutdown Startup kerf Refuel CoreTherr elPower 5 Nominal 1775 MWT /7f9 MWT Core Fl-" $ 57.6 + 1 (Inst error) x 10*Lb/Hr 47 7X /O G Lb/Hr Core /Rx Op 518.6 / $ 27 PSID /A.5 / /M PSID Rx Pressure 51008 +20 PSIG /006 PSIG Rx Level +30 to +40 INCHES indicated 75 INCHES Torus Level 2" to +2" O INCHES RCPDp 5143 PSID 89 / 92 PSID Steam Flow $ 7.20 + .25 (Inst Error) x 10*Lb/Hr "7. /g y ;O ' Lb/Hr FW Flow ~ < 7.20 + g5fnst Error) X 10 Lb/Hr 8
"7. /'/ x 10 ' Lb/Hr
" SiNI.TRUMENTATiaWhT6Es%5f85S$5$[E"TdW23;'MR,$MEMMAb'6v'e[nfaItM Nuclear instruments ,
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Rx Level 1 element MAN MSTR-MAN Mnt O Main Reg Va Lo Flow Reg Va @ AUTO RFP LevelTrip BYPASS Press Contr MPR# 900 N@ 90Q EPR #
" h5R7ENNISjS,IRMMIUY5Nb#lEGyyMfiMd@@$S.;jffdMNEthTNNtilh5M Controller - !
System Sw.Pos. Mode /SP/Outout Alarms Valve Line-Uo l 11D Gen Avb N/A OK N/A 12 D Gen N/A N/A l ADS "A", "C", "D" N/A N/A SRV Low-Low Set C-03 "E", "G", "H" V N/A N/A OfV 11 Low-Low Set Logic AItsbyp N/A N/A "A"RHR 3uYo N/A OK
*A" RHRSW OFF * / Jo /o "A" Core Spray M N/A - l HPCI N/A ph. h / E 5 / loo f "B" RHR /k,h N/A l
*B" RHRSW OFP mW/ &0 /o "B" Core Spray Ah N/A l RCIC N/A AlvfC / .PO //O (
"A" SBGT M m /4D/0 "B" SBGT /,kdt e / 40 / 0 l SBLC d PF- N/A CKT Q:pt ind . . j "A" EFT R"'j N/A
*B" EFT /kMs/f%/ N/A ~
i
$MUXPQ91/ERMEMi#SF9MMinsdEifz@UndhMd.OM'.dC/ing,$55E2dO55$ l Source Supplying: 2R 1R 1AR EDGs is a Manual 2R/1R Transfer required prior to taking generator off line? Yes @
3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: 99 -/t/ 76
- R ADMINISLRATIV Reso Suov: OPER W/A l Assoc Ref: OPER I SR:/\ 2 Frea: 10 ksi DatefMN SELONI'. - .4 ARMS
- 3139 "I Doe Tvoe- 407C l Admin initials 4 '4
MONTICELLO NUCLEAR GENERATING PLANT l NIT-OP-TEST 03 TITLE: STEAM LEAK IN SECONDARY Revision 0 CONTAINMENT WITH A LOSS OF HIGH Page 1 of 12 PRESSURE INJECTION l Prepared By: g{ Date: 7,9_g9 I Validated By: Mg /Y1a% Date: % ) , J 9 at 3 Reviewed By: ks (uk Date: c) 74 gg Approved By: k) [ Date: f yh_pof ATTACHMENTS
- 1. Form 3139 (CONTROL ROOM SHIFT TURNOVER CHECKLIST)
- 2. Form 3140 (SHIFT SUPERVISORS OFFICE TURNOVER CHECKLIST)
- 1. PRAINPUT i i
A. Initiating Event:
)
- 1. Loss of Feedwater B. Accident Class:
- 1. Class V - Unisolated leak outside Primary Containment.
C. Human Errors / Equivalent:
- 1. XRPVBLDWNY - Failure to manually depressurize
- 2. RLOTORCLGY - Failure to initiate Torus Cooling II. SCENARIO
SUMMARY
A. Scenario Descriotion
- 1. Initial Conditions The plant is operating at 90% power. Power was reduced to 90% last shift to determine the effects on No.11 Condensate pump vibrations. Vibration on No.11 Condensate Pump has been slowly increasing. RCIC operability testing is required for post-maintenance testing following work on the governor. "B" RHR loop is in service for Torus cooling.
- 2. Scenario Events
- a. RCIC RPM Meter 'will fait downscale during system operability testing.
- b. A power reduction is requested by OC in an attempt to reduce the vibration on No.
11 Condensate Pump. The Nuclear Engineer will request the power reduction to be completed with Recire Speed Control and control rods. 1/cmb
F MONTICELLO NIJCLEAR GENERATING PLANT INIT-OP-TEST 03 TITLE: STEAM LEAK IN SECONDARY Revision 0 CONTAINMENT WITH A LOSS OF HIGH Page 2 of 12 L PRESSURE INJECTION l c. While reducing power with control rods, the selected rod will inadvertently drift out with a failed rod drift alarm and rod drift light.
- d. Later, No.12 Condensate Pump will trip on Overcurrent,
- e. With an increased flow through No.11 Condensate Pump, vibrations will increase to the trip point causing a loss of normal feedwater.
- f. At -47" Reactor Vessel level, HPCI will auto start and trip on high exhaust pressure due to a failed check valve in the exhaust line.
- g. RCIC will Auto Start at -47" and a failure of the Steam Supply Line will occur along with an inability to Close the Steam Supply isolation Valve.
- h. The RCIC Steam Line break will be required and an entry into C.5-1100 and C.5-1300 will be required.
- i. An RPV Emergency depressurization when two (2) ARMS reach Max Safe.
J. Reactor Vessel level recovery will be required using low pressure ECCS Systems. No.13 RHR Pump will fail to Start.
- 3. Termination Cues
- a. When Reactor level is restored above 9 inches.
NOTEi: Stable plant conditions are not possible in a reasonable amount of time. B. Scenario Objectives:
- 1. Complete a routine RCIC surveillance procedure.
- 2. Reduce Reactor power using Recirc pump speed control and control rods in accordance with procedural guidance fount in C.2 (LOAD REDUCTION). _
- 3. Respond to a control rod drifting out of the core. Timely actions are necessary to limit the reactivity affects of the drifting rod. Implementation of procedural steps are required to secure the control rod at position 00.
- 4. A loss of high pressure feed will require operator response to restore and maintain adequate RPV level per the RPV Control EOPs. A failure of the Primary Containment Group 5 isolation valves combined with a steam line break will require operator actions in Secondary Containment Control EOPs that ultimately results in Emergency RPV depressurization.
S. RPV water level will be restored using low pressure pumps following the blowdown. An RHR pump will fail to start requiring the operator to use redundant pumps to restore RPV level and to cool the Torus. 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT INIT-OP-TFST03 TITLE: STEAM LEAK IN SECONDARY Revision 0 CONTAINMENT WITH A LOSS OF HIGH Page 3 of 12 PRESSURE INJECTION 111. SCENARIO CREATION A. Initial Conditions
- 1. IC-173 B. Manual Settina Summarv
- 1. None C. Event Triaaer
- 1. None D. Procedures /Surveillances
- 1. RCIC Operability Test eso e
1/cmb
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MONTICELLO NUCLEAR GENERATING PLANT Revision 0 Page 12 of 12 i SHIFT TURNOVER INFORMATION The Plant is operating at 90% power. RCIC testing is required to satisfy post-maintenance testing l following work on the governor. No.12 RHR and No.12 RHRSW pumps are in service for Torus I cooling. Vibration levels on No.11 Condensate Pump motor have been slowly increasing. Power was reduced to 90% last shift to determine the effect of reduced pump flow on vibration. OC is currently meeting to discuss the course of action. MONTICELLO SIMULATOR USE ONLY INSTRUCTIONS FOR PLANNED POWER REDUCTION TO 50% POWER, FROM NUCLEAR ENGINEER: l Reduce Reactor power to 50% by following the below steps in sequence:
- 1. Reduce recire pump speed at 5 MWe/ minute to reduce Reactor power to 80%.
- 2. Insert the following control rods:
Rod 30-31 from 12 to 00
=
Rod 22-23 from 12 to 00
=
Rod 22-31 from 12 to 00 l
=
Rod 30-23 from 12 to 00
- 3. Reduce power to 50% by decreasing the speed of both recire pumps.
Call me at 1839 if you have any questions. Nuclear Engineer 1/cmb
#3 l MONTICELLO NUCLEAR GENERATING PLANT 3140 TITLE: SHIFT SUPERVISORS OFFICE TURNOVER Revision 14 CHECKLIST Page 1 of 2 t 1
Shift Mgr: W., ;- o Shift Supv: A. to (Circle items where applicable) ) a a > Completed By: y yyy Date: yrA-r Shift: 1900-0700
- 1. Unit status: Power level ^ 9 0 7o MWT //o O (o MWE Don l 2. Any Surveillance Tests in progress now? YES NO If YES, Numbers:
- 3. List Surveillance Tests scheduled for next shift: l Numbers: 1350. OArf - c) A- n1 - 1 (Rd.;eoneca,thf)' y l
- 4. Any infrequent Test or Evolution (as defined in 4 AWi-04.05.07) in progress? YES @
! If YES, state Test or Evolution i If YES, on-coming Shift Manager SHALL ensure that on-coming crew is briefed by the Senior Line Manager responsible for the Test or Evolution, prior to tumover using the same Fonn 3560 that was used for the previous crew.
- 5. Any limiting conditions for operation? h NO (List,if YES) ,
- a. ~7 e2 h r I-.CO Co r LPc I i.A "
Penk s bue +o 75rus Goboa b.
- 6. System deviations from normal during shift:
- a. Pleweb 7~3 ras comAm:. in sert / ire k r vocomima i2C(C &S
- b. L e r- r ec%cph + T' 9 8 9e che -fo ibcres shko IAl-rdi Pu J 5 -I-rm h e+ "// Comb a
- d. ;
- e. j l~ f, -
- 7. Any new memos orinstructions issued? @ NO (if YES, then list or attach copy)
- a. nc meek o +n hiseass
- ll Con d numn n &rchbu.
b. l ! I -- ! 8. On-coming shift review the following and sign below: i a. Shift tumover checklist f. WRAs/OCDs in progress
- b. Equipinent status sheet g. Shift Supv log l
! c. Active jumper /byass log h. Controlled key log
- d. Night order book i. SS/SM controlled key rings received
- e. New memos / instructions Shift Manager: Date:
Shift Supervisor: Date: l 3087 (DOCUMENT CHANGE. HOLD. AND COMMENT F_QBM) incorporated: HMWl isR: 9 Frea: .0 Arts /,
' QlS D TIPER Reso supv- Gs0 \AMWJ Assoc Ref: Gs0 f, I ' E DNIH ARMS: 3140 lDoTType: 407D I Admin initials: y Date! l,W/4/ //f(
Pd SIMLLATOR USE ONLY
ws so MONTICELLO NUCLEAR GENERATING PLANT 3139 TITLE: CONTROL ROOM SHIFT TURNOVER CHECKLIST Revision 23 Page 1 of 2 l Snift Manager. T 2AIW M S Date: T72 AiNI.di Shift: C70 0 - J 9 6 0 ] Completed By: V Ac. Reviewed By: Shift Supv.: x'/X LPEO: x(x i PEO: >< ,,/ 4 Others: Mode Switch Core Thermal Power Shutdown 5 Nominal 1775 MWT Startup k /60 b Refuel MWT Core Flow 8 5 57.6 + 1 (Inst error) x 10 Lb/Hr 40 9 X lO C lb/Hr Core /Rx Dp $ 18.6 / $ 27 PSID /o J / p/,5 PSID Rx Pressure 51008 +20 PSIG 9RA PSIG Rx Level +30 to +40 INCHES Indicated 25 INCHES Torus Level -2" to +2" O INCHES RCPDp $ 143 PSID ~70 / 70 PSID Steam Flow $ 7.20 + .25 (Inst Error) x 10'Lb/Hr (e.45 y iO4 lb/Hr FW Flow (t.43 yIO' Lb/Hr
" < 7.20 h[NSINEMEOMOME,42/I'MM*~edYkfMZMid2!!MiM18Ati6v+ .245 Inst Error) X 10*Lb/Hr r$$IYM i
O Nudear Instruments . Rad Monitors g I
" . ld.h, . , ,
l [UO'NTROLLEN Rx Level hikD'ES3dIicleMekha'chEy'sIerri) 1 element UECld.i nt .d.'h, I Main Reg Vs MSTR-MAN Lo Flow Reg Va A RFP LevelTrip BYPASS Press Contr MPR# 9/0 EPR # 90O_
" NE[ENCQiSIg!A((Mhh'M:E2iIKBMNNMIM+1WdrMENDMs&@MS$ l Controller System Sw. Pos. Mode /SP/Outout Afarms Valve Line-Uo 11 D Gen p$v40 N/A N/A Cf N/A N/A 12D Gen i ADS "A", "C", "D" N/A N/A SRV Low-low Set C-03 "E", "G", "H" l/ - N/A N/A DIV !! Low-Low Set Logic Auto /Byp N/A N/A "A" RHR /4<.,-4-D N/A o//
"A" RHRSW CFF e/c00 /o j' "A" Core Spray /}udb N/A y f HPCI N/A /1Mt / ,fPI~ / /0 0 "B" RHR 7~oN.t 0o51') N/A M A 4/
*B" RHRSW 99+M M/ cp O / (, "7 DE "B" Core Spray A/h N/A RCIC N/A M / 80 //W "A" SBGT g p / 4/O / O f "B" SBGT A pg / NG /6 (k S8LC 0FF N/A CKT Cont ind U "A" EFT Ib-M N/A "B" EFT 514 ff4(q N/A MAUX,fddER.j,dj@'WF ~ WMD:d6-28,FjnilGdj71'Unis:iWn;Mh252 Source Supplying: 1R 1AR EDGs is a Manual 2R/1R Transfer required prior to taking generator off line? Yes h
3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: 99 -/ t/ 7d O- MINIST TjVN. Rese Suov- OPER ,W/# l Assoc Ref- OPER l SR:/\ $ Frea: }0 Ivts. l
,MONL M,M ARMS' 3139 "I Doe Tvoe- 407C l Admin initials 4 -d DatekMM M/ciii W a;11 Pi -r a r* ! Q t m H
.~. .
MONTICELLO NUCLEAR GENERATING PLANT INIT-OP-TEST 04 TITLE: LOSS OF NORMAL FEEDWATER WITH Revision 0 LOW POWER ATWS Page 1 of 12
/
Prepared By: g ,, Date: 7 g ,9 g Validated By: M Mc% ' Date: Q $ , /999 Reviewed By: }kvp Date: $ p( g 3 Approved By: g}h Date: 7 -/g 97 ATTACHMENTS
- 1. ' Form 3139 (CONTROL ROOM SHIFT TURNOVER CHECKLIST)
- 2. Form 3140 (SHIFT SUPERVISORS OFFICE TURNOVER CHECKLIST)
- 1. PRA INPUT A. Initiating Event:
- 1. Loss of Feedwater Pumps B. Accident Class:
- 1. Class IV - Accident sequences involving failure to SCRAM leading to a high pressure challenge to Containment resulting from power generation into the Containment. )
l C. Human Errors / Equivalent: ;
- 1. UH - Failure to control reactor level during an ATWS -
- 2. PSMSABCDXY - Failure to manuallyinitiate ATWS II. SfdfllABlQ.IVMMABY A. . Scenario Descriotion
- 1. Initial Conditions:
Reactor power is at 705 Complete EDG Operability Test No. 0187-01. No.11 SW Pump is out-of-service for packing replacement. When EDG testing is complete,
' increase Reactor power to 80% with recirc per C.2. Hold at 80% for Nuclear Engineer instructions.
- 2. Scenario Events:
a? Drywell CAM Trouble Alarm will annunciate.
- b. Comp;ete surveillance of No.11 EDG Operability Test.
- c. "C" Mainsteam Line Flow indicator will fail Downscale requiring I&C response.
, 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT l NIT-OP-TESTO4 i TITLE: LOSS OF NORMAL FEEDWATER WITH Revision 0 LOW POWER ATWS Page 2 of 12
- d. No.11 RBCCW Pump will trip and a failure of No.12 RBCCW Pump to Start will occur.
I
- e. No.12 4KV Bus will lockout from a fault resulting in a loss of No.12 RFP and No.
12 Recirc Pump placing the Plant in single loop operation.
- f. A spurious trip of No.11 RFP causes a Reactor SCRAM at +9 inches. All rods do not insert requiring an EOP ATWS 2007 entry. Control rods will drift into the Core when C.5-3101, Part C is performed. Some rods will need to be driven into the Core using RMCS.
- g. At -48 inches HPCI will fail to initiate. HPCI will function with the controller in Manual.
- 3. Termination Cues
- a. All control rods inserted to position 00. Reactor water level is being controlled using HPCI or RCIC +9 to +48 inches.
NOTE: Stable plant conditions are not possible in a reasonable amount of time. B. Scenario Objectives:
- 1. To evaluate the ability to operate the EDG during the conduct of routine surveillance test.
- 2. To evaluate the ability to increase Reactor power using Recirc Pump Speed Control.
- 3. A loss of RBCCW could result in potential equipment damage and require a Plant l Shutdown if actions are not initiated to restore closed cooling water.
- 4. Loss of 4160v Bus No.12 results in a loss of No.12 RFP and a loss of No.12 Recirc Pump. Actions must be initiated to reduce power and implement follow-up actions for the inpped pumps.
- 5. A trip of the remaining RFP will require implementation of the EOPs for decreasing Reactor water level and a failure to SCRAM condition. A SCRAM with a failure of all rods to insert is a situation which could quickly jeopardize Primary Containment if immediate actions to mitigate are not taken.
- 6. Manually controlling HPCI requires the operator to diagnose the injection failure and implement actions to maintain water level as directed by the EOPs.
Ill. SCENARIO CREATION A. Initial Conditions
- 1. IC-174 B. Manual Settino Summarv
- 1. SECURE Card on No.11 Service Water Pump.
1/cmb
r [. . MONTICELLO NUCLEAR GENERATING PLANT l NIT-OP-TEST 04 l TITLE: LOSS OF NORMAL FEEDWATER WITH Revision 0 LOW POWER ATWS Page 3 of 12 C. Event Triacer 1
- 1. None !
l ? l D. Procedures /Surveillances
- 1. No.11 EDG Operability Test No. 0187-01. Continue at STEP 59.
1 \ l l l 1
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1/cmb
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MONTICELLO NUCLEAR GENERATING PLANT Rcvision 0 l ' Page 12 of 12 SHIFT TURNOVER INFORMATION Reactor power is 70% Complete EDG Operability Test No. 0187-01. (PMT for work done on the EDG Air Start System.) (Required steps are complete through STEP 58.) Complete EDG surveillance test, then increase Reactor power to 80% per C.2 (POWER OPERATIONS). Hold power at 80% per Nuclear Engineer. l l l l h a 1/cmb
ae MONTICELLO NUCLEAR GENERATING PLANT 3139 1 TITLE: CONTROL ROOM SHIFT TURNOVER CHECKLIST Revision 23 l Page 1 of 2 1 Shift Manager. W 4lr\( N Q Date: TD A/Af / uf Shift: 07d 0 - /9 0 0 Completed By: sg N i / Reviewed By: Shift Supv.: )/WP LPEO: 36//( PEO: >tW X. Others: Mode Switch Shutdown Startup g / 2 'I4 Refuel MWT Core Thermal Power 5 Nominal 177ti MWT Core Flow 5 57.6 + 1 (Inst error) x 10'Lb/Hr
- 21. (, /10 ' Lb/Hr Core /Rx Dp 518.6 / 5 27 PSID
~7 , o /96 PSID j Rx Pressure 51008 +20 PSIG 9 '19 PSIG i Rx Level +30 to +40 INCHES indicated 7.5 INCHES Torus Level -2" to +2" o INCHES RCPDp 5143 PSID _'h / ~? D_ PSID Steam Flow 5 7.20 + .25 (Inst Error) x 10'Lb/Hr d/. CL v i 0 k Lb/Hr .
FW Flow < 7.20 + .25 Inst Error) X 10'Lb/Hr 4/.W n d Lb/Hr I
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$UAURO2$EFCOjf,37h@~.MGtj,dGZSi&Q2:d6dj2dW6GICMISCO jd,72 Source Supplying: 1R 1AR EDGs is a Manual 2R/1R Transfe quired prior to taking generator off line? Yes 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: 99 -/ '/ 76 I OPER l SR:/\ K Frea: 'O krs.
~ADMINISTRATIVF-X Reso Suov- OPER W/# I Assoc Ref:
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\ MONTICELLO NUCLEAR GENERATING PLANT 3140 1 TITLE: SHIFT SUPERVISORS OFFICE TURNOVER Revision 14 l CHECKLIST Page 2 of 2 Shift Mgr: xu( Shift Supv: xxxx (Circle items where applicable) Completed By: 74 6.w Wo Date: ere a ta w G Shift: 0700-1900
- 1. Unit status: Power level 70 96 MWT /M G MWE WQ
- 2. Any Surveillance Tests in progress now? NO l If YES, Numbers: O/P7-0( 6AwpGle -M+o$A % % 58
- 3. List Surveillance Tests scheduled for next shift: ,
Numbers: 1216-1.
- 4. Any infrequent Test or Evolution (as defined in 4 awl-04.05.07) in progress? YES If YES, state Test or Evolution if YES, on-coming Shift Manager SHALL ensure that on-coming crew is briefed by the Senior Line Manager responsible for the Test or Evolution, prior to tumover using the same Form 3560 that was used for the previous crew.
- 5. Any limiting conditions for operation? h NO (List,if YES)
- a. W }( E D (.>---
b. I
- 6. System deviations from normal during shift:
- a. # // 8 DG 00eral.-\< b -lf8 oU ip vw rer/
- b. 0 // X L d int A isc k W A t pnet,'5 c.es(me n d-.
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- 7. Any_new memos or instructions issued? YES (if YES, then list or attach copy) a.
b.
- 8. On-coming shift review the following and sign below;
- a. Shift tumover checklist f. WRAs/OCDs in progress
- b. Equipment status sheet g. Shift Supv log
- c. Active jumper /byass log h. Controlled key log
- d. Night order book 1. SS/SM controlled key rings received
- e. New memos / instructions Shift Manager: Date:
Shift Supervisor: Date: 1/ pdc 't . l .;t '; r '
r INITIAL SUBMITTAL OF THE WRITTEN EXAMINATION FOR THE l MONTICELLO EXAMINATION - THE WEEK OF AUGUST 23,1999
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l I-1 l l l J
Monticello Nuclear Generating Plant August 1999 RO Exam l l 1 ! l Written Exam Answer Key l l l l
1 1999 INITIAL NRC RO LICENSE EXAM ANSWER KEY Name: Date: 1 C 21 B 41 D 61 D 81 D 2 D 22 C 42 B 62 B 82 8 3 D 23 8 43 B 63 C 83 C 4 A 24 A 44 D 64 B 84 D 5 A 25 B 45 A 65 A 85 B 6 B 26 C 46 D 66 C 86 B 7 C 27 B 47 D 67 C 87 B 8 D 28 8 48 8 68 B 88 A 9 A 29 8 49 B 69 C 89 D _ 10 B 30 D 50 C 70 D 90 B 1 11 D 31 A 51 B 71 C 91 C ._ 12 B 32 A 52 D 72 A 92 C 13 A 33 C 53 C 73 C 93 A 14 A 34 C 54 B 74 A 94 B 15 D 35 B 55 D 75 D 95 C 16 C 36 D 56 A 76 B 96 A 17 D 37 D 57 A 77 D 97 C 18 B 38 C 58 A 78 A 98 C 19 A 39 C 59 D 79 B 99 D 20 C 40 C 60 C 80 A 100 A
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~IONTICELLO A NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 1 of 127 APPLICANT INFORMATION l
NAM 5: DATE: l REGION: 111 LIC. LEVEL: RO RX TYPE: BWR
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l START TIME: FINISH TIME: INSTRUCTIONS: Use the answer sheets provided to document your answers. Each question has only one cor- l l rect answer. Staple this cover sheet on top of the answer sheets. Points for each question are l Indicated in the Exam Number Question bar for each question. The passing grade requires a i i final grade of at least 80 percent. Examination papers will be picked up four (4) hours after the ) examination starts. All work done on this examination is my own. I have neither given nor received aid. l APPLICANT'S SIGNATURE: 1 Examination Value: 100 Points Applicant's Score: Points Applicant's Grade: Points Prepared By:gy //J g - Reviewed By: g4 v Approved By: Effective Date: 1 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 ' LICENSE EXAMINATION - ANSWER KEY Page 2 cf 127 l Exam Question Number: 1 Point Value: 1.00 Time (Minutes): NA During a Reactor SCRAM what causes the SCRAM Discharge Volume Vent and Drain Valves to Close? A. The 125 VDC Battery de-energizes solenoid valves to Open the backup SCRAM valves which also Close the SDV vents and drains. B. The 125 VDC Battery energizes solenoid valves to Open the backup SCRAM valves which also Close the SDV vents and drains. C. The RPS power supply de-energizes solenoid valves to Close the SDV vents and drains. D. The RPS power supply energizes solenoid valves to Close the SDV vents and drains. Answer: C Question No.: 1-B.01.03-027 Reference (s): B.1.3-01 K/A
Reference:
201001 Task Number: A1.05 Rating RO/SRO: 3.5/3.4 Monticello JTA: CR201.033 Objective (s): M-8107L-020 EO-13 I i 1/cmb I
/- MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 4 of 127 l Exam Question Numbe3~ Point Value: 1.00 Time (Minutes): NA During a Reactor startup there are several reactivity concerns associated with the Control Rod Drive System. When are continuous rod withdrawals allowed? Continuous control rod withdrawal are allowed... A. on a hi-lighted control rod that is to be k.ncd from position 12 to 48, while power is on the SRMs. B. any time the average SRM count rate is less than 1500 cpm. C. any time the SRM period meters indicate a stable period less than 100 seconds. I D. after Reactor power is on the IRMs at range seven or above. Answer: D 1 Question No.: 1-C.01-028 Reference (s): C.1 Startup Procedures K/A
Reference:
201002 Task Number: K4.05 Rating RO/SRO: 3.3 ; Monticello JTA: CR201.011 Objective (s): M-8107L-032, EO-4 M-8113L-001, EO-1 l I/cmb l l l
1 MONTl5ELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 5 of 127 i [ Exam Question Number: 3 Point Value: 1.00 Time (Minutes): NA l While on duty in the Control Room a loss of 4160 KV Bus 16 occurs. While walking down the Janels during your follow-up actions, you notice Alarm 8-A-9 (Y-20 INSTRUMENT AC JNDERVOLTAGE) is flashing slowly. l Which of the following would be a concern that would require operator action, if a Reactor l l SCRAM occurs? A. There is a loss of CRD flow control. B. The plant paging system would not function. C. You are unable to drive the SRM and IRMs in. D. The Recirc Scoop Tubes would be locked. l l Answer; D Question No.: 1-C.4.B.09-009 Reference (s): C.4-B.09.13.B K/A
Reference:
202002 Task Number: K4.06 Rating RO/SRO: 3.1 Monticello JTA: CR202.013 Objective (s): M-8107L-029, EO-9 1/cmb I l
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Redsion 0 LICENSE EXAMINATION - ANSWER KEY Pa;;e 6 of 127 l Exam Question Number: 4 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions: a Reactor Scram initiated from 100% power due to a loss of offsite power. Both HPCI and RCIC failed to inject. No.12 EDG is providing power to No.16 Bus. All other 4160 busses are dead.
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No.12 Core Spray pump failed to start. No.12 and No.14 RHR pumps are injecting to the vessel. Three (3) ADS valves are Open. Reactor pressure is 200 psig and decreasing. Reactor level is -110 inches and increasing, i Per the EOPs (C.5.1100) what is the status of the core for the above conditions? Core cooling... A. is assured due to the core being submerged. B. is assured due to the steam cooling effects of three (3) Open SRVs. C. is not assured due to Reactor level being near the top of active fuel. D. is not assured due to only two LPCI pumps injecting. l Answer. A 1 Question No.: 1-C.05.01 -1000-002 i Reference (s): C.05.01-1100 j K/A
Reference:
203000 ( l Task Number: K5.02 l Rating RO/SRO: 3.5 Monticello JTA: CR304.002 Objective (s): M-8114L-005. EO 2,3 l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 7 of 127 l l Exam Question Number: 5 Point Value: 1.00 Time (Minutes): NA If a loss of normal off-site power occurs coincident with an ECCS signal, there are time delays that go into effect for ECCS equipment. How long will it be from the time that all normal off-site power is lost until the Core Spray System receives a Start Signal? No.11 and No.12 Core Spray Pumps will Auto Start... A. 25 seconds after the loss of power event. B. 20 seconds after the loss of power event. C. 15 seconds after the loss of power event. D. 10 seconds after the loss of power event. Answer: A Question No.: 1-B.03.04-031 Reference (s): B.03.04-02 (Page 7 of 18) K/A
Reference:
203000 Task Number: K6.01 Rating RO/SRO: 3.6 Monticello JTA: CR209.007 Objective (s): M-8107L-005, EO-4 1/cmb
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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 8 of 127 l Exam Question Number: 6 Point Value: 1.00 Time (Minutes): NA During the conduct of the quarterly HPCI surveillance test, the HPCI CST Suction Valve MO 2063 is stroked Closed to measure closing and opening times. HPCI receives an initiation signal while MO-2063 was stroking closed. l Choose the correct answer. A. HPCI will start and will automatically realign suction to the Torus, if MO-2063 is closed. i B. HPCI will start but may trip on low suction pressure that should clear when MO-2063 l automatical!y strokes open. I C. HPCI will fail to start until MO-2063 is given an open signal. l l D. HPCI will need to be manually initiated if needed following manual restoration of MO-2063 l to full open. Answer: B Question No.: 1-B.03.02-024 Reference (s): B.03.02.01 K/A
Reference:
206000 Task Number: K1.05 Rating RO/SRO: 3.7 Monticello JTA: CR206.003 Objective (s): M-8107L-002, EO-4, 7 t/cmb
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/ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 9 of 127 ,
lE.xam Question Number: 7 Point Value: 1.00 Time (Minutes): NA During HPCl operation, Turbine speeds are maintained to prevent damage to HPCI equipment. Which of the following represents the Turbine speeds that the operator must be aware of during l HPCI operations? A. Speeds less than 3900 rpm and greater than 4500 rpm l B. Speeds less than 3900 rpm and greater than 5000 rpm C. Speeds less than 2150 rpm and greater than 5000 rpm D. Speeds less than 2150 rpm and greater than 3900 rpm I Answer: C Ouestion No.: 1-B.03.02-025 Reference (s): B.03.02-01 B.03.02-05 K/A
Reference:
206000 Task Number: A3.01 Rating RO/SRO: 3.6 Monticello JTA: CR206.003 Objective (s): M-8107L-002, EO-8 l l/cmb
l l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 10 of 127 I l l Exam Question Number: 8 Point Value: 1.00 Time (Minutes): NA l The plant is operating at 100% power when there is an event that causes the MSIVs to close and initiates a Reactor SCRAM. 1 Concerning the system relationshi3 between the Automatic Depressurization System (ADS) and ) ! the Core Spray System, which of t1e following describes what will happen if the ADS logic fails to I initiate the blowdown? (All conditions for an ADS initiation have been met.) l A. The Core Spray Pumps will be prevented from starting due to the ADS logic not being available. I B. The Core Spray Pumps will Automatically Start when their ECCS signal is satisfied but will not inject due to the ADS logic not allowing the injection valves to Open. C. The Core Sp, ray Pumps will Automatically Start when their ECCS signal is satisfied and immediately inject into the Reactor due to the loss of the ADS logic. D. The Core Spray Pumps will Automatically Start when their ECCS signalis satisfied and will inject when an alternate means of depressurization is used. l l Answer: D l Question No.: 1-B.03.03-017 Reference (s): B.3.3-01 l K/A
Reference:
209001 1 1 Task Number: K6.11 Rating RO/SRO: 3.6/3.7 Monticello JTA: CR209.007, CR218.003 Objective (s): M8107L-005, M8107L-025 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 12 of 127 j l l Exam Question Number: 9 Point Value: 1.00 Time (Minutes): NA The plant has just returned to full power following a 40-day outage. The following conditions apply: l
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l 100% power was achieved approximately 7 hours ago. Outplant operators have begun the SBLC Quarterly Surveillance Test. 3D Monicore indicates MWT @ 1772. l Soon after receiving a call that No.11 SBLC Pump has been started per test instructions, you notice Reactor power has decreased. Each time 3D Monicore updates Reactor thermal power, you have to increase recirc speed in small, incremental increases to maintain Reactor power at l 100 %. l l Which of the following explains why Reactor power is decreasing? A. The natural buildup of Xenon. l B. SBLC Squib Valves can leak while in test lineup. C. Recirc speed control scoop tube positioner is hunting. l D. Recirc oil temperature is decreasing. Answer: A 1 I Question No.: 1-B.03.05-022 Reference (s): B.03.05-02 (Page 6 of 7) K/A
Reference:
211000 Task Number: K4.01 Rating RO/SRO: 3.1 l Monticello JTA: CR211.007 Objective (s): M-8107L-004, EO-7,8,13 j 1/cmb 1
l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 13 of 127 l l Exam Question Number: 10 Point Value: 1.00 Time (Minutes): NA Given the following Standby Liquid Control (SBLC) Tank parameters: Boron concentration is 12.1% (wt%).
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Boron Tank levelis 1200 gallons.
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Boron Tank temperature is 70* F. Using the above parameters, what is the status of the SBLC System? A. Inoperable due to Boron concentration being too low for any tank volume. l B. Inoperable due to Boron concentration being too low for the tank volume listed above. C. Inoperable due to tank temperature being too low for the Boron concentration. i l D. Operable for the above conditions. l i Answer: B PROVIDE FIGURES 3.4-1 AND 3.4-2 FROM TECH SPEC 3.4 FOR THE EXAM. 1 Question No.: l-TS-045 Reference (s): Tech Spec 3.4, Figure 3.4-1 and Figure 3.4-2 K/A
Reference:
211000 Task Number: A4.01 Rating RO/SRO: 3.9/3.9 Monticello JTA: CR211.007, CR999.004 Objective (s): M8107L-004 EO-10 1/cmb
[- l MONTICELLO NUCLEAR GENERATING PLANT M89000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 15 of 127 l l Exam Question Number: 12 Point Value: 1.00 Tme (Minutes): NA The plant is operating at 100% power when one of the electrical protection assemblies for the #12 RPS MG set inadvertently trips open. Choose the correct answer. A. The Reactor will SCRAM due to the failure of the Scram Discharge Volume level switches. B. Reactor power Indication on APRMs 4,5, and 6 will be lost. C. IRM power will be lost requiring associated APRMs to be declared inoperable. D. Power will automatically transfer to the RPS alternate source. Answer: B ! Question No.: 1-B.09.12-009 Reference (s): B.09.12-06, Figure 1 B.05.01.02-05 K/A
Reference:
212000 Task Number: K3.04 Rating RO/SRO: 3.5 Monticello JTA- CR212.006 Objective (s): M-8107L-043, EO-5 l
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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 16 of 127 l Exam Question Number: 13 Point Value: 1.00 Time (Minutes): NA Given:
. The plant is in cold shutdown.
. The SRM Shorting links are all removed.
- AllIRMs are on range 1.
Mode switch is in refuel
. IRM 12 fails downscale.
. IRM 14 fails upscale.
What is the status of RPS? A. There is a full SCRAM signal from RPS. B. There is a half SCRAM signal on the A channel of RPS.
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C. There is a half SCRAM signal on the B channel of RPS. D. There is no SCRAM signal from RPS. Answer: A Question No.: 1-B.05.06-029
References:
B.5.06-02 K/A
Reference:
215003 Task Number: A1.05 Rating RO/SRO: 3.9/3.9 Monticello JTA: CR215.037 Objective (s): M8107L-064 EO-6 1/cmb x
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 \ TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 i LICENSE EXAMINATION - ANSWER KEY Page 17 of 127 i l l Exam Question Number: 14 Point Value: 1.00 Time (Minutes): NA 1 Choose the correct answer regarding the SRM System Detector Drive Control Pushbuttons. The Drive-In Pushbutton... A. is a seal-in button and only needs to be momentarily depressed. The Drive-Out Pushbutton is not a seal-in button and must be continuously depressed. B. is not a seal-in button and must be continuously depressed. The Drive-Out Pushbutton is a seal-in button and only needs to be momentarily depressed. C. is a seal-in button and only needs to be momentarily depressed. The Drive-Out Pushbutton is a seal-in button and only needs to be momentarily depressed. D. is not a seal-in button and must be continuously depressed. The Drive-Out Pushbutton is not a seal-in button and must be continuously depressed. Answer: A Question No.: 1-B.05.01.01 -040 Reference (s): B.S.01.1 -05 K/A
Reference:
215004 Task Number: A4.04 Rating RO/SRO: 3.2/3.2 Monticello JTA: CR215.011 Objective (s): M-8107L-054 EO-5,6 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 ( TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 i i LICENSE EXAMINATION - ANSWER KEY Page 19 of 127 l Exam Question Number: 15 Point Value: 1.00 Tme (Minutes): NA Given: Reactor Recirc Flow is 28.8 x 106 lb/hr l l . Both recirc pumps are running 57.6 x 10e Ib/hr is rated core flow What is the setpoint for the APRM Flow Biased SCRAM? l l A. 81.0% of rated thermal power l B. 84.6% of rated thermal power C. 95.0% of rated thermal power l D. 98.6% of rated thermal power i Answer: 1 D l l l l Question No.: 1-TS-044 Reference (s): Tech Spec 2.3 (FUEL CLADDING INTEGRITY) l K/A
Reference:
215005 l Task Number: K5.05 i Rating RO/SRO: 3.6/3.6 Monticello JTA: CR215.038 ; Objective (s): M-8107L-069 EO-3 l l \ i 1 1 1/cmb l
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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 21 of 127 l l Exam Question Number: 16 Point Value: 1.00 Time (Minutes): NA Operations Manual C.4-B.5.1.2.A " Control of Neutron Flux Oscillations"is entered during a rapid power reduction. The pressure control and recirculation control systems are operating normally. Which of the following is used as an indication of neutron flux oscillations? A. SPDS APRM readings fluctuate greater that 10% peak to peak. B. A LPRM Hi alarm combined with a LPRM DOWNSCALE alarm. C. APRM recorders indicate peak to peak oscillations greater than 10%. D. APRM HI or DOWNSCALE alarms come in then clear. enswer: C Question No.: 1-C.4.B.05-006 Reference (s): C.4-B.05.01.02.A i K/A
Reference:
216000 Task Number: A4.01 Rating RO/SRO: 3.3 ! Monticello JTA: CR999.011 Objective (s): M-8114L-002, EO-1 i I/cmb
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MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 22 of 127 l l Exam Question Number: 17 Point Value: 1.00 Time (Minutes): NA A loss of normal offsite power occurs. HPCI and RCIC Auto initiate and refill the Rx vessel to
+50" resulting in a Turbine trip. The following current conditions exist:
Low-Low Set is controlling Rx pressure. Rx water levelis slowly decreasing. No.15 and No.16 Busses are powered from their respective EDGs. No pressure boundary leakage has occurred. l Assuming no operator action and Reactor water level is allowed to decrease to the ECCS initiation setpoint, which of the following is correct? l A. MO-2080 (TRIP THROTTLE VALVE) will Auto OPEN and initiate the RCIC Turbine Ramp Generator. B. MO-2075 (RCIC INBOARD STEM SUPPLY) will Auto OPEN and initiate the RCIC Turbine i Ramp Generator. O. RCIC will not re-initiate unless the RCIC Initiation Logic Reset PB is depressed. l D. MO-2078 (STEAM SUPPLY VALVE) will Auto OPEN and initiate the RCIC Turbine Ramp l Generator. l l l l Answer: D l Question No.: 1-B.02.03-017 Reference (s): B.02.03-02, Pages 5 and 6 of 13 K/A
Reference:
217000 Task Number: A2.01 Rating RO/SRO: 3.8 Monticello JTA: CR217.007 Objective (s): M-8107L-003, EO-5 l/cmb l
'MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 33 of 127 l Exam Question Number: 27 Point Value: 1.00 Time (Minutes): NA Given the following:
Drywell pressure is 1.0 psig. Reactor levelis 35 inches.
"A" SBGT is isolated for maintenance.
"A" RPS MG Set is tripped.
What is the status of SBGTs? A. "B" Train starts immediately on the MG Set trip. B. "B" Train starts if low flow on "A" Train remains for more than 10 seconds. C. "B" Train starts if the Reactor Building pressure is not maintained negative. D. "B" Train remains in Standby with no initiation signal present. Answer: B Question No.: 1-B.04.02-021 Reference (s): B.04.02-01 B.05.11 -01 B.05.11 -05 K/A
Reference:
261000 Task Number: A3.01 Rating RO/SRO: 3.2 Monticello JTA: CR261.007 Objective (s): M8107L-008, EO-3,4,11 1/cmb I L
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 34 of 127 l Exam Question Number: 28 Point Value: 1.00 Time (Minutes): NA A loss of normal offisite power has occurred resulting in a No.15 and No.16 bus being supplied by the 1 AR Transformer. A leak on the Rx caused Drywell pressure to increase to >18 psig. Containment Spray was initiated per the EOPs. Using the following current conditions Drywell pressure < 2 psig. Rx level @ 35 inches.
. Rx pressure O psig.
All RHR pumps in service for Torus Cooling. No.11 Core Spray and No.12 Core Spray prevented per EOPs. Which of the following would be required by the operator to start No.11 CRD Pump? A. Shutdown No.11 EDG, then place No.11 CRD Pump Control Switch to START. B. Shutdown No.11 or No.13 RHR Pump, then place No.11 CRD Pump Contro! Switch to START. C. Depress the LPCI Loop Select Reset Pushbutton on C-03, then place No.11 CRD Pump Control Switch to START. D. Shutdown No.11 or No.13 RHR Pump, depress the LPCI Loop Select Reset Pushbutton on C-03, then place No.11 CRD Pump Control Switch to START. Answer: B Question No.: 1-B.09.06-035 Reference (s): B.09.06-01, Page 10 of 11 K/A
Reference:
264000 Task Number: K4.05 Rating RO/SRO: 3.2 Monticello JTA: CR201.001, CR999.011 Objective (s): M-8107L-020, EOM-4, 7,13 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC IW!TIAL REACTOR OPERATOR Revision 0 , LICENSE EXAMINATION - ANSWER KEY Page 35 of 127 i l Exam Question Number: 29 Point Value: 1.00 Time (Minutes): NA If the operator receives an indication that the rod is uncoupled, under certain plant conditions he is procedurally required to fully insert the control rod to 00 and electrically isolate the HCU.
- 1. What is the basis for inserting the rod to 00?
- 2. When is this required?
i Fully inserting the rod to 00... A. 1. prevents potential control rod drifting.
- 2. :s required when the Reactor is critical.
i B. 1. allows the rod to re-couple to the drive when the piston tube reaches the Full-In position. '
- 2. is required when the Reactor is critical. l C. 1. eliminates the possibility of a control rod drop accident for that rod.
- 2. is required when the Reactor is subcritical.
D. 1. allows an analysis to be performed.
- 2. is required when the Reactor is subcritical. l Answer:
B Question No.: 1-B.01.03-028 Reference (s): B.1.3-05 Tech Spec 03.03.B Bases K/A
Reference:
201003 Task Number: A2.02 Rating RO/SRO: 3.7 /3.8 Monticello JTA: CR201.017, CR201.021 Objective (s): M 8107L-032 EO-3, M-8107L-021 EO-1,8 1/cmb
- - \ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 36 of 127
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l Exam Question Number: 30 Point Value: 1.00 Tme (Mir.utes): NA The RWM will enforce an insert block'thereby preventing control rod insertion during low power operations. What is the primary purpose of imposing control rod insert blocks? A. To force the operator to Scram the Reactor if conducting rapid power reduction. B. To prevent the operator from inserting rods that may result in an inverse power response. ) C. To limit the rate that rods are inserted during normal shutdown thereby managing the negative reactivity inserted into the core. D. To maintain sequenced control rod insertions such that high worth rods are not created. 1 Answer: D Question No.: 1 B.05.02-035 Reference (s): B.05.02-01 K/A
Reference:
201006 Task Number: K5.13 Rating RO/SRO: 3.5 Monticello JTA: CR201.013 Objective (s): M-8107L-032, EO-1 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 37 of 127 l Exam Question Number: 31 Point Value: 1.00 Time (Minutes): NA The plant is operating at 100% power with RCIC isolated for on-line maintenance. The following events happened in chronological order: Both Main Feedwater Regulator Valves fail closed.
- Group 1 Isolation Valves close.
Low Low Set initiates. Eight (8) SRVs cycle open, limiting Rx pressure spike s 15 psig above SRV safety setpoint.
. Low Low set controls Rx pressure.
HPCI Auto Initiates.
- Rx Mode Switch placed in Shutdown.
Low pressure ECCS Pumps have not Auto initiated. Which of the following caused the Recirc MG Set field breaker to trip open? A. Low Low Rx level B. High Drywell pressure C. High Rx pressure D. Generator Lockout Answer: A Question No.: 1-B.01.04-047 Reference (s): B.01.04-02, Pages 12 and 13 of 14 K/A
Reference:
202001 Task Number: K2.02 Rating RO/SRO: 3.2 I Monticello JTA: CR202.013 Objective (s): M-8107L-029, EO-4 l l/cmb i
E I MONTICELLO NUCLEAR GENERATING PLANT M81000-99?3 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 38 of 127 l l Exam Question Number: 32 Point Value: 1.00 Time (Minutes): NA Which one of the following describes the effects on the Reactor water chemistry if there is a RWCU resin intrusion? l A. Increased sulfates, increased conductivity, and decreased pH. B. Decreased sulfates, decreased conductivity, and decreased pH. C. Increased sulfates, increased conductivity, and increased pH. D. Decreased sulfates, decreased conductivity, and increased pH. Answer: A Question No.: 1-B.02.02-021 Reference (s): B.2.2-05 . K/A
Reference:
204000 l Task Number: K1.10 Rating RO/SRO: 3.3/3.5 Monticello JTA: CR204.014 Objective (s): M-8107L-030 EO-8 l I/cmb
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l l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 I LICENSE EXAMINATION - ANSWER KEY Page 40 of 127 { Exam Question Number: 33 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions: Reactor is Shutdown with mode switch in Shutdown. Reactor water levelis 60 inches.
. Reactor vessel head is installed, l No.11 RHR Pump in Shutdown Cooling maintaining 120 degrees. I No.11 RHR Pump flow is 4000 gpm. 1 "B" Loop RHR is isolated and partially drained for leak rate testing.
Both Recirc pumps at minimum speed. If No.11 Bus trips open during 4160 VAC Breaker testing and cannot be immediately reset, which l of the following is correct? l Shutdown Cooling injection... A. must be immediately removed from service to prevent vessel stratification. B. into an idle recirc loop is allowed with System Engineer approval. C. flow must be maintained at rated conditions. D. into an idle loop is not allowed by Technical Specifications. Answer: C Question No.: 1-G.03 110 Reference (s): C.3.Vlil.1 K/A
Reference:
205000 Task Number: K6.03 P.ating RO/SRO: 3.1 l 1 Monticello JTA: CR205.031 Objective (s): M-8107L-023, EO-14,17 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINAT!ON - ANSWER KEY Page 41 of 127 l l l Exam Question Number: 34 Point Value: 1.00 Time (Minutes): NA l Under which of the followin position from Panel C-05? g conditions would an operator lose the ability to determine co 1 A. Loss of Y-30 ' B. Loss of Y-20 C. Loss ovY-10 D. Loss of RPS Busses A and B Answer: - C Question No.: 1-B.05.04-008 Reference (s): 8.05.04.-02, Page 6 of 6 C.4-B.09.13. A, Page 8 of 12 K/A
Reference:
214000 Task Number: A4.02 Rating RO/SRO: 3.8 Monticello JTA: CR214.003 Objective (s): M-8107L-058, EO-6 i I/cmb
F
)
l [ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 f LICENSE EXAMINATION - ANSWER KEY Page 42 of 127 l l Exam Question Number: 35 Point Value: 1.00 Time (Minutes): NA i The C.5-1100 (RPV CONTROL) level leg instructs the operator to use the RHR Heat Exchanger l as soon as possible when using LPCI for level control. 1 i Why is it important to use the heat exchanger when you are in the RPV Control portion of the EOPs? , 1 Injecting through the RHR Heat Exchanger as soon as possible... I A. minimizes head loss by providing the most direct flow path to the vessel. B. minimizes Torus heatup and prolongs the avaliability of the Torus as a heat sink. C. requires RHRSW be placed in service which maintains RHR Heat Exchanger dP. D. maximizes the cooldown to ensure that ECCS vortex limits are not exceeded. 1 i Answer: B Question No.: l-C.5-1100-001 Reference (s): C.5-1100 C.5.01 -1100 K/A
Reference:
219000 Task Number: A1.01 Rating RO/SRO: 4.0 /4.0 Monticello JTA: CR205.003 Objective (s): M-8107L-023, EO-14,16,17 l l 1 1 I/cmb I
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 44 of 127 l l Exam Question Number: 36 Point Value: 1.00 Time (Minutes): NA Following a small break LOCA, Plant conditions require Drywell Sprays be placed in service. The SS orders Drywell Sprays be removed from service when Drywell pressure drops below 2 psig. , What is the basis for removing Drywell Spray when Drywell pressure drops below 2 psig? A. To allow Drywell-to-Torus vacuum breakers to operate properly. B. To reduce the possibility of chugging in the downcomers. C. To avoid exceeding the Drywell Spray Limit. D. To ensure Primary Containment pressure will remain above atmospheric pressure. Answer: D Question No.: l-C.5-1200-001 Reference (s): C.5 EOP 1200,1200 Bases K/A
Reference:
226001 Task Number: K3.01 Rating RO/SRO: 3.6/3.7 Monticello JTA: CR304.010 Objective (s): M-8114L-005, EO-5,7 i l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 45 of 127 l Exam Question Number: 37 Point Value: 1.00 Time (Minutes): NA The Shift Supervisor has instructed you to re-open the MSIVs following a Group i isolation. Which of the following is a concern with outboard air pressure? Main air supply pressure must be greater than... A. 295 psig to assure the MSIVs w!!! close against steam line pressure dPs of 100 psig or greater. B. 255 psig to overcome the weight of the MSIV valve body disc. C. 295 psig to assure proper opening and closing times. D. 255 psig to assure sufficient pressure is available to prevent other MSIVs from drifting closed. i Answer: D 1 l Question No.: 1-B.02.04-015 { Reference (s): B-02.04-05 i K/A
Reference:
239001 Task Number: K4.09 Rating RO/SRO: 3.3 Monticello JTA: CR240.004 Objective (s): M-8107L-007, EO-2,6 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 46 of 127 l Exam Question Number: 38 Point Value: 1.00 Time (Minutes): NA Given the following conditions: Plant Startup is in progress. Reactor power is 30% No.11 Feedwater Pump is in service. No.11 and No.12 Feedwater Recirculation Flow Control Valves are in AUTO. Hotwelllevel 0 inches. If a trip of No.11 Feedwater Pump were to occur, which of the following valves would be open 30 seconds after the feedwater pump trip? A. The Condensate Demin Bypass Valve. B. The Reactor Feedwater Recirculation Valves. C. The Condensate Recirculation Valves. D. The Hotwell Reject Valve. i Answer: C Ouestion No.: 1-B.06.05-020 Reference (s): B.06.05-02 K/A
Reference:
256000 Task Number: K6.06 Rating RO/SRO: 3.3 Monticello JTA: CR259.021 Objective (s): M-8107L-068, EO-3 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 ( LICENSE EXAMINATION - ANSWER KEY Page 47 of 127 l Exam Question Number: 39 Point Value: 1.00 Time (Minutes): NA l Which of the following is a concern while operating an Emergency Diesel Generator in parallel with the AC Distribution System? l i A. Circulating currents develop within the generator windings due to the voltage differences between the system (345KV) and the EDG output (4160VAC). B. During this time the EDG operates in a high voltage low load condition resulting in an increased carbon buildup within the engine. C. A system disturbance could cause an overspeed trip when the output breaker opens. The EDG would not be immediately available if a Station Blackout would occur. D. During this time the EDG is operated at normal speeds and loads aie above 50%. The EDG Turbocharger operating life is significantly reduced as a result of this type of operation. Answer: C i Question No.: 1-B.09.08-047 Reference (s): 1-8.09.08-05, Page 5 of 52 K/A
Reference:
262001 Task Number: K1.01 Rating RO/SRO: 3.8 Monticello JTA: CR264.003 Objective (s): M-8107L-042, EO-2,4 I/cmb , I
- = -
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 i LICENSE EXAMINATION - ANSWER KEY Page 48 of 127 l Exam Question Number: 40 Point Value: 1.00 Eme (Minutes): NA l A fault on the Uninterru atible AC System resulted in a low output voltage (108V) on Y-71. The static switch transferrec to the alternate load. How does the Uninterruptible AC System respond following the automatic transfer to the alternate power source? A. The Inverter will remain lined up to the alternate until it is manually transferred back to the normal source. B. The Inverter will ramp power to the 150% current limit for about 30 seconds and then ramp i down to 125% current. C. The static switch will automatically transfer back to the normal source once the fault has been cleared. D. The static switch will remain lined up to the alternate; the Inverter will go into the ZIP mode. l 1 Answer: C Question No.: 1-B.09.13-012 Reference (s): B.09.13-01 1 K/A
Reference:
262002 l ! Task Number: K4.01 i Rating RO/SRO: 3.1 /3.4 Monticello JTA: CR262.006 ' Objective (s): M-8107L-063, EO-2 l l l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 50 of 127 l Exam Question Number: 41 Point Value: 1.00 Time (Minutes): NA l What is an effect of a complete loss of Div II,250 VDC Distribution Panel, D-100? A. RWCU pumps will trip. B. RCIC will be inoperable. C. MCC D313 willloss power. I D. HPCI will be inoperable. I Answer: ; D Question No.: 1-B.09.09-007 Reference (s): B.9.9-06, Figures 1 and 2 K/A
Reference:
263000 Task Number: K2.01 Rating RO/SRO: 3.1 /3.4 Monticello JTA: CR206.003 i Objective (s): M8107L-002 EO-5 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 52 of 127 l Exam Question Number: 42 Point Value: 1.00 Time (Minutes): NA Using the following conditions: MCC 125 is isolated to investigate a ground.
. Rx power is 100%
No.11 and No.12 Circulating Water Pumps are in service.
"B" Recombiner is in Operate.
A lockout on Load Center 101 occurs. For the above conditions, what would be a reason for a loss of condenser vacuum? A. Loss of Y-25 would result in a trip of the operating recombiner. B. Loss of Y-26 would result in a trip of the operating recombiner. C. Loss of MCC-116 would result in a loss of excitation to No.12 Circulating Water Pump. D. Loss of MCC 116 would de-energize the r,olenoids for the air ejector suction valves. These valves fail Closed. Answer: B Question No.: 1-C.4.B.09-010 Reference (s): C.4-B.09.13.0 C.4-B.09.13.D C.4-B.09.07.A K/A
Reference:
271000 Task Number: K3.01 I Rating RO/SRO: 3.5 Monticello JTA: CR262.006 Objective (s): M-8107L-063, EO-6 1/cmb 1
1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: '1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 53 of 127 i l Exam Question Number: 43 Point Value: 1.00 Time (Minutes): NA During a test of the Process Radiation Monitor (PRM) system a high level trip is in, for the test, on channel A of the Steam Jet Air Ejector (Off-Gas) Monitor. l What are the automatic actions, related to the PRM system, that occur if there is a loss of RPS MG Set B concurrently with the test? A. SJAE AUTO ISOLATION TRIP alarms and the Steam Jet Air Ejector suction valves go closed after a 5 second time delay. B. OFF-GAS TIMER ACTUATED alarms are received and the recombiners will trip after a thirty minute time delay. C. There are no automatic actions due to an One-Out-of-Two Taken Twice logic scheme not being satisfied. D. A Group I isolation will occur with a trip of the MVP and an isolation of the MVP suction l valves. i i Answer: B Ouestion No.: 1-B.05.11 -038 Reference (s): B.5.11 -02 K/A
Reference:
272000 Task Number: K4.03 l Rating RO/SRO: 3.6/3.9 Monticello JTA: CR273.004, CR271.007 Objective (s): M-8107L-077 EO-4, M-8107L-091 EO-11 1/cmb i
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 55 of 127 l Exam Question Number: 44 Point Value: 1.00 Time (Minutes): NA An On-Duty Operator inadvertently depresses the Turbine Building siding deluge initiation button on C-20. Which of the following is correct? The clapper valve is open causing a decrease in Fire System pressure which will result in the... A. Diesel Fire Pump Auto Starting at 70 psig, and flow through the spray nonle will begin when the fusible links melt. B. Electric Fire Pump Auto Starting at 70 psig and flow through the spray nonle will begin when the fusible links melt. C. Diesel Fire Pump Auto Starting at 80 psig and flow through the nonle will begin when sufficient air pressure develops in the HAD. D. Electric Fire Pump Auto Starting at 80 psig and flow through the nonles will begin immediately. Answer: D 1 I Question No.: 1-B.08.05-016 Reference (s): B.08.05-01, Pgs 5,6, and 11 of 20 K/A
Reference:
286000 Task Number: A3.04 Rating RO/SRO: 3.2 Monticello JTA: CR286.005 Objective (s): M-8107L-010, EO-4 l/cmb l
MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 { TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 56 of 127 l i Exam Question Number: 45 Point Value: 1.00 Time (Minutes): NA A train derailment has occurred by SHERCO and the resultant gas plume has drifted over the Monticello Plant. The operators have implemented C.4-J l EVENT) and the proper A-Manual procedures. Two (2) ho(OPERATIONS DURING A TOX urs into the event a team is preparing to start changing out air supply bottles for the Control Room Air Supply System. What does the team need to consider before leaving the Control Room? The team SHALL... A. don protective gear (i.e., SCBA and chemical suit) before exiting the Control Room into an unknown environment. B. wait until the Low-Low Alarm for low air pressure is received before leaving the Control Room with an unknown atmosphere present. C. have at least four people on the team, one for each bottle being replaced. D. wait until the SCBA tanks are in alarm before proceeding to change out the Control Room Air Supply bottles. Answer: A Question No.: 1-C.4.J-001 Reference (s): C.4-J K/A
Reference:
290003 Task Number: A2.02 Rating RO/SRO: 3.1/3.4 Monticello JTA: CR999.011 Objective (s): M-8114L-004, EO-1 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 57 of 127 Exam Question Number: 46 Point Value: 1.00 Time (Minutes): NA During maintenance activities a smallinstrument air line supplying the Main Feedwater Reg Valves was severed. Which of the following is correct? The Feedwater Regulator Valves will fail... A. OPEN and may drift CLOSED. B. CLOSED and may drift OPEN. C. CLOSED until the Master Flow Control Station is placed in MANUAL. D. AS IS and may drift in either direction. Answer: l D i Question No.: l-C.4.B.08-004 Reference (s): C.4-B.08.04.01.A C.4-B.05.07.A K/A
Reference:
30000 Task Number: K3.02 Rating RO/SRO: 3.3 Monticello JTA: CR259.017 Objective (s): M-8107L-046, EO-3 1/cmb
l I l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 58 of 127 l [ Exam Question Number: 47 Point Value: 1.00 Time (Minutes): NA l The plant is operating at 100% normal operation. The following alarms are received in the l Control Room: j 4-B-5 (RECIRC PUMP A LOW COOL WATER FLOW) 4-B-10 (RECIRC PUMP B LOW COOL WATER FLOW) 6-B-32 (RCT BLDG CLG WTR LOW DISCH PRESS) l The operator cannot start either RBCCW Pump. Which of the following is a required action by the operator? A. Trip both Recirc Pumps and insert a Reactor Manual SCRAM. l B. Trip the CRD Pumps if RBCCW flow is not restored in 60 seconds. C. Monitor Fuel Pool Cooling filter outlet temperature and trip the pumps if the temperature l exceeds 1500F. I D. Close RBCCW Drywell isolation Valves MO-1426, MO-4229, and MO-4230. l i Answer: D l Question No.: 1-C.4.B.02-010 Reference (s): C.4-B.2.5.A K/A
Reference:
400000 Task Number: A2.01 Rating RO/SRO: 3.3/3.4 Monticello JTA: CR999.011 1 Objective (s): M-8114L-002, EO-1 1/cmb { l
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 ~ TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 60 of 127 l l Exam Question Number: 48 Point Value: 1.00 Time (Minutes): NA l With a complete loss of RBCCW, the fuel pool starts to heat up. Which of the following is a proper action for this plant condition? A. Place both fuel pool pumps in service so that RHR Heat Exchangers can be lined up. B. Place available fuel pool pumps in service to mix the pool and prevent thermal stratification. l C. Place both filter demins in service to ensure that the fuel pool water chemistry stays in I specs. D. Discharge water to the Condenser Hotwell and then makeup water from the CSTs. Answer: B Question No.: 1-B.02.01 -013 Reference (s): B.02.01 -05 K/A
Reference:
233000 Task Number: Al.03 l Rating RO/SRO: 3.1/3.3 1 Monticello JTA: CR999.011, NL233.011 Objective (s): M8107L-022 EO-2,4,5 1 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 \ TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 62 of 127 l Exam Question Number: 49 Point Value: 1.00 Time (Minutes): NA l Which of the following will place a control rod withdraw block on the Reactor Manual Control System? l A. The Bridge is over the fuel pool with the main grapple lowering a fuel bundle into a fuel pool storage rack. B. The Bridge is over the core, the grapples are all full up, and the Bridge is moving a fuel bundle towards the fuel pool. ; C. The Bridge is over the core, all grapples are full up, and nothing is loaded on any of the grapples. D. The Bridge is over the core, only the frame mounted hoist is not full up, and nothing is loaded on any of the grapples. l l Answer: B l Question No.: 1-B.05.05-020 Reference (s): B.S.5-06 K/A
Reference:
234000 Task Number: K1.04 Rating RO/SRO: 3.3/3.6 Monticello JTA: CR234.017 Objective (s): M8107L-019 EO-7 1/cmb
r MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 63 of 127 I l Exam Question Number: 50 Point Value: 1.00 Time (Minutes): NA Due to an error in a surveillance the plant has had a Group ll Isolation. The cause of the isolation i has been identified and rectified. The operators are in the process of resetting the Group 11 isolation. Which of the following fans automatically start when the isolation reset pushbuttons are d: pressed? A. V-FU-5 RWCU Pump Area Filter Unit B. V-MZ-1 Turb Bldg 951' NW H&V Unit (Supply to 4KV Areas) C. V-EF-28 Reactor Building Fuel Pool Exhaust Fan D.- V-EF-26 SJAE and Pipe Tunnel Exhaust Fan Answer: 1 C Question No.: 1-C.4.B.04-008 Raference(s): C.4-B.4.1.B K/A
Reference:
288000 Task Number: K4.02 Rating RO/SRO: 3.7/3.8 Monticello JTA: CR999.011 Objective (s): M8114L-002 EO-1,2 l 1/cmb l L
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 65 of 127 Exam Question Number: 51 Point Value: 1.00 Time (Minutes): NA Which of the following is a Safety Limit Violation? i A. Steam dome pressure reaches 1300 psig for a hydrostatic test during cold shutdown. B. MCPR reaches 1.08 during a loss of feedwater heating transient from full power. C. Reactor mode switch is placed in RUN with steam dome pressure at 0 psig. D. Indicated RPV water level drops to -20 inches on the Core Flooding Level Instrument during Refueling. 1 Answer: l 8 PROVIDE FIGURE 17 FROM B.01.01-06.02 WITH EXAM. Question No.: l-TS-047 l l Reference (s): Tech Spec 2.0 l K/A
Reference:
290002 Task Number: K5.07 Rating RO/SRO: 3.9 Monticello JTA: CR999.004 Objective (s): M-8108L-003, EO-3, 4 1/cmb
l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 66 of 127 l Exam Question Number: 52 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions: Reactor at 100% power Site Power from 2R Transformer 8N11 GCB open Sudden pressure relays cause a main generator lockout (286/G) to occur. For the above conditions, which of the following is correct? A. Knife Switch 16/C31 needs to be opened in order to prevent a trip of the circulating water pumps when 8N4 and 8N5 are opened. , B. 8N4 and 8N5 will automatically trip open when the main generator output reaches 0 MWe, C. Site power needs to be manually transferred from the 2R Transformer to the 1R Transformer to ensure that the recirculation pumps remain running. D. An automatic transfer from 2R Transformer to the 1R Transformer will have occurred due to the loss of 345kv Bus 1. Answer: D Question No.: 1-C.4.A-022 Reference (s): C.4.A (REACTOR SCRAM B.09.02-02 B.09.06-01 K/A
Reference:
295005 Task Number: AK3.06 Rating RO/$RO: 3.3 Monticello JTA: CR262,006 Objective (s): M-8107L-036, EO-4,9 1/cmb
I l MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 67 of 127 l Exam Question Number: 53 Point Value: 1.00 Time (Minutes): NA The plant is operating at 100% power with feed water level control in manual. A Turbine trip causes a Reactor SCRAM. The operators initiate C.4-A Reactor SCRAM procedure and begin to follow their required actions. How does water level respond immediately following the Reactor l SCRAM? A. Actual water level floods the steam lines due to increased feed water flow. B. Actual water level decreases due to the loss of recirculation flow. l l C. Indicated water level decreases due to the collapse of voids. l l D. Indicated water level increases to above the high water level alarm. ! . I l Answer: C Ouestion No.: 1-C.4.A-020 Reference (s): C.4-A Bases 1 K/A
Reference:
295006 Task Number: AA2.03 Rating RO/SRO: 4.0/4.2 i y j Monticello JTA: CR999.011 Objective (s): M-8114L-001 EO-3 l l l l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 69 of 127 l Exam Question Number: 54 Point Value: 1.00 Time (Minutes): NA Using the following information: All SCRAM signals are bypassed per C.5-3101 (ALTERNATE ROD INSERTION) 4
. Group I isolation Valves CLOSED RPS Busses A and B amber lights ON
. Rx power ~ 30%
Rx water level- 55 inches Which of the following is correct? A. Low-Low Set will actuate and control Reactor pressure. l B. Rapid cycling of relief valves will occur and operability of the SRVs will be challenged. C. Turbine Bypass Valves and Low-Low Set will control Reactor pressure. D. Turbine will use available steam maintaining relief and bypass valves CLOSED. Answer: B Ouestion No.: 1-C.05.01-2000-003 Reference (s): C.05.01-2007, Page 46 of 64 K/A
Reference:
295007 Task Number: AA1.04 Rating RO/SRO: 3.9 Monticello JTA: CR314.006 Objective (s): M-8114L-005, EO-7 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 70 of 127 Exam Question Number: 55 Point Value: 1.00 Time (Minutes): NA Using the following information: Reactor power 4% MSIVs closed Feedwater Level Control in Manual Reactor water level at 0 inches indicated and increasing 1 inch / minute Reactor pressure 982 psig Low-Low set controlling pressure if water level is increasing at a rate of 1 inch / minute and 12 minutes later "H" relief valve c aens for 1 minute and then closes, which of the following is an expected level indication after the S7V closes? (Assume no operator action.) A. +12 inches B. +8 inches C. -12 inches D. -8 inches Answer: D Question No.: 1-B.03.03-019 Reference (s): B.03.03-05 K/A
Reference:
295009 Task Number: AK2.02 Rating RO/SRO: 3.9 Monticello JTA: CR259.017, CR218.004 Objective (s): M-8107L-025, EO-10 I I/cmb i
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 71 of 127 l Exam Question Number: 56 Point Value: 1.00 Time (Minutes): NA Using the following information: Rx SCRAM from 80% power. Rx water level decreased to -60 inches and was then restored to 30 inches. Rx pressure is 820 psig and slowly increasing. Which of the following describes the status of the Recirc System due to the above events and conditions? The LPCI Loop Select Logic will... A. close the Recirc Pump Discharge Valve on the selected loop. B. trip the Recirc Pump Field Breaker for the selected loop. C. lock the scoop tube for the selected loop. D. not initiate until Reactor pressure decreases to 450 psig. Answer: A Question No.: 1-B.03.04.030 Reference (s): B.03.04-02 (Page 8 of 18) K/A
Reference:
295009 Task Number: AA1.03 Rating RO/SRO: 3.0 Monticello JTA: CR202.013 Objective (s): M-8107L-029, EO-9 1/cmb
[_ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 I LICENSE EXAMINATION - ANSWER KEY Page 72 of 127 j l Exam Question Number: 57 Point Value: 1.00 Time (Minutes): NA l Using the following conditions: Mode switch in S/D HPCI Auto initiated and is injecting at 3000 gpm. No.11 and No.12 Core Spray Pumps Auto initiated. No.11,12,13, and 14 RHR Pumps Auto initiated. Rx pressure is 950 psig. Rx level decreased to -35 inches and is currently at 0 inches and slowly increasing. Which of the following is correct? A. DW cooling fans are tripped. B. RCIC failed to Auto Start. C. ADS timer is activated. I D. Group i Valves Auto Closed. Answer: A Question No.: 1-B.08.16-001 Reference (s): B.8.16-02 (Page 3 of 5) K/A
Reference:
295010 Task Number: AK2.05 Rating RO/SRO: 3.7 Monticello JTA: CR273.006 i Objective (s): M-8107L-044, EO-8 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision, O LICENSE EXAMINATION - ANSWER KEY Page 73 of 127 l Exam Question Number: 58 Point Value: 1.00 Time (Minutes): NA During operation at 100% power, the dump valves for the 14A and 15A heaters fail open. Choose the correct response. ' A. Reactor power will increase over 1775 MWth due to the positive reactivity effects from cooler feedwater. B. Reactor level control will swap to single element control due to the sensed increase in feedwater flow. 4 C. Increased subcooling in the hotwell from the dump flow will cause condenser vacuum to increase and Turbine electrical output to increase. D. The control valves for the affected heaters will close on decreasing heater level resulting in no measurable affect on feedwater temperature. Answer: A Question No.: 1-B.06.05-021 Reference (s): B.06.05-05.01 K/A
Reference:
295014 Task Number: AK1.06 Rating RO/SRO: 3.8 Monticello JTA: CR259.021 Objective (s): M-8107L-068, EO-7, 8 I/cmb
MONTICELLO NUCLEAR GENERATING PLANT MB1000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 74 of 127 l Exam Question Number: 59 Point Value: 1.00 Time (Minutes): NA l The plant is operating at 100% power when a leak in the Drywell causes the following plant I conditions: j Drywell pressure is at 6 psig.
. l Fifteen control rods are not in past the 04 position, i The EOPs have been entered.
The SS directs you to insert rods per C.5-3101. Why does C.5-3101 direct you to close valves CRD-79-1, CRD 79-2 and CRD 168? A. To minimize radioactive water going to the CSTs. i 1 B. To maximize drive pressure above 400 psid. ' O. To minimize charging water flow. D. To maximize cooling header dP. Answer: D Question No.: , 1-C.5-3000-009 Reference (s): C.5-3103, Part C K/A
Reference:
295015 Task Number: AK2.07 Rating RO/SRO: 3.3/3.4 Monticello JTA: CR314.009 l Objective (s): M8114L-011, EO-3 1/cmb l L
MONTICELLO NUCLEAR GENERATING PLANT M81000 9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 76 of 127 i l Exam Question Number: 60 l Point Value: 1.00 Time (Minutes): NA Using the following information: ; Rx water level - 55 inches and slowly increasing i
- Rx pressure 280 psig DW pressure 15 psig and decreasing I
= Div i DW spray in service Div i and Div ll Torus Spray in service Ten minutes later Rx water level is being maintained at 35 inches by Feedwater level control system. DW pressure is 6 psig and slowly decreasing.
If the reactor operator depresses the RHR Div i CTMT SPRAY PERM INTERLOCK RESET PB 10A-S23A with DW pressure at 6 psig and slowly decreasing, the Div i Containment Spray Valves will... A. remain open and will not automatically close. B. automatically close when DW pressure decreases to approximately 2 psig. C. automatically close when DW pressure decreases to approximately 1 psig. D. close immediately. Answer: C Question No.: 1-B.03.04-029 Reference (s): B.03.04-02 K/A
Reference:
295024 l Task Number: EA1.17 Rating RO/SRO: 3.9 Monticello JTA: CR205.035 Objective (s): M-8107L-023, EO-8,10 I/cmb c
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 77 of 127 l Exam Question Number: 61 Point Value: 1.00 Time (Minutes): NA l The plant has just experienced a Group I isolation. The Reactor has received a SCRAM signal. All eight (8) SRVs initially Open due to the high pressure setpoint being exceeded. After a short time the SRVs start to cycle due to the Low-Low-Set System. What is the function of the Low-Low-Set System? A. Provides overpressure relief operation to prevent overpressurization of the primary nuclear system. B. Provides a backup to HPCI System for automatically depressurizing the Reactor. C. Provides about a 30 psig blowdown of the Reactor Vessel on high pressure. D. Minimize the possibility of a safety relief valve reopening while an elevated water leg exists in the discharoe line. i Answer: D Ouestion No.: 1-B.03.03.-016 Reference (s): B.03.03-01 K/A
Reference:
290025 Task Number: EK3.09 Rating RO/SRO: 3.7/3.7 Monticello JTA: CR218.003, CR999.003 Objective (s): M-8107L-025, EO-7, 9 1/cmb I l 1
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 79 of 127 l Exam Question Number: 62 Point Value: 1.00 Time (Minutes): NA , Given the following Plant conditions: Mode Switch in Shutdown
- Reactor power ~20%
f Reactor 'pressure at 1090 psig i e Procedure C.5-3101 in progress !
=
SBLC System 1 injecting { Torus water temperature 115 degrees and increasing, j Per the Emergency Operating Procedures, answer the following two (2) questions. ) 6
- 1. Why would the operators lower water level during the above event?
- 2. At what water level would the operators stop lowering water level?
i A. 1. l To increase core void fraction. t
- 2. -150 inches B. 1. To increase core void fraction.
- 2. -126 inches C. 1. To increase natural circulation. !
-150 inches ;
l D. 1. To increase natural circulation.
- 2. -126 inches Answer: i B
Question No.: l-C.05.01 -2000-001 Reference (s): C.S.1 -2007; C.5-2007 K/A
Reference:
295031 Task Number: EA2.02 Rating RO/SRO: 4.0 Monticello JTA: CR314.007 Objective (s): M-8114L-005, EO-6 l 1/cmb l l
/
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 80 of 127 Exam Question Number: 63 Point Value: 1.00 Time (Minutes): NA Given the following conditions: ATWS Event in progress SBLC System 1 injecting
=
immediate SCRAM actions complete Reactor pressure being maintained by the Turbine bypass valves What effect could an inadvertent Reactor cooldown during an ATWS event have regarding the plant? A Cooldown of the Reactor will cause... S A. SBLC effectiveness to be reduced due to the reduction in Reactor coolant mixing that occurs at lower temperatures. B. the MSIVs to close at 840 psig thereby further challenging primary containment. C. Reactor power to increase or cause the Reactor to return to criticality. D. unreliable Safeguards level instrument readings due to the instruments being calibrated Hot. Answer: C Question No.: l-C.05.01-2000-002 l Reference (s): C.S.1 -2007 I l K/A
Reference:
295037 Task Number: EK1.06 ! Rating RO/SRO: 4.0 Monticello JTA: CR314.007 Objective (s): M-8114L-005, EO-6 1/cmb l l
/ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 , LICENSE EXAMINATION - ANSWER KEY Page 81 of 127 ' l Exam Question Number: 64 Point Value: 1.00 Time (Minutes): NA During Loss of Coolant (LOCA) conditions CGCS is used to control the concentration of combustible gasses in the Drywell. Which gas and at what concentration is CGCS designed to control during a LOCA7 A. 0 2concentration below 6%. B. O2concentration below 5%. C. H2concentration below 8%. D. H2concentration below 4%. Answer: 8 Question No.: 1-B.04.03.02-010 Reference (s): B.04.03.02-05 K/A
Reference:
500000 Task Number: EK3.03 Rating RO/SRO: 3.0/3.5 Monticello JTA: CR244.003 Objective (s): M81071-079, EO-01 l/cmb
)
i MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 83 of 127 l Exam Question Number: 65 Point Value: 1.00 Time (Minutes): NA Following a trip of No.11 Recirculation Pump, the following conditions exist:
. Reactor power 1065 MWth l SPDS core flow indicates 29 Mlbm/Hr No.11 Recirc Jet Pump flow indicates 3.5 Mibm/H-No.12 Recirc Jet Pump Flow indicates 26.5 Mlbrrfelr Using the above conditions, choose the correct answer.
A. The Buffer regior of the Power / Flow Map has been entered and must be exited immediately by d%ng control rods or increasing recirculation flow. B. The Exclusion Region of the Power / Flow Map has been entered and an immediate Reactor Scram is required. C. Power distribution controls are not required at this time. The operator should continue to l monitor for entry into either the Buffer or Exclusion Regions. D. The Buffer Region of the Power / Flow Ma a has been entered, however, no immediate action is required. Operators should noti'y the Nuclear Engineering Staff for guidance to exit the Buffer Region. Answer: A PROVIDE POWER - FLOW MAP WITH EXAM. Question No.: ' l-C.4-B.05-005 Reference (s): C.4-B.05.01.02-A K/A
Reference:
295001 Task Number: AK2.07 Rating RO/SRO: 3.4 Monticello JTA: CR999.011; CR202.013 Objective (s): M-8107L-029, EO-8 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 84 of 127 l Exam Question Number: 66 Point Value: 1.00 Time (Minutes): NA While performing Rapid Power Reduction due to a Recombiner trip, the following conditions occur: Condenser Vacuum 24 inches Hg and slowly decreasing
- Generator output 190 MWe Rx water level +35 inches Reactor Recirc for both loops at minimum The Shift Supervisor orders the C-05 Operator to reduce Reactor power an additional 10% in an attempt to increase condenser vacuum,
- 1. If condenser vacuum does not improve from the power reduction, what action is required?
- 2. Why is this action required?
A. 1. Open the Condenser Crosstie Valves.
- 2. To protect the Turbine blading.
l l B. 1. Open the Condenser Crosstie Valves. !
- 2. To allow the MVP to be placed in-service.
C. 1. A manual SCRAM is rec uired.
- 2. To protect the Turbine b ading.
D. 1. A manual SCRAM is re uired.
- 2. To allow the MVP to be laced in-service.
Answer: C Question No.: 1-C.4-B.06-007 Reference (s): C.4-B.6.3.A (DECREASING CONDENSER VACUUM) K/A
Reference:
295002 Task Number: AK3.02 Rating RO/SRO: 3.4 Monticello JTA: CR999.011, CR255.002 Objective (s): M-8104L-002, EO-1, M-8107L-011, EO-5 1/cmb
r
/
l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 85 of 127 l Exam Question Number: 67 Point Value: 1.00 Time (Minutes): NA The plant is operating at 100% power when there is an electrical disturbance on the NSP System. The Control Room Operators assess the plant status and find the following indications: Busses 11 through 16 show 0 volts. . RCIC is injecting at full flow. : Bus 16 has a Lock Out. . HPCI is injecting at full flow. No.11 EDG failed to start. . MSIVs are closed. Reactor water levelis at -10 inches . All control rods are full in. and increasing. 1 According to procedure vw is the preferred method for maintaining Reactor water level control using HPCI and RCIC? A. Manually trip RCIC, then use HPC! to maintain Reactor water level -126 inches to +48 inches. B. Manually trip RCIC, then Isolate the steam lines by closing the Steam isolation Valves. Use HPCI to control level -150 inches to +48 inches. C. Manually trip HPCl, then place the HPCI Aux Oil pump and HPCI Gland Seal Condenser Blower in Pull-To-Lock. Use RCIC to maintain level -126 inches to +48 inches. D. Manually trip HPCI, then place the HPCI Aux Oil Pump and HPCI Gland Seal Condenser Drain Pump in Pull-To-Lock. Use RCIC to maintain water level -150 inches to +48 inches. Answer: C Question No.: 1-C.4-B.09-012 Reference (s): C.4-B.09.02.A (STATION BLACKOUT) K/A
Reference:
295003 1 Task Number: AK1.06 Rating RO/SRO: 3.8/4.0 Monticello JTA: CR999.011, VR217.007 Objective (s): M-8114L-003, EO-1,2; M-8107L-003, EO-10 i l i \ I/cmb i
/ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 87 of 127 l Exam Question Number: 68 Point Value: 1.00 Time (Minutes): NA Using the following information:
Mode Switch in Shutdown following a Reactor SCRAM Reactor water level currently 30 inches and slowly decreasing Orywell pressure is 1.9 psig and increasing White light above HPCI High Level Trip Reset Pushbutton is lit. For the above conditions, which of the following is correct? A. HPCI will not start on low-low Reactor water level unless the high level trip is reset. B. HPCI will not start on high Drywell pressure unless the high level trip is reset. C. HPCI will start automatically on Low Low Reactor level or high Drywell pressure, due to the high Reactor water level trip having already been reset. D. HPCI will start when the Drywell prusure setpoint is reached, as long as Reactor level is below 48 inches. Answer: O I l Question No.: 1-B.03.02-023 Reference (s): B.3.2-01 l K/A
Reference:
295003 Task Number: AA1.04 Rating RO/SRO: 3.5 Monticello JTA: CR206.003 Objective (s): M-8107L-002, EO-7 i i I/cmb l
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 88 of 127 l Exam Question Number: 69 Point Value: 1.00 Time (Minutes): NA Following a loss of coolant accident, the SS orders that an RPV Emergency Depressurization be initiated based on Drywell temperatures approaching 281* F. What is the basis for depressurizing the Reactor when Drywell temperatures approach 281 *F? To ensure... A. energy within the Reactor is directed to the Torus before the Torus Heat Capacity Umit is exceeded. B. the blowdown is performed such that the RPV water !evel instruments remain valid. C. the blowdown is performed while the ADS Valves are still operable and before temperature rises high enoug 1 to damage the Drywell. D. that additional damage to the RPV is prevented when the ability to maintain Primary Containment integrity is being challenged. 1 Answer: C Question No.: 1-C.5-01-1200-001 Reference (s): C.S.01-1200 K/A
Reference:
295012 Task Number: AA1.02 Rating RO/SRO: 3.8 Monticello JTA: CR999.012, CR304.010 Objective (s): M-8107L-028, EO-3 M-8114L-005, EO-6 i I/cmb
s
/ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 I
TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LIMNSE EXAMINATION - ANSWER KEY Page 89 of 127 l l Exam Question Number: 70 Point Value: 1.00 Time (Minutes): NA The plant is in a startu a and is currently at 140 psig. HPCI testing is in progress with RCIC and SRV testing schedulec to follow. Plant parameters are as follows: Reactor Pressure 140 psig
=
Reactor Level 38 inches a Drywell Temp 120'F
= Drywell Pressure .3 psig Torus Level +0.3 inches
. Torus Temp 80* F What mode should the RHR System be in based on the above information?
A. RHR is not required in service at this time, due to all critical plant parameters being in acceptable ranges. B. RHR should be in Shutdown Cooling to help maintain a steady heatup rate. C. RHR should be lined up to allow the Torus to be pumped down to Radwaste. D. RHR should be in Torus Cooling to mix the Torus and prevent localized heating. Answer: D Question No.: 1-B.03.02-022 Reference (s): B.03.02-05; B.03.03-05 K/A
Reference:
295013 Task Number: AK1.03 Rating RO/SRO: 3.0/3.3 Monticello JTA: CR205.016 ! Objective (s): M-8107L-025, EO-10 1 1/cmb l
f 1
/ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 91 of 127 i
l Exam Question Number: 71 Point Value: 1.00 Time (Minutes): NA There has been a Control Room fire that has forced an evacuation of the Control Room. The l l The operators have started a c(ooldown using SRVs. operators have entered C.4I Given the time line from the event for Reactor pressure, determine if the operators violated the cooldown requirements for the above conditions. TIME LINE: Time (In mins.) Reactor Pressure (in osia) , 0 1005 SCRAM per C.4-C l 20 800 l 30 680 40 550 50 510 60 400 , l l A. Yes, all points on the chart trace stay within the operation allowed area of the Reactor Depressurization Rate Curve. B. No, The time line shows that Reactor pressure dropped into the operation not allowed area in one spot on the time line. l l C. No, The time line shows that Reactor pressure dropped into the operation not allowed area I in two spots on the time line. D. No, The time line shows that Reactor pressure dropped into the operation not allowed area in three spots on the time line. Answer: C PROVIDE FIGURE 2, RX DPERESSURIZATION RATE, C.4-C WITH EXAM. 1 Question No.: 1-C.4.C-001 ! Reference (s): C.4-C, Revision 15, Page 29 of 29 K/A
Reference:
295016 Task Number: 2.1.25 Rating RO/SRO: 2.8/3.1 Monticello JTA: CR218.004, CR999.011 Objective (s): M-8107L-025, EO-1,2,4; M-8114L-004, EO-1 l I/cmb i
T l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 i TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 93 of 127 l Exam Question Number: 72 Point Value: 1.00 Time (Minutes): NA A leak in the Reactor Building has caused SBGT to initiate on High Radiation in the Reactor Building Plenum. Two (2) hours after the initiation, the operators respond to Alarm 3-A-49 (SBGT ANNUNCIATOR). During investigation of the alarm, the operator notices that "B" SBGT has Automatically initiated and "A" SBGT has tripped. I What action will the operator perform to protect the SBGT System from damage? l l A. Place "A" SBGT Train in the Cooling Mode. l B. Isolate "A" SBGT Fan V-EF-17A power supply. C. Place "B" SBGT in Manual to prevent restarting "A" SBGT. l l l D. Place Stack Dilution Fan V-E-F-18B in service and Stack Dilution Fan V-E-F-18A in Auto. l l l Answer: 1 A Question No.: 1-B.04.02-022 1 Reference (s): B.04.02-02 B.04.02-05 K/A
Reference:
295017 Task Number: AA1.09 Rating RO/SRO: 3.6 Monticello JTA: CR261.008 Objective (s): M-8107L-008, EO-11 l I/cmb l
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 , LICENSE EXAMINATION - ANSWER KEY Page 94 of 127 l l l l Exam Question Number: 73 Point Value: 1.00 Time (Minutes): NA l l Given the following Plant conditions: Plant is in a Station Blackout.
. MSIVs have just closed.
. SRVs are cycling on Low-Low Set
. RCIC and HPCI are running.
Reactor water level is -40 inches and increasing. For the above conditions several systems are analyzed for Reactor Pressure Vessel (RPV) loses. SRVs, RCIC and HPCI are part of this analysis. Besides these systems there are additional RPV loses calculated in. Which of the following is included in the above analysis and why? A. Identified DW leakage because there is Pressure Boundary leakage that needs to be accounted for. B. Unidentified DW leakage because Tech Specs allow up to 25 gpm unidentified leakage. C. Recirc Pump seals because loss of RBCCW leads to Recirc Pump seal failure. D. MSIVs because the MSIVs have exceptance criteria that is verified during leak rate testing. Answer: C Ouestion No.: l-C.4-B.09.02-001 Reference (s): C.4-B.09.02.A K/A
Reference:
295018 Task Number: AK1.01 Rating RO/SRO: 3.5 Monticello JTA: CR999.011 Objective (s): M-8114L-002, EO-1, 2 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 95 of 127 l Exam Question Number: 74 Point Value: 1.00 Time (Minutes): NA Using the following information: Reactor Shutdown for refueling outage Shutdown cooling in service on 'B' RHR Loop.
- No.14 Air Compressor out of service for maintenance activities.
The Turbine Building Operator calls the Control Room to inform you that No.11 Air Compressor just tripped and No.13 failed to start. Air system pressure is rapidly decreasing. Which of the following is correct? A. The RHR minimum flow valves will remain closed due to the valves being blocked closed while Shutdown Cooling is in service. B. Tne RHR minimum flow valves will remain closed due to the valves having backup air supplied from the RHR auxiliary air compressor. C. The RHR minimum flow valves will fail open when instrument air header pressure drops below 60 psig. Shutdown cooling needs to be secured to preclude a vessel drain down ! event. ' D. The RHR minimum flow valves fail closed and RHR aump minimum flow protection is lost. Operators should not remove RHR from service unti air supply is restored. Answer: , A Question No.: 1-B.03.04-033 Reference (s): B.03.04-05, B.03.04-02 K/A
Reference:
295019 Task Number: AA2.02 Rating RO/SRO: 3.6 Monticello JTA: CR999.011, CR205.010 Objective (s): M-8114L-002, EO-1,2 M-8107L-023, EO-14 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 ' LICENSE EXAMINATION - ANSWER KE ' Page 96 of 127 l Exam Question Number: 75 Point Value: 1.00 Time (Minutes): NA While performing the quarterly SBLC Functional Test, a miscommunication results in a Control Room Operator starting the No.11 SBLC Pump from C05 rather than locally, as directed by the procedure. Due to this error, which of the following would be correct? A. Both Squib Valves would be fired. B. The operating RWCU Pump will receive a direct trip from the SBLC logic. C. SBLC Pump injection to the Reactor will be prevented due to system alignment in test status. D. An RWCU lsolation will occur causing MO-2399, MO-2397 and MO-2398 to Close. l l Answer: ' D Question No.: 1-B.02.02-022 Reference (s): B.02.02-01 (Page 5 of 15) K/A
Reference:
295020 Task Number: AK2.04 Rating RO/SRO: 3.1 Monticello JTA: CR211.012 Objective (s): M-8107L-004, EO-8 I/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 97 of 127 l Exam Question Number: 76 Point Value: 1.00 Time (Minutes): NA Given the following Plant conditions: Reactor is at 90% power for monthly valve testing. Drywell pressure is 1 psig. Reactor water levelis +35 inches. e No.11 RBCCW Pump in service No.11 CRD Pump is isolated for replacement of the pump bearings, a No.12 CRD Pump in service Alarm 5-B-38 (CRD ACCUMULATOR LO/ PRESS Hl/ LEVEL) is in Alarm for HCU 26-27. A fault on Bus 16 occurs causing the 4160 Bus to Lock Out. While the operators are responding to the Bus Lockout, HCU 10-39 has its orange accumulator light come on. What actions are required for the above conditions? A. Trip both Recirc pumps in 60 seconds. B. SCRAM the Reactor. C. Isolate the CRD Pumps by closing CRD-3-1, CRD-5-1, CRD-3-2, and CRD-5-2. { D. Start a Condensate Pump if the CRD Pumps cannot be isolated. Answer: B Question No.: 1-C.4-B.01 -020 Reference (s): C.4-B.1.3.A l K/A
Reference:
295022 l Task Number: AA2.01 Rating RO/SRO: 3.5/3.6 Monticello JTA: CR999.011, CR201.021 Objective (s): M-8114L-002, EO-1; M-81071-020, EO-7,12 1/cmb ps
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 99 of 127 Exam Question Number: 77 Point Value: 1.00 Time (Minutes): NA Using the following conditions: Drywell pressure 7.3 psig and increasing Rx water level -40 inches (manual control) Rx pressure 1008 psig and decreasing 67 control rods not Full-In Torus temperature 108" F and increasing MSIVs Closed Which of the following EOP actions is appropriate for these conditions and why? A. Spray Drywell to prevent SRVs from exceeding the Torus Boundary Design Load. B. Maintain water level +9" to +48" to prevent large power swings on the Reactor Core. C. Emergency Depressurize to prevent Drywell pressure from exceeding Primary Containment Pressure Limit. D. Inject SBLC to prevent Torus temperature from exceeding the Heat Capacity Limit. Answer: D l l Question No.: 1-C.5-2000-013 Reference (s): C.5-2007, C.S.1 -2007, C.5.1 -1200 K/A
Reference:
295026 i Task Number: EK3.04 Rating RO/SRO: 3.7 Monticello JTA: CR314.007 i Objective (s): M-8114L-005, EO-6, 7 1/cmb I
r 1 1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 100 of 127 l l Exam Question Number: 78 Point Value: 1.00 Time (Minutes): NA j l Given the following conditions: SPDS failed due to a computer software problem. . TR 23-115 pt. 21 = 156* F o The plant was manually scrammed following a stuck open "B" SRV. . TR 23-115 pt. 22 = 129 F Reactor levelis being maintained at 30 inches. . TR 23-115 pt. 23 = 152* F Annunciator 5-B-53 "DW-TORUS . TR 23-115 pt. 24 = 164* F AIR Hi TEMP" is in alarmed condition. The SS directs the Control Room Operator to closely monitor the primary containment parameters due to the failure of SPDS concurrent with changing plant conditions. I Using the above conditions, determine the value for bulk Drywell temperature. A. 146.1* F B. 147.4* F l C. 150.3* F D. 164.0* F Answer: A PROVIDE OPERATOR A!D C-13 (BULK DRYWELL TEMP CALC) WITH EXAM Question No.: 1-C.05.01-1000-001 Reference (s): C.5.1 -1200 K/A
Reference:
295028 Task Number: EA2.01 Rating RO/SRO: 4.0 Monticello JTA: CR304.010 Objective (s): M-8114L-005, EO-4,5 l I/cmb l l
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 101 of 127 l Exam Question Number: 79 Point Value: 1.00 Time (Minutes): NA The EOPs direct the operator to remove HPCI from service at a low Torus level of -3.7 feet. l Why does HPCI have to be removed from service at low Torus levels? l A. The level is low enough to allow air to enter the HPCI Pump Suction. I B. HPCI exhaust would pressurize the Torus. air space. l C. Minimum flow requirements cannot be met because of flow vortex limits. D. The Drywell-Torus Vacuum Breakers are completely uncovered allowing HPCI exhaust to discharge directly into the Drywell. l l Answer: B Question No.: 1-C.5-1000-070 Reference (s): C.S.1-1200 EOP K/A
Reference:
295030 Task Number: EK2.01 Rating RO/SRO: 3.8 Monticello JTA: CR304.010, CR206.003 Objective (s): M-8114L-005, EO-6 l M-8107L-002, EO-5 i i 1/cmb l
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 L! CENSE EXAMINATION - ANSWER KEY Page 102 of 127 l Exam Question Number: 80 Point Value: 1.00 Time (Minutes): NA When resetting a Reactor SCRAM, why are you directed to evacuate the Reactor Building 896' Floor and Equipment Drain Tank Room? A. The Scram Discharge Volume vent and drains empt Tanks causing radiation levels to possibly increase. y into the Floor and Equipment D B. The Scram Discharge Volume vents will blow steam directly into the Floor and Equipment Drain Tank Room when the SCRAM is reset causing airborne radiation levels to possibly increase. C. The SCRAM valves will discharge a burst of air into the Floor and Equipment Drain Tank Room causing the airborne radiation levels to possibly increase. , D. The SCRAM valves will vent the Reactor pressure into the Floor and Equipment Drain Tanks causing radiation levels to possibly increase. Answer: A Question No.: 1-C.4.A-021 Reference (s): C.4-A K/A
Reference:
295033 Task Number: EK3.04 Rating RO/SRO: 4.0/4.4 Monticello JTA: CR999.011 Objective (s): M-8114L-005 EO-6,7 1/cmb
I I MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: \ 1999 NRC INITIAL REACTOR OPERATOR Revision 0 I LICENSE EXAMINATION - ANSWER KEY Page 104 of 127 l Exam Question Number: 81 Point Value: 1.00 Time (Minutes): NA I l A Primary Containment Group 2 Isolation is initiated as a result of high radiation conditions in the ! Reactor building plenum. The SBGT System initiates and the Reactor and Turbine Building ventilation systems operate properly. If indications of a significant radioactive leak were identified in the Turbine Building, which of the following would be correct? A. The SBGT System should be re-aligned to take suction from the Turbine Building. B. Operation of the SBGT System should be secured to prevent contaminants from being drawn into the Reactor Building. C. The Turbine Building supply fans should be started to pressurize the Turbine Building to minimize the leak. D. The Reactor Building plenum exhaust fans should be started to assure the release monitored by the RBV WRGMs. l l Answer: D Question No.: 1-C.4-B.04-009 Reference (s): C.4-B.4.1.8 K/A
Reference:
295034 Task Number: EK2.04 Rating RO/SRO: 3.9 Monticello JTA: CR999.011; CR261.007 Objective (s): M-8114L-002, EO-1,2 l M-8107L-008, EO-11 l l/cmb l J l
/ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 105 of 127 Exam Question Number: 82 Point Value: 1.00 Time (Minutes): NA Reactor power is approximately 3% during a Reactor startup. Main Steam Line radiation levels are increasing due to leaking fuel bundle. A short time later, condenser vacuum begins to decrease. Choose the correct answer. Condenser vacuum is decreasing due to the... A. trip of the Hydrogen Water Chemistry System. B. trip of the Mechanical Vacuum Pump. C. trip of the Steam Jet Air Ejector Suction Valves. D. auto isolation of the Main Steam isolation Valves. Answer: B Ouestion No.: 1-B.05.11-039 Reference (s): B.05.11 -02 K/A
Reference:
295038 Task Number: EK2.10 Rating RO/SRO: 3.2 Monticello JTA: CR255.002 Objective (s): M-8107L-011, EO-3 1/cmb
l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 106 of 127 l Exam Question Number: 83 Point Value: 1.00 Ime (Minutes): NA i 1 If a Fire Alarm is activated on Panel C-348 (REACTOR BUILDING ELEVATOR LOBBY AND MACHINE ROOM SMOKE DETECTOR ANNUNCIATOR PANEL), what automatic actions occur? 1 A Trouble Alarm is sent to... ! A. the Control Room on C-20 and the Reactor Building elevator goes into phase I operation. B. the Control Room on C-20 and the Reactor Building elevator goes into phase 11 operation. C. C-300 (ZONALERT CONTROL ROOM ANNUNCIATOR) and the Reactor Building elevator goes into phase 1 operation. D. C-300 (ZONALERT CONTROL ROOM ANNUNCIATOR) and the Reactor Building elevator l goes into phase ll operation. l i Answer: C Ques'Jon No.: 1-B.08.05-017 Reference (s): B.08.05-01 B.08.15-02 K/A
Reference:
60000 Task Number: AA1.06 Rating RO/SRO: 3.0 Monticello JTA: CR286.005 Objective (s): M-8107L-010, EO-2, 6 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 l TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 107 of 127 l Exam Question Number: 84 Point Value: 1.00 Time (Minutes): NA l Given the following plant conditions:
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Reactor shutdown with all rods inserted to 00. Reactor water temperature 170 degrees. , Shutdown cooling in service on "A" Loop of RHR. Reactor disassembly work in progress.
. Time to boiling calculated at 1.6 hours.
Shutdown cooling is lost when a jumper is inadvertently placed on the wrong terminal strip in the cable spreading room. The control room crew is unable to restore normal shutdown cooling. What is the reason that the operator is directed to control Reactor water level greater than +55 inches? Reactor water level is maintained greater than 55 inches to allow... A. the feedwater spargers to effectively mix the feedwater added to the Reactor Vessel. B. the Reactor water level instrumentation to remain on scale when the Reactor water temperature increases. C. the water from the annulus area of the Reactor to flow into the core shroud area as level decreases inside the shroud. D. natural circulation during periods when forced circulation is unavailable. Answer: D i Question No.: l-C.4.B.03-010 l l Reference (s): C.4-B.03.04.A i K/A
Reference:
295021 Task Number: AK3.05 Rating RO/SRO: 3.6 Monticello JTA: CR999.011 Objective (s): M-8114L-002, EO-1, 2 1/cmb
/ MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 108 of 127 l Exam Question Number: 85 Point Value: 1.00 Time (Minutes): NA During a Refuel Outage, half-way through a Full Core Unload, the refueling crew notifies the Control Room that they dropped a fuel bundle and it is balancing over the edge of the cattle shoot. Using the following information: Refuel Floor radiation levels are normal Rx Building radiation levels are normal
. Rx Building Plenum radiation levels are normal Immediately following the incident, which of the following is a correct action for the refueling crew?
A. Attempt to move the fuel bundle to a stable orientation. l l B. Evacuate the Refuel Floor of all personnelimmediately. ! C. Move the bundle to a stable location and then evacuate the Refuel Floor of all personnel. . D. Halt refueling operations and notify the Radiation Protection Coordinator to initiate area monitoring. Answer: B Question No.: 1-D.02-05-001 Reference (s): D.2 05 l K/A
Reference:
295023 Task Number: AA1.04 Rating RO/SRO: 3.4 Monticello JTA: CR234.014 Objective (s): M-8107L-019, EO-5 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 109 of 127 1 I l Exam Question Number: 86 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions: Reactor SCRAM from 90% power. A steam leak in the 935' Reactor Building West CRD HCU area has just been reported.
- Local report is that the area is too hot to enter.
Which of the following is a true statement concerning EOPs? i A. There are no EOP entry conditions associated with a steam leak in this area. I B. 1300 EOPs will be entered if local reports on temperature in the area indicate that temperature is greater than 120oF. I l C. 1300 EOPs will be entered when the area temperature monitoring equipment indicates : greater than 1S0oF in the area. l D. 1400 EOPs will be entered due to the spread of airbome contamination caused by the steam leak. Answer: B Question No.: 1-C.5-1000-067 Reference (s): C.51300 Bases K/A
Reference:
295032 Task Number: EK2.06 Rating RO/SRO: 3.3/3.4 Monticello JTA: CR304.012 Objective (s): M-8114L-005 EO-6,7 1/cmb
1 l l MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 111 of 127 1 Exam Question Number: 87 Point Value: 1.00 Time (Minutes): NA Thirty (30) minutes after an earthquake, the following conditions exist: Reactor water levelis normal.
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All control rods are at position 00. l 1 One (1) foot of water is on the Torus floor due to a leaking Torus drain flange. The MSIVs are Closed. l Reactor Scram has been reset. RPS Busses A & B amber lights are on. Torus level is -2 feet. For the above conditions, which of the following is correct? A. Water will be flooding the 250 VDC MCC-313. B. RHR Room ECCS sump pumps are running. C. RHR and Core Spray pumps are allinop. D. Full core display " Blue" Scram lights are ON. Answer: B Question No.: l-B.07.01 -001 Reference (s): B.07.01-02 (Page 28 of 47) K/A
Reference:
295036 Task Number: EA2.02 Rating RO/SRO: 3.1 Monticello JTA: CR209.007, CR205.010 Objective (s): M-8107L-005, EO-3; M-8107L 101, EO-2,4 1/cmb
1 MONT' CELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 112 of 127 l l Exam Question Number: 88 Point Value: 1.00 Time (Minutes): NA A Duty Control Room Operator received a call from the Turbine Building Operator. The Turbine Building Operator states that a small fire has started on No.11 EDG Oil System and he was j unable to put it out with a fire extinguisher. The Control Room Operator's first action is to... A. call out the Fire Brigade. B. initiate an evacuation of the EDG Room. C. Instruct the Turbine Building Operator to secure the No.11 EDG. D. notify the System Engineer to investigate with the Turbine Building Operator. l 1 l l Answer: A Question No.: 1-C.04.B.08-006 Reference (s): C.04-B.08.05.A K/A
Reference:
Generic Knowledge and Ability Task Number: 2.1.8 Rating RO/SRO: 3.8 Monticello JTA: CR999.011 Objective (s): M-8114L-002, EO-1 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 113 of 127 l Exam Question Number: 89 Point Value: 1.00 Time (Minutes): NA i While conducting a plant tour you come across an injured individual that appears to have fallen. I Which of the follow,ing is the proper response? A. Notify the SS at Ext.1140 and report to the Fire Brigade Assembly Room. B. Notify the Control Room at Ext. 9111, and move the' victim from any immediate hazards. C. Retrieve the emergency medical kit from the Fire Brigade Room and administer first aid while waiting for the emergency medical team to arrive. { D. Notify the Control Room at Ext. 5111 and stay with the victim until the Fire Brigade arrives. I Answer: l D Question No.: l-A.5-001 Reference (s): A.5-100 K/A
Reference:
Generic Knowledge and Ability Task Number: 2.1,16 Rating RO/SRO: 2.9 Monticello JTA: CR999.008 Objective (s): M-7702L-004, EO-27 M-8108L-033, EO-1 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 1 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 114 of 127 l Exam Question Number: 90 Point Value: 1.00 Time (Minutes): NA 1 Given the following information:
. Reactor power 100%
Annunciator 4-A-11 " Reactor BUILDING HIGH RADIATION" alarms. ARM A-14 "HPCI TURBINE AREA (896') indicates 300 mr/hr and increasing
. Set point for ARM-14 is 200 mr/hr Reactor building APEO reports steam in the HPCI room.
. HPCI system has not isolated C.4 immediate actions for leak outside of containment have been completed.
. Shift Supervisors name is Dave.
Choose the communication that best satisfies the standard for this situation. A. " Dave, Annunciator 4-A-11 is in Alarm. EOP entry condition."
- 8. " Dave, Reactor Building High Radiation Alarm was received. HPCI Turbine area radiation level is 300 millirem per hour and increasing. We have a report of steam in the HPCI room. EOP entry condition."
C. " Dave, I have been notified by the Reactor Building APEO that there is steam in the HPCI Room. I also have received an unexpected alarm. Reactor power is still 100% We have a possible EOP entry condition based on Reactor Building radiation levels." D. " Dave, we have a C.4 entry condition on Steam leak outside containment. Annunciator response procedure entry condition on increasing HPCI room radiation levels and a possible EOP entry condition." Answer: B Ouestion No.: l-MISC-004 Reference (s): owl-01.03 (OPERATIONS COMMUNICATION STANDARD) owl-01.04 (OPERATIONS GENERAL PROCEDURAL GUIDANCE) K/A
Reference:
Generic Knowledge and Ability Task Number: 2.1.17 Rating RO/SRO: 3.5 Monticello JTA: CR999.007 Objective (s): M-8108L-029, EO-1 1/cmb
c , -- MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 115 of 127 [ Exam Question Number: 91 Point Value: 1.00 Time (Minutes): NA The C.4 Abnormal Procedures are written to address a wide variety of plant conditions. i If, while performing one of these procedures a subsequent STEP does not apply to the current conditions, what is the operator required to do? i A. Process a 3087 to have the STEP changed before proceeding to the next step. B. Process a temporary change before proceeding in the procedure. C. Omit the step and continue in the procedure. D. Make an entry in the Control Room Log describing compensatory actions taken. I A_nswer: C , Question No.: 1-C.4-003 Reference (s): C.4 (GENERAL INSTRUCTIONS), Page 2 of 4 K/A
Reference:
Generic Knowledge and Ability Task Number: 2.1.20 Rating RO/SRO: 4.3 Monticello JTA: CR999.011 Objective (s): M-8114L-001, EO-1 f 1 1/cmb
1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY u Page 116 of 127 l l Exam Question Number: 92 Point Value: 1.00 Time (Minutes): NA l Given the following plant parameters: Reactor is shutdown. Refueling is in progress. Reactor level is 10 inches on the safeguards indicators. No.11 SBGT system is isolated. All other plant equipment is normal. What does the Monticello Technical Specifications have to say about the above conditions? A. A Safety Limit is being exceeded. B. A LSSS is being exceeded. 1 C. A LCO is in effect. D. There are no related Tech Spec concerns. Answer: C i l Question No.: l-TS-046 Reference (s): T.S. 3.7-4.7 - (CONTAINMENT SYSTEMS) Ops Manual B.04.02-05 K/A
Reference:
GENERIC KNOWLEDGES AND ABILITIES Task Number: 2.1.33 Rating RO/SRO: 3.4/4.0 Monticello JTA: CR999.004 Objective (s): M-81081-003, EO-3 1/cmb
r MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 , LICENSE EXAMINATION - ANSWER KEY Page 117 of 127 l Exam Question Number: 93 Point Value: 1.00 Time (Minutes): NA l ; While conducting a routine surveillance test, the Turbine Building APEO calls the Control Room requesting permission to complete STEP 46 of the procedure pnor to completing STEP 45. i Following a review of the procedure, you concur that STEP 46 needs to be completed in order to l complete STEP 45. Choose the correct answer. i A. Completion of the Steps out-of-order is allowed only if a temporary change to the procedure is processed by the SS or SM. B. Completing Steps out-of-order is allowed if current sequence is incorrect. Allow the operator to complete the Steps out-of-order and note in the Comments Section that this ; was done including the reason for the change. i C. OC Review is required for all changes made to a procedure prior to performing the procedure. Stop the surveillance and submit a procedure change form. l D. Complete the procedure without completing STEP 45. Note in the Comments Section the STEP not completed, including the reason for the change. ' l Answer: A , i Question No.: l-4AWI.04-027 4 Reference (s): 4 awl-04.05.07 (PROCEDURE IMPLEMENTATION) K/A
Reference:
Generic Knowledge and Ability Task Number: 2.2.12 Rating RO/SRO: 3.0 Monticello JTA: CR999.007 Objective (s): M-8108L-029, EO-1 1/cmb
N MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 118 of 127 l Exam Question Number: 94 Point Value: 1.00 Time (Minutes): NA l Electricians have called the Control Room to request that operations stroke a motor-operated valve for VOTES testing. When the operator goes to stroke the valve per the Electrician's request, both a VOTES tag and a Secure Card are found on the valve handswitch for the valve. What course of action is required by the operator? A. Stroke the valve per the Electrician's request. B. Notify the SS that there is a Secure Card on the valve handswitch. C. Notify the SS that a Hold Card needs to be placed on the valve handswitch. D. Remove the Secure card, stroke the valve, then replace the Secure card. Answer: B Question No.: 1-4 awl-04-028 Reference (s): 4 awl-04.04.01 (EQUIPMENT ISOLATION) K/A
Reference:
Generic Knowledges and Abilities 3 Task Number: 2.2.13 Rating RO/SRO: 3.6/3.8 Monticello JTA: CR299.012 Objective (s): M-8108L-029, EO-1 I i 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 120 of 127 Exam Question Number: 95 Point Value: 1.00 nme (Minutes): NA (ou are currently assigned as the Control Room Operator on C-05 during refueling activities. You have not heard from the refuel bridge for 10 minutes and contact them to inquire about their activities. The operator doing accountability informs you that a blade guide was inadvertently 31 aced in the wrong cell in the Reactor and that they have just completed moving it to the correct ocation. Choose the correct answer. A. The Supervisor on the Refuel Floor is responsible for the error and no action on your part is required. B. You should note the additional steps taken on the master refuel procedure in the Control Room and have the Refuel Floor Supervisor initial the Steps when he comes down from the Refuel Floor. C. The mistake is considered a refueling error and refuel activities should be stopped until an evaluation of the event is complete. D. Blade guides pose no reactivity concerns, therefore, incorrect placement of a blade guide is insignificant and no actions are required. Answer: C Question No.: 1-D.02-05-002 Reference (s): D.02-05 (REACTOR AND CORE COMPONENTS HANDLING EQUIPMENT) K/A
Reference:
Generic Knowledge and Ability Task Number: 2.2.30 Rating RO/SRO: 3.5 Monticello JTA: CR234.017 Objective (s): M-8107L-019, EO-9 1/cmb
o 1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 l LICENSE EXAMINATION - ANSWER KEY Page 121 of 127 Exam Question Number: 96 Point Value: 1.00 Time (Minutes): NA l The HWC System affects several plant area radiation levels. What is the correlation between HWC and the listed areas? If HWC injection rate is increased, radiation levels will increase in the... A. Steam Chase, Condenser Hot Side, Turbine Operating Floor. B. Steam, Chase, Condenser Hot Side, Air Ejector Room. C. Steam Chase, Recombiner Room, Turbine Operating Floor. D. Steam Chase, Condenser Hot Side, Recombiner Room. l Answer: A l l 1 Question No.: 1-B.02.06-012 Reference (s): B.02.06-05, Page 4 of 24 K/A
Reference:
Generic Knowledge and Ability Task Number: 2.3.10 Rating RO/SRO: 2.9 Monticello JTA: CR301.001 Objective (s): M-8107L-085, EO-4 l I/cmb
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MONTICELLO NUCLEAR GENERATING PLANT .. 90-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revc.on 0 LICENSE EXAMINATION - ANSWER KEY Page 122 of 127 l Exam Question Number: 97 Point Value: 1.00 Tme (Minutes): NA Given the following plant conditions: Reactor is manually scrammed due to an identified Reactor coolant leak. All rods are inserted to 00. Reactor levelis 35 inches. There is a Group 1 Isolation on high steam flow. The Low-Low Set system has failed. Reactor pressure is being controlled by SRV safety actuation.
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Drywell pressure is 1.7 psig. Drywell bulk average temperature is 145 degrees F. l West CRD ARM is in Alarm. An Alert has been declared based on the Reactor coolant leak. I Which EOP procedures require entry based on the current plant conditions? 1 A. C.5-1100 and C.5-1200 B. C.5-1200 and C.5-1300 C. C.5-1100 and C.5-1300 D. C.5-1300 and C.5-1400 Answer: C Ouestion No.: 1-C.5-1000-068 Reference (s): C.5 EOPs K/A
Reference:
Generic Knowledge and Ability Task Number: 2.4.1 Rating RO/SRO: 4.3 Monticello JTA: CR304.002, CR304.012 Objective (s): M-8114L-005, EO-4 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 123 of 127 l Exam Question Number: 98 Point Value: 1.00 nme (Minutes): NA The purpose of the Post Accident Sampling System (PASS) is to obtain representative liquid and gas samples for chemical and radiochemical analysis in associated with the possible event of a _oss-of-Coolant Accident (LOCA) as required by NUREG-0578. Which of the following is a sample taken by the PASS? A Reactor coolant sample is taken from the... A. Core Spray Discharge Line. B. Recirc Pump Casing. C. RHR Loop in shutdown Cooling. D. Drywell Equipment Drain Sump. Answer: C Question No.: 1-B.05.18-001 Reference (s): B.05.18-01 K/A
Reference:
Generic Knowledges and Abilities Task Number: 2.4.3 Rating RO/SRO: 3.5/3.8 Monticello JTA: CR999.006 i Objective (s): M-8107L-023, EO-18 1/cmb 1
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l l l MONTICELLO NUCLEAR GENERATING PLANT M81000-gg23 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 125 of 127 l l Exam Question Number: 99 Point Value: 1.00 Time (Minutes): NA Given the following plant conditions: Reactor manually scrammed after a Group I Isolation Drywell pressure 8.5 psig
- Torus temperature 125*F
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Reactor level-100 inches Which of the following Control Room instruments can be used to help determine the amount of, if any, fuel failure that has occurred? A. Control Room Radiation Monitor B. IRM or SRM indications C. Area Radiation Monitors D. Containment Radiation Monitor Answer: D Question No.: 1-A.2-003 Reference (s): A.2-101, B.5.12-02 i K/A
Reference:
Generic Knowledge and Ability Task Number: 2.4.21 Rating RO/SRO: 3.7 l Monticello JTA: CR999.021 Objective (s): M-8110L 014, EO-4,8 1/cmb I
1 MONTICELLO NUCLEAR GENERATING PLANT M81000-9923 TITLE: 1999 NRC INITIAL REACTOR OPERATOR Revision 0 LICENSE EXAMINATION - ANSWER KEY Page 126 of 127 l Exam Question Number: 100 Point Value: 1.00 Time (Minutes): NA While in C.5-2007 (FAILURE TO SCRAM ) the following plant conditions were noted:
. Reactor power at 16% on APRMs.
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IRMs are being inserted. MSIVs are Closed. Control rods are being inserted using procedure C.5-3101. g . The SBLC Tank drain has cracked and is spilling borated water on the floor. SBLC Tank is 3/4 full and decreasing. Torus temperature is 108' F and increasing. Which of the following will result in the lowest Reactor power? A. Use C.5-3103 Alternate Boron injection with RWCU to inject boron into the Reactor vessel. B. Use C.5-3102 Alternate Boron injection with CRD to inject Boron into the vessel. C. Use C.5-3101 Alternate Control Rod Insertion to shutdown both CRD Pumps. D. Use C.5-2007 Failure to SCRAM to lineup RWCU System for dump flow mode. ( Answer: A Question No.: 1-C.5-2000-014 Reference (s): C.5-2007 K/A
Reference:
Generic Knowledges and Abilities Task Number: 2.4.34 Rating RO/SRO: 3.8/3.6 Monticello JTA: CR314.007, CR314.013 Objective (s): M-8114L-005, EO-6,7; M-8114L-011, EO-1 1/cmb _ _ _ - _ - _ _ _ _ - /}}