ML20212H203
| ML20212H203 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/27/1999 |
| From: | Bies M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20212H208 | List: |
| References | |
| NUDOCS 9909300242 | |
| Download: ML20212H203 (250) | |
Text
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/g neouqg NUCLEAR REGULATORY COMMISSION
[ o REGION lli J* 801 WARRENVILLE ROAD LISLE, ILLINOIS 60532-4351 September 27,1999 NOTE TO: NRC Document Control Desk Mail Stop 0-5-D-24 n - FROM: Mary Ann Bies, Licensing Assistant v . Operations Branch, Rlli i
SUBJECT:
OPERATOR LICENSING EXAMINATION ADMINISTERED THE WEEK OF AUGUST 23,1999, AT THE MONTICELLO NUCLEAR GENERATING PLANT, DOCKET NO. 50-263
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During the week of August 23,1999, Operator Licensing Examinations were administered { at the referenced facility. Attached, you will find the following information for processing i through NUDOCS and distribution to the NRC staff, including the NRC PDR: Item #1 - a) Facility submitted outline and initial exam submittal, designated for distribution under RIDS Code A070. b) As-given operating examination, designated for distribution under RIDS Code A070. Item #2 - Examination Report with the as-given wri* ten examination attached, designated for distribution under RIDS Code IE42. Attachments: As stated V w
l-I I FINAL AS-ADMINISTERED OPERATING TEST FOR THE I MONTICELLO EXAMINATION - THE WEEK OF AUGUST 23,1999 l 1 l 1 l 1 l l I 1 i
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i I l FINAL AS-ADMINISTERED ADMINISTRATIVE JPMS FOR THE MONT10ELLO EXAMINATION -THE WEEK OF AUGUST 23,1999
( MONTICELLO NUCLEAR GENERATING PLANT JpM.nwp.31 001 l TITLE: DETERMINE RADIATION PROTECTION Revision 0 REQUIREMENTS Page 1 of 4 t a we ar,m A MA w:ch u . % ,: b 'rwS& veas warr_eewey; SRO: SRO/RO: X SRO/RO/NLO: NLO: Plant
Reference:
RWP 31 Task Standard: Determine radiation protection requirements and projected whole body exposure for isolation of an HCU. K/A
Reference:
Generic K/A Task No: 2.3.10 Rating RO/SRO: 2.9/3.3 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 l l Simulator: Normal: X l Alternate Maximum Tme to Complete: 20 Min ! In-Plant: X Path: Eme Critical: Yes X No Prepared By: /d'wd/14% Date: 7_ y-pp Reviewed By: Date:
, 7 y.pp Shift Supv/ Shift Mgr Review By M /t1 Date: 7-/y- ?)
Approved By: (Supt Ops Trng) Date: yy.pp v
. i = ;) ? ^..- J , ;. n m me . 6, 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated:
Resp Supv: OTRNG l Assoc Ref: MTCP-3.32 lSR: N Frea: 0 yrs ARMS: JPMRWP31001 l Doc Type: 8505 l Admin initials: Date: 1/cmb w _.
F 4 MONTICELLO NUCLEAR GENERATING PLANT JPM.RWP-31.ooi TITLE: DETERMINE RADIATION PROTECTION Revision 0 REQUIREMENTS Page 2 of 4
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l l Initial Conditions: l HCU 14-23 required to be isolated for accumulator changeout. Initiating Curss: Determine the appropriate RWP, RWP requirements and expected exposure for isola-i tion of HCU 14-23. System draining is not required at this time. Expected time to j complete isolation is one half (1/2) hour l l l l l i I l l i l l l l I/cmb
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r 1 MONTICELLO NUCLEAR GENERATING PLANY JPM-RWP-31 -001 TITLE: DETERMINE RADIATION PROTECTION Revision 0 l REQUIREMENTS Page 3 of 4 l PERFORMANCE INFORMATION [ffggjpgrfgancepJgp,egggg gpg3pggggg@dardggggggggg 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. Clas3 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. exposure. 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! 1 I 1/cmb L
MONTICELLO NUCLEAR GENERATING PLANT JPM RWP.31001 TITLE;l DETERMINE RADIATION PROTECTION Revision 0 REQUIREMENTS Page 4 of 4 M 5 M SIONdi?NUNO[%%E!90!U$9?XEki%EM OS M 1AN W N Initial Conditions: HCU 14-23 required to be isolated for accumulator changeout. gpg!MFARMTHEiEVALUATOR;.WHENiYOU HAVEi,Q,OMP,LETED@EJASigjg3fp3}D3 l [ I e I/cmb
i l 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 l l I l I I 1/cmb -
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Monticello Nuclcar Generating Plant RWP Num 1 ) Rev 16 l RADIATION WORK ?ERMIT 12/15/98 10:15 l Werk Location All Non-Centaminated, Non-High Radiation and Non-Neutr:n Zac_ani:n 1 Areas within the Restricted Area. l Description of Work General entry to perform casks which are passive in nature, as define; in 4 AW! 0,8.04.05, authoritec Ra by the Rac,d.iological Work Control... Other work only as iation Protection Coorcinater. i Radiological Conditions l Location Contact General Area Smearable l mrem /hr mrem /br dpm/100cm?. I RX,TS,RW and Recom Eldgs G/A .2-90 100 ; Admin 31dg Hot Lab, & H&V Km .2-2.5 100 i Access Control .2-2.5 100 l Cond Storage Tanks Basin .2-3 _20 ; Admin,Recom,RW,RX,D/G Reefs .2-30 1:0 TS Roof .2 10: Requirements Exposure Monitoring m_ r_D s Elec:renic Dosimeter - Alarm points 100 mrem /hr and 50 mrem. Entries to the following areas for less than 1 hour per day do not require electronic dosimeters:
- 1) Turbine & Reacter 31dgs Railroad Says,
- 2) Other posted areas outside the power block which are gcVerned under this RWP.
In: ries to Access C:ncr:1 cr the Het Lab under this RMP de ::: recu r5 electronic desimeter use. Other Accraval from the Radiation Protecticn Coordinator SHALL be obtained p'rier to climbing :: :he upper levels (above 3') of any floor or , accessinc areas off of stairways in the Reactor :r Rad Waste Bu11c,in s except 15 the case of using permanently installed ladders or platf:rm: that are NOT posted as Contaminated Areas. Nhen using installed ladders, platforms, or stairways DO NOT access areas bevond the installed ladder, platform or stairway without contactihg the Radiation Protection Coordinator for additional surveys. l Observe the dose rate maps posted in the plant for more precise ! information on dose rates in areas you will be entering. Canvas gloves should be wern when handling or transpcr7 n7 200 3 .. scaffolding, or other equipment that may have a: ::.e ne cee.1 ins'e Ce a C:n aminated Area. Additionally coveralls In:uli ce +:rn v:.
,t c c i s , scaffolding, or other equipment may 2:ne in : n:2:: wl:n your cecy.
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Rev 6 RADIATION WORK PERMIT 09/11/97 14:45 Work Location --
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935 Reactor - Tip Cubicle ) I 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 l Requirements l I Exposure Monitoring TLD Electronic Dosimeter - Alarm points 250 mrem /hr and 100 mrem j High Radiation Area Dose Rate Meter l 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 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.
' All entries to this area other than those listed in the Description of Work section SHALL be approved by the Radiation Protection Coordinator AND your supervisor prior to each specific entry.
Prior to each entry the crew leadperson is to verify with the RPC that l secure cards in the name of the RPC have been placed such that the TIP detectors are held in their shields for the duration of the entry l 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.
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F Monticallo Nuclear Sennrating Plant RWP Num 31 Rov 4 RADIATION WOAK P E 7. M I T 11/04/97 12:30 Work Location 935 Reactor - East and West CRD Accumulator Banks Description of Work General entry to perform valving operations, instrument work or routine surveillances or other tasks which are. passive in nature, as defined in 4 AWI 08.04.05, Radiological Work Control. Other work only as cuthorized 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 Ovsrhead areas above banks 120 10 Requirements Exposure Monitoring TLD Elsctronic 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 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 thnt require manual dexterity. Rsaching 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 loodperson notify the RPC at Ext 1135. Excluded from this requirement aro instrument connections and valve caps. Whsn tool carts are required, use only tool carts labeled as potentially contaminated. Notify the RPC for follow-up smears on carts, tools, and l work areas immediately after job completion. t
- 71878 - J
Montic llo Nuclctr Genersting Plant RNP Num 65 Rev 4 RADIATION WORK PERMIT 04/03/98 12:00 Work Location 935 Reactor - CRD Rebuild . Description of Work G:neral entry to perform tasks which are passive in nature, as defined in 4.AWI 08.04,05, Radiological Work Control. Other work as cuthorized by the Radiation Protection Coordinator. . 1 1 1 Radiological Conditions Location Contact General Area Smearable mrem /hr mrem /hr dpm/100cm2 CRD Rebuild Area General Area 100 6-60 40,000 3 i High Radiation Area Around Drives 450 30-150 120,000 ' Requirements Exposure Monitoring TLD Elsctronic 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 l Class 3 Protective Clothing Minimum requirements for entry. Other NO ENTRY allowed to this area under this RWP when Control Rod Drives are being rebuilt. i
- 50550
MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWI-04.04.01-001 TITLE: ISOLATION OF NO.11 FUEL POOL PUMP Revision 0 i Page 1 of 4 geyapamawawwasq$eas;m at MMWdOBspEB@@@lfigNSEMERSyJREE i re EN $l$GX?"$d250 f knZh 5 di % %Y O; $I?% G4sm gaf +$$k 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 i Pump. l l K/A
Reference:
Generic K/A Task No: 2.2.13 Rating RO/SRO: 3.6/3.8 I Recent Events: None l 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 Other: X Time Critical: Yes X No Prepared By: dg [. %r g/,j Date: 7-/'f6g/ Reviewed By:
/ Date: 7/c/-9 f Shift Supv/ Shift Mgrkview By: #J 4 jr1 ['. BliekI.3 Date: 7.- /C/ ',- 7f Approved By: (Supt Ops Trng) Date: 7_7y, y
, =;.. . 1, .v; iT s -- ~ .1 , o 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated-Resp Supv: OTRNG l Assoc Ret MTCP-3.32 lsR: N Frea: 0 yrs ARMS: JPM4 awl 441001 l Doc Type: 8505 l Admin initials: 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 [EEN did?M k Ef5 k ' E M Y E O 5 $ g}(jy Pg [S g g yd y g y % g jfgj g jjig {gj g gl g ?f y yj 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 Cooling Pump. Maintenance will be repacking the pump. Determine whether the isolation provides adequate protection for maintenance workers who will be work-ing on the pump. I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-AAWi-04.04.01 -001 l TITLE: ISOLATION OF NO.11 FLIEL POOL PUMP Revision 0 Page 3 of 4 ; PERFORMANCE INFORMATION l g(ggeppggncepMyctije[ifygg g7j{iggyjggggjjS_tejgalgNygggggggg STEP 1 Standard: Locates P&iD 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 awl-04.04.01 (EQUlPMENT ISOLATION) for instruction son re-Correct valve position and proper use of viewing isolations. (Not critical portion of Stan-HOLD and SECURE Cards should be verified. dard.) Cue: None Comments: None i STEP 3 Standard: identifies that Valve PC-52-1 is not in- Critical portion of the Standard is the identification cluded on the isolation. of PC-52 not included on the isolation. 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: INFORM EVALUATOR THAT THE TASK HAS BEEN COMPLETED. Cue: None Comments: DO NOT PROMPT! l/cmb
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 and current documentation to verify completeness and adequacy of the 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, i 4.3.12 The isolation reviewer SHALL indicate completion of a satisfactory review by one of the following: 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 l the WO for submittal to the WO Coordinator. . I 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. l 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. i 4.4 Anoroval 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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l MONTICELLO NUCLEAR GENERATING PLANT JPM-4AWl-04.04.01 -001 TITLE: ISOLATION OF NO.11 FUEL POOL PUMP Revision 0 Page 4 of 4 l 1 I 1 i j l 3%(7 tygg;ggggg;$gD1 DATES;QOPJggiglgpg;gggggggpf initial Conditions: No.12 Fuel Pool Cooling Pump is in service. MiyijplNgORMJHElEV6LUATOR;WHENNQU,H6VE COMPEEQEDTHETASig!!g;gf;.gpg 1/cmb c
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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 Cooling Pump. Maintenance will be repacking the pump. Determine whether the isolation provides adequate protection for maintenance workers who will be work-ing on the pump. i l l 1 I l I I I 1/cmb u.
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/IdolationId: 99-80224 v1 ,
Status: DRAFT
Title:
- 11 FUEL POOL COOLING PUMP PACKING REPLACEMENT Asrc Wrk Docs. Oid: 132917
, Icolated For: EAWATZKE'B Prcpared by: Reviewed.by: Equipment Isolated: Equipment: P-7.A, 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 Icolation Instructions: Rectoration Instructions:
-- Tags ------------------------------------------------------------------------
Tcg: 1 Type: SECURE Size: SMALL IV: Y Status: NEW Equipment: '42-3302/CS-1, 11 FPCC PUMP (LOCAL)
' Alt Id: B3302/CS-1 System: FPC - Fuel Pool Cooling and Cleanup Location: Bldg: REACTOR BLDG Floor: 985' ELEVATION Room: RX BLDG 985' FUEL ~ POOL HX RM Remarks: PANEL C-66 Tag Pos:-STOP Norm Pos: START Rsmarks:
CSDS:
.IV: Yen:
Holds: SAWATZKE B i l Tag: 2 Type: SECURE Size: SMALL IV: Y Status: NEW j Equipment: 42-3302/CS-2, 11 FPCC PUMP ' Alt Id: B3302/CS-2 System: FPC - Fuel Pool Cooling and Cleanup Location: Bldg: RAD WASTE BLDG Floor: 935' ELEVATION Room: RW 935' CONTROL ROOM Remaris: PANEL C-88 i Tag Pos: OFF Norm Pos: ON Remarks: i ! CSDS: 1
.IV: Yes:
Holds:
.SAWATZKE B l Tcg: 3 Type: HOLD Size: LARGE IV: Y Status: NEW
( Equipment: B3302, P-7A, 11 FUEL POOL COOLING PUMP 480V SUPPLY System: 480 - 480 V Station Auxiliary u
v' Location: Bldg: TURBINE BLDG Floor: 911' ELEVATION Room: TURB BLDG 911' EAST Remarks: MCC-133A
'Tcg Pos: OPEN Norm Pos: CLOSED Remarks:
CSDS: IV: Yes: Holds: SAWATZKE B Tcg: 4 Type: HOLD Size: LARGE IV: Y Status: NEW j 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 985' FUEL POOL HX RM Remarks: Tag Pos: CLOSED Norm Pos: OPEN Remarks: CSDS: IV: Yes: Holds: I SAWATZKE B Tcg: 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 Remarke: l Tag Pos: CLOSED Norm Pos: OPEN Remarks: CSDS:
'IV: Yes: l
' Holds:
SAWATZKE B Tcg: 6 Type: HOLD Size: LARGE IV: Y Status: NEW Equipment: PC-46-1, 11 FPCC PUMP CASING DRAIN Syrtem: FPC - Fuel Pool Cooling and Cleanup Location: Bldg: REACTOR BLDG Floor: 985' ELEVATION Room: RX' BLDG 985' FUEL POOL HX RM Remarks: Tag Pos: OPEN Norm Pos: CLOSED Rcmarks: a.
I l l CSDS: l IV: Yes: l-Holds: SAWATZKE B 1 l .Tcg: 7 Type: HOLD Size: LARGE IV: Y Status: NEW l Equipment: PC-45-1, 11 FPCC PUMP SUCTION DRAIN System: FPC - Fuel Pool Cooling and Cleanup
' Location: Bldg: REACTOR BLDG Floor: .985' ELEVATION l Room: RX BLDG 985' FUEL POOL HX RM Remarks:
Tag Pos: OPEN Norm Pos: CLOSED Remarks: CSDS: IV: Yes: Holds: SAWATZKE B i ! l l l l l
MONTICELLO NUCLEAR GENERATING PLANT JPM-hDMIN-O-001 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0
'Page 1 of 1
!!!E!!!!!EE4REEIEliEMtEl Question:
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 C-05 operator position. In addition to tne required shift turnover, what additional administrative requirements must be satisfied prior to assuming the duty, and what are your responsibilities as the C-05 Operator after you take 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. The C-05 NPE&RO SHALL be responsible for: a.) Satisfying core monitoring expectations (Section Ill.A). b.) Manipulating Reactor controls in accordance with plant procedures. c.) Informing the Shift Supervisor when unexplained or abnormal Reactor conditions arise.
Reference:
C.1 (STARTUP), pgs 6,10 and 11 of 63 i I I 1/cmb I
MONTICELLO NUCLEAR GE$ RATING PLANT JPM-ADMIN-O-002 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 N l Question: A Reactor Startup is in progress. Part V.A., Step 3 directs the removal of RHR Shutdown Cooling when Reactor Coolant temperature is greater than 110* F. The following step directs you to bring the Reactor Critical. If the Nuclear Engineer requested Shutdown Cooling be removed after the Reactor is Critical, would it be acceptable to perform these steps out of order and why? Answer: Yes. 212* F Reactor temperature is the operating condition which requires RHR LPCI to be i lined up in Standby. Shutdown Cooling is required to be removed between 110*F and i 212*F. The specific sequence of C.1 Steps is flexible for this instance as long as the ; temperature requirements are met. I {C.1 allows flexibility in the sequence of steps provided the following:
- 1. Steps are not omitted.
- 2. Steps are performed in the manner described. I
- 3. Ste as that are called for at or prior to reaching specific operating conditions are per ormed before passing beyond these conditions.}
Reference:
C.1 (STARTUP), pg 4,22,23,27 of 63 I l l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-hDMIN-O-003 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 ggth#&aat'E36xmpggggg 3 f_ ,
- h a ~L83 ic3 EI IC Question:
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 next control rod withdrawn is bypassed by installing a jumper.
Reference:
D.2-05, pgs 27 and 28 of 58 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-hDMIN-O-004 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 ( Page 1 of 1 4
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,k . $i ?YkN E h 5 ?if 5t C U M E'2 3 ::L'a % 2a c G t 2 M E JL Question:
While changing tools on the monorail crane you inadvertently drop an adjustable wrench in the fuel pool. What are your responsibilities in this situation? I Answer: Note where it comes to rest and in. mediately notify the Refuel Coordinator, Shift Supervisor, or Supt. Nuclear Engineering.
Reference:
D.2-05, pg.15 of 58 I l l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-005 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 c
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w+w y20E5D}LTL:OU. . ~ ~5C,'**j[2 $$d 1~l*. w uAU1DE5A i5 CLOSED REFERENCE QUESTION Question: While performing duty activities in the Reactor Building, an announcement over the page system informs all personnel to evacuate the plant. Where should you report? Answer: Control Room
Reference:
A.2-103, pg 9 of 12 i { l/cmb
MONTI(?ELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-006 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 BENEEEEEBEREIE CLOSED REFERENCE QUESTION Question: The fitness of individuals should be assessed prior to their engaging in safety-related emergency response activities. How much time should elapse since consuming alcoholic beverages prior to performing unsupervised emergency duties? Answer: 5 Hours
Reference:
FFD Handbook A.2-106, pg. 5 of 20 1/cmb
1 1 MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-001 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 EMBEtBEREBEM Question: 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 C-05 operator position. In addition to the required shift turnover, what additional administrative requirements must be satisfied prior to assuming the duty, and what are your responsibilities as the C-05 Operator after you take the duty? l l l l l I I l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-002 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1
$ t - L -
Ouestion: A Reactor Startup is in progress. Part V.A., Step 3 directs the removal of RHR Shutdown Cooling when Reactor Coolant temperature is greater than 110' F. The following step directs you to bring the Reactor Critical. If the Nuclear Engineer requested Shutdown Cooling be removed after the Reactor is Critical, would it be acceptable to perform these steps out of order and why?
!lcm' >
MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-003 _ TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 B ER R E RBE R EM E M M X t Question: 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 00? l l i i i l I/cmb
r-l MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-004 l TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 ! Page 1 of 1 i I e ' 5; 1 Question: i While changing tools on the monorail crane you inadvertently drop an adjustable wrench in i the fuel poo . l What are your responsibilities in this situation? l 1 l l/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-005 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 i [4412hiis&^9;333:p Mpj'tp,Q$$tg[31%y+l3g5Q3ggy"ggy ML slPEBFieBifl =tV E$$$8EW# ns/d dudh,%@3f551,E!E$ELiE951NESNIf33E@9d5$e@7~US7 5 CLOSED REFERENCE QUESTION Question: ) I While performing duty activities in the Reactor Building, an announcement over the page system informs all personnel to evacuate the plant. Where should you report? l s_ 1/cmb
i l MONTICELLO NUCLEAR GENERATING PLANT JPM-ADMIN-O-006 TITLE: ADMINISTRATIVE JPM QUESTIONS Revision 0 Page 1 of 1 9' g.;gg s. a w: %. 1
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CLOSED REFERENCE QUESTION j Question: The fitness of individuals should be assessed prior to their engaging in safety-related emergency response activities. How much time should elapse since consuming alcoholic beverages prior to performing unsupervised emergency duties? l l l I/cmb
F l FINAL AS-ADMINISTERED IN-PLANT JPMS FOR THE i MONTICELLO EXAMINATION -THE WEEK OF AUGUST 23,1999 I l { f
g-MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 TITLE: ' CHARGE A HCU Revision 4 I Page 1 of 13 b SRO: SRO/RO: SRO/RO/NLO: X NLO: i i Plant
Reference:
Procedure No. 2188, Rev 10 Task Standard: Simulate nitroger' recharging of HCU 22-51. K/A
Reference:
201001 Task No.: A1.06 Rating RO/SRO: 3.4/3.4 A2.10 3.5/3.6 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
NL201.012 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 20 Min i Simulator: Normal: _ X Alternate Maximum Time to Compiete: 40 Min
.In-Plant: X Path:
Time Critical: Yes X No Prepared By: '/V/ Datgjg j9pp
)
Reviewed By: y Date: 12 M 9i Shift Supv/Shi;b gr Review By: h/f[ Dateqja, jg Approved By: . [ (Supt Ops Trng) Date: gjy _ y 0.@ Y "'" Fi; lu m._ ' h*6 '/ 3087 (DOCUMENT CHANGE. HOLD, AND COMMENT FORM) incorporated-Resp Supv: OTRNG l Assoc Ref MTCP-3.32 lSR: N Freo 0 yrs r ARMS: JPM-813-004 l Doc Type: 8505 l Admin Initials: Date: 1/mif
F MONTICELLO NUCLEAff GENERATING PLANT JPM-B.1.3-004 l TITLE: CHARGE A HCU Revision 4 Page 2 of 13 i l M s$ $ 1 Y M Ellis!$11?32 332FJfE 2 52EPJ g[G yfj g pfj ffg g ggf{;g p[jyjfg l Plant Setup:
- 1. Fill out procedure 2188 for HCU 22-51:
- RWP 31
- Complete PREREQUISITES and sign.
- Sign Shift Supv approval.
- Sign reason for performing Part A.
- Enter HCU on front page.
, 2. Verify all tools are available:
- Obtain key #41 from SS Office.
- Ensure charging cart is available and ready for cW.rging an HCU.
- Cart is to be attended at all times while it is in the Reactor Building.
Initial Conditions: The plant is operating at 100% power and HCU 22-51 accumulator alarm has been actuated due to a low pressure condition. Initiating Cues: l l The 2188, Shift SCRAW Suav ACCU directs UlATORou Ni toOGEN rechabe HCU 22-51 in accordance with Pro CHARGING. Provide operator with a copy of Procedure No. 2188. All prerequisite steps have been
- completed and all necessary tools will be provided. .
ALL OPERATOR ACTIONS ARE TO BE SIMULATED! l l I/mlf
I MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 i TITLE: CHARGE A HCU Revision 4 Page 3 of 13 PERFORMANCE INFORMATION M3.DM!K@gdtliTe'jgg e g g g g Sti'@ arp$g g g'g gff. g STEP 1 (Procedure STEP 1) Standard: l Record AS FOUND accumulator nitro- 1. Operater records pressure from PI-131 on gen pressure indicated on PI-131, HCU HCU 22-51. Accumulator Nitrogen Pressure. 2. Operator calls control room to verify status of AS FOUND pressure = psig accumulator alarm on C-05. i a. JE AS FOUND pressure is less Cue: than 950 psig. 1. As found pressure is 975 psig. i THEN abort th.is procedure, AND initiate a 2188 to charge 2. Accumulator low press alarm is on and amber the accumulator using PART B. light is lit.
- b. .E the AS FOUND pressure is Comments:
ess than 950 psig, WO is not required. l AND annunciator 5-B-38 (CRD ! ACCUMULATOR LO/ PRESS Hl/ LEVEL) is not in ALARM due to low pressure, OR the amber light on Panel C-05 is not on for the HCU being charged, THE 9 initiate a WO to calibrate / ! repa r/ replace pressure switch, i pressure gauge, or light as required, AND record WO number in l COMMENTS section, l AND notify Shift Supervisor to l assess o aerability and reportabi ity concerns. STEP 2 (Procedure STEP 2) Standard: Allow thermometer readout to . stabilize, Allows thermometer to stabilize and then indicates THEN indicate ambient temperature at temperature at HCU by circling value on Table l accumulator by circling value or by using one. l an alternate method to identify the value Cue *- on Table 1,
- AND determine the maximum and mini- After the operator reads the thermometer correctly mum allowable pressures from Table 1. 2*F, inform them that for purposes of this JPM, the temperature is 88*F.
Comments: Thermometers are permanently installed on north end of HCUs near fuse panels l l l I/mit i
t 1 MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 TITLE: CHARGE A HCU Revision 4 j Page 4 of 13 1 , M } g g y M iel g y g g g g gjggg@lg{gSli~n,dhFdggggggg l STEP 3 (Procedure STEP 3) Standard: Verify that CRD-203-1 (CRD-203-2), Verifies CRD-203-2 is closed by attempting to Charging Cart Nitrogen Header Shutoff turn the respective valve handwheel CW l Valve, is CLOSED. Cue: The valve stem is In; CRD-203-2 meets resis-tance and is tight. Comments: Operator may use any method of verification listed in 4 awl-04.04.02. (SEE PAGE 13.) STEP 4 "C" (Procedure STEP 4) Standard: Verify that CRD-202-1 (CRD-202-2), Verifies CRD-202-2 is closed by attempting to turn Charging Cart Nitrogen Header Vent the valve handwheel CW. Valve, is CLOSED. Cue: The valve stem is in: CRD-202-2 meets resistance and is tight. Comments: Operator may use any method of verification listed in 4 awl-04.04.02. (SEE PAGE 13.) STEP 5 "C" (Procedure STEP 5) Standard: Verify that CRD-201-1 (CRD 201-2), Verify CRD-201-2 is OPEN. Charging Cart Nitrogen inlet Isolation Valve, is OPEN. Cue- . Nitrogen cylinder valve stem rises. Comments: Operator may use any method of verification listed in 4 awl-04.04.02. (SEE PAGE 13.) STEP 6 (Procedure STEP 6) Standard: OPEN the nitrogen cylinder valve and Opens the N2cylinder valve by turning counter-verify that the nitrogen charging station clockwise and verifies gas pressure is 2: 100 psig contains sufficient gas pressure for above the maximum allowable pressure. l char,ging at least 100 psig above the Cue-maximum allowable pressure by reading l
- 1. N2cylinder valve stem rises.
l pressure R ^( ggu ke Nitrogen PI-3-232A PI-3-2328), C arging Sta- 2. N cylinder pressure is 1450 psig. I t on P essure. 2 Comments: Maximum allowable pressure is 1201 (Table one). 1/mit
[ , MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004
- TITLE: CHARGE A HCU Revision 4
! Page 5 of 13 ggPjjfoiWiah~6e[Objecggjg gggglggggS1hydarg g g g g g;g STEP 7 "C" (Pr5cedure STEP 7) Standard: CLOSE the Nitrogen Cylinder Valve. Closes Nitrogen Cylinder valve by turning valve handle CW. Cue: Valve stem is in, meets resistance and is tight. Comments: None STEP 8 "C" (Procedure STEP 8) Stardard: OPEN CRD-202-1 (CRD-202-2), Charg- Opens CRD-202-2 by turning valve handwheel ing Cart Nitrogen Header Vent Valve, to CCW. vent the charging station. Cue: CRD-202-2 valve stem rises, escaping air noise is heard and charging line pressure decreases to O psig. (PI 3-2328) Comments: CRD-202-2 does not have to be full oper to vent the charging station. STEP 9 "C" (Procedure STEP 9) Standard: CLOSE CRD-202-1 (CRD-202-2), Closes CRD-202-2 by turning valve handwheel Charging Cart Nitrogen Header Vent CW. Valve. Cue: Valve stem moves in, meets resistance and is l tight. Comments: None STEP 10 (Procedure STEP 10) Standard: CLOSE CRD-111, Accumulator Nitrogen Closes CRD-111 by turning the valve handle CW. Gas Charging Valve, in the accumulator instrumentation block. cue- . Valve stem moves IN, meets resistance and is tight. Comments: None 1/mlf
F 1 MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 j TITLE: CHARGE A HCU Revision 4 Page 6 of 13 grfo@WeAQQgfg ggg g ggfff g ydgggygh pjgg[gg{g STEP 11 "C" (Procedure STEP 11) Standard: FIRST loosen cap at connection P6 to 1. Loosens cap at connection P6 by turning bleed gas pressure from instrumentation CCW with wrench, AND N remove the cap from connection 2. 't t leed from the P6, stru en b!cc A AND connect the gas charging line to 3. Completes removal of P6 connector cap, AND the instrumentation block. 4. Threads the gas charging line connector onto the P6 connector by turning CW, and then tightens down with wrench. Cue:
- 1. P6 connector cap rotates in the CCW direction.
- 2. Sound of escaping gas is present; instrument block pressure has decreased to zero. j
- 3. P6 connector cap is removed.
l
- 4. Charging line connector rotates CW; charging line connection at P6 is tight.
Comments: None STEP 12 "C" (Procedure STEP 13) Standard: OPEN the Nitrogen Cylinder Valve. Opens Nitrogen Cylinder Valve by turning hand-wheel CCW. Cue: Nitrogen Cylinder Valve stem rises, meets resis- i tance and is tight. ! Comments: None STEP 13 "C" (Procedure STEP 13) Standard: Adjust PCV-2444 (PCV-2445), Charg- Selects the correct regulator adjustment handle ing Cart Nitrogen Pressure Regulator, and rotates CW to obtain a setting of approxi-until charging station pressure as indi- mately 975 psig. (Pl 3-232B) cated on PI-3-232A PI-3-2328), CRD Cue A(B) Nitrogen Charg(ing Station Pres-sure,is at the AS FOUND accumulator 1. Adjustment handle turns CW. pressure recorded in STEP 1. 2. Regulator gauge indicates 975 psig. Comments: None I/mit
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 TITLE: CHARGE A HCU Revision 4 i i Page 7 of 13
$M5@Q ggggiggdjjpgiggggyg STEP 14 "C" (Procedure STEP 14) Standard:
OPEN CRD-111, Accumulator Nitrogen Opens CRD-111 by turning the valve T-handle Gas Charging Valve, in the instrumenta- CCW. tion block. Cue: Valve stem moves OUT; CRD-111 meets resis-tance and is tight. Comments: None STEP 15 (Procedure STEP 15) Standard: Opens CRD-203-2 by turning valve handwheel Charging Cart Nitrogen He(ader ShutoffSlowly OPEN CRD-203-1 CRD-203-2), counterclockwise. Valve. Cue: CRD-203-2 valve stem rises, meets resistance and is tight. Comments: None STEP 16 "C" (Procedure STEP 16) Standard: lE the accumulator gas pressure is less Opens PCV-2445 by turning handwheel in the than 50 psid above the target pressure CW (" ection. Increases accumulator pressure by indicated in Table 1, increments of less than 100 psig. THEN: Cue: C 244 ) ha ng art As PCV-2445 is being turned CW, pressure Nitrogen Pressure egulator, in [au e in re se about 50 psig for each move-the gas charging line to raise the - accumulator gas pressure to Comments: than e targ t res ure Accumulator pressure is 975. Target pressure indicated on Ta ale 1 to allow for from Table 1 is 1191. pressure losses which may occur when disconnecting hoses and repressurizing the instrument block. During charging ensure that pressure differential between PI-232A (PI-2328) and PI-131 is less than 100 psid. l l l/mif i l
l MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 TITLE: CHARGE A HCU Revision 4 l Page 8 of 13 ( l _g g a K O Q gpy g [jy gyfjgggg}{gah@Mgjijggggg[gg STEP 17 "C" (Procedure STEP 17) Standard: CLOSE CRD-111, HCU Accumulator Observes pressure gauge and closes CRD-111 Nitrogen Gas Charging Valve. by rotating handwheel fully CW when pressure reaches approximately 1250 psig. Cue:
- 1. Pressure is approximately 1250 psig.
- 2. CRD-111 valve stem moves in, meets resistance, and is tight.
Comments: Closing CRD-111 is the critical part of this STEP. STEP 18 "C" (Procedure STEP 18) Standard: CLOSE the nitrogen cylinder valve. Closes the cylinder shutoff valve by turning valve handwheel CW. Cue: Valve stem moves IN, meets resistance and is tight. Comments: None STEP 19 (Procedure STEP 19) Standard: Back off PVC-2444 (PCV-2445), Charg- Backs off PCV-2445 by turning handwheel CCW ing Cart Nitrogen Pressure Regulator, until it moves freely. until the regulator handle moves freely. Cue: PCV-2445 moves CCW and moves freely. Comments: None STEP 20 "C" (Procedure STEP 20) Standard: Slowly OPEN CRD-202-1 Opens CRD-202-2 by turning valve handwheel in (CRD-202-2), Charging Cart Nitrogen the CCW direction and slowly bleeds pressure Header Vent Valve, to bleed pressure from charging line. from the gas charging line. Cue:
- 1. Valve handwheel rotates CCW.
- 2. Sound of escaping gas is present.
- 3. CRD-202-2 valve stem moves OUT.
- 4. Charging line pressure indicates 0 psig.
Comments: Valve does not have to be full open. 1/mif
1 l - MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 l TITLE; CHARGE A HCU Revision 4
- Page 9 of 13 g [ g g g (a @ O bj @ y?g g g g p y g g g S,t g gE,r g g g } g g g g g STEP 21 "C" (Procedure STEP 21) Standard
Remove the gas charging line from the 1. Using a wrench, loosens the charging line instrumentation block and replace the connector by turning it CCW, then completes cap on connection P6. removal of the charging line connector. l
- 2. Threads cap on P6 connection by turning CW, i then using a wrench, tightens the cap on the P6 connection.
Cue:
- 1. Charging line is removed.
- 2. P6 connection cap is installed and tight.
Comments: None STEP 22 "C" (Procedure STEP 22) Standard: l Slowly OPEN CRD-111, HCU Accumula- 1. Slowly opens CRD-111 by turning the valve ; tor Nitrogen Gas Charging Valve, in the handle CW. instrumentation block and observe the 2. Obser/es pressure indication on PI-131. accumulator pressure shown on PI-131. : Cue:
- 1. Valve stem moves OUT; CRD-111 meets resistance and is tight.
- 2. PI-131 indicates about 1195 psig.
Comments: None STEP 23 "C" (Procedure STEP 23) Standard: Perform the following: Verifies pressure reading is acceptable.
- a. E the pressure is above the Cue: None maximum allowable pressure as Comments.
determined using Table 1, THEN loosen cap on connection Steps are N/A due to acceptable pressure (not P6 to lower pressure below the above or below max or min allowed). maximum allowable pressure.
- b. E the pressure is below the minimum allowable pressure as determined using Table 1, THEN repeat this procedure, OR initiate WO to repair cause for accumulator leakage.
1/mlf
f ) i i MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 TITLE: CHARGE A HCU Revision 4 Page 10 of 13 1 1 g j g j g y p y n W M e g g gjy [g ggyygy;[gy{Fjj,$an,,pp,@ggg[j[ggijggy STEP 24 "C" (Procedure STEP 24) Standard: Veri the accumulator pressure shown 1. Verifies pressure is within allowable band. on P 131 is within the allowable prec. 2. Req ests independent verification of pressure Cue: 1
- 1. Pressure is 1195.
- 2. Independent verification is complete.
Comments: None STEP 25 (Procedure STEP 25) Standard: Snoop the cap on connection P6 and Performs leakage check by " snooping" around CRD-111, HCU Accumulator Nitrogen connection cap and verifying no leakage. Gas Charging Valve, for leakage. Cue:
- a. IF leaka e is present at P6, THEN ti hten or replace P6 cap No bubbles are present.
to stop I akage. Comments: None
- b. lE leakage is present at CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, THEN cycle the valve. Leaving the valve up to 1/2 turn from full OPEN is acceptable if doing so eliminates or reduces leakage.
- c. Note any uncorrected leakage from P6 or CRD-111, HCU Accumulator Nitrogen Gas .
Charging Valve, in COMMENTS. I STEP 26 (Procedure STEP 26) Standard: Verify that the amber light on Panel C-05 Contacts Control Room personnel and requests for the HCU being charged is OFF. the status of accumulator trouble alarm for CRD 22-51. Cue: Amber light for CRD 22-51 is clear. Comments: None STEP 27 "C" (Procedure STEP 27) Standard: Record AS LEFT pressure indicated on Records AS LEFT pressure as cued by examiner. PI-131. Cue: AS LEFT pressure = psig PI-131 indicates 1190 psig. Comments: None I/mlf
r MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 i TITLE: CHARGE A HCU Revision 4 f l Page 11 of 13 l M j g pfy W M IO @ lv,epyg(($3 [gjg$gggs,ygaj,da djgggggyffyfjjp] L STEP 28 (Procedure STEP 28) Standard: , Verify the following: 1. Verifies CRD-111 is OPEN.
- a. CRD-111, HCU Accumulator 2. Verifies CRD-113 is OPEN.
- Nitrogen Gas Charging Valve, 3. Verifies CRD-107 is CLOSED. I OPEN.
- 4. Request independent verification, j
- b. CRD-113, HCU Charging Water lsolation Valve, OPEN. Cue:
- c. CRD-107, HCU Accumulator 1. CRD-111 is verified OPEN.
Water Drain Valve, CLOSED. 2. CRD-113 is verified OPEN.
- 3. CRD-107 is CLOSED.
- 4. Independent verification is complete.
Comments: Operator may use any of the approved methods of valve position verification as specified in 4 awl-04.04.02. (SEE PAGE 13.) STEP 29 Standard: INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted. Cue: None Comments: DO NOT PROMPT! I 1/mit
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 TITLE: CHARGE A HCU Revision 4 Page 12 of 13 i i I l l l g g g g g ggyg g glEgjgOf,7 6 g g g Jgfg g , Initial Conditions: The plant is operating at 100% power and HCU 22-51 accumulator alarm has been ! actuated due to a low pressure condition.
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Initiating Cues: The Shift Supv directs you to recharge HCU 22-51 in accordance with Procedure No. 2188, SCRAM ACCUMULATOR NITROGEN CHARGING. Provide operator with a copy of Procedure No. 2188. All prerequisite steps have been completed and all necessary tools will be provided. ALL OPERATOR ACTIONS ARE TO BE SIMULATED! l W?e9511 JO_R_MjTygglyEOgME,NjYOg,HAV_E[COJ4fLEEDgE} N TASK!!!j?g3M:f3 1/mif i
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.3-004 TITLE: CHARGE A HCU Revision 4 Page 13 of 13 4 POSITION VERIFICATION ATTACHMENT (Excerot out of 4AWi-04.04.02 section 4.5)
- 1. Verification Methods for Manual Valves NOTE: All manual valves in the 'alant are designed so that clockwise rotation of the handwheel is for CLOSib G and counterclockwise is for OPENING.
A. CLOSED Position - When physically checking a valve to be in the CLOSED position, the following SHALL be checked:
- 1. Look at the valve stem.
- a. If it is a rising stem gate valve, the stem will be flush or slightly above the i handwheel.
- b. If it is a globe valve, the stem will be at a minimum length above the valve body.
- c. If the valve has a mechanical indication of valve position, the indicator will point at the closed mark.
NOTE: Never attempt to open a valve to verify that it is CLOSED. Opening the valve may cause equipment damage or jeopardize personnel safety. l
- 2. Attempt to turn the valve handwheel in the clockwise (CLOSED) direction. If the valve is closed, the handwheel should not move.
B. OPEN Position - When physically checking a valve to be in the OPEN position, the following SHALL be checked:
- 1. Look at the valve stem.
- a. If it is a rising stem gate valve, the stem will be extended beyond the handwheel.
- b. If it is a glove valve, the stem will be exposed between the handwheel and valve body.
- c. If the valve has mechanicalindication of valve position, the indicator will point at the open mark.
NOTE: Do not attempt to turn a handwheel in the counterclockwise direction to check a valve in the OPEN position. If the valve has been closed for a specific reason, opening the valve may cause equipment damage or jeopardize personnel safety.
- 2. If position cannot be verified visually, attempt to turn the valve handwheel in the clockwise (CLOSED) direction. If the valve is OPEN, the handwheel will move. Turn the handwheel in the counter-clockwise direction to return it to the fully OPEN position.
1/mif
F? i l l Question #: . JPM-B.I.3-004-Ql Point Value:1.0 Time (Minutes): NA l l If alarm 5-A-27 activates and a control rod is slowly inserting from position 48 to 00, l what would be the cause of frilure? 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 l l I i i
r 1 l Question #: JPM-B.I.3-004-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. i 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. I Reference (s): C.2-01, pg 9 of 15 K/A
Reference:
K5.05 Task Number: 201003 Rating RO: 3.0 i l l
HCU-Q2 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? I i { i l
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IICU - Q1 l If alarm 5-A-27 activates and a control rod is slowly inserting from position 48 to 00, what would be the cause of failure? i i
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\ ' 1 Initial Conditions: The plant is operating at 100% power and HCU 22-51 accumulator alarm has been actuated due to a low pressure condition. Initiating Cues: The Shift Supv directs you to recharge HCU 22-51 in accordance with Procedure No. 2188, SCRAM ACCUMULATOR NITROGEN CHARGING. Provide operator with a copy of Procedure No. 2188. All prerequisite steps have been completed and all necessary tools will be provided. l ALL OPERATOR ACTIONS ARE TO BE SIMULATED! MINE,QRMiTH,EEEVAEUATORtWilENiYsO_UIEfAVEECO_MRl!EEEDEHESTASK!!!QQg4:J l
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c l ) MONTICELLO NUCLEAR GENERATING PLANT 2188 l TITLE: SCRAM ACCUMULATOR NITROGEN Revision 1 l CHARGING Page 1 of 18 l REVIEW AND' APPROVALS Prepared By: @)gf/ /QGg Reviewed By: COaq. OC Review Req'd: YES OC Meeting Number:g[g7 Date: .2/n/pg OC Results Review Req'd: NO[) ,f ,f[/ Date: 09/10/81 Approved By: ! Date: a/25[99 ( )
- REVIEW AND APPRMOF ACTIVITIES DATE Shift Supv Approval to Commence: Time:
Operator: Completed By Shifi Supervisor: Completion Reviewed Engineer: By OC Results Reviewed at Meeting Number: NA NA L COMMENTS Enter HCU Number (s): WO(S) ISSUED YES NO NUMBER (S) l 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated: If-MD Resp Sun NUC l Assoc Ref B.1.3 d SR: Y Frea: i yrfe e ARMS: 2188 l Doc Type: 1030 l Admin initials: Dated 4/fNF/ l I/jik
MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 2 of 18 PURPOSE The purpose of this procedure is to charge the gas side of the scram accumulator in the hydraulic control unit following maintenance or following a 5-B-38 ACCUMULATOR LO/ PRESS Hl/ LEVEL) ALARM, whichdwas cause(CRD by accumulator low nitrogen pressure, and to verify accumulator pressures are below the maximum allowable pressures, following CRD hydraulic system startup. This procedure may be used to Ch CPJ14. char eingan accumulator Water Header (s) Isolation Valve, OPEN or CLOSED.with or without a CRD STEF.315,16.a.,44,45.b., and 46.c. include the recommendations of GE SIL No. 536, HCU Liquid Level Switch Malfunction. REFERENCES
- 1. NX-7866-79-1, Hydraulic Contr'ol Unit Instruction Manual
- 2. P&lD M-119
- 3. Technical Specification 3.3.D/4.3.D
- 4. , GE SIL No. 536, HCU Uquid Level Switch Malfunction
- 5. Ops Man Section B.1.3-05.02 (CRD HYDRAULIC SYSTEM STARTUP)
- 6. CR98000574 (Combine 2048 and 2188)
- 7. CR91000330 (HCU Uquid Level Switch Malfunctioil) l PERSONNEL Operators (2)
EQUIPMENT - HCU Accumulator Nitrogen Charging Station Adjustable Wrench Thermometer Snoop Cap for P6, if required, (NSP Stock Number REDSEW) PRECAUTIONS 1. An imphrnrly person uryloosened or equipment capdamage. at connection P6 may give way under pressure causing
- 2. Damage to the HCU liquid level switch can be caused by high velocity nitrogen impingement during charging operations. Keep the pressure differential across
! CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, less than 100 psid by keeping the pressure difference between PI-3-232A (PI-3-2328) and PI-131 to !sss than 100 psid. 1/jlk
MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 3 of 18
- 3. IE a scram occurs while performing this proceduro, THEN CLOSE CRD-111 HCU Accumulator Nitrogen Gas Charging Valve, AND CLOSE CRD-107,'HCU Accumulator Water Drain Valve, AND leave the area.
Notify Radiation Protection Coordinator before continuing procedure.
- 4. Instruction steps identified with'a "$" SHALL be satisfactorily completed to meet an OETS recommendation. If one of these steps cannot be satisfactorily completed, contact the System Engineer.
- 5. Tech Spec 3.3.D requires accumulators to be operable, with certain exceptions.
Accumulators with low pressure shouid be recharged as soon as possible to prevent inoperability. REASON FOR PERFORMING PROCEDURE Check One
- 1. Char psig.ge an accumulator with an as-found pressure of at least 950 Typically used t 3ressure following a 5-B-38 (CRD ACCUMULATOR LO/ PRESS
-lI/ LEVEL) ALARM which was caused by accumulator low nitrogen
- pressure. Complete PART A.
- 2. Charge an accumulator with an as-found pressure less than 950 psig.
Typically used to charge a nitrogen accumulator from atmospheric pressure to the proper pressure. This is the preferred method of charging after an accumulator was discharged for maintenance. , Perform PART B.
- 3. Charge multiple accumulators to the proper pressure. For each HCU to be charged, complete PART B for esch accumulator which has an AS FOUND pressure below 950 psig; PART A for each accumulator which has an AS FOUND pressure greate than or equal to 950 asig.
For the first accumulator, record data and sign offs in the body of this procedure, for subsequent accumulators, record data and sign offs ori~ Table 2.
- 4. Verify accumulator pressures are below the maximum allowable pressure. Complete PART C.
- 5. Other - Specify in COMMENTS section. Note steps to be performed and requirements satisfied if any.
PREREQUISITES Initial
- 1. RWP established. RWP No.
Rad Prot Coord
- 2. CRD-14 position established. OPEN CLOSED Shift Supv
- 3. CRD pump status established. RUNNING STOPPED Shift Supv l/Jik
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MONTICELLO NUCLEAR GENERATING PLANT 2188 l TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 4 of 18 PROCEDURE 1rstiaj PART A NOTE: Since the pressure switch PS-130, Accumulator Low Nitrogen Pressure, Is set at 1000 psig with a potential drift of 50 asig, annunciator 5-B-38 (CRD ACCUMULATOR LO/ PRESS.H !/ LEVEL) may not ALARM until the actual pressure is as low as 950 psig. JE t le accumulator pressure is less than 950 psig, WHILE the mode switch is not in shutdown, _ l OR the control rod for the associated HCU is not " full in" with its directional control valves electronically disarmed, THEN there may be o serability and re sortability concerns that need to be addressec by shift supery;sion. STEP 1 Record AS FOUND' accumulator nitrogen pressure indicated on PI-131, HCU Accumulator Nitrogen Pressure. AS FOUND pressure = psig
- a. IE AS FOUND pressure is less than 950 psig, THEN N/A the remainder of PART A, AND charge the accumulator using PART B.
- b. JE the AS FOUND pressure is less than 950 psig, WHILE annunciator 5-B-38 (CRD ACCUMULATOR l LO/ PRESS Hl/ LEVEL) is not in ALARM due to low pressure,
_OR the amber light on Panel C-05 is not on for the HCU being charged, THEN initiate a WO to calibrate / repair / replace pressure switch, pressure gauge, or l'ght as required, AND record WO number in COMMENTS section, AND notify Shift Supervisor to assess operability and . reportability concerns. STEP 2 Allow thermometer readout to stabilize, T[iEN_ indicate ambient temperature at accumulator by circling value or by using an alternate method to identify the value on Table 1, AND determine the maximum and minimum allowable pressures from Table 1. , STEP 3 Verify that CRD-203-1 (CRD-203-2), Charging Cart Nitrogen l Header Shutoff Valve, is CLOSED. STEP 4 Veri y that CRD-202-1 (CRD-202-2), Charging Cart Nitrogen Header Vent Valve,is CLOSED. STEP 5 Verify that CRD-201-1 (CRD-201-2), Charging Cart Nitrogen inlet isolation Valve, is OPEN. 1/jik PART A
Efl$ELLO NUCLEAR GENERATING PLANT 2188 l ! TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 l CHARGING Page 5 of 18 l l STEP 6 OPEN the nitrogen cylinder valve and verify that the nitrogen charging station contains sufficient gas pressure for charging at least 100 psig above the maximum allowable pressure by reading pressure gauge PI-3-232A (PI-3-2328), CRD A(B) Bank Nitrogen Charging Station Pressure. STEP 7 CLOSE the nitrogen cylinder valve. STEP 8 OPEN CRD-202-1 (CRD-202-2), Charging Cart Nitrogen Header Vent Valve, to vent the charging station. , STEP 9 CLOSE CRD-202-1 (CRD-202-2), Charging Cart Nitrogen Header Vent Valve.
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STEP 10 CLOSE CRD-111, Accumulator Nitrogen Gas Charging Valve, in the accumulator instrumentation block. STEP 11 FIRST loosen cap at connection P6 to bleed gas pressure from instrumentation block, 1 THEN remove the cap from connection P6, AND connect the gas charging line to the instrumentation
, block.
STEP 12 OPEN the nitrogen cylinder valve. STEP 13 Adjust PCV-2444 (PCV-2445), Chargin,g Cart Nitrogen Pressure Regulator, until charging station pressure as indicated on PI-3-232A (PI-3-2328), CRD A(B) Nitrogen , Charging Station Pressure, is at the AS FOUND l accumulator pressure recorded in STEP 1. STEP 14 OPEN CRD-111, Accumulator Nitrogen Gas Charging Valve, in the instrumentation block. .
$ STEP 15 Slowly OPEN CRD-203-1 (CRD-203-2), Charging Cart Nitrogen Header Shutoff Valve (OETS Item 91000330). l l STEP 16 JE the accumulator gas pressure is less than 50 psid above the tar THEN:get pressure indicated in Table 1,
- $ a. Slowly OPEN PCV-2444 (PCV-2445), Charging Cart Nitrogen Pressure legulator, in the gas charging line to raise the accumulator gas pressure to a aproximately 50 l
psid greater than the target pressure inc icated on Table 1 to allow for pressure losses which may occur when disconnecting hoses and repressurizing the instrument ! block. During charging ensure that pressure differential between PI-232A (PI-2328) and PI-131 is less than 100 psid (OETS Item 91000330). l I/jlk PART A
y --- MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 l CHARGING Page 6 of 18 l STEP 17 CLOSE CRD-111, HCU Accumulator Nitrogen Gas Charging Valve. , STEP 18 CLOSE the nitrogen cylinder valve. STEP 19 Back off POV-2444 (PCV-2445), Charging Cart Nitrogen Pressure Regulator, until the regulator handle moves freely. STEP 20 Slowly OPEN CRD-2b2-1 (CRD-202 2), Charging Cart Nitrogen Header Vent Valve, to bleed pressure from the gas charging line. i STEP 21 Remove the gas charging line from the instrumentation block and replace the cap on connection P6.
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STEP 22 Slowly OPEN CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, in the instrumentation block and observe l the accumulator pressure shown on PI-131. STEP 23 Perform the following:
- a. E the pressure is above the maximum allowable
, pressure as determined using Table 1, TF EN loosen cap on connection P6 to lower pressure ,
be ow the maximum allowable pressure.
- b. E the pressure is below the minimum allowable pressure as determined using Table 1, THEN repeat this procedure, QB initiate WO to repair cause for accumulator leakage.
STEP 24 Verify the accumulator pressure shown on PI-131 is within the allowable pressure band. Performed By: Independently Verified By: STEP 25 Snoop the caa on connection P6 and CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, for leakage.
- a. Eleakage is present at P6, THEN tighten or replace P6 cap to stop leakage.
- b. E leakage is present at CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, THEN cycle the valve. Leaving the valve up to 1/2 tum from full OPEN is acceptable if doing so eliminates or reduces leakage.
- c. Note any uncorrected leakage from P6 or CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, in COMMENTS.
Ifjlk PART A
c MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 7 of 18 STEP 26 Verify that the amber light on Panel C-05 for the HCU being charged is OF,F. STEP 27 Record AS LEFT pressure indicated on PI-131. AS LEFT pressure = psig STEP 28 Verify the following: l a. CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, OPEN. l b. CRD-113, HCU Charging Water Isolation Valve, OPEN.
- c. CRD-107, HCU Accumulator Water Drain Valve, CLOSED.
l Performed By: l Independently Verified By: 1 ( 1/jlk PART A
I . MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 8 of 18 PART B l NOTE: Since the pressure swi{ch PS-130, Accumulator Low Nitrogen ! Pressure, is set at 1000 psig with a potential drift of 50 psig, annunciator 5-B-38 (CRD ACCUMULATOR LO/ PRESS Hl/ LEVEL) l may not ALARM until the actual pressure is as low as 950 psig.
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E tl1e accumulator pressure is less than 950 psig, i WHILE the mode switch is not in shutdown, l l OR the control rod for the associated HCU is not " full in" with its l l directional control valves electronically disarmed, ; THEN there may be o serability and re portability concerns that l need to be addressec by shift supervision. !
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STEP 29 Record AS FOUND accumulator nitrogen pressure indicated on PI-131, HCU Accumulator Nitrogen Pressure. l l AS FCOND pressure = psig ; l I a. E AS FOUND pressure is greater than or equal to 950 psig, THEN N/A the remainder of PART B. ! , AND charge the accumulator using PART A.
- b. E the AS FOUND pressure is less than 950 psig, WHILE annunciator 5-B-38 (CRD ACCUMULATOR [
LO/ PRESS Hl/ LEVEL) is not in ALARM due to low ; pressure, l OR the amber light on Panel C-05 is not on for the HCU 1 being charged, l THEN inrtiate a WO to calibrate / repair / replace pressure switch, pressure gauge, or light as required, AND record WO number in COMMENTS section, AND notify Shift Supervisor to assess operability and reportability concerns. STEP 30 Allow thermometer readout to stabilize, I THEN indicate ambient temperature at accumulator by i circling value or b l value on Table 1, y using an alternate method to identify the i AN_Q determine the maximum and minimum allowable ! l pressures from Table 1. E STEP 31 Verify that CRD-203-1 (CRD-203-2), Charging Cart Nitrogen Header Shutoff Valve,is CLOSED. , 1 STEP 32 Verify that CRD-202-1 (CRD-202-2), Charging Cart Nitrogen . Header Vent Valve, is CLOSED. STEP 33 Verify that CRD-201-1 (CRD-201-2), Charging Cart Nitrogen inlet isolation Valve, is OPEN. 1/jlk PART B i
1 l MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 9 of 18 STEP 34 OPEN the nitrogen cylinder valve and verify that the nitrogen charging station contains sufficient gas pressure for charging at least 100 psig above the maximum allowable pressure by reading pressure gauge PI-3-232A (PI-3-2328), CRD A(B) Bank Nitrogen Charging Station Pressure. STEP 35 CLOSE the nitrogen cylinder valve. STEP 36 OPEN CRD-202-1 (CRD-202-2), Charging Cart Nitrogen Header Vent Valve, to vent the charging station. STEP 37 CLOSE CRD-202-1 (CRD-202-2), Charging Cart Nitrogen Header Vent Valve. STEP 38 Perform the following:
- a. CLOSE CRD-113, HCU Accumulator Charging Water I Header Isolation Valve. -
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- b. Remove drain line pibg, AND connect drain hose to route water through CRD-107, HCU Accumulator Water Drain Valve, to the
- floor drain.
- c. Slowly open CRD-107, HCU Accumulator Water Drain l Valve, to drain the water accumulator. The water accumulator is fully drained when the nitrogen pressure as shown on PI-131, HCU Accumulator Nitrogen Pressure, remains constant.
STEP 39 CLOSE CRD-111, Accumulator Nitrogen Gas Charging Valve, in the accumulator instrumentation block. STEP 40 FIRST loosen cap at connection P6 to bleed gas pressure ~ from instrumentation block, THEN remove the cap from connection P6, AND connect the gas charging line to the instrumentation block. _ STEP 41 OPEN the nitrogen cylinder valve. STEP 42 Adjust PCV-2444 (PCV-2445), Chargin,g Cart Nitrogen Pressure Regulator, until charging station pressure as indicated on PI-3-232A (PI-3-2328), CRD A(B) Nitrogen Charging Station Pressure,is at the AS FOUND accumulator pressure recorded in STEP 29. STEP 43 OPEN CRD-111, Accumulator Nitrogen Gas Charging Valve, in the instrumentation block.
$ STEP 44 Slowly OPEN CRD-203-1 (CRD-203-2), Charging Cart Nitrogen Header Shutoff Valve (OETS Item 91000330). l I/jlk PART B
l l MONTICELLO NUCLEAR GENERATING PLANT 2188 i TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 10 of 18 HOTE: STEPS 45a. through d. will likely need to be repeated to move the piston to the top of the. accumulator as desired. STEP 45 Perform the following:
- a. CLOSE CRD-107, HCU Accumulator Water Drain Valve.
~$ b. Slowly OPEN PCV-2444 (PCV-2445), Charging Cart Nitrogen Pressure Regulator, in the gas charging line to raise the accumulator gas pressure to approximately 620 psig (590-650) as indicated on pressure gauge l PI-131. During char differential between1-3-232A iging ensure that pressure (PI-3-2328) and PI-131
~ is less than 100 psid (OETS ltem 91000330). l l Opening CRD-107 will cause the piston in the accumulator to move from I the bottom toward the top of the accumulator. When the piston moves upward, water will be discharged through CRD-107. n
- c. SLOWLY OPEN CRD-107, HCU Accumulator Water Drain Valve. ,
- d. WHEN water discharge through CRD-107 stops, THEN CLOSE CRD-107, HCU Accumulator Water Drain Valve.
- e. Verify PI-131 is reading between 590 and 650 psig.
Repeat STEPS 45a. through d. as needed to accomplish this.
- f. Disconnect drain hose, AND replace drain line plug.
- g. CLOSE CRD-203-1 (CRD-203-2) Charging Cart Nitrogen Header Shutoff Valve,
- h. Slowly OPEN CRD-113, HCU Accumulator Charging Water Header Isolation Valve. Allow about 1 minute after valve is full open for pressure to stabliize.
- i. lE a CRD pump is running,
/.ND CRD-14 is OPEN, THEN verify the nitrogen pressure increased to approximately double its initial pressure. This assures that the accumulator piston is free to move, since the charging water has displaced the piston and compressed the nitrogen in the cylinder.
1/jlk PARTB
MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 11 of 18 STEP 46 lE a CRD pump is running, AND CRD-14 is OPEN, A_JLQ the accumulator gas pressure is less than 50 psid above the target pressure indicated in Table 1, THEN:
- a. Adjust PCV-2444' (PCV-2445), Charging Cart Nitrogen Pressure Regulator, until charging station pressure as
, indicated on PI-3-232A (PI-3-2328), CRD A(B) Nitrogen Charging Station Pressure, .is approximately equal to the current accumulator pressure as indicated on PI-131.
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- b. OPEN CRD-203-1 (CRD-203-2) Charging Cart Nitrogen Header Shutoff Valve.
$c. Slowly OPEN PCV-2444 (PCV-2445), Charging Cart Nitrogen Pressure Regulator, in the gas charging line to raise the accumulator gas pressure to a ] proximately 50 psid greater than the target pressure inc icated on Table 1 to allow for pressure losses which may occur when
,, disconnecting hoses and repressurizing the instrument block. During charging ensure that pressure differential between PI-232A (PI-232B) and PI-131 is less than 100 psid (OETS Item 91000330). l STEP 47 CLOSE CRD-111, HCU Accumulator Nitrogen Gas Charging Valve.
STEP 48 CLOSE the nitrogen cylinder valve. STEP 49 Back off PCV-2444 (PCV-2445), Charging Cart Nitrogen Pressure Regulator, until the regulator handle moves freely. STEP 50 Slowly OPEN CRD-202-1 (CRD-202-2), Charging Cart Nitrogen Header Vent Valve, to bleed pressure from the gas charging line. STEP 51 Remove tha gas charging line from the instrumentation block and replace the cap on connection P6. STEP 52 Slowly OPEN CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, in the instrumentatinn block and observe the accumulator pressure shown on PI-131. 1/jik PART B
i 1 MONTICELLO NUCLEAR GENERATING PLANT 2168 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 12 of 18 STEP 53 E a CRD pump is running, AND CRD-14 h OPEN, 4 N IliE.N_:
- a. E the pressure is above the maximum allowable pressure as determined using Table 1, Tid EN loosen cap on connection P6 to lower pressure be ow the maximum allowable pressure.
- b. E the pressure is beiow the minimum allowable pressure as determined using Table 1, THEN repeat this procedure, OR initiate WO to repair cause for accumulator leakage.
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STEP 54 Verify proper accumulator pressure by performing either of I the foi owing: 1
- a. E a CRD pump is running, AN_D CRD-14 is OPEN, THEN the accumulator pressure shown on PI-131 is within the allowable pressure band per Table 1.
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- b. E a CRD pump is NOT running, OR CRD-14 is CLOSED, THEN accumulator pressure is between 590 and 650 ps;g.
Performed By: Independently Verified By: l STEP 55 Snoop the cap on connection P6 and CRD-111,4iCU Accumulator Nitrogen Gas Charging Valve, for leakage.
- a. Eleakage is present at P6, ..
T_idE.itighten f or replace P6 cap to stop leakage.
- b. Eleakage is present at CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, THEN cycle the valve. Leaving the valve up to 1/2 turn from full OPEN is acceptable if doing so eliminates or reduces leakage.
- c. Note any uncorrected leakage from P6 or CRD-111,
- HCU Accumulator Nitrogen Gas Charging Valve, in COMMENTS.
STEP 56 Verify that the amber light on Panel C-05 for the HCU being charged is OFF, STEP 57 Record AS LEFT pressure indicated on PI-131. AS LEFT pressure = psig 1/jlk PART B
l MONTICELLO NUCLEAR GENERATING PLANT 2188 l TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 l CHARGING Page 13 of 18 I STEP 58 Verify the following:
- a. CRD-111, HCU Accumulator Nitrogen Gas Charging Valve, OPEN.
- b. CRD-113, HCU Charging Water Isolation Valve, OPEN.
- c. CRD-107, HCU Accumulator Water Drain Valve, CLOSED.
Performed By: Independently Verified By: l I/jik PART B
MONTICELLO NUCLEAR GENERA 11NG PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 14 of 18 PART C STEP 59 Allow thermordeter readout to stabilize, THEN indicate ambient temperature at the EAST BANK accumulators by circling value and writing EAST nearby or by using an alternate , method to identify the temperattre on Table 1, AND determine the maximum allowable pressure from Table 1. IE th,e pressure of any EAST BANK HCU is above the maximum allowable pressure, THEN: ~
- a. Record the HCU number and the AS FOUND aressure~
indicated on PI-131 for the HCU in the COMM ENTS section.
- b. Loosen the cap on connection P6 to lower the pressure' below the maximum allowable pressure.
. c. Snoop the cap on connection P6 for leakage.
lEleakage is present, THEN tighten or replace P6 to stop leakage. Note any uncorrected leakage in COMMENTS.
- d. Record the AS LEFT pressure indicated on PI-131 in the COMMENTS section.
STEP 60 Allow thermometer readout to stabilize, THEN indicate ambient temperature at the WEST BANK accumulators by circling value and writing WEST nearby or by using an alternate method to identify the temperature on hble 1, I AND determine the maximum allowable pressure from Table 1. l lE th,e pressure of any WEST BANK HCU is above the maximum allowable pressure, , THEN: ! i
- a. Record the HCU number and the AS FOUND pressure indicated on PI-131 for the HCU in the COMMENTS 5
section. ,
- b. Loosen the cap on connection P6 to lower the pressure I below the maximum allowable pressure.
t 1/jik PART C
m i 1 MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 15 of 18
- c. Snoop the cap on connection P6 for leakage, lEleakage is present, IHEN tighten or replace P6 to stop leakage.
Note any uncorrected leakage in COMMENTS.
- d. Record the AS LEFT pressure indicated on PI-131 in the COMMENTS section.
l l 1 1/jik PART C
l l MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 16 of 18 Table 1 wiTemperatureg ~ Minimum' Allowable Pressure 4 q arge1Nitr, ogen Pressure e5 . Maximum' Allowable Pressure. , N(bedIdd$5I2 i$$8SI$[d510$5dSI7$5 Ew.ieIM(psidI'dE$$2kN [E55$N[MgY$[3$$d$ l 60 1117 1127 1137 61 111 9 1129 1139 62 1122 , 1132 1142 63 i. 44 1134 1144 l 64 1126 1136 1146 65 1129 1139 1149 66 1131 1141 1151 67 1133 1143 1153 68 1135 1145 1155 69 1138 -- 1148 -1158 70 1140 1150 1160 71 1142 1152 1162 72 1145 1155 1165 73 1147 1157 1167 74 1149 1159 1169 75 1152 1162 1172 76 1154 1164 1174 77 1156 1166 1176 78 1158 1168 1178 79 1161 1171 1181 80 1163 1173 1183 81 1165 1175 1185 82 1168 1178 1188 83 1170 1180 1190 84 1172 1182 1192 85 1175 1185 1195 86 1177 1187 1197 87 1179 1189 1199 88 1181 1191 1201 89 1184 1194 1204 90 1186 1196 1206 91 1188 1198 1208 92 1191 1201 1211 93 1193 1203 1213 94 1195 1205 1215 95 1198 1208 1218 96 1200 1210 1220 97 1202 1212 1222 98 1204 1214 1224 99 120't 1217 1227 100 1209 1219 1229 ff)\k
p l MONTICELLO NUCLEAR GENERATING PLANT 218e TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 I CHARGING Page 17 of 18 l
- l. Table 2 1
i @yI6] 4Ef$m,bleM$3 GREE %EMSi2ER 3ffB3ME65f 15:ida @; STEP 24;(54)(Y l-ASfOUNDN", I@SfEpp Ngd jndsphiidsnityVeriiisd" l n." M g ;McGinsE%&lfp;fGcd2ilS)d PECUr fdi?4TempWtn m> Pressure #6 42;PJessure&gJ Mh;pTEP e f?e'rforme24 (54)]$h By42
@QMF41ByMf5%ij (Degrees F) (psig) (psig) 1 1
i I l
.w l
1 1/jik
~
MONTICELLO NUCLEAR GENERATING PLANT 2188 TITLE: SCRAM ACCUMULATOR NITROGEN Revision 11 CHARGING Page 18 of 18 BASES The data in Table 1 was obtkined by using Figure 3.2 and Section 3-15 of NX-7866-79-1 ! on nitrogen charging to create a table rather than a graph for ease of use when performing this procedure. The 950 psig criteria used in STEPS 1 and 29 of this procedure was chosen by knowledge that when an accumulator is being charged during normal 3lant oparation the minimum pressure should be at least 950 psig. 950 psig is low enouglio allow a simplified method of charging during normal plant operation, and high enough to ensure that the accumulator will be precharged when the accumulator is being charged from an initially low pressure. ~ Sign off blanks are included for each step if the REASON FOR PERFORMING i PROCEDURE is to charge a' single accumulator. If the REASON FOR PERFORMING PROCEDURE is to charge multiple accumulators, a reduced set of sign offs (Table 2 used. It is expected that this procedure will occasionally be used to charge a single ) ; accumulator, and that the Operator charged an accumulator, therefore ultiplem(s) signperforming theOperator offs ensure the procedure may with is familiar not have rece the procedure and that he completes all steps. When multiple accumulators are being charged, the Operator charged, therefore multip (s)le sign offs are not required, and only those steps wh significant need to be documented. When charging multiple accumulators, the Operator should sign the multi]!e steps for the first accumulator charged, and each subsequent accumulator chargec should be recorded in Table 2. PART C was added to provide a method to verify accumulator pressures are below the maximum allowable pressure, Excess accumulator pressure could result in internal CRD damage in the event of a scram. This section is intended to be used shortly after startup if the accumulators were charged without charging water pressure available. 1/jik
l MONTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS Page 1 of 6 EEEEEBREMEXEEME SRO: SRO/RO: SRO/RO/NLO: X NLO: Plant
Reference:
B.9.12-05.D.1, Rev 4 Task Standard: Startup the No.11 RPS MG Set K/A
Reference:
Generic,212000 Task No.: 2.1.30, Rating RO/SRO: 3.9/3.4, K1.04 3.4/3.6 Recent Events: None Probabilistic Risk Assessment Human Error: None 1 Monticello Specific Task List
Reference:
NL212.003 j l METHOD OF TESTING TIME FOR COMPLETION l Estimated Time to Complete: 10 Min ; Simulator: Normal: X Alternate Maximum Time to Complete: 20 Min l In-Plant: X Path: Tme Critical: Yes X No Prepared By: gM- fy[ Date:g ja, )999 Reviewed By: gg Date: g_g , g l Shift Supv/ Shift Mgr Review By: MM /P( Dateg /4, /997 Approved By: gg (Supt Ops Trng) Date:g-g .77 l l 1 .= ;v "9 . -i nva S ** N.: i ~
/.
3087 (DOCUMENT CHANGE. HOLD. AND COMMENT FORM) incorporated-Resp supv: OTRNG l Assoc Ref MTCP-3.32 lSR: N Frea: 0 yrs ARMS: JPMB912001 l Doc Type: 8505 l Admin in tials: Date: 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS Page 2 of 6 JPM SET-UP - Plant Setup: None i 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. Initiating Cues: ' The Shift Supv directs you to startup No.11 RPS MG Set and place it on RPS Bus A. I ALL OPERATOR ACTIONS ARE TO BE SIMULATED! l 1/cmb i
MONTICELLO NUCLEAR GENERATING PLANT dPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS Page 3 of 6 PERFORMANCE INFORMATION
& ' LPerformance Objective. Standard '
STEP 1 Standard: Locate procedure B.9.12-05.D.1., "MG Locates appropriate procedure. Set Startup". Cue: l Provide operator with a copy of procedure. Comments: None 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 cortion of Standard)
- 1. Operator should remove access cover from No.11 RX PROTECTION M-G SET control panel to allow access to controls.
- 2. 03erator should observe that the red POWER O 4 light is lit.
Cue: > The cover plate is removed and the red POWER l ON light is lit. Comments: None STEP 3 "C" (Procedure STEP 2) Standard: Press drive motor START button. Momentarily depresses No.11 RX PROTECTION 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 cortion of Standard) Operator should observe local volt meters. Cue:
- Drive motor is running. AC VOLTS meter indica-l tion is increasing.
! Comments: None I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS Page 4 of 6 T6g.g . . Performance. Objective _ JStandardi. ;yy
- 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 volt-age. 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 pushing it up-ward to the ON position. (Non-Critical cortion 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 l I/cmb
f MONTICELLO NUCLEAR GENERATING PLANT JPM-B.9.12-001 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS Page 5 of 6 y ; Performance; Objective: Standard:: , 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. E starting up MG Set A, down to reset the breaker then upward to the THEN CLOSE breaker on ON position.
(Non-Critical cortion of Standard) ID._ CL SE breaker on l EPA-154. 1. Upon closing the output breaker for EPA-153,
- b. E starting up MG Set B, the operator should verify:
THEN CLOSE breaker on a. The red POWER OUT light on EPA-153 is I EPA-156, lit AND CLOSE breaker on AND 1 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. i Cue:
- 1. When the operator looks at EPA prior to operating 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 i STEP 8 (Procedure STEP 7) Standard: None To reset and close the output breakers Cue: None on the EPA units associated with t Comments: ternate source, perform the follow,he ing in al-the order written: The operator should determine it is not necessary to, complete this step of the procedure due to initi-
- a. 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. l Cue: None Comments: DO NOT PROMPT! 1/cmb
1 MONTICELLO NUCLEAR GENERATING PLANT JPM.B.9.12-008 TITLE: STARTUP THE REACTOR PROTECTION Revision 3 MOTOR GENERATORS Page 6 of 6 i i I I fQgghgyjg}ggg?gpQifyANgiD,AT.ESfCOPXppfigggggggggjg Initial Conditions: Reactor is in cold shutdown with a Refuel Outage in progress. "A" RPS is de-ener- l 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. Initial 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! fg sf +.-INFORM-THEEVALUATOR.WHEN YOU HAVE COMPLETEDJHELTASK!!!i-1%p,2@; I l l l l ! i l l 1/cmb l J
n , L ,
-l Question #: JPM-B.9.12-001-Ql Point Value:1.0 Time (Minutes): NA l I l .-
Blockage in the East SDV results in increasing water level in the SDV. SDV water level ! reaches the point that relays SAK1C 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.5.6-06 K/A
Reference:
212000 Task Number: A4.12 ! Rating RO: 3.9 l l l
f - s l
- -l Question #
- JPM-B.9.12-001-Q2 Point Value:1.0 Time (Minutes): NA l
- l. . -
! An inadvertent opening of 52-307.results in an auto close of 52-209. The length of time . l- for this evolution was approximately one-half second. What is the status of the RPS bus ifpower was supplied through CB1 A and CB1B during
- l. the event? -
Answer: Both RPS busses will remain energized, and both RPS MG sets will remain running. The , flywheel on MG Set A'will retain voltage for up to 2 seconds. l Reference (s): B.9.12-02, pg 3 of 5; B.9.12-06, Figure 1, page 3 of 6 K/A
Reference:
2.1.28-Task Number: 212000 Rating RO: 3.2 l I I'
r: l RPS - Q2: l l: l An inadvertent opening of 52-307 results in an auto close of 52-209. The length of time ! { for this evolution was approximately one-halfsecond. I What is the status of the RPS bus if power was supplied through CBI A and CBIB during the event? l i l l
F 1
- RPS - Q1: - - Blockage in the East SDV results in increasing water level in the SDV. SDV water level reaches the point that relays 5AKlC on panel C-15 and 5AKID on panel C-17 de-energize. What is the status of the Reactor Protection System?
f I i o l i
'l
)
l I l i I l , ! ) J
{ ? I l ENM635!$[M#MiFij%UhD.CAN DIDATES CORRQ3ggggy;i j ipygyp3gggj l 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 i closed. CB1 A is closed and CB2A is open in Cable Spreading room. Initial 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! !
$ . INFORM:THEEVALUATOR WHEN YOU' HAVE COMPCETED7HETASK!!!Mg,q@ 'l/cmb l
L
MONTICELt.O NUCLEAR GENERATING PLANT JPM-C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 FOR RPV MAKEUP Page 1 of 5 gggymmagsp; ppg Mr "~~* 3 J2M R ENEESWS M31Enners 19
$sd SRO: SRO/RO: SRO/RO/NLO: X NLO:
Plant
Reference:
C.5-3203, Part D, Rev 1 Task Standard: Simulate Using Fire Water Cross-tie to LPCI K/A Refarence: Generic,286000 Task No.: 2.1.23, Rating RO/SRO: 3.9/4.0, A1.05 3.2/3.2 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 Time to Complete: 20 Min in-Plant: X Path: Time Critical: Yes X No Prepared By: [M /7[ Date-g /.0, /997 Reviewed By: b f Date: g_g, pp Shift Supv/ Shift Mgr Review By: [d/'P/ Dateg p,ffg7 Approved By: y h !(Supt Ops Trng) Date:g,.7g ,p 7~ . . . ..- .__. 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated: Resp supv: OTRNG l Assoc Ref- MTCP-3.32 lSR: N Fren: 0 yrs ARMS: JPMC53203001 l Doc Type: 8505 l Admin initials: Date: 1/cmb
i MONTICELLO NUCLEAR GENERATING PLANT JPM-C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 FOR RPV MAKEUP Page 2 of 5
.u g -
JPM SET-UP ,J >; Plant Setup: Hand candidate Part "D" only. Initial Conditions: The plant is in an emergency condition requiring the use of Alternate injection Sys-tems for RPV Makeup. The Diesel Fire Pump ,s i 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 steps only. ALL OPERATOR ACTIONS ARE TO BE SIMULATED! 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM.C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 FOR RPV MAKEUP Page 3 of 5 PERFORMANCE INFORMATION 3 ' Performance, Objectives .t Standard:. -_,.. STEP 1 Standard: Locate procedure C.5-3203 (USE OF Locates appropriate procedure. ALTERNATE SYSTEMS FOR RPV Cue: 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. Cue: RHRSW-13 moves in dockwise direction, stem lowers, meets resistance and is tight. Comments: None STEP 3 (Procedure STEP 2) Standard: Verify CLOSED RHRSW-12, EMER Verifies RHRSW-12 closed. INJECTION VIA 11 LOOP. Cue:
- 1. RHRSW-12 when attempt to move clockwise, 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 (Procedure STEP 3) Standard: Verify Closed the following valves: Calls 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 i
- 4. MO-2007 (RHR "B" DISCHARGE 4. MO-2007 TO TORUS-OUTBOARD) l I/cmb 1
l MONTICELLO NUCLEAR GENERATING PLANT JPM-C.5-3203-001 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 FOR RPV MAKEUP Page 4 of 5 l f.ft 7 Performance' Objective ' ' Standard - ,.
~
7 I 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 cortion of Standard)
- b. HR W MER INJECTION Informs Control Room STEP 4 is complete.
Cue: RHRSW-46 and RHRS$N-14 handwheels move in 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! i 4 1/cmb
F MONTICELLO NUCLEAR GENERATING PLANT JPM-C.5-3203-008 TITLE: USE OF ALTERNATE INJECTION SYSTEMS Revision 4 j FOR RPV MAKEUP Page 5 of 5 l I i 2g$$$yggsyygg.i$ygg$$gygyA,NQ!gATEgggfyggjg(yggggpyggggggggpj Initial Conditions: The plant is in an emergency c6ndition 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 steps only. ALL OPERATOR ACTIONS ARE TO BE SIMULATED!
?;;gg+ Y;;~ ilNEORM1THE EVALUATOR WHEN YOU HAVECOMPLETED.THETASKl!D'Q,G;3)$?
I/cmb
r l Question #: JPM-C.5-3203-001-Ql Point Value: 1.0 Time (Minutes): NA Only P& ids may be used for reference material Besides Diesel fire pump injection, what other systems can be used to inject through
. MO-2012 and MO-20147 Answer:
Note: Question No. I must be asked prior to Question No. 2
- 1. RHRSW
- 2. ' Condensate service through the pressurizing station.
]
Reference (s): C.5-3203, pg 2; P&ID M-112 (RHR SERVICE WATER) D,6 P&ID M-121 (RESIDUAL HEAT REMOVAL SYS) C.2 K/A
Reference:
A1.05 Task Number: 286000 Rating RO: 3.2 1 l l I l I t r
l l l Question #: JPM-C.5-3203-002-Q2 l Point Value: 1.0 Time (Minutes): NA l During an emergency, the SS directs you to line-up and inject with RHRSW Pump No. 11, the only available pump. When opening the LPCI injection valves, what is the { maximum flow that can be placed on the pump without causing damage? 1 j Answer: Note: Questions No. I must be asked prior to Question No. 2. 6000 gpm. Reference (s): B.08.01.03-05, pg 4 of 27 K/A
Reference:
EA1.08 Task Number: 295031 Rating RO: 3.8 l 1 l l l l i
l ! Alternate Injection - Question 2 During an emergency, the SS directs you to line-up and inject with RHRSW pump No. I1, the only available pump. When opening the LPCI injection valves, what is the maximum flow that can be placed on the pump without causing damage? l t
F 1 l i I Alternate Injection - Question I
- Only P& ids may be used for reference material l
Besides Diesel fire pump injection, what other systems can be used to inject through l MO-2012 and MO-2014? 1 l I l l 1 l 1 l l
gej}$?jRf}$43@Mj$$fECANDIDATES;COPYppy;pg7,gt!gggfg;gsp initial Conditions: The plant is in an emergency condition requiring the use of Alternata .'njection Sys-tems for RPV Makeup. The Diesel Fire Pump is operating, RHREW 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 steps only. ALL OPERATOR ACTIONS ARE TO BE SIMULATED! I';R . ilNEORMiTHE EVALUATOR WHEN YOU HAVECOMPLETED THE TASK!!!$%Q133 i l I/cmb' L.
FINAL AS-ADMINISTERED SIMULATOR JPMS FOR THE MONTICELLO EXAMINATION -THE WEEK OF AUGUST 23,1999 l l l l L...
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM Revision 6 Page 1 of 7 1 1
=
.a.
~~~amsgrs&ane=samensp@w@rar w w. B!.BEB
,. u. we E.,GBm,
-n lE gm. .E.. ..ASM..y 5fGEM. s B_E. t ... %
c1 - _ Msta.u 2&K::a La%L>x Edi ' = ^ . =:;. ,.u . w w ' n,:.: . SRO: SRO/RO: X SRO/RO/NLO: NLO: Plant
Reference:
B.02.02-05.D.1, 8.02.02-05.G.1, Rev 14 i Task Standard: Place RWCU System in Service with No.11 RWCU Pump and 11 RWCU Filter /Demineralizer in Service K/A
Reference:
204000 Task No.: A2.04 Rating RO/SRO: 2.7/2.9 l A4.01 3.1/3.0 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
CR204.003 l METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 10 Min Simulator: X Normal: Alternate Maximum Tme to Complete: 20 Min in-Plant: Path: X Tme Critical: Yes X No Prepare'd By: /7L Date:Qug //,1997 I ( ' Reviewed By: j Date: ; { q Shift Supv/Shi gr Review By: /d d r Date:% u, /977
/
Approved By: g (Supt Ops Trng) Date: g 7; y v FAE2%DMINNTR ATIVMIN#nNf' 3087 (DOCUMENT CHANGE. HOLD. AND COMMENT FORM) incorporated-Reso suov: OTRNG l Assoc Ret MTCP-3.32 lsR: N Frea: 0 yrs ARMS: JPM822001 l Doc Type: 8505 l Admin Initials: Date: 1/cmb
~_ ,
f MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM Revision 6 Page 2 of 7 l l N$-MENiNE@$$:EMNipygyggjS,hT-UR5?gggt.f fif.G$1Tigyp. jgy . y Simulator Setup: Initialize to any IC with the Reactor shutdown, <212*F and RWCU out of service. l RWCU system should be unisolated with both pumps off. Insert the following IOS to cause a failure of No.11 RWCU pump to start: S26-02 (A520P28-26), Digital Value to OFF, INSERT. Initial Conditions: The Reactor is Shutdown and Reactor coolant temperature is <212*F. Preparation for a plant outage is 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 Instru-ment Air are operating properly. Initiating Cues: The Shift Supv directs you to place No.11 RWCU system in service by performing STEPS 12 through 14 of the RWCU system startup procedure B.2.2-05.D.1. STEPS 1 - 11 have been successfully completed. When STEP 14 is complete, begin Reactor vessel draining to the hotwell using ! procedure 8.02.02-05.G.1 and establish approximately 20 gpm dump to the condenser hotwell. I 1/cmb l
II MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM Revision 6 l . Page 3 of 7 PERFORMANCE INFORMATION EgggggminKObjejtigg3gg gj5@Jff?.JQ]pta,ngay,dyggq 6-3p = , 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 STEP 2 "C" (Procedure STEP 12) Standard: CAUTION Attempts to start A RWCU pump using HS-12A-SS, realizes pump does not start. Noti-STEP 13 must be performed immedi- fies Shift Supv' ately following STEP 12. (Non-Critical portion of Standard) Start a Reactor Water Cleanup pump using the Pump A or Pump B switch for Operator should observe the following: the desired pump.
- 1. Pump run indication does not change from green to red.
- 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: Have operator call Booth for all operations. STEP 3 "C" (Procedure STEP 12) Standard: CAUTION Starts B RWCU pump using HS-12A-S6. STEP 13 must be performed immedi- (Non-Critical cortion of Standard) ately following STEP 12. Operator should observe the following: ng he Pum or up$ ch for 1. Pump run indication changes from green to re . the desired pump.
- 2. CLEANUP PUMP DISCH pressure as indicated on PI-12-131 increases.
Cue: None Comments: None l 1/cmb j
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001
- TITLE
- STARTUP THE RWCU SYSTEM Revision 6 l -
Page 4 of 7 l l F8&IlerfQFrnEhce'Qbl{clij,ejgg, spj g g 5i{. p g e,Stajl d ard h j g ; p; p, STEP 4 (Procedure STEP 13) Standard: NOTE 1: The AIR-TO-LOCK- Directs the Radwaste APEO to slowly OPEN GAUGE will indicate CV-12 4-15A. : about 3 psig when the valve starts to open. (Non-Critical portion of Standard) NOTE 2: At flow >35 gpm the Operator should observe the following: , HOLDING PUMP will trip 1. C04-B-21, CLEAN UP F!LTER 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: To Booth. 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 cortion of Standard) 4 Operator should observe that FILTER A FLOW as indicated on F1-12-141 A increases to =70 gpm. 4 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. i i I/cmb
l MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM Revision 6 Page 5 of 7 g@j,Rgorrnanc.e;ObjiecfVeE;92,ffye @ 5 T g g g g g t g d g g g g g g g ; g g .] STEP 6 Standard: Locate procedure B.02.02-05.G.1, Locates appropriate procedure. Reactor Vessel Draining During Cold Cue. None Shutdown Conditions. . Comments: None STEP 7 (Procedure STEP 1) Standard: Verif OPEN RC-8, EXCESS DUMP Notifies APEO to verify RC-8 OPEN. STO . Cue: APEO verifies RC-8 OPEN. Comments: None STEP 8 (Procedure STEP 2) Standard: CLOSE Bkr B3201. Notifies APEO to CLOSE Bkr B3201, AND verify green light ON for MO-2401. Cue: APEO has completed closing of Bkr B3201. Comments: None STEP 9 "C" (Procedure STEP 3) Standard: OPEN MO-2401, DISCHARGE ORI- Places HS-12A-51 for MO-2401 in the OPEN FICE BYPASS. position and verifies valve fully opens. (HOLD to OPEN.) Cue: None > Comments: None STEP 10 "C" (Procedure STEP 4) Standard: OPEN MO-2404, DUMP TO HOTWELL) Places HS-12A-52 for MO-2404 to the OPEN (or MO-2405, DUMP TO WASTE COL- position and verifies valve fully opens. LECTOR AND WASTE SURGE TANKS). Cue: None Comments: None STEP 11 (Procedure STEP 5) Standard: Ensure that the reactor vessel is vented Verifies MSIVs are open. (Red switch lights are through the main steam line isolation ON.) valves (MSIVs) or the reactor head vent Cue.. None valves (CV-2371 and CV-2372). Comments: None I/cmb
f MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2 2-001 TITLE: STARTUP THE RWCU SYSTEM Revision 6 Page 6 of 7 [EMd.P;,pffo~drisri6e;O,bje,ctivejy@g QgggggpjSpiidajg;gE:3jpgggg STEP 12 "C" (Procedure STEP 6) Standard: OPEN CV-2403, DUMP FLOW, using Adjusts / turns FC-12-143 in the clockwise direc-hand control on Panel C-04. tion to open CV-2403 and establish 20 gpm ( 2.5) dump flow to condenser. Cue: None Comments: None STEP 13 (Procedure STEP 7) Standard: Verify that flow through each filter /demin Observes flow indicator F1-12-141 A and adjust does not exceed 85 gpm. MO-2399 and/or CV-2403 to maintain <85 gpm filter flow. , Cue: None Comments: None l STEP 14 (Procedure STEP 8) Standard: Monitor water levels in the reactor and Monitors both reactor and hotwell water levels. hotwell (or radwaste tanks). Cue: Another operator will be assigned the responsibil-ity to monitor reactor and hotwell levels. Comments: None STEP 15 Standard: INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted. Cue: None Comments: DO NOT PROMPT! I/cmb
t MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.2-001 TITLE: STARTUP THE RWCU SYSTEM Revision 6 Page 7 of 7 CANDIDATESiCOPJgg Initial Conditions: The Reactor is Shutdown and Reactor coolant temperature is <212 F. Preparation for a plant outage is in progress. The RWCU system is ready for operation. The No.12 ! RWCU Filter is being backwashed and will be put in service later. I The RWCU pumps and heat exchangers are filled and vented. RBCCW and Instru-ment Air are operating properly. Initiating Cues: The Shift Supv directs you to place No.11 RWCU system in service by performing STEPS 12 through 14 of the RWCU system startup procedure B.2.2-05.D.1. STEPS 1 - 11 have been successfully completed. When STEP 14 is complete, begin Reactor vessel draining to the hotwell using l procedure B.02.02-05.G.1 and establish approximately 20 gpm dump to the i condenser hotwell. EgiRQCJNEO_RMjTfHiEEVACUATO RjWH ENJ,0UiHAVECO MPjETED gLESTA_Sggplgg$f 1/cmb
r )
~
l Question #: JPM-B.2.2-001-Ql Point Value: 1.0 Time (Minutes): 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 I 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 maximum dump flow is established and why? (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 K/A
Reference:
A4.03 Task Number: 204000 Rating RO: 3.2 O l l l l
l l l Question #: JPM-B.2.2-001-Q2 l Point Value: 1.0 Time (Minutes): NA l Soon after returnmg No. I1 RWCU filter to service, Reactor conductivity increases to the 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 hours, then initiate an orderly plant shutdown and cold shutdown achieved within 16 hours. Reference (s): C.2-05, pg.14 of 20 K/A
Reference:
K3.01
- Task Number: 204000 Rating RO: 3.2 i
l
II l l RWCU - Q2 Soon after returnmg No.11 RWCU filter to service, Reactor conductivity increases to the 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? l i l
r; c- RWCU-Q1 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 maximum 4 dump flow is established? (Assume Reacter pressure is 750 psig and very slowly q decreasing.)
, )
l l 1 I i l 4 i i I
p i l, l l t l l l l M,MCANDIDATES]CO,P,,Kp@W ..---ggggiMigjig Initial Conditions: l The Reactor is Shutdown and Reactor coolant temperature is <212*F. Preparation for . a plant outage is in progress. The RWCU system is ready for operation. The No.12 l RWCU Filter is being backwashed and will be put in service later. I The RWCU purnps and heat exchangers are filled and vented. RBCCW and Instru-ment Air are operating properly. _ initiating Cues: The Shift Supv directs you to place No.11 RWCU system in service by performing i STEPS 12 through 14 of the RWCU system startup procedure B.2.2-05.D.1. 1 STEPS 1 - 11 have been successfully completed. l When STEP 14 is complete, begin Reactor vessel draining to the hotwell using procedure B.02.02-05.G.1 and establish approximately 20 gpm dump to the condenser hotwell. , MfgglNfpRMjTHEEVACUATOR;WHENNOU HAVECOMPJETEDJTJHJQE TAJK!!!iM*Qy 1 i I/cmb
[ , l l MONTICELLO NUCLEAR GENERATING PLANT JpM.B.4.4.cos l TITLE: START NO.11 RECIRC PUMP Revision 0 j [ Page 1 of 7 l
,N* y ??:msFKraMMi&EEEmmam7gMMEdiz M Gff H g g !G 2 8 Q %i G 5 5{g SRO: SRO/RO: X SRO/RO/NLO: NLO:
Plant
Reference:
B.1.4-05.02, Rev 8 1 Task Standard: Complete STEPS 1 through 6 of B.1.4-05.02 for Starting No.11 Recirc Pump Only K/A
Reference:
202001 Task No: A4.01 Rating RO/SRO: 3.7/3.7 ; Recent Events: None i Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
CR202.009 - METHOD OF TESTING TIME FOR COMPLETlON 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: // 4M Date:q n, /MS Reviewed By: v Date: y g qq Shift Supv/ Shift W r Review By: Md M Date:% 11, I WI Approved By: ,
} (Supt Ops Trng) Date: g g , g 9 l
l I I snvanaankminarivdimvnerv l 3087 (DOCUMENT CHANGE. HOLD, AND COMMENT FORM) incorporated-Resp Supv: OTRNG l Assoc Ref- MTCP-3.32 lSR: N Frea: 0 yrs ARMS: JPMB14004 l Doc Type: 8505 l Admin initials: Date: 1/cmb
l MONTICELLO NUCLEAR GENERATING PLANT JPM.B.1.4-004 l TITLE: START NO.11 RECIRC PUMP Revision 0 Page 2 of 7 E25$5$$5f$$84EEjs[YdlEdEkid.PMiSyffj{f36g33gdygftggp 3 g,, , Simulator Setup: Initialize to an IC 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 l JPM. MO-2-53A Open MO-2-43A Closed i 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 level is above 30". Initiating Cues: The Shift Supv directs you to perform a cold of start No.11 Recirculation Pump. 1/cmb
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1 1 MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.4-004 l > TITLE: START NO.11 RECIRC PUMP Revision 0 l Page 3 of 7
)
1 PERFORMANCE INFORMATION Eddf2$fpgajge!Qpggt1geMygg f ,, jggjgy].yfj@Stan~dard.;.7gg.pg, _ STEP 1 Standard: Locates procedure and verifies all pre- Locates procedure B.01.04-05.02.A.1, and requisites are met. verifies all necessary prerequisites are completed. ! Cue: Bus 11 is being supplied from 2R Transformer. ! operator verifies knife switch 4 in Panel C-31 is { closed. Comments: Procedure B.1.4-05.02. STEP 2 (Procedure STEP 1) Standard: Complete Form 2114 (Prestart Checklist None
- Reactor Recire System).
Cue: Form 2114 is complete for the Reactor Recirc System. Comments: None 1 STEP 3 "C" (Procedure STEP 2a) Standard: Verify the following for start of 11 Recirc Places MO-2-53A handswitch to the CLOSE l pump: position and verifies valve closes. ' Valve MO-2-53A,11 RECIRC PUMP Cue: None DISCHARGE CLOSED. Comments: Verification is performed by observing the green I
" closed" indicating light on.
STEP 4 "C" (Procedure STEP 2b) Standard: Valve MO-2-43A,11 RECIRC PUMP Places MO-2-43A handswitch in the OPEN posi-SUCTION OPEN. tion and verifies valve opens. 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 approximately 2.55 ( ) for 11 2-184-22A reads approx 2.55 (2.45 - 2.65). Recirc Pump. Cue: None j Comments: None I/cmb
MONTICELLO NUCLEAR GENERATING PLANT J P M.B.1.4-004 TITLE: START NO.11 RECIRC PUMP Revision 0 Page 4 of 7 gge,rfo665nce!ObjectiveM@$/. Ef3jy,ggy{fS,tanJard).gg.pg , . 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 handswitch (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:
" ign ith the valve 1. MG Set Drive Motor light indication changes
]ntrol -
from green to red, AND Place 11 MG Set drive motor control switch to START and observe: 2. Generator speed peaks at a point between 80 and 100% speed, as indicated on meter Si
- a. Generator speed peaks 2- 4-16A, Pump Speed.
between 80 to 100% speed (because field generator breaker is OPEN). 3. Generator field breaker closes about 6 seconds after the drive motor breaker is ergtra pl ox break f b. closed, as indicated by the indicating light a ely 6 seconds after drive motor fNDging from green to red, breaker is CLOSED
- 4. After the field breaker closes, generator
- c. Generator speed lowers to speed slowly decreases to 40% speed and h then lowers to minimum (approx. 30%).
lowers to n mum speekn Cue: None Comments: None I/cmb j
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.4-004 TITLE: START NO.11 RECIRC PUMP Revision 0 Page 5 of 7 g;gP qrmari6sjObjelcgeQQgg @f50]QfgjS,tand,argTggyjg;9 t - 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 l PUMP DISCHARGE, from green to red. ; AND observe the following: (Non-Critical cortion 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 - min 6500 GPM on F1-2-159A.
rated (6 x 106 lb/hr). b. Pump speed remains constant
- d. Pump Current - 50 (Normal for SI-2-184-16A.
25% speed)
- c. Jet Pump Flow - Flow on FI-2-3-928 is
- e. Pump Volts - 900 (Normal for dependent on plant condition.
25% speed)
- d. Pump Amps - min 50 on 2-184-22A
- f. Drive Motor Amps - 150 (Normal for 25% speed) e. Pump Volts - min 900 on 2-184-23A.
- g. Valve AO-2-2-11 A,11 REClRC I-
$IVe M tor Amps - min 150 on 2-4,24A-PMP SEAL LEAKOFF is OPEN as indicated on Panel C-04 g. Seal Leakoff Block valve light indication, (green light off). SV-2-2-11 A, is no longer lit.
Cue: Call booth. Comments: If candidate questions indicated flow is higher (~10,000 gpm) vs procedure flow, (6,500 gpm) ' inform candidate that 6,500 gpm is the minimum acceptable flow and that 10,000 gpm is expected under present plant conditions. 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: approximately 60% by Outlet of lube oil heat exchanger is 100*F. control rod withdrawal per Ops. Manual C.1 (Startup Comments: None Procedure). Monitor and adjust service water at 11 MG Set oil cooler to maintain lube oil temperature at approximately 100*F leaving the cooler. 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.1.4-004 TITLE: START NO.11 RECIRC PUMP Revision 0 Page 6 of 7 hkWggadrisnce;O.bjectiverfs!W EM),'gyggS,tandaggg 59 9 STEP 12 "C" (3) (Procedure STEP 6) Standard: NOTE TO SIMULATOR OPERATOR: Operator Actions: C.6-4-B-25 (RECIRC PUMP
- 1. AFTER RO calls APEO to MOTOR "A" HI VIBRATION) adjust / monitor oil temperature, 1. Operator monitors Recirc pump motor activate RR08A (RECIRC PUMP vibration and temperatures on TR-2-2-31, MOTOR "A" HI VIBRATION) at point 1 and 2 on C-21 and SPDS screen 510, 99% severity, point REC 126.
- 2. When candidate trips recirc 2. Operator dispatches Rx Bldg APEO to the pump, delete malfunction RR08A. Recirc MG Set Room to:
- a. Determine Recirc pump motor vibrations
- 1. Monitor "A" Pump Motor on VM-5603 temperatures and vibration via Cue:
SPDS and TR-2-2-31 (C-21)' When candidate dispatches APEO to MG Set
- 2. Dispatch an operator to the Recirc Room, inform him vibration on No.11 pump motor MG Set Room to determine "A" is at 5 mils. and oil flow and temperature appear Recirc Pump Motor vibration as to be normal. (NOTE: Vibs only with pump run-indicated on localindicator ning.)
-5603.
- 3. Operator determines vibrations are high and
- 3. E "A" Recirc Pump Motor vibration trips A Recirc MG Set per B.01.04-05.
H rp Re cM et per a. p v mo e ith HS RECIRCULATION SYSTEM - b. Closes discharge valve with HS V-2-53A. SYSTEM OPERATION). 4. Notifies the following:
- 4. E"A" Recirc Pump Motor vibration drops below 3 mils, a. Shift Supervision THEN perform the following: Comments: None
- a. RESET vibration annunciator by depressing "A" Recirc Pump Vibration Monitor Resat pushbutton on C-04.
- b. Continue monitoring "A" Recirc Pump Motor vibration and bearing temperatures.
- 5. Nctify the following:
- a. Shift Supervision
- b. System Engineer STEP 13 INFORM CANDIDATE THAT JPM IS COMPLETE.
(Pre-approved prompt) I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JpM.B.9.a. coa TITLE: START NO.11 RECIRC PUMP Revision 0 Page 7 of 7 l 1 l l E kbbEd$y_jpjgy]{GyfAg g]g{jpg,Py@{g3y{yg e {yjg gyj{j]jyygg Initial Conditions: ) A Reactor startup is planned for next shift. All control rods are fully inserted and reac- I 1 tor water level is above 30". Initiating Cues: The Shift Supv directs you to perform a cold of start No.11 Recirculation Pump. RRY$" f.QN_F,O_RMiTHEEVACUATO3WHENWOU]iAV_E;C_OMREETEDiTH_EETASK!!ggg:fglR ( l i ! I/cmb
p-l Question #: JPM-B.1.4-004-Ql Point Value: 1.0 l Time (Minutes): NA l CLOSED BOOK /NO REFERENCE MATERIAL ALLOWED. During normal system operation, what are four (4) non-electrical conditions that will trip the Recire Generator Drive Motor breaker? Electrical Drive Motor Breaker Tries:
- 1. Control Switch to Stop
- 2. Drive Motor Bus Undervoltage
- 3. Generator Lockout Relay Tripped
- 4. Auto Transfer of Station Aux Answer: (Any 4 of 6)
- 1) Low lube oil press (6 sec. Delay) 4)
- Pump disch. valve <20-25% open
- 2) Lube oil high high temperature 5) Low-Low water level (-47 inches)
- 3) Pump Suction valve <90% open 6) Auto initiation of LPCI j i
'66 sec. Time delay on pump start. I Reference (s): B.I.4-02, pg.12 and 13 of 14 K/A
Reference:
A3.09
- Task Number: 202001 Rating: .RO 3.3 l
l l l- 1 I l
p l o l l l i l Question #: JPM-B.1.4-004-Q2 Point Value: 1.0 l 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 levelindicators.) l Answer: When feedwater flow decreases to <20% for 15 seconds, the Recire MG 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 1 I l l 1 i 1 l 1 l l l l I l } l' ;
r l l Recire - Q2 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 level indicators.) l I l ) l l
g. i' Recire- Q1 CLOSED BOOK /NO REFERENCE MATERIAL ALLOWED. During normal system operation, what are four (4) non-electrical conditions that will trip the Recire Generator Drive Motor breaker? Electrical Drive Motor Breaker Trips:
- 1. Control Switch to Stop l 2. Drive Motor Bus Undervoltage i 3. Generator Lockout Relay Tripped
- 4. Auto Transfer of Station Aux l
l l 1
4:.,:y? ^4 >,..?i,5fjf2LQQgif DfAJ}$;90QfG_fgRfG]gfg?ggfg Initial Conditions: A Reactor startup is planned for next shift. All control rods are fully inserted and reac-tor water level is above 30". Initiating Cues: The Shift Supv directs you to perform a cold of start No.11. Recirculation Pump. gTgM41NEORMiTHEEVAliUATORiWHENgO_U!HAVECOg!!ETEDITHET:ASK!!!SgffgQt T i l l l I I/cmb 1 i E- .
I MONTICELLO NUCLEAR GENERATING PLANT J PM.C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 1 of 10
- Egijjig;geg-;3;ggpfzg;;.gy.giggrgy.pggsgge 3 RERFfGBMENGEiM$SWFJEG M EW3aEAmesmmishem%mJe@t; 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:
241000 Task No.: A4.11, Rating RO/SRO: 3.1/3.1, Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
CR245.005 METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 15 Min Simulator: X Normal: X Alternate Maximum 11me to Complete: 30 Min in-Plant: Path: Time Critical: Yes X No Prepared By: [t.u./-/7/ Date:q /a. /997 Reviewed By: Date: 3 ja _9 g Shift Supv/ Shift Mgr Review By: [.x.u/--/9( Date-q /4 jyg Approved By: (Supt Ops Trng) Date: g_g. p p v
' n m 3SmeNC
~
i ~' . . - > . ,, O.* - 3087 (DOCUMENT CHANGE. HOLD, AND COMMENT FORM) incorporated-Resp Suov: OTRNG l Assoc Ret MTCP 3.32 lSR: N Freo: 0 yrs ARMS: JPMC1002 iDoc Type: 8505 l Admin initials: Date: 1/cmb
r MONTICELLO NUCLEAR GENERATING PLANT J P M-C.1 -002 l TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 2 of 10 l I ERM12SEGEG2;&&EEEss3PgSETjuPy',,,4psj{l;MQjjig ]gj[4 l Simulator Setup: { initialize to any IC with the Turbine speed at 1800 rpm and ready for loading. Load I limit, at 90%, speed / load changer adjusted for about 1800 rpm, Voltage Regulator at l minimum. { 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. Initiating Cues: The Shift Supv directs you to synchronize Main Generator to the grid and pickup mini-mum load in accordance with the Startup Procedure C.1, Section VI.C. 1 i I/cmb
l l MONTICELLO NUCLEAR GENERATING PLANT J p M.C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 3 of 10 PERFORMANCE INFORMATION
$$$Nf.j[fogay,pejO jjt,1j yygggj gy[4j,}ppy-- 6jylandar'dMi j7 ' ;;m T 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 j STEP 2 "C" (Procedure STEP C.1) Standard: NOTE: The Main Generator Field 1. Closes the main generator field breaker by ACB (fleid breaker) will placing the MAIN GENERATOR FlELD ACB trip if No.1 Main switch (241/CS) to close Generator Kilovolts AND (generator voltage) is not
>5KV within 30 seconds of 2.
closing the field beaker. Determines it is not necessa to set the MANUALVOLTAGE ADJUS to raise With the Turbine at approximately 1800 generator voltage above SKV. rpm CLOSE the MAIN GENERATOR FIELD ACB (Non-Critical cortion of Standard) 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. JUST to increase No.1 MAIN GENERA-TOR KILOVOLTS to slightly greater than Cue: None 5 KV. Comments: None 4 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT J PM-C.1 -002
- TITLE
- SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 4 of 10 yjypyPe{rnia,nge(Ogj{glyeE;f 3 g,gggy:$ iiStandardfpgq@Qh .,
STEP 3 "C" (Procedure STEP C.2) Standard: CAUTION: 1. Uses MANUAL VOLTAGE ADJUST (CS-70) to raise Generator voltage to 22 KV as Never exceed 23.1 KV when increas-indicated on NO.1 MAIN GENERATOR l ing voltage as indicated on No.1 KILOVOLTS meter. (Acceptable range: 21.56 Main Generator Kilovolts meter to 22.44). ! (C-08). (Non-Critical cortion of Standard) CAUTION:
- 2. May verify all three phases are at 22 KV by
>1000 Field Amps to obtain 20 KV as selecting A-8, B-C, and C-A positions on the indicated on No.1 Main Generator PHASE VOLTAGE SELECT SWITCH (VS1). i Field Amps and No.1 Main Generator '
Kilovolts meters on C-08 may cause Cue: None generator damage. Comments: NOTE: The voltage Regulator 1. Voltage adjusts to 20 KV with less than 1000 should be adjusted slowly field current amps so there is no need to take due to rheostat overtravel. alternate actions a.1)-4). Use the MANUAL VOLTAGE ADJUST to raise No.1 Main Generator Kilovolts to ap 3roximately 22 KV. Ab D monitor on all three phases for the ; following condition: I
- a. !F_ 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 '
ADJUST
- 2) OPEN the Generator Field breaker
- 3) Notify Plant Technical staff
- 4) Notify System Dispatch of the delay to load the Generator I/cmb
MONTICELLO NUCLEAR GENERATING PLANT J P M-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 5 of 10 BliBMPjjg6iiEri6lgO,pgtgejygf M jj g j g g S g n ,d af g g g g g y 4 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. (Red light ON.) 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 light will be ON.
- 2. Operator should verify red light is on.
- b. Perform a localinspection of the Cue:
Amplidyne.
. APEO reports that localinspection of the ampli-
- c. Using the REGULATOR dyne reveals no abnormal conditions.
VOLTAGE ADJUST, zero the No.1 MAIN GENERATOR Comments: AMPLIDYNE VOLTAGE meter The adjusting of the amplidyne in this step is to (C-08). verify it operates properly. It will need to be 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: Turn ON the synchronizing switch Inserts SYNC SWITCH handle and turns on syn-(8N4SS or 8N5SS on C-08) for one 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: of MAIN GENERATOR BREAKER No. 2 GCB 8N5.
- a. Synchronizing pointer is moving.
- b. Synchronizing Voltmeters and (Non-Critical cortion of Standard) sensing lights are activated. Operator should verify synchronizing pointer is moving and synchronizing voltmeters and sensing lights are activated.
Cue: None Comments: None 1 i 1/cmb
j 1 MONTICELLO NUCLEAR GENERATING PLANT J P M-C.1 -002 \' TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 6 of 10 Mil 3fdSr.nian#@]{ctige3 igg ilggggggMtandardgggg , ggi, :. STEP 7 "C" (Procedure STEP C.6) Standard: Use SPEED LOAD CHANGER to adjust Uses SPEED LOAD CHANGER handswitch on the Generator speed until clockwise syn- C-07 to adjust Generator speed so that clockwise chronous pointer rotation of one revolu- rotation is established on the synchroscope. tion in 30 to 120 seconds is established. Cue: None Comments: None STEP 8 "C" (Procedure STEP C.7) Standard: CAUTION Uses MANUAL VOLTAGE ADJUST (CS-70) to match INCOMING VOLTAGE to RUNNING VOLT-Generator voltage is limited to a max- AGE' 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 NOTE: Incoming voltage indicates generator voltage. Use MANUAL VOLTAGE ADJUST con-trol switch to adjust Jncoming Voltage to match Running Voltage. STEP 9 "C" (Procedure STEP C.8) Standard: ) i Repeat STEPS C.6 and C.7, until both if necessary, continue to adjust voltage and speed I conditions are met. until voltages are approximately the same and i synchroscope is rotating once every 30 to 120 seconds. Cue: None Comments: None . 1 STEP 10 (Procedure STEP C.9) Standard: 1 Allow the synchroscope to make at least Allows synchroscope to complete a minimum of two complete revolutions to verify that two revolutions. the synchroscope is operating properly. None Cue: Comments: None I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID ' Page 7 of 10 l l E1Pyrfchirianle4Qb16gefg3~;.g ggg3Q3gStandardgglggy STEP 11 "C" (Procedure STEP C.10) Standard: WHEN the synchroscope pointer is in 1. Closes selected Main Generator output l 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 I generator: second while the synchroscope pointer is in ' n band,
- a. CLOSE the selected Main kr Generator Output Breaker (8N4 or 8N5 by firmly placing its 2. Uses SPEED LOAD CHANGER handswitch :
control) switch to CLOSE, for on CO7 to increase Generator load to about approximately 1 second. 20-40 MWE.
- 1) !F the breaker does not (Non-Critical cortion of Standard) 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. aker c nt ol switch in the Ngp po o 2. Turn off synchroscope by placing 8N4/SS or AND return to STEP 5 8N5/SS to OFF and remove handle from switch, above. AND
- 2) th b dce "
- 3. ect p ropriate entries be made in Control 9 e on seeond attempt, 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. Us,e SPEED LO,3D CHANGER 1. Appropriate log entries have been made.
to !mmediately pick up 5% load (about 30 MWE). 2. If the breaker does not close on the second
- c. Verify phase to phase voltages' attempt, when the system engineer is notified, AND phase to phase currents he says to cont.inue to attempt closing breaker are approximately equal. until successful.
- d. Turn OFF the synchroscope and 3. The No.1 Gen Transformer and 345 KV disconnects appear normal.
remove handle from switch,
- e. Log in the Control Room Log. Comments:
If the breaker does not close, the operator should en ra o ans or e'r area and follow through with the procedure guidance. 345 KV disconnects to verify no abnormal conditions such as arcing, smoke, etc. l/cmb
r MONTICELLO NUCLEAR GENERATING PLANT ' J P M-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 8 of 10 Ehggergf rinangjsctiVd.M:Ej;3 {2;.i?g?QgyyffStandardfIigg. f(ii ; 7. 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 8N5/SS) for remain-and observe the following: ing Generator output breaker.
- a. Incoming and Running (Non-Critical cortion of Standard) voltmeters are matched Operator should verify the following:
- b. Synchroscope indicated frequency is matched 1. SYNCHRONIZING INCOMING VOLTAGE and SYNCHRONIZING RUNNING VOLTAGE meters are matched.
- 2. SYNCHRONIZING meter is pointed straight up and is not rotating.
Cue: None Comments: None i i I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-C.9 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 9 of 10
$$k?$,[QmQcf9gQtQfQQjjj ((Q,9L Qf};S,ta,nd,ard[,$yp !3y , ,
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. G8NS/CS) to CLOSE.
- a. E the breaker does not close on (Non-Critical cortion of Standard)
E reset he breaker control 1. Verifies phase to phase voltages and phase switch and the alarm by placing currents are approximately equal. the selected breaker contrcl 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
- 2. System Dispatch has been notified.
AND phase currents are , approximately equal. Comments: None ,
- d. Turn OFF the synchroscope and remnve handle from switch,
- e. Leg 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: This JPM is complete. Comments: DO NOT PROMPT! I l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT J P M-C.1 -002 TITLE: SYNCHRONIZE TURBINE GENERATOR Revision 5 WITH OUTPUT GRID Page 10 of 10 1 1 i l Ed(@;C,ANDIDALESRO,Pgggg[ggggg*ggg 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. Initiating Cues: The Shift Supv directs you to synchronize Main Generator to the grid and pickup mini-mum load in accordance with the Startup Procedure C.1, Section VI.C. $g63@lNEORM;THEEVALUATOR.WHENiYOUTHAVECOMgEEED 3 T_HEKASMyg?] l I/cmb
r-d t- ! ( i l Question #: JPM-C.1-002-Q1 l Point Value: 1.0 l Time (Minutes): NA If Reactor pressure is increased from 1000 to 1010 psig with the pressure regulator, what
- - effect will this have on Reactor power? 1 i
Answer: A power increase of approximately 3 Mwt. Reference (s): B.5.9-05, pg 3 of 10 . K/A
Reference:
Kl.01 Task Number- 241000 Rating RO: 3.8 I i I l I i
! Question #: JPM-C.1-002-Q2 l Point Value: 1.0 l Time (Minutes): NA While operating at normal power, what automatic protection is provided for a pressure regulator setpoint low failure? (Assume no operator action is taken.) i l
Answer: Reactor pressure at 840 psig and decreasing with the mode switch in Run. Reference (s): C.4-A, Bases, pg 10 of 13 K/A
Reference:
K3.02 Task Number: 241000 Rating RO: 4.2 l l l
i Turbine Generator- Q2 While operating at normal power, what automatic protection is provided for a pressure regulator setpoint low failure? (Assume no operator action is taken.)
)
l l I i i 1 l
I
!l l
l 4 1 1
<; lpp y.;gy;.jyjg.{.,pg,; .' f,iCAN,DRAJE,SjCORygdpggggg.y.';gyg 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. Initiating Cues: The Shift Supv directs you to synchronize Ma:n Generator to the grid and pickup mini-mum load in accordance with the Startup Procedure C.1, Section VI.C. MIN EO RM ;THEEVAL;U ATg.WHEN SYOU:NAVEC,OMLETEDITHESTASK!!!7;yt;Q3] l l
\
1/cmb
Turbine Generator- Q1 If Reactor pressure is increased som 1000 to 1010 psig with the pressure regulator, what - effect will this have on Reactor power? 1 1
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 1 of 8 g*g*CEW
*EN L zwananz Bi SEORM w w .DE " ? M aw n m y % w,J'-
bk$?.$i- %$ .aROEi:52.?2 eel %(M ERS l3 B Edim 22T2.2.Ch)?$E$iiN 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 A4.01 3.8/3.6 Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
CR209.007 CR209.018 NL209.003 l METHOD OF TESTING TIME FOR COMPLETION Simulator: X Normal: Alternate Maximum Time to Complete: 40 Min in-Plant: Path: X Time Critical: Yes X No Prepared By: g fy( Date: q . //, /T/J
\
Reviewed By: , Date: ygq Shift Supv/Shhgr Review By: MM M Date:q //, /M7
/
Approved By: (Supt Ops Trng) Date: g._ l g g 1 I i l rnatanursinTvnTwisn'nus X 3087 (DOCUMENT CHANGE. HOLD. AND COMMENT FORM) incorporated: Resp Suov: OTRNG l Assoc Ret MTCP.3.32 lSR: N Frea: 0 yrs ARMS: JPMB31005 l Occ Type: 8505 l Admin Initials: Date: l I/cmb (
l i MONTICELLO NUCLEAR GENERATING PLANT J p M.B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 2 of 8
.!$$$$.gj{pjgjig7gggglJJM.S_ET3JPfjf, ,,,,, :pgjgpyg g.{
Simulator Setup: 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 out 0255-03-IA-1 as follows:
- Sign Shift Supv approval.
- Reason for performing: Other _X
- Write in Comments," Perform STEPS 5-10,12-13, and 15-21 for PMT."
- N/A all other steps in procedure.
- 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 Core Spray System Test No. 0255-03-IA. Begin procedure at Step 5 and perform applicable steps. (Provide operator with a copy of Test.] [ Provide operator with stopwatch. (Simulated calibration date.)] - Located in Operator Desk. I 1 l t/cmb I
I MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01 -005 l TITLE: CORE SPRAY OPERABILITY TEST Revision 0 l Page 3 of 8 l PERFORMANCE INFORMATION bEi!P erfornihhegObject,ijegdM inMWg?-:5ggjStandaldjpt3 rr 4 Q. gig STEP 1 (Procedure STEP 5) Standard: Verify that a suction pressure of a 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. (45 psig.)
psig. Cue:
*b. 14-4 , IV S N 1 CS
- Reactor Building APEO reports that PI-14-36A indicates 5 psig, psig.
Comments: None STEP 2 "C" (Procedure STEP 6) Standard: CAUTION: Starts 11 Core Spray ing control switch HS pump inbySTART. 14A-SSA momentarily plac-Do not start pump if system is not pressurized, as damage could result (Non-Critical portion of Standard) '
" n Pmss&- Operator should observe the following:
g an un i le i e. START P 208A,11 CORE SPRAY 1. Pump run indication changes from green to red. PUMP (Breaker 152-505).
- 2. Pump discharge pressure as indicated on PI-14-48A, increases to =360 psig.
- 3. Annunciator C03-A-41, AC INTERLOCK, alarms.
Cue: None Comments: None I I/cmb
l MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 4 of 8
~ $[fj[p3PgfoYmhiice:Objeet,1yejgry Eg[ggjy%g'jgSt ,adard#35p f.g7 y STEP 3 "C" (Procedure STEP 7) Standard:
NOTE: Establishing flow verifies 1. Selects CS for readout. k V IV 2. Throttles open MO-1749 using handswitch CS-9-1 has opened-HS-14A-S4A until F1-7189 indicates the Slowly OPEN MO-1749,11 CORE appropriate mV value, (between 10.01 and SPRAY TEST LINE TO TORUS, until 10.13) l F1-7189, CS LOOP A FLOW, indicates AND J 10.01 - 10.13 mV. Record mV reading 3. Records mV reading. and hour and minute. Reference value: 3080 gpm (10.07). 4. Records current Hr/ Min reading, mV (Non-Critical cortion of Standard) Hr/ Min Operator should observe the following: I
- 1. Valve position Indication changes to dual indication (green and red) from green only.
- 2. System flow as indicated on FI-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. \/erifies that the pump runs for at least 2 utes, at the required flow before pro- minutes, ceeding record hour and minute. AND Hr/ Min 2. Records hour and minute. Cue: Evaluator may inform candidate that two (2) minutes has elapsed once the two-minute run has begun. Comments: Evaluator may shorten run time for performance , of this JPM. 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT J P M-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 5 of 8 pyggggPjrf6'rrn~ahce:Objec,tivegd.;g f;g.pEggg,St,andar,dygg.g.jp.; STEP 5 "C" (Procedure STEP 9) Standard: Record discharge pressure indicated on Records pump discharge pressure >279 psig from PI-14-48A, CS PUMP 11 DISCHARGE PI-14-48A. PRESSURE. Cue: None Comrrents: None psig
>279 psig 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 subtracting pump suction pressure from DP. pump discharge pressure. None Cue: Discharge Press Suction Press N o e s: None STEP 8 "C" (Procedure STEP 13) Standard: NOTE: Required Action Range 1. Determines AP in the acceptable range, AND (low) is based on Tech 2. Initials the appropriate line. Spec requirements which 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: Required Action < 276 and > 327 l PSID: l a. lE the value is in the Required l Action range, THEN notify the Shift Supervisor. 1/cmb
l MONTICELLO NUCLEAR GENERATING PLANT J PM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 6 of 8 gjge'rformlincMObjectiv,e:QG.3 g@rMQQS,tandajdyggpgi'gg STEP 9 (Procedure STEP 15) Standard: l 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 l Cue *- the test. Vibration tests are complete. Readings are in Aceptable Range. Comments: None STEP 10 (Procedure STEP 16) Standard: Initial the appropriate line to indicate the Operator initials Acceptable Range. i range in which the vibration values for P-208A fall. Cue: None mmen s: None Acceptable Range: Alert Range: Reouired Action Range:
- a. 1F 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 bre ker*
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. 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 7 of 8 ifggPerfoiminchiObjective4%-{ yjgg[t: ,, ggStan;dardgg{ , _ t STEP 13 "C" (Steps a., b., c.) Standard: No.11 Core Sorav Overload Alarm Reviews ARP 3-A-14 (CORE SPRAY PUMP NO. 3-A-14 11 OUMAN-OVRD) and 3-A-22 (CORE SPRAY
- 1. Determines pump over!oad has OGOM ,
occurred. 1. Dispatches Turb Operator to check Core
- 2. Isolate No.11 Core Spray per k'ay Breaker 152-505 and Core Spray B.03.01 -05.E.2 mP'
- a. Place 14A-SSA, No.11 Core Cue:
Spray Pump control switch APEO reports ACB 152-505 relay flags indicate (Panel C-03) in the overcurrent and Core Spray Pump motor is hot to PULL-TO-LOCK position. touch.
- b. Place 14A-S1 A, MO-1753 Div I 2. Isolates No.11 Core Spray Pump per CS Injection inboard control B.03.01 -05.E.2.
switch, in the CLOSE position.
- a. Places HS 14A-55A in PTL.
- c. Place 14A-S16A, MO-1751 Div I
- b. Place HS 14A-51 A to Close and verifies CS, injection Bypass keylocked switch in the BYPASS position, Red Ught goes out and Green Light I AND lace handswitch comes on.
14A- 2A, MO-1751 Div i CS c. Places HS 14A-516A to Bypass. I In ection Outboard, in the
- d. Places HS 14A-52A to Close and verifies C OSE position.
Red Light goes out and Green Light
- d. Declare No.11 Core Spray comes on.
inoperable.
- e. Declares No.11 Core Spray INOP.
- e. Notify Shift supeivisor.
- f. Notifies Shift Supervisor.
- f. Notify System Engineer.
STEP 14 INFORM CANDIDATE THAT THE JPM IS COMPLETE. i l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.03.01 -005 TITLE: CORE SPRAY OPERABILITY TEST Revision 0 Page 8 of 8 1 1 Ed&M_ SMIINd?INDN7diNdbh8ME$.03(({g}jj[gggggggg 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 Core Spray System Test No. 0255-03 IA. Begin procedure at Step 5 and perform applicable steps. jEEd@6MINF,ORMiTHEEVACUgOR,yHENjY,0QHAVEjC,O_MPEETED;THETASj$!!!".7 :f7 ' l l Ilcmb
r i l l Question #: JPM-B.3.1-005-Q1 Point Value: 1.0 l Time (Minutes): NA l With the plant operating at 100% power, a leak in RHR Room "A" has required the closing of SW-115 and SW-114. What effect will this have on plant equipment and continued plant operations? Answer: With loss of room cooling, Division I Core Spray and RHR pumps must be declared ) inoperable, and room cooling restored within two (2) hours or begin an orderly shutdown. Reference (s): B.3.1-05, pg 3 of 19; B.3.4-05, pg 4 of 67; P&ID M-112 (EMERGENCY SERVICE WATER SYSTEM) B,1 K/A
Reference:
K6.05 Task Number: 209001 Rating RO: 2.8
p ll l-j Question #: JPM-B.3.1-005-Q2 l Point Value: 1.0 1 Time (Minutes): NA l I'
' Given the following plant conditions:
l' . Reactor S/D in progress. l
* "A" Loop RHR placed in Shutdown Cooling Mode.
i e Reactor level 55 inches. 1 The reactor building APEO reports to the Control Room and informs the lead operator I 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, or why not? l t 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 t a 1 l l
CORE SPRAY-Q2 Given the following plant conditions:
*: Reactor S/D in progress. . "A" Loop RHR placed in Shutdown Cooling Mode.
- Reactor level 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, or why not? e 1 1
F CORE SPRAY-QI A leak in RHR Room "A" has required the closing of SW-115 and SW-114. What effect will this have on plant equipment and continued plant operations? l l 1 i i l l l 1
]
Il l' L f- , L l l Mg[ ygf.CANDIDATEgggggjgig;pjgggjgggg Initial Conditions: The plant is at 100% power. Maintenance has just be'en completed on the No.11 Core Spray pump. Initiating Cues: The Shift Supv directs you to perform Core Spray System Test No. 0255-03-IA. Begin procedure at Step 5 and perform applicable steps. gW;p..T. ilNEARM4THEEVA,_EU__AT_OR;WH.E_Ni.Y..OU:.HA.V_EC_O,_MP._L_E_T,E_DhTH_E. T..AS_K!!.!.N._SS.M_ P::. J.:. I I i 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 1 of 8
~.:LEWQ#% 2 PEBEG BEA@b3bii%^hN*GW%%&h}}Qf}4Ls59.y sE:M kSl9RF bd d __
TiWE42m m s&E mamm sninME4Bi j SRO: SRO/RO: X SRO/RO/NLO: NLO: Plant
Reference:
B.7.2.1-05.02, Rev 4 i 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 A1.01 3.3/3.2 Recent Events: None Probabilistic Risk Assessment Human Error: "GRECTRNAY" Monticello Specific Task List
Reference:
CR271.012 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 Prepared By: M /VLoe./4. Date:q jl,/99p Reviewed By: r~ h Date: ll g q Shift Supv/Shf(tj ugr Review By: gg g Date-q j/,j997 Approved By: ,., (Supt Ops Trng) Date: g_jf , p 7 s:nn'anAilNISTWATIVWils#0NI 3087 (DOCUMENT CHANGE. HOLD. AND COMMENT FORM) incorporated: Resp Supv: OTRNG l Assoc Ret MTCP-3.32 lsR: N Frea: 0 yrs ARMS: JPMB721001 l Doc Type: 8505 l Admin initials: Date: t/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B 7.2.1-001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 2 of 8
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Initialize to any at power IC. Ensure "A" Off-Gas Recombiner is in STANDBY and "B" Off-Gas Recomb,ner is in OPERATE. i 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-ing (1 in Hg every 30 minutes) and the Shift Supv believes the problem to be the "B" recombiner. Initiating Cues: Shift Supv directs you to switch recombiner trains by placing "A" Off-Gas Recombiner in OPERATE and B" Off-Gas Recombiner in FULL STEAM FL OW. 1/cmb l
i 1 MONTICELLO NUCLEAR GENERATING PLANT J P M-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 l l Page 3 of 8 l l PERFORMANCE INFORMATION I ((5Cl[il@eM,p(manjeiO,bjg,gt,lge,gf:[? yJig" ?"
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y i7 STEP 1 Standard: l- Locates procedure 87.2.1 -05.02.B.2, Locates appropriate procedure. Recombiner Train Switching Cue: None ! Comments: None STEP 2 (Procedure STEP 1) Standard:
!E Shift Supervisor requests, None THEN lower HWC hydrogen injection t l 8 CFM, Cue *-
O_R_ perform procedure B.2.6-05.F, Hy- HWC has been shutdown IAW B.2.6-05.F. ' drogen Water Chemistry Shutdown. Comments: [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. Ibs/hr by: (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 1 l l l/cmb L
MONTICELLO NUCLEs2 GENERATING PLANT JPM-B.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 4 of 8 MWdBRerforinance.Obje~ctijdM@,tEs jj:2.f31;[:;% > ga,pd,ardy .-fg
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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 require steam flow asindicated
,d to achieve 6700lbs/hr2. Verifies steam flow on FR-7508A about 6700 on FR-7508A lb/hr' OGHU TR A ED OUTLT FLOW / PRESS (C-2528). 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 for 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 STEP 7 (Procedure STEP 5) Standard: 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: NOTE: It is important that FY-7491 A' 1. Verifies FY-7491 A is in N : MAL and M491B are not AND simultaneously in AUTO orin 2. Verifies FY-7491 A has zero output. MANUAL mode of control for more than a couple of Cue: None minutes or Train Low Inlet Comments: None pressure may result. Verify FY-7491 A, OGHU TR A OG INLT FLW AUCTIONEER is in MANUAL with zero output. l/cmb
MONTICELLO NUCLEAR GENERATING PLANT J P M-8.7.2.1 -001 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 5 of 8 Q jP,jyof W jQ],yytf f Q ;&:([:yy 'CQS ahda,rd:_ f fy.y:[ STEP 9 "C" (Procedure STEP 7) Standard: Place FY-74918, OGHU TR B INLT FLW Places FY-74918 in MANUAL using the manual / AUCTIONEER in MANUAL. auto selector switch. Cue: None Comments: None STEP 10 "C" (Procedure STEP 8) Standard: i NOTE: While performing the Places TSS-A in OPERATE. following step, both FCV-7489A and FCV-74898 (Non Critical cortion of Standard) will be OPEN. Operator should observe PI-7495 for pressure Place TSS-A, TRAIN SELECTOR SW transients. (B Panel.) TRAIN A in the OPERATE position, Cue: None AND observe PI-7495, OGHU MN IN- l Comments: None LET LINE PRESSURE AND TI-7514A, OGHU TR A PREHEAT-ER OUTLET TEMP. STEP 11 (Procedure STEP 9) Standard: E PI-7495 pressure changes rapidly, if PI-7495 changes rapidly OR if TI-7514A de-OR TI-7514A temperature decreases creases below 320*F, places TSS-A in FULL STM below 320*F, FLOW. THEN place TSS-A, TRAIN SELECTOR Cue: None SW TRAIN A to the FULL STM FLOW position. Comments: None STEP 12 "C" (Procedure STEP 10) Standard: l Slowly increase flow of FY-7491 A, 1. Slowly increases Off-Gas flow using OGHU TR A OG INLT FLW AUC- FY-7491 A open pushbutton, TlONEER. AND E"A" 2. IF "A" Train trips, balances "B" Train inlet THENTrain balancetrips"Bwhile,being started're Train inlet pressu pressure by adjusting PC-74788 or PC-74798 from PC-74788, OGHU TR B INLET OG setpoint until low in the green band AND an t Gas Controller, P -747 , OGHU TR B INLET OG Pfces p y4g1 B'"B" ' PRESS CNTRL by a so the needle is lowin,djusting the setpoint green band, (Non-Critical cortion of Standard) AND placeOGHU FY-74918, the InletTR Gas B INLTController'AUC. FLW Operator should observe Off-Gas flow increasing TIONEER in the AUTO position. on FR-7492A. Cue: None Comments: None I/cmb
o MONTICELLO NUCLEAR GENERATING PLANT JP M-B.7.2.1 -001 l TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 6 of 8 ggPe'rfo r~ni'ande' O bjectigeg((fj $539jg.jhStandardP: sgg4fg STEP 13 (Procedure STEP 11) Standard: Maintain total off- as flow approximately Maintains off-gas flow constant by slowly decreas-constant by slowl decreasing output of ing the output of FY-7491 B to zero using the FY-7491 B, OGH TR A OG INLT FLW CLOSE pushbutton. AUCTIONEER, to zero. (Non-Critical cortion of Standard) Operator should observe flow decreasing on FR-74928. Cue: None Comments: None STEP 14 "C" (Procedure STEP 12) Standard: CAUTION: 1. Balances PC-7478A OR PC-7479A using the OPEN or CLOSE pushbuttons for FY-7491 A,
- Must balance low in the green band until FY-7479A 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 Josition using NOTE: PC-7479A is the preferred the Manual / Auto Selector switc1.
controller. Cue: None Balance PC-7478A, OGHU TR A INLET OG PRESS CNTRL, OR PC-7479A, Comments: None OGHU TR A INLET OG PRESS CNTRL, AND place FY-7491 A, OGHU TR A OG INLT FLW AUCTIONEER in the AUTO position. STEP 15 (Procedure STEP 13) Standard: Slowly adjust PC-7478A, OGHU TR A Slowly adjusts in service PC-7478A l INLET OG PRESS CNTRL OR PC-7479A until setpoint is 11.8 to 12.2 PSIA. ! OR PC-7479A, OGHU TR A INLET OG Cue None l PRESS CNTRL setpoint, to 12 PSIA. Comments: None STEP 16 "C" (Procedure STEP 14) Standard: l Place TSS-8, TRAIN SELECTOR SW Places TSS-B in the FULL STM FLOW position. TRAIN B, in the FULL STM FLOW posi-Cue: None tion. Comments: None i I/cmb
MONTICELLO NUCLEAR GENERATING PLANT J P M-B.7.2.1 -009 TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 7 of 8
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STEP 17 "C" (Procedure STEP 15) Standard: NOTE: Desired dilution air can be Sets FC-7.576A to approximately 1.0 scfm. obtained from the System Cue-Engineer. inform operator to set flow rate at 1.0 scfm. Adjust FC-7576A to the desired air injec- Comments- l tion rate. I STEP 18 (Procedure STEP 16) Standard: Locally verify flow indicated by F1-7794A Instructs APEO to verify local flow is 1.0 scfm. OGHU TR A DILUTION AIR FLOW is approximately 1.0 scfm. Cue. . Local Flow is verified to be 1.0 scfm. 1 Comments: None l STEP 19 (Procedure STEP 17) Standard: None Return HWC to previous injection rates Cue: per Op3 Man Section B.2.6-05.D, HY-HWC is being placed service IAW Ops. Man. DROGEN WATER CHEMISTRY - SYS- B.2.6 05.D by another operator. 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 I/cmb
o MONTICELLO NUCLEAR GENERATING PLANT J P M. g.7.2.1.oo s TITLE: RECOMBINER TRAIN SWITCHING Revision 5 Page 8 of 8 MMg}}{gfCANDiDATfSjQpQQQ3ff;Qg?fggggg _ 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-ing (1 in Hg every 30 minutes) and the Shift Supv believes the problem to be the "B" recornbiner. Initiating Cues: Shift Supv directs you to switch recombiner trains by placing "A" Off-Gas Recombiner in OP!9 ATE and B" Off-Gas Recombiner in FULL STEAM FLOW. Sji?MN N EC 7 MITHE EVACUATO R;WH ENiYOU:HAVECO MP EETEpgfiEgS K!!!Tggg$ l 1 i I l/cmb
l l Question #: JPM-B.7.2.1-001-Q1 Point Value: 1.0 Time (Minutes): NA j l Ddring performance of steps in C.1 (STARTUP) you are directed to remove one of the recombiner trains from service. Currently, the following plant conditions exist: l
. 50% power
- Off-gas flow is normal.
- Current date is May 19*. )
e Generator load is 310 Mwe.
- Two recombiners in service.
1 When directed to remove one of the recombiners from service, which one of the two ' should be removed? Answer:
"A" recombiner. During the months of May, June, and July, "B" recombiner is preferred l to be in " operate".
m l Reference (s): B.7.2.1-05, pg 6 of 9 K/A
Reference:
2.1.32 l Task Number: 271000 Rating RO: 3.4
p-i Question # 2 JPM-B,7.2.1-001-Q2 l Point Value: 1.0 l Time (Minutes): NA l With'"B" recombiner in " operate", what edect would there be on the off-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:
A3.01 Task Number: 271000 Rating RO: 3.3 l l
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l Recombiner - Q2 With "B" recombiner in " operate", what effect would there be on the off-gas compressor if a 4% hydrogen trip occurred on the "A" recombiner outlet analyzers? J 9 l l I l
Recombiner- Q1 During performance of steps in C.1 (STARTUP) you are directed to remove one of the recombiner trains from service. C
' urrently, the following plant conditions exist: . 50% power. i . . Off-gas flow is normal. . Current date is May 19*.
e '. . : Generator load is 310 Mwe.
- Two recombiners in service When directed to remove one of the recombiners from service, which one of the two should be removed?
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I-F l l l l i 1? V: # }%; . 73%gpCTANDIDATES1G, OPfp3?ggTp)$g:egggq Initial Conditions: The plant is operating at 100% "B" Off-Gas Recombiner is in OPERATE. "A" Off-
- Gas Recombiner is in STANDBY. HWC is not in service. Vacuum is slowly decreas-ing (1 in Hg every 30 minutes) and the Shift Supv believes the problem to be the "B" recombiner.
1 l Initiating Cues: ; Shift Supv directs you to switch recombiner trains by placing "A" Off-Gas Recombiner in OPERATE and B" Off-Gas Recombiner in FULL STEAM FLOW. j MINf 0 R_ MATH Ef_VAJU_A,T,OgH ERO_UJ._HAVECO M PJETEDjTj 1 ETAS K!!p; Mgjf$ l l I/cmb I l L-
7 I f"MONTICELLO NUCLEAR GENERATING PLANT 0255-03-\A-1 TITLE: CORE SPRAY SYSTEM TESTS Revision 25 l l Page 1 of 14 j l l 0255-03-IA-1 CORE SPRAY SYSTEM VALVE OPERABILITY TEST I 0255-03-111 CORE SPRAY SYSTEM PUMP OPERABILITY TEST _ _ REVIEW AND APPROVALS Prepared By: Ug O g. Reviewed By:pg 4% OC Review Req'd: YES OC Meeting Number: 201S Date: y d -y7 OC Results Review Reg'd: NO A, f[/ Date: 03/22/78 Approved By: (((M Date: S 27- >7
/N REVIEW AND APPRWAL OF ACTIVITIES DATE Shift Supv Approval to Commence: rowiM Time: ne,uv.wy r ,e m ~ , ,
Operator: l Completed By Shift Supervisor: l Completion CS System Engineer - Reviewed -- By PCT System Engineer: 1 Section XI IST Coord: l OC Results Reviewed at Meeting Number: Not Required 03/22/78 i COMMENTS Pe r m n u s - o u /2 , a /s -o / Ac emr ! l i l l l 9 s WO(S) ISSUED YES NO NUMBER (S) 2 5 W W M W .22:fdd W.at FOWADMINISTRATIVEUSE ONLY'9"%9ylE.t 3.1- W';&ry:
~
3087 (DOCUMENT CHANGE. HOLD, AND COMMENT FORM) incorocrated.1 9DNY MOI Reso Suov: SSSE l Assoc Ref: B 3.1 { ( MSA: Y 'Frec: 3 vrs ARMS: 0255031A1 lDec Type: 4030 l Admin Initials: \ 14'- DateQ3DM l mum AT0ESE ONLT
i I MONTICELLO NUCLEAR GENERATING PLANT J P M-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 1 of 11 l
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r EBEGEME E! MEAS 1!!JRtse e:FM im:=E5$5055055;Tr&YT W M55%l0A~ W~*'~ i n.52 SRO: SRO/RO: X SRO/RO/NLO: NLO: Plant
Reference:
B.2.4-05.H.1, Rev 14 Task Standard: Open the MSIVs fo!!owing a Group I Isolation l K/A
Reference:
223002 Task No.: A4.03 Rating RO/SRO: 3.6/3.5 l Recent Events: None Probabilistic Risk Assessment Human Error: None Monticello Specific Task List
Reference:
CR239.003 METHOD OF TESTING TIME FOR COMPLETION Simulator: X Normal: X Alternate Maximum Time to Complete: 30 Min in-Plant: Path: Time Critical: Yee X No ! Prepared By:[d MM Date-q /41997 I Reviewed By: g Date: g -g - pp Shift Supv/ Shift Mgr RMew By: [M g% Dateg /A /977 Approved By: j (Suk Ops Trng) Date: g,j,, p 7 j l i I 3087 (DOCUMENT CHANGE, HOLD. AND COMMENT FORM) incorporated- l' Resp Suov: OTRNG l Assoc Ret MTCP-3.32 lSR: N Frea: 0 yrs ARMS: JPM- B.2.4-001 l Doc Type: 8505 l Admin Initials: Date: 1/cmb i 2
f l l MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-003 l l TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 l GROUP I ISOLATION Page 2 of 11
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Simulator Setup: Initialize to any IC which places the Reactor at power and insert malfunctions PP05A l 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-aus Group I isolation. The initiating signal for the spurious Group I was corrected. The Main Steam Lines are still hot. Initiating Cues: The Shift Supv directs you to re-open the MSIVs per Ops Manual B.2.4-05 procedure, Steps 1 through 13. l l l I 1/cmb
l MONTICELLO NUCLEAR GENERATING PLANT JPM.B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP I ISOLATION Page 3 of 11 PERFORMANCE INFORMATION Pgg4RerfofmWncelObje j tgeigry Q.fg@JggStandard[ y:sfEp g._ 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 prerequisites.
- 1. Outboard MSIV air pressure is 270 psig.
- 2. Main Condenser and auxiliaries are available for service.
Comments: None STEP 2 (Procedure STEP 1) Standard: Verify the following: 1. Verifies that the initiating signal for the Group I
- a. I itiat.in . nal for t e Group 1 isolation has cleared by monitoring parameters and given initial conditions.
s
- 2. Operator should verify annunciators 5-A-44,
- b. !F Group 1 isolat. ion caused by Group i CHAN A TRIP and 5-A-52, Group I one of the following: CHAN B TRIP are reset.
- 1) TemperatureSteam Cue:
Tunnel High None Comments: None
- 2) Main Steam Line High Flow
- 3) Main Steam Une Low Pressure THEN confirmation made that main steam line break has not occurred.
4 l I/cmb
MONTICELLO NUCLEAR GENERATING PLANT d P M-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP l ISOLATION Page 4 of 11 l e Eig;jg Rerf 61FnishdifO bjeyljleg.pg gggjitjpjQtandHFdaggg,y,,; c ! STEP 3 "C" (Procedure STEP 2) Standard: l Reset the Group i isolation by perform- 1. Places HS 16A-S1 A for A0-2-80A to CLOSE, i ing the following: AND
- a. Place all MSIV handswitches in 2. Places HS 16A-S1B for AO-2-808 to CLOSE, CLOSE position. 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 (Panel C-03). 5. Places HS 16A-S2A for AO 2-86A to CLOSE, AN D__
- 6. Places HS 16A-S2B for AO 2-868 to CLOSE, l AND i
- 7. Places HS 16A-S2C for AO 2-86C to CLOSE, AND
- 8. Places HS 16A-S2D for AO 2-86D to CLOSE, THEN
- 9. Resets Group I isolation by depressing pushbuttons 16A-S32A, AND 16A-S328.
- 10. Depresses pushbutton (Non-Critical cortion of ' Standard)
Operator should observe the following:
- 1. All MSIVs closed by observing light indications, AND
- 2. Group i reset by observing white light indicators above pushbutton 16A-S32A lit,
- AND
- 3. White light indicators above pushbutton 16A-S328 lit.
Cue: None Comments: None STEP 4 "C" (Procedure STEP 3a) Standard: Isolate steam usage downstream of the 1. Places A Recombiner Train Selector Switch MSIVs by performing the following: TSS-A to SHUTDOWN, AND
- a. Place both recombiner trains in 2. Places B Recombiner Train Selector Switch SHUTDOWN. TSS-B to SHUTDOWN.
Cue: None Comments: None 1/cmb l
I l MONTICELLO NUCLEAR GENERATING PLANT J P M-B.2.4-001 l~ TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 5 of 11 ggghgPeggmaggggpj@tiyeg@g Es,9;$yj@ WIStandard. ~
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STEP 5 "C" (Procedure STEP 3b) Standard: Place both SJAE steam su] 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 turning control knob to closed i p sition, AND
- a. CV-1242
- 2. CLOSES CV-1243 using 12 SJAE E-28 l
- b. CV-1243 PRESS controller by taking controller to MANUAL and turning control knob to closed position.
Cue: None j Comments: The controller must be turned CW to close valve. l STEP 6 (Procedure STEP Sc) Standard: CLOSE the following: Closes MO-1045 using HS-1045, AND
- a. MO-1045, Steam Seal Reg (Non-Critical cortion of Standard)
Feed Valve
- 1. Verifies MO-1046 is closed.
- b. MO-104 Steam Seal Reg
- 2. Operator should observe valve position Y
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, AND drain valves: 2. Verifies MO-1739 CLOSED, AND
- 1. MO-2565, Steam Line Drain Orifice 3. Verifies MO-1617 CLOSED, AND Bypass
- 4. Verifies MO-4000 CLOSED, AND
- 2. MO-1739, 'l. b.ur ine Steam Bypass Hdr Drain 5. Verifies MO-1180 CLOSED, AND
- 3. MO-1617, Deaerating Steam Supply 6. Verifies MO-1181 CLOSED, AND
- 4. MO-4000, Main Hdr Press Equalizer 7. Verifies MO-1182 CLOSED, AND Drain 8. Verifies MO-1183 CLOSED.
- 5. MO-1180, Main Stop Valve SV-1 (Non-Critical cortion of Standard)
Drain p
- 6. MO-1181, Main Stop Valve SV-2 ; $ator should observe valve position indicating Drain
- 7. MO-1182, Main Stop Valve SV-3 Cue: None Drain Comments: None
- 8. MO-1183, Main Stop Valve SV-4 Drain 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 6 of 11 gjRerfdimancegbj,egvggg b pgj!fjj?gg/fg.iggStandardWg;,gy - STEP 8 (Procedure STEP 4) Standard: CLOSE Turbine Bypass Valves. Verifies Turbine Bypass Valves are closed. (Non-Critical cortion of Standard) Operator should observe valve position indication. Cue: None Comments: None l STEP 9 (Procedure STEP 5) Standard: 1 Perform the following: Operator verifies air supply pressure by checking l computer point AIR 100. '
- a. Verify main air supply pressure is 255-285 psig. Cue:
- b. !E 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, Special Simulator computer point may be unavailable, Procedures - Relieving High therefore the operator must be provided with the Pressure in the Main Air Supply reading. Procedure B.2.4-05.G.4 is not required to Outboard MSIVs, 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-S2B, AND Operation of an Outboard MSIV with HS-16A-S2C, and HS-16A-S2D. main air supply 3ressure above 295 psig may result n actuator damage. (Non-Critical cortion 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. Comments: None
- b. PLACE handswitch to AUTO /
OPEN.
- c. Intermittently release and depress TEST pushbutton at approximately 1/2 second intervals to jog open MSlV. ,
I 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-001 l TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 ' GROUP 1 ISOLATION Page 7 of 11 1 Pl@dii dPJrjf msifide;Ob,jbc, tid gg?j i $;Q$gQMg[S,t,a,h,dag @'f _.yf;;- STEP 11 (Procedure STEP 7) Standard: CLOSE MO-2564, Steam Line Drain Closes MO-2564 using HS-16A-S35. Downstream MSIVs. (Non-Critical portion 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-SS, AND Steam Drain Isolation Valves: 2. Opens MO-2374 using HS 16A-S6. l
- a. MO-2373 (Non-Critical cortion of Standard)
- 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: J Perform the following: Opens MO-2564 using HS-16A-S35.
- a. OPEN Outer Steam Une Drain (Non-Critical cortion of Standard) !
Sto M -2 64, to pressurize I Operator should observe the following:
- b. IF 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 l MSIVs to cool down, LOW PRESS CH A and 5-A-34 MAIN STEAM THEN control warming rate by UNE LOW PRESS CH B reset. opening and closing MO-2564 intermittently. Cue: None Comments: ' The steam lines are hot. l i i ! I/cmb
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MONTICELLO NUCLEAR GENERATING PLANT JPM-B.2.4-009 ' TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP 1 ISOLATION Page 8 of 11 ) \ MEPgfgma_nie!O_bjeictifsygg; p,g5yggghgStshdddW;ggg(;y3l.p , STEP 14 (Procedure STEP 10) Standard: None NOTE: The computer point Cue: ne t rec ds If operator, asks for readings of seriods of t me 3ressure the main air pressure is 270 ig. ps, AIR 100, state that s above main a r pre:.,sure Comments: None of 295 psig. Therefore, P " ' Procedure 0255-07-IA-1 is not required to be per-may e de ermine b IOf.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 3rocedure 0255-07-IA-1 on affected out-board MSIV(s). STEP 15 "C" (Procedure STEP 11) Standard: l CAUTION 1. At <100 psid, depresses the TEST pushbutton I f r nboard MSIV, AND A water hammer could occur if inboard MSIVs are opened at differen- 2. Places HS-16A-S1C in AUTO /OPEN, AND tial pressures >100 psid. 3. Intermittently releases and depresses TEST I WHEN pressure difference between Pushbutton at approximately 1/2 second main steam lines and reactor is s100 intervals to jog the first MSIV open, psid, (Non-Critical cortion of Standard) THEN OPEN inboard MSIV AO-2-80C 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 positic.; hdicating lights change from 9'**" '*'
- c. Intermittently release and depress TEST pushbutton at 3. Valve position ndication 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 I/cmb
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 l gpgpPggg, mad?h?O.bfg,tivepjg?Q 'fj:.;,jpjggQ StandardWM;h'r4lr yl;3{3 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 l differential pressure across valves is less than 2. AO-2-808 using HS-16A-S1B, AND approximately 77 psid. 3. AO-2-80D using HS-16A-S10.
OPEN the following inboard MSIVs: Cue: None
- a. AO-2-80A Comments: None
- b. AO-2-808
' c. AO-2-80D 1
l l l l l I/cmb
I MONTICELLO NUCLEAR GENERATING PLANT JPM.B.2.4-001 l TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 l GROUP 1 ISOLATION Page 10 of 11 l
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STEP 17 (Procedure STEP 13) Standard: CAUTION 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 pressure of 1.5 psig. Place seal steam in service by perform-ing the following:
- 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 maintains steam seal header steam seal header pressure at pressure at 4 psig by opening MO-1047 approx. 4 psig. IF pressure IE pressureis!s
- < 3>psig.
5 ps!g, or opening MO 1046
- 2. Maintain steam seal header pressure at approx. 4 psig. Cue:
IF Another operator will perform Step 14
- a. Is'> steam 5 psig,seal THENheader open pressure Comments: None MO-1047 (STEAM SEAL ,
REGULATOR UNLOADING VALVE) to unload excess steam.
- b. .E steam seal header pressure is < 3 psig, THEN OPEN I MO-1046 to increase steam I seal header pressure. l 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! 1/cmb
MONTICELLO NUCLEAR GENERATING PLANT J P M-B.2.4-001 TITLE: OPEN THE MSIVs FOLLOWING A PCIS Revision 5 GROUP l ISOLATION Page 11 of 11 MlVlFAMAW53fSSi9.L9E!IEofEEfge#IERM3rdEEE Initial Conditions: The Reactor is in a hot shutdown condition following a Reactor Scram due to a spuri-aus Group I isolation. The initiating signal for the spurious Group I was corrected. The Main Steam Lines are still hot. Initiating Cues: The Shift Supv directs you to re-open the MSIVs per Ops Manual B.2.4-05 procedure, Steps 1 through 13. 4 " ?gyffINEORMhTHEEVAEUATQR3]iE_NgOUJHAVE u C,0,MEllETEDjTJEIAS_Kl_l![j'WEj i l/cmb ;
i j Question #: IPM-B.2.4-001-Q l l Point Value: 1.0 l Time (Minutes): NA ! 1 1 While performing logic testing, an inadvene::t Group I occurs with the plant at 100% power. 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 all 8 MSIVs. Reference (s): B.5.6-06, pg 8 of 17, Figure 6 K/A
Reference:
K4.04 Task Number: 223002 Rating RO: 3.2 1 i i
l Question #: JPM-B,2.4-001-Q2 l Point Value: 1.0 l Tirne (Minutes): NA ; What effect will a loss of Y-80 have on the Group I logic and what operator action i:: required when power is restored? Answer: NOTE: No effect on MSIV position orindication. Loss of power to solenoid power and indicating light goes out. Loss of Y-80 will de-energize the white MSIV AC outboard solenoid power indicating light on C-04. When power is restored, then momentarily jumper from M3 to Tl on relay 16A-K68 on C-03. Reference (s): B.5.6-06, pg. I1 of 12; B.5.6-06, 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 J i l l 1
l PCIS - Q2 What effect will a loss of Y-80 have on the Group I logic and what operator action is required when power is restored? 4 l l l l' 1
PCIS - Q1 While performing logic testing, an inadvertent Group I occurs with the plant at 100% power, 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?
Md%i i Mss ^gyggCANDIDATESCCOPXg: Initial Conditions: 3pggggFggggg The Reactor is in a hot shutdown condition following a Reactor S rn due to a spuri-ous Steam Main Group Linesi isolation. are still hot. The initiating signal for the spurious e G Initiating Cues: . The Shift Supv directs you to re-open the MSIVs Steps 1 through 13. . . per Ops Man procedure, M,1NEORMiTHEEEVAEUATORtWHENWOgMAVEpCO__ _ 1/cmb
\ MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-03-001 TITLE: RESTORE ESSENTIAL LOAD CENTERS Revision 2 I i FROM 13 DIESEL GENERATOR Page 1 of 5 , 1 1 1 I
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Reference:
E.4-03, Rev 0 l Task Standard: Restore Essential Load Centers from 13 Diesel Generator K/A
Reference:
295003 Task No.: AA1.01 Rating RO/SRO: 3.7/3.8 Recent Events: None Probabilistic Risk Assessment Human Error: "ABKFDXXXXY" l l Monticello Specific Task List
Reference:
CR262.025 l SS333.038 l METHOD OF TESTING TIME FOR COMPLETION Estimated Time to Complete: 7 Min Simulator: X Normal: X Alternate Maximum Time to Complete: 14 Min in-Plant: Path: Time Critical: Yes X No Prepared By: [ om Datg //, /9ff Reviewed By: Date: .) J g g g Shift Supv/Shhgr Review By: [M / Dateg/f /ff) Approved By: , (Supt Ops Trng) Date: g g., p 7 mst'anuisistsraTer'ikr'hktv 3087 (DOCUMENT CHANGE, HOLD, AND COMMENT FORM) incorporated-Reso suov: OTRNG I Assoc Ret MTCP-3.32 lSA: N Frea: 0 vrs ARMS: JPM-E.4-03-001 l Doc Type: 8505 l Admin initials: Date: l I/mit
o MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-03-001 l TITLE: RESTORE ESSENTIAL LOAD CENTERS Revision 2 FROM 13 DIESEL GENERATOR Page 2 of 5 l
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- f Lt k [hdYkh.Uk [fdh[5hh[bk'['i' .': k y j Simulator Setup:
Initiate a Station Black Out, perform C.4-A, applicable C4s and EOPs. Restore Reac-tor water level with RCIC. Perform E.4-01 to backfeed 13 Bus from 13 DG. Perform Steps 1-3 of E.4-03, including (ED-81) Knife Switch 3/308 in 152-308 and listed MCC breakers. NOTE: Simulator instructor should silence non-related alarms, ( 1 Initial Conditions: < A Station Black Out occurred about 90 minutes ago. C.4-B.9.02.A (STATION BLACK-OUT and E.4-01 (BACKFEED BUS 13 FROM 13 DG) have been completed. RCIC is con) trolling Reactor water level. It is not known when off-site power will b i Initiating Cues: Shift Supervisor directs you to perform E.4-03 beginning at Step 4 (RESTORE ESSENTIAL LOAD CENTERS FROM 13 DIESEL GENERATOR). Steps 1 - 3 have + been completed. Step 14 will be completed at a later time. l l l i I/mif i
1 I l l l l MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-03-001 TITLE: RESTORE ESSENTIAL LOAD CENTERS Revision 2 i FROM 13 DIESEL GENERATOR Page 3 of 5 l PERFORMANCE INFORMATION ljggglferfdiriifande Ob ec,t,ljejg,ygg g
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STEP 1 (Procedure STEP 4) Standard: Verify 103 LOAD CTR XFMR PRI Verifies 103 LC XFMR PRI ACB 152-509 is ACB-152-509 is CLOSED. closed, l Cue- ; 1 If asked about 13 DG load limitations, state 13 DG ! has 550 KW,475 volts, and 410 amps. l Comments: None STEP 2 (Procedure STEP 5) Standard: Verify 103 LOAD CTR SEC ACB-52-301 Verifies 103 LC SEC ACB 52-301 is closed. is CLOSED. Cue: None Comments: None 1 STEP 3 "C" (Procedure STEP 6) Standard: Place 52-409/CS,103/104 LC BUS TIE Closes 103/104 LC BUS TIE ACB fi2-409. ' ACB-52-409, to CLOSE. . Cue: None Comments: None STEP 4 "C" (Procedure STEP 7) Standard: Place 52-309/SS, SYNC 103/104 LC Places 52-309/SS to ON and at serves synch BUS TIE ACB-52-309, to ON. meter indication. Cue: None Comments: No voltage is indicated as both sides are dead. STEP 5 "C" (Procedure STEP 8) Standard: NOTE: ACB 52-309 will not CLOSE Closes 52-309 ACB,103/104 LC BUS TIE. unless ACB 52-409 is Cue: None CLOSED. Comments: None Place 52-309/CS,103/104 LC BUS TIE ACB-52-309, to CLOSE. STEP 6 (Procedure STEP 9) Standard: Place 52-309/SS, SYNC 103/104 BUS Places 52-309/SS to OFF. TIE ACB-52-309, to OFF. Cue: None l Comments: None f 1/mif
MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-03-001 TITLE: RESTORE ESSENTIAL LOAD CENTERS Revision 2 FROM 13 DIESEL GENERATOR Page 4 of 5
@EY9feffff g[neggglygtjggigfgy ggggggjigggsjagdgggg^ =w STEP 7 "C" (Procedure STEP 10) Standard:
Place 1-LO/CS, Bus 15 ESSENTIAL Places 1-LO/CS to LOCKOUT position. TRANSFER SWITCH, to LOCK-(Non-Critical cortion of Standard) Observes red LOCKOUT light ON. Cue: None Comments: None
)
STEP 8 "C" (Procedure STEP 11) Standard: Place 152-308/SS, SYNC 13/15 BUS Places 152-308/SS to ON and observes synch TIE ACB-152-308, to ON. and voltage meters. Cue: None Comments: None STEP 9 "C" (Procedure STEP 12) Standard: Place 152-308/CS,13/15 BUS TIE Closes 152-308 ACB,13/15 BUS TIE. ACB-152-308, to CLOSE. (Non-Critical cortion of Standard)
- 1. Observes voltage pick-up on 15 Bus.
- 2. Observes any amperage increase on LC-103 and LC-104.
Cue: If asked about local voltage indication on LC-103 and LC-104, state that they read 470 volts. Comments: None STEP 10 (Procedure STEP 13) Standard: Place 152-308/SS, SYNC 13/15 BUS Places 152-308/SS to OFF. TIE ACB-152-308 to OFF. Cue: None Comments: None STEP 11 Standard: INFORM EVALUATOR THAT THE Operator informs evaluator that the task is com-TASK HAS BEEN COMPLETED. pleted. Cue: None Comments: DO NOT PROMPTl I/mif
f MONTICELLO NUCLEAR GENERATING PLANT JPM-E.4-03-001 l TITLE: RESTORE ESSENTIAL LOAD CENTERS Revision 2 FROM 13 DIESEL GENERATOR , Page 5 of 5 l l l l
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l Mgj(ggjgyggg J D j lE,Sj C y j g y y j g g { g pf g g g g g g g f g l Initial Conditions: A Station Black Out occurred about 90 minutes ago. C.4-B.9.02.A (STATION BLACK-OUT) and E.4-01 (BACKFEED BUS 13 FROM 13 DG) have been completed. RCIC is controlling Reactor water level. It is not known when off-site power will be available. Initiating Cues: Shift Supervisor directs you to perform E.4-03 beginning at Step 4 (RESTORE ESSENTIAL LOAD CENTERS FROM 13 DIESEL GENERATOR). Steps 1 - 3 have been completed. Step 14 will be completed at a later time. QM7g" lNEORMITHEEVA11UATORiWHENXOUiH, AVE [COMBEE_TEDjlH_E. TAM!!!!yggj$iff l i l I/mif
l Question #: JPM-E.4-03-001-Q1 l Point Value: 1.0 Time (Minutes): NA l Using the plant conditions set by this JPM, what is the current source of power to MCC-133B? Answer: Note: This question must be asked on the simulator following JPM completion. Energized from LC-104 through MCC-1438. l Reference (s): B 09.07-02, pg 4 of 8 K/A
Reference:
295003 Task Number: AA1.01 Rating RO: 3.7 I 1 l a I l 1
i l Question #: JPM-E.4-03-001-Q2 Point Value: 1.0 l 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 concem is there with this isolation request? 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 j qualifications. Reference (s): B.09.07-05, pg 26 of 69 K/A
Reference:
295003 Task Number: 2.2.13 Rating RO: 3.6 1 1 I
LOAD CENTER - Q2 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 concem is there with this isolation request? 1
)
)
l l t
r 1 1 I LOAD CENTER - Q1 Using the plant conditions set by this JPM, what is the current source of power to MCC- , 133B? I i 1 4 1 1 I 1 l i l l I i
1 I l l l i l i i Q A y j 3 LE g g {jp g [ggy;,g s y gg gg g j g ,3fgj l Initial Conditions: ) A Station Black Out occurred about 90 minutes ago. C.4-B.9.02.A (STATION BLACK- i OUT) and E.4-01 (BACKFEED BUS 13 FROM 13 DG) have been completed. RCIC ; is controlling Reactor water level. It is not known when off-site power will be available. ; initiating Cues: Shift Supervisor directs you to perform E.4-03 beginning at Step 4 (RESTORE ESSENTIAL LOAD CENTERS FROM 13 DIESEL GENERATOR). Steps 1 - 3 have been completed. Step 14 will be completed at a later time. Ed@fdLNfpjyEH.,g,E3XUA_TORiW_HENT,0UjH_AVErCOgl'ETEDiTHE:@SK!!!?gffRC E . I/mif
\
I F!NAL AS-ADMINISTERED CCENARIOS FOR THE MONTICELLO EXAMINATION - THE WEEK OF AUGUST 23,1999 l i
r l Appendix D Scenario Outline Form ES-D-1 Facility: MONITCELLO Scenario No.: OP-TEST 01 Op-Test No.: 01 Examiners: Operators:_ _ _ _ 4 Obiectives: t: valuate operator ability to address a SCRAM with failure of rods to fully insert , with potiential for containment damage. l Initial Conditions: The unit is in the process of starting up with power about 55%. No.12 RFP l will be started M ods will be withdrawn to reach the 100% rod pattern. 'B: CRD FCV has a l ruptured diaph ei.;,n and is out of service. SHERCO Unit 3 is down for an outage. System l Dispatch has requested VAR load be maintained approximately 140MVAR delivered. Turnover: 'B' CRD FCV is isolated for diaphram work. Hold Generator VAR loading at ~140 delivering. No.12 RFP is being returned to service. Withdraw control rods per Nuc Eng j directions. Event Malf. Event Event l No. No. Type
- Description 1 N-B Start the No.12 RFP 2 R-R Increase Reactor Power with Control Rods 3 A22 l-B H2 Cooling TC-1589 Auto Controller Failure 4 SLO 2B l-R SBLC Squib Valve Failure 5 APO4A C-B 'A' SRV Bellows Leak 6 TUO4D C-B No. 4 Turbine Bearing High Temp and High Vibration 7 M-R/B Manual Reactor SCRAM CH07D C-R CRD FCV CV19A/B Failures - ATWS CH07B CH19 (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor (R)O, (B)OP I
NUREG-1021 1 Interim Rev. 8, January 1997
MONTICELLO NUCLEAR GENERATING PLANT INiT-OP-TEST 01 TITLE: ATWS WITH SBLC INJECTION REQUIRED Revision 0 Page 1 of 15 i Prepared By:[M /tf Date: q. /.2, /99$ Validated By: //j y Date: g - /3 9 4/ Reviewed By: Date: f-/g.jPp Approved By: v [ Date: 8--/J-ff ATTACHMENTS
- 1. Form 3139 (CONTROL ROOM SHIFT TURNOVER CHECKLIST)
- 2. Form 3140 (SHIFT SUPERVISORS OFFICE TURNOVER CHECKLIST)
PRA INPUI
- 1. Initiating Event:
Turbine trip due to vibration.
- 2. Accident Class:
Class IV - Accident sequences involving failure to scram leading to a high pressure challenge to containment resulting from power generation into the containment.
- 3. Human Errors / Equivalent:
- LSLCINJECY Failure to inject SBLC e UH Failure to control reactor level during an ATWS e RLOTORCLGY Failure to initiate Torus Cooling
- PSMSACCDXY 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 55%. 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. SHERCO Unit 3 is down for an outage.
System Dispatch has requested VAR load be maintained approximately 140MVAR delivered.
- 2. Scenario Events l I/cmb l
l
MONTICELLO NUCLEAR GENERATING PLANT l NIT-OP-TEST 01 TITLE: ATWS WITH SBLC INJECTION REQUIRED Revision 0 Page 2 of 15
- 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).
- c. H2TC-1589 malfunctions requiring operator to place controller in Manual.
- d. SBLC squib valve failure on system No. 2.
- e. SRV "A" Bellows Leak Alarm requiring ARP actions to determine operability.
- f. No. 4 Turbine Bearing temperature will start to increase. Vibration on No. 4 Bearing will also increase until the Turbine Vibration High Alarm comes in.
Operator Action to unload the Turbine may slow the vibration increase.
- g. 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 insertion will not occur,
- 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 power, as indicated by the APRMs, is less than 3%, SBLC has been injected, and plant conditions are under control.
NOTE: Stable plant conditions are not possible in a reasonable amount of time. l B. Scenario Objectives l
- 1. Evaluate ability to Start an RFP during a Plant Startup and increase Reactor power using control rods.
- 2. Increase Rx power per C.1 and Nuclear Engineer instructions.
l
- 3. Identify and respond to instrument malfunction, H2 CLG-1589 Controller.
- 4. Increasing Turbine bearing vibration could lead to potential Turbine damage in addition to a reactor scram and must be responded to promptly.
- 5. 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.
- 6. Increasing Torus temperature has a high potential for damage to the containment and must be responded to promptly.
- 7. During followup actions after the scram, an RHRSW pump will fail to start when given a start signal. Use of redundant pumps will be required to complete required actions 1/cmb
i ) ( MONTICELLO NUCLEAR GENERATING PLANT INIT-OP-TEST 01 TITLE: ATWS WITH SBLC INJECTION REQUIRED Revision 0 Page 3 of 15
- 11. SCENARIO CREATION A. Initial Conditions
- 1. 1C-171 l B. Manual Settina Summary 1
- 1. Hang SECURE Card on "B" CRD FCV.
C. Event Triacer
- 1. None D. Procedures /Surveillances
- 1. None i
i 1/cmb l
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T AtONTICELLO NUCLEAR GENERATING PLANT R:; vision 0 Page 14 of 15 SHIFT TURNOVER INFORMATION l ' The unit is currently at 55% 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 per C.1 Vil, Step 11.. Increase power per C.1 (STARTUP) and Nuclear Engineer guidance. Within the next half hour, the Nuclear Engineer will provide a list of required control rod moves to return the plant to 100% power. k The plans for this shift are to continue with the Startup. The formal review of C 1 (STARTUP) ! requirements has been completed. However, if you feelit is necessary to review specific notes and conditions you may take time to complete this review but it is not required.
"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.
SHERCO Unit 3 is down for an outage. System Dispatch has requested that VAR load be maintained i approximately 140 MVAR delivered. j l l t l 1/cmb
1 MONTICELLO NUCLEAR GENERATING PLANT Ravision 0 Page 15 of 15 MONTICELLO SIMULATOR USE ONLY INSTRUCTIONS FOR: CONTROL ROD WITHDRAWAL TO 100% ROD PATTERN increase Reactor power by withdrawing control rods to 100% rod pattern.
- 1. Withdraw the following control rods from position 12 to position 48:
14 - 23
~
38 - 31 22 - 39 30 - 15 14 - 31 38 - 23 ! 30 - 39 i 22 - 15
- 2. Withdraw the following rods from position 4 to position 12:
22 - 31 30 - 23 30 - 31 22 - 23 i 1/cmb 1
MONTICELLO NUCLEAR GENERATING PLANT 3139 TITLE: CONTROL ROOM SHIFT TURNOVER CHECKLIST Revision 23 Page 1 of 2 Shift Manager: /R46 Date: Tre wG Shift: 7 pap 4 Completed By: rrto o- Reviewed By: Shift Supv.: 7 RA> 6 LPEO: PEO: 7'R 4 6- Others: _ Mode Switch Core Thermal Power Shutdown 5 Nominal 1775 MWT Startup k NI Refuel MWT Core Flow $ 57.6 + 1 (inst error) x 10'Lb/Hr & 8. 9 X LOG Lb/Hr Core /Rx Dp 518.6 / 5 27 PSID Q/8 PSID Rx Pressure 51008 +20 PSIG 933 PSIG Rx Level +30 to +40 INCHES indicated 35 INCHES Torus Level -2" to +2" O INCHES RCP Dp 5143 PSID cD3 / c93 PSID Steam Flow 8 5 7.20 + .25 (Inst Error) x 10 Lb/Hr S.4/ x 10
- Lb/Hr FW Flow < 7.20 + .25 J. 4 4 x lO' Lb/Hr ONSIBUMENTATIONSIMif[$gnst $ UNI d Error) X 10'Lb/Hr@bDenPM"V" Ab6de%Idh}$M 8k Nuclearinstruments ,
g Rad Monitors -
" u..n .., 4 , ~ ~ n n , ~, -
1 CONTROLLER MODES;L(. Circle mode for each system) and.bd:lst " / 3 ter ' ~~ : n m;gsn ,,v.vd .. - Rx Level 1 element Main Reg Va MSTR-MAN Lo Flow Reg Va A RFP Level Trip BYPASS R Press Contr MPR # hO7 EPR # hob [b h.U$SiSTEMS3N M $f-j[ n $fjl M dii M E [ N 5?fM M E[3 S n fdMi!;$ $ Controller System Sw. Pos. Mode /SP/Outout Alarms Valve Line-Uo 11 D Gen AM N/A oK N/A 12 D Gen N/A ! N/A ADS "A", "C", "D" N/A N/A SRV Low-Low Set C-03 "E", "G", "H" V N/A N/A OlV ll Low-Low Set Logic 16t38yp N/A N/A "A" RHR la N/A OK "A" RHRSW OFC MA/ .:?o / o "A" Core Spray AAS N/A HPCI N/A Ale / 84 / Jo o "B" RHR Ash Avh N/A "B" RHRSW oFF jaaw f .% f e, "B" Core Spray M M N/A i RClO , N/A Ah / 80 / MO "A" SBGT A<+t @/ 4 o / O "B" SBGT Ad* M/ 40 / O O , SBLC Off~- N/A CKT Cont ind f
"A" EFT R*^M N/A $ 1 "B" EFT Ad/J4/ N/A l l
FGAUX.PpWER J2Mi@$'ChME thi1SMEISHCd235dGhdu **C w.E l 2 1AR EDGs i I Source Supplying: 1R _ is a Manual 2R/1R Transfer required prior to taking generator off line? Yes No 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: 99 -/ 6' 7d Q: EOR'ADMINISTRATIV : Reso Suev- OPER W/# I Assoc Ref: OPER l SR /T p Frea- 10 hrs. j M AMOS$'6ACY $ $ .~. ARMS- 3139 "I Doc Tvoe- 407C I Admin initials 4 + Date n f 4 M l P .9 1 n w a r*
- M/djj VJJh us n L V a d Db ~ k*P 1
MONTICELLO NUCLEAR GENERATING PLANT 3139 TITLE: CONTROL ROOM SHIFT TURNOVER CHECKLIST Revision 23 Page 2 of 2
,.__m.-. _ _ .. m ,_, . , . . . - , . ~ .
DW F_AN MODE::...- _ ,._. .. .= ,a.g43ydM.Ls a. .
<' e L'+a '
-7 -a E Hi Temp Post Scram 4 Fan F Shutdewn SYSTEM COMPONENTS / OUT INOP AS ALLOWED BY TECHNICAL SPECIFICATIONS SHALL be Operable System and Date Out Backup System Tested Prior To 1.
2. 3. 4. 3ANEL CHE.CKC(Rx in_ShutdowrfiNot Required) * ' - /- W a Q :s y '. u w a , ; b ,J.1.u , Panel 2 3 4 5 6 7 8 Alarms OK OK CK CK C,K SM OR I Une-up Ind. Ughts V g s/ V 3/ 3/ y Panel 20 21 24A 24B 252B 252C 259 Alarms OK CX OX OK OK % CK Line-up O< fr.d. Ughts V V b 5/ \/ h \/ [SYSIE5I[DEyiNl
~
N? 1.W C R 6 WSlRO,Mif70F(MAL FC U isoTAM SorDURING ieW 6 SHIFJ[3M[$W[#E,32ME;ig;i'fA.3 ohraq m 2.91.2 41rp cuL ot secuwe s4aA-oes C.I
- 3. Gn 4My Au h4n,( Rn,I f a<f Afbe e/,.g em I w.r4 w e.4 c m a r.
4.,t}/el (~ m (ja r feel,We d4 N /40 dpfoO/w t)47 ,3vt cl,'ch -Ic/t .
- 5. } '
6. On-Coming shift review the following and sign below: A. Tumover Checklist B. Previous 24 hour CR Log entries C. Equipment status - D. New Memos and Control room Master signed E. Active Jumper BP Forms F. Control Room Key Set received by LPEO G. Computer Alarm and Out of Processing Summaries should be printed at shift tumover and retained at the Operators work station during shift Values may exceed the given limits provided deviations are attributed to known situation and appropriate action has been initiated (example: FW Heater Leak). Criteria for acceptable status SHALL be allowable operating conditions spectfied in the applicable Operations Manual, Operations Section. Computer summaries may be discarded at end of shift. Additional comments per separate comment sheet Form 3139A.: YES NO Duty Oper(s): LPEO: PEO: Date: Shift: SS: SM: i l I
\
1 M/djj J
r j l MONTICELLO NUCLEAR GENERATING PLANT 3140 TITLE: SHIFT SUPERVISORS OFFICE TURNOVER Revision 14 CHECKLIST Page 2 of 2 Shift Mgr: TRe/ G-- Shift Supv: rved G- (Circle items where applicable) Completed By: r 2 o c,-. 3 Date: r ec a c,- Shift: 0700-1900
- 1. Unit status: Power level S 5 'k MWT 9.0 / 'MWE 700 l
- 2. Any Surveillance Tests in progress now? YES If YES, Numbers:
- 3. List Surveillance Tests scheduled for next shift:
Numbers: 1216-1. l
- 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? YES h (List,if YES) a, b.
- 6. System deviations from normal during shift:
- a. "B" cRO fcv in khd fe e dkpAm b.
c. d. e. f.
- 7. Any new memos or instructions issued? NO (if YES. then list or attach copy)
- a. }/oJJ Gam var loadwe a+ at N O c/s li v r:a c .
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 l e. New memos / instructions l
Shift Manager: Date: Shift Supervisor: Date: 1/ pdc
MONTICELLO NUCLEAR GENERATING PLANT 3140 TITLE: SHIFT SUPERVISORS OFFICE TURNOVER Revision 14 CHECKLIST Page 1 of 2 Shift Mgr: Shift Supv: (Circle items where applicable) Completed By: Date: Shift: 1900-0700
- 1. Unit status: Power level MWT MWE
- 2. Any Surveillance Tests in progress now? YES NO if YES, Numbers:
- 3. List Surveillance Tests scheduled for next shift:
Numbers: 1350. l
- 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 NO (List,if YES) a.
b.
- 6. System deviations from normal during shift:
a. b, c. d. e. f.
- 7. Any new memos or instructions issued? YES NO (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: 3087 (DOCUMENT CHANGE. HOLD. AND COMMENT F_QBM) incorporated; %- OW l ~Fo Y DMINISTRAT VEi Resp Supv: GSO WW"J Assoc Ref: GSO l sR: 4 f, Frea: ,0 /vrs / , ;
'usE!oNLY ARMS: 3140 IDoTType: 407D l Admin Irutials: rff,-
Date: /J4;/1! /% l I/ pdc SWiULATOR LSE ONI.Y I o
[-... . Appendix D Scenario Outline Form ES-D-1 i , Facility: MONITCELLO Scenario No.: OP-TEST 02 Op-Test No.: 02 l l: Examiners: _ Operators:_ _ l - - - Obiectives: Evaluate operator ability to respond to a stuck open SRV requiring emergency depressurization of the Reactor, initial Conditions: The unit is operating at full power with No.11 SW Pump'out-of-service. l Tumover: No.11 SW pump is isolated for packing replacement. Reduce power and conduct MSIV exercise test No. 0160 at 90% Power. Event Malf. Event Event No. No. Type
- Description 1 MSO9A l-B Steam Packing Exhauster 3A Blower Trip j 2 R-R Reduce Reactor Power to approximately 90%
i 3 N-B Perform MSIV Exercise test No. 0160 4 CH08A C-R Trip of Running CRD Pump No.11 l- 5 ED75 l-R Loss of MCC-142A/Div ll Sprays 6 AP03F C-B 'F' SRV leak - High discharge line temperature 7 PC09F M-R/B SORV Tailpipe Break requiring manual Reactor SCRAM 100 % MSO4A C-B Main Steam Line Rupture in Drywt11 area l AP01F C-B 'F' SRV Fails OPEN I i (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor j (R)O, (B)OP l NUREG-1021 2 Interim Rev. 8, January 1997 ; L..
MONTICELLO NUCLEAR GENERATING PLANT INIT-OP-TEST 02 TITLE: SORV WITH TAILPIPE BREAK AND Revision 0 FAILURE OF DW SPRAY Page 1 of 16 Prepared By: }/ J-JY{ Date: ; g9y Validated By: hd ' Date: f f3, ey of Reviewed By: Date: gy3. y Approved By: [ Date: g_g.pp i ATTACHMENTS I
- 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 1
- 2. Accident Class: '
Class lilB - Accident sequences initiated or resulting in small or medium 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
j l A. Scenario Descriotion
- 1. Initial Conditions The unit is operating at full power with No.11 SW Pump out-of-service.
i
- 2. Scenario Events l
- a. Reduce Rx power to 90% for MSIV monthly test.
- b. AoRM No. 3 Recorder Fails as is at 99% power.
- c. No. i1 Recire Speed Indication is Failed as is.
- d. No.11 CRD pump trip.
l/cmb
, l MONTICELLO NUCLEAR GENERATING PLANT INIT-OP-TEST 02 TITLE: SORV WITH TAILPIPE BREAK AND Revision 0 FAILURE OF DW SPRAY Page 2 of 16
- e. A ground will develop in MCC-142A. The crew must verify proper MPR operation and LCO requirements.
- f. During this period, SRV-F will begin leaking and a tailpipe break in the Torus will release the energy above the su the leak continues to increase. ppression pool. DW pressure will slowly rise as
- g. 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.
- h. 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.
- i. 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. l J. When the 3 ADS valves a e en an open signal, "C" SRV will not open, requiring the opening of a different
- k. Successful operation of Drywell sprays will be allowed after emergency depressurization has been initiated following restoration of MCC-142A. Drywell and Torus sprays must be secured before negative containment pressures are !
sustained.
- 3. Termination Cues
- a. Emergency Depressurization initiated.
- b. Drywell pressure under control.
- c. Prior to crew entering RPV flooding.
NOTE: Stable plant conditions are not possible in a reasonable amount of time. B. Scenario Obiectives:
- 1. Reduce Reactor power using recirc and recognize Failed APRM Recorder and Failed Recire Speed Indicator.
- 2. Perform MSIV Exercise Test.
- 3. Respond to a loss of MCC-142A
- 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 Fails to OPEN.
1/cmb
MONTICELLO NUCLEAR GENERATING PLANT INIT-OP-TEST 02 l TITlf.: SORV WITH TAILPIPE BREAK AND Revision 0 l FAILURE OF DW SPRAY Page 3 of 16 ll. SCENARIO CREATION l A. Initial Conditions . l 1. IC-172 B. Manual Settina Summarv
- 1. Place a SECURE Card on No.11 SW Pump Handswitch.
C. Event Triaaer
- 1. None D. Procedures /Surveillanegg
- 1. 0160 (MSIV EXERCISE TEST) i i
l/Cmb
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v MONTICELLO NUCLEAR GENERATING PLANT R:: vision 0 l:
Page 16 of 16 l l
SHIFT TURNOVER INFORMATION l
The plant is at 100% power. The No.11 SW Pump is tagged out-of-service for packing replacement. l actor power reduction to 90% is scheduled to allow MSIV exercise testing per surveillance No.
i I/cmb
[: , .-
MONTICELLO NUCLEAR GENERATING PLANT 3139 TITLE: CONTROL ROOM SHIFT TURNOVER CHECKLIST Revision 23 Page 1 of 2 Shift Manager: 7 >t a c- Date: 7 R.v c-- Shift: TR-J c-Completed By: r-res c. Reviewed By Shift Supv.: 7-RA/4- LPEO: r re v o PEO: 7-re v c-- Others:
Mode Switch Core Thermal Power Shutdown Startup M /77O Refuel MWT iNominal1775 Mwr Core Flow $ 57.6 + 1 (Inst error) x 10*Lb/Hr 6'7 7//04 Lb/Hr 3 Core /Rx Dp $ 18.6 / 5 27 PSID /3 / /G 5 PSID Rx Pressure 51008 +20 PSIG /000 PSIG Rx Level +30 to +40 INCHES indicated .2.5 INCHES Torus Level -2" to +2" O INCHES RCP Op 5143 PSID $8 / 6S PSID 8
Steam Flow 5 7.20 + .25 (Inst Error) x 10 Lb/Hr 7, / 7 x /0' Lb/Hr FW Flow < 7.20 + .25 (Inst Error,) X 10*Lb/Hr 7./5 yloC ,Lb/H,r
--~n- - n . .~ ,
a Th wr
" DNSTRUMENTATIONd< i'mSE.AM'Jn!MSmm' Bypassed 5.,,U. .W N W.h ".Above NormalM/A NuclearInstruments .
/' ##* #F *#
, Rad Monito._rs .- _ _ _, y b .
" tCONTROLLE8 MODES;;(. Circle,rnode'for each system) .aniMky.CA q.; ;2 1 . c ;an ' 1 Rx Level 1 element Main Reg Va MAN MSTR-MAN MSTR-AUT Lo Flow Reg Va MAN M N RFP LevelTrip BYPASS .JbRMM)
Press Contr MPR # 9/0 EPR # 903 (
" $didERGENCfisygIEMSildid$b!ddiiM.W,.$M'@iNENiiM7N3239l$.dO15$ l Controller System Sw. Pos. Mode /SP/Outot_4 Alarms Valve Line-Uo 11 D Gen /Yvf0 N/A Cl< N/A i
12D Gen N/A N/A ADS "A", "C", "D" N/A N/A SRV Low-Low Set C-03 "E", "G*, "H" ___ T/ N/A N/A DIV 11 Low-Low Set Logic (Auto /$yp -- N/A N/A
*A" RHR ~ )4crfo N/A Ol<
"A" RHRSW OFF MMH / 00 /O )
"A" Core Spray f@N/A /kdO /
N/A Bo / /CO i
I HPCI "B"RHR /1uh) N/A "B" RHRSW OFF MW / c?O /0 "B" Core Spray Phtfo N/A N/A Att / 80 / /00 l RCIC ,
"A" SBGT %dC fM gh / SO /O l "B" SBGT 14vt0 fn it h / y, o / g g/ l SBLC OFP N/A CKT Cent ind . / j "A" EFT bWJ$ N/A 1 "B" EFT Muh)JTf?/ N/A l TCf,EMUX;P0.WERlLGEfG2MP34M(f$I.Jdid?d;.idku:;1;i ;.gcxfMWh, NR x.a I Source Supplying: 1 1AR EDGs l Is a Manua12R/1R Transfer re ired prior to taking generator off line? Yes 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated: 99-/4'70 i OR'ADMINIST.RATI,VER Reso Suov- OPER W/# l Assoc Ref: OPER l SR:/T 4 Frea: 10 k i MDS$3NITEtW ARMS- 3139 "I Doe Tvoe: 407C l Admin initials 4 Y DatendNM Q
"'* EWU1.?/20f USE ONU l l
E.
MONTICELLO NUCLEAR GENERATING PLANT 3139 TITLE: CONTROL ROOM SHIFT TURNOVER CHECKLIST Revision 23 Page 2 Of 2
.,y . . . , ,. .s._ ..~.,c.. , , , _ , . .. _
.. .. -- _ _.. ..,f. y@, CC%u tDW FAN M_ ODE: ... , 7:, M V W C . i f,,d fft a c_.. g T,; V ' W i . . ..s Hi Temp Post Scram 4 Fan Fa Shutdown SYSTEM COMPONENTS / OUT INOP AS ALLOWED BY TECHN CAL SPECIFICATIONS SHALL be Operable System and Date Out Backup System Tested Prior To 1.
2.
3.
4.
3ANELICHE.CK;jRz lg ShutdowgENot Re. quired);"f;s.C n C E-M/ , c.x e.' l.tj. " C.";
Panel 2 3 4 5 6 7 8 Alarms QK CK cK CK CK CX OK Une-up ind. Ughts v )/ )/ )/ 3/ y y Panel 20 21 24A 24B 252B 252C 259 Alarms OK OK oK oK DM M'l cK Une-up
\
eK l
Ind. Ughts y v v U V r s'
[S15TEfDMiMEERTAWOilMAtlDURIN6 SHi5,I21ES!EYINz35fenheem NW3 e h ;] Q s
- 1. A H Smice water Dunn isolohel e bacW,W
- 2. %ds L- MOU Eyrir%e ' T*T h d oid o c/ 90 % 'Deau /. '
3.
4 6.
8.
On-Coming shift review the following and sign below:
A. Tumover Checklist B. Previous 24 hour CR Log entries C. Equipment status D, New Memos and Control room Master signed E. Active Jumper BP Forms F. Control Room Key Set received by LPEO
~ ' G. Computer Alarm and Out of Processing Summaries should be printed at shift tumover and retained at the Operators work station during shift.
Values may exceed the given limits provided deviations are attributed to known situation and appropriate action has been initiated (example: FW Heater Leak).
Criteria for acceptable status SHALL be allowable operating conditions specified in the applicable Operations Manual, Operations Section.
~
Computu summaries may be discarded at end of shift.
Additional comments per separate comment sheet Form 3139A.: YES NO /
Duty Oper(s): LPEO: PEO:
Date: Shift: SS: - SM:
M/djj
MONTICELLO NUCLEAR GENERATING PLANT 3140 TITLE: SHIFT SUPERVISORS OFFICE TURNOVER Revision 14 CHECKLIST Page 2 of 2 Shift Mgr: r /t o 0- Shift Supv: 7 R A/ G- (Circle items where applicable) ;
Completed By: r R AJ 6- -
Date: r7R Al G-- Shift: 0700-1900
- 1. Unit status: Power level /00'70 MWT /776 'MWE 6 c2 5
- 2. Any Surveillance Tests in progress now? YES .
If YES, Numbers: ;
1
- 3. List Surveillance Tests scheduled for next shift:
l Numbers: 1216-1. FMSI V Eserc tpe # C K-O l
- 4. Any infrequent Test or Evolution (as defined in 4 awl-04.05.07) in progress? YES If YES, state Test or Evolution l
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 l Form 3560 that was used for the previous crew. 1
- 5. Any limiting conditions for operation? YES (List,if YES) a.
b.
- 6. System deviations from normal during shift:
- a. *// St"rva're (AJ0 der furnp l50 lcdfc' br hCbW5 " epbYP, 1
- b. PA4uee pwret h 90 "la Strr r??S) U rp rceT ro 7'5sT d6/6o c.
d.
e.
f.
l 7. Any new memos or instructions issued? YES NO (if YES, then list or attach copy) l 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:
l/ pdc L
MONTICELLO NUCLEAR GENERATING PLANT 3140 TITLE: SHIFT SUPERVISORS OFFICE TURNOVER Revision 14 CHECKLIST Page 1 of 2 Shift Mgr: Shift Supv: (Circle items where applicable)
Completed By: -
Date: Shift: 1900-0700
- 1. Unit status: Power level MWT MWE
- 2. Any Surveillance Tests in progress now? YES NO If YES, Numbers:
- 3. List Surveillance Tests scheduled for next shift:
Numbers: 1350. l
- 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 respons'ble i 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 NO (List,if YES) a.
b.
- 6. System deviations from normal during shift:
a.
b.
c.
d.
e.
f.
- 7. Any new memos or instructions issued? YES NO (if YES, then list or attach copy) a.
b.
- 8. On-coming shift review the following and sign below;
- a. Shift turnover 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:
3087 (DOCUMENT CHANGE. HOLD. AND COMMENTf.QBM) incorporated: HNDL6 i ATIVEJ Resp Supv- CSO \AAAf*] Assoc Ref: GSO lsR: No Freo: .0 /vrs / ,
FO 7usE!ONLV DMINisIR.MW ARMS: 3140 IDcETvoe: an70 I Admin initials: th. Date: /M/"L / /4t5' "P"
SMi.LATOR USE ONLY
T i
l n.
l lNITIAL SUBMITTAL OF THE OUTLINE FOR THE l
MONTICELLO EXAMINATION - THE WEEK OF AUGUST 23,1999 l
1 l
[
I A-070
ES-201 - Examination Outline Form ES-201-2 Quafrty Assurance CheckJist t .
Facsme Date of Ereminanon I hem Task Desenpoon
- s. b. c.
, 1. a. Vedfy that the outline (s) St(e) the appropdate model per ES-401.
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- b. Aseees whether eil 6 knowledge and 4 ability ostegones are ,,4-t:', sempted.
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- 2. a. Using Form ES-3016, verify that the propeeed sceneno sets oever the required number of normal evolueens. Instrument and component failures, and maior trennents. p S' -
l' b. Assess whether there are enough sceneno sets (and opereel to test the protected number M and mix of applicante in oooeedence with the exposted orow oompooroon and rotation schedule without comprenesing exam integdty; ensure each applioent can be tested using et least one new ecenario and esenerios wiu not be repeated over successive days.
- c. To the extent pesodde, seseos whether the oudines conform with the qualitadve and j g guantitative entene speerned on Form ES-301-4 and described in Appendiz D. "/d I l
- 3. a. Verify that the audines oentan the required number of control room and in plant teoks and verify that no more then 30% of the test ansterialis repeated from the last NRC examsnation.
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/ b. Vedfy that the tooke are diserbuted among the oefety funodon youpmos as specified in j l
l T ES-301; ensure one teak reguwee a low power er shuefown eendition; one reeuwes the epplicant to 1, -__: en ehemete path procedure, and one requires entry to the RCA. h !
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- c. Check the fasew up K/As for balance, distrbunon, and oveden with the written exem. O k
- d. Vedfy that the required admoestruove topios are covered, with emphasis on performance- /J l bened eseh4 ties.
- e. Deterrrene if there oro enough different outlines to test the protected number and mix of applieente and ensure that no more than 30% of the items are duphcoted on succeserve days. .
4 a. Asseee whether .; -
- priorition Gneluding PRA and PE insights) are e, overed in the /s
. _ , ._ exam esodon -
77
- h. Aeosom whether the 10 CFR 55.41/43 and 55.45 sempEng is sopropriate.
- e. Ensure thet K/A importance retinos (except for plantMe prioch. eel are et leerJt5. 4 A d. Check for duplication and evodeo among exam sections.
- e. Check the entire ' exam for belance of coverage. k
- f. Assess whether the selected K/As/ test items are operationally oriented G.e do they relate to the teoks Ested for the system?).
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- g. Assese whether the exam fits the appropdate lob level (RO or SRO).
Printed Name / Signature Date
- e. Author kA NM %f hh'M lAnon I(/a, ), && $*)}$f
- b. Facsiity Reviewer (*) '7"Ir #)Mede f / dC',,dVMD tr YJdi
- c. Chief Exemmer
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- d. NRC Supervisor
(*) Not applicable for NRC-developed examinations.
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I ES-401 BWR RO Ex:mir.ctin Outline Printed: 06/17/1999 !
fagj[lin Monticello Nuclear Generating Plant Form ES-401-2 I
Eaam Date: 08/23/1999 Exam Level: RO 1
K/A Category Points i
Tier Group K! K2 K3 K4 K5 K6 Al A2 A3 A4 G Point l
Total 1.
i 2 3 3 h f u, ,..+ w. <y .
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p .., ,, r ;
N, ,; 0 13 g
17 * .
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W I 19 i
& 'A n 4 MET Wii 1
Abnormal 9- g, gp ;p ,
,, p_a Z'Y; l Plant 3 0 1 1 kJ;tX f3$g& 1 1 ,M,,n "'
0 4 .
Evolutions NE 'i40[ [#N (M# '.W
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Totals 5 9 7 ;g%;? W' W QS 4 6
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94 u.831 pE,W 8
g% .y.
- 1 36 Tier
$fh$ .T F.,is 1 2 2 2 4 2 2 3 4 3 3 1 28 2.
2 2 2 3 3 1 2 1 3 1 1 0 19 Plant Systems 3 1 0 0 1 1 0 1 0 0 0 0 4 Tier Totals 5 4 5 8 4 4 5 7 4 4 1 51 Cat 1 Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge And Abilities 5 3 1 4 13 Note:
- 1. Attempt to distnbute topics among all K/A Caegories; select at least one topic fan every K/A category within each tier.
- 2. Actural point totals must match those specified in the table.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant 4pecific priorities.
- 4. Systems / evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category tier, i
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Scenario Outline
. ' Simulator Scenario 1, "ATWS with SBLC Injection Required" Simulator Scenario 2, " Main Steam Line Rupture in Drywell with Spurious Group 1 Isolation" l
Simulator Scenario 3, " Steam Leak in Secondary Containment with a Loss of High Pressure injection"
. Simulator Scenario 3 (Spare) " Loss of Norma Feedwater with Low Power ATWS" Attached are forms ES-D-1 outlining the scenario events.
he SW
*O 1'
p Facility: Scenan Monticello BWR Op-Test No.: 1 r No.: 1 Examiners: Operators: RO Brady BOP Casperson 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 alternate 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.
Tumover Continue with reactor start-up by placing #12 RFP in service. Increase power per C.1 Start-up and Nuclear engineer 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.
#12 RFP discharge pressure gauge fails in position 2 A510P04-08 l(BOP) requiring notification of I&C/ engineering to correct.
Increase reactor power using control rods per C.1 3 N/A R(RO) and Nuclear Eng,ineer guidance.
4 P07-15 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.
TUO3D 6 TUO3C C(BOP) Turtiine bearing #3,4 and 5 vibration alarms. -
TUO3E Turbine trip and reactor scram with only a few rods CH16 inserted; Turbine casing will be penetrated CH19 M(Both) 7 resulting in loss of condenser vacuum necessitating A24 C(Both) closure of the MSIVs MCO3 CV-19A CRD FCV fails closed preventing rod 8 CH07B C(RO) insertion using CRD hydrauhes.
9 MS028 C(BOP) "B" outboard MSIV will fail to close.
RHR torus cooling will be required to control torus A510PS-15 temp. DP indication for #11 RHR heat exchanger 10 1(BOP) will fait downscale.
#11 RHRSW pump fails to start when given a start 11 A520P30 C(BOP) .
signal
* (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor 2
i i
1
i
- 8 d yofti lio BWR N 2 Op-Test No.: 1 Examiners: Operators: RO Eigen :
BOP Brady Objectives: To evaluate the applicants' ability to; reduce reactor power using recirc pump speed I control; perform MSIV exercise test; respond per AOPs to a loss of an essential MCC, leaking i SRV, and SRV failed open; implement EOP actions on increasing drywell temperature and i pressure escalating to conditions requiring a emergency RPV depressurization. l Initial Conditions: IC-172; 100% reactor power; #11 SW pump is tagged out of service for packing replacement. j Turnover: 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 tack pump trip 2 C05A49 l(RO) following completion of release to CSTs
#2 APRM recorder fails as is at 95% indicated 3 P06 f(RO) power requiring notificat;on of l&C to correct condition.
4 A510P07-11 1(BOP) #11 Recire pump speed indication fails as is l 5 N/A N(BOP) MSlV exercise testing law surveillance 0160.
MCC-142A ground resulting in feeder breaker trip i 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 0
"F" SRV fails open with broken tailpipe. Rx scram 0F 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 vzwe MO-2022 failed closed. This combined with the loss of power to the Div 2 drywelI spray valves inhibits DW spray capability.
9 A520P31 C(BOP) ,
This will result in DW pressure increasing to a poini requiring RPV emergency depressurization per EOPs.
"C" SRV fails closed when RPV emergency depressurization is required. Power is 10 A520P30 C(BOP) subseq~uently restored to MCC 142 allowing DW spray to begin.
* (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor 3
I l
Facility 0 '"*"
Monticello BWR N o.: 3 Op-Test No.: 1 Examiners: .
Operators: RO =Casperson l BOP =Eigen l
Objectives: To evaluate the applicants' ability to; complete RCIC surveillance; reduce reactor l power using recire pump speed control and control rods; respond to a control rod drifting from I the core; respond to loss of high pressure feed and implement EOPs on low reactor water level i and high secondary containment radiation; complete an RPV emergency depressurization l including level restoration with low pressure pumps. ]
Initial Conditions: IC-174; 100% reactor power; RCIC monthly testing in progress for post i maintenance testing. The valve timing portion of the surveillance test is complete.
Turnover: Complete the RCIC monthly testing. Vibrations on #11 condensate pump have beer increasing slowly (not yet at the alarm point) and OC is meeting to discuss course of action.
Event No. Malf. No. Event Type
- Event Description 1 N/A N(BOP) Complete RCIC monthly surveillance test.
2 A510P06-08 l(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 i 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 C(RO) light and the rod drift alarm. Recovery of the 4 _
05 7 inadvertent rod withdrawal requires hydraulic BA543P30 l(RO) isolation at position 00.
5 FWO3B C(BOP) #12 condensate pump breaker trip
#11 condensate pump trip on high vibration 6 FWO3A C(BOP) resulting 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 higt 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, (l)nstrument, (C)omponent, (M)ajor
1 l- 1 i
Facility: Scenad BWR Op-Test No.: 1 Monticello No.: 4 Examiners: Operators: Spare l
Objectives: 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 oi a recire and RFP pump on a loss of #12 4160 bus; implement EOP actions on decreasing ,
reactor water level with an ATWS condition; manually control HPCI.
initial Conditions: IC-173, 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 C04822 C(BOP) to advance.
2 N/A N(BOP) Complete surveillance test for #11 EDG "C" MSL flow indicator fails downscale requiring 3 A510P7 1(BOP) I&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 C(BOP)
A531P27-01 signal. -
#12 4kv bus ground resulting in a trip of #12 6 ED058 C(BOP) reactor feed pump and #12 recire pump.
Spurious trip of #11 reactor feed-pump causes a
~
reactor scram at +g Inches. All rods do not insert 7
^ } requiring EOP ATWS entry. Control rods will drift C 6 B h) into core when increased cooling water flow is l applied. l HPCI controller will fail in automatic. HPCI will 8 AS10P6 f(BOP) funct, ion with the controller in manual.
* (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor i
5 l
- y ,
l^
1 l
l ES-301 AdministrativeTopics Outline Form ES-301-1 Facihty: _Monticello Nuclear Generating Plant _,_ Date of Examination: _8/23/1999__,,
Examination Level (circle one): RO / SRO Operating Test Number:
Administrative Topic / Subject Describe method of evaluation:
Description 1. ONE Administrative JPM, OR 2.TWO Administrative Questions 1 Administrative JPM; Fill out side one of the tumover sheet.
Shift Turnover (On Simulator)
A.1 Refueling Error (Administrative Question)
Fuel Handling Foreign Material Exclusion (Administrative Question) 1 Administrative JPM; Determine if Work Order (WO)
A.2 Familiarity with the use of P&lDs isolation is adequate, q 1 Administrative JPM; Determine radiation protection requirements and projected exposure from RWP for work A.3 Radiation Work Permits (RWP) assignment involving the isolation of a HCU.
Non-Duty reporting requirements (Administrative Question) l Emergency Action Lsvels and A.4 Classification Recommendation to Shift Management (Administrative Question)
ES-301 Individuci Walk-through Tc t Outlinn Form ES-301-2 Facility: Monticello Nuclear Generating Plant Week of Examination: 8/23/1999 Examination Level: RO Operating Test Number 1 ,
System / JPM Title / Type Safety Planned Follow-up Questions:
Codes
- Function KIA/G // Importance // Description
- 1. 202001/ Start #11 Recirc 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
- 2. 204000 / Startup RWCU System / a. A4.03 / 3.2 / RWCU drain flow regulator (D)(S) 2
- 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 1 isolation 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. K4.08 / 3.8 / Automatic system initiation 5,259001/ Place a Feedwater a. Kl.09 / 3.8 / Reactor water level Regulating Valve in service 2 (D)(S)(L)
- b. A4.01/ 3.6 / System flow
- 6. 271000 / Recombiner Train a. 2.1.32 / 3.4 / Ability to explain and apply system limits and Switching 9 precautions.
(D)(S) '
- 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 9,286000 / Use of Alternate Injection a. K5.03 / 3.3 / Effect of water spray on electrical components systems for RPV Makeup, 8 (Firewater crosstie).
(N)(P)
- b. Al.05 / 3.2 / System lineups
- 10. 212000 / Startup RPS MG Set a. 2.1.28 / 3.2 / Knowledge of the purpose and function of major system components and controls.
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)ltemate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P) ant, (R)CA l/nrc/mif}}