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{{Adams
{{Adams
| number = ML041410417
| number = ML041410410
| issue date = 04/19/2004
| issue date = 09/15/2003
| title = V. C. Summer April 2004 Exam 50-395/2004-301 Draft
| title = V. C. Summer April 2004 Exam 50-395/2004-301 Draft Written Exam Quality Checklist ES-401-6 & Sample Plan
| author name =  
| author name = Laska G
| author affiliation = - No Known Affiliation
| author affiliation = NRC/RGN-II/DRS
| addressee name =  
| addressee name =  
| addressee affiliation = NRC/NRR
| addressee affiliation =  
| docket = 05000395
| docket = 05000395
| license number = NPF-012
| license number = NPF-012
| contact person =  
| contact person =  
| document type = License-Operator, Part 55 Examination Related Material
| document type = License-Operator, Part 55 Examination Related Material
| page count = 167
| page count = 17
}}
}}


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=Text=
=Text=
{{#Wiki_filter:Draft Submittal (Pink Paper) 1. Administrative Topics Outline (ES-381-1)
{{#Wiki_filter:Draft Submittal (Pink Paper)
2. Control Room Systems & Facility Walk-Through Test Outline (ES-301-2) 3. Administrative JPMs 4. In-plant JPMs 5. Control Room JPMs (simulator JPMs)
DRAFT Written Exam Quality Checklist (ES-401-6)
..- ..........
ti Written Exam Sample Plan
............
.............
.. ES-301 ........ Administrative
....... Topics Octline Form ES-30f.:i'
............ . Facility:
V. C. Summer Date of Examination:
04/19/2004 Examination Level (circle one): / SRQ Operating Test Number: 1 (see NG~) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Describe activity to be performed:
Shutdown Margin Verification STP-I 34.OO.YAttachment X for Mode fentry. ,4 .' ................
..........
:. ,.,, :. ,? ............
JM&~ a QPTR Calculation STP-108.001
:;$ Prepare a Tagout for maintenance on the "C" Charging pump. Determin~xdose pi:, rates with airborne activity present. 6' ?>. ........ ,:.: pa... ., .e:, N/A NOTE: All items (5 total) are required for SRos. 6'0 applicants require only 4 items unless they are retaking only the administrative topics, when 5 are require R>>:>-.-.7
.... ........... , .........
!:: 1:: :::. 22 of 27 NUREG 1021, Draft Revision 9 .... ....................
.... ........................
;,..%..- .....................
........................
...
2 I? p r 7 ES-301 Control Room/ln-Plant Systems Form ES-301-2 Outline Facility:
V.C. Summer Date of Examination:
04/19/2004 Exam Level (circle one): EO/ SRO(I) / SRO(U) Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for 330-U) Operating Test No.: f I m / JPM Title , ... ecirc. JPSF-002 Deveh an alternate b. Operate the CVCS System to Increase RCS Pressure. (JPS-023) 04A1.03) ...... C. Start and Load 'B Die rator (JPSF-025) Develop J MAS alternate path (malfun generator after parail t requires tripping the d. Minimize the Consequences of A Total Loss of Service Water. (JPS- 033). 8; :::> f. Steam Generator Tube Rupture@kjpressurize RCS to less 'J than S/G pressure). (JPSF-OO$~'i::, _.. In-Plant Systems (4 for RO; 3 for SRO-I; 3 or 2 for!SR:O-U)
Safety Function ~ 4P 2 6 45 1 3 8 k. boss of Containment Integrity (JPPF-112) Develoea \ modified JPM using a different valve in RCA. I ff F, '4' 5 Type Codes: (D)irect from bank, (M)odified from bank, (N.&w, .... (Qlternate path, (C)ontroI
,::> 'oom, (S)imulator, &)ow-Power, (R)CA *:. 3.:. ,. . .... 23 Of 27 NUREG-I 021, Draft Revision 9 ............
...............
ADMINISTRATIVE JPMs NRC-A-001 Shutdown Margin Verification STP-I 34.001 Attachment I for Mode 5 Entry Perform a QPTR Calculation STP-188.001 Prepare a Tagout for Maintenance on the 'C: Charging Pump Determine Dose Rates with Airborne Activity Present NRC-A-002 NRC-A-003 NRC-A-004
...........
.... ..................
Monday, JPhf NRC-A401 CALCULATE RCS BORON CONCENTRATION FOR COLD SHUTDOWN, XENON FREE AT 68'F APPROVAL:
APPROVAL DATE: REVNO: 0 March 29. 2004 PageioflO TASK: TASK STANDARD:
iW3:: Obtain required datea from the Curve Book tables and graphs. Use obtained data to calculate required boron concentration, using Attachment IV of STP-134 001 PREFERRED EVALUATIOX LOCATION PREFERRED hW4L &'.A TIO?JMETHOD SIMULATOR PERFORM MFERETCES:
STP-134.001 SHUTDOWN MARGIN VERIFICATION TOOLS: EVAL LiATION TIAWE TIME CEITIC4L NO lOCFR55: 45(a)8 GOP-5; STP-134.001; Station Curve Book CANDIDATE:
TIME TIME trnrim PERFORMANCE RA TLQG: S A T UNSAT QUkSTIUN GRAIX- PERFORM 4NLE EMMINER: DATE INSTRUCTIONS TO OPERA TOR READ TO OPERATOR:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE LYITIAL 1. The reactor is being shutdown after several months operation at 100% power. 2. The initial conditions for entry into GOP-5, Reactor Shutdown from Startup to Hot Standby, have been met. 3. Reactor power has been reduced to IOE-l&nd RCS temperature has been stabilized at 557°F using the steam dumps. 4. Current core burnup is 16,000 MWDIMTU. 5. Current boron concentration is 1000 ppm. 6. A11 control rods are operabl . Shutdown and Control Rod Drop Testing is to be performed. - IATTIA TING In preparation for borating the RCS to shutdown the Reactor for this testing per Step 3.5 of GOP-5, you have been directed to calculate the boron concentration required for Cold Shutdown, Mode 5, Xenon Free? at 68°F using STP-134.001. Mocronda.v, March 29,2004 Page3 of IO OPERA TOR DJSTRUCTIONS:
SA FET'TY COiVSIDERATIONS:
NIA INITIAL 1. The reactor is being shutdown after several months operation at 100% power. 2. The initial conditions for entry into GOP-5, Reactor Shutdown from Startup to Hot Standby, have been met. 3. Reactor power has been reduced to 10E-1% and RCS temperature has been stabilized at 557°F using the steam dump . Current core burnup is 16,000 MWDlMTU 5. Current boran concentration IS 1000 ppm. 6. All control rods are operabl . Shutdown and Control Rod Drop Testing is to be performe In DreDaration for boratincr the RCS to shutdown the Reactor for this testin$ per Step 3.5 of GOP-5. you have been directed to calculate the boron concentration required for Cold Shutdown, Mode 5, Xenon Free, at 68°F using STP-134.001. EVALUATOR WHEN YOU FEEL THAT YOU Monday, .UpIrcII 29,2004 Poge40f 10 SIART. TIUE. . . ...


STEPS CR SEQ FIEP: 1 No Yes Review Piecaution STEPS CR SEQ FIEP: 1 No Yes Review Piecaution CUBS: COMWEXTS:
ES-401    Written Examination  Form E S - 4 0 M Quality Checkllst Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
CR SEQ STEP: 2 No Yes Review Initial Condition CUES: CR SEQ STEP: 2 No Yes Review Initial Condition CUES: COMiWEh'TLT:
-the audit exam was systematically and randomly develcped: or the audit exam was completed before the license exam was started: or 2 the examinations were developed independently: or-the licensee certifies that there is no duplication; or from the bank at least 20 percent new, and the actual 80 / SRO-onl Between 50 end 60 percent of the questions on the RO exam are written at the comprehension/analysis level; the SRO exam may exceed 60 percent if the randomly selected WAS support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at a. Author b. Facility Reviewer (")
CR SEQ STEP: 3 No Yes Record Cycle Burnup. CLET: COMMENTS: .MonduJj, March 29,2004 STEP STANDARD:
c. NRC Chief Examiner (#)
Reviews Precautions in front of STP-134.00 Initials the top blank on Page 1 of Atbchrnent IV of STP-134.00 SAT UXS.4 T STEP Si?4h1DARD:
d. NRC Regional Supervisor Note: ' 'I he facility reviewer's initialsisignature are not applicaDle for NRC-developedexaminativn # inde~!!~~e!?!NRC,eviewei~~~!eal
Reviews Initial Conditions for STP-134.00 Initials the second blank on Page 1 of Attachment IV of STP-134.00 SAT UW.4 T STEP STARDARD:
    ..........items .....'c;"
Enters " 16,000 on Attachment IV. Page 1. of STP-134.00 Pugc 5 of io CR SEQ STEP: 4 No Yes Record the present RCS temperature Cb'ES: CR SEQ STEP: 5 No Yes Record the desired temperatur CUES: CQMMEXTS:
    ..... i'l Column ......chief
CR SEQ STEF: 6 STEP STANDARD:
      .._ examiner co~currence.!pql;lred..........-
Enters "557" on Attachment IV, Page 1 of STP-134.001 STEPSTAXDARD:
3Qof 34  NUREG-1821, Draft Revision 9
Enters " 68" on Attatchment IV, page 1 of STP134.001 STEP STAKDARD: Yes Yes Record the highest boron concentration within the desired temperature range to be maintained as well as the Curve Book Figure from which it was obtaine Enters "'I319 ppm" and Figure 11-9.4" on Attachment IV, Page 1 of STP-I34.00 C[TES: C3MMENTS':  
,%fQndQ>~, March 2% 2004 s.4 T iXWAT Page 6 of10 CR SEQ STEP: 7 STEP STANDARD:
Yes No Contacts Reactor Engineerin Contacts Reactor Engineering via phone or plant page system. CUES: SAT As the Reactor Engineering representative, the Evaluator should cue the examinee
~NSAT to enter 200 pcm for §amarium. Since this caicuiaicn is being performed for conditions other than the current conditions of this JPM, the examinee should apply "NOTE 2.1" and contact Reactor Engineerin COMM2?'TTS'
CR SEQ STEP: 0 STEP STANDARD: Yes Yes Enter Samarium Worth. Enters " 200 pcm" on Attachment IV, Page 1 of STP-134.001. CUES: SAT l7NS4 T COil4:WEiVTS:
STEP STAXDARD:
CR SEQ STEP: 9 Yes Yes Bounding Worth of one or more inoperable Control Rods. of STP-134.00 Enters "0 pcm on Attachment IV, Page 2 CUES: SAT L'NSA T COM~WE.~TS~
iUon&y, March 29,2004 CR SEQ STEP: 10 STEF STANDARD: Yes Yes Add lines 2.1 and 2.2 . Enter "-200 pcm" on line 2.3 of Attachment IV, Page 2 of STP-134.001 CUES: SA 1' m"A 1' COMMENTS:
CR SEQ STEP: I? STEP STAiVDARD:
Yes Yes Enter Differential Boron Worth for the boron Enters " 7.45 (allow for rounding off) on line 2.40f Attachment IV, Page 2 of concentration on line 4.4 (Use Figure 11-7.3 @ 557°F). STP-134.00 CCES: COMMENTS:
SAT UNSA T CR SEQ STEP: 12 Yes Yes Divide line 2.3 by line 2.4 STEP STANDARD:
Enters " 26.85 (allow for rounding cff) on line 2.5 of Attachment IV, Page 2 of STP-134.001. CUES: COMMENTS:
Monday, Murch 29,2004 SAT U.WA T Page 8 of 10 CR SEQ STEP: 14 STEP STANDARD:
Yes Yes Minimum boron concentration to maintain Subtracts
" 29" from " 7319" and enters Shutdown Margin (subtract line 2.5 from line " 1292" on line 3.1 of Attachment IV. kg6 1.4). 2 of STP-134.001. CUES: SAT Examinee may be conservative and subtract " 26 (rounding down)
from "1 319 then6LWAT enter " 1293 on line 4.1. COMMENTS:
Examiner ends JPM at this point. Monday, March 29,2004 Page 9 of IO JPM SETUP SHEET i BORON CONCENTRATION FOR DESCHPTI0.W:
CALCULATE RCS BORON CONCENTRATION FOR FREE AT 68°F IC SET: INSTRUCTIQiVS:
COMMENTS:
COLD SHUTDOW XENON
.-- STP-I 34.001 ATTACHMENT IV PAGE I OF 2 REVISION 11 STTS # SHUTDOWN MARGIN VERIFICATION FOR MODES 4 AND 5 6.1 PRECAUTIONS, Section 2.0 have been reviewe INITIALS 6.2 1 .I Cycle Burn-up. 16. 000 MWB/MTU 1.2 Present RCS temperature:
567 "F INITIAL CONDITIONS, Section 5.0 have been met. INITIALS 1.3 Desired WCS temperature:
6+@ "F a. The RCS must be borated to aCold Shutdown, Xenon-Free concentration prior to manually blocking either the Low Pressurizer Pressure SI below P-I 1 or the Low Steam Line Pressure SI The Shutdown boron concentration requirements of some Mode 4 temperatures may be greater than the Cold Shutdown, Xenon-Free concentration required for Mode 5. 6. 1.4 The highest baron Concentration required to maintain Shutdown Margin for all Modes and temperatures between the present WCS temperature and the desired RCS temperature:
1314 ppm 1.5 The Curve Book Figure from which this boron concentration was obtained:
Curve Book Figure: z-7~ y (Figure 11-9.2,9.3, or 9.4) I NOTE 2.1 I The IPCS (XENDISP or U1503) should be used. if the IPCS is not available, of if a calculation is desired for other than current conditions, Reactor Engineering should be contacted to obtain Samarium worth. 2.2 Record Samarium Worth using 2.1.8 g2.l.b: a. IPCS Samarium Worth (XENBISP or U1503). (-1 rlh pcm b. Obtain Samarium Worth from Reactor Engineerin (-) 200 pem STP-134.001 ATTACHMENT IV PAGE 2 OF 2 REVISION 11 STTS # SHUTDOWN MARGIN VERIFICATION FOR MODES 4 AND 5 (Cont'd) In Mode 4 or 5 with one or more inoperable Control Rod(s), the RCS should be borated per the applicable Abnormal Operating Procedur A value of 2200 pcm should be entered for one inoperable rod and 7000 pcm for more than one inoperable rod. 2.2 2.3 2.4 2.5 3.1 3.2 8.3 Bounding Worth of one or more inoperable Control Rods. (+) 0 /pcm Add lines 2.1 and 2.2: 0 = (-{ 200 r/ pcm Step 2.2 Inoperable Control Reds Bounding (-) 200 + (+) Step 2.1 Samarium Worth Worth d W Enter the Differential Boron Worth forrthe boron concentration on line 1.4 (-) 7*qb pcml (Use Figure 11-7.3 at 557&deg;F). ppm - / / Divide line 2.3 by line 2.4: Step 2.3 pcm + (-) 7.4s- pcmlppm = (6 26.BS PPm Step 2.4 (4 2- < (Subtract line 2.5 from line 1.4): T.1 / $7 (..) 27or26 - Minimum boron concentration to maintain Shutdown Margin .--. ppm - Step 2.5 IT17 Step 1.4 Required Shutdown Margin Boran Concentration c- STOP Present boron concentration:
ppm Shutdown Margin is satisfied if line 3.2 is greater than line 3.1. INITIALS Calculated By: DATE Verified By: DATE Monday, March 29,2004 TASK: TASK STANDARD:
ivo:: QPTK has beef7 calculated within 0.001 of actual QPTK value and identified as within Technical Specifications (61.02) per SPP-108.001. PREFERRED EVAL LJATION LQCATIOX PREFERRED E B'AL CIA TIOX,WETHOD CLASSKOOM PERFOKM REFERENCES:
STP-108.001 QUADRANT POWER TILT RATIO 'FOOLS: : CALCULATOR STP-108.001 DETECTOR CURRENT VALUES HANDOUT E VAL klA TION TIME 20 TIME CRPTICAL CANDIDA TE: 8% 9 PERFOEWANCI?
RA TIAT2 SAT UNSAT: QCESIION GRADE No IOCFRSS: 41(b)2 TIME TIME FINISH PERFORMA4CE Monday, March 29,ZROj Page 2 of 8 BNSTRD'e7TBOiQS IF8 QPEXATQR =AD TO OPERATOR:
WHEN i TELL YOU TO BEGIN, YOU ARE TO PERFORM TH* ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE N%GE&sect;&sect;ARY TOOL&sect; WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS:
WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIE SAFETY COXSIDEM TIONS: IMTIA L "ITPA TIRG The plant is operating at 100% power. Tha Shift Supervisor directs a Licensed Operator to perform a QPTR surveillance test? per STP-108.001,&f=p+++
+%eJ&IlaCSbehg out of service. \b Page 3 of 8


CONDITION:
Tier 't Group 1 FunctIon: K1 K2 K3 A i A2 G KIA Number Question Type    KIA Topic    RB Sa0 1   1         '43 46 ReactorTnp- 0 0 0 0 0 0 007EA2 02 Ability to detmmine and interpret the following as they WA Randomly Rejected Stabilization -    apply to (EMERGENCY PLANT EVOLUTION) (CFR uecovery I 1 1 1  41 1 0 / 4 3 5 / 4 5 1 3 )
STERY CR SEQ STEP: 1 No No Review Precautions of STP-208.001 CUES: COMMENTS:
I I
CR SEQ STEF: 2 STEF STXVDARPP:
Pressurizer Vapor Space 0 0 0 0 1 0 'OOBA41.01 , Ability to operate and / or monitcr the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I KIA Randomly Rejected
No No Reviews initial conditions of STP-208.001 Operator reviews precautions section of STP108.001 and initials the second blank on page 1 of Attatchment I, STP108.00 CUES: COMMENTS:
          ,
STEP S%LVDARIP:
    ~
Operator reviews precautions and initials the first blank on page 1 of Attachment I, STP-108.001 SAT UlVSA T SAT GTSA T CR SEQ STEF: 3 STEF SE4h'DARb): No No Determine method of QPTR caculation to be Operator determines Manual calculation used. per step 6.2 will be used, due to IPCS not being available. Operator cicles
Accident I 3    45.6)
"Step 6.2 on page 1 of Attachment I, STP108.00 CUES: Cue operator if asked: All Power Range Instruments are operationa ~.'oM~~E~vTs:
i i
Monday, March 29,2004 SAT 1:NSAT Page 5 of 8 C.X SEQ STEP: 4 STEP STANDARD):
Yes No Record the expected detector current for Records the detector current values for 100% power for each excore detector using VCS CUNE book Figure V-3A. 100% power from VCS curve bock Figure V-3A CUES: SAT If the JPM is being performed in the plant control room, after the student has UVSAT satisfactorily demonstrated that they know where to obtain the values the evaluator should give the student the handout sheet for FIGURE V-3A with the expected detector currents for 400% power. CQMMENTS:
CR SEQ STEP: 5 STEP STAiVDMD:
No No At the NI panel: ensure all detector's range Verifies all detector range sdector switches are selected to 4000 micro ampslslow selector switches are in the same scale. c*.ms: SAT GWAT COIMWEAVTX CR SEQ STEP: 6 STEP STANDARD:
Yes Yes Read the actual excore detector readings snd record on Attachment ll of STP-108.001. Reads actual excore detector readings for all NIs and records on Attachment I of STP-108.001 CUES: SAT if the JPM is being performed in the plant control room, after the student has UVSAT satisfactorily demonstrated that they know where to obtain the values the evaluator should give the student a handout sheet with detector current value Co.wnfEA~Ts:
Manday, March 29,2004 PuguSaf8 CIZ SEQ STEP: 7 STEP STANDARD:
No No Read reactor power and cofltrd bank "B" Reads reactor power and control rod bank "D" position, records on Attachment I1 of position and record on Attachment I1 of STP-lO8.00 STP-108.001 CUB: SAT If JPM is performed in classroo Cue operator when asked: Reactor power as KVSAT read on Nl's =loo% Control Bank B position = 230 steps COMMENTS:
CR SEQ STEP: 8 SIEP STA.?JDARD: Yes Yes Calculate maximum QPTR pet Attachment I Calculates maximum QPTR (1.004 *0.001 for handout values)
per STP-108.881, Attachment II and records QPTR for upper and lower core section and record data on Attachment II CUES: SAT Prompt operator that all calcuation should be taken out to AT LEAST THREE UNSAT DECIMAL PLACES. CO&fMENTS:
CY2 SEQ STEP: 9 STEP STANDARD: Yes Yes Determines if the QPTR is within Determines calcuiated QPTR to be within specification T.S. limit of 1.02. Operator initials Acceptance criteria met on page 1 of Attatchment I, STP108.001 CUES: SAT If necessary, prompt the operator to state whether or not the QPTR is acceptabl LiMSAT COMWEiVTS: Examiner ends JPM at this poin Monday, .+faarch 29,2004 Page 7 of 8 JPM SETUP SHEET DESCRIPTION:
PERFORM A QFTR CALCULATION HCSE'T: 10 1. Insert the following overrides:
IND-N1048 Analog Value=340 N-41 Detector A IND-N1049 Analog Value=334 N-41 Detector E) INB-N1084 Analog Value=335 N-42 Detector A IND-NI 085 Analog Value=364 N-42 Detector B OND-N1099 Analog Value=317 N-43 Detector A !NB-N1100 Analog Value=347 N-43 Detector B INB-N1135 Analog Value=389 N-44 Detector A INB-NI 136 Analog Value=377 N-44 Detector B 2. When student is ready RUN 1 is critical because student must be able to read proper normalized detector current values in r to properly calculate the QPTW. 3 is critical because the student must record the detecter readings properly on Attachment I tQ tep 5: Must calculate correct QPTR (fO.OO1 if given in-plant). Tolerance is low because student is ven values and no interpretation is require Tolerance is given solely for ioundoff error. Monday, March ZU,ZOQd Page 8 of 8 STP-108.001 ATTACHMENT I PAGE B OF 4 REVISION 7 SBTS NO. ~ CHANGE A TESTDATASHEET 2.0 PRECAUTIONS reviewed:
Initials 5.0 INITIAL COMDITK"3 met: Initials 6.0 Method used (circle one): Step 6.'l SkQ 6.3 8.0 ACCEPTANCE CRITERIA met: Initials PERFORMED BY: DATE/TIME:


.PAM BIUEFIXG SHEET OPERA TOR INSTRUCT1O.W:
Small Break ~ 0 10 ~ 0 ~ 0    o stem statement is associak Knowledge OF how to conduct and verify valve lineup LOCA I 3
SAFETY CQ.WIDERA TIOiW: INITIAL INITIATING The plant is operating at 100% power. (&I: The Shift Supervisor directs a Licensed Operator to perform a QPTR surveilla service. to IPCS being out of /tdT-v pGJ ;>..I., 772- 6rc &d! 3 EVALUATOR WHEN YOU FEEL THAT YOU Marrdu.p, Mnrch 29,2004 Puge 4 of8 EXCORE DETECTOR CURRENT READINGS NRC-A-002 I I DETECTOR A DETECTOR B N42 335 364 I I I
-- *---. ~ .
.,. . K Ce SUMMER NUCLEAR STATION JOB PERF NCE MEASURE JP.M NRGA-003 TAGQUP "C CHARGING PUMP APPRO VAL: APPROVAL DAlE: Munday, March 69,2004 TASK: TASK STANDA RD: NO:: 'c' CHG/SI Pump is tagged out IAW SAP-201. The pump is hydraulically isolated from the CVCS system, electrical power is removed from pump and valve motors, and pump is vented and drained. The correct tag hang sequenc is identifie The use of Human Performance Teols(3-way communications, self-checking, peer checking, phonetic alphabet, etc.) and industrial safety practice PREFERRED E VXL LM TIO?JLOCA TION PREFERRED EVALUA TIONMETHOD CLASSROOM PERFORM SAP-201 DANGER TAGGING REFERENCBS:
Large Break 0 0 11 0 OllEK3 WAKnowledge of the reasons for the following responses as  Placing wntainment fan cooler damper in accident pasition
SAP201 DANGER TAGGING TOOLS: SAP-201 SAP-201, ATTATCHMENT la SAP-201, ATTATCHMENP IB SAP-201, ATTATCHMENP IC 8-302-875, Chemical and Volume Control ELECTRICAL FEEDER LIST FOR IDA, 1DB, and 1DB2Y SOP-102 VALVE LINEUPS TECH SPEC CROSS REFERENCE FOR XPP-0043C PERFORMANCE EATIXG: Motpdny, March 29,2004 30 TIAWE CBTICAAL NO lOCFR55: 45.13 IIME TIME FINISH SAT: 1JNS.KT: QUESl'lON GRADE: PERI.OKM.4NCE SIGXATKXE DATE Page 2 of 13 IIVSTRUCTIONS TO OPE= TOR READ TO OPERATOR:
, LOCA / 3  ,   they apply to (EMERGENCY PLANT I   EVOLUTION) (CFU 41 5 / 45 6)       2 RCP  1
WHEN I TELL YOU TO BEGIN, YQU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE:
THE GENERAL CONDiTlONS UNDER WHICH THE TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR RISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THLS JOB PERFORMANCE MEASURE WILL BE SATISFIE SAFETY C.'OhBIDERA TIOM: INITIAL The plant is in Mode 1. "c" CHGlSl PUMP (XPP00436)
has developed a umps balancing line. msrgency Repair" tagout, generate a tagout for the %' CHG/SI Pump to facilitate flex gasket replacemen gs, or Locked Component - Monday, March 29, 2004 Page 3 of 13 START: TIME:


STEPS CR SEQ STEP: 1 STEP STAAIVDARD:
I o 1c o c 3 o O + ~ A I ( ofifinow L  e& nf tne .r.teireial ons uewecn {ABNORMAL  ccws    I26 Malfunctions / 4    PLANT ~ V PLANT
No Nu SYSTEM- Enter the system desinator Enters "CS" beside " SYSTEM" on affected by this Danger Tag. SAP-201, ATT. IA CUES: SAT Once the operator has determined th biNSAT completed, the evaluator will provide SAP401 is classified as " INFORM from memory; hcwever, the user retains accountability for proper performanc CUMMENZX hments lA, IB, and IC need to be cedure may be performed
      .\
/' CR SEQ STEP: 2 STEP STrlilDARD:
v O L L T , O N anJ
No No TRAIN - Enter Enters "S" beside "TTRAIN" on appropriate, ie. Attachment IA. SAT U'VSA T CLJES: COMMENTS:
      , Ihr lo ww,nr, C r R 41 7 s 45 81 I
Monda.v, Mu~rii 29, 2004 Page 5 of 13 CR SEQ STEP: 3 STEP STANDARD:
I 3
No No REASON FOR TAG - Enter a brief and Enters wording similar to
  . ,
"Replace Flex Gasket on 'C CHGlSl pump (XPWQ43C) " beside "REASON FOR TAG" on accurate account of work being performed or reason for equipment not to be operated, 1.9. MVVRs, PMs M when operation of the ,,,' Attachment IA. equipment results in a hazard i SAT If operator wants to include nomendat e in addition to the valve number, examiner ELWAY" should ask "Where can you obtain th / nomenclature?" Operator should answer CUES: " CHAMPS". If so, examiner should say, " CHAMPS is unavailable, where else can you find the nomenclature?" Operator should answer
LO55 Of R X 0 ,o 1 0 0 ;022AA1.OF ~ Ability to operate and / o r monitor the following as they CVCS charging low iiow alarm, sensor and indicator 3 Coolant Makeup / 2  ~I1 1 apply to (ABNBUMAL PLANT EVOLUTION):(CFR: 41.7 /
" SOP valve lineups." When examinee volunteers
45.6) h        4 Loss of RHU 0 0 0 lo 1 I 10 025AA202J
"valve lineups" examiner should hand the operator SOP-102 valve lineup COMMENZS:
    ',
STEP STAXDARD: Enters wording similar to  
6bility to determine and interpret the following as they ieakage of reactor coolant from RHR into closed cooling water .8 System / 4    apply to ABNORMAL PLANT EVQLUTION):(CFR: 41.10 /  system or into reactor building atmosphere 43.5/45.13),
" Ensure deenergined and isolated and drained" beside " SAFETY REMINDEW on Attachment IA CR SEQ STEP: 4 /I' No No SAFETY REMINDER
          ~
~ Indi4 any precautions such as drainin , venting, special notes or hazards associat d with this tagou SAT UWAT / ems: Operator may elect to include wording Similar to " Contaminated System: RWP required". COMMEAVTS:
Momfay, March 29,2004 Pnge 6 af I3 CR SEQ STEP: 5 STEP STXNDARD:
No No SAFETY RELATED Circle YES or NO. Circles " YES" beside " SAFETY /' ,,' RELATED" on Attachment IA. ,' /' SAT UNSAT ,I STEP STANDARD:
Circles " YES" beside " TECH SPE Attachment IA. / CUES: COMMENTS:
CR SEQ STEP: 6 No No TECH SPEC - Circle YES or NO. CLiES: il. SAT Operator may ask for a Tech Sp c Cross Reference for XPP-0043 If so, the LLVSAT evaluator will provide the Tech pec Cross Reference. Operator may ask for a Removal and Restoration (R&R) number (or the R&R form). Examiner should tell the operator
"The NROATC is completing the R&R and will provide that number when the tagout is complete." P CQMWENTS:
CR SEQ STEP: 7 No No PREPARED BY - Enter n me of the preparing this tagout pa kage. CUES: r CQMWENTS:
Mmday, .Much 29,2004 individual STEP STANDARD: Enters own name beside 'PREPARED BY" on Attachment IA. SAT Pa.?+! 7 of 13
, i I i CR SEQ STEP: 8 STEP STA.VDARD:
No No ALTERNATESF Enter the May enter "Mechanical Supervisor" or " Foreman" under " MECH" and beside lead individual's NIA. Foreman o used in " ALTERNATES FOR CLEARANCE" on lieu of a specific al Attachment IA. Foreman CL'ES: SAT UASA T CO.MWEWS:
CR SEQ . STEP: 9 STEP STAAYL4RD:
No No MWR - Enter work activity number, ie MWR, Enters " 041234" under " MWR" on PMTS, MRF, ECR or Attachment IA. STEP STANDARD: on Attachment IA. CL'ES: co'w'%fE.vTs:
CR SEQ STEP: 10 CHAMPS Enters
'XPP0043C" under " EQUIPMENT" SAT should hand the operator the 1L4Sz4T CUES: Maintainence Work Request Sheet (" green sheer') included with this packag COMMENTS:
Monday, March 29,2004 SAT UNSAT Page 8 of13 CR SEQ STEP: 11 STEP STAAD.4RD:
No No RSP GRP - Enter the abbreviation for e Enters "MECH" under " RSP GRP on Attachment IA. discipline to which the work activity ' assigne SAT WiV&sect;'4 I- / i 1 CUES: COMMENTS:
CR SEQ STEP: 12 STEP STAXDARD:
No No COMPONENT I.D. -Enter the complete CHAMPS identification number of the component to be realigned. See completed Attachment IB. SAT If operator wants to include nomen ature in addition to the valve number, examiner WVS.4T CEE&sect;: should ask 'Where can you obtain the nomenclature?" Operator should answer
" CHAMPS". If so, examiner should say, "CHAMPS is unavailable, where else can you find the nomenclature?" Operator should answer "SOP valve lineups.''
When examinee volunteers
" vaive lineups" examiner should hand the operator SOP-102 valve lineup COMMEiWS:
CR SEQ STEP: 13 STEP STANDARD:
No No PLANT LOCATION ~ Enter the specific plant location of the component o be realigned. See completed Attachment IB SAT hNSA T CWES: For this JPM, the building and elevati location. is all that is required for component COMWEX'B:
Monda.v, March 29.2004 Page 9 of13 CR SEQ STEP: 14 STEP STANDARD:
No No . BEQ'DOPEtWBbE PO the See completed Attachment iB. normal operable positio nent as specified by the applic SAT DNSA T COMMENTS:
SI%P STANDARD:
\ See completed Attachment IC. Q STEP: 15 No TAG - Enter the sequential tag number. SA T LWSAT Tag number is not critical, only the sequence is. COMMENTS:
CR Sh'Q STEP: 16 fld STEP STANDMW: No No ISSUED TO Check blocks for which See completed Attachment IC. discipline each component is tagged. SAT UXSAT COMMEATS:
:Monday, March 29,2004 Page IO of 13 CR SEQ STEP: 17 STEP STANDARD:
No No HOLD TAG INST - Enter a check mark if a Hold Tag is to be placed on a control panel component. See completed Attachment IC. CUES: SAT LWSA T COMMENTS:
SEQ STEP: 18 \-i STEP STAXDARD:
No COMPONENT I.D. ~ Enter the complete CHAMPS identification number of the component being tagged. See completed Attachment IC. CUES: SAT If operator wants to include nomenclature in addition to the valve number, examiner UWAT should ask 'Where can you obtain the nomenclature? Operator should answer
" CHAMPS". If so, examiner should say, " CHAMPS is unavailable, where else can you find the nomenclature?" Operator should answer " SOP valve lineups." When examinee volunteers
" valve lineups" examiner should hand the operator SQP-102 valve lineup COMME.VZ7:
SEQ STEP: 49 STEP STANDARD:
o No PLANT LOC - Enter the specific plant location See completed Attachment I of the component beging tagged. CUES: SAT For this JPM, the building and elevation is all that is required for eompanent UASA T locatio COMMENZS:
Moonday, Murch 29,2004 Page Ii of 13 CR SEQ STEP: 20 STEP STA,VI?ARD:
No REQ'D TAG POSIT - Enter the position in which the component is to be tagged. See completed Attachment IC. SAT ENSAT CO.WMEIVZY:
CR SEQ STEP: 21 STEP STAXDAD: No INST SEQ - Enter sequence that tags are to be installe If no sequence is needed, place a 1 in each INST SEQ black. If only some tags require a sequence, number these tags in sequence starting with 1 and ending with all tags not requiring sequence having the same number, for example, 1, 2. 3, 4, 4,4. See completed Attachment IC. COMME.VTS: Examiner ends JPM at this poin Monhj?, March 29,2004 Pnge 12 of13 JPM SETUP SHEET JPMiVO: NRC-A403 DESCRZPTION:
TAGOUT " C CHARGING PUMP IC SET: JPMiVO: NRC-A403 DESCRZPTION:
TAGOUT " C CHARGING PUMP IC SET: ZNSTR GrCTIQiVS:
Monday, March 29,2004 I 1 I I I I I I I I I D S 1 8 fb n I1 El I e1 E tl I 01 I 91 I LI -- I I z E I t V


OPERA TOR LVSTRLiCa"IOLVS:
I boss of D O 0 0 0 0 026AK301  Knowledge of the reasons for the following responses as KIA Randomly Uqected  I 32 Component    they apply lo (ABNORMAL PLANT EVOLUTION) (CFR Cooling Water /    41 5 / 4 5 6 )
SAFETY CONSIDERA T1O.V.Y: I.VITIAL "C" CHG/SI PUMP (XPP0043C)
I8 Isolation of PZR spray following loss of PZR heaters 35 38
has developed a flex gasket on the pumps balancing line. has requested an " Emergency Repair" tagout, epiace flex gasket. Shift Supervisor directs you to generate a tagout for the 'c' GHGISI Pump (isolated,vented and drained) to facilitate flex gasket replacemen Completion of individual Danger Tags, Hold Tags, or Locked Component Tracking Sheets is NOT REQUIRE HAVE SATISFACTORILY COMPLETED THE ASSIGNE Monday, Marcli 29,2004 Page 4 of 23 JPLWBRIEFING SHEET OPERATOR PMSTRLrCTPOMS:
'1 Pressurizer pressure Control System 0 0  hnowlcoge of the reasons for the fu owing responses as tnev apply to ,ABNORMAL PLAN1 FVOL'JT ON, (CFR
SAFETY COLVSIDERATIOIW:
INITIAL An NLQ has been assigned the task of performing a valve lineup in the Auxiliary Building. The area where the valves ate located has a dose rate of 24 mWHr. and also has some airborne activity. From experience the NLO knows that it will take 45 minutes to perform the valve lineup with out a respirator, or 75 minutes to complete the job with a respirato If the job is done without a respirator the NLO will receive 2 DAC-hours of internal exposur You have been directed to: Determine the dose the MLQ will receive if he doesn't wear a respirator whiie performing the valve lineup and the dose he will receive if he wears a respirato Report to the Shift Supervisor which method will be the lowest dose and keep exposure ALARA. HAVE SATISFACTOMLY COMPLETED THE Menday, March 29,2004 Page 4 of 7 ( tu%-
. R STATION NCE MEASURE NRC-A404 s with Airborne Activity Present APPRO VAL: APPRO VAL DATE: CAND[DATE-.~..- - bX&UINER:..~
~. .- , . .Moortdoy, March 29,2004 R STATION NCE MEASURE NRC-A404 s with Airborne Activity Present APPRO VAL: APPRO VAL DATE: LANDCDATE- - bX&UINER - .Moortdoy, March 29,2004 Pug@ I of 7 TASK: 343-029-03-03 E4SK STANDARD: Assess exposure limits of personnel for assigned duties NO:: Dose is correctly calculated with a respirator and without a respirato GEN 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. (RO 2.6/SRO 3.0). GEN 2.3.4 Knowledge of facility MAW program. (RO 2.5/SR02.9)
PEEFERRdD EVALUATION LOU TIOA' PREFERRED E VAL lL4 TIOX METHOD PLANT PERFORM REFEmlVCEs:
TOOLS: EVAk UATIQN TIME 10 TIME CRITICAL NO lOCFR5.f:
43B4 CANDIDA TE: TIME TThlE FMISII: PERFORMAACE RA TIXG: SAT: UNSAT QCEWLON GKrWE PERFORMANCE ExA,1.INER:
CQMMENZS:
SIGNhrURP DATE Monday, March 29,2004 Page 2 of 7


WART TIME:
Malfunction I 3
STEPS CR SEQ STEP: 1 STEP STANDARD:
Yes No Calculates NLO dos Calculates the dose to the NLO without a = 18.0 mRem + respirato .75 hours X 2 DAC hours 18.0 + 5 mRem ems: SAT UNSA T CO.WMENTS:
CR SI@ STEP: 2 STEP SITANDARD:
Yes No Calculates NLO dose Calculates the dose to the NbO with a respirator 1.25 hours X 24 mRemlhour
= 40 mRem. / CUES: SAT UXSA T COMMBNT.9:
STEP STAXDARD: Reports to Shift Supewisor that performance of work should be performed without a respirator to achieve a dose that is ALARA. CR SEQ STEP: 3 Yes No job should be performed and reports findings to CUES: COMMENTS:
A4oonJa.v. .March 29,2004 SAT UN.9'4 T Page 5 of 7 Examiner ends JPM at this point Monday, March 29,2004 P5ge 7 of 7 V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE *=e--. JPM NO: JPPF-028 STARTUP AND PARALLEL A ROD DRIVE MW SET APPROVAL:
TRH APPROVAL DATE: 07/07/2003 - - - CANDIDATE
.. ~ .~ EXAMINER Page I of I I TASK: .--.-. 001 -007-01 -04 TASK STAXDARD:
STARTUP THE FULL LENGTH ROD CONTROL SYSTEM The "#1" rod drive MIG set has been started and parallel has been attempted. Due to the failure to parallel, the operator restores 81 MG set to standby status in accordance with Step lll.A.2. The use of applicable Human Performance Tools (3-way communications, self checking, pser checking, phonetic alphabet, etc)
and industrial safety practices meets expectation PREFERRED EVALVA TION LOCATION PREFERRED EVALUATION METHOD PLANT SIMULATE REFERENCES: SOP-403 ROD CONTRQL AND POSITION INDICATING SYSTEh TOOLS: SOP-403 SECTION III.A, STEPS 2.1 AND 2.3 EVALUATION TI.ME 20 TME CRITICAL No lOCFR55: 45(a)l Il'ednusduy, March 24, 2004 V. Page 2 of11 INSTRUCTIOXS TO OPERATOR REAZ) TO OPEZUTOR:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YQU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIE ZNZTZAL CONDZTIOA:
A plant heatup is in progres Initial conditions for startup of the red drive M/G sets have been completed per SOP-403, Section 1lI.A. The "#2" Rod Drive Motor Generator is already running. ZA'ZTZAZZNG CUES: NROATC directs that #1 red drive M/G set be started and paralleled in accordance with SOP-403, Section III.A, Steps 2.1 and 2.3. -.-- iATNO TIMEAR* YOU TO OPERATE :ANY PLANT EQUIPMlENT!
I I Wednrsduy, March 24. 2004 Page 3 uf 11
.IPM BRIEFING SHEET OPERA TOR INSTRUCTIONS:
SAFETY COA'SIDERA TIOAW INITIAL COA7DITION:
A plant heatup is in progress. Initial conditions for startup of the rod drive M/G sets have been completed per SOP-403, Section 1II.A. The "#2" Rod Drive Motor Generator is already running. INITIATING CEES: NROATC directs that
#1 rod drive MIG set be started and paralleled in accordance with SOP-403, Section IIM, Steps 2.1 and 2.3. I I :AT NO TiME ARE YOU TO OPERATE ANY - :PLANT EQUIPMENT! - HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. Wednesdaj, March 24,2004 Page 4 of 11 STEPS CR SEQ STEP: 1 STEP STANDARI):
No Yes Place VOLTMETER selector is position 1-2. Positions M/G set 81 VOLTMETER selector switch to the 1-2 positio ~- CUES: SAT LJhJSA 1' Cue operator before entering Rod Control Room to point to each operation performed and indication observed due to high noise area. Operator may use a pad of paper to write down additional information for examiner. Cue operator that voltmeter selector switch is in position 1-2. COMMEh7ZS:
CR SEQ STEP: 2 STEP STAXDARI):
No Yes Adjust VOLTAGE ADJUST potentiometer to Adjusts VOLTAGE ADJUST minimum by releasing the lock and turning fully counterclockwis potentiometer to minimum by releasing the lock and rotating potentiometer fully counterclockwis ~~~~ ~~~~~ ~ CUES: SAT UNSA T Cue operator that VOLTAGE ADJUST potentiometer has been turned fully counterclockwis CUMMEi\J1;F:
___.. CR SEQ STEP: 3 STEP STANDARD:
No Yes Place AMMETER selector in position A. Places ME set #1 AMMETER selector switch to the
" A position. - CUES: SAT LWS.4 T Cue operator that AMMETER switch is in the
" A positio ___ COMMENTS:
Wednesday, March 24,2004 Page 5of 11 CR SEQ STEP: 4 STEP STANDARL): Yes Yes Close MOTOR Breaker to start MIG #l. Positions MIG set #1 MOTOR Breaker to CLOSE positio Ct7ES: SAT After operator describes the expected response, then cue operator that the red ETA,sAT light is lit on MIG set #1 and the green light is off. COMhfEiVtS:
CR SEQ STEP: 5 STEP STANDARB: Yes Yes Depress and hold GEN FIELD FLASH Depresses and holds GEN FIELD pushbutton until voltage is at least 235 VOLTS as indicated by GENERATOR LINE VOLTS, then release. releases pushbutto FLASK pushbutton until voltage reads at least 235 volts on voltmeter and then ~~ CUES: SAT Examiner informs operator that the voltmeter reads 240 volt after field flash by ULvsAT pointing at indicatio COMhfENTS:
~ - CR SEQ STEP: 6 STEP STANDARD: Yes Yes Adjust VOLTAGE ADJUST potentiometer Adjusts VOLTAGE ADJUST clockwise until 255 TO 265 VOLTS is indicated by GENERATOR LINE VOLTS. potentiometer clockwise until voltage meter at MIG control panel for
#1 MIG set indicates 260 * 5 volts. CCJES: SAT UNSA T Cue operator that voltage increases to 260 VOLT&sect; (as seen) by pointing at indicatio CUMiWEi\'TS:
___ Wedne\day, March 24,2001 Page 6ofII CR SEQ STEP: 7 STEP STANDARD:
No Yes With the VOLTMETER selector in position 2- Verifies 260 a 5 volts on voltmeter phase 2-3 by placing voltmeter selector switch to the 2-3 positio , verify indication is between 255 and 265 volts. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~. CUES: SAT C'NSA T Examiner informs operator that each phase indicates 260 volts when each phase is selected by pointing at indicatio COMMENTS:
._ C,'X SEQ STEP: 8 STEP STANDARD:
No Yes With the VQLTMETER selector in position 3- Verifies 260 5 volts on voltmeter 1, verify indication is between 255 and 265 volts. phase 3-1 by placing voltmeter selector switch to the 3-1 positio ~ CUES: SA T UNSA T Examiner informs operator that each phase indicates 260 volts when each phase is selected by pointing at indicatio ___ CR SEQ STEP: 9 STEP STANDARD:
No Yes Lock the VOLTAGE ADJUST potentiomete Locks the Voltage Adjust potentiomete CL'ES: SAT If performed correctly, cue operator that the voltage adjust potentiometer is CWSA T lacked. COMMENTS:
Wednesday, Murch 24, 2004 Page 7ofII C R SEQ srm: IO STEP SIAh'DARD: Yes Yes Parallel Generator No. 1 as follows: Turn Positions the Generator No.1 Generator No.1 SYNCHRONIZE Switch ON. SYNCHRONIZE Switch to the ON positio CIIES: SAT Examiner informs operator that #2 M/G set I S already running per step 2.2 SOP- UlvsAT COM-WENTS:
___ 403 and the #2 M/G set generator breaker is as-is if information is requeste ~ CR SEQ STEP: 11 STEP STANDARD: Yes Yes Place Generator No. 1 GENERATOR Positions the M/G set #1 GENERATOR Breaker Switch to CLOSE. circuit breaker switch to the CLOSE positio ~___ CUES: SAT After examinee describes expected actions, cue operator that green light is off ti:asAT and that red light is lit by pointing to indicatio COMMENTS:
__ - .. CR SEQ STEP: 12 STEP STAXDARD: Yes Yes Verify GENERATOR No. 1 GENERATOR Verifies M/G set #I generator breaker Breaker closed. closed by red light indicator lit for #1 M/G generator breaker. CUES: .. SA I' After examinee describes expected actions, cue examinee that green light is lit and that the red light is off by pointing to M/G set #1 generator circuit breaker. Inform examinee that conditions have not changed for TWO (2) minutes. NOTE: This indicates a failure to parallel, the examinee should perform the following steps. (13 -18). COMMENTS:
t;N,~A~ Wednesday, March 24, 2004 Page 8 of I1 CR SEQ STEP: 13 STEP SlilNDARD:
~.. . . .. Yes Yes Place Generator No. 1 GENERATOR Positions the MM set #I GENERATOR Breaker Switch to TRIP. circuit breaker switch to the TRIP positio CL'ES: SAT After examinee describes expected actions, cue operator that green light is ON and that red light is OFF by pointing to indicatio C:(IMMEh"TS:
c,xsA1' CR SEQ STEP: 14 STEP STANDARD:
No Yes Turn Generator No. I SYNCHRONIZE Positions Generator No. i Switch to OFF. SYNCHRONIZE switch to the OFF positio CUES: SAT L'NSA T After examinee describes expected actions, cue operator that MIG set #1 synchronizer is in OFF positio COM34ENT.Y:
,-. CR SEQ STEP: 15 STEP STANDARD: Yes Yes Readjust VOLTAGE ADJUST potentiometer Readjusts VOLTAGE ADJUST clockwise until 255 TO 265 VOLTS is indicated by GENERATOR LINE VOLTS. potentiometer clockwise until voltage meter at M/G control panel for #I MIG set indicates 260 f 5 volts. ~. [INSAT Cue operator that voltage increases to 260 VOLTS (as seen) by pointing at indicatio Wednehday, March 24,2004 Page 9 of I1 CR SEQ STEP: 16 s1'EP STANDARD:
~-~, No Yes Turn Generator No. 1 SYNCHRONIZE Positions Generator No. 1 Switch to ON. SYNCHRONIZE switch to the ON positio ~. CUES: SAT L:1ISA T After examinee describes expected actions, cue operator that M/G set #I synchronizer is in ON positio COM.ME"S:
__ CR SEQ STEP: 17 Yes Yes Place Generator No. 1 GENERATOR Breaker Switch to CLOSE. STEP STANDARD:
Positions the MIG set #1 GENERATOR circuit breaker switch to the CLOSE positio ____ CUES: SA 1 After examinee describes expected actions, cue operator that green light is off U~~SAT COMMENTS:
and that red light is lit by pointing to indicatio _ , .-a STEP STANDARD:
CR SEQ STEP: 18 No No Verify Generator No. 1 GENERATOR Verifies Generator No. 1 GENERATOR breaker closed. breaker closed. UJES: SA T After examinee describes expected actions, cue operator that green light is off u,v,~r and that red light is lit by pointing to Generator Breaker indicatio COMMEXTS:
Examiner ends JPM at this point. Wedraesduy, March 24,2004 Page 10 of I1 JPM SETUP SHEET -_. JPMNO: JPPF-028 DESCRIPTION:
STARTUP AND PARALLEL A ROB DRIVE ME &sect;ET IC SET: INSTRUCTIOi1Ts':
IVednrsda)'.
March 24, 21104 Page 11 of 11 V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE JPM NO: JPP-108 LOCALLY SHED NOM-ESSENTIAL UC LQAUS APPROVAL:
TRH APPKOVAL DATE: 07/31/2003 REVh'O: 9 CANDIDATE . EXAMINBR Wednesday, March 24,2004 .- Page I of9 TASK: 000-1 14-05-04 RESPOND TO LOSS OF ALL ENGINEERING SAFETY FEATURES ALTERNATING CURRENT POWER TASK STARTDARD:
Nonessential DC loads have been shed per EQP-6.0. Attachment 2. The use of applicable Human Performance Tools (3-way communications, self checking, peer checking, phonetic alphabet, etc) and industrial safety practices meets expectation PREFERRED EVALUATION LOCATION PLANT REFERENCES:
EO$-6.0 TOOLS: EOP-6.0, Attachment 2 FLASHLIGHT EVALUATION TIME 15 CANDIDATE:
PERFORMANCE RATING: SAT PREFERRED EVALUATION METHOD SIMULATE LOSS OF ALL ESF AC POWER TIME CRITICAL No IOCFRSS: 45(a)8 Wednesday, March 24,2004 Page 2 of9 INSTRUCTIONS TO OPERATOR READ TO OPERATOR:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED SAFETY CONSIDERATIONS:
INITIAL CONDITIOAr:
The plant is at 100% power when a station blackout occurs, with subsequent entry into EOP-6.0. INITIATING CUES: Control Roam Supervisor directs stripping nonessential BC loads per EOP-6.0, Attachment 2. Wednesday, Marrir 24,2004 Page 3 of 9 JPM BRIEFING SHEET \_ OPERATOR INSTRUCTIONS:
SAFETY CONSIDERA TIONS: IhTTIAI, CONDITION:
The plant is at 100% power when a station blackout QCCUIS, with subsequent entry into EQP-6.0. INITIATING ClJES: Control Room Supervisor directs stripping nonessential DC loads per EOP-6.0, Attachment 2. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE
-.e ASSIGNED TASK. Wednesday, March 24,2004 Page 4 of 9 STEPS CR SEQ STEP: 1 STEP STANDARD:
.... Yes Yes Close GEN GAS PURGING SYS Operator closes GEN GAS PURGING HYDROGEN SUPPLY valve (TB-412). SYS HYDROGEN SUPPLY VLV (XVr12225-HY)
by turning valve handwheel in the clockwise direction until the valve is closed. CUES: Valve turns clockwise then stops COMMENTS:
SAT UNSAT CR SEQ STEP: 2 STEP STANDARD:
Yes Yes Open HYDROGEN-CARBON DIOXIDE Operator opens HYDROGEN-CARBON XCONN VALVE (TB-412). DIOXIDE XCONN VALVE (XVT-12218-
HY) by turning the handwheel in the counter-clockwise direction until the valve is open. . _, CUES: Valve turns counter-clockwise then stops COMMEh'TS:
Wednesday, Murch 24,2009 SAT Page 5 of 9 CR SEQ STEP: 3 .-. ~ Yes Yes Open CARBON DIOXIDE VENT HEADER ISOL VALVE (TB-412).


STEP STAA'DARD:
75 Point Teh...
Operator opens CARBON DIOXIDE VENT HEADER ISOL VALVE (XVTl0556-CD)
Pier *-Group I Name i Safely Function: Kt KZ K3 A I A2 G KIA Number ~ Question Type    KIA Topic    RO SRO IATWSII  029EK2 O&Knowledge  ofthe interrelations between (EMERGENCY Breakers. relays, and disconnects .1 PLANT EVOLUTION) and the following (CFR 41 7 145 8)
by turning the valve handwheel in the counter-clockwise direction until the valve is open CUES: Valve turns counter-clockwise then stops. COMMEVTS:
h
CR SEQ STEP: 4 Yes Yes Open MAIN CONDENSER A & B VACUUM BREAKER (TE-436). CUES: SAT .- UA'SAT STEP STANDARD:
  . ,
Operator opens MAIN CONDENSER AR) operating the Declutch mechanism and turning the handwheel CCW until handwheel stops. A&B VACUUM BREAKER (XVEOOlOl-
Steam Ge Ability to operate and / o r monitor the following as they KIA Randomly Rejected .4
SAT -. Valve position indicator is not calibrated and therefore not required for this step. Valve turns clockwise then stops. COMMENTS:
, Tube Rupture /   amlv to EMEUGENCY PLANT EVOLUTION):(CFR: 4 I I3
UN,~AT .-__ CR SEQ STEP: 5 STEP STAXDARD:
            !
No Yes Check if the MFW pumps have stopped. Operator verifies that the shafts of the (TB-436). MFW pumps are stopped. CUES: SAT When requeste inform the examinee that each MFW pump shaft is stopped UNSAT COMMENTS:
Ueactivity effects of cooldown .4 Steam Line  0 0 0 1040AK1 05 Ruptuie -
Wednesday?
1 Excessive Heat Transfer I 4 Loss of Main Feedwater / 4
March 24,2004 - Pa@ 6 of 9 CR SEQ STEP: 6 STEP STANDARD:
No Yes Check if the Main Turbine has stopped. (TB- Operator verifies that the main turbine 463). shaft has stopped. CUES: SAT When requested inform the examinee that Main Turbine speed indicates
" zero". UNsAT COMMENlS:
~ CR SEQ STEP: 7 STEP STANDARD:
No Yes Check that IPI-5130, MACHINE Operator verifies that IPI-5130 indicates HYDROGEN GAS PRESSURE INDICATOR, indicates less than 5 psig. (TB- 412). less than 5 psig on the Turbine/Generator Auxiliary Panel. CUES: SAT Cue examinee that 20 minutes has elapsed and hydrogen pressure indicates C"SAT " zero" after XVTl0556 is opened. COMMENZS:
~ ~__ CR SEQ STEP: a STEP STANDARD:
Yes Yes De-energize TPP00224, (B), (C) - FWPT Operator opens breaker for EMERGENCY BEARING OIL PP (TB-412). FWPA(B)(C) - FWP EBOQ (XSX0002A(B)(C))
from Panel DPN-2X 01 (02)(03) after FW pumps stop. ClJES: SAT UNSA T If requested, inform the examinee that each MFW pump shaft is stopped. ~ COMMENTS:
Wednesday, March 24,2004 i Page 7 of 9 CR SEQ STEP: 9 -_ Yes Yes De-energize EMERGENCY SEAL OIL PUMP, XPTTOoOl-PP3 (TB-412). STEP STANDARD:
Operator de-energizes XI PO001 -FY3 EMEHGENCY SEAL OIL PUMP from ?ace1 DPN.QX by ope'ling breaker #4. CUES: If requested, inform operator that machine gas pressure is < 5 psig. COMMENTS:
CR SEQ STEP: 10 STEP STANDARD: Yes Yes De-energize breaker for EBOP (XSXOOCS)
Operator deenergizes MAIN TURB. EMERG. BEARING OIL PP, (XQROOI), by opening breaker 05 (XSXOOOS)
on BPN-ZX, after the Main Turbine has stopped. (TB-412). CUES: If requested, inform examinee that Main Turbine shaft has stopped --. COMMENTS:
Examiner ends JPM at this point U'ednesduy, Murch 24,2004 Page 8 of 9 JPM SETUP SHEET .d JP.%f,VU:
JPP-108 DESCRIPTION:
LOCALLY SHED NON-ESSENTIAL DC LOADS IC SET: INSTRUCTIONS:
COMMENTS:
Wedizesduy, Murch 24,2004 L. Puge 9 of 9 V.C. SUMMER NUCLEAR STATION JQB PERFORMANCE MEASURE JPM JPPF-301 LOSS OF CONTAINMENT INTEGRITY (MVG-6797) APPROVAL:
APPROVAL DATE: REV NO: Wednesday, March 10,2004 Page 1 of 7 TASK: -- TASK STANDARD:
NO:.' Fire service to the Reactor Building is isolated per EOP 1 .Or Attachment 4 and 5. The use of the PREFERRED EVALUATION LOCA TION PREFERRED EVALUATION METHOD PLANT SIMULATE REFERENCES:
EOP-I .o REACTOR TRIP/SAF*TY INJECTION ACTUATION TOOLS: EOP 1 .O Attachment 4, page 3 of 4 EOP 1 .0 Attachment 5, page 2 of 4 OAP 100.5 GUIDELINES FOR CONFIGURATION CONTROL AND OPERATION OF PLANT EQUIPMENT, Step 9.5 EVALCJATION TIME 10 TIME CRITICAL NO IOCFRSS: CAXDIDA TE: TIME START TIME RMSH PERFORMANCE RATING: S A T: LXL'SAT u QUESTION FR.ADE PEKFORMANCE EXAMIA'ER:
CQMMENTS:
Wednesday, March 10,2004 SICKATCRE UATE Page 2 of 7 INSTRUCTIONS TU OPERATOR READ TO OPERATOR:
WHEN I TELL YOU TO BEGIN. YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIE L SAFETY CONSIDERATKONS:
INZTKAL CONDITION:
The plant has experienced an SI from 100% power with the CRS implementing EOP 1 .O. The BOP operator, while performing EOP 1 .O Attachment 3, notes that the status light for SAFETY INJECTION PHASE A lSOb on XCP 6104 for FIRE SERV ISOL 6797 CLSD is dim, indicating the valve has failed to close on a valid phase "W containment isolation signal. The CMC switch on the MCB for MVG 6797 has no white indicating lights, and the red OPEN light is lit and the green CLOSE llght is not lit. KNPI'KATINC; CUES: The Control Room Supervisor directs you to close MVG-6797 manually as the BACKUP ISOLATION to XVG06797-FS per EOP 1 .O, Attachment 5, page 2 of 4. AT NO TIME ARE YOU TO OPERATE ANY PLANT EQUIPMENT!
HAND JPM BRIEFING SHEET TO OPERATOR AT 1'111s TIME! applicable Human Performance Tools (3-way communications, self checking, peer checking, phonetic Wdnesdny, March 10, 2004 - .- Page 3 of 7  
'TIME:
JPM BRIEFING SHEET OPERA TOR ILVSI'KUCTIONbS:
SAFETY CONSIDERA I'IONS: INITIAL CONDIIIIION:
The plant has experienced an SI from 100% power with the CRS implementing EOP 1 .O. The BOP operator, while performing EOP 1 .O Attachment 3, notes that the status light for SAFETY INJECTION PHASE A ISOL on XCP 6104 for FIRE SEWV SOL 6797 CLSD is dim, indicating the valve has failed to close on a valid phase " A containment isolation signal. The CMC switch on the MCB for MVG 6797 has no white indicating lights, and the red OPEN light is lit and the green CLOSE light is not lit. INITIATING CIJES: The Control Room Supervisor directs you to close MVG-6747 manually as the BACKUP ISOLATION to XVG06797-FS per EOP 1 .O, Attachment 5, page 2 of 4. ATNO T/MEARE YOU TO OPERATEANY PLANT EQUIPMENT!
alphabet, etc.) and industrial safety practices meets expectation ASSIGNED TASK. Wednesday, March l0,2004 Page I of 7 STEPS CR SEQ STEP: 1 STEP STANDARD: No No Puli down on the declutch lever, to disconnect Examinee simulates pushing the declutching lever away from the the motor from the handwheel via a clutch assembl handwhee CUES: SAT If examinee mentions checking the breaker first and/or opening the breaker prior to KVSAT operation of the valve manually, inform the examinee that 1 BB2Y 23 AD, FS TO RB CHARCOAL CLEANUP SYS 4A-4B ORC XVG 6797-F&sect;, has already been checked. The overloads were found tripped and could not be reset, and the breaker was opened. COMMENTS:
CR SEQ STEP: 2 STEP STANDARD:
No No Turn the handwheel in the clockwise direction The examinee simulates turning the valve handwheel in the clockwise (closed)
direction until movement stops. CUES: SAT Cue to examinee that the handwheel rotated manually for several revolutions and UNSAT -_ then stopped. COMMEIL'I'S:
Wednesduy, .Wurch 10,2004 ._ Pa@ 5 of 7 CR SEQ STEP: 3 STEP STANDARD:
No No Leave declutch lever in the down (motor Examinee simulates releasing the ... _.. disengaged)
positio The motor will declutching lever. re-engage when motion is demanded electricall CUES: SAT There is no reliable valve position indication on an MOV. Cue the operator that the L'NSAT CRS has informed the operator that the SAFETY INJECTION PHASE A ISOL monitor light on XCP 6404 for FIRE SERV IWL 6797 CLSD light is now BRIGHT. Examiner ends JPM at this point. Wednasdq, March 10,2004 Page 6 of 7 JPM SETUP SHEET JPM NO: JPPF-301 DESCRIPTIOIV:
LOSS OF CONTAINMENT INTEGRITY (MVG-6797) IC SET: INSTRUCTIONS:
COMMENTS:
Wednesday, March 10,2004 - Page 7 of 7 V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE JPM JPSF-002 TRANSFER TO HOT LEG RECIRCULATION APPROVAL:
APPROVhL DhlE: REVNO: 6 CANDIP ATE EX/U1IIVER Wednesday, March IO, 2004 Page I of I1 TASK: 000-1 37-05-01 TRANSFER RHR FROM COLD LEG TO HOT LEG RECIRCULATION
.. , TASK STANDARD:
NO:: Safety Injection system has been aligned for Hot Leg Recirculatio Charging pumps haw not been runout or deadheade The use of applicable Human Performance Tools (Sway communications, self checking, peer checking, phonetic alphabet, etc) and industrial safety practices meets expectation PREFERRED EVALUATION LOCATION PREFERRED EVAGLTA TIOh' METHOD SIMULATOR REFERENCES:
EOP-2.0 EOP-2.3 'rooLs: EVALUATION TIME CANDIDATE:
PEIWORhfANCE RATING: - EXAMINER:
COMMENTS:
Wednesday, March 10,2004 PERFORM LOSS OF REACTOR OR SECONDARY COOLANT TRANSFER TO HOT LEG RECIRCULATION 10 TIME CRITICAL No loCFR55: 45(a)7 TIME START: TIME FINISH:
SAT: UNSAT QUESTION GRADE:
PERFORM ANCE SIGNATURE DATE Page 2 of 11 IA'STRUCTIONS TO OPERATOR READ TO OPERATOR:
._ WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHIW TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED SAFETY CONSlDERA TIONS: INITlAL CONDITlON:
It has been 8 hours since a Loss of Coolant Accident occurred and the plant is presently in the Cold Leg Recirculation mode. The CRS has entered EOP-2.3 (Hot Leg Recirculation)
from EOP-2.0. CHG/&sect;I Pump C is aligned to " B hain. INITIATING CUES: The CRS directs the NROATC to transfer from Cold Leg to Hot Leg Recirculation per EOP-2.3. ._ . HAND JPM BRIEFING MEET TO OFEKATOR AT THIS TIME! Wednecday, March IO, 2004 Pap 3 of I1 TME: .. .
..- JPM BRIEFING SHEET OPERA TOR ZiVSTRC%TIONS:
SAFETY CONSlDE TIONS: Ih'ZTlAL CONDIllON:
It has been 8 hours since a Lass of Coolant Accident occurred and the plant is presently in the Cold Leg Recirculation mode. The CRS has entered EOP-2.3 (Hot Leg Recirculation) from EOQ-2.0. CHGiSl Pump C is aligned to "B" train. INZTZATZNG CUES: The CRS directs the NROATC to transfer from Cold beg to Hot Leg Recirculation per EOP-2.3. -_ HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TAS Wedriesday, March 10, 2004 ._I Page 4 of11 STEPS CK SEQ STEP: 1 STEP STANDARD: - Ye Yes Stop the Charging Pump on " A" Train CHG/SI Pump 'A indicates OFF SAT Charging Pump " A is still running when 8885 is closed, it will be deadheaded; this onstitutes failure. Running the charging pump with both 8885 and a84 runs the mp out, also failing. UNSA T CK SEQ STEP: 2 No Yes Check if CHG/SI Pump C is aligned to Train A by verifying XFER switch XET 2002C on Train A is lit. CUES: COMMENTS:
CH SEQ STEP: 3 --- Ye Yes Ensure MVG-8132A(B), CHG PP C TO LP A BISCH, are closed. CUES: COMMENTS:
STEP SlAiVDAKD:
XFER SWITCH XET 2002C on Train A is not lit, directing the operator to alternative action step 1 .b. SAT UNSAT STEP STANDARD:
MVG-8132A and MVG-81328, CHG PPL C TO bP A BISCH, indicate CLOSE. SAT UNSAT Wedrresrlay, March 10,2004 PageSofII CR SEQ STEP: 4 STEP STANDARD:
Ye Yes Close charging LP " A" ALT to COLD LEG MVG-8%%5, CHG LP A TO COLD LEGS, -. (MVG-8885).


indicates CLOSE. CUES: C0M.WENT.S:
  ,
SAT UNSA T CR SEQ STEP: 5 STEP STANDARD:
Ye Yes Open CHG LP " A" to HOT LEGS (MVG-8884).


MVG-8884, CHG LP A TO HOP LEGS, indicates OPEN. CUES: COMMENTS:
  . .
CR SEQ STEP: 6 Ye No Start " A Charging Pump -.._ CUES: COMMELVI'S:
0 054AA1.02' -4 Ability lo operate and / o r monitor the following as they
Wednrsday, March 10, 2004 SAT UNSAT STEP STANDARD:
        ~-
CHG/SI PUMP " A indicates ON with normal running amps. SAT Uh'SA T PageduflI CR SEQ STEP: 7 Ye Yes Stop "B" charging pump. CUES: CR SEQ STEP: 8 No Yes Check if 'c' charging pump is aligned to Train B. CUES: COMMENTS:
apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 /
CK SEQ STEP: 9 STEP STANDARD:
45.6)
CHGlSI Pump 't3' indicates OFF with 0 amps. SAT UNSAT STEP STANDARD:
        ' Manual staltup of electric and steam-driven ARM pumps ~
Verifies XFER SWITCH XET2000C ON TRAIN B is lit. SAT UhSA T STEP STANDARD:
I , !  &
No Yes Ensum MVG-8132A and MVG-$1328, CHG PP MVG-8132A and MVG-81328, CHG PP C C TO bP A DISCH, are closed. TO bP A DISC#, indicate CLOSE. .- CUES: COMMEXT s: Wednesduy, &furrh 10,2004 SA T UNSA T Puge 7 of I1 CR SEQ STEP: 10 STEP STANDARD:
      \ = & I b /       ~
No Yes Verify HI HEAD to COLD LEG INJECTION MVG-8801A, HI HEAD TO COLD LEG INJ -._. (MVG-88OlA)
Instruments and cantrols operable with only dc battery power 3.7 , Station  0 1 0 ,055EA2.04 Ability lo determine and interpret the following as they Blackout / 6   apply to (EMERGENCY PLANT EVOLUTICJN):(CFR: available 41.10 /43.5 /45,13H        !
is closed. indicates CLOSE. CUES: COMMENTS:
Loss of Off-site Power 16 0 0 0 056AK1 03  -
SA I' UNSA T CR SEQ STEP: 11 STEP STANDARD:
Knowledae of theooerational a ~ ~ l ~ c a l i of co:icepls as they appy to me ARNORMhl. PLANT o nthe -
Ye Yes Close HI HEAD TO COLD LEG INJECTION valve MVG-8801 B, Hi HEAD TO COLD LEG INJ MVG-8801 B. indicates CLOSE. CUES: SAT constitutes failure of the JPM. pi'/v &z+~/N COMMENTS:
s followinQ Definition of subcwling: use of steam tables to determine it 3.1 , EVOLiTlONl (CFR 41 81041 10)
/k- If 8801 B is closed with "B" Charging Pump running, this deadheads the pump and UNSAT . ( N2a-- ~~7 -$ CR SEQ STEP: 42 STEP STANDARD:
  . . .
Ye Yes Open MVG-8886,CHG LOOP "B" in HOT LEGS. MVG-8886, CHG LP B TO HOT LEGS, I indicates OPEN. CUES: COMMENTS:
Loss Of V l k l 0 ! 0 1 '057AG his is a Generic, no stem statement is associate Ability to explain and apply all system limits and precautions. .8
Wednesday, March IO, 2004 SAT UNSAT Page 8 of 11 CR SEQ STEP: 13 Ye No Start "5" CHGiSl pump. .-_ STEP STAiVIEARD:
bs ,d7 /ci"' 4 P" C#G/SI Pump 'B' indicates OFF with zero running amps, and annuciator XCP 614. 4-2, CHG PP BIC TRIP is receive The NRO should review the ARP for XCP 614, 4-2 and recognize that the only step which will result in a success path would be the direction that if "8'. Charging Pump is inoperable, then align " C" Charging Pump to '.B" train. CUES: SAT If requested, IB A0 andlor electical maintenance personnel will investigate and UNSAT determine that a breaker malfunction exists and they estimate 6 hours to complete changeout and testing. COMMENTS:
CR SEQ STEP: 14 STEP STANDARD:
No No Align Charging Pump on Train C to B train electicall Place "*3" Charging Pump in PTL, direct I5 A0 to rack down "*3" Charging Pump, ensure " C" Charging Pump (" B" train) is in PTL, direct IB AB to rack up " C" Charging Pump ("E? train). CUES: SAT If requested, SOP 102, Att VB, Charging Pump C to Train *3 lineup had previously UNSAT been performed and verified, with the exception of racking down "B" Charging Pump breaker and racking in "C" Charging Pump ("B" train). Booth operator should request NRO to verify both Charging pump switches are in PTL prior to racking breakers up or down: IAW SOP 313. COMMENTS:
Wednesday, March PO, 2004 i '
CR SEQ STEP: 15 STEP STANDARD:
No No Start the Charging Pump on Train B (PUMP B or C). running amps. C#G/SI Pump " C indicates ON and normal CUES: This completes this JPM. COMMENTS:
Examiner ends JPM at this point. Wednesday, March 10, 2004 .__/ SAT UNSAT Page 10 of 11 JPM SETUP SHEET
.- JPM NU: JPSF-002 DESCRZPTZON:
TRANSFER TO HOT LEG RECIRCULATION KSET: 10 ZNSTRUCTZUNS:
1. Activate MAL-RCS005A RCS Loop 'A DBA LOCA 2. RUN 3. Perform actions of EOP-1 .O and 2.0 4. FREEZE 5. Ensure RHR Sump Level >415', then activate LOA-AUXll5 SEVERITY=0.17 (17% in RWST) 6. RUN 7. Transfer Cold Leg Injection to Cold Leg Recirculation IAW EOP-2.2. 8. To shift CCW to fast speed during EQP-2.2: LOA-CCW050 SELECT-FAST SPEED 'A CCW Pump Speed Switch to fast or LOA-CCW052 SELECT=FAST SPEED 'c' CCW Pump Speed Switch to fast 9. FWEEZE 10. When student is ready: RUN COMMENTS:
Charging Pumps must be stopped before opening Hot Leg High Head Valves (8884/8886)
to prevent pump runout. Wednesday, March 10, bOQ4 Page 11 of11 V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE JPM NO: JPS-023 OPERATE THE CVCS SYSTEM TO INCREASE RCSPRESSURE APPROVAL:
TRH APPROVAL DATE: 06/19/2003 KEVMO: 3 Wednesday, March 24,2004 ./ Page 1 of 8 TASK: 004-032-01 41 OPERATE CHEMIC* AN5 VOLUME CONTROL SYSTEM TO INCREASE REACTOR COOLANT SYSTEM PRESSURE .-. TASK STANDARD:
RCS pressure has been increased to 350-425 psig without lifting RHR suction relief and is stable PREFERRED EVALUATION METHOD PREFERRED EVALUATION WCATION SIMULATOR PERFORM REFERENCES':
SOP-I 02 CHEMICAL AND VOLUME CONTROL SYSTEM EVALUATION TIME 15 TIME CWTICAL No IOCFRSS: 45(a)6 __ .~ CANDIDATE:
TME WART TME FlNISH PERFORMANCE RATING: SAT: UNSAT ~ PERFORMANCE TIME - Q[JESIlON GRADE: ,/' ~ ~ .~ -.- EXAMINER:
~ ~~~~~~~ SlGNATilRE DATE COMMENTS:
Wednesday, March 24,2004 XSd Page 2 of 8
..-.. INSTRUCTIONS TO OPERATOR READ TO OPERATOR:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WlU DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOB THIS JOB PERFORMANCE MEASURE WILL BE SATISFIE SAFETY CONSIDERATIONS:
INITIAL CONDITION:
The plant has been in long term cold shutdown due to refuelin The RCS is in solid plant conditions with RCS pressure at 50 psg and the RHR system in operatio INITIATING CUES: The CRS directs that RCS pressure be increased to 350-425 psig per SOP-102, Section III.C., by performing step 2.1 and 2.2 so that a reactor coolant pump may be started for plant heatup. HhXD JPM BRIEFING SHEEI' TO OPER4TOR AT THl&sect; TIME! Wrdnesdqv, March 24,2004 Page 3 of 8
-- JPM BRIEFING SHEET OPERA TOR INSTRUCTIONS:
SAFETY CONSIDERATIONS:
INITIAL CONDITION:
The plant has been in long term cold shutdown due to refuelin The WCS is in solid plant conditions with RCS pressure at e 50 psis and the RHR system in operatio INITIATING CUES: The CRS directs that RCS pressure be increased to 350-425 psig per SOP-102, Section III.C., by performing step 2.1 and 2.2 so that a reactor coolant pump may be started for plant heatup. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. Wednesday, March 24,2005 Page 4 of 8 STEPS .- CR SEQ STEP: 1 STEP STANDARD:
No Ne Ensure RCP seal leakoff valves are open. PVT-8141 A (B,C) A (5) (C) SEAL LKOFF indicate OPEN. CUES: COMMENTS:
CR SEQ STEP: 2 No No Ensure normal letdown availabl CUES: COMMENTS:
SAT C'NSAT __ STEP STANDARD:
LCV-459 and 460, PVT-8152, LTDN LINE ISOL, and 8149A, B, C, LTDN ORIFICE A (B) (C) ISOL indicate OPEN. .- SAT UNSAT CR SEQ STEP: 3 STEP STANDARD: Yes Yes Adjust PCV-145 controller to increase RCS Decreases PCV-145 controller output to pressur close PCV-145. CC'E.7: SAT UNSAT __ Wednesday, March 24,2004 Page 5 of 8 CR SEQ STEP: 4 STEP STANDARD:
No Yes Monitor RCS pressure meters and/or Monitors N.R. and/or W.R. 86s recorders to observe trend in RCS pressur pressure meters and recorders to determine increase in RCS pressure above 50 psig. CUES: .___ SAT UNSA T COMMENTS:
CR SEQ STEP: 5 No No Establish RCP Seal Water Return. CUES: STEP STANDARD:
MVT-8112 S*AL WTR TRN ISOL, and indicate OPEN. MVT-8100, SEAL WTR RPN ISOL, ._ SA T UNSA T - CR SEQ STEP: 6 No No Maintain Seal Injection Flow. Wednesday, March 24, ZOUl STEP STANDARD:
Adjusts HCV-186, INJ FLOW, as required to keep seal injection flow between 6 and 13 gpm. Page 6 of 8 CR SEQ STEP: 7 STEP STANDARD: Yes Yes Adjust PCV-145 controller to maintain RCS Adjusts PCV-145 controller output to pressure at 350-425 psig. maintain RCS pressure at 350-425 psig. CUES: COMMENTS:
SA 1' UNSAT __ CR SEQ STEP: 8 STEP STAIVDARD:
No No Monitor RCS pressure meters and/or Monitors N.R. and/or W.K. RCS recorders to observe trend in RCS pressur pressure meters and recorders to determine RCS pressure stable at 350- 425 psig. CUES COMMENTS: - Examiner ends JPM at this point. Wednesday, March 24,2004 SAT UNSA T . Faze 7 of 8 JPM SETUP SHEET JPM NO: JPS-023 DESCRIPTION:
OPERATE THE CVCS SYSTEM TO INCREASE RCS PRESSURE ICSfiT: 1 INSTRUCTIONS:
1. RUN 2. Close PCV-145. Establish 3. When RCS pressure 420 psig, reduce charging flow to ,>75 gpm. Open PCV-145 to 40% demand. 4. FREEZE 5. When student is ready gpm flow on FI-122 by manually opening FCV-122. RUN COM.WENTS:
Wednesday, AfaFCh 24,2804 Page 8 of 8 V.C. SUMMER NUCLEAR STATION JQB PERPQRMANCE MEASURE JPM J PSF-025 START AND LOAD "B" EMERGENCY DIESEL GENERATOR APPROVAL:
APPROVAL DATE: REVR'O: 4 CANDIDATE Wednesday, March IO, W04 _- Page I of13 TASK: 064-003-01 -01 -. LOAD THE DIESEL GENERATOR NO:: " B" Diesel Generator is started and loaded to 4150-4250 KW, and then tripped and the engine shutdown when oscillations occur. The use of applicable Human Performance Tools (3-way communications, self checking, peer checking, phonetic alphabet, etc) and industrial safety practices meets expectation PREFERRED EK4ILlATI LOCATION PREFERRED EVALLiATlON METHOD SIMULATOR PERFORM REFERENCES:
SSCB-IV-7 DIESEL GENERATOR POWER FACTOR, CURRENT VS. LOAD SOP-306 EMERGENCY DIESEL GENERATOR TOOLS: EVALUATZOhT TIME 15 TIME CRITICAL No IOCFRSS: 45(aj8 CANDIDAlE:
TIME START TME FEWB: PERFORMANCE RATZhGs SAT I!XSAl' QLIESTION GRADB: PERFORMANCE - EXAMIh'ER:
COMMENTS:
Wednesda~, March 10,2004 .-- SIGNATURE DATE Page 2 of 13 TASK STANDARD:
-* INSTRUCTIONS TO OPERATOR READ TO OPERATOR:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIE SAFETY CONSIDERA TIONS: INITIAL CONDITION:
The plant is operating at 100% power with normal AC power available to all buses. " B" D/G is to be started and loaded for monitoring cylinder temperature A11 local steps have been complete ZNITIATING CUES: CRS directs starting and loading of "W D/G to 41 50-4250 KW per SOP-306, Section IV.B, steps 2.3 thru 2.10. - HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIMEf Wednesday, March 10,2001 Page 3 of 13 JPM BRIEFING SHEET OPERA TOR I,V.STRLIC!TZONS:
SAFETY COXSZDEZU TZONS: INZliAL CONDITION:
The plant is operating at 100% power with normal AC power available to all buses. "W DIG is to be started and loaded for monitoring cylinder temperature All local steps have been complete ZNZTZATZA'G CUtiS: CRS directs starting and loading of "B" DIG to 41 50-42250 Kw per SOP-306, Section IVB, steps 2.3 thru 2.10. Page 4 of 13 STEPS CR SEQ STEP: 1 STEP STAXDARB:
No No Verify Annuoicia!or XCP-637 1-2, DS B Verities Annunciator XCP.637 1-2, DG B AGTOS'I'AITT NOT READV, is clear. AUTOSTART NOT HEADY, is clear. CUES: CQMMENTS:
SAT UA'SA T CR SEQ STEP: 2 STEP STANDARD:
No No The READY FOR AUTO START light is Calls the 18 operator and verifies the " READY FOR AUTO START" light is lit at me "B" D/G Local Control Panel. illuminated at the D/G Local Control Panel CUES: SAT When requested, as the IB operator, inform the operator that the " READY FOR UNSAT AUTO START" light is lit at the "B" D/G Local Control Panel. COMMENTS:
,- CR SEQ STEP: 3 STEP STANDARD:
No Yes Verify D/G starts and accelerates to 58.9 - 61.1 Hertz and 6700-7600 volts. DG B VOLTS indicates 6700-7600 volts and FREQUENCY indicates 58.9 - 61.1 Hertz. CUES: COhfMEATS:
Wednesday, March 10, 2004 SAT UNS.4 T Pa@ 5 of 13 CR SEQ STEP: 4 STEP SZANDARD:
No Yes Place " E" Diesel Generator TEST switch to Momentarily rotates "B" Diesel Generator TEST switch to the START positio START. CUES: COMMENTS:
SAT UNSA T CR SEQ STEP: 5 SZEP STANDARD:
No Yes Place the DG B SYNC SEL switch in BSL. DG B SYNC SEL switch indicates DSL. CUES: SAT CRS directs BOP to load "6" DG per Section Ill Precaution 24. When examinee UNSAT mentions that he is waiting 3-5 minutes for pressures and temperatures to stabilize inform examinee that he may continue without waiting the 3-5 minutes referenced by the procedur COMMENTS:
CR SEQ STEP: 6 __ No No Ensure VOLT REG switch is in AUTO. CUES: COMMENTS:
Wednesday, Murrh 10,2004 _, STEP STANDARD:
VOLT REG switch for the '5 DIG indicates AUTO. SAT UXSA T Page 6 of 13 CR SEQ STEP: 7 STEP STANDARD:
No No Monitor voltage on 1 DB SYNC VOLTS and Locates 1 DB SYNC VOLTS and SYNC .- SYNC VOLTS. VOLTS meters and monitors voltage. CUES: COMMENTS:
SAT UXSAT CR SEQ STEP: 8 STEP STANDARD:
Ye No Adjust SYNC VOLTS to slightly higher than VOLT REG RAISE LOWER switch used to adjust DG 'B' SYNC VOLTS slightly higher 1 DB SYNC VOLTS using VOLT REG RAISE LOWER. than 1DB SYNC VOLTS. CtiES: SAT UNSAT COMMENTS:
CR SEQ STEP: 9 STEP STAhlDARD:
Ye No Adjust Diesel Generator
"8" frequency to DG 'B SPEED switch used to adjust D/G speed so that SYNCHROSCOPE rotates slowly in the FAST directio .- ~ cause synchroscope to rotate slowly in the FAST direction using SPEED switch. CUES: COMMENTS:
Wednesday, March IO, 2004 - SAT UNSA T Page 7 af 13 CR SEQ STEP: 10 STEP STARWARD:
Ye Yes When synchroscope is in proper position, close BUS 1 DE BG FEED breaker. When synchroscope is between 11 o'clock and 12 o'clock, closes BUS 1 DB DG FEED breaker. -- CUES: COMMENTS:
CR SEQ STEP: 11 SZEP STANDARD:
No Yes Verify breaker 1 DB DG FEED breaker closed. Bus 1 DE3 DG FEED breaker indicates red light ON, green light OFF. CUES: SAT UNSAT COMMENTS:
CR SEQ STEP: 12 STEP STANDARD:
DE 'B' KILOWATTS indicates 850-1250 KW for 3-5 minutes. DG B VOLTS indicates 6840-7344 volts and DG AMPS indicates
+IO0 amps. No Yes Adjust load to 850-1250 KW using SPEED switch and maintain for 3-5 minutes -- CUES: SAT When examinee mentions that he is waiting 3-5 minutes for pressures and UNSAT temperatures to stabilize inform examinee that he may continue without waiting the 3-5 minutes referenced by the procedur COMMENTS:
Wednesday, March 10, 2004 ~ Page 8 of 13 CR SEQ STEP: 13 STEP STANDARD:
DIG 'B KILOWATTS indicates 2150-2550 KW for 3-5 minutes. DG 6 VOLTS indicates 6840-7344 volts and BG AMPS indicates i 100 amps. D/G 'B indicates 2150 - 2550 KW for 3-5 minutes. No Yes Adjust load to 2150-2550 KW using SPEED switch and maintain for 4-5 minutes. .. CL'ES: SAT temperatures to stabilize, inform examinee that he may continue without waiting the 3-5 minutes referenced in the procedur COMMEVTS:
When examinee mentions that he is waiting 3-5 minutes for pressures and C'NSA T CK SEQ STEP: 14 Ye Yes Adjust load to between 4150 and 4250 KW using SPED switch. CUES: COMMEM'S:
CR SEQ STEP: 15 No Yes Place DIG '8' SYNC SEL switch in OFF. CUES: COMMENTS:
Wednesday, March 10,2004 - -4 STEP STANDARD:
B1G '3' KILOWATTS indicates 4150-4250 Kw 6800-7400 VOLTS. SAT UA'SAT STEP STANDARD:
BG I3 SYNC SEL switch indicates OFF. SAT UR'SA T Page 9 of 13 CR SEQ STEP: 16 STEP STANDARD:
Ye No Annunciator XCP 637, 6-3 DG B ENG TEMP Operator reviews ARP for XCP 637, 6-3 investigate. -id TRBL is receive and dispatches the BG operator to CUES: SAT DG operator reports receipt of XCP 5202,l-2 HIGH LUBE OIL TEMPERATURE and reports that LUBE OIL TEMP TO ENGINE on the "B" DG gaugeboard reads 170 degrees F and increasin If the operator requests permission to begin decreasing load on "B" DG, prompt him to begin a normal load reduction using SOP 305, step 2.6.b using narmal time limits. CO.Wn.IEI\T~SS:
UNSAT CR SEQ STEP: 17 STEP STANDARD:
Ye No Annuciator XCP 637,2-5 DG B ENG TRBL Refers to ARP for XCP 637,2-5 and notes that the diesel should have shutdow ARP further directs that the operator ensure "8" DG is shutdow SHUTBN is receive CUES: SAT DG Operator reports receipt of XCP 5202,6-3 ENGINE TROUBLE SHUTDOWN, but the diesel engine continues to run at full load and LUBE OIL TEMP TO ENGINE on the "W DG gaugeboard now reads 176 degrees F and still increasin If the operator requests permission to trip the "*3" DG under full load, CRS directs that load be rapidly reduced using SOP 306, step 2.6.b as a guide only. If the operator trips "6" DG under full load due to a trip condition being exceeded without receiving a trip, proceed to step 21 of this JPM and continu UNSA T v COMMENTS:
Wednesday, March 10,2004 Page 10 of 13 CR SEQ STEP: 18 STEP STANDARD:
No No Unload Diesel Generator B by holding the SPEED Switch in LOWER until load is 50 KW. BG B KILOWATTS indicates less than 100 KW. .__./ CUES: SAT If the operator requests guidance from the CRS as to whether or not to trip "B" BG UNSAT or unload, the CRS will direct that the "B" DG be unloaded rapidly using SOP 306, step 2.6.b as a guide only. if the operator decides to open the DG output breaker under full load due to a trip condition being reached and exceeding without receiving a trip, proceed to step 21 of this JPM and continu COMMENTS:
CR SEQ STEP: 19 STEP STANDARD:
No No Using the VOLT REG RAISE-LOWER Switch, reduce KILOVARS to minimum. DG B KILOVARS indicates approximately zero KVARS. CUES: C(1MAfENTS: . -. CR SEQ S T E P: 20 No No Open BUS 1 DB DG FEED Breaker. CUES: Wednesday, .Murch 10, 2004 --.a SAT UhSA 1 STEP STANDARD:
BUS IDB DG FEED breaker green light is LIT. SAT UhSA T Page 11 of 13 CR SEQ STEP: 21 STEP STANDARD:
No No Momentarily place the EXCITER Switch in DG E AMPS and VOLTS decrease to zero, ......- SHUTDN. and FREQUENCY decreases to minimum. CUES: COMMENTS:
SAT UNSAT CR SEQ STEP: 22 STEP STANDARD:
No No Momentarily place the TEST Switch in STOP. TEST Switch is placed in the STOP positio CUES: DG "8" operator reports that the "B" DG engine is shutdow COMMENTS:
Examiner ends JPM at this point. Wednesday, March 10,2004 i-. SAT UNSAT Puge I2 of 13 JPM SETUP SHEET . JYiM,VO: JPSF-025 DESCRZPTIOA':
START AND LOAD "5 EMERGENCY DIESEL GENERATOR ZC SET: 10 (1 00% ZNSTRUCTZUNS:
1. When student is ready; RUN JPM Initial Condition of " Cylinder Monitoring" was intentionally used to prevent requiring STP-125.002 attachments from having to be availabl Also to prevent having to have a stopwatch availabl This is too much effort to test the same skills as in SOP-306. COMMENTS:
Wednesday, March IO, ZOO4 Page 13 of 13 V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE JPM NO: JPS-033 MITIGATE THE CONSEQUENCE8 OF A TOTAL LOSS OF SERVICE WATER APPROVAI,:
DclW APPROVAL DATE: 06/20/2002 REVNO: 2 -, .- CANDIDATE - - - EXAMINER Wednesduy, March 24.2004 -.._ Page I of10 TASK: L.' 000-062-05-01 RESPOND TO LOSS OF NUCLEAR SERVICE WATER TASK STANDARD:
Plant is stabilized pending evaluatio '6 and 'C RCPs have been tripped. B CCW Loop has been placed in service without loss of cooling to the running RCP. The use of applicable Human Performance Twls (3-way communications, self checking, peer checking, phonetic alphabet, etc) and industrial safety practices meets expectation PREFERRED EVALkrATIOiV LOCATION PREFERRED EVALUATION METHOD SIMULATOR PERFORM REFERENCES:
SOP-1 18 COMPONENT COOLING SYSTEM AOP-117.1 TOTAL LOSS OF SERVICE WATER TOOLS: EVALUATION TIME 10 TIME CRITICAL No CANDIDATE:
__ ____ ~ IOCFR55: 45(a)8 Wediiesday, March 24,2004 .._ - Page 2 of 10 INSTRUCTIONS TO OPERATOR jp READ TO 0PER.I TOR: INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STAflTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SlhNLATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SAFETY CONSIDERA TIOM: ZNZTZAI, CONDZTZON:
Mode 3 ready to startup. Both running SW pumps have tripped. The running WAC chiller units have tripped on high temperatur Attempts to restore at least one train of SW have failed. ZNITZATZNG CUES: The CRS has directed the NROATC to respond to a total loss of service water, per BOP-I 17.4 and complete steps 11-14. HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME! Wednmdaj, Murch 242004 - ..  
.IPM BRIEFING SHEET OPERATOR INSTRlJCTIONS:
SAFETY CONSIDERA T1O.W: INITMI, CONDITION:
Mode 3 ready to startup. Both running SW pumps have tripped. The running HVAC chiller units have tripped on high temperatur Attempts to restore at least one train of SW have failed. INITIATING CUES: The CRS has directed the NROATC to respond to a total loss of service water, per AOP-11 and complete steps 11-14 - HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. Wednesday, March 24,2004 Page 4 of 10 STEPS CR SEQ STEP: 1 STEP STANDARD:
Yes Yes Minimize CCW heatup by stopping
'0 and'C .. Secures '0 and 'C RCPs by taking control switch to trip position and verifying green fight li RCPs. CUES: SAT When asked examiner informs examinee that the CRS concurs with securing L,NsAT COMMENTS:
two RCPs and directs securing
'B' and 'C RCPs per SOP-IO? section 4A. ___ CR SEQ STEP: 2 No Yes Checks RCP A temrmatures CC'ES: I COMMENTS:
STEP STANDARD:
Displays ZZ RCP BRG on IPCS monitor to verify: RCP motor bearing temperature z 1950F, Lower seal water bearing temperature
< 225oF. CR SEQ STEP: 3 STEP STANDARD:
No Yes Minimize CCW heatup by alternating Perform an active CCW loop switchover operation of Component Cooling Water loops. per SOP-1 18, section 38 step 2.3. CUES: SAT Examiner states that the NROATC has been directed to perform an activ@ CCW LJ,%rs~~ IQQ~ switchover Per SOP-1 18, by CRS. COMMENTS:
_. Wednesday, March 24,2004 Page 5 of 10 CR SEQ STEP: 4 STEP STANDARD: .i_.._ Yes Yes Place XPP-OQfJlC, PUMP C, TRAIN B, in The B Train Handswitch for C PULL TO LOCK. Component Cooling Water Pump is in Pull To Lock. CUES: SAT COMMENTS:
CR SEQ STEP: 5 STEP STAR'DARD:
No Yes Align XPP-0001C PUMP C, to Train B per Direct the AB Operator to complete Attachment VIB with the exception of racking up the breaker for C CCW Pump on B Train. Attachment VIB with the exception of racking in CCW pump C breaker. CUES: SAT in the procedur Racking up the breaker for C CCW Pump at this time does not Racking up the breaker is a separate direction from the NROATC in a later step constitute 2 failure of this JPM. avsAT ~~ ~ ~ ~.___ COMMENTS:
-- CR SEQ STEP: 6 STEP STANDARD: Yes Yes Verify CCW to the RHR HX B is open. The red light for MVB-95038, CC TO RHR HX B, is lit and the green light is off. CUES: Wednesday, March 24,2004 SAT UNSA 2 Page 6 of 10 CR SEQ STEP: 7 Yes Yes Start B CCW Pump. STEP STAA7DARD:
Indicated by the red light for B CCW Pump lit and the green light off CR SEQ STEP: 8 STEP STANDARD: Yes Yes Start MVB-9503B in the closed directio Start MVB-9503B CC TO RHR HX B, strocking in the closed directlon as indicated by both the red and green lights being lit. CUES: COMMENTS: . CR SEQ STEP: 9 Yes Yes When flow is indicated on Fl-7044 between 5000 and 4000 gpm Open MVB- 96878/95258 and MVB-9524B/9526B; and 9587N9525A; and Open MVB-9503 Close MVE9524N9526A; MVB- STEP STAXDARD:
Indicated by the red light on the handswitchs for MVB-9687B/9525B, MVB-9524BB526B being lit and the green light on the handswitches for MVB- 9524N9526A and MVB-9687N9625A being lit, and the red light on the handswitchs for MVB9503A being lit. ~- CUES: SAT The valves listed in this step must be operated in rapid succession to prevent CTN,~AT loss of flow or excessive flow perturbations in the non-essential loop and should ___ be operated by Train sequence as indicate Auto closure of the CCW valves to the RB or Thermal Barrier constitutes a failure of this JPM. COLWMEIVTS:
Wednesday, March 24,2004 Page7of10 CR Sh'Q STEP: 10 STEP STAXIIARD:
No No Rack in the C CCW Pump breaker on Train B. Direct the A0 to Rack in the breaker for B Train power to C CCW Pump per Attachment VIB. Indicated by the green light on the B Train switch for C CCW Pump being lit. CUES: COMMENTS:
SAT UNSAT - CR SEQ STEP: 11 STEP STANDARD: No No Place XPP-0001C Switch in After-Stop. Place the handswitch for 6 CCW Pump in the Normal After-Stop positio CUES: ____ SAT CNSA T ~ COMMENTS:
._ - CR SEQ STEP: 12 STEP STANDARD: No No Direct the AB Operator to verify flow for The AB Operator reports that flow is greater than 1 gpm. RML2B is greater than 1 gpm. CUES: COMMENTS:
Wednesdaj, March 24,2004 --. s.4 T UNSA 1' Page 8 of IO CR SEQ SlEP: 43 STEP STANDAKD: - Yes Yes Ensure the following valves have not auto Ensure that MVG-9625, MVG-9626, closed due to high flow. MVG09583, and MVT-9593A (B) (C) are open as indicated by the red lights on the switches being lit and no alarms indicating closure are receive CUES: SAT Closure of these valves constit~tes a failure of this JPM. This concludes this ulvsA~ JPM. COMMEi\'lS: - - Examiner ends JPM at this point. Wednesday, March W? 2004 Page 9 of 1u JPM SETUP SHEET - JPM NO: JPS-033 DESCRIPTION:
MITIGATE THE CONSEQUENCES OF A TOTAL LOSS OF S*RVICE WATER IC SET: INSTRUCTIONS:
COMMENTS:
Wednesday, .Wararch 24,2004 Page 10 of 10 bl V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE JPM NO: JPS-052 PERFORM BORON GONCENTflATlON DILUTION OF THE RCS APPROVAL:
TRH APPROVAL DATE: 06/16/2003 REVNO: 3 EXAMINER:
THfS JPM bS APPROVED Wednesday, March 24,2004 >-
.-----=-- TASK: -. 004-007-01 -01 PERFORM BORON CONCENTRATiONlDlbUTlON OF THE REACTOR COOLANT SYSTEM ThSK STANDARD:
Bank 'D' Control Rods have been alternate diluted to 198 steps using the Alternate Dilution mode of the Reactor Makeup Water System. Tavg-Tref maintained within 15&deg;F. PREFERRED EVALUATION LOCATION PREFERRED EVALUA TIOh' METHOD SIMULATOR PERFORM REFEREh'CES:
SOP-lo6 REACTOR MAKEUP WATER SYSTEM TOOLS: EVALlJhTION TIME 10 TIME CRITICAL No lQCFR55: 45(A)1 TIME START TIME mISH -- CANDIDATE:
__ - Wednesday, March 24,2004 .-., Page 2 of I1 INSTRUCTIONS TO OPERATOR REhD TO OPERATOR:
INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASUBE WILL BE SATISFIE SAFETY COXSIDERA TION$: INITIAL COA9DITION:
The reactor is operating at 75% power, all controls in automatj Turbine load has been held at 75% for 2 weeks due to NIS problems Reactor engineering has requested that Bank "D" control rods be positioned to 198 steps by Alternate Dilution (10,000 MWD/MTU).


INITIATING CUES: CRS directs NROATC to alternate dilute Bank D Control Rod to 198 steps. HAND JPM IIRPEFING SHEET TO OPERATQR AT THIS TME! Wednesday, March 24,2004 ~ Page 3 of I1
AC lnst Bus 16        ,,
.IPM BRIEFING SHEET OPERA TOR INSTRUCTIONS:
L(-& 4 i
SAFETY CONSIUERA TIONS: INII'IAL CONDITION:
          ~(?*&< ,
The reactor is operating at 75% power, all controis in automati Turbine load has been held at 75% for 2 weeks due to NIS problems Reactor engineering has requested that Bank
P I !
"8" control roods be positioned to 198 steps by Alternate Dilution (10,000 MWD/MTU).
    .~ -
o o o
  ~ O ~ ~ A K I . O $ 1 Knowledge of the operational applications of the following Battery charger equipment and instrumentation  28 31 Power 16    concepts as they apply to the (ABNORMAL PLANT
    ~ EVOLUTION):(CFR: 41.8 toAl.10)
0 1 0 %?AA2 C1 L'kbI 1y 111 oetermine and nterorel tho follow ng as lnoy  Location of a leak in the SWS  2.9 j apply to ABNORMAI. PIAN1 EVCl.Lh'Olu, (CFH 41 10 '


INITIATING CUES: CRS directs NROATC to alternate dilute Bank 5 Control Rod to 198 steps. ASSIGNED TAS Wedne,yday, March 24,2004 Page 4 of I1 STEPS CR SEI,) STEP: 1 SiEP STANDARL):
75 Point Teb<..-
No Yes Operator calculates expected amount of Calculation result is 415 - 453 gallons dilutio CUES: COMMENTS:
Tier W r o u p 1 Name I Safety Function: Kf K2 K3 A I A2 0 WANumhgr QueStiQnType    WA Topic boss of   Ability to operate and I or monitor the following as they Restoration of systems served by instrument air when Instrument Air /      41.7 / pressure is regained
~- SAT UNSA T CR SEI,) STEP: 2 STEP STANDARD:
No Yes Place RX COOLING SYS MU switch to RX COOL SYS MU SELECT switch in STOP. the STOP positio CUES: SAT - This is a Reference Use Procedur The operator should verify actions with UN~~~ procedur .~ COMMENTS: - CM SEI,) STEP: 3 STEP STANDARD:
Yes Yes Place RX COOLING SYS MU mode select RX COOL SYS MU MODE SELECT switch to ALT DlL positio switch in the ALT DIL positio CUES: COMMERTTS:
Wednesday, March 24,2004 S.4 T ___ UNSA T Page 5 of I1 CR SEQ STEP: 4 STEP STANDARD:
No Yes Adjust FCV-168, TOTAL MU FLOW Adjust FCV-I 68 controller to desired controller to desired flowrat flowrate CUES: Optional: Controller normally set for 120 gpm flow rate. COMMENTS:
SAT -~ UNSA T CR SEQ STEP: 5 STEP STANDARD:
Yes Yes Set FIS-I68 TOTAL MU FLOW batch Set FIS-168 batch integration to 200 integrator to desired volume. gallons. CUES: Cue the operator to set to 200 gallons. COMMENTS:
CR SEQ STEP: 6 Yes Yes Start dilutio Wednesday, March 24,2004 ... -_ SAT UNSAT STEP STANDARD:
RX COOL SYS MU switch indicates red light on, green light off. Page6oflI CR SEQ STEP: 7 STEP STANDARD:
No Yes Verify RX MU WTR PP start. RX MU WTR PP running by MC5 indicatio CUES: COMMENTS:
CR SEQ STEP: 8 STEP STANDARD:
No Yes Verify FCV-I68A, MU TO VCT opens. FCV-168A indicates red light on, green light off. CUES: COMMENTS: - SAT UNSAT CR SLCQ STEP: 9 STEP STANDARD: - No Yes Verify FCV-4685, MU WTR TO BLENDER FCV-1685 indicates red light on, green light off. FCV-1138 indicates red light opens and FCV-1133, MU TO CHG PP, opens. an, green light off. CUES: COMMEA'TS:
Wednesdqv, March 24,2004 SAT [JiVSA I' Page 7uf II CR SEQ STEP: 10 SIEP STANDARD:
-_. No Yes Verify desired fiowrate on FR-113, TOTAL 120 gpm indicated on FR-113 recorde MU GPM (F-168). CIJES: COMMENTS:
CR SEQ STEP: 11 Yes Yes Energize PZR BU Heaters. CIJES: Step 10 is optiona SAT UNSAT __ STEP STANDARD:
PZR HTRS BU GP 1 (2) indicate red light on, green light off. SAT UNSAT ___ COMMENTS:
CR SEQ STEP: 12 STEP STANDARD:
%- No Yes Verify letdown diverts to Holdup Tanks. LCV-l15A, LTDN DIVERT TO HU-TK, indicates HU-TK positin when VCT level - 70%. CUES: COMMENTS:
Wednesda.y, March 24, 2004 Page 8 of I1 CR SEQ STEP:
13 Yes Yes Verifies dilution (alternate dilution)
stops when preset volume is reached on FIS-168, TOTAL MU FLOW batch integrato STEP STANDARD:
Verfies dilution has stopped by observing FIS-268, total MU flow batch integrator counter stopped at set gallons. CUES: CR SEQ STEP: 14 No Yes Verify rods controlling Tavg-Tref. CUES: - SA 1' WNSA T STEP STAh'DARD:
Verifies rods controlling Tavg-Tref within 1.5"F in Auto or Manual. SAT ~ Examinee should be verifying Tavg-Tref controlled by rods during dilutio UNSAT COMMEA'TS:
CR SEQ STEP: 15 STEP STAXDARL):
.- No Yes Place RX COOL SYS MU switch to STOP. RX COOL SYS MU indicates red light off. green light on. CWES: SAT Cue the operator that 425 gallons have been added and Bank B control rods are [INSAT at 198 steps. COMMENTS:
__ Wednesday, March 24,2004 ~ Page 9 of11 CR SEQ STtiP: 16 STEP STANDARD:
No Yes Place RX COOL SYS MU MODE SELECT RX COOL SYS MU MODE SELECT switch to AUTO. switch in the AUTO positio CUES: COMMEA'TS: - SAT UNSA T ~ CU SEQ STEP: 17 STEP STAlvDARD:
No Yes Place RX COOL SYS MU switch to START. RX COOL SYS MU indicates red light on, green light off. CUES: COMMENTS:
Examiner ends JPM at this point. - Wednesday, h4arch 24,2004 SAT UNSAT - - Page 10 of I1 JPM SETUP SHEET JPiM NO: JPS-052 DE,TCRIPTION:
PERFORM BORON CONCENTRATION DILUTION OF THE RCS ICSET: 11 INSTRUC~~OLVS'S:
1. When student is ready: RUN COMMENTS:
Wednesda.y, March 24,2004 Page 11 of 11 V.C SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE JPM NO: JPSF-007 STEAM GENERATOR TUBE RUPTURE (DEPRESSURIZE RCS TO e RUPTURED SI6 PRESSURE)
APPROVAL:
TRH APPROVAL DATE: 05/29/2003 REVNO: 7 , Wednesday, March 24,2004 ---_-' Page i of 7 TASK: .-- 000-038-05-01 TASK STAR'DARD:
RESPOND TO STEAM GENERATOR TUBE RUPTURE RCS pressure is reduced to less than ruptured WG pressure with PZR level > 18% or PZR bVd> 68% or RCS subcooling e 30&deg;F. The use of applicable Human Performance Tools (3-way communications, self checking, peer checking, phonetic alphabet, etc) and industrial safety practices meets expectation PREFERRED EVALUATION LOCATiON PREFERRED EVALUATION h4ETHOD SIMULATOR REFERENCES:
EOP-4.0 TOOLS: E17ALUATION TIME 10 CANDIDATE:
PERFORMANCE RATING: SAT PERFORM STEAM GENERATOR TUBE RUPTURE TlME CRITICAL No IOCFRSS: 45(a)6 LINSAT Wedi8esd March 24, 2004 -. . Page 2 of 7 INSTRUCTIONS TO OPERATOR READ TO OPERATOR:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTIN I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFQRMANCE MEASURE WILL BE SATISFIE SAFETY CONSIDERATIONS:
INITIAL CONDITION:
A Steam Generator Tube Rupture is in progres S/G "c" has been isolated per EOP-4.0. An operator initiated cooldown has been performed according to EQQ-4.0, through step 24. INITIATING CUES: Control Room Supervisor directs operator to depressurize the RCS using PZR Spray, per EQP-4.0, Step 22. HAND JP.W BRfEFING SHEET TO OPERATOR .AT THIS TIME! Wednesday, March 24,2004 Page 3 of 7
.IPM BRIEFING SHEET OPERA TOR INSTRUCTZUXS:
SAFETY CUNSZDERA TZUNS: ZNITZAZ. CULVDZTZUN:
A Steam Generator Tube Rupture is in progres S/G "C' has been isolated per EOP-4.0. An operator initiated cooldown has been performed according to EOP-4.0, through step 21. INZTZATZNG CUES: Control Room Supervisor directs operator to depressurize the RCS using PZR Spray, per EOP-4.0, Step 22. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. Wednesday, Marcti 24,2004 Page 4 of 7 STEPS CR SEQ STEP: 1 STEP STANDARD: Yes Yes Depressurize the RC&sect; using normal spray Places PZR Spray PVC-444C & 444D controllers in MANUAL and increases output to 100% demand. valves PCV-444C and 444D. CUES: SAT UNSAT Give examinee 1-2 minutes to familiarize himself with his control hoard indications and his place in the procedur COMMENTS:
___ __ CR SEQ STEP: 2 STEP STANDARD:
No Yes Use ma.ximum available spray until any Recognizes from MCB indication that RCS pressure is less than 'c' SIG pressure with PZR level 218% or PZR level >68%. termination criteria is met; RCS pressure c'c' (ruptured)
&sect;/G pressure and PZR level > 18%; or PZR level >68; or RCS subcooling
<30"F. CUES: COMMENTS:
CR SEQ STEP: 3 Yes Yes Stop RCS depressurizatio SAT UNSAT __ STEP STANDARD:
Decreases PCV-444C & 444D controller output demand to zero. CUES: SAT If RCS pressure equals ruptured S/G pressure first and student continues to UNSAT depressurize to 68% PZR level, this would constitute failure. COMMENTS:
~ Wedileday, March 24,2004 Page 5 of 7 CR SEQ STEP: 4 smr STAXLMRD:
.. Yes Yes Identify failure of PCV-444B to close and 'A RCP tripped to stop depressurizatio secures 'A RCP. CUES: SAT COM.MENTS:
Examiner ends JPM at this point. Wednesday, March 24,2004 Page 6 of 7 JPM SETUP SWEET , \-- - JPh4NO: JPSF-007 DESCRIPTION:
STEAM GENERATOR TUBE RUPTURE (DEPRESSURIZE RCS TO e RUPTURED SIG PRESSURE)
ICSET: 10 INSTRUCTlOiVS:
1. Activate MAL-WCS002C SEVERITY=450 RAMP=30 (SIG Tube Rupture on 'C' S/G) 2. RUN 180 seconds 3. RUN 4. Manual SI and perform actions of EOQ-I .O & EOP-4.0 up through step 39 5. Throttle EFW to 'C' S/G when level > 30%. 6. FREEZE 7. Activate LOA-MSS033 SELECT-RACK OUT (RACK OUT BKR FOR MVG-2802B (STM SUPPLY TO ''. ..-~.' ' TDEFP)) 8. RUN 9. Perform actions of steps 3h-20 of EOP-4.0. 10. FREEZE I i. Place BIU heaters in P-T-L. 12. When Student is ready: RUN 13. After spray valve is started manually closed by student when depressurization termination criteria met, Activate:
MAL-PRS003B SEVERITY=IOO RAMPzO (PCV-444D STUCK OPEN) COMMENTS:
This JPM can be run from the same snap as JPSOO7 with the addition of MAL-PRSQ03B
= 100% Wednesday, March 24,2004 .. - Page 7 of 7 V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE JPM NO: JPS-008 LOSS OF POWER RANGE INSTRUMENT N-44 APPROVAL:
TRH APPROVAL DATE: 06/09/2003 REVNO: 5 W'edneyday, March 24,2004 _. Page 1 of 10 TASK: \-_ 030-034-05-01 RESPOND TO POWER RANGE INSTRUMENTATION CHANNEL FAILURE TASK STANIMRD:
N-44 has been removed from service (control power fuses removed) Control rod motion has been stopped (Bank selector switch placed in MAN). PREFERRED EVALLMTION IBChTlOh'
PREFERRED EVALUATION METHOD SIMULATOR PERFORM REFEREIVCES:
AOP-401 .IO POWER RANGE FAILURE TOOIS: EVALUATIOLV TIME 15 TIME CRITICAL No IOCFR55: 45(a)4 TIME START: Tlhm FWISW: ~ CA NDZDA TE: -. ~ ~ ~. ~ IIEjSAT - PERFORMANCE RATING: SAT - PEKklRMANCE TIME: - ~~ QUESTTON GRADE: . : ~~~~ ___ ~ ~ ~ ~ ~~~ ~ ~ ~ . L- EXAMIAWR:
COMMENTS:
SIGNATIJRE DATE Wednesday, March 24,2004 .-. Page 2 of I0 INSTRUCTIOA'S TO OPERATOR READ TO OPERATOR:
WHEN I TELL YOU TO BEGIN, YOU ARE TQ PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY POOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIE SAFETY CONSIDEM TZONS: INITIAL CONDITION:
The reactor is at 75% power. All controls are in automati INZTZATZNG CUES: Respond to developing plant condition .. . HAW JPM BRlEFING SHEET TO OPERATOR AT THIS TIME! Wednesday, March 24,2004 .. Page 3 of IO JPM BRIEFING SHEET OPERATOR INSTRUCTIONS:
SAFETY CONSIDERATIONS:
ZNZTIAL CONDITION:
The reactor is at 75% power. All controls are in automati ZNZTZATZNG CUES: Respond to developing plant condition HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TAS Wednesday, iVarck 24,2004 Page 4 of 10 STEPS CR SEQ STEP: 7 STEP STANDARB:
No Yes Identify power range channel N-44 has Operator identifies N-44 has failed low failed. by MCE indicatio CUES: SAT ~. UNSAT COMMENT'S:
CR SEQ STEP: 2 Yes Yes Manually control rods. CUES: Steps 2 and 3 are immediate Operator Actions. COMMENTS:
CR SEQ STEP: 3 No No Stop any transients in progres CUES: COMMENTS:
Wednesduy, March 24,2004 STEP STANDARD:
Positions the ROD CNTRL BANK SEL switch to the MAN positio ~ SAT UNSAT STEP STANDARD:
Verifies no load change is in progres SAT UNSAT Puge 5 of 10 CR SEQ STEP: 4 No No Maintain stable plant condition CUES: Note: This is a continuous action step. COMMENTS:
CR SEQ STEP: 5 No No Verify no testing is in progres CUES: Cue operator that no testing is in progres COMMENTS:
STEP STANDARD:
Pzr pressure and Tavg maintained stable. __ SAT UNSAT STEP STANDARD:
Looks at NI panel and/or asks examiner if any testing is in progres SAT UNSA T ~ CR SEQ STEP: 6 STEP STANDARD:
Yes No Set the rod stop bypass switch for the failed channel to bypass and verifies bistable light lit. Positions the ROD STOP BYPASS switch to the BYPASS Pi3 N-44 position and verifies XCP 61 11 light 4-4 lit. CUES: COMMEXTS:
Wednesday, March 24.2004 - SAT UNSAT Page 6 of I0 CR SEQ STEP: 7 STEP STANDARD:
.-_ Yes No Maintain Tavg within IT of Tref. Controls Tavg within 1&deg;F of Tref with manual rods. CUES: COMMENTS:
SAT UNSA T ___ - CR SEQ STEP: 8 STEP STANDARD:
Yes No Remove control power fuses from the N-44 Control power fuses fer the N-44 power range " A" drawer removed. power range " A" drawer. __ CUES: SAT Instruct NROATC that the CRS has requested him to remove N-44 from service. UN~~~ COMMENTS:
CR SEQ STEP: 9 STEP STANDARD:
Yes No Remove instrument power fuses from the N- Instrument power fuses from the power - 44 power range "B" drawer. range N-44 power range " B" drawer removed. Wednesday, March 24,2004 SAT C'h'SA T ___ .__ Pagf7oflO CR SEQ STEP: 10 STEP STANDARD:
"..-_: No No &sect;et the comparator defeat switch on the Positions the comparator channel defeat comparator and rate drawer to position associated with failed channel. switch to the N44 positio CUES: SAT UNSAI' ___ COMMENTS:
CR SEQ STEP: 11 STEP STANDARD:
No No &sect;et upper section and lower section Upper and lower section switches on the detector current comparator indicate Pi3 N44 positio switches on the detector current comparator to position associated with the failed channel. CUES: COMMENTS:
.-- CR SEQ STEP: 12 No No Ensure NR-45 is selected to operable channel CUES: COMMENI'S:
Wedaesda.v, March 24,2004 SAT UNSA T STEP STANDARD:
Selects pen 2 (delta I) to N42 (Delta Flux 11). .__ SAT G'NSA T __ Page 8 of 10 CR SEQ SlEP: 13 STEP STAh7DAlW:
-',. . No No Verify the status lights indicate the bistables Operator verifies that bistable lights fer trip. Channel IV, PR RATE HI, P!? LO and HI setpoints have energized to bright. CUES: SAT UNSAT COMMENTS:
Examiner ends JPM at this point. Wednesdaj, March 24, 2004 Page 9 of I0 JPM SETUP SHEET JPM NO: JPS-008 DESCRIPTION:
LOSS OF POWER RANGE INSTRUMENT N-44 ICSET: 11 INSTRUCTIONS:
1. RUN 2. When student is ready Activate MAL-NIS003B
&sect;EVE. ..TY = 0 RAMP = 5 (N-44 Failure) COMMENTS:
Rods will eventually (3 min.) restore Tavg to Tref (power rate mismatch signals die off, rods control on Tavgnref).


Leaving rods in AUTO still constitutes failure, as further transients on the failed channel (e.g. trouble shooting)
  * ,
would produce more uncontrolled rod motion. .- Wednesday, March 24,2004 Page 10 of 10 V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE JPM NO: JPS-056 CONTROL ROOM EVACUATION (DUTIES OF NROATC) APPROVAL:
LOCAQutside , 1 0 0  Knowledge of the operational applications of the following Annunciators and conditions indicating signals, and remedial Containment / 3  ncepts as they apply to the EMERGENCY PLANT  actions associated with the (LOCA Outside Containment).
TRH APPROVAL DATE: 06/16/2003 REVNO: 5 Wednesday, March 24,2004 L. Page 1 of 10 TASK: 000-068-05-01 PERFORM CONTROL ROOM EVACUATiON TASK STANDARD:
 
Reactor is tripped, Turbine is tripped, WCPs "EY and "C are tripped, PCV-444C (spray vlv) is closed PREFERREQ EVALL'A TION LOCATION PREFERRED EVALUATION METHOQ SiMUMTOR PERFORM REFERENCES:
EVOLUTION):(CFR: 41.8 to 4Z.10)       !\b
AOP-600.1 CONTROL ROOM EVACUATION TOOLS: AOP-600.1 EVALUATION TIME 10 TIME CRITICAL No IOCFRSS: 45(a)12 PERFORMANCE RATING: SAT UNSAT ~ PBRFORMANCE TIME: ~~~~~~ ~ - QUESTION GRAIIZ: i ~ . ~1~ __ . EXAMINER:
  ,I I 1          ~
SIGNATURE DATE COMMENTS:
,
Wednesday, March 24,2004 , Page 2 of 10 INSTRUCTIONS TO OPERATOR READ TO OPERATOR:
~
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AN5 PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AN5 PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OWlECTlVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIE I I SAFETY CONSIDEMTZONS:
,
Z,VZTZAL CON1)ZTION:
LOSS of Emergency
The plant is operating at 100% power, all controls in automati A bomb has been found in the Control Room. The Shift Supervisor has directed a Control Room evacuatio INITIATING CUES: The Shift Supervisor directs that the Control Room should be evacuate The CRS directs the NROAPC to complete Attachment I of AOP-600.1, starting with step 2. : HAND JPM BRIEFfNG SHEET TO OPERATOR AT THIS TIME! Wednesda.v, March 24,2004 .. Page 3 of 10  
/C4001ant Recirc i :
.IPM BRIEFING SHEET OPERA TOR ZNSTKUCTZONS:
0 ' 0 ~0
SAFETY CONSZDEZU TZONS: ZNZI'ZAL CONDZTZON; The plant is operating at 100% power, all controls in automati A bomb has been found in the Control Room. The Shift Supervisor has directed a Control Room evacuatio ZNZTZATZNG CUES: The Shift Supervisor directs that the Control Room should be evacuate The CRS directs the NROATC to complete Attachment I of AOP-600.1, starting with step 2. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY CONl PLETED THE ASSIGNED TASK. L Wednesday, March 24,2004 - Page 4 of 10 STEPS CR SEQ STEP:
  !
1 STEP STANDARD: Yes Yes Trip Reactor manually from the MCB. Position the reactor trip switch (CS- .- CROl or CS-CflOlA)
i1 !
to the TRIP position CUES: SAT UVSA T Cue operator time IS available to complete additional Control Room actions. COMMENTS: - CR SEQ STEP: 2 STEP STANDARD:
 
Yes No Verify all reactor trip breakers open. TRIP BKR A & B indicate red light OFF, green light ON. CUES: SAT UNSAT ~ COMhfENTS:  
  ~
-- CR SEQ STEP: 3 Yes No Verify all rod bottom lights lit. CUEIS: COMMENTS:
Knowledge of event based EOP mitigation strategie .1 .8
Wednesday, March 24 2004 STEP STANDARD:
 
All roc! bottom lights are lit by DRPl indicatio Page 50flO CR SEQ STEP: 4 STEP STANDARD:
            ~
Yes No Verify reactor power level decreasin Reactor power level decreasing on N35 and N36 indicatio CUES: SAT ~ G'NSAT COMMENTS:
ET Steam Line 0 0 0 0 0 ' 0 ,M12EA2.1 , Ability to determine and interpret the following as they WA Randomly Rejected Rupture -   ~ apply to (EMERGENCY PLANT EVQLUTION):(CFR:
CR SEQ STEP: 5 Yes Yes Trip the main turbine from MCB. ClJES: COMMENTS:
Excessive Heat  41 . I O / 43.5 / 45.13)
CR SEQ STEP: 6 Yes No Verifies turbine stop valves closed. - CUES: COMMENTS:
Transfer I 4  ~
Wednesday, Murch 24,2004 STEP STANDARD: Momentarily depresses EMERG TRIP push button. .- SAT UNSAT STEP STANDARD:
i l Inadequate 0 0 0 0 1 0 lWE05EA2. . Ability to detennitie and interpret the following asthey Adherence to appropriate procedures and operation within the Heat Transfer -  y a p p l y to (EMERGENCY PLANT E V O L U T m ( C F R : limitations in the facility's license and amendment Lass of  ~ 41 . I O I43.5 / 45.13) > /'
STM STOP VLVs indicate closed by lit indication on XCP-6114 status light Pugs 6 of 10 CR SEQ STEP: 7 STEP STANDARD:  
Secondary Heat Sink / 4
.. Yes No Ensures GEN BKR open (after 30 second GEN BKR indicates red light OFF, green time delay). light ON. CUES: COMMENTS:
 
CR SEQ STEP; 8 STEP STANDARD:
75 Point Tes.--
Yes No Ensures generator field breaker is open. GEN FIELD BKR indicates red light OFF, green light ON. CUES: COMMENTS:
Name I Safety Tier ?--Group2 Function: K1 K2 K3 A l A2 G KIA Number Question T w e    KIA Tonic    RO SRO
CR SEQ STEP: 9 Yes Ne Trips Exciter Field Control breaker. - CUES: COMMEA!TS:
' Continuous .9 I
Wednesday, March 24 2004 SAT UNSA T STEP STANDARD:
Dropped Control Rod / 1 1 0 0 0 003AK1 01 %, Knowledge of the operational appilcations of the following COnCeptS as they apply to the (ABNORMAL PLANT Reason for turbrne following reador on dropped rod event I EVOLUTION) (CFR 41 8 to 41 IO)
EXC FIELD CNTRL indicates red light OFF, green light ON. SAT UNSAT Page7ofll)
inoperable/Stuc 3 0 0 0 085AK305 1 enowledge af the reasons for the following responses as Power limits on rod misaligflment .2
CR SEQ STEP: 10 Y@s NQ Stop WCP'B'. CC'ES: COMMENTS:
 
CR SEQ STEP: 41 No No Verify RCP 'A is running. CUES: COMMENTS:
i k Control Rod /  they appiy to (ABNORMAL PLANT EVOLUTiON):(CFR:  ~ -?
STEP STANDARD:
          ;. .
Stop XPP-00308, RCP 8, indicates red light OFF, green light ON. SAT UNSAT __ STEP STANDARD:
1   41.5 145.6) C<'v Lw<d%l.:l
XPP-O030A, RCP A, indicates red light ON, green light OFF, normal running amps. SAT __ __ UNSA T CR SEQ STEP: 12 STEP STANDARD:
    .P- j 26 Emergency 0  0 024AK203
Yes NQ Close pressurizer spray valve, PCV-444 Manually closed PCV-444C, PZR SPRAY, and indicates red light OFF, green light QN. CUES: COMMENTS:
    /
Wednesdn), March 24,2004 SAT UNSAT __ __ Puge 8 of IO CR .$E& STEP: 14 Yes No StopRCP'C'.
k:
Examiner ends JPM at this point. Wednesday, March 24,2004 __._,' STEP STANDARD:
Knowledge of the interrelations between (ABNORMAL
Stop XPF-O030C, WCP C, indicates red light OFF, green light ON. SAT UNSAT Page 9 of 10 JFM SETUP SHEET JPM NO: JPS-056 DE,YCRIPTION:
        !
L CONTROL ROOM EVACUATION (DUTIES OF NRQATC) iesm IO INSTRUCTIQLVS:
KIA Randomly Rejected , Boration I 1  PLANT EVOLUTION) and the foilowing:(CFR: 41.7 !45.8)
7. When student is ready: RUN COMMENTS:
I Pressurizer ~ o 0 0 0 028AKI 01 Knowledge of the operational applications of the following KIA Randomly Rejected  2.8 ~ Level    concepts as they apply to the (ABNORMAL PLANT Malfunction I 2  EVOLUTION) (CFR 41 8 to 41 IO)
Wednesday, March 23,2004 .. Page IO of10
1 ~ng;y;= i O 0 0 0 032AKZa Knowledge of the interrelations between (MINORMAL PLANT EVOLUTION) and the foiiowing:(CFR: 41.7 / 45.8) ~
Power supplies. including proper switch positions 2.7 ~ i " ,
  ! 1 I
LOSS of 0  Knowledge of the interrelations between (ABNORMAL KIA Randomly Rejected  0 0 Intsrmediate  PLANT EVOLUTION) and the following (CFR 41 7 I 45 8)
 
1 Fuel Handling 0 0 10 ~036AG2.4.22 This is a Generic, no stem statement is associate KiA Randomly Rejected  3 4 Accident I &  ! :
i Steam  0 0 037AG2.4.31 This is a Generic, no stem Statement is associate KIA Randomly Rejected .4 Generator Tube Leak / 3 1 :
 
75 POIP~ re.
 
Name I Safety Tier ?-tSr~t.ip2 Function: K1 K2 K3 A I A2 G KIA Number Question Type  KIA Topic  RO SRO LOSS of Condenser Vacuum / 4 Acudental
  "T" 0 0 0 0 0 0 059AK3 02 I
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTiON):(CFR:41.10 /
43.5 /45.15)
Knowledge of the reasons for the following responses as Conditions requiring reactor and/or turbine trip WA Randomly Rejected 3.9 41 Llquld    they apoiy to (ABNORMAL PMNT EVOLUTlONl (CFR
~ /RQadWasteRe1
!
Accidental 0 0 0      WA Randomly Rejected I Gaseous Radwaste Re1 19  ~
I ARM System Alarms / 7 10 1o ' 0 I
WA Randomly Rejected  34 36 Plant Fire On- 0 0 0 1      Bypass of a heat detector .7 I site / 9 8 Control Ueom 0 0 0      KIA Randomly Rejected  29 33 Evac / 8 I Loss ofCTMT Integrity / 5 0 0 0 0 1 0 069A41'01 I
  '
    ' Ability to operate and I or monitor the following as they aPPIv to (ABNORMAL PLANT EVOLUTI0N):ICFR: 41.7 /
KJA Randomly Rejected Inad. Core 0 0 0 0 0 0 074FA1 OG Aoilly 10 Operate ard Ior monilo: rhe fo low8ngas they &A Ranaonily Re.ec1eo Cooling / 4  app:y tu .EMERGENCY PLANT EVOLUTi3N! (CFH 41 7
 
High Reactor a 1 0 0 0 0 076AK20 nowledee of the interrelations between (ABNORMAL Process radiation monitors  26 Coolant Activity  PLANT &OLUTIOM) and the foilowlng (CFR 41 7 I 4 5 8)
/9
 
      ""?UP 2 I A2 G KIA Number Question Type    KIA Topic Rediagnosis/3 0 0 0 0 0 1 WEOlEG2 This is a Generic, no stem statement is associated Knowledge of loss of cooling water procedures I Steam Generator
  ~ 0 0 0 0 0 0 'WE13EG2.1, This is a Generic. no stem Statement is associated,
    ~    KIA Randomly Rejected I ! !
I , ,
Components and funciiens of control and safety systems, 0 , 1 , 0 0 1WEi5A to operate and I or monitor the following as they ply to (EMEUGENCY PLANT EVOLUTiON):(CFR:4 including instrumentation signals, interlocks, failure modes i 145.6)    and automatic and manual features
 
0 0 0 WE16EA Ability to operate and /or monitor the following as they KIA Randomly Rejected  29 High Containment 0 0 0 '
i l I apply to (EMERGENCY PLANT EVOLUTION):(CFR:4 Radiation / 9 I / 45.6)
  . .
l SI Termination 0 0      Normal. abnormal and emergency operating procedures 33 associated with (SI Termination)
I 13    i EVOLUTION):(CFR:41.5 / 4 5 . 6 )      t LOCA 0 0 0 0 0 0 WE03EA2 I Ability to determine and interpret the following as they KIA Randomly Rejected  34 Cooidown -  apply to (EMERGENCY' PLANT EVOLUTION):(CFR:
Depress I 4  41.10 / 43.5 145.13)
I  I I Natural Circ I 4 0 0 0 0 0 0 WE09EA21 Aoility 10 aeterm ne and ntarpiet !ne follow.ny as ttiey KIA Randomly Rejected  31 apply 10 (MtHGENCY PLANT EVOLUT:ON, oCFR 41 : O I 43 5, 45 13)
NaturalCirc 0 0 0  This s d Geiiei c no olein st3lement IS assooa.:cJ KIA Randomly Rejected  34 3.8 1 With Seam Void/ 4 RCS 0 0 0 0 WE08EK2 2 Knowledge 01 lne inle.rela1ions Deheen iEMERGEhCY KIA Randomly Rejected  36 Overcooling  PLAhl' EVOLUTION, and li~clo ow.ng (CFH 41 I 45 8,     ~
PTS / 4
 
75 Point T& -.
Name I Safety Tier Tdroup 2 Function: K I K2 K3 A l A2 G KIANumber QuestionType    KIA Topic RO SRO 41.10 143.5 /45.13)
Saturated Core Cooling Core 0 " "0' I 0 ' 0 0 0 ,WE07EG2.2. This is a Generic, no stern statement is associate i KIA Randomly Rejected
 
25 134
 
Cooling I 4 i
LossofCTMT lntegrdy / 5 0 0 0
  , I
 
1 I
 
  . 1 0 :wE14A I
    , Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:
1, I
KIA Randomly Rejected ,34 38 41 1 0 / 4 3 5 / 4 5 1 3 )
 
75 Point \,--
Name / Safety  ,.-I-Tier z Group 1 Function: K1 KZ K3 K4 K5 K6 A1 A2 A3 A4 G WANumber QuestionType    KIA Topic  R5 SR5
!ChGiczand 0
  ~
 
  ~_
 
  .
0 ~0 1-1 ; ~ / L! ~4~~~~
    ~ ~ ~~ __.__~~ ~
      \\&ti-
      ~ ~ ~ ~ ~
Knowledge of the effect that a loss or malfunction of the I I id
' Volume Cmtrol    following will have on the (SYSTEM):(CFR: 41.7 / 45.7)
Emergency 0 '0 0 10 ' 11 1 0 0 U 0 0 0DtiKfi.tB    mafun:tiunof Ilie Core faoiing
~~~
  ~
_ ,1 :
  ,    .. _.___  ~ ~ ~ ~_
Pressurizer  0 0 0 0 007A1.01 ity to predict and/or m6nitor changes in parameters Maintaining quench t a m water level 3.1 ~
Relief/Cltlench    ociated with operating the (SYSTEM) controls within limits i Tank I
I including:(CFR: R 41.5 I45.5)
I 008K3.03 4 howiedge ofthe effect that a loss or malfunctionof the RCP I (SYSTEM) will have on the following:(CFf?: 41.7 I45.4)
r Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: f l . 2 lo 41.9 I45.7 to 45.8)
1 Reactor    Ability10 predict andlor monitorchangesin parameters Trip setpoint adjustment j Protection    associated with operating the (SYSTEM) mntrols 1      including:(CFR: 41.5 / 45.5) F, R--___-~ ~
ledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7 / 45.4)
Features i ~~~.~~ .     ~~
        ~____
 
75 Point 't Name / Safety Tier ~ G r o u pI Function:
  -
K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G
    - KIA NumhRr Question T..v ~ e
      \ I KIA ToDic  RO SUO
            - Containment  0  0  lo (a) predict the impacts of the fo!lowing on the Fan motor thermal overiaadlhigh-speed Cooling    STEM) and (b) based on those predictions. use >peration ures to correct, control. or mitigate th%
consequences of those abnormal operatlon:(CFR: 41.5 /
  .-  - - 45.6)  -~    __
II
        ~
Ice Condenser  0  0 025K5 02 Knowledge of th@operational implications oFthe following Up. Rejected copCeptS as they apply to the (SYSTEM):(CFR: 41.5 I j ..        -~  _ _ ~  -
Containment  0  0 D26A4.05 & & u a i y operate and/or monitor in the control 3mtsinment spray reset switches ! Spray    ~ room:(CFR: 41.7 I45.5 to 45.8)
i""' w*+#&sm
... ...
..
  .. .
  ......~~
.......................
0 'I 0 0
    -.
 
        ~~
Knowiedge of (SYSTEM) design feature@)and of
        ~
interlock(s) which pmvide for the foHowing:(CFR: 41.7)
___- I            -
0 0 0 0      9bllily to locate and operate components. ncluding local controls
  ~~ -
Main Feedwater    0 059Y1 02 I hiowledge of (he physica ccnnectms andlor c a s e -
affect relatioiishios between (SYSTEM) and the ~~ ~
            -~
hdtty to mw:w ddomiltic operations of the (SYSTEM) Auxiii2rylEmerg 5' ency Feedwater      (CF9 41 7 145 I )
i .
AC Electrical Distribution
  - .
          :DIG
            - __ .4
            ~- ___ _- .1
!    o QC Eiectrical    063~d.03 ,Ability to manudly operate and/or rlionitor in the wntrui 3attery discharge rate Distribution    mom:(CFH: 41 7 / 45.5 to 4 5 4 r\
I 1-f\.!;. .>
      ' ,
Y--
_...---
        .    .-
 
  ,
75 Point Te-..
Tier 2-Group 1
 
Name I Safety  .-P Funetion:
I K1 K2 K3 K K5 K6 A I A2 A3 G WA Number Questian Type    WATopic
            -
RO SRO
            -
3.3
~ Emergency o o    Ability to manually operate andior monitor in the MntrOl Establishing power from the ring bus (to Diesel    rmrn:(CFR 41.7 145.5 to45.8)  relieve EBiG)
, Generator
        ~~
edge of the operationai i ons of the foilowing Radiation theory. including sources, %
M):(CFB: 41.5 / types. units and effects
      , no stem statement is associate Ability to locate and operate components. .4 l          including bcal control ~--    -
    )78K2.02  power supplies to the  Emergency air compressor .5 0 0
            - .3 0 1 10362.4.4 fPQs is a Generic, no stem statement is associate Ability to recognize abnormal indications lo    A /  f w system operating parameters which are entry-level conditions for emergency and abnormal operating p:osedure ~      ~~~~
          ~  ~. ~- __ ~~~~
1 7 M r & n o w l e d g e of (SYSTEM) design feature(s) and or  Automatic start features associated with .2 Service Water 0 0 0 , l 0 0 0 interlock(s) which prov.$e for the fallo-R:  41.7) SWS pump mntrois
  ~
I instrument AI^
  -
o
  ..I-I io  0
    ~~~  ~ ~~~~~~
__ of the effect that a loss or malfunction of the (SYSTEM) will have on the Containment air system ~. .___    ___ .2 0 Io  0  o (a) predict the impacts of the following on the M) and (b) based on those predictions, use ures to correct. wntro  e equenses of those abno  (CFR: 41.5 I
        ~ ~~
__ .~~~~ .9 nowledge of eleclrical power supplies to the following:(CFR 41.7)  /----
            --
 
75 Paint T-         .
Name I Safety Tierk Group 1 Function:
Emergency
  --
KI K2 K5 K4 K5 K6 A I A2 A3 A4 G KIA Number Question Type    KIA Topic Operating voltages. currents and RO BRO i Generator sociated wlth operating the (SYSTEM) contro!s cludmg:(CFR 41.5 / 45.5)
temueratures
      ~~~~~~~~~~~~ ~~  __ ~
0 0  the operational implications of the following Pump head eff@ctswhen contrul valve IS ency Feedwater    ncepts as they apply to the (SYSTEM):(CFR 41.5 /
 
75 POI!
-.
Name ISafety Tier  Group 2 Function: K1 K2 K3 K4 K5 K6 A 7 X 2 A3 A4 G KIA Number QuesttDoPt Type    KIA Topie  RO SRQ 1 Hydrogen  TTq7  1 hbiiity to predict a n d h monitor changes in paramaters 028A1.02      KIA Randomly Rejected i j t
Recombiner and Purge Control 1 associated with operating the (SYSTEM) controls including:(CFR: 41.5/45.5)      3.4 ~ ~ ~  --  -  ~ - -  -  __ -
Containment  0 0 0 029hZ.03  Ability to (a) predict the impacts of the foilovdng on the KIA Randomly Rejected  2.7 Purge      (SYSTEM) and (b) based on these predictions. use procadures to correct, control, or mingate the Spent Fuel Pool Cooling
- - __
4lo
_ -
    ~ ~ .-
    -.
    ~ ~
    ~
      ~.
consequences of th3se abnormal operation:(CFR 41.5/
      ~
      ~
      ~ _ _-~ - -
__
no stem Sfatement is associate ~~  -
__
KIA Randomly Rejected
          ~
            - -
            ~
            -
Fuel Handling  0 0 0 034K6.02  wledge of the effect that a io% or malfunction Radiation monitoring systems 1 Equipment      owing will h,awon the (SYSTEM):(CFR: 41.7/45.7)
f-i i\  I L&,CL--.--
I 1 Steam
, Generator  i 0 0 0
        -. -~
wiedge of the physical connections andlur cause-ct relationships between (SYSTEM) and the h S F ll I
followingJCFR41.2 to41.9/45.71045.8)  i 1I-.- /A-  __  I
, Steam 1 Dump/Turbrne 0 0 0 341K1.02  1
      ~ L-~~- -
Knowledge of the ~5,vsicalwnnections andIa cause-eftzct rcliionshipi between (SYSTEM) and the i ihxid&y&iected I .
Bypass Control    folfowing.(CF'R41.2 tu 41.9 145.7 tu 45.8)
I
,
-
Main Turbine Generator
  ~
4 1
    ~~~ ~~~    -~
I
 
Turbine Slop/govemo: valve closure on turbinetrip l -
Condenser Air -t 0 0  0 , 055K1.06  wledge of the physical connections andlor cause-ct relatiofwhips between (SYSTEM) and the PRM system i
Remavat owing:(CFR 61.2to41.9/45.7to45.8)
i'l-,/
      & A c i_.~        ~~~ ~~~~ - - - -
Liquid  0 lo  O I 0  edge of the physical wnnections and/or cause- KIA Randomly Rejected 1 Radwaste    effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9I45.7to 45.8)
 
75 Point .-
Tier 2 Group 2 I
Name I Safety  -,-.-
 
Function: K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KIA Number Question Type    KIA Topie    190 SRO 071K6 K r f o w l a e of the effect that a loss or malfunction of the KIA Randomly Rejected  0 3 following wiil have on the (SYSTEM):(CFR: 41.7 / 45.7)
    + .-    .~ __    -
 
          ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
0  07262.1.16 This is a Generi no stem statement is associete Knowledge of system status criteria Y whioh require the notiflcation of plant u'    monne I
.~~-~
-
Circulating Water Statim Air
 
I, -
I 0 0 1' 075K1.02
    -
079K2
    -
b W l @ d Q of e the physical connections and/or cause-effect relationships betwean (SYSTEM) and the fdlowing:(CFR 41.2 to41.9 /45.7 to 45.8)
Knwrledge of e:edncat powet nupp!ies lo tho foliov!'r:g:(CFR: 41.7)
__
WA Randomly Rejected WA Randomly Rejected
__
__
___
            ~~~~
            -
1t9
            --p i
              ~- !i        +T
~          ~
Fire Protection 0  0 0 086K5.03 nowledye 01 the operatioiiai imp:ications o! the fdlowinp Effect of water spray on electrical i c ~ p t sas Ibey apply lo the (SYSTEM):(CFR: 41.5 1 components L/ 45.3)
      -
~
Control Rod Drive 0 0 O
0 0I 001K2.01
      .,.., -.--.
      - . ... . . ..
Know:edge of eiectfica: power supplies 10 Ihe 1ol:owing:iCFR: 41.7)
KIA Randomly Rejected  jjs ~ .    ~ .~~ ~ ~ _ _ ~  -~    . _- --
002K3.02 Knowledge of the effect that a loss or malfunction d the WA Randomly Rejected .5 Ueactor Coo!ant 0 0  0 0 (SYSTEM) will have on the following:(CFR: 41.7 / 45.4)
i
    ~_      -~    _- -
Ability to monitor automatic operations of the (SYSTEM) Charging and letdown .3 Pressurizer Level Control  0HA3.03j 'nduding:(CFR: 41.7 / 45.7)
h
__ - ~-
 
0 01  0 1 4 K 3 . 0 2 ~ knowledge of the effac: lhal a loss ar maifunctior, of the Plant computer .8 Rod Position  0 0 Indication    (SVSIEM) will have on the fo lovnng (CFR 41 I I 4 5 4)
I
 
75 Point --
Name I Safety Tier L Group 2 Function:
I Nuclear
  -
K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G W A Number Question TVDR .. KIA Topic
          -
RO SRO 0      KIA Randomly Rejected
. ~ ~. ~~
      ~  ~
__
0  Ability to predict andlor monitor changes in parameters KIA Randomly Rejected  0 associated with operating the (SYSTEM) cOntrols including:(CFR: 41.5/45.5)
~  -      ~
In-core  0 1 I 01782.2.22 H h i s is a Generic, no stem statement is associated Kmwledge of limiting conditions for Temperature        operations and safety limit Monitor
  -
Containment a  0 027A4.02 'lity to manually operate andlor monitor in the control Remote oDeratiin and handiinu of iodine Iodine Removal    m:(CFB: 41.7 I45.5 to 45.8)
 
75 Point Test Tier 3 Category KA Number KIA Toplc    RO SRO
.. __ ~~~
  - -  .-
Conduct of  ility to make accurate. clear and concise verbal reports.
 
Operations
    + - -
 
  ~- ~
      -  1 Conduct of  ity to direct personnel activities inside the control room.
 
Qperatiins (g
 
    .-
wledge of new and spent fuel movement procedure ons and safety limit ~
G o t IimGconditions for operations and safety limit ~
nowledge GEOP entry conditions and immediate adion steps.
}}
}}

Latest revision as of 01:07, 24 November 2019

V. C. Summer April 2004 Exam 50-395/2004-301 Draft Written Exam Quality Checklist ES-401-6 & Sample Plan
ML041410410
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 09/15/2003
From: Laska G
Division of Reactor Safety II
To:
References
Download: ML041410410 (17)
v • d • e


Text

Draft Submittal (Pink Paper)

DRAFT Written Exam Quality Checklist (ES-401-6)

ti Written Exam Sample Plan

ES-401 Written Examination Form E S - 4 0 M Quality Checkllst Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

-the audit exam was systematically and randomly develcped: or the audit exam was completed before the license exam was started: or 2 the examinations were developed independently: or-the licensee certifies that there is no duplication; or from the bank at least 20 percent new, and the actual 80 / SRO-onl Between 50 end 60 percent of the questions on the RO exam are written at the comprehension/analysis level; the SRO exam may exceed 60 percent if the randomly selected WAS support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at a. Author b. Facility Reviewer (")

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor Note: ' 'I he facility reviewer's initialsisignature are not applicaDle for NRC-developedexaminativn # inde~!!~~e!?!NRC,eviewei~~~!eal

..........items .....'c;"

..... i'l Column ......chief

.._ examiner co~currence.!pql;lred..........-

3Qof 34 NUREG-1821, Draft Revision 9

Tier 't Group 1 FunctIon: K1 K2 K3 A i A2 G KIA Number Question Type KIA Topic RB Sa0 1 1 '43 46 ReactorTnp- 0 0 0 0 0 0 007EA2 02 Ability to detmmine and interpret the following as they WA Randomly Rejected Stabilization - apply to (EMERGENCY PLANT EVOLUTION) (CFR uecovery I 1 1 1 41 1 0 / 4 3 5 / 4 5 1 3 )

I I

Pressurizer Vapor Space 0 0 0 0 1 0 'OOBA41.01 , Ability to operate and / or monitcr the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I KIA Randomly Rejected

,

~

Accident I 3 45.6)

i i

Small Break ~ 0 10 ~ 0 ~ 0 o stem statement is associak Knowledge OF how to conduct and verify valve lineup LOCA I 3

-- *---. ~ .

Large Break 0 0 11 0 OllEK3 WAKnowledge of the reasons for the following responses as Placing wntainment fan cooler damper in accident pasition

, LOCA / 3 , they apply to (EMERGENCY PLANT I EVOLUTION) (CFU 41 5 / 45 6) 2 RCP 1

I o 1c o c 3 o O + ~ A I ( ofifinow L e& nf tne .r.teireial ons uewecn {ABNORMAL ccws I26 Malfunctions / 4 PLANT ~ V PLANT

.\

v O L L T , O N anJ

, Ihr lo ww,nr, C r R 41 7 s 45 81 I

I 3

. ,

LO55 Of R X 0 ,o 1 0 0 ;022AA1.OF ~ Ability to operate and / o r monitor the following as they CVCS charging low iiow alarm, sensor and indicator 3 Coolant Makeup / 2 ~I1 1 apply to (ABNBUMAL PLANT EVOLUTION):(CFR: 41.7 /

45.6) h 4 Loss of RHU 0 0 0 lo 1 I 10 025AA202J

',

6bility to determine and interpret the following as they ieakage of reactor coolant from RHR into closed cooling water .8 System / 4 apply to ABNORMAL PLANT EVQLUTION):(CFR: 41.10 / system or into reactor building atmosphere 43.5/45.13),

~

I boss of D O 0 0 0 0 026AK301 Knowledge of the reasons for the following responses as KIA Randomly Uqected I 32 Component they apply lo (ABNORMAL PLANT EVOLUTION) (CFR Cooling Water / 41 5 / 4 5 6 )

I8 Isolation of PZR spray following loss of PZR heaters 35 38

'1 Pressurizer pressure Control System 0 0 hnowlcoge of the reasons for the fu owing responses as tnev apply to ,ABNORMAL PLAN1 FVOL'JT ON, (CFR

Malfunction I 3

75 Point Teh...

Pier *-Group I Name i Safely Function: Kt KZ K3 A I A2 G KIA Number ~ Question Type KIA Topic RO SRO IATWSII 029EK2 O&Knowledge ofthe interrelations between (EMERGENCY Breakers. relays, and disconnects .1 PLANT EVOLUTION) and the following (CFR 41 7 145 8)

h

. ,

Steam Ge Ability to operate and / o r monitor the following as they KIA Randomly Rejected .4

, Tube Rupture / amlv to EMEUGENCY PLANT EVOLUTION):(CFR: 4 I I3

!

Ueactivity effects of cooldown .4 Steam Line 0 0 0 1040AK1 05 Ruptuie -

1 Excessive Heat Transfer I 4 Loss of Main Feedwater / 4

,

. .

0 054AA1.02' -4 Ability lo operate and / o r monitor the following as they

~-

apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 /

45.6)

' Manual staltup of electric and steam-driven ARM pumps ~

I , ! &

\ = & I b / ~

Instruments and cantrols operable with only dc battery power 3.7 , Station 0 1 0 ,055EA2.04 Ability lo determine and interpret the following as they Blackout / 6 apply to (EMERGENCY PLANT EVOLUTICJN):(CFR: available 41.10 /43.5 /45,13H  !

Loss of Off-site Power 16 0 0 0 056AK1 03 -

Knowledae of theooerational a ~ ~ l ~ c a l i of co:icepls as they appy to me ARNORMhl. PLANT o nthe -

s followinQ Definition of subcwling: use of steam tables to determine it 3.1 , EVOLiTlONl (CFR 41 81041 10)

. . .

Loss Of V l k l 0 ! 0 1 '057AG his is a Generic, no stem statement is associate Ability to explain and apply all system limits and precautions. .8

AC lnst Bus 16 ,,

L(-& 4 i

~(?*&< ,

P I !

.~ -

o o o

~ O ~ ~ A K I . O $ 1 Knowledge of the operational applications of the following Battery charger equipment and instrumentation 28 31 Power 16 concepts as they apply to the (ABNORMAL PLANT

~ EVOLUTION):(CFR: 41.8 toAl.10)

0 1 0 %?AA2 C1 L'kbI 1y 111 oetermine and nterorel tho follow ng as lnoy Location of a leak in the SWS 2.9 j apply to ABNORMAI. PIAN1 EVCl.Lh'Olu, (CFH 41 10 '

75 Point Teb<..-

Tier W r o u p 1 Name I Safety Function: Kf K2 K3 A I A2 0 WANumhgr QueStiQnType WA Topic boss of Ability to operate and I or monitor the following as they Restoration of systems served by instrument air when Instrument Air / 41.7 / pressure is regained

  • ,

LOCAQutside , 1 0 0 Knowledge of the operational applications of the following Annunciators and conditions indicating signals, and remedial Containment / 3 ncepts as they apply to the EMERGENCY PLANT actions associated with the (LOCA Outside Containment).

EVOLUTION):(CFR: 41.8 to 4Z.10)  !\b

,I I 1 ~

,

~

,

LOSS of Emergency

/C4001ant Recirc i :

0 ' 0 ~0

!

i1 !

~

Knowledge of event based EOP mitigation strategie .1 .8

~

ET Steam Line 0 0 0 0 0 ' 0 ,M12EA2.1 , Ability to determine and interpret the following as they WA Randomly Rejected Rupture - ~ apply to (EMERGENCY PLANT EVQLUTION):(CFR:

Excessive Heat 41 . I O / 43.5 / 45.13)

Transfer I 4 ~

i l Inadequate 0 0 0 0 1 0 lWE05EA2. . Ability to detennitie and interpret the following asthey Adherence to appropriate procedures and operation within the Heat Transfer - y a p p l y to (EMERGENCY PLANT E V O L U T m ( C F R : limitations in the facility's license and amendment Lass of ~ 41 . I O I43.5 / 45.13) > /'

Secondary Heat Sink / 4

75 Point Tes.--

Name I Safety Tier ?--Group2 Function: K1 K2 K3 A l A2 G KIA Number Question T w e KIA Tonic RO SRO

' Continuous .9 I

Dropped Control Rod / 1 1 0 0 0 003AK1 01 %, Knowledge of the operational appilcations of the following COnCeptS as they apply to the (ABNORMAL PLANT Reason for turbrne following reador on dropped rod event I EVOLUTION) (CFR 41 8 to 41 IO)

inoperable/Stuc 3 0 0 0 085AK305 1 enowledge af the reasons for the following responses as Power limits on rod misaligflment .2

i k Control Rod / they appiy to (ABNORMAL PLANT EVOLUTiON):(CFR: ~ -?

. .

1 41.5 145.6) C<'v Lw<d%l.:l

.P- j 26 Emergency 0 0 024AK203

/

k:

Knowledge of the interrelations between (ABNORMAL

!

KIA Randomly Rejected , Boration I 1 PLANT EVOLUTION) and the foilowing:(CFR: 41.7 !45.8)

I Pressurizer ~ o 0 0 0 028AKI 01 Knowledge of the operational applications of the following KIA Randomly Rejected 2.8 ~ Level concepts as they apply to the (ABNORMAL PLANT Malfunction I 2 EVOLUTION) (CFR 41 8 to 41 IO)

1 ~ng;y;= i O 0 0 0 032AKZa Knowledge of the interrelations between (MINORMAL PLANT EVOLUTION) and the foiiowing:(CFR: 41.7 / 45.8) ~

Power supplies. including proper switch positions 2.7 ~ i " ,

! 1 I

LOSS of 0 Knowledge of the interrelations between (ABNORMAL KIA Randomly Rejected 0 0 Intsrmediate PLANT EVOLUTION) and the following (CFR 41 7 I 45 8)

1 Fuel Handling 0 0 10 ~036AG2.4.22 This is a Generic, no stem statement is associate KiA Randomly Rejected 3 4 Accident I &  ! :

i Steam 0 0 037AG2.4.31 This is a Generic, no stem Statement is associate KIA Randomly Rejected .4 Generator Tube Leak / 3 1 :

75 POIP~ re.

Name I Safety Tier ?-tSr~t.ip2 Function: K1 K2 K3 A I A2 G KIA Number Question Type KIA Topic RO SRO LOSS of Condenser Vacuum / 4 Acudental

"T" 0 0 0 0 0 0 059AK3 02 I

Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTiON):(CFR:41.10 /

43.5 /45.15)

Knowledge of the reasons for the following responses as Conditions requiring reactor and/or turbine trip WA Randomly Rejected 3.9 41 Llquld they apoiy to (ABNORMAL PMNT EVOLUTlONl (CFR

~ /RQadWasteRe1

!

Accidental 0 0 0 WA Randomly Rejected I Gaseous Radwaste Re1 19 ~

I ARM System Alarms / 7 10 1o ' 0 I

WA Randomly Rejected 34 36 Plant Fire On- 0 0 0 1 Bypass of a heat detector .7 I site / 9 8 Control Ueom 0 0 0 KIA Randomly Rejected 29 33 Evac / 8 I Loss ofCTMT Integrity / 5 0 0 0 0 1 0 069A41'01 I

'

' Ability to operate and I or monitor the following as they aPPIv to (ABNORMAL PLANT EVOLUTI0N):ICFR: 41.7 /

KJA Randomly Rejected Inad. Core 0 0 0 0 0 0 074FA1 OG Aoilly 10 Operate ard Ior monilo: rhe fo low8ngas they &A Ranaonily Re.ec1eo Cooling / 4 app:y tu .EMERGENCY PLANT EVOLUTi3N! (CFH 41 7

High Reactor a 1 0 0 0 0 076AK20 nowledee of the interrelations between (ABNORMAL Process radiation monitors 26 Coolant Activity PLANT &OLUTIOM) and the foilowlng (CFR 41 7 I 4 5 8)

/9

""?UP 2 I A2 G KIA Number Question Type KIA Topic Rediagnosis/3 0 0 0 0 0 1 WEOlEG2 This is a Generic, no stem statement is associated Knowledge of loss of cooling water procedures I Steam Generator

~ 0 0 0 0 0 0 'WE13EG2.1, This is a Generic. no stem Statement is associated,

~ KIA Randomly Rejected I ! !

I , ,

Components and funciiens of control and safety systems, 0 , 1 , 0 0 1WEi5A to operate and I or monitor the following as they ply to (EMEUGENCY PLANT EVOLUTiON):(CFR:4 including instrumentation signals, interlocks, failure modes i 145.6) and automatic and manual features

0 0 0 WE16EA Ability to operate and /or monitor the following as they KIA Randomly Rejected 29 High Containment 0 0 0 '

i l I apply to (EMERGENCY PLANT EVOLUTION):(CFR:4 Radiation / 9 I / 45.6)

. .

l SI Termination 0 0 Normal. abnormal and emergency operating procedures 33 associated with (SI Termination)

I 13 i EVOLUTION):(CFR:41.5 / 4 5 . 6 ) t LOCA 0 0 0 0 0 0 WE03EA2 I Ability to determine and interpret the following as they KIA Randomly Rejected 34 Cooidown - apply to (EMERGENCY' PLANT EVOLUTION):(CFR:

Depress I 4 41.10 / 43.5 145.13)

I I I Natural Circ I 4 0 0 0 0 0 0 WE09EA21 Aoility 10 aeterm ne and ntarpiet !ne follow.ny as ttiey KIA Randomly Rejected 31 apply 10 (MtHGENCY PLANT EVOLUT:ON, oCFR 41 : O I 43 5, 45 13)

NaturalCirc 0 0 0 This s d Geiiei c no olein st3lement IS assooa.:cJ KIA Randomly Rejected 34 3.8 1 With Seam Void/ 4 RCS 0 0 0 0 WE08EK2 2 Knowledge 01 lne inle.rela1ions Deheen iEMERGEhCY KIA Randomly Rejected 36 Overcooling PLAhl' EVOLUTION, and li~clo ow.ng (CFH 41 I 45 8, ~

PTS / 4

75 Point T& -.

Name I Safety Tier Tdroup 2 Function: K I K2 K3 A l A2 G KIANumber QuestionType KIA Topic RO SRO 41.10 143.5 /45.13)

Saturated Core Cooling Core 0 " "0' I 0 ' 0 0 0 ,WE07EG2.2. This is a Generic, no stern statement is associate i KIA Randomly Rejected

25 134

Cooling I 4 i

LossofCTMT lntegrdy / 5 0 0 0

, I

1 I

. 1 0 :wE14A I

, Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

1, I

KIA Randomly Rejected ,34 38 41 1 0 / 4 3 5 / 4 5 1 3 )

75 Point \,--

Name / Safety ,.-I-Tier z Group 1 Function: K1 KZ K3 K4 K5 K6 A1 A2 A3 A4 G WANumber QuestionType KIA Topic R5 SR5

!ChGiczand 0

~

~_

.

0 ~0 1-1 ; ~ / L! ~4~~~~

~ ~ ~~ __.__~~ ~

\\&ti-

~ ~ ~ ~ ~

Knowledge of the effect that a loss or malfunction of the I I id

' Volume Cmtrol following will have on the (SYSTEM):(CFR: 41.7 / 45.7)

Emergency 0 '0 0 10 ' 11 1 0 0 U 0 0 0DtiKfi.tB mafun:tiunof Ilie Core faoiing

~~~

~

_ ,1 :

, .. _.___ ~ ~ ~ ~_

Pressurizer 0 0 0 0 007A1.01 ity to predict and/or m6nitor changes in parameters Maintaining quench t a m water level 3.1 ~

Relief/Cltlench ociated with operating the (SYSTEM) controls within limits i Tank I

I including:(CFR: R 41.5 I45.5)

I 008K3.03 4 howiedge ofthe effect that a loss or malfunctionof the RCP I (SYSTEM) will have on the following:(CFf?: 41.7 I45.4)

r Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: f l . 2 lo 41.9 I45.7 to 45.8)

1 Reactor Ability10 predict andlor monitorchangesin parameters Trip setpoint adjustment j Protection associated with operating the (SYSTEM) mntrols 1 including:(CFR: 41.5 / 45.5) F, R--___-~ ~

ledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7 / 45.4)

Features i ~~~.~~ . ~~

~____

75 Point 't Name / Safety Tier ~ G r o u pI Function:

-

K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G

- KIA NumhRr Question T..v ~ e

\ I KIA ToDic RO SUO

- Containment 0 0 lo (a) predict the impacts of the fo!lowing on the Fan motor thermal overiaadlhigh-speed Cooling STEM) and (b) based on those predictions. use >peration ures to correct, control. or mitigate th%

consequences of those abnormal operatlon:(CFR: 41.5 /

.- - - 45.6) -~ __

II

~

Ice Condenser 0 0 025K5 02 Knowledge of th@operational implications oFthe following Up. Rejected copCeptS as they apply to the (SYSTEM):(CFR: 41.5 I j .. -~ _ _ ~ -

Containment 0 0 D26A4.05 & & u a i y operate and/or monitor in the control 3mtsinment spray reset switches ! Spray ~ room:(CFR: 41.7 I45.5 to 45.8)

i""' w*+#&sm

... ...

..

.. .

......~~

.......................

0 'I 0 0

-.

~~

Knowiedge of (SYSTEM) design feature@)and of

~

interlock(s) which pmvide for the foHowing:(CFR: 41.7)

___- I -

0 0 0 0 9bllily to locate and operate components. ncluding local controls

~~ -

Main Feedwater 0 059Y1 02 I hiowledge of (he physica ccnnectms andlor c a s e -

affect relatioiishios between (SYSTEM) and the ~~ ~

-~

hdtty to mw:w ddomiltic operations of the (SYSTEM) Auxiii2rylEmerg 5' ency Feedwater (CF9 41 7 145 I )

i .

AC Electrical Distribution

- .

DIG

- __ .4

~- ___ _- .1

! o QC Eiectrical 063~d.03 ,Ability to manudly operate and/or rlionitor in the wntrui 3attery discharge rate Distribution mom:(CFH: 41 7 / 45.5 to 4 5 4 r\

I 1-f\.!;. .>

' ,

Y--

_...---

. .-

,

75 Point Te-..

Tier 2-Group 1

Name I Safety .-P Funetion:

I K1 K2 K3 K K5 K6 A I A2 A3 G WA Number Questian Type WATopic

-

RO SRO

-

3.3

~ Emergency o o Ability to manually operate andior monitor in the MntrOl Establishing power from the ring bus (to Diesel rmrn:(CFR 41.7 145.5 to45.8) relieve EBiG)

, Generator

~~

edge of the operationai i ons of the foilowing Radiation theory. including sources, %

M):(CFB: 41.5 / types. units and effects

, no stem statement is associate Ability to locate and operate components. .4 l including bcal control ~-- -

)78K2.02 power supplies to the Emergency air compressor .5 0 0

- .3 0 1 10362.4.4 fPQs is a Generic, no stem statement is associate Ability to recognize abnormal indications lo A / f w system operating parameters which are entry-level conditions for emergency and abnormal operating p:osedure ~ ~~~~

~ ~. ~- __ ~~~~

1 7 M r & n o w l e d g e of (SYSTEM) design feature(s) and or Automatic start features associated with .2 Service Water 0 0 0 , l 0 0 0 interlock(s) which prov.$e for the fallo-R: 41.7) SWS pump mntrois

~

I instrument AI^

-

o

..I-I io 0

~~~ ~ ~~~~~~

__ of the effect that a loss or malfunction of the (SYSTEM) will have on the Containment air system ~. .___ ___ .2 0 Io 0 o (a) predict the impacts of the following on the M) and (b) based on those predictions, use ures to correct. wntro e equenses of those abno (CFR: 41.5 I

~ ~~

__ .~~~~ .9 nowledge of eleclrical power supplies to the following:(CFR 41.7) /----

--

75 Paint T- .

Name I Safety Tierk Group 1 Function:

Emergency

--

KI K2 K5 K4 K5 K6 A I A2 A3 A4 G KIA Number Question Type KIA Topic Operating voltages. currents and RO BRO i Generator sociated wlth operating the (SYSTEM) contro!s cludmg:(CFR 41.5 / 45.5)

temueratures

~~~~~~~~~~~~ ~~ __ ~

0 0 the operational implications of the following Pump head eff@ctswhen contrul valve IS ency Feedwater ncepts as they apply to the (SYSTEM):(CFR 41.5 /

75 POI!

-.

Name ISafety Tier Group 2 Function: K1 K2 K3 K4 K5 K6 A 7 X 2 A3 A4 G KIA Number QuesttDoPt Type KIA Topie RO SRQ 1 Hydrogen TTq7 1 hbiiity to predict a n d h monitor changes in paramaters 028A1.02 KIA Randomly Rejected i j t

Recombiner and Purge Control 1 associated with operating the (SYSTEM) controls including:(CFR: 41.5/45.5) 3.4 ~ ~ ~ -- - ~ - - - __ -

Containment 0 0 0 029hZ.03 Ability to (a) predict the impacts of the foilovdng on the KIA Randomly Rejected 2.7 Purge (SYSTEM) and (b) based on these predictions. use procadures to correct, control, or mingate the Spent Fuel Pool Cooling

- - __

4lo

_ -

~ ~ .-

-.

~ ~

~

~.

consequences of th3se abnormal operation:(CFR 41.5/

~

~

~ _ _-~ - -

__

no stem Sfatement is associate ~~ -

__

KIA Randomly Rejected

~

- -

~

-

Fuel Handling 0 0 0 034K6.02 wledge of the effect that a io% or malfunction Radiation monitoring systems 1 Equipment owing will h,awon the (SYSTEM):(CFR: 41.7/45.7)

f-i i\ I L&,CL--.--

I 1 Steam

, Generator i 0 0 0

-. -~

wiedge of the physical connections andlur cause-ct relationships between (SYSTEM) and the h S F ll I

followingJCFR41.2 to41.9/45.71045.8) i 1I-.- /A- __ I

, Steam 1 Dump/Turbrne 0 0 0 341K1.02 1

~ L-~~- -

Knowledge of the ~5,vsicalwnnections andIa cause-eftzct rcliionshipi between (SYSTEM) and the i ihxid&y&iected I .

Bypass Control folfowing.(CF'R41.2 tu 41.9 145.7 tu 45.8)

I

,

-

Main Turbine Generator

~

4 1

~~~ ~~~ -~

I

Turbine Slop/govemo: valve closure on turbinetrip l -

Condenser Air -t 0 0 0 , 055K1.06 wledge of the physical connections andlor cause-ct relatiofwhips between (SYSTEM) and the PRM system i

Remavat owing:(CFR 61.2to41.9/45.7to45.8)

i'l-,/

& A c i_.~ ~~~ ~~~~ - - - -

Liquid 0 lo O I 0 edge of the physical wnnections and/or cause- KIA Randomly Rejected 1 Radwaste effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9I45.7to 45.8)

75 Point .-

Tier 2 Group 2 I

Name I Safety -,-.-

Function: K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KIA Number Question Type KIA Topie 190 SRO 071K6 K r f o w l a e of the effect that a loss or malfunction of the KIA Randomly Rejected 0 3 following wiil have on the (SYSTEM):(CFR: 41.7 / 45.7)

+ .- .~ __ -

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

0 07262.1.16 This is a Generi no stem statement is associete Knowledge of system status criteria Y whioh require the notiflcation of plant u' monne I

.~~-~

-

Circulating Water Statim Air

I, -

I 0 0 1' 075K1.02

-

079K2

-

b W l @ d Q of e the physical connections and/or cause-effect relationships betwean (SYSTEM) and the fdlowing:(CFR 41.2 to41.9 /45.7 to 45.8)

Knwrledge of e:edncat powet nupp!ies lo tho foliov!'r:g:(CFR: 41.7)

__

WA Randomly Rejected WA Randomly Rejected

__

__

___

~~~~

-

1t9

--p i

~- !i +T

~ ~

Fire Protection 0 0 0 086K5.03 nowledye 01 the operatioiiai imp:ications o! the fdlowinp Effect of water spray on electrical i c ~ p t sas Ibey apply lo the (SYSTEM):(CFR: 41.5 1 components L/ 45.3)

-

~

Control Rod Drive 0 0 O

0 0I 001K2.01

.,.., -.--.

- . ... . . ..

Know:edge of eiectfica: power supplies 10 Ihe 1ol:owing:iCFR: 41.7)

KIA Randomly Rejected jjs ~ . ~ .~~ ~ ~ _ _ ~ -~ . _- --

002K3.02 Knowledge of the effect that a loss or malfunction d the WA Randomly Rejected .5 Ueactor Coo!ant 0 0 0 0 (SYSTEM) will have on the following:(CFR: 41.7 / 45.4)

i

~_ -~ _- -

Ability to monitor automatic operations of the (SYSTEM) Charging and letdown .3 Pressurizer Level Control 0HA3.03j 'nduding:(CFR: 41.7 / 45.7)

h

__ - ~-

0 01 0 1 4 K 3 . 0 2 ~ knowledge of the effac: lhal a loss ar maifunctior, of the Plant computer .8 Rod Position 0 0 Indication (SVSIEM) will have on the fo lovnng (CFR 41 I I 4 5 4)

I

75 Point --

Name I Safety Tier L Group 2 Function:

I Nuclear

-

K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G W A Number Question TVDR .. KIA Topic

-

RO SRO 0 KIA Randomly Rejected

. ~ ~. ~~

~ ~

__

0 Ability to predict andlor monitor changes in parameters KIA Randomly Rejected 0 associated with operating the (SYSTEM) cOntrols including:(CFR: 41.5/45.5)

~ - ~

In-core 0 1 I 01782.2.22 H h i s is a Generic, no stem statement is associated Kmwledge of limiting conditions for Temperature operations and safety limit Monitor

-

Containment a 0 027A4.02 'lity to manually operate andlor monitor in the control Remote oDeratiin and handiinu of iodine Iodine Removal m:(CFB: 41.7 I45.5 to 45.8)

75 Point Test Tier 3 Category KA Number KIA Toplc RO SRO

.. __ ~~~

- - .-

Conduct of ility to make accurate. clear and concise verbal reports.

Operations

+ - -

~- ~

- 1 Conduct of ity to direct personnel activities inside the control room.

Qperatiins (g

.-

wledge of new and spent fuel movement procedure ons and safety limit ~

G o t IimGconditions for operations and safety limit ~

nowledge GEOP entry conditions and immediate adion steps.

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