ML13066A461
| ML13066A461 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/27/2013 |
| From: | D'Antonio J Operations Branch I |
| To: | Entergy Nuclear Indian Point 3 |
| Jackson D | |
| Shared Package | |
| ML12214A189 | List: |
| References | |
| TAC U01866 | |
| Download: ML13066A461 (230) | |
Text
{{#Wiki_filter:---~.----~----~ Appendix C Job Peliormance Measure Form ES-C-1
.. ~.. - - - - - - - - Worksheet Facility: Indian Point 3 Task No: 2000060131 Task
Title:
Perform a Quadrant Power Tilt Calculation by Hand 1940012125 KIA
Reference:
RO - 3.9
~-~-----
Job Performance Measure No: RO Admin 1 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testin~ Simulated Performance Actual Performance Classroom x Simulator
-- Plant READ TO THE EXAMINEE 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.
Initial Conditions:
- Plant is at 100% power BOL.
- The Control Room personal computer is unavailable.
Task Standard: QPTR properly calculated. Required Materials: Calculator, GRAPH-NI-2 General
References:
3-S0P-RPC005A, GRAPH-NI-2 Initiating Cue: You are the BOP and You are directed to perform a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC-005A Time Critical Task: No Validation Time: 45 minutes 1 of 15
Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark v)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-S0P-RCP-005A Comment:
- 2. Performance Step: Review Note before Step 1 Standard: Reviews Note Comment:
- 3. Performance Step: ENSURE appropriate meter range for detectors A and B, for each operable NIS Power Range Channel Standard: EnsurE3s range meter indication between 1/3 and 2/3 of full scale Comment: Attachment Step 1.0 2 of 15
~A~pp~e~n=d=ix~C~____________________~P~age3 Form ES-C-1 Performance Information (Denote critical steps with a check mark..J)
- 4. Performance Step: Record the following current information:
Standard: Records the following on Attachment 1
- Date T odays Date
- Time Current Time
* % Power Indicated Power Comment: Attachment Step 2.0 "5. Performance Step: RECORD UPPER and LOWER detector currents on operable NIS Power Range drawers Standard: Records detector currents on the attachment Comment: Attachment Step 3.0
- 6. Performance Step: If power range current amp is unavailable Standard: This step is Not Applicable Comment: Attachment Step 3.1 3 of 15
Appendix C m Page 4 F()rm ES-C-1 Performance Information (Denote critical steps with a check mark ;/) ..J 7. Performance Step: CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps by full power zero axial offset detector current from 3 GRAPH-NI-2 Standard: Enter data and calculate corrected detector current ratios 41 Upper 799/790=1.011 41 Lower 843/850=0.991 42 Upper 818/825=0.991 42 Lower 823/822=1.001 43 Upper 875/890=0.983 43 Lower 873/875=0.998 44 Upper 832/830=1.002 44 Lower 896/910=0.985 Comment: Attachment Step 4
..J 8. Performance Step: DETERMINE both upper and lower Average Normalized Ratios Standard: CALCULATE average normalized ratios for Upper detectors:
= 41U + 42U + 43U + 44U = 1.011+0.991+0.983+1.003 4 4
= 0.996 CALCULATE average normalized ratios for Lower detectors:
= 41L. + 42L + 43L + 44L = 0.991+1.001+0.998+0.985 4 4
= 0.994 Comment: Attachment Step 5 4 of 15
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,j> ...J 9. Performance Step: DETERMINE both upper and lower Quadrant Power Tilt as follows Standard:
= Highest Ratio of 41U + 42U + 43U + 44U = 1.011 Average Ratio 0.996
= 1.015
= Highest Ratio of 41 L + 42L + 43L + 44L = 1.001 Average Ratio (Step 6.2) 0.994
= 1.007 Comment: Values obtained by the candidate may vary depending on how decimal places the}' carry.
Attachment Step 6.0
- 10. Performance Step: Record Highest Quadrant Power Tilt calculated Standard: Records 1.015 Comment: Attachment Step 7.0 5 of 15
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 11. Performance Step: If Quadrant Power Tilt exceeds 1.02 in either top or bottom of core ...
Standard: Determines QPTR does not exceed 1.02 Comment: Attachment Step 8.0 Terminating Cue: JPM Complete 6 of 15
No: 3-S0P-RPC-OOSA Rev: 5 QUAQRANT POWER TILTCALCULAnONS Page 10 of 13 ATI'ACHMENT1, MANUAL QUADRANT POWER TILT CALCULAnON (Page. 1 of 4) Adetector current meter range should be selected which places meter indication between 1/3 and full scale, 1.0 ENSURE appr()pri~t~ meter.range is selectec;lfor detectors A and Bf for eachoperable NIB PowerRange~hanneJ; . 2.0 RECORQthe follo~ing current information: Date :To'O'l\'I 3.0' RECOFUYindividual upper and lower Power' Range detector currents indicated on each operableNIS Power Ranga drawer in the following. Table 1: "
. Enter"Q" ,ifonepowerraOge cl1anneUs out Qfserviqa.
". TABL~1 c'
POWER RANGE CHANNEL, UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT
". "7 41 '1'lcr g,~3 . ...
I 42 ~(e Sol 3 43 81-5' 67?l 44 . " 8~ ~q(..
I QUADRANT POWER TILT CALCULATIONS I No: J..SOP-RPC-005A Rev:sl Page 11 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILTCALCULATION (Page 2pf 4) . WARNING Electrical shock hazard inside drawer. 3.1*' IF power range current amp is unavailable, THEN: 3.1.1 CONTACT I&C to obtain a DVM current,reading for the appropriate drawer. 3.1.2 RECORD DVM reading(s)in Table 1 ofStep 3.0. 4.0 CALCULATE corrected (normalized) detector current ratios. by dividing actual Detector Current Mic(<>amps recorded in TableJof Step3.0.~yfull pow~rzero axiaL offset detector current obtained from last incore/excore calibration (3:..Graph-NI-2, NIS Full Pciwer Detector Currents): Inqicated 3-Graph-Nl:..2 Normalized Detector Indicated 3-Graph-NI-2 Normalized Det~tor Current Current Ratio Current Current Ratio 41 Upper 144* ... 1'io = t.otl 41 Lower .;. i1s-o = D.qtll 42 Upper &', "" I}:.ti = (>.~**f 42 Lower .;. 6~) = tOOt 43 Upper t1.S -. e9:~ == O.1&~ 43 Lower t>16 = O.C)q~ 44 Upper ~32 + ~:30 Mtower 91'0 = Il/'JI35 8 of 15
I QUADRANT POWEIHILT CALCULATIONS No: 3-S0P-RPC-005A Page 11 of 13 Rev:5 I AnACH~ENT1, MANUAL QUADRANT POWER TILT CA:LCULATION (Page 2of4) WARNING 3.1 IFpowerrang~current amp is unavailable, THEN: 3.1.1 CONTACTI&C to obtain a DYMcurrent rE~ading forthe appropriate drawer. 3.1.2 RECqRD DVM reading(s) in Table 1 of Step 3.0. 4.0' CAl,CUtATE corrected (normalized) detector current ratios by dividing actual Detector Current Microarnps recorded ill Table 1 of Step3.0byfuUcpo~.rz~ro axialoffsetdetectof currentobtainedfrom last incore/excore calibratiol1 (3-Graph-NI-2. NIS Full Power Detector Currents): .. Detector Indicated 3-Glf,iph-NI-2 Normalized D t t Indicated 3-Graph-Nf-2 Normalized
. Current Current Ratio* e ec or Current Current Ratio 41 Upper _~,;..;._'t--.;".~+- lifo 41 Lowef_*.-...-;.~...,.. +- e5D = ~.&[lfl 42 Upper&f3 +- i)ji _"--.:.......;,..:.--1.42 Lower--.-;:.....,...,..-....,...,..- +- 6'1 = too, 43Upper 11-) +- ~o ... t>1f; = D.ci't~
44 Upper ~+ ~O +- 1tp = fl.6f/J~ 9 of 15
No: 3-S0P-RPC-005A Rev: 5 QUADRANT POWER 'OllT CALCULATIONS Page 12 of. 13 ATIACHMENTt, MANUAL QUADRANT POWERTllT CALCULATION (Page 3 of4) 5.0 DETERMINE both upp~r and lower Average Normalized Ratios. as follows:
!':!QIS When Reactor Power is less than or equal t075%, then 3 N!S power range channels can be us~d: (R~fer!9nce 5.2.2) If ONLY 3 NIS power range channels are in service. then "0" is entered for the inoperCible channel. AND the sum of the currents is divided by 3.
5.1 CALCULATE average normalized .ratio for Upper detectors: 41U + 42U+ 43U + 44U
=
3* or4*
... See note above 5.2 CALCULATE average normalized.ratiofor Lower detectors:
41 L + 42L + 43L+44L
= 3* or 4*
=
... See note above previous sub-step NOTE.
- Upper Quadrant = Highest Normalized Ratio for UpperDetector(Step 4.0}
Power TUt Average Normalized Ratio for Upper petector (Step 5.1)
- Lower Quadrant = HighestNormalized Ratio for lower Detector(Step 4.0)
Power Tilt Averag~Normalized Ratio for Lower Detector {Step ,5.2) 6.0 DETERMINE both upper and lower Quadrant Power Tilt as follows: 6.1 CALCULATE Quadrant Power Tilt for Upper detectors:
= Highest Ratio of 41U, 42U. 43U. or44U = =
Average Ratio (Step 5.1) 6.2 CAlCULATEQuadrant Power Tilt for Lower detectors:
= Highest Ratio. of 41[, 42L. 43L, or44L = lDo'
=
Average Ratio. (Step 5.2) l).qq ~ Leol 10 of 15
I No: 3-S0P-RPC-005A Rev:5 QUADRANT PQWERTILT CALCULATIONS I Page 13 of 13 ATTACHMENT 1, MANUAL QUADRANt POWER TILT CALCULATION (Page 4 of 4) 7.0 RECORD highest Quadrant Power Tilt calculated in StepsS.1 OR 6.2: Highest Quadrant Power Tilt._.....:...:L...::;O_I'_ 5 _....,..-.,_"'--_ _ _ __ 8.0 IF Quadrant Power Tilt exceeds 1.02 in either ~op OR bottom of core, THEN PERFORM the foUowing:
- VERIFY requirements of LCO 3.2A are met
- NOTIFY CRS.AND SM
- ENTER calculated Quadrant Power Tilt in the Narrative Log 9.0 REVIEW Attachment 1 for satisfactory completioO:
I Control. Room Supervisor Date I Time I Shift Manager Dat~ r Time 10.0 WHEN complete, THEN FORWARD this Quality Record tathe Operations Department Records Custodian. . Signature Date 11 of 15
Appendix C Page 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiners signature and date: _ _ _ _ _ _ _ _ _ _ __ 12 of 15
_Appendix C_ _ _ _ _ _ _ _--'-ln:. . . ;i. .; .tia.;,. I_C.;,. o:. . . ;n_--'d;. ;.cit: . .: io--'-n--=-s____________ Fo-=-rm--=E--=-S_-C-=--_1_ Initial Conditions:
- Plant is at 100% power BOL
- The Control Room personal computer is unavailable_
Initiating Cue: You are the BOP and You are directed to pl:trform a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC-OOSA
_Appendix C Initial Conditions Form ES-C-1 Actu;al Detector Currents Channel Top Bottom I 41 799 843 42 818 823 43 875 873
- 44 832 896
- _ Appendix C Initial Conditions Form ES-C-1 3-GRAPH-NI-2 Rev. 19X NIS FULL POWER <DETECTOR CURRENTS (pA)
Cycle 17 (Values updated based on 17C20 flux map at 99.9% RTP) FACE PLATE CURRENT Channel TOP BOTTOM N41 790 850 N42 825 822 N43 890 875 N44 830 910 IR DETECTOR CURRENT LIMITS FOR USE IN 3-POP-1.2I N35 Current limit (Amps) N36 Current limit (Amps) 4%RTP 0.85 E-05 1.72 E-05 8%RTP 1.70 E-05 3.44 E-05 Written By: Signature Reviewed By: Signature Approved By Signature Effective Date: Today's Date
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point Task No: 0040270131 Task
Title:
Perform Deborating Demineralizer In-Service Time Calculation 2.1.25 Job Performance Measure KIA
Reference:
RO - 3.9 No: ROAdmin2 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom x Simulator Plant READ TO THE EXAMINEE 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. Initial Conditions:
- CVCS is aligned for normal operation
- RCS filter is in service
- The demineralizer has been final rinsed
- Reactor Power is 100%
- Control Bank D is at 228 steps
- Current Tavg is 568°F
- Desired Tavg 569°F
- ITC -33.4 pcmrF
- Letdown Flow is 84 gpm
- Current Boron Concentration is 98 ppm
- Deborating Bed 31 is in service
- Deborating Demineralizer effluent is 14 ppm Sampled 0100 today.
- The SM had determined that the Deborating Demin will be used to reduce RCS boron concentration.
Task Standard: In-Service Time properly calculated. Required Materials: Calculator Procedure 1 of 6
Appendix C Job Performance Measure Form ES-C-1 Worksheet General
References:
3-S0P-CVCS-004 Initiating Cue: You are the spare RO and the CRS has directed you to determine the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4. Time Critical Task: No Validation Time: 45 minutes 2of6
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -,J)
- 1. Performance Step: Determine RCS has not been borated to cold shutdown
+100 ppm and Rx Trip Breakers are Open Standard: Given in Initial Conditions Comment: Procedure Step 4.3.4.1
- 2. Performance Step: Determine RCS Boron Concentration is > 3ppm and Rx Power is > 99%.
Standard: Given in Initial Conditions Comment: Procedure Step 4.3.4.2 "3. Performance Step: Calculate the change in Tavg on Attachment 1 Standard: A Tavg = TF - TI
=
A Tavg 569°F - 568°F Comment: Procedure Step 4.3.4.3 "4. Performance Step: Calculate the change in RCS Boron Concentration for the change in Tavg on Attachment 1 Standard: = A B A Tavg 'It ITC 'It IBW A B = 1°F'" -33.4 pcm/oF"'-O.1074 ppm/pcm AB = 3.58 ppm Comment: Procedure Step 4.3.4.4 30f6
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) ..J 5. Performance Step: Calculate Boron Efficiency for selected deborating demineralizer Standard: = BE 1 - (BO/BI) BE = 1 - (14/98) BE = .86 Comment: Procedure Step 4.3.1.1 ..J 6. Performa nce Step: Calculate G - gallons of water using Graph CVCS-3 Standard: From Nomograph - 2000 +/- 100 gallons Comment: Procedure Step 4.3.4.fi
..J 7. Performance Step: Calculate the Deborating Demineralizer in-service time Standard: T = G I (LF
- BE)
T = 2000 gallons I (84 gallons/min
- 0.86)
T =28 minutes (26 to 29 minutes) Comment: Procedure Step 4.3.4.5 Terminating Cue: JPM Complete 40f6
Append=ix~C~__________________~P=a~g~e~5~_________________F_o~r_m~E~S~-=C_-~1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result SAT or UNSAT Examiner's signature and date: 50f6
,~---------------------------------~-'---------..---------------,----,-,--------------~ Form Initial Conditions:
- CVCS is aligned for normal operation
- RCS filter is in service
- The demineralizer has been final rinsed
- Reactor Power is 100%
- Control Bank D is at 228 steps
- Current Tavg is 568°F
- Desired Tavg 569°F
- ITC -33.4 pcmJOF
- Letdown Flow is 84 gpm
- Current Boron Concentration is 98 ppm
- Deborating Bed 31 is in service
- Deborating Demineralizer effluent is 14 ppm Sampled 0100 today.
- The SM had determined that the Deborating Demin will be used to reduce RCS boron concentration.
Initiating Cue: You are the spare RO and the CRS has directed you to determine the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4.
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point 3 Task No: 2000390131 Task
Title:
Prepare a Tagout 1940012213 Job Performance Measure KIA
Reference:
- 4.1 No: ROAdmin3
--~------------
Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom x Simulator - - - - - - - - Plant -------- READ TO THE EXAMINEE 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. Initial Conditions:
- The unit is in Cold Shutdown with no fuel in the reactor
- The eSOMS Clearance Module is unavailable.
- The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement.
- Clearance Number is 3C20
- Tagout Number is CH-038.
- No deficiencies exist on valves identified in tag out boundary
- The shift manager has waived the requirement for double valve protection.
- Single Valve protection is adequate for this tagout.
- Restoration alignment is NOT necessary. Restoration lineup will be performed in accordance with the Fill and Vent procedure.
Task Standard: Manual Tagout Complete and ready for review Required Materials: None 1 of 11
Appendix C Job Performance Measure Form ES-C-1 Worksheet General
References:
EN-OP-102, Protective and Caution Tagging 3-COL-CVCS-001 Chemical and Volume Control System EN-OP-102-1, Protective and Caution Tagging Forms & Checklists 3-S0P-CVCS-002, Charging, Seal Water, and Letdown Control 3-S0P-EL-004, Electrical Equipment Operations 9321-F-27363 Flow Diagram Chemical and Volume Control System Sheet 1 617F644, 480 One Line Diagram Initiating Cue: You are a spare reactor operator and the SM has directed you to prepare a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP 102-01. Time Critical Task: No Validation Time: 45 minutes 2 of 11
Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 1. Performance Step: Obtain Correct Procedure Standard: Obtains EN-OP-102 and EN-OP-102-01 Comment:
- 2. Performance Step: Ensure requirement Attachments 9.1 and OP-102 are followed Standard: Review Attachment 9.1 and 9.2 CommentStep Procedure Step 5.3 [1]
- 3. Performance Step: Review Scope of Work Standard: Tagout Required for emergent work.
Given in Initial Conditions Comment: Procedure Step 5.3 [2]
- 4. Performance Step: Determine Safe Work Boundary for 33 Charging Pump Seal Replacement Standard: Review Plant Prints & Procedures 3-S0P-CVCS-002 3-S0P-EL-004 9321-F-27363 617F644 Comment: Procedure Step 5.3 [2] (g) 3 of 11
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ~)
- 5. Performance Step: Boundary Valves should be reviewed for outstanding deficiencies Standard: No deficiencies exist on valves identified in tagout boundary - Given in Initial Contitions CUE: No deficiencies exist on valves identified in tagout boundary Comment: Procedure Step 5.3 [3]
- 6. Performance Step: Utilizing the Isolation Boundaries, Prepare the tagoUit For each tag include:
- Tag Type
- Component/Equipment Number
- Component/Equipment Name
- Component/Equipment Location
- Component Hang and Restoration Position
- Tagout Hang Sequence Standard: See Attached Answer Key Comment:
4 of 11
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) Key Elements From Attachment 9.2 Tagging Sequence
- All Tagouts require tags to be hung and cleared in the order specified on the Tag Hang sheet or Tags To Be Removed sheet. When no definitive order is required for certain components of a Tagout, the Operations Supervisor may specify a given order number for multiple components (e.g., multiple components listed on the Tagout may be given order number "5" when their sequence relative to each other is not important).
- Recommended tagging order for pumps A. Control switch B. Breaker for main power C. Breakers for auxiliary power (motor heater, oil pumps, etc.)
D. Discharge valve E. Suction valve F. Other components within scope of T agout Terminating Cue: JPM Complete 5 of 11
\~-- I OJ -3/4#
a....... #242
.... 5T-4
\ \
)
.. (\J
....... 3 nX -..'..._1 'ij 1175C SEE NOTE P \\
J (\J
- 1 1/2'" RED, '-4-CH-151R JW I II.. !IV LINE #207'" Pu]
.z ,L-_!
-I ........ 113 /
J __J
~2 r- 3-CH-2502R LINE #19 Oli. /- NOTE 'ell L o <-",Co - *
- 0
#C16~R
"(\j
'10:: 3/4-CH-250 237:1:= 13 .... "7"'" */ r 3/ 4-CH-151 4 R
~ k~
,1.{)
lru I LINE T ' D. #218 LINE
'II jU 2'".3Q 405 X 3/ '
--- L I
I- ("") L 0> 9.. 1-CH-" ~ LI NE # I :> 1R I
/f:
' /
~- ST-5
- ~~ -----t~. ;;
i SEE NOTE P
\&_ ~
~-4-CH-151R STABILIZER 3-CH 11.:1>**\ '
WHT [ ._ 3' LINE-2502R
#402 9321-F-27283 LINE #200 RED~ 1 1/211 CHARG I NG PUt-1PS LEAKAGE COLLECTION 4-CH-2502R TANK 9321-F-27283 LINE #402 4' X 3' RED,
NUCLEAR MANAGEMENT MANUAL Protective and Caution Ta Forms & Checklist TAGOUT COVER SHEET Clearance: _MANUAL 3 C;l 0 Tagout: _ CH "016 Component to be worked: tL. De$cr'fp'~tio-n-:_ _ _ _ _---"a'-"'~~c:::.....:ha.'_=__D:\'~-At1~!!::!..:n'\~f------ 5.4_1 Rep13C1 MlA-l
--"'--'--'--' ----~---.---.---.
.~estoration Inst:
I Status Descriptlon-'- User ---'--'-rverification I _ _~~_--;- _ _ _ _-+_0 ~__ ,_!...-- Date . f~:~'k~, ReVie:e.r-
)~2.2!gyed - - '
Reviewed A rqyed - - -
... ~.._I. ~.t~____..
r - _,+..'I P~___
-.l~Verified Mung , Tags Verified Hung, -_.
j Re'!loval Approved ,I Removal~Q2!Qy'ed.= -~----
. Tags Verified Remov~~ I Tagsyerified Removed _ ~_----L _ _ ,_ _.....J 7 of 11
ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: MANUAL._3"'-'C:=;.:2=-:O'--__ TAGOUT: CH-038
------ ------------------~ -~--
Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement! Serial Type Equipment Description Place. Placement 1st Verif 2nd Venf Rest. Restoration Verif Verif Removal No. Eauioment Location Seq. Configuration Datemme Datemme I--Se~ _90nfiguration Datemme Datemme Tag Notes
~3 Charging Pump Pullout 1 Danger ~ontrol Switch 1 Or CRITICAL Auto Pull to Lock CCR --
33 Charging Pump 2 Danger Breaker Control Fuses 2 Removed/Off Installed/On 480V Room Bus 5A ------- 33 Charging Pump 3 Danger Breaker 3 Racked Out CRITICAL Racked In
~80V Room Bus 5A ----- --- -----------~ ----
p3 Charging Pump 4 Danger ~emote-Local Transfer Switch 4 Remote Remote PAB 55' Elevation ---- P3 Charging Pump Suction Stabilizer Danger
~eaters 5 Off Per Fill and Vent 5 Procedure PAB 55' Elevation Strip Heater Panel; --- ---------- -----
CH-238
~3 Charging Pump Outlet Isolation to Per Fill and Vent 6 Danger 6 Closed CRITICAL Procedure Seal Injection 33 Charaina Pump Cell ------ ---- 1----------
vH-236 Per Fill and Vent 7 Danger 33 Charging Pump Outlet Isolation 7 Closed CRITICAL Procedure 33 Charging Pump Cell .. - -- ---- --- CH-284 Per Fill and Vent 8 Danger 33 Charging Pump Inlet Isolation 8 Closed CRITICAL Procedure 1------ f------ PAB 55' Elevation
~H-281
~3 Charging Pump Relief and Per Fill and Vent 9 Danger 9 Closed
~ecirculation Line Outlet Isolation Procedure P3 Charging Pump Cell ---
8 of 11
ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE: MANUAL._3::..;C=2=O~__ TAGOUT: CH-038
..... ~ -------- --
PH-1175D Per Fill and Vent 10 Danger ~3 Charging Pump Suction Line Drain 10 Open CRITICAL Procedure p3 Charging Pump Cell pH-418 P3 Charging Pump Suction Stabilizer Per Fill and Vent 11 Danger 11 Open CRITICAL prain Procedure P3 Charging Pump Cell ...- ----- PH-103 Cap Per Fill and Vent 12 Danger P3 Charging Pump Outlet Vent Cap 12 Cap Removed CRITICAL Procedure 33 Charging Pump Cell ..... ~ --------- .....- -------- - -------- CH-103 Per Fill and Vent 13 Danger 33 Charging Pump Outlet Vent 13 Open CRITICAL Procedure 33 Charging Pump Cell l;H-420 Cap 33 Charging Pump Suction Stabilizer Per Fill and Vent 14 Danger 14 Cap Removed Vent Cap Procedure 33 Charging Pump Cell CH-420 P3 Charging Pump Suction Stabilizer Per Fill and Vent 15 Danger 15 Open
~ent Procedure P3 Charging Pump Cell PH-419 Cap P3 Charging Pump Suction Stabilizer Per Fill and Vent 16 Danger 16 Cap Removed CRITICAL
~entCap Procedure P3 Charging Pump Cell
,",H-419 17 Danger P3 Charging Pump Suction Stabilizer 17 Open CRITICAL Per Fill and Vent f,/ent Procedure
_. 33 Charging Pump Cell
-~---
9 of 11
Appendix C Initial Conditions Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The unit is in Cold Shutdown with no fuel in the reactor
- The eSOMS Clearance Module is unavailable.
- The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement.
- Clearance Number is 3C20
- Tagout Number is CH-038.
- No deficiencies exist on valves identified in tag out boundary
- The shift manager has waived the requirement for double valve protection.
- Single Valve protection is adequate for this tag out.
- Restoration alignment is NOT necessary. Restoration lineup will be performed in accordance with the Fill and Vent procedure.
Initiating Cue: You are a spare reactor operator and the 8M has directed you to prepare a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01.
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point Task No: 2000130131 Task
Title:
Prepare a VC Pressure Relief Release Permit 1940012311 Job Performance Measure ROAdmin4 KIA
Reference:
- RO--- 3.8
---- No:
Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom x Simulator Plant - - - - - READ TO THE EXAMINEE 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. Initial Conditions:
- 1. The Unit is operating at 100% power.
- 2. All radiation monitors are operable.
- 3. VC Pressure is 1.5 psig
- Permit Number 120204
- Radiation Monitor Data:
o R-12 Current Reading 7.170 E-7IJCi/cc o R-12 Current Alarm 9.948E-7 IJCi/cc o R-14 Current Reading 9.948E-7 IJCi/cc o R-14 Current Alarm 1.5E-5 IJCi/cc o R-15 Current Reading 1.32 E-6 IJCi/cc o R-27 Current Reading(CH - 4) 10.0 IJCi/sec o R-27 Current Alarm (CH - 4) 3.25 E+3 IJCi/sec o Plant Vent Sample 1.85 E-5 IJCi/cc Plant Vent Flow 3.21 E+4 scfm Condenser Air In leakage 5.8 scfm 1 of 10
Appendix C Job Performance Measure Form ES-C-1 Task Standard: . A VC Pressure Relief Gaseous Release Permit (3-S0P-WDS 013 Attachment 1) is correctly filled out. Required Materials: Calculator General
References:
3-S0P-WDS-013. Initiating Cue: You are the BOP operator and the CRS has directed you to perform a manual VC Pressure Relief Gaseous Release Permit in accordance with 3-S0P-WDS-013. Time Critical Task: No Validation Time: 25 Min 2 of 10
Appendix C Page 3 Form ES-C-1 Per1'ormance Information (Denote critical steps with a check mark --J)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-S0P-WDS-013 Review Precautions and Limitations CUE: All P&L are satisfactory to continue.
Comment:
- 2. Performance Step: Review NOTES before Step 4.1.1 Standard: Reviews Notes Comment:
- 3. Performance Step: Record VC Pressure Relief as system to be released on Attachment 1 Standard: Enters "VC Pressure Relief' on Attachment 1 Comment: Procedure Step 4.1.1
- 4. Performance Step: Record current date/time on Attachment 1 Standard: Enters current date/time on Attachment 1 Comment: Procedure Step 4.1.2 3 of 10
Appendix C Page 4 Form Performance Information (Denote critical steps with a check mark ...J)
- 5. Performance Step: ASSIGN permit number and RECORD on Attachment 1.
Standard: Records Permit Number. Given in Initial Conditions Comment: Procedure Step 4.1.3
- 6. Performance Step: Record current VC pressure on Attachment 1 Standard: Records 1.5 psig on Attachment 1. Given in Initial Conditions Comment: Procedure Step 4.1.4
- 7. Performance Step: VERIFY one of the following conditions satisfied:
- R-12 operable.
- R-11 operable AND a VC noble gas sample is obtained.
Standard: R-12 is operable. Given in Initial Conditions Comment: Procedure Step 4.1.5
- 8. Performance Step: Determine VC Noble Gas concentration using one of the following methods
- R-12 reading (~Ci/cc)
Standard: Determines R-12 reading is available Comment: Procedure Step 4.1.6 4 of 10
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
- 9. Performance Step: If using R-12, THEN circle "R-12 Monitor" and Enter the following on Attachment 1
- R-12 reading for Concentration of Nobel Gas (IlCi/cc)
- NA for Sample #, Date, and Time for Grab Sample Standard: Circle R-12 Monitor; Enter 7.170 E-7lJCi/cc and enter NA for Sample #, Date and Time Comment: Procedure Step 4.1.8
'\J 10. Performance Step: Determine calculated release rate ( R ) IJCi/sec and record on Attachment 1 Standard: R = (2.83E+05 cc/sec)
- 7.170 E-7IJCi/cC R= 2.02E-1 Comment: Procedure Step 4.1.9
'\J 11. Performance Step: Determine available release rate D in IJCi/sec with R-27 In Service (given in Initial Conditions) Standard: 3.25E+3IJCi/sec ... 10 IJCi/sec
=3.24E+3 IJCi/sec Comment: Procedure Step 4.1.10.1
- 12. Performance Step: Record Discharge Monitor on Attachment 1 Standard: Record R-27 on Attachment 1 Comment: Procedure Step 4.1.11
.--.----~-----------
5 of 10
Appendix C Page 6 Form ES-C-1 Perimmance Information (Denote critical steps with a check mark ...J)
- 13. Performance Step: Record Actual Alarm Setpoint on Attachment 1 Standard: Records 3.25E+3IJCi/sec Comment: Procedure Step 4.1.12
- 14. Periormance Step: If R is less than D THEN record NA for calculated alarm setpoint on Attachment 1 Standard: Records NA on Attachment 1 Comment: Procedure Step 4.1.13
- 15. Periormance Step: If calculated release rate R is greater than available release rate D THEN obtain authorization for higher release rate.
Standard: Determines R is less than D and authorization is not required Comment: Procedure Step 4.1.14
- 16. Performance Step: If R-27 is operable THEN enter an alert setpoint at a value below current alarm setpoint at CRS discretion and record on Attachment 1.
Standard: Records any value less than 3.25E+3IJCi/sec Comment: Procedure Step 4.1.15 6 of 10
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ""> .J 17. Performance Step: If R-12 is operable THEN determine R-12 calculated auto closure setpoint and record on Attachment 1 Standard: R-12 Setpoint = 7.0E4
- 3.53E-S
=2.471E-1 Comment: Procedure Step 4.1.1S.1
- 18. Performance Step: IF necessary THEN adjust R-12 auto closure setpoint to less than or equal to calculated value Standard: Determines setpoint adjustment is NOT necessary Comment: Procedure Step 4.1.16.2
- 19. Performance Step: When permit is complete, THEN record NA for the following:
- Release path valve alignment verification
- Volume
- Activity
- Iodine 131 Activity
- Calculated Alarm Setpoint
- Emax
- E
- RCV-014 setting Standard: Records NA on Attachment 1 Comment: Procedure Step 4.1.17 Terminating Cue: JPM Complete 7 of 10
Appendix C Page 8 Form ES-C-1 ANSWER KEY 8 of 10
Appendix C Page 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: 9 of 10
rtri'U wtiSt .. )in 1 t t r , " Appendix C Initial Conditions Initial Conditions:
- 1. The Unit is operating at 100% power.
- 2. All radiation monitors are operable.
- 3. VC Pressure is 1.5 psig
- Permit Number '120204
- Radiation Monitor Data:
o R-12 Current Reading 7.170 E-7 j.JCi/cc o R-12 Current Alarm 9.948E-7 j.JCi/cc o R-14 Current Reading 9.948E-7 j.JCi/cc o R-14 Current Alarm 1.5E-5 j.JCi/cc o R-15 Current Reading 1.32 E-6 j.JCi/cc o R-27 Current Reading(CH - 4) 10.0 j.JCi/sec o R-27 Current Alarm (CH - 4) 3.25 E+3 j.JCi/sec o Plant Vent Sample 1.85 E-5 j.JCi/cc Plant Vent Flow 3.21 E+4 scfm Condenser Air In leakage 5.8 scfm Initiating Cue: You are the BOP operator and the CRS has directed you to perform a manual VC Pressure Relief Gaseous Release Permit in accordance with 3~ SOP-WDS-013.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 2000070132 Task
Title:
Review a Quadrant Power Tilt Calculation by Hand 1940012125 KIA
Reference:
SRO - 4.2 Job Performance Measure No: SRO Admin 1 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom x Simulator Plant - - - - - READ TO THE EXAMINEE I will explain the initial conditions, which steps to sirnulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:
- Plant is at 100% power BOl..
- The Control Room personal computer is unavailable.
- A Reactor Operator performed an Manual Quadrant Power Tilt Ratio Calculation
- The Reactor Operator recommended a 9% power reduction.
Task Standard: QPTR properly calculated. Required Materials: Calculator, GRAPH-NI-2 General
References:
3-S0P-RPC005A, GRAPH-NI-2 Initiating Cue: You are Spare SRO and The SM directed you to REVIEW a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC OOSA. Determine if RO recommendation is accurate. Fix any errors you may find. Time Critical Task: No 1 of 38
Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 45 minutes 2of38
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-S0P-RCP-OOSA Comment:
- 2. Performance Step: K~\JIP'\J\I Note before 1 Standard: Reviews Note Comment:
- 3. Performance Step: ENSURE appropriate meter range for detectors A and B, for each operable NIS Power Range Channel Standard: Ensures range meter indication between 1/3 and 2/3 of full scale Comment: Attachment Step 1.0 3 of 38
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..,f)
- 4. Performance Step: Record the following current information:
Standard: Records the following on Attachment 1
- Date T odays Date
- Time Current TimE~
* % Power Indicated Power Comment: Attachment Step 2.0
- 5. Performance Step: RECORD UPPER and LOWER detector currents on operable NIS Power Range drawers Standard: Reviews Table 1 Entries - All Correct Comment: Provide the Candidate with detector currents for use in the remainder of the JPM Attachment Step 3.0
- 6. Performance Step: If power range current amp is unavailable Standard: This step is Not Applicable Comment: Attachment Step 3.1 4 of 38
nn.,.nl'l'IV C Form Performance Information (Denote critical steps with a check mark --J> ~ 7. Performance Step: CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps by full power zero axial offset detector current from 3 GRAPH-NI-2 Standard: Reviews entered data and calculate corrected detector current ratios 41 Upper 799/790=1.011 41 Lower 823/850=0.968 42 Upper 818/825=0.991 42 Lower 843/822=1.026 43 Upper 875/890=0.983 43 Lower 873/875=0.998 44 Upper 832/830=1.002 44 Lower 896/910=0.985 Identify incorrect vaiues used for 41 and 42 lower detector actual currents (Channel 41 current was entered in Channel 42 location and vice versa) Comment: Attachment Step 4 50f38
_Appendix C Page 6 --------'---=-. Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J)
- 8. Performance Step: DETERMINE both upper and lower Average Normalized Ratios Standard: CALCULATE average normalized ratios for Upper detectors:
= 41U+42U+43U+44U = 1.011+0.991+0.983+1.003 4 4
= 0.995 CALCULATE average normalized ratios for Lower detectors:
= 41L + 42L + 43L + 44L = 0.968+1,026+0.998+0.985 4 4
= 0.994 The actual calculated value for the lower average normalized ratio is the same as the correctly calculated value. Since current values were only entered in the wrong location, the sum and aven=!ge are still the same.
Comment: Attachment Step 5 60f38
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark --./) "9. Performance Step: DETERMINE both upper and lower Quadrant Power Tilt as follows Standard:
= Highest Ratio of 41 U + 42U + 43U + 44U ;; 1.011 Average Ratio 0.997
=1.014
= Highest Ratio of 41L + 42L + 43L + 44L = 1.026 Average Ratio (Step 6.2) 0.994
= 1.032 is incorrect.
The Correct value is 1.007 Comment: Values obtained by the candidate may vary depending on how decimal places they carry. Attachment Step 6.0
- 10. Performance Step: Record Highest Quadrant Power Tilt calculated Standard: Observes 1.032 on attachment 1 is incorrect value Identifies that based on earlier mistake QPTR is incorrectly calculatE~d.
Actual Correct QPTR is 1.014. Comment: Attachment Step 7.0 70f38
Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) ..J 11. Performance Step: If Quadrant Power Tilt exceeds 1.02 in either top or bottom of core ... Standard: Determines actual QPTR does not exceed 1.02 Determine RO power reduction recommendation is NOT correct. No reduction in power is necessary. Comment: Attachment Step 8.0 Terminating Cue: JPM Complete 80f38
Procedure Use Is: Control Copy: Entergy ~ Continuous Nuclear Northeast a Reference Effective Date: CJ Information Page 1 of 13 Approved By: I Procedure Sponsor, RPOI Designee Date Team 3D Procedure Owner k-~==~====~=~~~===--= __======__~=====-______~ EDITORIAL REVISION
QUADRANT POWER TILT CALCULATIONS REVISION
SUMMARY
(Page 1 of 2) 1.0 REASON FOR REVISION 1.1 Updated to eliminate poor practices and ensure procedure contains proper level of detail. 2.0
SUMMARY
OF CHANGES 2.1 Moved and revised former Step 1,2, of Purpose, to Step 2.2.1 of P&Ls, General Information (Editorial 4.6.13). 2.2 Moved and revised former Step 1.3, of Purpose, to Step 2.2.2 of P&Ls, General Information (Editorial 4.6.13). 2.3 Deleted former P&L 2.1 regarding RA-11 ,.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12). 2.4 Split Section 2, Precautions and Limitations, into 2 parts: 2.1, Precautions and Limitations and 2.2, General Information (Editorial 4.6.10). 2.5 Added P&L 2.1.1 regarding use of uncorrected detector outputs to be consistent with Unit 2 procedure (Editorial 4.6.11). 2.6 Added P&L 2.2.3 regarding short term Tilt spikes with alarm actuation following RCS boron changes to be consistent with Unit 2 procedure (Editorial 4.6.11). 2.7 Added "J£ Reactor Power is less than or ,equal to 75%, THEN" to Step 3.1 to clarify SR 3.2.4.1 (Editorial 4.6.13). 2,8 Deleted former Step 3.2 regarding reactor power being greater than 50%. Per Reactor Engineering, QPTR can be performed at lower power, but becomes less accurate (Editorial 4.6.12). 2.9 Added Step 3.2 "IF Reactor Power is greater than 75%, THEN VERIFY all four NIS channel upper and lower detectors are in service" to clarify SR 3.2.4.1 (Editorial 4,6.11) 2.10 Added Note prior to Step 4.1 regarding normalization factors not being available following refueling or detector maintenance (Editorial 4.6.11 ). 2.11 Split Section 4.1 into two parts: 4.1, Manual Quadrant Power Tilt Calculation and 4.2, Computer Network Program Quadrant Power Tilt Calculation (Editorial 4.6.14).
QUADRANT POWER TILT CALCULATIONS (Page 2 of 2) 2.12 Changed Step 4.2.8 from "SELECT' to "ENTER" and deleted bullet regarding clicking "OK" and appropriate option button as there are no 'select' options (Editorial 4.6.13). 2.13 Added 2 bullets to Note prior to Step 4.2.8 to clarify when 3 or 4 operable NIS Power Range channels are used (Editorial 4.6.11). 2.14 Deleted former Step 4.1.13 regarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12). 2.15 Deleted former Steps 4.1.14.2,4.1.14.3 and 4.1.14.4 as these are all included in Tech Spec 3.2.4 (Editorial 4.6.12). 2.16 Added bullet to Step 4.2.13 to enter calcu!lated Quadrant Power Tilt in the Narrative Log (Editorial 4,6.11). 2.17 Added Reference 5.2.2, SR 3.2.4,1 (Editorial 4.6.4). 2,18 Deleted former Reference 5.3.1, RA-11.1, as it is no longer mentioned in procedure (Editorial 4.6, 12). 2.19 Added Reference 5.6.1, O-NF-303, Core Quadrant Power Balance as an Interface Document (Editorial 4.6.11). 2.20 Added Reference 5.7.1 UFSAR Section 7'.6.2 (Editorial 4.6. 11). 2,21 Deleted former Step 4.0 of Attachment 1 regarding performing RA-11.1 ) Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements arE~ met (Editorial 4.6.12). 2.22 Added "when Reactor Power is less than or equal to 75%, then 3 NIS power range channels can be used" to Note in Step 5 of Attachment 1 to clarify when 3 operable NIS Power Range channels can be used (Editorial 4.6.13). 2.23 Added bullets to Step 8.0 of Attachment '1 to verify requirements of LCO 3,2.4 are met, notify CRS and SM and to enter QPTR in the Narrative log (Editorial 4,6.11). 2.24 Changed Step 10.0 of Attachment 1 to forward Attachment 1 to Operations Staff to simplify the action. Placing in Operations Log binder has the same result of forwarding to Operations Staff (Editorial 4.6.13).
No: 3-S0P-RPC-OOSA Rev:5 QUADRANT POWER TILT CALCULATIONS 4 of 13 TABLE OF CONTENTS Section Title Page 1.0 PURPOSE .. ................................................................................................................'" .... 5 2.0 PRECAUTIONS AND LIMITATIONS ................................................................................ 5 3.0 PREREQUISITES .............................................................................................................. 5 4.0 PROCEDURE ........ ............ .............. .......... ........... . ........................................................... 6
~Manual Quadrant Power Tilt Calculation ....... ,...... ...................................................... 6 4.2 Computer Network Program Quadrant Power Tilt Calculation ................................... 6
5.0 REFERENCES
............................................................................................ "..................... 9 6.0 RECORDS AND DOCUMENTATION ................................................................................ 9 Attachments ATTACHMENT 1 MANUAL QUADRANT POWER TILT CALCULATiON ................................ 10
QUADRANT POWER TILT CALCULATIONS Page 5 of 13 1.0 PURPOSE 1.1 This procedure provides guidance for the preparation of quadrant power tilt calculations in accordance with Technical Specification surveillance requirement SR 3.2.4.1. (if' PRECAUTIONS AND LIMITATIONS
~ Precautions and limitations g Uncorre.9!.~5:t.Q~~tor OU.!.Ql!~SHALL NOT be used to calculate quadrant QQY'{~J.H!Jte.J;§us.~.they do NOT 1:5ill.resent relative core power in their
£1IssociElted quadrant.
g General Information
~ WHEN in MODE 1 with greatecfO?ln 50 Qercent of rated thermal QQ.wer
<v JiNQ.glJ.~I£lDl'p..9w~r tiJL~,<c~~dJL1.02, THEN VERIFY QPTR IS within Iimi!J2'C<2<!1£Y.@!tQn oncELQ..~2 hours-:J.Befer.ence_5.2.1}
WHEN in MODE 1 with greS!teJ.lbarL~!;tQ~L<,:enl of rated theml~lJ29\}Jer AND either one ~OR lower ,9l!adrantpower tilt alarm monitors are inoperable, THEN verify QPTR h:; within limit by calculatiq,[l...Qnce per 12 houf..§....AN CU~ft~r load. change greateJjbi!.IJ..1.Q~cent qfL~~.sL'p'~Jer. {Reference 5.2.31
)3hort term Quadrant Power Tilt Galculation sl:;liking wi!bJln.ssible Plant Computer System alarm actuation c~ur immediately follQwing
/:<eilctor ~oolant S:x:stem (RCS)ooron change.s. These short term spik~
!,;3pr;>foximately five minutes qill.~~LQ~Q}, shou!c;LoQJ.J:2.~..fgJ1sidered
§h~nificant. as thGY are transitory in na.t.ure.
~ PREREQUISITES W :~,~~~~~c~~...:.~~
NA n*u;.!i. VERIFYi?_NlinifIlJ!m of three NIS .ghann§!lJ,!QJ2§f and iower detectors are in
§'~lY~E:!' iHeference 5.2.2)
IE Reactor Power is greaterJhan ?fir'l.. l
- Il::! ENJ/E RJFY_i!.U_LqhlLJ::lJ.:5r;:.h an nel uJ~.~Ls!il9Jg)ver d'?te_c;_tQX:U!I~in qervice.
QUADRANT POWER TILT CALCULATIONS Page 6 of 13 8 PROCEDURE Follovying refl,leling or detector maintenance, prior to performClnce of lQ!!i~.L.§J-power incoJ:Q flltx Inapping Q~ration§.;.lil§'. detector current Qutppt normalization factors will not R.e available. During tl1jl?J2§:!i9sLNI$.. detector current.outputs must be logged as required below. but quadrant tilt c§llcl}lations cannot be performed.
~ Manual Quadrant Power Tilt Calculatlol]
IF desired to perform a manual calculation, THEN GO TO ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION. 4.2 Computer Network Program Quadrant Power Tilt Calculation 1-**** NOTE ! A detector current meter range should be selected which places meter indication between 1/3 and 2/3 offull scale. 4.2.1 VERIFY appropriate meter range is selected for detectors A and 8 for each operable N1S channel. 4.2.2 RECORD the individual upper and lower power range detector currents indicated on each operable NIS Power Range drawer in the following table: TABLE L UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 42 43 i 44 I
_-.--~~et. \,~ I No: 3-S0P-RPC-005A QUADRANT POWER TILT CALCULATIONS r~a-;~~ of 13 i WARNING Electrical shock hazard inside drawer. I 4.2.2.1 IF a power range detector current amp reading is unavailable, THEN: a) CONTACT I&C to obtain a DVM current ri9ading for the appropriate drawer. b) RECORD DVM ,-eading(s) in the Table provided in Step 4.2.2. 4.2.3 ACCESS the QPTR Program (\\ipcfsetsp002\OPERATIONS\OPS GeneraI\IP3\Software\Unit 3\QPTR\QPTRexe). 4.2.4 IF the network is unavailable ANQ CCR computer is operational, THEN: 4.2.4.1 OBTAIN the QPTR Program CD from Shift Manager's office. 4.2.4.2 INSERT CD in a CCH computer AND OPEN QPTR Program. 4.2.5 CLICK the "Click Here to Start" button to retrieve 100% NIS currents from 3-Graph-NI-2. 4.2.6 COMPARE the latest NIS currents against the 3-Graph-NI-2 values. 4.2.6.1 IE the 100% NIS currents do not match 3-Graph-NI-2, THEf'i CLICK the "No" button AND ENTER 100% currents and 3-Graph-NI-:2 revision number in the text boxes when prompted. 4.2.6.2 IF the 100%) NIS currents match the latest revision of 3-Graph-NI-2, THEN[ click the "Yes" button. 4.2.7 WHEN prompted. THEN ENTER today's date, the current time and the current % power.
QUADRANT POWER TILT CALCULATIONS NOTE This program can be used for either 3 or 4 operable NIS Power Range channels.
- Ihree QPeraQL~J:':lIS Power Rang5Lchqnnels cat1Q~.JJsed whenBea_~tqLEQ~Yt?Lis less than or equal to 75% (Reference 5.2,2)
- All four operable NIS Power Range chanpels 8[!fLrequired when.Reactor Power is greater than 75%
4.2.8 ENTER the correct number of operable NIS Power Range channels. 4.2.9 ENTER appropriate NIS information from Table of Step 4.:2.2 in the white text boxes. 4.2.10 IF a power range channel that is out of service, THEN ENTER "0" for the applicable channel in the white text boxes. 4.2.11 CLICK on the CALCULATE QPTR button to show the current QPTR 4.2.12 CLICK on the PRINT RESU LTS button to obtain computer printout of the quadrant power tilt calculation. 4.2.13 lE Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:
- VERIFY requirements of LCO 3.2.4 are met.
- NOTIFY eRS AND SM.
- ENTER calculated Quadrant Power Tilt if'} the Narrative ~gg.
4.2.14 WHEN QPTR calculation program is no longer required, THEN CLICK "Quit Program". 4.2.15 OBTAIN CRS and SM signatures for the completed QPTR printout. 4.2.16 PLACE completed QPTR compLlter printout in Operations Log binder.
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 9 of 13
5.0 REFERENCES
5.1 Commitment Documents 5.1.1 None 5.2 Technical Specifications: 5.2.1 LCO 3.2.4 Action Statement 5.2.2 SR 3.2.4.1 5.2.3 TRO 3.2.A Action Statement 5.3 Development Documents 5.3.1 None 5.4 Historical Development Documents 5.4.1 3PT-W022. Quadrant Power Tilt Calculation 5.5 Drawings 5.5.1 None 5.6 Interface Documents 5.6.1 O-NF-30LQor~J~JadrarJt Pawer Balance 5.6.2 3-Graph-NI-2. NIS Full Power O(;}tector Currents 5.7 5.7.1 Section '[2.2 6.0 RECORDS AND DOCUMENTATION 6.1 Records 6.1.1 The following required records n3sulting from this procedure are controlled and maintained in accordance with the IP3 Records Retention Schedule.
- Attachment 1. Manual Quadrant Power Tilt Calculation Sheet
- Computer-generated printout of Quadrant Power Tilt Calculation 6.2 Documentation 6.2.1 The following documentation is required to be controlled (lr maintained in accordance with the IPEC Records Retention Schedule:
- None
QUADRANT POWER TtLT CALCULATIONS ATTACHMEN.f0 MANUAL QUADRANT POWERLfiLT CALCULATION (Page 1 of 4)
-~-.--.~~- ..... - - -..
A detector current meter range should be selected which places meter indication between 1/3 and 2/3 of full scale. ENSURE appropriate meter range is selected for detectors A and 8, for each operable N IS Power Range channel. RECORD the following current information: Date Ton ~'1 / Time CU(2.e~ 11 Me. % Power ......"D"""O"",--_/ 3.0 RECORD individual upper and lower Power Range detector currents indicated on each operable NIS Power Range drawer in the following Table 1:
~
nn\.",,'" range channel is out of service. TABLE 1 HANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 42 43 44
- - - .-.. ---------~. -----r.....!./~....:..::..:::;=a.d=-=-t.::..:.=----'IL=-f'¥_-1*f-----l INo: 3-S0P-RPC-OOSA Rev:S, QUADRANT POWER TILT CALCU_L_A_T_IO_N__S_-,-Ip~.,ge, 11 of 13 ~
ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 2 of 4)
~
f.C/
~/wARNING Electrical shock hazard inside drawer.
IF power range current amp is unavailable, THEN: I O~\3@ CONTACT I&C to obtain a DVM current reading for the appropriate drawer. 3t?f. RECORD DVM reading(s) in Table 1 of Step 3.0. CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps recorded in Table 1 of Step 3.0 by full power zero axial offset detector current obtained from last incore/excore calibration (3-Graph-NI-2, NIS Full Power Detector Currents): Indicated 3-Graph-NI-2 3-Graph-NI-2 Normalized Detector Current Current Current Ratio 41 Upper 1f1/ .;. 7iV 82'0 v = O.tlf~ t)*1tf.,t 42 Upper Blll $'/ .;. ~:l'5" v i'~:l.v = ,.~(. I.ceq 43 Upper tl 'S""""-- .;. ttl£> / -""-'-'''''''''''-- 43 Lower i'7~/" .;. i15,/ . = D.tMB .r 44 Upper f"~;}. v + i~Q i/" -'-'-~--... 44 Lower B91. V""'.;. q, 'b v" == b.1 f> '!l y'"
ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 3 of 4) DETERMINE both upper and lower Average Normalized Ratios as follows: NOTE When Reactor Power is less than or equal to 75%, then 3 NIS power range channels can Q~Lus_~.Q., (Reference 5.2.2) If ONLY 3 NIS power range channels are in service, then "0" is entered for the inoperable channel, AND the sum of the currents is divided by 3. CALCULATE average normalized ratio for Upper detectors: 41U + 42U + 43U + 44U = ~.:.-.tf:..-'-=-8__ ;: 3* or4* 4-/
- See note above
{!J' CALCULATE average normalized ratio for Lower detectors:
;: 41L + 42L + 43L + 44L = .3. '(7(, V =
3*or4* +/ l>.qq4-./
- See note above previous sub-step NOTE I!r Power Upper Quadrant Tilt
;: Highest Normalized Ratio for Upper Detector (Step 4.0}
Average Normalized Ratio for Upper Detector (Step 5.1) V Lower Quadrant ;: Power Tilt Highest Normalized Ratio for Lower Detector (Step 4&1 Average Normalized Ratio for Lower Detector (Step 5.2) 9' DETERMINE both upper and lower Quadrant Power Tilt as follows: V CALCULATE Quadrant Power Tilt for Upper detectors:
;: Highest Ratio of 41 U, 42U, 43U, or 44U = \ ,0 II ;:
Average Ratio (Step 5.1) (). qq1 y CALCULATE Quadrant Power Tilt for Lower detectors: I.co l Highest Ratio of 41 L, 42L, 43L, or 44L ;: .J.;...lI~~
\~
Average Ratio (Step 5.2) () .qt\4- 1.0J tOO7
No'. 3-S0P-RPC-OOSA Rev:S QUADRANT POWER TILT CALCULATIONS 3 of 13 ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION (Page 4 of 4) @!f RECORD highest Quadrant Power Tilt calculated in Steps 6.1 OR 6.2: Highest Quadrant Power Tilt:'--l.(.w.~~~~.....:I~.V:.....:I:.....A-.:.--_ _ _ _ __ 8.0 IF Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:
- VERIFY reguirermmts of lCO 3.2.4 are mel
- NOTIFY CRS AND 8M
* ~NTER calculat~Q1@drant Po.w~LliIt inl!l§ Nar rSlti.veJJJ-9 9.0 REVIEW Attachment 1 for satisfactory completion:
I Control Room Supervisor Date I Time I Shift Manager Date I Time 10.0 WHEN complete, THEN FORWARD this Quality Record to the Operations Department Records Custodian, Signature Date
_.Appendix C Page 22 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __ 22 of 38
Ii,. Appendix C Initial Conditions Form ES-C**1 Initial Conditions:
- Plant is at 100% power BOlo
- The Control Room personal computer is unavailable.
- A Reactor Operator performed an Manual Quadrant Power Tilt Ratio Calculation
- The Reactor Operator recommended a 9% power reduction.
Initiating Cue: You are Spare SRO and The SM directed you to REVIEW a Manual Quadrant Power Tilt Rate Calculation using Attachment 1 of SOP-RPC-OOSA. Determine if RO recommendation is accurate.
Appendix C Initial Conditions Form ES-C-1 Actual Detector Currents Channel Top Bottom I 41 799 843 42 818 823 43 875 873 44 832 896 I
Appendix C Initial Conditions Form ES-G-1 3-GRA:PH-NI-2 Rev. 19X NIS FULL POWER DETECTOR CURRENTS (pA) Cycle 17 (Values updated based on 17C20 flux map at 99.9% RTP) FACE PLATE CURRENT Channel TOP BOTTOM N41 790 850 N42 825 822 N43 890 875 N44 830 910 IR DETECTOR CURRENT LIMITS FOR USE IN 3-POP-1.3 N35 Current limit (Amps) N36 Current limit (Amps) 4%RTP 0.85 E-05 1.72 E-05 8%RTP 1.70 E-05 3.44 E-05 Written By: Signature Reviewed By: Signature Approved By Signature Effective Date: Today's Date
*
- WtttMM_ M
~Entergy
~ucleaz ~ortheast Procedure Use Is:
liJ Continuous [J Heference Control Copy: Effective Date: CJ Information Page 1 of 13 3-S0P..RPC..005 Revision: 5 ILT CJ'LCULATIONS Approved By: I Procedure Sponsor, RPOI Designee Date
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Team 3D .~\
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Procedure Owner EDITORIAL REVISION
... n 5i I NO: 3-S0P-RPC-005A QUADRANT POWER TILT CALCULATIONS Page 2 of 13 REVISION
SUMMARY
(Page 1 of 2) 1.0 REASON FOR REVISION 1.1 Updated to eliminate poor practices and ensure procedure contains proper level of detail. 2.0
SUMMARY
OF CHANGES 2.1 Moved and revised former Step 1.2, of Purpose, to Step 2.2.1 of P&Ls, General Information (Editorial 4.6.13). 2.2 Moved and revised former Step 1.3, of Purpose, to Step 2.2.2 of P&Ls. General Information (Editorial 4.6.13). 2.3 Deleted former P&L 2.1 regarding RA-11.1, Reactor Engineering prclcedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12). 2.4 Split Section 2, Precautions and Limitation:s, into 2 parts: 2.1, Precautions and Limitations and 2.2, General Information (Editorial 4.6.10). 2.5 Added P&L 2.1.1 regarding use of uncorrected detector outputs to be consistent with Unit 2 procedure (Editorial 4.6.11). 2.6 Added P&L 2.2.3 regarding short term Tilt spikes with alarm actuation following ReS boron changes to be consistent with Unit 2 procedure (Editorial 4.6.11). 2.7 Added "tE Reactor Power is less than or equal to 75%, THEN" to Step 3.1 to clarify SR 3.2.4.1 {Editorial 4.6.13). 2.8 Deleted former Step 3.2 regarding reactor power being greater than 50%. Per Reactor Engineering. QPTR can be performed at lower power, but becomes less accurate (Editorial 4.6.12). 2.9 Added Step 3.2 "IF Reactm Power is greater than 75%, THEN VERIFY all four NIS channel upper and lower detectors are in service" to clarify SR 3.2.4.1 (Editorial 4.6.11) 2.10 Added Note prior to Step 4.1 regarding normalization factors not being available following refueling or detector maintenance (EditoriaI4.S.11). 2.11 Split Section 4.1 into two parts: 4.1, Manual Quadrant Power Tilt Calculation and 4.2, Computer Network Program QUClldrant Power Tilt Calculat10n (Editorial 4.6.14).
t p t . !
....- - - - -... "\.. I I "~~"-""* >> ** --~-">>'->
- No: 3-S0P-RPC-OOSA Rev:5 I QUADRANT POWER TILT CALCULATIONS ~-- .",,,,,,,,,,,~,,-.-,, \
I I Page 3 of 13 (Page 2 of 2) 2,12 Changed Step 4.2.8 from "SELECT" to "ENTER" and deleted bullet regarding clicking "OK" and appropriate option button ciS there are no 'select' options (Editorial 4.6.13). 2.13 Added 2 bullets to Note prior to Step 4,2.8 tc> clarify when 3 or 4 operable NIS Power Range channels are used (Editorial 4.6.11). 2.14 Deleted former Step 4.1.13 rtegarding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors, Other methods exist to ensure requirements are met (Editorial 4,6.12). 2.15 Deleted former Steps 4.1.14.2,4.1.14.3 and 4.1.14.4 as these are al 1 included in 1 Tech Spec 3.2.4 {Editorial 4.6.12). 2.16 Added bullet to Step 4.2.13 to enter calculated Quadrant Power Tilt in the Narrative Log (Editorial 4.6.11 ). 2.17 Added Reference 5.2.2, SR 3.2.4.1 (Editoric:1I4.6.4). 2.18 Deleted former Reference 5.3.1, RA-11.1, as it is no longer mentioned in procedure (Editorial 4.6.12). 2.19 Added Reference 5.6.1, 0-NF-303, Core Ql.ladrant Power Balance as an Interface Document (Editorial 4.6.11). 2.20 Added Reference 5.7.1 UFSAR Section 7.6.2 {Editorial 4.6.11). 2,21 Deleted former Step 4.0 of Attachment 1 re!~arding performing RA-11.1, Reactor Engineering procedure which performs QPTR using in core detectors. Other methods exist to ensure requirements are met (Editorial 4.6.12). 2,22 Added "when Reactor Power is less than or equal to 75%, then 3 NIS power range channels can be used" to Note in Step 5 of Attachment 1 to clarify when 3 operable NIS Power Range channels can be used (Editorial 4.6.13). 2.23 Added bullets to Step 8.0 of Attachment 1 to verify requirements of LCO 3.2.4 are met, notify eRS and SM and to enter QPTR in the Narrative log (Editorial 4.6.11). 2.24 Changed Step 10.0 of Attachment 1 to forward Attachment 1 to Operations Staff to simplify the action. Placing in Operations Log binder has the same result of forwarding to Operations Staff (Editorial 4.6.13).
,,~-----~----------- 5 t mrl Ii iZ 3-S0P~RPC*005A QUADRANT POWER TILT CALCULATIONS TABLE OF CONTENTS Section Title Page 1.0 PURPOSE ....................................................................................................................... 5 2.0 PRECAUTIONS AND LIMITATIONS ................................................................................. 5 3.0 PREREQUiSiTES ............................................................................................................ 5 4.0 ~EDURE .......................................................... "......................................................... 6
!zy Manual Quadrant Power Tilt Calculation .................................................................... 6 4.2 Computer Network Program Quadrant Power Tilt Calculation ................................... 6
5.0 REFERENCES
.............................................................................................. " .................. 9 6.0 RECORDS AND DOCUMENTATION ................................................................................ 9 Attachments ATTACHMENT 1 MANUAL QUADRANT POWER TILT CALCULATION ................................ 10
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCU 5 of 13 1.0 PURPOSE 1.1 This procedure provides guidance for the preparation of quadrant power tilt calculations in accordance with Technical Specification surveHlanc'e requirement SR 3.2.4.1. ~ PRECAUTIONS AND LIMITATIONS {i;ff Precautions and Limitations g iJncorrected detector outputs SHALL NOT be used to calculate quadrant power tilt because they do NOT represent relative core power in their associated quaQumt. (fjf' General Information
~ I£JHEN in MODE 1 with greater than 50 percent of rated thermal power
<v AND quadrant power tilt exceeds 1.02, THEN VERIFY QPTR is within limit by calculation once_per 12 h;9urs. (Reference 5.2.11 WHEN in MODI; 1 with greater ti'1an 50 percent of rated thermal power AND either one upper OR lower quadrant power tilt alarm monitors are inoperable, THEN verify QPTR is within limit by calculation once per J 2 hours AND after load change greater than 10 percent of rated power.
(Reference 5.2.3)
~hort term Quadrant Power Tilt calculation spiking with possible Plant Computer System alarm actuation can occur immediately' following Reactor Cgo/ant System (RCS) boron changes. These short term spikes, (approximately five minutes duration), should not be considered Significant, as they are transitory in nature.
~ PREREQUISITES W'IE_.Reactor Power is less than or equal to 75%. NI>c THEN Vf;RIFY a Minimum of three NIS channel upper and lower detectors are in
§.ervic~LReference 5.2.2)
IF Reactor Po~ver IS QIeater than 75%, D:tttULF.",BIE:*C::!!LlQJ!L NI~_f.O a fl!1!31 UP2EL~II(;tL91YY._f?L,j~1~£tOt§.,i:}LE2JD_?52L'!!f.12.
No: 3-S0P-RPC-005A Rev:5 QUADRANT POWER TILT CALCULATIONS Page 6 of 13 I 8 PROCEDURE Following refueling or detector maintenance, prior 'to performance of initial at-power incore flux mapping operations, NIS detector current output normalization factors will not be available. During this period, NtS detector current outputs must be loggE::d as required below, but quadrant tilt calculations cannot be performecl L______________________________________________________, _ _________ ~
~ Manual Quadrant Power Tilt C.lculatio!l
~ IF desired to perform a manual calculation, THEN GO TO ATTACHMENT 1, MANUAL QUADRANT POWER TILT CALCULATION.
4.2 Computer Network Program Quadrant Power Tilt Calculation NOTE A detector current meter range should be selected which places meter indication between 1/3 and 2/3 offull scale. L -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ 4.2.1 VERIFY appropriate meter rangE! is selected for detector~s A and B for each operable NIS channel. 4.2.2 RECORD the individual upper and lower power range de!tector currents indicated on each operable NIS Power Range drawer in the following table: TABLE POWER RANGE CHANNEL UPPER DETECTOR CURRENT LOWER DETECTtOR CURRENT 41 42 43 44
H <<~1 r l
-j I I No: 3-S0P-RPC-00SA Rev:51 Ipa~f 13 QUADRANT POWER TILT CALCULATIONS
_____._.____J WARNING Electrical shock hazard inside drawer. 4.2.2.1 IF a power range detector current amp reading is unavailable, THEN: a) CONTACT I&C to obtain a DVM current reading for the appropriate drawE~r. b) RECORD DVM fElading(s) in the Table provided in Step 4.2.2. 4.2.3 ACCESS the OPTH Program (\\ipdsetsp002\OPERATIONS\OPS General\l P3\Software\U nit 3\0 PTR\Q PTR. exe). 4.2.4 IF the network is unavailable AND CCR computer is operational, THEN: 4.2.4.1 OBTAIN the QPTR Program CD from Shift Manager's office. 4.2.4.2 INSERT CD in a CCR computer AND OPEN QPTR Program. 4.2.S CLICK the "Click Here to Start" button to retrieve 100% NIS currents from 3-Graph-N 1-2. 426 COMPARE the late~st NIS currents. against the 3-Graph-NI**2 values. 4.2.6.1 lE. the 100% NIS currents do not match 3-Graph-NI-2, THEN CLICK the "No" button AND ENTER 100% currents and 3-Graph-NI-2 revision number in the text boxes when prompted. 4.2.6.2 LE the 100% NIS currents match the latest revision of 3-Graph-NI-2, THEN click the "Yes" button. 427 WHEN prompted, THEN ENTER today's date, the current time and the current % power.
1 No: 3-S0P-RPC-OOSA ReV:51 QUADRANT POWER TILT CALCULATIONS Page 8 of 13
----------~----------
NOTE This program can be used for either 3 or 4 operable NIS Power Range channels.
- Three operable NIS Power Range channels can be used when Reactor Power is less than or equal to 7!?:y'?.:. (Reference 5.2.2)
- All four operable I\IIS Power Range channels ar~required when,Reactor Power is qreater than 75'%
4.2.8 ENTER the correct number of operable NIS Power Range channels. 4.2.9 ENTER appropriate NIS information from Table of Step 4.2.2 in the white text boxes. 4.2.10 IF a power range channel that is out of service, THEN ENTER "0" for the applicable channel in the white text boxes. 4.2.11 CLICK on the CALCULATE QPTR button to show the current QPTR. 4.2.12 CLICK on the PRINT RESULT8 button to obtain computE~r printout of the quadrant power tilt calculation. 4.2.13 IF Quadrant Power Tilt exceeds 1.02 in either top OR bottom of core, THEN PERFORM the following:
- VERIFY requirements of LCO 3.2.4 are met
- NOTIFY CRS AND SM.
- ENTER calculated Quadrant Power Tilt in the Narrative Log.
4.2.14 WHEN QPTR calculation program is no longer required, THEN CLICK "Quit Program". 4.2.15 OBTAIN CRS and SM signature!s for the completed QPTR printout. 4.2.16 PLACE completed QPTR computer printout in Operations Log binder.
I No: 3-S0P-RPC-005A QUADRANT POWER TILT CALCULATIONS
! Page 9 of 13
5.0 REFERENCES
5.1 Commitment Documents 5.1.1 None 502 Technical Specifications: 5.2.1 LCO 3.2.4 Action Statement 5.2.2 §.R 32.4.1 5.2.3 TRO 3.2.A Action Statement 5.3 Development Documents 5.3.1 None 5.4 Historical Development Documents 5.4.1 3PT-W022, Quadrant Power Tilt Calculation 5.5 Drawings 5.5.1 None 5.6 Interface Documents 5.6.1 O-NF<ill3, Core Quadrant Power Balance 5.6.2 3-Graph-NI-2, NIS Full Power Detector Currents 5.7 UFSAR reference 5.7.1 Section 7.6.2 6.0 RECORDS AND DOCUMENTATION 6.1 Records 6.1.1 The following required records resulting from this procedure are controlled and maintained in ac(;ordance with the IP3 Records Retention Schedule.
- Attachment 1, Manual Quadrant Power Tilt Calculation Sheet
- Computer-generated printout of Quadrant Power Tilt Calculation 602 Documentation 6.2.1 The following documentation is required to be controlled or maintained in accordance with the IPEC Records Retention Schedule:
- None
I No: 3-S0P-RPC-OOSA Rev:S! I QUADRANT POWER TILT CA,L_CU_L_A_T_IO_N__ S_:=====.__--_-_-_-_-_-_-_-_,1 Page 1 0 of 13 I ATrACHMEN~) MANUAL QUADRAfo,lT POWER-tlLT CALCULATION (Page 1 of 4) r ~ A detector.current meter range should be selected which places meter indica~ion I I between 1/3 and 2/3 of full scale. ENSURE appropriate meter range is selected for detectors A and Bf for each operable NIS Power Range channel. RECORD the following current information: Date1DD~Y Time C.UtZ.2L~ 11 M Co % Power-1,..::;D'-=IO::...-_ __ 3.0 RECORD individual upper'and lower Power RanfJe detector currents indicated on each operable NIS Power Range drawer in the following Table 1: f!fs Enter "0". if one power range channel is out of service. TABLE 1 POWER RANGE CHANNEL UPPER DETECTOR CURRENT LOWER DETECTOR CURRENT 41 1'1~ 'i4~ 42
~ti X'~g 43
?1.;' ~7?l 44 fo~ a'ttt,.
=_.--,------------------------------..-.
3-S0P-RPC-OOSA QUADRANT POWER TILT CALCULAT10NS ATTACHMENT 1. MANUAL QUADRANT POWER TILT CALCULATION (Page 2 of 4)
~ARNtNG Electrical shock hazard inside drawer.
I
~ IF power range current amp is unavailable.
V THEN: fJ~ \3@ CONTACT I&C to obtain a DVM current reading for the appropriate drawer. 3!Ji. RECORD DVM reading(s) in Table 1 of Step 3.0. CALCULATE corrected (normalized) detector current ratios by dividing actual Detector Current Microamps recorded in Table 1 of Step 3.0 by full power zero axial offset detector current obtained from last incore/excore calibration (3-Graph-NI-2. NIS Full Power Detector Currents): Detector Indicated 3-Graph-NI-2 Normalized Detector Indicated 3-Graph-NI-2 Normalized Current Current Ratio Current Current Ratio 41 Upper M ;- 7'10 41 Lower t~!l ; SoS"Q == ()*1k~ 42 Upper 8. ttl ;- ~~'i = 42 Lower 2"~ ;
~~!l. = [!Q;2 f.
43 Upper. tlS- + t~() = 43 Lower 8:1~ + il5: == DltftI& 44 Upper f3:l ; ~~Q == 44lower ~~, + ~Il) == ~.1.~
No: 3-S0P*RPC-005A Rev: QUADRANT POWER TILT CALCULATIONS 3 ATTACHMENT 1, MANUAL QUADRANT POWER T'ILT CALCULATION (Page 3 of 4) DETERMINE both upper and IOWE3r Average Normalized Ratios as follows:
~ NOTE Y'Jhen Reactor Power is !.ess than or equal to 75%, then 3 NIS power ranqe cl1annels can b.~. ..1Lsed. (Reference 5.2.2) If ONLY 3 NIS power ratnge channels are in service, then "0" is entered for the inoperable channel. AND the sum of the currents is divided by 3.
CALCULATE average normalized ratio for Upper detectors: 41U + 42U + 43U + 44U 3* or 4*
- See note above CALCULATE average normalized ratio for Lower detectors:
41L + 42L + 43L + 44L 3* or 4*
.. See note above previous sub-step NOTE
{J" Upper Quadrant :: Highest Normalized Ratio for Upper Detector (Step 4.0) Power Tilt Average Normalized Ratio for Upper Detector (Step 5.1) fit" Lower Quadrant :::; Power Tilt Highest Normalized Ratio for Lower Detector (Step 4.0,! Average Normalized Ratio for Lower Detector (Step 5.~~) fif' DETERMINE both upper and lower Quadrant Power Tilt as follows: V CALCULATE Quadrant Power Tilt for Upper detectors:
- Highest Ratio of41U, 42U, 43U. or44U ::: l.011 Average Ratio (Step 5.1) ". qfn =
@' CALCULATE Quadrant Power Tilt for Lower detectors:
Highest Ratio of 41 L, ~+2L, 43L, or 44L~
= Average Ratio (Step 5.2)
=
No: 3-S0P-RPC-005A Rev: 5 QUADRANT POWER TILT CALCULATIONS ATTACHMENT 1, MANUAL QUADRANT POWER TilLT CALCULATION (Page 4 of 4) @!f RECORD highest Quadrant Power Tilt calculated in Steps 6.1 OR 6.2: Highest Quadrant Power Tilt:--1Jf.UlQ~3.Lt:l
- 8. 0 IF Quadrant Power Tilt exceeds 1,02 in either top OR bottom of core, THEN PERFORM the following:
- YERIFY requirements of LeO 3.2,4 are met
- NOTIFY CRS AND SM
- ENTER calculated Quadrant Power TIlt in the Narrative Log 9.0 REVIEW Attachment 1 for satisfactory completion:
I Control Room Supe!rvisor Date I Time I Shift Manager Date I Time 10.0 WHEN complete. THEN FORWARD this Quality Record to the Operations Department Records Custodian. Signature Date
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Task No: 2000100132 Task
Title:
Review Deborating Demineralizer In-Service Time Calculation 2.1.25 Job Performance Measure KIA
Reference:
SRO - 4.2 No: SROAdmin 2
--~------------
Examinee: NRC Examiner: Facility Evaluator: Date: -..Method of testi~ Simulated Performance Actual Performance x Classroom x Simulator Plant READ TO THE EXAMINEE 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. Initial Conditions:
- A Deborating Demineralizer In-Service Time Calculation was prepared by the Spare RO
- CVCS is aligned for normal operation
- RCS filter is in service
- The demineralizer has been final rinsed
- Reactor Power is 100%
- Control Bank D is at 228 steps
- Current Tavg is 568°F
- Desired Tavg 569°F
- ITC -33.4 pcmrF
- Letdown Flow is 84 gpm
- Current Boron Concentration is 98 ppm
- Deborating Bed 31 is in service
- Deborating Demineralizer effluent is 14 ppm Sampled 0100 today.
- The SM had determined that the Deborating Demin will be used to reduce RCS boron concentration.
Task Standard: In-Service Time properly calculated. 1 of 8
Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials: Calculator Procedure General
References:
3-S0P-CVCS-004 Initiating Cue: You are a spare SRO and the SM has directed you to review the Deborating Demineralizer In-Service Time using 3-S0P-CVCS-004 step 4.3.4. Make any necessary corrections. Time Critical Task: No Validation Time: 45 min 20f8
Appendix C."---_ _ _ _ _ _ _ _ _ _P-'-a-"<g-'-e-'--3 Form ES-C-1 Performance Information (Denote critical steps with a check mark --i)
- 1. Performance Step: Calculate the change in Tavg on Attachment 1 Standard: 1\ Tavg :: TF - TI 1\ Tavg :: 569°F - 568°F
~ Tavg =1°F Calculation is correct Comment: Procedure Step 4.3.4.3
- 2. Performance Step: Calculate the change in RCS Boron Concentration for the change in Tavg on Attachment 1 Standard: 1\ B = A Tavg
- ITC
- IBW 1\ B = 1°F * -33.4 pcmrF*-O. 1074 ppm/pcm
~ B =3.59 ppm Calculation is correct Comment: Procedure Step 4.3.4.4
- 3. Performance Step: Calculate Boron Efficiency for selected deborating demineralizer Standard: BE = 1 - (BO/BI)
BE = 1 - (14/98) BE = .86 Clculation is correct Comment: Procedure Step 4.3.1.1 3 of 8
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) ..J 6. Performance Step: Calculate G - gallons of water using Graph CVCS-3 Standard: From Nomograph 21,000 gallons This is NOT the correct value
-2500 gallons ;s the correct value Comment: Procedure Step 4.3.4.5. This value can be obtained if candidate uses 30 ppm for boron concentration change
..J 7. Performance Step: Calculate the Deborating Demineralizer in-service time Standard: T =G , (LF
- BE)
T =20,00galions / (84 gallons/min
- 0.86)
=
T 276.8 minutes This is NOT the correct value due to incorrect G from previous step,. 34.6 minutes Is ;the correct value Comment: Procedure Step 4.3.4.5 Terminating Cue: JPM Complete 40t8
PLACING THE CVCS DEMINERALIZERS Rev: 25 IN OR OUT OF SERVICE Page: 36 of 37 ATTACHMENT 1 DEBORATING DEMINERALIZER IN*SERVICE TIME CALCULATIONS (Page 1 of 1) 4.3.4.3 Required change in Tavg:
----::......-- = 5' q "r=
TF (OF) 4.3.4.4 Change in RCS Boron concentration:
<l. ~tJ
.1._ ,J-,
L\ B (ppm) L\Tavg (OF)
- :a. ~ '""T' v...J.
ITC (pcm/OF)
.A 1\
* ... w.
IBW (ppm/pcm) ro ',4 4.3.1.1 Boron Efficiency for Deborating Demineralizer: 51 OIDD -DDAV Bed No. Sample Time Sample Date
- . 1 ~ (_......!r-!4-:....-__ I_q..:..J~iII!--_-....l BO (ppm) BI (ppm) 4.3.4.5 Oemineralizer in-service time:
~~ .:i'f6l>
~~~ ~J~I ( 84-
- f:J.8f..
~ LF (gprn) BE 50f8
Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: 6 of 8
_J.\ppendix C Initial Conditions Form ES-C-1 Initial Conditions:
- A Deborating Demineralizer In-Service Time Calculation was prepared by the Spare RO
- CVCS is aligned for normal operation
- RCS filter is in service
- The demineralizer has been final rinsed
- Reactor Power is 100%
- Control Bank D is at 228 steps
- Current Tavg is 568°F
- Desired Tavg 569°F
- ITC -33.4 pcmJOF
- Letdown Flow is 84 gpm
- Current Boron Concentration is 98 ppm
- Deborating Bed 31 is in service
- Deborating Demineralizer effluent is 14 ppm Sampled 0100 today.
- The SM had determined that the Deborating: Demin will be used to reduce RCS boron concentration.
Initiating Cue: You are a spare SRO and the SM has directed you to review the Deborating Demineralizer In-Service Time using 3-S0P-CVCS*-004 step 4.3.4. Make any necessary corrections.
PLACING THE evcs DEMINERALIZER.5 No: 3-S0P-CVCS-004 Rev: 25 IN OR OUT OF SERVICE Page: 36 of 37 ATTACHMENT 1 DEBORATING DEMINERALIZER IN-SERVICE TIME CALCULATIONS (Page 1 of 1) 4.3.4.3 Required change in T avg: 4.3.4.4 Change in ReS Boron concentration: _j~.'5":....-.:...'1_= _ _ _ _ * -33.4 * -at 1074
~ B (ppm) ~Tavg (OF) ITe (pcm/OF) IBW (ppm/pcm) 4.3.1.1 Boron Efficiency for Deborating Demineralizer:
51 III Q/) T(tOAy' Bed No. Sample Time Sample Date
.8(, =1-( 14- I tte )
BE BO (ppm) BI (ppm) 4.3.4.5 Deborating Demineralizer in-service time:
~4'D. (. =j.l,ot>i> I 8~~
- CJ.8t.
T (min) G (gal) LF (gpm) BE
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point Task No: 2000390131 Task
Title:
Review a Tagout 1940012213 Job Performance Measure KIA
Reference:
- 4.3 No: SROAdmin 3 Examinee: NRC Examiner:
Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom x Simulator Plant --------- READ TO THE EXAMINEE 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. Initial Conditions:
- The unit is in Cold Shutdown with no fuel in the reactor
- The eSOMS Clearance Module is unavailable.
- The Shift Manager has determined that 33 Charging Pump must be tagged out for seal replacement.
- Clearance Number is 3C20
- Tagout Number is CH-038.
- No deficiencies exist on valves identified in tag out boundary
- The shift manager has waived the requirement for double valve protection.
- Single Valve protection is adequate for this tag out.
- Restoration alignment is NOT necessary. Restoration lineup will be performed in accordance with the Fill and Vent procedure.
- An RO prepared a manual tag out for 33 Charging Pump Task Standard: Manual Tagout Reviewed and errors located Required Materials: None 1 of 11
Appendix C Job Performance Measure Form ES-C-1 Worksheet General
References:
EN-OP-102, Protective and Caution Tagging 3-COL-CVCS-001 Chemical and Volume Control System EN-OP-102-1, Protective and Caution Tagging Forms & Checklists 3-S0P-CVCS-002, Charging, Seal Water, and Letdown Control 3-S0P-EL-004, Electrical Equipment Operations 9321-F-27363 Flow Diagram Chemical and volume Control System Sheet 1 617F644, 480 One Line Diagram Initiating Cue: You are a spare 8RO and the 8M has directed you to review a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01. Time Critical Task: No Validation Time: 45 minutes 2 of 11
- . . .;A--'Jpc.lp:. : e:. :.,.n:. =d:-i:.;xc.. . ;C"----_ _ _ _-_ _ _--'-'-ln, '-'.iti:. =ac.. . ;1C-=- o.; . .;n.; . .;dc.. . ;it:. . .;io:. :.,.n. .: . s_______~__'_F__
orr,n ES-C-1 Performance Information (Denote critical steps with a check mark ,j)
- 1. Performance Step: Obtain Correct Procedure Standard: Obtains EN-OP-102 and EN-OP-102-01 Comment:
- 2. Performance Step: Ensure requirement of Attachments 9.1 and 9,,2 of EN OP-102 are followed Standard: Review Attachment 9,,1 and 9.2 Comment: Procedure Step 5.3 [1]
- 3. Performance Step: Review Scope of Work:
Standard: Tagout Required for emergent work. Given in Initial Conditions Comment: Procedure Step 5.3 [2]
.....:.A~pI:Jpc:-=e:..:.n~d=:;,,;.ix:.-.C=---__________.-::I-'-Cn::.:::iti=a:-'C=-o=-n..;. :d: . ;.it: . :io:. :.n;. ;:.s_________--'F. . .:.o:. .:.r:c;. .;m. ES-C-1 Performance Information (Denote critical steps with a check mark ;/)
- 4. Performance Step: Determine Safe Work Boundary for 33 Charging Pump Seal Replacement Standard: Review Plant Prints & Procedures 3-S0P-CVCS-002 3-S0P-EL-004 9321-F-27363 617F644 Comment: Procedure Step 5.3 [21 (g)
- 5. Performance Step: Boundary Valves should be reviewed for outstanding deficiencies Standard: No deficiencies exist on valves identified in tagout boundary - Given in Initial Conditions CUE: No deficiencies exist on valves identified in tagout boundary Comment: Procedure Step 5.3 [3]
..J 6. Performance Step: Utilizing the Isolation Boundaries, Review the tagout and identify the following errors:
- Incorrect sequence for Item 1 (Breaker) and Item 3 (Control Switch)
- Item 9 CH-281 Placement Configuration is Open should be CLOSED Standard: See Attached Answer Key Comment:
Appendix C Initial Conditions Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) Key Elements From Attachment 9.2 Tagging Sequence
- All T agouts require tags to be hung and cleared in the order specified on the Tag Hang sheet or Tags To Be Removed sheet. When no definitive order is required for certain components of a Tagout, the Operations Supervisor may specify a given order number for multiple components (e.g., multiple components listed on the T agout may be given order number "5" when their sequence relative to each other is not important).
- Recommended tagging order for pumps A. Control switch B. Breaker for main power C. Breakers for auxiliary power (motor heater, oil pumps, etc.)
D. Discharge valve E. Suction valve F. Other components within scope of Tagout Terminating Cue: JPM Complete
ATTACHMENT 9.3 T AGOUT TAGS SHEET CLEARANCE:__ MANUAL 3C20 TAGOUT: SI-038 Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement! Serial Type Equipment Description Place. Placement 1st Venf 2nd Verif Rest. Restoration Verif Verif Removal ~o. Equipment Location Seq. Configuration Datemme Datemme Seq. Configuration Datemme Datemme Tag Notes [33 Charging Pump 1 Danger ~reaker 1 Racked Out CRITiCAL Racked In i ftBOV Room Bus SA r-,
~3 Charging Pump Danger ~reaker Control Fuses 2 Removed/Off Installed/On
~80V Room Bus 5A - -
P Charging Pump Pullout 3 Danger ~ontrol Switch 3 Or CRITICAL Auto Pull to Lock k.';CR
~3 Charging Pump 4 Danger "emote-Local Transfer Switch 4 Remote Remote PAS 55' Elevation
~3 Charging Pump 5 Danger ~uction Stabilizer Heaters 5 Off Off PAS 55' Elevation Strip Heater Pane!;
CH-238 I D e '33 Charging Pump Outlet Isolation to Per Fill and Vent 6 ang r ~eal Injection 6 Closed Procedure 33 Charging Pump Cell ---- -- ---- -- vH-236 Per Fill and Vent
-~-
7 Danger 33 Charging Pump Outlet Isolation 7 Closed Procedure 33 Charging Pump Cell vH-284 Per Fill and Vent 8 Danger 33 Charging Pump Inlet Isolation 8 Closed Procedure PAS 55' Elevation vH-281 9 Danger 33 Charging Pump Relief and Recirculation Line Outlet Isolation 9 Closed CRITICAL ~'Procedure Fni ,,' Vern 33 Charging Pump Cell
ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE:__ MANUAL 3C20 TAGOUT: SI-038
-I*
L~:::::i:: p:~: ::.00 Uoe ~'io I 1~+ Per Fill and Vent Open Procedure Per Fill and Vent 11 Open Procedure Cell
~-
Per Fill and Vent 12 12 Cap Removed Procedure Per Fill and Vent 13 Open Procedure Cell Per Fill and Vent 14 14 Cap Removed Procedure Per Fill and Vent 15 Open Procedure Cell Per Fill and Vent 16 Cap Removed Procedure Per Fill and Vent 17 Open Procedure
Appendix C Page 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The unit is in Cold Shutdown with no fuel in the reactor
- The eSOMS Clearance Module is unavailable.
- The Shift Manager has determined that ~~3 Charging Pump must be tagged out for seal replacement.
- Clearance Number is 3C20
- Tagout Number is CH-038.
- No deficiencies exist on valves identified in tagout boundary
- The shift manager has waived the requirement for double valve protection.
- Single Valve protection is adequate for this tag out.
- Restoration alignment is NOT necessary. Restoration lineup will be performed in accordance with the Fill and Vent procedure.
- An RO prepared a manual tag out for 33 Charging Pump Initiating Cue:
You are a spare 8RO and the 8M has directed you to review a manual tagout for 33 Charging Pump using EN-OP-102 and EN-OP-102-01.
ATTACHMENT 9.3 TAGOUT TAGS SHEET CLEARANCE: MANUAL..=..3C=2=O'--_ __ TAGOUT: -""C!...!.H-,,-O~38l:!..-_ __ Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement! Serial Type Equipment Description Place. Placement 1st Verif 2nd Verif Rest. Restoration Verif Verif Removal No. Eauipment Location Seq. c;oQflguration DatefTime DatefTime Sea. Configuration DatefTime DatefTime Tag Notes 33 Charging Pump 1 Danger Breaker 1 Racked Out Racked In 480V Room Bus 5A 33 Charging Pump 2 Danger Breaker Control Fuses 2 Removed/Off Installed/On 480V Room Bus 5A 33 Charging Pump Pullout 3 Danger ~ontrol Switch 3 Or Auto Pull to Lock (:CR 133 Charging Pump 4 Danger ~emote-Local Transfer Switch 4 Remote Remote PAB 55' Elevation 33 Charging Pump 5 Danger ~uction Stabilizer Heaters 5 Off Off I:>AB 55' F!evation Strip Heater P~ne!; CH-238 33 Charging Pump Outlet Isolation to Per Fill and Vent 6 Danger 6 Closed Procedure Seal Injection 33 Charging Pump Cell ---------- CH-236 Per Fill and Vent 7 Danger 33 Charging Pump Outlet Isolation 7 Closed Procedure 33 Charaina Pump Cell ------- -- CH-284 Per Fill and Vent 8 Danger ~3 Charging Pump Inlet Isolation 8 Closed Procedure PAS 55' Elevation
~H-281
~3 Charging Pump Relief and Per Fill and Vent 9 Danger 9 Open
~ecirculation Line Outlet Isolation Procedure 3} Chargingf>lIIllP<:;eU
ATTACHMENT 9.3 TAGOUT TAGS SHEET I CLEARANCE: MANUAL=.;3C=2=O'-_ __ TAGOUT:~~~________
~H-1175D Per Fill and Vent 10 Danger ~3 Charging Pump Suction Line Drain 10 Open Procedure
~3 Charging Pump Cell pH-418
~3 Charging Pump Suction Stabilizer Per Fill and Vent 11 Danger 11 Open prain Procedure
~3 Charging Pump Cell PH-103 Cap Per Fill and Vent 12 Danger ~3 Charging Pump Outlet Vent Cap 12 Cap Removed Procedure
~3 Charging Pump Cell PH-103 Per Fill and Vent 13 Danger 33 Charging Pump Outlet Vent 13 Open Procedure 33 Charging Pump Cell CH-420 Cap 33 Charging Pump Suction Stabilizer Per Fill and Vent 14 Danger 14 Cap Removed Drain Cap Procedure 33 Charging Pump Cell CH-420 33 Charging Pump Suction Stabilizer Per Fill and Vent 15 Danger 15 Open Drain Procedure I
33 Charging Pump Cell CH-419 Cap
~3 Charging Pump Suction Stabilizer Per Fill and Vent 16 Danger 16 Cap Removed rvent Cap Procedure
~3 Charging Pump Cell pH-419 17 J ~3 Charging Pump Suction Stabilizer D.",,", rvent
~3 Charging Pump Cell 17 Open Per Fill and Vent Procedure
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 2000180132 Task
Title:
Review a VC Pressure Relief Release Permit 1940012311 Job Performance Measure KIA
Reference:
SRO - 4.3 No: SROAdmin4 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom x Simulator - - - - - - - Plant - - - - - READ TO THE EXAMINEE 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. 1 of 14
Appendix C Job Performance Measure Form ES-C-1
------~
Worksheet Initial Conditions:
- 1. The Unit is operating at 100% power.
- 2. All radiation monitors are operable except R-27
- 3. VC Pressure is 1.5 psig
- Permit Number 120204
- Radiation Monitor Data:
o R-12 Current Reading 7.170 E-7 IJCi/cc o R-12 Current Alarm 1.5 E-6IJCi/cc o R-14 Current Reading 9.948E-7 IJCi/cc o R-14 Current Alarm 1.5E-5 IJCi/cc o R-15 Current Reading 1.32 E-6IJCi/cc o R-27 Current Reading OOS o R-27 Current Alarm OOS o Plant Vent Sample 1.85 E-5 IJCi/cc o Grab Sample Data is NOT available o Authorized Release Rate from IP-SMM-CY-001 3570 lJei/sec o Instantaneous Release Rate from IP-SMM-CY-001 7.0 E +4 IJCi/sec Plant Vent Flow 3.21 E+4 scfm (Obtained from PICS) Condenser Air In leakage 5.8 scfm Task Standard: . A VC Pressure Relief Gaseous Release Permit (3-S0P-WDS 013 Attachment 1) is correctly filled out. Required Materials: Calculator General
References:
3-S0P-WDS-013. Initiating Cue: You are the FSS and the SM has directed you to review a manual VC Pressure Relief Gaseous Release Permit in accordance with 3 SOP-WDS-013. Time Critical Task: No Validation Time: 25 Min 2 of 14
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-S0P-WDS-013 Review Precautions and Limitations CUE: All P&L are satisfactory to continue.
Comment:
- 2. Performance Step: Review NOTES before Step 4.1.1 Standard: Reviews Notes Comment:
- 3. Performance Step: Record VC Pressure Helief as system to be released on Attachment 1 Standard: Checks "VC Pressure Relief' entered on Attachment 1 Correct Comment: Procedure Step 4.1.1
- 4. Performance Step: Record current date/time on Attachment 1 Standard: Checks current date/time on Attachment 1 Correct Comment: Procedure Step 4.1.2 3 of 14
Form Performance Information (Denote critical steps with a check mark ;J)
- 5. Performance Step: ASSIGN permit number and RECORD on Attachment 1.
Standard: Checks Permit Number entered on Attachment 1. Given in Initial Conditions Correct Comment: Procedure Step 4.1.3
- 6. Performance Step: Record current VC pressure on Attachment 1 Standard: Checks 1.5 psig on Attachment 1. Given in Initial Conditions Correct Comment: Procedure Step 4.1.4
- 7. Performance Step: VERIFY one of the following conditions satisfied:
- R-12 operable.
- R-11 operable AND a VC noble gas sample is obtained.
Standard: R-12 is operable. Given in Initial Conditions Comment: Procedure Step 4.1.5
- 8. Performance Step: Determine VC Noble Gas concentration using one of the following methods
- R-12 reading (j..I.Ci/cc)
Standard: Determines R-12 reading is available Comment: Procedure Step 4.1.6 4 of 14
~ppend~ _ _ _ _ _ _ _ _ _ £,.~a",,-ge_5_ _ _ _ _._ _ _ _ _ F_or_m _ _E_S_-C_-_1_ Performance Information (Denote critical steps with a check mark ,J)
'" 9. Performance Step: If using R-12, THEN circle "R-12 Monitor" and Enter the following on Attachment 1
- R-12 reading for Concentration of Nobel Gas (J.LCi/cc)
- NA for Sample #, Date, and Time for Grab Sample Standard: Checks "R-12 Monitor" Circled Correct Observes incorrect data entered for Concentration of Noble Gas 9.948E-7 J.l.Ci/cc entered CRITICAL Should have entered 7.170 E-7 #lCilcc Observes "NA" for Sample #, Date and Time NOT CRITICAL Comment: Procedure Step 4.1.8
'" 1O. Performance Step: Determine calculated release rate ( R ) ...Ci/sec and record on Attachment 1 Standard: Observes Calculation performed correctly using incorrect numbers R = (2.83E+05 cc/sec)
- 9.948E-7 IJCi/cc R= 2.81 E-1 CRITICAL.
Correct Calculation should be 2.02E*1 Comment: Procedure Step 4.1.9 5 of 14
. Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/)
- 11. Performance Step: Determine available release rate D in IJCi/sec with R-27 OOS and R-14 In Service (given in Initial Conditions)
Standard: Checks calculation correct (2.356 E 9.948E-7)
- 3.21 E+4
- 472
= 3.55SE+3 IJCi/sec Comment: Procedure Step 4.1.10.2 "'112. Performance Step: Record Discharge Monitor on Attachment 1 Standard: Checks R-14 on Attachment 1 Observes R-27 entered on Attachment 1 INCORRECT Comment: Procedure Step 4.1.11
- 13. Performance Step: Record Actual Alarm Setpoint on Attachment 1 Standard: Checks 1.SE-S IJCi/sec Correct Comment: Procedure Step 4.1.12
- 14. Performance Step: If R is less than 0 THEN record NA for calculated alarm setpoint on Attachment 1 Standard: Checks NA on Attachment 1 Correct Comment: Procedure Step 4.1.13 6 of 14
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 15. Performance Step: If calculated release rate R is greater than available release rate D THEN obtain authorization for higher release rate.
Standard: Determines R is less than D and authorization is not required Comment: Procedure Step 4.1.14
- 16. Performance Step: If R-27 is operable THEN enter an alert setpoint at a value below current alarm setpoint at CRS discretion and record on Attachment 1.
Standard: R-27 is not operable (Given in Initial Conditions) Comment: Procedure Step 4.1.15
- 17. Performance Step: If R-12 is operable THEN determine R-12 calculated auto closure setpoint and record on Attachment 1 Standard: Checks R-12 Setpoint == 7.0E4
- 3.53E-6
== 2.471 E-1 Correct Comment: Procedure Step 4.1.16.1
- 18. Performance Step: IF necessary THEN adjust R-12 auto closure setpoint to less than or equal to calculated value Standard: Checks setpoint adjustment is NOT necessary Comment: Procedure Step 4.1.16.2 7 of 14
Form Performance Information (Denote critical steps with a check mark v)
- 19. Performance Step: When permit is complete, THEN record NA for the following:
- Release path valve alignment verification
- Volume
- Activity
- Iodine 131 Activity
- Calculated Alarm Setpoint
- Emax
- E
- RCV-014 setting Standard: Checks NA on Attachment 1 Comment: Procedure Step 4.1.17 Terminating Cue: JPM Complete 8 of 14
Kev: lH GASEOUS WASTE RELEASES Page 37 of 56 ATTACHMENT 1, GASEOUS WASTE RELEASE PERMIT FORM (Page 1 of 1) Tank! \JC~" Current System (1) Relie( OateJTime (2)-=.:I~~~_ _. C"ffMol1i., Permit No. (3) I~l>~+ rl Date Time 1.17 C- I Concentration of Volume (4) NA fe Initial Pressure (5)-l1t..:..'t).:.-__ psig Noble Gas (C)(6'~~~~;Z::-_IJ.1CilCC Grab Sample:(7) Sample # JJ~ Date tJl Time t-lJ.. Activity (A)(8)_---=N~~~_ _ _ _, Noble Gas Iodine 131 Activity (8a)_..;;.;.N::..Jfl.'-'=--_-rJ.1Cilcc VC Purge Only Ci/secAvailable Release Rate (0)(10) 3'S~-5 ~Ci/sec Discharge Monitor (11 ),~..a~...IIE--""':"'=--=-"';" Actual Alarm Setpoint (12)~/~'S E" 4- J.1Ci/sec Calculated alarm setpoint (13) IJJI-. J.1Cilsec Alert setpoint (14) N~ J.1Ci/sec R-12 Auto Closure/Alarm Setpoints: Calculated (15) J 14-1 e. .. , J.1Ci/cc Actual (16) ,.')';; .. ~ J.1Ci/cc IF discharge monitor is OOS, THEN COMPLETE the following:
- Monitor (17) N~ placed out service @ _..;.c~~A.____ __---=N..z...;:..~::...-. __
Date Time
- Vent Sample:(18) Sample # tl). Date_--L::lNu:~=--_ _ Time tJ" Results (19)~~;....~_-rJ.1Ci/C(
(Noble Gas)
- Vent flow rate (20) t.1 A, cfm Continuous Release Rate (CR)(21 )_______N:...::..!./)....:..-_ _,J.1Ci/seC Release Calculations verified by (22),_----'N""'--~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Release Path Valve Alignment Verified (23),_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ CRS/SM Discharge Authorized (24)____ ===-=----- Release Start (25},____- CRS/SM Date Time Final Pressure (26)_ _ _ _ _ _psig Release Stop (27)_---=_ _ Date Time Calculations Results: S (28) _ _ _ __ Emax (29)_ _ _ _ _ _ _fe/min E(30)_ _ _ _ _ _tr/min RCV-014 Setting (31) _ _ _ _%open Comments:(32)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~
~SEOUS WASTE RELEASES No: 3-S0P-WDS-013 Rev: 28
~
I I1 Page 43 of 56 ATTACHMENT 7, CALCULATIONS FOR R-14 IN PLACE OF R-27 (Page 1 of 1) Calculating An R-14 Alarm Setpoint Sp = _ARR 357{) ~II'5t!'C (FR .. 472) 3..Jt 110 .,e{ft\ x: t./7.l SP :: alarm setpoint for R-14 (in ~tCi/cc) 2. ~5 ~ ID -4 ,,uCt'!CC, ARR = authorized release rate (in /-lei/sec), from, IP-SMM-CY-001, Radioactive Effluents Program FR =plant vent flow rate (in ft3/min) 472:: (28,317 cC/ft3 ) / (60 sec/min) Available Release Rate (0) D :: (D14) * (FR) * (472) (!l.~tre'4)"(3d Itt4)~ (4-13-) D = available release rate (in !-lCi/sec)
- 3 ~/itC D14:: difference between current alarm setpoint and current R-14 reading (in !-lCi/cc)
- J,5t.i(.-q ::. (;J. ~5'E ... 4 -- 't .tl46 ~>'1)
FR = plant vent flow rate (in ft3/min) I ~"4- \' I\. << r",Jd\&'f\.,) 472:: (28,317 cC/ft3 ) / (60 sec/min) ANSWER KEY 10 of 14
Appendix C Page 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No, Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _,_ _ __ 11 of 14
Initial Conditions:
- 1. The Unit is operating at 100% power.
- 2. All radiation monitors are operable except R-27
- 3. VC Pressure is 1.5 psig
- Permit Number 120204
- Radiation Monitor Data:
o R-12 Current Reading 7.170 E-7lJCi/cc o R-12 Current Alarm 1.5 E-H lJCi/cc o R-14 Current Reading 9.948E-7 lJCi/cc o R-14 Current Alarm 1.5E-5 lJCi/cc o R-15 Current Reading 1.32 E-6 lJCi/cc o R-27 Current Reading OOS o R-27 Current Alarm OOS o Plant Vent Sample 1.85 E-5lJCi/cc o Grab Sample Data is NOT available o Authorized Release Rate from IP-SMM-CY-001 3570 !-ICi/sec o Instantaneous Release Rate from IP-SMM-CY-001 7.0 E +4 lJCi/sec Plant Vent Flow 3.21 E+4 scfrn (Obtained from PICS) Condenser Air In leakage 5.8 scfm Initiating Cue: You are the FSS and the SM has directed you to review a manual VC Pressure Relief Gaseous Release Permit in accordance with 3-S0P-WDS-013. Make any necessary corrections.
No: 3-S0P-WDS-013 Rev: 28 GASEOUS WASTE RELEASES 37 of 56 ATTACHMENT 1, GASEOUS WASTE RELE:ASE PERMIT FORM (Page 1 ()f 1) Tank! \Jt ~')~" Current System (1) fgrl,', ( Date/Time (2)1~ _CI.U'~ 1'IM' Permit No. (3) 1!)t>~4-Date Time Concentration of Volume (4 )--=-N...::.1A'-'--__ft 3 Initial Pressure (5),.......!..:.I,~_"'_____ psig Noble Gas (C)(6)~.q4~ 6 ..1 J.1Ci/cc Grab Sample:(7) Sample #--:..tJ;;.:A.~__ Date ~A Time t-l" O~12 ~~ Activity (A)(8)_ _N!.:!.C"~ ____ ~lCi Noble Gas Iodine 131 Activity (8a) tJ ~ f.\.Ci/cc VC Purge Only Calculated Release Rate (R)(9) ~Bf I!'" , IlCi/sec Available Release Rate (0)(10) 3'5',51 I1CiJsec Discharge Monitor {11 )_-=f(=--J"'---f.1_ _ __ Actual Alarm Setpoint (12)~~"5 ,; "" + }lCifsec Calculated alarm setpoint (13) tJ~ ~tCi/sec Alert setpoint (14) IS t\ f.\.Cilsec R-12 Auto Closure/Alarm Setpoints: Calculated (i5) 3.. L(1 e." , ~!Ci/cc Actual (16) II")~ -£, ~lCi/cc IF discharge monitor is 008, THEN COMPLETE the following:
- Monitor (17) t-J~ placed out service @ _...:.tJ.:::....:...;~~___ _ __N!..1..:'A.~_
Date Time
- Vent Sample:(18) Sample # 1\\). Date_-,NL.:L..:::~--'_ _ Time tJ A. Results (19) tJftr ).lCi/cc
{Noble Gas}
- Vent flow rate (20) "~ cfm Continuous Release Rate (CR)(21),_ _.....;N:...!...!A~_ _ f.\.Cj/SeC Release Calculations verified by {22),_-...:"'-=-.c..~_ _ _ _,_ _ _ _ _ _ _ _ _ _ _ _ _ __
Release Path Valve Alignment Verified \-~J _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ CRSfSM Discharge Authorized (24),_ _ _ _ _ _ _ __ Release Start (25) CRS/SM Date TIme Final Pressure (26) psig Release Stop (27) Date Time Calculations Results: 8 , __ ,_ _ _ _ __ Emax (29) fe/min E(30)_ _ _ __ ft3/min RCV-014 Setting (31 % open
,-------------------,-----------------*----*-*****-1 No: 3-S0P-WOS-013 Rev: 28 GASEOUS WASTE RELEASES Page 43 of 56 ATTACHMENT 7, CALCULATIONS FOR R-14 IN PLACE OF R*27 (Page 1 of 1) Calculating An R-14 Alarm Setpoint J.~st.~fo"'f)lC.lte Sp = ARR (FR 1< 4(72) SP =alarm setpoint for R-14 (in ~LCilcc) ARR ;;;; authorized release rate (in f..lCi/sec), frcm, IP-SMM-CY-001, Radioactive Effluents Program
~ -3io ,uti I ~e FR =plant vent flow rate (in ft 3fmin) 472 = (28,317 cclft3) I (60 sec/min)
Available Release Rate {O} o = (014) " (FR) * (472)
~55~f ..3= (~.'-lt- ~ ..'-I>>)((~, .JI f"~))I.' ('" 1~ )
o= available release rate (in f..lCi/sec)
~.~ 5-$ E"'?>
014 =difference between current alarm setpoint and current R-14 reading (in J-tCi/cc)
~.~+(, ~ -'-/ ;: ~ ~'5L E. ...L{)- (t:t -'1' t.I f ~~ .. ,)
FR::: plant vent flow rate (in fe/min)
~.~, E... ,.,.
472 = (28,317 cC/ft3) I {60 seclmin)
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point 3 Task No: 1500010532 Task
Title:
Classify Emergency Events requiring Emergency Plan Implementation 1940012438 Job Performance Measure SRO KIA
Reference:
SRO-4.4 No: Admin~5
~~~~--------
Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance x Actual Performance Classroom x Simulator Plant --------- READ TO THE EXAMINEE 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. 1 of 8
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initial Conditions: A reactor trip occurred approximately 18 minutes ago after 108 days @ 100% reactor power. The trip was automatic due to a loss of 31 Instrument Bus while N41 was DOS for repair. 33 EDG is tagged out for air-start motor replacement following a failed surveillance. A loss of offsite power occurred during the auxiliary power transfer. 32 EDG has failed to start. The Control Room Supervisor has completed the immediate actions of ECA-O.O and the following conditions exist according to the brief:
- 31 EDG is operating. 2AT3A tie breaker will not close due to a tripped 3A normal supply breaker with its amber light illuminated.
- The Con Ed DO has reported a grid stability problem due to severe weather to our South and power should be restored to the region within the hour
- 33332L and 33332M are ODS and the Buchanan Ring Bus is de-energized
- 31 Instrument Bus has been reenergized on MCC-34
- The Conv NPO and the FSS are working to start the 32 EDG
- The NPO is trying to start the Appendix R EDG
- 32 ABFP is feeding all SGs adequately
- RCS pressure is 2050 psig and increasing
- I&C is investigating the cause of the :3A Bus problem
- Natural Circulation flow has been verified in the RCS METEOROLOGICAL CONDITIONS:
Wind Speed: 2.8 meters/second Wind Direction: 110 degrees @ 10 meters Stability Class: o Task Standard: Event properly classified and Part 1 form correctly completed within the required time. Required Materials: General
References:
IP-EP-120, Emergency Classification IP-EP-210, Central control Room IP-EP-410, Protective Action Recommendation EAL Wall Chart EAL Technical Basis Document 2 of 8
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The Shift Manager has become ill. You are the CRS and you must perform the duties of the Emergency Director until a replacement SM can arrive on site. This is a Time Critical Job Performance Measure You must Classify the event and Complete the NYS Part 1 form. Inform the examiner when you have classified the event. Inform the examiner when you have completed the Part 1 form. Time Critical Task: Yes Validation Time: 25 3 of 8
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 1. Performance Step: Obtain Correct Procedure Standard: Obtains IP-EP-120 Comment: CUE: Candidate will be given all necessary procedure before the JPM is started.
Record the time the JPM is started: _ _ _ _ _ _ _ __ '" 2. Performance Step: Evaluate Plant Status to determine if GE, SAE, Alert, or NUE applies. Determine the highest classification and make declaration. Standard: Determines Event is SAE per EAL 6.1.4 TIME CRITICAL - Must complete this step within '15 minutes of start of JPM. Comment: Record the Time Declaration Made: _ _ _ _ _ _ _ __ '" 3. Performance Step: Complete and approve "New York State Radiological Emergency Data Form", IP-EP-115 EP-1 Standard: Completes all necessary information on the form and signs the form TIME CRITICAL - Must complete this step within 15 minutes of Time of Declaration (JPM step 2) Comment: Record the Time Form is complete: _ _ _ _ _ _ _ __ 40fa
Performance Information (Denote critical steps with a check mark -Y)
- 4. Performance Step: Refer to procedure IP-EP-210, Attachment 9.1.
Standard: Refers to Attachment 9.1 Comment:
- 5. Performance Step: Initiate County, State and NRC Notification per IP-EP-115, Form EP-6.
Standard: Request a communicator Comment: CUE: Acknowledge the communicat()r is prepared to make notifications Terminating Cue: JPM Complete 5 of 8
_A-I..Jppc:....;e:..:..n.:..:.d=ix"--C=--_ _ _~_ _ _ _ _ _~P~age 6 Form ES-C-1 New YorK State lndi~n Point Energy Center RADIOLOGICAL EMERGENCY DATA FORM - PART 1 Notification #. _,_ ACTUAL EMERGENCY* at:. UNIT 2 9 BOTH UNITS Tpda'-l . _ . . ._. (Time)* Cu.rrentJine(24hrCIOCk)
- 2. . The Emergency Classification is:
Page 1 of 1 Form EP-1. Rev 3 6of8
VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __ 7 of 8
_.. . . .,._----_.. _. -_.-, -------.--------"~--<~
Appendix C Initial Conditions Form ES-C-1 Initial Conditions: A reactor trip occurred approximately 18 minutes a~lo after 108 days @ 100% reactor power. The trip was automatic due to a loss of 31 Instrument Bus while N41 was DOS for repair. 33 EDG is tagged out for air-start motor r,eplacement following a faHed surveillance. A loss of offsite power occurred during the auxiliary power transfer. 32 EDG has failed to start. The Control Room Supervisor has completed the immediate actions of ECA-O.O and the following conditions exist according to the brief:
- 31 EDG is operating. 2AT3A tie breaker will not close due to a tripped 3A normal supply breaker with its amber light illuminated.
- The Con Ed DO has reported a grid stability problem due to severe weather to our South and power should be restored to the region within the hour
- 33332L and 33332M are ODS and the Buchanan Ring Bus is de-energized
- 31 Instrument Bus has been reenergized on MCC-34
- The Conv NPO and the FSS are working to start the 32 EDG
- The WF NPO is trying to start the Appendix R EDG
- 32 ABFP is feeding all SGs adequately
- RCS pressure is 2050 psig and increasing
- I&C is investigating the cause of the 3A Bus problem
- Natural Circulation flow has been verified in the RCS METEOROLOGICAL CONDITIONS:
Wind Speed: 2.8 meters/second Wind Direction: 110 degrees @ 10 meters Stability Class: D Initiating Cue: The Shift Manager has become ill. You are the CR.S and you must perform the duties of the Emergency Director until a replacement SM can arrive on site. This is a Time Critical Job Performance Measure You must Classify the event and Complete! the NYS Part 1 form. Inform the examiner when you have classified the event. Inform the examiner when you have COml)leted the Part 1 form.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0000420501 Task
Title:
Align Low-Head 81 Flow Path for Hot Leg Recirculation 000011A111 Job Performance Measure SIMA KJA
Reference:
RO- 4.2 SRO- 4.2 No: Examinee: NRC Examiner: Facility Evaluator: Date: Method of testi~ Simulated Performance Actual Performance x --- Classroom Simulator x Plant READ TO THE EXAMINEE 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. Initial Conditions:
- It is 5 hours after a large break LOCA with loss of offsite power.
- The SI System is aligned for Cold Leg Recirculation per ES-1.3
- Transfer to hot leg recirculation is desired.
Task Standard: The SI System in aligned for Hot Leg Recirculation with 32 and 33 HHSI Pumps Operating. Required Materials: General
References:
3-ES-1.4 Transfer to Hot Leg Recirculation Initiating Cue: You are the ATC and the CRS has directed you to transfer to Hot leg Recirculation in accordance with ES-1.4 steps 1 through 11. Time Critical Task: No Validation Time: 20 1 of 13
Appendix G _ _ _ _ _ _ _ _ _ _ Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,J)
- 1. Performance Step: Obtain correct procedure Standard: Obtain current revision of 3-ES-1.4 Comment:
- 2. Performance Step: Review Caution and Note before Step 1 Standard: Reviews Caution and Note Comment:
- 3. Performance Step: CHECK Low-Head Recirc flow Standard: Observe flow on FI-946A through D on Panel SBF-2 Comment: Procedure Step 1
- 4. Performance Step: Review Note before Step 2 Standard: Reviews Note Comment:
2 of 13
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V) '" 5. Performance Step: Align Non-BIT Hot Leg Injection Valves:
- Close 856J and 856H
- Open 856B Standard: Rotate switches for 856 J and H to CLOSE Rotate switch for 856B to OPEN All above switches are on Panel SBF-2 Comment: Procedure Step 2 The sequence of operation of the above valves is important.
'" 6. Performance Step: Align BIT Hot Leg Injection Valves:
- Close 856E and 856C
- Open 856G Standard: Rotate switches for 856 E and C to CLOSE Rotate switch for 856G to OPEN All above switches are on Panel SBF-2 Comment: Procedure Step 3 The sequence of operation of the above valves is important.
- 7. Performance Step: Check HHSI Hot Leg Injection valve status Standard: Verify 8568 or 856G OPEN Comment: Procedure Step 4 3 of 13
Form ES-C-1 Performance Information (Denote critical steps with a check mark ")
- 8. Performance Step: Dispatch Nuclear NPO to deenergize the following valves
- 856G
- 856E
- 856C
- 856J
- 856H
- 856B Standard: Contact NPO using radio and direct deenergizing valves CUE: Acknowledge as Nuclear NPO to Deenergize valves Comment: Procedure Step 5 NOTE: Booth Operator Deenergize valves listed above
- 9. Performance Step: Check Recirc Pumps only one running Standard: Observes both Recirc Pumps Operating.
Places one Recirc Pump in Trip Pull Out Comment: Procedure Step 6.a 4 of 13
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 10. Performance Step: Dispatch NPO to verify the following valves CLOSED
- IV-1403
- IV-1447
- IV-1448
- IV-1464
- IV-1465
- IV-1479 Standard: Contact NPO using radio and direct verifying valves CLOSED CUE: Acknowledge as Nuclear NPO. Report "All Valves are Closed".
Comment: Procedure Step 6.b.1
- 11. Performance Step: Ensure the following valves OPENED
- SI**MOV*850A
- SI-MOV-850C Standard: Indication only available on SBF-2 Candidate may contact Contact NPO using radio and direct verifying valves OPENED CUE: If candidate calls the NPO, Acknowledge as Nuclear NPO Comment: Procedure Step 6.b.2
- 12. Performance Step: Ensure the following valves are OPEN
- 888A
- 888B Standard: Rotate switches for above valves to OPEN position Both of the valves listed above are located on Panel SBF-1 Comment: Procedure Step S.c 5 of 13
ES-C-1 Performance Information (Denote critical steps with a check mark ."j)
- 13. Performance Step: Ensure the following valves are OPEN
- 1869A
- 1869B
- 1835A
- 1835B
- 1852A
- 1852B Standard: Verify valves listed abc)ve are opened All of the valves listed above are located on Panel SBF-1 Comment: Procedure Step 6.c
- 14. Performance Step: Ensure the following valves are OPEN
- 1869A
- 1869B
- 1835A
- 1835B
- 1852A
- 1852B Standard: Verify valves listed above are opened Rotate switch for 1869A to Open All of the valves listed above are located on Panel SBF-1 Comment: Procedure Step 6.c
- 15. Performance Step: Place SI Pump Suction Low Pressure Alarm Block switch to UNBLOCK Standard: Rotate Switch to UNBLOCK on Panel SBF-1 Comment: Procedure Step 6.d 6 of 13
Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 16. Performance Step: Check SI Pump Suction Low Pressure Alarm on Panel SBF-1 CLEAR Standard: Observes alarm not illuminated Comment: Procedure Step 6.e
'" 17. Performance Step: Place Safety Injection Recirc Switch 6 to OFF position Standard: Rotate switch to OFF Comment: Procedure Step 6.f
- 18. Performance Step: Start High Head Safety Injection Pump 31 Standard: Observes that 31 HHSI Pump does not start, then places switch in TRIP PULLOUT Go to Step 8 Comment: Procedure Step 7.a
~ 19. Performance Step: Start High Head Safety Injection Pump 33 Standard: Rotate switch for 33 HHSI pump to Start Comment: Procedure Step 8.a 7 of 13
___________________~P~a=g~e~B~_________________F~o~rm~E~S_-C~-~1 Append_ix_ C Performance Information (Denote critical steps with a check mark --J)
- 20. Performance Step: Check BIT header loop injection flow Standard: Verify stable flow on Loop 2 Comment: Procedure Step B.b
- 21. Performance Step: Check HHSI pump status Standard: Observes 33 HHSI pump running Comment: Procedure Step 9
- 22. Performance Step: Check status of 31 and 33 HHSI pumps Standard: Verify only 33 HHSI pump is running Comment: Procedure Step 9.b
- 23. Performance Step: Check HHSI pump 32 status Standard: Verify 32 HHSI pump SHUTDOWN Comment: Procedure Step RNO 9.b.1 B of 13
_____________________Page9 _A~p~p_e_n_d_ix_C Form ES-C-1 Performance Information (Denote critical steps with a check mark "./>
- 29. Performance Step: Check control switches for non-running HHSI pumps in Trip Pullout Standard: Verifies 31 HHSI pump switch in Trip Pullout Comment: Procedure Step 9.d 9 of 13
Form Performance Information (Denote critical steps with a check mark ")
- 30. Performance Step: Check high-head loop injection flows established in at least 1 header Standard: Observes flow in both loops on FI-925 and FI-982 Comment: Procedure Step 9.e
'\J 31. Performance Step: Terminate Low Head Recirculation Standard: Rotate switches for the following to CLOSE
- 746 (Not Critical already closed)
- 747
- 899A
- 899B The switches above are located on Panel SGF Comment: Procedure Step 10 Terminating Cue: JPM Complete 10 of 13
Appendix C Page 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __ 11 of 13
Appendix C Simulator Setup Form ES-C-1 Reset Simulator to any 100% IC Insert Malfunction MAL-RCS001B; 100%; No Ramp or Time Delay (Loop 2 RCS Cold Leg Rupture) Perform actions of E-O, RO-1, E-1 and ES-1.3. Insert Malfunction MAL-SIS004A; Trip; No Time Delay. 31 SIP fails to start (trips). 12 of 13
- '* r
- 1 ) .,
Appendix C Initial Conditions Form Initial Conditions:
- It is 5 hours after a large break LOCA with IClss of offsite power.
- The SI System is aligned for Cold Leg Recirculation per ES-1.3
- Transfer to hot leg recirculation is desired Initiating Cue:
You are the ATC and the CRS has directed you to transfer to Hot Leg Recirculation in accordance with ES-1.4 steps 1 through 11.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0100180431 Task
Title:
Respond to a Pressurizer Low Pressure Alarm 000027A101 Job Performance Measure SimS KIA
Reference:
- 4.0 SRO-3.9 No:
Examinee: NRC Examiner: Facility Evaluator: Date: Method ofJ~~tl~ Simulated Performance Actual Performance Classroom Simulator x Plant READ TO THE EXAMINEE 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. Initial Conditions:
- The plant is operating at 100% power
- No Equipment is Out of Service Task Standard: Pressurizer pressure stable, reactor tripped with 33 and 34 RCPs tripped.
Required Materials: None General
References:
3-ARP-003 Initiating Cue: You are the ATC. Respond to changing plant conditions or events. Time Critical Task: No Validation Time: 1 of 7
Appendix C ~_ _P_a..... g'_e_2_ _ _ _ _ _ _ _ _ _ _ Form ES-C-1 Performance Information (Denote critical steps with a check mark -,J) NOTE: Candidate may diagnose failed open Spray Valve at any time during this JPM. The exact order of actions before the Reactor Trip is not important, and they may be performed in any order. The reactor must be tripped before the Reactor Coolant Pumps are tripped.
--------~.----
- 1. Performance Step: Acknowledge Pressurizer Low Pressure Alarm and refer to ARP Standard: Observe alarm and retrieve ARP from holder Comment: Candidate may recognize pressure lowering before alarm annunciates.
- 2. Performance Step: Verify alarm by observing PRZR Pressure Standard: Observe pressure decreasing on all 4 channels Comment: ARP Step 3.1
- 3. Performance Step: Determine if Channel or Controller Failure has occurred Standard: Determine NOT instrument failure (All 4 channel indications decreasing)
Determine NOT a controller failure (Controller output calling for heaters. Pressurizer heaters will eventually energize). Comment: ARP Step 3.2 20f7
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 4. Performance Step: IF the Pressurizer heaters or sprays are NOT operating properly, THEN PLACE Pressurizer Pressure Master Controller in MANUAL and ATTEMPT to establish RCS pressure at 2235 psig.
Standard: Transfer controller to Manual (T-bar up) and output adjusted to Heaters (Left of nUll) Comment: ARP Step 3.3 -~ ....-- - --------------------------
- 5. Performance Step: If Pressure is low, then check:
- PORVs Closed
- PRZR Spray and Aux Spray Closed
- PRZR Heaters Energized Standard: Identifies Pressurizer Pressure is low and one Spray Valve is Open Comment: ARP Step 3.4
- 6. Performance Step: If PRZR PORV are NOT closed THEN close PORVs Standard: Observes PORVs are closed and no action is required Comment: ARP Step 3.4.2
- 7. Performance Step: If Spray Valve(s) are not closed Close Spray Valve in Manual Standard: Transfer controller to Manual (T-bar up) and output adjusted to Close (Left)
Comment: ARP Step 3.4.3.1 30f7
Form ES-C-1 Performance Information (Denote critical steps with a check mark -.J)
- 8. Performance Step: IF PRZR Spray Valve does NOT close, THEN CLOSE PRZR Spray Valve by removing power fuse from back of Foxboro controller for affected PRZR Spray Valve.
Standard: Observes Spray Valve NOT Closed and removes controller from Flight Panel. When controller is removed, then fuse is removed from back. Comment: ARP Step 3.4.3.2 '\J 9. Performance Step: If Spray Valve(s) can NOT be closed, Then TRIP the Reactor Standard: Identifies spray valve will not close; depresses the Rx TRIP button on Panel FCF Comment: ARP Step 3.4.3.3.a '\J 10. Performance Step: Trip 33 and 34 Reactor Coolant Pumps Standard: Verifies Reactor Tripped then rotates RCP switches to STOP position Comment: ARP Step 3.4.3.3.b
- 11. Performance Step: Go To E-O Reactor Trip or Safety Injection Standard: Observes conditions to verify reactor tripped Comment: ARP Step 3.4.3.3.c Terminating Cue: ..'PM Complete NOTE: If a Safety Injection occurs during the performance of this JPM, it is likely a failure. The candidate's progress through the required actions will determine actual pass or fail grade.
40f7
Appendix C Page 5 Form ES-C-1
------~~----------------------
VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __ 5 of 7
~pendixC Simulator Setup Form ES-C-1 Reset Simulator to any 100% Ie Insert Malfunctions: IOn Action Description ! Event i 1 . Insert override SWI-RCS019D to 3-PC-455G AUTO SIGNAL(8) On trigger 1 PRESSURIZER SPRAY FLOW CONTROLLER 1 setjeps935f=t On Trigger 1 I
- 1 Insert override SWI-RCS019E On 3-PC-455G SLOW CLOSE (9)
Trigger 1 PRESSURIZER SPRAY FLOW CONTROLLER
- 1 Insert override SWI-RCS019F On 3-PC-455G FAST CLOSE (10)
- Tngger 1 PRESSURIZER SPRAY FLOW CONTROLLER
- 1 Insert malfunction MAL REACTOR TRIP BREAKERS FAIL TO RPS002A to ALL FAIL OPEN (AUTO FAILURE) 1 Insert malfunction MAL PZR SPRAY VLV 455A AUTO PRS002A to 50.00000 in 120 On FAILURE Trigger 1 Run Schedule JPM Sim B.sch to insert above malfunctions/actions. This schedule must be run each time before the JPM is given.
6 of 7
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The plant is operating at 100% power
- No Equipment is Out of Service Initiating Cue:
You are the ATC. Respond to changing plant conditions or events.
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point 3 Task No: 003*010*04*01 Task
Title:
RCP #1 Seal Failure Actions
--------.--~------~~,-.~- -------
KIA
Reference:
003000A2.01 Job Peliormance Measure No: Sim-C RO - 3.5 SRO - 3.9 Examinee: Facility Evaluator: Date: ~ethod of testing: Simulated Performance Actual Performance x Classroom Simulator X Plant - - READ TO THE EXAMINEE 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. Initial Conditions: Plant is at indicated power level. A malfunction is in progress on 34 RCP. The CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Pump Malfunction. Task Standard: AOP-RCP-1 actions completed. Required Materials: 3-AOP-RCP-1 General
References:
Initiating Cue: You are the ATC and the CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Malfunction for the indicated malfunction on 34 RCP. Time Critical Task: No Validation Time: 10 minutes SIM-D rev. 0 1 of 8
Appendix C 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark)
- 1. Performance Step: Determine if reactor trip is required:
- Checks motor winding temp> 250°F with Tave > 540°F
- Checks upper or lower motor bearing temp> 200°F
- Checks shaft vibration> 20 mils
- Checks shaft vibration> 15 mils and increasing
- Checks Frame vibnation > 5 mils
- Checks Frame vibration> 3 mils and increasing
- Checks seal delta-p < 200 psid
- Checks seal inlet temp> 225°F
- Checks seal outlet temp> 235°F Standard: Determines reactor trip required goes to step 4.2 Comment: Procedure Step 4.1
- 2. Performance Step: Are Reactor Trip Breakers Closed Standard: Observes red lights illuminated - Reactor Trip Breakers are closed Comment: Procedure Step 4.2
..J 3. Performance Step: Trip the reactor Standard: Reactor manually tripped CUE: CRS directs the rest of the crew to perform E-O immediate actions. You are to continue with the subsequent actions of AOP-RCP-1. Comment: Procedure Step 4.3 ..J 4. Performance Step: Stop 34 Reactor Coolant Pump Standard: Places 34 RCP Control Switch to stop. Comment: Procedure Step 4.4 SIM-D rev. 0 2 of 8
Performance Information (Denote critical steps with a check mark)
- 5. Performance Step: Initiate E-O, Reactor Trip or Safety Injection Standard: E-O initiated CUE: CRS directs the rest of the crew to perform E-O immediate actions. You are to continue with the subsequent actions of AOP-RCP-1.
Comment: Procedure Step 4.5
- 6. Performance Step: 1MT RCP #1 seal inlet temperature is > 225°F the dispatch NPO to close CH-241 D 34 RCP Seal Injection Flow Control Valve Standard: Observes #1 seal inlet temperatures greater than 225 0 and dispatches NPO to ci<)se valve.
CUE: Acknowledge as NPO and report valve is closed Comment: Procedure Step 4.6 "7. Performance Step: If 33 or 34 RCP shutdown then close affected spray valve - Closes PC-455G Standard: Places controller PG-455G to manual and reduces output to 0 (closed)., Comment: Procedure Step 4.7
- 8. Performance Step Was RCP Shutdown due to #1 seal return flow> 6 gpm Standard: Determines RCP NOT secured due to High Seal Return Flow Comment: Procedure Step 4.8 SIM-D rev. 0 3 of 8
Appendix C 4 Form ES-C-1 Perf(nmance Information (Denote critical steps with a check mark)
- 9. Performance Step Was RCP Shutdown due to #1 seal return flow < 0.84 gpm and Seal Temperatures Increasing?
Standard: Determines RCP was secured due to Low flow and Increasing Seal Inlet temperature Comment: Procedure Step 4.10 '" 1O. Performance Step: IAAT :34 RCP has stopped rotating then manually close the seal return valve 2610 Standard: Observes flow stable at 20 - 30% on loop 34. 2610 closed by placing control switch on panel SAF to close. Comment: Procedure Step 4.23 NOTE: Stable Loop flow of 20 - 30 % is used to indicate the RCP has stopped rotating. This is due to reverse flow through a single loop with 3 remaining RCP running.
- 11. Performance Step: Are EOPs in Use Standard: Determines EOP are in use Goes to step 4.29 Comments: Procedure Step 4.24 and 4.25
- 12. Performance Step: When directed by the SM Return to procedure and step in effect.
Standard: Comments: SIM-D rev. 0 40f8
Appendix C 5 Form ES-C-1 Terminating Cue: JPM is Complete SIM-O rev. 0 5 of 8
Appendix C 6 Form ES-C-1
-~------------~----
VERIFICATION OF COMPLETION Job Performance Measure No. Sim Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: SIM-D rev. 0 6of8
Reset simulator to IC-11 The malfunctions below will simulate a failure closed of 34 RCP #1 Seal resulting in heating up of the water surrounding the pump bearing and out of the #1 Seal. Insert Malfunction:
- MAL-RCS013D Final Value 20% Ramp 10 Seconds (#2 seal failure)
- ANN-SAF-1-1 OFF (Reactor Coolant Pump Standpipe High Level)
- IND-RCS024D OFF #34 RCP Standpipe Level Off Normal Indicator Light
- IND-CVC015 Final Value 235 Ramp 90 Seconds (Seal Inlet Temp Increasing)
- IND-CVC016 Final Value 252 Ramp 90 Seconds (Seal Outlet Temp Increasing)
Reset Simulator to IC-155 SIM-D rev. 0 7 of 8
--.------------------------------ un Appendix C Initial Conditions Form ES-C-1 Initial Conditions: Plant is at indicated power level. A malfunction is in progress on 34 RCP. The CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Pump Malfunction. Initiating Cue: You are the ATC and the CRS has directed you to perform the actions of AOP-RCP-1, Reactor Coolant Malfunction for the indicated malfunction on 34 RCP. SIM-D rev. a 8 of 8
\ Appendix C Job Performance Measure Form ES-C-1 Indian Point 3 Task No: 0590060301 Facility: Place Main Feed Reg Valve Controllers in Automatic Task
Title:
059000A403 Job Performance Measure No: Sim D KIA
Reference:
RO-2.9 SRO-2.9 Examinee: NRC Examiner: Facility Evaluator: Date: .-----.~.-~.~.---- Method of testing: Simulated Performance Actual Performance x Classroom Simulator x Plant READ TO THE EXAMINEE 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. Initial Conditions:
- The plant is at 25% power
- 32 Main Boiler Feed Pump is in service
- 31 Main Boiler Feed Pump is in Standby
- SG Levels are being controlled using the Low Flow Bypass Valves
- Pre Job Discussion for this evolution has been completed
- Venting of Steam Flow Transmitters is NOT occurring
- All required Precautions and Limitations and Prerequisites of 3-S0P-FW 001 are satisfied Task Standard: 31 Main Feed Reg Valve in Automatic control.
Required Materials: None General
References:
3-S0P-FW-001 1 of 8
_ _ ** _ _ _ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _
- _ _ _ _ _ _ _ _ _c _ __
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are the ATC and the CRS has directed you to transfer 31 SG feed flow from the Low Flow Bypass Valve to the Main Feed Regulating Valve, in accordance with 3-S0P-FW-001, Main Feedwater System Operation, section 4.10.2. Time Critical Task: No Validation Time: 15 Minutes 2 of 8
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,f)
- 1. Performance Step: Obtain correct procedure Standard: Obtains current revision of 3-S0P-FW-001 Comment:
- 2. Performance Step: Observe CAUTION and NOTE before step 4.10.2 Standard: Reviews Caution and Note Comment:
- 3. Performance Step: Verify venting of stearn flow transmitters is NOT occurring.
Standard: Given in Initial Conditions Comment: Procedure Step 4.10.2."
- 4. Performance Step: Verify SG Level is slightly higher than 45% with steam flow and feed flow signals approximately equal Standard: Identify 31 SG level slightly higher than 45% and increase feed flow to 32, 33, and 34 SG by opening Low Flow Bypass Valve (Panel FBF)
Comment: Procedure Step 4.10.2.2 3 of 8
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -V)
- 5. Performance Step: Prepare MFRV for service by unseating the applicable MFRV using Manual Control Standard: Rotate large potentiometer on FCV 417 counterclockwise until an increase in feed flow is observed the rotate clockwise to close the valves. (Panel FBF)
Comment: Procedure Step 4.10.2.3 '.\j 6. Performance Step: Place 31 MFRV in AUTO Standard: Move controller toggle switch on FCV 417 controllers to left postion Comment: Procedure Step 4.10.2.4 V7. Performance Step: Adjust the associated low Flow Bypass Valve to lower feed flow to slightly less than steam flow Standard: Rotate large potentiometer on FCV 417l clockwise (Panel FBF) Comment: Procedure Step 4.1 0.2.5.a 4 of 8
~Qpendix C Page 5 Form ES-C-1 Perf,ormance Information (Denote critical steps with a check mark -V)
"J 8. Performance Step: When associated MFRV starts to OPEN then adjust the Low Flow Bypass Valve as needed to minimize overshoot Standard: Rotatf~ large potentiometer on FCV 417L counterclockwise when associated MFRV starts to open, (Panel FBF)
Comment: Procedure Step 4.10.2.S.b "J 9. Performance Step: Continue to adjust associated Low Flow Bypass Valve until it is fully closed Standard: Continue to Rotate large potentiometer on FCV 417L clockwise in small increments, (Panel FBF) Comment: Procedure Step 4.1 O.2.5.c "J 1O. Performance Step: Repeat JPM Steps 6-9 as desired Standard: Repeat steps to place MFRVs in Auto for as many MFRVs as examiner desires Comment: Terminating Cue: JPM Complete 5 of 8
Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: 6of8
Appendix C Simulator Setup Form ES-C-1 Reset Simulator to IC-9 Ensure 31 and 32 SG levels are greater than 45% Ensure 33 and 34 SG levels are less than 45% Reset Simulator to IC-156 7 of 8
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The plant is at 25% power
- 32 Main Boiler Feed Pump is in service
- 31 Main Boiler Feed Pump is in Standby
- SG Levels are being controlled using the Low Flow Bypass Valves
- Pre Job Discussion for this evolution has been completed
- Venting of Steam Flow Transmitters is NOT occurring
- All required Precautions and Limitations and Prerequisites of 3-S0P-FW 001 are satisfied Initiating Cue:
You are the ATC and the CRS has directed you tC) transfer 31 SG feed flow from the Low Flow Bypass Valve to the Main Feed Regulating Valve, in accordance with 3 SOP-FW-001, Main Feedwater System Operation, section 4.10.2.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0590100331 Task
Title:
Transfer Main feed to bypass feed during power reduction 059000A403 Job Performance Measure Sim-D KIA
Reference:
RO-(2.9) SRO (2JL No: Makeup Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom Simulator - - - - X --- Plant - - - - - - READ TO THE EXAMINEE 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. Initial Conditions:
- The plant is at approximately 25% power
- 31 Main Boiler Feed Pump is in service
- 32 Main Boiler Feed Pump is in Standby
- SG Levels are being controlled using the Main Feed Regulating Valves
- Pre Job Discussion for this evolution has been completed
- All required Precautions and Limitations and Prerequisites of 3-S0P-FW 001 are satisfied Task Standard: 31 SG Feed Control is transferred to Low Flow Bypass Control in accordance with 3-S0P-FW-1 .
Required Materials: None General
References:
3-S0P-FW-1 10f9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: Your are ATC and the CRS has directed you to transfer 31 SG feed flow from the Main Feed Regulating Valve to Low Flow Bypass control in accordance with 3-S0P-FW-001 section 4.15.2 Time Critical Task: None Validation Time: 20 20f9
ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 1. Performance Step: Obtain correct procedure Standard: Obtains 3-S0P-FW-001 Comment:
- 2. Performance Step: TRANSFER Steam Flow and Feedwater Flow Recorder inputs to narrow range transmitters Standard: Rotate Switches to Narrow Range Comment:Step Procedure Step 4.15.2 30f9
Appendix C Page 4 Performance Information (Denote critical steps with a check mark ;/) ...J 3. Performance Step: THROTTLE OPEN bypass FRVs: Standard: Rotate dial for FCV-417L counterclockwise to open 31 SG Bypass FW Reg Comment: Procedure Step 4.15.2.2
- 4. Performance Step: VERIFY MFW FRVs begin to CLOSE Standard: Obse'rve FCV-417 closing Comment: Top deviation meter should move to the left of null. The operator should rotate the large dial on FCV-417 clockwise to close to maintain "Null". This is not required by procedure.
Procedure Step 4.15.2.3 4 of 9
Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) "5. Performance Step: IF extended low power operation is anticipated, THEN PERFORM the following:
- One MBFP in Standby
- Verify MBFP Speed controller for remaining pump in manual
- Maintain FW Pressure greater than steam header pressure Standard: Obse:rves:
MBFP is in Standby Control for operating pump is in manual FW header pressure is greater than steam header pressure Comment: Procedure Step 4.15.2.3
- 6. Performance Step: WHEN MFW FRVs are fully Closed, THEN PERFORM the following
- Adjust controller setpoint dial to 0%
- Place each selector switch in Manual Standard: Rotate MFRV dial clockwise to 0 (Not Critical)
Place each selector switch to Manual Comment: Adjusting the setpoint is not critical. Placing the FRV in maual is critical to prevent reopening and potential overfill of SG. Procedure Step 4.15.2.5 50f9
_A_pL...1p_e_n_d_ix_C_ _ _ _ _ _ _ _ _~Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J)
..J 7. Performance Step: MAINTAIN SG levels at approximately 40 to 50% Narrow Range by adjusting bypass FRVs Standard: Rotate Low Flow Bypass valve controller as necessary to maintain SG level Comment: Procedure step 4.15.6 Terminating Cue: JPM Complete 60f9
_Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __ 70f9
--'A'-I:Jppc:.. :e:..:. n:.;;:;.d:.;:cix=--C=--_ _ _ _~_ _ _S::..:.:im.:. :. ::::.;ul=ator Setup Form ES-C-1 80f9
t ... II I ** n t Appendix C Initial Conditions
------~
Form ES-C-1 Initial Conditions:
- The plant is at approximatl31y 25% power
- 31 Main Boiler Feed Pump is in service
- 32 Main Boiler Feed Pump is in Standby
- SG Levels are being controlled using the Main Feed Regulating Valves
- Pre Job Discussion for this evolution has been completed
- All required Precautions and Limitations and Prerequisites of 3-S0P-FW 001 are satisfied Initiating Cue:
Your are ATC and the CRS has directed you to transfer 31 SG feed flow from the Main Feed Regulating Valve to Low Flow Bypass control in accordance with 3-S0P-FW-001 section 4.15.2
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point 3 Task No: 0220010131 Task
Title:
Start a Fan Cooler Unit Job Performance Measure No: SIM E Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom Simulator x Plant - - - - - READ TO THE EXAMINEE 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. Initial Conditions:
- The plant is at indicated power
- 31 - 34 Containment Fan Cooler Units (FCU) are in operation
- Breaker Maintenance is scheduled for 32 FCU
- Containment Temperature is 87.5°
- Service Water is properly aligned to all FCUs
- All Precautions and Limitations have been satisfied
- 35 FCU was secured 6 hours ago for breaker maintenance
- Motor Starting Frequency requirement have been verified.
Task Standard: 35 Fan Cooler Unit is operating. Required Materials: None General
References:
3-S0P-C8-010, Containment Recirculation Fan Cooler Unit Operations. 1 of 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: You are the BOP and the CRS has directed you to start 35 Fan Cooler Unit in accordance with 3-S0P-CB-010. Time Critical Task: None Validation Time: 10 Minutes 20f9
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,f)
- 1. Performance Step: Obtain correct procedure Standard: Obtain 3-S0P-CB-010 Comment:
- 2. Performance Step: Review NOTES before step 4.2.1 Standard: Review Notes Comment:
- 3. Performance Step: Verify motor starting requirements of 3-S0P-004A will be met for 35 FCU.
Standard: Given in Initial Conditions Comment: Procedure Step 4.2.'1 "4. Performance Step: Verify that the Fan Cooler Filter Unit Normal Inlet Dampers (A and B) for 35 Fan Cooler Unit are OPEN. Standard: Rotate CONT. RECIRC. UNIT NO. 35 FLOW VLV 1305 switch to OPEN. Observe Green Light OFF and red light ON. PaneISBF-2 Comment: Procedure Step 4.2.2
~~----~-----------~-
30f9
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ") "5. Performance Step: Verify that the Fan Cooler Filter Unit Normal & Incident Damper (Bypass Damper C) for 35 Fan Cooler Unit is OPEN. Standard: Rotate CONT. RECIRC. UNIT NO. 35 FLOW VLV 1306 switch to OPEN. Observe Green Light OFF and red light ON. Observe Containment Control Recirc Air Unit Valve Tripped alarm clear Panel SBF-2 Comment: Procedure Step 4.2.3
- 6. Performance Step: Review NOTE before step 4.2.4 Standard: Reviews NOTE Comment:
- 7. Performance Step: Verify that the Fan Cooler Filter Unit Incident Damper (Damper D) for 35 FCU is CLOSED.
Standard: Observe CONT. RECIRC. UNIT NO. 35 FLOWVLV 1307 switch in CLOSE and Green Light is ON Panel SBF-2 Comment: Procedure Step 4.2.4 4of9
_ _ _ _ _ _ _ _ _ _ _P~age 5 _A--'--'pp'--e_n_d_ix_C Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/)
- 8. Performance Step: Verify that the FCU starts by monitoring the current on the associated 480V bus.
Standard: Observe 480V bus amps for bus 6A Panel SHF CUE: A Spare RO will standby and observe bus 6A amps when the fan is started. Comment: Procedure Step 4.2.5
'" 9. Performance Step: Revie~w NOTE before step 4.2.5 Standard: Reviews NOTE Comment:
- 10. Performance Step: Start 35 Fan Cooler Unit Standard: Rotate Containment Recirc Fans Switch for 35 FCU to START. Observe green light OFF and Red Light ON Panel SBF-2 CUE: The spare RO reports and increase and then decrease in bus 6A amps.
Comment: Procedure Step 4.2.6 The CONTAINMENT RECIRC FAN MOTORS BEARING VIBRATIONS alarm on SBF-1 is expected to annunciate. Candidate should acknowledge this alarm 5 of 9
Appendix C ___ P..:ca"'-ge-"---'-6_ _ _ _ _ _ _ _ _~Fo.rm ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 11. Performance Step: If CONTAINMENT RECIRC FAN MOTORS BEARING VIBRATIONS alarms, THEN RESET the alarm using the reset pushbutton on Panel SBF-1 Standard: Depresses pushbutton on Panel SBF-1 Observer the alarm resets.
Comment: Procedure Step 4.2.7 Terminating Cue: JPM Complete 6of9
Appendix C Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: 7 of 9
~ppendixC Simulator Setup Form ES-C-1 This JPM can be run from virtually any simulator Initial Condition Ensure that 35 FCU is secured Ensure Dampers AlB and C are closed for 35 FCU 8 of 9
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The plant is at indicated power
- 31 - 34 Containment Fan Cooler Units (FCU) are in operation
- Breaker Maintenance is scheduled for 32 FCU
- Containment Temperature is 87.5°
- Service Water is properly aligned to all FCUs
- All Precautions and Limitations have been satisfied
- 35 FCU was secured 6 hours ago for breaker maintenance
- Motor Starting Frequency requirement have been verified.
Initiating Cue: You are the BOP and the CRS has directed you to start 35 Fan Cooler Unit in accordance with 3-S0P-CB-010.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0800060331 Task
Title:
Energize Buses 5 and 6 from 13.8 KV Power 062000A401 KIA
Reference:
RO - 3.3 SRO - 3.1 Job Performance Measure No: - SIM
-F ---
Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance x Classroom Simulator - - - -X- - - - Plant - - - - - READ TO THE EXAMINEE 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. Initial Conditions:
- The plant is at approximately 45% power.
- The Station Service Transformer experienced a fault
- The operating crew entered of 3-AOP-138KV-1.
- 13.8KV power is available.
- 6.9 KV Bus 5 Lockout Relay 86ST5 is reset
- 6.9 KV Bus 6 Lockout Relay 86ST6 is reset Task Standard: 6.9 KV buses 5 and 6 are energized from 13.8KV source Required Materials: None General
References:
3-AOP-138KV-1 Attachment '1 Initiating Cue: You are the BOP and the CRS has directed you to re-energize Buses 5 and 6 from 13.8KV in accordance with steps 1.10 through 1.30 in 3-AOP 138KV-1, Attachment 1. Time Critical Task: No 1 of 12
Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 15 Minutes 2 of 12
...cA'-I.Jppc...;e:..;..n:..;..d::.:.ix~C",,---_ _ _ _ _ _ _ _ _-,-P-=a'-'"lg~e-=3,----_________-,F......:o:rm ES-C-1 Performance Information (Denote critical steps with a check mark ,j>
"1. Performance Step: Place the 6900V bus tie breaker in PULL OUT.
Standard: Place the following in pullout: o 6900V Bus No. 1-5 Tie in PULLOUT o 6900V Bus No. 2-5 Tie in PULLOUT o 6900V Bus No. 3-6 Tie in PULLOUT o 6900V Bus No. 4-6 Tie in PULLOUT Panel SHF Comment: Procedure Step 1.10
- 2. Performance Step: Will 6.9 KV Bus 5 be energized from 13.8KV source?
Standard: YES - Given in Initiating Cue Comment: Procedure Step 1.11 "3. Performance Step: Place 35 Circ Water Pump breaker in PULL OUT Standard: CCR control switch placed in PULL OUT for 35 Circ Water Pump PanelSJF Comment: Procedure Step 1.12 3 of 12
Appendix C Page 4 Form ES-C-1 Perl:ormance Information (Denote critical steps with a check mark ...J) "4. Performance Step: Is 6900KV bus No.5 Normal Feed breaker in Pullout? Place 6900KV bus No.5 Normal Feed breaker in Pullout Standard: 6900V Bus No.5 Normal Feed breaker control switch placed to PULL OUT Panel SHF Comment: Procedure Step 1.13
- 5. Performance Step: Is 6.9KV Bus 5 lockout relay B6ST5 reset?
Standard: YES. Given in Initial Conditions Candidate may contact the Nuclear Plant Operator to verify 86ST5 reset at the 6.9KV switchgear. CUE: IF NPO contacted, report 86ST5 is reset Comment: Procedure Step 1.14
- 6. Performance Step: Is Station Service Transformer Supply Breaker 5 open and flag matched to green?
Standard: Observes green and amber lights ON and switch flag red. Rotate switch to TRIP then back to AUTO Panel SHF Comment: Procedure Step 1.15 4 of 12
-.l\ppendix C Page 5
- - -Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 7. Performance Step: Is voltage zero on 6.9KV bus 5 Standard: YES. Places 6900V Bus Voltmeter switch to Bus 5 position and verifies 6900V Bus meter indicates zero.
Panel SHF Comment: Procedure Step 1.16 "8. Performance Step: Close GT-35 6.9 KV Bus No.5 Feed Breaker Standard: Rotate Breaker Control Switch from Pullout to Close position. Observes Green light OFF and Red light ON PanelSHF Comment: Procedure Step 1.17
- 9. Performance Step: Is 6.9KV Bus 5 energized?
Standard: YES. Observes voltage indicated on 6900V Bus Voltmeter. Panel SHF Comment: Procedure Step 1.18
- 10. Performance Step: Is Bus 5A Normal Feed breaker open?
Standard: YES. Observes Gree Light ON. The flag is still RED. The candidate may rotate the switch to TRIP to match the flag position with breaker position. Panel SHF Comment: Procedure Step 1.19 5 of 12
~pendixC Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ")
- 11. Performance Step: Close Sta. Serv Trans. 5 Supply Breaker SS5 Standard: Rotate Switch to CLOSE position. Observe Green Light OFF and Red Light ON.
Comment: Procedure Step 1.20 This step in not critical because it is not necessary to energize bus 5. It is a step necessary to energize 480V bus 5A. 12.. Performance Step: Will 6.9 KV Bus 6 be energized from 13.8KV source? Standard: YES -- Given in Initiating Cue Comment: Procedure Step 1.21 "13. Performance Step: Place 34 Circ Water Pump and Standby Circ Water Pump breakers in PULL OUT Standard: CCR control switch placed in PULL OUT for 34 and Standby Circ Water Pump PanelSJF Comment: Procedure Step 1.22 6 of 12
Appendix 9_________---'-P-=a......ge-=7_ _ _ _ _ _ _ _ _----'-Fo-'-r_m_E=.S-=..--'C'--_1 LC Performance Information (Denote critical steps with a check mark -,J) '" 14. Performance Step: Is 6900KV bus No.6 Normal Feed breaker in Pullout? Place 6900KV bus No.6 Normal Feed breaker in Pullout Standard: 6900V Bus No.6 Normal Feed breaker control switch placed to PULL OUT Panel SHF Comment: Procedure Step 1.23
- 15. Performance Step: Is 6.9KV Bus 6 lockout relay 86ST6 reset?
Standard: YES. Given in Initial Conditions Candidate may contact the Nuclear Plant Operator to verify 86ST6 reset at the 6.9KV switchgear. CUE: IF NPO contacted, report 86S15 is reset Comment: Procedure Step 1.24
- 16. Performance Step: Is Station Service Transformer Supply Breaker 6 open and flag matched to green?
Standard: Observes green and amber lights ON and switch flag red. Rotate switch to TRI P then back to AUTO Panel SHF Comment: Procedure Step 1.25 7 of 12
Appendix C_ _ _ _ _~_____P_a_""g_e_8__ Form ES-C-1 Performance Information {Denote critical steps with a check mark ...J}
- 17. Performance Step: Is voltage zero on 6.9KV bus 6 Standard: YES. Places 6900V Bus Voltmeter switch to Bus 6 position and verifies 6900V Bus meter indicates zero.
Panel SHF Comment: Procedure Step 1.26 ...J 18. Performance Step: Close GT-36 6.9 KV Bus No.6 Feed Breaker Standard: Rotate Breaker Control Switch from Pullout to Close position. Observes Green Light OFF and Red Light ON Panel SHF Comment: Procedure Step 1.27
- 19. Performance Step: Is 6.9KV Bus 6 energized?
Standard: YES. Observes voltage indicated on 6900V Bus Voltmeter. Panel SHF Comment: Procedure Step 1.28
- 20. Performance Step: Is Bus 6A Normal Feed breaker open?
Standard: YES. Observes Green Light ON. The flag is still RED. The candidate may rotate the switch to TRIP to match the flag position with breaker position. Panel SHF Comment: Procedure Step 1.29 8 of 12
Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 21. Performance Step: Close Sta. Serv Trans. 6 Supply Breaker SS6 Standard: Rotate Switch to CLOSE position. Observe Green Light OFF and Red Light ON.
Comment: Procedure Step 1.30 This step in not critical because it is not necessary to energize bus 6. It is a step necessary to energize 480V bus 6A. Terminating Cue: JPM Complete 9 of 12
VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: 10 of 12
Appendix C Simulator Setup Form ES-C-1 Reset Simulator to IC24 Insert Malfunction MAL EPS006 Place Simulator in Run and let conditions stabilize. Perform the first 17 steps of AOP-138KV-1 11 of 12
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The plant is at approximately 45% power.
- The Station Service Transformer experienced a fault
- The operating crew entered of 3-AOP-13,8KV-1.
- 13.8KV power is available.
- 6.9 KV Bus 5 Lockout Relay 86ST5 is reset
- 6.9 KV Bus 6 Lockout Relay 86ST6 is reset Initiating Cue:
You are the BOP and the CRS has directed you to re-energize Buses 5 and 6 from 13.8KV in accordance with steps 1.10 through 1.30 in 3-AOP-138KV-1, Attachment 1.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0390120431 Task
Title:
Respond to a Steam Flow Channel Failure 035000K401 KIA
Reference:
RO - 3.6 SRO - 3.8 Job Performance Measure No: SIM G Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance Classroom Simulator x Plant - - - - - READ TO THE EXAMINEE 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. Initial Conditions:
- The reactor is at indicated power
- Steady State, equilibrium Xenon conditions exist
- No equipment is out of service Task Standard: Stable plant conditions.
Required Materials: None General
References:
3-AOP-INST-1 Initiating Cue: You are the ATC. Take appropriate actions to stabilize plant. Time Critical Task: No Validation Time: 10f9
_~n_d_ix_C _ __ Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -I)
- 2. Performance Step: Check. All Control Systems
- Rod Control - Not Affected
- PRZR Pressure Control - Not Affected
- PRZR Level Control - Not Affected
- MBFP Speed Control - Not Affected
- SG Pressure Control - Not Affected
- SG Level Control - IS AFFECTED All above indications are located on the Flight Panel Standard: Check indications for all controls systems - Only Steam Flow is affected.
Comment: This is part of the immediate actions step 3.1 for 3-AOP-INST-1. The candidate should check all of these indications from memory. When conditions are stable the candidate should obtain the procedure and evaluate the control systems again. CUE: Remove equipment from service per appropriate AOP. Give candidate AOP-INST -1. 20f9
Form Performance Information (Denote critical steps with a check mark ..J)
- 3. Performance Step: Has an instrument failure occurred?
Standard: YES Operator determines FT-449B has failed low. Panel FBF Comment: Procedure Step 4.1
- 4. Performance Step: Got to the applicable step for the indicated failure. Step 4.70 for Steam Flow Failure Standard: Operator determines step 4.70 is the correct step from the table Comment: Procedure Step 4.2
- 5. Performance Step: Are both SG Transfer Switches selected to the NON affected channel.
Standard: YES. However, the Steam Flow Transfer Switch did not transf,er control to the non-affected channel. Operator may attempt to transfer again. Panel FBF Comment: Procedure Step 4.3 30f9
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ."j)
- 7. Performance Step: Return controls for unaffected equipment used to stabilize plant conditions to auto as desired.
Standard: No equipment can be returned to auto. Comment: Procedure Step 4.72
- 8. Performance Step: Refer to the following TS tables for required actions
- 3.3.1-1
- 3.3.2-1 Standard: No Action Required Comment: Procedure Step 4.73 CUE: The STA will evaluate Tech Specs.
40f9
_.A.ppendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 9. Performance Step: Observe CAUTION before Step 4.74 Standard: Reviews Caution Comment:
- 10. Performance Step: Are all redundant bistable status lights for failed instruments listed in Attachment 4 Table 1 extinguished Standard: Check. each of the listed status lights OFF
- H-19 -- SG 34 LO LEVEL LC447G
- 1-7 -- HI STM FLOW LP31 FC419A
- J-7 -- HI STM FLOW LP31 FC419B
- 1-8 -- HI STM FLOW LP32 FC429A
- J-8 -- HI STM FLOW LP32 FC429B
- 1-9 -- HI STM FLOW LP33 FC439A
- J-9 -- HI STM FLOW LP33 FC439B Comment: Procedure Step 4.74
- 11. Performance Step: Observe NOTE before step 4.75 Standard: Reviews Note Comment:
50f9
Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ;/) ...J 12. Performance Step: Trip bistables for failed instrument listed in Attachment 4 Table 2 Standard: Locate rack White A*a Place the switches listed below in the tripped (Up) postion
- Loop 48, High SF 51
- Loop 48, SF > FWF Comment: Procedure Step 4.75
- 13. Performance Step: Are all bistable status lights for failed instrument listed in Attachment 4 illuminated?
Standard: At panel SOF verify status lights are illuminated. Comment: Procedure Step 4.76 Terminating Cue: JPM Complete 60f9
~----~-- ----~-----
Append_ix_C_____ Page 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: 70f9
-- --~-~~--.~---~-~------ Appendix_C_ _ _ _ _ _ Simulator Setup Form ES-C-1 Reset Simulator to any 100% Power IC Insert Malfunction MAL-MSS004H to 0% (Ramp time 30 seconds, No Delay time) Insert Switch Override SWI-PCS007 to ON (Prevents contacts from transferring) 8of9
-~~~~---------------------- _____*____ ____;_'_'_f1_0_(_n****_______________
~.
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The reactor is at indicated power
- Steady State, equilibrium Xenon conditions exist
- No equipment is out of service Initiating Cue:
You are the ATC. Take appropriate actions to stabilize plant.
Appendix C Job Performance Measure Form ES-C-1 Facility: Indian Point 3 Task No: 0730150101 Task
Title:
Adjust R-27 Process Radiation Monitor Setpoints 073000A402 KJA
Reference:
RO - 3.7 SRO - 3.7 Job Performance Measure No: - Sim
-H ---
Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance X Actual Performance X Classroom Simulator X Plant - - - - - READ TO THE EXAMINEE 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. Initial Conditions: Plant startup is in progress. Post maintenance testing is complete on R-27 Channel 4. A new alert setpoint has been provided by chemistry. All requirements for setpoint control and log keeping have been met and are being performed by the CRS Task Standard: New alert setpoints entered into Bantam 11 and RM-23A for rad monitor R-27 Required Materials: None General
References:
3-S0P-RM-008, Radiation Monitoring Control Cabinet (BANTAM 11/RM23A Cabinet. Initiating Cue: You are the BOP and the CRS has directed you to adjust the R-27 Channel 4 Bantam-11 to 3.5E+3 per 3-S0P-RM-008, Radiation Monitoring Control Cabinet steps 4.3.5.1 Time Critical Task: No 1 of 8
Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 10 minutes 20f8
Appendix C _ _~______....:.P-,a=gi!...:;e-,3=----___________F~o.rm ES-C-1 Performance Information (Denote critical steps with a check mark --J)
- 1. Performance Step: Refer to 3-S0P-RM-010 Radiation Monitor Setpoint Control Standard: 3-S0P-RM-010 requirements verified to be met. Given in Initial Conditions CUE: All requirements for setpoint control and log keeping have been met and are being performed by the CRS'.
Comment: Procedure Step 4.3.5.1 Performance Step: Select Bantam 11 RM-27 channel per section 4.3.1 Standard: This can be accomplished several ways. From the Group Display enter 4027 then press SEL and verify RM-27 is backlit From the Group Menu press SEL button repeatedly until RM-27 is backlit From Grid Display select grid 1 and enter 4027 then press SEL and verify RM-27 and verify channel is backlit. From the Grid Display press SEL repeated until RM-27 is backlit Comment: Procedure Step 4.3.5.2 ...J 3. Performance Step: Select Channel Items display by depressing the Channel Items pushbutton. Standard: Depresses Channel Items Pushbutton Comment: Procedure Step 4.3.5.2.a 3 of 8
AppendixC Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ..., 4. Performance Step: Insert Key and turn Normal Supervisor Switch to Supervisor Standard: Insert and Rotate Key to Supervisor position Comment: Procedure Step 4.3.5.2.b
..., 5. Performance Step: If changing Alert Set point Then enter 010 press SEL and verify channel item is backlit Standard: properly enters numbers and presses SEL, then verifies channel is backlit Comment: Procedure Step 4.3.5.2.d-e ..., 6. Performance Step: Enter new set point Standard: Enter setpoint in the following format 3 5 + 0 3 Comment: Procedure Step 4.3.5.4 4 of 8
_A~pp~e_n_d_ix_ C ______________________P_~ge5 Form ES-C-1 Performance Information (Denote critical steps with a check mark "./)
'" 7. Performance Step: Verify desired value is displayed If correct press Enter Standard: Observe display and depress Enter if correct. If not correct press Clear and repeat step 4.3.5.4 Comment: Procedure Step 4.3.5.5 '" 8. Performance Step: Turn Normal Supervisor keyswitch to NORMAL and REMOVE key.
Standard: Rotate switch to NORMAL and Remove Key Comment: Procedure Step 4.3.5.6
- 9. Performance Step: Restore normal All Monitors display Standard: Depresses Group Menu Pushbutton then 026 and SEL to restore normal display Comment: Procedure Step 4.3.5.7 Terminating Cue: JPM Complete 50f8
Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ _ __ 6 of 8
Form No Simulator Setup is necessary for this JPM 7 of 8
Initial Conditions: Plant startup is in progress. Post maintenance testing is complete on R-27. A new alert setpoint has been provided by chemistry. All requirE~ments for setpoint control and log keeping have been met and are being performed by the CRS Initiating Cue: You are the BOP and the CRS has directed you to adjust the R-27 Channel 4 Bantam 11 to 3.5E+3 per 3*S0P-RM-008. Radiation Monitoring Control Cabinet steps 4.3.5.1.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point Task No: 0040010504 Task
Title:
Locally Emergency Borate 000024A104 Job Performance Measure KIA
Reference:
RO - 3.6 SRO - 3.7 No: In-Plant 1 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance Classroom Simulator Plant x READ TO THE EXAMINEE I wi" 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. Initial Conditions:
- The Control Room has been evacuated due to a fire
- Source Range N-38 is on scale but count rate has not been decreasing as expected
- MCC-36A is energized, MCC-3138 is de-energized
- 31 BATP had been in-service
- Seal injection is in service to All RCPS Task Standard: Local Emergency Boration has been established for 35 minutes per 3 AOP-SSD-1 , Attachment 8 Required Materials:
General
References:
2-AOP:-SSD-'I, Attachment 8, Emergency Boration - Local Initiating Cue: You are the ATC and the SM has directed you to Emergency Borate the RCS in accordance with 3-AOP-SSD-1, Attachment 8. Time Critical Task: No Validation Time: 20 minutes 1 of 9
Appendix C _________---'P--"age 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,J)
- 1. Performance Step: Obtain correct procedure Standard: Obtains 3-AOP-SSD-1 Attachment 8 This procedure would have been picked up from the APP R cage outside the Unit 3 Control Room upon evacuation.
Comment:
- 2. Performance Step: Verify 31 BATP energized from MCC-36A Standard: Locate! breaker for 31 BATP on MCC-36A and verify it is closed. (Can also be locally verified if pump lIS)
Comment: Procedure Step 8.1 CUE: Breaker on MCC36A is CLOSED
- 3. Performance Step: Determine if 32 Boric Acid Transfer Pump energized at MCC-36B?
Standard: Determine 32 Boric Acid Transfer Pump cannot be energized. MCC-36B is de-energized - Given in Initial Conditions. Comment: Procedure Step 8.2
- 4. Performance Step: Determine that 31 Boric Acid Transfer Pump be used to supply blender?
Standard: Given in Initial Conditions Comment: Procedure Step 8.3 CUE: If requested the SM directs you to use 31 Boric Acid Transfer Pump. 2 of 9
Form Performance Information (Denote critical steps with a check mark..J)
- 5. Performance Step: Open CH-360 (31 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER).
Standard: Locate CH-360 and determines valve is open Comment: Procedure Step 8.4. This step in NOT critical because if 31 BATP was in service, this valve would be opened. Depending on actual plant configuration this valve may be opened or closed. CUE: Valve is Open
- 6. Performance Step: Close CH-370 (32 BORIC ACID TRANSFER PUMP DISCHARGE ISOLATION TO 31 BORIC ACID FILTER).
Standard: Locate CH-370 and determine valve is closed Comment: Procedure Step 8.5. This step in NOT critical because if 31 BATP was in service, this valve would be closed. Depending on actual plant configuration this valve may be opened or closed. CUE: Valve is Closed
- 7. Performance Step: Close CH-267B (31 BORIC ACID FILTER BYPASS ISOLATION FROM 32 BORIC ACID TRANSFER PUMP)
Standard: Locate CH-267B and determine valve is closed Comment: Procedure Step 8.6. This step in NOT critical because if 31 BATP was in service, this valve would be closed. Depending on actual plant configuration this valve may be opened or closed. CUE: Valve is Closed 30f9
Appel1dix C P~ge4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- ..j 8. Performance Step:* Close CH-HCV-104 and CH-HCV-105 (Boric Acid Transfer Tank Recirculation Flow Controllers)
Standard: Locate valves. Isolate air supply to the valves and vent the air from the diaphragm. OR Candidate may adjust "rabbit ears" to vent air from diaphragm. Comment: Procedure Step 8.7 CUE: Valves are closed
- 9. Performance Step: Depress clutch lever for CH-MOV-333 (EMERGENCY BORATION VALVE). (PAB 73' el. Boric Acid Blender area)
Standard: Locate valve and depress clutch lever. Comment: Procedure Step 8.8 CUE: Lever moves down freely
- 10. Performance Step: Engage clutch by moving handwheel as necessary and release clutch lever.
Standard: Rotate handwheel as necessary until clutch engages and then release lever Comment: Procedure Step 8.9 CUE: Handwheel rotates slightly and clutch is engaged
- 11. Performance Step: Open CH-MOV-333 by rotating handwheel counterclockwise.
Standard: Attempts to rotate handwheel counterclockwise. Comment: Procedure Step 8.10 CUE: Handwheel will NOT rotate 4of9
Appen=d~ix~C~__________________~P~a~g~e~5~_________________F~o=r~m~E=S~-~C~-~1 Performance Information (Denote critical steps with a check mark ...J) Transfer control of aligned Boric Acid Transfer Pump to LOCAL at the boric acid transfer pumps. Standard: Place hand switch for 31 BATP in Local Comment: Procedure Step 8.11 CUE: Switch rotates to Local Position ..J 15. Performance Step: Place aligned Boric Acid Transfer Pump Speed Switch to FAST. Standard: Locate switch and rotate to Fast Speed Comment: Procedure Step 8.12 CUE: Switch is in Fast Position 50f9
Performance Information (Denote critical steps with a check mark ..J)
- 16. Performance Step: Determine that Seal Injection flow to all RCPs was NOT isolated Standard: Given in Initial Conditions. Goes to Procedure Step 8.15 Comment: Procedure Step 8.13
- 17. Performance Step: Dispatch Nuclear NPO to monitor RCP Seal Injections Flows Standard: Directs Nuclear NPO to monitor Rep Seal Injection Flows Comment: Procedure Step 8.15 CUE NPO Acknowle~ges direction.
- 18. Performance Step: Observe NOTE before Step 8.17 Standard: Reviews NOTE Comment:
CUE: 35 minutes has elapsed. 60f9
Appendix C Page 7 Performance Information (Denote critical steps with a check mark ..J)
'" 19. Performance Step: Increase Charging Pump Speed until each RCP Seal Injection indicates 10 -12 gpm Standard: Locate Charging Pump Controls Establish communication with the Nuclear NPO Rotate speed potentiometer for operating charging pump Stop adjustment when NPO reports Seal Injection flow is 10 -12 gpm on a" pumps Comment: Procedure Step 8.16 Charging Pump Controls are located in a cabinet by the entrance to the charging pump cells.
CUE: NPO reports all RCP seal injection flows indicate 10 - 12 gpm
- 20. Performance Step: WHEN boration has been ongoing for> 35 minutes, THEN stop Boric Acid Transfer Pump.
Standard: Rotate Boric Acid Transfer Pump switch to STOP Comment: Procedure Step 8.17 _qUE: Pump is s!o~pL.p-=-ed::::..-.-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Terminating Cue: JPM Complete 70f9
VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: _ _ _ _ _ _ _ _ _ __ 80f9
Conditions Form Initial Conditions:
- The Control Room has beE~n evacuated due to a fire
- Source Range N-38 is on scale but count rate has not been decreasing as expected
- MCC-36A is energized, MCC-36B is de-energized
- 31 BATP had been in-service
- Seal injection is in service to ALL RCPS Initiating Cue:
You are the ATC and the SM has directed you to Emergency Borate the RCS in accordance with 3-AOP-SSD-1, Attachment 8.
Appendix C Job Performance Measure Form ES-C-1 Worksheet
.~--------------------------
Facility: Indian Point 3 Task No: 0840050432 Task
Title:
Perform Actions for RHR Pump Cooling using City Water 005000K101 KIA
Reference:
RO - 3.2 SRO - 3.1 Job Performance Measure No: In Plant 2 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance x Actual Performance Classroom Simulator - - - - - - - - - - Plant x READ TO THE EXAMINEE 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. Initial Conditions:
- The unit is in Mode 5 with #31 RHR pump in service.
- The CCW supply to the RHR pumps has failed.
- City Water is available for 31 RHR Pump.
Task Standard: Backup City Water aligned to the 31 RHR Pump and draining to the floor Required Materials: None General
References:
3-S0P-ESP-001, Initiating Cue: You are the Spare RO and the CRS has directed you to align Normal Backup City Water to cool 31 RHR Pump per SOP-ESP-001, Section 4.12. Time Critical Task: No Validation Time: 20 Minutes 1 of 7
Appendix-=C"--_ _ _ _ _ _~______ P_'_"age"___2_
.... _ __ Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J)
- 1. Performance Step: Obtain Correct Procedure Standard: Obtains 3-S0P-ESP-001, Local Equipment Operation and Contingency Actions.
Comment:
- 2. Performance Step: Observe Cautions before Step 4.12.1 Standard: Reviews Cautions Comment:
"3.----------.---------------~ ..
Performance Step: Close AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation Standard: Locates Valve, Simulates rotating in the clockwise direction CUE: The Valve is Closed Comment: Procedure Step 4.12.1.1 20f7
Performance Information (Denote critical steps with a check mark "-') ..J 4. Performance Step: Close AC-737 A, CC Return from 31 RHR Pump Thermal Barrier Inlet Isolation Standard: Locates Valve, Simulates rotating in the clockwise direction CUE: The Valve is Closed Comment: Procedure Step 4.12.1.2 ..J 5. Performance Step: Close AC-1871D, CC Supply to 31 RHR Seal HX Inlet Isolation Standard: Locates Valve, Simulates rotating in the clockwise direction CUE: The Valve is Closed Comment: Procedure Step 4.12.1.2
'" 6. Performance Step: INSTALL emergency city water supply jumper (e.g.,
hose) between MW-18-16, Hose Connection Isolation, (across from filter room on column) and one inch tee located immediately downstream of AC-736A, CC Supply to 31 RHR Pump Thermal Barrier Inlet Isolation Standard: Jumper hose located in spare RHR pump cell, hose connection locations identified, and simulate connection actions. CUE: Jumper Hose is connected. Comment: Procedure Step 4.12.1.4 30f7
Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark >i)
- 7. Performance Step: INSTALL drain hose on % inch tee located immediately downstream of AC-1871D, CC Supply to 31 RHR Pump Seal Hx Inlet Isolation(31 RHR pump room)
Standard: % inch tee located and simulated hose connection actions CUE: Hose is connected Comment: Procedure Step 4.12.1.5
- 8. Performance Step: Route drain hose to suitable drain Standard: Drain hose routed CUE: Drain Hose is routed to drain Comment: Procedure Step 4.12.1.6
...J 9. Performance Step: OPEN AC-1871 C, CC Return from 31 RHR Pump Seal Hx Outlet Isolation (31 RHR pump room). Standard: Valve located simulated rotating counterclockwise CUE: Valve is Open Comment: Procedure Step 4.12.1.7 4 of 7
Appendix C PageS Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) V10. Performance Step: OPEN. MW-1S-16, Hose Connection Isolation (across from filter room on column) Standard: Locate valve and simulate rotate counterclockwise (Open) CUE: Valve is Open Comment: Procedure Step 4.1:tS Terminating Cue: JPM Complete S of7
Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: 60f7
Appendix C Initial Conditions Form ES-C-1 Initial Conditions:
- The unit is in Mode 5 with #311 RHR pump in service.
- The CCW supply to the RHR pumps has failed.
- City Water is available for 31 RHR Pump.
Initiating Cue: You are the Spare RO and the CRS has directed you to align Normal Backup City Water to cool 31 RHR Pump per SOP-ESP-001, Section 4.12.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Indian Point 3 Task No: 0710040134 Task
Title:
Release a Gas Decay Tank KIA
Reference:
RO - 2.6 SRO - 2.6 Job Performance Measure No: In Plant 3 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance x Actual Performance Classroom Simulator - - - - - - Plant X READ TO THE EXAMINEE 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. Initial Conditions:
- The release of 31 Small Gas Decay Tank is complete
- 32 Small Gas Decay Tank must be released.
- RCV-014 is closed
- An Independent Verifier (IV) is standing by
- The Precautions and Limitations of 3-S0P-WDS-013 have been reviewed and are satisfied.
Task Standard: Required Materials: None General
References:
3-S0P-WDS-013, Gaseous Waste Releases Initiating Cue: You are the Nuclear NPO and the SM directs you to complete the restoration lineup for 31 Small Gas Decay Tank (SGDT) and perform the Release Alignment for 32 SGDT in accordance with 3-S0P-WDS-013 Attachment 9. 1 of 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 2ot9
Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) ..J 1. Performance Step: Perform restoration section of applicable Attachment 9 for 31 Small Gas Decay Tank Standard: Obtains Attachment 9 Locates and Simulates Closing WD-1652A (Rotate Clockwise) CUE: Valve is Closed Comment: ..J 2. Performance Step: Perform valve alignment to isolate tank and prepare to sample per Attachment 9. Standard: Locate each valve on list below and check or reposition valve Only WD-1652 is critical, the remaining valves are expected to be in the indicate position CUE: The valves are in the position indicated WD-16528 is OPEN Comment: 30f9
Appendix C Page 4 Form ES-C-1
- VALVE VALVE DESCRIPTION REQUIRED NUMBER POSITION N2 Supply to 32 SGDT Isolation
- WD-1641B
- CLOSED WD-1642B 32 SGDT Drain (1) CLOSED
~-~~-+-=-32:::--:::S-:=G-=D-=T:-::F:::-::iI-:-:1l:-so-=l:-atC:-io-n-=(7.1):--~_---,_ _ _ _ ----l WD-1651 B . CLOSED
,--- I PT-1053 Root Isolation I WD-1676B OPEN I 32 SGDT to Release Header WD-1652B OPEN
- Isolation i 31 SGDT to Release Header WD-1652A I CLOSED I Isolation 33 SGDT to Release Header i WD-1652C
- CLOSED Isolation 34 SGDT to Release Header I WD-1652D CLOSED Isolation I 35 SGDT to Release Header I WD-1652E I CLOSED Isolation 36 SGDT to Release Header I WD-1652F CLOSED I Isolation 31 LGDT to Release Header I
~D-1617 Isolation CLOSED 32 LGDT to Release Header i WD-1618 CLOSED Isolation 33 LGDT to Release Header WD-1619 CLOSED I Isolation 34 LGDT to Release Header I WD-1620 CLOSED Isolation I CUE: The valves are in the position indicated WD-1652B is OPEN 40f9
_Appendix C Page 5 Form ES-C-1
- 3. Performance Step: Initiate Independent Verification (IV) of gas decay tank release path per Attachment 9 Standard: Contact another individual to perform independent verification. Independent Verifier is standing by on radio.
Given in Initial Conditions. CUE: Acknowledge as Independent Verifier and report that IV is complete. Comment: Terminating Cue: JPM Complete 50f9
Appendix C Page 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to complete: Question Documentation: Question:
Response
Result: SAT or UNSAT Examiner's signature and date: 6 of 9
$- . l' er 'q *I') : I
~nitial Conditions Form Initial Conditions:
- The release of 31 Small Gas Decay Tank is complete
- 32 Small Gas Decay Tank must be released.
- RCV-014 is closed
- An Independent Verifier (IV) is standing by Initiating Cue:
You are the Nuclear NPO and the SM directs you to complete the restoration lineup for 31 Small Gas Decay Tank (SGDT) and perform the Release Alignment for 32 SGDT in accordance with 3-S0P-WDS-013 Attachment 9.
tnt) * ~,_.t ______ No: 3-S0P-WDS-O 13 Rev: GASEOUS WASTE RELEASES Page 48 of 56 ATTACHMENT 9, SGDT RELEASE ALIGNMENT (Page 1 of 6) 31 SMALL GAS OECAY TANK oate:_'_I_O_D_A_\_I_ _ _ __ RELEASE ALIGNMENT VALVE REQUIRED ALIGNED VERIFIED VALVE DESCRIPTION NUMBER POSITION BY BY I WD-1641A N2 Supply to 31 SGDT Isolation CLOSED 7)/lt! ! f)/'l ") WQ..1642A 31 SGDT Drain (1) CLOSED '-nI'l) I 7) It) J WO-1651A 31 SGDT Fill Isolation (1) CLOSED I
'nl'lJ I 7)/'£1.,)
WD-1676A PT-1052 Root Isolatkln OPEN Illb I I!P
, . if\ "
"~f WD-1652A 31 SGDT to Release Header ISl::llation OPEN njJd -/ })fJtJ )
WD-16528 32 SGDT to Release Header isolation CLOSED 7)[>lil 7J Pf! 1 WD-1652C 33 SGDT to Release Header Isolation CLOSED 'J PI) I l}j>l) ,) WD-i6520 34 SGDT to Release Header Isolation CLOSED 'nptL / 7)1)0") WO-1652E :i5 SGDT to Release Header Isolation CLOSED 7) I'f;/ 7,)/1) J WD-1652F 36 SGDT to Release Header Isolation CLOSeD '7)PiJ l 7) It};) WO-1617 31 LGDT to Release Header Isolation CLOSED 77/1tJ I nPIJ.J I WO-1618 32 LGOT to Release Header Isolation CLOSED 7)/JrJ #/ J1/1v }. WD-1619 33lGDT to Release Header Isolation CLOSED 'nfJtJ / f}jJ/,I;) I WD-1620 34 LGOT to Release Header Isolation CLOSED n/~p / TiJ'C I (1) Actual nomenclature for these valves on label is Small Gas Decay Tank.
/1 t* 1/:1 /l' The above valve alignment has been venfled correct t-'t'/l Fe :t!t"'u."Ui:'?.f"~i~eference 5.1.2}
CRS/SM RESTORATION ALIGNMENT i VALVE REQUIRED ALIGNED VERIFIED VALve OESCFUPTION NUMBER POSITION BY BY WD-1652A 31 SGDT to Release Heac1er Isolation CLOSED
No: 3-S0P-WOS-013 Rev: 28 GASEOUS WASTE RELEAses Page 49 of 56 ATTACHMENT 9, SGOT REL.EASE ALIGNMENT (Page 2 of 6) 32 SMALL GAS OeCAY TANK Date: Tv 'Oft.., AELEASE ALIGNMENT VALve _MBER v ALve DeSCRIPTION ReQUIR~: POSITIO I BY ED VERIFIED BY WD*1641B N2 Supply to 32 SGOT Isolation CLOSED WO-16428 32 SaDT Dram (1) CLOSED WD-1651B
- 32 SGDT Fill Isolation (1) CLOSED WO-1676B PT -1053 Root Isolation OPEN WD-1652B 32 SGOT to Release Header Isolation OPEN WD*1652A 31 SGOT to Release Header Isolation CLOSED
! WO-1652C 33 SGOT to Release Header !solation CLOSED WD*16520 34 SGDT to Release Header Isolation CLOSED WO-1652E 35 SaDT to Release Header !solation CLOSED WO-1652F 36 SGOT to Release Header Isolation CLOSED WO-1617 31 LGOT to Release Header !solation CLOSED WO*1618 32 LGOT to Release Header :solation CLOSeD WD-1619 33 LGOT to Release Header jsolalion CLOSED WD-1620 34 LGDT to Release Header Isolation CLOSED (1) Actual nomenclature for these valves on label is Small Gas Decay Tank. The above valve alignment has been verified correct _ _ _-=-=:-:::"":'~:__--{Reference 5.1.2} CRS/SM RESTORATION ALIGNMENT VALve REQUIRED ALIGNED y VALVE OeSCRI,PTION !~MBER POSITION BY g,
'S ease HeadElf Isolalion CLOSED I}}