ML051400106
| ML051400106 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/17/2005 |
| From: | D'Antonio J Operations Branch I |
| To: | Wilson M Dominion Nuclear Connecticut |
| Conte R | |
| References | |
| Download: ML051400106 (94) | |
Text
ES-401 PWR Examination Outline Form ES-401-2
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 , 4 7 Categories 2 3 2 3 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA category shall not be less than two).
- 2. The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by il from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Systemsfevolutionswithin each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriateWA statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-onty portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
- 7. The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.
- 8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (1%) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3,select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.Limit SRO selections to WAS that are linked to 10 CFR 55.43.
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Ernergenc and Abnormal Plant Evolutions - Tier llGroup 1 (RO)
~
E/APE # I Name I Safety Function WA Topic@)
000007 (BWIE028tElO; CE/E02) EK1.2 Knowledge of the operational implications of the following concepts as they apply Reactor Trip - Stabilization - X to the (Reactor Trip Recovery): Normal, abnormal and emergency operating procedures Recovery / 1 - associated with (Reactor Trip Recovery) 000008 Pressurizer Vapor Space AA2.02 Ability to determine and interpret the following as they apply to the Pressurizer Accident 13 Vapor Space Accident: PZR spray valve position indicators and acoustic monitors 000009 Small Break LOCA 1 3 EK2.03 Knowledge of the interrelations between the small break LOCA and the followina: WGs 000011 Large Break LOCA 13 EA1.17 Ability to operate and monitor the following as they apply to a Large Break LOCA: Safety parameter display system 000015/17 RCP Malfunctions 14 AK2.10 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP indicators and controls 000022 Loss of Rx Coolant Makeup 1 2 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels 000025 Loss of RHR System 1 4 AA2.07 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Pump cavitation 000026 Loss of Component Cooling AA1.05 Ability to operate and I or monitor the following as they apply to the Loss of Water / 8 Component Cooling Water: The CCWS surge tank, including level control and level c , alarms, and radiation alarm 000027 Pressurizer Pressure Control 2.1.7 Ability to evaluate plant performance and make operational judgments based on System Malfunction13 operating characteristics, reactor behavior, and instrument interpretation I
000029 ATWSI1 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation 000038 Steam Gen. Tube Rupture 13 EK1.03 Knowledge of the operational implications of the following concepts as they
~ apply to the SGTR: Natural circulation 000040 (BWIEO5; CE/E05; WIE12) EA1.1 Ability to operate and I or monitor the following as they apply to the (Excess Steam Line Rupture - Steam Demand): Components, and functions of control and safety systems, including Excessive Heat Transfer I 4 instrumentation, signals, interlocks, failure modes, and automatic and manual features.
L Page 2 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
n 000054 (CWEO6) Loss of Main EA1.2 Ability to operate and Ior monitor the following as they apply to the (Loss of Feedwater I 4 000055 Station Blackout I 6
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000056 Loss of Off-site Power I 6 000057 Loss of Vital AC Inst. Bus 1 6 000058 Loss of DC Power I6 oooO62 Loss of Nuclear Svc Water I 4 000065 Loss of InstrumentAir 1 8 WlE04 LOCA Outside Containment 13 WlE11 Loss of Emergency Coolant Recirc. 1 4 BWlE04; WE05 Inadequate Heat Transfer Loss of Secondary Heat Sink I 4
WA Category Totals:
Page 3 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
ES-401 3 Form ES-401-2 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 Guidance contained in EOP for Page 4 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
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A2.02 Ability to (a) predict the impacts of the following malfunctionsor 2.7 1 operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure K4.02 Knowledge of IAS design feature@)and/or interlock(s) which provide 3.2 2 for the following: Cross-over to other air systems X 2.2.13 Knowledge of tagging and clearance procedures 3.6 3 2 Group Point Total: 28 Page 8 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 nt $stems Tier ZYGroup 2 (RO)
I 0 WA Topi@)
I IR K5.26 Knowledge of the following operational implications as they apply to the 3.3 CRDS: Definitionof moderator temperature coefficient; application to reactor control 014 Rod Position Indication Al.04 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPlS controls, including:
016 Non-nuclear Instrumentation I I I I 1 I 1 1 1 1 1 1 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control X
I 029 Containment Purge X Al.02 Ability to predict and/or monitor changes in parameters (to prevent 2.9 1 exceeding design limits) associated with operating the Fuel Handling System controls including: Water level in the refuelingcanal Page 9 of I8 March 2005 Millstone Unit 2 NRC Exam Outline
2.8 1 068 Liquid Radwaste 3.2 1 2.5 1 2.8 1 3.4 1 Page 10 of I8 March 2005 Millstone Unit 2 NRC Exam Outline
I PWR Examination Outline Form ES-401-2III ES-401 rgenc and Abnormal Plant Evolutions - Tier l/Group 1 (SRO)
WAPE # IName / Safety Function WA Topic@) IR #
oM)oo7 (BW/E02&E10; CUE02) EA2.2 Ability to determine and interpret the following as they apply to the (Reactor Trip 4.0 1 Reactor Trip Stabilization - Recovery): Adherence to appropriate procedures and operation within the limitations in Recovery I1 the facilitys license and amendments 000008 Pressurizer Vapor Space Accident I 3 000009 Small Break LOCA / 3 1 000011 Large Break LOCA I3 000015/17 RCP Malfunctions/ 4 000022 Loss of Rx Coolant Makeup I 2.2.12 Knowledge of surveillance procedures 3.4 1 2
000025 Loss of RHR System I 4 OW026 Loss of Component Cooling 2.4.20 Knowledge of operational implications of EOP warnings, cautions, and notes 4.0 1 Water I 8 000027 Pressurizer Pressure Control System Malfunction/ 3 000029 ATWSI1 EA2.09 Ability to determine or interpret the following as they apply to a ATWS: 4.5 1 Occurrence of a main turbine/ reactor trip II 1 000038 Steam Gen. Tube Rupture I 3 2.1.23 Ability to perform specific system and integratedplant procedures during all modes of plant operation 4.0 1 000040 (BWIEOS; CEIEOS; W E l 2 )
Steam Line Rupture -
Excessive Heat Transfer I 4 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls I 4.0 1 000054 (CWEO6) Loss of Main Feedwater I 4 000055 Station Blackout I 6 -
Page 11 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
000056 Loss of Off-site Power I 6 I1 1 1 I I 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant BW/E04; WIE05 Inadequate Heat Transfer Loss of Secondary Heat Sink /
I I WA Category Totals: I 2I 41 Group Point Total: I 6 11 Page 12 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
ES-401 3 Form ES-401-2 Page 13 of I8 March 2005 Millstone Unit 2 NRC Exam Outline
CElAll ; W E 0 8 RCS Overcoollng PTS 1 4 ret the following as they apply to the (RCS election of appropriate procedures during Page 14 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
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X 2.2.2 Ability to manipulate the console controls as required to operate the 3.5 facility between shutdown and designated power levels X 2.4.30 Knowledge of which events related to system operationdstatus 3.6 should be reported to outside agencies
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3 Group Point Total:
Page 16of 18 March 2005 Millstone Unit 2 NRC Exam Outline
ES-401 PWR Examination Outline Form ES-401-2 System # / Name K
-1 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate Page I7 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
Page 18of 18 March 2005 Millstone Unit 2 NRC Exam Outline ES-401 Record of Rejected WAS Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected WA 2/1 073.K4.02 Not applicable to Millstone Unit 2. CVCS letdown does not auto (RO) isolate on high radiation. Selected 073.K4.01.
2.1.16 Ability to operate plant phone demonstrated during simulator operating test. Randomly selected alternate GKA 2.1.1 4.
1 (SRO) 2.1.16 II Ability to operate plant phone demonstrated during simulator operating test. Randomly selected alternate GKA 2.2.1 2 1 (SRO) 2.1.6 II Ability to supervise and assume a management role during plant transients and uDset conditions demonstrated durina simulator operating test. Randomly selected alternate GKA w
033.G2.3.4 Unable to develop system question related to this GKA. Randomly selected alternate GKA 2.2.22.
010.A3.01 Similar to knowledge tested by 007.A1.03. Unable to develop system question related to this KA. Randomly selected alternate KA 010.A3.02.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: 3/21/05 Examination Level (circle one):@* Operating Test Number:?
1 Ad ministrative Topic (see Note)
TYPe Code*
Describe activity to be performed N Perform an ECP: The examinee properly completes an ECP. (2.1.25) ir------
Equipment Control N RO Taq Clearance Preparation: At the completion of this JPM, the examinee will present a recommended tagging clearance to the tagging authority. (2.2.13)
Review RWP and Survey Mae: At the completion of this JPM the examinee has reviewed the applicable RWP and survey map to Radiation Control N determine the radiological requirements to perform the assigned task (2.3.10)
~~
Use RATS to Determine and Prioritize the Safety Functions: The l Emergency Plan N examinee will correctly identify and prioritize the Safety Function Success Paths. (2.4.4)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
(N)ew or (M)odified from bank (21)
(P)revious 2 exams (51, randomly selected)
(S)imulator ES-301, Page 22 of 27
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: 3/21/05 Examination Level (circle one): RQ /@ Operating Test Number:
I Administrative Topic (see Note)
TY Pe Code*
Describe activity to be performed SRO Shift Turnover: At the completion of this JPM, the Conduct of Operations N SRO has performed a review of turn over documents and found incorrect information related to a shift turnover. (2.1.3)
II SRO Tan Clearance Approval: At the completion of this JPM, the examinee will have discovered that the tag out is in error. He will recommend the clearance not be approved unt N the Cross tie valve 2-CHW-125 is added to the clearance and the other Cross tie valve 2-CHW-124 is removed.
(2.1.24)
SRO AWO Acceptance: At the completion of this JPM, the Equipment Control N examinee will recommend the correct PMT, HPSl Pump IST (SP2604A-003). (2.2.21)
SRO Review and Approve a Radioactive Liquid Waste Release Permit: At the completion of this JPM, the Radiation Control N examinee will have discovered a plant operating condition that will NOT allow authorizing a radioactive liquid waste discharge. (2.3.6)
Classify the Event: At the completion of this JPM, the examinee will determine the classification of the scenario to N, S be an Alert/Cl The examinee will also determine the classification and PARS for conditions provided after the simulator scenario. (2.4.41)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
(N)ew or (M)odifiedfrom bank (21)
(P)revious 2 exams (51;randomly selected)
(S)imulator ES-301, Page 22 of 27
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 2 Date of Examination: 3/21/05 Exam Level (circle one): Operating Test No.: 1 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title Type Code* Safety Function
- a. Manual Makeup to the VCT: At the completion of this JPM, the D. S 1 examinee completes a manual blended make up to the VCT. (004 A2.06) (RO & SRO)
- b. Fill #ISafetv lniection Tank: When the examinee begins to fill # I 3 Safety Injection Tank to between 55.2% and 59.3%, the AHPSl Pump trips. The examinee will declare the A HPSl Pump inoperable, place the B HPSl Pump in service on Facility 1, and complete filling
- c. Start 4h RCP; The examinee will start the RCP, monitor critical RCP parameters, including alarms, and secure the RCP per OP 2301C and/or ARP 2590B-083. (003 A2.03) (RO & SRO)
- d. Perform TDAFP Operabilitv Test: Examinee completes the assigned section of 2610B, determines that the TDAFP is not operable. (061 A2.04) (RO & SRO)
- e. A DG Operabilitv Test (Alternate Path): Examinee performs the 6 Facility 1 Diesel Generator Operability Test, SP 2613A, on the A D/G, recognizes the D/G 12U Trouble annunciator. Upon receipt of information from the PEO in the diesel room, the examinee trips the A DIG. (064 A4.01) (RO)
- f. Power Ranqe Safetv Channel and Delta T Power Channel 7 Calibration: During the performance of SP 2601D, Power Range Safety Channel and Delta T Power Channel Calibration, the examinee determines that the -10 Volt power Supply voltage is not in the acceptable range and bypasses the channel. (012 A2.04) (RO & SRO) g Placinq 6 RBCCW Pump and Heat Exchanqer in Service and D. S 8 Removinq A RBCCW Pump and Heat Exchanqer The examinee places 6RBCCW Pump and Heat Exchanger in service in place of A RBCCW Pump and Heat Exchanger (008 A4 01) (RO & SRO) h Chanqe the Alarm Setpoint of the SJAE RM 5099 The examinee will 9 adjust the setpoint of the Steam Jet Air Ejector Radmonitor as specified on the attached SP2833-007 (071 A4 25) (RO & SRO)
I [SPARE) Hydroaen Recombiner Surveillance At the completion of 5 this JPM the examinee will have A Hydrogen Recombiner in service In accordance with SP 26084, (028 A4 01) (RO & SRO)
ES-301, Page 23 of 27 Implant Systems@(3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- a. Removing Section 201B-I, of Batterv Charger 201 B , From N 6 Service: At the completion of this JPM, battery charger section 201A-1 will be removed from service in accordance with 2345C section 4.13.
(063 K1.03) (RO & SROI b Local Manual Operation of the A Atmospheric Dump Valve Examinee has taken local manual control of the A ADV and placed in c
to 25% open per OP 2316A (041 A2 03) (RO & SRO)
Cross-Tie Station Air With Unit 3 to Supply Unit 2 Instrument Air The examinee has successfully performed the alignment to allow Unit 3 to supply Unit 2 with Station Air and to permit Station Air to supply 7 E, L. N d
Instrument Air (079 A2.01) (RO & SRO)
(SPARE) Loss of SDC/ Vent the A LPSl Pp. At the completion of thrs JPM the examinee will have simulated venting the A LPSl Pp per AOP 2572, Loss of SDC (005A2 03) (RO & SRO)
E, L. N.R 1 4(P)
@ All Control Room (and In-Plant) systems must be different and serve different safety functions, In-Plant systems and functions may overlap those tested in the Control Room
- Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path ____.
~ ~ 4-6 14-6 12-3 (C)ontrol room ~~- ~ ~-
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(D)irect from bank ~ _ _ _ ~ ~ ~
-<9 158 154 (E)rnergency or abnormal in-plant, ~~~
~~ >I 121 131 (L)ow-Power ___~- ~~ -21 121 121 (N)ew or (M)odified from bank includind1A) >2 112 1 2 1 (P)revious 2 exams I -
<3 1 ~ / 2 35 (randomly selected)
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(R)CA - ~ ~ -> I 131 / 21 (S)irnulator
Appendix D Scenario Outline Form ES-D-1 Facility: MP2 Scenario No.: ES04LI 1 Op-Test No.: 1 Examiners: Operators:
Initial Conditions: 100% Power, EOL, RCS Boron is 35 ppm, Equilibrium Xenon, Bus 24E is aligned to Bus 24D. SG blowdown is 25 gpm on each SG. All swing components are aligned to Facility 2, Facility 2 is protected. Four hours prior to this shift, a minor earthquake, (0.09 q ZPA) was felt. No equipment is out of service.
Turnover:
100% Power. Facilitv 2 is protected. RCS Boron is 35 ppm, Blend ratio is 1 6 5 : l . SGBD @ 25 gpm per SG, 24E aligned to 24D, Minor earthquake about 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago. All actions for AOP 2562, Earthquake, are complete. CTMT entw made.
Discovered 5 gpm leak on CH-442. RC-200 AVMS 00s. Need to perform SP 2654B, Forcinq Sprays. Crew is periodically pumping CTMT sump.
Event I Malf. I Event Event No. I No. I Type* Description 2
I NA SWOlC 1 N (SROI C(B0P)
Commence Forcing Sprays IAW SP 2654B.
Loss of C Service Water Pump.
C (SRO) 3 FW38B I (BOP) Feedwater Heater 6A Level Transmitter, L-5043A, fails low I (SRO) 4 RCOGA C(ATC) PORV, RC-402, leakage requires closing block valve C (SRO) 1 5 RC04 3% R (ATC) Plant shutdown required by Tech Specs, using AOP 2575, Rapid Downpower.
RCS leakage increase resulting in a LOCA and plant trip.
4 I*
Alarm A-4 C (ATC) A Containment Air Cooling Fan high vibration alarm.
Tube rupture in #I SG.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: MP2 Scenario No.: ES04L12 Op-Test No.: 2 Examiners: Operators:
Initial Conditions: 1% Power, EOL, RCS Boron is 466 ppm, Equilibrium Xenon, Bus 24E is aligned to Bus 24C. SG blowdown is 40 qpm on each SG. Group 7 CEAs are at 120 steps, Facility 2 is protected. No equipment is out of service.
Turnover:
1O h Power. Facilitv 2 is protected. RCS Boron is 466 ppm, Blend ratio is 11.8:l. SGBD @
40 gpm per SG, 24E aligned to 24C. A snow storm is in progress with sustained winds of 20-25 mph. Need to raise power to 4%, usinq PMW, to commence warming the main turbine. Reactor Engineering would like to leave Group 7 CEAs at 120 steps up to 5%
power to allow for better AS1 control when raisinq power above 5%. OP 2203, Plant Startup is complete up through step 4.5.10.
I Event I Malf. Event Event No. I No. TY Pe* Description 1 N/A N (BOP)
R (ATC)
I (ATC)
Raise power to 4%.
PMW Addition Valve, CH-21OX, fails open.
CW02D C (BOP) D Circulating Water Screen D/P increases causing loss of D Circulating Water Pump.
RXOl B I (ATC) Channel Y Pressurizer pressure transmitter fails high.
Alarm C-8 M (ALL) #2 MSIV closes resulting in a plant trip and a steam line break on C-05 upstream of #2 MSIV.
MSO6B MS02B ED16B C (ALL) Loss of Vital Instrument Bus, VA 20.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: MP2 Scenario No.: ES04L13 Op-Test No.: 3 Examiners: Operators:
Initial Conditions: 100% Power, BOL, RCS Boron is 1201 ppm. Equilibrium Xenon, Bus 24E is aligned to Bus 24C. SG blowdown is 40 qpm on each SG. Facility 1 is protected. The Turbine Driven Auxiliary Feed Pump is out of service. F-16 is out for filter replacement.
Turnover:
100% Power. RCS Boron is 1201 ppm, Equilibrium Xenon, Blend ratio is 3.4:1, SGBD @
40 gpm per SG. Bus 24E is aligned to Bus 24C. Facilitv 1 is protected. The Turbine Driven Auxiliary Feed Pump is out of service. Radwaste Fan, F-16 is out for filter replacement.
Containment pressure is approximately 21 inches. Containment will need to be depressurized. Steps 4.13.1 through 4.13.7 are complete in OP 2314B. Chemical use has been prohibited in the Enclosure Building for the past week.
I Event NO. i Malf.
No. Twe*
Event I Event DescriPtion 1
2 II NA PCOl N (ATC)
C (ALL)
Depressurize Containment IAW OP 23148, Containment and Enclosure Building Purge.
Loss of the Plant Process Computer 3 I NA R (ATC) Restore AS1 to the normal operating range using AOP 2575, Rapid Downpower to reduce power by approximately 5%
++%E- l I (ATC)
C (BOP)
Channel C Pressurizer Pressure transmitter fails low.
Degradation of condenser vacuum requiring a continued reduction of power using AOP 2575, Rapid Downpower.
6 FW33 M (ALL) Loss of condenser vacuum requiring a plant trip and a loss of main feedwater.
7 1 EDO5C C (ALL) Overload trip of Bus 24C resulting in a complete loss of all feedwater.
8 I ES03J C (ATC) Failure of C HPSl to automatically start on SlAS resulting in loss of all HPSl Pumus.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: MP2 Scenario No.: ES04L14 Op-Test No.: 4 Examiners: Operators:
Initial Conditions: 100% Power. BOL, RCS Boron is 1201 ppm, Equilibrium Xenon, Bus 24E is aliqned to Bus 24C. SG blowdown is 25 qpm on each SG. Facilitv 1 is protected. C Charging Pump is out of service for seal replacement. B Charqing Pump is aligned to Facilitv 2 Turnover:
100% Power. RCS Boron is 1201 ppm, Equilibrium Xenon, Blend ratio is 3.4:1, SGBD @
25 gpm per SG. Bus 24E is aligned to Bus 24C. Facilitv 1 is protected. C Charainq Pump is out of service for seal replacement. B Charainn Pump is aligned to Facility 2.
The site experienced a seismic event 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> aqo. A UE/Delta 1 was declared bv Unit 3. All accessible plant piping has been visually inspected. No indications of leakage have been noted, including accessible portions of Containment. Manaqement is evaluating options for a plant shutdown.
Event Malf. Event Event TY Pe* Description CCOIA C (SRO, Trip of A RBCCW Pump BOP) l2 CV22 C(SR0, ATC)
Degraded Charging Pump I I RPolF SGOlB 1 I(SRo, ATC)
R (ALL)
Loop 1B Cold Leg temperature transmitter noisy Tube leak in #2 SG resulting in a rapid down power.
SG02B M (ALL) Tube rupture in #2 SG requiring a plant trip
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Failure of ActuationModule AM523 to actuateassociated components Loss of running HPSl Pumps I 1 M(ALL)
I MS02B Unisolable main steam line break on #2 SG in the Enclosure Building 11 * (N)ormal, (R)eactivity, (I)nstrument, (Cpnponent, (M)ajor Appendix D, Page 38 of 39
ES-301 Transient and Event Checklist Form ES-301-5
-~ ~-
Facility:
A P
P L
I C
A N
T I
SRO-I SRO-U 3
SRO-I SRO-U P
Instructions:
- 1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each evolution type; TS are not applicable for RO applicants. ROs must serve in both the at the controls (ATC) and balance of plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (IC) malfunctions and one major transient, in the ATC position.
- 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirement.
Author:
NRC Reviewer:
ES-3-1, Page 26 of 27
JOB PERFORMANCE MEASURE APPROVAL SHEET I JPM
Title:
Perform an ECP ID Number: JPM-A1 RO Revision: - 0
- 11. Initiated:
Richard J. Ashey 1/16/2005 Developer Date Ill. Reviewed: .
IV. Approved:
PLIA User Department Supervisor Date Date
JOB PERFORMANCE MEASURE WORKSHEET Facility: MP-2 Examinee:
JPM Number: JPM-A1 RO Rev. 0 Task
Title:
Perform an ECP System: Administrative Time Critical Task: Yes No X Validated Time (minutes): 35 Task No.(s): NUTIMS #121-09-195 Applicable To: SRO X RO X PEO K/A No.: 2.1.25 KIA Rating: 2.813.1 Method of Testinq Sim uIated Performance : Actual Performance: X Location:
Classroom: X Simulator: X In-Plant: X Task Standards: The examinee properly completes an ECP.
Required Materials OP 2208, Reactivity Calculations, Rev. 13-05 Lprocedures,equipment): Completed ECP Data and Analysis Sheet, OP 2208-001 ECP Reference Data Sheet, Attachment 1 General
References:
OP 2208, Reactivity Calculations, Rev. 13-05
- * *
- READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and log entries as if the evolution was actually being performed.
2 o f 18
JOB PERFORMANCE MEASURE WORKSHEET JPM Number: JPM-A1RO Rev. 0 Initiating Cues: The US has directed you to complete an ECP in accordance with OP 2208, Reactivity Calculations,without the use of the PPC.
Initial Conditions: A Reactor startup is planned to begin within the next 30 minutes with criticality anticipated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from now.
The PPC is presently unavailable, but will be returned to service prior to the startup.
Desired critical position is group 7 at 55 steps The following conditions exist:
- The plant tripped from 100% power 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago.
- The plant had been at 100% for the past 220 days.
- Present Burnup provided by Reactor Engineering is 12,988 MWD/MTU
- RCS Tavg is being maintained constant at 532°F.
Reference data taken at 0900 on 03/15/05 at 100% power is as follows:
- 572"Tavg
- 2.794 %Ap Xenon
- 0.900 Y01p Samarium
- 12,850 MWD/MTU Burnup
- Group 7 CEAs at 180 steps Data is good until 14,000 MWD/MTU Simulator Requirements: N/A
- * *
- NOTES TO EXAMINER **
- 1. Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, critical steps must be completed correctly.
- 2. When examinee states what his/her simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question examinee for details of simulated actions / observations (1.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
3of18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A1RO TITLE: Perform an ECP START TIME:
STEP 1 __ Performance Steps: Verify the following:
Reactor Engineering has completed and provided reference critical position data on Attachment 1, ECP Reference Data Sheet (ECP Data Book)
Chemistry Department has been requested to sample and determine present RCS boron concentration.
GRADE- - Standards : Examinee obtains and/or asks for Attachment 1 ECP ~
Reference Data Sheet and the RCS Boron concentration.
Cue: 0 Provide a copy of OP 2208-001, ECP Reference Data Sheet and Attachment 1, ECP Reference Data Sheet.
0 If requested, as chemistry, report that the RCS Boron concentration was reported 30 minutes ago.
Comments:
STEP 2 Performance Steps: Refer To Attachment 1 and TRANSFER Reference Critical Data.
GRADE X Standards: Examinee records the critical data on OP 2208-001, ECP Data and Analysis Sheet..
Cue:
Comments:
4 o f 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 3 -X Performance Steps: RECORD the following Estimated Status at Criticality data:
Date and time RCS temperature (TAVG)
GRADE X Standards: Examinee records the Estimated Status at Criticality is as follows:
The date is today The time is two hours from now T A V G is 532°F.
Cue:
Comments:
STEP 4 2 Performance Steps: OBTAIN present burnup from one of the following and RECORD:
"CVBURNUP" (PPC)
Reactor Engineering.
GRADE X Standards: Examinee obtains Burnup from fhe initial data sheet and records 12,988 MWD/MTU on the ECP Data and Analysis Sheet.
Cue:
Comments:
5of18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 5 2 Performance Steps: Unless otherwise specified by Reactor Engineering, CHECK core burnup change from reference data specified on Attachment 1, to present burnup, does nof exceed 1,000 MWDIMTU.
GRADE X Standards: Examinee determines the change in burnup is less than 1000 M WD/MTU.
Cue: If asked, as Reactor Engineering, there are no additional requirements for the core burnup change.
Comments:
STEP 6 Performance Steps: WHEN sample results are obtained, RECORD present boron concentration.
GRADE- -X Standards: Examinee records the recorded present boron Concentration on OF 2208-001, ECP Data and Analysis Sheet is 4600 ppm.
Cue: If asked, as chemistry, report that the RCS Boron concentration was reported 30 minutes ago.
Comments:
6 o f 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A1RO TITLE: Perform an ECP STEP 7 2 Performance Steps: Refer to Attachment 1 and RECORD Desired Critical CEA Position.
GRADE X Standards: Examinee records the Desired Critical CEA Position on O f 2208-001. ECP Data and Analysis Sheet. (group 7 at 55 steps).
Cue:
Comments:
STEP 8 X Performance Steps: DETERMINE Power Defect as follows:
- a. RECORD Reference Critical Data power value.
- b. Refer to OP 2208-018 and DETERMINE Power Defect at Reference Critical power value.
- c. Record Power Defect GRADE X Standards: Examinee records the Reference Critical Data power value on the ECP Data and Analysis Sheet Examinee refers to O f 2208-018 and determines the Power Defect at Reference Critical Power and records it on the ECP Data and Analysis Sheet.
Cue:
Comments:
7of18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 9 Performance Steps: DETERMINE Xenon Defect as follows:
- a. RECORD Reference Critical Data Xenon worth.
- b. Refer To one of the following and DETERMINE estimated Xenon worth at criticality:
Xenon-Samarium Post Trip Report (printed automatically on Control Room special typer following reactor trips)
OP2208-004 0 XENON-SAMARIUM DEMAND program on PPC 0 Reactor Engineering
- c. RECORD estimated Xenon worth at criticality
- d. CALCULATE Xenon Defect as follows and RECORD:
Reference Critical Data Xenon worth - Estimated Xenon worth = Xenon Defect GRADE X Standards: 0 Examinee records the Reference Critical Data for Xenon worth on the ECP Data and Analysis Sheet.
0 Examinee refers to OP 2208-004 to obtain the estimated Xenon worth at criticality and records the value on the ECP Data and Analysis Sheet.
0 Examinee records the calculated Xenon Defect.
Cue: The Xenon-Samarium Post Trip Report is NOT available.
Comments:
8 o f 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 10 -X Performance Steps: DETERMINE Samarium Defect as follows:
- a. RECORD Reference Critical Data Samarium worth.
- b. Refer To one of the following and DETERMINE estimated Samarium worth at criticality:
0 "Xenon-Samarium Post Trip Report" (printed automatically on Control Room special typer following reactor trips)
OP2208-011 0 "XENON-SAMARIUM DEMAND" program on PPC 0 Reactor Engineering
- c. RECORD estimated Samarium worth at criticality.
- d. CALCULATE Samarium Defect as follows and RECORD:
Reference Critical Data Samarium worth - Estimated Samarium worth = Samarium Defect GRADE X Standards: 0 Examinee records the Reference Critical Data for Samarium worth on the ECP Data and Analysis Sheet.
0 Examinee refers to OP 2208-0.11 to obtain the estimated Samarium worth at criticality and records the value on the ECP Data and Analysis Sheet.
0 Examinee calculates the Samarium Defect and records it on the ECP Data and Analysis Sheet.
Cue: The Xenon-Samarium Post Trip Report is NOT available.
Comments:
9 o f 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A1RO TITLE: Perform an ECP STEP 11 -X Performance Steps: DETERMINE CEA Worth Defect as follows:
- a. Refer To OP 2208-007 and DETERMINE CEA Worth for the following and RECORD Reference Critical Data CEA Position 0 Desired Critical CEA Position
- b. CALCULATE CEA Worth Defect as follows and RECORD:
Reference Critical Data CEA Position worth - Desired Critical CEA Position worth = CEA Worth Defect GRADE- X
__ Standards: Examinee refers to OP 2208-007 to obtain the CEA worth for the Reference Critical Data CEA Position and the Desired Critical CEA Position.
0 Examinee records the value on the ECP Data and Analysis Sheet.
0 Examinee calculates the CEA Worth Defect and records the value on the ECP Data and Analysis Sheet.
Cue:
Comments:
10 of 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 12 X
__ Performance Steps: DETERMINE Boron Defect as follows:
- a. RECORD Reference Critical Data boron concentration.
- b. RECORD present boron concentration.
- c. Refer To OP 2208-005 and DETERMINE the Inverse Boron Worth at present burnup.
- d. RECORD Inverse Boron Worth.
- e. CALCULATE Boron Defect as follows and RECORD:
(Reference Critical Data boron concentration -
Present boron concentration) / - Inverse Boron Worth
= Boron Defect GRADE X Standards: Examinee records the Reference Critical Data for Boron concentration on the ECP Data and Analysis Sheet.
Examinee records the present Boron concentration of 460 ppm on the ECP Data and Analysis Sheet.
Examinee refers to OP 2208-051 to obtain the Inverse Boron Worth at present burnup and records the value on the ECP Data and Analysis Sheet.
Examinee calculates the Boron Defect and records the value on the ECP Data and Analysis Sheet.
Cue:
Comments:
11 of 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 13 X
__ Performance Steps: DETERMINE Plutonium Buildup as follows:
- a. Refer To OP 2208-01 9 and DETERMINE Plutonium Buildup worth at criticality.
- b. RECORD Plutonium Buildup worth at criticality GRADE X Standards: Examinee refers to O f 2208-019 to obtain the Plutonium worth at criticality.
Examinee records the value on the ECP Data.
Cue:
Comments:
STEP 14 X
__ Performance Steps: DETERMINE the sum of all defects as follows:
- a. ENTER a// previously calculated reactivity defects.
- b. CALCULATE the sum of all reactivity defects and RECORD.
GRADE X Standards: Examinee records each of the defects on the ECP Data and Analysis Sheet.
Examinee adds the defects and determines records the total on the ECP Data and Analysis Sheet. (16 to -
19)
Cue:
Comments:
12 of 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 15 -X Performance Steps: DETERMINE Boron Equivalent of Defects as follows:
- a. Record the following:
Sum of defects lnverse Boron Worth at present burnup
- b. Calculate Boron Equivalent of Defects as follows and record:
Sum of Defects x lnverse Boron Worth = Boron Equivalent of Defects GRADE X Standards: 0 Examinee records the sum of defects and the inverse Boron worth on the ECP Data and Analysis Sheet.
rn Examinee calculates the value of Boron Equivalent of Defects and records it on the 0 Data and Analysis Sheet.
Cue:
Comments:
STEP 16 X
__ Performance Steps: DETERMINE Boron Equivalent of Reactivity Change Due to Burnup as follows:
- a. If the difference between present burnup and Reference Critical Data burnup is less than or equal to 200 MWD/MTU, record N/A in this section and go to step 4.1.17.
GRADE X Standards: Examinee determines that this step is Not Applicable and enters N/Aon the ECP Data and Analysis Sheet.
Cue:
Comments:
13 of 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 17 ~ X Performance Steps: DETERMINE Required Boron Change for Criticality as follows:
- a. Record the following:
Boron Equivalent of Defects If any, Boron Equivalent of Reactivity Change Due to Burnup.
- b. Calculate critical boron concentration as follows and record:
Present Equivalent of Defects + Boron Equivalent of Reactivity Change Due to Burnup = Required Boron Change.
GRADE X Standards: 0 Examinee records the value for Boron Equivalent of Defects on the ECP Data And Analysis Sheet. (-16 to
-19 should be entered.)
Examinee determines that the Boron Equivalent of Reactivity Change due to Burnup is N/A.
0 Examinee calculates the Required Boron Change and records it on the ECP Data and Analysis Sheet. (-1 6 to -19 should be entered.)
Cue:
Comments:
14 of 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 18 Performance Steps: DETERMINE Critical Boron Concentration as follows:
- a. Record the following:
0 Present Boron Concentration Required Boron Change.
- b. Calculate the Critical Boron Concentration.:
Present Boron Concentration + Required Boron Change = Critical Boron Concentration.
GRADE X Standards: 0 Examinee records the value for Present Boron Concentration on the ECP Data And Analysis Sheet.
(460 should be entered.)
Examinee records the value for Required Boron Change on the ECP Data And Analysis Sheet. (-7 6 to
-1 9 should be entered.)
0 Examinee calculates the critical boron concentration and records it on the ECP Data and Analysis Sheet.
(441 to 444 should be entered)
Cue:
Comments: Per OP-2202 step 2.3.1 calculated boron concentration can be + or - 10 ppm.
431 to 454 ppm is acceptable.
15 of 18
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AIR0 TITLE: Perform an ECP STEP 19 X
__ Performance Steps: DETERMINE Limits on CEA Position at Criticality as follows:
- a. Record the following:
CEA worth for Desired Critical CEA Position.
Calculate CEA worth at minimum insertion.
Calculate CEA worth at maximum insertion.
- b. Refer to OP 2208-007 and calculate CEA position at minimum and maximum insertion and record on ECP Data and Analysis Sheet.
Desired Critical CEA Position worth + and - 0.5 %delta rho.
GRADE X Standards: Examinee records the value for Desired Critical CEA Position on the ECP Data And Analysis Sheet. (.710 to .75 should be entered.)
Examinee records the value for minimum CEA worth on the ECP Data And Analysis Sheet. (. 20 to .25 should be entered.)
Examinee records the value for maximum CEA worth on the ECP Data And Analysis Sheet. (1.0 to 1.251 should be entered.)
Examinee calculates the CEA position at minimum and maximum insertion and records it on the ECP Data and Analysis Sheet.(Mimimum = Group 7 @ 145 to 155, Maximum = Group 6 @ 55 to 95 should be entered)
Cue:
Comments: The following band is acceptable:
Minimum 155 to 145 steps in Group 7 Maximum 97 to 55 steps in Group 6 Comments: When the examinee completes the ECP, this JPM is complete.
STOP TIME:
16 of 18
VERIFICATION OF JPM COMPLETION Job Performance Measure No. JPM-A1 RO Rev. 0 Date Performed:
Operator:
Evaluator(s):
For examinee to achieve a satisfactory grade, &LJ critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a Satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 35 Actual Time to Complete (minutes):
Resu It of J PM: (Denote by an S for satisfactory or a u for unsatisfactory)
Areas for Improvement:
17 of 18
EXAMINEE HANDOUT JPM ID Number: JPM-A1RO Initiating Cues: The US has directed you to complete an ECP in accordance with OP 2208, Reactivity Calculations, without the use of the PPC.
Initial Conditions: A Reactor startup is planned to begin within the next 30 minutes with criticality anticipated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from now.
The PPC is presently unavailable, but will be returned to service prior to the startup.
Desired critical position is group 7 at 55 steps The following conditions exist:
- The plant tripped from 100% power 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago.
- The plant had been at 100% for the past 220 days.
- Present Burnup provided by Reactor Engineering is 12,988 MWD/MTU
- RCS Tavg is being maintained constant at 532°F.
Reference data taken at 0900 on 03/15/05 at 100% power is as follows:
- 572"Tavg
- 2.794 %Ap Xenon
- 0.900 %.\p Samarium
- 12,850 MWD/MTU Burnup
- Group 7 CEAs at 180 steps Data is good until 14,000 MWDlMTU 18 of 18
JOB PERFORMANCE MEASURE APPROVAL SHEET I. JPM
Title:
RO Taq Clearance Preparation ID Number: JPM-A2RO Revision: -0 II. Initiated:
1/28/05 Developer Date Ill. Reviewed:
I Technic I Reviewer IV Approved:
User Department Supervisor Date Date
SUMMARY
OF CHANGES 1
I I -[-
All 8. Date DESCRIPTION REVICHANGE I,
i 1 Developed new JPM
~
11-15-2005 0 IDAPI 2
JOB PERFORMANCE MEASURE WORKSHEET Facility: MP-2 Examinee:
JPM Number: __.
JPM-A2RO Rev. - 0 Task
Title:
Perform Tagging Operations System: Administrative Time Critical Task: Yes No X Validated Time (minutes): 25 Task No.(s): NUTIMS #I 19-03-170 Applicable To: SRO X RO X PEO X KIA No.: 2.2.13 KIA Rating: 3.613.8 Method of Testing:
Simulated Performance: X Actual Performance: -
Location:
Classroom: X Simulator: X In-Plant: X Task Standards: At the completion of this JPM, the examinee will present a recommended tagging clearance to the tagging authority.
- The clearance must be similar to the ANSWER KEY attached to this JPM except for the exceptions as noted in the step 3 of this JPM.
Required Materials - WC 2 "Tagging" (procedures, equipment): - P&ID 25203-26027 sheet 2 of 4
- P&ID 25203-3001 1 sheet 12F
- OP-233OC-001 Genera I
References:
WC 2, Section 1.3 (Rev. 6-06)
- * *
- READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Contr-ol Room, including logs. Make all written reports, oral reports. alarm acknowledgments, and log entries as if the evolution was actually being performed.
3
FOR TRAINING ONLY Manual Tagout Sheet ANSWER KEY 1, Tagout Number 2. Date 3. AWC) Number (or Multiple) 4. Contact Person Tagout Number
!33 OC62-003 Todav M2-04-03686 V. Team
- 5. Equipment 8. Tag Lift Sheet Attached [Coinm. 3.41 I_ Yes
-CHUr- 123 Chill
? (b . W w p(1-491- . 3.
- 9. Additional AWOs under this tagout - Yes
- 6. Reason Tagged 10. Partial Restoration __ Yes w e ?~-CHW-123. 1-e,a.t
- 7. Special Instructions/Cautioii 1 1. Prepared by zontact chemistry for draining instructions and NPDES considerations. Examinees Naine h Note: Initid position.fiir Blue Tugs. Nf2 ifposition not required 5 Red: 2-CHW- 126. X-l96B Outlet Isolation Turbine Building 146 (Closed)
N o Tag: 2-CHW-13 7 Chi11
-? L Water Pump (P-149C) noD - 17 T u r b u d U h g 14 6 . (QLEJ) 7 .
3 Red; 2-CHW- 147, Chill Water P u m ( P - 1 4 9 0 Discharge Drain Turbine Building 146 (Open) 9 Red; 2-CHW- 174, P 149C Crosstie Header Vent, Turbine Building 146 (Open)
I ! I I3a. Tagout correct and equipment map be isolated SMAJS notified for power block Boundary approved by:
Authorized to be huiifi bv:
Levelof Use STOP THINK AC r REVIEW Information
JOB PERFORMANCE MEASURE WORKSHEET JPM Number: JPM-A2 RO Rev. 0 Initiating Cues: The WC-SRO has reviewed the work package and has directed you to prepare a tagout for 2-CHW-123 "Chill Water Pump (P-149C) Discharge Isolation" valve.
The valve must be replaced due to leakage past the seat.
Restoration information is not required.
The Tagout Number (Section Number) is 233OC62-003 The AWO number is M2-04-03686 The contact person is V. Team Chemistry will advise as to the disposal of water per NPDES.
All drawings have been verified "Controlled, Approved, and Up to Date".
The examiner will review and approve the tagout.
Initial Conditions: 2-CHW-123 "Chill Water Pump (P-149C) Discharge Isolation" valve is leaking by it's seat.
Maintenance advised removal and replacement of the valve.
The Station Tagging Computer Program is unavailable.
The need for a manual tagout has been evaluated and approved by all required personnel.
The tagout will be entered into the computer as soon as the computer is available.
Simulator Requirements: None
- * *
- NOTES TO EXAMINER * * * *
- 1. Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, critical steps must be completed correctly.
- 2. When examinee states what hidher simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question examinee for details of simulated actions / observations (i.e. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
4
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A2RO TITLE: RO Tag Clearance Preparation START TIME:
STEP 1 X Performance Steps: Per WC-2, Attachment 8, Manual Tagouts
- Prepare a Manual Tagout using (Attachment 9), Manual Tagout Sheet, and appropriate sections in this procedure.
GRADE- __X Standards: The examinee obtains a copy of WC-2. Tagging, and WC-2 Attachment 9 Manual Tagout Sheet.
Using the following references;
- P&ID 25203-26027 sheet 2 of 4
- P&lD 25203-3001 1 sheet 12F
- OP-233OC-001 Chilled Water System Valve Alignment The examinee determines the:
- Components being tagged.
- Colors for each tag.
Cue: 0 When requested, provide the examinee with the required documentation, including the enclosed WC2, Tagging.
0 If requested, provide examinee with Attachment 7, Tagout Request.
Comments: The examinee may use equivalent documentation for determining components to be tagged.
5
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A2RO TITLE: RO Tag Clearance Preparation STEP 2 X Performance Steps: Enter the sequential steps for establishing a safe working area to include:
- Components
- Equipment ID
- Tag color
- Appropriate instructions
- Appropriate Tag Position GRADE Standards: On attachment 9, enter the following:
- Tagout number
- Date
- A WO number
- Contact person
- Equipment
- Reason Tagged
- Special instructions Cue:
Comments: Special Instructions may reference chemistrys involvement in draining fluids and/or NPDES .
6
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-AZRO TITLE: RO Tag Clearance Preparation STEP 3 X Performance Steps: Enter the component name, identification number, location, tag type, and required position on Attachment 9.
GRADE Standards: Examinee enters the following information on Attachment 9:
- 1. Yellow, P149C-HSt Non- Vital Chilled Water Pump C Turbine Building 146. (Optional)
- 2. Red. 8 2 I 75 P149C Non- Vital Chilled Water Pump C!
Turbine Building 31 6:. (Open)
- 3. Red, B2174, X196B Vital Chiller Supplemental Turbine Building 31 6; (Open)
- 4. Red; 2-CHW-116, Chill Water Pump (P-149C)
Suction Isolation, Turbine Building 146 (Closed)
- 5. Red; 2-CHW-125, P-1498 Cross Tie to X-196B Turbine Building 146 (Closed)
- 6. Red; 2-CHW- 126, X- 196B Outlet Isolation Turbine Building 146 (Closed)
- 7. No Tag: 2-CHW-123, Chill Water Pump (P- 149C)
Discharge Isolation Turbine Building 146: (Open)
- 8. Red; 2-CHW-147, Chill Water Pump (P-149C)
Discharge Drain Turbine Building 146(Open)
- 9. Red; 2-CHW-174, P149C Crosstie Header Vent, Turbine Building 146 (Open)
Cue:
Comments: The component order may differ slightly provided:
- Breakers, B2175 and B2174, are tagged open before the boundary valves are closed, (Le., the pump & compressor breakers must be opened prior to closing the pump discharge and suction valves).
- The boundary valves are closed before opening the vent and drain valves.
7
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A2RO TITLE: RO Tasl Clearance Preparation
~~ ~
STEP 4 - Performance Steps: Complete block number 11, Prepared by:
GRADE Standards: Examinee enters his (her) name in block I 1 of Attachment 9.
Cue:
Comments: After this step is completed, the JPM is considered complete.
_----------5----55--5--------------
STOP TIME:
8
VERIFICATION OF JPM COMPLETION Job Performance Measure No. JPM-A2RO Rev -
0 Date Performed:
Operator:
Evaluator(s):
For examinee to achieve a satisfactory grade, ALL critical steps must be completed correctly If task IS Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No Validated Time (minutes): 25 Actual Time to Complete (minutes):
Result of JPM: (Denote by an S for satisfactory or a J .! for unsatisfactory)
Areas for Improvement:
9
EXAMINEE HANDOUT JPM Number: JPM-A2RO Rev. 0 lnitiatinq Cues: The WC-SRO has reviewed the work package and has directed you to prepare a tagout for 2-CHW-123 "Chill Water Pump (P-149C) Discharge Isolation" valve.
The valve must be replaced due to leakage past the seat.
Restoration information is not required.
The Tagout Number (Section Number) is 233OC62-003 The AWO number is M2-04-03686 The contact person is V. Team Chemistry will advise as to the disposal of water per NPDES.
All drawings have been verified "Controlled. Approved, and Up to Date".
The examiner will review and approve the tagout.
Initial Conditions: 2-CHW-123 "Chill Water Pump (P-149C) Discharge Isolation" valve is leaking by its seat.
Maintenance advised removal and replacement of the valve.
The Station Tagging Computer Program is unavailable.
The need for a manual tagout has been evaluated and approved by all required personnel.
The tagout will be entered into the computer as soon as the computer is available.
l-4 0
n E
2 Y
1 0
M 4
d
JOB PERFORMANCE MEASURE APPROVAL SHEET I. JPM
Title:
Review RWP and Survey Map ID Number: JPM-A3RO Revision: -0 II. Initiated:
e$&
R. J. Ashey 10/29/04 Developer Date II I . Reviewed:
IV. Approved:
User Department Supervisor Date 4 Nuclear Trai g Supervisor
JOB PERFORMANCE MEASURE WORKSHEET Facility: MP-2 Examinee:
JPM Number: J PM-A3 RO Rev. 0 Task
Title:
Review RWP and Survev Mao System: Radiation Control Time Critical Task: Yes No X Validated Time (minutes): 10 Task No.(s): NUTIMS # 404-01-004 Applicable To: SRO RO X PEO K/A No.: 2.3.1 KIA Rating: 2.613.0 Method of Testinq:
Sim ulat ed Performance: Actual Performance: X Location:
Classroom: X Simulator: X In-Plant: X Task Standards: At the completion of this JPM the examinee has reviewed the applicable RWP and survey map to determine the radiological requirements to perform the assigned task.
Required Materials Operations blanket RWP No. 5.
Iprocedures,equipment): Survey map for -45' 6" elevation of the Auxiliary Building General
References:
RPM 5.2.2, Basic Radiation Worker Responsibilities, Rev. 009-03
- * *
- READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and 1oq entries as if the evolution was actuallv beinq performed.
2
JOB PERFORMANCE MEASURE WORKSHEET JPM Number: JPM-A3RO Rev. 0 Initiating Cues: 0 You have been directed to align 2-Sl-306, SDC Total Flow Control Valve, for remote operation and to perform the position indication surveillance.
0 Based on previous experience, you estimate that this task will take 10 minutes.
0 State the radiological requirements for entering this area. Include in your discussion:
- Which RWP task (job step) is appropriate for this assignment
- Protective clothing required in the work area
- Highest radiation level in the work area
- Expected dose for this assignment
- Dose rate alarm 0 The examiner will act as Health Physics (HP) for any related questions.
Initial Conditions: 0 The plant is in MODE 3 and cooling down in preparation for a refueling outage.
The crew is preparing the Shutdown Cooling System for operation in accordance with OP 2207, Plant Cooldown.
Simulator Requirements: N/A
- * *
- NOTES TO EXAMINER * * * *
- 1. Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, ALL critical steps must be completed correctly.
- 2. When examinee states what hidher simulated action/observation would be, read the app ropriat e "Cue".
- 3. If necessary, question examinee for details of simulated actions / observations (Le. "What are you looking at?" or "What are you observing?").
- 4. Under NO circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
3
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A3RO TITLE: Review RWP and Survey Map START TIME:
STEP 1 __ Performance Steps: Review Operations Blanket RWP No. 5 and Radiation Survey Figure 27.
GRADE- __ Standards: Examinee reviews Operations Blanket RWP No. 5 and Radiation Survey Figure 27.
Cue: Provide examinee with Operations Blanket RWP No. 5 and Radiation Survey Figure 27.
If required, state that the HP brief is complete with a reminder to follow the requirements of the RWP.
Comments: 0 Examinee may state that a briefing with HP is required prior to entry into the work area.
0 The examinee may perform the following steps in any order.
STEP 2 X Performance Steps: Review survey map and determine the highest radiation level in the work area.
GRADE X Standards: Examinee reviews the survey map and states that the highest radiation level in the work area is 90 rnrhr.
Cue:
Comments: The examinee may point out the 200 mr/hr hot spot on the SDC Heat Exchanger, but the assigned task does NOT require him/her to approach that area.
4
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A3RO TITLE: Review RWP and Survey Map STEP 3 Performance Steps: Review the RWP and determine the following:
0 Which RWP task (job step) is appropriate for this assignment Protective clothing required in the area x 0 Expected dose for this assignment
-X Dose rate alarm GRADE Standards: Examinee reviews the RWP and states that:
- - x 0 Task (job step) No. 1 is appropriate for this task
- - X There is NO contamination in the work area; therefore, NO additional protective clothing is required
- - X Expected dose is approximately 75 mr
- - X 0 Dose rate alarm is 100 mr/hr Cue: if required, ask examinee what protective clothing helshe thinks should be worn.
Comments: Although NO protective clothing is required, the examinee may opt to don a lab coat and/or gloves due to the potential for contamination.
Comments: After this step is completed, the JPM is considered complete.
STOP TIME:
5
VERIFICATION OF JPM COMPLETION Job Performance Measure No. JPM-A3RO Rev. 0 Date Performed:
Operator:
Evaluator( s):
For examinee to achieve a satisfactory grade, critical steps must be completed correctly. If task IS Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No X Validated Time (minutes): 10 Actual Time to Complete (minutes):
Result of JPM: (Denote by an S for satisfactory or a u for unsatisfactory)
Areas for Improvement:
6
EXAMINEE HANDOUT JPM ID Number: JPM-A3R initiating Cues: You have been directed to align 2-Sl-306, SDC Total Flow Control Valve, for remote operation and to perform the position indication surveillance.
0 Based on previous experience, you estimate that this task will take 10 minutes.
0 State the radiological requirements for entering this area. Include in your discussion:
- Which RWP task (job step) is appropriate for this assignment
- Protective clothing required in the work area
- Highest radiation level in the work area
- Expected dose for this assignment
- Dose rate alarm The examiner will act as Health Physics (HP) for any related questions.
Initial Conditions: 0 The plant is in MODE 3 and cooling down in preparation for a refueling outage.
0 The crew is preparing the Shutdown Cooling System for operation in accordance with OP 2207, Plant Cooldown.
7
RADIATION WORK PERMIT - 5 Code 1 Year 1RWP Number 5 1, 0005
]Rev. IRWP Start
- 1. 0 0 I .Ol-jan-2005
~ R W PType I. G IRWP I.
Category POWER I
~ R W PExpiration 05-jan-2006 I
1, RWP DESCRIPTION Operations General RWP TASK
SUMMARY
Job Description 1 Operations activities in RCAs, Radiation Areas, and H 2 (TSLHRA) Operations activities in Tech Spec Locked Hi 3 Operations Training clasees activities in R E I D , Radia 4 Charging System activities by Operations; walkdowns, ALARA INPOFMATION ALARA Review Hours- Estimated Authorized Internal(DAC)- Estimated Authorized External(mRem)-Estimated Authorized No 26000 00000 0000 0000 026000 026000 SPECIAL INSTRUCTIONS
- enera1 access to RCAs to perform routine and special Entry on this RWP requires the worker to understand rounds, inopections, tagging, surveillances, and canply with the following
m d training and qualifications during Power *
- Be knowledgeable of radiological conditions of 3perations. the work area
- Adhere to the requirements of the RWP
- Notify HP before entering overhead areas
- Monitor electronic dosimeter frequently, especially in high noise areas
- 4 Unless specifically briefed otherwise, if DOSE RATE alarm sounds, move to a lower dose area and notify HP
- If DOSE alarm sounds, leave the area and notify HP
- I f electronic dosimeter malfunctions, notify HP BEFORE logging out
- Modesty garments will be worn whenever PCa are worn
RADIATION WORK PERMIT (5) JOB STEP I OF 4 - -
Plant Code ]Year IRWP Number IRev. IRWP Start JRWP Type ~ R W PCategory IRWP Expiration I I 5 1, 0005 1.00 I 01-jan-2005 I. G I POWER I OS-)an-2006 I Responsible Individual/Exteneion WILLIAM HOFFNER/ 62 00 I Department/Company OP/DNC 1 Job Supervisor/Extension WILLIAM HOFMER/6 2 00 Department/Company
\Building /Floor 2 AUX i Zone i Location LEVELS/MULTIPLE AREAS i Plant Equipment MISCELLANEOUS u - 2 EQUIPMENT i Rad. Area Type WRXTTBN DESCRIPTION OF JOB (MATERIALS & XETHODS)
Operations activitiee in RCAs, Radiation Areas. and High Radiation Areas.
ALARA Review Hours- Estimated Authorized 1nternallDAC)- Estimated Authorized External(mRem)-Estimated Authorized No 10000 00000 00000 00000 010000 010000 System Code Component Code Task NRC Task Alara Zone Locati on Plant Equipment 2000 MISC 0 PS RO ZMISC 2200 2MISC
~ ~ ~ ~~ ~ ~~
SURVEY XBASURKMENTS RADIATION IMR/HR) CONTAMINATION(DPM/lOOc712 AIRBORNE (DAC)
I Review latest radiological surveys or historical data prior to entering SPECIAL INSTRUCTIONS
-.. NO e n t r y to Tech Spec Locked H i g h Radiation Areas Notify HP before venting or draining any contaminated permitted using this Job Step. systems.
PCs required in contaminated areao.
HP supervision may adjuet protective clothing requirements based on any of the following:
- FME controls Requirements f o r High Radiation Area entriee:
Dose rate meter or alarming dosimeter AND knowledge of area dose rates, OR continuous HP coverage Health Physics briefing for High Radiation Areas Lab coats may be worn for inspection-related tasks only; no physical work in contaminated areas may be performed.
Dose L i m i t Alarm(Stay T i m e ) = 0025 m r e m D o s e Rate Alarm= 0100 m/hr Elapsed T i m e Alarm= 0000 m i n .
Health Physics Representative Date RWP Term/Rev Date/Time Tenninated/Rev by
RADIATION WORK PERMIT ( 5 ) JOB STEP 2 OF 4 - -
I Plant Code 2
Year 5 I RWP Number 0005 I Rev.
00 I RWP Start 01-jan-2005 I RWP Type G I RWP Category POWER I RWP Expiration 0 5 - jan-2006 I 1
Responsible Individual/Extension Department/Company Job Supervieor/Extension Department/Company WILLIAM HOFFNER/LZOO OP/DNC WILLIAM HOFFNER/6200 OP/DNC I I I I Building Floor Zone Locati o n Plant Equipment Rad. Area Type 2 AUX LEW/MULTIPLE AREAS MISCELLANEOUS U- 2 EQUIPMENT ALARA INFORHATION ALARA Review Hours- Estimated Authorized Internal(DAC)- Estimated Authorized External(mRem)-Estimated Authorized NO 05000 00000 00000 00000 005000 005000 System Code Crmponent C o d e Task NRC Task Alara Zone Location Plant Equipment 2000 MISC OPS RO 2HISC 2200 2MISC SURVEY MgASURBMEWl'S RADIATION (MR/HR1 CO~AMINATION(DPM/100M2) AIRBORNE (DAC)
Solid Rad Waste 5 - 1500 <1K
-5' West Penetration 10 - 2000 c1K Let down Heat Exchanger 10 - 1200 c 1x c.3 I ~ ~~ ~~~
Dose Limit A l a m i S t a y Time)= 0 0 5 0 m r e m E l a D s e d T i m e Alarm= 0000 m i n .
D o s e Rate Alarm= 0 5 0 0 mr/hr REQUIRENBNTS Lab coat Health Physics Coverage Periodic Electronic dosimeter TLD Minimum Margin:
0225 w e m Health P h p ~ c sRepresentative Date RWP Term/Rev Date/Tirne Tenninated/Rev by I
RADIATION WORK PERMIT - ( 5 ) JOB STEP 3 OF 4 -
Plant Code 2
Year RWP Number 5 1 'I 0005 Rev.
1'00 I
RWP Start 1'01-jan-2005 I I RWP Type G I, RWP Category POWER I I RWP Expiration 05-jan-2006 I 1
Responsible Individual/Extension Department/Company Job Supervisor/Extension Department/Company WILLIAM HOFFNER/CZOO OPlDNC WILLIAM HOFFNER/BZOO OP/DNC 2 AUX IBuilding IFloor I Location LEVELS/MULTIPLE AREAS Plant Equipment Rad. Area Type i
WRITTEN DESCRIPTION OF JOB (WTBRIALS & METHODS)
ICperotions Training classes activities in R C A s , Radiation Areas, and High Radiation Areas.
I ALARA Review Hours- Estimated Authorized 1nternallDAC)- Estimated Authorized External(rnRem)-Estimated Authorized No 01000 00000 00000 00000 001000 001000 I System Code 2000 lcomponent Code MISC
~ [Taik OPS INRC Task RO I Alara Zone ZMISC ILocation 2200 I Plant Equipment 2MISC SIJRVKY MRASDREXXNTS RADIATION ( M R / H R ) CONTAMINATION ( DPM/ 10 0 (312) A IRBORNE (DAC)
I Review latest radiological surveys or historical data prior to enterinq I SPECIAL INSTRUCTIONS I N O entry to Tech spec Locked H i g h Radiation Area-permitted using this Job Step.
PCs required in contaminated areas.
HP oupervieion may adjust protective clothing requirements based on any of the following:
- Heat stress evaluations R1E controls Requirements for High Radiation Area entries:
D o s e rate meter or alarming doeimeter AND knowledge of area dose rates, OR continuous HP coverage
- Health Physics briefing for High Radiation Area6 Lab coats may be worn for inspection-related tasks only; no physical work in contaminated areas may be performed.
Dose L i m i t A l a r m ( S t a y Time)= 0025 mrem D o s e Rate A l a r m = 0100 mr/hr Elapsed Time A l a r m = 0000 m i n .
RBQUIREHKNTS Protective clothing: Lab coat Cotton linere Health Physics Coverage Booties Routine 9 Coveralls Electronic doeimeter
- Shoe covers TLD Minimum Margin:
- Rubber gloves 0125 mrem
- Modesty qarments H e a l t h P h y s i c s Representative Date II IRWP Term/Rev Date/Time I
II Terminated/Rev by
Plant Code 1 Year IRWP Number 1.
[Rev. IRWP Start IRWP Type ~ R W PCategory IRWP Expiration 1, 1, 1
5 0005 1.00 1.01-jan-2005 I. G I. 05-jan-2006 Responsible Individual/Extension Department/Company Job Supervisor/Exteneion Department/Company WILLIAM HOFFXER/62OO OP/DNC WILLIAM HOFFNJZR/CZOO OP/DNC Building 2AUX I Floor
-25' I
Zone Location CHARGING PUMP CUBICLES Plant Equipment MISCELLANEOUS 6
Rad. Area Type r-
~~~~
Charging System activities by Operations, walkdowns, inspections, necessary support activities ALARA INFORXATION I ALARA Review NO IHours- Eetimated Authorized 10000 00000 I Internal(DAC)- Estimated Authorized 00000 00000 1 External(rnRem)-Estimated Authorized 010000 010000 I I System Code 2000 (Component Code PUMP ITask OPS
( N R C Task (Alara Zone RO 2226 1 Location 2226 Plant Equipment 12300 I SURVBY M E A S U R E X ~ S RADIATION (MR/HR) coNTnmIN~TION(DPM/lOOM2) AIRBORNE (DAC)
Review latest radiological surveys or hiotorical data before entering RCA .
SPECIAL INSTRUCTIONS
-' I I
NO entry to Tech Spec Locked High Radiation Areas permitted using this Job Step.
JPCs required in contaminated areas.
HP will eetablieh dosimetry placement baeed on intended tasks and work area surveys.
Notify HP before disassembling components.
HP supervision may adjust protective clothing Notify HP before entering overhead areas.
requirements based on any of the following:
TEDE ALARA reviews Heat stress evaluations FME controls Requirements for High Radiation Area entries:
Dose rate meter or alarming dosimeter AND knowledge of area dose rates, OR continuous HP coverage Health Physics briefing for High Radiation Areas Lab coats may be worn for inspection-related taeks only; no physical work in contaminated areas may be performed.
D o s e Limit Alarm(Stay Time)= 0025 mrem Dose Rate Alarm= 0100 ~ / h r Elapsed Time Alarm= 0000 mln.
RBQUIREMENTS Lab coat Health Physics Coverage Routine Electronic dosimeter TLD Minimum Margin.
0125 mrem Health Phyeics Repreeentative Date RWP Term/Rev Date/Time Terminated/Rev by
TI ,'a$
bj6r2 p - ,+
~
i-c JOB PERFORMANCE MEASURE APPROVAL SHEET I. JPM
Title:
Use RATS to Determine and Prioritize the Safetv Functions ID Number: JPM -A4RO Revision: -0 It. Initiated:
1121I05 Developer Date II I . Reviewed:
IV. Approved:
User Department Supervisor Date Date
SUMMARY
OF CHANGES 1 A l l & Date 1 DESCRI PTlON REVKHANGE 1 1111912004 Developed new JPM 0 IDAP)
I 2
JOB PERFORMANCE MEASURE WORKSHEET Facility: MP-2 Examinee:
JPM Number: JPM-A4RO Rev. 0 Task
Title:
Use RATS to Determine and Prioritize the Safety Functions System: Administrative Time Critical Task: Yes No X Validated Time (minutes): 20 Task No.(s): NUTIMS #OOO-05-226 Applicable To: SRO X RO X PEO KIA No.: 2.4.21 K/A Rating: 3.7/4.3 Method of Testing:
SimuIated Performa nce X Actual Performance:
Location:
Classroom: X Simulator: X In-Plant: X Task Standards: The examinee will correctly identify and prioritize the Safety Function Success Paths.
Required Materials Form 2540-002 rev. 001, Functional Recovery Resource Iprocedures,equipment): Assessment Tree 2540 rev-21 page 8, Safety Function Status Checklist General
References:
EOP 2540, Functional Recovery
- * *
- READ TO THE EXAMINEE * * *
- I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. You may use any approved reference materials normally available in the Control Room, including logs. Make all written reports, oral reports, alarm acknowledgments, and loa entries as if the evolution was actually being performed.
3
JOB PERFORMANCE MEASURE WORKSHEET JPM Number: J PM-A4RO Rev. 0 lnitiatinq Cues: The crew has just transitioned to 2540. You are an extra license on shift. The SM has directed you to:
- Determine the Safety Function Success Paths
- Prioritize all nine safety functions
- Submit your determination to the SM for comparison.
The plant conditions are as follows.
Initial Conditions: At the completion of EOP 2525, the following conditions exist:
- CEAs 45 and 46 are fully withdrawn, all other CEAs are fully inserted
- Power is at 2 x and stable
- A and B Charging Pumps are operating
- Both 6.9 kV buses are de-energized
- Bus 24C is energized from the A DIG (RSST is de-energized)
- Bus 24D is de-energized (B D/G will not start)
- Both DC buses are energized
- VA-10 and VA-20 are energized
- Facility 1 RBCCW and Service Water Pumps are operating
- A Auxiliary Feed Pump tripped when started
- The Terry Turbine will not start
- #1 SG level is 95 inches and lowering
- #2 SG level is 280 inches and slowly lowering
- #1 SG pressure is 485 psia and lowering
- #2 SG pressure is 820 psia and stable
- Pressurizer pressure is 1700 psia and slowly rising (Pressurizer level is 9% and rising very slowly)
- CETs are reading 475 deg. F and slowly lowering (CET subcooling is 138 deg F and rising)
- Loop delta-T is 36 deg F and stable
- Containment pressure is 27 psig and lowering
- Containment rad monitors are not in alarm and stable
- SJAE and blowdown rad monitors are not in alarm and stable
- Enclosure Building D/P is normal.
- SIAS, ClAS, EBFAS, MSI, and CSAS have actuated
- A Containment Spray Pump flow is 1450 gpm.
- RVLMS is 100%
- RWST is 97% and lowering slowly
- Total SI flow is 0 gpm Simulator Requirements: None 4
- * *
- NOTES TO EXAMINER * * * *
- 1. Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, & J critical steps must be completed correctly.
- 2. When examinee states what hidher simulated action/observation would be, read the appropriate "Cue".
- 3. If necessary, question examinee for details of simulated actions / observations (i.e. "What are you looking at?" or "What are you observing?").
4 Under circumstances must the examinee be allowed to manipulate any devices during the performance of this JPM (in-plant only).
5
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A4RO TITLE: Use RATS to Determine and Prioritize the Safety Functions START TIME:
STEP 1 Performance Steps: Identify success paths to be used to satisfy each safety function using both of the following:
- Resource Assessment Trees
- Safety Function Tracking Page GRADE- X
__ Standards: The examinee identifies the Safety Function Success Paths for the given plant conditions per attached Safety Function Status Checklist.
Cue:
Comments: Give the examinee a copy of the Resource Assessment Trees and the Safety Function Tracking Page.
STEP 2 Performance Steps: Prioritize safety functions to be addressed first based on ALL of the following:
- Safety functions which do not meet the Safety Function Status Checklist for the selected success path.
x - Safety functions for which the equipment to support the success path is not operating.
-X - Safety functions for which success path three has been selected.
x - Safety functions for which success path two has been selected.
- Safety functions for which success path one has been selected.
6
PERFORMANCE INFORMATION JPM ID NUMBER: JPM-A4RO TITLE: Use RATS to Determine and Prioritize the Safety Functions GRADE X Standards: The examinee prioritizes the Safety Functioi? Success Paths for the given plant conditions per attached Safety Function Status Checklist.
Cue:
Comments: When the examinee submits the completed Safety Function Status Checklist, this JPM is complete.
STOP TIME:
7
VERIFICATION OF JPM COMPLETION Job Performance Measure No. JPM-A4RO Rev. 0 Date Performed:
Operator:
Evaluator(s):
For examinee to achieve a satisfactory grade, & critical steps must be completed correctly. If task is Time Critical, it MUST be completed within the specified time to achieve a satisfactory grade.
Time Critical Task? Yes No Validated Time (minutes): 20 Actual Time to Complete (minutes):
Result of JPM: (Denote by an S for satisfactory or a u for unsatisfactory)
Areas for Improvement:
8
I Safety S u c c e s s Path Equipment SFSC P r ior ity I Function Operating Met I Reactivity RC-2 Y Y Control Mainte na nce MVA- Y Y 6 of Vital DC DC-1 Power
~- ~~
Maintenance MVA- Y 4 of Vital AC AC-2 Power
-~
RCS IC-2 Y 5 inventory Control RCS Pressure PC-1 Y Y Control
~ RCS and HR-3 YORN N Ccre Heat Remova I t - ~---___ ~
Containment CI-I Y Y 8
, isolation
_ ~ - __ ~___
I Containment CTPC- Y Y 2 Temperature 3 and Pressure Control Containment CCGC- Y Y Combustible I Gas Control 9
EXAMINEE HANDOUT JPM Number: JPM-A4R0 Rev. 0 Initiating Cues: The crew has just transitioned to 2540. You are an extra license on shift. The SM has directed you to:
- Determine the Safety Function Success Paths
- Prioritize all nine safety functions
- Submit your determination to the SM for comparison The plant conditions are as follows.
initial Conditions: At the completion of EOP 2525, the following conditions exist:
- CEAs 45 and 46 are fully withdrawn, all other CEAs are fully inserted
- Power is at 2 x and stable
- A and B Charging Pumps are operating
- Both 6.9 kV buses are de-energized
- Bus 24C is energized from the A DIG (RSST is de-energized)
- Bus 24D is de-energized (6 DIG will not start)
- Both DC buses are energized
- VA-10 and VA-20 are energized
- Facility 1 RBCCW and Service Water Pumps are operating
- A Auxiliary Feed Pump tripped when started
- The Terry Turbine will not start
- #I SG level is 95 inches and lowering
- #2 SG level is 280 inches and slowly lowering
- #I SG pressure is 485 psia and lowering
- #2 SG pressure is 820 psia and stable
- Pressurizer pressure is 1700 psia and slowly rising (Pressurizer level is 9% and rising very slowly)
- CETs are reading 475 deg. F and slowly lowering (CET subcooling is 138 deg F and rising)
- Loop delta-T is 36 deg F and stable
- Containment pressure is 27 psig and lowering
- Containment rad monitors are not in alarm and stable
- SJAE and blowdown rad monitors are not in alarm and stable
- Enclosure Building DIP is normal.
- SIAS, CIAS, EBFAS. MSI, and CSAS have actuated
- A Containment Spray Pump flow is 1450 gpm.
- RVLMS is 100%
- RWST is 97% and lowering slowly
- Total SI flow is 0 gpm 10
Millstone Unit 2 Functional Recovery I Page 8 of 30 Revision 21 4.0 SAFETY FUNCTION STATUS CHECKLlST SAFETY FUNCTION TRACKING PAGE EOP ENTRY TIME Equipment SFSC Priorit:
Safety Function Success Path Operating Met I I--
1 CEA Insertion I Reactivity I Boration using CVCS Control
~ RC-3 Boration using SI
~
Maintcnance of I Battery Chargers/
Vital DC Power 'MVA-DC-1 Station Batteries I
MVA-AC- 1 RSST 1 MVA -AC- 2 EDG I
~~ ~~
I MVA-AC-3 Bus 34N34B I RCS Inventory IC- 1 cvcs I Control IC- 2 Safety Injection PC- 1 Subcooled RCS Pressure Control PC-2 Saturated I 1-- -1 PC-3 PORVs I I I RCS and Core HR-1 SI not operating I I I Heat Removal HR-2 ST operating HR- 3 0-T-C Containmcn t Isolation CI-1 Automatic/Manual I
containment CTPC- 1 CARS (Normal) I I I Temperature and mc-2 CARS (Emerg)
Prcssure Control CTPC-3 Containment CCGC-1 Hydrogen Recombiners Combustible Gas C
Control CCGC-2 Hydrogen Purge I 1 I
Millstone Unit 2 EOP 254G Revision 21 Functional Recovery Page 6 of 30 INSTRUCTIONS CONTINGENCY ACTIONS NOTE If the Safe Function Status Checklist is not satisfied for the selected success pax, the us may commence the operator actions for safe functions which are not met based on Safety Function hierarchy. X e remaining Safety Functions should be prioritized as time permits.
- 6.
- IDEFJTIFY success paths to be used to satisfy each safety function using BOTH of the following:
Resource Assessment Trees Safety Function Tracking Page
- 7. PRIORITIZE safety functions to be addressed first based on ALL of the following:
- a. Safety functions which do not meet the Safety Function Status Checklist for the selected success path.
- b. Safety functions for which the equipment to support the success path is not operating.
C. Safety functions for which success path three has been selected.
- d. Safety functions for which success path two has been selected.
- e. Safety functions for which success path one has been selected.
- 8. DIRECT the STA to check that Safety Function Status Checklist Acceptance Criteria are satisfied for chosen success paths.
/qq t safety Functwn suwcss Path RC- 1 CEA Insertion bration Using CVCS
> 40 m,go direcUyt0 G Bondon Using SI 1
I f SI boratiun addition rate aoceplanccmtena below > 40 gprn, go dirwto acapfance criteria k l o w
'I londitionr ourcc OIIVC Path
~ t eceptanct a. Less than Iwo CE& not fully inxrrcd.
- a. Boratwn addition rate u > 40 gpm.
3terir b. Reactor power dropping. a.Boration addition rate is > 40 gpm,
- b. Reactor power dropping.
- c. SUR negative. b.Rcactor power dropping.
- c. SUR negative.
E. SUR negative.
a.Reactor power < IO-'%.
a.Rcactorpower <
iucces b.Resctor power stablc or dropping b.Rcactor p e r srablc or dropping. a.Rcstorpowcr < IO-'%,
'ath I RC-I I I RC-2 I b . R e m o r power stable or bopprg.
1 RC-3 I I OPS Form 2540-002 Rev. 001 Page 1 of 10 J
safely Maintenance of Function Viral DC Power 1
Success Pal h I 1 Conditions 48ov 48OV Bus 22E . BUS 22F Bnnery Battery Station Station source Charger Charger Battery Battery A B A B Motive Path Dc Bus DC B w 201 A a %tal DC Bus 201A ISenergzed Acteptancc h 12OV AC Bus VA10 is energzed Criteria
Kcwurce Tree Safety 8-2 Function Maintenance of Vital AC Power
& v i
PucCeU Path i MVA-AC-2 Emergency Diesel Gcncrator(r)
MVA-AC-3 Bus 3 4 W B hditionr ource 1otNe V 1 -
4.16 KV 4.16 KV Mtal 4.16 KV vital 416KV Bus 24C Bus 24D t I it h J.
- a. Bus 24C is energized. LLudmnl !2anuml a Bus 24C is energized
- c. Facility I RBCCW i s opernhng. b. Vital DC Bus 20lA is energucd c Facility 1 RBCCW is operaung d Facility 1 Service Water isoperating. c Faality 1RBCLW i s operatmk d Facihty 1S ~ M C WtcrC is operating CQQdhG d Facility 1 servlee Water i s operating
- a. Bur 24D is cncrgkd. !z!mwQd !Andum2
- b. Vital DC Bus 2018 is cnergned. a Bus 24D is encrgued.
rcptancc a Bus 24D LF energued b Vital DC Bus 2018 u energzed itcria c. Facility 2 RBCCW is operaling. b Vital DC Bus 2OlB IS cncrglred
- d. Facility 2 SCMW, Water ia operaling. E Facility 2 RBCCW is operating.
fccP d Faulity 2 S e ~ c Water c u opraung th LMVA-AC-1 I I MVA-AC-2 I
- d. Facility 2 Senice Water i s operating.
11 MVA-AC-3_ _I
& Tk!NK p,@, *,I OPS Form 2540-002 Rev. 001 Page 3 of 10
Reso% Tree safety Function V
Success IC-2 Path SI If SI pumps are operating. go directly 10 sfceprance criteria below V
cooditiom 1
I iourcc Available Lvl> 10%
Cntmtv -Emerg sump Level Rising t
Boric Acid Gravity GrWicg Pump Feed Feed dolive v V v
ath v Normal HPSI Charging Row R!Jl Path v I f a If SRAS has not occurred and HPSI throttldstop uitena aoptance are not met. then all avvlabk chargmg pumps arc ritcria 1 operating a Pressurucr lcvcl is > 20%. b. If SRAS has not occurred and LPSI termmailon cmtcna arc not met, then LPSI flow swthm SI llow curve.
- b. RCS subcooling is 2 minimum subcoollng lmc of the Prr c u m . c If HPSI thronlehtopcnteria are not met,then HPSI flow IS wttun SI flow curve.
- c. Reactor vessel lcvcl is z 43%. d Reactor vewl level IS e 7%
1 IC-I I IU-2 OPS Form 2540-002
. , Rev. 001 Page 4 of 10 1
W B
P 85 dk 9 h
safety Function Succerc Path IfHPSlflow> If LPSl flow >
SIam nuv~,go SI flowcurve go d i r d y to acoaptm directty to aaeptakc critwi. bslow critcri. below Conditions iource I Rur AvaJ I
Chtmt Emerg swnp Level Lvl =. 9% LVl > 9%
Aotive ath t
L J
If SRAS has not oCCurred and HPSI throttlelstop cnteria not met. then all cccptancc available charging pumps are opcrating.
riteria b. If SRAS has not occurred and US1 termination criteria are not met. then WSl flow is aithm SI flow w e .
- c. If HF'SI (hrottl4stopcriteria are not met. a. Pressurizer pressure is within then HPSI flow iswithin SI flow curve.
the P ~ C U I Vlimits.
C 1cccss Ilh I PC-2 I
Safety bdion
- AI least one steam generator WR level is less than or q u a l to 70 inches.
iucccss
'ath SG Heat Sink 1- Once-Through-
- onditions SG Available for SG Available. for Heat Removal ource c Cntmt Emcrg Stcam Dumps ADVs 88 ADVs Iotive I ilh I
- a. At least one SG Lcvel IS wtbm 40 to 70% or being restored h. If SRAS has not m r c d and t1PSI rhroitlc/siop critena Ecptance a. At leal one SG k c 1 is within 40 to 70% or being rcslored. h. CeTtcrnpcrature IS c 700°F itcria c. If SRAS has not occurred and HPSI throtrlchtop criteria arc not mct. then all avadablc chargmg pumps are
- b. If RCPs are operating, then loop delta T is 40'E operatmg.
are not met. then all evarlablc charging pumps are
- c. If RCPs are no1 operating. thcn loop delta f is < 55'E opcnhng. c If S f U S has not omtrrcd and LPST tcrrninatton alterla
- d. TH and C f l t c m p e r a t u r e is < 600°F d If SRAS h u no1 occurred and LPSI lerrmnatlon Critcria arc not me4 then LPSI flow IS wthm SI flow curve
- e. RCS subconling is 2 minimum subcooling line of the P/f curve. arc not met. then LPSI flow is w'thm SI flow a w e . d IF HF'SI throttlc/slop Cnterla are not met. then HPSI flow
- f. Rcactor VCLKI level IS 5 43%. within SI flow curve.
HR-2 OPS Form 2540-002 Rev. 001 Page 7 of 10 ---
Resource Tree Safety Function NOTE 1 Both of thc AbnormaJ Containmcnt conditions should be evaluated to determine if thc quipmcnt is rcqulrcd 1
CI-l -
IO maintain the CI 1 Acceptance Criteria.
AutomatidManual succcss Containment Path Isolation Cunbtions
- 1. (hbnt pressure < 4.42 pdg
- 2. Radialion monitors inside m m have M)unwrplaincd ANY of the followin.&
A I. Steam plant ramation alarms and no unexplained 1. Om1 pressure 2 4.42 pig. monilorr have unupluned rk. 2. Radiationmoniton inride alarm and unexplained mscs
- 3. Radiation monitoring cntmt have uncxplaincd Ouhidc cntml have no dams or unurplaincd rises unexplained alarms and M) 3. Radiation monitoring unexplained rises. outside mtmt have
- 4. Steam plant radiation unexplained alarmror monitors have no unexplained rises.
unexplained alarms and no uncmlaincd m.
Normal Containment Conditions CIAS v
- a. ONE of the following:
Steam plant radiation monitors have no unwrplamcdalarms
~p1aOcc and no unuplaincd n m .
kiteria If a S G I R cxisu. all release paths from most affected SG to the environment not hcing w d for planned release a n isolated
- b. Contiunmcnt pressure < 4.42 psia.
c Radiation monitors inside containment have no uncxplaincd a l m s and no unexplarncd rircs.
- d. Radiation monitors outside containment have no unexplained alarms and no unexpl~inedrises.
- e. SG pressure c 920 psia.
- a. ONE of the following:
Steam plant radiahon monilon have no unexplamed alarm and no unexplained rises.
- If a S W exists, all release paths born most affected SG to the environment not being used for planned release are isolatcd
- 3. Each containment penetration required to be closed for a n e n t JCUXS plant conditions has an ioolrtion valve dosed.
ath ICI-1 I OPS Form 2540-002 Rev. 001
T h e determination for the C l T C succcss path should be Containment E3ion based on containment pmssurc and not thc operating Temperature and mode (normal or cmcrgency) of the CAR Fans. Pressure Control success Gantoinment F a Containment Fans Containment Path (Nomul Made) (Emergency Mode)
Conditions Containment Containment Containment Plarurc Pressure 2 4.42 prig h 9.48 pstg e 4.42 psig c 9.48 p i g source T One Facility Paver Molivc Fwility 1 Facility 2 Facility 1 Facility 2 Avail CAR CAR F.nr FanS Power Power Power Power Avail Avail Avail Avail Path Acceptance CZitena
- a. Both CS pumps with I: 1300 gpm cach
- b. Containment pressure IS 4 51 pig.
I
- a. Containment temperature e 155-L b. Containment temperature < 19O'F. b. One CS pump w h 2 1300 gpm.
- b. Containment prcsrurc < 4.42 psig. c. Cont.mrncnt pcesaurc< 9.48 psi& c. C o n t i m m t pressure u < 51 psig.
SuaCW Path OPS Form 2540-002 Rcv. 001
Resource Tree safety Containment Combustible Gas Control Safety Function Combustible Function IS considered satisfied until the hydrogen analyzer can Gm Control be placed in senice and the warm up is complete.
c success Path Conditions source MofNe Path L
Acceptance Criiceria
- a. Contrummt hydrogen conceauatinn i
< 1.4%.
S U ~ C U a All available hydrogcn raombiners Path energized
- b. Containment hydrogen mncentratron CCGC-1