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 Categories 2
3 2
3 1
2 3, 4 7
1 2
2 2
Note:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
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).
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.
Systemsfevolutions within 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 inappropriate WA statements.
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.
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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
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.
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.
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 AK2.10 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP indicators and controls 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels AA2.07 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Pump cavitation AA1.05 Ability to operate and I or monitor the following as they apply to the Loss of Component Cooling Water: The CCWS surge tank, including level control and level 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation EK1.03 Knowledge of the operational implications of the following concepts as they
, alarms, and radiation alarm I
~ apply to the SGTR: Natural circulation EA1.1 Ability to operate and I or monitor the following as they apply to the (Excess Steam Demand): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
~
E/APE # I Name I Safety Function 000007 (BWIE028tElO; CE/E02)
Reactor Trip - Stabilization -
Recovery / 1 000008 Pressurizer Vapor Space Accident 13 000009 Small Break LOCA 13 00001 1 Large Break LOCA 13 00001 5/17 RCP Malfunctions 14 000022 Loss of Rx Coolant Makeup 12 Loss of RHR System 14 000025 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System Malfunction 13 000029 ATWSI1 000038 Steam Gen. Tube Rupture 13 000040 (BWIEO5; CE/E05; WIE12)
Steam Line Rupture -
Excessive Heat Transfer I 4 X -
c L
Ernergenc PWR Examination Outline and Abnormal Plant Evolutions - Tier llGroup 1 (RO)
WA Topic@)
EK1.2 Knowledge of the operational implications of the following concepts as they apply to the (Reactor Trip Recovery): Normal, abnormal and emergency operating procedures associated with (Reactor Trip Recovery)
AA2.02 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: PZR spray valve position indicators and acoustic monitors EK2.03 Knowledge of the interrelations between the small break LOCA and the followina: WGs EA1.17 Ability to operate and monitor the following as they apply to a Large Break LOCA: Safety parameter display system Page 2 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
n 000054 (CWEO6) Loss of Main Feedwater I 4 000055 Station Blackout I 6
~
000056 000057 000058 Loss of Off-site Power I 6 Loss of Vital AC Inst. Bus 16 Loss of DC Power I 6
oooO62 Loss of Nuclear Svc Water I 4 000065 Loss of Instrument Air 18 WlE04 LOCA Outside Containment 13 WlE11 Loss of Emergency Coolant BWlE04; WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4
Recirc. 1 4 WA Category Totals:
EA1.2 Ability to operate and I or monitor the following as they apply to the (Loss of 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
Page 5 of I8 March 2005 Millstone Unit 2 NRC Exam Outline
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A2.02 Ability to (a) predict the impacts of the following malfunctions or 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-401-2 014 Rod Position Indication 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 X
and Purge Control I
029 Containment Purge nt 0
$stems - Tier ZYGroup 2 (RO)
I I IR WA Topi@)
K5.26 Knowledge of the following operational implications as they apply to the CRDS: Definition of moderator temperature coefficient; application to reactor control 3.3 Al.04 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPlS controls, including:
2.9 1
X Al.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fuel Handling System controls including: Water level in the refueling canal Page 9 of I8 March 2005 Millstone Unit 2 NRC Exam Outline
068 Liquid Radwaste 2.8 1
3.2 1
2.5 1
2.8 1
3.4 1
Page 10 of I8 March 2005 Millstone Unit 2 NRC Exam Outline
ES-401 2
PWR Examination Outline Form ES-401-2 I WAPE # I Name / Safety Function oM)oo7 (BW/E02&E10; CUE02)
Reactor Trip - Stabilization -
Recovery I 1
000008 Pressurizer Vapor Space Accident I 3 000009 Small Break LOCA / 3 11 00001 1 Large Break LOCA I 3
000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup I 2
Loss of RHR System I 4 Water I 8 000025 OW026 Loss of Component Cooling 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWSI1 II 11 000038 Steam Gen. Tube Rupture I 3 000040 (BWIEOS; CEIEOS; WEl2)
Steam Line Rupture -
Excessive Heat Transfer I 4 000054 (CWEO6) Loss of Main Feedwater I 4 000055 Station Blackout I 6 rgenc and Abnormal Plant Evolutions - Tier l/Group 1 (SRO)
WA Topic@)
IR EA2.2 Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments 4.0 2.2.12 Knowledge of surveillance procedures 3.4 2.4.20 Knowledge of operational implications of EOP warnings, cautions, and notes 4.0 EA2.09 Occurrence of a main turbine/ reactor trip 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation Ability to determine or interpret the following as they apply to a ATWS:
4.5 4.0 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls I
4.0 II 1
1 1
1 1
1 Page 11 of 18 March 2005 Millstone Unit 2 NRC Exam Outline
000056 000057 000058 000062 000065 W/E04 W/E11 Loss of Emergency Coolant BW/E04; WIE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink /
Loss of Off-site Power I 6 Loss of Vital AC Inst. Bus / 6 Loss of DC Power / 6 Loss of Nuclear Svc Water / 4 Loss of Instrument Air / 8 LOCA Outside Containment / 3 I I WA Category Totals:
I 1
1 1
I I
I 2 I 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 ; WE08 RCS Overcoollng - PTS 14 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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2.4.30 Knowledge of which events related to system operationdstatus 3.6 should be reported to outside agencies 2.2.2 facility between shutdown and designated power levels Ability to manipulate the console controls as required to operate the 3.5
~
~~
~~
3 Group Point Total:
Page 16of 18 March 2005 Millstone Unit 2 NRC Exam Outline
ES-401 5
Form ES-401-2 I
ES-401 System # / Name K
1 -
001 Control Rod Drive 002 Reactor Coolant 01 1 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 01 6 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 PWR Examination Outline Form ES-401-2 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 Randomly Selected WA 073. K4.02 Tier I Group 2 / 1 (RO)
Reason for Rejection Not applicable to Millstone Unit 2. CVCS letdown does not auto isolate on high radiation. Selected 073.K4.01.
1 (SRO) 033.G2.3.4 01 0.A3.01 1 (SRO)
Unable to develop system question related to this GKA. Randomly selected alternate GKA 2.2.22.
Similar to knowledge tested by 007.A1.03. Unable to develop system question related to this KA. Randomly selected alternate KA 01 0.A3.02.
2.1.16 Ability to operate plant phone demonstrated during simulator operating test. Randomly selected alternate GKA 2.1.1 4.
2.1.16 Ability to operate plant phone demonstrated during simulator I operating test. Randomly selected alternate GKA 2.2.1 2 I
2.1.6 Ability to supervise and assume a management role during plant I transients and uDset conditions demonstrated durina simulator w
I operating test. Randomly selected alternate GKA
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Examination Level (circle one):@*
Date of Examination: 3/21/05 Operating Test Number:?
Ad min istra tive Topic 1
(see Note) ir------
Equipment Control Radiation Control Emergency Plan ll TY Pe Code*
N N
N N
Describe activity to be performed Perform an ECP: The examinee properly completes an ECP. (2.1.25)
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 determine the radiological requirements to perform the assigned task (2.3.10)
~~
Use RATS to Determine and Prioritize the Safety Functions: The 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.
- Type Codes & Criteria:
(C)ontrol room (D)irect from bank (53 for ROs; 54 for SROs & RO retakes)
(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 Examination Level (circle one): RQ /@
Date of Examination: 3/21/05 Operating Test Number:
Administrative Topic I
(see Note)
Conduct of Operations II Equipment Control Radiation Control TY Pe Code*
N N
N N
N, S Describe activity to be performed SRO Shift Turnover: At the completion of this JPM, the SRO has performed a review of turn over documents and found incorrect information related to a shift turnover. (2.1.3)
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 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 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 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 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.
- Type Codes 8 Criteria:
(C)ontrol room (D)irect from bank (53 for ROs; 54 for SROs & RO retakes)
(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 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 2 Exam Level (circle one):
Date of Examination:
3/21/05 Operating Test No.:
1 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title
- a.
Manual Makeup to the VCT: At the completion of this JPM, the examinee completes a manual blended make up to the VCT. (004 A2.06) (RO & SRO)
- b.
Fill #I Safetv lniection Tank: When the examinee begins to fill # I Safety Injection Tank to between 55.2% and 59.3%, the A HPSl 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 2301 C 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 Facility 1 Diesel Generator Operability Test, SP 261 3A, 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 Calibration: During the performance of SP 2601 D, 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 Removinq A RBCCW Pump and Heat Exchanqer The examinee places 6 RBCCW Pump and Heat Exchanger in service in place of A RBCCW Pump and Heat Exchanger (008 A4 01) (RO & SRO)
Chanqe the Alarm Setpoint of the SJAE RM 5099 The examinee will adjust the setpoint of the Steam Jet Air Ejector Radmonitor as specified on the attached SP2833-007 (071 A4 25) (RO & SRO)
[SPARE) Hydroaen Recombiner Surveillance At the completion of this JPM the examinee will have A Hydrogen Recombiner in service In accordance with SP 26084, (028 A4 01) (RO & SRO) h I
Type Code*
D. S D. S Safety Function 1
3 6
7 8
9 5
ES-301, Page 23 of 27 N
Implant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
Removing Section 201 B-I, of Batterv Charger 201 B, From 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
- a.
6 7
E, L. N E, L. N. R 1 4(P) b Local Manual Operation of the A Atmospheric Dump Valve Examinee has taken local manual control of the A ADV and placed in 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 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 (005 A2 03) (RO & SRO)
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 c
d
- Type Codes Criteria for RO I SRO-I I SRO-U
~
~
4-6 14-6 12-3
~
~
I (A)lternate path (C)ontrol room
~~-
~
~-
<9 158 154 (D)irect from bank
~
~
~
~
~~ >I 121 131 (E)rnergency or abnormal in-plant,
~~~
(L)ow-Power
_ _ _ ~ -
~~
21 121 121
>2 112 121 (R)CA
~
~
> I 131 / 21
<3 1 ~ 3
/ 25 (randomly selected)
I (N)ew or (M)odified from bank includind1A)
(P)revious 2 exams (S)irnulator
-~
2 3
4 1
5 Appendix D Scenario Outline Form ES-D-1 SWOlC C(B0P)
C (SRO)
FW38B I (BOP)
I (SRO)
RCOGA C(ATC)
C (SRO)
RC04 3%
R (ATC)
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 165: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 No.
I No.
I Type*
I NA 1 N (SROI Alarm A-4 C (ATC) 4 Event Description Commence Forcing Sprays IAW SP 2654B.
Loss of C Service Water Pump.
Feedwater Heater 6A Level Transmitter, L-5043A, fails low PORV, RC-402, leakage requires closing block valve Plant shutdown required by Tech Specs, using AOP 2575, Rapid Downpower.
RCS leakage increase resulting in a LOCA and plant trip.
A Containment Air Cooling Fan high vibration alarm.
Tube rupture in #I SG.
I*
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Event TY Pe*
N (BOP)
R (ATC)
Facility:
MP2 Scenario No.: ES04L12 Op-Test No.: 2 Examiners:
Operators:
Event Description Raise power to 4%.
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:
1 O 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 (ATC)
C (BOP)
I (ATC)
M (ALL)
I PMW Addition Valve, CH-21 OX, fails open.
D Circulating Water Screen D/P increases causing loss of D Circulating Water Pump.
Channel Y Pressurizer pressure transmitter fails high.
Event I Malf.
C (ALL)
No.
I No.
Loss of Vital Instrument Bus, VA 20.
N/A
1 CW02D RXOl B Alarm C-8 on C-05 MSO6B MS02B ED1 6B (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
Appendix D Scenario Out line Form ES-D-1 N (ATC)
C (ALL)
R (ATC)
I (ATC)
C (BOP)
M (ALL)
Facility:
MP2 Scenario No.: ES04L13 Op-Test No.: 3 Depressurize Containment IAW OP 23148, Containment and Enclosure Building Purge.
Loss of the Plant Process Computer Restore AS1 to the normal operating range using AOP 2575, Rapid Downpower to reduce power by approximately 5%
Channel C Pressurizer Pressure transmitter fails low.
Degradation of condenser vacuum requiring a continued reduction of power using AOP 2575, Rapid Downpower.
Loss of condenser vacuum requiring a plant trip and a loss of main feedwater.
Examiners:
Opera tors:
6 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.
FW33 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.
C (ALL)
C (ATC)
Event I Malf.
Overload trip of Bus 24C resulting in a complete loss of all feedwater.
Failure of C HPSl to automatically start on SlAS resulting in loss of all HPSl Pumus.
NO.
i No.
1 I
NA 2
I PCOl 3
I NA
++%E-l 7
1 EDO5C 8
I ES03J Twe*
Event I
Event DescriPtion (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 CV22 C(SR0, l 2 ATC)
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 CCOIA C (SRO, TY Pe*
BOP)
II I
RPolF 1 ATC)
I(SRo, SGOlB R (ALL)
SG02B M (ALL)
I MS02B 1 M(ALL)
II Event Description Trip of A RBCCW Pump Degraded Charging Pump Loop 1 B Cold Leg temperature transmitter noisy Tube leak in #2 SG resulting in a rapid down power.
Tube rupture in #2 SG requiring a plant trip
~~
Failure of ActuationModule AM523 to actuateassociated components Loss of running HPSl Pumps 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
Form ES-301-5
~-
Transient and Event Checklist
-~
ES-301 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.
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.
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.
- 2.
- 3.
Author:
NRC Reviewer:
ES-3-1, Page 26 of 27
JOB PERFORMANCE MEASURE APPROVAL SHEET I
Title:
Perform an ECP ID Number:
JPM-A1 RO
- 11.
Initiated:
Revision:
0 -
Richard J. Ashey Developer 1/16/2005 Date I l l.
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 Si m u I a ted Perform an ce :
Actual Performance:
X Location:
Classroom:
X Simulator:
X In-Plant:
X Task Standards:
The examinee properly completes an ECP.
Required Materials Lprocedures,equipment):
OP 2208, Reactivity Calculations, Rev. 13-05 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-A1 RO 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:
The following conditions exist:
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 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, 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:
4of 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 TAVG 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/M TU.
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:
6of 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) 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 OP2208-004 GRADE X
Standards:
0 Examinee records the Reference Critical Data for Xenon worth on the ECP Data and Analysis Sheet.
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.
Examinee records the calculated Xenon Defect.
0 0
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) 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 OP2208-011 GRADE X
Standards:
0 Examinee records the Reference Critical Data for Samarium worth on the ECP Data and Analysis Sheet.
Examinee refers to OP 2208-0.1 1 to obtain the estimated Samarium worth at criticality and records the value on the ECP Data and Analysis Sheet.
Examinee calculates the Samarium Defect and records it on the ECP Data and Analysis Sheet.
0 0
Cue:
The Xenon-Samarium Post Trip Report is NOT available.
Comments:
9of 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 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 Reference Critical Data CEA Position 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.
Examinee records the value on the ECP Data and Analysis Sheet.
Examinee calculates the CEA Worth Defect and records the value on the ECP Data and Analysis Sheet.
0 0
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 -
1 9)
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.
Examinee calculates the value of Boron Equivalent of Defects and records it on the 0 Data and Analysis Sheet.
rn 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/A on 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. (-1 6 to
-19 should be entered.)
Examinee determines that the Boron Equivalent of Reactivity Change due to Burnup is N/A.
Examinee calculates the Required Boron Change and records it on the ECP Data and Analysis Sheet. (-1 6 to -19 should be entered.)
0 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.)
Examinee calculates the critical boron concentration and records it on the ECP Data and Analysis Sheet.
(441 to 444 should be entered) 0 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.
Date Performed:
Operator:
Evaluator( s):
0 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:
The following conditions exist:
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 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.
Title:
RO Taq Clearance Preparation ID Number:
JPM-A2RO II.
Initiated:
Developer Ill. Reviewed: I Technic I Reviewer IV Approved:
User Department Supervisor Revision: -
0 1/28/05 Date Date Date
SUMMARY
OF CHANGES
-[-
DESCRIPTION I All 8. Date 1
I I---
~
i 11-15-2005 1 Developed new JPM REVICHANGE 0
IDAPI 2
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number: __.
J PM-A2 RO 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 Location:
Classroom:
X Actual Performance: -
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 ANSWER KEY Manual Tagout Sheet 1, Tagout Number Note: Initid position.fiir Blue Tugs. Nf2 ifposition not required Tagout Number
- 2. Date
- 3. AWC) Number (or Multiple)
- 4. Contact Person
!3 3 OC62-003 Todav M2-04-03686
- 5. Equipment
-CHU r-123
? (b Chill
- 6. Reason Tagged
- 7. Special Instructions/Cautioii zontact chemistry for draining instructions and NPDES considerations.
W w
(p-149-1 3.
w e
?~-CHW-1 23. 1,-eat.
V. Team
- 9. Additional AWOs under this tagout Yes
- 10. Partial Restoration
__ Yes 1 1. Prepared by Examinees Naine
- 8. Tag Lift Sheet Attached [Coinm. 3.41 I_ Yes h
Levelof Use Information 5
3 9
STOP THINK AC r REVIEW No Tag: 2-CHW-13 7 Chi11 Water Pump (P-149C) D-on T u r b u d U h g 14 6. (QLEJ)
Red: 2-CHW-126. X-l96B Outlet Isolation Turbine Building 146 (Closed)
Red; 2-CHW-147, Chill Water P u m (P-1490 Discharge Drain Turbine Building 146 (Open)
Red; 2-CHW-174, P 149C Crosstie Header Vent, Turbine Building 146 (Open) 7
-?
L 1 7 I
I3a. Tagout correct and equipment map be isolated SMAJS notified for power block Boundary approved by:
Authorized to be huiifi bv:
I
JOB PERFORMANCE MEASURE WORKSHEET JPM Number:
J P M -A2 RO Initiating Cues:
Initial Conditions:
Simulator Requirements:
Rev.
0 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.
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.
None NOTES TO EXAMINER * * * *
- 1.
Critical steps for this JPM are indicated with an "X". For the examinee to achieve a satisfactory grade, When examinee states what hidher simulated action/observation would be, read the appropriate "Cue".
If necessary, question examinee for details of simulated actions / observations (i.e. "What are you looking at?" or "What are you observing?").
critical steps must be completed correctly.
- 2.
- 3.
- 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 A lignm ent 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.
If requested, provide examinee with Attachment 7, Tagout Request.
0 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 NPD E S.
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.
GRADE Standards:
Examinee enters the following information on Attachment 9:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
Yellow, P149C-HSt Non-Vital Chilled Water Pump C Turbine Building 146. (Optional)
Red. 82 I 75 P149C Non-Vital Chilled Water Pump C!
Turbine Building 31 6:. (Open)
Red, B2174, X196B Vital Chiller Supplemental Turbine Building 31 6; (Open)
Red; 2-CHW-116, Chill Water Pump (P-149C)
Suction Isolation, Turbine Building 14 6 (Closed)
Red; 2-CHW-125, P-1498 Cross Tie to X-196B Turbine Building 146 (Closed)
Red; 2-CHW-126, X-196B Outlet Isolation Turbine Building 146 (Closed)
No Tag: 2-CHW-123, Chill Water Pump (P-149C)
Discharge Isolation Turbine Building 146: (Open)
Red; 2-CHW-147, Chill Water Pump (P-149C)
Discharge Drain Turbine Building 146 (Open)
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.
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 Date Performed:
Operator:
Evaluator(s):
0 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 lnitiatinq Cues:
Initial Conditions:
Rev.
0 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.
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.
Title:
Review RWP and Survey Map ID Number:
JPM-A3RO II.
Initiated:
e$&
R. J. Ashey Developer I I I.
Reviewed:
IV. Approved:
User Department Supervisor 4
Nuclear Trai g Supervisor Revision: -
0 10/29/04 Date Date
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
J P M -A3 RO Task
Title:
Review RWP and Survev Mao Rev.
0 System:
Radiation Control Time Critical Task:
Yes No X
Validated Time (minutes):
10 Task No.(s):
NUTIMS # 404-01-004 Applicable To:
PEO K/A No.:
2.3.1 KIA Rating:
2.613.0 Method of Testinq:
Si m u la t 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 Iprocedures,equipment):
Operations blanket RWP No. 5.
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 The examiner will act as Health Physics (HP) for any related questions.
0 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 a pp ro p r i a t 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 0
Examinee may state that a briefing with HP is required prior to entry into the work area.
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 X
X Expected dose is approximately 75 mr X
0 Dose rate alarm is 100 mr/hr 0
Task (job step) No. 1 is appropriate for this task There is NO contamination in the work area; therefore, NO additional protective clothing is required 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.
Date Performed:
Operator:
Evaluator( s):
0 -
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.
The crew is preparing the Shutdown Cooling System for operation in accordance with OP 2207, Plant Cooldown.
0 7
RADIATION WORK PERMIT - 5 ALARA Review No Code Year 1RWP Number
]Rev. IRWP Start 1
5 1,
0005 1. 0 0 I.Ol-jan-2005 Hours-Estimated Authorized Internal(DAC)- Estimated Authorized External(mRem)-Estimated Authorized 2 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 6 0 0 0 0 2 6 0 0 0
~ R W P Type IRWP Category
~ R W P Expiration I
I. G I.
POWER I
05-jan-2006 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 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,
- 4 Unless specifically briefed otherwise, if especially in high noise areas 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
- Modesty garments will be worn whenever PCa are worn BEFORE logging out
RADIATION WORK PERMIT - (5) JOB STEP - I OF 4 ALARA Review No Plant Code ]Year IRWP Number IRev. IRWP Start I
5 1,
0005 1.00 I 01-jan-2005 Hours-Estimated Authorized 1nternallDAC)- Estimated Authorized External(mRem)-Estimated Authorized 10000 0 0 0 0 0 00000 00000 010000 010000 JRWP Type
~ R W P Category IRWP Expiration I
I. G I
POWER I
OS-)an-2006 I
System Code 2000 Responsible Individual/Exteneion Department/Company Job Supervisor/Extension WILLIAM HOFFNER/ 6 2 00 I
OP/DNC 1 WILLIAM HOFMER/6 2 0 0 Component Code Task NRC Task Alara Zone Locat i on Plant Equipment MISC 0 PS RO ZMISC 2200 2MISC Department/Company Health Physics Representative Date i Zone
\\Building /Floor 2 AUX RWP Term/Rev Date/Time Tenninated/Rev by Location Plant Equipment Rad. Area Type i LEVELS/MULTIPLE AREAS i MISCELLANEOUS u-2 EQUIPMENT i
WRXTTBN DESCRIPTION OF JOB (MATERIALS & XETHODS)
Operations activitiee in RCAs, Radiation Areas. and High Radiation Areas.
~
SURVEY XBASURKMENTS
~
~~
~
~
~~
RADIATION IMR/HR)
CONTAMINATION (DPM/l OOc712 AIRBORNE (DAC)
Review latest radiological surveys I or historical data prior to entering SPECIAL INSTRUCTIONS NO entry 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.
RADIATION WORK PERMIT - (5) JOB STEP - 2 OF 4 I
Plant Code 2
Year RWP Number Rev. RWP Start RWP Type RWP Category RWP Expiration 1
5 I 0005 I 00 I 01-jan-2005 I
G I
POWER I
0 5 - jan-2006 I
Responsible Individual/Extension WILLIAM HOFFNER/LZOO Building Floor Zone I
I 2 AUX ALARA INFORHATION Department/Company Job Supervieor/Extension Department /Company OP/DNC WILLIAM HOFFNER/6200 OP/DNC I
I Locat ion Plant Equipment Rad. Area Type LEW/MULTIPLE AREAS MISCELLANEOUS U-2 EQUIPMENT ALARA Review NO RADIATION (MR/HR1 CO~AMINATION(DPM/100M2) AIRBORNE (DAC)
SURVEY MgASURBMEWl'S Hours-Estimated Authorized Internal(DAC)- Estimated Authorized External(mRem)-Estimated Authorized 0 5 0 0 0 00000 00000 00000 0 0 5 0 0 0 005000 System Code Crmponent Code Task 2000 MISC OPS
~
~~
~~~
I Dose Limit AlamiStay Time) = 0050 mrem D o s e Rate Alarm= 0500 mr/hr ElaDsed Time Alarm= 0000 m i n.
NRC Task Alara Zone Location Plant Equipment RO 2HISC 2 2 0 0 2MISC REQUIRENBNTS Solid Rad Waste
-5' West Penetration Let down Heat Exchanger Lab coat 5 - 1500
<1K 10 - 2000 c1K 10 - 1200 c 1x c.3 Electronic dosimeter TLD Health P h p ~ c s Representative Date RWP Term/Rev Date/Tirne Tenninated/Rev by I
Health Physics Coverage Periodic Minimum Margin:
0 2 2 5 w e m
RADIATION WORK PERMIT - (5) JOB STEP - 3 OF 4 Plant Code 2
Year RWP Number Rev. RWP Start RWP Type RWP Category RWP Expiration 1
5 1 ' I 0005 1'00 I
1'01-jan-2005 I
I G
I,
POWER I I 05-jan-2006 I
IBuilding 2 AUX IFloor Responsible Individual/Extension WILLIAM HOFFNER/CZOO Location I LEVELS/MULTIPLE AREAS Department/Company Job Supervisor/Extension Department/Company OPlDNC WILLIAM HOFFNER/BZOO OP/DNC i
Plant Equipment Rad. Area Type ALARA Review No WRITTEN DESCRIPTION OF JOB (WTBRIALS & METHODS)
Hours-Estimated Authorized 1nternallDAC)- Estimated Authorized External(rnRem)-Estimated Authorized 01000 0 0 0 0 0 00000 0 0 0 0 0 001000 001000 I
ICperotions Training classes activities in RCAs, Radiation Areas, and High Radiation Areas.
System Code I 2000 lcomponent Code
~
[Taik MISC OPS Plant Equipment I 2MISC INRC Task I Alara Zone Location RO ZMISC I 2200 SIJRVKY MRASDREXXNTS RADIATION (MR/HR)
CONTAM INATION ( DPM/ 1 0 0 (31 2 )
A I RBORNE (DAC)
I Review latest radiological surveys I or historical data prior to enterinq SPECIAL INSTRUCTIONS NO 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 Alarm= 0100 mr/hr Elapsed Time Alarm= 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 I
H e a l t h Physics Representative Date I
IRWP Term/Rev Date/Time Terminated/Rev by I
I I
Plant Code Year IRWP Number
[Rev. IRWP Start 1
5 1.
0005 1.00 1.01-jan-2005 Responsible Individual/Extension WILLIAM HOFFXER/62OO Building Floor Zone I
2AUX I -25' IRWP Type
~ R W P Category IRWP Expiration 1
I. G I.
1, 05-jan-2006 1,
Department/Company Job Supervisor/Exteneion Department/Company OP/DNC WILLIAM HOFFNJZR/CZOO OP/DNC 6
Location Plant Equipment Rad. Area Type CHARGING PUMP CUBICLES MISCELLANEOUS Health Phyeics Repreeentative Date
~~~~
Charging System activities by Operations, walkdowns, inspections, necessary support activities r-RWP Term/Rev Date/Time Terminated/Rev by ALARA INFORXATION I
I NO I
10000 00000 I
00000 00000 1 010000 010000 ALARA Review Hours-Eetimated Authorized Internal(DAC)- Estimated Authorized External(rnRem)-Estimated Authorized I
System Code (Component Code ITask (NRC Task (Alara Zone Locat ion Plant Equipment I 2000 PUMP OPS RO 2226 1 2226 12300 SURVBY M E A S U R E X ~ S RADIATION (MR/HR) c o N T n m I N ~ T I O N ( D P M / l O O M 2 ) AIRBORNE (DAC)
Review latest radiological surveys or hiotorical data before entering RCA.
SPECIAL INSTRUCTIONS NO entry to Tech Spec Locked High Radiation Areas permitted using this Job Step.
-' I HP will eetablieh dosimetry placement baeed on intended tasks and work area surveys.
Notify HP before disassembling components.
I JPCs required in contaminated areas.
HP supervision may adjust protective clothing 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.
Notify HP before entering overhead areas.
D o s e Limit Alarm(Stay Time)= 0025 mrem Dose Rate Alarm= 0100 ~ / h r Elapsed Time Alarm= 0000 mln.
RBQUIREMENTS Lab coat Electronic dosimeter TLD Health Physics Coverage Routine Minimum Margin.
0125 mrem
T I,'a$
bj6r2
~
p -,+ i-c JOB PERFORMANCE MEASURE APPROVAL SHEET I.
Title:
Use RATS to Determine and Prioritize the Safetv Functions ID Number:
J P M -A4 RO Revision: -
0 I t.
Initiated:
Developer I I I.
Reviewed:
IV. Approved:
User Department Supervisor 112 1 I05 Date Date Date
SUMMARY
OF CHANGES 1
1111 912004 I
IDAP) 1 All& Date 1 DESC RI PTlON Developed new JPM REVKHANGE 0
2
JOB PERFORMANCE MEASURE WORKSHEET Facility:
MP-2 Examinee:
JPM Number:
JPM-A4RO Rev.
0 Task
Title:
System:
Administrative Use RATS to Determine and Prioritize the Safety Functions 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:
Si m u I a ted Perform a nce Location:
Classroom:
X Task Standards:
Required Materials Iprocedures,equipment):
General
References:
X Actual Performance:
Simulator:
X In-Plant:
X The examinee will correctly identify and prioritize the Safety Function Success Paths.
Form 2540-002 rev. 001, Functional Recovery Resource 2540 rev-21 page 8, Safety Function Status Checklist Assessment Tree 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 P M-A4 RO 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:
Power is at 2 x and stable CEAs 45 and 46 are fully withdrawn, all other CEAs are fully inserted 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.
RWST is 97% and lowering slowly Total SI flow is 0 gpm RVLMS is 100%
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.
support the success path is not operating.
been selected.
x Safety functions for which the equipment to X
Safety functions for which success path three has Safety functions for which success path two has been selected.
x 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.
Date Performed:
Operator:
Evaluator(s):
0 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 Function I
Success Path Equipment Operating SFSC Met P r i o r i ty RC-2 Y
Y I Reactivity Control Ma in te na nce of Vital DC Power Maintenance of Vital AC Power RCS inventory Control
~-
~~
-~
MVA-DC-1 Y
6 Y
MVA-AC-2 Y
4 IC-2 Y
5 RCS Pressure Control PC-1 Y
Y N
~ RCS and Ccre Heat HR-3 Y O R N Remova I t
- ~-
' Containment
, isolation
_ ~ - __ ~ _ _ _
~
Y CI-I 8
Y CTPC-3 Y
Y 2
I Containment Temperature and Pressure Control Containment Combustible Gas Control CCGC-I Y
Y 9
EXAMINEE HANDOUT JPM Number:
J P M-A4 R 0 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:
Power is at 2 x and stable CEAs 45 and 46 are fully withdrawn, all other CEAs are fully inserted 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.
RWST is 97% and lowering slowly Total SI flow is 0 gpm RVLMS is 100%
10
Equipment Operating Success Path SFSC Priorit:
Met 1 CEA Insertion I
Boration using CVCS Boration using SI Battery Chargers/
Station Batteries RSST I
I I
1 EDG Bus 34N34B I
I I
RCS Inventory Control RCS Pressure Control RCS and Core Heat Removal Containmcn t Isolation containment Temperature and Prcssure Control Containment Combustible Gas Control C
Millstone Unit 2 Functional Recovery Revision 21 I
Page 8 of 30 4.0 SAFETY FUNCTION STATUS CHECKLlST SAFETY FUNCTION TRACKING PAGE Safety Function EOP ENTRY TIME
~ RC-3 Reactivity Control Maintcnance of I--
Vital DC Power Reactivity Control Maintcnance of Vital DC Power
~
I 'MVA-DC-1 MVA-AC-1 MVA - AC-2
~~
~~
MVA-AC-3 IC-1 IC-2 PC-1 cvcs Safety Injection Su bcooled I
Saturated I
1--
-1 PC-2 PC-3 PORVs I
I I
SI not operating I
I I
HR-1 HR-2 HR-3 ST operating 0-T-C CI-1 I
Automatic/Manual CARS (Normal)
I I
I CTPC-1 mc-2 CARS (Emerg)
Hydrogen Recombiners CTPC-3 CCGC-1 Hydrogen Purge I
1 I
CCGC-2
Millstone Unit 2 Functional Recovery EOP 254G Revision 21 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.
- 7.
- 8.
IDEFJTIFY success paths to be used to satisfy each safety function using BOTH of the following:
Resource Assessment Trees Safety Function Tracking Page PRIORITIZE safety functions to be addressed first based on ALL of the following:
- a.
- b.
C.
- d.
- e.
Safety functions which do not meet the Safety Function Status Checklist for the selected success path.
Safety functions for which the equipment to support the success path is not operating.
Safety functions for which success path three has been selected.
Safety functions for which success path two has been selected.
Safety functions for which success path one has been selected.
DIRECT the STA to check that Safety Function Status Checklist Acceptance Criteria are satisfied for chosen success paths.
safety Functwn suwcss Path londitionr ourcc OIIVC Path eceptanct 3terir iucces
'ath
/qq t
RC-1 CEA Insertion
~
t
- a. Less than Iwo CE& not fully inxrrcd.
- b. Reactor power dropping.
- c. SUR negative.
a.Reactor power < IO-'%.
b.Resctor power stablc or dropping I RC-I I bration Using CVCS
> 40 m, go direcUyt0 aoceplanccmtena below
- a. Boratwn addition rate u > 40 gpm.
- b. Reactor power dropping.
- c. SUR negative.
a.Rcactorpower <
b.Rcactor p e r srablc or dropping.
I RC-2 I G
Bondon Using SI 1
I f SI boratiun addition rate
> 40 gprn, go dirw to acapfance criteria klow
'I a.Boration addition rate is > 40 gpm, b.Rcactor power dropping.
E. SUR negative.
a.Rcstorpowcr < IO-'%,
a.Boration addition rate is > 40 gpm, b.Rcactor power dropping.
E. SUR negative.
a.Rcstorpowcr < IO-'%,
b.Remor power stable or bopprg.
1 RC-3 I I
OPS Form 2540-002 Rev. 001 Page 1 of 10 J
safely Function I
1 Success Pal h Conditions source Motive Path 48ov Bus 22E Acteptancc Criteria succeu Path 48OV BUS
. 22F Maintenance of Viral DC Power 1
Station Battery A
Station Battery B
Bnnery Charger A
Dc Bus DC B w 201 A Battery Charger B
a %tal DC Bus 201A IS energzed h 12OV AC Bus VA10 is energzed
Safety Function PucCeU Path hditionr ource 1otNe it h rcptancc itcria fccP th Kcwurce Tree Maintenance of Vital AC Power 8-2 v
i MVA-AC-3 Bus 3 4 W B 4.16 KV 4.16 KV
- a. Bus 24C is energized.
- b. Vital DC Bus 2OlA is cncrgned
- c. Facility I RBCCW is opernhng.
d Facility 1 Service Water isoperating.
- a. Bur 24D is cncrgkd.
- b. Vital DC Bus 2018 is cnergned.
- c. Facility 2 RBCCW is operaling.
- d. Facility 2 SCMW, Water ia operaling.
LMVA-AC-1 I CQQdhG MVA-AC-2 Emergency i Diesel Gcncrator(r)
V 1
t 4.16 Mtal KV 416KV vital J.
Bus 24C Bus 24D I
LLudmnl a Bus 24C is energized b Vital DC Bus B l A IS cnerglred c Facility 1 RBCCW is operaung d Facihty 1 S ~ M C C Wtcr is operating
!z!mwQd a Bus 24D is encrgued.
b Vital DC Bus 2018 u energzed
!2anuml a Bus 24C IS snergmd
- b. Vital DC Bus 20lA is energucd c Faality 1 RBCLW i s operatmk d Facility 1 servlee Water i s operating
!Andum2 a Bus 24D LF energued b Vital DC Bus 2OlB IS cncrglred E Facility 2 RBCCW is operating.
- d. Facility 2 Senice Water is operating.
1 MVA-AC-3 I
1 OPS Form 2540-002 Rev. 001 Page 3 of 10 Tk!NK p,@, *,I
safety Function OPS Form 2540-002 Page 4 of 10 Rev. 001 1
Success Path cooditiom iourcc dolive ath Reso%
Tree 1
Lvl> 10%
Available t
v V
Boric Acid Gravity GrWicg Pump Feed Feed v
v v
I Normal HPSI R!Jl Path Charging Row aoptance ritcria 1
a Pressurucr lcvcl is > 20%.
- b. RCS subcooling is 2 minimum subcoollng lmc of the Prr c u m.
- c. Reactor vessel lcvcl is z 43%.
1 IC-I I
V IC-2 SI If SI pumps are operating.
go directly 10 sfceprance criteria below V
I
v Cntmt Emerg Rising sump Level f
a If SRAS has not occurred and HPSI throttldstop uitena are not met. then all avvlabk chargmg pumps arc operating
- b. If SRAS has not occurred and LPSI termmailon cmtcna arc not met, then LPSI flow s wthm SI llow curve.
c If HPSI thronlehtop cnteria are not met, then HPSI flow IS wttun SI flow curve.
d Reactor vewl level IS e 7%
IU-2
P 8 5 d k W
9 h
B
safety Function Succerc Path Conditions iource Aotive ath cccptancc riteria 1cccss Ilh IfHPSlflow>
d i r d y to acoaptm critwi. bslow SI am nuv~,
go If LPSl flow >
directty to aaeptakc critcri. below SI flow curve go Chtmt Emerg swnp Level Lvl =.
9%
LVl > 9%
t J
L If SRAS has not oCCurred and HPSI
- b. If SRAS has not occurred and US1 throttlelstop cnteria not met. then all available charging pumps are opcrating.
termination criteria are not met. then WSl flow is aithm SI flow w e.
- c. If HF'SI (hrottl4stop criteria are not met.
then HPSI flow iswithin SI flow curve.
I PC-2 I Rur AvaJ I
I
- a. Pressurizer pressure is within the P ~ C U I V C limits.
AI least one steam generator WR level is less than or q u a l to 70 inches.
Safety b d i o n iucccss
'ath Ecptance itcria
- a. At leal one SG k c 1 is within 40 to 70% or being rcslored.
- b. If RCPs are operating, then loop delta T is 40'E
- c. If RCPs are no1 operating. thcn loop delta f is < 55'E
- d. TH and Cfltcmperature is < 600°F
- e. RCS subconling is 2 minimum subcooling line of the P/f curve.
- f. Rcactor VCLKI level IS 5 43%.
- onditions SG Available for ource Iotive Stcam Dumps ADVs I
ilh I
SG Heat Sink
-1 Once-Through-SG Available. for Heat Removal c
88 ADVs
- a. At least one SG Lcvel IS wtbm 40 to 70% or being
- h. CeTtcrnpcrature IS c 700°F
- c. If SRAS has not occurred and HPSI throtrlchtop criteria d If SRAS h u no1 occurred and LPSI lerrmnatlon Critcria
- e. If HPSI throttlt/stop crltena arc not met. then HPSI O w IS HR-2 restored are not met. then all evarlablc charging pumps are opcnhng.
arc not met. then LPSI flow is w'thm SI flow a w e.
within SI flow curve.
Cntmt Emcrg
- h. If SRAS has not m r c d and t1PSI rhroitlc/siop critena arc not mct. then all avadablc chargmg pumps are operatmg.
c If SfUS has not omtrrcd and LPST tcrrninatton alterla d IF HF'SI throttlc/slop Cnterla are not met. then HPSI flow arc not me4 then LPSI flow IS wthm SI flow curve IS wthur SI flow curve OPS Rev. 001 Form 2540-002 Page 7 of 10
Safety Function succcss Path unexplained alarms and M) unexplained rises.
- 4. Steam plant radiation monitors have no unexplained alarms and no uncmlaincd m.
Cunbtions Normal Containment Conditions
~ p 1 a O c c kiteria J C U X S a t h C I A S Resource Tree 1
CI-l AutomatidManual Containment Isolation
- 1. (hbnt pressure < 4.42 pdg
- 2. Radialion monitors inside alarms and no unexplained r k.
- 3. Radiation monitoring Ouhidc cntml have no m m have M) unwrplaincd ANY of the followin.&
- 1. Om1 pressure 2 4.42 pig.
- 2. Radiation moniton inride cntmt have uncxplaincd dams or unurplaincd rises
- 3. Radiation monitoring outside mtmt have unexplained alarmror unexplained rises.
NOTE 1
Both of thc AbnormaJ Containmcnt conditions should be evaluated to determine if thc quipmcnt is rcqulrcd IO maintain the CI - 1 Acceptance Criteria.
A I. Steam plant ramation monilorr have unupluned alarm and unexplained mscs v
- a. ONE of the following:
Steam plant radiation monitors have no unwrplamcdalarms and no unuplaincd n m.
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~ined rises.
- 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 plant conditions has an ioolrtion valve dosed.
- 3. Each containment penetration required to be closed for a n e n t ICI-1 I OPS Form 2540-002 Rev. 001
E 3 i o n success Path The determination for the ClTC succcss path should be based on containment pmssurc and not thc operating mode (normal or cmcrgency) of the CAR Fans.
Conditions Containment Temperature and Pressure Control source Molivc Fwility 1 CAR F.nr Power Avail Path Facility 2 CAR FanS Power Avail Acceptance CZitena Gantoinment F a (Nomul Made)
Containment Plarurc e 4.42 psig S u a C W Path
- a. Containment temperature e 155-L
- b. Containment prcsrurc < 4.42 psig.
Containment Fans (Emergency Mode)
Containment 2 4.42 prig c 9.48 p i g T Facility 1 Facility 2 Power Power Avail Avail
- a. z 2 CAR fans operatmg UI emergency mode.
- b. Containment temperature < 19O'F.
- c. Cont.mrncnt pcesaurc< 9.48 psi&
Containment Containment Pressure h 9.48 pstg One Facility Paver Avail I
- a. Both CS pumps with I: 1300 gpm cach
- b. Containment pressure IS 4 51 pig.
- a. 5 2 CAR fans operating m emergency mode.
- b. One CS pump w h 2 1300 gpm.
- c. Contimmt pressure u < 51 psig.
OPS Form 2540-002 Rcv. 001
safety Function success Path Conditions source MofNe Path Acceptance Criiceria S U ~ C U Path Containment Combustible Gas Control Safety Function IS considered satisfied until the hydrogen analyzer can be placed in senice and the warm up is complete.
Resource Tree Combustible Gm Control c
L
- a. Contrummt hydrogen conceauatinn
< 1.4%.
a All available hydrogcn raombiners
- b. Containment hydrogen mncentratron energized CCGC-1 i