ML13057A218
| ML13057A218 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/05/2012 |
| From: | Garchow S Operations Branch IV |
| To: | Pacific Gas & Electric Co |
| Laura Hurley | |
| References | |
| Download: ML13057A218 (267) | |
Text
Appendix D (rev 9) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 1 Op-Test No.: L111-NRC Examiners: Operators:
Initial Conditions: 75%, MOL, steady-state conditions, 838 ppm boron Turnover: Maintain current power level (for Htr #2 Drip Pp monitoring); place 120 gpm letdown in service (per chemistry) for minor crud burst cleanup. DG 1-3 is OOS.
Event Malf Event Event No No. Type* Description 1 OP B-1A:XII, N (ATC, Places 120 gpm letdown in service (including 2nd CCP) sec 6.3 BOP) 2 pmp asw1/2 C (SRO, ASW Pp 1-1 trips on OC (1-2 ASW Pp fails to start in auto, and is started BOP) manually) (TS) 3 mal gen4 C (ALL) Full Load Rejection (from 75%); stabilizes @ 20-30% power R (ATC) 4 xmt rms23 I (SRO, S/G Blowdown RM-23 fails high (with blowdown isolation; valves vlv sgb13,14 BOP) (FCV-498 & FCV-499) fails to isolate, but can be manually closed) (ECG) 5 xmt cvc19 I (SRO, VCT level LT-112 fails low (causes continuous makeup; is stopped manually)
ATC) 6 mal mss3b M (ALL) Steamline 1-2 break OC (with ATWS on SI); the 1-2 S/G must be isolated mal ppl3a C (BOP) (CT) ** (see next page); terminates SI once the faulted S/G is isolated; Train A SI does not actuate, and must be manually aligned (including Phase A components) 7 mal ppl5a/5b C (ATC) Reactor must be manually tripped on safety injection (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 1. Total malfunctions (5-8) 7
- 2. Malfunctions after EOP entry (1-2) 2
- 3. Abnormal events (2-4) 4
- 4. Major transients (1-2) 1
- 5. EOPs entered/requiring substantive actions (1-2) 2
- 6. EOP contingencies requiring substantive actions (0-2) 0
- 7. Critical tasks (2-3) 2 Rev 2 comments: changed valve that fails on event 4; some timing changes DC-2012-11-DRAFT OPERATING TEST.docx Page 1 of 263 Rev 2
Appendix D (rev 9) Scenario Event Description Form ES-D-2 SCENARIO
SUMMARY
- NRC #1
- 1. (Normal Evolution) Crew places 120 gpm letdown in service per OP B-1A:XII, section 6.3 (for RCS cleanup)
- 2. Auxiliary Salt Water (ASW) Pump 1-1 trips on overcurrent (OC). ASW Pump 1-2 fails to start in automatic, but the BOP can place the pump in manual and start it. Actions will be per AR PK01-03 (for OC trip of 1-1 ASW PP); actions may also be taken per OP AP-10, Loss of Auxiliary Salt Water. (TS)
- 3. A full load rejection occurs on Unit 1 (due to a grid disturbance) (from 75% power). OP AP-2, Full Load Rejection, is implemented to stabilize the plant between 20-30% power on steam dumps.
- 4. The S/G Blowdown radiation monitor (RM-23) fails high, causing a blowdown isolation.
Isolation valves (FCV-498 & 499, blowdown to discharge tunnel) fails to operate in automatic; the BOP recognizes the failure and completes the isolation manually; actions are taken per AR PK11-17, S/G Blowdown Hi Rad. The crew diagnoses that the high reading on the radiation monitor is a failure (due to comparisons with other monitors, the rate of failure, etc), and applies the appropriate Equipment Control Guideline (ECG) ECG 39.3.B).
(ECG)
- 5. Volume Control Tank (VCT) level channel LT-112 fails low, causing a continuous (and erroneous) makeup signal. The crew diagnoses the level channel failure by comparing other VCT parameters, and by using OP AP-19, Malfunction of the Reactor Makeup Control System. The makeup system is secured, and makeup is accomplished (if needed) by using the manual mode (or enabling the auto mode for short periods).
- 6. A steamline break (outside containment) occurs on the 1-2 S/G, almost immediately causing the need for a Safety Injection (SI) and reactor trip**. Train A of SI does not occur automatically, and must be manually actuated. The S/G will be isolated per EOP E-2, Faulted S/G Isolation (CT), and ECCS will be terminated per EOP E-1.1, SI Termination.
- 7. On the Safety Injection, Reactor Trip does not automatically occur (ATWS), causing the need for a manual reactor trip (which is successful) (CT); transition to EOP FR-S.1 is, therefore, not required, and EOP E-0 is continued.
The scenario is terminated once RHR pumps have been stopped in E-1.1 (approximately step 8 completed), at the discretion of the lead examiner.
- CT / TCOA note: Steam break was evaluated against Time Critical Operator Actions (TCOAs) # 18 & 19 (MSLB IC & OC); the break sizes, ramp times, initial power levels, and other conditions differ significantly from the conditions used in this scenario. For these reasons, the S/G isolation will remain critical (a critical task, per WOG), but no TCOA time limits are applied to this scenario.
DC-2012-11-DRAFT OPERATING TEST.docx Page 2 of 263 Rev 2
Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 1 Page 01 of 20 Event
Description:
Crew Places 120 gpm Letdown in Service per OP B-1A:XII (sec 6.3)
Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.
Note: The Shift Foreman (SFM) may chose to read (direct) the procedure him(her)self, or hand off the procedure to the BOP and ATC to perform SRO Shift Foreman implements OP B-1A:XII, section 6.3, to raise letdown from 75 gpm to 120 gpm flow (OP B-1A:XII, sec 6.3)
- Reads procedure NOTES prior to step 6.3.1 BOP * (6.3.1) Makes call to field (aux bldg watch, ABW) to monitor letdown filter pressure while raising letdown flow BOP * (6.3.2) Notes IF/THEN statement on what to do if letdown filter P gets too high BOP/ATC * (6.3.3) Implements OP B-1A:V to start a second charging pump (implements OP B-1A:V, sec 6.2, to start 2nd charging pump)
ATC * (6.2.1) Places FCV-128, charging flow control (CC2, right side) in MANUAL BOP * (6.2.2, 6.2.3) Starts a 2nd CCP (takes switch momentarily to Start), and verifies normal amps on pump (VB2, lower left of center, skirt area)
Note: HCV-142 is RCP backpressure valve, and FCV-128 is charging flow control valve; after 2nd pump is placed in service, charging may have to be throttled back slightly (or left as-is due to impending rise to 120 gpm letdown flow).
ATC * (6.2.4) Verifies (using HCV-142 and FCV-128) that Pzr level is still on program level (it is)
ATC * (6.2.5) Verifies (using HCV-142, and FCV-128 as needed) that RCP seal injection flows are 8-13 gpm (they are)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 1 Page 02 of 20 Event
Description:
Crew Places 120 gpm Letdown in Service per OP B-1A:XII (sec 6.3) (con't)
Time Position Applicants Actions or Behavior (OP B-1A:V, sec 6.2, con't)
Note: May not chose to go back to AUTO on FCV-128 in the next step, since they will be raising charging flow to go to 120 gpm letdown in the next few steps.
- Places Pzr level (FCV-128) back in AUTO if on program level (if desired)
(returns to OP B-1A:XII, sec 6.3, con't)
ATC * (6.3.4) Monitors TI-127 (CC2 right side), regen HX outlet, while charging and letdown flows are mismatched during the following steps ATC * (6.3.5) Adjusts charging to keep Regen HX temps (both sides) in normal ranges during the following steps (uses FCV-128)
BOP * (6.3.6) Places letdown HX temp ctrl valve TCV-130, in MANUAL, and then raises the demand 10% higher than current demand (VB2, vertical section, lower center)
BOP * (6.3.7, 6.3.8) Places letdown pressure ctrl valve PCV-135 (right next to TCV-130) in MANUAL, and raises demand (opens valve) until letdown pressure is down to 200 psig.
ATC * (6.3.9) Places FCV-128 in MANUAL (if not already in MAN from previous step)
ATC * (6.3.10) Raises charging flow by opening both FCV-128 (to 132 gpm) and HCV-142 (keeps RCP seal flows 8-13 gpm) to achieve 132 gpm flow.
- Reads CAUTION prior to step 6.3.11 (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 1 Page 03 of 20 Event
Description:
Crew Places 120 gpm Letdown in Service per OP B-1A:XII (sec 6.3) (con't)
Time Position Applicants Actions or Behavior (OP B-1A:XII, sec 6.3, con't)
BOP * (6.3.11) Reads IF/THEN statement on what to do if letdown pressure is not controlled in next steps BOP * (6.3.12) OPENS 8149A, 45 gpm letdown orifice stop vlv, to raise letdown flow; raises demand on PCV-135 as needed to control letdown pressure at approx 350 psig.
BOP * (6.3.13, 6.3.14) Verifies that letdown pressure is < 400 psig, and that letdown flow is 120 gpm (it is)
BOP * (6.3.15) Reads IF/THEN statement on what to do if letdown relief was lifted during evolution (shouldn't have), and lowers letdown pressure to 200 psig using PCV-135 to reseat letdown relief (only if needed)
BOP * (6.3.16) Adjusts PCV-135 (letdown pressure) to 350 psig, and places PCV-135 in AUTO BOP * (6.3.17, 6.3.18) Adjusts TCV-130 to normal letdown temperature (90-100 °F),
and returns TCV-130 to AUTO (if desired).
ATC * (6.3.19, 6.3.20) Adjusts FCV-128 (and HCV-142 if needed for seals) to bring Pzr Level back to program, and returns to AUTO (may not occur, due to upcoming events); controls level in manual or auto Proceed to the next event once 120 gpm letdown is in service, per lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 2 Page 04 of 20 Event
Description:
1-1 ASW Pump trips on OC, and the 1-2 ASW Pump does not auto start (man OK)
Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.
ATC Observes PK01-03 (ASW Pp OC trip) and PK01-01 (three low press / low P inputs) alarming, and informs the Shift Foreman.
ATC/BOP Observes that 1-1 ASW Pp has a blue OC light (VB1, far left), and reports condition to the Shift Foreman.
BOP Observes that 1-2 ASW Pp did not start, and attempts to start the pump (it will start) by taking the pump Auto/Manual switch to Manual, and attempting to start the pump (all at far left of VB-1 vertical section). Note that these actions may be performed prior to AR PK01-03 or OP AP-10 entry (due to it being an automatic action that did not occur), or may be performed during these procedure.
Note: The Shift Foreman (SFM) may enter OP AP-10 (Loss of ASW), either directly, or after implementing AR PK01-03. AR PK01-01 may be entered briefly, but it is not expected.
(ONLY if AR PK01-01 is entered; otherwise, section is N/A)
SRO * (1.0) Goes to section 2.1 due to multiple low pressure inputs SRO * (2.1.1) Determines that a loss of ASW has occurred, and goes to OP AP-10, Loss of ASW (ONLY if AR PK01-03 is entered; otherwise, section is N/A)
SRO * (1.0) Goes to section 2.1, due to OC trip inputs SRO/BOP * (2.1.1) Determines that the standby ASW pump is NOT running with normal current (did not start); takes 1-2 ASW pp to MAN, and starts it (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 2 Page 05 of 20 Event
Description:
1-1 ASW Pump trips on OC, and the 1-2 ASW Pump does not auto start (con't)
Time Position Applicants Actions or Behavior (AR PK01-03, con't) (if used)
SRO * (2.1.2) Determines that ASW flow has been restored, and continues to next step.
- Reads NOTE prior to step 2.1.3 SRO/BOP * (2.1.3) Determines that ASW/CCW HX P is normal @ between 100-140" BOP * (2.1.4) Directs intake watch to secure continuous chlorination to the 1-1 ASW bay SRO * (2.1.5a) Dispatches operator to pump breaker (1-1 ASW)
SRO * (2.1.5b, 2.1.5c, 2.1.5d) Determines if breaker reclose is allowed, using Ops Policy B-2 (if desired; will not do this, as the 1-2 ASW pp is running normally);
directs maintenance to investigate (including clearance and notification).
Note: "Normalizing" the ASW/CCW trains is not needed for this event (will move on to next event once Tech Specs checked).
SRO * (2.1.6) Established normal ASW/CCW alignment (will not start/complete)
SRO * (2.1.7) Refers to Tech Spec 3.7.8.A (72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action) for ASW Pp 1-1 (note: the failure of the low press auto-start on the 1-2 ASW pp is not a Tech Spec required function)
Note: Actions (significant) in AR PK01-03 and OP AP-10 are very similar; both procedures and actions are detailed here, depending on which procedure(s) are chosen by the crew.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 2 Page 06 of 20 Event
Description:
1-1 ASW Pump trips on OC, and the 1-2 ASW Pump does not auto start (con't)
Time Position Applicants Actions or Behavior (IF OP AP-10, Loss of Auxiliary Salt Water, is implemented; otherwise, N/A)
SRO Implements OP AP-10, Loss of ASW BOP * (1) Verifies an ASW PP running; takes 1-2 ASW to MANUAL, and starts (if not already done)
BOP * (2) Verifies running pump amps (1-2 ASW) are normal (they are)
SRO/BOP * (3) Verifies AR PK01-01 is OFF (was initially on during failure, but should be off now)
BOP * (4) Verifies CCW HX temperature normal (it is)
SRO * (5) Complies with Tech Specs for failed ASW pump (Tech Spec 3.7.8.A for ASW Pp 1-1, 72 hrs)
Proceed to the next event once the standby ASW pump has been started, and Tech Specs have been addressed, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 3 Page 07 of 20 Event
Description:
Full Load Rejection (from 75%)
Time Position Applicants Actions or Behavior ALL Diagnosis made of load rejection by use of various alarms, generator load dropping, and/or generator output breakers open.
SRO Implements OP AP-2, Full Load Rejection Note: Once the generator output breakers open, the rod control system will drive rods in, lowering power (via steam dump demand). Rods are placed in manual, and power stabilized on steam dumps between 20-30% power (ideally, but not required, is to stabilize at a point where group 1 steam dumps are throttled, and group 2 steam dumps are closed).
(OP AP-2, Full Load Rejection)
SRO Reads CAUTION prior to step 1 ATC * (1) Verifies that control rods are inserting properly in AUTO (VB2, intermittent green IN light)
ATC/BOP * (2) Verifies proper operation of steam dumps, Tave trending to Tref (VB3, red/green indicator lights; Tave/Tref from CC1 recorder/PPC)
BOP * (3) Checks MFP suction adequate
- (3a) Verifies 3rd Condensate/booster Pp set running (VB3, lower, center, will auto-start)
BOP * (4) Verifies DFWCS in AUTO and controlling S/G levels (CC3 MFW HMI, VB3, PPC)
- Checks MFW control and bypass valves in AUTO
- Checks both MFPs and their controller in AUTO
- May check level trends, as well as steam flow/feed flow trends (CC3, PPC, and/or big VB3 DFWCS electronic recorders)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 3 Page 08 of 20 Event
Description:
Full Load Rejection (from 75%) (con't)
Time Position Applicants Actions or Behavior (OP AP-2, Full Load Rejection, con't)
ATC * (5) Rod Control is placed in manual, and power is controlled (via Tave and steam dumps) between 20-30%
ATC * (6) Verifies Pressurizer Pressure is controlling in automatic (2210-2260 psig)
(may be outside this for short periods, but is controlling in automatic)
ATC * (7) Verifies Pzr Level is controlling at program, and (optional) charging flow adequate to prevent letdown flashing: may take manual control of Pzr level (now, or any time during ramp) to prevent flashing of letdown (under these conditions, approx 60 gpm charging flow is required to keep letdown properly cooled)
- Places HC-459D (master level controller) or FCV-128 (charging flow controller) in manual (CC2, right side, for both)
- Keeps charging high enough (approx 60-65 gpm, as minimum) to prevent letdown from flashing (VB2, upper panel, letdown temperature, is monitored)
- Uses HCV-142 (seal backpressure) to maintain RCP seal flows 8-13 gpm SRO/ATC * (8) RCS is borated per reactivity handbook for approx 50% load reduction (the following guidance is on the boration checklist in the reactivity handbook)
- Presses STOP on M/U Ctrlr HMI (CC2)
- Presses BORATE on HMI
- Sets target gallons for boration (as decided above, and per the Shift Foreman); verifies batch is reset
- Sets boric acid flowrate
- Presses START, and monitors boration
- Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman SRO Reads NOTE on stabilizing the plant prior to step 9 (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 3 Page 09 of 20 Event
Description:
Full Load Rejection (from 75%) (con't)
Time Position Applicants Actions or Behavior (OP AP-2, Full Load Rejection, con't)
BOP * (9) Stabilizes secondary:
- Places hotwell reject valve HC-3 controller in manual and closed (VB3, lower, right)
- Places FCV-31 (part of cold gas temp control scheme) in manual and full open (VB3, lower right; note that this valve/controller is reverse acting, in that 0% on controller is full open demand)
- Adjusts TCV-23 and FCV-31 to attain acceptable steam jet air ejector (SJAE) flows and cold gas temps, and then returns controllers to auto, and monitors (all VB3, lower right)
- Secures one condensate booster pp set, and places it back in AUTO Proceed to the next event once step 9 (above) is completed, and at least the 1st boration is completed by the ATC, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 4 Page 10 of 20 Event
Description:
S/G Blowdown Radiation Monitor RM-23 fails high (ECG)
Time Position Applicants Actions or Behavior ALL Diagnoses RM-23 (Blowdown rad monitor) failing high from the following:
- PK11-17 alarms (S/G Blowdown high rad alarm)
- PPC rad monitor screen
- VB2 rad monitor recorder (PPC)
SRO Enters PK11-17 annunciator response (AR PK11-17, S/G Blowdown Hi Rad)
Note: The below action to complete the blowdown isolation may be done using the AR procedure, or may be done when noted by the ATC or BOP, as it is a failure of an automatic action.
BOP * (2.1.1) Verifies that blowdown has isolated; verifies all (8) outside containment and sample isolation valves closed (two lower rows of red valve lights at bottom left of VB3; FCVs 151/154/157/160, and FCVs 250/248/246/244)
BOP * (2.1.1.a, 2.1.1.b, 2.1.2) Verifies that S/G blowdown has shifted from the outfall to the Equipment Drain Receiver (EDR) (VB3, lower, far left) (FCV-499 opens, FCV-498 closes) Must take FCV-498/499 switch on VB3 to Drn Tk position.
ALL * (2.1.3, 2.1.6) Evaluates other S/G RMs (RM-19 vs RM-23, and also checks RMs 71-74 (steam line) and RM-15/15R (steam jet air ejector) to determine that RM-23 is probably a failure of the rad monitor SRO * (2.1.4, 2.1.5, and later steps) May make directions to prepare to restore blowdown (will not have time prior to next event)
SRO * (2.1.7) Directs S/Gs to be sampled per CAP AP-1 (quick sample procedure)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 4 Page 11 of 20 Event
Description:
S/G Blowdown Radiation Monitor RM-23 fails high (ECG) (con't)
Time Position Applicants Actions or Behavior (AR PK11-17, S/G Blowdown Hi Rad, con't)
ALL * (optional) (2.1.8) May check OP O-4 (small S/G Tube leakage check and guidance procedure) and PPC screens to confirm that no S/G tube leakage is occurring (none is, and screens will show this)
- Directs maintenance to investigate failed rad monitor and valve Cue: (using appropriate time compression) Preliminary troubleshooting shows that none of the auto-closure signals are reaching FCV-498; RM-23 is failed (high) (this cue is critical to Tech Spec call on FCV-498)
SRO Implements ECG for failed Rad Monitor RM-23 (ECG 39.3.B, requires grab samples)
SRO May go to OP AP-3 "Steam Generator Tube Failure." After finding no indications of increasing S/G activity, should exit AP-3 in step 4.a RNO.
Proceed to the next event once Tech Specs / ECGs are addressed, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 5 Page 12 of 20 Event
Description:
VCT Level Channel LT-112 Fails Low (causes auto makeup)
Time Position Applicants Actions or Behavior Note/Caution: Ensure that the ATC has placed the makeup system back in AUTO prior to activating this failure.
ALL Diagnosis of makeup control failure is made by one or more of the following:
- LT-112 shows low level (0%), but VCT pressure shows normal, and CCP operation (suction) is normal (all on VB2)
- Yokogawa recorder (LT-112A) (VB2 upper left)
- Makeup Control is taken to STOP (on the makeup control HMI, CC2) (may be done before or during OP AP-19 use)
SRO Implements OP AP-19, Malfunction of the Reactor Makeup Control System (OP AP-19, Malfunction of the Reactor Makeup Control System)
ATC * (1) Ensures M/U set to correct mode (either AUTO and running, or AUTO and stopped if action taken above)
ATC * (1) Ensures system is selected to start (will probably be selected to STOP [now or later] due to unneeded makeup operation); may select STOP before or during OP AP-19 use BOP * (2) Checks makeup system pumps and valves lineup up, and in AUTO (VB2, lower center; they are all normal)
ATC/BOP * (3) Verifies VCT level channels OPERABLE:
- Observes discrepancy between LT-112 (0%), and LT-114 (normal level); may use VCT pressure and/or normal CCP operation to diagnose that LT-112 has failed (probably diagnosed prior to procedure entry); note: may use operator information manual (OIM) as a diagnostic tool (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 5 Page 13 of 20 Event
Description:
VCT Level Channel LT-112 Fails Low (causes auto makeup) (con't)
Time Position Applicants Actions or Behavior (OP AP-19, Malfunction of the Reactor Makeup Control System, con't)
ALL * (3 RNO) Goes to App A (1.a.1), and determines what effect the failed LT-112 will have on makeup system operation ATC * (App A, 1b) If not already done, places makeup system in STOP ALL * (App A, 1b) (optional) Crew may tailboard how to operate the makeup system; the two most obvious methods would be to do MANUAL makeups from that point, AND/OR just enable AUTO makeup each time makeup is needed (and STOP when done on the HMI)
ATC/BOP * (as time permits) (4) Verifies CCP suction parameters are normal (CCP flow/amps/ pressure, VCT level/pressure; VB2 and CC2 meters)
SRO * (as time permits) (5) Notifies Tech Maintenance to troubleshoot and repair Proceed to the next event once the diagnosis is made, and the makeup system has been placed in STOP, per the lead examiner
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 6&7 Page 14 of 20 Event
Description:
Steamline Break OC (1-2 S/G) and ATWS (man trip works) (CT)
Time Position Applicants Actions or Behavior ALL Increased steam flow (VB3/CC3 steam flow meters, recorder, PPC) and noise is noted, as well as dropping S/G pressures (VB3, PPC) and Tave (PPC, CC2, VB2)
ALL Crew responds to SI by going to EOP E-0; may initiate manual SI/trip prior to automatic actuation ALL/ATC After noting that reactor trip is needed but not actuated, manual trip switch is used (CC1 or VB2) to trip reactor (successfully); this may be done prior to entry to EOP E-0, or during step 1 of EOP E-0. (Critical Task) (WOG CT E-0-A, reactor is manually tripped prior to completion of step 1 of EOP E-0) **
SRO Implements EOP E-0, Reactor Trip or Safety Injection (EOP E-0, Reactor Trip or Safety Injection)
ATC * (1) Notes reactor NOT tripped (unless tripped above), and performs manual trip (CC1, or VB2), then verifies trip (trip bkrs open (VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left)) (CT, see above) **
ATC * (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)
BOP * (3) Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)
ATC/BOP * (4) Checks if SI actuated (PK08-21 ON, also checks VB1 red train lights and/or train equipment to verify both trains actuated)
SRO * (5) Directs App E implemented (usually to BOP)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 6 Page 15 of 20 Event
Description:
Steamline Break OC (1-2 S/G) (con't)
Time Position Applicants Actions or Behavior (EOP E-0, Appendix E) (EOP E-0 body steps con't on next page)
BOP App E is implemented:
- (1a) Checks no personnel in Containment (part of turnover; may not voice)
- (1b) Announce trip/SI on PA system
- (2) Checks main generator - tripped (PK14-01 ON, output bkrs open, and exciter field bkr open, CC3 right side)
- (3 & 4) Verify Phase A and containment vent isolation complete (VB1, ESF status lights, red lights ON, white lights OFF)
- (6) Verifies Feedwater isolation complete (normal FWI portion is complete, with red light ON, and white lights OFF) (S/G portion: red light is ON, white lights OFF)
- (7 & 8) Checks containment spray, Phase B, and main steam isolation - NOT required (red lights are OFF for ESF for these on VB1, and white lights are OFF)
- (9) Checks AFW status (MDAFPs running, TDAFP may be running, VB3 center area); verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)
- (10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel); expected is that only CCPs will be delivering flow at this RCS pressure
- (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)
- (14) Checks secondary systems (MFPs tripped (VB2, green lights ON), only one CB Pp set running, condenser status (not avail))
- (15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)
- (16 - 21) Verifies DGs running normally (VB4, freq (60), volts (120), speed (900)); verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area); verifies MSRs reset (CC3 Triconex HMI);
throttles RCP seal injection flows to normal (FCV-128, to 8-13 gpm each, CC2);
checks PK11-04 NOT IN (SFP alarm); notifies Shift Foreman of completion (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 6 Page 16 of 20 Event
Description:
Steamline Break OC (1-2 S/G) (con't)
Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, con't)
ATC * (6) Checks RCS temperature - stable (temps will initially be dropping due to faulted S/G; AFW will be throttled back (VB2, upper panel lower area)
ATC * (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open), and no elevated tailpipe temps or sonic flows on safeties/PORVs (VB2 -
upper panel, far right); checks Pzr sprays closed (CC2)
SRO/ATC * (8) Checks RCP trip criteria (RCS pressure [VB2, PPC] is not < 1300 psig, all SI and ECCS CCPs are running, criteria is not met) (VB1 and VB2)
ATC/BOP * (9) Checks for faulted S/Gs
- Faulted - notes 1-2 S/G pressure is dropping rapidly and/or completely depressurized (all S/G pressures on VB3)
SRO Transitions to EOP E-2 (EOP E-2, Faulted S/G Isolation)
SRO Reads (3) CAUTIONS prior to step 1 BOP * (1) Verifies ALL MSIVs and bypasses are closed (VB3, upper panel, left side)
BOP * (2) Checks for any intact S/G (1-1, 1-3, and 1-4 S/Gs have stable pressures, consistent with the RCS cooldown from the 1-2 S/G); continues in E-2 (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 6 Page 17 of 20 Event
Description:
Steamline Break OC (1-2 S/G) (con't) (CT)
Time Position Applicants Actions or Behavior (EOP E-2, Faulted S/G Isolation, con't)
BOP * (3) Identifies 1-2 S/G as faulted (VB3, pressure is still dropping in uncontrolled manner, or completely depressurized at this point)
BOP * (4) Isolates 1-2 faulted S/G (see BOLD substeps below, completed prior to exit from EOP E-2) (Critical Task) (WOG CT E-2-A, isolate faulted S/G prior to exit from EOP E-2): **
- Verifies MFIV FCV-439 closed (all of these controls on VB3, lower left)
(already closed)
(already closed)
- Verifies S/G 1-2 10% steam dump closed (PCV-20) (already closed)
- Closes FCV-37 to isolate steam from 1-2 S/G to TDAFP BOP * (4f) Verifies AFW flow to at least one intact S/G (VB3, upper panel, center area meters)
BOP * (5) Checks CST level > 10% (VB3, upper panel, center area meter and recorders)
BOP * (6) Removes WR Thot input to SCMM for loop 2 (behind boards, PAMS panel behind VB3)
- Goes to PAM4 panel
- Presses Configuration Summary
- Presses Failed S/G
- Presses the PB for the Thot to be disabled (2)
- Presses Disable Loop 2 (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 6 Page 18 of 20 Event
Description:
Steamline Break OC (1-2 S/G) (con't)
Time Position Applicants Actions or Behavior (EOP E-2, Faulted S/G Isolation, con't)
ATC/BOP * (7) Checks for ruptured S/Gs
- No valid alarm on PK11-06, PK11-17, or PK11-18 (RM-23 is failed high)
- No upward trend on RM-19, 15/15R, or RM-71/72/73/74 (no trends)
(recorders on VB2 (and PPC))
- Chemistry contacted to sample (per CAP AP-1, quick sample procedure)
ATC/BOP * (8) Checks ECCS Termination Criteria (met)
- RCS Subcooling > 20°F (it is)
- Secondary Heat Sink (> 435gpm AFW flow or NR S/G level) (satisfied)
- RCS pressure - stable or rising (it will be)
- Pzr Level - greater than 12% (it will be)
SRO Implements E-1.1, SI Termination, and performs a procedure transition brief (EOP E-1.1, SI Termination)
ATC * (1) Resets Safety Injection (SI) (VB-1, vertical panel, right of center)
ATC/BOP * (2) Aligns Charging (stops all but one high head ECCS CCP)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 6 Page 19 of 20 Event
Description:
Steamline Break OC (1-2 S/G) (con't)
Time Position Applicants Actions or Behavior (EOP E-1.1, SI Termination, con't)
Note: RCS pressure may need to be watched for a time (Pzr subcooling may cause slight lowering of RCS pressure until heaters catch up, following fill of Pzr during this event);
pressure tends to drop a bit after the 1st ECCS CCP is stopped. Crew should evaluate conditions (subcooled pressurizer) and wait to stabilize vs improper transition to E-1.2.
ATC * (3) Checks RCS pressure - stable or increasing (it is - or, if dropping slightly, it will stabilize shortly and rise again - see note above)
ATC * (4) Isolates charging injection, by closing 8803A/B and 8801A/B (lower left on VB-2)
ATC/BOP * (5) Establish (normal) charging flow
- Closes HCV-142 (CC2 right side) (ATC)
- Opens 8107 and 8108, Charging Hdr isolation valves (VB2 lower center area) (BOP)
- Verifies 8146 (normal charging valve) OPEN (it is) (VB2 lower left area)
(BOP)
- Verifies 8145 and 8148 (aux spray valves) CLOSED (they are) (VB2 lower left area) (BOP)
- Throttles open FCV-128 to establish flow (already open to maintain seal flows) (CC2, right side) (ATC)
ATC * (6) Adjusts FCV-128 (charging flow control) and HCV-142 (RCP seal backpressure) to maintain Pzr level 17-60% and seals 8-13 gpm (most likely, level will be high, so both valves will be throttle to a minimum charging to support RCP seal flows) (CC2, right side)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 1 Event No.: 6 Page 20 of 20 Event
Description:
Steamline Break OC (1-2 S/G) (con't)
Time Position Applicants Actions or Behavior (EOP E-1.1, SI Termination, con't)
ATC/BOP * (7) Stops SI PPs
- Checks RCS pressure - stable or increasing (it is)
- Checks RCS pressure - greater than 1650 psig (it is)
- Stops both SI pps (VB1, lower center)
ATC * (8) Stops both RHR pps (VB1 lower right), after checking aligned to RWST (they are)
Terminate this scenario once the RHR pumps have been stopped, per the lead examiner (may extend to placing letdown in service, if desired)
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ATTACHMENT 1 - SIMULATOR SETUP Run Init/Initialize /CCs and VBs/Run Drill 81 Any tags are placed/removed as necessary
- CBCs on 1-2 DG start/stop, auto/manual, and output breaker The proper Delta-I curve on CC1 and Reactivity Handbook for the simulator INIT in place.
The Rod Step Counters indicate correctly.
Run Clear Recorders icon on lower left desktop to clear YOKOGAWA recorder memories.
Clear the PCS HMIs (NSR) by "flushing" the trend buffer; then, restart the "Window Viewer" app.
Boric Acid and Primary Water Target Blender set to values identified in Lesson Record PPC MAX on CC2 lamicoid.
Record Boron Concentration for desired simulator INIT on CC2 lamicoid.
Circuit breaker flags are correct on CC1 (Proportional Heaters), CC3, VB4, and VB5 Equipment status lamicoids are correct:
RHR Valves (8726A/B and 8734A/B) - CLOSED (OPEN if RHR in service)
H2 or N2 on VCT - H2 ( unless shut down training)
SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - CONT. RM. VENT TRAIN 1 BUS F SELECTED TO BUS 1H - CONT. RM. VENT TRAIN 1 BUS H B.A. XFER PP SUPPLYING BLENDER - BA PP 1-2 RADWASTE DISCH AND CHLORINATION - ASW 1-1 OFF NORMAL LAMICOIDS OR PINK MARKERS - Placed as needed or return to CC3 The Plant Abnormal Status Board is updated for Charging Pump Status, Boron Conc, PRA Risk Status and Work Week Matrix.
Copies of Procedures, Attachments; Appendixes; Foldout Pages; Annunciator Response Procedures and commonly used forms are in binders and NOT Marked up.
PPC Setup:
- PPC BIG Screen (set to TABULARLG1), select new list, private, Sim Large)
- RODCONFIG is updated (click Apply when completed)
SPDS (screens and time updating), A screen RM, B screen SPDS.
CC3 Annun. CRT big screen (if enabled then get alarm it needs reset - Tools, keyboard, Tools, password - which is "A", File Exit - Start over)
The chart recorders are operating properly. DDR10s and Turbine Vib Recorder are acknowledged and in AUTO. CC1 NR-45 on proper screen. PAMS RVLIS/TMS screens on Summary Page.
All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status, as needed.
Alarm A&E Viewer window is activated prior to run, and printer is placed ,ONLINE, if needed.
Triconex DEH/DFW alarms have been acknowledged/cleared.
Seismic drawer put back; check for any alarms on the Rad panels PC setup for SVC tailboard (G-3 ENF Reset, RCPs, U-1 Safety Monitor)
Verify paper in HPD2 and print a test page.
Verify Annunciator Horn is on (BELL ON) and Sound Effects are on (SOUND ON).
The video, audio, and communication systems are set up and functioning Turn down plant PA on simulator floor (restore to original setting when scenario completed)
DC-2012-11-DRAFT OPERATING TEST.docx Page 23 of 263 Rev 2
TIMELINE AND BOOTH/CONSOLE OPERATOR ACTIONS Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Setup Simulator INIT IC-511 75% power, MOL, CB = 838 , Integrators: BA - 00, per Checklist and PW - 25
- Tags: CBCs on DG 1-3 (A/M, Start, output bkr)
X Setup Drill 81 Reset normal engineering values X Setup Start TEAM data collection Collect data for scenario for NRC Exam Team X Setup DRILL 36 in AUTO Clears DG 1-3 for maintenance X Once crew has DRILL 9203 in AUTO Scenario malfunctions are inputted once the crew taken the watch takes the watch X 15 min after pmp asw2 1,0,0,0,d,0 1-2 ASW pp does not auto-start on low pressure 8149A is opened pmp asw1 4,0,0,900,c, 1-1 ASW pp trips on OC 15 min after 120 letdown is xv2o212r,0 placed in service (8149A opened)
X When requested Turbine Bldg: 52-HF-08 bkr for ASW pp 11 has B phase OC flag dropped.
Intake: ASW pp 11 motor has charring (bring in door alarm prior to this report) 15 min after 1-2 mal gen4 act 3,0,900,c, Load Rejection (occurs 5 min after 1-2 ASW pump ASW pp is started xv1i243c,0 started) 15 min after xmt rms23 3,1e+06,1,900,c, RM-23 fails high power drops fnispr.lt.28,0 below 28% vlv sgb14 2,1,0,0,d FCV-498 (blowdown to disch tunnel) doesn't auto
,.not.xv3ia89c #rbdf498 close & FCV-499 doesnt auto open, can be operated VLV SGB13 2,0,0,0,d manually on VB3
,.not.xv3ia89c #rbdf499 X When Maint told Cue: (using appropriate time compression) Preliminary troubleshooting shows to investigate that none of the auto-closure signals are reaching FCV-498; RM-23 is failed FCV-498 & RM-23 (high) (this cue is critical to Tech Spec call on FCV-498)
X Note: Make sure that Makeup Controller is in AUTO PRIOR to actuating next event!
15 min after xmt cvc19 3,0,3,900,c, LT-112 fails low (15 minutes after FCV-498 is closed) closing FCV-498 .not.xv3ia89c,0 (causes continuous auto makeup)
On SI mal ppl5a act 1,0,0,d,0 ATWS (short) on steam break/SI (man trip switch mal ppl5b act 1,0,0,d,0 works)
On SI mal ppl3a act 3,0,0,d,0 Train A of SI and Phase A do not actuate in AUTO mal ppl1a act 2,0,0,d,0 (must be aligned manually) 15 min after mal mss3b act Steam Break (large) OC on the 1-2 S/G (15 minutes LT-112 failure 5e+06,205,900,c, after primary water flow detected from LT-112 failure, wcvc111(1).gt.10,0 above)
X 5 min after SI/Trip DRILL 32 in AUTO Nuclear Operator actions on a trip X If requested DRILL 17 in AUTO If requested to open S/G B/D sample valves for S/G samples X If requested DRILL 15 in AUTO If requested to break vac, secure gland steam, etc DC-2012-11-DRAFT OPERATING TEST.docx Page 24 of 263 Rev 2
DRILL FILE TEXT
- L111 NRC Exam Scenario 01 (DRILL 9203)
- 9/7/12, glh
- (1-2 ASW PP doesn't auto start; man OK)
- PMP ASW2 AUX SALTWATER PP 12 #ocwasp12 pmp asw2 1,0,0,0,d,0 #ocwasp12
- (1-1 ASW trips on OC 15 min after 8149A opened)
- PMP ASW1 AUX SALTWATER PP 11 #ocwasp11 pmp asw1 4,0,0,900,c,xv2o212r,0 #ocwasp11
- (load rejection 15 minutes after 1-2 ASW pp started)
- mal GEN4 GENERATOR LOSS OF LOAD mal gen4 act 3,0,900,c,xv1i243c,0
- (FCV-498 doesn't auto-close on RM-23 fail high - man OK) vlv sgb14 2,1,0,0,d,.not.xv3ia89c #rbdf498 VLV SGB13 2,0,0,0,d,.not.xv3ia89c #rbdf499
- (RM-23 fails high 15 min after reaching 28% power)
- XMT RMS23 RE-23 S/G BD OVERBOARD LIQUID MONITOR #rrmsr23 xmt rms23 3,1e+06,1,900,c,fnispr.lt.28,0 #rrmsr23
- (LT-112 fails low, causing auto m/u, 15 min after closing fcv-498)
- XMT CVC19 VCT 1-1 LEVEL, ALM0341, SPDS, LI-112 #bcvc112 xmt cvc19 3,0,3,900,c,.not.xv3ia89c,0 #bcvc112
- mal PPL5A REACTOR TRIP BREAKER RTA FAILURE TO OPEN (TRAIN A) mal ppl5a act 1,0,0,d,0
- mal PPL5B REACTOR TRIP BREAKER RTB FAILURE TO OPEN (TRAIN B) mal ppl5b act 1,0,0,d,0
- mal PPL3A SAFETY INJECTION ACTUATION/PHASE A FAILURES (TRAIN A) mal ppl3a act 3,0,0,d,0 mal ppl1a act 2,0,0,d,0
- (1-2 S/G stm break OC, 15 min after M/U water > 10 lbm/sec)
- mal MSS3B STEAMLINE BREAK OUTSIDE CONTAINMENT (S/G #2) mal mss3b act 5e+06,205,900,c,wcvc111(1).gt.10,0 DC-2012-11-DRAFT OPERATING TEST.docx Page 25 of 263 Rev 2
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 111 Days Operating Mode: 1 Gross Generation: 891 MWe Power Level: 75.7 % Net Generation: 843 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 307 SCF / 326 SCFD 5 day ave NEW EMERGENT WORK:
- none SHUTDOWN TECH SPECS / ECGS:
- TS 3.8.1.B DG 1-3 OOS for corrective maintenance on fuel racks (discovered during normal surveillance run last night); RTS estimate is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; last partial STP I-1C completed 30 minutes ago (due in 7.5 hrs); action 3.8.1.B.3.1 has been completed.
ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- none TURNOVER ITEMS:
- Unit was ramped to 75% 8 days ago for high vibrations on the Htr #2 Drain Pump; the motor has been replaced, and following some alignment problems, the pump has been returned to service; due to some minor/intermittent pump vibrations, engineering will be doing data-taking for another shift or two; management will then decide if the plant will ramp back to 100%.
- Chemistry has requested 120 gpm letdown first thing on your shift for minor crud burst (OP B-1A:XII and OP B-1A:V provided for your PJB)
PRIORITY ITEMS FOR NEXT SHIFT:
- Maintain current power level
- Place 120 gpm letdown in service OPERABILITY ITEMS:
- TS 3.8.1.B DG 1-3 OOS - 1 day into 14 day action DC-2012-11-DRAFT OPERATING TEST.docx Page 26 of 263 Rev 2
Shift Foreman Turnover ANNUNCIATORS IN ALARM:
TURNOVER ITEMS:
- U maintain 75% - no one in containment; following more data-taking on the Htr #2 Drip Pump, the unit may ramp back to 100% (as early as tomorrow).
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: _MOL_.
- Power History: Steady State @ 75% for 7+ days, previously at 100% for 73 days.
- Boron concentration is _838 ppm_ from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 200 steps on CBD.
- Diluting the RCS approximately 25 gallons every 1.5 hrs.
- The last dilution was completed _15_ min ago.
- Rod motion: none planned, as needed to maintain I on target CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
- Partial STP I-1C due in 7.5 hrs OTHER ABNORMAL PLANT STATUS
- None DC-2012-11-DRAFT OPERATING TEST.docx Page 27 of 263 Rev 2
Appendix D (rev 9) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 2 Op-Test No.: L111-NRC Examiners: Operators:
Initial Conditions: 2% with MFW in service, BOL, 1575 ppm boron Turnover: OP L-3, @ step 6.29, ready to raise power to 8%
Event Malf Event Event No No. Type* Description 1 N/A R (ATC) Raise reactor power from 2% to 8% power 2 ser 0232 C (SRO, At 3% power, Pzr PORV PCV-455C block valve 8000B causes ground, vlv pzr2 BOP) shorts out/goes mid-position, and then breaker trips (can't be closed) (TS) dsc pzr2 3 xmt cvc16 I (SRO, TE-130 fails low (causes TCV-130 to close in auto), causing high letdown BOP) temperature; manual control is used to restore letdown temperature 4 mal sei1 C (SRO) Earthquake (mod) causes construction crane impact on RWST about 35%
asisrwst level (TS only) (later will cause ECA-1.1 entry and CT) 5 cnv rcs2 C (ALL) PCV-455B (Pzr spray valve) opens slightly on earthquake (mech bound, can't control from C/R); will fail fully open (requiring reactor trip and RCP S/D) (once RWST TS addressed) 6 mal rcs3d C (ALL) RCS leak starts and escalates (on aftershock), requiring manual SI 7 vlv sis3/sis4 C (BOP) 8801A/B fail to open on SI, requiring manual opening to establish high head ECCS injection (CT) 8 mal rcs3d M (ALL) SBLOCA and Loss of Emergency Coolant Recirculation (ECR): with low asisrwst RWST level, causes transfer to cold leg recirc procedure and then loss of ECR procedure; M/U to RWST is directed, and ECCS flow is reduced (CT)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 8. Total malfunctions (5-8) 6
- 9. Malfunctions after EOP entry (1-2) 2
- 10. Abnormal events (2-4) 3
- 11. Major transients (1-2) 1
- 12. EOPs entered/requiring substantive actions (1-2) 2
- 13. EOP contingencies requiring substantive actions (0-2) 1
- 14. Critical tasks (2-3) 2 Rev 2 comments: deleted one event; adjusted timing; added one more ARP option DC-2012-11-DRAFT OPERATING TEST.docx Page 28 of 263 Rev 2
Appendix D (rev 9) Scenario Event Description Form ES-D-2 SCENARIO
SUMMARY
- NRC #2
- 1. Control Rods are pulled one full step at a time to raise power slowly from 2% to 8% power, in preparation for rolling the main turbine.
- 2. At 3% power, a 480v Bus G ground alarm will signal a malfunction of Pzr PORV block valve 8000B. The valve will (shortly after the alarm) simulate a short/electrical problem, and move to mid-position (and not move thereafter); a few minutes later, the breaker for the valve (8000B) will trip open (and the ground alarm will clear. Tech Spec actions for TS 3.4.11.C will apply (1 hr to place associated PORV in MAN/CLOSED). (TS)
- 3. Letdown heat exchanger temperature element TE-130 will fail low, causing actual letdown temperature to rise and causes alarms, letdown divert from the demineralizers, and rising VCT temperature. OP AP-11, Malf of the CCW System, Sec D, will be used to take manual control of letdown temperature (TCV-130), and control temperature manually.
- 4. A moderate seismic event causes a large crane in the 115' tank area to tip over and puncture the RWST, about 1/3 of the way up from the bottom of the tank (and it drains slowly to that level). Tech Spec 3.5.4.B will be implemented (1 hr to restore, which is not possible). This failure sets up the final event (loss of emergency coolant recirc capability).
(TS)
- 5. Also, one Pzr Spray Valve (PCV-455B) fails partially open (but remains within the ability of the pressure control system at this point). Once the RWST Tech Spec is addressed, the spray valve will fail full open, causing the need for a manual reactor trip, and trip of the 1-1 and 1-2 RCPs. The crew will stabilize in EOP E-0.1, Reactor Trip Response.
- 6. An RCS leak starts (aftershock) (slow ramp to 900 gpm), requiring actions to try to keep up with the leak, and then initiate a manual Safety Injection (SI) when those efforts fail.
- 7. On the SI, two of the charging injection isolation valves fail to open, but are opened manually in order to supply high-head ECCS injection. (CT)
- 8. The RCS leak escalates to a SBLOCA, and the crew proceeds (eventually) to ECA-1.1, Loss of Coolant Recirc Capability, where the crew will direct makeup to the RWST, and throttle ECCS flow to conserve RWST inventory. (CT)
The scenario is terminated once RWST makeup has been directed, and ECCS flow has been reduced, per EOP ECA-1.1.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 1 Page 01 of 19 Event
Description:
Raise Reactor Power from 2% to 8%
Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.
(OP L-3, Secondary Plant Startup, starting at step 6.29)
SRO Reads NOTE prior to step 6.29 ATC * (6.29) Slowly raises power to 8% by pulling control rods one step at a time.
SRO Provides reactivity oversight while raising power BOP * (6.30) Monitors feed/steam P (PI-509, VB3 or CC2, DFWCS HMI on CC3)
BOP * (6.31) Verifies that DFWCS maintains constant P during rise in power (it's in auto, and will maintain P)
SRO Reads CAUTION prior to step 6.32 The next event will occur when power (nuclear) reaches 3%, or per lead examiner.
- Critical Task DC-2012-11-DRAFT OPERATING TEST.docx Page 30 of 263 Rev 2
Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 2 Page 02 of 19 Event
Description:
Pzr PORV Block Valve 8000B ground/short (TS)
Time Position Applicants Actions or Behavior ATC Notes and updates to SFM alarm on 480v Bus G (PK17-24, 480v Bus 1G Ground),
Note: The Shift Foreman (SFM) may take one or more of the following actions, using guidance in AR PK17-24, or just basic troubleshooting principles.
(AR PK17-24, 480v Bus 1G Ground, IF implemented; otherwise, steps per SFM)
Sequence: The ground alarm will be followed by 8000B going mid-position (simulating a short),
and stick there. Several minutes later, the bkr will trip and the gnd alarm will clear.
SRO Implements AR PK17-24, 480v Gus 1G Ground SRO Reads NOTE prior to step 2.1.1 ALL * (2.1.1) Attempts to locate grounded equipment (has board operators check bus 1G equipment for problem indications
- Notes that 8000B is mid position (and may attempt to restore to open); should note 8000B as the problem, either by the mid-positioned valve and/or by the time the breaker trips and 8000B goes dark, and the alarm clears.
SRO * (2.1.2) May have breaker for 8000B opened (may not happen, if the breaker trips first )
SRO * (2.1.3) Determines that de-energizing the entire 480v Bus is not needed, and moves on SRO * (2.1.4) Directs maintenance to write notification and repair valve motor/breaker SRO/BOP * (2.1.5) Implements Tech Spec 3.4.11.C for 8000B (1 hr)
SRO Should recognize a mode change is not allowed (TS 3.0.4). If Shift Manger is asked about continuing the startup, cue SFM to refer to Tech Specs.
Proceed to the next event once the event is diagnosed, and Tech Specs have been implemented, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 3 Page 03 of 19 Event
Description:
Letdown Heat Exchanger temperature (TE-130) fails low (causes high temp)
Time Position Applicants Actions or Behavior Note: There are two possible procedure-driven outcomes to this event: the predicted outcome is that the crew will recognize the controller failure in auto due to the temperature indicator failing low, and use manual on the controller to restore normal temperature, using AR PK04-21. The operator may continue to OP AP-11, section D; however, another outcome is written (on following page(s)) to allow for valid entry into the letdown line failure procedure (OP AP-18), which will isolate letdown. Either outcome will provide actions for at least the SRO and BOP (no credit taken for ATC).
ALL Notes/diagnoses letdown high temperature (or TE-130 failure) from one or more of the following:
- TE-130 temperature low (lower than ultimate heat sink) (VB2, center vertical)
- VCT temperature rising (VB2, center vertical)
- Letdown diverted (TCV-149) to VCT (away from demineralizers) (VB2, skirt, center)
- PK04-21 alarm (on letdown high temp and/or high temp divert)
(AR PK04-21, Letdown Press/Flow/Temp, IF used; otherwise, see AP-11 or AP-18 actions following these)
SRO Implements AR PK04-21 section 2.1 for General Actions SRO/BOP 2.1.1 Checks letdown not isolated SRO/BOP 2.1.2 Checks Letdown break is not suspected SRO/BOP 2.1.3 Checks letdown HX outlet pressure is not high.
SRO/BOP 2.1.4 Checks letdown flow not excessive SRO/BOP 2.1.5 Notes that letdown HX outlet temperature is high
- a. Adjusts HC-130B (VB2) manually as necessary to control ltdn temperature (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 3 Page 04 of 19 Event
Description:
Letdown Heat Exchanger temperature (TE-130) fails low (causes high temp) (con't)
Time Position Applicants Actions or Behavior (OP AP-11, Malf of the CCW System, Section D, if used) (if OP AP-18 used, go to next section and mark this section N/A)
SRO Implements OP AP-11, Malfunction of the CCW System, Section D (loss of CCW to Ltdn HX)
BOP * (1) Checks TCV-130 controlling letdown temperature (actual temperature is high, but controller output is zero, so it is not controlling in auto) (VB2, vertical center, lower area)
BOP * (1 RNO) Takes manual control of TCV-130 by pressing MAN PB, and then raise PB to reestablish flow to the letdown HX (can use VCT temperature as alternate indication of letdown temperature)
SRO/BOP * (2) Determines that letdown temperature can be maintained in the normal range using the TCV-130 controller in MANUAL SRO
- May contact maintenance to repair TE-130 Note: The crew may discuss contacting chemistry about placing demineralizers back in service (TCV-149 back to normal), but the next event will occur before that evaluation can be completed.
Note: If for any reason the crew decides that they do not have temperature under control, the procedure directs them to isolate letdown. If that occurs, the steps are listed in the next section (under AP-18 actions), and not repeated in the AP-11 actions, above).
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 3 Page 05 of 19 Event
Description:
Letdown Heat Exchanger temperature (TE-130) fails low (causes high temp) (con't)
Time Position Applicants Actions or Behavior (OP AP-18, Letdown Line Failure, if used; mark N/A if not used)
SRO Implements OP AP-18, Letdown Line Failure ATC * (1a) STOPS load changes (power rise) by stopping rod pulls (CC1, right side)
SRO * (1b, 1c) Notes no RCS heatups/cooldowns, or draindowns in progress BOP * (2) Isolates letdown by:
- (2a) Closes 8149C (letdown orifice isolation) (VB2 skirt, left side)
- (2b) Closes LCV-459 and LCV-460 (letdown isolations) (next to above vlv)
- (2c) Verifies HCV-133 Closed (it is) (RHR letdown controller) (VB2 vertical, center, lower area)
ATC * (3) Checks RCS for leakage (pressure and level) both will now be rising (PPC, CC2 recorders, VB2 meters)
ATC * (4) Reduces charging to minimum (RCP seals only)
- Takes FCV-128 (or HC-459D) to MAN, and lowers demand to get charging header flow to about 32 - 52 gpm (all on PPC or on CC2)
- Takes HCV-142 dial CCW (basically fully closed, all flow to seals); RCP seal flows at 8-13 gpm (CC2, and PPC)
SRO Next steps are to place excess letdown in service and take recover actions (the next event will occur first and preclude this)
Note: Placing excess letdown in service during this scenario is not needed or desired (too much time); the next event should be implemented.
Proceed to the next event once either 1) TCV-130 is controlling letdown temperature manually using OP AP-11, or 2) Letdown has been isolated per OP AP-18, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 4 Page 06 of 19 Event
Description:
Earthquake & Rupture of the RWST (TS)
Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable (per NRC request).
Note: Although the Shift Foreman may choose to implement CP M-4 (Earthquake) him/her-self, it is not an objective of the scenario, and it would be expected that with equipment problems and a plant status that the procedure be handed over to the Shift Manager or U-2 Shift Foreman.
ALL Earthquake is diagnosed from one or more of the following:
- PK15-24, Seismic Instrument System (actuated on triggers)
- Physical shaking and noise from the earthquake
- Various tank alarms going in and out (due to water shifting from earthquake, programmed into simulator modeling)
Note: AR PK15-24 actions are to go to CP M-4 if the reactor does not trip, so those procedure actions are not listed here.
SRO Implements CP M-4, Earthquake (may hand off this procedure at any time to the Shift Manager or U-2 Shift Foreman)
Cue: (from Shift Manager, once CP M-4 identified as procedure to use) The U-2 Shift Foreman (U-2 SFM) and the Work Control Shift Foreman (WCSFM) will implement CP M-4, Earthquake.
ATC/BOP During board walkdown and/or review of tank alarms coming in/out, RWST level is diagnosed as dropping from review of actual levels (VB2, far left, top) and/or PK06-20 (PPC Select alarm, with low RWST level required to be assigned)
Cue: (from security, in 115' tank area) A large industrial crane (with a load attached) became unstable and tipped over during the earthquake, striking and coming to rest on U-1 RWST.
A rip about 4' long and several inches wide occurred about 1/3 the way up from the bottom of the tank, which is currently draining to the 115' yard area. RP and maintenance have been called, and an action plan will be created to try to repair the breach. No injuries were reported.
Note: AR PK06-20 actions are not written here, as they basically just say to identify and correct the cause.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 4 Page 07 of 19 Event
Description:
Earthquake & Rupture of the RWST (con't) (TS)
Time Position Applicants Actions or Behavior SRO Determines Tech Spec ramifications of RWST break:
- Implements Tech Spec 3.5.4.B (1 hr to restore, which is not possible; otherwise S/D and cooldown is required)
Note: RWST level will settle out (after about 10 minutes or so) to 34-35% level.
The next event (spray valve failure, in stages) occurs in parallel with this event.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 5 Page 08 of 19 Event
Description:
Pzr Spray Valve (PCV-455B) fails open during earthquake Time Position Applicants Actions or Behavior ALL Pzr Spray Valve PCV-455B is diagnosed as partially open from one or more of the following:
- Green "closed" light out above spray valve controller (CC2, above PCV-455B controller)
- Pzr Pressure is noted to be dropping slowly (CC2 recorder, PPC, VB-2 meters)
- Low pressure alarm (eventually, at approx 2210 psig), PK05-16 Note: PCV-455B is a 2-stage failure. Initially, the valve will be open only enough to cause pressure to fall and rise with extra Pzr heater operation. Once the RWST Tech Spec has been addressed (and with cue from lead examiner), the valve will fail full open, eventually requiring a reactor trip and tripping of RCPs 1-1 and 1-2.
ATC Attempts to close PCV-455B (will not close using controller) (either before or during procedure guidance below)
Note: Crew may go directly to OP AP-13, Malfunction of the Reactor Pressure Control System, or may enter the AR PK05-16 for low pressure first, and then go to AP-13.
(AR PK05-16, Pzr Press Hi/Lo, if entered; otherwise, mark section as N/A)
SRO Implements PK05-16, Pzr Press Hi/Lo (due to pressure intermittently below 2210 psig)
ATC * (2.1.1) Determines that reactor has not tripped (pressure is low, but cycling with heaters)
ATC * (2.1.2) Verifies Pzr PORVs closed (they are)(VB2, far right)
- (2.1.2) Attempts to close PCV-455B (won't close) (if not already done above)
- (2.1.2) Verifies backup heaters ON (already cycling ON/OFF to maintain pressure); may take all backup heaters to manual ON (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 5 Page 09 of 19 Event
Description:
Pzr Spray Valve (PCV-455B) fails open during earthquake (con't)
Time Position Applicants Actions or Behavior (AR PK05-16, Pzr Press Hi/Lo, con't)
ALL * (2.1.3 --> 2.1.7) Checks controller output, channel checks press channels, and checks pressure < 2175 psig (it is not), and eventually goes to section 2.3 for low pressure SRO * (2.3.1) Determines pressure is still low, and goes to OP AP-13, Malfunction of the Reactor Pressure Control System (OP AP-13, Malfunction of the Reactor Pressure Control System)
SRO Implements OP AP-13, Malfunction of the Reactor Pressure Control System ATC * (1) Stops power change in progress (already done) (ie, no more rod pulls)
BOP * (2) Verifies all Pzr PORVs closed (they are) (VB2, vertical, far right)
BOP * (3) Verifies all Pzr Safeties closed (via tailpipe and sonic flows) (VB2, vertical, far right) (they are closed)
ATC * (4) Notes one spray valve open (PCV-455B), and cannot be closed (CC2)
Note: (once the RWST Tech Spec has been addressed, per lead examiner cue, increase the failure of PCV-455B to full open (crew will return to AP-13, step 4a RNO).
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 5 Page 10 of 19 Event
Description:
Pzr Spray Valve (PCV-455B) fails open during earthquake (con't)
Time Position Applicants Actions or Behavior (OP AP-13, Malfunction of the Reactor Pressure Control System, con't)
ALL Crew diagnoses that pressure is dropping, and not recovering (trending towards trip setpoint) (VB2 meters, CC2 recorders, PPC, and/or PK05-16 alarms on 2nd low pressure alarm)
ALL * (4 RNO) Trips Reactor (ATC)
- (4 RNO) Goes to EOP E-0, Reactor Trip or Safety Injection (SRO (EOP E-0, Reactor Trip or Safety Injection)
ATC * (1) Verifies reactor trip (trip bkrs open (VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left))
ATC * (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)
BOP * (3) Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)
ATC/BOP * (4) Checks if SI actuated (PK08-21 OFF, also NO ESF status light coincidence requiring SI) (SI is not required at this time)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 5 Page 11 of 19 Event
Description:
Pzr Spray Valve (PCV-455B) fails open during earthquake (con't)
Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, con't)
BOP * (4 RNO) Determines that S/Gs levels are already in their normal range, but that AFW pps (motor-driven) are not running (not yet required); may start now or later in E-0.1 (VB3, skirt, lower center)
SRO * (4 RNO) Transitions to E-0.1, Reactor Trip Response, and performs a procedure transition brief Note: With RCPs 1-1 and 1-2 shut down, the trip response will be normal (at this point); the crew may perform a few steps from E-0.1, but the next event may be brought in as soon as E-0.1 performance is started.
(E-0.1, Reactor Trip Response)
ATC * (1) Checks RCS temperature stable at 547 F (it is) (CC1 recorder, VB2 meters, PPC)
ATC/BOP * (2a) Checks RCS Tave < 554 F (it is) (ATC)
- (2b) Verifies FWI (feedwater isolation), Red light ON, white lights OFF (they are) (VB1, vertical, upper left of center) (ATC)
- (2c) Starts MDAFPs (if not done earlier), and controls S/G levels in auto or manual (VB3, skirt, lower left, for controllers) (BOP)
Proceed to the next event once E-0.1 has been entered, per lead examiner (RCS leak and aftershock will start automatically, conditional on 5 min after shutting down the 1-2 RCP).
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 6 Page 12 of 19 Event
Description:
RCS leak initiates, requiring manual SI Time Position Applicants Actions or Behavior ALL RCS leak is diagnosed from the following (leak ramps up to 900 gpm slowly):
- Pzr level dropping (PPC, CC2 recorder, VB2 meters)
- Pzr level hi flow demand and/or low level deviation alarms (PK05-21)
- Containment parameters slowly rising (temp, press) (PPC, VB1 recorder, PAMS panels)
Note: The crew may take actions to try to keep up with the leak (referring to actions in OP AP-1, Excessive RCS Leakage, prior to initiating a manual SI per that procedure or the Foldout Page of E-0.1).
- May throttle up charging (opening FCV-128 and HCV-142, CC2) in manual to attempt to maintain Pzr Level (per OP AP-1 actions, and leak diagnostics)
- May start 2nd charging pump (CCP) (also AP-1 guidance) as level continues to drop (VB2, lower, center)
- May isolate letdown (closes 8149C and LCVs 459/460, VB2, skirt, left of center) as level continues to drop SRO/ATC
- Per AP-1 (or E-0.1 FOP), initiates a manual SI, and returns to EOP E-0 (EOP E-0, Reactor Trip or Safety Injection)
ALL Repeats first three steps (verifies reactor/turbine trips, and 4KV bus status)
ATC/BOP * (4) Checks if SI actuated (PK08-21 ON, also checks VB1 red train lights and/or train equipment to verify both trains actuated) (they are)
SRO * (5) Directs App E implemented (usually to BOP)
The next events (8801 failures, and increase to SBLOCA) are already proceeding (or have occurred already)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 DC-2012-11-DRAFT OPERATING TEST.docx Page 42 of 263 Rev 2
Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 7 Page 13 of 19 Event
Description:
High-Head ECCS Flow Path Failure (8801A/B); must open manually (CT)
Time Position Applicants Actions or Behavior (EOP E-0, Appendix E) (EOP E-0 body steps on next page)
BOP App E is implemented:
- (1a) Checks no personnel in Containment (part of turnover; may not voice)
- (1b) Announce trip/SI on PA system
- (2) Checks main generator - tripped (PK14-01 OFF, Manual Unit Trip required, output bkrs open, and exciter field bkr open, CC3 right side)
- (3 & 4) Verify Phase A and containment vent isolation complete (VB1, ESF status lights, red lights ON, white lights OFF)
- (5) Verify ESF (SI) actuation complete (ESF/SI red light ON, white lights OFF, EXCEPT for 8801A&B [VB2 skirt, far left], which must be opened manually to restore high-head ECCS) (Critical Task - WOG CT E-0-D, establish high head ECCS flow prior to exiting EOP E-0) **
- (6) Verifies Feedwater isolation complete (normal FWI portion is complete, with red light ON, and white lights OFF) (S/G portion: red light is ON, white lights OFF)
- (7 & 8) Checks containment spray, Phase B, and main steam isolation - NOT required (red lights are OFF for ESF for these on VB1, and white lights are OFF)
- (9) Checks AFW status (MDAFPs running, TDAFP may be running, VB3 center area); verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)
- (10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel)
- (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)
- (14) Checks secondary systems (MFPs tripped (VB2, green lights ON), only one CB Pp set running, condenser status (not avail))
- (15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)
- (16 - 21) Verifies DGs running normally (VB4, freq (60), volts (120), speed (900)); verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area); verifies MSRs reset (CC3 Triconex HMI);
throttles RCP seal injection flows to normal (FCV-128, to 8-13 gpm each, CC2);
checks PK11-04 NOT IN (SFP alarm); notifies Shift Foreman of completion Next event is already in progress...
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 8 Page 14 of 19 Event
Description:
SBLOCA Response; Loss of Emergency Coolant Recirc Actions are taken Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, con't)
Note: With the size of the RCS leak/SBLOCA, it is expected that the RWST will reach 33% level (the auto-stop point for the RHR pumps, as well as the required transition point for the cold leg recirc procedure, EOP E-1.3) in just a few minutes after entering EOP E-0. The crew may not complete the procedure prior to transition to EOP E-1.3 (or may get a step or two into EOP E-1, LOCA; this is non-consequential).
ATC * (6) Checks RCS temperature - stable (temps will be dropping due to SBLOCA/ECCS flows; AFW may be throttled back (VB2 meters, upper panel lower area)
ATC * (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open, which is failed mid-position with bkr tripped), and no elevated tailpipe temps or sonic flows on safeties/PORVs (VB2 - upper panel, far right); checks Pzr sprays closed (CC2)
SRO/ATC * (8) Checks RCP trip criteria - observes RCS pressure (may or may not be <
1300 psig; stops last two RCPs if < 1300 psig (VB1 and VB2)
ATC/BOP * (9) Checks for faulted S/Gs
- Faulted - checks all S/G pressures on VB3 (not uncontrolled drop or depressurized)
ATC/BOP * (10) Checks for faulted and ruptured S/Gs
- Ruptured - checks RE-71/72/73/74 and RE-15/19 recorders on VB2 (and PPC); (all normal), and PK11-06/17/18 (all OFF); may request samples (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 8 Page 15 of 19 Event
Description:
SBLOCA Response; Loss of Emergency Coolant Recirc Actions are taken Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, con't)
SRO/ALL * (11) Checks RCS intact (it is not) (note: only one valid abnormal reading needed to transition from E-0)
- (11a) Checks containment pressure normal (it is very elevated) (VB1 meters, PPC)
- (11b) Checks containment level normal (may already be elevated) (VB1 meters, PAMS)
- (11c) Checks containment radiation normal (elevated) (PK11-21 and PK11-19)
- (11 RNO) Places 2nd ASW/CCW HX in service (opens FCV-603 and FCV-431, VB1 far left), and transitions to EOP E-1, Loss of Reactor or Secondary Coolant ALL Crew notes RWST level at 33% in RWST (by VB2 meters, stopping of RHR pumps, and/or PK03-05 alarm)
SRO * (FOP) Transitions to EOP E-1.3, Transfer to Cold Leg Recirculation, per the E-0 or E-1 Foldout Page (FOP)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 8 Page 16 of 19 Event
Description:
SBLOCA Response; Loss of Emergency Coolant Recirculation Actions are taken Time Position Applicants Actions or Behavior (EOP E-1.3, Transfer to Cold Leg Recirculation)
Note: With very little RCS leakage reaching the containment sumps, and the RWST prematurely drained (due to leak), E-1.3 will only be performed for the initial alignment, and then the operators will transition to ECA-1.1 when the containment sumps are checked for adequate level for cold leg recirc transfer.
BOP * (1) App EE assigned/performed:
- (App EE, 1) All (6) series contactor switches are cut in (VB2, upper panel)
- (App EE, 2, 3) Resets SI and both trains of CI Phase A and Phase B (VB1, upper panel) (probably done earlier)
- (App EE, 4) Verifies two ASW/CCW HXs in service (already done, VB1, far left)
- (App EE, 9) Dispatches operators to rack in breakers for 8980 and 8976.
ATC * (2, 3) Verifies RHR Pp 1-2 stopped and closes 8700B (VB1, lower right)
ATC * (4, 5) Verifies RHR Pp 1-1 stopped and closes 8700A (VB1, lower right)
ATC * (6) Closes RHR crosstie valves 8716 A/B (VB1, lower center)
ATC * (7) Isolates ECCS Pp recirc paths by closing 8974 A/B, and closing 8105 / 8106 (VB2)
ATC * (8) Verifies recirc sump level > 92 ft (will be low or low off-scale SRO * (8 RNO) Transitions to EOP ECA-1.1, Loss of Emergency Coolant Recirculation Capability, and performs procedure transition brief.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 8 Page 17 of 19 Event
Description:
SBLOCA Response; Loss of Emergency Coolant Recirculation Actions are taken, including RWST makeup and ECCS reductions (CT) (con't)
Time Position Applicants Actions or Behavior (EOP ECA-1.1, Loss of Emergency Coolant Recirculation Capability)
SRO * (1) Determines recirc failure is caused by lack of RWST level (not by sump blockage)
SRO/ATC * (2a) Notes power available to both RHR pps (VB2, lower right) (ATC)
- (2b) Notes recirc sump level (VB2, vertical, right side) is still low (expected for these conditions); goes to step 3 (ATC/SRO)
ATC * (3) Resets both trains of SI (VB2) (should already be reset)
ATC * (4) Verifies fan coolers (CFCUs, VB1 vertical center area) in low speed (ie, yellow lights; they are)
ATC * (5) Checks RWST level (VB2, far upper left) < 4% ( 25-30% at this point)
ATC * (6) Determines Containment Spray Requirements (N/A, not running/activated)
(VB1 vertical left of center)
ATC * (7) Adds makeup to the RWST (here) and reduce ECCS (next pages)
(WOG CT ECA-1.1-B, must be completed prior to end of procedure)
(critical task): **
- Implements App M of procedure
- Reads notes prior to steps, and selects section A for makeup (makeup from SFP is preferred method)
- Directs field operators to perform the section A steps (all in field); may direct entire procedure section to field, as desired (since all performance is in the field, directing the performance satisfies the CT).
- Note: flow can be confirmed by RWST level rise and/or sim console flow monitoring (although is not required for CT or to end scenario)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 8 Page 18 of 19 Event
Description:
SBLOCA Response; Loss of Emergency Coolant Recirculation Actions are taken, including RWST makeup and ECCS reductions (CT) (con't)
Time Position Applicants Actions or Behavior (EOP ECA-1.1, Loss of Emergency Coolant Recirculation Capability, con't)
BOP * (8) Checks S/G levels, controls 20-65%, and shuts down TDAFP (levels already being controlled, TDAFP not running) (all on VB3)
ATC/BOP * (9) Checks normal (condenser) steam dump available (it may be); if not 10%
steam dumps (atmospheric) will be used for cooldown (CC2, VB3)
Note: There will be some cooldown from the SBLOCA (ECCS flow), but it should be well under 100°F of cooldown, so a cooldown should actually be started.
ATC/BOP * (10) Initiates coodown (< 100°F/hr) via condenser or normal steam dumps Cooldown is performed by:
- HC-507 (CC1) is place in manual and the demand is raised (to start cooldown)
- When P-12 permissive comes in (on PK08, which closes the steam dumps);
the steam dump interlock bypass switches are both taken to bypass, which enables the steam dumps again (probably have to do this to start C/D).
(CC2)
- (contingency) IF MSIVs are closed, the operators will cooldown by throttling open the 10% steam dumps (PCVs 19, 20, 21, & 22 on VB3 lower middle panel area).
- @ P-11 permissive (1915 psig, probably done at start), low steamline pressure SI is blocked (no consequence if already on 10% steam dumps)
(CC2)
ATC/BOP * (11) Checks ECCS is in service, and determines that CCPs and SI pumps are still delivering flow to the RCS (VB1 and VB2)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 2 Event No.: 8 Page 19 of 19 Event
Description:
SBLOCA Response; Loss of Emergency Coolant Recirculation Actions are taken, including RWST makeup and ECCS reductions (CT) (con't)
Time Position Applicants Actions or Behavior (EOP ECA-1.1, Loss of Emergency Coolant Recirculation Capability, con't)
ATC/BOP * (12) Establishes one train of SI flow (part of Critical Task) **:
- Determines that RHR PPs are not running; goes to next step (ATC/SRO)
ATC * (13) Verifies recirc sump isolation valves 8982A/B closed (they are) (VB1)
BOP/SRO * (14a) Checks RCPs stopped (should all be by now) (VB2)
- (14b) Checks RCS subcooling (will not be > 20°F); moves on to step 15 (VB2)
Note: The App G required minimum flow should be between 410-490 gpm, depending on how long the crew took to get here. The remaining CCP or the remaining SI pump will be probably not be capable of this flowrate (alone) at this point, so no pumps will be shut down per step 15 RNO. Only IF the remaining SI pump is up to the minimum flow (and the CCP is shut down), OR if either pump is shut down and minimum flow is not maintained, will this next step be critical (sim console operator should monitor time since trip and App G requirements to assist examiners in determining proper step actions (based on the actual crew sequence of actions, and timing).
ALL * (15) Checks RVLIS level (adequate) and subcooled margin (not adequate) to terminate ECCS, so goes to RNO to reduce ECCS
- (15B RNO) Determines App G minimum flow requirement, based on time since trip (see above; most likely, can't shut down a pump)
- (15B RNO) Determines that stopping either the last CCP or SI PP will go below that minimum (most likely), and does not stop any pumps The scenario may be terminated once step 15 has been completed (ie, minimum flow determined, and any actions needed are taken).
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ATTACHMENT 1 - SIMULATOR SETUP Run Init/Initialize /CCs and VBs/Run Drill 81 Any tags are placed/removed as necessary
- Caution tags on Generator Relay C/Os for backfeed (if needed)
The proper Delta-I curve on CC1 and Reactivity Handbook for the simulator INIT in place.
The Rod Step Counters indicate correctly.
Run Clear Recorders icon on lower left desktop to clear YOKOGAWA recorder memories.
Clear the PCS HMIs (NSR) by "flushing" the trend buffer; then, restart the "Window Viewer" app.
Boric Acid and Primary Water Target Blender set to values identified in Lesson Record PPC MAX on CC2 lamicoid.
Record Boron Concentration for desired simulator INIT on CC2 lamicoid.
Circuit breaker flags are correct on CC1 (Proportional Heaters), CC3, VB4, and VB5 Equipment status lamicoids are correct:
RHR Valves (8726A/B and 8734A/B) - CLOSED (OPEN if RHR in service)
H2 or N2 on VCT - H2 ( unless shut down training)
SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - CONT. RM. VENT TRAIN 1 BUS F SELECTED TO BUS 1H - CONT. RM. VENT TRAIN 1 BUS H B.A. XFER PP SUPPLYING BLENDER - BA PP 1-2 RADWASTE DISCH AND CHLORINATION - ASW 1-1 OFF NORMAL LAMICOIDS OR PINK MARKERS - Placed as needed or return to CC3 The Plant Abnormal Status Board is updated for Charging Pump Status, Boron Conc, PRA Risk Status and Work Week Matrix.
Copies of Procedures, Attachments; Appendixes; Foldout Pages; Annunciator Response Procedures and commonly used forms are in binders and NOT Marked up:
PPC Setup:
- PPC BIG Screen (set to TABULARLG1), select new list, private, Sim Large)
- RODCONFIG is updated (click Apply when completed)
SPDS (screens and time updating), A screen RM, B screen SPDS.
CC3 Annun. CRT big screen (if enabled then get alarm it needs reset - Tools, keyboard, Tools, password - which is "A", File Exit - Start over)
The chart recorders are operating properly. DDR10s and Turbine Vib Recorder are acknowledged and in AUTO. CC1 NR-45 on proper screen. PAMS RVLIS/TMS screens on Summary Page.
All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status, as needed.
Alarm A&E Viewer window is activated prior to run, and printer is placed ,ONLINE, if needed.
Triconex DEH/DFW alarms have been acknowledged/cleared.
Seismic drawer put back; check for any alarms on the Rad panels PC setup for SVC tailboard (G-3 ENF Reset, RCPs, U-1 Safety Monitor)
Verify paper in HPD2 and print a test page.
Verify Annunciator Horn is on (BELL ON) and Sound Effects are on (SOUND ON).
The video is turned off, audio and communication systems are set up and functioning Turn down plant PA on simulator floor (restore to original setting when scenario completed)
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TIMELINE AND BOOTH/CONSOLE OPERATOR ACTIONS Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Setup Simulator Load snap30 and IC_30 from 2% power, Mol, CB = 1575 , Integrators: BA - 00, per Checklist exam flash drive and PW - 00 INIT to IC-30
- Tags: none X Setup Drill 81 Reset normal engineering values X Setup PPC select Verify PPC Select alarms setup per PK06-20 & 25 X Setup Start TEAM data collection Collect data for scenario for NRC Exam Team X Once crew has DRILL 9204 in AUTO taken the watch Once NI power is ser 0232 act,1,0,0,c,fnispr.gt.3, Ground alarm (bus G) simulates 80000B ground;
> 3% .not.i521g46 short simulated by valve going partially closed (won't vlv pzr2 2,0.8,10,60,c, move); then, after several minutes, the bkr for fnispr.gt.3,0 80000B trips (ground alarm clears) dsc pzr2 act,0,0,360,c, fnispr.gt.3,0 15 min after xmt cvc16 3,50,120,900,c, TE-130 fails low (manual available on TCV-130);
8000B bkr trips .not.i521g46,0 causes letdown temp to rise and letdown divert (TCV-149) 15 min after TCV- mal sei1 act 0.21,180,900,c, 1st earthquake; causes hole in RWST, and Pzr spray 130 placed in xv2i158m,0 vlv PCV-455B to fail partially open (htrs will control) manual ramp asisrwst=1.54e6,900, 10,c,jmlsei1 cnv rcs2 2,0.2,10,0,c,jmlsei1,0 X One minute after Cue: (from security in 115' tank area behind Aux/FHB) A large industrial crane crew notes RWST (with a load attached) became unstable and tipped over during the level dropping earthquake, striking and coming to rest on U-1 RWST. A rip about 4' long and several inches wide occurred about 1/3 the way up from the bottom of the tank, which is currently draining to the 115' yard area. RP and maintenance have been called, and an action plan will be created to try to repair the breach. No injuries were reported.
X When CP M-4 Cue: (from Shift Manager) The U-2 SFM and WCSFM will handle CP M-4 actions.
entry discussed or made X Once RWST Tech cnv rcs2 2,1,100,0, Manual Entry: Fails PCV-455B full open (requires Spec is discussed d,xv2i261o reactor trip and tripping of RCPs 1-1 and 1-2 by crew (and per lead examiner tc xv2i261o, cnv rcs2 Clears when RCP 12 is stopped 2,0,10,0,d,0 X After reactor trip DRILL 32 in AUTO Nuclear Operator actions on a trip are performed announced (continued on next page)
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TIMELINE AND BOOTH/CONSOLE OPERATOR ACTIONS Timeline The following table shows the simulator computer operations and other instructions the examiners (con't) need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION 5 min after 1-2 bst aux1 1,0,0,300,c, Seismic aftershock causes RCS leak to develop RCP is stopped xv2i261o,0 (initially ramped up to 900 gpm to allow diag and tc jistbst1, mal sei1 act 0.27, action) (will increase after SI) 10,30,d,0 mal rcs3d act 0.9,600,360,c, xv2i261o,0 X After RWST level Cue: (from security in 115' tank area behind Aux/FHB) Water has stopped ramp has draining from the hole in the U1 RWST.
completed ~ 34%
X If requested DRILL 15 in AUTO Breaks cond vac, secures gland steam, etc (if requested)
On SI (RHR PP bst aux2 1,0,0,30,c,xv1o236r,0 Leak size increases to 2.5" SBLOCA (provide proper start) tc jistbst2, mal rcs3d act 2.5, actions and timing to RWST getting to 33%)
10,15,d,0 On SI vlv sis3 1,0,0,0,d,xv2i227o 8801 A&B don't auto-open, but can be manually vlv sis4 1,0,0,0,d,xv2i228o opened X When requested dsc rhr4 act,1 Closes breakers for 8980 (52-1f-31) & 8976 (52-1h-dsc sis14 act,1 20)
X When APP M DRILL 112 in AUTO Makes up to RWST from SFP (1-1 pp) (starts in 2 directed min)
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DRILL FILE TEXT
- L111 NRC Exam Scenario 02 (DRILL 9204)
- 9/9/12 glh
- ser ALM345B 0232 480V BUS-1G GRD #0232 ser 0232 act,1,0,0,c,fnispr.gt.3,.not.i521g46 #alm345b
- (8000B strokes partially closed, and then won't move)
- (bkr for 8000B trips about 5 minutes later)
- TE-130 fails low 15 minutes after 8000B bkr opens
- XMT CVC16 LTDN HX 1-1 OUT TEMP, T0145A, ALM0394, TI-13 #txmtte130 xmt cvc16 3,50,120,900,c,.not.i521g46,0 #txmtte130
- 1st earthquake, 15 min after TCV-130 placed in MAN
- mal SEI1 SEISMIC ACTIVITY mal sei1 act 0.21,10,900,c,xv2i158m,0
- PCV-455B fails 20% open on 1st earthquake
- CNV RCS2 PZR SPRAY VALVE #rrcp455b cnv rcs2 2,0.2,180,0,c,jmlsei1,0 #rrcp455b
- (will be failed full open once RWST Tech Spec addressed)
- close spray valve when RCP 12 tripped tc xv2i261o, cnv rcs2 2,0,10,0,d,0
- seismic aftershock 5 min after 1-2 RCP is S/D
- (sets up RCS leak)
- BST AUX10 INSTRUCTOR BISTABLE 10 #jistbst1 bst aux1 1,0,0,300,c,xv2i261o,0 #jistbst10 tc jistbst1, mal sei1 act 0.27,10,30,d,0
- mal RCS3D SMALL LOCA IN BOTTOM OF COLD LEG 4 mal rcs3d act 0.9,600,360,c,xv2i261o,0
- (conditional on RHR pp start) xv1o236r bst aux2 1,0,0,30,c,xv1o236r,0 #jistbst2 tc jistbst2, mal rcs3d act 2.5,10,0,d,0
- 8801 A/B won't open until manually opened
- VLV SIS4 COLD LOOP BORON INJ LINE VLV #rsi8801b vlv sis4 1,0,0,0,d,xv2i228o #rsi8801b DC-2012-11-DRAFT OPERATING TEST.docx Page 53 of 263 Rev 2
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 1 Days Operating Mode: 2 Gross Generation: 0 MWe Power Level: 2 % Net Generation: 0 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 307 SCF / 326 SCFD 5 day ave NEW EMERGENT WORK:
- none SHUTDOWN TECH SPECS / ECGS:
- none ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- none TURNOVER ITEMS:
- A reactor startup was completed early last shift. OP L-2 was closed out, and OP L-3 is now in progress, and steps are complete up to step 6.29 (raise power to 8%), and is attached.
- The main feedwater system is in service (in auto), controlling S/G levels; The AFW system is secured and lined up for automatic operation. Busses were recently transferred to Startup Power.
- Several hours ago, the main turbine rolled off the turning gear (on leakby), rolled up to about 200 rpm, and then slowly slowed down again. When all of the speed pickups (channels) were lost at about 50-75 rpm (expected, and by design), a turbine trip was generated. The turbine was relatched without incident, per OP C-3:II, and has been on the turning gear for the last couple of hours.
PRIORITY ITEMS FOR NEXT SHIFT:
- Raise power to 8%, startup and parallel the main generator, and raise power to 28%.
OPERABILITY ITEMS:
- The mode 2 to 1 checklist (OP L-0) is complete, and signed off DC-2012-11-DRAFT OPERATING TEST.docx Page 54 of 263 Rev 2
ANNUNCIATORS IN ALARM:
- all current alarms are consistent with current mode and power level (no unexpected alarms)
Shift Foreman Turnover TURNOVER ITEMS:
- U 2%, preparing to raise power to 8%, and roll the main turbine
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: _BOL_.
- Power History: Previously at 100% for 17 days. Currently power level is 2%, following a reactor trip a week ago (MFP trip; repairs have been completed, and other unscheduled outage work has been worked)
- Boron concentration is _1575 ppm_ from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 130 steps on CBD.
- Rod motion: being used to maintain current power level, and will be used for raising power to 8%
CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
- None OTHER ABNORMAL PLANT STATUS
- None DC-2012-11-DRAFT OPERATING TEST.docx Page 55 of 263 Rev 2
Appendix D (rev 9) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: 3 Op-Test No.: L111-NRC Examiners: Operators:
Initial Conditions: 100% power, MOL, 774 ppm boron Turnover: DG 1-2 OOS Event Malf Event Event No No. Type* Description 1 N/A N (BOP) Swap to CCP 1-1 from CCP 1-3 per OP B-1A:V, sec 6.1 2 xmt pzr24 I (SRO, Pzr Press transmitter PT-474 fails low (makes (2) PORVs inoperable) (TS)
BOP) 3 xmt cvc4 I (SRO, FT-128 (charging flow transmitter) fails low (actual charging flow goes high);
ATC) manual control of FCV-128 is required 4 mal mfw2b C (ALL) MFP 1-2 vibrations rise until ramp is required; the pump trips during the ramp ovr xc3i196o R (ATC) (at 93% power), which causes a faster programmed ramp ( 50% power after ramp) 5 mal eps4d C (SRO, Loss of 4KV Vital Bus G (diff trip); alternate equipment is placed in service, BOP) and Tech Specs are implemented (TS) 6 Ser 1244 C (ALL) RCP 1-3 vibration coincident with motor bearing temperature increase Xmt rcp38 (requires reactor trip and trip of RCP 1-3) 7 mal sei1 M (ALL) Earthquake causes loss of Loss of all AC Power; the unit is backfed from mal deg1a,c 500KV power (CT, TCOA), and RCS inventory control is established mal syd2 (TCOA). RCP seal injection is isolated prior to starting a CCP (CT, TCOA) 8 vlv afw7 C (BOP) TDAFP does not auto start on trip/loss of AC; must be manually started
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 15. Total malfunctions (5-8) 7
- 16. Malfunctions after EOP entry (1-2) 1
- 17. Abnormal events (2-4) 5
- 18. Major transients (1-2) 1
- 19. EOPs entered/requiring substantive actions (1-2) 1
- 20. EOP contingencies requiring substantive actions (0-2) 2
- 21. Critical tasks (2-3) 2 Rev 2 comments: dropped one event (scenario too long), adjusted timing; changed bus that trips; other minor changes following validations DC-2012-11-DRAFT OPERATING TEST.docx Page 56 of 263 Rev 3
Appendix D (rev 9) Scenario Event Description Form ES-D-2 SCENARIO
SUMMARY
- NRC #3
- 2. Pressurizer pressure channel PT-474 fails low. System control is not affected (control is 2nd highest chan select), but since this channel provides the low press interlock for two Pzr PORVs (PCV-474 and PCV-455C), they must be declared INOPERABLE (block valves must be closed, and power removed). OP AP-5 is used to respond to the failure. (TS)
- 3. FT-128 (charging flow) fails low, causing actual charging flow to rise. FCV-128 (or HC-459D) must be taken to manual, and charging flow controlled by alternate indications for the remainder of the scenario. OP AP-17, section B, may be used to respond to the failure.
- 4. MFP 1-2 develops vibrations (moderate level) requiring the plant be ramped to 50% power
@ 50-200 mw/min (per AR PK09-14). At 93% power, the 1-2 MFP will trip, initiating an even faster automatic programmed ramp down to 50% power. OP AP-25 and OP AP-15 will be used to respond to the ramp/trip.
- 5. Once the plant is stable at 50% power, 4KV bus G will trip on differential. OP AP-27 will be used to stabilize and respond to the loss of the bus, and restoration of equipment. (TS)
- 6. RCP 1-3 develops vibrations (Danger level) coincident with motor bearing temperature increase. The crew will respond by using AR PK05-05 and will trip the reactor and RCP 1-3 (stabilizing the plant in EOP E-0.1).
- 7. An earthquake will cause sequential electrical failures (loss of 230KV, DGs 1-1 & 1-3) which will result in a loss of all AC to the vital busses. Since backfeed (500KV) is available, the crew will backfeed the unit to restore power (CT, part of TCOA), and eventually restore RCS inventory control (part of TCOA), using EOP ECA-0.0 and ECA-0.1. The turbine driven AFW pump (TDAFP) does not auto-start from the trip of loss of busses, and must be started to restore AFW flow to the S/Gs. RCP seal cooling is isolated prior to restarting a CCP.
(CT, and part of TCOA). The TCOA is to backfeed the unit, isolate RCP seal cooling, and restore inventory control within 54 minutes (of loss of all AC). ***
The scenario is terminated once the unit is backfed, vital buss(es) are restored, and RCS inventory control is restored.
- (TCOA) The loss of all AC was evaluated against TCOA #37 (station blackout); the conditions of the scenario are close enough to the TCOA conditions that both the TCOA and time limits are applicable: must complete 500KV backfeed, RCP seal isolation (just direction w/I 42 min), and restore RCS inventory control within 54 minutes (of loss of power).
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 1 Page 01 of 28 Event
Description:
CCP swap per OP B-1A:V, sec 6.1 (normal evolution)
Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.
SRO Implements OP B-1A:V, section 6.1, Transferring from a CCP to another CCP (OP B-1A:V, CVCS - Transfer Charging Pumps)
Note: The SRO or one of the board operators may be tasked with reading the procedure steps.
SRO Reads NOTE prior to step 6.1.1, which does not apply in this mode.
BOP * (6.1.1) Directs radiation protection to verify survey/posting guidelines implemented (Complete per Turnover instructions)
ATC * (6.1.2) Place FCV-128 in manual.
Note: Starting CCP 1-1 will place Auxiliary Building Ventilation in Buildings and Safeguards mode of operation.
BOP * (6.1.3, 6.1.4, 6.1.5, 6.1.6) Start CCP 1-1, verify proper amps, secure CCP 1-3, verify acceptable flow on pump CCP 1-1.
ATC * (6.1.7, 6.1.8) Using HCV-142 and FCV-128 adjust PZR level to program band, adjust seal flow to 8-13 gpm.
ATC * (6.1.9) When PZR level is at reference, place FCV-128 in auto.
BOP * (6.1.10) Place Auxiliary Building Ventilation to BLDG ONLY mode. (N/A since CCP 1-3 is NOT the on-coming pump)
BOP * (6.1.11) Update the Abnormal Status Board for shutdown charging pump, CCP 1-3, boron concentration, date, and time Proceed to the next event once CCP 1-1 in service, CCP 1-3 shutdown, and PZR level control in AUTO, and per the lead examiner.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 2 Page 02 of 28 Event
Description:
Pzr Pressure Channel PT-474 Fails Low (TS)
Time Position Applicants Actions or Behavior Note: When this press channel fails low, no controls will be affected (2nd highest signal select will kick out the channel from control input). This channel (PT-474) is the interlock (blocking) channel for Pzr PORVs PCV-474 and PCV-455C (will no longer lift in AUTO).
ATC/BOP Observes one or more of the following indications:
- PT-474 (VB2 upper right side, PPC picture Pzr) failing low
- PK05-16 (input on low press) Pressurizer Pressure Low
- PK04-06 (two inputs on low press) Protection Channel Activated
- PK02-04 Safeguard Channel Activated
- PK04-04 OTT C-3 Channel Activated
- PK06-21 PCS Trouble Note: The PK05-16 response may be used, in addition to OP AP-5. Both are detailed in the case both are used.
SRO (ONLY IF USED) Implements AR PK05-16, Pressurizer Pressure Low (only if used) (AR PK05-16, Press Hi/Lo) (otherwise, this section is N/A)
ATC * (2.1.1) Verifies reactor did not trip (it didn't)
BOP * (2.1.2) Verifies Pzr PORVs closed (they are) (VB2, upper panel, right)
ATC * (2.1.2) Verifies Pzr Sprays closed (they are) (CC2, controllers and green lights ON, above them)
ATC * (2.1.2) Verifies Pzr Htrs - ON, if needed (they are not affected by this failure)
(CC1, left)
ATC * (2.1.3) Checks RCS pressure above 2175 psig (it is) (Tech Spec concern) (VB2 upper right side, PPC picture Pzr)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 2 Page 03 of 28 Event
Description:
Pzr Pressure Channel PT-474 Fails Low (TS) (con't)
Time Position Applicants Actions or Behavior (AR PK05-16, Press Hi/Lo, con't)
ATC * (2.1.4) Verifies HC-455K Pzr Press controller @ 78.8% (it is; not affected)
(CC2)
BOP * (2.1.5) Performs channel check of Pzr Pressure channels; notes PT-474 does NOT channel check (failed low), if not already noted/diagnosed (VB2 upper right)
SRO Reads NOTE prior to step 2.1.6 SRO/ATC * (2.1.6.a) Notes HC-455K is in AUTO and controlling normally (CC2) (ATC)
- (2.1.6.b) N/A (SRO)
- (2.1.6.c) Directed to go to OP AP-5 SRO Implements OP AP-5, Malf of Eagle-21 Protection or Control Channel (OP AP-5, Malfunction of Eagle-21 Protection or Control Channel)
SRO/ATC * (1) Notes that Pzr pressure is controlling properly in Auto (chan failure does not affect normal control) (CC2, VB2 meters)
BOP * (2) Determines that the failure is not Eagle-21 related (PK06-01 and PK06-03 are OFF)
SRO/ATC * (3) Determines that T channel has not failed (Pzr press chan); ensures T channel not selected to Loop 14 (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 DC-2012-11-DRAFT OPERATING TEST.docx Page 61 of 263 Rev 3
Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 2 Page 04 of 28 Event
Description:
Pzr Pressure Channel PT-474 Fails Low (TS) (con't)
Time Position Applicants Actions or Behavior (OP AP-5, Malfunction of Eagle-21 Protection or Control Channel, con't)
BOP * (4) Verifies steam dumps are not actuated (no armed or open, unless not reset from ramp just completed - VB3, center)
SRO * (5) Notifies I&C of the PT-474 failure, as time permits SRO Reads CAUTION prior to step 6 SRO/BOP * (6, 7) Notes step 6 requirements to take channel OOS prior to working; Places OOS stickers on failed channel indications (VB2 PT-474 meter, uses Att 4.1 and 4.2)
SRO * (8) Determines Tech Spec actions using Att 4.1:
- 3.3.2.D Low press SI (72 hrs)
- 3.3.1.E High press trip (72 hrs)
- 3.3.1.E OTT trip (72 hrs)
- 3.3.1.M Low press trip (72 hrs)
- 3.4.11.B PCV-474 & 455C low press intlk (1 hr to close block valve 8000A and 8000B, and remove pwr from both, 72 hrs to repair for PCV-455C only)
SRO/BOP * (8) Closes Pzr block valves 8000A and 8000B w/I 1 hr (for PCV-474 and PCV-455C) (VB2, vertical lower right) (BOP)
- (8) Directs that power be removed from block valves 8000A and 8000B (SRO/BOP)
Proceed to the next event once the Tech Specs have been determined, and the 1 hr actions above have been done, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 3 Page 05 of 28 Event
Description:
Charging Flow Transmitter FT-128 fails low (charging goes high)
Time Position Applicants Actions or Behavior ALL Diagnoses charging flow problem from one or more of the following:
- RCP seal flows indicate high and rising (due to controller perceived need for more flow) (VB2 meters, PPC)
- Pzr level rising slowly (due to rising charging flow) (VB2 meters, PPC, CC2 recorder)
- Diagnostic brief may be held (gather above data and conclude that indicated flow has failed low)
Note: The corrective action for this failure may be taken without procedure use, or OP AP-17, section B, may also be referenced (only has general, obvious guidance).
ATC Takes manual control of charging (using charging controller FCV-128), and lowers charging flow to normal (uses alternate indications to control flow (ie, RCP seal flows, VCT level, Pzr level, etc) (CC2, PPC)
(if used, OP AP-17, Loss of Charging, Sec B; otherwise, mark N/A)
SRO (if used) Implements OP AP-17, Loss of Charging, Section B SRO * (1) Stops unit load changes (N/A)
BOP/ATC * (2) Checks letdown flow normal (it is) (VB2 meter, PPC)
ALL * (3a) Determines that charging amps are rising, charging flow (indicated) is at zero, and charging pressure has also risen (determines that RNO actions are N/A, since charging pump is stable) (VB2 meters, CC2 meters, PPC)
- (3b) Determines that VCT level is lowering slowly (due to rising charging flow)
(CC2, PPC)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 3 Page 06 of 28 Event
Description:
Charging Flow Transmitter FT-128 fails low (charging goes high) (con't)
Time Position Applicants Actions or Behavior (OP AP-17, Loss of Charging, Sec B, con't)
ATC/BOP * (4a) Determines that Pzr level is stable/rising (rising slowly) (VB2 meters, CC2 recorder, PPC)
- (4b) Determines that RCP seal flows are high (contradicts indicated charging flow); ATC may or may not adjust FCV-128 or HCV-142 at this time to return charging flow and seal flows to normal. (CC2)
ATC/ALL * (5a) Determines that charging flow is NOT responding properly to Pzr level changes (unless manual control already taken) (ie, flow high with level high, with indicated flow low) (CC2, VB2, PPC); goes to step 5d.
ATC * (5d) Determines charging control not responding normally due to flow indicator failure; takes manual control of charging (HC-459D or FCV-128), and returns charging flow to normal (or below normal, to return level to setpoint) (CC2)
SRO * (6, 7) Notifies maintenance of failed transmitter, and operates with Pzr level in manual Proceed to the next event once charging is in manual with flow restored to normal, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 4 Page 07 of 28 Event
Description:
MFP 1-2 High Vibrations, requiring plant ramp Time Position Applicants Actions or Behavior ATC/BOP The alarm PK09-14, MFP 1-2, is noted as unexpected and reported to the Shift Foreman; the high vibration input is reported SRO Implements AR PK09-14, MFP 1-2 (high vibrations)
(AR PK09-14, MFP 1-2) (high vibrations)
SRO * (1) Input table refers crew to section 2.2 BOP * (2.2.1.a) Evaluates vibration readings from 1-2 MFP (turbine/MFP HMI on VB4, lower left); notes multiple probes with rising vibration readings SRO * (2.2.2) Notes that the 1-2 MFP is not the only MFP in operation, and is directed to go to OP AP-25, Rapid Load Reduction, and ramp the unit to 550 MWe at 50-200 mw/min, and then trip that MFP SRO Implements OP AP-25, Rapid Load Reduction (OP AP-25, Rapid Load Reduction)
SRO Enters OP AP-25, Rapid Load Reduction
- (1a) Determines runback/programmed ramp is not in progress (may not vocalize, since this ramp is initiated by the crew)
- Ramp is started (guidance is also on lamicoid pegboard on CC3):
- (1c) 550 MWe load target is entered into Triconex HMI
- (1d) Sets ramp rate to 50-200 mw/min
- (1e) Pushes GO (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 4 Page 08 of 28 Event
Description:
MFP 1-2 High Vibrations, requiring plant ramp (con't)
Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction, con't)
SRO/BOP (OP O-3) May make calls to chemistry if/when 15%/hr shut down rate is exceeded ATC * (2) Verifies that control rods are inserting properly in AUTO (VB2, intermittent green IN light)
ATC * (3, 4) Verifies ON all pressurizer backup heaters (CC1, left), and verifies CCP (1-3) running (VB2),
ATC * (5) Verifies charging flow adequate to prevent letdown flashing: may take manual control of Pzr level (already in manual from prior event) to prevent flashing of letdown (under these conditions, approx 60 gpm charging flow is required to keep letdown properly cooled)
- Places HC-459D (master level controller) or FCV-128 (charging flow controller) in manual (CC2, right side, for both)
- Keeps charging high enough (approx 60-65 gpm, as minimum) to prevent letdown from flashing (VB2, upper panel, letdown temperature, is monitored)
BOP * (6) Verifies DFWCS in AUTO and controlling S/G levels (CC3 MFW HMI, VB3, PPC)
- Checks MFW control and bypass valves in AUTO
- Checks both MFPs and their controller in AUTO
- May check level trends, as well as steam flow/feed flow trends (CC3, PPC, and/or big VB3 DFWCS electronic recorders)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 4 Page 09 of 28 Event
Description:
MFP 1-2 High Vibrations, requiring plant ramp (con't)
Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction, con't)
ATC * (7) RCS is borated per reactivity handbook for approx 50% load reduction (the following guidance is on the boration checklist in the reactivity handbook)
- Presses STOP on M/U Ctrlr HMI (CC2)
- Presses BORATE on HMI
- Sets target gallons for boration (as decided above, and per the Shift Foreman); verifies batch is reset
- Sets boric acid flowrate
- Presses START, and monitors boration
- Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman SRO
- The Shift Foreman provides reactivity oversight for the ramp BOP * (8) Checks secondary system status:
- (8b) Verifies 3rd Condensate/booster Pp set running (VB3, lower, center; all pumps will be running)
ATC * (9) Verifies proper operation of steam dumps, Tave trending to Tref (VB3, red/green indicator lights; Tave/Tref from CC1 recorder/PPC)
Note: Once the MFP 1-2 trips, the crew will go to OP AP-15; note that the actions in AP-15 and AP-25 are very similar, and often repeat each other; some of those overlapping actions are also repeated here, so that the examiner can follow along in one procedure until the actual transition occurs to the other.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 4 Page 10 of 28 Event
Description:
MFP 1-2 High Vibrations, requiring plant ramp (con't)
Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction) (cont)
ATC * (10) Checks pressurizer pressure and level trending to program (actual will be close to program, but may be in manual control) (CC2, PPC)
Note: At approx 93% power, the 1-2 MFP will trip (causing a faster programmed ramp to occur),
and OP AP-15, Loss of Feedwater Flow, will be implemented; OP AP-15 action duplicate most AP-25 actions, and the crew will probably stabilize the plant from that point using OP AP-15.
SRO Implements OP AP-15, Loss of Feedwater Flow, Section A (OP AP-15, Loss of Feedwater Flow, Section A)
ATC/BOP * (1) Determines if power is still > 80% (ATC)
- (1 RNO) Starts both MDAFPs (VB3 lower center) (if still > 80%) (BOP)
BOP * (2, 5) Verifies programmed ramp is in progress (Triconex HMI on CC3; 225 mw/min down to 650 MWe, then 25 mw/min to 550 MWe)
BOP * (3) Verifies that MFP suction pressure is > 260 psig (it is) (VB3 meter, PPC)
ATC * (4) Verifies that control rods are inserting properly in AUTO (VB2, intermittent green IN light)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 4 Page 11 of 28 Event
Description:
MFP 1-2 High Vibrations, requiring plant ramp (con't)
Time Position Applicants Actions or Behavior (OP AP-15, Loss of Feedwater Flow, Section A, con't)
ATC * (6) Verifies charging flow adequate to prevent letdown flashing: may take manual control of Pzr level (already in manual from prior event) to prevent flashing of letdown (under these conditions, approx 60 gpm charging flow is required to keep letdown properly cooled)
- Places HC-459D (master level controller) or FCV-128 (charging flow controller) in manual (CC2, right side, for both)
- Keeps charging high enough (approx 60-65 gpm, as minimum) to prevent letdown from flashing (VB2, upper panel, letdown temperature, is monitored)
BOP * (7, 11) Verifies DFWCS in AUTO and controlling S/G levels (CC3 MFW HMI, VB3, PPC)
- Checks MFW control and bypass valves in AUTO
- Checks both MFPs and their controller in AUTO
- May check level trends, as well as steam flow/feed flow trends (CC3, PPC, and/or big VB3 DFWCS electronic recorders)
ATC * (8) RCS is borated per reactivity handbook for approx 50% load reduction (the following guidance is on the boration checklist in the reactivity handbook)
- Presses STOP on M/U Ctrlr HMI (CC2)
- Presses BORATE on HMI
- Sets target gallons for boration (as decided above, and per the Shift Foreman); verifies batch is reset
- Sets boric acid flowrate
- Presses START, and monitors boration
- Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman ATC * (9) Verifies proper operation of steam dumps, Tave trending to Tref (VB3, center)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 4 Page 12 of 28 Event
Description:
MFP 1-2 High Vibrations, requiring plant ramp (con't)
Time Position Applicants Actions or Behavior (OP AP-15, Loss of Feedwater Flow, Section A, con't)
ATC * (10) Checks pressurizer pressure and level trending to program (actual will be close to program, but may be in manual control) (CC2, PPC)
Note: It is not expected that all of the OP AP-15 actions be performed, but additional actions are included (below), depending on how much of the event is evaluated, per the lead examiner.
ALL * (12) Stabilizes the plant once ramp completed (as time permits, these are later AP-25 actions)
- Tave within 1.5 F of Tref
- Axial flux difference (AFD) in target band (or borating to get it there); rods >
RIL
- S/Gs are trending towards program level (CC3, VB3, PPC) (they will be stable and close to program level of 65%)
- MFP D/Ps are on program (DFWCS HMI on CC3) (D/P will be very close to program, and stable)
- Pzr pressure and level stable, in normal bands (CC2, PPC)
- Returns turbine to standby status
- Sets valve position limit (VPL) to 1-2% above current value (same controller)
- May perform reactivity brief SRO/BOP * (13a, 13b) Resets steam dumps (to normal control)
- Checks steam dumps closed (they are, CC3 middle status light panel), and UI-500 (demand signal; next to status lights) @ 0%)
- Resets C-7A/7B (C-7A may be in) (CC2, right)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 4 Page 13 of 28 Event
Description:
MFP 1-2 High Vibrations, requiring plant ramp (con't)
Time Position Applicants Actions or Behavior (OP AP-15, Loss of Feedwater Flow, Section A, con't; optional)
SRO/BOP * (14) Stabilizes secondary:
- Secures MDAFPs
- Places hotwell reject valve HC-3 controller in manual and closed (VB3, lower, right)
- Places FCV-31 (part of cold gas temp control scheme) in manual and full open (VB3, lower right; note that this valve/controller is reverse acting, in that 0% on controller is full open demand)
- Adjusts TCV-23 and FCV-31 to attain acceptable steam jet air ejector (SJAE) flows and cold gas temps, and then returns controllers to auto, and monitors (all VB3, lower right)
The next event may be implemented once the plant is stable @ 50% power, at least one boration has been completed, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 5 Page 14 of 28 Event
Description:
Loss of 4KV Vital Bus G (differential trip) (TS)
Time Position Applicants Actions or Behavior ALL Diagnoses loss of 4KV Bus G from one or more of the following:
- Numerous equipment alarms associated with the loss of 4KV Bus G equipment
- PK17-02/04/09 DG-1-2 (bus G) alarms
- PK17-16 and PK17-17 4KV Bus G alarms (both related to loss of bus)
- Blue light on 4KV Bus G (diff) (VB4)
- White lights out on 4KV and 480 vac Bus G (VB4)
BOP Diagnoses differential trip on Bus G due to alarms (above), blue light on Bus G, and loss of power available white light on Bus G.
SRO (ONLY IF USED) Implements AR PK17-17, 4KV Bus G Fdr UV (note that OP AP-27 may be entered directly, or from one of the following ARPs)
(only if used) (AR PK17-17, 4KV Bus G Fdr UV) (otherwise, this section is N/A)
SRO/ATC * (1) Determines section 2.1 applicable from input of alarm SRO/BOP * (2.1) Determines Bus G is not energized, and transitions to OP AP-27, Loss of Vital 4KV and/or 480 vac Bus SRO (ONLY IF USED) Implements AR PK17-16, 4KV Bus G Diff Lockout (only if used) (AR PK17-16, 4KV Bus G Diff Lockout) (otherwise, this section is N/A)
SRO * (1) Determines that section 2.1 is applicable, from alarm input(s)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 5 Page 15 of 28 Event
Description:
Loss of 4KV Vital Bus G (differential trip) (TS) (con't)
Time Position Applicants Actions or Behavior (AR PK17-16, 4KV Bus G Diff Lockout, con't)
SRO/BOP * (2.1.1) Verifies the Aux, DG, and S/U feeder breakers open to Bus G
- (2.1.1) Opens 480 vac Bus G breaker 52-HH-5 (VB4, below 4KV Bus G mimic)
SRO * (2.1.2) Determines Bus G is not energized, and transitions to OP AP-27, Loss of Vital 4KV and/or 480 vac Bus (OP AP-27, Loss of Vital 4KV and/or 480vac Bus)
BOP * (1) Checks vital 4KV busses energized (only Bus G OFF; other white bus lights checked ON) (VB4, lower)
ATC * (2) Checks DRPI energized (on) (VB2, upper left)
BOP * (3) Confirms 4KV Bus G is tripped on diff OC (VB4, blue light on bus)
SRO * (4) Notifies maintenance of bus fault ATC/BOP * (5) Checks alternate pumps running on 4KV busses (ASW, CCW, CCP); CCW PP 1-3 may need to be started BOP * (6) Checks 480 vac vital busses - only bus 1G de-energized (VB4 - white pwr light for each 480 vac bus)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 5 Page 16 of 28 Event
Description:
Loss of 4KV Vital Bus G (differential trip) (TS) (con't)
Time Position Applicants Actions or Behavior (OP AP-27, Loss of Vital 4KV and/or 480vac Bus, con't)
BOP * (Att 4.2) Implements Attachment 4.2 for bus 1G:
- (Att 4.2, 1) Places PCV-455C Pzr PORV in CLOSE position (due to 8000B loss of power) (VB2, upper panel, far right), and refers the Shift Foreman to TS 3.4.11 (TS 3.4.11.C (1 hr)
- (Att 4.2, 1c/d & 2 Verifies other equipment not aligned to bus 1G (ie, on backup; none are), and redundant equip running
- (Att 4.2, 1.e.2) Sends Aux bldg watch to align BATP 11 to blender)
- (Att 4.2, 1.e.6) Verifies 3 CFCUs in service (places 1 stby CFCU in service, starts in low speed, then transfers to high speed by pressing the start button, swapping the speed select to fast, and then pressing the stop and start buttons)
- (Att 4.2, 1.e,f) Verifies other minor equipment status (as time permits)
- Battery charger 1-21 placed on the 1-2 battery (2 hr TS)
- Transfer of AC Panel PY-16 to backup power
- Verify DG fuel transfer pump 02 not on backup power
- C/R vent pwr panel EPCB2 not on backup SRO * (Att 4.2, 2a) Does assessment on DG loads either prior to adding loads, or after (SFM judgment)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 5 Page 17 of 28 Event
Description:
Loss of 4KV Vital Bus G (differential trip) (TS) (con't)
Time Position Applicants Actions or Behavior (OP AP-27, Loss of Vital 4KV and/or 480vac Bus, con't)
SRO * (7) Evaluates Tech Specs and ECGs (longer specs as time permits, per lead examiner):
- TS 3.4.11.C - PORV block valve (1 hr)
- TS 3.8.1.B - AC Sources - operating (STP I-1C w/I 1 hr, continues to be in effect)
- TS 3.8.4.A - DC Sources - operating (restore batt charger) (2 hrs)
- NOTE: may not have time to look up all (longer time limit) Tech Specs prior to next event
- TS 3.6.3.A & C - Cont isolation valves (4 hrs, 72 hrs)
- TS 3.8.9.A - Distribution system (vital bus) - operating (8 hrs to restore)
- TS 3.7.3.A - MFIVs, MFRVs & bypasses, etc (72 hrs)
- TS 3.8.7 - Inverters (only a trouble alarm at this point, so none INOPERABLE)
- ECG 23.6.A - Vital 480 vac swgr class 1 ventilation (30 days)
SRO/BOP * (8) Check unloaded DGs (N/A)
SRO * (9) Checks OPERABILITY of ESF equipment (pumps, valves lost due to Bus G loss)
Proceed to the next event once the Tech Spec actions above have been addressed, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 6 Page 18 of 28 Event
Description:
RCP 1-3 Vibration with motor bearing temperature increase Time Position Applicants Actions or Behavior Note: RCP 1-3 vibration coincident with motor bearing temperature increase per AR PK05-05 step 2.1.2 requires reactor trip and RCP 1-3 trip.
ALL Diagnosis is made of RCP 1-3 vibration and motor bearing temperature increase using one or more of the following:
(PPC picture and various group displays)
- PK05-05 RCP Vibration
- Vibration Monitoring Operations Console (simulated: Desktop PC behind Sim control console)
SRO Implements AR PK05-05, RCP Vibration SRO * (1) Will select section 2.1 based on input BOP * (2.1.1) Determines RCP 1-3 is in alarm using the Vibration Monitoring Operations Console (Desktop PC behind Sim control console)
Cue: When Desktop PC is checked for RCP vibration, (from Shift Manager) report Danger level vibration on RCP 1-3 Motor Shaft X axis on Vibration Monitoring Operations Console.
ATC/BOP * (2.1.2) Monitors RCP parameters Seal Flows (no change), Seal Temperatures (no change), Motor Bearing temperatures (rising) (PPC picture RCP, other PPC displays, and VB2 meters). After a short time, operator should report rising motor bearing temperatures as significant change coincident with vibration.
ATC/BOP * (2.1.3) Once step 2.1.2 parameter changes (motor bearing temperature increase) are reported, SRO directs reactor trip and RCP 1-3 trip after immediate actions, and E-0 entered.
Note: The rest of AR PK05-05 is not listed here. It is expected that the operators report motor bearing temperatures significantly changing, prompting a reactor trip and RCP 1-3 trip.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 6 Page 19 of 28 Event
Description:
RCP 1-3 Vibration with motor bearing temperature increase (con't)
Time Position Applicants Actions or Behavior ATC * (2.1.3) Initiates reactor trip (CC1, or VB2)
BOP/ATC * (2.1.3) Trips RCP 1-3 (may do this following EOP E-0 immediate actions)
SRO Implements EOP E-0, Reactor Trip or Safety Injection (EOP E-0, Reactor Trip or Safety Injection)
ATC * (1) Verifies reactor trip (trip bkrs open(VB2 upper left), rods on bottom (VB2 upper left DRPI panel), Nis decreasing (CC1 left))
ATC * (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)
BOP * (3) Checks vital 4kv busses (VB4, vital busses F/H have white lights on mimic busses)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 6 Page 20 of 28 Event
Description:
RCP 1-3 Vibration with motor bearing temperature increase (con't)
Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, con't)
ATC/BOP * (4) Checks if SI actuated (PK08-21 OFF, also checks SSPS ESF status lights on VB1 and PK02-02 to verify SI is NOT required)
ATC/BOP * (4 RNO) Checks AFW status (VB3, AFW Pp 1-2 & 1-3 may be running, but S/Gs will likely still be on scale), and exits E-0 for E-0.1 (If AFW running, may throttle AFW LCVs on VB3 lower left to limit RCS cooldown; note that AFW will not be running if S/G levels adequate, but may choose to start them NOTE: Motor Driven AFW pumps may still be running from AP-15 ALL
- Transitions to EOP E-0.1, Reactor Trip Response, and performs procedure transition brief (EOP E-0.1, Reactor Trip Response)
Note: EOP E-0.1 actions will be performed until the loss of all AC occurs (a couple of minutes; there is no requirement to perform any particular E-0.1 actions prior to the transition to ECA-0.0)
ATC/BOP * (1) Checks Tave stable or trending towards Tref (if should be); no actions expected here other than continued throttling of AFW flow may be done (AFW LCVs on VB3 lower left), to control RCS temperature (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 6 Page 21 of 28 Event
Description:
RCP 1-3 Vibration with motor bearing temperature increase (con't)
Time Position Applicants Actions or Behavior (EOP E-0.1, Reactor Trip Response, con't)
ATC/BOP * (2) Checks Feedwater Isolation (FWI) complete
- Checks Tave < 554°F (expected, or soon will be)
- Checks FWI MLB (monitor light box) (VB1, upper center), RED light ON, WHITE lights OFF (they are, if actuated; this actuation will occur when <
554°F) (note: temperature will fluctuate a bit due to stopping the RCPs earlier)
- Checks AFW flow > 435 gpm (the flow will be adequate, and/or S/G levels will still be on-scale) (VB3)
ATC * (3) Checks all control rods - fully inserted (they are) (VB2 upper left, for DRPI panel)
ATC/BOP * (4) Checks Pzr and level control
- Checks Pzr level > 17% (it is) (VB2 meter, CC2 recorder, PPC)
- Checks charging and letdown in service (they both are) (CC2 and VB2 CVCS mimic)
- Checks Pzr level trending to 22%; operates FCV-128 and HCV-142 (CC2) to control Pzr level 22% - 60% (RNO)
- Operates Pzr heaters as needed (auto/manual) to maintain normal pressure (normal auto operation expected at this point, with pressure returning to normal or normal already)
The next event may be implemented once EOP E-0.1 is in progress and the RCPs have been secured, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 7 Page 22 of 28 Event
Description:
Earthquake and Loss of ALL AC Time Position Applicants Actions or Behavior Note: The Loss of ALL AC develops when a loss of Startup Power (230KV) occurs; Bus G is de-energized due to the differential trip, the 1-2 DG is cleared, and the 1-1 and 1-3 DGs trip during their start. 500KV is available, so backfeed will be accomplished using App DD early in the procedure.
ALL Diagnosis of the Loss of AC is made using one or more of the following:
- Many alarms occur, mostly associated with the earthquake or equipment power problems
- All of the vital and non-vital bus white power available lights are out (VB4 and VB5, lower panel, near each mimic bus)
- The S/U Pwr available light (right end of VB5) is out
SRO Implements ECA-0.0, Loss of All Vital AC Power Cue: (from Shift Manager) The U-2 Shift Foreman will take CP M-4 actions.
(ECA-0.0, Loss of All Vital AC Power)
ATC * (1) Verifies reactor trip (trip bkrs open (VB2 upper left), NIs decreasing (CC1 left))
ATC * (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)
ATC * (3) Performs RCS isolation steps
- (3a) Verifies letdown isolated 8149 A/B/C close OR LCV-459/460 closed (all 8149s will be closed due to the loss of AC (to CCPs) (VB2 lower left) (ATC)
- (3c) Verifies excess letdown isolated (8166/8167, VB2 lower far right) (they are both closed) (ATC)
- (3d) Verifies NSSS sample valves closed (VB1 lower left) (some are still open, and must be taken to close position) (ATC)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 7&8 Page 23 of 28 Event
Description:
Loss of ALL AC, con't; TDAFP auto-start failure Time Position Applicants Actions or Behavior (ECA-0.0, Loss of All Vital AC Power, con't)
- AFW flow > 435 gpm (VB3 upper center meters, SPDS) (the TDAFP does not start in auto, but will start from VB3); starts TDAFP Note: The TDAFP is available, but the valves no longer have power (usually open); once the TDAFP is started, then local operators may be stationed to control the TDAFP LCVs (and AFW flow) until 4KV bus G is restored.
SRO/BOP * (5a, and RNO) Starts any DG from the Control Room (VB4, upper panel); there is no action to do here, since Bus G has an diff trip, and busses F & H, DG 1-3 &
1-1 have a S/D relay trip; the Shift Foreman (SFM) may authorize an attempted reset of the relay and DG starts (wont be successful)
SRO May request maintenance and/or operators to investigate/make available any or all of the DGs at this point SRO/BOP * (5b) Checks any vital bus energized (theyre not, VB4 white lights light on busses); there is currently no power to manually close in to these busses SRO/ATC * (5c) Observes that no vital busses are energized (VB4 white bus lights out);
may use the sync key in one of the generator output bkrs (CC3 far right) to check for voltage, or by asking the Shift Manager or switchyard, it is determined that 500KV will be available in 5-10 minutes.
SRO * (5c RNO) Directs App DD implementation to backfeed, while the rest of crew continues with ECA-0.0 body Cue (when status checked): 500KV power will be available in about 5-10 minutes.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 7 Page 24 of 28 Event
Description:
Loss of ALL AC, con't; energize vital bus (CT)
Time Position Applicants Actions or Behavior (ECA-0.0, Loss of All Vital AC Power, con't)
BOP * (App DD) Implements App DD (steps vital to critical task of energizing bus are bolded)
- (App DD, 1) Checks 500KV power available by putting sync key in PCB-532 and/or PCB-632 (CC3 far right) (may have already been done above and given report that 500KV would be available shortly; not needed if crew already received report of backfeed power available from switchyard)
- (App DD, 2) Verifies generator exciter field bkr open (it is) (may take it to pull-to-lock position)
- (App DD, 4) Cuts out generator protective relays for backfeed clearance (all toggles on VB4 upper panel with blue lamicoids)
- (App DD, 5) Verifies generator output breakers trip reset blue light off (VB4 upper left near gen trip lockout relays) (blue light is off)
- (App DD, 6) Resets unit trip lockout relays (VB4 upper left) (reset is vertical position on handles, not slanted)
- (App DD, 7) Closes generator output breakers, PCB-532 and PCB-632 (CC3) (inserts sync key, turns to ON, closes bkr, turns off sync key, and removes for each breaker) (only one breaker required for CT)
- (App DD, 8) Cuts out vital bus auto transfer relays (toggle switch adjacent to each bus on VB4, each taken to cutout position) (only one of bus F or G required for CT)
- (App DD, 9) Resets auto transfer relays for vital busses (PBs next to cutout switches on VB4); makes blue lights go out (any actions on Bus G are not relevant at this point, since the bus cannot be energized) (only one of bus F or H required for CT)
- (App DD, 10) Verifies personnel clear of vital bus swgr (phone); may also check status of installation of interlocks on vital 4KV loads prior to energizing busses (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 7 Page 25 of 28 Event
Description:
Loss of ALL AC, con't; energize vital bus, and isolate RCP seals/cooling (CTs & TCOA)
Time Position Applicants Actions or Behavior (ECA-0.0, Loss of All Vital AC Power) (cont)
BOP * (App DD) Implements App DD (cont)
- (App DD, 11) Verifies S/U and DG feeder breakers for each vital bus are open (VB4, lower, above each bus mimic); opens any startup breakers that are still closed
- (App DD, 12) Closes Aux Feeder breakers for busses F and H (inserts sync key, turns to ON, closes bkr, turns off sync key, and removes for each breaker) (VB4, lower; left side feeder breaker on each bus) (only one of bus F or H required for CT)
- (App DD) (WOG CT E-0-C, energize at least one vital bus prior to exiting ECA-0.0) (steps in bold above required for CT) (Critical Task)
(also, part of non-timed TCOA) **
- (App DD, 13) (as time permits, not expected) Reviews backfeed procedure OP J-2:V for additional actions and clearance actions Note: The actions below (body of procedure) will continue as the BOP is aligning backfeed to the vital busses (above).
ATC * (6) Checks any vital bus energized (will not be at this point, before the appendix is completed)
SRO/ATC * (7) Directs actions to isolate RCP seal cooling (all field actions); directing local actions in step 7 is a Critical Task (WOG CT ECA-0.0-H, isolate RCP seals prior to starting a CCP, in ECA-0.1 or ECA-0.2) (Critical Task) (also, part of non-timed TCOA) **
SRO/ATC * (8) Controls S/G levels by local/manual control, as needed (assigns operators in field and has them throttle TDAFP LCVs as needed to maintain 20-65% level)
(VB3 meters, PPC)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 7 Page 26 of 28 Event
Description:
Loss of ALL AC, con't; energize vital bus, and isolate RCP seals/cooling Time Position Applicants Actions or Behavior (ECA-0.0, Loss of All Vital AC Power) (cont)
SRO/ATC * (9) Installs interlocks (to prevent Pp starts) for all ESF pumps (ASW, CCW, CCP, SI, RHR, AFW) (may not do Bus G at this time, since it cannot be energized) (VB1, VB2, VB3, lower sections) (interlock physically fits over start switches and locks them in stop position)
ATC * (9) Places all ASW and CCW stby selector switches in MANUAL (VB1, upper left)
SRO/ATC * (9) Directs field operators to rack out breaker on CFCUs (may not do Bus G at this time)
- (9) Places CFCU speed selector switches in slow speed (VB1, upper center)
Note: A few more ECA-0.0 body actions may be completed before a vital bus is energized, but only the RCP seal isolation and interlock installations above are required before leaving the procedure.
SRO * (6) Per step 6, when at least one vital bus is energized, goes to step 27 of the procedure BOP * (27) Checks S/Gs pressures stable (they are) (VB3)
SRO/BOP * (28) Aligns battery chargers from available 480 vac busses (Bus G is OOS, so the crew may direct aligning battery charger 1-21 to the 1-2 battery) (all field actions) (only IF not done earlier during OP AP-27 actions)
Note: It is expected that the crew will find conditions that allow exit to EOP ECA-0.1 (no SI),
however, exit to either ECA-0.1 or ECA-0.2 is allowable and will complete the scenario objectives.
ALL * (29) Checks SI initiation criteria, and determines recovery procedure (most likely ECA-0.1)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 7 Page 27 of 28 Event
Description:
Loss of ALL AC; energize vital bus; restore inventory control (con't)
Time Position Applicants Actions or Behavior SRO (29) Implements ECA-0.1, Loss of All AC without SI Required (ECA-0.1, Loss of All Vital AC Power without SI Required)
Note: If ECA-0.2 is used, essentially the same actions are performed, but in addition ECCS pumps and CFCUs are considered for starts as well. That procedure is not detailed here.
- Reads CAUTIONs and NOTE prior to step 1 SRO/BOP * (1) Verifies RCP seal isolation step (from ECA-0.0) completed (all field actions; should already have received phone call from field) (done) (note: this is part of the critical task of isolating RCP cooling PRIOR to starting a CCP)
BOP * (2) Check Containment Isolation Phase A NOT Actuated (probably won't be -
resets if it is actuated)
Note: All of the following substeps establish minimum loading of equipment on to the available vital busses (F & H), the goal being to re-establish RCS inventory control.
ATC/BOP * (3a, 3b) Checks instrument air available (FCV-584 is on VB4, lower left); if isolated, the valve is opened, and header pressure checked (above it)
Note: FCV-584 wont open if instrument air pressure is too low Cue: If AP-9 implemented, (from Shift Manager) U-2 SFM will implement AP-9.
ATC * (3c, 3d, 3e) Prepares ASW/CCW pumps for starts
- Resets vital bus auto-transfers (bus F & H) (pushbuttons, making the blue lights go out, VB4, adjacent to each bus mimic) (may have been done earlier in App DD)
- Verifies ASW and CCW pps all in MANUAL (may already have been done)
(VB1, far left, vertical panel)
ATC * (3f) Removes interlock(s), and starts at least one ASW pump (VB1, far left, vertical)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: 3 Event No.: 7 Page 28 of 28 Event
Description:
Loss of ALL AC; energize vital bus; restore inventory control (CT) (con't)
Time Position Applicants Actions or Behavior (ECA-0.1, Loss of All Vital AC Power without SI Required, con't)
ATC * (3g) Verifies RCS isolation (from ECA-0.0 step; already complete), removes interlock(s), and starts one CCW pump (VB1 just to right of ASW pumps)
ATC * (3h1, 3h2) Notes no CCP is currently running, and that only CCP 1-1 is available
- (3h4) Verifies charging injection valves closed (either closed, or can be closed)
(VB2, far left, lower)
- (3h5) Sets HCV-142 (seal backpressure) to 20% open (CC2)
- (3h6) Opens 8105/8105 (CCP recircs) (probably already open) (VB2, lower, center)
- (3h7, 3h8, 3h9, 3h10) (all VB2 left, lower) Verifies normal charging valve 8146 open (it is), aux spray vlvs 8145/8148 closed (they are), and charging hdr isolations 8107 and 8108 open (open, or can be opened)
- (3h11) Removes interlock(s), and starts CCP 1-1 (Critical Task: RCP seal isolation [direction] must have been completed prior to this point); also, establishes RCS inventory control (part of TCOA to establish within 54 min)) **
- (3h12) Throttles open FCV-128 to establish charging flow The scenario may be terminated once power is establish to a vital bus, RCP seal isolation has been directed, and a CCP has been started (RCS inventory control), per the lead examiner.
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ATTACHMENT 1 - SIMULATOR SETUP Run Init/Initialize /CCs and VBs/Run Drill 81 Any tags are placed/removed as necessary
- CBCs on 1-2 DG start/stop, auto/manual, and output breaker The proper Delta-I curve on CC1 and Reactivity Handbook for the simulator INIT in place.
The Rod Step Counters indicate correctly.
Run Clear Recorders icon on lower left desktop to clear YOKOGAWA recorder memories.
Clear the PCS HMIs (NSR) by "flushing" the trend buffer; then, restart the "Window Viewer" app.
Boric Acid and Primary Water Target Blender set to values identified in Lesson Record PPC MAX on CC2 lamicoid.
Record Boron Concentration for desired simulator INIT on CC2 lamicoid.
Circuit breaker flags are correct on CC1 (Proportional Heaters), CC3, VB4, and VB5 Equipment status lamicoids are correct:
RHR Valves (8726A/B and 8734A/B) - CLOSED (OPEN if RHR in service)
H2 or N2 on VCT - H2 ( unless shut down training)
SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - CONT. RM. VENT TRAIN 1 BUS F SELECTED TO BUS 1H - CONT. RM. VENT TRAIN 1 BUS H B.A. XFER PP SUPPLYING BLENDER - BA PP 1-2 RADWASTE DISCH AND CHLORINATION - ASW 1-1 OFF NORMAL LAMICOIDS OR PINK MARKERS - Placed as needed or return to CC3 The Plant Abnormal Status Board is updated for Charging Pump Status, Boron Conc, PRA Risk Status and Work Week Matrix.
Copies of Procedures, Attachments; Appendixes; Foldout Pages; Annunciator Response Procedures and commonly used forms are in binders and NOT Marked up:
PPC Setup:
- PPC BIG Screen (set to TABULARLG1), select new list, private, Sim Large)
- RODCONFIG is updated (click Apply when completed)
SPDS (screens and time updating), A screen RM, B screen SPDS.
CC3 Annun. CRT big screen (if enabled then get alarm it needs reset - Tools, keyboard, Tools, password - which is "A", File Exit - Start over)
The chart recorders are operating properly. DDR10s and Turbine Vib Recorder are acknowledged and in AUTO. CC1 NR-45 on proper screen. PAMS RVLIS/TMS screens on Summary Page.
All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status, as needed.
Alarm A&E Viewer window is activated prior to run, and printer is placed ,ONLINE, if needed.
Triconex DEH/DFW alarms have been acknowledged/cleared.
Seismic drawer put back; check for any alarms on the Rad panels PC setup for SVC tailboard (G-3 ENF Reset, RCPs, U-1 Safety Monitor)
Verify paper in HPD2 and print a test page.
Verify Annunciator Horn is on (BELL ON) and Sound Effects are on (SOUND ON).
The video, audio, and communication systems are turned off Turn down plant PA on simulator floor (restore to original setting when scenario completed)
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TIMELINE AND BOOTH/CONSOLE OPERATOR ACTIONS Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Setup Simulator INIT 510 100% power, MOL, CB = 774 , Integrators: BA - 00, per Checklist and PW - 20
- Tags: DG 1-2 CBCs X Setup Drill 81 Reset normal engineering values X Setup Start TEAM data collection Collect data for scenario for NRC Exam Team X Setup DRILL 35 in AUTO Clears DG 1-2 for maintenance X Once crew has DRILL 9205 in AUTO Scenario malfunctions are inputted once the crew taken the watch takes the watch X Note: The first event is the crew swapping CCPs per OP B-1A:V section 6.1 X When Aux Board Cue: There are no releases in progress on either unit.
called 15 min after CCP xmt pzr24 2,0,0,900,c, PT-474 fails low (no control effect, but makes two 1-1 started XV2O264R,0 PORVs inoperable, due to loss of interlock channel; PCVs, PCV-474 and PCV-455C)
X When requested dsc pzr1 act,0 Opens breakers for 8000A & 8000B dsc pzr2 act,0 15 min after xmt cvc4 3,0,5,900,c, FT-128 fails low (charging flow goes high); manual 8000A closed xv2i195c,0 control is available, and taken to control flow 45 min after FCV- mal mfw2b act 8,600,2700,c, MFP 1-2 vibs increase to 8 mils, requiring fast 128 taken to MAN xc2i016m,0 ramp to 50%. MFP 1-2 will trip @ 93%, causing ovr xv3i196o act,1,0,0,c, even faster programmed ramp.
fnispr.lt.93,0 15 min after < 575 mal eps4d act 2,0,900,c, Loss of 4KV Vital Bus G (diff trip)
MW on turbine smss.lt.575,0 X Once bus trip Cue: There is an acrid smell in the 4KV bus G room, but no smoke or fire.
investigated X When Requested DRILL 12 in AUTO Opens breaker for 8000B to open breaker for 8000B X When Requested, DRILL 47 in AUTO Transfers 1-2 battery to 121 charger.
to transfer 1-2 bat to 121 charger (continued on next page)
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TIMELINE AND BOOTH/CONSOLE OPERATOR ACTIONS Timeline The following table shows the simulator computer operations and other instructions the examiners (con't) need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X When Requested DRILL 97 in AUTO Transfers PY-16 to back power to transfer PY-16 to backup 30 min after loss ser 1244 act,1,0,1800, RCP 13 high vibration and increasing motor bearing of bus G c,.not.jeps1g,0 temperature xmt rcp38 3,322,200,1800, c,.not.jeps1g,0 #txmtrlrb(3) 10 min after 1-3 mal sei1 act 0.35,10,600,c, Seismic event triggers loss of ALL AC (loss of S/U, RCP is shut down xv2i262o,0 DG 1-1 & 1-3 fails, bus G is already dead, and mal deg1a act 2,0,0,c,jmlsei1,0 DG 1-2 is cleared) (backfeed is available) mal deg1c act 2,0,0,c,jmlsei1,0 MAL SYD1 act 2,5,0, c,jmlsei1,0 When TDAFP vlv afw7 1,0,0,0,d,xv3i219o TDAFP won't start in AUTO; will start from VB3 start needed X After reactor trip DRILL 32 in AUTO Nuclear Operator actions on a reactor trip X One minute after Cue: (from Shift Manager) The U-2 Shift Foreman and I will handle CP M-4 earthquake actions.
X Once backfeed Cue: 500 KV power will be available from Gates in 5 -10 minutes. 230 KV power status checked has relayed out, and there are no estimates for its return.
X When Requested DRILL 24 in AUTO (or MAN) Isolates RCP seal cooling, FCV-357, etc (don't forget as needed) return phone call, as this is part of TCOA)
X Once Drill 24 Cue: Notify C/R that RCP seals have been isolated per ECA-0.0 (use whatever actions complete wording they gave you on the direction to perform the step)
X When Requested DRILL 23 in MAN - ONLY Racks out breakers for CFCUs (if requested) (only do CFCU breakers in the file)
X When requested DRILLS 161-170 in AUTO Use these drills to throttle AFW as directed to throttle AFW locally X Once Bus G is DRILL 171 in AUTO IMPORTANT: Releases GCFs on TDAFP LCVs so restored valves will work again from the control room.
X To restore 500KV Mal syd1 clr Clears malfunction and restores power from Gates power Loa syd11 act,1,0,0,d,0 substation.
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DRILL FILE TEXT
- L111 NRC Exam Scenario 03 (DRILL 9205)
- 10/4/12 glh
- PT-474 fails low (PCV-455c & pcv-474 INOP)
- (15 min after CCP 1-1 started)
- XMT PZR24 PZR PRESS #pxmtpzr(4) xmt pzr24 2,0,0,900,c,XV2O264R,0 #pxmtpzr(4)
- FT-128 fails low (chrg fails high; manual works) 15 min after 8000A closed
- XMT CVC4 CHARGING FLOW, P0128A, FI-128B, SPDS, FI-128 #wxmtf128 xmt cvc4 3,0,5,900,c,xv2i195c,0 #wxmtf128
- MFP 1-2 vibrations (need AP-25 ramp to 50%) (45 min after FCV-128 to MAN)
- mal MFW2B MAIN FEEDWATER PUMP 1-2 VIBR ALARM AND TRIP mal mfw2b act 8,600,2700,c,xc2i016m,0
- MFP 1-2 trips @ 93% power
- ovr VB3143D FEED PP 12 TRIP XV3I196O #xv3i196 ovr xv3i196o act,1,0,0,c,fnispr.lt.93,0 #vb3143d
- 4kv bus G diff trip 15 min after 50% reached (smss.lt.575)
- mal EPS4d 4KV BUS D FEEDER BREAKER TRIP mal eps4d act 2,0,900,c,smss.lt.575,0
- RCP 13 high vibration & motor brg temp increase
- VLV CCW6 2,0,10,1800,c,.not.jeps1g,0 #rccf749 not used ser 1244 act,1,0,1800,c,.not.jeps1g,0 xmt rcp38 3,322,200,1800,c,.not.jeps1g,0 #txmtrlrb(3)
- seismic event (triggers rest) 10 min after 1-3 rcp is S/D
- mal SEI1 SEISMIC ACTIVITY mal sei1 act 0.35,10,600,c,xv2i262o,0
- (backfeed is available)
- mal DEG1a DIESEL GENERATOR 11 FAILURE mal deg1a act 2,0,0,c,jmlsei1,0
- mal DEG1C DIESEL GENERATOR 13 FAILURE mal deg1c act 2,0,0,c,jmlsei1,0
- mal SYD1 LOSS OF offsite POWER MAL SYD1 act 2,5,0,c,jmlsei1,0
- TDAFP doesn't start is AUTO (starts when 95 taken to OPEN)
- VLV AFW7 AFW TURB 11 STM SUPPLY HDR #rmsf095 vlv afw7 1,0,0,0,d,xv3i219o #rmsf095 DC-2012-11-DRAFT OPERATING TEST.docx Page 90 of 263 Rev 3
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 203 Days Operating Mode: 1 Gross Generation: 1190 MWe Power Level: 100 % Net Generation: 1147 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 309 SCF / 327 SCFD 5 day ave NEW EMERGENT WORK:
- none SHUTDOWN TECH SPECS / ECGS:
- TS 3.8.1.B DG 1-2 OOS for corrective maintenance on fuel racks (discovered during normal surveillance run two nights ago); RTS estimate is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; last partial STP I-1C completed 30 minutes ago (due in 7.5 hrs); action 3.8.1.B.3.1 has been completed.
ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- none TURNOVER ITEMS:
- Maintain 100% power
- Swap from CCP 1-3 to CCP 1-1 first thing your shift per OP B-1A:V, section 6.1 (procedure attached) to support a routine surveillance next shift.
PRIORITY ITEMS FOR NEXT SHIFT:
- See turnover items OPERABILITY ITEMS:
- TS 3.8.1.B DG 1-2 OOS - 2 days into 14 day action DC-2012-11-DRAFT OPERATING TEST.docx Page 91 of 263 Rev 3
ANNUNCIATORS IN ALARM:
Shift Foreman Turnover TURNOVER ITEMS:
- U maintain 100% - no one in containment
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: _MOL_.
- Power History: Steady State, previously at 100% for 73 days. Currently power at 100%
- Boron concentration is _774 ppm_ from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 231 steps on CBD.
- Diluting the RCS approximately 20 gallons every 1.5 hrs.
- The last dilution/boration was completed _15_ min ago.
- Rod motion: none planned, as needed to maintain I on target CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
OTHER ABNORMAL PLANT STATUS
- None DC-2012-11-DRAFT OPERATING TEST.docx Page 92 of 263 Rev 3
Appendix D (rev 9) Scenario Outline Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No.: S Op-Test No.: L111-NRC Examiners: Operators:
Initial Conditions: 100%, MOL, 774 ppm boron Turnover: CCP 1-3 OOS, DG 1-2 OOS Event Malf Event Event No No. Type* Description 1 dsc rod1 C (SRO, The normal DRPI power supply fails; rods are placed in manual until the ATC) power supply is transferred to backup (TS) 2 N/A C (ALL) The GCC orders a load shed of 350 MWe in the next 10 minutes; the crew R (ATC) uses OP AP-25 to ramp the unit down to comply ( 35 mw/min) 3 xmt rcs93 C (SRO, Loop 3 Tc fails high (slowly), causing rods to move in; rods should be taken ATC) to manual; the rods may be placed back in auto once the failed channel has been "kicked out" by the PCS. (TS) 4 cnv mfw4 C (SRO, FCV-520 fails closed (slowly) in auto; manual control is taken and S/G 1-2 BOP) level is controlled manually 5 mal rsc3a M (ALL) A SBLOCA (with failure of all CCPs and SI Pps, and TDAFP won't start) pmp cvc1/2 leads to Inadequate Core Cooling (ICC); S/Gs are eventually depressurized pmp sis1/2 to inject low head ECCS (RHR) (CT) mal syd2 6 mal ppl3a/b C (ATC) Auto SI fails on the SBLOCA; a manual SI is performed. (CT) 7 mal ppl1b C (BOP) Train B Phase A fails to actuate on the SI; manual alignment is performed.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes
- 22. Total malfunctions (5-8) 7
- 23. Malfunctions after EOP entry (1-2) 2
- 24. Abnormal events (2-4) 4
- 25. Major transients (1-2) 1
- 26. EOPs entered/requiring substantive actions (1-2) 1
- 27. EOP contingencies requiring substantive actions (0-2) 1
- 28. Critical tasks (2-3) 2 Rev 2 comments: updates based on validations (including remove one event due to length of scenario), updated summary; adjusted timing DC-2012-11-DRAFT OPERATING TEST.docx Page 93 of 263 Rev 2
Appendix D (rev 9) Scenario Event Description Form ES-D-2 SCENARIO
SUMMARY
- NRC #Spare
- 1. The normal power supply to DRPI trips open. The crew will take actions to place DRPI on backup, and place control rods in manual during this period. (TS)
- 2. The Grid Coordination Center (GCC) orders the unit to drop 350 mw of load in the next 10 minutes (due to grid imbalance from a line trip); the crew will ramp the unit down using OP AP-25, Rapid Load Reduction, at about 35 mw/min, and then stabilize the unit.
- 3. One of the loop 3 Tc transmitters will fail high (slowly); this slow failure will cause rods to initially move in (based on the failure, uses auct high Tave) before the PCS system kicks out that channel (based on excessive deviation). Control rods should be placed in manual. If the rods are not in manual before the failing channel is automatically removed from control, then the control rods will drive out to compensate for the previous movement. Actions will be taken per OP AP-5, Malfunction of an Eagle-21 Protection or Control Channel. (TS)
- 4. Main Feedwater Reg Valve (MFWRV) FCV-520 fails closed (slowly); manual control is available, and is taken to return feedflow and S/G 1-2 level back to program.
- 5. A SBLOCA (5") occurs, rapidly causing the need for a safety injection. All ECCS CCPs and SI Pps will fail on OC (common mode relay failures), leaving no high or medium head ECCS; eventually, core conditions will degrade to an Inadequate Core Cooling (ICC) condition, where the S/Gs will be depressurized in order to inject ECCS flow from the RHR system (CT).
- 7. Phase A containment isolation, train B, also fails, and equipment must be repositioned manually.
The scenario is terminated once the RCS is successfully depressurized and low-head (RHR) ECCS is injecting into the RCS.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 1 Page 01 of 21 Event
Description:
Normal Power to DRPI Fails (transferred to backup)
Time Position Applicants Actions or Behavior Note: Procedure step numbers are included at the front of each action/comment in parenthesis, where applicable.
ALL DRPI power loss is diagnosed from one or more of the following:
- DRPI Panel is "dark", with no rod position lights (VB2, left, black DRPI panel)
- PK03-21 alarms on two inputs SRO Implements AR PK03-21, "DRPI Failure / Rod Bottom" (AR PK03-21, DRPI Failure / Rod Bottom)
SRO * (1) Selects section 2.1 from "DRPI urgent failure" input ATC * (2.1.1) Takes manual control of rods by placing bank selector switch in MAN, and verifying normal manual speed on meter (45-51 spm) (CC1 right)
SRO * (2.1.4) Implements Tech Spec 3.1.7.B (immediate action to place rod control in manual)
Cue: (for next step) There are currently no loads on their backup source (from the OP O-13 attachment 1 table)
SRO/BOP * (2.1.5.a) Directs that DRPI be transferred to backup power (may send Nuclear Operator to normal breaker first to investigate) per OP A-3:I (all field actions, except below)
SRO * (2.1.5.a) May perform OP O-13 load assessment prior to (or after) transferring DRPI power) (use cue above; margin is available)
ATC * (2.1.5.b) Once DRPI is restored, Rod Control is returned to auto by placing the back selector in AUTO, and verifying 8 spm on the speed indicator (CC1, right)
Proceed to the next event once control rods are back in AUTO, and Tech Specs have been discussed, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 DC-2012-11-DRAFT OPERATING TEST.docx Page 96 of 263 Rev 2
Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 2 Page 02 of 21 Event
Description:
Unit Receives Backdown Order - Ramps Unit down 350 MW Time Position Applicants Actions or Behavior Cue: (from Shift Manager) I have just received a valid backdown order from the Grid Coordination Center (GCC). Per Ops Policy B-1, ramp unit 1 down 350 MW in the next 10 minutes.
SRO Implements OP AP-25, Rapid Load Reduction (OP AP-25, Rapid Load Reduction)
SRO Enters OP AP-25, Rapid Load Reduction
- (1a) Determines runback/programmed ramp is not in progress (may not vocalize, since this ramp is initiated by the crew)
- Ramp is started (guidance is also on lamicoid pegboard on CC3):
- (1c) 840 MWe (1190-350, approximate) load target is entered into Triconex HMI
- (1d) Sets ramp rate to 35 mw/min (approximate rate)
- (1e) Pushes GO SRO/BOP (OP O-3) May make calls to chemistry if/when 15%/hr shut down rate is exceeded ATC * (2) Verifies that control rods are inserting properly in AUTO (VB2, intermittent green IN light)
ATC * (3, 4) Verifies ON all pressurizer backup heaters (CC1, left), and verifies CCP (1-2) running (VB2),
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 2 Page 03 of 21 Event
Description:
Unit Receives Backdown Order - Ramps Unit down 350 MW (con't)
Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction, con't)
ATC * (5) Verifies charging flow adequate to prevent letdown flashing: may take manual control of Pzr level (now, or any time during ramp) to prevent flashing of letdown (under these conditions, approx 60 gpm charging flow is required to keep letdown properly cooled)
- Places HC-459D (master level controller) or FCV-128 (charging flow controller) in manual (CC2, right side, for both)
- Keeps charging high enough (approx 60-65 gpm, as minimum) to prevent letdown from flashing (VB2, upper panel, letdown temperature, is monitored)
BOP * (6) Verifies DFWCS in AUTO and controlling S/G levels (CC3 MFW HMI, VB3, PPC)
- Checks MFW control and bypass valves in AUTO
- Checks both MFPs and their controller in AUTO
- May check level trends, as well as steam flow/feed flow trends (CC3, PPC, and/or big VB3 DFWCS electronic recorders)
ATC * (7) RCS is borated per reactivity handbook for approx 30% (roughly) load reduction (the following guidance is on the boration checklist in the reactivity handbook)
- Presses STOP on M/U Ctrlr HMI (CC2)
- Presses BORATE on HMI
- Sets target gallons for boration (as decided above, and per the Shift Foreman); verifies batch is reset
- Sets boric acid flowrate
- Presses START, and monitors boration
- Once stopped, either returns to AUTO (presses AUTO, then START), or performs additional boration per the Shift Foreman (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 2 Page 04 of 21 Event
Description:
Unit Receives Backdown Order - Ramps Unit down 350 MW (con't)
Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction, con't)
- The Shift Foreman provides reactivity oversight for the ramp BOP * (8) Checks secondary system status:
- (8b) Verifies 3rd Condensate/booster Pp set running (VB3, lower, center; all pumps will be running)
ATC * (9) Verifies proper operation of steam dumps, Tave trending to Tref (VB3, red/green indicator lights; Tave/Tref from CC1 recorder/PPC)
ATC * (10) Checks pressurizer pressure and level trending to program (actual will be close to program, but may be in manual control) (CC2, PPC)
SRO * (11) Determines if it is desired to shut down the #2 Htr Drip Pp (it is currently running, and needs to continue running) (VB3, upper panel, center)
SRO * (12) Determine if the unit can remain on line; the Shift Foreman determines that the unit can remain at this power level (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 2 Page 05 of 21 Event
Description:
Unit Receives Backdown Order - Ramps Unit down 350 MW (con't)
Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction, con't)
ALL * (13) Stabilizes the plant once ramp completed (as time permits)
- Tave within 1.5 F of Tref (ATC)
- Axial flux difference (AFD) in target band (or borating to get it there); rods >
RIL (ATC)
- S/Gs are trending towards program level (CC3, VB3, PPC) (they will be stable and close to program level of 65%) (BOP)
- Returns turbine to standby status (BOP)
- Sets valve position limit (VPL) to 1-2% above current value (same controller)
- May perform reactivity brief (ALL)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 2 Page 06 of 21 Event
Description:
Unit Receives Backdown Order - Ramps Unit down 350 MW (con't)
Time Position Applicants Actions or Behavior (OP AP-25, Rapid Load Reduction, con't)
SRO/BOP * (14a, 14b) Resets steam dumps (to normal control) (as time permits)
- Checks steam dumps closed (they are, CC3 middle status light panel), and UI-500 (demand signal; next to status lights) @ 0%)
- Resets C-7A/7B (C-7A may be in) (CC2, right)
- (15) Stabilizes secondary:
- Places hotwell reject valve HC-3 controller in manual and closed (VB3, lower, right)
- Places FCV-31 (part of cold gas temp control scheme) in manual and full open (VB3, lower right; note that this valve/controller is reverse acting, in that 0% on controller is full open demand)
- Adjusts TCV-23 and FCV-31 to attain acceptable steam jet air ejector (SJAE) flows and cold gas temps, and then returns controllers to auto, and monitors (all VB3, lower right)
- (16) (as time permits) May verify all secondary controllers back in auto, and secure the third condensate booster pump (if running)
Proceed to the next event once power stabilized, and at least one boration completed, per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 3 Page 07 of 21 Event
Description:
Loop 3 Tcold Fails High (slowly)
Time Position Applicants Actions or Behavior Note: One of the loop 3 Tc transmitters will fail high (slowly); this slow failure will cause rods to initially move in (based on the failure) before the PCS system kicks out that channel on excessive deviation. Control rods should be placed in manual. If the rods are not in manual before the failing channel is automatically removed from control (by PCS), then the control rods will drive out to compensate for the previous movement.
ALL Diagnosis of the failed Tc channel (and/or unwarranted rod movement) is made using one or more of the following:
- Reactor and generator power are approx equal and not moving
- Tave and Tref were initially matched
- Loop 3 Tave, T, and other indications (CC1, VB2 meters) are diverging from the other loops)
- PK06-03 (RTD failure), PK06-04 (PPS Trouble), and other alarms related to failed channel Note: Pzr level control will also be momentarily affected by the Tc failure; level control will probably be in manual from the previous ramp, but if in AUTO, level control may be placed in manual during the transient.
ATC Control rods are placed in manual (may be done prior to OP AP-5 entry, or during its use) (CC1 bank selector switch)
SRO Implements OP AP-5, Malf of Eagle-21 Protection or Control Channel (OP AP-5, Malfunction of Eagle-21 Protection or Control Channel)
SRO/ATC * (1a, 1b) Notes that rod control (Tave) is NOT controlling properly in Auto (see above) and goes to step 1a, 1b RNO and takes MANUAL control of rods (CC1);
"may" take control of Pzr level (FCV-128 to MAN) if it is in auto at the time of the failure (CC2). SRO refers to Att. 4.2 now or later.
BOP/SRO * (2a) Determines that the failure is Eagle-21 related (PK06 ON), and goes to step 2a RNO)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 3 Page 08 of 21 Event
Description:
Loop 3 Tcold Fails High (slowly)
Time Position Applicants Actions or Behavior (OP AP-5, Malfunction of Eagle-21 Protection or Control Channel, con't)
ATC * (2a RNO) Determines which Protection Set is affected (from Ronan or Viewer/board indications); set III SRO * (2a RNO) Directs WCL (Work Control Lead)/watchstander to open all Prot Set III doors (racks 11,13) and monitor per Att 4.2 SRO * (2a RNO) Determines which instruments are in the affected racks (11 & 13) using Att 4.1 (would include loop 3 Tave, T, OPT and OTT setpoint on VB2/PPC)
SRO * (2a RNO) Determines affected bistables and fills out Bistable Trip Authorization Sheet (Att 4.4) (may do now or in later step)
- TC-431C Loop 3 OTT Trip
- TC-431G Loop 3 OPT Trip
- S/G TTD bistables (4) are an option, but not required (ie, either TTDs set to zero, or lo-lo bistables tripped)
SRO/ATC * (3) Verifies that Loop 3 T is NOT selected as a recorder input (on CC1)
BOP * (4) Verifies steam dumps are not actuated (no armed or open, unless not reset from ramp just completed - VB3, center)
SRO * (5) Notifies I&C of the Loop 3 Tcold failure, as time permits SRO Reads CAUTION prior to step 6 SRO/BOP * (6, 7) Notes step 6 requirements to take channel OOS prior to working; Places OOS stickers on failed channel indications (VB2 meters, uses Att 4.1 and 4.2)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 3 Page 09 of 21 Event
Description:
Loop 3 Tcold Fails High (slowly)
Time Position Applicants Actions or Behavior (OP AP-5, Malfunction of Eagle-21 Protection or Control Channel, con't)
SRO * (8) Determines Tech Spec actions using Att 4.1:
- 3.3.1.X, 3.3.2.M S/G TTD inputs (set to zero, or lo-lo bistables tripped, 72 hrs)
- 3.3.1.E, TC-431C, OTT trip (72 hrs)
- 3.3.1.E. TC-431G, OPT trip (72 hrs)
Proceed to the next event once Tech Specs have been addressed, and per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 4 Page 10 of 21 Event
Description:
MFW Reg Valve FCV-520 (1-2 S/G) Fails low Time Position Applicants Actions or Behavior Note: The valve will fail slowly closed (auto failure); as feedwater flow to the 1-2 S/G lowers, the bypass valve will open to try to maintain flow (will help, but not be enough); Manual control will work, and flow should be restored and the S/G 1-2 level controlled in manual.
ALL Diagnosis is made by using one or more of the following:
- PK09-15, Digital Feedwater System alarm
- Lowering flow (VB3 meters, DFWCS console (CC3), PPC) on 1-2 S/G
- FCV-520 actual valve position going down (DFWCS HMI on CC3)
- FCV-1520 throttling open to try to maintain flow (DFWCS HMI)
BOP FCV-520 is placed in manual, and flow / normal level is restored in the 1-2 S/G SRO May refer to TS 3.7.3, but valve is capable of closing (on FWI)
Proceed to the next event S/G 1-2 level is being controlled in MANUAL, and per the lead examiner.
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5&6 Page 11 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC); Auto SI fails (CT)
Time Position Applicants Actions or Behavior ALL RCS leak (SBLOCA) is diagnosed from the following (5" break):
- Pzr level dropping rapidly (PPC, CC2 recorder, VB2 meters)
- Pzr level hi flow demand and/or low level deviation alarms (PK05-21)
- Containment parameters rising rapidly (temp, press) (PPC, VB1 recorder, PAMS panels)
- PK02-02, Safety Injection Initiate, alarms (as well as other ESF related alarms)
ATC/ALL
- Manually initiates Safety Injection when it is noted that SI did not actuate (may be done before or during E-0) (Critical Task) (WOG CT E-0-XX, actuate SI prior to exit from E-0) **
SRO Implements EOP E-0, Reactor Trip or Safety Injection (EOP E-0, Reactor Trip or Safety Injection)
ATC * (1) Verifies reactor trip (trip bkrs open (VB2 upper left), rods on bottom (VB2 upper left DRPI panel), NIs decreasing (CC1 left))
ATC * (2) Verifies turbine trip (stop valves closed) (CC3 HMI or VB2 RPS indicator lamps)
BOP * (3) Checks vital 4kv busses (VB4, vital busses F/G/H have white lights on mimic busses)
ATC/BOP * (4) Checks if SI actuated (PK08-21 OFF, but ESF lights and PK02-02 require an SI) SI is actuated manually, if not already done above (CT) **
SRO * (5) Directs App E implemented (usually to BOP)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5&7 Page 12 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, con't)
BOP App E is implemented:
- (1a) Checks no personnel in Containment (part of turnover; may not voice)
- (1b) Announce trip/SI on PA system
- (2) Checks main generator - tripped (PK14-01 ON, output bkrs open, and exciter field bkr open, CC3 right side)
- (3 & 4) Verify Phase A and containment vent isolation complete (VB1, ESF status lights, red light ON (one), white lights - some ON); manually positions equipment as needed
- (5) Verify ESF (SI) actuation complete (ESF/SI red light ON, white lights - some ON); takes RNO actions after discovering that all SI Pps and CCPs have tripped on OC; may check lineups locally and breaker indications, as well as call maintenance) (pumps will not become available)
- (6) Verifies Feedwater isolation complete (normal FWI portion is complete, with red light ON, and white lights OFF) (S/G portion: red light is ON, white lights OFF)
- (7 & 8) Checks containment spray, Phase B, and main steam isolation - NOT required (red lights are OFF for ESF for these on VB1, and white lights are OFF)
- (9) Checks AFW status (MDAFPs running, TDAFP does not start (and cannot be started, VB3 center area); verifies either min of 435 gpm flow (VB3 center) or S/G level > 15% (VB3 center)
- (10) Verifies ECCS flows (charging injection (VB2 upper panel left), SI, RHR (both on VB1 upper panel); with no high/med head PPs, there is no flow
- (12 & 13) Checks excess letdown - not in service (8166/8167 closed); turns on aux bldg vent charcoal filter preheater (VB4 lower panel, left side)
- (14) Checks secondary systems (MFPs tripped (VB2, green lights ON), verifies only one CB Pp set running, condenser status (not avail))
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 13 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, con't)
BOP App E is con't:
- (15) Verifies proper operation of Aux Bldg and Control Rm vent systems (VB4 vent status light panel white lights); verifies containment iodine fans secured (VB4, lower panel)
- (16 - 21) Verifies DGs running normally (VB4, freq (60), volts (120), speed (900)); verifies vital batteries supplied by chargers (charger and bus volts on VB5, upper panel middle/lower area; notes DG 1-2 OOS); verifies MSRs reset (CC3 Triconex HMI); throttles RCP seal injection flows to normal (FCV-128, to 8-13 gpm each, CC2); checks PK11-04 NOT IN (SFP alarm); notifies Shift Foreman of completion ATC * (6) Checks RCS temperature - stable; AFW may be throttled back (VB2 meters, upper panel lower area)
ATC * (7) Checks Pzr PORVs and Pzr safeties (closed) / PORV block valves (all open), and no elevated tailpipe temps or sonic flows on safeties/PORVs (VB2 -
upper panel, far right); checks Pzr sprays closed (CC2) (tailpipe temps will be elevated, but consistent with containment temperatures from the SBLOCA)
SRO/ATC * (8) Checks RCP trip criteria - observes RCS pressure (< 1300 psig, but NO SI/CCPs running); does NOT stop RCPs) (VB1 and VB2)
Note: 230KV power (startup power) will be lost shortly after this decision is made (helps with ICC conditions timing), so RCPs will eventually be lost ATC/BOP * (9) Checks for faulted S/Gs
- Faulted - checks all S/G pressures on VB3 (not uncontrolled drop or depressurized)
ATC/BOP
- Notes that 230KV (startup) power has been lost (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 14 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior (EOP E-0, Reactor Trip or Safety Injection, con't)
ATC/BOP * (10) Checks for faulted and ruptured S/Gs
- Ruptured - checks RE-71/72/73/74 and RE-15/19 recorders on VB2 (and PPC); (all normal), and PK11-06/17/18 (all OFF); may request samples SRO/ALL * (11) Checks RCS intact (it is not) (note: only one valid abnormal reading needed to transition from E-0)
- (11a) Checks containment pressure normal (it is very elevated) (VB1 meters, PPC)
- (11b) Checks containment level normal (may already be elevated) (VB1 meters, PAMS)
- (11c) Checks containment radiation normal (elevated) (PK11-21 and PK11-19)
- (11 RNO) Places 2nd ASW/CCW HX in service (opens FCV-603 and FCV-431, VB1 far left), and transitions to EOP E-1, Loss of Reactor or Secondary Coolant ALL Implements CSFSTs SRO Transitions to EOP E-1, Loss of Reactor or Secondary Coolant, and may perform procedure transition brief (continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 15 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior (EOP E-1, Loss of Reactor or Secondary Coolant, con't)
Note: The ICC conditions should cause enough degradation to core conditions that transition to FR-C.2 or FR-C.1 should occur within about 15-20 minutes following the initiation of the SBLOCA.
ATC * (1) Checks RCPs tripped (already done, VB2)
- (1) Continues to maintain RCP seal flows 8-13 gpm (FCV-128) (CC2)
ATC/BOP * (2 & 3) Checks for faulted/ruptured S/Gs
- Faulted - checks all S/G pressures on VB3 (not uncontrolled drop/depressurized; all are dropping slowly, as the primary is now the heat sink for the secondary)
- Ruptured - checks RE-71/72/73/74 and RE-15/19 recorders on VB2 (and PPC; no upward trends or spikes, unless containment shine is noted), and PK11-06/17/18 (alarms not in); requests chemistry to sample S/Gs for activity (as follows, if done):
- Verifies phase A containment isolation reset (VB1)
- Opens FCV-584 (air to containment) (VB4, lower left)
- Opens blowdown isolation valves inside containment (FCV-760, 761, 762, 763)
- May require blocking low steamline pressure MSI/SI (due to low steamline pressures); two block switches on CC2 taken to block position BOP * (4) Maintains S/G levels 20 [25] - 65% (VB3, AFW controls)
ATC * (5) Check Pzr PORVs (closed) / blocks (open/powered) (VB2 - upper panel, far right)
ATC * (6) Verifies containment spray in service (PK01-18 OFF, containment spray is not in service, and not required) (VB1)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 16 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior (EOP E-1, Loss of Reactor or Secondary Coolant, con't)
ATC/BOP * (7) Checks ECCS termination criteria (not met, SCM is < 20°F, Pzr level is also below 12% [40%])
Note: If RCS pressure is still stabilized at this point, RHR pumps will be shut down [until needed later] (if pressure going down, they will be left in service); either condition is satisfactory for now.
ATC * (8) Maintains RHR pumps running, and aligns cooling (may open FCV-364 and 365 now [will open in later step], VB1 far left lower)
ALL * (9) Checks S/G pressures (VB3) and RCS pressure - consistent with LOCA (they are, although RCS pressure may be almost stable at saturation)
ATC/BOP * (10) Check if DGs should be stopped (busses are powered from DGs, so they cannot be secured) (VB4)
ATC * (11a, b) Verifies recirc capability (RHR Pps have power (VB1), checks aux bldg rad levels (RM-04, 06, 10, 13 show no elevated readings) (PPC, back RMS panels), and checks RHR systems alarms (PK02-16 and PK02-17 off) for intersystem LOCA (ISLOCA - no indications other than for SBLOCA)
ATC * (11c) Checks RHR Pps running, and establishes cooling to the heat exchangers (by opening FCV-364/365, as noted above), if not already open (and pumps running) (all on VB1)
ATC/BOP * (11d) Implements App P (2nd/manual check of ESF status lights; may be a lower priority)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 17 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior (EOP E-1, Loss of Reactor or Secondary Coolant, con't)
ALL * (11e, f, g) Requests RCS samples; monitors turbine status (oil Pps, coastdown, etc), checks SFP status ATC/SRO * (12) Determines that post LOCA cooldown procedure is appropriate (RCS pressure is > 300 psig [VB2, PPC, CC2], and no RHR flow [VB2])
SRO Transitions to EOP E-1.2, Post-LOCA Cooldown and Depressurization, and may perform a procedure transition brief Note: It is expected that RCS conditions will degrade soon (or will have already degraded); it is not expected that the crew will advance this far to perform E-1.2 actions (any significant actions are repeated in FR-C.2 and/or FR-C.1, such as S/G depressurization), therefore, EOP E-1.2 actions will not be listed here.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 18 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior Note: Depending on timing, the crew will note degrading RCS conditions and transition to either FR-C.2, Degraded Core Cooling, OR EOP FR-C.1, Inadequate Core Cooling. If EOP FR-C.2 is entered first, eventual transition to EOP FR-C.1 will occur within a short period.
SRO (if degraded core conditions of high temperature, > 700°F or low RVLIS level <
32%, are noted) Transitions to EOP FR-C.2, Degraded Core Cooling, and may perform a procedure transition brief (if used) (EOP FR-C.2, Degraded Core Cooling; otherwise this section N/A)
ATC * (1) Resets Safety Injection (SI) (PBs on VB1)
SRO/ATC * (2) Checks ECCS alignment (notes alignment correct; problem is still with lack of CCPs and SI PPs) (VB1, VB2)
ATC * (3) Tries to verify ECCS flow (none) (VB1 & VB2 meters)
- Notes CCP 1-3 is not available (VB2)
- May send operators to the field to reverify lineups (won't help)
ATC/BOP * (4) Checks Pzr PORVs and RCS head vents - closed (they are) VB2 far right, PAM1 for head vents)
ATC * (5) Checks RCP status (none running, no power available); goes to step 8 Cue: (when offsite power checked, per Shift Manager) 230KV has relayed out and RTS is not known; 500KV power also relayed out due to line problems, and RTS is about an hour (500KV is energized, but NOT stable).
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 19 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior (FR-C.2, Degraded Core Cooling, con't)
ATC/BOP * (8) Checks core cooling (T/Cs and RVLIS) - determines that conditions are still degrading SRO/ATC * (9) Directs that accumulator breakers be racked in (SRO)
- (9) Verifies accumulators are available (ATC)
BOP * (10) Maintains S/G levels 15 [25] - 65% (VB3, AFW controls)
ATC * (11) Blocks both trains of low steamline pressure SI (both switches to BLOCK)
(CC2)
SRO/BOP * (12) Performs RCS cooldown at < 100°F/hr rate Cooldown is performed by:
- (condenser is NOT available) Places each 10% steam dump controller in Manual, and throttles open (PCVs 19, 20, 21, and 22 on VB3 lower middle panel area). (target is 250 psig RCS pressure, and lower once accumulators are injected and isolated)
ATC * (13) Verifies RHR Pps are running SRO * (14) Directs accumulators isolated one injected Note: If EOP FR-C.2 is entered (prior to EOP FR-C.1), most likely only a few steps will be performed prior to transition to EOP FR-C.1; many of the two procedures have similar steps for the initial stages of the procedure. No further EOP FR-C.2 steps will be listed here.
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 20 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior SRO Notes conditions for Inadequate Core Cooling, and implements EOP FR-C.1 for ICC conditions (EOP FR-C.1, Inadequate Core Cooling)
ATC * (1) Verifies ECCS flow path - correct (it is) (VB1, VB2, local walkdowns)
ATC * (2) Tries to verify ECCS flow (none) (VB1 & VB2 meters)
- Notes CCP 1-3 is not available (VB2)
- May send operators to the field to reverify lineups (won't help)
ATC * (3) Checks RCP status (none running, no power available); goes to step 8 Cue: (when offsite power checked, per Shift Manager) 230KV has relayed out and RTS is not known; 500KV power also relayed out due to line problems, and RTS is expected in about an hour (500KV is energized, but NOT stable).
SRO/ATC * (4) Directs that accumulator breakers be racked in (SRO)
- (4) Verifies accumulators are available (ATC)
ATC * (5, 6, 7) Checks temperatures > 700/1200°F and/or RVLIS < 32% (one or both are unsat at this point); stays in this procedure (ie, this step looks for procedure success) (PPC, PAMS, SPDS)
SRO * (8) Directs that post-accident containment H2 monitor be placed in service BOP * (9) Maintains S/G levels 15 [25] - 50% (VB3, AFW controls)
(continued on next page)
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Appendix D (rev 9) Required Operator Actions Form ES-D-2 Op-Test No.: L111-NRC Scenario No.: S Event No.: 5 Page 21 of 21 Event
Description:
SBLOCA, leading to Inadequate Core Cooling (ICC) (con't)
Time Position Applicants Actions or Behavior (EOP FR-C.1, Inadequate Core Cooling)
ATC/BOP * (10) Checks Pzr PORVs and RCS head vents - closed (they are) VB2 far right, PAMS1 for head vents)
ATC * (11a) Blocks both trains of low steamline pressure SI (both switches to BLOCK)
(CC2)
SRO/BOP * (11b/c) Performs RCS cooldown at maximum rate possible Cooldown is performed by:
- (condenser is NOT available) Places each 10% steam dump controller in Manual, and throttles open (PCVs 19, 20, 21, and 22 full open on VB3 lower middle panel area). (target is 250 psig RCS pressure, and lower once accumulators are injected and isolated)
ATC * (12) Isolates accumulators once 250 psig reached in RCS, by taking each outlet valve switch to CLOSE (Resets SI if not already done) (VB1)
BOP * (14) Continues S/G depressurization until ECCS flow from RHR system is achieved (Critical Task) (WOG CT FR-C-1-B, to depressurize S/Gs until low head ECCS injects into the RCS, prior to need to restart RCPs) **
Terminate the scenario once low head RHR flow is injecting into the RCS, per the lead examiner.
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ATTACHMENT 1 - SIMULATOR SETUP Run Init/Initialize /CCs and VBs/Run Drill 81 Any tags are placed/removed as necessary
- Caution tags on CCP 1-3 and DG 1-2 (bkr, man/auto, and start/stop The proper Delta-I curve on CC1 and Reactivity Handbook for the simulator INIT in place.
The Rod Step Counters indicate correctly.
Run Clear Recorders icon on lower left desktop to clear YOKOGAWA recorder memories.
Clear the PCS HMIs (NSR) by "flushing" the trend buffer; then, restart the "Window Viewer" app.
Boric Acid and Primary Water Target Blender set to values identified in Lesson Record PPC MAX on CC2 lamicoid.
Record Boron Concentration for desired simulator INIT on CC2 lamicoid.
Circuit breaker flags are correct on CC1 (Proportional Heaters), CC3, VB4, and VB5 Equipment status lamicoids are correct:
RHR Valves (8726A/B and 8734A/B) - CLOSED (OPEN if RHR in service)
H2 or N2 on VCT - H2 ( unless shut down training)
SUPPLYING IN-SERVICE SCW HX - CWP 1-1 AUTO RECLOSE FEATURE CUTIN ON THIS CWP - CWP 1-1 SELECTED TO BUS 2F - CONT. RM. VENT TRAIN 1 BUS F SELECTED TO BUS 1H - CONT. RM. VENT TRAIN 1 BUS H B.A. XFER PP SUPPLYING BLENDER - BA PP 1-2 RADWASTE DISCH AND CHLORINATION - ASW 1-1 OFF NORMAL LAMICOIDS OR PINK MARKERS - Placed as needed or return to CC3 The Plant Abnormal Status Board is updated for Charging Pump Status, Boron Conc, PRA Risk Status and Work Week Matrix.
Copies of Procedures, Attachments; Appendixes; Foldout Pages; Annunciator Response Procedures and commonly used forms are in binders and NOT Marked up:
PPC Setup:
- PPC BIG Screen (set to TABULARLG1), select new list, private, Sim Large)
- RODCONFIG is updated (click Apply when completed)
SPDS (screens and time updating), A screen RM, B screen SPDS.
CC3 Annun. CRT big screen (if enabled then get alarm it needs reset - Tools, keyboard, Tools, password - which is "A", File Exit - Start over)
The chart recorders are operating properly. DDR10s and Turbine Vib Recorder are acknowledged and in AUTO. CC1 NR-45 on proper screen. PAMS RVLIS/TMS screens on Summary Page.
All typewriters are on, with adequate paper/ribbon/etc., and are in the ON LINE status, as needed.
Alarm A&E Viewer window is activated prior to run, and printer is placed ,ONLINE, if needed.
Triconex DEH/DFW alarms have been acknowledged/cleared.
Seismic drawer put back; check for any alarms on the Rad panels PC setup for SVC tailboard (G-3 ENF Reset, RCPs, U-1 Safety Monitor)
Verify paper in HPD2 and print a test page.
Verify Annunciator Horn is on (BELL ON) and Sound Effects are on (SOUND ON).
The video, audio, and communication systems are set up and functioning Turn down plant PA on simulator floor (restore to original setting when scenario completed)
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TIMELINE AND BOOTH/CONSOLE OPERATOR ACTIONS Timeline The following table shows the simulator computer operations and other instructions the examiners need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION X Setup Simulator INIT 510 100% power, MOL, CB = 774 , Integrators: BA - 00, per Checklist and PW - 25
- Tags: CCP 1-3, DG 1-2 X Setup Drill 81 Reset normal engineering values X Setup Start TEAM data collection Collect data for scenario for NRC Exam Team X Setup Board Operations Place the 1-2 CCP in service, and stop/clear the 1-3 CCP.
X Setup DRILL 35 in AUTO Clears the 1-2 DG X Setup ser 0219 act,0,0,0,d,0 Clears the 1-3 CCP dsc cvc29 act,0,0,0,d,0 X Once crew has DRILL 9206 in AUTO Scenario malfunctions are inputted once the crew taken the watch takes the watch 2 min after crew dsc rod1 act,0,0,120,d,0 Normal power supply to DRPI trips (backup is takes the watch available)
X When requested loa eps act,1,0,0,d,0 Places DRPI on backup to place DRPI on backup X When DRPI Cue: The normal DRPI breaker (52-1F-45) is tripped open, with no apparent problem damage, no unusual smells.
investigated X Once rods Cue: (from Shift Manager) I have just received a valid backdown order from placed back in the Grid Coordination Center (GCC). Per Ops Policy B-1, ramp unit 1 AUTO, per lead down 350 MW in the next 10 minutes.
examiner 3 min after xmt rcs93 3,679,180,600,c, Loop 3 Tc fails slowly high (first causes rods to drive generator load is smss.lt.900,0 in, and if left long enough in auto, will eventually less than 900 cause rods to drive back out in AUTO (once PCS MWe kicks out that loop) 25 min after gen cnv mfw4 2,20,120,1500,c, FCV-520 fails slowly closed; manual control will work load < 900 MWe smss.lt.900,ftd520_man (vlv failure clears on hitting manual on controller);
(per lead level is controllable examiner)
(continued on next page)
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TIMELINE AND BOOTH/CONSOLE OPERATOR ACTIONS Timeline The following table shows the simulator computer operations and other instructions the examiners (con't) need to know about the scenario to successfully run the exam. X = Manual entry required!
TIME LINE CONSOLE ENTRY SYMPTOMS, CUES, AND DESCRIPTION Failures on Safety mal ppl3a act 1,0,0,d,0
- AUTO SI fails Injection mal ppl3b act 1,0,0,d,0
- One train of Phase A fails mal ppl1b act 2,0,0,d,0 Failures to enable pmp cvc1 4,0,0,15,c,
- All ECCS SI Pps and CCPs trip on OC (no high inadequate core fnispr.lt.5,0 or med head ECCS cooling scenario pmp cvc2 4,0,0,15,c,
- Loss of 230KV startup power (3 min after (and reasonable fnispr.lt.5,0 pressure is < 1300 psig); ensures RCPs not timing) available (less time to ICC) pmp sis1 4,0,0,15,c,fnispr.lt.5,0 pmp sis2 4,0,0,15,c,fnispr.lt.5,0
- TDAFP won't start (do not make available) mal syd2 act 0,1,180,c, prcmstar(1).lt.1300,0 vlv afw7 1,0,0,0,d,0 5 min after mal rcs3a act 5,10,300,c, SBLOCA (5") eventually leads to ICC conditions FCV-520 is taken ftd520_man,0 to MAN DC-2012-11-DRAFT OPERATING TEST.docx Page 119 of 263 Rev 2
DRILL FILE TEXT
- L111 NRC Exam Scenario - Spare (DRILL 9206)
- 09/04/12 jfb
- Loss of normal DRPI power
- Loop 3 Tc fails high (slowly) 10 min after gen < 900 MW
- XMT RCS93 RCS LP3 NR T-COLD: TQM-430B, TQM-430B1 #txmt410b(3) xmt rcs93 3,679,180,600,c,smss.lt.900,0 #txmt410b(3)
- mal PPL3A SAFETY INJECTION ACTUATION FAILURE (TRAIN A) mal ppl3a act 1,0,0,d,0
- mal PPL3B SAFETY INJECTION ACTUATION FAILURE (TRAIN B) mal ppl3b act 1,0,0,d,0
- mal PPL1B CONTAINMENT ISOLATION PHASE A FAILURE (TRAIN B) mal ppl1b act 2,0,0,d,0
- FCV-520 fails low in AUTO (MAN OK) 25 min after turb load is less than 900 MW,
- CNV MFW4 MAIN FEEDWATER REG. VALVE #rfwf520 cnv mfw4 2,0.20,120,1500,c,smss.lt.900,0 #rfwf520 tc ftd520_man, cnv mfw4 clr
- PMP CVC1 CHARGING PP 11 (CENT.) #ocvp11 pmp cvc1 4,0,0,15,c,fnispr.lt.5,0 #ocvp11
- PMP CVC2 CHARGING PP 12 (CENT.) #ocvp12 pmp cvc2 4,0,0,15,c,fnispr.lt.5,0 #ocvp12
- PMP SIS1 SAFETY INJECTION PP 11 #osip11 pmp sis1 4,0,0,15,c,fnispr.lt.5,0 #osip11
- PMP SIS2 SAFETY INJECTION PP 12 #osip12 pmp sis2 4,0,0,15,c,fnispr.lt.5,0 #osip12
- mal RCS3A SMALL LOCA IN BOTTOM OF COLD LEG 1 mal rcs3a act 5,10,300,c,ftd520_man,0
- Loss of S/U power once decision made to leave RCPs on MAL SYD2 act 0,1,180,c,prcmstar(1).lt.1300,0
- VLV AFW7 AFW TURB 11 STM SUPPLY HDR #rmsf095 vlv afw7 1,0,0,0,d,0 #rmsf095 DC-2012-11-DRAFT OPERATING TEST.docx Page 120 of 263 Rev 2
Diablo Canyon Power Plant Operations Shift Log Unit 1 Today - Dayshift Unit 1 Days at Power: 207 Days Operating Mode: 1 Gross Generation: 1190 MWe Power Level: 100 % Net Generation: 1147 MWe Shift Manager Turnover PRA RISK STATUS NEXT SHIFT: GREEN GRID STATUS NEXT SHIFT: Normal AVERAGE RCS CALCULATED LEAKRATE: 0.01 gpm CONDENSER INLEAKAGE: < 0.01 gpd MAIN GEN H2 USAGE (475 SCFD Limit): 311 SCF / 322 SCFD 5 day ave NEW EMERGENT WORK:
- CCP 1-3 (see below)
SHUTDOWN TECH SPECS / ECGS:
- TS 3.8.1.B DG 1-2 OOS for corrective maintenance on air starter motor (discovered during normal surveillance run two nights ago); RTS estimate is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; last partial STP I-1C completed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago (due in 7 hrs); action 3.8.1.B.3.1 has been completed.
ECG ACTIONS THAT IF COMPLETION TIME NOT MET ECG 0.3 IS ENTERED:
- ECG 8.1.A - CCP 1-3 OOS, due to rising vibrations; alignment is almost complete, expect to run sometime this shift. Declared inoperable 5 hrs ago, doing hourly fire watches and complying with actions in the A.1.2 section; pump is required back in 6.5 days (RTS is later this shift).
TURNOVER ITEMS:
- Maintain 100% power
- Run the 1-3 CCP if it becomes available PRIORITY ITEMS FOR NEXT SHIFT:
- See above OPERABILITY ITEMS:
- TS 3.8.1.B DG 1-2 OOS - 2 days into 14 day action ANNUNCIATORS IN ALARM:
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Shift Foreman Turnover TURNOVER ITEMS:
- U maintain 100% - no one in containment
- U-2 is at 100%
REACTIVITY MANAGEMENT:
- Time in core life: _MOL_.
- Power History: Steady State, previously at 100% for 177 days. Currently power at 100%
- Boron concentration is _774 ppm_ from a sample taken 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.
- Control Rod Height: 231 steps on CBD.
- Diluting the RCS approximately 25 gallons every 1.5 hrs.
- The last dilution/boration was completed _15_ min ago.
- Rod motion: none planned, as needed to maintain I on target CONDITIONAL SURVEILLANCES & INCREASED MONITORING:
OTHER ABNORMAL PLANT STATUS
- None DC-2012-11-DRAFT OPERATING TEST.docx Page 122 of 263 Rev 2
Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-A1
Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) HAS BEEN EXCEEDED Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (modified from L061Audit ADMRO1)
Note: This is an admin JPM (RO), intended for the classroom setting.
References:
U-2 STP I-1A, Routine Shift Checks Required by Licenses, Rev 121 U-2 COLR, Core Operating Limits Report, Rev 6 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes (average validation time ___ min)
Critical Steps: 2, 3 Job Designation: RO Rev Comments/TIPs: Rev 1: minor corrections following Ops Rep review DCPP Task # / Rating: 796200 N/A Gen KA # / Rating: GEN 2.1.25, Conduct of Operations 3.9 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Required Materials:
- U-2 STP I-1A, Routine Shift Checks Required by Licenses, Rev 121 (partial, with step 11, is adequate)
- U-2 COLR, Core Operating Limits Report, Rev 6 (partial, with RIL page, is adequate); Figure 1 Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Control Bank positions are compared with the RIL, and it is determined that CBC and CBD are NOT meeting RIL requirements (see answer key for details).
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Operator obtains correct Note: Provide the U-2 STP I-1A (partial procedures. OK) and U-2 COLR (partial OK), if not already provided.
1.1 Operator obtains STP I-1A, Attachment 12.1.
1.2 Operator obtains COLR for Diablo Canyon Unit 2, Figure 1.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 2. Records data (thermal power 2.1 Determines present power level to level, Rod Insertion Limit (RIL), be U4300A05/A15 reading (25%).
and bank positions) on STP Data Sheet . (step 11a) 2.2 Records present thermal power level on STP I-1A Data Sheet (25%).
2.3 Determines Insertion limit for current power level for CBD is 25
(+/- 3) steps.**
2.4 Determines Insertion limit for current power level for CBC is 152
(+/- 3) steps.**
Note: Both bank RILs and bank positions will be placed on the answer sheet, but only one (either bank) need be entered on the STP (both OK).
2.5 Records Insertion limit on STP I-1A data sheet (either bank, or both; see answer key). **
2.6 Records current bank position on STP I-1A data sheet (either bank, or both; see answer key). **
2.8 Initials PERF field.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 3. Determines if RIL limits are met. Note: The next substeps may be done in (step 11b) any order. The Answer Sheet will be the official grading document for this JPM.
3.1 Compares CBD RIL with current bank position, and determines RIL limit NOT met. **
(will be documented on answer sheet) 3.2 Compares CBC RIL with current bank position, and determines RIL limit NOT met. **
(will be documented on answer sheet)
Note: This above may be done in any order.
3.3 Initials PERF field.
3.4 (optional) may add asterisk/note that step is UNSAT (RIL limits NOT met (and/or add to comment page).
Cue: (if examinee attempts to notify the SFM (proctor), just tell them to document their results on the answer sheet and STP data sheet.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Verify sequence and overlap limits 4.1 Notes that CBA and CBB are fully specified in the COLR are met for withdrawn.
control banks not fully withdrawn from the core. (step 11c)
Note: Proper sequencing can be determined by the fact that the first two control banks are fully withdrawn, and that CBC is 128 steps higher than CBD, and CBC is > 103 steps (ie, CBA/CBB are all rods out).
4.2 Determines that CBC and CBD have proper overlap and sequence.
4.3 Initials PERF field.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED ANSWER KEY Note to Examiner: The STP I-1A (step 11) should be filled out, however, the ANSWER SHEET is the official grading document for this task (since it documents intermediate steps not shown on the STP data sheets)
Step 11 of STP I-1A:
JFB 25 (see below)
CBC/CBD 147 / 19 (1)
JFB (note: step 1b may include * / note / comment with some or all of the below information on the STP data sheet (or comment page))
ANSWER KEY Bank RIL (from COLR) Is Control Bank Above the Rod Insertion Limit (RIL)?
A N/A (ARO) [ X ] YES [ ] NO B N/A (ARO) [ X ] YES [ ] NO C 152 + 3 steps [ ] YES [ X ] NO D 25 + 3 steps [ ] YES [ X ] NO DC-2012-11-DRAFT PAGE 129 OF 263 REV. 1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
ANSWER SHEET Control RIL (from Is Control Bank Above the Rod Insertion Limit Bank COLR) (RIL)?
CBA N/A (ARO) [ ] YES [ ] NO CBB N/A (ARO) [ ] YES [ ] NO CBC [ ] YES [ ] NO CBD [ ] YES [ ] NO DC-2012-11-DRAFT PAGE 130 OF 263 REV. 1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET DC-2012-11-DRAFT PAGE 131 OF 263 REV. 1 OPERATING test.docx
Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-A2
Title:
DETERMINE RAMP RATE RESTRICTIONS Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (modified from L061Audit ADMRO2, and LJACO-12R)
Note: This is an admin JPM (RO), intended for the classroom setting.
References:
OP L-4, Normal Operation at Power, Unit 2, Step 6.3.3.j, Rev. 67 Load Changing Recommendations, Volume 9B, Page VA-2, Rev. 0 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes (average validation time ___ min)
Critical Steps: 2, 3, 4, 5 Job Designation: RO Rev Comments/TIPs: Minor updates following validation DCPP Task # / Rating: 816200 4.2 Gen KA # / Rating: GEN 2.1.32, Conduct of Operations 3.8 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Required Materials: OP L-4, Normal Operation at Power, Unit 2, Step 6.3.3.j, Rev. 67.
(partial procedure recommended)
Load Changing Recommendations, Volume 9B, Page VA-2, Rev. 0 (attached to answer sheet)
Initial Conditions: Given:
- Both Units are at 100% power.
- A High Swell Warning is in effect (9.5 overall rating), and an Operational Decision-Making (ODM) meeting has resulted in plans for both units to ramp down to < 25% power, in anticipation of a "kelp attack".
- OP L-4 has been implemented on both units for the ramp.
Initiating Cue: U-2 Shift Foreman (SFM) directs you to calculate the minimum time allowable to ramp Unit 2 from 100% to 20% turbine power, per OP L-4, step 6.3.3.j; the SFM directs that you use the recommended normal operating line on the referenced figure for your calculations.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: It is determined that the minimum ramp time for the U-2 ramp from 100% to 20% power is 1.5 hrs / 90 min (1.25 to 1.75 hrs is the acceptable range, or 75 - 105 minutes).
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Refers to appropriate procedure. Note: Provide the partial OP L-4 (step 6.3.3.j, as a minimum), and drawing VA-2 from Vol 9B, if not done previously. These pages are attached to the answer sheet.
1.1 References Volume 9B, Page VA-2.
1.2 References OP L-4, step 6.3.3.j.
Step was: Sat: ______ Unsat _______
- 2. Determines st Initial Turbine Load 2.1 Determines initial turbine load to be and 1 stage temperature based on 100%.
current power level.
2.2 Determines 1st stage temperature to be 275 °F (+ 5 °F). **
2.3 Records both above values in step 6.3.3.j.2.
Step was: Sat: ______ Unsat _______
- 3. Determines st Final Turbine Load 3.1 Determines final turbine load to be and 1 stage temperature based on 20%.
final (target) power level.
3.2 Determines 1st stage temperature to be 135 °F (+ 5 °F). **
3.3 Records both above values in step 6.3.3.j.3.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Determines Temperature Change 4.1 Determines temperature change for for ramp. 1st stage temperature to be 140 °F (275-135) (acceptable range, based on two previous curve readings is 130 - 150 °F). **
4.2 Records value in step 6.3.3.j.4.
Step was: Sat: ______ Unsat _______
- 5. Determines minimum permissible Cue: The U-2 SFM has directed use of time for ramp. the "recommended normal operating line" while doing this calculation.
5.1 Uses graph on Vol 9B VA-2 to determine that minimum ramp time, based on above T (from step 4.1, above), is 1.5 hrs (acceptable range is 1.25 - 1.75 hrs, based on above curve readings). **
5.2 Records value in step 6.3.3.j.5.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED ANSWER KEY ANSWER KEY Minimum Ramp Time: 1.5 hrs / 90 min (1.25 - 1.75 hrs is acceptable, as is75-105 minutes)
Partial OP L-4 (step 6.3.3.j) copied here:
100 275 (270-280 acceptable) 20 135 (130-140 acceptable)
(130-150 acceptable) 90 (see above range)
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
ANSWER SHEET Minimum Ramp Time:
Partial OP L-4 (step 6.3.3.j) copied here:
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET DC-2012-11-DRAFT PAGE 138 OF 263 REV. 1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET DC-2012-11-DRAFT PAGE 139 OF 263 REV. 1 OPERATING test.docx
Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-A3
Title:
DETERMINE IF AXIAL FLUX DIFFERENCE (AFD) IS WITHIN TECH SPEC LIMITS Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (modified for RO from LJAEC-11S and L081CAdmin ADM03)
Note: This is an admin JPM (RO), intended for the classroom setting.
References:
Vol 9B, Figure R23-2F-1, U-2 Cycle 17 RAOC Limits, Rev 260 U-2 COLR, (last page, AFD limits), Rev 6 U-2 STP I-1C (partial), Att 12.1, step 1, Rev 81 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes (average validation time ___ min)
Critical Steps: 2, 3, 4, 6 Job Designation: RO Rev Comments/TIPs: Rev 1: minor corrections following Ops Rep review; added refs to cue sheets DCPP Task # / Rating: 816200 4.2 Gen KA # / Rating: GEN 2.2.42, Equipment Control 3.9 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Required Materials:
- Vol 9B, Figure R23-2F-1, U-2 Cycle 17 RAOC Limits, Rev 260
- U-2 COLR, (last page, AFD limits), Rev 6
- U-2 STP I-1C (partial), Att 12.1, step 1, Rev 81
- calculator Initial Conditions: Given:
- Unit 2 has just completed a partial stator cooling water runback that was terminated when the Turbine Building Watch started the standby pump.
- The crew is in OP AP-25, and are taking actions to stabilize following the ramp. Power is about 65%.
- The Work Control Lead (WCL) just finished reviewing alarms, and noted that PK03-25, input 1252, Reactor Axial Offset PPC Alarm, is IN, and has implemented PK03-25, section 2.1.
- Plant status is as follows:
- U4300A05/A15 is not available.
- U1169A05 is @ 66.0%.
- PPC MAX (NI POWER) is 100.3%
- I readings are as follows:
- NI-41C -27.2%
- NI-42C -23.9%
- NI-43C -26.5%
- NI-44C -26.8%
Initiating Cue: The U-2 Shift Foreman (SFM) directs you to determine if AFD is within Tech Spec limits, using STP I-1C, Attachment 12.1, step 1, and note your results on the STP data sheet, and below on the Answer Sheet.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: The examinee determines that 3 of 4 AFD channels are NOT within Tech Spec Limits (see Answer Key).
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. This is a left column step. Note Note: Provide copies of partial STP I-that it is the same as the old 1C (Att 12.1, step 1), and Figure format. R23-2F-1, if not already done.
Provide U-2 COLR (last page) if requested. Note that R23-2F-1 and the drawing in the COLR are the same, except that R23-2F-1 includes admin limits.
Note: The surveillance only checks AFD within Tech Spec limits. This task checks both Tech Spec and admin limits (by using the answer sheet).
1.1 References U-2 STP I-1C, Attachment 12.1, step 1.
1.2 References U-2 Vol 9B Figure R23-2F-1.
1.3 (May) reference U-2 COLR (last page, AFD Tech Spec Limits).
Step was: Sat: ______ Unsat _______
- 2. Determines Rated Thermal Power Note: With thermal power (U4300A05)
(RTP) for AFD Check. not available, the alternate (NI power, using calc) will be used.
2.1 Determines that 1st choice (thermal power) for power reading (U4300A05) is not available.
2.2 Determines RTP by dividing current NI power (66.0%) by PPC MAX (100.3) to get 65.8% (65.8 - 65.803 acceptable), and enters on data sheet. **
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 3. Determines Upper AFD Limit. Note: Using either curve will yield the same results.
3.1 Compares 65.8% RTP with right side of R23-2F-1 (and/or U-2 COLR AFD curve).
3.2 Determines upper limit to be
+20.5% (20.0% - 21.0% is acceptable), and enters on data sheet. **
Step was: Sat: ______ Unsat _______
- 4. Determines Lower AFD Limit. Note: Using either curve will yield the same results.
4.1 Compares 65.8% RTP with left side of R23-2F-1 (and/or U-2 COLR AFD curve).
4.2 Determines lower limit to be -25.0%
(-24.5% -25.5% is acceptable),
and enters on data sheet. **
Step was: Sat: ______ Unsat _______
- 5. Enters AFD readings on data sheet 5.1 Enters AFD readings on data sheet for comparison. (from initial conditions).
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 6. Compares RTP to AFD readings, 6.1 Checks NI-41C against the lower and determines if AFD is within limits, determines it is NOT in the Tech Spec limits. "Acceptable Operation" area, and marks the "AFD Within Limits" NO box. **
6.2 Checks NI-42C against the lower limits, determines it is in the "Acceptable Operation" area, and marks the "AFD Within Limits" YES box. **
6.3 Checks NI-43C against the lower limits, determines it is NOT in the "Acceptable Operation" area, and marks the "AFD Within Limits" NO box. **
6.4 Checks NI-44C against the lower limits, determines it is NOT in the "Acceptable Operation" area, and marks the "AFD Within Limits" NO box. **
Note: Examinee may use asterisk/note/
comment to note that AFD is outside limits on step 1b. Any of these is acceptable; the Answer Sheet makes this part of the step very clear.
6.5 Determines that more than one AFD channel is outside the limits (also, marks YES on answer sheet). **
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED ANSWER KEY ANSWER KEY
-27.2 X 65.8 +20.5 -25.0
-23.9 X
(65.8 - 65.803) (20.0 - 21.0) (-24.5 -> -25.5) -26.5 X
-26.8 X Do more than one excore channel exceed AFD Limits? [ X] YES [ ] NO DC-2012-11-DRAFT PAGE 146 OF 263 REV. 1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
Do more than one excore channel exceed AFD Limits? [ ] YES [ ] NO DC-2012-11-DRAFT PAGE 147 OF 263 REV. 1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET DC-2012-11-DRAFT PAGE 148 OF 263 REV. 1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET DC-2012-11-DRAFT PAGE 149 OF 263 REV. 1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET DC-2012-11-DRAFT PAGE 150 OF 263 REV. 1 OPERATING test.docx
Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-A4
Title:
CALCULATE MAXIMUM STAY TIME Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (modified from L081NRCADM04 & L061NRCADM04.)
Note: This is an admin JPM (RO), intended for the classroom setting.
References:
RP1.ID6, Personnel Dose Limits and Monitoring Requirements, Rev 10B Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes (average validation time ___ min)
Critical Steps: 3, 4 Job Designation: RO Rev Comments/TIPs: Minor changes following validation DCPP Task # / Rating: GET RWTLIMIT06 N/A Gen KA # / Rating: GEN 2.3.4, Radiation Control 3.2 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Required Materials:
- RP1.ID6, Personnel Dose Limits and Monitoring Requirements, Rev 10B
- calculator Initial Conditions: Given:
- The Work Control Shift Foreman (WCSFM) and Work Control Lead (WCL) have assigned you to hang an outage clearance in two locations, which are both in a High Radiation Area.
- The first portion of the clearance is in an area where the dose rate is 150 mr/hr, and the work there will take 30 minutes.
- The second portion of the clearance is in an area where the dose rate is 325 mr/hr; it is not known how long this work will take.
- Your current year exposure history (per NRC Form 4) is as follows:
- Deep Dose Equivalent (DDE) = 873 mrem
- Committed Dose Equivalent (CDE) = 25 mrem
- Committed Effective Dose Equivalent (CEDE) = 187 mrem
- Lens Dose Equivalent (LDE) = 18 mrem
- Shallow Dose Equivalent (SDE) = 555 mrem
- Effective Dose Equivalent (EDE) = 1111 mrem Initiating Cue: The WCSFM has directed you to determine the maximum time you can stay in High Radiation Area above, to complete the 2nd portion of the clearance (once you have completed the first portion of the clearance),
and still remain within DCPP administrative dose guidelines for Total Effective Dose Equivalent (TEDE, whole body) dose.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Determines maximum stay time to be 1.93 hrs (1.9 - 1.93 hrs, or 114 -
116 minutes)
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Determines current TEDE. Note: TEDE = EDE + CEDE. Steps preceding step 3.2 may be performed in any order.
1.1 Determines current TEDE by adding the EDE (1111 mrem) to the CEDE (187 mrem) = 1298 mrem.
Step was: Sat: ______ Unsat _______
- 2. Determines dose required to Note: Dose Rate x Stay Time = Dose complete 1st portion of clearance. used for 1st portion of clearance.
2.1 Multiplies dose rate (150 mrem/hr) time stay time (1/2 hour) =
75 mrem used for 1st portion of clearance.
Step was: Sat: ______ Unsat _______
- 3. Determines nd dose margin allowed Note: All guidelines and limits can be for 2 portion of clearance. found in RP1.ID6.
3.1 Determines administrative guideline is 2000 mrem for the year.
3.2 Determines dose margin for 2nd portion of clearance by subtracting current annual dose (1298 mrem) and dose for 1st portion of clearance (75 mrem) from dose limit (2000 mrem); 2000 - (1298 + 75) =
627 mrem margin (for job). **
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Determinesnd maximum stay time 4.1 Stay Time = Margin / Dose Rate (for 2 portion of clearance).
4.2 Stay Time = 627 mrem / 325 mrem/hr..
4.3 Stay Time = 1.93 hrs (allowable range is 1.9 - 1.93 hrs, or 114-116 minutes) **
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
ANSWER (Stay Time) =
Work Area (use back of sheet as needed)
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-A5
Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) HAS BEEN EXCEEDED Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (modified from L061Audit ADMRO1)
Note: This is an admin JPM (SRO), intended for the classroom setting.
References:
U-1 & U-2 Technical Specifications U-2 COLR, Core Operating Limits Report, Rev 6 U-2 STP I-1A, Routine Shift Checks Required by Licenses, Rev 121 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 10 minutes (average validation time ___ min)
Critical Steps: 2, 3, 4 Job Designation: SRO Rev Comments/TIPs: Rev 1: minor corrections following Ops Rep review DCPP Task # / Rating: 796200 / 910400 NA / 4.7 Gen KA # / Rating: GEN 2.1.25, Conduct of Operations 4.2 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Required Materials:
- U-2 STP I-1A, Routine Shift Checks Required by Licenses, Rev 121 (partial, with step 11, is adequate)
- U-2 COLR, Core Operating Limits Report, Rev 6 (partial, with RIL page, is adequate); Figure 1 Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you as the Work Control Shift Foreman (WCSFM) to use the COLR to independently determine if control banks are above the Rod Insertion Limit (RIL); also, note any Tech Specs action statements that are applicable (if any). Write your results on this Cue / Answer Sheet.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Control Bank positions are compared with the RIL, and it is determined that CBC and CBD are NOT meeting RIL requirements (see answer key for details), and that TS Action 3.1.6.A is applicable (see answer key).
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Operator obtains correct Note: Provide access to Technical procedures. Specifications, and the U-2 COLR (partial OK), if not already provided.
1.1 Operator obtains Technical Specifications (may do this later).
1.2 Operator obtains COLR for Diablo Canyon Unit 2, Figure 1.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 2. Determines Rod Insertion Limits 2.1 Determines present power level to (RILs) for the current power level. be U4300A05/A15 reading (25%).
2.2 Determines Insertion limit for current power level for CBD is 25
(+/- 3) steps.**
2.3 Determines Insertion limit for current power level for CBC is 152
(+/- 3) steps.**
Step was: Sat: ______ Unsat _______
- 3. Determines if RIL limits are met. 3.1 Compares CBD RIL with current bank position, and determines RIL limit NOT met. **
3.2 Compares CBC RIL with current bank position, and determines RIL limit NOT met. **
Cue: (if examinee attempts to notify the SFM (proctor), just tell them to document their results on the answer sheet.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Determines Tech Spec 4.1 Notes that not meeting the RIL Applicability. constitutes a failure to meet Tech Spec LCO 3.1.6.
4.2 Determines that Tech Spec Action Statement 3.1.6.A is applicable to this condition (and notes on answer sheet). **
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED ANSWER KEY ANSWER KEY Control RIL (from COLR) Is Control Bank Above the Rod Insertion Limit Bank (RIL)?
CBA N/A (ARO) [ X ] YES [ ] NO CBB N/A (ARO) [ X ] YES [ ] NO CBC 152 + 3 steps [ ] YES [ X ] NO CBD 25 + 3 steps [ ] YES [ X ] NO Tech Spec Actions TS Action 3.1.6.A (may also spell out actions, as shown below, but applicable (if any) this is not required)
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
ANSWER SHEET Control RIL (from COLR) Is Control Bank Above the Rod Insertion Bank Limit (RIL)?
CBA N/A (ARO) [ ] YES [ ] NO CBB N/A (ARO) [ ] YES [ ] NO CBC [ ] YES [ ] NO CBD [ ] YES [ ] NO Tech Spec Actions applicable (if any)
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET DC-2012-11-DRAFT PAGE 163 OF 263 REV. 1 OPERATING test.docx
Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-A6
Title:
APPROVE MOVEMENT OF SPENT FUEL ASSEMBLIES Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (modified from L061NRC/L061CAudit ADM06 and LJACO-14S)
Note: This is an admin JPM (SRO), intended for the classroom setting.
References:
OP B-8DS3, Insert Shuffle Within the Spent Fuel Pool, Rev. 26 (not needed as handout for JPM)
Tech Spec 3.7.17, Spent Fuel Assembly Storage Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes (average validation time ___ min)
Critical Steps: 2, 3, 4, 5 Job Designation: SRO Rev Comments/TIPs: Rev 1: minor corrections following Ops Rep review DCPP Task # / Rating: 816600 / 356800 4.1 / 2.6 Gen KA # / Rating: GEN 2.1.37, Conduct of Operations 4.6 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee. The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Required Materials: U1/U2 Technical Specifications (may give just TS 3.7.17 if not enough full volumes to go around)
Initial Conditions: Given:
- Unit One is at 100% power.
- Reactor Engineering is planning to move spent fuel assemblies from "All Cell Configuration" areas to the "B" locations in "2 x 2 Array Configuration" areas.
Initiating Cue: You are the SRO assigned to review the proposed changes (shown below). Review each change and determine if the proposed move should be allowed or dis-allowed, based on the conditions given for each assembly. Document your evaluations below, on this cue/answer sheet.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Determines if each move should be allowed (see Answer Key).
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. References correct Technical Note: for a move to the "B" location in Specification and figures. a 2 x 2 Array, Figures 3.7.17-1 and 3.7.17-3 should be used.
1.1 References Tech Spec 3.7.17, Spent Fuel Assembly Storage.
1.2 References Figure 3.7.17-1 to determine what limits apply to the "B" location in a 2 x 2 Array (ie, comply with figure 3.7.17-3 for 2 x 2 Array).
Step was: Sat: ______ Unsat _______
- 2. Determine if Element AE-22 can 2.1 Compares burnup on fuel cell be placed in a "B" location for a AE-22 with Figure 3.7.17-3.
2 x 2 Array Storage Location.
2.2 Determines that fuel move is ALLOWABLE. **
Step was: Sat: ______ Unsat _______
- 3. Determine if Element AA-01 can 3.1 Compares burnup on fuel cell be placed in a "B" location for a AA-01 with Figure 3.7.17-3.
2 x 2 Array Storage Location.
3.2 Determines that fuel move is ALLOWABLE. **
Step was: Sat: ______ Unsat _______
- 4. Determine if Element AG-11 can 4.1 Compares burnup on fuel cell be placed in a "B" location for a AG-11 with Figure 3.7.17-3.
2 x 2 Array Storage Location.
4.2 Determines that fuel move is NOT ALLOWABLE. **
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 5. Determine if Element AD-33 can 5.1 Compares burnup on fuel cell be placed in a "B" location for a AD-33 with Figure 3.7.17-3.
2 x 2 Array Storage Location.
5.2 Determines that fuel move is NOT ALLOWABLE. **
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED ANSWER KEY ANSWER KEY Element Initial Enrichment Discharge Burnup Allow or Dis-allow (wt% U-235) (MWD/MTU)
AE-22 3.25 34,106 Allow [ X ] Dis-allow [ ]
AA-01 3.5 36,503 Allow [ X ] Dis-allow [ ]
AG-11 3.75 36,117 Allow [ ] Dis-allow [ X ]
AD-33 4.00 39,433 Allow [ ] Dis-allow [ X ]
Note: Figure with plotted (approximate) locations is on next page (for examiner information only).
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED ANSWER KEY AA-01 AD-33 AE-22 AG-11 DC-2012-11-DRAFT PAGE 169 OF 263 REV. 1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET / ANSWER SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
Fuel Initial Enrichment Discharge Burnup Allow or Dis-allow Assembly (wt% U-235) (MWD/MTU)
AE-22 3.25 34,106 Allow [ ] Dis-allow [ ]
AA-01 3.5 36,503 Allow [ ] Dis-allow [ ]
AG-11 3.75 36,117 Allow [ ] Dis-allow [ ]
AD-33 4.00 39,433 Allow [ ] Dis-allow [ ]
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-S1
Title:
RESPOND TO HIGH ACCUMULATOR PRESSURE Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (from LJC-009)
Note: This JPM is designed to be performed in // with the S2 JPM.
References:
U-1 AR PK02-05, ACCUM PRESSURE HI-LO, Rev. 18A U-1 OP B-3B:I, Accumulator Fill and Pressurize, Rev. 27B Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 25 minutes (average validation time ___ min) (OCT ave time 13.7 min)
Critical Steps: 5, 6, 7, 8, 9 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1: corrected typos, minor updates DCPP Task # / Rating: 327600 3.1 AUTHOR: GARY HUTCHISON DATE:
REV. 1
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Gen KA # / Rating: 006.A1.13 3.5 / 3.7 DC-2012-11-DRAFT PAGE 172 OF 263 REV. 1 operating test.docx
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The task standard will NOT be read to the student. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.
Required Materials: None Initial Conditions: Given:
- Unit 1 is at 100% power.
- PK02-05 is in alarm .
Initiating Cue: The Shift Foreman directs you to respond to the alarm, and take necessary action to return accumulator parameters to normal in accordance with AR PK02-05 and other applicable procedure(s), as required.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Alarm is cleared and the lineup returned to normal in accordance with AR PK02-05 and OP B-3B:I.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Obtain the correct procedure. 1.1 References AR PK02-05.
Step was: Sat: ______ Unsat _______
- 2. Verify abnormal condition exists. 2.1 Reads NOTE prior to step 2.1.1.
2.2 Checks PI-960 and PI-961 to verify alarm is not due to instrument failure. (can be checked on VB-1, or on the PPC) 2.3 Reads step 2.1.2 that refers to Tech Specs. (give cue below)
Cue: The SFM is addressing all Technical Specification requirements at this time.
2.4 Checks Annunciator PK02-10 ACCUM LEVEL HI-LO CLEAR 2.5 Determines the alarm condition is accumulator 11 high pressure and transitions to Section 2.2 High Pressure Step was: Sat: ______ Unsat _______
- 3. Determine High Accumulator 11 3.1 Determines level is normal and Pressure is NOT due to Level pressure is high from previous step, increase (step 2.2.1, first line) and goes on to next step (2.2.2).
Step was: Sat: ______ Unsat _______
- 4. Transition to OP B-3B:I 4.1 Implements OP B-3B:I, step 6.4 Accumulators - Fill and (may review applicable P&Ls prior Pressurize (per step 2.2.2 of to continuing with section 6.4).
PK02-05)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 5. Close valve SI-1-8880, 5.1 Positions valve control switch for accumulator nitrogen fill header SI-1-8880 to CLOSE. **
isolation.
Step was: Sat: ______ Unsat _______
- 6. Open valve SI-1-8875A, 6.1 Reviews CAUTION prior to accumulator 11 fill and vent opening valve.
isolation.
6.2 Positions valve control switch for SI-1-8875A to OPEN. **
Step was: Sat: ______ Unsat _______
accumulator. 7.2 Manipulates (rotates partially CW) potentiometer to OPEN valve HCV-943 until accumulator 1-1 pressure decreases to approximately 625 psig and PK02-05 CLEARS (critical substep met if high pressure alarm cleared). **
NOTE: Examinee may close HCV-943 first (prior to closing 8875A);
closing either valve in time to prevent a low pressure alarm is the intent.
Step was: Sat: ______ Unsat _______
- 8. Close valve SI-1-8875A, 8.1 Positions valve control switch for accumulator 11 fill and vent SI-1-8875A to CLOSE. **
isolation.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
9.1 Manipulates (rotates fully CCW) the potentiometer to CLOSE valve HCV-943. **
Step was: Sat: ______ Unsat _______
- 10. Open valve SI-1-8880, 10.1 Positions valve control switch for accumulator nitrogen fill header SI-1-8880 to OPEN.
isolation.
Step was: Sat: ______ Unsat _______
- 11. Monitor accumulator pressure. 11.1 Determines no other accumulators need to be vented.
11.2 Verifies that PK02-05 is no longer in alarm (may have done this when venting.
11.3 Reads NOTE prior to step 2.2.3.
11.4 Continue to monitor accumulator pressure.
Cue: Pressure has remained constant for 20 minutes.
Cue: The SFM will have other operators continue monitoring accumulator pressure and any required troubleshooting.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
Enter drill file 1009 or manually insert the following:
Command Description
- 1. delm psisacc (1) Removes point from monitor screen
- 2. monv psisacc (1) Monitors accumulator 11 pressure
- 3. set psisacc (1) = 665 Increases accumulator 11 pressure to 650 psig
- 4. run 10 Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-S2
Title:
PARALLEL DG 1-2 TO STARTUP POWER Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (modified from LJC-087)
Note: This JPM is designed to be performed in // with the S1 JPM.
References:
OP J-6B:V, Diesel Generator 12, Manual Operations, Rev. 31 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 20 minutes (average validation time ___ min)
Critical Steps: 3, 5, 7, 8, 9 Job Designation: RO/SRO Rev Comments/TIPs: Minor updates following validation DCPP Task # / Rating: 941200 4.0 Gen KA # / Rating: 064.A4.06 3.9 / 3.9 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: None - a partial OP J-6B:V may be provided if available (otherwise, provide the entire procedure)
Initial Conditions: Given:
- Unit 1 is at 100%.
- Diesel Generator 1-2 is supplying 4kV bus G in the Auto Mode.
- Both Auxiliary and Startup power are available, and stable.
Initiating Cue: You are directed by the Shift Foreman to parallel Diesel Generator 1-2 with Startup power, per OP J-6B:V, section 6.4.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: DG 1-2 is paralled to Startup power, in accordance with OP J-6B:V, section 6.4.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Obtain the correct procedure. 1.1 References OP J-6B:V, Step 6.4.
Step was: Sat: ______ Unsat _______
- 2. Check auxiliary power available. 2.1 Reads NOTE 2.2 Checks breaker 52-HG-14 available.
2.3 Checks white potential light ON.
Step was: Sat: ______ Unsat _______
- 3. Prepare the diesel generator for 3.1 Reads CAUTION.
parallel to aux power.
3.2 Places Mode Selector Switch to MANUAL. **
3.3 Adjusts Man Speed Control switch to obtain frequency of 60 Hz, as necessary.
3.4 Places Bus G Xfer to S/U PWR C/O switch to CUT-OUT. **
3.5 Verifies that Bus G Auto Xfer indicating light (blue light) is off.
3.6 Verifies generator protective relays CUT-IN.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Verify 4kV bus G at 60 Hz. 4.1 Verifies 60 Hz indicated on Bus G frequency indication.
4.2 Adjusts Man Speed Control switch to obtain 60 Hz, as necessary.
Step was: Sat: ______ Unsat _______
- 5. Cuts in the Startup Feeder Sync 5.1 Inserts Sync key into Startup Feeder Switch (52-HG-14). Breaker switch. **
5.2 Turns key to ON position. **
Step was: Sat: ______ Unsat _______
- 6. Verify proper operation of the NOTE: If the sync scope is not moving, Synchroscope. the examinee may "bump" the speed control to check the following.
6.1 Observes light out at the 12 oclock position.
6.2 Observes lights full bright at 6 oclock position.
Step was: Sat: ______ Unsat _______
- 7. Adjust diesel generator 12 speed. 7.1 Adjusts Man Speed Control switch to obtain synchroscope turning slowly in the counterclockwise (SLOW) direction. **
NOTE: This is identified as NORMAL in the procedure.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 8. Adjust diesel generator voltage. 8.1 Adjusts Man/Auto Volt Control switch to match diesel voltage, w/in 2 volts, to the incoming auxiliary power voltage, as necessary.**
Step was: Sat: ______ Unsat _______
- 9. Close Startup Feeder Bkr. 9.1 When Synchroscope is slightly (52-HG-14) to parallel the DG to before 12 oclock (counter clockwise startup power. direction), CLOSES 52-HG-14. **
9.2 Verifies breaker 52-HG-14 is closed.
9.3 Observes VARS-OUT.
9.4 Turns S/U FDR SYNC SW OFF.
Cue: Another operator will monitor DG 1-2 operation, and separate/secure the diesel once parallel operations are completed.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-510 (100%, MOL).
There is no drill for this JPM Go to RUN on the simulator.
Perform the following:
- 1. Place diesel generator 12 Mode Select switch in MANUAL.
- 2. Start diesel generator 12.
- 3. Parallel to bus G and pick up 0.5 MW Load.
- 4. Open Aux Transformer Breaker for bus G.
- 5. Place diesel generator 12 Mode Select switch in AUTO.
- 6. CUT-IN protective relays.
Go to FREEZE on the simulator.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-S3
Title:
ESTABLISH EMERGENCY BORATION Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (modified from LJC-063)
Note: This JPM is designed to be performed in series with the S4 JPM.
(both JPMs relatively short, and similar setups; do S3 first, then S4)
References:
OP AP-6, Emergency Boration, Rev. 19 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes (average validation time ___ min)
Critical Steps: 3, 4, 6, 7 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1: corrected typos and one repeated substep on step 4 DCPP Task # / Rating: 64200 4.1 Gen KA # / Rating: 024.AA1.03 3.5 / 3.3 AUTHOR: JOHN F. BUCKLEY DATE:
REV 1
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: None.
Initial Conditions: Given:
- Unit 1 tripped from low power about 10 minutes ago.
- The plant is now stable in MODE 3, and is proceeding through EOP E-0.1, Reactor Trip Response.
- (3) control rods did not fully insert during the reactor trip response.
- The crew is currently at step 3 of EOP E-0.1, and implementation of OP AP-6, Emergency Boration, is required due to the stuck rods.
Initiating Cue: The Shift Foreman directs you to commence emergency borate in accordance with OP AP-6, Emergency Boration, while the crew continues with EOP E-0.1.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Emergency boration has been established from the CVCS makeup controller, per OP AP-6 (> 30 gpm flow rate, and target of > 2700 gallons of boric acid). Completion of the boration is NOT required.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Obtain the correct procedure. 1.1 References OP AP-6.
1.2 Reads NOTES prior to Step 1.
Step was: Sat: ______ Unsat _______
- 2. Verifies charging in service. 2.1 Verifies charging in service (using one or more of the following):
- Traces charging lineup on VB-2
- Notes normal charging flow on CC2 (charging flow meter)
Step was: Sat: ______ Unsat _______
- 3. Places VCT makeup control in 3.1 PRESSES STOP on makeup BORATE mode. controller. **
3.2 Notes "AUTO-STOPPED" and change in screen color, confirming that auto makeup has stopped.
3.3 PRESSES BORATE on makeup controller. **
3.4 Notes "BORATE" mode lights up, and/or "BORATE STOPPED" at top of screen (screen options also change).
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Sets TARGET BATCH for 4.1 Determines amount of boric acid emergency boration. required per Appendix A, item #2: (3 stuck rods) x (900 galllons boric acid per rod) = 2700 gallons boric acid. **
4.2 Determines amount of boric acid required per Appendix A.
4.3 PRESSES TARGET BATCH window (pop-up window appears). **
4.4 ENTERS "2700" in pop-up window, and PRESSES ENTER. **
4.5 Verifies "2700" in "TARGET BATCH" window.
Step was: Sat: ______ Unsat _______
- 5. Resets BATCHED GALLONS. NOTE: The BATCHED GALLONS is normally at zero (as in this case), and verifying (or resetting) are both adequate for this step.
5.1 May PRESS BATCHED gallons window, and notes pop-up window.
5.2 May PRESS RESET on pop-up window (window disappears).
5.3 Verifies "0.0" in BATCHED GALLONS window.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 6. Sets BORIC ACID FLOW SP. 6.1 PRESSES BORIC ACID FLOW SP window . ** (and notes pop-up window).
NOTE: Normally, a number between 30 and 35 or so will be entered (higher numbers aren't achieveable).
6.2 ENTERS a number > 30, and presses ENTER. ** (pop-up disappears) 6.3 Verifies > "30.0" in BORIC ACID FLOW SP window.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 7. Commences Emergency Boration. 7.1 Presses START to start emergency boration. **
7.2 Notes one or more of the following, indicating that boration has started:
- Screen color change
- BORATE BATCHING at top of screen
- BATCHED GALLONS and BORIC ACID FLOW windows both counting / coming up to flow rate 7.3 Verifies boric acid flow rate is > 30 gpm (M/U controller/CC2 flow recorder/VB2 meter).
NOTE: Completion of the entire emergency boration is not required for this task. Once the examiner has completed his/her observations of the proper start of the emergency boration, the JPM may be ended with the following cue.
Cue: Another operator will monitor and complete this emergency boration.
Step was: Sat: ______ Unsat _______*
[ ] Comment # (required for Unsat)
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-514 (HSB, 550°F, MOL).
This JPM is meant to be performed in concert with JPM NRCL111-S4 (emergency control room evacuation). The two JPMs shall NOT be performed at the same time (too close in proximity, and need slightly different setups). They are short enough that they can (and should) be performed one after the other. This JPM should always be performed FIRST, and the S4 JPM done right after this JPM (after it's setup is complete).
Enter drill file 9201, or manually insert the following:
Command Description ovr xv3i224c act,1,0,0,d,10 Starts CB Pp set 1-2 (for S4 JPM) mal rod4a act 2,j11,0,d,0 Sticks 3 rods (j11,G5,L7) for mal rod4b act 2,g5,0,d,0 emergency boration task mal rod4c act 2,l7,0,d,0 ovr xc1i072t act,1,0,5,d,2 Trips reactor to set up HSB and E-0.1 conditions needed for task run 15 Runs for 15 sec.
anack Acknowledges alarms Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-S4
Title:
PERFORM CONTROL ROOM ACTIONS PRIOR TO EVACUATION Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (from LJC-021)
Note: This JPM is designed to be performed in series with the S3 JPM.
(both JPMs relatively short, and similar setups; do S3 first, then S4)
References:
U-1 OP AP-8A, Control Room Inaccessibility - Establishing Hot Stby, Rev. 30 OP1.ID2, TCOAs, Rev 4 (& TCOA database); TCOA item 63 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 15 minutes (average validated time ___ min) (OCT ave time 8.1 min)
Critical Steps: 6, 7, 8, 9, 10, 11 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1: corrected typos, minor updates DCPP Task # / Rating: 805200 4.2 Gen KA # / Rating: 068.AA1.11/21 3.9 / 4.1 (for both)
AUTHOR: GARY HUTCHISON DATE:
REV. 1
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: None.
Initial Conditions: Given:
- Unit 1 was at low power, when a fire was reported in the Cable Spreading Room
- Unit 1 tripped, and is now stable in hot standby (HSB), with the crew working their way through EOP E-0.1.
- The Fire Brigade has responded to the fire.
- Smoke is now present in the Control Room, and the Shift Manager has directed that the Control Room be evacuated.
- Conditions in the control room are not yet extreme. "Immediate" evacuation is NOT required.
Initiating Cue: The Shift Foreman directs you to perform the actions required in OP AP-8A prior to evacuation of the control room.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: The Control Room actions for OP AP-8A have been performed.
Time Critical This JPM was evaluated against TCOA # 63, "Trip RCPs W/I 10 Operator Action minutes".
(TCOA): This TCOA:
- is not applicable to this JPM, because the RCPs are successfully tripped from the Control Room, and the TCOA is based on local tripping of the RCPs.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Obtain the correct procedure. 1.1 References OP AP-8A.
Step was: Sat: ______ Unsat _______
- 2. Verifies reactor trip. 2.1 Reads Note.
2.2 May trip reactor using the reactor trip switch (already done).
2.3 Checks reactor trip and bypass breakers open.
2.4 Checks rod bottom lights ON.
2.5 Checks reactor power decreasing.
Step was: Sat: ______ Unsat _______
- 3. Determine immediate evacuation 3.1 Reads CAUTION.
is not required.
3.2 Determines immediate evacuation is not required.
Cue: Immediate evacuation is not required.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Verify turbine tripped. 4.1 Checks all 4 stop valves closed.
Step was: Sat: ______ Unsat _______
- 5. Manually initiate a unit trip and 5.1 Trips the Unit using the unit trip verify bus transfers. switch.**
5.2 Verifies all 4kV and 12kV buses transfer to startup power.
5.3 Verifies all vital 4kV buses are energized.
Step was: Sat: ______ Unsat _______
valves.
6.2 Verifies MSIVs are closed.
6.3 Checks all bypass valves closed.
Step was: Sat: ______ Unsat _______
- 7. Transfer charging suction to the 7.1 Reads Note.
RWST. 7.2 Opens 8805A OR 8805B (OK to open both). **
7.3 Verifies valve(s) are open.
NOTE: Step 7.4 is NOT critical if VCT pressure is less than 28 psig.
7.4 Closes LCV-112B or 112C. (OK to close both) **
7.5 Verifies valve(s) closed.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 8. Trip all reactor coolant pumps. 8.1 Trips ALL reactor coolant pumps. **
8.2 Verifies pumps tripped.
Step was: Sat: ______ Unsat _______
- 9. Isolates letdown 9.1 Verify CLOSED 8149A, 8149B.
9.2 CLOSES 8149C **
Step was: Sat: ______ Unsat _______
10.2 Verifies relays reset.
Step was: Sat: ______ Unsat _______
- 11. Shutdown all but one running 11.1 Verifies MAN/AUTO selector condensate/booster pump sets. switch in MAN for pump set(s) to be secured.
11.2 Stops all but one condensate/booster pump set. **
11.3 Verifies pump(s) shutdown.
Step was: Sat: ______ Unsat _______
- 12. Open or check open RCS hot leg 12.1 Verifies open NSS-9356A and and pressurizer liquid space 9356B.
sample valves.
12.2 Verifies open NSS-9355A and 9355B.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 13. Collect equipment needed from 13.1 Collects the fire brigade, security the control room. key rings, and radios.
Cue: The Shift Foreman will transport the Fire Brigade, security key rings, and radios to the hot shutdown panel.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED ATTACHMENT 1, SIMULATOR SETUP This JPM is meant to be performed in concert with JPM NRCL111-S3 (emergency borate - normal means). The two JPMs shall NOT be performed at the same time (too close in proximity, and need slightly different setups). They are short enough that they can (and should) be performed one after the other. This JPM should always be performed AFTER the S3 JPM (and assumes the S3 setup has already been done).
Verify NRC L111 S3 JPM setup complete, or S3 JPM completed (IC-514, and Drill 9201, if not doing the S3 JPM)
Go to STOP on the makeup control system, and place it back in AUTO.
Clear the (3) stuck rod malfunctions (from S3 JPM) (mal rod4a, 4b 4c clr)
Activate cardox alarm for CSR: loa fir1 act,1,0,0,d,0 Acknowledge alarms.
NOTE: an IC can be created at this point, to shorten setups for multiple JPMs, if desired Go to FRZ, and inform the examiner that the setup is complete.
Go to RUN when the examinee is given the cue sheet.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-S5
Title:
TERMINATE HIGH-HEAD ECCS AFTER A SAFETY INJECTION Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments:
References:
U-1 EOP E-1.1, SI Termination, Rev 27 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: ___ min (average validation time ___ min)
Critical Steps: 1, 2, 3, 4, 5, 6 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1: corrected typos, minor change to cue DCPP Task # / Rating: 888400 4.0 Gen KA # / Rating: 013.A4.02 4.3 / 4.4 AUTHOR: GARY HUTCHISON DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The student will be given the initial conditions and initiating cue. The task standard will NOT be read to the student. The examiner will then ask if any clarifications are needed. After identifying the appropriate procedure for the task, the examinee may be given the procedure and told the step with which to begin.
Required Materials: None Initial Conditions: Given:
- Unit 1 was operating at low power, when an RCS leak developed.
- OP AP-1 for RCS Leakage was entered, and the leakrate required the initiation of a Safety Injection.
- The crew has completed EOP E-0; EOP E-1 progressed to step 7, where SI Termination Criteria was checked, and met.
- Transition was made to EOP E-1.1, SI Termination. The procedure transition brief has just been completed.
Initiating Cue: The SFM directs you to perform actions in EOP E-1.1, starting at step 1 of E-1.1.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: High-head ECCS is secured, normal charging established, and then high head ECCS reestablished (after evaluating Pzr Level), per steps 1-6 of EOP E-1.1.
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Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. RESET Safety Injection (SI). Note: This task is mostly carried out on VB-1 and VB-2.
1.1 RESETS both trains of Safety Injection (presses both PBs). **
Step was: Sat: ______ Unsat _______
Note: There are 3 of these, just to right of 4KV bus breakers for each vital bus (VB-4). Pressing the PB makes the blue light next to it go OFF, and the alarm (above) to clear.
2.2 Depress Vital 4kV Auto Transfer Relay Resets: Blue Light - OFF (presses PB for each vital bus: F, G, and H; any order). **
Note: There will be two ECCS CCPs running (the 1-3 CCP will already be stopped). One running pump will be stopped. (VB-2) 2.3 STOPS one ECCS CCP (stops either running ECCS CCP). **
Note: This pump was already stopped per EOP E-0, App E.
2.4 VERIFIES 1-3 CCP stopped (already stopped).
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
and/or from numerous PPC screens.
3.1 CHECKS RCS Pressure - Stable or increasing (it is). **
Note: Makes decision to continue to step 4.
Step was: Sat: ______ Unsat _______
- 4. Isolates Charging Injection. Note: (far left end of VB-2) May be done in any order. Closing "either" set of valves satisfies the "critical" portion of the step.
4.1 CLOSES 8803A & B (takes each valve to CLOSE). **
4.2 CLOSES 8801A & B (takes each valve to CLOSE). **
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 5. Established Normal Charging. Note: HCV-142 (charging backpressure) and FCV-128 (charging flow control) are on CC-2. The other header valves are on VB-2.
5.1 CLOSES HCV-142 (dials fully CCW on pot).
5.2 OPENS 8107 and 8108, Norm Chg to Regen Hx Stop Vlvs (takes each valve ctrl to OPEN). **
5.3 VERIFIES 8146 OR 8147 (chrg hdr iso) - OPEN (8146 is already OPEN).
5.4 VERIFIES 8145 AND 8148 (aux spray vlvs) - CLOSED(both already CLOSED).
Note: The following substep is not critical, as the valve will already be partially open, and in Manual.
The examinee may throttle the valve to control flow.
5.5 Throttle open FCV-128 to establish Charging flow (may throttle further by pressing press up or down PBs).
Cue: (use ONLY IF examinee evaluates FOP #3 during step 5 for SI re-initiation criteria prior to going to step 6) Another operator is evaluating the FOP. Continue in E-1.1.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step.
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Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
6.1 CHECKS Pzr Level, 17% to 60%
and stable (within range, but level is dropping - NOT stable).
Note: The examinee may perform this next substep, or jump right to the RNO instructions for step 6a (ie, skip charging adjustments, based on current indications).
6.2 May raise charging flow (to try to stabilize level), using FCV-128 to raise flow, and HCV-142 to set seal flows (can achieve 8-13 gpm on seal flows, but Pzr Level will continue to drop).
Note: Step 6A RNO instructions will now be implemented. First IF/THEN statement will evaluate if any faulted S/Gs are present (they are NOT) 6.3 Determines that there are NO faulted S/Gs (checks pressure on VB-3 or any PPC terminal).
(continued on next page)
- Denotes a Critical Step.
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Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 6. (con't) Note: 2nd IF/THEN statement is applicable (no faulted S/Gs), so following actions are taken.
Note: One of each of the following two sets of valves must be opened to satisfy the critical step (// paths).
6.5 OPENS 8803A and B (each switch taken to OPEN). **
6.6 OPENS 8801A and B (each switch taken to OPEN). **
Note: Only one of the following valves must be closed to satisfy the critical substep.
6.7 CLOSES 8107 and 8108 (each switch taken to CLOSE). **
Note: The following step is optional, but may be performed due to foldout page instructions (FOP #3).
6.8 May restart ECCS CCP previously secured.
6.9 Transitions to EOP E-1.2.
Cue: Other operators will continue with performance of EOP E-1.2.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step.
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Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED ATTACHMENT 1, SIMULATOR SETUP Initialize the simulator to IC-514 (100%, MOL, HSB for S/U).
Enter drill file 9202 or manually insert the following:
Command Description ovr xc2i016m act,1,0,0,d,2 FCV-128 to manual, for seals/etc mal rcs3b act 0.2,1,0,d,0 RCS leak (to cause need for SI) ovr xc2i030c act,1,0,0,d,3 Manual SI ovr xv1i158o act,1,0,40,d,0 Opens FCV-603 and FCV-431 (per E-0) ovr xv1i160o act,1,0,40,d,0 ovr xv2i266o act,1,0,40,d,10 Stops CCP 1-3 (per App E) ovr xv4i388c act,1,0,40,d,0 Aux Bldg charcoal filter preheater ON (per App E) mal rcs3c act,0.15,10,0,c,xv2i248o,0 Adjust RCS leakage so that all examinees will get consistent indications of Pzr level dropping at step 6 of E-1.1 (conditional on 8108 opening) run 120 Runs sim for 2 min, then FRZ Perform the following:
- 1. Place FCV-603 and FCV-431 in OPEN position.
- 2. Place LCV-12 in CTRL Only (optional) Create IC at this point, to minimize multiple setups (if desired)
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-S6
Title:
INITIATE BLEED AND FEED FOR A LOSS OF HEAT SINK Examinee:
Evaluator:
Print Signature Date Testing Method: Perform X Simulate Results: Sat Unsat Total Time: minutes Comments: (from LJC-122)
References:
U-1 EOP FR-H.1, Response to Loss of Secondary Heat Sink, Rev 27 OP1.ID2, TCOAs, Rev 4 (& TCOA database); TCOA item 33 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 minutes (average validation time ___ min) (OCT ave time 10.1 min)
Critical Steps: 2, 9 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1: corrected typos, minor updates DCPP Task # / Rating: 196800, 889200, 317800, 875800, 169600 3.3 / 3.5 / 3.3 / 3.7 / 3.0 Gen KA # / Rating: E05.EA1.1 4.1 / 4.0 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. If the task is being done in the plant or lab, and after identifying the appropriate procedure for the task, the examinee may be given the procedure and told what step to begin the task at.
Required Materials: None.
Initial Conditions: Given:
- Unit 1 experienced a loss of secondary heat sink.
Initiating Cue: At least 3 steam generator wide range levels are less than 18% and the SFM directs you to establish and verify RCS bleed and feed per EOP FR-H.1, FOP Item #5.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: RCS bleed and feed has been established and verified as required by EOP FR-H.1, steps 12-18.
Time Critical This JPM was evaluated against TCOA # 33, "Initiate Feed and Bleed Operator Action Cooling within 2500 seconds".
(TCOA): This TCOA:
- is not applicable to this JPM because (per the TCOA database), it does not meet the definition of a TCOA, and is not part of the licensing bases.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Obtain the correct procedure. 1.1 References EOP FR-H.1.
1.2 Reads CAUTION prior to Step 12.
Step was: Sat: ______ Unsat _______
- 2. Actuate Safety Injection. 2.1 Positions the SAFETY INJECTION ACTUATE switch on CC-2 or VB-1 to ACTUATE. **
2.2 Verifies that SI is actuated by observing PK08-21 ON and/or SI Monitor Light Box red status light ON.
Step was: Sat: ______ Unsat _______
3.2 Observes that ECCS valves are in their proper emergency alignment on the VB1 and VB2 mimic (may also use Monitor Light Box status lights).
Step was: Sat: ______ Unsat _______
4.1 Depresses the SAFETY INJECTION RESET TRAIN A and TRAIN B pushbuttons.
4.2 Verifies that SI is reset by observing PK08-22 ON and/or SI Monitor Box red status light OFF.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 5. Reset Containment Isolation 5.1 Depresses the CONTMT ISOL Phase A and Phase B. PHASE A RESET pushbuttons.
5.2 Verifies Phase A red lights are OFF or PK02-01 is OFF.
5.3 Observes that Phase B is NOT actuated, or depresses the Phase B RESET pushbuttons.
Step was: Sat: ______ Unsat _______
- 6. Establish instrument air to 6.1 Opens FCV-584.
containment.
6.2 Verifies that FCV-584 has opened.
6.3 Observes that instrument air header pressure is > 90 psig on PI-380.
Step was: Sat: ______ Unsat _______
8000A 8000B 8000C 7.2 Attempts to opens all PORVs by taking switches to the OPEN position.
PCV-474 PCV-455C PCV-456 Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 8. Verify PZR PORVs and 8.1 Diagnoses that at least two PORVs associated block valves - at least have NOT opened.
two open.
Step was: Sat: ______ Unsat _______
- 9. Open reactor vessel head vents. 9.1 Opens reactor vessel head vents:
8078A & D (PAM 1) 8078A & 8078D. **
8078B & C (PAM 1) 8078B & 8078C. **
9.2 Verifies 8078A, B, C, & D have opened.
Cue: Other operators will continue with the FR-H.1 procedure steps.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED ATTACHMENT 1, SIMULATOR SETUP INIT to IC 716. (ONLY IF no IC available, you can create conditions as follows; DON'T use if IC 716 works):
- IC-510, then run drill 1053
- When drill complete, use 10%ers to B/D 3 S/Gs to < 18% (use max chrg during depress)
- 10%ers to normal and FRZ once stable (takes about 20 min)
This SNAP allows entry into EOP FR-H.1 at Step 12. Three (3) steam generator wide range levels are < 18% and steam generator 10% steam dumps are in AUTO at 8.38 turns.
Enter drill file 1122 or manually insert the following:
Command Description vlv pzr4 1,0,0,0,d,0 #rrcp455c PCV-455c fails as is.
vlv pzr5 1,0,0,0,d,0 #rrcp456 PCV-456 fails as is vlv pzr6 1,0,0,0,d,0 #rrcp474 PCV-474 fails as is Perform the following:
- 1. Display the E-0 screen on SPDS panel A.
- 2. Display the CSF-3 screen on SPDS panel B.
Inform the examiner that the simulator setup is complete.
Go to RUN when the examinee is given the cue sheet.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-C1
Title:
RESPOND TO RHR LEAKAGE INTO THE PRT Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate X Results: Sat Unsat Total Time: minutes Comments:
NOTE: THIS JPM MAY BE PERFORMED ON EITHER UNIT.
NOTE: THIS JPM IS INTENDED TO BE SIMULATED IN THE C/R.
References:
U-1 & U-2, OP AP-16, Malfunction of the RHR System, Rev 13A Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 15 min (average validation time ___ min)
Critical Steps: 4 Job Designation: RO/SRO Rev Comments/TIPs: Minor updates following validation DCPP Task # / Rating: 39800 4.0 Gen KA # / Rating: 025.AA1.03 3.4 / 3.3 AUTHOR: GARY HUTCHISON DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT JPM Number: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.
Note: Clearly state the Unit for performance during the initial conditions and cue, below. A procedure is attached for each unit (use the correct procedure for the unit selected).
Required Materials: OP AP-16, Unit 1 & 2 Initial Conditions: Given:
- Unit 1 / Unit 2 (specify) is in Mode 4, cooling down to Mode 5 for a normal refueling outage.
- RHR cooling is in service (both pumps and both HXs), with RHR letdown in service. RHR flows are 1600-1700 gpm on each HX.
- RCS temperature is 302°F, and slowly lowering (slow cooldown in progress)
- RCS Pressure is 325 psig and stable (pressure band is 300-350 psig).
- The BOPCO has just reported to the SFM that both PRT level and pressure are slowly rising. The Aux Bldg Watch has been dispatched to walk down the RHR system, and report back to the Control Room.
Initiating Cue: The SFM directs you to perform OP AP-16 to respond to the leakage into the PRT, starting at step 1.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Both RHR pumps have been stopped, and the RHR system isolated from the RCS, per steps 1-4 of OP AP-16.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Check RHR pump status (step 1). Note: Most of the indications and controls for this JPM are located on VB-1 and VB-2. The examinee may also reference plant parameters from the PPC for some indications Note: Pump indications on the lower "skirt" area on the right hand side of VB-1. The ammeters are on the vertical section just above the pumps.
1.1 Verifies an RHR pump is running (they both are).
Cue: (for both pumps) The Red light is ON, Green light OFF, pumps amps are 40-42 and stable.
Note: These indications are just above the pumps on the vertical section on the right side of VB-2). The examinee may also refer to several PPC plots or displays (with the same cue below).
(continued on next page)
- Denotes a Critical Step or substep.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 1. (con't) 1.2 Verifies RHR flow indicated on FI-970/971.
Cue: Both meters read 1600-1700 gpm each on FI-970B and FI-971B (FI-970A and FI-971A both pegged high).
Note: The two supply valves are on the "skirt" at the left end of VB-1; the CCW flow meters are on the left vertical section of VB-1 (just to right of the ASW system).
CCW header A & B flows are 4000-5000 gpm higher than normal with RHR HXs in service.
1.3 VERIFIES CCW to the RHR Heat Exchangers.
Cue: (if checked) FCV-364 and FCV-365 are Red Light ON, Green Light OFF.
Cue: (if checked) CCW header flows are 8200 gpm (FI-68 for hdr A),
11,000 gpm (FI-48, hdr B), and 3400 (FI-46, hdr C).
Note: The examinee should proceed to step 2.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step or substep.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 2. Starts an alternate means of heat Note: The examinee should find the removal, if required (it is NOT) RHR still in service and move to (step 2). the next step after the first substep.
2.1 (observes CAUTION prior to step)
Checks RHR not in operation (IT IS), goes to RNO instructions, and goes to step 3)
Note: The examinee should conclude that RHR IS in operation, and go to step 3 (per the RNO instructions for step 2A). If the examinee rechecks pumps or flows again, the cues from step 1 may be repeated here.
Note: The following cues are ONLY if the examinee attempts to complete step 2 (vs going on to step 3, above). This will move the examinee on to step 3.
Cue: (for step 2b) (VB-2 vertical section) RCPs #2 and #4 (#1 and
Cue: (for step 2c) Another operator has been assigned to control RCS temperature, using steam dumps.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step or substep.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 3. CHECKS For Indication of Note: The following indications will Leakage From the RHR System show leakage from the RHR (step 3) (there IS leakage). system (to the PRT); the examinee should go to step 4 from the step 3A RNO instructions.
3.1 Checks NO indications of leakage from the RHR system (see symptoms) (there ARE indications);
determines that leak exists, and goes to step 4 per step 3A RNO instructions.
Cue: (once checked) (all of these may be checked on the PPC as well)
- PRT (VB2, vertical, right): level is 90%, and still rising
- PRT: pressure is 3.7 psig and rising slowly
- Pzr level (VB-2, same area, or CC2 right side): 33.2%, and dropping slowly
- Pzr Pressure (VB2, same area): 325 psig and stable, being maintained with additional heater operation Step was: Sat: ______ Unsat _______
- Denotes a Critical Step or substep.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
4.1 (reads NOTE prior to step)
Confirms that PRT level is still rising; goes to step 4A RNO instructions.
Note: The examinee may go to the RNO instructions based on previous data, or may confirm PRT level rising again prior taking those actions.
Cue: (if PRT level checked again)
- PRT (VB2, vertical, right): level is 90.7%, and still rising
- PRT: pressure is 3.9 psig and rising slowly
- Pzr level (VB-2, same area, or CC2 right side): 33.0%, and dropping slowly
- Pzr Pressure (VB2, same area): 325 psig and stable 4.2 STOPS both RHR pumps. **
Cue: (for each pump) amps are zero, the Red light is OFF, Green light ON, and FI-970/971 flows are all bottom of scale.
Note: If operator mentions that step 2 was a continuous action step, Cue him/her that another operator will perform step 2
- Denotes a Critical Step or substep.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET
- Denotes a Critical Step or substep.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
4.3 CLOSES RHR Letdown to CVCS, HCV-133. **
Cue: The pot rotated several turns CCW, and now reads zero (won't turn any more).
Note: These are both located at the far left end of the VB-2 "skirt". The switches are normal, two-position valve controls 4.4 CLOSES RHR Loop 4 Suction Isolation Valves, 8701 and 8702. **
Cue: (prior to operation) Lamicoids on both valves indicate breakers are racked in for both valves.
Cue: (for each valve, once switch taken to CLOSE) The Green light is ON; after (stroke) time, the Red light is OFF .
(continued on next page)
- Denotes a Critical Step or substep.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. (con't) Note: The next substep directs the operator to additional diagnostic and action steps, not part of this task.
4.5 The operator is directed to step 13.
Cue: Other operators will continue with OP AP-16 actions.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step or substep.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET CAUTION: No plant controls or equipment are to be operated during the performance of this JPM. Controls may be pointed at, but are not to be touched.
Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-C2
Title:
CHECK IF CONTAINMENT SPRAY SHOULD BE STOPPED Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate X Results: Sat Unsat Total Time: minutes Comments:
NOTE: THIS JPM MAY BE PERFORMED ON EITHER UNIT.
NOTE: THIS JPM IS INTENDED TO BE SIMULATED IN THE C/R.
References:
U-1 EOP E-1, Loss of Reactor or Secondary Coolant, Rev 32 U-2 EOP E-1, Loss of Reactor or Secondary Coolant, Rev 23 Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: ___ min (average validated time ___ min)
Critical Steps: 4, 5 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1: corrected typos, minor updates DCPP Task # / Rating: 849200 3.7 Gen KA # / Rating: 026.A4.01 4.5 / 4.3 AUTHOR: GARY HUTCHISON DATE:
REV. 1
Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.
Note: Clearly state the Unit for performance during the initial conditions and cue, below. A procedure is attached for each unit (use the correct procedure for the unit selected).
Required Materials: U-1 or U-2 EOP E-1, Loss of Reactor or Secondary Coolant (pg 6 / step 6 is adequate)
Initial Conditions: Given:
- A steam break occurred inside containment on Unit 1 / Unit 2 (specify)
- The steam break caused the following actuations:
o Safety Injection/Reactor Trip o Main Steamline Isolation o Containment Spray Actuation
- Both trains of Containment Spray are currently in service, with Containment pressure 7 psig and dropping slowly.
- The crew has progressed in the EOPs through EOP E-0, and are now up to step 6 of EOP E-1 Initiating Cue: The SFM directs you to check if containment spray should be stopped, by performing step 6 of EOP E-1.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: The Containment Spray system is secured, per EOP E-1, step 6.
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Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Check PK01-18 CONTAINMENT Note: This is a note.
SPRAY ACTUATION - ON.
1.1 CHECKS PK01-18, Containment Spray Actuation ON (it is).
Cue: PK01-18 is LIT. (if checked; not required) the RED lights for the Containment Isolation Phase B and Main Steam Isolation (Monitor Light Box D) are LIT.
Note: Continues on to step 6b.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step or substep.
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Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 2. Check Containment Radiation Note: The alarms are located above the Levels (normal). right side of VB-3, and the RM-2
& 7 are behind the control boards (Westinghouse RMs near the NIs); RM-30/31 are on PAM2 (also behind the boards). Rad monitors can also be accessed on the PPC.
2.1 CHECKS PK11-21, HIGH RADIATION - OFF (it is OFF).
Cue: PK11-21 is not LIT.
2.2 CHECKS RE-2/RE-7-NORMAL (they are).
Cue: (at monitor or PPC) (for each monitor) The radiation monitor is reading lower than the at-power reading, and stable.
2.3 CHECKS PK11-19, CONTMT RADIATION - OFF.
Cue: PK11-19 is not LIT.
(continued on next page)
- Denotes a Critical Step or substep.
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Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 2. (con't) 2.4 CHECKS R-30/R-31-NORMAL (PAM 2) (they are).
Cue: (at monitor or PPC) (for each monitor) The radiation monitor is reading lower than the at-power reading, and stable.
Note: Continues on to step 6c.
Step was: Sat: ______ Unsat _______
- 3. Check Containment Pressure - Note: Containment pressures are LESS THAN 20 PSIG. located on the vertical potion of VB-1, left side (also available on the PPC). One or more channels may be checked.
3.1 CHECKS containment pressure(s),
< 20 psig (it is).
Cue: (for each channel checked)
Pressure is reading 5.5 psig, and dropping slowly.
Note: Continues on to step 6d.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step or substep.
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Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Resets Containment Spray Trains Note: These are in the same area on A and B. VB-1, vertical panel, left of center. They are pushbutton controls. These two substeps may be done in any order (or at the same time).
4.1 RESETS Containment Spray, Train A (PB depressed). **
Note: There are no ESF red status lights for each train of containment spray, so a cue is only appropriate once "both" pushbuttons have been depressed.
4.2 RESETS Containment Spray, Train B (PB depressed). **
Cue: PK01-18 is not LIT (RED alarm window cleared)
Note: Continues on to step 6e-6h.
Step was: Sat: ______ Unsat _______
- Denotes a Critical Step or substep.
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Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 5. Secures Containment Spray Note: These controls are all below the System. containment pressure meters on VB-1 (on the skirt area, to the right of the ASW/CCW systems).
5.1 STOPS both Containment Spray Pps (control switch taken to STOP of each pump). **
Cue: (for each pump, if checked):
- The pump Red Light is OFF, and the Green Light is ON
- Pump amps are zero (only if checked)
- Spray Additive Tank Flow is zero (only if checked)
- Spray flow (on PAMS panel) is zero (only if checked)
Note: These are the spray header isolation valves, about a foot above the spray pump controls.
5.2 CLOSES 9001A & B (each switch taken to close). **
Cue: (for each valve) The Green Light is ON; after a few seconds (stroke time), the Red Light is OFF.
- Denotes a Critical Step or substep.
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Title:
DETERMINE IF ROD INSERTION LIMIT (RIL) JPM Number: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 5. (con't) Note: These are the RHR to containment spray valves, and have not repositioned due to the actuation (require only verification). They are just above and outside of the pump controls.
5.3 VERIFIES closed 9003A & B.
Cue: These valves are AS-SEEN (Red light OFF, Green Light ON).
Note: These are the spray additive tank outlet valves (above the pumps, below the spray tank mimic).
5.4 CLOSES 8994A & B (each switch taken to CLOSE). **
Cue: (for each valve) The Green Light is ON; after a few seconds (stroke time), the Red Light is OFF.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes a Critical Step or substep.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET CAUTION: No plant controls or equipment are to be operated during the performance of this JPM. Controls may be pointed at, but are not to be touched.
Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
o Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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NUCLEAR POWER GENERATION DIABLO CANYON POWER PLANT JOB PERFORMANCE MEASURE Number: NRCL111-P1
Title:
PERFORM A LOCAL START OF DG 1-2 (2-1)
Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate X Results: Sat Unsat Total Time: minutes Comments: (modified from LJP-038)
NOTE: THIS JPM MAY BE PERFORMED ON EITHER UNIT.
References:
OP AP-8A, Control Room Inaccessibility, Establishing HSB, Rev. 30 (U1)
OP AP-8A, Control Room Inaccessibility, Establishing HSB, Rev. 23A (U2)
Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 25 minutes (average validation time _____ min) (OCT - 12.6 min ave)
Critical Steps: 1, 2, 3, 4, 5, 6, 8, 9, 10 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1: corrected typos, updated labels on some steps DCPP Task # / Rating: 589400 4.2 Gen KA # / Rating: 064.A4.01 4.0 / 4.3 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-P1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.
Note: Clearly state the Unit for performance during the initial conditions and cue, below. A procedure is attached for each unit (use the correct procedure for the unit selected).
Required Materials: Copy of OP AP-8A (Unit 1, or Unit 2), Attachment 6.3 Initial Conditions: Given:
- A fire in the vertical boards has required an evacuation of the control room.
- Unit 1 / Unit 2 (specify) control has been established from the Hot Shutdown Panel.
Initiating Cue: The Shift Foreman directs you to establish local control and start diesel generator 1-2 / 2-1 (specify) to energize 4KV bus G, in accordance with OP AP-8A, Attachment 6.3, step 3.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Diesel Generator 1-2 or 2-1 has been started in accordance with OP AP-8A, Att 6.3, step 3.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-P1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Place the 125 V DC Control 1.1 Reads and observes procedure Power Transfer (EQD-12, for CAUTIONs prior to Step 3.
U-1) (EQD-21, for U-2) in NEUTRAL. 1.2 Locates the 125 V DC Control Power Transfer Switch on the right side of the DG 1-2 (U-1) / DG 2-1 (U-2) DC Cont Pwr Transfer Switch Panel.
1.3 Places the 125V DC Control Power Transfer Switch (EQD-12, U-1) /
(EQD-21, U2) in NEUTRAL/OFF.
Cue: EQD-12 (U-1) / EQD-21 (U-2) is in the NEUTRAL [middle, OFF]
position.
Step was: Sat: ______ Unsat _______
- 2. Place the droop switch on the 2.1 Locates the diesel generator 1-2 (2-1) excitation cubicle to the ISOC droop switch on the excitation mode. cubicle.
2.2 Places the droop switch to the ISOC position.**
Cue: The Droop Switch is in the ISOC position.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-P1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 3. Verify the AUTO/TEST selector 3.1 Locates the Mode Control selector switch on the local control panel switch on the diesel generator 1-2 is in the TEST position. (2-1) local control panel.
3.2 Places the Mode Control selector switch to the TEST position.**
Cue: The Mode Control Switch is in the TEST position.
Step was: Sat: ______ Unsat _______
- 4. Place the diesel generator control 4.1 Locates the diesel generator 1-2 (2-1) selection switch on the excitation control selection switch on the cubicle to the LOCAL position. excitation cubicle.
4.2 Places the diesel generator 1-2 (2-1) control selection switch to the LOCAL position.**
Cue: The Control Selector Switch is in the LOCAL position.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-P1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 5. Place the Appendix R fuse 5.1 Locates the 43DC-12/SS (43DC-selector switch 43DC-12/SS 21/SS) switch on the diesel generator (43DC-21/SS) to the BACKUP 1-2 (2-1) local control panel.
position.
5.2 Places the Appendix R fuse selector switch to the BACKUP position.**
Cue: The Appendix R Switch is in the BACKUP position.
Step was: Sat: ______ Unsat _______
for U-1) (EQD-21, for U-2) in NORMAL.
Cue: The EQD-12 (EQD-21) is in the NORMAL [top] position.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-P1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 7. Depress the alarm relay reset 7.1 Locates the alarm relay reset push push button. button on diesel generator 1-2 (2-1) local control panel.
7.2 Depresses the alarm relay reset push button.
Cue: The Alarm Reset PB depressed and then returned to normal.
Step was: Sat: ______ Unsat _______
- 8. Place the START/STOP switch 8.1 Reads NOTE on the local control panel to the START position. 8.2 Locates the START/STOP switch at the diesel generator 1-2 (2-1) local control panel.
8.3 Places the START/STOP switch to the START position.**
Cue: There was no audible noise level change in the room (the diesel generator did not start).
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-P1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 9. Place the 125VDC Control 9.1 Locates control power transfer switch Power Transfer Switch, EQD-12 EQD-12 (EQD-21) opposite the (EQD-21), in NEUTRAL, wait diesel generator 1-2 (2-1) local for 10 seconds, then Place in control panel.
BACKUP position.
9.2 Places the 125V DC control Power transfer switch (EQD-12, or EQD-21) in NEUTRAL/OFF, waits 10 seconds, then places in BACKUP position.**
Cue: The normal power supply light is OFF and the backup power supply light is ON.
Step was: Sat: ______ Unsat _______
- 10. Restart the diesel generator. 10.1 Locates the Engine Control switch at the diesel generator 1-2 (2-1) local control panel.
10.2 Places the Engine Control switch to the START position. **
Cue: Normal DG startup noise level is heard.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-P1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 11. Notifies the HSDP of DG status. 9.1 Notifies the SFM at the U-1 (U-2)
HSDP of DG status, and asks if 4KV bus voltage is satisfactory.
Cue: The U-1 (U-2) SFM reports that DG 1-2 (2-1) operation and 4KV bus G voltage are satisfactory.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes Critical Step and Sub Steps.
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JPM NUMBER: NRCL111-P1 EXAMINEE CUE SHEET CAUTION: No plant controls or equipment are to be operated during the performance of this JPM. Controls may be pointed at, but are not to be touched.
Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-P2
Title:
OPERATE CONTAINMENT H2 RECOMBINER 1-2 (2-2)
Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate X Results: Sat Unsat Total Time: minutes Comments: (modified from LJP-004)
NOTE: THIS JPM MAY BE PERFORMED ON EITHER UNIT.
References:
OP H-9, Inside Containment H2 Recombination System, Rev. 11 (U-1)
OP H-9, Inside Containment H2 Recombination System, Rev. 7 (U-2)
Volume 9, Table T-VF-1 (1A) Electric Hydrogen Recombination System Reference Power, Rev. 18 (both units)
Alternate Path: Yes No X Time Critical: Yes No X Time Allotment: 35 minutes (average validation time ___ min) (OCT ave time 22.2 min)
Critical Steps: 1, 4, 7, 8, 9 Job Designation: RO/SRO Rev Comments/TIPs: Minor updates following validation DCPP Task # / Rating: 306200 3.9 Gen KA # / Rating: 028.A4.01 4.0 / 4.0 AUTHOR: JOHN F. BUCKLEY DATE:
REV. 1
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.
Note: Clearly state the Unit for performance during the initial conditions and cue, below. A procedure is attached for each unit (use the correct procedure for the unit selected).
Required Materials:
- Calculator
- Copy of OP H-9, including attachments (partial procedure OK)
(U-1 or U-2).
- Copy of Vol 9 Table T-VF-1 (U-1 or U-2)
Initial Conditions: Given:
- Unit 1 / Unit 2 (specify) has experienced a large loss of coolant accident.
- All vital and non-vital buses are being supplied by offsite power.
- Containment hydrogen concentration has increased to 1.2% and the Site Emergency Coordinator has determined that the Internal Hydrogen Recombiner System (IHRS) is to be placed in service.
- All OP H-9 prerequisites are complete and precautions and limitations reviewed.
Initiating Cue: The Shift Foreman directs you to place the 1-2 / 2-2 (specify) IHRS into service, per OP H-9, section 6.1.
NOTE: Do NOT provide the student with the Task Standard.
Task Standard: Hydrogen Recombiner 1-2 (2-2) is in service at a power setting of 52.74 KW, 1-2 (56.80 KW, 2-2) . (acceptable ranges are 50.23 -
54.42 KW for 1-2, and 54.10 - 58.60 KW for 2-2)
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
- 1. Prepare recombiner for operation. 1.1 Reads first note prior to step 6.1.1.
1.2 Notes that step 6.1.1 to check DG loading is N/A (part of initial conditions that all busses are on offsite power).
1.3 Reads note prior to step 6.1.2.
1.4 Verifies Recombiner Unit 1-2 (2-2) redundant breaker 52-1H-35R (52-2H-35R) is closed.
Cue: The breaker handle is in the full up (ON) position.
1.5 Closes Recombiner Unit 1-2 (2-2) normal breaker 52-1H-35 (52-2H-25). **
Cue: (for the "normal" breaker) An audible "clunk" is heard as the breaker handle was pushed upward. It stayed in the full up (ON) position. (the backup breaker can be checked, and is normally closed in; you may provide the same cue as above if the backup breaker is not closed).
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 2. Verify power is available to 2.1 Locates Recombiner Unit 1-2 (2-2),
recombiner unit 1-2. and reads the note and initial part of the step.
2.2 Verifies white POWER IN AVAILABLE light in ON.
Cue: The Power In Available white light in ON.
Step was: Sat: ______ Unsat _______
- 3. Verify the potentiometer labeled 3.1 Verifies that POWER ADJUST POWER ADJUST is set to zero. potentiometer is set to zero.
Cue: (only if not at "000") POWER ADJUST is at "000".
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. Turn the switch labeled POWER 4.1 Turns POWER OUT SWITCH on OUT SWITCH to the ON the recombiner control panel to the position. ON position.**
4.2 Verifies that the red lamp on the switch plate is ON.
Cue: A small audible click was heard, and the switch is in the full UP (ON) position. The Red Light is ON.
Step was: Sat: ______ Unsat _______
- 5. Measure and record on 5.1 Goes to or contacts the control room Attachment 3 the present and requests containment pressure containment pressure reading. readings from PI-934 through PI-937.
Cue: The Control Room CO reports that U-1 (U-2) containment pressure readings on PI-934 through PI-937 are 2.8 psig, 3.2 psig, 3.4 psig, and 2.6 psig, respectively.
5.2 Calculates average containment pressure and records 17.7 psia on Attachment 3.
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 6. Determine and record pre-LOCA 6.1 Goes to or contacts control room containment temperature on Att 3. and requests the PPC history trend or YR-26 pre-LOCA containment temperature reading.
Cue: Containment temperature before the LOCA was 90º F (from PPC).
6.2 Records containment temperature of 90º F on Attachment 3.
Step was: Sat: ______ Unsat _______
- 7. Determine and record pressure 7.1 Uses Figure 1, Attachment 9.1, to factor, Cp, on Att 3. determine Cp is approximately 1.26
- (range of 1.2 to 1.3 is acceptable, due to graph reading).
7.2 Records Cp on Attachment 3.
Note: Reference power for recombiner 1-2 (2-2) from Vol 9 Table T-VF-1 (1A) is 41.86 KW (45.08 KW)
(supplied to the examinee at start of task)
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 8. Calculate the power setting by 8.1 Multiplies the reference power by multiplying the reference power Cp to obtain the power setting of by Cp. approximately 52.74 KW, 1-2 (56.80 KW, 2-2) . ** (acceptable range is 50.23 - 54.42 KW for 1-2, and 54.10 - 58.60 KW for 2-2) 8.2 Records calculated power setting on Attachment 3.
Step was: Sat: ______ Unsat _______
- 9. Turn the potentiometer clockwise 9.1 Turns the potentiometer clockwise until the calculated power level is until 5 KW is obtained on POWER obtained on the POWER OUT OUT meter and holds for 10 min.
meter. **
Cue: The potentiometer rotated CW; 5 KW is indicated on the AC power meter. Using time compression, the unit has been at 5 KW for 10 minutes.
9.2 Turns the potentiometer clockwise until 10 KW is obtained on POWER OUT meter and holds for 10 min. **
Cue: The potentiometer rotated CW; 10 KW is indicated on the AC power meter. Using time compression, the unit has been at 10 KW for 10 minutes.
(con't on next page)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT (RIL) JPM NUMBER: NRCL111-A1 HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 9. (continued) 9.3 Turns the potentiometer clockwise until 20 KW is obtained on POWER OUT meter and holds for 5 min. **
Cue: The potentiometer rotated CW; 20 KW is indicated on the AC power meter. Using time compression, the unit has been at 20 KW for 5 minutes.
9.4 Advances to the calculated reference power setting. **
Cue: The potentiometer rotated CW until 52.7 KW (56.8 KW) was indicated on the AC power meter and the power reading is stable.
The SFM has directed another operator to monitor the unit and continue this procedure.
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes Critical Step and Sub Steps.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET CAUTION: No plant controls or equipment are to be operated during the performance of this JPM. Controls may be pointed at, but are not to be touched.
Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET UNIT 1 Table T-VF-1 DC-2012-11-DRAFT PAGE 258 OF 263 REV.1 OPERATING test.docx
JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET UNIT 2 Table T-VF-1A DC-2012-11-DRAFT PAGE 259 OF 263 REV.1 OPERATING test.docx
Nuclear Power Generation Diablo Canyon Power Plant Job Performance Measure Number: NRCL111-P3
Title:
ESTABLISH CCW TRAIN SEPARATION Examinee:
Evaluator:
Print Signature Date Testing Method: Perform Simulate X Results: Sat Unsat Total Time: minutes Comments: (modified from LJP-158)
NOTE: THIS JPM MAY BE PERFORMED ON EITHER UNIT.
References:
Unit 1 EOP E-1.4, Transfer to Hot Leg Recirculation, Rev 19 Unit 2 EOP E-1.4, Transfer to Hot Leg Recirculation, Rev 10 OVID 106714 (107714), Sheet 2 Alternate Path: Yes X No Time Critical: Yes No X Time Allotment: 35 minutes (average validation time ___ min) (OCT ave time 19.5 / 21.4 min)
Critical Steps: 3, 4 Job Designation: RO/SRO Rev Comments/TIPs: Rev 1: corrected typos, minor updates DCPP Task # / Rating: 131400 4.0 Gen KA # / Rating: 011.EA1.11 4.2 / 4.2 AUTHOR: GARY HUTCHISON DATE:
REV. 1
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Directions: No plant controls or equipment are to be operated during the performance of this Job Performance Measure. All actions taken by the examinee should be clearly demonstrated and verbalized to the evaluator. The examinee will be given the initial conditions and initiating cue. The task standard will NOT be read to the examinee.
The examiner will then ask if any clarifications are needed. The examinee should be given the "required materials" shown below, and access to other plant references as appropriate.
Equipment operation "Cues" are contingent on proper operation by the examinee, and should be "adjusted" should equipment operation differ from expected.
Note: Clearly state the Unit for performance during the initial conditions and cue, below. A procedure is attached for each unit (use the correct procedure for the unit selected).
Required Materials: Copy of :
- OVID 106714 (107714), Sheet 2
- Unit 1 (or Unit 2) EOP E-1.4, step 10 (partial procedure OK).
Initial Conditions: Given:
- A large break LOCA has occurred on Unit 1 / Unit 2 (specify).
- The Control Room operators are transferring to hot leg recirculation and are ready to establish CCW train separation.
- The following conditions exist:
Initiating Cue: The Shift Foreman directs you to locally separate the CCW on Unit 1 /
Unit 2 (specify) trains in accordance with EOP E-1.4, step 10.
Note: Do NOT provide the student with the Task Standard.
Task Standard: CCW headers are split per E-1.4 step 10.c DC-2012-11-DRAFT PAGE 261 OF 263 REV. 1 OPERATING test.docx
JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Start Time:
Step Standards
Step was: Sat: ______ Unsat _______
- 2. Open FCV-430 or FCV-431, Idle 2.1 Notes that FCV-430 and FCV-431 CCW HX Outlet Stop Vlv. are OPEN (from initial conditions).
Step was: Sat: ______ Unsat _______
- 3. Performs initial steps in Aux Bldg **********************************
to separate CCW header B from A Cue: Provide a copy of OVID 106714 and C. (107714), if referenced by the examinee.
Cue: The Shift Foreman has given permission to break component seals, and another operator will follow through with the sealed component paperwork.
3.1 Evaluates step 10 of E-1.4 and determines that step 10c RNO must be performed (from initial conditions).
3.2 Notes that CCW Pps 2 and 3 are running (from initial conditions).
3.3 Notes that FCV-355 is OPEN (from initial conditions).
(con't on next page)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
Note: Valve is located in O/H in the #2 CCW Pp room, near and above pump on west wall. It is a normal handwheel operated valve, CW to CLOSE.
Cue: (once valve operation described)
The position pointer is pointing at "C".
3.5 Closes CCW-17, CCW pump 13 discharge to header B.**
Note: Valve is located in O/H in the #3 CCW Pp room, near and above pump on west wall. It is a normal handwheel operated valve, CW to CLOSE.
Cue: (once valve operations described)
The position pointer is pointing at "C".
Step was: Sat: ______ Unsat _______
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
header B from A and C.
Note: The following cue may be used to minimize the trips in and out of the Aux Bldg. It does not have to be used.
Cue: (if/once the examinee verbalizes that CCW-23 is located in the TB, give the following cue) The SFM authorizes the performance of steps out of sequence.
Note: Valve is located in O/H platform between the two CCW HXs in the CCW HX room (turbine bldg). It is a normal handwheel operated valve, CW to CLOSE.
Cue: (once valve operations described)
The position pointer is pointing at "C".
(con't on next page)
- Denotes Critical Step and Sub Steps.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-A1 (RIL) HAS BEEN EXCEEDED INSTRUCTOR WORKSHEET Step Standards
- 4. (con't) 4.2 Closes CCW-5, suction crosstie header A to C.**
Note: Valve is located adjacent to and behind the #3 CCW Pp (#3 CCW Pp room) (aux bldg), towards north (south for U-2)) wall. It is a normal handwheel operated valve, CW to CLOSE.
Cue: (once valve operations described)
The position pointer is pointing at "C".
Step was: Sat: ______ Unsat _______
Stop Time:
Total Time: (Enter total time on the cover page)
- Denotes Critical Step and Sub Steps.
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JPM NUMBER: NRCL111-A1 EXAMINEE CUE SHEET CAUTION: No plant controls or equipment are to be operated during the performance of this JPM. Controls may be pointed at, but are not to be touched.
Initial Conditions: Given:
- Units 1 and 2 were ramped down to 25% power, due to a large storm moving in (impending "kelp attack").
- Unit 2 is currently at 25% power, and stable (per U4300A05/A15).
- Current group step counter readings on Unit 2 are as follows:
CBA CBB CBC CBD Group 1 231 231 147 19 Group 2 231 231 147 19
- PK03-13, ROD LO INSERTION LIMIT, has just alarmed, and the crew is responding to that alarm.
Initiating Cue: The U-2 Shift Foreman (SFM) has directed you to perform step 11 of STP I-1A to determine if control banks are above the Rod Insertion Limit (RIL). Note your results on the STP, and on this Cue / Answer Sheet.
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JPM TITLE: DETERMINE IF ROD INSERTION LIMIT JPM NUMBER: NRCL111-(RIL) HAS BEEN EXCEEDED A1 ATTACHMENT 1, SIMULATOR SETUP DC-2012-11-DRAFT PAGE 267 OF 267 REV. 1 OPERATING test.docx