ML032461292
| ML032461292 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/21/2003 |
| From: | Berry P FitzPatrick |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-333/03-301 | |
| Download: ML032461292 (61) | |
Text
L TITLE:
LOI-03-01 SCENARIO I, STUCK RODlRWCU LEAK EOP-5 SCENARIO NUMBER:
NEW JAMES A. FITZPATRICK NUCLEAR POWER PLANT NRC INITIAL LICENSE EXAMINATION SCENARIO 27 MAY 2003 PATH:
SIGNATURE I
VALIDATION TRAINING I OPERATIONS
---./
LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5
DATE v
LOI-03-01 SCENARIO 1, SfUCK ROD/RWCU LEAK EOP-5 SOURCE OF BRIEF DESCRIPTION OF CHANGE CHANGE INITIATOR REVIEWED
LA.
TITLE:
LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK/EOP-5 B.
UP:
- 1.
Initial Protected IC-I 37
- 2.
Special Instructions:
- a. Reactor Startup in progress at approximately 8% CTP.
- b. OP-65 complete through step D.21.I
.b. Ready to place reactor mode switch into RUN (Mode 1).
- c. FWLC in automatic master control on either reactor feed pump.
- d. Confirm Reactor Analyst pull sequence agrees with simulator modeling.
- e.
- denotes critical task@)
- 3.
Preset Conditions:
- a.
- b.
C.
- d.
- e.
AD07:C and E. Two ADS SRVs fail to open.
- f.
- g.
RD10:42-27. Third rod in RWM Group 28 stuck ED24:B on Trigger E-6. Loss of MCC-153 triggered on 12MOV-15 green lamp on.
RDI 3:22:27. Control rod 22-27 fails to scram. RMCS insertion still available.
TC04:A-D. On event trigger 9. All BPVs fail closed after opening CU02:A on event trigger 5. RWCU Pump A trip.
CU07 on event trigger 5 at 50%, 10 minute ramp.
- 4.
Consumable Forms and Procedures:
. AOP-24, STUCK CONTROL ROD, Rev. 7 AOP-1 Reactor Scram, Rev. 39
- 5.
Modified Shift Turnover Sheet See Attachment 1 V
LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5
Commitment Document:
The scenario begins with the plant at -8% CTP with a reactor startup in progress. The crew will continue the startup per OP-65 by placing the reactor mode switch in RUN, starting a second condensate pump and continuing rod withdrawal with guidance to proceed to 25% CTP with rods. After an appreciable reactivity manipulation with rods, an in-sequence rod will be found stuck requiring entry to AOP-24. All procedural actions will fail resulting in a Technical Specification review for an inoperable rod. The " A RWCU pump will trip resulting in diagnostic actions. Shortly after, a steam leak will be detected in the Reactor Building vicinity of the Reactor Water Cleanup pumps. Automatic or manual isolation of RWCU will result in a loss of MCC-152 as 12 MOV-15 begins to stroke. This renders the leak unisolable. The leak severity will slowly grow requiring entry into EOP-5. EOP-5 actions to manually scram the reactor will find a control rod that failed to scram. This coupled with the previously stuck control rod will require entry into EOP-3 until operator action to insert the second rod with RMCS. Leak severity will eventually force an Emergency Depressurization when reactor building temperatures exceed 2 maximum safe values. Timely action to insert the above control rod and thus exit EOP-3 to EOP-2 will provide the opportunity for the crew to anticipate an Emergency Depressurization and open all Bypass Valves. Upon opening, the Bypass Valves will subsequently fail closed forcing the Emergency Depressurization. Upon Emergency Depressurization, 2 ADS SRVs will fail to open forcing additional SRVs to be operated. The scenario will terminate upon Emergency Depressurization.
-I Shift Turnover ATTACHMENT 1 A reactor startup is in progress. The plant is at approximately 8% CTP ready to place the Reactor Mode Switch into RUN (Mode 1). OP-65 is complete through Step D.21.I
.b. ST-5D has just been completed to satisfy D.21.1.i and D.22.3 and is satisfactory. Chemistry has reported that all chemistry parameters are well within specification for Power Operation. 1-1 31 Dose Equivalent is <.2uci/gm. Reactor Engineer auidance is to continue reactor startup with rods until 25%CTP. You are currently in RWM SteD 26.
-..-.J LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5
---I EVENT I EVENT SEQUENCE I.
- 2.
- 3.
Preparations for and placing Reactor Mode Switch to RUN (Normal)
Start of second Condensate Pump (Normal)
Continue startup with Rod Withdrawal (Reactivity Manipulation)
- 4.
- 5.
Stuck Control Rod (AOP-24) (Component and Tech Specs)
RWCU pump trip and steam leak into Rx Bldg. {Component)
- 8.
I One rod fails to scram (Component)
I
- 6.
- 7.
Loss of MCC-152 upon 1 2NIOV-15 closure Non-isolable RB steam IeaklEOP-5IManual ScramlEmergency Depressurization (Major)
D.
A T D N CIlF&
.L
- 1.
Emergency Depressurization in progress with 7 SRVs
- 9.
10 L.
LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5 BPVs fail closed after opening (Component) 2 ADS SRVs fail to open (Component)
I I
I I
INSTRUCTOR ACTIVITY Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Modified Turnover After the shift turnover, allow no more than five minutes for panel wal kdow n POSITION OPERATOR ACTIONWSTANDARD COMMENTS/EVALUATION All Walkdown the control panels SAT / UNSAT / NA CRS Conduct turnover brief. Order continuation of OP-65 startup SAT / UNSAT / NA I -
I I
I SNO/BOP Close Main Steam Line Drain Valves (29MOV-101A-D, 77, 78, SAT UNSAT NA SNO/RO SAT / UNSAT I NA 79 and 74)
Place reactor mode switch in RUN Place IRMlAPRM recorder select switches in APRM/RBM Select and Withdraw all 8 IRMs per OP-16 E.9 Start second condensate pump per OP-3 D.7 Report to CRS that the plant is ready to continue power ascent.
SNO/BOP SAT / UNSAT / NA SNO/BOP SAT / UNSAT / NA CRS Order in-sequence rod withdrawal SAT / UNSAT / NA SNOlRO SAT / UNSAT / NA SNO/RO SAT / UNSAT / NA ANY/ALL Recognize symptom of AOP-24 SAT / UNSAT / NA CRS Order performance of AOP-24 SAT / UNSAT / NA SNO/BOP SAT I UNSAT I NA Selects and withdraws control rods in sequence.
Reports that control rod 42-27 will not move at normal drive pressures. May adjust up to 400 psid per OP-25 Section E.
Role Play: After several expected.
Confirm 09-5 panel indications and HCU lineup are normal per minutes report lineup as OP-25 SNO Incrementally raise drive D/P at 50 psig increments and attempt rod movement after each adjustment.
SAT / UNSAT / NA LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5
I OPERATOR ACTIONS/STANDARD Report to CRS that rod will not move with maximum DIP applied.
Restore CRD hydraulic parameters to normal values Consult Technical Specification 3.1.3 Declare control rod 42-27 inoperable and enter condition A.
Brief crew on inoperability and required actions Recognize and report RWCU pump A trip.
Order response per ARPs and local investigations.
INSTRUCTOR ACTIVITY I POSITION COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT I NA SAT / UNSAT I NA SAT / UNSAT / NA I SNO
~
I CRS I SNO SNO SNO I CRS SAT / UNSAT / NA SAT / UNSAT / NA Dispatch NPO to RWCU panel.
Relay report to CRS elevation.
CRS SNO/BOP TRG! E5 Order actions to trip and isolate RWCU (OP-28, Section G.2)
Turn off RWCU pumps SAT UNSAT / NA SAT / UNSAT / NA Role Play: After several minutes report a steam leak in overhead area of RWCU pumps on RB 300 foot Close 12 MOV-I 5, 18, and 69 Recognize bus loss coincident with valve closures Order investigation of bus loss.
CRS SAT / UNSAT / NA ANY/ALL CU07 severity may need to be slowly adjusted to drive the rest of the scenario actions by
, trackina temr>eratures on SCT CRS CRS ANY/ALL CRS Determinelreport failure of 12MOV-15 to close Recognize RWCU steam leak is un-isolable.
Recognize EOP-5 entry condition on RB Area TemperaturelRadiation Enter EOP-5 ANY/ALL CRS SNOlBOP I
Determine/report loss of MCC-I 52 I SAT / UNSAT / NA SAT / UNSAT I NA SAT / UNSAT / NA SAT / UNSAT / NA LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5
INSTRUCTOR ACTIVITY POSITION i
(
COMMENTS/EVALUATION SAT I UNSAT / NA
\\
OPERATOR ACTIONS/STANDARD
~~
Execute RBIT, RB/R and RBlL concurrently prioritizing RB/T SAT / UNSAT / NA Order maximizing Reactor Building area cooling Start all remaining Crescent Area Unit Coolers.
1 SNO/BOP SAT / UNSAT / NA
- CRITICAL TASK 1 CRS Before any RB area Temperature exceeds Max Safe, Order Manual Scram and enter EOP-2 Insert Manual Scram and perform AOP-1 Immediate Actions e
Depress Manual Scram pushbuttons e
Reactor Mode Switch to Shutdown e
Fully Insert all SRMs and IRMs e
Verify SDlV Vent and Drain valves closed Verify APRMs downscale Verify at least I Circ Water pump running Order SNO/BOP to level control with FeedlCondensate at 177-222.5 inches.
Trend level performance and manipulate GEMAC MasterAndividual controllers, RFP discharge valves and RFP triD as necessary to control level.
SAT / UNSAT / NA
- CRITICAL TASK
~
~~
SAT / UNSAT I NA CRS SAT / UNSAT / NA S N O/BO P S NO/RO Recognize and report that 1 rod failed to scram (22-27) and that another (42-27) was previously stuck and also did not insert SAT / UNSAT / NA Enter EOP-3 based on 2 rods not inserted to or beyond 02 Order SNO to Pressure Control with EHC in automatic.
Confirm EHC controlling pressure in automatic I CRS SAT / UNSAT / NA SAT / UNSAT / NA I SNO
~~
~
SAT / UNSAT / NA Order SNO/RO to initiate ARI Initiate ARI and confirm all 5 valves energized.
Order SNOlRO to insert control rods per EP-3 SAT / UNSAT / NA 1 SNO/BOP SAT / UNSAT I NA I CRS LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5
(
INSTRUCTOR ACTIVITY If rod 22-27 is attempted, it will insert.
If rod 42-27 is attempted, it will not To reset ARI:
RFI-RP20 to test If ED is anticipated, TRG! E9 As BPVs are opening POSITION SNO/RO CRS
~
S N O/BO P SNO/RO
~~
CRS CRS CRS CRS CRS SNO SNO OPERATOR ACTIONS/STANDARD Determine EP-3 success path is RMCS BypassRWM Establish drive DIP.
Select control rod Drive in with Rod Movement or Emergency In Control Switch.
Reset ARI by dispatching NPO to Relay Room SDlV Hi Level Trip Switch to BYPASS Scram Reset Switch to Group 2&3 then I & 4.
May order O/R ADS and TIP Core Spray If ordered:
Both ADS O/R switches to O/R Both 14MOV-1 I valve keylocks to bypass Close 14MOV-11 A and B Report all rods in except 1 Exit EOP-3 and enter EOP-2 Recognize that 2 RB area temperatures above rnax safe reauires Emerqencv Depressurization.
Order pressure control on SRV's at a 200 psig band.
~
~~
If 2 max safe RB area temperatures are exceeded, announce that an emergency depressurization is required.
Enter EOP-2 ED leg and order opening of 7 ADS valves.
Open ADS valves A-H (excluding F)
.~
~
~..
~~
Report that ADS valves C and E failed to open COMMENTSEVALUATION SAT / UNSAT I NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA
- CRITICAL TASK SAT / UNSAT / NA
- . CRITICAL
- TASK SAT / UNSAT / NA
- CRITICAL TASK LOI-03-01 SCENARIO 1, STUCK RODlRWCU LEAK EOP-5
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTlONSlSTANDARD CRS Order additional SRV's opened to a total of 7 valves SNO Opens 2 additional SRV's and reports 7 valves open TERMINATE THE SCENARIO LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5 I
COMMENTSlEVALUATlON 1 I
SAT I UNSAT I NA
- CRITICAL TASK SAT l UNSAT I NA
- CRITICAL TASK
i ATTACHMENT 1 Shift Turnover A reactor startup is in progress.
The plant is at approximately 8% CTP ready to place the Reactor Mode Switch into RUN (Mode I).
OP-65 is complete through Step D.21.1.b.
ST-SD has just been completed to satisfy D.21. I.i and 0.22.3 and is satisfactory.
Chemistry has reported that all chemistry parameters are well within specification for Power Operation. 1-1 31 Dose Equivalent is <.2uci/gm.
Reactor Engineer guidance is to continue reactor startup with rods until 25%CTP. You are currently in RWM Step 26.
LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5
111 -
I -EnteZgy James A. FibPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 1 APPL. TO JPM NUMBER REV: 0 DATE: 5/25/03 NRC WA SYSTEM NUMBER: 7 4.41 4.1 JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED E: 20 Minutes SUBMITTED:
OPERATION REVIEW:
APPROVED:
CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
( ) Simulated
( X ) Performed Location:
(
) Plant
( X ) Simulator DATE PERFORMED:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory EVALUATOR:
SIGNATURE/PRINTED CANDIDATE REV1 E W:
SIGNATURE REVIEWED BY:
PROGRAM ADMINISTER DOC. COMPLETE:
Page 1 of 4
Job PERFbfiiir&riiC~ MEASiiKk RECORD AND CHECKLIST SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 1 APPL. TO JPM NUMBER Current Update: 5/25/03 By: RWD Int.
Date Outstanding Items:
Technical Review Additional Information Questions and Answers Validation Procedural Change Required
___ None Comments:
Previous Revision Dates:
Page 2 of 4
SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 1 APPL. TO JPM NUMBER
- 1.
II.
ill.
IV.
L-V.
VI.
SAFETY CONSIDERATJONS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
JAF Emergency Pian Implementing Procedures IAP-2, Rev. 23 TOOLS AND EQUIPMENT A.
None SET UP REQUIREMENTS A.
This JPM is completed as followup after the scenario progress has been frozen.
EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and nat actually performed.
B.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
TASK CONDITIONS A.
B.
- - CRITICAL STEP L*
Page 3 of 4
C I,
S/RO/NLO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO I
- 1.
VII.
INITIATING CUE STEP ObtainlApproach IAP-2, Attachment Based on the events that have just occurred determine if the current circumstances warrant classification in accordance with the JAF Emergency Plan and, if so, determine the appropriate classification level.
~
~
~
Candidate obtains the procedure or approaches the posted attachment.
SAT / UNSAT 12.1 Candidate recognizes that the scenario events included a non isolable RWCU leak into the Reactor Building.
Candidate may also recognize that an Emergency DeDressurization was required.
Candidate reviews IAP-2 Technical Bases for expected declarations.
Candidate selects Recognize the applicable conditions
- 2.
SAT / UNSAT SAT / UNSAT SAT / UNSAT
- 3.
1 Confirm the conditions STANDARD EVALUATION I COMMENT F
D Terminate the task at this point.
Page 4 of 4
JAMES A. FITZPATRICK NUCLEAR POWER PLANT NRC INITIAL LICENSE EXAMINATION SCENARIO 27 MAY 2003
--I TITLE:
LOI-03-01 SCENARIO 2, TURBINE VlBRATlONlLOSS OF VACUUMlATWS SCENARIO NUMBER:
NEW PATH:
I SIGNATURE VALIDATION TRAINING OPERATIONS LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUMIAIWS REVIEWED
.,A.
JU. LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK/EOP-5 B.
- 1.
Initial Protected IC-I 38
- 2.
Special Instructions:
- a. Plant operating normally at -95% CTP
- b. Rod Pattern exchange just completed. Returning to 100% CTP.
- c. Confirm Reactor Analyst pull sequence agrees with simulator modeling.
- d. Confirm RAP-7.3.16 guidance is at the 09-5 panel
- 3.
Preset Conditions:
- a.
- b.
C.
- d.
Preset RD22:A at 70%
- e.
Preset RDO1A:A On Trigger 1, RR19:B fail as is.
On Trigger 3, TU04:E at 21% and D at 22% no ramp. (7-9 mils)
On Trigger 3, MCOI at 42% severity over 20 minutes.
- 4.
Consumable Forms and Procedures:
0 0
AOP-66, MAIN TURBINE HIGH VIBRATION, REV. 3 AOP-31, LOSS OF CONDENSER VACUUM, REV. 15 AOP-41/42, FEEDWATER MALFUNCTION, Rev. 611 0 AOP-1 Reactor Scram, Rev. 39
- 5.
Modified Shift Turnover Sheet See Attachment 1 w
LOI-03-01 SCENARIO 2, TURBINE VIBF%TION/LOSS OF VACUUM/AlWS
.-.- c.
FNA-RY:
Commitment Document:
The crew will take the shift with the plant operating normally at -95% CTP following a rod pattern exchange. Following Reactor Analyst guidance, the crew will continue a power ascent to 100% CTP using recirculation flow. Shortly into the power ascent, the operators will notice that the non-controlling FWLC level instruments are trending down while the controlling is steady. The crew will diagnose that the FWLC controlling instrument has failed as is causing actual level to trend down slowly. The crew will take manual control, of FWLC, enter AOP-41/42 and determine the cause to be a failed instrument. The crew will then swap FWLC to the alternate instrument input and return to automatic level control. The Control Room Supervisor will consult technical specifications for the failed instrument. The Main Turbine will then lose part of a low pressure blade that will penetrate the low pressure turbine exhaust boot. This will be indicated by a step change in turbine vibration followed by a slow loss of condenser vacuum that will eventually worsen. Turbine vibration will result in entry to AOP-66 but will not be severe enough to require a turbine trip. The condenser vacuum loss will eventually result in AOP-31 entry which will require a power reduction. The vacuum loss will worsen such that power reductions with both recirculation flow and rods will occur. Eventually the AOP-31 manual scram milestone will be met. The manual scram will not be completely successful due to hydraulic blockage in one of the scram discharge volumes. Power will be above 2.5% requiring significant EOP-3 action. As a nuisance, one SDlV vent valve will fail to close. The EP-3 success path will be inserting rods with RMCS and repeated manual scrams. As vacuum continues to trend away, level control will need to transition to HPCl and pressure control augmented with SRVs.
The resultinn challenne to containment will result in SLC iniection if not alreadv started.
I Shift Turnover ATTACHMENT 1 I
The plant is operating normally at -95% CTP. A rod pattern exchange has just been completed and the reactor analvst guidance is to return to 100% CTP usinq recirculation flow.
-e LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
EVENT SEQUENCE I
I.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
FWLC Controlling Instrument upscale failure (Instrument and Tech Specs)
Swap to alternate FWLC Instrument input and return FWLC to automatic.
Step change in Turbine Vibration (Component)
Slow loss of condenser vacuum (Component)
Power reduction with recirculation flow (Reactivity)
Power reduction with rod insertion (Reactivity)
ATWSlEOP-3 (Major)
SDlV Vent and Drain valve fails to close (Component)
D.
- 1.
- 2.
- 3.
Pressure control stable Control rods beinghnserted using EP-3 level control stable at 0-222.5 inches
%L, 4.
SLC injecting LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
INSTRUCTOR ACTIVITY POSITION COMMENTS/EVALUATION OPERATOR ACTIONS/STAN DARD Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Modified Turnover All Walkdown the control panels SAT / UNSAT / NA After the shift turnover, allow no more than five minutes for panel walkdown CRS SAT / UNSAT / NA Conduct turnover brief. Order continuation of power ascent to 100% usinn recirculation flow S NO/BO P Alternatively adjust recirculation MG set speeds in 1-3%
increments.
SAT / UNSAT / NA TRG! E l SNO/RO Monitor power pressure and level at 09-5 during ascent.
SAT / UNSAT / NA
~
ANY/ALL Recognize off normal RPV water level condition SAT / UNSAT / NA
~~
~
Select FWLC to manual, Stabilize and restore RPV level to nreen band.
~~
CRS SNOlBOP Order entry into AOP-41/42 SAT / UNSAT / NA
~~
-~
Perform actions of AOP-41/42. Determine that controlling B instrument is failed which caused an actual low RPV level condition.
SAT / UNSAT / NA CRS Order swap to A level transmitter and return FWLC to automatic Der OP-2A SAT / UNSAT / NA Select OP-2A, section G.30 Place column select switch to A Return to Automatic FWLC per G.7 Select Master Controller to MANUAL Balance individual MIA Stations Select individual and master controllers to Balance SAT / UNSAT / NA S N O/BO P LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
OPERATOR ACTIONS/STANDARD Recognize Main Turbine High Vibration condition.
Order entry into AOP-66
~~
ROLE PLAY as Mike Tallents and acknowledge report.
State that you are coming in COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA CRS INSTRUCTOR ACTIVITY TRG! E3 ROLE PLAY: If requested, report that there is abnormally high noise levels and vibrations on the Main Turbine elevation (300)
POSITION ANYIALL CRS SNO CRS Announce turbine bearings 4 and 5 are alarming at elevated vibration values (7-9 mils)
I ANY/ALL SAT UNSAT 1 NA May order power reduction using recirculation flow at normal rates to attemPt to reduce vibration levels.
SAT UNSAT / NA Report abnormal vibration to Main Turbine Expert I SAT / UNSAT / NA TRG! E4 Monitor and adjust MCOI as SNOlBOP ANY/ALL CRS SNOIBOP
~
~
If ordered, commence power reduction using recirculation flow.
Alternativelv reduce each MG set meed in I-3% increments.
~
Recognize and announce worsening trend in condenser vacuum.
1 SAT / UNSAT / NA SAT I UNSAT / NA Order entry into AOP-31 I SAT / UNSAT I NA Order power reduction with recirculation flow to counter vacuum trend. Caution against _ _ _
reducing below
. - 50% - core flow. --
Reduce recircualtion flow to -50% Core Flow.
Recognirelreport that condenser vacuum is still worsening
~~
~
~
Commence actions of AOP-31 SAT / UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA I SAT / UNSAT / NA Trip Recombiner Isolate TB Equip Sump Vacuum Drag Order spare SJAEs in service Determine source is air in-leakage Dispatch operators to search for air leak Set Manual Scram benchmark of 23-25 inches Hg 1 SAT / UNSAT / NA LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
(
I INSTRUCTOR ACTIVITY ROLE PLAY: As NPO, report that there is a visible tear in the exhaust boot of LP turbine B.
Monitor and adjust MCOI as necessary to force manual scram Delete TU04: D and E POSITION CRS SNO/RO ANWALL CRS SNO/RO CRS SNO/BOP SNO/RO CRS OPERATOR ACTIONS/STAN DARD Order insertion of the first cram group.
Select and fully insert all rods in the first cram group Recognize/report that condenser vacuum is still worsening Order Manual Scram Insert Manual Scram and perform AOP-1 Immediate Actions Depress Manual Scram pushbuttons Reactor Mode Switch to Shutdown Fully Insert all SRMs and IRMs Verify SDlV Vent and Drain valves closed Verify APRMs downscale (Will not be)
Verify at least 1 Circ Water pump running Order SNOlBOP to level control with Feed and Condensate 177-222.5 inches Manipulate RFP, GEMAC Controllers and RFP Discharge valves to control RPV level.
~~
~
~
Report multiple rods out, APRMs NOT downscale and one SDlV Vent valve failed to close.
Announce EOP-3 entry from EOP-2 i v COMMENTSlEVALUATlON :
SAT / UNSAT / NA SAT / UNSAT / NA i
i SAT I UNSAT / NA SAT / UNSAT / NA
~
SAT / UNSAT I NA SAT I UNSAT I NA SAT / UNSAT I NA
- CRITICAL TASK SAT I UNSAT / NA
- CRITICAL TASK LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
INSTRUCTOR ACTIVITY Adjust MCOI to force loss of Bypass Valves POSITION 2RS CRS SNO/BOP SNO CRS SNO SNO/BOP
('
OPERATOR ACTIONS/STANDARD
~
Order SNO/RO to perform the following EOP-3 actions B
Initiate ARI Trip both recirculation pumps Override ADS Reduce recirculation flow to minimum Determine EP-3 success path and insert rods.
Order SNOlBOP to terminate and prevent all injection except SLC, CRD and RClC per EP-5. New level band is -1 9 to 1 I O.
Injection source will be Feedwater. Caution against rapid iniection.
Perform the following EOP-3IEP-5 level control actions:
Reduce running RFP(s) MIA stations to manual minimum.
Ensure running RFP min flow valve(s) open Depress HPCl Turbine Trip pushbutton.
10MOV-27A/B Auto Control to bypass and close IOMOV-27A/B (May be deferred) 14MOV-1 IA/B Auto Actuation to Bypass and close 14MOV-I 1 AIB (may be deferred)
Order SNO to pressure control with EHC in automatic. Band of 900-1000 psig.
Confirm EHC in automatic controlling RPV pressure in band.
Reinject with HPCl by:
Ensure SGT running Depress turbine trip reset Verify automatic initiation lineup Control speed to control injection Ensure 01 -1 25MOV-13A or B is open Ensure HPCl flow controller in Manual minimum i
i COMMENTS/EVALUATION SAT I UNSAT / NA
' CRITICAL TASK I
I SAT / UNSAT / NA
- CRITICAL TASK I
SAT / UNSAT / NA
- CRITICAL TASK
~
~~~
SAT / UNSAT / NA
~~
SAT I UNSAT I NA
~
SAT / UNSAT I NA SAT / UNSAT I NA LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
INSTRUCTOR ACTIVITY To reset ARI, RFI-RP20 to Test Monitor and adjust MCOI as necessary to force RFP trip and loss of bypass valves POSITION SNO/RO CRS SNO/RO SNO/RO ANY/ALL CRS SNO CRS OPERATOR ACTIONS/STANDARD Perform the following EOP-3 actions:
Select ARI Switch to ACT Adjust both recirculation GEMAC manual controls to minimum speed demand while trending RPV level Select both drive motor breaker control switches to PTL Select both ADS override switches to override Determine EP-3 success path is both RMCS and Manual Scrams Order control rod insertion with EP-3 success paths NOTE: SNO/RO should pursue both paths in that RMCS can complete partial insertions while SDIV's are draining to enable Manual scrams.
RWM Keylock to Bypass Dispatch NPO to reset ARI and observe solenoids de-energized. (if not already done)
Raise drive water DIP. Options include shut CRD-56, Start second CRD pump, manually adjust FIC-301 to open AOV-1 9A( B)
Select and drive rod full in in EP-3 attachment sequence.
Recognize that as condenser vacuum continues to worsen, Pressure control will need to transition to HPCl augmented with SRV's.
If not already done, order SLC injection with either system.
SLC injection is required prior to exceeding BIIT.
Select SLC control switch to ordered division and report tank level.
Order transition of RPV pressure control to HPCl and augment with SRVs. Modify band to 800-1000 psig.
i' COMMENTS/EVALUATION I SAT I UNSAT / NA
- CRITICAL TASK SAT / UNSAT / NA
- CRITICAL TASK SAT / UNSAT / NA LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
INSTRUCTOR ACTIVITY RFI-RP21 :AI, A2, BI, and When the scram is reset, delete malfunction RD22A POSITION SNO SNO SNOlRO CRS
\\
OPERATOR ACTIONS/STANDARD To transition Pressure Control.
Augment HPCl operation with sequential opening of SRVs to maintain 800-1000 psig Report downward trend in SLC tank level.
EP-3 Manual Scram path actions Dispatch NPO to reset ARI and observe solenoids de-energized (if not already done)
Order/hang 09-1 5/17 auto scram jumpers.
Open CRD-56 if closed.
SDlV Hi Level Trip to Bypass Rx Scram Reset to Group 2 and 3 then 1 and 4.
When SDIVs are drained insert Manual Scram
~
When all rods in exit EOP-3 and enter EOP-2
~~
~
-~ -~~
TERMINATE THE SCENARIO COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA
- CRITICAL TASK SAT / UNSAT / NA LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
$4
- ATACHMENT 1 Shift Turnover The plant is operating normally at -95% CTP. A rod pattern exchange has just been completed and the reactor analyst guidance is to return to 100% CTP using recirculation flow.
LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS
-as
-z-zz-Entegy James A. FibPatrick Nuclear Power Plant Nuclear Northeast
'I OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 2 APPL. TO JPM NUMBER REV: 0 DATE: 5/25/03 NRC WA SYSTEM NUMBER: 7 4 41 4 1 JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME:,10 Minutes SUBMITTED:
OPERATION REVIEW:
APPROVED:
CANDIDATE NAME:
JPM Completion:
( ) Simulated
( )Performed Location:
( ) Plant
( )Simulator
~L4-DATE PERFORMED:
S.S. NUMBER:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory EVALUATOR:
SIGNATUREIPRINTED CANDIDATE REVIEW:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER Page 1 of 4
L-1 SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 2 APPL. TO JPM NUMBER Current Update: 5/25/03 By: RWD Int.
Date Outstanding Items:
Technical Review Additional Information Questions and Answers Procedural Change Required Validation None Comments:
Previous Revision Dates:
Page 2 of 4
JGB @EkruPi&hAnbe MtASGKE REQUIRED TASK INFORMATION
-.-, SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DE FOR SCENARIO 2 APPL. TO JPM NUMBER LAR,TION
- 1.
- 11.
111.
IV.
u V.
VI.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
JAF Emergency Plan Implementing Procedures IAP-2, Rev. 23 TOOLS AND EQUIPMENT A.
None SET UP REQUIREMENTS A.
This JPM is completed as followup after the scenario progress has been frozen.
EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and nat actually performed..:
The candidate should, at a minimum, identify the change in equipment status fight indication when equipment operation is simulated.
B.
TASK CONDITIONS A.
B.
- - CRITICAL STEP
'v Page 3 of 4
S/RO/NLO NEW VII.
INITIATING CUE TASK TITLE: LOI-03-01 NRC EXA I,
/l E-PL Based on the events that have just occurred determine if the current circumstances warrant classification in accordance with the JAF Emergency Plan and, if so, determine the appropriate classification level.
- 2.
(
. ?4 DECLARATION FOR SCENARIO 2
- 3.
/ i
- 4.
STEP
~~
~
Obtain/Approach IAP-2, Attachment 2.1 Recognize the applicable conditions
~
Confirm the conditions Classify the event STANDARD Candidate obtains the procedure or approaches the posted attachment.
Candidate recognizes that the scenario events included an ATWS condition with a challenge to primary containment intearitv.
Candidate reviews IAP-2 Technical Bases for expected declarations.
Candidate selects SAE-2.2.2 Any RPS setpoint has been exceeded AND Automatic and manual scrams fail to result in a control rod pattern which assures reactor shutdown under all conditions without boron Reactor power > 2.5%
Torus temperature > Boron Injection Initiation TemDerature AND Either:
OR EVALUATION / COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT EVALUATOR: Terminate the task at this point.
Page 4 of 4
JAMES A. FITZPATRICK NUCLEAR POWER PLANT NRC INITIAL LICENSE EXAMINATION SCENARIO 27 MAY 2003 I
TITLE:
SCENARIO NUMBER:
NEW LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4 PATH:
I I
I SIGNATURE VALIDATION TRAINING OPERATIONS LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4
SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4 REVIEWED
\\--
A.
I l I L E LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4 B.
FNARln SFTLJP:
- 1.
Initial Protected IC-I 39
- 2.
Special Instructions:
- a. Plant operating normally at 100% CTP
- b. Confirm Reactor Analyst pull sequence agrees with simulator modeling.
- c. Confirm Reactor Analyst RAP-7.3.16 guidance is available at 09-5 panel.
- d. Ensure LPRM bypass postings are current to support scenario.
- e. Bypass additional LPRMs as necessary to support Event 2 Tech Spec exercise.
- f.
Ensure A and B SW pumps in service. C in standby
- 3.
Preset Conditions:
- a.
NM11:6B3613 on Trigger E-2 at 100% severity and 10 minute ramp, LPRM Upscale failure. (LPRM will be assigned to a B division APRM such that upon failure, APRM inop on 2 per level count).
OG04 on Trigger E-3, Combustion in Off-Gas Annunciator 09-6-1 -23 crywolf on Trigger E-3 Recombiner trip on Trigger E-3 RR15:A on Trigger E-6 at 50% severity and 10 minute ramp, Steam Leak in Drywell.
Preset RD13:XX:W, One rod fail to scram ED18:X on Fast transfer trigger assigned to Trigger E-7, Loss of 10500 Bus.
- b.
- c.
- d.
- e.
- f.
- g.
- 4.
Consumable Forms and Procedures:
AOP-5, Combustion in SJAE After Condenser, Rev. 10 AOP-1 Reactor Scram, Rev. 39
- 5.
Modified Shift Turnover Sheet See Attachment 1 L-,
LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4
Commitment Document:
The scenario begins with the plant operating normally at 100% CTP. A repair of the C SW strainer has just been completed and the tags are clear. The shift will swap to the C SW pump in service and B in Standby to facilitate a pressure leak test of the C SW pump strainer. An LPRM will start a slow upscale failure resulting in a single LPRM slowly trending up. If not caught and bypassed, a half scram on APRM upscale will result. The crew will determine the failed LPRM as the cause and bypass the LPRM. The bypass will result in an INOP APRM on the 2 per level count basis. A Tech Spec review will identify a Potential LCO with trip function maintained by the remaining divisional APRMs. A fire in the SJAE After Condenser will require entry to AOP-5. Actions to extinguish the fire will not be successful until Rx power has been reduced with both recirculation flow and control rods. After the fire is out, a steam leak in the drywell will force entry into EOP-2 and 4. On the Manual Scram, a single rod will fail to insert and will subsequently be driven in by normal RMCS. On the fast transfer, the 10500 bus will experience catastrophic failure resulting in a loss of containment cooling capability with the A RHR loop as well as a loss of both A and B RHR pumps. This reduces EOP-4 actions to a single (D)
RHR pump in the B loop. A single drywell spray evolution will result in scenario termination.
I Shift Turnover ATTACHMENT 1 The plant is operating normally at 100% CTP. Maintenance has just completed a repair to the C SW pump discharge strainer and the tags have been cleared. An NPO is standing by with maintenance to perform a pressure leak check of the strainer. Swap to the C SW pump in service and B in Standby.
c
~-..
LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4
' EVENT NO.
I EVENT SEQUENCE I.
- 2.
- 3.
- 4.
D.
CI IF&
- 1.
Completion of 1 Drywell Spray Evolution Swap in service Service Water pumps (Normal)
LPRM Upscale failure/APRM half scram (Instrument and Tech Specs)
Combustion in SJAE After Condenser (AOP-5) (Component)
AOP-5 directed Dower reduction with recirculation flow IReactivitv)
LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4
- 5.
- 6.
- 7.
AOP-5 directed power reduction with Control Rods (Reactivity)
Steam leak in the Drywell (Major)
Loss of 10500 bus (Component)
INSTRUCTOR ACTIVITY OPERATOR ACTIONWSTAN DARD Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Modified Turnover After the shift turnover, allow no more than five minutes for Dane1 walkdown COMMENTS/EVALUATION TRG! E2 Recognize that APRM is inoperable on 2 per level criteria and consult Tech Specs 3.3.1. I and TRM 3.3.B.1. Determine that no condition entry is required.
POSITION SAT UNSAT NA All CRS SNO/BOP ANY /ALL SNO/RO CRS SNO/BOP CRS I
Walkdown the control panels SAT / UNSAT / NA Conduct turnover brief. Order coordination with field to start C SW pump and place B in STBY per OP-42 G.l Start C SW pump. Stop B and place in Standby Recognize/Report LPRMIAPRM upscale trend. Determine failed LPRM is 36-1 3-8 Report that all other APRMs are stable.
Order bypass of LPRM 36-1 3-8 per OP-16 SAT I UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT I NA LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4
f TRG! E3 ANYlALL Cause of recombiner trip is low outlet temperature OPERATOR ACTIONS/STAN DAR D RecognizelReport indications of combustion in SJAE after condenser.
Announce entry to AOP-5. Direct SNO/BOP to perform actions Perform the following actions:
of AOP-5 Dispatch NPO to place additional SJAEs in service.
Report to CRS that power reduction is required until 40% or fire is extinguished.
e Brief crew and direct SNO/BOP to reduce power using recirculation flow to 50% core flow or the fire is out.
NOTE: CRS judgment on desired power ramp rate.
Alternatively adjust Recirculation GEMAC controllers in 1-3%
increments OR Concurrently reduce both GEMACs at a rapid rate without causing RPV Hi Water level trip.
Monitor power/pressure/level during downpower.
Report Core Flow at - 50% and combustion still indicated.
Order SNO/RO to insert the first cram group Select and fully insert all rods in the cram group.
Recognize that combustion has extinguished.
Order chemistry to complete a confirmatory hydrogen sample.
Recognize indications of steam leak in drywell Order establishment of a Torus Vent per OP-37 I CRS COMMENTS/EVALUATION SAT / UNSAT / NA SAT uNSAT / NA SAT / UNSAT I NA SAT / UNSAT / NA SAT / UNSAT / NA I
SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT UNSAT NA SAT / UNSAT / NA SAT / UNSAT / NA
~
I SNO/BOP DELETE OG04 TRG! E6 CRS SNO/BOP SNOlRO SNO/BOP CRS SNO/RO ANY/ALL CRS ANY/ALL I CRS pressure.
Commence actions to establish Torus vent.
I SNO/BOP SAT / UNSAT / NA
--I -
Set a benchmark for a manual scram of 2-2.3 psig drywell 1
LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4
I Role Play: Report as NPO that 10500 bus has heavy damage at the 1051 4 breaker and heavy smell of burnt insulation.
INSTRUCTOR ACTIVITY I POSITION SNO CRS I ANY/ALL I SNO/RO CRS SNO/BOP 1
I SNO/RO 1 SNO 1 CRS 1 SNO I ANY/ALL I CRS OPERATOR ACTIONS/STANDARD Recognize/Report manual scram benchmark Insert Manual Scram and perform AOP-1 Immediate Actions a
Depress Manual Scram pushbuttons Reactor Mode Switch to Shutdown Fully Insert all SRMs and IRMs e
Verify SDIV Vent and Drain valves closed Verify APRMs downscale e
Verifyhip Main Turbine e
Verify electrical fast transfer NSS-RSS Verify at least 1 Circ Water pump running Order SNO/BOP to level control with FeedICondensate at 177-222.5 inches.
~
Trend level performance and manipulate GEMAC Master/lndividual controllers, RFP discharge valves and RFP trip as necessary to control level.
Recognize and report that 1 rod failed to scram and that the 10500 is de-energized with A and C EDGs running Dispatch NPO to assess status of 10500 bus and EDGs Order SNO to Pressure Control with EHC in automatic.
Confirm EHC controlling pressure in automatic Order EDG A and C shutdown Shutdown EDG A and C Recognize/Report EOP2/4 entry condition on DNV pressure Announce entry into EOP-2 and 4 COMMENTS/EVALUATION SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4
(
(
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD ANYlALL RecognizelReport HPCl initiation CRS SNO Trip HPCl CRS Determine HPCl injection not needed and order HPCl tripped RR15:A severity may need to De adjusted to force scenario milestones When torus pressure >2.7 psig order 6 loop of RHR in torus spray with excess flow to torus cooling.
Startup B loop RHR in Torus Spray. Excess flow to torus cooling while observing current limitation on RHR pump.
Set a torus pressure benchmark of 15 psig. Order terminate and prevent RHR and Core Spray per EP-5 Close IOMOV-27A/B Close 14MOV-I IA/B Order RPV cooldown at 4 0 0 degrees per hour with caution that drywell steam leak is contributing to cooldown Trend cooldown and adjust bypass jack and auxiliary steam loads to commence a cooldown at c 100 degrees per hour.
Announce torus pressure 15 psig milestone Ordedconfirm drywell cooling fans and recirculation pumps tripped SNO CRS SNO/RO Keylock override 1 OMOV-27A/B to bypass Keylock override 14MOV-I I A/B Stop Core Spray pumps A/B CRS SNO SNO CRS SNO Trip both recircualtion pumps CRS CRS Confirm operation in safe region of DNV spray initiation limit.
Order drywell sprays using B RHR. Caution SNO to terminate drywell sprays before drywell pressure drops below 0 psig.
LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4 COMMENTS/EVALUATION SAT / UNSAT / NA SAT UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT I NA SAT UNSAT NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA
- CRITICAL TASK
I I
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I SNO Places B RHR in drywell spray observing caution for excessive SAT I UNSAT NA i
1
- CRITICAL TASK I ANY/ALL I Trend and report drop in drywell pressure I SAT / UNSAT / NA 1 I I
I I
I I
I TERMINATE THE SCENARIO I
I I
I I
I LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4
!z w E
I
-..-.-' u F
a S
mi
- 7 James A. FibPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 3 APPL. TO JPM NUMBER REV: 0 DATE: 5/25/03 NRC WA SYSTEM NUMBER: 7 4 41 4.1 JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: L Minutes SUBMITTED:
OPERATION REVIEW:
APPROVED:
\\ I CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
( ) Simulated
( )Performed Lo cat ion :
( ) Plant
( )Simulator DATE PERFORMED:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory EVALUATOR:
SIGNATURE/PRINTED CANDIDATE REVIEW:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER L
Page 1 of 4
JOB PERFORMANGE MEASURE RECORD AND CHECKLIST L-SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECIARATION FOR SCENARIO 3 APPL. TO JPM NUMBER Current Update: 5/25/03 By: RWD Date Int.
Outstanding Items:
Technical Review Questions and Answers Procedural Change Required Comments:
Previous Revision Dates:
Additional Information Validation None Page 2 of 4
i, SRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 3 APPL. TO JPM NUMBER
- 1.
II.
111.
IV.
V.
VI.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
JAF Emergency Plan Implementing Procedures IAP-2, Rev. 23 TOOLS AND EQUIPMENT A.
None SET UP REQUIREMENTS A.
This JPM is completed as followup after the scenario progress has been frozen.
EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and mt actually performed.
B.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
TASK CONDITIONS A.
B.
- - CRITICAL STEP L
a Page 3 of 4
i b SIROINLO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 3 VII.
INITIATING CUE
- 1.
- 2.
- 3.
Based on the events that have just occurred determine if the current circumstances warrant classification in accordance with the JAF Emergency Plan and, if so, determine the appropriate classification level.
STEP Obtain/Approach IAP-2, Attachment 2.1 Recognize the applicable conditions Confirm the conditions STANDARD Candidate obtains the procedure or approaches the posted attachment.
Candidate recognizes that the scenario events included a steam leak in the drywell challenging primary containment intearitv.
Candidate reviews IAP-2 Technical Bases for expected declarations.
Candidate selects ALERT-3.1.1 Primary containment pressure cannot be maintained 2.7 Dsia due to coolant leakaae
--*4. I Classify theevent EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT EVALIIATOB: Terminate the task at this point.
Page 4 of 4
a e
I --
I TITLE:
SCENARIO NUMBER:
NEW LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building PATH:
I SIGNATURE I VALIDATION I TRAINING OPERATIONS L
LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building
v SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED 1
LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building I
I
I A.
J I
LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building B.
CFTIIP:
- 1.
Initial Protected IC-I40
- 2.
Special Instructions:
- a. Plant operating normally at 75% CTP
- b. Confirm Reactor Analyst pull sequence agrees with simulator modeling.
- c. Confirm Reactor Analyst RAP-7.3.1 6 guidance is available at 09-5 panel.
- 3.
Preset Conditions:
- a.
- b.
- c.
- d.
- e.
- f.
- g.
- h.
I.
On trigger 1, MFI-EPO9, Seismic Alarm On trigger 1, AN964: 18, RFP Vibration Crywoif On trigger 1, ZA031VR100 (2) and (3) to 5 mils on 20 minute ramp On trigger 2, RR23:B, B Flow Unit Downscale On trigger 7, MS05 to 50% on 15 minute ramp, MSL leak in Turbine Building Preset RPI 3, MSlV Failure to Automatically Isolate Set Scram to trigger 8 On trigger 8, RFI-HP15, HPCl AOP Breaker Trip Preset AD07:A, E, and K, SRVs fail to operate
- 4.
Consumable Forms and Procedures:
- 5.
Modified Shift Turnover Sheet See Attachment 1 L
LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building
-C.
RY:
Commitment Document:
The crew will relieve the watch at 75% power returning to 100% after a rod pattern adjustment. Shortly into the watch, the EPIC Seismic Event alarm will occur simultaneous with a Reactor Feed Pump vibration alarm in and clear. Shortly after the 'B' Recirculation flow unit will fail downscale prompting a corrective action to bypass the erroneous signal, reset of the half scram and declaring the flow unit inoperable. The seismic event will be confirmed at >.08g requiring a normal reactor shutdown. While performing the AOP-14 actions, additional RFP vibration in and clear alarms will prompt monitoring vibration. The crew will observe a rising trend and dispatch an NPO for local observation. The NPO report will conclude the need to remove the RFP from service. A power reduction with both rods and recirculation flow will end with a normal shutdown of the RFP. The major event will be a slowly worsening Main Steam Line break in the steam tunnel. At the high temperature setpoint, the MSIV's will FAIL to automatically isolate. AOP-40 directed action or recognizing the failure to isolate will cause the crew to manually scram the reactor and manually isolate the MSIV's. Shortly after the scram the HPCI AOP breaker will trip disabeling HPCI. With the leak isolated, the crew will be forced to either depressurize with the SRV's to enable Condensate Booster Pump injection OR establish pressure and level control with RClC and augment pressure control with the SRV's.
Shift Turnover ATTACHMENT 1 L
Currently at 75% Power A rod pattern exchange has just been completed.
1 Return to 100% with Recirculation Flow.
J u
LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building
EVENT L
EVENT SEQUENCE NO.
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
EPIC Seismic Alarm and RFPT Vibration in and clear Flow Unit Downscale Failure RFPT High Vibration Power Reduction using recirculation flow Power reduction using rods Remove RFPT from service MSL Break in Turbine Building, Failure to Auto Isolate HPCl Start Failure Several SRVs fail to operate D.
I.
- 2.
Pressure control on SRVs
- 3.
Leak Isolated Level Control on RClC or CBPs LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Modified Turnover After the shift turnover, allow no more thanfive minutes for panel walkdown COMMENTS/EVALUATION TRG! E l Then delete crywolf Report B RFP vibration is abnormal but not significant TRG! E2 When contacted, report earthquake magnitude at.log Order the commencement of a normal reactor shutdown per Recognize/report half scram B and flow unit off normal Order response per ARPs and local report of Flow Unit status Observe comparator and downscale lamps at 09-14 and reports B flow unit downscale Order bypass of B flow unit and reset of half scram.
Report Earthquake magnitude at.log CRS SAT / UNSAT I NA SAT / UNSAT / NA SAT / UNSAT / NA SAT / UNSAT I NA SAT / UNSAT / NA OP-65 ANYlALL CRS SNOlBOP CRS r
All CRS
~~
ANYIALL SNO/BOP CRS SNOlBOP Walkdown the control panels
~~
Conduct turnover brief. Order return to 100% using recirculation flow Recognize and report EPIC Seismic alarm and RFP B vibration alarm Dispatch NPO to investigate RFP B vibration Order actions of AOP-14 Obtain AOP-14:
Dispatch NPOs to tour plant and component verification I
SAT I UNSAT I NA SAT I UNSAT / NA SAT / UNSAT / NA SAT / UNSAT / NA
~~
SAT / UNSAT / NA
~~~
SAT I UNSAT / NA Contact NMP-2 or National Center for Earthquake Engineering I SNO/BOP I Per ARP 09-5-2-25 and OP-16 E.22, bypass B flow unit I SAT / UNSAT / NA I
1 1
LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building
OPERATOR ACTIONS/STANDARD Per ARP 09-5-1-4, Rest half scram Review ITS 3.3.1.I
.2.b bases and TRM T3.3.B.1 and concludes the flow unit inoperable requires a potential LCO related to APRM operability Share report with CRS
~
I SNO/RO COMMENTS/EVALUATION SAT / UNSAT / NA SAT I UNSAT / NA SAT / UNSAT / NA INSTRUCTOR ACTIVITY POSITION Report as NPO that B RFP vibration is worsening.
Recommend removing from CRS SNO/BOP service.
Upon shutdown, ramp vibrations to 0 over 5 minutes TRG! E7 Order SNO/BOP to perform AOP-40 actions I SAT / UNSAT / NA CRS SAT I UNSAT I NA SNOlBOP SAT / UNSAT I NA CRS SAT / UNSAT / NA SNO/RO Insert first cram group SAT I UNSAT / NA SAT / UNSAT I NA CRS SNO/RO Insert additional cram groups SAT / UNSAT / NA CRS SNO/BOP SAT / UNSAT / NA ANY/ALL Recognizeheport EPIC alarms:
SAT I UNSAT / NA Order power reduction using recirculation flow to not less than 50% core flow.
Commence recirculation flow reduction to -50% core flow.
Order insertion of first cram group.
Order additional cram group(s) to achieve <50% CTP When power <50%, order shutdown of B RFP Shutdown B RFP per OP-2A Turbine Building Ventilation Exhaust LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building NPO reports a large amount of steam coming from TB-272 Condenser Bay through LHRA door SNOIBOP CRS Steam Tunnel Temperature Dispatch NPO with caution to area of steam tunnel SAT I UNSAT I NA
i OPERATOR ACTIONS/STANDARD Report that actions include MSIV closure Isolate Control Room and Relay Room Ventilation Order TSC filtered ventilation started.
Order SNOIRO to perform manual scram and AOP-1 immediate actions Order SNO/BOP to perform level control on Feed and Condensate 177-222.5 inches I
INSTRUCTOR ACTIVITY POSITION SNO/BOP CRS CRS SNOIRO SNO/BOP ANY/ALL CRS CRS SNO Insert Manual Scram
- Mode Switch to Shutdown APRM's Downscale SDlV Vent and Drains closed Trip Turbine Verify Fast Transfer Manipulate RFP controls to stabilize RPV level 177-222.5 inches.
If EOP-2 entry condition occurs, announce.
When scram is successful, order closure of MSIV's Verify at least I circ water pump running Close all 8 MSIV' Order level control transition to HPCl at 177-222.5 inches Order pressure control transition to SRVs at 800-1000 psig.
Operate SRV's in sequence to maintain 800-1 000 psig Observe HPCl failure to start/not available COMMENTS/EVALUATION SAT / UNSAT / NA SAT I UNSAT I NA
- CRITICAL TASK SAT / UNSAT / NA
~~
SAT / UNSAT / NA SAT / UNSAT I NA
- CRITICAL TASK SAT I UNSAT I NA
- CRITICAL TASK SAT I UNSAT I NA SAT / UNSAT / NA SAT / UNSAT I NA LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building
INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD SNO Observe that at least 1 SRV will not operate.
COMMENTS/EVALUATION SAT I UNSAT I NA LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building
~~~
CRS Order level control transition to RClC or Feed and condensate at 177-222.5 inches. If feed and condensate, order new pressure band of 500-700 psig.
Manipulate Feed and Condensate or RClC as directed.
SAT / UNSAT / NA SNO SAT / UNSAT / NA SNO Operate SRV's as directed.
SAT I UNSAT / NA TERMINATE THE SCENARIO
I Shift Turnover I
~~~
Currently at 75% Power A rod pattern exchange has just been completed.
Return to 100% with Recirculation Flow.
n r?
LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building
"Entersy Nuclear Northeast James A. FibPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS JOBPERFORMANCEMEASURE SRO APPL. TO NEW JPM NUMBER TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 4 REV: D DATE: 5/25/03 NRC WA SYSTEM NUMBER: 7 4.41 4 I JAF TASK NUMBER:
ESTIMATED COMPLETION TIME: 1D Minutes JAF QUAL STANDARD NUMBER:
SUBMITTED:
APPROVED:
OPERATION REVIEW:
CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
( ) Simulated Location:
(
) Plant u
( )Performed
( )Simulator DATE PERFORMED:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
EVALUATOR:
SIGNATURE/PRINTED CANDIDATE REVIEW:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER Page 1 of 4
JOB Pk K t UKMANbC dCM5 LKe RECORD AND CHECKLIST USRO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 4 APPL. TO JPM NUMBER Current Update: 5/25/03 By: RWD Date Int.
Outstanding Items:
Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:
Previous Revision Dates:
Page 2 of 4
iCjrr, PCrirG-I \\ l f l h,.PUG i v i c n 3 vnc REQUIRED TASK INFORMATION NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 4 APPL. TO JPM NUMBER
- 1.
II.
111.
IV.
,\\--
V.
VI.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
JAF Emergency Plan Implementing Procedures IAP-2, Rev. 23 TOOLS AND EQUIPMENT A.
None SET UP REQUIREMENTS A.
This JPM is completed as followup after the scenario progress has been frozen.
EVALUATOR NOTES A,
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and nat actually performed.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
B.
TASK CONDITIONS A.
B.
- - CRITICAL STEP U'
Page 3 of 4
(
S/RO/NLO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 4 Vil.
INITIATING CUE
~
~
STANDARD Candidate obtains the procedure or approaches the posted attachment.
Candidate recognizes that the scenario events included a Main Steam Line steam leak in the turbine building resulting in a release pathway outside primary contain men t.
Candidate reviews IAP-2 Technical Bases for expected declarations.
Based on the events that have just occurred determine if the current circumstances warrant classification in accordance with the JAF Emergency Plan and, if so, determine the appropriate classification level.
EVALUATION / COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT Obtain/Approach IAP-2, Attachment
- 3.
Recognize the applicable conditions
- 2.
Confirm the conditions I
Candidate selects I
SAT / UNSAT 8.4.4 Alert Seismic activity >.08g 3.4.1 Site Area Emergency (Transitory)
Any steam line or RWCU isolation failure resulting in a release pathway outside primary containment, Table 3.1 Table 3.1 Steam Lines MSLs HPCl RClC FVAl IJATOR: Terminate the task at this point.
Page 4 of 4