ML032461292

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Draft - Section C Operating
ML032461292
Person / Time
Site: FitzPatrick Constellation icon.png
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)
v • d • e


Text

JAMES A. FITZPATRICK NUCLEAR POWER PLANT NRC INITIAL LICENSE EXAMINATION SCENARIO L 27 MAY 2003 TITLE: LOI-03-01 SCENARIO I,STUCK RODlRWCU LEAK EOP-5 SCENARIO NUMBER: NEW PATH:

SIGNATURE I

VALIDATION TRAINING I OPERATIONS

---./

LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5

- SOURCE OF BRIEF DESCRIPTION OF DATE CHANGE CHANGE INITIATOR REVIEWED v

LOI-03-01 SCENARIO 1, SfUCK ROD/RWCU LEAK EOP-5

LA. TITLE: LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK/EOP-5 B. UP:

1. Initial Protected IC-I37
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. RD10:42-27. Third rod in RWM Group 28 stuck
b. ED24:B on Trigger E-6. Loss of MCC-153 triggered on 12MOV-15 green lamp on.

C. RDI 3:22:27. Control rod 22-27 fails to scram. RMCS insertion still available.

d. TC04:A-D. On event trigger 9. All BPVs fail closed after opening
e. AD07:C and E. Two ADS SRVs fail to open.
f. CU02:A on event trigger 5. RWCU Pump Atrip.
g. 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. 1-131 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. Preparations for and placing Reactor Mode Switch to RUN (Normal)

2. Start of second Condensate Pump (Normal)
3. Continue startup with Rod Withdrawal (Reactivity Manipulation)
4. Stuck Control Rod (AOP-24) (Component and Tech Specs)
5. RWCU pump trip and steam leak into Rx Bldg. {Component)
6. Loss of MCC-152 upon 12NIOV-15 closure
7. Non-isolable RB steam IeaklEOP-5IManual ScramlEmergency Depressurization (Major)
8. I One rod fails to scram (Component)

I

9. BPVs fail closed after opening (Component) 10 2 ADS SRVs fail to open (Component)

D. A T D N CIlF&

.L 1. Emergency Depressurization in progress with 7 SRVs L.

LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5

I I I I INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONWSTANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Modified Turnover After the shift turnover, allow All Walkdown the control panels SAT / UNSAT / NA no more than five minutes for panel walkdown I - I CRS I Conduct turnover brief. Order continuation of OP-65 startup I SAT / UNSAT / NA SNO/BOP Close Main Steam Line Drain Valves (29MOV-101A-D, 77, 78, SAT UNSAT NA 79 and 74)

SNO/RO Place reactor mode switch in RUN SAT / UNSAT I NA Place IRMlAPRM recorder select switches in APRM/RBM Select and Withdraw all 8 IRMs per OP-16 E.9 SNO/BOP Start second condensate pump per OP-3 D.7 SAT / UNSAT / NA SNO/BOP Report to CRS that the plant is ready to continue power SAT / UNSAT / NA

- ascent.

CRS Order in-sequence rod withdrawal SAT / UNSAT / NA SNOlRO Selects and withdraws control rods in sequence. SAT / UNSAT / NA SNO/RO Reports that control rod 42-27 will not move at normal drive SAT / UNSAT / NA pressures. May adjust up to 400 psid per OP-25 Section E.

ANY/ALL Recognize symptom of AOP-24 SAT / UNSAT / NA CRS Order performance of AOP-24 SAT / UNSAT / NA Role Play: After several SNO/BOP Confirm 09-5 panel indications and HCU lineup are normal per SAT I UNSAT I NA minutes report lineup as OP-25 expected.

SNO Incrementally raise drive D/P at 50 psig increments and SAT / UNSAT / NA attempt rod movement after each adjustment.

LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5

I INSTRUCTOR ACTIVITY I POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I SNO Report to CRS that rod will not move with maximum DIP applied.

SAT / UNSAT / NA I SNO Restore CRD hydraulic parameters to normal values SAT / UNSAT / NA I CRS Consult Technical Specification 3.1.3 SAT / UNSAT / NA I CRS

~

Declare control rod 42-27 inoperable and enter condition A. SAT / UNSAT / NA CRS Brief crew on inoperability and required actions SAT / UNSAT I NA TRG! E5 ANY/ALL Recognize and report RWCU pump A trip. SAT / UNSAT I NA CRS Order response per ARPs and local investigations. SAT / UNSAT / NA SNO Dispatch NPO to RWCU panel.

___ _-- SAT / UNSAT

__ / NA __

Role Play: After several SNO Relay report to CRS SAT / UNSAT / NA minutes report a steam leak in overhead area of RWCU pumps on RB 300 foot elevation.

CRS Order actions to trip and isolate RWCU (OP-28, Section G.2) SAT UNSAT / NA SNO/BOP Turn off RWCU pumps SAT / UNSAT / NA Close 12 MOV-I 5, 18, and 69 ANY/ALL Recognize bus loss coincident with valve closures SAT / UNSAT / NA CRS Order investigation of bus loss.

SNOlBOP Determine/report loss of MCC-I 52 I SAT / UNSAT / NA Determinelreport failure of 12MOV-15 to close CU07 severity may need to be CRS Recognize RWCU steam leak is un-isolable. SAT / UNSAT I NA slowly adjusted to drive the rest of the scenario actions by

, trackina temr>eratureson SCT ANY/ALL Recognize EOP-5 entry condition on RB Area SAT / UNSAT / NA TemperaturelRadiation I CRS Enter EOP-5 SAT / UNSAT / NA LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5

i

\ (

INSTRUCTOR ACTIVITY POSITION ~~

OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Execute RBIT, RB/R and RBlL concurrently prioritizing RB/T SAT I UNSAT / NA Order maximizing Reactor Building area cooling SAT / UNSAT / NA 1 SNO/BOP Start all remaining Crescent Area Unit Coolers.

1 CRS Before any RB area Temperature exceeds Max Safe, Order SAT / UNSAT / NA Manual Scram and enter EOP-2

  • CRITICAL TASK Insert Manual Scram and perform AOP-1 Immediate Actions SAT / UNSAT / NA e Depress Manual Scram pushbuttons e Reactor Mode Switch to Shutdown
  • CRITICAL TASK e Fully Insert all SRMs and IRMs e Verify SDlV Vent and Drain valves closed Verify APRMs downscale Verify at least ICirc Water pump running ~ ____ ~~

CRS Order SNO/BOP to level control with FeedlCondensate at 177- SAT / UNSAT I NA 222.5 inches.

SNO/BOP Trend level performance and manipulate GEMAC SAT / UNSAT / NA MasterAndividual controllers, RFP discharge valves and RFP triD as necessary to control level.

S NO/RO Recognize and report that 1 rod failed to scram (22-27) and SAT / UNSAT / NA that another (42-27) was previously stuck and also did not insert Enter EOP-3 based on 2 rods not inserted to or beyond 02 I CRS Order SNO to Pressure Control with EHC in automatic. SAT / UNSAT / NA I SNO Confirm EHC controlling pressure in automatic ~~

SAT / UNSAT / NA

~

Order SNO/RO to initiate ARI SAT / UNSAT / NA 1 SNO/BOP Initiate ARI and confirm all 5 valves energized. SAT / UNSAT / NA I CRS Order SNOlRO to insert control rods per EP-3 SAT / UNSAT I NA LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5

(

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTSEVALUATION If rod 22-27 is attempted, it SNO/RO Determine EP-3 success path is RMCS SAT / UNSAT I NA will insert. Reset ARI by dispatching NPO to Relay Room If rod 42-27 is attempted, it BypassRWM will not SDlV Hi Level Trip Switch to BYPASS Scram Reset Switch to Group 2&3 then I & 4.

To reset ARI:

Establish drive DIP.

RFI-RP20 to test Select control rod Drive in with Rod Movement or Emergency In Control Switch.

CRS May order O/R ADS and TIP Core Spray SAT / UNSAT / NA

~

SNO/BOP If ordered: SAT / UNSAT / NA Both ADS O/R switches to O/R Both 14MOV-1Ivalve keylocks to bypass Close 14MOV-11 A and B SNO/RO Report all rods in except 1 SAT / UNSAT / NA

~~

CRS Exit EOP-3 and enter EOP-2 SAT / UNSAT / NA CRS Recognize that 2 RB area temperatures above rnax safe SAT / UNSAT / NA reauires Emerqencv Depressurization.

CRS Order pressure control on SRV's at a 200 psig band. SAT / UNSAT / NA

~ ~~

If ED is anticipated, TRG! E9 CRS If 2 max safe RB area temperatures are exceeded, announce SAT / UNSAT / NA As BPVs are opening that an emergency depressurization is required.

CRS Enter EOP-2 ED leg and order opening of 7 ADS valves. SAT / UNSAT / NA

  • CRITICAL TASK SNO Open ADS valves A-H (excluding F) SAT / UNSAT / NA

____- . .~ ~ ~.

.-. ~~

  • CRITICAL

. - TASK SNO Report that ADS valves C and E failed to open SAT / UNSAT / NA

  • CRITICAL TASK LOI-03-01 SCENARIO 1, STUCK RODlRWCU LEAK EOP-5

I INSTRUCTOR ACTIVITY POSITION OPERATOR ACTlONSlSTANDARD COMMENTSlEVALUATlON 1 I

CRS Order additional SRV's opened to a total of 7 valves SAT I UNSAT I NA

  • CRITICAL TASK SNO Opens 2 additional SRV's and reports 7 valves open SAT l UNSAT I NA
  • CRITICAL TASK TERMINATE THE SCENARIO LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK EOP-5

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. 1-131 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 Nuclear Northeast James A. FibPatrick Nuclear Power Plant 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: 2 0Minutes 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 REV1EW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER 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 Date Int.

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. SAFETY CONSIDERATJONS A. Ensure proper safety equipment and safety procedures are observed.

II. REFERENCES A. JAF Emergency Pian Implementing Procedures IAP-2, Rev. 23 ill. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. This JPM is completed as followup after the scenario progress has been frozen.

L-V. 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.

VI. TASK CONDITIONS A.

B.

  • - CRITICAL STEP L*

Page 3 of 4

CI, S/RO/NLO NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO I VII. INITIATING CUE 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 ~ ~ ~

STANDARD EVALUATION I COMMENT

1. ObtainlApproach IAP-2, Attachment Candidate obtains the procedure or approaches the SAT / UNSAT 12.1 posted attachment.
2. Recognize the applicable conditions Candidate recognizes that the scenario events included SAT / UNSAT a non isolable RWCU leak into the Reactor Building.

Candidate may also recognize that an Emergency

3. 1 Confirm the conditions DeDressurization was required.

Candidate reviews IAP-2 Technical Bases for expected declarations.

SAT / UNSAT Candidate selects SAT / UNSAT 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 REVIEWED LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUMIAIWS

A

., . JU. LOI-03-01 SCENARIO 1, STUCK ROD/RWCU LEAK/EOP-5 B.

1. Initial Protected IC-I38
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. On Trigger 1, RR19:B fail as is.
b. On Trigger 3, TU04:E at 21% and D at 22% no ramp. (7-9 mils)

C. On Trigger 3, MCOI at 42% severity over 20 minutes.

d. Preset RD22:A at 70%
e. Preset RDO1A:A
4. Consumable Forms and Procedures:

0 AOP-66, MAIN TURBINE HIGH VIBRATION, REV. 3 0 AOP-31, LOSS OF CONDENSER VACUUM, REV. 15 AOP-41/42, FEEDWATER MALFUNCTION, Rev. 6110 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. FWLC Controlling Instrument upscale failure (Instrument and Tech Specs)

2. Swap to alternate FWLC Instrument input and return FWLC to automatic.
3. Step change in Turbine Vibration (Component)
4. Slow loss of condenser vacuum (Component)
5. Power reduction with recirculation flow (Reactivity)
6. Power reduction with rod insertion (Reactivity)
7. ATWSlEOP-3 (Major)
8. SDlV Vent and Drain valve fails to close (Component)

D.

1. Control rods beinghnserted using EP-3
2. level control stable at 0-222.5 inches
3. Pressure control stable

%L, 4. SLC injecting LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Modified Turnover After the shift turnover, allow All Walkdown the control panels SAT / UNSAT / NA no more than five minutes for panel walkdown CRS Conduct turnover brief. Order continuation of power ascent to SAT / UNSAT / NA 100% usinn recirculation flow TRG! E l SNO/BOP Alternatively adjust recirculation MG set speeds in 1-3% SAT / UNSAT / NA increments.

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

~~ ~

SNO Select FWLC to manual, Stabilize and restore RPV level to SAT / UNSAT / NA

~~

nreen band.

CRS Order entry into AOP-41/42 SAT / UNSAT / NA

-~ ~~

SNOlBOP Perform actions of AOP-41/42. Determine that controlling B SAT / UNSAT / NA instrument is failed which caused an actual low RPV level condition.

CRS Order swap to A level transmitter and return FWLC to SAT / UNSAT / NA automatic Der OP-2A SNO/BOP Select OP-2A, section G.30 SAT / UNSAT / NA 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 LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION TRG! E3 ANYIALL Recognize Main Turbine High Vibration condition. SAT / UNSAT / NA CRS Order entry into AOP-66 SAT / UNSAT / NA ROLE PLAY: If requested, SNO Announce turbine bearings 4 and 5 are alarming at elevated SAT UNSAT 1 NA report that there is vibration values (7-9 mils) abnormally high noise levels and vibrations on the Main Turbine elevation (300)

I

~~

ROLE PLAY as Mike Tallents CRS Report abnormal vibration to Main Turbine Expert SAT / UNSAT / NA and acknowledge report.

State that you are coming in May order power reduction using recirculation flow at normal SAT UNSAT / NA

~

rates to attemPt to reduce vibration levels.

~

SNOlBOP If ordered, commence power reduction using recirculation flow. SAT I UNSAT / NA Alternativelv reduce each MG set meed in I-3% increments.

TRG! E4 ANY/ALL

~

Recognize and announce worsening trend in condenser vacuum.

1 SAT / UNSAT / NA CRS Order entry into AOP-31 I SAT / UNSAT I NA I SAT / UNSAT / NA

~~ ~ ~

Monitor and adjust MCOI as SNOIBOP Commence actions of AOP-31 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 CRS Set Manual Scram benchmark of 23-25 inches Hg 1 SAT / UNSAT / NA Order power reduction with recirculation flow to counter SAT / UNSAT / NA vacuum

___ - _- - trend. Caution against reducing

_ _ _ below

. - 50%-core flow. --

Reduce recircualtion flow to -50% Core Flow. SAT I UNSAT / NA I ANY/ALL Recognirelreport that condenser vacuum is still worsening SAT / UNSAT / NA -

LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS

( i v I

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTSlEVALUATlON :

CRS Order insertion of the first cram group. SAT / UNSAT / NA ROLE PLAY: As NPO, report SNO/RO Select and fully insert all rods in the first cram group SAT / UNSAT / NA i that there is a visible tear in i the exhaust boot of LP turbine B.

Monitor and adjust MCOI as ANWALL Recognize/report that condenser vacuum is still worsening necessary to force manual scram Delete TU04: D and E CRS Order Manual Scram SAT I UNSAT / NA SNO/RO Insert Manual Scram and perform AOP-1 Immediate Actions SAT / UNSAT / NA 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 ~

CRS Order SNOlBOP to level control with Feed and Condensate SAT / UNSAT I NA 177-222.5 inches SNO/BOP Manipulate RFP, GEMAC Controllers and RFP Discharge SAT I UNSAT I NA

~~

valves to control RPV level.

~ ~

SNO/RO Report multiple rods out, APRMs NOT downscale and one SAT / UNSAT I NA SDlV Vent valve failed to close.

  • CRITICAL TASK LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS

('

INSTRUCTOR ACTIVITY POSITION 2RS

~

OPERATOR ACTIONS/STANDARD Order SNO/RO to perform the following EOP-3 actions COMMENTS/EVALUATION SAT I UNSAT / NA iI B Initiate ARI Reduce recirculation flow to minimum

' CRITICAL TASK i Trip both recirculation pumps Override ADS Determine EP-3 success path and insert rods.

CRS Order SNOlBOP to terminate and prevent all injection except SAT / UNSAT / NA I

SLC, CRD and RClC per EP-5. New level band is -1 9 to 1I O . I Injection source will be Feedwater. Caution against rapid

  • CRITICAL TASK ,

iniection.

SNO/BOP Perform the following EOP-3IEP-5 level control actions: SAT / UNSAT / NA Reduce running RFP(s) MIA stations to manual minimum.

  • CRITICAL TASK Ensure running RFP min flow valve(s) open Depress HPCl Turbine Trip pushbutton. ~ ~~~

SNO 10MOV-27A/B Auto Control to bypass and close IOMOV- SAT / UNSAT / NA 27A/B (May be deferred) 14MOV-1IA/B Auto Actuation to Bypass and close 14MOV-I 1AIB (may be deferred) ~~

CRS Order SNO to pressure control with EHC in automatic. Band of SAT I UNSAT I NA 900-1000 psig. ~

SNO Confirm EHC in automatic controlling RPV pressure in band. SAT / UNSAT I NA Adjust MCOI to force loss of SNO/BOP Reinject with HPCl by: SAT / UNSAT I NA Bypass Valves Ensure SGT running Ensure 01-125MOV-13A or B is open Ensure HPCl flow controller in Manual minimum Depress turbine trip reset Verify automatic initiation lineup Control speed to control injection LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS

i' INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I SNO/RO Perform the following EOP-3 actions: SAT I UNSAT / NA Select ARI Switch to ACT

  • CRITICAL TASK 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 CRS Order control rod insertion with EP-3 success paths SAT / UNSAT / NA SNO/RO NOTE: SNO/RO should pursue both paths in that RMCS can SAT / UNSAT / NA complete partial insertions while SDIV's are draining to enable Manual scrams.

To reset ARI, RFI-RP20 to SNO/RO EP-3 RMCS path actions: SAT / UNSAT I NA Test Dispatch NPO to reset ARI and observe solenoids de-

  • CRITICAL TASK energized. (if not already done)

RWM Keylock to Bypass Raise drive water DIP. Options include shut CRD-56, Start second CRD pump, manually adjust FIC-301 to open AOV-19A(B)

Select and drive rod full in in EP-3 attachment sequence.

Monitor and adjust MCOI as ANY/ALL Recognize that as condenser vacuum continues to worsen, SAT / UNSAT / NA necessary to force RFP trip Pressure control will need to transition to HPCl augmented with and loss of bypass valves SRV's.

CRS If not already done, order SLC injection with either system. SAT / UNSAT I NA SLC injection is required prior to exceeding BIIT.

  • CRITICAL TASK SNO Select SLC control switch to ordered division and report tank SAT / UNSAT / NA level.
  • CRITICAL TASK CRS Order transition of RPV pressure control to HPCl and augment SAT / UNSAT / NA with SRVs. Modify band to 800-1000 psig.

LOI-03-01 SCENARIO 2, TURBINE VIBRATION/LOSS OF VACUUM/ATWS

\

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SNO To transition Pressure Control. SAT / UNSAT / NA Augment HPCl operation with sequential opening of SRVs to maintain 800-1000 psig SNO Report downward trend in SLC tank level. SAT / UNSAT / NA RFI- RP21:AI, A2, B I , and SNOlRO EP-3 Manual Scram path actions SAT / UNSAT / NA Dispatch NPO to reset ARI and observe solenoids de-

  • CRITICAL TASK energized (if not already done)

Order/hang 09-15/17 auto scram jumpers.

Open CRD-56 if closed.

When the scram is reset, SDlV Hi Level Trip to Bypass delete malfunction RD22A Rx Scram Reset to Group 2 and 3 then 1 and 4.

When SDIVs are drained insert Manual Scram

~

CRS When all rods in exit EOP-3 and enter EOP-2 SAT / UNSAT / NA

-~ -~~ ~~ ~

TERMINATE THE SCENARIO 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

- a Entegy

-z-zz-s Nuclear Northeast James A. FibPatrick Nuclear Power Plant

'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: , 1 0Minutes SUBMITTED: OPERATION REVIEW:

APPROVED:

CANDIDATE NAME: S.S. NUMBER:

JPM Completion: ( ) Simulated ( )Performed

~L4-Location: ( ) Plant ( )Simulator DATE PERFORMED: TIME TO COMPLETE: -Minutes PERFORMANCE EVALUATION: ( ) Satisfactory ( ) Unsatisfactory EVALUATOR:

SIGNATUREIPRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER Page 1 of 4

L-1SRO 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 Date Int.

Outstanding Items:

-Technical Review Additional Information

-Questions and Answers -Validation

-Procedural Change Required -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 LAR ,TION FOR SCENARIO 2 APPL. TO JPM NUMBER

1. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.
11. REFERENCES A. JAF Emergency Plan Implementing Procedures IAP-2, Rev. 23 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. This JPM is completed as followup after the scenario progress has been frozen.

u V. 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 fight indication when equipment operation is simulated.

VI. TASK CONDITIONS A.

B.

  • - CRITICAL STEP

'v Page 3 of 4

S/RO/NLO

< NEW

.?4

(

/

i TASK TITLE: LOI-03-01 NRC EXA /lE-PL DECLARATION FOR SCENARIO 2 VII. INITIATING CUE 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

~

STANDARD EVALUATION / COMMENT I, Obtain/Approach IAP-2, Attachment Candidate obtains the procedure or approaches the SAT / UNSAT 2.1 posted attachment.

2. Recognize the applicable conditions Candidate recognizes that the scenario events included SAT / UNSAT an ATWS condition with a challenge to primary

~

containment intearitv.

3. Confirm the conditions Candidate reviews IAP-2 Technical Bases for expected SAT / UNSAT declarations.
  • 4. Classify the event Candidate selects SAE-2.2.2 SAT / UNSAT 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 AND Either:

Reactor power > 2.5%

OR Torus temperature > Boron Injection Initiation TemDerature 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: LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4 SCENARIO NUMBER: NEW 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 REVIEWED LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4

\-- A. IlILE 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-2at 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).
b. OG04 on Trigger E-3, Combustion in Off-Gas
c. Annunciator 09-6-1-23 crywolf on Trigger E-3
d. Recombiner trip on Trigger E-3
e. RR15:A on Trigger E-6 at 50% severity and 10 minute ramp, Steam Leak in Drywell.

-- f.

g.

Preset RD13:XX:W, One rod fail to scram ED18:X on Fast transfer trigger assigned to Trigger E-7, Loss of 10500 Bus.

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-03-01SCENARIO 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 c

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.

~-..

LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4

' EVENT EVENT SEQUENCE I NO.

I. Swap in service Service Water pumps (Normal)

2. LPRM Upscale failure/APRM half scram (Instrument and Tech Specs)
3. Combustion in SJAE After Condenser (AOP-5) (Component)
4. AOP-5 directed Dower reduction with recirculation flow IReactivitv)
5. AOP-5 directed power reduction with Control Rods (Reactivity)
6. Steam leak in the Drywell (Major)
7. Loss of 10500 bus (Component)

D. CI IF&

1. Completion of 1 Drywell Spray Evolution LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4

I INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONWSTAN DARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Modified Turnover After the shift turnover, allow All Walkdown the control panels SAT / UNSAT / NA no more than five minutes for Dane1 walkdown CRS Conduct turnover brief. Order coordination with field to start C SAT I UNSAT / NA SW pump and place B in STBY per OP-42 G.l SNO/BOP Start C SW pump. Stop B and place in Standby SAT / UNSAT / NA TRG! E2 ANY/ALL Recognize/Report LPRMIAPRM upscale trend. Determine SAT / UNSAT / NA failed LPRM is 36-13-8 SNO/RO Report that all other APRMs are stable. SAT / UNSAT / NA CRS Order bypass of LPRM 36-13-8 per OP-16 SAT / UNSAT I NA SNO/BOP CRS Recognize that APRM is inoperable on 2 per level criteria and SAT UNSAT NA consult Tech Specs 3.3.1. I and TRM 3.3.B.1. Determine that no condition entry is required.

LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4

f ,

OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION TRG! E3 ANYlALL RecognizelReport indications of combustion in SJAE after SAT / UNSAT / NA condenser.

Cause of recombiner trip is low outlet temperature I CRS Announce entry to AOP-5. Direct SNO/BOP to perform actions of AOP-5 SAT uNSAT / NA SNO/BOP Perform the following actions: SAT / UNSAT I NA Dispatch NPO to place additional SJAEs in service.

e Report to CRS that power reduction is required until 40% or fire is extinguished.

CRS Brief crew and direct SNO/BOP to reduce power using SAT / UNSAT / NA recirculation flow to 50% core flow or the fire is out.

NOTE: CRS judgment on desired power ramp rate.

SNO/BOP Alternatively adjust Recirculation GEMAC controllers in 1-3% SAT / UNSAT / NA increments I OR Concurrently reduce both GEMACs at a rapid rate without causing RPV Hi Water level trip.

SNOlRO Monitor power/pressure/level during downpower. SAT / UNSAT / NA SNO/BOP Report Core Flow at - 50% and combustion still indicated. SAT / UNSAT / NA CRS Order SNO/RO to insert the first cram group SAT / UNSAT / NA SNO/RO Select and fully insert all rods in the cram group. SAT / UNSAT / NA DELETE OG04 ANY/ALL Recognize that combustion has extinguished. SAT / UNSAT / NA CRS Order chemistry to complete a confirmatory hydrogen sample. SAT UNSAT NA TRG! E6 ANY/ALL Recognize indications of steam leak in drywell SAT

_ _-_ - - _____ ---. _ - _ _ . - . __ / UNSAT / NA I CRS

~

Order establishment of a Torus Vent per OP-37 SAT / UNSAT / NA I I

Set a benchmark for a manual scram of 2-2.3 psig drywell pressure.

1  !

SNO/BOP Commence actions to establish Torus vent.

LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4 SAT / UNSAT / NA -I

I INSTRUCTOR ACTIVITY I POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I ANY/ALL Recognize/Report manual scram benchmark SAT / UNSAT / NA I SNO/RO 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 CRS Order SNO/BOP to level control with FeedICondensate at 177- SAT / UNSAT / NA 222.5 inches.

1

~

SNO/BOP Trend level performance and manipulate GEMAC Master/lndividual controllers, RFP discharge valves and RFP trip as necessary to control level.

I SNO/RO Recognize and report that 1 rod failed to scram and that the SAT / UNSAT / NA 10500 is de-energized with A and C EDGs running Role Play: Report as NPO SNO Dispatch NPO to assess status of 10500 bus and EDGs SAT / UNSAT / NA that 10500 bus has heavy damage at the 10514 breaker and heavy smell of burnt insulation.

CRS Order SNO to Pressure Control with EHC in automatic. SAT / UNSAT / NA 1 SNO Confirm EHC controlling pressure in automatic SAT / UNSAT / NA 1 CRS Order EDG A and C shutdown SAT / UNSAT / NA 1 SNO Shutdown EDG A and C SAT / UNSAT / NA I ANY/ALL Recognize/Report EOP2/4 entry condition on DNV pressure SAT / UNSAT / NA I CRS Announce entry into EOP-2 and 4 SAT / UNSAT / NA LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4

( (

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION ANYlALL RecognizelReport HPCl initiation SAT / UNSAT / NA CRS Determine HPCl injection not needed and order HPCl tripped SAT UNSAT / NA SNO Trip HPCl SAT / UNSAT / NA RR15:A severity may need to CRS When torus pressure >2.7 psig order 6 loop of RHR in torus SAT / UNSAT / NA De adjusted to force scenario spray with excess flow to torus cooling.

milestones SNO Startup B loop RHR in Torus Spray. Excess flow to torus SAT / UNSAT I NA cooling while observing current limitation on RHR pump.

CRS Set a torus pressure benchmark of 15 psig. Order terminate SAT UNSAT NA and prevent RHR and Core Spray per EP-5 SNO/RO Keylock override 1OMOV-27A/B to bypass SAT / UNSAT / NA Close IOMOV-27A/B Keylock override 14MOV-I IA/B Close 14MOV-I IA/B Stop Core Spray pumps A/B CRS Order RPV cooldown at 4 0 0 degrees per hour with caution SAT / UNSAT / NA that drywell steam leak is contributing to cooldown SNO Trend cooldown and adjust bypass jack and auxiliary steam SAT / UNSAT / NA loads to commence a cooldown at c 100 degrees per hour.

SNO Announce torus pressure 15 psig milestone SAT I UNSAT / NA CRS Ordedconfirm drywell cooling fans and recirculation pumps SAT / UNSAT / NA tripped SNO Trip both recircualtion pumps SAT / UNSAT / NA CRS Confirm operation in safe region of DNV spray initiation limit. SAT / UNSAT / NA CRS Order drywell sprays using B RHR. Caution SNO to terminate

  • CRITICAL TASK drywell sprays before drywell pressure drops below 0 psig.

LOI-03-01 SCENARIO 3, Combustion in After Condenser, Steam Leak in Drywell, EOP-4

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

  • CRITICAL TASK 1

I ANY/ALL I Trend and report drop in drywell pressure I SAT / UNSAT / NA I

1 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

!wz E

I

-..-.-' u Fa

.-S mi

--- - 7 Nuclear Northeast James A. FibPatrick Nuclear Power Plant 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: LMinutes SUBMITTED: OPERATION REVIEW:

APPROVED: \ I CANDIDATE NAME: S.S. NUMBER:

JPM Completion: ( ) Simulated ( )Performed Location: ( ) 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 Additional Information

-Questions and Answers . - , Validation

-Procedural Change Required -None Comments:

Previous Revision Dates:

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. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.

II. REFERENCES A. JAF Emergency Plan Implementing Procedures IAP-2, Rev. 23 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. This JPM is completed as followup after the scenario progress has been frozen.

V. 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.

VI. 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 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 STANDARD EVALUATION I COMMENT

1. Obtain/Approach IAP-2, Attachment Candidate obtains the procedure or approaches the SAT / UNSAT 2.1 posted attachment.
2. Recognize the applicable conditions Candidate recognizes that the scenario events included SAT / UNSAT a steam leak in the drywell challenging primary containment intearitv.
3. Confirm the conditions Candidate reviews IAP-2 Technical Bases for expected SAT / UNSAT declarations.

--*4. I Classify theevent Candidate selects ALERT-3.1.1 Primary containment pressure cannot be SAT / UNSAT maintained 2.7 Dsia due to coolant leakaae EVALIIATOB: Terminate the task at this point.

Page 4 of 4

a e

I --

I TITLE: LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building SCENARIO NUMBER: NEW PATH:

I I VALIDATION SIGNATURE 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 I I LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building

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-7.3.16 guidance is available at 09-5 panel.
3. Preset Conditions:
a. On trigger 1, MFI-EPO9, Seismic Alarm
b. On trigger 1, AN964: 18, RFP Vibration Crywoif
c. On trigger 1, ZA031VR100 (2) and (3) to 5 mils on 20 minute ramp
d. On trigger 2, RR23:B, B Flow Unit Downscale
e. On trigger 7, MS05 to 50% on 15 minute ramp, MSL leak in Turbine Building
f. Preset RPI 3, MSlV Failure to Automatically Isolate
g. Set Scram to trigger 8
h. On trigger 8, RFI-HP15, HPCl AOP Breaker Trip I. Preset AD07:A, E, and K, SRVs fail to operate L
4. Consumable Forms and Procedures:

AOP-40 AOP-1 AOP-14

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

L EVENT EVENT SEQUENCE NO.

1. EPIC Seismic Alarm and RFPT Vibration in and clear
2. Flow Unit Downscale Failure
3. RFPT High Vibration
4. Power Reduction using recirculation flow
5. Power reduction using rods
6. Remove RFPT from service
7. MSL Break in Turbine Building, Failure to Auto Isolate
8. HPCl Start Failure
9. Several SRVs fail to operate D.

I. Level Control on RClC or CBPs

2. Pressure control on SRVs
3. Leak Isolated LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION Simulator in RUN Recorder and Alarm Power ON Simulator Checklist Complete Provide Modified Turnover After the shift turnover, allow All Walkdown the control panels SAT I UNSAT I NA no more thanfive minutes for panel walkdown ~~

CRS Conduct turnover brief. Order return to 100% using SAT I UNSAT / NA

~~

recirculation flow TRG! E l ANYIALL Recognize and report EPIC Seismic alarm and RFP B SAT / UNSAT / NA vibration alarm Then delete crywolf Report B RFP vibration is SNO/BOP Dispatch NPO to investigate RFP B vibration SAT / UNSAT / NA abnormal but not significant ~~

CRS Order actions of AOP-14 SAT / UNSAT / NA

~~~

When contacted, report SNOlBOP Obtain AOP-14: SAT I UNSAT / NA earthquake magnitude at .log Dispatch NPOs to tour plant and component verification I

Contact NMP-2 or National Center for Earthquake Engineering Report Earthquake magnitude at .log CRS Order the commencement of a normal reactor shutdown per SAT / UNSAT I NA OP-65 TRG! E2 ANYlALL Recognize/report half scram B and flow unit off normal SAT / UNSAT / NA CRS Order response per ARPs and local report of Flow Unit status SAT / UNSAT / NA SNOlBOP Observe comparator and downscale lamps at 09-14 and SAT / UNSAT I NA reports B flow unit downscale CRS Order bypass of B flow unit and reset of half scram. SAT / UNSAT / NA r

I SNO/BOP I Per ARP 09-5-2-25 and OP-16 E.22, bypass I 1

_. B flow unit I SAT / UNSAT / NA 1 -

LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION I SNO/RO

~

Per ARP 09-5-1-4, Rest half scram SAT / UNSAT / NA CRS Review ITS 3.3.1.I .2.b bases and TRM T3.3.B.1 and SAT I UNSAT / NA concludes the flow unit inoperable requires a potential LCO related to APRM operability Report as NPO that B RFP SNO/BOP Share report with CRS SAT / UNSAT / NA vibration is worsening.

Recommend removing from service.

CRS Order power reduction using recirculation flow to not less than SAT I UNSAT I NA 50% core flow.

SNOlBOP Commence recirculation flow reduction to -50% core flow. SAT / UNSAT I NA CRS Order insertion of first cram group. SAT / UNSAT / NA SNO/RO Insert first cram group SAT I UNSAT / NA CRS Order additional cram group(s) to achieve <50% CTP

______ ____ SAT / -UNSAT I NA SNO/RO Insert additional cram groups SAT / UNSAT / NA CRS When power <50%, order shutdown of B RFP Upon shutdown, ramp SNO/BOP Shutdown B RFP per OP-2A SAT / UNSAT / NA vibrations to 0 over 5 minutes TRG! E7 ANY/ALL Recognizeheport EPIC alarms: SAT I UNSAT / NA Turbine Building Ventilation Exhaust Steam Tunnel Temperature NPO reports a large amount SNOIBOP Dispatch NPO with caution to area of steam tunnel SAT I UNSAT I NA of steam coming from TB-272 Condenser Bay through LHRA door CRS Order SNO/BOP to perform AOP-40 actions I SAT / UNSAT / NA LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building

i I

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SNO/BOP Report that actions include MSIV closure SAT / UNSAT / NA Isolate Control Room and Relay Room Ventilation Order TSC filtered ventilation started.

CRS Order SNOIRO to perform manual scram and AOP-1 SAT I UNSAT I NA immediate actions

  • CRITICAL TASK CRS Order SNO/BOP to perform level control on Feed and SAT / UNSAT I NA Condensate 177-222.5 inches SNOIRO Insert Manual Scram
  • SAT / UNSAT I NA Mode Switch to Shutdown
  • CRITICAL TASK APRM's Downscale SDlV Vent and Drains closed Trip Turbine Verify Fast Transfer Verify at least Icirc water pump running SNO/BOP Manipulate RFP controls to stabilize RPV level 177-222.5 SAT / UNSAT / NA inches. ~~

ANY/ALL If EOP-2 entry condition occurs, announce. SAT / UNSAT / NA CRS When scram is successful, order closure of MSIV's SAT / UNSAT I NA

  • CRITICAL TASK Close all 8 MSIV' SAT I UNSAT I NA
  • CRITICAL TASK CRS Order level control transition to HPCl at 177-222.5 inches SAT I UNSAT I NA Order pressure control transition to SRVs at 800-1000 psig.

SNO Operate SRV's in sequence to maintain 800-1000 psig SAT / UNSAT / NA Observe HPCl failure to start/not available SAT / UNSAT I NA LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building

INSTRUCTOR ACTIVITY POSITION OPERATOR ACTIONS/STANDARD COMMENTS/EVALUATION SNO Observe that at least 1 SRV will not operate. SAT I UNSAT I NA

. ~~~

CRS Order level control transition to RClC or Feed and condensate SAT / UNSAT / NA at 177-222.5 inches. If feed and condensate, order new pressure band of 500-700 psig.

SNO Manipulate Feed and Condensate or RClC as directed. SAT / UNSAT / NA SNO Operate SRV's as directed. SAT I UNSAT / NA TERMINATE THE SCENARIO LOI-03-01 SCENARIO 4, Seismic Event, MSL Break in Turbine Building

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 NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 4 APPL. TO JPM NUMBER REV: D DATE: 5/25/03 NRC WA SYSTEM NUMBER: 7 4.41 4 I JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 1 DMinutes SUBMITTED: OPERATION REVIEW:

APPROVED:

CANDIDATE NAME: S.S. NUMBER:

JPM Completion: ( ) Simulated ( )Performed u

Location: ( ) Plant ( )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 PkK tUKMANbC dCM5LKe 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 v n c REQUIRED TASK INFORMATION NEW TASK TITLE: LOI-03-01 NRC EXAM E-PLAN DECLARATION FOR SCENARIO 4 APPL. TO JPM NUMBER

1. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.

II. REFERENCES A. JAF Emergency Plan Implementing Procedures IAP-2, Rev. 23 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. This JPM is completed as followup after the scenario progress has been frozen.

,\--

V. 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.

VI. 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 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.

- ~ ~

STANDARD EVALUATION / COMMENT Obtain/Approach IAP-2, Attachment Candidate obtains the procedure or approaches the SAT / UNSAT posted attachment.

Recognize the applicable conditions Candidate recognizes that the scenario events included SAT / UNSAT 2.

a Main Steam Line steam leak in the turbine building resulting in a release pathway outside primary containment .

3. Confirm the conditions Candidate reviews IAP-2 Technical Bases for expected SAT / UNSAT I

declarations.

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

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