ML19207B834

From kanterella
Jump to navigation Jump to search
Forwards Simulator Retraining Program as Required by NRC Licensed Operator Requalification Program
ML19207B834
Person / Time
Site: Pilgrim
Issue date: 08/28/1979
From: Mcguire P
BOSTON EDISON CO.
To: Collins P
Office of Nuclear Reactor Regulation
References
79-169, NUDOCS 7909050396
Download: ML19207B834 (37)
v • d • e


Text

"t 'l August 28, 1979 BECo Letter #79-169 Director of Nuclear Reactor Regulation Attention: Mr. Paul F. Collins, Chief Operator Licensing Branch U.S. Nuclear Regulatory Commission Washington, D. C. 20555 License No.: DPR-35 Docket No.: 50-293 Gentlemen: ,

t t In accordance with Pilgrim Nuclear Power Station's NRC Licensed Operator Requal-ification Program the attached Simulator Retraining Program is submitted for your approval.

As discussed with your Mr. J. Holman, each class will represent a normal watch section consisting of a Watch Engineer, Watch Supervisor, three NPO's and one licensed management person. It is intended thrt scenarios shown on the attach-ment will not be given in a numerical sequence, but be mixed to reduce anticipa-tion of "what's next" from class to class. Each licensed operator's record of approved reactivity manipulation will be reviewed to ensure that he will be on Panel 905 for any situation which he hasn't accomplished in the last year. During scenarios consisting of major emergency procedures the individuals will be assigned their normal watch assign =ent to develop a team concept in response to the situation.

If you have any further questions, please contact us.

Very truly yours, P. J. McGuire Station Manager Nuclear Operations

/cf Attachments General Electric's Letter Dated 8/23/79 Scenarios Q t g(

,, m e* , 0 ~"

7909050 376 25\

.- NUCLEAR ENERGY h a b a PROJECTS DIVISION BOIL!NG WATER REACTOR SERVICES DEPARTMENT ,

GENERAL ELECTRIC CCMPANY,7655 EAST COLLINS RD., MORRIS, ILLINOIS 60450 BOLLING WATER REACTOR Phone (815) 942-5790 TRAINING CENTER JCG-79-19 August 23, 1979 Mr. R. Morris Pilgrim fluclear Power Station R. R. #1 Rocky Hill Road Plymouth, Massachusetts 02360

Dear Sob,

inclosed you will find two copies of the scenarios that we will be tsing for your retraining to be conducted here at the training center.

Please check them over and make corrections as you see fit. We can discuss the changes when I come out to the site the week of September 17.

I will have Ron Greiner with ne who will be the instructor for the retraining sessions. He will need to spend two or three days orienting himself to your control room to familiarize himself there. This will aid him when he is back here to simulate your plant with our control room.

The retraining sessions which we will conduct will have the same genercl format for each group as discussed below.

1. Each class will be four days in length with six of your people in each class. A senior licensed instructor from our staff will be the instructor for these classes. He will be assisted by someone from your organization who will assist him with some of the technical details.
2. The four day sessions will include normal startuo and shutdown operations,.

casualty drills to be imposed during the normal evolutions, surveillance testing, and discussions. The discussions will include theoretical, operational, and procedural aspects of all evolutiosn being performed by the students.

3. An evaluation / documentation form will be completed on each individual by our instrutor. It will list the various evolutions he performs, and give an evaluation of the nan's performance in the areas observed. These sheets will be forwarded to you at the conclusion of the last retraining session.
c. , c e , . n s) m.t.} >4 L2 ' 2

. i 2

4 As we discussed during your visit here, the casualties imposed c i the students will 'o e as realistic as our simulator is capable of for the Pilgrim plant. They will vary from simple system trips to the Design Basis Accident and include ATWS conditions from time to time. Each transient will have a critique at the conclusion of it to discuss the actions taken, any further actions which should have taken place, and to clarify questions which the students nay have.

5. A separate independent evaluation _ of each student will be performed by a senior staff member during the last day of retraining.

I will be out to Pilgrim along with Ron Greiner hopefully the week of September 24. If you have any further questions, please do not hesitate to call.

Sincerely ,

O  ?'

VJ. C. Griffin,h Manager Training Projects 11 Operator Training Services - Morris Je

c. , -: m -

O A debtiA4

TABLE OF CCNTENTS SCENARIO l' -

  • 100% Reactor Power CRD Flow Control Failure APRM Failure Feedwater Pump Failure Fire in Vital Bus SCENARIO 2 - *20% Reactor Power Power Increase Ground on DC Power Loss of Cleanup System High Process Radiation High Conductivity Stator Water System Recirculation Pump Trip Loss of Both RPS Buses Steam Leak in Drywell SCENARIO 3 -
  • 100% Reactor Power Recirculation MG Ground Area Radiation Monitor High Cable Tunnel Fire SCENARIO 4 -
  • 100% Reactor Power Stuck Open Relief Valve Off Gas High Activity Master Level Controller Failure Feedwater Heater String Iscl:-ion RPS Bus Failure Steam Leak in Drywell SCENARIO 5 -
  • 100% Reactor Power AVR Failure Reactor Seal Ring Leakage Startup Transformer Sea Water Leak in Condenser Loss of HP CSCS 013C.'dk

TABLE OF CONTENTS (Continued)

SCENARIO 6 - *850 lbs. Heatup in Progress Bypass Valve Failure Stuck Control Rod Recirculation Pump Trip Scram Valve Air Leak CRD Flow Control Failure Master Level Control Failure SCENARIO 7 -

  • Scram Recovery Stuck Control Rod Turbine Hood Spray Failure CRD Pump Trip SBLC High Temperature Feedwater Regulatien Valve failure SCENARIO 8 -
  • Hot Scram Recovery CRD Pump Failure Off Gas High Flow Condensate Pump Failu"e Feedwater Heater Stri: 3 Isola tion Stuck Control Rod CRD Pump Failure (spare)

Loss of Offsite Power SCENARIO 9 -

  • 50% Reactor Power Power Increase Stuck Control Rod Bypass Valves Fail Open ATWS SCENARIO 10 - *150 l bs. Heatup in Drogress Power Increase Uncoupled Control Rod Relief Valve Fail Cpen Vessel Flood Coul down Steam Leak in Drywall

OI.'$.CR

TABLE OF CONTENTS (Continued)

SCENARIO 11 -

  • 100% Reactor Power Off Gas Explosion Loss of Offsite Power Area High Radiation
  • 50% Reactor Power Shutdown Loss of Reactor Control Panel ATWS SCENARIO 12 -
  • 850 lbs. Startup Loss of 4 kV Bus Loss of Offsite Power Rupture in Drywell SCENARIO 13 -
  • 50% Reactor Power Power Increase Recirculation Pump Seal Leak Feedsater Regulation Valve Lockup Recirculation Pump Trip Steam Leak in Drywell
  • l65 F. Startup SRM Detector Stuck Accumulator Trouble IRM Failure CRD Flow Control Valve Failure Major Leak Inside Drywell
  • 850 lbs. Startup APRM Downscale Scram Valve Leak Feedwater Regulation Valve Failure 3102b8

TABLE OF CONTEllTS' (Continued)

SCEllARIa 14 -

  • 50% Reactor Power Power Reduction
  • Hot Scram Recovery IRM Failure Control Rod Stuck Shutdown to Hot Standby Failure of Bypass Valves SCE?lARIO 15 -
  • 100% Reactor Power Loss of Offsite Power loss of Seal Steam

- Loss of Condenser Vacuum Failure of Turbine Control and Bypass Valves

SCENARIO 1 Time No tes Probl em 0 Initialize at Mode 10 100% power.

Hotwell level increasing Orders:

. Weekly & Daily Turbine checks

. D/G surveillances, one at a time - shift to Droop Control

. Core Spray surveillance Allow students to perform surveill ances . Trip A Core Spray Pump immediately after start.

30 min. Trip A Core Spray pump (due to overcurrent - pump bearing frozen).

Insure students discuss technical specifications and perform required actions.

1 hr. Fail CRD flow control valve shut.

(due to electrical failure)

Spare CR0 flow contriel valve will work - insure students valve it in properly.

1 hr. 30 min. Discuss Hi flux vs. APRi Full Scale (cause unknown) electrical failure of APRM with students.

Store Snaoshot 310..$ s~l

SCENARIO 1 (Continued)

Time No tes Pro bl em 2 br. RFP 2A Hi vibration. Feedwater pump failure (low suction trip electrical failure) Note reactor rectre runback to 65% if water level drops < 19" .

If scram occurs, carry thrcugh until plant ready to restart. Then re- Turbine building ARM Hi initialize into Snapshot (due to sensor failed Hi) mode.

2 hr. 45 min. Equipment operator reports thin white smoke from Eus (A5).

Students s! auld work to remove Bus frca service and secure equipment as necessa ry.

Continue with this problem until end of class.

313.261

SCENARIO 2 Time No tes Probl em -

0 I61tialize at Mode 8 Give Main Steam Line High Radiation 20% power. downscale prior to initialization.

(Failure mode unknown.)

Orders:

. Synchronize generator H2 pressure low with grid.

. Transfer house loads.

. Increase power to 100%

load line.

Allow students to recognize MSL High Radiation downscale has not cleared.

30 min. Casualty prior to generator 125V DC battery ground synchronization.

32 min. Fire protection deluge control power failure (due to grounded wire).

1 hr. Cleanup isolation on high Loss of Cleanup demineralizer inlet tem-perature 1 hr.15 min. Discuss loss of cleanup effect on reactor operation.

I hr. 30 min. Equipment operator reports Stator water cooling panel cogductivity of 4.9 umho/ troubl e.

cm 5 minutes after sent to local panel .

2 hr. Clear casualty after pump Recirculation Pump A high trip. vibration.

{j f nd.c,s i '

SCENARIO 2 (Continued)

Time No tes Probl em 2 hr. 45 min. Recirculation Pump B Speed Feedback signal failure.

3 hr. Allow B CRD pump to start. Trip A CRD pump. (Due to over-current - bearing fro;en.)

3 hr.15 min. Loss of power to RPS Bus A.

3 hr. 30 min. RPS Bus B lost while Loss of power to RPS Bus B.

trans fer o f RPS Bus A.

After scram and mode switch is out of Run, give Steam leak in drywell .

steam leak in drywell .

Continue with casualty until end of class.

81.3.E.) T?,

SCENARIO 3 Time No tes Probl em 0 Initiali:e at Mode 10 100% power.

. Tag out stator cooling Pump B

. D/G 2 Fail to Start

. On limiting rod pattern Orders:

. Maintain 800 MWe.

. D/G surveillances 30 min. Loss of stator cooling pump A 1 hr. When power is reduced for Recirculation MG Set A generator shutdown, Recirculation ground.

MG Set A generator ground al a rm. Allcw operator to manually trip Recirculation MG set.

1 hr.10 min. Equipment operator does not Announce small cable tunnel fire.

report back status.

1 hr. 30 min. Clear after recharging. Accumulator trouble.

1 hr. 45 min. RBM Downscale 2 hr. Reactor Building High Area Radiation Monitor Upscale Radia tion 2 iir.15 min. Cable tunnel fire

. As fire progresses initiate random annunciato rs and component trips.

Continue through scram until end of class.

c.

e, ..i .ny.

> r a>:

i SCENARIO 3 (Continued)

Time No tes Problem 3 hr. Compl ete cool down.

Questioning and discussion should include all indica-tions local and remote that are available to assist the operator in monitoring reactor 70wer, level and pressure.

,,,,n.

o .>_ . 3. . . . , r

  • SCENARIO 4 Time Notes Problem O Initialize at Mode 10 100% power.

Prior to initialization press:

. ADS Valve (D) Fail to Clo se Orders:

. Maintain 800 MWe.

. Tag out A CRD pump for maintenance.

. ADS surveill ance

. Tag out A feedwater regulation val ve Trip of Condensate pump Trip of Feed pump (auto feature) 1 hr. During ADS surveillance ADS valve B does not open.

instruct that ADS valve B will not open.

ADS valve D fails to close. ADS valve D fails to close.

If operator scrams the plant continue until plant is stabilized and cooling down.

Re-initialize at Mode 10 100% power as at start of exercise and order power reduction to 30%.

1 hr. 30 min. Decrease activity as flow Off Gas Hi Activity decreases.

Master Level Controller Master Level Controll er inter-failure - place failure in mittent failure and out several times to cause level oscillation and simul ate impending failure.

3)321M

SCE?lARIO 4 (Continued)

Time flo tes Pro bl em 2 hr. Loss of air to feedwater Feedwater regulation valve lockup regulation valve annun-ciato rs . Clear after discussion of feedwater regulation valve operation.

2 hr. 15 min. Heater string isolation. Heater 2A2 Hi L'evel Discuss transient effects.

2 hr. 30 min. Discuss with students. APRM Downscale (Cause unkncwn.)

2 hr. 45 min. Carry out required action. RPS Bus B failure 3 hr. Turbine Hi Vibration trip When mode switch is out of Run initiate Steak leak in drywell .

Trip HPCI after initiation.

Continue until end of class.

n . --

zi . O -, a .

e SCENARIO 5 Time No tes Pro bl em 0 Initialize Mode 10 100% power.

Press:

.11 LPRM Cownscale/Bypcssed

. IRM Detector Stuck Order:

. RCIC tagged out (Stm Lk)

. Maintain 600 MWe.

30 min. Half scram if LPRM bypassed LPRi Full Scale on APRM Inop.

45 min. Auto voltage regulator fail 1 hr. Reactor seal ring high prersure 1 hr. 15 min. Loss of offsite startup transformer 1 hr. 30 min. Sea water introduction Hi condensate conductivity 1 hr. 45 min. Condenser tube le?k (After 10 min.)

Hi Demin Effluent Conductivity Control pressure / water HPCI trip if started level after MSIV's shut.

Perform scram action and continue until end of class.

3 hr. Conduct cooldown for condenser repair.

31.0260

SCENARIO 6 Time Notes Probl em O Initialize at Mode 7 850 lbs. critical and heatup in progress.

prior to initialization press :

. Bypass feed pump Hi Level trip

. Not all rod scram in.

Orders:

. Increase power to the 50%

rod pattern line.

30 min. At 900 lbs. fail 1 bypass. Fail 1 bypass valve open.

Clear after discussion of bypass failure full open during heatup.

45 min. Unstick rod when CRD drive Stuck control rod pressure is increased.

Discuss drive seal leakage.

I hr. Press: Store Snapshot Recirculation MG Set B generator differential current high with MG set trip.

hr.15 min. If scram occurs, perform Scram valve air supply low corrective action until pressure.

plant ready to restart. Re-initialize at Snapshot mode and continue under above conditions.

3].3269

i SCENARIO 6 (Continued)

Time Notes Probl em I hr. 45 min. Allow operation of spare CRD flow control valve fail shut flow control valve. (due to electrical failure).

2 hr. Perform corrective action. Isolation phase bus duct tempera-ture Hi.

2 hr. 15 min. Recirculation MG Set B speed feedback failure.

2 hr. 30 nin. Hi conductivity inlet to demins Clears after 10 min.

3 hr. RBCC1 Hi Activity Activity decreases if heat exchanger is removed from service.

3 hr. 15 min. Continue until end o f class. Feedwater regulation master controller fail open.

- s ,1, .3 U .i < va ' ' ~

SCENARIO 7 Time No tes Problem 0 Initialize at Mode 15 Scram Recovery.

Prior to initialization push:

. Main Steam Line Radiation Downscal e

. Bypass Feed Pump Hi Level Trip Allow students to determine MSL radiation failed 'down-scale.

Orders:

. Reactor startup

. Power increase to 100f.

rod pattern line.

30 min. Free stuck rod when drive Stuck rod pressure is increased.

Perform intermittently.

Discuss CRD seals and excessive leakage.

I hr. Conduct as turbine is rolled. Turbine Hood Spray Failure 1 hr. 30 min. Perform after turbine Trip CRD Pump A. (Pump can be temperature is under restarted when suction strainer control or trip. cleaned.)

1 hr. 4b min. Equipment operator reports SBLC tank Hi/Lo temperature temperature centroller set low.

r . s ,- , s c.

gf M. d *'= ' i . -

i SCENARIO 7 (Continued)

Time Notes Problem 2 hr. HPCI Stm Leak - isol ate 2 hr. 30 min. Conduct this casualty with Feedwater regulation valve lock feedwater regulation valve up. After this, fail the feed-in Master Automatic Control . water regulation master controller closed.

Cl ear the feedwater regula- Loss of air to feedwater regulation tion valve lock-up with val ve.

Master Controller failed closed.

Trip of both pumps and Loss of both speed feedback signals -

scram. recirc pumps run up in speed.

If scram occurs on low reactor water l evel, continue until end of class.

If scram does not occur, trip both RPS buses.

Discuss GEMAC controller o peration .

3p;,T'f3

5 SCENARIO 8 Time No tes Probl em 0 Initialize at Mode 17 Hot Scram Recovery at power.

Prior to initialization press:

. Diesel generator 2 Fail to Start.

. Core Spray surveillance unsatis factory.

. Incomplete Sequence Recirc MG Set B.

Order:

. Diesel generator and CS surveillances.

45 min. Inadvertant Recire Trip B Incomplete sequence on restart.

I hr. CRD Filter High AP 1 hr. 15 min. Trip due to low suction CRD Pump A trip (failed bearines) pressure.

CRD Pumo B is operable on tran sfer. .

1 hr. 30 min. Reactor seal ring Hi pressure I hr. 45 min. Off Gas Hi Flow 2 hr.15 min. Condensate pump failure (no feed pump selected for trip)

Press: Snapshot

,,3 ,],<2-in u .m.n .L a 4 t >

SCENARIO 8 (Continued) .

Time No tes Pro bl em 2 hr. 30 min. When RO starts to first low pressure heater tube leak insert rods, cause rod to (heater string isolation) be stuck.

Second rod has free move-ment. Third rod stuck.

All other rods free.

If no scram occurs, continue Trip CRD Pump B. Cause cannot pro bl ems . be immediately found.

If scram occurs, re-initialize at Snapshot and continue.

3 hr. Loss o f offsite power.

(Startup and shutdown transformers)

Continue with no CRD pumps or offsite power until end of cl ass.

3 hr.15 min. Loss of TBCCW pumps Scram initiated within 60 sec. on loss of RFP gland seal.

J n ,1d A4O t " $ , * .

SCEflARIO 9 Time Notes Probl em 0 Initialize to Mode 8 50% power.

Prior to initialization press:

. CS Flow Test unsatisfactory

. Not All Rods scram

. ATWS

. IRM Detector Stuck Orders:

. ADS surveillance

. CS surveillance

. Increase power to 100%.

. RWM Out of Service

. ADS A Fails to Open 30 min. Control rod stuck Permit rod movement after CRD drive pressure increased.

1 hr. Decision to go to cold CS flow test unsatisfactory shutdown should be reached.

1 hr. 20 min. Rod Block Monitor full scale 1 hr. 40 min. Equipment operator reports Turbine bearing oil temperature low flow to ccolers from hi service water.

2 hr. Trouble of unknown origin. Condensate demineralizers hi

. differential pressure.

press : Snapshot D, ,s, t ) 4 4 / LP

i SCENARIO 9 (Conti nued)

Time Notes Pro bl em 2 hr. 30 min. At =5% power, with made switch in Startup, Bypass valves fill open.

3 hr. After corrective operator action on ATWS and plant in stable condition, re-initialize to Snapshot mode.

Continue with shutdown until end of class.

o , ,3,'..e a ,n <

.n - 4 . -

i U

SCENARIO 10 Time Notes Problem 0 Initialize to Mode 4.

Heatup at 150 lbs. Prior to initialization press:

. ADS Val ve D Fail to Close

. Not All Rods Scram

. Hood Spray Failure Orders:

. Increase power to 1 C0%.

30 min. Perform correcti te actions. Control rod uncoupled 1 hr. Instructor open relief valve Reliev Valve Fail Open D to simulate valve fail open.

If LPCI initiation occurs, Trip LPCI Pump A & B equipment operator report cause of trip of LPCI Pumps A & B unknown.

Discuss exercise with students.

When plant is stable, ordet-vessel to be flooded to just below MSL's so ADS valve may be removed (alarm).

1 hr. 45 min. Continue with cooldewn and floodup.

2 hr. Initiate prior to moderator Steam leak in drywell temperature of 2120F.

Perform corrective action.

3IUI((.7

l SCENARIO 10 (Continued) ,

Time Notes Probl em 2 hr. 30 min. Re-initialize to Mode 15, Hot Scram Recovery.

Prior to initialization press:

. Not All Rods Scram

. ATWS

. Reactor Water Cleanup flow as high as possible (cold water addition).

3 hr. Continue with startup. IRM Cownscale 3 hr.15 min. Timer may be repaired Timer malfunction quickly.

If IRM Hi is approached IRM Hi-Hi fail IRM Hi-Hi, If scram doesn't occur, initiate Main Steam Line High Radiation, perform ATWS corrective action.

Continue until end of class .

3.G25U

SCENARIO 11 Time Notes Probl em 0 Initialize to Mode 10 100% power.

Prior to initialization press:

. Not All Rods Scram

. ATWS

. SRM Stuck

. IRM Stuck 10 min. Discuss computer require- Computer trouble ments.

30 min. Off Gas Hi Flow 40 min. Report of Off Gas explosion.

Supervisor orders power reduced to 50%.

50 min. Report of major explosion Loss of offsite power (stack at stack with two men hit lines). Main Xfmr 2 trouble.

seriously injured. Off Gas Unit Aux Xfor 2 trouble. TR 2 is isolated by instructor water spray on.

closing isolation valve.

(Cause unknown.)

1 hr. Equipment operator reports Turbine Building high radiation turbine deck reading 200 mR/hr.

1 hr. 5 min. Equipment operator reports Reactor Building high radiation reading near railway door 250 mR/hr.

Continue until corrective action complete and plant stabl e.

3.3.U5.U9

SCENARIO 11 (Continued)

Time No tes Probl em 2 hr. Re-initialize to Mode 8 50% power. Conditions in simulator as before.

Orders:

. Shutdown to Hot Standby 2 hr. 30 min. Recirculation MG Set A speed feedback failure.

3 hr. Operator spils drink ~ on Rod Select matrix. Fire starts.

Pet' form corrective action Reactor control panel is now on ATHS situation and unreliable.

discuss until end of class.

Scram plant on RPS bus and nuclear instrumentation problems.

<yy3ggg

SCENARIO 12 Time Motes Probl em 0 Initialize at Mode 10 100% power.

Prior to initialization press :

. Not All Rods Scram

. ATWS

. RFP Hi Level Trip Bypass Orders:

. Maintain 100%.

. Turbine Weekly tests

. HPCI surveillance 1 hr. Allow all surveillance: Rod Drift In compl eted.

Proceed with casualty. TR 2 gas combust'bles high I hr.10 min. After equipment operator sent to investigate TR 2 problem, proceed with next probl em. Main Transformer 2 trouble.

Transformer Area 2 water spray on.

Transformer 2 explosion. Generator trip.

Equipment operator missing. Stuck open bypass valve after scram.

Take corrective action.

Continue until plant in stable condition.

2 hr. Initiali:e to Mode 8 850 psig.

Same cor.ditions as before with LPCI and CS pumps inoperative .

ca g . . <, s

.u . F., u; n..

9

I SCEtlARIO 12 (Continued)

Time flotes Pro bl em Orders:

. Increase power to 100%.

2 hr. 20 min. Fault in feed pinp C. Bus Al trip. (Loss of A & C RFP and B Cond pump)

Re-energize bus after Simultaneous Recirc MG A failure locating problem.

Restart MG set.

2 hr. 45 min. With mode switch in Run, Recirculation pump B feedback introduce this problem failure before other recirc pump is restarted.

3 hr.15 min. Design Basis Accident loss of offsite power Rupture in drywell Continue until class ends. "

Initiate torus cooling and long term ccoling systems.

O $g ed

l SCENARIO 13 Time No tes Probl em 0 Initialize to Mode 9 50% core flow and 42%

reactor power.

Prior to initiclization press :

. Not All Rods Scram

. Reactor Feed Pump Hi Level Trip Bypass Orders:

. Increase power to 100%.

. Core Spray surveillance 15 min. Cl ear alarm when equipment Main transformer 2 trouble operator resets at trans-former panel (coolers started).

17 min. Recirculation Pump A number 2 seal leak alarm (Clear immediately.)

22 min. Load dispatcher requests 25 MVARS as soon as possible.

23 min. 2 gpm leakage noted Recirculation Pump A number 2 seal leak alarm 31 mi n . Equipment operator at feedwater regulation station reports air leak.

35 min. Feedwater regulation valve loss of air Feedwater regulation valve lockup ne :o o i h% G T

  • s1 A .s.

SCENARIO 13 (Continued)

Time Notes Probl em 50 min. Recirculation Pump A Hi vibration (Clears immediately.)

51 mi n . Recirculation Pump A Hi vibration (Clears when pump speed decreases.)

52 min. Isolation phase bus duct temper-ature Hi 57 min. Must trip pump. Tu rbine Recirculation Pump A Hi trip on high water level vibration will result. (Does not clear.)

I hr. Continue until plant in Steam leak in drywell stable condition.

1 hr. 30 min. Re-initialize Mode 2165UF.

subcritical .

Prior to initialization press:

. SRM Detector Stuck

. Turbine Acceleration Control Failure Orders :

. Reactor startup 2 hr.15 min. Discuss reactor physics SRM detector stuck during startup.

2 hr. 35 min. Accumulator trouble 2 hr. 40 min. IRM Full Scale 3.Ks?S.S

4 SCENARIO 13 (Conti nt.ed)

Time Nctes Pro bl em 2 hr. 50 min. Spare flow control valve CRD flow control valve failed availabl e. closed. (Due to electricai failure. )

Stabilize water level . Drywell water rupture 3 hr. 15 min. Re-initialize at Mode 6 with plant pressure at 850 lbs. :nd continue startup a =, before.

3 hr. 20 min. Allow students to discover APRM Downscale prior to overlap APRM Cownscale. Scram valve leak If stuifents do not notice scram valve leak, have equipment operator report high temperatures on CRD piping at the accumulators.

3 hr. 30 min. Turbine roll Acceleration control failure 3 hr. 50 min. Feed regulating valve failed closed 373,g3;,

I SCENARIO 14 ,

Time Notes Probl em 0 Initialize at Mode 8, 20%

reactor power.

Prior to initialization press:

. D/G 2 Fail to Start

. IRM Detector Stuck Orders:

. D/G surveillance

. Generator synchronization and loading

. HPCI surveillances

. Increase power to 50%

20 min. Main transformer differential current Turbine / Generator trip 25 min. Problem resolved, restart APRM Downscale turbine.

40 min. Synchronize and load generator.

45 min. Order feed pump 2C removed frcm service.

1 hr. Re-initialize to Mode 9, 50% reactor power.

Conditions as above.

Orders :

. Power to 38%

. 110 MVARS 3132[N.

I SCENARIO 14 (Continued) ,

Time Notes Probl em 1 hr. 30 min. Continue when plant in Turbine Trip stable condition.

1.hr. 50 min. Re-initialize to Mode ~.16.

Hot Scram Recovery Conditions as above.

Orders.

. Increase power to 100%.

2 hr. 20 min. 2 IRM's Downscale 2 hr. 40 min. After generator synchroni-zation, Control rod stuck.

3 hr. Recirculation MG Set B trip.

Unable to restart MG set. (Field breaker opened)

Initiate shutdown to Hot

' Standby for condenser work.

3 hr. 30 min. At 5% power and made switch in Startup, Fail bypass valves open.

Continue until end of class.

n Uk; Och d:) :;

,g_

i SCENARIO 15 Time No tes Pro bl em 0 Initialize Mode 10, 100% reactor power.

Prior to initialization press:

.11 LPRM's downscale

. HPCI Fail to Start

. D/G 2 Fail to Start Orders:

. 650 MWE

. 200 MVARS

. Tag out stator cooling pump B.

. Tag out feed pump 2C.

. Tag out CR0 pump B.

8 min. Loss of offsite power 10 min. At low l evel scram, Trip all feed pumps.

initiate MSL high radiation. MSL high radiation 11 min. High Off Gas Turbine and Reactor Building high radiation 1 hr. When plant conditions stable, restore offsite power for students to recognize.

Re-energize buses and start required loads.

I hr. 30 min. Re-initialize Mode 10, reactor power 100%.

Same conditions as before except HPCI auxiliary oil pump is tagged out.

O.l.OCfiS

SCENARIO 15 (Continued) probl em Notes Time Loss of offsite power I hr. 45 min.

At scram and Group I Fail turbine control valves and bypass val ves open.

2 hr. isolation, trip both feed pumps.

Continue until level under Restore offsite power.

control .

Continue until plant in stable condition.

Re-initialize Mode 6, 3 hr. reactor pressure 850 lbs.

continuing startup.

Prior to initialization press:

. ATWS

. Not All Rods In Order _:

. Reactor startup

. Synchronize and load generator Generator synchronized.

3 hr. 30 min. Equipment operator reports steam leak at air ejectors.

Loss of steam jet air ejectors 3 hr. 35 min.

Continue until ATWS procedures ccmplete and plant in stable condition.

82.3..?S9

Retrieved from "https://kanterella.com/w/index.php?title=ML19207B834&oldid=2613039"