Text

Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal) for Tests Administered on 960816-24 for Rept 50-261/96-301
	ML20147C229
Person / Time
Site:	Robinson
Issue date:	01/24/1997
From:	Michael B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20147C236	List: IR 05000261/1996301; ML20147C259;
References
	NUDOCS 9702060039
	Download: ML20147C229 (101)
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6#pagoNe UNITED STATES y

f 4 o NUCLEAR REGULATORY COMMISSION REGloN 11 3 S 101 MARIETTA STREET, N.W., SUITE 2900 j ATLANTA, GEORGIA 303230199

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January 24, 1997 i NOTE T0: NRC Document Control Desk Mail Stop 0-5-D-24

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FROM: Beverly Michael, Licensing Assistant h }NM

, Operating Licensing and Human Performance Branch, Region II SUBJECT: OPERATOR LICENSING EXAMINATION ADMINISTERED AUGUST 16 - 24, 1996 AT CAROLINA POWER AND LIGHT COMPANY, H. B. ROBINSON STEAM ELECTRIC PLANT - DOCKET NO. 50-261

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During the period August 16 - 24, 1996, Operator Licensing Examinations were administered at the referenced facility. Attached, you will find the i

following information for processing through NUDOCS and distribution to j the NRC staff, including the NRC PDR: .

Item #1 - a) Facility submitted outline and initial exam submittal,

designated for distribution undar RIDS Code A07 b) As given operating examination, designated for distribution under RIDS Code A07 "

Item #2 - Examination Report 50-261/96-301 has already been submitted with the as given written examination attached, designated for distribution under RIDS Code IE4 l l

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p reg UNTTED STATES

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NUCLEAR REGULATORY COMMISSION REGloN 11 y S 101 MARIETTA STREET, N.W., SUITE 2900 g ;j ATLANTA, GEORGIA 303234199 i

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January 24, 1997 i

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NOTE T0: NRC Document Control Desk Mail Stop 0-5-D-24 l FROM: Beverly Michael, Licensing Assistant h NM Operating Licensing and' Human Performance Branch, :

Region II '

SUBJECT: OPERATOR LICENSING EXAMINATION ADMINISTERED AUGUST 16 - 24, 1996 AT CAROLINA POWER AND LIGHT COMPANY, H. B. ROBINSON STEAM ELECTRIC PLANT - DOCKET N0. 50-261

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During the period August 16 - 24, 1996, Operator Licensing Examinations

,

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were administered at the referenced facility. Attached, you will find the following information for processing through NUDOCS and distribution to

,

the NRC staff, including the NRC PDR:

i Item #1 - a) Facility submitted outline and initial exam submittal, ;

designated for distribution under RIDS Code A07 !

b) As given operating examination, designated for !

distribution under RIDS Code A07 l Item #2 - Examination Report 50-261/96-301 1,as already been submitted with the as given written examination attached, designated for distribution under RIDS Code IE4 ,

f" 9702060039 PDR 970124ADOCK0500gi ;

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t ES-301 Administrative Topics Outline ES-301-1 Set #1 Examination Level (Circle One): SRO .

Facility- Week of Examination:

Examiner's Name (print): !

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Administrative Describe method of evaluation:

Topic / Subject f

1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions - Shift What do the oncoming and offgoing CRSSs discuss Turnover :

What review actions are completed by the oncoming ROs l

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Temporary How would the Shift Superintendent know that a Temporary Mods l

Modification existed that prevented heating up above 200 degrees ;

while preparing for a plant heatup? 1 What is the disposition of the temporary mods !

! Plant JPM-CR-033 :

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JPM-IP-075 ' Use of Covered in RCA entry e.g. RWPs, hand held friskers I Radiation Instrument Covered in RCA entry e.g. RWPs, hand held friskers Emergency Covered in Simulator Scenario Action Levels and Classificatio Covered in Simulator Scenario n i Developed By: ,(onmM Approved By: 9 j

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ChiefExaminer: b M f

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ES-301 Administrative Topics Outline ES-301-1 Set #2 Examination Level (Circle One): SRO Facility: Week of Examination:

Examiner's Name (print): 1 Administrative Describe method of evaluation: l Topic / Subject 1. ONE Administrative JPM, OR l Description 2. TWO Administrative Questions l

Shift Staffing What are the requirements for the STA if they are not in the control room l What are the requirements if the shift complement is less than the i

minimum shift complement Short Term Explain purpose /use of the " Operation's Directive Book"

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How long do night orders remain in effect

, Plant JPM-CR-041(Set #2) -OR- JPM-IP-033(Set #3)

Drawings JPM-CR-045 . Use of Covered in RCA entry e.g. RWPs, hand held friskers Radiation Instruments Covered in RCA entry e.g. RWPs, hand held friskers

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' Emergency Covered in Simulator Scenarios Action Levels and Classificatio Covered in Simulator Scenarios n

Developed By: / Lee, [ h Approved By: &

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ChiefExaminer: Cl . L

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ES-301 Administrative Topics Outline ES-301-1

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Set #3 J

t Examination Level (Circle One): RO j Facility: Week of Examination:

Examiner's Name (print):

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Administrative Describe method of evaluation

} Topic / Subject 1. ONE Administrative JPM, OR l Description 2. TWO Administrative Questions

Shift Staffing What is the minimum shift complement W

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Actions taken by offgoing RO if oncoming RO is not physically l fit to assume the watch f Key Control What are the required actions if a controlled key is lost What is required to revise the key inventory Plant JPM-IP-002 l Drawings JPM-IP-043 Use of Cove red in RCA entry e.g. RWPs, hand held friskers Radiation --

Instruments Covered in RCA entry e.g. RWPs, hand held friskers Emergency Describe purpose / activities of OSC Facilities List the Emergency Event Classifications in order ofincreasing severity

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Developed By: a(,e Approved By:

I V 4 ChiefExaminer: _

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ES-301 INDIVIDUAL WALK-THROUGH TEST OUTLtf4E FORM ES-301-2 JPM Simulator / Control Room /In-Plant Set # 1 EXAMINATION LEVEL (Circle One): h SRO (I)/ SRO (U)

FACILITY: H. B. ROBINSON WEEK OF EXAMINATION:

EXAMINER'S NAME (PRINT):

SYSTEM /JPM SAFETY FUNCTION PLANNED FOLLOWUP QUESTIONS K/A/G // IMPORTANCE // DESCRIPTION CR-033, Perform Boration of the RCS - 1 004000. Gen.7 // 3.0/3.3 // Loss of Aux Panel DC 1AW GP-007 SIM 004000.Kl.16 // 3.3/3.5 // Clearance Reg'd on "A" BAST CR-005. Re-establish Letdown Flow 11 004010.A2.04 // 3.6/4.2 // PCV-145 fails / effects on CVCS IAW OP-30i SIM 073000.K3.01// 3.6/4.2 // R 17 alarm while est. LTDN 3 CR-099, PZR Pressure Control 111 010000.A3.02//3.6/3.5//Effect of raising pot setpt on PC-444J Malfunction IAW AOP-019(PSA)(Al SIM Path)(NEW) 010000.Kl.06 // 2.9/3.1// Why can't use Aux Spray if normal LTDN isolated at power I

' CR-030, Loss of Residual Heat IV 005000.A2.04//2.9//2.9// Plant cooled and solid on RilR. PCV-Removal (Shutdown Cooling)1AW SIM 145 closed down. Result on RCS pressure? l AOP-020 00$000. GEN.15/G.8/3.9// Reduced inventory and lose RHR l cooling. Time to boi . CR-009, Remove Power Range Channel IX 015000.K4.09 // 2.8/3.1//N-44 OOS, What effect if pull

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N-44 from service IAW OWP-011 MCR instrument power fuses 015000.K6.04//3.lG.2// Upper / lower Section Deviation alarms response to comparator channel defeat switch out of NORMA . CR-028, Restoration of Normal Power VII 062000.K4.01//2.6/3.2// Resides the turb trip at power, what else After Loss of Start-Up Transformer MCR is n:cded to get a Gen lockout /4kv bus transfer?

Co2000.K4.03//2.8/3.1// Signals input to SUT lockout, and

results of SUT l 1 CR- 066, Respond to a Loss of CCW to X 026000.kl.02//4.1/4.1//How determine adequate CCW flow to l the RCP motor coolers IAW AOP-014 SIM CV Spray Pumps i (Alt Path)

008000.A4.01// 3.3/3.1// FCV-626 open, How verify flow to RCP thermal barrier IP-055, Align Deepwell to AFW IAW V 061000.K4.07/G.1/3.3//frip and reset overspeed trip device on OP-402 (NEW)(PSA) PLANT the SDAFW pump 061000.K4.02//4.5/4.6// Auto start signals for SDAFW pump IP-075, Energize Pressurizer Heaters Vil 010000.K4.02 // 3.0/3.4 // Htt response if PZR level dec. below

, from the Emergency Busses IAW EPP- PLANT 14.4 %

21 (Alt Path)(RCA)(S/D)(NEW)

010000.Kl.03 // 3.60.7 // What is purpose of the PZR HTR BKR arm switch 10. IP-053, Turbine Building Operator Vill 039000.K4.04/G.lG.2//S/G PORV oper during load 75% reject Actions IAW AOP-004 (S/D)(Alt Path) PLANT 041020.K4.12//2.3/2.4// Secondary control panel indications used to determine Tcold constan DEVELOPED BY: /vw APPROVED BY:_ h/ h EXAMINER: -

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ES-301 INDIVIDUAL WALK-THROUGH TEST OUTLINE FORM ES-301-2 JPM Simulator / Control Room /In-Plant Set # 2 EXAMINATION LEVEL (Circle One): RO / RO 1)/ SRO (U)

FACILITY: H. B. ROBINSON WEEK OF EXAMINATION:

EXAMINER'S NAME (PRINT):

SYSTEM /JPM SAFETY FUNCTION PLANNED FOLLOWUP QUESTIONS K/A/G // IMPORTANCE // DESCRIPTION CR-101, Withdrawing Control Rods to 1 001000.K4.04//3.2/3.4//S/U in progress, movement of control the Point of Adding fleat IAW GP-005 SIM rods with respect to bank overlap 001000.K5.38//3.5/4.1// Changes in SDM after a trip CR-074, Re-establish Letdown Flow II 004010.A4.02 // 3.1/3.6 // Charging System Response IAW OP-301 (Alt. Path) MCR 004000.A2.07 // 3.4/3.7// Des. L/U aner a Phase A iso CR-082, Depressurize RCS using 111 000038.EK3.06 // 4.2/4.5 // Options for SGTR Cooldown PORV's IAW Path-2 ( Alt. Path)(PSA) SIM (S/D) 000038 EK3.01//4.1/4.3//Use Steam Tab!es to determine target j for RCS depressurization < CR-041, Respond to a RCP Seal IV 003000.K6.14//2.6/2.9//RCP finw Detectors an d Pressure Taps Malfunction IAW AOP-018 SIM l 004000.A2.05 // 4.0/4.3 // Seal Leakoff ind. during #2 seal ,

l CR-045. Transfer from the Bypass to V 059000.K4.19 // 3.2/3.4 // Auto closure of FRV's ;

the Main Feedwater Regulating Valves SIM IAW GP-005 (low power) 059000.A3.06 // 3.2/3.3 // FWI signal inputs / actions CR-100, Resond to a Loss of X 075000.K4.01//2.5/2.8// Response when stopping the last Cire Circulating Water Pump (Alt Path) MCR Water pump (NEW)

075000.A2.03//2.5/2.7// Leakage detection from the condenser integrally grooved tube sheet CR- 010, Place a Reactor Protection IX 012000.K4.01// 3.7/4.0 // Prot & Cont func of sw positions Channel in the Tripped Condition IAW MCR OWP-030 000027.EA1.01// 4.0/3.9 // Lvl chan. Fail during NC Cooldown IP-051, Perform Electrical Operator Vil 067 GEN // 3.8/4.0 // Criteria for entering DSP's Actions of DSP-002 (Turbine Building)

l PLANT i (Alt. Path)(low power) 000067.EA2.16 // 3.3/4.0 // Est.\ Control AFW flow to S/G IP-56, Perform Subsequent Actions of V 076000.Kl.16//3.6/3.8//How can both SWBPs be operated if AOP-022 in the Auxiliary Building PLANT the North SW licader is isolated (PSA)(RCA)(NEW)

076 Gen.05//2.8/3.2// Service water pump declared inoperabl Time and date for going to cold shutdown 10. IP-033, Establish Emergency Cooling XI 008000.K4.01// 3.1/3.3 // Operation of CCW Pumps to the Spent Fuel Pit lleat Exchanger PLANT IAW OP-306 (RCA) 033000.A2.01//3.0/3.5//fime to boiling in SFP if lose off-site pwr i

DEVELOPED BY: [ A/ u% h '

f I APPROVED BY: [b V EXAMINER: _

CHIEF EXAMINER: _, /L l

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ES-301 INDIVIDUAL WALK-THROUGH TEST OUTLINE FORM ES-301-2 JPM Simulator / Control Room /In-Plant Set # 3 l

EXAMINATION LEVEL (Circle One): R / SRO (U)

FACILITY: H. B. ROBINSON WEEK OF EXAMINATION:

EXAMINER'S NAME (PRINT):

SYSTEM /JPM SAFETY FUNCTION PLANNED FOLLOWUP QUESTIONS K/A/S // IMPORTANCE // DESCRIPTION

, CR-047, Perform Boron Concentration 1 004000.A2.01// 4.2/4.3 // What prot. features prevent Dilution of the RCS IAW OP-30! SIM overpower condition & core damage of continuous dilution with no operator action 004000.K4.04//3.2/3.1//Effect on CVCS when LT-Il5 fails high i CR-086, Depressurize RCS LAW Path- 111 000038.EK3.01//4.1/4.3// Basis for S/G pressure >220 F in 2, PORV Failure (Alt. Path)(PSA) SIM Path-2 prior to depressurizing the intact S/Gs

(S/D)

010000.A2.03//4.1/4.2//How control PZR PORVs if normal power supply lost due to fire 3 CR-057, Respond in a Loss of RCP IV

003000.A2.01// 3.5/3.9 // Des. all norm flowf aths thru RCP SealInjection IAW AOP-018 SIM

, 003000.K5.01//3.3/3.9// Loss of flow trips CR-023, Transfer Aur.iliary Loads from VII 062000.A4.07 // 3.7/4.2 // Interlocks for 52/7&l2 Auxiliary to Startup Transformer OP- SIM 603 062000.K2.01//3.3/3.4// Automatic actions which occur on Generator Trip CR-062, Remove Source Range IX 015000.K6.02 // 2.6/2.9 // During S/D lose IR compens. Volts Channel N-31 from Service IAW MCR to N-35 OWP-Oli 015000.K4.01//3.1/3.3// Actions required if N-35 flows pow er fuses during a startup CR-098, Initiate Containment Spray VI 026000.A3.01//4.3/4.5// Auto vs Manual Spray Actuation (Alt Path)(NEW)(S/D) MCR 0000ll.EK3.14//4.1/4.2//Why RCPs tripped when Spray actuates 7, CR- 097 Establish Excess Letdown 11 004010.A2.05 // 4.1/4.3 // Ilow Phase A effect ability to (Alt. Path), (NEW) MCR maintain Ex. LTDN tem .Kl.01// 3.6/4.0 // Expected alarms w/No Ltdn avai . IP-002, Shift Auxiliary Fredwater V 076000.K4.01// 2.5/2.9 // Turbine Building isolation Pump Suction to Service Water IAW PLANT OP-402 (PSA)(RCA) 022000.Kl.01// 3.5/3.7 // Bas. for SW Booster Pmp Ope . IP-052, Perform Subsequent Actions of V 000067.EA2.04 //1.1/4.3 // Local control / operation of SW AOP-022 in the Auxiliary Buildiu PLANT pumps (Alt. Path)(RCA)

076000.Kl.16//2.7/3.1//Keylock switch purpose / location for V6-16A 10. IP-043, Transfer "D" Service Water Vll 076000.A4.05//2.0/21//SW Strainer Operation Pump to the DS Bus (RCA) PLANT 076000.Kl.16//3.6/3.8//SW Booster Pump normal operation / control vs responsefo safeguards or blackout DEVELOPED BY: t/ uw h, N APPROVED BY: /k /t _

EXAMINER: CHIEF EXAMINER: a.-

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ES-301 SCENARIO EVENTS- ES-301-3 SIMULATION FACILITY: H. B. Robinen SCENARIO NO.: DSS-003 EXAMINERS: APPLICANTS :

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i INITIAL CONDITIONS: The Unit is at 100% nower. The followine ea_uinment is out of service: "B" Chareine

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Pumn for an oil chance (OOS for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months /back in 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months st SDAFW numn for steam inlet line leak (OOS for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months /back in 14 hour1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months st "A" CCW numn for excessive vibrations (numn uncounledl TURNOVER: Reduce nower to 80% to remove HDP from service. Track couinment out of service and orenare for ~

nost maintenance testine to retum couloment to service. Boron concentration 1017 nom. CBD at 218 sten couillibrium xeno EVENT N MAL EVENT EVENT MFI SIS 01 A C SI Failure to Auto Initiate f MFI SIS 01B P

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RFI CFWO83 C "A" and "B" AFW pumps auto start failure '

RFI CFWO84 MFI CCW1B (C) C Trip of running CCW pump after Path-I entry point C -

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7. W^:' du799 ;?O$;ptuM@;Hc; n * Reduc:a e wk nw.euwe MM5a4 -nu"l + power to anove'HDPfro s w m pi Q MlN M ik% w&s@ % UE W C9%m$G hG3 %,pv?y% W Q2iMQ'W N KCMG%M% ,*a

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y o. . m .,r CRF08: 575 degrees Trefinput to rod control fails as is

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3 MFI CRF03A ROD G-3 Q. g' *3 OCM'fy it Dropped Rodfrurbine Runback

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4 MFI RCS09A C .75 gpm R.C. S..LeakWr&,. y s .,gp;t, A M@a ..M w,.o . m ,s. 4, ,

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N, R Power reduction due to excessive RCS leakag t 5 MFI RCS01 A M LOCA

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(N) Normal, (R) Reactivity, (I) Instrument, (C) Component, (M) Major

Developed By: /, try cS. - Approved By: M t 4 b ' Il l f

Examiner: N k #t d- Chief Examiner: -w IM l I

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4 CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON PLANT

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l INITIAL LICENSE EXAMINATION SCENARIO l

... DSS 003

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CCW PUMP HOT BEARING DROPPED ROD RCS LEAK LOCA LOSS OF EMERGENCY COOLANT RECIRCULATION

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APPROVED BY: DATE

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DYNAMIC SIMULATOR SCENARIO EXAMINATION SCENARIO NUMBER: DSS-003

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SCENARIO NAME: Power reduction, Hot bearing on CCW pump, Dropped Rod, RCS Leak, LOCA, Loss of Emergency Coolant Recirculation TEAM MEMBERS / INDIVIDUAL EVALUATIONS EXAMINERS:

SCO SAT _ UNSAT_

RO SAT _ UNSAT _

BOP SAT _ UNSAT _

l INITIAL CONDITIONS / TURNOVER INFORMATION:

IC#: 5 POWER LEVEL: 100% BORON: 1017 ppm Tavg: 575 *F TARGET VALUE: + TARGET BAND:i5 MWD /MT: 150 RODS: 218D NORMAL CURRENTS UPPER LOWER N-41 250 250 N-42 250 250 N-43 250 250

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N-44 250 250 REQUIRED XENON FREE SHUTDOWN BORON CONCENTRATION:

HOT: 1188 ppm 100*F COLD: 1646 ppm EQUIPMENT OUT OF SERVICE: -

"B" charging pump has been out for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for oil change, return to service in =2 hours; SDAFW pump has steam inlet line leak, has been OOSfor 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , will be retumed to service in = 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months ; ,Q_

"A" CCW pump OOS due to excessive vibration, pump uncoupled for remova POWER HISTORY:

Equilibrium Xenon, No power ramp rate restrictio Page 1 of 14

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DSS-003 SCENARIO DESCRIPTION After shift turnover and allowing the crew to walk down the board, the crew will commence a power re duction to remove the "A" Heater Drain pump from service for maintenance. After the power reduction has commenced, the initiating event will be a hot bearing on the running CCW. After the crew has started the standby pump and secured the running pump, one (1) control rod will fall into the

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core initiating a turbine runback. The Tref input into rod control will fail at 575 degrees causing the

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rod control system to only respond to the power mismatch signal. After the plant is stabilized, an RCS leak develops which will require a plant shutdown. The leak will escalate to a LOCA requiring a

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manual reactor / turbine trip and will result in a manual or automatic SafetyInjection signal. PATH-1

..will be entered and followed to mitigate the accident. Safety injection will fail to automatically

, initiate requiring manual action. The MDAFW pumps will fail to auto-start requiring identification and manual actuation. A failure of the last operable CCW Pump will require the use of EPP-015, Loss

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of Containment Recirculation Ability, due to insufficient Supplement D components. The scenario should progress until EPP-015 entry is directed. The exercise may be terminated at any time at the

evaluator (s) discretion after EPP-015 entr SCENARIO OBJECTIVES Evaluate the response to hot bearings on the mnning CCW pump.

' Evaluate the response to a dropped control rods and attendant turbine runback IAW AOP-00 . Evaluate the response to excessive RCS leakage IAW AOP-01 I Evaluate the response to radiation alarms IAW AOP-00 . Evaluate the response to a reactor trip and SI due to LOCA IAW PATH- . Evaluate the response to a'ito-stait failures of safeguards equipment IAW PATH- ~ . Evaluate the ability to recognize the need to conserve injection water due to the lack of sufficient Supplement D components and transition to EPP-01 , Evaluate the SRO's ability to direct the crew during abnormal and emergency conditions in accordance with the above listed procedure l l POWER REDUCTION TO SECURE HDP Page 2 of 14 l

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DSS-003 EVENT COMMENTS Actions for OP-105

. Review precautions an limitations and hold crew brief Notify load dispatcher that unit load will be decreased to 80%

... Notify RC of expected increase in rad levels in the CV pump bays and pipe alley Verify NR-45 selected to the highest reading channel (PR and IR)

> If additional charging and letdown flow are desire, then initiate IAO OP-301 1 Reduce turbine load ts follows Set the desired load in the SETTER

Select the desired load rate Depress the GO pushbutton

~ Monitor AFD and Tave-Tref HOT BEARING ON RUNNING CCW PUMP s

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NOTE: Inside AO reports to the control room the hot bearing on the "B" CCW pump Crew shifts CCW pumps i

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DSS-003 EVENT COMMENTS Notifies Maintenance and/or Work Control to investigate CCW pump bearings

. Refers to T.S 3. NOTE: If the crew elects to NOT rack out the breaker, the pump will trip on overcurrent during next attempted pump start

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II. DROPPED CONTROL ROD Actions (AOP-001)

! Check for unwarranted rod motion Evaluate indications for multiple dropped rods 1 Checks for Turbine runback i

! Checks S/G levels Checks Tavg trending to Tref Checks Condenser Steam Dump operation

. Checks PZR PORV closed Checks RCS Press. trending to 2235

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. .- Checks PZR level trending to program 1 Go to Section A of AOP-001 Page 4 of 14

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, l-DSS-003 EVENT COMMENTS

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NOTE: Initiate the 75 FPm RCS leak. Upon recognition AOP-001 should be terminated and AOP-016 entered III. RCS LEAKAGE

... Respond to RCS leakage IAW AOP-016 I Check RCS level decreasing in and uncontrolled manner Check charging pumps all stopped :

, Place mnning charging pumps in manual and adjust to max speed l Check RCS level decreasing in an

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uncontrolled manner Adjust Charging and Letdown flow

Check two charging pumps l running and at maximum l

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speed ,

..l ' Check normalletdown in service l

l Reduce to a 45 gpm orific,e

.. _ Check PZR level decreasing in an uncontrolled manner l

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' Control charging to maintain PZR level

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DSS-003 EVENT COMMENTS Checks charging flow > RCS i

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Leakage Check VCT level < 12.5 inches 1 Align charging pump suction to the RWST as follows

. . . Check RWST level > 9% Verify LCV-Il5B open Verify LCV-115C closed i 1 Implement T.S. 3. I 1 Implement EAL's 1 Check for primary to secondary t leakage j NOTE: The actions of AOP-005 for the rad monitor alarms should be taken as the alarms are received Source check and verify alarms - Make appropriate plant announcemen's

..., l Notify E&RC for needed - .

surveys l

\ Go to AOP-016 '

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l DSS-003 l EVENT COMMENTS NOTE: Leak rateincreases. When

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recognized should go back to step #8 1 Isolate letdown flowpath 1 Check RCS level decreasing in an uncontrolled manner

.

1 Establish maximum charging flow l 1 Check RCS level decreasing in an i

uncontrolled manner 1 Check accumulator discharge valves open i '

1 Trip the reactor and go to PATH-1 l

IV. LOCA A. PATH-1 Immediate Actions Verify Rx tripped Verify turbine tripped

.. E-1 & E-2 energized Verify SIinitiated

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NOTE: The RO should notethat SI has not auto initiated and l manually initiates SI or i

manually starts components j Opens Foldout A t

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DSS-003 EVENT COMMENTS NOTE: RCP's should be tripped j

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when trip criteria are met in Foldout A Verify Phase A valves closed i Verify FW isolation i

.._ Verify FW pumps tripped Verify both MDAFW pumps running NOTE: The BOP should note that both AFW pumps failed to sequence / auto start and take manual action to start ,

both pumps 1 Start SDAFW pump as necessary NOTE: Pump is OOS and not available 1 Verify 2 SI pumps running 1 Verify both RHR pumps mnning 1 SI valves properly aligned -.

1 Verify at least 1 CCW pump running

, 1 Verify all SW & SW booster piamps.

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running .-

t 1 Verify HVH 1-4 running

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1 Verify IVSW system initiated 1 Verify CV ventilation isolation l

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DSS-003 1

. EVENT COMMENTS I

1 Verify CR vent aligned for j -

press. mode

.

l l 2 Verify both EDG's runmng l l 2 Energize battery chargers as i necessary

]

.

)

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. 2 Verify CV pressure remains <20 psig i i

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2 Checks for auto steam line isolation '

2 Checks if steam line isolation

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required 2 Imcally open breaker for HVS-1 at MCC-5 2 Check RCS pressure > 1350[1250] ,

1 Psig 2 Verify proper SI flow 2 Check RCS pressure > 125 psig 2 Verify at least 300 gpm AFW flow available

. . .

3 Verify AFW valves properly aligned 3 Control AFW to maintain S/G level 10 [20]% to 50% 'N

_s_. .:.

3 Check RCP thermal barrier cooling water hi or low flow alarm lit i

3 Place the steam dump mode selector Switch in manual

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, DSS-003 EVENT COMMENTS

3 RCS temperature stable at or trending l

~

. to 547 degrees l l

3 Check PZR PORV's closed 3 Check PZR spray and aux spray valve closed

... 3 Check at least one RCP running :

3 Any S/G pressure decreasing in an uncontrolled manner or completely depressurized 3 R-15 and R-19A, B, C rad levels normal 4 Check forindications of an RCS leak Rad monitors, CV pressure, sump level 4 Go to PATH-1 Entry Point C Entry Point "C" on PATH-1 I i Reset SPDS, CSFST Monitonng ;

NOTE: If FR-P.1 conditions are i met, the crew will transition 1 but not implement any , ,

actions due to the LOGA - 1 Open Foldout "B" l

NOTE: At this time,"C" CCW ;

pump trips. When "B" tries I

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to start, the breaker trips Page 10 of 14

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DSS-003 EVENT COMMENTS NOTE: The SCO should assign

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AOP-014 to the Ro or BOP to complete the required actions for loss of all CCW Request periodic activity sample of S/G's

.._ Check at least one RCP running Any S/G depressurizing in an uncontrolled manner of completely depressurized Control AFW flow to maintain S/G level Check for S/G with uncontrolled level increase Check R-15 and R-19's rad levels normal Check PZR PORV's closed and at least one block valve open 1 Reset SI, CV Spray and Phase A and B ..

I Establish instrument air to the CV 1 Check offsite power available.io-the l charging pumps and establish desired l Dow

i 1 Check CV Spray pumps running I 1 Check RCS subcooling > 35 [55]

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. ,5 DSS-003 EVENT COMMENTS 1 When below 10 E-10 amps then

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energize the source ranges and transfer the recorders 1 Check RCS pressure > 275 [400]

psig 1 If RCS pressure stable or increasing

. , _ .

then stop the RHR pumps 1 E-1 and E-2 energized by offsite power 1 Check starting air receivers repressurized on the unloaded EDGs

. . .

2 Stop the unloaded EDG's 2 Verify Supplement D components capable of recirculation NOTE: The crew should note that no CCW pumps are running and transition to EPP-15 2 Transition to EPP-15 -

NOTE: Scenario can be terminated at this point at the .

evaluators discretion? ..,

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.. All SRO's l

' Classify the event as Site Area Emergency (RCS leakage > makeup capability)

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ES-301 SCENARIO EVENTS ES-301-3 SIMULATION FACILITY: H.B. Robinson SCENARIO NO.: DSS-005 EXAMINERS: APPLICANTS :

INITIAL CONDITIONS: The Unit is at 100% power. The following equipment is out of service "B" MDAFW for motor replacement (OOS for 8 hrs /no oroiected return time). HVH-1 for vibration concerns (OOS for 1 hr/back in 3 hrs).

TURNOVER: Maintain current plant conditions. Boron concentration 1017 nom. CBD at 218 steo equillibrium xeno EVENT MAL EVENT EVENT MFI EDG4A C "A" and "B" HHSI Pump auto start failure RFI CFW83 C "A" MDAFW auto start failure RFI CFW85,86 C VI-8A, B, C fails to auto open, steam supply to the steam driven and 87 AFW pump 1 CORD PT:445 I PT-445 Fails high (pressurizer control channel)

m ..

2 MFI SGN2B ic 100 gpm steam generator tube leak

$ g&R%, ...

._h,. :

., ?:jpyp ;O;.Qg}!$,. T .w . $$,$tf$

n.suMm nm nM%y&;yv%i

$ $7I.9,l6${fki i e gy S, m%:ylI$$Sf p2 ~ , %k{'{f.pa $(w

-

% &.,.e J :Pb2J$r.-kUK MMiifd WQhWbh #1 h %1% M?:NlCA WORN 3 MFI CND2 C Condenser air inleakage 300,180 -

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MFI CND2 .eq%C%i9 9 ;,) :: +>., ,, p Condenser Air inleak (Rapid load reduction) (Leak increases l 700,120 @lMnh; after initial actions taken) - 1 4:nny l 4 SGN0lH k5Mk hMbthN$iiMNg'inbth'Ij$$f1l$E'ktishD M $kS? MMMIEWi$isMMRNME@%l0M8 '

,

(N) Normal, (R) Reactivity, (I) Instrument, (C) Component, (M) Major l Developed By: ~

tm ND o <

Approved By: i

>

(

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p 4-Examiner: 4 6W Chief Examiner: M

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CAROLINA POWER & LIGHT COMPANY

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H. B. ROBINSON PLANT

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INITIAL LICENSE EXAMINATION SCENARIO

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DSS-005 PZR PRESSURE CHANNEL FAILURE SGTL LOSS OF CONDENSER VACUUM SG SAFETY VALVE FAILS OPEN DEVELOPED BY: DATE -

APPROVED BY: DATE

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SCENARIO NUMBER: OSS-005 SCENARIO NAME: PZR Pressure Channel Failure, SGTL, Loss of Condenser Vacuum, S/G Safety Valve Fails Open TEAM MEMBERS / INDIVIDUAL EVALUATIONS EXAMINERS:

.SCO SAT _ UNSAT _

RO SAT _ UNSAT _

BOP SAT _ UNSAT _

INITIAL CONDITIONS / TURNOVER INFORMATION:

IC#: 5 POWER LEVEL: 100% BORON: 1017 ppm Tavg: 575*F

...

TARGET VALUE: + TARGET BAND: 5 MWD /MT: 150 RODS: 218D NORMAL CURRENTS UPPER LOWER N-41 250 250 N-42 250 250 N-43 250 250 N-44 250 250 REQUIRED XENON FREE SHUTDOWN BORON CONCENTRATION:

HOT: 1188 ppm 100*F COLD: 1646 ppm EQUIPMENT OUT OF SERVICE:

"B" MDAFW pump, OOS for 8 hrs, motor replacement; HVH-1, OOS for 1 hr, investigating vibration problem POWER HISTORY:

Equilibrium Xenon, no power ramp rate restrictions. eMaintain current power leve ,

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., DSS-005 l

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SCENARIO DESCRIPTION After shift turnover and allowing the crew to walk down the board, pressurizer pressure control channel PT-445 will fail high. After the plant has been stabilized and appropriate procedure actions >

have been completed, a 100 gpm tube leak will occur on the "B" SG requiring a plant shutdown due to excessive leakage. A condenser vacuum leak will escalate into the need to trip the turbine due to a loss

_of condenser vacuum. Following entry into PATH-1, a S/G safety valve will open on "B" SG, causing l

a safety injection. The operators will work through PATH-1 with a subsequent transition to Path- Safety Injection pumps, MDAFW pumps, and the Steam Driven AFW pump valves will fail to start /open automatically, requiring operator action. The final plant conditions will be a faulted / ruptured "B" steam generator. The scenario may be terminated at the evaluators discretion >

following transition to EPP-1 . . . SCENARIO OBJECTIVES Evaluate the response to a failed pressurizer pressure transmitter PT-44 . Evaluate the response to a steam generator tube leak IAW AOP-005 and AOP-03 . Evaluate the response to a partial loss of condenser vacuum IAW AOP-01 . Evaluate the response to a failed open steam generator safety valve while attempting to recover l from a turbine trip coincident with a tube lea . Evaluate the response to a reactor trip and SI due to steam break IAW PATH-1 and PATH- . Evaluate the response to auto-start failures of safeguards equipment IAW PATH-1 Evaluate the ability to recognize to conduct the post SGTR response IAW EPP-017 Evaluate the SRO's ability to direct the crew during abnormal and emergency conditions in accordance with the above listed procedure .,

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EVENT COMMENTS l

1. PT-445 FAILURE !

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NOTE: The crew may respond in accordance with AOP-019 or AOP-025. The most likely path is via AOP-025 . Crew identifies failed channel and implements AOP-025 "RTGB Instmment Failure" Identifies correct channel and implements ;

,,,

Section "C" ! Check either PORV open > Closes the open PORY NOTE: Depending on recognition time, the crew may get a short cyclic runback due to OT delta T Check PT-444 failed Verify the selector switch PM-444 selected -

to the operable channel Implement EAL's Checks Tech Specs for applicable LCO's Return to procedure and step in effect

.- Crew identifies failed channel and implements AOP-019 " Pressure Control Malfunction"

' Identifies PCV-456 open and closes the .

valve -

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l Checks PZR pressure < 2335#

Verify both PORV's closed Control spray valves and heaters to restore

. RCS pressure Check PZR pressure control under

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operator control Page 3 of 14 l

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DSS-035

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EVENT COMMENTS Check PC-444J operating properlyin AUTO

. Check RCS pressure less than required for current plant conditions i

i Check both PZR spray valves closed ' Check aux spray valve closed

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10. Check AOP-003-F8 extinguished

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11. Check PZR pressure stable or trending to required value 12. Implement EAL's 13. Contact I&C and Work Control l 14. Refer to Tech Spec 3.1.1.5 l

! I SG TUBE LEAK l

NOTE: If crew detects RCS leakage prior to the R-15 alarm they may enter AOP-016 for l excessive RCS leakage. This procedure l will direct entry into AOP-035 Actions for R-15 alarm, AOP-005

' Verify alarm validity

! Source check

. t l Reset alarm -

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l AOP-005 actions for R-15 alarm Check R-14C, R-19's, R-31's for an

[ increasing trend or alarm Request E&RC group to sample the i S/G's and survey around R-15 l

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., DSS-005 i

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EVENT COMMENTS ! IF pri-sec leakage confirmed, THEN go to AOP-035

~ Refer to Tech Spec 3. Implement EALs I AOP-035 actions l

,,, Check PZR level decreasing in an .

uncontrolled manner 1 Start addtional charging to have two pumps running at max speed i Reduce letdown to a 45 gpm orifice i

! Check PZR level decreasing in an !

uncontrolled manner l l

1 Control charging flow to maintain program PZR level Check available charging flow greater than RCS leakage Check VCT Izvel - not less than 1 inches Notify chemistry personnel to periodically ..

sample all S/Gs for activity and boron concentration Determine RCS leak rate .,

s NOTE: R-19 actions of AOP-005 willte-completed by the BOP when the alarm is received and directed by the SRO ,

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10. R-19B alarm, AOP-005, use status lights to check blowdown isolation FCV-1931 A & B, S/G B Blowdown !

Flow Control Valves close Page 5 of 14

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, DSS 005 ,

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EVENT COMMENTS FCV-1934 A & B, S/G B Sample !

Flow Control Valves closed i

. l Verify FCV-4204B, S/G B Blowdown Flow Rate Control Valve

- Closed Verify VI-31, S/G Blowdown Drain I Header Discharge to circulatinF water catch basin valve -

.

' Verify All S/G Drain / Wet Layup Pumps - OFF Request E&RC Perform The Following:

l Sample Steam Generators for l indication of Primary to Secondary Perform a background radiation survey at Radiation Monitor R-19B Check primary to secondaryleakage indicated, if yes the go to 1) EOP Network or 2) AOP-035, Steam Generator Tube Leak

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11. Identifies that the leak rate is greater than i

the following: .35 gpm for a single S/G or , I gpm for all S/Gs' -

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12. Identify leaking S/G based on R-19's, R-t 31's or chemistry samples 13. Implement EAL's 14. Refer To Tech Spec 3. . Check reactor critical Page 6 of 14 I - - . -

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,., DSS-005

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EVENT COMMENTS 16. Normally perfonned steps in GP-006, such as placing S/G Blowdown to the Flash

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Tank may require ~ Release Permit . Initiate Plant Shutdown To Hot Shutdown Using GP-006, Normal Plant Shutdown From Power Operation To Hot Shutdown, While Continuing With This Procedure !

NOTE: Allow time to commence the power

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reduction prior to inserting the vacuum leak NOTE: Vacuum leak inserted at the evaluators discretion

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III. PARTIAL LOSS OF CONDENSER VACUUM AOP-012 Immediate Actions ; Check Circulating Water Pump-ANY TRIPPED Verify stand-by vacuum pump running Reduce turbine load as necessary to maintain back press < 5.5 in. H , Notify load dispatcher

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NOTE: Vacuum leak increases < Verify vacuum breakers closed NOTE: The crew may manually trip'the reactor / turbine or may trip '-

automatically on low vacuum IV. LOSS OF VACUUM. REACTOR TRIP PATH-1 Immediate Actions Verify Rx tripped l Verify turbine trip l

Page 7 of 14

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., DSS-DOS

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EVENT COMMENTS Verify El & E2 energized

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NOTE: Insert the failure of"B" S/G safety at this time Verify SIinitiated Opens Foldout A Verify Phase A valves closed

"' Verify FW isolation Verify both FW pumps tripped Verify both MDAFW pumps running NOTE: BOP should recognize the start failure of the "A" MDAFW and start the pump 10. Start the SDAFW pump as necessary NOTE: BOP should recognize the start failure of the SDAFW pump and open the required valves 11. Verify two SI pumps running NOTE: RO should recognize the start failure of the HHSI pumps and . . .

start the required pumps 12. Verify both RHR pumps running

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13. SI valves properly aligned s

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14. Verify at least 1 CCW pump running 15. Verify all SW & SW booster pumps running

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16. Verify HVH 1-4 running 17. Verify IVSW system initiated 18. Verify CV ventilation isolation Page 8 of 14

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., DSS-005 l

l EVENT COMMENTS 19. Verify CR vent aligned for i press. mode l

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l 20. Verify both EDG's running l

21. Energize battery chargers as necessary 22. Verify CV pressure remains <20 psig 23. Checks for auto steam line isolation

"'

24. Checks if steam line isolation required 25. I.x>cally open breaker for HVS-1 at MCC-5 26. Check RCS pressure > 1350[1250] psig 27. Verify proper SI flow 28. Check RCS pressure > 125 psig 29. Verify at least 300 gpm AFW flow

, available

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30. Verify AFW valves properly aligned 31. Control AFW to maintain S/G level 10 [20]% to 50%

32. Check RCP thermal barrier cooling water hi or low flow alarm illuminated ,,

33. Place the steam dump mode selector Switch in manual 34. RCS temperature stable at or trendi$g to 547 - -

)

35. Check PZR PORV's closed !

36. Check PZR spray and aux spray valve i closed 37. Check at least one RCP running 38. Any S/G pressure decreasing in an uncontrolled manner or completely depressurized Page 9 of 14

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., DSS-005

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EVENT COMMENTS 39. Transition to EPP-11 " Faulted S/G Isolation

~ Faulted SG Isolation IAW EPP-11 Maintain at least 1 S/G available for RCS cooldown Check S/G status by identifying intact and faulted S/G's

.

' Isolate faulted SG using Supplement G Close MSIV and bypass when Tave

<547 F Close FW reg and bypass valves Close V2-6B Close V2-14B Close V2-16B and open it's breaker Close steam line PORV Close Vl-8B and open it's breaker Check blowdown isolation and sample valves closed

' Direct AO to close MS-29 Direct AO to verify MSIV above seat drains closed .

.s Direct AO to verify MSIV below ~

seat drains closed Check CST level >10% Check available secondary radiation monitors normal Go to PATH-2 entry point J Page 10 of 14

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,., DSS-005 l .

EVENT COMMENTS PATH-2 Entry Point J l

l , Reset SPDS, initiate monitoring CSFSTs Open Foldout C

! Ensure SR detectors energize Request periodic activity samples of all S/G's

' Place steam dumps mode switch to Pres Mode Bypass Condensate Polishers Check for at least one RCP running 8 Ruptured SG identified Maintain at least one S/G for cooldown 10. Verify ruptures S/G PORV setpoint at 1035 psig 11. Verify RCS temp less than 547 12. Close ruptured S/G MSIV and bypass 13. Verify ruptured SG PORV shut

..

NOTE: Supplement G actions from EPP-11 for the faulted S/G should have already isolated the ruptured S/G 14. Verify ruptured SG isolated

_ }s 15. Any S/G with uncontrolled depressurization or completely depressurized 16. Check faulted S/G isolated per EPP-11 l 17. Control feed flow to maintain intact S/G

! level between 10-50%

l l 18. Any other S/G with an uncontrolled level I increase Page 11 of 14

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., DSS 005

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EVENT COMMENTS

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19. Check PZR PORV's closed

, 20. Check at least one block valve open unless isolated for a leaking PORV 21. - Reset SI, phase A and B, and CV Spray

22. Establish instrument air to containment

23. Verify AC busses energized from offsite

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24. Check RCS pressure >275 psig 25. Stop RHR pumps 26. Verify ruptured SG isolated 27. Check ruptured SG pressure > 250 psig 28. Check for at least 1 intact SG 29. Transition to EPP-17 "SGTR with Loss of Reactor Coolant - Subcooled Recovery" NOTE: Scenario can be terminated at this point at the evaluators discretion All SRO's Classify the event as

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Site Area Emergency (two fission product barriers breached)

NOTE: May classify SAE based on RCS leakage > charging. No way to know if leakage has increased and based orrSI'

flow it would be conservativ {

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ES-301 SCENARIO EVENTS ES-301-3 SIMULATION FACILITY: H.B. Robinson SCENARIO NO. DSS-008 EXAMINERS: APPLICANTS :

INITIAL CONDITIONS: The Unit is at 100% nower. The followine couinment is out of service: "B" EDG (OOS for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months /back in 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months st "B" MDAFW Pumo (OOS for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months /bumo motor croundedt "B" ~

Service Water booster numo SWBP (OOS for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . motor crounds)"B" S/G PORV has a small casket leak . "A" S/G tube leakage is 0.1 gp TURNOVER: Commence a norraal olant shutdown to repair"B" S/G PORV. Chemistrv samoling S/G's IAW OP-504. Boron Concentration 1017 com. CBD at 218 steo EVENT MAL EVENT EVENT N TYPE DESCRIPTION RFI SGN023,024 C Failure of all MSIV's to auto close and 025 MFI MSS 03C C Failure of the "C" MSIV to manually close c..my

, :%c ., ;ORPXAOOOS6R> wt C,? 8: , Failure of,e,

.

,. . . . ~ , , , , , , . ~ ,

m, m, ,.~...

' ...m ..

. .. .,, . me m ., . .a Phase "A" valve WD-1721.to cloiich3/Vl1,MI,.,

,' 41 h,, M y q $ # .Q (. (.>. f g i g g . g ,? ,..Qx Q ~ W Q.,mS p @ ' w 4 4 T;$. '.2

-

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.. . . .

1 - %. .c 5m . . . 4 m ,- ,

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7 <.

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, R'7.eg: L?RFICVC046 uCg.9 :CVC-348 , . '#o@

a , q" qqmBAST.outlit'cidse,_d.:.)

3y _ y n;,n f . y..yy'.Jgg d 7;4-b -- .e

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. n p,., . Q 7. p ,

2 , c 1 N, R Plant Shutdown

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2 MFI NIS12A 4 (I p N-41 Fails low (control power fuse) . ,

q. p /;

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3 ORP .XN36105 C Override of a seismic alarm to cause an earthquake 1

- l MFI CFW029 C 2000 gpm leak on the bottom of the CST due to the earthquake, p' _

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- W,h/

,k MFITURB18 C EH pump common suction line leak l' ?4/ ' MFI RPS01 A $ M b' Failure of both reactoitril i bicakers io openLeausin[an' TW ~~

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MFI RPS01B - ", '

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J i, ' " '

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J-

~^

5 f' )

< ,

<r

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i f ,' 4g ,

.,e MFI MSS 09 a .

M*" . Steam break on the 72" h' ;eader (common steam line)1 .

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(N) Normal, (R) Reactivity, (I) Instrument, (C) Component, (M) Major Developed By: lux Approved By:

Examiner: 7 77 Chief Examiner: 6 I

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CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON PLANT

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INITIAL LICENSE EXAMINATION SCENARIO

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DSS-008 PR NI CONTROL POWER FUSE FAILURE SEISMIC EVENT CST LEAK EH LEAK ATWS STEAM BREAK

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DEVELOPED BY: ,

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DATE l

APPROVED BY: DATE

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DYNAMIC SIMULATOR SCENARIO EXAMINATION l

SCENARIO NUMBER: DSS-008

_ SCENARIO NAME: PR NI Control Power Fuse Failure, Seismic Event, CST Leak, EH Leak, ATWS, Steamline Break l

l TEAM MEMBERS / INDIVIDUAL EVALUATIONS EXAMINERS:

SCO SAT _ UNSAT _

RO SAT _ UNSAT _

BOP SAT _ UNSAT _

.

.._

INITIAL CONDITIONSfrURNOVER INFORMATION:

IC#: 5 POWER LEVEL: 100% BORON: 1017 ppm Tavg: 575*F TARGET VALUE: + TARGET BAND: *5 MWD /MT: 150 RODS: 218D NORMAL CURRENTS UPPER LOWER l N-41 249 249 N-42 249 249 N-43 249 249 N-44 249 249 REQUIRED XENON FREE SHUTDOWN BORON CONCENTRATION:

l HOT: 1188 ppm 100*F COLD: 1646 ppm !

EQUIPMENT OUT OF SERVICE: ,l l

"B" MDAFW Pump, OOS for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , pump motor grounded.

l "B" EDG, OOS for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , exoected to be back i'i 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months "B" SWBP OOS due to motor ground, has been OOS for 6$o'urs.

! "A" S/G tube leakage of 0.1 gpm, chemistry is monitorin "B" S/G PORV has been identified to have a small gasket leak.

l POWER HISTORY:

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Equilibrium Xenon, No power ramp rate restrictio Page 1 of 17 l

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DSS-008 l

l EVENT COMMENTS ;

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SCENARIO DESCRIPTION

! After shift tumover and allowing the crew to walkdown the board, the crew will initiate a normal l plant shutdown due to the S/G PORV. Following initiation of the plant shutdown, a blown fuse in the control circuit of PR NI-41 A will initiate a Turbine Runback. When the plant is stabilized, a seismic event will occur. The seismic event causes an unisolable leak at the bottom of the CST that will be found by the makeup water treatment AO. Use of AOP-021 (Seismic Disturbances) and

.. Technical Specifications should result in a plant shutdown being directed. During the subsequent plant shutdown an EH leak will result in a Turbine / Reactor Trip signal with a failure of the reactor l to trip (ATWS). A Steam Break on the 72" header will develop immediately after the turbine / reactor trip and will be compounded by an automatic close failure of all MSIV's and a stuck open MSIV on

"C" MS line. The scenario should progress through EPP-11 (Faulted S/G isolation); The scenario may be terminated at the evaluators discretion following transition to EPP- SCENARIO OBJECTIVES Evaluate the crew's response to a PR NI control power fuse failure IAW AOP-01 . Evaluate the crew's response to a Seismic Event IAW AOP-02 . Evaluate the crew's response to a CST leak (T.S. shutdown required) Evaluate the crew's response to a MSLB IAW PATH- . Evaluate the crew's response to an ATWS using Path-1, and FRP- ) Evaluate the SP,O's ability to direct the crew during abnormal and emergency conditions in i accordance with the above listed procedure l l

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EVENT f.OMMENTS j I. . PLANT SHUTDOWN j i

. Initiate shutdown per GP-006 j

- , Review precautions and limitations Complete initial conditions per section j . Start addidtional charging pumps and

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.._ open additional letdown orifices as necessary Reduce turbine load as follows l 1 Set desired load in the SETTER j Select the desired load rate ; Depress the'GO push button

. Monitor axial flux power distribution

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NOTE: At evaluator discretion after the load decrease has commenced, the NI failure

! may be inserte i l

I NI-41 A FUSE FAILURE - Recognition of failure

, 1 Checks instrument busses energized s

. >-. Checks for a dropped rod 1 Checks power range channels "

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NOTE: May identify the power range l l failure without checking other ,

parameters j i

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., DSS-008 EVENT COMMENTS Actions of AOP-015 for Turbine Runback Checks S/G level trending to program

. Checks Tave trending to Tref Checks load reduction > 100 Mwe Checks Steam Dumps to condenser actuated

.., Checks PZR PORV closed Checks PZR pressure trending to 2235# I Checks PZR level trending to program Check APP-005-B5 Rod Banks A/B/C/D low limit extinguished Monitors AFD to ensure compliance with Tech Specs 1 Checks reactor power > 15%

1 Check APP-006-F5 Steam Dumps ;

armed illuminated l 1 Check steam dump valves closed

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NOTE: Continuous action. When the valves are closed, the BOP should reset ,

s 1 Check GEN VARS within limits for -

current plant conditions 1 Checks regulator balance between

+2 and -2 1 Check Power Range NIS cause of mnback Page 4 of 17

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., DSS-008

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EVENT COMMENTS 1 Check affected Power Range NIS control power fuses intact

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1 Contact I&C to replace blown fuse using PLP-049 NOTE: Seismic event intiates at this time. Booth instructor should call with prompt from load dispatcher

... .

1 Remove N41 from service using OWP-11, NI-l II SEISMIC ALARM AOP-021 (Seismic Disturbancesj Actions NOTE: When AOP-21 is identified, the CST leak should be inserted Compare current indications with known values or log reading to observe trends

' Check for noticeable tremors or vibrations l

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NOTE: Inform SRO that vibrations l are felt in the control room Notify Manager - Operations of se,ismic l

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event and any identified al::sinilip:.: )

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j Checks Reactor Critical

> Notify Manager - Operations to obtain Plant General Manager concurrence for I plant to continue operations until data is analyzed Page 5 of 17

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,, DSS-008

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EVENT COMMENTS 2 ,

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NOTE: Permission is given to continue

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operation ;

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! Place the unit in condition specified by Manager - Operations

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NOTE: If CST leak has been identified should direct power reduction l Notify I&C to perform attachment 2 of

..- AOP-21 to obtain and analyze the data Evaluate RCP and Turbine vibration levels

NOTE: If BOP has not identified CST

leakage a call should be made i

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to the control room from the j l outside AO reporting the i rupture of the tank j Condensate Storage Tank leak )

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' Recognize level decrease and inform SRO

! Evaluate Tech Spec 3. ' Initiate a plant shutdown . EH Reservoir leak Recognize / Identify EH leak ,

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l Accelerate the load reduction due to !

severity of the El? leak l l

NOTE: May manually trip or receive !

an automatic reactor trip signal 1 Manually trip the reactor and turbine if load decrease can not be controlled Page 6 of 17

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., DSS-008

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EVENT COMMENTS

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I ATWS - STEAM BREAK l PATH-1 Entry

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Verify reactor tripped Attempt to maually trip the reactor using

, both push buttons

' Go to FRP- , ...

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B. FRP-S.1 Actions 1 Check reactor tripped

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. Insert control rods AND direct AOs to locally trip reactor trip breakers OR rod

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drive MG sets i

NOTE: Trip the reactor from the

booth after the RO has initiated emergency boration i Verify turbine tripped NOTE: Initiate the steam break at this time

, Verify all available AFW pumps are running ~'

, Initiate Emergency Boration

' Verify that 2 charging pu'mpsere running at maximum spetd" - Verify boric acid pump aligned l for blend is running Verify MOV-350 is open Page 7 of 17 1

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. DSS-008 l

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EVENT COMMENTS Verify flow on FI-l10 > 10gpm !

NOTE: Should not no flow an

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open LCV-115B and close LCV-115C Verify charging valves CVC- I 310B and HCV-121 are open I Check charging flow to the RCS 1

... on FI-122 '

l If SI signal exists then verify auto start of SI equipment using Supplement "L" I

NOTE: The RO or BOP will be broken '

off to complete this attachment Check reactor and turbine tripped NOTE: The BOP should recognize the failure of the MSIV's to shut and request to close them Check for adequate heat sink, level in at least one S/G >10% or total AFW flow 4

> 600 gpm Maintain total feed flow > 600 gpm

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untillevelin one S/G > 10%

1 Control feed flow to maintain S/G level between 10-50% ,

1 Verify both primary w~ater pumps ~ ~

stopped NOTE: The RO should take the control switch to off for both pumps l

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DSS-008

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EVENT COMMENTS 1 Verify FCV-114A closed NOTE: The RO should take the valve

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switch to close ,

1 Check for reactivity from uncontrolled cooldown

' NOTE: Depending on timing and crew ,

pace, the faulted S/G may still

.._ be depressurizing. Steps 14-16 will only apply if S/G is still !

depressurizing 1 Verify all MSIV's and bypass valves are closed 1 Identify the faulted S/G l

1 Isolate the faulted S/G using Supplement "G" ,

l 1 Chaeck Battery Charger alarms APP- ,

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036-D1/D2 illuminated 1 Check reactor suberitical 1 Check emergency boration being performed

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2 Notify Tech Support to evaluate RCP conditions

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2 Reset SPDS and initiate monitoring of -

l the Critical Safety Function Status Trees

2 Transition back to procedure and step in

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effect which was PATH-1 PATH-1 actions f Verify turbine tripped

Verify E1 & E2 energized Page 9 of 17 l

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. ,., DSS 008

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EVENT COMMENTS Verify SIinitiated Opens Foldout A

. Verify Phase A valves closed l

NOTE: RO should recognize WD-1721 did not close and manually closes i

.._ Verify FW isolation Verify both FW pumps tripped Verify both MDAFW pumps running NOTE: The BOP should note the "B" MDAFW pump can not be started - OOS Start the SDAFW pump as necessary l

1 Verify two SI pumps running 1 Verify both RHR pumps running 1 Verify SI valves properly aligned 1 Verify at least 1 CCW pump mnning i

- (1 1 Verify all SW & SW booster pumps i running

' Attempts to start all Service's Water and Service Water - -

Booster pumps Checks North and South SW header low pressure alarms illuminated NOTE: BOP sh'ould note the "B" SWBP can not be started -

OOS Page 10 of 17

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,.,, DSS-008 f

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EVENT COMMENTS l

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1 Verify HVH 1-4 running 1 Verify IVSW system initiated

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1 Verify CV ventilation isolation 1 Verify CR vent aligned for i

press. mode 1 Verify both EDG's running

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2 Energize battery chargers as necessary (<30 min)

2 Verify CV pressure remains <20 psig '

2 Checks for auto steam line isolation ,

NOTE: BOP should acknowledge that MSIV's failed to auto close and the "C" MSIV is failed open 2 Locally open breaker for HVS-1 at MCC-5 2 Check RCS pressure > 1350[1250] psig 2 Verify proper SI flow

.

2 Check RCS pressure <125 psig 2 Verify at least 300 gpm AFW flow available x

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2 Verify AFW valves properly aligned 3 Control AFW to maintain S/G level 10 [20]% to 50% 1 3 Check RCP thermal barrier cooling water hi or low flow alarm illuminated Page 11 of 17 I

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, DSS-008

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EVENT COMMENTS 3 Place the steam dump mode selector l Switch in manual l

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3 RCS temperature stable at or trending to 547 4 3 Check PZR PORV's closed

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3 Check PZR spray and aux spray valve ;

closed j

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3 Check at least one RCP running 3 Any S/G pressure decreasing in an uncontrolled manner or completely depressurized l

3 Transition to EPP-11 " Faulted S/G l Isolation I i Faulted SG Isolation IAW EPP-11 I Maintain at least 1 S/G available for

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RCS cooldown Check S/G status by identifying intact and faulted S/G's NOTE: The following suppliment may

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itave been completed in ltRP-S.I. The SRO will direct one of the board operators to complete the supplement, Isolate faulted S/G using Supplemsht G Close MSIV and bypass when Tave <547 *F Close FW reg and bypass valves Close V2-6B Close V2-14B

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., DSS-008

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EVENT COMMENTS l

. Close V2-16B and open it's ;

breaker i

- Close steam line PORV Close VI-8B and open it's breaker Check blowdown isolation and sample valves closed

. . .

' Direct AO to close MS-29 Direct AO to verify MSIV above seat drains closed Direct AO to verify MSIV below seat drains closed Check CST level >10% Check available secondary radiation monitors normal Transition to PATH-1 entry point C

' PATH-1 entry point C Reset SPDS, CSFST Monitoring

.. , Open Foldout "B" Request periodic activity sample of S/G's N . Check at least one RCP running '

1 Check at least one HHSI pump mnning ;

, Check RCS subcooling < 35 degrees

)

1 Any S/G depressurizingin an uncontrolled manner of completely depressurized Page 13 of 17

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DSS-008

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EVENT COMMENTS Faulted S/G isolated using Supplement "G"

- When faulted S/G dries out, then dump steam from intact S/G's to control RCS repressurization NOTE: S/G dryout has already occurred and the crew may already be performing this

.., step to control RCS temperature 1 Control AFW flow to maintain S/G level 11. Check for S/G with uncontrolled level increase 1 Check R-15 and R-19's rad levels normal 1 Check PZR PORV's closed and at least one block valve open 1 If offsite poweris lost then restart safeguards equipment 1 Reset SI, CV Spray and Phase A and B

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1 Establish instrument air to the containment 1 Check offsite power available to'$e .

charging pumps and establish desifed ~

flow I 8. Check CV Spray pumps running 1 Check RCS subcooling > 35 2 Check levelin at least one S/G > 10% or greater than 300 gpm AFW flow Page 14 of 17

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., DSS-008

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< EVENT COMMENTS G

! 2 Check RCS pressure > 1650 psig

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a

. NOTE: The intent is to teminate SI.

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The conditions may not be met '

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at this time dependent on crew pace. If not the crew willloop back to the beginning of entry point "C" and return to this

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point in the procedure

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... 2 RCS pressure stable or increasing l

2 Pressurizer level > 10% i

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2 Go to EPP-7 "SI Termination" ;

NOTE: Scenario can be terminated at j this point at the evaluators discretion V EVENT CLASSIFICATION Classifies as Site Area Emergency (ATWS)

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. ES-301 SCENARIO EVENTS ES-301-3 SIMULATION FACILITY:_H.B Robinson SCENARIO NO: .DSSc-QQ2 EXAMINERS: APPLICANTS :

INITIAL CONDITIONS: The Unit is at 100% nower. The followine couinment is out of service: HVH-1 out for motor reolacement. will be back this shift. "A" EDG out for covernor renair (OOS for 2 days /back in 2 davst j i

TURNOVER: You have been instmeted to maintain current olant conditions. Boron concentration 1017 pom. CBD at 218 stens. CV oressure relief in crocress IAW OP-921. section EVENT MAL EVENT EVENT N N TYPE DESCRIPTION C Prevents auto closure of V12-10 and V12-11 on the R11/R12 alar CORDS PI:953 C Auto spray actuation failur CORDS PI:955 RFI RHR009 C RHR-764 out of position close SHUTRHR764 MFI CFWOIC C SDAFW Pump trips on auto star i 1 ORP AA085A I PC-444J partial failure causes spray valves to ope PC444J 60%

2 MFI RCS013B C RCP "B" #1 Seal failure

<._ MFI RCS016B C RCP "B" high vibrations L ..

Ys ([j[N

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N,Rk ,j.gF

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Power redu~c'iori; N *M i '?. $

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nc, 3 MFI RCS02B [7C(

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RCP "B" trips on overcurrent prior to operator action to trip the RC , ,

f, -- . . . . . , ,- r' l ; ,, g 't l MFI RCS09A C 300 gpm RCS leak ramped lover 120 seconds .

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4 MFI RCS01 A M Large Break LOCA (N) Normal, (R) Re etivity, (I) Instrument, (C) Component, (M) Major Developed By: -

Amm Approved By:

p i ,

6 l Examiner: b Chief Examiner: Chd .

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CAROLINA POWER & LIGHT COMPANY :

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q H. B. ROBINSON PLANT '

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INITIAL LICENSE EXAMINATION SCENARIO

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l DSS-009 i

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i PZR MASTER CONTROLLER FAILURE

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i RCP VIBRATIOli

RC. SEAL LEAK

'l RCS LEAK LBLOCA

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DEVELOPED BY: DATE APPROVED BY: DATE

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, DYNAMIC SIMULATOR SCENARIO EXAMn4ATION SCENARIO NUMBER: DSS-009 SCENARIO NAME: PZR Master Controller, RCP Vibration, RCP Seal leak, RCS Leak, LBLOCA

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TEAM MEMBERS / INDIVIDUAL EVALUATIONS EXAMINERS:

SCO SAT _ UNSAT _

RO SAT _ UNSAT _

BOP SAT _ UNSAT _

aeg INITIAL CONDITIONS / TURNOVER INFORMATION:

IC#: 5 POWER LEVEL: 100% BORON: 1017 ppm Tavg: 575.3 *F TARGET VALUE: + TARGET BAND: 5 MWD /MT: 150 RODS: 218D NORMAL CURRENTS UPPER LOWER N-41 250 250 N-42 250 250 N-43 250 250 N-44 250 250 l

REQUIRED XENON FREE SHUTDOWN BORON CONCENTRATION:

HOT: 1188 ppm 100*F COLD: 1646 ppm i

EQUIPMENT OUT OF SERVICE: ,, ]

HVH-1, motor to be replaced this shift

"A" EDG OOS for governor repairs, out for two days, repairs to be completed in two day '

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POWER HISTORY:

Equilibrium Xenon, No power ramp rate restrictio l EVOLUTIONS IN PROGRESS:

CV Pressure Relief in progress IAW OP-921, Section 6.1; maintain current power leve Page 1 of 16

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, DSS-009 SCENARIO DESCRIPTION After shift turnover and allowing the crew to walk down the board, the first event will be a failure of-PC-4443 which causes - PZR spray valve to open slowly and continuously until the controller is shifted to Manual. PZR pressure will decrease due to the excess spray flow requiring prompt operator action. When the plant has been stabilized, "B" Reactor Coolant Pump will develop high vibration These vibrations will cause seal leakoff flows and pump bearing temperatures to increase, indicating a severe problem with the RCP. The RCP vibrations will increase as the crew attempts to decrease power to' remove the pump from service. As power is decreased, RCS leakage will increase until the RCP shaft binds resulting in an overcurrent trip of the pump and subsequent Loss of Flow trip lollowed by a LBLOCA in the affected loop. The CV spray will fail to operate automatically requiri operator identification and manual actuation. RHR flow does not occur during large break LOCA due to valve RHR-764 being shut. The operating crew will investigate and have the valve re-opened. The LOCA will require entry into PATH-1 and eventually transition to FRP-P.I. The scenario may be terminated at the discretion of the evaluators any time after FRP-P.1 has been implemente SCENARIO OBJECTIVES Evaluate the response to a failed PZR master pressure controller (PC-444J). Evaluate the response to a RCP vibration alarm IAW AOP-01 . Evaluate the response to a RCP #1 seal failure IAW AOP-01 . Evaluate the response to a loss of flow trip and LBLOCA LAW PATH- . Evaluate the response to a failure of CV spray to actuate automaticall ~- Evaluate the response to a lack of RHR flow following a LBLOC . Evaluate the response to radiation monitor alarms IAW AOP-00 . Evaluate the SRO's ability to direct the crew'during abnormal and emergency conditions in l accordance with the above listed procedures. --

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, DSS-009 EVENT COMMENTS i

I. PC-444J FAILURE

! - RO recognizes malfunction with the pressure l control system and informs the SRO l Action of AOP-19 " Pressure Control Malfunction" Checks RCS pressure less than 2335 psig

... Checks PZR PORV's closed i Controls heaters and spray to restore RCS

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pressure Checks PZR pressure control under operator control Checks PC-444J operating properly in automatic Places PC-444J in manual Adjust PC-444J as necessary to restore RCS pressure NOTE: PC-444J will respond in as expected in manual

. Implement EAL's Contact I&C to repairs to the syste . Refer to Tech Specs for ' applicable LCO's NOTE: No EAL's or Tech Specs apply NOTE: Insert the RCP vibration i

Page 3 of 16

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DSS-009 EVENT COMMENTS l

II. RCP VIBRATION / SEAL LEAKAGE i

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NOTE: After the vibration alarm has been i received, then insert the seal leakage to ensure crew enters section "B" prior to

"C" of AOP-018 1 Enters AOP-018 Section "C" l l

.._ Checks for valid alarm !

I Check green OK status light for '

affected channelilluminated j

) Check both x and y probes for the i affected channel valid Checks for the following vibration levels to determine if RCP trip is required I Frame > 5 mils ; Frame > 3 mils and increasing at greater than 0.2 mils per hour Shaft > 20 mils j Shaft > 15 mils and increasing at greater than 1.0 mils per hour '-l NOTE: Shaft vibrations should be 14 mils Notify engineering to determine if" ' %

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installation of vibration analysis equipment for the "B" RCP is required Monitor the affected RCP for proper operation #1 sealleakoff temp < 235 degrees i Pump bearing temp < 225 degrees i

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DSS-009 EVENT COMMENTS Thrust guide temp < 200 degrees

- RCP current < 880 amps NOTE: Ensure #1 sealleakoffis greater than 5 gpm but less than 6 gpm at this point to ensure transition to section "B"

,,_

5 Check APP-001-E8 for the oil reservoir hi/lo level extinguished Check #1 sealleakoff between 1 and 5 gpm Go to section "B" for pumps seal failure Enters AOP-018 section "B" Check any RCP #1 sealleakoff flow greater than 6 gpm Check affected RCP parameters RCP bearing temp less than 225 degrees RCP #1 sealleakoff temp less than '-

235 degrees Check affected RdP #1 seal leakoff flow less than 5 gpm s

. -- Verify seal injection flow exceeds #1 seal leakoff flow for the "B" RCP Closely monitor RCP seal parameters

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DSS-009 EVENT COMMENTS Notify Engineering of RCP seal condition and instmet them to contact Westinghouse

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for further instruction NOTE: Inform the SRO that Westinghouse has already been contacted and their recommendation is to shut the pump down as soon as possible

' Check affected RCP #1 seal leakoff flow less than 1 gpm NOTE: Operations Manager calls and directs the shutdown at 2% per minute NOTE: Direction should be given from the SRO to commence unit shutdown in accordance with GP-006. The SRO may elect to direct GP-006 or AOP-018. AOP-018 may be given to a board operator to complete Check APP-001-C5 RCP standpipe hi/lo levelilluminated Check seal injection flow between 8 and 13 gpm '-

10. Check FCV-626 closed

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NOTE: After the load decrease is s commenced and at the evaluatbrs discretion the #1 sealleakoff should be increased above 6 gpm 11. RO should recognize the increase in #1 sealleakoff and inform the SRO NOTE: Trip of the RCP on overcurrent and increase in RCS leakage to 300 gpm should occur at this time Page 6 of 16

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DSS-009 EVENT COMMENTS III. REACTOR TRIP / INCREASED RCS LEAKAGE

- PATH-1 actions Verify reactor tripped Verify turbine tripped

Verify E-1 and E-2 energized

"' Verify SIinitiated NOTE: SRO should direct the implementation of, or implement the actions of AOP-018 for the "B" RCP AOP-018 actions to stop RCP Check RCP "B" running Place PCV-455A controller to manual and adjust output to zero After 90 seconds has elapsed since pump trip then close CVC-303B NOTE: Insert LBLOCA at this time

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IV. LBLOCA

' PATH-1 actions -

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. -- Opens Foldout NOTE: RCP's should be tripped when trip criteria are met in Foldout A Verify Phase A valves closed Verify FW isolation Page 7 of 16

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. DSS-009 EVENT COMMENTS Verify FW pumps tripped

- Verify both MDAFW pumps running Start SDAFW pump as necessary NOTE: The BOP should note that the SDAFW pump has trippe May attempt one restart

' Verify 2 SI pumps running Verify both RHR pumps running SI valves properly aligned 10. Verify at least 1 CCW pump running 11. Verify all SW & SW booster pumps running 12. Verify HVH 1-4 running )

NOTE: RO should note that HVH-1 can not be started - OOS 13. Verify IVSW system initiated 14. Verify CV ventilation isolation -

NOTE: The RO should recognize the failure of V12-10 and 11 to l close. Can be closed by using the control switch onRTGB 15. Verify CR vent aligned for press. mode 16. Verify both EDG's running NOTE: The BOP should recognize the "A" EDG is not running -

OOS Page 8 of 16

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DSS-009 EVENT COMMENTS 17. Energize battery chargers as necessary

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18. Verify CV pressure remains < 20 psig NOTE: RO should note that CV Spray did not actuate and manually initiate CV spray Verify CV spray initiated

... Verify all CV spray pumps running with valves properly aligned Verify approximately 12 gpm spray additive tank flow Verify phase B isolation valves closed Stop all RCP's 19. Verify all MSIV's and MSIV bypass valves are closed 20. Locally open breaker for HVS-1 at MCC-5

21. Check RCS pressure > 1350[1250] psig 22. Verify proper SI flow

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23. Check RCS pressure > 125 psig

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24. Verify proper RHR flow s Align RHR valves j NOTE: RO should recognize no RHR flow l and dispatch an A If dispatched to look for a leak, report back no leak exist , 4

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, DSS-009 EVENT COMMENTS If dispatched to check lineup, report back as directed in scenario

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25. Verify at least 300 gpm AFW flow 26. Verify AFW valves properly aligned 27. Control AFW to maintain S/G level 10 [20]% to 50%

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28. Check RCP thermal barrier cooling water hi or low flow alarm illuminated <

29. Place the steam dump mode selector Switch in manual 30. RCS temperature stable at or trending to 547 degrees Check RCS temperature > 547 degrees Attempt to limit cooldown If cooldown continues and is not due to SI flow then shut the MSIV's and bypass valus 31. Check PZR PORV's closed -

32. Check PZR spray and aux spray valve closed ,

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33. Check at least one RCP mnning l

34. Any S/G pressure decreasing in an uncontrolled manner or completely depressurized 35. R-15 and R-19A, B, C rad levels normal 36. Check for indications of an RCS leak

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DSS 009 EVENT COMMENTS

- Rad monitors, CV pressure, sump level

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37. Go to PATH-1 Entry Point C Entry Point "C" on PATH-1 Reset SPDS, CSFST Monitoring !

NOTE: FRP-P.1 entry conditions will be

.., met and the crew should transition. The crew will transition but not implement any actions due to the LBLOCA Open Foldout "B" Request periodic activity sample of S/G's Check at least one RCP running Any S/G depressurizing in an uncontrolled manner of completely depressurized Control AFW flow to maintain S/G level between 10%[20%) and 50% Check for S/G with uncontrolled level increase

.. Check R-15 and R-19's rad levels normal Check PZR PORV's closed and at least one block valve open -

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10. Reset SI, CV Spray and Phase A and B 11. Establish instrument air to the CV 12. Check offsite power available to the charging pumps and establish desired flow 13. Check CV Spray pumps running Page 11 of 16 . . _ . . _ _ _ _ . _ _ .

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DSS-009 EVENT COMMENTS

, When CV pressure decreases below 4 psig then stop the CV spray pumps

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and close SI-880 valves NOTE: Report back as the inside AO that RHR-764 was found out of position and request permission to reposition the valve (if AO was requested to investigate)

..,

15. SRO should provide permission to open the valve and RO should verify proper RHR flow 16. Check RCS subcooling > 35 [55]

17. When below 10 E-10 amps then energize the source ranges and transfer the

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recorders 18. Check RCS pressure > 275 [400] psig i

j 19. E-1 and E-2 energized by offsite power 20. Check starting air receivers repressurized ,

on the unloaded EDGs j i

21. Stop the unloaded EDG's

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l 22. Verify Supplement D components capable of recirculation NOTE: If the crew never reque'sted -

the AO to investigatewalve

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line up, the crew will transition to EPP-15 due to loss of recirc capability 23. Check Aux building rad levels normal 24. Obtain RCS, boron, and H2 samples 25. RCS pressure > 275 [400] psig

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DSS-009

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EVENT COMMENTS I

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26. Check flow from RHR pumps > 1200 gpm l -

27. Check RWST > 27% I NOTE: Iflevel not below 27% the crew I will be in a loop until this level criteria is met ,

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28. SI system aligned for cold leg recirc ( 29. Transition to EPP-9 " Transition to Cold

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Leg Recirculation" NOTE: Scenario can be terminated at this point at the evaluators discretion l IV. EVENT CLASSIFICATION Classify the event as Site Area Emergency based on RCS leakage > makeup capability and two fission product barriers breached l

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INITIAL CONDITIONSfrURNOVER INFORMATION:

POWER LEVEL: 100% . BORON: 1017 ppm Tavg: 575.3 *F

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TARGET VALUE: + TARGET BAND: 15 MWD /MT: 150 RODS: 218D NORMAL CURRENTS UPPER LOWER N-41 250 250 N-42 250 250

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N-43 250 250 l N-44 250 250 REQUIRED XENON FREE SHUTDOWN BORON CONCENTRATION: l

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HOT: 1188 ppm 100 F COLD: 1646 ppm EQUIPMENT OUT OF SERVICE:

i HVH-1, motor to be replaced this shif "A" EDG OOS for governor repairs, out for two days, repairs to be completed in'two day POWER HISTORY:

Equilibrium Xenon, No power ramp rate restrictio EVOLUTIONS IN PROGRESS:

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CV Pressure Relief in progress IAW OP-921, Section 6.1; maintain current power leve .

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i ES-301 SCENARIO EVENTS - ES-301-3 J

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j SIMULATION FACILITY: H. B. Robinson SCENARIO NO: . DSS-038

! EXAMINERS: APPLICANTS :

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i INITIAL CONDITIONS: The Unit is at 20% nower. The followine eauinment is out of service: HVH-4 out for

{ motor reolacement. will be back this shift. "B" EDG out for hich chromates in cooline water. will

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return this shift. MOV-350 out for limit switch repair. back in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Pressurizer level channel 461 j out due to beine out of tolerance.

I TURNOVER: You have been instmeted to increase oower to 50% in accordance with GP-005. Boron

concentration is 1378 com. CBD at 179 steos. GP-005 comolete through sten 5.4.40.

$ EVENT MAL EVENT EVENT l

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N N TYPE DESCRIPTION I

-

,. _ . m .

,.w.,n. m o m . ... . . n.

! WRFISWS56 : C !"ATSevids1Wil s t .,iE auto"stiutfM.5 a

w@pmAgpgA% -4 kyy mambr'B60sie.n~ un f/f . .

A h R ham >4hd%E % ge Mi.camuc h w4.u migmennyyn

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! 5RFIRHR013h C CA" src.wena pum mygg; fail to auto startsfgy.,pMM ,, !

l IM M M $$ ( U M S $psN@BOMshdd$#MM3/S

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my.~ w,w a w ,ofe~,n.-.;.ymwappm

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1 Eq5 CORD 9 I ! Failure ' 85;S/G "BTiteanipressures

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m W. 5a m f NMbNUM u m + k u wmaM" N SN @x$ :

!

4 2 CORD I Failure low of LT-459, Pressurizer level channel.

LT:459 !

i j 3 N Reduce power to take unit off line due to inability to ' )

take channel LT-459 OOS without tripping unit.

, , . + ,

7 . ny mmy . ., gm,gnmgw m ..x.m . w,e . ,4RM JMFIGEN06d FjnCW ;Sp;urious; Turbine Generator lockoutM,jQ A

.

s%e~$p wm.gc 1.wgge saa gwp ie pq.amic.w mgNmnpyg um;gtwtw !! Ag %%we

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egwgA wan w;..%s .

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. n # w w s Qs,y, m eg ,t w <uts y g iSBLOCA' due to" failure' of Pr,es,.py e gjy s.% v7:g py%,

_

(q,M,;we MFI PRS 04C M y b?

-

su.rizer s'afety causing

. c xanwn steam space LOC .1gs,y .n Re mmw;W vaywee 4 a-

s e w F.w

(N) Normal, (R) Reactivity, (I) Instrument, (C) Component, (M) Major

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Developed By:

v A. m Approved By: W 0/ Q

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I Examiner: JG Chief Examiner:

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SCENARIO EVENTS ES-301-3

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ES-301 SIMULATION FACILITY- H. B. Robinson SCENARIO NO: . DSS-038 A EXAMINERS: APPLICANTS :

HVH-4 out for INITIAL CONDITIONS: The Unit is at 20% oower. The followinc couloment is out of service:

motor reolacement. will be back this shift. "B" EDG out for hich chromates in cooline water. will retum this shift. MOV-350 out for limit switch reonir. back in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Pressurizer level channel 461 out due to beine out of toleranc You have been instmeted to increase power to 50% in accordance with GP-005. BQr.On TURNOVER:

concentration is 1378 com. CBD at 179 steos. GP-005 comolete throuch sten 5.4.4 MAL EVENT EVENT EVENT N TYPE DESCRIPTION N '

^

!RHSWS5d,7 C " AESi$ise:WatEBoostnit$nps~ fail'to aiito startsk

.d.;R,$b .N;hk@$rg,2l&C:@f.&dl &.. N

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C

..

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.T% ":2i 3RHRHR0132 A"JHR'pumpsifail 5 As to auto.startrh%,$. iQ S.?. . _,N ug+ns;5Wf

. , A Q. Mx-m,

..

% : wLt+e 5..u%:. . . 9.:%.w'KC.m w . ..

. , r. s'. vm wr u.gy . ..m,p ws,gyeen.. .y. m c .. :v:a* ,p.w , .7 ;ressure.:U . 9 w-

1 CORDhb; I FsilureJow.of RTd85.S/G "B"Jteanip; WM,

$'yp/p[4g55 7W W-N.. . M U N W. , . . .

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CORD I Failure low of LT-459, Pressurizer level channe LT:459 <- SM N Reduce power to take unit off line due to inabi o (y g

\_ take channel LT-459 OOp ing uni ,. ,

"" o 4 .MFIGEN nerator lykout j ,, ,;c.,

IMe:

e. . C.- :Iass.of offsite po j, ,y ; y 9s3 g EPSl ,

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SBLOCA dtie to failure of Psssurizer causing -

MFIPRSO4C M steam space LOC . w: >V

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(N) Normal, (R) Reactivity, (I) Instrument, (C) Component, (M) Major Approved By:

Developed By:_ v Am g 0 /

.s o 1 / - Chief Examiner:

N Examiner: '77lA % M1

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. ES-301 SCENARIO EVENTS ES-301-3

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k SIMULATION FACILITY- H B. Robinson

SCENARIONO:. DSS-038 8

EXAMINERS: APPLICANTS :

100 % ;

INITIAL CONDITIONS: The Unit is at 909. oower. The followine couinment is out of service: HVH-4 out for ;

motor renlacement will be back this shift. "B" EDG out for hich chromntes in cooline water. will retan this shift. MOV-350 out for limit switch repair. back in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Pressurizer level channel 461 out due to beine out of toleranc checeed to -006 TURNOVER: You have been instructed to inecease power to 50% in accordance with GP-009. Boron concentration is 1378 pom. CBD at 179 steos. CP 005 m J.c.; J.._.. aS 1 !

t EVENT MAL EVENT EVENT N N TYPE DESCRIPTION

. . . . - .. .w

.fA'LSevil: is:Wate. .

nRF.g II_NVS56@..

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o,o,s a %_ , . .. e..%.f l toy auto-starthh y , .-:

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tY *b Y $! 2 h $$ . YY +W Y

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.:.y 4.a ~. yu. u,p . - . , , . .

%RFIRHR0134 C MJtHRyu,mps. fail to auto startr.hW::ssE9 M 5551 d N M3NNf8dNM$$@Id$NE[$6hb@d g

% *m.4; CORD H I n m n .n m ~ 'Emilure3owofEr485.SAI"B"fc* w,4me

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@S M $ N i?RNIh?EN!?N d.GIF$

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f LT:459 RB ' I 'Eiilirreiow-of LT-459, Pressurizer level channe ~ .

3 N Reduce power to take unit offline due to inability to take channel LT-459 OOS without tripping uni . . . .

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iMFI GEN 06;

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i ithT;;w nfh.- 3,E :G C i.% y.yJ Spurious Turbine Generatorlockout

'+S,;4;+p.my.'qy; :.*x pys: 3 *. C+F . x +:V! ..%;9.. m-2,L

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steam space LOCA.CSBLOCA.due

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to. failure of

. . . ."7 (N) Normal, (R) Reactivity, (I) Instrument, (C) Component, (M) Major Developed By: *

s An* 'N Approved By:

O/

f ;

Examiner: '7 72 f) -. !/

YJG N Chief Examiner:

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1 CAROLINA POWER & LIGHT COMPANY

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H. B. ROBINSON PLANT

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INITIAL LICENSE EXAMINATION SCENARIO DSS-038 STEAM PRESSURE CHANNEL FAILURE i

PZR LEVEL CHANNEL FAILURE l

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EXCESS LETDOWN l

TECH SPEC REQUIRED SHUTDOWN TURBINE GENERATOR LOCKOUT - LOSS OF OFFSITE POWER SMALL BREAK LOCA

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DEVELOPED BY: DATE I

APPROVED BY: DATE

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DYNAMIC SIMULATOR SCENARIO EXAMINATION SCENARIO NUMBER: DSS-038

_ SCENARIO NAME: PT-485 failure, LT-459 failure, Excess letdown, Plant shutdown, Turbine Generator Lockout - Loss of Offsite power, SBLOCA TEAM MEMBERS / INDIVIDUAL EVALUATIONS EXAMINERS:

SCO SAT _ UNSAT_

RO SAT _ UNSAT_

BOP SAT _ UNSAT_

...

INITIAL CONDITIONS /rURNOVER INFORMATION:

IC#: 44 POWER LEVEL: 20% BORON: 1378 ppm Tavg: 551 *F TARGET VALUE: + TARGET BAND: 5 MWD /MT: 150 RODS: 179D NORMAL CURRENTS UPPER LOWER N-41 250 250 N-42 250 250 N-43 250 250 N-44 250 250 REQUIRED XENON FREE SHUTDOWN BORON CONCENTRATION:

HOT: 1188 ppm 100*F COLD: 1646 ppm EQUIPMENT OUT OF SERVICE:

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"B" EDG OOS for high chromates in the cooling water, return this shif HVH-4 OOS for motor replacement, expected to return this shif s MOV-350 OOS for limit switch repair, return in 6 hourt -

LT-461 OOS doe to power supply problem, bistables tripped POWER HISTORY:

Reactor startup completed last shift. Unit placed on line two hours ago. No power ramp rate restriction Page 2 of 18

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DSS-038 !

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EVENT COMMENTS SCENARIO DESCRIPTION

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i After shift turnover and allowing the crew to walk down the board, the initiating event will be a failure of steam pressure transmitter Irr-485 low on "B" S/G. This will require manual feed control of the "B" S/G main FRV to restore S/G level. After the plant has been stabilized and the ;

appropriate actions taken to remove the channel from service, a failure of pressurizer level channel

LT-459 low will occur. The crew will not be able to remove the instmment from service due to LT-l '

461 being out of service and will be required to place excess letdown in service. This will require

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.a plant shutdown in accordance with Technical Specifications. After excess letdown has been established and a power reduction has been initiated, a spurious generator lockout will cause a ;

turbine / reactor trip and a loss of offsite power. On the trip, the transient causes a PZR safety valve

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to prematurely open and has failed to rescat causing a PZR steam space LOCA. The service water i booster pump and RHR pump powered from the "A" EDG will fail to automatically start and will

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require manual operator action to start. The crew should respond in accordance with PATH-1. The exercise may be terminated at the discretion of the evaluators after entry into EPP-8 " Post LOCA '

cooldown and depressurization".

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SCENARIO OBJECTIVES i

, Evaluate the response to failed steam pressure channel PT-485 IAW AOP-025.

I Evaluate the response to failed PZR level channel LT-459 IAW AOP-02 . Evaluate the response to a Tech Spec required shutdown due to two PZR level channels out i of servic ~ Evaluate the response to a Turbine generator lockout and loss of offsite power IAW PATH- . Evaluate the response to a SBLOCA IAW PATH- . Evaluate the SRO's ability to direc't the crew during abnormal and emergency conditions in accordance with the above listed procedure l i

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DSS-038 EVENT COMMENTS I. ~ STEAM PRESSURE CHANNEL FAILURE l

I BOP recognition of failure BOP diagnose the failure of PT-485 "B" S/G pressure low which causes steara flow channel FT-484 to indicate low 1 Takes the "B" FRV maintain S/G level to 39%-52%

NOTE: These are immediate operator actions for AOP-025. Actual l S/G levi will not change much due to low power condit! ion l l Actions per AOP-25 "RTGB Instrument l Failure" l l l Enter appropriate section for the failure NOTE: Since both the steam pressure and steam flow are affected.

l Should implement section G first since the steam pressure channelis the failed channel

- Place the "B" FRV in manual Restore the affected S/G level to ,

N between 39% and 52% '

. -. Place the "B" S/G steam flow selector l switch to channel 485 l Restore "B" FRV to autornatic Check S/G level within 1% of

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programmed level Page 4 of 18 l

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DSS-038 EVENT COMMENTS

~ Place the "B" FRV in AUTO Remove the steam pressure channel 485 from service using OWP-025, SGP-8 Implement EAL's

..- Check Tech Specs for applicable LCO's Retum to procedure and step in effect NOTE: The crew may also elect to take steam flow channel FT-484 out of service at this time. Insert the LT-459 failure prior to taking FT-484 out of service I PZR LEVEL CHANNEL FAILURE RO recognition of failure Diagnose that PZR level channel LT-459 has failed lo Actions per AOP-025 "RTGB Instmment

Failure" Check CVC-460A&B closed

' Place control switches to close for CVC-

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460 A and B Restore PZR level to between 22% and 53 %

. Check the number of operable PZR i level channels greater than one

Page 5 of 18

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.t DSS-038 EVENT COMMENTS

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NOTE: Number of operable channels equals one due to LT-461 OOS Place excess letdown in service using OP-301 " Chemical and Volume Control System"

..- Consult Tech Spec Tables 3.5-2 and 3.5-5 for LCO actions NOTE: The SRO should determine that a plant shutdown is required for not meeting minimum degree of redundancy Contact plant operations staff to expedite repair of the failed PZR level channels NOTE: Inform the crew as I&C that repairs can not be completed on 461 due to parts and can not work on 459 without tripping the unit

Verify selector switch LR-459 for PZR level recorder selected to LT-460 Implement EAL's .

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II GP-006 ACTIONS FOR PLANT SHUTDOWN Prepare for unit shutdown SRO conducts a brief and reviews the precautions and lindtations of the procedure Page 6 of 18

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DSS 038 EVENT COMMENTS

- Complete the initial conditions of '

section Initiate plant shutdown ' Start additional charging pumps and open additional orifices as necessary for

..- the shutdown NOTE: Can not complete due to letdown isolated and on excess letdown Reduce turbine load as follows Set desired load in the SETTER

, Select the desired load rate i Depress the GO push button Verify that Tave and PZR level remain on program Maintain rods above the rod insertion limit

. Have the AO start the Aux boilers IAW OP-401 if required When poweris in the range of 15h20%

then open all turbine drain valvis - When generatorload is between 90 and l 110 MW then transfer the auxiliary l electricalloads from the Aux l

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transformer to the S/U transformer

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DSS-038

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EVENT COMMENTS

Open feed pump recire valves FCV-1444 and FCV-1445

, When poweris etween 15% and 20%

then transfer rods to manual 1 When poweris between 10% and 15%

' *

... then transfer feed to the bypasses )

i i NOTE: Initiate the generator lockout '

and loss of offsite power when doing the transfer to the S/U

transformer or when the crew requests additional assistance in the control room for a S/G

level watch I SMALI BREAK LOCA PATH-1 actions Verify reactor trip Verify turbine tripped

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NOTE: Initiate the PZR steam space break on the loss of offsite power

' Verify E1 & E2 energized _y Attempt to restore power to the deenergized bus If additional power is required then place the dedicated shutdown dieselin service using EPP-25 Page 8 of 18

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DSS-038 EVENT COMMENTS NOTE: If requested, tell the crew that

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the "B" EDG will be ready for service in 30 minutes i' Verify SIinitiated Opens Foldout A

- NOTE: Will have to call the AO's to locally close MSR valves Verify Phase A valves closed NOTE: Request AO's to locally close valves without power Verify FW isolation valves closed NOTE: Request AO to close or verify closed V6-B and V6-C Verify both FW pumps tripped NOTE: Only one bus energized, will not be able to start components powered from "B" EDG

. Verify both MDAFW pumps running 1 Start the SDAFW pump as necess

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1 Verify two SI pumps running 1 Verify both RHR pumps running

)

NOTE: RO should recognize the !

failure of the "A" RHR pump )

to start and manually start the ;

pump i

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DSS-038 EVENT COMMENTS

1 Verify SI valves properly aligned 1 Verify at least 1 CCW pump running NOTE: Crew will have to manually start either "B" or "C" CCW Pump

.., Check CV spray initiated Start one CCW pump Verify FCV-626 is closed 1 Verify ali SW & SW booster pumps running Attempts to start all Service Water and Service Water Booster pumps Checks North and South SW headerlow pressure alarms illuminated Close V2-16C or V2-16 A and B

- Implement Supplement "M" NOTE: The RO should note the failure of the "A" SW booster pump to start and nianually starTthe Pump 1 Verify HVH 1-4 mnning NOTE: Can only run HVH 1 and 2 with the loss of"B" ED Page 10 of 18

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DSS-038 EVENT COMMENTS t

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1 Verify IVSW system initiated 1 Verify CV ventilation isolation 1 Verify CR vent aligned for press, mode

... NOTE: Evaluator que that exhaust fans are stopped and dampers are closed 2 Verify both EDG's running NOTE: "B" EDG OOS 2 Energize battery chargers as necessary 2 Verify CV pressure remains < 20 psig 2 Checks for auto steam line isolation 2 Verify MSIV's and bypass valves closed 2 Locally open breaker for HVS-1 at MCC-5 2 Check RCS pressure > 1350[1250] psig ~l 2 Verify proper SI flow

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I NOTE: No indications on control * l board of flow'due to LOOP 2 Check RCS pressure >125 psig 2 Verify at least 300 gpm AFW flow available

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3 Verify AFW valves properly aligned l

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DSS-038 EVENT COMMENTS

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3 Control AFW to maintain S/G level l 10 [20]% to 50%

3 Check RCP thermal barrier cooling water hi or low flow alarm illuminated 3 Place the steam dump mode selector

... Switch to steam pressure t

3 RCS temperature stable at or trending to 547 degrees i

3 Check PZR PORV's closed j 3 Check PZR spray and aux spray valve closed

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3 Check at least one RCP running l

3 Any S/G pressure decreasing in an uncontrolled manner or completely depressurized l 3 R-15 and R-19A, B, C rad levels normal

NOTE: PRT should be ruptured at this ,

point providing increasing CV ~ '

trends 4 Check for indications of an RCS leak s Rad monitors, CV pressure,-

sump level

! 4 Go to PATH-1 Entry Point C l

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. c DSS 038 EVENT COMMENTS

- PATH-1 entry point C Reset SPDS, CSFST Monitoring Open Foldout "B" NOTE: If requested earlier, call the

- control room and inform them the "B" EDG is ready to be returned to service i Request periodic activity sample of S/G's Check at least one RCP running i Any S/G depressurizmg m an l

uncontrolled manner of completely !

depressurized ;

l Control AFW flow to maintain S/G l level between 10%[20%) and 50% Check for S/G with uncontrolled level increase

Check R-15 and R-19's rad levels normal Check PZR PORV's clos 6d and at least i one block valve open , .y I 1 If offsite poweris lost then restart safeguards equipment i

1 Reset SI, CV Spray and Phase A and B

1 Establish instrument air to the containment Page 13 of 18

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DSS-038

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EVENT COMMENTS

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1 Check offsite power available 1 If adequate diesel capacityis not available to run charging pumps then shed non-essentialloads using Supplement "F'

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... 1 Start at least one charging pumps and establish desired flow 1 Check CV Spray pumps mnning 1 Check RCS subcooling > 35 1 When below 10 E-10 amps then energize the source ranges and transfer the recorders 1 Check RCS pressure > 275 [400] psig 2 Check RCS pressure stable or increasing i 2 Stop RHR pumps 2 Check for any S/G with uncontrolled depressurization

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2 Check RCS pressure increasing 2 E-1 and E-2 energized by offsite power s

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2 Attempt to restore offsite power to l E-1 and E-2 NOTE: If requested, inform the l operator that offsite power will j be restored in about 30 - 60 l minutes Page 14 of 18 l

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DSS 038 EVENT COMMENTS i

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2 Restart battery chargers within 30 :

minutes t

2 Verify EDG's are properly loaded )

2 Verify emergency oil pump is mnning )

..- 2 Locally verify the air side seal oil I backup pump is running 3 If diesel capacity is not adequate to run instrument air compressors and battery chargers then shed non-essential loads using Supplement "F'

3 Locally load instmment air compressor and battery chargers :

3 Check E-1 and E-2 energized by offsite ;

power i l

3 Verify Supplement D components l capable of recirculation 3 Check Aux building rad levels normal 3 Obtain RCS, boron, and H2 samples i 3 RCS pressure > 275 [400] psig 3 Transition to EPP-8 " Post LOCA 4 Cooldown and Depres'surization- - 1 NOTE: Scenario can be terminated at this point at the evaluators discretion Page 15 of18

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! VI.- EVENT CLASSIFICATION .

. Classifies as Site Area Emergency based on l RCS leakage > charging pump capacity

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JANf24-97FR10915 DRSt1AllR00t1 FAX N0. 8608212 P.02

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EFFECTIVE DATE: 08/15/06, G U I D A N C E WHAT /HOW/WHEN/WHERE0T0_S1HD _" pit OT-STYLE" EXAMINATION MATERI A1. TO THE PDR o 'WHAT TO SEND: Facility outline Facility initial exam submittal (written and operating portion)

3. As given final exam (written and operating in its entirety)

o HOW TO SEND:

The facility outline and the facility initial exam submittal (written and operating portion) are bond together and be one package. The bottom right hand corner of the first page will have distribution code A07 The as given final written exam (as usual) will be attached to the examination report and distributed as you did before. The bottom right

. . hand corner of the first page will have distribution code IE4 .

The as given final operating exam in its entirety will be one packag The bottom right hand corner of the first page will have distribution code A07 NOTE: YOU WILL HAVE THREE SEPARATE PACKAGE Place the entire exam material for each facility in one xerox box marked as follows:

Name of Fecility, Region, Document Control Desk, Mail Stop 0-5-D-24, Box I of If all three packages do not fit into one xerox box, please include the same information on additional box (s) and number the boxes appropriately, (i.e., Box 1 of 2, Box 2 of 2).

- - - 1f your region feels the above in not incompliance with NRC****

Inspection Manual, Mano.. Chapter 0620, Section 04.06(b)

" Licensee Controlled Documents, Records, and Information,"

you may forward your material to the PDR under a separate cover letter containing the above informatio Distribution code IE42 should NOT appear anywhere but on the Examination Repor This code has a distribution list attached to it with the following:

Distribution:

PD NRR/DRCH/HHFB PM RGN. . File 01 ACRS NOAC File Center NRC POR NRR/DRCH/HOLB

+

a -

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JA!P24-97 FRI'09iS9 DRS M IL 1 ~ FAX'NO.86082i2 ~ 5 03 i

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g' *

t UNITED STATES I'

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= 2 NUCLEAR' REGULATORY COMMISSION 5 f WASHINGTON, D.C. 20555-0001

\..,..../ i August 15, 1996 MEMORANDUM FOR: Virgil Curley, Licensing Assistant Operator Licensing and Human Performance Branch Division of Reactor Safety, RI q l

Beverly Michael, Licensing Assistant Operator Licensing and Human .

Performance Branch l Division of Reactor Safety, RII Mary Ann Bies, Licensing Assistant Operations Branch ,

Division of Reactor Safety, RIII l Laura Hurley, Licensing Assistant Operations Branch Division of Reactor Safety, RIV THRU: Stuart A. Richards, Chief Operator Licensing Branch Cg h1 Division of Reactor Controls and Human Factors, NRR

.

Debbie McCain, Licensing Assist V N

hd[\O(hb l

FROM: _

Operator Licensing Branch ;

Division of Reactor Controls I and Human Factors, NRR i I

SUBJECT: PLACEMENT OF EXAMINATION ITEMS INTO THE PUBLIC )

DOCUMENT ROOM (PDR)

I am providing you additional information on the above. On June 5,1996,

R01-96-11 and a memo to you from me regarding the placement of examination items into the PDR was distributed. I received 5 additional items from ;

Mary Ann Bies, Licensing Assistant, Rill, requesting verification / guidance 1 on the following: l l "We send to the PDR the facility's initial submission of their outline j and all parts of the exam they write." j This is correct. As stated in the June 5, 1996, note, 'What is required l by law and what needs to be placed in the PDR is correspondence to the NRC that leads to the issuance of an operators license, i.e., the outline the facility submits and the facility's initial exam submittal that is sent to the NRC for review."

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j ; JAW 24-97 FRI 10:00 DRS liAll R00l1 F5fi$.86i51f P,04

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Licensing Assistant August 15, 1996 i

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I "Any changes before reaching the final product approved by the NRC is i not to go to the PDR."

l This is correct. As stated in the June 5, 1996, note, "All reiterations i that happen between the time the facility submits their exam to the NRC {

for review, and the time the NRC actually puts a seal of approval on the !

final product, is not what is required to be sent to the PDR." l i "The final written goes to the PDR as an enclosure to the exam report ,

(as usual). However what about the operating exam? The masters are not ;

sent out with the exam report. Are we required to send to the PDR these i final NRC-approved operating exam masters as written by the facility?"

This is correct. You are required to send to the PDR those final NRC- *

. approved operating exam masters as written by the facilit See the attached for guidanc *

' "Also, regarding record retention of the operating exam masters, we keep the scenarios in the exam package, but we only keep in the exam package the JPMs if they result in a failure of the JPM portion of the exam by a .i candidate. Rev. 8 nakes no mention of keeping the final JPMs in the ':

package. However, if we are required to keep the initial submission of ;

the exam the facility licensee submits to the NRC for review and !

approval, it seems we should also keep the final product as approved by !

the NRC. Is this correct?" '

The as given' written and operating exam in it's entirety is sent to the PD See the attached for guidance. As stated in the June 5, 1996, note, the as given written exam (as always) is attached to the exam report and placed in the PDR. As always, only keep in the exam package the JPMs if they result in a failure of the JPM portion of the exam by a candidate.- As stated above, the entire operating exam will be sent to the PDR. Nothing new is being required to be kept. I believe the issue here is you will be sending all parts of the operating exam to the PDR and only retaining a copy of a portion. It is up to you if you chose to keep copies of all portions of the o]erating tes It is not going to be required in NUREG-1021. If you c1oose to keep copies, I suggest, at a maximum, keep. copies of the complete exam for the first few. You can always call the PDR (202-634-3273) and see if your material made it until you gain some trust in the system and develop a level of comfor The chances of something not arriving in the POR are not very great. I i don't'believe it is worth your time and effort to make copies of the voluminous amount of material Just in case this happens. It is your choice.

l i "We talk of the Pilot items going to the PDR, but am I correct in j

! understanding that once the pilot-style exams become Rev. 8 exams that i are written by the facility licensee, we will routinely continue sending these items to the PDR?"

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Licensing Assistants -3- August 15, 1996 This is correct. Any exam that is the " pilot-style" exam and once the

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p'ilot-style exams become Rev. 8 exams that are written by the facility j licensee, you will routinely continue sending these items to the PDR )

using the guidance attache !

> When we first started talking about this whole issue of what, how, when, and where to send pilot-style exam material to the PDR, I had suggested, and actually gave you, a sample cover note to send with the material being sent to the PDR. This cover note is not necessary, and the Document Control Desk chooses not to get it. The attached guidance specifically states how to mark the boxes being sent. If the boxes are marked correctly, the cover note T

serves no purpos Most importantly, that is one less thing for you to do.

,

I suggest that as quickly as possible, you take the time to box these exams up

'

and get them out of your office. In the middle of August, exams being given l l the " pilot style" are starting up again. This will avoid some confusion and !

lessen the room for error. Not to mention getting alot of paper out of your !

,

offic J

.

I have had several meetings with the Document Control staff and many l

-

'

conversations with the PDR. During these meeting and conversations I informed i them that in the near future there will be twenty-two examination packages j- being sent to them, and then things should level off to a steady flow.

l

Attachment:

As stated i l

REGION N

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NUMBER OF PAGES~. .o PLUS TRANSMITTAL SHEET TELECOPY NUMBER: _ VERIFICATION NUMBER:

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l EFFECTIVE DATE: 08/16/06 9*

G U I D A N C E WHAT/HOW/WHEN/WHERE TO SEND " PILOT-STYLE" EXAMINATION _ MATERIAL TO THE PDR

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o WHAT TO SEND: Facility outline Facility initial exam submittal (written and operating portion)

3. As given final exam (written and operating in its entirety)

a HOW T0__ SEND:

The facility outline and the facility initial exam submittal (written ,

and operating portion) are bond together and be one package. The bottom

'

right hand corner of the first page will have distribution code A07 The as given final written exam (as usual) will be attached to the examination report and distributed as you did before. The bottom right l

,

. hand corner of the first page will have distribution code IE4 The as given final operating exam in its entirety will be one packag The bottom right hand corner of the first page will have distribution code A07 NOTE: YOU WILL HAVE THREE SEPARATE PACKAGE Place the entire exam material for each facility in one xerox box marked as follows:

Name of facility, Region, Document Control Desk, Mail Stop 0-5-D-24, i Box 1 of ). If all three packages do not fit into one xerox box, I please include the same information on additional box (s) and number the boxes appropriately, (i.e., Box 1 of 2, Box 2 of 2). >

- - - If your region feels the above in not incompliance with NRC**** I Inspection Manual, Manual Chapter 0620, Section 04.06(b)

" Licensee Controlled Documents, Records, and Information," l you may forward your material to the POR under a separate cover letter containing the above informatio Distribution code IE42 should NOT appear anywhere but on the Examination Report. This code has a distribution list attached to it with the following:

Distribution:

PD NRR/DRCH/HHFB PM RGN... File 01 ACRS NOAC File Center NRC POR NRR/DRCH/HOLB

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August 15, 1996 MEMORANDUM FOR: Virgil Curley, Licensing Assistant Operator Licensing and Human Performance Branch Division of Reactor Safety, RI Beverly Michael, Licensing Assistant Operator Licensing and Human Performance Branch Division of Reactor Safety, RII Mary Ann Bies, licensing Assistant Operations Branch Division of Reactor Safety RIII Laura .Hurley,: Licensing Assistant Operations Branch Division of Reactor Safety, RIV THRV: Stuart A. Richards, Chief Operator Licensing Branch Cg(M Division of Reactor Controls and Human Factors, NRR

.

FROM: Debbie McCain, Licensin0 Assist Operator Licensing Branch q- N Division of Reactor Controls Qh_aQd .KN4UA >

d and Human Factors, NRR

,

SUBJECT: PLACEMENT OF EXAMINATION ITEMS INTO THE PUBLIC DOCUMENT ROOM (PDR)

I am providing you additional information en the above. On June 5, 1996, R01-96-11 and a memo to you from me regarding the placement of examination i items into the PDR was distributed. I received 5 additional items from

'

Mary Ann Bies, Licensing Assistant, RIII, requesting verification / guidance !

'

on the following: "We send to the PDR the facility's initial submission of their outline and all parts of the exam they write "

This is correc As stated in the June 5, 1996, note, "What is required by law and what needs to be placed in the PDR is correspondence to the NRC that leads to the issuance of an operators license, i.e., the outline the facility submits and the facility's initial exam submittal that is sent to the NRC for review."

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. Licensing Assistants -2- August 15, 1996 "Any changes before reaching the final product approved by the NRC is j not to go to the PDR." l

! 1 This is correct. As stated in the June 5,1996, note, "All reiterations I r

'

that happen between the time the facility submits their exam to the NRC '

for review, and the time the NRC actually puts a' seal of approval on the I final product, is not what is required to be sent to the PDR." "The final written goes to the PDR as an enclosure to the exam report i

(as usual). However what about the operating exam? The masters are not I sent out with the exam report. Are we required to send to the PDR these final NRC-approved operating exam masters as written by the facility?"

1 This is correct. You are required to send to the PDR those final NRC-l approved operating exam masters as written by the facilit See the

'

attached for guidanc . "Also, regarding record retention of the operating exam masters, we keep the scenarios in the exam package, but we only keep in the exam package the JPMs if they result in a failure of the JPM portion of the exam by a candidat Rev. 8 makes no mention of keeping the final JPMs in the packag However, if we are required to keep the initial submission of the exam the facility licensee submits to the NRC for review and approval, it seems we should also keep the final product as approved by the NRC. Is this correct?"

!

The as given written and operating exam in it's entirety is sent to the PD See the attached for guidance. As stated in the June 5, 1996, l note, the as given written exam (as always) is attached to the exam '

report and placed in the PDR. As always, only keep in the exam package

'

the JPMs if they result in a failure of the JPM portion of the exam by a candidat As stated above, the entire operating exam will be sent to the PDR. Nothing new is being required to be kept. I believe the issue l here is you will be sending all parts of the operating exam to the PDR

! and only retaining a copy of a portion. It is up to you if you chose to l keep copies of all portions of the operating test. It is not going to I

be required in NUREG-1021. If you choose to keep copies. I suggest, at i a maximum, keep copies of the complete exam for the first few. You can always call the PDR (202-634-3273) and see if your material made it until you gain some trust in the system and develop a level of comfor The chances of something not arriving in the PDR are not very great. I don't believe it is worth your time and effort to make copies of the voluminous amount of material just in case this happen It is your ,

choice.

' "We talk of the Pilot items going to the PDR, but am I correct in

understanding that once the pilot-style exams become Rev. 8 exams that

are written by the facility licensee, we will routinely continue sending

these items to the PDR?"

e

JAW 24-97 FH1 10:00 DRS HA!L N000 PAX NU bbub212 r Uo

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' _ Licensing Assistants -3- August 15, 1996 i

"

This is correc Any exam that is the " pilot-style" exam and once the pilot-style exams oecome Rev. 8 exams that are written by the facility licensee, you win routinely continue sending these items to the PDR using the guidance attached.

q

When we first started talking about this whole issue of what, how, when, and where to send pilot-style exam material to the PDR, I had suggested, and

,

actually gave you, a sample cover note to send with the material being sent to the PDR. This cover note is not necessary, and the Document control Desk chooses not to get it. The attached guidance specifically states how to mark i the boxes being sent. If the boxes are marked correctly, the cover note serves no purpos Most importantly, that is one less thing for you to d I suggest that as quickly as possible, you trke the time to box these exams up

and get them out of your office. In the middle of August, exams being given j' the " pilot style" are starting up again. This will avoid some confusion and lessen the room for error. Not to mention getting alot of paper out of your

,

office.

I have had several meetings with the Document Control staff and many conversations with the PDR. During these meeting and conversations I informed j them that in the near future there will be twenty-two examination packages being sent to them, and then things should level off to a steady flo Attachment:

As stated cc w/ attachment:

G. Heyer, RI T. Peebles, RII

< M. Leach, RIII J. Pellet, RIV b

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JnN-24-81 PK1 10:01 UMS DHit KUUN PHA NU. Obud212 P. Ud

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EFFECTIVE DATE: 08/15/96 G U I D A N C E

,

WHAT/HOW/WHEN/WHERE TO SEND " PILOT-STYLE" EXAMINATION MATERIAL TO THE PDR i

.

!

o WHAT TO_ SEND- Facility outline ! Facility initial' exam submittal (written and operating portion) l 3. As given final exam (written and operating in its entirety)

-

!

o HOW TO_ SEND:

The facility outline and the facility initial exam submittal (written i and operating portion) are bond together and be one package. The bottom right hand corner of the first page will have distribution code A07 The as given final written exam (as usual) will be attached to the i examination report and distributed as you did before. The bottom right hand corner of the first page will have distribution code IE4 !

The as given final operating exam in its entirety will be one packag The bottom right hand corner of the first page will have distribution ;

code A07 !

NOTE: YOU WILL HAVE THREE SEPARATE PACKAGE Place the entire exam material for each facility in one xerox box f marked as follows: !

'

Name of Facility, Region, Document Control Desk, Mail Stop 0-5-D-24, Box 1 of 1. If all three packages do not fit into one xerox box, I please include the same information on additional box (s) and number j the boxes appropriately, (i.e., Box 1 of 2, Box 2 of 2).

- - - If your region feels the above in not incompliance with NRC**** !

Inspection Manual, Manual Chapter 0620, Section 04.06(b) !

" Licensee Controlled Documents, Records, and Information," ;

you may forward your material to the PDR under a separate i cover letter containing the above informatio ;

i Distribution code IE42 should NOT appear anywhere but on the Examination l Report. This code has a distribution list attached to it with the :

following: !

Distribution: .

PD NRR/DRCH/HHFB !'

PM RGN... File 01 ACRS NOAC !

'

File Center NRC PDR l

NRR/DRCH/HOLB

- . _ _ _, _ _ .-

r'. u r ^^ ~~

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JRN-24-sl}Mi IV:Ul'~ ^ DES hNiL31fUh ~ rHi sV.~ oo0c2i2 ~

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EFFECTIVE DATE: 08/15/96 PAGE 2 0F 2

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G U I D A N C E j

If distribution code IE42 were placed on all 3 packages going to the Document Control Desk /PDR it would receive the above distribution. IT IS TOO V01.UMINOUS AND NOT NECESSARY TO HAVE ANYTHING OTHER THEN THE f)(AMINATION REPORT RECEIVE THIS DISTRIBUTIO Distribution Code A070 has a distribution list attached to it with the following:

Distribution:

! File Center PDR

! o WHEN TO SEND:

The above 3 packages are sent AT THE SAME TIME to ensure it remains and

' is filed in the PDR together. Since it has to be sent to the Document Control Desk at the same time, it obviously gets sent after the exam is give o WHERE TO SEE: ,

Any material going to the Document Control Desk is sent to headquarters l

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at Mail Stop 0-5-0-24.

.

ADDITIONAL INFORMATION:

!

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When the exam material reaches the Document Control Desk, it is given to the

< contractor, and is placed on microfiche. All the exam material in the POR is available on microfiche and paper. Microfiche can be purchased for $7.00 per fiche. Each microfiche contains approximately 300 hundred pages of material

,

and be carried away in your shirt pocket. A paper copy can be purchased for

5.09 per page, and most likely would be unable to carry it awa The paper copy that you sent to the Document Control Desk is sent to the PDR with the appropriate microfiche and kept for the public to look at in the PD i

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7-JAF2697'FR1'09iS9 ~ ~"DRSrtIUO0fi ~ ~}AX'110.8608212 ~ P. 01

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UN!1ED STATES

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PRIORITY:

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MESSAGE FROM: M4 / I/ i V > -

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CONTA c- /N f[d ~ [c2M

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TRANSMITTAL INSTRUCTIONS / ATTACHMENT (Sk i

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DISPOSITION:

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Transmitted & Verified by: Return to Originator Place in Mail 4 Other

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v t e Inspection Report - Robinson - 1996301 (Operator Exams)
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
1996 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle 7(0) 8(0) 10(0) 11(0) 12(0) 13(0) 14(0) 99(0) Security Operator Exams 300(0) 301(0) Emergency Planning Other

IR 05000261/1996301

Text

Attachment:

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