ML082950384

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R. E. Ginna Draft - Outlines (Folder 2)
ML082950384
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/01/2008
From:
Ginna
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML080030004 List:
References
TAC U01687
Download: ML082950384 (23)
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ES-301, Rev. 9 Administrative Tooics Outline Form ES-301-1 Facility: R. E. Ginna Date of Examination: 08/25/2008 Examination Level: RO SRO 0 Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

CRITICAL ROD POSITION CALCULATION Conduct of Operations M,S or R JPM N-RA-I WA 2.1.25 3.9 14.2 Manually Calculate QPTR Conduct of Operations M,P,S JPM N-RA-2 KIA 2.1.7 4.4 14.7 ragout Boundary for B Heater Drain Tank Pump Equipment Control M,S P M N-RA-3 WA 2.2.13 4.1 14.3 Radiation Control Monitor Critical Safety Function Status Trees Emergency Plan M,S or R JPM N-RA-4 IUA 2.4.13 4.0 14.6

Type Code* Safety Function

3. Alternate Dilution of the RCS (RIB occurs; during dilutiion) JPM A S,N,A I 004 A2.16 3.213.6
3. Transfer ECCS to Cold Leg Recirculation (Ah. Path) JPMB S,M,A 2 EPE 01 1 EA1.11 4.214.2
2. Placing LTOP on Service 010 A4.03 4.013.8 JPM I S,N,L I 3 A. Respond To a Control Room Evacuation (4lt Path) JPM S,N,A 4P APE 068 AA1.23 4.3 14.4
3. Respond to a Total Loss of SW JPME S,M,A 4s 076 A2.01 3.5*/3.7*
. Shutdown the "A" Emergency Diesel Generator JPM S,D 6 064 A4.06 3.913.9
3. Remove a Power Range Channel From Service JPM S,D 7 015 A2.02 3.1/3.5*

I. Shutdown Containment Purge JPM S,D,L 8 APE 036 AA1.01 3.313.8 I. Startup and Parallel Rod Drive MG Set (Parallel Fails) JPM I N,L,A 1 001 A4.08 3.713.4

. Align Fire Water System to Fill the CSTs Llsing JPM J Condensate Transfer System D,E 4s 061 K4.01 4.114.2

q. Trip of Failed AC Emergency UV Relay JPM D,R,E 7 APE 077 AA1.05 3.914.0
  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 14-6 I 2-3 (C)ontrol room (D)irect from bank sgisais4 (E)mergency or abnormal in-plant 21121I21 (L)ow-Power I Shutdown E l I21 I21 (N)ew or (M)odified from bank including 1(A) 2212212 1 (P)revious 2 exams I3 I 5 3 I I2 (randomly selected)

( W A I 2 1/ E l I21 (S)imulator

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: R. E. Ginna Date of Examination: 08/25/2008 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Verify Estimated Critical Rod Position Calculation Conduct of Operations IPM N-SA-I KIA 2.1.37 4.6 4-52.12, Inoperability of Equipment Conduct of Operations .IPM N-SA-2 WA 2.1.18 3.8 Review the Tagout Boundary for B Heater Drain Tank Pump Equipment Control .rPM N-SA-3 IUA 2.2.13 4.3 Implement the Requirements of ODCM for RMS Operability Radiation Control N,S or R JPM N-SA-4 IUA 2.3.15 3.1 Event Classification Emergency Plan D,S or R JPM N-SA-5

/A 2.4.41 4.6 NOTE
All items (5 total) are required for Sl3Os. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
  • Type Codes & Criteria: (C)ontrol rclom, (S)imulator, or Class(R)oom (D)irect froin bank ( S 3 for ROs; I 4 for SROs & RO retakes)

(N)ew or (h4)odified from bank (2 1)

(P)revious .2 exams (I1; randomly selected)

ES-301, Rev. 9 Control Room/ln-Pla nt Systems Outline Form ES-301-2 I(1 Facility: R. E. Ginna Exam Level: RO 0 SRO-I SRO-U 0 Date of Examination: 0812512008 Operating Test No.:

Control Room Systems@(8 for RO); (7 for SFIO-I); (2 or 3 for SRO-U, including 1 ESF) 1 Type Code* Safety Function

a. Alternate Dilution of the RCS (RIB occurs during dilutiion) JPM A
b. Transfer ECCS to Cold Leg Recirculation (Ah. Path) JPM B EPE 01 1 EAl.11 4.2/4.2
d. Respond To a Control Room Evacuation (Alt Path) JPM D APE 068 AA1.23 4.3 14.4
e. Respond to a Total Loss of SW JPM E 076 A2.01 3.5*13.7*
f. Shutdown the "A" Emergency Diesel Generator JPM F 064 A4.06 3.913.9
g. Remove a Power Range Channel From Service JPM G 015 A2.02 3.1/3.5*
h. Shutdown Containment Purge JPM H APE 036 AA1.01 3.313.8 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Startup and Parallel Rod Drive MG Set (Parallel Fails) 001 A4.08 3.713.4
j. Align Fire Water System to Fill the CSTs Using Condensate Transfer System 061 K4.01 4.114.2
k. Trip of Failed AC Emergency UV Relay JPM D,R,E 7 APE 077 AA1.05 3.914.0

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes I Criteria for RO / SRO-I I SRO-U (A)lternate path 4-6I 4-612-3 (C)ontrol room (D)irect from bank S9/58/14 (E)mergency or abnormal in-plant 2-l/rllrl

&)ow-Power I Shutdown 2 1 I 2 1121 (N)ew or (M)odified from bank including 1(A) 2212212 1 (P)revious 2 exams 5 3 I 5 3 I -c 2 (randomly selected)

(RFA 21/21/21 (S)imulator I

Appendix D Scenario Outline Form ES-0-1 Facility: R. E. Ginna Scenario No.: 1 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: 70%, EOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed electronics, MDAFW Pump A 00s for impeller replacement Event Malf. Event Event No. No. Type*

Description 1 TUR16B I- BOP/SRO PT-486. Turbine First Staae Pressure Fails Low.

2 RCS11F I-All, TS-SRO Loop B That TE-404A fails high.

C-ATCISRO, 3 SGN04B TS-SRO S/G B T -Ibe Leak of = 10 gpm R-ATC, 4 N/A N-BOP/SRO Plant Pcwer Reduction RCS158, 5 RCSl5D C-ATC/S RO RCP 1 6 High Vibration SGN046, STMOS, STM05B, Main Steam Line Break Downstream of MSlVs which causes S/G tube RHRO1A, leak to rise to a 400 GPM tube rupture in S/G 6.MSlV B fails to close M-All, RPS07C, automatically or manually from the MCB, SI Pump C fails to Auto Start on 6 RPSO7D C-BOP SI Signal, RHR Pump A trips on auto start.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (h!)ajor Revision 00 Page 1 of 17

Amendix D Scenario Outline Form ES-D-1 Facility: R. E. Ginna Scenario No.: 2 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: 1OO%, BOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed electronics, MDAFW Pump A 00s for impeller replacement Event Malf. Event Event No. - No. Type* -

1 HTR02A C-BOP/SR0 Heater Drain Tank Pump 1A Trips R-ATC, 2 N/A N-BOP/SRO Power Reduction to 70%

I -ATC/SRO, 3 PZR04 TS-SRO Pressurizer Pressure Master Controller PC-431K output fails high C-ATC/SRO, 4 RCS02C TS-SRO RCS Leak Hot Leg 6 I -BOP/SRO, 5 SGNO1D TS-SRO S/G A Level LT-463 fails high RCSOBC, RPS07E, RPS07F, RPS07L, Large Break LOCA Hot Leg 6, RHR Pumps A and 6 ,fail to auto start RPS07M, M-ALL, on SI Signal, MDAFW Pump B and the TDAFW Pump fail to auto 6 RPS07N C-BOP start

  • (N)orrnal, (R)eactivity, (I)nstrurnent, (C)ornponent, (M)ajor Revision 00 Page 1 of 20

Appendix D Scenario Outline Form ES-D-1 Facility: R. E. Ginna Scenario No.: 3 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: io%, BOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed electronics Event No.

Malf.

No. I Event Type*

R-ATC, 1 N/A N-BOP/SRO Power Ascension RCSl 1C, I-ALL, 2 ROD12 TS-SRO Loop A TcoldTE-401B Fails Low, Rod Block failed OVR-MISO6B, OVR-MISOGD, C-SRO, 3 A-EDS16 TS-SRO Containment Recirculation Fan Cooler A Trips 4 CVC 1OA I-ATC/SRO VCT Level Transmitter LT-112 Fails High Feedwater Control Valve B, FCV-476, Auto Controller Fails 5 FDWO7C I- BOP/SRO High, w/Manual Control available STM03, STM05A, STMOSB, Main Steam line break downstream of MSIVs, both MSlVs fail to SIS02A, M-ALL, I- close automatically or from the MCB, SI fails to actuate when 6 SISO2B ATC setpoint reached

  • (N)ormal. (R)eactivity, (I)nstrument, (C)ornponeni, (M)ajor Revision 00 Page 1 of 16

- Appendix D Scenario Outline Form ES-D-1 Facility: R. E.Ginna Scenario No.: 4 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: 70%, MOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed Electronics, MDAFW Pump A 00s for impeller replacement Event Malf. Event Event No. No. Type* - Description C-ATCISRO, 1 RCS16 TS-SRO High RCS Activity I-BOP/SRO, 2 SGN03B TS-SRO Steam Generator A Pressure Transmitter PT-469 Fails Low Letdown Non-Regenerative Heat Exchanger Outlet Temperature TT-3 cvco5 I-ATC/S RO 130 '=ails Low 4 FDW04B C-BOP/SRO Feeclwater Pump B Lube Oil System Leak N-BOP/SRO, 5 N/A R-ATC Down Power to 50%

CND08, RPS05A, RPS05B, FDW12, Concensate Line Break, Bus 16 Fault, Loss of Feedwater &

6 EDS04B M-All Preferred AFW

  • (N)orrnal, (R)eactivity, (I)nstrument, (C)omponen, (M)ajor Revision 00 Page 1 Of 16

-Appendix D Scenario Outline Form ES-D-1

- - - P -

Facility: R. E. Ginna Scenario No.: 5 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions: 100°/~,EOL Turnover: SI Pump A 00s to refurbish failed motor, S/G A LT-461 00s due to failed Electronics, MDAFW Pump A OOS for impeller replacement Event Malf. Event Event No. No. Type*

- Description 1 N/A TS-SRO EDG A Fuel Oil High Particulates 2 TURl 1B Turbine Control Valve V3463 Fails Closed N-BOP/SRO, 3 N/A R-ATC Plant Down Power C-ATC/SRO, 4 ROD02-G7 TS-SRO Dropped Rod G7 5 RCS12A C-ATC/SRO RCP 1A #1 Seal Failure 6 C-ATC/SRO Rods C5 and K9 fail to insert on trip R CS02D, RPSO6, RPS07B, RPS07C, M-All, Small Break LOCA, CI fails to occur automatically or manually, SI 7 RPS07D I/C BOP Pumps B and C fail to start automatically (N)orrnal, (R)eactivity, (I)nstrurnent, (C)ornponent, (M)ajor Revision 00 Page 1 of 19

ES-401 PWR Examination Outline Form ES-401-2 Facilitv: R. E. Ginna Date Of Exam: 09/05/2008 I

~~

SRO-Only Points Note:

1. Ensure that at least two topics from every applic:able WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by *1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutionswithin each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolutim or system. Refer to Section D.l .b of ES-401 for the applicable WAS.

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A:? or G' on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

1

PWR RO Examination Outline Facility: R. E. Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2

--4PE # I Name I Safety Function I K1 Points 000007 Reactor Trip - Stabilization - Recovery X I1 000008 Pressurizer Vapor Space Accident I 3 000009 Small Break LOCA I 3 000011 Large Break LOCA I 3 I000022 Loss of Rx Coolant Makeup I 2 1

I 000025 Loss of RHR System I 4 000027 Pressurizer Pressure Control System Ix 1 Malfunction 13 000038 Steam Gen. Tube Rupture 13 1 I000040 Steam Line Rupture - Excessive Heat X 1 mfer I 4 000054 Loss of Main Feedwater I 4 1 000055 Station Blackout 16 1 000056 Loss of Off-site Power I 6 1 1

1 000065 Loss of Instrument Air I 8 000077 Generator Voltage and Electric Grid Disturbances 1 6 r

WE04 LOCA Outside Containment I 3 WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 1

PWR RO Examination Outline Facility: R. E. Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 4PE # I Name I Safety Function WA Category Totals:

m 2

PWR RO Examination Outline Facility: K.E. Ginna ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2

' -'4PE # I Name I Safety Function Points 000003 Dropped Control Rod I 1 1 000033 Loss of Intermediate Range NI 17 1 00005 1 Loss of Condenser Vacuum I 4 3.9 000068 Control Room Evac. I 8 3.9 WE02 SI Termination I 3 3.5 WE03 LOCA Cooldown - Depress. 1 4 3.7 WE08 RCS Overcooling - PTS 14 3.6 1 WE10 Natural Circ. 14 3.3 1 W E 16 High Containment Radiation / 9 2.9 1 K/A Category Totals: Total:

-9 I

PWR RO Eramination Outline Facility: R. E. Ginna ES - 401 Plant Systt:ms- Tier 2 / Group 1 Form ES-401-2

.,~3 Reactor Coolant Pump 003 Reactor Coolant Pump 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 0 10 Pressurizer Pressure Control 0 12 Reactor Protection 0 13 Engineered Safety Features X Actuation 022 Containment Cooling 2 Containment Cooling 026 Containment Spray 039 Main and Reheat Steam 7

06 1 AuxiliaryEmergency Feedwater 06 1 AuxiliaryEmergency Feedwater X 062 AC Electrical Distribution 062 AC Electrical Distribution 063 DC Electrical Distribution I 1x1 064 Emergency Diesel Generator

~~

073 Process Radiation Monitoring

PWR RO Elramination Outline Facility: R. E. Ginna ES - 401 -

Plant Systems Tier 2 / Group 1 Form ES-401-2 dEvol # / Name

~ ~

076 Service Water 078 Instrument Air 078 Instrument Air 103 Containment KIA Category Totals:

2

PWR RO Examination Outline Facility: R. E. Ginna Plant Systcmms - Tier 2 / Group 2 ES - 401 -

Form ES-401-2 I

-dEvol# / Name Imp. 'oints d 2 Reactor Coolant 3.2 1

31 5 Nuclear Instrumentation 3.9 1

3 17 In-core Temperature Monitor 3.7 1 334 Fuel Handling Equipment 2.6 1 341 Steam Dumpmurbine Bypass 2.7 1 Control -

345 Main Turbine Generator 4.2 1 of system and understand 07 1 Waste Gas Disposal A4.09 - Waste Gas release 3.3 1 072 Area Radiation Monitoring 3.4 1 075 Circulating Water 2.6" 1

~~ --

Q86Fire Protection 3.1 1 I KIA Category Totals: 10 1

ES-401 PWR Examination Outline Form ES-401-2 Facilitv: R. E. Ginna Date Of Ex.am: 09/05/2008 I I RO w A Category Points I SRO-Only Points Note:

1. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by i 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutionswithin each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted ancl justified; operationally important, site-specific systems/evolutionsthat are not included on the Dutline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolutim or system. Refer to Section D.1.b of ES-401 for the applicable WAS.

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable licen:;e level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A:! or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

1

PWR SRO Examination Outline Facility: R. E. Ginna ES - 401 -

Emergency and Abnormal Plant Evolutions Tier 1 I Group 1 Form ES-401-2 IPE # I Name I Safety Function U K 3 Points 300015/000017 RCP Malfunctions / 4 1 300026 Loss of Component Cooling Water I 8 1 andor availability of safety related 300029 ATWS I 1 1 300058 Loss of DC Power / 6 W E 1 1 Loss of Emergency Coolant Recirc. 1 4 WE12 - Steam Line Rupture - Excessive Heat Transfer I 4 WA Category Totals:

0 0 0 1

PWR SRO Examination Outline Facility: R. E. Ginna ES 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 4PE# / Name / Safety Function K1 K2 K3 000036 Fuel Handling Accident I 8 000037 Steam Generator Tube Leak I 3 000059 Accidental Liquid RadWaste Rel. 1 9 I I1 WE14 Loss of CTMT Integrity I 5 WACategory Totals: 0 0 0 1

PWR SRO ESxamination Outline Facility: R.E. Ginna Form ES-401-2 1

PWR SRO Examination Outline Facility: R. E. Ginna ES - 401 Plant Systi:ms - Tier 2 / Group 2 Form ES-401-2 Group Point Total:

rI 1

2008 Ginria NRC Exam SRO

7. SRO Question # 77 - Changed from: 000026 Loss of Component Cooling Water 2.2.39 -

Knowledge of less than or equal to one hour Technical S pecification action statements for systems Changed to: 000026 Loss of Component Cooling Water 2.2.37 - Ability to de1,ermine operability andor availability of safety related equirlment.

Reason: Unable to write a discriminating question at the SRO level.

8. SRO Question ## 80 - Changed from: \.'/El 1 Loss of Emergency Coolant Recirc EA2.2 - Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Changed to: W E I 1 Loss of Emergency Coolant Recirc. EA2.1 - Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation): Facility cond itions and selection of appropriate procedures during abnormal and emergency operations.

Reason: Unable to write a discriminating question at the SRO level.

9. SRO Question # 94 - Changed from: 2.1.4 - Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

Changed to: 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc Reason: Unable to write a discriminating question at the SRO level.

10. SRO Question ## 100 - Previously reported.
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