ML110400252

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Final Outlines (Folder 3)
ML110400252
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 12/12/2010
From:
Susquehanna
To: Caruso J
Operations Branch I
Hansell S
Shared Package
ML102180025 List:
References
TAC U01793
Download: ML110400252 (22)
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Text

ES-401 Written Examination Outline Form ES-401-1 Susquehanna LOC-23 Facility:

NRC Written Exam ROKIA Tier Group K K 1 2

1. 3 4 Emergency

& 2 Plant Tier Evolutions 4 5 Totals 2

2.

Plant 2 0 12 Systems Tier 3 4 3 6 3 4 3 3 3 4 3 38 Totals

3. Generic Knowledge & Abilities 2 3 4 10 Categories 2 3 2 3 Note: I. Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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 +/-l 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/evolutions within each group are identitied on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.I.b of ES-401, for guidance regarding elimination of inappropriate K/A 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 KAs 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 KIA categories.
7.
  • The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b of ES-40 I for the applicable KIA's
8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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 A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
  1. 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 KIA numbers, descriptions, IRs, and totals Form ES-40\-3. Limit to KlAs that are linked to IOCFR55.43 Rev 4, 12/20/10

ES-401 2 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # I Name Safety Functi KIA Topic(s)

AKI.OI Knowledge of the operational 29500 I Partial or Complete Loss implications of the following concepts as of Forced Core Flow Circulation I I X they apply to PARTIAL OR COMPLETE 3.5 39

&4 LOSS OF FORCED CORE FLOW CIRCULATION: Natural circulation AKI.Ol- operational implications of the following concept~ as 295006 SCRAM I I X 3.7 40 they apply to SCRAM: Decay heat and removal AK 1.03 - Knowledge of the operational implications of the following concepts as 295003 Partial or Complete Loss they apply to PARTIAL OR COMPLETE of AC 16 X LOSS OF A.C. POWER: Under 2.9 41 295025 High Reactor Pressure I 3 X 4.1 42 295030 Low Suppression Pool X 3.7 43 Water Levell 5 295028 High Drywe\l Temperature X 3.2 44 15 Rev 4, 12/20/10

ES-401 2 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE It I Name Safety Function KJA Topic(s)

EK3.06 - Knowledge of the reasons for the following responses as they apply to 295024 High Drywell Pressure I 5 X J> 4.0 45 HIGH DRYWELL PRESSURE: Reactor SCRAM i

.: *.:;c AK3.04 - Knowledge of the reasons for the following responses as they apply to 600000 Plant Fire On-site I 8 X I: PLANT FIRE ON SITE: Actions 2.8 46 contained in the abnormal procedure for

" plant fire on site AK3.05 - Knowledge of the reasons for the following responses as they apply to 295005 Main Turbine Generator X MAIN TURBINE GENERATOR TRIP: 2.5 47 Trip/3 I,\~~{\\: Extraction steam/moisture separator isolations

.'/> EA1.03 - Ability to operate andlor monitor the following as they apply to 295026 Suppression Pool High X SUPPRESSION POOL HIGH WATER 3.9 48 WaterTemp./5 TEMPERATURE: Temperature

.>':..' monitoring I:' EA1.05 - Knowledge of the reasons for the following responses as they apply to 295038 High Off*site Release Rate X HIGH OFF-SITE RELEASE RATE: Post 3.0 49

/9 accident sample system (PASS): Plant Specific

.: . AA 1.07 - Ability to operate andlor monitor the following as they apply to 295023 Refueling Accidents 18 X 3.6 50 REFUELING ACCIDENTS: Standby gas treatment/FRVS EA2.04 - Ability to determine andlor 295031 Reactor Low Water Level interpret the following as they apply to X 4.6 12 REACTOR LOW WATER LEVEL:

Adequate core cooling

.' AA2.04 - Ability to determine andlor interpret the following as they apply to 2950 IS Partial or Total Loss of )( PARTIAL OR COMPLETE LOSS OF CCW/S Y; COMPONENT COOLING WATER:

System flow

.. : AA2.03 - Ability to determine andlor H~

295016 Control Room interpret the following as they apply to Abandonment 17 4.3 53 CONTROL ROOM ABANDONMENT:

Reactor pressure 295021 Loss of Sh 2.4.1 - Emergency Procedures I Plan:

/4 Knowledge of EOP entry conditions and 4.6 54 immediate action steps.

. AK2.01 - Knowledge of the 295004 Partial or Total Loss of interrelations between PARTIAL OR DC Pwr/6 X 3.1 55 COMPLETE LOSS OF D.C. POWER and the following: Battery Charger.

1-*( c.

2.4.9 - Emergency Procedures 1 Plan:

295019 Partial or Total Loss of Knowledge of low power 1 shutdown Inst. Air /8 implications in accident (e.g., loss of 3.S 56 coolant accident or loss of residual heat I  :-",: removall mit!flation strategies.

k:* AA 1.04 - Ability to operate andlor 295016 Control Room monitor the following as they apply to Abandonment 17 X 3.1 57 CONTROL ROOM ABANDONMENT:

A.C. electrical distribution 700000 Generator Voltage and AK3.02 - Knowledge of the reasons for X the following responses as they apply to 3.6 58 Electric Grid Disturbances GENERATOR VOLTAGE AND Rev 4, 12120/10

ES-401 2 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # I Name Safety Function KIA Topic(s)

ELECTRIC GRID DISTURBANCES:

l:~ Actions contained in abnormal operating procedure for voltage and grid

':"',,2:", disturbances.

K/A Category Totals: 3 4 3/3,. 2/4 Group Point Total:

I 20/7 Rev 4, 12120/10

ES-401 3 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # I Name Safety Function KiA Topic(s) 295035 Secondary Contaimnent X 3.9 59 High Differential Pressure 15 EK2.0 I - Knowledge of the operational 295033 High Secondary implications of the following concepts as 3.8 Containment Area Radiation X they apply to HIGH SECONDARY 60 Levels 19 CONTAINMENT AREA RADIATION LEVELS: Area radiation AK3.0 I - Knowledge of the reasons for the following responses as they apply to 295015 Incomplete SCRAM II X 3.4 61 INCOMPLETE SCRAM: Bypassing rod 295007 High Reactor Pressure I 3 X 3.7 62 EA2.02 - Ability to determine andlor interpret the following as they apply to 295034 Secondary Contaimnent SECONDARY CONTAINMENT 3.7 63 Ventilation High Radiation 19 VENTILATION HIGH RADIATION:

Cause of radiation levels 2.1.23 - Conduct of Operations: Ability to 295029 High Suppression Pool perform specific system and integrated plant Water Levell 5 X procedures during all modes of plant 4.3 64 AA2.04 - Ability to determine andlor 295008 High Reactor Water Level interpret the following as they apply to 12 HIGH REACTOR WATER LEVEL: 3.1 65 KIA Category Totals: 7/3 Rev 4, 12/20/10

ES-401 4 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#

1 2 3 4 5 6 1 3 4 Kl.OI - Knowledge of the physical connections and/or cause- effect relationships between 264000 EDGs 3.8 EMERGENCY GENERATORS (DIESEUJED and the following:

A.c. electrical K1.07 - Knowledge of the phySical connections and/or cause- effect relationships between PRIMARY 223002 PCIS/Nuclear Steam CONTAINMENT ISOLATION 3.4 2 Supply Shutoff SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the Reactor core isolation cooling; 263000 DC Electrical Distribution 3.1 3 2150031RM 2.5 4 206000 HPC[

Rev 4, 12120/10

ES-401 4 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 System # I Name K K K K K K A A2 A A G I~P Q#

1 2 3 4 5 6 1 3 4 K3.11 - Knowledge of the effect that a loss or malfunction of the 212000 RPS X REACTOR PROTECTION 6 SYSTEM will have on following:

Recirculation system K4.07 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM 215005 APRM I LPRM X 3.7 7 design feature(s) and/or

interlocks which provide for the following
Flow biased trip setpoints K4.03 - Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) 217000 RCIC X design feature(s) and/or 2.9 8 interlocks which provide for the following: Prevents pump over heating K5.01 - Knowledge of the operational implications of the following concepts as they apply 2.6 215004 Source Range Monitor X 9 to SOURCE RANGE MONITOR

' , (SRM) SYSTEM: Detector J. ....... '. operation K5.13 - Knowledge of the operational implications of the 300000 Instrument Air X following concepts as they apply 2.9 10 to the INSTRUMENT AIR SYSTEM: Filters K6.01 - Knowledge of the effect that a loss or malfunction of the 263000 DC Electrical X following will have on the D.C. 3.2 II Distribution ..

ELECTRICAL DISTRIBUTION:

A.C. electrical distribution K6.04 - Knowledge of the effect that a loss or malfunction of the 209001 LPCS X following will have on the LOW 2.8 12 PRESSURE CORE SPRAY SYSTEM: D A1.05 - Ability to predict and/or monitor changes in parameters associated with operating the 261000 SGTS X STANDBY GAS TREATMENT 2.7 13 SYSTEM controls including:

Primary containment oxygen level: Mark*I&1I A1.02 - Ability to predict and/or monitor changes in parameters 203000 RHRlLPCI: Injection associated with operating the X 3.9 14 Mode RHRlLPCI: INJECTION MODE (PLANT SPECIFIC) controls including: Reactor pressure Rev 4, 12/20/10

ES-401 4 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # / Name A2 G Q#

1 2 3 4 5 6 1 3 4 A2.03 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on 211000SLC those predictions, use 3.2 15 ii*.. ' procedures to correct, control, or

'i'(r' mitigate the consequences of 1/

.ii" those abnormal conditions or

.i.":: operations: A.C. power failures

. *. . A2.02 Ability to (a) predict the I impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) 259002 Reactor Water Level based on those predictions, use Control x** procedures to correct, control, or 3.3 16 mitigate the consequences of

.! those abnormal conditions or operations: Loss of any number

..

'.. A3.04 - Ability to monitor

.!.. automatic operations of the 239002 SRVs x .0.( RELIEF/sAFETY VALVES 3.6 17

.. .,;~ including: Acoustical monitor noise: Plant-Specific

, .... A3.01 - Ability to monitor

.....**. 'i' ~ automatic operations of the

'£;: CCWS including: Setpoints on 400000 Component Cooling x .. '~ instrument signal levels for 3.0 18 Water normal operations,wamlngs, and

'. trips that are applicable to the

  • CCWS A4.04 - Ability to manually 215004 Source Range operate and/or monitor in the 3.2 19 Monitors control room: SRM drive control switches

...~ A4.02 Ability to manually operate and/or monitor in the 205000 Shutdown Cooling X 3.6 20 control room: SDC/RHR suction valves 2.4.18 - Emergency Procedures 26200 I AC Electrical Distribution X / Plan: Knowledge of the specific 3.3 21

" bases for EOPs .

2.2.40 - Equipment Control:

218000 ADS X... Ability to apply technical 3.4 22 specifications for a system.

K2.03 - Knowledge of electrical 206000HPC[ x power supplies to the followlng: 2.8 23 Initiation logic: BWR-2,3,4 K4.02 - Knowledge of D.C.

ELECTRICAL DISTRIBUTION 263000 DC Electrical design feature(s) and/or Distribution x / interlocks which provide for the 3.1 24 following: Breaker interlocks, permissives, bypasses and cross ties: Plant-Specific Rev 4, 12/20110

ES-401 4 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name KKK K A A2 A A G Imp Q#

1 2 3 6 1 3 4 A4.16 - Ability to manually operate and/or monitor in the control room: Manually activate 212000 RPS X 4.4 25

,. ~. antiCipated transient without

. SCRAM circuitry/RRCS: Plant

", Specific A3.08 - Ability to monitor automatic operations of the 203000 RHRlLPCI: Injection I *r~,

Mode X RHRlLPCI: INJECTION MODE 4.1 26

'" (PLANT SPECIFIC) including; System initiation sequence KIA Category Totals: 2 3 2 3 2 2 2~3 3 ~' Group Point Total:

T 2615 Rev 4, 12/20/10

ES-401 5 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K A A

~ ~

Q System # I Name A2 G Imp.

1 2 3 4 5 3 4 #

x 201003CRDM 3.2 27 219000 RHRlLPCI:

2.5 28 Torus/Pool Cooling Mode 202002 Recirculation Flow X 2.9 29 Control 216000 Nuclear Boiler Inst. 3.4 30 234000 Fuel Handling 2.9 31 Equipment K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the 201001 CRD Hydraulic 3.0 CONTROL ROD DRIVE HYDRAULIC System: Plant Air monitor changes in parameters associated with operating the 290003 Control Room HVAC 3.2 3 CONTROL ROOM HVAC controls including: Radiation Rev 4, 12120/10

ES-401 5 Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 System # 1 Name K K K K K K A A2 A A G Imp. a 1 2 3 4 5 6 1 4 m

3 #

A2.01 - Ability to (a) predict the

.... impacts of the following on the

. ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions. use 215002 Rod Block Monitor procedures to correct. control.

X 3.3 34 System " or mitigate the consequences of those abnormal conditions or operations:

'.' Withdrawal of control rod in f~~ high power region of core:

BWR-3.4,5 Knowledge of REACTOR MANUAL CONTROL SYSTEM 201002 RMCS X

< design 3.5 35

> feature(s) and/or interlocks f:1 which provide for the ntrol rod blocks

~

1:"< A4.09 - Ability to manually 204000 RWCU X ope**" ."diDC mo"ilo"" tho 2.9 36 control room: Reactor water temperature 2.1.28 - Conduct of Operations:

202002 Recirculation Flow Knowledge of the purpose and 4.1 37 Control  ;:. function of major system components and controls.

K4.02 - Knowledge of

< SECONDARY CONTAINMENT design feature(s) and/or 29000 I Secondary CTMT X r interlocks which provide for the following: Protection against 3.4 38

.. . over pressurization: Plant-

.... System KJ A Category Totals
1 1 1 3 1 1 1 1/2 0 1 1/1 Group Point Total:

I 12/3 Rev 4, 12/20110

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: LOC-23 NRC Written Exam Date:

Category 1.

Conduct 2.1.3 3.7 66 of Operations 2.1.29 4.1 67 s

2.

Equipment conditions for 2.2.22 4.0 68 Control rations and limits.

Ability to determine the expected plant configuration using design and configuration 2.2.15 3.9 69 control documentation, such as drawings, line-u etc.

Knowledge of conditions and limitations in the 2.2.38 3.6 74 facil license.

3.

Radiation Control 2.3.11 Ability to control radiation releases. 3.8 70 Rev 4, 12120/10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such 2.3.12 as containment entry requirements, fuel 3.2 71 handling responsibilities, access to locked h-radiation areas, filters etc.

Knowledge of the parameters and logic used

4. to assess the status of safety functions, such Emergency as reactivity control, core cooling and heat 2.4.21 4.0 72 Procedures / removal, reactor coolant system integrity, Plan containment conditions, radioactivity release cont etc.

Ability to recognize abnormal indications for system operating parameters which are entry 2.4.4 4.5 73 level conditions for emergency and abnormal ures.

Knowledge of system set pOints, interlocks 2.4.2 and automatic actions associated with EOP 4.5 75 conditions.

Subtotal 3 Tier 3 Point Total 10 Rev 4, 12120110

ES-401 Record of Rejected KIA's Form ES-401-4 Randomly Tier / Group Reason for Rejection Selected KIA 2/1 262002 I Al.02 The subject KIA isn't relevant at the subject facility.

This KIA is too similar to question #43,295030 EK2.04, 211 203000 I K6.06

. double *eODlard 2 11 211000 I K6.04 2I 1 300000 I 2.2.4 Operation of the FPCC system does not routinely require operators to refer to reference material such as graphs, 2/2 233000 12.1.25 tables or charts. Therefore it is not possible to prepare a sufficiently discriminating question related to this subject k/a.

Insufficient procedural, training material, or design basis 295013 I documentation is available to create a sufficiently 1/2 AK1.01 discriminating, psychometrically sound question for this Rev 4, 12120/10

ES-401 Record of Rejected KIA's Form ES-401-4 3 11 2.1.1 Rejected KIA based on Chief Examiner direction.

2/2 226001 1 K1.11 Replaced with 226001 K6.11 per Chief Examiner direction.

It is not possible to write an RO level discriminating 111 295004 1 2.2.25 related to the ect KIA.

211 2180001 A4.01 Repeat of task evaluated in simulator scenario 2/2 2260011 K6.11 NRC Chief Examiner direction It isn't possible to prepare a psychometrically sound 2/2 201001 1 K6.03 related to the ect KIA It isn't possible to prepare a psychometrically sound 2/2 2010021 A3.02 related to the ect KIA 1/2 295012/2.1.23 Rev 4, 12120/10

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Date of Examination: 1/11/11 Examination Level SRO IRI Operating Test Number: LOC-23 NRC Administrative Topic Type Describe activity to be performed Code*

(See Note)

Conduct of Operations M,R 2.1.7 4.7 OO.AD.3658.101 Perform RE-1 TP-026, Validation of Heat Balance at 90% Power Conduct of Operations M,R 2.1.25 3.9 45.0N.1829.101 Implement ON-145-004, "Reactor Water Level Anomaly",

Determine Cause For Erroneous RPV Water Level Indications And Determine Required Tech Spec Actions Equipment Control M,R 2.2.14 4.3 78.AD.2319.102 Perform LPRM Upscale Alarm Operability Tracking In Accordance With 01-078-001 and Determine Required Actions Radiation Control N,R 2.3.11 4.3 00.AD.1018.001 Respond to SGTS Exhaust High Radiation While Purging Primary Containment Emergency Plan M,R 2.4.41 4.6 00.EP.001.087 Classify A Site Area Emergency Under Shutdown Conditions And Complete The Emergency Notification Report; Upgrade To A General Emergency And Determine Protective Action Recommendations NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; S 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (s 1; randomly selected)

NUREG-1021 , Revision 9, Supp 1 LOC-23 NRC Exam Rev 5

Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Date of Examination: 1/11/11 Examination Level RO Ixl Operating Test Number: LOC-23 NRC Administrative Topic Type Describe activity to be performed Code*

(See Note)

Conduct of Operations N, R 2.1.5 2.9 00.AD.3246.052 Evaluate Overtime Request With Respect To Work Hour Limits lAW NDAP-QA-0025 Conduct of Operations M,R 2.1.25 3.9 45.0N.1829.101 Implement ON-145-004, "Reactor Water Level Anomaly",

Determine Cause For Erroneous RPV Water Level Indications Equipment Control M,R 2.2.14 3.9 78.AD.2319.102 Perform LPRM Upscale Alarm Operability Tracking In Accordance With 01-078-001 and Determine Required Actions Radiation Control N/A Emergency Plan M,S 2.4.43 3.2 00.EP.1135.081 Control Room Communicator Emergency Notification NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

"Type Codes & Criteria (C)ontrol Room, (S)imulator, or Ctass(R)oom (D)irect from bank (S.3 for ROs; .::;, 4 for SROs & RO retakes)

(N}ew or (M}odified from bank (~ 1)

II (P}revious 2 exams (.::;, 1; randomly selected)

NUREG-1021, Revision 9, Supp 1 LOC*23 NRC Exam Rev. 2

ES-301 Control Room/In-Plant Systems Outline ES-301-2 Facility: SSES Date of Exam ination: 1/18-21/11 Exam Level: RO IX I Operating Test No.: LOC-23 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. 44.0N.1792.1 01 256000 A4.08 3.7/3.7 L,N,S 2 EmerQency Cond Pump Ops b.64.0P.4841.101 202001 A4.01 3.7/3.7 L,N,S 4 Post Scram Recovery of RRP
c. 34.EO.1619.1 01 400000 A4.01 3.1/3.0 E,EN,M,S 8 Reset / restore OW Cooling d.04.0N.1203.251 262001 A2.07 3.0/3.2 A,N,S 6 Energize a Dead 4KV ESS Bus (Alt Path) e.35.0N.1662.101 233000 A2.02 3.1/3.3 N,S 9 RHRSW to Fuel Pool f.55.0N.2000.152 201003 A2.01 3.4/3.6 A,M,S 1 Respond to a Stuck Rod (Alt Path) g.78.0P.3680.101 215005 A2.04 3.8/3.9 N,S 7 Insert SLO Setpoints h.93.EO.1129.151 241000 A4.02 4.1/4.1 A,I'J,S 3 Perform Alternate RD Using Bypass Valves (Alt Path)

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. 24.0P.1443.051 264000 A4.04 3.7/3.7 A,M 6 Manual SID EDG (Alt Path)
j. 55.EO.1995.201 201003 A2.01 3.4/3.6 D,E,L,R 1 Vent Rod overpiston k.73.0P.2289.103 223001 A2.01 4.3/4.4 E,M 5 Start Recombiner manually

@ 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 Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank :S9/:S8/:S4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - / - / ~1 (control room system)

(L)ow-Power / Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams :S 3/ :S 3/ :s 2 (randomly selected)

(R)CA ~1/~1/~1 (S)imulator

ES-301 Control Roomlln-Plant Systems Outline ES-301-2 Facility: SSES Date of Examination: 1/18-21/11 Exam Level: SRO-I IX I Operating Test No.: LOC-23 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function a.44.0N.1792.101 256000 A4.08 3.7/3.7 L,N,S 2 Emergency Cond Pump Ops

b. I'J/A SRO-I c.34.EO.1619.101 400000 A4.01 3.1/3.0 E,EN,M,S 8 Reset / restore DW Cooling d.04.01'J.1203.251 262001 A2.07 3.0/3.2 A,N,S 6 Energize a Dead 4KV ESS Bus (AIt Path) e.35.0N.1662.101 233000 A2.02 3.1/3.3 N,S 9 RHRSW to Fuel Pool f.55.0N.2000.152 201003 A2.01 3.4/3.6 A,M,S 1 Respond to a Stuck Rod (Alt Path) g.78.0P.3680.101 215005 A2.04 3.8/3.9 N,S 7 Insert SLO Setpoints h.93.EO.1129.151 241000 A4.02 4.1/4.1 A,N,S 3 Perform Alternate RD Using Bypass Valves (Alt Path)

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. 24.0P.1443.051 264000 A4.04 3.7/3.7 A,M 6 Manual SID EDG (Alt Path)
j. 55.EO.1995.201 201003 A2.01 3.4/3.6 D,E,L,R 1 Vent Rod overpiston k.73.0P.2289.103 223001 A2.01 4.3/4.4 E,M 5 Start Recombiner manually

@ 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 Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant  ;::1/;::1/;::1 (EN)gineered safety feature - / - / ;::1 (control room system)

(L)ow-Power / Shutdown  ;::1/;::1/;::1 (N)ew or (M)odified from bank including 1(A)  ;::2/;::2/;::1 (P)revious 2 exams :5 3/:5 3/:5 2 (randomly selected)

(R)CA  ;::1/;::1/;::1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline ES-301-2 Facility: SSES Date of Examination: 1/18-21/11 Exam Level: SRO-U IX I Operating Test No.: LOC-23 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. 44.0N.1792.1 01 256000 A4.08 3.7/3.7 L,N,S 2 Emergency Cond Pum pOps
b. N/A SRO-U c.34.EO.1619.101 400000 A4.01 3.1/3.0 E,EN,M,S 8 Reset I restore DW Cooling
d. N/A SRO-U
e. N/A SRO-U
f. N/A SRO-U
g. N/A SRO-U h.93.EO.1129.151 241000 A4.02 4.1/4.1 A,I'J,S 3 Perform Alternate RD Using Bypass Valves (Alt Path)

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. 24.0P.1443.051 264000 A4.04 3.7/3.7 A,M 6 Manual SID EDG (Alt Path)
j. 55.EO.1995.201 201003 A2.01 3.4/3.6 D,E,L,R 1 Vent Rod overpiston
k. N/A SRO-U

@ 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 Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 12-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 ~1 (control room system)

(L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~ 1 (P)revious 2 exams s 31 s 3 1 s 2 (randomly selected)

(R)CA ~1/~1/~1 (S)imulator

Appendix 0 Scenario Outline Form ES-O-1 Facility: SSES Scenario No.: 1 Op-Test No.: LOC23 NRC Examiners: Operators:

Initial Conditions: U1 operating a 75%. Unit 2 Mode 2. Startup.

Turnover:

Suppression Pool Cogling is in sgrvice with RHR Loop 'A'. OP-149-005 is complete up to Step 2.1.20. RHRSW and ESW arg not to bg /agcured followi!Jg shuldown gf RHR Pump 'A' due to subseguent sugport of schedulgg RHR Surveilli3nce Test. Qnce Suppression Pool Cooling is secured, commence returning Rx Power 10 100~ using Recirc. RE direclions: rai/ae Power iaw Form OP-AO-338-1 (1o/olmin from 75% to 85%, then Hold until RE verifications completed). r Event Malf. Event Event No. No. Type* Description 1 N Secure Suppression Pool cooling: BOP 2 SBLC injection valve: SRO TS 3.1.7 3 1 N Raise Rx Power: SRO ATC 4 2 C,R EHC oscillation: C: SRO, BOP R:ATC 5 3 C HPCI inadvertent start: SRO BOP TS 3.5.1 6 4 C Aux Bus 11 A de-energize: ALL 7 5 R Loss Main Condenser vacuum: SRO,ATC 8 6 I Failure to Scram: ATC 9 7 M SRV tailpipe rupture \ stuck open: ALL

. (N)ormal (R)eactlvity, (I)nstrument, (C)omponent (M)ajor

Appendix 0 Scenario Outline Form ES*[)'1 J

Facility: SSES Scenario No.: g Op-Test No.: LOC23 NRC Examiners: Operators:

Initial Conditions: Unit 1 at 100 percent power EOL. Unit 2 in MODE 1.

Turnover: U1 at 100%1 U2 at full power. Scheduled activit~ for the jihift is tQ swap TBC~W pumQs.

Maintain full Qower oQeration.

Event Malt. Event Event No. No. Type* Description 1 N SwapTBCCW: SRO BOP 2 1 C Loss 1Y115: SRO BOP TS 3.3.3.1 3 R Min Gen Emera: SRO,ATC 4 2 C CREOASS inoo: BOP 5 3 C RRP MG hi temp: SRO. BOP 6 4 C Loss FW Heatina: SRO,ATC TS 3.2.2 7 5 C 4 Rods Drift: ATC 8 6 M ATWS: ALL 9 7 C SBLC dearadation: BOP 10 8 C RWCU fail to isolate: BOP 11 9 C EHC malfunction: SRO, BOP 12 M RD due to HCTL: SRO, BOP

. (N)ormal (R)eactivitv, (l)nstrument (C)omponent (M)aior

"'.....

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