ML072690112

R. E. Ginna Final Examinations Outlines (Folder 3)

ML072690112
Person / Time
Site:	Ginna
Issue date:	05/11/2007
From:	Reid J Constellation Energy Group
To:	Caruso J NRC Region 1
Sykes, Marvin D.
Shared Package
ML063560007	List: ML071310329 ML072340101 ML072400127 ML072640224 ML072681173 ML072681198 ML072681202 ML072690061 ML072690085 ML072690103 ML072690105 ML072690112 ML072690120 ML072690132 ML072690139 ML072690147 ML072690158 ML072780402
References
ES-401-2 IR-07-301
Download: ML072690112 (20)

Text

\

f%Lf#[ 0LK4AIc

- - ES-401 Form ES-401-2 RO WA Category Points SRO-Only Points Systems 2 2 0 1 1 1 1 1 0 1 1 1 10 0 1 1 2 3 Tier 5 2 3 3 3 4 4 3 3 4 4 38 3 5 8

, Totals

3. Generic Knowledge and Abilities 1 2 3 1 4 10 1 2 3 4 ,

Categories 2 2 2 4 2 2 1 2 Note: I I l'

2.

Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e.. except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA cateaorv shall not be less than two).

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 +from I 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. Systemslevolutions within 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding 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 KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratinas for the RO and SRO-onlv oortions. resDectivelv.

I 6. I Select SRO toDics for Tiers 1 and 2 from the shaded svstems and WA cateaories 17' I The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the toDics must be relevant to the aDDliCable evolution or svstem.

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 A2 or G' on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # I does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the WA 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 10CFR55.43 NUREG-I021 1

ES-401 Ginna Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function I G I K1 1 K2 I K3 I A I I A2 I Number I KIA Topic@) I Imp. I Q#

009 /Small Break LOCA / 3 I l l Ability to determine or interpret the following as they apply to a small break LOCA Actions to be taken if PTS limits are violated Emergency Procedures / Plan Ability to perform 4.4 without reference to procedures those actions that 022 I Loss of Reactor Coolant Makeup / 2 X 4.0 require immediate operation of system m p o n e n t s and controls.

Equipment Control Knowledge of bases in technical 027 iPressurizer Pressure Control System Malfunction 3.7 specifications for limiting conditions for operations and safety limits.

Emergency Procedures / Plan Knowledge of which 029 I Anticipated Transient Without Scram (ATWS) I 1 events related to system operationslstatus should 3.6 be reDorted to outside aqencies.

Ability to determine or interpret the following as they 4.4 038 /Steam Generator Tube Rupture / 3 apply to a SGTR RCP restart criteria Ability to determine and interpret the following as they apply to the (Uncontrolled Depressurizalion of E12 I Uncontrolled Depressurization of all Steam a11 Steam Generators) Adherence to appropriate 3.3 Generators i4 procedures and operation within the limitations in the facilitys license and amendments.

Knowledge of the interrelations between the 008 / Pressurizer Vapor Space Accident / 3 Pressurizer Vapor Space Accident and the 3.8 followino: Sensors and detectors.

<noMeoge of the reasons for Ine foilofflng responses as tney apply to tne Reactor Coolant 015 / 17 /Reactor Coolant Pump Malfunctions / 4 P m p Ma fdnclons ,-ass of RC Flow) Polenl a 25 damage from high mna ng analor beanng temoeratwres AO ty 10 operate an0 I or monllor h e follomng as tney apply 10 tne -05s of Reactor Cooant MakeJp 022 / Loss of Reactor Coolant Makeup / 2 RCP sea Row. IemperatJres. pressJres. and nbral ons 025 / Loss of Residual Heat Removal System / 4 I l l Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Shifl to alternate flowpath 026 / Loss of Component Cooling Water I 8 1 x 1 I Conduct of Operations: Ability to locate and operate wmponents. including local wntrols.

NUREG-I021 2

ES-401 Ginna Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 I E/APE # I Name Safety Function I G I K1 I K2 I K3 I A I I A2 I Number I MA Topic(s) 1 Imp. 1 Q#

A6203 I Knowleoge of tne .nlerrelal ons between tne Pressdnzer Pressdre Conlro MalLnclons an0 tne fo own9 Conlro ers and PosiLoners 2.6 Conduct of Operations: Knowledge of system status 2.5 4.5 and its ootential wnseouences Anowledge of me operational implicat ons of the AK1 01 fo onnng wncepls as lney app y to Sleam L ne 4.1 Rdpldre ConseaLences of PTS Knodedge of the Operational implications of the following wncepts as they apply to Loss of Main AK1 ,ol 4.1 Feedwater (MFW): MFW line break depressurizes the S/G (similar to a steam line break)

Emergency Procedures / Plan Knowledge of 2.4.31 anniinciators alarms and indications, and use of lhe 3.3 response instructions.

Ability to determine and interpret the following as AA2.15 they apply to the Loss of Vital AC Instrument BUS: 3.8 That a loss of ac has occurred I Knowledoe of the reasons for the followina 058 / Loss of DC Power / 6 X AK3.02 responsCs as mey apply to tne -ass of DE Power. 4.0 Act ons wnla ned in EOP for loss of dc power Ability to determine and interpret the follwjlng as they apply to the Loss of Nuclear Service Water:

062 / Loss of Nuclear Service. Water / 4 X AA2.03 The valve lineups necessary to restart the CCWS 2.6 while bypassing the portion of the System causing the abnormal condition Ability to operate and I or monitor the following as they apply to the Loss of instrument Air:

065 / Loss of InstrumentAir / 8 X AA1.03 2.9 Restoration of Systems served by instrument air when pressure is regained Knowledge of the operational implications of the following wncepts as they apply to the (LOCA E04 / LOCA Outside Containment / 3 X EK1.2 Outside Containmentl Normal. abnormal and 3.5 emergency operat ng proced-res assocared vntn (LOCA Oulsloe Conlalnmenl)

ES-401 Ginna Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 I E/APE # / Name Safety Function I G I K1 I K2 I K3 I A I I A2 I Number I WA Topic(s) 1 Imp. I Q#

-E05 I Loss of Secondaw Heat Sink I 4 E l 1 / Loss of Emergency Coolant Recirculation / 4 7-

- EK2.1 EA1.3 Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:

Components and functions of control and safety systems. including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

AO ty to operate ana I or mon lor me followng as tney apply 10 the (Loss of Emergency Coo ant Rec rcLlatdon) Desireo operating re% I s omng abnormal ana emeraencv s ualons 3.7 37 55 56 6 i Grouo PointTotal: i 1 24 I NUREG-1021 4

ES-401 Ginna Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 RAPE # / Name Safety Function I G I K1 1 K2 I K3 I A I I A2 I Number I KIA Topic(s) 1 Imp. I Q#

Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear 3.9 82 AA2.02 Instrumentation: Expected change In source range count rate when rods are moved Emergency Procedures IPlan Ability to recognize abnormal indications for system operating 4.3 83 2.4.4 parameters which are entry-level conditions for emergency and abnormal operating procedures.

Ability to determine or interpret the following as they apply to a inadequate Core Cooling: The effect of EA2.08 4,6 84 turbine bypass valve operation on RCS temperature and pressure Conduct of Operations: Knowiedge of operator 4.0 85 2.1.2 responsibilities during all modes of plant operation.

Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: 4.5 57 AA2.03 Proper actions to be taken if automatic safety functions have not taken place Knowledge of the reasons for the following responses as they apply to the Loss of Source 3.2 58 AK3.01 Range Nuclear Instrumentation: Startup termination on source-range loss Ability to operate and I or monitor the following as they apply to the Loss of Intermediate Range 3.0 59 X AA1.03 Instrumentation I 7 Nuclear Instrumentation: Manual restoration of Dower Knodedge of the interrelations between the 059 IAccidental Liquid RadWaste Release I 9 X AK2.01 Accidental Liquid Radwaste Release and the following: Radioactive-liquidmonitors Ability to determine and interpret the following as 060 /Accidental Gaseous RadWaste Release/ 9 X EA206 they apply to the Accidental Gaswus Radwaste:

Valve lineup for release of radioactive gases Conduct of Operations: Ability to perform speciflc E02 ISI Termination 13 X 2.1.23 system and integrated plant procedures during all modes of Dlant ooeration.

Knowledge of the operational implications of the following concepts as they apply to the (LOCA 63 E03 / LOCA Cooldown and DepressurizationI 4 X EK1.l 3.4 Cooldown and Depressurization)Components.

capacity, and function of emergency systems.

NUREG-I021 5

ES-401 Ginna Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2

/APE # / Name Safety Function I G I K1 I K2 I K3 I A I I A2 I Number I WA Topic(s) I Imp. I Q#

Knowledge of the interrelations between the (Natural Circulation Operations) and the following:

Facility's heat removal systems, including primary EO9 / Natural Circulation Operations I 4 EK2.Z coolant. emergency coolant. the decay heat removal 3.6 64 systems. and relations between the proper operation of these systems to the operation of the facility.

I Knowledge of the operational implications of the following concepts as they apply to the (Degraded 3.5 65 E06 / Degraded Core Cooling / 4 EK12 Core Cooling)Normal, abnormal, and emergency procedures associated with Degraded Core Cooling.

WA Cateaow Point Total: Group Point Total: 13 NUREG-I021 6

ES-401 Ginna Form ES-401-2 Written Examination Outline Plant Systems -Tier 2 Grow 1 System #/Name KIA Topics 1 Imp. I Q#

AO 'If 10 (a, pie0 CI IIC inipacis of tile fo oMng ma f.nci ons or oi)eralions on me CVCS. m c ( D .

004 Chemical and Volume base0 011Inose prco clions. .dse proceoJreS 10 Control wrrecl ~ o n i i oof . ni t gale !ne wnseq-elices of iiiosc maifJiici wis or opera! LI s -ow L CT ores.Lre

~

AD ,rY 10 ra, D I ~ U I C IIhe rnpacls of m e 10 lonmg ma'fLnCtionsLr operatioils on rne R h R S . anc 10, 005 Residual Heat Removal oasPd on [nose prw,;ions m e procedwcs io co(rcct coiilroi or m t c a w tne conseq-enccs of tn05e rila lLnc1.ons or opera1.onS R h R v a w malfuxlion Eq-.pmeni Comrol &rio.vleage of oaseb II 006 EmergerrcyCore Cooling X lecnn mi specifiahons for I miiinq r.ond8i ons for operations and safelb ,.m 1s 013 Engineered Safety Features C o n d d d Operx o m AD, t y io apply tecnnca X

Acluation spec 'Ical oris for a sysiem Conaai of Opera1ons An illy IO recogn 2e 064 Emergency Diesel Generator X inb cat ons for s/siem opera! ng pardmerefs A n c i are emry eve1 ~ 3 ~ 0ons . 1 *rJr ! x n r ??

soec.fcai ons

~

Knowledge of the physical connections andlor 003 Reactor Coolant Pump X cause-effect relationships between the RCPS and the following svstems: RCP seal system 004 Chemical and Volume Knowledge of the operational implications of the Control following concepts as they apply to the CVCS:

Flow paths for emergency boration Knowledge of RHRS design feature(s) andlor 005 Residual Heat Removal inteiiock(s) which provlde or the following: Lineup for low head recirculation mode (external and internal)

Emergency Procedures I Plan Ability to perform 005 Residual Heat Removal X without reference to procedures those actions that require immediate operation of system components and controls.

Knowledge of the effect of a loss or malfunction 006 Emergency Core Cooling on the following will have on the ECCS: Core flood tanks (accumulators) 007 Pressurizer RelieflCluench Knowledge of the operational implications of the Tank following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR NUREG-I021 7

ES-401 Ginna Form ES-401-2 Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name I G I K1 I K2 I K3 I K4 I K5 I K6 I A I I A2 I A3 I A4 I Number I KIA Topics I Imp. I Q#

Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions. use procedures to 008 Component Cooling Water AT02 correct, control, or mitigate the consequences of those malfunctions or operations: Highllow surge tank level.

Ao ty to preacl analor monitor changes in A I .08 parametem (to prevent excee0,ng desgn m ts) 8 010 Pressurizer Pressure Control assocatea wln operating the PZR PCS controls m l L o nq S ~ r a vnozzle OT Conduct of Operations: Knowledge of operator 010 Pressurizer Pressure Control 2.1.2 responsibilities during all modes of plant Knowledge of the operational implications of the 012 Reactor Protection K5.01 followino conCeDts as the amlv to the RPS: ONB Knowledge of the effect of a loss or malfunction 013 Engineered Safely Features K6.01 on the following will have on the ESFAS: Sensors 2.7 11 Actuation and detectors Ability to predict andlor monitor changes in 013 Engineered Safety Features parameters (lo Prevent exceeding design limits)

A1.09 3,4 ,2 Actuation associated with operating the ESFAS controls including: T-hot Knowledge of CCS design feature@)andlor 022 Containment Cooling K4.03 interlock(s) which provide for the following: 2.8 13 Automatic Containment Isolation.

EqJlpment Control KnoMeage 01 llmlung 026 Containment Spray 2.2.22 3.4 14

- wna ltons for operations ana safety limits.

Knowledge of the effect that a loss or malfunction 039 Main and Reheat Steam K3.04 of the MRSS will have on the following: MFW pumps 039 Main and Reheat Steam I lx K1.01 Knowledge of the physical connections andlor causeeffect relationships between the MRSS and the followinq systems: SIG I

Knowledge of the physical connections andlor cause-effect relationships between the MFW and 059 Main Feedwater K1.04 3.4 17 l x the following systems: SIGS water level control system Ability to predict andlor monitor changes in 061 AuxillaryIEmergency parameters (to prevent exceeding design limits)

A1.05 3.6 18 Feedwater associated with operating the AFW controls including: AFW flowlmotor amps NUREG-1021

ES-401 Ginna Form ES-401-2 Written Examination Outline Plant Systems -Tier 2 Group 1 I I K1 I K2 I K3 I K 4 I K5 I K6 I A1 I A2 I A3 I A4 I Number I I I Q#

+7 System #/Name G KIA Topics Imp.

Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) 161 AuxillarylEmergency based on those predictions, use procedures to

eedwater correct. control. or mitigate the consequences of those malfunctions or operations: Total loss of feedwater.(no Value Listed in KA CAT)

Knowledge of bus power supplies to the following:

162 AC Electrical Distribution Major system loads Ability to manually operate and/or monitor in the 162 AC Electrical Distribution control room: Synchronizing and paralleling of different ac supplies Ability to manually operate andlor monitor in the 3.0 22 163 OC Electrical Distribution control room: Banery discharge rate Knowledge of bus power supplies to the foliowing:

)64 Emergency Diesel Generator Control oower knowleage of the effect tnat a loss or malfunnlon

)73 Process Radiation Monitoring of me PRM Syslem WI have on the following Rao oac1:ve emLent releases AD ty to mon.tor aLtomal c operat on of tnc SWS.

176 Service Water nclLd.ng. Emergency heat oads AD.. ty lo manually operate andlor monitor In tne 3.1 26 178 Instrument Air control room' PressLre gaJges Ability IO(a) predict the impacls 01 Ihe lo omng ma fJnct ons or operahons on tne containment system-ana (bj base0 on tnose preo cl ons. Jse 103 Containment proceoures to correct. contro.. or miugate tne cOnseqJences of !hose malfdncuons or Operations Phase A ana B 150 allon Ability to monitor automatic operation of the 103 Containment containment system. including: Containment isolation UA Category Point Totals: iintTotal: I I --

NUREG-I021 9

cn N N o 2

r- N 0 VI 9

5 9

2 R Y

9 2

X 0

r X

X X

X mk r

0 P zVI v) o W

ES-401 Ginna Form ES-401-2 Written Examination Outline Plant Systems -Tier 2 Group 2 t Svstem #/Name I G IKlIK2 Number I K/A Tnnics I Imn~

068 Liquid Radwaste I l l K6.02 Knowledge of the effect of a loss or malfunction on the following will have on the NIS :

DiScriminatOr/COmDenSationcircuits 2.6 079 Station Air I l l K4.01 linowedge 01 SAS oes gn featJre(s)andlor mlenocn(s)Wicri pruvioe fur [ne followng Cross-wnneclwlh AS Grow Point Total: I 29 NUREG-I 021 11

Facility: I Ginna I D a t e o f Exam: I 81: 2007 I , SR(

Categoly KIA # Topic -

I IR Ability to obtain and interpret station reference I 2.1.25 - .

materials such as araohs.. monoaraohs.

~., ~.~

~~

and~

I 3.1 94 lables wnicn conlain performance data.

2.1.5 Ability In locate and use procedures ano I 3.4 95

1. directives related to shift staffing and activities. I -

Conduct of Operations 2.1.22 Abilitv to determine Mode of ODeration. I 2.8

~~~

-66 Ability to perform specific system and integrated 2.1.23 plant procedures during all modes of plant 3.9 67 operation.

Subtotal I 2 2

Knowledge of the process for determining if the margin of safety, as defined in the basis of any 22'10 3.3 96 technical specification is reduced by a uroposed I change, test or expennient

2. _. .,,, I Knowlcdae Gf ne* and saenl fuel movement Equipment Control L.L.LU I proceduGs.

3.5 97 2.6 68 2.2.12 Knowledge of surveillance procedures.

3.0 69 2 2 I _ . _ . -

cI ~

I Knowledge of the Drocess for uerformina a 3.4 98 Ao.lity 10 perform procedbres to rcobce

3. 2 3 10 I

excessive levels of radiatron and auard aaainst porsonnei exposure.

29 70 Radiation Control 2'3'1 1 Knowledge of 10 CFR: 20 and related facility radiation control reqLirements 2.6 71 Subtotal I 2 1 Knowledge of symptom based EOP mitigation 2.4.6 4.0 99 strategies.

Knowledge of RO tasks periormed outside the main control room during emergency operations 2.4.34 3.6 100 including system geography and system

4. - implications.

Emergency 2.4.27 Knowledge of fire in the plant procedure. 3.0 72 Procedures I Plan 2.4.3 Ability to identify post-accident instrumentation. I 3.5

-73 2.4.17 Knowledae of EOP terms and definitions. 1 3.1

~~~~ _

74 2.4.29 Knowledge of the ememencv Dlan. I 2.6 75 Subtotal

- 4 2

Tier 3 Point Total II 10 7 NUREG-1021 12

rier I Randomly Reason for Rejection

roup Selected~WP No LCOs and Safety Limits associated with Circulating Water System.

212 075 G2.2.25 Randomly reselected G2.1.32 Removed due to excessive overlap with 027 AK2.03. Since 027 had only 1 KA 1I 1 008 AK2.03 >2.5 in that category and 008 had 3 topics, removed the 008 topic and randomly reselected AK2.02 Overlap with 045 A I .05, so removed 035 topic since it had a lower KA 212 035 K5.01 importance value. Manually added K5.03 because it was the only other K5 in the 035 topic area. (Same as random)

Excessive overlap with Admin Task on Operating exam. Randomly reselected 314 G2.4.44 G2.4.6 Too difficult to develop an SRO question from selected KA. Randomly 313 G2.3.2 reselected G2.3.9 068 G2.1.27 Selected topic had no tie to IOCFR55.43(b) and only yielded information at the 212 ROIAO level. Randomly reselected G2.1.23 Selected toDic had no tie to IOCFR55.43(b) and onlv vielded information at the 211 013 G2.1.28 , I

~~ ~

RO/AO level. Randomly reselected G2.i.12 Excessive overlaD with information In auestion 24. No olher K6 tooics-

~~~~ ~~~ ~ ~~

~ ~ ~ ~ 8 -

212 068 K6.10 available in 068, iandomly reselected irom available topics, replaced with 015 K6.02.

Topic would not yield a discriminating question without excessive effort. Other 212 011 K2.02 K2 topics similar. Randomly reselected 011 K1.04 Topic would not yield a discriminating question without excessive effort.

21 1 022 K4.04 Randomly reselected 022 K4.03 Topic would not yield a discriminating question without excessive effort.

211 008 A2.08 Randomly reselected 008 A2.02 Operating Exam modifications resulted in excessive overlap with JPM.

112 E14 EK1.3 Randomly reselected E06 EKI .2 NUREG-1021 13

ES-301 Administrative Topics Outline Form ES-301-1 Rev Final Facility: Ginna Date of Examination: a127107 Examination Level (circle one). RO/SRO Operating Test Number: N07-1-1 Administrative Topic Describe activity to be performed 2.1.7 (4.4) Ability to evaluate plant performance and make Conduct of Operations operational judgments based on operating characteristics, reactor behavior, and instrument interDretation JPM: Calculate QPTR and take action as necessarv 2.1.25 (3.1) Ability to obtain and interpret station reference I -

Conduct of Operations materials such as graphs, monographs, and tables which contain Derformance data JPM: Verify Required Service Water to Emergency Diesel Generators 2.2.26 (3.7) Knowledge of Refueling Administrative Requirements JPM:

2.3.10 (3.3)

Determine if the Electrical System is aligned for Mode 6 ODeration Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure JPM: Respond to a contaminated injured person 2.4.44 (4.1) Knowledge of Emergency Plan Protective Action Recommendations JPM: Make Protective Action Recommendations during a General Emergency NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room Class(R)oom (D)irect from bank (< 3 for ROs; 5 4 for SROs & RO retakes)

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

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

(S)imulator NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1

~

Rev Final SRO Admin JPM Summary A1 a The operator will be required to calculate QPTR using 0-6.4. The initial conditions will be off normal in that one NIS PR Detector will be out of service and reactor power will be at 65%. QPTR will be high requiring the operator to take action in accordance with TS 3.2-4. This JPM will be accomplished on the Simulator. (Similar JPM exists in Facility Bank - JR015.001)

Alb The operator, as part of the Daily Surveillance (0-6.13) will be directed to verify sufficient Service Water flow to the Emergency Diesel Generators. The Controlotron flow instrumentation will be unavailable requiring the operator to use Attachment 12, and Lake Temperature will be 69OF requiring that the candidate identify that the use of Attachment 14 is inappropriate. The operator should determine that the SW flow to the EDG is insufficient and declare the EDG inoperable in accordance with TS 3.8.1, and that both EDG coolers sets must be flushed.

A2 While in Mode 5, the operator will be directed to verify that the electrical system will support operation in Mode 6. The operator a copy of 0-15.1 (Step 6.1.6) marked up by the Outage Control Center. The operator will determine that one full Electrical Distribution train is not operable in accordance with TS 3.8.10, and determine that the system must be made operable before Core Alterations can occur. This JPM will be accomplished on the Simulator.

A3 While operating at power, the operator will receive a report of an employee who received serious steam burns while performing RCS sampling activities. The sampling system will be reported as stabilized and no radioactive releases are in progress. The operator will be expected to respond in accordance with A-7, and address the issue that the individual being transported to an off-site medical facility is contaminated. The operator will need to place an emergency response organization in place and determine which off site notifications must be made.

This JPM will be accomplished on the Simulator.

A4 The operator will be placed in a post-accident condition with a Large Break LOCA in Containment with a release from the Containment. The Emergency Plan is being implemented. The operator will be given an emergency classification of General Emergency, the wind direction, and then asked to determine the PAR at Time = 0 (Le. Initial PAR) in a Time Critical setting of 15 minutes. Following the initial recommendation, two updates will be required (T=30 and T=60) where wind direction and projected dose assessments will change. (Similar JPMs exist in Facility Bank - JS340.003, 013, 015)

NUREG-1021. Revision 9

ES-301 Control RoomAn-Plant Systems Outline Form ES-301-2 Final acilitv: Ginna Date of Examination: 8/27/07 ixam Level (circle one): SRO(I) / SRO (U) Operating Test No.: N07-1-1

ontrol Room Systems" (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

1 Safety Function I. 004 Chemical & Volume Control S,N, A 1 All Rods Not Fully Inserted

), 010 Pressurizer Pressure Control System S, M, A 3 c

Depressurize RCS Using Pzr Porvs on Nitrogen

. 005 Residual Heat Removal System S,D,L Start Up the RHR System

1. 062 A.C. Electrical Distribution Transfer Instrument Bus B

?. 041 Steam Dump System Use Atmospheric Dump Valves to Cooldown in a SGTR

. 008 Component Cooling Water System Restore CCW to RHR

3. 026 Containment Spray System Manually Actuate Containment Spray

~

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

h. 004 Chemical &Volume Control Take Local Manual Control of Charging Pump

i. 039 Main and Reheat Steam System M, A, E 4s Locally Operate the ARVs

j. EPE 038 Steam Generator Tube Rupture N, R. E 3 Respond to SGTR Outside Control Room All RO and SRO-, conlroi room land in-plant)systems mLst be different and serve oillcrent safety f A c l ons all 5 SRO-U systems m4st SCNe d.llerent Safety fdnctions, in-planf SJStemSand fJnctlons may overlap those teste0 in the control room

~~ ~

NUREG-1021. Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: GlNNA Scenario NO.: 1 Op Test No.: N07-1-1 1

Examiners: Operators:

I

~

Initial Conditions:

T..rnover.

1 The plant is at approximately 48% power (BOL), with both A and B MFW Pumps operating. Load was reduced due lo ' A MFW pump vibration. Pump repairs have anticipated.

been made, the pump has been tested and restarted, and a Load Ascension is The follow ng eqJ pmenl s O4l-Of-Service A EDG (Expected bacd in 4 ho~rs].ana Conla nment Pressure cnannel PT-945 (The cnannel has Deen delealea per ER-lhST 1 )

Event No.

1 Malf. No.

1 Event Type' 0 2%

1.O (60 sec ramp)

CVCIOA to I - RO, 7 1 Post Contingency Low Voltage Alarm occurs VCT Level Transminer (LT-112) Fails Low 0% SRO EDS04B (TS)- An Electrical Ground Fault occurs on Safeguards Bus 16 Load Decrease at l%/Minute.

N - SRO, ROD02-J4 C - RO. Dropped Rod RODOZ-JIO C-fl Second Dropped~ Contro! Rod occur during load decrease , . ' Del& RO. SRO 1 EDSO6 A Total Loss of On-Site Power occurs RPS07M C- Steam Admission Valves on TDAFW Pump Fail to Open and N Automatically N/A N/A The A EDG is restored to

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent.

(M)ajor 1

Appendix D Scenario Outline Form ES-D-1

acility: GINNA Scenario No.: 2 Op Test No.: N07-1-2 Ixaminers: Operators:

iitial Conditions: The Plant is at 100% power Steady-State (BOL), and been for the last 9 days following Refueling Outage.

urnover: The following equipment is Out-Of-Service: A MDAFW Pump (Expected back in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), Steam Flow channel FT-475 (The channel has been defeated per ER-INST.1) and MCB Annunciator J-8 has alarmed spuriously several times over the last hour (I&C is investigating).

Event Type* Description RMS02B (TS) - SRO R-12 fails hiqh.

I E; I (TS) - SRO A Small SG Tube Leak (.4 gpm) develops on B SG 3 I NIA I R-RO Rapid Down Power.

Uncontrolled Automatic Rod motion occurs Pzr level Fails High.

6 I SlSOl (0-A) lM Inadvertent Safety Injection.

7 1 RPSOSNB I C-RO, BOP ATWS - AutomaticlManual Pushbutton Reactor Trip blocked -

Manual Trip Received.

8 I FDWllA I C-BOP B MDAFW Pump fails to auto start and then trips shortly after manual start.

TDAFW Pump trips on overspeed.

S A W Flow Transmitters are isolated resulting in pump run out of NB SAFW Pump. (Pumps trips c 60 seconds after start).

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

-1.

Appendix D Scenario Outline Form ES-D-1

acility: Ginna Scenario No.: 4 Op Test No.: N07-1-4 fxaminers: Operators:

nitial Conditions: The Plant is at 100% power Steady-State (BOL), and has been for the last 9 days following Refueling Outage.

rurnover: The following equipment is Out-Of-Service: A MDAFW Pump (Expected back in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), Containment Pressure channel PT-945 (The channel has been defeated pel ER-INST.l) and MCB Annunciator J-8 has alarmed spuriously several times over the last hour (I&C is investigating).

~ Event Type* Event Description C (TS)-SRO N2 Leak on E Accumulator SIS43 I I-SRO 1 I-BOP C-BOP 1 Stage Pressure Transmitter Fails Low AFRV Controller fails causing valve to Close 1 C-SRO 1 TUR05H I Hiah Vibrations on Main Turbine 4

4 C-BOP 1 R-RO Rapid Downpower N SRO, LBOP ROD03 C-RO Misaligned Rod

, C(TS) - SRO 7 1 EDS07C M Loss of Instrument Bus C (causing SI)

RPS07 C-RO AI6 SI Pumps fail to Auto Start RCSl9D NA I Check Valve CV-8538 fails causing intersystem LOCA iorin Laruso - wnna txam From: John Caruso To: mdsl Date: 08/30/2007 3:44:17 PM

Subject:

Ginna Exam Marvin, Two things I wanted to share with you and the Branch regarding our Ginna exam administration this week

1) When we were administering our 3rd scenario, the operator was a little slow at controlling a FRV controller failure and the plant tripped prematurely. This resulted in skipping over 3 planned malfunctions (i.e., the SRO applicant was short one TS and one malfunction as a result). We continued to run the scenario to the end since the malfunctions had no direct affect on the major transient and remainder of the sceanrio. Gil made a very good suggestion for recovery to just go back and start the scenario over again with the same set-up and we just ran the 3 previously missed malfunctions. In essence, we ran the same scenario in two parts. There was no need to run the spare scenario.

2 ) Since we didn't use the spare scenario, I asked Fred Guenther if it would be appropriate to withhold it from the exam record in ADAMS, so that the licensee could re-use this on a future exam. Fred suggested it would be okay, if I put a note to file explaining the circumstances that the spare scenario was not used and the licensee wishes to use it for afuture qxam. It had no bearing the exam outcome and it saves the licensee future resources. # 25 /$ J-cc: bchl; dms3; gxj; jcs5; jmd; pap3; rrm2; sxg; thf