ML041410383
| ML041410383 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/28/2004 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML041410383 (17) | |
Text
Final Submittal V. C. SUMMER EXAM 50-39512004-301 APRIL 19 23,2004 April 28,2004 (written)
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Es-301 Fac lity: V. C. Summer Administrative Topics Outline Date of Examination:
Form E§-301-1 044 9/2004-Examination bevel (circle one): / SRO Operating Test Number: 1
- Ajministrative Topic Cor duct of Operations Describe activity to be performed:
Calculate RCS Boron Concentration For Cold Shutdown, Xenon Free AT 68°F. (NRC-A-001)
Cor.duct of Operations Perform a BPTR Calculation STP-108.001 (NRC-A-OO2)
Eqi ipment Control Prepare a fagout for maintenance on the "C" Charging pump.
(NRC-A-003)
Radiation Control Determine dose rates wtth airborne activity present (NRC-A-004)
Em 3rgency Plan NlA
-L NOTE: All items (5 total) are required for %Os. RO applicants require only 4 items unless the!/ are retaking only the administrative topics, when 5 are required.
- e 22 of 27 NUREG 1021, Draft Revision 9
ES-3(,1 Control Room/ln-Plant Systems Form ES-301-2 Fac lity: V.C. Summer Date of Examination: 04/19/2004 c
-- Exan Level (circle one): mi SRO(l) I SRO(U) Operating Test No.:
Control Room Systems (8 for RO;7 for SRO-I; 2 or 3 for SRO-U) 1 -
I 1
- a. Transfer to Hot Leg Recirc. (NRC-S-001) MAS 4P
- d. f A Total boss of Service
- f. Steam Generator Tube Ruplure (depressurize RCS to less than §/Gpressure). (NRC-§-006) I DAS I 3 Loss of Power Range Instrument N-44 (NRC-S-007)
-h.
In-P ant Systems (3 for RO; 3 for SRO-i; 3 or 2 for SRO-U) i.
I _
i.
- k. Loss of Containment Integrity (XVG-503B), (NRC-1-003).
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)irnulator, &)ow-Power, (R)CA 23 of 27 NUREG-l02I, Draft Revision 9
Scenario 1 Appendix D Scenario Outline Form ES-D-I Facility: V. C. Summer Scenario NO.:^ @-Test No.:
Examiners: Operators:
Initial Conditions: IC-161 100% Power BOL. 25 GPD Tube Leak on the A S/G. Enlergency Feed Uater Pump A (XPP-21A) inooerable for maintenance. Severe Thunderstom1storms in effect.
RMA 9 OOS. I&C Derformine STP 345.040 ENGWEEFUD SN.ETY.FEAWRE A C T U m N SLAVE RELAY TEST Tnmover: Maintain 100% reactor power .-
ATWS Reactor fails to trip Page 1 of 18
scenario 2 Appendix D Scenario Outline Form ES-D-1 Facility: V. C. Summer Scenario No.: 2 Op-Test No.: 2 Examiners: Operators:
Initial Conditions: 12-162 25% Power MOL. 25 GPD Tube Leak on the A S/G.Emeraency Feed Water Pump E (XPP-21E) inoperable for maintenance. Severe Thunderstorm watch in effect. RMA 9 OOS Turnover: Ramp unit up to 50% power Der GOP-4A (POWER OPERATION - MODE 1 ASCENDING) startinq at step 3.1 1.
Event Steam Space Break 5Qgpmto 600gpm ramped in over I
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page Iof 20
ES-401 PWR Examination Outline Form ES-401-2 Facility: V.C. Summer Date of Exam:04/X?/$004 I I Note: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the "Tier Totals" in each WA category shall not be less than two). Refer to Section D.1 .c for additional guidance regarding SRO sampling.
- 2. The point totel 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 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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
6.* The generic ( 6 ) WAS 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. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
- 7. On the following pages, enter the WA 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled " K and "A." Use duplicate pages for RO and SRO-only exams.
- h. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
I. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
22of 34 NUREG-1021, Draft Revision 9
ES-401 Ition Outline Form ES-401-2 Emergency ~
Abnoi utions - Tier 1iGnwp 1 (RO ISRO)
E/APE # IName ISafety Function WA Topic(§) IR 000007 BW/E02&10 CUE02)
Reactort r i p - Stabilizition -
Recovery I1 -
000008 Pressurizer Vapor Space Accident / 3 -
000009 Small Break LOCA i 3 62.1 2 0 Ability to execute procedure steps. -
4.3 00001 1 Large Break LOCA / 3 EK3.04 Knowledge of the reasons for the 4.0 following responses as they app,,y to Placing containment fan cooler damper in accident position.
000015117 RCP MalfunctionsI4 AK2.08 Knowledge of the Ir1terrulat;ons 2.6 between abnormal plai!t evolution) and tile (ccws followlllg... ........__ -
000022 Loss of Rx Coolant Makeup AAl.02 Abilit to operate and/or monitor the 3.0 12 following as txe a ply to (abnormal lant evolution) C V C clarging
~ low flow akrm, sensor and indicator. -
000025 Loss of RHR System I4 AA2.02 Abilit to determine and interpret the 3.4 following as tiey apply to (abnormal lant evolution) Leakage of reador uxlanrfroy RHR into closed coolin water system or into reactor building atmos$ere. -
000026 Loss of Component Cooling Water / 5 -
000027 Pressurizer Pressure AK3.03 Knowledge of the reasons for the 3.7 Control System Malfunction / 3 following responses as they apply to
[abnormal lant evolution actions contained in EOP for bZR PCA Malf?nction. -
000029 ATWS 11 EK2.06 Knowldge of the interrelations 2.9 between Emergency lant evolution) and the follovhg (Breakers. regys, and disconnects. -
000038 Steam Gen. Tube Rupture I 7 -
000040 (BWEO5; CEEO5; W1E12) AK1.05 Knowledge of the operational 4.1 Steam bine Ru ture - Excessive applicahons of the following miice 1s ds they a ply to the dtmornial plant evolu(lon;:
Heat Transfer F4
&Deactivity&ctt.of
-. ..... cooldown. -
000054 (CE/EOG) Loss of Main AA1.02 Abilit lo operate and /or monitor the 4.4 Feedwater I 4 fcllowing as :xey apply to (abnormal plant evolution): Manual startbp cf eledric aRd steam dr.ven AF W pumps. - -
000055 Station Blackout I 6 x
EA2.04 Abili to de:ermine and interpret the foliowii:g as t ey apoly to (Eniergency Plant Evo,ut;on Iiistriiments and miitrols operable 3.7 wlth only Cb batten/ power
........ ..... available. -
000056 boss of Of-site Power I6 3.1 000057 Loss of Vital AC Inst. Bus 1 t 02.1.32 Ability to explain and apply all system 3.4 limits and precaustions. -
2 3 0 f 34 NUREG-1021, Draft Revision 9
AKI.01 Kiiuwledge of the opernliunal 2.6 000058 Loss of QC Power / 6 applications of the foilowing mncc ISas they apply io the (abnormal plant evolui?o~i):
Battev charger eqbiprnent and inst'lJmenta'ion. -
OW062 Loss of Nuclear Svc Water I 4
000065 Loss of Instrument Air I8 AA2.01 Abili :o de:ermine and interpret the lodowing as t ey,appl tu (abnormal ldnt
/
e v o l c t i o n ~ . l y ~qkinfhe ~ l ~ . &S.
~ ~ ~
AA1.03 Abilit to operate and /or monitor the 2.9 following as tzey a ply to (abnormal plant evolution):Restora!on of systems SeNed by instrument air when pcessure is regained.
W E 0 4 LOCA Outside Containment / EKI .3 Knowled e of the operational 3 a plications of t t e following as they apply to
&mergency Plant Evolution): Annunciators and conditions Indicating SI nals, and remedial actions associatAwith the (LQCA outside Containment).
WIE1I Loss of Emergency Coolant G2.4.7 Knowledge of event based EOP Recirc. / 4 mitigation strategies.
BWE04: W1E05 Inadequate Heat EA22 Ability to determine and interpret the Transfer - Loss of Secondary Heat following as they apply to Emergency Plant Sink / 4 Evolution): Adherence to app'opriate j?rqcedures and operations within the imitations in the facility's license and amendments.
KIA Category Totals: Group Point Total:
24of 34 NUREG-1021, Draft Revision 9
ES-401 PWF Ixaminatior utline Form ES-401-Emergency and Abnormal F lnt Evolutio - Tier IIGroup 2 (RO ISRO)
E/APE #I Name / Safety Function WA Topic@) IR #
I I 000003 Dmpped Contrd Rod 1 I 005AK3.06 Knowledge of the reasons for the f o h w n q s e s y as theyS a > I to Inope;aole/
&#Actions tuck Control od 1 3 9 ......
032AK2.0$ Knowledge of the interrelaboqs between Loss of Sourm range Ni a i d tha follnwiiy P o w r supplies, including proper switch psitions ..........1 2 ........
7 1 .-
000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Bel. / 9 000060 Accidental GaS6GUS Radwaste Rel. /
a 067AA1.08 Abilihr to ooerate and or I 3.4 I 076AK2.01 Knnvd!edge ot the interrelations betweer: Hi h reactor coolant activity and thq fc!low,ng:
Prccess radia ion .norlitor ....
- 4 WlEOl Rediagnosis / 3 W E O l E G 2 p Knowiedge of loss 01 cool'ng wa er procedures vVEO2 SI Termination / 3 WE02EK3.2 Knowledge of the reasons 3.3 fnc the following responses as they a ply to SI term:iiation' Norma:,
alnnrnial and cnier p n q opcratiog
. yrocedures associagd wi!h (SI
-.e......
rwatlon) 25 of 34 NUREG-1021, Draft Revision 9
WtSEAl.l Ability to operate ana or 2.9 mon;tor the following as they app!y to Contaicmcnt F'looding. Components and !unctions of control and safety svs:nms. Incluciru instrumentalin.
signals, interlock6 failure modes and automatic and manual features I
BW!EOB: W!EO3 LOCA Cooldown - Depress.
BWiE09; CE/A13; WiE09BE10 Natural Cifc. i A
260f 34 NUREG-1021, Draft Revision 9
ES-402 System # / Name WA Topic(s) 003 Reactor Coolant Pump D03K6.14 Knowledge of the effect
!hat a loss or malfunction of the following will have on the Reactor Coolant Pump: Starting Requirements.
004 Chemical and D04K6.14 Knowledge pf the effect that a loss or malfunctionof the Volume Control !oI.nwino will have on tlic CIlemical and Volhme control, Recirculation path for charging pumps 005 Residual Heat Removal 005A4.01 Ability to nianually o ciate or monitor in Coctrol Room
&-mtrols and indications for RIiR Dumps.
006 Emergency Core Cooling 006K6.18 Kncwledge of the effect that a loss or malfunction of the followingwill have on the Emergency Core cqoling system:
Subcooling margin indicators.
007 Pressurizer 007A1.01 Ability to predict and or Relief/Quench Tank monitor chanaes in parameters assoc'at4ed 6 t h o eration the F'ressur~zerRelle!!6uench Tank contols inc,t.oing: Ma.n!ainiiig quench tank water level within 008 Component Ccoling 008K3.03 Knowledge of the sffect Water that a loss or malfunction of the CCW system will have on the following: RCP 010 Pressurizer Pressure OdOK1.08 Knowledge of the Control Dhvsical connections and or cause-etfecl re~d:ionshipsbelwset' ressurizer ioswre control and the fkowing P R
! LCS .......
012 Reactor Protection 012A1.01 Ability to predict and or monitor chanaes in Darameters associated vrifh,opt!idtillg the Reactor prolect,on controls iccl-dicg I'iip setpoht adjustmcnt 013 Engineered Safety 013K3.02 Knowledge of the effect Features Actuation that a loss or malfunction of the ESF actuation will have on ths following: RCS 022 Containment Cooling 022A2.03 Ability to (a) predict the impacts of the following on the Containment coolina and (bl based 025 Ice Condenser 026 Containment Spray 026A4.05 Ability to manually operate and w monitor in the contml room' Contnmiient sorav 27of 34 NUREG-1021, Draft Revision 9
026 Containment Spray 026K2.02 Knowledge of electrical 2.7 ower supplies to the following:
R~ov~ -
039 Main and Reheat Steam 3.7 056 Condensate 05662.1.30 Ability to locate and 3.9 operate momponents, including local controls. -
059 Main Feedwater 059K1.02 Knowledge of the 3.4 physical connections and or cause-effect relat oilships Delweeii main feedwater and the followina: AFW I
system 061 Auxiliary/Emergency 4.1 Feedwater 061 Auxiliary/Emergency 061KJ.05 Knowled e of me 2.7 Feedwater operational implica#ons of the followin concepts as they appll to the A F J s stem: Feed line voi&g and water xammer. -
062K1 .Q2Knowledge of the 4.1 physical connections and or cause effect relationships between AC electri,cal distribution and the following: EIDG. -
063A4.03 Ability to niamrally 3.0 operate and or nioriitoi in the control roar1 Battery discharge
,-+a 063A2.01 Ability to (a) pcedict the 2.5
!iripacts of the following on the [).C.
Electrical distrihJiion systetii and Io) based on those oiedictaons use hitigate the conseqmnws of those
......Grounds
..........opt.rstlon:
abnormal 064 Emergency Diesel 064A4.09 Ability to manually 3.2 Generator operate and or monitor,in the control room: Establishing power from the ring bus (to relieve ED/G). -
064 Emergency Diesel 3.2 Generator Cberatina voltaaes currgnts and teinperatims. ~
073 Process Radiation 2.5 Monitoring system: Radiation theo including sources, types units anpertects. -
076 Service Water 07662.1.30 Ability to locate and 3.9 operate components, including local ControIs. -
28 of 34 NUREG-1021, Draft Revision 9
076 Service Water 076K4.02 Knowledge of Service d
Water design feature(s and or iiite:locks) which nrovi e tor the followinu Automat~cstaq fcatuics associarkd with $W%~pump controls.
078 Instrument Air 078K2.02 Knowledge of electrical owcc supplies to the following:
Emergency ulr wrnpressor.
078 Instrument Air 078K3.01 Knowledge of the effect Mat a loss or malfunction of the instrument air system will have on the following: Containment Air system.
r 10362.4.4 Abili ru recognize abnormal indica ions for System operating ararneters which are entry-leverconditionsfor emergency and abnormal operating procedures.
I WA Category Point Totals: Group Point Total:
290f 34 NUREG-1021, Draft Revision 9
ES-401 nminatit
'ier 2/G - \---. -..-I System # / Name WA Topic(s) 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer bevel Control OZdA3.03 Ability to monitor automatic operations of the Pressurizer Level Control system including: Charging and letdown 014 Rod Position Indication 014K3.02 Knowledae of the effect that a loss or m a l f i d i o i i of the Rod Position Indication system will have on the foKowtfig Piant Covputer.
015 Nuclear Instrumentation 016 Nor.-nuclear mtrdmentation 019 In-core Temperature 017G2.4.47 Ability to diagnose and Monitor recoanize trends in an accurate and timek manner utilizing the apprcpria!a
-cont:ol room reference.........niatetial 027 Containment Iodine Removal 028 Hydrogen Wecombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 034K6.02 Knowledae of the effect 035 Steam Generator 035K1.14 Knowledge of the hysical connections and or cause-efkct relationships between Seam e_ enerator.;
......: and the followiiq: , ESF 041 S t e m Dump/Turbine 041A4.08 Ability to o erate and or Bypass Control monitor in the controrroom: Steam Dump valves.
045 Main Turbine Generator 045A3.07 Ability to monitor automatic o erdions of the M a n Turbine
&nera!or including Turbne stoplGovernm valve closure 311 turbine trip ...........- ....
055 Condenser Air Removal 068 Liquid Radwaste 30Qf 34 NUREG-1021, Draft Revision 9
072G2.1.14 Knowledge of sys!em slatus criteria Hhich requite notificationsot planr personnel 075 Circulating Water I 1I 086 Fire Protection O86K5.03 Knowjeage 3f the operaliowi impliwt,ons of the fol owing rancepts as tliay ap ly to the Fire protect,onsystems: e ect of water sp(ay 01 electrical
.......... coinponents.
........... 3.: ......
Group Point Total:
- 2 31 of 34 NUREG-1021, Draft Revision 9
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ~s-401-:
za u avA .__II-.
./rv Facility: 2. Summer Date of Exam: 04//07/2804
'\..
Category 1.
Conduct of Operations 2.
Equipment Control 3.
Radiation Control 4.
hergency
'rocedures Plan 21 of 34 NUREG-1021, Drafl Revision 9
E§-401 Record of Rejected WAS Form ES-401-4 Reason for Rejection Computer randomly selected, but has no WAS listed, Randomly selected 005K4.01 to replace. 7 0/29/2003 Small Break LOCA /Knowiedge of how to conduct valve lineups difficult to ask a discriminatory question on. Randomly changed WA to G2.1.20 Knowledge of the Reasons for the following responses as they apply to isolation of PZR spray following loss of pressurizer healers. WA changed to AK3.03 because sprays are not isolated.
Knowledge of reasons for the following responses as they apply to power limits as they apply to a stuck rod. Not RO knowledge, randomly selected K3.06 to replace. (Reasons for EOP actions)
Ability to make accurate, clear, and concise verbal reports, very difficult to evaluate with a written exam question, randomly selected 2.1 2 8 to replace.
In core temperature monitor, knowledge of limiting conditions for operations and safety limits. Very difficult to ask as an RO question.
Selected 027G2.4.47 to replace.
Could not find information on bypassing heat detectors, and it was very low discriminatory value. Selected 067AA1.08 to replace 2/1 061K5.03 Could not find information with exam validity to ask a question on pump head effects with control valve shut. Selected 061K5.05 to replace.
212 O2784.02 Ability to manually operate and or monitor in the control room Remote operation of iodine filters. Not appiicable, selected 041A4.08 to replace.
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28 of 34 NUREG-1021, Draft Revision 9