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) . . . . . . . . . .:*.++:<d
- Es-301 Administrative Topics Outline Form E§-301-1 ~ -- Fac lity: V. C. Summer Date of Examination:
044 9/2004- Examination bevel (circle one): / SRO Operating Test Number: 1 - - Ajministrative Topic - Cor duct of Operations - Cor.duct of Operations - Eqi ipment Control - Radiation Control Em 3rgency Plan -L Describe activity to be performed:
Calculate RCS Boron Concentration For Cold Shutdown, Xenon Free AT 68°F. (NRC-A-001) Perform a BPTR Calculation STP-108.001 (NRC-A-OO2)
Prepare a fagout for maintenance on the " C" Charging pump. (NRC-A-003)
Determine dose rates wtth airborne activity present (N RC-A-004) NlA 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 -> - c Fac lity: V.C. Summer Date of Examination:
04/19/2004 Exan Level (circle one): mi SRO(l) I SRO(U) Operating Test No.: 1- -- Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U) - - a. Transfer to Hot Leg Recirc. (NRC-S-001)
I MAS 1 4P b. Operate the CVCS System tu Increase RCS Pressure.
2 (NRC-S-oo2)
- c. - d. f A Total boss of Service - 3 I DAS I f. Steam Generator Tube Ruplure (depressurize RCS to less than §/G pressure). (NRC-§-006)
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 Scenario Outline Form ES-D-I Appendix D 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 U'ater Pump 'A' (XPP-21A) inooerable for maintenance. Severe Thunderstom1 storms in effect. RMA 9 OOS. I&C Derformine STP 345.040 ENGWEEFUD SN.'ETY.FEAWRE ACTUmN 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:
1'2-162 25% Power MOL. 25 GPD Tube Leak on the "A" S/G. Emeraency Feed Water Pump 'E' (XPP-21 E) inoperable for maintenance.
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. Severe Thunderstorm Event Steam Space Break 5Qgpm to 600gpm ramped in over I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page I of 20
- ES-401 PWR Examination Outline Form ES-401-2 Facility:
V.C. Summer Date of Exam:04/X?/$004 I I Note: 1. 2. 3. 4. 5. 6.* 7. h. I. 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. 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. 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.
Systems/evolutions within each group are identified on the associated outline. The shaded areas are not applicable to the category/tier. 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.
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. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
22of 34 NUREG-1021, Draft Revision 9
ES-401 Emergency E/APE #I Name I Safety Function 000007 BW/E02&*10 CUE02) Reactor trip - Stabilizition - Recovery I 1 000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA i 3 00001 1 Large Break LOCA / 3 00001 511 7 RCP Malfunctions I4 000022 Loss of Rx Coolant Makeup 12 000025 Loss of RHR System I4 000026 Loss of Component Cooling Water / 5 000027 Pressurizer Pressure Control System Malfunction
/ 3 000029 ATWS 11 000038 Steam Gen. Tube Rupture I 7 000040 (BWEO5; CEEO5; W1E12) Steam bine Ru ture - Excessive Heat Transfer F4 000054 (CE/EOG) Loss of Main Feedwater I4 000055 Station Blackout I6 000056 boss of Of-site Power I6 000057 Loss of Vital AC Inst. Bus 1 t Abnoi ~ Form ES-401-2 Ition Outline utions - Tier 1iGnwp 1 (RO I SRO) WA Topic(§) 62.1 20 Ability to execute procedure steps. EK3.04 Knowledge of the reasons for the following responses as they app,,y to Placing containment fan cooler damper in accident position.
AK2.08 Knowledge of the Ir1terrulat;ons between abnormal plai!t evolution) and tile followlllg
... (c cws ........ __ AAl.02 Abilit to operate and/or monitor the following as txe a ply to (abnormal lant evolution)
CVC~ clarging low flow akrm, sensor and indicator.
AA2.02 Abilit to determine and interpret the following as tiey apply to (abnormal lant evolution)
Leakage of reador uxlanrfroy RHR into closed coolin water system or into reactor building atmos$ere.
AK3.03 Knowledge of the reasons for the following responses as they apply to [abnormal lant evolution actions contained in EOP for bZR PCA Malf?nction.
EK2.06 Knowldge of the interrelations between Emergency lant evolution) and the follovhg (Breakers.
regys, and disconnects.
AK1.05 Knowledge of the operational applicahons of the following miice 1s ds they a ply to the dtmornial plant evolu(lon;:
-. &Deactivity&ctt.of
..... cooldown.
AA1.02 Abilit lo operate and /or monitor the fcllowing as :xey apply to (abnormal plant evolution): Manual startbp cf eledric aRd steam dr.ven AF W pumps. EA2.04 Abili to de:ermine and interpret the Evo,ut;on Iiistriiments and miitrols operable wlth only b C batten/ power available. - foliowii:g as x t ey apoly to (Eniergency Plant
........ ..... 02.1.32 Ability to explain and apply all system limits and precaustions.
IR - - - 4.3 4.0 - 2.6 - 3.0 - 3.4 - - 3.7 - 2.9 - - 4.1 - 4.4 - 3.7 - 3.1 - 3.4 - 230f 34 NUREG-1021, Draft Revision 9 000058 Loss of QC Power / 6 OW062 Loss of Nuclear Svc Water I 4 000065 Loss of Instrument Air I8 WE04 LOCA Outside Containment
/ 3 WIE1 I Loss of Emergency Coolant Recirc. / 4 BWE04: W1E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 KIA Category Totals: AKI.01 Kiiuwledge of the opernliunal applications of the foilowing mncc IS as they apply io the (abnormal plant evolui?o~i):
Battev charger eqbiprnent and inst'lJmenta'ion.
AA2.01 Abili :o de:ermine and interpret the lodowing as t ey,appl tu (abnormal ldnt evolction~.ly~~l~.~~~
' / qkinfhe &S. AA1.03 Abilit to operate and /or monitor the following as tzey a ply to (abnormal plant evolution):Restora!on of systems SeNed by instrument air when pcessure is regained.
EKI .3 Knowled e of the operational a plications of tte following as they apply to &mergency Plant Evolution):
Annunciators and conditions Indicating S I nals, and remedial actions associatAwith the (LQCA outside Containment).
G2.4.7 Knowledge of event based EOP mitigation strategies.
EA22 Ability to determine and interpret the following as they apply to Emergency Plant Evolution):
Adherence to app'opriate j?rqcedures and operations within the imitations in the facility's license and amendments.
Group Point Total: 2.6 - 2.9 24of 34 NUREG-1021, Draft Revision 9
.... . ES-401 PWF Emergency and Abnormal F E/APE #I Name / Safety Function 000003 Dmpped Contrd Rod 1 I 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Bel. / 9 000060 Accidental GaS6GUS Radwaste Rel. / a WlEOl Rediagnosis
/ 3 vVEO2 SI Termination
/ 3 Ixaminatior lnt Evolutio 25 of 34 utline Form ES-401- - Tier IIGroup 2 (RO I SRO) WA Topic@) IR # I I 005AK3.06 Knowledge of the reasons for the fohwnq sesy as theyS a > I to Inope;aole/
tuck Control od
&#Actions 1 39 ...........
...... interrelaboqs between Loss of Sourm 032AK2.0$
Knowledge of the range Ni aid tha follnwiiy Powr supplies, including proper switch psitions ..........
1271 ........ .- 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 WEOlEG2p Knowiedge of loss 01 cool'ng wa er procedures WE02EK3.2 Knowledge of the reasons fnc the following responses as they a ply to SI term:iiation' Norma:, alnnrnial and cnier pnq opcratiog yrocedures associagd wi!h (SI ....... .- ..........
3.3 -. erwatlon)
...... NUREG-1021, Draft Revision 9 BW!EOB: W!EO3 LOCA Cooldown - Depress. BWiE09; CE/A13; WiE09BE10 Natural Cifc. i A 260f 34 W*tSEAl.l Ability to operate ana or mon;tor the following as they app!y to Contaicmcnt F'looding.
Components and !unctions of control and safety svs:nms. Incluciru instrumentalin.
2.9 signals, interlock6 failure modes and automatic and manual features I NUREG-1021, Draft Revision 9 ES-402 System # / Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Ccoling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser 026 Containment Spray WA Topic(s) D03K6.14 Knowledge of the effect
!hat a loss or malfunction of the following will have on the Reactor Coolant Pump:
Starting Requirements.
D04K6.14 Knowledge pf the effect that a loss or malfunction of the !oI.nwino will have on tlic CIlemical and Volhme control, Recirculation path for charging pumps 005A4.01 Ability to nianually o ciate or monitor in Coctrol Room &-mtrols and indications for RIiR Dumps. 006K6.18 Kncwledge of the effect that a loss or malfunction of the following will have on the Emergency Core cqoling system: Subcooling margin indicators.
007A1.01 Ability to predict and or monitor chanaes in parameters assoc'at4ed 6th o eration the F'ressur~zer Relle!!6uench Tank contols inc,t.oing:
Ma.n!ainiiig quench tank water level within 008K3.03 Knowledge of the sffect that a loss or malfunction of the CCW system will have on the following:
RCP OdOK1.08 Knowledge of the Dhvsical connections and or cause- etfecl re~d:ionships belwset' ressurizer ioswre control and the fkowing P!R LCS . .. . . . . 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 . .. . . . . . . . . . . 013K3.02 Knowledge of the effect that a loss or malfunction of the ESF actuation will have on ths following:
RCS 022A2.03 Ability to (a) predict the impacts of the following on the Containment coolina and (bl based 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 039 Main and Reheat Steam 056 Condensate 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 061 Auxiliary/Emergency Feedwater 064 Emergency Diesel Generator 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water 28 of 34 026K2.02 Knowledge of electrical ower supplies to the following:
R~ov~ 05662.1.30 Ability to locate and operate momponents, including local controls.
059K1.02 Knowledge of the physical connections and or cause- effect relat oilships Delweeii main feedwater and the followina:
AFW system I 061KJ.05 Knowled e of me operational implica#ons of the followin concepts as they appll to the AFJ s stem: Feed line voi&g and water xammer. 062K1 .Q2 Knowledge of the physical connections and or cause effect relationships between AC electri,cal distribution and the following:
EIDG. 063A4.03 Ability to niamrally operate and or nioriitoi in the control roar1 Battery discharge
,-+a 063A2.01 Ability to (a) pcedict the !iripacts of the following on the [).C. Electrical distrihJiion systetii and Io) based on those oiedictaons use hitigate the conseqmnws of those abnormal opt.rstlon: . . . . . .
Grounds . . . . .
_. . . . . . . . . . .
064A4.09 Ability to manually operate and or monitor,in the control room: Establishing power from the ring bus (to relieve ED/G). Cberatina voltaaes currgnts and teinperatims.
~ system: Radiation theo including sources, types units anpertects.
07662.1.30 Ability to locate and operate components, including local ControIs. - 2.7 - 3.7 - 3.9 - 3.4 - 4.1 - 2.7 - 4.1 - 3.0 2.5 - 3.2 - 3.2 - 2.5 - 3.9 - NUREG-1021, Draft Revision 9 076 Service Water 078 Instrument Air 078 Instrument Air I WA Category Point Totals:
076K4.02 Knowledge of Service Water design feature(s and or followinu Automat~c staq fcatuics iiite:locks) which nrovi d e tor the associarkd with $W%~ pump controls.
078K2.02 Knowledge of electrical owcc supplies to the following:
Emergency ulr wrnpressor.
078K3.01 Knowledge of the effect Mat a loss or malfunction of the instrument air system will have on the following: Containment Air system. 10362.4.4 Abili ru recognize operating ararneters which are entry-leverconditions for emergency and abnormal operating procedures. abnormal indica r ions for System Group Point Total:
290f 34 NUREG-1021, Draft Revision 9 ES-401 System # / Name 001 Control Rod Drive 002 Reactor Coolant 01 1 Pressurizer bevel Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Nor.-nuclear mtrdmentation
............
019 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Wecombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Stem Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 068 Liquid Radwaste nminatit 'ier 2/G - - \---. -..-I WA Topic(s) OZdA3.03 Ability to monitor automatic operations of the Pressurizer Level Control system including: Charging and letdown 014K3.02 Knowledae of the effect that a loss or malfidioii of the Rod Position Indication system will have ..... on the foKowtfig Piant Covputer.
............
017G2.4.47 Ability to diagnose and recoanize trends in an accurate and timek manner utilizing the apprcpria!a cont:ol room reference niatetial - ............. . 034K6.02 Knowledae of the effect 035K1.14 Knowledge of the hysical connections and or cause-efkct relationships between Seam e_ enerator.;
and the followiiq:
ESF ...... : , 041A4.08 Ability to o erate and or monitor in the controrroom:
Steam Dump valves.
045A3.07 Ability to monitor automatic o erdions of the Man Turbine &nera!or including Turbne stoplGovernm valve closure 311 turbine trip .- ..........
.... 30Qf 34 NUREG-1021, Draft Revision 9 075 Circulating Water 086 Fire Protection 31 of 34 072G2.1.14 Knowledge of sys!em slatus criteria Hhich requite notifications ot planr personnel
............
...... O86K5.03 Knowjeage 3f the I 3.: 1 operaliowi impliwt,ons of the fol owing rancepts as tliay ap ly to the Fire protect,on systems: e ect of water sp(ay 0'1 electrical coinponents.
........ ...... ._ , -. .......... ...........
I :2" Group Point Total: NUREG-1021, Draft Revision 9
'\.. .._ ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ~s-401-: za u avA ./rv Facility:
Category 1. Conduct of Operations
- 2. Equipment Control 3. Radiation Control 4. hergency 'rocedures Plan .__II-. 2. Summer Date of Exam: 04//07/2804
.. 21 of 34 NUREG-1021, Drafl Revision 9 E§-401 Record of Rejected WAS Form ES-401-4 2/1 061 K5.03 212 O2784.02 --t---- 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 28 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 Could not find information with exam validity to ask a question on pump head effects with control valve shut. Selected 061K5.05 to replace. Ability to manually operate and or monitor in the control room Remote operation of iodine filters. Not appiicable, selected 041A4.08 to replace. 28 of 34 NUREG-1021, Draft Revision 9