ML053330026

CNS - 06-2005 - Initial Final Admin Outline

ML053330026
Person / Time
Site:	Cooper
Issue date:	06/27/2005
From:	Nebraska Public Power District (NPPD)
To:	Office of Nuclear Reactor Regulation
References
ES-301, ES-301-1
Download: ML053330026 (36)

Text

ES-301 Adminis trative To pics Outline Form E S-301-1 NUREG-1021, R evision 9 Facility: Cooper Nucl ear Station Date of Examin ation: 6/6/2005 Exami natio n Lev el (ci rcle o ne): RO Operati ng Test N umber: Administrativ e Topic (*)

Type Code(s)Describe Ac tivity to be Performed Conduct of Operatio ns N Verify Valv e Position (perform on > 1 mockup valve either at main tenance traini ng building o r stage d in the tr aining bu ilding; at least o ne valve verified ope n and close , one val ve to be found not in the expec ted posit ion, SKL0 34xxxx)Conduct of Operatio ns D S Perform RO Revie w of Dail y Logs, SKL0 345019 (collection of a variety of inform ation from panels and the simul ator PCIS usi ng procedure 2.0.2, Operations Logs an d Reports)

Equipment Control D Develop, Verify, and Impl ement Tagouts, SKL0345034 Radiation Control M S Perform Dose Assess ment, #2, SKL034 5037 (Perform a dose calcu latio n usi ng CNS Dose with data o btain ed from p anel indi catio n and PCIS), NRC deve loped Radiation Control D Evaluate an RWP and identify the minimum radiolog ical pro tection r equirem ents.Emergency Pla n Not Tested NOTE: All i tem s (5 total) are required for SRO

's. RO app li cants require only 4 it em s unless they are reta king onl y t he administ rati ve top ics, when al l 5 a re requi red.* Ty pe Co de s & Crite ria: (C) Contr ol Room (D) Dir ect fr om Bank (#3 for RO's, # 4 for SRO's and RO retakes)(N) New or (M) Modi fi ed f rom Bank ($1 requi red)(P) Prev ious 2 exams (#1, r andomly sel ected)(S) Si mulator ES-301 Control Room /

In-Plant Sy stems Outline Form E S-301-2 NUREG-1021, R evision 9 Facility: Cooper Nucl ear Station Date of Examin ation: 6/62005 Exam Leve l (ci rcle o ne): RO Operati ng Test N umber: Contro l Roo m Sys tems@ (8 for RO; 7 for SRO-Instant; 2 or 3 for SRO-Upd ate)System / JPM Title Type Codes

(*)Safety Functio n a. Recirc Flow Co ntrol Syste m, SKL0342123, Respo nd to Tr ip of R eactor Reci rc Pump D S Reactivi ty Control

b. Co ndens ate Sy stem, S KL034 2121, Perform Feedwater Startup from 0 to 350 psig D L S Reacto r Inve ntory Control c. ADS, SK L03420xx , Perform ADS M anual Valve A ctuation Surv eillance (valve does not close wh en demanded)

M A S Reacto r Press ure Control d. RHR Shutd own Cooling Mode, SKL034 xxxx, Shutdown Cooling Coo ldown R ate Adjustment L N S Core Heat Re moval e. Primary Containment &

Auxil iaries, SKL0342025, Primary Con tainment Venti ng for PCPL M S Contai nment In tegrity f. Reac tor Equi pment C ooli ng Sys tem, SKL0342144, Separation o f REC Critica l Loops (REC pump trip

)D S A Plant Serv ice Syste ms g. APRM, SKL0342019, Perform APRM Gain Adjustment for Single Loop Operation s (potentiometer mal function)D S A Instrumentation

h. Plant V entilation Systems, SK L0342075, Respond to S ustained Co mbustion in Offgas System D S Radiologica l Release In Pla nt Sy stems@ (3 for RO; 3 for SRO-Instant; 3 or 2 for SRO-Upd ate)i. Uninterru ptible Pow er Supplie s, SKL034109 5, Respo nd to N o-Brea k Powe r Pane l Fai lure D A E Electrical

j. RPS , SKL0 34xx xx, 5.1AS D Fai lure t o SCRAM; NRC deve loped N A C Reactivi ty Control

k. Rea ctor Co re Isol ation Cool ing Sy stem, SKL034xx xx, M anual Start o f the RCIC Turbine per 5.3AL T Str ategy R N Reacto r Inve ntory Control ES-301 Control Room /

In-Plant Sy stems Outline Form E S-301-2 NUREG-1021, R evision 9 (@)All Control Room and In-Plant syst ems m ust be di ffer ent and se rve di ffer ent saf ety funct ions;in-plant syst ems and functi ons may overl ap those t ested i n the Cont rol Room* Type Codes Crit eri a for RO / SRO-Inst ant / SRO-Upgrade (A) A lterna te Pa th (C) Contr ol Room (D) Dir ect f rom Bank (E) Emergency or Abnormal i n plan t (L) Low Power (N) New o r (M) Modi fi ed fr om bank inc lu di ng 1(A)(P) Prev ious 2 exams (R) RC A Entry (S) Si mulator 4 - 6 / 4 - 6 /

2 - 3# 9 / # 8 / # 4$ 1 / $ 1 / $ 1$ 1 / $ 1 / $ 1$ 2 / $ 2 / $ 2# 3 / # 3 / # 2 (ran domly sel ected)$ 1 / $ 1 / $ 1 ES-301 Adminis trative To pics Outline Form E S-301-1 NUREG-1021, R evision 9 Facility: Cooper Nucl ear Station Date of Examin ation: 6/6/2005 Exami natio n Lev el (ci rcle o ne): SRO Operati ng Test N umber: Administrativ e Topic (*)

Type Code(s)Describe Ac tivity to be Performed Conduct of Operatio ns D S Report abil ity D etermi natio n per p rocedu re 2.0.5 (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, given an event that should have resulted in ECCS disc harge into the R eactor Coola nt System as a result o f a valid signal, SKL 0343028, Reportable Occu rrence to the N RC, #3)Conduct of Operatio ns N Shift S taffing De termin ation per pr ocedu re 2.0.3 section 10 (giv en a mode and a partial crew complement, determi ne what a dditional crew positions a re required); NRC develop ed Equipment Control N Risk Assessment a nd Mock Safety Function Determi natio n usi ng proce dure 0.26 pe r proce dure 0.49, step 3.5 (e valuatio n of the schedul e, includin g risk assessment, duri ng periods outsi de normal office hours, for i mpact of emergent equipment problems including missed TS/TRM surve illa nces o n sche duled activ ities & ens ure mock safet y funct ion d etermi natio n is p erformed to assess the impact of m issed TS/TRM surve illa nces o n safety-relat ed equi pment)Radiation Control M Revi ew a nd App rove Liqui d Radi oacti ve Waste Disch arge pe r proce dure 8.8.11, Attach ment 1 (complete sections 1-3, pr ovide information for SM to complete sec tion 4, faulted - SM shou ld not approve, SKL03450 xx, Approve Ra dioactive Disch arge Re lease Permi t)Emergency Pla n M Protective Action Reco mmendation determi nation per procedure 5

.7.20 and compl ete the appropriate se ction(s) of the offsite noti fication form (CNS Dose is no t ava ilab le; pr ovid e data to use Attachments 1 and 2, SKL03430xx, PAR Tabletop)NOTE: All i tem s (5 total) are required for SRO

's. RO app li cants require only 4 it em s unless they are reta king onl y t he administ rati ve top ics, when al l 5 a re requi red.

ES-301 Adminis trative To pics Outline Form E S-301-1 NUREG-1021, R evision 9* Ty pe Co de s & Crite ria: (C) Contr ol Room (D) Dir ect fr om Bank (#3 for RO's, # 4 for SRO's and RO retakes)(N) New or (M) Modi fi ed f rom Bank ($1 requi red)(P) Prev ious 2 exams (#1, r andomly sel ected)(S) Si mulator ES-301 Control Room /

In-Plant Sy stems Outline Form E S-301-2 NUREG-1021, R evision 9 Facility: Cooper Nucl ear Station Date of Examin ation: 6/62005 Exam Leve l (ci rcle o ne): SRO-U Operati ng Test N umber: Contro l Roo m Sys tems@ (8 for RO; 7 for SRO-Instant; 2 or 3 for SRO-Upd ate)System / JPM Title Type Codes

(*)Safety Functio n a. Recirc Flow Co ntrol Syste m, SKL0342123, Respo nd to Tr ip of R eactor Reci rc Pump Not Tested

b. Co ndens ate Sy stem, S KL034 2121, Perform Feedwater Startup from 0 to 350 psig Not Tested

c. ADS, SK L03420xx , Perform ADS M anual Valve A ctuation Surv eillance (valve does not close wh en demanded)

M A Reacto r Press ure Control d. RHR Shutd own Cooling Mode, SKL034 xxxx, Shutdown Cooling Coo ldown R ate Adjustment L N Core Heat Re moval e. Primary Containment &

Auxil iaries, SKL0342025, Primary Con tainment Venti ng for PCPL Not Tested

f. Reac tor Equi pment C ooli ng Sys tem, SKL0342144, Separation o f REC Critica l Loops (REC pump trip

)D S A Plant Serv ice Syste ms g. APRM, SKL0342019, Perform APRM Gain Adjustment for Single Loop Operation s (potentiometer mal function) Not Tested

h. Plant V entilation Systems, SK L0342075, Respond to S ustained Co mbustion in Offgas System Not Tested In Pla nt Sy stems@ (3 for RO; 3 for SRO-Instant; 3 or 2 for SRO-Upd ate)i. Uninterru ptible Pow er Supplie s, SKL034109 5, Respo nd to N o-Brea k Powe r Pane l Fai lure D A E Electrical

j. RPS, SKL034xxxx, 5.1ASD Failure to SCRAM Not Tested

k. Rea ctor Co re Isol ation Cool ing Sy stem, SKL034xx xx, M anual Start o f the RCIC Turbine per 5.3AL T Str ategy R N Reacto r Inve ntory Control ES-301 Control Room /

In-Plant Sy stems Outline Form E S-301-2 NUREG-1021, R evision 9 (@)All Control Room and In-Plant syst ems m ust be di ffer ent and se rve di ffer ent saf ety funct ions;in-plant syst ems and functi ons may overl ap those t ested i n the Cont rol Room* Type Codes Crit eri a for RO / SRO-Inst ant / SRO-Upgrade (A) A lterna te Pa th (C) Contr ol Room (D) Dir ect f rom Bank (E) Emergency or Abnormal i n plan t (L) Low Power (N) New o r (M) Modi fi ed fr om bank inc lu di ng 1(A)(P) Prev ious 2 exams (R) RC A Entry (S) Si mulator 4 - 6 / 4 - 6 /

2 - 3# 9 / # 8 / # 4$ 1 / $ 1 / $ 1$ 1 / $ 1 / $ 1$ 2 / $ 2 / $ 2# 3 / # 3 / # 2 (ran domly sel ected)$ 1 / $ 1 / $ 1 ES-301 Control Room /

In-Plant Sy stems Outline Form E S-301-2 NUREG-1021, R evision 9 Facility: Cooper Nucl ear Station Date of Examin ation: 6/62005 Exam Leve l (ci rcle o ne): SRO-U Operati ng Test N umber: Contro l Roo m Sys tems@ (8 for RO; 7 for SRO-Instant; 2 or 3 for SRO-Upd ate)System / JPM Title Type Codes

(*)Safety Functio n a. Recirc Flow Co ntrol Syste m, SKL0342123, Respo nd to Tr ip of R eactor Reci rc Pump Not Tested

b. Co ndens ate Sy stem, S KL034 2121, Perform Feedwater Startup from 0 to 350 psig Not Tested

c. ADS, SK L03420xx , Perform ADS M anual Valve A ctuation Surv eillance (valve does not close wh en demanded)

M A Reacto r Press ure Control d. RHR Shutd own Cooling Mode, SKL034 xxxx, Shutdown Cooling Coo ldown R ate Adjustment L N Core Heat Re moval e. Primary Containment &

Auxil iaries, SKL0342025, Primary Con tainment Venti ng for PCPL Not Tested

f. Reac tor Equi pment C ooli ng Sys tem, SKL0342144, Separation o f REC Critica l Loops (REC pump trip

)D S A Plant Serv ice Syste ms g. APRM, SKL0342019, Perform APRM Gain Adjustment for Single Loop Operation s (potentiometer mal function) Not Tested

h. Plant V entilation Systems, SK L0342075, Respond to S ustained Co mbustion in Offgas System Not Tested In Pla nt Sy stems@ (3 for RO; 3 for SRO-Instant; 3 or 2 for SRO-Upd ate)i. Uninterru ptible Pow er Supplie s, SKL034109 5, Respo nd to N o-Brea k Powe r Pane l Fai lure D A E Electrical

j. RPS, SKL034xxxx, 5.1ASD Failure to SCRAM Not Tested

k. Rea ctor Co re Isol ation Cool ing Sy stem, SKL034xx xx, M anual Start o f the RCIC Turbine per 5.3AL T Str ategy R N Reacto r Inve ntory Control ES-301 Control Room /

In-Plant Sy stems Outline Form E S-301-2 NUREG-1021, R evision 9 (@)All Control Room and In-Plant syst ems m ust be di ffer ent and se rve di ffer ent saf ety funct ions;in-plant syst ems and functi ons may overl ap those t ested i n the Cont rol Room* Type Codes Crit eri a for RO / SRO-Inst ant / SRO-Upgrade (A) A lterna te Pa th (C) Contr ol Room (D) Dir ect f rom Bank (E) Emergency or Abnormal i n plan t (L) Low Power (N) New o r (M) Modi fi ed fr om bank inc lu di ng 1(A)(P) Prev ious 2 exams (R) RC A Entry (S) Si mulator 4 - 6 / 4 - 6 /

2 - 3# 9 / # 8 / # 4$ 1 / $ 1 / $ 1$ 1 / $ 1 / $ 1$ 2 / $ 2 / $ 2# 3 / # 3 / # 2 (ran domly sel ected)$ 1 / $ 1 / $ 1 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Facil it y: Cooper Nucl ear Sta ti on Date of Exam: June 13, 2005 Tier Group RO K/A Ca tego ry Points SR O O nly K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*Total A2 G*Total 1.1 2 3 3 N/A 4 3 N/A 5 20 4 3 7 2 1 3 0 1 1 1 7 1 2 3 T ota ls 3 6 3 5 4 6 27 5 5 10 2.1 4 2 2 2 2 2 4 2 4 1 1 26 2 3 5 2 1 0 1 2 0 2 1 1 1 1 2 12 1 2 3 T ota ls 5 2 3 4 2 4 5 3 5 2 3 38 3 5 8 3. Generi c Knowledge and Abil it ies Cat egori es 1 3 10 1 1 7 2 3 2 2 3 2 3 2 4 2 4 2 Note: 1.Ensure that at least 2 topics fr om every ap plicable KA categ ory are sampled within each tier o f the RO and SRO-o nly o utline s (i.e. exce pt for Categ ory 1 in Tie r 3 of the SR O-onl y out line, the Ti er To tals in each K A category shall not be less than 2).

2.The point to tal for each group and tier in the proposed outline must match that sp ecified in the table. The final point total for each group and tier may deviate by +/- 1 from that spec ified in the table based on NRC revis ions. The fi nal R O ex am must tot al 75 poin ts and the SR O-onl y ex am must tot al 25 poin ts.3.Systems/evolutions w ithin each gr oup are i dentified on the associated outline; systems or evolutions th at do not apply at the facility should be d eleted and justified; oper ationally i mportant, site-specific systems that are not in cluded on th e outline sho uld be add ed. Refer to ES-401, Attachment 2 , for guida nce regard ing the elimina tion o f inap propr iate KA statemen ts.4.Select topics from as many systems and evol utions as possible

sample every system or evolu tion in the group befo re selecting a second topic fo r any system or evolution.

5.Absent a plant-specific priority only those KA's having an importance rati ng of 2.5 o r higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.Select SRO top ics for Tiers 1 and 2 fro m the sha ded sy stems and KA cate gorie s.7.(*) T he ge neric (G) KA's in T iers 1 and 2 shall be sel ected f rom Secti on 2 o f KA Cat alog but th e topi cs must be rel ev ant to the ap pli cab le ev olu tio n o r sy ste m.8.On the follo wing page s enter the KA number s, a br ief de scripti on of each to pic, th e topi c's impor tance ratings for th e applicable license leve l and the p oint totals for each system and ca tegory. Ente r the grou p and ti er tot als for each c atego ry in the ta ble a bove. Use dupli cate pa ges for RO an d SRO-only exa ms.9.For Tier 3 select topics from Section 2 of the KA C atalog and enter the KA n umbers, description s, IR's and point totals on Form ES 401-3.

Limit SRO selections to KA's that are linked to 10 CFR 55.43.

ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Emergency and Abnormal Pl ant Evolu tions - Tier 1

/ Group 1 (RO)E/APE#/Name/Safety Functi on K 1 K 2 K 3 A 1 A 2 G KA T opic(s)IR#295001 Part ial or Complet e Loss of Forced Core Fl ow Circu lat ion 1 1 Relation be tween loss o f forced core flow circulation an d the reacto r or turb ine pressure re gulating system Reasons for r educed loop operating requirements as applies to lo ss of forced core flow circulation 3.3 3.2 AK2.04 AK3.05 295 003 Par ti al or Compl et e Lo ss of AC 1 Opera tiona l implica tions o f fails afe component design applied to partial or complete loss of AC p ower 2.6 AK1.05 295004 Part ial or Total Loss of DC Pwr 1 Determine or interpret th e cause of pa rtial or complete loss of DC powe r 3.2 AA2.01 29 50 05 Ma in T urb ine Ge ne rato r Trip 1 Monitor o r operate RPS as applies to main turbine ge nerator tr ip 3.6 AA1.02 295 006 SCRAM 1 Ability to pr ioritize an d interpre t the significance of each annunc iator and alarm 3.3 2.4.45 295016 Contr ol Room Abandonment 1 Ability to de termine or inte rpret rea ctor power a s applies to C R abandon ment 4.1 AA2.01 295 018 Par ti al or Tot al Los s o f CCW 1 Reasons for r eactor pow er reduction as applied to partial or total loss of CCW 3.3 AK3.02 29 50 19 Pa rtial o r To tal Lo ss o f Inst A ir 1 Ability to ev aluate plan t performance a nd make operationa l judgements based on operating characteristic s, reactor behavior, and instrument in terpretation 3.7 2.1.07 295021 Loss of Shut down Cooli ng 1 Knowledge of the pur pose and fun ction of major sy stem compon ents an d contr ols.3.9 2.1.28 295023 Refuel ing Acci dent 1 Monitor o r operate radiation monito ring equip ment as a pplie s to re fuelin g accid ents 3.4 AA1.04 295 024 High Dryw ell Pre ssu re 1 Operate or monitor RPS as ap plies to high drywell pressure 3.9 EA1.05 295 025 High Re acto r Pres sure 1 Relationship with Safety Relief Valv es 4.1 EK2.05 295026 Suppre ssion Pool Hig h W ater Te m pera ture 1 Relationship between suppression po ol cooling and high water temperature 3.9 EK2.01 295 027 High Co ntainm ent T em pera ture Not Applicable to Cooper 295 028 High Dryw ell Te m pera ture 1 Verify alar m setpoints and op erate contro ls as identified in the alar m response manual 3.3 2.4.50 295030 Low Suppr essio n Pool Water Level 1 Monitor o r operate RCIC as appl ies 3.4 EA1.02 Conti nued o n the n ext p age...

ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Conti nued fro m the pr evio us page...Emergency and Abnormal Pl ant Evolu tions - Tier 1

/ Group 1 (RO)E/APE#/Name/Safety Functi on K 1 K 2 K 3 A 1 A 2 G KA T opic(s)IR#295031 React or Low Water Level 1 Ability to loca ted CR sw itches and indications and determine they reflect the desired pla nt line up 4.2 2.1.31 295037 SCRAM C ondit ion Pr esent and Power Ab ove APRM Downsca le or Unkn own 1 Determine or interpret r eactor wa ter level as applied to SCRAM w/ATWS condition 4.1 EA2.02 295 038 High Offsite Re leas e R ate 1 Knowledge of the rea sons for contro l room ventilation isolation dur ing condition s of high offsite r elease rate.

3.7 EK3.03 600 000 Plan t Fire O n S ite 1 Operational implications of fire fighting as appli es to p lant f ire o n site 2.9 AK1.02 KA Category Totals 2 3 3 4 3 5 Group Point T otal: 20 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Emergency and A bnormal Plant Ev olutions - Tie r 1 / Group 2 (RO)E/APE#/Name/Safety Function K 1 K 2 K 3 A 1 A 2 G KA T opic(s)IR#295002 Lo ss of Main Co ndenser Vacuum 295007 High Reactor Pressure 1 Determine or interpret r eactor wa ter level as applies to high reactor pressure 3.7 AA2.03 295008 Hig h Reactor Water Lev el 1 Monitor o r operate HPCI as applie s to high reactor w ater level 3.1 AA1.04 295009 Lo w Reactor Water Level 1 Relations betw een reactor water l evel control and low rea ctor water level 3.9 AK2.02 295010 High Drywell Pressure 295011 Hig h Containment Te mp.Not Applicable to Cooper 295012 High Drywell Temperature 295013 Hig h Suppression Pool Temp.

1 Relation of suppression po ol cooling 3.6 AK2.01 295014 Ina dvertent R eactivity Addi tion 1 Ability to pe rform pre-star tup procedu res for th e facil ity in cludin g ope ratin g those controls associated with pla nt equipment that co uld a ffect r eactiv ity 3.7 2.2.01 29501 5 Incomp lete SC RAM 1 Knowledge of the ope rational implicati ons of the follo wing concep ts as th ey ap ply to incomple te scra m: Reacti vity affects 3.8 AK1.03 29501 7 Hig h Offsi te Rel ease R ate Not Applicable to the RO Po sition 295020 Ina dvertent C ontainment Isol 295022 Lo ss of CRD Pumps 295029 Hig h Suppression Pool Level 295032 Hig h Secondary Containment Area Temperature 1 Relation between CNMT area temperature and l eak de tection system co ncepts 3.6 EK2.07 295033 Hig h Secondary Containment Area Radiati on Levels 295034 Secon dary Con tainment Ventilation Hi gh Radiatio n 295035 Secon dary Con tainment High Differential Pressure 295036 Secon dary Con tainment High Sump / Area Water Level 50000 0 Hig h CTM T Hyd rogen Conc.KA Category Point Total 1 3 0 1 1 1 G ro up Po int T ota l: 7 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Plant Systems-Tier 2 / G roup 1 (RO)Sys tem # / Nam e K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G KA Topi cs IR#203000 RHR LPCI: I nject ion Mode 1 Effect of malfunction on water l vl.4.3 K3.01 205000 Shutd own Cooli ng 1 Design & Interlocks providing for reacto r cool dow n rate 3.6 K4.05 206 000 HPCI 1 Conne ctions with Keep Fill sy stm 4.0 K1.09 207000 I solat ion Condens er Not applicabl e to Coope r 209 001 LPCS 1 Predict/monitor System Lin eup 3.3 A1.08 209 002 HPCS Not applicabl e to Coope r 211000 SLC 1 1 Rel ati on wi th p lan t ai r sy ste ms Ability to ap ply Te ch Spec s 2.5 2.9 K1.03 2.1.12 212 000 RPS 1 1 Knowledge of electrical power systems to RPS M/G sets RPS Bus Voltage 3.2 2.8 K2.01 A1.04 215 003 I RM 1 Operational implications of changing de tector positions 3.0 K5.03 215 004 So urce Ra nge Mon itors 1 Electrical power supplies to SRM channels or detectors 2.6 K2.01 215 005 ARPM / LPRM 1 Monitor a utomatic operation s of max. disagree ment of flow comparator chann els 3.3 A3.06 21 70 00 RC IC 1 Predict/monitor Supp. Pool Leve l 3.3 A1.07 218 000 ADS 1 1 Effect of mal function on ADS valve air supply Predict impact of small br eak LOCA o n ADS a nd mitig ate[Deleted]Ability to monitor automatic operations o f the ADS includ ing ADS valve o peration 3.8 4.2 K6.04 A3.01 223002 PCIS /

Nuclear Steam Su pply S huto ff 1 Predi ct / Mo nitor chang es assoc.with indi vidual re lay status 2.6 A1.04 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 239002 Safet y Rel ief Valves 1 1 Connections w ith nuclear boiler instrumentation syste m Monit or SRV and a coustica l mnt.[Deleted]Lig hts an d Al arm s 3.5 3.6 K1.03 A3.08 259002 React or Water Level Contro l 1 Monitor a uto operati ons and changes in main steam flow 3.2 A3.03 26 10 00 Sta nd by G as Tre atm en t Sys 1 Moritor o r operate fans from the Con tro l R oom 3.0 A4.03 262001 AC Elect ri cal Di str ibut ion 1 Physica l conn ection s with offsite power 3.4 K1.03 Plant Systems-Tier 2 / G roup 1 (RO)Sys tem # / Nam e K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G KA Topi cs IR#262 002 UPS (AC-D C)1 Design & inte rlocks w hich provide fo r transfer fr om preferred to alterna te power Predi ct/monito r chan ges asso c.with motor g enera tor ou tputs[Delete]3.1 2.5 K4.01 A1.02 263000 DC Elect ri cal Di str ibut ion 1 Eff ect of malf unc tio n o n sy ste ms with DC co mponen ts 3.4 K3.03 26 40 00 ED G's 1 1 Operations implicati ons of paralleling AC powe r sources Predict conseque nces of over/unde r-excited operation and mitigate 3.4 2.9 K5.05 A2.04 30 00 00 Instru m en t Air 1 Predict effect of a ir dryer and filter malfunc tions a nd mitig ate 2.9 A2.01 400 000 CCW 1 Effect of loss or malfun ction of pumps will have on CCW 3.0 K6.05 KA Cate gory Point Totals: 4 2 2 2 2 2 4 3 3 1 1 Group Point Total: 26 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Plant Systems-Tier 2 / G roup 2 (RO)Sys tem # / Nam e K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G KA Topi cs IR#201001 CR D Hydrau lic 201002 RMCS 201003 Control Rod and Drive Mecha nism 201004 RSCS Not Applicable to Cooper 20100 5 RCIS Not Applicable to Cooper 20 10 06 RW M 202001 Re circulation 202002 Re circ Flow C ontrol 204000 RWCU 21400 0 RPIS 1 Monitor o r operate control rod pos iti on fro m th e co ntr ol roo m 3.8 A4.02 215001 Traversing In-Core Probe 215002 Ro d Block Monitor 216 000 Nu cle ar Boi ler Ins tru m.21900 0 RHR LPCI: Torus /Pool Cooling Mode 1 Ability to pr edict and/or monitor change s in pa rameter s , including supp ression pool level.3.2 A1.04 22300 1 Pri mar y CNMT & Aux.1 Monitor a utomatic operation and Drywell pressure 4.3 A3.05 22600 1 RHR LPCI: Containment Spra y Mode 1 Knowledge of the bases for prioritizin g safety functio ns 3.0 2.4.22 23000 RHR LPCI: Torus /

Pool Spray Mod e 233000 Fue l Pool Cooli ng &Cleanup 1 Knowledge of physical connec tions a nd cau se/effe ct with RHR 2.9 K1.02 234000 Fue l Handling Equip.239001 M ain & Rehea t Steam 1 Design & inte rlocks p ertai ning to equalization of MSIV pressure prior to o pening 3.3 K4.09 239003 M SIV Leakage Co ntrol Not Applicable to Cooper Conti nued o n Nex t page...

ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Conti nued fro m prev ious page...Plant Systems-Tier 2 / G roup 2 (RO)Sys tem # / Nam e K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G KA Topi cs IR#241000 Re actor / Turbi ne Pressure Regu lator 245000 M ain Turbine Generator

& Auxiliar ies 25600 0 Rea ctor C onden sate 1 Effect of main steam system loss or malfunction on condensate system [De lete]Effect of main steam system loss or malfunction on the reactor feed water syste m 3.3 K6.10 K6.06 259001 Re actor Feedw ater 26800 0 Rad waste 271000 Offga s 1 Monitor a uto operati on of ind ica tin g l igh ts a nd ala rms 2.9 A3.05 272000 Ra diation Mo nitoring 1 Operator r esponsibilities d uring all modes of ope ration 3.0 2.1.2 286000 Fir e Protection 1 Effect of loss or malfun ction on personnel p rotection 3.2 K3.02 288000 Plan t Ventilation 290001 Secondary Containment 29000 3 Con trol R oom HVAC 1 Predict impact of ini tiation or recon figur ation and mit igate abnormal conditi ons 3.1 A2.01 290002 Re actor Vessel Internals 1 Design & inter locks provide for natural circul ation 3.3 K4.05 KA Category Point Totals 1 0 1 2 0 2 1 1 1 1 2 Group Point Total 12 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Average IR for Tier 1, Group 1 3.52 Tier Total 20 Average IR for Tier 1, Group 2 3.63 Tier Total 07 Average IR for Tier 2, Group 1 3.12 Tier Total 26 Average IR for Tier 2, Group 2 2.91 Tier Total 12 Avera ge IR for Tier 3 3.06 Tier Total 10 Average IR for RO E xam 3.23 Exam Total 75 ES-401 BWR Examination Outline Form E S-401-3 ES-401 , NUR EG 1021 Rev ision 9 Generic Know ledge and Abilities Outline (T ier 3)Category KA #Topic RO SRO Only IR#IR#1. Conduct of Operations 2..1.10 Know ledge of con dition s and l imitatio ns in t he faci lity license 2.7 1 2..1.28 Knowledge of the pur pose and fun ction of major syste m compone nts and contr ols.3.2 1 2..1.33 Ability to re cognize ind ications for syste m operating parameters w hich are en try condition s for technical specifi cation s.2.7 1 Subtotal 3 2. Equipment Control 2..2.22 Know ledge of limit ing co nditio ns for oper ation s and s afety limits 3.4 1 2..2.30 Knowledge of RO dutie s in the CR during fue l handling 3.5 1 2..2.34 Knowledge of the pro cess for determinin g the inter nal and exte rnal effects on cor e rea ctivity 2.8 1 Subtotal 3 3. Radiation Control 2..3.01 Knowledge of 10 CFR 20 and re lated facility radiation contro l req uireme nts 2..6 1 2..3.10 Ability to pe rform procedur es to reduce excessive l evels of radiation and guard against personnel exposure 2..9 1 Subtotal 2 4. Emerg ency Procedures and Plan 2..4.46 Ability to ve rify that al arms are consistent with plan t conditions 3.5 1 2..4.49 Ability to pe rform w ithou t refe rence to pr ocedur es thos e actions which require i mmediate operations of system components and con trols 3.3 1 Subtotal 2 Tier 3 Point Total 10 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Emergency and Abnormal Pl ant Evolu tions - Tier 1

/ Group 1 (SRO)E/APE#/Name/Safety Functi on A 2 G KA T opic(s)IR#295 001 Pa rtial or Co m plete L oss of Forc ed C ore Flow Cir culat ion 1 Knowledge of limiting condi tions for ope rations and safety limits 4.1 2.2.22 295 003 Par ti al or Compl et e Lo ss of AC 295004 Part ial or Total Loss of DC Pwr 29 50 05 Ma in T urb ine Ge ne rato r Trip 1 Ability to de termine or inte rpret feedw ater temperature as applied to a main turbine generator trip 2.7 AA2.06 295 006 SCRAM 295016 Contr ol Room Abandonment 295 018 Par ti al or Tot al Los s o f CCW 29 50 19 Pa rtial o r To tal Lo ss o f Inst A ir 1 Know ledge of an nuncia tors, a larms, a nd in dicati ons, and use of th e response i nstructions 3.4 2.4.31 295021 Loss of Shut down Cooli ng 295023 Refuel ing Acci dent 295 024 High Dryw ell Pre ssu re Ability to de termine or inte rpret suppr ession pool level as ap plied to hig h dryw ell pressure

[Deleted]

295 025 High Re acto r Pres sure 1 Ability to de termine or inte rpret suppr ession pool temperature as applied to high reactor press ure 4.1 EA2.03 295 026 Su ppre ssion Po ol Hig h W ater T em pera ture 295 027 High Co ntainm ent T em pera ture 1 Ability to re cognize ind ications for syste m operating parameters w hich are en try-level conditions for technical specificatio ns 4.0 2.1.33 295 028 High Dryw ell Te m pera ture 1 Ability to de termine and/or interpret the follow ing as they apply to high dr ywell te mperature: Rea ctor Water Level.

3.9 EA2.03 295030 Low Suppr essio n Pool Water Level 1 Ability to de termine or inte rpret dry well /suppr ession pool diffe renti al pr essure as app lied t o low suppr ession pool w ater level 3.7 EA2.04 295031 React or Low Water Level 295037 SCRAM C ondit ion Pr esent and Power Above APRM Downsca le or Unkn own 295 038 High Offsite Re leas e R ate 600 000 Plan t Fire O n S ite KA Category Totals 4 3 Group Point T otal: 7 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Emergency and Abnormal Pl ant Evolu tions - Tier 1

/ Group 2 (SRO)E/APE#/Name/Safety Function A 2 G KA T opic(s)IR#295002 Lo ss of Main Co ndenser Vacuu m 295007 High Reactor Pressure 1 Knowledge of surveill ance procedu res 3.4 2.2.12 295008 Hig h Reactor Water Lev el 295009 Lo w Reactor Water Level 295010 High Drywell Pressure 295011 Hig h Containment Te mp.Not Applicable to Cooper 295012 High Drywell Temperature 295013 Hig h Suppression Pool Temp.

295014 Ina dvertent R eactivity Addi tion 29501 5 Incomp lete SC RAM 29501 7 Hig h Offsi te Rel ease R ate 1 Knowledge of symptom-based EOP mitiga tion strategies 4.0 2.4.6 295020 Ina dvertent C ontainment Isol 295022 Lo ss of CRD Pumps 295029 Hig h Suppression Pool Level 295032 Hig h Secondary Containment Are a Temperature 295033 Hig h Secondary Containment Are a Radiation L evels 295034 Secon dary Con tainment Ventilation High Radia tion 1 Ability to de termine or inte rpret ven tilation rad iation levels 4.2 EA2.01 295035 Secon dary Con tainment High Differential Pressure 295 036 Sec ond ary Co nta inme nt H igh Sum p/ Area Water Level 50000 0 Hig h CTM T Hyd rogen Conc.KA Category Point Total 1 2 G ro up Po int T ota l: 3 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Plant Systems-Tier 2 / G roup 1 (SRO)Sys tem # / Nam e A 2 G KA Topi cs IR#203000 RHR LPCI: I nject ion Mode 1 Know ledge of the proce ss for ma nagin g mainte nance activities duri ng shutdow n operatio ns 3.5 2.2.18 205000 Shutd own Cooli ng 206 000 HPCI 1 Ability to ex ecute procedu re steps 4.2 2.1.20 207000 I solat ion Condens er Not Applicable to Cooper 209 001 LPCS 209 002 HPCS Not Applicable to Cooper 211000 SLC 212 000 RPS 215 003 I RM 1 Ability to de termine Mode of Operation 3.3 2.1.22 215004 Sourc e Range Monit or 215 005 ARPM / LPRM 21 70 00 RC IC 218 000 ADS 223 002 PC IS / Nu clea r Stea m Su pply S huto ff 23 90 02 SR V's 259002 React or Water Level Contro l 261000 Stand by Gas Tre atment Sy stem 262001 AC Elect ri cal Di str ibut ion 1 Ability to pr edict t he impa ct of op ening a disc onnect under loa d and....corre ct, control or mitigate the consequences 3.6 A2.08 262 002 UPS (AC-D C)263000 DC Elect ri cal Di str ibut ion 264 000 Em erge ncy D iese l Ge nera tors 1 Ability to pr edict the impacts of sy nchronizatio n of the emerge ncy ge nerat or w ith ot her e lectri cal sup plies, and....correct, con trol or mitigate the conseque nces 3.6 A2.05 30 00 00 Instru m en t Air 400 000 CCW KA Cate gory Point Totals: 2 3 Group Point Total: 5 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Plant Systems-Tier 2 / G roup 2 (SRO)Sys tem # / Nam e A 2 G KA Topi cs IR#201001 CR D Hydrau lic 201002 RMCS 20100 3 Con trol R od an d Dri ve Me chanis m Ability to pe rform specific system and integrated plant proced ures during different modes of plant operations [D eleted]4.0 2.1.23 201004 RSCS Not Applicable to Cooper 20100 5 RCIS Not Applicable to Cooper 20 10 06 RW M 202001 Re circulation 1 Ability to pr edict the impacts of r ecirculation scoo p tube lockup on the recircul ation system and o n the basis o f the p redict ion u se pro cedur es to co rrect, control, or mitiga te the consequ ences of the abnor mal cond itions or op erati ons.3.4 A2.09 202002 Re circ Flow C ontrol 204000 RWCU 21400 0 RPIS 215001 Tra versing In-Core Probe 215002 Ro d Block Monitor 216000 Nu clear Boiler Instrumentation 219000 RH R LPCI: Torus

/ Pool Coolin g Mode 22300 1 Pri mar y CNMT & Aux.226001 RH R LPCI: Conta inment Spray Mode 23000 RHR LPCI: Torus /

Pool Spray Mode 233000 Fue l Pool Cooli ng & Cleanu p 1 Ability to ob tain a nd in terpr et stati on re feren ce materia ls...w hich co ntain perfo rmance data 3.1 2.1.25 234000 Fue l Handling Equip.1 Ability to tra ck limiting conditions for operati ons 3.8 2.2.23 239001 M ain & Rehea t Steam 239003 M SIV Leakage Co ntrol 241000 Reactor / Turbine Pressure Regulator 245000 Main Turbine Generator &

Auxiliari es ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 25600 0 Rea ctor C onden sate...cont inued on Ne xt pa ge......cont inued from Pre viou s page...Plant Systems-Tier 2 / G roup 2 (RO

/ SRO)Sys tem # / Nam e A 2 G KA Topi cs IR#259001 Re actor Feedw ater 26800 0 Rad waste 271000 Offga s 272000 Ra diation Mo nitoring 286000 Fir e Protection 288000 Plan t Ventilation 290001 Secon dary Con tainment 29000 3 Con trol R oom HVAC 290002 Re actor Vessel Inter nals Deleted KA Category Point Totals 1 2 Group Point Total 3 ES-401 BWR Examination Outline Form E S-401-1 ES-401 , NUR EG 1021 Rev ision 9 Average IR for Tier 1, Group 1 3.69 Tier Total 7 Average IR for Tier 1, Group 2 3.87 Tier Total 3 Average IR for Tier 2, Group 1 3.64 Tier Total 5 Average IR for Tier 2, Group 2 3.76 Tier Total 3 Avera ge IR for Tier 3 3.43 Tier Total 7 Average IR for SR O Exam 3.64 Exam Total 25 ES-401 BWR Examination Outline Form E S-401-3 ES-401 , NUR EG 1021 Rev ision 9 Generic Know ledge and Ab ilities Outline (Tier 3)

Category KA #Topic RO SRO Only IR#IR#1. Conduct of Operations 2.1.14 Knowledge of system status cri teria which require notification of pla nt personnel 3.3 1 Subtotal 1 2. Equipment Control 2.2.14 Knowledge of the process for making configuration changes 3.0 1 2.2.26 Knowledge of refueling administr ative requireme nts 3.7 1 Subtotal 2 3. Radiation Control 2.3.3 Knowledge of SRO responsib ilities for aux iliary systems outside the control room (w aste disposal and handling syste ms)2.9 1 2.3.4 Knowledge of radiation ex posure limits and contamination control , including permissible levels in excess of those authorize d 3.1 1 Subtotal 2 4.Emergency Procedures and Plan 2.4.22 Knowledge of the bases for pr ioritizing safet y functions during ab normal or emergency operations 4.0 1 2.4.44 Knowledge of emergency plan protective acti on recommendations 4.0 1 Subtotal 2 Tier 3 Point Total 7 Facility:

COOPER Scenario No.: 4Op-Test No.:1 Examiners:

_Paul Gage

_______________

Operators:

__________________________

_Steve Garchow

___________ __________________________

_Kelly Clayton

____________ __________________________

Plant Status: The plant is operating at 75% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a norma l configuration with the exception of Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 are out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity Turnover: The plant is operating at 75% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a norma l configuration with the exception of Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 are out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity.

Scenario: The plant is operating at 75% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with the exception of Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 are out of service.

Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity. A surveillance testing the operability of main steam

isolation valve 80A fails resulting in one MSL being isolated. A lightning strike on the grid results in the loss of the 69kV OPPD Nebraska City Line and requires performing a tech spec surveillance. When the Technical Specification assessment is complete, a MSL radiation monitor fails upscale. When the assessment of this is complete, APRM Channel B fails INOP. When the actions for the APRM are complete, a loss of off-site power, reactor scram, and a steam leak into primary containment occur. Later in the scenario EDG-2 fails. The scenario ends when RPV water level is being restored to the normal band, drywell pressure is being controlled and classifications have been made.

Event No.Malf. No.Event Type*Event Description 1.Trigger 1N (SRO, RO)Power reduction to < 70% using control rods and recirc flow 2.Trigger 2C, T (BOP, Surveillance 6.MS.201 Section 5 (Failure of MSIV MOV-80A to open)

Facility:

COOPER Scenario No.: 2Op-Test No.:1 Examiners:

_Paul Gage

_______________

Operators:

__________________________

_Steve Garchow

___________ __________________________

_Kelly Clayton

____________ __________________________

Plant Status: The plant is operating at 60% power with instructions to continue the power ascension to 100%. The A1 Reactor Feedpump LO Pump and D1 Sump Pump are both tagged out due to a motor failure. The Sentinal Status is Green.

Turnover: The plant is operating at 60% power with instructions to continue the power ascension to 100%. The A1 Reactor Feedpump LO Pump and D1 Sump Pump are both tagged out due to motor failures. The Sentinal Status is Green. Reactor engineering is working on the computer program used to calculate AGAFs. Assume all AGAFs

are in specification unless otherwise notified by the STA.

Scenario: The plant is operating at 60% power with instructions to continue the power ascension to 100%. The crew will raise power greater than 70% before the first event is called in. The "A1" Feed Pump Lube Oil Pump and Sump Pump D1 are tagged out for maintenance. Following the power ascension, an accumulator fault due to low N2 pressure is received. Following the Tech Spec assessments, an inadvertent initiation of HPCI

occurs. The crew should respond per 2.4CSCS and the Technical Specifications. After the Tech Spec assessment is complete, a tube rupture occurs in feedwater heater A5. This will require a diagnosis since the alarm clears. Eventually the crew will have to commence a plant shutdown. Once the shutdown is underway, an unisolable steam line leak will develop on the HPCI steam line. The automatic isolation for the steam supply valves will not function and the valves cannot be closed from the control room. The crew is expected to take action EOP-05, Secondary Containment Control and scram the plant before one area reaches a Maximum Safe Operating Temperature (MSOT). Due to a hydraulic lock, many control rods will fail to insert. The crew should respond to the ATWS per EOP-06A, 7A and 5.8.3. Power level should be ~ 10%

after the Recirculation pump trip, so RPV water level will have to be lowered.

Control rods can be inserted via RMCS.The secondary containment temperatures will continue to rise, resulting in MSOT in 2 areas. The crew is expected to take action iaw EOP-6B and perform an Emergency Depressurization. After the Emergency Depressurization is complete and RPV water level is being controlled, the control rods will insert the next time the scram is reset and scrammed again.The scenario will terminate when the RPV has been depressurized, control rods have been inserted. and RPV water level has been restored to +15 to +40".

EventMalfNo EventEventDescription Facility:

COOPER Scenario No.: 3Op-Test No.:1 Examiners:

_Paul Gage

_______________

Operators:

__________________________

_Steve Garchow

___________ __________________________

_Kelly Clayton

____________ __________________________

Plant Status: The plant is operating at 100% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity Turnover: The plant is operating at 100% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity.

Scenario: The plant is operating at 100% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity.

When the Technical Specification assessment is complete, a bus ground results in

a loss of MCC "F". The loss of MCC F causes a trip of RFPT A due to low lube oil pressure, A1 pump tagged out, requiring a power reduction to maintain reactor water level and to reduce heat load to the capacity of the remaining pump. When conditions have stabilized, RFP "B" vibrations increase to the point that the pump must be tripped. The crew will scram the reactor and trip the last remaining RFP.

When RCIC initiates, a break develops on the "A" feedwater line inside the drywell. HPCI fails to automatically start, but may be manually started. RCIC will not inject due to the location of the leak. The feedwater line check valve leaks, and the leak continues. HPCI can maintain RPV water level for the selected leak size. Containment sprays will be required by the EOPs. Drywell sprays will be initiated. Drywell sprays will fail to isolate on low containment pressure. The operator must either maintain pressure by controlling spray flowrate or manally isolate drywell sprays when containment becomes negative before air is drawn into the primary containment. The scenario ends when RPV water level is being restored to the normal band, drywell pressure is being controlled and classifications have been made.

Event No.Malf. No.Event Type*Event Description 1.Initiated by turnoverN (RO)Power reduction of 100 MWe 2.Trigger 1T, I (RO, BOP, SRO)Drywell Pressure Instrument Fails UPSC (PC-PS-12C)Trigger2C(All)LossofMCCF/LossofRFPT

Facility:

COOPER Scenario No.: 3Op-Test No.:1 Examiners:

_Paul Gage

_______________

Operators:

__________________________

_Steve Garchow

___________ __________________________

_Kelly Clayton

____________ __________________________

Plant Status: The plant is operating at 100% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity Turnover: The plant is operating at 100% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity.

Scenario: The plant is operating at 100% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity.

When the Technical Specification assessment is complete, a bus ground results in

a loss of MCC "F". The loss of MCC F causes a trip of RFPT A due to low lube oil pressure, A1 pump tagged out, requiring a power reduction to maintain reactor water level and to reduce heat load to the capacity of the remaining pump. When conditions have stabilized, RFP "B" vibrations increase to the point that the pump must be tripped. The crew will scram the reactor and trip the last remaining RFP.

When RCIC initiates, a break develops on the "A" feedwater line inside the drywell. HPCI fails to automatically start, but may be manually started. RCIC will not inject due to the location of the leak. The feedwater line check valve leaks, and the leak continues. HPCI can maintain RPV water level for the selected leak size. Containment sprays will be required by the EOPs. Drywell sprays will be initiated. Drywell sprays will fail to isolate on low containment pressure. The operator must either maintain pressure by controlling spray flowrate or manally isolate drywell sprays when containment becomes negative before air is drawn into the primary containment. The scenario ends when RPV water level is being restored to the normal band, drywell pressure is being controlled and classifications have been made.

Event No.Malf. No.Event Type*Event Description 1.Initiated by turnoverN (RO)Power reduction of 100 MWe 2.Trigger 1T, I (RO, BOP, SRO)Drywell Pressure Instrument Fails UPSC (PC-PS-12C)Trigger2C(All)LossofMCCF/LossofRFPT

Facility:

COOPER Scenario No.: 4Op-Test No.:1 Examiners:

_Paul Gage

_______________

Operators:

__________________________

_Steve Garchow

___________ __________________________

_Kelly Clayton

____________ __________________________

Plant Status: The plant is operating at 75% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a norma l configuration with the exception of Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 are out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity Turnover: The plant is operating at 75% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a norma l configuration with the exception of Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 are out of service. Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity.

Scenario: The plant is operating at 75% power near the end of the current fuel cycle when the crew takes the shift. The plant is in a normal configuration with the exception of Rx Feed Pump Lube Oil Pump A1 and Sump Pump D1 are out of service.

Southeast Nebraska is in a severe thunderstorm warning, which includes intense electrical storm activity. A surveillance testing the operability of main steam

isolation valve 80A fails resulting in one MSL being isolated. A lightning strike on the grid results in the loss of the 69kV OPPD Nebraska City Line and requires performing a tech spec surveillance. When the Technical Specification assessment is complete, a MSL radiation monitor fails upscale. When the assessment of this is complete, APRM Channel B fails INOP. When the actions for the APRM are complete, a loss of off-site power, reactor scram, and a steam leak into primary containment occur. Later in the scenario EDG-2 fails. The scenario ends when RPV water level is being restored to the normal band, drywell pressure is being controlled and classifications have been made.

Event No.Malf. No.Event Type*Event Description 1.Trigger 1N (SRO, RO)Power reduction to < 70% using control rods and recirc flow 2.Trigger 2C, T (BOP, Surveillance 6.MS.201 Section 5 (Failure of MSIV MOV-80A to open)

ES-401 Recor d of R eject ed KA's Form E S-401-4 ES-401 , NUR EG 1021 Rev ision 9 For the RO Ex amination:

Tier Group Randomly Selected KA Reason for Rejecti on 1 1 295028 High Dr ywell Temperature, 2.1.6, Ability to supervise and assume a management role dur ing plant transients and upset conditions Not applicable to the RO positio n; represents SR O-level knowledge 1 1 295031 Reactor L ow Water Level, 2.4.41, Knowledge of the emergency action level thresholds and classifi cations Not applicable to the RO positio n; represents SR O-level knowledge 1 1 295031 Reactor L ow Water Level, 2.2.8, Knowledge of the process for deter mining if the proposed change (et.al.) Involv es an unreview ed safety questi on IR for RO is less than 2.5 1 1 295019 Partial or Total Loss of Instrument Air, 2.2.18, Know ledge of the process for managing maintenance activit ies during shutdown oper ations IR for RO is less than 2.5 1 1 2.4.02 Know ledge of system setpoints, interlocks, and automatic actions associa ted with EOP entry conditions, as applie d to 29 5021 , Los s of S hutd own Cooling There are n o EOP entry conditions associated with loss of shutdown cooling, therefor e another KA w as selected at ran dom.1 2 295014 Inadver tent Reactivit y Addition, 2.2.31 , Knowledge of the effects of alt erations on core configuration IR for RO is less than 2.5 1 2 295014 Inadver tent Reactivit y Addition, 2.4.41 , Knowledge of the emergency act ion level thresholds and classifi cations Not applicable to the RO positio n; represents SR O-level knowledge 1 2 295017 High Of fsite Release Rate, AK1.02, Operational Implications of high offsite release rate as af fects protection of the general p ublic Not applicable to the RO positio n (per M. Barton, 1/19/05); replace d by EK3.03, Knowledge of the reasons for Control R oom isolation as pert ains to High O ffsite Release Rate 2 1 262002 UPS, K2 No KA's in catalog for catego ry K2 2 2 239003 MSI V Leakage Contr ol Not Applicable t o Cooper (per M. Bar ton, 1/19/05) ;

replaced by 2330 00 K1.02 ES-401 Recor d of R eject ed KA's Form E S-401-4 ES-401 , NUR EG 1021 Rev ision 9 2 2 272000 Radiation Monitoring System, 2.4.30 , Knowledge of which event s related to sy stem operation/status w hich should be reported to out side agencies No applicable repo rting requirement s 2 2 256000, K6.10, K nowledge of the effect that a loss or malfunction of the mai n steam system wil l have on the condensate f eedwater system.This KA w as replace due to there being no r elationship between main steam and the condensa te system.

Anothe r KA was chos en from the sam e KA cate gory.2 2 219000 RHR LP CI: Suppression Pool Cooling M ode, A3.01, Monitor au tomatic operation a s applied to valv es There is no a utomatic operation or repositioning o f valves associated with RHR LPCI Suppression Pool Cooling Mode. Replaced by A1.04, Ability to predict and/o r monitor changes in parameters associ ated with RHR LPCI Suppressio n Pool Cooling M ode controls, includi ng suppression pool lev el.2 2 214000 Rod Posit ion Indication System, A4.03 , Ability to manually operate or monitor control rod driv e temperature from the control room Temperature i ndication is limited t o PMIS (computer system) with effe ctively n o contr ol over CR d rive temperature. R ejected because no discr iminating question can be w ritten. Repla ced by A4.02, Ability to manually operate or monitor contr ol position from t he contro l room.3 0 2.1.26, Know ledge of non-nuclea r safety procedur es IR for RO is less than 2.5 3 0 2.1.13, Know ledge of facility requirements for controlling vita l and controlled are as IR for RO is less than 2.5 3 0 2.2.19, Know ledge of maintenance wor k order requirements IR for RO is less than 2.5 3 0 2.2.17, Know ledge of the pro cess for managing mainten ance activities during power oper ations IR for RO is less than 2.5 3 0 2.2.4, Ability to explain variations between unit s at a facility Cooper is a single unit facility 3 0 2.215, Ability t o ident ify and ut ilize as-built design and configuration change documentation..

.IR for RO is less than 2.5 3 0 2.3.7, Know ledge of the pro cess for preparing a radiation w ork permit IR for RO is less than 2.5 ES-401 Recor d of R eject ed KA's Form E S-401-4 ES-401 , NUR EG 1021 Rev ision 9 For the SRO Ex amination:

Tier Group Randomly Selected KA Reason for Rejecti on 2 1 Predict/monitor ch anges assoc.

with motor generator output s There are n o MG set s associated wit h the UPS at Cooper. Anot her KA w as randomly select ed.2 1 Monitor S RV and acoustical monitors There are n o SRV acoustical monitors at Coope

r. Another KA was randomly selected from the same KA catego ry.2 1 Ability to pr edict the impacts of a small break LOCA on ADS, and based on those pred ictions use procedures to corr ect, control, or mitigate the conseque nces of those abnormal condit ions or operations.

A small break LO CA has no impact on the operation of the ADS. A nother KA w as randomly select ed.1 1 Ability to de termine or inter pret suppression pool lev el as applied to high dryw ell pressure Unable to constru ct an SRO on ly question for this KA.

Another KA w as randomly select ed.2 2 Ability to pe rform specific sy stem and integrated pl ant procedures during different modes of plant operations, as appl ied to 201003, Control Rod and Dri ve Mechanism.

Unable to constru ct an SRO on ly question for this KA.

Another KA w as randomly select ed.2 1 Ability to ex ecute procedure ste ps as applied to 206000 , High Pressure Coolant Injection.

Unable to constru ct an SRO on ly question for this KA.

Another KA w as randomly select ed.2 2 290002 Reactor V essel Internals, A2.05, Ability to predict the impacts of ex ceeding thermal limits on reactor v essel internals and on the basis of the prediction use procedures to co rrect, control, or mitiga te the consequences of the ab normal conditions or opera tions.Rejected because ope rators have v ery limited dir ect knowledge of reactor vessel i nternals and because they are static components have little abi lity to opera te the components. Replace d by 202001 A 2.09, Ability to predict the impacts of recirculation sco op tube lockup on the recirculation system and on the basis of the prediction use proce dures to correct, control, or miti gate the consequences of t he abnormal condition s or operations.