ML092850004

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Draft Administrative Documents
ML092850004
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 10/10/2009
From:
NRC/RGN-II
To:
South Carolina Electric & Gas Co
References
50-395/09-301
Download: ML092850004 (30)
v • d • e


Text

I~s=401, E8-401, Rev. 9 QPA~r PWR examination Outline Fonn E8-401*2 I

! Facility: <;;11 M t71/A..

~ tI nt." tA... Date of Exam: 1~9 ltfl9 I

Ii Tier Group RO KIA Category Points SR~1y SRO-Only Points I

II K K K K K K A A A A G A2 G*

G* Total Ii 1 2 3 4 5 6 1 2 3 4 ** Total II II 1. 1 3 4 3 3 3 2 18 3 3 6 I i Emergency &

Abnormal Plant Abnonnal 2 2 1 2 N/A NJA 1 1 4

N/A NIA 2

9 27 2 2 4 Evolutions Evolutlons 5 5 5 4 4 Z7 5 5 10 I, I Tier Totals 1 2 2 2 3 , , ,, ,

3 3 2 3 3 2 3 28 2 ,

3 5 I I 2.

2 1 0 , ,, , , , , , ,

1 1 1 1 1 1 1 1 1 10 2 ,

1 ,

3 I Plant Systems , , ,

3 4 ,

3 4

,I lTier ief" Totals

3. Generic Knowledge and Abilities 3 2 3 4 1

4 4 2 3 4

4 4

38 10 1 2 3 4

4 8

17 III Categories ,3 2 ,

3 2 2 ,

1 2 2 i

I

1. Ensure that at at least two topics ~cs from every appUca~ applicable KIA category are sampled within each tier tier of the RO I

and SRO-only arK! SRO-ooiy ouUlnes ouUlnea (I.e., 8J(ceptexcept for one category In Tier 3 of the SRQ-onIy SRO-only outline.

outline, the '"Tier ller Totals" Totals "

kI ead! KIA categOl'}'

In each category ahall shall not be lualess than two).

(~

2. The point total for each grnup group and tier In In*the the proposed ooUineoutline must match that specified In the table.

The final point total for each group and tler tier may deviate by t+/- 1 from that specified In the fable table I boIsed on NRC revision based revisions. The flnal

  • . Tl1e final RO exam must total totaL 75 points paints and the SRO-only SRO-ooly exam eKam must total 25 pOints.

points.

I iI

3. Systemslevolutions within each group are identified Systems/evolutions Identified on the assoo::lated associated outline; systems sys tems or evolutions that do I not apply at the fac ility should be deleted and JU3tlfied; facility justified; operationelly Important, sl operationally important, te-spe<:Uic systems that are site-specific not Included included on the outline sl'K)uld should be added. Refer to E5-401 ES-401,, Attachment 2, for guidance regarding I I 4.

the eliminatJon elimination ofof Inappropriate inappropriate KIA statements.

Select topics from as many systems and evolutions as possible; sample every system Of" Seleet or evolution In the group before selecting a second topic for ro.- any system or evolution.

I I 5. Absent a plant-specific Pflorlty, priority, only those KlAs selected. Use the RO and SRO ratings for the RO and SRQ-on/y KIAs having an Importance rating 0( higher shall be raUng (IR) of 2.5 or Ii SRO-only portions, respectively.

8.

6. Select SRO topics for TIers Tiers 1 and 2 from the shaded systems sys tems and KIA categories.

II

7. --rhe
  • The generic (G) K/As KlAs In TIersTiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics relavant to the applicable evolutlon must be relevant or system.

evolution Of"

8. On the following pages, enter the KIA numbers, a brief descrlptlon description of each topic, the topiCS' topics' Importance I ratings (IRs) forto( the applicable license level, and the point totals (')

the group and tier totals for tOf" each category In the table above; If

(#) for each system and category. Enter if fuel handling equipment Is is .ampted sampled In other I,

I than Category A2 or 01"" G*

G* on the SRO-ooly SRO-only exam,ellam, enter It on the left sideslOe of Column A2 for TIer Tier 2, Group 2 (Note

,# 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. FO(

For TIer Tier 3, select topiCS and point totals (') (#) on Form E5-401 Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, topiC S from section ES-401-3.*3. Limit SRO selections to KIA. KIAs that are linked to 10 CFR 55.43.

I

____________ JI

(

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 ES-401*2 KA NAME I SAFETY FUNCTION: IR IR K1 K2 K3 1(3 1<4 K4 K51(5 1(6 K6 A1Al A2 A3 A4 G TOPIC:

TOPIC:

RO SRO 008AA1.06 Accidenlf3 Pressurizer Vapor Space Accident 13 3.6 3.6 0 0 0 0 0 0 ~ 0 0 0 0 Control of PZR level Ability to predict and/Of" monitor changes in p redict andlor parameters pall'lmeters associated with operating the (SYSTEM) controls including:(CFR:

inciuding:(CFR: 41 .5 f 41.51

.45.5) 45.5) 0"EK3,15 011EK3.15 Large Break LOCA LOCA/3 13 44.3

.3 4 .4 4.4 0OO 0 ~ 0 0 0 0 0 0 0 0 OOOOOOOO Criteria for shifting to recirculation mode Knowledge of the effect that a loss or malfunction of the (SYSTEM) will wi" have on 00 the following:(CFR:

folkrMng:(CFR: 41.7/45.6) 41 .7145.6) 0 15AK2.01 015AK2.07 Rep Malfunctions 1 RCP MalfunctiOns f4 2.'

2.9 2.'

2.9 0O 0 0 0 0 0 0 0 0 0

~ OOOOOOOOO seats RCP seals Kno'NIedge of Knowledge 01 electrical power suppfles supplies to the following:(CFR:

foliowing:(CFR: 41 41.7)

.7) 0 15AK2.07 015AK2.07 Rep 14 RCP Malfunctions 14 2.'

2.9 2.'

2.9 0 ~ 0OOOOOOOOO O 0 0 0 0 0 0 0 0 Rep seals RCP Knowledge of electrical power supplies to the following:(CFR:

foIlO'Ning:(CfR: 41.7) 022AA2.02 oss of Rx Coolant Makeup 1 lLoss 122 3.2 3.7 0 0 0 0 0 0 0 ~ 0 0 0 Charging pump problems Ability to (a) pt'edict predict the impacts of the following on the (SYSTEM) and (b) based on those predictions.

predictions, use procedures to 10 COITeCl control, or mitigate the correct.

consequences of those abnormal opef3tioo:(CFR:

operation:(CFR: 41 .5 / 43.5/45_3 145.13) 41.5/43.5/45.3/45.13) 025AK1 .0 1 025AK1.01 Loss of RHR System 1 14 4 3.'

3.9 4.3 0 0 0 0 0 0 0 0 0 0

~ OOOOOOOOOO of RHRS during all Loss 01 an modes of01 operation Knowledge 01 of the physical connections and/or cause-effect relationships between andlor (SYSTEM) loIlowing:(CFR 41.2 to (SYSTE M) and the following:(CFR:

41 .9/45.11045.8) 41.9/45.7 to 45.8)

P","'3

~

P~f3 41312008 4/3/2008

~ "-./ J

ES-401, ES-401. REV 9 T1Gl PWR EXAMINATION OUTLINE T1G1 FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC, TOPIC:

RO SRO 026AG2.1.20 Loss of Component Cooling Water / 8 LossofComponentCooliogWater/8 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to execute exectJle procedure steps.

This Is is a Generic. no stem statement is 8 Genenc.

aSSOCiated.

associated.

027AK2.03 Pressurizer Pressure Control System 2.6 2.8 0D ~ 0 0 0 0 0 0 0 0 0 DDDDDDDDD Controllers CootroliefS and positioners poSitioners Malfunction I/ 3 J

Knowledge of electrical power supplies to

, the following:(CFR:

followlng:(CFR: 41.7) 029EK1.02 029EK 1.02 ATWS 11 ATWSf1 2.6 2.8 ~ 0 0 0 0 0 0 0 0 0 0 DDDDDDDDDD Definition of reactivity Knowledge of the physical connections physiCal conl'leCtions and/or cause-effect andlor cause-effecl relationships between (SYSTEM) and the following:(CFR:

foUowing:(CF R: 41.2 41 .2 to 41.9/45.7 41.9145.7 to 45.8) 038EK1 .01

.0 1 TUbe Rupture Steam Gen. Tube 3 RuplUfe 1/3 3.1 3.1 3.4 ~ 0 0 0 0 0 0 0 0 0 0 Ii/I Use of steam tables Knowledge of the physical connections Kl'lOYI'Iedge and/or andlor cause-effect causa-effect relationships between (SYSTEM) and the following:(CFR:

following :(CFR: 41.2 to 41.9/45.1 to 45.8) 41.9/45.7 054AK3.03 Loss of Feedwater 1 01 Main Feedwaler 144 3.8 4.1 41 0 0 ~ 0 0 0 0 0 0 0 0 Manual control of AFW flow control valves Koo-Medge Knowledge of the effect that thai a loss or malfunction m alfunction of the th e (SYSTEM) willwin have on the following:(CFR:

following :(CFR: 441.7/45.6) 1.7145.6) 055EA1 .01 Station Blackout {/ 6 3.7 3.9 0DDDDDD 0 0 0 0 0 0 0 0 0

~ DDDD thefTTlocouple temperatures In-core thermocouple Ability to predict andfor and/or monitor changes in parameters associated with operating opera ting the (SYSTEM)

(SYS TEM) controls includlng:(CfR:

including:(CFR: 41.5/

41 .5 (

45.5)

~ 1-'3

,-f3 41312008 4/3/2008

~.

'---./

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE ES-401-2 FORM ES-4111 -2 KA NAME I SAFETY FUNCTION:FUNCTION : IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO SRQ 056AA2.02 Loss of Off-site Power 1/6 6 3.53.6 3.5 3.6 0 0 0 0 0 0 0 Ii'l DDDDDDD ~ DDD0 0 0 lights ESF load sequencer status fights Ability to (a) predict the Impacts impacts of the following on the (SYSTEM) and (b) based on those predictions, predictions. use procedures pnx:edures to correct, COITed , control, control , or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) oplWtion:(CFR: 41.5/43.5/45.3/45.13) 057AG2.4.8 057AG2.4.B loss alVital Loss of Vital AC Inst.

lost Bus 16 3.645 3.B 0 0 0 0 0 0 0 0 0 0 Oil 4.S DDDDDDDDOO ~ Knowledge 01 KnO'Medge of how abnormal opemting operating procedures are used in conjunction with EOPs.

Geoe~. no stem statement Is This is a Generic, is associated.

associated.

06SAK3.0B 065AK3.08 (B Loss of Instrument Air 18 3.7 3.9 3.7 3.9 0 0 Ii'l ~ 0 0 0 0 0 0 0 0 Actions contained in EOP loss ollnstrumeol EQP for Joss of instrument air Knowledge of the effect that a loss or Of malfunction malfunctioo o off the (SYSTEM) will have on the following:(CFR:

foliowing:(CFR: 41.7/4S.6) 41.7 ' 45.6) 077AK2.02 OnAK2.0 2 Generator Voltage and Electric Grid GOd 3.1 3.1 3.3 0 ~

O  !;;] 0 0 0 0 0 0 0 0 0 Breakers, relays Breakers.

Disturbances DisbJrbances I, 6 Knowledge Knov.1edge of electrical electriCal power supplies to the foIlowing:(CFR:

foliowing:(CFR: 41 41.7}

.7)

WE04EA1.1 WE04EA1 .1 LOCA Outside Containment 1 3 4.040 4.0 4.0 0 0 0 0 0 0 Ii'lD 0000DD ~ 0 ODD 0 0 0 Components and functions 01 of control and safety systems, including instrumentation.

Including instrumentation, signals.

signals, in interlocks, failure teriocks . Failure Ability to predict and/or Abnily aod/or monitor changes in modes and automatic and mllnual manual features features..

parameters associated with operating the (SYSTEM) controls conlrols including:(CFR:

includlng:(CFR: 41.SI 41 .5/

4S.S) 45.5)

WEOSEA2.1 WE05EA2 .1 Inadequate Heat InadeQuate Transfer Heal Tra Secondary Heal nsfer - Loss of Heat Sink /4 I4 3.4 4.4 0 0 0 0 0 0 0 Ii'l ODOOODO ~ ODD0 0 0 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Ability to 10 (a) predict the impacts of 01 the following on the!he (SYSTEM) and (b) based on those predictions, predictions, use procedures procedlJ'l'8S to10 correct, control, correct. control. Ofor mitigate the consequences of those abnormal COll5equences operation:(CFR:

operalio<l:(CFR: 41 41.S

.5/( 43.S

<1 3.5'( 4S.3

<15,3/14S.13) 45_13)

~ P""f3 P.",..f3 4/3/200B 4/312008

"--..-/ \...J ~

ES401 , REV ES-401, REV9 9 T1G2 PWR EXAMINATION OUTLINE ES-401 -2 FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR IR K1 Kl K2 K3 K4 K5 KG K6 A1 A 1 A2 A3 A4 G TOPIC:

RO SRO 001AK1 .16 001AK1.16 Continuous Rod Withdrawal I 1 ,3 ' .4 02J 3.4 ~ 0 DDDDDDDDDD 0 0 0 0 0 0 0 0 0 Definition and <lpplication application of power defect Knowledge Kno ...... edge of the physical connections and/or cause-effect relationships betweefl between (SYSTEM) and the thl! following:(CFR: 41 .2 to 41.9 (45.7 to 45.8) 41.9/45.7 024AK2.01 024AK2 .01 Bora60n (I 1 Emergency Boration 2.7 2.7 27 2.7 0 ~ 02J 0 0 0 0 0 0 0 0 0 Valves electrical power suppl1es Knowledge of electrteal supplies to the following:(CFR:

foIlowing:jCFR: 41.7) 41 .7) 033AG2.4.11 Loss of Intermediate Intermedia!1! Range Nil NI/77 4.04.2 4.0 4.2 0DDDDDDDDDD 0 0 0 0 0 0 0 0 0 ~ 02J Knowledge of abnormal

<lboOl'lTlal condition prOCl:!dures.

procedures.

This is a Generic, Genetic, no sstemtem sstatement tatement is associated.

associated.

051AA1.04 051AA 1.04 Loss of Condenser Vacuum (/ 4 2.52.5 2.5 2.5 DDDDDDIi'IDDDD 0 0 0 0 0 0 ~ 0 0 0 0 position Rod poSition Ability to predict andlor andfor monitor monilOt changes in parameters associated associa ted with operating Opel"ating the controls including:(CFR:

(SYSTEM) tXIntroiS Including:(CFR: 41.51 41.5/

45.5) 061AK3.02 Ala rm s 1 ARM System Alarms 177 '.4 3.4 ,3.6.* DD 0 0 Ii' ~I DDDDDDDD 0 0 0 0 0 0 0 0 Guidance contained in alarm<llann response for ARM system Knowledge Kno\IAedge of the ltIe effect that thai a loss or malfunction of the (SYSTEM) will win have on the foliowing:(CFR: 41.7/45.6)

!tie foUowing:(CFR: 4 1.7/45.6) 068AA2.0Z 068AA2.02 Room Evac.

Control Room Evac.I18B '.7 4.2 0 0 0 0 0 0 0 ~

3.7 4.2 Ii'I 0 0 0 Local ftow Loca l boric acid flow Ability to (a) predict the impacts o AbIlity off the following on the (SYSTEM) and (b) (b ) based on those predictions, use procedures proce<lures to correct, correct , control, or m mitigate itiga te the consequences of those abnormal operation:(CFR:

operation:(CFR 41.5 I 43.5 I 4 41.5143.51 45.3 5.31I 45.13)

~

4/312008 4/3/2008 P""f2

\ ---/ \......./ -

--J

ES-401, ES-401 , REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K1 K2 K3 K4 K5 K6 A1 At A2 A3 A4 G TOPIC; TOPIC:

RO SRO 074EK3.03 Inao. Core Coolirtg/4 Inad. Cooling I 4 3.43.8 3.4 DD 3.8 0 0 ~ Ii?I 0DDDDDDDD 0 0 0 0 0 0 0 Placing the plant phmt in In hot standby status Knowledge of the effect !hal KnoYAedge that a loss or Of malfunction of the (SYSTEM) will have on 41 .7 145.6) foiloWing:(CFR: 41.7/45.6) the foliowing:(CFR:

WE01EK1 .2 WE01EK1.2 Rediagnosis 13

/3 3.4 4 ~DDDDOODDDD Ii?I DDDDDDDDDD Normal, abnormal and emergency operating procedures Normal, pnx;edUfes

. associated with (Reactor Trip or Safety InJection Injection 1 Kno ..... edge of KnoWledge ol the lhe physical connections c:.onnections Rediagnosis Rediagnosis).).

andlor cause-effect relationships between 8OOlor ca.use-effed (SYSTEM)

(SYSTEM ) and the Ihe foliowing:(CFR:

foIlowing:(CFR: 41.2 toID 41 .9/45.7 to 45.8) 41.9/45.7 we03EG2.4.21 LOCA Cooldown - Depress. I 4 4.04.6 4.0 DDD 4.6 0 0 0 0D DDDDDD 0 0 0 0 0 0 ~ I!Il Knowledge Knowtedge of the parameters and logic used to assess the status of safety functions fuoctions This is a Generic, no stem statemen statementt is associated.

associated.

P",'2 4 P"~ 2 41312008 4/3/2008

.../

ES-401,, REV 9 ES-401 T2Gl T2G1 PWR EXAMINATION OUTLINE FORM ESa401 -2 ES-401-2 KA NAME I/ SAFETY FUNCTION: IR IR Kl K2 K3 K4 K5 K6 AI K1 A1 A2 A3 A4 G TOPIC:

RO SAO SRO 003G2.1.7 Reactor Coolant Pump 44.4

.4 4.7 0 0 0 [J 0 0fJ 0 0 0 0 0 621 ~ Ability 10 to evaluate plant performance and make judgments based on operating operational Judgments This is a Generic, no stem statement is characteristics, reaC10f behavior and instrumenl characteristics, reactor instrument associated. interpretation .

interpretation.

004A3.15 004A3. 15 Chemical and Volume Control 3.53.6 3.5 3.6 0 0 0 0 0 0 0 0 0 [J 0 0 0 00 0 62100

~ 0 0 pressure and temperature PZR Pf8SSl,II8 monitor automatic operations of Ability to mooi(Or the (SYSTEM) inCludiog:(CFA including:(CFR:: 41 41.7/45.5)

.7 / 45.5) oo.

- K2~05 004K2.05---'; CChemical h",",,

=iCalandVolumeConlrol-----O:

and Volume Control 2.7 2.7 2.=-.---:OO~

2.9 0 0~ iI

"'-'O~O=O~"O~O'-"[l 0 0 0 0 0 [l"--'0O~O~O=C---CMO=V'C-------------

0 0 MOVs Knowledge 01 electrical power supplies to of eJeclrical the IOllowing:(CFR: .. , .7) foliowing:(CFR: 41.7)

OO5K5".",'--'

005K5.02 '; , HHeat R"':,"""-","'

Residual '~..:;'OR;;: '~ =';;;'-----,3;:

Removal . 4'-c3" 3.4 . 5,---ro;-ro 3.5 DOD "'o 0 F-lI ~ [J 0 O'O""O"'O""-"O"--'

0 0 0 0 0 N "'= tor Need adequate Subcool for adequate "

subcooling Knowledge of \tie KnoWledge the opetatlona operationall lmp/lcations implications tollOYling concepts as they apply to the following of !he (SYSTEM):(CFR:

the (SYST EM):(CFA: 41.5/45.7) 0lJ 0 0 0- - -Pump - ampera ==:-:--- -start,

- Mmlal

- - - _... _------------------_._._---_.-C::=::7.:'~-. ._--------_._-

006A1.09 006Al .09 Emergency Core Cooling 2.8 3.2 o0 0 0 0[J 0 0 ~ amperage, ge. including slart, nonnal and locked Ability to predict and/or monitor changes in parameters associated with operating !he the controls incIuding:(CFR:

(SYSTEM) cootrols including:(CFR: 41.5/ 41.5 /

45.5) .

- - _ .._------_ . ._ - - - - _ ._----...,.-:=---

007A2.03'- D p",,=,,::m",,:::,".Relief/Quench - - - ' --

.9 0 0 0 0 0 0 0 007A2.03 Pressurizer Ro.~ill~;:;II;ra"

",:;:O:::h C ;;-7 T:,"=k---'3" Tank . 6;--;33.9 3.6 ~

~ 0 0 0 Overpressurizalion of Overpressurization 01 the PZR Ab~ity 10 Ability predict the impacts 01 to (a) predicl of the fo~ on the (SYSTEM) and (b) based following predictions, use procedures to on those predictions.

correct control, correct, control. Of or mitigate the consequences of those abnotma! abnonnal operation:(CFR: 41 .5/43.5' operation:(CFR; .5/43.5/45.3/45_13) 45.3' 45.13)

~

413/2008 ...

P J I I '.5

'~ ~

E$-401, REV 9 ES-401, T2G1 PWR EXAMINATION OUTLINE FORM ES-401 ES-401-2 -2 KA NAME / SAFETY FUNCTION: IR Kl K1 K2 K3 K4 K5 K6 Al A1 A2A2. A3 A4 G TOPIC, TOPIC:

RO SRO SAO OOSA1.03 OO8AI.03 Component Cooling Water 2.7 2.7 2.9 2.9 0ODD 0 0 0 0 [] 0 Ii1I ~ 0 0 DOD 0 0 CCW p!"asstJre pressure predict and/or monitor changes In Ability to Pfedlct in parameters associated with operating the (SYSTEM) controls 1nc1uding:(CFR:

including:(CFR: 41 41.5/.5 1 45.5)

OTOA2.01~~

010A2.01 PC-fassuriZer Pressure Cont*c-Pressurizer ",,~--~3 Control '"".-3 3.6 0 0 3.3 0 0 [J 0 0 !ill ~ 0 LJ "O"'O=;--

0 0 Heater Heater failur6S:-------

failures Ability to (a) predict the Impacts Abltlly impacts of the following on the (SYSTEM) and (b) based lollo'hing on those predictions, use procedures to correct, control.

COtrect. control, Of or mitigate mHigateltte the consequences consaqU6f"CeS of those abnormal operation:(CFR:

op!Iration:(CFR: 41.5/43.5/45.3/45.13) 41 .5' 43.5 f 45.3 / 45.13)

"'012K4.01

";;;K"4."", --';Rea=ct;:~:OProtection Reactor Protection =---------' 3.7 4.

3.7 4.0 o 0 0 I~i1I"O"O'-;O=;-;OOO'o=;--Trlp

", -'o=;-ro;-rO'-; 0 0 0 0 0 0 0 Trip logic vmen when one channel OOC or in test one Channa. I~:;-'- - - -

Knowtedge Knowledge of (SYSTEM) design tSesign feature(s) feature(s) and or interlock(s) ....nic" which provide for the lor !he following:(CFR:

foilowing:(CFR: 41 41.7)

.7)

=~- --.

012K6.10 012K6. 10 Aeactor Reactor Protection 3.33.5 3.3 3.5 0 o0 0 0 [J 0 00 0 1i1l~ 0 0 0 0 0 0 0 00 0 Permissive circuits Knowledge of the effect sHect that a loss or malfunction of Ihe malfuoclion the following will win have on (SYSTEM):(CFR: 41.7/45.7) the (SYSTEM):(CFA: 41.7 f 45.7)

' - -.. .. - - ---. = -;:------ - - - -

0 0 0-

_ _ _ _ ***** _ _

  • _ _ _ _ * ** _
  • _ _ _ _ . N _ _ _ ** _ * *** _ _ _ _ _ _ _ * *
  • _ _ _ _ _
  • _ _

~--.---- . --

013K6.01 Engineered Safety Features Actuation Engineered Safety Features Actuation 2.7 3.1 2.7 3.1 0DOODO~ODDOD 0 ~ 0 0 0 0 0 Sensors and OOtectors detectors Knowledge of the effect that a loss Of or malfunction 01 maitlrlCtion of the following loIlowing will have on the (SYSTEM):{CFA:

(SYSTEM):(CFR: 41 41.7/45.7)

.7/45.7) 022KI.02 022K1.02 Containment Cooling 3.73.5 3.7 3.5 Ii1I [] [J 0 0 0 0 0 0 0 0

~ OC100000000 SEC/remote monitoring systems Knowledge of the !he physical connections and/or cause-effect relationships between (SYSTEM) and the follo'hing:(CFR:

following:(CFR: 41 41.2.210 to 41.9/45.7 41.9 to 45.S)

/45.71045.8)

~ P~5 4/31200S

./ J -

ES-401, ES-401. REV 9 T2G1 PWR EXAMINATION OUTUNE OUTLINE FORM ES-401-2 ES-401~2 KA NAME I/ SAFElY SAFETY FUNCTION, FUNCTION: IR K1 K2 K3 K4 KS K5 K6 A1 At A2 A3 A4 G TOPIC:

RD RO SAO SRO 022KB,08 022K6.0S Containment ContaifYlloot Cooling 1.92.0 1.9 0 0 0 0 0 0il 2.0 00000 0 0 0 0 0

~ OOOOO Heat exchangers and condensers Knowledge of !he effecllttat the effect that a loss or maltunclion malfunction 01 of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 41 .7 ' 45.7) 026A4.05 CootainmentSpray-----.---S.5 Containment Spray 3.53.5 3.S--tJ 00 0 0 [1 0 0 0 0 0 0 0 0 0 0 0 0il O

= ==.._-_._---

0 ~-O--Coriiainment-sprayresetswitcties------

Containment spray reset switches ----*----

Ability to manually Q9&1'3te operate and/or monitor in the control room:{CFA:

room:(CFR: 41.7 41.7/45.5 145.5 to 45.S) 45.6)

=-----'. _ . _ ._ -

---==----,:- -_. -----_._----- -

039A2.04 Main and Reheat Stearn Steam 3.4 3.7 0 [l

[J 0 0 0 0 0 0 !ill ~ 0 [] 0 [J Malfunctioning steam dump Ability to (a) predict the Impacts Abilily impacts of the following on the (SYSTEM) and (b) based on those predictions, \JS8 use procedures to con9CI. control.

correct, control, or mitigate millgale the consequences 01 of those abnormal 41 .5 / 43.5/45.3/45.13) operalion:(CFA: 41.5/43.5/45.3/45.13) operation:(CFR:

039K5.;;05 039K5.05'-M".  :;;;"~ and Main Reheat S"I and Reheat ..

Steam:;:mO;-- 2.7 2.7 3.1 3.1 COO [ J [] 0 0 Cl Oil

~ [] 0 0 0 0 0[J 0 Bases for 101 RCS cookIoWn cooldown limits Knowledge of the operational implications of the following conceptS concepts as they apply to (SYSTEM):(CFR: 441.5/45.7) the (SYSTEM):(CfR: 1,5/45.7)

,..:;:-;;  : = -- - - - - . -0,--,-;,.--,=,-;= ----- - --- _

059K4.13 Main Feedwater Main 2.9 2.9 LJ 2,9 0 0 0 blI ~ 0 0 0 0 0 0 0 FeedWater Feedwater fill for fOl" SIG loss of RCPs S/G upon bss Knowledge of (SYSTEM) deslg1 design feature(s) and or intertock(s)

Intel1ock(s) which provide for Ihe the foliowing:(CFR: 41 foliowing:(CFA: 41.7)

.7)

- - _.. - - 0= . --- .._-------

061K3.01 061K3.Q1 Auxiliary/Emergency Feed AuxiliarylEmergeocy Feedwater

.....ater 4.4 4.6 4.6 OO 0 [] I!il DOD 0 0 0 0 0

~ OOOOOOOO RCS Knowledge of the that a loss or effect Ihat tfte eHeet malfunction of the (SYSTEM) will have on matfu-w::tion the following:(CFR: 41.7 / 45.6) foliowing:(CFA: 41.7/45.6)

- C C 7 . - -- - - - - ----- -- - - - - .. _ - - - ------ ---_. ._--------._-

061 KS.05 061K505 Auxiliary/Emergency Feedwater 3.6 3.6 3.9 3.9 OO~O0 0 LJ 0 ~ 0 Oil OOOOOO0 0 0 0 0 Relationship betweeo between AFW flOW ACS~hea flow and RCS =I~"""

heat =" 'I~

transfer Knowledge of the !tie operational implications of the folloWing 01 following concepts as they apply to the (SYSTEM):(CFR:

(SVSTEM):(CFR: 41.S / 4S.7) 41.5 145.7) 4 413/2008 41312008  :

PlI'S

--/ V '-...-/' -

ES-401,, REV 9 E5-401 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION.FUNCTION: IR K1 K1 K2 K3 K4 K5 K6 A1 AI A2 A3 A4 G G TOPIC.

TOPIC:

RO AO SRO SAO 062G2.4.46 Electrical Oistribution AC E1ectncaJ Distribution 4.2 4.2 42 0 0 0 0 0 0 0 0 0 0 ~

0000000000 Ability to verify that thai the alarms are consistent with the plant oooditions.

planl conditions.

Generic. no stem statement is This is a Generic, associated.

062G2.4,9 062G2.4.9 AC Electrical Dislribulioo Distribution 3.8 3.' 4.2 00000000000 0 0 0 0 0 0 [J 0 0 ~ Knowledge 01 loW power I1 shutdown implications In of low in (e.g. LOCA accident (e.g. or loss of l OCA Olloss RHR) mitigation 01 AHA)

This is a Generic, Generic. no slemstem statement is strategies.

associated.

063A4.01 DC Electrical Dlstribu'!lon

' O C - - - - - 2.'

Distribution 2.8 3.1 3.1 0 0 0 LJ 0 0 0 0 0Cl Oil ~ 0 Major breakers and control power fuses Ability to manually operate andlor and/or monitor in the control room In room:(CFR: 41 .7/45.5 to

(CFR: 41.7/45.5 45.8)

~~--.::=

064A3.05 Emergency Diesel Generator 2.'

2.8 2.' 0 0 0 0 0 0 0 0 2.9 OOOOOOOO ~ 0 Oo 0 Operation of the goveffiOf Operalloo governor control of frequency and voltage control in parallel operation Ability to monitor automatic opemtions operations of the (SVSTEM)

(SYSTEM) including:(CFR: 41 .7 / 45.5) including:{CFA: 41.7/45.5)

---=--=_ .. .' -...

064K4.10 Eme~y Emergency Diesel Generator 3.5 4.0

-=~~-

0 0 0 ~ 0 0 0[J 0 0[] 0 0 -~~==~~~,~~.~~~~-

Automatic load sequencer: blackout Knowledge 01 feature(s) of (SYSTEM) design faature(s) and Of or interk:lcl\(s) interlock(s) which v.tlich provide for the prO'Jide 101 following:(CFR:

toIlowing:{CFR: 41.7) 41 .1)

=-~ -- --~~~~~~~~~~rc eleas.~:----

073K3.01 073K3.01 Process Radiation Monitoring Monitoring 3.6 4.2 0 0 ~ 0 0 [J 0 [] 0 0 0 [J 0 0 Radioactive effluent 'releases .

Knowledge 01 thai a loss of the effect that toss Of or malfunction 01 mallunctlon of the (SYSTEM) will have on the foIiO'Mng:(CFR:

following:(CFR: 41.7/45.6) 41.7 1 45.6) 076K1.16 Water Service Waler 3..

3.6 3.'

3.8 ~

~ 00 00 00 0[1 [l 0 0 0 O"O""O"'O;-----;;

0 0 [] [] ."S.

ESF, - - - - - - - - - - - - - - -

Knowledge 01 of the physical connections arG'or and/or c3use-effect cause-effect relationships between following:(CFR: 41.2 to (SYSTEM) and the 101i0wing:(CFR:

41 .9 1 45.710 41.9/45.7 to 45.8) 45.8J P1""'5 P~5

~

41312008

'---./ -' ~

ES-401, ES-401 , REV 9 T2Gl T2G1 PWR EXAMINATION OUTLINE ES-401 -2 FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K1 K2 K3 K4 K5 K6 A1 102 A2 A,3 A3 A4 G TOPIC:

RO SRO 078K2.01 Instrument tnslrun enl Air 2.7 2.7 2.9 2.9 0 ., ~ 0 0 0 0 0 0 0 0 0 Instrument aair

'nsbunent ir compressor compreSSOf Knowledge of electrical power supplies 1to0 following:(CFR:: 441.7) the followiog:(CFR 1.7)

.103A3.01 Coolainm6fl1 Containment 3.9 4.2 0 0 3.94.20 0 0 0 0 0 0 [1 00 0 DOli']

0 0il 00 0 0 Containment isolation Ability to monitor automatiC automatic operations of the (SYSTEM) locIuding:(CFR:

including:(CFR: 41.7/45.5) 41.7 /45.5) of 5 Page 5 015 41312008 2:42 PM

~

\...J' \..J

E5-401, REV 9 ES-401, T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 ES-401*2 KA NAME I/ SAFETY FUNCTION: IR Kl K2 K3 K4 KS K1 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 00lA2.07 001A2,Q7 Control Rod Orive Drive 4.1 4.4 4.1 4.4 0 0 0 0 0 0 0 ~ 0 0 0 Effect of reactor trip on primary aJ'ld parameters and systems and SOOOIldalY secondary Ability to (a) predict tnathe impacts Impacts of the following on the (SYSTEM) and (b) based on those predictions. use procedures to correct. COfltrol, correct, control, Of or mitigate the consequences of those abnormal operalion:(CFR: 41 .5/

operation:(CFR: 43.5/45.3 f 45 .13)

.5/43.5/45.3/45.13) 002A4.02 Reactor Coolant 4~

4.3 4.5 4 .5 0 0 0 0 0 0 0 0 0 "~ 0 Indications necessary to verify natural circulation from level, !I(JY,I appropriate level, flow and temperature indications OInd and Ability to manually operate andlOl' and/or monitor valve positions upon loss of forced circtJlatlon circulation in the control room:(CFR: 41 .7 /45. 5 to 41.7/45.5 45.S) 45.S}

011K6.05 011K6.0S Pressurizer Level Control 3.1 3.7 3.7 0 0 0 0 0 " ~ 0 0 0 DOD 0 0 Function of PZR level gauges as postaccident monitors Knowledge of the effect that a loss or malfunction of the following will have on malfunctlon the (SYSTEM):(CFR: 41.7/45.7) 41 .7' 45.7) 0161<5.01 016K5.01 Non-nudear Non-nuclear InSlrumentation Instrumentation 2.7 2.8 2.7 2.8 0 0 0 0 111 ~ 0 0 0 0 0 0 control and protection circuits Separation of conltol Knowledge of the operational implicatiol'l5 Knowtedge implications of the following concepts as they apply to the (SYSTEM):(CFR tI'IEt (SYSTEM):(CFR: 41 .5/45.7)

.51 45.7) 027G2.4.31 027G2.4.31 Containment Iodine Removal Cootainmeot 4.2 4.1 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of annunciators alanns.

alarms, indications 01' or response procedures This Is is a Genenc, Generic, no stem statement is associated.

02SK3.01 0281(3.01 Hydrogen Recombiner Recombineraodand Purge 3.3 3.3 4.0 0 0 111 4.0 00 0 0 0 0 0 0 0 0

~ 00000000 Hydrogen concentration in containment Coo,",i Control effect that a loss or Knowledge of the effecltOat malfunction of the (SYSTEM) will have on malfurldion the foliowing:(CFR:

lolfowing;(CFR: 41 .7/45.6)

P~2 P~.2 4I3I2OOa 4131200S

~

\...J

ES-401, REV 9 ES-401. T2G2 PWR EXAMINATION OUTLINE .FORM ES-401-2 ES-401*2 KA NAME I SAFElY SAFETY FUNCTION FUNCTION:: IR Kl K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC ;

TOPIC:

RO SRO 03SA1.01 Q35A1.01 Steam Sl eam Generator 33.6

.* 3.6 3.8 0 0 0 0 0 0 ~ OOOO OOOOOO 0 0 0 0 SlG wide and narrow range level during startup.

S/G shutdown and normal nonnal operations Ability to predict and/or monitor changes in parameters associated with operating 1he the (SYSTEM) controls lllCludlng:(CFR:

including:(CFR: 41 .5 f 41.S/

45.5) 4S.5) 072K1.0S 072Kl .0S Area Radiation Monitoring 2.6 2.8 2.9 0 0 0 0 0 0 0 0 0 0

~ OOOOOOOOOO MRSS KnOlliledge Knowledge of the physical connections and/or eause-effec:l cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 foIlowIl"9:(CFR: 41 .2 to 41.9/4S.7 41 45_8)

.9/45.7 to 4S.8) 07SK4.01 075K4.01 Circulating Water 2.5 2.S 2.'

2.8 0 0 0 ~ OOOOOOO OOO 0 0 0 0 0 0 0 Heat sink KOO'Ntedge of (SYSTEM) design feature(s)

Knowledge and or InleOock(s) interlock(s) which provide for the foIlowing=(CFR: 41 following:(CFR: .7) 41.7) 086A3.01 FlreProtectioo Fire Protection 2.

2.9 3.3 0 0 0 0 0 0 0 0 ~ OO OOOOOOOO 0 0 mechaoisms of fire ~ter Starting mechanisms water pumps pUmps Ability to monitor automatic operations of the thl! (SYSTEM) including:(CFR:

induding:(CFR: 41 .7.7/4S.5) f 45.5) 41312008  :

~

P"c2

\...J

ES-401, REV 9 ES401, T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 KS K5 K6 AI A1 A2 A3 A4 G TOPIC:

RO SRO 02.1 G2.1 .11

.17 Conduct of operations 3.9 4.0 0 0 0 0 0 0 0 0 0 0 011 3.9 '.0 ~ Ability to make accurate. clear and concise ..verbal erosl reports.

This is a Generic, Generic. no stem statement is slem stalem6flt assOCiated.

associated.

G2.1.18 G2.1 .18 operations Conduct of opemtions 3.63.8 3.6 3.8 DDDDDDDDDD 0 0 0 0 0 0 0 0 0 0 Ii'I ~ Ability to make accurate. clear and concise logs.

logs, records.

records, status boards and repo!1s.

reports.

a Generic.

This is II Generic, no stem statement is associated.

G2.1.43 G2.1 .43 Conduct of operations Cooduct ,.,

4.1 '.3 4.3 0 0 0 0 0 0 0 0 0 0 Ii'I ~ Ability to use procedures 10to determine detemllne the effects on reactivity of Dlant plant changes This Is is II a Generic. no stem statement is associated.

02.2.14 G2.2.14 Equipment Control 3.9 3.9 '.6 4.6 0 0 0 0 0 0 0 0 0 0 Ii'I DDDDDDDDDD ~ Knowledge of Knowtedge 01 the process for conlrolling controlling equipment eQuipment configuration or status This is II a Generic. no stem statement statemen t is associated.

02.2.37 G2.2.37 Equipment Control 3.6 '4.6 3.6 .60 0 000000000011 0 0 0 0 0 0 0 0 0 ~ Ability to determine operability and/or availability of safety related retated equipment This is a Generic. no stern stem sstatement tatement is associated.

G2.3.11 Radiation Control 3.8 3.8 <.3 4.3 0 0 0 0 0 0 0 0 0 0 Ii'I DDDDDDDDDD ~ Ability to control radiation releases.

releases .

This is a Generic, Generic. no stem statement is associated.

G2.3.S G2.3.5 Radiation Control 2.9 2.9 2.9 2.9 0 0 0 0 0 0 0 0 0 0 Ii'I ~ Ability Abltity to use radiation monitoring systems Generic. no stem This is a Generic, statement is slem Slalemenl associaled~

associated.

P,.,..2 4131'2008 4/3/2008

~

~

ES-401, REV 9 ES-4ll1, T3 PWR EXAMINATION OUTLINE FORM ES-4ll1-2 ES-401-2 KA NAME I SAFETY FUNCTION FUNCTION:: IR K1 K2 K3 K4 K5 KS KB K6 A1 A2 A3 A~ A4 G TOPIC:

RO SRO G2.3.7 Radiation Control 3.53* 0 0 0 0 0 0 0 0 0 0 ~

3.5 3.B 00000000001i21 Ability to comply with radiation work woOl permit penni! requirements during' normal or abnormal conditions during This is a Generic.

ThiS Generic, no stem statement is associated.

G2.4.3O G2A.30 Emergency Procedures/Plans 2.7 4.1 4.1 0 0 0 0 0 0 0 0 0 0 Ii2I ~ Knowledge of events related to system operations/status internal orglnizaHoos that must be reported to intemal orginizations or ootside outside This is a Generic, /10 no stem statement is agencies.

associated.

G2.4.32 Emergency Em ProceduresIPlans ergency ProcedureslPlans 3.64.0 3.B 0 0 0 0 0 0 0 0 0 0 1i' 4.0 0000000000 ~J Knowledge of operator response 10 to loss of all annunciators.

ann uncialars.

This Is is a Genetic, Generic, no stem statement is associated.

asSOCiated.

4/312008 4/3/2008 P-.2

\..J \J

ES-401,, REV 9 ES-401 SRO T1G1 PWR EXAMINATION OUTLINE ES-401-2 FORM ES-401 -2 KA SAFETY FUNCTION NAME I SAFElY FUNCTION:: IR K1 Kl K2 K3 K4 K5 KS K6 A1 Al A2At. A3 A4 G TOPIC:

RO SRO 008AG2.4.6 00SAG2.4.6 Pressurizer Vapor Space Accidentl Preuurizer Accident! 3 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~ Knowfedge symptom based EOP mitigation strategies.

Knowtedge strategies.

This is a Generic, Geoefic, no stem statement is Is associated.

asSOCiated.

015AA2.10 015AA2. 10 RCP Malfunctions 1 Rep I4 3.7 3.7 0 0 0 0 0 0 0 ~ Ii1I 0 0 0 When to secure Reps RCPs on loss of cooling or seal injection oooIlng or Ability to (a) predict Abilily predictltlethe impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct. control, or mitigate the correct, consequences of those abnormal coosequences abnonnal operation:(CFR: 41.5/43.5/45.3/45.13) operalioo:(CFR: 41 .5 / 43.5 / 45.3 /45. 13) 026AG2.4.34 Loss of Component Cooling Water 18 loss 18 4.2 4.1 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowfedge of Knowledge of RO tasks performed outside the main taslFW AFW pumps and regulallng regulating valves Ability to 10 (a) predict the impacts of 01 the on the follOwing on following !he (SYSTEM) and (b) based on those Ihose predictions.

predictions, use procedures procedl.1l'es to correct. control, or mitigate m itigate the of those abnormal consequences ollhose operation:(CFR: 41 .5/43.5/45.3/45.13)

.5 , 43.5 , 45.J /45 .13) 062AG2.2.36 062AGZ.2.36 Loss of Nuclear Svc Water 1 f4

" 3.1 4.2 42 0 0 0 0 0 0 0 0 0 0 Ii1I ~ the effect of maintenance activities, Ability to analyze Ihe activities.

the stalus sources. on Ihe such as degraded power sources, status of This ThiS is Is a Generic. no no' stem statement is operations limiting conditions of ope!CItions associated.

WE04EA2.1 LOCA Outside Containment OJolainment 1 f3J 3.4 4.3 0OOOODOO 0 0 0 0 0 0 ~ OOO0 0 0 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

opera~OI"Is.

Ability to (a) predict the Impacts impacts of the following on the tfle (SYSTEM) and (b) based on those predictions, predic~ons, use procedures to correct, correct. control, control . or mitigate the conseQuences of those abnormal consequences operation:(CFR: 41 .5 J/ 43.51 45.3 f 45.13) 4J .5/45.3/45.1J)

P~1 4/3/2008 4/312008

~

~

ES-401, REV 9 ES-401. SRO T1G2 PWR EXAMINATION OUTLINE OUTliNE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 001AA2.03 001AA2.0J Continuous Rod Withdrawal/1 Withdrawal / 1 4.54.8 0 0 0 0 0 0 0 Ii[J 4.5 4.8 DDDDDDD ~ DDD0 0 0 Proper actions to be takef1 taken if automatic sasafety fety functions have nol not takafl taken place Ability to 10 (a)

(3) predict the impacts of01 the following on the (SYSTEM) and aod (b) based predictions, use procedures to on those predictions, correct, correct, control, cootrol , or mitigate the cons equences of those abnormal consequences abnofTTlal operation:(CFR: 41 .5/43.5/45.3/45.13) operatloo:(CFR: .5/43.5 f 45.3/45.13) 003AA2.03 Dropped Control Rod 11 3.6 3.6 3.8 0 0 0 0 0 0 0 3.8 DDDDDDD ~ DDD0 0 0 Dropped rod, rod , using in-core/ex-core instrumentation in-in-core/ex-c:;orQ inslnlrnentation in*

or loop temperature measurements core 0(

Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictiom.

predictions. use procedures to correct, control, control, or mitigate the consequences of those abnormal abnolmal operation:(CFR: 4 operatiort:{CFR: 41.5/43.5/45.3/45.13) 1.5/43.5/45.3/45.13) 037AG2.4.8 037AG2.4.B Steam GaneratorTube Generator Tube Leak 13 3.84.5 3.8 0 0 0 0 0 0 0 0 0 0 ~

4.5 0000000000 " Knowledge of how aboomlal KnO\ldedge abnormal opeIiIting procedures are operating procedUteS used in conjunction wi withth EOPs.

This is a Generic, Generic. no stem statement is associated.

aSSOCiated.

we08EG2.2.25 RCS Overcooling -. PTS 1 weOSEG22.2S 144 3.2242

3. 4.2 0 0 0 0 0 0 0 0 0 0 .,

0000000000 ~ Knowledge of the bases in Technical Specifications for limiting conditions for fof operations and safety limits.

This Thi$1sis a Generic, no stem 8 Generic. $tam statement is 1$

associated.

associaled.

P~1 4/3/2008

~

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE ES-401-2 FORM ES-401*2 KA NAME I SAFETY FUNCTION:

SAFE1Y FUNCTION, IR IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 013G2.2.42 Engineered Safety Features Actuation 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to recognize system parameten; Abi!ity parameters that alare e entry-conditions fOf level coodiUoos for Techn Technical SpeCifications ical Specifications This is a Generic, Generic, no nQ stem statement is associated.

associa ted.

062G2.4.6 AC Electrical Distribution Oisllibution 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge symPfQm Kna'Madge symptom based EOP mitigation strategies.

stra tegies.

This is a Generic, no 00 stem statement is Is associated.

assoclated.

064A2.13 Emergency Diesel Generator Genelator 2.'

2.6 2.S 0 0 0 0 0 0 0 0~ 000 2.8 0000000 0 0 0 auxiliary feeder bus (ED/G sub Consequences of opening au..aflary supply)

Atrility Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, predictioos, use procedures proeecIlK8S to correct, control, control , or mitigate the consequences of those abnormal operation:{CFR: 41.5/43.5/45.3 opera.tJoo:(CFR: 41.5/43.5 /4 5.3 145.13)

/ 45.13) 073G2.4.S 073G2.4.8 Process Radiation Radlatioo Monitoring "4.5 3.S 0 0 0 0 0 0 0 0 0 0 ~

4.5 0000000000 0 Knowledge of how abnOfTllal KnO'Medge abnormal operating procedures are used in conjunction with EOPs.

This is a Generic, Generic, no stem statement is associated.

07SA2.01 078A2.01 Instrument Air 2.4 2.9 2.4 2.9 0 0 0 0 0 0 0 01J ~ 0 0 0 Air dryer dryer and filter malfunctions Ability to (a) predict the impacts of the following fQl\Qwing on the (SYSTE (SYSTEM) M) and (b) based on those predictions, use procedures to correct, control c:orrec:t, control,, or Of mitigate the consequences of those abnormal operation:(CFR: 41 .5 143.5 41.5 / 43.5/45.3/45.13) 1 45.3 145.13)

P~1 4/3/200S _.

4/312008

,'---'"~

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 ES-40' *2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K1 TOPIC:

RO SRO 001G2. 4.34 001G2.4.34 Control Rod Drive 4.2 4.1 4.1 0 0 D DOD0 0 0 0 DOD 0 0 0 0 RI ~ Knowledge of RO tasks performed perfonned outside the main control during CQfllroi room d uring an emergency and the resultant Ihe resullant This is a Generic.

Generic, no stem statement is operaUonal effects operational aSSOCiated.

associated.

034A2.03 Fuel Handling Haodlillg Equipm Equipment ent 3.3 4.0 D 3.34.0 D D DOD 0 ~

DDDDDDD Rl DOD DDD Mispositioned fuel element elem en t Ability to (a) predict predIct the Impacts impacts of the following on the (SYSTEM)

(SVSTEM) and (b) based on Ofl those predictions.

predictions, use procedures procedUfes to correct. control.

correct, con trol, or mitigate the consequences of those abnomlat abnonnal operation:(CFR: 41 operation:{CfR: .51 43.51 45.3/ 45. 13) 41.5/43.5/45.3/45.13) 068A2.04 Liquid Uqukl Radwaste 3.3 3.3 3.3 0 DOD DOD ~

3.3DDDDDDD IiII 0 DDD 0 0 FaH ure of automatic Failure isolation autom atic Isolation Ability to (a)

(a ) predict the impacts 01 of the following on the (SYSTEM) and (b) based on those predictions, Ofl predictions. use procedures to correct. control.

correct, control, or mitigate the consequences of those abnormal abnonnal operation:(CFR: 41 opef8tion:(CFR: 41.51 43.5145.3

.5/43 145.13)

.5/45.3/45.13)

P~. 1 41312008

~

~

ES-401 ES-401,, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME NAM E If SAFETY FUNCTION: IR K1 K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 02.1 ,27 G2.1.27 Conduct of operations 3.9 4 oooooooooo oooooooooo~ ~ Knowledge of system purpose and or ruoclion function .,

This is a Generic.

Generic, no slem stem statement is associated.

G2.1.34 G2.1 .34 Conduct of operations '.7 2.7 3.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of primary and secondary chem chemistry limits istry ijmits This Is is a Generic, no stem sta tement is statement associated.

G2.2.38 Equipment Control 3.6 4.5 0 0 0 0 0 0 0 0 0 0 OOOOOOOOOO~ ~ Knowledge of Kncw.iOOge of conditions and limitations in the facility license.

no stem statement is This is 8a Generic, 00 asSOCiated.

associated.

G2.3.13 Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~

OOOOOOOOOO KnO'Nl edge of radiological safety procedures pertaining to Knowledge operator duties licensed operator This is a Generic, no stem statement is associated.

02.3,14 G2.3.14 Radiation Cootrol Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~

OOOOOOOOOO~ Knowledge of radiation orcootaminaUon or contamination hazards that arise dorirlg may anse during nOllTlal, normal, abnormal.

abnormal, or emergency This is a Generic, no stem statement is conditions or activities associated.

G2.4.20 Emergency Procedures/Plans 3.8 4.3 0OOOOOOOOOO 0 0 0 0 0 0 0 0 0 ~ Knowledge of operational implications 01 of EOP wa warnings, rnings.

cautions and notes.

This is a Generic, no stem statement is associated.

associated.

G2.4.41 Emergency Procedures/Plans Proce(lures!Plans 2.9

'.9 4.6 0 0 0 0 0 0 0 0 0 0 ~

OOOOOOOOOO Knowledge of the emergency action level thresholds and classifications.

This is a Generic.

Generic, 00 no stem statement is associated.

Page 1 of 1

~20082i 'I L"

413121)Oa

~

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

/J)/iA.t-v",rr-Facility: VCSUMMER VC SUMMER Date of Examination:

Examination: 2009 NRC

((

Examination Level (circle one):

one) : ~/SRO I!!QII SRO Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code*

RO/SRO Common Conduct of Operations P,M P, M Calculate the Maximum Allowable Head Venting Time (A1-1) in accordance with EOP-18.2,EOP-1S.2, RESPONSE TO VOIDS IN REACTOR VESSEL, VESSEL, Attachment 2 G2.1.25 (3.9/4.2): Ability to interpret reference materials, materials, such as graphs, curves, tables, tables, etc.

etc.

Perform a Shutdown Margin Verification for intended Conduct of Operations M plant conditions in accordance with GOP-DOS, GOP-005, (A1-2)

(A 1-2) REACTOR SHUTDOWN FROM STARTUP TO HOT STANDBY (MODE 2 TO MODE 3), Step 3.7.b.

G2.1.23 (4 (4.3/4.4):

.3/4.4) ; Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Perform the surveillance test procedure and complete Equipment Control (A2) N the associated documentation for the Pressurizer PORV motor operated block valves.

( G2.2.12 (3.7/4.1): Knowledge of surveillance procedures.

RO/SRO Common Radiation Control (A3) M Determine the dose limit and apply the RWP dose limits to calculate stay time for performance of a task involving whole body exposure. exposure.

G2.3.7 (3.513.6):

(3.5/3.6): Ability to comply with radiation work permit requirements during normal or abnormal conditions ..

Emergency Plan Category not selected for RO 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 required..

NUREG-1021 , Revision 9 NUREG-1021,

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

((

  • Type Codes & Criteria:

"Type Criteria: (C)ontrol room (D)irect from bank (oS ,; for SROs &

ROs; :s;

(:s; 3 for ROs; & RO retakes)

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

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

(S)imulator JPM

SUMMARY

STATEMENTS CONDUCT OF OPERATIONS (A1-1): (A1*1): Given a set of conditions, conditions, calculate the Maximum Allowable Head Venting Time in accordance with EOP*1B.2, EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2. Modify 2005 NRC JPM A1-2 A 1-2 by changing the Reactor Building initial conditions. RO/SRO Common JPM.

CONDUCT OF OPERATIONS (A1*2): (A1-2): Perform Perfonm a Shutdown Margin Verification for intended plant conditions in accordance with GOP-005, GOP*OOS, REACTOR SHUTDOWN FROM STARTUP TO HOT STANDBY (MODE 2 TO MODE 3), Step 3.7.b. The applicant will be directed from GOP- GOP*

perform STP-134.001, 005 to perfonm STP*134.001 , SHUTDOWN MARGIN VERIFICATION, to determine detenmine the required boron concentration for the intended conditions (Mode 5). Modify a Bank JPM by changing core

( burnup, existing boron concentration, burnup. ~ untrippable~ rod.

concentration , and adding an "untrippable" rod . In addition, addition, STP-134.001 has undergone significant revisions since the Bank JPM being modified was last revised.

EQUIPMENT CONTROL (A2): Perform the surveillance test procedure and complete the associated documentation for the Pressurizer PORV motor operated block valves. The perfonm STP-127.001, PRESSURIZER BLOCK VALVE OPERABILITY TEST, applicant will perform TEST, on the simulator; stroke testing the three PZR PORV Block Valves with a malfunction placing one valve outside of the specified acceptance criteria.

criteria . New JPM. JPM.

RADIATION CONTROL (A3): Determine the stay time for performance perfonmance of a task involving whole body exposure to ensure compliance with RWP requirements. requirements. Identified as a modified rateldose calculation JPM's in the facility bank (JPA-007).

JPM because there are dose rate/dose (JPA*007).

RO/SRO ROISRO Common JPM. JPM.

NUREG-1021, NUREG*1021 , Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: VCSUMMER Date of Examination: 2009 NRC

((

Examination Level (circle one): RO /~

RO/~ Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code*

Code*

RO/SRO Common Conduct of Operations P,M P, M Calculate the Maximum Allowable Head Venting Time (A 1-1)

(A1-1) in accordance with EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL, VESSEL, Attachment 2 G2.

G2.1.25 1.25 (3.9/4.2): Ability to interpret reference materials, such as araohs, curves, tables, etc.

graphs, Evaluate the impact of a change in the plant electrical Conduct of Operations N lineup (close ALT Feed BRKR to ESF Bus 1DA 1DA or (A1-2) 1DB) on the TS LCO and complete SAP-205, Attachment 1 - REMOVAL AND RESTORATION CHECKSHEET (3.613.8): Ability to make accurate, dear, G2.1.18 (3.6/3.8): clear, and concise loas logs, records records, status boards boards, and reoorts.

reports.

Evaluate the completed surveillance test procedure for Equipment Control (A2) M a safety related system G2.2.12 (3.7/4.1):

(3.7/4.1): Knowledge of surveillance procedures.

(( Radiation Control (A3)

RO/SRO Common M Determine the dose limit and apply the RWP dose limits to calculate stay time for performance of a task involving whole body exposure.

(3.513.6): Ability to comply with radiation work permit G2.3.7 (3.5/3.6):

requirements during normal or abnormal conditions ..

Given a set of conditions, conditions, determine the EAL and Emergency Plan (A4) M complete the Emergency Notification Form within the required time (2.9/4.6) : Knowledge of the emergency action level G2.4.41 (2.9/4.6):

thresholds and classifications.

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 required..

-Type Codes & Criteria:

  • Type Criteria: (C)ontrol room (5 3 for ROs; 5 (D)irect from bank (:$  :$ for SROs & RO retakes)

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

(P)revious 2 exams (:$ (:5 1; randomly selected)

(S)imulator

((

NUREG-1021 , Revision 9

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

((

JPM

SUMMARY

STATEMENTS CONDUCT OF OPERATIONS (A1-1): Given a set of conditions,cond"ions , calculate the Maximum Allowable Head Venting Time in accordance with EOP-18.2, EOP-1S.2, RESPONSE TO VOIDS IN VESSEL, Attachment 2.

REACTOR VESSEL, 2. Modify 2005 NRC JPM A1-2A 1-2 by changing the Reactor Building initial conditions.

conditions. RO/SRO Common JPM.

CONDUCT OF OPERATIONS (A1-2): Evaluate the impact of a change in the plant electrical lineup (close alternate feed breaker to ESF Bus 1DA or 1DB in Mode 1) on the Technical Specification LCO and complete SAP-205, SAP-205, STATUS CONTROL AND REMOVAL AND RESTORATION, Attachment 1 - REMOVAL AND RESTORATION CHECKSHEET. The RESTORATION, applicant will be required to determine the Technical Specification Action Statements that must be entered and then complete the status tracking document. New JPM.

EQUIPMENT CONTROL (A2): Evaluate the completed surveillance test procedure for a safety related system.

system . The applicant will be directed to review (for approval) a completed STP-205.004, RHR PUMP AND VALVE OPERABILITY TEST, 205.004, TEST, containing three significant errors.

errors.

Modify a Bank JPM by changing all errors.

RADIATION CONTROL (A3): Determine the stay time for performance of a task involving whole body exposure to ensure compliance with RWP requirements. Identified as a modified rateldose calculation JPM's in the facility bank (JPA-007).

JPM because there are dose rate/dose

( RO/SRO Common JPM.

EMERGENCY PLAN (A4): Given a set of conditions, conditions, determine the EAL and complete the Emergency Notification Form within the required time.

time. The applicant will be given a set of conditions requiring declaration of a GENERAL EMERGENCY for an ATWS ATWS Event.

(

NUREG-1021 , Revision 9

-301 ES-301 Room/In-Plant Systems Control Room/ln-Plan ems Outline -301 -2 ES-301-2 R

ES Form ES 0/JIUJ, Facility: VC Summer Date of Examination: 2009 Exam Level (circle one): ROII SRO(I)

RO Operating Test No.:

No.: NRC SystemsC (8 for RO; 7 for SRO-I)

Control Room Systems@

System I/ JPM TiUe Title Type Code" Code* Safety Function

a. APE 001 [JPSF-036]

Respond to Continuous Rod Withdrawal (AOP-403.3) M,A,S M, A, S 1

b. System 006 [JPS-058]

Raise ECCS Accumulator level (SOP-112) D,S D, S 2

  • System 010 [JPSF-150]

Depressurize the ReSRCS to Refill the Pressurizer (EOP-2.1) P, D,A,E,S P,D,A,E, S 3

d. APE 025 [JPSF-065]

Establish hot leg injection during loss of RHR at mid-loop A, S, L D,A,S,L D, 4P (AOP-115.5) conditions (AOP-11S.5)

e. System 045 [JPSF-022B]

Respond to Turbine Trip Failure (EOP-1.0)

(EOP-1 .0) M,A,E,S M, A, E, S 4S

f. System 026 [JPSF-019A]

( Manually Initiate Reactor Building Spray (EOP-1 (EOP-1.0)

.0) M, A, E, S M,A,E,S 5

g. System 015 Perform an Intermediate RaAge Rcmge NI Analog Channel Operational N, S N,S 7 Test (STP-l02.003)

(STP-102.003)

h. System 078 Establish Instrument Air to Reactor Building (EOP-3.0) N,A,E,S N, A, E, S 8 Systems@

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

i. System 001 [JPPF-096]

Locally locally Trip the Reactor (EOP-13.0) D, A,E D,A, E 1

j. System 061 [JPP-068]

Reset Turbine Driven Emergency Feed Pump (SOP-211) D, D,RR 4S

k. System 062 Transfer a Vital 120VAC Power Supply - Return of Alternate N 6 Source (SOP-31 (SOP-310)0)

RO Only ROOnly NUREG-1021 , Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

@ in-plant) systems must be different and serve different safety functions; in-All control room (and in*plant)

( plant systems and functions may overlap those tested in the control room room..

    • Type Codes Criteria for RO I/ SRO-I (A)lternate path 4-6 4-6/4-6 / 4-6 [6V [6J

[6y [6]

(C)ontrol room (D)irect from bank (O)irect  ::;

s: 9 f/ s:::; B 8 [5]/ [4J

[5JI [4]

(E)mergency or abnormal in-plant ~ 1 ~ 11 1 /f "2 [4]/ [4J

[4JI [4]

(L)ow-Power  :::~ 1f 1 / :z.~ 1 [1]/ [lJ

[lJI [1]

(N)ew or (M)odified from bank including 1(A)1(A) "2~ 2/

2 / "2

~2 [6]/ [6J

[6JI [6]

(P)revious 2 exams :s::; 31 3/ :s

3 (randomly selected) [1]/ [1]

[lJI [lJ (R)CA "2~ 1 / "2~ 1 [1]/ [1]

[lY[lJ (S)imulator

((

NUREG-1021 , Revision 9 NUREG-l021

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

( VC SUMMER 2009 NRC EXAM JPM

SUMMARY

a. Respond to continuous rod withdrawal in accordance with AOP-403.3, CONTINUOUS a.

CONTROL ROD MOTION.MOTION. The alternate path is that the applicant will respond to a loss of charging flow that will require manual control of FCV-122, Charging Flow Control Valve, to restore PZR level. Modify Bank JPM JPS-036 by adding the procedure steps response .

for evaluating PZR level response.

b.

b. Raise the level in an ECCS Accumulator in accordance with SOP-112, SAFETY INJECTION SYSTEM. The applicant will restore ECCS Accumulator level to within the technical specification band using the system operating procedure. Bank JPM JPS-058.
c. Depressurize the ReS RCS to refill the Pressurizer using a PORV in accordance with EOP* EOP-2.1 2.1,, POST-LOCA COOLDOWN AND DEPRESSURIZATION, Step 8. The alternate path is that the applicant must use a PZR PORV to depressurize because the spray valve for the running RCP fails to open.

open. After depressurizing, depressurizing, the PZR PORV will fail to close closed . Randomly selected from 2007 NRC requiring the respective isolation valve to be closed.

Exam. Bank JPM JPSF-150.

d. Establish hot leg injection during loss of RHR at mid-loop conditions in accordance with AOP-115 .5, LOSS OF RHR WITH THE RCS NOT INTACT (MODES 5 &

AOP-115.5, & 6). The alternate path is that the applicant will respond to degrading plant conditions by aligning RHR injection and establishing flow to the RCS hot legs. legs. Bank JPM JPSF-065.

e.

e. Respond to a turbine trip failure in accordance with EOP-1.0, EOP-1 .0, REACTOR TRIP/SAFETY

( INJECTION ACTUATION.

ACTUATION . The alternate path is that the applicant will be required to trip the turbine using diverse means from the MCB and/or locally. After completing the immediate operator actions for the turbine trip, trip, the applicant will respond to degrading plant conditions that require manual initiation of SI. Modify Bank JPM JPSF-022A by adding a simulator malfunction that leads to a requirement for MANUAL SI actuation.

f.f. Manually initiate reactor building spray in accordance with EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION, ACTUATION , Step 8. The applicant will implement alternate path actions to actuate RB Spray using Train B switches or by manually aligning spray pump suction and header isolation valves. Failure of MVG-3003A, RB Spray Isolation Valve, Valve, to open automatically will require the applicant to manually open the valve to establish Train A Reactor Building Spray flow. Modify Bank JPM JPSF-019 by adding the MVG-3003A failure.

g. Perform an Intermediate Range Analog Channel Operational Test for N35 in accordance
g. Peifonn with STP-102.003. New JPM. JPM. .
h. Establish instrument air to the Reactor Building in accordance with EOP-3.0, FAULTED h.

STEAM GENERATOR ISOLATION,ISOLATION , Step 11.11 . Following a complete loss of instrument air the applicant will be required to start an instrument air compressor and then align instrument air to the Reactor Building. The alternate path requires the applicant to start the Supplemental Air Compressor.

Compressor. New JPM. JPM.

NUREG-1021, NUREG-1021 , Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

i. Locally trip the reactor in accordance with EOP-13.0, RESPONSE TO ABNORMAL

( NUCLEAR POWER GENERATION, ATTACHMENT 1 - TRIPPING THE REACTOR LOCALLY. The alternate path requires the applicant to open the Rod Drive MG Set breakers after attempts to manually open the reactor trip breakers fail. Bank JPM JPPF-096.

096.

j.j. Reset turbine driven emergency feed pump in accordance with SOP-211 SOP-211,, EMERGENCY FEEDWATER SYSTEM. Bank JPM JPP-068.

k. Transfer a vital 120VAC power supply in accordance with SOP-310, 120 VAC k.

INSTRUMENT AND CONTROL SYSTEM. The applicant will complete the steps to restore the alternate source of power to Inverter XIT-5901 in accordance with procedure section IV.AD.

IV.AD. New JPM.

(

NUREG-1021 , Revision 9

Roomlln-Plant Systems Outline Control Room/In-Plant Form ES-301-2 ES-301 Facility: VC Summer

/J RIJ t:-7 lJ 1<'1.1 r--r Date of Examination: 2009

( Level (circle one):

Exam level SRO (U) Operating Test No.: NRC Control Room Systems Systems@ C (8 for RO; RO; 7 for SRO-I:

SRO-I; 2 or 3 for SRO-U)

System 1 I JPM Title Type Code' Code* Safety Function

a. [JPSF-036]

APE 001 (JPSF-036)

Respond to Continuous Rod Withdrawal (AOP-403.3) M,A,S M, A, S 1

d. APE 025 [JPSF-065)

[JPSF-065]

Establish hot leg injection during Jossloss of RHR at mid-loop D,A,E,S, D,A, E, S, L 4P conditions (AOP-11S.S)

(AOP-115.5)

f. System 026 [JPSF-019A)

(JPSF-019A]

Manually Initiate Reactor Building Spray (EOP-1(EOP-1.0).0) M, A A,, E, EN EN,, 5 S

S Systemsilll (3 or 2 for SRO-U)

In-Plant Systems@

j. [JPP-068]

System 061 [JPP-068)

Reset Turbine Driven Emergency Feed Pump (SOP-211) D,R D, R 4S k.

k. System 062 Transfer a Vital 120VAC Power Supply - Return of Alternate N 6

( Source (SOP-310)

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room room..

..* Type Codes Criteria for RO 1 SRO-II SRO-U (A)lternate path (A)ltemate ' 4-61 4-6 1 2-3 (C)ontrol room (C)ontror (D)irect from bank $~9/~8/~4 9/ $ 8/ $ 4 (E)mergency or abnormal in-plant  ;:::

~ 1/ ~  ;::: 1/ ~  ;::: 1 1

(EN)ngineered safety feature - 1 1-- 1 1;:::

~ 1 (L)ow-Power  ;::: 1/ ~;::: 1/

~ 1 /~  ;::: 1 1

(N)ew or (M)odified from bank including 1(A) 1(A)  ;::: 2/ ~

~  ;::: 2/ ~  ;::: 1 1

(P)revious 2 exams $~ 31 3 1 $~ 3/ 31 :S" s 2 (randomly selected)

(R)CA  ;::: 1/ ~

~  ;::: 1/ ~  ;::: 1 1

(S)imulator iSiimutator NUREG-1021 , Revision 9

ES-301 Control Room/In-Plant RoomJln-Plant Systems Outline Form ES-301-2 VC SUMMER 2009 NRC EXAM JPM

SUMMARY

((

a. Respond to continuous rod withdrawal in accordance with AOP-403 AOP-403.3,.3, CONTINUOUS CONTROL ROD MOTION. The alternate path is that the applicant will respond to a loss of charging flow that will require manual control of FCV-122, Charging Flow Control Valve, to restore PZR level. Modify Bank JPM JPS-036 by adding the procedure steps for evaluating response.

PZR level response.

d. Establish hot leg injection during loss of RHR at mid-loop conditions in accordance with AOP-115.5, LOSS OF RHR WITH THE RCS NOT INTACT (MODES 5 &

AOP-115.5, & 6). The alternate path is that the applicant will respond to degrading plant conditions by aligning RHR injection and establishing flow to the RCS hot legs.

legs. Bank JPM JPSF-065.

f.

f. Manually initiate reactor building spray in accordance with EOP-1 .0, REACTOR EOP-1.0, TRIP/SAFETY INJECTION ACTUATION, Step 8. The applicant will implement alternate path actions to actuate RB Spray using Train B switches or by manually aligning spray valves. Failure of MVG-3003A, RB Spray Isolation pump suction and header isolation valves.

Valve , to open automatically will require the applicant to manually open the valve to Valve, establish Train A Reactor Building Spray flow. Modify Bank JPM JPSF-019 by adding the MVG-3003A failure.

jj.. Reset turbine driven emergency feed pump in accordance with SOP-211 SOP-211,, EMERGENCY FEEDWATER SYSTEM. Bank JPM JPP-068.

k. Transfer a vital 120VAC power supply in accordance with SOP-310, 120 VAC k.

( INSTRUMENT AND CONTROL SYSTEM. The applicant will complete the steps to restore the alternate source of power to Inverter XIT5901 in accordance with procedure section IV.AD. New JPM.

NUREG-1021 , Revision 9

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