ML072920196

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Exam Final Outlines (Folder 3)
ML072920196
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/17/2007
From: D'Antonio J
NRC Region 1
To:
Public Service Enterprise Group
D'Antonio J
Shared Package
ML062050204 List:
References
50-354/07-301, ES-401, ES-401-1 50-354/07-301
Download: ML072920196 (19)
v • d • e


Text

Rev 0 e?SeYob\\ E..s, and SRO-only outlines (i.e:, except for on> Category in ~ i e r 3 of the SRO-O"~~

outline, the "Tier ~otals" in each KIA category shall not be less than two).

I

2. The point total for each group and tier in ed outlline must match that specified in the pble.

The fins! point total for each group and by'fl from that sp8aed In the table bsased on NRC revision*. The final RO exam must total the SRO-only exam must total 25 points.,

3. ~~s~ms)evolutions within each group the associated outllne; systems or evolqtions that site-specific systems 2, for guldanae regarding
4. Select topics from as ma s poqlble; sample every system or evolution in the group before selecting a
5. Absent a plant-specific p nce rating (IR) of 2.5 or hlgher shall be selected. Use the RO and SRO ratings for SRO-only portions, respectively.

6.* Select SRO topics for Tiers I and 2 from t ystew and KIA categories.

7. The generic (G) KlAs in Tiem 1 and 2 shall from Section 2 of the KIA Catalog, but the topics must be relevant to the a
8. On the following pages, enter the KIA nu desckription of each topic, the topics' impprtance

.. a.

ratings (IRs) for the applicable license I int this (#)for each system and categoty. Enter the group and tier totals for each category In the table bove; lfrfuel handling equipment is sampled In other than Category A2 or Gf on the SRO-only e m, en r it on tHe left slde of Column A2 for Tier 2, Group 2

g. kinii3; sele&bpi~

from &tkn of$ kA$kIog; the K/* numbers, d~criptions, point tous (#)on Form E-1-3.

Limit SR sele ons to As that are linked to 10 CFR 55.43.

Summary

Yam. 1 Safely Fur 18 Partla or CompMe Loor of Compormnt 1.01 B k t a on componenVsyotem 85019 Parlial or Comdde Lou of Insbwnant Alr B K n W & of the reasons for the fdowing re6ponses as they apply to 1 I I I I I lloSSOF6HuToowNCOolNG:(CFR:41.5145.6)AK3.04~~a I I

2.1.32 AMhy to explain and apply aH system limits and precautions. (CFR:

I 2 r. j 41.101431 145.12) 3.4 12 K n W g d of the openlionat implications of lha ODIICBW a s h y 2-buppreo+la\\ Pool Huh Watu Tmpu.turol apptyto SUPPRESSON POOL HIGH WATER TEMPERATURE : (CFR:

B 5 1 M 41.8to 41.301 EK1.01 Puma NPSH 3.0 3.4 30 12 I ION PdOL WAER L%L:

(CFR: 41.5 145.6) E K ~ ~ S L ~ ~ ~ s l l m n r l a n - - ~ ~ ~

I I IsJ I !

=:=3.e3.8 1 3, I,S

ANDOMMENT: (CFR: 41.10 143.5 145.131 AA2.06

~kry-level conditions for technical specifications. (CFR. 43.2 1 0 43.5 45.13)AA2.03

BWR Examination Outline I

I lAbllle IO (a, oredm me ~moacts of me follomno on (he RH&PCI:'I~JECTION M ~ D E (PLANT SPEC~FIC) : and (b, based on (hwe predictions, use procedures lo cone*. control, o mibgale the consequences of (hose abnonnal conditions or ope&ions: (CFR: 41.5 1 45.6) A2.01 Inadequate net positive 2.01 suction head 3.2 3.4 COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) 205000 Shutdown Cwlng System (RHR including:

l~hutdown Cooling mode j I

I I

I I

I I

I I

I I

501 I

(CFR: 41.7 I 45.7) A3.01 Valve operation 3.2 3.1 A b i l i b manually operate andlor monitor in (he conbol mom:

206000 Hlgh P ~ u r o Coolant Injection (CFR: 41.7 145.5 lo 45.8) A4.03 Turbine tempenlures: BWR-lnt*lmhlpr bhvwn LOW PRESSUaE C a E SPRAY S Y S m and the foYowCp: ( C m 41.2 to 41.91 45.7 to 45.8) 2.6 2.7 K n o l k O. d ? m ~ m u l a l a r o r m i l h n d a, d m a Mlo*nnpWlhmon?mSOURCERAmK~OR(SRH)

SYSTEM : (CFR: 41.7 145.7) K6.W W 4 8 voll D.C. po*r 3.1 M I I

  • l w ~ ~ n d l o r m o n l l a l n m I 4 e o n w r b m :

(CFR 41.7 146.5 to 46.8) M.W Plml Spedlfi. 2.5 2.F

- A

  • n q u i n I m n w d i r (. ~ d r y l ( a m c m p w M

' I I I I

~ d

  • u p h ~ a n n. o o w u r d l a c u u M u l b#*r REACTOR WATER LEVEL CONTROL SYSTEM.nd Uu 1CFR 41 2 lo 41.S 145.7 b 46.8) 1~1.08 PpUT ul (con#nular)

.2.9 3.0

~ d t h e d h c t m u l a l o r a ~ d h.

STAMJOY GAS TAEA-SYSTEM Wl hm on Wlmh:

of W M E R N P T M L E POWER SUPPLY Ih.fQblhg:(CFR41.7)K4.01 T ~ ( m m p. h m d p a r w to rmU porn rupprw 3.1 3.4 j

~

d h

o p

n

(

l o

l u

l

~

d l

h

~

wnolptr as Uwy.PPIY to D.C. ELECllUW M%TW%UTY)N :

f

( W R 4t.6 145.3) KJ.01 nydmOen @ u m d a l Mng Wbty d#gng. 2.6 29 I I I I I 1 I I I I I H

~ d h. ~ h a t r l o s r o r ~ o f h.

l o l a C g r r W haw on Iw EERCXNCY GENERATORS

I l l I l

l 1

C assochw w(lh opsnnng me CCWEl c~bols lncbdhg: (CFR 1.5 I $5.5)A1.03 CCW Ressua 2.7 2.7 2.7 48 I

I I

I I

I I

I I

!I I ~ b m o n a o r a u t o r o I I c ~ o f t h e n W P f t e r s s U R E I I

7000 R u c t w C o n bolation CwUng 15000 Shutdown CooUng Syat.m (RHR 13000 D.C. E M

d DbbibuUon

,2002 Unlntvruptabh Powr Supply

.CJD.C.)

A Category Totals:

NT lNJECTlOW S Y

S

~

Including: (CFR 41.7 146.7) maMIlgy opas(e Mdlu monilor In h e contrd room:

.7 1455 b 45.8) A4.M Twbwre blp LhmAlo valve nwKt

002 Primary Contalnmant holatlon tamNuclaar S u m Supply 2.2.22 K d e d g e of limiting conditions for operations and safety 2.2.22 limits. (CFR: 43.2 145.2) 3.4 4.1 4.1 93 2.1.12 Ability to apply technical smcations for a system.

2.1.12 (CFR: 43.2 143.51 45.3) 4.0 87 Ability lo (a) predicl the impacts of the follamng on h e HIGH I I I I 1 IPRESSURE COOLANT INJECTION SYSTEM : and (b) based on1 1

those predcbons, use procedures to comet wnlrol, or mtbgale I I I I 1 lthe consequemea of those abnormal condhons oroperaUons: I I

(CFR: 41.5 145.6) A2.17 tHPCl Inadvertent lnhiabon: BWR-2.3,4 2 1 3.9 4.3 4.3 92 I

I I

I I

I I

I 1

1 1

1 1

1 2.4 49 Abllty to perform mhoul referance lo procedures those actlons lhat reaure ~mmedlale o~erabon of svslem comwnents I I

I I I 1

12.4.49 land controls. (CFR: 41.10 I 43.2'1 45.6) 1 4.0 (

89 I 1 IAbili~

lo (a) predict Re im~acts of the fdlowina on the PRIMARY~

I CONTAINMENT ISOLATION SYSTEWNUCL~AR STEAM S W L Y SHUT-OFF : and (b) based on moaa Dredictlons. use I I I I I I I

I procedures to conecl, conioi, cf mmicigale h e cinsequencis of those abnormal conditions or operations:

2.10 (CFR: 41.5 145.6) A2.10 Loss of coolant accidents 3.9 4.2 4.2 91

E W 1 # Rev 9 (Errata) 1001 Conbd Rod lMvr Hydnulk i

201003 Control Rod and Drive I

Mechanis~ C 201004 Rc 11204000 Reactor Water Cleanuo Svste '

214000 Rod Position Information IlS".._

230000 RHRILPCI: ToruslSuppressio~

Rev 0

""900 Fire Protection Sy-stem 3.7 64 of We operational impliu*ons of the Ulawing b as they apply 10 SECONDARY CONTAINMENT : (CFR:

DO1 Secondary Containment 6.01 290003 Conbol Room HVM:

290002 h e t o r Veuel Intamah 12

(CFR: 41.5 145.6) A2.1 I

I 1

I ES-~OI{R~V 9 Generic Knowledge and Abilities Outline (Tier 31 (Errata)

I[

Facilitv:

Creek Date of Exam:

Date Conduct of Operations I

Topic I

I I

fications ford system. (CFR: 43.2 143.5 145.3) 2.2.1 2 Knowledge of surveillance procedures. (CPR: 41.10 1 45.1 3) iM WRTANCE 2.2.12 RO 3.0 SRO 3.4 3.0 69 2.2.24 Ability to anabze the affed of maintenancg activities on LC0 status. (CFR:

2.2.24 4 3. 2 / 4 5. 1 3 ) 1 ~ W d ~ ~ ~ ~ ~ R 0 2. 6 S R 0 3. 8 2.6 70 2.2.33 Knowledge of control rod programming. (CFR: 43.6) IMPORTANCE RO 2.5 2.2.33 SRO 2.9 2.9.

71 L

I I

I i

2.3.10 Ability to wiform procedures to reduce ex6esaive levels of radiation and nuard 2.3.10 lagainst pe&&

expo&.

(CFR: 43.4 145.10) IMPORTANCE RO 2.9 SRO 3.3 1

2.91 72 12.3.4 Knowledge of radiation exposure limits and Contamination control I including I I

permissible levels In excess of those authodzed. (CFR: 43.4 145.1 0) IMPORTANCE 2.3.4 RO 2.5 SRO 3.1 2.5 73 2.4.1 5 Knowledge of communications p m ~ u r &

associated with EOP I

2.4.15 implementation. (CFR: 41.I0 145.13) IMPORT&E RO 3.0 SRO 3.5 3.0 74 2.4.46 AMlW to verify that the alarms are consistent with the plant conditions. (CFR:

2.4.46 43.5 145.3 145.12) IMPORTANCE RO 3.5 SRO 3 6 3.5 75

Rev 0

Hope Creek NRC Exam Rev 0 For Official Use Only Tier and Group Randomly Selected KIA TI GI(R0) 2950 19. K2.02 T2 G2 (RO) 201001.K5.02 T2 G2 (RO) 230000.A4.03 T2 G2 (RO) 233000. G2.1.2 T2 G2 (RO) 259001. K2.01 T3 C1 (RO)

G2. I. 16 TI G2 (SRO) 295034.A2.02 T2 GI(SR0) 21 5003. G2.1.33 T3 C1 (SRO)

G2.1.25 T3 C2 (SRO)

G2.2.15 T3 C3 (SRO)

G2.3.3 T2 GI(SR0) 223002.A2.03 T2 GI(SR0) 263000.A2.01 T2 G2 (SRO) 205000.A2.04 T2 G2 (SRO) 215001.G2.2.25 T2 G2 (SRO) 239003.A2.04 T2 G2 (SRO) 226001.A2.15 Reason for Rejection Q.08: This was not a rejection. The question was developed based on the randomly selected WA, but after question review, it was determined that WA K2.01 was a closer fit to the question, so the sample plan was revised.

Q.54: Could not develop a question related to CRD Pump runout. Randomly selected K5.02 as a replacement.

(2.59:

Already had a question (31) dealing with keep-fill. Randomly selected A4.02 as a replacement.

Q.60: Could not develop a discriminating question for this topic. Randomly selected 2.1.30 as a replacement.

Q.62: Hope Creek does not have motor driven Feed Pumps. Could not select another K2 topic since all were less than 2.5 importance. Randomly selected K4.10 as a replacement.

Q.67: Low operational validity (plant phones and paging system). Randomly selected 2.1.10 as a replacement.

Q.85: Too many other questions related to secondary containment / high rad. Randomly selected new system and t o ~ i c 500000.A2.03.

Q.87: Could not develop an SRO level question for this topic. Randomly selected G2.1.12 as a replacement.

Q.95: Chief Examiner directed reselection since topic requires giving a reference that will most likely be a direct look up. Randomly selected G2.1.4 as a replacement.

Q.97: Could not develop a question for this topic. Randomly selected 2.2.1 1 as a replacement.

(2.98: Could not develop a question for this topic. Randomly selected 2.3.1 as a replacement.

Q.91: This was not a rejection. The question was developed based on the randomly selected WA, but after question review, it was determined that WA K2.10 was a closer fit to the question, so the sample plan was revised.

Q.93: Could not develop an SRO question related to DC grounds. There was only one other A2 WA left and a similar question already existed (Q.45). Randomly selected 264000.G2.2.22 as a replacement.

Q.92: Could not develop an SRO level question. In addition, other questions on the exam cover SDC. Randomly selected 206000.A2.17 as a replacement.

Q86: This was a TIP related WA and a similar topic was already covered in question 91 under WA 223002.A2.10 for the NSSSS isolation function. In addition, G2.2.25 is related to Tech Specs and TIPS are now covered in the TRM not Tech Specs. Randomly selected 245000.A2.09 as a replacement.

Q.88 HC does not have MSlV Leakage Control. Randomly selected 202001.A210 as a replacement.

Q.90 Tech Spec related questions are already heavily sampled in the exam. Randomly selected WA A2.15 for better balance.

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

acility: HODe Creek ixamination Level: RO I7 SRO Conduct of Operations M, S Conduct of Operations D. S Equipment Control DL R Radiation Control I

D,S Emergency Plan N, S Date of Examination: 9/24/2007 Operating Test Number: NRC2007 -

Describe activity to be performed Complete the Daily Surveillance Logs & identify any applicable Technical Specification Actions. (G2.1.18)

Modified HC JPM ZZO16 Perform required operations in preparation for -+\\ant startup / NI checks IAW 1O.ZZ-002 Attachment 2.

(G2.1.23)

HC JPM 22028 Complete an Action Statement Log Sheet. (G2.2.23)

HC JPM 22029 Calculate Total Noble Gas Release Rate IAW ABCONT-0004. (G2.3.10)

HC JPM 22020 ERP Classification and Reporting after each simulator scenario. (G2.4.41)

New I_

VOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

' Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs 8 RO retakes)

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

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

ES 301, Page 22 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: HODe Creek Exam Level: RO SRO-I [XI SRO-U Date of Examination: 9/24/2007 Operating Test Number: NRC2007 I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety Function Type Code*

System / JPM Title I a. Respond to an uncoupled control rod (HC JPM BFOl1) 1 D,A,S 1

1 1 b. Respond to RPV level unknown / RPV Flooding (New)

I N, A, S, L I 2

1 c. Roll the Main Turbine (HC JPM AC004) 1 D,A,S 1

3

d. Respond to a loss of Shutdown Cooling (HC JPM BC003)

D, L, S 4

e. Place a water seal on the " A

& "B" Feedwater headers D, A, S 5

f. ResDond to a RPS malfunction (HC JPM SBO10) 7 (HC JPM AE004)

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

i. Defeat the PClS Isolation of the Non-I E Instrument Gas header All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must 5ewe different safety functions; in-plant systems and functions ma) overlap those tested in the control room.
  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power / Shutdown (N)ew or (M)odified from bank including l(A)

(P)revious 2 exams

< 3 I5 3 I 5 2 (randomly selected)

> I /,I / > I 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 System / JPM Title Exam Level: RO 0 SRO-I 0 SRO-U Operating Test Number: NRC2007 ntrol Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety Type Code' I a. ResDond to RPV level unknown I RPV Flooding (New) l N, A, S, L \\

2 1

b. Roll the Main Turbine (HC JPM AC004)
i. Perform a DC load shed during Station Blackout IAW AB.Z.2-0135 N, E, R 6
j. Respond to a SACS malfunction (HC JPM EG003) 8 (New)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety (A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irect from bank c 9 1 sa 1 5 4 (E)mergency or abnormal in-plant

- >I/

>I 1 3 1 (C)ow-Power I Shutdown

- >I/

21 / ? I (N)ew or (M)odified from bank including l(A)

> 2 / 2 2 1 2 1

- >I/

21 1 2 1 (P)revious 2 exams

< 3 Is 3 / 5 2 (randomly selected)

ES-301, Page 23 of 27

Appendix D Scenario Outline Form ES-D-1

=acility: Hope Creek Scenario No.: 1 Op-Test No.: NRC2007 Examiners:

J. DAntonio Operators:

FRO)

T. Fish P O )

B. Haagensen (BOP) nitial Conditions: 95% power.

rurnover: Raise reactor power to 100% per Load Dispatcher request.

_E Event No.

1 2

3 4

5 6

Malf.

No.

NIA MSO9A CDIOA PC07A ED1 6 PCO7B EG12 DG08B DG02A DG02C DG02D HPOI HPO6M RC02 RC05 Event Type*

FUN (RO/SRO)

I (SRO)

C (ROISRO)

C (All)

M (All)

C (RO/PRO)

Event Description Raise power to 100% with recirculation flow PT-N076A MSL Pressure Fails Upscale (TS)

A CRD Pump Trip OBE Earthquake wl 10A403 Bus Fault & Lockout Aftershock w/ LOP, Main Generator Lockout, B EDG Start Failure (recoverable), A & D EDG fail resulting in unrecoverable loss of 10A401 & 10A404 Buses (TS)

HPCl & RCIC auto start failure (RCIC recoverable)

APPENDIX D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 8

Facility: Hope Creek Scenario No.: 2 Op-Test No.: NRC2007 MS19D MS20D C (All)

Failure of D Steam Line to auto isolate Examiners: J. DAntonio T. Fish B. Haagensen Operators:

PRO)

Initial Conditions: Startup is in progress with the unit at about 19% power just after Main Generator Synchronization.

Turnover: Raise power by withdrawing control rods IAW 10-3 and RE guidance.

Event Malf.

Event Type*

Event No.

No.

Description 1

NIA WN (RO/SRO)

Raise power by withdrawing control rods 2

NM21A I (RO/SRO)

A APRM fails upscale after Is rod is withdrawn 3

CD23 G (RO/SRO)

Stuck control rod 4

FW29A I (SRO)

DFCS LT-N004A fails upscale (TS) 5 MS04A C (All)

Steam Leak in steam tunnel 6

Multiple I/O M (All)

Hydraulic ATWS when operators attempt to scram 7

CUIlA C (All)

Failure of RWCU to isolate on manual SLC initiation MS04D Overrides due to rising steam tunnel temperatures

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39
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