ML072920196
| ML072920196 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| 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) | |
Text
Rev 0 e?SeYob\E..s, 2.
and SRO-only outlines (i.e:, except for on> Category in ~ i e3rof the SRO-O"~~
each KIA category shall not be less than two).
The point total for each group and tier in
' outline, the "Tier ~otals"in ed outlline must match that specified in the pble.
I The fins! point total for each group and by'fl from that s p 8 a e d 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-specificsystems 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 TiersIand 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 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; lfrfuelhandling 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 a.
- g. kinii3;sele&bpi~ from &tkn of$ kA$kIog; the K/* numbers, d~criptions, point t o u s (#)on Form E-1-3. LimitSR 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 Parlialor Comdde Louof InsbwnantAlr B 1 I I I I I K n W & of the reasonsfor the fdowing re6ponses as they apply to 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 2
B 5 buppreo+la\Pool Huh W a t u Tmpu.turol 1M K n W g d of the openlionat implications of lha apptyto SUPPRESSON POOL HIGH WATER TEMPERATURE : (CFR:
41.8to 41.301 EK1.01 Puma NPSH3.0 3.4 ODIICBW ashy 30 12 I
L ~ ~ ~ s l l m n r l a n - - ~ ~ ~ I I IsJ I ! =:=3e
.38 ION PdOL WAER L%L: (CFR:41.5 145.6) E K ~ ~ S 1 3 , I ,S
ANDOMMENT: (CFR:41.10143.5145.131AA2.06
~kry-levelconditions for technical specifications. (CFR.43.21 0 43.5 45.13)AA2.03
I BWR Examination Outline I lAbllle OI (a, oredm me ~moactsof me follomno on (he RH&PCI:'I~JECTION M ~ D (PLANT E SPEC~FIC): and (b, based on (hwe predictions, use procedureslo cone*. control, o mibgale the consequences of (hose abnonnalconditions or ope&ions: (CFR:41.5 1 45.6)A2.01 Inadequatenet positive
2.01 suction head 3.23.4 COOLING SYSTEM (RHR SHUTDOWNCOOLING MODE) 205000 Shutdown C w l n g System (RHR including:
l~hutdown Cooling modej . I I I I I I I I I 501I I I(CFR: 41.7I 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 Coolant o Injection (CFR: 41.7 145.5lo 45.8)A4.03Turbine tempenlures: BWR-lnt*lmhlpr bhvwnLOW PRESSUaE C a E SPRAY S Y S m and the foYowCp: ( C m 41.2 to 41.9145.7 to 45.8) 2.6 2.7 KnolkO.d?m~mulalarormilhnda,dma Mlo*nnpWlhmon?mSOURCERAmK~OR(SRH)
SYSTEM : (CFR:41.7 145.7)K6.W W 4 8 voll D.C. po*r 3.1 MII*lw~~ndlormonllalnmI4eonwrbm:
(CFR 41.7146.5 to 46.8)M.W Plml Spedlfi. 2.5 2.F
-A*nquinImnwdir(.~dryl(amcmpwM
'IIII ~d*uph~ann.oowurdlacuuMul SYSTEM
- - - - .nd b#*r REACTOR WATER LEVEL CONTROL
- Uu 1~1.08PpUT ul (con#nular)
-.-1CFR- 412 lo 41 .S
.2.93.0 145.7
- b-- 46.8)
~ d t h e d h c t m u l a l o r a ~ d h .
STAMJOYGAS TAEA- SYSTEM Wl hmon W l m h :
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 pornrupprw 3.1 3.4
~ d h . o p n ( l o l u l ~ d l h . ~
j 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 Mng d#gng.2.6 2 9 l Wbty I I I I I 1 IIIIIH ~ 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 I l l I l l 1; C I I I I I I I I !I assochw w(lh opsnnng me CCWEl c ~ b o l lncbdhg:
1.5 I $5.5)A1.03 CCW Ressua 2.7 2.7 I~bmonaorautoroIIc~ofthenWPfterssUREI s (CFR 2.7 I
48 NT lNJECTlOW S Y S Including:
~ (CFR 41.7 146.7) maMIlgy opas(e Mdlu monilor In h e contrd room:
7000 R u c t w C o n bolation CwUng .7 1455 b 45.8) A4.M Twbwre blp LhmAlo valve nwKt 15000Shutdown CooUng Syat.m (RHR 13000D.C. E M d DbbibuUon
,2002 Unlntvruptabh P o w r Supply
.CJD.C.)
A Category Totals:
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 s m c a t i o n s for a system.
2.1.12 (CFR: 43.2 143.51 45.3) 4.0 87 I I I I 1 Ability lo (a) predicl the impacts of the follamng on h e HIGH IPRESSURECOOLANT INJECTION SYSTEM :and (b) based on1 1 I I I I 1 those predcbons, use procedures to comet wnlrol, or mtbgale lthe consequemea of those abnormal condhons oroperaUons:
(CFR: 41.5 145.6) A2.17 tHPCl Inadvertent lnhiabon: BWR-2.3,4 I I 21 3.9 4.3 4.3 92 I I I I I I I I 1I 1I 1I 11 1 1 2.4 49 Abllty to perform mhoul referancelo procedures those actlons lhat reaure ~mmedlale 12.4.49 land o~erabonof svslem comwnents controls. (CFR: 41.10 I43.2'1 45.6) '
I1 (I 4.0 89 I 1 IAbi. l ilo of the fdlowina on the PRIMARY~
~"(a)' predictR e im~acts I 002 Primary Contalnmant holatlon I I I I I I CONTAINMENT ISOLATION SYSTEWNUCL~AR S W L Y SHUT-OFF :and (b) based on moaa Dredictlons.use STEAM procedures to conecl, conioi, cf mmicigaleh e cinsequencis of I I tamNuclaar S u m Supply 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) i 1001 Conbd Rod lMvr Hydnulk C 201003 Control Rod and Drive Mechanis~
201004 Rc I
11204000 Reactor Water Cleanuo Svste IlS"._
214000 Rod Position Information 230000 RHRILPCI: ToruslSuppressio~
Rev 0
""900 Fire Protection Sy-stem 3.7 64 of We operational impliu*ons ofthe 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 Generic Knowledge and Abilities Outline (Tier 31 ES-~OI{R~V 9 (Errata)
I [ I Facilitv: Creek Date of Exam: Date Topic I I I fications ford system. (CFR: 43.2 143.5 145.3)
Conduct of Operations 2.2.12 Knowledge of surveillance procedures. (CPR: 41.10 145.13) iMWRTANCE 2.2.12 RO 3.0 SRO 3.4 3.0 69 2.2.24 Ability to anabze the affed of maintenancgactivities on LC0 status. (CFR:
2.2.24 43.2/45.13)1~Wd~~~~~R02.6SR . 03.8 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 controlIincluding I I permissible levels In excess of those authodzed. (CFR: 43.4 145.10) IMPORTANCE 2.3.4 RO 2.5 SRO 3.1 2.5 73 I
2.4.15 Knowledge of communications p m ~ u r &associated with EOP 2.4.15 implementation. (CFR: 41 . I 0 145.13) 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 Tier and Group Randomly Selected KIA Reason for Rejection Q.08: This was not a rejection. The question was developed based on the randomly selected WA, but after T I GI(R0) 2950 19.K2.02 question review, it was determined that WA K2.01 was a closer fit to the question, so the sample plan was revised.
T2 G2 (RO) 201001.K5.02 Q.54: Could not develop a question related to CRD Pump runout. Randomly selected K5.02 as a replacement.
T2 G2 (RO) 230000.A4.03 (2.59: Already had a question(31) dealing with keep-fill. Randomly selected A4.02 as a replacement.
T2 G2 (RO) 233000.G2.1.2 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 T2 G2 (RO) 259001.K2.01 than 2.5 importance. Randomly selected K4.10 as a replacement.
T3 C1 (RO) G2. I . 16 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 I G2 (SRO) 295034.A2.02 t o ~ i 500000.A2.03.
c T2 GI(SR0) 215003.G2.1.33 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 T3 C1 (SRO) G2.1.25 look up. Randomly selected G2.1.4 as a replacement.
T3 C2 (SRO) G2.2.15 Q.97: Could not develop a question for this topic. Randomly selected 2.2.1 1 as a replacement.
T3 C3 (SRO) G2.3.3 (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 T2 GI(SR0) 223002.A2.03 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 T2 GI(SR0) 263000.A2.01 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 T2 G2 (SRO) 205000.A2.04 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 TIPSare now covered in the T2 G2 (SRO) 215001.G2.2.25 TRM not Tech Specs. Randomly selected 245000.A2.09 as a replacement.
T2 G2 (SRO) 239003.A2.04 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 T2 G2 (SRO) 226001.A2.15 better balance.
For Official Use Only
ES-301 Administrative Topics Outline Form ES-301-1
- acility: HODe Creek Date of Examination: 9/24/2007 ixamination Level: RO I7 SRO Operating Test Number: NRC2007 Describe activity to be performed Complete the Daily Surveillance Logs & identify any Conduct of Operations M, S 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.
Conduct of Operations D. S (G2.1.23)
HC JPM 22028 Complete an Action Statement Log Sheet. (G2.2.23)
Equipment Control DLR HC JPM 22029 Radiation Control I D,S Calculate Total Noble Gas Release Rate IAW ABCONT-0004. (G2.3.10)
HC JPM 22020 ERP Classification and Reporting after each simulator Emergency Plan N, S 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 1) (z (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 Date of Examination: 9/24/2007 Exam Level: RO SRO-I [XI SRO-U 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 System / JPM Title Type Code*
Function 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) IN,A,S,LI 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
- f. ResDond to a RPS malfunction (HC JPM SBO10) 7 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 4-6 I 4-6 I 2-3 (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 ES-301,Page 23 of 27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 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 System / JPM Title Type Code' I a. ResDond to RPV level unknown I RPV Flooding (New) lN,A,S,L\ 2 1
- b. Roll the Main Turbine (HCJPM AC004)
- j. Respond to a SACS malfunction (HC JPM EG003) 8
@ 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 / >I1 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 (P)revious 2 exams <3 Is 3 / 5 2 (randomly selected)
> I /2 1 1 2 1 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 PO)
B. Haagensen (BOP) nitial Conditions: 95% power.
rurnover: Raise reactor power to 100% per Load Dispatcher request.
_ E Event Malf. Event Type* Event No.
1 No.
NIA FUN (RO/SRO)
Description Raise power to 100% with recirculation flow
- 2 MSO9A I (SRO) PT-N076A MSL Pressure Fails Upscale (TS) 3 CDIOA C (ROISRO) A CRD Pump Trip 4 PC07A C (All) OBE Earthquake wl 10A403 Bus Fault & Lockout
- ED16 (TS) 5 PCO7B M (All) Aftershock w/ LOP, Main Generator Lockout, B EG12 EDG Start Failure (recoverable), A & D EDG fail resulting in unrecoverable loss of 10A401 & 10A404 DG08B Buses DG02A DG02C
- DG02D 6 HPOI C (RO/PRO) HPCl & RCIC auto start failure (RCIC recoverable)
HPO6M RC02
- RC05 APPENDIX D, Page 38 of 39
Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 2 Op-Test No.: NRC2007 Examiners: J. DAntonio Operators: PRO)
T.Fish B. Haagensen 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 MS04D 6 Multiple I/O M (All) Hydraulic ATWS when operators attempt to scram Overrides due to rising steam tunnel temperatures 7 CUIlA C (All) Failure of RWCU to isolate on manual SLC initiation 8 MS19D C (All) Failure of D Steam Line to auto isolate MS20D
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39