ML091730151

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05000321/366-2009-301 Draft Administrative-QA Sheets
ML091730151
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 06/22/2009
From:
Office of Nuclear Reactor Regulation
To:
References
Download: ML091730151 (12)
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Text

ES-401, Rev. 9 ~WR Examination Outline Form ES-401-1 Facility: HAiCH Date of Exam: APRIL 2f)09 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total 4 3 2, 4 3 4 20 3 4
1. 1 7 Emergency & 1 1 1 1 1 2 7 1 2 3 2

Abnormal Plant N/A N/A Evolutions 5 4 3 5 4 6 27 4 6 10 Tier Totals 1 2 2 2 4 2 2 2 2 2 3 3 26 2 3 5

2. 1 . 1 1 1 2 1 1 1 1 1 1 12 0 1 2 2 3 Plant Systems Tier Totals 3 3 3 5 4 3 3 3 3 4 4 38 3 5 8
3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 1 2 2 2
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 ofthe SRO-only outline, the ATier Totals@

in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by '11 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. *The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be relevant to the applicable evolution or system.
8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
  1. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 ofthe KIA catalog, and enter the KIA numbers, descriptions, IRs,

. and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43 .

ES-401 Record of Rejected KIAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KIA III (RO) 295027EK2.02 Hatch does not have Mark 3 containment; randomly re-selected 295026EK2.01 111 (RO) 295025 G2.1.27 Generic statement did not match high reactor pressure; randomly re-selected G2.1.23 2/1 (RO) 203000G2.4.41 Generic statement did not match RHRlLPCI Injection Mode for RO knowledge; randomly re-selected G2.4.8 2/1 (RO) 207000K5.02 Hatch does not have an Isolation Condenser; randomly re-selected 264000K5.06 211 (RO) 209002K6.02 Hatch does not have High Pressure Core Spray; randomly re-selected 206000K6.02 211 (RO) 223002K3.13 Hatch does not have an Isolation Condenser: randomly re-selected 223002K3.11 211 (RO) 259002A4.05 Hatch does not have run out flow reset controls; randomly re-selected 259002A4.01 2/2 (RO) 201004K4.02 Hatch does not have rod sequence control system (RSCS) any longer; randomly res elected 201001K5.02 1/2 (SRO) 295011AA2.01 Hatch does not have a Mark 3 containment; randomly re-selected 295017AA2.01 2/1 (SRO) 262002A2.04 Hatch is a BWR 4 (vs BWR 1); randomly res elected 262002A2.01

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO 1 SRO)

E/APE # 1 Name 1 Safety Function KJA Topic(s) IR #

295001 Partial or Complete Loss of Forced Core Flow Circulation 1 1 & 4 295003 Partial or Complete Loss of AC 16 g Z9S>D0'3 Gi 2 .-t. ~4- ,.4.2-295004 Partial or Total Loss of DC Pwr 1 6 R. ~I~\ R2't 5004 AAI* 0:3 P.., .1-295005 Main Turbine Generator Trip 1 3 (l. 7' ~ '2. '15'~()5A #::3. D4 f..o.:z.

295006 SCRAM 1 1 It IT s (J.. 2.'H.ct>~ It K I. 0, SZQCS()()f-6;z*'*.27 IU..7 ~ 4. 0 295016 Control Room Abandonment 1 7 ira b, R 2"1501'" AI\2.. 0 I '4-.1 295018 Partial or Total Loss of CCW 1 8 ~ ,'< ., *..*. p. Z,~ /:> l8 A1C.3. 0 3 R. 3.1 295019 Partial or Total Loss of Inst. Air 1 8 tRJr}~ "2 ~S o,~ A.A2-. o~ ~3.,"

295021 LossofShutdownCoolinQ/4  !:;' R (t'2.~SO;t,G.'2.+,3S/ S2.,5DZIAA2.03 l?3.& 5~.S-295023 Refueling Accl 8 <<. t;j:~' tz.. "Z.ct5 02~ AA l. 04- S.?q50'2-3~ 2,1; .g"f<34 54-. '$

j 295024 High Drywell Pressure 1 5 [R.\ ., .. R 2~ S 0;).+ ti.1\2..0~ ~+'I R4.~

295025 High Reactor Pressure 1 3 295026 Suppression Pool High Water' Temp. 1 5 .

. T fr.

295028 High brywell Temperature 1 5 295030 Low Suppression Pool Wtr Lvi 1 5 29503'1 Reactor Low Water Levell 2 R4.4-295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown 11 295038 High Off-site Release Rate 1 9 600000 Plant Fire On Site 1 8 700000 Generator Voltage and Electric Grid Disturbances (6

~~~~~Ory~T~ot~al~s:~======.t4tL3~~ll4tl:m Group Point Total: ;to/ 2017 31 7

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emerqency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

IE/APE # / Name / Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 5 SZQ500ts"2.4-.2J) S4S 295009 Low Reactor Water Level / 2 f?4.0 295010 Hiqh Drvwell Pressure / 5 R P. '2//)50 ( OG; 2. '2.2.2 295011 Hiqh Containment Temp / 5 I** ..

295012 Hiqh Drvwell Temperature / 5 295013 High Suppression Pool Temp. / 5 rz R').'15013A K 2.01 f!.j. "

295014 Inadvertent Reactivity Addition /1 S .$'2-'1~{)14<;2.Z. 4-D S4-.7 I.*****

(( AZ, 5 DIS ~ 1,2.4 R3,~

295015 Incomplete SCRAM /1 295017 High Off-site Release Rate / 9 S 5 2-QsoltJAA2. 0/ 51.2..

~2'!>f)2.0A K I ,oS- 1(3.3 295020 Inadvertent Cont. Isolation / 5 & 7 f{

295022 Loss of CRD Pumps / 1 295029 Hiqh Suppression Pool Wtr Lvi / 5

<<2. tjSt?32. 'fAt./)5 1<3*7 295032 High Secondary Containment Area Temperature /5 <<

295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High 1<2'l503SE A2.0'2- R2.t Differential Pressure / 5 P-.

295036 Secondary Containment High Sump/Area Water Level /5 R'5l1Oo 0 (> 61< '3 I f)(p Rs .1 500000 Hiqh CTMT Hydrogen Conc. / 5 P--

I

  • I KIA Category Point Totals: \ I I I ! ~ Group Point Total: 7/ 7/3 3

ES-401 4 Form ES-401-1 I ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name KKK KKK A ~ A AG KIA Topic(s) IR #

1 2 3 4 5 6 1 .~ 3 4 203000 RHR/LPCI: Injection Mode R3.1 205000 Shutdown CoolinQ R 206000 HPCI R (Z. ti<

20799Q IsslalisR (~fI'lelgeli~

Condenser 209001 LPCS 0099921-1PGe 211000SLC 212000 RPS 2150031RM 215004 Source RanQe Monitor 215005 APRM / LPRM 217000 RCIC 218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS I . . . R 2b) D()()A2.1?.

262001 AC Electrical R. 2-h 2 DO I )(.4.t) 2.

Distribution R'2.~a/)", K4.0S-262002 UPS (AC/DC) 263000 DC Electrical Distribution

.R R 1*/

264000 EDGs 300000 Instrument Air 400000 Component Cooling Water KIA Category Point Totals: Group PointTotal: .:(~ / 26/5 5

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-40 Plant Svstems - Tier 2/Group 2 (RO / SRo\

System # / Name KKK KKK A A A A G KIA Topic(s) IR #

123456 1 2 3 4 I>.

1'2,10 201001 CRD Hvdraulic 201002 RMCS 201003 Control Rod and Drive Mechanism 1r=2~01~0~05~R~C~IS~______________4-~-+-4__~+-~~<~-r-t~*H*______________________----~--~--~I 201006 RWM 1~4~

202001 Recirculation k:,; R.,Z,D2()011<4-t 0'7 IR2..~

202002 Recirculation Flow Control 204000 RWCU R.2.,

214000 RPIS ,;...'

215001 Traversing In-core Probe 1~2.&'

215002 RBM 216000 Nuclear Boiler Inst.

219000 RHRlLPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

226001 RHRlLPCI: CTMT Spray Mode 230000 RHRlLPCI: Torus/Pool Spray Mode 233000 Fuel Pool Coolina/Cleanup 234000 Fuel Handlina Eauipment .*. . *. . **.Ir l:~r 239001 Main and Reheat Steam R'S.1-239003 MSIV Leakage Control 241000 ReactorlTurbine Pressure Regulator R

245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation Ir=~~~~~------+-~~-+-+~ ~~r;~*!~~~~~~--------~~~~I I

290001 Secondary CTMT .; 5 Z q Out) I A Z .04-290003 Control Room HVAC 290002 Reactor Vessel Internals KIA Category Point Totals: 7I 1 I I;). I I;J I I r Group Point Total; I 'J.7 12/3 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: H- A'T c: H Date of Exam: Apv;\ 'ZOO '3 Category KIA # Topic RO SRO-Only IR # IR #

I 1.

Conduct of Operations 2.1. ZO"£;:;<;: () I 2.1.

2.1.

Subtotal 2.2. hr I<v 2.

Equipment Control 2.2./ I s I~' '0 2.2.7 5l!,o 2.2.

Subtotal I** ** *i*. *.*.**/,ii.

2.3. /1-2.3. ?

3. 2.3. j I Radiation Control 2.3.5 2.3.

2.3.

Subtotal 2.4. j leo 4.

2.4.9 l{,1) g,g J if Emergency I Procedures I 2.4.30 $,.'<<1) I Plan 2.4.

2.4.

Subtotal ~ Ii,::.'.:

I~Ti-er-3-p-o-in-tT-o-ta~I~~=-------------------------------~~~ +-1-o--~I:~~;>.9<i#>~<-7--~1

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ES-301 Administrative Topics Outline Form ES-301-1 Facility: Plant E. I. Hatch, HLT 4 Date of Examination: 04/20/2009 Examination Level: RO X SRO X Operating Test Number: 2009-301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Requirements for position and safety gear around Conduct of Operations N,R electrical equipment. RO & SRO,G 2.1.26, 3.4, 3.6 Admin 1 Perform ECCS Status Check and determine a valve is Conduct of Operations N,S out of position. RO and SRO, G 2.1.29 4.1, 4.0 Admin 2 Given a inoperable Tech Spec component, initiate a Equipment Control N,R Required Action Sheet (RAS). SRO ONLY, 2.2.23, Admin 3 4.6 Equipment Control Prepare Equipment Danger Tagout RO ONLY 2.2.13, Admin 7 D,R 4.1 Radiation Control N,R Given an inoperable ODCM Effluent Radiation Admin 4 monitor, determine the required actions. SRO ONLY, G 2.3.11, 4.3 Radiation Control N,R Evaluate an RWP, RO only, G2.3.7, 3.5 Admin 5 Emergency Procedures/Plan N,R Review/Authorize Emergency Exposures Admin 6 SRO ONLY, G2.4.38, 4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:::; 3 for ROs; :::; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (;:': 1)

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

(

ES-301 Control Room/In-Plant Systems Outline - Rev 1 Form ES-301-2 Facility: Plant E. I. Hatch, HLT 4 Date of Examination: 04/20/2009 Exam Level: RO X SRO-I X SRO-U Operating Test No.: 2009-301 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title Type Code* Safety Function

a. Perform IRM Overlap Test, AlllRMs Do Not Pass Test. (JP25038) L,D,S 215003, SF 7
b. Shutdown Cooling Isolation Failure. (JP13047) A, L, N, S 223002, SF 5
c. Diesel Generator Manual Start Surveillance (Trip Failure) A, D,S 264000, SF6 (JP25034)
d. Perform A Manual Startup Of HPCI, Controller Failure Low, A, D, S 295031, SF 2 Alternate Path (JP00502b)
e. Over Ride And Open PSW Isolation Valves, (JP20003) M,S 295018, SF 8
f. Rx Press Control With SRVs (JP25040) A,D,S 295025, SF 3
g. Using the Override Switches, Vent the Torus With the CAD D,S 261000, SF 9 System, (JP01363)
h. Move Control Rods after a CRD Pump Trip (JP25012) (RO Only) A,D,S 202001, SF 1 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Inject SBLC LocallY (JP01112) A, E, M, R 295037, SF1 Modified with failure of the "A" pump to start requiring start of the "B" pump.
j. From the Remote Shutdown Panel, Start RHR in Torus Cooling D,E,R 295013, SF 5 (JP00720)
k. Transfer 600 VAC Essential (LPCI Bus) From Normal To Alternate D,R 203000, SF 4 (JP02718)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6/ 4-6 / 2-3 (C)ontrol room (D)irect from bank s9/sS/s4 (E)mergency or abnormal in-plant  ::::1/::::1/;::1 (EN)gineered safety feature - / - / ;::1 (control room (L)ow-Power / Shutdown system)

(N)ewor (M)odified from bank including 1(A)  ::::1/;::1/::::1 (P)revious 2 exams  ::::2/;::2/;::1 (R)CA s 3/ s 3/ s 2 (randomly (S)imulator selected)

1/;::1/::::1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: HATCH Date of Examination: _ _2009_ _

Exam Level: RO X SRO-I X SRO-U Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Perform IRM Overlap Test, AlllRMs Do Not Pass Test. (JP25038) L,D,S 215003, SF 7
b. Shutdown Cooling Isolation Failure. (JP13047) "-

A,L,N,S 223002, SF 5

c. Diesel Generator Manual Start Surveillance (Trip Failure) A, D,S 264000, SF 6 (JP25034)
d. Perform A Manual Startup Of HPCI, Controller Failure Low, A, D,S 206000,SF 2 Alternate Path (JP00502b)
e. Over Ride And Open PSW Isolation Valves, (JP20003) M, S 400000, SF 8
f. Rx Press Control With SRVs (JP25040) A,D, S 239002, SF 3
g. Using the Override Switches, Vent the Torus With the CAD D,S 261000, SF 9 System, (JP01363)
h. Move Control Rods after a CRD Pump Trip (JP25012) (RO Only) A,D,S 202001, SF 1 f

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

i. From Outside The Control Room, puriIJ!Lt\~ntrQ~m A,E,M,R 201001, SF 1

~acuation, Maximize CRD System Flow (JP00124A)

~."'-- -

j. Fro_m the Remote Shutdown Panel, Start RHR in Torus Cooling D,E,S 219000, SF 5 (JP00720)
k. Transfer 600 VAC Essential (LPCI Bus) From Normal To Alternate D;R* 203000, SF 4 (JP02718)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes I Criteria for RO / SRO-I / SRO-U

(A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant  ;::1/;::1/;::1 (EN)gineered safety feature - / - / ;::1 (control room system)

(L)ow-Power / Shutdown  ;::1/;::1/;::1 (N)ew or (M)odified from bank including 1 (A) ;::2/;::2/;::1 (P)revious 2 exams :5 3/:5 3/:5 2 (randomly selected)

(R)CA  ;::1/;::1/;::1 (S)imulator

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