ML103050172
| ML103050172 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/16/2010 |
| From: | Division of Nuclear Materials Safety II |
| To: | |
| References | |
| 50-338/10-301, 50-339/10-301 | |
| Download: ML103050172 (22) | |
Text
11/18/2e9 12:22 44562455 NRC PGE 2/15 S-4O1, Rev. 9 PWR ExemlnadonOuUlne Farm ES-401-2 F,cllfty NoriAnna DateofExam: 2010 rr Croup T
[_
RO IdA Categoty Poinla SRO-Opiy PoInts IKKKKKKAAAIAG A2 G* Total 11 2 3 4 5 6 1 2 Total
- 1. 1 333 33 3 18 3 3 8 2 221 ii 29 2 2 4 AbnorvnalPbnt NIA NIA Tier Totals 4 4 4 5 27 5 5 10 1 331333322 2328 32 5 2 111111110 1110 20 1 pit Systems TiarTotals 44244443234 35 5 3 8 V
- 3. GnnencKnowledgeendAbflltjeg 1 2 3 4 10 1 2 3 4 7 Catsgones 2 3 2 2 2 2 1 -
- 1. Sneure Ut at least two topIcs from every applicable K1A category are eompiad whim each tier of the BC end SRO.nely outlines (I.e., except for one category In TierS of the SIlO-only outline, the TIerToteh in each KIA category shell not be lass then two).
- 2. The point total for each group and tier In the proposed outline must match that specified In the table.
ma final pclnttotal for each group and tier may deviate by +/-1 from that specified In the table based on NRC revisions.
The final RO exam must total 75 pointe and the SRO-ordy exam must total 25 poInts.
- 3. $ystemelevolutlona within each group are Identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted an jusufted; operationally hnpOrtent site-specIfic syetan that are not Included on the outline should be added. Refer to section 0.1 .b of 53.401 for goldence reqanding the ailmiThitiOn of inappropriate KIA statements.
- 4. Select topics from as many systems and evolutions as possible, sample every system or evolution In the group before selectinga second topic forany system orevolutlon.
- 5. Absent a plant-specific priority, only these KIM having sri Importance rating (IR) of 2.5 or higher shall be selected.
Use the BC and SRO ratings for the BC and SIlO-only portions
, respectively.
4
- 5. Select SRO topics for Tiers I and 2 from the shaded systems end KIA categories.
- 7. The generic (G) KIAs in Tiers I and 2 shall be selected from SectIon 2 of tie KIA Catalog, but the topics must be relevant to the applicable ovolution cc system. Refer to section DA.baf E3401 for the applicable KAa.
- 8. On the following pages, enter the KM nunthers, a brief description of each topic, the toploS Importance ratings (IRS) fOr the applicable Ucanee level, and tie point totals(S) fur each system and category. Enter the group and tier totale fOr each category In the table above; if fuel handling equipment Is sampled In other than Category A2 or (35 the SIlO-only exam, enter It on the left aide of Column A2 for TIer 2, Group 2 (Note #1 does not apply). Use duplicate pages fur RO and SRO-only esams.
- 9. For TierS, select topics from Seetloq 2 of the KIA catalog, and enter the KM numbers, descdptloiie, IRS, and point totala (0) on Form [.44)14. Umit SIlO selections to KIM that are linked 10 CFR 55.43..
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ES-401, REV 9 T1GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR 1(1 1(2 1(3 K4 1(5 1(6 Al A2 A3 A4 G TOPIC:
RD SRO 055A02.4.9 Loss ol Off-ella Power I 6 3.8 42 [] [] [] fl 0 0 [3 [3 [3 [3 j Knowledge at low power! etiutLfown Impitcallons in acddent(e.g, LOCA or lose of RHR) mitigatIon atiategies.
O57AG2AAS Loss of Vilal AC test Baa 16 4.1 4.3 [3 [J [] [] [3 [] [] [] [3 [3 Ability to pilontIze and interpret the signilicanca of each anrdatrn or alaiin.
062AA2.01 Loss of Nuclear Svc Water 14 2.8 3.5 [] [3 [J [] [] [3 [1 J [3 [] [3 LOCatIOn 01 a leak In the SWS 085AG2.1 27 Loss oF Instrument Air! 8 3.9 4 [3 [3 [J [J [] [3 [3 [3 [3 El J Knowledge ci system upoee and or funciton.
077AA1 .02 Generator Voltage and ElectrIc GrId 3.8 3.7 [] [3 [] [] [3 [3 ] [3 [] [3 [3 TurbIne I generator controls Dtsiujbaiicas / 6 WEO5EX3.3 Inadequate Heat Ttansfer Loss ci 4.0 4,1 ManipulatIon of controls required to obtain dasThd Secondary Heal Sink 14
[3 [3 [] [3 [3 [] [] [] [] []
operating results thirfng abnomial and emergency situations.
WEll EA2.1 Loss oF Emergency Coolant Racirc. 14 3.4 4.2 [3 [3 [3 [3 [3 [3 [3 (3 (3 [1 Facility conditions and selection of appropriate procedures during abnorma and eniergancy operatIons.
Page 2 at 2 11/12/2009 200 PM
ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 CD KA NAMEISAFETY FUNCTION: IR 1(1 1(2 1(3 K4 1(5 1(8 Al A2 A3 A4 G TO P LC: CD CD RO SRO us OOIAK1,03 Con eflod With&awehJl 4 El LI U El (1 E] [1 [1 L] El Rerationship at reactivity and reactor power to rod moremei1I tj rs.i 032AA2.09 Loss of Source flange Ni /7 2.5 2.9 El LI LI El El U U U El El Effect of tel proper HV eettfrg CD OG3AA1 .01 LOSS of intemiedrate Range NI 17 2.9 3.l u [1 El El El LI E) U El U El Power-available lrxfcators In cabinets ci equipment drawers U
0 us Ui 036AK3.0l Fuel Handing Accident/B ai 3.7 [] El [I El LI El LI LI LI LI U Different Inputs that wlH cause a reactor building U,
evacuation oalAGal .19 Steam Generator rube Leakl 3 3-9 S.B LI El El [I L] LI [1 Li LI U LI Ability to use pPant coniputor to evaluate system Or component status.
D74EK103 Iriad. Core CoolirigI4 4. [1 [] [I LI C] C] LI LI El U Processes for removing decay heat from the core WEO2EK2.1 SlTemdnatlon/3 3.4 z 3.9 0 [1 U [] LI LI Li L] U LI Components and functions of control and safety systems. xi irleJuding fnslnirnerila&o, sljiai&, inle,1ocks failure C) niodes and automatic and manual features.
WEt SEK2.2 Containment Flooding /5 2.7 2.9 [] U LI El El El El [] 1] 1] FacliWs heat removal systems. lncludfn9 prlrnmy coolant, emergency coolants die decay heat removal systems and relations between the proper operation of these systems to the operalfon at the ?acllity.
weI6EG2.4.50 HibContakin,ent Radiation /9 4.2 4.0 UUElDElEIEIElElEl AbIlity to vodty system alarm setpoints arid operate controls idnidifled In the alarm response manual.
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ES-4OJ,RV 9 sno T3 PWR EXM*JATLON OUTLINE FORM E-4O12 KA NAME I SAFETY FUNCTION: Ki 1(2 K3 M 1(6 ice Al A2 A3 A4 0 TbPC:
no SIlO AbUIty to iocab ontroi room switofles, controls and 62.1.31 Conduct at operations E1flDDflOUDDEJ bidicalfone and to detennlno that th5y are cQfrecUy reflecting the liesired plant laiSup.
02.1.38 Conduct of operallons 3-7 3.8 DDOUDflDDOD] Krtowtedge t the stations reajjçemenIs fçj veibai communication han ImpIamntIng procedures Knowledge of thp preas for managing lmubiethoollng 022.20 Equlpnienl Control 2.6 3.8 OQEJflQQflflUfl activWe 02.2.30 Equlpm ant Control sq 4. IJQflflQ1fljFJflQ Knowledge f less than one haul Lecliiiical specification action statements for systems.
GaaJ4 Radlattori CcnIro 34 38 1<nowtedge of radlatton or contamination hazards that may arise dwing .iomial, abnormal, or eniergency condlttan& or activities 02.3;6 Radiation ConoI 2.0 aa Qj Ali[tty to aprove release pemilta z
C) 02.4.20 Elnergertoy Procedura&P?ans a 3.6 00 JL1LIU0LJDI Knowledge ci facdiltj protection requirements including lire lelgade and portable fire lighting equipment usage.
0 Page 1 cli Jl112/2000 2.OOPM
ES-301 Administrative Topics Outline Form ES-301-1 Facility: North Anna Power Station Date of Examination: 6/21/2010 Examination Level: Combined (See Below) Operating Test Number: 1 F Administrative Topic Type Describe activity to be performed (KA)
[ (see Note) Code*
Conduct of Operations M, R Perform the calorimetric heat balance (hand calculation).
G2.1.20 (ALL) (2.1.7, R04.41SR04.7)
D, R Determine time to boil (1-GOP-13.1, Att. 1).
Conduct of Operations G2.1 .25 (ALL) (2.1.25, RO 3.9! SRO 4.2)
M, R Evaluate and apply Tech Specs and procedure requirements Equipment Control G2.2.40 based on UNSAT condition of a plant component.
(SRO 2.2.37)
M, R Given an attached survey, determine entry requirements and Radiation Control G2.3.4 stay times associated with a given work activity.
(All) (2.3.7, RO 3.5 I SRO 3.6)
M, R Classify an emergency event (EPIP-1 .01)
Emergency Plan G2.4.29 Determine protective action recommendations (EPIP-1 .06)
(SRO ONLY) (2.4.41, RO 2.9 I SRO 4.6)
M, S, P Transmit report of emergency to State and local governments.
Emergency Plan G2.4.39 (RO only)
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; oo for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams ( 1: randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: North Anna Power Station Date of Examination: 6/21/2010 Examination Level: Combined (See Below) Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (KA)
(see Note) Code*
M, R Perform the calorimetric heat balance (hand calculation).
Conduct of Operations G2. 1.20 (ALL) (2.1.7, RO 4.4! SRO 4.7)
D, R Determine time to boil (1-GOP-13.1, Aft. 1).
Conduct of Operations G2.1 .25 (ALL) (2.1.25, RO 3.9! SRO 4.2)
M, R Evaluate and apply Tech Specs and procedure requirements Equipment Control G2.2.40 based on UNSAT condition of a plant component.
(SRO 2.2.37)
M, R Given an attached survey, determine entry requirements and Radiation Control G2.3.4 stay times associated with a given work activity.
(All) (2.3.7, RO 3.5 ! SRO 3.6)
M, R Classify an emergency event (EPIP-1 .01)
Emergency Plan G2.4.29 Determine protective action recommendations (EPIP-1 .06)
(SRO ONLY) (2.4.41, RO 2.9 !SRO 4.6)
M, 5, P Transmit report of emergency to State and local governments.
Emergency Plan G2.4.39 (RO only)
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; cc for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: North Anna Set A Date of Examination: 6/21/2010 Exam Level: RO SRO-l Q SRO-U 0 Operating Test No.: 1 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title (KA) Safety Type Code* Function a.) 026 / Terminate quench spray (1/2-E-1). (A4.05) C, D, E, EN, L b.) 005 / Restore RHR flow (1 .AP1 1). (A4.01) A, L, M, S 4 (Pri) c.) 001 / Borate the reactor coolant system using the blender (1-OP-8.3, 1-GOP-8.3.4, 1-OP-8.3.4). A, D, S 1
(A4.02) d.) 039/059/061 I Identify and isolate a ruptured steam generator (EA1 .32) A, M, S 4 (Sec) e.) 062 / Reset load shed (0-AP-47). (A4.01) C, D, E 6
f.) 073 / Restore the blowdown radiation monitors (1-E-1). (A4.02) D, E, S g.) 075 / Respond to circulating water flooding in the turbine building (0-AP-39.1). (A2.02) A, D, E, S 8
h.) 006 / Fill the safety injection accumulators (1-OP-7.3), 1-MOP-7.3). (A4.02) D, EN, S
[ In-Plant Systems (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U) i.) 063 / Place a battery charger in operation on the safeguards watchstation (1-OP-26.4.1, D 6 1-ECA-0.0). (A4.01)
[ j.)
k.)
003 / Isolate the reactor coolant pump seals locally (1-ECA-0.0, 1-ECA-0.2, 1-AP-33.2, B.5.b) 061 / Reset the auxiliary feedwater turbine trip and throttle valve (1/2-PT-71 .1 Q, 112-AR-F-D8, D, E, R 2 D, E 4 B.5.b)._(A2.04)
@ 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 serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Type Codes Criteria for RO / SRO-l I SRO-U (A)Itemate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9I8I4 (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power I Shutdown i 1 /* 1 (N)ew or (M)odified from bank including 1 (A)
- 2/
- 2 /
- 1 (P)revious 2 exams (similar topic) 3 / 3 / 2 (randomly selected)
(R)CA (S)imulator
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: North Anna SetA Date of Examination: 6/21/2010 Exam Level.: RO Q SRO-l SRO-U 0 Operating Test No.: 1 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title (KA) Safety Type Code* Function a.) 026 /Terminate quench spray (1/2-E-1). (A4.05) C D, E, EN, L b.) 005/ Restore RHR flow (1-AP-1 1). (A4.01) A, L, M, S 4 (Pri) c.) 001 / Borate the reactor coolant system using the blender (1-OP-8.3, 1-GOP-8.3.4, 1-OP-8.3.4). A, D, S 1
(A4.02) d.) 039/059/061 / Identify and isolate a ruptured steam generator (EA1 .32) A, M, S 4 (Sec) e.) 062/ Reset load shed (0-AP-47). (A4.01) C, D, E 6
f.) 073 / Restore the blowdown radiation monitors (1-E-1). (A4.02) D, E, S g.) 075 / Respond to circulating water flooding in the turbine building (0-AP-39.1). (A2.02) A, D, E, 5 8
h.) NOT USED FOR SRO-I In-Plant Systems (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U) i.) 063 / Place a battery charger in operation on the safeguards watchstation (1-OP-26.4.1, D 6 1-ECA-0.0). (A4.01)
[ j.) 003 / Isolate the reactor coolant pump seals locally (1-ECA-0.0, 1-ECA-0.2, 1-AP-33.2, B.5.b) D, E, R 2 k.) 061 / Reset the auxiliary feedwater turbine trip and throttle valve (1/2-PT-71 .1 Q, 1/2-AR-F-D8, B.5.b). (A2.04) 1 D, E 4 J
@ 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 serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Type Codes Criteria for RO I SRO-l I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrom bank 9I8/4 1 I (E)mergency or abnormal in-plant 1 / 1 (EN)gineered safety feature
- I - I
- 1 (control room system)
(L)ow-Power I Shutdown
- 1 I
- 1 I
- 1 (N)ew or (M)oditied from bank including
- 2 I
- 2/
- 1 1 (A)
(P)revious 2 exams (similar topic) 3 / 3 I 2 (randomly selected)
(R)CA 1I.1/1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: North Anna Set A Date of Examination: 6/21/2010 Exam Level: RO Q SRO-l Q SRO-U Operating Test No.:
Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title (KA) Safety Type Code* Function a.) 026 /Terminate quench spray (1/2-E-1). (A4.05) C, D, E, EN, L b.) 005 / Restore RHR flow (1-AP-1 1). (A4.01) A, L, M, S 4 (Pri) c.) 001 / Borate the reactor coolant system using the blender (1-OP-8.3, 1-GOP-8.3.4, 1-OP-8.3.4). A, D, S (A4.02) d.) NOT USED FOR SRO-U e.) NOT USED FOR SRO-U f.) NOT USED FOR SRO-U g.) NOT USED FOR SRO-U h.) NOT USED FOR SRO-U In-Plant Systemse (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U) i.) 063 / Place a battery charger in operation on the safeguards watchstation (1-OP-26.4.1, D 6 1-ECA-0.0). (A4.01) j.) 003/lsolatethereactorcoolantpumpsealslocally(1-ECA-0.0, 1-ECA-0.2, 1-AP-33.2, B.5.b) D, E, R 2 k.) NOT USED FOR SRO-U
@ 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 I SRO-I I SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)cntrol room (D)irectfrombank 9I8I.4 (E)mergency or abnormal in-plant 1 I. 1 I 1 (EN)gineered safety feature - I - I 1 (control room system)
(L)ow-Power I Shutdown i i 1 I* 1 (N)ew or (M)odified from bank including 1 (A)
- 2/* 2I* 1 (P)revious 2 exams (similar topic) 3/
- 3 I
- 2 (randomly selected)
(R)CA 1/1I1 (S)imulator
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: North Anna Set B Date of Examination: 6/21/2010 Exam Level: RO SRO-I Q SRO-U Q Operating Test No.: 1 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title (KA) Safety Type Code* Function a.) 001 / Respond to a misaligned control rod (1 -AP-1 .3). (A1.02) A, E, M, P, S 1
b.) 055 / Manually align condenser air ejector discharge to containment (i-E-3, SG Monitoring D, E, L, S 4 (Sec)
Prog.)._(A4.0i) c.) 003 / Respond to a loss of reactor coolant pump seal cooling (1-AP-33.2). (AA1 .22) A, E, M, S 4 (Pri) d.) 026 / Configure emergency bus loads to prevent emergency diesel overload (0-AP-lO). (A2.05) D, E, S 6
e.) 004 / Charging flow control valve fails closed (1-AP-49). (A4.06) A, D, E, S 2
f.) 073 / Respond to recirculation spray heat exchanger service water radiation monitor alarm C, D, E, P (1/2-AP-5)._(A4.01) g.) 006/ Transfer the safety injection system to the cold leg recirculation mode (1-ES-i .3). (A4.06) A, D, EN, S h.) 022 / Reduce containment pressure to subatmospheric (1/2-FR-Z4). (A4.04) C, A, D, EN In-Plant Systems (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U) i.) 004 / Align a charging flowpath locally. (A2.07) D, R 2 j.) 055 / Prepare the station blackout diesel generator for loading following an automatic start D, E, L 6 (0-OP-6.4), (EA2.03) k.) 061 / Align both motor driven auxiliary feedwater pumps to feed the steam generator by way of D, E, L 4 (Sec) the motor operated valve header (i-AP-22.i)._(A2.04)
@ 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 serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Type Codes Criteria for RO / SRO-I I SRO-U (A)ltemate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irectfrom bank 9I8I4 (E)mergency or abnormal in-plant 1 I 1 /* 1 (EN)gineered safety feature - I - I 1 (control room system)
(L)ow-Power I Shutdown
- 1 I
- 1 I
- 1 (N)ew or (M)odified from bank including 1 (A) 2I* 2I 1 (P)revious 2 exams (similar topic) 3 I 3 I :2 (randomly selected)
(R)CA 1I1I1 (S)imulator
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: North Anna Set B Date of Examination: 6/21/2010 Exam Level: RO EJ SRO-I SRO-U Q Operating Test No.: 1 Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title (KA) Safety Type Code* Function a.) 001 I Respond to a misaligned control rod (i-AP-1.3). (A1.02) A, E, M, P, S 1
b.) 055 / Manually align condenser air ejector discharge to containment (1-E-3, SG Monitoring D, E, L, S Prog.)._(A4.01) 4 c.) 003 / Respond to a loss of reactor coolant pump seal cooling (1-AP-33.2). (AA1 .22) A, E, M, S 4 (Pri) d.) NOT USED FOR SRO-I e.) 004 / Charging flow control valve fails closed (1-AP-49). (A4.06) A, D, E, S 2
f.) 073 I Respond to recirculation spray heat exchanger service water radiation monitor alarm C, D, E, P (112-AP-5)._(A4.01) g.) 006 / Transfer the safety injection system to the cold leg recirculation mode (1 -ES-i .3). (A4.06) A, D, EN, 5 h.) 022 / Reduce containment pressure to subatmospheric (1/2-FR-Z4). (A4.04) C, A, D, EN In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
I.
j.)
004 / Align a charging flowpath locally. (A2.07) 055 / Prepare the station blackout diesel generator for loading following an automatic start D, R
[ 2 D, E, L 6 (0-OP-6.4), (EA2.03) k.) 061 I Align both motor driven auxiliary feedwater pumps to feed the steam generator by way of j
[
D, E, L 4 (Sec) the motor operated valve header (1-AP-22.1)._(A2.04)
@ All RO and SRO-l control room (and in-plant) systems must be different and serve different satety 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-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank (E)mergency or abnormal in-plant :9I!:8I!:4 1 / 1 I* I (EN)gineered safety feature I - I
- 1 (control room system)
(L)ow-Power I Shutdown
- 1 I
- 1 I
- 1 (N)ew or (M)odified from bank including 1 (A)
- 2/ 2I* 1 (P)revious 2 exams (similar topic)
- 3 / 3/
- 2 (randomly selected)
(R)CA 1I1I1 (S)imulator
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: North Anna Set B Date of Examination: 6/21/2010 Exam Level: RO EJ SRO-I EJ SRO-U Operating Test No.: 1 Control Room Systems 5 (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title (KA) Safety Type Code* Function a.) NOT USED FOR SRO-U b.) NOT USED FOR SRO-U c.) 003 / Respond to a loss of reactor coolant pump seal cooling (i-AP-33.2). (AA1.22) A, E, M, 5 4 (Pri) d.) NOT USED FOR SRO-U e.) 004 / Charging flow control valve fails closed (1-AP-49). (A4.06) A, D, E, S 2
f.) NOT USED FOR SRO-U g.) 006 / Transfer the safety injection system to the cold leg recirculation mode (1 -ES-i .3). (A4.06) A, D, EN, S h.) NOT USED FOR SRO-U In-Plant Systems (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U) i.)
j.)
004 / Align a charging flowpath locally. (A2.07) 055 / Prepare the station blackout diesel generator for loading following an automatic start D, R
[ 2 D, E, L 6 (0-OP-6.4), (EA2.03) k.) NOT USED FOR SRO-U
@ 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 serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Type Codes Criteria for RO / SRO-l I SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrom bank (E)mergency or abnormal in-plant 1 I I I (FN)gineered safety feature - I - I 1 (control room system)
(L)ow-Power I Shutdown i i
- 1 I 1 (N)ew or (M)odifled from bank including 1 (A) 2/ 2 I 1 (P)revious 2 exams (similar topic) 3 / :3 / 2 (randomly selected)
(R)CA lI.1I.1 (S)imulator