ML041070253
| ML041070253 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/19/2004 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-280/04-301, 50-281/04-301 | |
| Download: ML041070253 (21) | |
See also: IR 05000281/2004301
Text
Final Submittal
SURRY EXAM
50-280, 50-281 /20Q4-301
FEBRUARY 24 - MARCH 2
& MARCH 4,2004 (WRITTEN)
... .
PWR Examination Outline
Form ES-401-2
Facility: Surry
Date of Exam: 2004
Note: 1.
2.
3.
4.
5.
6.
7.
h.
1.
Ensure that at least two topics from every WA category are sampled within each tier
of the 80 outline (i.e., the Tier Totals in each WA category shall not be less than
two). Refer to Section 69.1 .c for additional guidance regarding SRQ sampling.
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 51
from that specified in the table based on NRG revisions. The final RO exam must
total 75 points and the SRO-only exam must total 25 points.
Select topics from many systems and evolutions; avoid selecting more than two WA
topics from a given system or evolution unless they relate to plant-specific priorities.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the categoryitier.
The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the %(/A
Catalog, but the topics must be relevant to the applicable evolution or system. The
SRO WAS must also be linked to 10 CFW 55.43 or an SWO-Bevel learning objective.
On the following pages, enter the WA numbers, a brief description of each topic, the
topics importance ratings (IR) 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; summarize all the SRO-only knowledge and non-A2 ability categories in
the columns labeled K and A. Use duplicate pages for RQ and SRO-only exams.
For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals
on Form ES-401-3.
Refer to E%-401, Attachment 2, for guidance regarding the elimination of
inappropriate WA statements.
22 of 34
NUREG-1021, Draft Revision 9
PWR Emmrnation Outline
Form ES-401
Emergency a
Abnormal Plant Evolutions - Tier l/Group I (ROJ I SRQx)
000015/i7 RCP Malfunctions I 4
000022 Loss of Rx Coolant Makeup / 2 I
000025 LQSS of RHR System / 4
000026 Loss of Component Cooling
Water I 8
000027 Pressurizer Pressure Control
Svstem Malfunction / 3
000029 AVVVS I 1
000038 Steam Gen. Tube Rupture / 3
0OQ840 (BW/EO5' CWE05. W/E12)
Steam Line Rupthe - Exc&ssive Heat
Transfer I4
000064 (CUE06) Loss of Main
Feedwater / 4
000058 Loss of Off-site Power / 6
000858 Loss of M: Power I 6
000862 LOSS of Nuclear Svc Water / 4
300065 Loss of Instrument Air / 8
WE04 LOCA Outside Containment / 3
X W . 3 9 AbLL3y lo drlermho 0. Interpret the IoilowiF as
4514.7
1
I I
I they swiy to a tmll break LOCA: A e q w l c core cooli%p
J EK3.09: Knvded
sons for the fdl
a of the in:errelntions bel-en the
nzapim 01 all Steam Generatmi end the
remval systems. including pnhary
Ian!. the decay heat m v a l system and
oper aperabon of these systems 10 the
J J 2.4.31: Know&
e of annuncialo?s. d a m . acd indicF.btms and I 3.31 3.4 I 1
l l l l l
use 01 response in.s$ructions.
23 of 34
NUREG-1 021 I Draft Revision 9
s of Emergency Coolant
NUREG-1 021, Draft Revision 9
E§-401
Emergency and Abnorm
I
1:
WAPE #I
Name I
Safety Function
000032 Loss of Source Range NI I7
000033 Loss of Intermediate Range NI / 7
000036 (BWIAO5) Fuel Handling Accident I 5
OOOU37 Steam Generator Tube Leak I3
000051 Loss of Condenser Vacuum / 4
030059 Accidental Liquid KadWaste Bel. i 9
030061 ARM System Alarms I 7
~
000074 (WIEOfXE07) Inad. Core Cooling / 4
OOQO76 High Reactor Coolant Activity i
9
WE01 & E02 Rediagnosis & SI Termination I3
WE13 Steam Generator Over-pressure i
4
W/E45 Containment Flooding I 5
IK Examination Outline
F
o
~
E$-401-2
lant Evolutions -Tier IiGroup 2 (ROJ I SRBx)
,
1
1
1
1
I
I
.Ut: Abili!y to d e e m s and Nlterprel the
p as they
10 Me 5
Rad,ta:im
ng (ARM) ys em- Nams ARM panel
25 of 34
NUREG-1021, Draft Revision 9
BW!A07 Flooding I E
26 of 34
I
E
NA
I
I
I
I
I
-
I
I
NA
I
1
NUREG-1Q21 , Draft Revision 9
27of 34
e
Form ES-IIOl-.
iJ / SRQX)
I
I
I
'
R
I #
WA Topic(s)
x 2.:.52 Abillly Io eaplaln anit apply all
5.613.9
1
rystsrn lirnnr and precuallunr.
I
I
d K5.M: Know'ed e 01 the werational
3.1 13.4
1
vnp(ications GI
the?ollodn concepts as they
ap ly to BRTS: Msth~d
of tming a steam
bligble in the PZR.
I
I
tSFW.
and lest swtches.
malfunctioe d the 8 F . G vili have on lhw
Wlowin Fuel.
.r A3.d Abaitylomnitorautomstic operation 1 4.1 14.2 I 1
of the ESFAS including Operatian of acfuztd
3 6 1 3 9
35/36
d A2.M: Ability to (a) predict the impacts 01 the
followirp mI4wa1m5 or 0 erStionS On the
Condenszts Syslm; and 8, based on those
predytcms. use prmedrrres to correct. cQntro1,
or m.tjgate the cons8CdmCe.9 of thwe
mallundions oropera:iono: Lo= ol condensate
pumps.
2.812.8
1
d A l . 0 3 Ahilitv to oredict and I or nonilor
I 2.7 12.9 1 1
NUREG-1 021, Draft Revision 9
061 AuxiliaryiErnergency
062 AC Electrical Distribution
073 Process Radiation
076 Service Water
! I
838 Instrument Air
NUREG-1821, Draft Revision 9
nmatton Outline
YGroup 2 (ROJ I SROx)
Form E
IR
PWW Ex:
items - Tie
WA Topic(sj
System # I Name
K
K
K
1
2
3
I
l
l
I l l
001 Control Rod Drive
2.5/2.8
3.9 14.1
3.7 13.8
01 1 Pressurizer bevel Control
014 Rod Position Indication
/ K4.07: Kno?uledge of NIS d&gn,feature(s) and 1
or in!erlock(s) prwde :or me following: Pemseves.
2.9 i 2.8
017 In-core Temperature Monitor I I 1
J
/ A4.03: AbiMy to naanwa!ly 0 @rate and ior
I mnitm in the contml room. ClfiS fans.
B
I
I
3.3 13.2
027 Containment Iodine Removal
3.013.4
028 Hydro en Remmbinei and
Purge C o n h
029 Containment Puroe
I l l
Not SelRctnd.
3.3 19.7
/ A4.01: hili@ to m u a l l y opqale ard / Q?
m i l o r in tha conim! mam: Ra(Ia1.m lwels.
Not SBFe*ed.
Not SdBCLed.
035 Steam Generator
I l l
4.0 / 3.9
045 Main Turbine Generator
055 Condenser Air Removal
I l l
068 Liquid Radwaste
3.414.1
2.7 13.5
071 Waste Gas Oisposal
079 Station Air
I l l
3.513.8
WA Category Point Totals
29 of 34
NUWEG-I 021, Draft Revision 9
Administrative Topics Outline
Form ES-301-1
Administrative Topic
Conduct of Operations
Csndud Of Operations
Equipment Control
Radiation Control
Describe activity to be performd
Calculate the Maximum Allowable Reactor Vessel Hydrogen
Venting Time
G2.1.23 (3.914.8); 621.25 (2.W3.1)
Shutdown Margin CalcuEation at Peso Power
G2.1.7 (3.7144
Construct Tagout for 1 -RT-P-IC (SG Recirc & Transfer Pump)
G2.2.13 (3.6/3*$)
Dose I Stay Time Calculation
G2.3.1 (2.W3.1); G2.3.4 (2.E~/3~1)
VOTE: Ail items (5 total) are r@quirecJ for SROs. RO applicants require only 4 items unless
bey are retaking only the administrative topics, when 5 are required.
NUREG-1021, Draft Revision 9
Administrative Topics Outline
Fom ES-301-1
i
.
FaeiBky: Sursy
Examination Level (Underline one): RO / SRO
Date of Examination: FEB200r
Operating Test Number: 2004-331
Administrative Topic
Conduct of Operations
~~
~
Equipment Control
3adliatioss Control
- mergency Plan
Describe activity b be performed
Calculate the Maximum AElawable Reactor Vessel Hydrogen
Ventlwg Time
(32.1.23 (3.9A.h)); 62.1 25 (2.W3.1)
Shutdown Margin Calculation at Zero Power
G2.1.7 (3.714e4)
Construct Tagout for 1 -RT-P-1 C (SG flecirc & Transfer Pump)
62.2.13 (3.tY3.8)
Dose / Stay Time Calculation
62.3.1 (2.tY3.1); 62.3.4 (2.93.1)
Emergency Classification
2.4.41 (2.341); 2.4.44 (2.1f4.8)
KITE: All items (5 total) are required for SflOs. 80 applicants require only 4 item unless
hey ere retaking only the administrative topics, Wen 5 are requir
NUWEG-1021, Draft Revision 9
Contrd Roodln-Plant Systems
Form ES-301-2
Outtine
Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
a. start P RCP / High Vibratloar
015AA1.M (3.113.2)
N A S
4,Iimv
b. Place Hydrogen Analyzer In Service Fdlowlng LOCA (58.01)
028A4.03 (3.1i3.3)
D S
5
C. O-AP-Z.O(p, Fuel Handling Abnormal Condiibn Imsnddiste Actions (35.06)
D A S
034A2.01 (3.W4.4);
03W1.01 (3.S4.1)
8
d. Restore Offsite Bwdestc SH 4%BQV
Emergency Bus IAW AP-10.08 (f8.06)
6
of32A4.01 (3.33-6); owEA2.08 (3.7/4.1)
I
I
8. Transfer to Hot Leg RecLrcuhtlon with 1 Chaqhg Pump in Sewice (52.02) - ESF
011EF11.11(4.Z4.2)
I
I
I
I
I
I
I
2
I
I
1
I
I
7
In-Plant Systems (3 for WO;
3 for SWQ-I;
3 or 2 far SRO-U)
. ems-Tie Unit 2 Emergency Buses for Circulating Water IMtion (35.02)
D
062A2.12 (3.El.6); 062AA2.02 (2.913.6); 07682.06 (3.5B.7); 056pIA1.02(4.0/3.$)
6
.
Locally Emmer@ncy Borate per ABP-3.0, Emergency Eoratim (44 .048)
024AA1.04 (3.6k3.7)
D A R
1
NUREG-1021, Draft Revision 9
ES-38 f
GorPtroJ Roodln-Plant Systems
Form ES-301-2
OutBine
. 7 n . s ) ; o S s ~ . ~ ( 3 . ~ 4 . 4 )
dified from bank, (N)ew, @)Itemate path, (@)ontrol
NUREG-1 021, Draft Revision 9
Control RoodBn-Plant Systems
Form ES-301-2
Outline
Facility: Surt-y
Exam bev@i (underline one): RO / SROrl)/ SRO(U)
Date of Examination: FEE3200
operating Test No.: 2004-30'
Control Room Systems (8 for WO; 7 for SWO-I; 2 or 3 for SWO-U)
System / JPM Title
Safety
Function
Code"
N A S
8. stars P RCP / High Vibration
015ABI 2 3 (3.1B.2)
b.
D A S
8
C. O-AP-22.6)0, Fuel HaMIlng Abnormal CondMcri Immediate Actions (38.06)
044A2.01 (3.614.4]; 03MK1.01 (3.S4.1)
d. Restore ~
i
e
powerto i H 41~3011 ~mergmncy BUS I ~ W
AP-IO.OB (18.06)
Q6A4.08 (333.1); 0 5 5 ~ . 0 6
(3.914.1)
8. Transfer to Hot Leg Recirculation wwI 1 Charging Bump in Senrice (52.02) e ESF
Ol'lEAl.ii(4.2/4.2)
3
M A S
N L S
4-p1
D A S
2
g. Response to f a W 1w Pressurizer bevel Channel (38.07)
028AAI .OB (3.7t3.6)
D S
7
7. Remove B failed Saume ban* NI hsm Service During a Reactor Startup (52.02)
51582.02 (3.105); 6)156\\4.03[3.&r3.9)
In-Plant Systems (3 for RO;
3 for SRO-I; 3 or 2 for SRB-U)
. Cross-Tie Unit 2 Emerggncy Eluses for Clrcuiathg Water Isolation (35.02)
062.42.12 (3.2EI.5): 062w82.02 (2.9136); 075A2.01 (3.5B.7); 056AAI.O2(4.OB.9) B
6
.
Locally Emwgency Borate per AOP-3.0, Emergency Bomtion (4t .59 B)
024AA1.04 (3.6B.7)
D A R
1
NIBREG-IMI, Draft Revision 9
Control Rosdlss-Plant Systems
Form ES-301-2
Outline
0
a NUREG-1021, Draft Revision 9
Control Waodln-Plant Systems
FQhm ES-301-2
Outline
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, @)Iternate path, (C)~ntrol
Facility: Surry
Exam Lewd (underline one): RO / SRO(1) 1 SROlUl
Date of Examination: FEW004
Operating Test No.: 2804-301
Control Room Systems (8 for RO; 7 for SRO-E; 2 Of 3 far SRO-U)
System / JPM Titie
8. Stslrt 2" RCQ I High Vbtion
015M1.23 [3.1/3.2)
N A S
b.
3. Transfer to Hot Leg Recirculatim with 1 Charging Pump in Sewice (52.02) - ESF
If!! A s
I
01 1 -1.1
1 (4.Y4.2)
/. Swap operating Main Fedwater Pumps due to preblms with operating pimp
N L S
059A4.08 [3.QM.!3)
3-
~
1.
In-Plant Systems (3 far RO; 3 for SR8-I; 4 or 2 for SRO-Ug
Safety
Function
3
,
Locally E r n e ~ w
Borate per AOP-3.0, Emergency Boratlon (41.01 5)
024AA1.04 (3.813.7)
D A R
1
NUREG-1021. Draft Revision 9
Control Wsodln-Plant Systems
Form ES-901-2
Outhe
k. Cross-Connect Turbine Building Instrument Air (17.02)
065AK3.04 (3.W3.2); 078K1.03 (3.33.4);
ossAK3.6ls(3.7/3.q;o~~~.~2(3.~/4.4
Appendix D
Scenario Outline
Form E§-D-1
Facility: Surry
Scenario No.: Scenario #1
Op-Test No.: 2004-301
Examiners:
Operators:
Initial Conditions:
75% Reactor Power
Known leakage in 1 A Steam Generator
Thunderstorms are approaching from the West
Turnover:
Shift orders are to maintain ~ Q W W at 75%.
Event
NO.
1
(N)orm
MWC-15
c
MEL-27 I
C
Event
Description
(ROISRO) boss of C@ to NWHX requiring normal letdown to
be secured.
(BOP/SRBJ Place excess letdown in service.
(RO/ sao) Median select Tave fails high.
(BOP / SRQ) f -FW-LP-I 476 1A Steam Generator Level
Transmitter fails law. Ramped to allow adequate operator
response to gain control of SG level prior to trip on steam /
feed mismatch.
(RB/ SRO) Pressurizer Pressure Controller (PC-444A /
Channel 1) fails high. Ramped to allow adequate operator
response to gain contror of pressure.
(BOP sao) 16 Steam Generator tube leak with failure of
Condenser Air Ejector Rad Monitor auto actions.
(ALL) 1 C Steam Generator tube rupture coincident with Loss
of Offsite Power.
(BOP / sao) #3 Emergency Diesel Generator fails to start.
EDG can be manually started from tke Control Room.
I
(f?)eactivitys (Ijnstrurnent, (C)ornponent, (Mjajsr
Appendix D
Scenario Outline
Form ES-6)-1
Scenario No.: Scenario #2
Op-Test NO.: 2004-301
Examiners:
Operators:
initial Conditions:
58% Reactor Power
Known leakage in 1A Steam Generator
Thunderstorms are approaching from the West
1-EH-P-MP2 (EHC Pump) is Tagged Out of Service for Thermal Overload Replacement
Turnover:
Shift orders are to maintain power at 50%.
Event
Malf.
I
No.
NO.
3
I MMS-14
7
I MTU-09
Event
Type*
c
c
I
c
c
l
c
M
C
c
Event
(mws~o) Bearing Cooling Water Pump trips and standby
pump fails to auto start.
(RO/SRO) Letdown Divert Valve fails open.
(aomo) Selected 1 Stage Turbine Pressure Transmitter
fails low (MS-PT-446)
(RO/SRO) Pressurizer Level Controller fails low.
(ROISRO) Tavg Taylor Math Unit Fails low.
(eopwao) Selected 1 B Steam Generator Steam Flow
Transmitter fails high.
(BOPISRO) Turbine Governor Valve fails closed. Ramp in
slow enough for BOP to detect and respond.
(ALL) LBLOCA - Auto Reactor Trip
(BOP/SRO) Turbine fails to trip and Gen Brks fail to open.
(RO/SRO) Both trains of Safety lnjection Fail to automatically
actuate. Manual actuation from the control room is
necessary.
I
I
- (N)ormal, (Rjeactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix B
Scenario Outline
Form ES-B-1
Facility: Surry
Exarni ners:
Operators:
Scenario No.: Scenario 3
Initial Conditions:
Reactor Power is 75%
Known leakage in 1 A Steam Generator
Thunderstorms are approaching from the West
Turnover:
Shift orders are to raise power immediately following turnover.
Event
Description
(ROISRO) Raise power. (Rods initially should be positioned to
prompt dilution, as opposed to rod puBt)
(RQ/SRO) FT-CH-I 1 14, Primary Water Flow XMTR fails low.
(BOPISRO) 1 -CN-P-I A Condensate Pump Performance
Degradation ramped in t~ require timely operator response.
Failure of standby pump auto stat Manual start required.
(BQPISRO) 1 A SG MFW Flow XMTR fails low.
(BOPISRO) 18 S/G PORV Controller Fails high.
(RWSRO) lsslable letdown line leak in containment.
(ALL) Main Steam Line Break in Containment in 18 Steam
Generator.
(RO/SROJ Auto and Manual Reactor Trips fail.
(wasao) Failure of one HI CLS Train To Activate.
(BOPISRO) Failure of 4-CC-TV-105A (CCW return from RCP
1A) to close on Phase Ill Isolation.
I
I
I
(N)ormal, (W)eactivity, (i)nstrument, (C)omponent, (M)ajor
Appendix D
Scenario Outline
Form ES-D-1
Facility: Sur9
Scenario No.: Spare Scenario
Op-Test No.: 2804-301
Examiners:
Operators:
initial Conditions:
100% Reactor Power
Preparing to conduct partial rod movement testing.
Turnover: Off normal conditions for Unit 1 : 1 -RC-PICV-I 5578 (Excess Letdown) is isolated
due to ieakby, 1 -EH-P-MP2 (EHC Pump) is tagged out for thermal overload replacement.
Unit 2 is at 1 0Q% power with 2-W-P-2 (TDAFW Pump) tagged out for governor
repiacernent.
earn Driven AFW
I
I
I
(N)orrnal, (R)eactivity,
(I)nstrurnent, (C)omponent, (M)ajor