ML020910678
| ML020910678 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/15/2002 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-369/02-301, 50-370-02-301 50-369/02-301, 50-370/02-301 | |
| Download: ML020910678 (77) | |
See also: IR 05000369/2002301
Text
Draft Submittal
(Pink Paper)
1. Written Exam Sample outlines
MCGUIRE EXAM
50-369, 370/2002-301
FEBRUARY 11 - 15, 2002
Copy 1 of 3 McGuire Sample Plan
Form ES
Facility: McGuire Date of Exam: 2/22/02 Exam Level: RO
K/A Category Points Point
Tier Group
1
I 2
K
3 4 5 6 1
A
2
A
3
A
4
Total arget
16
17
2 4 2 5 2 2 17
Emergency &
3
3 0 1 0 W, __ 3
Abnormal
Plant Tier
36
Totals 6 4 9 8 5 36
Evolutions '4
4 3 1 2 0 4 1 1 1 23 23
1 4 2
20
-- -20 r3 3 1 2 3 20
2r2-
0 1 0 1 0 3 1 1 0 8 8
Plant 3 0 1
Systems Tier
51
7 6 3 3 3 10 3 4 4 51
Totals 5 3
3 Generic Knowledge and Cat I Cat 2 Cat 3 I Cat 4
13
Abilities 4 3 3 3 13
Totals:
Note: 1. Ensure that at least two topics from every K/A category are sampled
than
within each tier (I.e., the "Tier Totals" in each K/A category shall not be less
two).
outline must match that
2. The point total for each group and tier In the proposed
specified in the table. The final point total for each group and tier may deviate by
+/-1 from that specified in the table based on NRC revisions. The final exam must
total 100 points.
3. Select topics from many systems; avoid selecting more than two or three K/A
topics from a system unless they relate to plant-specific priorities.
outline.
4. Systems /evolutions within each group are identified on the associated
5. The shaded areas are not applicable to the category/tier.
6.
of the K/A
The generic K/As in Tiers I and 2 shall be selected from Section 2
or system.
Catalogue, but the topics must be relevant to the applicable evolution
7. On the following pages, enter the K/A numbers, a brief description of each topic,
totals for
the topic's importance ratings for the RO license level, and the point
justified on the basis of
each system and category. K/As below 2.5 should be
in the Table
plant specific priorities. Enter the Tier totals for each category
above.
12/10/01
Summary For Official Use Only Until After 2/22/02
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KK K 3 1K 1K A 1 A1A
A G K-iAToplo(i) Imp. points Ouestion
SyK1em12NKme
Abc~dyto monitor automatic operation of tpe...Mtdpstldof odladlity at any
Ime when adding positve reactivity -3/49140 86U
001 Coatrol Rod Did.e 3.081
K1oospledge or the affect Mat a lose Or malfurnotioawit have on ,,.Str/og
eulntet 2,6/2S 1 867
003 IReactodr Coolant Pump 6.14
Knowedasdg of bus pownt supplies to.. .o*dtw inatrunmontaloat 2"/2?1 885
004 Chemical Volume Control 2.0
milityto pr edctt h im pac alot I hefollowdng r n lfuc oarperat ed,. i d
bided cn those padictlons. use procedures to correct, c*nloo or onalgatethe
46W48 1 540
2,01
2I01 coleuences of. LOCA
013 Eng~n*ered Sefety Features A*ctaton
Knowledge of pyslcal connecut/oe and/or cause and effect
IS 30/33 893 1
I relatioripe..
014 Rod Position Indicationl10A
KrnoýtMac,of des/on feature(s) and/or nledcck(a) which provIde for, Sorc
range detector hut ff al high powers 878
01)1 1 .rl n r[,Gu4,1)1tttlon 410
0
Ktorwladgeof The effect anal a lose or ma/function w.ill have on Natural
ciculatlon Indications 3.5"/37 911
017 In-core Temperature Monitor 301
I 658
1422 Kn(ow/edoa.1 the bases for prIorItizIn Safety functions duri*n abnormal / nme 30/40
022 Containment Cooling
AbIlityto prod/cl the impacts 0f the toilowicg nalniton cc operation and
based on those predictions. use procedures 1Ocorrect, control Or mitigate Mte
consequences of .High/low fior coolingtemperature 27-12,5 1 681
025 Ice Condenser 1202
Knowledge of ae effoct Ial loss or malftncton - wl have on
1 ReWlreulatori sprla sy-M ase4 , e
026 Containment Spray 3 02
knowledge of physical connections and/or cause and effect
856 Condensate 1 03 relaionships MFW 26 826 1 4151
Know/edge of physicai convectiora and/or ca*se and effect
relationships ./G, 3S1/33 1 14
059 Mea/ Feedweatr 0 . .
Krowledge of the affect that a ions or malfunction .wilthave or .6/0 4 2/44 r 16 I
oat Au/ltlarv/Emerganlcy Feadwatar 3.02
control room Battety
S
0613DC Eecrtrial 4 03 disoharga rate
Abilityto manually operate and/or monitor in the 30"31 1 8819
Abilityto manbaliy operate and/or monitor in the conrtol room BattStoppage
of
3 9/3 8 1 407
403 relese ifliri tare eceeded
088 Liquid Red Waste
KnOWledge of physical cornections and/or cats, and effect
3 113 1 771 1
-relationshps. ARM and PRM syste..
071 Waste Gas Disposal 106
Ai/lily to predict The impacts or the folow/mg malfunotrt or operation.. and
based on those priedfifchorsuse procedures to correct,control or mitigate the
2 N2o9 1 No
-case/qUcfh 2 02 of.. Detector tors
072 Area Radiation Monitoring
containment cooling fans 3 0'`3 1 1 898
201 Kowledge of bus power supplies to
022 Contain* .t. Cot*/* g
Antry to manually operate andlor nortior In the control room.. LOss of
423N
=2OreouS/ont 1 0.. 4. 1 2J1 Total 10 10 1
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Cate I K/A # Topic Im . Points 1 Question
,.A tarift, rnnfrniiad nrnr.srliirs cony 13.1/3.2
1 143.1
21.2 t~bl'iIty to. oJI an e u
Ability to perform specific system and integrated plant procedures during all modes
3.9/4.0 1 331.1
Conduct of 2.1,23 of operation
Ability to locate switches, controls and indications and to determine it they are
lineup 4.2/3.9 1 164.1
Operations 2.1.31 correctly reflecting the desired plant i~~~ ~~ d4icnrle
oeuacp .1.
4
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(multi unit) Ability to explain the variation in control board layouts, systems, 2.8/3.0"
260.1
2.2.4 instrumentation, and procdra.Ullac onusl aL~l an *= *,,- ...
f o
2..3 Koweg
otrlporamn 2.5/2.9 16.
Equipment
Control
33
2.5/2.9 1 124
2.3.2 Knowledge of facility ALARA program
Knowledge of radiation exposure limits and contamination control including 703.1
2.5/3.1
Radiation 2.3.4 permissible levels in excess of those authorized
Control
3
____________ I3
I I........ . 2 9/3.4 910
2.4.25 Knowledge or lire proneciion proceuuua...
Knowledge o acili pro*,rcon requireaents including tire bnigae* and po*tble lire 889
12.9/3.3 1
2.4.26 fighting equipment usage
Emergency
Procedures
and Plan
3 3
Tier 3 Point Total 13 131 13
For Official Use Only Until After 2/22/02 12/10/01
Generics
Copy 1 of 3 McGuire Sample Plan
_2
Facility: McGuire Date of Exam: 2/22/02 Exam Level: SRO
K/A Catego Points Point
Group K K KK 5 6 A A A A G
Tier Total Iatgnt
6I 1 2 3 14
131 2 3
6 2 0M J2 24 24
2 16 16
Emergency & 2 3 2 3 2 4
3 0 1 0 0 1 X 1 3 3
Abnormal
Plant Tier J
Evolutions Totals 6 4 9 , 4 Nn
15*i; 5 43
43
19
0 0 2 2 2 1 3 4 0 1 2 17 17
2 2
3 0 0 0 1--- 0 0--- 1 -- 1 0 4 4
Plant
Systems Tier
Totals 4 2 5 4 2 2 3 9 2 4 3 40
40
Cat 1 Cat 2 Cat 3 Cat 4
3 Generic Knowledge and 17
Abilities1 5 4 4 4 17
Totals
Note: 1. Ensure that at least two topics from every K/A category are sampled
within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than
2. The point total for each group and tier in the proposed outline must match that
3. Select topics from many systems; avoid selecting more than two or three K/A
topics from a system unless they relate to plant-specific priorities.
4. Systems /evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.
6.
The generic K/As in Tiers I and 2 shall be selected from Section 2 of the K/A
Catalogue, but the topics must be relevant to the applicable evolution or system.
7. On the following pages, enter the K/A numbers, a brief description of each topic,
for
the topic's importance ratings for the SRO license level, and the point totals
each system and category. K/As below 2.5 should be justified on the basis of
plant specific priorities. Enter the Tier totals for each category in the Table
above.
For Official Use Only Until After 2/22/02 12/10/01
Summary
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001 Controal Rod Des308
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401
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Knowledgnaes nofM a lsseor rat
yofuMa sodrt wil haveon iar
3 7
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301 cIrculation Indications
011 In-eon. Temperature Monitor
Knowledge ofthe bases for prionitining safetyfunctions during abnormal/
30140 I 858
- 4.22 emergency openations
022 Coentainment Cooling
3 0"/3 1 t 898
201- - - - - - - - - Knowledge of bus power supnes to. containment cooling fans
022 Containment Cooling
Abilityto predict teaimpacts of the followingmalfunction operation. nd
based on those predo*ions, use procedures to coaTed. control oa mittgate the
S of. Higintlaw toot coolng ternperature 27-12S 1 581e
- - - - - - 2 02 coom mnoseuct
t25Ic Condenser
Knowledge of physicalconnections andulorcause and effact
2612S 1 4151
1 3Ablity netationsahipsMFW 1 1914
04 C.onlldensate. 3..
to manually oparate and/or monitortn e 11133
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,56 Condeneat. a a ti na ip*
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Conduct of Ablt o1Ct wths otosadidcations and to determine-i tey are
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2..3 Knowledge of rod control programming 2.563.9
Equipment
Control
Total
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Knowledge of facility ALARA program
Knowledge of
permissible radiation
levels eJ(xposure
in excess of those and co-nta-min-atio-n-c=4
10111sauthordzed Including 1251.
Radiation
Control
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2425 Knowledge of fire protection procedures 1
Knowledge of facility protemtion requirements including tire brigade and portable i re
2.4.26 fighting equipment usage
Emergency
Procedures
and Plan
4 4
Toter 3 on oa 7 17 1
For Official Use Only Until After 2/22/02 12/10/01
Generics
NRC Written Exam Sample Plan Development Method
The sample plan was developed in accordance with the methodology recommended by
the NRC in Attachment 1 of ES-401. The following statements amplify this process.
Differences of Method: The sample plan was developed using the random number
generation function of Excel instead of using tokens. The random number generation
function is programmed to produce an evenly distributed random number between 0 and
the number entered into the argument of the function. For example, if the number 20 is
entered as the argument, the function produces a resultant between 0 and 20 on an evenly
distributed random basis. The result is mathematically equivalent to using the method of
selection by tokens.
Initially, all K/A E/APE, System and Generic topics listed in ES-401 are screened and
those topics that apply only to B&W or CE are eliminated. All NRC K/A topics and all
Westinghouse (WE) E/APEs are retained for sampling. Using the selection methodology
described in Attachment I to ES-401, an Excel spreadsheet is used to generate the RO
examination. When the K/A is randomly selected, the author manually enters the
corresponding K/A stem statement, the K/A description and importance rating from
SRO Exam Samoline: The SRO examination spreadsheet automatically imports all
applicable RO K/As into the corresponding Tiers and Groups in the SRO sample plan.
The final outcome results in 89 K/As that are common to both the RO and the SRO
sample plans. There are 7 E/APEs and 4 Generic SRO-only K/As that must then be
randomly selected to increase the number of questions to 100. These K/As are restricted
to those K/As that are identified as having ties to 1OCFR55.43(b) in NUREG 1122 for
those K/As in Tiers 1 and 2. For Tier 3 (generic K/As), one additional SRO-only K/A is
randomly added to each of the four K/A generic categories. It should be noted that there
are very few generic K/As that were explicitly correlated to 10CFR55.43 in NUREG
1122 (and no generic K/As in category 2.3 (Radiation Control) although
1OCFR55.43(b)(4) states: "Radiationhazards that may arise during normal and
abnormalsituations, including maintenance activities, and emergency situations.') This
seems inappropriate, as one of the primary differences between the jobs of RO and SRO
is the SRO responsibility for plant administrative tasks. Therefore, all generic K/As are
randomly sampled when adding the fourth K/A to each generic category. These are then
reviewed to ensure that an SRO-only question can be drafted to the K/A.
This produces an exam outline with 100 K/As of which 89 are common to both exams
and 1 are unique to the SRO exam. Similarly, there will be 11 system K/As that are
used on the RO exam but not used on the SRO exam due to the larger number of RO
system K/As in the sample plan.
During the exam development process, 25 questions will be written that are unique to the
SRO exam. The sampling process only identifies 11 of these questions. The exam
authors will identify 14 additional SRO-only questions as they become more familiar
ES-401 Record of Rejected K/As Form ES-401 -10
Tier and Randomly Reasons for Rejection
Group Selected K/A
1- 1 APE 026 Loss There is no significant difference between Units 1 and 2 in
of Component regards to the Component Cooling Water system.
Cooling Water
G 2.2.4
1-1 APE 026 Loss "Knowledge of procedures and limitations involved in
of Component initial core loading" does not apply to the CCW system
Cooling Water because there are no procedures and limitations on this
G2.2.31 system that are unique to initial core loading..
1-2 APE 008 This K/A states: "Ability to operate and/or monitor the
Pressurizer ...LPI system for a pressurizervapor space accident
Vapor Space (Relief Valve Stuck Open)". There is no plant requirement
Accident to operate the low-pressure injection system under these
AAl.05 conditions because plant pressure would stabilize above the
low pressure system injection point.
2-1 System 004 Resampled from K6.12 top K6.04 because there is no BIT
CVCS K6.12 installed at McGuire. K6.12 only applies to systems with a
Boron Injection Tank. Approved per telcon with Lee
Miller on 10/10/01.
2-1 System 068 System 068 (Liquid Radiological Release) was randomly
Liquid selected to be tested twice. This system is already being
Radiological tested once and the number of valid test items that could be
Release developed is relatively small. The CVCS (NV) system was
randomly selected to fill out the sample plan for a total of
23 RO systems.
2-1 System 071 System 071 (Waste Gas Disposal) was randomly selected
Waste Gas to be a tested twice. This system is already being tested
Disposal once and the number of valid test items that could be
developed is relatively small. The ESFAS system was
randomly selected to replaced the WGD system and fill out
the sample plan for a total of 23 RO systems.
2-1 System 072 System 072 (Area Radiation Monitoring) was randomly
Area Radiation selected to be a second system for testing. This system is
Monitoring already being tested once and the number of valid test
items that could be developed is relatively small. The
Condensate system was randomly selected to replaced the
ARM system and fill out the sample plan for 23 RO
systems.
2-1 System 022 This generic K/A "Knowledge of low power and shutdown
Containment implications in accident (e.g. LOCA, loss of RHR)
Cooling G2.4.9 mitigationstrategies" does not apply to the containment
cooling system. The containment cooling system is not
used to mitigate low power or shutdown accidents.
Draft Submittal
(Pink Paper)
Operating Test Simulator Scenarios
MCGUIRE EXAM
50-369, 370/2002-301
FEBRUARY 11 - 15, 2002
Appendix D Scenario Outline Form ES-D-I
Facility: McGuire Scenario No.: 1 Op-test No.:
Examiners: Operators:
Objectives: 1) The crew will deal with minor malfunctions that will be
compounded by the rods not working in automatic. 2) The crew will have to cut
load due to condenser dump valve being open and power going above 100%. 3)The
crew will deal with a loss of essential bus as a result the crew will have to
swap to the other train of components. 4) The crew must deal with a small NC
leak that becomes a LOCA and a loss of ECR.
Initial Conditions: 100% Power/ "B" Train Components in Service/
Turnover: "IA" D/G Tagged/ "IA" AFW pump tagged/ Unit 2 is available for
auxiliary steam/ Maintain present plant conditions
Event Malf. Event Event
No. No. Type t Description
1 RO Tref failure - fails to 557 degrees
2 BOP Pressurizer Level Channel 2 fails low
2 N Place excess letdown in service
3 RO Atmospheric dump valve fails open
3 R Reduce turbine load due to dump valve failure
4 BOP Loss of ETB with failure of D/G to start
5 M(ALL) LOCA with a failure of ECR
Post major event failures
Main Steam isolation fails in automatic
2 rods fails to insert on trip
Automatic Phase "A" on "A" train does not work
No automatic Safety Injection
Sump suction valve fails to open automatically
The loss of ETB is a DAS at MCGuire. It comprises
i of the important core melt events.
(N)ormal, R)eactivity, (I)nstrument, (C)omponent, (M)ajor
NUREG 1021, Revision 8
PROGRAM: McGuire Operations Training
MODULE: Initial License Operator Training Class 20
TOPIC: Nuclear Regulatory Commission Simulator Exam
Scenario 1
REFERENCES:
1. McGuire Technical Specifications
2. AP/1/A/5500/01 Steam Leak
3. AP/1/A/5500/12 Loss of Letdown, Charging or seal Injection
4. AP/1/A/5500/14 Rod Control Malfunction
5. AP/1/A/5500/07 Loss of Electrical Power
6. EP/1/A/5000/E-0 Reactor Trip or Safety Injection
7. EP/1/A/5000/E-1 Loss of Reactor or Secondary Coolant
8. EP/1A/5000/FR-P.1 Response to Imminent Pressurized Shock
9. EP/1/A/5000/FR.Z.1 Response to High Containment Pressure
10. EP/1/A/5000/ES-1.3 Transfer to Cold Leg Recirculation
11. RP/O/A/5700/00 Classification of Emergency
Author:
Facility Review:
NRC Review:
February 1, 2002
Rev. 1
1
SIMULATOR OPERATOR INSTRUCTIONS
Bench Mark ACTIVITY DESCRIPTION
S Sim. Setup Rod Step On
[] IC-142
o] RUN
O Update Status Board, See Shift Turnover Information
Setup OAC
Setup ICCM, Turbine
Displays, & Trend
Recorders.
Check Rod Step
Counters agree with rod
positions
El (M)EPQ001A Loss of D/G "IA" Control Power
Set = 1
El (LOA) CA009 Rack out breaker for "1A" Auxiliary Feedwater Pump
Set = Rack Out
o (MAL) IRE010D14 2 Rods fail to insert when tripped
(MAL) IRE010H2
o (M) ISE002A No automatic S/I both trains
(M) ISE002B
(M) ISE006A Failure of automatic Main Steam Isolation
(M) ISE006B
El (M)ISE003A Failure of Phase "A"Train "A"to automatically actuate
El (OVR) SVO05D Fails 1SV-47 OPEN
Off - Insert
El (M)NI002F "A"train containment sump valve fails to automatically
open
0
Set =
o (M) NV020E Fails 1 NV-35 open
Set = 100
2
Bench Mark ACTIVITY DESCRIPTION
o] Freeze.
E] Update Fresh Tech.
Spec. Log.
o] Fill out the NLO's
Available section of
Shift Turnover Info.
E] Prior to Crew RUN
Briefing
o3 Crew Briefing
1. Assign Crew Positions based on evaluation requirements
2. Review the Shift Turnover Information with the crew.
3. Direct the crew to Review the Control Boards taking note of present conditions, alarms.
E T T-0 Begin Familiarization
Period
O At direction of (MAL) IRE001 Tref fails to 557 degrees
examiner
Set = 557
At direction of (XMT) ILE002 Pressurizer level channel 2 fails to "0"
examiner Set = 0 INV-1A will not reopen
(M) NV020A
Set = 0
Set both to trigger 1
At Direction of (MAL) IDE004A Fails atmospheric dump valve open
Examiner Set = 100
Ramp = 2
O] At direction of (MAL) EP008B Trips Operating Train ETB
examiner
At step 39 of (M) NCO07A Initiates a small NC system leak
AP/07
Set = 1
Ramp 300
At direction of (M) NC008A Initiates LOCA
examiner
0 Delete malfunction when BOP opens 1NI-185A
Terminate the scenario upon direction of Chief Examiner
3
Event 1: Tref failure
Time Pos. Expected Actions/ Behavior Comments
RO Recognizes Unwarranted Control Rod Insertion
and informs Crew.
" No turbine or reactor power excursion
" Tref circuit failed to 557 degrees
RO Places CRD Bank Selector Switch to manual RO places Rods in Manual
and verifies movement stopped Checks rod movement stopped
SRO Enters AP/14, Rod Control Malfunctions and
directs activities.
RO Performs the following as necessary to maintain
Tcolds 555 degrees to 557 degrees
"* Lower turbine load or
"* Borate NC system
RO Announce occurrence on page
RO Check all rods - ALIGNED WITH ASSOCIATED
BANK
RO Checks "Rod Control Urgent Failure" alarm dark
RO Checks the following normal:
- Turb Imp Pressure Channel 1 Go to Enclosure 4 (Response to
Continuous Rod Movement)
- T-ref
- 1A NC loop T-ave
- 1B NC loop T-ave
1C NC loop T-ave
1D NC loop T-ave
SRO Go to Enclosure 4
SRO e Evaluate rod movement Tref circuit is the failure SRO
Check the following normal should notify IAE to investigate and
1. Turb Imp Pressure Channel 1 maintain Tcolds 555 degrees to 557
2. T-ref degrees by adjusting control rods in
3. 1A NC loop T-ave manual or adjusting turbine load or
4. 1 B NC loop T-ave boration/dilution of NC system.
5. 1C NC loop T-ave
6. 1D NC loop T-ave
- Checks to see iffailed channel has been
identified
1 Exit procedure
4
Event 2: Pressurizer Level Channel 2 Failure
Poe. Expected Actions/Behavior Comments
BOP On a loss of letdown ensure the following INV-35A will not close - BOP must
closed: attempt to close. Immediate action
SRO Enters AP/12 Loss of Letdown, Charging or Seal
Injection
BOP If at any time "REGEN HX LETDN HI TEMP" BOP will take action if appropriate
alarms, close:
RO Stop any power or temperature changes in
progress
RO Announces occurrence on page
SRO IF this AP entered due to loss of letdown only, SRO will go to step 35 in this AOP
then go to step 35.
BOP Ensures "NC Sys M/U Controller" in AUTO
BOP Ensures charging flow going down to maintain
Pzr at program level
BOP Checks "Letdn Relief Hi Temp" alarm has
remained dark
5
Event 2: Pressurizer Level Channel 2 Failure
I Pos. F Expected Actlons/ Behavior Comments
BOP Checks Pzr heater group supply breakers NO, due to level instrument failure
closed
BOP will perform the following:
1. Ensures the following are selected to
an operable channel
"Pzr level control select" 1-3 position
"Pzr level rec select"
2. Ensure Pzr level greater than 17%
3. Place the following switches in "MAN"
A
B
D
4 Close the following breakers:
A
B
"D
5 * Close C Pzr heater group supply
breaker
b. Check normal spray available
c. Place the following Pzr heater groups in
Manual and ON to maximize spray.
- A
0D
BOP Checks the following OPEN NO, go to step 42
"* 1NV-1A
"* 1NV-2A
SRO Checks to see if immediate restoration of normal Orifice isolation valve NV-35 has not
letdown is possible closed. So will go to step 47 to place
excess letdown in service.
"* Both NV 1 & 2 open in the past 30 minutes
May have to provide management
"* Orifice isolation valves closed before or at the guidance that excess letdown is
same time as NV 1 & 2. desired.
6
Event 2: Pressurizer Level Channel 2 Failure LO
Pos. Expected Actlons/ Behavior J Comments
BOP Establish excess letdown
Adjust charging to minimum while maintaining
the following:
"* NC pump seal injection flow greater than 6
gpm
"* Pzr level at program level
1. Opens the following:
- Places 1 NV-27B to VCT position
2. Opens and closes 1NV-26
3. Checks the following OPEN:
4. Opens 1NV-24B and 1 NV-25B
5. Slowly opens 1NV-26 while maintaining
excess letdown heat exchanger temp. less
than 200 degrees.
SRO Go TO step 47.n
BOP Notified chemistry that excess letdown is in
service.
Adjust charging flow as desired while
maintaining:
"* NC pump seal injection flow greater than 6
gpm
"* Pzr level at program level
"* Operate Pzr heaters as desired
SRO SRO should notify Work Control Center or IAE Tech Spec. 3.3.1 function 9
to investigate and repair failed instrument
7
Event 3: Atmospheric Dump Valve Fails OPEN
Time Poo. Expected Actior Behavior Comments
CREW Recognizes symptoms of a steam leak T-ave-Tref annunicator may come in
alarm
"* T-ave decreasing
"* Power increasing
SRO Enters AP/01 Steam Leak
Crew Monitors fold out page
RO Reduces turbine load to maintain:
"* Excore NI - less than 100%
"* NC loop DITs - less than 60 degrees
"* T-ave at T-ref
BOP Checks Pzr level -stable or going up
SRO Will return to step 3 if Pzr level can not be
maintained.
RO Announces occurrence on page
RO Identifies and isolates leak:
"* Checks S/G PORVs - CLOSED
"* Checks condenser dump valves -CLOSED An atmosphericdump valve will be
OPEN - RO must select "OFFRESET'
"* Checks atmospheric dump valves - 1 OPEN on Steam dump interlock Bypass
"channelA and B. Isolation valve will nol
- Checks containment conditions - NORMAL close. Must dispatch an operatorto fail
"* Checks turbine driven CA pump - OFF air to atmosphericdump valve.
"* Checks steam line drain valves - CLOSED
"*Checks Unit 2 - steam header pressure
SRO Exits procedure when leak is isolated.
8
Event 4: Loss of Operating Train ETB
Time I Poe. Expected Actions/ Behavior Comments
Crew Recognizes loss of operating train "ETB"
SRO Checks bus energized and sequencer applying The diesel will NOT start due to failure
loads.
SRO entered AP/07
BOP If both NV pumps off, Then isolate NORMAL
Critical letdown.
Start opposite train:
"* NV pump
"* KC pump
"* RN pump
Go to step 3
SRO Verifies NO Safety Injection has occurred "A" train NV pump will be on
If both NV pumps off then isolate:
"* Excess letdown
"* ND letdown
If any pump was manually started per step 1 go
to step 5
SRO Check D/Gs - OFF
BOP Align KC as follows:
Critical Places 1KC-51 A to AUTO
- Ensures the following are open
1. 1KC-3A
2. 1KC-230A
3. 1KC-394A
4. 1KC-345A
5. If needed keep thermal barrier valves open
raise KC flow to KF hx by opening 1KC-1 49
- Ensures KC flow is less than 4000 gpm per
operating KC pump
SRO Checks any charging pump - Running - YES
BOP Align RN as follows:
"* Check 1A RN pump- Running -YES
"* Close 1 RN-43A
"* Throttle 1 RN-89A to desired cooling
SRO Notifies Unit 2 RO to start 2A RN pump EXAMINER CUE:
2A RN pump is running
SRO Checks B/O on 1ETA NO, go to step 22
BOP Checks 1RN-86A-OPEN
SRO Dispatches operator to close:
9
Event 4: Loss of Operating Train ETB
Time Poe. Expted Actlons/ Behavior T Comments
SRO Checks 1B ND train -was not in RHR mode Go to step 30
SRO Checks normal letdown - IN SERVICE No, may have operator place excess
letdown back in service.
SRO Go to step 36
RO Announces occurrence on page.
SRO Checks D/G on bus that was blacked out - NO * Place affected D/G Mode Select to
"C/R"
"* Depress then release the "RESET"
pushbutton for the affected train's
sequencer.
" Start D/G.
BOP Check bus energized and sequencer applying * Place affected D/G Mode Select to
loads "C/R"
"* Ensure normal and standby breaker
open to allow auto loading of bus.
"* If bus not energized or sequencer
not loading bus then go to
Enclosure 1.
SRO Go to Enclosure 1 - Manual Loading of
Emergency Bus
BOP e Ensure S/I Reset
- Check 1ETA - Energized from Offsite
Power
- Go to Step 15
BOP Check 1ETB - Energized from Offsite Power - Go to step 20
NO
BOP Hold "RESET" on "1B D/G LOAD Seq" while
completing steps 21 through 23.
10
Event 4: Loss of Operating Train ETB
Time Poe. Expected Actions/ Behavior
BOP Unload 1ETB bus as follows:
I Comments
1. Open 1B CA pump breaker
2. Open the remaining pump breakers on
1ETB
"* NV
"* ND
"* NI
"* KC
"* RN
"* KF
"* Ensure Train B NS is reset and open NS
pump breaker
3. Open 600v essential transformer feeder
breakers:
S1 ELXB
- 1ELXD
- 1ELXF
BOP * Place "IB D/G Mode Select switch to "C/R" Breaker will not close.
- Close "1ETB Emerg Breaker" Release "RESET" on "1B" D/G Load
SEQ"
Stop D/G
Return to procedure and step in
effect.
Go back to step 38 in body of
procedure.
NC LEAK WILL BEGIN AT THIS POINT
11
Event 5: NC System Leakage AP-10 Evaluation
Time I Pos. I Expected Actions/ Behavior Comments
BOP Report either of the following:
" Pzr level decreasing
" Pzr press decreasing
" Containment Vent Isol (EMF39)
"* "Ice Cond Doors Open" Annunciator
SRO Go to AP/10 (Case II) NC System Leakage
and directs activities
BOP Report Pzr Level decreasing:
" Report NV-238 opening
" Open NV-241 while
maintaining 6 gpm
Seal Injection Flow
Starts additional NV Pump
Isolate excess letdown
- IfPzr level less than 4% then:
" Manually Trip Reactor
" Manually SI
Crew Returns to step 1 if Pzr level can not be
maintained.
Crew Isolated leak if location is known
BOP Reports Pzr Pressure stable or trending to 2235
psig
RO Reports Main Steam line is INTACT
" Reactor power at turbine power
" NC loop T-Ave is stable
SRO When leak is determined greater than makeup
capability, directs crew to trip reactor and initiate
Safety Injection
RO Manually trips Reactor (Train A & B) Two rods fail to insert
Critical BOP Manually initiates Safety Injection both trains
12
Event 5: LOCA E-0 Evaluation
Time I Poe. Expected Actions/ Behavior Comments
SRO Go to EP/E-0 and directs activities
SRO Reviews Foldout page with crew NCP trip criteria based on loss of
subcooling
RO Report Reactor Trip:
"* rod bottom lights TWO rods will be stuck
"* reactor trip breakers open
"* I/R amps decreasing
RO Reports Turbine Generator tripped
1 TV's or GV's closed
BOP Reports ETA and ETB energized "B" will be de-energized
RO Reports SI status light - LIT After Immediate Actions are
completed by operator they can
close MSIV's if they recognize they
are open and should be closed.
(A & B) actuated
RO Announce "Unit 1 Safety Injection" on page
BOP Checks ESF Monitor Light Panel
"* Groups 1,2 and 5 DARK The "B"side of all panels will be dark
"* Group 3 LIT
"* Checks OAC in service
BOP Reports all Ss and St components in Group 4 If not already done BOP should
NOT -LIT manually initiate Phase "A"Train "A"
RO Reports that CA is running and at least 3 S/G's Motor driven pumps are not available.
NR level > 17%
BOP Reports KC pumps running "A"train only
BOP Reports RN pumps running "A"train only
13
Event 5: LOCA
Time Pos. Expmct*d Actlonsd Behavior Comments
SRO Directs Unit 2 Operator to throttle RN to EXAMINER CUE:
minimum & start 2A RN pump * 2A RN pump is running
RO Checks/reports all S/G pressures > 775 psig
BOP Reports Containment pressure has remained NO
less than 3 psig a record approximate time of reactor
trip
"* Check row G on Monitor Light
Group 4
"* If any row G is dark on energized
train
- Stop all NC pumps
- Stop all RV pumps
- Energize H2 igniters by depressing
"ON" and Override
When time allows check Phase B
HVAC equipment per Enclosure 2
BOP Report NV Pump to Cold Leg Flow gauge
indicating flow - YES
"* checks NC pressure < 1600 psig
"* checks NI pumps indicating flow
"* checks NC pressure - less than 286 psig
"* checks ND pumps - indicating flow to cold
legs
SRO When available notifies OSM or other SRO to EXAMINER CUE:
implement Generic Enclosure 22 OSM will ensure Generic Enclosure
22 is implemented.
RO * Checks CA flow > 450 gpm and takes RO will take control of auxiliary
control of CA to maintain no load levels feedwater.
- checks VI header pressure > 60 psig
- Maintains N/R level between 32% and 50%
BOP * If any NC pump ON, then check Tave stable
or trending to 557 degrees
- If all NC pumps off, then check NC T-colds
stable or trending to 557 degrees.
BOP Reports Pzr PORV & Spray Valves closed
BOP Reports subcooling > 0 degrees based on Core
Exit Thermocouples
BOP Reports all main steamlines INTACT
RO/ Report S/G tube rupture parameters indicate
BOP that S/G tubes intact
14
Event 5: LOCA
Time Pos.I Expected Actions/ Behavior Comments
SRO Checks if NC system is NOT intact: Perform the following:
"* Containment EMFs - normal If H2 igniters are off then perform
"* Ice Condenser Lower Inlet Doors Open the following:
alarm - DARK Energize H2 igniters by depressing On
- Containment pressure < 1 psig and Overrride
- Implement F-0 CSFST
- Go to E-1
CSFST will necessitate going to P-1 then Z-1 The crew will only do the first step on
P-1 and based on pressure will exit
P-1.
BOP P-1 - Response to Imminent PTS ND pump flow is greater than 500 gpm
Check NC pressure - Greater than 286 psig -Then return to procedure and step in
NO effect. Go to Z-1
SRO Will go to Z-1, Response to High Containment
Pressure
CREW If loss of emergency coolantberecirc has occurred,
THEN this procedure may completed as time
allows.
Crew Monitors foldout page
BOP Stop all NC pumps.
BOP Ensure all RV pumps are in manual and off.
SRO Dispatch operator to remove tags and close
breakers for the following valves:
"* 1EMXA-R2A
"* 1EMXAB1-6B
BOP Check containment pressure - LESS THAN 15
PSIG.
BOP Check any NS pump - ON
SRO The remainder of this EP may be performed as
time allows.
15
Event 5: LOCA
Time Pos. Expected Actions/ Behavior Comments
SRO ES 1.3 Transfer to cold leg recirc.
BOP Checks containment sump level - greater than 3
feet
Checks KC flow to each ND heat exchanger No, on "B" train crew will do RNO
BOP greater than 5000 gpm
BOP Resets Safety Injection and Sequencer MAKE SURE SIMULATOR RUNNER
READY TO DELETE MALFUNCTION
FOR 1NI-185A IN NEXT STEP.
BOP Align ND system for recirc: Place the control permissive in
Critical Check 1NI-185A OPEN - NO "BYPASS" and open 1NI-185A
Checks 1A ND pump on - YES Go to step 6b
Check 1NI-1 84B OPEN - NO Go to step 6e
Close 1FW-27A
Check any ND pump on
Align NV and NI systems for recirc:
BOP Check NC pressure less than 1600 psig
Close the following:
"*1NI-115A
" 1NI-144B
Close 1NI-147A
Close
Align ND train discharge to NI and NV pump
suctions:
" Open 1NI-332A
" Open 1ND-58A
Close 1NI-100B- can not close
- Close 1NV-221A
SRO !Check if NS should be aligned for recirc - NO go
to step 9
SRO Check is ND aux spray is required - NO go to
step 10
16
Event 5: LOCA
Time( Poe. I Expected Actions/ Behavior
CREW If at any time a B/O signal occurs, then restart
j Comments
S/I equipment previously on.
SRO Checks for proper recirc flow and valve
alignment
Checks the following closed
Checks flow indicated from:
"* NV pump
"* NI pump
"* ND pump
Checks the following closed:
Check KC flow to ND heat exchanger
established
SRO Return to procedure and step in effect.
TERMINATE SCENARIO AT DIRECTION OF CHIEF EXAMINER
EXAMINER NOTE: Be sure SRO classifies event at end of scenario.
Classification of event: ALERT
17
SHIFT TURNOVER INFORMATION
UNIT 1 STATUS:
{PRIVATE 100% NCS [B] 7,59ppm Pzr [B]: 759 ppm Xe: OAC
}Power Level:
{PRIVATE At 100% for 100 days Core Burnup: 200 EFPDs
}Power History
CONTROLLING PROCEDURE: OP/1/A/6100/03 Controlling Procedure for Unit Operation
OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:
"lA"Diesel Generator tagged for maintenance.
"1A" Auxiliary Feedwater pump tagged for oil change - PM
Unit 2 is available for auxiliary steam.
Reduce power to 90% to do turbine valve movement test.
Work Control SRO/Offsite Communicator Thad
Unit 2 SRO Jim
NLO's AVAILABLE
Unit 1 Unit 2
Aux Bldg. Robb Aux Bldg. Joe
Turb Bldg. Fred Turb/Service Bldg. Mike
Extra(s) Bill, Craig, Russ, Ron
18
Appendix D Scenario Outline Form ES-D-l
Facility: McGuire Scenario No.- 2 Op-test No.:
Examiners: Operators:
Objectives: 1) Determine if the crew can deal with a variety of malfunctions
using immediate actions and AOP's. 2) Determine if the crew can perform an
orderly shutdown of the plant then handle a large STGR without filling the
Initial Conditions: 55% Power/ "B" Train Components in Service/
Turnover: "lA" DIG Tagged/ "lA" AFW pump tagged/ Unit 2 is available for
auxiliary steam/ Begin load increase
Event Malf. Event Event
No. No. Type* Description
1 RO Power Range 43 fails high
2 BOP Pressurizer Pressure channel 2 fails high
3 BOP NC PORV 36 fails to 25% open - must close block
valve to isolate
4 RO S/G Control Valve failure - normal controller
fails
5 M (ALL) Steam generator Tube Leak - 40 gallons per minute
6 N Removing Feedwater Pump from service
6 R Load reduction due to shut down of plant
7 M (ALL) SGTR - 430 gpm
Post Major Event Failures
Failure of automatic feedwater isolation
MSIV on ruptured S/G will not close
No automatic Safety Injection
One reactor trip breaker will not open
EMF for ruptured S/G failed as is
- (N)ormal, R)eactivity, (I)nstrument, (C)omponent, (M)ajor
NUREG 1021, Revision 8
PROGRAM: McGuire Operations Training
MODULE: Initial License Operator Training Class 20
TOPIC: Nuclear Regulatory Commission Simulator Exam
Scenario 2
REFERENCES:
1. McGuire Technical Specifications
2. AP/1/A/5500/06 Loss of S/G Feedwater
3. AP/1/A/5500/11 Pressurizer Pressure Anomalies
4. AP/1/A/5500/10 NC System Leakage Within the Capacity of both NV Pumps
5. AP/1/A/5500/16 Malfunction of Nuclear Instrumentation
5. EP/1/A/5000/E-0 Reactor Trip or Safety Injection
6. EP/1/A/5000/E-3 Steam Generator Tube Rupture
7. RP/O/A/5700/00 Classification of Emergency
Author:
Facility Review:
NRC Review"
February 1, 2002
Rev.1
1
SIMULATOR OPERATOR INSTRUCTIONS
Bench Mark ACTIVITY DESCRIPTION
Q Sim. Setup Rod Step On
o IC-143
o] RUN
O Update Status Board, See Shift Turnover Information
Setup OAC
Setup ICCM, Turbine
Displays, & Trend
Recorders.
Check Rod Step
Counters agree with rod
positions
o (MAL) EPQ001A Loss of D/G "iA"Control Power
Set = 1
o (LOA) CA009 Rackout breaker for "lA" Auxiliary Feedwater Pump
Set = F
o (M) SM006A MSIV on ruptured generator fails open
O (M)ISE002A No automatic S/I both trains
(M) ISE002B
O (M) ISE007A Failure of Feedwater Isolation - both trains
(M) ISE007B
o (M) EMF133 Set EMF 33 at 10
Set = 10
O (M) EMF173 Fails EMF 24 to "0"
Set = 1
O (M) IPE001A Failure of "A"train reactor trip breaker to open
(M) IPE002A
[]
2
SIMULATOR OPERATOR INSTRUCTIONS
Bench Mark ACTIVITY DESCRIPTION
O] Freeze.
o] Update Fresh Tech.
Spec. Log.
o] Fill out the NLO's
Available section of
Shift Turnover Info.
o Prior to Crew RUN
Briefing
o] Crew Briefing
1. Assign Crew Positions based on evaluation requirements
2. Review the Shift Turnover Information with the crew.
3. Direct the crew to Review the Control Boards taking note of present conditions, alarms.
o T-0 Begin Familiarization
Period
O At direction of (MAL) ENBO13E Power Range NI 43 fails high
examiner
Set = 200
Ramp = 5
O At direction of (MAL) NCO03F Pressurizer Pressure Channel 2 fails HIGH and NC
examiner Set = 25 PORV NC-36 sticks at 25% open
Set both to trigger 1
(XMT) NC039
Set = 2500
O At direction of (MAL) IFE009B1 S/G "B" Control Valve Failure
examiner Set = 0
Ramp = 5
At direction of (M) S/G001A Initiates 50 gpm tube leak on "A"steam generator
examiner
Sel = 50
Ramp = 120
C (M) S/G001A Initiate once FWPT has been shutdown
Sal =435 Design basis tube rupture
Ramp = 120
o] Terminate the scenario upon direction of Chief Examiner
3
Event 1: Power Range 43 Fails High
Time Pos.f Expected Actions/Behavior Comments
RO Determines NI-43 has failed high and places Immediate action
rods to manual
SRO Entered AP/16 Malfunction of Nuclear
Instrumentation
RO Checks S/G levels at programmed level Should place reg. Valve for "A"and "D"
S/G to manual and return to program
level
RO Announce occurrence over page
RO Checks P/R channels - only one failed
RO Positions "PR to S/G Program level defeat"
switch to 41/43 position
RO Secures any power increase.
BOP Performs the following actions at the
"Miscellaneous Control and Indication Panel"
"* Rod Stop Bypass to N43
"* Power Mismatch Bypass to N43
BOP Performs the following actions at the "Detector
Current Comparator" drawer
"* Upper Section to N43
"* Check upper section light lit
"* Lower Section to N43
"* Check lower section light lit
BOP Performs the following at the "Comparator and
Rate" drawer
"* Comparator Channel to N43
"* Check comparator light for N43 lit
BOP Trips bistables for failed channel
e Remove control power fuses from N43
RO Checks the following status lights for the failed
channel lit:
"* NUC Overpower Rod Stop Bypass
"* P/R Hi Flux Lo Stpt
"* P/r Hi Flux Hi Stpt
"* P/R Hi Flux rate
4
Event 1: Power Range 43 Fails High
Time Poe. Expected Actions/ Behavior j Comments
RO Checks the following annunciators lit:
"* P/R Hi Voltage Failure
"* P/R Hi Flux Hi Stpt Alert
"* P/R Hi Flux Rate Alert
RO Checks the following status light lit:
"* P/R Lo Setpoint Train A Trip Blocked
"* P/R Lo Setpoint Train B Trip Blocked
SRO If desired to control S/G levels in auto then
return affected s/G CF control valves to auto
RO Ensures operable P/R channel selected to
record on NIS recorder
RO Adjust control rods to maintain T-ave at T-ref
RO When T-ave within 1 degree of T-red and auto
rod control desired then return control rods t
auto
SRO Instructs IAE to fail OTDT and OPDT bistables Tech Spec evaluation
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of failure Table 3.3.1-1
3.3.1.2
3.3.1.3
3.3.1.6
3.3.1.16 b,c,d
3.3.1.7
CREW Ensures proper bistables failed for P/R 43
"* NC loop C OPDT Trip
"*NC loop C OTDT Trip
______ I _______ I __________________________________________
5
Event 2 and 3: Pressurizer Pressure Channel 2 Fails High with NC 36 failed to 25%
Time Poe. Expected Actions/ Dehei..r Comments
BOP Recognizes/reports PZR pressure decreasing
SRO Implements AP/1 1 Pzr Pressure Anomalies,
Case 2 and directs activities
BOP Reports Pzr Pressure decreasing
Critical BOP Determines all channels not the same Places "Pzr Pressure Control Select" to
backup channel - 1-4 position
Critical BOP Checks/reports Pzr PORV's Closed Will try to close - will not close - must
close block valve
BOP Checks/reports Spray Valves Closed
BOP Reports Pzr PORVs - closed No for NC-36 will close 1 NC-269
BOP Reports Spray Valves Closed
SRO Go to Step 9
RO Announce occurrence on page
BOP Checks/reports NV-21A , CLOSED
BOP Checks/reports Pzr A,B & D heaters ON
BOP Checks 1C PZR heater - ON
BOP Checks Pzr pressure going UP
SRO Go to step 21
SRO Ensures "Pzr PRESS REC SELECT" is on an
operable channel
SRO Will notify Work control center and/or IAE to Failure will not be fixed
investigate and repair Tech spec issue with two channels of
OTdT inoperable.
Tech Spec 3.0.3 for two channels
Plus Tech Specs
"* 3.3.1.6
" 3.3.1.8
" 3.3.2.1 .d
" 3.3.2.8.b
6
Event 4: Normal Controller for "B"S/G Fails Low
Time_ Pos. Expected Actlons/ Behavior Comments
BOP Refer to annunciator responses Annunciators on 1AD-4
C-2
SRO Goes to AP/06 Loss of Feedwater
Critical RO Places Feed Regulator to Manual If S/G CF control valve fails to
respond in manual then:
Restores S/G level to program level
o Select ALT on control circuit
. Restore to program level
RO Checks the following channel indicating the Immediate Action step
same:
"* Feed flow
"* Steam Flow
"* S/G Level
RO Checks S/G CF control valve in manual control YES
RO When the following are met then return affected
S/G CF control to automatic
1. Selected control channels indicated correctly
"* Feed flow
"* Steam flow
"* S/G level
2. Affected S/G level restored to program level
3. Automatic control is desired
SRO Checks the reactor tripped NO
RO Maintains S/G level Go to step 7
RO Controls feed flow to maintain S/G NR level - at
programmed level
SRO Checks NC temperature with NC pumps on
stable or trending to programmed temperature
SRO Checks procedure enter due to failed controller
SRO Contacts I&E to repair failed controller Failure will not be repaired
Exit procedure
7
Event 5: S/G Tube Leakage on "A"S/G
Time Po. Expected Action) Behavior Comments
BOP Report either of the following:
"* Pzr level decreasing
"* Pzr press decreasing
"* EMF 24 - Blocked - crew will not see
SRO/ Refer to Ann. Response and/or AP 10
BOP/ e Notify RP shift
- CT lab
- Refer to AP/1 0
1 Have operator secure drains to TB sump
SRO Go to AP/10 (Case I) S/G Tube Leakage and
directs activities
BOP Report Pzr Level decreasing:
"* Report NV-238 opening
"* Open NV-241 while
maintaining 8 gpm
Seal Injection Flow
"* Starts additional NV Pump
- Reduce letdown to
45 gpm or isolate letdown
- Iflevel less than 11% then:
- Manually Trip Reactor
- Manually SI
SRO If primary to secondary leak is greater than 100 Leak is < 100 gpm
gpm, then trip reactor and go to E-0
RO Announce occurrence on page
SRO If at anytime while in this procedure Pzr level
can not be maintained stable then perform step
1.
BOP Checks Pzr pressure - stable or trending to
2235 psig.
SRO If NC leakage exceeds Tech Spec limits then Tech Spec 3.4.13
ensure outside air pressure filter train in service.
SRO Check ifunit shutdown is required:
1. Leakage in one S/G - greater than 125 gpd
2. Reduce load in step 8
" Ensure reactor power is less than 50%
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of exceeding 125 gpd
- Be in Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of exceeding
125 gpd.
SRO Reduce load PER one of the following:
" AP/1/A/5500/04 Rapid Downpower OR
" OP/1A/6100/03 Controlling procedure for
Unit Operation
8
Event 5: S/G Tube Leakage on "A"S/G AP/04 Evaluation - Rapid Downpower
Time f Poe. Expected Actlons/ Behavior Comments
RO Identify "C" S/G as having excessive leakage AP/04 evaluation Rapid Downpower
- Monitor foldout page
- determine power reduction rate
- check control rods in AUTO - YES
- notify SOC of load reduction
- initiate turbine load reduction
- borate the NC system
- check control rods moving in as
required
- check turbine impulse pressure >
290#
- May refer to RP/00 Classification of
Emergency and RP/10 Immediate
NRC Notification Requirements
- check turbine control in AUTO
- check Unit 2 aux steam available to
supply header
check P/R instruments indicate
power < 40%
Check < P-8
all CF flows < 40%
Impulse pressure < 290#
Once FWPT is removed from
service the leak size will increase
SRO When leak is greater than makeup capability, Crew will go back to step 1 of AP/1 0
directs crew to trip reactor and initiate when Pzr level begins decreasing
Safety Injection
RO Manually trips Reactor (Train A & B)
Critical BOP Manually initiates Safety Injection
9
Event 6: SGTR on "A"S/G E-0 Evaluation
Time Pos. Expected Actions/Behavior Comments
SRO Go to EP/E-0 and directs activities
SRO Reviews Foldout page with crew
RO Report Reactor Trip:
rod bottom lights
- reactor trip breakers open
SI/R amps decreasing
RO Reports Turbine Generator tripped
- TV's or GV's closed
BOP Reports ETA and ETB energized
RO Reports SI status light - LIT
BOP Report LOCA sequencers (A & B) actuated
SRO/ Announce "Unit 1 Safety Injection" on page
BOP Checks ESF Monitor Light Panel If not already recognized the crew
"* Groups 1,2 and 5 DARK should initiate feedwater isolation.
"* Group 3 LIT
- Checks OAC in service
BOP Reports all Ss and St components in Group 4
NOT -LIT
RO Reports that CA is running and at least 3 S/G's
NR level > 17%
BOP Reports KC pumps running
BOP Reports RN pumps running
10
Event: SGTR "A"S/G
[Time j Poe. Expected Abilons/ Behavior Comments
SRO Directs Unit 2 Operator to throttle RN to EXAMINER CUE:
"minimum & start 2A RN pump * 2A RN pump is running
RO Checks/reports all S/G pressures > 775 psig
BOP Reports Containment pressure has remained
less than 3 psig
BOP Report NV Pump to Cold Leg Flow gauge
indicating flow - YES Crew will ensure ND pump mini-flow
" checks NC pressure < 1600 psig valves are open
" checks NI pumps indicating flow - NO
SRO When available notifies OSM or other SRO to EXAMINER CUE:
implement Generic Enclosure 22 OSM will ensure Generic Enclosure
22 implemented.
RO e Checks CA flow > 450 gpm and takes
control of CA to maintain no load levels
- checks VI header pressure > 60 psig
I Maintains N/R level between 11% and 50%
BOP Checks NC pumps ON and Tave stable or If not stable and decreasing crew will go
trending to 557 degrees to Enclosure 3
BOP Reports Pzr PORV & Spray Valves closed
BOP Reports subcooling > 0 deg.
BOP Reports all main steamlines INTACT
RO/ Report S/G tube rupture parameters indicate Implements F-0 and E-3
BOP that S/G tubes NOT intact
11
Event: STGR on "A"S/G E-3 Evaluation
Time Pos. Expected Actions/ Behavior Comments
SRO Implement CSF Status Trees and go to EP/E-3
SRO Go to EP/E-3 and directs activities
SRO Monitor foldout page
RO/ Identify "A"as the ruptured S/G
RO Check at least one S/G - AVAILABLE FOR NC
SYSTEM COOLDOWN
RO Isolate steam flow from ruptured S/Gs as
follows:
a checks ruptured S/G PORV closed
RO Check S/G 1B and 1C INTACT
RO Check blowdown isolation valves - CLOSED:
- 1BB- 1B
- 1BB- 5A
BOP Close steam drain and check "CLSD" light lit for
ruptured S/Gs:
RO Close the following on ruptured S/Gs: MSIV on ruptured S/G will not close.
Critical * MSIV RO will close other S/G
- MSIV bypass valves
- steam dumps
- Close SM-14,SM-15,AS-12,TL-3
- SPI and SP2
- Dispatch an operator to isolate
steam line drains per enclosure 4
- When cooldown is initiated in
subsequent steps then use intact
S/G PORVs for steam dump.
12
Event 6: SGTR on "A"Steam Generator
Event: Pos. Expected Actions/ Behavior Comments
RO Checks ruptured S/G NR levels greater than
11%
Isolates feed flow to "A"S/G
- Close 1CA-66AC
- Close 1CA-62A
BOP Checks Pzr PORV and isolation valves:
"* Power to all Pzr PORvs available
"* All Pzr PORVs CLOSED
"* At least one Pzr PORV isolation valve OPEN
RO Checks main stream lines intact:
"* All S/G pressures stable or going up
"* All S/G pressurized
BOP Reset the following:
- S/I
- Sequencers
- Phase A isolation
- Phase B isolation
BOP Established VI to containment
"* 1VI-129B open
"* 1VI-160B open
I1VI-150B open
- Checks VI header pressure > 85 psig.
RO Controls intact S/G levels:
"* N/R level in all intact S/Gs > 11%
"* Throttles feed flow to maintain intact S/Gs
N/R levels between 22% and 50%
BOP Checks 1ETA and 1 ETB energized by offsite
power
SRO Checks ruptured S/G identified
SRO Checks the following closed on ruptured S/G: NO, MSIV open
" MSIV
" MSIV bypass valve
SRO Checks ruptured S/G pressure greater than 280
psig.
13
Event: STGR on "A" S/G
Time Pos. Expected Actions/ Behavior Comments
SRO Checks any NC pump running
SRO When P-11 status light lit then block steamline
isolation and maintain NC pressure less than
1955 psig.
RO Initiate a NC system cooldown as follows:
Critical Determine required core exit temperature based
on lowest ruptured S/G pressure.
"* COND AVAILABLE FOR STEAM DUMP"
status light - LIT
"* MSIV on intact S/Gs OPEN NO
" IfPzr pressure is greater than 1955
psig, then depressurize to 1900 psi9
using Pzr PORV.
"* Depress "BLOCK" on low pressure
steamline isolation block switches.
"* Maintain NC pressure less than
1955 psig.
- Ensure Main Steam Isolation reset.
- Ensure S/G PORVs reset.
- Dump steam using all intact S/Gs
PORVs at maximum rate as follows:
Close S/G PORV manual loader on
ruptured S/G
2. Place intact S/G PORV manual
loaders at 50%
3. Select "MANUAL" on "SM PORV
MODE SELECT"
4. Adjust manual loader on intact S/G
PORVs as required to control intact
S/G depressurization rate at
approximately 2 psig per second.
" Check low pressure steamline isolation
BLOCKED
" Check core exit T/Cs - less than required
temperature.
" Stop NC system coodown
" Maintain core exit T/Cs less than required
temperature.
SRO Checks ruptured S/G pressure - stable or going
up
SRO Checks NC subcooling based on core exit T/Cs
> than 20 degrees
14
Event: STGR on "A"S/G
Time Pos. Expected Actions/ Behavior Comments
BOP Depressurizes the NC system
1. Checks ruptured S/G NR level less than
73%
2. Checks normal Pzr spray available Ifcrew uses PORV go to step 21.
3. Initiates NC depressurization using
maximum spray
4. Do not continue in procedure until one of the
following satisfied:
" NC subcooling less than 0 degrees
" Pzr level greater than 76%
Or
- Both of the following
NC pressure less than ruptured S/G pressure
Pzr level greater than 11%
- Go to step 23
Crew Checks for S/I termination criteria
1. NC subcooling greater than 0 degrees Must meet all criteria to terminate.
2. Secondary heat sink
3. NC pressure- stable or going up
4. Pzr level greater than 11%
BOP Stop S/I pumps as follows:
a NI pumps
1 All but one NV pump
BOP Isolate NV S/I flowpath
"* Check NV pump - SUCTION ALIGNED TO
FWST
"* Check the following valves OPEN:
1NV-1 51A
"* Close the following valves:
STOP SCENARIO HERE
TERMINATE SCENARIO AT DIRECTION OF CHIEF EXAMINER
EXAMINER NOTE: Be sure SRO classifies event at end of scenario.
Classification of event: Site Area Emergency
15
SHIFT TURNOVER INFORMATION
UNIT 1 STATUS:
(PRIVATE 55% NCS [B] 866 ppm Pzr [B]: 865 ppm Xe: Per OAC
}Power Level:
(PRIVATE Reduced power to 20% to add Oil to Core Burnup: 200 EFPDs
}Power History: "D"reactor coolant pump.
CONTROLLING PROCEDURE: OP/1/A/6100/03 Controlling Procedure for Unit Operation enclosure 4.1
step 3.21.
OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:
"lA"Diesel Generator tagged for maintenance.
"lA"Auxiliary Feedwater pump tagged - PM
Unit 2 is available for auxiliary steam.
Continue load increase at 2 MW/Min.
Conditioned power level 100%.
Work Control SRO/Offsite Communicator Thad
Unit 2 SRO Jim
NLO's AVAILABLE
Unit 1 Unit 2
Aux Bldg. Robb Aux Bldg. Joe
Turb Bldg. Fred Turb/Service Bldg. Mike
Extra(s) Bill, Craig, Russ, Ron
16
Appendix D Scenario Outline Form ES-D-1
Jp-LeL +/-NtJ
scenario NO.: pare
Facility: McGuire Scenario No.:
Opare Op-test No.:
operators:
Objectives: 1) Diagnose failures that are not readily understood such as
letdown back pressure instrument and charging line leak. 2)Deal with a small
steam generator tube leak after a large steam line break. This exercise will
give the candidates opportunity to exercise a variety of AOPs and EOPs.
Initial Conditions: 70% Power! Increasing Load! "B" Train Component in
service
Turnover: "A" D/G inoperable/ "A" CA pump tagged/Unit 2 is available for
auxiliary steam/ Begin load increase to 100%.
Event Malf. Event Event
No. No. Type* Description
iN Load Increase
1R Rod Withdrawal/Dilution
2 SOP Letdown Back pressure Instrument Failure
3 RO Steam Generator Narrow Level Instrument fails low
4 BOP Charging Line Leak
5 RO power Mismatch Circuit Failure
6 M(ALL) Steam Leak becomes Steamline Break Inside
Containment with a SGTR
Post Major Event Malfunctions
No automatic spray actuation
No Auto Main Steam Isolation - done manually
Tube Leak on Faulted Steam Generator
No automatic safety injection
- (N)ormal, R)eactivity, (I)nstrument, (C)omponent, (M)ajor
NUREG 1021, Revision 8
PROGRAM: McGuire Operations Training
MODULE: Initial License Operator Training Class 20
TOPIC: Nuclear Regulatory Commission Simulator Exam
Spare Scenario
REFERENCES:
1. McGuire Technical Specifications
2. AP/1/A/5500/06 Loss of S/G Feedwater
3. AP/1/A/5500/12 Loss of Letdown, Charging or Seal Injection
4. AP/1/A/5500/14 Rod Control Malfunction
5. AP/1/A/5500/10 NC System Leakage Within Capacity of Both Charging
Pumps
5. EPIl/AI5000IE-O Reactor Trip or Safety Injection
6. EP/I/A/5000/E-2 Faulted Steam Generator Isolation
7. EPI1IlA5000IE-3 Steam Generator Tube Rupture
8. EP/I/N5000/FR-Z.1 Response to High Containment Pressure
9. RPIOIA/57001000 Classification of Emergency
Author:
Facility Review:
NRC Review"
December 0, 2001
Rev. 1
1
SIMULATOR OPERATOR INSTRUCTIONS
[] Sim. Setup Rod Stop On
- . IC-144
[] RUN
o3 Update Status Board, See Shift Turnover Information
Setup OAC
Setup ICCM, Turbine
Displays, & Trend
Recorders.
Check Rod Step
Counters agree with rod
positions
o (M) EPQ001A Loss of D/G "IA"Control Power
Set = Rack Out
o (LOA) CA009 Rackout breaker for "IA" Auxiliary Feedwater Pump
Set = Racked Out
o (MAL) ISE006A Blocks auto main steam isolation
(MAL) ISE006B
Block auto
O (MAL) ISE004B Failure of Phase "B"train "B" to actuate
Block auto
O] (M) ISE002A Failure of automatic Safety Injection - both trains
(M) ISE002B
2
V~ E~ T OESOWIPTION, ~~A< <
-Freeze.
o] Update Fresh Tech.
Spec. Log.
o Fill out the NLO'e
Available section of
Shift Turnover Info.
o Prior to Crew
Briefing
RUN
o] Crew Briefing
1. Assign Crew Positions based on evaluation requirements
2. Review the Shift Turnover Information with the crew.
3. Direct the crew to Review the Control Boards taking note of present conditions, alarms.
o T-0 Begin Familiarization
Period
o At direction of
examiner
(XMT) NV030 Fails NV letdown back pressure regulator - causes a loss
of letdown
Set = 0
o At direction of
examiner
(XMT) CF020
Set= 0
Steam Generator "B"Narrow Range Instrument Fails
Ramp = 5
Q At direction of
examiner
(MAL) NV0O8C Initiates leak on charging line
Ramp = 10
Set = 25
3
Bench Mark ACTIVITY DESCRIPTION
-l At direction of (MAL) IRE001 Power Mismatch Circuit Failure
examiner Set = 557
At direction of (MAL) SM007A Initiates a Steam Leak
0] examiner
Set = 3e4
Ramp 200
Q At direction of (MAL) SM007A Initiates Steam Break
examiner
Set = 4e6
Set to trigger 1
(MAL) SM001A Initiates a SGTR
Set = 200
Set to trigger I
-5- Terminate the scenario upon direction of Chief Examiner
4
EVENT: Normal Operations - Turbine Load Decrease
SRO Notifies SOC of load increase
SRO Increases load per OPIIIN63001001A and
OPI1IAG6100103
Determines load changing rate
RO Depress the "LOAD RATE" pushbutton
RO Set the selected rate of load change in the
"Variable Display" window
RO Depress the "ENTER" pushbutton
RO Depress the "REFERENCE" pushbutton
RO Set in the desired load
RO Depress the "ENTER" pushbutton
RO Depress the "GO" pushbutton
RO erify that the load starts to change at the
selected rate
Event: Normal Operations Rod Insertion
SRO Provide guidance to RO on expectations for rod SRO should provide some general
wthdrawal on load increase. guidance as to using rods to maintain
maintains control rods within insertion limits Iave within a pre-determined range of
AFD within target band Tref.
RO Will withdraw rods as necessary based on
nstructions from SRO
BOP Will dilute NC system per guidance provided
I I
I I
5
Event: Letdown Back Pressure Instrument Failure
SRO EZnters AP/12 Loss of Letdown, Charging or Seal
Injection
BOP On a loss of letdown ensure the following Immediate action step
closed:
- 1 NV-457A
BOP If at any time "REGEN HX LETDN HI TEMP' BOP will take action if appropriate
larms, close:
RO Stop and power or temperature changes in
progress
RO Announces occurrence on page
BOP Checks "1B" NV pump- ON
BOP Checks to following NV pump parameters
stable:
- Motor AMPs
- Charging header pressure
- Charging flow
BOP Checks seal injection flow parameters:
- Seal flow to each NC pump > 6 gpm
a Seal Water Inj Filter Hi D/P alarm - DARK
SRO IF this AP entered due to loss of letdown only, SRO will go to step 35 in this AOP
then go to step 35.
BOP Ensures "NCSys M/U Controller" in AUTO
SOP Ensures charging flow going down to maintain
Pzr at program level
SRO NOTE: A failure of the letdown pressure
instrument may cause loss of letdown.
BOP Checks "Letdn Relief Hi Temp" alarm has No, crew should evaluate note prior
remained dark to step 37.
6
Event: Letdown Backpressure Instrument Failure
N'
4A~lI. XŽ> i
S........
r-7- .. r,
BOP Checks Pzr heater group supply breakers
closed
YES
NO, go to step 42
BOP Checks the following OPEN
" INV-2A
" 1NV-2A
go to step 46.
SRO Checks to see if immediate restoration of normal Yes,
letdown is possible
" Both NV 1 & 2 open in the past 30 minutes
" Orifice isolation valves closed before or at the
same time as NV I &2.
Establish normal letdown Crew should determine normal letdown
BOP control is not available and establish
1. Ensures 1NV-459 is closed excess letdown.
2. Place 1NV-124 in manual between 10-20%
open 1. Opens the following
3. Establish cooling to Regenerative Hx by * 1KC-315
performing the following concurrently:
- 1 KC-305
"LThrottle open 1NV-238
"* Throttle INV-241 to establish approximately 8 2. Places 1 NV-27B to VCT position
gpm seal injection
3. Opens and closes 1 NV-26
Check the following OPEN
1NV-1A 4. Checks to following OPEN
1NV-2A * INV-94
5. Open letdown line isolation valves: * 1NV-95
5. Opens INV-24 and 1NV-25
- INV-2A & Slowly opens INV-26
- 1NV-35A 7. Notifies chemistry that excess
1. Establish desired letdown rate by completing letdown is in service.
the following concurrently:
" Slowly throttle open 1NV-459
" Adjust 1NV-124 to maintain letdown pressure
between 250 and 350 psig.
2. Do not continue until desired flow rate is
established.
3. Adjust charging flow as desired
4. Crew may stay on variable orifice or swap to
75 gpm orifice.
SRO End of Procedure
7
Event 2: Steam Generator "B' Narrow Range Level Failure
,, ifl
7*
BOP Refer to annunciator responses Per annunciator response and AP/06
the operator will swap failed channel to
" A-3 operable channel
"* B-3
RO Places Feed Regulator to Manual Immediate Action step
Restores S/G level to program level
RO Checks the following channel indicating the Immediate Action step
same:
"* Feed flow
"* Steam Flow
"*S/G Level
RO Checks S/G CF control valve in manual control YES
RO When the following are met then return affected
SIG CF control to automatic
1. Selected control channels indicated correctly
" Feed flow
" Steam flow
" S/G level
2 Affected S/G level restored to program level
3. Automatic control is desired
SRO Checks the reactor tripped NO
RO Maintains S/G level Go to step 7
RO Controls feed flow to maintain S/G NR level - at
programmed level
SRO Checks NC temperature with NC pumps on
stable or trending to programmed temperature
SRO Checks procedure enter due to failed controller
SRO Contacts I&E to repair failed controller Failure will not be repaired
Exit procedure
8
Event 3: NC System Leakage- Charging Line Leak AP-10 Evaluation
Pdt4*1f~k4m777ht8a77 i..7
- ý 7,'tl Q ZP I 1, - 3 .
BOP Report either of the following:
"* Pzr level decreasing
"* Pzr press decreasing
"* Containment Vent Isol (EMF39)
"Ice Cond Doors Open" Annunciator
SRO Go to AP/10 (Case II) NC System Leakage
and directs activities
BOP Report Pzr Level decreasing:
"* Report NV-238 opening
"* Open NV-241 while
maintaining 6 gpm
Seal Injection Flow
" Starts alternate NV Pump
" Reduce letdown to 45 gpm or isolate
letdown
- IfPzr level less than 11% then:
- Manually Trip Reactor
- Manually SI
RO lnnounce Occurrence on page
SRO If Pzr level can not be maintained go to step 1
SRO If location of leak is known, than initiate actions Crew may go to step 18
to isolate leak.
BOP Reports Pzr Pressure at or increasing to
2235 psig
RO Reports Main Steam line is INTACT
" Reactor power at turbine power
" NC loop T-Ave is stable
SRO IRefer to RPI000
SRO Ensures OPIOIA/6450111 done if NC leakage
exceeds Tech Spec leakage
SRO Ensures VCT aligned to FWST if VCT level goes
below 16%
9
qt
BOP Checks the following EMFs normal:
"*1EMF-38L
" 1EMF-39L
" 1EMF-40
a 1EMF-41
"1 EMF-46A
" 1EMF-46B
BOP Checks NC pump thermal barrier KC outlet flow GO to step 17
_computer alarms NORMAL
SRO If leak is suspected on letdown line near It should not be suspected there.
dlemineralizers
SRO If leak on letdown line, then isolate leak as Leak is not on letdown line.
follows:
If leak is on normal charging line then isolate as
follows:
1. close letdown isolation valves
- 1 NV-457A
Isolate charging:
- Close 1NV-244A
- Close 1NV-245B
- Manually throttle 1NV-238 to maintain 6-10 Crew should have already established
gpm seal injection flow per NC pump. excess letdown
SRO Checks the following NORMAL:
- Pzr Safeties
e Pzr PORvs
- PRT Conditions
SRO Checks CLAs level NORMAL
SRO Checks the NCDT NORMAL
SRO Checks the containment floor and equipment
sumps NORMAL
10
11
Event 4: Power Mismatch Circuit Failure
RO Recognizes Unwarranted Control Rod Insertion
and informs Crew.
" No turbine or reactor power excursion
" Tref normal
RO If more than one rod dropped - trip Rx
RO Places CRD Bank Selector Switch to manual RO places Rods in Manual
and verifies movement stopped
SRO Enters AP/14, Rod Control Malfunctions and
directs activities.
RO Perform the following to maintain T-colds 555
to 557 degrees.
- Lower turbine load or raise T-cold
Or
- Borate the NC system to lower T-cold
RO ,nnounce occurrence on paging system
RO Check all control banks aligned with associated
bank
RO Checks Rod Control Urgent Failure alarm
DARK
RO Checks to following reactor control instruments
NORMAL
"i Turb Imp Press Ch 1
"* T-ref indication
"* "IA" NC loopT-ave
"* "lB" NC loop T-ave
"* "lC"No loopT-ave
" '110" NC loop T-ave
RO Check Nuclear power P/R Channels
NORMAL
SRO rill go to enclosure 4 based on unwarranted
rod movement.
CREW Evaluates the following prior to any control rod
withdrawal:
" Ensures no inadvertent mode change will
occur.
"* Ensures rods are withdrawn in a deliberate
manner.
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Event 4: Power Mismatch Failure
CO.hecks the following normal:
"TurbImp Press Ch 1
" T-ref indication
BOP Checks the following channels - NORMAL
SRO Checks iffailed channel - HAS BEEN
IDENTIFIED.
RO When the problem is repaired then
Ensure T-ave at T-ref +/- 1 degree and auto
rod control is desired, then return rod control to
auto.
ýR-O Exits procedure
I I ...- I
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E-O Evaluation
Event: Steam Line Break Inside Containment with SGTR
I
ý
<F 4
AIO
EP/-U
Got ad aiectsactiitie
SRO Ro to EPiE-O andparects acthvices
with crew
SRO Reviews Foldout page
-RO lReport Reactor Trip:
rod bottom lights
reactor trip breakers open
I/R amps decreasing
RO Reports Turbine Generator tripped
"lTV's or GV's closed
BOP IReports ETA and ETB energized
RO Reports SI status light - LIT
BOP Report LOCA sequencers (A & B) actuated
SROP Announce "Unit 1 Safety Injection' on page
SOP Crew should take actions to correct
Checks ESF Monitor Light Panel Phase "B" alignment.
"* Groups 1,2 and 5 DARK
"* Group 3 LIT
"* Checks OAC in service
BOP Reports all Ss and St components in Group 4
NOT -LIT
RO R*eports that CA is running and at least 3 S/G's
NR level > 17%
BOrP Reports KC pumps running
BOP lReports RN pumps running
-I
14
Event: Steam Line Break Inside Containment
SRO Directs Unit 2 Operator to throttle RN to EXAMINER CUE:
minimum &start 2A RN pump 2A RN pump Is running
RO Checks/reports all S/G pressures > 775 psig
BOP Reports Containment pressure has remained NO
less than 3 psig
BOP Report NV Pump to Cold Leg Flow gauge
indicating flow - YES
" checks NC pressure < 1600 psig
"checksNI pumps indicating flow - NO
SRO When available notifies OSM or other SRO to
implement Generic Enclosure 22
RO @ Checks CA flow > 450 gpm and takes
control of CA to maintain no load levels
" checks VI header pressure > 60 psig
" Maintains N/R level between 11% and 50%
BOP Checks NC pumps ON and Tave stable or If not stable and decreasing crew will go
trending to 557 degrees to Enclosure 3
BOP Reports Pzr PORV & Spray Valves closed
BOP Reports subcooling > 0 deg.
BOP Reports all main steamlines INTACT NO, crew will go to F-2 and implement
F-0 - Crew should go to Z-1
15
Event: Steamllne Break Inside Containment with SGTR Z -1 Evaluation
CREW If loss of emergency coolant recirc has occurred,
THEN this procedure may be completed as time
allows.
CREW Monitors foldout page
BOP Stop all NC pumps
BOP Ensure all RV pumps are in manual and off.
SRO Dispatch an operator to remove tags and close
breakers for the following valves:
" 1NI-173A
" INI-178B
BOP Checks containment pressure - LESS THAN 15
PSIG.
BOP Check any NS pump - ON
SRO The remainder of this EP may be performed as
time allows.
I
_____________
_i-I
16
Event: Steam Line Break Inside Containment E-2
Crew Alonitors foldout page
Crew Vlaintamns one SAG available for NC system
cooldown
SRO hecks the following closed,
o All MSIVs
- All MSIV Bypasses
SRO Check at least one SIG pressure - stable or
going up
RO Identifies faulted SIG;
" Any SIG pressure - going down in an
uncontrolled manner
" Any SIG depressurized
RO Checks faulted S/G PORV closed
RO Isolates faulted S/G as follows for "A"S/G:
" Check S/G A FDW Isolated status light LIT
" Close 1CA-66A
Close 1CA-62A
Close 1SM-83
SRO Checks if SIG tubes INTACT NO, 1EMF-24 will indicated a tube leak
Checks EMFs normal
"* IEMF-24
"* 1EMF-25
"* 1EMF-26
"* 1EMF-27
SRO Go to EP-E-3 Steam Generator Tube Rutpure
17
Event: STGR on "A"S/G E-3 Evaluation
Even: STR on SIG
1"A" E-= vluto
SRO Implement CSF Status Trees and go to Erit--
I SRO Go to EP/E-3 and directs activities
SRO INonitor foldout page
RO/ Identify "A"as the ruptured S/G
RO Check at least one S/G - AVAILABLE FOR NC
SYSTEM COOLDOWN
RO Isolate steam flow from ruptured S/Gs as
Follows:
checks ruptured S/G PORV closed
RO ICheck SIG 1B and 1C INTACT
RO Check blowYdown isolation valves - CLOSED:
"* 1BB-1
"* 1BB- 5
and check "CLSDL" light lin for
BOP Close steam drain
ruptured S/Gs:
RO Close the following on ruptured S/Gs:
"* MSIV
"* MSIV bypass valve
RO Checks ruptured S/G NR levels greater than
11% (32% ACC)
Isolates feed flow to "D' S/G
"* Closed 1CA-66A
I"* Closed
I
1CA-62A I
-I- I I
Event: SGTR on"D" Steam Generator
18
BOP hecks Pzr PORV and isolation valves:
Power to all Pzr PORvs available
All Pzr PORVs CLOSED
At least one Pzr PORV isolation calve OPEN
RO Checks main stream lines intact NO, "A" depressurizing or depressurized
"AllS/G pressures stable or going up
"AllS/G pressurized
BOP Reset the following:
" S/I
"* Sequencers
"* Phase A isolation
"* Phase B isolation
BOP Established VI to containment
" 1VI-129B open
" 1VI-160B open
" 1VI-150B open
" Checks VI header pressure > 85 psig.
RO Controls intact S/G levels:
"* N/R level in all intact S/Gs > 11% (32%
ACC)
" Throttles feed flow to maintain intact SIGs
NIR levels between 22% and 50%
BOP Checks 1ETA and 1ETB energized by offsite
power
SRO Checks ruptured S/G identified
SRO Checks the following closed on ruptured S/G:
a MSIV
- MSIV bypass valve
SRO Checks ruptured S/G pressure greater than 280 NO, crew should go to ECA 3.1
psig.
Note to Examiner: Be sure SRO classifies event at end of scenario.
Classification of Event: Site Area Emergency
19
SHIFT TURNOVER INFORMATION
UNIT I STATUS:
Power Level: 100% NCS [B] 66 ppm Pzr [B]: 66 ppm Xe: 2895pcm
Power History: At this power for 400 days Core Bumup: 440 EFPDs
CONTROLLING PROCEDURE: OPI1IN6100103 Controlling Procedure for Unit Operation
OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:
"IA' Diesel Generator tagged for maintenance.
"IA" Auxiliary Feedwater Pump Tagged for PM
Unit 2 is available for auxiliary steam
Begin load reduction to take the plant to mode 6 to begin refueling outage.
Reactor group has determined it will take 300 gallons of boric acid for the shutdown.
Insert 50 gallons of acid to begin shutdown and use rods for AFD control.
Begin load reduction at 2 MW/min.
Work Control SROiOffsite Communicator Thad
Jim
Unit 2 SRO
NLO's AVAILABLE
Unit I Unit 2
Aux Bldg. Eric Aux Bldg Bill
Turb Bldg. Fred TurblService Bldg Buster
Extra(s) Mark, Bruce
20