ML032340709
| ML032340709 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/16/2003 |
| From: | Operator Licensing and Human Performance Branch |
| To: | Duke Energy Corp |
| References | |
| 50-369/03-301, 50-370/03-301 | |
| Download: ML032340709 (110) | |
See also: IR 05000369/2003301
Text
Administrative Documents
MCGUIRE JUNE 2003 EXAM
50-369/2003-301 AND
50-37012003-301
JUNE 16 30,2003 -
/I. Exam Preparation Checklist .................... ES-201-1f
2
. Exam Outline Quality Checklist . . . . . . . . . . . . . . . . . ES-201-2
4.Exam Security Agreement . . . . . . . . . . . . . . . . . . . . . ES-201-3 ~
4. Administrative Topics Outline (Final) . . . . . . . . . . . . . ES-301-1
/ 5. Control Room Systems and Facility Walk-through Test Outline
(Final) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I ES-301-2
6. Operating Test Quality Check Sheet . . . . . . . . . . . . . ES-301-3
7. Simulator Scenario Quality Check Sheet . . . . . . . . . . ES-301-4
8. Transient and Event Checklist . . . . . . . . . . . . . . . . . . ES-301-5
9. Competencies Checklist ...................... ES-301-$-b
4 0 . Written Exam Quality Check Sheet . . . . . . . . . . . . . . ES-401- . b
/ 11. Written Exam Review Worksheet
. . . . . . . . . . . . . . . . ES-401-9 .,
J 12. Written Exam Grading Quality Checklist . . . . . . . . . . ES-403-1
~ 1 3 .Post-Exam Check Sheet . . . . . . . . . . . . . . . . . . . . . . ES-501-1
ES-201 Examination Preparation Checklist Form ES-201-1
)I Facility: McGuire Date of Examination: Weeks of June 16 and 23,200:
I
Target Chief
Date* Task Description /Reference Examiner's
Initials
-1 80 1. Examination administration date confirmed (C.l .a; C.2.a & b) RSB
-120 2. NRC examiners and facility contact assigned (C.l .d; C.2.e) RSB
-120 3. Facility contact briefed on security & other requirements (C.2.c) RSB
-120 4. Corporate notification letter sent (C.2.d) RSB
[-go1 15. Reference material due (C.1.e; C.3.c)I I RSB
I
~~
-75 6. lntearated examination outline(s) due (C.l .e & f; C.3.d) RSB
_ _ _ ~ ~
-70 7. Examination outline(@reviewed by NRC and feedback provided RSB
to facility licensee (C.2.h; C.3.e)
-45 8. Proposed examinations, supporting documentation, and RSB
reference materials due (C.l .e, f, g & h; C.3.d)
-30 9. Preliminary license applications due (C.l .I; C.2.g; ES-202) RSB
-14 I O . Final license applications due and assignment sheet prepared RSB
(C.1.l; C.2.g; ES-202)
-14 11. Examination approved by NRC supervisor for facility licensee
review (C.2.h: C.3.f)
I RSB
12. Examinations reviewed with facility licensee (C.l .j; C.2.f & h; C.3.g) RSB
13. Written examinations and operating tests approved by RSB
NRC supervisor (C.2.i; C.3.h)
14. Final applications reviewed; assignment sheet updated; waiver RSB
letters sent (C.2.g, ES-204)
15. Proctoringlwritten exam administration guidelines reviewed with RSB
facility licensee and authorization granted to give written exams
(if aDolicable) (C.3.k)
~~ ~
-7 16. Approved scenarios, job performance measures, and questions RSB
distributed to NRC examiners (C.3.i)
- Target dates are keyed to the examination date identified in the corporate notification letter.
They are for planning purposes and may be adjusted on a case-by-case basis in coordinatior
with the facility licensee.
[ ] Applies only to examinations prepared by the NRC.
23 of 25 NUREG-1021, Draft Revision 9
ES-201 Examination Outline Quality Checklist FOITIIES-201-2
Facility: Date of Examination: L- /q*fl?
item I Task Description
implement an alternate path
ency or abnormal condition. and
b. Facility Reviewer V)
Nolc * hol appl cablo for NRC.aevcloped examinat OnS
- mdependcnt NRC rev ewer milia1 Items m Colann 'c; chlof exam ner concurrence roqulred
NUREG-1021, Draft Revision 9 24 of 25
'
M
N
ES-301 Administrative Topics Outline Form ES-301-1
Facility: McGuire Date ofExamination: Weeks of June 16 and 23,2003
Examination Level (circle one): RO / SRO Operating Test Number:
Administrative Topic Describe activitv to be performed-
w
. .
Desw@w+ (see Note)
&La Evaluate Overtime Eligibility
Conduct of Operations (Modified)
Calculate ECP with an additional ECB calculation
Conduct of ODerations
A,1,B Evaluate a Work Order for Clearance to do Work.
EauiPment Control (New)
A73 Evaluate Liquid Waste Release with Fault
Radiation Control (New)
Evaluate Condition for PARS
Emerqency Plan
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless
ihev are retakinq only the administrative topics, when 5 are required.
22 of 27 NUREG 1021, Draft Revision 9
ES-301 Administrative Topics Outline Form ES-301-1
~~ ~
Facility: McGuire Date ofExamination: Weeks of June 16 and 23, 2003
Examination Level (circle one): RO I SRO Operating Test Number:
Administrative Topic Describe activitv to be performed-
-(see
. v. Note)
~~ ~ ~
A.1.a
Calculate QPTR with an Inoperable Power Range Instrument
Conduct of Operations and Make Technical Specification Evaluation
A.1.b Calculate ECP
Conduct of Operations
A2 Identify Boundaries for Tagout
Eauiprnent Control (New)
A73 Utilizing a Survey Map, Calculate the maximum permissible Stay
Time with the Alert limit ofthe Duke Power Basic Administrative
Radiation Control
limits.
A4
Emeraencv Plan
NOTE All Items (5 total) are reqdred for SROs KO applica<!s require onlv 4 items unles.?
they are retakinq only the adrn!nlstrativetoplcs when 5 are requireo
-
22 of 27 NUREG 1021, Draft Revision 9
ES-301 control Room/In Plant Systems Outline Form ES-301-2
L,'
system / JPM Title Safety
Type Codes* Function
a. Respond to a Leak on RHR While in Mid-loop D,S,L 4P
(SROU)
b. Calculate Boric Acid Pot and Perform Manual D,A,S 1
Makeup
c. Synchronize Main Generator (New Voltage N,S,A,L 4s
Regulator) (SROU)
d. Align for Cold Leg Recirculation D,A 2
e. Isolate Stuck Open PORV (Immediate Action JPM) D,A 3
f. Respond to a Failure of Power Range N-42 I D,A I 7
g. RN Alignment after a Loss of AC Power on Unit D,C 8
2 (SROU)
h. Start Up Unit 2 Lower Containment Ventilation D,C 5
systems
'v In-Plant Systems (3 for RO, 3 for SRO-I; 3 or 2 for SRO-U
~~ ~
a. Establish Reactor Coolant Pump Seal Injection D 2
from SSF
b. Start 1A Hydrogen Analyzer N, A, R 5
(SROU)
c. Manually Start 'H' Instrument Air Compressor D 8
for 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> run. (SROU)
NUREG-1021, Draft Revision 9
\u ES-301 Operating Test Quality Checklist Form ES-301-3
Facility: M t &i~ci*@ Date of Examination: %k C 'ZDOJ
Operatin
1. GENERAL CRITERIA
b. There is no day-tc-day repetition between this and other operating t&o be add
during this examination.
C. The operating test shall not duplicate items from the applicanl
d. Overlap with the written examination and between different PE
is within acceptable limits.
It appears that the operating test will differentiate between MI
2. W A L K . T H R O U G H ~
a Each JPM includes the foliowing. as applicable:
. system response and othq
- statements describing ii
criteria for successful o
- identification of CnWI 1
~
d. NRC Supervisor M m e L
~
NOTE * The facility signature is not applicable for NRCdevelopedtests.
- Independent NRC reviewer initial items in Column "c:"chief examiner concurrence required.
__ NUREG-1021, Draft Revision 9 24 of 27
ES-301 Simulator Scenario Quality Checklist Form ES-301-4
u
QUALITATIVE ATTRIBUTES Initials
a b'
1. Tne niua wno;rions are realist c. 'n that some eqL'pment and/or instrumentationmay De OJt of
SeN:ce. bJ1 it OOeS not cJe tne operalors nto expected evenu.
2. The scenarios wnsist mostly of related events. EP- @L
3. Each event description wnsists of
the point in the scenario when it is to be initiated
the maifunction(s)that are entered to initiate the event
the symptomstcues that will be visible to the a e w
the expected operator actions (byshift position)
the event termination point (if applicable)
4 ho more than one non-mecnanisuc fa Jre (e 9.. pipe brea4 is inwrporaleo nlo me Scenar 0
w mod1 a credib e precea ng ncioent SLCn as a seism c event
5. The events are valid with regard to physics and thermodynamics. I chldc
6. Seqdencng and tim ng of events s reasonaole. ana allows the exam.nat on team to obta n L b CN
wmpiete eva Jat on resLlls WmmensJrale wdh the scenar o ob:ectives.
7 If lime wmpression techniqJes are Jseo. tne scenario sLmmary c early so inoicates. Operators
nave sLffc'ent l m e to carry out expected acuviues without JnoJe t me wnstrainrs. CJes are
6. The simulator modeling is not altered. L4. coc
I 9. The scenarios have been validated. ~ ~ ~ ! r s ! ~ a ~ ~ ~ t ~ . l O . . ~ F .open
~ . . ~simulator
.~~46~~)~.~.~y
ii
performance deficiencies have been evaluated to ensure that functional fidelity is maintained
while running the planned scenarios.
d
10 Every operator w.II be evaluate0 Jsmg at least one new or significantly mootfed scenar 0 AI
I other scenar os have been altere0 n accordance w.th Section 0 45 of ES-301
I I
11. All individual operator competencies can be evaluated, asverified using Form ES-301-6 (submit
the form along with the simulator scenarios).
12 Eacn applicant will be sign.ficanily involveo .n the min mLm n m b e r of trans ents and evenls
spec fiea on Form ES-301-5 (sJbrn.1 rhe form w tn Ihe simL a m Scenar os)
I .I.,
13. The level of difficulty is appropriate to support licensing decisions for each crew position. 118 Idr-
I I I
TARGET QUANTITATIVE AlTRlBUTES (PER SCENARIO, SEE SECTION Actual Attributes -- --
I D.W52d)
1. Total malfunctions (5-8) 7 /7/
2. Malfunctions afler EOP entry (1-2) 2/21> a&
3. Abnormal events (2-4) 41% 4 %
I d
'
4. Major transients (1-2) 2 / L / I /A .., OJC
5. EOPs enteredtrequiring substantive actions (1-2) 2 / 2 . / 2 ck.(b(
6. EOP contingencies requiring substantive actions (0-2) 0 tDl0 wl
7. Critical tasks (2-3) 2 1212
25 of 27 NUREG-1021, Draft Revision 9
ES-301 Transient and Event Checklist Form ES-301-5
..-,, OPERATING TEST NO.:
I Reactivitv 1"
Normal 0
I AsRO e
I strument
omponen
Maior
c 21
1
Reactivity 0
I Normal 1'* 1, sf 1
u I
s,piu e
I strument
omponen
Major
c 21
1
2-6
7
2-6
7
Instructions: (1) Enter the operating test number and Form ES-D-1 e\ent numbers for
each evolution type.
(2) Reactivity manipulations may be conducted under normal or controlled
abnormal conditions (refer to Section D.45.d) but must be significant per
Section C.2.a ofAppendix D. * Reactivity and normal evolutions may b e
replaced with additional instrument or component malfunctions on a one-
for-one basis.
(3) Whenever practical, both instrument and component malfunctions should
be included; only those that require verifiable actions that provide insight
to the applicant's competence count toward the minimum requirement.
Author: Charles Sawyer
NRC Reviewer: Richard S. Baldwin
26 of 27 NUREG-1021, Draff Revision 9
ES-301 Transient and Event Checklist Form ES-301-5
Reactivity 0
I Normal I* 1
I SRO-U
3-4
8
I strument
omponen
2: 2-6
28,
Major 1 7 7
Author: Charles Sawyer
N R C Reviewer: Richard S. Baldwin
26 of 27 NUREG-1021, Draft Revision 9
-\ ES-301 Competencies Checklist Form ES-301-6
SRU 1
- 1
Rmt
Competencies
-
v
-
Interpret I Diagnose Events
and Conditions
Comply With and
Use Procedures (1)
Operate Control
Boards (2)
Communicate and
Interact-
Demonstrate Suoervisow A
NRC Reviewer: _
27 of 27 NUREG-1021, Draft Revision 9
b' ES-301 Competencies Checklist F o ES-301-6
~
nse type and enter one or more event numbers that will allow the
/
NRC Reviewer:
27 of 27 NUREG-1021, Draft Revision 9
--1 ES-301 Competencies Checklist F o ES-301-6
~
.. ,.
u
. ; ..,
.&.,
ctions:
one or more event numbers that will allow the
for every applicant.
I
NRC Reviewer:
27 of 27 NUREG-1021, Draft Revision 9
I
ES-301 Competencies Checklist F o ES-301-6
~
nse type and enter one or more event numbers that will allow the
petency for every applicant.
NRC Reviewer:
27 of 27 NUREG-1021, Draft Revision 9
I ES-401 Written Examination Form ES-40136
Quality Checklist
i/ -acility: McGuire Exam: Weeks of June 16 & 23,2003 Exam Level:
I
I
ii
7. Between 50 and 60 percent of the questions on
randomlv selected KiAs suwort the hisher
c.ognit.!vc.!s!vc!.s; enter the actual .R.O./.S.R.O
)
8. Referenceslhandoutsprovided do not give away answers cp. &C
9. Question content conforms with specific KIA statements in the previously
approved examination outline and is appropriate for the Tier to which they
are assigned: deviations are justified
& ($1
10. Question psychometric quality and format meet ES, Appendix B,
guidelines
11. The exam contains ~ t t I . e . r e ~ . u ~ ~ ~ e d . . n uone-point.
r r ~ b . ~ . .multiple
~f choice ,&?
items; the total is correct and agrees with value on cover sheet
Date
a. Author 4-/7.0.
b. Facility Reviewer r)CIWcbli cord q-Il-bS
c. NRC Chief Examiner (#) &&&o 5. %L04J,n) A A ? - lhaj-aa
d. NRC Regional Supervisor A I C & i
EL f. ER S . I C J ) U C , a d/ /& ,OJ
L .-' Note: * The facility reviewer's initialskignature are not applicable for NRC-developed examinations.
3004 34 NUREG-1021, Drafi Revision 9
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ES-403 Written Examination Grading Form ES-403-1
Quality Checklist
Facility: McGuire Date of Exam: June 30,2003 Exam Level: W/SRO
Initials
ling examinations checked to ensure that grades
Printed Name / Signature Date
a. Grader Richard S. yd=J
b. Facility Reviewer(*) N/A
c. NRC Chief Examiner (*) @hL, 0L11 ch"d- 0-
d. NRC Supervisor (*) /*)ICWOEL * Eauw/m.&/ fGjlf; 712 Y / s ,
(*) The facility reviewer's signature is not applicable for examinations graded by the
NRC; two independent NRC reviews are required.
5of5 NUREG-1021, Draft Revision 9
ES-403 Written Examination Grading Form ES-403-1
Quality Checklist
Facility: McGuire Date of Exam: June 30,2003 Exam Level: R O 1 m
Initials
I
Item Description a
1. Clean answer sheets copied before grading &
documented
3. Applicants' scores checked for addition errors
(reviewers spot check > 25% of examinations) m
4. Grading for all borderline cases (80 +/- 2% overall and 70 +/-
4% on the SRO-only) reviewed in detail w
5. All other failing examinations checked to ensure that grades
are justified
M
6. Performance on missed questions checked for training
deficiencies and wording problems; evaluate validity of P%
questions missed by half or more of tho applicants
Date
a. Grader Richard S. Baldwin 7/ZBj33
b. Facility Reviewer(*) N/A
c. NRC Chief Examiner (*) Uh\w+, O;;h&>) ~ / /c&@&A&-- ;/z </O>
d. NRC Supervisor (*) P7lCUc)EL E.EAP)SIPS/4E:iz..2k- 7 1 2 6 /Q>
(*) The facility reviewer's signature is not applicable for examinations graded by the
NRC; two independent NRC reviews are required.
NUREG-1021, Draft Revision 9
ES-501 Post-Examination Check Sheet Form ES-501-1
Task Description Date
Complete
1. Facility written exam comments or graded exams received and 7/08/03
verified complete
~ ~ ~ ~ ~
2. Facility written exam comments reviewed and incorporated and 711 6/03
NRC grading completed, if necessary
3. Operating tests graded by NRC examiners 7/28/03
4. NRC Chief examiner review of written exam and operating test 7/28/03
grading completed
5. Responsible supervisor review completed 7/29/03
5. Management (licensing official) review completed 7/30/03
7. License and denial letters mailed 7/30/03
3. Facility notified of results 7/30/03
3. Examination report issued (refer to NRC MC 0612) 8/7/03
IO. Reference material returned after final resolution of any NA
a p pe aIs
210f 23 NUREG-I 021, Draft Revision 9
NRC EXAM
2003
SCENARIOS
Appendix D Scenario Outline Form ES-D-1
Facility: McGuire Scenario No.: 1 Op-&t NO.:
Examiners: Operators:
Initial Conditions: 100% Power, 'B' Train Components in Service, 'IA' Auxiliary Feedwater
Pump is tagged, 'IA" Diesel Generator is tagged, thunderstorms are in the area
Event Malf. Event Event
No. No. Type* Description
1 N (RO) Main turbine Bearing Oil Pump Test
2 C (BOP) 1NV-137 Fails to Hold UP Tank (ARP)
3 I (RO) S/G 'B' Steam Pressure Channel 1 Fails
4 C (BOP) ET6 Blackout due to Ground Fault
5 N (BOP) Establish Normal Letdovm
6 C (RO) '1 B' FWPT Trips and Runback to 50%
7 M ATWWLoss of Heat Sink
Second FWPT trips afier crew settles out in AOP.
No Auto SI, Failure of Auto Turbine Trip
TD CA pumps trips on overspeed
Failure of turbine to runback automatically
(N)ormal, (R)eactidty, (I)nstrument, (C)omponent, (Major
4004 41 NUREG-1021, Drat? Revision 9
PROGRAM: McGuire Operations Training
MODULE: Initial License Operator Training Class 21
TOPIC: Nuclear Regulatory Commission Simulator Exam
Scenario 1
REFERENCES:
1. McGuire Technical Specifications
2. PTIl /B/4250/028 Main Turbine Bearing Oil Pump Test
3. APIA /A/5500/03 Load Rejection
4. APII lA/5500/06 Loss of SIG Feedwater
i d
5. APll /A/5500/07 Loss of Electrical Power
6. AP/1/A/5500/12 Loss of Letdown, Charging or Seal Injection
7. EP/l/A/500O/E-O Reactor Trip or Safety Injection
8. EP/llA/5000/FR-S.1 Response to Nuclear Power Generation/An/VS
9. EPll/A/5000/FR-H.I Response to Loss of Secondary Heat Sink
10. RP/O/A/5700/00 Classification of Emergency
n
Author:
Facility Review:
April 3,2003
Rev.1
1
EVENT SUMMARY
i/ 1. Main Turbine Bearing Oil Pump Test.
2. INV-137 fails to HUT.
3. SIG B Channel 1 Steam Pressure fails High. Enter AP-6
4. IETB BIO. Ground fault on bus. Enter AP-7
5. Place Normal Letdown in service, per AP-12
6. Load Rejection due.to trip of 1B FWPT with a failure of the Turbine to runback. Enter AP-03
7. ATWS. Failure of Auto & Manual Rx trips, failure of Auto turbine trip on loss of 2ndFWPT. Enter E-0
and transition to FR-S.1.
a. Loss of Heat Sink. A MDCA tagged in Initial Conditions, B MDCA unavailable due to BO on IETB
and TDCA trips on over speed when started. Enter FR-H.l
2
_ _
I
SIMULATOR OPERATOR INSTRUCTIONS
Bench Mark, DESCRIPTIOI~~. ,. . . .
'u' Sim. setup
-
IC 130
RUN
Update Status Board, See Shift Turnover Information
Setup OAC
Setup ICCM, Turbine
Displays, &Trend
Recorders.
Check Rod Step
Counters agree with rod
positions
(M) EPQOOIA LOSS of DIG " 1 A Control Power
Set = 1
(LOA) CA009 Rackout breaker for " 1 A Auxiliary Feedwater Pump
Set = F
L'
(M) IPEOOIA Defeats automatic and manual reactor trips
(M) IPEOOIB
(M) IPE002A
(M) IPE002B
(M) DEH002B6 Blocks all turbine runbacks
(M) DEH003A Failure of Auto Turbine tripped blocked
3
I
'
Bench Mark ACTIVITY DESCRIPTION
(M) CA005 Turbine Drlven AFW pump trips on over speed
--+---
Failure of automatic Safety Injection - both trains
(M) ISE002B
Freeze.
, Fill out the NLO's
Available section of
Shift Turnover Info.
Prior to Crew RUN
Briefing
~~ -
rew Briefing
1. Assign Crew Positions based on evaluation requirements
?, Review the Shift Turnover information with the crew.
3. Direct the crew to Review the Control Boards taking note of present conditions, alarms.
T-0 Begin Familiarization
Period
At direction of (OVR) NV070D INV-137 to HUT
examiner
Select: ON
At direction of (XMT) SM016 'ails SIG " 6 Steam Pressure Channel 1 HIGH
examiner
Ramp = 10
Set = 1300, insert
At direction of (M)EP008B .oss of 1ETB due to ground Fault
examiner
Insert
illow manual closing of 1KC18B and 1KC-228B
(M) KC008C
Set = 0. insert
(M) KC007D
Set = 0, insert
Bench Mark I
.. .
j .
~.. . DESCRIPTION
. ..
I .
.. .
1
- ..
' '
,
' . , . ..
At direct.on of Initiates a oil leak on 1B FWPT
examiner
Set = 100, insert -
Trips the " 1 6 FWPT if necessary Initiates an turbine
runback - RO must manually runback the turbine
(M) LFOO3B
Af direction of (M) IWE002A Speeds up '"A FWPT
examiner
-
Set 125
(M) LF003A Trips the '"A FWPT and initiates an ATWS
(MAL) IPEOOIA Delete -Opens reactor trip breaker 30 seconds after
request by operator
(MAL) IPEOOIB
(MAL) ISE007A Allows feedwater to be reset in H-I
Block Both
(MAL) ISE007B
Block Both
Terminate the sceni upon direction of Chief Examiner
5
I
EVENT 1: . Normal Operations - PT/I/B/4250/028 Main Turbine Bearing Oil Pump Test
Pump
Ro Start Emerg Brg Oil Pump
RO Stop and ensure in Auto Emerg Brg Oil Pump
RO Verify Acceptance Criteria met.
6
I
Event 2: INV-137 Fails to HUT position
I
Event 3: Steam Generator1B Steam Pressure Channel 1 Failure HIGH
Pos. Expected Actions/ Behavior Comments
BOP Refer to annunciator responses Per annunciator response and API06
the operator will swap failed channel tc
A-2 operable channel
c-2
SRO Enters API06 Loss of S/G Feedwater
RO Places Feed Regulator to Manual lmmediafe Action
Restores SIG level to program level
RO Checks the following channel indicating the Immediate Action
same:
Feedflow Selects operable channel
Steam Flow
SIG Level
RO Checks the reactor trip breakers closed Yes
RO Monitor SIG NR Level If at any time SIG NR Level approache
17% or 83%, then trip Reactor
BOP Check CMICF feeding SIG
RO SIG level stable or trending to program
BOP Checks NC temperature with NC pumps on
stable or trending to programmed temperature
RO When the following are met then return affected
SIG CF control to automatic
1, Selected control channels indicated correctly
Feed flow
Steam flow
SIG level
2. Affected SIG level restored to program level
3. Automatic control is desired
~~
SRO \Contacts WCC to have WR written, have I&E IFailure will not be repaired
investigate and repair failed channel and
evaluate T.S.. Tech Spec 3.3.2.4.d.1 I3.3.2.d.2 I
3.3.4.3.b 13.3.3.19 116.10.1
Exit procedure
At this time 1ETB blacks out
8
I
i
Event 4: B/O 1ETB Ground Fault
Pos. Expected Actions/ Behavior Comments ,.
~~
Crew Recognizes loss of operating train " E T 6
SRO Enters AP/07 Case 2
BOP Checks bus energized and sequencer applying imediate Acfions
loads he DIG will not start due to a ground
ult on 1ETB.
BOP If both NV pumps off, Then isolate NORMAL imediate Actions
letdown.
Start opposite train:
NVpump
KCpump
RN'pump
Go to step 3
BOP Verifies NO Safety Injection has occurred 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
BOP Check D/Gs OFF - :S
BOP Check ND system in RHR mode at time of B/O o Go to steD 7
I
BOP lign KC as follows:
Places 1KC-51A to AUTO
Ensures the following are open
1 1KC3A
. 1KC-345A
thermal barrier valves open
raise KC flow to KF Hx by opening 1KC-14:
Ensures KC flow is less than 4000 gpm per
operating KC pump
-
BOP Chec6s any charging pump Running - YES
Check 1A RN pump - Running -YES
Ensure 1RN-86A is open
Throttle IRN-89A to desired cooling
SRO Notifies Unit 2 RO to start 2A RN pump XAMINER CUE:
4 RN pump is running
9
Pos. . Expected Actions/ Behavior, (' :,' .:.. " ' ,, Comments - . : . 2'
3 ". . L . *. '" I
. . ?, . . .
SRO Checks B/O on 1ETA No, go to step 22
SRO Dispatches operator to close:
IKC-2288
IKC-18B
SRO Checks 1B NO train - was in RHR mode No. Go to step 29
SRO Checks normal letdown - IN SERVICE No, have BOP place letdown back in
service per AP12.
SRO Will hand off to BOP AP-12 and direct him to BOP will place letdown back in service
place normal Letdown in service. And continue per AP-'l2.
on in AP-7
RO Check VCT make up Control system
~~ ~
RO Announce occurrence on page
SRO Check if an SI has occurred during the event. An SI has not occurred; the SRO will ga
to the RNO. He may ask the Unit 2 BOF
to perform EP/1/N5000/G-1 Encl. 13 or
he may direct the Unit 1 RO to perform
it. It is time critical to have the enclosure
initiated within 30 minutes of the BO
SRO Have available licensed operator initiate Encl. 7 He may ask the Unit 2 BOP to perform
Encl. 7 or he may direct the Unit 1 RO
to perform it. It is time critical to have
the enclosure initiated within 30 minute:
of the BO
RO Checks DIG on bus that BO is on. If it is not
known that bus is locked out the RO will be
directed to attempt to start DIG.
SRO Will go to step 42 per RNO step 40. Determine
an SA has not occurred and go to step 44
RO Control CA flow All CA will be off.
RO Place recirc valve for KC pumps to auto for A
Train and to Close for B Train
SRO Will continue through AP-7
10
I
Event 5: Placing Letdown in Service
, . . . .
Time Pos. ' ' . Expected Actions/ Behavior Comrne'nts
BOP If a loss of charging through the Regenerative No
HX has occurred, Then ensure closed
lNV-458A
lNV457A
INV-35A
BOP Check PZR Level < 96%
If at any time "REGEN HX LETDN HI TEMP" BOP will take action if appropriate
alarms, close:
0 INV-1A
INV-2A
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 36 in this AP
then go to step 36.
Ensure Closed
lNV-458A
Bop Ensures "NC Sys MIU Controller" in AUTO
BOP Ensures charging flow going down to maintain
Pzr at Droaram level
BOP Checks "Letdn Relief Hi Temp" alarm has
remained dark
Bop Checks INV-21A-closed
BOP Checks Pzr heater qroup supply breakers -
1 Bop IChecks normal PZR Spray available
Place A, B, and D PZR heater groups in manual Maximizes spray flow
and on
Checks the following OPEN
SRo Go to step 48
11
.:' . .. , . . > , , , V ! ?;,: -
,,.:,.. .
" . ..
' . Expekteh Actions/ Behavior : "
stablish normal Letdown
Ensure 1NV-459 closed
Place INV-124 in manual and 10 to 20%
open
Check INV-1Aand INV-2Aopen
Establish Regenerative Hx cooling by
throttling 1NV-28 to establish 65 gpm
charging flow and throttling INV-241 to
establish 8 gpm seal flow
I NV-7B will not have power. Position
Open 1NV-78,I NV-IA, 1NV-2A & 1NV- vi11 be determined using OAC
35A
Letdown isolated < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
Throttle open 1NV-459 to establish
letdown flow
Adjust 1NV-124 to maintain Letdown
pressure between 250 & 350 psig
Adjust charging flow while maintaining sea
flow 5 6 gpm, Regenerative Hx temp.
380 degrees and PZR level at program.
Place 1NV-124 in auto
hen PZR level matches program level
Place 1NV-238 to auto
Adjust seal flow to 8 gpm
Notify Chemistry normal letdown is in
service
Check INV-127 aligned to Demin ;elect Demin if required
ODerate PZR heaters as reauired
When time allows notify Engineering to
document transients
Return to procedure and step in effect rP-7 Step 29
At this time an oil leak develops on 1B
FWPT
12
-~ ~- -~ ~-
I
Event 6: Trip of 18 FWPT due to oil leak - Failure of Turbine to Runback
Commenti
. ..
UE: NLO at FWPT reports oil is
xaying everywhere
SRO May decide to reduce load per AP-4 in an crew does not trip the 1B FWPT ther
attempt to get power low enough to secure the will be tripped to get them in a runbac
FWPT. or he may decide to trip the FWPT and
go to AP-3
CREW Recognizes trip of 1B FWPT and Load Rejectior
SRO Enters AP-03 Load Rejection
RO Ensures Control Rods in Auto his is an immediate action Step.
RO Check Turbine Generator Tied to Grid and 0 will take Turbine to manual and
output going down. :duce impulse pressure to 400-410
jig in fast action
RO Checks Control rods moving in as required &
aligned with associated bank.
BOP Checks proper CM system operation: OP Should start pumps and check
Standby Hotwell and Condensate Booster ianual loader OPEN
pumps RUNNING
.1 -
lCM-420 OPEN
I RO IEnsures impulse pressure decreasing to < 410
Psig
RO Check PIR meters less than 20% 0
SRO Designates an operator to continuously monitor
reactor power and go to step 9.
RO Checks condenser dump valves modulating
open
RO Checks load rejection -due to loss of CF pump
I I
t this time 1A FWPT will trip and initiate an
Event 7: ATWS with a loss of Heat Sink
Pos. Expected Actions! Behavior ' Comments, . ;; . .. '
'
, .. .. . . . ..
Crew Recognizes ATWS
RO Checks Reactor trip: RO should attempt to trip reactor using
switches and will realize the turbine ha
All rod bottom lights LIT l o t tripped and should trip the turbine.
Reactor trip and bypass breakers OPEN
IIR amDs - Goina Down
SRO Recognizes reactor did not trip and implements
F-0 and goes to FR-S.1
RO Checks Reactor trip: Manually inserts rods
All rod bottom lights LIT
Reactor trip and bypass breakers OPEN
IIR amps -Going Down
RO Checks turbine trip: Manually trips turbine if not already
ione.
All throttle valves closed
All governor valves closed
Crew IMonitors fold out page
BOP Checks proper CA pump status: IA Tagged out
MD CA pumps - ON I B no power 1ETB deenergized
Check NIR level in at least 3 SIGs greater TD CA tripped on over speed
than 17%
BOP Initiates emergency boration of NC system:
Ensures one NV pumps ON
Opens 1NV-265B INV-265B no power
Starts both boric acid transfer pumps
Checks emergency boration flow > 30 gpm Mill have to align NV pump suction to
he FWST
Checks INV-244A and INV-245B OPEN
I NV-245B position will be verified usin(
Checks Pzr pressure < 2335 psig IAC
BOP Close
1VQ-lA,IVQ-6A,lVQ-2B & 1VQ5B
14
SRO If an SI1 signal exists or occurs perform Encl. 3
SRO Checks the following trips have occurred: Dispatches operator to open:
Reactor trip Reactor trip breakers
Turbine trip Reactor trip bypass breakers
MIG Set Generator Breakers
MIG set Motor Breakers
RO Controls SIG levels: If CA flow is less than 700 gpm, then
start pumps and align valves as
Checks NR level in at least one SIG > 11% required,
.1 Checks VI header pressure > 60 psig (Maintain total CA flow areater than 70(
Throttles feed flow to maintain SIG NR level gpm until at least on S/G NR level
greater than 11%
between 11% and 50%
BOP Checks'all dilution paths ISOLATED
Places NC System MIU controller to OFF
1 Places Reactor Makeup water pumps to
STOP I
RO Checks steam lines intact: If any SIG depressurized or pressure
going down in an uncontrolled manner
-
AI1 S/G pressures Stable or Going UP the followingclosed:
All SIG pressurized All MSlVs
All MSlV bypass valves
BOP Checks NC T-colds - Stable or Goina UP
RO Checks Core Exit TICS 1200 degrees
SRO Checks the reactor subcritical: Yes
PIR channels < 5%
I/R SUR - NEGATIVE
WIR Neutron Flux c 5%
SRO Calls chemistry to obtain current boron
concentration
SRO Refers to RPIOOO Classificationof Emergency
SRO Return to procedure and step in effect. Due to RED Path on Heat Sink goes tc
H-I.
SRO Goes to FR-H.l
Crew Determines feed flow is less than 450 gpm but
not due to operator action
15
NC Pressure > greater than any non-faulted
SIG pressure
Anv NC T-hot - areater than 350 dearees
Crew Monitor foldout page At this point in the scenario Feed and
Bleed criteria may be met.
SRO IF Feed and Bleed Criteria met go to step 20
SRO Perform steps 21-25 quickly to establish Feed
land Bleed
BOP IEnsure NC pumps off
BOP Initiate SI1
BOP Check NV pumps to cold legs indicating flow
ISA-3 Is closed, linkage is
16
SRo IWCC informsthat'lA CA pump is available
SRo \Returnsto steo 7 in FR-H.l
SRo !Attempt to establish CA flow to at least one SIG I
Ro Check Power to both motor driven CA pumps 1A CA has power
Check that CA valves have been aligned per
Encl. 4
Ro Start 1A CA DUmD
Ro Check TD CA running NO
Ro Check total CA flow >450 gpm
SRo A CA pump running and step 35 has been
implemented .Go to Step 7h
Ro Check any SIG less than 12% WR At this point in scenario thefe should be
a SIG with less than 12% WR
Ro Check core exit TIC stable or going down At this point in scenario core exit TIC
may be going up.
SRo Will direct RO to open CA control Valve to either
A or B SIG (which ever had the highest level) to
establish flow rate required to lower core exit
17
Note to Examiner: Be sure SRO classifies event at end of scenario.
L.
Classification of Event: General Emergency due to:
1) Valid reactor trip signal received or required and automatic trip
was not successful.
AND
2) Manual reactor trip from the control room was not successful in
reducing reactor power t o less than 5% and decreasing.
AND
3) Heat Sink CSF-RED
18
r I
SHIFT TURNOVER INFORMATION
UNIT 1 STATUS:
L.
Power Level: 100% NCS [B] 953 ppm Pzr[B]: 953ppm Xe: 2895pcm
Power History: At this power since startup Core Burnup: 350 EFPDS
CONTROLLING PROCEDURE: OP/l/N6100/03 Controlling Procedure for Unit Operation
OTHER INFORMATION NEEDED TO ASSUME TO SHIFT
" 1 A Diesel Generator tagged for PM.
" 1 A Motor Driven Auxiliary Feedwater Pump tagged for oil sample.
Unit 2 is available for Auxiliary Steam
PT/l/B/4250/028' Main Turbine Bearing Oil Pump Test is scheduled to be performed
Vibration readings are not required for PT/I/B/4250/028
Work Control SROlOffsite Communicator Tim
u
Plant SRO Gary
NLO's AVAILABLE
-
Unit 2
Aux Bldg. Missy AUX Bldg. Warren
TurbBldg. AI Turb Bldg. Greg
51h Rounds. Tom
Extra(s) Richard, Andy
19
Appendix D Scenario Outline Form ES-D-1
Facility: McGuire Scenario No.: 2 Op-Zst NO.:
Examiners: Operators:
Initial Conditions: 35% Powr, 'B'Train Components in Service, ' I A Auxiliary Feedwater
Pump is tagged, ' 1 A Diesel Generator is tagged, thunderstorms are in the area
Turnover: Remove FWPT from Service
1 Event
No. 1 Malf.
No. 1 Event
Type' 1 ~ ~ ~ ~ ~ ~ ~ ~ ~~~ ~~~~~~~~~~~~~~~~~~~~~~~~~~
Event
Description
1 N (RO) Remove FWPT from Service
2 C (RO) ICF-20 Feed Regulating Valve Fails OPEN
3 I (BOP) Pressurizer Pressure Channel 1 Fails HIGH uith
Spray Valve Failure
A C (BOP) 1RN-1878 Fails Closed -Loss of RN to KC
5 C (RO) ISB-12 Condenser Dump Fails OPEN
6 C (BOP) 1KC-132 Erratic -Letdown Heat Exchanger Valve
_ _ _ - ~ 1
No Auto SI
4
- (N)ormal, (R)eactiuty, (I)nstrument, (C)omponent, (Major
4004 41 NUREG-1021, Drafl Revision 9
PROGRAM: McGuire Operations Training
MODULE: Initial License Operator Training Class 21
TOPIC: Nuclear Regulatory Commission Simulator Exam
Scenario 2
REFERENCES:
1. McGuire Technical Specifications
2. OPlllN61001003 Controlling Procedure for Unit Operation
3. A P l l /A/5500/01 Steam Leak
4. APJI /A/5500/06 SIG Feedwater Malfunction
,4 5. APlllA/5500/11 Pressuizer Pressure Anomalies
6. APlllN5500120 Loss of RN
7. E P l l /N5000/E-0 Reactor Trip or Safety Injection
8. EPII/N5000/E-3 Steam Generator Tube rupture
9. RPIOIA/5700/000 Classification of Emergency
n
Author:
Facility Review:
April 3,2003
Rev.1
1
EVENT SUMMARY
b' 1. Remove from service one FWPT per OP/1/A/6100/003.
2. ICF-20 (C SIG FRV) fails open. Enter AP-6
3. Pressurizer Pressure Channel 1 fails High. 1NC-27 fails open. Enter AP-11
4. IRN-1878 closes, Loss of RN to operating KC Hx. Enter AP-20
5. ISB-3 (Condenser Dump Valve) fails open. Enter AP-1
6. 1KC-132 fails closed in Auto.
7. SGTR. Enter AP-10
8. Manual Rx Trip and SI. Enter E-0
9. Implement F-0 and Go to E-3 from E-0 step 21
10. LOOP
2
I
SIMULATOR OPERATOR INSTRUCTIONS
., . . . .
Bench Mark . ACTIVITY . . .
. .I. '
a DESCRIPTION
' C .
i/ Sim Setup Rod Step On
-
IC 131
RUN
Update Status Board, See Shift Turnover Information
Setup OAC
Setup ICCM, Turbine
Displays, & Trend
Recorders.
Check Rod Step
Counters agree with rod
positions
(M) EPQOOIA Loss of DIG " 1 AControl Power
Set = 1
(LOA) CA009 Rack out breaker for " 1 AAuxiliary Feedwater Pump
Set = F
W
(M) IPEOOIA Defeats automatic reactor trips
(M) IPEOOIB
(M) ISE003A Phase A Train A isolation fails to actuate automatically
(M) ISE007A FWI train A fails to actuate automatically
(M) ISE007B FWI Train B fails to actuate automatically
(M) IRE01088 Control Rod B8 stuck
(M) IREOIOFZ Control Rod F2 stuck
3
Bench,Mark.. . .'.. :'C:ACTIVIW.
.,. . .:&' .: . 1, ,. :... .. , ,..
.. .- ..., '..'DESCRIPTION . .. .,:. .:.':,!;,!
.
'
, .
. ../. . . . I . .
.' : ' . , i . a ' .
(M) EMF171 EMF-71 fails as is
(M) EMF174 EMF-74 fails as is
Set as is
(M) ISE002A Failure of automatic Safety Injection - both trains
(M) ISEOOZB
I Freeze.
Update Fresh Tech.
, Spec. Log.
Fill out the NLO's
Available section of
Shift Turnover Info.
Prior to Crew RUN
Briefing
2. Review the Shift Turnover Information with the crew.
3. Direct the crew to Review the Control Boards taking note of present conditions, alarms
T-0 Begin Familiarization
Period
At direction of (M) IFE006C Fails ICF-20 ( C S/g FRV ) open
examiner
Set 100,Ramp 20
At direction of (XMT) NC038 Fails PZR Pressure Channel 1 HIGH
examiner
Set 2500, Ramp 5
Trigger 1
At direction of (M) ILE003A Fails 1 NC-27 oDen
examiner
Set 100
Trigger 1
4
examiner
Set 100, Ramp 10
Set100 Ram
Set 450, Ramp 300
examiner
5
I
EVENT 1: ' Remove from service one FWPT per OPll/N6100//003
-
. . . . ~ ' , ,.I. i .. ...e : ~, . , .. r &.. , .I ',. 'I .'
1 .>. . .' .
'
.
~
'
Time Pos.'. ' , Expected'Actions/B'eha\;:ior.', ' ..' "Comments ' :
- ... ,
SRO Conduct a prejob br;ef Prejob brief will be conducted prior to
W taking turnover.
Ro Ensure AMSAC actuation is blocked
Ro Place FWPT's to Manual
Ro Raise speed on FWPT to remain in service until
an increase is seen in
CF suction flow
CF Hdr Press/ SM Hdr Press DIP
Turbine RPM
Ro Lower speed on FWPT to be removed from
service and raise speed on FWPT to remain in
service while maintaining constant
RO SID FWPT removed from service using
\
c 0PI1/N6250/001
RO Reduce speed of FWPT to be SID to minimum
RO Verify CF pump Recirc is open
Calculate program DIP
Adjust FWPT to obtain program DIP
Place FWPT in auto
6
Event 2: ICF-20 fails open
Pds. ' ' . 'Expected Actions/ Behavior Comments .
BOP Refer to annunciator responses er annunciator response and API06
le operator will swap failed channel tc
A-3
. c-3
perable channel
SRO IEnters API06 SIG Feedwater Malfunction
RO Places Feed Regulator to Manual mediate Action
Restores S/G level to program level
RO Checks the following channel indicating the mediate Action
same:
Feedflow
Steam Flow
SIG Level
RO Checks the reactor trip breakers closed es
> P-11
RO Monitor SIG NR Level at any time SIG NR Level approache
7% or 83%, then trip Reactor
BOP Check CMICF feeding SIG
BOP Checks NC temperature with NC pumps on
stable or trending to programmed temperature
RO When the following are met then return affected utomatic will not operate
SIG CF control to automatic
1. Selected control channels indicated correctl)
Feedflow
Steam flow
S/G level
2. Affected SIG level restored to program level
3. Automatic control is desired
SRO Checks procedure enter due to automatic
control of ICF-20 failing
ailure will not be repaired
failed valve and evaluate T.S.
Exit procedure
I
I
Event 3: Pressurizer Pressure Channel 1 Failure HIGH with INC-27 failed open
.
'POS. I ,. ., ,.
Expected Actions/ Behavior.
.:
Comments.
, .
..
.
.
.
,
. I
i
,
BOP Recognizeslreports PZR pressure decreasing
SRO llmolements AP/I IPzr Pressure Anomalies,
BOP Checks Pzr Pressure decreasing lmmediate action Yes
BOP Checks all channels the same lmmediate Action No Places PZR
Press Cntrl Select to back up channel
BOP Checks Pzr PORV's Closed Immediate action Yes
BOP Checks Spray Valves Closed lmmediate action 1NC-27 open takes
controller to manual and closes valve
~~~
~~
I
BOP /Checks Sorav Valves Closed
SRO Go to Step 9
BOP Checks NV-21A , CLOSED
BOP Checks Pzr A,B & D heaters ON Place Pzr heaters mode select switc
in manual
Turn on heaters as necessary to
control oressure.
~~ ~ ~~
BOP Checks I C PZR heater - ON If pressure below desired pressure,
then:
Place "Pzr PRESS MASTER in
manual
Control Pressure
When Pzr pressure return to normal
and automatic control is desired the
dace Pzr master in auto.
BOP Checks Pzr pressure going UP
SRO Go to step 22
SRO Ensures "Pzr PRESS REC SELECT" is on an
operable channel
SRO Will notify WCC to write WR, have I&E Failure will not be fixed
investigate and repair and evaluate T.S.
T.S.: 3.3.1.61 3.3.1.8.aI3.3.1.8.bl
3.3.2.1.d I3.3.2.3.a.3 / 3.3.2.5.c /
3.3.2.6.~/3.3.2.8.b/3.3.4.2/3.3.6.3/
3.4.1 13.4.11
8
I
Event 4 IRN-1876 (RN to KC Heat Exchanger) Fails CLOSED
Pos. . Expected Actions/ Beha& I Comments
BOP Recognizes loss of RN flow to KC HX
SRO Go to AP-20 Loss of Operating RN Train -
Lase 1
BOP IChecks for potential loss of LLI ~XAMINERCUE:
Check Unit 2 RN pumps that are aligned to Unit 2 RN pumps are Operating
LLI- operating properly properly
Check suction flow path -available
BOP Checks idle train available to start
IT0 start 1A RN pump performs the following I
1 Places manual loader for IRN-89A to 10%
OPEN
Starts 1A RN Pump
Ensures IRN-86A OPEN
SRO Go to step 4 Enclosures for local venting of RN
pumps and NV Pump cooling via gravit)
drain have not been performed.
BOP bheck 1A KC pumw on IN0
BOP Check 18 KC pumps on Yes
BOP Ensure 1KC-228B and IKC-188 open
Ensure 1KC-230A and 1KC3A closed
BOP Checks 1B RN pump running properly If BOP answers no, he will place IRN-
187 in manual and open (the
malfunction will prevent from opening).
He will then be directed to secure the
1B RN pump. The SRO will then go to
step 5
If the BOP answers yes, the SRO Will g(
to step 5
BOP Throttles IRN-89A to establish desired flow
while maintainina less than 16.000 aDm
GOlhnltioate reason for loss of RN train I
SRO Ensure CR Area Chiller in Service per Encl.3. Request Unit 2 RO to perform
SRO Swap operating equipment cooled by affected
train of RN to opposite train
9
. .. . I.,;
Expected Actions/.Behav;or
- . , % .
. ,. . .
. .. .. ,_ . .. . . . , ;I
Coniments , .:., . ..
Pos. . . . <
BOP Swaps trains of KC per Enclosure 2
Limits KC flow to 4000 gpm per operating KC
pump
Checks the following open:
1, 1RN-40A
2. IRN-41B
3. 1RN43A
4. Any KC pump running
Checks both ND pumps OFF
GotoStep19
Ensukes IRN-1878 select switch is in manual
Throttle open 1RN-89A to establish desired
flow to 1A KC HX maintain less than 16,000
gPm
Places 1K C d l A in the AUTO position
Ensure IKC-51A openslcycles
Starts 1Al and 1A2 KC pumps
Aligns Reactor Bldg header to 1A train as
follows:
1. Open 1KC9A
2. Open IKC-230A
3. Close 1KKC-228B
4. Close 1KC-188
Checks both ND pumps OFF
Places IRN-1878 Mode Select switch to
Auto
Check close 1RN-187B
Places control switch for 1KC-54B to close
position Stops 1B1 and 1B2 KC pumps
Stops 1B1 and 182 KC pumps
~
1OP Swaps trains of NV per OP/l/A16200/001B love to next event during swap of NV
ains
Enclosure 4.2
10
Event 5: 1%-3 (Condenser Dump Valve) Fails OPEN
Pos. Expected Actions1 Behavior Comments
- REWIRecognizes symptoms
.~ of a steam leak IT-ave-Tref annunicator may come in
alarm
T-ave decreasing
.I Power increasina I
SRO Enters AP-01 Steam Leak
Crew Monitors fold out page
RO Reduces turbine load to maintain:
Excore NI -less than 100%
NC loop D/Ts -less than 60 degrees
T-ave, atT-ref
BOP Checks Pzr level - at or going to programmed
level
SRO Will return to step 3 if Pzr level can not be
maintained.
RO Announces occurrence on Daae
-RO lldentifies and isolates leak:
Checks SIG PORVs -CLOSED
. Checks condenser dump valves - 1 OPEN condenser dump valve Will be OPEN
RO must select "OFF RESET" on
Checks containment conditions - NORMAL dump interlock Bypass channel
and B. Due to failure valve will not
Checks turbine driven CA pump - OFF
call WCC to have valve
Checks steam line drain valves - CLOSED
Checks Unit 2 -steam header pressure
SRO Exits procedure when leak is isolated.
11
I
Event 6: 1KC-132 fails Closed
BOP Takes manual control of 1KC132. Opens valve,
lowers UD Hx outlet temperature.
SRO Calls WCC to have WR written and Have I&E
investigate and repair.
12
I
Event 7: SGTR on "A" SIG
Time Pos.
- ecognizes symptoms of SGTR
nters AP-10 Case 1
hecks PZR level Stable or going up
1 BOP erforms the following
Charging flow 4 7 5 gpm
Ensures 1NV-238 opening
Open 1NV-241 maintain 6 gpm seal flow
Isolate letdown
Start 1A NV pump
SRO : PZR level going down with max Charging flow
)ired Tripping of Reactor and ensure SI1
itiated.
c
'
13
Event 7: SGTR on "A" S/G E-0 Evaluation
. . Comments . ., :.
. . . . ..
," .
. .
- rew Monitors Foldout page
RO Check Reactor Trip: mediate action
rod bottom lights I I rod bottom lights will not be lit due tc
reactor trip breakers open rods being stuck out. Per RNO RO W I
I/R amps decreasing ip Reactor and SRO and RO should
etermine the Reactor is tripped.
_ _ _ ~
RO Check Turbine Generator tripped mediate action
TV'sclosed
BOP Check CTA and ETB energized mediate action
-
RO Check SI status light LIT nmediate action
BOP Check LOCA sequencers (A & B) actuated mediate action
jRO/ Announce "Unit 1 Safety Injection" on page
BOP Checks ESF Monitor Light Panel
Groups 1,2 and 5 DARK
Group3 LIT
Checks OAC in service
BOP Checks Group 4, Rows A thru F LIT as .ut0 actuation of Phase A is blocked
Required ,OPwill
ensure both trains Phase A
Isolation are initiated
Align or start S/l and Phase A
components with individual
windows in Group 4 as
required.
BOP Check the following on Monitor Light Panel ,ut0 Action of FWI is blocked
.
Group 4 LIT
c-3
C-6
- OP will
Check OAC Monitor Light
Program for associated light
F-4 Align valves as required while
F-5 SRO continues on with the
procedure.
RO Checks CA is running and at least 3 SIG's NR
level > 17%
14
BOP Checks RN pumps running
SRO Directs Unit 2 Operator to throttle RN to EXAMINER CUE:
- minimum & start 2A RN pump 2A RN pump is running
RO Checks.all S/G pressures > 775 psig
BOP Checks Containment pressure has remained
less than 3 psig
BOP Checks NV Pump to Cold Leg Flow gauge -
indicating flow - YES BOP will ensure ND pump mini-flow
checks NC pressure < 1600 psig valves are open
SRO When available notifies OSM or other SRO to EXAMINER CUE:
implement Generic Enclosure 21 OSM will ensure Generic Enclosure
21 implemented.
RO Checks CA flow > 450 gpm and takes
control of CA to maintain no load levels
checks VI header pressure > 60 psig
Maintains NIR level between 11% and 50%
BOP Checks NC pumps ON and Tave stable or If not stable and decreasing crew will g
trending to 557 degrees to Enclosure 3
BOP Checks Pzr PORV & Spray Valves closed
RO Checks subcooling > 0 deg.
RO Checks all main steam lines INTACT
ROI Report S/G tube rupture parameters indicate PER RNO Implement F-0 and Go to E.
BOP that SIG tubes NOT intact
SRO Implement CSF Status Trees and go to E-3
15
~
I
Event: STGR on "A" SIG E-3 Evaluation
Pos. . ..,.,'. ...;:? ' Expected Actions/;Behavior ",', '* .,
. . ! .. . .,. : * ;.* \ 8:
z',.%'
. . ; ,
- , . .
,. .. ,~ .. ..I.
i_/
- REW Monitor foldout page
ROI Identify "A" as the ruptured SIG
~~
RO Check at least one SIG -AVAILABLE FOR NC
SYSTEM COOLDOWN
RO Isolate steam flow from ruptured SIGs as
follows:
checks ruptured SIG PORV closed
check SIG 1B and I C INTACT
check IBB-IB and 1BBdA Closed
.1 close ISM-83
RO IClose the following - on ruptured SIGs:
MSlV
MSlV bypass valve
RO Checks ruptured SIG NR levels greater than
11%
Isolates feed flow to " A SIG
Close 1CA-66A
Close 1CA-62A
BOP Checks Pzr PORV and isolation valves:
Power to all Pzr PORVs available
All Pzr PORVs CLOSED
c. At least one Pzr PORV isolation valve OPE1
RO Checks main stream lines intact:
All SIG pressures stable or going up
All SIG pressurized
BOP Reset the following:
SI1
Sequencers
Phase A isolation
Phase B isolation
BOP Established VI to containment
IVI-1296 open
1VI-160B open
IVI-1506 open
Checks VI header pressure > 85 psig.
RO Controls intact SIG levels:
NIR level in all intact SIGs > 11%
Throttles feed flow to maintain intact SIGs
NIR levels between 22% and 50%
BOP Checks 1ETA and IETB energized by offsite
power
SRO Checks ruptured SIG identified
i_/'
,
16
'b'
Ro
..11Checks the following closed on ruptured SIG:
MSlV
MSlV bypass valve
RO /Checks ruptured SIG pressure greater than 280 I
psig.
BOP Checks,any NC pump running
BOP When P-11 status light lit then block steamline
isolation and maintains NC pressure less than
1955 psig.
RO Initiate a NC system cooldown as follows: 3nce the RO has initiated a cooldown a
Determine required core exit temperature base -0OP will occur.
on lowest ruptured SIG pressure.
Check Condenser available
COND AVAILABLE FOR STEAM D U M P
status light - LIT
MSlV on intact SIGs OPEN
Place Steam Dumps in steam pressure mode.
When P-12 stat light lit place steam dumps in
bypass interlock.
Dump steam to condenser at max rate.
- REW Recognizes the LOOP B DIG starts and
energizes ETB. ETA is deenergized due to ?A
DIG tagged. Restarts SI1 equipment previously
ii on.
SRO Recognizes NCPs are off and loss of condenser
Vacuum. Returns to Step 15 in E-3
BOP Checks any NC pump running
BOP When P-I 1 status light lit then block steamline
isolation and maintains NC pressure less than
1955 psig.
17
Determine required core exit temperature base
on lowest ruptured S/G pressure.
I Check:
COND AVAILABLE FOR STEAM DUMP
status light - LIT
MSlV on intact S/Gs OPEN
MODE SELECT"
Adjust manual loader on intact S/G
PORVs as required to control intacl
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 TICS less than required
temperature.
RO Checks ruptured SIG pressure - stable or going
up
SRO Checks NC subcooling based on core exit TICS
> than 20 degrees
30P Depressurizesthe NC system Observe caution prior to step 21 and go
1. Checks ruptured S/G NR level less than to step 21
73%
2. Checks normal Pzr spray available
30P Depressurize NC system using one PZR PORV
18
satisfied .
NC Subcooling c 0
PZR level >76%
NC pressure < ruptured SIG pressure &
PZR level > 11%
BOP Check NC System Pressure going up
Crew Checks for SI1 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
.
I I
14. Pzr ievel greater than 11%
BOP Istop NI pumps and one NV pump
BOP Check NV pump suction aligned to FWST
I
Open INV-1508 & INV-151A
Close INI-9A &INI-lOB
19
SHIFT TURNOVER INFORMATION
UNIT 1 STATUS:
L
Power Level: 40% NCS[E.?] 13ppm Pzr [B]: 13 ppm Xe: 2895pcrn
Power History: At this power for 400 days Core Burnup: 440 EFPDs
CONTROLLING PROCEDURE: OP/l/N6100/03 Controlling Procedure for Unit Operation
OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:
" 1 A Diesel Generator tagged for PM.
"1A Motor Driven Auxiliaw Feedwater Pump . tagged
_.for PM
Unit 2 is available for Auxiiiary Steam
Remove 1B FWPT from service and Shutdown per 0P/l/N6100/003 Encl. 4.2 Step 3.6.13 to
repair oil leak.
Work Control SROlOffsite Communicator Tim
Plant SRO Gary
NLO's AVAILABLE
-
Unit 1 -
Unit 2
Aux Bldg. Missy Aux Bldg. Warren
TurbBldg. AI Turb Bldg. Greg
gTHRounds. Tom
Extra(s) Richard, Andy
20
Appendix D Scenario Outline Form ES-D-1
Facility: McGuire Scenario No.: Spare Op-Sst No.:
Examiners: Operators:
Initial Conditions: 100% Power, ' B Train Components in Service, '1A Auxiliary Feedwater
Pump is tagged, '1A Diesel Generator is tagged, thunderstorms are in the area
Turnover: Reduce Turbine Load to 90% to Perform Turbine Valve Movement Test
(N)ormal, (R)eactiwty, (I)nstrument, (C)omponent, (Major
40041 41 NUREG-1021, Draft Revision 9
PROGRAM: McGuire Operations Training
MODULE: Initial License Operator Training Class 21
TOPIC: Nuclear Regulatory Commission Simulator Exam
Scenario Spare
REFERENCES:
1. McGuire Technical Specifications
2. OP/l /A/6 100/003 Controlling Procedure For Unit Operation
3. AP/I/A/5500/06 S/G Feedwater Malfunction
4. AP/l/A/5500/10 NC System Leakage within Capacity of Both NV
u Pumps
5. AP/l/A/5500/14 Rod Control Malfunction
6. AP/l/A/5500/16 Malfunction of Nuclear Instrumentation
7. EPll/Al5000/EO Reactor Trip or Safety Injection
8. RPIO/A/5700/00 Classification of Emergency
April 3, 2003
Rev.1
1
EVENT SUMMARY
ii 1. Reduce power in preparation for Turbine Valve Movement Test
2. B NC loop T Cold fails High. Enter AP-14
3. D SIG NR Level Channel 1 fails Low. Enter AP-6
4. PR-42sfails. Enter AP-16
5. PZR Level Master fails
6. NC System Leak. Enter AP-10
7. Rods Ejection 2000 gpm NC system leak. Enter E-0
2
I
SIMULATOR OPERATOR INSTRUCTIONS
Bench Mark
Sim Setup Rod Step On
IC 127-
~
RUN
Update Status Board, See Shift Turnover Information
Setup OAC
Setup ICCM, Turbine
Displays, &Trend
Recorders.
Check Rod Step
Counters agree with rod
positions
(M) EPQOOIA Loss of DIG "1A Control Power
Set = 1
(LOA) CA009 Rack out breaker for "1AAuxiliary Feedwater Pump
Set F
(M) IPEOOIA Defeats automatic reactor trips
(M) IPEOOIB
(M) DEH003A Failure of Auto Turbine tripped blocked
~~ ~
(M) ISE003B Failure of Phase '"A train " Bto actuate automatically
Sel + BLK Auto
3
..
Bench Mark ...'... . .'iACTIVITY ;, ..
,: .., . '. ': : .: ;DESCRIPTION'
,. .. . . .
- . .
' I _ . '
. . . ,
1
" i : ..
(M) ISE002A Failure of automatic Safety 1n;ection - both trains
(M) ISE002B
Freeze.
Update Fresh Tech.
Spec. Log.
Fill out the NLO's
Available section of
Shift Turnover Info.
Prior to Crew RUN
Briefing
Crew Briefina "
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
T-0 Begin Familiarization
Period
At direction of (XMT) NC102 B NC Loop T-Cold fails High
examiner
Set = 630, Ramp = 10
At direction of (XMT) CF008 '"ASIG NIR Level Channel 1 fails Low
examiner
Set = 0, Ramp 10
At direction of (M) ENB013D Power Range N-42 fails High
examiner
Set =200, Ramp = 10
At direction of (OVR) N C l l l PZR Level Master fails High
examiner
Set 4 0 0 , Ramp = 60
At direction of (M) NC007A NC System leak 50 gpm
examiner
Set = .25, Ramp = 300
At direction of (M) NC005 Ejected rod M8. Leak rate increases to 2000 gpm
examiner
Set = 2000
Terminate the scenai upon direction of Chief Examiner
4
Event 1: Reduce Load per OP/l/N6100/003 Step 3.2
Ro Check quality Thermal power best OAC points
Operate PZR Heaters per OP/l/A6100/003
Enc1.4.3
I
Reduce Turbine load per OP/1/A/6300/001 A
(Turbine Generator Load Change)-. I
I
I CREW IMaintain Control Rods within insertion and
withdrawal limits per COLR
CREW Maintain' AFD within Target Band
RO At 98% power Place MW Loop in service
5
I
Event 2: B NC Loop T Cold fails High
POS. Expected.Actions/.Betiavior Comments '
RO IRecoonizes Unwarranted Control Rod Insertion knnunciator AD-6 B -10
IT-refr-auct Abnormal
SRO Enters AP-14. Stops load decrease
RO -
If more.than one rod dropped trip Rx lmmediate action
RO Places CRD Bank Selector Switch to manual lmmediate action
and verifies movement stopped
RO Check all control banks aligned with associated
bank
RO Checks Rod Control Urgent Failure alarm DARb
RO Checks to following reactor control instruments .oop " B T-ave identified
NORMAL
Turb Imp Press Ch 1 o; to Enclosure 4
T-ref indication
" 1 A NC loop T-ave
"1 B NC IOOD T-ave
"IC" NC loop T-ave
"1D" NC loop T-ave
SRO Goes to Enclosure 4
BOP /Announce occurrence on page
withdrawal:
Ensures no inadvertent mode change will
occur.
Ensures rods are withdrawn in a deliberate
manner. I
RO IChecks the following normal:
.1 Turb Imo PressCh 1 I
T-ref indication
RO Checks the following normal: Loop "B" Tave identified
" 1 A NC loop T-ave
"IB" NC IOOD T-ave .
BOP will perform the following:
Places DTT Defeat switch to failed
"1C NC loop T-ave
"1D" NC loop T-ave
I Places T-ave Defeat switch to
loop IOOD
failed . - - I ~
RO will perform the following as
necessary to maintain T-ave at T-ref:
Position control rods in manual
BoratelDilute NC system
Adjust turbine load
When T-ave at T-ref +I- 1 degree and
auto rod control is desired, then return
rod control to auto.
Ensure P-12 is in required state for
existing plant conditions
6
Tech Spec 3.3.1 and 3.3.2
ithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of failure.
OPDT
LowT-ave
SRO Checks if failed channel has been identified YES
SRO Call WCC SRO and have WR written, IAE to
investigate and repair and evaluate T.S.
t
Event 3: "A"SIG NR Level channel 1 fails Low
Pos. Expected Actions/ Behavior Comments
BOP Refer to annunciator responses Annunciators on 1AD-4
A-I Per annunciator response and API06
the operator will swap failed controller
B-1 from normal to alternate
RO Places Feed Regulator to Manual lmmediate Action
Restores SIG level to program level
RO Checks the following channel indicating the lmmediate Action
same:
Feedflow
Steam Flow
SIGaLevel
BOP Announce Occurrence on page
BOP Check Reactor Trip Breakers closed and > P-I 1
RO Monitor SIG NR Level If at any time SIG NR Level approache:
17% or 83%, then trip Reactor
BOP Check CMICF feedina SIG
RO SIG level stable or trending to program
BOP Checks NC temperature with NC pumps on
stable or trending to programmed temperature
RO When the following are met then return affected
SIG CF control to automatic
1. Selected control channels indicated correctly
Feed flow
Steam flow
SIG level
2. Affected SIG level restored to program level
3. Automatic control is desired
SRO Contacts WCC to have WR written, have I& Failure will not be repaired
investigate and repair failed channel and
evaluate T.S.
Exit procedure
8
I
Event 4: PR-42 fails High
BOP p n o u n c e occurrence on page
I I
RO Checks N-42 as only failed channel
RO Position "PR to S/G Program Level Channel
Defeat" switch to defeat inoperable channel.
RO Reports'power stable
BOP Complete steps to take channel out of service
and verifies proper lights - lit
RO Ensure operable PR channel selected to record
on NR45'chart recorder
RO Adjusts control rods to maintain T-Ave = T-Ref
RO When T-Ave = T-Ref to within + or - 1 deg-F.
then return Rods to "Auto" if desired
SRO Instruct IAE to fail associated BIS's for failed
channel
OPDT
BOP When IAE trips B/S's, verifies proper status
lights -lit
SRO Call WCC to have WR written, have I&E Instrument will not be repaired
investigate and repair and have T.S. evaluated
T.S. 3.3.1.2/3.3.1.3/3.3.1.6/3.3.1.7/
3.3.1.16.b/3.3.1.16.~/3.3.1.16.d
9
Event 5: Pressurizer Level Master fails High
.
-
1 Pos. 1 '.
. .
Expected A c t i o n s l B e h a h ' . : .: '1 ,
.
,
i
.. . . . . . , .
comments
. . . . . . , ..
. * ..
I I I
CREW Recognize charging flow increasing.
dREW Determine from plant conditions (NC System
temperature and pressure stable and PZR level
going up) that there is an instrument failure.
SRo
Direct BOP to place 1NV-238 in manual and
control charging flow.
SRo Contact WCC to write WR, have I&E investigate
and repair.
10
Event 6: NC System Leak 50 gpm
Pos. Expected Actions/ Behavior
- REW Recognize symptoms of a system leak
Ensure INV-238 opening
- REW Estimate leak rate
SRO Refer to RP/O/A/5700/000
BOP If at any time NC leakage exceeds T.S. place in
service Outside Air Pressure Filter Train
SRO Have another SRO evaluate if leakage exceeds
SLC 16.9.7 condition C limits
BOP If VCT level less than 16% swap NV pump
suction to FWST
BOP Check seal leakoff on NC pumps greater than 6
gpm
BOP Check Thermal Barriers intact
SRO Check if leak suspected on Letdown line near
Demineralizers
SRO Check leak on Letdown line
BOP Check the following normal, PZR Safeties, PZR
BOP Check CLA levels normal
BOP Check NCDT parameters normal
BOP Check Containment floor and equipment sumps
normal
SRO Check leak location identified
11
u
I/ I I
SRO Contact Station Management to evaluate need
to Shutdown
SRO Check unit shutdown required
SRO Shutdown per AP-4
SRO EnterAP-4
Initiate a 2000 gpm leak by ejecting control
rod M8
12
~
Event 7 NC System leak 2000 gpm due to ejected rod
I I I
I SRO IReviews Foldout page with crew INCP trip criteria based on loss of
subcooling
RO Report Reactor Trip: Immediate Action
rod bottom lights Reactor will be tripped manually
reactor trip breakers open
IIR amps decreasing
RO Reports Turbine Generator tripped Immediate Action
Wsclosed Turbine will be tripped manually
BOP Reports ETA and ETB energized lmmediate Action
RO Reports SI status light - not LIT Immediate Action
SA will be manually initiated
BOP Report LOCA sequencers (A & B) actuated Immediate Action
RO Announce "Unit 1 Safety Injection" on page
BOP Checks ESF Monitor Light Panel
Groups 1,2 and 5 DARK
Group 3 LIT
Checks OAC in service
BOP Reports all Ss and St components in Group 4
LIT
RO Reports that CA is running and at least 3 SIGs
NR level > 17%
BOP Reports KC pumps running
BOP Reports RN pumps running
.~~ Directs Unit 2 Ooerator to throttle RN to EXAMINER CUE:
lminimum & stari ZA RN pump .1 2A RN pump is running
I RO ICheckslreports all S/G pressures > 775 psig
I I I
BOP Reports Containment pressure has not
remained less than 3 psig
SRO Record time of reactor trip
BOP Reports Monitor Light Group 4, Row G, lit
BOP Stop all NC pumps while maintaining seal
injection
BOP Secure RV pumps
BOP Energize H2 Igniters
.:. ? , ,.: . :,. ,_.. ..
Pos.; I '
- . , '.. ....,,*.:':,&. : .,.,
.Expected Actions/,Bihavior
. .. > .,,
,.:,
..
+.;:.*,
.';."Comments.
,. 2'
..:
. . . . .i
, . ; .;
SRO Dispatch operator to secure all NF AHUs
BOP Perform Encl. 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 < 286 psig
checks ND pumps indicating flow
SRO When available notifies OSM or other SRO to EXAMINER CUE:
imolement Generic Enclosure 21 OSM will ensure Generic Enclosure
RO .1 Checks CA flow > 450 gom and takes
control of CA to maintain no load levels
121 is implemented.
I
che6ks VI header pressure > 60 psig
Maintains NIR level between 32% and 50%
BOP If any NC pump ON, then check Tave stable If not stable and decreasing crew will go
or trending to 557 degrees to Enclosure 3
If all NC pumps off, then check NC T-colds
stable or trending to 557 degrees.
BOP Reports Pzr PORV & Spray Valves closed One PORV will be open but isolated
BOP Reports subcooling < 0 deg.
BOP Reports all main steam lines INTACT
ROI Report SIG tube rupture parameters indicate
BOP that SIG tubes intact
BOP Checks if NC system is intact:
Containment EMFS- normal
Ice Condenser Lower Inlet Doors Open
alarm DARK -
Containment pressure < 1 psig
Containment sump level normal
I
SRO Implement F-0
- REW Evaluate CSF trees
SRO Enter FR-P.l
14
I
Event 7 FR-P.l Evaluation
Reports ND pump flow is > 500 gpm
SRo Return to procedure and step in effect and
enters FR-2.1
15
FR-2.1 Evaluation
-,.-
lhas not occurred and continue in procedure
Crew IMonitors foldout page
I
Bop [Ensure NC pumps and RV pumps are off.
2
SRO Dispatches operator to close breakers for
INI-173Aand INI-1788
Bop Reports containment pressure less than 15 psis
Bop Reports both NS pumps on
SRO Continues in FR-2.1
SRO Checks OAC in service
SRO Checks the following light lit on group 4
. c-3
c-6
G-4
G-5
SRO Checks NS system in operation as follows o to step 10.d
-
ECA 1.1 in effect NO
BOP Checks the following valves aligned
INS-18A - closed
1NSQOA - open
1NS-1B closed
1NS3B - open
Bop Reports containment pressure greater than 3
Psig
Checks the following valves open
INS-32Aand INS-29A
INS-128 and INS-158
checks NS pumps on
BOP Check phase "6" HVAC equipment per Encl.3
RO Checks MSlVs and MSlV bypass valves closed
RO Checks steam lines intact
SRO Checks if any ND train is operating in the cold
eg rec:rc mode - NO. When transfer to Cold
\Leg Recirc is complete perform step 14.
Go to step 15
SRO Ensures operator sent to stop NF AHUs
Checks H2 analyzers in service NO.
Send operators to put H2 Analyzers in service
Goes to E-I
16
I
Event 7 E-1 Evaluation
Time I Pos; .I . '
.
j' EXpected'Actioni! .o
Behavior
.. . %.
.
,
,.
. jl e;.
..
, . .c
. ,
. ',..
. I.
. . .. . , Y I . . ~.
'comment'$ '.
.*.,
..., :i ,
~
SRO Enters E-I
SRO Reviews fold out page with crew and reminds NOTE: When FWST decreases to
crew to monitor FWST level for 180 inches (Lo 180 inches, the crew should enter
level) EPIES-1.3 and manually swap to sum1
RO Reports subcooling less than 0
RO Reports main steam lines INTACT
All SIG pressures -STABLE OR GOING UP
AI1 SlGs - PRESSURIZED
RO Checks SIG level > 32%. Resets CA Modulating
Valves Reset switches and throttles CA flow as
necessalv to maintain 32-50%
I RO Fhecks Secondary EMFs - NORMAL
Reports Pzr PORV lsol Valves open 8, energized
and Pzr PORVs closed
SROI Checks SI Termination Criteria NOT met
RO Go to step 7f
BOP Checks NS status:
NS pumps ON -
checks containment pressure 2psig
Go to step 9
SRO/ Checks ND pumps on and aligned to FWST
BOP Check NC pressure > 286 psig
Go to step 11
SROl Reset SI and Load Sequencers and dispatch
BOP ooerator to locallv stoD DIGS
SRO Dispatch operators to locally stop NF AHUs and
place H2 Analyzers in service
17
Expected Actions/ Behavior Comments
valuate plant status:
I Any ND pump available
I Power available to
ower will not be available to A
IND-19A ain valves
INI-185A
IND-46
INI-1846
INI-1366
INI-147A
INI-1158
I S Latch LIT for:
INI-184B
INI-185A
I EMF41 NORMAL
I All area monitors NORMAL
I Notify Chemistry to sample appropriately
I Notify RP to sample Cont air
I Consult Station Management on recovery
eport NC pressure 286 psig and ND flow to
]Id legs is > 500 gpm
~~
- oto step 15
hecks transfer to cold leg recirc criteria
FWST level 180 inches
not return to step 13
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~~
Event 7 ' ES-1.3 Evaluation
SRO Enters ES-1.3 on FWST low level This procedure should be implemented
C' ithout delay.
SRO Have STA monitor fold out page
kRO This procedure should be implemented without
delay.
BOP Checks containment sump level >3 feet
BOP Checks KC flow to ND heat exchangers > 5000
BOP Resets SI and Load Sequencers
BOP IChecks NI-185A and 1A ND pump - ON
Bop Checks NI-1848 and 1B ND pump -ON
Bop Closes IFW-27A and checks ND pumps On
Aligns NV and NI systems
Check NC pressure < 1600 psig
Close 1NI-1158 & INI-144B
Close INI-147A
Close 1ND30A & 1ND-158
'u
Check open 1Ni-3348
Open INI-332A& 1NI-333B
Open 1ND-58A& INI-136B
Close INI-100B
Close INV-221A &INV-222B
Terminate Scenario upon direction of Examiner
Note to Examiner: Be sure SRO classifies event at end of scenario.
Classification of Event: Alert due to Greater than available makeup capacity as indicated
by loss NCS subcooling.
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SHIFT TURNOVER INFORMATION
UNIT 1 STATUS:
u
Power Level: 100% NCS[B] 13ppm Pzr [E]: 13 ppm Xe: 2895pcm
Power History: . At this power for 400 days Core Burnup: 440 EFPDs
CONTROLLING PROCEDURE: OP/l/Af6100/03 Controlling Procedure for Unit Operation
OTHER INFORMATION NEEDED TO ASSUME TO SHIFT:
" 1 A Diesel Generator tagged for PM.
"1A" Motor Drivkn Auxiliary Feedwater Pump tagged for PM
Unit 2 is available for Auxiliary Steam
Reduce power per OP/1/~6300/001(Controlling Procedure for Unit Operation) End. 4.2 in
preparation for Main Turbine Throttle Valve Movement Test.
Work Control SROlOffsite Communicator Thad
Unit 2 SRO Jim
NLO's AVAILABLE
Aux Bldg. Eric Aux Bldg Bill
Turb Bldg. Fred TurblService Bldg Buster
Extra(s) Mark, Bruce
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