ML20133L524
| ML20133L524 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/14/1984 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20133L516 | List: |
| References | |
| FOIA-85-419 5211-84-2119, NUDOCS 8508120643 | |
| Download: ML20133L524 (42) | |
Text
,.
f GPU Nuclear Corporation 1
El duclear
- = e m e :
48o o
s Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
May 14, 1984 5211-84-2119 Dr. Thcmas E. Murley Region I, Regional Administrator U. S. Nuclear Regulatory 0rnussion 631 Park Avenue King of Prussia, PA. 19406
Dear Dr. Murley:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Operational Readiness Evaluation (Inspection No. 50-289/84-05)
On April 2,1984, Mr. Robert Keller, 01ief Section 1D, DPRP, Region I, conducted an exit brief for an Operational Readiness Evaluation which was conducted at TM1-1 on February 8 & 9, 1984. The result of the evaluation was that licensx1 personnel at TMI-l were found to be knowledgeable and well trained.
This evaluation consisted of twenty-six (26) individual two hour interviews by NRC staff of Licensed Operators or Senior Operators. During the exit brief, individual operator weaknesses in thirteen (13) topics were addressed.
The NRC indicated that these weaknesses were due to inexperience with an operating facility.
In order to upgrade the operational knowledge of the licensed operators at TMI-l these thirteen (13) topics will be addressed in the requalification training program, a three day simulator program, or during on shift training.
Additionally, a restart qualification card (Attachment I) for all crews has been instituted that will be used during Hot Functional Testing (HET), Zero Physics Testing (ZPT) and the Power Escalation Test (PET) program. The PET program contains time periods at 40% and 75% power levels designed to allow all crews an opportunity to participate in hands on performance of items identified on the restart qualification card.
Attadiment 2 specifically addressed training on the thirteen (13) topics and includes information on the simulator training that is presently being conducted at the Babcock and Wilcnx Simulator.
S' f,
[
N 8508120643 850703 PDR FOIA H
. Hukil,
REBER85-419 PDR Director, TMI-l N
HDH/BPI/bHR/OiS/mle 3
AtgNObfba$orporation is a subsidiary of the General Public Utilities Corporation cc: CARIRS_TbIE
[,
T
,i f
Eli] NUCLEAR THREE MILE ISLAND NUCLEAR GENERATING STATION 4
/*
G[>c C
UNIT 1 RESTART QU ALIFIC ATION C ARD
e:
PRIMARY SR0/CR0 Date A0 Date A0 Date 9;
CRD - Transfer rods to N/A N/A aux.-power supply.
(I)
N/A N/A N/A N/A N/A N/A l Comments:
I I
I I
I l
CRD - Walk thru aropped N/A N/A rod recovery & location of N/A-N/A S2 bypass,. safety, rod out N/A N/A bypass, ollution permit N/A N/A bypass.,-(C) l Comments:
l l
l l
I I
CRD - Adjust relative N/A
'N/A rod position in C.R.
(I)
N/A N/A N/A N/A N/A N/A l Comments:
l l
I I
l 1 0576K
- ~
PRIMARY v
SRO/CR0 Date A0 Date A0 Date N/A N/A h,
RCPs Verif prerequisites N/A N/A for pump start (seal flow, IC flow etc.) & set.up pump N/A N/A N/A N/A for startup including oil system = operation.
Discuss l Comments:
I starting interlocks.
(I) i 1
1 I
l N/A N/A RCPs - Operate RC pumps N/A N/A
. in parallel.with the OH' removal system.
(C)
N/A N/A N/A N/A l Comments:
I I
I I
I l
N/A N/A
. Int. Closed Cooling -
Shift int. closeo pump.
(C)
N/A N/A N/A N/A N/A N/A l Comments:
1 I
I I
i l
0576K m
PRIMARY SR0/CRO Date A0 Date A0 Date P.
Int. Closed Cooling - Verify proper JP across CRDM filters: discuss limits.
.(C) l Comments:
l~
l l
l I
I Int. Closed Cooling - Walk N/A thru or perform CRD filter N/A isolation &-draining.
N/A (Do this in groups of.
N/A 2 at a time)
N/A l Comments:
1 N/A I
I N/A l
l I
N/A N/A Makeup & Purif. - Establish N/A N/A
.. normal makeup &_ letdown -
review-limits on number of N/A N/A filters & demins. vs.
N/A N/A letoown flow.
(C) l Comments:
l l
l l
l l
i
' 0576K i-
PRIMARY SRO/CR0 Date A0 Date A0 Date N/A N/A 10.
Makeup & Purif. - Shift N/A N/A makeup pumps including trans-N/A N/A fer of B pump breakers to alt. bus.
(I - if possible)
N/A N/A l Comments:
l l
l l
I l
Ll.
Makeup & Purif. - Verify N/A proper seal injection &
N/A return filter AP.
Discuss N/A how to isolate & change N/A supply & return filters.
N/A l Comments:
s l
Review limits.
(I)
N/A l
l N/A l
l l
12.
Makeup & Purif. - Establish oaisy chain letoown & makeup paths thru the bleeo tanks to clean the RCS system.
(C) l Comments:
l l
l l
l l 0576K d
PRIMARY SRO/CR0 Date A0 Date A0 Date la, Makeup & Purif. - Regulate N/A RCP seal leakoff adjustment N/A at PI-39.
(I)
N/A N/A N/A l Comments:
1 N/A l
l N/A I
I I
N/A N/A Makeup & Purif. - Make an addition to the makeup tank.
N/A N/A Include a calculation'to N/A N/A deborate by 2 ppm.
Use N/A N/A
. batch controller & discuss l Comments:
I interlocks.- (I) l I
I l
l N/A N/A
- i. Makeup & Purif. - Regulate N/A N/A
. makeup tank overoressure.
Discuss reason for max.
N/A N/A makeup tank pressure.
(I)
N/A N/A l Comments:
I I
I I
l 1
0576K -. -.
PRIMARY SRO/CR0 Date A0 Date A0 Date t6.
Pressurizer - Control pzr.
N/A N/A spray & heaters. Discuss N/A N/A input signal source.
(C)
N/A N/A N/A Ni;;*
l Comments:
l l
1 1
I i
1 Pressurizer - Discuss new N/A N/A T.S. on PORV operability.
N/A N/A (C)
N/A N/A N/A N/A
'l Comments:
1 1
I l
l l
3.
Pressurizer /RCS - Control N/A N/A N/A N/A RCS press. in bank to allow simultaneous operation of N/A N/A RCP's & DH removal sys.
(C)
N/A N/A l Comments:
l l
l l
1 1
C576x PRIMARY SRO/CR0 Date A0 Date A0 Date 19.
RCS - Plot 1/m curve during N/A N/A rod withdrawal & deboration.
N/A N/A (C)
N/A N/A N/A N/A l Comments:
l l
l l
l l
).
Pressurizer - Discuss how N/A N/A to shift signal inputs to N/A N/A pressurizer controls & ICS N/A N/A inputs.
(I)
N/A N/A l Comments:
l l
l l
l l
L.
Pressurizer - Transfer group 8 or 9 heater to P or S 480v bus.
(C) l Comments:
l l
1 l
1 1 C576K
F PRIMARY SRO/CR0 Date A0 Date A0 Date;
.~2.
Participate in plant heatup & cooldown as specified by operating proceoures.
(C) l Coments:
l l
l l
l l
C576K <
r SECONDARY SRO/CR0 Date A0 Date A0 Date 5
Startup/ Shutdown C.W. Sys.
(C) l Comments:
1 I
l i
I l
Place amertap in service and
. secure.
(C) l Comments:
I I
I I
I I
Place C.W. C1 & Acid Sys.
N/A in service & secure.
(C)
N/A F
N/A N/A N/A l Comments:
I N/A I
l N/A l
l 1 0576K Y
SECONDARY SRO/CR0 Date A0 Date A0 Date Establish condensate sys. on 4
recirc.
Shift one condensate pump.
(No flow thru heaters unless authorized.)
(C) l Comments:
I l
l 1
I I
Fire Aux. boilers & perform N/A valve lineup to support N/A vacuum operation (to seals).
N/A (C)
N/A N/A l Comments:
1 N/A l
l N/A l
l l
Place condensate chemical N/A feeo in service & secure.
N/A l
(C)
N/A N/A N/A I Comments:
l N/A l
l N/A l
l 1 0576K
SECONDARY SRO/CR0 Date A0 Date A0 Date Place main turbine on i.
(C)
I comments:
1 I
I I
I l
Place main feed pumps on turning gear.
(C) l Comments:
I I
l l
l l
Demonstrate how to regulate main turbine exhaust hood spray.
(I) 6 l Comments:
I I
I I
I l
I 0576K l
i SECONDARY SRO/CR0 Date A0 Date A0 Date Shift to standby main & aux.
vacuum pumps.
(C)
E l Comments:
E l
l l
Demonstrate how to makeup N/A to the condensate head tank.
N/A (C)
N/A N/A N/A l Comments:
N/A l
g N/A l
pj L
i I
).
Run one feed pump turbine on aux. steam (uncoupled or coupled - as directed).
(C)
"]
L I Comments:
il l
i
~
f'].
I i
_ 0576K
E SEC0tOARY SRO/CR0 Da'.e A0 Date A0 Date so.
Run one powcex vessel thru N/A a regen. cycle (with or N/A without resin - as directed).
N/A (C)
N/A N/A l Comments:
I 1
N/A I
I N/A l
l n
I'.
Establish F.W. heating &
n flow thru heaters (if W
authorized).
(C)
I Comments:
1 1
J l
I I
m l
u I
l l,
3.
Run one cond booster pump N/A N/A f
(
or recirc. (if authorizec).
N/A N/A (C)
N/A N/A N/A N/A l Comments:
I l
l l
l l
1
-l
- i 1 0576K
=
l y
SECONDARY SRO/CR0
~ Date AO Date A0 Date l
N/A N/A Operate the powdex system N/A N/A bypass valve from the control N/A N/A room.
Verify holding pump N/A N/A operation on a powdex vessel.
l Comments:
(c)
I I
I l
l k
a
- p. m k
P
' S, A
l l
3 l
I]
- ]
- 1 0576K.
s POWER EXCALATION/ PHYSICS TESTING EVOLUTIONS
~
SRO/CR0 Date A0 Date A0 Date 3
N/A N/A Participato 3,,,,i coserve
~
N/A N/A (C) natural ci l ' ' ' l"' I '.
N/A N/A N/A N/A l Comments:
I I
l l
l 1
a main Startup 4 pstil1.l running feed pump wIeI,.
pump.
(1 if invisible) a l Comments:
I f
I l
1 1
I vessel in N/A r
Place a pi witi s i
)
< o.it the vessel N/A service.
1 N/A
Pi i.it e the h
removeo.
t N/A backwash ti * '6' ry system.
l]}
l N/A 1 Comments:
(1) 1 1
l
"'a N/A l
l l1 1
0576K POWER EXCALATION/ PHYSICS TESTING EVOLUTIONS SRO/CR0 Date A0 Date A0 Date N/A N/A tlalk thru or complete a N/A N/A plant precritical checkoff N/A N/A per 1102-2.
(C) l N/A N/A l Comments:
l l
m l
l
.a l
w Complete a turbine plant u
startup.
This incluces n
d bringing Rx power up, I
putting turbine & generator W
on line & increasing power l Comments:
I to approximately 40%.
(C) l I
l l
l N/A N/A Complete main turbine &
N/A N/A feed pump valve testing.
N/A N/A (C) l N/A N/A r1 LJ I Comments:
1 1
h l
I I
q 1
fn l
!:1 0576K i
w SURVEILLANCES SRO/CR0 -
Date A0 Date A0 Datt t.
1303-4.11 N/A N/A HPX/LPI logic & analog N/A N/A channels.
(C)
N/A N/A 3
N/A N/A l Comments:
I I
l 1
l l
1403-4.14 N/A N/A Rn. 810g. 30 psig analog N/A channels.
(C)
N/A N/A l Comments:
T l
I l
I u
l l
l.
1303-4.19 N/A N/A HPI/LPI analog channels.
N/A N/A (C)
N/A N/A
~
N/A N/A l Comments:
l l
l
~
l I 0576K
SURVEILLANCES SRO/CR0 Date A0 Date A0 Date
~
1303-5.1 N/A N/A Rx. bldg. cooling & isolation N/A N/A logic channel & component N/A N/A test.
(C)
N/A N/A l Comments:
I l
I I
l l
'1303-5.2 N/A N/A
-Loading sequence & component N/A N/A test.
(C)
N/A N/A N/A N/A I Comments:
I 1
I I
I I
1303-11.8 N/A N/A HPI injection.
(C)
N/A N/A N/A N/A N/A N/A l Comments:
l I
I I
l
.~ 0576K
~
SURVEILLANCES n
1 l
SRO/CR0 Date A0 Date A0 Date I.
1303-11.9 N/A N/A Rn. Bldg. emergency cooling.
N/A N/A (C)
N/A N/A N/A N/A l Comments:
1 i
l I
I I
1303-11.10 N/A N/A ESAS sequence & power N/A N/A 1
~
transfer.
(C)
N/A N/A N/A N/A l Comments:
1 l
l I
1303-11.54 N/A N/A LPI injection.
(C)
N/A N/A N/A N/A N/A N/A l Comments:
I 1
i l
~l 1 0576K bi
SURVEILLANCES SRO/CR0 Date A0 Date A0 Date
),
1302-1.1 N/A N/A Po~::er range calibration N/A N/A CR0 portion only.
N/A N/A (C)
N/A N/A I Comments:
l I
l l
l l
1303-4.1 N/A N/A Rx protection sys.
(C)
N/A N/A N/A N/A N/A N/A l Comments:
l l
l l
\\
l e.
1301-1 (Shift & Dailys)
N/A N/A Perform in colo shu'. sown.
N/A N/A s
(I)
N/A N/A N/A N/A I Comments:
l l
l l
l c- 0576K a
I SURVEILLANCES SRO/CR0 Date A0 Date A0 Date 3.
1301-1 (Shif t & Dailys)
N/A N/A Perform in hot shutdown.
N/A N/A (I)
N/A N/A N/A N/A l Comments:
I I
l 1
l l
1301-1 (Shift & Dailys)
N/A N/A 2
Perform at 40% power.
N/A N/A (I)
N/A N/A N/A N/A l Comments:
l l
1 l
l l
4 0576K 1
d
a.
1 ()
ATTImeNr 2 In Operational Readiness Evaluation (Inspection No. 50-289/84-05) wcs condacted, at TMI-l on February 8 & 9, 1984. Based on the results of this evaluation, individual operator weaknesses ware identified in thirteen (13) topics which were indicative of inexperien with an cperating facility.
!~
Tnese topics are being addressed during the current requalification training cycle. A su:ntary of the training on these topics is detailed in the following paragraphs.
The following topics have been incorporated into classrocm training for the
-licensed operator requalification program. This classroom training ccnnenced 34 on Igril 9,1984, and will be cumpleted the week of May 14, 1984.
INSPEC. ITEM SUBJECT No. 2 Transient Analysis for Ioss of Main Feedwater and a Deboration (Itderator Dilution) Accident.
No. 4 Calculation of the boron change required for a power change.
No. 5 Calculation of Heat Balance without a CaTputer.
No. 8 Fanipulation of the Makeup and Purification System to reposition Control Pods.
I No. 9-Basis of Limit Settings Incmporated into the Integrated Control System.
i-No. 11 Iogic and Control of Control Rod Drive Circuit Breakers.
No. 12 Construction and Operation of an RCP Seal Package.
No. 13 Predicting Indication of NIs during a reactor startup.-
In addition to the training being conducted as described above, classroan
- instruction will be conducted on Reactivity Coefficient effects while at cower -
during Licensed Operator Requalificaticn Training Cfcle 84-2, (Insp. Item No.1). This -
trai-ing will be conducted cnmencing the week of I'ay 28 thru July 2,1984.
Inocrporation of this training into the present regualification schedule cr;uld not be accmplished due to higher priority training. All licensed operators have been directed to review the applicable. sections of the TMI Training l
. reference n:aterial.
l (In Training on Predicting Indication of NIs during a Paactor Startup, is being l.
conducted on the Basic Principles Simulator at "MI.
Licensed Operator Requalificaticn Training is presently being conducted at
.'the Babcock and WilcDx Simulator inLynchburg, VA.
This training is being i
conducted to e.phasize both the use of the ATCG procedures and norral cp2 rations.
Tne topics ' listed balow have been incorporated into this training:
4 e
m
..T l
l INSP. ITEM SUBJECT 1
No. 3 Plant Manuevering when placed in a situation not covered by procedures.
No. 6 Methods of Cbntrolling the plant cooldcwn rate following reactor trips.
No. 7 Methods of Controlling Xenon oscillations.
Training being conducted on the A'IOG procedures emphasizes the operator response during abnormal transients. The philosophy of A'IOG and the basis of the procedures developed include operator's actions on item nine above.
Due to the constraints of the requalification scheduling, formal classrocm training is not being conducted on Control Functions of the Electrohydraulic i
Control System. (Insp. Item. No.10). All licensed operators are required to review the EHC section of the TMI-l Operations Plant Manual. This material is to be included in requalification weekly quizzes during cycle 84-2.
t i
i i
i i
i
Training Content Record Lesson Course Title Number Lesson Plan Title Number Rev CALCULATIONS FOR BORON CHANGES Objectives Following instruction, the student should be able to:
1.
Using Procedure 1103-4, perform hand calculations involving additions of fluids to the RCS that; a.
Dilute the boron concentration (rods move in, in auto).
b.
increase the boron concentration (rods move out in auto).
Responsibility l
Signature l
Title l
Data
,f Origination l
[ f NgIg l Mm ff % [4,<A % l 9[j,/pg i
2f
/bi:
bdIw b$
l Review / Concurrence l
h l
b O
I_
e I
I i
'ffl&;{./r. f
{
pfp ll Q q lLj'l l @)
8 Okiectives
/
- I
'[/
Q j
[j '
(/
j'( (
p;,,g
Triining CrntIn ; 3:: d Lesson Course Teve Nummer t.u nm nr!MNIPULATION OF iMKEUP SYSTEM TO REPOS:
.I CONTROL RODS objectives Given the necessary procedures for reference, each student would be able to explain the makeup system manipulations required to borate, deborate or dilute the RCS to achieve a predetermined rod position.
l Responsibility l
Signature l
Title l
Date i
k Origination lhjp&
hphf)& Mj.; lll</l&
l 3
L' Q
l l//
Review / Concurrence l
[
l A
I I
I h
Ob5**'I"**
f h M / ${l] h k/V hVfYh l
Y g#* * *'
Final l
N 1 n' 3
//
/
'/
'l # '
Training Content Record Lesson Course Title Numcer Lesson Pfen Title Number Rev HEAT BALANCE CALCULATIONS Objectives Following instruction, the student should be able to:
1.
Perform a hand calculation " Heat Balance" for the core thermal power in accordance with procedure 1103-16.
Responsibility l
Signature l
Title l
Date f
Origination l h hD41. -
, l gp. //n fa Tr,
l y/g/gy
?
415M GsA DsL ~
Iv/i/N y
Review / Concurrence C 0 C
(
[
l/'
l
~;
e I
i oui ctiv =
YEis&M n'>h,Ata%%
\\v/A/et i
?
[.
Final l
D l
9 U /
f l
l
-l Trainino Content Record 1
i.nson coon. re.
%n -
T h s,i jbd
/l<j r; '.
' e-.CJ CF1.A [fDWA!
'! E S -
L
'.ns:-=i r.
, ;t
...m ee r H n..
ama: n.,-.a n L.........
S s
...n l
l Obiectives Following instruction, tne stucent should be able to:
1.
Perform a hand calculation " Heat Balance" for the core thennal power in accordance with precedure 1103-16.
~
~.
I
~-
Responsibility Signature
~itle Cate
- ' Origination
,*n d '"
,. m u-a f
- I
/.
E! Review / Concurrence 5
i I
,y l
5 l Objectives jh/(k'(,/&k
{lp,,%'b;.ylj*s),.
id/j /@f b
f, l Final l
O l
N U '
I A00018 v.
s 1
Training Content Record L
n cou, rio.
Numeer
***"*f13RSTRUCTION AND OPERATION OF RCP SEAL PACKAGE r.' : :. :
j At the conclusion of, this lesson, each student should be able to:
A.
Given a simplified drawing of the reactor coolant pump seal package, label the components indicated, show seal water flowpaths, and indicate approximate flow rates during nomal operation.
B.
State the purpose of the No. I seal bypass valve, and list or identify the conditions under which the valve may or may not be opened.
C.
Identify the correct range of back pressure to be maintained on the No. I seal return line and describe how, where, and why it is maintained.
(As read on MU-PI39).
D.
State the purpose of the standpipe and identify noma 1, Icw alam, and high alam levels.
E.
Describe reactor coolant pump seal flow during a loss of nomal seal injection, and explain how given seal package monitored parameters will change during this condition.
(i.e., temperatures, flows, D/P 's ).
F.
State the temperatures of the No.1 seal outlet and radial bearing which reesire ptarp shutdown.
G.
State at what RCS pressure and temperature seal injection is reouired to the reactor coolant pumps.
1 I
nesponsibility l
A Signature l
Title
,l Date j
M M*"
_h
[
d.
9
- 24 M
i
' M f L k - ! ka.,_ E, W, D W h Y
\\
j neview/ concurrence C'
G *l
~
.f I
j 2
i b
I 06iectivee YO??(C,GL U Q...i 5,.n h i //,C/f-t' ?
$ N "'
MGW4x2ou?
- A&L,#2rr i V//c///
i maai y
u
TRAINING CONTENT RECORD Lasson course ilt4e numcer l
jbM2N.
J.
/'
A/
g,g, c &
Lesson Plan Title Numcar nev SPT INTRODUCTION /0RIENTATION FOR LICENSED OPERATORS OBJECTIVES Following instruct 1on, une stucent snould be anle to:
SPT INTRODUCTION / ORIENTATION FOR LICENSED OPERATORS REFERENCE FILE DJLPW1 1.AFTER INSTRUCTION AND DEMONSTRATION EACH PARTICIPANT SHALL BE ABLE TO IDENTIFY THE BASIC COMPONENTS OF THE SPT AS:
MIMIC AND CONTROL PANElePLANT CONTROL SYSTEM, TRAINEE GRAPHICS SYSTEM INTERFACEe AND INSTRUCTOR CONSOLE.
1.0 GENERAL DESCRIPTION OF THE DRILL I
333333333333333333333333333333333333332 LICENSED OPERATOR INTRODUCTION: STARTUP TO 15% REACTOR POWER.
s I
A.
USING SPT OP-3 INCREASE REACTOR 80WER FROM 1E-S AMPS TO 15%
RATED POWER AT 10% PER HOUR WITHOUT CAUSING A REACTOR TRI*.
B.
DURING REACTOR STARTUP TO 15% RATED POWER CONTROL PRESSURIZER LEVEL SETWEEN THE LIMITS OF OP-3 FIGURE 1 (ALLOWABLE PRESSURIIER LEVEL LIMITS FOR REACTOR POWER INCREASE FROM 0-15%).
t C.
DEMONSTRATE AND CORRECTLY CAS DEFINED IN THE OPERATOR TRAINING l
MANUAL) EXPLAIN FUEL AND TEMPERATURE REACTIVITY EFFECTS ON REACTOR CORE SUR AND KEFF WHEN REACTOR PodER IS RAISED TO THE POINT OF INITIAL SENSIBLE FISSION HEAT PRODUCTION.
D.
DEMONSTRATE AND CORRECTLY EXPLAIN WHY CRITICAL ROD POSITION CHANGES AS REACTQR POWER IS INCREASED IN THE POWER RANGE.
E.
TREND VALUES OF RCS TAVE, THOTeTCOLD AND JAIN STEAM TEPoERATURE, AND CORRECTLY EXPLAIN THE EFFECTS DUE TO OTSG LEVEL CONTROL i
ON REACTOR STARTUP TO 15% RATED POWER.
E F.
ROLLe SYNCHPONIZEs AND INITIALLY LOAD THE MAIN TURBINE GENERATOR EE UNTIL ALL TURBINE BYPASS VALVES ARE CLOSED (IN AUTOMATIC) WHILE O
MAINTAINING TURBINE HEADER PRESSURE AT 885 PLUS/MINUS 50 PSIG.
5 RESPONSIBILITY l
SIGNATURE TITLE gA7g ORIGINATICH l Ac4 j M -
lS,,A g 4 gg-yjgjgg h
REVIEW /
U I
b E M iw2 1 W4/f#
CCNC' RRENCE 7
~
J
{
U l
?N Ss4cb<&&
/db//141 I Y-t'$~d9 m ygy,t ceaEC :vEs v v t/. UL,ddu L.Jcv u,.
/t m ga FINAL I
U
[/
l l'
, *. o" Training Content Record Lamaan cowam v<m w
" M GIC AND CONTROL OF CRD BREAKERS Ohi.ceve Following instruction, the student should be able to:
1.
Given a combination of breaker and/or electronic trips, state whether; a.
The reactor is fully tripped (If not fully tripped), what the control rods's configuration in the b.
core is (i.e., which groups inserted) 2.
State the configuration of the rods and UV coil circuits on a loss of:
a.
one vital busses b.
all vital busses 3
State that av two out of four RPS channel trips result in full reactor trip (assuming only single failure on CRD breaker / elect. trip systems).
4 How the following operate to open the breakers that use them; a.
Undervoltage coils j
b.
Shunt trip coils 5
How the"E" ("F") relys operate to trip the reg groups.
6 Why APSR's do not drop on reactor trip.
1
\\
w uw sw m.
m I
orw~e-(LL D J W lW w~ Ta rc.;, \\ wh,/sv dB 6 A.ah
% A cst n '\\4-a-n v
i o
i 5
i i
5 d&v,
S dc6 Cob /b lY-d-fv obi = * =
^*'**
l g
n,,.
l v
i v
i 1
l TRAINING CONTENT RECORO Lesson Gourse iltke i
numcer Lesson Plan Title Numoer Kev.
3 A S\\ S o f: L\\m (T SerTW G hea.0ceATEO Iurc> I.C.5,.
d.2,o/.cS5-d OBJECTIVES Following instruction, the student should be able to:
j I. WMW M WL5 h 'n4E FcLLewicG LimgTs As.sectAm wtm Tae wresexso cmmo e se l
o.. MWH W O Llewtf
- b. LOW LCAO Ltm t T
- c. Leap a sm e,e me
- d. Snu Ltm t1-f.
Lew LSJO L4m 87 f. Mys A LNdL u m f
$. cress umiTs.
- h. EeMBL DEMAO 4%H/Lew um tm 4
i i
C s"2 E
RESPONSIBILITY SIGNATURE TITLE DATE ORIGINATION d/b/pd S,gg 6g h 7pm-/
y-f ft/
~
- c. w l
- i; REVIEW /
O y
~
7 CONCURRENCE 6.
,Q APPROVE OBJECTIVES 8h
/b4/ 4 h # 14 4
<//6/&
t t
FINAL
_ _ _ _ _, ~. _ _ _.. _ _,. _.
Training Content Record
/ Lasson Cowse True hwneer y
ltya PS-
& /4-
/f. 2.c f * -
~
t on m.nmn.
Nwneer Asw.
MODERATOR DILLITION AND LOSS OF FEEDWATER 06,ectives A.
At the completion of the training, the trainees should be able to:
1.
Identify the correct present plant response to a LOFW or a Moderator Dilution.
2.
Identify the correct final plant conditions for the LOFW and Moderator.
Dilution accident.
3.
State wny the FSAR cannot. be used to describe transients based on present plant descriptions.
4.
Indicate the effect of changing an asstaned value of a parameter on the severity of the accident (Dilution or LOFW).
no neinuity I
s4enetw.
l Tits.
l osta l
?
ors inetnen l y& l lJM lTecnmen. Aue 36.
l ~'// 7/ ? 4 e
?
W M &o. 8 LCwd OnL3tt-/I H7-Pf h
it.wiew/ Concur C
l N
l 5
l l
l 3
t 066ectiv.e W&s0.&
kffff% /l Lap l ({-ff-PV l
h U
I I
Ra*8 l
1.0 AOndtRAM
Trzining C:nt:nt Rrtrd Lesson course Title Number Lenon Plan Tide Number Rev Reactivity Coefficients 11.2.01.124 0
Objectives At the conclusion of this lesson the student will be able to:
A.
Describe each of the major reactivity coefficients, their mechanisms for reactivity feedback, approximate values, and the varying effects of temperature changes and Core Age.
B.
List the factors most affected by changes in the moderator-to-fuel ratio, describing the direction and magnitude of these effects during a plant heatup or cooldown.
C.
Define the terms:
Dyer Moderated Under Moderated and Power Defect.
D.
Explain in detail how the presence of boren in the moderator makes the reactor core appear to be over moderated.
E.
Explain how and why the Power Defect changes over the life of the core.
F.
Explain how and why fuel tenperature varies with fuel burnup - even with a constant thermal power level.
G.
Define point of Initial Sensible Heat Production, list its contributing factors, and explain why its value cai
~
change.
H.
Describe the response of the Excore Nuclear Detectors to core void formation during accident or transient conditions.
1.
Describe how a Reactor Coolant pH change can induce a reactivity change.
p Signature l,
Responsibliity Title l
Date 8
kl'c/M's WJW76. b[tL s~/7/7+
i NVe% M
% % w sn/
d&tt l
Review / Concurrence C
h l'
(/
l
~
m p
61** *'"
IM M de.ulm7E m % ks-s4y 6
4,,,ov.i G
Finel l
l0
(_)
A0001840
Trcining C nt:nt R:cird
- Lessdn Course Title Number Leeson Plan Titte Number Rev.
Methods of Controlling Xenon Oscillations Objectives At the completion of this lecture, each student should be able to explain how the operator can recognize and control axial or radial xenon oscillations.
l Responsibility l
Signature f
Ori:! nation lfQkg,,f, l
Title l
Date j
& g & Q,7pyz.;
J-ff
.f.
('
V l
C7 l
Review / Concurrence l
l 1
l l
i Objectives
[q
!M hy rhp l y-f.#/
2 Apprzval
}
Final l
lY U
l
Trcining Cont:nt R:ccrd i
Lesson Course Title Number Lesson Plan Title Number itev.
Methods of Controlling Plant Cooldown following a Reactor Trip Objectives At the completion of this simulator session each student should be able to list the methods of plant cooldown following a reactor trip in order of prioritization (preference).
Responsibility l
Signature l
Title l
Data f
Origination l(([J
,h,d, dj, kny&f/ l V-)-fy
~
(~
Q l
C/
l Revi:w/ Concurrence l
l l
3 l
l l
I Approval
[i, Final l
l[
8 l
l
Training C:nt:nt Record L.sson Course T,ve Number t on pi.n Tm PLANT STARTUP OPERATING PROCEDURE Numbw Rh Objectives After reviewing Procedures 1102-2 and 1550-02, each student should be able to:
1.
Explain the basis for each limitation and precaution listed in each Procedure.
2.
Given a step in either Procedure, identify approximate power level step is performed; and for verification steps, identify how and where the verificaion is made.
Responsibility l
Signature l
Title l
Date R*
Origination l g,j g,_ /.
l g g f,-
@gf4 k.Y k k h o /5 9% /N /'I
- l0?W h
j Review / Concurrence h
l N
l s
l l
Approval I 4, Am/
i/wFGtZA& I 2A 4-i 5
riasi i
g A00o1840
Training Content Record wson cm mu ww OPERATING CURVES Objectives At the completion of this training, each student should be able to:
1.
Explain the basis for and ideritify areas of pemissible, restricted and/or
~
prohibited operation on each of the following operating curves:
Rod Position Limits (Reg & APSR)
Power Imbalance Envelope LOCA Limited Maximum Allowable LHR 1210-10 Figure 1 1102-1 Figure 1 and 1A 2.
For the operating curves listed above, state the action (s) required when operation occurs outside the pemissible area.
3.
Identify specific operating circumstances which allcw intentional operation outside pemissible areas on the curves listeo in Objective #1.
Meeponsibility l
Signature l
Title l
Date f
'Y"*
Y.kkb
$ s a 0. C e ~Cterq Nfil./ l3./W.8W h
Yd$
lAWrf N./ M. s v
'o' Review / Concurrence
~
l l
s l
I e
Approval U-lW O
S" 5
Sa*'
% w had dg'qAbp4-w-/y i
Tr;ining Cent:nt R :ord Leeson Course Title Number Lesson Plan Title Number Rev.
REVIEW 0F JANUARY / FEBRUARY 1984 RIMlli ATnR ATnG EXPERIENCE Objectives At the end of this lesson, the student should be able to state the following:
A.
Major training issues that were addressed during previous ATOG training session (s).
B.
Philosophy of ATOG in emphasizing priorities and operator interface with the procedures.
C.
Emphasis of ATOG on the crew concept and comand authority.
Responsibility Signature Title Date k
Origination E
pq
[ 09 7 p f.(
3., j q.,p 5
(
U c./
.:.j Review / Concurrence O
s O
O-Approval M[Q J
7 g
g,/ s/-g,/
d y
Final I
d Aooots4o
MIRE ROSS INSTRUCTORS NtELEAR TRAINING CENTtR FRANK RACINEO HARVEY DALICHERTY CPU NUCLEAR HENRY SHIPMAN MARRY llEltNEIER 3 DAY REQUAl.!FICATION DENNY ROLTZ FRANK ORER WEER I 0F I DARRYL WILT YtRRY MCRELLIPS "I
CHARCE #AT40i976 Class Room Schodule Contr&Titso"r'iSchedule
= nnE Day Reference No.
Day /Date Time Subject Tinw f,efe[,ence g,,,,,c,,,
oper ggen
,gy 1600 Pl. ANT STARTUP 3 BCP's SAFETIES OUT TO 4T l
TO ATOG PRtEEDURE REVIEW HD FIANT STARTUP 3 BCP's 152 TO 40T 1930 ATOC DRILLS 74,
CRD OPERATIONS AT FULL POWER t
RUD INDEI CURVES (2 HRS.)
BRIAN DELANO TUFSDAY ft)
P-T Ct!RVES (HEATUP & COOLDEMN llMITS) y HH F
E P
7 3/27/84 1930 FUEL PIN IN CtetPRESSION 24(W)
ATnC WINDOW (1.5 HRS.)
MANUAL ICS OFFRATIONS (30 MIN.)
)
I
.)
1600 W!INESDAY 3
TO PROCFDURE REvitM (2.5 HRS.)
2000 PLANT OPERATIONS (2 HRS.)
1910 S
OPERATIONAL EVALUATION (2 HRS.)
l I
e i
j l
t 4
Babcock & Wilcox Nuclear Training Center i
Customer Lynchburg. Virginie