ML20043E396
| ML20043E396 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/01/1990 |
| From: | Burdick T, Lennartz J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20043E394 | List: |
| References | |
| 50-282-OL-90-01, 50-282-OL-90-1, NUDOCS 9006120387 | |
| Download: ML20043E396 (10) | |
Text
i.
.:e
,[
g _.
.: e
!'. f U.S. NUCLEAR-REGULATORYCOMMISSION REG 10NLill 1
~ReportNoL50-282/0L-90-01(DRS)'
Docket Nos. 50-282; 50-306-Licenses No. DPR-42; DPR-60 Licensee:- Northern States Power m.
414 Nicollet Mall
~
Minneapolis, MN 55401 Facility Name:
Prairie Islahd Nuclear Plant a
- Examination Administered At:- Prairie Island'
?
Examination Conducted:.May 1-7, 1990 a
1-Chief Examiner: 91 1 M, fofl[f D.
-J. Lennartz g_
Date l
Approved By:.ib(Md b/iho T. Burdick, Chief Date-1 10perator licensing, Section 2 4
Examination Summary-1 i
Examination administered on'May 1-7, 1990 (Report No. 50-282/0L-90-01(DRS)).
Written and operating examinations were administered to five Senior Reactor j
Operator candidates.and ten Reactor Operator candidates.
Results:. Five: Senior Reactor operator candidates-and:nine Reactor Operator i
candidates passed both the written and operating examinations. One Reactor 0perator candidate _ passed the written examination but failed:the operating j
examination.
i
_]
i i
9006120387 900601 PDR ADOCK 05000282 V
~
1 1
d M',
p REPORT-DETAILS-
=
u
.1.
Examiners
- J. Lennartz, NRC J. Walker, NRC A.;Lopez, PNL L. Sherfey, PNL "O
- Chief Examiner
- ?.-
Examiner Observations c
a..
Examination Development The reference material that the licensee-sent to the NRC for examination preparation was all properly: bound and labeled, and for the most part the NRC examiners were able to extract the needed information.
However, an index for System Lesson Plans and for Annunciator Response Procedures would be very helpful, and the licensee should include these items with the reference material on future examinations.
The pre-examination review conducted by the licensee on the written 4
examinations was very productive. The licensee's input to the-
-examinations ensured that the terminology used on the examination was' plant specific thus avoiding confusion-on the part of the i
candidates during the examination.
In addition, the review process ensured that the examinations were technically correct and appropriate for each license type _ as specified by the licensee's job description._
.During the development-process a few examples of examination reference r
L material deficiencies were identified. The licensee should ensure that System Descriptions and Operating Procedu es correctly reflect the equipment in the plant to prevent negative training on and incorrect operations of systems because of invalid' references.
Examples of these problems.are:
System Description B-10. "Incore Instrumentation System",
describes the operation of the incore thermocouple control panel.
However,Ldue to system modifications, the incore thermocouple control panel no longer exists.
Operating Procedure C34, " Station Air System", Table 1, indicates that 11, 12, 21'and 22 Steam Generator Feedwater Regulating-
' Valve Bypass Valves are supplied by air accumulators, when in-D fact there are no air accumulators associated with these valves.
2 W
wt
m 4.
[g s.-
e 3,
b.
Oyerating Examination Administration
~
' DuringLthe administration of the. operating examinations, the examiners observed both deficiencies and strengths on the part of; the Senior Reactor Operator and Reactor Operator candidates.
.The following deficiencies in the candidates' performance'were observed in the majority of the candidates that were examined in each particular knowledge or ability:
The candidates ability to determine the subsequent discharge path that a waste gas release would take over the plant site after obtaining wind direction information from the Meteorological Information Data Acquisition System (MIDAS) computer was poor, The candidates ability to locate indications (status lights) that would have to be verified if a high radiation alarm-occurred on the Auxiliary Building Vent Gas Monitor A (2-R-37)-
while conducting a waste gas release was-poor, The following strengths in the candidates' performance were c
observed in the majority of the candidates that were examined'in each particular knowledge or ability:
The candidates' ability to correctly implement required Annunciator Response, Abnormal, and Emergency Procedures was good.
3 The " team work" concept demonstrated by the candidates during i
the simulator scenario examinations.was very good.
The candidates communications with plant management, maintenance personnel and auxiliary operators regarding plant
- status were generally very good.
The candidates' positive-control of removing instrumentation l
from service which required IC-personnel to place associated 1
bistables in the " tripped" condition was very good.
. Additionally,-the examiners noted that plant cleanliness and general-
~j housekeeping were very good for the areas which were entered-during i
the plant walkthrough examinations.
1
- c.
Written Examination Administration 3
The post-exam review identified the following deficiencies _in the candidates' knowledge as evidenced by: the majority of the-candidates 3
a
l
(,
LMi f:
U ifailing to provide the correct response for each part'icular-knowledge area examined. This information is being provided as input to the licensee System Approach to Training (SAT) process.
No; response is_ required.
The minimum Control Room manning requirements per SWl-0-2, n
" Shift Organization; Operation and Turnover", during a Reactor Trip on Unit 1 with Unit 2 at full power (SR0 examination question 004).
l The prerequisites for starting a Reactor Coolant Pump (in j
a'ccordance with procedure C-3, " Reactor Coolant Pump" SR0 examinationquestloo022;R0 examination-question 006).
The annunciators that would be associated with a dropped 4
control rod event as opposed to a misaligned control rod or u
failedpowerrangenuclearinstrumentevent(SR0 examination j
question 065).
j The method which should be used to verify the position of an individual rod if its individual rod
-failed-(SR0 examination question 081) position indication is
- )
i The time it takes for the source range nuclear instruments to :
energize following a reactor trip from 100% power (SR0 l
s examination question 090).
'The definition of a " Restricted Area" as described'in procedure
-F2,." Radiation. Safety," (SR0 examination question 007; R0
{
examination question 092)
=!
-The ability to calculate-Quadrant Power Tilt Ratio (QPTR) given-required' nuclear instrumentation data (R0 examination question 032).
i The operation of the power range nucle'ar instrumentation j
channel comparator (R0-examination question 033).
The administrative requirements =regarding station log entries (R0 examination question 100).
3.
Exit Meeting
-l
_An exit meeting was held to discuss the examiners observations, discussed in Section 2 of this report, on May 7,1990, with facility management and training staff representatives 4
>, r p,t >
[#
R 1
.f
~NRCirepresentatives-in attendance were:
E,
_J.~Lennartz, Examiner 9
.L. Sherfey, Examiner e
LA. Lopez, Examiner P. Hartmann, Senior Resident inspector, Prairie Island.
~
Facility representatives in attendance were:
E. Watzl, Plant Manager M; Sellman, General Superintendent,-Plant Operations T. Amundson, General Superintendent, Training Center D. Reynolds, Operations Training Supervisor M. Wadley, Shift Manager, Operations W. Bell, Shift Supervisor, Operations D.' Westphal, Lead' Instructor M. Hall, Lead Instructor
^
R.JWirkkala, Instructor
- J Gosman, Instructor-The f acility. management acknowledged the examiners observations.
I 4.
-Written Examination Review Facility representatives were allowed to review the written examinations prior to their administration'as discussed in Section 2,a of this report, and any applicable comments from the review were incorporated into the examinations.
Following the conclusion of the written examinations,' the facility was i
.given a= copy of the_ Senior Reactor Operator and Reactor _ Operator examinations and answer keys. The facility then-had until the end of examination administration week to provide any additional comments in' writing to the NRC.
L
._.The-following paragraphs contain the facility coninents concerning the examinations followed by the NRC resolutions, i
1
-I
- o
)
L 5
)
t a
h,
]
4
[
e Senior Reactor Operator Examination QUESTION 18:.
On the ERCS thermocouple display a thermorouple indicated 2550 degrees F.
.Which ONE (1) of the following indications would be seen on the digital
' display of the Incore Thermocouple. Control Panel, if that thermocouple were-selected?
l I
a.
-The display is BLANK.
b.
FourEs. appear'(EEEE).
E c.
A reading of 2550.
d.-
Fourdashes(----)..
1 Answer:
D Prairie Island Comment:
Question should be deleted. The Incore Thermocouple Control Panel referenced in system description B-10 "Incore Instrumentation" was replaced with-the Inadequate Core Cooling Monitor (ICCM). Displays on the ICCM are different than those that were on the Incore Thermocouple Control Panel.
NRC Resolution:
Comment accepted. The technical error in this question should have been identified during the f acility representative pre-exam review. The question has been deleted from the examination.
QUESTION 19:
In reviewing the operation logs you observe the following log entry, " Leaving 7 day action statement for LC0 3.15, Refer to entry at 1335 on 4/27/90".
WHICH ONE of the following statements. applies to this log entry?
a.
11.S1 pump.had been out of service for 4 days.
b.
Core Quadrant 4 had only'3 operable thermocouples.
c.
21 Battery Charger was inoperable due to a " burned out" rectifier
- assembly, d.
N51 had been removed from service for I&C calibration.
. Answer C Prairie Island Comment.
- Reference. is to' the Technical Specification for core exit thermocouples.
Answer should be "B" vice "C".
Appears answer key may be just a typo error.
Reference Technical Specification 3.15.
y r
x q
y.4. s p
.o t
q w
-,-1,
,'s l
a v
y, NRC Resolution:1 m
L"
- Comment-accepted. The answer key has been changed to reflect choice "B" as F
the correct answer, b
QUESTION 24: 1.
i With'the'"AUT0-MANUAL-SHUTDOWN AUT0" selector switch for the Motor Driven Aux Feedwater Pump selected to " SHUTDOWN-AUT0", which ONE of-the following AUTO.-
W
, START signals are blocked?
a '.
Low-Low S/G level;
_b.
' Safety-. Injection.
"c._
AMSAC signal.-
-l Ed '
Loss of Both Main Feedwater Pumps.
i Answer:- ;D Prairie Island Comment:.
~
Shutdown Auto-position of switch blocks ~ start signals due to loss.of both main.
s p
feedwater pumps or AMSAC. Thus both "C"' and "D" are correct answers.
+
Reference:
Lesson Plan P8180L-007 " Auxiliary feed Water System" page 17,
-electrical diagram HE-40006 sheet 78 "21 Aux Feedwater Pump",
4 s
NRC Resolution 4
Coninent accepted. ; The answer key has been changed to accept choice "C" or "D"
~
as correct answers.
-QUESTION 96:
Which ONE.of the following statements correctly reflects a condition where the
,RCPs may be tripped per procedure IE-3, " Steam Generator Tube _ Rupture"?
ASSUME operator cooldown hastnot been initiated and containment conditions are 4
normal.
a.-
_ONE SI pump _is running 0R'RCS pressure.is 1200 psig.
- b..
ONE SI-pump is running and RCS pressure is-1400 psig.
- c.
TWO SI pumps are running or RCS pressure is 1400 psig.
~
d.
'TWO SI pumps are running AND RCS pressure is 1200 psig.
iAn'swer:
B 3
1 Prairie Island Comment:-
'RCP tripicriteria per E-3 is_ SI pun 1p running and RCS pressure less than 1250 s
s psig. Correct answer should be "D,
-NRC Resolution:
Comment accepted. The answer key has been changed to reflect choice."D" as-the correct answer.
1 2
+,
a
m+
.b ' ; j
- p E,
- c 6-
?
a Reactor Operator Examination eo
't p"
QUESTION 23:
- t i
L The following plant conditions exist for testing of the reactor protection system:
f
-Train B reactor trip. breaker open
-Train B bypass breaker closed
-Train A reactor trip breaker closed
-Train A bypass-breaker open
-R.eactor at 100% power Which-0NE(1)of'thefollowingisthecorrectsystemresponseIMMEDIATELY following a spurious reactor trip signal and Bypass Breaker B fails to open?
a.
Turbine Generator must be manually tripped.
. 1 b.
Steam dumps receive an open signal, but doinot arm.
c.
Feedwater regulating valves remain open.
- d..
If.an SI. were to occur, manual reset would not be possible.
- Answer:
C Prairie Island Coment:
Both "c" and "d" are correct. A timer prevents SI reset until 90 seconds-after the SI. Thus, immediately after an SI, with the given conditions, manual reset-is not possible.
Reference:
Logic = diagram X-HIAW-1-242 1
NRC Resolution:
I
-Comment accepted. The answer key has been changed to accept choice "c" or. "d" as correct. answers.
r i
QUESTION 34:.
On the ERCS thermocouple display a thermocouple indicated 2550 degrees F.
Which ONE'(1) of the following indications would be seen on the digital display of the Incore< Thermocouple Control Panel, if that thermocouple were selected?
a.
-The display is BLANK.
b '. _
FourEs' appear (EEEE).
4 c..
A reading.of 2550.
~d.'.
.Four' dashes (----).
' Answer:
0 1
4.
e
q; n --
q
=
v:nV;c
.;;v 7
e
... 2 i
s (by:
's 1b iPrairie Isla6d-Comment:
JQuestion should be deleted.. The'Incore-Thermocoup"le Control, Panel referenced =
s; 1_nosystem description;B-10 "Incore Instrumentation was replaced with the 1
fiL InadequateCore_CoolingMonitor(ICCM); DisplaysontheICCM!are'.differenti-
.:l 0
- <Jfc 1than"those that were on the incore Thermocouple Control! Panel'.
-s
.THRC Resolution:.
,s 7:,
Comment accepted.The technical error ~in this question should have been identified during the. facility representatives pre-exam review.' The question-
]
4.
=has been deleted from'the examination.
t w -
r
~(
si e
3 h
(
<F r
t f
-' W.
- t
?
i o
f y
.[l
- f;
]!
t
~ i-l -Ji:[, '.
'i t
i*
+n i
if
~
t.'
i.,-
u j
l-2.
1 m
c;
- m. <c.3,w.
a_.
r:
4.-
QlpW f*/
's ~
u-,
p%. <, W, -,
+
u&
g.:
EM-E:t I ag n fg '", ' 4
- SIMULATION' FACILITY REPORT w
c I
.)
L sT. it' l Facility'LicenseeE Prairie' Island' o.-.
,ifaciliti: Licensee-DocketNo.150-282/50-206
~
l o20perat'ing Tests Administered At:' Prairie-Island Training-Center-
- .m c
p'_
!j[ ' ' '
During the conduct of'the simulator' portion of the operating' tests.,the (following. items'were observed.(if none, so state):-
x K
ITEM-DESCRIPTION-
- Non'e
, s~..
1d;
,i
-h l i.
.ki
' 'jc, i '
i I ';.g,
~
i
+ ;
)
{f m
.e n.
4 3>
b f
o 4
t l$ -
4
[.1 s
,n i
!'f 8
a l'
I 3
.y>
1 a,
.