ML20045B529
| ML20045B529 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/10/1993 |
| From: | Jordan M, Mcneil D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20045B528 | List: |
| References | |
| 50-155-OL-93-01, 50-155-OL-93-1, NUDOCS 9306180042 | |
| Download: ML20045B529 (8) | |
Text
i U.
S.
NUCLEAR REGULATORY COMMISSION REGION III i
Report No. 50-155/OL-93-01 Docket No.
50-155 License No. DPR-6 Licensee:
Consumers Power Company 10269 US 31 North Charlevoix, MI 49720 i
Facility Name:
Big Rock Point Nuclear Plant Examination Administered At:
Big Rock Point Nuclear Plant i
10269 US 31 North Charlevoix MI Examination Conducted:
April 26 - 30, 1993 Chief Examiner:
Id
/!,
/!/c J D.
R. McNeil Date'
((
MI d!/f!73 Approved By:
M. J. Jordan, Chief Dats Operator Licensing Section 1 Examination Summary Examination administered durina the week of April 26 - 30, 1993 Report No. 50-155/OL-93-01(DRS))
i Two non-licensed operators were given Reactor Operator examinations.
Results:
Both individuals passed all sections of their respective examination.
The following is a summary of the strengths and weaknesses noted during the performance of the examinations.
i f
Strenoths Operator knowledge of equipment location and operation.
e (For details see Sections 3b/c)
Interaction between simulator operators and candidates.
I (For details see Section 3c) 9306180042 930610 PDR ADDCK 05000155
.V PDR L
.-m-r-,
5 Examination Summary 2
h Weaknesses Knowledge of personnel monitoring devices and radiation e
detection devices.
(For details see Section 3b)
Emergency dose limits and potassium iodide use.
(For o
details see Section 3b)
I No previously prepared instrument failures developed for e
use during the operating test.
(For details see Section 3c) j Materials required to execute emergency procedures.
(For e
details see Section 3b)
Valve labeling in the plant.
(For details'see i
e Section 4) f h
t
}
l s
i REPORT DETAILS i
1.
Examiners
- D.
R. McNeil, Chief Examiner, NRC, Region III
- M.
J. Jordan, Chief, OLS 1 f
2.
Persons Contacted Facility l
- G.
C.
Withrow, Acting Plant Manager / Engineering Support I
- W.
J.
Trubilowicz, OPS Superintendent
- D.
G.
La Croix, Training Administrator
- D.
N.
Staton, Senior Nuclear Instructor
- M.
Bourassa, Senior Plant Licensing Tech U.
S.
Nuclear Reaulatory Commission (NRC)
}
R.
Leemon, SRI, Big Rock Point
- Denotes those present at the exit meeting on April 30, 1993.
3.
Initial License Trainina Procram Observations The training department was found to be responsive to the needs of the examination team especially in the area of scenario development and validation.
They put in extra time when necessary without complaint and maintained a i
professional attitude throughout the examination.
i The following information is provided for evaluation by the licensee via their SAT based training program.
No response 7
is required.
s I
a.
Written Examination Strenaths/ Weaknesses:
I No strengths or weaknesses were observed in this category of the examination.
b.
Job Performance Measures (JPMs)
Strenaths:
Candidates were very knowledgeable concerning equipment location and operation.
The candidates were able to proceed rapidly to equipment and understood how to operate the equipment without prompting.
3
Candidates were very familiar with their operating procedures.
They obtained and executed the procedures well and without prompting or clarification by the examiners.
Weaknesses:
Candidates began executing the emergency procedures without having the correct equipment.
Both candidates being examined would have had to return to the control room to execute Job Performance Measures (JPMs) because they had forgotten to obtain keys or other equipment before they began to execute the assigned procedure.
Candidate's knowledge of radiation detection devices and personnel monitoring devices is deficient.
Neither candidate was able to correctly state what types of radiation was detected by different instruments found in the plant.
One candidate stated the TLDs are developed like a film badge and kept as a permanent record off site.
The candidates were unsure of emergency radiation dose limits, when potassium iodide was to be used, and who could authorize the higher dose limits and use of potassium iodide.
c.
Dynamic Simulator Scenarios Strengths:
Candidates were very knowledgeable concerning control room equipment location and operation.
The candidates were able to proceed rapidly to switches and instruments and understood how to operate the equipment.
Candidates were very familiar with their operating
~
procedures.
They obtained and executed the procedures well.
Interaction between simulator operators and candidates was excellent.
The simulator operators kept track of how many outside operators were being used and their assignments and made realistic-radio reports concerning their assignment status.
This added a significant amount of realism to the conduct of the scenarios.
4
The simulator is identified as a strength in the Big Rock Point training program.
The simulator performed well during the scenarios and JPMs.
However, there were some minor problems which are identified in the weaknesses section and,
Simulation Facility Report.
Weaknesses:
There were no previously developed instrument failures for use during the simulator portion of the operating test.
Each instrument failure had to be developed individually.
This caused the validation time to be excessive and accuracy depended on the individual instructor's memory.
The candidates divided the control room responsibilities in an unusual fashion, with one operator responsible for control board manipulations and the other operator rerponsible for procedure retrieval and reading.
This is not consistent with the normal Big Rock Point control room operating philosophy.
4.
Operations. Security, Rad Protection. Other Strenaths:
Training, Operations, Security and Rad Protection were all professional in their dealings with the examination team.
The examination team was able to quickly process through the gate house and into the plant.
The examination team was able to quickly obtain all materials needed for efficient administration of the examination.
The shift supervisor on shift during the examination was very cooperative and even restricted access to the control room during the examination without request from the examiners.
This action helped to provide the candidates with a quieter, less stressful examination atmosphere.
Weaknesses:
Valves in the plant are labeled with round brass tags.
In many cases the valve numbers on those tags are difficult.to read which makes it difficult to perform a correct valve lineup.
This is especially important for these cases where emergency equipment must be lined up rapidly to mitigate the consequences of an accident.
The training department has indicated the labels for ECCS equipment are scheduled to be replaced with plastic labels containing valve numbers and equipment noun names during.the next fuel cycle.
5
5.
Simulator Observations Some simulator problems were identified.
These problems are noted in Attachment 4.
6.
Exit Meetina An exit meeting with the Big Rock Nuclear Station management was held at the Big Rock Nuclear Station training offices on April 30, 1993.
Those attending the meetings are listed in Section 2 of this report.
The following items were discussed during the exit meeting:
Strengths and weaknesses noted in this report.
The general observations relating to the plant noted in Section 4.
\\
5 s
r 6
FACILITY COMMENTS AND NRC RESOLUTION OF COMMENTS Question 59 on the RO examination is as follows:
SELECT the choice that completes the following statement.
The liquid poison tank is supplied with heaters to maintain the liquid poison at
- F. The poison tank is also insulated so that, upon loss of the heaters, the solution will be maintained above saturation temperature for hours.
a.
130, 30 b.
140, 40 c.
150, 50 d.
160,-60 Answer: c.
Facility Comment:
There is no correct answer provided for this question.
The correct answer should be 150, 40.
Request deletion of the question.
NRC Resolution:
Concur with the facility.
The question is deleted.
Ouestion 59 on the RO examination is as follows:
SELECT the choice that completes the following statement.
The Diesel Fire pump will automatically start if fire header pressure reaches:
a.
70 psig, or steam drum level is -4 inches below center line b.
60 psig, or steam drum level is -17 inches below center line c.
50 psig, or steam drum level is -8 inches below center line d.
80 psig, or steam drum level is -17 inches below center line i
Answer: b.
Facility Comment:
-This question has "d" indicated as the answer.
The correct answer is "b".
Request change of the answer key.
1 ERC Resolution:
Concur with the facility.
The question was modified and the' answer key not changed when the modification changed the correct answer.
The key now accepts "b"
as the only correct i
answer.
l I
I l
l c-j
r
+
SIMULATION FACILITY REPORT Facility:
Big Rock Point Nuclear Plant Docket No.
50-155 i
Operatina Tests Administered On:
April 26 - 30, 1993 The following documents observations made by the NRC examination team during the April 1993, initial examination.
These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of non-compliance with 10 CFR 55.45 (b).
These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations.
No licensee action is required in response to these-observations.
During the conduct of the simulator portion of the operating tests, the following items were observed:
I_T_EM DESCRIPTION f
Instrument The simulator does not have any installed Failures instrument malfunctions / failures.
Accuracy of the malfunctions now depends on the mental awareness and knowledge of the individual instructors.
P OG Selector Behind the front control room panels there is an Switch Off-Gas selector switch installed.
Pictures of-all other equipment have been taken and are in place in the simulator.
This switch has apparently been missed.
Installation of the switch or a picture of the switch would enhance scenarios when failure ~of the OG detentors is inserted as a malfunction.
i t
1
- w. -