ML19327B976
| ML19327B976 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/03/1989 |
| From: | Burdick T, Damon D, Hopkins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19327B975 | List: |
| References | |
| 50-282-OL-89-02, 50-282-OL-89-2, NUDOCS 8911140304 | |
| Download: ML19327B976 (5) | |
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'U.S. NUCLEAR REGULATORY COMMISSION REGION III
. Report No. 50-282/0L-89-02 Docket Nos. 50-P.82; 50-306 Licenses No. DPR-42; DPR-60 Licensee:- Northern States Power Company l
1660 Wakonade Drive West Welch, MN' 55089 t
Facility Name: Prairie Island Nuclear Generating Plant Examination Administered At: Welch, MN Examination Conducted:
October 23-27, 1989 RIII. Examiner:
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fJ. +Hopkins /
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. Chief Examiner:
v D.00amon Date Approved By:
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/N T. Surdick Date Examination Summary Examination administered during week of October 23, 1989'(Report No. 50-282/
DT.-89-02))
Examination given to six reactor operators and ten senior reactor operators.
Results: All operators passed all sections of the NRC administered examinations. The licensee failed two senior reactor operators on the dynamic simulator' portion of the examinations.
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REPORT DETAILS b
- 1.
Examiners t#
. D. Damon J.,Hopkins m
P K. Parkinson F.-Victor
- Chief Examiner
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2.
Exit Meeting On October 27, 1989, the examiners met with members of the facility staff l
to discuss the examination process.
The following persons attended the i
meeting' L
D..Revnolds, Operations Training Supervisor, NSP M. Se"1 man, General Superintendent Plant Operations, NSP l
L. Anderson, Shift Manager, NSP J. Sorensen, Shift Manager, NSP M. Hall, Instructor, NSP D. Mendele, General Superintendent Engineer and Radiation Protection, NSP T.'Amundson, General Superintendent PITC, NSP e
R. McGillic, Operations Training Supervisor - Monticello, NSP P. Hartmann, Senior Resident: Inspector, NRC T. O' Conner, Resident Inspector, NRC D. Damon, Chief Examiner, NRC J. Hopkins, Examiner, NRC During the meeting, preliminary NRC results and final facility results a
were discussed. Preliminary NRC results.were that all individual examinees passed the exams, with one crew failure. Facility results were that all crews passed the exams, two individuals failed the simulator examinations.
and all other sections of the exam were passed. The Chief Examiner explained r,
that the NRC results were preliminary, and as such were subject to change based on further review of additional data being supplied by the facility i
staff.
The examiners outlined several observations that were made during the course of the examinations:
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Procedure C20.5 contains guidance on the operations of the station 4160 a.
t volt distribution system. Portions of this procedure were written in such'a general nature that three crews applied the procedural steps K
in three different ways, and each of the three different methods fell within the guidelines in the procedure. The facility staff has agreed to evaluate the need for changes in this procedure.
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During performance of procedure E-1, " Loss of Reactor or Secondary Coolant," a determination is made concerning whether or not RCS 1
4-pressure is stable or increasing. This criteria is used to determine the need to stop RHR pumps. Three crews applied the RCS pressure criteria in three different ways.
c.-
During response to en ATWS event, only one of three crews observed used all means available in the control room to attempt to trip the reactor, i.e., use of the second control room reactor trip switch.
The facility staff has agreed to stress in training that there is more than ore switch available to trip the reactor from the control room.
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Two of four crews incorrectly determined the Emergency Action level for an ATWS event.
L e.
All crews were observed making good use of procedures and Technical Specifications.
f.
Fecility evaluators need to be more aware of providing inadvertent prempts to examinees when performing JPM evaluations. These inadvertent prom)ts consist of phrases such as "ok", "I'm satisficd",
or "That's enoug1".
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Evaluators need to be conscious of the cues that are provided in the JPM, and to consistently provide the appropriate cues to the examinee.
Cues should not be given only when an examinee does not perform an action correctly, at the cue then becomes a prompt.
h.
The facility should choose a single method to be used to determine when an examinee is finished. answering JPM questions. This method should then be used by all facility evaluators.
Several different methods were in use during this examination, and not all methods were equally effective.
3.
Comparison of NRC and facility evaluation practices.
Facility evaluation of crew performance was consistent with NRC evaluation of the crew performance during dynamic simulator scenarios.
Facility evaluation of individual performance during dynamic simulator scenarios appeared to be stricter than NRC evaluation of individuals.
This is considered satisfactory per ES-601.c.3.b.(2).
Facility grading of written exams was consistent with NRC grading.
Facility grading of JPM walkthroughs and JPM questions appeared to be more lenient than grading done by the NRC. The facility evaluators should take care to document subtle differences between examinee performance or response and the performance or response required for l
satisfactory performance.
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Facility: P,rairie Island. Nuclear' Generating Plant 4
Examiners:D. Damon,'J. Hopkins, K. Parkinson, F. Victor I
Dates of Evaluation: October 23 - 27, 1989
$ 's-Areas Evaluated: XX Written
~XX Oral XX Simulator g
I Examination Results:
R0 SR0 Total Evaluation Pass / Fail Pass / Fail Pass / Fail (S. M. or U)
. Written Examination 6/O-10/0 16/0 S
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Operating Examination Oral.
6/0~
10/0 16/0 S
Simulator G/0 10/0 16/0 S
. Evaluation of facility written examination grading-S y
Overall Program Evaluation Satisfactory.
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Facility grading.of JPH questions appeared to be more lenient than NRC grading l~'
of the same questions.
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. Damon Examiner Section Chief Branch Chief i
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SIMULATION FACILITY REPORT t
L Facility Licensee:
Northern States Power Facility Licensee Docket No.
0-282; 50-306 Operating Tests Administered At:
Prairie Island Nuclear Generating Plant During the conouct of the simulator portion of the operating tests, the following items were observed.
ITEM DESCRIPTION 1.
Following a reactor trip, the core cooling status tree should toggle from green to yellow based on whether or not core subcooling is greater than 20"F.
The status tree was toggling to yellow with greater than 20' subcooling when it should remain green.
2.
Following a loss of transformer 1R and a loss of bus 15, letdown isolates for no apparent reason.
3.
Following a scenat io for inadequate core cooling, core exit thermocouple temperatures continue to increase despite all operator action.
CET temperatures should decrease when adequate core cooling is established.
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