IR 05000410/1991025
| ML17056B629 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/08/1992 |
| From: | Conte R, Williams J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17056B628 | List: |
| References | |
| 50-410-91-25OL, NUDOCS 9201290017 | |
| Download: ML17056B629 (14) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION I
OPERATOR LICENSING REQUALIFICATION EXAMINATION REPORT REQUALIFICATION EXAMINATION REPORT NO.: 50-410/91-25 (OL)
FACILITY DOCKET NO.:
50-410 FACILITY LICENSE NO ~:
NPF-14 LICENSEE:
FACILITY:
EXAMINATION DATES:
EXAMINERS:
Niagara Mohawk Power Corporation 301 Plainfield Road Syracuse, New York 13212 Nine Mile Point Nuclear Station, Unit 2 December
5, 1991 Don Draper, PNL John Hammer, PNL CHIEF EXAMINER:
lian H. Williams enior Operations Engineer WR Section, Operations Branch, DRS a
e APPROVED BY:
Ri har
.
onte, ref BWR Section, Operations Branch, DRS ate SUMMARY:
Requalification written examinations and operating tests were administered to four senior reactor operators (SROs)
and five reactor operators (ROs).
Four SROs and four ROs passed these examinations.
One RO failed the walk-through portion of the exam.
Generic weaknesses in operation of the Feedwater Control System and the Rod Worth Minimizer were identified.
c 9201290017 920114 PDR ADOCK 05000410 V
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DETAILS 1. 0 INTRODUCTION During the examination period, the NRC administered requalification examinat,ions to nine licensed operators (5 ROs and 4 SROs).
The examiners used the process arid criteria described in NUREG-1021,
"Operator Licensing Examiner Standards,"
Revision 6, Section ES-601,
"Administration of the NRC Requalification Program Evaluations."
Since 12 operators were not examined, a program evaluation could not be made.
The NRC will combine the results of this examination with further examinations to evaluate this program.
2.0 TYPE OF EXAMINATIONS:
Requalification 2.1.
EXAMINATION RESULTS REQUAL RESULTS
)Written RO Pass/Fail 5/0 SRO Pass/Fail 4/0 TOTAL Pass/Fail 9/0 I]Simulator 5/0 4/0 9/0 I
f Wa1 k-through 4/0 8/1 I
] Overal
4/0 8/1 These results reflect 100% agreement between the facility and NRC evaluators.
In addition, one RO failed the simulator portion of the examination as graded by the facility.
This RO met NRC's minimum standards for performance.
2.2 Generic Stren ths and Weaknesses A summary of generic strengths and weaknesses noted by the NRC during the requalification examinations is discussed below.
This information is being provided to aid the licensee in upgrading the requalification training program.
A.
~Stree ths:
~
The training department did a good job in planning and administering all phases of the requalification exa ~
The operating crews worked well together during the simulator (dynamic) portion of the exam.
Several instances were observed where operators were corrected by their team mates.
B.
Weaknesses:
~
During the dynamic portion of the exam, each crew showed weaknesses in operating the feedwater control system.
For example, this caused a turbine trip and reactor scram which were not critical tasks in one instance and an undesirable, but manageable, cold water injection in another instance.
One of the written exam questions dealing with narrow range level instruments and feedwater pumps was missed by four of the five operators, and this reinforced the observation.
~
Two crews were required to use the Rod Worth Minimizer (RWM).
during the simulator scenarios.
Both crews had difficulty in using the RWM.
2.3 General Observations:
A.
Simulator Portion of the Exam All three crews demonstrated proficiency in the use and knowledge of technical specifications and emergency operating procedures.
Communications between crew members was inconsistent, depending on the crew being examined.
Staff crew communications was generally weaker than that of the operating crews.
B.
Walk-throu h Portion of the Exam The operators did an adequate job of discussing the expected results of action taken during a JPM.
In some cases, more discussion would have been helpful.
The facility evaluators did a good job of controlling and administering the JPMs.
The simulator JPMs were very well planned to eliminate waiting and reduce operator stress.
For one plant JPM (JPM-93),
the examiner noted an uncontrolled operator aid at the UPS Panel.
The licensee investigated and found that the operator aid was not needed and removed it.
C.
Written Exam Except for the problem already noted about feedwater control, the operator performance on the written exam demonstrated a high level of knowledg.0 EXIT MEETING On December 6,
1991, at the conclusion of the requalification examination, the NRC conducted an exit meeting.
Preliminary examination results, general observations, strengths, and weaknesses were discussed.
Personnel in attendance are noted in Attachment Attachment
Persons Contacted Exit Meetin Nia ara Mohawk Power Cor oration M.
D.
R.
0.
J.
C.
R.
P.
F.
S.
D.
J.
Colomb, Manager - Operations R. Hartrauft, Plant Operating Clerk L. Magnant, Generation Specialist J.
McCormick, Jr., Plant Manager W. Pettit, Senior Operations Instructor G. Reid, Supervisor, Operator Training, Requal R. Robert, Plant Operating Clerk K. Slade, Senior Supervisor, Operator Training J. Walsh, Senior Operator Instructor R. White, Supervisor, Operator Training W: Wilzcek, Vice President, Nuclear Support E. Wilson, Associate Senior General Engineer - Nuclear Nuclear Re ulator Commission L. H. Bettenhausen, Chief, Operations Branch J.
H. Williams, Senior Operations Engineer
Cr
Attachment
Re uglification Examination Test Items Written Exam Part A
02-REQ-009-1 s t-2-17, 02-REQ-009-1st-2-17, 02-REQ-009-1st-2-36, 02-REQ-009-1st-2-36, Written Exam Part B
Rev.
0, 12 Questions (RO)
Rev.
0, 12 Questions (SRO)
Rev.
0, 10 Questions (RO)
Rev. 0, 10 Questions (SRO)
02-REQ-C18-BEX-2-01, Rev.
0, 25 Questions (RO)
02-REQ-C18-BEX-2-01, Rev.
0, 25 Questions (SRO)
Walk-throu h
Exam JPM SJE-15 SJE-97 SJE-25 SJE-27 SJE-99 SJE-08 SJE-98 SEE-13 PJE-73 SJE-95 SEE-04 PJE-93 SJE-44 PJE-77 PJE-67 PJE-72 Drywell Vacuum Breaker Operability Test Manually Initiate SLC (faulted)
Raise Reactor Power with Recirc Flow 50 MWe Transfer Reactor Recirc Pumps to Fast Speed Start Reactor Water Cleanup -in Full Reject Startup Suppression Pool Spray Warm up the B
RHR Loop Discharge Piping for Shutdown Cooling Inject with HPCS (Time Critical)
Inject Boron Using the SLC Hydro Pump Inject with RCIC (faulted)
Trip the Main Turbine from the Control Room (time critical)
Restore UPSID from No Power to the Maintenance Supply Parallel the Division One Diesel with Offsite Place the Standby Off-Gas Vacuum Pump in Service Transfer Control to the Remote Shutdown Room Vent the Scram Air Header D namic Simulator Exam 02-REQ-009-IDY-2-19, 02-REQ-009-IDY-2-03, 02-REQ-009-IDY-2-11, 02-REQ-009-IDY-2-14, 02-REQ-009-IDY-2-18, Rev.
0, ATWS Rev.
4, LOCA-D/W Rev. 8, ATWS with SLC Injection Rev.
5, LOCA Rx Bld I
Attachment
SIMULATION FACILITY REPORT Facility Licensee:
Niagara Mohawk Power Corporation, Nine Mile Point, Unit 2 Facility Docket No.:
50-410 Requalification Examination Administered from:
December 2 - 5, 1991 This form is to be used only to report observations.
These observations do not consittute audit or inspection findings and are not, without further verification and review, indicative of noncompliance 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 (if none, so state):
Non t 1