IR 05000220/1980020
| ML17053C281 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/10/1980 |
| From: | Caphton D, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053C280 | List: |
| References | |
| 50-220-80-20, NUDOCS 8102060046 | |
| Download: ML17053C281 (10) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-220/80-20 Docket No. 50-220 License No.
DPR-63 Priority Category C
Licensee:
Nia ara Mowhawk Power Cor orati on 300 Erie Bou evar West racuse, ew Yor 3 02 Facility Name:
Nine Mile Point Unit 1 Inspection at:
Scriba, New York Inspection conducted:
November 18-20, 1980 Inspectors:
J.
T. Wiggins, Reactor nspector ld m ate signe Approved by:
.
C t n, C ief, Nuc ear Support Section No. 1, R08(S Branch r~/i~so ate signed ti R
Ins ection'on November 18-20; '1980 (Report'No.'0-220/80-20)
reas Ins ecte
Routine, unannounce inspection of t e icensed operator re-qua i ication training program, general employee training, non-licensed personnel training and a plant tour.
The inspection involved 19 inspector-hours onsite by one regionally based inspector.
Results:
No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
,
- J. Aldrich, Training Superintendent K. Dahlberg, Maintenance Superintendent J. Duell, Radiation Protection Supervisor
- T. Perkins, General Superintendent
- T. Roman, Station Superintendent B. Taylor, Instrument and Control Supervisor
- K. Zollitsch, Training Supervisor Other NRC Personnel
- S. Hudson, Resident Reactor Inspector
- Denotes those present at the exit meeting conducted November 17, 1980.
The inspector also interviewed nine other licensee employees.
They included a licensed senior. reactor operator, a licensed reactor operator, an auxiliary operator, an electrician, a mechanic, a Radiation Protection Technician, an Instrument and Control Technician and two temporary employees.
0 erator Re ualification Trainin References:
(1)
CFR 55, Appendix A
(2)
Nine Mile Point (NMP) Site Administrative Procedure No.
APN-10B, Licensed NRC Operator Retraining Rev. 2, May 7, 1980.
a ~
Pr o ram Review In response to the March 28, 1980 letter from Mr. H. Denton, Director, Nuclear Reactor Regulation (NRR), to all licensees, NMP revised the Licensed NRC Operator Retraining program and implemented this revised program on May 7, 1980.
The revised program did not decrease the scope, time allotted or frequency of conduct of any portion of the program from that specified in the NRR approved requalification program.
The revised program contains:
an established, planned, continuing lecture schedule including lectures on heat transfer, fluid flow, thermodynamics and mitigation of accidents involving a degraded core;
documentation of personnel attendance; required control manipulations; reviews of changes in facility design, procedures and the facility license; review of Special Operating Procedures; and, evaluation processes with.applicable acceptance criteria.
The inspector reviewed the lesson plans for heat transfer, instrumentation and control and reactor theory and principles of operations.
Two requalification lectures in the heat transfer area were attended.
No items of noncompliance were identified.
b.
Record Review c ~
The inspector reviewed the individual records of three licensed senior
, operators and three reactor operators.
The records reviewed contained:
annual examinations with answers; records of lecture attendance; performance evaluations; records of procedure reviews, facility design change reviews, and technical specification change reviews; records of simulator training No items of noncompliance were identified.
Personnel Interviews
'he inspector interviewed two licensed personnel in order to obtain a
subjective appraisal of the adequacy and quality of the program and to confirm the information documented in the program records.
No items of noncompliance were identifie.
General Em lo ee Trainin References:
(1)
ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel (2)
NNP Station Site Administrative Procedure No. APN-10D, General Employee Training, January 1980.
~PII The inspector reviewed the training program to verify consistency with the requirements of 10 CFR 19,
CFR 50, Appendix B, Criterion II, and ANSI N18.1-1971.
The program sets.forth training in plant administrative procedures and controls, radiological health and safety, industrial safety, station security, quality assurance, fire protection and station emergency plans.
Training is given to new and temporary employees upon their arrival on-site and repeated yearly thereafter for all employees.
Female employees receive training on the contents of Regulatory Guide 8. 13.
No items of noncompliance were identified.
b.
Pro ram Partici ation P
The inspector reviewed the individual training records and interviewed five individuals to verify.that the documented training was conducted in accordance with program requirements and that the training conducted was adequate and meaningful for the participants.
The individuals interviewed consisted of:
one new female employee; two existing employees; and, two temporary employees The inspector also attended one lecture in the radiation protection area.
No items of noncompliance were identifie. Non-Licensed'PersonnelRTrainin Reference:
(1)
ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel (2)
NMP Station Site Administrative Procedure No. APN-lOC, Training of Non-Licensed Personnel; dated September 19, 1977.
'~P'
The inspector reviewed the training program for technicians and craftsmen.
The program consists of an automatic progression course series taught by the licensee's corporate staff, and on the job training controlled by the licensee's on-site staff.
No items of noncompliance were identified.
b. Pro ram Partici ation The inspector reviewed the records of training in this area and interviewed two craftsmen and two technicians.
The, inspector found no inconsistencies between the training that was documented and'hat was actually received.
No items of noncompliance were identified.
5.
Plant Tour
The inspector conducted tours of the control room, the turbine building and the plant exterior areas inside the protected area boundary.
l<hile in the control room on November 19 and 20, 1980 the inspector compared the calculated core thermal power with the expected'alue and licensed limits and observed the manner in which control air pressure to the CRD scram system is monitored in the control room.
No items of noncompliance were identified.
6.
~6i On November 17, 1980, a management meeting was conducted by the inspector.
The attendees are listed in Detail 1..
The inspector reviewed the scope of the inspection and discussed the inspection findings.