IR 05000245/1986024
| ML20212C094 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/12/1986 |
| From: | Eapen P, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20212C070 | List: |
| References | |
| 50-245-86-24, 50-336-86-26, 50-423-86-34, NUDOCS 8612290388 | |
| Download: ML20212C094 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report Nos.
50-245/86-24 50-336/86-26 50-423/86-34 Docket Nos.
50-245 50-336 50-423 License Nos.
DPR-21 DPR-65 NPF-49 Licensee:
Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270 Facility Name: Millstone Units 1, 2 and 3 Inspection At: Waterford, Connecticut Inspection Dates: November 17-20, 1986 W
/2 2 [f Inspector:
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. Oliveira, Reactor Ehgineer date'
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QAS, OB, DRS, RI Approved by:
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/E 2/7/3 Dr.P.K.'Eap'en,[ Chief,QualityAssurance dat(
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Section, Operations Branch, DRS, RI Inspection Summary: Routine unannounced inspection on November 17-20, 1986 (Raport Nos. 50-245/86-24, 50-336/86-26 and 50-423/86-34).
Areas Inspected: Non Licensed Staff Training Results: No violations or deviations were identified.
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DETAILS-1.0 Persons Contacted J. Black, Nuclear Training Department Manager
- G. Closius, Quality Assurance / Quality Control (QA/QC) Supervisor
- H. Haynes, Operator Training Manager
- J. LaWare, Senior Engineering Technologist, NUSCO QA
- T. Mcdonald, Technical Training Mechanical Supervisor
- D. Nordquist, QA Manager, NUSCO
- W. Romberg, Station Superintendent
- S. Scace, Millstone Unit 2 Superintendent
- J. Stetz, Millstone Unit 1 Superintendent
- W. Varney, Millstone Unit 1 Maintenance Supervisor United States Nuclear Regulatory Commission (NRC)
T. Rebelowski, Senior Resident Inspector
- G. Grant, Resident Inspector
- Denotes those who attended the exit meeting on November 20, 1986.
2.0 Non Licensed Training 2.1 Introduction The effectiveness of the implementation of the licensee's non licensed staff training program in operations, maintenance, instrumentation and control (I&C), engineering, and Quality Assurance (QA) w~as assessed by reviewing the following:
Shift turnover for plant equipment operators.(PEOs).
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PE0s conducting routine plant tours and pre-start up checks of Emergency Diesel Generator (EDG) B in accordance with ops Form 2346A; and valve alignment of the Reactor Building Closed Cooling Water (RBCCW) System.
Training instructor discussions with I&C technicians to enhance
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technical content of the lesson plans.
Mechanics installation of snubbers, and 18 month surveillance of
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EDG B assembly in accordance with Automatic Work Order (AWO) M2 85 02680 and Maintenance Procedures (MPs) 2719A & D.
Electricians reworking a Reactor Coolant Pump (RCP).
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I&C technicians performing checks of failed Control Element Drive System (CEDS) sensors, and surveillance of radiation monitors per Surveillance Procedure (SP) 2404.
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Engineering activities in processing Plant Design Change
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Requests (PDCRs),
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1-66-86, 2-53-86, 2-60-86, 2-81-86, 2-83-86, and 2-100-86.
Student feedback factored into the training program.
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QA audits and surveillance reports.
Training records of personnel interviewed and observed
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Lesson plans The Manager of Technical Training in the Nuclear Training Department is responsible for non licensed training except for the training for engineers and managers. The Manager of General Nuclear Training is responsible for managers' and engineers' training programs.
The following procedures implement the non-licensed training program.
Nuclear Training Manual (NTM) 3.05. Revision 0,
"Non-Licensed
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Operator Initial Training Program Implementing Procedure".
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NTM 3.07, Revision 0. "Non-Licensed Operator Continuing Trairing Implementing Procedure".
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NTM 3.201, Revision 0,
" Technical Staff and Manager Training Program"
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NTM 3.101, Revision 0,
" Millstone Unit 1 Instrumentation &
Control Technician" M3-TT-MMIT, Revision 0,
" Mechanical Maintenance Initial
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Training".
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M3-TT-MMCT, Revision u,
" Mechanical Maintenance Continuing Training".
These procedures were developed in accordance with INPO guidelines and Regulatory Guide (RG) 1.8, 1975,
"Perscnnel Selection and Training".
Activities were conducted in accordance with the procedures by personnel knowledgeable in the requirements of the procedures and technical specifications as evidenced by the followir.g:
During a walk down of the pre-start check list (ops Form 2346A) with the NRC inspector the PE0 noted, recorded and reported to the control room that the rotary switches 43-1 were lined up in the local vice remote position.
In another case, the PE0 noted, recorded and
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reported that the power supply on-off lights to the air compressor were not functioning. He tested the bulbs to be sure that they were not burned out. The PE0 was aware that there was no power supply to the air compressor. He also verified that the control room was aware of this condition.
During a walk down of the RBCCW valve alignment with the NRC inspector, another PE0 had to climb over equipment to verify valve positions. 'The inspector noted that he applied his training to assure that he.did not inadvertently damage other equipment while climbing to the valve.
The NRC inspector witnessed the installation of a snubber in the low pressure coolant injection (LPCI) system, in a radiation area.
The lead mechanic realized that additional tools would be required.
' Because of radiation concerns, the lead mechanic instructed the accompanying. personnel to leave the area while the personnel were waiting for additional tools.
He explained that this action was taken for ALARA considerations and to avoid unnecessary exposures.
The same lead mechanic also teaches mechanics how to remove, test and install snubbers.
It is an informal three week course.
Four mechanics have been trained and two were in training at the time of this inspection.
The Training Center has requested this lead mechanic 9 provide tours of his snubber shop to mechanics and other technical personnel as a supplement to the classroom training.
An electrician explained to the NRC inspectors his duties and responsibilities regarding the work being performed on the
"C" RCP motor in accordance with AWO M2-86-11644. He was overseeing the work.
The inspector observed that he was knowledgeable of the requirements as well as what was expected of the vendor representatives.
An I&C technician was trouble shooting to resolve a problem with failed sensors. His actions were in accordance with procedure IC 2420A. Though the procedure did not specifically refer to the technical manual, the technician had been trained to use the technical manual as a source of information.
An engineer walked down PDCR 1-66-84 with the NRC inspector. This was a Millstone Unit 1 design change and it upgraded the seal water manifold to the C and D service water pumps to be seismically qualified.
The engineer was responsible for presenting the PDCR to PORC for their approval, initiating final drawings, preparing test procedures, supervising the work, and preparing the affected procedure changes. The training for processing PDCRs was primarily OJT.
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- Millstone Units 1 and 2 have programs accredited by INP0 for Non Licensed Operator Training. Self Evaluation Reports for the balance of the non licensed training programs have been submitted to INP0.
Final accreditation board review by INP0 is planned for late 1986. The licensee expects the remaining non-licensed training program to be accredited by INP0 in late 1987.
The training personnel are seeking feedback from the trainees on a continued basis. They also work closely with the linc personnel to enhance technical content cf the lessons.
The inspector witnessed one such technical discussion of an instructor with the I&C technicians.
2.3 QA/QC Interface With Millstone Training Four QA audits and one QA Surveillance audit were conducted in non-licensed training area.
All identified deficiencies were corrected in a timely manner, except for items F15b & c in audit A60427 issued August 16, 1986. This deficiency was followed up in QA Audit A60477 issued September 1986 and deals with Maintenance personnel not receiving QA training, and Engineering personnel not receiving training in surveillance tests. This deficiency remains open and is scheduled for reaudit during the Corrective Action Audit A60479 scheduled to start on December 1, 1986.
A QC inspector was observed witnessing the installation of the LPCI snubber. He walked down the installation with the NRC inspector and explained the basis for the witnessing of certain hold points.
2.4 Conclusions Based on the above, the inspector concluded that non licensed training at Millstone Units 1 and 2 was acceptable. No devia~tions or violations were observed.
3.0 Management Meetings Licensee management was informed of the scope and purpose of the inspection at the entrance interview on November 17, 1986. The findings of the inspection were discussed with the licensee representatives during the course of the inspection and presented to licensee management at the November 20, 1986, exit interview (see paragraph 1 for attendees).
At no time during the inspection was written material provided to the licensee by the inspectors. The licensee indicated that no proprietary information was involved within the scope of this inspection.