IR 05000245/1989005
| ML20247L788 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/17/1989 |
| From: | Anderson C, Julio Lara, Woodard C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20247L782 | List: |
| References | |
| 50-245-89-05, 50-245-89-5, 50-336-89-07, 50-336-89-7, NUDOCS 8906020253 | |
| Download: ML20247L788 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
z 50-245/89-05 Report Nos.
50-336/89-07 r
50-245 Docket Nos.
50-336 DPR-21 License No.
DPR-65 l
Licensee: Northeast Nuclear Energy Company
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P.O. Box 270 Hartford, Connecticut 06141-0270 Facility Name: Millstone Nuclear Station, Units 1 and 2
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inspection At:
NUSCO Offices in Berlin, CT and Millstone Units 1 and 2
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Inspection Conducted: April 17-21, 1989 br Q? TC Inspectors:
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i C. If. Woodard, Reactor Engineer, DRS, PSS
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f7 f>bS J. f. Lara, Reactor Engineer, DRS, PSS date Approved by:
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C. J. Ahderson, Chief, Plant Systems Section date Inspection Summary:
Routine announced Inspection on April 17-21, 1989 for Millstone Units 1 and 2.
The areas inspected included engineering organization and staffing, quality assurance, plant modifications and technical training.
Results of the inspection indicated that the licensee's engineering support of the stations functions is good with strong interfacing between NNECO and the supporting company NUSCO.
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DETAILS 1.0 Persons Contacted 1.1 Northeast Nuclear Energy Company R. T. Blanchard, ISI Coord., NNECO
- P. Blasioli, Licensing Supervisor, NUSCO
- W. Briggs, General Civil Engineer, NUSCO
- F. Dacimo, MP-2 Engineering Supervisor
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B. Duffy, Asst. Engineering Supervisor, NNEC0 J. Ferguson, General Mechnical Engineer, NUSCO J. Festa, MP 1/2 I&C Engr. Supervisor, NUSCO K. W. Fox, General I&C, NUSCO E. G. Gilbert, Engineer, NNECO
- H. F. Haynes, Station Services Superintendent, NNECO
- G. L. Johnson, Director, Generation Engineering & Design, NUSCO
- B. Kaufman, Quality Services Supervisor, NUSCO R. McGuinness, Licensing Supervisor, NUSCO D. O. Nordquist, Director, Quality Services, NUSCO
- G. Pitman, Gener. Elec. Engr. Mgr., NUSCO T. Quinly, ISI Engineering J. Regan, Gener. Elec. Engr., NUSCO
- L. R. Steinke, Technical Reports Supervisor, NUSCO
- J. Stetz, Unit 1 - Superintendent T. Thull, Engineer, NNECO
- W. Vogel, MP-1 Engineering Supervisor D. Yapchanyk, Engineer, NNECO 1.2 U.S. Nuclear Regulatory Commission P. Habighorst, Resident Inspector
- L. Kolonauski, Resident Inspector B. Raymond, Senior Resident Inspector
- Attendees at the exit meeting on April 21, 1989.
2.0 Objective The objective of this inspection was to assess the effectiveness of the licensee's program for engineering support to plant operations including engineering design, management effectiveness, staffing and experience, training and responsiveness to NRC requirements and concerns.
Licensee procedures addressing the above areas also were reviewed.
(See Attach-ment A for a list of procedures reviewed.)
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3.0 Engineering and Support Organization The inspectors held discussions with licensee personnel to review the division of responsibility within the engineering organization.
Northeast Utilities maintains an engineering staff in both the corporate service company (NUSCO) and the operating company (NNECO).
NUSCO maintains two engineering divisions at its corporate offices which provide extensive technical support to Millstone Units 1 and 2.
These are the Generation Engineering and Construction Division and the Nuclear and Environmental Engineering Division. On-site technical support is provided by the units' corresponding engineering departments in the Nuclear Operations Division.
These three divisions headed by Vice-presidents report to the Senior Vice president of Nuclear Engineering and Operations (NEO).
The Generation Engineering and Construction Division is divided into several departments including the Engineering and Design Department.
This department is sub-divided into various engineering areas such as Generation, Mechanical and Electrical Engineering, Design and Civil Structures. These discipline departments are further divided into various areas of responsibilities including plant systems, special programs and studies and qualification engineering.
The Nuclear and Environmental Engineering Division provides support services in the areas of quality assurance, facility licensing, performance engineering, probabilistic risk assessment, and reactor engineering.
Within the Nuclear Operations Division each Millstone unit has its own dedicated engineering department to provide on-site technical support.
These departments are structured as follows.
Unit 1 The Engineering Department which provides technical support to the Unit 1 Superintendent, is headed by a supervisor with three assistant engineering supervisors. Within these three subsections the plant engineering staff is responsible for providing on-site engineering support to the plant.
The department presently has a total engineering staff of 21 with one
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l vacancy. The engineering department interfaces extensively with the NUSCO engineering staff in the resolution of technical issues.
Unit 2 The Engineering Department which provides technical support to the Unit 2 Superintendent, is headed by.a supervisor with four :ssistant engineering supervisors. The engineering management consists of personnel with wide ranging backgrounds including the supervisors holding SR0 licenses. As is the case with the Unit 1 engineering staff, extensive interfacing with NUSCO is evident.
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Conclusions The on-site engineering departments are staffed to interact with NUSCO engineering departments to provide support to the operation of both Millstone units. NUSCO engineers' involvement in the development of major plant modifications provides additional support in the resolution
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of problems and in the generation of the. plant design changes.. The engineering departments are adequately staffed with experienced personnel to provide the needed support to plant operations.
4.0 Quality Assurance (QA) Involvement in Technical Support
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The quality assurance area was reviewed to evaluate QA involvement in l'
assessing the quality of the Engineering Divisions.
The Quality Services Department (QSD) supports the Nuclear Engineering and Operations (NEO)
divisions at Northeast Utilities to assure that the design, procurement, modification, testing, and operation of the Millstone units are performed in compliance with regulatory requirements.
It is responsible for developing and. implementing planned audits, inspections, in process
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verifications, and surveillance to verify compliance with the licensee's QA~ program.
The inspectors reviewed QSD procedure QSD-2.02 " Performance, Reporting, and Follow-up of Audits." The procedure describes the functions and requirements of the QSD for audits scheduled to' cover 12 month periods.
The inspectors reviewed the following audits and surveillance which the QSD has performed in the engineering area.
Audits:
A-30123 May 19 through August 20, 1987 A-30131 March 28 through August 4,1988 Surveillance:
SS-113 Review of PDCR 2-36-87 AS-227 Review of PDCR 2-30-88 AS-228 Review of PDCR 2-11-88 AS-229 Review of PDCR 2-27-88 QSC 89-014 Review of MP2 outage activities on 2/25/89 l
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During the review of the above audits and surveillance the inspectors
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interviewed QSD personnel responsible for performing such activities.
The licensee has a program to address and resolve audit and surveillance findings. The findings and subsequent resolutions between QSD and the engineering organizations were reviewed and determined to be adequate.
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5.0 Engineering and Technical Support In assessing the quality of work done in the engineering department,
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Nonconformance Reports, Plant Design Change Records, reporting proce-dures, and responses to 10 CFR 21 notifications were reviewed.
In addition, the licensee's program for complying with NRC reporting require-ments was reviewed. The details of the review are discussed below.
5.1 Nonconformance Reports (NCR)
NCRs are processed by the licensee utilizing their Procedure NEO 3.05
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- Nonconformance Reports.
To assess the adequacy of licensee NCR procedures the inspectors randomly selected the following Nonconfor-mance Reports for a detailed review.
Unit 1 NCR 188-025 Electrical testing 4160 V breaker NCR 188-026 Diesel generator speed switch NCR 188-045 LPCI 'A' pump term, box / motor body gasket NCR 188-067 HSS-073 (Hydraulic snubber)
Unit 2 NCR 289-036 Coating inspection NCR 288-094 Leak sealant repair NCR 288-012 RWST level loop blown fuse NCR 288-024 ESAS voltage actuation circuit NCR 288-032 ESAS fuse holder replacement Review of the above NCRs and interviews with cognizant licensee personnel indicated that the NCRs were adequately evaluated for proper technical resolution.
5.2 Plant Design Changes Engineering for plant modifications is performed by onsite engineering or by a combination of onsite and corporate engineering personnel.
These modifications are processed as Plant Design Change Records (PDCRs). Nuclear Engineering and Operations Procedure NE0 3.03 - Preparation, Review and Disposition of Plant Design Change Records describes the process for making plant design changes.
It includes the detailed procedures for the initiation, preparation, reviews, approvals, safety analyses, implementation, acceptance and completion of the PDCRs.
Sub-tier procedures cited in Procedure NEO 3.03 establish the detailed requirements for safety evaluations, administrative controls, design verifications, seismic qualification reviews, environmental qualification reviews and 10 CFR 50.59 reviews.
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In accordance.-with procedure NE0 3.03 the PDCR process is conducted as follows:
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Upon approval of the PDCR for implementation it is, assigned a Plant Authorization (PA) number j
A decision is made by the site superintendent as to whether the engineering will be performed by site engineering or.by. site engineering assisted by corporate engineering. A lead
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discipline and lead project engineer are assigned to the project.
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.The lead' project engineer will perform and coordinate design.
and upon completion, the design will be forwarded to PORC/SORC for. approvals.
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The approved PDCR will be issued by the Plant Superintendent i
for construction
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The lead project. engineer continues to follow the PDCR through construction and preoares final, as-built documents.
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'The lead project engineer will ensure that all pre-operational i
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The following PDCRs were reviewed to verify the implementation of the.PDCR procedures:
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PDCR 1-25-88 - Millsto.ne Unit 1 Gas Turbine Governor Replacement l
PDCR 1-28-88 - Millstone Unit 1 Instrument and Service Air
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Modification Findings:
The PDCRs reviewed were found to be well organized, complete and in accordance with the procedures.
These design change packages l
included a clear definition of the scope of the change, the reasons
for the change, and documentation with appropriate approvals for each phase of the PDCR. The PDCRs packages included design check-off/ sign off/ approval sheets which were executed up to the current phase of each project.
Both of these PDCRs required exten-sive on-site and corporate engineering effort.
Evidence of good
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communications between these two organizations was readily apparent i
in the work documents and in the visibility of both on-site and corporate personnel on the job.
No deficiencies were observed during this inspection of the licensee's engineering activity in conducting
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the PDCR process.
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5.3. Reporting Procedures.
This inspection was made to assess the adequacy of the engineering organization involvement in NRC reporting requirements.in accordance with:10 CFR 21,'10 CFR.50.72, 10 CFR 50.73, and 10 CFR.
50.9. 'A review was made of the licensee's Nuclear Engineering and Operations procedures for accomplishing these reporting requirements.
Procedures reviewed were the following:
_NEO 2.01 - Implementation of 10 CFR 21 Reporting of Defects and
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Non Compliance j
o NEO 2.25 - Identification and Implementation of NRC. Reporting
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t Requirements (10 CFR 50.72,10 CFR 50.73 and 10 CFR 50.9)
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responsibilities of' engineering personnel in accomplishing the
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-reporting. requirements.
These procedures establish time frames for the accomplishment of evaluations of deportability to ensure the timeliness of reporting.
In order to assure top management, involvement.in.the. timeliness of evaluations.and reporting, a monthly status report listing all deportability evaluations is issued with distribution to all senior management.
'A review of the status report for the current and last month did not reveal any past due eval uati on s'.
The inspectors reviewed the following LERs to evaluate the implementation of the above procedures.
LER 88-011-00 11/22/88 Automatic actuation of an
ESF system LER 88-010-00 10/20/88 Containment atmosphere
gaseous radiation monitor switch alignment LER 88-006-01 3/27/89 Combined bypass leakage rate
exceeded No deficiencies were identified.
5.4 Response to 10 CFR 21 Notifications During this inspection, the inspectors reviewed the adequacy of the licensee's response in addressing a 10 CFR 21 notification by Limitorque regarding Limitorque valve operator torque switches.
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The. engineering and maintenance' personnel for Unit I have completed-a preliminary review of all Limitorque operators with serial numbers which coJ1d be subject to the problems identified in the 10 CFR 21 notice.
During the upcoming outage, the licensee will complete a
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further review to ensure that they have thoroughly addressed the notice. The licensee also plans to review all Limitorque operators
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regardless of their seria1' numbers. These reviews with appropriate
' replacement actions should adequately address this notification.
During the 1989 refueling outage, Unit 2 implemented a program to replace the subject Limitorque torque switches' regardless of their-serial number.
The unit has completed this task thereby adequately addressing the 10 CFR 21 notification, No deficiencies were identified.
6.0 Engineering Support Training 6.1 Training-Programs The licensee's training program was inspected in order to evaluate its adequacy in training engineering support personnel. Training of the engineering support personnel is included under the licensee's Technical Staff and Manager (TSM) Training program.
Training require-ments are estab_11shed by Nuclear Engineering and Operations Procedure NE0 2.26.
raining is conducted by the Nuclear Training Department whose director' reports directly to the Vice President of Nuclear and Environmental Engineering. The training department-is organized into six divisions including the Technical Training and General Nuclear Training Divisions which conduct most of the in-house training of the engineering support personnel. These two training divisions have an assigned staff of approximately 50 instructors.
6.2 Indoctrination Training Engineering support training begins with an. indoctrination program for new employees.
This training includes classroom instruction in the following topics.
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Nuclear safety Emergency plan
Fire protection
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Security
Safety 1.
- Chemical hazards
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The course outlines for several-of these courses were reviewed for content-and were considered adequate.
6.3 Initial Training Program
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Following the indoctrination-program, engineering personnel are-l required to' complete an " Initial Training Program" as applicable to I
their particular area of engineering.. This program is described in the General Nuclear Training manual.
It includes course work in the categories of Plant Fundamentals, Plant Modifications, Plant Outages, Plant Components and Plant Systems.
Each-of these categories is broken down into subcategories i.e., Plant Modifications /0utages includes such courses as:
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Non Conformance Reports,
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Root Cause Analyses, a
PDCR Workshop,
. Safety Evaluations,
Work Orders,
Work Control Procedures, and
ASME Codes.
- The course outlines-for several of these courses were reviewed and considered adequate.
Personnel are required by their: managers to complete all of the course. work applicable to their positions as a part of their qualification training, 6.4 Continued (On-Going) Training Support engineering personnel are required to complete training on an on going basis. This program includes such general topics as:
General employee training,
Plant and industry events, and
Refresher training courses.
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This training includes-specialized training within the engineering groups in areas of specific interest and need.
The Technical Staff and Managers Training Program schedule of courses for the balance of the year was reviewed.
It includes 35 courses with multiple scheduled dates for each course.
Engineering
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managers schedule their employees individually to attend these courses based upon need and employee time availability.
Besides the-training conducted at the. licensee's facility, licensee personnel are sent for specialized training at other locations.
Interviews were conducted with several corporate engineers who attended technical courses / seminars during the past year.
During these' interviews, several'of the licensee personnel were identified who participate through various utility groups and professional societies in the application. and development of industry standards for nuclear ~ appli-cations. A review of the. Nuclear Engineering and Operations Group external professional' society' committee assignments showed that during 1988, 93 personnel assignments were made in these areas.
Personnel in these assignments functioned at various levels from member up to_ chairman of the particular group and expended a total of 467 days on these assignments.
No' deficiencies were observed.
6.5 Unit l' Training On site engineering implementation of the TSM training program was reviewed in detai_1 for Unit 1 engineering employees by a review of their qualification and training record files. This review included
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a determination of the status of each of the engineering employees completion of the TSM - Initial Program.
The 23 courses required have a' total class length of 193 hours0.00223 days <br />0.0536 hours <br />3.191138e-4 weeks <br />7.34365e-5 months <br />. Most of the employees had either completed these courses or had been validated (based upon previous 1 training and experience) as not requiring the' course. The review included a determination of course work completed and-
-scheduled for each employee on the TSM continuing training program.
During the first quarter of 1989, the engineering employees had completed an average of more than two courses per employee. The inspector also determined that Unit 1 engineering personnel during their weekly meeting discuss industry events, etc. and their
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relevance to Millstone as a part of their ongoing training effort.
No deficiencies were observed.
6.6 Engineering Training Record.
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The Employee Qualifications and Training Record files for several corporate engineering employees were reviewed to confirm training completed and their current qualifications.
These files included records of:
Validation of previous training experience,
Indoctrination training,
Initial training,
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Completion of nuclear engineering mandated courses,
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-Refresher training,
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Read and sign procedures training (including the Code of
Federal Regulations), and
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Growth and enhancement training.
.No deficiencies were observed.
'6.7 Conclusions The licensee recognizes the need for an effective training program and has addressed this need by the establishment of a well-staffed training department with the resources and the authority to conduct an effective program.
Implementation of this program is evidenced by the training and qualification records of personnel. The effective-ness of the program was evident in the interviews conducted with select personnel-and by. a : review of engineering documentation prepared by them.
The training provided to engineering support personnel was considered adequate.
.7.0' Management Meetings
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Licensee management was informed of the scope and purpose of the.
inspection at-the' entrance interview on' April 17, 1989. The findings of.
the inspection were discussed with licensee representatives during the course of the inspection and presented to licensee management at the April 21,.'1989 exit interview (see paragraph I for attendees).
At no time-during the inspection was written material provided to the licensee by the inspectors.
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Attachment A Procedures Reviewed:
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No.
Procedure Title 1.01 Organization of the Nuclear Engineering and Operations Group-2.01 Implementation of the 10 CFR 21:
Reporting of Defects and Nonc.ompliances
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2.02 Performance, Reporting and Follow-up of Audits
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2.08 Management Review of the Northeast Utilities Quality Assurance Program 2.25 Identification and Implementation of NRC Reporting Requirements (10 CFR 50.72,10 CFR 50.73 and 10 CFR 50.9)
2.26 Technical Staff and Manager Training Program 3.03 Preparation, Review, and Disposition of. Plant Design Change Records (PDCRs)
3.04 Project Assignments 3.05 Nonconformance Reports 3.12 Safety Evaluations l
4.01 Communications with the Nuclear Regulatory Commission 5.11 Design Change Notices for Design Documents i
l 7.03 Preoperational Testing of Plant Modifications g
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