IR 05000412/1987022
| ML20209J294 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/22/1987 |
| From: | Duncan A, Eapen P, Hunter J, Napuda G, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20209J268 | List: |
| References | |
| 50-412-87-22, NUDOCS 8705040256 | |
| Download: ML20209J294 (20) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-412/87-22 Docket No.
50-412 License No. CPPR-105 Licensee: Duquesne Light Company 1 0xford Center 301 Grant Street Pittsburgh, Pennsylvania 15279 Facility.Name: Beaver Valley Power Station, Unit 2 Inspection At: Shippingport, Pennsylvania Inspection Conducted: March 16-20, 1987
/87 Inspectors: (G.thapuda, Lead Reactor Engineer, DRS e
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@ K-b 4!4 A.h(7 Approved by:
Dr. P.K. Eapen, Chief, Quality Assurance
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Section, Operations Branch, DRS Inspection Summary:
Routine announced inspection on March 16-20, 1987 (Report No. 50-412/87-22)
Areas Inspected:
The licensee's programs for Maintenance, Design Change and Modifications, Test and Experiment Control, Measuring and Test Equipment Control, Procurement Control, Offsite Review Committee, and Operational
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Staffing.
Results: No violations or deviations were identified.
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DETAILS 1.0 Persons Contacted Duquesne Light Company (DLCO)
- D. Claridge, Compliance Engineer
- A. Cooper, Senior Engineer, SVG A. Dulick, Supervisor, Chemistry
- G. Ewing, Manager, QA
- J. Godleski, Senior Test Engineer
- R. Hansen, Site Maintenance Director
- J. Kasunick, Maintenance Director SVG J. Kosman, Radiological Control Manager J. Kowalski, Chairman, Offsite Review Committee K. Krayvo, Supervisor, Unit 2 M&TE N. Lancy, Plant Manager
- A. Lerzak, Supervisor, BV-2 Procedures
- K. Lowrie, Supervisor, Procurement
- R. Martin, Manager, Regulatory Affairs T. McGhee, Onsite Safety Committee Chairman B. Mills, Maintenance Procedure Engineer T. Noonan, Superintendent, Operations and Maintenance, SVG
- M. Pergar, Supervisor, Operations QC
- L. Rabenau, Lead Compliance Engineer
- D. Roman, Supervisor, QA Maintenance
- C. Sabol, Senior QA Specialist C. Schultz, Procedure Review Committee Chairman
- R. Swiderski, Manager, Startup
- T. Walsh, NERU Transition Coordinator, ECI D. Weakland, Supervisor, ISI Services T. Zyra, Director, Test and Plant Performance
United States Nuclear Regulatory Commission (USNRC)
A. Asars, Resident Inspector J. Beall, Senior Resident Inspector, Unit 2
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- L. Prividy, Resident Inspector
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W. Troskoski, Senior Resident Inspector, Unit 1 l
- denotes those present at the exit meeting held March 20, 1987 The inspectors also contacted other administrative, engineering, QA/QC, i
operations, startup and technical personnel during the conduct of the inspection.
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2.0 General The inspection was performed to assess the adequacy of licensee's programs for Maintenance, Design Changes and Modifications, Test and Experiment Control, Measuring and Test Equipment Control, Procurement Control, and the Offsite Review Committee to support the operations phase. Operational staff member qualifications were also reviewed to ensure that the required level of expertise and experience was present to support operations.
3.0 Design Changes and Modifications Program 3.1 Reference / Requirements 10 CFR 50, Appendix B, Criterion III 10 CFR 50.59 Beaver Valley Unit 2 proposed Technical Specifications, Section 6 Beaver Valley Unit 2 Final Safety Analysis Report, Section 17 ANSI N18.7 - 1976, "QA for the Operations Phase of Nuclear Power Plants".
Regulatory Guide ~1.33, Revision 2, "QA Program Requirements (Operation)"
ANSI N45.2.11-1974, "QA Requirements for the Design of Nuclear Power Plants".
Regulatory Guide 1.64, Revision 2, "QA Requirements for the Design of Nuclear Power Plants".
3.2 Program Review
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The basic requirements for controlling design changes and modifica-tions are described in the documents listed above.
The inspector reviewed the licensee's program and procedures (listed in Attachment A) that control design changes and modifications and verified that:
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A formal method exists to initiate, review, evaluate and approve design changes prior to implementation; Responsibilities have been assigned to insure safety evaluations
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are performed in accordance with 10 CFR 50.59 to assure the change does not involve an unreviewed safety question, and then reported to the NRC; Procedural controls exist and responsibilities are delineated to
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assure that applicable fire protection / prevention requirements
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are included in the design process and procurement documents;
Organizational design responsibilities and interfaces have been
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delineated;
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Review of the design change is commensurate with the original design and the responsibility for final approval of design documents exist; Responsibilities and procedural controls exist for identifying,
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reviewing and approving design inputs; Procedural controls exist for design analysis, drawings,
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specifications, installation instructions, tests and other procedures;
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Methods, procedures and responsibilities exist for performing independent design verifications; Administrative Controls exist for design document control
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including controls for review, approval, release, distribution, storage, retrieval, disposition of obsolete documents and updating plant procedures, drawings and training department materials; Controls require that post modification tests be performed and
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results evaluated; A method exists and responsibilities are delineated to correct
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nonconformances and deficiencies; Control of special processes is addressed;
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Responsibilities are delineated to assure QA audits are
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performed to verify compliance with the design control program;
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QA responsibilities exist to review the design documentation,
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witness and inspect modification activities and track corrective action; Controls require that temporary modifications are reviewed and
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approved in accordance with 50.59 and the Technical Specifications; Controls require the use of detailed procedures or approved
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installation instructions to perform temporary modifications; Controls require keeping a status and performing a periodic
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review of temporary modifications, and; Controls require independent verification for installation and
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removal of temporary modifications and functional testing after remova *
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3.3 Program Implementation The Duquesne Light Company (DLC) Nuclear Engineering and Records Unit (NERU)
assumes overall responsibility for design changes and modification control during the operations phase of BVPS Unit 2.
Modifications during the operations phase will be controlled in accordance with the licensee's draft SAP-Chapter 45, Design Change
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Control, which defines the responsibilities, requirements and l
guidelines for initiating, controlling and documenting design changes at BVPS. The licensee plans to utilize Stone and Webster Engineering Corporation (SWEC) for design changes when necessary.
Requests for station modifications will be processed as Station Modification Requests (SMRs) by the NERU.
The required Design Change Package (DCP) engineering responsibilities may be performed by the NERU or by SWEC, depending upon the scope and schedule requirements of the design change.
Engineering and design activities executed by SWEC will be implemented in accordance with four new and existing project specific procedures (2 BVMs) and existing Engineering Assurance Procedures (EAPs) to provide a program commensurate with the DLC Operations Quality Assurance program requirements, The draft SWEC project procedure 2BVM-186 and the draft NERU procedure UAP 2.2 establish the necessary organizational interfaces for implementing the design changes and modifications program.
The licensee's NERU consists of the Nuclear Engineering Department (NED), the Management Services Department (MSD) and the Engineering
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Information Services Department (EISD)
and is responsible for providing engineering and records support for BVPS.
The NERU currently utilizes Nuclear Engineering Department Internal Instructions (NEDIIs), Nuclear Engineering Management Procedures (NEMPs) and Nuclear Engineering and Construction Unit Management Procedures (NECUMPs) to implement the design change and modification program.
The NERU is in the process of incorporating the afore-mentioned procedures into NERU Unit Administrative Procedures (UAPs)
which are being phased into implementation as they are approved.
The engineering and design activities performed by SWEC will be governed by 2BVM-87A,
" Management Plan for Quality for the Operational Phase of BVPS, Unit 2", which was approved by the DLC QA Manager and the NERU General Manager.
Project procedure 2BVM-186,
"SWEC Interface with the DLC Operations Design Change Control Program", establishes the requirements for interfaces with DLC and is applicable to all SWEC design activities when SWEC acts as the Outside Design Organization.
Project procedures 2BVM-185," 10 CFR 50.59 Safety Evaluations" and 2BVM-187, " Technical Specification Change Requests", were also written to supplement the existing project procedures and Engineering Assurance Procedure.
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SAP-Chapter 45 requires that the Quality Assurance Unit (QAU) review installation documents to identify appropriate QC holdpoints and develop an inspection plan for the DCP.
The Manager of the QAU shall ensure that inspections for the DCPs are carried out in accordance with the inspection plan and that the resolutions of nonconformances are adequate. The QAU also performs periodic audits of the Engineering Unit to verify compliance with the design control program.
The licensee's control over temporary modifications will be accom-plished through the implementation of SAP-Chapter 36, " Temporary Modifications". The current revision is only applicable to Unit I as written, however, the licensee plans to implement the procedure for both units.
3.4 Findings and Conclusions The inspector determined that the licensee's program for handling design changes and modifications consisting of existing NEDII's, NEMP's, NECUMP's and UAP's and the draft SAP 45 and draft UAP's adequately addressed the attributes listed above in the program review section. The inspector also determined that the SWEC program consisting of approved and draft project procedures and Engineering Assurance Procedures also adequately addressed the attributes listed above.
The licensee's program for controlling temporary modifications had adequate administrative controls to insure that the attributes listed above are met.
The licensee is currently reviewing procedures which may be used for temporary modifications to ensure that the required independent verification steps are incorporated.
Licensee management has initiated a program to incorporate the existing engineering unit procedures into a more workable manual of Unit Administrative Procedures.
This program will provide a single accessible reference for the staff.
The management has also decided to provide each individual with a copy of the new manual.
The licensee has added approximately twenty positions in the Nuclear Engineering Department (NED) to staff up for two unit operation at BVPS.
Eight positions have tentatively been filled pending final approval by management.
The licensee is currently reviewing personnel qualifications to fill the remaining twelve positions. The budgeted level of staffing has been sufficiently increased and expanded to perform engineering activities for both units with the addition of a Design Basis Supervisor, a Configuration Control Supervisor, a
Materials, Codes and Standards Supervisor, an Electrical and Control Engineering Director and various other engineering position.
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The NERU maintains training records of personnel including required reading checklists for various engineering, administrative and Quality Assurance procedures, 10 CFR and various Regulatory Guides.
Supplemental' Nuclear Engineering Department management, technical and professional development training classes, seminars and lectures are provided to the employees on an as need basis. The training history of each employee is tracked on a computer. To insure personnel are aware of new revisions to engineering procedures, the NED routes a copy of the procedure to each section member for review and signature i
to signify completion of the review.
The licensee plans to hold extensive training sessions to familiarize NERU personnel with the new manual of VAP's upon issuance.
The inspector reviewed the training records and qualifications for selected personnel and determined that the training and qualification were commensurate with the duties to be performed with the exception of one individual.
This individual does not perform safety related design activities and would not be required to complete the entire required reading checklist under the licensee's new training procedures. Subsequent to the inspector identifying the problem, the individual began completing the required reading checklist. The lack of training documentation in this instance was considered an isolated case with no safety significance.
Based on the review of the licensee's programs and draft procedures, the inspector determined that adequate measures have been established to control the design change and modification program in accordance with the NRC requirements and licensee commitments.
4.0 Tests and Experiments 4.1 Program Review In accordance with 10 CFR 50.59, the holder of an operating license may conduct tests and experiments not described in the Final Safety Analysis Report (FSAR) provided such tests and experiments do not involve a change to the technical specifications or an unreviewed safety question. The insp ?ctor reviewed the licensee's program and procedures (listed in Attachment A), that control such tests and experiments, and verified tha
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A formal method exists to process requests or proposals for
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conducting plant tests and experiments involving safety related components, systems or structures or modes of operation different from those described in the FSAR; Provisions assure that all tests and experiments are conducted
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in accordance with approved written procedures;
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Responsibilities are assigned for review and approval of test
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and experiment procedures; Responsibilities are assigned to assure that the controls
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identified above are implemented;
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A formal system is established to assure that all proposed tests and experiments are reviewed to determine if they are in the FSAR;
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Responsibilities are assigned to assure that a written safety evaluation pursuant to 10 CFR 50.59 is performed for each test and experiment not described in the FSAR to assure that it does not involve unreviewed safety questions or a change in the Technical Specifications; and
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Responsibilities are assigned to assure that all tests and experiments pursuant to 10 CFR 50.59 are formally reported to the NRC in a timely manner.
4.2 Implementation The licensee's Station Administrative Procedures (SAPS) establish the administrative programs that define the methods and responsibilities for conducting plant activities, in accordance with the Technical Specifications, Regulatory Guides and applicable industry standards.
They provide the basic procedural requirements that apply to all work activities on all equipment, components and systems at Beaver Valley Power Station (BVPS), Unit 2.
The BVPS Operating Manual provides supplemental guidance and control over various operations and support activities including temporary operating procedures to conduct special tests and experiments. Additionally, the Testing and Plant Performance (TPP) Administrative Procedures provide the necessary control for writing test procedures and ensuring that special test procedures receive the appropriate level of review and approval.
The Onsite Safety Committee (OSC) will perform a review of all proposed tests and experiments that affect nuclear safety. A safety evaluation required by 10 CFR 50.59 will be performed and then reviewed by the OSC for each test or experiment not described in the FSAR to assure that it does not involve an unreviewed safety question or a change in the Technical Specifications. Tests and experiments performed pursuant to 10 CFR 50.59 will be reported to the NRC in accordance with sap 38, Reporting Requirements.
4.3 Findings and Conclusions Licensee management has established the required controls to ensure that tests and experiments not described in the FSAR are performed pursuant to the requirements of 10 CFR 50.59.
The effectiveness of
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9 the OSC was reviewed in a previous inspection and it was determined that they were adequately staffed and qualified to perform their-review duties.
Based on the review of the licensee's program and procedures, the inspector determined that adequate measures have been established to control the conduct of tests and experiments not listcd in the FSAR in accordance with the NRC requirements and licensee commitments.
5.0 Procurement Program 5.1 Program Review The licensee's procurement program, for Unit 2 was reviewed to determine whether administrative controls were established for:
The identification of items purchased, identification of tests
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and/or special instructions; technical requirements and documentation to certify the item; assurance that the contractor / supplier has implemented a QA program consistent with 10 CFR 50, Appendix B; and where deemed appropriate by the licensee, access to the supplier's plant or records for auditing purposes; Initiation of procurement documents; review and approval of
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specifications, differing from the original design documents; review and approval of procurements, including changes thereto; and the designation of quality classification of procedure items; and, Assignment of the evaluation and approval of bidders / suppliers,
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including review / update of the listing of approved suppliers; providing for rights of access to suppliers facilities and records; and maintenance of records of suppliers qualifications and audits.
5.2 Implementation The Nuclear Engineering and Records Unit (NERU) has established procedures for purchasing new equipment required by design changes during operation.
The group is responsible for both Units 1 and 2 and has been implementing the program adequately for Unit 1.
The staffing level is adequate to handle the projected work load.
NERU has updated three of the procedures needed to combine Unit 2 work with Unit l's.
The three new procedures and the four interim procedures were reviewed.
The seven procedures (NERU UAP #3.1 -3.7)
adequately covered all areas of administrative control discussed in Section 1 abov *
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The Start Up Group (SUG) has established a program with procedures for procurement of spare and replacement parts.
This program has been fully implemented and is functioning satisfactorily.
All QA program requirements are being met.
The SVG group is presently developing a " Dedication Program" that will enable DLCs to buy preengineered equipment from a non qualified supplier.
The SUG's Stock Item Request (SIR) system for spare parts procurement has been adequately implemented with an established trail of QA documentation. The required inputs include identification _ of items purchased, special instructions, technical -and QA documentation, storage and shelf life requirements, and quality classification of items to be purchased.
The same system is used by the Nuclear Operations Unit to track the storage location and number of parts on hand.
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The Nuclear Operatir>ns Unit's receipt inspection and shelf life programs were reviewed.
The receipt inspection program has been developed and satisfactorily implemented.
The program is used for both Unit 1 and 2.
A shelf life program is in use but is undergoing revision to allow for easier identification and tracking of shelf life items.
A study has been completed to provide engineering justification of the shelf life used.
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Operations QA was reviewed for its vendor qualification, audit and surveillance program. The program has been developed and is being
satisfactorily implemented.
The unit is performing its audits and surveillance functions in a scheduled and timely manner. The unit is also maintaining and updating the
" Qualified Suppliers List" according to procedures.
The surveillance function is being performed by qualified contractors.
Operations QC was reviewed for its receipt inspection and review of purchase orders from both the SUG and NERU. The receipt inspection program has been developed and is being satisfactorily implemented.
The receipt inspectors cover both Units 1 and 2.
The procedures for review of purchase orders have been developed and are being used for spare part orders from the SVG group.
The QC receipt inspectors verify that all required QA documentation, identification and markings, protective covers and seals, desiccants and inert gas blankets, cleanliness, workmanship, and storage level requirements that were requested in the purchase order have been met.
Receipt inspection logs and logs of nonconforming items and their disposition are kept as required by procedures.
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5.3 Findings
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Based on the results of the ' reviews performed., the procurement program is in compliance with FSAR commitments and is ready to support plant
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No violations were identified.
6.0 Maintenance 6.1 program Review The basic requirements for a corrective and preventive maintenance program are described in the documents listed in Attachment A.
Procedures (listed in Attachment A) were reviewed to verify the administrative controls included the following:
preventive and corrective maintenance schedules / procedures have
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been established.
written procedures have been established for initiating requests
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for routine and emergency maintenance.
work control procedures have been established for special
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processes, fire protection, radiation protection, cleanliness, and housekeeping.
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procedures and responsibilities have been established for
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equipment control.
provisions have been established for the coordination of
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maintenance activities and interface controls among
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participating organizations.
personnel training program established for performing main
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tenance activities.
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adequate staff available to perform maintenance activities.
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criteria and responsibilities have been established to identify
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safety and non-safety-related maintenance activities.
criteria and responsibilities have been established for
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designating hold points and for performing work inspections.
criteria and responsibilities have been established for review
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l and approval of all maintenance requests.
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criteria and responsibilities have been established for
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verifying work classification and the use of industry accepted procedures.
administrative controls have been established to prepare,
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assemble, review and store the maintenance records.
6.2 Implementation Required preventive maintenance has been determined and entered into a computerized data base.
Preventive maintenance tasks are automatically printed out a month prior to the due date so as to provide sufficient time for planning, processing and scheduling the work. Postpened maintenance and tasks are tracked and their total can be readily determined by a " sort search" of the data base. The Maintenance Work Request (MWR) process is not yet an "on-line" computerized system but the licensee's objective is to also automate this process.
Maintenance and Process Engineers have and intend to continue reviewing technical information such as modification packages to develop preventive maintenance needs.
The Planning and Scheduling group then enters this preventive maintenance scheduling into the data base.
One positive feature of this data base is a work card printout that lists the applicable procedures.
This card is returned to the Planning and Scheduling group when work is completed.
6.3 Findings All the Station Administrative Procedures (SAPS) applicable to maintenance have been issued. The Nuclear Operations Unit Procedures (NOUPs) for Unit 1 maintenance are currently being reviewed for use at Unit 2.
Planning and scheduling procedures are also under a similar suitability review.
It was concluded that the administration and control of the maintenance program, staffing levels, and personnel experience and qualifications were adequate to support Unit 2 operations.
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No violations were identified.
7.0 Plant Surveillance Program 7.1 Program Review 10 CFR 50, Appendix B, Criterion XI and 10 CFR 50.55a requires that the licensee establish, implement and maintain a test program including operational tests during nuclear power plant operation.
The proposed Technical Specification Section 4 requires surveillances and Section 6.8 requires written procedures be established, implemented and maintained for surveillance and test activities of safety related equipment.
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l The licensee is committeo i Regulatory Guide (RG) 1.33, Revision 2, l
" Quality Assurance Program Requirements', and ANSI N18.7-1976/ANS l
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" Administrative Controls and Quality Assurance for the
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Operational Phase of Nuclear Power Plants".
The documented Plant Surveillance Program is described in FSAR Chapter 17 and is to be implemented through the procedures listed in Attachment A.
The inspector reviewed the applicable documents listed in Attachment A and determined that the established controls for the Plant Surveil-lance Program addressed the following:
Responsibilities for establishing and implementing a Plant
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Surveillance Program.
A master schedule that includes frequency, plant group
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responsibilities and status.
Procedures for preparation, conduct of tests, and reporting of
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the results Review and evaluation of test results and implementation of
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corrective and preventive actions for identified deficiencies.
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7.2 Program Implementation The inspector randomly selected 20 surveillance requirements from the Technical Specifications (TS).
Each of these TS surveillance was covered by a specific procedure with the exception of TS surveillance requirement for the structural integrity of ASME Code Class 1, 2, and 3 components.
This surveillance is being developed and will be completed after the issuance of the operating license.
The surveillance procedures reviewed were mainly Maintenance Surveillance Procedures (MSPs) and Operating Surveillance Tests (OSTs).
The procedures were current and were consistent with the proposed TS requirements for setpoints, frequency, and operating parameters. QC hold points were also established as appropriate. All the completed procedures were properly filled out, signed and conducted on i
schedule.
The personnel involved in surveillance test programs were l
knowledgeable of the technical and procedural requirements.
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l No violations were identified.
The licensee's plant surveillance l
programs are in accordance with NRC reoutrements and licensee commitments.
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8.0 Measurement and Test Equipment (M&TE)
8.1 Program Review 10 CFR 50, Appendix B,
Criterion XII requires the licensee to establish a program to control M&TE. The licensee, as described in FSAR Chapters 13 and 17, is committed to establish an M&TE program that is consistent with Regulatory Guide (RG) 1.33, Revision 2,
" Quality Assurance Program Requirements", and ANSI N18.7-1976/ANS 3.2,
" Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants." The licensee implements this program using applicable procedures listed in Attachement A.
The inspector reviewed the applicable documents listed in Attachment A and determined that the established controls for the M&TE Program addressed the following:
Responsibilities for establishing and implementing an M&TE
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Program.
Development of an equipment inventory list including addition of
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new equipment.
A recall system for the M&TE.
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Out of calibration controls and traceability of the M&TE to
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previous uses.
8.2 Program Implementation The inspector randomly selected M&TE that was used in the conduct of Maintenance Surveillance Procedures (MSPs) and Preventive Maintenance Procedures (PMPs). The calibration status, storage, use, return and the records of the M&TE were reviewed and found to be in compliance with the procedures. The personnel interviewed were knowledgeable of the technical and procedural requirements.
8.3 Findings Management is converting the Startup M&TE Laboratory into the Unit 2 Calibration Facility.
The Measured Maintenance Data (MMD) is the official record of all calibration data.
The Unit 2 Calibration Facility staff consists of a supervisor (former I&C foreman) and eight (8) qualified contractor technicians.
The Duquesne Light Company (OLC) Manchester Standards Laboratory, provides additional support on an as-needed basis.
No violations were identified.
The licensee's M&TE program is in accordance with NRC requirements and licensee commitments.
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9.0 Onsite Organization and Staffing 9.1 Program Review and Personnel Qualifications Organizational charts, plans and procedures were reviewed and discussed with licensee personnel to verify the following.
The onsite organizational structure was as described in the
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proposed facility Technical Specifications (TS) and Final Safety Analysis Report (FSAR).
Personnel qualification levels were in cunformance with appli-
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cable codes and standards described in the proposed TS and FSAR (including Amendment 15).
Lines of authority and responsibility were consistent with the
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proposed TS and FSAR.
Changes or differences were or are to be reported to the NRC as
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required by the proposed TS.
Resumes and training files were reviewed for incumbents in the following positions and interviews were held with selected personnel to verify qualifications and experience conformed to that required by the proposed TS and FSAR.
Principle Operating Staff
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First Level Supervisors
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Technical Engineering Staff
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Plant Craftsmen (e.g. mechanical, electricians)
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Plant Operators
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NDE Examiners
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Support Technicians (e.g., Health Physics, Chemistry, Instrument
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and Control, Radwaste)
9.2 Staffing and Organization Managers of Planning and Outage Management, Technical Services, Radiological Control, and the plant report to a Senior Manager Nuclear Operations.
Managers of Nuclear Construction, Nuclear Training, Administrative Services, Nuclear Safety and a General Manager Nuclear Engineering and Records report to the Vice President Nuclear.
The Senior Manager Nuclear Operations, Vice President Nuclear and Manager Quality Assurance report to the Senior Vice President Nuclear Group who reports directly to the President and Chief Executive Officer of Duquesne Light Company.
Reporting to the Plant Manager are the following:
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for each unit) each with a staff of Nuclear Shift Supervisors, Nuclear Shift Operating ~ Foremen, Nuclear Control ' Operators
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(licensed) and Nuclear Operato,rs'(non-licensed).
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A Maintenance Director; two Mechanical Maintenance Supervisors
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and an Electrical Maintenance Supervisor.
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An I&C Director; I&C Maintenance Supervisor; and an I&C
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Calibration Supervisor
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Nuclear Operating Supervisor Operations Support; and Radwaste,
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and Operations Coordinators.
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A Testing and Plant Performance Director.
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Each of the above groups was staffed appropriately with electricians, engineers, foremen, mechanics, technicians and other workers.
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a The personnel *ecords of each incumbent inlthe positions listed in
FSAR Table 13.1-3 were reviewed and their qualifications compared to the requirements of ANSI N18.1-1971, the FSAR. and proposed Technical Specifications.
The qualifications of supervisors and management g listed above, two foremen, two electricians, two mechanics, two technicians, and two receiving inspectors were also reviewed.
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Actual staffing levels were reviewed. The licensee added 50-70% more non-licensed workers (i.e. mechanics, technicians, electricians) and g approximately 40% more supervisors to support Unit 2 operation.
9.3 Findings and Conclusions Management and supervisory positions have been filled except in a few
instances where candidates are still under review (e.g. Nuclear Operations Supervisor Operations Support).
The House and Yard laborer group is the only one that is not fully staffed. All other groups have essentially completed their staffing plans and are capable of providing support to operation of the plant.
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Specific Unit 2 non-licensed worker training has been. ongoing and the last contingent of mechanics / technicians are schedule for supple-mentary training by mid-April, 1987.
It was concluded that management support was evident, personnel were qualified and staffing was sufficient to support plant operation 'c
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'10.0 Offsite Review Committee
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The current Offsite Review Committee (ORC) for Unit 1 will also function
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as the Unit 2 ORC required by the Unit 2 proposed Technical Specifications (TS). An update of the committee's manual is in process but will remain r
essentially the same since the proposed Unit 2 TS, Section 6, is not different from that for Unit 1.
The manual contains four sections, including the committee charter and procedures.
There.are eleven appointed members including the nine specific persons required by the proposed T.S.
A committue member is chairperson of each
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of the four subcommittees:
Engineering and Construction; Maintenance and (
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Operations; Radiological and Environmental; and Audits and Inspections. A member participates as a technical specialist in those T.S.
audits
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conducted by the QA Unit.
Action items assigned to individual members are tracked on a computerized data base. The committee held its first Unit 2 meeting in September 1986.
Two additional meetings were also held since then.
The qualifications and T.S. membership of appointees to the committee meet established requirements.
11.0 Licensee Actions on Previous Inspection Findings (0 pen) 50-412/87-03-01 - Completion of Implementing Procedures for the Design Change Program.
The inspector reviewed the licensee's program consisting of approved and draft procedures (discussed in paragraph 3 above). The item remains open pending NRC review of the approved procedures currently in draft form.
(0 pen) 50-412/87-03-02 Review of Operations Procedures and other
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procedures performed by the PRC is not consistent with Technical Specification requirements.
The licensee's Onsite Safety Committee (OSC) has begun reviewing the PRC meeting minutes and has recommended approval of the procedures reviewed by the PRC.
They also assured that the resolutions of the PRC concerns and the qualifications of the PRC committee members performing the initial reviews were adequate. The licensee plans to attach a second cover sheet to the procedures bearing the OSC meeting number and the plant manager or his designee's approval signature. The OSC has sent a quorum representa-tion to the PRC meetings and will assume their review responsibilities in mid-April.
The inspector reviewed the OSC meeting minutes for meeting BV-0SC-04-87 and verified that the OSC has begun their reviews of PRC minutes. This item remains open pending completion of the reviews by the OSC and plant manager or his designee's approval of the procedure.
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12.0 Management Meetings
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Licensee management was informed of the scope and purpose of the inspection at the entrance interview on March 16, 1987. The findings of the inspection were discussed with licensee representatives during the m
. course of the inspection and presented to licensee management at the c-March.20, 1987, exit interview (see paragraph I for attendees).
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At no time during the inspection was written material provided to the g
licensee by the inspector. The licensee did not indicate that proprietary information was involved within the scope of this inspection.
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ATTACHMENT A 1.0 Reference Requiremen_ts 10 CFR 50.59 10 CFR 50, Appendix B, Criteria I-XVIII
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Proposed Technical Specifications Section 6 l
FSAR Section 13 and 17.
2.04 0ccuments Reviewed Site Administrative Procedures (SAP) Chapter 27, Revision 1, Inservice Test Program.
SAP Chapter 33, Revision 1, Control and Coordination of Surveillance Tests and Calibrations.
SAP Chapter 34, Revision 0, Inservice Inspection Program SAP Chapter 37, Revision 0, Operations Quality Control Quality Assurance Procedure (QAP) OP-12, Revision 0, Control of Measuring and Test Equipment.
Quality Assurance Instruction (QAI) 18.3.2, Revision 13, Quality Assurance Surveillances.
Beaver Valley Power Station (BVPS) 1/2 Maintenance Manual.
BVPS 1/2, Instrument and Control (I&C) Administrative Manual.
Beaver Valley Unit No. 2 Technical Specification Procedure & UFSAR Matrix, Revision 1.
Unit 2 Beaver Valley Test (BVT) Summary (01/16/87).
QA Audit Reports BV-1-86-04, 05, 08, 13, 14, 15, 19, 20, 26, 36, 39, 42, 46; and 87-03.
QA Surveillances OP3-04/08-86; ICG-03-86; TPP-06 & 07-87; OST 2.6.9, 2.30.1A, 2.33.1.2, 2.3.6.7, and 2.39.01.
SAP Chapter 3B, Revision 3, Reporting Requirements SAP Chapter 58, Revision 6, Site Testing and Plant Performance SAP Chapter 10, Revision 7, Onsite Safety Committee SAP Chapter 11, Revision 7, Procedure Preparation, Review, Approval TPP 4.1, Revision 7, Procedure For Writing BVT Procedures BVPS Chapter 48, Conduct of Operations, Section 2 - Operating Procedures SAP Chapter 30, Revision 3, The Maintenance Work Request SAP Chapter 36, Revision 0, Temporary Modifications SAP Chapter 45, Revision 0, (draft) Design Change Control
UAP 1.1, Revision 0, NERU Organization and Responsibilities j
UAP 1.7, Revision 0, (draft), Training Program
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UAP 2.1, Revision 0, (draft) Station Modification Requests UAP 2.2, Revision 0, (draft), Design Change Control UAP 2.4, Revision 0, Safety Evaluation UAP 2.6, Revision 0, (draft) Design Concepts UAP 2.8, Revision 0, Engineering Drawing and Sketches NEMP 1.3, Revision 1, Personnel Training NEMP 1.4, Revision 0, Technical Support Personnel Qualification NEMP 2.3, Revision 2, Handling of Station Modification Requests NEMP 2.8, Revision 3, Handling of Design Change Packages
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NEMP 2.15, Revision 0, Engineering Change Notice NEMP 5.1, Revision 2, Issue of Controlled Documents NEMP 7.1, Revision 0, Non-conformance Reports NECUMP 2.5, Revision 0, Design Analyses NECUMP 2.7, Revision 1, Engineering Specifications NECUMP 2.10, Revision 0, Design Verification NECUMP 6.7, Revision 1, Records Update Control NEDII 2.15.1, Revision 0, Engineering Change Notice Control NEDII 31, Revision 0, Appendix R Review of Design Change Packages NECU Guideline 1, Revision 1, Interim Issue Type I As-Built Documents NECU Guideline 3, Revision 0, Handling of Design Change Packages NECU Guideline 5, Revision 0, Training Checklists NECU Guideline 8, Development and Control of Design Input Lists OP-4, Revision 0, Design Change Control 0P-10, Revision 0, Maintenance and Modification Planning OP-11, Revision 0, Control of Maintenance and Modification 2BVM-87A, 3/2/87, Management Plan for Project Quality for the
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Operational Phase of the BVPS, Unit 2 l
2BVM-186, draft, SWEC Interface with the DLC Operations Design Change Control Program 2BVM-185, 2/24/87, Performing 10 CFR 50.50 Safety Evaluations 2BVM-57, Revision 9, Calculations
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2BVM-7, Revision 8, The Preparation of Specifications 2BVM-203, Revision 17, Revisions to Drawings by the Site Engineering Group 2BVM-212, Revision 6, Interim Drawing Control 2BVM-303, Revision 5, Instructions for the Preparation, Review and Control of Preoperational, Initial Startup, and System Operability Verification Test Procedures.
EAP 3.1, Revision 2, Verification of Nuclear Power Plant Design EAP 4.13, Revision 0, Processing of Project Specifications Personnel files and resumes of slected personnel Detail organizational charts listing incumbents identity Offsite Review Committee Manual and meeting minutes Computerized preventive maintenance data base Computerized maintenance backlog listings l
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