ML20076E939
| ML20076E939 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/19/1983 |
| From: | Moore D, Quinton M, Turkett J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20076E851 | List: |
| References | |
| PROC-830519, NUDOCS 8306010357 | |
| Download: ML20076E939 (9) | |
Text
r INSERVICE INSPECTICII PROGRAM 1st INTERVAL for the VIRGIL C. SUMMER NUCLEAR STATION REVISION 2 DOCKET NO. 50/395 l
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8306010357 830523
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INSEdVICE INSPECTION PROGRAM 1st INTERVAL for the VIRGIL C. SUMMER STATION REVISION 2 DOCKET Uo. 50/395 Oi!NER: South Carolina Electric and Gas Company F.C. Box 764 Main 3treet Columbia, South Carolina 29218 PLANT: V. C. Summer Station Location - Twenty-six miles northwest of Columbia in Jenkinsville, S.C.
CAPACITY: 1 Unit of 900 MWe PREPARED BY: /k a /[ T- /f- f 3 PROGR/iM APPROVAL 3: M[/) kMA~
Incervice In,spection Coordinator /Date f" / P-/.'f
/, 3k'kb Manager, ,U
' lear " ality Control /Date QA Manager /Date
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Manager, V. C. Summer Nuclear Station /Date' bb~. ? k <lf]n b 0 0k, 5'19-f h M anage r , l/H u c le ar En gine e ni n g/ D at e h h ,&.)<m T- 19 ' V 3 C0ilCURRENCE: Authoriced Nuclear Enservice Inspector /Date t
1ST INTERVAL INSERVICE INSPECTION ~ PROGRAM REVISION 2 5/18/83 ISIRODUCTION:
Thic document represents the Inservice Inspection and Testing Program for the V. C. Summer Nuclear Station, Unit 1, pressure retaining components (including supports) which are classified ASME Code Class 1, Class 2 and Class 3 INSERVICE INSPECTION:
Except for inservice inspection testing of pumps, the ISI Program complies with requirements of 100FR50 55a(b)(2) and 50.55a(g) effective April 17, 1981 and utilizes the ASME Section XI Code, 1977 Edition through and includino the Summer 1978 Addenda except as specified in 10CFR50.55a(b)(2)[IV) as a basis for the inservice examinations and tests to be performed during the firut 120 months inspection interval. The first inspection interval will be scheduled to begin when the unit is placed into commercial operation.
The inserviceofinspection requirements testing)forand 100FR50 55a(b)(2 pumps comulies 50.55a(g) with September effective the 1, 1982 and utilizes the ASME Section II Code, 1980 Edition through and including the Winter 1980 Addenda.
The ISI Program is presented in the following seven (7) sections:
SECTION I:
Station Administrative Procedure, SAP-145, details the administrative controls for the ISI Program which includes delegation of authority and responsibility for conduct of the ISI Program, qualification requirements for individuals participating in and performing inspections and tests required by the program, and documentation and tracking requirements for the program.
SECTION II - INSERVICE TESTING OF PUMPS, GENERAL TEST PROCEDURE, GTP-001 The pump testing program demonstrates the operational readiness of Code Class 1, 2 and 3 pumps, as applicable, which are required to perform a specific function in safely shutting down the reactor or in mitigating the consequences of an accident. This program is presented in the form of a procedure incorporating tables identifying the pump by number, location, coordinates, relief request (if applicable) and the appropriate Surveillance Test Procedure.
In addition, tables are included to determine the allowable ranges of test parameters, such as pump speed, inlet pressure, differential pressure, flow rate, vibration, bearing temperature, detection instrument type, I.D. number and calibration due date.
A Puup Test Summary is included to track the status of successful tests. Also, relief requests are referenced in this procedure and kept under separate tabs as part of the Pump Test Program.
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1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 2 5/18/83 SECTIO:. III - INSERVICE TESTING OF VALVES, GENERAL TEST PROCEDURE, GTP-Ou2 The valve testing program demonstrates the operational readiness of Code Class 1, 2 and 3 valves, as applicable, which are required to perform a specific function in safely shutting down the reactor or in mitigating the consequences of an accident. This program is presented in the form of a procedure, incorporating tables identifying the valve by number, system, description of function, category, class, location, normal position indicator status, test requirement (s), and relief request (s) status. Applicable alternate test (s), stroke time, leak tests and an approved Surveillance Test Procedure are referenced for use during evaluation and interpretation of Test Results.
Specific relief requests are referenced along with proposed alternate test (s). In addition, a table and a data sheet are included to determine the number of Safety and Relief valves to be tested between refueling outages and to record specific data for
. each of the valves requiring such tests.
SECTION IV - NONDESTRUCTIVE EXAMINATION OF COMPONENTS, GENERAL TEST PROCEDURE, GTP-003 This section provides the nondestructive examination program for the V. C. Summer Nuclear Station. It describes the ASME Code Class 1, 2 and 3 components subject to. surface, volumetric and visual (VT-1 and appropriate VT-3) examinations as required by ASME Section II Code during the first ten year inspection interval.
The NDE Section provides a procedure which establishes the rules necessary to develop, implement and control the plans, schedules and examinations required by ASME Cection XI Code. Should it become impractical to perform the required NDE examinations due to unusually high levels of residual radiation, fixed contamination and/or permanent structural interferences, a request for relief will be initiated along with selecting alternate examinations and/or components when such alternate tests are meaningful.
In the procedure, Sections 4 4 and 4 5 identify those items or types of items requiring the code examinations. In some cases, such as Class 1 and 2 piping systems, the items to be examined are identified by the type and percentage based upon the ASME Section XI Code, 1977 Edition through the 1978 Addenda requirements.
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l 1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 2 5/18/83 3ECTI2H IV (Continued)
When welds requiring specific seismic analysis, as required by tne code, have been identified, GTP-003 will be revised to reflect the required examinations of such welds. A table is also included in the procedure identifying the category, item number, Seneral deceription, examination method, total items in general description, examination amount and extent, examination period, intended examination % and relief request / remarks. In addition isometric sketciies are identified and provided under separate binder identifying the system, class and appropriate Inservice Inspection Veld Numbers.
Since design geometric discontinuities may exist at the point of interest, meaningful ultrasonic examinations and surface examinations may not be practical. However, a best effort examination will te performed and so noted on the inspection data sheet.
Due tc their anomalous nature, certain material product forms, such as auctenetic stainless steel, may not lend themselves to meaningful ultrasonic examinations in the root areas of the weld with the present " State of the Art" methods available. Therefore, ultrasonic examinations will be performed on a best effort basis using the " State of the Art" methods available at the time the exanination is performed.
SECTION V - INSERVICE INSPECTION SYSTEM PRESSURE TESTING, GENERAL TEST PROCEDURE, GTP-004 This section provides the System Pressure Test Program Plan. It describes the ASME Code Class 1, 2 and 3 components subject to the pressure tests as required by ASME Code Section XI during the first ten year inspection interval.
The program is presented in the form of a procedure incorporating tables to identify the type of component, required tests, examination method, inspection frequency and references for specific activities performed during the test.
In addition, tables are incorporated to identify the system / subsystem designation, code class, description of system / subsystem, Surveillance Test Procedure and the applicable flow drawing. Relief requests are identified in GTP-004 and provided under separate binder identifying the system / subsystem, name of item and class of item to be tested.
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1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 2 5/18/83 SECTION VI - INSERVICE IN3PECTION OF COMPONENT SUPPORTS, GENERAL yEST PiiOCEDURE, GTP-005 This section provides the component support examination program plan. It describes the ASME Code Class 1, 2 and 3 component tupports and other component supports listed in the Plant Technical Specification subject to the examination requirements of ASME Section XI Code and the Technical Specification during the first ten year interval.
The required testing and visual examinations shall be documented in accordance with the applicable Surveillance Test Procedures. In the event circumstances such as radiation / contamination levels, geometric design, building struct1ral design or other unforeseen factors require such action, provision for relief request has been made in this procedure.
SECTION VII - REPAIR PROGRAM A program has been developed in accordance with requirements of the Code to perform repairs on those Code Class 1, 2 and 3 items and other safety related systems and structures.
The repair program is presented in the form of four (4) procedures:
(1) SAP-304, "ASME Code,Section XI Repair Program".
(2) SAP-302, " Administration of Maintenance Welding".
(3) VM-1.0, " Welding Manual Procedure".
(4) WM-2.0, " Welding Material Procedure".
(1 ) SAP-304, ASME CODE, SECTION XI REPAIR PROGRAM:
This procedure vas developed to establish a repair program in conjunction with the Inservice Inspection Program.
Included in this procedure are:
- a. Responsibilities 1
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- b. Documentation Requirements
- c. Disposition of Repair Methods j d. Implementation Requirements
- e. Review and Approval Requirements
- f. Interfacing Requirements l
IST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 2 5/18/83 (2) 3AP-302, ADMINISTRATION OF MAIHTEHAUCE WELDING:
This procedure establ.i shes the means for developing, implementing and maintaining the controls for the maintenance welding prograc. Included in this procedure are:
- a. Responsibilities
- b. Training and Qualification Requirements
- c. Documentation Requirements
- d. Material Control Requirements
- e. Welding and Brazing Activity Control Requirements
- f. Welding by External Organization Requirements
- g. Authorized Huclear Inservice Inspector Involvement (3) WM-1.0, WELDING MANUAL PROCEDURE:
This procedure was developed as part of the repair program to provide the necessary rules for controlling welding and brazing activities, thus ensuring the requirements have been met for code and safety-related items. Included in this procedure are:
- a. Training of Welders and Brazers
- b. Qualification of WPSs and BPSs
- c. Procedure Qualification Tests
- d. Standard Qualification Tests
- e. Acceptance Criteria of Qualification Tests
- f. Documentation of Welding and Brazing Activities
- g. Welding Activities
- h. Brazing Activities
- i. Repair of Weld Metal and Base Metal Defects
- j. Defect Removal and Cavity Preparation of Weld Metal and Base Metal
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1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 2 5/18/83
- k. Post deld Heat Treatment
- 1. Post Braze Heat Treatment
- n. Calibration (4) WM-2.0, VELDING MATERIAL CONTROL:
This procedure was developed to establish and implement the methods for controlling, procuring, storing, issuing and proper disposition of unused and used welding electrodes.
Included in this procedure are:
- a. Responsibilities
- b. Practices of Handling Materials
- c. Documentation
- d. Rod Room Control of Welding and Brazing Material
- e. Rod Room Issuance Control of Welding and Brazing Material
- f. Field Control of Welding and Brazing Material
- g. Rod Roon Return Control of Welding and Brazing Material
! Where conformance with certain code requirements is impractical, l requests for relief 3 and/or explanatory comments are referenced into each section with supporting information and proposed alternatives.
Each section of this program used as controlled copies is indexed and tabbed for convenience of retrieval, planning, controlling and scheduling those activities necessary to achieve timely results.
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1 Reference FR50 55alg)(5)(iiij l
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1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 2 5/18/83 Augmented examinations, if required by the NRC, 2 are included as part of this program. Examples of these are those required for the Reactor Coolant Pump Flywheels, Steam Generator Tubes and Component Supports. Each Reactor Coolant Pump Flywheel will be inspected in accordance with Regulatory Guide 1.14, Revision 1, August 1975 In addition to the requirements of this program and ASME Section XI Code, eddy current examination of the Steam Generator Tubes and the visual examination and functional test of snubbers will be j performed to ceet the requirements of the plant Technical Specification. The examinations and tests will be performed utilizind procedures and personnel which meet the requirements of the plant Technical Specification.
Providing revision to any of the procedures captioned' herein will not delete any of the requirements specified in the codes or other applicable standards, any procedure may be revised without further revision to the Inservice Inspection Program. In all cases, the latast approved revision of the applicable procedure shall become part of the Inservice Inspection Program.
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Pursuant to 10CFH50 55alg)(6)(ii)
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