ML20029E111
| ML20029E111 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/29/1993 |
| From: | John Baker SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20029E108 | List: |
| References | |
| QSP-210, NUDOCS 9405160274 | |
| Download: ML20029E111 (11) | |
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g SOUTH CAROLINA ELECTRIC & GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS O
NUCLEAR OPERATIONS IQLE0RKQLQLY COPY NO. Sq O
QUALITY SYSTEMS PROCEDURE QSP-210 INSERVICE INSPECTION NON-DESTRUCTIVE EXAMINATION REVISION 2 SAFETY RELATED j kh eA O b I A/J Tb3 D1(glPLINE SUPERVISOR DATE M // / / j
( A As3/ n/nM3 M OVAEAUTHORITY DATE '
RECORD OF CHANGES CHANGE DATE CHANGE DATE -
LETTER CANCELLED LETTER CANCELLED O
REFERENCE USE Procedure Segments May Be Performed from Memory Must Verify Work Following Each Segment.
9405160274 940511-PDR ADOCK 05000395 P .PDR
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PAGEi O- REVISION 2 l
Q TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE i O 2.0 ReseReNCES ,
3.0 GLOSSARY 2 4.0 RESPONSIBILITY 3 5.0 GENERAL 4 6.0 EQUIPMENT 4 7.0 PERSONNEL REQUIREMENTS 4 8.0 PROCEDURE AND DOCUMENTATION 4 9.0 ACCEPTANCE CRITERIA AND CORRECTIVE ACTION 7 10.0 RECORDS 9 O
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. QSP 210 Revision 2 Page 1 of 9 1.0 PURPOSE 1.1 This procedure provides the rules necessary to plan, schedule, develop and control the non-destructive examinations required by ASME Section XI Code on Class 1 and 2 pressure retaining components and their welded supports f r the Inservice Ex min ti n Pr gr m t the V. C. Summer Nuclear Station.
O NOTE: The Inservice Examination NDE requirements for Code Class 3 components are implemented and controlled in accordance with Q5P-211.
O 1.2 The effective date of this procedure, this revision, shall be 1-1-94.
2.0 REFERENCES
2.1 Al-104," Qualification and Certification of Quality ControlInspection Personnel" 2.2 ASME Code Section lil,1971 Edition through summer 1973 addenda for piping systems and original construction code for other components 2.3 ASME Code Section V,1989 Edition 2.4 ASME Code,Section XI,1989 Edition 2.5 ASNT-TC-1 A, " Personnel Qualification and Certification in Non-Destructive Testing,1984 Edition" 2.6 FSAR (Section 5.2.6 RCP Flywheel) 2.7 15E-1, " Inservice Inspection Manual" 2.8 NRC Regubtory Guide 1.14 2,9 NRC Regulatory Guide 1.150 2.10 QSP-100, " Development, Revision, Control and Distribution of Quality Systems Plans, Procedures and Instructions" 2.11 QSP-211, " Inservice Examination For Component Supports" 2.12 QSP-213, "NDE Inservice Examination Program" 2.13 SAP-139, " Procedure Development, Review, Approval and Control" O 2.14 5AP-642, " Administration of Maintenance Welding" 2.15 SAP-601, " Maintenance Work Request" 2.16 SAP-643, " ASME Code Section XI Repair Program" O 2.17 SAP-1141, "Nonconformance Control Program" l
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, Q5P-210 Revision 2 Page 2 of 9 O 2.18 NRC Regulatory Guide 1.147 2.19 STP-804.901, " Eddy Current Examination of 5/G Tubing" 2.20 Tech. Spec. 4.0.5 O 2.2, wu-1.0. weiding uenuei erocedure-2.22 10 CFR50.55a 3.0 GLOSSARY 3.1 Authorized Nuclear Inservice Inspector (ANll)- An inspector empt yed by an insurance company authorized to write boiler and pressure vesselinsurance and having qualified in accordance with the requirements of ANSI /ASME N626.1,1975.
3.2 Code - ASME Code Section XI,1989 Edition.
3.3 Code Class - A classification of items and components based upon Section 111 code subsection used to fabricate and/or install such items.
3.1.1 Class 1 - Subsection NB 3.1.2 Class 2 - Subsection NC O 3.1.3 Class 3 - Subsection ND 1
3.1.4 Cornponent Supports- Subsection NF 3.4 Code Category the major type s) of(Designation - A designation parts to be examined used within a code by theorcode component a to delineate selected group of code components, as applicable.
3.5 Code item Number- A number used by the code to specify: the type of part to be examined, the examination requirements, the examination method, the acceptance standard, the extent of frequency of examination, and if permitted, the deferral of inspections.
O 3.6 Commercial Service -The date of placement of the power unit into the regulation of the Federal Power commercial service Commission Chapter as defined 1, Title 18 by' Code of Federal Regulations",(January 1984).
3.7 Examination - The performance of visual observations or non-destructive testinc such as radiography, ultrasonic, liquid penetrant, magnetic particle <
t and ec dy current methods. I 3.8 Flaw- An indication denoted by evidence or signal obtained by of non-destructive examination methods (s) such as inclusions, cracks, slag , applicai ,
aligned or clustered porosity, incomplete penetration, incomplete fusion j and f aminations or combinations thereof.
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Page 3 of 9 o O 3.9 Inservice Examination (ISE)- Those scheduled examination activities performed during the plant lifetime as outlined in ASME Code and implemented by the use of specific procedures.
3.10 Inservice Examination Coordinator That person designated by the Manager of Qualit ystems, who is responsible for development and implementation o t e ISE program.
3.11 Inservice Examination Program - Those planned and systematic actions performed to: categorize the area subject to examination and responsibilities, provide for accessibility, apply examination methods and procedures, qualify 3ersonnel, establish frequency of examination, establish and maintain recorc keeping and reporting requirements, evaluation of O examination resuits end. if necessarv. subsequent disposition and corrective action of such results, and document a repair program.
3.12 Inspection interval-That amount of time approximately equal to 1/4 of expected plant life,(10 years), reference Manual 15E-1.
3.13 Inspection Period - That amount of time in calendar years and/or months approximately equal to 1/3 of an inspection interval,(3 to 4 years),
reference Manual ISE-1.
3.14 Regulatory Authority - A federal government agency such as the USNRC.
3.15 Replacement - A spare component (s), parts of such component (s), or subsystem (s) but not the addition of new systems.
3.16 Rework- Replacement and/or other non-welding activities, required to return an item to a condition acceptable to the Code.
3.17 Repair - Welding activities, including initial and surface finishing processes, required to return an item to a condition acceptable to the Code.
3.18 Supervisor, Licensing and Operating Experience - That individual designated by the General Manager, Nuclear Safety, to act as liaison for South Carolina Electric and Gas Company Nuclear Operations (SCE&G/NO) and the United States Nuclear Regulatory Commission.
3.19 Encased welded attachments, enclosed by using equipment or other structural products such that the enclosed item can only be visually O observed by the removal of the equipment or structural product with resulting damage to the enclosing equipment or structural products.
4.0 RESPONSIBILITIES O 4.1 The Manager, Quality Systems, has overall responsibility for the administration and control of this procedure.
4.2 The Supervisor, Quality Control, has overall responsibility for the development, coordination and implementation of this procedure.
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4.3 The inspection personnel are responsible for the execution of the requirements assigned by this procedure.
5.0 GENERAL 5.1 Examinations shall be performed in accordance with procedures developed O to applicable code requirements.
5.2 The Code does not address all possible combinations of limitations which may be encountered during inservice Inspection Examinations. These limitations will be quantified and documented in accordance with approved procedures.
O 5.3 Manual 15E-1 will be used for planning scheduling activities and work in accordance with the guidelines of QSP-213.
5.4 When required, radiation work permits (RWP) will be initiated and completed in accordance with Health Physics Procedures. ,
5.5 Reports, records and results of examinations shall be prepared in accordance with the requirements of the Code and the applicable examination procedures.
6.0 EQUIPMENT O 6., ^s needed by the exeminer. -
7.0 PERSONNEL REQUIREMENTS 7.1 Personnel performing the examinations shall be qualified in accordance with Al-104.
7.2 Contractors /or subcontractors performing examinations shall either prepare written procedures or utilize existing QC procedures and qualify their personnel in accordance with requirements specified therein.
7.3 Contractors and/or subcontractors shall obtain a " Release to Work", when required by purchase order, from SCE&G QA prior to performing any work O at V. C. Summer Nuclear Station.
8.0 PROCEDURE AND DOCUMENTATION 8.1 Non-Destructive Examination Scheduling O 8.1.1 The rec uired examinations to be performed on Class 1 items shall be schedu ed in accordance with Section 8.3 in accordance with ISE-1 Manual.
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QSP-210
,- Revision 2 Page 5 of 9 0 8.,.2 The rec uired examinations to be performed on Class 2 items shall be schedu ed in accordance with Section 8.4 in accordance with 15E-1 Manual.
8.1.3 The required examinations to be performed on the three Reactor Coolant Pump flywheels shall be in accordance with Regulatory O Guideline 1.14 and scheduled in accordance with Section 8.3 in accordance with 15E-1 Manual.
8.1.4 Manual 15E-1 has been developed in accordance with ASME Section XI Code 1989 Edition.
8.1.5 The ISE NDE Plan shall be developed and implemented in accordance O with Manual 15E-1. Each plan shall be maintained in accordance with Nuclear Records Management Program Procedures (NRMPP).
8.2 Preservice Examination (Class 1 and Class 2) 8.2.1 The required preservice examinations are performed to establish '
baseline data for comparison with the results of future inservice examinations.
8.2.2 The PSI Examination Data includes identification, examination and records of those items required to be examined during the inservice inspection program except as specified herein.
8.2.3 PSI Examination Data is stored and maintained in accordance with A Nuclear Records Management Program Procedures (NRMPP).
8.2.4 Components to be examined during inservice examination shall be identified by comparing the PSIitems with the code requirements and applicable regulatory guides. New or modified items shall be incorporated in the ISE Program pursuant to Code requirements.
8.2.5 During the effective life of the V. C. Summer Nuclear Station, the isometric sketches will be revised as necessary to reflect modifications, construction drawings changes or applicable code requirements. The original isometnc sketches may be redrawn into two or more isometric sketches to provide directional and/or legibility clarification. The redrawn isometric sketches will provide a Q method, through notes or other ositive identification, for linking preservice data with current ISE ata.
8.2.6 Revised isometric sketches will normally be drawn by_ Quality Systems, reviewed for accuracy by Quality Control ISE 3ersonnel, approved by -
the NDEll5E coordinator and distributed by t le Documents department in accordance with DCP-101. The drawings are issued O and maintained in manuals as VC5 948-375 for Class 1 com aonents and VC5-94B-376 for Class 2 items. The revised sketches wi l be transmitted to documents for incorporation into the respective manuals upon the completion of their revision.
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QSP-210 Revision 2 Page 6 of 9 O 8.2.7 Records for PSI Steam Generator tube eddy current examinations are V recorded under separate cover and maintained in accordance with Nuclear Records Management Program Procedures (NRMPP).
8.3 Class 1 ISE Components Categorization and itemization 8.3.1 ASME Class 1,2 and 3 Components along with component supports O* are itemized and listed in Manual 15E-1. This manual lists components subject to examination , scheduling and testing for the appropriate interval. Pertinent code classifications, exceptions and tabulations are also contained in Manual 15E-1.
8.4 ISE NDE Performance Conditions O 8.4.1 ISE NDE may be performed on-line while the system is operating or off-line while the system is out of service.
8.4.2 Whether the system is on-line or off-line the specific NDE shall be compatible with Technical Specification Operating Criteria. -
Consideration must be afforded the system itself, location of specific item the time involved to erect scaffold, remove insulation, welcl preparation, conduct the specific NDE, performconduct repairs, perform re-examinations, reinstall insulation, remove scaffold, clean up, etc.
8.4.3 When a safety related item must be removed to provide accessibility to the specific component or item to be examined, an engineering evaluation must be obtained prior to removing the safety-related
(] item. (Reference MMP-305 Series procedures) 8.4.4 Other conditions may be specified by the ISE Coordinator in order to provide a quality examination consistent with radiation, contamination safety or technical specification requirements.
8.4.5 Any special plant conditions for ISE NDE will be identified on the MWR, the MWR additional sheets and/or approved NDE procedures.
8.5 Weld Preparation and Tools 8.5.1 The welds selected for examination shall be prepared to accommodate the appropriate NDE methods, O 8.5.2 Weld preparation tools shall be used in accordance with the requirements specified in WM-1.0 for base metal preparation.
8.6 Technical Specification Requirements I 8.6.1 For some of the plant's systems and/or components there exists specific operability time criteria. When such components, systems O. end/or >roximity systems are deciered inoperebie to erect scaffolc ing, remove interference and/or perform ISE NDE examinations, the Shift Supervisor shall be notified via MWR, MWR l additional sheets and/or STTS, etc. The appropriate record shall indicate the removal and restoration tags and time criteria.
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. Revision 2 Page 7 of 9 O 8.6.2 When the examination (s) have been completed, the scaffold has been removed or the interference (s) have been reinstalled, the Shift Supervisor shallindicate the date and time of restoration to operable conditions via the appropriate record.
Q 8.7 Examination plans and schedules shall be prepared and approved in accordance with the component selection and NDE requirements of this procedure and the code.
8.8 A NDE summary shall be completed and become part of the final records at the end of each inservice inspection outage. This summary shall be used as p part of the NIS-1 form. The:e records shall be compared and utilized to V pre 3are subsequent NDE plans. Such plans shall be in accordance with the Coc e and this procedure.
8.9 Examination summary report (NIS-1 Form) shall be prepared from the examination data sheets and submitted to the regulatory authority within 90 days after completion of the inspection / refueling outage schedule.
8.10 Evaluation, dis aosition and subsequent corrective measure records may become part o" the examination data sheets or maintained separately with appropriate reference for retrieval.
8.11 Examination, evaluation, disposition, corrective measures and summary reports, including the NIS-1 form, shall be maintained for the service
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O 8.12 Relief requests,if any, shall be referenced in ManualISE-1. Such relief requests shall be indexed, stored and maintained under separate cover per reference 2.12.
8.13 Confined entry permits, scaffold request and/orinsulation removal shall be as specified on the MWR additional sheet (s), MWR or STTS, as required.
9.0 ACCEPTANCE CRITERIA AND CORRECTIVE ACTION 9.1 Evaluations of indications exceeding code allowable limits detected during the examination shall be performed in accordance with the requirements of the Code for Class 1 and 2 items except as noted in 9.2 and 9.3.
O 9.2 Evaluations of the reported indications detected during the examination of the reactor coolant pump flywheel, shall be performed in accordance with the requirements of the Final Safety Analysis Report (FSAR) and Regulatory Guide 1.14.
O 9.3 eveiuetion of indicetions detected durino eddy current examination of Steam Generator tubes shall be performed in accordance with the requirements of the Plant Technical Specification.
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, Revision 2 Page 8 of 9 pJ 9.4 Evaluation of indications determined to be within the allowable limits set forth in the code need only be documented and such evaluation records retained as part of the examination records.
9.5 The disposition (s) for rejectable indications may consist of:
9.5.1 Repair to remove the fiaw altogether, or 9.5.2 Repair to remove the flaw to an acceptable limit, or 9.5.3 Perform fracture mechanics analysis and,if permitted by such analysis, monitor the item during subsequent inservice examinations as required by the Code, or O 9.5.4 Replace the component and in addition to one or all of the disposition (s)in 9.5.1 through 9.5.4, an additional number components within the same examination category of a aproximately equal to the number of components examined initially c uring that inspection shall be examined. If these additional examinations reveal rejectable indications, subsequent examinations shall be in accordance with IWB 2430 or IWC-2430 as applicable.
9.5.5 Engineering Services may use other methods when the above actions do not cover the indication repair / removal.
9.6 Evaluation of items, for which no standard exists in the Code of Record (ASME XI), may be performed in accordance with the original construction O code or if no construction code stendard exists then e ieter edition of ASMe Section XI may be used for evaluation.
9.7 Indications determined to be unacceptable by evaluation shall be identified for disposition. Disposition shall be in accordance with SAP-1141.
9.8 Re-examinations and Retest 9.E.1 Re-examinations A. Re-examinations required as a result of unsatisfactory 151 NDE will be as specified by any applicable repair code (s) and ,
the appropriate edition and addenda of ASME Section XI '
Code.
B. Re-examination frequency shall be in accordance with the code, lWB 2420 or IWC 2420. !
l C. Performance of the re examination shall be in accordance '
with QC, or other approved procedures and be of the same Q method as originalinspection.
9.8.2 Re-testing will be performed under the MWR/STTS program using approved procedures.
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QSP-210
. Revision 2 Page 9 of 9 9.10 Unacceptable indications requiring repair (s) by welding shall be corrected in accordance with SAP-643 and appropriate references. For repairs and as required for examinations, danger tags shall be attached to each of the affected com aonents in accordance with the requirements of the MWR or the MWR adc itional sheets.
O 10.0 RECORDS 10.1 Ins pection records and the N15-1 Summary will be controlled by QSP-213, Reference 2.12.
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