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Latest revision as of 03:28, 16 March 2020
| ML19323D320 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/08/1980 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML19323D318 | List: |
| References | |
| PROC-800408, NUDOCS 8005210432 | |
| Download: ML19323D320 (700) | |
Text
{{#Wiki_filter:I O . e c os sio'3b. l l VIRGIL C. SUMMER NUCLEAR STATION PRELIMINARY PRESERVICE INSPECTION PROGRAM 9 e ( U l 8005210 % 9__i._
j APRIL 8, 1980 - , 4 l SOUTH CAROLINA ELECTRIC AND GAS COMPANY P.O. Box 764 Columbia, S. C. 29218 i
- VIRGIL C. SUMMER NUCLEAR STATION P. O. Box 88 Jenkinsville, S. C. 29065 VIRGIL C. SUMMER UNIT 1 May 1, 1981 i
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VIRGIL C. SUMMER NUCLEAR STATION (~ PRELIMINARY PRESERVICE INSPECTION PROGRAM Pursuant to the requirements of the Code of Federal Regulations, Title 10, Part 50 (10CFR50.55 a(g)), the Preservice Inspection Program for the Virgil C. Summer Nuclear Station is established in accordance with American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI; " Rules for Inservice Inspection of Nuclear Power Plants"; 1974 Edition through Summer 1975 Addenda. Enclosed within this manual is the Administrative Procedure developed to control the overall preservice inspection program at the Virgil C. Summer Nuclear Station, the listing of Class 1 and 2 systems and components to be examined, the schedule of Class 1 and 2 welds to be inspected, the listing of Class 3 examinations to be conducted, and the listing of ASME Code Hydrostatic Tests to be conducted for preservice inspection. Also included within this manual are copies of the applicable examination and inspection procedures. _, Examinations for Class 1 and 2 systems and components, including Class 1 and 2 weld inspections, will be conducted by Westinghouse Nuclear Services Division, Inspection Services Group. Examinations and inspections for Class 3 systems, components and welds will be conducted by South Carolina Electric and Gas Company Start-Up Group and Daniel Construction Company. The American Motorist Insurance Company, a subsidiary of the Kemper Insurance Group, will provide the Authorized Nuclear Inspector for the Virgil C. Summer Nuclear Station Preservice Inspection Program. a I t ._ ! l
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SOUTH-CadOLINA ELECTRIC AND CAS C0!!PANY 1 - VIRGIL C. S Ul!!!ER NUCLEAR STATION PRELIMINARY I PRESERVICE INSPECTION PROGRAM ! I i : i i t i l Recent regulatory positions (Attachment I to Branch Technical i Position - MEB No. 2) in regards to preservice inspection has prompted a review of Administrative Procedure, AP-014, !
"Preservice Inspection Program". This review has resulted in ; changes to Attachments Vi and VII.
9 Updates in the Start-Up Program have resulted in changes to s Attachment IX. The revised hydrostatic examination list may ; l be found under tab heading " PSI Hydrostatic Test". ! l . l Accordingly, AP-014 is currently being revised to reflect these changes to the program and the revision will be inserted . in the Preliminary Preservice Inspection Manual, when approved. i, I . i t 6 1 I . i 1 t 4 i i
l O O SOUTH CAROLINA ELECTRIC AND CAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS 8 e fe!,h)hf,I L., g [ South Carolina Dectric and Ga OPERAT10NS DEp.g,, f? 5 i h_d em \ a l h h u a A o p93y - abn t ADMINISTRATIVE PROCEDURE AP-014 PRESERVICE INSPECTION PROGRAM
. REVISION O DECEMBER 27, 1978 SAFETY RELATED L C' . m~bo: /- 23 -79
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AP-014 Page i Revision 0 12/27/78 LIST OF EFFECTIVE PdGES Page Revision 1 0 11 0 1 0 2 0 3 0 4 0 . 5 0
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7 0 8 0 9 0 10 0 Attachment I O Attachment II O a 0 e O
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AP-014 Page 11 Revision 0 12/27/78 l TAllLE OF C0tlTENTS i
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List of Effective Pages i l 1.0 PURPOSE 1 l 2.0 REFERElICES AND GLOSSARY 2 i
'.0 RESPONSIBILITY , 3 j 11 . 0 GEllERAL 4 5.0 PROCEDURE 7 ATTACHi<EllTS Attachment I - Article IWA-6000, Records and Reports 1
Attachment II - Preservice Inspection Flow Chart i 4 . i i 4 I i l 1 i
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. Revision 0 12/27/78 1.0 PURPOSE The purpose of this procedure is to provide the administrative guidelines, coordination control and the interface with associated organizations for Nuclear Operations personnel in the administration of the preservice inspection program required by the A.S.M.E. code, section XI, for the Virgil C. Summer Nuclear Station.
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AP-014 Page 2 Revision 0 12/27/78
2.0 REFERENCES
AND GLOSSARY 2.1 References. 2.1.1 A.S.M.E. code, Section XI, 1974 edition. 2.1.2 SCE&G Operational Qual'ity Assurance Plan. 2.1.3 SCE&G Quality Assurance Plan 2.1.4 SCE&G Production Engineering Procedu'es. r 2.1.5 SCE&G Quality Control Procedures. 2.1.6 D.C.C. Quality Control Procedures. 2.1.7 D.C.C. Work Procedures. 2.1.8 SCE&G Muclear Operations Start-Up Procedures. 2.1.9 VCS Administrative Procedure AP-101. 2.1.10 Code of Federal Regulations, Title 10, Part 50.55 a(c)(4) 2.1.11 AP-002, Qualifications of External Personnel 2.1.12 AP-1200, Inspection of Activities Affecting Quality 2.2 Glossary 2.2.1 Abbreviations. AI - Authorized Inspector (Section 5.9 2) CWR - Construction Work Request; Outlined in Star.t-Up Manual SUM-B-5. DN - Deficiency Notics; Outlined in AP-209 Nonconformance Control NCN - Non-conformance Notice; Outlined in AP-209 Nonconformance Control. SFR - Start-Up Field Report; Outlined in Start-Up Manual SUM-B-13. . 2.2.2 Definitions. Code - in this procedure shall refer to ASME Code, Section XI. l l _ . _ _ _ _ . . _ _ _ . . . _ _ J
AP-0111 Page 3 Revision 0 12/27/78 Designee - Any individual, approved by the Manager, V. C. Sua:mer Station or appropriate supervisor, designated to assume the responsibilities and duties of titled plant personnel and function in their stead, to include the authority to make decisions in the same capacity as the titled plant personnel for whom the assigned individual is an alternate. O e e e 9 I e i 4 I o i S i l m _. .~- . -- -
- ) AP-014 Page 4 Revision 0 12/27/78 3.0 RESPONSIBILIY 3.1 The SCE&G Manager, VC Summer Nuclear Station, is responsible for the overall implementation of the preservice inspection program for Nuclear Operations.
32 The SCE&G Nuclear Operations Maintenance Supervisor is assigned the responsibility for the coordination of scheduling activities, procedure development and control, problem resolution, and the general day to day work activities associated with the conduct of the preservice inspection program. , 33 SCE&G Nuclear Operations personnel are responsible for assuring that work is performed in accordance with this procedure. e 9'
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) ) AP-014 Page 5 Revision 0 12/27/76 4.0 GENERAL ,
4.1 Section XI, Rules for Inservice Inpection (which includes preservice inspection) of Nuclear Power Plant Components , of the ASME Soiler and Pressure Vessel Code is addressed tc provide rules for the examination, testing, and inspection of Class 1, 2, and 3 components and systems in a nuclear power plant. Application of this Section of the Code begins when the requirements of Section III, Rules for Construction of Nuclear Power Plant Components, have been satisfied. 4.2 ASME Code, Section XI, assigns SCE&G the responsiblity of developing a program which will demonstrate conformance to the requirements of Section XI of the Code. Responsibilities assigned SCE&G include the requirements to provide access in the design and arrangement of the plant to conduct the examination and tests. SCE&G's responsibilities include developing plans and schedules, including detailed examination and testing procedures for filing with the enforcement and regulatory authorities having jurisdiction at the plant site. Conduct of the proEram of examinations and tests, system leakaSe and hyd rostatic pressure tests, as well as performance tests of pumps and valves, are assigned as SCE&G responsibilities. SCEaG is responsible for recording the results of the examinations and tests, including corrective actions required and the actions taken. 4.3 SCE&G Production Engineering has given Westinghouse (Class 1 and
- 2) and GAI (Class 3) the task of providing access in the desi E n and arrangement of the plant to conduct the required examinations and tests.
4.4 On site inspections and responsible organizations are listed below: TYPES OF INSPECTION RESPONSIBLE ORGANIZATIO" a) Examination & Inspection Westinghouse (Note 1) IWB-2000, IWC-2000 b) Examination & Inspection SCE&G Nuclear Operations IU D-2000 c) System Leakage and Hydrostatic Pressure Tests - IUE-5000,
. IUC-5000, IWD-5000 SCE&G Nuclear Operations d) Innervice Testinc of Pumps SCESG !!uclear Operations Subsection IWP e) Inservice Testing of Valves SCE&G Nuclear Operations Subsection IWV l l
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AP-014 Page 6 Revision 0 12/27/78 NOTE 1 - Conduct of examinations other than hydrostatic testing required by ASME Code, Section III, for Code Class 1 and 2 systems will be performed by Westinghouse. 4.5 Control and Interface. In conducting the on-site inspections, testings, problem identification and resolution, documentation, etc., Nuclear Operations and other interfacing organizations will perform work to various procedures. These interfacing procedures are as follows: 4.5.1 Westinghouse ProceduEes. A. ISI-QP-6.1 " Isometric Sketch, Preparation and Control". - B. ISI-QP-6.2 " Control of Onsite Inspection Activities". C. ISI Visual Examination Procedure. D. ISI Preservice and Inservice Examination Manual Ultrasonic Equipment Qualification. E. ISI Liquid Penetrant Examination Procedure. F. ISI Ultrasonic Examination of Studs, Bolts and Nuts. G. ISI-17.1 - " Preparation of Inspection Program Reports". , H. ISI Manual Ultrasonic Testing of Reactor Coolant Pump Flywheels. I. ISI Manual Ultrasonic Examination of Circumferential and Longitudinal Butt Welds in Ferritic Vessels of 2 1/2" Thick and Greater. J. ISI-52 " Operation Prccedure for Reactor Vessel Examination Using the Westi.:ghouse Remote Inspection Tool". K. ISI-71 "het Ma g e 3 Particle Inspection".
. L. ISI-205 - Manual Ultrasonic Examination of Full Penetration Circumferential and Longitudinal Butt Welds.
M. OPS-NSD-101 - Presarvice and Inservice Inspection Documentation. 1 we w e e- --eh - 9
AP-014 Page 7 Revision 0 12/27/78 4.5.2 SCE&G Production Engineering Procedure NE-127, ASME Code Section XI, Engineering Interface Procedure. 4.5.3 SCE&G Nuclear Operations Procedures from the Start-Up Manual: A. SUM-B Construction Work Requests. B. SUM-B Start-Up Field Report (SFR). C. SUM-C Hydrostatic and Pneumatic Tests. D. Surveillance Testing Procedures. 4.5.4 SCE&G Quality Control Procedures. A. FQCP 2.1.4 - Nonconformance Control and Procedure. 4.5.5 DCC Procedures. A. Daniel AP-VI-02, ASME Code Related - Nonconformance and Corrective Action. B. DCC QC Procedures - Weld Inspection or Evaluation. 4.6 Functional Organization. 4.6.1 A group will be established, under the administration of the SCE&G Nuclear Operations Maintenance Supervisor, under the authority of the SCE&G Manager, V.C. Summer Nuclear Station. The purpose of the group will be to coordinate the day to day on site activities of the preservice inspection program. These activities include scheduling, procedure review, approval, revision and control, coordinating on site inspections, problem resolution and tracking, collecting and reviewing results, interface with NRC and Authorized Inspection Agency and the submittal of required documents.
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AP-014 Page 8 Revision 0 12/27/78 5.0 PROCEDURE 5.1 Work Coordination. 5.1.1 The SCE&G Nuclear Operations Maintenance Supervisor or his designee shall coordinate the day to day activities required to implement and perform the onsite preservice inspection program. He shall call upon Nuclear Operations personnel and other SCE&G Organizations to assist him in performing this work. Periodically, he shall hold meeting to update all int'erfacing organizations and per.~ form the functions set forth in this procedure. 5.1.2 Preservice Inspection Flow Chart (Attachment II) outlines organizations needed to coordinate the preservice inspection. 5.2 Scheduling. 5.2.1 The SCE&G Maintenance Supervisor or his designee shall develop a schedule of inspection and work activities. He shall update the schedule as required. He shall ensure that interfacing organizations review the schedule and perform work, under their interfacing procedures, as required to meet the schedule. He shall coordinate the work of these organizations and that of Nuclear Operations from a schedule standpoint to ensure that inspections and work are performed in a timely manner. He shall keep the SCE&G Manager, V.C. Summer Station, informed of the progress of the schedule and on any problems that arise in order that app?opriate levels of management may be informed. 5.3 Procedure Review and Approval. 5.3.1 Subcontractor procedures used for conduct of inspections, correction of deficiencies and documentation of results shall be subjected to an administrative / technical review and approval as described in reference 2.1.9. Work performed by these procedures will be under the guidelines of the SCE&G Operational Quality Assurance Plan. A " Release to Work" will be given by QA prior to _ the performance of any inspections by contract personnel. i 5.4 Performance of Inspection. I 5.4.1 The required inspections are listed in Section 4.4, I components to be inspected are listed by Attachment III to this procedure. Performance of these inspections
- shall be in accordance with the approved procedures .
listed in Section 4.5 by responsible organizations. Qualifications of personnel performing these inspections will be in accordance with reference 2.1.11 and 2.1.12. 4 W
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( AP-014 Page 9 Revision 0 12/27/78 5.5 Technical Problem Resolution and Tracking. 5.5.1 Technical problems discovered during the course of the inspection will be reported to the SCE&G Nuclear Operations Maintenance Supervisor or his designee. He will decide upon the correct course of action to resolve the problem. Approved site procedures such as N.C.N.'s, D.N.'s, SFR's, CWR's, etc., will be used to correct these problems. Resolution of problems outside the scope of existing procedures shall be directed to appropriate levels of management or other organizations as appropriate. . 5.5.2 The resolution of problems may involve repairs of welds, components, supports, equipment, etc. Where the requirements of ASME Code, Section III, Rules for Construction of Nuclear Power Plant Components, have been satisfied and repair is necessary, repair procedures shall be in accordance with ASME Code, Section XI, article IWA-4000. Where the above requirements ' nave not been satisfied, repair procedures shall be in accordance with ASME Code, Section III. All repairs performed in accordance with ASME Code Section XI will be under the jurisdiction of the SCE&G Manager, Quality Control and/or SCE&G Nuclear Operations Quality Control. 5.5.3 The SCE&G Nuclear Operations Maintenance Supervisor shall establish a system for tracking problems that develop during the preservice inspection program. The system shall consist of appropriate log sheets or tracking forms that will identify the problem, follow its resolution, and follow any required retest or inspection to close out the problem.
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5.6 Evaluation of Resul.ts. 5.6.1 The SCE&G Nuclear Operations Maintenance Supervisor or his designee will be responsible for ensuring that interfacing organizations or other qualified personnel perform evaluations of examinations in accordance with ASME Code, Section XI. Standards for evaluation of examination results are listed below: AREA 0F EXAMINATION STANDARD FOR EVALUATION
- 1. Weld Examination Evaluation IWA-3000
- 2. Pressure Test Evaluations IWA-5000
- 3. Pump Performance Test Evaluations IWP-3000
- 4. Valve Testing Evaluations IWV-3000 l
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- Page 10 Revision 0 12/27/78 5.6.2 Generally, DCC QC shall be responsible for evaluating code class 1 and 2 weld examinations and SCE&G Nuclear Operations will be responsible for performing any other examinations or test evaluations or coordinating examinations or test evaluations performed by other organizations.
5.7 Qualifications of Inspection Personnel. 5.7.1 All personnel performing non-destructive examination of systems or components will be qualified under the requirements of ASNT-TC-1A. A list of qualifications of contractor supplied dxaminers will be submitted to SCE&G/QC and SCE&G/QA for review in accordance with Section 12.2.4 of the SCE&G Operational Quality Assurance Plan and reference 2.1.11. 5.8 Reports and Records 5.8.1 The SCE&G Manager, V.C. Summer Nuclear Station, shall be responsible for the compilation of results, records and inspection reports. Requirements of ASME Code, Section XI, Article IWA-6000 (Attachment I) will be met. The precise formats for recording of results are shown in the procedures listed in Section 5.1. 5.8.2 The SCE&G Manager, V.C. Summer Nuclear Station or his designee shall be responsible for ensuring that all records of preservice inspection results, problem evaluation and resolution and changes to the inspection program are prepared and retained in accordance with the guidelines established by articles IWA-6000, IWP-6000 and IWV-6000 of the ASME Code, Section XI, 1974 edition. 5.8.3 A copy of inspection, test and examination records shall
. be retained for the service lifetime of the component inspected.
5.8.4 The SCE&G Manager, V.C. Summer Nuclear Station, will ensure that a preservice inspection report is prepared and submitted in accordance with the guidelines established by article IWA-6000 of the ASME Code, Section XI, 1974 edition. 5.9 Authorized Inspection Agency Interface.
, 5.9.1 The Authorized Inspection Agency for preservice inspection is Kemper Insurance Company.
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AP-014 Page 11 Revision 0 12/27/78 5.9.2 Duties' of tiie Authorized Inspector ( AI) include witnessing any pressure testing, reviewing nondestruqtive examination procedures, reviewing repair programs, verifying that the visual examinations and test on pumps and valves have been completed and the results recorded, and requiring requalification of any operator or procedure when he has reason to believe the require.m.ents of ASME Code, Section XI, 1974 edition, are not being met. 5.9.3 The SCE&G Nuclear Operations Maintenance Supervisor will , ensure that the AI 14 provided with the following: A. Procedures for examination, testing, evaluation and repair of code class 1, 2 and 3 systems and componenets, including pumps and valves. B. Results and evaluations of examinations of pumps and valves. C. Schedules pertinent to the pressure testing of systems and components. 5.9.4 The SCE&G Muclear Operations Maintenance Supervisor shall act as liason between the AI and other interfacing organizations. 5.10 NRC Interface. - 5.10.1 The SCE&G Manager, V.C. Summer Nuclear Station or his designee shall be responsible for providing the NRC with any information pertinent to the preservice inspection. He shall ensure that all records and reports are correctly assembled, reviewed and documented prior to submittal to the NRC for review. The SCE&G Manager, V.C.
, Summer Nuclear Station or his designee shall act as the station liason for any NRC inspection or audit during the performance of the preservice inspection.
5.11 Revision to the Scope of the Preservice Inspection. 5.11.1 Changes to the number or types of components or equipment to be inspected will be the responsibility of the organization performing the inspection. Justification for deletion, alternate means of inspection or additional components to be inspected will be provided in accordance with the A.S.M.E. Code, Section XI, iqen any change to the inspection program is to be madr.
AP-014 Attachment I Page 1 of 2 Revision 0 r JA ARTICLE IWA-6000 RECORDS AND REPORTS I I IWA-6100 SCOPE (3) Name and address of nuc! car generating plant in which the nuclear power unit is located. r The rules in this Article establish requirements for (4) Name or number assigned to the nuclear records and reports developed and maintained bf the pow.r unit by the Owner. Owner concerning the inservice inspection of Class 1. (5) Commercial service date assigned to the { nuclear power unit by the Owner. g 2, and 3 components of the nuclear power plant. (d) All inservice inspection reports shall have a J summary providing the followinginformation:
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( (I) The number assigned to the " boiler", IWA-6200 REQUIREMENTS .. pressure vessel", or component by the State. Mu-nicipality,or Province.
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II *" "" * " * *# * ** S"* E lWA-6210 RECORDS FOR CLASS 1, CLASS manufacturer to the ,' boiler,, , pressure vesse ., or
; 2. AND CLASS 3 COMPONENTS component.
; (3) Names of the components or parts of the The following records shall be available:
* *P "*nts for wMch this is a record. including such (a) Examination plans and schedules. .
mf rmation regardm, g size, capacity, material, Ic-
. (b) Examination results and reports. and. drawings as may aid accurate (c) Examination methods and procedures. pation, ,
identification. (d) Evaluations of results. (4) Name of the manufacturer of the com- {pi (c) Corrective actions and repairs.
- ponents or parts for which this is a record,incluomg the manufacturer's component or part numbers and such information regarding the manufacturer's cor-IWA 6220 REPORTS FOR CLASS 1 AND Porate office or manufacturing plant locations as rnay
! CLASS 2 COMPONENTS and in gaining access to the manufacturer's records I
(a) The Owner shall prepare plans and schedules regarding the components or parts that the man-
' for inservice inspection that will satisfy the re- ufacturer is maintaining in accordance with re-p quirements of this Division. Plans and schedules shall quirements of Section Ill.
6 be filed with the enforcement and regulatory au- (5) Date of completion of the Inservice In-
;i ti.orities havingjurisdiction at the plant site. spection.
(b) rhe Owner's inservice inspection reports shall (6) Name or names of the Inspector (s), when
; j; be filed within ninety (90) days after completion of the required.
- ),8 inservice inspection with the enfcrcement and reg- (7) Nameandmailingaddressof theemployer(s) ip ulatory authority havingjurisdiction at the plant site. of theInspector(s).
i (c) All information, plans, schedules, and reports ,,,. (3) Abstract of examinations performed, con-ditions observed corrective measures recommen'ded (V relating to inservice inspection of a nuclear power unit shall have a cover sheet providing the following and taken. (
- information: (9) Signature of Inspector, when required.
i, j (/) Date- (c) All inservice Inspection reports shall ' e an (2) Name of Owner and address of corporate Owner's Data Report for Inservice inspection. Fo-' l ' {; offices. NIS-1,as shownin Appendix 11. l 14 I
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'8 IWA-6000-RECORDS AND REPORTS IWA.6230-lWA 6240 p7 4 I ..;
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;W.*.-6230 RECORDS OF PRESSURE TEST IWA-6240 RECORDS OF PUMP AND VALVE Mb e INSERVICE TESTS o ;f .
The record of the visual examination conducted m 1. during a system leakage test and a system hydrostatic The record of the inservice tests of pumps and '
. u valves shall be in accordance with IWP-6000 and 9*
test (!WA-5000) shall consist of itemization of the number and location of leaks found in a system and IWV-6000. j) ,.I i the actions taken. :c > - F t - o e ;..
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AP-014 h h ATTACIDENT II
.Page 1 of 2 Revision 0 PRESERVICE INSPECTION FLOW CHART MAINTENANCE SUPERVISOR
-Coordinates Program-
-Schedules Inspection-
@ INTERFACING ORGANIZATIONS
. -Review Schedule-
-Perform Work-69 TECHNICAU ORGANIZATIONS
-Identify & Report Problems- -
MAINTENANCE SUPERVISOR
-Implements Corrective Action w/in his scope to app. org.-
f/4) PRESERVICE ORGANIZATION
-Resolve Problems-DCC SCE&G
-Perform Repairs-(f) PRESERVICE ORGANIZATION
-Reinspect-
~
W SCE&G
-Document /Insp. & File Report-NRC
-Review-PARTICIPATING ORGANIZATIONS:
- 1. W, DCC QC/QA, DCC S/U,
- SCE&G/NO, AI/NRC
- 2. W, SCE&G/NO, AI/NRC
- 3. W, SCE&G QC/QA, DCC QC/QA, DCC S/U, GAI, SCE&G/NE,
- SCE&G/MO
- 4. W, DCC QC/QA, DCC S/U, SCE&G QC/QA, AI/NRC,
- SCE&G/NO
- SCE&G/NO includes Operations, Maintenance and Start-Up (SCE&G, GAI, & W).
9
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AP-014 Attachment II Page 2 of 2 Revision 0 PRESERVICE INSPECTION FLOW PROCESS
- 1. Maintenance Supervisor will develop a schedule for inspection activities based on inputs from interfacing organizations.
- 2. Inspections will be conducted by the responsible organizations / agencies. Schedule changes will be corrdinated through the Maintenance Supervisor.
3 Problems will be identified by the inspection organizations to the Maintenance Supervisor.
- 4. Maintenance Supervisor will coordinate the resolution of problems with the responsible organizations utilizing approved
. SCE&G procedures.
- 5. Repairs, as required, will be made by either Daniels or SCE&G/NO, as applicable.
- 6. Reinspection of repairs will be conducted by the responsible organization / agencies.
- 7. Inspection results will be reviewed by W, SCE&G and the AI for completeness and correctness.
- 8. The Preservice Inspection report will be completed and filed with the NRC at least 90 days prior to fuel loading.
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f AP-014 Attachnent III
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. . e C! ASS 1 SYSTE.'IS A!!D COMP 0:iEllTS +
N - SCHEDULED EXAMI;:ATI0iiS N N *
\ 'GIL C. SUM:1ER PLA:lT U' LIT #1 \ 7
. m w;;
All items listed below shall be examined to the extent committed to the !!ucler.r Regulatory Cc mission in the Final Safety and Analysis Report. The interrt of this program is to perform a baseline examination of Class 1 systems and compon-ents to the intent of Section XI 1974, ASME Boiler and Pressure Vessel Code 51975 Summer Addenda. All Class 1 examinations described in the Final Safety Analysis Report will be included in this program. - IUB-2600 EXAMIf;ATIO:: ITEM , COMP 0ffEf1T - PROCEDURES U/T P/T V/T
- REACTOR VESSEL .
Bl .1 Middle Shell Course to Lower Shell Course 52 - -
. Circumferential Weld .
Bl .1 Upper Shell Course Longitudinal Welds (2) 52 - - Bl .1 Middle Shell Course Longitudinal Helds (2) 52 - -
~ .- - Bl .1 Lower Shell Course Longitudinal Welds (2) 52' - -
d M; Bl.1 Upper Shell Course to Middle Shell Course
52 - -
Circumferential Weld Bl.1 Lower Head .to. Shell Weld , 5? ..- .. . Bl.2 Lower Head Ring to Disc Circumferential Weld 47 - - 81.2 Lower Head Ring Meridional Welds (6) 47 - - -
~
Bl.3 Vessel to Flange Weld . 52 - - Bl.3 . Closure Head to Flange Weld 47 - - Bl.4 Inlet Itozzle.'to Shell Welds (3) 52- - - i
. ,... .. 4. .
Bl
.r e -Outlet..!;ozzie t.o Shel.1 Welds.,(3)..
52 :. , , m. ., .. . i. Bl.5 Vessel Penetrations, Including Control Rod Drive (1) i Penetrations and Control Rod Housing Pressure - Boundary Welds Bl.6 Primary flozzle to Safe End Welds (6) 205/52 11 - 1 . ,-
't. g Bl.7 Closure Studs, In Place !;/A !:/A i'!/
U Bl.B Closure Studs and I;uts, When Re.noved 15 71 -
. A-P-01.4 ttachment III
, Page 2 of 5 e 'IVB-2600 '
EXAMIl'ATIC'i
~
ITEM COMPONENT PROCEDUP.ES (}-Q ,
, U/T P/T V/I Bl.9 Vessel Flange Ligaments . 52 - -
Bl .10 Closure Stud Washers - - 8 B1.11 Conoseal Bolting ,
~
- 8 Bl.12 Vessel Supports (Integrally Welded) . 52 - -
Bl .13 Closure Head Cladding . - 11 8 Bl .14 Vess'el Cladding . - 8 g . Bl.15' Interior Surface of Vessel and Internals - - 8
\ .
Bl .16! Interior Attachments and Core Support Structures N/A N/A N/A - Bl.17l; Core Support Structures - - 8 o Bl .18 Control Rod Drive Housing 205 - -
, Bl .19, , Exempted Components
~
.. (1)
- cc h '
PatSSURIZER B2.1 .' Pressurizer Shell Welds (Includi.ng Lower Shell 47 - -
. ,, . Repair) EAN279349 .. . . . . . . . .
^
B2.2 Nozzle to Vessel Welds (6) 47 - - B2.3 Heater Penetrations (1) 82.4 Nozzle to Safe-End Welds 205 11 - - 82.5 Pressure Retaining Bolts and Studs, In Place N/A N/A N/A B2.6 Pressure Retaining Bolts and Studs, When Removed N/A N/A N/A
. . . , 82.7 . o j. . Pressure. Retaining Manway Bolt.ing ..
, .. .s .
g,,,......8..,.',.,. 82.8 Support Skirt Extension Weld 205 - - 82.9 Vessel Cladding .
. . - 8
,' B2.10 Exempted Components . - - 8 r *
%t...)
v -
****-.Ae=m.
- AP-014
, Attachment III Pege 3 of 5 IWB-2600 EXAfilllATIO:1 7.' ITE!4 -C0f4P0flErlT PROCEDUP.ES ,(.s d. .
U/T P/T V/T STEAllGETEbATORS(PRD1ARYSIDEl B3.1 , Channel Head to Tubesheet Weld (3) , 47 - -
- 83. 3 flozzie to Safe End Welds 205 11 -
B3. 4 Pressure Retaining Bolts and Studs, In Place N/A N/A fl/A - B3.5 Pressure Retaining Bolts and Studs, When Removed 15 - 8 83.6 Pressure Retaining Bolting -
,- 8 B3.7 Integrally Welded Vessel Supports N/A N/A N/A B3.8 Vessel Cladding -
- 8 83.9 Exempted Components (1) l PIPIllG SYSTE!4S
-/' B4.1 Safe End to ripe Weld N/A N/A N/A A, .
, V ,,) B4.2 Pressure Retaining Bolts and Studs, In Place N/A ft/A N/A B4.3 Pressure Retaining Bolts and Studs When Removed N/A N/A N/A
. . . . . ~ . .. .. -
B4.4 Pressure Retaining Bolting - - 8'
.B4,5 .C.,ircumferential and Longitudinal Pipe Welds 205 - -
- B4,6 ,
Branch Pipe Connection Welds > 6" 205 - - B4.7 Brancit Pipe Connections Uelds 6" Diameter and - 11 - Smaller
" ~
' " ' ~ *
'B4.8 "So'cket Welds -
11 - ? .,.. ...... . .... .
- -" . *
- ;B4.9' ~.... Intogrally' Welded Supportsi. . -4 4' .i. ' D; ' G"?; ..
205' R - B4.10 Supports Components - - 8
~
B'4.11 eye ~mpte'd Components (1) is+- u. . :--. . r,. - . _.) v .
. I
hP-d14
. Attachment III
, PPSe 4 of 5 C' IWB-2600 ITEM COMP 0NEllT EXAMINATIO!!
PROCED'JP.ES C , U/T P/T V/T REACTOR C00LAtiT PUMPS B5.1 Pressure Retaining Bolts and Studs, In Place 15 - - 85.2 Pressure Retaining Bolts and Studs, When Removed 15 (3) 8
~
B5.3 Pressure Retaining Bolts - (8) 85.4 Integrally Welded Supports N/A N/A .N/A B5.5 Support Components '
- - 8 B5.6 Pump Casing Welds .
N/A N/A N/A
. ' ' ' ~ ~ ^ '
.B5.7 -
Pump" Casing-
'(2)
B5.8 Exempted Components . (1) N/A' Flywheels , 41 (4) 8
..;. , .. . . . . . . .. .c .L VALVES . .
B6.1 Pressure Retaining Bolts and Studs, In Place . N/A N/A N/A B6.2 Pressure Retain'ing Bolts and . Studs, When . Removed N/A. N/A. N/A B6.3 P'ressure Retaining Bolts - . (8) B6.4 Integrally Welded Supports N/A N/A N/A _
,B6.5 Support Components -
8 B6.6 V'alve Body Welds N/A N/A N/A B6.7 Valve Bod.ies . (2)
.. B6.8 E .x.empted .w Co.m.p:onent
- .:: ;: ,: ,q_ .
.: < .y ..;.e.
. . . . ; ....: :.; p.: y,.
. . , f.m .. .. 5 . . . ;..1 ::, ., : : . . .
. :. . .(,1 ) . .x-. -:
i .': .-:.i .: :. i . y;
.: , ..y .....;...
- v. .
'
- Ar-U14 . .
. . . , Attachment III
- P. age 5 of 5 L.C.,
-- Il0TES .
(1) Visual during hydrostatic ~ testing. .
~
'(2) Complete'd b'y oth'ers -- us'e shop examination data for baseline information.
(3) flot accessible for examination unless disassembled. . . (4) All surfaces of flywhell are painted and not accessible for PT examination. ft/A Indicates that there are no items in this category on the component or
- i
. system. .
... . ~ . . . . ,. ....:.. > . . . . a. . . . . , ,. ...,.:.-.,. .m.... . .w, . - . n.
s
. . . . . . , . , . s . . .. c . . . , . . , .. . . . . . . . . .
(P
~
g . (U ..
.c.
. . . . . . . . . .. . . . . .. . . . . , f. . . . . .
- . . . : . :. .l : : ...:
. . . .. . .';, ' ', . e . * < . .
.1.; ,} , y.r . > : ;: . ,,.:. , ;..:.. .
. . . ?.. v.. . ..y ::,> ,. ....z .. .
. . ~ . . .. , . , ...
g .
.g l /J . . .
I i _ _ , , _ - _ _ __ _ _ am.r & _ .sNwN
. AP-014 .
. s
- . Attachment IV Page 1 of 6 l O'
CLASS 2 SYSTE:iS A:D C0:iP0ftEllTS SCHEDULED EXA:ll!!ATI0iS h- j VIRGIL C. SU"l1ER PLAtlT Uf!IT #1 N, - N -5 m . 1 . .. qd All itc listed below shall be examined to the extent conhttted to the NucidW ' Regula' .ry Commission in the Final Safety Analysis Report. The intent of this program is to perform a baseline examination of Class 2 systems and components to the intent of Section XI of the ASME Boiler & Pressure Vessel Code 1974 & Summer 1975 Add. All Class 2 exaiainations described in the ~ " " Final Safety Analysis Report will be included in this program. IWC-2600 . . EXAMINATIC::- ITEM ' COMP 0NEllT PROCEDUPES U/T P/T V/7 LETDOWN HEAT EXCHAflGER
~
. Cl .1 Head to Shell Weld .
205 - - C1.1 Shell to Flange Weld 205 - - Cl.2 .. Nozzle to Vessel Weld '
, ...s..... . . . . .
..N/A .N/A .N/A '. -
D Cl.3 Integrally Welded supports N/A N/A N/A C1.4 Tubesheet Flange Bolting N/A N/A N/A
.. . .. x.
- ~
EXCESS LETDOW:: HEAT EXCHA!GER 1
! C1,1 Head to Flange Weld 205 - - I C1,2 Nozzle to Vessel Wcld l
i N/A N/A N/A i Cl,3 IntegrallyWeldedSupports(2)' - II - l C1,4 Tubeshect Flange Bolting 15 - 8 I . .l,
.p - c .:. .. , REGENERATIVE HEAT EXCHANGER-A .: e. ' 17.-? "U f i ' ' b t ' ' '" - C v-
.- ' ' 's Cl .1 Transition Cone to Tubesheet Circ. Welds (2) 205 - -
Cl .1 Head to Shell Welds (2) 205 - - Cl . l' Shell to Tee Circ. Welds (2) 205 - -
.. n b,m) C1.1 Shell to'Tubesheet Welds (2) 205 - -
!! .y l ll Cl .1 Tee to Tee Circ. Weld (1) 205 - - I l: . (I . Cl.2 - Nozzle to Vessel Ucid N/A N/A N/A
. . . . . . . . . ..... Ar-uia Att3.chment IV IWC-2600 EXA!!If;ATIC:t ITTM -
C0!1PO!!Ef!T Page 2 of 6
'
- PROC E Cc'E S U/. i P/T V/T C1.3 Integrally Welded Supports -
N/A N/A N/A ,
~ ~ ~ ~ ~
. C1.4 Pressure Retaining Bo1 ting . N/A N/A N/A RESIDUAL HEAT EXCHAilGERS ".
- C1.1 Head to Shell Weld . . 205 - -
C1.1 Shell to Flange Weld . 205 - - C1.2 Nozzle to Vessel Weld (3) (3) (3) C1 Integrally Welded Supp6its ,, N/A N/A fl/A C1.4 Tubesheet Flange Bolting exceeding 1" Diameter 15 - 8 SEALWATERHEATEXCHAlG5R , . ., ,
' C1.1 Head to Shell Weld .
(1) 11 8
. .C1.1 Shell to Flange Weld .. . . . . , - -
. . . .. . . . , ,. .- . . .(1) .11 8 . .
v C1.2 Nozzle to Vessel t! eld . N/A.N/A N/A C1.3 Integrally Welded Supports N/A N/A N/A C1.4 , , Tubesheet Flange Bolting
- iN/A'N/A N/A
. . STEAM GEf;ERATOR (SECO:DARY SIDE).
. Cl.1' Upper Head to Shell Weld ,
'47 - -
Cl.1 Upper Shell to Transition Cone Weld - 47 - - C1.1 Transition Cone to Lower Shell Weld - 47- - -
..... . . C1. ] . ,',, ,,,,, .,QSpel1.to' Stub fBarre'lJeld.. .. , . ,.
- . , , .. -;.g, .g . 47 3.., . s. ."
' '1. l C "St'ub 'BaYrel to Upper Tubesheet Weld 47 - -
"C1.2 Steam Outlet Nozzle to Head Weld 47 - -
s
. C1.2 Feedwater Nozzle to Lower Shell Weld 47 - -
.(j C1.2 Auxiliary Feet.:ncr Nozzle to Upper Shell "cid 47 - - V C1.3 . Integrally Welded Supports N/A N/A N/A C1.'4 ' Ma'n'way Bolting (Secondary Side) . 15 - 8 M*****hA..*emma.e**=m- w w _ a me.spe=.+ eme.e as e er _ a newsP.. h y . ec ap.
. ?
. - . . . < - . * . AP-014 '
~
At'tachment IV,, Rage 3 of 6
.~l IWC-2600 . . . . EXAMIt'ATIC:'
' * 'COMPO!!E!!T . . PROCED'.'F.ES ITEM. .
hQ U/.T P/I v/T L REACTOR C00LAliT FILTER Cl.1 Flange Weldment to Shell Weld (l) , II 8
' ~
C1.1 Shell to.Lewer Head Weld (1) 11 8 C1.2 - Nozzle to Vessel Weld , ,
. N/A N/A !!/A C1.3 Integrally Welded Supports (4) ,
11 -
'C1.4. Pressure Re,taining Bolting ,
N/A !!/A fl/A - SEAL UATER RETURil FILTER
" ~
Cl.1 $,Il FlhngeWeldmensto'$h$11t.]tdid
'(1)' 11 8' ,
C1.1 i Shell to Lower Head Weld (1) 11 8 i . .
.C1.2 Nozzle to Vessel Weld ,
N/A N/A N/A
'C1.3 IntegrallyWeldedSupports(4) ', < -~ ." - 11 - --
Q ' C1.4 Pressure Retaining Bolting - N/A N/A N/A
~' - -
- -., *VOLUMEC0tTROLTAftX
.- .- .: . . . a .. .
C1.1 Upper Head to,Shell Weld 205 - - C1.1 S.he.ll to Lower Head Weld .
.205 - - .
C1.2 Nozzle to Vessel Weld N/A N/A N/A C1.3 Integrally Welded Support - 11 8 C1.4 Pressure. Retaining . Bolting .
- 15. .- .
.. ... .,.. . ~ -9 :.s . .; 5. : . .L0;,;r :::..s. ; .. .:.:;p.:..;
. 3.. e. . . .
p : .. .. .; .. ... ; . . . .. , 5.. . g . .; .. , ; ,,. . . . . ,. . : ,. : . ..__..;.. . .. . -_ T.' e - Sn: i.i~t' ::. ::r . .: n s:. .
, U. . ' Sis t ' ., .f r. ' ::: .. : .n: .. :
.- Fee:,et . r. - :::- -- .- 5..
, f-O'l m V
C ' . !- Integ re ". . , t'.::: 5.:::..: C *i . dnviayhiu--de::u.5: ' 11 . :
@M . -- -
AP-014
- Attachmen: IV
. , , Page 4 of 6
EXAMINATIO'l IWC-2660 . .
COMPONENT PROCEDU3.ES
. ITEf1 -
L - U/T P/T V/i -
~ '
LETDOWN REHEAT ltEAT EXCHANGER
' ~
~
C1.1 Head to'Shell Weld . (1) 11 8
~
Cl .1 ' - Shell to Flange Weld -(1) 11 8 C1.2 Nozzle to Vessel Weld N/A II/A N/A
'C1.3 Integrally Welded Supports ,
N/A N/k N/A Cl.4 , Pressure Retaining Bolting . N/A N/A N/A
' RESIDUAL' HEAT REMOVAL-pVMPS 2- ~ , - +- .- ~.-
. C3.'1 Pump Casing Welds. N/A N/A N/A
~
Pressure Retaining Bolting 15 - 8
.C3.2 .
'C3.3 -
Integrally Welded Supports ... . : .. . -. . . .. ;. :e . . - I. . I L. ., _ . ._ _ _ .-. C3.4 Support Components . .
- - .8
. CENTRIFUGAL CHARGI"G PUMPS ,
C3.1, Pump Casing Welds .(2) - - C3.2 Pressure Retaining Bolting . 15 - 8 ',
. C3.3 , "Integraily Welded Supports ,
- 11 -
C3.4 Support Components
~
- - '8 l
- 1
. ?. .. p. . :..-: . .. :, : , ..p IP T NG
~
~
.:.i,.*. p .~,.' ,.*. e..g g :a~. .'.;:n .
.. 1 } ... .;.,.;. ...; . *y . . '.'.. .: ... ; j,.
C2.'1 Circumferential Butt Welds 205 - - C2.2 Longitudinal Welds'in Fittings 205 - - V. .
. 1
\ l 1
\'
AP-014 l i'ttachment IV l
. VPne 5 of 6 !
EX/MI!!ATIO.'l G IWC-2600 '
'.
- C0P01 EllT
~PROCEDU.C.ES_
u ITE!4 - U/ f P/T V/T PIPIfiG(Cont'd) . I C2.3 Branch Pipe to Pipe Weld Joings . .
.205 - -
Pressure Retaining Bolting Exceeding 1" Diameter 15- - 8
. C2.4 .
~
C2.5 Integr. ally Welded Supports .
. 11 -
Support Components
- -f 8
.C2.6 .-
~ e .
l
. VALVES . - . .
Valve Body.. Welds .. ..N/A...N/A. N/A ., . l
.C4.1 -
- 1 Bolting Exceeding 1" in Diameter 15 - 8 C4.2 t
C4.3 Integrally Welded Supports . N/A N/A N/A
.C4.4.....~.. Supp. ort Components 2.
...v,........
w......
. . . . . . < 8. . . . . . a . ..
~
cy
.. . . w, .
. ~ .. . . . ".. '
)
. .s .- .
.n . : . ic. p h. . . .n., ,..;...: u , ,. .z . . . p.<: . :: :
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l . . . g 1
.- l 1
.()
-y -
O '.-
~
.I-AP-0,14
- . . .. .. .. .. . . . . . . . . . ... . . ' Attachment IV
. Page 6'of 6 (v .
~ *
- NOTES -
a _ . . . . . . . - (1) Ultrasonic examination not feasible due to limited material thickness. ' Penetrant .. . and visual examination to be substituted.
... (2) Not accessible for examination. - -
(3) lleids not accessible for ultrasonic examination. Substitute
. surfac.andvisualofnozzlereinforcement(saddleweld).
N/A Indicates that there are'no items,in this category on the component.
. ~.
...;. .. . . . . .~ . . , . . .
- c. ... . . . . - . . , ,. .
\
. . . - .... v. . e...a: ,., . .w
= ,. , ......e
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, _ w is.l . . . ?:: .y ., . . ..
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." J DM- -# 'E___ ' PP m__'.. .mi__ m __ ,,,_f ._'gw-
, hM===** * * -
I... m: m . l *c
. _. h: ,- . ___ __ _ _ _ _ _ _ _ _ _
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x.. ..* if; . ~ < ..- AP 014; .
- s. :s .'
c . * .;, . - ,
* : c , -T :
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. A t.t 'a c h tn'e n t .Y c^
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' < j[(f.' , , . , , ,', .' . 4. , ? -
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. : .m .w. n. n: :w.m.c.w, .w' {r.I *! . 'i - l;, g.m.h .m[I . Y.;ir$a.'- c , $li.% 'll * ' \' ' ' . ' .), m
.. x .:_ .
. :,.9 -. s. .3;; .: ' .
i INSERVICE INSPECTION , PROCPut TOR AS!!E. . Page 1 of 26 j * -* , CODE CIASS 3 , e . , C0!'PO?;13TS
. .- r.
. SPIN
- SYSTDI PRESSURE * ' 'VISDAf.' ~~ ~ DESIGN SYSTDt .
6/0K TAC Tr.ST (IWA5000) EIAMINATIO!I FRESS. COMPONE!.*TS 1.TMEER SYSTEM 1.0 CATI 0tt & ilm5000) (IWA5240 & IWD2600) (paig) RD4 ARKS j 1. Resc' tor Coolant s Systeri , , a 1.1-F.D."114 072 ~- RC - Connections to vaste processing I
- Sht. 2. Safety Class ,
. system (WGS) gas decay tanks 3 . .
1.1.1-No Equipment None RC RB/dB N/A N/A N/A 1.1.2-Piping & Valves
- RC RB/AB (1) ' .- ,
(2) 100
, 1.1.3-Piping ItanBers & None AC RB/AB , N/A , N/A N/A Supports >4" t
j 2. Chem. & Vol. Control'i .
- 1. Cation bed and mixed 1.pd' System ~. '
.i denineralizer subsystem
't 2.1-F.D. 114E073
- CS - -
s
- 2. I.ine to boron. recycle systen 9 Sht. 2. Safety Class. ,
,' recycle holdup tank
, 3 -
2.1.1-Cation Bed CSDMCS CS AB-436 (1) , .y (2) 300 . Demineralizer (XDM-8) 2-2.1.2-H1xed Ecd . CSD:0:301 CS AB-436 (1) (2) 300 Demineralizer "A" ,* (XD?:-5A)
- 1 , !
2.1.3-Ittxed Bed . ' .CSIW:tu02 CS AB-436 (1) . (2) 300 Detainer.slizer "B" (Xtitt-58) ',
- i :
Non-Controfed Copy s . ~
- i
.~. y l -
- g. /. - 3 9
.-g ,
- - -y
+
- l. ,
, e .
.,- , , - , . ,4. , .
f ... ,.t. c..
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6;.
,. '.:.: t : . ;*-
; n .*. >u :y!.M. ,3, . .. . .v... , .
g.:.. U.....e )p. e. . . ,.4... r .; . .
;..v . .' : $..c y. .; .v ... . .v
; >.e .
- s. r. . , . ,- ,- . ...
.a .f p:s/ , . . .: ..
.. .7,l .
~v .<. . ~
, , .. . . - 4 L. ~ .. . ' ;= '
*.;., .c .
c, ' ,;. t .s. s.
.\.m. .:.y o :+. n p: v T . '.* -Q.,(,.:. ...: . ;.c. 'w.Mp:.:,J..Q u:..%,.. .
2 . ...
- 4 g;C. '*%.,'.i: T. ',..:*..e...,7 p:n
, .; :.s' i....*.
. . c ' x *. Q% ' n, d ,' . s. ',. . *
- E%Y ' .p,Wr.u p .,U
. . .;n %, u.u.: .
t'& ,.,.. ,.:e'..
;. .':':.wr.2.
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.1. ;'n se .- :. :' :,. 1: ,' ~ . r, s3 e...a,, , .,_g s .,
1 l %
, INSERVICE It:SPECTION PRr **t FC:t AS::E .
I .
< C 155 3 ,.
- Page 2 of 26 1 >. t. ?.itTS .
SPIN Si rt PRESSURE VISUAL ~~ DESICM ST'STDI . &/OR TAG Tn r (IWA5000) EIAMINATION FRESS. COMPC::EtiTS titD!BER SYSTDt 1.0 CAT 10N & IMD5000) (IMA52I.0 & IWD2600) (psic) RD8 ARKS . 2.1.4-Piping & Valves *. - CS AB (1) (2) 300 l . l 2.1.5-Piping ifangers None CS . AB N/A . N/A' N/A
& Supports 7 4" .
7 2.2-F.D. 114E073 4 i Sht. 3. Safety class',' - C5 -
- 1. Boric acid blender subsystem 2b & 3 C. .
* ., 2. Line to W7S vent header a.
2.2.1-Boric Acid . CS!!DBI. CS AB-46) (1) ,- (2)'. 255 . Blender - (XA.I-15) '4 j s s 4 *' . 2.2.2-Piping & Volves - CS- . AB '~ . (1) (2) 255 . l 2.2.3-Piping llangers None CS AB N/A ,
. N/A N/A
& Supports ;P 4" .
( ,. . 2.3-F.D. 114E073
- Sht. 4, Safety Class ,** ,
- TR -
- - '- j - - Entire boron thermal regeneration subsystem a 3 4 , .-
y 2.3.1-Thermal Regeneration' TRDMRE TR AB-435 (1) (2) 300 ,
. Regeneration 01, 02, 03 -
T Dentneralizer & 04 * *
"A. Bi C. D" 1 t
I - 2.3.2-1.etduvn Rcheat TRAttLR TR AB-412 (1) ' !. - (2) 300
!! cat Exctianger (X1tE-15) o
. i
)
, , i
s, . e' e r v
- e. . ., .,
. v ..
.: r
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3 . 3-
. IN$tRVICE INSPECTION -
'FROGPA.t FOR ASv.E l
. . CODE CtJLSS 3
. F88e 3 d H
' . ,e .
CO:!PO!:F 3TS I g 4 . ! . SPIN .,. SYSTI21 FRESSURE VISUAL DESICN SYSTDi - 8/OR TAG e TEST (IWA5000) . EXAMINATION FRESS.
- f. COMrot:ENTS to cER SYST!M 1.0CATfort & IV:0000) (IWAL240 & IMD2600) (pstg) REMARKS 8
. 2.3.3-Litdown Chille? Heat TRAL!LC TR AB-412 ' (1) (2) 3GO l Exchanger (XI!E-8) . 2.3.4-Modcrating !! eat TRAll'Cl
- TR AB-412 - (1) _
. (2). g 300 g Exclanger (XitE-1) 2.3.5-Piping & Valves, 11L As - (1) ,, ., (2)', 300 2.3.6-Piping !! angers . None TR AB -
N/A /,<* N/A' N/A
& Supporta > 4"
- s.
.I .A
- 2. 4-F.D. 114 E073 -
CS . - M - - - Boric acid storage and transfer Sht. 5. Safety class'
't ..
I sub=yste: 2b . . 5 g", 2.4.I'-Boric Acid Tank XTK-12A&B CS AB-463 (1) . (2) ATM + Nos. 1 & 2 .
~
.,. a .
2.4.2-Boric Acid CSFI.EA CS AB-463 : (1) . * (2)' 150 Filter (XFL-14) -
- 2.4.3-Boric Acid < CSAPBA CS AB-436 '
(1) .. (2)- 150 Transf er P. ape ' 01 & 02 .
, ..M "A & B" C:??-M F M -
- s. .
2.4.4-Piping & Valves' ... - CS A5 , il) (2): 150
.g s- .
T
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~
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6 .
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- i. . .
INSERVICE INSPECTION 7
. . PROGRA't FOR ASttE
! CODE CIAS$ 3 Fage 4 of 26 .
Cottrona.TS SFIN . SYSTCt PRESSURE VISUAI, Pr. SIGN ST'STZH 4/OR TAG
' Tl;ST (IWA5000) EKM It:ATION TRESS.
COMPONENTS
}
1:IntBER STSTEM IDCATION' & IV05000) (IWA5240 & IW32600) (psig) __ RYMARRS 2.4.5-Piping Nangers - None CS AB s N/A N/A N/A
; & Supporte > 4" .
t . e
. 3. Safsty inicetton . , #.
yster * . Boron injection surge ta:0 . h re. I. 1 ". injection recire. pumps 3.1-F.D. 114E075 :., - SI - V. - ! . - , - i Sht. 1. Safety Class'
- 2b . . ,
/ h l 3.1.1-Boron Injection - SIATST SI . FB-436 , (1) *
.' (2)* ATM Surge Tank . (KTK-29) , , , ,
3.1.2-Boron Injection SIAPRP
. SI FE-436 (1) .
.; . (2)' 150 -
Rectreulation
- 01 & 02 4 Pumps A & B (XPP-34A & B) , ,
3.1.3-Piping & Valves. - SI FB (1) .; (2) *2735/ *2735 psig for recire. lin'e aa50 frees baron3935,inf ection tank to* valves 8936 & 8927. f . ** Balance of Safety Class 2b
. $. piping is 50 psig.
' 1 -
3.1.4-F1 ping Hangers Ncne SI FB . ' , N/A 'T N/A N/A
& Supports 7 4"
- 7 ,
** . .' .r
+
. 1. , .
. t
. i
.I s, . *'.
. 9
..,t .
g
,3 n.
3,- ps rv m Q = _ -. __ _ y -
.g .
s' %. 3 .
*,*'. '. . a
.. e *
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- g*f ,8* :'.'. r . . . , *'. - * %; . .
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s f.,
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, i, .
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r . * .. - .
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.,v.
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. o . . .8
., j. INSERVIC3INSPECTkO3 -
FROCFAM FCR ASME ' . i CODE CIASS 3 Fage 5 of 26 ' Cott:TNFNTS . ,
, , i,.,
SPIN SYStrl! PRESSURE VISUAL DESIGN STSTDI &/CR TAC . TEST (IWA5000) EXAtt1 NATION TRESS. COMPONENTS TM:3ER SYSTTH 1.0 CATION & 11m5000) (IWA5240 & IWD2600) (psig) Rc ARKS
- 4. Eoren Recycle System '-
.+ All process piping and equipment excepts
- 4.1-F.D. 114E076 -
BR - . - s. i . . #. -
- 1. Recycle evaporator Safet,y Class 3 *
'I. concentrate filter (NNS)
. '.; (
- 2. Recycle evaporator reagent
. - . 3 tank (NNS)
, s
! 4.1.1-Recycle Evaporator * *.BRDMRE BR AB-436 (1) ' *
- 3 (2) . 150 .
- Feed Dcmineralizer - 01 & 02 j".' '
l No. A & B (XDM-4 A & B) . 4: g . . 4.1.2-Recycle Holdup
- XTK-6 A & B BR AB-388 (1) *
. , , , (2) ATM Tanks No. 1 & 2 '.
i* 4.1.3-Recycle Evap. ;- BRF1.RE . BR AB-436 (1) .
, (2) 150
! Teed Filter +
(XFL-7) .-s..
- . . 1 e 4.1.4-Recycle Evap. , DRAPRE01 BR AB-368 (1) ,,. .{ (2)., 150
; Feed Pumps A & B & 02 s ;' .
(KrP-7A & B)
, s
=
l 4.1.5. Recycle Evap. BREVRE BR, AB-412 (1) . (2) 150 .
; Fackage (XLV-8) ,.
4.1.6-Piping & Valves , BR AB . (1) *. (2) ,- 150, 4.1.7-Piping !! angers None BR AB , N/A
"{ N/A N/A
& Supports > 4" .,
. . e p
, .- y. .
s
- r . .
- e -
i - .
,, I,
- e. .
{ .. \ G
.' . .ry eq-
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i . , e . l* INSE'?.* ICE INS?ECT'ON I
. PRCC:/Jt TC:t ASME .
* . CODE CIAS3 3 .. Page 6 of 26 I * *
. Cc::~o::rsts
.:, SPIN
$<
- SYSTDi PRT.SSURE "' VISUAL DESIGN ST'STDI *
&/OR TAG TEST (ll.*A5000) EIA~tINATION TRESS.
{; . C0!!PONENTS
- frJMUER SYSTDt 1.0 CAT 10?e & wn5000) (IVA3240 & IWD2600) (psig) RDtARKS I .
S. Vaste Processing , . l ,
; Sytg 5.1-F. D. 114 E07 7 '
WI. -
'. - 1.
- Discharge header from
, Sht. 1, Safety Class'.
valves 7136 and valves 3 '
'y 7133 to 7137 l
i
. . '. ; 2. *aDischarge line to WPS gas or system 2
i 5.1.1-No Equipment - None WI. AB . N/A , N/A* N/A
- t-5.1.2-Piping & Valves -
- WI. A3 , (Note 1) *' (Note 2) *150/
f .g (* . ea100 5.1.3-Piping Hanger . None WI. - N/A 5 N/A. N/A
& Supports *> 4" *
. e . . *
- v. .
5.2-F.D. 114E077 - WI. - .*- -
- 1. Vaste holdup tank and waste
?
, Sht. 2, Safety Clase , ,, ,
. - . evaporator feed pump and.
3 . filter process piping 9
.y
- 2. Spent resin dischstge from
_ vaste evaporator coc.tensate
. ,', dcmin.
i '" 5.2.1-vaste !!oldup LTAIL*lt UK. AB-374 (1) ,; (2). AT?t Tc*ik * (XTK-26) 3 , i 5.2.2-Maste Evap. kTAPWE VI. AD-374 (1) ., .*- (2) 150 Feed Pump (XPP-27) !
, g 9 ..
s' .
.. g* .
i Y$' ., . ( 6. 7
.y ,
- - - ~ . - - -- -
, _ -y _ .- -
. E
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,3,o . n
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5 t. . ~ n. .--* '..,-
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2
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.: ' . , y.
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e p. . t. .;v...
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. . . .. - ., . . . .e
. . . ..y.. . ...7..
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u,.
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..*i ... . . .- ,!. G ./....',.,9 ::?. .yy s~ :.t *). .W.t. '.i.- *..y. .: 9. .: .
_ , . . .. 1 3 , .. ;, ,. . .. 9 *
, , INSr.RVICE INSPECTION
* * * - PROC W ! FOR ASME .
. , CODE C!/.SS 3 , Page 7 of 26 S. CCt!"CNEhTS .
SPIN SYSTDI PRESSURE VISUAL
. -. - _ - gym -. .. --- ,
DESICM ~~~ ~ 5/0R TAG TEST (3WA5000) E W11 NATION' ~ TRESF. Cc'tPO::D3TS NTisrR SYST!M I.0 CATION & IW5000) (IVA5240 & IUD 2600) (pstg) y De.Aggs 5.2.3-Wiste Evap. WPFLVE VL /.B-436 (1) (2)" 150 Feed Filter (XFL-28) . . 5.2.4-Vasie Evap. ,, WPCvun WL AB-412 (1) (2) f, 150 Package
. , (XEV-29) ;
5.2.5-Piping & Valves , WI. AB (1) ,. . (2). 150 5.2.6-Piping trangers None NL AB N/A N/A. N/A
& Supports > 4" .
. . C' ;f
- 5. 3-F.D. 114 E077 ",7 - WL - . - T, . .- - Spent resin storage sad sluicing Sht. 3, Safety Class. -
. *{ subsysten 3 -
5.3.1-Spent Resin s WPATRS WL AB-412 (1) * (2) 150 ,- Storage Tank ~; (XTK-36) , 7 5.3.2-Spent Resin . WPAPRS WL ' AB-412 (1) [ (2)* 150 . . Slutce Pu:np (XPP-37) Y 5.3.3-Spent Resin WPF1.RS VL AB-436 (1) (2) 150
- Sluice Filter (XFL-38) ,
. 4 (2).
5.3.4-Piping & Valves .- WL AB (1) 150 i 5.3.5-Piping !!.ncers .; None WL AB , N/A ( . N/A N/A
& Supportm 7 4"
- e'
- g . .* ,
e :. .
~k *
*1 .
9
. o s
-=
a
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~-
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t.. g
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; 4 ..f .. : .. .c t.
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.? 8 ~? - '
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.' M. . -. ., . .
r'.-,;( [... .','.(
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- , D ' n. .',,;.'
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.,. . ~ ; . .
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;.. s . ' .".e.:.,....,.:
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. . t .
. INSr.RVICE INSPECTION
.. FROGRA*! FOR AStt3 .
*- 't . CODE CIASS 3 , Page 8 of 26
- COMPONF';TS
.g SPIN . SYSTE!! rRESSURE YkSUAL DESIGN SY' STEM &/OR TAG TrST (luA5000). EXAll1NAT10N l'RESS.
COMr0 net.TS 1R'MBER SYSTDt 1.0 CATION & 11:05000) (IWA5240 & IwD2600) (psir,) RD'. ARKS s Spent resin discharge f rom vaste 5.4-F.D. 114E077 ,- WL - - .r - - Sht. 4, Safety Class. *:.
^
,; monitor tank de:ntneralizer to spent 3 ,
resin storage tank
. .. f, 5.4.1-No Ev;utpment , None WI.
AB .~. N/A - r
'. N/A N/A 5.4.2-Piping & Valves '- WI. AB . , (1) .
(2), 150 5.4.3-Fiping Itangers
- None W1. AB ?. N/A I T N/A N/A
& Supporte ;P 4" *
- s
. 5.5-F.D. 114E077 - . WG -
Waste gas decey tank subsyste:s Sht. 5. Safety Clave 5* process piping, except drain syste:s 3 . y
.. piping a.
5.5.1-Cas Decay Tanks < CitATCD WG AB-388 (1) , .{ (2) , 150 - A.B.C D.E. & F , 01 thru 06 i. 4
~
(KTK-40A . .[ thru . . < XTK-40F) . o .
. .\ . .
5.5.2-F1 ping & Valves ' - WG AB (1) . . (2): 150
's t*
5.5.3-Piping ifangers None WC AB
- N/A .,- N/A N/A
& Support ;> 4" ",
j
.h Y- .
. t I
. .s .
f . 4
. .i '
e kJ. . G)
.(% ~- -
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y .- :: .- . .
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...Q.J. s : .,.f.z j i.'.,y .. '? ~..y ?.* C.)*' l.)j.l y, , , ...l.' '.;i li.?.i i .. _
U.; ; y. .,.. ,
- u- .. u.
l .>. . .
. . I!!S'.:tVICE I!;SPECTION
/ FPERMI TOR ASIiE , s
!- CODE CIASS 3 s
* ,4 ' Fage 9 of 26 j_ C0;tPO:!rt:TS . .-
~~ . - .
. SPIN SYSTDI FPISSURE VISUA1. . DESIGN SYSTDt &/02 TAG ','. TI;ST (IWA5000)
EXMilt ATIO t FRESS. Cc':r0NE:TrS
- Inmnta STSTD( t.0cATf0N
- & lutn000) ~ (IVA5240 f. IW32600) (psic) RDtARKS 5.6-Y.D.'-114E077 - WC AB - - -
- 1. Vaste gas compressor package Sht. 6. Safety Claes * .'
process piping 3 .
. g 5.6.1-Cas Decay . ,, C1!ATCD WC AB-388 - (1) (2) 150 2. Catalytic recombiner paclunge Tanks Cf.!! 07 & 08 ;' . process piping
, (ITK-40C .
3g .., 6 *
. 3. Vaste gas elecay tank subsystem
.s
. .t, ,- process piping s .
5.6.2-Maste Cas
- Ct!APCP 01 & 02 WG AB-388 (1) ? 1
* (2) 150 Compressor A & B .
(XCC-1A & B) .7 / $. 5.6.3-Catalytic CitRECA WC AB-388 (1) {. (2) 120 Recombiner A & B 01 & 02
- a .
* (XIIR-3A & B) p 5.6.4-Piping & Valves .- WC AB * (1)*
i - (2) 150
. . 2 5.6.5-Piping !! angers *'None WC AB (. N/A N/A - *
& Supports ;P 4 '."
. . ",; - S
- 6. T.,ertency Feedustar . ,"
2.ystem *
.
- g ., ,
', ? From condensate storage tank and 6.1-l'.D. D-302-085
, . , , service water system tt. rough
'EP -
- 4 ,', - -
energency feedvster pu=ps to valves r.if ety Cla,s 2t> . ;
]' .j ; . 1009A B, and C, including portiens
.. , of the pump recirculation line
'. ;' . . ~. N ,
6.1.1-condensat- ,- XTK-8 CO YD (1) * (2) - Storage T.,nk ( ATM
..t .
r (- ~
.t. .
s
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m f, . , .. ) . a . . ..- _ . pa s .
... ~
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it e,
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.c w ..w. -..a. ~.GG.; 8.%:'. : .' m '
. . r. . ..a. . .;
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c.
- INSERVICE INSPECTION , .
l PROGR. art 70R ASug'. ,
.* CODE CIASS 3 Page 10 of 26
.' ~
cc:rr0::ntTS
, SPIN 1- SYSTCt PRESSURE VISUAL DESICN SYSTDt *
, 4/OR TAC 7F.ST (IWA5000) EXAMINATION PRPSS.
CC'!?0NE:ITS IMIEER SYSTFM 1.OCATION - & Tun 5000) (IWA5240 & IWD2600) (ps t e:) RDtARKS 6.1.2-Motor Driven XPP-21 A & B EP 15-412 (1) (2)
- 1715 Eccrgency Feedvater# '
Pumps A & B '
- I
(, 6.1.3-Turbine Driven XPP-8 EF 15-41'2 (1) * (2) 2300 Emergency Feedwater. 3 Pump
~-
5.1.4-Er.ergency Feedwater, XST-23 EF 18-412 (1) (2) 88 Turbine Pump Suction . .- Strainer . ,.,- .
. . .t . -
6.1.5-Emerg,. cy Feedwater XST-22 A & B EF IB-4k2 (2)'. Pumps A & B Suction (1) . ' . 88 Strainers
- 6.1.6-Steam Turbine e' TPP-8 EF 15-412 . N/A 4 i
, (2) -
Drive for Turbine' .
~
. Drive Emergency * '. .'
! Fcedwater Pump . - * #
s 6.1.7-Hotor Driven XPS-101 IF- IB (1) :. (2) 1715 Pump Recirculation , s i Orifices . $ ' 6.1.8-Breakdown orifice *. XPS-43 EF Ia (1) . (2) 2300 s 6.1.9-P! ping & Valve - EF IB . (1) . (2)* (4) 6.1.10-Piping Itancers
- IB EF ', N/A (3) (5) N/A #6" and 8" Piping
& Support:s 7 4" -. ,-- ,
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* . INSERVIC3 INSEECTION FRT,RA!! TOR Anf5 '.
Fage 11 of 26 CODE CIASS 3 .
- e. Corr:'o?:E':TS -
s .
.v
. . SPIN . SYSTE!! PRESSURE VISUfJ., DESIC!i SYSTEM 4/0R TAG TI;ST (IWA5000) EXAti1 NATION FRCSS.
COMP 01:ENTS fCf3E*t SYSTfM LOCATION t. IV05000) (IVA3240 & IWD2600) (psig) RDtARKS
- 7. Service Water System.
$,. (
7.1-F.D. D-302-221 - SW - ,. - - - Entire portion shown on this Safety Class 2b *.. , .'. #. drawing. s
=
7.1.1-Screen Vash XPP-44 SW SW-436 (1) , ,. (2) 186 Pumps A, B, & C . AB&C . i 1 , 7.1.2-Service Water - XPP-39 SW SW-436 (1) (2) 110
'. 7 Pumps A, B & C 8, 3&C .' t
~. '
7.1.3-Traveling Screens XRS-2 SW SV-436', N/A (2)'i N/A A, B & C , t , , 7.1.4-Trash Racks XRT-7 SW SW-436 N/A *a (2). N/A A, B & C A, B & C . .
=
s 'a 7.1.5-Piping & Valves - SW' i- ' (1) ,'.-- (2) - (4)
, t .
- s 7.1.6-Pipinc !!sngers *
- SW N/A , .' (3) (3) N/A *24" Fiping
& Supports 7 4*' * *
- s. - . e
. .p . -}
7.2-F.D. D-302-222 - SW - Entire drawing except containment
.S itty Class 2b
')
?-
penetrations (Safety Class 2a) 7.2.1-Component Coding' XIIE-2 A & 3 CC , IB-4 i2 - (1) *f, j (2)' f 60 Tube side Iteat En hanners
- s A & B (tubc) s 7.2. 2-IIVAC Sy: stun XlIX-1A, B & C VU 15-?42' (1) .
(2) 6e Tube side Hech. W. ster . 4 ' Clit tleru A, B & C . .
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., INSERVICE INSPECTION i -
. PROGRAM TCR ASME -
. /* CODE CIASS 3 . .
Fase 12 of 26 CO'It'0 :Ef;TS .
- r .
.. SPIN g SYSTD1 FRESSURE , VISUAL DESICN , SYSTEN .
3 8/0R TAC .- TEST (IVA5000) EIMtINATION FRESS. *
. COMPONEffrS _ NUMBER SYSTEM IDCATION & 1WD5000) (IWA5240 & IW32600) (ps t g) _ REMARKS
. .s c *
; 7.2.3-Diesel Generator. XHE-17 A & B DC DB-4,63 . (1) ', (2) 60 Tube side
- Cooler !! eat ,
- j ',,
Exchangers A & B ] (tubc) -
. . . v' f
7.2.4-Service Water *
'XPP-45 A & B SW IB-412 . ~
(1) .. k (2) 185 Booster Pumps
- 2,'
A&B .i t 7.2.5-Expansion Joint . XEJ-40A & B SW DB f'. (1) g:. - (2) 60 54 to Diesel Cen. T* . Coolers A & B , ,.. f. li ; ,
- . . +
7.2.6-Expansion Joint XEJ-41 A & B SW DB (1) , 'l * (2) 55 SV to Diesel Cen. *
i Coolers A & B s'
- 4. '
. 7.2.7-Reactor Eu11 ding . XAA-1A !. B AR RB-463 ,
(1) , (2) *
- 188 Tube side -
, Cooling Unit . . . .
Plenu:ns A & B -i- . 7.2.8-Reactor Building . * ,XAA-2 A & 5 AH RB-463 (1) I 3. , . (2) 188 Tube side Cooling Unit N . ', f Plenums A & B -
. C,
. .~.
7.2.'.t-Piping & Valves - SW (Various).. - (1) .
< (2) (4) 3 7.2. ! )-Piping !!. igers ,
- SW (Various) N/A :(
.i;. (3) (5) N/A *6", 8", 10", 12" 16", 20",
& Supports 7 4" ..
24" and 30" s .z r
- 3. Inesel Cenerator , . ; . --
Ds' b S! g ,
., g
. , /. 5 N, . .
t r * - ; *
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. l INSERVICE INSPECTION .
PROGRAM Toa AS}c
~. . CODC CIASS 3' .
4 .- , cc rroN ntTs Page 13 of 26 ,
. SPIN SYSTDI PRESSURE VISUAL DESIGN STSTEM ' ; &/0R TAC .
TEST (IWA5000) EKAMINATION PRESS. COMPo m rs !.vinER SYSTrx 1.oCATTok & Jun5000) (TVA5240 & IUD 2600) (pstr) RryARKs
~
, 8.1-P.D.' D-302-351 . . - . DC - - - -
- 1. Tuel oil storage tank to Safety Class 2h , , fuel oil transfer pump 8.1.1-Diesel Cen. i XEC-1A & B DC DB-436 ' N/A . (2) #.- 2. Tuel oil transfer pump to (Fuel System) .
day tank
- 3. Day tank to diesel generator 8.1.2-DC Fuel Day ' XTK-20A & B DC DB-436 (1),
. .b (2) Ant Tanks A & B . N
-1 .
t
.XTK-53A & 5 3.1.3-0C Fuel oil DC YD (1) ;, .
. (2) ADt -
Storage Tanks . i . A&B , 4,
- 8.1.4-Suetion Strainers XST-88A, B, DC
( . YD .t (1) ,, , (2) 0 .- for DC Fuel 011 C&D .', * , Transfer Pueps *
?
- A thru D . < . -
8.1.5-Diesel Cen. '
- XPP-14LA & B DC DB-427' (1)'-
(2) 70 9 i Fuel 011 Transfer Pumps t A&B * **
- I 8.1.6-Diesel Cen. . XPF-4A & 5 DC DB-436 (1) ' ' *
. (2) .70 Fuel Transfer .
Fumps A & 3 . - *
, F .
. 3 3.1.7-Piping & Valves DC DB & YD (1) (2) (4)
{- .
'
- None 8.1.8-Pipe Itancer DC DB & YD N/A N/A J'
N/A
& Supperta :> 4*' ,
, 1 -
li
, (, 1 -
,8- 8 '
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.t .. INSERVIC: INSPECTION
.- PROGRAM FOR ASME
' ' . ~ CODE CII.S3 3 Fase 14 d 26 COffi'O 3CITS . .
* ~
. SPIN . SYSTD1 FRESSURE VISUA1.' DESICN j STSTDI &/OR TAC . TEST (IWA5000) EXA!!INATION FRESS.
e COMPONEt.T5 . NUl*BER SYSTEN IJDCATION & IMD5000) (IWA5240 & IWD2600) (psig) RTXGKS ] - ' I 8.2-F.D. D-302-353 *
- DC -
- . - Diesel generator air starting Safety Class 2b Package
+. .
i 4 8.2.1-DC Air Receiver
- XTK-9A, 5 DG DB-436 " (1) #, , (2) t,, 480 Tank A D, C & D . C&D -
* ,0 *.
i 8.2.2-Diesel Cen. . XNA-7A & B DC DB Roof . N/A '.- (2) N/A 8 Huffler/ Silencer * ' A&B . \ .' ' 8.2.3-Diesel Cen. . XIID-IlA, 5 DC DB Roof. N/A j, ? (2). N/A . Air Filter . C&D . 4 Silencer A, B, ,-
- C&D *
+,- '.
..u .. ( i' , 8.2.4-Piping & Valves - DC DB e, (1) .
. i. (2) (4)
-. . .' 5-8.2.5-Piping !! angers
* .DC DB r N/A .
?- (3) (5) -
N/A *6" and 20" F1 ping
& Supports 7 4"
- j *
-i .
- 9. Component Cooling . , , ,
- e. Water System i H .
.e .1 9 '
9.1-F.D. D-302-611 .- CC '- '
.{
- - Entire drawing except chemical
.,- injection subsystea 9.1.1-CC llent .
XI!E-2A & B CC IB-41'2 (1) , (2) 150 ExcW ngers A & B * (slic1L side) , f p . # 1 ;.
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g . I g 6
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. . . INSERVICE INSPECTION .
- j. PROGRA!! TOR ASME;*
.. CODE Ct. ASS 3 . Fase 15 of 26
. .32
_ C0:1r0::1037 5
.. SPIN
- SYSTCil PRESSURE
- VISUAL D:'.SfCT SYSTDi '
8/OR TAG , TEST (IWA5000) ' EXA.11NAT10N FRCSS. COtfPON!!!TS IMf5ER SYSTFM I.OCATTCN & 11:D5000) (IWA5240 & 11:02600) (peig) REMARKS 9.1.2-Residual I! eat . XI!Z-5A & B RH AB-412 (1) , (2) 150 Removal !! cat . (RITAllRS 6 Exchangers A & B 01 & 02) , c. (shell aide) *
. 1 9.1.3-CC Surge Tank i XTK-3 CC AB-463 (1) -
(2) 15 i . , 9.14.-CC Pursps A,B,&C XPP-1A,B &C CC 15-412 (1) ;I, . ' Sl (2) 150 9.1.5-CC Pump Strainers XST-5A. B & C CC 15-412 (1) '.'
* (2) - .
30 . A, B & C . l ;-
~*
; 9.1.6-Piping & Valves - CC AB &,IB (2) ; (2) (4)
- 9.1.7-Piping I! angers
- CC AB & IB ~
N/A , .* (3) (5) N/A *16", 18". 20" and 24"
& Supporta > 4" },.,
t.
. . t -
/
9.2-F.D. D-302-612 - CC - - . . - - Entire drawing except contain=c'nt
,..j . penetrations 9.2.1-Reactor Coolant XPP-30A, B. & C RC RB-436 (1)
." . (2) - (a) 2485 Pump Casings j (RCPCPC01, 02 & e, /
(b) 150 (a) Thermal 03) ,' { Barrier ] (b) Upper / Lower Sc.arings 3* '.
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. . . INSERVICE USPECTION
! PROGRAM PO3 AS21E .
CODE CLSSS 3 Fage 16 of 26
- j. CCYront"NTS-o .
+
SPIN . .. S. TD1 PRESSURE
- VISUAL DESIGN SYSTDi '. 6/0K TAC ', TEST (IWA5000) ZZA'{INATION TRESS.
COMPONENTS h At3ER SYSTD( I.0 CATION & IVn5000) (IWA5240 & IWD2600) (rsig) RD'. ARKS 9.2.2-Excess 1.ctdown X1tE-9 CS .RB-436 (1) (2) 150 fleat Exchanger (CSAtlEL) . . (shell side)
- v, 9.2.3-Reactor Coolant XIIE-12 WI. RB-412 (1) . (2) 150 Dr. sin Tank !, (WPAl!RD) '
Itcat Exchanger . ,. . ," - (Shell side) '.
~
'. e. .r.
9.2.4-CC Booster 15-412 (1) 4 (2) 200 XPP-58 CC . . Purnps A, B & C j. . i' ;
- 9.2.5-Piping & Valves .8
- CC
- RB & B -(2) (2) - 0)
- i. Y[ *6" and 8" F1 ping 9.2.6-Piping l! angers ,
- CC RB , N/A (3) (5) N/A ,
& Supports ;> 4" ,
.1 .
.. A. .
if :. . . . 9.3-P.D. D-302-613 . - ,
- CC - ' ,i -
l ( - - Entire drawing i '- 9.3.1-Letdown 11 eat ** X1tE-14 CS AB-412 (1) i ), (2) 150 . Exchanger (CSAltLD) .
.) .
(Shell side) ,
~
- 9.3.2-Seal Water X1tE-11 CS AB-412 (1) -
(2) 150 lient Exchanger ,(CSAllSW) ; i . (Shell side) -
.,? .
- i. %-
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INSERVICE INSFECTION FROGRAM TOR ASME . CODE CIASS 3 l Fage 17 of 26 CO:!PONENTS :
. =
~
} . SPIN SYSTD1 PRT:, SURF.' " ' ~ YIsUAL" " DESIGN ST'STDi 4/OR TAG TEST (lu.5000) EXMtI!WIION FRESS. COMPCNENTS 1: UMBER SYSTEN LOCATION & Itm5000) (IWA5240 & IVD2600) _(psig) REMARKS 9.3.3-Sp'ent Fuel . X11E-7A & B SF AD-397 (1) - (2). 150 Ilest Exchanger ' } A&B (Shell side) -[
- 9.3.4-Radioactive XCE-3 A B &C SS CB-412 * (1) i .I. (2)- 150 Scsple Coolers ,,- .?
? .
A,B,&C (Shell side) , a 4 - Stm. Gen. , ., .-
. f . .' , .
9.3.5-HadloactIve - ': XCE-4 CB-412 , (1)- Sample Coolers SS '
^ (2)' 150 .
(Shell side) *
. , f, .- g R.C. Loop B .
p ,, 9.3.6-Radioactive XCE-2 SS CB-412- (1) (2) 150 Sample Coolers , ;< f . (Shell side)
- R.C. Loop C .
. f.
. ! y
( 9.3.7-Radioactive . -~'XCE-5 SS CB-412. (1) ',. (2). , 150 j Sample coolers , (Shell side) . .* Rl!R Loop ** j,
. 7 9.3.8-Radioactive .XCE-1 SS CB-412 (1) *
(2)- 150 Sampic Coolers . j . (Shell Side)
- Pressurizer i ',
' 4 s
i
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.t . INSERVICE IN3?ECTIO.1
,' . PROGR.u! ro:t ASME.*
CODc crass 3 -' , . Fase 18 of 26
- s C0tfr0NE!3TS -
$. ~
SPIN ** SYSTDI PRESSURE ' VISUAL DESIGN SY' STEM &/OR TAC - Tr.ST (ItJA5000) EXMtINATION FRESS. COMPONENTS ta.0!3ER SYSTTM LOCATION & 1WD5000) (IVA5240 & IUD 2600) _ (psic) R D'. ARKS 9.3.9-Weste cas . XCC-IA & 5 WG AB-388 (1) (2) 150 Compressors A & B . (Ct!APCP01 . I (Shc11 side) s & 02) .
. 3.s j' i '.
9.3.10-caea1yc1c XilR-3 A & B VG AB-388 (1) J. y (2) 150 . Ilydrogen (CI!!!ECA01 & 02) 1 . Recombiners A & 3 ' . S. * (CCV Side) * * -' .
. < 4
?.3.11-Waste Evaporator XEV-29 WI. AB-412. (1) 6 (2). 150 Package-shell . (WPEWD)
! T*. f. ,
e side of: * . 4 * (a)Ev.sp. condenser [
- j 'V (b) Ventilation .) .k
- condenser **
1 ;i . (c) Distillate *
.) ,
Cooling *
. t . . .
s 9.3.12-Recycle Evaporator
- XEV-8 BE AB-412, (1) 1 (2) 150 .
Packa ge-shell , (BPT.NE) , (a) Evap. Condenser' I, Y . (b) Ventilation '? ; y, . . Condenser *
., (
(c) Dluttilate *
- P Cooling y .:. ;
=?.
- b *
. a
.. ..z. .
. . . e s
4 s. t
. t ,
- g.
, f, .
. l'T . ,
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. .,.. -..,a....
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! ,.' I';.1 - .. . ;l. .* ;\ ...:"'.:....t...
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INSERVICE IttSPECTIO:I .
. FROGRAM TOR ASME.'
- I"8' II O CODE Cif.SS 3 '
cc TO?:Cas
. e .l ,
SYSTDI - SPIN 4/CR TAG SYSYDi'rRESSURP.
- TI'.ST (IWA5000) .
VISUA!. EKAMI::ATION DESICN FRESS. COM70'IE ~r$ IMtBER SYSTPM 1.0 CATI'ON & IW5000) (IWA3240 & IWD2600) (psic) RD4 ARKS 6 9.3.13-Piping & Valves - CC AB&CB- (2) ', (2) (4) 9.3.14-Pipe Hengers ' l.
- CC AB&CB* N/A (3);(5) N/A *6", 8", 12", and,16" Piping
- 6. Supports >" 4" * -
9.4-F.D. D-302-614 * - CC - -
- - Entire drawing. .
,. e .,
9.4.1-Residual Iteet
- XPP-31A & B R!t AB-37,4, (1) }.. v. (2)' 150 Removal Pumps (R!!APRit 01 & ,
( A&B . - 02)
.4 I
- 9.4.2-Piping & Valves
.- CC - AB
. (1) e. .
(2). (4) 9.4.3-Piping !! angers . Nano CC N/A ., N/A l
,g . N/A- -
N/A
& Supports ;P 4" . ., . :
g, e ,
. ~ ,,. . '
- 10. Spent --Fue' *), s Y .
. . ,. s .
. Cooling 5,.+ tem .
- as ;
, 10.1-F.D. D-302-651 .- ST - 4 -
i' ' 'i *
- # Entire drawing, excepts *
.i <
10.1.1-Spent Tuel XRE-7A & B SF AB-397 (1) i (2). 84 1. Spent fuel purification subsystes
),'.
Itcat Exctianger .. , which is N:iS except spent resin A&B y lines to spent resin storage tank q t- . . 10.1.2-Spent Fuel XPP-32A & B SF AD-412 (1) $. (2) 84 2. Containment penetrations (Safety Coolinr. Pumps
.; * / Class 22) . A&B '. -
ei# i , 10.1.3-Sp:nt Fuel XST-8A & B SF AB-612 (1) g ? * (2) 35 3. Refueling water storage tank (Safety Class 2a) rump Suctton , Strainer:s A & B .; , ,
. t. ' 'i -
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g . . g ;. . . 2NSERVICE INSPECTION . I PROGR.t't FOR ASME - Page 20 of 26 i t
. '. CODE CLASS 3 .
j -
. Co ro*:ctrS-
, ) -
l
- SPIN SYSTDI PRESSURE VISUAL D2 SIGN
; j SfSTDI &/CR TAG . Tr r (I.A5000) . EXAMINATION FRESS.
; COMPO!iD;TS Nt!HBER SYSTDf LOCATION
_ & 1MD5000) (IVA5240 & IWD2600) (pstr) RDr. ARKS
- =
10.1.4-Piping & Valves - SF AB . '. (1) (2) (4) 10.1.5-Pipe stangers
- SF AB , N/A -
(3) (5) N/A *10* Ftping
. & Supports > 4" , s * --
,. .s
.- .j ,*f
- 11. Reactor Building . .. . .
Spray System .r. -
, -'T - .
1 .. 11.1-F.D. D-302-661
- SF -
s,. . ( / -
- 1. Sodiu:s hydroxide storage tank to valves 3013A, 3
. .- .~ ,.,' .
11.1.1-Sodlum ' XTK-60 SP /j (1) ;- (2) 3, Ilydroxide i. 3 - Storage Tank-
! f ,
- 3 ?
11.1.2-Fiping & Valve - W ;N (1) '. (2) (4)
. SF . .
11.1.3-Pipe Itangers . None SP YD 2 N/A I N/A N/A 6 Supports 7 4" ? 6-
. 1a .
- 12. Excess I.fquid
*, ,, f, ,
Umste Processing .
-& Storaec System .*N .* ~.
..t
- 12.1-F.D. D-302-734 - WX -
12.1.1-No Equipment . None MX FB E N/A - 0- N/A N/A Line from vaste holdup tank to valve 6325A 12.1.2-Piping & Valves ' - WX FB (1) .(,. f* (2) (4) 17.1.2-Pipo Ifanr,cra None. , WX Fn , 2 N/A i ~ N/A N/A *
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, s ,]INSCRVIC::IN3FECTION I * *
* * * .:
- FECCPw'J! FOR ASP.E .-
. , $* CODE C1 ASS 3 .
. Page 21 of 26
- t, COM:'ONC3TS
, SFIN . SYSTDI PRESSURE -' VISUAL DESIGN'
[ SYSTZH &/OR TAG ', TEST (IWA5000) EXN11 NATION FRESS. I COMPO!ENTS N'JMBER SYSTEM !.0 CATION & IWD5000) (IWA5240 & 1WD2600) - (ps_f g) RD8 ARKS l . I , 13. Nuclear Samp1tna j systein *
- f -
13.1-F.D. D-302-771 - SS - .* - 4 ,
- #. - Entire drawing except*
. .? ? '
. 13.1.1-No Equipment
- None SS CB N/A '. . N/A N/A 1. Containment penetratter.s for
. . J ", satspling lines (Safety Class 2a) o g
**y
. ' 13.1.2-Piping & V'alves - SS CB ,Y-.,* (1) (2) " (4) 2. Nue1 car process sarrple lines
~ * .f * '
- inside reactor butiding (Safety 13.1.3-FJpe llangers I
- None . SS C8 N/A i;
. N/A. N/A Class 2a) i & Supports ? 4".
- 1:.
r . s.
- 3. Sampling packages (NNS)
, ,, 4. Sainple 1tne from Volume Control .
> J'.
< ,' 3 .
4-tank (SC-2a)
- 14. Reactor m heup : 5 . -
Water Systes ; * *
'r- .*
14.1-F.D. D-302-791 - HU - *jl, . - - ~ Fros reactor esakeup water storage tak
,, o $ through pumps to makeup to spent fuci
' 14.1.1-Reactor Hakeup XTK-39 NU TD 't (1) .
* (2) ATM cooling and boric acid blender.
Water Storage , , Balance of system is N't$. Tank .:.
. i 14.1.2-Reactor m keup XPP-40A & B MU AB-374 (1)
- i. - (2). 210 Wa t e r l' umps , ,
A&B .
. ,e r -
.. 9' b
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. .i
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. 6
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o . c ., ,- i. i ! - INSERVICE INSPECTION
. - rnocrus ran A$nE : -
.. CODE CIA 35 3 Fage 22 of 26 .
. . g,. COMPO!;r. fits - -
- o .
. SPIN SYSTEM FP.T.SSURE VISUAL DESIGN SYST) &/OR TAC . TEST (IWA5000) EXA'.tINATION FRESS.
COMPo? ,.1 ,. NWISER SYSTEM !.0 CATION & IUb5G00) (IWA5240 & IW32600) (psis) Rt24 ARKS
. 14.1.3-Piping Valves - W AB & YD (2)
(2). (4)
. < '7
- 14.1.4-Pipe llangers . None W AB & YD N/A : N/A N/A
& Support pr." "',- O S 8
J a
' 15. Ch111ed uater .>
'i
- System y ** .
.. Y .
15.1-F.D. D-302-841
- V'J -
* - - Entire systen, except:
1* w . 15.1.1-Expansion KTK-113A & B W . IB-43'6' (1) }l. ; (2) - i 90 1. Chemical feed subsystes. Tank A & B - *
, . 2. Deminera11 red water makeup 15.1.2-IIVAC tiech. . , X1tX-1 A,3 & C W 15-412' (1) 0. , e -
(2) 90 Water Chiller 1.' l' .
)
A.B & C (Shell side) , Y 15.1.3-liVAC System XPP-48A, B & C W IB-412', (1) : (2) . 90 i f
. Chilled Water ,
f , . . Pumps A. B & C - - **
* . . .E. ,
15.1.4-Piping & Valves - W. IB (1) ;. - (2) (4)
- 15.1.5-Pipe Itangers
"# . W IB ., N/A ' k. ) . (3) (5) ,
N/A *6" Pipins .
& Supports 7 4" , .
.s . .
15.2-F.D. D-302-842
- W - ;- -
f,* - - Entire system, except
- . D-302-843 .* i
.i. . 1.
. w.
.' 4 Controlled access ares, cenruter roen. Instrunent repair slwp
-g ,
coalute 4 .
. 4. - .
A . 4 *
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. - INSF.RVICE INSPECTION FROCr/Ji FCR ASME -
CODP. CLASS 3 Fage 23 of 26 COMPOND4TS i
." SFIN ,f ' SYSTE!! PRESSURE VISUAL ~~~hYi! F STSTC( &/OR TAG .
TEST ( WA5000) EXAMINATICN l'RESS. COMPONENTS Pr!3ER SYSTDt LOCATION & 11.115000) (It'A5240 & I'.D2600) (psin) F:D'A.'dKS 15.2.1-ESF Switchgear XAll-6 VL 15-485 (1) '. (2) 90 2. Turbine building switchgear, IDA Room .. , CF.D'1 switchgest room coolere, Cooling Unit - Coil *,' - . -
, and BOP charging space unit Nos. 1 & 2 , .
15.2.2-Co. trol Room , XAll-12A & B AH CB-485 (1) V , (2)' 90 Coolint Inits A & . 1 ., B (with coil Nos. .'
. 1 & 2 cach unit)' ,.
S*
. r .
15.2.3-Relay Room *
. XAH-13A & B AH CB-485 (1) E .. '
(2) 90 .
- Cooling Units I .
A&B t .
- J 15.2.4-Eattery Room
- XA!!-24A & B AH 13-48'5 (1) .- (2)7 93 .
j Supply Air IL ndling . . i Units A & B .
., s .
t' . . x. . 15.2.5-Speed Switch XAH-19A & B VL IB- @ (1) ')* f. (2)' 90 Rooms Cooling , . .,, ' Units A & B , -,A ,
. s' ..
15.2.6-Charging /SI Pump Room No. 2
/
XAH-2 VL AB-388 ' (1)
,3
. (2) 93
.a Cooling Unit .
y, ' a 15.2.7-Charging /SI , XAll-1A & B VL AB-383 (1) ) - (2)' 90 Pumt Roon No. 1 . . - n' 8 .
& 3 Cooling Units ,
r - A&D , s t . r- .: 15.2.8-Aux. Bldg. HCC XAll-32 VI. AD-4'12 (1) *-
, (2)- 90 Switcl'r...nr Air . . .
ILinJllur. Unit ,I. e .
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.' ' '. INSr.KVIC: INSP::CTION
. PFCCTJM 70't ASP.: Page 24 of 26 *
~
C00E CIASO 3'
. r COMro::C:TS - >$ d I
. ; SPIN . . SYSTDI PRrSSURE VISUA1. DESIGN . .
. SYSTEM
&/OR TAG >' TEST (IWA5000) EXAMINATION FRESS.
COMPO::ENTS _ NL';1CER SYSTfM 1.0 CATION & IVI)5000) (IVA5240 & IVD2600) __ps!g) ( _ prMARKs 15.2.9-RitR/ Spray XAII.4A & B VL AB-.385. (1) , (2) 93 Pump Roon .
. Units A & B .
15.2.10-Energency XAH-11A & B VL 23-485*. (1) (2)- 90 W Purp Roon . Cooling Units - t .
. =.
A&B .. v.
,- I *
. .i '
15.2.11-SW Booster . XAH-9A & B VL. 15-485 (1) . (2) .* 90 Pump Ares , Units A & B - e . . 15.2.12-Corponent ,HPP-IA & C CC 18-412$- (1)
. . (2)' 90 Cooling Pumps A
- l ,.
& C Motor -
Coolers (D-302-842) 8. ', 15.2.13-Component
- HPP-1C . CC 15-412,.. (1) f, (2) 90 Cooling Pump C .
Hotor Cooler *
- ' ,e 4 (D-302-843) -, ,
*, . , s. .
f 15.2.14-ESF . XAH-8 VL 15-485'?" (1) - (2)! 90 Switcligear IDS ** J [ ' - Coo 11ng Unit B ** I * -
=
J., w
- 15. 2.15-Ainx. Bl<!g. . XA!!-33 VL AB-463 (1) 1* -
(2)' 90 itCC Sultcligear Air * - Ifandling Unit .f a, .
. s.
+ .*, .
l n
. J' - . 3 a .
1 - g o', et.
- e l
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' q g
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. . .i u . .
. .- n. .
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. . INSERVICE INS'rECTION
* ',' Tr.0G:T! Toa ASM3 .
Page 25 of 26
'., COD:" . CIASS 3 CO*tPONENTS '
.' 5' ~'
3
. . SPIN % STSTD! PRESSURE VISUAL DESIGN -
SYSTZN 5/OR TAG . TEST (IWA5000) EXAMINATION FPISS. COMPONCTTS KU:15ER STSTFM 1.0 CATION & IMD5000) (IVA5240 & IWD2600) (pstg) RD' ARKS 15.2.16-Clorging/SI .- No tag No. 51. AB-385 (1) . (2) 90 5 Pump Gear & 011 ' ~ Coolers A.B & C - .
), t 15.2.17-Piping & Valves - W AB C3 & IB (1) g (2) (4)
. v.
15.2.18-Pipe it.ange.ra * .W AB,CB[&IB N/A (' (3) (5) N/A *6" Fiping
& Supporta 7 4". . ., . ,
.. e.
- 16. Post Acetdent -
liydrofon Removal , .7 . . . I System , I. . D .
. *: . N l )
16.1-F.D. D-302-861 - MR - Y - ;-
- - Tubing lines to and
',i, i from the portable
, 16.1.1-No Equipment ,,. None HR - N/A '
N/A N/A hydrogen analyzer .
,h t connections to the 16.1.2-Piping & Valisa - 11R AB ., (1) J (2)
(4) containment isolation
, valves. .
16.1.3-Pipe Hangers None HR , AB . N/A }. . N/A N/A
& Supports 7 4" * : - .
.I* 8
- 17. Main Steam System -*
- i
-P*
I . : s 17.1-F.D. D-302-011 .
- HS - - 5.' - -
From main steam line to EW P turbino. 17.1.1-EWP Steam Stratact XST-36 HS. 15-412 (1) ? (2) 1284 i
- 17. 3.2-Emergency W Fump - - -
-[
Sccam Turbine is, ' indicated with the . .s.* 7 "EF" System ..
. s. - *
,,, . . t* i
. .s .
. e , 3 .. .
5
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- INSERVICE INSFECTION
.g PROGRA*f FOR ASME Fage 26 of 26
. CODE CIASS 3 .
CO :70!!C;TS *
. SFIN .s' SYSIE!! PRdSS!!RE VISUAL DESICN ST' STEM } 8/OR TAC ZXMtItMTION
, TEST (IWA5000) TRESS.
COMPo?iENTS NLHDER SYSTDt IDCATION & IUD 5000) (IWA5240 & IwD2600) (psin) RetARKs 17.1.3-FJping & Valves - MS - (1) (2) (4) { . 17.1.4-F1pe Hangers
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AP-014 Attachment V Page 27 of 27 IliSERVICE I:1SPECTIO: PROGR/JI . FOR ASME CODE CLASS 3 COMPO!!E;lTS y& - O - Note (1) - Components will be pressure tested and examined at least once during the 10 year inspection interval (IWA-5000 and IWD-5000). The test pressure is to be 1.10 times the design pressure. e - Note (2) - Visual examinations shall be conducted for evidence of uncontrolled co=ponent leakage, and structural distress or corrosion during periods of system operation at 1 cast
- once every 3 1/3 years of the 10 year inspection interval (IWA-5240 and IWD-2600).
Note-(3) - Supports (restraint.s) and hangers shall be visually
- examined to detect any loss of support capability or cvidence of inadequate restraint. .
Note (4) - See applicable GAI flow diagram for.. design pressure
'd6marcations.
Note . (5) - The GAI Pipe Support' Design List gives the code class 3
,. c. .su... .. ..- ~ . hanger and support mark numbers that require di=crisional
. . . ..... -.< - F.
verification during inservice inspection. The drawings .;.. - giving ~ the dimensions are referenced for each item on the Design List. . Q. -
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AP-014 s
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Attachnent VI Page 1 -of- 4 .
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INSERVICE TESTINC OF Pt:MPS FOR THE V. C. St%CR NL' CLEAR. STATION I Tag No. t
, Physical Flow Test Treq.
Description & B/M Sys. Location Dias:. No. & Ret'es. Criteria Remarke
- 1. Motor Driven Energency Feed XPP-21 A&B EF IB-412 302-085 Monthly !Ceneral: The pu=ps can be tested during *
. Watur Pumps Rev. 3 Notes (1). Note (3) ,startup and shutdown. Tha RJd-la (2) recirculation lin. can be used '
T: b Note (6) as a test loop. Pg Note (4) '
- 2. Turbine Driven Emergency XPP-8 EF IB-412 302-085 Monthly Ceneral: The pumps can be tested during Tecdwater Pump RJd-1 Rev. 3 Notes (1). Note (3) startup and shutdown. The (2) , recirculation line can be used Tb Note (6) as a test loop.
Pg Note (4)
- 3. Service Water Pue:ps XPP-39 SW SW-435 302-221 Monthly Ceneral: Pueps are tested in the norrwl A.B&C Rev. 4 Notes (1). Nate (3) operating moJe. (Discharge routed RCe-1 (2) throuj;h service water cooling loop).
Tb N te (6)
,Pg Note (4)
, 4. Service Water Pumps XPP-45 A&B SW 13-412 302-222 Monthly i;eneral: The recirculation line can be used
, RCe-4 Rev. 5 Notes (1). Note (3) as a test loop.
~
(2) - T:b Note (6) Pg: Note (4) ,
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- f Tag No. Physical. Flow Test Freq. ,
Description & 8/M Sys. 1.ocation Dia2. No. & Reg'ts. Criteria Recarks' 3 Diesel Cenerator Puel 011 XPP-141 A & B DC DC-436 302-351 Honthly ,Ceneral: Pumps are tested in their normal Transfor Pumps El-3 Rev. 2 Notes (1). Note (3) mode. (Fuel oil is rumped from the (2) storage tank to the day tank and re-T bt Note (6) turned to the storage tank via the
/Pg: Note (4) overflow). The inservice test for these
, pumps is best run when the diesel genera- 6
, . tors are tested. This is a fixed resta- 3 tance system and flow rate is not re- ?
. quired to be measur=J if AP is. ;
I
- 6. Diesel Generator Puel XPP-4 A & B DC DB-463 302-351 Monthly . Central: (. Pumps are tested in their nore.1 mode.
Transfer EI-3 Rev. 2 Notes (1). " Note (3) (Fuel oil is pumped from the storage (AC) Pumps (2) .. tank to the day tank and returned to .
'.Tb t Note (6) the storage tank via N overt 1uw). The
.P i a Note (4) inservice test for these p. .as is best run when the diesel generatorm are tested !
This is a fixed resistance system . 4 flow rate is net required to be swasureu ; If a P is.
- 7. Component Cooling Pumps XPP-1 A. B&C CC 15-412 -
302-611' Monthly ,' General Pumps can be tested in the normal loop . RCa-2 Rev. 4 Notes (1). Note (3) or threugh the rentdual heat remavat neat (2) exchanger. The Icw speed mode is the - T:b Note (6) aade required for safety. The pucip , Pg Note (4) running during normal operation w!!! ha<e ' to be run at the low speed. Reference , valves will have to be established for the normal loop and/or the residual heat j removal heat exchanger loop whichever is ; selected for inservice testing. l i
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' }l 3. h Tag No. Physical Plow Test Preg. *
, ? iDeserlption & 5/M Sys. 1.ocation Diar.. No. & Reg'ts. Criteria R et-a rk s ,
a , r 8 'esidual Neat Removal Pumps XPP-31 A&R RH AB-374 114E074 Monthly General: Purps are tested using test loop
' f;l RJa-1 Rev. 6 &
Notes (1).
- Note (3) shoun on fjov diagrai 114E075 Sht. 3
[ (RitAPR!t 114E075 (2) valves BSE8A (3SS85) and SSS9 are 01 & 02) Sht. 3 TbNote (6) closed and valves 8837A (88878) Sub 8 Pg Note (4) and 8881 are open to direct pump
, discharge back to the F57. .D t+
g i
- I. 9. Spent Puel Cooling Pumps XPP-32 A&R SP A8-412 302-651 Monthly General: Pumps are tested in the moran.1 N RCb-5 Rev. 8 Notes (1), . Note (3) operating moJe. (Suction is taken free
- j. (2),(5) the spent fuct pool and the pump is j . TbNote (6) discharged through the best exchanger Pg Note (4) back to the pool).
10 IIVAC System XPP-48 VU 15-412 302-841 Monthly , General: Pumps are tested in the normal
, ,, Chilled Water Pumps A. 5 & C Rev. 3 Notes (1). Note (3) operating mode. (Discharge routed SM-5 .' through chilled water cooling loop).
. l[, .
.Tb t Note (6)
Pg Note (4)
- 11. Boric Acid Transfer Pumps XPP-13 CS AB-436 114E073 Honthly General Pumps are tested using the recircu-3: A&B Sht. 5 Notes (1),
- Note (3) lation line back to the boric acid q RE-1 of 5 (2), (5) . tank. valves 8320A (63203) an,1
_ ii (CSAP8A Rev. 8 Tb Note (6) 8321A (83218) era open and valve I' 01 & O2) Pg Note (4) 6315A (83158) is closed. With valves 8320A and 8321A fully open the syntes . can be considered to have a fixed resistance and only or needs to be measured. t
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. ** 4, Tag No. Physical Plow Test Preg.
Description & B/M Dian. No. & Reo'ts. Re*Jrks h location Criteria
- 12. Boron Injection Recir- XPP-34 SI PB-436 114E075 Honthly , General Pumps are tested in normal operating culation Pumps A&B Sht. 1 Notes (1), Note (3) mode. (Discharge routed through boron RJc-1 of 3 (2) (5) injection tank back te boron injection (SIAPRP Rev. 7 *Tb
~
Note (6) surge tank). The system can be 01 & 02) - Pit Note (4) considered fixed resistance so AP does not have to be measured if flow is.
- 13. Reactor Bldg. Sprey Pumps XPP-38 SP AB-374 302-661 Monthly General: Pumps are tested using a test loop.
A&B Rev. 5 Notes (1).
- Note (3) Valve 3003A (3003B) is closed and RGe-1 (2) -
valves 3010A (30103) and 3011 are
- Tb Note (6h opencJ to allow pump discharge flow
-Pg: Note (4) to return to the refueling water i
storage tank.
- 14. Charging / Safety Injection XPP-43 CS AB-388- 114E073 Honthly . 'Ceneral: Pua:ps are tested in normal operating Pumps A. B & C Sht. 3 Notes (1), . Note (3) mode i.e., changing flow path. Each RE-1 of 5 (2) pump r.ust be tested once a month (CSAPCH Rev. 8 Tb Note (6) during normal operation. The pump to 01.02&O3)
- Pt s Note (4) be tested must be . aligned to the l charging line.
1 NOTES:
- 1. The inservice test shall Le run on each pump, nominally each emnth during normal plant operation. If the pump has not been tested during an extended shutdown, the pump shall be tested within one week af ter the plant is returned to normal operation. Pu:sps that-
, are operated more frequently than once a month need not be run or stopped for a special test as long as the data was properly logged
, and analyzed. (IWP-3400)
- 2. All quantitles on table IWP-3100-1 must be recorded and analyzed for each inservice test.* except bearing temperature which shall
- be c.easured at least once a year during an inservice test. (IWP-3300)
- 3. the values of the inservice test parameters are to be evaluated against the results of the reference test using the allowable limits Itated in Table IWP-3100-2 " Allowable Ranges of Test Quantitles."
- 4. Pump inlet pressure will be determined during pre-operations! testinC.
- 5. The pump is not considered safeguard equipinent but is safety class 2b or 3 and receives energency power (the requirements for a pump to be inservice tested to subsectiun IWP).
. 6. usaring temperature will be dete mined during pre-operational testing.
i -
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9 O O f (O l AP-014 ' 'l - Attachtnent VII l Fage 1 of 16 1 h . IsSnYtCE TEStruc _
! . CF YALVES i; rOR v.C. S=Es ext.Ea 2 9
STATION 1 4 STRCKE
} $!CT, FCSITIC:t TEST TIP.E I TAC 30 FIFIEC FLOW OFER. XI CAT. INDICATOR TREQ. (SEC.) TEST REQ"IR. M.3 ! (I*Orr. Ko.) E 3/M .Si!E TYPE . DIAC. No. I'4. # (NOTE 1) Q 1.0 CAT 10N (NOTE 2) (NOTE 5) (NOT! 4) (No-E 1) (Nett 6 & 7) R M tts J
I 2033 RC RA-1J 1 Diaph 114E072 Sht. 2 304-744 A0 2a FB-412 A =
*/3M 10 Penet. 420 Isolation Yalve i 1-CA9:1 2007 RC RA-1J 1 Diaph. 114E072 Sht. 2 304-603 A0 2a RS-412 A . */3M 10 Penet. 420 Isolation Valve
- 1-t\92R
'l 8025 BC RA-1J 3 Diaph. 114:072 3ht. 2 304-794 A0 2a Fa-412 A -
*/3M 10 Fenet. 422 1solattoa Valve 2
l 3-c.\921 S046 RC RA-1J 3 Check 114E072 Sht. 2 304-791 N 2a RS-423 A/C - * - Note 71 50F Fenet. 4221 solation Yalve 3-C22 . { , 2 2010A,8 C. RA-13 6 Relief 1142072 Sht. 2 304-603 13-463 C TS t* Note 6 i' RC F0 1 - - 6-RV28?$3 * (a) 2453 Pets I (b) 420,000 lb/hr s 8152 C3 RA-1J 3 Clebe 114E073 Sht. 1 304-676 A0 2a FR-412 A =
- 10 Fenet. 318 Ia'olatteo Valve 3-IA76;.E 8331 CS RA-1J 3 Check 114E073 Sht. 1 304-671 N 2a RS-412 A/C = .
* = Not.e 7; NDP Fenet. 409 !aoletten Valve, 3-C76
$1&?A & C CS RA-1J 2 Clobe 114E073 Sht. 1 304-671 A0 2a RS-412 A =
c
- 10 Fenat. 318 Isolation valve 2 1A76KC . . ,
, 81498 CS RA-13 2 Clobe 114E073 Sht. 1 304-671 A0/FC 2a , RS-412 A
= .
- 10 Penet. 318 Isolation Valve 2-IA7823 2153 CS RA-1J 1 Clobe 114E073 Sht. 1 304-671 A0 1 RS-412 5 -
- N/A 1-1AGSEE 114E073 Sht.1 304-671 A0
- f 8154 CS RA-1J 1 Clebe 1 RS-412 3 . N/A
- 1 !AS;RE ,
k RS-412 3 g LCV-450 CS RA-1J 3 Clobe 114E073 Sht. 1 304-671 ? AO 1 . *FS N/A
;* 3-1 A 3310 ki RA-1J Clobe 114E073 Sht.1 304-671 AD 1 RS-412 B = *FS N/A LCV-439 CS 3 .
- i. 3-1A53RG ,
r
)
$346 CS RA-1J Check 114E073 Sht. 1 304-671 N 1 R3-412 C = * .
Note 73 NCF
!. 3-C33 L .
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I ~ I Page 2 et 16 . INSERVICE TESTING
- OF VALVES
. FOR V.C. S'.DC'.CR NUCLEAR
. STATION
. SUCKE SECT. TOSITION TEST T1.4 TAC NO.
FLCV FIFING OFER. . 11 CAT. INDICATOR TREQ. (SEC.) TEST REQUIREMElCS
. (NME 3) (NME 4) (NOTE 3) NME 6 & 7 RENUtKS (IrC:T. NO.) & Sht _ STZE TYPE. DU C. NO. tVC. # . (NCTE 1) Q LOCATIOle (NOTE 2)
- Note 7; NOP 8317 CS FA-1J 3 Check 114E073 Sht.1 304-671 N
- 1 RS-412 C = * .
3-C88
- Note 73 NOF 8378 CS 'RA-13 3 Check 113E073 Sht. 1 304-671 N 1 RB-412 C = * .
3-C83 R5-412 * = Note 73 NCF 8379 CS RA-1J 3 Check, 114E073 Sht. 1 304-671 N 1 C - 3 C33 RS-463 * = . Note 73 NCF 8377 CS Row-2 2 Check 114E073 Sht 1 304-672 N 1 C = . . . 2-C85 - 8145 CS PA-1J' 2 Clebe 114E073 Sht. 304-671 A0 1 RS-412 5 - 3M #.N/A 2 -IA 83'J. . 8100 CS RA-1J 2 Clobe 114E073 Sht. 1 304-676 Dt0 2e FR-412 A Tee *FS 10 Fenet. 410 Isolettos Valve 2-UtT8FN 8133 CS R0q-18 3/4 Check 114EO73 Sht.1 304-672 N 2e RS-412 = * = = Note 73 NCF Fenet. 410 Isolettes Valve 3/4-C73 . . 3112 - CS RA-1J 2 Clobe 114E073.Sht. 1 304-672 EMO 2e 15-412 I Yes *FS 10 Fenet. 410 Isolation valve 2-TM78Fh"E , RS-412 C
- Note 73 NOF 83tSA.S.C CS Row-1 1 1/2 Check 114E073 Sht. 1 304-671 ' N 1 =* =
1 1/2-CL8 . R3-412
- Note 7. NOF 8367A.B.C CS Row-1 1 1/2 Check 114E073 Sht. 1 304-571 N 1 C - .
1 1/2 C89 '
, CS 30g-13 1 1/2 Check 114E073 Sht. 1 304-671 It to RF.-412 A/C - * . Note
- 7, N0F Fenet. 408 Isolatton Valve 8353A.3.C 1 1/2-C78
- 810 3 .5.C CS RA-1J 1 1/2 CLobe 114E073 Sht. 1 304-676 EMO 2e FR-412, A Yes
- 10 Penet. 408 Isolation Valve 1 1/2-TM78FN 8106 CS FA-1J 3 Cate 114E073 Sht. 3 304-674 EMD 2e A3-412 3 . *FS It/A 3-CM18Da FA-1J 2 Clobe 114E073 Sht. 3 304 673 EMO 2e AS-323 3 = 3M N/A 8109A.S.C CS 2 -1M7S*3
$197 CS RA t, 3 Cate 114E073 Sht. 3 304-676 EMO 2e FA-412 A Yes
- 10 Penet. 409 teolation Valse 3 -C.'t ? 8 Di RA-1J 3
- Cate 114E073 Sht. 3 304-676 Dio 2e FR-412 A Yes
- 10 Penet. 40' Ifolatfo9 Valve SIM Cs 3 ' 2:7tna i ,
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"'***'N ST STROE
{ SECT. F031 TION TEST TD2
- P TAG FO. FIM P!FIFG OPER. El CAT. INDICATOR FREq. ($1C.) TEST RECTIRC2:ffS (t?DO WO.) E, _ Bht STE! TYPE DIAQ. FO. tVC. # (NOTE t) Q LOCATION (NOTE 2) _ (?t0TE 5) (NCTE 4) (NOTE 3) FME 6 & 7) RDWtKS 8451A,3,C CS . RA-1J 3 Check 114E073 Sht. 3 304-673 N 2a AB-388 C =
3M = Note 73 NOF 3-C78 , 8t83A,3,C C3 R09 20 2 Check 114E073 Sht. 3 304 673 N 2a AS-383 C = 3M = Note 73 50F k 2-C78 *
; 3130 A & 5 CS RA-1J 8 Cate 1142073 Sht. 3 304-673 EMD 2e AB-385 3 = *FS 8-ct71TS
- N/A 8131 A & 3 CS RA-1J 8 Cate 114E073 Sht. 3 304-673 EHO 2e AS-388 3 = *FS .
8-ct12T3 W/A LCV 115C & E CS RA-1J 4 Cate 114E073 Sht. 3 304-674 EMO 4-CM72TB . 2a AS-412 3 =
*FS ( N/A .
LCV-1155 & D CS RA-1J $ Cate 114E073 Sht. 3 304-673 EMO 2a A3-388 5 = *NC 8-C:72TS N/A
- 8134 CS RA-1J 2 Clobe 114E071 eht. 3 304-677 EMO 2a AB-426 3 = 3M 2-TM78TN N/A J, .
8442 CS , R0 1-21 2 Check k14E073Sht.3 304-674 5 2a AS-412 C =
- 2-C78
- s Note 7;,NCF .
g . f 8137A & 3 C3 RA-1J 4 Cate 114E073 Sht. 3 304 673 EMO 2a A3-338 5 = *FS N/A
- 4-Cf 78TN 8133A & 3 CS RA-1J 4 Cete 114E073 Sht. 3 304-673 EMO 2a AB-388 3 = *FS 4-C't78FN N/A .
o 8311.4 & 3 CS 101-27 2 Check 114E073 Sht. 3 304-677 N 2b AB-436 C = 33
- 2-C58 .
Note 73 NCF 8716A & B RI! RA-1J 10- Check 114E074' 304-644 W 2a A5 412 C = * = 10-C74 Note 73 NCF 8706A & B R!! RA-1J 8 Cate 114E074 304-644 EMO 2e AS-412 3 = *NC 8-CM74TE N/A .
. TCV-602A & 3 RIl RA-1J 2 Clobe 114E074 304-643 EMO 2a AS-397 3 = 3M N/A
- 4 2-T::3TN b 87f.4A f. 3 RH RA-1J 3 Relief 114E074 304-641 FO 2a RS-412 A/C = TS * =
Note 6: $ 3 R'.'76LW3 Yelves are te leek tested 1 (a) 600 Fels reverse direction. (b) 1133 gps i b '4 e 9, 8 * . t s-
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=
- Fase 4 of 16 .
a
- INSERVICE TESTINC OF VALVES
- FOR V.C. S'Tt R NUCLEAR STATION h .
STROKE SECT. PCSITION TEST TIME TAC NO. .
. F1.Cv FIFINC CFER. R1 CAT. UDICATOR FREQ. (S EC.) T$$T REQUIRZMENTS DIAC. FO. _ ff *C, # (NOTE 5) (NOTE 4) (NOTE 3) (NOTE 6 & 7) REMAR1tS (TE"NT. FO.) h B/M Si2t _ TYPE (N0'TE 1) Q EOCATION (NOTE 2)_
87015 PJL RA-1J 12 Cete 114E074 304-641 EP.0 1 R3-412 A Tee *NC 120 Feest. 226 Isolation Valve 12-C"$8SDI 304-692 1 8701A RR RA-1J 12 Cate 114E074 304-641 EMO 1 RS 412 A Tee *NC 120 Fenet. 316 Isolation valve, 12-CY.3 SSDt 8702A 68 R5 RA-13 12 Cate 114E074 . 304-641 EMO 1 .RS-412 3 - *NC N/A 12-CP48SEM 8301A & B S1 RA-1J 3 Cate 114E075 Sht. 1 304-697 pto 2a F3 411 A Yes *NC 10' Fenet. 426 Isolettoe Velve 3-CM78FN 8t36 SI RA-1J 3 Cate 114E075 Sht.1 304-692 EMO 2e FR-412 A Yee *NC f.10 Penet. 415 Isolation Valve 3 C'08fy
- 8135 51 RA-1J 3 Cate 114E075 Sht.1 304-691 D10 2a FR-412 A Tee *NC 10 Fenet. 2221 solation valve
.s 3-CM78nt ,
83t6 '31 RA-1J 3 Cate 114E073 Sht. 1 304-692 Dio 24 FR-412 A Ye's **NC 10 Penet. 412 Isolation Valve l 3-CM78DI 29fSA.8,C' $1 RA-1J 6 Check 114E075 Sht. 1 304 694 N 1 18-412 A/C = . * = Not'e7 NCF Leatuge tested ustes ECCS *
- check valve testics systee 6-C88 .
. and flow tested to see if j valve operates, g
b j 2997A.3,C SI R0w-2 2 Check 114E075 Sht. 1 304-694 W '1 . RB-412 A/C ,
- * =
Note 73 NCF Femet. 426 Isolation valve 2-CES . l
- 8995A 3,C $1 Row-2 2 Check 114E075 Sht. 1 304-694 N 1 RS-412 A/C = =
Eote 73 NCF Femet. 222 1 solation valve 2-CCS 8933A 6 3 31 F.A-1J 6 Check 114E073 Sht. 1 305-694 W 1 RS-412, A/C = * * = Note 73 NCF Fenet. 325 Isolation valve l 6-C88 , l - 114E075 Sht. 1 304-694 N 1 RS-412 A/C = * = Note 73 NCF 2993A,5,C $1 RA-1J 6 Check 6-C33 8990A.8,C SI R0w-2 2 Check 114E075 Sht. 1 304 694 N 1 33-412 A/C = * = Note 73 NCF Fenet. 412 Isolation Ystre 2-Ct3 St Pow-2 2 Check 114E075 Sht. 1 304-694 W 1 RB-412 A/C = * = Fote 73 NCF Fenet. 415 teolation Yalve ( 8992A.B.C .
) 2-C&S 8)*.5 A 6. 5 !! PA 1J 1 Clobe 114E075 Sht. 1 304-697 A0 2e FB-436 B = 3M N/A 1-I A 7374 .
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, INSERVICE TESTING
- CF VALVES
.. FOR V.C. SLMER NUCLEAR '
STATION r
- ST10KZ SECT. FCSITION TEST 'T!ME TAC 30. . FLOW FIFING CFER. II CAT. INDICATC1 FREQ. (SEC.) TEST F.EQU11MNTS (TCEN"" FO.) S'S . 3/M STEE TYPE DIAC. NO. _tv3. # (NOTE 1) Q LOCATION (NOTE 2)_ (NOTE 5) (FOTE 4) (NOTE 3) (NOTE 6 & 7) _
REMARK $
~
8942 31 RA-1J 1 Clobe 114E073 Sht. 1 304 697 A0 2e F5-436 8 1-IA73FZ .
- 3M
- N/A .
8303A & C SI RA-1J 3* Cate 114E075 Sht.1 304-692 EMO 2a FB 412 5 - *NC N/A 3.CM1811r *
- 8961 SI RA-1J 3/4 Clobe 114E073 sht. 2 304-691 A0 2a FR-412 A *NC 3/t.-1A78RZ *
- 10 Penet. 321 Is lattoa valve 8371 31 RA-1J 3/4
- Clobe 114E075 Sht. 2 304-694 A0 2e RB-412 A - *NC 10 . Fenet. 321 !aolation valve
,3/4 1A78RZ
- 8913A,8,C Si RA-1J' 12. Check 114E075 Sht. 2 (A&B)304. N A&B-RB
- 12-C88 1 A/C -
f, - Note 73 NCF Leakage tested ustaa ECC3
-436 * '* * ""'"# *I**
(h0,4,- g
- C
.cd rio. te.ted to vetirF valid opens.
8935A,B,C SI RA-1J 12 Check 114E073 Sht. 2 304-695 N 1 A&S-B- A/C -
- 12-C35
, g -
Note 73 NCF Leakage tested votes ECC5 412 check valve testtes system
' C-R3 436 and flow tested to verify valve opens..
8808A,B,C SI RA-13 12 Cate 114E075 sht. 2 304-695 IHO 2e A&B-RB. 5 -
; *FS It/A 12-CM38D11 . 412 C=RS-436 83754.3,C 51 RA-!J 1 Cist's 114E075 sht. 2 (A&3)304- A0 2e RB-412 - *JC N/A . -
1 1-1A76RIS 694 (C)304-695
- 8947 51 10q-25 1 Check 114E075 Sht. 2 304-694 N 2a RB-412 A/C
- 1 C66 Note 73 NOP Fenet. 320 Isolation Valve j .
8 80 SI RA-13 2 Clobe 114E073 Sht. 2 304-717 A0 2e FR-412 A -
*/3M 10 Penet. 320 Isol'attoa valve 1-TA68IIS
- 8351 St R0q-26 1 Check 114E073 Sht. 2 304-694 N 2e RD-412 A/C -
- 1-C78 Itote 73 NOF Fenet. 317 !aoistion valve
! STA0 31 RA-!J 1 Clobe 114E073 Sht. 2 304-691 A0 2a FR-412 A - */3M 10 Penet. 317 Isolation valve ! 1-!A7813 ,
L 8359 :: RA-1J 10 Cate 114E075 Sht. 3 304-642 EMO 2a FR-412 A Tee */3M 12.2 10-CM78FN , Fenet. 325 Isolation valve 0 e 4 .
j -
- c. < '
d m n - m L -
- . C -
I . Fase 6 of 16 INS *,.RVICE TESTD0
- CF VALVES
- FOR V.C. St:M:CR h"JCLZAR
. STATION ,
. STECKE SECT, POSITION TEST TIME .
TAC FO.
- Fr.02 FIFu c orER. . x1 CAT. INDICA!CR TEQ. (SEC.) TEST R!tTJHEMDIS (te n t. ro.) E s/M JIE TTrE DIAc. wo. tuC. # (NorE 11 % t.0 CATION (NOTE 2) (NOTE 5) (MrrE A) (FOTE 3) (NOTE 6 & 7) REwARKS 8838A St RA-1J 10 Cete 114E073 Sht. 3 304-642 IMO 2a F1-412 A Tee . */3M 12.2 Fenet. 322 teolation Yalve 10-CM787M
- 23333 SI ~ RA-1J 13 Cate 114E075 Sht. 3 304-642 EMO 2a FR-412 A Tee */3M 12.2 Penet. 227- tectation valve 10-CM78FN t?74A SI RA-1J 10 Check 114E075 Sht. 3 304-694 N 2a RS-412 A/C - * =
Note 73 NCF Fenet. 322 Isolation valve 10-C78 89745 SI RA 1J 10 Check 114E075 Sht. 3 304-694 N 2a RS-412 A/C = * = Note 73 NCF Fenet. 227 laelatten Yalve 10 C78 8973A,B,C SI RAalJ 6' Check 114E075 Sht. 3 304-694 N RB-412
- 4*
6-C;S 1 A/C =
- Note 73 NCF Leakage tested estes the ICCS check valve teettra systes and flow tested to verify valve opens.
8837A & S $1 RA-1J 10 Cate 114E075 Sht. 3 304-642 EHO 2e FR-412 B = 3M N/A 10-CM74TE 5953A & 3 SI' RA-1J 14 Check 114E075 Sht. 3 304-693 N 2a A5-397 C =* * - Note 73 NCF 14-C74 -
~
f511A SI RA-1J 14 Cate 114E075 Sht. 3 304-693 EMO 2a AB-397 A Tee - */3M 17.1 Penet. 329 Isolation Yatre 14-CM74TER 88118 SI RA-1J 14 Cate 114E075 Sht. 3 304,-693 EMO 2a A5-397 A Tee */3M 17.1 Fenet. 425 I olstion Valve 14-CM74TER
- 8312A & B SI RA-1J 14 Cate 114E075 Sht. 3 304-693 EMo
- 2a An-397 3 - 3M N/A ,
14-Ct74TE 6209A & B SI RA-1J 14 Cate 114E075 Sht. 3 304-693 EMO 2a AB-397 3 = *
,3M N/A 14-CM74ff. .
8926 SI RA-1J 8 Check 114E075 Sht. 3 304-693 N 2a AB-397 C = d * - Note 73 NCF 8-CT2 7126 k' RA-1J 3/4 Diaph. 114E077 Sht. 1 304-733 AD 2a RS-412 A - */3M 10 Penet. 418 1so'istion Yelve 3 /4-D;62R 7150 LT. RA-1J 3/4 Diaph. 114E077 304 744 A0 2a F5-412 A = */3M 10 Penet. 418 !aolation valve 3/4-DA62R 7136
- RA-1J 2 Diaph. 114E077 304-736 AD 2a FB-412 A - */3M 10 Penet. 423 !aolation Velve 3-DA92R t
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- CF VALVES FCR V.C. 31002R HUC12AR ,
STATION t . STROKE SECT. FCSITION TEST TD2 TAC 50 F1.CW FIFINC CFER. XI CAT. INDICATCR FREQ. (SEC.) TEST RIQUIRC2NTS (t m T. FO.) g 3/M STEE TTFE DIAc. No. If>C. # _ (NCTf! 1) Q 1.0 CATION (NOTE 2) (NOTE 5) (NOTE 4) 1ECTE3) NOTE 6 & 7) RD*AtKS Butterfly
- 302-611
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- Cate 302-612 3f4-615 EHO 2a FR-436 A Yes-
- FS 42 . Penet. 330 !aolation Valve
. 4 9368 . CC ENn-30 8 Cate 302-612 304-615 FMD 2a FR-436 A Tee
- FS 42 . Fenet. 312 leolattom Yalve 9510 CC R0q-3 8 Check 302-612 304- N N 2a RS-436 A/C = - * . -
Note 73 N0F Fenet. 312 teolation Velve
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Note 73 NOF l
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* = Note 73 NOF 1 .
9625 CC RNg-25 8 . Cate 302-612 304-612 EMO 2b AB-412 3 = = *FS N/A 9626 CC RNg-25 8 Cate 302-612 304-612 'EMD 2b AB-412 B = *FS N/A
- j#
9600 CC RNn-5 3 Cate 302-61'2 304-611 hMD 2b FR-436 A Yes . *FS 19 Fenet. 204 isolatten valve l 9602 CC Rog-4 . 3 Check 302-612 304 617 N 2b RS-436 A/C *= * = Note 73 NOF Fenet. 204 Isolattoa valve '} 6671 SF Rot-11 3 Diaph. 302-631 304-631 N 2a RB-412 A = * = Fenet. 419 Isolation Yalve
- 6672 3-I42D SF Rot-5 3 Diaph. 302-651 304-652 N 2a FS-412 A = * = Penet. 419 teolation Valvee
! 6697 3-X42D SF Rot-5 3 Diaph. 302-651 304-652 N 2a FS-412 A = , * = Fenet. 421 1 solation Valves 6678 SF Rot-11 3 Diaph. 202-651 304-651 W 2a RS-412 A = * = Penet. 421 Isolation valves 3003 A SF RNa-16 10 Cate 302-661
- 304 666 EMO 2a FR-463 A ,
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- Note 73 30F Fenet'. 401 leolation valve 439 A SF Rog-9 10 Check 302-661 = =
3003 3 SF RNa-16 10 Cate 302-661 304-656 EMO 2a FR-463 A Yes *NC 30 Penet. 303 leolation Valve 3c09 3 SF Rog-9 to Check 302-661 304-665 N 2a RB-463 A/C = * = Note 73 It0F Fenet. 301 Isa'- w valve ,F 3094 A .. RNn 21 12 Cate 302-661 , 304-661 EHO 2a An-397 A Yes *NC 75 Fenet. 31 . 21stten valve
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. . STR0K3 SECT. POSITIcs T:ST TIME
,, TAC FO. . F7Di FIFING CFER. R1 CAT. INDICATCR TREQ. (SEO.) TEST REQtlIRDINTS (Im:7. No.) 3 3/M . SIZE TTFE DIAC. NO. EUC # (NOTE 1) Q INAT10N (NOTE 2) (NOTE 3) (NOTE 4) (NME 3) (NME 6 & 7) D E*AMS 3006 3 SP RNn-21 12 Cate 302-661 304-661 E'O 2a A3 397 A Yes *NC 75 Penet. 328 !aolation valves 3005 A & B SF RNa-17 12 Cate 302-661 304-661 EMO 2a AS 397 3 Yes *NC NfA . 3001 A & 3 SF ,RNn-18 12 Cate 302-661 304-661 EED 2a AS-397 5 Tee
- N/A 3006 A & S SF E0g-8 12 Check 302-661 304-66'1 N 2a AS-397 C - 3M . Note 73 NCF ,
3013 A & B SF R0q-10 3 Check, 302-661 304-661 N 2a AB-397 C . 3M - Note 73 NCF 3M?8 8. B SF RNg-21 3 ,Cate 302-661 304-661 DC 2a AS-397 5 Yes
- N/A 8767 DN Rot-1 1 Diaph. 302-715 304-716 N 2a FR-436 A - * - Fenet. 231 Isolation Talve 3768 EN 10t-12 1 Diaph. 302-715 304-712 N 2a RB-436 A =
- f. - Fenet. 231 leolation valve 9311 A & B SS RNa-35 1 Ball 302-771 814-201 A0 2a (A)RB. A Yes */3M 4,10 Fenet. 407 Isolation valve 463 (3)FR-463 9312 A & 3 SS RNa-33 1 Ball 302-771 814-201 A0 . 2a ( A)'.3- A Yes */3M 4 10 Fenet. 407 Isolation valve
. 463 . ,
(B) F1-
- 461 9356 A & 3 SS RNt 2 3/8 Clebe 302-771 304-771 30 2e Rs.436 A Yes */3M 4 10 Penet. 405 Teolation Valve 9357 $$ RNc-2 3/8 Clobe 302-771 304.,772 SO 2a FR-436 A Yes */3M < 10
- Fenet. 405 leolation Valve 9364 3 SS RNt-2 3/8 Clebe 302-771 304-771 30 2a RS-412' A Yes * */3M < 10 Penet. 314 leolation valve 9365 5 . SS RNt-2 3/8 Clobe 302-771 304 772 30 2a FR-412 A Yes ^ */3M 4 10 Penet. 314 Isolation Valve 9364 C SS RNt-2 1/8 Clebe 302-771 304-771 30 2a RB 412 A Yes * */3M < 10 Feest. 223 Isolation valve 9365 C $$ RNt-2 3/8 Clebe 302-771 304 773 SO 2a FR-412 A Yee */3M < 10 9398 A SS RNt-2 3/8 Clobe 302-771 304 772 SO 2a FR-412 A . Yee */3M < 10 Fenet. 411 Isoletion valve 9393 S SS F3t-2 3/8 clobe 302 771 304-773 SO 2a FR-412 A Yes */3M < 10 Penet. 225 !aola tion Yalve 9393 C $$ RNt 2 3/8 Clobe 302-771 304-773 30 2a FR-412 A Yes */3M 4 10 Penet. 2201 solation valve 9337 SS RNt-2 3/8 Clobe 302-771 304-772 30 2a FR-412 A Yes */3M .C0 . Fenet. 323 leolation valve
$$ RNc-2 3/8 Clobe 302-771 304-771 50 2a RS-412 B = .' 3M N/A 7350 a 9331 3 $$ RNt-2 3/8 Globe 302-771 304-771 30 24 RS-412 B - 3M N/A q ,
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- AP-U14 Attachment VIII.
I
~
INSERVICE TESTING OF VALVES Page 1 of 3
.(f
\ FOR V.C. SUMMER UUCLEAR STATION OTES: ,
Method of Actuation - OPER. (Operator)
- 1. ,
S.O - Solenoid Operator
- b. EMO - Electric Motor Operator
- c. AO - Air Operator
- d. PO - Process Pressure to open; spring return, fail close on loss of process' pressure .,
- c. PH - Pneumatic /llydraulic ,
- f. N - No external operator .
- 2. Categories of Valve's - SECT. XI CAT' .
l
- a. A - Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.
.. ., ,b...B.; . Valves.for which seat leakage in the closed position is inconsequential
~ ~ ' ' '
- for fulfillment of their function.
- c. C - Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves). .; .
- d. A/C - Indicates a check or relief valve wh.ich must be evaluated ih, both
(, categories A and C. , ,
\ ( c. N - Valves provided for operating convenience and are not required to e/ act to' perform a safety function but have remote position indication to verify their position. ,
- 3. STROKE TIME (SEC.) ,
-a. Number indicates closure time in seconds. Valve stroke must be measured to the nearest second or 10% of the maximum allowabic st'roke time, whichever is Icss (TUV-3410) . -
- b. US - Under siz'e, i.e., less than 2 1/2 inch'es nomihal size. -
- c. N/A - Not applicable.
- 4. Test Frequency - TEST FREQ. -
S. TS - Test Schedule for safety and' relief valves. (reference TABLE IWV-3510-1) . g O e
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