ML20066E785
| ML20066E785 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/08/1982 |
| From: | Collier L SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20066E783 | List: |
| References | |
| NUDOCS 8211170186 | |
| Download: ML20066E785 (377) | |
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f INSERVICE INSPECTION PROGRAM 1st INTERVAL ,
for the VIRGIL C. SUMMER NUCLEAR STATION REVISION 1 DGCKET.NO. 50/395 t
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l~8211170186 821110 PDR ADOCK 05000395 -
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INSERVICE INSFECTION PROGRAM 1st INTERVAL 3
for the VIRGIL C. SUMMER STATION REVISION 1 4
DOCKET No. 50/395 OWNER: South Carolina Electric and Gas Company P.O. Box 764 Main Street Columbia, South Carolina 29218 PLANT: V. C. Summer Station Location - Twenty-six miles northwest of Columbia in Jenkinsville, S.C.
CAPAC TY: 1 Unit of 900 MWe PREPARED BY:
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// d -8 L A R0 LS: N O. h //- J - I Z-In~ service Inspection Coordinator /Date
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Manager, Nucleay Qual ($y Control /Date/
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. ) Retr!!!!Tip Nttpear Station /Dat'e
% b V/? A // }' U Manager, Nuclearj/Engineerfng/Date / /
CONCURRENCE:
fr f -- y //~V'E L Authorized' Nuclear Insefvice Inspector /Date
y 1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 1' '
11/2/82 INTRODUCTION:
y This document represents the' Inservice Inspection and Testing Program'for the V. C. Summer Nuclear Station, Unit 1, pressure retaining components (including supports) which are classified ASME Code Class 1, Class 2 and Class 3. ,
INSERVICE INSPECTION:
The ISI Program complies with requirements of 100FR50.55a(b)(2) and 50.55a(g) effective April 17, 1981 and utilizes the,ASME Section XI Code, 1977 Edition through.and including the Summer 1978 Addenda except as specified in 100FR50.55a(b)(2)(IV) as a basis for the inservice examinations and tests . to be performed during the first 120 months inspection interval. The first inspection interval will be scheduled to begin when the unit is placed into commercial operation. ,
The ISI Program is presented in the following seven (7) sections:
SECTION I:
Station Administrative Procedure, SAP-145, details the administrative controls for the ISI Program which includes delegation of authority and responsibility for conduct of the ISI O Program, qualification requirenents for individuals participating in and performing inspections and tests required by the program, and documentation and tracking requirements for the program.
SECTION II - INSERVICE TESTING OF PUMPS, GENERAL TEST PROCEDURE, GTP-001 The pump testing program demonstrates the operational readiness of Code Class 1, 2 and 3 pumps, as applicable, which are required to perform a specific function in safely shutting down the reactor or in mitigating the consequences of an accident. This program is presented in the form of a procedure incorporating tables identifying the pump by number, location, coordinates, relief request (if applicable) and the appropriate Surveillance Test Procedure.
In addition, tables are included to determine the allowable ranges of test parameters, such as pump speed, inlet pressure, differential pressure, flow rate, vibration, bearing temperature, detection instrument type, I.D. number and calibration due date.
A Pump Test Summary is included to track the status of successful tests. Also, relief requests are referenced in this procedure and-kept under separate tabs as part of the Pump Test Program.
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1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 1 11/2/82 +
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SECTION III - INSERVICE TESTING OF VALVES, GENERAL TEST PROCEDURE, GTP-002 The valve testing program demonstrates the operational readiness of Code Class 1, 2 and 3 valves , as applicable, which are required to perform a specific function in safely shutting down the reactor or in mitigating the consequences of an accident. This program is presented in the_ form of a procedure, incorporating tables identifying the valve by number, system, description of function, category, class, location, normal position indicator status, test requirement (s), and relief request (s) status. Applicable alternate test (s), stroke time, leak tests and an approved Surveillance Test Procedure are referenced for use during evaluation and interpretation of Test Results.
Specific relief requests are referenced along with proposed alternate test (s). In addition, a table and a data sheet are included to determine the number of Safety and Relief valves to be tested between refueling outages and to record specific data for each of the valves requiring-such tests.
SECTION IV - NONDESTRUCTIVE EXAMINATION OF COMPONENTS, GENERAL TEST PROCEDURE, GTP-003 This section provides the nondestructive examination program for the V. C. Summer Nuclear Station. It describes the ASME Code O. Class 1, 2 and 3 components subject to surface, volumetric and visual (VT-1 and appropriate VT-3) examinations as required by ASME Section XI Code during the first ten year inspection interval.
The NDE Section provides a procedure which establishes the rules necessary to develop, implement and control the plans, schedules and examinations required by ASME Section XI' Code. Should it become impractical to perform the required NDE examinations due to unusually high levels of residual radiation, fixed contamination and/or permanent structural interferences, a request for relief will be initiated along with selecting alternate examinations
- and/or components when such alternate tests are meaningful.
In the procedure, Sections 4.4 and 4.5 identify those items or types of items requiring the code examinations. In some cases, l such as Class 1 and 2 piping systems, the items to be examined are I identified by the type and percentage based upon the ASME Section XI Code,1977 Edition through the 1978 Addenda requirements.
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1ST INTERVAL INSERVICE INSPECTION. PROGRAM REVISION 1 11/2/82 g
s sj 1 SECTION IV (Continued)
When welds requiring specific seismic analysis, as required by the 7 code, have been identified, GTP-003 will be revised to reflect the required examinations of such welds. A. table is also included in the procedure identifying the category, item number, general description, examination method, total items in general description, examination muount and extent, examination period, intended examination % and relief request / remarks. In addition isometric sketches are identified and provided under separate binder identifying the system, class and appropriate Inservice Inspection Weld Numbers.
Since design geometric discontinuities may exist at the point of interest, meaningful ultrasonic examinations and surface examinations may not be practical. However,.a best effort examination will be performed and so noted on the inspection data sheet.
Due to their anomalous nature, certain material product forms, such as austenetic stainless steel,'may not lend themselves to meaningful ultrasonic examinations in the root areas of the weld with the present " State of the Art" methods available. Therefore, ultrasonic examinations will be performed on a best effort basis using the " State of the Art" methods available at the time the examination is performed.
SECTION V - INSERVICE INSPECTICN SYSTEM PRESSURE TESTING, GENERAL TEST PROCEDURE, GTP-004 This section provides the System Pressure Test Program Plan. It describes the ASME Code Class 1, 2 and 3 components subject to the pressure tests as required by ASME Code Section XI during the first ten year inspection interval.
The program is presented in the form of a procedure incorporating tables to identify the type of component, required tests, examination method, inepection frequency and references for specific activities performed during the test.
In addition, tables are incorporated to identify the system / subsystem designation, cod,e class, description of system / subsystem, Surveillance Test Procedure and the applicable flow drawing. Relief requests are identified in GTP-004 and provided under separate binder identifying the system / subsystem, name of item and class of item to be tested.
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1ST INTERVAL INSERVICE INSPECTION PROGRAM -
REVISION 1 11/2/82 A SECTION VI - INSERVICE INSPECTION OF COMPONENT SUPPORTS, GENERAL
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i TEST PROCEDURE, GTP-005. ,
This section provides the component support examination program plan. It describes the ASME Code Class 1, 2 and 3 component supports and other component supports listed in the Plant Technical Specification subject to the examination requirements of ASME Section XI Code and the Technical Specification during the first ten year interval.
The required testing and visual examinations shall be documented in accordance with the applicable Surveillance Test Procedures. In the event circumstances such as radiation / contamination levels, >
I geometric design, building structural design or other unforeseen factors require such action, provision for relief request has been l made in this procedure. i SECTION VII - REPAIR PROGRAM, A program has been developed in accordance with requirements of the Code to perform repairs on those Code Class 1, 2 and 3 items and other safety related systems and structures.
The' repair program is presented in the form of four (4) procedures:
O (1) SAP-304, "ASME Code,Section XI Repair Program". l (2) SAP-302, " Administration of Maintenance Welding" .
(3) WM-1.0, " Welding Manual Procedure".
(4) WM-2.0, " Welding Material Procedure" .
l (1) SAP-304, ASME CODE, SECTION XI REPAIR PROGRAM:
This procedure was developed to establish a repair program in conjunction with the Inservice Inspection Program.
Included in this procedure are:
- a. Re sponsibilities
( b. Documentation Requirements
- c. Disposition of Repair Methods
- d. Implementation Requirements
- e. Review and App
- oval Requirements
- f. Interfacing Requirements
1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 1 11/2/82 f~)
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,( 2) SAP-302, ADMINISTRATION OF MAINTENANCE WELDING:
This procedure establishes the means for developing, implementing and maintaining the controls for the j maintenance welding program. Included in this procedure are:
- a. Responsibilities
- b. Training and Qualification Requirements
- c. Documentation Requirements
- d. Material Control Requirements
- e. Welding and Brazing Activity Control Requirements
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- f. Welding by External Organization Requirements
- g. Authorized Nuclear Inservice Inspector Involvement (3) WM-1.0, WELDING MANUAL PROCEDURE:
This procedure was developed as part of the repair program to provide the necessary rules for controlling welding and brazing activities, thus ensuring the requirements have
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\- been met for code and safety-related items. Included in this procedure are:
- a. Training of Welders and Brazers
- b. Qualification of WPSs and BPSs
- c. Procedure Qualification Tests
- d. Standard Qualification Tests
- e. Acceptance Criteria of Qualification Tests
- f. Documentation of Welding and Brazing Activities
- g. Welding Activities
- h. Brazing Activities
- 1. Repair of Weld Metal and Base Metal Defects J. Defect Removal and Cavity Preparation of Weld Metal and Base Metal O
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. 1 1ST INTERVAL INSERVICE INSPECTION PROGRAM -
REVISION 1 11/2/82
- k. Post Weld Heat Treatment
- 1. Post Braze Heat Treatment
- n. Calibration (4) Wit-2.0, WELDING MATERIAL CONTROL:
This procedure was developed to establish and implement the methods.for controlling, procuring, storing, issuing and proper disposition of unused and used welding electrodes.
Included in this. procedure are:
- a. Responsibilities
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- b. Practices of Handling Materials
- c. Documentation
- d. Rod Room Control of Welding and Brazing Material
- e. Rod Room Issuance Control of Welding and Brazing Material
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() f. Field Control of Welding and Brazing Material
- g. Rod Room Return Control of Welding and Brazing Material Where conformance with certain code requirements is impractical, requests for relief 7 and/or explanatory comments are referenced into each section wivh supporting information and proposed alternatives.
Each section of this program used as controlled copies is indexed and tabbed for convenience of retrieval, planning, controlling and scheduling those activities necessary to achieve timely results.
1 Reference 10CPR50 55a(g)(5)(111)
1ST INTERVAL INSERVICE INSPECTION PROGRAM REVISION 1 11/2/82 Augmented. examinations, if required by the NRC, 2 are included as 9 part of this program. Eiamples of these are those required for the Reactor Coolant Pump Flywheels, Steam Generator Tubes and Component Supports. Each Reactor Coolant Pump Flywheel will be inspected in accordance with Regulatory Guide 1.14, Revision 1, August 1975 In addition to the requirements of this program and ASME Section XI Code, eddy current examination of the Steam Generator Tubes and the visual examination and functional test of snubbers will be performed to meet the requirements of the plant Technical Specification. The examinations and tests will be performed utilizing procedures and personnel which meet the requirements of the plant Technical Specification.
Providing revision to any of the procedures captioned herein will not delete any of the requirements specified in the codes or other applicable standards, any procedure may be revised without further revision to the Inservice Inspection Program. In all cases, the latest approved revision of the applicable procedure shall become part of the Inservice Inspection Program.
,7 Pursuant t 10CFR50 55alg)(6)(11) 2
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.. e SOUTH CAROLINA ELECTHIC ' AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS
, g e r e ~:iu PERim0NS COPY yo_,___ S o STATION ADMINISTRATIVE PROCEDURE SAP-145 INSERVICE INSPECTION
~~~ ' x REVISION 0 JULY 12, 1982 gpp.5 e4
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Date Approved: /
PLANT MANAGER Date kW
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SEP 2 81982
/ g/] ] Date Issued:
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J SAP-145 PAGE 1 REVISION 0 7/12/82 LIST OF EFFECTIVE PAGES l
Page Revision 1 0 11 0 1 ,- 0 2 0 3 0 4 0
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5 0 6 0 7 0 8 0 9 .
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10 0 -
11 -- - 0 12 0 13 0 14 0 ATTACHMENTS Attachment I O I
Attachment II O W
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.PAGE i REVISION O l
7/12/82 =
4 TABLE OF CONTENTS i Page f List of Effective Pages i 1.0- PURPOSE 1 2.0 SCOPE 1 l
30 REFERENCES 1
! 4.0 DEFINITIONS 1-
! 50 RESPONSIBILITY 2 i 6.0 PROCEDURE 5 l 7.0 FIGURES 8
! -8.0 RECORDS 8 i.
, ~ ATTACHMENTS ; i j Attachment I - Inservice Inspection , Report
- Attachment II - NIS-1 Data Report 1 -
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SAP-145 REVISION 0 7/12/82 1.0 PURPOSE
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~l The purpose of this procedure is to provide the administrative .
guidelines, coordination and interface control ,for Nuclear Operations personnel in the administration of the Inservice Inspection Program as required by 10 CFR 50 55 a(s).
2.0 SCOPE This procedure is applicable to all station organizational elements responsible for performing inservice inspection activities required by 10 CFR 50.55 a(s).
30 REFERENCES 3.1 10 CPR Part 50.55 a(s) 32 Virgil C. Summer Nuclear Station Facility Operating License and Technical Specifications.
33 South Carolina Electric and Gas Company Operational Quality Assurance Plan.
34 ASME Code,Section XI, 1977 Edition, through and including g w( the Summer 1978 addenda.
U 3.5 GTP-001 General Procedure.for Inservice Testing of Pumps.
3.6 GTP-002 General Procedure for Inservice Testing of Valves.
37 GTP-003 General Procedure for Nondestructive Examination for Inservice Inspection.
3.8 GTP-004 Inservice Inspection System Pressure Testing.
3.9 GTP-005 Inservice Inspection for Ccmponent Supports.
3 10 SAP-108 Station Staff Qualifications and Training.
-- 4.0 DEFINITIONS 4.1 Authorized Nuclear Inservice Inspector ( ANII or ANI) - An inspector employed by an insurance company authorized to write boiler and pressure vessel insurance and having qualified in accordance with the requirements of ANSI /ASME N626.1-1975 O
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SAP-145 REVISION O
^- 7/12/82 4.2 Code - AS:tE Boiler,and Pressure Vessel Code,Section XI (Reference 3 4) except as modified by 10 N CFR50.55A(B)(2)(IV). .
4.3 Code Class - A Classification of items and Components basr* upon Section III Code subsection used in the Cor 'uction of such items.
4.3 1 Class 1 - Subsection NB 4.3.2 Class 2 - Subsection NC 4.3 3 Class 3 - Subsection ND 4.3.4 Class MC - Subsection NE 4.3 5 Component Supports Subsection NF 4.4 Code Category Designation -- A designation used by the code to delineate the major type (s)'of parts to be examined-within a Code Component"or a selected group of Code Components, as applicable.
4.5 Code Item Number - A number used by the Code to specify:
The type of part to be examined, the examination requirements, the examination method, the acceptance standard, the extent and f requency of examination and, if g_), permitted, thg, deferral of inspections . /
4.6 Commercial Service - The date of placement of the power unit into commercial service as defined by the regulation of the Federal Power Commission Chapter 1 Title 18 Code of
- Federal Regulations.
4.7 Component Supports - Those netal supports that are designed to transmit loads f rom the component and piping to the load carrying building and/or foundation structures
" jand those elements used to support the weight or provide structural stability.
4.8 Examination - The performance of all required visual observation and nondestructive testing such as radiography, ultrasonic, liquid penetrant, magnetic particle, and eddy current methods.
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4 SAP-145 REVISION 0 7/12/82 4.9 Inservice Inspection Coordinator (ISI Coordinator) - That
/~ person designated by the Manager, V. C. Summer Nuclear
- Station, who is responsible _for development and '
implementation of the ISI Program.
4.10 Inservice Inspection Program (ISI Program) - Those planned and systematic actions performed to: Categorize the area subject to inspection and responsibilities, provide accessibility, apply testing and examination, and inspection methods, apply procedures, qualify personnel, establish frequencys of inspection, establish and maintain record keeping and reporting requirements, evaluation of inspection and Corrective action of such results, and document a repairs program.
4.11 Inspection Interval - That amount of time approximately equal to 1/4 of expected plant life. (10 years) 4.12 Inspection Period - That amount of tbne in Calendar years and/or months approximately equal to 1/3 of an inspection interval. (3 to 4 years) 4.13 Regulatory Authority - A Federal Government Agency such as the USNRC.
4.14 Replacement - The addition of space component (s) parts of
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component ( s ) , appurtenances, piping subassemblies, rerouted piping but not the addition of new complete systems. .
4.15 Rework - Repair or replacement activities or a combination thereof required to return an item to a condition acceptable to the Code.
4.16 Repair - Welding rework activities, including initial and final _finLshing processes, required to return an item to a condition acceptable to the code.
4.17 Recordable Indication - An indication requiring evaluation
/ by qualified personnel.
i 4.18 Rejectable Indication - An evaluated indication of an item or component requiring repair, rework, monitoring, analysis or a combination thereof.
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! SAP-145 .
REVISION O 7/12/82 1
50 RESPONSIBILITY
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V 51 The Manager, V. C. Summer Nuclear Station, 1s. responsible for.the overall implementation of the Inservice Inspection Program.
52 The ISI Coordinator shall be responsible for, but not limited to: !
l 5 2.1 Coordinating activities between various work and support groups as necessary to, implement the required nondestructive examinations including the following:
A. Operations B. Maintenance C. Station Quality Control D. Technical Support E. Health Physics '
F. Support Services ,
/~h 5.2.2 Scheduling and, if necessary,/ timely rescheduling 5-s/ of the required NDE, '
5 2.3 Designating required tests or examinations, as applicable, after repair, rework and/or replacement activities, 5.2.4 Coordinating evaluation of NDE recordable indications, 525 Performing review and evaluation of test results, 5 2.6 Initiating an off normal occurrence report (s) when required.
5 2.7 Coordinating disposition and, if necessary,
, corrective measures implemented for unacceptable examination and test results by initiating and/or l
identifying.
A. Pre-Approved Dispositions B. NCN(s)
C. MWR(s), or PAGE 4 0F 14
- i. SAP-145 --
l REVISION O j 7/12/82
,-s D. A combination thereof, where applicable.
5 2.8 Upon receipt, temporary Maintenance of required records and documents and, when required, submittal of such records to the Assistant Manager - Support Services for permanent storage and maintenance, 5.2 9 When required, submitting a copy of the NIS-1 Form and other specified records and documents to the Assistant Manager - Technical Support, 5.2.10 Promptly notifying the Assistant Manager -
Maintenance Services and the Assistant Manager Operations of unacceptable test results for appropriate corrective action and/or rescheduling of specified tests, as applicable.
5 2.11 Maintaining a summary of examination and test results.
NOTE: This summary may be a chart, graph, table or other appropriate document (s) defining the date and results of test.
5 2.12 Interfacing with NRC Inspectors who are auditing the ISI Program.
() 5.3 The Assistant Manager - Maintenance Services shall be responsible for supporting the ISI Coordinator in the performance of examinations and tests by. c.
5 3.1 Removing access plates, covers, collars, restraints '~
insulation, etc.,
5.3 2 Providing platforms, scaffolding and equipment supporting structures as required, 5.3 3 Performing rework, repair and/or replacement activities as required to return an item or
. component to an acceptable condition.
5.3.4 Placement and operation of hydrostatic, pneumatic, and/or leakage test equipment , instrumentation and gages as required for testing under direct guidance of operations personnel, 5.3 5 Developing and maintaining a welding repair program which satisfies the requirements of the code, 536 Performing any required bench tests. _
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SAP-145 REVISICN 0 7/12/82 f3 5 3.7 Reviewing procedures and certification records and (y' '
c' other supporting documentation of Contractor personnel performing repairs and testing.
538 Informing the ISI Coordinator when repair, rework or replacement activities affect those items specified in the General-Test Procedures.
NOTE: The Assistant Manager, Maintenance Services shall have the responsibility and accountabilicy for functioning as the ISI
,' Coordinator.
54 The Assistant Manager - Operations shall be responsible for supporting the ISI Coordinator in the performance of examinations and applicable tests by:
5.4.1 Attaching safety tags to appropriate equipment
. ar . . - and/or systems, when required.
5.4.2 Directing hydrostatic and/or leakage tests and '
performing concurrent visual examinations, 5.4.3 Draining appropriate piping systems / subsystems or other components as required,
/) 5.4.4 Developing and Reviewing applicable Surveillance
(_/ Test Procedures ~for compliance to the ISI Program.
5.4.5 Performing applicable operational tests on spec'ified equipment in accordance with approved Surveillance Test Procedures.
5.4.6 Promptly transmitting revorded results of specified tests to the ISI Coordinator.
55 The Assistant Manager - Support Services shall be responsible for supporting the ISI Coordinator in the performance of examinations and applicable tests by:
551 Scheduling and, if necessary, timely rescheduling of applicable tests for specified pumps and valves, 5.5.2 Maintenance and storage of required records and documents after receipt from the ISI Coordinator, 553 Tracking test results of pumps and valves modifying testing schedule as necessary.
5.5.4 When practical, scheduling NDE concurrent with other activities during maintenance outages.
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SAP-145 REVISION 0 7/12/82 p
/~h 5.6 The Assistant Manager - Technical Support is responsible
( ,/ for supporting the ISI Coordinator in the performance of applicable tests and examinations by:
5.6.1 Providing engineering disposition for unacceptable test and examination results as required by an NCN.
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5.6.2 Maintaining liason between the regulatory authority and other S.C.E.&G. N/O Supervisors and Coordinators through licensing engineering, 5.6.3 Submittinc programs or plans and schedules to the regulatory authority and coordinating such activities chrough the Assistant Manager, Support Services.
5.6.4 Submitting examination and test results, evaluation of test results and corrective measures implemented to the regulatory authority, as required, 5.6.5 '4 hen required, submitting repair and/or rework records to the regulatory authority, 5.6.6 Filing the completed Inservice Inspection Report (NIS-1 Form) with the regulatory authority within O 90 days after the completion of the Inservice Inspection.
57 The Director of Station Quality Control is re5ponsible for the following NDE Activities:
5.7.1 Directing and managing non-destructive examinations.
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5 7.2 Examination evaluations.
5.7.3 Procuring and Maintaining liaison with Contractor (s).
5 7.4 Interfacing with the ISI Coordinator including:
'~~' ss A. Promptly transmitting identified unacceptable~~~~
examination results to the ISI Coordinator.
575 Review of procedures, qualification records, s reports, demonstration records and other supporting N documentation for accuracy and adequacy.
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SAP-145 -
REVISION 0 7/12/82 g-~1 5 7.6 Performing any needed additional examination and
(_,) investigations for resolu. tion of examination results.
577 Preparation of required records, reports and documents.
578 When required, initiating NCN(s) for unacceptable NDE results.
579 Transmitting records, reports and other supporting documentation, including the NIS-1 Form, to the Assistant Manager, Support Services, for permanent maintenance and storage.
5 7 10 Transmitting a copy of the NIS-1 Form to the ISI Coordinator.
. 5 711 Training scheduling for unescorted personnel performing NDE.
5 7 12 Performing other activities as deemed necessary by Nuclear Quality Control and the affected Nuclear Operations Department.
58 Respective department heads may appoint designated
[ \ alternate (s) to perform any or all.of the specified
\~- activities or functions as described in 5.1 through 5.6 of this procedure.
6.0 PROCEDURE 6.1 Preservice Inspection '
6.1.1 The Preservice Inspection Program was ' implemented to assure initial operational performance of Code Class 1, 2 and 3 Components. - -
6.1.2 The results of preservice inspection provide initial data to be used for:
A. Baseline Component operational performance data, B. NDE baseline data, C. Reference values for future acceptance criteria, D. Pre-operational equipment test acceptance criteria, PAGE 8 0F 14
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SAP-145 -
REVISION O 7/12/82 6.1 3 Preservice Baseline Data was compiled in accordance O with ASME Code Section XI 1974 Edition through and including the Summer 1975 addenda and in accordance with the Preservice Inspection Program.-
6.2 Inservice Inspection Program (ISI Program) 6.2.1 The ISI Program, including the repair program, shall be used to reasonably assure operational performance of Code Class 1, 2 and 3 Components is maintained throughout the service life of the affected Component.
6.2.2 Examinations, tests and rep' airs shall be performed in accordance with the requirements of the ISI program.
6.2 3 The ISI program will consist of this procedure and 9 additional written approved procedures which outline the adminiscrative and specific requirements of the applicable examination, test or repair. The 9 additional procedures will be as follows:
, - A. GTP-001 General Procedure for Inservice Testing of Pumps
'O B . '/GTP-002 General Procedure for Inservice Testing
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of Valves j C. GTP-003 General Procedure for Nondestructive Examination for Inservice Inspection D. GTP-004 Inservice Inspection System Pressure Testing - -
E. GTP-005 Inservice Inspection for Component Supports F. SAP-304ASMESectionXIRepairProgham G. SAP-302 Maintenance Welding Program H. WM1.0 Welding Manual Procedure I. WM2.0 Welding Material Control 6.2.4 Each procedure in the ISI Program will either detail or reference the appropriate controls to be used in the administration of the ISI Program.
("N 6.3 Contractor Activities
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E A SAP-145
~ REVISION O
. 7/12/82 6.3 1 Procedures, qualification records, certification Os records, demonstration records and other supporting documentation of Contractor personnel shall be reviewed for accuracy, adequacy and compliance to the Code prior to their performing examinations, testing or repairs, as applicable.
6.3 2 NDE Personnel qualification records shall be submitted to SCE&G Q.C. and Q.A. for review and approval prior to such personnel performing testing or examinations.
6.3 3 Personnel performing examinatioas , tests, repairs or welding activities shall be qualified to perform such activities by the department heads, contractors, subcontractors or other appropriate departments in accordance with the requirements of the Code.
NOTE: ISI Contractors shall obtain a " Release to Work" f rom SCE&G Q. A. prior to performing any work at the V. C. Summer Nuclear Station.
6.4 Inservice Inspection Activities (Pump Testing)
() 6.4.1 Only those pumps which meet all of the following criteria need to oe included in the ISI program.
A. Class 1, 2 and 3 Centrifugal and positive displacement pumps B. Needed to perform a specific function in shutting down the reactor to a Cold shutdown condition C. Needed to mitigate the consequences of an accident D. Provided with an emergency power. source except those supplied with emergency power solely for operating convenience Each pump identified in accordance with the
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6.4.2 criteria of 6.4.1 shall be tested in accordance with the requirements of GTP-001 and the referenced Surveillance Test Procedure (s).
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.) SAP-145
. REVISION 0 7/12/82 r si c . 6.4 3 The Preservice Baseline Reference Values will be
( ,/ /- used as initial data to establish certain operating characteristics of each designated pump. .
6.4.4 A summary of test results shall be maintained in accordance with GTP-001.
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6.5 Inservice Inspection Activities (valve Testing) k 6.5.1 Only those valves which meet all of the following requirements need to be included in the ISI Program.
A. Class 1, 2 and 3 Valves and their actuation and position indicating systems B. Needed to perform a specific function in shutting down a reactor to a cold shutdown condition C. Needed to mitigate the consequences of an accident 6.5 2 Each valve identifie'd in.accordance with the criteria of 6.5.1 shall be tested in accordance with the requirements of GTP-002 and the referenced
/ Surveillance Test Procedure.(s).
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6.5 3 The Preservice Baseline Reference Values will be N. used as initial data to establish certain operating characteristics of each designated valve.
6.5 4' A summary of test results shall be maintained in accordance with GTP-002.
6.6 Inservice Inspection Activities (NON DESTRUCTIVE EXAMINATION) 6.6.1 Class 1 and 2 items to be included in the ISI program shall be identified and selected by reviewing the Preservice Isometric Sketches and List of Examinations.
6.6.2 Items required to be examined by IWB-2000, and IWC-2000 shall receive the specified examination (s) as required by GTP-003 and the code.
6.6.3 The Preservice examinations will be used as data to establish baseline data for comparison to ISI examinations.
1 6.7 Inservice Inspection Activities (System Pressure Testing)
O PAGE 11 0F 14
SAP-145 REVISION 0 7/12/82
, 6.7.1 Code Class 1, 2 and 3 systems and components will be incipded in the ISI Program.
( ). ,
6.7 2 Each system, identified as Code Class 1, 2 and 3 shall be tested in accordance with the requirements of GTP-004 and the referenced Surveillance Test P rocedure( s ) .
6.8 Inservice Inspection Activities (Component Supports) 6.8.1 Component supports to be included in the ISI program shall be identified and selected by' reviewing Construction drawings and compodent support detail drawings.
6.8.2 Component Supports required to be examined and/or tested by IWB-2000, IWC-2000 and IWD-2000 shall receive the specified examinations and/or tests as required by GTP-005 and the referenced Suqye111ance Test Procedure (s). "= 'r 6.9 Documentation 6.9 1 Procedures, reports , qualification and certification records and other applicable records of tests, examinations and repairs shall be
(~)S
(_ prepared' in accordance with the Code and the appropriate examination, test or repair procedure.
Such documents shall be maintained and stored for '
the service lifetime of the affected component in accordance with SAP-150. These documents include but are not' limited to:
A. General Test Procedures B. Applicable Surveillance Test Procedures C. Repair Procedures D. NDE Written Practice E. Material Control Procedures F. Inservice Inspection Reports G. NDE Procedures
, PAGE 12 0F 14
- 1
SAP-145 REVISION O 7/12/82 ,
H. Personnel Qualification Records '
{ .
x/ I. Testing Reports J. NDE Reports K. Evaluation Reports L. Analysis Reports V. Equipment Certification Records N. Material Certification Records O. Calibration Records P. Calibration Standards Q. Repair Records R. Testing and Examination Summaries S. NIS-1 Form ( Attachment II) 6.9.2 Each inservice inspection report shall be completed within 90 days after the inservice inspection r~' ' outage. The inservice inspection report will
( -
consist of, as a minimum, the Inservice Inspection Report Cover Sheeb (Attachment I) and the NIS-1.
Form. --
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6.9 3 Generally the NIS-1 Form will be a collection of data deemed necessary to verify the required NDE examinations have been performed in accordance with the requirements of this' program. The NIS-1 Form will be four basic documents as follows:
A. Components Inspected B. List of Examinations C. List of Recordable Indications D.
List of Rejectable Indications
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6.10 Documentation Review
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REVISION 0 7/12/82 6.10.1 The documentation specified in 6.9 1 and other
() required documentation shall- be reviewed for accuracy and adequacy and placed in permanent .
storage in accordance with Plant Document Control Procedures.
6.10.2 During review and evaluation of test results an off-normal occurrence report shall be initiated in accordance with SAP-132 if such report has not been previously initiated. .
6.11 Design Accessibility Limitations 6.11.1 Examinations or tests, as applicable, required by this procedure or its references shall be performed at the specific frequency to the extent practical as limited by design accessibility.
6.12 Relief Requests 6.12.1 Limitations of-the required examinations or tests which may be identified from time-to-time will be submitted to the NRC in the form of relief request (s). Relief request (s) will specify alternate examinations or tests to be performed when such tests or examinations are meaningful.
O V 6.13 NON CONFORMANCE NOTICES (NCNS) 6.13 1 Non-Conformance notices shall be initiated and dispositioned for unacceptable NDE results in accordance with A-NQCP-2.
6.14. Training 6.14.1 Unescorted Personnel performing examinations, repairs, tests or other Inservice Inspection Activities On-Site shall receive training and ,
badging in accordance with SAP-108 and other applicable Station Administrative Procedures.
4
,;,,, 7.0 FIGURES None 8.0 -RECORDS 8.1 Records generated under this procedure are identified in Section 6.9.1 and 6.9 2.
PAGE 14 0F 14
, . . . . . ._ . ~ . .- . . .- . .- . . - . . . -- . .. . ..
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~. SAP-145 i
ATTACHMENT I PAGE 1 0F 1 REVISION 0 i
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4 i
i INSERVICE INSPECTION REPORT I
! F.OR 4
VIRGIL C. SUMMER NUCLEAR STATION (Unit #1)
P. O. Box 88 Jenkinsv111e, S. C. 29065 i
)
1 SOUTH CAROLINA ELECTRIC & GAS CO.
j P. O. Box 764
}
Columbia,~S..C. . 29128 i
i Commercial Service Date
- r ' Report Completion Date
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SAP-145 .
ATTA0LEff II PAGE 1 of 2 REVISION O
( FOP 24 NIS-1 CWNERS' CATA fEPORT ICR INSERVICE INSPECTIONS
- As requimd by the Provisions & the ASME Code Rules
- 1. Owner (Nane and Address of Owner)
- 2. Plant (Nane and Address of Plant)
- 3. Plant Unit 4. Owner Certificate of Anthorization
- 5. Cannercial Service Date 6. National Bmed Number for Unit
- 7. Canponents Inspected:
Manufacturer State or National Canponent or Manufacturer or Installer Province Smed Accurtenance or Installer Serial No. No. No.
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- ATTAGE4ENT II PAGE 2 of 2 f RE7ISION O POP 4 NIS-1 (tack)
- 8. Examination Dates to 9 Inspection Interval fran _ to
- 10. Abstract of Examinations. Include a list of examinatiom and a statenent concerning status of work required for current interial.-
- 11. Abstract of Conditions Noted.
- 12. Abstract of Cormctive Measures Reconmended and Taken We certify that the statenents in this report ad cormet and ,the exaninatiom and cormctive measures taken conform to the rules of the ASME Code,Section XI.
Date 19 Signed By -
Owner -
Certificate of Authorization No. (if applicable) _ _ _ Expimtion Date
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cut.ciFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid conmission issued by the Nationa'r Board of Boiler and Pressure Vessel Inspectom and/or the State of Province of and enployed by of have inspected the conponents described in this Owner's Data Report during the period to and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Data Report in accordance with the requirunents of the ASME Code,Section XI.
By signing this certificate neither the 'Impector nor his enployer makes .any warranty, expressed or implied, concerning the examinatiom and cormctive measures described in this Owner's Data Report. Furthermore, neither the Inspector nor his enployer shall be liable in any manner for any pemonal injur"/
or property damage or a loss of any kind arising fran or connected with this inspection.
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Date 19 Ccmmissions Inspector's Signature National Board, State, Province and No.
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l SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUbE4ER NUCLEAR STATION
. NUCLEAR OPERATIONS NON-CONTROLLED C0PY GENERAL TEST PROCEDURE GTP-001 GENERAL PROCEDURE FOR INSERVICE TESTING OF PUMPS REVISION 3 OCTOBER 6, 1982
! O SAFETY RELATED Reviewed by:
%_ $ f /d b' &
VORIGIKATOR (of this revision) Date M /2 0 , la .sc ski is-zr-72 DISCIPLINE / SUPERVISOR '
Date Approved:
ff h &Q /d 7 -[2-ASST MGR, MAINTENANCE SERVICES Date 1
Date Issued:
GTP-001 PAGE 11 REVISION 3 10/6/82
() TABLE OF CONTENTS PAGE s
List of Effective Pages i 1.0 PURPOSE 1
2.0 REFERENCES
AND GLOSSARY 1 30 RESPONSIBILITIES 2 4.0 GENERAL 2 50 RECORDS 7 6.0 RESULTS 8 70 ATTACHMENTS 9 Attachment I - Pump Li st Attachment II - Symbols Attachment III- Allowable Ranges of ISI Test Quantities Attachment IV - Pump Test Sur: mary O
GTP-001 REVISION 3 10/6/82 1.0 PURPOSE 1.1 The purpose of this procedure is to define the general rules and requirements for testing of safety related ASME Code Class 1, 2, and 3 pumps which are provided with an emergency power source in accordance with subsection I'd?
of Reference 2.1.1.
2.0 REFERENCES
AND GLOSSARY 2.1 References 2.1.1 ASME Boiler and Pressure Vessel Code,Section XI, 1977 Edition through Summer 1978 addenda.
2.1.2 Virgil C. Summer Nuclear Station Technical Specifications 2.1 3 Control of Station Surveillance Test Ac tivities ,
SAP-134 2.1.4 Development, Review, and Approval of Procedures, Revisions, Changes, SAP-139 .
2.1.5 Inservice Inspection Program, SAP-144 2.1.6 Control and Calibration of Measuring and Test Equipment, SAP-141 2.1.7 Preservice Inspection Program, AP-014 2.2 Glossary 2.2.1 ANII - Authorized Nuclear Inservice Inspector 2.2.2 AP - Administrative Procedure 2.2.3 CHAMPS - Comprehensive Handling and Maintenance Program System 2.2.4 GTP - General Test Procedure 2.2 5 ISI - Inservice Inspection 2.2.6 SOP - System Operating Procedure 2.2.7 STP - Surveillance Test Procedure O
PAGE 1 OP 9
GTP-001 REVISION 3 10/6/82
() 2.2.8 STTS - Surveillance Test Task Sheet 2.2 9 Symbols - the various symbols used in this procedure to define pump parameters are listed on Attachment II.
30 RESPONSIBILITIES 3.1 The responsibilities for implementation of this procedure are delineated and described in SAP-145 4.0 GENERAL NOTES: 1) Attachment I to this procedure lists those pumps which are included in the scope of the Inservice Inspection Program. The list was developed in accordance with Reference 2.1.1 with guidance from Branch Technical Position M.E.B. No. 2.
- 2) The detailed steps necessary for the Inservice testing of these pumps are outlined in separate Surveillance Test Procedures. Attachment I lists the Surveillance Test Procedures that are applicable
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for each type of pump.
(~/ 3) The performance of Inservice Testing per Reference 2.1.1 shall be in addition to any other specified surveillance requirements.
- 4) Nothing contained in Reference 2.1.1 shall be construed to supersede the requirements of any Technical Specification.
4.1 Components
, 4.1.1 All pumps which are required to be tested in the ISI Program are listed on Attachment I.
4.2 Reference Values 4.2.1 Reference values will be used as a basis of comparison for all subsequent testing. Deviations from these reference values are indicative of changes which, depending upon the degree of !
deviation, may indicate a need for corrective action or further tests. (Refer to Section 6.0 of this procedure.)
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PAGE 2 0F 9
GTP-001 REVISION 3 10/6/82 4.2.2 Reference values shall be obtained during the G)
Preservice Inspection Program (PSI) at points of operation easily duplicated during power operation or separate baseline reference established utilizing Surveillance Test Precedures.
4.2 3 The reference values shall be clearly marked and filed as part of the pump record. If new reference values are established in accordance with subsections IWP-3111 and IWP-3112 of Reference 2.1.1, the new reference values should be clearly marked and the previous reference values retained as part of the pump record. If new reference values are established, the reason for doing so shall be justified and documenced in the pump file.
4.3 Scope of Tests 431 Each ISI test shall include measurement or observation of all quantities specified on the Pump Data Sheet, except bearing temperatures which shall be recorded at least once per year during ISI testing. -
432 When bearing temperature measurement is not h required each pump shall be run for at least $
minutes. At the end of that period at least one measurement or observation of the quantities specified in the STP shall be made and recorded on the Pump Data Sheets provided in the procedure which directs the test.
433 When measuring bearing temperature, run the pump until the bearing temperature stabilizes. Bearing temperature shall be considered stable when three successive readings taken at 10 minute intervals do not vary by more than 3%. After bearing temperature etabilization, the quantities specified on the Surveillance Test Procedure shall be measured or observed and recorded on the data sheets provided in the procedure which directs the test.
4.4 Frequency O
PAGE 3 0F 9
GTP-001 REVISION 3 10/6/82
() 4.4.1 All Quantities specified in the applicable Surveillance Test Procedure, except bearing temperature, shall be measured or observed and recorded for each pump every 31 days during normal plant operation.
NOTE: It is recommended that the above test frequency be maintained, if possible, during plant shutdown to minimize accumulation of required tests. If the tests are not conducted during plant shutdown the pump shall be tested within one week af ter the plant is returned to normal operation.
NOTE: The test frequency may be increased as a result of deviations in test quantities in comparison to reference values. Refer to Section 6.0 of this procedure for details.
4.4.2 Pumps which are normally operated more frequently than every month may be tested during normal operation provided the Pump Data Sheets and the l Pump File show each such pump was operated at the i reference values in the required flow path and the required quantities specified in the STP were ,
measured, observed, analyzed and recorded on the
() 4.4.3 applicable Pump Data Sheets.
Bearing temperature shall be measured and recorded at least once per year for each pump during an ISI test on that pump.
4.4.4 Each pump's Inservice test shall be performed at the specified time interval with:
A. A maximum allowable extension not to exceed 25%
of the Surveillance Interval.
B. A total maximum combined interval for any three (3) consecutive surveillance intervals is not to exceed 3.25 times the specified surveillance interval.
NOTE: Refer to the applicable Surveillance Test Procedure for the required parameters to be measured.
4.5 Measurement Methods PAGE 4 0F 9
GTP-001 DEVISION 3 10/6/82 4.5 1 All instruments used for Inservice Tests may have nominal errors within the following limits and the l range of each instrument shall not exceed three (3) times the reference value.
NOMINAL MAXIMUM INSTRUMENT ERRORS Pressure i 2% of Full Scale Differential Pressure 1 2% of Full Scale Flowrate + 25 of Full Scale Speed i 25 of Full Scale Temperature ? 5% of Full Scale Vibration Amplitude 1 5% of Full Scale NOTE: V. C. Summer calibrated Field Test Equipment and/or Process Instruments satisfy these accuracy requirements.
452 All instruments (together with their transmitters, -
if required) used in measuring the inservice test quantities listed in the STP during Inservice testing shall be calibrated in accordance with reference 2.1.6, SAP-141, " Control and Calibration of Measuring and Test Equipment".
453 Instruments, in which the readings are position sensitive, i.e., vibration amplitude, shall be permanently mounted or provisions will be made in the Preoperational/ Functional testing procedures and the STPs to duplicate position for each test.
4.5 4 Symmetrical damping devices or averaging techniques may be used to reduce instrument fluctuations to within + 2% of the observed reading. Hydraulic readings may be damped by using gage snubbers or by throttling small valves in instrument lines. If throttling of small valves is used, the operator should alternately open and close the valve several times to verify unobstructed pressure communication, while observing the instrument reading.
O PAGE 5 0F 9
GTP-001 REVISION 3 7-- 10/6/82
- 4.5 5 The following instructions refer to pressure measurement during the test as outlined in subsection IWP-4200 of Reference 2.1.1.
A. Gage Lines: If a gage line is such that the presence or absence of liquid could produce a difference of more than 1/4% in the indicated value of the measured pressure, means shall be provided in the STP to assure or determine the presence or absence of' liquid as required for the static correction used.
B. Pressure Taps: Pressure taps shall be located in a section of the flow path that is expected to have reasonably stable flow as close as practical to the pump. Any line valves between inlet and discharge pressure taps shall be in a fully open position during the test.
C. Differential Pressure: The differential pressure across a pump shall be determined by use of either a differential pressure gage or differential pressure transmitter that provides direct measurement of pressure difference, or .
s by taking the difference between the pressure Os at a point in the inlet pipe, and the pressure at a point in the discharge pipe.
456 The following instructions refer to temperature measurement during the test as outlined in Subsection IWP 4300 of Reference 2.1.1.
A. Bearing Temperature: The temperature of all centrifugsl pump bearings outside the main flow path shall be measured at poin* selected to be responsive to changes in the temperature of the bearing. These points will be used for subsequent measurements. Lubricant temperature, when measured prior to a cooler, shall be considered the bearing temperature.
B. Alternately, a contact pyrometer on the pump bearing housing may be used. When usir.g a contact pyrometer on the bearing housing the location at which the reference value is established will be used for subsequent measurements.
s PAGE 6 0F 9
GTP-001 .
REVISICN 3 10/6/82 4.5.7 The following instructions refer to vibration llhI measurement during the test as outlined in Subsection IWP-4500 of Reference 2.1.1.
A. At least one displacement vibration amplitude (peak-to-peak composite) shall be read during each inservice test. The direction of displacement shall be measured in a plane approximately perpendicular to the rotating shaft, and in the horizontal or vertical direction that has the largest deflection for the particular pump installation.
B. The locatien shall generally be on a bearing housing, or its structural support, provided it is not separated from the pump by any resilient mounting. On a pump coupled to the driver, the measurement shall be taken on the bearing housing near the pump coupling, the measurement point shall be as close as possible to the inboard bearing.
4.5.8 The following instructions refer to Flow Measurement during the test as outlined in
- Subsection IWP-4600 of Reference 2.1.1.
A. Flow vate shall be measured using a rate or quantity meter installed in the pump test circuit. The meter may be in any class that provides an overall readout repeatability within the accuracy limits of 4.5.1.
B. Where the meter does not indicate the flow rate directly, the record shall include the method to reduce the data.
5.0 RECORDS 5.1 A file will be maintained for each pump covered by this ISI Program. The file will include the following items and must be retained for the lifetime of the component.
5 1.1 A Pump Data Sheet listing reference values.
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PAGE 7 0F 9 l
1
GTP-001 REVISION 3 10/6/82
() NOTE: If a new set of reference values are established as permitted by Subsection IWP-3111 and IWP-3112 of Reference 2.1.1, the file will contain documentation of the reasons for establishing additional set of reference values. In addition, the previous reference values may be maintained to indicate they have been superseded or maintained as a separate set of reference values.
5 1.2 Pump Data Sheets for each test which has been performed.
513 The name of the pump manufacturer, manufacturer's serial number, manufacturer's model number and the equipment identification number.
5 1.4 A copy of the Manufacturer's Acceptance Test, if any, or a summary thereof.
515 A copy of the ISI Pump Data Sheet Acceptance-Criteria and a record of corrective action, if applicable, for each test which has been performed.
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5 1.6 Any additional data which would enhance the ability O of plant personnel to analyse trends and assess operational readiness.
52 When using flow meter (s) to measure flow in inches of H 2 O the following formula may be used to calculate flow in gallons per minute where:
0 = Flow (gallona per minute)
- X = Constant for type and size of orifice and system resistance Y = Flow in inches of water Q = X1fi'~
53 Relief requests, if any, shall be referenced on Attachment I. Such relief requests shall be indexed, stored and maintained under separate cover.
6.0 RESULTS 6.1 All test data must be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> of test 4 completion; however, weekends and/or holidays are not included in this ttne frame. (Reference Relief Request E.1) 6.2 The Acceptable, Alert, and Required Action Ranges of ISI test quantities are tabulated on Attachment III. The ranges are expressed as a percentage of the reference O values. If the ISI Test Quantities deviate from the Acceptable Range, the following corrective action statements shall be observed:
PAGE 8 0F 9
GTP-001 REVISION 3 10/6/82 6.2.1 If the ISI Test Quantities fall within the Alert Range as shown on Attachment III, the frequency of testing shall be doubled until the cause of deviation is determined and corrected and either the existing reference values reverified or a new set established in accordance with Subsections, IWP-3111 and IWP-3112 of Reference 2.1.1.
6.2.2 If the ISI Test Quantities fall within the Required Action Range of Attachment III:
A. The pump shall be declared inoperative.
B. The pump shall not be returned to service until the condition has been corrected and a satisfactory ISI test has been conducted or engineering evaluation has been performed to permit operability of the pump.
63 The Shift Supervisor will review the test data immediately upon completion of the test and compare it to the acceptable ranges as shown on Attachment III. If the results are unsatisfactory, he shall initiate corrective action, including any Limiting Condition for Operations, .
as required by V. C. Summer Technical Specification.
NOTE: The Limiting Condition for Operation will be O referenced in the STP for those pumps whose inoperability require a Limiting Condition for Operation.
6.4 A summary, Attachment IV, will be maintained indicating the "Date of Successful Test" for each pump.
70 ATTACHMENTS 71 Attachment I - Pump List 72 Attachment II - Symb'ols 73 Attachment III- Allowable Ranges of ISI Test Quantities.
7.4 Attachment IV - Pump Test Summary e
PAGE 9 0F 9
GTP-001 ATTACHMENT I PAGE 4 of 4 REVISION 3 I
. TEST LIST STP-120.001 - Emergency Feedwater Pump (Electric) Test STP-120.002 - Emergency Feedwater Pump (Turbine) Test STP-123 002 - Service Water Pump Test STP-125.002 - Diesel Generator Operability Test STP-122.002 - Component Cooling Water Pump Test l
STP-105 004 - RHR Pump Test STP-129 001 - Chilled Water Pump Test STP-104.005 - Boric Acid Transfer Pump Test STP-112.002 - RB Spray Pump Test STP-105.001 - Charging / Safety Injection Pump Test O
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UfP-001 ATIACE'E?C II PAGE 1 of 1 REVISICfl 3 SDEiOLS QUAlfflTIES U!iiTS UNIT AEEFEVIATICU M, 1 Exponents - -
P Differential Pressure Ebunds per psi across Pump square inch Pi Inlet Pressure Pounds per psig square inch gage Pd Discharge Pressure Pounds per psig square inch gage Q Flow Pate 3allons per gpn ninute r Subscript denotes reference quantity N Rotative Speed Revolutions per minute Tb Bearing Temp. Deg. Fhhrenheit F l
Tp Fluid Temp. Deg. Fahrenheit F V Vibration amplitude Ihousaniths of mil (Peak-to-Peak) an inch
> Greater Wan - -
< Less 'Ihan - -
> Greater 'Ihan or Equal to - -
1 Less 'Ihan or Equal to - -
O
GTP-001 ATTACilMENT III-PAGE 1 of 1 REVISION 3 ALLOWABLE RANGES OF ISI TEST QUANTITIES
_ CORRECTIVE ACTION _
Test Alert Range 3 Required Action Range 3 Quantity Acceptable Range Low Values High Values Low Values High Values F1 Note 1 Note 1 Note 1 Note 1 Note 1 P ( Pd-P1) (.93 to 1.02) Pr (.90 to 93) Pr (1.02 to 1.03) Pr <.90 Pr >1.03 Pr Q (.94 to 1.02)Qr (.90 to 94)Qr (1.02 to 1.03)Qr <.90 Qr >1.03 Or V When 0 i Ve < 0.5 mil o to 1 mil none 1 < V 1 1. 5 mil none V > 1. 5 mil V When 0.5 mil < Vr 2 Vr mil to 1 2.0 mil V(0 to 2)Vr mil none 3 Vr mil none > 3Vr mil V When 2.0 mil < Vr (2tVr) mil to I 5 0 mil 0 to (2+Vr) mil none (4+Vr) mil none > ( 4+Vr) mil V When Vr > 5.0 mil (0 to 1.4)Ve mil none 1.4 Vr mil to 1.8 Vr mil none > 1.8 Vr mil Tb Note 2 Note 2 Note 2 Note 2 Note 2
'OTES:
- 1) Pt - The pump inlet pressure will be determined during the PSI portion of this program.
- 2) Tb - The bearing temperature will be determined during the PSI portion of this program.
- 3) Refer to Section 6.0 of this procedure.
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GTP-001 ATTACllMENT I PAGE 1 oP 13 IlEVISION 3 PUMP PUMP DRAWING RELIEF HUMBEll SYSTEM DESCRIPTION NUMBER CO-ORD REQUEST REMAflKS X P P- 21 A EF MOT 0ft DRIVEN EMEllGENCY FEED 302-085 D-7 NO STP-120.00l*
WATER PUMP _
XPP-21B EP MOTOR DITIVEN EMERGENCY FEED 302-085 F-6 NO STP-120.00l*
WATER PUMP XPP-8 EP TUllBINE DilIVEN EMERGENCY FEED 302-085 II-6 NO STP-120.0025 WATEll PUMP XPP-39A SW SEllVICE WATER PUMP 302-221 C-2 NO STP-123.002*
XPP-39B SW SERVICE WATER PUMP 302-221 C-10 NO STP-123 002*
X P P- 39 C SW SEllVICE WATEll PUMP 302-221 C-6 NO STP-123 002*
XPP fl5A SW SERVICE WATEll BOOSTER PUMP 302-222 C-6 YES STP-123 0025 i B.1 XPP 145B SW SEllVICE WATEll BOOSTER PUMP 302-222 G-6 YES STP-123.002* I B.1 X PP-ll41 A DG DIESEL GENEllATOR FUEL OIL 302-351 0 - 1 14 YES STP-125 002* .
TIlANSFER PUMP A.1 XPP-1111B DG DIESEL GENEllATOR FUEL OIL 302-351 0-2 YES STP-125 002*
I TRANSFEll PUMP A.1 XP P 14 A DG DIESEL GENERATOR FUEL OIL 302-351 0-12 YES STP-125 002* ,
TilANSFER PUMP A.1 O O O
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~ (_) A'l IMENT I PAGE 2 of 4 REVISION 3 PUMP PUMP DRAWING RELIEF NUMBER SYSTEM DESCRIPTION NUMBER CO-ORD REQUEST IlEMARKS XPP IB I DG DIESEL GENEllATOR FUEL OIL 302-351 G-3 YES STP-125.002" TRANSFER PUMP A-1 XPP-1A CC A COMPONEllT COOLING WATER PUMP 302-611 G-8 NO STP-122.0025 X PP- 1B CC B COMPollENT COOLING WATER PUMP 302-611 Gll NO STP-122.002n X P P-1C CC C COMPONEllT COOLING WATER PUMP 302-611 H-6 NO STP-122.0025 X P P- 31 A Ril A RESIDUAL HEAT REMOVAL PUMP 114 E0711 C-7 NO STP-105.004*
X PP-31B Ril B llESIDUAL llEAT REMOVAL PUMP 114E074 E-7 NO STP-105.0045 XPP Il8A VU llVAC SYSTEM A CilILLED WATER 302-841 E-10 NO STP-129 001*
PUMP XPP Il8B VU llVAC SYSTEM B CHILLED WATER 302-841 E-5 NO STP-129 001*
PUMP XPP il8C VU llVAC SYSTEM C CilILLED WATER 302-8141 E-5 NO STP-129.001*
PUMP XPP-13A BH A BORIC ACID TRANSFER PUMP 1118 E073, E-8 YES STP-10ll.005*
Sil 5 C.1 a XPP-13B BR D BORIC ACID TIIANSFER PUMP 111lE07 3, C-8 YES STP-10ll.005*
Sil 5 C.1 (
GTP-001 ATTACilMENT I PAGE 3 or 4 REVISION 3 PUMP PUMP DRAWING RELIEP NUMBER SYSTEM DESCRIPTION NUMBER CO-ORD REQUEST REMARKS 3 XPP-38A SP A REACTOR BUILDING SPRAY PUMP 302-661 D-6 NO *STP-112.0025 E X P P- 38 B SP B REACTOR BUILDING SPRAY PUMP 302-661 E-6 NO STP-112.0028 X PP-4 3 A CS A Cil AllGING AND SAFETY INJEC- 114E073 E-8 YES STP-105.00l*
TION PUMP Sil 3 D.1 _
X PP-43B CS B CHARGING AND SAFETY INJEC- 114E073 C-8 YES STP-105 001*
TION PUMP SH 3 D.1 X P P-43C CS C CHARGING AND SAFETY INJEC- ll4E073 D-8 YES STP-105 00l*
TION PUMP Sil 3 D.1
- See attached Test List (page 4 or 5)
- itELIEP REQUEST E.1 APPLIES TO ALL PUMPS IN TilIS ATTACilMENT.
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PUNP TEST RELIEF I?lDEX i
A. System: Diesel Fuel Oil A.1 Pumps: XPP-141A Page 1 XPP-141B XPP-4A XPP-4B B. System: Service Water B.1 Punps: XPP-451. Page 2 XPP-45B C. System: Chemical and Volume Control C.1 Pumps: XPP-13A Page 3 XPP-13B D. Systen: Safety Injection D.1 Pt:mps : XPP-43A Page 4 XPP-43B XPP-43c E. System (s): EP, SW, DG CC , RH , VU RB, SP, CS E.1 Pump (s): All Identified in the ON Inservice Inspection Program (GTP-001)
NOR-CONTROLLD C0PY PAGE I-1 i
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PUMP TEST RELIEP REQUESTS A.1 Pump (s): XPP-141A, XPP-141B, XPP-4A, XPP-4B Class: 3 Function: Diesel Fuel Oil Transfer Pumps Test Requirement: Each Inservice Test shall include measurement and/or observation of the following quantities: Inlet Pressure (P1),
Differential Pressure @ P), Flow Rate (Q) ,
Vibration Amplitude (V), Lubricant Level and Bearing Temperature (Tb).
Relief Request: Relief is requested from ASME Code Section XI Requirements for measuring everything except flow.
Basis For Relief: These pumps are positive displacement with self lubricated internal bearings.
Therefore, flow measurement is indicative of pump performance.
Alternate Test: Flow measurement will be taken when pucps are used to pump up the Diesel Fuel Oil Tank at least once each month.
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PUMP' TEST RELIEF REQUESTS B.1 Pump (s): XPP-45A, XPP-45B -
Class: 3 Punction: Service Water Booster Pumps Test Requirenant: Each Inservice Test .shall include measurement and/or observation of the following quantities: Inlet Pressure (P1),-
Differential Prescure (DP), Flow Rate (Q),
Vibration Amplitude (V), Lubricant Level or Pressure and nearing Temperature (Tb' .
Relief Request: Relief is requested f rom ASME Code Section XI Requirements for measuring flow.
Basis For Relief: Full Flcw Test would be detrimental to water chemistry the Reactor Building cooling units. The installed flow element / transmitter is downstream of the recirculation line and would .6t be representative of total pump flow when pump is tested by recirculation flow.
Alternate Test: Pumps will be tested on recirculation, measuring pump P utilizing pump suction and discharge pressure instrumentation. Pump P
(
A is indicative of pump performance which satisfies the intent of ASME Code Section XI.
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PUMP TEST RELIEF REQUESTS C.1 Pump (s): XPP-13A, XPP-13B
() Clacs:
Function:
2 Boric Acid Transfer Pumps Teat Requirement: Each Inservice Test shall include measurement and/or observation of the following quantities: Inlet Pressure (P1),
Differential Pressure ( AP), Flow Rate (Q),
Vibration Amplitude (V), Lubricant . Level or Pressure and Bearing Temperature (Tb) .
Relief Request: Relief is requested from ASME Code Section XI Requirements f or measurin$ flow and vibration.
Basis For Flow Relief There is no installed flow element in the system.
Alternate Test Fo r Flow : Pumps will be tested by recirculating to their associated tank and measuring pump AP utilizing tank level as suction pressure Basis For (S Vibration Relief: These pumps are canned motor / pump units t which have water lubricated sleeve bearings.
Representative vibration indication cannot be obtained on the pump casing due to the
- damping effect of the water.
Alternate Test For Vibration: Each pump will be disassembled annually and inspected for abnormal wear or degradation in accordance with Mechanical Maintenance Procedures.
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PAGF 3
PUMP TEST RELIEF REQUESTS D.1 Pump (s): XPP-43A, XPP-43B, XPP-43C f
(v)) Class: 2 .
Func tion : Charging / Safety Injection Pumps Test Requirement: Each Inservice Test shall include measurement and/or observation of the following quantities: Inlet Pressure (P1),
Differential Pressure ( AP) , Flow Rate (Q),
Vibration Amplitude (V), Lubricant Level or Pressure and Bearing Temperature (Tb) .
Relief Request: Relief is requested from ASME Code Section XI Requirements for measuring flow.
Basis For Relief: The installed Flow Element / Transmitter is downstream of the seal injection and would not be representative of total pump flow.
Alternate Test: Technical Specification 4.1.2.3.1 " Required Charging Pump shall be demonstrated operable by verifying, on recirculation flow, a differential pressure across the pump of greater than or equal to 2472 PSIG is developed.
fN This test is required to be performed at
() least once per 31 days except when the vessel head is removed, thus is indicative of pump performance and satisfies the intent of ASME Code Section XI Flow Test.
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PUMP TEST RELIEF REQUESTS E.1 Pump (s): All identified in the Inservice Inspection Pror,ran (OTP-001)
Class: 1, 2 and 3 Function: Defined by GTP-001 Requirements: To review test data within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from the time test was performed.
Relier Request: To exclude weekends and/or holidays from ' the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> time frane starting at 4 : 00 P.M. on day preceding and ending at 8:00 A.M. on the day following the weekend and/or holiday, as applicable.
Alternate Review test data within 3 working days Requirements: follow 1N the weekend and/or holiday not to -
exceed 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> accumulated time excluding weekends and/or holidays.
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! SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS ,
GENERAL TEST PROCEDURE
- GTP-002 GENERAL PROCEDURE FOR INSERVICE TESTING OF VALVES REVISION 4 i SEPTEMBER 11, 1982 NON-CONTROLLED SAFETY RELATED Reviewed by
COPY OKIGIt4 ATTN 1 (of this revision) b . $& }0~/f~T &
Date A M . b OAS /0 Date -/ f "N FISCItLINE SUPERVISOR
- I
! Approved:
h ASST.MGR. MAINTENANCE SERVICES w fa - 2 7 -fz Date Date Issued: OCT 2 9 s82 O
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4 GTP-002 PAGE i REVISION 4 9/11/82 h LIST OF EFFECTIVE PAGES PAGE REVISION L 4 11 4 1 4 2 4 3 4 4 4 5 4 6 4 7 4 8 4 9 4
!. 10 4 11 4 12 4 ;
, 13 4 i j 14 4 15 4
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': le rt sd ,A 1 Attachment I, Pages 1 thro 69 r.- 4
. .pg Attachment II pt y j; 2.;vf TV y 4 Attachment III 4 i
Attachment IV, Pages 1 and 2 4 l ;
Attachment V, Pages 1 and 2 4 i
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, i GTP-002 PAGE 11 REVISION 4 9/11/82 TABLE OF CONTENTS
. PAGE 1.0 PURPOSE 1
2.0 REFERENCES
AND GLOSSARY 1
2.1 REFERENCES
1 2.2 GLOSSARY 2 30 RESPONSIBILITIES 4 4.0 GENERAL 4 4.1 COMPONENTS 4 4.2 PRESERVICE EXAMINATION 5 4.3 VALVE RE."LACEMENT/ REPAIR MAINTENANCE 5 4.4 INSERVICE TESTING REQUIREMENTS 5 50 RECORDS 12 6.0 RESULTS 12 70 ATTACHMENTS 15 7.1 ATTACHMENT I 72 ATTACHMENT II 73 ATTACHMENT III 7.4 ATTACHMENT IV 7.5 ATTACHMENT V O
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. s GTP-002 REVISION 4 9/11/82 1.0 PURPOSE 1.1 This procedure defines the general rules and requirements for testing of ASME Code Class 1, 2 and 3 valves in -
accordance with subsection IWV of reference 2.1.1 and provides for the scheduling of the Inservice Testing of those valves. In addition, this procedure provides the interface between the Preservice Inspection Program for
. valves which are the responsibility of the SCE&G Start-Up personnel and the Inservice Inspection Program which is the responsibility of SCE&G Nuclear Operations personnel.
1.2 ' Attachment I to this procedure lists those valves included in the scope of the Inservice Inspection program. The valve list was developed, with guidance from Branch Technical Position MEB No. 2, " Pump and Valve Operability ,
Assurance Program, utilizing the following criteria:
" Valves that are required to perform a specific function in shutting down the reactor to the cold shutdown condition or in mitigating the consequences of an Accident".
1.3 The detailed steps necessary for preservice testing of '
these valves are outlined in separate -
Preoperational/ Functional Test Frocedures.
1.4 The detailed steps necessary for the Inservice testing of these valves are outlined in separate Surveillance Test Procedures. Attachment IV to this procedure lists the Surveillance Test Procedures that are applicable for each valve. ; ,
1.5 The performance of Inservice Testing in accordance with Reference 2.1.1 shall be in addition to any'other specified surveillance requirements . '
l.6 Nothing contained in Reference 2.L: 1 shall be co'natrued to supersede the requirements of any Technical Specification.
2.0 REFERENCES
AND GLOSSARY 2.1 References 4
PAGE 1 0F 15 O
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GTP-002
' REVISION ~4 O ,
2.1.1 American Society of Mechanical Engineers (ASME) 9'11'82 Boiler and Pressure' Vessel Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 1977 Edition, Summer 1978 Addenda, Subsection IWV.
2.1.2 V. C. Summer Technical Specifications 2.13 SAP-139 Development, Revision and Approval of Procedures 2.1.4 SAP-145, Inservice Inspection Program 2.1.5 SAP-134 Control of Station Surveillance Test Activities 2.1.6 SAP-141, Control and Calibration of Measuring and Test Equipment 2.17 PTC 25 3 1976 - Power Test Cedas, " Safety and Relief Valves with Atmospheric or Superimposed Backpressure Before Charging" 2.1.8 V. C. Summer Operational Quality Assurance Plan -
2.1 9 v. C. Summer Final Safety Analysis Report 2.1.10 10 CFR 50.55a(g) 2.1.11 Branch Technical Position MEB No. 2, " Pump and Valve Operability Assurance Program" 2.2 Glossary 2.2.1 STP - Surveillance Test Procedure 2.2.2 AP - Administrative Procedure 2.2.3 GTP - General Test Procedure 2.2.4 PSI - Preservice Inspection - Preservice Inspection as used in this procedure refers to the establishment of reference values by conducting a Preservice Inspection test prior to service. The.
Preservice Inspection is conducted through the use of Preoperational/ Functional tests.
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GTP-002 REVISICN 4 9/11/82 2.2 5 ISI - Inservice Inspection - Inservice Inspection as used in this procedure' refers.to a special valve test whose results may be compared to previously established reference values to assess the operational readiness of a valve. The Inservice Inspection is conducted through the use of Surveillance Test Procedures.
Code - As used in this procedure, shall refer to ASME Code,Section XI,1977 Edition, Summer 1978 Addenda, unless otherwise specified.
2.2.6 LCO - Limiting Condition for Operation 2.2 7 Categories of valves subject to the rules of this procedure are defined in accordance with reference 2.1.1 as follows:
A. Category A - valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function.
B. Category B - valves for which seat leakage in the closed position is inconsequential for -
fulfillment of their function.
C. Category C - valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves).
D. Category D - valves which are actuated by an energy source capable of only one operation, i.e. , Rupture Disks or Explosive-Actuated Valves.
NOTE: Combination of categories, such as categories A/C are to be used when more than one distinguishing category characteristir is applicable. In such cases, all requirements of each of the individual categories are applicable, although duplication or repetition of common testing requirements are not necessary.
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GTP-002 REVISION 4 g-s 9/11/82
- 2.2.8 " CHAMPS" - Comprehensive Handling and Maintenance Program System; i.e., Periodic Task Scheduling 2.2 9 ISI Coordinator - SCE&G Nuclear Operations Assistant Manager Maintenance Services or his designee will fill this position.
2'.2.10 PS - Excercise valves (full stroke) for operability every three (3) months measuring time of stroke and comparing it to the previous measured time.
2.2.11 LT - Valves are leak tested at each refueling outage per Appendix J to 10 CFR50 55a.
2.2.12 CV - Exercise check valves to the position required to fulfill their function every three (3) months .
2.2.13 SRV - Safety and' Relief valves are tested per Section XI Article IWV-3510.
2.2.14 CS - Excercise valves (full stroke) for operability every cold shutdown measuring time of stroke and comparing it to the previous measured time.
2.2.15 RS - Exercise valve (full stroke) for operability
(N every refueling shutdown measuring time of stroke
\s,) and comparing it to the previous measured time.
2.2.16 ANII - Authorized Nuclear Inservice Inspector 2.2.17 LOCA - Loss of Coolant Accident 30 RESPONSIBILITIES 31 The responsibilities for implementation of this procedure are delineated and described in SAP-145 4.0 GENERAL 4.1 Component's 4.1.1 All valves which require inservice testing are listed on Attachment I. The guidelines of Branch Technical Position MEB No. 2, " Pump and Valve Operability Assurance Program" was used in developing this. list.
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GTP-002 REVISION 4 9/11/82 4.1.2 Valve categories are listed on Attachment I. Valve categorization has been performed in accordance with subsection IWV-2100 of the Code.
4.2 Preservice Examination 4.2.1 Each valve listed en Attachment I shall be given a Preservice Test, as required by subsection IWV of the Code, af ter installation and prior to entering service. This test will constitute the Preservice test required by subsection IWV-3100 of the Code.
4.2.2 The preservice examination shall be conducted in accordance with approved Preoperational/ Functional test procedures.
43 Valve Replacement / Repair and Maintenance 4.3 1 After a valve or its control system has either been replaced, repaired, or has undergone maintenance that could affect its performance, and prior to the time it is returned to service, it shall be tested as necessary to demonstrate that the performance parameters which cculd be affected by the replacement, repair, or maintenance are within acceptable limits .
l EXAMPLE: Adjustment of stem packing; removal of the bonnet, stem assembly, or actuator; Or disconnection of hydraulic or electrical lines are examples of maintenance that could affect valve performance parameters.
4.4 Inservice Testing Requirements 4.4.1 Category A & B Active Valves Exercising Test Frequency A. Category A & B valves shall be exercised at least once every 3 months with exceptions as noted in Section 4.4.2A and 4.4.2B-B. Category A & B valves in regular ase which operate at a frequency which woulc satisfy the exercising requirements noted above need not be additionally excercised provided that the required observations are made, analyzed and recorded at the specified intervals.
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GTP-002 REVISION 4 9/11/82
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5/ C. If Category A & B valves are located in a system which is out of service exercising is not required for such valves except immediately prior to returning the system to service.
NOTE: During plant shutdown Inservice test frequencies should be maintained where possible to minimize the number of tests required prior to returning to normal operation.
4.4.2 Category A & B Valves Exercising Procedure Scope A. Valves shall be exercised to the position required to fulfill their function unless-such operation is not practical during plant operation. If only limited operation is practical during plant operation the valve shall be part-stroke exercised during plant operation and full-stroked during each cold shutdown; in case of frequent cold shutdowns these valves need not be exercised more often than once every 3 months. Normally closed valves that cannot be exercised during normal plant operation are identified on Attachment I and shall be exercised during each cold -
/)
(,j shutdown; in case of frequent cold shutdowns these valves need not be exercised more often than once every 3 months.
B. Fail-Safe Valves. Where practical ' valves with fail-safe actuators shall be tested by observing the operation of the valves upon loss of actuator power. When these "alves cannot be tested once every 3 months they shall be tested during each cold shutdown; in case of frequent cold shutdowns, these valves need not be tested more often than once every 3 months.
C. The necessary valve stem cr disk movement shall be established by exercising the valve while observing either an appropriate indicator which signals the required change of valve stem or disk position, or indirect evidence, such as changes in system pressure, flow rate or temperature which reflect stem or disk position.
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e GTP-002 REVISION 4 9/11/82 D. The following requirements apply to Category A
& B Power Operated Valves .
- 1. The limiting value of fall stroke time of each power operated valve is listed on Attachment I.
- 2. The strok3 time of all power-operated valves shall be measured to the nearest second or within 10% of the maximum allowable stroke time, whichever is less, whenever such a valve is full-stroke tested.
3 Stop watches or other appropriate timing devices shall be used when timing power operated valves.
- 4. Panel light indicators shall be used when verifying motor operated, air operated and valves with fail-safe actuators.
NOTE: At least once every two years, remote indication will be checked to verify that remote valve indications accurately reflect valve operation for -
valves which are inaccessible for direct observation during plant operation. lh 4.4.3 Category A Valve Leak Test Frequency A. Category A valves shall be leak tested at the same or greater frequency as scheduled refueling outages but not less than once every two years.
4.4.4 Category A Valve Leak Test Procedure Scope A. The Category A Valve seat leakage tests shall be made with the pressure differential in the same direction as w111 be applied when the valve is performing its function with the following exceptions:
- 1. Any globe type valve may be tested with pressure under seat.
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GTP-002 REVISION 4 9/11/82 7s i 2. Butterfly valves may be tested in either direction, provided their seat construction is designed for sealing against pressure on either side.
3 Gate valves with two-piece disks may te tested by pressuricing such valves between the seats.
- 4. All valves (except check valves) may be tested in either direction if the function differential pressure is 15 psi or less.
5 The use of leakage tests involving pressure differentials lower than function pressure differentials are permitted in those types of valves in which service pressure will tend to diminish the overall leakage channel opening, as by pressing the disk into or onto the seat with greater force.
Gate valves, check valves, and globe type valves having function pressure differential applied over the seat, are examples of valve applications satisfying this requirement. When leakage tests are .
made in such pressures lower than function
/~' maximum pressure differential, the observed
(~~T/ leakage shall be adjusted to function maximum pressure differential value by calculation appropriate to the test media and the ratio between test and function pressure differential assuming leakage to be directly proportional to the pressure differential to the one-half power.
- 6. Any valves not qualifying for reduced pressure testing as defined above shall be leak tested at full maximum function pressure differential, with adjustment by calculation if needed to compensate for a difference between service and test media.
7 Valves which function in the course of plant operation in a manner that demonstrates functionally adequate seat tightness need not be leak tested. In such cases, the valve record shall provide the basis for the conclusion that operational observation constitutes satisfactory demonstration.
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GTP-002 REVISION 4 9/11/82 B. Category A valve seat leakage may be determined by: ,
- 1. Draining the line, closing the valve and pressurizing the valve to be tested as outlined in Section 4.4.4.A and r.easuring leakage through a downstream telltale connection.
- 2. Measuring the feed rate required to maintain pressure between two valves, or between two seats of a gate valve, provided the total apparent leak rat is charged to the valve or gate valve seat being tes ted, and that the conditions required above are satisfied.
C. The detailed steps necessary to check seat leakage will be outlined in the STP or Preoperational/ Functional Test Procedure directing the test.
D. The test medium shall be spec.ified in the STP or Preoperational/ Functional Test Procedure -
directing the test.
E. The leakage limits associated with valve seat leakage are listed on Attachment V. These limits are established based on the following:
- 1. For penetration / containment Isolation Valves there are three limits (1) suggested limit so as not to exceed the .6 La limit, as specified in Appendix J, (2) an alert limit to identify those valves which might become a problem, and (3) the maximum limit when repairs or replacement snould occur except as may be otherwise approved by Nuclear Engineering.
- 2. Technical Specifications 3.4.6.2f - 1 GPM leakage at a Reactor Coolant System Pressure Isolation Valve specified on Attachment V, Page 2 of 3, when RCS pressure is at 2235 120 psig.
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GTP-002 '
REVISION 4 9/11/82 O)
(, 4.4.5 Category C Valves Test Frequency A. Safety / Relief valves shall be tested at the end of each time period as defined on Attachment I.
B. Check valves shall be exercised every 3 months subject to the exceptions listed in section 4.4.6.B of this procedure.
4.4.6 Category C Valves Test Procedure Scope A. Safety Valve and relief valve set points shall be tested in accordance with reference 2.1 7 B. Check valves shall be exercised to the position required to fulfill their function unless such operation is not practical during plant operation. If only limited operation is practical during plant operation the check valve shall be part-stroke exercised during plant operation and full-stroked during each cold shutdown. In case of frequent cold shutdowns these check valves need not be exercised more often than once every 3 months. .
Normally closed check valves that cannot be
(/)
operated during normal plant operation are identified on Attachment I and shall be exercised during each cold shutdown. In case of frequent cold shutdowns these check valves need not be exercised more of ten than once every 3 months. The following section delineates the general methods to be used in testing either a normally open or normally closed check valve.
- 1. Check valves which are normally open during plant operation whose function is to prevent reversed flow, shall be tested in a manner that proves that the disk travels to the seat promptly on cessation or reversal of flow. Confirmation that the disk is on its seat shall be by visual observation, by an electrical signal initiated by a position indicating device, by observation of appropriate pressure indications in the system, or by other positive means.
PAGE 10 0F 15 y n p - _-_ _ .-m -,- #-- ,
. GTF-002 REVISION 4 9/11/82
- 2. Check valves which are normally closed during plant operation, whose function is to open on reversal of pressure differential, shall be tested by proving that the disk moves promptly away from the seat when the closing pressure differential is removed and flow through the valve is initiated, or a mechanical opening force is applied to the disk. Confirmation that the disk moves away from the seat shall be by visual observation, by electrical signal initiated by a position indicating device, by observation of substantially free flow through the valve as indicated by appropriate pressure indications in the system, or by other positive means.
This test may be with or without flow through the valve. If it is made without flow through the valve, a mechanical exerciser shall be used to move the disk.
The force or torque delivered to the disk by the exerciser must be limited to no more than 10% of the equivalent force or torque represented by the minimum emergency condition pressure differential acting on the disk, or 200% of the actual observed a force or torque required to perform the exercise on the valve when the valve is new and in good operating condition, whichever is less.
The disk movement shall be sufficient to prove that the disk moves freely off the seat. For swing or tilting disk type valves, if the test is made by use of fluid flow through the valve, the pressure differential for equivalent flow shall be no greater than that observed during the preservice test. For other types of check valves , it shall be shown that disk movement is sufficient to provide a flow area of no less than 50% of the area of the seat port, or to permit flow adequate for the function of the valve.
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GTP-002 REVISION 4 9/11/82 4.5 Those valves required to be tested during Cold Shutdown will commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving Cold Shutdown and continue until Startup or untti testing is complete, whichever occurs first.
5.0 RECORDS 5.1 A' file will be maintained for each group of valves covered by the ISI Program. The file will include the following:
5.1.1 Valve Test Summary (Attachment III).
5.1.2 Recordr. of cer.ults from ISI tests that have been conducted on a valve.
5.1.3 Any additional data which would enhance the ability of plant personnel to analyze trends and assess operational readiness.
5.2 Relief requests, if any, shall be referenced on t';tachment I. Such relief requests shall be indexed, stored and maintained under separate cover.
6.0 RESULTS
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6.1 The results of Inservice Valve Tests shall be analyzed to acsess the operational readiness of each valve.
6.2 The following points shall be observed when analyzing the results of the power operated Category A & B valve exercising test.
6.2.1 If any power operated Category A & B valve shows an increase in the stroke time of 25% or more from the
- i previous test for valves with stroke ttmes greater than ten seconds or 50% or more for valves with stroke times less than or equal to ten seconds, the
- test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed.
In any case any abnormality or erratic action shall be reported.
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4 GTP-002 REV.ISION 4 9/11/82 6.2.2 If a power operated valve fails to exhibit the h required change of valve stem or disk position by this testing, corrective action shall be initiated immediately. If the condition is not , or can not be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the valve shall be declared inoperative. (The STP directing the test will outline any LCO's which apply.)
6.2 3 When corrective action is required as a result of the inservice tests made during cold shutdown, the condition shall be corrected before startup. A retest showing acceptable operation shall be run following any required corrective action before the valve is returned to service.
6.3 When analyzing the results of the Category A valve leakage tests the current test data shall be compared with the previous test data as well as with the maximum permissible leakage rate specified in the STP directing the test. If no specific permissible leaka$e rates have been established the values shown on Attachment V shall be used in evaluating test results. The following corrective action shall be observed if any Category A valve fails to satisfy the acceptance criteria of the STP on Preoperational/ Functional Test directing the test.
6.3 1 valves with leakage rates exceeding the values specified on Attachment V, shall be replaced or repaired and retested to demonstrate satisfactory operation before being returned to service.
6.3 2 For valves 6 in. and larger, if a leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 50% or more, the test frequency shall be doubled and tests scheduled to coincide with a cold shutdown until corrective action is taken, at which time, the original test frequency shall be resumed.
When tests show a leakage rate increasing with time, and a projection based on three or more tests indicates that the leakage rate of the next scheduled test will exceed the maximum permissible leakage rate by more than 10%, the valve shall be replaced or repaired and retested to demonstrate satisfactory operation before being returned to service.
PAGE 13 0F 15 O e e m.e m = .,*o e - = = . map we- w-g e=4 - , ** p .e e, mw w- = = . --m a e m
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4 GTP-002 REVISION 4 9/11/82 f3 i ,) 6.3 3 The failure of a category A valve to satisfy the leakage rate acceptance criteria of the applicable STP constitutes .am inoperable component and may require a Limiting Condition of operation per V. C.
- Su=mer Technical Specifications. The STP directing the test will outline any LCO's.
6.4 If any Category C safety / relief valve in a system fails to satisfy the Acceptance Criteria as specified in the STP directing the test the following corrective action steps will be observed.
6.4.1 Any safety / relief valve failing to function properly during test shall be repaired or replaced and shall sucessfully pass a retest before being returned to service.
6.4.2 If any safety / relief valve in a system fails to function properly during a regular test, additional valves in the system shall be tested as determined by an arbitrary assumption that a twelve month operating period has passed to another refueling, and the additional valves shall be tested to make the cumulative total tested at least N/60 x total valves in this category, where N now includes the ,
additional 12 months . (See Attachment II for definition of N.) If any of these additional O' valves fail to function properly on test, then all valves in the system in this category shall be tested.
6.4.3 If any safety / relief valve fails to satisfy the Acceptance Criteria of the applicable STP it shall be considered inoperable and may require a Limiting Condition for operation per V. C. Summer Technical Specifications. The STP directing the conditions of the test will outline any Limiting Condition of Operation.
6.5 If any Category C check valve fails to satisfy the acceptance criteria of the STP directing the exercising test the following points shall be observed.
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GTP-002 REVISION 4 9/11/82 6.5 1 Corrective action shall be initiated immedi'ately.
If the condition cannot be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the check valve shall be declared
-inoperative. When corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup. A retest showing acceptable performance shall be run following any required corrective action before the valve is returned to service.
6.5.2 With a check valve inoperable certain Limiting Conditions for Operations as decalled in the V. C.
Summer Technical Specifications may apply. The STP directing the test will list any applicable Limiting Condition for Operation.
6.6 The Nuclear Shift Supervisor or Shift Foreman will initially review the test data and compare it to the Acceptance Criteria detailed in the STP. If the results are satisfactory he will sign the data sheet. If the results are unsatisfactory, he shall initiate corrective action including any Limiting Condition for operation required by the V. C. Summer Technical Specifications.
NOTE: The STP conducting the performance of the test will .
list any Limiting Conditions of Operation.
70 ATTACHMENTS 71 Attachment I - Valve List 7.2 Attachment II - Safety / Relief Valve Testing Schedule and Category A Permissible Leakage Ra;es 73 At tachment III - Valve Test Summary 7.4 Attachment IV - List of Applicable STP's 75 Attachment V - Allowed leakage for Category A Valves PAGE 15 0F 15 h
CTP-002 AT TAOtKt4T I PAGE I OF 69 REVISION 4 VALVE SYS, VALVE VALVE [R AW itG CO- NCIN POS TEST FTLIEF ALTEIN AT E l tireER PESm lPTini CAT /CLS P4ml0ER 000 POS ItD REQ' MENT REQE ST TEST RfMAI!KS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
'! FS WS G STf0KE TlHE 40 SEC
! XVG-7501 AC ita.ET ISOL TO OtDt COnLER A D-302-652 E-11 NO YES M-l PENET 208 ISDLAT104 (ORC) 6a MOTOR OPERATED WALV' 2a LT PO WA APm0VED STPS FS YES G STIDKE TIME 40 SFC XVG-7502 AC INLET ISOL TO @DI COOLER A D-302-052 D-1 1 NO YE S H-1 KNET 208 13)LAT 101 (IRC) 6* HOTOR OPERATED VALVE 2a LT N0 PVA APfROVED STPS FS YE S G STfDKE TIME 40 SEC
, XVG-7505 AC OUTLET ISOL FROM CR[fl COOLER A D-302-852 0-11 PO YES M-1 PENET 209 19)t AT104 (IRC) 6" MOTOR OPERATFT) VALVt 2a LT NO tyA APIROVED STPS FS YE S G STfDKE TlHE 40 SEC j XVG-7504 AC OUTLET ISOL FR0tt CRON COOLER A D-302-852 E-1 1 NO YES M-1 KNET 209 ISOLATiul (ORC) 6" HOTOR OPERATED WALVF 2a LT NO tVA APFROVED STPS l
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. GTP- ?
. ATTACIMNT I PAGE 2 0F 69 '
REylSION 4 I VALVE SYS, VALVE VALVE [ItAWitG (X)- NOTI POS T EST REllEF ALTEIN AT E I tant'ER (fS0tlPil04 CAT /CLS 98M3ER Oft POS IN) REQ' MENT REQtE ST TEST RfMARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
- FS YE S CS STIOKE TlHE 5 SEC i XVfk002A AH RB PLPT ExHAIST ISOL A 912-103 G-10 PC Yf S N-1 PENET 101 ISOL 36" AIR OPERATED VALVE 2a LT t10 PVA APfit0VED STPS FS YE S CS STf0KE TIME 5 SEC
. XVIwo020 All PB PtitT EYHAtST ISOL A 912-103 H-11 FC YE S H-1 PENET 101 ISOL l 36" AIR OPERAffD 2a LT NO WA APITIOVID STPS FS YE S CS STfDKE TIME 5 SEC xvD-001A All Rf) PtitG StPPLY ISOL A 912-103 D-6 tC YE S N-1 PENET 402 BRIL 36" AIR OPERATLD VALVE 2a LT YE S PVA APIROVED STPS FS YE S CS STIOKE TIME 5 SEC XVIF001B All RB PiftE StPPLY ,lSOL A 912-103 C-4 tC YE S N-1 FYNET 402 ISOL 36" AIR OPERATED VALVE 2a LT NO WA APITIOVED STPS T
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. GTP-O ATTAOtKNT I i PAGE 4 OF 69 REVISION 4 i
VALVE SYS, VALVE VALVE UtAWitG CO- N0fH l'O S TEST FTLIEF ALTEINAT E tMUER PE'.OtlPTIOl CAT /CLS PUMBER OnD POS IPO REQ'itENT PEQtE ST TEST RLMARKS (NOTE #6)
(NOTE (NOTE (POTE (NOTE (NOTE #5)
- I) #2) #3) #4)
IVV-7096 CC SITmE TATE VFt4T B 302-6)I F-12 NO YE S FS NO WA STfDKE TIME 5 SEC 1 1/2* GLWE VALVE 2b APIROVED STP C(MP0t4D4T COOLitG PP A TESTED OtfiltG MONDLY X VC-9682 A CC D1501 OlLCK C 302-611 G-5 -- --
CV NO WA PtNP TEST 24" OIECK VALVE 2b APTROVED STP 1 COMPONENT C00LitG PP B TESTED Otflit0 HONDLY XVC-9G120 CC 01501 OtECK C 302-611 G-5 -- --
CV NO WA PLMP TEST
, 24" OfECK VALVE 2b APITIOVED STP C01 POND 4T COOLitG PP C TESTED OtnitG tot 4TILY xyC-9(,82C CC 01501 OiECK C 302-611 G-6 -- -- CV NO PVA PLMP TEST 24" CHECK VALVE 2b APfROVED STP FS YE S CS STIOKE TIME 60 SEC XVG-9605 CC CC Rx DLt/; lHTifflAL ISOL A 302-612 G-12 NO YE S A-5 PENET 330 ISOL VALVE 8" HOTOR OPERATED VALVE 2a LT NO WA APm0VED STPS FS YE S G STfDKE TlHE 60 SEC XVG-9606 CC CC Rx DLDG EXTEftlAL ISOL A 302-612 Il-12 to YE S A-5 FYNET 330 ISOL 8" MOTOR OPFRATED WALVE 2b LT to WA APITIOVED STPS
~
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X VG-956R CC CC Rx RLDG EXTElt4AL ISOL A 302-612 H-Il to YE S A-5 PENET 312 ISOL VALVE 8" MOTOR Of'ERATED WALVE 2a LT NO WA APm0VED STPS
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Gl?-002 ATTAOtPENT I PACE 5 0F 69 REVISION 4 VALVE SYS. VALVE VALVE DIAWitG Q)- NOIN FO S TEST RELIEF ALTEINAT E IJit0ER DES 011PTIU4 CAT /CLS talHPER OID FUS IID REQ'MDIT PEQtEST TEST RD4 ARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
CV YE S CS XVC-95/0 CC CC Rx DLDG INTUNAL DIECK A/C 302-612 G-12 -- -- A-l PENET 312 ISOL 8" CHECK VALVE 2a LT NO WA APIROVED STPS FS YE S G STIOKE TlHE 60 SEC XVPr-9600 CC Rx HLDO EXTEfYlAL ISOL A 302-612 F-2 No YE S A-3 PENET 204 ISOL VALVE 3" MOTOR OPFRATED VALVE 2a LT NO WA APIT10VED STPS CV ES CS XVC-9602 CC Rx DLIC lilTEINAL OIECK A/C 302-612 F-1 -- -- A-2 PENET 204 ISOL VALVE 3" OlECK VALVE 2a LT NO WA APfROVED STPS XVR-9502A CC CCW PtfP le C D-302-611 G-7 -- -- SRV NO WA SETPolNT 150 psig 01501 ilEAf1ER RFLitF 2b APFROVED STP XVR-9502R CC CCW Pl#P 10 C D-302-611 G-4 -- -- SRV NO WA SETPolNT 150 psig DIS 01 ilEADER RELIEF 2b APfROVED STP 1
XVR-950?C CC CCW PtH' IC C D-302-611 H-6 -- --
SRY NO WA SETPolNT 150 psig 01501 RELIEF VALVE 2b APfROVED STP t
i XVR-19545 CC A SPENT FlEL HEAT EX01At0 Eft C D-302-613 F-11 -- --
SRV NO WA SETPOINT 160 psig REllEF 2b APIROVED STP
, XVR-19544 CC D SPENT FlFL HEAT EXOIAtlGER C D-302-613 81- 1 1 -- -- SRV NO WA SETPolHT 160 psig RELIEF 2b APIROVED STP e
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GTP-002 ATTAOi9ENT I PA E 9 OF 69 REVISION 4 l
1 f VALVE SYS. VALVE VALVE ITI AW IPC CD- N'J t4 POS TEST PELIEF ALTER 4AT E j tufflEP DESM lPT10tl CAT /CLS ff5tlER ORD POS ItD REQ' MEN T PEQE ST TEST RD4 ARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- l) #2) #3) #4)
LT NO PVA STn0KE TIME 10 SEC
, XVG-8107 CS OG liEADER ISOL A 114E073 (3) E-13 NO YES PENET 40) ISOL VALVE j 3" MOTOR OPERATED VALVE 2a FS YE S CS APITIOVED STPS i D-10
- STRDKE TIME 10 SEC l XVG-8108 CS O G llEADER ISOL B 114E073 (3) E-13 NO YES
] 3" MOTOR OPERATED VALVE 2a FS YE S CS APfROVED STP B-10
- XVC-8481A CS O G Ptw A Dl'01AR K CK C 114E073 (3) E-9 -- --
CV YE S RS APIROYED STP
} 3" CHECK VALVE 2a B-2 I
XVC-84SID CS DIG Pl#P B DISOIART OlECK C 114E073 (3) C-9 -- -- CV YE S RS APITt0VED STP I 3" DiECK VALVE 2a B-2 XVC-8481C CS OlG PltP D DISOIART OlFCK C ll4E073 (3) D-9 -- --
CV YES RS APIROVED STP 3" OiECK VALVE 2a B-2 LCV-1150 CS VCT OUTLET ISOLAT104 0 114E073 (3) F-7 t10 YE S FS YE S CS STIOKE TIME 10 SEC 4" MOTOR OPERATED 2a B-1 APFTIOVED STP LCV-115E CS VCT OUTLET llDR ISOL D 114E073 (3) F-7 NO YE S IS YE S CS STIOKE TIME 10 SEC ,
4" MOTOR OPERATED 2a S-l APIROVED STP ItWST ? SOL TO DIARGE PtJP A LCV-115H CS SLCTION HEADER D 114E073 (3) D-6 r0 YE S FS NO WA STf0KE TIME 14 SEC
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. VALVE SYS. VALVE VALVE tR AW itG CD- N0tl POS T EST REllEF ALTER 4AT E i tsPUER DESGilPTIO4 CAT /CLS HNBER ORD 005 Ito REQ' MENT REQtE ST TEST RD%RKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4) f RWST ISOL TO OtARE Ptw B (CV-I ISD CS SICT104 itEADER 0 114E073 (3) C-6 PC YE S FS NO WA STIDKE TINE 14 SEC A" NOTOR OPERATED 2a NYYt0VED STP l XVT-8104 CS emf RTHCY DORATE B 114E073 (3) D-3 PC YES FS NO WA STIDEE TINE 10 SEC i VALVE 2a ArtROVED STP
! 7" HOTOR OPERATED VALVE j XVC-8442 CS DA TO OG Ptw C C 114E073 (3) D-2 -- -- CV YE S G APfROVED STP I HEAttR OtECK 2a B-7
- VALVE WILL BE TESTED
,i XVC-8314 A CS BORIC ACID TRANSFEli C 114E073 (5) E-9 -- --
CV NO WA WITH THE Pll4P TEST
{ Plw A DISOI OtECK 2b APfROVED STP i
- VALVE WILL BE TESTED XVC-n314B CS DORIC ACID TRNISFER C 114E073 (5) C-9 -- --
CV NO WA WITH THE PLMP TEST PtM' B D1504 OtECK 2b APIROVED STP C
XVR-8116 A CS RH ltF ADER TO OtARGitG Ptw A 114E073 (3) D-5 -- -- SRY NO WA SETPOINT 220 psig RELIEF 2a APPROVED STP XVR-84160 CS RH HEADER TD OtARGiro PtfP B C 114E073 (3) C-5 -- --
SRV NO WA SETPolNT 220 psig RELIEF 2a APPROVED STP XVC-6480A CS OiG/Sl PttP A NINIFLOW IIX1 C 114E073 (3) F-9 CV NO WA VALVE WILL BE T.ESTED DlRilG '
OIECK VLV. 2" VALVE 2a -- -- PLMP TEST APPROVED STP i
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- REVISION 4 VALVE SYS. VALVE VALVE [R AW itG CO- NOIN FOS TEST RELIEF ALTEfNAT E tut 0ER 81.50tlPTIO4 CAT /CLS M)teER ORD POS ItD REQ' MENT REQtEST TEST ffNARKS (NOTE #6)
- (NOTE (NOTE (NOTE (NOTE (NOTE #5) 4
- 1) #2) #3) #4)
XVC-972A DG 2" CllECK VALVE C 302-351 G-14 -- --
CV to WA APfROVED STP 2b X VC-977B DG 2" CHECK VALVE C 302-351 G-1 -- -- CV NO WA APITIOVED STP 1 2b XVC-970A DG 2" CliECK VALVE C 302-351 G-12 -- -- CV NO WA APfBOVED STP 2b XVC-9700 DG 2= alrr.K VALVE C 302-351 G-3 -- -- CV NO WA APfROVED STP 2b 1
i
GTP-002 AT TAOITNT I PAGE 12 OF 69 REVISION 4 VALVE SYS. VALVE VALVE litM itG CO- NGH POS TEST RELIEF ALTEfMAT E I41t1RER DESUtlPTION CAT /CLS tlJtBER ORD POS ItD REQ' MENT REQtEST TEST RD4 ARKS (NOTE #6)
(NOTE (TOTE (NOTE (NOTE (NOTE #5) !
- 1) #2) #3) #4) i XVC-97 t A DG 3" CHECK VALVE C 302-351 G-1 1 -- -- CV fB WA APfl10VED STP 2b XVC-971D DG 3" OttCK VALVE C 302-351 G-4 -- --
CV 70 WA APITIOVED STP i
, XVR-979 A DG DG FilEL OIL TRANSFER Ptf P C D-302-351 G-13 -- --
SRV to tVA SETPOINT 63 psig ,
141 A DIS 01 HEADER RELIEF 2a APfTt0VED STP XVR-980A OG IC FtEL Olt TRANSFER Ptte C D-302-351 G-12 -- --
SRV to WA SETPolNT 63 psig 4 A DISOI IIEADfR RELIFF 2a APITIOVED STP XVR-9790 DG DG FtEL Olt TRANSFER Pil1P C D-302-351 G-2 -- -- SRV NO WA SETP0lNT 63 psig 1418 DISol HEADEf1 RELIEF 2a APITIOVED STP XVR-9900 DG DG FUEL OIL TRANSFER Pif4P C D-302-351 G-3 -- --
SRV N0 FVA SETPOINT 63 psig 40 DISolitEADER REllEF 2a APITIOVED STP r
9
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i CTP-Ca/
1 ATTACHsENT I j PACE 13 0F M j REVISION 4 j~ VALVE SYS. VALVE VALVE [R M ifG CO- NOIN . ft)S TEST RELIEF ALTEfMATE j f pf tER DESOtlPTION CAT /CLS P4JNDER OHD evs 18 0 HEQ' MEN T REQtE ST TEST RfMARKS (NOTE #6)
" ~
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 11 #21 #31 del .
XVC-1039A EF EF IOR INLFT CK TO A T'G C 302-083 C-12 -- -- CV YES CS APIROVED STP 4" CHECK VALVE 2a C-1 i
i X WC-10390 EF EF IOR INLET CK TO B S/G C 302-083 E-12 -- --
i j 4" DiECK VALVE' 2a C-1 ,
f
' 302-003 G-12 XVC-1039C EF EF HR INLET CK TO C S/G C -- -- CV YE S CS APIROVED STP j
- 4" CHECK VALVE 2a .
G-1 '
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- XVC-1038 A EF EF 00R StPPLY EK TO A S/G C 302-083 C-12 -- -s l CV YES CS APlROVED STP f 4" CHECK VALVE 2a G1
~
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_____1
} XVC-1038B EF EF KR StPPLY CK TO D S/G C 302-083 E-12 -- -- CV 1ES CS APfROVED STP da CHECK VALVE 2a C-1 XVC-103nC EF EF ttR StPPLY CK TO C S/G C 3'12-083 H-12 -- -- CV YES CS APfROVED STP i ~~ 4" CHECK VAL'/F 2a C-1 l MOTOR [ RIVE EFWP 21B DISO4 s XVC-10150 EF OiECK
.- ~ C 302-005 F-8 -- --
CV ' ' YE S CS Af1 ROVED STP 4" CHECK VALVE - 2b 4 C-2 g .
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ATTAO#ENT I PAGE IS OF 69 REVISION 4 VAtvE SYS. VALVE VALVE (RM itC CO- NON IX)S TEST RELIEF ALTEI41AT E ,
IAM1t R DES 011PTION CAT /CLS MA4BER Ofr, POS 170 REQWNT REQtEST TEST PDeARKS (NOTE #6)
)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) fel StPP FM SW LOOP A TO TtEB X VG-10')2 EF THivE EFWP t0R ISOL R 302-005 J-5 tC YE S IS YES G STFOKE TIME 42 SEC ,
, 8" MOTOR OPERATED VALVE 2b O-4 APtROVED STP i.
StPP FW SW LOOP B TO TtEB XVG-1008 EF litlVE EFWP HDR ISOL 8 302-005 J-6 PC YE S F5 YES G STIDKE TlHE 42 SEC B" MOTOR OPERATED VALVE 2b C-4 APfROVED STP i
StPP FM SW LOOP A TO TLRB XVG-1037A EF DRIVE EFWP WI ISOL B 302-085 F-2 tC YES FS YES G STfDKE TIME 42 SEC .
', 8" HOTOR OPERATED VALVE 2b C-4 APfROVED STP 1
StPP FM SW LOOP B 10 TtRB XVG-10370 EF IRIVE EFWP MN ISOL B 302-005 G-2 BC YES F3 1E S G STf0KE TIME 42 SEC 8" MOTOR OPERATED VALVE 2b C-4 APfROVED STP EF FM TtRD [ HIVE EFWP I F V-35% EF TO A S/G B 302-085 B-9 NO YES IS V WA STf0KE TIME 30 SEC 3" AIR OPERATFD VALVE 2b APtROVED STP IFV-3546 EF EF FM TtRB EFWP TO O S/G B 302-085 E-9 NO YE S F5 NO WA STFOKE TIME 30 SEC 3" AIR OPERATED VALVE 2b APIROVED SIP IFV-3556 EF EF FH TIRD (FWP TO C S/G B 302-085 G-9 NO YE S FS NO WA STIOKE TIME 30 SEC 3" AIR OPERATED VALVE 2b APfROVED STP
/
XVC-1016 EF TittB DRIVE EFWP DISOl CK C 302-085 H-9 -- -- CV YES CS APfROVED STP 4" Clif CK VALVE 2b C-5 i
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GTP-002 AT TAOttt tti t PACE 16 0F 69 REVISION 4 VALVE $15. VALVE VALVE DtAWIPG Ob NOIt1 f o e. TEST RELIEF ALTUN AT E tH*t ER DES 0tlPilott CAT /CLS fut0ER ORD IVS ItD REQ'ftENT REQtE ST TEST F<EMARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (rote #5)
- 1) #2) #3) #4) xvC-1015A EF HOTOR TRIVE EFWP 21 A DISol C 302-005 A-8 -- -- CV WS G APfROVED STP 4" OIICK VALVE 2b C-2 XVC-1013A EF StPP fil CST TO 7t A DiECK C 302-005 th5 -- -- CV WS G APIT10VED STP 6" OtECK VALVE 2b C-6 xvC-10130 EF StPP FM CST TO f fWP 210 OtECP C 302-005 F-4 -- -- CV YE S CS ANROVED STP 6" 'ItECK VALVE 2b C-6 XVG-1023 A EF HIR [ RIVEN EF PP A REClR LOR C 302-005 A-7 -- -- CV NO WA APITIOVED STP OtK VLV 28 OiECK #ALVE 2b XVC-1023B EF HIR [ RIVEN EF PP 0 RECIR liDR C 302-2 5 F-7 -- --
CV NO WA APIROVED STP OIK VLV 2" OlECK VALVE D
XVC-1027 EF EF RECIR HEADER OtECK VALVE C 302.005 C-4 -- --
CV NO WA APITIOVED STP 4" OIECK VALVE 2b XVC-1024 EF TtRB IIllVEN EF IP RECIRC IOR C 302.005 H-8 -- --
CV NO WA APIROVED STP OIK VLV 3" OfECK VALVE
/ 2b XVK-1019A EF S/G A HOTOR DWN EFWP StPPLY C 302.005 A-10 -- --
CV YES CS APfROVED STP STAY OtLCK C-8 4" STAY CilECK VALVE 2D 9
O O O
'N D/ CTP-00c ATTAODENT I PAGE IF W 69 REVISION 4 VALVE SYS. VALVE VALVE [R AW IPO Q)- NOIN ft)S TEST REL IEF ALTUNATE tilf EER DES 0llPTini CAT /CLS MJM0ER ORD POS ItD REQ' MENT RFQtEST TEST RDMRKS (NOTE #6)
, (NOTE (NOTE (tote (NOTE (NOTE #5)
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XVK-10190 EF S/G B HOTOR D1 Ef WP StPPLY C 302.085 D-10 -- -- CV YES CS APIROVED STP STOP OlECK C-8
- 4" STOP OtECK VALVE 2B XVK-1019C EF S/G MOTOP Ut EFWP StPPLY C 302.085 F-10 -- -- CV YE S G APTROVED STP STOP 04ECK C-8 4" STOP OiECK VALVE 2b l XVC-1022A EF ItRB IRIVEN EF PP SUCT C 302-085 H-6 -- -- CV YES RS APfROVf D STP l OfECK FRON SW A 2b C-7 2
XVC-10220 EF TtHD (RIVEN EF PP SUCT C 302-085 H-5 -- -- t,v YES RS APfROVED STP OIECK FROM SW B , 2b C-7 i XVC-1034 A FF MOTOR ORIVEN EF PP STET C 302-085 D-5 -- -- CV YES RS APfROVED STP
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CV 1ES G APfROVED STP STOP OlECK C-8
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(lote (NOTE (NOTE (NOTE (NOTE #3) a
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XVK-1633A FW OtEM FD SUI'P TO A $/G ISOL B/C 302-083 B-9 T10 YE S FS NO WA STf0KE TIME 60 SEC
- 1 1/2" fHO STOP 04ECK 2a APfROVED STP XVK-16338 FW D104 FD StPP TO B S/G ISOL BA
- 302-083 D-9 NO YES FS NO WA STICKE TIME 60 SEC 1 1/2= D90 STOP Off CK 2a APIROVED STP FS STfDKE TIME 60 SEC XVK-1633C FW 0404 FD StPP TO C S/G ISOL B/C 302-083 G-9 NO YES NO WA APIROVED STP 1 1/2a D40 STOP OIECK 2a FS YE S CS STf0KE TIME 5 SEC XVG-1611A FW Mtl FD WTR StPP A S/G ISOL B 302-083 D-6 NO YES D-l APfROVED STP 18" AIR TO IfYtHAULIC 2a FS YES G STIOKE TIME 5 SEC XVG-16 tin FW Mit FD WIR StPP O S/G ISOL B 302-083 E-6 NO YES D-l APIROVED STP Ifta AIR TO IftfRAULIC 2a FS 1E S G Sif0KE TIME 5 SEC g
XYG-1611C FW MN FD WTR StPP C S/G ISOL B 302-083 G-6 NO YES D-1 APfROVED STP j 18= AIR TO HYlHAULIC 2a 4
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ATTAO# TNT I PAGE 21 OF 69
, REVISION 4 val.VE SYS. VALVE VALVE (PM IPG CD- NON FOS TEST RELifF ALTERIATE ta1tUER DESctlPTION CAT /CLS NMDER ORD POS IPO REQ'NENT REQtF.ST TEST PD4 ARKS (NOTE #6)
, (NOTE (NOTE (NOTE (NOTE (NOTE #5)
FI) #2) #3) #4)
FS YES RS STIOKE TINE 40 SEC XVG-7660 IA 2" AIR OPERATED VALVE A 302-273 G-4 NO YE S F-l FENET 311 ISOL VALVE
- 2h LT NO WA M1 ROVED STPS 4-Cy YE S (s i'
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F-2 ITNET 311 ISOL VALVE l 2a LT NO WA APINOVED STPS I
FS NO WA STIOKE TINE 40 SEC 8
XVG-2662A lA 6" AIR OPERATED VALVE A 302-273 B-4 NO YES ITNET 319 ISOL VALVE f 2a LT NO WA APIROVED STPS FS NO WA STICKE TINE 40 SEC s XVG-26620 1A 6" Alft OPERATED VALVE A 302-273 B-3 NO YES FTNET 319 130L VALVE
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( ) CTP-002b ATTAQ M NT I PAGE 23 0F 69 REVISION 4 VALVE SYS. VALVE VALVE IRAW itG 00- NOFN TOS TEST RELIEF ALTEH4 ATE is p3ER DES 0tiPTIO4 CAT /CLS P4MBER OfO FVS I tfl REQ' MENT REQt[ST TEST REMARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
MS LINE A ISOLATIO3 iS NO WA STf0KE TIME 10 SEC
, XVG-2fl69A MS BYLASS VALVE D 302-011 C-4 PC YE S AffROVED STP 4" AIR OPERATLD VALVE 2a .
MS LINE D ISOLATION FS NO WA STfDKE TIME 10 SEC
! XVG-2869B MS BYPASS VALVE B 302-011 E-3 to YES APfROVED STP
. 4" AIR OPERATLD VALVE 2a
{
4 MS LINE C ISOLATION / FS NO WA STFOKE TIME 10 SEC i
XVG-20MC MS BYPASS VALVE B 302-011 G-4 tC YES APfROVED STP
- 4" AIR OPERATED VALVE 2a j
, XVS-2006F MS MS SIE#1 LINE D SAFETY VALVE C 302-011 E-7 -- -- SRV NO WA APfROVED STP 6 x 10 RELIEF VALVE 2a XVS-2806G MS ttN STEAM LINE B SAFETY VALVE C 302-011 E-6 -- -- SRV NO WA APfROVED STP 6 x 10 RELIEF VALVE 2a XVS-2006H MS MN STEMI LINE D SAFETY VALVE C 302-011 E-6 -- -- SRV NO WA APfROVED STP 6 x 10 RELIEF VALVE 2a XVS-20061 MS MN STEAM LINE B SAFETY VALVE C 302-011 E-6 -- --
SRV NO WA APIROVED STP 6 x 10 RELIEF VALVE 2a
- XVS-2806J MS MN STEAM LINE D SAFETY VALVE C 302-011 E-5 -- -- SRV NO WA APfROVED STP 6 x 10 RELIEF VALVE 2a
/
O
CTP-002 ATTACaltENT l PAGE 24 0F 69 REVISION 4 i VALVE SYS. VALVE VALVE mMitG CO- NOIN PCS TEST REL IEF ALTERIAT E tuteFR DESmf 9T10N CAT /CLS PU1BER ORD POS ItD REQ' MEN T REQlfST TEST RDt4RKS (NOTE #6) i (NOTE (NOTE (NOTE (NOTE (NOTE #5) ,
- 1) #2) #3) #4)
FS NO WA STfDKE TIME 3 SEC f IPV-2010 MS MN STEN 4 LINE D POWER PELIEF 0 302-011 D-7 tC YE S APfROVED STP '
8" AIR OPERATED VALVE 2a i FS NO WA STIDKE TIME 20 SEC XVG-2r02A MS Mti STEN 4 LotP 0 TO EFVP TlRB B 302-011 E-8 to YE S APfROVED STP 4" MOTOR OPERATED VALVE 2a c I
FS NO WA STfDKE TIME 20 SEC ,
XVG-2002n MS Mrs STEAM LOOP C TO EFWP TtRD D 302-018 G-5 NO YE S APfROVED STP I 4" MOTOR OPERATED VALVE 2a i XVC-2376A MS Mri STENi LOOP D TO EFWP CK C 302-011 E-5 -- -- CV NO tVA APIROVED STP 4" CHECK VALVE '
25
. XVC-2876B MS MN STEAM LOOP C TO EFWP CK C 302-011 F-5 -- --
CV NO WA APIROVED STP 4" CHECK VALVE 2b 6
IFV-2030 MS STEN 4 STOP VALVE TO EFWP TtEl- 0 302-011 E-4 ?C YES FS to WA STfDKE TIME 3 SEC 4" AlH OPEPATED VALVE 2b APfl10VED STP FS NO WA STIDKE TIME 3 SEC IPV-2020 MS Mri STEAM LINE C P0rfER RELIEF 0 302-011 C-7 PC YE S APITIOVED STP -
8" AIR OPERATED VALVE 2a 3,
FS YE S CS STfDKE TIME 5 SEC XVPk2801C MS Mr4 STEN 4 LINE C ISOL D 302-011 G-5 no YE S G-1 APIROVED STP I 32a AIR &ERATED VALVE / 2a
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CTP-00h'^
ATTACl#ENT I PAGE 25 0F 69 REVISION 4 VAtVE SYS. VALVE VALVE (RM i tG (X)- NOIN 105 TEST REL IEF ALTETN AT E ,
taltoEn DESutiPTION CAT /CLS P4MDER ORD POS ItD REQ' MENT REQtEST TEST REMARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- #t) #27 #3) #4)
XVG-2813 MS MS TO EFWP TlNin (RAIN ISOL 0 302-011 H-3 NO YE S FS NO WA STIOKE TIME 24 SEC
, 1 1/2" MOTOR OtTRATED VALVE 2b APIROVED STP XVS-2806K MS Mtl STEAM LINE C SAf ETY VALVE C 302-011 F-7 -- --
SRV NO WA M1HOVED STP 6 x 10 RELIEF VALVE 2a XVS-2806L MS Mit STEAft Lit:E C SAFETY VALVE C 302-011 G-7 -- -- SRV NO WA APIROVED STP 6 x 10 PELIEF VALVE 2a XVS-20rW4 MS MN STEM 4 LINE C SAFE 1Y VALVE C 302-011 F-6 -- -- SRV NO WA APfROVED STP 6x 10 RELIEF VALVE 2a XVS-2906;I MS MN STEN 1 LINE C SAFETY VALVE C 302-011 G-6 -- -- SRV NO WA APIROVED STP 6 x 10 RELIEF VALVF 2a l
XVS-2806P MS ftN STEAM LINE C SAFETY VALVE C 302-011 F-6 -- --
SRV NO WA APfROVED S1P i 6 x 10 RELIEF VALVE 2a d
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, PAGE 27 Or 69 RFVISIOta 4 n
VALVE SYS. VALVE VALVE LRM itC (X)- NGet R)S TEST RELIEF ALTER 4AT E f t#0ER DESM iPT lue CAT /CLS 14#0ER Or0 POS ItD REQ' MENT RcQtEST TEST ItEMARKS (NOTE #6) 4 (NOTE (NOTE (NOTE (TOTE (NOTE #5) fil #2) #3) #4)
IS to WA STf0KE TIME 40 SEC XVD-8035 RC P.R.T VENT 4 N2 f t1R .lSOL A Il4E072 (2) J-5 NO YES PENET 420 ISOL la AIR OPERATED (DIAPNRACN) 2a LT NO WA APfROVED STPS FS NO WA STIOKE TIME 40 SEC XVD-8047 ftC P.R.T VENT & N2 FOR ISOL(IRC) A Il4E072 (2) 1-5 NO YES PENET 420 ISOL la AIR OPERATED (DIAPifRAfN) 2a LT NO WA APEROVED STPS FS NO WA Sif0KE TIME 40 SEC XVD-8028 RC P.R.T SPRAY 10R ISOL (ORC) A II4E072 (2) 1-2 tC YE S PENET 422 ISOL 3= AIR OPERATED 2a LT NO WA N'RIOVED STPS CV NO WA X VC-8046 RC P.R.T SIBAY IOR QiECK A/C 114E072 (2) 1-3 -- --
PENET 422 ISOL VALVE
, 3" OlECK 2a LT NO WA APfROVED STPS Xvn-0010 A RC PRZR Q)DE SATETY C ll4E072 (2) G-9 -- -- SRV NO WA APfROVED STP 6" RELIEF VALVE I XVR-8010B RC PRZR CODE SAFETY C II4E072 (2) G-I l -- -- SRY NO WA APfROVED STP 6" RELIEF VALVE I XVR-0010C RC IHZR CODE SAFETY C 114E072 (2) G-12 -- --
SRV NO WA APfROVED STP 6a RELIEF VALVE 1 I
FS NO WA XVT-8095A RC ft! ACTOR VESSEL NEAD VENT B ll4E072 (1) F-6 tC YE S STfDKE TIME 23 SEC
, 2" HOTOR OPERAT ED 1 APfROVED STP f
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I
GTP-002 ATTAOttENT I PACE 2n W 69 REVISION 4 VALVE SYS. VALVE VALVE [R AW itC 0)- N0ft1 POS TEST REL IEF ALTERIAT E ts#0ER DESUtlPTION CAT /CLS tOMBER ORD POS ItD REQ' MEN T REQtEST TEST REMARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5) ft) #2) #3) #4)
FS NO WA X VT-80150 RC RE ACTGt VESSIL ltEAD YENT D 114E072 (2) F-5 tC YE S STFOKE TIME 23 SEC 2" MOTut TEftATED I APIPOVED STP FS NO WA XVT-8096A RC REACTOR VESSEL HEAD VENT D II4E072 (1) E-6 PO YE S STFOKE TIME 23 SEC 2" f40 TOR OPERATED 1 APFROVED STP FS NO VA ,
XVT-80960 RC RE ACTOR VESSEL llEAD VENT D 114E072 (1) E-5 NO YE S STFOKE TIME 23 SEC 2" HOTOR OPERATED I APFROVED $TP PCV-445A RC PRZR PWt OP RELIEF D 114E072 (2) G-13 FC YE S FS YE S CS STIOKE TIME 2 SEC 3" AIR OPERATFD I Q-1 (ACTUATED WAP HlTIOGEN)
APPROVED STP i
PCV-4458 RC PR/R PWt OP RELIEF D II4ED72 (2) F-13 FC YES FS YE S CS STFOKE TIME 10 SEC 3" AIR OPERAT ED 1 0-1 AFTTtOVED STP PCV-4440 RC PIGt PWI OP REllEF B YES STIOKE TIME 2 SEC T" AIR OPERATED 1 114E072 (2) F-13 PC YES FS Q-1 CS APFTIOVED STP
( ACTUATED W/IP NITROGEN)
XVG-8000A RC PZR PWit OPER PELIEF D 114E072 (2) G-13 PO YES FS NO WA STFOKE TIME 10 SEC VALVE ISOLAT I(#4 1 APIROVED STP 3" t0T0ft OPERATED ;
XVG-80000 RC P7It PWR OPER REL IEF D 114E072 '(2) F-13 10 YE S FS NO ,
WA STFOKE TIME 10 SEC VALVE ISOLATION I APFROVED STP 3" POTOR OPERATED e
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GTP-002 ATTAOt% NT I PACE 30 OF 69 REVlSION 4 VALVE SYS. VALVE VALVE Dt AW ito 00- NOIN PO S TEST RELIEF ALTEFNAT E tair0ER f(SOtIPTION CAT /CLS PINBER ORD POS ItD REQ' MENT REQtE ST TEST RD4 ARKS (NOTE #6)
(t0TE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
XVC-87160 Rt R4 StPt'LY liiR n OiECK C I I4 E07 4 H-10 -- --
CV NO WA APRt0VED STP I 10" OtECK VALVE 2a XVC-8 716 A Rt Rf Sil' PLY ttit A OlECK C 114 E074 1-10 -- --
CV NO WA APIROVED STP l 10" CHECK VALVE 2a FCV-602A Rif Rt PtfP A MINIFLOW VALVE D 114 E074 F-9 to YE S FS to tVA STIOKE TIME 10 SEC 2" MOTOR OPERATED 2a APITIOVED STP FCV-6020 Rt F31 PIPP O filNIFLOW VALVE D 114 E074 F-9 to YE S FS N0 tVA STfDKE TittE 10 SEC 2" MOTOR OPEftATED 2a APITIOVED STP SETPOINT 450 psig XVR-8 70B A F11 IdtR A IIV1 REllEF. A/C 114 E074 D-11 -- -- SRV NO N/A APfROVED STP 3" PrLIEF VALVE 2a LT NO tVA SETPOINT 450 psig XVR-87000 Rt RIR D itYt RELIEF A/C l l4 E07 4 F-11 -- -- SRV to N/A APIROVED STPS 3" RELIEF VALVE 2a LT to WA
~
DIARGitG Pltt' StCTIOi TO STfDKE TIME 10 SEC XVG-370r.A RI A LOOP RtR D 114 E074 1-6 PC YE S FS to PVA APfROVED STP 8" MOTOR OPERATED VLV 2a OIARGirU Ptf4' StCTir24 TO ST!DKE TIME 10 SEC XVG-870F0 Rti D LOOP RIR D I I4 E074 G-6 tC YES FS to WA APfitOVED STP 8" MOTOR OPEllATED VLv 2a t
O O O
, CTP-002 1 ATTADIE NT I PAE 31 Of" 69 REVISION 4 VALVE SYS. VALVE VALVE BRAbf itC Q)- NOIM IDS TEST REL IEF - ALTEINAT E P8M3ER DES 0tlPT10N CAT /CLS t0tOER OIU POS Ito REQ'HEllT REQtEST TEST RDMRKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE #5)
(NOTE
- 1) #2) #3) #4)
STf0KE TIME 10 SEC XVG-8801A SI 80I0t4 INJ TK OUTLET B ll4E075 (I) G-13 PC YE S PENET 4E IS)L VALVE '
3a MOTOR OPERATED Vf.LVE 2a ES YES RS APfROVED STP
! J-I6 4
STIOKE TIME 10 SFC 4 XVG-86010 S1 00Ioil INJ TK OUTLET D 114E075 (l) G-13 fC YES PENET 4E ISDL VALVE 3= MOTOR OPEl<ATED VALVE 2a FS YE S RS APfROVED STP J-16 f5 YE S CS STICKE TIME 10 SEC XVG-8885 St HI 6D ICT LEG INJ ISOL 8 Il4E075 (1) G-7 tc YES J-13 PENET 222 ISOL VALVE 3a MOTOR OPERATEL* VALVE 2a APfROVED STP CV YE S CS XVC-8998A St LfW 10 COLD LEC TO LOOP A CK A/C 114E075 (1) J-13 -- --
J-l APfROVED STPS 6" CdECK VALW I. LT NO WA CV YE S G
- V?,-0998n i
. St LOW ID COLD LEG TO LOOP B CK A/C 114E015 (I) J-13 -- --
J-l APFROVED STPS
- 6" CHECK VALVE 1 LT NO WA
)
CV YE S G ll4E075 (1)
XVC-8998C St LOW ID COLD LEG TO LOOP C CK A/C 1-13 -- -- J-l APfROVED STPS i
6" QIECK VALVE I LT NO WA HI IIEAD 610T LEG INJECTION FS YE S G ST0 FEE TIME 10 SEC X W 8884 SI ISOLATIOl A 1 RAIN B ll4E075 (1) G-5 8C YES J-13 PENET 415 150L VALVE 3" MOTOR OPERATED VLV 2a APfROVED STP HI llEAD DUT LEG INJECTl04 FS YES G STIOKE TIME 13 SEC X W O886 Si isonATION B TRAIN D 114E075 (1) G-7 PC YE S J-13 PENET 4121SDL VALVE 3* MOTOR OPERATED VLV 2a APfROVED STP i
f
GTP-012 ATTAOBENT I PAf7 32 OF 69 REVISION 4 VALVE SYS. VALVE VALVE (R M itG CD- NG H POS TEST RELIEF ALTEINAT E taMIER DES (TllPT101 CAT /CLS fp10ER ORD POS ItD REQ' MENT REQtf ST TEST REMARKS (NOTE #6)
(NOTE (NOTE (NOTE (ta0TE (NOTE #5)
- 1) #2) #3) #4)
CV YE S RS XVG-899 7 A St Hi to COLD LEG LOCP A OtECK A/C ll4E075 (I) 1-13 -- --
J-2 f1 NET 43 190L 2a CHECK VALVE 1 LT NO WA APmOVED STPS CV ES RS XVC-89978 Si til to COLD LEG LOOP B OlECK A/C 114E075 (1) 1-12 -- --
J-2 MNET 43 ISOL 2" CHECK VALVE 1 LT NO WA APmOVED STPS CV ES RS XVC-0997C S1 Ill 60 COLD LEG LOOP C CHECK A/C 114t075 (1) 1-12 -- --
J-2 PENET 43 ISOL
[ 2" 04ECK VALVE I LT to WA APmOVED STPS CV YES RS XVG-8995A St HI 60 HOT LEG LOOP A DIECK A/C ll4E075 (1) 1-11 -- --
J-3 PENET 222 ISOL VALVE 2" OlECK VALVE 1 LT NO WA APIROVED STPS CV YE S RS XV4 69950 $1 HI 60 HOT LEG LOOP B OIECK A/C 114E07 5 (1) 1-10 -- --
J-3 PENET 222 ISOL VALVE 2" CHECK VALVE 1 LT NO WA APm0VED STPS i CV YES RS 6 XVC-8995C S1 HI 10 LOT LEG LOO' C CHECK A/C 114E075 (1) 1-9 -- -- J-3 pet 4ET 222 ISOL VALVE
! 2" OtECK VALVE 1 LT NO WA APm0VED SIPS CV YE S (5 XVG-898SA SI RIIR StPPLY TO RCS LOOP A A/C 114E075 (l) J-7 -- --
J-4 PENET 325 ISOL VALVE i 6" OIECK VALVE I LT fl0 WA APm0VED STPS CV YE S G XVC-89880 .51 RilR SLPPLY TO RG LOOP D A/C 114E075 (1) J-7 -- --
J-4 MNET 325 150L VALVE j 6" CHECK VALVE -1 LT ta0 WA APm0VED STPS e
O O O
. GTP h'/
ATTACH 8ENT l PAfE 33 Of 69 REVISION 4 VALVE SYS. VALVF VALVE [RM itG CD- NOIN fVS TEST RELIEF ALTEINAT E til!1 DER DES 0llPTION CAT /CLS RMBER ORD POS ItD REQ' MENT REQtEST IEST REMARKS (NOTE #6) l (NOTE (NOTE (NOTE (NOTE (NOTE #5)
', #11 #2) f3) #4)
, 111 to foi LFG LOOP A HDR CV W5 CS XVG-8993A St OtECK A/C ll4E075 (1) J-3 -- --
J-5 APfROVED STPS
- 6" DiECK VALVE I LT HO WA I
j CV YES (3 3
XVC-09930 St HI 60 HOT If f; LOOP B 80R CK A/C ll4E075 (1) J-3 -- --
J-5 APfROVED STPS
. 6" OiECK VALVE I LT NO WA I CV YES RS l XVC-8993C Si fit to ICT LEG LOOP C 10FI CK A/C 184E075 (1) 1-3 -- --
J-15 APfROVED STPS 6" CalECK VALVE I LT HO WA CV YE S RS
, XVC-8990 A SI Hi to ICT LEG LOOP A 04ECK A/C ll1E075 (1) 1-7 -- -- J-6 R NET 412 ISDL VALVE
! 2" OlECK VALVE 1 LT NO WA APIROVED STPS 1
J-6 PENET 412 ISOL VALVE 2" OIECK VALVE I LT NO WA APIROVED STPS l
e CV YES RS l XVG-8990C St Hi to 10T LEG LOOP B OtECK A/C ll4E075 (1) 1-5 -- --
J-6 PENET 412 ISOL VALVE I
2" OtECK VALVE LT NO WA APfROVED STPS i CV RS YES XVC-8992A St Ill to 10T LEG LOOP A OtECK A/C ll4E075 (1) l-5 -- --
J-7 PENET 415 ISDL VALVE
- 2" OtfCK VALVE I LT NO WA APfHOVED STPS i
l W WS E
, XVC-89920 St HI lo ICT LFG LOOP O CHECK A/C ll4E075 (1) 1-4 -- --
J-7 PENET 415 ISOL VALVE I
2" CHECK VALVE LT NO WA APfDOVED STPS f
1 t
CTP-012 ATTAOnENT I PAGE 34 OF 69 REVISION 4 VALVE SYS. VALVE VALVE UtAWitG CO- NGit NS TEST REL IEF ALTERIAT E fpf ER DESallP110! CAT /CLS NMIE R ORD POS ItD PIQ' MENT REQtEST TEST RfMARKS (NOTE #6)
(ta0TE (NOTE (TOTE (NOTE (NOTE #5)
- 11 #2) #3) #4) ,
O ES M XVC-0992C St HI 10 6DT L FG LfXP C lA/C g
114E075 (1) 1-3 -- --
J-7 FYNET 4l5 IY)L VALVE 2" CHICK VALVE 1 LT PC PVA APIROVED STPS x yr-8945 A Si DomN ltIJ RICIRC ipt ISOL R 114E075 (1) F-12 NO YF S FS NO PVA STFOKE TIME 10 SEC la AIR OPERATED VALVE 2a APIROVED STP X VG-8945B St DOHOf3 tilJ RECIRC IOR ISOL D 114 E07 5 (1) F-12 NO YE S FS NO tVA STf0KE TlHE 10 SEC la AIR G'ERATED VALVE 2a APfit0VED STP BOROrt INJ RECIRC OUTLET XVG-8942 S1 IOR ISOL B I I4 E07 5 ( 1) D-I I PO YE S FS PO PVA STIOKE TIME 10 SEC 1" AIR OPEftATED VALVE 2a APITIOVED STP xvG-8803A Si DNON It!J TK INLET B 114E075 (1) C-Il tC YE S FS YE S CS STIUKE TIME 10 SEC 3" MOTOI: Ol'FRATED VALVE 2a J-14 APfROVED STP f
xVG-88030 51 BOR0tl INJ TK INLET B 114E075 (1) B-l l PC YE S FS YE S G STIDKE TIME 10 SEC i 3" MOTOR OPEttATED VALVE 2a J-14 APITt0VED STP FS IJO IVA
, XVG-n961 St ACCU 4 TEST LINE TO RWST (ORC) A 114 E075 (2) 1-82 FC YE S STFUKE TIME 40 SEC 3/4" AIR OPEPATTD VALVE 2a LT NO PVA PENET 321 IS)L VALVE APf90Vr0 STPS FS to PVA XVr-8871 St ACCut TEST LINE TO RWST (IRC) A Il4E075 (2) 1-11 FC YE S STFDKE TIME 40 SEC 3/4a AIR OF'ERATED VALVE 2a LT PO PVA PENET 321 IsnL VALVE APfHOVED STPS 9
O O O
~
(- f3 b O cTP-ooz ATTAOtPENT I PAGE 35 0F 09 RivISION 4 VALVE SYS, VALVE VALVE (RAWitG CD- NOIN FOS TEST PELIEF ALT EitlAT E tsJf ftER DESfR IPit f N CAT /CLS tiMDER OftD FOS itD ITQ't1ENT RF QtE ST TEST RENARKS (tmTE #6)
(FOTE (NOTE (TOTE (NOTE (NOTE #5)
- 1) #2) 83) #4)
Sl OUTLET ltR CK TO RCS CV TE S RS xVmC948A St LOOP A A/C 114ER S (2) 1-13 -- --
J-8 APlit0VED STPS 12" QIECK VALVE 1 LT Pn tVA SI OUTLET 10R CK TO RCS CV YE S RS xvC-8940B SI LOOP D A/C 114E075 (2) F-13 -- --
J-8 APITIOVED STPS 12" CliECK VALVE 1 LT NO WA St OUTLET IER CK TO RCS CV YE S RS XVG-89tSC St LOOP C A/C 114E075 (2) D-13 -- --
J-8 APIROVED STPS 12" CatECK VALVE I LT NO WA CV YES RS
,' XVC-89 % A SI SI ACCtn A cif rLFT Hm A/C 114E075 (2) 4-11 -- --
J-8 APITIOVED STPS 12" CHECK VALVE I LT NO IVA 1 CV YE S RS I
XVC-8956D $1 St ACCui 0 OUTLET IER A/C 114E075 (2) F-11 -- --
J-8 APfit0VED STPS i 12" CitfCK VALVE 1 LT to WA CY YES RS XVC-89%C St SI ACCitt C OUTLET HOR A/C 114 E07 5 (2) D-1 1 -- --
J-8 APIPOVED STPS s 12" CliECK VALVE I LT NO WA XVG-nam A St St ACCut A OUTLfT D 114E075 (2) 1-8 to YES FS YE S CS STFUKE TIME 15 SEC 12" MOTOR Ol'EPATED VALVE 2a J-9 APfl10VED STP
~
i XVG-00mD SI St ACCut D OUTLET D II4E075 (2) F-8 to YE S FS YES ES STFOKE TIME IS SEC 12" MOTOR OPEPATED VALVE 2a J-9 #plit0VED STP t
t 9
GTP-012 ATTAODENT I PACE % Ot 69 REVISION 4 VAIVE SYS. VALVE VALVE tR AW itr, No tt POS T EST RLLIEF ALTEIN AT E l CO-tart 0ER DESQllPTION CAT /CLS #8 WE R OD POS IPD REQ' MENT RE Qt EST TEST PDtARKS (NOTE #6)
(POTE (NOTE (TOTE (NOTE (TOTE #5)
- 1) #2) #3) #4)
XVG-P801C St Sl ACCtf1 C 01TLET B 114E075 (2) D-8 NO YE S FS YE S G STICKE TIME 15 SEC 12" tOTOR OPERATED VALVE ?a J-9 APIROVED STP i
CV to PVA XVC-0947 si t12 SII' PLY TO ACCtf4 (IRC) A/C II4E075 (2) J-3 -- --
PENET 320 ISOL VALVE i la OtECK VALVE 2a LT to tVA VfROVED STPS i
FS to WA STIDKE TIME 40 SEC i XVP-0880 St N2 Stf' PLY TO ACCtf1 (ORC) A 114E075 (2) J-2 to YE S PENET 320 ISOL VALVE .
1" AIR OPERATfD VALVE 2a LT NO PVA APIROVED STPS .
CV NO PVA XVC-8861 St ACClf t FILL lt0R ISOL (IRC) A/C 114 E075 (2) D-3 -- --
PENET 317 ISOL VALVE '
la OlECK VALVE 2a LT NO PVA APfROVED STPS g FS to tVA STIOKE TIME 40 SEC .
XVT-0860 St ACCtf1 FILL lift ISOL (ORC) A 114E075 (2) 0-2 BC YES PENET 317 ITL VALVE la AIR OPERATED 2a LT NO PVA APfROVED STPS
/
CV YES G XVC-0974A St SI 10R A OIECK (IRC) A/C l l4 E075 ( 3) F-12 -- --
J-ll PENET 322 ISOL VALVE ,
10" CllECK VALVE 2a LT PC fVA /PfROVED STPS CV YE S CS XVC-0974B St $1 t0R 0 OtECK (lRC) A/C ll4E075 (3) E-12 -- --
J-11 PENET 777 .SL VALVE i 10" CHECK VALVE 2a LT to PVA APfROVED STPS :
/ i i
i f
l' l.
l t
O O O
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J O GTP-CC2 O
ATTAQll(NT I PAGE 37 0F 69 REVISION 4 ,
VALVE SYS. VALVE VALVE (R 4fito C0- NG94 POS TEST RELIEF ALTEINAT E talt0Efr DISGllPTIGl CAT /CLS M#t0ER ORD IVS IPO RrQ' MENT REQtEST TEST REMARKS (NOTE #6)
(NOTE (NOTE (NOTE (PIOTE (NOTE #5) !
- 1) #2) #3) #4) ,
a St TO RCS COLD LEG CV YES (3 XVO-8973A St LOG' A DER OIECK A/C ll4E075 (3) F-13 -- --
J-Il APIROVED STPS ;
6" 04fCK VALVE 2a LT NO PVA St TO RCS COLD LEG CV 1E S CS ' )*
XVC-89738 $1 LOOP B IOR OtECK A/C ll4E075 (3) F-13 -- --
J-ll APfROVED STPS ;
6" OlECK VALVE I LT NO WA Si TO l'CS COLD LEG CV YES CS XVG-89 73C $1 LOOP C (OR OtECK A/C l l4 E07 5 (3) E-13 -- --
J-Il APIROVED STPS 6" CitECK VALVE I LT NO WA [
i XVC-8958A S1 Ril PillP A SUCTIOrt HDR OtECK C ll4E075 (3) F-4 -- --
CV NO WA APIROVED STP 14" OtECK VAltE 2a
- XVC-89500 $1 RH PtHP D StCTION IOR Q1ECK C ll4E075 (3) E-4 -- -- CV HO WA APfROVED STP 14" OtECK VALVE 2a C0tlT StNP 10 IMR PP A FS NO WA STfDKE TIME 17.1 SEC XVG-88tlA SI StCTION ISOL (IRC) A Il4E075 (3) B-9 PC YES PENET 321 ISOL VALVE 14" MOTOR OPERATED VALVE 2a LT NO WA APfROVED STPS 1
C0t4T StMP TO luiR PP B FS NO WA STfDKE TIME 17.1 SEC l XVG-881In St St) Tlati ISOL (IRC) ,A Il4E075 (3) C-9 #C YES PENET 425 ISOL VALVE l 14" fl0 TOR OPERATED VALVE 2a LT HO WA APIROVED STPS .
XVG-8812A S1 Ril PP A SICT FR0tt SUMP 0 Il4E075 (3) 0-9 PC YES FS NO WA STFDKE TIME 17 SEC 14" MOTOR OPERATED VALVE 2a APfROVED STP I
t
. +
GTP-003 AT TAOttENT I PAE 38 0F 69 .
REVISION 4 VALVE SYS. VAIVE VALVE tRM itG CO- NOIN POS TEST REL IEF ALTEINAT E fMilER DESCR IPT10t4 CAT /CLS ID40ER ORD POS Il0 REQ' MENT REQlEST TEST RfmRKS (NOTE #6) j (NOTE (NOTE (t40TE (NOTE (NOTE #5)
- 11 #2) #3) #4)
XVG-P,8120 Si foi PP A StCT FROM St*P 0 ll4E075 (3) C-9 PC YE S TS NO PVA STFolrE TIME 17 SEC 14" tOTOR OPERATED VALVF 2a APFROVED STP XVC-8926 51 RWST SUPP TO OIG PP, itVt DIK C
/ 114E075 (3) C-3 -- --
CV YE S RS MIROVED STP Ba OIECK VALVE 2a J-12 i
FS YE S CS XVG-Ban 8A St Riilt Ptf P LOW HEAD St 01501 0 114E075 (3) F-12 NO YE S J-17 STFOKE TIME 12.2 SEC ,
ISOLATION 2a ITNET 322 ISDL ;
iga MOTOR OPERATED VLV APPROVED STP ,
G ES G XVG-8888B S1 FalR PtfP LOW llEAD Si D1501 D II4E075 (3) E-12 No YE S J-17 STf0KE TittE 12.2 SEC ISOLAT latl 2a ItNET 22F ISOL ,
10" MOTfTt OPERATED VLV ATTROVED STP FS to tVA XVG-n889 Si lain DISOI TO 110T LEG B 114E075 (3) H-12 tC YE S STIOKE TIME 12.2 SEC
- RECIRC C0 tat ISOLATiffi 2a FENET 325 ISOL 10" HOTOR OPERATED VLV APf' ROVED STP XVC-8809A St Fatit LOW IIEAD SI StCT D 114E075 (3) r-4 .N0 YE S FS YE S CS STIOKE TittE 17 SEC FR0ft PWST 2a J-18 APFROVED STP 14" MOTOR OPERATED VLV t
XVG *,0090 Si fair LGf itEAD St SICT FROM D 114E075 (3) E-4 NO YE S FS YES G STFOKE TIME 17 SEC PWST 2a J-18 APITt0VED STP .
Ida MOTOR OPERATED VALVE XVre8940A SI 00f t0N INJECT REClR PLW A C 114EO-75 (1) E-9 -- --
CV N0 PVA APITIOVED STP DISOIAPCE OtECK VALVE 2a
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CIP-002 j ATTAOttENT I
. PAGE 40 CF 69 i REYlSION 4 l
j VALVE SYS. VALVE VALVE DtAW itC ' CO- NCIN POS TEST RELIEF AL TEIN AT E t81tTIF R DESCR IPT 10tl CAT /CLS ttJOER ORD FOS ItD REQ'MF HT REQtEST TEST 84 MARKS (NOTE #6)
- (NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
FS NO PVS STf0KE TIME 30 S:C XVG-3003A SF SIR AY int A ISOL A 302-661 E-10 IC YE S PENET 401 ISOL VALVE 10" lOTOR Ol'ERATED VALVE 2a LT NO WA APfROVED STPS STYtAY ttVI A DiECK VALVE CV YE S RS XVC-3009A SP lNSIDE Rx DLDG A/C 302-661 E-Il -- -- K-1 ITNET 401 ISOL VALVE 10" OiECK VALVE 2a LT PO WA APIT10VED SIPS IS to WA STIOKE TIME 30 SEC XVG-30030 SP SfTIAY 101 B ISOL A 302-661 E-10 PC YE S PENET 303 ISOL VALVE 10" MOTOR OPERATED VALVE 2a LT to WA APIROVE0 STPS CV 1E S RS
. xvC-300)B SP SIRAY IUt D 10" OIECK VALVE A/C 302-661 E-Il -- --
K-1 ITNET 303 ISOL VALVE INSIDE Rx BLDG 2a LT NO WA M W VED STPS 4
Rx BLOG SFR AY St#P ISOL FS NO WA STIOEE Tite 75 SEC XVG-3004A SP VALVE A It31DE A 302-661 F-10 PC YE S PENET 327 ISOL VALVE 12" MOTOR OPERATED VALVE 2a LT PO WA APfROVED STPS Rx DLDG SiftAY St#P ISOL FS NO WA STf0KE TIME 75 SEC
- XVG-30048 SP VALVE B 1rGIDE A 302-661 H-10 PC YE S PENET 328 IS)L VALVE 12" MOTOR OPERATED VALVE 2a LT to WA AF4 ROVED STPS d
l RD SiitAY Site ISOL j XVG-MO5 A SP VALVE A OUTSIDE D 302-661 F-9 FC YE S IS to WA STIUKE TIME 62 SIC 12" MOTOR TERATED VALVE 2a APfi10VED STP
/
. RD 5 TRAY StNP ISOL f XVG-30050 SP VALVE D DJTSIDE D 302-661 H-9 BC YES f3 to WA STfDKE TIME 62 SEC i
12" MOTOR OPERATED VALVE 2a APfi10VED STP t
4
' t O O O
- t. M -OO ATTACHE NT I PA E 41 0F 69 REVISION 4 VALVE SYS. VALVE VALVE DIAWlPG CO- NorH POS TEST RELIEF ALTEINAT E
, _- r j tot 0ER DESOllPTION CAT /CLS PaM'ER 000 POS IPO REQ' met 4T REQlEST TEST RD4 ARKS (NOTE #6) ~%
(NOTE (NOTE (NOTE (NOTE (NOTE #5) '
i #1) #2) #3) #4) __
i XVG-3001A SP RwST TO SIHAY PP SICTION A B 302-66l D-4 NO YE S FS NO WA STf0KE TlHE 15 SEC 12" HOTOR OPERATED VALVE 2a APTT 10VED STP 4
XVG-30010 SP RW"T TO SPRAY PP StCTION A B 302-661 E-3 NO YES IS to WA STIDKE TIME 15 SEC l
12" MOTOR OPERATED VALVE 2a APFPSVED STP i
}
, XVC-3006B SP RWST TO SPRAY PP SlCTitN C 302-661 E-3 -- --
CV NO WA APfROVED STP 12" CHECK VALVE 2a
.s XVC-3013A SP H4H 10 SmAY PP StCTION C 302-661' F-4 -- --
CV YE S RS APF110VED SIP 3" CHECK VALVE 2a K-3 XVC-30138 SP HaOH TO SPRAY PP StCTIO4 C 302-661 F-4 '
CV YE S RS APifl0VED STP 3" CHECK VALVE 2a K-3 t >
XVG-3002A SP NaOH TO SPRAY PP A StCT101 0 302-661 G-3 PC YES FS YES CS STIDKE TIME 15 SEC I 1 3" MOTOR OPEPATED VALVE 2b K-2 APITIOVED STP
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VALVF SYS. VALVE VALVE [RM i>G Q)- NOIN POS TEST RELIEF ALTEINAT E j
ts)t0ER Of SmlPT104 CAT /CLS P4JMOER ORD POS 190 REQ'MErli REQtE ST TEST REMARKS (NOTE #6) . .
i' (NOTE (NOTE (NOTE (NOTE (NOTE #5) i
- 1) #2) #3) #4) ;
AIR liar #1LitG RAD H0tilTOR FS NO WA STFOKE TIME 40 SEC L XVA-9311A SS INSfDF SLOTI0tt A 302-771 D-13 NO YE S PENET 407 ISDL VALVE i la AIR OPERATED VALVE 2a LT NO WA APfROVED STPS [
AIR llANDLitC RAD Mor41 TOR FS NO WA STFUKE TIME 40 SEC .
XVA-93 t lB SS OUTSIDE SUCT104 A 302-778 D-14 NG I YE S PENET 401 250L VALVE la AIR OPERATED VALVF 2a LT PO WA APIROVED STPS RAD HnNITOR SNPLE RFTURN FS No WA STIOKE TIME 40 SEC XV A-9412 A SS lilSIDE A 302-771 E-13 NO YES PENET 407 ISDL VALVE l la AIR OPERATED VALVE 2a LT NO WA APIROVED STPS !
l RAD M0tilTOR SM1PLE RtTURN FS NO WA STFOKE TlHE 40 SEC *
- XV A-95120 $5 OUTSIDE A 302-771 E-14 NO YE S PENET 407 I!DL VALVE !
1" AIR OPERATED VALVE 2a LT NO WA APIBOVED STPS FS to WA STIOKE TIME 40 SEC XVW1356A SS STEM 4 SPACE 10R ISOL A 302-771 0-12 FC YE S PENET 405 ISDL VALVE -
3/8" SOLENotD OPERATED VALVE 2a LT NO WA APfROVED STPS FS to WA STf0KE TIME 40 SEC xv49356D SS LIQUID SPACE 10R l SOL A 302-771 C-12 PC YE S PENET 405 ISOL VALVE 3/8" SOLEN 01D OPERATED VALVE 2a LT NO WA APIROVED STPS '
FS NO WA STFUKE TlHE 40 SEC XVS9357 SS PZR SMtPLE CorITAltitENT ISOL A 302-771 C-10 FC YES ENET 405 ISOL VALVE 3/8" SOLENOID OPERATED VALVE 2a LT HO WA APIROVE3 STPS Lf 4P 0 CONTAltNEllT FS to WA STf0KE TIME 40 SEC ;
XVM-93648 SS SN1PLE ISOL A 302-771 D-Il PC YE S PENET 314 ISOL VALVE 3/8" SOLENOID OPERATLD VALVE 2a LT NO WA AFYROVED STPS e
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GTP-002 ATTACilW NT I PACE 44 0F 69 '
REVISION 4 VALVE SYS. VALVE VALVE m AWifD Q)- Hr44 POS TEST REL IEF ALTEINAT E t##1'ER DESM lPTION CAI/CLS F#JMDER Of0 PO S ltD REQ'HENT REQlE ST TEST RD4 ARKS (NOIE #6)
(NOTE (NOTE (NOTE (NOTE (PDTE #5)
- 1) #2) #3) #4)
LOOP D C0t1TAlt#1ENT FS NO WA STFOKE TIME 4G SEC
, XV49365B SS SNV'LE ISOL A 302-771 D-10 to YE S FYNET 314 IS)L VALVE 3/9" SOLENOID OPERATED VALVE 2a LT NO WA N'm0VED STPS 9 i LOOP C CONTAlt#4ENT FS NO WA STFUKE TIME 40 SEC XV4 9364C $$ SAM'LE ISOL A 302-771 E-11 FC YE S TYNET 223 ISOL VALVE
{ 3/8" SOLEN 0in O'ERATFD VALVE 2a LT NO WA APITt0VED STPS LOOP C CONTAlt#1ENT FS to WA STIOKE TIME 40 SEC XV49M5C SS SAMPLE ISOL A 302-771 E-10 FC YE S PENET 223 ISOL VALVE 3/8" SOLENOID OPERATED VALVE 2a LT NO WA APfit0VED STPS S/G A StMPLE CONTAltitENT FS NO WA STf0KE TIME 40 SEC XVM-9598A SS ISOL VALVE D 302 771 F-10 t10 YE S PENET 4I1 19)L VALVE 3/8" SOLEN 0ID O'ERATED VALVE 2a APm0VED STP S/G B sat 4PLE Cot 4TAltf4ENT FS NO WA STIOKE TIME 40 SEC XVt4-0 59SD SS ISOL VALVE D 302-771 C-10 NO YE S PENET 225 ISOL VALVE 3/8" SOLEHOID O'ERATED VALVE 2a Arm 0VED STP S/G C SNtPLE cot 4TAlttiENT FS #10 WA STf0KE TlHE 40 SEC Xvn-03900 SS ISOL VALVE D 302-771 H-10 PC YES FYNET 220 ISOL VALVE 3/8" SOLEN 010 0'ERATED VALVE 2a APtit0VED STP
, FS NO WA STf0KE TIME 40 SEC XV49307 SS ACClf t SNT'LF CONT ISOL VALVE A 302-771 J-10 FC YE S PENET 323 ISOL VALVE 3/8" SOLINOID O'ERATED VALVE 2a LT NO WA APm0VED STPS POST ACCIDENT $NV'LitG FS NO WA STf0KE TIME 40 SEC XVT-9339 SS ftETURtl llDR ISOLATION (IRC) A 302-772 J-3 tC YE S PENET 417 ISOL VALVE 3/8" SOLLHOID OPERATED VALVE 7a LT NO WA APm0VED STPS 9
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CTP-002 ATTACiltENT I l' ACE 46 0F 60 REVISION 4 l
1
,; VALVE SYS. VALVE VALVE DIAWltG Q)- Natt POS TEST REL I EF ALTLIN AT E
', tar BER DESGtlPTION CAT /CLS tutOER CRC FUS ItD REQ'MEi4T PEQt[ST TEST RO4 ARKS (NOTE #6)
(NOTE (NOTE (TOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
SEltV WATElt SLI'P TO A D/G xvC-3119A SW GEN CtR C 302-222 0-10 -- --
CV NO WA APINOVED STP l 0" CHECK VALVE 2b SERV WATEft StPP TO B WG XVC-31190 SW GEN CLR C 302-222 J-10 -- --
CV to WA APITIOYEI; STP 8" CHECK VALVE 2h
{
XVC-3135A S'J 16" OtECK VALVE C 302-222 C-5 -- --
CV to WA APIT10VED STP 2b XVC-31350 SW 16" QiECK VALVE C 302-222 G-5 -- -- CV NO WA APITtCVED STP 2b FS NO WA STiDKE TIME 60 SEC XVtb3106 A SW SW BOOSTER l'P A DISOI A 302-222 C-5 NO YES FYNET 304 ISOL VALVE 16" itOTOR OPERATED VALVE 2a LT NO WA APfTIOVED STPS FS to WA STIOKE TIME 60 SEC XV(b31u60 SW SW TOOSTFR Ptf1P B DISOI A 302-222 G-5 IC YE S ITNET 403 ISOL VALVE 16" MOTOR OPERATED VALVE 2a LT to WA APIT10VED STPS e
f5 NO WA STIOKE TIME 60 SEC XVth3110 A SU 12" toTOR OPERATED VALVE A 302-222 B-5 to YES PENET 304 ISOL VALVE 2a LT FO WA APITt0VED STPS FS to WA STf0FE TlHE 60 SEC xVB-31 ton SW 12" f tOTOR G'ERATED VALVE A 302-222 11- 5 to YE S PENET 403 ISOL VALVE 2a LT NO WA APtROVED STPS t
9 O O O
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GTP-002-)
AT TAdid.NT l PACE 47 0F 69 REVISION 4 <
VALVE SYS, VALVE VALVE DIM itG CO- N(TN FY)S TEST REL IEF ALTETNATE tilf 0ER DEStitlPil0N CAT /CLS f0MUER 00D IVS ItD REQ'HENT REQtEST TLST RD4 ARKS (NOTE #6) !
(NOTE (NOTE (NOTE (NOTE (NOTE #5) .
1
- 1) #2) #3) #4)
CV NO WA XVC-3137A SW 16" CHECK VALVE A/C 302-222 C-4 -- --
PENET 304 ISOL VALVE !
2a LT NO WA APIROVED STPS ,
CV to WA i XVG-3137B SW 16" CHECK VALVE A/C 302-222 G-4 -- --
PENET 403 ISOL VALVE 2a LY NO WA APIROVED STPS t i
fS NO WA f XVG4103A SW 16" HOTOR OPERATED VALVE A 302-222 C-2 NO YES STIOKE TIME 75 SEC !
2a LT to WA PENET 305 ISOL VALVE !
1 API' ROVED STPS 6 % WA ;
XVG41030 SW 16" N010R OPF RATED VALVE .A 302-222 G-2 NO YE S STf0KE TIME 75 SEC g 2a LT NO WA PENET 102 ISOL VALVE APFROVED STPS ,.
a 302-222 B-2 XYG-3111A SW 12" N0 TOR OPERATED VALVE B NO YE S IS NO WA STFOKE TIME 62 SEC 2b APIROVED STP ,
l i
XVG-31110 SW 12" 140 TOR OPERATED VALVE D 302-222 F-2 NO YE S FS NO WA STFOKE TlHE 62.SEC 2b AITROVED STP .
t I
XVT-3164 SW ORPI C00Lito llDR ltLET ISOL 8 302-222 F-14 to YES FS NO WA STFOKE TIME 10 SEC l 2" AIR OPERATED 21, APIROVED STP
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XVT-3169 SW ORPl C00LIN's 60R OUTLtk ISOL 0 302-222 J-14 NO YE S FS NO WA STIOKE TIME 10 SEC 2" AIR OPEl<ATED 2b APfROVED STP O
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i 2
GTP-002 ATTAODENT I PACE 48 0F (.9 RLvisl0N 4 VALVE SYS. VALVE VALVE M AWitG CO- NOIN POS TEST RELIEF ALT EINAT E ;
taftf tf ft DES (R IPTiott CAT /CLS 9040ER ORD FCS ItO REQ' MENT REQtEST TEST RDIARKS (fl0TE #6) I (NOTE (t10TE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
XVC-3115A SW Sf itV WATift Pts 1' A DISOt CK C 302-221 F-2 -- --
CV NO IVA APm0VED SIP 24" Clif CK VALVE 2h I,
i XVC-31150 SW SEltV WATER Ptf t' D DISO4 CK C 302-221 F-10 -- -- CV NO IVA APITt0VED STP 24" OIECK VALVE 2b f
I XVC-3115C SW SEftV WATIR Ptfl* C D1501 CK C 302-221 G-6 -- --
CV N0 PVA APm0VED STP ,
24" Ol[CK VALVE 2h t
XVB-3116 A SW SEftV WATER Pt15' A DISOl ISOL D 302-221 G-2 OPEN YE S FS to tVA STIOKE TIME 60 SEC ;
24" tt0 TOR OPEllATED VALVE 2b AUTO APm0VED STP XVB-31160 SW SEltV WATER PtfP A DISol ISOL D 302-221 G-10 CPEN YES f3 NO PVA STIOKE TIME 60 SEC ;
24" MOTOR OPEftATED VALVE 2b AUTO Arm 0VED STP
)
XVB-3116C SW SERV WATER Ptfl' C DIS 01 ISOL D 302-221 G-6 CPEN YES FS N0 PVA STIOKE TIME 60 SEC ;
24" MOTOR OPERATED VALVE 2b AtJTO APm0VED STP t
XVT-3165 SW 04P1 C00 Lits IOR ISOL 0 302-222 F-14 P40 YE S FS H0 tVA STIOKE TIME 10 SEC 2" AIR OPERATED 2b APITIOVED STP XYB-312f!A SW SW A To HVAC CHILLER C0t3D. D D 302-222 0-11 fl0 YE S FS HO IVA STIOKE TIME 15 SEC I 6" MOTOR OPERATED 2b APITIOVED STP ,
1 I
O O O i
k b GTP-C02 ATTAClipENT I PAGE 49 0F 69 REVtsl0N 4 j i
i VALVE SYS. VALVE VALVE IRM itG CO- NOIN POS TEST REllEF ALTEINAT E ,
tut <ER DESmiPil0N CAT /CLS itJMBER ORD FOS Ito REQ' MENT REQtEST TEST RLHARKS (NOTE #6) f (NOTE (NOTE (NOTE (NOTE (NOTE #5) l A st) #2) #3) #4) l 1
XVG-3108A SW RD C00 Lith UNIT lA IFLET ISol D 302-222 0-4 NO ' 'd $ FS NO WA STIOKE TIME 53 SEC l 5
10" MOTOR G' ERAT [D 2b APfROVED STP [
/ !
1 RD C00LitG UNIT 2A ltLET 150t 0 *,
XVG-31000 SW 302-222 D-4 NO FS NO WA STIOKE TIME 50 SEC i 10" MOTOR OPERATED 2b APfROVED STP 1
XVG-3108C SW RD C00LitU UNIT 2A IPLET ISol D 302-222 F-4 NO YES IS NO WA STf0KE TIME 50 SEC 10" MOTOR Ol'ERATW 2b APFROVED STP i 1
XVG-31080 SW RD COOLING UNIT 20 INLET ISOL D 302-222 H-4 NO YES FS NO WA STf0KE TIME 50 SEC 10" HOTOR OPERATED 2b APIROVED STP I RD C00LitG UNIT IA .
XVG-3109A SW OLITLET ISOL D 302-222 fi-3 fD YES FS NO WA STIOKE TIME 50 SEC r 10" MOTOR OPERATfD 2b M*FROVED STP .
RD C00LilG UNIT 2A i XVG-31090 SW Ollf LET ISOL D 302-222 0-31 No YES FS NO WA STf0KE TIME 50 SEC !
10" MOTOR O'ERATED 2b APfROVED STP r RD C(XX.lto UNIT ID 00fLET ISOL XVrr-3109C SW D 302-222 F-3 NO YES FS NO WA STf0KE TIME 50 SEC i 60" 140 TOR OPrRATED 2b APfROVED STP 4
Ril COOLlPU UNIT 2D XVG-31090 SW OUTLET ISOL D 302-222 H-3 NO YES FS NO WA STIOKE TIME 50 SEC ,
10" t10 TOR OPERATED 2b APIROVED STP i
i
GTP-002 AT TACHf E NT I PAGE 50 Of 69 '
REVISION 4 i VALVE SYS. VALVE VALVE UtAWIPC CO- NOIN FUS TEST RELIEF ALTEIN AT E i (A#ttEP DESotlPTIOri CAT /CLS t1NUER OfD POS ItD REQ'MEtlT REQtE ST TEST REMARKS (NOTE #6) t 3
(NOTE 8HOTF (NOTE (NOTE (NOTE #5) l
- I) ( (2) #3) #4) '
SW A 10 flVAC CHILLER I t AVB-3128C SW Coto. C D ' %2
_ '? 3 E.' "r 'rE S rs t10 WA STIOKE TIME 15 SEC j 6" MOTOR OPERATFD l 5 2b l APlY10VED STP f
~ ' ~
XVG-3107A SW RETtHr1 ISOLAT10t1 VALVE '8 302-222 C-1 fC YE S C G STlor! TIME 75 SEC j 16" MOTOR OPERATED lb L-1 APlit0VED STP !
f h/' s SW P0tU RDCU 10 & [ ES i I X VG-31070 SW RETURil ISotATIRI V4t'vE l6 302-222 G-1 FC YES F5 STIOKE TIME 75 SEC +
16" 10 TOR OPERA 1 ED 2b L-1 CS APfit0VED STP l !,
RitCU 1 A & 2A Cl SYSTD4 XVG-3112 A SW RETT #tti VALVE 8 302-222 0-2 NO YE S TS NO WA STf0KE TlHE 62 SEC i 12" MOTOR OPERATED 2b APIROVED STP l f i I RlCU IB & 20 Cl SYSTEN XVG-31120 SW RETtHti VALVE D STFOKE TIME 62 SEC g
12" MOTOR OPERATED 2b 302-222 E-2 NO YE S FS NO WA APH10VED STP SW POND SW RETURN l
X VO-3130 % Su IMH A IHLET CliECK VLV C 302-222 A-6 - -
CV NO WA APITIOVED STP 30" CHECK VALVE 2b '
SW Poto SW RETlltN XVC-31300 SW INH B IHLET CliECK VLY C 302-222 J-7 - -
CV NO WA APlit0VED STP 30" CHECK VALVE Eb '
IIVAC Chit LEft CONDENSER A i XVB-3126A SW SW SLPPLY VALVE B 302-222 D-I l NO YE S FS NO WA STFOKE TIME 30 SEC f
6" MOTOR OPEllATED 2b APf110VED STP j i
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GTP-002 AT TAODENT I PAGE 52 0F 69 REVISION 4 VALVE SYS. VALVE VALVE m AWitG Q)- NON POS TEST RELIEF ALTERIATE tUtt!LR DESGllPTION CAT /CLS PUMBER ORD POS lid REQ' MENT REQtE ST TEST RD4 ARKS (NOTE #6)
(NOTE (TOTE (tote (NOTE (POTE #5)
- 1) t
- 2) #3) #4)
MVT-6412A VU A OllLLED WTR TO C8 tol-ESS 0 302-842 E-12 to YE S F5 NO tVA STIOKE TWE 5 SEC 3" AIR OPERATLD VALVE 2b APITt0VED STP MV T-6490A VU A OllLLED WTR TO CD tol-ESS B 302-842 E-12 PO YE S FS N0 PVA STf0KE TIME 5 SEC 3a AIR OPEPATED VALVE 2b APm0VED STP t1VT-6505A VU A OllLLED WATER TO N(el-ESS B 302-842 G-3 NO YE S FS to WA STIOKE TfME 10 SEC 2a AIR OPERATED Zb Arm 0VED STP HVT-6304 A VU A OllLLED WlR TO IB NOI-ESS B 302-842 G-3 to YE S FS to WA STIOKE TittE 10 SEC 2" AIR OPERATED 2b APm0VED STP i MVT-6412D VU B OllLLED WTR TO CD NON-ESS D 302-843 C-13 to YE S F5 NO PVA STIOKE TIME 5 SEC 3" AIR OPERATED 2b APm0VED STP tiVT-64900 VU D OllLLED WIR TO CD int-ESS B 302-843 C-12 to YES FS to PVA STf0KE TIME 5 SEC 3" AIR OPERATED VALVE 2b APm0VED STP P
XVT-6384B VU 0 OllLLED WTR TO 10 tal-ESS B 302-843 C-3 to YE S IS NO tVA STFUKE TIME 10 SEC ,
2a AIR Ol'ERATED VALVE 2b APm0VED STP i I
XVT-63050 VU B OllLLED WIR TO ID NGi-ESS B 302-843 11- 3 to YE S FS t10 PVA STIOKE TIME 10 SEC 2a AIR OPERATED VALVE 2b APm0VED STP t i
s 6
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k' \' k GTP-0. /
AT TACHtENT I PAGE 53 0F 69 REVISION 4 VALVE SYS. VALVE VALVE DIM itG CO- NOR1 POS TEST RELifF ALTERlAT E taatlER DES 011PTIn4 CAT /CLS PIJHDER ORD POS It0 PfQ' MENT PEQtEST TEST RD4 ARKS (NOTE #6)
(NOTE (rote (NOTE (NOTE (NOTE #5)
- 1) E2) #3) #4)
XVG-6516 VU A LOOP OtittEI) YATTR TO D 302-842 H-14 NO YE S FS NO WA STf0KE TIME 7.5 SEC "A" COP COOL 1tn WTR PSP 3 APf110VED STP 1 POTOR COOLER XVt'r6517 VU R LOOP OilLIED WATER TO D 302-642 J-13 to YES FS to WA STf0KE TIME 7.5 SEC an" C(*P C00LitG WTR P'FP 3 APlYt0VED STP t010R COOLER XVG-6518 VU A LOOP OilLlED WATER TO D 302-843 J-12 PC YES FS NO WA STf0KE TIME 7.5 SEC "C" COLP C00Litt. WTR PifP 3 AP1110VED STP 4
t0 TOR C00LfR j XVG-6519 VU 11 LOOP OflLIED WATER TO D 302-843 J-11 FC YES FS NO WA STIOKE TIME 7.5 SEC an" CDP OYt.itG WTR Ptf P 3 APfROVED STP 5, t0 TOR COOLfR i
f XVt'r6410 A VU NO3 ESS EQUIP OUT VU C 302-842 E-8 -- --
CV to WA APIROVED STP f RET lut A DiECK VLV 2r i
! XVC-64100 VU t10N ESS EQUIP OUT VU C 302-043 C-8 -- --
CV NO WA APfit0VED STP
? RET lut 0 OtECK VLV 2t 9
XVC-6489A VU F10N ESS EQlilP OUT VU C 302-842 E-8 -- -- CV NO WA APITIOVED STP j RET Hlit A QiECK VLV 2t i
j XVC-64893 VU NON ESS EQUIP OUT VU C 302-843 C-8 -- --
CV to WA APfROVED STP
i
GTP-002 ATIAOiH.NT I PAGE 54 OF 69 REVISION 4 i
VALVE SYS. VALVE VALVE [TI AW itG CO- NOI!4 POS TEST ITLIEF ALTEINAT E taltoE R DESCRIPTirrl CAI/CLS 13 MER ORD POS ItD TEST REQ' met 4T REQtEST REMRKS (NOTE #6)
(NOTE (NOTE (TOTE (TOTE (NOTE #$)
- 1) #2) #3) #4)
XVC-638 7 A VU tiori ESS EQUIP OUT VU C 302-842 11 - 7 -- --
CV NO WA APITIOVED STP ICT IIDR A OtECK VLV 7t.
XVC-6307tl VU tKW ESS EQU1P OUT VU C 302-843 H-7 -- --
CV NO WA AP1 ROVED STP f(ET ttDR B OIECK VLV 7t xvC-6308A VU t10tl ESS EQUlm OUT VU C 302-842 H-7 -- -- CV NO WA APITIOVf D STP FET IIDR A OtFCK VLV 2t XVC-638 BB VU IKil ESS EQUIP OUT VU C 302-843 H-7 -- -- CV NO WA APITIOVFD STP PCT ifDit 0 CHECK VLV 21 XVC-6461 A VU CHILL WTR PtFF 151 A C 302-841 E-10 -- --
CV NO WA APf110VED STP 01501011CK 21
- 6" CliFCK VALVE XVC-6461f1 VU C
- llLL WTR ltf' 1518 C 302-841 E-5 -- --
CV t10 WA AP! ROVED STP DISol OtECK 2t'
, 6" OtEf'K VALVE XVC-6161C VU ClllLL WTR Ptte 151C C 302-841 E-7 -- --
CV NO WA APITt0VED STP D8501 OIECK 2t 6" OlECK VALVE 1
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.ALVE SYS. VALVE VALVE DlAWitC CO- NonH NS T EST REL4E7 ALTDNAT E ta M ER DESM iPTlatt CAT /CLS t0MDER 000 NS ItD REQ' MENT REQtE ST TEST RDtARKS (NOTE #6)
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XVX-6051A HR RH sat #'LE TO H2 A 302-861 B-12 FC YE S LT YES APP. J CAT A PASSIVE AtIAL A 2< P-1 LEAK TEST OtlLY 3/8" SotEt1010 OP. VLV. APfROVED STP XVX-6051C tlR RD SAtPLE TO H2 A 302-861 A-11 FC YES LT YE S APP. J CAT A PAS $lVE AtlAL A 2 P-1 LEAK TEST OilLY 3/8" E01.f fl010 OP. VLV. APPROVED STP XVX-6053A IIR POST ACC H2 StPP A 302-861 D-10 'O YE S LT YE S APP. J CAT A PASSIVE ISOL L0nP A 2< P-1 LEAK TEST OrlLY 3/8" SOLENOID OP. VLV. APm0VED STP XvX-6052A HR POSI ACC il2 RETtRH A 302-861 C-10 tC YE S LT YE S APP. J CAT A PASSIVE ISOL VLV. 2< P-1 LE AK T EST W.Y 3/8" SOLENOID OP. VLV. APIROVED STP XVX-60510 HR POST ACC H2 REltRtl A 302-861 E-12 FC YE S LT YE S CAT A PASSIVE ISOL VLV. 2a P-1 APP. J LEAK TEST ONLY 3/8" SOLEHOID OP. VLV. APTHOWED STP 4 XVX-60*iOH HR POST ACC H2 RETLRN A 302-861 F-12 FC YE S LT YE S APP. J CAT A PASSIVE ISOL VLV. 2e P-l LEAK TEST ONLY 3/8* SOLENGID OP. VLV. APfROVED STP t
XVX-6053B HR POST ACC H2 SUPPLY A 302-861 E-10 FC YE S LT YE S APP. J CAT A PASSIVE ISOL. LOOP A 2e P-1 LEAK TEST ONLY 3/8" SOL OP. VLV. APIROVED STP XVX-60523 HR POST ACC H2 StPPLY A 302-861 E-10 PC YES LT YE S APP. J CAT A PASSIVE ISOL LOOP A 2a P-1 LEAK TEST ONLY .
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REYlSION 4 l VALVE SYS. VALVE VALVE IRM itC (X)- N0fH POS TEST RELIEF ALTEFNAT E !
talttDER TE50t lPT 10N CAT /CLS MRiDER ORD POS Ito REQ' MENT REQlEST TEST RD1 ARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
, 3" MANilAL APPROVED STP I i
YVD-6672 SF RF CAVITY SF A 302-651 G-12 10 NO LT 1ES APP J CAT EGORY A PASSIVE LEAK t Ptit StPP ISOL VLV (ORC) 2a P-l TEST ONLY 3" MANUAL APIT10VfD STP xvD-Gu)7 SF SF PtR HEATER A 302-651 G-12 LC NO LT YE S APP J CATEGORY A PASSIVE LEAK RF CAVITY ISOL VLV (ORC) 2a P-1 TEST ONLY 3a m HUAt APIROVED STP XVD-6U18 SF RF CAVITY SF A 302-651 H-12 LC HO LT YE S APP J CATEGORY A PASSIVE LEAK PIR int ISOL VLV (IRC) 2a P-1 TEST ONLY 3" MANUAL '
APfROVED STP I
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ATTACIMNT 1 PACE 67 Or 69 i REVISION 4 g i
VALVE VALVE VALVE [ TIM itG 00-lSYS. NOFN POS TEST REllEF ALTERIAT E M M;r.P i DES 0!IPTION t
CAT /CLS M#40ER ORD IVS ltD REQ' MEN T REQLEST TEST RIMARKS (NOTE #6)
(NOTE (NOTE (NOTE (NOTE (NOTE #5)
- 1) #2) #3) #4)
XVC-6799 FS FS TO XAA-4 A & D IDR Ot[CK A/C 302-231 D-6 -- --
LT YE S APP J CATEGORY A PASSIVE /C LEM 4" CitECX VALVE 2a P-1 TEST ONLY r APFROVED STP +
XVG-6172 FS IS SIPPLY HEADER A 302-231 D-6 IC NO LT YE S APP J CATLT,0RY A PASSIVE LEM TO li1ET ISOLATION 2a ;
P-1 TEST ONLY '
a4a MANUAL (ORC)
APPROVED STP XVG-67?3 FS RD FS ItEADER A 302-231 D-6 tC NO LT WS APP J CATEGORY A PASSIVE LEAK
, 150L VLV 2a P-1 TEST ONLY 4a f4ANUAL (litC)
APPROVED STP
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GTP-002 ATTACHMENT I PAGE 68 or 69 I\ REVISION 4
\_] '
A. SYSTEMS
- 2. AH - Ventilation Systems
- 3. BD - Steam Generator Blowdown System ,
- 6. DG - Diesel Generator System
- 11. IA .nstrument Air System .
- 12. MS - Main Steam System
- 13. ND - Reactor & Auxilinry Building Sump Pumps
- 14. NG - Nitrogen Blanketing System
- 15. RC - Reactor Coolant System
- 16. RH - Residual Heat Removal System I
i 17. SA - Station Air System
- 18. SI - Safety Injection System
- 19. SP - Reactor Building Spray System
- 20. SS - Nuclear Sampling System 21: SW - Service Water System 22.'7U - Chilled Water System
- 23. WL - Waste Processing System
- O 4
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s GTP-002 ATTACHMENT I PAGE 69 of 69 REVISION 4
' VALVE LIST NOTES NOTE 1 Normal Position - indicates the position of the valve, No or NC, during plant operation.
NOTE 2 Position Indication - a Yes in this column indicates that the valve has remote position indication.
NOTE 3 Test Requirement - indicates those required test to a valve as listed in ASME code Section XI, Subsection IWV.
NOTE 4 Relief Request - indicate whether or not relief has been requested. If a "Yes" appears in this column, it will be followed by a A-1, B-1, etc. ; which indicates the relief request number in the relief request binder.
NOTE 5 Alternate Test - if relief has been requested, the alternate test will be listed in this column.
NOTE 6 Remarks - the stroke times listed here are the maximum ~
stroke time for the applicable valves.
- The stroke times with this indicator are the suggested maximum times, if exceeded, the ISI coordinator will determine operational readiness of the valv'es.
O l
. .. .. - ... . .. .. j
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GTP-002
-s ATTACHMENT II s
i PAGE 1 of 1 REVISION 4 CATEGORY C: SAFETY AND RELIEF VALVES Testing Schedule Time Period Number of Valves to be Tested Startup through Minimum of Ni l x total valves in 60 firs't refueling this category.
First refueling Additional valves to make cumulative through second tested at least N2 1 x total 60 refueling valves in this category Second refueling Additional valves to make cumulative through third tested at least N3 1 x t tal 60 .
() refueling valves in tha category etc.
i etc.
I A N1, N, 2 N3 , etc. , equal number of months from startup to first refueling, second refueling, third refueling, etc. When N is a number larger than 60, all valves which have not been tested during the preceding five year period shall be tested. The following period shall then be considered to 'e b the same as "startup to first refueling" for purposes of determining test frequency, with the added requirement that at each refueling all valves which have not been tested during the preceding five year period shall be tested.
( Subsequent period will be considered the same as first refueling to second refueling, etc., with N determined by counting months from the l new starting point.
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GTP-002 ATTACHMENT IV P' AGE 1 of 2
[s\'-] REVISION 4 LIST OF APPLICABLE STPS STP-104.005 - Boric Acid Transfer Pump Test STP-105.001 - Charging /SI Pump Test STP-105.002 - Charging System Valve Operability Te'st STP-105.003 - Safety Injection Valve Operability Test STP-105.005 - RER System Valve Operability Test STP-112.002 - RB Spray Pump Test STP-120.001 - EFWP Test (Electric Pump)
STP-120.002 - E7WP Test (Turbine Driven)
STP-112.003 - RB Spray System Valve Operability Test STP-120.004 - Emergency Feedwater Valve Operability Test STP-121.002 - Main Steam Valve Operability Test STP-122.002 - Component Cooling Water Pumn Test STP-122.003 - Component Cooling Valve Operability Test STP-123 003 - Service Water Valve Operability Test .
STP-125.002 - Diesel Generator Operability Test (V) STP-127.001 - PORV Operability Test STP-128.013 - Fire Valve Operability Test STP-129.002 - Chilled Water Valve Operability Test STP-130.001 - Valve operability Test (Cooldown and Shutdown)
STP-130.002 - Valve operability Test (Refueling Shutdown)
STP-136.001 - Steam Generator Blewdown Valve Operability Test STP-138.001 - Post Accidents H2 Removal Valve Operability Test STP-139.001 - Reactor Building Instrument Air Valve Operability Test STP-140.001 - RB & Auxiliary Building Nuclear Drains Valve Operability Test STP-142.001 - RCS Valve Operability Test STP-144.001 - Nuclear Sampling Valve Operability Test STP-145.001 - Liquid Waste valve Operability Test STP-148.001 - Feedwater Valve Operability Test STP-401.001 - Pressurizer Code Safety ASME XI Test STP 401.002 - Main Steam Code Safety ASME XI Test STP-401.003 - Code Relief Valves ASME XI Test a
GTP-002 ATTACHMENT IV PAGE 2 of 2 REVISION 4 LIST OF APPLICABLE STPS STP-115 005 - RCS Valve Leakage Test STP-115 006 - Charging System Valve Leakage Test STP-115 007 - Safety Injection valve Leakage Test STP-115 008 - RHR Valve Leakage Test STP-115 009 - Waste Processing Valve Leakage Test STP-115 012 - Service Water Valve Leakage Test STP-115 013 - Station Air Valve Leakage Test STP-115 014 - Ins trument Air Valve Leakage Test STP-115 015 - N2 Blanketing Valve Leakage Test STP-115 016 - Component Cooling Valve Leakage Test STP-115 017 - RB Spray Valve Leakage Test STP-115 018 - Sampling System Valve Leakage Test STP-115 020 - Nuclear Drains Valve Leakage Test STP-115 021 - Post Accident Hydrogen Removal Valve Leakage Test -
STP-115 022 - RB Purge & Exhaust Valve Leakage Test j l STP-115 023 - Fire Protection Valve Leakage Test STP-115 025 - Demineralized Water Valve Leakage Test STP-115 026 - Spent Fuel System Valve Leakage Test STP-115 029 - CRDM Cooling System Leakage Test i
e
- ** .O ..s..... [_ . .. _. _ .. __.. . . . . _ . . . . . -
- GTP-002 ATTACH!1Eh"f V a PAGE 1 of 2 REVISION 4 SUGGESTED APP. J. ALERT SUGGESTED MAX SIZE LIMIT (1) (cc/ min) LIMIT (2) (cc/ min) ASME LIMIT (3) (ce/ min) 3/8" 450 575 700 3/4" 450 575 700 3" 500 625 750 1" 500 625 750 1-1/2" 500 625 750 2" 500 625 750 4" 500 625 750 6" 675 850 1050 8" 725 925 1125 10" 800 1025 1200
~
12" 900 1150 1350 14" 900 1150 1350 16" 950 1225 1400 36" 2000 2500 3000 NOTES:
1 (1) This is the suggested leakage limit in order not to exceed the .6 La limit. Penetration leakage can exceed this limit provided other penetration leakage is below their limit making up the dif f erence and not exceeding the .6 La limit.
(2) The Alert limit is to inform the personnel that the penetration is or could become a problem. If a penetration exceeds the alert limit, but still does not cause exceeding the .6 La limit, the penetration test f requency should be doubled and scheduled to coincide with a cold shutdown until corrective action is taken.
(3) Valves / Penetrations with leakage rates exceeding the suggested maximum ASME . limit shall be replaced or repaired.
NOTE: Some valve / penetration leakages are limited by technical specification and do not fall into this category.
)
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GTP-002 ATTACHMENT V PAGE 2 of 2 REVISION 4 REACTOR COOLANT SYSTEf1 PRESSURE ISOLATION VALVES
_L_Ii11TED TO 1 GP" LEAKAGE VALVE !!O.
DESCRIPTION XVC-5993 A,B,C SI to Hot Legs XVC-8992 A,B,C SI High Head to Hot Legs XVC-8990 A,B,C f SI High Head to Hot Legs XVC-8988 A,B SI Lcw Head to Hot Lega y
XVC-8997 A,B,C ;
Primarf SI Migh Head to Cold Legs XVC-8995 A,B,C ,i Alternate SI High Head to Cold Legs g' XVC-8998 A,B,0 SI to Cold Legs w XVC-8973 A,B,C
- j 4
RER Low Head to Cold Legs y
XVC-8948 A,B,0 9 Accumulators to Cold Legs XVC-8956 A,B,C S Accumulators to Cold Legs -
XVG-8701 A,3 if$
RHR Suction from Hot Legs XVG-8702 A,B a RHR Suction from Hot Legs ,
.g XVC-8973 A,3 RHP Low Hep.d to Cold Legs
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W 9 f VALVE TEST RELIEF REQUEST INDEX s A. System: Component Cooling Water System (CC)
C A.1 Valve: XVC-9570 PAGE 1 A.2 Valve: XVC-9602 PAGE 2 A.3 Valve: XVG-9600 PAGE 3 A.5 Valve: XVG-9605 PAGE 4 XVG-9606 XVG-9568 B. System: Chemical and Volume Control System (CS)
B.1 Valve: LCV-1150 PAGE 5 LCV-115E B.2 Valve: XVC-8481A PAGE 6 XVC-8481B XVG-84810 B.7 Valve: XVC-8442 PAGE 7 B.8 Valve: XVT-8152 PAGE 8 B.9 Valve: XVC-8381 PAGE 9 B.10 Valve: XVG-8107 PAGE 10 XVG-8108 B.11 Valve: XVT-8100 PAGE 11 XVT-8112 C. System: Emergency Feedwater System (EP)
C.1 Valve: XVC-1039A PAGE 12 XVC-1039B XVC-10390 XVC-1038A XVC-1038B XVC-10380 C.2 Valve: XVC-1015A PAGE 13 XVG-1015B i C.3 Valve: XVG-1001A PAGE 14
- XVG-1001B C.4 Valve
- XVG-1002 PAGE 15 XVG-1008 XVG-1037A XVG-1037B O
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I VALVE TES2 RELIEP' REQUEST INDEX 4
() C. System: Emergency Feedwater System (EF)
XVC-1016 PAGE 16 C.5 Valve:
j C.6 Valve: XVC-1013A PAGE 17
- XVC-1013B
! XVC-1014 I C.7 Valve: XVC-1022A PAGE 18 4 XVC-1022B
, XVC-1034A XVC-1034B C.8 Valve: XVC-1019A PAGE 19 XVC-1019B XVC-10190 XVC-1020A XVC-1020B XVC-10200 D. System: Main Feedwater System (FW)
D.1 Valve: XVG-1611A PAGE 20 XVG-1611B
., XVG-1611C .
() F. System: Instrument Air System (IA)
P.1 XVG-2660 PAGE 21 F.2- Valve: XVC-2661 PAGE 22 G. System: Main Steam System (MS)
G.1 Valve: XVG-2801A- PAGE 23 XVG-2801B
! XVG-28010 J. System: Safety Injection System (SI) t
! J.1 Valve: XVC-8998A PAGE 24 l XVC-8998B i XVC-89980 j J.2 Valve: XVC-8997A PAGE 25
- XVC-8997B
! XVC-89970 J.3 Valve: XVC-8995A PAGE 26 XVC-8995B XVC-8995C I-2 +
VALVE TEST RELIEF REQUEST INDEX
( J.- System: Safety Injection System (SI)
J.4 Valve: XVC-8988A PAGE 27 XVC-89888 J.S Valve: XVC-8993A PAGE 28 XVC-8993B J.6 Valve: XVC-8990A PAGE 29 XVC-8990B XVC-89900 J.7 Valve: XVC-8992A PAGE 30 XVc-8992B XVC-8992c J.8 Valve: XVC-8948A PAGE 31 XVC-8948B XVC-89480 XVC-8956A XVC-8956B XVC-89560 i J.9 Valve: XVG-8808A PAGE 32 l XVG-8808B XVG-8808C J.ll Valve: XVC-8974A PAGE 33 XVC-8974B '
XVC-8973A XVC-8973B XVC-89730 J.12 Valve: XVC-8926 PAGE 34 J.13 Valve: XVG-8884 PAGE 35 XVG-8885 XVG-3886 J.14 Valve: XVG-8803A PAGE 36 XVG-8803B J.15 Valve: XVC-89930 PAGE 37 J.16 Valve: XVG-8801A PAGE 38 XVG-8801B J.17 Valve: XVG-8888A PAGE 39 XVG-8888B J.18 Valve: XVG-8809A PAGE 40 XVG-8809B 0 I-3
VALVE TEST RELIEF REQUEST INDEX K. System: Reactor Building Spray System (SP) ,
K.1 Valve: XVC-3009A PAGE 41 XVC-30098
(
K.2 Valve: XVG-3002A PAGE 42 XVG-3002B K.3 Valve: XVC-3013A PAGE 43 XVC-3013B L. System: -Service Water System (SW)
L.1' Valve XVG-3107A PAGE 44 XVG-3107B M. System: CRDM Cooling System M.1 Valve XVG-7501 PAGE 45 XVG-7502 XVG-7503 XVG-7504 N. System: Ventilation N.1 Valve XVB-0001A PAGE 46 XVB-0001B XVB-0002A XVB-0002B P. System: Passive Containment Isolation Valve (s)
P.1 Valve (s) PAGE 47 Q. System:
Q.1 Valve PCV 445A PAGE 48 PCV 445B PCV 444B 4
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VALVE TEST RELIEF REQUESTS O,.A. SYSTEM: COMPONENT COOLING WATER SYSTEM (CC)
A.1 Valve: XVC-9570 Category: A/C
.; Class: 2a i
Function: Prevent reverse flow from the reactor i containment to the component cooling water j
system.
Test Requirement: Check valves will be-exercised to the I positions required to fulfill their function j every three (3) months.
Basis for, Relief. Tbsting this valhe would require securing cooling water to the reactor coolant pumps .
i
! During plant operation this could damage the 1
pumps.
! Alternate Test: Valve will be tested during cold shutdown, i
i when the RHR System is in operation and the l
- reactor coolant pumps can be shutdown.
O PAGE 1 i
. o VALVE TEST RELIEF REQUESTS
, A.2 Valve: XVC-9602 .
Category: A/C Class: 2b Function: Prevent reverse flow from the reactor i
containment to the component cooling water system.
Test Requirement: ' Check valves will be exercised. to the positions-required to fulfill their function every three (3) months.
i Basis for Relief: Testing this valve would require securing 1
O cooling water to the reactor coolant pumps.
During plant operation this could damage the e pumps.
Alternate Test: Valve will be tested during cold shutdown, when the RRR System is in operation and the reactor coolant pumps can be shutdown.
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VALVE TEST RELIEF REQUESTS A.3 valve: XVC-9600 Category: A/C Class: 2b Function: Isolation component cooling water to the reactor containment from the component cooling water booster pumps.
Test Requirement : Exercise valve (full stroke) for operability every three (3) months.
Basis for Relief: Testing these valves ~would require securing cooling water to the reactor coolant pumps.
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During plant operation this could damage the pumps.
Alternate Test: Valve will be tested during cold shutdown, when the RHR System is in operation and the reactor coolant pumps can be shutdown.
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VALVE TEST RELIEF REQUESTS O A.5 Valve: XVG-9605 & 9606 & 9568 Category: A Class: 2a Function: Isolation component cooling water-to the reactor containment.
Test Requirement: Exercise valve (full stroke) for operability every three (3) months.
Basis for Relief: Testing these valves would require securing cooling water to the reactor coolant pumps.
l During plant operation this could damage the I
pumps.
1 Alternate Test: Valve will be tested during cold shutdown.
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VALVE TEST RELIEF REQUESTS i
\- B. SYSTEM: CHEMICAL AND VOLUME CONTROL SYSTEM (CS)
B.1 Valve: LOV-1150 & ll5E Category: B Class: 2a Function: Volume control tank outlet header isolation Test Requirement: Exercise valve (full stroke) for operability every three (3) months.
Basis for Relief: Testing these valves during plant operations 1
would require shifting charging pump suction mY from the VCT to the RWST. This would cause an inadvertant boration and plant shutdown.
Alternate Test: Valve will be tested during cold shutdown.
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VA5VE TEST RELIEF REQUESTS O B.2 Valve: XVC-8481A, 8481B and 8481C Category: C Class: 2a Function: Charging pump discharge header check valves Test Requirement: Check valves will be exercised to the position required to fulfill their function every three (3) months.
Basis for Relief: Exercising these valves during normal operations would require establishing full charging flow into the RCS causing a O'
overpressure condition and possible reactor 3
trips. During cold shutdown, full charging flow would cause a pressure surge and exceed the maximum pressure for the low temperature
- of the RCS.
Alternate T'est: Valve will be partial stoke tested quarterly l,
and full flow exercised each refueling i shutdown when the vessel head is removed.
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VALVE TEST RELIEF REQUESTS O
B.7 Valve: XVC-8442 Category: C Class: 2a Function: Emergency Borate Check Valve Test Requirement: Check valves will be exercised to the position required to fulfill their function every three months.
Basis for Relief: Testing this valve during plant operations O would inject high concentrated boric acid into the suction of the charging pump causing an inadvertant boration and plant shutdown.
i Alternate Test: Valve will be tested during cold shutdown.
PAGE 7
VALVE TEST RELIEF REQUESTS O .
B.8 Valve: XVT-8152 Category: A Class: 2a Punction: Letdown flow containment isolation Test Requirement: Exercise valve (full stroke) for operability every three (3) months.
Basis for Relief: Testing this valve during plant operation would isolate letdown which could cause thermal shock'to charging connection. Could also cause lif ting of letdown relief (XVR-8117)
Alternate Test: Valves will be tested during cold shutdown.
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j V_ALVE TEST RELIEF REQUESTS O
B.9 Valve: XVC-8381 Category: A/C Class: 2a Function: Containment isolate check valve for normal charging.
Test Requiremen: Check Valves will be exercised to the position required to fulfill their function svery three (3) months.
Basis for Relief: Testing this valve during plant operation would require securing charging and letdown i
flow which could result in a loss of voldme control and pressurizer level causing a j reactor trip.
Alternate Test: This valve will be tested during cold shutdown.
' O PAGE 9
VALVE TEST RELIEF REQUESTS O
B.10 Valve: XVG-8107 & 8108 Category: A Class: 2a Punction: Isolate charging flow to the containment.
Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
Basis for Relief: Testing these valves.during normal plant ,
operations would require securing charging and letdown flow, which could result in a loss of volume control and pressurized level. causing a reactor trip.
Alternate Test: Valves will be tested during cold shutdown.
O PAGE 10
VALVE TEST RELIEF REQUESTS O
B.11 Valve: XVT-8100 & XVT-8112 Category: A Class: 2a Function: Containment isolation valves for seal water return from the Reactor Coolant Pump seals.
Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
Basis for Relief: Testing these valves during normal plant operations would interrupt flow from the O Reactor Coolant pump Central leakage seal system. This flow disruption would cause the differential pressure across #2 seals to decrease causing a failure of the #1 seals.
Alternate Test: Valves will be tested during cold shutdown.
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VALVE TEST RELIEF REQUESTS O - .
C. SYSTEM: EMERGENCY FEEDWATER SYSTEM (EP)
C.1 Valve: XVC-1039A, B&O and XVC-1038A, B&C Category: C Class: 2a Function: Prevent reverse flow from the steam generator
'i nto the Emergency Feedwater System.
Test Requirement: Check valves will be exercised to the position required to fulfill their function every three (3) months.
O Basis for Relief: Testing any one of these valves during plant operation would introduce cold auxiliary feedwater to the steam generator inducing unnecessary thermal stress on the Emergency Feedwater Piping.
i Alternate Test: These valves will be tested during cold shutdown.
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VALVE TEST RELIEF REQUESTS O
C. SYSTEM: EMERGENCY FEEDWATER SYSTEM (EP)
0.2 Valve
XVC-1015 A&B Category: C Class: 2b Function: Prevent reverse flow from the associated steam generator to the emergency feedwater system.
Test Requirement: Check valves will be exercised to the position required to fulfill their function, every three (3) months.
O Basis for Relief: Testing these valves during plant operation will require establishing emergency feedwater flow to the associated steam generator placing unnecessary thermal stress on the feedwater piping.
l Alternate Test: Valves will be tested during cold shutdown.
i O PAGE 13 l
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VALVE TEST RELIEF REQUESTS O
- C.3 Valve
- XVG-1001 A&B Category: B Class: 2b Function: Isolate service water from Emergency Feedwater
, System.
Test Requirement: Exercise valve (full stroke) for operability i
every three (3) months.
Basis for Relief: Testing these valves during normal plant operation could introduce service water into
- the emergency feedwater pump suction lines and eventually cause chemistry control problems in i the steam generator.
! Alternate Test: Valves will be tested during cold shutdown.
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VALVE TEST RELIEF REQUESTS
. O C.4 Valve: XVG-1002, 1008, 1037 A&B '
1 Category: B Class: 2b t
l Function: Isolate service water from the Emergency i
Feedwater System.
Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
Basis-for Relief: Testing these valves during normal plant operation could introduce service water into the emergency feedwater pump suction lines and eventually cause chemistry control problems in the steam generators.
1 Alternate Test: Valves will be tested during cold shutdown.
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i VALVE TEST RELIEF REQUESTS '
1
,t' C.5 Valve: XVC-1016 ,
Category: C -
Class: 2b .' '
4 -
I .
Function: Prevens, reverse flow to an idle emergency l
! feedwate'r pump. -
. e Test Requirement: Check valves will be exercised to the .-position .
required to fulfill their function,'every (3) :
months. ,
I Basis for Relief: Testing this valve during plant operation will l require establishing emergency feedwater. flow l
- to a steam generator placing unnecessary, 1
- s thermal stress on thefreedwater piping. i, ,
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- Alternate Test
- Valve will be tested during cold shutdo'wn.
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-M' b VALVE TEST RELIEF REQUESTS p.
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. C.6 Valve: XVC-1013A & B and XVC-1014 y iCategory: C
,(' Class: 2a
\
,. Function: ,,
Emergency feedwater pumps discharge check valves.
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Test Requirement: Check valves will be exercised to the position required to fulfill their function, every (3) months.
4 _s g Basis for Relief. Check valves will be partial stroke exercised quarterly during the EFW Pump Test. Full flow
.. testing during normal plant operations would require establishing emergency feedwater flow to the steam generators placing unnecessary thermal stresses on the emergency feedwater piping, s
m__ Alternate Test: Valves wi11 be full flow exercised during the plant shutdown from mirtimum load to cold shutdown.
O PAGE 17
VALVE TEST RELIEF REQUESTS O
C.7 Valve: XVC-1022A & B and XVC-1034A & B )
Category: C Class: 2b Function: Prevent reverse flow from Emergency Feedwater system into the Service Water System Test nequirement: Check valves will be exercised to the position required to fulfill their function, j
every 'three (3) months.
l Basis for Relief: Testing this valve during plant operations could introduce service water into the Emergency Feedwater System and eventually into the Steam Generators causing severe chemistry control problems. Testing valves during cold shutdown would contaminate the l
Condensate Storage Tank. Partial stroke exercising these valves during normal l operation would require isolating the i
! applicable Emergency Feedwater pump which would be a violation of tech. specs.
l Alternate Test: Valves will be disassembled and inspected each refueling shutdown.
PAGE 18
l VALVE TEST RELIEF REQUESTS O)
(_- .
XVC-1019A,B&C and XVC-1020A, B & C
~
C.8 Valve:
Category: C Class: 2b Function: Prevent flow from Steam Generators into the Emergency Fee'dwater pump discharge piping.
Test Requirement: Check valves will be exercised to the position required to fulfill their function, every three (3) months.
Basis for Relief: Testing these valves during normal operations would require establishig emergency feedwater flow to the steam generators placing unnecessary thermal stress on the emergency feedwater piping and causing steam generator level control problems which could result in a 1
l Alternate Test: Valves will be tested during shutdown from minimum load to cold shutdown.
O PA1E 19 i
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l VALVE TEST RELIEF REQUESTS l O. D SYSTEM: MAIN FEEDWATER SYSTEM (FW) l D.1 Valve: XVG-1611A, B&C Category: B Class: 2a j Function: Provides a flow path from the main feedwater-I
- pumps to the associated steam generator.
l Test Requirement: Exercise valves (full. stroke) for operability every three (3) months.
Basis for Relief: Testing these valves during plant operation O. would isolate feedwater to the associated steam generator which could result in a reactor trip.
l
- Alternate Test
- Valves will be tested during cold shutdown.
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VALVE TEST RELIEF REQUESTS 4
F.1 Valve: XVG-2660 :
1 4
Category: A j Class: 2a j
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i Function: Provides flow path from ~ Instrument Air System into Reactor Containment Instrument Air.
- Test Requirement: Exercise valve-(full stroke) for operability 1
i' every 3 months. ;
i 1
i Basis for Relief: Testing this valve during plant operation or cold shudtown would icolate Reactor Building- .
l Instrument Air therefore rendering several systems, inoperable.
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Alternate Test: Valve will be tested during each refueling S/D. !
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VALVE TEST RELIEF REQUESTS 5
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, F.2 Valve: XVC-2661 Category: A/C Class: 2a Function: Prevent reverse flow from the reactor containment into -the instrument air system. l Test Requirement: Check valves will be exercised to the position required to fulfill their function, every three (3) months. .
Basis for Relief: Testing this valve requires entry into the Reactor Building. During plant operation this
)
could cause overexposure to the test personnel.
Alternate Test: This valve will be tested during cold shutdown.
F O PAGE 22
VALVE TEST RELIEF REQUESTS I
O G. SYSTEM: MAIN STEAM SYSTEM (MS)
G.1 Valve: XVG-2801A,B&C l
Category: B Class: 2a Function: Provides the flow path from the associated steam generator to ,he main _ steam line header.
Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
Basis for Relief: Testing any one of these valves during plant operation would isolate the associated steam generator from the main steam line header which would result in . a reactor trip.
Alternate Test: Valves will be tested during each cold shutdown.
NOTE: These valves are partially stroked every three months following surveillance test procedure (STP) 121.002 - Main Steam Valve Operability Test.
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}. _ _ - . _ _ _ . ._ __ _ _ _ _ _ . . _ _ _ _ _
" VALVE TEST RELIEF REQUESTS O
J. SYSTEM: SAFETY INJECTION SYSTEM (SI)
J.1 Valve: XVC-8998 A,B&C Category: A/C Class: 1 Function: ' Prevents reverse flow from the reactor coolant system to the low pressure safety injection i system.
i Test Requirement: Exercise check valves to the position required
() to fulfill their function every three (3) months.
~
Basis for Relief: Testing these valves during plant operation will require establishing flow from the low head ~ safety injection system. The RHR pumps
- do not develop sufficient head to overcome RCS pressure and open the check valves.
l Alternate Test: These valves will be tested during cold shutdown.
4 O PAGE 24 i
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VALVE TEST RELIEF REQUESTS
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V J.2 Valve: XVC-8997A,B&C Category: A/C Class: 1 Function: Prevent reverse flow from the reactor coolant system to the Boron Injection System.
Test Requirement: Exercise check valves to the position required to fulfill their function, every three (3) i months.
Basis for Relief: Teating these valves during plant operations will require establishing charging flow through the Boron Injection tank, not only placing unnecessary thermal stresses on the high head injection piping, but also diluting the boric acid concentration in the Boron Injection tank and causing inadvertant i
boration. Testing these valves during cold shutdown also requires establishing charging flow through the high head injection lines.
With the RCS at such a low pressure and temperature, we would have an uncontrolled injection of a large volume of water which could cause a pressure spike in the system and exceed the pressure temperature limits .
I Alternate Test: These valves will be tested during each refueling when the vessel head is removed and the refueling pool can be used to contain the (J large volume of water.
PAGE 25
VALVE TEST RELIEF REQUESTS
("'S J.3 - Valve: xvc-8995A, B&C b Category: A/C Class: 1 Function: Prevent reverse flow from the reactor coolant system to .the High Head Safety Injection System.
' Test Reauirenent: Exercise check valves to the position required to fulfill their function every three (3) months.
Basis for Relief: Testing these valves during plant operations requires establishing charging flow through the cold leg recir. lines placing unnecessary thermal stresses on the recir. lines. Testing these valves during cold shutdown also
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requires establishing charing flow through the cold leg recir. lines . With the RCS at such a low pressure and temperature we would have an uncontrolled injection of a large volume of water which could cause a pressure spike in the system and exceed the pressure temperature limits.
Alternate Test: These valves will be tested at each refueling when the vessel head is removed and the refueling pool can be used to contain the large volume of water.
O PAGE 26
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VALVE TEST RELIEF REQUESTS
. J.4 Valve: XVC-8988 Aea (VT Category: A/C Class: 1 Function: Prevent reverse flow 'from the reactor coolant system to the residual heat removal system.
- Test Requirement
- Exercise check valves to the position required to fulfill their function, every three (3) months.
Basin for Relief: Testing these valves during plant opera tions will require initiating flow, using the RER pumps, into the reactor coolant system. RCS
(
pressure will be higher than RHR pump discharge pressure precluding flow into the RC system.
Alternate Test: Valves will be tested during cold shutdo wn .
O PAGE 27
VALVE TEST RELIEF REQUESTS J.5 Valve: XVC-8993.A&B
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Category: A/C Class: 1 ,
Function: Prevent reverse flow from the reactor coolant system to the low pressure safety injection system.
Test Requirement: Exercise check valves to the position reauired to fulfill their function every three (3) months.
Basis for Relief: Testing these valves during plant operations will require establishing RHR flow into the
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RCS. The RHR pumps (low -head safety injection) do not develop enough head to overcome RCS pressure and establish flow.
Alternate Test: These valves will be tested during cold shutdown.
O PAGE 28
VALVE TEST RELIEF REQUESTS l
/~S J.6 Valve:- XVC-8990A,B&C Category: A/C Class: 1 Function: Prevent reverse flow from the reactor coolant i
system to the High Head Safety Injection Oystem.
Test Requirement: Exarcise check valves to the position required to fulfill their function, every three (3) months.
Basis for Relief: Testing these valves during normal operations would require establishing charging flow through the hot leg recir. lines, placir.g
, unnecessary thermal stresses on the recir.
[~h lines. Testing these valves during cold U
shutdown also requires establishing charging flow through the hot leg recir, lines. With the RCS at such a low pressure and temperature we would have an uncontrolled injection of a i
large volume of water which could cause a pressure spike in the system and exceed the pressure temperature limits.
Alternate Test: These valves will be tested at each. refueling when the vessel head is removed and the refueling pool can be used to contain the large volume of water.
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VALVE TEST RELIEF REQUESTS J.7 Valve: XVc-8992A, B&C
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Category: A/C Class: 1 Function: Prevent reverse flow from the reactor coolant system to the High Head Safety Injection System.
Test Requirement: Exercise check valves to the oosition reauired
- to f.ulfill their function every three (3) months.
Basis for Relief: Testing these valves during normal plant
~
operations would require establishing charging flow through the hot leg recir. lines , placing unnecessary thermal stresses on the recir.
I \ . lines. Testing these valves during cold L.)
shutdown also requires estaolishing charging flow through the hot leg recir lines . With the RCS at such a low pressure and temperature we would have an uncontrolled injection of a large volume of water which could cause a pressure spike in the system and exceed the pressure temperature limits. 1 Alternate Test: These valves will be tested at each refueling ,
when the vessel head is removed and the refueling pool can be used to contain the large volume of water.
PAGE 30 1
VALVE TEST RELIEF REQUESTS
($ J.8 Valve: XVC-8948A,B&C and 8956A,B&C
- \_ /
Category: A/C Class: 1 Function: Prevent reverse flow from the reactor coolant system to the safety injection accumulators.
Test Requirement: Exercise check valves to the position required to fulfill their function, every three -(3) months.
Basis for Relief: Testing these valves during plant operations would require- initiating flow f rom the SI accumulator to the Reactor Coolant System.
The SI accumulators does not have the required pressure to overcome nonnaL Reactor Coolant System pressure, therefore, flow could not be
. established. During cold shutdown, the RCS would not have the volume to contain the large volume of water required to test these valves causing an overpressure condition for the low temperature. During refueling shutdown, exercising these valves could damage the reactor internals due to the large volume of high pressure water.
Alternate Test: Valves will be disassenbled and inspected ' for operability during each refueling shutdown.
PAGE 31
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VALVE TEST RELIEF REQUESTS J.9 Valve: .XVo-8808A,B&O Category: B Class: 2a Function: Isolate the Safety Injection Accumulator from the reactor coolant loops.
Test Requirement: Exercise valves (full stroke) for operability' every three -(3) months.
Basis for Relief: Valves are required by Technical Specifications to remain open during normal plant operation.
O Alternate Test: Valves wil: be tested during cold shutdown.
O PAGE 32
VALVE TEST RELIEF REQUESTS rs J.11 Valve: 'XVC-8974A&B and XVC-8973A,B&C
(_,/ -
Category: A/C Class: 2a and 1 .
Function: Prevent reverse flow from the reactor coolant system to the low pressure safety injection system.
Test Requirement: Check valves will be exercis-;d to the position required to fulfill their. function, every three (3) months.
Basis for Relief: These valves cannot be tested during plant operations, because the low pressure safety injection pumps do not develop sufficient discharge head to establish a flow path to the reactor coolant system.
Alternate Test: These valves will be tested during cold shutdown. Closure of these valves will be verified in accordance with STP 130.001.
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VALVE TEST RELIEF REQUESTS .
A J.12 Valve: XVC-8926-U Category: C Class: 2a Function: Prevent reverse flow from the Charging Pump Suction /VCT to the refueling water storage tank.
Test Requirement: Check valves will be exercised to the . position required to fulfill their function, every three (3) months.
Basis for Relief: Testing this valve during normal plant operations would cause an inadvertant boration due to the high concentration of boric acid in the RWST, thus a plant shutdown. During cold shutdown, the RCS does not have the volume to l
contain the large volume of water required to a
test the valve and you would exceed the maximum pressure for the low temperature.
i Alternate Test: The valve will be tested at each refueling when the vessel head is removed and the refueling pool can be used to contain the large volume of water.
O PAGE 34 1
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VALVE TEST RELIEF REQUESTS e .
'J.13 Valve: xvo-8884, 8885 and xvo-8886 2
Category: A Class: 2a
! Function: High head hot leg injection -isolation valves.
Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
I Basis for Relief: Testing these valves during normal plant operation will place charging flow through the high pressure safety injection line placing unnecessary thermal stress on the safety ijection piping.
I Alternate Test: Valves will be tested during cold shutdown.
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O PAGE 35 pe- --+--,,y.,,,,.,-,,,.,,m..,e.-r-.w.,n.e ,.--e, ~,,,..e._,._... ,,,r,.w--+-.. vv.-,,-. me--
l = VALVE TEST RELIEF REQUESTS i
J.14. Valve: XVG-8803A&B-lt .
l Category: B i
Class: 2a Function: Isolate charging to the Boron Injection Tank i Test Requirement: Exercise valves-(full stroke) for operability every three (3) months.
i Basis for Relief: Exercising these valves during normal plant i operations could dilute the- boron injection j tank below the minimum concentration required -by i
Technical Specifications.
O Alternate Test: Valves will be tested during cold shutdown.
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- ..,.--_._.,.----..n-.....,,-.-_. __,,_._,.-,,,-n.. __,...n.,n,,,,.,,,-n.n, --m,,,_____, , ,,_,-m.-~ , , , ,
VALVE TEST RELIEF REQUESTS J.15 Valve: XVc-89930-
'~ Category: A/C -
Class: 1 Function: Prevent reverse flow from the Reactor Coolant-System to the hot leg injection lines.
Test Requirement: Exercise check valves to the position required to fulfill their function every three (3) months.
Basis for Relief: Since suction for the charging pumps would be shif ted to the RWST to perform this test, testing this valve during nonnal plant operation would cause an inadvertant boration due to the high concentration of boric acid in the RWST, thus a plant shutdown. In addition, testing this valve during normal operation would cause excessive thermal shock to the Safety Injection to RCS piping. During cold shutdown, the RCS does not have the volume to contain the large amount of water required to test the valve, thus exceeding.the maximum pressure for these low temperatures.
Alternate Test: Valves will be tested at the end of each refueling when the vessel head is removed and refueling pool can be used to contain the large volume of water.
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PAGE 37
VALVE TEST RELIEF REQUESTS >
J.16 Valve: XVC-8801A and 88018 b' Categor{: A Class: 2a~
Function: Boron Injection Tank outlet isolation valves.
Test Requirement: Exercise valves (full stroke) for operability everp three (3) months.
Basis for Relief: Testing these valves during- normal plant operation could inject high concentration of boric acid into the high head injection lines and thus into the RCS causing an inadvertant boration and plant shutdown. During cold
-s] shutdown exercising these valves cou'd l cause migration of the high concentration of boric acid into the high head injection lines , which-
~~
are not heat traced, causing solidification and blockage of these lines.
l Alternate Test: Valves will be exercised each refueling shutdown
,1 with the high head injection check valves.
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VALVE TEST RELIEF REQUESTS J.17 Valve: XVG-8888A and 8888B Category: B Class: 2a Function: RHR pump low head Safety Injection Isolation Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
Basis for Relief: Testing these valves during normal plant operation would require isolating one of the RHR loops. This would violate the Technical Specification Requirement 3/4.5.2, requiring two independent Emergency Core Cooling Systems
)
Alternate Test: Valves will be tested during cold shutdown when one loop of the RHR can be shutdown and tested.
6 O PAGE 39
- w- ; ,
VALVE TEST RELIEF REQUESTS
-- J.18 Valve: XVG-8809A and 8809B Category: B l
Class: 2a Function: . Isolate RHR pump suction from the RWST Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
Basis for Relief: Testing these valves during normal plant operation would isolate the RWST from the suction of the RHR pumps, violating Technical Specification Requirements, 3/4.5.2 requiring p two (2) Emergency Core Cooling Systems operable O with flow path capable of taking suction from the refueling storage tank on a safety injection signal.
Alternate Test: Valves will be tested during cold shutdown when one loop of the RER can be shutdown and tested.
9 O PAGE 40 l
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VALVE TEST RELIEF REQUESTS K.- SYSTEM: REACTOR BUILDIIIG SPRAY SYSTEM (SP)
(
K.1 Valve: XVC-3009 A & B Category: A/C Class: 2a Function: Prevent reverse flow from the reactor containment into -the Reactor Building Spray System.
Test Requirement: Check valves will be exercised to the position required to fulfill their function, every three (3) months.
O Basis for Relief: Testing these valves during plant operation would require placing the Reactor Building Spray System in operation which would result in dousing the containment and filters .
Alternate Test: Valves will be disassembled and inspected for
- operability during each refueling shutdown.
4 r
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U PAGE 41 4
-- , .-y. -,y- y-,- - - - - -, y,c -
, , , . . ,.-,_,y...y --y_.,,,y.--. , . , - . . ..,,.-- r_.e._, , - , . . . , , -.%m____..,._,,_,.-_. 7-__,_,r, _. _
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VALVE TEST RELIEF REQUESTS K.2 Valves: XVG.-3002A&B
. Category: B i
Class: 2a
- Function
- NaOH to spray pump suction isolations and I
checks 1
Test Requirements: Exercise valves (full stroke) for operability, every three (3) months.
Basis for Relief- Testing these valves during normal plant operations would require isola. ting the NaOH l storage tank, which would violate the Technical Specifications.
Alternate Test: Valves will be tested duaing cold shutdown.
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---..__.,-___.,,_..,._-..-..-._...____..,...,--.,-.,m,,....,.._.,_.. __,_,-.,r , _ . , , . m,.--,--. . ,.,-r-
. . . _ . . = . . _, -. - .. .- .. .
VALVE TEST RELIEF REQUESTS
(~' K.3 Valves: XVC-3013 A & B Category: C Class: 2a Function: -Prevent reverse flow from the reactor containment into the Reactor Building Spray System l .
[
Test Requirements: Check valves will be exercised to the position required to fulfill their function every three (3) months.
4 Basis for Relief: Testing these valve.s during plant operacion
- or cold shutdown would require placing the spray system in operation which would result in j dousing the containment and filters or. pumping
] sodium hydroxide to-the RWST.
1 1
Alternate Test: Valves will be disassembled and inspected for operability during each refueling shutdown.
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- _ , ,_. ~. . _
3 VALVE TEST RELIEF REQUESTS -
L. SYSTEM: SERVICE WATER SYSTEM (SW) l L.1 Valve: XVG-3107A&B l
Category: B l Class: 2b 4 Function: Isolate service water from the reactor containment.
Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
Basis for Relief: Testing these valves during plant onerations t
will cause service water to mix with the i
! in'iustrial cooling water, causing a problem i ,
i with the chemistry control of the Industrial cooling water system.
1 Alternate Test: Valves will be tested during ' cold shutdown.
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O PAGE 44
.j, - - . .
VALVE TEST RELIEF REQUESTS
/~' M. SYSTEM: CRDM COOLING SYSTEM M.1 Valve: XVG-7501, 7502, 7503 and.7504
]
j Category: A f
Class: 2a Function: Containment Isolation Valves for the CRDM Cooling System .
Test Requirement: Valves will be exercised (full stroke) for operability every three (3) months.
Basis for Relief: In the event that maintenance is required,
( ) upon the failure of either of these valves, by testing, during plant operation, it could cause overheating of the CRDM's.
Alternate Test: Valves will be tested during cold shutdown.
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t= . .
. VALVE TEST RELIEP REQUESTS N.1 Valve: XVB-0001 A & B and XVB-0002 A & B Category: A l Class: 2a Isolate the Neactor Building purgo supply and Function:
- exhaust.
Test Requirement: Exercise valves (full stroke) for operability every three (3) months.
?
I Basis for Relief: During normal plant operations these valves i
are locked closed and required by technical l specifications to remain closed.
!O Alternate Test: Valves will be full stroke exercised during cold shutdown.
]
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- PAGE 46 4
1
--,----,,..-,n,- - , . . - - - , ,,.,,,,.,_m---,,ym,,_,,-e,, ,-m ,,w. nam.. -,----,--e,,,.,---,.,,_ ,-,,_ ,,---,..,.,a-~r-,-
VALVE TEST RELIEF REQUESTS P. System: PASSIVE CONTAINMENT ISOLATION VALVES Cl' P.1 valves: XVC-7541, XVC-7544, XVC-9689, XVC-8103, XVC-8703A, XVC-8703B, XVG-8702A, XVG-8702B, XVC-2913, XVT-2912, XVG-8701A, XVC-8701B, XVC-6799, XVD-8767, XVC-6588, XVG-6587, XVT-2679, XVT-2680, XVX-6052B, XVX-6052A, _
XVX-6053A, XVX-6053B, XVX-6050B, XVD-6051A, XVD-60510, XVD-8768, XVX-60513, XVD-6671, XVD-6672, XVD-6697, XVD-6698, XVD-7135, XVG-6772, XVG-6773 Ca tegory: A/C for check valves. A for other valves.
Class: 2A i O Function: Provide Containment Isolation for various systems.
Test Requirement: Leak test in accordance with ASME Section XI Code every two (2) years.
Basis for Relief: Valves are required to be tested every eighteen (18) months to two (2) years in accordance with Appendix J and/or Techn.'. cal Specifications.
Alternate: Leak test valves in accordance with the requirements of Appendix J, Technical Specifications and/or Surveillance Test
() Procedures.
PAGE 47
~
ou o VALVE TEST RELIEF REQUESTS
~
Q. System: REACTOR COOLANT SYSTEM Q.1 Valves: PCV-445A, POV-4453, and PCV 444B
' Category: B Class: 1 Function: To provide overpressure protection for the Reactor Coolant System.
Test Requirement: Exercise Valve (full stroke) for operability every three (3) months.
O
%)
Basis for Relief: Testing of these valves during cower operation would require the associated downstream block valves to be closed. Should the associated block valve fail in the closed position the 4 margin of safety for overpressure protection i
would be reduced.
Alternate: Valves will be tested during cold shutdown.
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PAGE 48
. _ . . _ . . . . ~ . _ _ . _ _ . . . . . . . . . _ . _ . . . . _ . _ _ _ . . . . . . . _ . . . . . . _ . . . . . . . . . . . . . . . _ . _ _ .
SOUTH CAROLINA ELECTRIC AND GAS COMPAliY VIRGIL C. SUMMER NUCLEAR STATIO!!
?!UCLEAR OPERATIONS GENERAL TEST PROCEDURE GTP-004 INSERVICE INSPECTION SYSTEM PRESSURE TESTING i
REVISION 2 SEPTEMBER 13, 1982 SAFETY RELATED Reviewed by:
C0PY n, A. f /d = / 9' V b l ORIGINATOR (of this revision) Date
- c. _ _ - _ $. (lab G /d-/9'!*L d)iSCIESINE SUPERVISOR Date Approved:
h - /0 - 2 7 ~$::-
ASST. MGR, NAINTENANCE SERVICES Date l
Date Issued:
O
GTP-004 PAGE i REVISION 2 9/13/82 LIST OF EFFECTIVE PAGES PAGE REVISION i 2 11 2 1 2 2 2 3 2 4 2 5 2 6 2 7 2 8 2 9 2 10 2 11 2 12 2 13 2 ATTACHMENTS
~
^:::::::: ::: 01Dl3Tl4034iOl4 e .3 9 2 .4 i l 17 2 .5 2 .6 2 .7 2 .8 2 e
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._.-- .. . . . . ..~...~ --.. - .. .. .... .
GTP-004
+
PAGE 11 REVISION 2 f-'s 9/13/82
- (_'l TABLE OF CONTENTS PAGE 1.0 PURPOSE 1
2.0 REFERENCES
AND GLOSSARY l 3.0 . RESPONSIBILITIES 3 4.0 INSERVICE INSPECTION TESTING AND EXAMINATION 4 5.0 DOCUMENTATION 12 6.0 RESULTS 13 7.0 ATTACHMENTS 13 ATTACHMENTS Attachment 7.1 - Code Class 1, 2, and 3 Component Inspection Program Attachment . 7.2 - Test and Examination Schedule ,
Attachment 7.3 - ISI Hydro Reference Index Attachment 7.4 - Code Class 1, 2, and 3 System Leak Testing Attachment 7.5 - Code Class 1, 2, and 3 Relief Request Identification Attachment 7.6 - Appen-lix J Testing Attachment 7.7 - System Open/Reclose Leak Test Record Attachment 7.8 - System Open/Reclose Leak Test Acceptance Criteria O
.~. . . . . . . . . . . . . . . - . - . . . . . ~ . ---~ . ---
GTP-004 REVISION 2 9/13/82 1.0 PURPOSE 1.1 This procedure provides the necessary controls for system pressure tests including leakage tests, hydrostatic tests, and, if applicable, pneumatic tests for ASME Section III code class 1, 2, and 3 pressure retaining components.
2.0 REFERENCES
AND GLOSSARY 2.1 References 2.1.1 ASME Boiler and Pressure Vessel Code Section III, 1971 Edition through the summer 1973 addenda.
2.1.2 ASME Boiler and Pressure Vessel Code Section V,1977 Edition Through the summer 1978 addenda.
2.1.3 ASME Boiler and Pressure Code Section XI, Section 1977 Edition throuSh the summer 1978 addenda.
2.1.4 SAP-139, Development , Revision, and Approval of Procedures.
2.1.5 SAP-146, Non-Conformance Control Program ,
2.1.6 SAP-141, Control and Calibration of Measuring and Test Equipment.
2.1.7 SAP-145, Inservice Inspection.
2.1.8 10 CPR 50.55a.
2.1.9 SAP-108 Station Staff Qualifications and Training.
2.1.10 Applicable Surveillance Test Procedures 2.1.11 10 CFR 50.55 Appendix J O
PAE17 U
.. . _- . _ . . . _ _ . . . . . _ . _ _ _ _ . . _ . _ . _ .a . _ . . . . . . . _ _ _ . .
GTP-004 REVISION 2 g 9/13/82
, \-- 2.2 Glossary 2.2.1 Authorized Nuclear Inservice Inspection (ANII) - An inspector employed by an insurance company authorized to write boiler and pressure vessel insurance and having qualified in accordance with the requirements of ANSI /ASME N626.1 - 1975 2.2.2 ASME Code (Code) - An approved ANSI document published by the American Society of Mechanical Engineers including, but not limited to, specific construction requirements, pre-service inspection requirements and inservice inspection requirements for certain classified pressure systems, components and their supports.
2.2.3 Code Class - A classification of items and components based upon the Section III construction code subsection used to fabricate and/or install such items.
A. Class 1 - Subsection NB B. Class 2 - Subsection NC rN C. Class 3 - Subsection ND D. Class MC - Subsection NE E. Component Supports - Subsection NF 2.2.4 Inservice Inspection (ISI) - Those scheduled inspection activities performed during the plant lifetime as outlined in ASME Code Section XI.
2.2.5 Inservice Inspection Coordinator (ISI J
Coordinator)-That individual designated by the Manager, V. C. Summer Nuclear Station, who is responsible for development and implementation of the ISI Program.
2.2.6 Inservice Inspection Program - Those planned and systematic actions performed to: categorize the area subject to inspection and responsibilities, provide for accessibility, apply examination methods and procedures, qualify personnel, establish frequency of inspection, establish and maintain record keeping and reporting requirements, evaluation of inspection results and, if necessary cubsequent disposition and corrective action of such results, and document a repair program.
PAGE 2 0F 13
GTP-004 REVISION 2 9/13/82 2.2.7 Inspection Interval - That amount of time approximately equal to 1/4 of expected plant life.
(10 years) See Attachment 7.1.
2.2.8 Inspection Period - That amount of time in calender years and/or months approximately equal to 1/3 of an inspection interval. (3 to 4 years) See Attachment 7.1.
2.2.9 Regulatory Authority - A Federal Government Agency such as the USNRC.
2.2.10 Replacement - A spare component (s), parts of such component (s), or subsystem (s) but not the addition of new systems.
2.2.11 Repair - Welding rework activities, including initial and surface finishing processes, required to return an item to condition acceptable to code.
2.2.12 Rework - Repair or replacement activities, or a combination thereof required to return an item to a condition acceptable to the Code.
2.2.13 Technical Services Coordinator - That individual designated by the Manager, V. C. Summer Nuclear -
Station, to act as liason for SCE&G/NO with the USNRC.
2.2.14 Abbreviations.
A. SCE&G/NO - South Carolina Electric and Gas Company, Nuclear Operations.
B. USNRC - United States Nuclear Regulatory Commis sion.
3.0 RESPONSIBILITIES 3.1 Procedure SAP-145 establishes, describes and delineates the responsibilities associated with the System Pressure Testing Program.
O PAGE 3 0F 13
GTP-004 REVISION 2 9/13/82 O
k,,) 4.0 INSERVICE INSPECTION TESTING AND~ EXAMINATION 4.1 Inservice Inspection.
4.1.1 The required pressure tests and concurrent visual examinations (VT-2) shall be identified and scheduled in accordance with the requirements of
. attachment 7,2 unless specific relief has been granted by the Regulatory Authority. The required system pressure tests are indexed in attachments 7 3 and 7 4.
4.1.2 Pressure tests and examinations shall be performed in accordance with written approved procedures.
4.1.3 Personnel performing the required visual examinations during the pressure test shall be qualified in accordance with ASME Code Section XI and the appropriate Station Quality Control or Operations Procedures.
4.1.4 Type A, B, and C testing per 10 CFR 50 Appendix J
.shall be in accordance with Surveillance Test Program (206 and 115 Series) in accordance with Attachment 7.6. Appendix J testing may be ~
substituted for the required ASME Section XI 7s
(} Testing, when applicable.
4.2 Pressure Test and Examination Scheduling 4.2.1 In addition to the requirements of 4.1.2 class 1 inservice pressure tests and examinations shall be performed during plant outages; class 2 and 3 tests and examinations may be performed, as appropriate, either during plant outages or during systems operations.
4.2.2 The pressure tests and examinations shall be performed and completed during each period and/or interval, as applicable, during the the service lifetime of the plant except as otherwise noted in paragraph 4.2 3
(^)'
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GTP-004 REVISION 2 9/13/82 4.2.3 Each inspection interval may be decreased or extended (but not cumulatively) by as much as 1 year. If the plant is out of service continuously for 6 months or more, the inspection interval during which the outage occurred may be extended for a period of time equivalent to the outage.
4.2.4 The inspection interval and period is determined by the number of calendar years following placement of the plant into commercial service. Attachment 7.1, Inspection Program B, tabulates 4 consecutive intervals.
4.2.5 Inspection intervals for repaired items, component replacments, additions, and alterations shall coincide with the remaining intervals as originally scheduled prior to such repairs, replacements, additions or alterations.
4.2.6 Repaired items, replacements, additions, alterations and items which have been opened and reclosed shall be pressure tested and visually examined (VT2) in accordance with the applicable code and procedure after such activities have been completed prior to ,
or at the time the applicable component is placed back into service. g 4.2.7 System and/or component pressure tests and concurrent examinations may be performed in conjunction with one or more of the following operations.
A. Leakage test af ter pressurization to nominal operating pressure.
B. Leakage test performed concurrently with the system functional test.
C. Leakage test performed concurrently with a hydrostatic test.
D. Hydrostatic test or other required system pressure tests for repairs, alterations, replacements and additions may be performed concurrently with applicable scheduled pressure tests providing the requirements of paragraph 4.2.6 are not violated.
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GTP-004 REVISION 2 9/13/82 g E. Visual examination performed after the required
test pressure holding time has been satisfied.
NOTE: During tne required visual examination test conditions shall remain essentially constant.
4.2.8 Except for items repaired by welding, the appropriate leak test for items which have been opened and reclosed may be performed during or before the System Leak Test and recorded on Attachment 7 7 and a completed copy of Attachment 7 7 w'111 be attached to the appropriate MWR.
4.2 9 For Leak Tests required af ter opening and reclosing a system or component Attachment 7.8 shall be used to determine the maximum leakage rate without further engineering evaluation.
43 Pressure and Temperature Requirements (Class 1) 431 Class 1 system leakage tests shall be performed at a test pressure not less than the nominal operating pressure associated with 100% rated reactor power.
The system test pressure an'd temperature shall be
~
attained at a rate in accordance with the heatup limitations specified for the system.
- 4.3 2 Class 1 system hydrostatic tests shall be performed at a test pressure of.1.10 times the system nominal operating pressure (Po) that corresponds with 100%
rated reactor power or may be conducted at temperatures above 100*F in accordance with the following tempera .are-pressure criteria except as modified in 4 3 2( A) and/or 4 3 2(B), as applicable.
432 Test Temperature Test Pressure 200 F 1.08 Po 300 F 1.06 Po 400 F 1.04 Po 500* F 1.02 Po A. Class 1 hydrostatic tests shall meet the requirements as specified by fracture prevention criteria applicable to ferritic materials of system components.
B. Class 1 test temperature shall be modified as required by the results obtained from each set of material surveillance specimens withdrawn from the reactor vessel during the service
(-~3j lifetime.
4.4 Pressure and Temperature Requirements (Class 2) .
PAGE 6 0F 13
GTP-004 REVISION 2 9/13/82 4.4.1 Class 2 system and component leakage or functional tests shall be performed at nominal operating pressure of such systems or components, as applicable.
4.4.2 Class 2 system and/or component hydrostatic test pressures, as applicable, shall be determined as follows, except as described in 4.4.3 through 4.4.7 where Psv is the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.
Design Temoerature Test Pressure
< 200 F 1.10 Psv I 200 F 1.25 Psv 4.4.3 In the case of class 2 atmospheric storage tanks, hydrostatic test pressure developed with the tank filled to its design capacity shall be the acceptable test pressure.
4.4.4 For 0 - 15 PSI class 2 storage tanks the test pressure shall be 1.1 times Pg where Pg is the ,
design pressure of the vapor or gas space above the liquid level for which overpressure protection is provided.
4.4.5 Open ended portions of class 2 suction or drain lines from a storage tank to the first shutoff valve shall be considered as part of either an atmospheric storage tank or a 0 - 15 PSI storage tank, as applicable.
4.4.6 In the case of open ended portions of class 2 discharge lines in non-closed systems (such as the containment spray header), any test that demonstrates unimpaired flow shall be acceptable in lieu of system hydrostatic pressure tast.
4.4.7 The test temperature for class 2 systems and39 components containing ferritic steel items shall meet the requirements specified by fracture prevention criteria. In systems containing ferritic steel components in which fracture toughness and/or fracture prevention criteria were neither specified nor required the system test temperature shall be determined by SCF&G. There is no established limit on system or component test temperature for such systems and/or components constructed entirely of austenitic steel materials.
O PAGE 7 0F 13
GTP-004 REVISION 2 9/13/82 f3 ks _) 4.5 Pressure and Temperature Requirements (Class 3) 4.5 1 For Class 3 system inservice tests the inservice operating pressure during system operation shall be acceptable as the system test pressure.
4.5 2 For Class 3 sys*em functional tests the nominal operating pressure of the system shall be acceptable as the system test pressure.
4.5 3 For Class 3 system and component hydrostatic tests, the pressure and temperature shall be determined as specified in paragraphs 4.4.2 through 4.4.7 of this procedure.
- 4. 6 Pressure Holding Times for Class 1, 2, and 3 Items 4.6.1 SYSTEM LEAKAGE TEST - No holding time required.after attaining test pressure and temperature conditions.
4.6.2 SYSTEM HYDROSTATIC TEST A. Non-insulated system or component - 10 minutes-required after attaining test pressure and temperature conditions. -
0,\ ') B. Insulated system or component - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> required after attaining test pressure and temperature conditions.
4.6.3 SYSTEM FUNCTIONAL TEST - 10 minutes after attaining the required test pressure and temperature conditions.
4.6.4 SYSTEM INSERVICE TESTS - No holding time required providing the system has been in operation for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise, an additional amount of holding time is regniz ed to obtain 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> total.
4.6.5 SYSTEM PNEUMATIC TESTS - 10 minutes after attaining the required test pressure.
4.7 Visual Examination (VT-2) l l
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GTP-004 REVISION 2 9/13/82 4.7.1 Visual . examinations (VT-2) shall be performed after attaining the required test pressure and temperature conditions in accordance with the requirements of applicable Surveillance Test Procedures except as permitted by 4.7.2.
4.7.2 The visual examination, VT-2, following a repair or replacement of a component, or the alteration of a system may be limited to the repaired or replaced componencs, or the altered portion of a system, but shall include any connection made to the existing system.
4.8 Recair, Reclacement or Rework Pressure Tests 4.8.1 Repair Pressure Tests (Class 1, 2, and 3)
A. After repairs by welding on the pressure retaining boundary a hydrostatic test shall be performed and a visual examination (VT-2) shall be conducted as specified by paragraph 4.7.2 except as noted in 4.8.l(B).
B. The following maybe exempted from the required hydrostatic test (s): -
- 1) Cladding repairs. k
- 2) heat exchanger tube plugging
- 3) piping, pump and valve repairs that do not penetrate through the pressure boundary
- 4) pressure vessel repairs where the repaired cavity does not exceed 10" of the minimum design wall thickness
- 5) Component connections, piping and associated valves that are 1" nominal pipe size and smaller.
NOTE: Repairs made in accordance with a procedure which allows exception from postweld heat treatment shall not be exempted from hydrostatic tests.
4.8.2 Rework and Replacement Tests (Class 1, 2, and 3)
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GTP-004 REVISION 2 9/13/82 A)
I A. Pressure tests shall be performed subsequent to rework or replacement welding activities as specified in 4.8.1.
B. Subsequent to rework or replacement activities not involving welding a leakage test shall be conducted following reclosing of.a component in the system.
4.9 Test Gages, Instrumentation, and Equipment 4.9.1 system instrumentation, test instruments, or test gages may be used for the system tests described in this procedure providing the applicable requirements of 4.9.1 though 4.9.7 have been satisfied.
4.9.2 The test gages used in pressure testing shall provide results accurate to within .5% of full scale.
4.9.3 All test gages shall be calibrated against a standard dead weight tester or a calibrated master gage. The test gages shall be calibrated before each test or before each series of tests. A series of tests is a group of tests .that use the same ,
, pressure test gage (s) and such tests are conducted
(}
within a period not exceeding 2 weeks.
4.9.4 Indicating pressure gages used in testing shall have their dials graduated over a range of at least 1.5 times, but not more than 4 times, the intended maximum test pressure.
4.9.5 When testing an isolated component, the pressure measuring gage, instrument or sensor shall be connected as close to the component as practical.
4.9.6 When testing a group of components or a multicomponent system, the pressure measuring gage, instrument or sensor shall be connected to any point within the pressure boundary of the components or system such that the imposed pressure on any component, including static head, will not exceed 106% of the specified test pressure for those part of the system under consideration.
)
s FACE 10 CF 13
GTP-004 REVISION 2 9/13/82 4.9.7 Any equipment required to perform pressure testing shall meet as a minimum, the cleanliness requirements of the system or component to be
~
tested.
4.9.8 Test gages and instrumentation shall be calibrated in accordance with the requirements of SAP-141.
4.10 Corrective Measures 4.10.1 The source of leakages detected during the performance of system pressure test shall be located F.nd evaluated for corrective measures as follows:
A. Buried components with leakage losses in excess of limits acceptable for continued service shall be repaired or replaced; B. Repairs to components shall be performed in accordance with the requirements of SAP-302, SAP-304 WM-1.0, 'iM-2.0 and other criteria of the applicable design specifications.
C. Replacement of components shall be perferred in accordance with IWA-7000 of the Code. -
D. The detection of boric acid residues on ferritic steel components shall require the location of the leakage source and the areas of general corrosion, if any. Components or other items with local areas of general corrosions that reduce the wall thickness by more than 10%
on that would inhibit the capability of such items or components to perform their intended function shall be evaluated to determine whether the component may be acceptable for continued service, or repair or replacement is required.
NOTE: General Corrosion is an approximate uniform wastage
- f a surface of a component, through chemical or el3ctros chemical reaction, free of deep pits or cracks.
""GE 11 0F 13
. . ~ - - .. . ... - . .. +.. . . . . ..:. .. .- . . - - . . . .:...
GTP-004 REVISION 2 9/13/82 e-( ,N) 50 DOCUMENTATION 51 Examinations and test plans and schedule shall be developed, approved and distributed in 'accordance with the requirements of this procedure.
52 Surviellance Test Procedures used for system pressure tests
. during Inservice Inspection either have been or will be prepared and approved in accordance with, SAP-139 prior to performing the applicable test (s).
53 NDE personnel Qualification records shall be maintained in accordance with the requirements of Operations and Station Quality Control Procedures, as applicable.
54 System p" essure tests shall be documented in accordance with the requirements of this procedure and/or the applicable Surveillance Test Procedure.
55 When required, Radiation Work Permits will be initiated and completed in accordance with Health Physics Procedures.
5.6 When required, safety tags shall be issued, completed, attached to appropriate equipment, and filed in accordance ,
with SAP-201.
'/ 57 A copy of the evaluation and, if required, disposition and corrective measure records shall become part of the Surveillance Test Procedure record.
5.8 Test summary repodts shall be prepared from the Surviellance Test Procedure records and submitted to the Regulatory Authority within 90 days after completion of the inservice inspection outage.
5.9 Test, evaluation, disposition and corrective measure records shall be maintained for the service lifetime of the Component.
5 10 visual examination (VT-2) records shall be maintained in accordance with the applicable Surveillance Test Procedures.
5 11 When required, a non-conforming condition shall be documented in accordance with the requirements of SAP-146.
5 12 Flow drawings, as referenced in Attachment 7.4, shall be available for review during system hydrostatic testing activities.
O PAGE 12 0F 13
6 GTP-004 REVISION 2 9/13/82 5.13 Relief requests, if any, shall be referenced on Attachment 7.5 as applicable. Such relief requests shall be indexed, stored and maintained under separate cover.
6.0 RESULTS 6.1 Evaluation of the pressure test and examination data shall be performed in accordance with the requirements of the applicable code, standard or specification and included as part of the Surveillance Test Procedure Record as described in paragraph 5.7.
6.2 Disposition and corrective measures, as a result of unacceptable tests or examinations, may be implemented using original design data, improved design data, newly developed techniques, appropriate standards and codes, or a combination thereof.
6.3 corrective measures implemented to correct a non-conforming condition shall detail the activities performed including the action taken to prevent recurrence of the condition.
7.0 ATTACHMENTS
~
7.1 code class 1, 2, and 3 System and component Inspection Program (1 Page).
7.2 Code class 1, 2, and 3 Test and Examination Schedule (4 pages) 7.3 code class 1, 2, and 3 ISI Rydrostatic Test Reference Index (6 pages) 7.4 code class 1, 2, and 3 System Leak Testing (1 page) 7.5 code class 1, 2, and 3 Relief Request Identification 7.6 Appendix J Testing 7.7 System open/Reclose Test Record.
7.8 System Open/Reclose Test Acceptance Criteria O
PAGE 13 CF 13
. . ~.-.....--..-..:....a..- . . . - . . ~ . - - - :- - - - - - ~ ~ - -
GTP-004 ATTACHMENT 7 1 PAGE 1 0F 1 REVISION 2 CODE Class 1, 2, & 3 Component Inspection Program Inspection Interval Inspection Period Calendar Years of Plant Service 3
1st 7 10 2nd 13 17 20 3rd 23 27 30 4th 33 37 40 ,
l i
i GTP-004 ATTACEGff 7 2 PAGE 1 OF 4 REVISION 2 TEST AND EXA?4INATION SC EvULE CLASS 1 ITS4 PARIS- TEST EXAMINATICil lSf SUCCESSIVE CEFEPSAL Of NO. EXAMINED PSUIRED MEIHCD INSPECTION INSPECTICN INSPECTICN (1)(2)(3) (4) INIM AL INIERVALS 'IO END OF 2ND,3RD,41R IhT M AL FZAC'ICR VESSEL B15 10 Pressure Leakage Vr-2 Each Each refueling Scundary refueling Cutage outage B15 11 Pressure Hydrostatic VT-2 one test one test per Permissible Boundarf interral PRESSURIZER B15 20 Pressure Leakage VT-2 Each Each refuelire Boundar/ refuelirs outage outage B15 21 Pressure Hydrostatic Vf-2 One test Cne test per Permissible Boundary interval interval STEAM GENEFXICRS B15 30 Pressure Leakage VT-2 Each Each refueling Boundarf refuelirs outage outage B15.31 Pressure Hydrostatic VT-2 One test One test per Permissible Boundary interval HEAT EXCHANGERS B15 40 Pressure Leakage VT-2 Each Each refueling Boundary refuelirs outage outage B15 41 Pressure Hydrostatic VI-2 One test One test per Pernissible Boundarf interval IUIES: (1) - Entire pressure retaining boundary of the reactor coolant system is subject to systen pressure test conducted in accordance with TdA-5 coo with the er.ceptiens specified in IWA-5214 when system pressure tests are conducted for repaired, replaced or altered cagonents.
(2) - Leakage test twt >-5221, Hydrostatic Test TdB-5222.
(3) - Acceptance standard rdA-5250.
(4) - Visual examination of TdA-5240.
. _ . . . . . . . . . . _ . . . . . - _ _ . - . . . . . _ _ . ..__.... .....:___ _ _ . . _ .._._m. ..a._... _ , _ . .
GTP-004 ATIACF24ENT 7 2 PAGE 2 0F 4 PETISION 2 TEST AND EXAMINATION SCFiDULE CLASS 1 IT54 PARIS TEST EXAMINA'2 ION IST SUCCESSIVE DEFEEP.AL OF NO. EXAMDED REUIRED MEIHOD LNSPECTICN INSPECTICN INSPECTICN (1)(2)(3) (4) INTERVAL IN1EIVAIS 'IO END OF 2ND,3RD,4T. HTTERVAL PIPING B15 50 Pressure Leaka6e VT-2 Each Each refuelire Boundarf refueling Outage outage B15 51 Pressure Hydrostatic VT-2 One test One test per Permissible Boundarf interval PeAPS B15 60 Pressure Leakage Vr-2 Each Each refuelire Boundarl refuelirq; outage outage 315.61 Pressure Hydrostatic V2-2 One test Cne test per Pen::issible Boundarf ..nterval .
O Q VALVES B15 70 Pressure Leakage VT-2 Each Each refuelire Boundar/ refueling outage outage B15 71 Pressure Hydrostatic VI-2 One test One test per Permissible Boundarf interval IDIES: (1) - Entire pressure retaining boundary of the reactor coolant system is subject to systen pressure test conducted in accordance with IWA-5000 with the exceptions specified in TdA-5214 when system pressure tests are conducted for repaired, replaced or altered cm:ponents.
(2) - Leakage test E65221, Hydecstatic Test E65222.
(3) - Acceptance standard IdA-5250.
(4) - Visual examination of IdA-5240.
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(d'
. . . - . . . . . ~ . . . . . . . . . . . . . , . . . ~ .. .- . .. .- . - . . . . . .. . . . .
G22-004 ATTACRGIT 7.2 PAGE 3 OF 4 TEST AND EXAMINATICN SCHEDULE CLASS 2 ITS4 PAETS TEST EXAMINATICN EXTS7f FPK UENCY NO. EXAMDED PS UIRED ME1ED OF OF (1)(2)(3) (4) EXAMINATION EXAMINATION (5) (6) i FRESSURE l VESSELS C7.10 Pressure Leakage W-2 Pressure Ecundar/ Each Inspection Ccm;cnents Period C7 11 Pressure Hydrostatic W-2 Pressure Boundar/ Each Inspection Ccmponents Interial PIPIln C7 20 Pressure Leakage VI-2 Pressure Boundary Each Inspection C g nents Period l l
C7 21 Pressure Hydrostatic VT-2 Pressure Boundary Each Inspection Ccmponents Interval PUMPS C7 30 Pressure Leakage Vr-2 Pressure Boundary Each Inspection O Components Period C7 31 Pressure Hydrestatic vr-2 Pressure Ecundar/ Ech Inspection Components Interval VALVES C7.40 Pressure Leakage VI-2 Pressure Boundary Each Inspection Cmponents Period (7)
C7.41 Pressure Hydrostatic VT-2 Pressure Boundary Each Inspection Ccmponents Interval NMES: (1) - Other than open-ended portions of systems.
(2) - Systen pressure tests of IWA-5000 and IWC-5000; Leakage test IWC-5221, Hydrostatic Test T4C-5222.
(3) - Acceptance Standard T4A-5250.
(4) - Visual examination of TiA-5240.
(5) - There are no exsptions or exclusions frcxn these requirements except as specified in IdA-5214.
(6) - The systen hydrostatic test shall be conducted at ce near the end of each inspection interval or during the same inspecticn period of each inspection interval.
(7) - A system functional test (rdC-5221) serves as a required system pressure test.
GTP-004 ATTACHMENT 7 2 PAGE 4 0F 4 REVISION 2
[)
v TEF AND EXAMDIATION SCIdDULE CLASS 3 ITS4 PARIS TESf EXAMINATION EXZHlf MifMJBiCY NO. EXAMINED REUIRED ND CF OF (3) EXAMINATION EXAMINATION D-A D.1.1 Pressure Leakage W-2 NOIE (4) Each Period Con:ponents (2)
(1)
Pressure Hydrostatic W-2 NOTE (4) Same Period (5)
Components of each interval (1)
D-B D.2.1 Pressure Leakage W-2 NOIS (6) Each Period Cceponents (7) _
(6)
Pressure Hydrostatic W-2 NOIS (6) Same Period (5)
Components of each interval (6) ,
D-C D.3 1 Piping (8) Leakage W-2 NOTE (8) Each Period Pumps, (2)
Valves Piping (8) Hydrostatic Vf-2 NOIE (8) Same Period (5)
Pumps, of each interval Valves NOTES: (1) - Pressure retaining components within the boundary of systems or portions of systems required to operate in support of nor ::al plant safety functions of shutting down and maintaining the reactor in cold shutdown condition.
(2) - Operating system inservice test (IWD-5221).
(3) - Hydrostatic Pressure Test (IWD-5223).
(4) - The systen beundary includes only those portions of the system required to operate or support the safety system function up to and including the first nonnally closed valve or valve capable of autcmatic closure when the safety function is required.
(5) - Fbe Inspection Program B, the hydrostatic test and subsequent visual examination shall be performed during the same period of each inspection interval.
(6) - Pressure retaining ccuponents within the boundary of systems or portions of systers required to operate in support of the post-accident safety functions of energency core cooling, containment heat renoval and at:nosphere cleanup, and long tenn residual heat reenval from the reactor.
(7) - Operating systen functional test (IWD-5222).
(8) - Pressure retaining piping, pumps and valves within the boundary of systems or v portions of systems required to operate in support of residual heat renoval fecm spent fuel storage pool.
w w- , w
GIP-004 AITACEEE 7 3 PAGE 10F 6 RE'lISICN 2 ISI HERO AND/CR PNEE4A*IC TES1'UD R: :xD;CE INDEX STP M0. SYSTEMCO CCDE CLASS CESCRIPTION FIC4 D4G.
149 001 CC-01-H1 3 Carponent Cool Iow Pressure Hydro D-302-611 149 002 CC-02-H1 3 Cc=ponent Cool Surge Tnk Hydro D-302-611 149 003 CC-04-H1 2/3 Component Cool Inside Reactor Bldg. N302-612 !
149 004 CC-04-H2 2/3 CC Ebost Ebp Discharge Hydro D-302-612 l 149 005 CC-04-H3 3 CC to RCP ?.erm Earrier Hydro D-302-612 149 006 CC-05-E 3 CCW to Non-Essential Equip. Hydro Test D-302-613 149 007 CS-01-E 2 Charging Pump Suction Pipe Hydro 114ED73 149 008 CS-02-H1 2 Volume Control Tank and Piping 114ED73 l Hydro '
149 009 CS-02-H3 3 Mkeup Piping Hydro 114ED73 149 010 CS-03-E 2 Charging Pump Discharge Pipe Hydm 114ED73 149 011 CS-04-H1 2 Charging Header Hydro 114ED73 ,
149 012 CS-05-E Seal Injection Piping Hydro 2 114ED73 gl 149 013 CS-07-E 2 RC Pump Seal Retum Lines Hydro 114E073 149 014 CS-07-H2 2 RCP A,B,&C Seal Return Lines Hydro 114E073
(
149 015 CS-07-H3 2 RCP A,B,&C Cmznon Seal Return Line Hydro 114ED73 149 016 CS-08-E 1 Excess Iatdown Hydro 114ED73 149 017 CS-09-H1 1 High Pressure Letdown Hydro 114E073 l 149 018 CS-11-H1 2 Letdown Line IP Hydro 114ED73 149 019 CS-12-E 2/3 Ietdown Line LP Denin Hydro 114ED73 l 149 020 CS.-13-H1 2 BCMS Hydro 114ED73
, 149 021 CS-17-E 3 Boric Acid Transfer Pu::p Suction Hydro 114E073 l l
O
GTP-004 ATPACEGE 7 3 PAGE 2 0F 6 RE7ISICN 2 O
Q ISI HYDRO AND/OR PNEUMATIC TESfING RunnEICE INCEX STP NO. SYSTS4C#) CODE CLASS DESCRIPTION FLOW DWG.
149 022 cs-17-H2 3 Boric Acid Transfer Pump Discharge Hydro 114ED73 149 023 cs-17-H3 2 Ebric Acid Store Tanks Hydro 114E073 149 024 CS-20-H1 3 ERIS Demineralizer Hydro 114ED76 149 025 CS a 3 lbidup Enk Header Hydro 114E076 149 026 CS-22-a 3 Holdup Tank Fductor Ilydro 114E076 149 027 cs-23-H1 3 Becycle Evap Feed Demin Hydro 114ED76 149 028 CS-24-a 3 Recycle Evap Hydm 114E076 149 029 CS-26-H1 3 Recycle Evap Feed Pump Suction and Disch 114E076 149 030 cs-26-H2 3 Static Test Recycle Holdup Enk 1 114E76 149 031 cs-26-H3 3 Static Test Recycle Holdup Tank 2 114ED76 149 032 CS-27-H1 3' cVCS Palief Valve Discharge Header Hydro 114ED76 U 149 033 % 02-H1 3 WG Fuel Oil Storage hk A Pipe D-302-351 Hydro 149 034 DG-03-H1 3 D/G Riel Oil Storage hk B Pipe Hydro D-302-351 149 035 DG-04-H1 3 D/G "B" Day hk & Pipe PNEU D-302-351 149 036 WO5-E 3 WG "A" Day Sk & Pipe PNEU 0-302-351 149 037 DG-08-E 3 D/G "A" Starting Air Pneumatic % st D-302-353 149 038 DG-09-a 3 DLesel Gen "B" Starting Air Pneumatic Test D-302-353 149 039 DG-10-m 3 Diesel Gen "A" Crankcase Vac Systen Uc Test D-302-353 149 040 DG-11-m 3 DLesel Gen "B" crankcase Vac System Uc Test D-302-353 149 041 DG-12-a 3 Diesel G m "A" Jacket cool Watr Hydro D-302-353 149 042 W13-E 3 Diesel Gen "B" Jacket Cool Wate Hydro D-302-353 4
5115 025 DN-03-E2 2 Demin Water RB Penetration #231 Hydro D-302-715 I
we .o , eo.s e ow e ooo o e em=+=~u e **~ * * * * *ew**9
, + * * % W *' * '* **' * ** ' " * * ' "'""#
- 4
GTF-004 ATTACH'EiT 7 3 PAGE 3 0F 6 RE7ISICN 2 3I IEDRO AND/CR PN?d4ATIC TESTI'iG MuuECE INDEX STP NO. SYSE! (#) CCCE CLASS DESCRIPTION FILW DWG.
140.043 E?-01-H1 3 mer 74 mps Suction Piping Hydro D-ba-085 149 044 EF-02-H1 3 B:er F4 Pmps Discharge Header Hydro D-302-085
- 115 023 FS-01-H1 2 Fire Protection Sys R3 Pen #404 Hydro D-302-231
- 115 023 FS-19-H2 2 Fire Protection Sys R3 Pen #427 Hydro D-302-231 149 045 FW-01-H1 2 Hydrotest of ?4 Nuclear Lines D-302-083 149 046 GH-02-H1 3 Wastegas Ca:p Suct Ed & Recirc Hydro 114E077 150.020 GH-03-H1 3 Operatioral Leak Test of Wastegas Decay Snks 1,14E077 150.020 GH-04-H1 3 Cperational Ieak Test of Wastegas Shtdn Tks 114E077 149 049 HR-02-H1 2 Post Acc Hydro RB Pent 103&302 Pneu Test D-302-861 149 050 HR-03-H1 2/3 Ibst Acc Hydro Analy::er A Piping Pneu Test D-302-861, 149 051 HR-03-H2 2/3 Post Acc IC Analyzer B Piping Pneu Test D-302-273 l l
- 115 014 IA-08-H2 2 Pneu-:atic Test of Instr Air RB Pen # 319 D-302-273
- 115 014 IA-11-H2 2 Hydrotest P.ebu Instr Air Pen 311 D-302-273
- 115 004 IR-01,02 2 Leak Rate Test Sys Pneu::atic Test D-302-811 03,04-H1 ,
149 052 MS-01-H1 2/3 min Stm & Stm Generator Hydro D-302-011 149 053 5 03-H1 2 Reactor Mkup F/DegaseU'ier Hydro D-302-791 149 054 E02-2 2 Reactor Mkup Water Stor Tnk Hydro D-302-791 149 055 E 04-H1 2 Reactor Mkup Water Disah Pipe Hydro D-302-791 115 020 ND-35-H1 2 Incore Sump Disch Pipe Hydro D-302-821 115.020 E 01-E2 2 Hydro Test Nitro Blanket Pen #313 D-302-311 149 056 RC--01-H1 1 Peactor Coolant System Cold Hydro 114ED72 149 057 RC-01-H2 2 Reacter Vessel 'O' Ring Leakoff Hydro 114ED72 O
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G'IP-004 ATTACE SIT 7 3 PAGE 4 0F 6
^. RE7ISION 2 ISI HYDRO AND/OR PNEII4ATIC TESTDIG Re.cnnENCE INDEX STP NO. SYSM4(#) CCDE CLASS DESCRIPTION FIU4 LVG.
149 058 RC-02-E 2 Pressurizer Dead We.ight Tester 114ED72 Hydro 149 059 RC-03-H1 1 RD Bypass Loops Hydro 114ED72 149 060 RC-05-H1 2 RC Pt=p Stand Pipe Makeup Fydro 114ED72 149 061 RC-06-H3 3 N2 Gas Supply to ?RT Pipirg Hydro 114E072 149 062 RH-01-E 2 RER System Hydro 114E074
- 115.013 SA-03-H2 2 Station Air RB Pen #310 Hydro D-302-241 -
149 063 SF E 2 Static Test of R4ST D-302-651 149 064 SF-03-H1 2 SF Cool Train A&B Hydro D-302-651 149 065 SF-04-H1 2 SF Cool Demin for Refueling Cavity Hydro D-302-651
~
149 066 SI-01-H1 1 Safety Inject Highhead & BIT Hydro 114E075 O
V 149 067 SI-02-E 3 Boron Inject Recire Ptmp Suction Hydro 114E075 149 068 SI-02-H2 3 Static Test Ibem Inject Surge Tank 114ED75 149 069 SI-03-H1 2 Rd ST Supp. to RER, CVCS & RB Spr Rnps Hydro 114ED75 149 070 SI-04-H1 2 RHR Rnp Suction fran Cent Sunp Hydro 114ED75
- 115 007 SI-04-H2 2 Penetration #329 Guard Pipe Hydro 114ED75
U
I GTP-004 ATTACEM 7 3 PAGE 5 0F 6 ISI HYDRO AND/CR PNHDIATIC 'ESTDIG RureSICE INDEX STP NO. SYSTLi(#) CCCE CLASS DESCRIPTICN FILW U4G.
149 074 SP-02-E 2 P3 Spray Rings Hydro D-302-661 149 075 SP-03-H1 2 RB Spray Pt=p Discharge Hydro D-302-661
- 115 013 SS-01-H2 3 Sample Sys Lines from RCDr Ik Test D-3C2-771 a n5 018 SS-02-H1 2 Sa: ple Sys Lines fran RER Ik %st D-302-771
- 115 018 SS-04-E 2 Sample Sys Lines from RCS Lk Test D-302-771 5115 018 SS-05-H1 2 Sample Sys Lines fran SI tects Ik 'Ibst D-302-771 149 077 SS-07-H1 2 Sample Sys Lines from S/G's Hydro D-302-771 q g 149 078 54-01-H1 3 $ A 'nain Discharge D-302-222 149 079 SW-01-H2 3 54 B Train Discharge D-302-222 143 080 54-01-H3 3 S4 Pt=p A DLscharge Hydro Test D-302-221 149 081 SW-01-H4 3 SW Pu=p B Discharge Hydro Test D-302-221 149 082 S4-01-H5 3 F4 Pt=p C Discharge Hydro hst D-302-221 149 083 54-01-58 3 S4 Train A&B Disch to SW Pond Oper Test D-302-222 149 084 S4-04-H1 2 S4 'Hain A to RBCU Eydro D-302-222 149 085 54-04-H2 2 54 Train B to RB:0 Hydro D-302-222 0
-- .. .....a -. .---..~..-_..:....-. -.....: . . . - .. . . . . . . . . - .......,....~.
GTP-004 ATTACBENT 7 3 PAGE 6 OF 6 REVISION 2 ISI HYDRO AND/OR PNEMATIC TESTDU FIFEPZNCE HIDEX .
STP NO. SYSTE4(#) CCDE CIASS DESCRIPTICN FILW DWG.
149 086 vU-05-a 3 Hydrotest Chilled Water Lcop B D-302-841 149 087 VU-06-H1 3 FWrotest Chilled Water Ieop A D-302-841 149 088 WD-01-E 3 Spent Resin Store Tank Supply 114277 149 089 'a>04-m 2/3 RC Erain Tank Pump Pipi'- Hydro 114277 149 090 'nh06-E 3 Waste Holdup Tank Hydro 114277 149 091 WD-06-H2 3 Waste Evaporator Feed Punp Pipirg Hydro 114277 149 092 WD-10-H1 3 Waste Evap Paclege Hydro 114277 149 093 WD-12-H1 3 spent Pasin Storage Trans Piping Hydro 114277 149 094 WD-13-H1 3 Spent Resin Storage hk & Piping Hydro 114277
~
- Se first two alpha digits iderItify the syste::.
V'
- Falief Pequest see Attachnent 7 5 l
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GTP-004 ATTACEMENT 7.4 PAGE 1 OF 1 REVISION 2
" SYSTEM LEAK TESTING" 410 SERIES STP's 150.001 Reactor Coolant System Leak Test 150.002 Chemical and Volume Control System Leak Test 150.003 Safety. Injection System Leak Test 150.004 Residual Heat Removal System Leak Test 150.005 Component Cooling Water System Leak Test 150.006 Reactor Building Spray System Leak Test 150.007 Service Water System Leak Test 150.008 "A" Emergency Diesel Generator Support System Leak Test 150.009 "B" Emergency Diesel Generator Support Systems Leak Test 150.010 Emergency Fedwater System Leak Test 150.011 Feedwater (Nuclear) System Leak Test 150.012 Main Steam / Steam Generators Leak Test 150.013 Chilled Water System Leak Test 150.014 Reactor Building Ctaling System Leak Test 150.015 Spent Fuel Cooling System Leak Test.
150.016 Post Accident Hydrogen Removal and Alternate Purge System Leak Test 150.017 Boron Recycle System Leak Test 150.018 Reactor Makeup Water System Leak Test 150.019 Liquid / Solid Waste Disposal System Leak Test 150.020 Gaseous Waste Disposal System Leak Test 9
. . .~. .=.... . - . . . . . . ~ . . - . . . . . . . . . . . . . . . . . .... . . . .
GTP-004 ATTACHMENT 7 5 s PAGE 1 0F 1 I REVISION 2 CODE CLASS 1, 2, and 3 SYSTEM PRESSURE TESTING RELIEF REQUEST IDENTIFICATION RELIEF REQUEST ,
SYSTEM NO.
(AC) CRDM Cooling System 2-AC-1 (AH) Air Handling 2-AH-1 (BA) Breathing Air System 2-BA-1 (DN) Demineralized Water System 2-DN-1 (FS) Fire Protection System 2-PS-1 (HR) Post Accident H2 Removal System 2-HR-1 (IA) Instrument Air System 2-IA-1 (LR) RB Leak Rate Testing System 2-LR-1 1
(ND) Nuclear Drain System 2-ND-1 -
(RH) Residual Heat Removal 2-RH-1 (NG ) Nitrogen Supply System 2-NG-1 (SS) Nuclear Sample System 2-SS-1 (SA) System Air System 2-SA-1 (SP) RB Spray 2-SP-1 1
0
. . . . - . . . . . . . ~ . .-. . . - -- . . . . . - . . - - -.
GTP-004 ATTACHMENT 7.6 PAGE 1 0F 1 REVISION 2 APPENDIX J TESTING O
SYSTEM APPENDIX J TEST (AC) CRDM Cooling STP-115 029 (AH) Air Handling STP-115 022 (BA) Breathing Air STP-115 014 (DN) Demineralized Water STP-115 025 (FS) Pire Protection STP-115 023 (HR) Post Accident H2 Removal System STP-115 021 (IA) Instrument Air STP-115 014 (LR) RB Leak Rate Testing STP-115 004 (ND) Nuclear Drains STP-115 020
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(NO) Nitecgen Supply STP-115 015 (RH) Residual Heat Removal STP-115 008 lk (SS) Nuclear Sampling STP-115 018 (SA) Station Service Air STP-115.013 (SP) RB Spray STP-115 017 O
GTF-004 ATTACHMENT 7 7 PAGE 1 0F 1 REVISION 2
^% -
SYSTEM OPEN/RECLOSE LEAK TEST RECORD A. General
- 1. System t
- 2. Item Description I.D. Number, M'4R No .
3 Justification
- a. Replacement d b. Rework d c. Inspection d
- d. Investigation ((j e. Other [j WUAUlfisu UthdATUd / UAIL B. Test Data
- 1. Nominal Operating Pressure
- 2. Leak Test Pressure 3 Instrument Se rial No. Cal. Due Date 4.
O ITEM I.D.
NO.
ITEM NOMINAL SIZE LEAK RATE (cc/ min)
MAX LEAK RATE (cc/ min) SAT UNSAT b) $)
i t3 t3 t:1 L:)
td L:)
l C U td L:)
WUAbifisU W.G. 1N5PbOTUd /
OR OPERATOR (VT-2 EXAMINER / DATE Reviewed By:
Adi GUUduif4 ATUd / UAls O
4 GTP-004 ATTACHMENT 7.8 PAGE 1 0? 1 Rt.7, ISION 2 SYSTEM OPEN/RECLOSE LEAK TEST ACCEPTANCE CRITERIA ,
1
- ITEM MAXIMUM NOMINAL LEAKAGE SIZE (cc/ min) 1/8" 10
- ITEM NOMINAL SIZE 1/4" 30 A. Piping & Tubing - Nominal size of pipe as defined in 3/8" 50 ANSI B36.10 and ANSI 36.19 3/4" 150 B. Pumps & Valves - Nominal pipe size of the inlet 1" 200 connection 1-1/2" 250 2 300 3 450 4 590 ,
6 885 8 1180 10 1475 12 1769 14 2064 16 2359 18 2654 32 4718 36 5308 VESSELS 3308 NOTE: For those sizes not listed, the maximum leakage rate may be Extrapolated.
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Code Class 1, 2 and 3 Pressure Testing Relief Request Index l
Relief Request Number 2-AC-1
- 2. (AH) Air Handling, Reactor Building Purge Supply and Exhaust (Page 2)
Relief Request Number 2-AH-1 3 (BA) Breathing Air System (Page 3)
Relief Request Number 2-BA-1
- 4. (DN) Demineralized Water System (Page 4)
Relier Request Number 2-DN-1 5 (PS) Fire Protection System (Page 5)
Relief Request Number 2-FS-1
- 6. (HR) Post Accident H2 (Alternate Purge System) (Page 6)
Relief Request Number 2-HR-1 7 (IA) Instrument Air System (Page 7)
Relier Request Number 2-IA-1
- 8. (LR) RB Leak Rate Testing System (Page 8)
Relief Request Number 2-LR-1 9 (ND) Nuclear Drains System (Page 9)
Relief Reques t Number 2-ND-1
- 10. (NG) Nitrogen Supply System (Page 10)
Relief Request Number 2-NG-1
- 11. (RH) RHR Guard Piping (Page 11)
Relief Request Number 2-RH-1
- 12. (SA) Station Air System (Page 12)
Relief Request Number 2-SA-1
- 13. (SP) Building Spray Guard Piping (Page 13)
Relief Request Number 2-SP-1
- 14. (SS) Nuclear Sampling System (Page 14)
Relief Request Number 2-SS-1 I-1 ddr. uB] ' d 0115 i
D ?T Ry JO'E -
() SYSTEM PRESSURE TESTING RELIEF REQUEST SYSTEM (AC) CRDM Cooling System RELIEF REQUEST 2-AC-1 1
SYSTEM DRAWING NUMBER DL302-85 2 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times tae system pressure Psv for systems with design temperature of 200 F. or less and 1.25 times the system pressure Psv for systems with design temperatures above 200*F. The system pressure Pav shall be the lowest
\ pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF RF1UEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47 1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on tne Containment pressure retaining capabilities. This test satisfies the
' requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-115.029
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V PAGE 1 0F 14
SYSTEM PRESSURE TESTING RELIEF REQUEST
[U) .
SYSTEM
( AH) Air Handling, Reactor Building Purge Supply and Exhaust RELIEF REQUEST 2-AH-1 SYSTEM DRAWING NUMBER D-912-10 3 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Pav for systems with design temperature of 200*F. or less and 1.25 times the
,s system pressure Psv for systems with design temperatures
! i above 200'F. The system pressure Pav shall be the lowest pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Pottions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47 1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code. .
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-ll5.022 b
G PAGE 2 0F 14
i SYSTEM PRESSURE TESTING RELIEF REQUEST SYSTEM (BA) Breathing Air System RELIEF REQUEST 2-BA-1 SYSTEM DRAWING NUMBER D-302-27 4 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Powe r.
System Hydror,tatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Pav for systems with design temperature of 200*F. or less and 1.25 times the -
system pressure Psv for systems with design temperatures
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\
above 200*F. The system pressure Pav shall be the lowest pressure setting among the-number of Safety or Relief. valves provided for overpressure protection within the boundary of the system to be tested. .
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47 1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION .
Appendix J. testing as described above. STP-115 014 PAGE 3 0F 14
l SYSTEM PRESSURE TESTING RELIEF REQUEST
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SYSTEM (DN) Demineralized Water System RELIEF REQUEST 2-DN-1 SYSTEM DRAWING NUMBER D-302-715 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Psv for systems with design temperature of 200 F. or less and 1.25 times the system pressure Pav for systems with design temperatures
' ,\ above 200 F. The system pressure Pav shall be the lowest k- s pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47.1 + 10-0 psig is intended to prove that the penetration i
can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-ll5 025
-,) -
V 4
PAGE 4 0F 14
[)
V SYSTEM PRESSURE TESTING RELIEF REQUEST SYSTEM (PS) Fire Protection System RELIEF REQUEST.
2-FS-1 SYSTEM DRAWING NUMBER D-302-231 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Pav for systems with design temperature of 200*F. or less and 1.25 times the system pressure Pav for systems with design temperatures T above 200 F. The system pressure Psv shall be the lowest pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47.1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-115.023 PAGE 5 0F 14
~
[ SYSTEM PRESSURE TESTING RELIEF REQUEST
's SYSTEM (HR) Post Accident H2 , Alternate Purge Supply and Exhaust RELIEF REQUEST 2-HR-1 SYSTEM DRAWING NUMBER D-302-861 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be i conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Psv for systems with design temperature of 200 F. or less and 1.25 times the fs system pressure isv for systems with design temperatures above 200*F. The system pressure Pav shall be the lowest
(' ') pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been lassified as Nuclear Class 2 per current guidelines because it penetrates the l Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of l 47 1 + 10-0 psig is intended to prove that the penetration j can at least meet the requirements on the Containment l pressure retaining capabilities. This test satisfies the I
requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-115.021 7-i b PAGE 6 0F 14
i SYSTEM PRESSURE TESTING RELIEF REQUEST
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SYSTEM (IA) Instrument Air System i RELIEF REQUEST 2-IA-1 SYSTEM DRAWING NUMBER i
D-302-27 3 i EXAMINATION REQUIREMENTS 1
System Leakage Test - The system Leakage Test shall be d
conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
t System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Psv for systems with design temperature of 200*F. or less and 1.25 times the system pressure Psv for systems with design temperatures
, O above 200'F. The system pressure Pav shall be the lowest pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of
- the system to be tested.
) RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear
! Class 2 per current guidelines because it penetrates the i Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47 1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the
! requirements of the ASME Code Sub-Section IWC in proving the
- integrity of the code class piping; therefore, this line i segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-115 014 1
, PAGE 7 0F 14
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S_YSTEM PRESSURE TESTING RELIEF REQUEST SYSTEM (LR) Reactor Building Leak Rate Testing System RELIEF REQUEST 2-LR-1 SYSTEM DRAWING NUMBER D-302-811 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Powe r.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Pav for systems with design temperature of 200'F. or less and 1.25 times the system pressure Psv for systems with design temperatures 4
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above 200 F. The system pressure Pav shall be the lowest pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested. i RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47 1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on the Containment i pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION s Appendix J. testing as described above. STP-ll5 004
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PAGE 8 0F 14
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V SYSTEM PRESSURE TESTING RELIEF REQUEST SYSTEM (ND) Nuclear Drains System RELIEF REQUEST 2-ND-1 SYSTEM DRAWING NUMBER D-302-821 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Powe r.
Syatem Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Psv for systems with design temperature of 200*F. or less and 1.25 times the system pressure Psv for systems with design temperatures above 200 F. The system prersure Pav shall be the lowest
[(_)\ pressure setting among the r umber of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47 1 + 10-0 psig is intended to prove that the penetection can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
l ALTERNATE EXAMINATION
'l
- Appendix J. testing as described above. STP-ll5 020 O
V PAGE 9 0F 14
l
/~ SYSTEM PRESSURE TESTING RELIEF REQUEST SYSTEM (NO) Nitrogen Supply System RELIEF REQUEST 2-NG-1 SYSTEM DRAWING NUMBER D-302-311 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Psv for systems with design temperature of 200*F. or less and 1.25 times the system pressure Psv for systems with design temperatures
[ } above 200 F. The system pressure Pav shall be the lowest
\./ pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the l
Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each
- refueling cycle per Title 10 of the Code of Federal l Regulations, part 50, Appendix J. This pressure test of j 47 1 + 10-0 psig is intended to prove that the peneteation can at least meet the requirements on the Containment
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-115.015 PAGE 10 0F 14
_ - - - _ _ _ _. - =. .-_
/~'i SYSTEM PRESSURE TESTING RELIEF REQUEST b
SYSTEM (RH) RHR Containment Sump Suction Guard Piping RELIEF REQUEST 2-RH-1 SYSTEM DRAWING NUMBER 114E075 Sheet 3 of 5 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Pav for systems with design temperature of 200*F. or less and 1.25 times the system pressure Psv for systems with design temperatures T above 200*F. The system pressure Pav shall be the lowest pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations , part 50, Appendix J. This pressure test of 47 1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION
,-s Appendix J. testing as described above. STP-115 008 PAGE 11 0F 14
I' SYSTEM PRESSURE TESTING RELIEF REQUEST Sy TEM (SA) Station Air System RELIEP REQUEST 2-SA-1 SYSTEM DRAWING NUMBER D-302-241 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Pav for systems with design temperature of 200*F. or less and 1.25 times the
,~s system pressure Psv for systems with design temperatures i above 200'F. The system pressure Pav shall be the lowest pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47.1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-115 013 v
PAGE 12 0F 14
. , a SYSTEM PRESSURE TESTING RELIEF REQUEST
(}
SYSTEM (SP) RB Spray Containment Sump Suction Guard Piping RELIEF REQUEST 2-SP-1 SYSTEM DRAWING NUMBER D-302-661 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal operating pressure associated with 100% rated Reactor Powe r.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Pav for cystems with design temperature of 200'F. or less and 1.25 times the system pressure Pav for systems with design temperatures O above 200 F. The system pressure Psv shall be the lowest pressure setting among the number of Safety or Relief valves provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rate testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of
- 47.1 + 10-0 psig is intended to prove that the penetration l
can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requireinents of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-115 017 PAGE 13 OF 14
['v)' SYSTEM PRESSURE TESTING RELIEF REQUEST SYSTEM (SS) Nuclear Sampling System RELIEF REQUEST 2-SS-1 SYSTEM DRAWING NUMBER D-302-771 EXAMINATION REQUIREMENTS System Leakage Test - The system Leakage Test shall be conducted at a test pressure not less than the nominal pressure associated with 100% rated Reactor Power.
System Hydrostatic Test - The system Hydrostatic Test shall be at least 1.10 times the system pressure Psv for systems with design temperature of 200'F. or less and 1.25 times the system pressure Pav for systems with design temperatures above 200 F. The system pressure Psv shall be the lowest pressure setting among the number of Safety or Relief valves
\
provided for overpressure protection within the boundary of the system to be tested.
RELIEF REQUEST JUSTIFICATION Portions of the above system have been classified as Nuclear Class 2 per current guidelines because it penetrates the Reactor Containment liner. This line segment will be tested during the Local Leak Rte testing program during each refueling cycle per Title 10 of the Code of Federal Regulations, part 50, Appendix J. This pressure test of 47.1 + 10-0 psig is intended to prove that the penetration can at least meet the requirements on the Containment pressure retaining capabilities. This test satisfies the requirements of the ASME Code Sub-Section IWC in proving the integrity of the code class piping; therefore, this line segment will not require a separate test per Section XI of the ASME Code.
ALTERNATE EXAMINATION Appendix J. testing as described above. STP-115 018 e
PAGE 14 0F 14
I, SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATI0N ,
NUCLEAR OPERATIONS STATION ADMINISTRATIVE PROCEDURE SAP'-304 ASME CODE, SECTION XI REPAIR PROGRAM REVISION O JULY 12, 1982 / -
NON-CONTROLLED 0
ja u0PY C aGINATOR (of this revision) c-. ~,-
Date fh0 ASST MGR SINTENANCE mVICES P-/f-? 2.
Date W
Approved: $w / 6 P g MANw ER( g cslufsz D&te8 O REV EWEJ BY 3SRC 1- db"
. . _, _ _ _ _ _ . _ _ _ . _ _ _ . - , . . _ _ ~ _ . . _ . _ _ _ . . _ , _ . _ _ . _ . _ - _ _ _ . _ . _ . _ _ _ _ _ _ - . . . _ _ _ . _ _ _ _ . _ , . , , . ,
j 9 3 r
t j.
4 v
- SAP-304 I PAGE i ,
l REVISION O ;
- 7/12/82 '
?
e i LIST OF EFFECTIVE PAGES i
! PAGE REVISION i
1 i- 0 i
i .
i 11 -
O'
- l -
1 O
} , ,
I 0 t 2 3 0 ,
4
- 4 0 1
5 0 b
j 6 0 1
i
- 7 0 8 0 ATTACHMENTS
, Attachment I O I I
Attachment II O t'
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1 1
I .
I :
1 i
i
- j i !
i i
9 l i
I t 1
SAP-304 PAGE 11 REVISION O O 7/12/82 TABLE OF CONTENTS i
PAGE List of Effective Pages 1 1
1.0 PURPOSE ,
1 2.0 SCOPE 1
30 REFERENCES.
1 4.0 DEFINITIONS RESPONSIBILITY 3 50 4
6.0 PROCEDURE 8
70 FIGURES 8
8.0 RECORDS ATTACHMENTS
' Attachment I - Record of Section XI Repair Attachment II - Index to Section XI Repair I
i
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O
SAP-304 REVISION O Is1 7/12/82 L ,1 -
1.0 PURPOSE The purpose of this procedure is to provide a repair program in conjunction with the Inservice Inspection Program at Virgil C.
Summer Nuclear Station. This program is implemented to fulfill the repair requirements of ASME Code,Section XI.
2.0 SCOPE' This procedure is applicable to all Station organizational '
elements responsible for conducting repairs under the ASME' Code,Section XI.
30 REFERENCES 31 10 CFR 50.55a 32 ASME Code Section III 1971 Edition through the Summer 1973 addenda for Code piping installation.
33 ASME Code Section III original Construction Code for valves, pumps, vessels and component supports.
( 3.4 ASME Code Section IX 35 ASME Code Section XI 1977 Edition through and including Summer 1978 addenda 36 Virgil C. Summer Nuclear Station Facility Operating License and Technical Specifications 37 South Carolina Electric and Gas Company Operational Quality Assurance Plan 38 SAP-145, Inservice Inspection Program
4.0 DEFINITIONS I
4.1 ASME Code - The ASME Boiler and Pressure Vessel Code,Section XI 1977 Edition through and including the Summer 1978 addenda.
l O PAGE 1 0F 8
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3 '~ 9 --.
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.i fQ..
SAP-304 O JEVISION =I
() 4.2 Authorized Inspection Agency .$nlinsurance . company 7'/12/82
~
authorized to write boiler and pressure vessel insurance ,
in the State of Sou'th C6rolina. t S e" J
, A clars'sification iof 11tems and component s' 4.3 Code Class based upon tne Section' CII Ccde subsection used La the construction of items.
- A. Class l'- Subsection NB B. Class 2 - Subsection NC .
C. Class 3 - Subsection ND 'l D. Class MC - Subsection NE 1 E. Components Supports - Subsection NF 4.4 Construct' ion - An all inclusive term requiring . materials, design, fabrication, examination, installation,' testing, inspection and certification be in accordance ydth the * '
applicable Section III Code.
45 Indication - An expressed stateoof condition detected by the specified non-destructive , examination method. (
4.6 Flaw - An indication requiring evaluation by qualified personnel. ~g
\
4.7 Rejectable Flaw - An evaluated indication of an item or component recuiring repair, rework, monitoring, an analysis or a combinar. ion ,thereof'., , s 4.8 Repair - Welding rework act,1viti'es, including initial and final finishin5 processe:3, 1-equired to return an item to a condition acceptable to the Code.
r :
i 49 Replacement' - The addition of spar'e component (s) parts of component (s), appurtenances, piping subassemblies, l
rerouted piping but not ,tne addition of new complete >
l systems.
J 4.10 REWORK - ' Repair or replacement activities or a combination thereof required to return an item to a condition s acceptable to the Cede.
4.11 Recordable Indication - Same as the definit' ion for' " Flaw" 1
?
s
' PAGE 2 CF 8 -
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SAP-304 REVISION 0 7/12/82 O,V 4.12 Rejectable Indication - Same as the definition for
" Rejectable Flaw".
50 RESPONSIBILITY 51 The Manager, V.C. Summer Nuclear Station has the overall responsibility for the implementation of the Section XI Repair, Rework and Replacement Program.
52 The Assistant Manager - Maintenance Services is responsible for implementing repair, rework and replacement activities.
53 The Director of Station Quality Control (DSQC) or his designated alternate is responsible for:
531 Directing required non-destructive examination (s) specified for the applicable repair, replacement or rework activity.
532 Directing the preparation of the required non-destructive examination reports and attaching such reports or copies of reports to the applicable Maintenance Work Request.
533 Promptly notifying the ISI Coordinator or ISI Coordinator designated alternate (s) of any rejectable indications detected during inservice inspection.
534 Preparation and approval of other required Quality Control Records and Documents.
535 Performing any needed additional examinations and investigations for resolution and disposition of examination results.
l l 5.3.6 Maintaining liaison with the ANII for any inspections required as a result of knplementation of IWA-4140 of the Code.
54 The Inservice Inspection Coordinator is responsible for:
5.4.1 Coordinating tho'se activities necessary to perform repairs needed as a result of rejectable ,
indications detected during Inservice Inspection.
5 4.2 Initiating and completing the appropriate sections of Attachments I and II.
PAGE 3 0F 8 i
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SAP-304 REVISION 0 7s 7/12/8r g
5.4.3 When copies of records are requested by the JRC submitting the " Record of Section XI Repair" packet to the Technical Services Coordinator.
55 The Welding Supervisor shall be responsible for:
551 Developing and maintaining a welding program that fulfills the requirements of the Code.
552 Selecting and assigning applicable Welding Procedure Specifications and qualified welders ~ to perform. the welding in accordance with the requirements of the program.
6.0 PROCEDURE 6.1 Welding to Cuda stamped items or components meeting all the requirements of ASME Section III Construction Code, including installation requirements , shall be performed in accordance with the requirements of SAP-302, WM-1, WM-2 and the applicable section of the Code.
6.2 Code rework or replacement activities not requiring welding shall be performed in accordance with approved
(, maintenance procedures for the applicable component or item except as noted in 6.12.2.
6.3 Welding to shop fabricated Code stamped items not meeting the requirements of ASME Section III installation requirements need not meet the requirements of IWA-4140.
6.4 The Maintenance Work Request shall be used to initiate any repair, rework or replacement activity.
6.5 The " Record of Section XI Repair", Attachment I shall be i
initiated and completed in accordance with Section 6.10 9 of this procedure.-
(
6.6 The "Index to Section XI Repair" shall be initiated and completed in accordance with Section 6.10.10 of this procedure.
6.7 code repairs resulting in only mechanical defect removal may be performed in accordance with WM-1.0 under the l
' control of the Q. C. Inspection Program and documented on an MWR.
6.8 Components identified as having recordable indicatione, firws or other defects may be " Accepted as Is" only after evaluation has been performed by qualified personnel.
t I
PAGE -4 0F 8
. . .. ,. . ~.
SAP-304 REVISION O 7/12/82 6.9 Prior to performing any Code welding the ANII will be contacted to establish inspection hold points as determined by applicable quality control procedures.- This contact may be made by telephone conversation. If contact cannot be established repair activities may proceed at the discretion of the ,DSQC af ter documenting on Attachment I the date and time the attempt was made. d..
.c : -
6.10 Documentation 6.10.1 Code repair, replacement or rework activities shall be initiated by completing ,the appropriate sections of the MWR in accordance with SAP-301.
6.10.2 Attachments I and II of this procedure shall be used to implement the applicable Code repair except as otherwise noted in paragraph 6.1 and 6.11.4.
6.10 3 SAP-302, WM-1.0 and WM-2.0 shall be used to control the Code repair activities.
6.10.4 Code replacement and rework activities may be implemented by completing the appropriate sections of Attachments I and II of this procedure.
/)
NJ i
6.10 5 When required by the MWR, safety tags shall tue issued, completed and attached to the appropriate equipment in accordance with SAP-201.
6.10.6 When required by the MWR, Radiation Work Permits will be iniciated, completed and posted in accordance with applicable Health Physics Procedures.
f 6.10 7 only qualified welders using applicable qualified Welding Procedure Specifications are to be used in performing Code Welding.
6.10.8 When required, a modification request form shall be initiated and completed in accordance with SAP-133 l
6.10 9 " Record Section XI Repair" Attachment I entries A.1 through A.5 are to be completed as follows:
A. Entry A.1 - Name and identification of the item.
I lO
- PAGE 5 OP 8 l
i
SAP-304-REVI,SION 7 12 82 O
(::) B.
Entry A.2 - Nature of problem or discrepancy l
of the item. ,
C. Entry A.3 - Method of detection of the discrepancy such as routine maintenance, type of NDE, hydrostatic test , ' leak test , etc.
Entry A.4 - When required, enter NCN #(s) for 4
D. ~
the item.
E. Entry A.5 - MWR #(s) for the applicable iten or component F. For entries A.1 through A.5 the ISI Coordinator or his designated alternate (s) shall verify entries are correct by affixing signature and date.
G. Entries B.1 through B.10 shall be checked or marked, as appropriate, for the type of repair, replacement, rework, etc. required for the described item. The Welding Supervisor or Maintenance Engineer, as applicable , shall l
affix signature and date to identify those required activities .
(
H. Entries C.1 through C.3 shall be checked, l marked and/or completed, as appropriate, when l
actual contact or an attempt to contact the ANII was made for establishing inspection hold points for welded repairs.
I. Entry D - May be used by any individual involved with the repair, replacement, etc. to record information which may be worthwhile or l
meaningful in the production, inspection or final review of the specified activity.
l K. Entries E.1 through E.5 - Review, approval and/or acceptance of described. activities by those titled personnel identified.
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9 SAP-304 REVISION 0 7/12/82 6.10.10 "Index to Section XI Repair", Attachment II, lines and columns shall be completed by those departments and individuals responsible for initiating any document to be attached to the
" Record of Section XI Repair".
6.11 Code Repair Activities 6.11.1 Code repair activities requiring welding shall be
' performed by welders qualified to use the applicable WPS's in accordance with the ,
requirements of WM-1.0.
6.11.2 Alterations and/or modifications evolving from changes to existing design specifications or new design specifications resulting in welding activities to a Code iten shall be initiated through as Engineering Change Notice or modification request form prepared in accordance with the requirements of the appropriate specifications, and controlled in accordance with SAP-133 and this procedure.
6.11 3 Repair activities required to return a code item to its original design condition shall be O performed in accordance with the original design specification and/or WM-1.0, as applicable.
NOTE': The ANII shall be notified in accordance with paragraph 6.9 of this procedure prior to performing any Code repair welding activities. -
6.11.4 Mechanical removal of defects without subse'quent welding may be performed under the scope of a l MWR.
6.12 Code Rework and Replacement Activities 6.12.1 Code rework and/or replacement activities not l requiring welding shall be performed in accordance with paragraph 6.2.
6.12.2 Alterations and/or modifications evolving from j changes to existing design specifications or new l
design specifications resulting in rework or replacement activities shall be initiated through an Engineering Change Notice or modification request form prepared in accordance with the requirements of such specifications and controlled in accordance with SAP-133 and this procedure.
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SAP-304 .
REVISION 0 7/12/82 6.12.3 Code rework and replacement activities involving welding shall be performed in accordance with 6.11 of this procedure.
6.13 Repair, Rework and Replacement' activities by external organization.
6.13 1 A contracted or subcontracted organization program shall either:
A. Meet the S.C .E. &G.Q . A. Program; or B. Have their Q. A. Program approved by S.C.E.&G.Q.A.
6.13 2 Contracted or subcontracted personnel requiring access to the site must meet the requirements of SAP-108.
70 FIGURES None
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8.0 RECORDS Records developed for this procedure are records of Section XI Repair Forms and the index to Section XI Repair Forms.
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SAP-304 ATTACHMENT I PAGE 1 of 1 O
REVISION 0 SECTION XI COVER SHEET RECORD OF SECTION XI REPAIR A. GENERAL
- 1. Item Description and I. D. No.:
- 2. Discrepancy:
3 Detection Method:
- 4. NCN #(s) 5 MWR #(s)
- 4. Welding 5 Mechanical Removal of Defect
- 6. Accept As Is Justification Attached
WELD. SUPV. OR MECH ENGR. DATE C. WELDING ACTIVITIES
- 1. ANII Contacted Telephone On-Site
- 2. Attempted Contact of ANII By Date/ Time Hold Points Established By Date 3
D S Q C OR DESIGNEE DATE D. REMARKS:
E. REVIEW, APPROVAL AND/OR ACCEPTANCE
- 1. 2.
DATE WELD. SUPV . CR MECH. ENGR. DATE MECH. SUPERVISOR 3
4.
ISI COORDINATOR DATE D S Q C OR DESIGNEE DATE 5 ACCEPTANCE:
-s ANII DATE
'v - ,
MWR SHEET OF
r >
1 SAP-304 -
ATTACHMENT II
!' PAGE 1 of 1 REVISION O SECTION XI
' SHEET OF INDEX TO SECTION XI REPAIR DATA .
MWR #(s)
" DOCUMENT TITLE PAGE NO. SIGNATURE & DATE Record of Section XI Repair 1 Index to Section XI Repair 2 i
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MWR SHEET OF
SOUTH CAROLINA ELECTRIC AND GAS COPJANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS s;
a STATION ADMINISTRATIVE PROCEDURE SAP-302 ADMINISTRATION OF MAINTENANCE WELDING REVISION O JULI 12, 1982 NON-CONTR0llED Reviewed by:
00PY '
Y bl.xMY0wa ?~/? El Date O p aATUR @f phis revision)
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ASST. MGR. MA'INTENANCE SERVICES Date Approved: -
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Date PLpAGER 8
/
i Date Issued: #
O REVEWED BY 3SRC N#"/% dd82-
w SAP-302 PAGE 1 REVISION O O 7/12/82 LIST OF EFFECTIVE PAGES PAGE REVISION i 0 11 0 1 0 2 0 0
3 4 0 0
5 6 0 7
0 8 0
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SAP-302 P AGE 11 REVISION O 7/12/82 TABLE OF CONTENTS PAGE List of Effective Pages i 1
1.0 PURPOSE 2.0 SCOPE 1 1
30 REFERENCES 4.0 DEFINITIONS 1 RESPONSIBILITY 2 50 .
6.0 PROCEDURE 3 FIGURES 8 70 8.0 RECORDS 8 O
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e SAP-302 REVISION 0 7/12/82 1.0 PURPOSE This procedure establishes the means for developing, implementing and maintaining the controls for the Maintenance Welding Program.
2.0 SCOPE This procedure is applicable to Station organizational elements which conduct maintenance welding or brazing. Unless otherwise noted throughout this procedure the terms " process", " procedure specifications" and " welder" apply equally to welding and brazing.
30 REFERENCES 31 10 CFR Part 50.55a.
32 10 CFR Part 50, Appendix B.
33 ASME Boiler and Pressure Vessel Code Section III 1971 Edition through Smnmer 1973 Addenda for code piping installation and original construction requirements. for O other code items.
ASME Boiler and Pressure Vessel Code,Section IX.
34 35 ASME Boiler and Pressure Vessel Code,Section XI 1977 Edition through Summer 1978 addenda.
3.6 Virgil C. Summer Nuclear Station Facility Operating License and Technical Specifications.
l 3.7 Virgil C. Summer Nuclear Station Final Safety Analysis Report.
38 ANSI B31.1 Piping Code 1967 Edition and Addenda through 1972.
39 knerican Welding Standard D1.1,1972 and revision through 1974.
3 10 South Carolina Electric and Gas Company Operational Quality Assurance Plan.
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s SAP-302 REVISION 0 7/12/82 3 11 SAP-103, Statement of Responsibilities, Maintenance Services.
3 12 SAP-301, Maintenance Work Request.
4.0 DEFINITIONS 4.1 ASME Code - An approved ANSI document published by the American Society of Mechanical Engineers including, but not limited to specific construction requirements, .
pre-service inspection requirements. and in-service inspection require.ments for certain classified pressure systems, components and their supports.
4.2 Authorized Nuclear Inservice Inspector ( ANII OR ANI) - An inspector employed by an insurance company authorized to
- write boiler and pressure vessel insurance and having qualified in accordance with the requirements of ANSI /ASME N626.1-1975 4.3 Brazing Procedure Specification (BPS) - A documented record of the brazing variables, both essential and non-essential, and proven applicable test or tests, and also the acceptable ranges of these variables. ,
(~~~}
V 4.4 Procedure Qualification Record (PQR) - A certified record of tne actual welding or brazing variables experienced during the qualification of a WPS.
4.5 Standard Qualification Test (SQT) - A specific welding or brazing test performed by a welder or brazer permitting that welder or brazer to use one or more WPS's or BPS's, respectively.
4.6 Welding Manual 1 (WM-1)'- A written approved document, although separate, complimentary to the Welding Procedure Specification or Brazing Procedure Specification, to be used in performing weld or braze testing, maintenance welding or brazing, and repair welding and brazing.
4.7 Welding Manual 2 (WM-2) - A written approved document to be used in the procurement, issuance and control of welding and brazing mat'erial.
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SAP-302 REVISION O 7/12/82 O
r 4.8 Welding Procedure Specification (WPS) - A documented record !
of the welding variables, both essential and l non-essential, and proven applicable test or tests and also the acceptable ranges of these variables.
l l
RESPONSIBILTY )
50 51 Through and under the di'ection r of the Assistant Manager, Maintenance Services, the Welding Supervisor is responsible for performing those activities necessary to "
establish, implement, control and maintain the Maintenance Welding Program. These activities include, but are not ;
~
i limited to, the training of welders, welding operators and the welding foreman; the appropriate origination, issuance, qualification, revision, control and application of the WPS's, PQR's and SQT's.and other correlating applicable documents and procedures in accordance with the applicable codes. In addition, the Welding Supervisor, in conjunction with the Materials Supervisor, has the responsibility for procurement, field issuance and control of any welding materials used in any welding processes on any code item, safety related system or component.
! 52 The Materials Supervisor or his designee, through and j
under the direction of the Assistant Manager, Maintenance Service and in conjunction with the Welding Supervisor or his designee has the responsibility for procurement, i
warehouse issuance and warehouse control of any materials to be used in any welding processes on any code item, safety-related system or non-safety related system or component.
i
' 53 The Director of Station Quality Control has the responsibility for verifying the required destructive testing and for performing non-destructive testing of welded coupons, production welds and repair welds.
54 Under the direction of the Welding Supervisor, the welding foreman has the responsibility to direct the on-location welding activities including, but not limited to, assisting in welder training and qualification and application of WPS's.
55 Under the direction of 'the Welding Supervisor and/or the welding foreman the welders and welding operators have the responsibility for reviewing, following and adhering to the requirements of the applicable WPS's, WM-1 and WM-2.
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SAP-302 REVISION 0 7/12/82 56 The Mechanical Supervisor has the responsibility for providing support to the Welding Supervisor and the Director of Station Quality Control in the processing of weld test specimens. These processing activities include, but are not limited to, fabrication of weld test booths, machining, grinding and preparation of pre weld and subsequent post weld specimens.
6.0 PROCEDURE 6.1 This procedure and the welding manuals, WM-1 and WM-2', are prepared to establish and implement uniform standard applicable to code, safety-related and non-safety-related requirements. Documentation and control requirements mandate the need for this program in order to perform plant welding activities. Such requirements reduce errors and subsequent equipment downtime and thus promote and sustain the required standard of quality.
6.2 Each welder, welding operator and welding foreman shall receive training in the application of the WPS(s) and the applicable portions of WM-1 and WM-2 prior to his performing code or safety-related welding activities.
O This training will consist of both classroom and
\J on-the-job instructions consistent and commensurate with their existing knowledge, experience and understanding of the welding process involved.
6.3 Welding material issue personnel shall receive training in the proper methods of storage, issuance, and proper disposition of returned used and unused welding electrodes. This training will be consistent with their knowledge, experience and understanding of material control requirements.
6.4 Semi-annually each welder, welding operator and the welding foreman shall receive instruction in the ASME Section IX Code Addenda changes which affect the Maintenance Welding Program.
65 Training exercises will be documented in accordance with WM-1 and/or WM-2 as applicable.
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l SAP-302 REVISION O A 7/12/82
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6.6 Documentation 6.6.1 Initiation, origination, revision and approval of this procedure, WM-1, WM-2, and WPS's shall be in accordance with SAP-139. PQR's and SQT's shall be rev-iewed and approved in accordance with this procedure. WPS's and PQR's shall be reviewed by Quality Assurance and Quality Control prior to issuance. SQT's shall be reviewed by Quality Control pr;ce to issuance. WPS's, PQR's and SQT's shall be approved by the Assistant Manager, Maintenence Services prior to issuance.
6.6.2 WPS's, PQR's, and SQT's, are Station Records and shall be handled in accordance with SAP-150.
Copies of the latest revision to WPS's, PQR's and SQT's shall be maintained under the direction of Welding Supervisor.
6.6.3 The Maintenance Work Request (MWR), issued to initiate welding activities, shall be completed and filed in accordance with SAP-301.
6.6.4 When required by the MWR, a Radiation Work Permit will be initiated and completed in accordanca.with j (_, Health Physics Procedures.
6.6.5 When required by the MWR, safety tags shall be issued, completed, attached to appropriate equipment and filed in accordance with SAP-201.
6 . 6'. 6 When required as noted in 6.8.6, a Modification Request Package shall be initiated and completed in accordance with SAP-133 6.6.7 The weld traveler and the welder performance continuity record shall be issued, completed and filed in accordance with WM-1. These documents are described in WM-1.
I i 6.6.8 The welding material receiving record, holding oven I temperature record, welding material requisition record, and the portable caddie temperature
' verification rec,ord shall be issued, completed and filed in accordance with WM-2. These documents are -
described in WM-2.
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9 SAP-302 REVISION O
(-w 7/12/82 g
6.7 Material control 6.7.1 Welding and brazing material used in welding and brazing activities shall be procured, received, issued and controlled in accordance with WM-2. In
~
addition procured and received welding and brazing material shall meet the requirements of the applicable purchase requisition.
The Welding Supervisor or his designated alternate
' 6.7 2 will complete and submit a' purchase requisition. for approval in accordance with SAP-137 for brazing and welding material.
6.7.3 Any non-conforming welding material, brazing material or any item in which non-conforming welding or brazing material was used will be tagged and, if practicable, segregated as such and resolved as required by A-NQCP-2.
6.7 4 Radioactive contaminated welding or brazing material shall either be decontaminated and returned to the storage area for reuse or discarded in accordance with Health Physics Procedures.
6.7.5 Welding and brazing material issus personnel shall receive re-training annually or within 30 days of a new revision to WM-2.
6.8 Welding and Brazing Activities 6.8.1 Safety related and code welding or brazing shall be performed by welders / welding operators or beazers qualified to use the applicable WP3(s) or BPS (s) respectively, in accordance with WM-1.
6.8.2 Only applicable qualified WPS(s) or BFS(s) supported by one or more referenced PQR(s) shall be used in performing safety-related or code welding and brazing.
6.8.3 Any welder / welding operator or brazer determined to be lacking in the ability to produce the required weldment or brazed joint, respectively, shall have his qualification revoked in accordance with WM-1.
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SAP-302 REVISION 0
(, 7/12/82 6.8.4 Any WPS(s) or BPS (s) determined to be lacking in the required characteristics (e.g. material) to produce the required weldment or brazed joint, respectively, shall have its qualification revoked in accordance with WM-1.
6.8.5 Requalification and renewal of qualification, if required, of welder / welding operators, welding foreman, WPS(s), and BPS (s) shall be in accordance with WM-1. ,
6.8.6 Modifications or alterations evolving from changes to existing design specifications or new design specifications.resulting in welding activities to a Code or safety-related items shall be performed in accordance with the requirements of such specifications, and shall be in accordance with SAP-133 and this procedure.
Welding activities, including weld repairs, required to return a Code or safety-related item to its original design condition shall be performed in accordance with the original design specification and/or WM-1, as applicable.
6.8.7 Upon receiving or initiating an appropriate Maintenance Work Request the Welding Supervisor or his designated alternate (s) will initiate a weld or brazing traveler, select the applicable WPS(s) or BPS (s), welders or brazers respectively, to perform che code or safety-related welding or brazing activity respectively.
6.8.8 Af ter the weld traveler or brazing traveler has been initiated and any required ASME Section XI Code documentation has been initiated, the welding or brazing activity may start under the direction of the Welding Supervisor or his designated alternate.
The ANII wil'1 be notified of all ASME Section XI 6.8.9 Code welding or brazing activities in accordance with SAP-304.
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SAP-302 REVISION 0
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7/12/82 6.8.10 After the welding or brazing has been completed, the required NDE has been performed and accepted, and the hydrostatic test, the pnuematic test, or hydrostatic-pneumatic test if required, has been completed and accepted in accordance with the applicable Mechanical Maintenance Procedur'e and the modification, if required, has been closed, the documentation shall be filed in accordance with SAP-150.
6.9 Welding By External Organizations (Subcontractors) 6.9 1 A subcontracting organizations welding program shall either:
A. Meet the requirements of the Operational Quality Assurance Plan or B. Have their own Quality Assurance Program approved by the Manager, Quality Assurance.
6.9 2 All dochments related to ASME Section XI Code welding or brazirg activities shall be made '
available to the ANII for his review.
6.10 Authorized Nuclear Inservice Inspector .
) 6.10.1 The Authorized Nuclear Inservice Inspector is responsible for performing his duties in accordance '
with the referenced ASME Section XI Code.
6.10.2 The interface to be maintained for ASME Section XI Code welding activities with the ANII is specified in procedure SAP-304.
70 FIGURES l None i
8.0 RECORDS
- Records generated in accordance with this procedure are identified in Section 6.6.1.
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SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS WELDING MANUAL PROCEDURE WM-1.0 REVISION 2 JUNE 8, 1982 o NON-00NEDLLFD " SAFETY RELATED
~
COPY D-__ . fh /4 F b Date "0RIGINACOR (of this revision)
/ $ l0*N'f Date QUALIFIED REVIEWER Approved:
k & _ /u - 2 1 - f 2.
ASSIST. MGR4 MAINTENANCE SERVICES Date OCT 2 9 $@
Date Issued:
For:: AP-101-2 (1/80)
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, . - - . , y ---.- - - - - . - - - -
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- ,: ye WM-1.0 PAGE i REVISION 2 6/8/82 .
LIST OF EFFECTIVE PAGES PAGE REVISION i 2 11 2 til 2 iv 2 v 2 vi 2 vii 2 1 2
.2 2 3 2 4 2 5 2 6 2 7 2 8 2 9 2 10 2 11 2 12 2 13 Fi".' ~ ~ '7 f"$"f % j'-j [1
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14 15
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16 2 ' .D 17 ' _.J,7 p gi ) ?? 2 18 4 2
19 N y j ', , 2 20 2 21- 2 22 2 23 2 24 2 25 2 l
26 2 27 2 28 2
-- 29 2 _
30 2 i 31 2 '
32 2 33 2 34 2 35 2 36 2 2
l 37 38 . 2 2
39 0
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WM-1.0 PAGE 11 REVISION 2 O .
6/8/82
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LIST OF EFFECTIVE PAGES (con't)
PAGE REVISION
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40 2 41 2 42 2 43 2 44 2 45 2 46 2 47 2 48 2 49 2 50 2 51 2 52 2 53 2 54 2 55 2 i
56 2 57 2 58 2 59 ,
2 60 2 O- 61' 2 2
, 62 l 63 2 .
64 2 65 2 66 2 67 2 ATTACHMENTS Attachment I, Pages 1 and 2 2 l Attachment II 2 Attachment III, Pages 1 and 2 2 l Attachment III-A, Pa6es 1 and 2 2 Attachment IV, Pages 1 and 2 2 Attachment V 2 Attachment VI 2 Attachment VII 2 I Attachment VIII 2 Attachment II 2 O
. . t WM-1.0 PAGE 111 REVISION 2 6/8/82 TABLE OF CONTENTS PAGE 1.0 Purpose or Scope 1 2.0 References and Glossary 1 2.1 References 1 2.2 Glossary = 2 30 Responsibilities 6 4.0 General (Training) 6 50 Procedure 7 51 Qualification of WPS's and EPS's 7 52 Procedure Qualification Tests (ASME Section III and Section IX Codes) 9 53 Welding and Brazing Standard Qualification Tests (ASME Section III and Section II Codes) 11 _
~.s 54 Procedure Qualification Tests (AWS Dl.1 Safety ,
Related) 15 55 Welding Standard Qualification Tests ( AWS Dl.1 Safety Related) . 15 56 PQR and SQT Acceptance Criteria 16 57 Documentation of Welding Activities 18 5.8 Materials 24
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WM-1.0 PAGE iv REVISION 2 O .
6/8/82 TABLE OF CONTENTS PAGE 59 Welding Activities 24 5 9.1 Base Metal Preparation 25 592 Fitup of Butt Joints 26
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593 Pitup of Socket Joints , 27 594 Backing Rings 28 595 consunable Inserts 29 5.9.6 Shielding and Purging Gas 29 597 Preheat and Interpass Temperature 30 5 9.8 Tack Welds 43 5.9 9 Welding operations 43 5.9 10 Interpass cleaning -
45
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5911 Finished Weld Surfaces 46 5 10 Brazing Activities 49 5 10.1 Base Metal Preparation 49 5 10.2 F1 tup of Brazed Joints 49 5 10 3 Backing Rings 49 5 10.4 Brazing Temperature, Flux and Atmosphere 50 5 10.5 Brazing Applications 50 j 5 10.6 Brazing operations 50 0
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- .. 2 WM-1.0 PAGE v REVISION 2 10/8/81 TABLE OF CONTENTS PAGE 5 11 Repair of Weld Metal Defects (ASME Section III) 51 5 12 Weld Repair of Base Metal Defects (ASME Section III) 52 5 13 Repair of Weld Metal and Base Metal Defects
( ANSI B31.1 and AWS D1.1) 53 5.14 Defect Removal and Cavity Preparation of Weld Metal and Base Metal 53 5.15 Post Weld Heat Treatment 54 5.15 1 ASME Section III Class 1, 2 and 3 Components 54 5 15.2 ASME Section III Class MC 55 5.15 3 ASME Seccicn III Component Supports 55 5 15.4 Post Weld Heat Treatment of Other ,
ASME Section III Items 55 5 16 ASME section III Post Weld Heat Treatment Time, Temperature and Process Activities 55 5.17 ANSI B31.1 Post Weld Heat Treatment Requirements, Time, Temperature and Process Ac'ivities 57 5 18 AWS D1.1 Post Weld Heat Treatment Requirements 64 5 19 Post Braze Heat Treatment 64 5 20 Non-Destructive Examination 64 5 21 Removal of Welded Items Not To Be Reinstalled or Replaced 65 5.22 Calibration O
r .
WM-1.0 PAGE vi REVISION 2
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10/8/81 TABLE OF CONTENTS PAGE Figures 5.9 3-A(a) Dimensions for F1 tup of Socket Joints 29 5 9.7-D(a-d)
Preheat ar.d Interpass Te=perature, .
ASME Section III Items Not Listed in 5 9 7-A, -B o r -C 35 - 38 5 9 7-F(a) Preheat and Interpass Temperature, ANSI B31.1 It' ems Not Listed in 5 9 7-E 39 5 9.7-H(a-b) Minimum Preheat and Interpass Temperature, AWS Dl.1 (Items Not Listed in 5 9 7-G) 42 - 43 5 9 113 Minimum Welding Dimensions for Slip-On and j Socket Joints 50 5.15 4-A(a-d) Exemptions to Mandatory PWET 60 - 63 5.16.1( a) ASME Section III PWRT Minimum Holding Time ,
64 ..
5 17.1(a) ANSI 331.1 F#ET Requirements 65 i
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. , i WM-1.0 PAGE vii REVISION 2 10/8/81 TABLE OF CONTENTS Attachments Attachment I Welding Procedure Specification (WPS)
Attachment II Brazing Procedure Specification (SPS)
Attachment III Welding Procedure Qualification Record (PQR)
Attachment IIIA Brazing Procedure Qualification Record (PQR)
Attachment IV Welding Standard Qualification Record (SQT)
Attachment V Welder Performance Continuity Record Attachment VI Weld Traveler Attachment VII Brazer Standard Qualification Record (SQT)
Attachment _ VIII Training Exercise Record Attachment IX Brazing Traveler O
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. REVISION 2 '
6/8/82
"(
1.0 PURPCSE!OR SCOPE , , j 1.1 This procedure p,covides the necessary rules for controlling i welding and brazing activities, thus er.suring the requirements have been met for code, safety-related, and non-safety related components, equipment structures, and piping systems installed in the plant or to be' installed in the plant.
2.0, REFERENCES AND GLOSSARY 2.1 References.
I 2.1.1 Administration of Maintenance Welding SAP-302 and latest approved revision. e ,
2.1.2 Control and Calibration of Measuring and Test Equipment l SAP-141 and latest: app' roved revision.
2.1.3 Guidance for Documenta ion of Plant Staff Training-AP-1101jind latest approved revision. ,
2.1.4 Qualific.ation and Certification of Quality Control Inspection Personnel A-NQCP-8 and latest approved revision.
2.1.5 Solvent Removable Liquid Penetrant Examination T-NQCP-2
~-
and latest approved revision. ,
2.1.6 WaterWashable'orPobtEmuldifiableLiquidPenetrant 3-Examination T-NQCP-3 and latest approved revision.
2.1.7 Eigh Temperature Liquid Penetrant Examination T-NQCP-4 '
i and latest approved revision.
2.1.8 Magnetic Particle Examination for Prod and Coil Methods ~
T-NQCP-5 and latest approved revision. ,
2.1 9 Magnetic Particle Examinetion for-Yoke Method T-NQCP-6
\ q and latest approved reg'ision.
2.1.10 Visual Examination Serier T-NQCP-7 and latest approved. .o revision. 1
') ,
p 2.1.11 Eddy Current Examination of Steam Generator Tubing T-NQCP-8 and latest approved revision. ,[ '
2.1.12 Radiographic Inspection T-NQCP-9 and latest approved revision.
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PAGE 1 CP 67
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WM-1.0 REVISION 2 6/8/82 2.1.13 Qualification of Welders and Welding Procedures ,
T-NQCP-il and latest approved revision.
2.2 Glossary.
2.2.1 Arc Welding-a group of welding processes wherein coalescence is produced by heating with an electric arc or arcs, with or without the application of pressure and with or without the use of filler metal.
A. Gas Metal-Arc Welding - (GMAW) (MIG) Coalescence produced by heating with an electric are between a consumable metal electrode and the base material.
Sheilding is obtained from an inert gas and/or a flux core.
B. Gas Tungs ten-Arc Welding - (GTAW) (TIG) Coalescence produced by heating with an arc between a single non-consumable tungsten electrode and the base material. Shielding is obtained frem a gas or a gas mixture, and filler metal shall be used.
C. Shielded Metal-Arc Welding-(SMAW) Coalescence produced by heating with an are between a consumable covered metal electrode and the base =aterial.
Sheilding is obtained from decomposition of the electrode covering and filler metal is obtained from-the electrode.
2.2.2 Brazing-A metal joining process wherein coalescence is produced by the use of a non-ferrous filler metal having a melting point above 800*F but lower than that of the base metals joined. The filler metal is distributed between the closely fitted surfaces by capillary action.
2.2 3 Brazing Flow Position-The orientation of the brazed joint with respect to the planes of the work piece.
A. Flat flow-Work pieces mated horizontally with filler metal flowing between two flat surfaces.
B. Horizontal flow-Work pieces mated vertically wih the filler metal flowing horizontally between the two surfaces.
C. Vertical Upflow-Work pieces mated vertically with the filler metal flowing vertically uphill.
PAGE 2 CP 67 9
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' REVISIOff 2 6/8/82
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2.2.4 Capillary Action-The force of attraction between two closely mated solid surfaces and a liquid.
2.2.5 Cladding-Deposition of fill'er =etal ento a metal to obtain different desired chemical or physical properties from the original metal.
2.2.6 ft11er Metal-The metal to be added in a wolded or brazed joint or surface deposition.
2.2.7 Fillet Weld-A weld of approximately triangular cross-section joining two surfaces approximately at right angles to each other in a lap joint, tee joint, or corner joint.
2.2.8 Groove Weld-A weld made in a groove between two members to be joined. .
2.2 9 Groove eld Position-lG through 6G and 6GR as described.
A. 1G-Work piece in horizontal plane with the weld metal deposited from above.
B. 20-Work piece in vertical plane with axis of weld horizontal.
C. 30-Work piece in vertical plane with axis of weld vertical.
i D. 4G-Work piece in horizontal plane with the . weld metal deposited from underneath.
E. 50-Pipe with its axis horizontal with the welding groove in a vertical plane.
F. 6G-Pipe with its axis inclined at 45 degrees.
Welding performed without rotating the pipe.
G. 60R-Pipe with its axis inclined at 45 degrees, with an installed restriction located 1/2" on the upper side of the groove.- ~
2.2.10 Inspection Point-A point during welding or brazing operations at which verification for the welding or brazing activities is performed, s
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. , s WM-1.0 REVISION 2 6/8/82 A. Hold Point-A previously selected inspection point beyond which the operation cannot proceed until
- verification of the activity has been performed by authorized personnel.
B. Witness Point-A previously selected inspection point beyond which the operation cannot proceed without authorisation by the Quality Control Inspection Coordinator, or his designated alternate or the ANII, as applicable.
2.2.11 Indication-An expression of the state of the condition.
'A . Linear Indication-An indication in which the length l 13 more than 3 times the width.
B. Rcunded Indication-An indication which is circular or l elliptical with the length 3 times the width or less.
2.2.12 Notch Toughness Testa-A test or group of tests performed in which a metal spectnen is destructively examined to
~
determine its suitability for operation at various load and temperature conditions.
2.2.13 Preheat Temperature-The specified temperature which the base metal must attain in a welding, bracing or ther=al cutting operation immediately before these operations are performed.
2.2.14 Post Weld Heat Treatment-The application of heat at a predetermined temperature to a metal section subsequent l to a welding operation in order to relieve a major portion of the residual stresses.
2.2.15 Variables-A change in the characteristics which would i either effect or not effect the quality of the intended i use of the weld or braze joint.
A. Essential Variable-A change requiring requalification of a WPS or BPS. ,
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6/8/82 Non-essential Variable - A chan'ge which does not require requalification of a WPS or BPS.
C. Supplementary Essential Variable - A change requiring requalifiestien of a WPS cnly when notch toughness test properties are required for a particular application.
2.2.16 WPS Designation Definitions and/or abbreviations.
A. Gas Tungsten Arc Welding-GT i B. Shielded Metal Arc Welding-SM C. Gas Metal Arc Welding-GM D. P-Number Grouping-a distinctive group of base materials identified by ASME Section II Code as ha71ng compatible physical and chemical properties for specified welding applications.
- E. Basic weld Joint
- Types .
0-Open Butt 0-Backing ring, strip on tape O B-Backing ring, strip on tape
_C-Consumable Insert i
F. F-Number Grouping-a distinctive group of Welding .
filler metals and/or electrodes identified by ASME Section II Code as having bas'c fundamental usability characteristics in the qualification of welders and procedures.
G. A-Number Grouping-a distinct classification of ferrous weld metal chemical analysis for procedure qualification as identified by ASME Section IX Code.
H. Basic Thickness Application-Two specified ranges defined as follows:
- 1. LIGHTWALL (L)-up to and including 3/4" thickness, however, within the limits of the applicable WPS.
- 2. HEAVYWALL (H)-From 3/16" or greater to that maximum thickness limit (s) specified on the WPS.
I. Impact Properties (I) - Notch toughness tests such as charpy V-notch or drop weight tests specified by the code or its references.
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.. t WM-1.0 REVISION 2 6/8/82 J. Post Weld Heat Treatment (?)-If required by the WPS application -
30 RESPONSI3ILITIES 3.1 Procedure SAP-302 establishes, describes and delineates the responsibilities associated with the Maintenance Welding Program.
4.0 GENERAL (TRAINING) 4.1 Ample on-the-job training and classroom instruction shall be provided to all welders and brazers in order to improve the understanding of processes, grooming techniques and to emphasize safety and material control requirements.
4.2 Prior to his becoming qualified, each welder / welding operator and brazer will be instructed in the proper application of this procedure and the appropriate WPS(S).
4.3 For his appropriate qualified welding or brazing processes, each welder or brazer will be permitted to perform a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> nf welding per 90 calendar days or a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of bracing per 180 calendar days to maintain continuity of welding or brazing and quality craf tsmanship. Should his qualification lapse, renewal shall be in accordance witi Section 5.0 of this manual.
4.4 When the welder's or brazer's qualificatica has been revoked in accordance with this procedure and the cause can be justifiably corrected, retraining shall be provided. This retraining shall be in accordance with Sectio,n 5.0 of this manual.
4.5 Welding activity safety classes will be held monthly for the welders, brazers and those personnel involved with pre-weld or post-weld activities consistent and commensurate with previous training and experience.
4.6 Welding evolutions such as " Limited Position" and/or " Limited Space" may require mock-up training in order to improve craf tsmanship,' reduce radiation exposure and work costs ,
emphasize safety, and minimize rework or repairs.
4.7 Personnel assisting the welders or brazers will receive instruction in the applicable sections and subsections of this manual which affect the pre-weld and post-weld activities prior to their being used in such activities.
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. 6/8/82 4.8 Training exercises will be documented in accordance with AP-Il01 .
and Attachment VIII of this manual.
50 PROCEDURE 5.1 Quali,fication of WPS's and BPS's.
5.1.1 WPS or BPS qualific~ations are performed to ensure the required properties of the WPS or BPS, respectively, are reproduced during the application of its intended use.
5.1.2 The WPS or BPS, Attachments I and il respectively, shall be presented in either tabular or written form and shall describe in detail all the variables which are essential, supplementary essential (when required), and non-essential to the wel'iing processes employed.
5.1 3 Changes may be made La the non-essential variables to suit production requirements without requalification of the procedure, provided such changes are documented either in an amendment to the original WPS or BPS, or a new WPS or BPS. Non-essential variable changes documented on an existing WPS or BPS shall be included as a revision to the WPS or BPS respectively.
O, 5 1.4 All W?S(s) or BPS (s)'shall be supported by one or more PQR(s), Attachment III and IIIA, and vice versa.
5 1.5 WPS(s) or BPS (s) shall be requalified and the test results recorded on a separate PQR whenever there is to be a change in an essentia1' variable.
5 1.6 Requalification of revoked WPS(s) or BPS (s) shall follow the same format as original qualifications. However, code interpretations, code cases, and/or currently developed methods and techniques may be used.for requalification.
5.1 7 Essential variables shall be indicated on the WPS(s) or BPS (s) with the upper case letter "E" used as a prefix to the applicable essential variable. For supplementary essential variables an asterisk shall be used to identify the applicable variable (s).
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WM-1.0 REVISION 2 6/8/82 5.1.8 The WPS designation will generally take the form of - I either 8, 9, 12 or 13 alpha-numerical digits. However, the number of digits may vary using the same logi'c described herein.
A. 8 Digit Desi natioqs
- 1. The first two digits identify the process.
- 2. The third and fourth digits identify the P-Number grouping of the base materials being joined.
- 3. The fif th digit identifies the basic type of weld joint.
- 4. The sixth and seventh digits identify the welding electrode F-Number grouping and A-Number grouping respectively.
- 5. The eighth digit identifies the basic thickness application.
B. 9 Digit Designations
- 1. The first eight digits are as defined in 5.1.8 (A).
- 2. The ninth digit identifies whether PWHT is '
required for the intended application.
C. 12 Digit Designations
- 1. The first two digits identify the process to be used first during the welding activity.
- 2. The third and fourth digits identify the second process to be used during the velding activity.
- 3. The fif th and sixth digits identify the P-Number grouping of the base materials being joined.
- 4. The seventh digit identifies the basic type of weld joint.
- 5. The eighth and tenth digits identify the F-Number grouping of the welding electrodes for each of the two welding processes.
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(_ / The ninth and eleventh digits identify the
- 6. _
A-Number grouping of the welding electrodes for-each of the two welding processes.
7 Th[etwelfthdigitidentifiesthebasicthickness application.
D. 13 Digit Designation
- 1. The first twelve digits are as defined in 5 1.8 ,
(C). i
- 2. The thirteenth digit identifies whether PWET is required for the intended. application.
519 A copy of the WPS(s) or BPS (s) shall be available to the welder / welding operator or brazer, respectively, for reference during any code or safety related welding activity.
52 Procedure Qualification Tests (ASME Section III and Section IX Codes).
5 2.1 The type and ncaber of test specimens which must be 7s tested to qualify a WPS or BPS shall be removed and
- tested in accordance with ASME Section II Code, and, if
\~ ') applicable, ASME Section III Code. The procedure qualification testa shall encompass the thickness ranges to be used in production for the base metals to be joined or repaired. Essential variables are specified in both ASME Section III and Section IX Code.
5 2.2 Except for vessels or parts of vessels constructed of P-NO.11 (excluding F-NO. IlA GR.1 and 2) metals, WPS qualification tests shall qualify the WPS for use with groove welds within the range of the eescatial variables listed and shall also qualify for use with fillet welds in all thicknesses of metal, sizes of fillet welds, and diameters of pipe or tube within the limits of the other remaining essential variables.
523 Qualification of a BPS in the flat-flow, vertical-upflow, and horizontal-flow shall also qualify for the vertical-downflow position. A special orientation flow shall qualify only for that flow position.
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WM-1.0 REVISION 2 6/8/82 5 2.4 For Gas Metal Arc Welding, Shielded Metal Arc Welding, and Gas Tungsten Arc Welding processes, the position of
'T the test specimen shall be a supplementary essential variable 'when changing from any position to the
. vertical-uphill position.
5.2 5 Except as otherwise specified by ASME Section III Code and in 5 2.4 above, a WPS(s) qualification in any position qualifies the WPS(s) for all positions.
5 2.6 Qualification of the BPS in pipe also qualifies for plate, but not vice versa.
5 2.7 WPS(s) qualified on groeve welds shall be also applicefale for weld repairs to groove and fillet welds and for weld buildup under the following provisions:
A. There is no it:1tation on the minimum depth of deposited weld metal; B. The upper limit for base metal thickness shall be in accordance with the WPS; C. Qualification on 1 1/2" thickness or greater base metal shall also qualify to permit welding on unlimited thickness; D. The other remaining essential variables of the WPS are in accordance with ASME Section III Code and ASME Section II Code.
E. Cavity preparation shall be in accordance with 5 14.
5 2.8 WPS(s) qualified on groove welds shall be applicable for production welds between different base catal thicknesses provided:
A. The thickness of the thinner joint be within the range permitted by the WPS; B. The thickness of the thicker member be within the range permitted by the WPS; C. There is no limitation on the maximum thickness of the thicker member, providing qualification was made on base metal having a thickness of 1 1/2" or more; O
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WM-1.0 REVISION 2
!m i 6/8/82 V D. More than one PQR =ay' be ' required to qualify for some
- different thickness combinations; E. The other remaining essential variables of the WPS are in accordance with ASME Section III and Section IX Codes.
5 2.9 WPS qualification tests for stud welds shall be conducted in accordance with ASME Section III and Section IX -
Codes.
5 2.10 WPS qualification tests for corrosion wel'd.=etal overlay, hard surfacing, specially designed welded seals, and tube-to-tubesheet welds shall be conducted in accordance with ASME Section III and Section IX Codes.
- 5 2.11 BPS processes and the brazing filler materials must be compatible and suitable, respectively, for their use in specific flow positions and shall be in accordance with ASME Section III and Section IX Codes.
5 2.12 The BPS test coupon *shall be brazed using the joint design details specified in the captioned BPS.
Welding and Brazing Standard Qualification Tests (ASME Section I'} 5.3 III and Section IX Codes).
5 3.1 The welding or brazing SQT(s) are intended to determine the ability of the welders / welding operators or brazers / brazing operators to make sound welds or brazed joints, respectively, within the limits of the applicable essential variables.
5.3 2 A welder / welding operator or brazor/ brazing operator shall be qualified to the process following the applicable WPS or BPS, roepectively, during the qualification test. The results of welder's/ welding operator's or brazer's/ brazing operator's qualification test shall be recorded on the SQT forms, Attachments IV and VII, respectively.
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.' 'l WM-1.0 REVISION 2 6/8/82 5.3.3 A welder / welding operator or brazer / bracing operator performing the welding or brazing to qualify the WPS or )
SPS, respectively, is also qualified to perform welding .-
or brazing using that WPS or BPS, respectively.
However,the braser/ bracing operator using the BPS is qualified for that position only. The results of these welding or brazing tests shall also be recorded on Attachments IV and VII, respectively.
5.3.4 The type and number of test specimens for welded and braced joint testing shall be removed and tested in accordance witn ASME Seccion IX Code and, when required, ASME Section III Code.
5.3.5 Brazing SQT on plate in the flat-flow, vertical-upflow, or horizontal-flow positions shall qualify for the vertical-downflow position. Bracing SQT on pipe position shall qualify for plate positions, but not vice versa.
5.3 6 Within the limits specified by ASME Section IX Code, the welder's/ welding operator's test specimens shall be inspected in accordance ,with T-NQCP-11.
537 Groove weld SQT both in the 20 and 50 position, or in the 60 position, shall qualify for all positions, except as specified by paragraph 5.3.8.
5 3.8 A welder / welding operator or brazer / brazing operator ;.
qualified to weld or brace, respectively, in accordance --
with one qualified WPS or BPS is also qualified to weld or braze in accordance with other qualified WPS(s) or BPS (s), respectively, using the same welding or brazing process, respectively, within the limits of the essential variables specified by ASME Section III and Section IX Codes, except for the stud welding and electron beam welding processes. This objective evidence shall be recorded on the SQT forms, Attachments IV and VIII, respectively.
5.3 9 Welders / welding operators, who pass the tests for groove welds, shall also be qualified to make fillet welds of any size on base metals in all thicknesses and pipe diameters within the limits of other essential variables for that process.
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WM-1.0 RE7ISION 2
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< 5 3 10 Stud welding qualification in the 45 position also qualifies for the 13 position. Qualification in the 45 position and 2S position qualifies for all positions.
l l 5.3.'11 A special orientation position qualification test for 4 welding or brazing by a welder / welding operator or brazer / brazing operator, respectively, shall qualify only for that position.
5 312 When the welder / welding operator or brazer / brazing operator has not used th'e specific process for a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per 90 calendar days or a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per 180 calendar days, respectively, except when employed
- on some other process for a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per 90 calendar days or a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per 180 cal'endar
5 313 At the discretion of the . Welding Supervisor, a welder / welding operator or brazer / brazing operator, who fails his test, may be retested under the following
() _
provisions:
A. An immediate retest may be conducted and the ~
f welder / welding operator or brazer / brazing operator ,
shall make two test specimens for each test he failed or; B. The welder / welding operator or brazer / brazing
, operator may be given a minimum of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> additional training. Upon. completion of the training the l welder / welding operator or brazer / brazing operator shall repeat each test previously failed.
5 314 When the welding supervisor has specific reason to question the welder's/ welding operator's or brazer's/ brazing operator's ability to make welds or _
brazed joints, respectively, that meet the requirements, requalification of that welder / welding operator or brazer / brazing operator for the applicable processes is required prior to his performing welding or brazing activities on code or safety-related items. The welding l
supervisor may consult with Quality Control prior to making this decision.
PAGE 13 0F 67
WM-1.0 REVISION 2 6/8/82 5.3.15 A welder's/ welding operator's or brazer's/ brazing operator's renewal of qualification for a specific process, under paragraph 5.3.12, =ay be made in only a single test joint, plate or. pipe. The welding may be accomplished on any thickness, position, or material to reestablish the welder's/ welding operator's qualification for any thickness, position or material for which he was previously qualified. The brazing may be accomplished using any one of the brazer's/ brazing operator's previous qualification test joints utilizing all of the essential variables of the previous qualification. A minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of welding or 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of brazing, including practice or training, to reestablish the welding or brazing qualifications is required. This brazing activity will reestablish the brazer's/ brazing operator's qualification for all conditions for which he had previously qualified with the specific brazing process.
NOTE: If at any time during the. welder's/ brazer's qualification testing or production welding / brazing a qualified Certified Quality Control Welding Inspector determines a welder / welding operator's or brazer / brazing operator's performance to be unacceptable, the inspector has the authority to suspend further testing or request _
revocation of his certifications, respectively. In the case of qualification testing, resumption of test shall be in accordance with 5.3.13 of this procedure.
l 5 3.16 Requalification for a specific welding or brazing process:, under paragraph 5.3.14, shall meet the same requirements as the original qualification.
5.3 17 A record of the welder's/ welding operator's or brazer's/ brazing operator's work shall be kept on the applicable weld or bracing traveler, and, when permitted, welders or brazers may use assigned low stress stamps or etching devices to identify their respective welding or brazing activities.
NOTE: Stamping on ferrous materials 1/4" thick and less and on non-ferrous materials 1/2" thick and less is not permitted.
5.3.18 A record of assigned stamp number and/or symbols shall be maintained by the Welding Supervisor, or his designated alternate, on Attachment V.
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WM-1.0 REVISION 2 6/8/82
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5 3 19 Upon evaltation of circumstances as determined. by the Welding Supervisor, a welder / welding operator or brazer / brazing operator, who has a 10% or more reject rate, may be required to requalify to those processes for which the rejection criteria is applicable.
5.4 Procedure Qualification Tests (AWS Dl.1 Safety-Related).
5.4.1 The type and number of test specimens, if required, shall be removed and tected in accordance with AWS D1.1 Code.
5.4.2 Unless otherwise specified by this procedure, ASME Section IX Code qualified WPS(s) may be used fo'r AWS Dl.1 applications.
5 4.3 There shall be no Gas Tungsten Arc Welding processes or GTAW WPS's used for AWS D1.1 applications. Only Shielded Metal Arc Welding processes may be used for AWS Dl.1 applications.
5 4.4 The Welding Supervisor shall select the ASME Section IX Code qualified WPS(s) to be used for each AWS D1.1 application. These Section IX Code qualified WPS(s) shall conform to AWS Dl.1 code requirements.
55 Welding Standard Qualification Tests ( AWS Dl.1 Safety-Related) .
I 551 All welders / welding operators to be employed for this application shall have been qualified in accordance with AWS Dl.1 Code.
552 A welder / welding operatoc who makes a ecmplete joint penetration groove weld pipe procedure qualification test, without backing strip, that meets the requirements is thereby qualified for that process. However, the j following provisions shall apply:
A. Qualification on 6" diameter schedule 80 or 8" diameter schedule 120 pipe shall qualify for all thicknesses; B. Qualification on 6" diameter schedule 80 or 8" diameter schedule 120 pipe shall qualify for 4" diameter and over; C. Qualification on 4" dia=eter or less shall qualify for 3/4" diameter through 4" diameter; PAGE 15 OF 67
. e WM-1.0 REVISION 2 6/8/82 D. Qualification on 2" diameter schedule 80 or 3" diameter schedule 40 shall qualify for all diameters through 4";
E. Qualification in the 6GR position shall qualify for groove and fillet welds in all positions of pipe, tubing and plate.
553 The type and number of test specimens required for mechanical testing shall be removed and tested in accordance with AWS D1.1.
5.5 4 A welder / welding operator, who fails his test, may be retested under the applicable provisions of 5 3 13 555 When a welder / welding operator has not performed welding to the specific process for a minimum of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per 90 calendar days or there is specific reason to question his ability to make welds that meet the requirements, he shall be requalified under the applicable provisions of 5 3 12 and 5.3 14 respectively.
556 Renewal of qualification under the provisions of 5 3 12 need only be made in' carbon steel (P-1) material 3/8" thickness.
5.5 7 Requalification, under the provisions of 5 3 13, .."
shall meet the same requirements as the original qualification. ,
5.5.8 A welder / welding operator, as determined by the Welding Supervisor, may be required to requalify under the provisions of paragraph 5 3.19 5.6 PQR and SQT acceptance criteria.
5.6.1 In addition to any requirements imposed by the applicable ASME Section III construction Code, the following acceptance criteria shall apply for ASME Section IX Code WPS qualification:
A. Tension Test Acceptance Criteria.
- 1. The tension test specimen shall be ruptured under censile load and the tensile strength shall be computed by dividing the maximum load by the i
least cross-sectional area of the specimen as measured before the load is applied.
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- a. TENSILE STREGNTH= MAXIMUM LOAD LEAST GROSS-SE0 TION AREA
- 2. The tensile strength shall be not less than:
- a. The specified minimum tensile strength of the base metal; or
- b. If base metals of different minimum tensile -
strengths are used, the specified minimum tensile strength of the weaker of the two; or
lower room temperature strength than the base metal; or -
- d. If the specimen breaks in the base metal outside the weld or fusion line, the test shall be accepted as meeting the
' requirements, provided the strength is not more than 5.5.belc~w the specified minimum l
tensile strength of the base metal. , ,
B. Bend Tests Acceptance Criteria. !
- 1. The weld and heat-affected zone of a transverse t
weld bend specimen shall be completely within the bent portion of the specimen af ter testing; and i 2. The guided-bend specimens shall have no open defects exceeding 1/8", measured in any direction on the convex surface of the specimen after bending, except that cracks occurring on the corners of the specimens during testing shall not be considered, unless there is definite evidence that they result from slag inclusions or other internal defects.
. 3 For corrosion resistant weld overlay cladding, no open defect exceeding 1/16" measured in any i
' direction shall be permitted in the cladding, and no open defects exceeding 1/8" shall be permitted in the bond line.
C. Notch Toughness Tests Acceptance Criteria shall be in accordance with the applicable ASME Section III Code
),
and the current ASME Section IX Code.
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1 WM-1.0 REVISION 2 6/8/82 5.6.2 In addition to any requirements imposed by ASME Section ,
IX and III Codes, and paragraph 5 3.6, either 5.6.2 ( A) I or 5.6.2 (B) acceptance criteria shall apply for SQT.
A. Send Tests Acceptance criteria.
- 1. The bend test acceptance criteria shall be the same as specified in paragraph 5 6.1-3.
B. Radiographic Examination Acceptance Criteria shall be accordance with T-NGCP-9 C. The results of the welder / welding operator qualification tests shall be recorded on the SQT Record, Attachment IV.
5.6.3 The following acceptance criteria shall apply for AWS D1.1 SQT qualification:
A. The type and number of tests shall be removed and tested in accordance with AWS D1.1.
B. Eend Test Acceptance Criteria. ( _
h
- 2. The guided-bend specimens shall have no cracks or other open discontinuities exceeding 1/8" measured in any direction after bending. Cracks occurring on the corners of the specimen during testing shall not be considered.
57 Documentation of Welding Activities.
5.7 1 All maintenance welding or brazing activities to code or safety related items shall be initiated by a Maintenance Work Request. All welding or brazing activities will be controlled by the use of Weld Traveler or Brazing Traveler, Attachments VI and IX respectively, except as l noted in 5 7.4 (A)(2). These applicable documents will provide the welder or brazer, the Quality Control Inspector, and, for Section XI repairs, the ANII with the necessary information' to properly perform and control the welding and brazing activities.
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/ WM-1.0 REVISION 2 6/8/8.2 1
5.7 2 The Weld Traveler or Brazing Traveler shall be either typed or filled out in black ink. All corrections to the applicable travelers shall be completed by drawing one line through the entry to be corrected, clearly entering the correction as near to its intended position as possible, and initialling and dating the correction.
573 The Weld Traveler or Brazing Traveled may be computer-produced based upon pre-programmed information. The Welding Supervisor and the Inspection Coordinator, or their designated alternates, shall review any computer produced travelers for adequacy, accuracy, and proper application and, also, affix signature and date.
5.7.4 Weld or Brazing draveler, Attachments VI and II, respectively, entries (1) through (25).
A. The Welding Supervisor, or his designated alternate, e shall enter the information on the manually initiated Weld or Bracing Travelers in the following spaces prior to issue:
(1) SYSTEM CR CCMPONENT - Enter the system or. ,
component designation and item name on which the welding or brazing is to be performed. g (2) WELD OR BRAZED JOINT NUMBER - Enter tie number assigned to the weld or brazed joint. Fo r repair welds or repair braces, use the appropriate suffix: R1, R2, etc. For replacement welds, use the appropriate suffix:
A, B, etc. For seal welds used as sealing devices, only one weld traveler is required for a group of such welds not to exceed 25 in numbe r. Such welds shall be identified in remarks section of the weld traveler. Safety related tack welds used as locking devices need only be documented on the MWR with the following information.
A. WPS Number I B. Type and size welding electrodes used C. Qualified welder's name and I.D. symbol.
(3) MAINTENANCE WORK REQUEST - Enter the MWR Number.
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6/8/82 (4) CODE AND CLASS - Enter the applicable code and/or class, such as ASME Section III, Class 2.
(5) MATERIAL TRICKNESS - Enter the wall thickness of the items being joined. If different thicknesses, enter both thicknesses.
(6) DIAMETER - If applicable, enter the outside diameter of the items being joined.
(7) PREHEAT AND INTERFASS TEMPERATURE - Enter the minimum and maximum temperatures, as applicable.
These temperatures are obtained from the WPS(s) or BPS (s).
(8) POST WELD HEAT TREATMENT OR POST ERAZE REAT TREATMENT - Circle "YES" or "NO" as applicable.
(9) WELDING PROCEDURE OR BRAZING PROCEDURE - Entse the applicable WPS(s) or BPS (s) nu=ber(s) and designation (s) which are to be used to join the items.
(10) FILLER MATERIAL - Enter the applicable filler ;-
materials to be used with the listed WPS(s) or l BPS (s).
(11) NDE REQUIRED - Enter the type (s) of NDE required for the weld or brazed joint.
NOTE: Enter base material specification (s) and/or number, material identification number (s), as applicable in space 20.
(12) PREPARER'S SIONATURE AND DATE - The individual preparing the traveler shall affix signature and date.
B. Space is provided for the Quality Control Inspector and, for ASME Section XI hold or witness points, the ANII to verify the following operations by affixing signature and date as the welding or brazing activity progresses.
(13) PROCESS CHECK POINT SEQUENCE PAGE 20 0F 67 l
' ~
WM-1.0 REVISION 2 6/.8/82 (A) JOINT CLEANLINESS - Verification of joint cleanliness prior to fitup.
(B) POSSIBLE LIMITED ACCESS - Circle "YES" or "NO", as applicable. If "YES", verifies
- that welder or bracer is qualified for
" Limited Access" prior to proceeding to next operation.
(C) EXCAVATION (NDE. VT, PT, MT, RT) - To be completed at the time of the inspection activity to verify that repaired areas have been properly excavated and for the perfor=ance of any required excavation NDE.
(D) CHECK FITUP - Verifies that the joint is properly fitup in accordance with the applicable WPS(s) or BPS (s) and this procedure. Verifies the filler material is the proper type and size. Verifies that the shielding gas and flow rate are in
()x.
accordance with the requirements.
(E)- PURGE - Verifies.that the gas backpurge, when required, is in accordance with the requirements.
(F) CHECK PREHEAT PRIOR TO ROOT PASS - Verifies ,
that the preheat is in accordance with the specified requirements.
(0) CRECK BACKGOUGING/ GRINDING - Verifies that complete joint penetration double groove welds are backgouged or ground back to sound metal on the opposite side prior to deposition of weld metal on the back side.
(H) CHECK INTERPASS TEMPERATURE - Verifies that the interpass temperature is in accordance with specified requirements. It shall be verified at least once per day. If temperature is verified more than 3 times, additional verifications shall be entered in the " Remarks" section.
(13) PROCESS CEECK TOINT SEQUENCE (Continued) 3
-N PAGE 21 0F 67
._= _ . . _ . _ __ _ _ _ _ _.
~
~,
WM-1.0 REVISION 2 '
6/8/82 (I) VISUALLY INSPECT COMPLETED WELD OR BRAZED JOINT - Verifies that the completed weld or brazed joint =eets the applicable visual acceptance requirements.
(J) CHECK DELTA FERRITE / RECORD IN " REMARKS" -
Measures and records the Delta Ferrite Content of all stainless steel welds having a thickness greater than 1". Measurements shall be taken using a calibrated Severn Gage or equivalent and shall have a minimum reading of 3% Delta-Ferrite. The .
measurements shall be taken at 4 locations and, when appropriate, 90* apart around the circumf erence of the weld.
C. The following columns are used by the Quality Control Inspector and the ANII to verify the "In Process" welding or brazing inspection activities, as applicable:
(14) Quality Control Inspector's column for affixing signature and date for those welding or brazing inspection activities performed, as applicable.
(15) ANII's column for selecting inspection hold or witness points, and affixing signature and date for those welding or bracing inspection activities performed, as &pplicable.
D. Each welder or brazer performing the activity shall enter the applicable information in the following appropriate columns during the welding or bracing activity, respectively:
(16) FILLER MATERIAL - Enter the size, type, and heat / lot number of the filler material, e.g.,
1/8", ER308L B802.
(17) WELDER'S OR BRAZER'S NAME AND I.D. NUMBER - Each welder or brazer who performs the welding or bracing, respectively, shall enter his name and I.D. Number.
E. Space is provided for the Quality Control Inspector to verify the applicable information by affixing signature and date in the following appropriate columns:
9 PAGE 22 0F 67
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~
s- WM-1.0
/ REVISION 2 6/8/82 (18) Enter the W?S(s) or BPS (s') and its applicable revision used to make the weld or bra:ed joint, respectively.
(19) Enter NDE results (accepted or rejected) and report number. Affix signature and date.
(20) Base material specification (s) , heat number,
. and/or material identification numbers, as applicable. ' Affix signature and date.
(22) Affix signature and date after any required Post Weld Heat Treatment or Post 3ra:e Heat
, Treatment, as applicable, has been completed and accepted.
(23) Affix signature and date af ter all welding activities have been completed and accepted.
F. The Welding Supervisor or Assistant Manager-Maintenance Services shall affix signature 3 and date in appropriate columns (24) and (25),
respectively, after hydrostatic testing or a system leakage test, when required, has been completed in order for the applicable weld or brazed joints to be released to operations.
G. Any individual involved with the welding or brazing activity may use the " Remarks" section, column (21),
to record any information which may be worthwhile or meaningful in the production, inspection, or final review of the weld or brazed joint, respectively.
When an additional traveler is initiated, the
" Remarks" section, column (21) , shall be used to indicate the reason for an additional traveler and, also, to reference the applicable additional travelers. _
H. All entries made on the travelers shall be legible.
5.7.5 Prior to release for welding or brazing activities, the Director cf Station Quality Control or his Designee and, when required, the Authorized Nuclear Inservice Inspector
! shall review the Weld or Brasing Traveler along with the MWR for the establishment of any inspection hold or l witness points.
Q PAGE 23 0F 67
. . l 1
WM-1.0 REVISION 2 6/8/82 -
5.7.6 Upon completien of the welding or brasing activities, the Director of Station Ouality Control or Designee and the Welding Supervisor shall review the Weld or Brazing Traveler, respectively, in order to ensure all activities have been properly performed and the Documentation is correct.
5.8 Materials.
5.8.1 All replacement base materials shall conform to the requirements of the applicable construction code or other appropriate codes or standards.
5.8.2 All mcdification or alteration base materials shall conform to the requirements of the modification or alteration specification (s).
5.8.3 Welding material shall conform to the requirements of the applicable construction code or specification and the applicable WPS(s) or BPS (s). All welding materials shall be issued and controlled in accordance with Welding Material Procedure WM-2.0.
59 Welding Activities. 5 NOTE: , Reactor Coolant System piping shall be purged with
' nitrogen or argon before and during thermal cutting or grinding activities which would result in opening the.
Reactor Coolant. System to atmosphere.
5.9 1 Ease Metal Preparation.
A. The joint edges shall be prepared by machining, grinding, shearing, oxygen-fuel cutting or carbon air are gouging and shall be in accordance with the dimensions specified La the WPS and/or this procedure. Materials prepared by oxygen-fuel cutting or carbon air are gouging shall be pre-heated in accordance with the requirements of this procedure.
Oxygen-fuel cutting or carbon air are gouging shall be followed by grinding to the required angle or joint specification. The welding groove shall be reasonably smooth, uniform, and free from fins ,
tears, cracks and other discontinuities which would adversely affect the quality or strength of the weld.
The use of cutting oils is not permitted on stainless steels.
B. When oxygen-fuel cutting or carbon air are gouging is used for rough cutting, all remaining slag, scale, or ~
oxides shall be removed by machining or grinding the cut end to sound metal with a minimum of 1/16" removal.
PAGE 24 CP 67
E .* ,
. ,. 2 : . .. - . .
f O '
WM-1.0 REVISION 2 6/8/82 C. Prior to welding ASME Section III materials, ANSI B31.1 materials and AWS materials, all surfaces 1 to 2 inches on each side of the prospective weld shall be free f rom foundry skin, scale, moisture, rust, sand, slag, paint, marking crayon or ink, alkaline cleaner residue, low melting alley residue, oxides ,
' dirt or other deleterious material providing the size
- and shape of the material will accommodate this dimension. These deleterious materials may be removed by machining, wire brushing, or grinding.
Shot blasting is not permitted. All oil and grease 6' inches on each side of the weld joint shall be . _ ,
removed by cleaning with Magnaflux Cleaner-Remover SKC-S or other approved solvent. -
All ' stainless steel or inconel welds shall have surfaces 2 inches on each side of the welds specially cleaned using Magnafluz Cleaner-remover.SKC-S or other approved solvent. Primary Coolant or NSSS components shall'be cleaned only with technical grade acetone or isopropyl alcohol. For AWS welds , mill O scale that withstands vigorous wire brushing, a thin rust inhibitive ccating or anti-spatter coating may remain, except that for girders all =111 scale shall be removed from the surfaces on which the flange-to-web welds are to be made by the shielded metal arc welding process.
D. All cleaning and grinding tools to be used on stainless steel and incor.al shall be color-coded International Orange or Federal Orange for use on stainless steel and inconel only. The color-coding shall be marked on a part of the tool that will not come in contact with the work piece. Grinding shall be performed with rubber or resin bonded aluminum or silicon carbide grinding wheels. Tools previously used on carbon or low alloy steels shall not be used on stainless steels or inconel. Wachs cutters or equivalent which have been used on carbon or low alloy steels may be used on stainless steels or inconel provided no cutting oil is used. Simetallic welds (carbon to stainless steel) do not require the use of tools color-coded for stainless steel only.
t O
PAGE 25 0F 67
-c3 5 M o WM-1.0 REVISION 2 6/8/82 E. If welding has not started within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> af ter base-metal preparation and cleaning, the weld joint shall be suitably wrapped to prevent deleterious material contamination. Upon removal of the protective wrap and prior to weldihg, the weld joint shall be inspected by a certified Quality Control Inspector.
5.9 2 Fitup of Butt Joints.
A. F1 tup shall be accomplished by the use of clamps, al15 nment lugs, tack welds or other appropriate means to properly align the jcint for welding. Whenever possible, mechanical means for alignment should be used. If alignment lugs are used, the lug =aterial will be compatible with the base material. The lugs shall be of the same general chemical composition as the base materials. Bi-metallic welds (stainless to carbon steel) shall have lugs made from stainless steel. The carbon steel side must be welded in accordaned with a bi-metallic WPS.
B. If welded lugs are used, they must be removed af ter serving their purpose and the areas ground flush with the base material and the area inspected for mintnum .'
wall violation, cracks and other deleterious defects. -
The type and method of NDE shall.' be in accordance with the applicable code.
C, If required to meet fitup tolerance, material surfaces may be built up by buttering with weld metal by welders qualified to a WPS(s) for groove welds which is applicable to the part being buttered.
D. For ASME Section III piping, fitup and align pipe sections and components so the maximum offset of the finished weld is less than that listed below, where t is the nominal thickness of the thinner of the two pieces being joined:
O PAGE 26 0? 67 1
~
WM-1.0 REVISION 2 6/8/82 SECTION THICKNESS DIRECTION OF JOINTS LONGITUDINAL CIRCUMFERENTIAL Up to 1/2" inclusive 1/8" 1/4 t Over 3/4" to 1 1/2" inclusive 1/8" 3/16" -
Over 1 1/2" to 2" inclusive 1/8" 1/8 t
' Over 2"
O E. When component inside surfaces are inaccessible for welding or fairing,. inside diameter misalignment shall not exceed 1/16" maximum on ANSI B31.1 welds' and 1/32" concentric mismatch or 3/32" maximum at any one point for centerline offset on ASME Section III welds.
l 593 Pitup of socket joints.
A. The following steps shall be followed to obtain the i
proper socket gap dimension and alignment:
! 1. The pipe or tube shall be cut by mechanical means i so the tube or pipe end is square with the longitudinal axis of the tube or pipe.
- 2. Scribe a line with a scribe or center punch with a blunt nose punch on the socket fitting 0.D.
approximately 1/4" from the face of the socket fitting.
3 Fully insert tube or pipe into the socket fitting.
- 4. Holding tube or pipe in concentric alignment with the socket fitting, scribe a line on the tube or pipe 0.D. 1" away from the first scribe line.
PAGE 27 0F 67 i
WM-1.0 REVISION 2 ,
6/8/82 5 Withdraw the tube or pipe 1/16" to 1/8" to obtain a distance between the two scribe lines of 1 1/16" to 1 1/8" for socket fittings equal to or greater than 3/4" nominal pipe size.
- 6. Withdraw the tube or pipe 1/16" to 3/32" to obtain a distance between the two scribe lines of 1 1/16" to 1 3/32" for socket fittings less than 3/4" nominal pipe size.
7 Following other applicable variables of the WPS(s) and keeping the tube or pipe in concentric alignment with the socket fitting, tack weld in this position.
- 8. Af ter tack welding, the distance between the two scribi lines shall be 1 1/16" to 1 3/32" as described in 5.5 3.A (5) or 5.9 3.A (6) as applicable.
9 Refer uo figure 5 9 3-A(a) for a single view pictorial graphic of fitup dimensions.
5.9.4 Backing Rings -
A. Backing rings, stript or bars, if required by the applicable WPS(s), shall be made of material which is compatible with the base material.
B. Backing rings shall not be used for welds joining iL-ASME Class 1 components. Backing rings shall not be used for welds joining ASME Class 2 or 3 components, unless specified La the design specification.
C. If split type backing is used, the backing shall be welded to form a continuous length of backing af ter fitting but prior to welding of the joint.
D. The gap between the backing and the base metal in ASME Section III weldments shall not exceed:
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PAGE 28 0F 67
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PAGE 29 0F 67
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WM-1.0 REVISION 2
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6/8/82 WALL THICKNESS, IN. CLEARANCE, INCHES 1/4 to 1/2 .0 10 Over 1/2 to 1 .020 Over 1 to 2 .030 Over 2 .040 E. The gap between the backing and the base metal in ANSI B31.1 weld =ents shall not exceed 1/32".
F. The gap between the backing and the base =etal in AWS D1.1 weldments shall not exceed 1/16".
G. Spacer pins, if used, shall not be incorporated into the weld.
595 Consu=able Insects.
A. Consumable insects, when required, shall be of the type and/or dimensions specified on the WPS.
5 9.6 shielding and Purging Gas.
A. The shielding gas and flow rate during welding shall be as specified on the WPS.
B. Purging is required on stainless steel and inconel socket welds when the pipe or tube wall thickness is less than 1/8".
C. Prior to welding, the weld joint shall be purged, if required, at a flow rate of approximately 25 cubic feet per hour (CFH) until a minimum of 6 volume
' changes have occurred or until the czygen content has been analyzed to be below 1.0%.
D. During welding, the purge flow rate may be reduced to a minimum of 10 cubic feet per hour, but not less than that specified on the applicable WPS(s), and shall continue until the weld is 3/16" thick or two weld layers have been deposited, whichever is greater.
O PAGE 30 0F 67
WM-1.0 REVISION 2
()
- 6/8/82 v
E. Since water soluble purge dams may become insoluble at elevated temperatures, precautions shall be taken to ensure the dams are installed at least 12" on both sides of the weld joint. The outside of the piping system or other items shall be marked with an appropriate marker showing the internal locations of these dams.
The tempera $ture shall be checked periodically by use of appropriate temperature indicating crayons, calibrated thermocouple pyrometers or other suitable means on the outside surface of the pipe or other item at the das installation location. In the event the. temperature approaches or exceeds 275'F, the welding operation shall cease until the temperature has dropped to 150*F.
Should' subsequent' Post Weld Heat Treatment be required, the purge dass shall be located at a minimum distance of 36" on each side of the heating band. Temperature verification shall be performed as described above.
5.9 7 Preheat and Interpass Temperature.
ASME Section III Components, Class 1, 2 and 3
(' ) A. l
(~- 1. For carbon steel (P-1) circumferential butt joints, including branch connections or socket welds, in material with a maximum reported carbon content greater than 0.3% or a nominal wall thickness greater than 3/4", the minimum preheat and interpass temperature shall be 200*F. The minimum preheat shall not be interrupted until at least 30% of the weld joint is complete. After interruption, when permitted, the minimum preheat temperature must be re-established prior to resuming welding.
~.
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PAGE 31 0F 67 i
- . r WM-1.0 REVISION 2 6/8/82 ,
pressure parts to non-pressure parts where the nominal wall thickness of the pressure part is less than $/4", the minimum preheat and interpass temperature shall be 200*F. The minimum preheat shall not be interrupted until at least 30? of l the weld joint is completed. After interruption, when permitted, the minimum preheat temperature must be re-established prior to resuming welding.
3 For other carbon steel welds not specified herein, the minimum preheat and interpass temperature shall be 60*F.
- 4. .For stainless steel (F-8) and inconel (P-43) welds, the preheat and interpass temperature range shall be 60*F to 350*F.
5 For bi-metallic welds (carbon steel to stainless steel), the preheat and interpass temperature shall have a minimum temperature of that required for the carbon steel, as stated in 1. and 2.
above, and a maximum tempe'rature of 350*F.
- 6. For Main Steam, Feedwater and Reactor Building penetration welds over 5/8" wall thickness, the maximum interpass temperature shall be 350*F.
~-
- 3. ASME Section III, Class MC.
- 1. For carbon steel (P-1) welds in material with a nominal wall thickness over 1" and having a minimum specified tensile strength of 70,000 PSI or higher, the minimum preheat and interpass temperature shall be 200*F. For other lower strength materials, the 200*F preheat and interpass temperature requirement shall be applied to material with a nominal wall thickness of over 1 1/4".
9l l PAGE 32 OP 67 l
... 4 :. ,
WM-1.0 REVISION 2 6/8/82 For stainless steel (P-8)~and inconel (P-43) 3 welds, the preheat and interpass temperature range shall be 60*F to 350*F.
C. ASME Section III, Component Supports.
For groove welds in material with both a -
specified maximum carbon content in excess of
.30% and a thickness of 1", the minimum preheat shall not be interrupted until at least 30% of the joint is completed. This non-interruption requirement does not apply to fillet welds 3/4" and under in size which are used to attach insulation clips and other parts not carrying loading due to internal pressure. After g interruption, when permitted, the minimum preheat q, temperature must be re-established prior to resuming welding. ,
3 For other carbon steel (P-1) welds, the minimum t
preheat and interpass temperature shall be 60*F. l
- 4. For stainless steel welds, the preheat and interpass temperature range shall be 60*F to l 350*F.
' ~
< steel, as stated in 1. and 2. above, and a maximum temperature of 350*F.
D. ASME Section III Items Not Listed in A, B and C.
I &
l PAGE 33 0F 67
WM-1.0 ,
l REVISION 2 6/8/82 ,
- 1. For other ASME Section III items not described in A , B and C , figures 5 9 7-D (a) , 5 9 7-D (b) , ..e 5.9 7-D(c) and 5 9 7-D(d) shall be used to determine the preheating temperature -
requirements.
- 2. Notes applicable to figures 5.9 7-D(a) through (d) are as follows:
- a. The nominal thickness is defined as the thickness of the weld, base material, pressure retaining material or the thinner of -
the sections being joined, whichever is least. For fillet welds, the nominal thickness is the throat thickness and, for partial penetration and material repair welds, the nominal thickness is the depth of the weld groove or preparation.
- b. Preheat and interpass temperatures may be verified by the use of approved temperature indicating crayons, calibrated ther=occuple pyrometers, or other suitable methods.
E. ANSI B31.1 Piping and Supports.
For carbon steel (P-1) welds in material with 1.
both a specified carbon content greater than .30% s_.
and a thickness at the joint greater than 1", the miniman preheat and interpass temperature shall be 200*F.
3 For stainless steel (P-8) welds, the preheat and interpass temperature range shall be 60*F to 350*F.
above, and a maximum temperature of 350*F.
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PAGE 34 0F 67
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O PAGE 36 0F 67
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WM-1.0 REVISION 2.
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PAGE 37 0F 67
WM-1.0 REVISION 2 6/8/82 ,
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PAGE 38 0F 67
. . 1 l
1 WM-1.0 l REVISION 2 6/8/82
(N .
O 5 For carbon steel (P-1) to chromium-molybdenum ~
alloy steel (P-4 and P-5) welds, the minimum preheat and interpass temperature shall be 400*?.
The preheat shall not b~e interrupted until at least 3/8" thickness of weld is deposited or 25%
of the joint is completed, whichever is greater.
After interruption, when permitted, the minimum preheat temperature shall be re-established prior to resuming welding.
F. ANSI 331.1 Items Not Listed in E.
- 1. For other ANSI B31.1 items not described in E.,
figure 5 9 7-F(a) shall be used to determine the preheating temperature requirements.
I FIGURE 5.9 7-F(a) ANSI B31.1 ITEMS ASME Preheat Required Sec. IX
~
P-Nos. Minimum Wall, Min. Temperature, Inches 2.(a), 2.(b) *F 2 (c), 2.(d)
P-1 All 50 for T .30% carbon P-1 All 175 for > 1" l thickness and i > 30 carbon P-3 All walls 175 P. 4 Up to 3/4" 300 over 3/4" 400 P Up to'3/4" 300
< 5% CR. Over 3/4" 400 P-5 Up to 3/4" 300 7 5% CR. Over 3/4" 400 P-6 All walls 300 T 600*F intercass P-8 All walls None required PAGE 39 0F 67
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WM-1.0 REVISION 2 6/8/82 2 '. Notes applicable to figure 5 9 7-F(a) are as follows:
- a. Wall thickness of a butt weld is' defined as the thicker of the two abutting ends after end preparation including I.D. machining.
. b. The thickness of socket, fillet, and seal welds is defined as the throat thickness for pressure and non-pressur,e retaining weld.
- c. Preheat and interpass temperatures may be verified by the use of approved temperature indication crayons , calibrated ther=occuple pyrometers, or other suitable methods.
- d. For inert gas tungsten are root pass welding, lower preheat in accordance with the applicable WPS(s) may be used.
G. AWS Dl.1 Welds.
3 For welds in carbon steel material with a thickness over 2 1/2", the minimum preheat and interpass temperature shall be 225 F, unless otherwise specified on the WPS.
- 4. For welds in stainless steel material, the preheat and interpass temperature range shall be 60*F to 350*F.
PAGE 40 0F 67
t , ,, ,
WM-1.0 REVISION 2
() .
5 6/8/82 For bi-metallic welds (carbon steel to stainless steel), the preheat and interpass temperature range shall have a minimum temperature of that required for carbon steel, as stated in 1, 2 and 3 above, and a maximum interpass temperature of' 350*F.
- 6. Preheat and interpass temperatures shall be sufficient to prevent crack formation.
Where highly restrained welds are encountered, detail.ed work instructions shall specify the preheat and interpass temperature requirements.
H. AWS Dl.1 Items Not Listed in G.
- 1. For other AWS Dl.1 items not described in G. ,
figures 5 9 7-H(a) and 5 9 7-H(b) shall be used to determine the preheating and interpass temperature requirements.
- 2. Notes applicable to figures 5.9 7-H(a) and (b) are as follows:
- a. When the base metal temperature is below 32*F, the base metal shall be preheated to at least 70*F and this minimum temperature (y maintained during welding.
u
- b. For quenched and tempered steel, the maximum .
preheat and interpass temperature shall not exceed 400*F for thicknesses up to 1 1/2",
inclusive, and 450*F for greater thicknesses.
Heat input when welding quenched and tempered steel shall not exceed the steel producer's recommendation.
- c. In joints involving combinations of base metals, preheat shall be as specified for the higher strength steel being welded.
- d. Preheat and interpass temperatures may be l verified by the use of approved temperature l indicating crayons, thermocouple pyrometers ,
l j
.or other suitable methods.
l Q
PAGE 41 CF 67
WM-1.0 REVISION 2 6/8/82 (2.b.,2.c'.)
~
IGGU4 EEEAT 12D SEEFP!ss ':ETEFMPE ,
?!bneca ct WM M!rd:im WSdrg At Fair.t cf Temmtu:e, Steel Etecifh' P:ccess WC d q. , In. @F
/C1 E6 (2.a.)
1624 163 Gmde B tp tn 3/4 :nn
/01A106 GrMe B 101 A131 Gmdes A, 3, C, G, D, E m Aly) C.ade B ce M
/S! A301 Gmde E W4M thu$ 1 M 150 ADI 1600 Ccde A natal at Gmde B weldiq.id.th a /601 ctir thn aver 1 M N A516 G a des 55 ati 60 Icw i d w m thn@ 2 M 225
/Di 1624 Gmdes I atiII electrfes tat 429
/El1670 GrMes D a:1 E ce 21/2 300 m 1673 Gmde 65 m A709 GmJe 36 AE % Gmde B AE 5x Qtude @
IES Gedas A, B, C, CS, ES Gmde E .
6 A36 m 163 OcMe B m A1C6 GrMe B tp to M rrrn
/ElA131 GrMes A C, G, D, E AI 32 ad EP'4M DI 32 axi catal an EH 32 ati with c e 3/4 ADI A139 Gm$e B Icw b t.M1M 50 AS24 A242 ebuk:s i.E4 A381 Gru$e G ist ;M1 AS24 400 Gmde A ce 1 M Qtu$e B thu@ 2 M 150 m A501 -
ASD4 516 Gmdes 5 azi 60 6 ati70 ce 2 M 225 m E24 Ots$es I ati II AS24 A529 AS24 ;637 rimw 1 ati 2 ASDi A570 Gmths D ati E ASD41572 Gmdes 4, W, 50 AS31 lo, Gru$e 6 l' AS31- .
A524 A595 QW A, B, C FHIFE 5.9 7-iiCa) As cl.1 O
PAGE 42 0F 67 (
6 WM-1.0 REVISION 2 6/8/82
'u (2.b.,2.c.)
IGOU4 HEEE #D DEPAS3 'IEGEPA"TE PJness &
N Parc M:n'.:w.
Weld!rg At hi.T ; & Te: pas::.7., ,
Steel W + m Process %Idfrg,In. *F
- 324 'd6 (2.a.)
m 14:07 Ges$es 16, 50, 55 SMM to m y4
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rme m ;618 ::etal are -
m 1633 Gmdes B e.Idirs with Gmdes A, C D Iot luu.pl E A709 Grs$es 3$, 50, 531 elect:u5es a y4 tiz u @ l M 50
/PI 5L (1sde B API 5EX Grufe 42 API arc. EI w1M E Gtu$es AH 32 ad ttru gi 2 W 150 DI 31 ad El 32 e:ti E Gmdes A, B, D, G, IE w 2 V2 25 Gmde E XI24 Kil2 (ksdes 55, 60, 65 SMa'M t:p'n F4 50
- s
- M1633 Grs$e E metal au uth , w V4 lot tizu@ l 1/2 150
' . ebA f
i w1M '
' tirug 2 M 25 w 21/2 3:0 m ;514 S**'M to to V4 50 m ,%17 metal an AE:M A709 Gen $es ICO ad 1031 weldfrg uth w F4 lot inci ttzug 1 M 225 elsetzedes e 1 I/2 tizug 21/2 17 5 w 21/2 225 FIDWE 5.9 7-E(b) A16 C1.1 Q
PAGE 43 0F 67
WM-1.0 REVISION 2 6/8/82 I
I. The specified preheat shall be attained prior to any .
welding, including tack welding, or thermal cutting activities.
J. When preheat is required for any weld joints, the l preheat band shall extend from the point of welding to at least 3" in any direction providing the size of the work piece will accommodate this 3" dimension.
K. The. preheat temperature shall be verified approximately 1 to 2 inches away f rom the weld.
5 9.8. Tack Welds.
A. Tack welds shall be made by welders qualified to use the applicable WPS.
B. Tack welds shall be kept to a minimum size and number. When tack welds made in the open butt single vee pipe joints are not removed but are to be incorporated into the weld, they shall be ground so that they do not exceed 1/8" thickness and their ends shall be feathered to facilitate incorporation into
'the final weld.
C. Open butt pipe tack welds and root passes shall be /
performed by the GTAW process only, unless the reverse side of the weld is accessible for cleanup, repair and examination, in order to accomplish a "'
(
sound, uniform and full penetration wel'd.
D. Preheat and interpass temperature shall be the same for tack welds as required for the weld unless otherwise specified on the WPS(s).
E. Cracked or otherwise defective tack welds shall be removed in their entirety prior to proceeding with the welding operation.
F. The work piece shall be protected from deleterious contamination and from rain, snow, and wind during tack welding. Tack welding shall not be performed en wet surfaces.
5.9.9 Welding operations.
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l O.
PAGE 44 OF 67 j l
WM-1.0
- REVISION 2 6/8/82 ,
(} ,
A. .T?w applicable WPS(s), as shown on the Weld Traveler, -
shall be used to perform the welding operation .
following the welding para =eters and variables, tabulated or described in the WPS(s), such as current, voltage, electrode type and size, shielding gas, purge gas, etc.
B. The number of passes or layers as shown en the WPS(s) are typical and may vary with material thickness and welding electrode diameter.
C. Weld progression shall be as shown on the applicable WPS(s).
D. When welding p'ipe circumferential weld joints, each layer of weld metal shall be completed around the entire' circumference of the weld groove prior to depositing succeeding weld passes.
E. Weaving width shall not exceed three (3) times the welding electrode size or for inert Gas Tungsten Arc Welding the gas cup orifice inside dia=eter.
F. Peening or welds-is not permitted unless specific authorization is obtained from the welding supervisor.
- 'G. Weld bead thickness shall not exceed 'l/8" un1'ess '
otherwise specified on the WPS(s) or on the weld ,
traveler.
H. A minimum of two layers is required for all pipe i
joints.
I. When item to be welded is filled with water, welding is not permitted unless specific authorization is l
granted by the Welding Supervisor.
J. Complete- joint penetration double groove welds shall i
be ground or carbon air are gouged back to sound metal on the -opposite side. The opposite side weld l
t root area shall be cleaned to sound metal and contoured to permit proper deposition of the root l
i pass from the second side.
O PAGE 45 0F 67 l
WM-1.0
' REVISION 2 6/8/82 K. The work piece shall be protected from deleterious contamination and from rain, snow, and' wind during welding. Welding shall not be performed on wet surfaces. Welding shall not be performed within 18" of caulked lead joints or any other lead containing materials unless specific author.'.zation is granted.by the Welding Supervisor.
L. Typical weld joint groove designs are shown on the applicable WPS(s). Hewever, these groove designs may vary with the application and material specification.
M. The technique of depositing weld metal shall be such that undercutting of a groove face shall be minimum.
Undercutting of a groove face in excess of 1/32" shall be blended in by grinding before depositing the next layer of weld metal.
Sharp changes in sections at the toe of any weld, except undercut,. shall be eliminated by grinding, taking care to avoid thinning of the base metal. Any cracks, blowholes or other defects of any nature detected during welding shall be removed by grinding or chipping before the next successive bead or layer of weld metal is deposited.
5.9 10 Interpass Cleaning.
A. All beads or layers of weld metal shall be cleaned ,
prior to depositing the next successive bead.
G~eaning shall be accomplished by wire brushing, filing, chipping or grinding to sound metal.
Precautions shall be taken not to unduly harm the base metal outside and inside the welding groove during cleaning operations.
B. Craters of starting and stopping ends of each layer deposited and on groove faces shall be removed by grinding before depositing the next successive pass of weld metal.
C. Cleaning tools and equipment shall be as specified in 5 9 1 of this procedure.
D. Interpass cleaning shall be accomplished using the most effective and efficient methods compatible with material specification and welding process.
O PAGE 46 0F 67
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WM-1.0 REVISION 2 5 9 11 Finished Weld Surfaces.
A. As-welded surfaces are permitted. However, the surface of welds shall be sufficiently free fecm coarse ripples, grooves , overlaps , abrupt ridges and valleys, are strikes, weld splatter and slag to meet the following requirements:
- 1. Where non-destructive examination, including visual, of welds is required by codes and/or design specifications, the surface condition of-the f.inished weld shall be suitable for proper interpre. cation of the results of the appropriate NDE examination (s).
- 2. The applicable dimensions of butt weld reinforcement are listed herein as follows:
- a. ASME SECTION III VESSELS, PUMPS AND VALVES Material Nominal Max. Reinforcement, -
Thickness, Inches Inches Up to 1, inclusive 3/32 Over 1 to 2, inclusive 1/8 Over 2 to 3, inclusive 5/32 Over 3 to 4, inclusive 7/32 Over 4 to 5, inclusive 'l/4 Over 5 5/16 ,
- b. ASME SECTION III. PIPING WELDS Material Nominal Max. Reinforcement, Thickness,. Inches Inches outside Inside Surface Surface Up to 1/8, inclusive 3/32 3/32 Over 1/8 to 3/16, inclusive 1/8 3/32 over 3/16 to 1/2, inclusive 5/32 1/8 Over 1/2 to 1, inclusive 3/16 5/32 Over 1 to 2, inclusive 1/4 5/32 over 2 1/4 or 5/32 1/8 times the width of 4
the weld, whichever is greater.
D i -
(
PAGE 47 CF 67
u.
WM-1.0 REVISION 2 6/8/82
.Up to 1/U, inclusive 1/16 Over 1/2 to 1, inclusive 3/32 Over 1 to 2, inclusive 1/8 Over 2 5/32
- e. AWS D1.1 - Maximum reinforcement shall be 1/8".
3 Weld surfaces shall not be "washpassed" by use of '
.Ih '
the GTAW Process. ~-
- 4. The maximum allowable undercut at the toe of the weld shall not exceed 1/32" nor shall it encroach on the minimum wall thickness of the item.
Grinding to remove undercut is not permitted.
Undercut exceeding the maximum allowable shall be corrected by depositing a cover pass of weld metal using the applicable WPS(s).
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5 Concavity on the root side of a single welded circumferential butt weld is permitted when the resulting thickness of the weld is at least equal.
to the thickness of the thinner member of the two rections being joined.
O PAGE 48 0F 67
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WM-1.0 REVISION 2 6/8/82
- 6. When items of different diameters are welded~
together, there shall be a gradual trans1 tion between the two surfaces of not less than a 3: 1 taper unless greater slopes are permitted by analysis. The length of transition may include the weld, t
7 Specially' machined welded end transitions shall meet the requirements of paragraph 6. above.
t
- 3. Fillet Weld fizes
- 1. The minisc size of fillet welds used to attach '
socket fittings 2" diameter and under shall be not less - than 1.09 times the thickness of the pipe or tube measured along the fillet weld les and the throat dimension not less than .72 times the fillet weld leg size.
2 ~. The minimum size of fillet welds used to attach socket welded flanges shall be not less than 1.4 times the thickness of the pipe or tube, or the thickness of the hub whichever is smaller; O however, in any case the size shall be not less than 1/8" measured along the fillet weld leg.
The throat depth shall be not less than .72 times the fillet weld leg size. i 3 The minimum size of fillet welds used to attach slip-on flanges shall be not less than the thickness of the pipe or 1/4" whichever is smaller measured along the fillet weld leg. The throat depth shall be not less than .72 times the fillet weld leg size.
i i NOTE: Reference figure 5.9.11 for graphic l illustration of socket welding and slip-on flange fillet weld dimensions.
- 4. Fillet weld sizes for other applications shall be as specified by the applicable design l specification and/or the applicable code.
rb PAGE 49 CP 67
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~
W1. 0 REVISION 2 6/8/82 t= ncminal pipe O
lex :I < wall thickness /A I - '
ex min, l
] _
cx ..
,,, 1/!6 in, coprox. ,
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b fore welding x min.
,7 r
/' M /r i ;
/// $888$$it Il I/l6 in, cppr.I I before welding CX min. =.I.0 9 t Minimum Welding Dim ensions for x min.=l.4t er thickness of the hub, Socket Welding Fi t tin g s whichever is smaller (c) Socket Welding Fitting where t= nominct pipe weil thickness (b) Socket Welding F!cnge
////> ,
////h
, , _x min. , d I _x min.
4xmin.
/ f x min.
T A , P A !
%%N%Wi i RA%NNNNNNN t t 9 h t or'l/4 in., { i % % t or 1/4 in., '
i whichever is smaller whichever is smaller Front end Scek Weld Fcce and Scek Weld -
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(c)Siip-e n Ficng es Minimum Weicin; dimensiens f or slip-en onc soe x ei Jcints, os ccclicccie Fi g u r e Nc. 5.9.11 PAGE 50 of 67 g
WM-1.0 REVISION 2 6/8/82 5 Other size fillet welds may be used provided the requirements of the applicable code are met and the dimensions are specified on the weld traveler.
5 10 Brazing Activities.
5 10.1 Base Metal Preparation.
A. The joint edges shall be prepared by =achining, grinding or shearing and shall be in accordance with tne d1=ensions specified on the BPS (s). No carbon air are gouging or oxygen fuel cutting shall be permitted, unless specific authorisation is granted by the Welding Supervisor. The brazing groove or joint shall be reasonably smooth, uniform and free from fins, tears, cracks and other discon.tinuities which would adversely affect the quality or strength of the brazed joint. If cutting oils are used they shall be completely removed with Magnaflux Cleaner-Remover, trisodium phosphate solution or other appropriate solvent-cleaners. .
Prior to brazing l all surfaces 4 inches on each side of the joint, provided the work piece will
% accommodate this dimension, shall be free from 0s \.
foundry skin, scale, moisture, cust, sand, oxides, crayon or ink, residues, dirt or other deletericus materials. These materials may be removed by .
machining, wire brushing, appropriate solvents or grinding, or a combination of these processes may be used to remove these materials.
B. If brazing has not starced within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> af ter base metal preparation and cleaning, the joint may require protection with a suitable wrapping or covering.
Upon removal of any required protective wrapping the braze joint shall be cleaned as described in paragraph'A.
5 10.2 Pitup of Brazed Joints.
A. Fitup shall be accomplished by the use of mechanical devices and/or braze tacking, taking care to maintain the dimensions or tolerances specified on the applicable BPS (s) .
5 10 3 Backing Rings.
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PAGE 51 0F 67
WM-1.0 REVISION 2
. 6/8/82 A. Backing rings or lap rings shall be used when required'by the applicable BPS (s), taking care to ,
maintain the specified dimensions. These rings may be held in place by mechanical means and/or braze tacking.
5.10.4 Brazing Temperature, Flux and Atmosphere.
A. The brazing temperature range shall be maintained at the range specified on the BPS (s).
B. The brazing flux and/or atmosphere shall be as specified on the BPS (s).
5 10 5 Brazing Applications.
A. Brazed joints in a maximum nominal pipe size of 1" ,
'may be used only at dead end instrument cor.nections and in special applications where space and geometry conditions prevent the use of other joints. The special applications shall be specified in the design specification.
B. Brazed joints that depend upon a fillet rather than a capillary type filler addition are not acceptable.
C. Brazed joints shall not be used in systems containing ._,
flammable liquids. .
D. Soldered joints shall not be used in ASME Section III systems or components, and may only be used in other systems if permitted by the design specification.
5 10.6 Brazing operations.
A. The applicable BPS (s), as shown on the Brazing Traveler, shall be used to perform the brazing operation following the brazing parameters and variables, tabulated or described in the BPS (s), such.
as temperature, flux, electrode type and size, atmosphere, gas, etc.
B. Brazing progression or direction of major flow shall be as shown on the BPS (s).
PAGE 52 0F 67
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WM-1.0 REVISION 2 6/8/82
-s
/ C. Complete joint filling is required for all brazing prccesses.
D. No brazing shall be performed on any ites filled with '
water.
E. The' work piece shall be protected from deleterious contamination and from rain, snow, an'd wind during brazing. Brazing shall not be performed on wet surfaces.
F. Any cracks, porosity or craters decected during or after co=pletion of the brazing process shall be removed by grinding or chipping prior to proceeding with the brazing or testing, respectively.
5.11 Repair of Weld Metal Defects (ASME Section III).
5 11.1 Unacceptable defects in weld metal detected by the applicable NDE methods, hydrostatic, or leak testing shall be eliminated or the indications reduced to an acceptable itsit and repaired if necessary.
5.11.2 Weld metal surface defects may be removed by grinding machining and not repaired by welding, provided that the requirements of A, B, and C below are met.
A. The remaining thickness of the section is r.ot reduced that required by the applicable code. p j- .-
B. The depressions , af ter defect elimination, is blended uniformly into the surrounding surface.
C. The area is examined after tiending by a magnetic i particle or liquid penetrant method meeting the l requirements of the applicable code acceptance standards . to ensure that the defect has been removed or the indication has been reduced to an acceptable limit.
5.11.3 Excavations in weld metal, when repaired by welding, shall meet the following requirements:
sW4
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PAGE 53 0F 67 l
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WM-1.0 j REVISION 2 6/8/82 l l
I A. Unacceptable defects shall be removed by mechanical '
means or, if authorization is granted by the Welding Supervisor, by thermal gouging processes. The area prepared for repair shall be reasonably smooth and uniform and shall be examined by the magnetic particle or liquid penetrant method meeting the requirements of the applicable code acceptance standards. This examination is not required where defect removal essentially removes the full thickness and width of the weld in partial penetration or fillet welds; the area need only to be visually examined to determine the suitability for rewelding.
B. The weld repair shall be made using welding material, welders, and WPS(s) qualified in accordance with this procedure and the applicable code (s).
C. Af ter repair, the surf ace shall be' blended uniformly into the surrounding surface.
D. The examination of weld repair shall be repeated as required for the original weld, except that when the defect was originally detected by the liquid penetrant or magnetic particle method and when the repair cavity does not exceed the lesser of 3/8" or 10% of the thickness, it need only be re-examined by the liquid penetrant or magnetic particle method. _
E. When permitted by the applicable code, repairs to welds joining P-1 and P-3 materials requiring examination by radiography as required in D. above, but construction assembly prevents meaningful radiographic examination, ultrasonic examination may be substituted, provided:
- 1. The weld had been previously radiographed and met the applicable acceptance standards;
- 2. The ultrasonic examination is performed using a procedure in accordance with Article 5 of ASME Section V Code and to the acceptance standards of the applicable code;
5 12 Weld Repair of Base Metal Defects ( ASME Section III) .
9 PAGE 54 0F 67 l
WM-1.0 REVISION 2 6/8/82
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5 12.1 Defects in =aterial may be eliminated or repaired by wolding provided the defects are removed, repaired and examined in accordance with the requirements of the applicable code for the applicable product for=, except:
A. The limitation on the depth of the weld repair does not . apply;
~
- 1. location and size of the prepared cavity,
- 2. welding material identification, 3 WPS(s),
4' .- any required heat treatment, 5 NDE examination results,
- 6. resulting. thickness measurements;
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D. The material is repaired using qualified welders, applicable WPS(s), and welding material which =eets the requirements of the applicable code.
5 13 Repair of Weld Metal and Base Metal Defects ( ANSI B31.1 and AWS.
D1.1).
5131 Defects in base mat'erial and weld metal may be eliminated or repaired by welding, provided the requirements of the applicable construction code are complied with and any required non-destructive examinations are performed during and af ter the repair welding.
5 14 Defect Removal and Cavity Preparation of Weld Metal and Base Metal.
514.1 Defects may be removed and the resulting cavity prepared for welding by the methods described in 5 9 1, except the thermal Scuging process.
5 14.2 The thermal gouging processes may cnly be used providing specific authorica:1cn is granted by the Welding Supervisor. .
O-PAGE 55 0F 67
WM-1.0 REVISION 2 6/8/82 5 14.4 The wall thickness of the item, after elimination or fer repair of the defect, shall be verified to ensure that minimum wall thickness requirements are met by using the ultrasonic method or appropriate mechanical devices, as applicable. ith the applicable WPS(s).
5.14.5 Defects discovered on the final weld surf ace by the surface or visual examination methods shall be documented on the original Weld Traveler by stating the nature of the defect, method of repaic, and recording the welder '
~
I.D. and welding electrodes to be used.
5.14.6 Defects discovered.by the volumetric examination methods shall be documented by initiating a new Weld Traveler.
. The original Weld Traveler, if any, shall describe the nature of the defect and reference the new Weld Traveler.
The new Weld Traveler may contain. modified information, including additional repair instructions to be used.
5 14.7 Repairs not requiring the addition of filler material need only be documented on an NON in accordance with A-NQCP-2. A log or record of these NCN's may be kept by the Welding Supervisor, or his designated alternate, stating the extent of the defect, the mechanical method by which the defect was removed and subsequent non-destructive examination including verification of minimum wall thickness readings af ter the repair has been -'
completed.
5.15 Post Weld Heat. Treatment Requirements.
5.15.1 ASME Section III Class 1, 2, and 3 Components.
A. P-1 Material (Carbon Steel).
PAGE 56 0F 67
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- - . ' s. ,
e WM-1.0 \
REVISION 2 6/8/82 -
s O- -
3 Fillet welds attaching non-pressure parts to pressure parts when the throat' thickness of the fillet weld exceeds 3/4", regardless of pressure part wall thickness, shal:1 be post weld 0 heat '
treated. ,
specified in 1. abovs. '/
B. P-3 (Low Alloy Steel),to P-1 (Carbon Steel).
C. P-8 (Stainless Steel) to P-1 (Carbori Steel) .
5 15 2 ASME Section III Class MC. -
s A. Welds in material ecnstructed of carbon steel with a nominal wall thickness of over 1 1/2 inches shall be post weld heat treated.
515 3 ASME Section III Component Supports.
A. Welds in material constructed of carbon steel with a nominal thickness over 1 1/2 inches shall be post ,
weld heat treated.
5.15 4 Post Weld Heat Treatment of other,ASME Section III Items. .
A. Post weld heat treatments'of' welds for other materials and thicknesses shall be in accordance with the requirements of the applicable code, except as exempted by figures 5 15.4-A(a), 5 15.4-A(b),
5 15.4-A(c) and 5.15 4-A(d).
- 5 16 ASME Section III Post Weld Heat Treatment Time, Temperature and Process Activities. >
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PAGE 57 0F 67
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WM-1.0 REVISION 2 6/8/82 5.16.1 Post weld heat treatment minimum holding time and temperature shall be in accordance with figure 5 16.l(a).
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5 16.2 Alternative holding time and temperatures as specified by the code may be used only with specific authorization from the Welding Supervisor.
5.16.3 Post weld heat treatment process activities shall be as follows:
A. FWHT shall be accomplished using electric resistance heating. methods.
B. Only type K chromel-alumel thermocouples shall be used.
C. All recorders with thermocouples shall be calibrated l in accordance with SAP-141 D. The weld and/or ites number, as applicable, or name shall be recorded on the strip chart.
E. The post wcld heat treat cycle, including required heating and cooling rates, shall be recorded on a strip chart.
F. Air flow, if any, through the inside of piping shall be shut off, when practicable. .
G. Thermocouple attachment clips shall be attached to the item using tack welds or by mechanical means.
H. Tack welds to valve bodies or t'o nozzles shall not be used unless specific authorization is granted by the Welding Supervisor..
I. PWET clip tack welds, type size, and heat number of filler material, welder I.D. number, and the type and heat nesber of attachment material shall be recorded in the " Remarks" section of the Weld Traveler.
J. Tack weld clips shall be removed by grinding and the area from which removed shall be magnetic particle or liquid penetrant exasined.
O PAGE 58 0F 67 1
l
WM-1.0 RE*iISION 2 6/8/82 K. There shall be a spare thermocouple installed in the event of a recording thermocouple burnout.
L. For structural welds, the recorder thermocouples shall be placed as required to record the temperature along the length of the weld and heated band.
M. Unless otherwise specified by this procedure or the applicable code, the heated band shall extend a minimum of 2 times the nominal thickness of the material on each side of the weld and shall encompass the entire ciru=ference of the item.
N. Thermocouple ends shall be covered with high temperature putty to prevent inaccurate readings.
~
O. During the holding period there shall r.ot be a greater difference than 100*F throughout the portion of the part being PWET.
516.4 Except as specified by the code for ?-6 and P-7 material, the rate of heating and cooling above 800*F shall not exceed 400*F/ hour divided by the maximum thickness, but in no case more than 400*F/ hour. Regardless of thickness, the rate of heating and cooling need not be
% less than 100*F/ hour.
5 17 ANSI B31.1 Post Heat Weld Treatment Requirements. i 5 17 1 Welds shall be post weld heat treated in accordan! ce with the requirements of figure 5.17.l(a).
517 2 Notes following figure 517.l(a) shall be referenced and utilized for PWET operations.
PAGE 59 OF 67
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WM-1.0 REVISI0tt 2 O 6/8/82 O "cETIIIS 'H) F#DTIGY Eh?
Pn:pe."' ass & hm Fet:11. T .rg M:Ltar.'.al Eeirst Jdrad N b. Ihr.'.rni Max. ICn.
TJP d W.d 'Ihidm:s Bep2tei Prtent 04 Sect.'420}X Ca:tw % Pc:'d. "
i M wm 1.m.in'rg y* Yem, in 1u*'au 2 i V.:V MC itf!$ ... <
UBte.t'2' 1 k W ' ati D CVt:P A u w" . CO l V.JJ sr3 a::E: c.O 1IN' I s w e less l or u.:u ...
G T y v" to GW U.$ d.D 1 1/2" pkTa CB:;121 au P,C" y+ T M ... d.M r1L.ar,!,n wW W Naer 11/2' j u w.um, exwpc ~ w.a in yo" cc Laa G.c or aass d.M e:mt .-1m, pnwidsi ,e.d prusi e <p1*-
Gr.3 f%t*m is ::Ide in spil T gutter thicknees thn Wct'*m eld azuums, ,ec mrg rurgusaxe- ud' T mss v.c T .ess d.U MtBinirg nEter' tD JIB K b 7. M4 natec!al Cimmterin;;.at omt e T sxset v d' T .tess 0 4 w ages 4.0 wW in r *.sn ail 5+m 0 1-) T aess dM 4 clu 'e r a a.: w.lcsin y an tWes Ath rmiral 0.D. 4" e ess ati v e' T .ess (Un) i.;n. ;3o; wW 7 .
GLMet1EOa.L C ::0 WACS in ;1p au 1/d' T AEBs V.13 CC mss .1.D t2tes 4th cart m n!pca:eri dxunitm ,
3 03 x less arzi rc::iral 0.D. 4" T less ati a**:v+t:zrt welds
] 'y 4?) aC Had #!* 421 MC. I, 20" @ . Jins U.A w .ussa ...
mb. 8, T Nb. u3 f'11- eetal 1, j zcr N tt$31r WL nE O!!q.IIIB1 Mii', ... ... .$.U see to so FEIE5 515.4-A(b) ASE GKE 3 PAGE 61 0F 67
, . . o
'4M-1. 0 REVISIOli 2
^
EEfIDS ':D FidCEFl PS2 i Prg:e:*:ies & :htedal(s)
Beirr Jcimi N D. Ib."dml .\bx. Min.
W Sect A,
L-
'hed'M h ess Tep tted Cartat %
Pmmt Fra'd,*F a iu m a un ' em as v.w c es ...
cated311.m 1/2"mm .v.xc 're as, =
ail less cuer t uv m 0 9 ce _ess e 11/2" ce less ya"cras i ci.er 0 3 ...
OWP 9't" "O CV'SP U.S d 1 1/2" blaaet pl.h T M' au .PA y*,' T .ess ... &
WW .yn h"' a C'.T 1 1/2' d
N All *-.ds 1/d" T less 0.25 cr le=s 200 GP. )
4 m ecs .n r-;as cc == nm n=.s se cc a v.13 cc e a 0.D. 4" ce h a su i. m m pt;ns cc :.res am arcua vc cc mes v.17 cc.ess 3
-W d2u::ius 3 2 ce less mi rz::::imi 0.D. 4" cr less
( yA,b.
% aD 41U we wlm icio. I, 90" cr M 0.W Cr adss ...
8, ce Nb. 43 PNenl FnFE 515.4(c) /GE (11E SF . . .
- w'
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PAGE 62 0F 67
- x. _ ._ _
'dM-1. 0 REVISION 2 6/8/82 DlE:4TDS 'ID F#DCCF2 F.E W A cf P.mm It*E.::17!tter!.al(s)
Esiru Joinsi M2&ml Mut. Min.
Nb. Pntent
'Spr cf 'deld 'Ihidenss bsLJ Pa2'd,CF p' 20m. EC Cuttn. %
A.u. m.im, ex=;:: ve 2 ccsc.q a- i b," ce mes 0.s cc .ms ...
cr paum.cs *.c tra 'tsaal mell, in u.S cc 2.:s dA>
c'. T i u ,' :o caterial 11/2' ari less 1 1/2' y*" Cr ia'et O'.tr V.N ...
CWr is" 00 c'. T V.f) dl) l i 1 1/2" mar.::22.23 @ y 9" T 253 ... dJJ j 1 .=1.u.fC w.Ida!r.V4['cer ::ater 11/2', exmpe ,
l-w.Ida atta21rg rre=las T.smum tD tfB M -d 1 bed.1 ALL Weim dEtaT.'.'IV, ID22.las W2.m II2C:."B.L y +' T .Less ... dAJ
! I.E. 2" stiless
.*41IE 515 44(d) ASE CEAS5 ?E 9*
~.
4 W
j PAos 63 0F 67
. . o WM-1.0 REVISION 2 6/8/82
\
' ~#
(1) Min!cua Iwdrg tre at Tegedae N b. Ibitrg Fbe Wii F.4 mss Ghx*.:In) (2)
IX 1/2' cr le=3 Over 1/2' G e 2' m 5" G T 5" to 2" e m. pu.s e c. p:.us 15 rdn. erh 15 cf.n. each 1, 3 12120? % dn. 1 h ./in. xH'+'eral ad ."m irm av ir=h cr 2 inmes 21:tirs D W. M .
15 c:in. e 4 1EC-1250*F T c:i" 1tr./in. Itr./in. edt**aal irEIl G T 5 intes
- 2. O 3 T. W ex:g% N3, 15 dn. e Gr. 4 1250-1 M 30 cdn. 1 tr./in. 1tr./in. adt**.cnc.
inch s w 6,Gr.4 1100-1500 F 5 intes p x. pu.:s 15 min. edi 7 13D-1G F 30 :::in. 1tr./in. 1tr./in. ad1**.cral irrfi sw 5 irrms 11 and 11A 1100-1250 F 'O dn. Itr./in. 1tr./in. 1 h ./in.
_3, _
cn F-1 tese . BE raitime spimi rrr g**M'ai
- etal'4rae .5 pcrtai cutn cer*m is nct nere tim 0.'c (1) All *6*es are ::etal tepemuzes. ~
(2) tidass & tin ti'.ider cf tin caterials tairs EE.
FnIE 516.1(a) ISE SEEDI III I2SS O
PAGE 64 0F 67
WM-1.0 REVISION 2 6/8/82 J
O' .
FIGURE 5 17.1(a) ANSI B31.1 ITEMS (1)(2)
ASME POST WELD HEAT TREATMENT TIME CYCLE Sect. IX (3)(4) (5 ) (c ) (7 ) lo ) (9 ) (3)(4> Min. Time P-Nos. EKin. Wall Temperature, Hr./In. within and Other Range, *F of range, Min. - Max. wall hours F-1 Over 3/4" and 1100 - 1200 1 1 T .30% carbon F-1 Over 3/4" and 1100 - 1200 1 1
> .30% carbon P-3 Over 1/2" 1200 -
1350 1 1 P-4 over 1/2" or 4" nom. 1300 - 1400 1 1
- size or > .15% carbon P-5 Over 1/2" or 4" nom. 1300 -
1425 1 1
< 5% Ca. size or > .155 carbon P-5 All walls 1300 -
1425 1 2 I 5% CR.
P-6 All walls 1400 -
1500 1 2 P-8 All walls- None required n/a n/a ,
NOTES APPLICABLE TO FIGURE 5.17.l(a):
(1) Not applicable to dissimilar metal welds.
Annealing or normalizing PWHT shall be in accordance with
~
(2) the WPS(s).
- (3) Butt weld thickness is the tnicker of the two abutting ends I af ter end preparation, including I.D. machining.
(4) Socket, fillet and seal weld thicknesses are their throat thicknesses for pressure retaining and non-pressure retaining welds.
(5) PWHT temperature listed for each P-number is a recommended maximum temperature.
O-i PAGE 65 0F 67 i
O WM-1.0 RE7ISION 2
- J MCTES APPLICABLE TO FIGURE 5.'17.l(a) (CONT'D): J (6) Heating rate for electric resistance is:
(a) For thickness 2" and under, the rate shall be 600*F per hour maximum.
(b) For thickness over 2", heating rate shall be 600 F per hour divided by 1/2 thickness in inches maximum.
(7) The weld shall be allowed to cool slowly in still air after wrapping the weld in insulating material.
(8) The minimum width of the PWH'T band shall be the width of the weld plus 2" on each side of the weld, including branch connections.
(9) Process activities shall be in accordance with 5 16.3, except as modified herein.
5 18 AWS Dl.1 Welded Items Post Weld Heat Treatment Requirements.
5 18.1 AWS Dl.1 welded items, when required by the construction design specifications or new design specifications, shall be post weld heat treated in accordance with specific instructions prepared by the Welding Supervisor, or his designated alternate. ;
5 19 Post Braze Heat Treatment. .
5 191 ASME Section III Class 1, 2 and 3 Components; ANSI B31.1; and AWS Dl.l.
A. When required by the construction design specifications or new design specifications, post braze heat treatment shall be in accordance with specific instructions prepared by the Welding Supervisor, or his designated alternate.
5 20 Non-Destructive Examination.
5 20.1 ASME Section III Class 1, 2 and 3 Components.
A. All ASME Code welds or brazed joints, including repairs, shall have the appropriate NDE specified on the Weld cc Braze Traveler, respectively.
O PAGE 66 0F 67
. . a. ,. .
WM-1.0 REVISION 2 s
- 6/8/82 I
('_e) -
s- B. Personnel performing the applicable NDE shall be qualified in accordance with the requirements of A-NQCP-8 or SAP-302, as applicable. .
C. Non-destructive examinations shall be performed in accordance with the requirements of approved Quality Control Inspection Procedures, T-NQCP-2 through T-NQCP-9 or to approved contractor procedures which meet the. requirements of SAP-302, as applicable.
5.20.2 ANSI B31.1 and AWS Dl.1 Welded Items and Supports.
A. When required by the applicable construction design requirements or new design specifications, non-destructive examination personnel, procedures, and documen*,ation shall meet the requirements of 5 13.1 above.
5.21 Removal Of Items Joined By Welding j
5 21.1 The item or component may be removed in accordance with the requirements of SAP-133, when required, and in accordance with this procedure by machining, grinding or shearing. _
s 5.21.2 Removal of items or components by thermal gouging processes can only be performed with specific written instructions from the Welding Supervisor. Such items or components shall be preheated in accordance with the requirements of this procedure. Thermal gouging processes shsil be followed by machining or grinding to sound metal.
5 22 Calibration ,
5.22.1 Welding equipment instrumentation and post weld heat treatment recorders shall be calibrated in accordance with SAP-141.
PAGE 67 0F 67
SCUDI CAROLHIA ELECUlIC AND GAS CCtGA!TI W4-1.0 ATIAC'r0Eff I PAGE 1 cf 2 Q
\ /
hEDHD PRCCEUPS SPECIFICATICtl EEVISION 2 v
WPS. No. _ WPS Cesigr.ation Rev. Date 1.0 SUFFORTHiG PCR(s) 2.0 WEIDHiG PECCESS(es) 2.1 TIPE 30 SCOPE 4.0 SINEAES 50 PRCCEEUP2 VAF.IAELES: AS WELCED:
Tnk W/M Prge :CI. MAX.
51 BASE METAL Thk F/'4 Fanse :C1. MAX.
BASZ METAL __
Pipe Dia Fr.ge :CI. MAX.
P No.(s) ',
P lio.(s) POSIWELD HEAT TEAU D:
Group (s) Tnickness Pange :G1. MAX.
Other Pipe Dia Range IGI. MAX.
52 MIWTIWr.LUS FRCCEUFZ VARI)m:
- 1. LAYER No.
- 2. WELDDiG PRCCESS I
- 3. FTilFR MEIALS
- a. AWS Class G b c.. FSFA/AWS No .
- d. A No.
Stec No.
- e. Cons e hle Insert
- f. F111er Metal Dia. _.
- g. Flux Class
- h. Wire Feed Soeed
- 4. NON CCNSUMAPTR CTFMPLDES
- a. Tyoe i
- b. Soec I c. Class l d. Electrode Dia.
- 5. GAS ('. Cam /Flowrate)
- e. Shielding (Flcwrate)
(". Ca::cosition)
D. BacKir.g (Flcwrate) ~
(% C N iticn) l c.Tm411T (Flowrate)
(% C - sition)
O. 'EERNICUE
- a. Strinzer/ Weave
- b. Orifice / Gas Cup Size
- c. Cscillatien I d. Centact Tube to l Werk Dist.
I e. Mult/ Sirs:le Electrede l f. Travel Soeed (in/ an) l 7. F F E CAL CHARAC m tISZICS l A. Polarity I I i i v 'I I
_. ~
W 1.0 ATIACHGE I PAGE 2 of 2 REVISICN 2 SCUDI CAROLINA ELEC'IRIC AND GAS'COMPA!TI WEIDING PROCECCRE SPECIFICATICN WPS No. WPS Designation Revision Date 5 2.7 :~ W lCAL CHARACIERISITCS LAYER CCRTd2C i VOUPAGE 5 2.10 P.;I-ST 5 2.6 POSITICN Position of groove Preheat Temp.
Weldir4 Progression Interpass Ter::p.
Other Preheat Madntenance Other 5 2.9 TFricICUE 5.2.11 POS"dEID EEAT 'IFnNE Initial /Interpass Cleaning Temperature Range Method of Back Gou61ng TLne Range M.11t/ Single Pass (per side) Other Other 1 5 2.12 JODE DETAM l
~
Joint Design-Backin6 Mat.
Other -
5 2.13 AmwNAL DEIRLETICNS:
1 DE REVmvED SY DATE FREFARED E DA2E I5 sow BY DAIE O AF.%rg HI l
. \
-c. : a. !
l
'nM1. 0 SCUIH CAROLDIA ELECIRIC AND GAS CCMPANY ATIACIEGE II PAGE 1 of 1-
- BRAZDG PROCEDCPE SPECIFICATICH (EPS) !EVISIOi 2 Ccmpany Name -
EPS No. Date Supporting PQR No.
Revisiens Brazing Process (es) Type (s)~
SASE. METALS (QB-402) FiCW POSITICN (QS-40'/)
Flcw Positten(s)
P-No TO P-No. Method of Applying Filler Fetal "hickness Range (face feeding, preplaced rings, snims, spray deposit, claddire, etc.)
Methed of Precleat. v Other Other FIlla MEIALS (QB-403) Joints (QB-400)
, F-No. Other Type of Joint (s) l ASME Spec. No. Joint Clearance l AWS Class No. Iangth of Cverlap t
Size a/o Shape of Filler Metal Other e other j -cRAZHG 5:4PERAIUPS (GS-404) POSISRAZE HEAT TP2AS!EE Temperature P.ange Type of aging ce stablizing thencal Cther i
BRAZING PROCESS (QS404) P0cil:stAZE CLEANING (QB.-409) l H-No. Other Method of cleaning
' Cther .
FRAZING FLUX CR A2MCSPhuE (QB-406)
Flux Trade Name or Composition At:tcaphere for Furnace Brazing (name or ta de designation of tPA fuel used ce the nane ce trade designation of the sps cernpressing the am i ldre (hydrogen, Anno-Gas, etc.) and a statenent mgarding the designed character of the fumace at:nosphere, e.g., whether it is mduedrg, decarburizirs, 3
inert. etc.)
DATE APPROVED BY: DATE
-'REPARED BY:
. VIEWED BY: DAE ISSUED BY: DAS
-r m.+.m,-- -----------my+y-- . w-- - -m- - -w w ny- =r * -------v* - - ---e
. s . . .
SOUDI CAROLINA ELECTRIC AND GAS CCIEANY WM-1.0 WELDDiG PROCEDURE ATTAC9E2E III QUALIFICATION EECCRD PAGE 1 of 2 O,.~ PQL~*
No. PE/ISION 2 1.0 SUPPO!EDIG WPS(s) DA'IE 2.0 ' KELDDIG Po.0 CESS (es) 2.1 TYPE 30 SCOPE 4.0 SIldOASDS 50 PRCCEDURE VARIAM R:
51 J011ir DETAILS: Joint Design Eacking Mat. __
Other t
52 BASE E G : 5.o POST 4 ELD iiEAT 'DiEAET:
Material Spec (s) Tenperature Range Grade (s) Time Panii;e
, P No.(s) to P No.(s) 5.7 GAS:
'D11ckness .Malding (". Con:p)
Pipe Dia. Flow Pate Other Backirs (% Cec:p)
Flow Rate 53 FILLER METALS: Trailing (% Ccep)
F No. Other Flcw Ba*a i A. No. Otr.er SPA Spec No. 5.8 'IEchWIGUE: '
AWS No. (Class) String or Weave Bead Size of Electrode Orifice / Gas Cup Size Consunable Insert Initd e terpass Cleaning Other Method of Back Gou61r4 54 POSITION: Oscillation Position of Groove Contact Tube to Work Dist.
Welding Prqi!;ression I Mt/Sirge Pass (Per side)
( 55 PREHEAT:
! Preheat Temp. Mt/Sirge Electrodes
' Interpass Temp. -
Other Preheat Maintenance 59 ODER PROCEI11RE VARIAN FR:
WM DING PROCESS LAYER NUMBER TPAVEL SPEED in/ min
, AMPERAGE EAIKiE l
POLARITY l VOLTAGE RFG RODE DIA h,m
'IUNGmd m5 im R MEEAL DIA.*M pr0E OF MEIAL UJ&mt Jl %utn :c D m .:.D
W 1.0 6.0 TESTS, EXAMINATI0 tis AND INSPECTICIIS ATTACH 4ENE III PAGE 2 CF 2 6.1 TEISILE TEST: Test Recort No. FE/ISICN 2 Ulti::: ate Ulti::: ate Character of Speci:::en Width '211c'c .ess Area Total Load Unit Stress Failure i Locaticn No. (iri. ) (in.) (in. ) (ib.) (esi) 1 6.2 GUImn EBID TES"S: Test Retort No.
Tvre and Fimare No. Result I
6.3 TCUGEESS TESTS: Test Retort No.
Spectren Noten Noten Tesc In: pact Lateral Exo. Creo Wei:nt No. Location Tyre Tec:o. Values 7. Shear Mils Ereax No Break l
I 6.4 FTTn'r '4EID TEsr:
Test Report No.
Pasults Other ,
6.5 !;CND wmUvd/E TEST /EXAMDTATICN:
Type of TestAxa:nination Testa,xamination Faport No.
Pasults Other 6.6 VISUAL DISPECTION/EXR4DIATICN:
Inspection Report No.
Results Other 6.7 UTHER TESTS /EXAMDIATICN(s) CR VERIFICATICNS:
Type of Test /Exa:Lination Test / Examination Paport No.
Results/ Deposit Analysis Otter 7.0 WELCEBS NME/ID 8.0 PRCCELCRE GUALIFICATICN SLTERIISED BY 90 '4e certify that the statements in this record are correct arxi that the test welds were preptred, welded and tested in accordance with the reglirements of:
DAH. Pfi m ED El CA'IE A PRE. PARED SY U AP.O.CVED SY DATE ISSCED SY DATE
,-o....., . . .
SCUIH CARCLDIA ELEC".BIC NID GAS CC.M?NiY % 1.0 ATIACBG2R III-A BRAZING PROCEDUPS QUALIFICATICN RECCRD (PCR) PAGE 1 0F 2 R5VISICN 2 3
a pany Name FG No. Cate EPS No.
Era:ing Process (es) Type (s) l Jon!TS (GBJC8)
Type of Joint (s)
Joint Clearance length of Overlap Other Joint Design Used EASE !CAIS (QS-402) ERAZHIG PLUX CR AT8.OSPb2F2 (QB-406)
P-No. to P-No. ,
Flux Trade Name or.Cca: position Material Spec.
Type cc Grade Atmosphere for Pumace Brazirs l
'Ihickness sv.ethod of Precleaning (r.?ne or trade desig.atien of the fuel used er the name er trade desig.atien of the gas Q ther i
compressing tre atmosphere (PJd:~ ogen, dissociated anmcnia, etc.): and a statement
.6 MEI'ALS (QB-403) resa: ding the desigrad character of tre furnace atmosphere, e.g., it. ether it is F-No. Other reducing, decarburizing, inert, etc).
ASME Spec No.
XdS Class No.
Size a/o Shape cf Filler Metal FIN POSITICN (QB-407)
Otree Flow Position (s)
Method cf Applying r W er Metal BRAZING UNPEFA11.RE (QB-404)
(face feeding, preplaced rings, sr2.s, spray 14.,perature Range desposit, n'a m ng, etc.) ,
Other POSIBRAZE HEAT 'IFIADGIC (QB-409)
ERAZEiG PROCESS (QB-405)
Type of aging or s**M1**ing ther=al treatment l E-No. Other after brazirs-Other l I
4
^~ . ,
SCUDI CAROLDIA EI2CmIC #iD GAS CCMPMlY WM-1.0 ATIAQiMENT III-A SECTICN IX - PA?5' QB, BRAZING PAGE 2 CF 2
/'
REVISICN 2 Full Reduced Section
' ENSILE 'IEST (QB-150) .
Dimensions Ultimate Character of Specimen Total Ultimate Failure and No. '41dth fhick O.D. Area Lead, lb' Stress, esi Locatien 1
GUIDED ESID TESTS (QB-160)
Results Type and Figure No. ,
B ODER 'IESTS l
pe of Test l 'Other .
Brazer's Name Clock No. Stamp No.
Tests Cmducted by: Laboratory Test No.
We certify that the statements made in this record are correct and that the test brazes were prepared, brazed and tested in accordance with the requirements of Sectim IX of the ASE Code.
PREPARED BY Date APPROVED BY: DATE REVD!WED BY Date ISSUED BY: DATE -
l s l
I O-
W 1.0 O SCUIH CARCLOTA EIECTRIC #D GAS COMPRE WELED1 STRIDARD QUALIFICATICN RECCRD ATTAC'2CC PAGE 1 CF 2 c I'l PE/ISICN 2 NME (last, First, Micdle) Soc. Security No. Sit::ol
~
Standa.~d Qualificatien Test No. Rev.
Faterial Specificaticn & P So. Thickness Fange Pipe Outsice Diameter to MED SY/CAE Qualified for WPS(s, smD sST RESuLrS Pos.i Seeci:ren 1 Results l Pos.1 Sceci m Results F 50 Face Side I! 2G Face Side I or Face Side Root Side J P 6G Rcot i Side 5G Face i Side
.E Root i Side Rcot i Side Pos. Specimart 'Results Pos. ~ Specimen Results F 10 Root Side 3G Root Side L Face Sida Face Side '
A 2G Root i Side 40 Root '
Side I T Face Side Face Side Pos. Scecimen Results Pos. Specimen Results i 1? Fracture 3? Fractureu I Macro Macro L 2F Fracture 4F Fracture L Macro .%cro E
T RADIOGRAPHIC TEST FISULTS Pos. Results RT Report No.l 1Pos. Results '
RF Reoort No.
F 2G F 1G I 5G L 2G F 60 A 3G E I 4G E
TEST INFCRMATICN
( ) Ocidnal Test ( ) Retest ( ) Minime. cf six hours tradninz ccepleted l We certify that the statements in this report are correct and that the test welds were
- prepared, welded and tested in accordance with the mquirements of ASE Section IX Code.
l
. . - - - - . - - - . - - - - - - _ - - _ , - - --..-----,_,.n. --, - . . , - . - , . . _ . - . - - ,, - , - - . . . -
. i
. s s
. W1.0 ATIACHelNT IV PAGE 2 0F 2 RE'7ISION 2 PP.0 CESS- STANDARD CUALIFICATION EST No.
MATEP.IAL FIGURE CW 463 DATE:
POSITICil(s) 'D!ICiGiESS PIPE DIAPr u J0rfr DE3ICI Torch Gas Type BacKir;j; Gas Type Freneat & Weld Current ?/pe and Flow (CMI) ard Flow (C M)* Interpass Progressien- arxi Polarity Temp Parge
- Two layers or 3/16" whichever is greater Layer Welding Filler F Tungsten Filler Wire Slope ,
No. i Process Metal No. Diameter Metall AUS VOLE '
Feed Turns Diameter IFM i
PPIPARE M CATE PEEWED E CAE CAE ISSUED E CATE LPPRCVED E
. , . , , , , - -, -,-.,,.,e.,.,,,.v.,,,--. .u-.--, -. . - . - - - -., - - , - , - - - - ,-.n
.s 1 -
SCUIH CARMA ELEC'IRIC MO GAS CC4PArn W-1.0 ATIAClE4ENE V WEIDER PERFCFFRiCE PAGE 1 0F 1 CCelIINUITY PECRD PR ISION 2 WPCR NAME SIMBCL DNIE o PFLCFSS WEIDnn TIME mmj WEIDnD SUPERVISCR
~l 2
3 I
4 5
6 -
7 8
9 10 11 __
12 13 14 15 16 17 18 O 21 22 23 24 25 26 __
27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45
- 9 ,.
- m. .
WEID 'IRAVELER M4-1. 0 P
MCIage _ 3c' V. C. SCW.ER NUCLEAR SIATICI, UTIT 1 SCUDI CARCLHIA :"dCTRIC & GAS CO.
ATIACE S T VI PAGE 1 CF 1 G
PElISICN 2.
SYS'DC4 cc CCGCET Ed No.
O bg)No.
v CCOE & CLASS MNIERIAL 'SiICi0iESS DIAMER FFJ gi3I/Li & JASS Si? FW ' fES
& @ & u) NO
'fc.LDE.A' FRCCE!JJRE FC M/GtIAL hie EQ'O PREP ;;SS SIGiAIt.FJ/DA E
- 8) 10 (/d /2 Q.C. HISPEC"CR _
l I ANII PRLCESS CHECK POINT 5;GiiENCE vf) H Verified / Late (/4 iH Verified /Date /ff) l A Joint Cler.11 ness T I !
S Pcesible L1.ited Access TIS NO ' '
I I i u C Excavatten NEE L l l l D Check Fit-uo I ~
i I i t --
1 E Purre (incitx11nz Sack Purce) i l 1
? Checx Freneat crior to Rcou Pas.s G Check Back ctt-tn /Grindira H Check Intercass Te.r ersture Checx Interrass Tecterature 1 1 Check Interrass Te=rerature 11 I Visim117 Insrect Ccealeted Weld i I J Checx Delta Ferrite /Recerc fr.
"Recarks"
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51 llc ~.1 MATERIAL HEAT /IDT No. WEILERS NAME ID NO. WELDIMG PROCEICRE GSED/
SIZE & TYPE Revisien a@
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l P4iT ACCEFlID: QC/DAE W/S 69 FINAL ACCEPIANCE/CAE A/M
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[v-:s a Page of l
l SCUM CAROLINA EI.EC'IPlc AND GAS TMPANY M4-1. 0 AIIACW.:M VII l
ERAZER SIANDARD QUALIEdATICN REDORD PAGE 1 CF 1 PRISICN 2 Brazer Name Clock No. Sta=p No. _
Erazing Process (es) Typess)
In accordance with Brazing Precedure Specificatien (EP.S)
Ease Metal (QB 4C2): Faterial Spec. to cf P-Nn. To P-No Type or Grade _
'Ihickness Plate or Pipe Diameter Filler Metal (GE 403): ASE Spec. No. AWS Class No. 7-No.
Otrer Bracing Ter erature (QB 4C4): F.ange Brazing Process (QS-405): H-No.
Brazing Flux (QB hC6): Trade NarJe or Ccr::pesitien At=csphere fer Fu..T ace Bracing Flcw (QB-407) Positicn(s):
Methed cf Applying Filler Metal o Joint (QE 408): Type (s)
Joint Clearsnee -
Length of Overlap Cther l -
PEEL CR SEUI'ICNING 'ISST RESULTS (QB-170 or GB-180) l Flow Positien T70e and Fie. No. Results t
Tests Conducted by: Laboratory Test No.
We certify that the statements made in this record are ccrrect and that the test brazes were prepared, brazed, and tested in accordance with tre mquirements cf Secticn IX of the ASME Code.
NCTIE: Any essential variables in additien to those above 2.all be recorded en an ATenhic to this attac.%cnt.
PREPARED H: DATE PW T5e~iD BY: CATE APPROVED E: DATE c<
( ) ISSUED BY: DATE C' l
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. *~ , ,
NAME 'aM-1.0 ATIACFair VIII ID No. PAGE 1 0F 1 (if applicable) RE7ISICN 2 WlEER ID No.
Ini**ials Initials CNIE SCO?E OF 'IRArmiG of Instmeter EXA' O ATICN SCCPS of Exa:-h er
- and Cate (if a
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C l l : 1 D Check Fit-uc l 1 '
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? Checx Preceat crior to Em:1ra l G Check BacXMar/Grindinz li Check Interrass Tec:cerature Check Intems Te=reratura 1 Check Intertass Tecrerature 1 I 4
'l I Visuall'; Insrect Cc==leted Brace l t Joint W l i NV FILLER MATERIAL HEAT /IDT No. ERAZEES NAME ID NO. ERAZRJG FRCCEDUP2 USED/
SIZE & TYPE Revisien m b b b b b
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SOUTH CAROLINA ELECTRIC AND GAS COMPANY 1 VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS I
o WELDING MATERIALS PROCEDURE WM-2.0
-REVISION 2 JUNE 7, 1982 NON-CONTROLLED SAFETY RELATED C0PY W . .) . $~- Ah*
_ Q 2 o-Tr b QRIGINROR (or ,this revision ) Date th w w ALIFIED REVIEWER V ~ 23 SL Date
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App roved:
. .. f.- Z. Y-W .
ASST. MGR. MAINT. SERVICES Date N
OCT. O 1 1982 O
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a WM-2 PAGE 1 REVISION 2 6/7/82 i -
LIST OF EFFECTIVE PAGES t
} PAGE ,
REVISION I' i 2 i 11- 2 1 2
~2 2 3 2 4 2 5 2 6- 2
, ~7 2 9 2 ,
j 10 2 i
- ATTACHMENTS l ATTACHMENT I -
2 i
- . ATTACHMENT II_ 2 ATTACHMENT III 2 ATTACHMENT IV 2 -
ATTACHMENT V 2 I
ATTACHMENT VI
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2 ATTACHMENT VII 2 T
P rvr- y,- v v,- ww- y y --n .r-,.==w--,-"r-*w
- WM-2 PAGE 11 REVISION 2 6/7/82
() . TABLE OF CONTENTS 1.0 PURPOSE OR SCOPE .
2.0 REFERENCES
AND GLOSSARY 2.1 References 2.2 Glossary s 3.0 RESPONSIBILITIES 4.0 GENERAL .
5.0 PROCEDURE 5.1 Documentation 52 Rod Room Control of Welding and Brazing Material 5.3 Rod Room Issuance Control of Welding and Brazing Material 5.4 Field Control of Welding and Brazing Material I~D 5.5 Rod Room Return Control of Welding and Brazing Mate ~ rial V
5.6 Authorized Nuclear Inservice Inspector ATTACHMMENTS ATTACHMENT I - WAREHOUSE WELDING / BRAZING MATERIAL ISSUE SLIP ATTACHMENT II -
WELDING MATERIAL RECEIVING RECORD
~
ATTACHMENT'III - HOLDING OVEN TEMPERATURE RECORD ATTACHMENT IV -
LIST OF PERSONNEL AUTHORIZED TO RECEIVE WELDING AND
/ BRAZING MATERIAL ATTACHMENT V - FIELD WELDING / BRAZING MATERI AL REQUISITION ATTACHMENT VI - PORTABLE CADDIE TEMPERATURE VERIFICATION RECORD i
ATI'ACHMENT VII - TRAINING RECORD (a~3
T -
,] - .
.( n, j WM-2
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REVISION 2 ~
6/7'/82 ,
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( ,) 1.0 PURPOSE OR SCOPE p A' 1.1 This procedure est.iblishes and implements the methods' to cont roI-procurement, storage, issuance and proper disposition.of unused and used welding electrodes. ,
2.0 REFERENCES
'ANDGbOSSARY s-
, i
- 2.1 References <
2.1.1 Administration of Maintenance Welding S AP-302 and lates t approved revision.
2.1.2 ASME Boiler d Pressure Vessel Code Section-II Part C current edition and addenda. a 2.1.3 ASME Boiler and Pressure Vessel Code Section III 1971 edition through summer 1973 addenda < for code piping installaffom-and original construction requirements for other code and safety - related items.
2.1.4 ASME Boiler and Pressure Vessel Code Section IX current edition andj ddenda.
[) 2.1.5 ASME Boiler and Pressure Vessel Code Section XI 1977
\~/ edition through summer 1973. addenda.
2.1.6 Welding Maintenance Procedure WM-1 and latest approved revision.
2.1.7 Receiving Inspection QCP-R1 and latest approved revision.
2.2 Glossary and Definitions 2.2.1 Brazing Material - non-f errous electrodes , wire, strips, backing rings, lao rings, and flux tsed to join metallic materials together by capillary action of a liquid between two closely spaced solid metallic pieces.
2.2.2 Contaminat=' - undesirable element: such as cast, oxides, !
scale, et -
2.2.3 Welditz .a'. 17 - ferrous or non-fer.cous, as applicable, I bare w<ee, Lo.H spool wire, bare spool flux cor,e wire, backing rings, consumable inserts , and covered ~or uncovered electrodes used to join metallic materials by fusing the welding material to two specifically spaced metallic pieces and to itself.
b
(_f 2.2.4 Radioactive Contaminated - undesirable source of I radiation.
P AGE 1 0F 10
- HM-2
- REVISION 2 I 6/7/82
. O) t, 30 RESPONSIBILITIES 3.1 The rod room attendant has the responsibility for control of welding and brazing materials in the rod ~ room including, but.not limited to, warehouse procurement, receiving, rod room storage ,
and issuance, and proper dispositioning of, unused and used electrodes.
3.2 The welder and brazer, as applicable, has the responsibility for field control of welding or brazing material including rod room sequisition, transporting electrodes to work area, field storage, application in accordance with the appropriate WPS(s) or BPS (s), returning unused electrodes to the rod room and proper disposal of used electrodes.
33 Welder or brazer assistants , if any, may have the responsibility for rod room requisition of electrodes and
< transporting such electrodes to the work area.
3.4 SAP-302, " Administration of Maintenance Welding" establishes, describes, and delineates the responsibilities of other personnel associated with Maintenance Welding Program.
l 4.0 GENERAL
\,/ 4.1 All procured and received safety-related welding and brazing' materials shall conform to the requirements of the applicable code and the purchase requisition.
4.2 All required documentation shall be received from the supplier prior to, or with, the welding or brazing material, as applicable.
4.3 Welding material, brazing material and the applicable documentation content shall be inspected upon receipt in accordance with QCP-Rl.
4.4 Any broken or unsealed containers shall not be received from the warehouse.
! 4.5 covered welding electrodes shall be transported to the i
applicable rod room and/or rod ovens as soon as possible after issue from the warehouce.
4.6 Rod rooms and/or rod ovens, as applicable, shall be secured by locking when left unattended.
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WM-2 REVISION 2 6/7/82
( )4.7 Rod room attendant personnel shall receive ample on-the-job training and classroom instruction in the proper methods of field storage, issuance and disposition of returned unused and used welding materials prior to their being assigned to these activities.
4.8 Welders, brazers and their assistants, if 'ny, a shall receive classroom and on-the-job training in the proper methods of field storage and control of welding and brazing materials, as applicable.
4.9 Training exercises will be documented on attachment VII of this procedure. These training records shall be issued, controlled, ,
maintained and filed by the Welding Supervisor or his designated i alternate (s) in the employee's plant training files.
5.0 PROCEDURE 5.1 Documentation 5.1.1 The records captioned below in this paragraph shall be issued, maintained, controlled and filed in accordance with the referenced subsection (s) of this procedure:
A. " Warehouse Welding / Brazing Material Issue Slip,"
O-
- Attachment I,. Form VCS 202, subsection 5.2.1.
B. " Welding / Brazing Material Receiving Record," _.
Aittachment II, subsection 5.2.2.
C. " Holding Oven Temperature Record," Attachment III, subsections 5 . 2 . 8 , 5 . 2 . 9 , and 5 . 2 .10 .
D. " List of Personnel Authorized to Receive Welding / Brazing Material," Attachment IV, subsections 5.3 1 and 5.3.3 E. " Field Welding / Brazing Material Requisition,"
Attachment V, Form VCS 203, subsection (s) 5.3.2, -
5.3.3, 5.3.4, 5.4.1, 5.4.11, 5.5.1 and 5.5.6.
F. " Portable Caddie Temperature Verification Record. l Attachment VI, subsection 5.3.6. '_
G. " Training Record," Attachment VII, subsection 4.9 -
5.2 Rod Room Control of Welding and Brazing Material.
O PAGE 3 OR 13 .
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WM-2 REVISION 2 6/7/82
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( ,) 5 2.1 The wa$ehouse Storeroom Clerk shall issue welding or brazing material, as applicable, to the rod room (s) upon receipt of a properly initiated and authorized " Warehouse Welding / Brazing. Materials Issue Slip," Attachment I. The type, size, amount requested. and date shall be entered on this issue slip by the Welding Supervisor or- his ;
designated alternate (s). The Welding Supervisor, or his -
designated alternate, shall affix signature and date in the space " Authorized By." The manufacturer, heat or lot number, and amount issued shall be entered by the
~
Storeroom Clerk. The Storeroom Clerk shall affix signature and date in the space " Issued By." The yellow-copy of the " Warehouse Welding / Brazing Materials Issue Slip," shall be returned to the Welding Supervisor; the pink copy.shall be returned to the rod room; and the white copy will be retained by the Materials Section.
5 2.2 Upon receipt of welding and/or brazing material f rom the warehouse, the " Welding / Brazing Material Receiving Record," Attachment II, shall be initiated and ' completed by the rod room attendant. The type , size , heat or lot number, manufacturer and amount received shall be entered on this record. The rod room attendant shall affix signature and date the reco rd in the appropriate column.
Between the 1st and 10th of each calendar month or when n/
N-the welding / brazing material receiving record has- been completely filled out, whichever comes sooner, the rod room attendant shall forward this record to the Welding Supervisor for retention in a suspense file for one year.
The rod room attendant shall maintain a copy of this record until all the listed applicable materials have been issued or otherwise utilized.
5.2.3 For those covered welding electrodes requiring storage in the controlled atmosphere of a holding oven, the rod room attendant shall attach to the front of each holding oven a sketch which specifies location, by the type, size, heat or lot number, and Q.C. tag number. As new heat or lot numbers are added to the holding ovens the sketch shall be changed accordingly.
5.2.4 Uncovered welding electrodes (bare wire) shall be stored in their original containers until issued for use. These containers shall be legibly marked with size, type, heat or lot numb e r , and Q.C. tag number.
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WM-2 REVISION 2 6/7/82 (m)
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5.2.5 Stainless steel covered welding electrodes shall not be placed into holding ovens containing carbon or low alloy steel covered welding electrodes. ,
5.2.6 Code and safety related covered welding electrodes shall be placed into their respective heated holding ovens immediately upon removal from their containers. Only one size, heat or lot of covered welding electrodes may be placed .
in one location in the holding oven.
5.2.7 The Temperatures shown in figure 5.2.7(a) shall be maintained in the holding ovens for the respective types of covered welding electrodes.
FIGURE 5.2.7(a)
ELECTRODE TYPE AND/OR CLASS HOLDING TEMPERATURE (*F)
E308L-16 175-275 E309-16 175-275 .
ENiCrFe-3 175-275 E7018 200-300 E8018 B2L 200-300 E8018 C3 200-300
(S E9018 B3L 200-300 -
i
(_) Other (Low-Hydrogen) 200-300 5.2.8 At the beginning of each working shif t, the holding oven temperature shall be verified by the rod room attendant and the applicable data, including signature and date, shall be entered on the " Holding Oven Temperature Record," Attachment III.
5.2.9 Should the holding oven temperature not be within the specified range as shown in figure 5.2.7(a) all electrodes shall be removed from the affected holding oven and segregated for proper disposition. Such action shall be noted in the remarks section of Attachment III..
l 5.2.10 At the beginning of each month, between the 1st and'10th, i the rod room attendant shall forward the Holding Oven Temperature Record to the Welding Supervisor for review and filing. This record will be kept in a suspense file for a minimum of 1 year, after which, it may be discarded.
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P AGE 5 0F 10 b
WM-2 REVISION 2
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6/7/82 O 5.2.11 Brazing electrodes shall be stored in their original containers until issued for use. These containers shall be legibly marked with type, size, heat or lot number, and Q.C. tag number.
53 Rod Room Issuance Control of Welding and Brazing Material.
5.3.1 A " List of Personnel Authorized to Receive Welding and Brazing Material", Attachment IV, hereinaf ter may be ref erred to as the." List", shall be initiated and issued by the Welding Supervisor to the rod room attendant. The "
" List" will be revised to remove and/or add names of personnel as circumstances require.
5.3.2 Welding or brazing electrodes shall be issued only upon receipt by the rod room attendant of a properly initiated and authorized " Field Welding / Brazing Material Requisition," Attachment V, hereinaf ter may be referred to as the " Welding Material Requisition". The Welding Material Requisition shall be authorized by the Welding Supervisor, or his designated alternate, and shall specify the welders name, I. D. numbe r , MWR, type ~ and size of electrodes, amount requested, and Q.C. tag number.
5.3.3 The rod room attendant shall verify that the individual receiving the material is authorized to receive such O material ny checking the '!Lis t" .
the Ecd room attendant shall complete the Welding Af ter this ve rification Material Requisition by, entering the heat or lot numbe r ,
caddie number, amount issued; and then, affix signkture, time and date. For safety-related or code welding the words " Safety -Related" shall be stamped or written on the Welding Material Requisition.
NOTE: Personnel training as welders or brazers in the ,
test shop are not required to be on the " List";
5.3.4 The white copy of the Welding Material Requisition shall be retained by the rod room attendant; the yellow copy shall be forwarded to the Welding Supervisor; and the pink copy shall be kept by the welder until the unused and, if required, used welding electrodes have been returned to the rod room.
O PAJE 6 0F 10
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WM-2 REVISION 2 6/7/82 m)'
5.3 5 At the time of issue Safety-Related covered welding electrodes listed in Figure 5.2.7(a) shall be placed into portable caddies. These caddies ,shall be capable of obtaining a minimum temperature of 150*F.
5 3.6 A temperature check shall be performed every six months and recorded on the " Portable Caddie Temperature -
Verification Record", Attachment VI. The temperature ,
check shall be performed by use of a calibrated thermometer. The " Portable Temperature Verification Record" shall be forwarded to the Welding Supervisor to be placed in a suspense file for minimum of one year, af ter which it may be discarded.
5.3 7 Only one type of welding material shall be issued at one time. Examples of the same type of welding material are:
B. E70S-2 and E7018 5.4 Field Control of Welding and Brazing Material 5.4.1 The welder or brazer, as applicable, shall .have in his possession at all times the ' pink copy of the Welding Material Requisition except during periods of
(~%(_,) transporting welding or brazing materials to the work location as permitted by Paragraph 3 3 and after the welder or brazer has returne.d the applicable unused or used electrodes to the rod room.
5.4.2 The portable caddie shall be plugged into an appropriate electrical outlet near the work location as soon as possible af ter covered welding electrode issue from the rod room. The caddie shall remain plugged in at all times unlegs returning it to the rod room or moving it to another work location.
5.4.3 The lid on the caddie shall be kept closed at all times except for the removal of electrodes for welding activities.
5.4.4 The welder or his assis tant , as applicable , shall check the caddie periodically for heat producing capability.
In the event the caddie should be discovered to be defective, the welder shall return it, and the electrodes contained therein, to the rod room and notify the Welding Supervisor or his designated alter.nate(s) immediately in order that proper corrective action may be implement ed .
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WM-2 REVISION 2 6/7/82 m
( ') . 5.4.5 Humidity and other environmental factors permitting,
/ more than one covered welding electrode may be removed f rom the portable caddie for use at one time, however, no more than one hour's supply shall be removed at one time and these electrodes shall be kept in a welding pouch.
5.4.6 The maximum exposure time to the at'mosphere outside the p, ort ble caddie for the various covered welding
', electrodes is shown in figure 5.4.6(a).
FIGURE 5.4.5(a)
(hours)
ELECTRODE MAXIMUM EXPOSURE TIME
~
E308L-16 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> E309-16 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> E7018 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ENiCrFe-3 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> E8018 B2L 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> E8018 C3 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> E9018 B3L 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Other (Low Hydrogen) __,
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5 4.7 Unused electrodes, along with the po rtable caddie , when required to be issued, shall be returned to the rod room
(/}.
s- for proper disposition at the end of -the working shif t.
The used electrodes shall be segregated f rom the unused electrodes prior to returning them to the rod room. Used
, welding electrodes (stubs) shall be discarded in a container marked "Do NOT USE".
5.4.8 Should unused covered welding electrodes exceed the maximun exposure time or become otherwise contaminated, return them to the rod room and notify the Welding Supervisor or his designated alternate (s ). immediately.
5.4.9 Issued uncovered welding electrodes (bare wire) and brazing filler metal shall be kept in the welders or bracer's possession at all times, respectively, except as permitted by Paragraph 3.3
- 5. 4.10 If required, uncovered welding electrodes and brazing filler metal shall be cleaned with Magnaflux cleaner or equivalent to remove grease, oil or other solvent soluble contaminates prior to welding. If contaminated by penetrating oxides, scale, corrosion products or any other non-solvent soluble contaminant , segregate from satisfactory welding or brazing material, as applicable, for return to the rod room.
ul
UM-2 REVISION 2 6/7/82
() NOTE: A small amount of Surface Oxide on. uncovered electrode may be removed with abrasive cloth; l
after which, the uncovered electrodes shall be cleaned using an approved solvent. -
NOTE: Radioactive contaminated welding material shall be j disposed of in accordance with Health Physic-Procedures.
5.4.11 The welder or brazer, as applicable, shall return the pink copy of the Welding Material Requisition along with the unused and used, welding or brazing material, and the portable caddie (if issued) to the rod room at the end of the working shif t.
5.4.12 In the event additional welding or brazing electrodes are needed during the shift to complete or continue welding, an additional caddie may be issued along with the applicable welding or brazing electrodgs. However, all the requirements of this procedure applies to the issuance, control and return of both caddies along with the respective unused and used welding electrodes.
55 Rod Room Return Control of Welding and Brazing Material 5.5.1 The rod room attendant shall examine returned wel' ding or f) s/ brazing electrodes along with the appropriate pink copy of the " Welding Material Requisition."
5.5.2 If warm to the touch and no other contamination exists,- -
the rod room attendant shall place the covered welding electrodes in their respective holding oven according to type, size and heat or lot number as shown on the sketch attached to the holding oven.
5.5.3 If cold to the touch or other physical contamination exists, the covered welding electrodes shall be discarded in a container marked "Do No Use".
5 5.4 If no deleterious contamination exists for brazing or uncovered welding electrodes, the rod room attendant shall return this material to their original containers according to type, size, and heat or lot numb e r .
5.5.5 If penetrating contamination exists which cannot be j removed by use of Magnaflux cleaner or equivalent, the rod room attendant shall discard the brazing or uncovered welding electrodes in a container marked "Do No Use".
5.5.6 The rod room attendant shall enter the amount of welding or brazing naterial, as applicable, returned to the rod O room on the white copy of the Welding Material Requisition. The rod room attendant shall obtain the
? AGE 9 0F 10
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WM-2 REVISI0tl 2 4.
6/7/82 a
welder's or . brazer's pink copy, as applicable, and atthch '
it to the white copy. These copies shall be forwarded to the Welding Supervisor at least once per week. If ,
required, the white copy (s) .shall be inserted into the !
repe.ir packet by the welding supervisor or his designated l alternate (s).
5.6 Authorized Nuclear Inservice Inspector 5.6.1 For ASME Section XI code welding.or brazing activities .
the applicable documentation will be made available, upon j request, for the ANII's review.
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WM-2.0 -
ATTACHMENT I PAGE 1 0F 1 REVISION 2 (G
Issue Material To:
FORM VCS-202 SOUTH CAROLINA ELECTRIC & GAS CO.
V. C. SUMMER NUCLEAR STATION WAREHOUSE WELDING / BRAZING MATERIAL ISSUE SLIP Material Type Size Date Manufacturer Heat / Lot No.
Amt. Requested Amount Issued Issued By Date tuthorized By Date Copy Distribution: WHITE-Materials Section; PINK-Rod Room; ,
YELLOW-Welding Supervisor l
4
WM-2.0 ATTACHMENT II "
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PAGE 1 OP 1 REVISION 2 O WELDING MATERIAL RECEIVING RECORD
- HEAT or AMOUNT TYPE SIZE LOT No. MANUF. RECEIVED SIGNATURE DATE l
i O s ~
L> .
l REMARKS: 1 1
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WM-2.0 ATTACHMENT III PAGE 1 0F 1 REVISION 2 F) t
' HOLDING OVEN TEMPERATURE RECORD ATTENDANT OVEN ELECTRODE NAME l NO. TEMPERATURE TYPE TIME DATE SIGNATURE l
9
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REMARKS:
,r 3 L)
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- WM-2.0 ATTACHMENT IV PAGE 1 0F 1
, REVISION'2
,y i 1 V . LIST OF PERSONNEL AUTHORIZED TO RECEIVE '
WELDING AND BRAZING MATERIAL NAME S/S NUMBER DEPARTMENT REMARKS l l
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/
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Welding Supervisor /Date
. WM-2.0-
! ATTACHMENT V
- I PAGE 1 0F 1 REVISION 2 O
FIELD WELDING / BRAZING MATERIAL REQUISITION SOUTH CAROLINA ELECTRIC & GAS CO.
V.C. SUMMER NUCLEAR STATION Form: VCS-203 Issue Material To: Welder / Brazer (NAME) WELDER I.D. Number (NAME)
SMAW GTAW GMAW Other ASME/AWS Tyne Size HEAT / LOT No.
MWR CADDIE No.
O AMT REQUESTED AMT ISSUED AMT RETURNED Authorized by: Date: Issued By: Time: Date:
COPY DISTRIBUTION: WHITE-Rod Room; FINK-Welder; YELLOW-Welding Suprv.
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l_,.-..__ _ _ _ - . _ _ _ _ . _ _ _ _ _ . _ - _ . . _ _ . . _ - , , , - _ _ _ _ _ _ _ _ _ _ _ _ . - , _ _ . . ._ . _ _ . , . _ , . - _ _ _ _ _ , . _ . - - _ - - _ - _
WM-2.0'
- ATTACHMENT VI
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PAGE 1 0F 1 i REVISION 2 l A
PORTABLE CADDIE TEMPERATURE VERIFICATION RECORD I
CADDIE NO. TEMPERATURE DATE REMARKS I
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! BY: DATE:
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NAME WM-2.0 ATTACHMENT VII j ID No. PAGE 1 O? 1 1 (if applicable ) REVISION 2 Initials Initials I of Instructor EXAMINATION SCORE of Examiner DATE SCOPE OF TRAINING and Date (if acolicable) and Date i
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