ML20003J332
| ML20003J332 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/21/1981 |
| From: | Belew, Cantrell C, Daniels TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20003J333 | List: |
| References | |
| NUDOCS 8105110279 | |
| Download: ML20003J332 (223) | |
Text
{{#Wiki_filter:r L Sequoyah Nuclear Plant DISTRIBUTION-f 1C Plant Master File Plant Suparintendent -i l' Assistant Plant Supt. (Oper.) SURVETLLANCE INSTRUCTION Assistant Plant Supt. (Maint.). . Assistant Plant Supt. (H&S) !
- Administrative Supervisor SI-U h IC Maintenance Supervisor (M)
1C Assistant Maintenance. Supervisor (M) l f, ____
Maintenance Supervisor (E)- Assistant Maintena'nce Supervisor (E) PRESERVICE BASELINE INSPECTION, Maintenance Supervisor (I) g-FOR TENNESSEE VALLEY AUTHORIll - 17 Results Supervisor e SEQUOYAH NUCLEAR PLANT 1C Operations Supervisor , 10 Quality Assurance Supervisor ! I Health Physics Supercisor 5
- Public Safety Services Supv.
Chief Storekeeper - p Units 1 and 2 Preop Test, Program Coordinator
- 1C Octage Director Chemical Engineer (Results) .
Radiochem Laboratory Instrument Shop f- Reactor Engineer (Results) Instrument Engineer (Maint. I) 1,) 1C Mechanical Engineer (Results) ! [ 1U Plant Services Supervisor A, 1C Training Center Coordinator ! r Prepared By: Belev/Daniels Public Safety Services - SNP Shift Engineer's Office ! [ , Revised By: J A eJ hor m Aid 10 Unit Control Room Health Physics Laboratory ' I,. Submitted By: .. . _ in Nucir Document Control Unit Supervisor IU Plant Superintendent, WBNP Plant Superintendent, BFNP r PORC Review: 2l { Plant Superintendent, BENP j ( th 1U NEB-K ., Approved By: NRC Inspector - SNP _. Plant Hi: nager 1C NSRS-!" t
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' Technical Support Center T
Date Approved: 4 i 2.l JS l 1C Unit Control Room #2 1U Compliance Section Staff Supervisor i i l 1U QCRU - CONST SNP i
- 1U Pro.iect Man wer. Sea.
l Surv. Codes and Standards Sect . - C J' 1U Stup. Metalurgy 9 NDT Section, dua c.b-C 1L. Rev. No. Date Revised Pages Rev. No. Date Revise.d Pages 21,2z,su-s*,st-sy,59,98, h /10 Mg 10 (Cont.) 99, Added 5A,20A,21A 7 All A o/19/70 h_7n Addad hA 11 / ATL , Added Punchlist, 3A,
! o 9/18/80 A9_co . w.v4 n a 1. 9. 7 y.
Revised Punchlist, 1,3 in 9 /pn /A0 h ha q (_1 n 1 C_17 l o 9n The last page of this instruction is Number pal THIS DOCUMENT CONTAINS
T i SQNP SI-114 , I' Punch List I. Page l'of 1 Rev. 11 : g.
- b. i
- 1. Complete Appendix A
. 2. Complete Appendix B l i
X" 3. Add Scan Plan Data ,1 i
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- 4. Identify Exempted Components ar .
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SI-114 3r Cover Sheet Page 1 of 1. 1 Rev. 11 y L Preservice Inspection Program W
- j. Cover Sheet -
T ' 1 Owner: Tennessee Valley Authority , y . .. I Address of Corporate Office: Knoxville Office Complex 400 Commerce Avenue Knoxville, Tennessee 37902 [ Name and Address of Fuclear Power Plant: Sequoyah Nuclear Plant I, P.O. Box.2000 I- Daisy, Tennessee ~ 37319 - g- .;
- f. Applicable Nuclear Power Units: Sequoyah Nuclear Plant, Units 1 and 2 i
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- SONP SI-114 T Table of Contents
.[ Page 1 of 1 Rev. 11 y. .a TABLE OF CONTENTS , 4' .) , . Page No. g. 1.0 STATEMENT OF APPLICABILITY 3 2.0 PURPOSE _ 3 3.0 CODES.OF RECORD 3 , 4.0 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES 4 5.0 ABBREVIATIONS AND DEFINITIONS 6 p, 6.0 COMPONENTS SUBJECT TO EXAMINATION - TVA SAFETY CLASS A 7 ~ 7.0 COMPONENTS SUBJECT TO EXAMIhATION - TVA SAFETY CLASS B -20 ' L 8.0 COMPONENTS SUBJECT TO EXAMINATION - TVA SAFETY CLASS C AND D 25 1 9.0 HYDROSTATIC PRESSURE TESTS 25 10.0 AUTHORIZED INSPECTOR 26' 11.0 EXAMINATION METHODS 26 L 12.0 QUALIFICATIONS OF NONDESTRUCTIVE EXAMINATION PERSONNEL ~ 27 13.0 ACCEPTANCE CRITERIA 27 ., 14.0 REPAIRS AND REP'.ACEMENTS 27 15.0 RECORDS AND REPORTS 28 16.0 NOTIFICATION OF INDICATION 31 L
- 17.0 CALIBRATION BLOCXS 32 14 m 18.0 REQUESTS FOR RELIEF 33
19.0 REFERENCES
33
- APPENDIX A - Tables and Drawings 35 APPENDIX B - Calibration Block Drawings 189
[ ca APPENDIX C - Data Sheets 215 i' APPENDIX D - Notification of Indication Form 221 L APPENDIX E - Scan Plan Data
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- SQNP SI-114 F Page 1 of 32 m
Rev. 11 J . Y
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1.0 STATEMENT OF \PPLICABILITY i This program outlines details for performing the preservice nondestructive examinations of the Sequoyah Nuclear Plant ASME Code Class 1, 2, and 3 com-r ponents (and their supports). The program has been organized to fulfill preservice examination requirements of the Sequoyah Operational Quality Assurance Manual, Part II, Sectica 5.1 and comply as practical with the regtJrements of Section XI of the ASME Boiler and Pressure Vessel Code. In accordance with 10 CFR Part 50, 50.55a(g)(1), a preservice inspection I
" - is not required for Sequoyah. However, the areas outlined in this program to receive a preservice inspection will be examined. The requirements of F ASME Section XI are in effect when the requirements of the applicable con-struction code have been satisfied.
m Specifics concerning performance of nondestructive examinations are not a part of this program, but are included in nondestructive examination
"* procedures (DPM N80E3 and SNP TI-51).
2.0 PURPOSE The Preservice Inspection Program (hereinafter PSI) is preliminary in nature and is employed to obtain detailed information for' inclusion in the Inservice Inspection Program. The examinations required by this program will establish acceptance of components for service. In addition, this program partially satisfies the preservice requirements of SR 4.0.5, f 4.4.5, and 4.4.10. The PSI Program serves as a means of determining built-in limitations caused by original plant design, geometry, materials of construction of the components, and the current *mchnology or state-of-art of nondestructive , testing. The PSI Program will also permit verification of the examination methods selected, finalization of detailed procedures, and will establish preservice examination dats to be used as a reference for later inservice examinations. f . 3.0 CODES OF RECORD This program was prepared to meet the requirement's of the 1974 Edition, Summer 1975 Addenda of Section XI of ASME Boiler and Pressure Vessel Code. ! n. Criteria for determining Class 2 pressure retaining bolting subject to examination is in accordance with the 1977 Edition, Summer 1978 Addenda of Section XI. Criteria for determining components subject to system 1-pressure tests following repair by welding is in accordance with the
- Summer 1978 Addenda of Section XI. Procedures for Eddy Current Examination of heat exchanger tubing, which the Summer 1975 Addenda of ASME Section XI
}, has no provisions for, meets the requirements of the 1974 Edition, Summer ca 1976 Addenda of ASME Section XI. Steam generator tubing examination require-meats are in accordance with Regulatory Guide 1.83, Rev. 1.
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r ', SQUP SI-114 Page 2 of 32 4 Rev. 11 7 b 4.0 METH,0D OF IMPLEMENTATION AND RESPONSIBILITIES 1" Prelir.inary weld maps and other pertinent component drawings and tables
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are included in Appendix A of this program to define areas subject to examination (in addition to sections 5.0, 6.0, 7.0, and 8.0) . The preliminary piping weld sapc should be established by the Metallurgy and
.. Standards Group from CONST's latest revision weld maps.
r Prior to performance of the examinatlons, each system shall be walked down by the Baseline and Inservice Inspection Section of the Nuclear Central 0ffic7 QA Staff (hereinafter NCO QA Staff) to verify that the r NUC PR drawings depict field configurations. Any drawing revisions that are necessary as a resul', of the walkdown will be made befere the drtwings j
- are included in t'a. program.
P The NCO QA Tcaff shall prepare scas plans using component drawings for systems or components requiring examinations. :The plans should include as a mir. mum references to components to te examined, methods of i- examiu_ Lion, examination procedures, and calibration standards. Prior to performing examinations ou a system or component, ..e scan plans phall be 3' established and submitted to the Plant Manager fo information and system
- or component weld maps incorporated in Apperdix A of this program.
, If variations in piping configurations are discovered or alterations or .
repairs to piping are made during the course of the PSI, these changes r snall be marked on field copies of drawings. This information shall be g comraunicated to the Metallurgy and Standards Group which shall be responsible for revising the original drawings. The NCO QA Staff scau
, , plan shall also be revised to reflect these changes. Followi:.g com-pletion of each system examination, the revised drawings shall be '
h' incorporated into this program as a reference for inservice inspections. All latest revision scan plan inforiaation and other pertinent information (i.e., as-built calibration block drawings) shall be incorporated in this
, program as a reference for inservice inspections when all examinations required by this program have been completed.
The preservice examinations will be perfermed by either QA Staff personnel or outside contractors. Contract preparation, administration, and supervision will be the responsibility of the NCO QA Staff. Inspection plans and/or Quality Assurance Progrcms submitted by outside L contractors shall be reviewed and approved by the NCO QA Staff prior to use. All spe-ific NDE procedures used during the inspection progra n shall
- D ba reviewed and app:oved in accordance with OQAM Part II, Section 6.3.
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~ SQNP ,
SI-114 Page 3 of 32 { i Rev. 11 V Certain examinations performed in shop and/or oy CONST will be identified 1, by the Metallurgy and St.udards Group and employed to serve for the ASME
~ Sectun XI PSI. Ih these instances, a member of tne NCO QA Staff may perform a random sauple review of CONST data packages and/or may obtain r shop records to assure that examinations have been performed. CONST examication procedures shall be obtaic2d by the NCO QA Staff for reference. ,
Whenever inspection requirements are being accomplished under the juris-diction of NUC PR, a NCO QA Staff representatire shall be onsite to coord- -
' inate activities. He will be the designated TVA representative to ensure contract compliance and to ensure proper disposition of needed procedure r changes to both TVA and/or contractor procedures in accordance with approved
[ vendor QA program and Section 6.3, Part II of the OQAM. Additionally, the NCO QA Staff representative will be responsible for e notifying the Plant Manager of all unacceptable indications as soon as l' practical. Whenever an unacceptable indication is discovered, the procedure and form in Appendix D shall be utilized. In those cases where an outside I, contractor is furnishing preservice examination services, it will be the o responsibility of the contractor to initiate the form in Appendix D under the supervision of the NCO QA Staff representative. See section 16.0 of l' this program. . L As examirations are completed, the NCO QA Staff representative shall sign for completion the espropriate sections of Data Sheet 2 in Appendix C of this program. When all examinations of this pr t am have been completed,
' Data Sheet 2 shall be signed for co.apletion by tu NCO QA Staff represen-tative and reviewed by the Supervfnor, Baseline and Inservice Inspection i Section, QA Staff. In the evetc system o.r component alterations or repairs L
are made which require component reexamination, or coniponents are re-examined for other reasons, rollowing signoff of Data Sheet 2, the appropriate sections P of Data Sheet 3 it. Appendix C shall be completed and signed by the NCO QA j, Staff representative. (The requirements of this paragraph pertain to unit 2 only.) l Lg prese-vice examinations should be completed prior to initial plant-startup (Operati nal Mode 2). Prior to initial plant startup', Data Sheet 3,
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' - in addition to Data Sheet 2, in Appendix C shall be signed by the NCO QA j Staff reprecentative and reviewed by the Supervisor, Baseline and Inservice L Mspection Section, QA Staff and the Supervisor, Godes and Standardo Section of the Metallurgy and Standards Group. The Plant Manager shall approve the d::S p ,ckage (Data Sheets 1, 2, and 3) by signing Data Sheet 1. These data sheets shall be filed at the plant site with PSI examinatiota data and final b reports discussed in Section 15.0 of this program. (The requirements of this paragraph pertain to unit 2 only.)
** PSI program preparation is the responsibility of Metallurgy and Standards Group of.the Controls and Test Branch. Any revisions initiated by other
groups shall be rabmitted to the Metallurgy and Standards Group for informal approval prior to incorporating the revisions into this , rogram.
1 1 SQNP SI-114 T Page 4 of 32 ' [ Rev. 11
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r J 5.0 ABBREVIATIONS AND DEFINITIONS 1 b -5.1 AIA - Authorized Inspection Agency [ 5.2 AI,- Authorized Inspector (may denote an ANI or ANII) ' 1' 5.3 ANI - Authorized Nuclear Inspector , 5.4 ANII - Authorized Nuclear Inservice Inspector ~ 5.5 Alteration - Any operation which affects the design parameters or . E operating condition of pressure-retaining components or piping systems. Alterations may bnlude the addition of components such as valves or system danges such as rerouting of piping. The replacement of pressure-retaining items with other than like items. also constitutes an alteration. 5.6 Components - Denotes items in a nuclear plant such as pressure vessels, piping systems, pumps, valves, and component supports. 5.7 Examination - Denotes the performance of all visual observation 1- and nondestructive testing such as radiography, ultrasonic, eddy g current, liquid penetrant, and magnetic pdrticle methods. 5.8 Inspection - Denotes verifying the performance of examinations and l $. tests by an Inspector representing an Authorized Inspection L Agency. 5.9 Maintenance - Routine servicing or work on a component undertaken to correct or prevent an unsatisfactory condition. Maintenance a ! L does not include welding, heat treating, or defact removal which r affects the pressure boundary. Maintenance includes operations
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such as lapping of valve seats, adjustment of stem. packing, pump seal maintenance, asd replacement of nonpressure-retaining pump parts. Maintenance does not require the presence of or verification by the authorized inspector. 4 5.10 Normal Operation - Normal plant operation conditions include reactor F startup, operation at power, hot standby, and reactor cooldown to L cold shutdown conditions. Test conditions are excluded. p 5.11 Pressure-Retaining Material - Applies to items such as vessel i heads, nozzles, pipes, tubes, fittings, valve bodies, bonnets,
' disks, pump castings, covers, and boltings which join pressure-retaining items.
F d, 5.12 Repair - Those operations involving welding, Seat treatment, or defect removal which are required to restore a component or piping 1^ system to a safe and satisfactory operating condition. The s, replacement of pressure-retaining items with like items riso constitutes a wpair.
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- SQNP SI-114 Page 5 of 31 Rev. 11 l 1
Ir 6.0 COMPONENTS SUBJECT TO EXAMINATION - TVA SAFETY CLASS A Y The Class A (ASME Class 1) components to be examined for the PSI are j outlined in the following paragraphs. The entire length of each weld l described will be examined for the PSI. 7
" All Class A componenta are subject to volumetric ar.d/or surface 1 examination except component connections, p4. ping, and associated valves T (and their supports) that are one-inch. nominal pipe size and smaller (see i section 6.7). Class A vessels shall be examined after the CONST cold ,
e hydrostatic pressure test. e V When examinations have been completed on the various componente, the data sheet (s) in Appendix C shall be completed (unit 2 only). Table A in Appendix A supplies additional info,rmation such as reference.
< drawing numbers and Section XI, Table IWB-2600, examination categories.
6.1 Reactor Vessel 6.1.1 Reactor Vessel Eeam Welds , [ 6.1.1.1 Circumfegential Shell Welds - Beltline Region There are P.bree circumferential welds in tF-f vergel.cylinderical shell located behind the i thermal shield. Thecs welds will be ultra-sonically examined using remote inspection
- devices from the vessel I.D. with the core internals removed. ,
The vessel shell sections are machined forgings fabricated of A-568, Class 2, manganese-molyedanum
- steel and are clac with weld deposited austenitic -
stainless steel. p , L - 6.1.1.2 Circumferential Shell Weld There is one circumferential weld in the vessel e . I cylinderical shell 2ccated outside of the belt-line region. The weld will be ultrasonically exacined using remote inspection devices from the vessel I.D. with the core intervals removed. t The vessel shell i.ection material is identified l~ in section 6.1.1.1. L 1* i
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.. t SQNP SI-114 y Page 6 of 32 Rev. 11 }
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6.1.1.3 Lower Head Welds T' , j' There are six meridional welds and one circnm-ferential weld in the lower head. The welds will be ultrasonically examined using rea.ote r inspection de7 ices from the vessel I.D..with the i core internals removed. {' Base metal below'the lower head circumferential { weld is inaccessible for examination from the vessel I.D. due to instrumentation penetrations p (weld No. W01-02). A* manual ultrasonic examination of this area will be conducted from a the vessel 0.D. (see Request for helief ISI-7). The bottom head sectiona are fabricated of A-533, Gr. B, Class 1, manganese-molybdenum steel, and are clad with' weld deposited austenitic
.- stainless steel. ~
6.1.1.4 Closure Head Circumferental WeM The head cap weld will be manually ultrasonical.ly a examined from the head 0.D. The closure head does not include any meridienal welds. During the conduct of the unit 1 preservice examination a flaw indication in the closure
' head weld was observed (weld 09-10). Flaw evaluation and acceptability was based on Code Case N-209 (see nonconforming report 6P for additional information concerning flaw evaluation and location). Approximately 5 percent of the closure head weld shall be examined during the third innpection perio- of each inspection F interval. Tlie flaw indi:ation volume shall be o . included in the 5 percent each inspection interval.
In addition to these requirements, the flaw p indication volume shall be examined during the i first two inspection periods. This prwides
' examination of the flaw indication volume for three successive inspection periods. Should
; these successive examinations reveal that the L flaw indication has remained essentially unchanged, then the examination frequency may revert to that t'
of Examination Category B-B of Table IWB-2500 i of ASME Section XI. If the fuccessive examinations
" reveal that the flaw indication size has increased, then technical justification shall be presented i
to NRC for allowing continued operation. n ., , . . . , , , .,. ..
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1 T SQNP
- 3. SI-114' Page 7 of 32 Rev. 11 Y I L
l The closure head ring is fabricated of A-50D,
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y, Class 2, manganese-molybedenum steel. The l closure head hemispherical section is fabricated l of A-533, Gr. B, Class 1, manganese-molybdenum ) steel. Both sections are clad with weld .) deposi:ed austenitic stainless steel. 6.1.1.5 Vessel-To-Flange And Head-T-rFlange Weld 4
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The vessel-to-flvnge weld will'be ultrasonically , exa.ined from the vessel I.D. with remote ' inspection devices. The head-to-flange weld. I will be manually ultrasonically examined from head 0.D. r The vessel and closure head' flange sections are j" fabricated of A-508, Class 2, manganese-molyodenum steel a d are clad internally and on the gasket , face with weld deposited austenitic stainless , steel. 6.1.2 Reactor Vessel Nozzle-To-Vessel Welds And Inside Radiused - Sections There art. lour inlet nozzles (27-1/2-inch I.D.) and four outlet nozzles (29.937 inch I.D.). The nozzle-to-vessel
- welds and nozzle inside radiused sections (including outlet nozzle integral extensions) vill b. ultrasonically examined from the I.D. using remote inspection devices.
. In addition to the above examinations, all vessel mozzles cladding will be ultrasonically examined at the end of each 10-year inspection interval using techniques at least
' P r, as sensitive as those used ti conduct the supplemental examinations performed prior to fuel loading. The results p of t'ds examination shg11 be reported to NRC. - j t i '
" The o m ie fortings are fabjicated of A-bO8, Class 2, zanganese-molyboenum steel and are clad with weld l }-
a. deposited austenitic stainless steel. i' I s. t' w. _ __ __ _ _i ____-______.____i__ ___f_-
X i SQNP SI-114 Page 8 of 32 b, Rev. 11 Er
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6.1.3 Reactor Vessel Penetrations And Attachments Y The control rod drive, upper head injection, vent pipe,
" and instrumentation penetratious shall be visually examined by CONST for leakage during the cold tydrostatic pressure test.
6.1.4 Reactor Vessel Nozzle-To-Safe End Welds y . The nozzle-to-safe end welds shall be ultrasolically examined from the ".D. using remote inspection devices. In addition, these welds will be liquid penetrant examined. The nozzle end connections are clad wich weld depositeo r austenitic stainless steel. 6.1.5 Reactr Vessel Closure Studs, Nuts, Ligaments, And Wachers The vessel flange studs and nuts shall be ul rasonically
" and nagnetic particle examined. The vessel flange ..
ligam'ents between threaded stud holes shall be ultrasonically P examined, and closure washers shall be. visually examined. A Threads in base piaterial do not wequire additional examination. There is no additional pressure-retaining bolting I associated with the vessel. Studs, nuts, and washers are fabricated of SA-540, Gr. B23, aickel, chrome-molvbdenum steel. 6.1.6 Integrally-Welded Reac'wr Vessel Supports n There are no integrally-welded vessel supports. The vessel is supported by four support pads located on the bottom of two outlet n6zzles (16 and 18) and two inlet nozzles (11 and 12, Reference Drawing CH-M-2333-B).
.- 6.1.7 , Reactor Vessel And Closure Head Cladding 8- There are six clad patches (;5 square inches each) In the vessel cladding that shall be visually examined. There l' are six clad patches (36 square inches each) in the h closure head cladding which shall be visually and liquid penetraa. examined. Color photographs, video tapes, or
- y other recording systems of the inspection areas may be
- used fc-: comparison with inservice inspections.
t cd l Reactor vessel and closure head cladding is of weld deposited austenitic stainless steel. l t- ; l _. . _ . . i_ _
T SONP i Si-114 ; Page 9 of 32 ' T Rev. 11
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y , 6.1.8 Reactor Vessel Interior And Removable Core-Support Structures 7
- An c,verall general visual surveillance of the n actor vessel internals will be accomplished for the PS2.
7 6.1.9 Reactor Vessel Control Rod Drive Housings The pressure-retaining welds in the peripheral control' rod - drive housings shall be ultrasonicallp examined. .; I, , The housings consist of a 6-inch 0.D. adapter of A-182, 304SS and a 4-inch 0.D. body of SB-167. 6.1.10 Reictor Ver.sel Auxiliary Head Adapters The pressure-retaining welds in.the four auxiliary head adapters shall be -ltrasonically examined. The dissimilar , metal velds shall also be liquid penetrant examined. The adapters consir,t of SA-182, 304 stainless steel (upper portion) and Sb l66 (lower portion). f 6.2 Pressurizer 6.2.1 Pressurizer Longitudinal And Circumferential Welds
. There are four longitudinal welds and five circumferential welds .4 n the shell cylinderal region. These velds shall T' be n'.rasonically examined. There are no circumferential
- ,c cieridional head welds.
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.. All shell and head sect! ions are fabricated of T A-533, f Class 2, manganese-n2ybdenum steel and are clad with
' austenitic stainless steal, i {' 6.2.2 Pressurizer Nozzle-To-Vessel Welds And Inside Radiused L Sections ,
l . j' There are four 6-inch nozzles, one 4-inch nozzle, and one 14-inch nozzle The nozzle-to-vessel welds and nozzle inside radiused sections will be ultrasonically examined. ,
}" The nozzles are fabricated of SA-508, Class 2, mcaganese-molybderem steel.
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6.2.3 Pressurizer Heater Penetrat; ions y.. i The pressurizer lower head heater penetrations shall be
' visually examined by CONST for leakage during the cold hydrostatic pressure test.
J. 6.2.4 Pressurizer Nozzle-To-Safe'End Welds Each nozzle includes a welded forging. safe end. The nozzle-to-safe end welds shall be ultrasonically and liquid penetraat .-wamined. Safe-end connections are SA-182, Gr. F-316L forgings. { 6.2.5 Preusurizer Pressure-Retaining Bolting 1' i The pressurizer manway bolting' connection shall'be ; visually examined for leakage by CONST during the 7, cold hydrostatic pressure test. k' The manway includes ~ 5 balts at 1.88 inches in diameter. F 6.2.6 Pressurizer Integrally-Welded Vessel Support L The pressurizer support skirt-to-vessel weld shall be ultrasonically examined. The support skirt is fabricated of SA-516, Gr. 70, carbon steel plate. A 6.2.7 Pressurizer Cladding l' A clad patch (36 square inches) in the pressurizer L interior cladding near the manway shall be visually examined.
. Interior cladding is of austenitic stainless steel.
6.3 Steam Generators (4) ,
- 6.3.1 Steam Generator Primary Longitudinal And Circumfereatial Welds g.
- o. The primary head-to-tube sheet weld on each generator shall be ultrasonically examined. There are ro primary r- longitudinal welds.
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1 J T SQltP SI '114 L. Page 11 of 32 y 1*ev. Il 1, 1 T A The tube plate is a SA-508, Claes
- ateel fore ng, i clad on the primary side with NiCrFe al.sy (inconal). The r hemispherical chamber is a SA-216, Gr. WCC casing, clad with austenitic stainless steel.
6.3.2 Steam Generator Primary Nozzle-To-).2d Welds And Inside Radiused Sections The steam generator primary nozzles are integrally cast F with the hemispherical chamber. The nozzles inside L radiused sections cannot be ultrasonically examined and achieve meaningful results due to limitations of examining. F integrally cast material (see Request for helief ISI-8). The nozzles are fabricated to SA ' , Gr. WCC. 6.3.3 Stea. 4 serator P'rimary Nozzle-To-Safe End Welds , The .ceam generator primary nozzle-to-safe end welds shall be ultras <>nically and liquid penetrant examined. The nozzles have buttered 308L safe ends. 6.3.4 Steam Generator Primary Pressure-Retaining Bolting
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The steam generator manway bolting connections shall ba I visually examined for leakage by CONST during the col, L hydrostatic pressure test. Each manway has 16 bolts at 1.88 inches in diameter. 6.3.5 Steam Generator Integrally-Welded Vessel Supports f' There are no integrally-welded vessel supports. The four L main support pads are secured to tb e steam generator field support system by high strength bolts, f j, - 6.3.6 Steam Generator Vessel Cladding
.A clan patch (36 square inches) in the steam generator interior cladding near each generator manway shall be visually examined.
(~ The hemispherical chamber is clad with austenitic L, stainless steel. E' Olf r1 h n i W
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~ SQNP SI-114 1F Page 11 cf 32 l R:v, 11 l y l l
6.3.7 Steam Generator Tubing
. Each steam generator tube bu,.dle consists of 3,388 NicrFe ;
i alloy (SB-163) U-tubes of 0.?.75.0.D. by 0.050 average l' wall thickness.
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All tubes shall undergo a preservice inspection by. eddy current examination. The preservice examination shall be I, performed in accordance with Appendix"IV of the 1974 1 Edition, Summer 1976 Addenda of Section XI and Regulatory Guide 1.83, Rev. 1. Y 1, 6.3.7.1 Acceptance Criteria 6,7.7.1.1 As used in this section: I'- 6.3.7.1.1.1 Imperfection means an exception to the. dimensions, finish or contour of a tube from I I that required by fabrication drawings or specifications. Eddy-current tecting indications below 20 percent of the I- nominal tube wall thickness, if. l' detectable, may be considered a,1 4 1. imperfections. 6.3.7.1.1.2 Degradatior. metas a
]~ service-induced cracking, wastage, g, wear, or general I
** corrosion occuring on
- either inside or outside of a tube.
[ 6.3.7.1.1.3 Degraded Tube means a tube containing t' j, ' imperfections >20 percent of the nominal wall thickness caused by degradation. u
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T i SQNP SI-114 Page 13 of 32-I Rev. 11
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6.3.7.1.1.4 . Percent Degradation v -means the percentage of the tube wall thickness affected or removed by degradation. J. 6.3.7.1.1.5 Defect means an imperfection of such severity that g- it' exceeds the plugging limit.,A tube containing
}* a defect is defective.
"' '.3.7.1.1.6
, Plugging Limit means
- 3. the imperfection depth
-at or beyond thich the t' tube shall be removed
;, from service because it may;become-p, unserviceable prior to the next inspection
"' and is equal to 40 per-cent of the nominal l' tube wall thickness.
i 6.3.7.1.1.7 Unserviceable-I r describes the i condition of a tube if it leaks or contains a defect large enough to affe. t its structural integrity
.- in the event of a
[' seismic occurrence L greater f.han the Oper-l ating Basis Earthquake, a loss-of-coolant accident requiring actuation of the l engineered safeguards, { -, or a steam line or
- a. feedwater line break.
6.3.7.1.1.8 Tube Inspection means l { sa an inspection of the steam gener& tor tube t' from the point of entry (hot leg side)
- completely around the U-bend to the top support of the cold le r, .
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Pege 14 of 32 Rev. 11 so y L 6.3.7.1.1.9 Preservice Inspection - y means a tube - . inspection of each [ steam generator tube performed by eddy-
' l,.
current techniques
' prior to service to establish a baseline condition of the
{ tubing. This J, inspection shall be.
- performed prior to initial power
- operation using the equipment and techniques expected to *
.. be used during subsequent inservice inspections.
{ L 6.3.7.1.2 All defective tubes and tubes containing through-wall cracks shall be plugged. { 6.4 Piping . All Class A piping systems to be examined are fabricated of stairless steel. The reactor coolant main loop piping straight
' .gths are centrifugal cast and the elbows are static cast. The I- t.pper head injection auxiliary head adapter is included in Sec; son
6.1.10. Specific material specifications for each piping system are included in weld map isometrics in Appendix A. The following Class A piping systems are subject i.9 examination: Reactor Coolant { n . Chemical and Volume Control Residual Heat Removal 7-
, Safety Injection f Upper Head Injection j 6.4.1 Circumferential And Longitudinal Pipe Welds 5
lI The entire length of each circumferential and longitudinal pipe weld shall be ultrasonically examined as practical. r 1 en I' f _. . _ _ . _ _ _ - . _ - . _ - , . . . . _ , _ _ ~~~.~ _ _ , ~~~~ ~.
i 4 SQNP (, SI-114 Page 15 of 32 i Rev. 11 L I T l l l 2-6.4.2 Branch Pipe Connection Welds i 1 T All branch pipe connection welds exceeding s6x inches in ;
.}. diameter shall be ultrasonically examined. Each branch '
pipe connection weld six inches in diameter and smaller shall be liquid penetrant examined. 6.4.3 Piping Socket Welds , Each socket weld shall be liquid penetirant examined. I CONST examination data will be used for liquid penetrant examination or field welds. 1r b 6.4.4 Piping Integrally-Welded Supports .
,- All piping integrally-welded external support attachments shall be ultrasonically or surface examined. Integrally-welded external support attachments include those supports which have attachment welds to the piping pressure-retaining I _,
boundary. L 6.4.5 Piping Support Components t' y All piping .upport components shall be visually examined. - This examination includes integrally-welded and nonintegrelly-p welded support components. The support settings of ct,nstant and variable spring type hangers, snubbers, and shock
,L absorbers shall also be verified. These visual examisations shall be performed by CONST.
6.4.6 Piping Pressure-Retaining Bolting ., m There is no Class A pressure-retain;ing bolting 2 inches in q" diameter or larger. Class A bolting connections shall be visually examined by CONST for leakage during the cold
. hydrostatic pressure test.
U - 6.4.7 Piping Safe-End Welds
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(* There are no piping safe-end welds other than those j, discussed in Sectious 6.1.4, 6.2.4, and 6.3.3.
, 6.5 Reactor Coolant Pumps (4)-RCP 6.5.1 RCP Pressure-Retaining Bolting
[ The main flange on each pump includes 24 bolts at 4-1/2 L inches in diameter. The lower seal housing on each pump includes 12 sccket head cap screws at 2 inchas in diameter. L
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I l 7 L SQNP SI-114 Page 16 of 32 7 Rev. 11 ' { T l. The bolts and screws shall be ultrasonically examined and 1- shall be surface examined if removed. Threads in the base material and flange ligamenta between threaded stud (screw) holes shall be visually exais.ned if the connection is q. disassembled.
" Pressure-retaining bolting connections shall be visually examined for leakage by CON 6f during the cold hydrostatic T pressure test. -
All bolting may be examined either in place under tension, y when the connection is disassembled, or when the bolting is removed. The main flange bolts are fabricated to SA-540, Gr. B24, I, and the socket head cap screws are fabricated to
- SA-193, Gr. B7.
l 6.5.2 RCP Integrally-Welded Supports L There are no integrally-welded supports associated with
, the RCP for unit 1. There are three unit 2 RCP's with integrally welded pump feet (pump serial Nos. 704, 709, and 566). These velds shall be ultrasonically. examined.
6.5.3 RCP Support Components Each RCP includes three support components bolted to pump r feet, which are integrally cast with the pump. Each { support component shall be visually examined by CONST. , 6.5.4 RCP Casing Welds l Each unit 1 pump includes a two-piece welded type 304SST casing. The casing welds cannot be ultrasonically examined and achieve meaningful results due to limitations of examining
. integrally cast material. In lieu of this requirement.the casing welds shall be surface examined (see Request for 4 -
, Relief ISI-11). The unit 2 pumps do not include casing i ,.
welds. 6.5.5 RCP Casings , N The internal pressure boundary surfaces of each pump shall be visually examined. In shop visual examinations will j' be used. 0
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" SQNP SI-114 y Page 17 of 32 Rev. 11
{ I. 6.5.6 RCP Flywheel Each RCP flywheel shall undergo a complete ultrasonic examination and shall also be surface examined. I Shop examination data will be used to satisfy examination requirements. F The flywheel consists of two plates, approximately 5 inches and 8 inches thick, bolted together. Each plate is fabricated from vacuum degassed A-533, Gr. B, Class 1 steel. 6.6 Valves F 6.6.1' Valve Pressure-Retaining Bolting l-There is no Class A pressure-retaining bolting two' inches [ fa diameter or larger. ~ Class A bolting connections shall j, be visually examined for le,skage by CONST during the cold hydrostatic pressure test. P 6.6.2 Valve Integrally-Welded Supports i ., All valve integrally-welded external support attachments shall be ultrasonically examined. Integrally-n ldeli exterr.a1 support attachments include 1 those supports which have attachment welds to the valve g pressure-retaining boundary. ,, p 6.6.3 Valve Support Components L All valve support components shall be visually examined by CONST. This examination includes integrally-welded and I' nonintegrally-welded support components. The support. b settings of constant and variable spring type hangers, snubbers, and shock absorbers shall also be verified. I o 6.6.4 ' Valve Body Welds There are no Class A valves with body welds. 6.6.5 Valve Bodies
' ' When it becomes necessary to disassemble any Class / valve (s) l y for normal maintenance purportes, the interior surfac, ' f (
the valve (s': casing (s) will be visually examined and Jne ' s results recorded. Disassembly of valves solely for vitual examination will not be performed (si ASME Section XI, ; Table IWB-2500, Examination Category B-H-2; also see ! request for relief ISI-4). i
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SI-114 I Page 18 of 32 y , Rev. 11 l - [ 6.7 Exempted Components l All components exempted from examination in accordance with -1 IWB-1220 of iSME Section XI shall be visually examined for leakage l during system hydrostatic pressure tests. See Section 9.0. l Components' exempted f.om examination include component l 1., connections, piping, and associated valves (and their suppcrts) l m that are 1-inch nomiaal pipe size and smaller. y 7.0 COMPONENTS SUBJECT TO EXAMINATION - TVA SAFE-lY CLASS B The Class B (ASME Class 2) components to be examined for the PSI are outlined in the following p ragraphs. Selection of areas for examination vill be in accordance with paragraph IWC-1411 and Table IWC-2520 of ASME Section XI. The Metallurgy and Stancards Group shall select areas to be examined or the NCO QA Staff may assist in screcting areas to b6 examined. Components that are exempted from examination in accordance with r- IWC-1220 of ASME Section XI are discussed in Section 7.6 of this 7, program. 7, Class B vessels will be examined after the field hydrostatic tests.
- Where examinations specify a percentage of the total length of weld be examined, the areas (s) examined shall be physically marked on the
{ component and docemented in the examination report. Where a percer.tage 1 of weld length is not referenced, the entire weld length shall be examined. When examinations have been completed. on the various components, the data sheet (s) in Appendix C shall be completed (t nit 2 only). l Table B in Appendix A supplies additional information such as reference k drawing numbers and ASME Section XI Table-2520 examination categories. T 7.1 Steam Generators (4) l ! u - l 7.1.1 Steam Generator Secondary Circumferential Weldr [ There ore five circumferential shell welds located
*- at structural discontinuities on the secondary side of each steam generator. A total of five welds, all at different locations from the four generators, nz will be selected for ultrasonic examination and shall be distributed among the four generators. The o examinations shall cover at least twenty percent of each weld selected for examination, uniformly ;
[ I [ distributed among three areas around the vessel ! circumference. du
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.-v.- w -,.- . - - - .
T -f" SQNP-SI-114 Page 19 of 32 T Rev. 11 l p J' One of the five welds selected for examination is 7 partially inaccessible due t.o the upper steam i generator support arrange:nent (weld nos. SGW-D1, D2, L D3, or D4; see Request for Relief ISI-6). The weld selected for examination will be ultrasonically examined on a best effort basis. The vessel shell and head sections are fabricated of . y SA-533, Gr. A, Class 1 steel plate. .. 7.1.2 Steam Generator h-condary Nozzle-To-Vessel Welds There is one feedwat.ar nozzle (16-inch I.D.) and one main steam nozzle (32-inch I.D.) per generator. A total of two nozzle-to-vessel welds from the four F generators will be ultrasonically examined and shall g be distributed among two of the generators (one feedwater t and one main steam nozzle). (" i The nozzles are fabricated of SA-508, Class 2, L steel. 7.1.3 Steam Generator Integrally-Welded Supports There are ro integrally-welded vessel supports. 7.1.4 Steam Generator Pressure-Retaining Bolting Bolting on the two manway covers on the secondary I, side of each generator is not greater than two inches " in diaceter (see Requst for Relief ISI-10). Each manway has 20 boitn et 1-1/4 inches in diameter. g y 7.2 Residual Heat Removal Heat Dchangers (2) - RHRHX 7.2.1 RHRHX Circumferential Welds There are two circumferential welds located at structural discontinuities on the tube side of each
]'sa 'RHRHX. A total of two welds from the two heat exchangers will be selected for ultrasonic examination ;
and shal', he distributed among the two RHRHX The welds l { u selected shall be located at different areas. The examinations shall cover at least twenty percent of each weld selected for examination, uniformly distributed j
, , among three areas around the vessel circumference.
W The welds include the channel cylinder section to channel flange weld and the channel cylinder section I' to channel head weld. The channel flange is fabricated w from SS, SA-182-F304. The channel cylinder section and channel head are from SS, SA-240, TP-304.
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- 1. SQNP SI-114 y Page 20 of 32 Rev. 11 T ,
7.2.2 RHRHX Nozzle-To-Vessel Welds Y
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The channel cylinder section of each RHRHX includes one inlet nozzle (14-inch I.D.) and one outlet l, nozzle (14-inch I.D.). A total of two nozzle-to-vessel welds from the two RHRHX will be ultrasonically
" examined and shall be distributed among the two heat exchangers (one inlet nozzle and one outlet nozzle).
y .. The nozzles are fabricated from SS, SA-182-F304, 7.2.3 RHRHX Integrally-Welded Supporte There are two integrally-welded support attachments on each RHRHX. A total of two support pad-to-vessel 7 welds from the two heat exchangers will be liquid penatrant L examined and shall be distributed among the two heat exchangers (a different support on each heat exchanger). p. m The support pad is fabricated from SS, SA-240, TP-304. e, 7.2.4 RHRHX Pressure-Retaining Bolting N The channel flange bolting on each vessel is less than 2 inches la diameter (see Request for Relief ISI-10). Each flange includes 36 studs with nuts at 1-3/8 inches T in diameter. The studs and nuts are fabricated from i SA-193, Gr. B7 and SA-194, Gr. H respectively.
, 7.3 Piping "
h Material specifications for eacS piping system are included in weld map isometrics in Appendix A. The following Class B piping systems are sub,iect to examination: Residual Heat Removal y
,, Safet.y injection i Main Steam Feedwater Containment Spray I su 7.3.1 Piping Ciecumferential Welds 1
Circumferential welds subject to examination shall m include those welds at structural discontinuities and welds within three pipe diameters of the centerline
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' SQNP SI-114 t Page 21 of 32 j, Rev. 11 T
L of rigid pipe anchors, or anchors at the penetrations r of primary containment, or at rigidly anchored n componen t.s . Selection of areas to be examined shall be in accordance with IWC-2411 and Table IWC-2520 of
. ASME Section XI.
The entire length of each weld selected shall be ultrasonically examined. g . 1, 7.3.2 Piping Longitudinal Welds r Areas subject to examination include longitudinal welds in fittings (i.e., tees, elbows, reducers).
; ', The entire length of each weld selected for examination p
in accordance with IWC-2411 and Table IWC-2520 of ASME Section XI shall be ultrasonically examined. u 7.3.3 Branch Pipe Connection Welds p L, The entire length of all branch pipe connection welds selected foc examination in accordance with p IWC-2411 and Table IWC-2520 of Section XI will be ultrasonically examined. ( -i 7.3.4 Piping Pressure-Retaining Bolting There is no pressure-retaining bolting larger than 2 inches in diameter (see Request For Reliei ISI-10). 7.3.5 Piping Integrally-Welded Supports .,
- All pfping integrally-welded external support attachments l shall be surface examined. Integully-welded
( ' I' external support attachments include those supports whirJu have attachment welds to the piping pressure-f' retaining boundary. L I CONST examination data will be used for
, surface examination of integrally-welded piping supports.
7.3.6 Piping Support Components L All piping support components shall be visually e.ainined by CONST. This examination includes integrally-delded and nonintegrally-welded support components, {' o The support settings of constant and variable spring type hangers, snubbers, and shock absorbers shall also be e verified. l . L
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T SQNP [ SI-114 . Page 22 of 32 i y Rev. 11 b 7
- k. 7.4 Residual Heat Removal Pumps (2) - RHRP r 7,.4.1 RHRP Casing Weld _s The RHRP casing does not include any casing welds.
V' 7.4.2 RHRP Pressure-Retaining Bolting { The stuffing box extension to pumn casing connection T bol!:ing is not greater than two inches in diameter (see
- Request For Relief ISI-10).
y The connection includes 24 studs at 1-1/4 inches in j' diameter with nuts and washers. 1he studs are fabricated to SA-193, Gr: B7, and the nuts *.o SA-194, Gr. 2H. 7 RHRP Integrally-Welded Supports 7.4.3 There are no integrally-weided supports' associated with the RHRP. [L 7.4.4 RHRP Support Components n, Each RHRP includes three support components bolted to the
~
pump feet, which are integrally forged with the pump. Each support component shall be visually examined by
- CONST.
7.5 Valves 7.5.1 Valve Body Welds - There are no Class B valves with body welds. 7.5.2 Valve Pressure-Retaining Bolting I L - There is no Class B pressure-retaining bolting greater than 2 inches in diameter (see Request For Relief ISI-10).
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7 . .', . 3 Valve Integrally-Welded Supports All valve integrally-welded external support attachments shall be surface examined. Integrally-welded external N support att,achments include those supports which have attachment welds to the valve pressure-retaining boundary. a; CONST examination data will be used for surface ex.mination of integrally-welded valve supports. c l' !
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"' SQNP SI-114 y Page 23 of 32 Rev. 11
{ 1 L 7.5.4 Valve Support Components T J, All valve support components shall be visually examined by CONST. This examination includes integrally welded and nonintegrally welded support components. The support settings of constant and variable . spring type hangers, snubbers, and shock absorbers shall also be verified. T 7.6 Exempted Components -
/
All components exempted from examination in accordance with IWC-1220 of ASE Section XI shall be visually examined for leakage during system hydrostatic pressure tests. See Section 9.0.
. Corponents exempted from examination. include (1) components in systems where both the design pressure and temperature are equal
- to or .less than 275 psig and 200*F, res'pectively; (2) components in systems or portions of mystems, other than emergency core
[ cooling systems, which do not function during normal reactor L operation; (3) components which perform an emergency core cooling function for which the control of the chemistry of the contained p fluid is verified by periodic sampling and test, and (4) component connect. ions, piping, and associated valves, and vessels (and their 6 supports), that are 4-inch nominal pipe size and smaller. I 8.0 COMPONENTS SUBJECT TO EXAMINATION - TVA SAFETY CI. ASS C AND D L 8.1 Hy_drostatic Pressure Tests 3~ Class C and D (ASME Class 3) components shall be visually examined " , by CONST for leakage during system hydrostatic pressure tests. (See Section 9.0). l $, S- 8.2 Supports And Hangers ( { Supports and hangers for components exceeding 4-inch nominal pipe 0 . size whose structural integdty is relied upon to withstand design loads when the system function is required, shall be visually g. examine,d by CONST to detect any loss of support capability, and
.- esf.dence of inadequate restraint.
o When these examinations have been completed, the Data Sheet (s) in Appendix C shall be completed (unit 2 only). U} 9.0 HYDROSTATIC PRESSURE TESTS ; Class A, B, C, and D components (including exempted components) shall be visually exaiined for leakage during system hydrostatic i pressure tests. These examinations shall be performed by CONST.
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1 1 T , 1 SQNP l
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SI-114 Page 24 of 32 UI Rev. 11 L i 7 ! When these examinations have been verified completed, the Data 3 Sheet (s) in Appendix C shall be completed (unit 2 only). l l 10.0 AUTHORIZED INSPECTOR I T TVA shall employ an Authorized Inspector (s) in accordance with. _ ASME Section XI for unit 2 inspections. The Inspector shall verify, assure, or witness that code requirements have been met. He shall l y have the prerogative and authorization to require requalification of any operator or procedure when he has reason to believe the l requirements are not being met. TVA shall provide access for the
, AI in accordance.with IWA-2140 of ASME Section XI. ,
1 1 L 11.0 EXAMINATION METHODS 11.1 Visual Exemination A visual examinatirra is employed to provide a report of the m general condition of the part, component, or surface to be examined, including such conditions as scratches, wear, cracks, corrosion, or erosion on the surfaces; misalignment or movement of the part for component; or evidence c 1, leakage. N Visual examination shall be conducted in accordance with Article 9, Section V, of the ASME Code, except that lighting I, shall be sufficient to resolve the 1/32-inch wide black line , on an 18-percent neutral gray background. f 11.2 Surface Examinatf o.n (Magnetic Particlo) l
. Magnetic particle examination shall be conducted in accordance with Article 7, Section V, of the ASME Code.
IL 11.3 Surface Examination (Liquid Penetrant) m,
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Liquid penetrant examination shall be conducted in accordance with Article 6, Section V, of the ASME Code. 11.4 Volumetric Examination (Radiographic) o Radiographic techniques, employing penetrating radiation such as X-rays, gamma rays, or thermalized neutrons, may be f, utilized with appropriate image recording devices such 4.s pho' ographic film or papers, electrostatic systems, direct-image orthicons, or image converters. For radiographic exauinations employing either X-ray equipment or radioactive
"" isotopes and photographic films, the procedure shall be as specified in Article 2, Section V, of the ASME Code.
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2 L SQNP SI-114 T- Page 25 of 32 J, Rev. 11 y ! b 11.5 Volumetric Examination (Ultrasonic) I j, Ultrasonic examination shall be conducted in accordance with the provisions of Appendix I of Section XI of the ASME Code. p Where Appendix I (I-1200) is not applicable, the provisions of Article 5 of Section V of the ASME Code shril apply. 4 11.6 Volumetric Examination (Eddy Current) Eddy current examination of heat exchanger tubing shall be conducted in accordance with the provisions of Appendix IV of Section XI of the ASME Boiler and Pressure Vessel Code (Summer 1976 Addenda). p 12.0 QUALIFICATIONS OF NONDESTRUCTIVE EXAMINATION PERSONNEL 1' Personnel performing nondestructive examination operations shall be qualified in accordance with IWA-2300 of ASME Section XI (DPM N75C01). CONST personnel which perform visual examinations 2 '. in accordance with this program need not be qualified in accordance. with IWA-2300. Y 13.0 ACCEPTANCE CRITERIA g , All acceptance standards for Class A, B, C, and D components shall f be in accordance with IWA-3000 of ASME Section XI. 14.0 REPAIRS AND REPLACEMENTS i All repairs shall be made in accordance with IWA-4000, IWB-4000, I IWC-4000, and IWD-4000 of ASME Section XI and implemented by p approved written procedures. If rul'es for a particular repair are not specified, repairs may be performed in accordance with the provisions of the construction code of the components. L
!' After repairs by welding on the pressure-retaining boundary of .
components, a pressure test shall be performed in accordance with IWA-5000 and IWB-5000, IWC-5000, or IWD-5000 as applicable of ASME Section XI. .The following may be exempted from these pressure tests J exclusive of those repairs employing a temper bead technique: y (1) Cladding repairs l (2) Heat exchanger tube plugging n (3) Piping, pump, and valve repairs that do not penetrate n; through the pressure boundary
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l l l T i - 1 SQNP SI-114 Page 26 of 32 T Rev. 11 { i I (4) Pressure vessel repairs where the repaired cavity does not l exceed 10 percent of the minimum design wall thicknesc (5) Component connections, piping, and associated valves that are one-inch nominal pipe size and smaller 7 A Repaired areas shall be examined in accordance with applicable . nondestructive methods to establish a preservice record (see. T Sections 6.0, 7.0, and 8.0). These examinations shall include 2 the method that detected the flaw. If the repair is performed in accordance with the provisions of the code applicable to the y constr etion of the component, any additional nondestructive examinscions required by the construction code shall be performed (excluding pressure test requirements). I When component.s require alterations to satisfy the requirements of
- i. ASME Section XI, the repair and inspection procedures of ASME Section YI shall be used to effect the alteration.
In the event that components are to be replaced, or components are to be added to a system, the welds attaching the component to the
, system shall be constructed in accordance with these repair and inspectior procedures.
The requirements of this program and ASME Section XI are not applicable for additions of complete systems. ASME Section XI repairs and replacements may be coordinated as necessary with the Metallurgy and Standards Group of the Controls and Test Branch. Rept. irs and replacements which " r9 quire NDE shall be coordinated with the NCO QA Staff. 15.0 RECORLS AND REPORTS m 15.1 Recording of and Report of Examinations m,
- n. . A detailed report of all examinations shall be prepared by the performing or responsible organization and should contain 4 but not be limited to the following inforrution:
U (1) Date and time of examination.
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(2) Identification of part examined including wall thickness m (if applicable), type material, part temperature, and unit identification. (3) Identification of TVA's or contractor's examiner and personnel certification.
.F -
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1 7 SQNP SI-114
)
Page 27 of 32 Rev. 11 s, y (4) Type of examination (PT, UT, etc.) and r.pecific NDE procedure used. (5) Certification of NDE mater als such as penetrant, couplant, etc.
- (6) Results of examination.
F (7) Corrective action and repairs. -. (8) H&TE and inspection equipment used and th'ir calibratioc due dates. (9) For eddy current examination of heat exchanger tubing, the report f' shall include a record indicating the tube (s) examined (this may be marked on a tube sheet sketch or drawing), the extent to which each tube was examined, the location and depth'of each reported
. . indication, and. the identification or 'the operator (s) and data -
evalua'm(s) who conducted each examination or.part thereof. All procedures and equipment shall be identified sufficiently to permit , duplication of the examination at a later date. This shall include l initial calibration data for the equipment and any significant changes'. ; A marked drawing or sketch shall indicate the weld or part examined. Information should also include all other pertinent data that would {L 1ater permit duplication or relocation of a flaw, such as transducer type, size, shape, frequency, beam angle, couplant, and distances from some given reference points. All required and pertinent information will be recorded on the , appropriate data sheets by the performing organization. When portions of the inspection work are contracted, a detailed report r 7 will be submitted to TVA by the contractor with all pertinent L and required information. TVA will retain the original upies of all raw data taken, p , y The NCO QA Staff shall review and submit the final report to the ' Plant Manager for review. Alternatively, final reports may be p
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submitted a,s portions of the PSI are completed (i.e., final report l 1 of reactor vessel examination). These fiul reports shall be filed b at the plant site wit!. th>.: Data Sheets of Appendix C (unit 2 only) I of this program as discussed in Section 4.0 of this program. 6> 1 E s 1 xi-k e l
1 I SQNP l L SI-114 Page 28 of 32 I T Rev. 11 l b. r 1 l
-}' 15.2 PS: Report for Class A and B Components T Since a PSI is not required for Sequoyah, PSI report (s) for Class A
- 1. and B components in accordance with IWA-6220 need not'be submitted. .
to NRC. However, if TVA elects to submit a PSI report the NCO QA , y Staff shall prepare the report and the following information i should be included. The PSI report'should have a cover sheet. providing the following I- information: (1) Date. (2) Name of owner and address of corporate offices. (3) Name and address of nuclear generating plant in which the nuclear power unit is located.
, (4) Name or number assigned tc the nuclear power unit by TVA.
All repcrts should have a summary providing the following information: (1) National Board Number assigned by the manufacturer to the boiler, l' pressure vessel, or component. (2) Names o." the components or parts of the components for which f this is . record, including such information regarding size, capacity, n:aterial, location, and drawings as may aid accurate identification. (3) Name of the manufacturer of the components or parts for whicb. this is a record, including the manufacturer's component or p part numbers and such information regarding the manufacturer's
;" corporate office or manufacturing plant locations as may aid in gaining access to the manufacturer's records regarding the ,, components or parts that the manufacturer is maintaining.
L (4) Date of completion of the preservice inspection. (5,' Name or names of the Inspector (s) when required. L
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(6) Name and mailin; address of the employer (s) of the Inspector (s). [ (7) Abstract of examinations performed, conditions observed, a4 corrective measures recommended and taken. (8) Signature of Inspector, when required. a The PSI Report should have an owner's data report for inservice inspection, Form NIS-1 as shown in Appendix II of ASME Section XI g (unit 2 only). r I na
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~SQNP l SI-114 Page 29 of 32 f. .I Rev. 11 L
T j l 15.3 Records for Class A, B, C, and D Components , ThefollowingrecordsshallbeavailablefErreview: (1) Examination Plans v (2) Examination Results and Reports (3) Examination Methods and Procedures - (4) Evaluation of Results U (5) Corrective Actions and Repairs I 15.4 Records of Hydrostatic Pressure Tests Records of the visual. examinations conditeted during system hydrostatic tests as required by Section 9.0 of this program , l m should consist of an itemization'of the number and location of y leaks found in a system and the corrective. actions taken. g 16.0 NOTIFICATION OF INDICATION 6 Plant management shall be formally notified of the presence of unacceptable indications detected during the performance ; i F of nondestructive examinations. Unacceptable indications y are defined by the applicable NDE procedure. Formal notification shall consist of completing and submitting to the Plant Manager n the " Notification of Indication" form in Appendix D of this program. ., Part I of the " Notification of. Indication" shall be completed and r, signed by the NDE Level II or III examiner detecting the indication. s The Baseline and ISI Section representative of the NCO QA Staff shall review and sign the form. If the indication is detected by an outside contractor, the contractor's field supervisor shall review g .and sign the fmn. r Part II of the form shall be completed for evaluation of findings by i a TVA NDE Level III individual. This individual shall indicate b under " Disposition" his recommended disposition of the indication. He shall reference examination procedures to be used if reexamination is a requirement. He shall then sign and date the form. Copies of { u the form shall be distributed to the Plant Manager, the Baseline and ISI Section Representative, the Metallurgy and Standards Group, s and, if appropriate, the Plant Outage Director or Construction. One copy ' shall be filed with the examination report. U
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7 SQNP SI-114' , P.ge 30 of 32 j 7 Rev. 11. 1 3 L
]
t < i 1 Upon receipt of the Notification of Indication form, the Plant Manager
- y. shall be responsible for determining the organization to implement the i disposition. If NUC PR is responsible for the repair, the plant manager shall be responsible for preparing' instructions to repair the indication in accordance with N-0QAM, Part II, Section ;c.1, and .
I. the recommended disposition on the form. Dispositions other than 1 b res'.oring to original requirements shall be processed as modifications in accordance with N-0QAM, Part II, Section 3.0. If CONST 10 [ respcasible for the repair, it shall be performed in accordance with. L the recommended disposition on the Notification of Indication Form, and to the satisfaction of the NDE Level III individual. The plant or p CUST, as appropriate, shall cooroinate with the NCO QA Staff to tc,nduct reexamination when reexamination is a requirement. < Additionally,
.;oordination with the AIA representative shall be made, when appropriate, as follows: $. a. Make available to the ANII any records he needs t
to accomplish his dr. ties.
- b. Give adequate notice.to the AIA that an ANII and/or ANI will on require <' for repair work.
i Detailed requirements for interfacing with the AIA for repatrs to
- code items.are contained in N-0QAM, Part II, Section 2.3.
T' Upon completion of the action required to repair trie indication, L the Baseline and ISI Section representative of the NCO QA Staff shall review the repair instructions to assure completion, and-p shall sign and date the Notification of Indication Form, Part II. The review shall include referencing the repair instructions on ' 3 the completed form. The signed form shall remain with the examination report for use as a quality assurance record. In addition, if the component requires reexamination, one copy of
; the completed form shall be filed with the new examination report.
The reexamination report number shall also be referenced on the r completed form by the Baseline and ISI Section representative. e . Additional distribution of the form shall be performed as noted for Part II of the form. 17.0 CALIBRATION B' LOCKS j u Calibration blocks will be used fu _'.trasonic examinations (a . calibration tube will be used for eddy current examnation of steam [' p generator cubing). The blocks will be fabricated to the general I requirement s of ASME Section V and ASME Section XI. The blocks p shall be fabricated of the material to be examined or equivalent P numbers. Mill test reports shall be obtained and retained for
- all calibration blocks. The blocks shall employ drilled holes ,
and/or notches for calibration reflectors (see Request for Relief I
$, ISI-2). ,
l [ c. ; l
T
, SQNP ~
SI-114- ' Page 31 of.32 I Rev. 11 L 7 4 The NCO QA Staff shall maintain as-b'uilt calibration block drawings. 7 Copies of the original drawings and any revisions sifall be submitted to the Meta 11uri;y and Standards Group.' The calibration biccks shall be stored at the plant site and maintained by the plant QA organization. , T 18.0 REQUESTS FOR RELIEF 1 Where TVA has determined that certain code requirements or examinations T are impractical, TVA will submit written requests for relief to NRC with informat4.on to suppret the determinations and any proposed alternate
~
examinations. Thecimpractical code requirements or examinations shall be identified in this program, and references to particular. requests I for relief shall be included. L When inpractical examination requirements are identified in the field, { the NCO QA Staff shall notify the Metallurgy and Standards Group such [ that the information may be included in this program and requests ' for relief may be prepared if necessary. f
19.0 REFERENCES
19.1 ASME Boiler and Pressure Vessel Code - Scction XI through Surmer 1975 addenda, Summer 1976 addenda. 19.2 ASME Boiler and Pressure Fessel Code - Section V. 19.3 Instruction Manual - 173-inch I.D. Reactor Pressure Vessel - Rotterdam Dockyr.rd Company, Contract No. 68C60-91934, N2M-2-3. 19.4 Sequoyah Nuclear Plant Standard Practice SQA41. L 19.5 Sequoyah Nuclear Plant Final Safety Analysis Report. u 19.6 Westinghouse Technical Manual - Pressurizer, TM 1440-C225, Contract Ho. 68C60-91934, N2M-2-6. 7 i 19.7 Westinghouse Technical Manual - Vertical Steam Generators, TM
' 1440-C224, Contract No. 68C31-91934, N2M-2-4.
I 19.8 Westinghouse Instruction Manual - Auxiliary Heat Exchangers, L Contract No. 68C60-91934, N2M-2-25. l~ 19.9 Westinghouse Instruction Book - Reactor Coolant Pump, Contract L No. 68C60-91934, N2M-2-5. r 19.10 Ingersoll-Rand Instruction Manual - Residual Heat Removal Pumps, Contract No. 68C60-91934, N2M-2-30. c o { >
i T I .; SQNP ' SI-114
'Page 32'of 32 l - 7:
Rev. 11 ..
}. t
.i
. 7, .. ,
19.11 Sequoyan Nuclear Plent 0*er.Stional Quality Assurance Manual, t Part II,' Sections 2.1,-3.0, and 5.1. l
^
l' . 19.12 Division Procedure Manuals N80E3 and N75C01. l y, ' 19.13 Sequoyah Nuclear Plant. Technical Instruction TI-51. p .. g !
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t- , P ; P ; :- ^ . i c . r- &-1 m s-5 r-~ - - - -- -- t- - i t- + e e - -* t-% .. ++ SONP EI-114 Appendix A Page 1 of 154 Rev. 11 TABLE ~% SEQUOYAH PRESERVICE INSPECTION PROGRAM - CLASS A COMPONENTS Examination Category
- Program Reference Item No. From Table From Table IWl'.-2600, Method of Reference Component Section IWB-2600, Section X_I Section XI Inspection ^ Drawing No.
A. Reactor Vessel
- 1. Circumferential Shell Welds-Beltline Region 6.1.1.1 Bl.1 B-A UT CH-M-2343-B i 2. Circumferential Shell ~
O Weld 6.1.1.2 Bl.2 B-B UT CH-M-2343-B 1
- 3. Lower Head Welds 6.1.1. 3- Bl.2 B-B UT CH-M-2343-B 4 -: Closure Head Circum-ferential Weld 6.1.1.4 Bl.2 B-B UT CH-M-2358-A
- 5. Vessel-to-Flange and CH-M-2343-B Head-to-Flange Welds 6.1.1.5 Bl.3 B-C UT- Cil-M-2358-A '
- 6. Nozzle-to-Vessel Velds CH-M-2343-B and Inside Radiused CH-M-2333-B Sections 6.1.2 Bl.4 B-D UT CH-M-2360-A CH-M-2361-A ISI-0008-B
- 7. Vessel Penetrations and CH-M-2651-C Attachments 6.1.3 Bl.5 B-E VT. MSG-0004-C
; *See Section 6.0 for Additional Information.
- - , :- - r- - - - -
m m r-~ r -- -~ m - r- ~ -m e-n e-m .-
- - :- . t- .
SQNP SI-114 Appendix A Page 2 of 154 Rev. 11 TABLE A (Continued) SEQUOYAH PRESEi!VICE INSPECTION,_ l'ROGRAM - CLASS A COMPONENTS ._ Examination Category l
- Program Reference Item No. From Table From Table IWB-2600, Method of Reference Component Section IWB-2600, Section XI Section XI Inspection Drawing No.
A. Reacto. Vessel (Continued)
- 8. Nozzle-to-Safe End CH-M-2333-B Welds 6.1.4 DI.6 B-F _ UT, PT ISI-0008-B
- 9. Closure Studs and Nuts 6.1.5 Bl.8 B-G-1 UT, HFi CH-M-2341-B 4
i
$' 10. Ligaments Between CH-M-2341-B Threaded Stud Holes 6.1.5 Bl.9 B-G-1 UT
- 11. Closure Washers 6.1.5 Bl.10 B-G-1 VT CH-M-2341-B
- 12. Closure Head Cladding 6.1.7 Bl.13 B-I-1 PT, VT MSG-0001-B
- 13. Vessel Cladding 6.1.7 Bl.14 B-I-! VT ISI-0016-A
- 14. Vessel Interior 6.1.8 Bl.15 B-N-1 . VT
- 15. Removable Core-Support Structures 6.1.8 E1.17 B-N-3 VT
- 16. Control Rod Drive CH-M-2651-C Housings 6.1.9 Bl.18 B-0 UT CH-M-2359-A
- 17. Auxiliary 'iead 6.1.10 B4.1, B4.5 B-F, B-J UT, PT CH-M-2337-C CH-M-2651-C l ISI-0001~C -
ISI-0014-A
*See Section 6.0 for Additional Information.
=. *e-- . . , um ,- - - - - yv --'+-w- - - . - - e
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M ~ M i-M e+ SQNP SI-114 Appendix A Page 3 of 154 Rev. 11 TABLE A (Continued) SEQUOYAH PRESEP.VICE INSPECTION PROGRAM - CLASS A COMPONENTS Examination Category
-
- Program Reference Item No. Free Table From Table IWB-2600, Method of Reference Component Section IWB-2600. Section XI Section XI Inspection Drawing No.
B. Pressurizer
- 1. Longitudinal and ..
Circumferential Welds 6.2.1 B2.1 B-B UT CH-M-2363-A
- 2. Nozzle-to-Vessel Welds and Inside Radiused Sections 6.2.2 B2.2 B-D UT CH-M-2363-A O
- 3. Heater Penetrations 6.2.3 :
B7_ . 3 B-E 7T MSG-0006-A
- 4. Nozzle-to-Safe Ead Welds 6.2.4 B2.4 B-F UT, PT CH-M-2353-A
- 5. Pressure-Retaining Bolting 6.2.5 B2.11 B-G-2 VT MSG-0002-B
- 6. Integrally-Welded .
Vessel Support 6.2.6 B2.8 B-H UT CH-M-2362-A
- 7. Vessel Cladding 6.2.7 B2.9 B-I-2 VT MSG-0002-B
*See Section 6.0 for Additional Information.
, m tm .; m ~ r- -* e --w * - -- -
e , :- , r t . SQNP SI-114 Appendix A Page 4 of 154 Rev. 11 TABLE A (Continued) SEQUOYAH PRESERVICE INSPECTION PROGRAM - CLASS A COMPONENTS 4 Examination Category
- Program Reference Item No. From Table From Table IWB-2600, Method of Reference IWB-2600, Section XI Section XI Inspection Drawing No.
Component Section C. Steam Generators
- 1. Primary Head-to-Tube Sheet Weld 6.3.1 B3.1 B-B UT CH-M-2345-B
- 2. Primary Nozzle i Inside Radiused 6.3.2 B3.2 B-D NA CH-M-2345-3 Mi ' Sections Prima.y Nozzle *3-Safe
* ' CH-M-2333-B 3.
6.3.3 B3.3 B-F UT, PT CH-M-2345-B End We?ds ISI-0008-B
- 4. Pressure-Retaining MSG-0002-B Bolting 6.3.4 B3.10 B-G-2 VT 6.3.6 B3.8 B-I-2 VT MSG-00G2-B
- 5. Vessel Cladding .
N/A N/A ET 76M1 . 6. Tubing 6.3.7 D. Piping Circumferential Welds 6.4.1 B4.5 B-J UT See Table C 1. Longitudinal Welds B4.5 B-J UT See Table C
- 2. 6.4.1
*See Section 6.0 for Additional Information.
_ _ _ _ _ _ . _ _ _ _ _ _ _ - - -~,
e , P: r* - ~ t_ m :- - m M & M M i 1 m m m ~ M r'M t-* ' -~ d SQNP SI-114 Appendix A Page 5 of 154 Rev. 11 TABLE A (Continued) SEQUOYAH PRESERVICE INSPECTION i'ROGRAM - CLASS A COMPONENTS Examination Category
- Program Reference Item F9. From Table From Table IWB-2600, Method of Reference Component Section IWB-io00.,Section XI Section XI Inspection Drawing No.
D. Piping (Continued)
- 3. 2 ranch Pipe Connection Welds 6.4.2 B4.6 B-J UT See Table C
- 4. Branch Pipe Connection i Welds 6.4.2 B4.7 S-J PT See Table C S
' 5. Socket Welds 6.4.3 B4.8 B-J PT See Table C
- 6. - Int.egrally-Welded Supports 6.4.4 B4.9 B-K-1 UT or PT See Table C
' . Support Componentt 6.4.5 B4.10 . B-K-2 VT See Table C
- 8. Pressure-Retaining See Table C Bolting 6.4.6 B4.12 B-G-2 . VT (Weld Maps)
E. Reactor Coolant Pumps
- 1. Pressure-Retaining.
Bolting 6.5.1 B5.1 B-G-1 UT CH-M-2675-B
- 2. Pressure-Retaining Bolting 6.5.1 B5.2 B-G-1 UT, PT ~ CH-M-2675-B
. or MT
*See Sectica 6.0 for Additional Information.
t . r . ra t ; ; . ; , F, M r---- r~~ ~ -- m - - - ~ r~ -' r-~ ~ SQNP SI-114
- Appendix A Page 6 of 154 Rev. 11 TABLE A (Continued)
SEQUOYAH PRESERVICE INSPECTION PRO'F'.d - CLASS A COMPONENTS Examination Category
- Program Reference Item No. Froni Table From Table IWB-2600, Method of Reference Component Section IWB-2600, Section XI Section XI _ Ins,2ection Drawing No.
E. Reactor Coolant Pumps (Continued)
- 3. Fressure-Retaining Bolting 6.5.1 B5.3 B-G-1 VT CH-M-2675-B
- 4. Pressure-Retainin,
, Bolting 6.5.1 B5.9 B-G-2 VT
- 5. Integrally-Welded Supports ~ 6.5. 2 ~ ' B5.4 B-K-1 UT
- 6. Support Components 6.5.3 B5.5 B-K-2 VT MSG-0003-B (Unit 1 only)
- 7. Casing Welds 6.5.4 B5.6 B-L-1 -PT MSG-c'303-B (Unit 1 only)
- 8. Casings 6.5.5 B5.7 B-L-2 VT MSG-0003-B
- (Unit.1 only)
- 9. Flywheel 6.5.6 N/A N/A UT, PT F. Valves
- 1. Pressure-Retaining See Table C Bolting 6.6.1 .
B6.9 B-G-2 VT (Weld Maps)
*See Section 6.0 for Additional Information.
y- w wy - v- - n -w%,w w- - y _w _ _ .u_ _h._.s. 2~ 2 -
r . e; t. r ; .. . L & --1 m t- -3 m m m -- - ~ M ** **- t I . SQNP SI-114 Appendix A Page 7 of 154 Rev. 11 TABLE A (Continued) SEQUOYAH PRESERVICE IdSPECTION PROGRAM - CLASS A COMPONENTS Examination Category
- Program Reference Item No. From Table From Table IWB-2600, Method of Reference Component Section IWB-2600, Section XI Section XI Inspection Drawing No.
F. Valve (Continued)
- 2. Integrally-Welded Supports 6.6.2 u0.4 B-K-1 ITT or PT See Table C
- 3. Support Components 3.6.3 B6.5 B-K-2 VT See Table C i
- 4. Valve Bodies 6.6.5 B6.7 B-M-2 VT See Table D 1
7I G. Exempted Components '6. 7 ' Bl .1~r B-P .VT B2.10 B3.9 B4.11 B5.8- . B6.8
*See Section 6.0 for Additional Information.
~
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c ; P- r-, t , t . , ' . m-~ e- m m M r- 9 9 -w :-m -9 c -m t SQNP SI-114 Appendix A Page 8 of 154 Rev. 11 TABLE B SEQUOYAH PRESERVICE INSPECTION PROGRAM - CLASS B COMPONENTS Examination Category
- Program Reftience Item No. From Table From Table IWC-2600, Method of Reference Component Section IWC-2600. Section XI Section XI Inspection Drawing No.
A. Steam Generators ..
- 1. Circumferential Welds 7.1.1 C1.1 C-A UT CH-M-2345-B C1.2 C-B UT CH-M-2345-B
- 2. Nozzle-to-Vessel Welds 7.1.2 i B. Residual Heat Removal i Heat Exchangers
! 1. Circumferential Welds ' 7. 2.~ 1 ~ C1.1 C-A UT CH-M-2404-A t 1
- 2. Nozzle-to-Vessel Welds 7.2.2 C1.2 C-B UT CH-M-2404-A
- 3. Integrally-Welded .
Supports 7.2.3 C1.3 C-C CH-N-2404-A C. Piping .'
- 1. Circumferential Welds 7.3.1 C2.1 C-F, C-G UT See Table C
- 2. Longitudinal Welds 7. 3. 2 , C2.2 C-F. C-G UT See Table C
- 3. Branch Pipe Connection Welds 7.3.3 C2.3 C-F, C-G UT - See Table C
- 4. Integrelly-Wele 4 -
'See Table C Supports 7.3.5 .C2.5 C-E-1 Tnr-
*See Section 7.0 for AA'Itional Information.
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SQNP SI-114 Appendix A Pcge 9 of 154 Rev. 11 TABLE B SEQUOYAH PRESERVICE INSPECTION PROGRAM - CLASS B COMPONENTS Examination Category
- Program Reference Item No. From Table From Table IWC-2600, Met'aod of Reference Component Section IWC-2600, Section XI Section XI Iaspection Drawing No.
C. Piping (Continued)
- 5. Support Components 7.3.6 C2.6 C-E-2 PT or MT See Table C D. Residual Heat Removal Pumps
, 1. Support Components 7.4.4 C3.4 C-E-2 VT Ct E. Valves
- 1. Integrally-Welded Supports 7.5.3 C4.3 C-E-1 PT or MT See Table C
- 2. Support Components 7.5.4 C4.4 . C-E-2 VT See Table C F. Exempted Components 7.6 N/A -
N/A VT
< n
~
*See Section 7.0 for Additional Information.
SQNP' SI-114
Appendix A Page 10 of 154 Rev. 11 1
i
'IABI.E C I
I LIST OF DRAWINGS - UNIT 1 .
-l T
1 Reactor Vessel
~
Appendix A Drawing No. Title Page No. 13-14 [ CH-M-2333-b CH M-2337-C Reactor Coolant Piping Upper Head Infection System 56-57 I CH-M-2341-B Reactor Vessei Stud Locations and Details 15-16 CH-M-2343-B Reactor Vessel Seam Welds 17 [ 18 l CH-M-2358-A Reactor Vestel Closure Head , l' CH-M-2359-A Control Rod Drive Housing 19-20 CH-M-2360-A Reactor Vessel Inlet Nozzles 21 CH-M-2361-A Reactor Vessel Outlet Nozzles 22
- CH-H-2651-C CRD, UPI, and Vent Pipe Penetrations 23-24 IE -0014-A Auxiliary Head Adapter 25 i' ISI-0016-A Reactor Vessel Clad Patches 26 i, MSG-0001 _B Clo-ure Head Cladding Patches 27 MSG-0004-C Reactor Vessel Bottom Head Penetrations 28
^
\
j Presurit_er i Appendia A j [ Drawing No.' Title Page No. k. j' CH-M-2362-A Pressurizer Support Skirk Weld 29 CH-M-2663-A Pressurizer Seam Welds 30 MSG-0002-B Pressurizer and Steam Generator Cladding Patches 31 MSG-0006-A Pressurizer Heater Penetrations 32 o - Steam Generators e, Appendix A Drawing No. Title Page No. CH-M-2333-B Reactor Coolant Piping 13-14 I(' CH-M-2345-B Steam Generator 33 76M1 Vertical Steam Generators (Tube Sheet Arrangement) 34 I MSG-0002-B Pressurizer and Steam Generators Cladding Patches 31 t, si t .
7-SQNP SI-114 I Appendix A. L Page 11 of 154 Rev. 11 I,
- TABLE C (Continued) l
' - LIST OF DRAWINGS - UNIT 1 , Residual Heat Removal .. Heat Exchangers 1 e ~' Appendix A f' Drawing No. Title Page No. CH-M-2404-A Residual Heat Removal Heat Exchanger Channel 35
. Welds ,
Piping and Valve Weld Maps Appendix A Drawing No. Title Page No. a CH-M-2333-B Reactor Coolant Piping 13-14 CH-M-2333-0 Safety Injection System 36-42
.. CH-M-2334-C Reactor Coolant System 43-49 CH-M-2335-C Chemical and Volume Control System 50-51 - CH-M-2336-C Residual Heat Removal 52-55 i CH-M-2337-C Upper Head Injection System 56-57 ~
CH-M-2338-C Seal Water Injection (Chemical and Volume Contral System) 58-61
}, CH-M-2339-C Feedwater 62-63 L CH-M-2340-C Main Steam Line '
64-65 Centainment Spray System, 66 CH-M-2422-C
; MSG-0005-A Steau Generator /Feedwater Transition Spool Pier 67 L
l' Piping and. Valve Hanger Maps 1. Appendix A Drawing No. Title Page No. , 1. CH-M-2432-C Reactor Caolant 68-74 CH-M-2433-C Chemical ad Volume Control 75-76 CH-M-2434-C Seal Wate Injection (Chemical and Volume [". Controlj 77-80 CH-M-2435-C Residual Heat Removal 81-84 [, CH-M-2436-C Safety Injection 85-91 t' CH-r;-2437-C Upper Head Injection 92-93 CH-M-2438-C Main Steam Line 94-95 CH-M-2439-C Feedwater 96-97 CH-M-2440-C Containment Spray 98 s-3
$2
l T SQNP SI-114 - [ Appendix A L Page 12 of 154 , Rev. 11 1 TABLE C (Continued) L LIST OF DRAWINGS - UNIT 1 Y
}, Reactor Coolant Pumps p ,,
Appendix A Drawing No. Title _Page No. CH-M-2675-B Reactor Coolant Pump Main Flange and Lower Seal House Bolt Pattern 99
, MSG-0003-B Reactor Coolant Pump Casing 100 6
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