Text

Rev 0 to Inservice Insp Program
	ML20080C928
Person / Time
Site:	Sequoyah
Issue date:	08/23/1983
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20080C922	List: ML20080C918; ML20080C928;
References
	SQNP-SI-114.2, NUDOCS 8308290390
	Download: ML20080C928 (252)
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{{#Wiki_filter:_ TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT L SURVEILLANCE INSTRUCTION 114.2 Inservice Inspection Program Unit 2

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C308290390 830823 PDR ADOCK 05000328 O PDR

l 1 4 i ?~ Inservice Inspection Program Cover Sheet 4 i 4 Owner: Tennessee Valley Authority i Address of Corporate Office: Knoxville Office Complex

400 Commerce Avenue Knoxville, Tennessee 37902 s

1 j Name and Address of Nuclear Power Plant: Sequoyah Nuclear Plant P.O. Box 2000 Daisy, Tennessee 37319 l \- 4

                             ,                  Applicable Nuclear Power Units:                             Sequoyah Nuclear Plant, Unit 2

[i Commercial Operation Date: June 1, 1982 i i 1 4 a 4 i l i i j i 1, 4 I i i l i i l l

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SQa'P ) SI-114,2 i Punchlist-Page Icf 1 Rev_,0.__. l PL'NCHLIST Reactor Vessel Repair k' elds Beltline Region Class 3 System Functional Leakage SI's-O e e-9 9

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                                         ,SQNP SI-114.2 Page 1 of 2 Rev. 0 TABLE OF CONTENTS 1

Pare No. 1.0 Statement of Applicability / 2.0 Purpose .. l. 3.0 Inspection Intervals and Inspection Periods / 4.0 Codes of Record JL 5.0 Method of Implementation and Responsibilities 2-6.0 Abbreviations and Definitions h' 7.0 Components Subject to Examination - TVA Safety Class A J' 8.0 Cc=ponents Subject to Examination - TVA Safety Class B 33 9.0 Components Subject to Examination - TVA Safety Class C 5'1 and D 10.0 Authorized Inspector 52 l 11.0 Examination Methods 5J 12.0 Qualifications of Nondestructive Examination Personnel - 5~7 13.0 Acceptance Criteria 5' 7 14.0 Repairs 57 15.0 Replacements S~ 7 16.0 Records and Reports - II 17.0 Notification of Indication 41 18.0 Calibration Blocks /2 , 19.0 Requests for Relief fy 20.0 Augmented Inspections 44 21.0 References di 1 5-e

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                                                       ~ SQNP SI-114.2 4

Page 2 of 2 Rev. O TABLE OF CONTENTS ,

                                                                                                                                . Page No.

Appendix A - Tables and Drawings 49- 227 i Appendix B ' Calibration Block Drawings Appendix C - Data Sheets f 22o Appendix D - Notification of Indication Form 23/ Appendix E - Requests for Relief 1Ja~1"4 Appendix F - Augmented Inspections 2 47

,                Appendix G - Scan Plan Data 4

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SQNP SI-114.2 Page.1 of 67 Rev. 0 1.0 STATEMENT OF APPEICABILITI This program outlines requirements for performing the first . i I 10 year interval inservice nondestructive examinations of the ! Sequoyah Nuclear Plant, unit 2, ASME Code Class 1, 2, and 3 co=ponents (and their supports) containing water, steam, or radioactive material (other than radioactive waste management systems). The program has been organized to fulfill inservice examination requirements of the Sequoyah Operational Quality Assurance Manual, Part II, Section 5.1 and comply as practical with the requirements of Section XI of the ASMI Boiler and Pressure Vessel Code. In addition, this program implements applicable portions of the Sequoyah Technical Specifications. The Inservice Inspection Program (ISI) satisfies the requirements of Surveillance Requirements 4.4.3.2.4, 4.4.5.0, and 4.4.10, and partially satisfies the requirements of Surveillance Requirement 4.0.5. The requirements of this program are applicable beginning at the date of commercial operation of the unit. 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 ISI program shall be used for planning inspections and nondestructive examinations of the Sequoyah ASMI Class 1, 2, and 3 components for the first interval. Personnel responsible for performance of the examinations should familiarize themselves with the requirements of this program prior to performing the exami-nations. The examinations required by this program will establish accep-tance of components for continued service. 3.0 INSPECTION INTERVAES AND INSPECTION PERIODS The inservice examinations required by ASME Section XI shall be performed during each 10-year interval of service (inspection inte rval) . The inspection intervals represent calendar years after the unit has been placed into commercial service. The commercial operation date for unit 2 was June 1, 1982. The first 10-year interval may be decreased or extended by as much as one year. If the unit is out of service continuously for six months or more, the inspection interval may be extended for an equivalent period.

SQNP SI-114.2

Pege 2 of 67 Rev. O The inspection interval.shall be separated into three inspection periods. Except for examinations that may be deferred to th.e end

     ~                  of the inspection interval, the required examinations shall be performed in accordance with the following schedule.                             .

Minimum Examinations Maximum Examinations Insoection Period comoleted. Percent Comoleted, Percent 3 Years 16 34 7 Years 50 67 10 Years 100 100 The examinations deferred to the end of the inspection interval shall be co=pleted by the end of the inspection interval. 4.0 CODES OF RECORD AND CODE CASES The Sequoyah unit 2 operating license (low power) was issued on-June 26, 1981. Thus, as a minimum the ISI program shall not be prepared- to a Section XI Code Edition and Addenda prior to the 1974 Edition, Summer 1975 Addenda. In accordance with 10 CFR Part 50.55a(g)(4)(iv), this program was prepared to meet the requirements of the 1977 Edition, Summer 1978 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code. Steam Generator Tubing Examination requirements are in accordance with Regulatory Guide 1.83, Rev. 1, and Technical Specification 4.4.5.3. In accordance with 10 CFR Part 50.55a(b)(2), the extent of examination for piping welds Examination Categories B-J and C-F is in accordance with the 1974 Edition, Summer 1975 Addenda of ASME, Section XI (Examination Categories B-J, C-F and C-G). Extent of examination is defined as criteria for the selection of Class A and Class B components for examination and as criteria for determining which Class B components may be exempt from examination. The extent of examination also specifies the location on the components to ,be examined (i.e., length of weld). Preservice examinations were conducted in acecrdance with the 1974 Edition, Summer 1975 Addenda, of the-ASME Section XI (SI-114). The use of Code cases N-234 and N-235 have been approved for TVA use by NRC. 5.0 METHOD OF IMPI.EMENTATION AND RESPONSIBIEITIES Weld maps and othe. pertinent component drawings and tables are

included in Appendix A of this program to define areas subject. to examination (in addition to sections 7.0, 8.0, and 9.0).

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SQNP SI-114.2 Page 3 of 67 Rev. O The Quality Engineering B'anch r (QEB) NDE Section shall prepare scan plans using co=ponent drawings in this program for systems or compcnents requiring examinations for the inservice inspection. The plans should include as a minimum references to components to be examined, methods of examinations, examination procedures, and calibration standards. Prior to performing examinations on a system or component, the scan plans shall be established and submitted to the Plant Superintendent for information. When inservice examinations are implemented by instructions other than this program (i.e., MI's), copies of the instruction data sheets shall be submitted to the Quality Engineering Branch by the performing organination such that these examinations may be included in the reports discussed in Section 16.0. These additional implementing instructions are referenced in Sections 7.1. 6, 7.1. 9, 7.1.11, 7.2.5, 7.3.6, 7.3. 8, 7.5.1, 7.5.5, and 7.6.6 of this program. If variations in piping configurations are discovered or alterations of the unit, or repairs to piping are made during the service life drawings. these changes shall be marked on field copies of This information shall be communicated to the ISI Programs Section which shall be responsible for revising the drawings and incorporating the revised drawings into this program. The NDE Section scan plan shall also be revised to reflect these changes. All latest revision scan plan information and other pertinent information shall be incorporated in this program when each completed. inservice examination required by this program has been The inservice examinations will be performed by either Quality Engineering Branch personnel or outside contractors. Contract preparation, administration, and supervision will be the responsibility of the Quality Engineering Branch NDE Section. Inspection plans and/or Quality Assurance Programs submitted by outside Engineering contractors Branch shall prior be reviewed and approved by the Quality to use. All specific NDE procedures.used during the inspection program shall be reviewed and approved in. accordance with OQAM Part II, Section 6.3. The NDE Section representative will be responsible for notifying the plant superintendent of all unacceptable indications as soon as practical. Whenever an unacceptable indication is discovered, the procedure and form in Appendix D shall be utilized. In those cases where an outside contractor is furnishing inservice examination services, the con. tractor will normally initiate the form in Appendix D under the supervision of the NDE Section representative. See Section 17.0 of this program. l

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SQNP SI-114.2 Page 4 of 67 Rev. O When each inservice examination implemented by this program is completed, the data package cover sheet in Appendix C shall.be completed by the NCO Inspection Section representative and submitted to the plant with the final report discussed in -Section 16.0. ISI program preparation is the responsibility of the ISI Programs Section of the Quality Engineering Branch. Any revisions i initiated by other groups shall be submitted to the ISI Programs Section for approval prior to incorporating the revisions into this program. 6.0 ABBREVIATIONS AND DEFINITIONS 6.1 AIA--Authorized Inspection Agency. 6.2 AI--Authorized Inspector (may denote an ANI or ANII). 6.3 ANI--Authorized Nuclear Inspector. 6.4 ANII--Authorized Nuclear Inservice Inspector. 6.5 Components--Denotes items in a power plant such as vessels, piping systems, pumps, valves, and component supports. 6.6 Examination--Denotes the performance of all visual observation and nondestructive testing such as radiography, ultrasonic, eddy current, liquid penetrant, and magnetic particle methods. 6.7 Inspection--Denotes verifying the performance of exami-nations and tests by a representative of an Authorized Inspection Agency. 6.8 Maintenance--Routine servicing or work on an item undertaken to correct or prevent an unsatisfactory condition. Maintenance does not include welding, heat treating, or defect removal which affects the pressure boundary. Maintenance includes operations such as lapping of valve seats, adjustment of stem packing and pump seal maintenance. Maintenance does not require the presence of or verification by the Authorized Nuclear Inspector or Authorized Nuclear Inservice Inspector. 6.9 Normal Operation--Normal plant operation conditions include { reactor startup, operation at power, hot standby, and reactor cooldown to cold shutdown conditions. Test i conditions are excluded. O e 4

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                                                        -SI-114.2 Page 5 of 67 Rev. 0 6.10     Pressure-Retaining Material--Applies to items such'as vessel heads, no zles, pipes, tubes, fittings, valve bodies, bonnets, disks, pump castings, covers , and boltings which-join pressure-retaihing items.

6.11 Repair--Those operations involving welping, heat treatment, or defect removal which are required t; restore an item to a safe and satisfactory operating condition. - 6.12 Replacement--Replacements include spare and renewal components, or parts of a component (e.g., valve body bonnet, disc, bolting). It also includes the addition of components such as valves and system changes such as rerouting of piping. For the purpose of this procedure, the term replacement shall apply where attachment to the pressure boundary is by welding or mechanical means.

7.0 COMPONENTS SUEJECT TO EXAMINATION--TVA SAFETY CI. ASS A The Class A (ASME Class 1) components to be examined during the inspection interval are outlined in the following paragraphs. The entire length of each weld described will be examined for the first 10 year ISI unless otherwise noted. When a portion of a weld length is to be examined during an inspection period,' the areas examined each inspection period shall be documented on the examination data sheets. All Class A components are subject to volumetric and/or surface examination except components (and their supports) that are one-inch nominal pipe size and smaller (see section 7.7). Table A in Appendix A supplies additional information such as reference drawing numbers and Section XI, Table IWB-2500-1, exami-nation categories. 7.1 Reactor Vessel - 7 7.1.1. Reactor Vessel Seam Welds 7.1.1.1 Circumferential Shell Welds There are four circumferential welds (each approximately 50 feet in length) in the vessel cylindrical shell, three of which are located -behind the thermal shield. The entire length of each of these welds will be ultrasonically examined during the third inspection period.using remote inspection devices from the vessel I.D. with the core internals removed. 4

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1 l SQNP SI-114.2 Page.6 of 67 Rev. O The vessel shell sections are machined forgings fabricated ! of A-508, Class 2, manganese-molybdenum steel and are clad

     . with weld deposited austenitic stainless steel.

7.1.1.2 Loncitudinal Shell Welds There are no longitudinal shell welds associated with the reactor vessel. 7.1.1.3 Closure Head Circu=ferential Weld The entire length of the closure head cap weld (approximately 41 feet in length) will be manually ultrasonically examined from the head outside diameter. The length of weld to be examined each inspection period is included in Table A of Appendix A. The closure head ring is fabricated of A-508, Class 2, manganese-molybdenum steel. The closure head hemispherical section is fabricated of A-533, Gr. B, Class 1, manganese-molybdenum steel. Both sections are clad with veld depos-ited austenitic stainless steel. . 7.1.1.4 Lower Head Circumferential Weld The entire length of the lower head circumfer-ential weld (approximately 38 feet in length) will be ultrasonically examined during the third inspection period using remote inspection devices from the vessel inside diameter with the core internals removed (see Request for Relief ISI-5). The lower head sections are fabricated of A-533,

Gr. B, Class 1, manganese-molybdenum steel, and are clad with weld deposited austenitic stainless steel.

t 7.1.1.5 Closure Head Meridional Weld The closure head does not include any meridional welds. 7.1.1.6 Lower Head Meridional Welds There are six meridional welds (each approxi-mately 4 feet in length) located in the lower

head. The entire length of each of these welds will be ultrasonically examined during the third . .

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SQNP SI-114.2 Page 7 of 67 Rev. O inspection period using remote inspection devices from the vessel inside diameter with the core internals removed. The lower head section' . material is identified in section 7.1.1.4 of this program. 7.1.1.7 Shell-To-Flange Weld The entire length of the shell-to-flange weld (approximately 50 feet in length) will be ultrasonically examined from the vessel inside diameter using remote inspection devices during the third inspection period. The vessel flange section is fabricated of A-508, Class 2, manganese-molybdenum steel and is clad internally and on the gasket face with weld deposited austenitic stainless steel. 7.1.1.8 Closure Head-To-Flance Weld The entire length of the head-to-flange weld (approximately 45 feet in length) will be manually ultrasonically examined from the head outside diameter. The length of weld to be examined each inspection period is included in Table A of Appendix A. The closure head flange section is fabricated of

A-508, Class 2, manganese-molybdenum steel and is clad internally and on the gasket face with weld deposited austenitic stainless s't eel. 7.1.1.9 Repair Welds Base metal weld repairs in the beltline region where the repair depth exceeds 10 percent nominal of the vessel wall shall be ultrasonically examined. 7.1.2 Reactor Vessel Nozzle-To-Vessel Welds There are four inlet nozzles (27-1/2-inch I.D.) and four outlet nozzles (29.937-inch I.D.). The eight nczzle-to-vessel welds will be ultrasonically examined from the inside diameter using remote inspection devices. d-l

SQNP SX-114.2 Page 8 of 67 Rev. O The four outlet no::le-to-vessel welds shall be ultrasonically examined from the no::le bore when the upper internals are removed during the first - inspection period. The inlet nozzles are not- t accessible until the core barrel is removed. The four inlet nozzle-to-vessel welds shall be ultrasonically examined from the no::le bore and from the vessel shell inside diameter during the third inspection period when the core barrel has been removed. The outlet noz le-to-vessel welds shall also be ultra-sonically examined from the vessel shell inside diameter during the third inspection period when the core barrel has been removed. The nozzle forgings are fabricated of A-508, Class 2, manganese-molybdenum steel and are clad with weld deposited austenitic stainless steel. 7.1.2 Reactor Vessel No: le Inside Radius Section The eight no::le inside radius sections (including the outlet no::le integral extensions) shall be ultrason-itally examined at the same time as the examination of the nozzle-to-vessel welds conducted from the nozzle bore (see Section 7.1.2). Nozzle forging material is identified in Section 7.1.2 of this program. 7.1.4 Reactor Vessel Partial Penetration Welds The vessel includes 4 upper head injection nozzles, 1 vent pipe nozzle, 78 control rod drive nozzles, and 58-instrumentation nozzles with partial penetration welds. Approximately 25 percent of each group of nozzles shall be visually examined from the vessel outside diameter in accordance with visual examination method VT-2 (see section 11.1). This 25 percent shall include 1 upper head injection nozzle, I vent pipe nozzle, 20 control rod drive nozzles, and 15 instrumentation nozzles. Examination of these nozzles during the inspection interval shall be distributed among the inspection periods in accordance with Table A of Appendix A.

 --         The NDE Section shall designate in scan plans the nozzles requiring examination to be performed in accordance with SI-146 or SI-250. The examination examination results may be recorded on SI-146 or SI-250 data sheets.

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,                                                                            SQNP SI-124.2 Page.9 of 67 Rev. 0 7.1.5 Reactor Vessel Nozzle-To-Safe End Welds t

The inlet and outlet nozzle-to-safe end welds shall be -

ultrasonically examined from the inside diameter using remote inspection devices. The ultrasonic examination shall be performed at the same time as the examination of the nozzle-to-vessel welds conducted from the nozzle bore (see Section 7.1.2). All of the nozzle-to-safe end welds shall also.be liquid penetrant examined during the inspection interval coincident with the ultrasonic examinations.

            -                                         The Sequoyah Nuclear Plant Unit 2. Report--Evaluation of Cracking in Reactor Vessel Nozzle Stainless Steel Buttering,-Unit 2 nozzle-to-safe end welds 2RC-17SE and 2RC-24SE shall be examined during the first inspection inte rval . The remaining nozzles will be examined i                                                     during the normal inservice inspection intervals.

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                                                    *Each nozzle safe end weld is a stainless steel type 304 weld build up.

7.1.6 Reactor Vessel Pressure Retainine Boltine Larger Than Two Inches In Diameter During each refueling outage all closure studs, nuts, and washers are removed. All of the 54 closure studs and nuts shall be examined during the inspection interval in accordance with Table A of Appendix A. The closure nuts shall be magnetic particle examined and the closure studs shall be ultrasonically and magnetic particle examined. The closure studs may be ultrasonically examined in place under tension, when the closure head is removed, or when the studs are removed. Provisions for this examination are included in . MI-1.2. j All of the 54 ligaments between the vessel flange stud

;                                                  holes shall be ultrasonically examined during the inspection interval in accordance with Table A of Appendix A.

(This provides for ultrasonic examination of the threads in base material.) I - The 54 closure washers shall be visually examined in accordance with visual examination method VT-1 (see section 11.1) during the inspection interval in accordance with Table A of Appendix A. '

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SQNP SI-114.2 Page 10 of 67 Rev. 0 The 7-inch. diameter studs, nuts, and washers are fabricated of SA-540, Gr. B23 Nickel, chrome-molybdenum steel. ~ 7.1.7 Reactor Vessel Pressure Retaining Bolting Two Inches And Smaller In Diameter There is no pressure retaining bolting two inches or smaller in diameter. 7.1.8 Reactor Vessel Intecrallv Welded Attachments There are no integrally welded vessel supports. 7.1.9 Reactor Vessel Interior The vessel interior shall be visually examined in accordance with visual examination method VT-3 (see Section 11.1). These examinations shall include the space above and below the reactor core that is made accessible for examination by removal of components during normal refueling outages. The examinations shall be performed at the first refueling outage and subsequent refueling outages at approximately three year intervals. These examinations are implemented by SMI-0-68-12. i 7.1.10 Reactor Vessel Removable Core Sunnort Structures The visually accessible attachment weld.e sud visually accessible surfaces of the core support structure shall be visually examined in accordance with visual examination method VT-3 (see Section 11.1). This ' examination may be deferred to the third inspection period. The structure shall be removed from the reactor vessel for examination. These examinations are implemented by MI-1.4. 7.1.11 Reactor Vessel Control Rod Drive Housings There are 78 control rod drive housings penetrating the closure head. Each housing includes a pressure retaining dissimilar metal butt weld and canopy seal weld. The canopy seal welds are exempted from _ volumetric or surface examination in.accordance with IWB-1220(a). f %

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SQNP SI-114.2 Page 11 of 67 Rev. 0 There are 20 peripheral control rod drive housings. Two (10 percent) of the peripheral housing butt welds shall be ultrasonically examined during the inspection interval in accordance with Table A of Appendix A. The housings consist of a 6" C.O. adapter of A-182, 304SS and a 4" O.D. body of SI-:67. 7.1.12 Reactor Vessel Auxiliarv Head Adapters Each of the four auxiliary head adapters includes a pressure retain: ng dissimilar metal weld. The four dissimilar metal elds shall be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. The adapters consist of a SA-182, 304SS upper portion and a SB-166 lower portion. 7.2 Pressurizer 7.2.1 Pressurizer Circumferential Shell-To-Head Welds Tharm are two circumferential shell-to-head welds, each approximately 24 feet in length. The entire length of each weld shall be ultrasonically examined during the inspection interval in accordance with Table A of Appendix A. All vessel shell and head sections are fabricated of SA-533, Class 2, manganese-molybdenum steel and are

    .                   clad with austenitic stainless steel.

7.2.2 Pressurizer Loneitudinal Shell-To-Head Welds There is one longitudinal wrid intersecting each circumferential shell-to-head weld. One foot of each longitudinal ~ weld shall be ultrasonically examined

                      ~during the inspection periods in accordance with Table A of Appendix A.

The one foot of weld examined during each examination shall include the length of weld as measured from the point of intersection of the longitudinal wald with the circumferential head-to-shell weld. The Section vessel shell section material is identified in 7.2.1. 7.2.3

  .                   Pressurizer Circumferential a.nd Meridional Head Welds There are no pressurizer circumferential or meridional head welds.

9 SQNP SI-114.2 Page 12 of 67 Rev. 0 7.2.4 Pressurizer No::le-To-Vessel Welds and No::le Inside Radius Section The pressurizer includes three 6-inch safety valve nozzles, one 6-inch relief val e no::le, one 4-inch nozzle, and one 14-inch surge ::zle. All of the i nozzle-to-vessel welds, inclue.r.g nor:le inside radius section, shall be ultrasonically examined during the inspection interval in accordance with Table A of Appendix A. The nozzles are fabricated.of SA-508, Class 2, manganese-molybdenum steel. 7.2.5 Pressurizer Heater penetration Welds There are 78 heater penetration welds located in the pressurizer lower head. Approximately 25 percent of the heater penetration welds (20 welds) shall be visually e.xamined during the inspection interval in accordance with visual examination method VT-2 (see Section 11.1). Examinaticn of these penetrations' during the intpection interval shall be distributed among the inspection periods in accordance with ' Table A of Appendix A. The NDE Section shall designate in scan plans the heater penetrations requiring examination such that the organization performing the examinations may document examination results on SI-146 or SI-250 data sht-es. 7.2.6 Pressurizer Nozzle-To-Safe End Welds Each of the six nozzles identified'in section 7.2.4 includes a welded forging safe end. All of the nozzle-to-safe end welds shall be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. Safe end connections are SA-182, Gr. F-316L forgings. 7.2.7 Pressurizer Pressure Retainine Bolting Larger Than Two Inches In Diameter There is no pressure retaining bolting larger than two inches in diameter. 9

SQNP SX-114.2 Page 13 of 67 Rev. 0 7.2.8 Pressurirer Pr' essure Retainine Boltine Two Inches And Smaller In Diameter All of the p'essurizer r manway bolts shall be visually examined in accordance with visual examination method VT-1 (see Section 11.1). The ~;2minations shall be distributed during the inspect;,a interval in accordance with Table A of Appendix A. The bolts may be examined in place under tension or when the bolts are removed. It is preferrable to perform the examinations when the bolts are removed if possible. Removal of the manway cover is performed in accordance with MI-4.5 and provides for examination of bolting. The manway includes 16 bolts at 1.88 inches in diameter. 7.2.9 Pressurirer Integrally Welded Suevort Attachments The entire length of the pressurizer support skirt-to-vessel weld (approximately 23 feet.in length) shall be surface examined (magnetic particle) during the

       .                       inspection interval in accordance with Table A of Appendix A.

The support skirt is approximately 1.5 inches thick and is fabricated of SA-516, Gr. 70, carbon steel plate. P 7.3 Steam Generators (4) j 7.3.1 Steam Generator Primary Side Circumferential And Meridional Head Welds i i There are no steam generator primary side circumfer-ential or meridional head welds. . 7.3.2 Steam Generator Primarv Tubesheet-To-Head Weld Each steam generator includes a tubesheet-to-head weld (approximately 36 feet in length). The entire length l

    !                        of each weld shall be ultrasonically examined during the inspection interval. The entire length of a tubesheet-to-head weld shall be examined during the first and second inspection periods. The entire i; '                          length of the two remaining welds shall be examined during the third inspection period.

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                                         .                                               SI-114.2 Page 14 of 67 Rev. O The tube plate is a SA-508, Class 2, steel forging, clad on the primary side with NiCrFe alloy. The hemispherical chamber is a SA-216, Gr. WCC casting,       -

clad with austenitic stainless steel. 7.3.3 Steam Generator Primarv Nozzle . -Vessel Welds And No::le Inside Radius Secti n { I The steam generator primary nozzles are an integral part of the vessel. The inside radii of all nozzles cannot be ultrasonically examined and achieve meaningful results due to limitations of examining integrally cast material (see request for relief ISI-6). The no::les are fabricated to SA-216, Gr. WCC. 7.3.4 Steam Generator Pri=ary Nozzle-To-Safe End Welds Each steam generator includes two nozzles with buttered safe ends. Each co::le-to-safe end weld from each generator shall be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. The nozzles have buttered 308L safe ends. 7.3.5 Steam Generator Primarv Pressure Retainine Bolting Larger Than Two Inches In Diameter There is no pressure retaining bo'lting larger than two inches in diameter. 7.3.6 Steam Generator Primary Pressure Retaining Boltina i Two Inches And Smaller In Diameter Each steam generator includes two manways. All the manway bolts from each steam generator manway shall be visually examined in accordance with visual examination method VT-1 (see Section 11.1). The examinations-shall be distributed during the [ inspection interval in accordance with Table A of Appendix A. The bolts may be' examined in place under tension or

    --                                                           when the bolts are removed. It is preferrable to perform the examinations when the bolts are removed if possible. Removal of bolting *is performed in             .

accordance with MI-3.1 and provides for examination of bolting. Each manway includes 16 bolts at 1.88 inches in diameter. D

SQNP

   .                             SI-114.2 Page 15 of 67 Rev. 0 7.3.7  Steam Generato'r Primarv Intecrally Welded Suncort Attachments There are no integrally welded vessel supports. The four main support pads are secured to the steam generator field support syster - high strength bolts.

7.3.6 Steam Generator Tubing Each steam generator tube bundle consists of 3,388 NiCrFe alley (Inconel SB-163) U-tubes of 0.875 0.D. by 0.050 average wall thickness. During the inspection interval, steam generator tubing shall undergo eddy current examination. This examination is done in accordance with Sequoyah technical specifications and satisfies Surveillance Requirement 4.4.5.0. 7.3.8.1 Steam' Generator Samole Selection And Insoection Each steam generator shall be determined operable during the shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 1. 7.3.8.2 Steam Generator Tube Samole Selection and Insoection The steam generator tube minimum sample size inspection result classification, and the corresponding action required shall be as specified in Table SG-2. The inservice inspection of steam generator tubes shall be i performed at the frequencies specified in Section 7.3.8.3, and the inspected tubes - shall be verified acceptable per-the acceptance criteria of section 7.3.8.4. The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes

 ;                 selected for these inspections shall be selected on a random basis except:

a. Where experience in similar plants with

 -                       similar water chemistry indicates critical areas to be inspected, then at least 50% of the~ tubes inspected shall be from these critical areas.
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SQNp SI-114.2 page 16 of 67 - Rev. O

b. The first sample of tubes selected for each inspection (subsequent to the preservice inspection) of each steam generator shall include:

1. All nonplugged tubes that previously had detectable wall penetrations

                     >20%.

2. Tubes in those areas where experience has indicated potential problems.

3. A tube inspection (pursuant to Section 7.3.8.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be evaluated and recorded and an adjacent tube shall be selected and subjected to a . tube inspection, c.

The tubes selected as the second and third samples (if required by Table 2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2. The inspections include those -

portions of the tubes where imperfections were previously found. The results of each sample inspection shall be classified into one of the following three categories: Categorv Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective. 4 T

_;s SQNP SI-114.2 Page.17 of 67 Rev. 0 C'-2 One or more tubes, but not more

than 1% of the total tubes inspected are defective, or -

between 5% and 10% of the total tubes inspected are degraded tubes. C-3 More than 10% of the total tubes inspected'are degraded tubes or more than 1% of the inspected tubes are defective. NOTE: In all inspections, previously degraded tubes must exhibit

    ,                                                    significant (>10%) further wall penetrations to be included in the above percentage calculations.

7.3.8.3 Inspection Frecuencies The above required inservice inspections of steam generator shall be performed at the following frequencies:

a. The first inservice; inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be performed at intervals cf not less than 12 nor more chan 24 calendar months after'the

  ;                                        previous inspection. If two consecutive inspections following service under AVT conditions, not including the preservice inspection,. result in all inspection

i results falling into the C-1 category or if two consecutive inspections ..

demonstrate that previously observed I degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once-per 40 months. -1 j-

b. If the results of the inservice inspec-tion of a steam generator conducted in accordance with Table 2 at 40-month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspectiod frequency shall apply until the subsequent inspections satisfy the criteria of'section 7.3.8.3.a; - -

the interval may then be extended to a maximum of once per,40 mynths.' ~ li v

                                                 . 17..                          -

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         . . . - - - . . _        _      - .. - . _ . _ _ . - _ _ _ , - - . ~ _ ..-, . __                  ,   ....-c     . _ .       _

SQNP SI-114.2

          .                                                        Page.18 of 67 Rev. 0

c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 2 during the shutdown subsequent to any of the following conditions.

1. Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.6.2.

2. A seismic occurrence greater than the Operating Basis Earthquake.

3. A loss-of-coolant accident requiring actuatien of the engineered safeguards.

_ - 4. Abreak. main steam line or feedwater line , F 7.3.8.4 _ Acceptance Criteria a. As used in Section 7.3.8:

1. Imperfect' ion means an exception to'the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20%

of the nominal tube wall thickness, if' detectable,'may be considered as imperfections.

2. Degradation means a service-induced cracking, wastage, wear or general

     .                                                 corrosion occurring on either inside or outside of a tube.

l 3. Degraded Tube means a tube containing [ imperfections >20% of the nominal wall thickness caused by degradation.

4. Percent Derradation means the percent-

  ._                                                  age of the tube wall thickness affected or removed by degradation.

5. Defect means an imperfection of such

                                   '                  severity that it exceeds the plugging A tube containing a. defect is limit.

l

__ defective.

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k SQNP SI-114.2 Tage 19 of 67 -s Rev. 0

6. Pluccing Limit means the imperfection

      '.                                                              depth at or beyond which the tube shall be removed from service because           .

it may become unserviceable prior to the next' inspection and is equal to

40% of the nominal tube wall thickness.

7. Unserviceable describes the condition

        .                                                            of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a J

loss-of-coolant accident, or a steam line 'or feedwater line break as specified in Section 7.3.8.3.c. S. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) com-pletely .rourd the.U-bend to the top support of the cold leg.

9. Preservice Insoeetion ceans a tube inspection of each ster.m generator tube performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be 7 performed prior to initial power i.

operation using the equipment and

techniques expected to be used during subsequent inservice inspections.

i

b. The steam generator shall be determined operable after , completing the corre .

                    '                                      spending actions (plu2 all tubes exceeding the plugging limit and all
'           '                                              tubes containing through-wall cracks) required by* Table 2.

f l 7.4 Piping All Class A piping systems to be examined are fabricated of q stainless steel. The reactor coolant main' loop piping

     ~                               straight lengths are centrifugal cast and the elbows are static cast. The upper head injection auxiliary head adapter.

is included in Section 7.1.1.3. Specific material specifi-

                            '        cations for each piping system are included in weld map isometrics in Appendix A (see Request for Relief ISI-3).
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SQN? S2-114.2 Page.20 of 67 Rev. O The following Class A piping systems are subject to examination: I Reactor Coolant - Chemical and Volume Control Residual Heat Removal Safety Injection Upper Head Injection 1 7.4.1 Piping Dissimilar Metal Welds There are no Class A dissimilar metal welds. 7.4.2 Pipine Pressure Retaining Bolting: Larger Than 2_ Inches In Diameter There is no piping pressure retaining bolting larger than 2 inches in diameter. 7.4.3 Piping Pressure Retaining Boltine 2 Inches and Smaller in Diameter The following sections define the number of bolted piping flange connections in each system. All of the bolts or studs and nuts in each flange connection shall be visually examined during the inspection interval in accordance with visual examination method VT-1 (See Section 11.1). The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. The bolting may be examined in pl.ce under tension or when the bolting is removed. 7.4.3.1 Reactor Coolant Sy' stem Pining Bolting The Reactor Coolant System piping includes eight bolted flange connections.

     '~            7.4.3.2    Chemical and Volume Control System Piping Bolting 1
    .                         The Chemical and Volume Control System piping includes four bolted flange connections (from seal water injection).

7.4.3.3 Residual Heat Removal System Piping Bolting The Residual Heat Removal System piping does. not include any bolted connections.

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SQh*P S1-114.2 Page 21 of 67 l Rev. 0 7.4.3.4 Safety Injection Svstem Piping Bolting The Safety Injection System piping includes - four bolted flange connections. 7.4.3.5 Upper Head Injection System Piping Bolting The Upper Head Injection System piping includes twelve bolted grayloc connectors. 7.4.4 Circumferential and Loneitudinal Pine Welda The entire length of each circumferential pipe weld selected for examination shall be ultrasonically and/or liquid penetrant examined as practical. /11 Class A piping is seamless. Circumferential pipe welds four inches and greater nominal pipe size shall be ultrasonically and liquid

',                                                                penetrant examined. Circumferential pipe welds less than four-inch nominal pipe size shall be liquid penetrant examined.

1 The examinations performed during the inspection interval shall include approximately 25 percent of the 40-year sample of circumferential welds. The examina-tions shall be distributed during the inspection interval in accordance with Table A of Appendix A. 7.4.4.1 Reactor Coolant System Main Loop Piping Circumferential Welds The Reactor Coolant System main loop piping

includes 63 circumferential pipe welds 4 inches and greater nominal pipe size.

Of these welds 16 shall be ultrasonically and liquid penetrant examined during the - inspection interval (see Request for Relief ISI-7). 7.4.4.2 Reactor Coolant' System Piping Circumferential Welds Reactor Coolant System piping includes 62

             '                                                                                                              circumferential pipe welds.4 inches and greater nominal pipe size. . Of these welds 15 shall be ultrasonically and liquid penetrant examined during the inspection interval.

There are 122 pipe welds less than 4-inch nominal pipe size. Of these welds 30 shall be liquid penetrant examined during the inspection inte rval. *

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SQh*P SI-114.2 Page 22 of 67 Rev. 0 7.4.4.3 Chemical and Volume Control System Piping Circumferential Welds Ine Chemical and Volume Control System piping' (including seal water injection) includes 57 circumferential welds less than 4-inch nominal pipe size. Of these welds 14 shall be liquid penetrant examined during the inspection interval. 7.4.4.4 Residual Heat Removal System Piping Circumferential Welds The Residual Heat Removal System piping includes 45 circumferential welds 4 inches and greater nominal pipe size. Of these welds 11 shall be ultrasonically and liquid penetrant examined during the inspection interval. There are no Class A pipe welds less than 4-inch nominal pipe size in the RER system. 7.4.4.5 Safetv In_iection System Piping Circumferential Welds The Safety Injection System piping includes 92 circumferential pipe welds 4 inches and greater nominal pipe size. Of these welds 23 shall be ultrasonically and liquid penetrant examined during the inspection interval. There are 39 pipe welds less than 4-inch nomina,1 pipe size. Of these welds 9 shal1' be liquid penetrant examined during the inspection interval. 7.4.4.6 Uoner Head Iniection Svstem Piping Circumferential Welds The Upper Head Injection System piping . includes 123 circumferential pipe welds

   -                                     4 inches and greater nominal pipe size.

Of these welds 31 shall be ultrasonically i and liquid penetrant examined during the inspection interval. There are no piping welds less than 4-inch nominal pipe size. 7.4.5 Eranch Piping Connection Welds The entire length of each branch pipe connection weld . selected for examination shall be examined. Branch pipe connection welds exceeding 2 inches nominal pipe size shall be ultrasonically and liquid penetrant examined. Branch pipe connection welds 2 inches - nominal pipe size and smaller shall be liquid -. penetrant examined. d

SQNP SI-114.2 Page 23 of 67 Rev. O The examinations performed during the inspection interval shall include approximately 25 percent of the branch pipe connection welds. The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. l 7.4.5.1 Reactor Coolant System Main Loop Branch Pipe l Connection Welds i The Reactor Coolant System Main Loop piping i includes I branch pipe connection weld exceeding 2 inches nominal pipe size. This wsld shall be ultrasonically and liquid penetrant examined during the inspection ! interval. There are 13 branch pipe ' connection welds 2 inches nominal pipe size and smaller. Of these welds 4 shall be liquid penetrant examined during the inspection interval. 7.4.5.2 Reactor Coolant System Branch Pine Connection j Welds The Reactor Coolant System piping includes 7 branch pipe connection welds exceeding 2 inches nominal pipe size. Of these welds 2 shall be ultrasonically and liquid penetrant examined during the inspection interval. There are 7 branch pipe connection welds

        -                           2 inches nominal pipe size and smaller. Of these 4                                    welds 2 shall be liquid' penetrant examined during
                                  ,the inspection interval.

7.4.5.3 Chemical and Volume Control System Branch Pipe Connection Welds The Chemical and Volume Control System piping includes 4 branch pipe connection welds exceeding 2 inches nominal pipe size. Of these welds I shall be ultrasonically and liquid penetrant examined during the inspection interval. There are no branch pipe connection welds 2 inches nominal pipe size and smaller that shall be liquid penetrant examined during the inspection interval. 7.4.5.4 Residual Heat Removal System Branch Pipe Connection Welds l The Residual Heat Removal System piping includes 3 branch pipe connection welds

l exceeding 2 inches nominal pip'e size. Of these t ., .

i e _ . . _ - ,. , , - - m. __ w-

_ SQNP S2-314.2 Page 24 of 67 Rev. O welds I shall be ultrasonically and liquid pene-trant examined during the inspection interval. There are 2 branch pipe connection welds 2 inches - nominal pipe size and smaller. Of these welds I shall be liquid penetrant examined during the inspection interval. 7.4.5.5 Safety Injection System Branch Pine Connection Welds The Safety Injection System piping includes 6 branch pipe connection welds exceeding 2 inches nominal pipe size. Of these welds 2 shall be ultra-sonically and liquid penetrant examined during the inspection interval. There are 10 branch pipe connection welds 2 inches nominal pipe size and smaller. Of these welds 3 shall be liquid penetrant examined during the inspection interval.

            ~ 7.4.5.6   Upper Head Injection System Branch Pipe Connection Welds The Upper Head Injection Sys' tem piping includes 2 branch pipe connection welds 2 inches nominal pipe size and smaller. Of these I shall be liquid penetrant examined during the inspection inte rval .

7.4.6 Pipine Socket Welds The entire length of each socket weld selected for exami-nation shall be liquid penetrant examined. The examinations performed during the inspection interval shall include approximately 25 percent of the socket welds. The examinations shall be distributed during the inspec-tion interval in accordance with Table A of Appendix A. 7.4.6.1 Reactor Coolant System Piping Socket Welds i The Reactor Coolant System piping includes i- 239 socket welds. Of these welds, 60 welds will be examined during the inspection interval. 7.4.6.2 Chemical and Volume Control. System Pip'ing Socket Welds The Chemical and Volume Control System piping

'                     includes 224 socket welds. Of these welds, 56 welds will be examined during the inspection interval.                                              ~
                                                                                ~

? L- 24

SQNP SI-134.2 Page.25 of 67 Rev. 0 7.4.6.3 Residual Heat Removal System Piping Socket Welds The Residual Heat Removal System piping includes IS socket welds. Of these welds,

5 welds will be examined during the inspec-tion interval. 7.4.6.4 Safety Iniegtion System Piping Socket Welds The Safety Injection System piping includes 176 socket welds. Of these welds, 44 welds will be examined during the inspection interval. 7.4.6.5 Upoer Head In_iection System Pining Socket Welds The Upper Head Injection System piping includes 16 socket welds. Of these welds, 4 welds will be examined during the inspection ~ interval. 7.4.7 Picine and Valve Inteerally-Welded Sueport Members Integrally-welded support members include the support attachments of piping required to be examined by Examination Category B-J. Included are those supports which have attachment welds to the valve and piping pressure retaining boundary and those attaccments whose sunport base material design thickness is 5/8 inch and creater. The entire length of each support attachment weld selected for examination shall be surface examined. The examinations performed during the inspection - interval shall include 100 percent of the integrally-welded support members. The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. 7.4.7.1 Reactor Coolant System Piping and Valve Intecrally-Welded Support Members The Reactor Coolant System piping includes

9 integrally-welded support members. All of these shall be examined during the inspection-interval. l

SQNp SI-114.2 Page 26 of 67 Rev. 0 7.4.7.2 Chemical and Volume Control System Piping

          .-                      and Valve Intecrally-Welded Support Members The Chemical a.nd Volume Control System piping includes 1 integrally-welded support member.

This support shall be examined during the inspection interval. 7.4.7.3 Residual Heat Removal System Pining and Valve Integrally-Welded Sunport Members The Residual Heat Removal System piping includes 2 integrally-welded support member. Both supports be examined during the inspection interval. 7.4.7.4 Safety Injection System Pipine and Valve Intecrally-Welded Support Members The Safety Injection System piping includes 8 integrally-welded support members. All of these shall be examined during the inspection interval. 7.4.7.5 Upper Head Iniection System Pipine and Valve Intecrally-Welded Supports The Upper Head Injection System piping includes 1 integrally-welded support member.

       -                       This support shall be examined during the inspection interval.

7.4.8 Piping and Valve Component Supports

     .              All piping and valve component supports of piping required to examined by Examination Category B-J shall 3

be visually examined during the inspection interval in accordance with visual examination methods VT-3 and

"^

VI-4 (see section 11.2). This examination includes integrally-welded and nonintegrally-welded component supports. i Component supports extend from the piping and valves to and including the attachment to the supporting structure. [ The setting of snubbers, shock absorbers, and spring-type hangers shall be verified. The tetting of snubbers and shock absorbers is performed in accordance with SI-162. . De

   .ume 9
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1

          .                                                  SQNP
                                      '                      SI-214.2 l

Page 27 of 67 t Rev. O i i The examinations shall be distributed during the j

         ..                        inspection interval in'accordance with Table A of Appendix A.

7.4.8.1 Reactor Coola'nt Svstem Pioing and Valve Component Supports I The Reactor Coolant System piping includes 139 component supports. All of these shall - be examined during the inspection interval. 7.4.8.2 Chemical and Volume Control Svstem Piping and Valve Cocoonent Supports The Chemical and Volume Control System piping includes 114 component supports. All of these shall be examined during the inspection inte rval. 7.4.S.3 Residual Heat Removal System Piping and Valve Comoonent Sucports The Residual Heat Removal System piping includes 17 component supports. All of these shall be examined during the inspection interval. 7.4.8.4 Safety Injection System Piping and Valve Component Supports The Safety Injection System piping includes 103 component supports. All of these shall be examined during the inspection. interval. 7.4.8.5 Upoer Head Injection System and Valve Piping Component Supports - The Upper Head Injection System piping includes 88 component supports. All of these shall be examined during the inspection interval. , 7.5 Reactor Coolant Pumps (4) - RCP 7.5.1 RCP Pressure Retaining Bolting Larger Than Two Inches In Diameter The main flange on each pump includes 24 bolts at 4-1/2 inches in diameter and 30-1/2 inches in length. -4>. g e

       .                                           ~27--

SQNP SI-114.2 Page.28 cf 67 Rev. O All of th'e bolts from each pump shall be ultrason-ically examined during the inspection interval. The bolts may be examined in place under tension or when removed. All of the bolts from one pump shall be examined during the first inspection period, and all of the bolts from a different pump shall be examined during the second inspection period. All of the bolting from the two remaining pumps shall be examined during the third inspection period. Removed, the bolts shall be ultrasonically and magnetic particle examined. This examination needs to be performed only once during the. inspection interval and may be deferred to the third inspection period. Provisions MI-2.2. for this e'xamination are included in When a main flange connection is disassembled, the threads in the base material and flange ligaments

                      -between threaded bolt holes shall be visually examined in accordance Section   11.1). with visual examination method VT-1 (see included in MI-2.2.Provisions for this examination are The main flange bolts are fabricated of 4340 steel, heat treated to A-540, Gr B24.

g 7.5.2 RCP Pressure Retaining Boltine 2 Inches and Smaller

< -                    in Diameter Each RCP includes three sets of pressure retaining bolting 2 inches and smaller in diameter. The bolting sets include the Nos. 1, 2, and 3 seal assembly           -

bolting. All of the bolting from each pump seal assembly shall be visually examined in accordance with visual examination method VT-1 (see Section 11.1), The bolting may be exsmined in place under tension or ' when removed. It is preferable to perform the examinations when the bolts are removed if the connection (s) is disassembled. Removal of bolting is performed in accordance with MI-2.1 and provides for __ examination of bolting. All of the bolting from one RCP shall be examined

   .                 during the first inspection period, and all of the ,

bolting from a different pump shall be examined during. the second inspection period. All of the bolting from the remaining two pumps shall be examined during the

  ..                 third inspection period.
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1 SQh'P SI-114.2 Page.29 of 67 Rev. O : The Nos. 1, 2," and 3 seal housing bolting includes 12 socket head cap screws at 2 inches in diameter, 12 socket head cap screws at 1 inch in diameter, and 12 socket head cap screws at .375 inches in diameter respectively. 7.5.3 RCP Integrallv-Welded Sueport Members There are three unit 2 reactor coolant pumps, serial numbers 566 (RCP-1 casing), 704 (RCP-3 casing), and 709 (RCP-4 casing), with integrally welded supports. Each pump has three integrally welded pump feet. These integrally welded pu=p feet whose . design base is > 5/8 of an inch shall be surface examined during the inspection interval in accordance with Table A of Appendix A. The examination shall cover 100 percent of the required area of each support attachment. All of the supports from one RCP shall be examined

                       'during the first inspection period, and all of the supports from a different pump shall be examined during the second inspection period. All of the supports from the remaining two pumps shall be examined during the third inspection period.

7.5.4 RCP Component Supports Each RCP includes three integrally cast pump feet bolted to the support system. All component supports from each pump shall be visually examined during the inspection interval in accordance with visual examination method VT-3 (see Section 11.1). Support components extend from the RCP to and including the ( attachment to the supporting structure. 7.5.5 RCP Casing Welds . The unit 2 reactor coolant pumps do not include casing welds. 7.5.6 RCP Casing If a pump is disassembled for maintenance during the

   -                   inspection interval, the internal pressure boundary surfaces shall be visually examined.in accordance with visual examination method VT-1 (see Section 11.1).

Disassembly of RCP's is performed in accordance with MI-2.2 and provides for these visual examinations. he !! l

SQNP SI-114.2 Page.30 of 67 Rev. O If during the inspection interval a pump from either unit 1 or unit 2 is not disassembled for maintenance, a pump from one unit shall'be examined from the - exterior by ultrasonic thickness measurements. (See Request for Relief ISI-1.) 7.5.7 RCP Flvwheel At approximately 3-year intervals each pump flywheel shall undergo an in-place ultrasonic examination of areas of higher stress concentration at the bore and keyway. A complete in-place ultrasonic examination shall be conducted at approximately 10-year intervals along with a surface , examination of exposed surfaces. (See Regulatory Guide 1.14.) This examination is done in accordance with Sequoyah technical specifications and satisfies Surveillance Requirement 4.4.10. The flywheel. consists of 2 plates, approximately

                                   'S inches and 8 inches thick, bolted together. Each plate is fabricated from vacuum degassed A-533, GR. B, Class 1, steel.

7.6 Valves . Systems including class A valves subject to examination are identified in Section 7.4.

,                       7.6.1       Valve Pressure Retaining Boltine Larger Than 2. Inches

, in Diameter There are no valves with pressure retaining bolting larger than 2 inches in diameter. 7.6.2 Valve Pressure Retaining Bolting 2 Inches and Smaller in Diameter

The following sections define the number of valves with bolted bonnet connections in each system. All of the bolts or studs and cuts in each connection shall be visually examined during the inspection interval in accordance with visual examination method VT-1 (see Section 11.1). The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A.

The bolting may be examined in place under tension or when the bolting is removed. It is preferable to examine the bolting when removed if possible. Valve disassembly is performed in accordance with MI-6.15 and provides for examination of bolting. - I I

              ~       -
                             , - .         ., ,.      ,-   ---,,-n.,.          , . - - , , , -   - , , , , , . a e r,.,ee-     .- 4

SQN? SI-114.2 Page 31 of 67 Rev. 0 7.6.2.1 Reactor Coolant System Valve Bolting Tne Reactor Coolant System includes 14 valves - with bolted bonnet connections. 7.6.2.2 Chemical and Volume Control System Valve Bolting The Chemical and Volume Control System includes 6 valves with bolted bonnet connections. 7.6.2.3 Residual Heat Removal System Valve Bolting The Residual' Heat Removal System includes 2 valves with bolted bonnet conenetions. 7.6.2.4 Safety Injection System Valve Bolting The Safety Injection System includes 23 valves with bolted bonnet connections. 7.6.2.5 Unoer Head Injection Svstem Valve Bolting The Upper Head Injection System includes 8 valves with bolted bonnet connections. 7.6.3 Valve Integrally-Welded Sutoort Members Examination of valve integrally-welded support members

             .         is included in Section 7.4.7.

7.6.4 Valve Component Supports Examination of valve component supports is included in Section 7.4.8. . 7.6.5 Valve Body Welds There are no valves with' body welds. t'

  ;            7.6.6  Valve Bodies u

The internal surfaces of valve bodies exceeding 4-inch nominal pipe size shall be visually examined in accordance with visual examination method VT-1 (see Section 11.1). Examinations are limited to one valve within each group of valves that are of the same ) constructional design (i.e., globe, gate, or check l valve), manufacturing method, and that are performing t similar functions in the system. * - m l

SQNP SI-114.2 Page 32 of 67 Rev. O When it becomes necessary to disassemble any valve, subject to internal surface visual examination, for

~~

normal maintenance purposes, the interior surface of ; the valve body will be visually examined and the . results recorded. Disassembly of valves solely for

          -                              visual examination will not be performed (See ASME Section XI, Table IWB-2500, Examination Category B-M-2; also see Request'for Relief ISI-2).

A tabulation of valves by groupings is presented in Table D of Appendix A. Disassembly of valves is performed in accordance with MI-11.4 and provides for examination of valve internal surfaces. 7.7 Exemoted Components Components exempted from examination include component connections, piping, and associated valves and their support that are one inch nominal pipe sire and smaller, except for steam generator tubing; components connected to and part of the reactor coolant pressure boundary. (defined in 10 CFR 50, Section 50.2(V); revised January 1,1975) but exempted from Class I requirements by regulations of the regulatory authority having jurisdiction at the plant site; reactor vessel head connections and associated piping, 2 in. nominal pipe size and smaller, made inaccessible by control rod drive penetrations. 7.8 System Pressure Tests All Class A pressure-retaining components shall be subjected to a system leakage test in accordance with IWB-5221 of ASME Section XI each refueling outage. This is performed in accordance

with SI-146. In addition, all Class A pressure-retaining components shall undergo a system hydrostatic pressure test in accordance with IWB-5222 of ASME Section XI at the end of the inspection interval. This is performed in accordance with SI-250. ~ The .

components shall be visually examined during the pressure tests in accordance Section 11.1). All Class with visual exrmination method VT-2 (see A (ASME Class 1) System Pressure Tests i .- shall be performed in accordance with DPM ' SEQ 82E1. [, 8.0 COMPONENTS SUBJECT TO EXAMINATION - TVA SAFETY CLASS B The Class B (ASME Class 2) components to be examined during the

  -                     inspection interval are outlined in the following paragraphs. Extent of examination for piping welds will be in accordance with paragraph IWC-2411 and Table IWC-2520 of the 1974 Edition, Summer 1975 Addenda, ASME Section XI. The ISI Programs Section shall select areas to be examined or the NDE Section may assist in selecting areas to be examined.

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SQNP SI-114.2 Page 33 of 67 Rev. 0 Components that are exempted from examination in accordance with IWC-

1220 of ASME Section XI are discussed in Section 8.7 of this. program.

Where examinations specify a percentage of the total length of weld be examined, the areas (s) examined"shall be documented in the examination report.

Where a percentage of weld length is not referenced, the entire weld length shall be examined. (See Request for Relief ISI-3.) Table B in Appendix A supplies additional information such as reference drawing numbers and ASME Section XI Table-IWC-2500-1 examination categories. 8.1 Steam Generators (4) 8.1.1 Steam Generator Secon'dary Side Circumferential Shell Welds There are three circumferential shell welds at gross structural discontinuities on each generator. The

                         ' entire length of these three shell welds from one steam generator shall be ultrasonically examined during the inspection interval. The number of welds
      .                   to be examined during each inspection period shall be in accordance with Table B of Appendix A.

One of the three welds on each steam generator is partially inaccessible for examination due to the upper steam generator support arrangement (weld nos. SGW-DI, D2, D3, and D4; see Request for Relief ISI-4). r The weld selected for examination shall be ultrason-i ically examined on a best effort basis, The vessel shell sections are fabricated of SA-533,

GR. A, Class 1, steel plate.

8.1.2 Steam Generator Secondary Side Circumferential Head Welds Each steam generator includes a circumferential head-to-shell weld. The entire length of one head-to-shell weld {. shall be ultrasonically examined during the inspection L. interval in accordance with Table B of Appendix A. The weld selected for examination may be from the generator selected for examination by Section.8.1.1. The vessel head section is fabricated of SA-533, GR. A, Class 1, steel plate. 984 I i

SQNP SI-114.2 Page 34 of 67 Rev. 0 8.1.3 Steam Generator Secondarv Side Tubesheet-To-Shell Weld Each steam generator includes a tubesheet-to-s. bell weld. The entire length of one tubesheet-to-shell weld shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The weld selected for examination may be from the generator selected for examination by section 8.1.1 The tube plate is a SA-SOS, Class 2, steel forging. S.I.4 Steam Generator Secondary Side Nozzle-To-Vessel Welds Each steam generator includes one feedwater no::le (3.62 inches nominal vessel thickness) and one main steam no::le (3.62 inches nominal vessel thickness). All of the no::le-to-vessel welds from each generator shall be ultrasonically and magnetic particle examined during the inspection interval in accordance with Table B of Appendix.A. The no::les are fabricated of SA-508, Class 2, steel. 8.1.5 Steam Generator Secondary Side Inteerally-Welded Suonert Attachments There are no integrally welded vessel support attachments. 8.1.6 Steam Generator Secondary Side Comoonent Supports There are no component supports (including mechanical and hydraulie supports) which are in contact with the vessel. 8.1.7 Steam Generator Secondary Side Pressure Retaining. Boltine Exceeding 2 Inches in Diameter There is no steam generator secondary side bolting exceeding 2 inches in diameter. 8.2 Residual Heat Removal Heat Exchaneers (2) - RHRHX 8.2.1 RHRHX Circumferential Welds - t I l e l W

                                                                                                     , , ,      ..-,s     , ,

9

       ..                               SQNP SI-114.2 Page 35 of 67 Rev. 0 8.2.1.1    RHREX Shell Circumferential Weld              ,

There is one circumferential shell weld located at a gross structural discontinuity on each REREX. The entire length of this shell weld from one heat exchanger shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The RHRHX shell section is fabricated to SS, SA-182, F304. S.2.1.2 RHRHX Head Circumferential Weld There is one circumferential head-to-shell weld per RERHX. The entire length of one head-to-shell weld shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The weld selected for examination may be from the heat exchanger selected for examination by section 8.2.1.1. The channel cylinder section (shell) and channel head are fabricated from SS, SA-240, TP-304. 8.2.1.3 RHRHX Tubesheet to Shell' Weld There are no RHRHX tubesheet-to-shell welds. 8.2.2 RERHX Nozzle-to-Vessel Welds The channel cylinder section of each RERHX includes one inlet nozzle (14-inch I.D.) and one outlet nozzle (14-inch I.D.) over 1/2-inch nominal thickness. A

       -         total of four nozzle-to-vessel welds from the two RHRHX will be ultrasonically and liquid penetrant examined during the inspection interval.

I The nozzles are fabricated from SS, SA-240, TP-304. 8.2.3 RHRHX Integrallv-Welded Support Attachments There are two integrally-welded support attachments

(1-inch) on each RHRHX whose base material exceeds 1/2-inch nominal thickness. A total of two support pad-to-vessel welds from the RERHX will be liquid penetrant examined during each inspection interval in m== ' ,l,

SQNP ST-114.2 Page 36 of 67 Rev. O accordance dith Table B of Appendix A. The welds selected for examination may be conducted on one heat exchanger and shall cover 100 percent of the required ' area of each support attachment. The support pad is fabricated from SS, SA-240, TP-304. S.2.4 REREX Comoonent Supports There are two component supports on each RHRHX-which are in contact with the vessel. All component supports from each heat exchanger shall be visually examined during the inspection interval in accordance with visual examinatica method VT-3 (see Section 11.1). Thts examination includes integrally-welded and nonintegrally-welded component supports. Component

                  . supports extend from the heat exchanger to and including the attachment to the supporting structure.

The examinations shall be distributed during the inspection interval in accordance with Table B of Appendix A. There are no mechanical (snubbers) and/or hydraulic (shock absorbers) supports which are in contact with the vessel. S.2.5 RHRHX Pressure Retaining Boltine Exceeding Two Inches in Diameter There is not any RHRHX bolting exceeding two inches in' diameter. 8.3 Recenerative Heat Exchancer (One) - RHX - 8.3.1 REX Circumferential Welds 8.3.1.1 RHX Shell Circumferential 4' elds i

   .                        The regenerative heat exchanger is composed of three heat exchangers interconnected with piping. There are twelve circumferential welds located at structural discontinuities
  '~

on the heat exchanger. There are six channel cylinder to channel head welds and there are six tubesheet-to-shell welds. The channel cylinder sections are fabricated to SS, SA-351, CF8. The channel flanges are ' fabricated to SS, SA-182, F304. , b

SQNP SI-214.2 Pega.37 of 67 Rev. 0 8.3.1.2 lUD: Head Circumferential Welds There are six channel cylinder to channel - head welds. These welds shall be ultra-sonically examined during the inspection interval in Appendix A.accordance with Table B of The examinations shall cover 100 percent of the weld length. The channel heads are fabricated to SS,- SA-240, 304L. S.3.1.3 REX Tubesheet to Shell Weld There are six REX tubesheet-to-shell welds. These welds shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The examinations shall cover 100 percent of the weld length. The tubesheet is fabricated to SA-182, F304 SS. 8.3.2 REX Nozzle-to-Vessel Welds There are not any nozzles greater than four inch diameter. The nozzles are fabricated to SA-479, 304 SCH 160 material. 8.3.3 REX Integrallv-Welded Supports There are not any integrally-welded support attachments on the heat exchanger. There are three stops 5/8" x 5/8" x 1-3/4" welded to the heat exchanger. These stops (lugs) shall be surface 1 examined during the inspection interval. - 8.3.4 RHX Comoonent Supports There are two component supports on the regenerative heat exchanger. Both supports shall be visually examined (VT-3) during the inspection interval in accordance with Table B of Appendix A. 8.3.5 RHX pressure Retaining Bolting Exceeding Two In'ches in

      .           Diameter There is not any pressure retaining bolting associated

s. with the heat exchanger.

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SQNP SI-134.2 Page.38 of 67 Rev. 0 8.4 Letdown Heat Exchanger (One) - LHX S.4.1 LHX Circumferential Welds 8.4.1.1 LHX Snell Circumferential Welds There are not any shell circumferential welds associated with the LHX. S.4.1.2 LHX Head Circumferential Welds There are two circumferential welds located at structural discontinuities on the head side of the LHX. These welds shall be ultra-sonically examined during the inspection interval in accordance with Table B of Appendix A. The examinations shall cover 100 percent of the weld length. The LHX head section is fabricated to SS, SA-240, TP 304. 8.4.1.3 LHX Tubesheet to Shell Weld - There are not any LHX tubesheet to shell welds. 8.4.2 LHX Nozzle-to-Vessel Weld l There are not any nozzles greater than four-inch diameter. The nozzles are fabricated to SS, SA-312, ( 304. 8.4.3 LHX Interrallv-Welded Supports t ,J

i. There are two integrally-welded support attachments on the LEX whose base material design thickness is 1/2 inch and therefore requires no examination in

    .                      accordance with Table IWC-2500-1 of ASME Section XI.

8.4.4 LHX Component Supports

}'

There are two component supports on the letdown heat exchanger. Both supports shall be visually examined (VT-3) during the inspection interval in accordance 4 with Table B of Appendix A. L. 8.4.5 LHX Pressure Retaining Bolting Exceeding Two Inches in Diameter l'- The channel flange bolting associated with the LHX is . . less than two inches in diameter. l._ l{ ~38-H. \

SQNP S1-124.2 Page 39 of 67 Rev. 0 The flange ine'ludes 24 studs with nuts at 7/8 inch diameter. The studs and nuts are fabricated to SA-193, GRB7 and SA-194, GR2H, respectively. 5.5 Excess Letdown Heat Exchancer"(One) - ELEX 8.5.1 ELEX Circumferential Welds S.5.1.1 ELHX Shell Circumferential Welds There are not any shell circumferential welds associated with the ELHX. S.5.1.2 ELHX Head Circumferential Welds There is one circumferential weld, the channel flange to channel head, located at a structural discontinuity on the head side of the ELHX. This weld shall be ultrasonically examined during the inspection interval in accordance with Table 'B of Appendix A. The

            -                        examination shall cover 100 percent of the weld length.

The channel flange and the channel head are fabricated to SA182, F316 and SA-240, TP316, respectively. 8.5.1.3 ELHX Tubesheet to Shell Weld There are not any ELHX tubesheet to shell welds. 8.5.2 ELHX Nozzle to Vessel Welds There are not any nc zles greater than four-inch - diameter. The nozzles are fabricated to SA-312, 316. 8.5.3 ELHX Integrallv-Welded Supports There are no integrally-welded supports to the head side of the ELHX. 8.5.4 ELHX Component Supports There are no component supports to the head side of the ELHX. 8.5.5 ELHX Pressure Retaining Bolting Exceeding Two Inches l in Diameter \ - . The channel flange bolting associated with the ELHX is less than two inches in diameter.

SQNP SI-134.2 Page 40 of 67 ~ Rev. O The flange. includes 12 studs with nuts at 1-5/8 inch diameter. The studs and nuts are fabricated to SA-193, GRB7 and SA-194, GR2H, respectively. 8.6 Boron Injection Tank (One) - BIT S.6.1 BIT Circumferential Welds (Shell and Head) There are two circumferential head-to-shell welds located at structural discontinuities on the BIT. These welds shall be ultrasonically examined during the inspection interval in recordance with Table 2 of Appendix A. The examination shall cover 100 percent of the weld length. The head and shell are SA-264 material consisting of SA-516, GR70 steel backing outside with 1/8 inch SA-240, TP304L cladding inside. 8.6.2 ' BIT Nozzle-to-Vessel Welds There are two no::les, one located on each head with a 4 six-inch inside diameter whose nominal thickness (2.00 in.) is greater than 1/2 inch. These nozzle to vessel welds shall be ultrasonically and surface examined during the inspection interval in accordance with Table B of Appendix A. The examination shall cover 100 percent i of the weld length. The nozzles are fabricated to SA-350, LE2. 8.6.3 BIT Interrallv-Welded Supports There are four integrally-welded support attachment

             -                                                  pads welded to the shell, whose base material design thickness is 3/8 inch and therefore requires no .

examination in accordance with Table IWC-2500-1 of ASME Section XI. 8.6.4 BIT Component Supports i

             ' -                                               There are four component supports associated with the boron injection tank. All of these supports shall be visually examined (VT-3) during the. inspection interval in accordance with Table B of. Appendix'A.

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SQNP

SI-114.2 ' Page 41 of 67 1 Rev. O 1 l S.6.5 LIT Pressttre R'etainine Boltine Exceeding Two Inches in Diameter There are 16*manway cover studs at 2-1/2 inches in diameter. All 16 studs shall be ultrasonically examined during the inspection nterval in accordance with Table B of Appendix A. The studs may be examined in place under tension or when they are removed. It is preferrable to perform the examinations when the studs are removed if possible. The studs and nuts are fabricated to SA-193, GRB7 and SA-194, GR2H, respectively. 8.7 UHI Water Accumulator (One) WA S.7.1 WA Head and Shell Circumferential Welds There are two circumferential welds located'at struc-tural discontinuities. These two head to shell welds shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The examinations shall cover 100 percent of the weld length. The head and shell are fabricated to SA-516-71-70. E.7.2 WA No=zle-to-Vessel Welds The WA has three 12-inch nozzles whose nominal thick-ness is over 1/2 inch, one on the. top head and two on the bottom head. These nozzles to vessel welds shall be surface and ultrasonically examined during~the inspection interval in accordance with Table B of Appendix A. I' The nozzles are fabricated to SA-350, LF2. 8.7.3 WA Integrallv-Welded Supports

    ,              The water accumulator has an integrally welded support skirt attached to the bottom head. The support skirt-to-vessel weld shall be surface examined during the inspection interval in accordance with Table B of Appendix A. The examination shall cover 100 percent of the weld length.                            ,

i The integrally welded portion of the support skirt.is fabricated to SA-516, GR70. L.

SQNP SI-114.2 Page 42 of 67 Rev. 0 8.7.4 WA Component Support The water accumulator has a component support s k'irt attached to the bottom head'. The component support ' shall be visually examined (VT-3) during the inspection interval in accordance with Table B of Appendix A. S.7.5 WA Pressure Retainine Bolting Exceedine Two Inches in Diameter There are 16 manway cover studs at 2-1/2 inches in diameter. All 16 studs shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The studs may be examined in place under tension or when they are removed. It is preferrable to perform the examinations when the studs are removed if possible. The studs and nuts are fabricated to SA-193, GRB7 and SA-194, CL2H, respectively. 8.8 UHI Suree Tank (One) - ST 8.8.1 ST Head and Shell Circumferential Welds There are two circumferential welds located at structural discontinuities. These two head to shell

welds shall be ultrasonically examined during the inspection interval in accordance with Table B'of

      '              Appendix A. The examinations shall cover 100 percent of the weld length.

The head and shell are fabricated to SA-240, TP304. 8.8.2 ST Nozzle-to-Vessel Welds There are not any nozzles greater than four-inch ' diameter associated with the surge tank. The nozzles are fabricated to SA-479, TP304 and 9 SA-182, F304. 8.8.3 ST Integrallv-Welded Supports There are two saddle type support pads integrally welded to the shell. These pad to vessel welds shall be surface examined during the inspection interval in

accordance with Table B of Appendix A. The examination shall cover 100 percent of the weld length.

The support pads are fabricated to SA-240, TP304.

l SQNP SI-114.2 Page 43 of 67 Rev. O S.S.4 ST Cocoonent S'unoorts There are two component supports associated with the surge tank. Both these component support shall be visually examined (VT-3) during the inspection interval in accordance with Table B of Appendix A. 8.8.5 ST Pressure Retaining Bolting Exceedine Two Inches in Diameter There are not any pressure retaining bolting exceeding two inches in diameter. There are 24 1-inch studs and nuts associated with the surge tanks two handholes. The studs and nuts are fabricated to SA-193, GRB7 and SA-194, GR2H. 8.9 Piping Material specifications for each piping system are included in weld map iscmetrics in Appendix A. The following Class B piping systems are subject to examination: Residual Heat Removal Safety Injection < Main Steam Feedwater Containment Spray Upper Head Injection 8.9.1 Pinine and Valve Interrally-Welded Suoports Integrally-welded supports include the support - attachments of piping required to be examined by t Examination Category C-F. Included are those supports which have attachment welds to the valve and piping pressure retaining boundary, and those attachments whose support base material design thickness exceeds 3/4 inch. The entire length of each support attachment weld selected'for examination shall be surface examined. i The examinations performed during the inspection interval shall include 100 percent of the integrally-welded support members. The examinations shall'be distributed during the inspection interval in accordance with Table B of Appendix A. 8.9.1.1 Residual Heat Removal System Piping and Valve Integrally-Welded Supports The Residual Heat Removal System piping does l' not include any integrally-welded supports. \ (~_ l

SQNP SI-124.2 Page 44 of 67 Rev. 0 8.9.1.2 Safety Injection Svstem Pipinz and Valve Inteerally-Welded Supports The Safety Injection System piping includes

7 integre.lly-welded supports. All of these shall be examined during the inspection interval. 8.9.1.3 Main Steam System Piping and Valve Integrally Welded Supports The Main Steam System piping includes 9 integrally-welded supports. All of these shall be examined during the inspection interval. 8.9.1.4 Feedwater Svstem Piping and Valve Integrally-Welded Supports The Feedwater System piping includes 4 , ; integrally-welded supports. .All of these 1 shall be examined during the inspection interval. 8.9.1.5 Containment Soray Svstem Piping and Valve Integrally-Welded Supports

      ;                               The Containment Spray System piping does not include any integrally-welded supports.
    ;                       8.9.1.6 Upper Head Injection Svstem Piping and Valve j

Intecrally-Welded Supports The upper head injection system piping L includes 4 integrally-welded supports. All of these shall be examined during the - inspection interval.

                    -8.9.2 Piping and Valve Comoonent Supports All piping'and valve component supports shall be
   ;_                      visually examined during the inspection interval in accordance with visual examination methods VT-3 and
   ;                       VT-4 (see Section 11.1). This examination includes integrally-welded and nonintegrally-welded component supports. Component supports extend from the piping and valves to and including the attachment to the-supporting structure.

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SQNP SI-314.2 Page.45 of 67 Rev. 0 The setting oE snubbers, shock absorbers and spring-type hangers shall be verified. The setting of snubbers and shock absorbers is performed in - accordance with SI-162. The examinations shall be distributed during the inspection interval in accordance with Table B of Appendix A. 8.9.2.1 Residual Heat Removal System Piping and Valve Component Supports The Residual Heat hemoval System piping includes 82 . component support's. All of these shall be examined during the inspection interval. 8.9.2.2 Safety Injection Systir Piping and Valve Ccenonent Supports The Safety Injection System piping includes 53 component supports. . All cf these shall be

       .                examined during the inspection interval.

8.9.2.3 Main Steam Svstem Piping and Valve Component Supports The Main Steam'Svstem piping includes 72 component supports. All of these shall be

    ,                  examined during the inspection interval.
     ~

8.9.2.4 Feedwater Syst'em Pining and Valve Comnonent Supports The Feedwater System piping includes 35 component supports. All of these shall be examined during the inspection interval.- i 8.9.2.5 Cont'ainment spray System Piping and Valve { . Component Supports , The Containment Spray System piping includes 5 component supports. All of these shall be examined during the inspection interval. 8.9.2.6 Upper Head Injection System Piping and' Valve Cocoonent Supports The upper head injection system piping

  ..                  includes 7 component' supports. All"of these            .

shall b'e examined during the, inspection interval. * *

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SQNP SI-114.2 Page 46 of 67 Rev. O

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S.9.3 Pressure-hetainine Bolting There is nc Class B Pressu're-Retaining Bolting larger' -

                               ! ' than t'ws inches in diameter.

8.9.4 Circumferential and Lengitudinal Pipe Welds q The entire length of each weld selected for exami-nation shall be ultrasonically and/or surfaced examined. Selection of welds for examination is based on Table IWC-2520, Paragraph IWC-1220, and Paragraph IWC-2411 (Summer 1975 Addenda). All of the welds selected approximately 25 percent.of the 40-year sa=ple shall be examined during the inspection interval. The examin'ations shall be distributed in accordance with Table B of Appendix A. Circumferential and longitudinal piping welds in piping with a nominal wall thickness of 1/2 inch or

                                      'less shall be surface examined. Circumferential and longitudinal piping welds in piping with a nominal vall thickness greater than 1/2 inch shall be ultrasonically and surfaced examined.

The areas subject to examination include circumfer-ential pipe welds, at structural discontinuities within 3 pipe diameters of the centerline of rigid pipe anchors, anchors at the penetration of primary containment or at rigidly anchored components, and. longitudinal weld joints in pipe fittings.

S.9.4.1 Residual Heat Removal Piping The Residual Heat Removal Piping System - includes 42 Class B circumferential and 8 l Class B longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to examination. There are 175 circumferential and 46 longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less subject to examination. Five circumferential and one longitudinal piping weld with a nominal wall thickness greater ! than 1/2 inch shall be ultrasonically and

                '                                 surfaced examined each inspection interval.
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There are 26 circumferential and 7 longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less that shall be surface examined each inspection interval. jy See Table B of Appendix A for scheduled inspections. ( l . 1 1 L. '

                          --r       -

i i SQNP SI-114.2 j dage 47 of 67 Rev. O S.9.4.2 Safety Injection Piping The. Safety Injection Piping System includes 68 Class B circumferential and no Class B longitudinal piping velds with a nominal wall thickness greater tha..1/2 inch subject to examination. There are 61 circumferential and 12 longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less subject to examination. Eight circumferential piping welds with a nominal wall thickness greater than 1/2 inch shall be ultrasonically and surf ace examined each inspection interval. There are 7 circumferential and 1 longi-tudinal pipe welds with a nominal wall thickness of 1/2 inch or lass that shall be surfaced examined each inspection interval. See Table B of Appendix A for schedule inspections. 8.9.4.3 Main Steam Piping The Main Steam Piping System includes 48 Class B circumferential and 18 Class B longitudinal piping welds with a nominal wall

                         ' thickness greater than 1/2 inch subject to examination. The piping size is 32" O.D. x 1.038 wall unless noted. Twelve circum-ferential and four longitudinal piping welds shall be ultrasonically and surfaced examined each inspection interval. TVA intends to terminate main steam Class B on each main
                         ' steam loop after the check valve (1-623, 1-624, 1-625, 1-626) following the MSIV (1-4, 1-11, 1-22, 1-29) for ISI purposes.

See Table B of Appendix A for scheduled - inspections. 8.9.4.4 Feedwater Piping The Feedwater Piping System includes 31 Class B circumferential velds and 1 longitudinal weld with a nominal vall thickness greater than 1/2 inch subject to examination. The one longitudinal weld is on Loop 4 at the reducing elbow (18" x 16"). There are 8 circumferential and the one longitudinal I piping welds that sh'all be ultrasonically and surfaced excmined each inspection interval. See Table B of Appendix A for. scheduled

         ,               inspections.

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SQNP SI-114.2 Pagn 48 of 67 Rev. O S.9.4.5 Containment Spray Piping The Containment Spray Piping System includes 10 circumferential and 3 longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less, subject to examination. Three circumferential and 1 *:ngitudinal pipe welds shall be surface examined each inspection interval. The nominal wall thickness for the containment spray system is 0.406 inches. See Table B of Appendix A for scheduled inspections. S.9.4.6 Upper Head Injection Pining The upper head injection piping system includes 42 Class B circumferential welds and no Class B longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to examination. Seven welds shall be ultrasonically and surface examined during the inspection interval. S.9.5 Branch Piping Connection Welds There are no Class B Branch Pipe Connection Welds. 8.10 Pumos 8.10.1 Residual Heat Removal Pumns (2) - RHRP 8.10.1.1 RERP Integrally-Welded Supports There are no integrally-welded supports associated with the RHRP. 8.10.1.2 RHRP' Support Components *

    -                                     Each RERP in'cludes three support components bolted to the pump feet which are integrally forged with the pump. All component supports
   ;_                                     from each pump shall be visually examined during the inspection interval in accordance
   .                                      with visual examination method VT-3 (see I                                      Section 11.1). Support components extend
   '-                                     from the RERP to and including the attachment to the supporting structure.

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          -.                                      SQRP SI-114.2 Page 49 of 67 Rev. O Two o'f the supports from one RHRP shall be examined during the first inspection period.

The final (3rd) support from the same RHRP sha'll be examined during the second inspection period. All of the supports from the remaining RHRP sh. l be examined during the third inspection period. 8.10.1.3 RHRP Supports ' Mechanical and Hydraulic There are no mechanical and hydraulic supports associated with the RHRP. 8.10.1.4 RHRP Pressure Retainine Bolting The stuffing box extension to pump casing connection bolting is not greater than two inches in diameter. The connection includes 24 studs at 1-1/4 inches in diameter with nuts and washers. The studs are fabricated to SA-193, GR. B7, and the nuts to SA-194, GR. 2H. 8.10.1.5 RHRP Casing Welds The RERP does not include any casing welds. The casing is a one piece forging fabricated to SA-182, F304. 8.11 Valves 8.11.1 Valve Integrally-Welded Supports Examination of valve integrally-welded support members is included in Section 8.3.3. .. 8.11.2 Valve Compenent Supports b Examination of valve component supports is included in Section 8.3.4. t i - 8.11.3 Valve Pressure-Retaining Bulting l [ There is no Class B pressure-retaining bolting greater than 2 inches in diameter. .

8.11.4 Valve Body Welds . There are no Class B valves with body welds. l' l ' 1 I i I

SQNP SI-124.2 Page 50 of 67 Rev. O S.12 Pressure Retaining Components All Class B pressure retaining components in systems or portions of systems which are not required to operate during normal reactor operation but for which periodic system or component

       -           functional tests are required (exclui ng open-ended portions of systems), shall be subjected to a ystem functicnal leakage test with each inspection period in accordance with IWC-5221 of AS!E Section XI. This is performed in accordance with SI's to be developed later. Those Class B pressure retaining components in systems or portions of systems not subject to the functional leakage tests (excluding open-ended portions of systems), shall be subjected to a system hydrcstatic test with each inspection interval in accordance with IWC-5222 of AS!E Section XI. This is performed in accordance with SI-265.3. The components shall be visually examined during the pressure tests in accordance with visual examination method VT-2 (see Section 11.1). All Class B (AS!E Class

2) system pressure tests shall be performed in accordance with DPM SEQ 82E1.

8.13 Exemoted Components

    !     -       8.13.1 Exemoted Comoonents [Except Pipine Welds)

Components 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, respectively; (2) components in systems or

   ,                      portions of systems, other than emergency core cooling
   '                      systems, which do not function during normal reactor operation; (3) components which perform an emergency core cooling function for which the control of the chemistry of the contained fluid is verified by
  .                       periodic sampling and test, and (4') component connections, piping, and associated valves, and -

j vessels (and their supports), that are 4-inch nominal pipe size and smaller. 8.13.2 Exempted Components (Piping Welds Only)

        -                Piping exempted from examination include: (a) Piping systems where both the design pressure and temperature I                      are equal to or less than 275 psig.and 200*F, L                       respectively; (b) piping systems or portions of systems other than emergency core cooling systems-which do not function during normal reactor operation;
-                        (c) piping that is 4-inch noininal pipe size and smaller; (d) components which perform an emergency core cooling function provided the control of the chemistry of the contained fluid is verified by periodic sampling and test.

SQNP i

SI-114.2 Paga 51 of 67 ! Rev. 0 9.0 COMPONENTS SUBJECT TO EXAMINATION - TVA SAFETY CI. ASS C AND D Class C and D (ASME Class 3) components shall be subjected to the following examinations and tests. , 9.1 System Pressure Tests All Class C and D (ASME Class 3) system pressure tests shall be performed in accordance with DPM SEQ 82El. 9.1.1 System Inservice Tests '

    .                         Pressure retaining components within the boundary of systems or portions of systems required to operate in support of normal plant safety functions of shutting down and maintaining the reactor in the cold shutdown condition, and pressure retaining piping, pumps, and valves within the boundary or systems or portions of systems required to operate in support of residual
   .                          heat removal from spent fuel storage pool, shall be visually examined in accordance with visual exami-nation method VT-2 (see section 11.1) while the applicable systems are in service under operating pressure in accordanc~e with IWD-5221 of ASME Section XI.

These examinatiens and tests shall be performed during each inspection period. 9.1.2 System Fenetional Tests Pressure retaining components within the boundary of systems or portions of systems required to operate in support of the postaccident safety functions of emergency core cooling, containment heat removal and atmospheric cleanup, and long-term residual heat removal from the reactor vessel shall be visually ~ examined in accordance with visual examination method VT-2 (see Section 11.'1) during a system functional test conducted to verify operability in systems in

 !                          accordance with IWD-5222 of ASME Section XI.

l 9.1.3 System Hydrostatic Tests i Pressure retaining components identified in Sections 9.1.1 and 9.1.2 shall be visually examined in accordance with visual examination method VT-2 (see Section 11.1) durini a system. hydrostatic test conducted ia accordance with IWD-5223 of ASME Section XI. These examinations and tests shall be performed over each inspection interval. y , , e--, ---,-g, +-e - - - g

SQNP SI-114.2 Paga 52 of 67 Rev.'O 9.2 Component Suenorts and Restraints' Component supports and restraints within the boundaries ~of , the systems identified in Sections 9.1.1 and 9.1.2 for components exceeding 4-inch nominal pipe size shall be

         --                  visually examined each inspection period in accordance with visual examination method VT-3 (see Section 11.1).

9.3 Snubbers and Hangers Mechanical and hydraulic snubbers, spring loaded, and ' constant weight support hangers for components exceeding

           -                 4-inch nominal pipe size shall be visually examined each inspection period in accordance with visual examination method VT-4 (see Section 11.l.)

10.0 AUTHORIZED INSPECTOR TVA shall employ an Authorized Inspector (s) in accordance with

       -                ASME Section XI for inservice examinations, repairs, and replacements of TVA Class A, B and C components at Sequoyah Nuclear Plant. The inspector shall verify, assure, or witness that code requirements have been met. He shall have the prerogative and authorization to require requalification of any operator or procedure when he has reason to believe the requirements are not being met. TVA shall provide access for the AI in accordance with IRA-2140 of ASME Section XI.

l, TVA's interface with the Authorized Inspector for inservice inspection, repairs, and replacements is defined in OQAM Part II, Section 2.3 and Part II, Section 5.1 11.0 EXAMINATION METHODS 11.1 Visual Examination Visual examinations that require clean surfaces or - decontamination for valid interpretation of results shall'

t. be preceded by appropriate cleaning processes.

f 11.1.1 Visual Examination VT-1

^^

The VT-1 visual examination shall be conducted to determine the condition of the part, component, or

   ;                                   surface examined, including such conditions as
   '-                                  cracks, wear, corrosion, erosion, or physical damage on the surfaces of the part or components.

i

SQNP SI-114.2 Page 53 of 67 Rev. 0 11.1.I.'1 Direct Visual Examination VT-1 Direct VT-1 visual examination may be . conducted when access is sufficient to place the' eye 24 inches (610 mm) of the surface to be examined and at an angle not less than 30 degrees to the surface. Mirrors may be . sed to improve the angle of vision. Liguting, natural or artificial shall be sufficient to. resolve a 1/32 inch (0.8 mm) black line on an 18% neutral gray card. 11.1.1.2 Remote Visual Examination VT-1

          -                               Remote VT-1 visual examination may be substituted for direct examination.

Remote examination may use aids such as

                                         . telescopes, borescopes, fiber optics, cameras, or other suitable instruments provided such systems have a resolution capability at least equivalent to that i                                 attainable by direct visual examination.

11.1.2 Visual Examination VT-2 i The VT-2 visual examination shall be conducted to locate evidence of leakage from pressure retaining 4 (- components, or abnormal leakage from compenents

      '                   with or without leakage collection systems as required during the conduct of system pressure or functional test.

The visual examination, VT-2; may be conducted without the removal of insulation by examining.the accessible and exposed surfaces and joints of the insulation. Essentially vertical surfaces of t insulation need only be examined at the lowest elevation where leakage may be detectable. Essentially horizontal surfaces of insulation shall

     ..                  be examined at each insulation joint.

For components whose external insulation surfaces are inaccessible for direct examina. tion, only the examination of surrounding area, including floor areas or equipment surfaces located underneath the

.;                       components, for evidence of leakage, or other areas to which such leakage may be channeled, shall be required.
                                                                                           . l l

1

l l SQNP SI-124.2 ' Page 54 of 67 Rev. 0 I Discoloration or residue on surfaces examined shall be given particular attention to detect evidence of boric acid accumulations from borated reactor - coolant leakage. The visual examination shall be conducted during the system leakage tests conducted after refueling outages and prior to startup. VT-2 visual examination shall be conducted in accordance with ASME Section XI, IWA-5240. 11.1.3 Visual Examination VT-3 The VT-3 visual examination shall be conducted to determine the general mechanical and structural conditions of components and their supports such as the presence of loose parts, debris, or abnormal corrosion products, wear, erosion, corrosion, and the loss of integrity at bolted or welded connections. VT-3 may require, as applicable to determine structural integrity, the measurement of clearances, detection of physical displacement, structural adequacy of supporting elements, connections between load carrying structural

     .                   members, and tightness of bolting.

For component supports and component interiors, the visual examination may be performed remotely with or without optical aids to verify the structural integrity of the component. 11.1.4 Visual Examination VT-4 The VT-4 visual examination shall be conducted to [ determine conditions relating to the operability of components or devices such as mechanical and hydraulic snubbers, component supports, pumps, l valves, and spring loaded and constant weight

  . .                   hangers.

VT-4 shall confirm functional adequacy, verification of the settings, or freedom of motion. This examination may require (1) disassembly of components or devices and (2) operability test.

 .        11.2 Surface Examination 4

SQNP SI-114.2 Page 55 of 67 Rev. 0 11.2.1 Macnetic Pa'rticle Examination Magnetic particle examination (MT) shall be conducted in accordance with Article 7, Section V of the ASME Code. 11.2.2 liouid Penetrant Examination Liquid penetrant examination (PT) shall be conducted in accordance with Article 6, Section V of the ASME Code. 11.3 Volumetric Examination 11.3.1 Radiorrachic Examihation Radiographic techniques, employing penetrating radiation such as X-rays, gamma rays, or thermali-zed neutrons, may be utilized with appropriate image recording devices such as photographic film or papers, electrostatic systems, direct-image orthicons, or image converters. Fo'r radiographic examinations 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. 11.3.2 Ultrasonic Examination (a) Ultrasonic examination of Class I and Class 2 vessel welds in ferritic material greater than 2 inch (51 mm) in thickness shall be conducted in accordance with Article 4 of Section V of the ASMI Code. (b) Ultrasonic examination of Class I and Class 2 ferritic steel piping systems shall be

   .                                 conducted in accordance with Appendix III, amended as follows:

{, (1) r For examination of wel'ds, reflectors that ( l-produce a response greater than 50% of the reference level shall be recorded. (c) If the requirements of (a) and.(b) above are not applicable, the ultrasonic examination shall be conducted in accordance with the applicable requirements of Article 5 of

 '                                  Section V amended as follows:

1 e

SQNP 1 SI-114.2 Page 56 of 67 { i Rev. O (1) For examination on welds, reflectors that produce a response greater than 50% of the reference level shall be recorded. (2) For examination of welds, all reflectors which produce a response greater than 100% of the reference level shall be investigated to the extent that the operator can determine the shape, identity, and location of all such reflectors in terms of the acceptance-rejection standards of IWA-3100(b). (3) The size of reflectors shall be measured between points which give amplitudes equal to 100% of the reference level. 11.3.3 Eddy Current Examination 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. 12.0 QUALIFICATIONS OF NONDESTRUCTI1*E EXAMINATION PERSONNEL Personnel performing nondestructive examination operations shall

    ;           be cualified in accordance with IRA-2300 of ASME Section XI (DPM N75C01).
    . 13.0 ACCEPTANCE CRITERIA All acceptance standards for Class A, B, C, and D (ASME Classes 1, 2, and 3) components shall be in accordance with IWA-3000, IWB-3000, IWC-3000, or IWD-3000 of ASME Section XI, except where ASME Section III examinations are employed to satisfy ASME Section XI requirements.                                            -

14.0 REPAIRS i - All ASME Section XI components and their supports (ASME Classes l 1, 2, and 3) shall be repaired in accordance with the Repair and [* Replacement Program included in N-0QAM Part II, Section 2.3 and implemented by DPM SQ82MI. 15.0 Replacements - Replacements of ASME Section XI components (ASME Classes 1, 2, and 3) shall be in accordance with the Repair and Replacement Program in N-0QAM Part II, Section 2.3 and implemented by DPM SQB2MI. se l H.. 1 i .

SQNP SI-114.2 Pege 57 of 67 Rev.'O

ASME Section XI repairs.and replacements may be coordinated as necessary with the Chemical, Metallurgy and Standards Group of the Mechanical Branch. , 16.0 RECORDS AND REPORTS 16.1 Recordine of and Report of Examinations A detailed report of all examinations shall'be prepared by the performing or responsible organization and should contain but not be limited to the following information: Title Page Table of Contents I. Introduction - The introduction should include the following information: Plant, unit number, preservice or inservice inspection and cycle number, systems, components and vessels examinations were performed on, organization examinations were performed by, dates examinations were performed, ASME Section XI Code of Record.

     '                        II. Summary - The summary should include a brief description of the overall inspection: Program, performance, personnel, equipment, procedures, evaluations, and results.

III. Discussion - The discussion should discuss the governing documents (ASME Code, Technical Specifications, etc.), inspection schedule, materials, calibration standards, calibration performance, reporting, recording, interpretation,

   $.                               and brief evaluation.

L IV. Evaluation - Evaluation is based on the indication's location, metal path, general shape, and any tests

   -                               that could be applied, such as damping. The evaluation section also should contain a listing of i

each examination performed and the evaluated

  ;                                results.

L. V. Summary of Notifications - The summary of notifications shall give a short summary of each notification report along with the indication discrepancy and its location. It should also contain the final disposition and the date of completion. 4

                                                                                                                                 .n .-

SQNP SI-II4.2 Page 58 of 67 Rev. 0 VI. Scan Plan - The Scan Plan shall give a detailed description of all areas subject to examination during the inspection. It shall contain the following information: Examination Area, Code Category, Weld Siae and/or Number, Reference Drawing, Examination Method, Procedure, Calibration Block, and any reference details pertaining to the exam area, such as the weld number, meridional welds, pump studs, etc. VII. Weld Maps and Support Drawings - The Weld Maps and Support Drawings are the reference drawings for the inspection. The weld maps are isometric drawings showing the location of both field and shop welds on each vessel, component, and piping system subject to examination. The support drawings are also iso-metrics showing the location of hangers, snubbers and supports for each vessel, component, or piping system subject to examination. VIII. Log by System - The log is the daily status of the inspection section representative of the areas subject to examination during the inspection. This log keeps an up-to-date status of work complete and incomplete. IX. Personnel Certifications X. Equipment Certifications XI. NDE Procedures XII. Calibration Block Drawings t XIII. Calibration Sheets XIV. Examination Reports - Reports for inservice inspection shall be prepared in accordance with IWA-6220 of ASME Section XI. j For eddy current examination of heat exchanger tubing, the

  '       report shall include a record indicating the tube (s) exam-ined (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 evaluator (s) who conducted each examination or part thereof, and magnetic tape and strip charts.

b

SQNP SI-114.2 Pegn 59 of 67 Rev. O All procedures and' equipment shall be identified sufficiently to permit duplication of the examination at a later date. This shall include initial calibration data for the equipment and any significant changes. 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 will be submitted to TVA by the contractor with all pertinent and required information. TVA will retain the original copies of all raw data taken. The QEB NDE Section shall review and submit the final report to the Plant Superi,ntendent for review. These final reports shall be filed at the plant site with the data sheets of Appendix C of this program as discussed in Section 5.0 of this program. Data Sheet 1 in Appendix C will be completed and used as a cover sheet for the final report and to document the review process. 16.1.1 Repair and Replacement Reports The plant shall prepare a summary of repairs and replacements for all Class A and B components. The report shall include the applicable requirements of IWA-6220 of ASME Section XI and shall be submitted to the Chemical, Metallurgy and Standards Group i within 45 days after each refueling outage. The report shall include repairs conducted during each

   '                  refueling outage and all repairs conducted since the end of the preceding refueling. outage. The' Chemical, Metallurgy and Standards Group shall review the report to assure it contains applicable information required in IWA-6220 of ASME Section XI.

6 Af ter reviewing the summary report, the Chemical, Metallurgy and Standards Group shall forward it. to the Quality Engineering Branch for submittal to the NRC as part of the inservice inspection report described in N-OQAM, Part II, Section 5.1 and 16.2 of this program, within 90 days from the end of each refueling outage. 16.2 ISI Report for Class A and B Components The QEB NDE Section shall prepare an ISI Summary Report for Class A and B components to be submitted within 90 days after the completion of the inservice inspection with the Nuclear Regulatory Commission Region II Office in

 .-          accordance with IWA-6220, ASME.Section XI.

4 SQNP SI-114.2 Page 60 of 67 Rev. O The ISI Report should have a cover sheet providing the following 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 and number assigned to the nuclear power unit by TVA. (5) Co=mercial operation date for unit. All reports shall have a summary providing the following information: (1) National Board Number assigned by the manufacturer to the boiler, pressure vessel, or component. (2) Names of the co=ponents or parts of the components for which this is a record, including such information regarding size, capacity, material, location, and drawings as may aid accurate identification. L (3) Name of the manufacturer of the components or parts for which this is a record, including the manuf acturer's component or 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.

(4) Date of completion of the inservice inspection. . (5) Name or names of the Inspector (s) when required. (6) "Name and mailing address'of the employer (s) cf the Inspector (s). L (7) Abstract of examination performed, conditions observed, corrective measures recommended and taken. (8) Signature of Inspector, when required. All ISI Reports shall have an owner's data report for

    -    inservice inspection, Form NIS-1 as shown in Appendix II of ASME Section XI.

4 I

,I

-L i _ . -, - -~ ~~ ' '

SQNP SI-114.2 Page 61 of 67

                                  ,               Rev. 0..       ,

16.3 Records for Class A. B. C, and D Components The following records shall be available for review: (1) Examinatien Plans (2) Examination Results and Reports (3) Examination Methods and Procedures (4) Evaluation of Results (5) Corrective Actions and Repairs 16.4 Records of System Pressure Tests Records of the visual examinations conducted during system leakage or hydrostatic tests shall consist of an itemization of the number and location of leaks found in a system and the corrective actions taken. 16.5 Auemented Examination Reports Augmented examination special reports shall be submitted to the Nuclear Regulatory Commission Region II Office within the time period specified for each report. For specific details on records, reports and reporting see section 20.0, Augmented Inspections, of this program. 17.0 NOTIFICATION OF INDICATION Plant management shall be formally notified of the presence of unacceptable indications detected during the performance of nondestructive examinations. Unacceptable indications are i defined by the applicable NDE procedure. Formal notification

    "         shall consist of completing and submitting to the Plant Superintendent D  of this program. the " Notification of Indication" form in Appendix Part I of ths " Notification of Indicat' ion" shall be completed and signed by the NDE Level II or III examiner detecting the
                                                                   ~

indication. The NDE Section representative of the Quality Engi-l neering Branch shall review and sign the form. If the indication is detected by an outside contractor, the c'ontractor's field supervisor shall review and sign the form. Part II of the form shall be completed for evaluation of findings by a TVA NDE Level III individual. This individual shall indicate under " Disposition" his recommended disposition of the i indication. He shall reference examination procedures to be used l if reexamination is a requirement. He shall then sign'and date - l.. the form. Copies of the. form shall be distributed to the Plant l 1, i .. . --

SQNP

                                                          'SI-134.2 Page 62 of 67 Rev. O Superintendent, the NDE S'ection Representative, the ISI Programs Procedures Section, and, if appropriate, the Plant Field Services Director. One copy shall be filed with the examination report.

Upon receipt of the Notification of Indication form, the Plant Superintendent shall be responsible for de;ermining the organization to implement the. disposition. The Plant Superintendent or his representative, shall be responsible for preparing instructions to repair the indication in accordance with N-0QAM, Part II, section 2'.3, and the recommended disposition on the form. Dispositions other than restoring to 1 original requirements shall be processed as modifications in accordance with N-0QAM, Part II, section 3.0. The plant shall coordinate with the Quality Engineering Branch to conduct reexamination when reexamination is a requirement. Additionally, coordination with the AIA representative shall be made, when appropriate, as follows: i l

a. Make available to the ANII any records he needs to accomplish his duties.

b. Give adequate notice to the AIA that an ANII and/or ANI will be required for repair work. Detailed requirements for interfacing with th'e AIA for repairs to code items are contained in N-0QAM, Part II, section 2.3.

        .                  Upon completion of the action required to repair the indication, the NDE Section representative of the Quality Engineering Branch shall review the repair instructions to assure completion, and shall sign and date the Notification of Indication Form, Part II.
                                                                         ~

The review shall include referencing the repair instructions on 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 refer'enced on the completed form by the Inspection Section representative. Additional distribution of the form shall be performed as noted for Part II of the form. 18.0 CALIBRATION BLOCKS ~ Calibration blocks will be used for ultrasonic examinations (a calibration tube will be used for eddy current examination of steam generator tubing). The blocks will be fabricated to the general requirements of ASME Section V and ASME Section XI. The blocks shall be fabricated of the material to be examined or equivalent P numbers. Mill test reports shall be obtained and retained by the Quality Engineering Branch for all calibration blocks. The blocks shall employ drilled holes and/or notches for - l calibration reflectors (See Request for Relief ISI-2).

I 1 \

             .-                                               SQNF SI-114.2 Page 63 of 67 Rev. O The   NDE Section shall maintain as-built calibration block drawings.
           .                              Copies of the original drawings and any revisions shall be submitted to t,he ISI Programs Section. The calibration blocks shall be stored at the plant site and maintained.by the plant QA organization.

19.0 REQUESTS FOR RELIEF Where TVA has determined that certain code requirements or examinations are impractical, TVA will submit written requests for relief to NRC with information to support the determinations and any proposed alternate examinations. The impractical code requirements or examinations shall be identified in this program, and references to particular requests for relief shall be included. When impractical examination requirements are identified in the field, the NDE Section shall notify the ISI Programs Section such that the information may be included in this program and requests for relief may be prepared if necessary. The Requests for Relief are listed in Appendix E. The current Requests for Relief are ISI-I through ISI-11. Those requiring alternate and ISI-11.inspection are ISI-1, ISI-3, ISI-5, ISI-8, ISI-9, ISI-10 20.0 AUGMENTED INSPECTIONS Augmented inspections are performed in addition to ASME Section XI code requirements. The augmented inspections may be required by the NRC or self-imposed by TVA. Augmented examinations of components that require reporting (verbal r or written) to the NRC shall be the responsibility of the organiza-i tion designated in the particular examination. These reports shall be submitted to the Nuclear Regulatory Commission Region II Office within the time period specified for each report. Each augmented i exam shall state the required reporting time and the document requiring the information to be included in the report.

                        '0.1      Feedwater Svstem Piping and Supports i

! In order to satisfy the requirements of NRC-IE Bulletin 79-13, the following augmented examinations shall be performed. The augmented examination of the feedwater nozzle-to-pipe welds (includes nozzle-to-transitibn piece welds and i' transition piece-to-pipe welds) and of adjacent pipe and l nozzle areas are included in DPM No. SEQ 80M7. The requirements are a radiographic examination supplemented by ultrasonic examination on completion of the hot functional l

SQNP SI-114.2 Page 64 of 67 Rev. O testing and before fuel loading. During the first refueling outage, perform a volumetric examination of'the feedwater nozzle-to pipe velds, the feedwater piping welds to the first support, the feedwater line-to-cortainment - penetration welds and an area of at least one pipe diameter of the main feedwater line downstream at the auxiliary feedwater to main feedwater connecti n. Also perform a visual inspection of all feedwater sy nem piping supports and snubbers in containment to verify operability and conformance to design.

In the event cracking is identified during examination of the nozzle-to pipe welds, all feedwater lines up to the first piping support or snubber outboard of the nozzle shall be volumetrically examined as-stated in the first paragraph. All unacceptable code discontinuities shall be subject to repair unless justification for continued operation is provided.

Any cracking or other unacceptable code discontinuities identified shall be reported to the Director of the NRC Regional Office within 24 hours of identification. Plant management shall report this information to the Nuclear Regulatory Commission Region II Office per Plant Instruc-tion AI-18. A written report of the results of examination shall be submitted by the QEB NDE Section within 30 days of completion of the examination. See DPM SEQSOM7 for informa-tion to be included in this special report. 20.2 RPV Nozzle Safe Ends The augmented examination requirements of the RPV nozzle-to-safe end welds are included in the final report - Sequoyah Nuclear Plant - Evaluation of cracking in reactor vessel nozzle stainless steel buttering. TVA will reinspect nozzle 2RC-17SE and one additional unit 2 nozzle (2RC-24SE) at the first regularly scheduled cold shutdosn outage. Future examinations for unit 2 will be monitored at the normal inservice inspection intervals for dissimilar metal welds as required by Section XI of the ASME Code. This augmented examination does not require a special report.

 ,              The examination data sheets shall be included in the 90 day ISI report discussed in section 16.2 of this program.

20.3 Reactor Coolant Pump Flvwheel The augmented examination _ requirements of the reac' tor coolant pump flywheel are included in Regulatory Position C.4.b of Regulatory Guide 1.14; (1) an inplace ultrasonic examination of the areas of higher stress concentration at the bore and keyway at approximately three year intervals

SQNP ST-114.2 Page 65 of 67 Rev. 0 during the refueling or maintenance shutdown coinciding with the inservice inspection schedule as required by Section XI of the ASME Code, and.(2) a surface examination of all exposed surf. aces and complete ultrasonic examination - at approximately 10 year intervals during the plant shutdown coinciding with the inservice inspection schedule as required by Section XI of the ASMI Jode. This augmented examination does not require a special report unless the examination reveals a flaw. If the examination and evaluation indicate an increase in flaw size or growth rate greater than predicted for the service life of the flywheel, the results of the examination and evaluation should be submitted to the KRC for evaluation. Refer to Regulatory Guide 1.14 for information to be included. The examination data sheets shall be included in the 90 day ISI report discussed in section 16.2 of this program. 20.4 Steam Generator Tubing The augmented examination requirements of the steam generator tubing are included in Technical Specifications 4.0.5, 4.4.5.0 and section 7.3.8 of this program. Following each inservice inspection of steam generatar tubes, the number of tubes plugged in each steam generator shall be reported to the NRC within 15 days. Plant management shall report this information to the Nuclear Regulatory specified. Commission Region II Office within the time period instructions.See plant instruction AI-18 for reporting The complete results of the steam generator tube inservice inspection shall be submitted to the Nuclear Regulatory Commission in a special report pursuant to Technical Specifica-4, tion 6.9.2 within 12 months following completion of the inspection. The Chemical, Metallurgy, and Standards Group Staff Specialist shall prepare this special report and submit the report of the Nuclear Regulatory Commission Region II

   -             Office within the stated time period.                     This special report shall include:
  ;                      1.

Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged.

-               Results of steam generator tube inspections which fall into Technical Specification Category C-3 require prompt notifica-tion of the Nuclear Regulatory Commission pursua t to' Technic'al Specification 6.9.1 prior to resumption of plant operation.

.. - - - ---e. . . - , g - - - - , - ,, , .,----c - -- -

SQNP SI-114.2 Page 66 of 67 Rev. O The written followup ,of this report shall provide a de.scription of investigations conducted to determine cause of the tube

           .                     degradation and corrective measures to prevent recurrence.

Refer to Technical ~ Specifications 4.0.5 and 4.4.5.0 and section 7.3.8 of this program for information to be included. . 20.5 RPV Nozzle Cladding All vessel nozzles cladding shall be ultrasonically examined at the end of each 10-year inspection interval, using techniques at least as sensitive as those used to conduct the supplemental examinations performed prior to fuel loading. The results of this examination shall be - reported to NRC. This examination is done in accordance with Sequoyah technical specifications and satisfies Surveillance Requirement 4.4.10. This augmented examination does not require a special report. The examination data sheets shall be included in the 90 day ISI report discussed in secticn 16.2 of this program. Nozzle forging material and cladding is identified in section 7.1.2 of this program.

21.0 REFERENCES

21.1 ASMI Boiler and Pressure Vessel Code - Section XI, 1974 Edition, Summer 1975 addenda, Summer 1976 addenda.; 1977 Edition, Summer 1978 addenda. 21.2 ASMI Boiler and Pressure Vessel Code - Section V. 21.3 Instruction Manual - 173-inch I.D. Reactor Pressure Vessel -Rotterdam Dockyard Company, Contract No. i, 68C60-91934, N2M-2-3. 21.4 Sequoyah Nuclear Plant Standard Practice SQA41. 21.5 Sequoyah Nuclear Plant Final Safety Analysis Report. ( 21.6 Westinghouse Technical Manual - Pressurizer, TM 1440-C225, Contract No. 68C60-91934, N2M-2-6. 21.7 i Westinghouse Technical Manual - Vertical Steam Generators, TM 1440-C224, Contract No. 68C31-91934, N2M-2-4. , 21.8 Westinghouse Instruction anual , Auxiliary Heat

m. Exchangers, Contract No. 68C60-91934, N2M-2-25.

21.9

  '                          Westinghouse Instruction Book - Reactor Coolant Pump,-

Contract No. 68C60-91934, N2M-2-5.

 ._                                                                                         s

_--,e ,- - - - - , .,

( ' SQNP 1 SI-114.2 Page 67 of 67 Rev. 0.. 21.10 Ingersoll-Rand Instruction Manual - Residual Heat Removal > Pumps, Contract No. 68C60-91934, N2M-2-30. > 21.11 Sequoyah Nuclear Plant Operational Quality Assurance ' Manual, Part II, Sections 2.3, 3.0, 5.1, and 6.3. 21.12 Sequoyah Nuclear Plant Technical Instruction TI-51. 1 21.13 Sequoyah Nuclear Plant Technical Specifications Unit 2. 4 21.14 Division Procedures Manual: N75C01, N76A10, N80E3, 4 SEQ 80M7, SEQS2El, and SQ82M1. I s s 1 tj { !. 9 . 2 4 1 1' J

   %    .4 t                                                                                                                                               -

e

  +
         . . . . _ _ _ . - - , . . . . . . _ . . . , . . , . . , . . . . . .            . _ , _ ..,,,_,...,_,.,_,_,.._-m_,_..._.2,__.,__.                               _ . . . _ . . . . . . . _ _ _ _ , ,

t , , ; r- .- .. 1 , SQNP page 1 of 1 SI- 14.2 Page 1 of I Rev. O APPENDIX A TABI.E 1 Minimum Number of Steam Generators To De Inspected During Inservice Inspection Only No. of Steam Generators per Unit First Inservice Inspection Four Two Second and Subsequent Inservice' Inspections Onc3 Table Notation: 1. Each the second of theand other thirdtwo steam generators not inspected during the first inservice inspedion inspections. The fourth and subsequent inspections shall follow the . shall be inspected durir g g instructions elescribed below: 1 - The inservice inspection may be limited to one steam generator on a rotating schedule e if the results of the first or previous inspections indicate that all steam generat ors are ncompassing 12% of the tubes manner. Note that under some circumstances, the operating conditions performing in a like to be more severe than those in other steam generators. in one or more s;eam generators may be found modified to inspect the most severe conditions. Under such circumstances the yample sequence shall be 4 3 I I e I o t

-j_

I [

                         .        . -           .~

SQNP Page 1 of I SI-ll4.2 Al'I'ENDIX A Page I of 1 TAlli.E 2 Rev. O Steam Generator Tube Inspection First Sample Inspection Sample Size Result Second Sample Inspection Third Sample Inspection Action Required Result Action Required Result Action Required A minimum of S C-1 None tubes per S.G. N/A N/A N/A N/A C-2 Plug defective C-1 None N/A

tubes and inspect N/A Plug defective tubes C-1 additional 2S None C-2 and inspect additional C-2 Plug defective tubes in this S.G. 4S tubes in this S.G. tubes this S.G. C-3 Perform action Perform action for 'for C-3 result C-3 C-3 result of first df first sample C-3 Inspect all tubes N/A N/A All other this S.G., plug S.G.s are None defective tubes C-1 F/A N/A and inspect 2S .Some S.G.s tubes in.each C-2 but no Perform action for N/A other S.G. additional N/A C-2 result of S.G. are 'second sample Prompt notification C-3 i to NRC pursuant to Additional Inspect all tubes specification 6.9.1. S.C. is C-3, in each S.G. and N/A N/A plug defective tubes. Prompt notification to NRC pursuant to 1 specification 6.9.1. S=5 n Where'n is the number of steam generators inspected during an inspection.

7 , _. . p_.- .. m , SQtIP Page 1 of 16 Page 1 of 16 S1-114.2 Rev. O API'ENDIX A TABI,E A SEQUOYAll INSERVICE INSPECTION PROGRAff CI. ASS A CollPONENTS Program Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Length Component Section Method No. Length Inspection Periods Reference : Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. A. Reactor Vessel

1. Circumferential

Shell Welds 7.1.1.1 LT B-A 4/50 ft. 4/50 ft. 0 0 4 CIIII-2343-B

2. Closure llead Cire Weld 7.1.1.3 UT B-A 41 ft. 41 ft. 13 ft. 14 ft. 14 ft. Cliti-2358-A

3. Lowe'r llead l j Circ WeId 7.1.1.4 UT B-A 38 ft. 38 ft. 0 0 38 'It. Cllti-2343-B -

4. Lower IIcad Heridional Welds 7.1.1.6 UT B-A 6 6 0 0 6 Clit!-2343-B

5. Shell-to-Flange Weld 7.1.1.7 UT B-A 50 ft. 50 ft. O it. O ft. 50 ft. Clitl-2343-B

6. Closure Head-to-Flange Weld 7.1.1.8 UT B-A '

45 ft. 45 ft. 15 ft. 15 ft. 15 ft. Clit!-2358-A

7. Nozzle-to Vessel Welds 7.1.2 UT B-D 8 8 4 0 4 Clit!-2343-D Cilti-2333-B Cllti-2360-A

8. Inside Radius

Sections 7.1.3 UT B-D 8 8 4 0 4 Cliff-2361 - A ISI-0008-B

SQNe' gg Page 2 of 16 APPENDIX A Page 2 of 16 TAlli.E A Rev. O SEQUOYAll INSERVICE INSPECTION Pit 0GitAtl Cl. ASS A C0tlPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length Component Section ?!cthod No. Length Inspection Periods Category Welds /of Weld Reference i Welds /of Weld. 3 yrs. 7 yrs. 10 yrs. Dwg. No. A. Reactor Vessel (Continued)

9. Vessel Pene-trations and Attachments 7.1.4 VT-2 B-E Cilti-2051 -ra 141 37 12 12 13 HSG-0004-?

10. Nozzle-to-Safe End Welds 7.1.5 UT,PT B-F Cllti-2333- t 8 8 4 0 4- ISI-0008-II. Closure Studs and Nuts 7.1.6 UT,tlT B-G-1 54 54

    'J                                                                                                           18          18         18

12. Cliff-2341 -((

Ligaments Between Threaded Stud lloles 7.1.6 UT B-G-1 54 54 18 18 18 Cliff-2341-B

13. Closure Washers 7.1.6 VT-1 B-G-1 54 54 18 18 18 Cliti-2341-B

14. Vessel Interior 7.1.9 VT-3 B-N-1 1 1 1 1 1

15. Removal Core' Support i

Structure 7.1.10 VT-3 B-N-3 See Program Section 7.1.10

16. Control Rod

 !                   Drive llousings- 7.1.11       UT        B-0         20                                                                                      Clitl-2651-C 2                  0          1         ,1                          Cllti-2359-A i,

                                                                                       ^         '
                                                                               - p                                i       ,

SI-Il4.2 Page 3 of 16 Page 3 of 16 Rev. 0 APPENI)1X A TAlli.E A SEQl10YAll INSERVICE INSPECTION PROGRAtl CLASS A COtiPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length Component Section No. Length Inspection Periods Reference IIcthod Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. A. Reactor Vessel (Continued)

17. Auxiliary IIcad 7.1.12 NT, PT B-F 4 4 1 1 2 Cllli-2337-C Cllti-2651-C ISI-0001-C ISI-0014-A B. Pressurizer

1. Circumferential

Shell-to-liead j WeIds 7.2.1 UT B-B 2/24 fL. 2/24 ft. 12 It. 12 fL. 24 fL. Cliti-2363- A

2. Longitudinal Shell-to-llcad Welds 7.2.2 UT B-B- 2/1 ft. 2/1 ft. 1* 1* 1* Clit!-2363-A

3. Nozzle-to-Vessel and Inside Radius Section 7.2.4 IIT B-D '6 6 2 2 2 CIIM-2363-A

4. IIcater Penetrations 7.2.5 VT-2 B-E 78 20 6 7 7 MSG-0006-A 4 *

   ,The       longitudinal weld selected for examination is that weld intersecting the circumferential shell-to-head weld examined.

7~ , __

7 ._ . . . . . . S4NP Page 4 of 16 SI-Il4.2 APPENDIX A Page 4 of 16 TAHl.E A Rev. O SEQUOYAll INSERVICE INSPECTION PROGRAtt CI. ASS A CollPONENTS Program Section XI 40 Yr. Sample 1st insp. Interval ' Reference Exam Exam No. I.ength Component Section No. I.cngth Inspection Periosis Reference tiethod Category Welds /of Weld Welds /or Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. B. Pressut izer (Continued)

5. Nozzle-to-Safe End Welds 7.2.6 UT, PT B-F 6 6 2 2 2 Clit!-2363-A

6. Pressure Retain-ing Bolting 7.2.8 VT-1 B-G-2 I mvy/16 bolts 16 bolts 16 0 0

7. Integrally Welded Vessel Supports 7.2.9 HT B-li 23 ft. 23 ft. 7 ft. 8 ft. 8 ft. Clift-2362-A J C. Steam Generators 1.. Primary ifcad- ; '

to-Tube Sheet ' Weld 7.3.2 UT B-B 4/36 ft. 4/36 ft. I I 2 CIlli-2345-C

2. Primary Nozzle-to-Vessel and

, Inside Radius \ Section 7.3.3 See Program Section 7.3.3 (Request for Relief Isl-6) 3 .- Primary Nozzle- 9 to-Safe End Welds 7.'3.4 UT, PT B-F 8 8 2 3'

3 CllN-2333-B Cllti-2345-B f ISI-0008-B i

                                                                                                                                                               \                                                                                                              $

                                                              -- -- ~ - 7        _E       j      ,_    ,'   L_.   .   .   .
                                                                                                                                                                          ?        t        -

1 SQNP Page 5 of 16 SI-114.2

                                                      ,                           i APPENIIIX A    Page 5 of 16 TAlli.E A    Rev. O
                         +

SEQUOYAII INSERVICE INSPECTION PROGRAff CI. ASS A CollPONENTS Program Re fe rence Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. I.cng t h

                                                                   ' Component          Section                                                       No. l.cng t li        Inspection Periods
                                                                                                     !!c thod       Category    Welds /of Weld                                                              Reference Welds /of Weld        3 yrs.      7 yrs.      10 yrs. Dvg. No.

C. Steam Generators i

4. Pressure i

Retaining Bolting 7.3.6 VT-1 B-G-2 4 gens./2 mwy

   = .\                    ,                                                                                                                       8 muy                2          2            4          flSG-0002-0

5. Tubing 7.3.8 ET

. O B-Q 4 gens./3% 4 gens./3% 2 1 1 76til D. Pressure' Retaining Bolting ',

1. Reactor y Coolant System 7.4.3.1 VT-1 B-G-2

                                        -k                                                                                     8 Sets /8 Bolts    8 Sets               2         3             3          ISI-0013-C

2. Chemical and Volume Control System (SWI) 7.4.3.2 VT-I B-G-2 4 Sets /4 Bolts 4 Sets 1 I 2 ISI-0009-C

3. Residual IIcat Removal System. 7.4.3.3 VT-1 B-G-2 N/A See Program Section 7.4.1.1

4. Safety Injection System 7.4.3.4 VT-1 B-G-2 4 Sets /4 Bolts 4 Sets 2 1 1 ISI-0002-C

5. Upper IIcad Injection

System 7.4.3.5 VT-1 B-G-2 '12 Sets /2 Bolts 12 Sets 4 4 4 ISI-0001-C

                .-~~
                          ;;          7   .

r - . . i , j , ; SQNP Pzge 6 of 16 S1-114.2 APPENDIX A Page 6 of 16 TAlli.E A Rev. 0 SEQUOYAH INSESVICE INSPECTION PROGRAM CLASS A C0flPONENTS Program Section XI 40 Yr. Sample 1st insp. Interval - Reference Exam Exa.a No. I,engtli No. I.engtli Component Section Inspection Periods Reference Method Category Welds /of Weld l

      ,                                                                                                                                                                  Welds /or Weld      3 yrs. 7 yrs. 10 yrs.         Dwg. No.   '
    ,         E. Piping s

1. Circumferential Welds A. Reactor Coolant l_ , , System .

l l Hain Loops

I Cires >4" 7.4.4.1 UT/PT B-J 63 16
i 5 5 6 ISI-0008-B l B. Reactor !

y Coolant l q System - Cires >4" Nom. Size 7.4.4.2' UT/PT B-J 62 15 5 5 !' Cires <4" 5 ISI-0013-C Nom. Size

                                               ,7.4.4.2               PT                           B-J                            122                                  30                   10       10 10           ISI-0013-C C. Chemical         ,

l and Volume . Control - l System Cires >4" Nom. Size 7.4.4.3 N/A

                              'Cires <4"                                                                                                                                                                                    ISI-0009-C Nom. Size        7.4.4.3 PT                              ' B-J                           57-                                   14                   4        5         5           'ISI-0009-C 9

r-- p-- p -- ;-- p- - [ SI-114.2 E I APPENDIX A Page 7 of 16 TAlli.E A Rev. O SEQUOYAll INSERVICE INSPECTION PROGRAM CLASS A COtiPONENTS Program Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. I.engtli Component Section No. Length Inspection Periods Reference Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No.

 ,    ,E. Piping (Continued)                                                                                                                                                      l

1. Circumferential Welds D. Residual

Ilea t Removal System Circs ,

                      >4" Nom.

5ize 7.4.4.4 UT/PT B-J 45 11 3 4 4 ISI-0003-C

   )3         E. Safety Injection System                                                                                                    '

Circs >4" - Nom. Size 7.4'.4.5 UT/PT B-J 92 Cires <4" '23 8 7 8 ISI-0002-C Nom. Size 7.4.4.5 PT B-J

                                                                          ,39                      9                 3         3 3                       ISI-0002-C F.

Upper - llead

                  ' Injection System Cires >4"        7.4.4.6       UT/PT     B-J            123                     31               11'
                                                          ,                                                                                  10                      ISI-0001-C 9

m . 9 i + - Sqyp Page 8 of I6 SI-l14.2 APPENDIX A Page 8 of 16 TAltl.E A Rev. O SEQUOYAll INSERVICE INSPECTION PROGRAN Cl. ASS A C0flPONENTS Program Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Length Component Section No. Length Inspection Periods Reference tiethod Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. E. Piping (Continued) -

2. Branch Pipe '

Connection Welds A. Reactor Coolant System - Plain Loops Welds >2" Nom. Size 7.4.5.1 UT/PT B-J 1 d Welds $2" 1 . 1 0 0 ISI-0008-B Nom. Size 7.4.5.1 PT B-J 13 4 2 1 1 ISI-0008-B B. Reactor Coolant System Welds * , >2" Nom. Size 7.4.5.2 UT/PT B-J 7 2 0 Welds <2" 1 ISI-0013-C 1 Nom. Size 7.4.5.2 PT B-J 7 2 0 1 1 ISI-0013-C e I ___m.__._____________-,__m -_

 ~ - - ~

g_.. ~. ,. . 3

                                                                                                   .,quP SI-114.2                                                      Pege 9 of 16 Page 9 of 16      Rev. 0 APPENDIX A TABLE A SEQUOYAll INSERVICE INSPECTION PROGRAtt CLASS A CollPollENTS                              -

Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Component Section Method Inspection Periods Reference Category Welds /of Weld Welds /of Weld 3 yrs. i yrs. 10 yrs. Dwg. No. E. Piping (Continued) C. Chemical and Volume Control System Welds

                               >2" Nom.

Size 7.4.5.3 UT/PT B-J 4 1 Welds <2" 1 0 0 ISI-0009-C'

Nom. Size 7.4.5.3 N/A - -

                                                                                                                                                                        " ISI-0009-C D. Residual liea t                                                                                             ,

N8 Removal

          'l System                           -

Welds >2" ' Nom. Size 7.4.5.4 UT/PT B-J 3 1 0 Welds <2" 1 0 ISI-0003-C Nom. Size 7.4.5.4 PT B-J 2. I 1 d 0 ISI-0003-C E. S5fety Injection - System Welds >2"

         .                  ' Nom. Size     7.4.5.5           UT/PT      B-J                6                   2
                                              '                                                                                    0           1                               ISI-0002-C Welds <2"                                                        '

1 Nom. Size 7.4.5.5 PT t B-J . 10 3 1 1 , 1 ISI-0002-C e

SQt.. . S1-114.2 Pag 10 f 16 APPENDIX A Page 10 of 16 TABLE A Rev. O SEQUOYAll INSERVICE INSPECTION PROGRAff ' CLASS A C0tiPONENTS ,, .

Program , Reference Exam Section XI 40 Yr. Sample 1st Insp. Interval Component Exam No. Length Section liethod No. I.eng tle Inspection Periods Category Welds /of Weld Referende Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. E. Piping (Continued) F. Upper IIcad Injection System Welds >2" l ' Nom. Size 7.4.5.6 N/A - Welds <2 - - - ISI-0001-C Nom. Size 7.4.5.6 PT B-J 2 1

                                                                       ,                                                                                                1                                    0          0              ISI'-0001-C

3. Socket Welds A. Reactor yI' t

                                                    . Coolant System        7.4.6.1      PT         B-J 239                                       60 1                                                                                             20                                       20         20            ISI-0013-C B. Chemical                                                                                                                                                                            ,p and Volume Control System       7.4.6.2      PT         B-J          224 56                   19                                       18         19           ISI-0009-C C. Residual                                                                                                                                                                     ,

, lleat Removal System 7.4.6.3 PT B-J 18 5 1 2 2 ISI-0003-C , D. Safety ' Injection System 7.4.6.4- PT B-J 176 44 15 14 15 ISI-0002-C t

                                                                  - -ggg 7                                                                                              '

l SI-il .. Pare 11 of 16 Pare 11 of 16 AI'l'ENDIX A Rev. O TABI.E A SEQUOYAll INSERVICE 1NSPECTION PROGRAi! CLASS A C0flPONENTS i Program Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Length Component Section No. Length Inspection Periods Reference tiethod Category Welds /of Weld Welels/of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. E. Piping (Continued) E. Upper llead Injection System 7.4.6.5 PT B-J 16 4 1 1 2 ISI-0001-C

         ~4. Piping and Valve
             . In tegrally-

Welded Support ,

Flembe rs i A. no Reactor 9 Coolant System 7.4.7.1 PT B-K-1 9 9 3 3 3 flSG-0013-C B. Chemical and Volume Control System

7.4.7.2 PT B-K-1 1 1 0 0 1 flSG-0012-C tlSG-0015-C C. Residual IIca t -

Removal System 7.4.7.3 PT B-K-1 2 2 0 1 1 PfSG-0010-C 9

                                           ... .             ~.                        -
                                                                                       .g                                            -

31_ : , , _ , Page 12 of 16 4 P:d'i'hENDIX A12 ofRev. 16 0 TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAtt CLASS A C0flPONENTS Program Section XI 40 Yr. Sample 1st insp. Interval Reference Exam Exam No. Length Component Section Method No. I.cngth Inspection Periods Reference Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. E. Piping (Continued) D. Sa fety Injection System 7.4.7.4 PT B-K-1 8 8 3 2 3 flSG-0009-C E. Upper llead Injection 7.4.7.5 PT B-K-1 1 1 0 0 I ?!SG-0014-C

5. Piping and ,

Valve Component Supports i A. Reactor Coolant System 7.4.8.1 VT-3, B-K-2 139 139 VT-4 '47 46 46 ?!SG-0013-C B. Chemical . and Volume-Control System 7.4.8.2 VT-3, B-K-2 114 114 VT-4 38 38 38 HSG-0012-C

                                   .                                                                                                                        HSG-0015-C C. Residual                                                                        .

ifeat i Removal . System 7.4.8.3 VT-3, B-K-2 17 17 6 5 6 VT-4 ilSG-0010-C 9

                                                                            -           ^

(. . . . . . , SQNP % Page 13 of 16 S1-114.2 APPENillX A Page 13 of 16 TAlli.E A Rev. O SEQUOYAll INSERVICE INSPECTION l'ROGRAi! CLASS A Cotil'ONENTS Program Reference Section XI 40 Yr. Sample 1st insp. Interval Exam Exam No. Length Component Section No. Length Inspection Periods Reference ' Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. E. Piping (Continued) D. Sa fety Injection ' System 7.4.8.4 VT-3, B-K-2 103 103 35 VT-4 34 34 flSG-0009-C E. Upper Head Injection ' System 7.4.8.5 VT-3, B-K-2 88 88 30 29 VT-4 29 flSG-0014-C

 $3 F. Reactor Coolant Pumps

1. Pressure '

Retaining

Bolting '7.5.1 UT B-G-1 96 96 24 b .- 48 C1111-2675-i

2. Pressure-Retaining Bolting 7.5.1 UT,PT, B-G-1 96 96 24 24 48 or NT CIIM-2675- 1 3 .' Pressure-Retaining Bolting 7.5.2 VT-1 B-G-1 4RCP/3 Sets

144 36 36 72 CHH-2675-B t

  *S o Program Reference Section for explanation of inspection sample.
                                                                                                -13

e JQUI St-il.. Page 14 of 16 Page 14 of 16 Rev. O APPEllillX A TABI.E A SEQUOYAll INSERVICE INSPECTION PROGRAff , CLASS A COtlPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length Component Section Method No. Length Inspection Periods Reference Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No.

F. Reactor Coolant Pumts (Continued)

4. Integrally-Welded Supports 7.5.3 ST B-K-1 3 pumps /3 feet 9 feet 3 3 3 IISG-003-3 per pump *

5. Component Supports 7.5.4 VT-3, B-K-2 4 pumps /3 feet 12. feet 3 VT-4 3 6 ' tisG-0003-D per pump

en 6. Casing Welds' 7.5.5 B-L-1 tv PT , 4 1 0 J 1- IISG-0003-B

7. Casing 7.5.6 VT-1 B-L-2 4 See Program Section 7.5.6 tlSG-0003-B

8. Flywheel 7.5.7 UT

                                 ,                                 N/A          4                   See Program Section 7.5.7                         N/A G. Valves

1. Pressure Retaining Bolting 7.6.2 ST B-G-2 See Program Section 7.6.2 A. Reactor -

Coolant System 7.6.2.1 VT-1 B-G-2 14 14 4 5 5 ISI-0013-C B. Chemical a.nd Volume Control -

       .               System        7.6'.2.2          VT-1       B-G-2       6                    6                  2         2         2          ISI-0009-C
     *Src Program Reference Section for e'xplanation of inspection sample                                                                           tlSG-0008-C

7 .__ 7. _ _. ~ . . . --- SQNP page 15 of 16 SI-114.2 APPENDIX A Page 15 of 16 4, TABl.E A Rev. 0 SEQUOYAll INSERVICE INSPECTION pH0GRAN Cl. ASS A CollPONENTS Program Reference Section XI 40 Yr. Sample 1st Insp. Tr'.crval. Exam Exam No. Length Component Section No. Length Inspection Periods Reference Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. G. Valves (Continued) C. Residual Ileat Removal System 7.6.2.3 VT-1 B-G-2 2 2 0 1 1 ISI-0003-C D. Safety . Injection ' System 7.6.2.4 VT-1 B-G-2 23 23 7

8 8 ISI-0002-C ao' E. Upper Head

Injection System 7.6.2.5 VT-1 B-G-2 8 8 3 2 3- ISI-0001-C

2. Integrally-Welded Support tiembers 7.6.3 UT/PT B-K-1 See Program Section 7.4.7

3. Component ,'

Supports 7.6.4 VT-3, B-K-2 See Program Section 7.4.8 VT-4

4. Valve Bodies 7.6.6 VT-4 B-H-2 See Table D of Appendix A

                                 >4" N.P.S.

t SQNP Page 16 of 16 l' age 16 of 16 SI-ll4.2 Rev. O Al'I'Et11)IX A TAllLE A SEQUOYAll INSERVICE INSPECTION PROGRAtl CLASS A C0t!PONENTS Program Re ference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Lengtli Component Section No. Length Inspection Periods Reference

                                                        ?!c tliod   Categor'y   Welds /of Weld       Welds /of Weld 3 yrs. 7 yrs.                    10 yrs. Dwg. No.

H. Exempted Co_mponents 7.7 VT-2 B-P See Program Section 7.7

1. Reactor Vessel - Pressure Retaining Boundary

2. Pressurizer - Pressure Retaining Boundary

3. Steam Generators - Pressure Retaining Boundary

4. Ileat Exchangers - Pressure Retaining Boundary

5. Piping - Pressure Retaining Boundary N

D 6. Pumps - Pressure Retaining Boundary

7. Valves - Pressure Retaining Boundary.

s O l l .

r -- , . .

                                                                                                    '.QN P               '                    '
                                                                                                                                                                '      ~

SI-114.2 Page 1 of 11 #E Rev. O APPENDIX A TAlli.E 11 SEQUOYAll INSERVICE INSPECTION PROGRAM CLASS 11 COMPONENTS Program Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Length No. Length Component Section Method Inspection Periods Reference Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. A. Steam Generators

1. Circumferential Shell Welds 8.1.1 UT C-A 4 Gens./3 Welds 3 (12) 1 1 1 Cliff-2345-II

2. Circumferential .

IIcad Welds 8.1.2 UT C-A 4 Gens./1 Weld I wld/46 ft 15' 15' 16' (4) Clill-2345-II es

3. Tubesheet-to-Shell Weld 8.1.3 UT C-A I wld/36 ft 4 Gens./1 Weld 12' 12' 12' (4) Clitt-2345-B

4. Nozzle-to- -

Vessel Welds 8.1.4 UT, NT C-B 4 Gens /2 Noz'(8) 2 1 0 1 CKH-2345-B B. Heat Exchangers '

1. Residual lleat

                              ,          Removal 11 cat Exchanger (2)

RilRIIX

a. RilRifX Circumfer-ential Shell Weld 8.2.1.1 UT C-A 2]It.Ex./1 Wcid 1 1 0 0 CKH-2404-A

                         ,                 .                                                                                                         9

_1_

r-- - -

~'

SQNP SI-Il4.2 "E" II Page 2 of 11 Rev. O APPENDIX A TAlli.E D SEQ 110YAll INSERVICE INSPECTION PROGRAff CI. ASS 11 CollPONENTS Program. Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Length Component Section No. Length Inspection Periods Reference tiethod Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. B. Ileat Exchange _rs (Continued)

b. RIIRiiX Ci rcum fer-ential IIcad Weld 8.2.1.2 UT C-A 21It.Ex./1 Weld 1 1 0 0' (2) Clit!-2404-A

c. RIIRIIX c3 Nozzle-to-NJ Vessel Weld 8.2.2 UT, PT C-B 2llt. Ex ./2noz.

2 1 0 (4) 1 CIIM-2404-A

d. RIIRIIX Integrally-Welded Supports 8.2.3 PT C-C 211t.Ex./2 Welds 2 0 CilM-2404-A 1 1

(4)

e. RHRilX -

Component Supports 8.2.4 VT-3 C-E 211t.Ex./ 2 1 0

2 Sprts. (4) 1 CllH-2404-A t I . SQNp SI-il4.2 ** Page 3 of 11 Rev. O APPENDIX A TAllLE il SEQUOYAll INSERVICE INSPECTION PH0GRAff CLASS B C0til'ONENTS Program Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Length Component Section No. Length Inspection Periods Reference Hethod Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. B. Ileat Exchangers (Continued)

2. Regenerative lleat Exchanger (1) RilX

a. RilX Circum-ferential IIcad Weld 8.3.1.2 UT C-A lift.Ex./6 Welds 6 2 2 2 -

ISI-0066-A

b. RilX Circum- .

ferential og Tubesheet-to-Shell Weld 8.3.1.3 UT C-A 1. lit.Ex./6 Welds 6 2 2 2 It!-0066-A

c. EllX Int.-

Wid. Support Lugs 8.3.3 ST C-C lset/3 Lugs 1 0 0 1 ISI-0066-A

d. RHX Component Supports 8.3.4 VT-3 C-E 2 2 0 1 1 ISI-0066-A

3. L'etdown lleat Exchanger (1) LilX

a. LilX Circum-ferential llead Weld 8.4.1.2 UT C-A IIIL.Ex./2 Welds 2 1 1 '0 ISI-0068-A b .* LIIX Component Supports 8.4.4 VT-3 C-E 2 2 1 1 , O ISI-0068-4 9

7_ . _ r -- *

                                                                      '           ~ ~ ~ ~ ~

3

                                            .                                                   SQNP S1-114.2                                                           '8"              '

Pg 4 of 11 Rev. O APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAff CLASS B CollPONENTS Program Reference. Exam Section XI 40 Yr. Sample 1st Insp. Interval Exam No. Length Component Section Method No. Length Inspection Periods Reference

      ;                                                                          Category     Welds /of Weld  Welds /of Weld         3 yrs. 7 yrs.      10 yrs. Dwg. No.

B. Heat Exchange s (Continued) ,

4. Excess Letdown IIcat Exchanger ,

(1) ELilX

a. ELilX Circum- .

ferential llead Weld 8.5.1.2 UT C-A Ilit.Ex./1 Weld 1 1 0 0 ISI-0067-A C. Tanks . et

        '6
    ;                1. Boron Injection Tank (1) BIT

a. BIT Circum- ,

ferential Shell/IIead

  ,                               Wid         ,      8.6.1          UT        C-A           ITank/2W'el,ds         2                         0 1                      1         ISI-0074-A

b. BIT Nozzle to Vessel Wlds 8.6.2 ST C- B 1 Tank /2Noz 2 1 1 0 ISI-0074-A

c. BIT Component Supports 8.6.4 VT-3' C-E 2 2 1 .

1 O ISI-0074-A

d. BIT: Pressure Retaining ,

Bolting ) >2" Dia. 8.6.4 UT C-D 1 Hwy /16 Studs Illwy, 1 0 O ISI-0074-A k ,

7 . - -. 7 ,_ _ c __. . .. ._. _ . . . 3 SQN S I-I I .. : .' Page 5 of 11 Page 5 of 11 Rev. 0 APPENDIX A TAllt.E B SEQUOYAII INSERVICE INSPECTION PROGRAtl CLASS B C0!!PONENTS Program Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Length Component Section No. Length Inspection Periods Reference Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. C. Tanks (Continued)

2. Ull! Water Accutaulator '

(1) WA

a. WA Circum-ferential.

Shell/

                     ;b                        licad Wid      8.7 1            UT      C-A               ITank/2 Welds 2         1*                    0 i

1 ISI-0070-A

b. WA Nozzle to Vessel Welds 8.7.2 UT,ST C-B 1 Tank /3Noz 3 1 I 1 ISI-0070-A

c. ~WA Int.- .

Weld

                               .              Supports       8.7.3            ST      C-C               1 Support Skirt           35'        12'        11'        12'        ISI-0070-A

d. WA' Component

                                 .           Supports        8.7.4            VT-3    C-E              1 Cmpnt Support Sk,irt       1          0           1        0        ISI-0070-A

e. WA Pressure Retaining ..

Bolting

                                             >2" Dia.        8.7 5            UT      C-D              INwy/16 Studs       -

1 Hwy 0 1 0 ISI-0070-A 1 I

r_-.. . . . . , SQNP

S I- I t 's .' /

Page 6 of Il Page 6 of 11 Rev. O APPENDIX A TAlli.E Il SEQUOYAll INSERVICE INSPECTION PHOGRAll CI. ASS Il C0!!PONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. I.en gt h Component Section No. I.cngth Inspection Periods Reference Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. C. Tanks (Continued)

3. Ulli Surge Tank (1) ST

a. ST Circum-ferential Shell/ .

Head Wld 8.8.1 UT C-A ITank/2Wids 2 0 1 1 ISI-0071-A 4 b. ST Int.- Weld i Supports (PADS) 8.8.3 ST C-C 1 Tank /2 Pads 2 1 1 0 ISI-0071-A

c. ST Component Supports 8.8.4 VT-3 C-E 2 2 'n 0 1

ISI-0071-A D. Piping

1. Integra lly-Welded

_ Supports

a. Residual llea t Removal System 8.9.1.1 N/A C-C See Program Section 8.9.1.1 HSG-0010-C

b. Safety Injection System 8.9.1.2 .PT C-C 7 7 2 2 3 MSG-0009-C

p-

                                                                                                                                                                                             ;                        i SQNP       -

SI-ll4.2 Page 7 of 11 Page 7 of 11 Rev. 0

                                                                                                                                     ,      APPENDIX A TAltl.E B SEQUOYAll INSERVICE INSPECTION PHO,GRAtl CLASS B CollPONENTS Program Reference       Exam Section XI 40 Yr. Sample 1st Insp. Interval Exam           No. Length Component              Section     Hethod                                              No. Length        Inspection Periods Category        Velds /of Weld     Welds /of Weld                                       Reference 3 yrs.      7 yrs. 10 yrs. Dwg. No.

D. Piping (Continued)

c. Main Steam System 8.9.1.3 MT C-C 9 9 3 3 3 ffSG-0017-C

d. Feedwater ,

System ,8.9.1.4 HT C-C 4 4 1 1 2 flSG-0016-C e.

                               )                                             Contair! ment Spray System          8.9.1.5 PT          C-C See Program Section 8.9.1.5 ilSG-0011-C

f. Upper, Head Injection ,

System 8.9.1.6 PT C-C 4 4 1 l 2 MSG-0014-C

2. _ Component .

Supports '

a. Residual .-

IIca t '. - t i

                                                                         , Removal

System 8.9.2.1 VT-3;.

C-E 82 82 ;- ^ VT-4 28 ,27 27 HSG-0010-C [

                                                                                                                                                                                     '                                      ?.

b. . Safety .

Injection {. i System 8.9.2.2 VT-3, C-E 53 53 18 l VT-4 17 18

'                                                                                                                                                                                                             HSG-0009-C l
                                                                 .                                                                                                                                .                         g' .

7- p . ._ . . _ _ , 7-SQNP S1-114.2 Page 8 of 11 Rev. O APPENI)IX A TAlil.E 11 SEQUOYAll INSERVICE INSPECTION PROCHAN CLASS B C0flPONENTS Program Reference Exam Section XI 40 Yr. Sample 1st Insp. Interval Component Exam No. Length No. Length Section Method Category Welds /of Weld Inspaction Periods Reference Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. D. Piping (Continued)

c. Hain Steam System 8.9.2.3 VT-3, C-E 72 .

72 24 24

VT-4 24 HSG-0017-C

d. Feedwater .

System, 8.9.2.4 VT-3, C-E 35 35 12 11 12 V.T-4 flSG-0016-C

e. Contain-ment, Spray Syste,m 8.9.2.5 VT-3, C-E 5 5 2 VT-4 1 2 t!SG-00ll-C

f. Upper Head Injection System 8.9.2.6 VT-3, C-E 7 7 VT-4 2 2 3

                                                      .                                                                                                                         !!SG-0014-C

3. Circumferential and Longitudinal A. Residual lieat Removal System I'

a. RilR Cires.>\" Nom. Wall Thickness 8.9.4.1 IIT, PT C-F, C-C 22 5 1 2 2 ISI-0003-C

b. RilR Long. > " Nom.W'all Thickness 8.9.4.1 tlT PT C-F, C-G 4 1 0 1 0 ISJ-0003-C

r--- - - -- 4, - SQNP SI-Il4.2 #E " Page 9 of 11 Rev. O APPENDIX A TABI.E B SEQUOYAll INSERVICE INSPECTION PROGRAM Cl. ASS B COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Component Inspection Periods Reference : Section Method Category Welds /of Weld Welds /of Weld

        .                                                                                                                                                                   3 yrs. 7 yrs.       10 yrs.      Dwg. No.   '

D. Piping (Continued) c. RIIR Cires $\" Nom. Wall Thickness 8.9.4.1 PT C-F, C-G 103 26 8 9 9 ISI-0003-C

d. RHR Long. $\" Nom. Wall Thickness 8.9.4.1 PT C-F, C-C 28 7 2 2 3 ,

ISI-0003-C B. Safety Injection System - 1

a. SIS Cires >\" Nom. Wall Thickness 8.9.4.2 UT, PT C-F, C-G 33 8 t

3 2 3 ISI-0002-C l

b. SIS'Cires $\" Nom. W'all Thickness 8.9.4.2 PT C-F, C-G 30 -

7 2 2 3 ISI-0002-C !

c. SIS Long. $\" Nom. Wall Thickness 8.9.4.2 PT C-F, C-G 6 1 0- 0 1 ISI-0002-C C. Main Steam System '

a. MS Cires > " Nom. Wall Thickness 8.9.4.3 UT, NT C-F, C-G 24 6 2 2 2 ISI-0015-C

b. MS Long. > " Nom. W'all ' Thickness 8.9.4.3 UT, NT C-G, C-G 4 1 0 1 0 ISI-0015-C p 8

f*~' t r , 1 . SQNP SI-il4.2 sge 10 of 11 Page 10 of 11 Rev. O APPENDIX A TAHI,E H SEQUOYAll INSERVICE INSPECTION PROGRAtl CLASS H C0tlPONENTS Program Reference Section XI 40 Yr. Sample 1st Insp. Interval Exam Exam No. Length Component Section No.' Length Inspection Periods Reference tiethod Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. D. Piping (Continued) D. Feedwater System a. FW Cires >\" Nom. Wall Thickness 8.9.4.4 UT, ilT C-F, C-G 8 ' 2 0 l 1 Clitt-2403-C

b. FW Long. >\" Nom. Wall Thickness .

8.9.4.4 UT, MT C-F, C-G 1 - 1 1 0 0 Clift-2403-C '"I E. Containment Spray System a .' CS Cires $ " Nom. Wall Thickness ' 8.9.4.5 PT C-F, C-G 5 1 1 0 0 ISI-0007-C

b. CS Long. $\" Nom. Wall Thickness

    ,                             8.9.4.5.      PT          C-F, C-G            2            ,      1          0          1          0                  ISI-0007-C F.      Upperhead Injection System 8.9.4.6       UT, PT     C'F, C-G             26                  7 2         2           3                  ISI-0001-C          ,

E.' Pumps

1. Residual lleat Removal Pumps,(2) RilRP

a. RHRP Support Componen'ts 8.9.1.2 VT-3 C-C, C-E 6 6 '

2 1 O e

7 7 , . r SQNP SI-l14.2 Pd8" II I II' Page iI of 1I Rev. O APPENDIX A TAl:1.E H SEQUOYAll INSERVICE INSPECTION PROGRAff CLASS B CO?!PONENTS Program Reference Exam Section XI 40 Yr. Sample 1st Insp. Interval Component , Exam No. Length Section Hethod No. I.engt li Inspection Periods Category Welds /of Weld Reference Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. F. Exempted Components 8.12 VT-2 C-II See Program Section 8.12 9

9 I

O o f a

                                                                                                                                                                  -Il-

s.ne

SI-ny.3 l Page 1 of 3. tiiv. O I APPENDIX A TABLE C LIST OF DRAWINGS - UNIT 2 , Reactor Vessel Drawinz No. Appendix A Title Page No. ISI-000S-B Reactor Coolant Piping ISI-0001-C /5'9 //c Upper Head Injection System Cil-M-2341-B / 35 - / $7 CH-M-2343-B Reactor Vessel Stud Locations and Details /o0 - /v/ Reactor Vessel Seam Welds /01 CH-M-235S-A CH-M-2359-A Reactor Vessel Closure Head /03 Control Rod Drive Housing CH-M-2360-A lo7 - /or CH-M-2361-A Reactor Vessel Inlet Nozzles to 9 ISI-0014-A Reactor Vessel Outlet Nozzles //o Auxiliary Head Adapter -

                                                                                        /06 ISI-0016-A MSG-0001-B Reactor Vessel Clad Patches (PSI Only)                 ///

MSG-0004-C Closure Head Cladding. Patches (PSI Only) //1 ISI-0097-C Reactor Vessel Bottom Head Penetrations //3 Closure Head Penetrations /o4- /or 1st -c ott- A AdA croA ccelsur Paw swicar par /LZ Pressurizer Drawing No. Appendix A Title Page No. CH-M-2362-A Pressurizer Supp6rt Skirt Weld /'I CH-M-2663-A Pressurizer Seam Welds MSG-0002-B //1 - Pretsurizer and Steam Generator Cladding , Patches MSG-0006-A //# Pressurizer Heater Penetations /20-Steam Generators t Drawing No. Appendix A Title Page No. IST- 0008-8 Reactor Coolant Piping CH-M-2345-B Steam Generator

                                                                                   /5 9- /to 76M1
                                                                                      //r Vertical Steam Generators (Tube Sheet
   ~

Arrangement) /#4 MSG-0002-B Pressurizer and Steam Generators Cladding Patches MSG-0005-A l/s Steam Generator /Fe,edwater Transition Spool Piece .

                                                                                     //7 M+                                                                                ,

e 97

                                                                                           ~ , -

SQNP l SI-114.2 Page 2 of 3

       ~                                       Page 2 of 3                                           i t

Rev. O APPENDIX A

                                            ,       TABLE C LIST OF DRAWINGS - UNIT 2                                   -

Heat Exchangers Drawint No. ][iIl E Appendix A Pace No. CH-M-2404-A Residual Heat Removal Heat Exchanger /2 I ISI-0066-A Regenerative Heat Exchanger ISI-0067-A Excess Letdown Heat Exchanger /2V-/2/ ISI-0068-A Letdown Heat Exchanger j7

/2?

Pinine and Valve Weld Maps Drawint No. Appendix A 7,7L g pa g e No . ISI-0008-3 Reactor Coolant Piping (Main Loops) ISI-0002-C Safety Injection System /Ti- ##0 ISI-0013-C Reactor Coolant System /31 - /49 ISI-0009-C Chemical and Volume Control System

                                                                                   /t/ - 171 ISI-0003-C      Residual Heat Removal System                           /4/ - /42 ISI-0001-C       Upper Head Injection System                            /r: - 177 MSG-0008-C Seal Water Injection (Chemical and Volume      .         /20- /?7 Control System) '               /74- /*

CH-M-2403-C Feedwater System ISI-0015-C Main Steam System f 33- /.r u ISI-0007-C /74-e7f Containment Spray System

                                                                                         /ff Pipine and Valve Support Drawings              .

Drawing No. gg7gg Appendix A Page No. MSG-0013-C Reactor Coolant System MSG-0012-C J o!- l sv MSG-0015-C Chemical and Volume Control System . Jos - 102 Seal Water Injection (Chemical and Volume MSG-0010-C Control System) 2/1- 22I Residual Heat Removal System MSG-0009-C Safety Injection System f 93 - f97 MSG-0014-C Upper Head Injection System /r/- /72 MSG-0017-C Main Steam System 2/r- 2et MSG-0016-C Feedwater System' ~2 2 /- JJ 7 MSG-0011-C 224 - 225' - Containment Spray System 2 co 4 g

SQNP SI-114.2 Page 3of 3 Rev. 0 - Page 3 of 3 SPPENDIX A TA3II C LIST OY DRAWINGS - UNIT 2

~~

Reacto.- Ceelan Pumos Drawine No. 7f, g g Appendix A Pace No. CH-M-2675-3 Reactor Coolant Pump Main Flange and I.ower Seal House Bolt Pattern /21 Tanks . Drawine No. Appendix A T/ TIE Pare No. ISI-0070-A Upperhead Injection Water Ace'umulator ISI-0071-A Accumulator Surge Tank 12 f - /Jo ISI-0074-4 Boren Injection Tank /3/ i

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7 _ i I LIST OFCONTROL ROD DRIVE Il0USINGS C.RD, NO. NIAiBER B l-9 9 9.05 10-13 4 9.57 14 -17 4 12,2 0 18 -21 4 13.0 7

                                                           '22-29             8           14.0 2 30-37             8           16.81 38-41             4           19.69 4

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!PH II I !T llN s n . - f t E 9: E n i l - "~ 2~ -.e 3 $.$ Y i E CT h m m c- = r3 ; ,c. . ! l y -l g 7 ~I 7T w s#yis:i &C tv g :IP a v 4 7- 3 ? e "f^-aIk: !! } I - is : s." E*. i - r 4 t E e- t 3 22 g 99 ~~ ; . 1 5 t 4 e 'f .6. "***=w.aus iy, I I I ! !h , l ; ;aL ll a:L3 T si ';9:? ' e t: i ld E s J i .h,i 1 p @' 8 3;gg . b.Dj, .. 1,

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S - 1 ! Eu N I e . i . g 1 I 8

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1 F 6 ,m . j j L l V sT 4 I l M y ' s O Y r W 4 = 4 e . I 2ll ~ n , i ,i e{ i~,: l l@ 3; Ss-t, ui ? sg !: .

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b k I I il 1 - 3 1 . i ! E h h 5 ' ? I .~ } )' 9e 5 + . m = = , w V . l . ~ . e . e-e $~e u Z l ce > e, Cf M eg c p' t/3 t/3 L M g / -- ,s ,~ ? S

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ML20080C928

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21.0 REFERENCES

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