ML20215D395

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Rev 7 to Surveillance Instruction SI-114.2, Inservice Insp Program for TVA Sequoyah Nuclear Plant
ML20215D395
Person / Time
Site: Sequoyah  
Issue date: 10/14/1986
From: Crane E, Lewis J
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20215D372 List:
References
SI-114.2, NUDOCS 8612160349
Download: ML20215D395 (407)
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{{#Wiki_filter:- TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SURVEILLANCE INSTRUCTION SI-ll4.2 INSERVICE INSPECTION PROGRAM FOR TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT Unit 2 only Revision 7 PREPARED BY: _ , E. D. Crane RESPONSIBLE SECTION: , _ In-Service Insp Group-C REVISED BY: J. T. Lewis REVIEWED BY: R. M. Emrath SUBMITTED BY: ( ,, IM G. L. Belew ' Responsible Section Supervisor PORC REVIEW DATE: OCT14586 APPROVED BY: 

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Plant Manager DATE APPROVED: . __ OCT 14 %$6 Reason for revision sinclude a si Instruction Change Form Nos.): Revised to reflect organizational chang _es, plant configuration changes, comply with discrepancy report SQ-DR-86-05-119R, NRC commitments CCTS control numbers: NCO-85-0284-004, NCO-86-0119-004, NCO-86-0119-003, NCO-86-0119-002, and _ . NCO-86-0119-001, and SPTS item No. 860752A and 867012F. The last page of this instruction is number: 401 8612160349 DR 061210 g ADocg 050003g, PDR . ~

SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG SURVEILLANCE INSTRUCTION SI-ll4.2 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS) 0 07/22/83 ALL 61, 62 1 09/02/83 231 ISI Program 2 09/27/83 Coversheet Table of Contents, 28,29,33, 49-52C, 62-67,74, 82,93, 95-99, - 119,126, 130,132, 135-137, 145-148, 164-167, 176,17*/, , 179,180, - 183,185, 187,196, 

       '                 199,200, 214,215, 218,'

4 08/17/84 228-283 Revise: 282, 283-331 Added: 122D, 282A thru 5  : 09/04/84 282A67 6 05/16/85 264 Revised to reflect organizational . changes, plant configuration changes, comply with discrepancy report SQ-DR-86-05-119R, NRC commitments CCTS control numbers: NCO-85-0284-004, NCO-86-0119-004, NCO-86-0119-003, NCO-86-0119-002, and NCO-86-0119-001, 7 OE .i  ! 4 l988 ALL and SPTS item No. 860752A and 867012F. 0401C/vbo

SQNP SI-114.2 Punchlist Page 1 of 1 Rev.'7 ' PUNCHLIST Reactor Vessel Repair Welds Beltline Region J T &Ab Jo-zo-og a 1 i l s e i i i I l 4 L

SQNP SI-114.2. Cover Sheet Page 1aof 1 Rev. 7 Inservice Inspection Program Cover Sheet Owner: Tennessee Valley Authority Address of Corporate Office: Chattanooga Office Complex 1101 Market Street Chattanooga, Tennessee 37402-2801 Name and Address of Nuclear Power Plant: Sequoyah Nuclear Plant F.O. Box 2000 Daisy, Tennessee 37319 Applicable Nuclear Power Units: Sequoyah Nuclear Plant, Unit 2 Commercial Operation Date: June 1, 1982 O e SI-114.2 ,- -- __. _ , . , . . . . - . . . , , - _ - . _ _ _ . _ . _ _ . _ _ ,w,,. - . . - - - - - - * , - - . _ , - -

SQNP SI-114.2 Page 1 of 2 Rev. 7 TABLE OF CONTENTS Page No. 4 I. Prerequisites i II. Precautions i 1.0 Statement of Applicability 1 2.0 Purpose 1 3.0 Inspection Intervals and Inspection Periods 1 4.0 Codes of Record 2 5.0 Method of Implementation and Responsibilities 2 6.0 Abbreviations and Definitions 4 7.0 Components Subject to Examination - TVA Safety Class A 5 8.0 Components Subject to Examination - TVA Safety Class B 32 9.0 Components Subject to Examination - TVA Safety Class C and D 51 10.0 Authorized Inspector , 54 11.0 Examination Methods 55 12.0 Qualifications of Nondestructive Examination Personnel 58 13.0. Acceptance Criteria 58 14.0 Repairs 59 15.0 Replacements 59 16.0 Records and Reports 59 , 17.0 Notification of Indication 63 18.0 Calibration Blocks 64 

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19.0 Requests for Relief 65 20.0 Augmented Inspections 65 21.0 References 70 l SI-114.2 

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SQNP SI-114.2 Page 2 of 2 Rev. 7 T TABLE OF CONTENTS Page No. Appendix A - Tables and Drawings 71-270 Appendix B - ------ Appendix C - Data Sheets 271 Appendix D - Notification of Indication Form 272 Appendix E - Requests for Relief - 273-292 Appendix F - - Appendix G - Appendix H - Support Load Criteria 299-401 r ee I SI-114.2 

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_... SQNP SI-114.2 Page i Rev. 7 I. Prerequisites A .- k' hen craf t support of minor or similar maintena.'ce (Examples: Scaffolding, insulation removal , buffing of wel.ds using l scotchbrite pads, and cleaning bolts) is required to facilitate performance of this SI a single work request (WR) may be used per SQM-2. 

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13 . Contact rad llealth (RC) for radiation work permit (Rh'P), ALARA preplanning requirements. I Pressurizer loop seal insulat. ion may not be removed using a generic HR. t II. Precautions 4 A. Safety belts should be worn when working from scaffolding or ladders. . B. Protective clothing, such as-long sleeve shirts or gloves, ' should be worn except in RWP areas when working around hot-pipes and equipment. C. Care should be exerciued when climbing on plant structures and p2 puts to ensure firm footing. 11cxing of instrument lines and electrical conduit, for example, could ccuse equip.r. ant damage as well as bodily injury resulting from a fall. D. Ex ui:uttonn .<bould be planned to reduce delays and radi it ion exposure during performance of the t.'ork. E. Re.:d m oliserve .ul api,1! cable precautions as indicated in CC! 4dui;.irtrat ive .autructions (AT)-26 " Prevention of fcirei'n aa;.ria: iis t he Prii.ury System ' ind M-8 " Access tn Cent. h. nt". i S1-114.2 

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SQNP SI-114.2 Page 1 of 70 Rev. 7 1.0 STATEMENT OF APPLICABILITY This program outlines requirements for performing the first 10 year interval' inservice nondestructive examinations of the Sequoyah_ Nuclear' Plant, unit 2, ASME Code Class 1, 2, and 3 components (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 Nuclear Quality Assurance Manual, (NQAM) Part II, Section 5.1 and comply as practical with the requirements of Section XI of the ASME 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 Require-ments 4.4.5.0, and 4.4.10, and partially satisfies the require-ments of Surveillance Requirement 4.0.5. Inspectiion frequencies are in accordance with Appendix A of this instruction and are - generally scheduled to coincide with outage periods. 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 instruction but are included in nondestructive examination' procedures (PMP 1502.07 and SNP TI-51). , 2.0 PURPOSE The ISI program shall be used for planning inspections and nondestructive examinations of the Sequoyah ASME 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 examinations.

The examinations required by this program will establish accep-tance of components for continued service. 3.0 INSPECTION INTERVALS AND INSPECTION PERIODS The inservice examinations required by ASME Section XI shall be performed during each 10-year interval of service (inspection interval). 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 i year. If the unit is out of service continuously for six months L or more, the inspection interval may be extended for an equivalent
period. This SI may be preformed in any mode and is applicable i for all operational modes.

l 1 SI-114.2

SQNP SI-114.2 Page 2 of 70 Rev. 7' The inspection interval shall be separated into three inspection ~ periods. Except for examinations that may be deferred to the end of the inspection interval, the required examinations shall be performed in accordance with the following schedule. Minimum Examinations Maximum Examinations Inspection Period Completed, Percent Completed, Percent 3 Years 16 34 7 Years 50 67-10 Years 100 s 100 The examinations deferred to the end of the inspection interval shall be completed by the end of the inspection interval. 4.0 CODES OF RECORD AND CODE CASES - The Sequoyah unit 2 operating license (low poweb) 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 and Surveillance Requirement 4.4.5.0. 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 accordance with the 1974 Edition, Summer 1975 Addenda, of the ASME Section XI (SI-114). The use of Code cases N-234, N-235 and N-307 have been approved for TVA use by NRC. 

;     5.0    METHOD OF IMPLEMENTATION AND RESPONSIBILITIES Weld maps and other 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).

SI-114.2

SQNP * 

                                                          -SI-114.2                                                                   -

Page 3 of 70 Rev. 7 The Mechanical Services Branch NDE Inspection Section shall' - , prepare scan plans using component listings supplied by the ISI > Programs Section for the inservice inspection. The plans should include as a minimum' references to components to be examined, e methods of examinations,_ examination procedures, and calibration standards. Prior to performing examinations on a system or component, the scan plans shall be approved by a NDE Level III , individual from the NDE Engineering Section and submitted to the Plant Manager for information. When inservice ~ examinations "are implemented by instructions other than this program (e .g., . MI's), copies of the instruction data sheets shall be submitted to the Mechanical Services Branch by the performing organization 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, 17.2.5, 7.3.6, 7.3.8, 7.5.1, 7.5'.5, and 7.6.6 of this program. , following major modifications / replacements an ISI Programs Section representative will initiate a talkdown of the affected portion 

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of the system or components to verify the completeness of the ISI weld / support map. If variations in piping configurations are discovered or alterations or repairs to piping are made during the service life of the unit, these changes shall be marked on field controlled copies of drawings. This information shall be communicated s to the ISI Programs Section which shall be responsible for i revising the drawings and incorporating the revised drawings into this program. The NDE Inspection Section scan plan shall also be j revised to reflect these changes in the same manner as the original. r The inservice examinations will be performed by either Mechanical Branch, Quality Assurance Staff personnel or outside contractors. i Contract preparation, administration, and supervision will be the ( responsibility of the Mechanical Services Branch NDE Inspection j Section. Inspection plans by outside contractors shall be reviewed and approved by the NDE Engineering . Section prior to use. All specific NDE prccedures used during the inspection program shall be reviewed and approved in r accordance with NQAM Part II, Section 6.3. NDE Procedures shall be implemented in accordanca with TI-51. The ISI unit supervisor will be responsible for notifying the plant manager 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 uhere an outside contractor is furnishing inservice examination services, the contractor will normally initiate the form in Appendix D 4 under the supervision of the NDE Engineering Section representative.

] See Section 17.0 of this program. e Uhen the examination is completed, the NDE Engineering or Inspection Section repreacntative shall compare the completed exam results to the requirement of the scan plan. identifying 

                                                           ~3-                                                SI-114.2 v v     v - ,

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SQNP SI-114.2 Page 4 of 70 Rev. 7 any limitations or impractical examinations, and provide notification to the ISI Programs Section for possible action in accordance with Section 19.0 of this instruction. A NDE Level II or III individual shall evalaute the NDE results in accordance with Section XI, IWA-3000. The results shall be compared with recordeo n sults of the preservice NDE and previous In-service NDE re.ilts. Following each refueling outage when inservice examinations are performed, the' data package cover sheet in Appendix C shall be completed by the NDE Inspection Section representative and sub-mitted 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 Mechanical Services Branch. Any revisions initiated by other groups shall be submitted to the ISI Programs Section for approval prior to incorporating the revisions into this program. The ISI programs section maintains a computerized data base system for status and section XI credit of completed ISI examinations. 

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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 Normal Operation--Normal plant operation conditions include i reactor startup, operation at power, hot stendby, and ! reactor cooldown to cold shutdown conditions. Test j conditions are excluded. l l SI-114.2 I i

SQNP SI-114.2 Page 5 of 70 Rev. 7 6.9 Pressure-Retaining Material--Applies to items such as vessel heads, nozzles, pipes, tubes, fittings, valve bodies, bonnets, disks,. pump castings, covers, and boltings which join pressure-retaining items. 6.10 Repair--Those operations involving welding, heat treatment, or defect removal which are required to restore an item to a , safe and satisfactory operating condition. 6.11 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 SUBJECT TO EXAMINATION--TVA SAFETY CLASS 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 4 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) tha't 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 7.1.1 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. l SI-114.2

SQNP SI-114.2 Page 6 of 70 Rev. 7 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 Longitudinal Shell Welds There are no longitudinal shell welds associated with the reactor vessel. 7.1.1.3 Closure Head Circumferential 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 weld deposited austenitic stainless steel. 7.1.1.4 Lower Head Circumferential Weld The entire length of the lower head circumferential 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). t l 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. 7.1.1.5 Closure Head Meridional Weld The closure head does not include any meridional welds. l SI-114.2 )

SQNP SI-114.2 Page 7 of 70 Rev. 7 7.1.1.6 Lower Head Meridional Welds There are six meridional welds (each approximately 4 feet in length) located in the lower head. The entire length of each of these welds will be ultrasonically examined during the third 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 flang6 section is fabricated of A-508, Class 2, manganese-molybdenum steel and is clad internally and on the gasket face with weld deposited austenitic stain-less steel. 7.1.1.8 Closure Head-To-Flange Weld , The entire length of the head-to-flange a 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 fabri-cated of A-508, Class 2, manganese-molybdenum steel and is clad internally and on the gasket face with weld deposited austenitic stainless steel. 7.1.1.9 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. SI-114.2 

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SQNP '! SI-114.2 l Page 8 of 70 Rev. 7 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 nozzle-to-vessel welds will be ultrasonically examined from the inside diameter using remote inspection devices. The foar outlet nozzle-to-vessel welds shall be ultrasonically examined from the nozzle bore when , the upper internals are removed during the first 4 inspection period. The inlet nozzles are not accessible until the core barrel is removed. The four inlet nozzle-to-vessel welds shall be ultra-sonically examined from the nozzle bore and from the vessel shell inside diameter during the third inspection period when the core barrel has been removed. The outlet nozzle-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. L The nozzle forgings are fabricated of A-508, Class 2, manganese-molybdenum steel and are clad with weld deposited austenitic stainless steel. 7.1.3 Reactor Vessel Nozzle Inside Radius Section The eight nozzle inside radius sections (including the outlet nozzle integral extensions) shall be ultrasonically examined at the same time as the examination of the nozzle-to-vessel welds conducted from the nozzle bore (see Section 7.1.2). i Nozzle forging material is identified in j- Section 7.1.2 of this program. 4 7.1.4 Reactor Vessel Partial Penetration Welds The. vessel includes 4 upper head injection nozzles, e 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). l This 25 percent shall include 1 upper head injection nozzle, 1 vent pipe nozzle, 20 control rod drive j 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. SI-114.2

SQNP SI-114.2 Page 9 of 70 Rev 7 The NDE S.ection 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. 7.1.5 Reactor Vessel Nozzle-To-Safe End Welds The inlet and outlet nozzle-to-safe end welds shall be ultrasonically examined from the inside diameter using remote inspec' tion 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 interval (see memorandum from D. W. Wilson to H. H. Abercrombie, dated 08/01/86, L18 860730 899). The remaining nozzles will be examined during the normal inservice inspection intervals. Each nozzle safe end weld is a stainless steel type 304 weld build up. 7.1.6 Reactor Vessel Pressure Retaining Bolting 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. 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.) SI-114.2

SQNP SI-114.2 Page 10 of 70 Rev. 7 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. 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 Integrally 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 outaged at approximately three year intervals. 7.1.10 Reactor Vessel Removable Core Support Structures The visually accessible attachment welds and 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 i volumetric or surface examination in accordance with IWB-1220(a). SI-114.2

SQNP SI-114.2 Page 11 of 70 Rev. 7 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" 0.D. adapter of A-182, 304SS and a 4" 0.D. body of SB-167. 7.1.12 Reactor Vessel Auxiliary Head Adapters Each of the four auxiliary head adapters includes a pressure retaining dissimilar metal weld. The four dissimilar metal welds 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 There 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 Longitudinal Shell-To-Head Welds There is one longitudinal weld 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 weld with the circumferential head-to-shell weld. The vessel shell section material is identified in Section 7.2.1. 7.2.3 Pressurizer Circumferential and Meridional Head Welds There are no pressurizer circumferential or meridional head welds. l 1 SI-114.2

SQNP SI-114.2 Page 12 of 70 Rev. 7 

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                                          - 7.2.4 =        Pressurizer' Nozzle-To-Vessel Welds and Nozzle Inside Radius Section 1

The pressurizer includes three 6-inch safety valve , nozzles, one 6-inch relief valve nozzle, one 4-inch nozzle, and one 14-inch surge nozzle. All of the nozzle-to-vessel welds, including nozzle'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. 4 - 7.2.5 Pressurizer Heater Penetration Welds There are 78 heater penetration welds located in the i pressurizer lower head. Approximately 25 percent of the heater penetration welds (20 welds) shall be visually examined during the inspection interval in accordance with visual examination method VT-2 (see Section 11.1). Examination of these penetrations

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 heater penetrations requiring examination such that the organization performing the examinations may document examination results on SI-146 or SI-250 data sheets. b 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. t. 7.2.7 Pressurizer Pressure Retaining Bolting Larger Than Two Inches In Diameter 2 There is no pressure retaining bolting larger than two inches in diameter. SI-114.2 1 

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SQNP SI-114.2 Page 13 of 70 Rev. 7 7.2.8 Pressurizer Pressure Retaining Bolting Two Inches And Smaller In Diameter All of the pressurizer manway bolts 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 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 Pressurizer Integrally Welded Support 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. 7.3 Steam Generators (4) s 7.3.1 Steam Generator Primary Side Circumferential And Meridional Head Welds . There are no steam generator primary side circumfer-ential or meridional head welds. 7.3.2 Steam Generator Primary Tubesheet-To-Head Weld Each steam generator includes a tubesheet-to-head l weld (approximately 36 feet in length). The entire length 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 length of the two remaining welds shall be examined during the third inspection period. i SI-114.2 t._.

SQNP SI-114.2 Page 14 of 70 Rev. 7 

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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 Primary Nozzle-To-Vessel Welds And Nozzle Inside Radius Section 

         '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 nozzles are fabricated to SA-216, Gr. WCC. 7.3.4 Steam Generator Primary Nozzle-To-Safe End Welds Each steam generator includes two nozzles with buttered safe ends. Each nozzle-to-safe end we'ld 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 Primary Pressure Retaining Bolting Larger Than Two Inches In Diameter There is no pressure retaining bolting larger than two inches in diameter. 7.3.6 Steam Generator Primary Pressure Retaining Bolting Two Inches And Smaller In Diameter Each steam generator includes two manways. All the i 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 rerformed in accordance with MI-3.1 and provides for examination of bolting.

Each manway includes 16 bolts at 1.88 inches in diameter. SI-114.2

SQNP SI-114.2 Page 15 of 70 Rev. 7 7.3.7 Steam Generator Primary Integrally Welded Support Attachments There are no integrally welded vessel supports. The four main support pads are secured to the steam generator field support system by high strength bolts. 7.3.8 Steam Generator Tubing Each steam generator tube bundle consists of 3,388 NiCrFe alloy (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 Sample Selection And Inspection 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 Sample Selection and Inspection i ' The steam generator tube minimum sample size inspection result classification, ' and the corresponding action required shall be as specified in Table SG-2. l The full length of the tubes selected l for inspection will be examined (TVA commitment to NRC L44 850617 801). The inservice inspection of steam generator tubes shall be 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 l for these inspections shall be selected on l a random basis except: i I SI-114.2

SQNP SI-114.2 Paga 16 of 70 Rev. 7

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.
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 in-spection, 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 of Appendix A) during each inservice inspection m1y 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: SI-114.2

SQNP SI-114.2 l Page 17 of 70 

                             .Rev. 7 Category    Inspection Results C-1      Less than 5% of the l_                                              total tubes inspected

[ are degraded tubes and l= ' none of the inspected tubes are defective. C-2 One or more tubes, but not more than 1% of the l total tubes inspected l are defective, or between 5% and 10% of the total tubes in-spected are degraded

tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or l more than 1% of the i inspected tubes are defective. NOTE: In all inspections, previously degraded

tubes must exhibit significant (>10%)

l further wall penetrations to be included l in the above percentage calculations. 7.3.8.3 Inspection Frequencies

  • The above ' required inservice ins' p ections 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 l initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 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 results falling into the C-1 category or if two consecutive inspec-tions demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months. SI-114.2

SQNP SI-114.2 Page 18 of 70 Rev. 7 T

b. If the results of the inservice inspection 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 inspection 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 months.

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 actuation of the engineered safeguards.
4. A main steam line or feedwater line break.

7.3.8.4 Acceptance Criteria

a. As used in Section 7.3.8:
1. Imperfection means an exception to the dimensions, fir.ish or contour of a tube from that required by fabri-cation 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.
3. Degraded Tube means a tube containing imperfections >20% of the nominal wall thickness caused by degradation.

SI-114.2

SQNP SI-114.2 Page 19 of 70 Rev. 7

4. Percent Degradation 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 limit. A tube containing a defect is defective.
6. Plugging 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 r

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 loss-of-coolant accident, or a steam line or feedwater line break as specified in Section 7.3.8.3.c.
8. Tube Inspection means an inspection of
  • the steam generator tube from the point of entry (hot leg side) com-t pletely around the U-bend to the top support of the cold leg.
9. Preservice Inspection means a tube inspection of each steam generator tube performed by eddy current techniques prior to service to establish a baseline condition of the tu:d ng. This inspection shall be i per'~rmed prior to initial power operation using the equipment and techniques expected to be used during subsequent inservice inspections.
b. The steam generator shall be determined operable after completing the corre-sponding actions (plug all tubes exceeding the plugging limit and all tubes contaiuing through-wall cracks) j required by Table 2.

SI-114.2

SQNP r SI-114'.2 Page 20 of 70 Rev. 7 9 7.4 Piping All1 Class A piping systems to be examined are fabricated of 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). The following Class A piping systems are subject to examination: Reactor Coolant Chemical.and Volume Contrcl Residual Heat Removal Safety Injection Upper Head Injection 7.4.1 Piping Dissimilar Metal Welds There are no Class A dissimilar metal welds. 7.4.2 Piping 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 Bolting 2 Inches and Smaller in Diameter i 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. j The bolting may be examined in place under tension or

when the bolting is removed, i

7.4.3.1 Reactor Coolant System Piping Bolting 5 The Reactor Coolant System piping includes i thirteen bolted flange connections. I 7.4.3.2 Chemical and Volume Control System Piping

Bolting

! The Chemical and Volume Control System piping ! includes four bolted flange connections (from l seal water injection). SI-114.2 i

SQNP SI-114.2 P:g2 21 of 70 Rev. 7 7.4.3.3 Residual Heat Removal System Piping Bolting The Residual Heat Removal System piping does not include any bolted connections. 7.4.3.4 Safety Injection System 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 Longitudinal Pipe Welds The entire length of each circumferential pipe weld selected for examination shall be ultrasonically and/or liquid penetrant examined as practical. All 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. 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 62 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 cir-cumferential 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 101 pipe welds less than 4-inch nominal pipe size. Of these welds 25 shall be liquid penetrant examined during the inspection interval. SI-114.2

SQNP SI-114.2 Page 22 of 70 Rev. 7 7.4.4.3 Chemical and Volume Control System Piping Circumferential Welds The Chemical and Volume Control System piping (including seal water injection) includes 54 circumferential welds less than 4-inch nominal pipe size. Of these welds 14 shall be liquid penetrant examined during the inspection inte rval. 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 RHR system. 7.4.4.5 Safety Injection System Piping Circumferential Welds The Safety Injection System piping includes 92 ci,rcumferential 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 nominal pipe size. Of these welds 10 shall be liquid penetrant examined during the inspection inte rval. 7.4.4.6 Upper Head Injection System Piping Circumferential Welds The Upper Head Injection System piping includes 119 circumferential pipe welds 4 inches and greater nominal pipe size. Of these welds 30 shall be ultrasonically and liquid penetrant examined during the inspection interval. There are no piping welds less than 4-inch nominal pipe size. 7.4.5 Branch 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 i examined. Branch pipe connection welds 2 inches nominal pipe size and smaller shall be liquid penetrant examined. SI-114.2

SQNP-SI-114.2 Page 23 of 70 Rev. 7 4 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. 7.4.5.1 Reactor Coolant System Main Loop Branch Pipe Connection Welds , The Reactor Coolant System' Main Loop piping includes 1-branch pipe connection weld exceeding 2 inches nominal pipe size. This weld 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 Pipe Connection Welds The Reactor Coolant System piping includes .i 6 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. l There are 8 branch pipe connection welds 2 inches nominal pipe size and smaller. Of these welds 2 shall be liquid penetrant examined during the inspection interval. 7.4.5.3 Chemical and Volume Control System Branch Pipe Connection Welds i , The Chemical and Volume Control System piping l i includes 3 branch pipe connection welds I

exceeding 2 inches nominal pipe size. Of these welds I shall be ultrasonically and r 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

The Residual Heat Removal System piping i

includes 3 branch pipe connection welds exceeding 2 inches nominal pipe size. Of i f f SI-114.2 l i

SQNP l SI-114.2 l- Page 24 of 70 Rev. 7 these welds I shall be ultrasonically and

( liquid penetrant examined during the inspection , -interval. 'There are 2 branch pipe-connection ! welds 2 inches nominal pipe size and smaller.

These welds shall be liquid penetrant examined l

i during~the 40 year life, 7.4.5.5 Safety Injection System Branch Pipe Connection Welds The Safety Injection System piping includes l 5 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. l There are 11 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 Systen Branch Pipe, Connection Welds The Upper Head Injection System piping includes 2 branch pipe connection welds 2 inches nominal pipe size and smaller. Of these 1 shall be liquid penetrant examined during the inspection interval. ! 7.4.6 Pipian Socket Welds l The entire length of each socket weld selected for examination 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 inspection interval in accordance with Table A of Appendix A. 7.4.6.1 Reactor Coolant System Pipina Socket Welds The Reactor Coolant System piping includes 247 socket welds. Of these welds, 62 welds will be examined during the inspection interval. 7.4.6.2 Chemical and Volume Control System Piping Socket Welds The Chemical and Volume Control System piping includes 246 socket welds. Of these welds, 62 welds will be examined during the inspection interval. SI-114.2

SQNP SI-114.2 Page 25 of 70 Rev. 7 7.4.6.3 Residual Heat Removal System Piping Socket Welds The Residual Heat Removal System piping includes 18 socket welds. Of these welds, 5 welds will be examined during the inspec-tion interval. 7.4.6.4 Safety Injection System Pipina Socket Welds The Safety Injection System piping includes 170 socket welds. Of these welds, 43 welds will be examined during the inspection interval. 7.4.6.5 Upper Head Injection System Piping 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 Pipina and V,alve Intearally-Welded Support Members Integrally-weldedsupportmembersinc$udethesupport 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 attachments whose support base material desian thickness is 5/8 inch and arester. 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 Pipina and Valve Intearally-Welded Support Members The Reactor Coolant System piping includes 11 integrally-welded support members. All of these shall be examined during the inspection interval. SI-114.2

SQNP SI-114.2 Page 26 of 70 Rev. 7 7.4.7.2 Chemical and Volume Control System Piping and Valve Integrally-Welded Support Members The Chemical and 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 Piping and Valve Integrally-Welded Support Members The Residual Heat Removal System piping includes 5 integrally-welded support member. Both supports be examined during the inspection interval. , 7.4.7.4 Safety Injection System Piping and Valve Integrally-Welded Support Members The Safety Injection System piping includes 9 integrally-welded support members. All of these shall be examined during the inspection interval . 7.4.7.5 Upper Head Injection System Piping and Valve Integrally-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 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. The setting of snubbers, shock absorbers, and spring-type hangers shall be verified in accordance with the accepted criteria shown in Appendix G or applicable work instruction. The setting of snubers and shock absorbers is performed in accordance with SNP SI-162.2 or HI-6.13 series. SI-114.2

SQNP SI-114.2 Page 27 of 70 Rev. 7 The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. 7.4.8.1 Reactor Coolant System Piping and Valve Component Supports The Reactor Coolant System piping includes 137 component supports. All of these shall be examined during the inspection interval. 7.4.8.2 Chemical and Volume Control System Piping and Valve Component Supports The Chemical and Volume Control System piping includes 127 component supports. All of these shall be examined during the inspection interval. 7.4.8.3 Residual Heat Removal System Piping and Valve Component Supports 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 110 component supports. All of these shall be examined during the inspection interval. 7.4.8.5 Upper 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. SI-114.2

SQNP SI-114.2 Pega 28 of 70 Rev. 7 All of the 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 for this examination are included in MI-2.2. 1 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 with visual examination method VT-1 (see Section 11.1). Provisions for this examination are included in MI-2.2. The main flange bolts are fabricated of 4340 steel, heat treated to A-540, Gr B24. 7.5.2 RCP Pressure Retaining Bolting 2 Inches and Smaller in Diameter Each RCP includes two sets of pressure retaining bolting 2 inches and smaller in diameter. The bolting sets include the number 1, and 2 seal assembly bolting The number 1 seal assembly bolting from each pump shall be visually examined in accordance with visual examination method VT-1 (see Section 11.1). The number 2 seal assembly bolting is Class 2 and does not require examination. The bolting may be examined 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 HI-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. SI-114.2

SQNP SI-114.2 Page 29 of 70 Rev. 7 The number 1, and 2 seal housing bolting includes 12 socket head cap screws at 2 inches in diameter, 12 socket head cap screws at 1 inch in diameter, respectively. 7.5.3 RCP Integrally-Welded Support 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 pump 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 che 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 remsining two pumps shall be examined during the third inspection period. 7.5.4 RCP Component Supports Each RCP includes three integrally cast / welded pump feet bolted to the support system. All component supports from each pump shall be visually examined during the inspection interval in accor' dance 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. 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 fromthe remaining two pumps shall be examined during the third inspection period. 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 HI-2.2 and provides for these visual examinations. SI-Il4.2

SQNP SI-114.2 Page 30 of 70 Rev. 7 T If during the inspection interval a pump irom 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 Flywheel 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 5 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 Bolting 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 nuts 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. SI-114.2

SQNP SI-114.2 Page 31 of 70 Rev. 7 7.6.2.1 Reactor Coolant System Valve Bolting The Reactor Coolant System includes 15 valves with bolted bonnet connections. 7.6.2.2 Chemical and Volume Control System Valve Bolting The Chemical and Volume Control System includes 3 valves with bolted bonnet connections. 7.6.2.3 Residual Heat Removal System Valve Bolting The Residual Heat Removal System includes 6 valves with boli.ed bonnet conenctions. 7.6.2.4 Safety Injection System Valve Bolting The Safety Injection System includes 19 valves with bolted bonnet connections. 7.6.2.5 Upper Head Injection System Valve Bolting The Upper Head Injection System includes 8 valves with bolted bonnet connections. 

                                                                                                           ~

7.6.3 Valve Integrally-Welded Support Members 

  ;         Examination of valve integrally-welded support members 4

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 ne valves with body welds. 7.6.6 Valve Bodies The internal surfaces of valve bodies exceeding.4-inch nominal pipe size shall be visually examined in l accordance with visual examination method VT-1 (see k- 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 valve), manufacturing method, and that are performing similar functions in the system. SI-114.2

SQNP SI-114.2 Page 32 of 70 Rev. 7 fWhen;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

i. examination of valve internal surfaces.

7.7 Exempted Components 4 Components exempted from examination include component i connections, piping, and associated valves and their support that are one inch nominal pipe size 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 1 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 t drive penetrations. 7.8 Successful Examinations Areas of flaw indications evaluated in accordance with IWB 3122.4 and TI-51 that qualify for continued service shall be reexamined during the next three inspection periods listed

in the inspection schedules. If the reexaminations reveal that the flaw indications remain essentially unchanged for three successive inspections, then the component examination schedule may revert to the original schedule. Exceptions to
;                                         this requirement may occur when the examination schedule is dictated by the augmented inspection requirements (see
Section 20.0).

I 7.9 System Pressure Tests i 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 1 accordance with SI-250. The components shall be visually examined during the pressure tests in accordance with visual examination method VT-2 (see Section 11.1). All Class A SI-114.2 , . . _ _ , . , . . . . . _ _ . _ _ _ ,.__-,,._.-m_...,._.m , . , , _ _ . , ,.m-__-, __,,mr__,,, , . . .-

SQNP SI-114.2 Page 33 of 70 Rev. 7 (ASME Class 1) System Pressure Tests 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. Components that are exempted from examination in accordance with IWC-1220 of ASME Section XI are discussed in Section 8.12 of this program. Where examinatiens specify a percentage of the total length of weld to 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 Secondary 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). The weld selected for examination shall be ultrason-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 SI-114.2

SQNP SI-114.2 Psge 34 of 70 Rev. 7 4 Ea.ch 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 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. 8.1.3 Steam Generator Secondary Side Tubesheet-To-Shell Weld Each steam generator includes a tubesheet-to-shell weld. The entire length of one tubesheet-to-shell weld shall be ultrasonically examined during the in-spection 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-508, Class 2, steel forging. 8.1.4 Steam Generator Secondary Side Nozzle-To-Vessel Welds Each steam generator includes one feedwater nozzle (3.62 inches nominal vessel thickness) and one main steam nozzle (3.62 inches nominal vessel thickness). 

         ~ All of the nozzle-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 nozzles are fabricated of SA-508, Class 2, steel. 8.1.5 Steam Generator Secondary Side Integrally-Welded Support Attachments There are no integrally welded vessel support attachments. 8.1.6 Steam Generator Secondary Side Component Supports There are no component supports (including mechanical and hydraulic supports) which are in contact with the vessel. 8.1.7 Steam Generator Secondary Side Pressure Retaining Bolting Exceeding 2 Inches in Diameter There is no steam generator secondary side bolting exceeding 2 inches in diameter. 8.2 Residual Heat Removal Heat Exchangers (2) - RHRHX SI-114.2 

                        .SQNP SI-114.2 Page 35 of 70 Rev. 7 8.2.1 RHRHX Circumferential Welds 8.2.1.1   RHRHX Shell Circumferential Weld There is one circumferential shell weld located at a gross structural discontinuity on each RHRHX. 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. 8.2.1.2 RHRHX Head Circumferential Weld There is one circumferential head-to-shell weld per RHRHX. 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 RHRHX Nozzle-to-Vessel Welds The channel cylinder section of each RHREX 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. The nozzles are fabricated from SS, SA-240, TP-304. 8.2.3 RHRHX Integrally-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 RHRHX will be liquid penetrant examined during each inspection interval in SI-114.2

SQNP SI-114.2 Page 36 of 70 Rev. 7 I accordance with 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. 8.2.4 RHRHX Component 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 examination method VT-3 (see Section 11.1). This 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. 8.2.5 RHRHX Pressure Retaining Bolting Exceeding Two Inches iniDiameter i There is not any RHRHX bolting exceeding two inches in diameter. 8.3 Regenerative Heat Exchanger (One) - RHX 8.3.1 RHX Circumferential Welds 8.3.1.1 RHX Shell Circumferential Welds l The regenerative heat exchanger is composed j 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. SI-114.2 

  ~

SQNP SI-114.2 Page 37 of 70 Rev. 7 8.3.1.2 RHX Head Circumferential Welds There are-six channel cylinder to channel head welds. Refer to Relief Request ISI-12. The channel heads are-fabricated to SS, SA-240, 304L. 8.3.1.3 RHX Tubesheet to Shell Weld There are six RHX tubesheet-to-shell welds. Refer to Relief Request ISI-12. The tubesheet is fabricated to SA-182, F304 SS. 8.3.2 RHX 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 RHX Integrally-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. Refer to Relief Request ISI-12. 8.3.4 RHX Component Supports , There are two component supports on the regenerative heat exchanger. These supports are not required to be examined in accordance with footnote 4 of r Table IWC-2500-1, Examination Category C-C and C-E. 8.3.5 RHX Pressure Retaining Bolting Exceeding Two Inches in Diameter i There is not any pressure retaining bolting associated with the heat exchanger. 8.4 Excess Letdown Heat Exchanger (One) - ELHX 8.4.1 ELHX Circumferential Welds 8.4.1.1 ELHX Shell Circumferential Welds There are not any shell circumferential welds associated with the ELHX. SI-114.2  ; 1 

                                                                       -  ._. - - - - - .          ._.__-._J

SQNP SI-114.2

Page 38 of 70 Rev. 7 8.4.1.2- 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. Refer to Relief Request ISI-12.

The channel flange and the channel head are fabricated to SA182, F316 and SA-240, TP316, respectively. 8.4.1.3 ELHX Tubesheet to Shell Weld There are not any ELHX tubesheet to shell welds. . 8.4.2 ELHX Nozzle to Vessel Welds There are not any nozzles greater than four-inch diameter. The nozzles are fabricated to SA-312, 316. 8.4.3 ELHX Integrally-Welded Supports There are no integrally-welded supports to the head side of the ELHX. 8.4.4 ELHX Component Supports There are no component supports to the head side of the ELHX. 8.4.5 ELHX Pressure Retaining Bolting Exceeding Two Inches in Diameter The channel flange bolting associated with the ELHX is less than two inches in diameter. 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. 

                                                                     ^

8.5 Boron Injection Tank (One) - BIT 8.5.1 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 accordance with Table B of Appendix A. The examination shall cover 100 percent of the weld length. SI-114.2 

          .        .                    .                 ~                         __. _ _ . _                                        _            .                    __ _                             _ _ .-     ._   _._

SQNP SI-114.2 Page 39 of 70 Rev. 7 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. 8.5.2 BIT Nozzle-to-Vessel Welds t There.are two nozzles, one located on each head with a 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, LF2. s

8.5.3 BIT Integrally-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.

4 8.5.4 BIT Component Supports - . 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.
,                                                   8.5.5                    BIT Pressure Retaining Bolting 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 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, GR2H, respectively. T i e i SI-114.2 i 

   -.   ,   _ _ ~ . . . , . - _ , _ . _ . . _ , , _ , _ . _ _ - . . . . . - . . . _ . _ . . . - . _ . _ _ , . , _ - _ _ . _ _ _ _ _ _ _ . _ _ . . . _ _ _ . _ _ _ _ _ _ . , _ _ , _ _ _ _ _ _ _ . . _ _ _

SQNP SI-114.2 Page 40 of 70 Rev. 7 8.6 UHI Water Accumulator (One) WA 8.6.1 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. 8.6.2 WA Nozzle-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. The nozzles are fabricated to SA-350, LF2. 8.6.3 WA Integrally-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. The integrally welded portion of the support skirt is fabricated to SA-516, GR70. 8.6.4 WA Component Support The water. accumulator has a component support skirt 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. 1 SI-114.2

SQNP SI-114.2 Page 41 of 70 Rev. 7 8.6.5 WA Pressure Retaining Bolting Exceeding Two Inches in Diameter There are two manway covers with 16 manway cover studs each at 2-1/2 inches in diameter. Both manway covers 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. 8.7 UNI Surge Tank (One) - ST 8.7.1 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. 8.7.2 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 SA-182, F304. 8.7.3 ST Integrally-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. 8.7.4 ST Component Supports 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. SI-114.2

SQNP SI-114.2 Page 42 of 70 Rev. 7 8.7.5 ST Pressure Retaining Bolting Exceeding 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. 8.8 Piping Material specifications for each piping system are included in weld map isometrics 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 8.8.1 Piping and Valve Integrally-Welded Supports Integrally-welded supports include the support attach-ments of piping required to be examined by 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. 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. 8.8.1.1 Residual Heat Removal System Piping and Valve Integrally-Welded Supports The Residual Heat Removal System piping does not include any integrally-welded supports. SI-114.2

SQNP SI-114.2 Page 43 of 70 l Rev. 7 { 8.8.1.2 Safety Injection System Piping and Valve Integrally-Welded Supports The Safety Injection System piping includes 4 integrally-welded supports. All of these shall be examined during the inspection interval. 8.8.1.3 Main Steam System Piping and Valve Integrally Welded Supports The Main Steam System piping includes 12 integrally-welded supports. All of these shall be examined during the inspection interval. 8.8.1.4 Feedwater System Piping and Valve Integrally-Welded Supports 

                            ,The Feedwater System piping includes 5 integrally-welded supports. All of these shall be examined during the inspection interval.

8.8.1.5 Containment Spray System Piping and Valve Integrally-Welded Supports Th'e Containment Spray System piping does not include any integrally-welded supports. t 

 '            8.8.1.6        Upper Head Injection System Piping and Valve Integrally-Welded Supports The upper head injection system piping includes 4 integrally-welded supports. All of these shall be examined during the inspection interval.

8.8.2 Piping and Valve Component 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 ine.ludes integrally-welded and nonintegrally-welded component supports. Component supports extend from the piping and valves to and including the attachment to the supporting structure.

SI-114.2

SQNP SI-114.2 Page 44 of 70 Rev. 7 The setting of snubbers, shock absorbers and spring-type hangers shall be verified in accordance with the acceptance criteria shown in Appendix G or the applicable work instruction. The setting of snubbers and shock absorbers is performed in accordance with the SI-162.2 and MI 6.13 series. The examinations shall be distributed during the inspection interval in accordance with Table B of Appendix A. 8.8.2.1 Residual Heat Removal System Piping and Valve Component Supports The Residual Heat Removal System piping includes 83 component supports. _All of these shall be examined during the inspection interval. 8.8.2.2 Safety Injection System Piping and Valve Component Supports The Safety Injection System piping includes 57 component supports. All of these shall be examined during the inspection interval. 8.8.2.3 Main Steam System Piping and Valve Component Supports The Main Steam System piping includes 62 component supports. All of these shall be examined during the inspection interval. 8.8.2.4 Feedwater System Piping and Valve Component Supports The Feedwater System piping includes 30 component supports. All of these shall be examined during the inspection interval. 8.8.2.5 Containment 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. 8.8.2.6 Upper Head Injection System Piping and Valve Componeut Supports The upper head injection system piping includes 7 component supports. All of these shall be examined during the inspection interval. SI-114.2

t , SQNP SI-114.2 Page 45 of 70 Rev. 7' 8.8.3 Pressure-Retaining Bolting There is no Class B Pressure-Retaining Bolting larger 

                                                 - than two inches in diameter.

8.8.4 Circumferential and Longitudinal Pipe Welds 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 i sample shall be examined during the inspection interval. The examinations 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 wall thickness greater than 1/2 inch shall be ultrasonically and surfaced examined. The areas 

                                                 - subject to examination include circumferential pipe

', welds, at structural discontinuities within 3 pipe diameters of the centerline of rigid pipe anchors, i anchors at the penetration of primary containment or at rigidly anchored components, and longitudinal weld joints in pipe fittings . 3 8.8.4.1 Residual Heat Removal Piping The Residual Heat Removal Piping System includes 24 Class B circumferential and 5 Class B longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to examination. There are 105 circumferential and 28 longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less subject to examination. Six circumferential and one longitudinal piping weld with a nominal wall thickness greater than 1/2 in~ch shall be ultrasonically and surfaced examined each inspection interval. There are 26 circumfetential and 7 longitudinal pipe welds with a nominal wall thickness of i 1/2 inch or less that shall be surface examined 1- each inspection interval. See Table B of Appendix A for scheduled inspections. 4 SI-114.2 

           +e   i. ,. -- .y--- ,y-,   _-n-,-m--.      ,.e-   . - . -
                                                                     ,m,--,,            -   -      ,_,-._.-.c-
                                                                                                           --  . _ - - - - - - , - - - .       . . - - - - . - , , - , . . ,---.,.y..   -

  . .                       .     =  .-

SQNP SI-114.2 Page 46 of 70 Rev. 7 8.8.4.2 -Safety Injection Piping 

+

The Safety Injection Piping System includes 35 Class B circumferential and no Class B longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to examination.~ There are 40 circumferential and 15 longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less subject to examination. Nine circumferential piping welds with a' nominal wall thickness greater than 1/2 inch shall be ultrasonically and surface examined each inspection interval. There are 10 circumferential and 5 longi-tudinal pipe welds with a nominal wall thickness of 1/2 inch or less that shall be , surfaced examined each inspection interval. See Table B of Appendix A for schedule inspections. 8.8.4.3 Main Steam Piping The Main Steam Piping System includes 24 Class B circumferential and 5 Class B longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to examination. The piping size is 32" 0.D. x 1.088 wall unless noted. Six circumferential and one 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. 8.8.4.4 Feedwater Piping The Feedwater Piping System includes 17 Class B

circumferential welds and 1 longitudinal weld l with a nominal wall 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 4 circumferential and the one longitudinal piping welds that shall be ultrasonically and surfaced examined each inspection interval. See Table B of

, Appendix A for scheduled inspections. i SI-114.2 1 l

SQNP SI-114.2 Page 47 of 70 Rev. 7 8.8.4.5 Containment Spray Piping The Containment Spray Piping System includes 6 circumferential and 2 longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less, subject.to examination. One circumferential and I longitudinal 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. 8.8.4.6 Upper Head Injection Piping The upper head injection piping system includes 26 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. 8.8.5 Branch Piping Connection Welds There are no Class B Branch Pipe Connection Welds. 8.9 Punps 8.9.1 Residual Heat Removal Pumps (2) - RHRP 8.9.1.1 RHRP Integrally-Welded Supports There are no integrally-welded supports , associated with the RRRP. 8.9.1.2 RHRP Support Components Each RHRP includes 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 Section 11.1). Support components extend from the RHRP to and including the attachment to the supporting structure. SI-114.2

SQNP SI-114.2 Page 48 of 70 Rev. 7 The supports from one RHRP shall be examined during the first inspection period. The supports from the remaining RHRP shall be examined during the third inspection period. 8.9.1.3 RHRP Supports - Mechanical and Hvdraulic There are no mechanical and hydraulic supports associated with the RHRP. 8.9.1.4 RHRP Pressure Retaining 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. 8.9.1.5 RHRP Casing Welds The RHRP does not include any casing welds. The casing is a one piece forging fabricated to SA-182, F304. . 8.9.2 CVCS Centrifugal Charging Pumps (2) CCP I 

                   ' 8.9.2.1       CCP-Component Supports and Casing Welds The CCP is not in a piping run examined under Examination Category C-F therefore the                       ,

component supports and casing welds are not required to be examined except fer system - pressure tests. 8.9.2.2 CCP Pressure Retaining Bolting There is no CCP bolting greater than two l inches in diameter. i I ( SI-114.2 l

SQNP SI-114.2 Page 49 of 70 Rev. 7 8.9.3 CVCS Positive Displacement Pump (1) PDP/ Reciprocating Charging Pump 8.9.3.1 PDP Component Supports The PDP is not in a piping run examined under Examination Category C-F therefore, the component supports are not required to be examined. 8.9.3.2 PDP Pressure Retaining Bolting The cylinder tie, cylinder head and valve cover, and the stuffing box flange bolting connections are not greater than 2 inches in diameter. The connection includes 8 studs at 1-1/8" in diameter with nuts and washers for the cylinder ties; 40 cylinder head and valve cover studs at Ik" in diameter with nuts and washers; and 20 studs at Ik" in diameter with nuts and washers for the stuffing box flange. The studs are fabricated to SA-193 GRB7 and the nuts to SA-194, GR7. 8.9.3.3 PDP Casing Welds The PDP casing does not include any casing welds. The casing is fabricated to SA-182 F304, SA-204 Type 304, SA-479 T304, and SA-479, 410. 8.9.4 Safety Injection Pumps (2)-SIP 8.9.4.1 SIP Component Supports The SIP is not in a piping run examined under Examination Category C-F therefore, the component supports are not required to be examined. 8.9.4.2 SIP Pressure Retaining Bolting The SIP case capnuts are not greater than 2 inches in diameter. The casing bolting includes 32 studs at 2 inches in diameter with nuts and washers and 10 studs at 1 inches in diameter with nuts and washers. The studs are fabricated to SA-193, GRB7 and the nuts to SA-194, GR7. SI-114.2 

                               -SQNP SI-114.2 Page_50 of_70 Rev. 7 8.9.4.3    SIP Casing Welds
                        +
                          'The SIP casing does not include any casing welds. The casing consists of upper and lower housing ~ fabricated to A351 GF8.

8.10 Valves-8.10.1 Valve Integrally-Welded Supports Examination of valve integrally-welde'd support members is included in Section 8.3.3. 8.10.2 Valve Component Supports Examination of valve component supports is included in Section 8.3.4. 8.10.3 Valve Pressure-Retaining Bolting There is no Class B pressure-retaining bolting greater than 2 inches in diameter. 8.10.4 Valve Body Welds There are no Class B valves with body welds. 8.11 Pressure Retaining Components All Class B pressure retaining components in systems or i portions of systems which are not required to operate during normal reactor operation but for which periodic system or component functional tests are required (excluding open-ended portions of systems), shall be subjected to a system functional leakage test with each inspection period in accordance with IWC-5221 of ASME Section XI. This is performed in accordance with the SI-267 series. 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 hydrostatic test with each inspection interval in accordance with IWC-5222 of ASME Section XI. This is performed in accordance with the SI-265 series. The components shall be visually examined during the pressure tests in accordance with visual examination nethod VT-2 (see Section 11.1). All Class B (ASME Class 2) system pressure tests shall be performed in accordance with DPM SEQ 82El. SI-114.2

SQNP SI-114.2 Page 51 of 70 Rev. 7 8.12 Exempted Components 

                                         .8.12.1- Exempted Components (Except Piping 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) co.3ponents 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 vessels (and their supports), that are 4-inch nominal pipe size and smaller. , 8.12.2 Exempted Components (Piping Welds Only) Piping exempted from examination include: (a) Piping systems where both the design pressure and temperature are equal to or less than 275 psig and 200*F, 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 nominal pipe size and smaller; (d) components which 

,                                                     perform an emergency core cooling function provided 4

the control of the chemistry of the contained fluid is verified by periodic sampling and test.

8.13 Successive Examinations .

Components with flaw indications evaluated in accordance with IWC-3000 and TI-51 that qualify for continued service i shall be reexamined during the next inspection period l listed in the inspection schedule. If the reexamination reveals that the flaw indications remain essentially

unchanged, the component examination schedule may revert j to the original schedule. Exceptions to this requirement
may occur when the examination schedule is dictated by the augmented inspection requirements (see Section 20.07).

9.0 COMPONENTS SUBJECT TO EXAMINATION - TVA SAFETY CLASS C AND D Class C and D (ASME Class 3) pressure retaining components iden-tified in sections 9.1.1 and 9.1.2 shall be visually examined, VT-2, in conjunction with the system pressure test in accordance with IWA-5000, IWD-2000, and IWD-5000. SI-114.2 4 

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SQNP SI-114.2 Pzge 52 of 70 Rev. 7 The component supports and restraints within the boundaries identified in sections 9.1.1 and 9.1.2 for components exceeding 4-inch nominal pipe size shall be visually examined, VT-3, during each inspection period. Mechanical and hydraulic snubbers, spring loaded and constant weight supports within the boundaries identified in sections 9.1.1 and 9.1.2 for components exceeding 4-inch nominal pipe size shall 

 , be visually examined, VT-4, during each inspection period.

9.0.1 Piping and Valve Component Supports All piping and valve component supports shall be visually examined during each inspection period 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. The setting of snubbers, shock absorbers and spring-type hangers shall be verified in accordance with the acceptance criteria shown in Appendix G or applicable work instruction. The examinations (100%) shall be conducted during each inspection period during the inspection interval in accordance with Table C of Appendix A. 9.0.1.1 Auxiliary Feedwater System Piping and Valve Component Supports The auxiliary feedwater system piping includes 45 component supports. All of these shall be examined during each inspection period. 9.0.1.2 Chemical and Volume Control System Piping and Valve Component Supports The chemical and volume system piping includes 7 component supports. All of these shall be examined during each inspection period. 9.0.1.3 Component Cooling System Piping and Valve Component Supports The component cooling system piping includes 208 component supports. All of these shall be examined during each inspection period. 9.0.3.4 Containment Spray System Piping and Valve Component Supports The containment spray system piping including 26 component supports. All of these shall be examined during each inspection period. SI-114.2

SQNP SI-114.2 Page 53 of 70 Rev. 7 9.0.1.5 Essential Raw Cooling Water System Piping and Valve Component Supports The essential raw cooling' water system piping includes 222 component supports. All of these shall be examined during each inspection period. 9.0.1.6 Fuel Pool Cooling System Piping and Valve Component Supports The fuel pool cooling system component supports are examined in accordance with SI-114.1, Unit 1 program. 9.0.1.7 Residual Heat Removal System Piping and Valve Component Supports The residual' heat removal system piping includes seven component supports. All of these shall be examined during each inspection period. 9.0.1.8 Safety Injection System Piping and Valve Component Supports The safety injection system piping includes 28 component supports. All of these shall be examined during each inspection period. 9.1 System Pressure Tests All Class C and D (ASME Class 3) system pressure tests shall be performed in accordance with DPM SEQ 82E1. 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 accordance with IWD-5221 of ASME Section XI. This shall be performed in accordance with SI-267 series. These examinations and tests shall be performed during

each inspection period.

SI-114.2

SQNP SI-114.2 Page 54 of 70 Rev. 7 9.1.2 System Functional Tests Pressure ret'aining 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. This shall be performed in accordance with SI-267 series. 9.1.3 System Hydrostatic Tests 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) during a system hydrostatic test conducted in accordance with IWD-5223 of ASME Section XI. These examinations and tests shall be performed over each inspection interval. This shall be performed in accordance with SI-265 series. 9.2 Component Supports 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 11.1.) 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 IWA-2140 of ASME Section XI. SI-114.2

SQNP SI-114.2 Page 55 of 70 Rev. 7 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, and MI 6.21. 11.0 EXAMINATION METHODS 11.1 Visual Examination Visual examinations that require-clean surfaces or decontamination for valid interpretation of results shall. be preceded by appropriate cleaning processes. 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. 11.'1.1.1 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 used to. improve the angle of vision. Lighting, natural or artifi-t cial shall be sufficient to resolve a 4 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 attainable by direct visual examination. 11.1.2 Visual Examination VT-2 The VT-2 visual examination shall be conducted to locate evidence of leakage from pressure retaining components, or abnormal leakage from components with or without leakage collection systems as required during the conduct of system pressure or functional test. SI-114.2

SQNP-SI-114.2 Page 56 of 70 Rev. 7 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 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 examination, 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. 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. i VT-2 visual examination shall be conducted in accordance with ASME Section XI, IWA-5240, and TI-51. 11.1.3 Visual Examination VT-3 The VT-3 visual examination shall be conducted to i 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 4 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. l SI-114.2 

        ^

SQNP 

   ,                                                    SI-114.2 Page 57 of 70
     'a                                                 Rev. 7 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, 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 11.2.1 Magnetic Particle Examination Magnetic particle examination (MT) shall be conducted in accordance with Article 7, Section V of the ASME Code. 11.2.2 Liquid 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 Radiographic Examination 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. For 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. i 11.3.2 Ultrasonic Examination (a) Ultrasonic examination of Class 1 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 ASME Code, and TI-51. SI-114.2 

          .  .__ -.     ._   _          .-  - - _ _ ~        ..       ..

P SQNP SI-114.2 Page 58 of 70 Rev. 7 (b) Ultrasonic examination of Class 1 and Class 2 ferritic steel piping systems shall be conducted in accordance with Appendix III, amended as follows: (1) For examination of. welds, reflectors _that 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) 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 NONDESTRUCTIVE EXAMINATION PCRS01TEL Personnel performing nondestructive examinti.or. . ocations shall be qualified in accordance with IWA-2300 of ASME 'Section XI as required in program procedure 0202.14 (Formerly 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, cxcept where ASME Section III examinations are employed to satisfy ASME Section XI requirements. SI-114.2 l

SQNP l- SI-114.2 ! Page 59 of 70 Rev. 7 14.0 REPAIRS 

                              'All ASME Section XI components and their supports (ASME Classes 1, 2, and 3) shall be repaired in accordance with the Repair and                  l Replacement Program included in NQAM Part II, Section 2.3 and implemented by PMP 1402.02 (SQNP), and MI-6.21.
              'i 15.0 REPI.ACEMENTS
                   ^
                              ' Replacements of ASME Section XI components (ASME Classes 1, 2, and 3) shall be in accordance with the Repair and Replacement Program in NQAM Part II, Section 2.3 and implemented by PMP 1402.02 (SQNP), MI-6.21.

ASME Section XI repairs and replacements may be coordinated as necessary with the' Applications Engineering Group of the Mechanical Services Branch. 16.0 -RECORDS AND REPORTS 16.1 Recording of and Report of Examinations A detailed report of all examinations shall be prepared by the performing or responsible organization and should g 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. SI-114.2

SQNP SI-114.2 Page 60 of 70 Rev. 7 IV. Evaluation - Evaluation is based on the indication's locaticn, metal path, general shape, and any tests that could be applied, such as damping. The evaluation section also should contain a listing of each examination performed and the evaluated results. 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. 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 Size 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 a.re isometric drawings showing the location of both field and shop welds on each vessel, component, and piping system subject to e examination. The support drawings are also iso-4 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 XIII. Calibration Sheets XIV. Examination Reports - Reports for inservice inspection shall be prepared in accordance with IWA-6220 of ASME Section XI. SI-114.2

SQNP SI-114.2 Pagn 61 of 70 Rev. 7 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. 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 NDE Inspection Section shall review and submit the final report to the Plant Superintendent 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 Repairs and Replacements Summary Reports shall be prepared in accordance with HI-6.2 1. SI-114.2

SQNP SI-114.2 Page 62 of 70 Rev. 7 16.2 ISI Report for Class A and B Components The NDE Engineering 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. 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) Commercial 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 components 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. (3) Name of the manufacturer of the components or parts for which this is a record, including the manufacturer'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) of the Inspector (s). (7) Abstract of examination performed, conditions observed, corrective measures recommended and taken. SI-114.2

SQNP SI-114.2 Page 63 of 70 Rev. 7-(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. 16.3 Records for Class A, B, C, and D Components The following records shall be available for review: (1) Examination 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 Augmented 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 (excluding VT-2, visual examinations performed during system pressure tests). Unacceptable indi-cations are defined by the applicable NDE procedure. Formal notification shall consist of completing and submitting to the Plant Manager the " Notification of Indication" form in Appendix D of this program. Part I of the " Notification of Indication" shall be completed and signed by the NDE Level II or III examiner detecting the indication. The NDE Inspection Section representative shall assign a sequential number and review and sign the form. If the indication is detected by an outside contractor, the contractor's field supervisor shall review and sign the form. The original shall be sent to the plant manager or his designee and a copy to the ISI Programs Section. SI-114.2

SQNP SI-114.2 Page 64 of 70 Rev. 7 The plant manager or his assistant shall designate the organiza-tion.(Construction Modifications, Plant Maintenance), responsible for preparing a disposition in Part II of the form and performing the associated corrective action. If the organization assigned responsibility for dispostion is unable to determine a satisfactory disposition then the form should be sent to the Mechanical Services Branch for disposition. The individual responsible for preparation of the disposition shall sign and date Part II of the form. The cognizant supervisor of the appropriate organization shall review and approve the disposition and sign and date Part II of the form. Copies of the form shall be distributed to the I plant superintendent and the ISI Programs Section. The original shall be returned to the NDE Inspection Section Representative. One copy shall be filed with the examination report. If the organization assigned responsibility for repair is within NUC PR, they shall determine if the unacceptable condition is significant and potentially reportable in accordance with the requirements of NQAM, Part III, Section 7.2, and AI-12. Dispositions to correct the condition under the plant maintenance program shall be processed in accordance with NQAM, Part II, Section 2.1 (SQM 2). Dispositions other than restoring to original requirements shall be processed as modifications in accordance with NQAM, Part II, Section 3.0 (AI-19). Repair and replacement, activities, including coordination with the Authorized Inspection Agency (AIA), shall be performed in accordance with the requirements of NQAM, Part II, Section 2.3 MI-6.21). Dispositions to accept the condition as-is shall include in Part II of the form the basis for the disposition. In addition for dispositions to accept the condition as-is, a USQD shall'be prepared by the appropriate organization in accordance with established procedures. The organization responsible for corrective action shall include preservice examination requirements in the repair or replacement work instruction described in NQAM, Part II, Section 2.3 (MI 6.21. Upon completion of corrective action the NDE Inspection Section Representative shall verify completion of corrective action, enter the work instruction and/or DCR numbers on the Notification of Indication form, enter the examination report number if re-examination was performed, and sign and date the form, Part III. The signed form shall remain with the examination report for use as a quality assurance record. If re-examination was performed, a copy of the signed form shall also remain with the re-examination report. Copies of the form shall also be distributed to the plant superintendent and the ISI Programs Section. 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/or ASME Section XI as applicable. The blocks shall be fabricated of the material to be examined or equivalent P numbers. The blocks shall employ drilled holes and/or notches for calibration reflectors (See Request for Relief ISI-2). SI-114.2

SQNP SI-114.2 Page 65 of 70 Rev. 7 The as-built calibration block drawings and mill test reports or certificates of compliance shall be controlled and distributed by the Document Control Center. The calibration blocks shall be stored at the plant site and maintained by the NDE-Inspection Section. 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. 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 or written) to the NRC shall be the responsibility of the organiza-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 exam shall state the. required reporting time and the document requiring the information to be included in the report. 20.1 Feedwater System Piping and Supports The requirements of NRC-IE Bulletin 79-13 were satisfied during the unit 2, cycle 1 outage. Due to the safety-related ramifications of the steam generator nozzle transition section cracking problem, TVA will perform an augmented inspection (reference memorandum L29 831222 836) of one feedwater nozzle during each refueling outage on a rotating basis. The augmented examination of the steam generator nozzle transition section shall include nozzle-to-transition piece welds and transition piece-to pipe welds. These welds shall be ultrasonically examined and ultrasonic sensitivities should be equivalent to those required by NRC-IE Bulletin 83-02. The examination data sheets shall be included in the 90 day ISI report discussed in section 16.2 of this program. SI-114.2 

                                                                                                                        }

SQNP , SI-114.2 4 Page 66 of 70 Rev. 7 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 reinspected nozzles 2RC-17SE and 2RC-24SE at the first regularly scheduled cold shutdown 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 Flywheel The augmented examination requirements of the reactor 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 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 surfaces and complete ultrasonic examination at approximately 4 10-year intervals during the plant shutdown coinciding with the inservice inspection schedule as required by Section XI of the ASME Code. 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 NRC 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 i each inservice inspec tion of steam generator tubes, the l 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 Commission Region II Office within the time period specified. See plant instruction AI-18 for reporting instructions.

I i SI-114.2 l

SQNP SI-114.2 Page 67 of 70 Rev. 7 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 Specification 6.9.2 within 12 months following completion of the inspection. The Site Codes & Standards Section 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 notification of the Nuclear Regulatory Commission pursuant to Techni. cal Specification 6.9.1 prior to resumption of plant operation. The written followup of this report shall provide a description 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 section 16.2 of this program. Nozzle forging material and cladding is identified in section 7.1.2 of this program. 20.6 Steam Generator Feedring J-Tubes Due to the potential of a loose part (J-Tube) in the secondary side of the steam generators the following J-Tube , augmented examination plan shall be initiated. SI-114.2

, SQNP SI-114.2 Page 68 of 70 Rev. 7 At refueling outages, less than 920 EFPD, all J-Tubes in one steam generator must be ultrasonically examined for wall thickness in the area above the weld joining the J-Tube to the feedring. This inspection plan would provide wall thick-ness data on two steam generators per year, one per unit. 1 For operating periods greater than 920 EFPD, all J-Tubes should be ultrasonically examined on two steam generators. The probability of J-Tube thinning increases significantly after 920 EFPD of operation. If J-Tube thinning greater than 40 percent is detected during an examination, all J-Tubes in all steam generators must be F ultrasonically examined. This examination plan as outlined shall be adequate to detect J-Tube degradation and provide a planned J-Tube maintenance program. This augmented examina-tion is self imposed by TVA (L29 840109 859) and does not require a report. The examination data sheets shall be included in the 90 day ISI Report discussed in section 16.2 of this program. 20.7 Control Rod Guide Tube Flexures Due to the potential of intergranular stress corrosion cracking of guide tube flexures, the following control rod l- guide tube flexure augmented examination plan shall be 

!           initiated.

4 The control rod guide tube flexures shall be visually examined in accordance with visual examination method VT-3 I (see section 11.1) during each refueling outage. These examinations shall be performed in accordance with SMI-0-68-15. At each scheduled refueling outage the tops of all flexures are in their proper orientation. If any flexure heads are discovered to be broken from their stems, the heads should be retrieved and flexureless inserts installed. If flexureless inserts are not installed, a safety evaluation will be required to confirm continued safe plant operation. A copy of the required to confirm continued safe plant operation. A copy of the VT data sheets shall be forwarded to the appropriate cognizant engineer in the Mechanical Maintenance Section for enclosure in SMI-0-68-15. This augmented examination is self imposed by TVA and does

. not require a report. The examination data sheets shall be included in the 90-day ISI report discussed in section 16.2 of this program.
Any revisions or waivers of this examination plan shall be

{ initiated by the Mechanical Maintenance Supervisor. SI-114.2 i 

  - -           . , . _ , . . . . . _ _ _ . , .                ._.,_,_m._       _ _ - . _ _ . . - ,    _ _ _   _ _ , , _ , _ - _ , . . , , - . _   _ , . , . .

SQNP SI-114.2 Paga 69 of 70 Rev. 7 20.8 Rod Cluster Control Assembly (RCCA) Cladding Wear Examine (VT-3) a random sample of RCCAs during the unit 2, cycle 10 refueling outage. The sample should include those RCCAs which have resided in control banks the longest period. The examination should concentrate on the portion of the cladding surface facing the center or hub of the RCCA. The type of wear patterns observed at other utilities include (1) axially continuous wear scar on the rodlet of varying depth probably caused by RCCA axial stepping motion and scrams (2) approximately one-inch long score marks at elevations corresponding to the guide plate surfaces. This examination is TVA imposed (L22 840502 803) and does not 

    -require a special report. The examination data summary shall be included in the 90-day ISI report discussed in section 16.2 of this program.

9 SI-114.2

SQNP SI-114.2 Page 70 of 70 Rev. 7

21.0 REFERENCES

21.1 ASME Boiler and Pressure Vessel Code - Section XI, 1974 Edition, Summer 1975 addenda, 1977 Edition, Summer 1978 addenda. 21.2 ASME Boiler.and Pressure Vessel Code - Section V. 21.3 Instruction Manual - 173-inch I.D. Reactor Pressure Vessel -Rotterdam Dockyard Company, Contract No. 68C60-91934, N2M-2-3. 21.4 Sequoyah Nuclear Plant Standard Practice SQ1. 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 Westinghouse Technical Manual - Vertical Steam Generators, TM 1440-C224, Contract No. 68C31-91934, N2M-2-4. 21.8 Westinghouse Instruction Manual - Auxiliary Heat Exchangers, Contract No. 68C60-91934, N2M-2-25. 21.9 Westinghouse Instruction Book - Reactor Coolant Pump, Contract No. 68C60-91934, N2M-2-5. 21.10 'Ingersoll-Rand Instruction Manual - Residual Heat Removal Pumps, Contract No. 68C60-91934, N2M-2-30. 21.11 Nuclear Quality Assurance Manual, Part II, Sections 2.3, 3.0, 5.1, and 6.3. 21.12 Sequoyah Nuclear Plant Technical Instruction.TI-51. 21.13 Sequoyah Nuclear Plant Technical Specifications Unit 2. 21.14 Division Procedures Manual: N75C01, N76A10, N80E3, SEQ 80M7, SEQ 82El, and SQ82M1. 21.15 Memorandum from D. W. Wilson to H. L. Abercrombie dated August 01, 1986, "Sequoyah Nuclear Plant Units 1 and 2 indications in class 1 welds" (L18860730899) SI-114.2

SQNP SI-114.2 Page 1 of 1 Rev. 7 APPENDIX A TABLE 1 Minimum Number of Steam Generators To Be Inspected During Inservice Inspection Only No. of Steam Generators per Unit Four First Inservice Inspection Two Second and Subsequent Inservice Inspections Onel Table Notation:

1. Each of the other two steam generators not inspected during the first inservice inspections shall be inspected during the second and third inspections.

The maximum allowable time between eddy-current inspections of an individual steam generator should not extend beyond , 72 months (TVA commitment to NRC L44 850617 801). 5 SI-114.2

SQNP SI-Il4.2 Page I of 1 Rev. 7 APPENDIX A TABLE 2 Steam Generator Tube Inspection First Sample Inspection Second Sample Inspection Third Sample Inspection Sample Size Result Action Required Result Action Required Result Action Required A minimum of S C-1 None N/A N/A N/A N/A tubes per S.G. C-2 Plug defective C-1 None N/A N/A tubes and inspect Plug defective tubes C-1 None additional 2S 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 of first sample N/A N/A j, C-3 Inspect all tubes All other g) this S.G., plug S.G..s are None N/A N/A defective tubes C-1 and inspect 2S Some S.G.s tubes in each C-2 but no Perform action for N/A N/A other S.G. additional C-2 result of S.G. are second sample Prompt notification C-3 to NRC pursuant to Additional Inspect all tubes specification 6.9.1. S.G. is C-3 in each S.G. and N/A N/A plug defective tubes. Prompt notification to NRC pursuant to specification 6.9.1. S = 12% 

         - k 'here n is the number of steam generators inspected during an inspection.

SI-Il4.2

SQNP SI-114.2 Page 1 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method 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 UT B-A 4/50 ft. 4/50 ft. 0 -0 4 Clel-2343-B
2. Closure llead Cire Weld 7.1.1.3 UT B-A 41 ft. 41 ft. 13 ft. 14 ft. 14 ft. CifM-2358-A O 3. Lower llead Y Cire Weld 7.1.1.4 UT B-A 38 ft. 38 ft. 0 0 38 ft. CHM-2343-B
4. Lower llead fleridional Welds 7.1.1.6 UT B-A 6 6 0 0 6 CIDI-2343-B
5. Shell-to-Flange Veld 7.1.1.7 UT B-A 50 ft. 50 ft. O ft. O ft. 50 ft. Ciel-2343-B
6. Closure Ilead-to-Flange Weld 7.1.1.8 UT B-A 45 ft. 45 ft. 15 ft. 15 ft. 15 ft. CHH-2358-A
7. Nozzle-to Vessel Welds 7.1.2 UT B-D 8 8 4 0 4 CIRI-2343-B CIRI-2333-B CHH-2360-A
8. Inside Radius Sections 7.1.3 UT B-D 8 8 4 0 4 CHH-2361-A IS1-0008-B SI-114.2

SQNP SI-114.2 Page 2 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval . Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. A. Reactor Vessel (Continued)

9. Vessel Pene-trations and CHM-2051-C Attachments 7.1.4 VT-2 B-E 141 37 12 12 13 MSG-0004-C i
10. Nozzle-to-Safe CHM-2333-B End Welds 7.1.5 UT,PT B-F 8 8 4 0 4 ISI-0008-B b 11. Closure Studs 7 and Nuts 7.1.6 UT,HT B-G-1 54 54 18 18 18 Clet-2341-B
12. Ligaments Between Threaded Stud IIoles 7.1.6 UT B-G-1 54 54 18 18 18 Cle!-2341-B
13. Closure Washers 7.1.6 VT-1 B-G-1 54 54 18 18 18 CIRI-2341-B
14. Vessel Interior 7.1.9 VT-3 B-N-1 1 ,1 1 1 1
15. Removal Core Support Structure 7.1.10- VT-3 B-N-3 See Program Section 7.1.10 ,
16. Control Rod ISI-0097-C Drive llousings 7.1.11 UT B-0 20 2 0 1 1 CHM-2359-A SI-114.2

SQNP 

                                                                    '11-114.2 1 ge 3 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program          Section XI 40 Yr. Sample 1st Insp. Interval Reference   Exam       Exam       No. Length         No. Length       Inspection Periods

Reference:

Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. A. Reactor Vessel (Continued)

17. Auxiliary liead 7.1.12 LTT, PT B-F 4 4 1 1 2 CHM-2337-C ISI-0097-C ISI-0001-C ISI-0014-A B. Pressurizer h' 1. Circumferential Shell-to-liead Welds 7.2.1 UT B-B 2/24 ft. 2/24 ft. 12 ft. 12 ft. 24 ft. CHM-2363-A
2. Longitudinal Shell-to-Head Welds 7.2.2 UT B-B 2/1 ft. 2/1 ft. 1* 1*- 1* CHM-2363-A
3. Nozzle-to-Vessel and Inside Radius Section 7.2.4 UT B-D 6 6 2 2 2 CHM-2363-A
4. Ileater Penetrations 7.2.5 VT-2 B-E 78 20 6 7 7 MSG-0006-A
           *The longitudinal weld selected for examination is that weld intersecting the circumferential shell-to-head weld examined.

SI-114.2~

SQNP-SI-ll4.2 Page 4 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH_ INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS 2 Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. B. Pressurizer (Continued)

5. Nozzle-to-Safe End Welds 7.2.6 UT, PT B-F 6 6 2 2 2 CHM-2363-A
6. Pressure Retain-ing Bolting 7.2.8 VT-1 B-G-2 1 mwy/16 bolts 16 bolts 16 0 0 L 7. Integrally i' Welded Vessel Supports 7.2.9 MT B-H 23 ft. 23 ft. 7 ft. 8 ft. 8 ft. CHM-2362-A C. Steam Generators
1. Primary Head- ,

to-Tube Sheet Weld 7.3.2 UT B-B 4/36-ft. 4/36 ft. I 1 2 CHM-2345-B-

2. Primary Nozzle-to-Vessel and Inside Radius Section 7.3.3 See Program Section 7.3.3 (Request for Relief ISI-6)
3. Primary Nozzle-to-Safe End Welds 7.3.4 UT, PT B-F 8 8 2 3 3 CHM-2333-B CHM-2345-B ISI-0008-B S I- I l4'. 2

SQNP SI-Il4.2 Page 5 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS 

                                                 ~

Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category We,lds/of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. C. Steam Generators

4. Pressure Retaining Bolting 7.3.6 VT-1 B-G-2 4 gens./2 mwy 8 mwy 2 2 4 MSG-0002-B-
5. Tubing 7.3.8 ET B-Q 4 gens./3% 4 gens./3% 2 1 l 76M1 D. Pressure Retaining

, Bolting D

l. heactor Coolant System 7.4.3.1 VT-1 B-G-2 13 Sets 13 Sets 3 5 5 ISI-0013-C
2. Chemical and .

Volume Control System (SWI) 7.4.3.2 VT-1 B-G-2 4 Sets /4 Bolts 4 Sets 1 1 2 MSG-0008-C

3. Residual lleat Removal System 7.4.3.3 VT-1 B-G-2 N/A See Program Section 7.4.3.3
4. Safety injection System 7.4.3.4 VT-1 B-G-2 4 Sets /4 Bolts 4 Sets 1 1 2 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 SI-Il4.2
                                                                                                                                =

l l SQNP.- SI-114.2

  • Page 6 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAN CLASS A COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods -_ Reference Component Section Method Category Welds /of Weld Welds /of Weld 3-yrs. 7 yrs. 10 yrs.. Dwg. No.

E. Piping

1. Circumferential Welds A. Reactor Coolant ,

4 System 

 ?            Main Loops Cires 14"   7.4.4.1   UT/PT  B-J         62                16            5       5       6        ISI-0008-B B. Reactor Coolant System Cires 14" Nom. Size   7.4.4.2   UT/PT  B-J         62                15            5       5       5        ISI-0013-C Cires <4" Nom. Size   7.4.4.2   PT     B-J         101              25             8       8       9        ISI-0013-C C. Chemical and Volume Control System Circs >4" Nom. Size   7.4.4.3   N/A ISI-0009-C Cires <4" Nom. Size   7.4.4.3   PT     B-J         54                14            4       5       5        ISI-0009-C SI-Il4.2

                                                            .         SQNP SI-Il6.2 Page 7 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAll INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program            Section XI 40 Yr. Sample 1st Insp. Interval Reference   Exam        Exam         No. Length        No. Length      Inspection Periods      Reference Component       Section  !!ethod    Category     Welds /of Weld     Welds /of Weld  3 yrs. 7 yrs. 10 yrs. Dwg. No.

E. N ping (Continued)

1. Circumferential Welds D. Residual llea t Removal System 4 Cires j) >4" Nom.

Size 7.4.4.4 UT/PT B-J 45 11 3 4 4 ISI-0003-C E. Safety Injection System Cires >4" Nom. Size 7.4.4.5 UT/PT B-J 92 23 7 8 8 ISI-0002-C Cires <4" Nom. Size 7.4.4.5 PT B-J 39 10 3 3 4 ISI-0002-C F. Upper llead Injection System Cires >4" 7.4.4.6 UT/PT B-J 119 30 10 10 10 ISI-0001-C SI-Il4.2

SQNP SI-114.2 Page 8 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS - Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Re ference Component Section Method 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

$3 Coolant ? System - 

             !!ain Loops Welds >2" Nom. Size  7.4.5.1   UT/PT  B-J         1                 1              1       0       0        ISI-0008-B Welds $2" Nom. Size  7.4.5.1   PT     B-J         13                4              1       1       2        ISI-0008-B B. Reactor Coolant System Welds
             >2" Nom.

Size 7.4.5.2 UT/PT B-J 6 2 1 0 1 ISI-0013-C Welds 12" Nom. Size 7.4.5.2 PT B-J 8 2 0 1 1 ISI-0013-C SI-114'.2

SQNP- 

.                                                                                                 S1-114.2 l                                                                                                 Page 9 of 16 i                                                                                                  Rev. 7 3                                                                                                 APPENDIX A
TABLE A j SEQUOYAH INSERVICE INSPECTION PROGRAM 1 CLASS A COMPONENTS i

Program Section XI 40 Yr. Sample 1st Insp. Interval

Reference Exam Exam No. Length No. Length Inspection Periods Refe rence Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. .7 yrs. 10 yrs. Dwg. No.

{ t E. N ping (Continued) C. Chemical and Volume . ! Control - ! System Welds 

                              >2" Nom.

Size 7.4.5.3 UT/PT B-J 3 1 1 0 0 ISI-0009-C Welds <2" a'2 Nom. Size 7.4.5.3 N/A - - - - - ISI-0009-C s . D. Residual lleat Removal System Welds >2" ' Nom. Size 7.4.5.4 UT/PT B-J 3 1 0 1 0 ISI-0003-C Welds 52" Nom. Size 7.4.5.4 PT B-J 2 - 0 0 0 ISI-0003-C E. Safety Injection System Welds >2" Nom. Size 7.4.5.5 UT/PT B-J 5 1 0 1 0 ISI-0002-C' Welds $2" Nom. Size 7.4.5.5 PT B-J 11 3 1 1 1 , ISI-0002-C SI-ll4'.2

a SQNP SI-114.2 

                                                           'Page 10 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program         Section XI 40 Yr. Sample 1st Insp. Interval Reference  Exam      Exam      No. Length            No. Length      Inspection Periods       Reference Component      Section  Method  Category   Welds /of Weld     ' Welds /of Weld 3 yrs." 7' yrs. 10 yrs. Dwg. No.

E. I'_iping (Continued) F. Upper Head Injection System Welds >2" Nom. Size 7.4.5.6 N/A - - - - - 

                                                                                                                       'ISI-0001-C

$a Welds <2 S' Nom. SI'ze 7.4.5.6 PT B-J 2' 1 1 0 0 ISI-0001-C

3. Socket Welds A. Reactor Coolant System 7.4.6.1 PT B-J- 247 62 20 20 22 ~ISI-0013-C B. Chemical and Volume Control System 7.4.6.2 PT B-J 246 62 18 19 25 NSG-0008-C C. Residual Heat 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 170 43 14 14 -15 ISI-0002-C.

SI-114.2

SQNP SI-114.2. Page 11 of.16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length. Inspection Periods Reference-Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. E. 1]p_ing i (Continued) E. Upper IIcad - Injection System 7.4.6.5 PT B-J 16 4 1 l' 2 ISI-0001-C , 4. Piping and Valve o Integrally-

  • Welded Support Members A. Reactor Coolant System 7.4.7.1 PT B-K-1 11 11 3 4 4 MSG-0013-C 11 . Chemical anil Volume Control System 7.4.7.2 PT B-K-1 1 1 0 1 0 HSG-0012-C.

HSG-0015-C C. Residual llea t Removal System 7.4.7.3 PT B-K-1 5 5 1 2 2 MSG-0010-C SI-114.2

SQNP SI-114.2 Page 12 of 16 Rev. 7-APPENDIX A TABLE A 3 SEQUOYAH INSERVICE INSPECTION PROGRAM

CLASS A COMPONENTS
Program Section XI 40 Yr. Sample 1st Insp. Interval

) Reference Exam Exam No. Length No. Length Inspection Periods ReferenceL j Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. ! E. Piping (Continued) . I i D. Safety Injection j System 7.4.7.4 PT B-K-1 9 9 3 3 3' .HSG-0009-C. 3 , E. Upper llead gg Injection 7.4.7.5 PT B-K-1 1 1 1 0 0 MSG-0014-C 

   -I
5. Piping and Valve Component Supports
A. Reactor

] Coolant System 7.4.8.1 VT-3, B-K-2 137 137 45 46 46 MSG-0013-C VT-4 B. Chemical and Volume 

!                        Control l                         System      7.4.8.2          VT-3,  B-K-2            127               127              38        44       45-       MSG-0012-C MSG-0015-C  ,

VT-4 I I C. Residual Ileat Removal System 7.4.8.3 VT-3, B-K-2 17 17 5 6 6 MSG-0010-C VT-4 SI-114*.2 l l,

SQNP' SI-114.2 , Page 13 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program Section XI 40 Yr. Sampl'e 1st Insp. Interval .. Reference Exam -Exam No. Length No. Length Inspection Periods , Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs.- 10 yrs. Dwg. No. E. Piping (Continued) D. Safety Injection System 7.4.8.4 VT-3, B-K-2 110 110 35 37 38' HSG-0009-C VT-4 E. Upper Head i Injection E System 7.4.8.5 VT-3, B-K-2 88 88 29 29 30 MSG-0014-C VT-4 F. Reactor Coolant Pumps ,

1. Pressure-Retaining Bolting 7.5.1 UT B-G-1 96 96 24 -

24 48 CllH-2675-B

2. Pressure-Retaining Bolting 7.5.1 UT, B-G-1 96 96 24 24 .<48 CHH-2675-B PT or HT when removed
3. Pressure-Retaining Bolting 7.5.2 VT-1 B-G-2 4RCP/1 Set
  • 4 sets I set I set 2 sets . CHH-2675-B
 *See Program Reference Section for explanation of inspection sample.

SI-114.2

SQNP SI-Il4.2 Page 14 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH IhSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval , Reference Exam Exam No. Length No. Length Inspection Periods ' Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. F. Reactor Coolant Pumps . (Continued)

4. Integrally-Welded Supports 7.5.3 PT B-K-1 3 pumps /3 feet 9 feet 3 3 3* MSG-0003-B per pump *
5. Component

, $q Supports 7.5.4 VT-3, B-K-2 4 pumps /3 feet 12 feet 3 3 6 MSG-0003-B 3

VT-4 per pump *
6. Casing 7.5.6 VT-1 B-L-2 4 See Program Section 7.5.6 MSG-0003-B
7. 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 MT or PT B-G-2 See Program Section 7.6.2 '

A. Reactor Coolant System 7.6.2.1 VT-1 B-G-2 15 15 4 5 6 ISI-0013-C B. Chemical . and Volume Control System 7.6.2.2 VT-1 B-G-2 3 3 0 1 2 ISI-0009-C MSG-0008-C 

    *See Program Reference Section for explanat ion of inspection sample.
  • SI-114.2

SQNP SI-Il4.2 Page 15 of 16 Rev. 7 APPENDIX A TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category Welds /of Wel'd ' Welds /of Weld 3 yrs. 7 yrs. 10. yrs. Dwg. No. j G. Valves (Continued) i C. Residual lleat Removal System 7.6.2.3 VT-1 B-G-2 6 6 1 2 3 ISI-0003-C 

    ,          D. Safety
   $'               Injection System      7.6.2.4   VT-1   B-G-2            19                19             6      6         7        ISI-0002-C E. Upper llead Injection l

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

2. Integrally-Welded Support
              !! embers         7.6.3     UT/T7  B-K-1           See Program Section 7.4.7
3. Component j Supports 7.6.4 VT-3, B-K-2 See Program Section 7.4.8 l VT-4
4. Valve llodies 7.6.6 VT-4 B-M-2 See Table D of Appendix A
              >4V N.P.S.

SI-ll4.2

SQNP SI-114.2 Page 16 of 16 j Rev. 7 APPENDIX A 

 ,                                                                      TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS A COMPONENTS Program               Section XI 40 Yr. Sample 1st Insp. Interval Reference   Exam           Exam     No. Length         No. Length     Inspection. Periods     Reference Component        Section   Method       Category   Welds /of Weld    Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No.

II. Exempted Components 7.7 VT-2 B-P See Program Section 7.7

1. Reactor Vessel - Pressure Retaining Boundary
2. Pressurizer - Pressure Retaining Boundary I
3. Steam Generators - Pressure Retaining Boundary os 4. lleat Exchangers - Pressure Retaining Boundary
   ?
5. Piping - Pressure Retaining Boundary
6. Pumps - Pressure Retaining Boundary
7. Valves - Pressure Retaining Boundary l

h SI-Il4.2

SQNP SI-114.2 Page 1 of 10 

                                                               .Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS B COMPONENTS Program           Section XI 40 Yr. Sample 1st Insp. Interval Reference   Exam      Exam       No. Length        No. Length       Inspection Periods       Reference Component       Section   Method   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 1 1 1 CHM-2345-B (12)
2. Circumferential Head Welds 8.1.2 UT C-A 4 Gens./1 Weld I wid/46 ft 15' 15' 16' CHM-2345-B (4) -
3. Tubesheet-to- .

i Shell Weld 8.1.3 UT C-A 4 Gens./1 Weld I wld/36 ft 12' 12' 12' CHM-2345-B 05 (4) - 4. Nozzle-to-Vessel Welds & 8.1.4 UT, MT C-B 4 Gens /2 Noz (8) 8 1 3 4 CHM-2345-B Inner Radius B. Heat Exchangers

1. Residual Heat Removal Heat Exchanger (2)

RHRHX

a. RHRilX Circumfer-ential Shell Weld 8.2.1.1 UT C-A 2Ht.Ex./1 Weld I wld/113" 37" 38" 38" CHM-2404-A SI-114*.2

SQNP SI-114.2 Page 2 of 10 Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS B COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference { Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. ] l - B. Ileat Exchangers (Continued)

b. Ri!RHX Circumfer-ential llead Weld 8.2.1.2 UT C-A 2Ht.Ex./1 Weld I weld /113" 37" 38" 38" CHH-2404-A (2)
                                                                                                                                                                              ]

a c. RllRHX * 

 ?              Nozzle-to-                                                                                                                                                    j Vessel Weld 8.2.2      UT, PT C-B         2Ht.Ex./2noz.         i       4             1                                          1       2         CHM-2404-A '

(4)

d. RHRHX .

Integrally-Welded Supports 8.2.3 PT C-C 2Ht.Ex./2 Welds 2 0 1 1 Cl&I-2404-A (4)

e. RHRllX Component Supports 8.2.4 VT-3 C-E 211t. Ex./ 4 1 1 2 CIRI-2404-A 2 Sprts. (4)

SI-11'4.2

SQNP SI-114.2 Page 3 of 10 Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAN CLASS B COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Component Section Reference Method Category Welds /of Weld- Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. B. Ileat Exchangers (Continued) '

2. Regenerative Heat See Relief Request ISI-12 Exchanger (1) RHX
4. Excess Letdown See Relief Request ISI-12 '

Ileat Exchanger (1) ELHX 

  , C. Tanks                                                                 .

e l' 1. Boron Injection . Tank (1) BIT

a. BIT Circum-ferential Shell/llead Wld 8.5.1 UT C-A ITank/2 Welds 2 0 1 1 ISI-0074-A
b. BIT Nozzle to Vessel Wlds 8.5.2 MT, UT C-B ITank/2Noz 2 0 1 1 ISI-0074-A
c. BIT Component Supports 8.5.3 VT-3 C-E 4 4 i

1 1. 2 ISI-0074-A

d. BIT Pressure

. Retaining Bolting 

                 >2" Dia. 8.5.4      UT      C-D          IMwy/16 Studs           IMwy      1        0         0         ISI-0074-A SI-114.2

SQNP SI-114.2 Page 4 of i0 Rev. 7 APPENDIX A - TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS B COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. C. Tanks (Continued) '

2. UllI Water Accumulator (1) WA
a. WA Circum-ferential j3 Shell/ -
Q3 Ilead Wld 8.6.1 UT C-A ITank/2 Welds 2 wld/428" ea 214" 214" 428" ISI-0070-A t
b. WA Nozzle to Vessel Welds 8.6.2 UT,MT C-B ITank/3Noz 3 1 1 1 ISI-0070-A
c. WA Int.-

Weld Supports 8.6.3 MT C-C 1 Support Skirt 35' 11' 12' 12' ISI-0070-A

d. WA Component Supports 8.6.4 VT-3 C-E 1 Capnt Support Skirt 1 0 1 0 ISI-0070-A
e. WA Pressure Retaining Bolting
                                >2" Dia. 8.6.5     UT     C-D         2Mwy/16 Studs each          2Mwy    0        1        1         ISI-0070-A SI-11d.2

m SQNP SI-114.2 Page 5 of 10 Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM ., CLASS B COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference

Component Section 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 i
a. ST Circum- -

ferential Shell/ Ilead W1d 8.7.1 UT C-A ITank/2W1ds 2 0 1 1 ISI-0071-A

b. ST Int.-
  ,               Weld 8               Supports (PADS)       8.7.3      PT     C-C          ITank/2 Pads             2          1        1       0         ISI-0071-A
c. ST Component Supports 8.7.4 VT-3 C-E 2 2- 0 1 1 ISI-0071-A D. Piping
1. Integrally-Welded Supports
a. Residual IIca t Removal System 8.8.1.1 N/A C-C See Program Section 8.9.1.1 MSG-0010-C
b. Safety Injection System 8.8.1.2 PT C-C 4 4 1 1 2 MSG-0009-C SI-114.'2

SQNP SI-114.2 Page 6 of 10 Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS B COMPONENTS i Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. 

                                                                                                                                                                                                ~

i D. Piping (Continued)

c. Main Steam System 8.8.1.3 MT C-C 12 12 2 5 5 MSG-0017-C
d. Feedwater System 8.8.1.4 MT C-C 5 5 0 2 3 MSG-0016-C
e. Containment Spray i System 8.8.1.5 PT C-C See Program Section 8.9.1.5 MSG-0011-C
f. Upper llead Injection System 8.8.1.6 PT C-C 4 4 1 1 2 MSG-0014-C
2. Component Supports
a. Residual llea t Removal System 8.8.2.1 VT-3, C-E 83 83 27 28 28 HSG-0010-C VT-4
b. Safety Injection System 3.8.2.2 VT-3, C-E 57 57 18 19 20 MSG-0009-C VT-4 SI-11d.2

SQNP SI-114.2 Page 7 of 10 Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS B COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. D. Piping (Continued)

c. Main .

Steam System 8.8.2.3 VT-3, C-E 62 62 20 20 22' MSG-0017-C VT-4 da d. Feedwater Y' System 8.8.2.4 VT-3, C-E 30 ' 30 10 10 10 MSG-0016-C VT-4

e. Contain-ment Spray System 8.8.2.5 VT-3, C-E 5 5 1 2 2 MSG-0011-C VT-4 .
f. Upper Head Injection System 8.8.2.6 VT-3, C-E 7 7 2 2 3 MSG-0014-C VT-4
3. Circumferential and Longitudinal A. Residual Heat Removal System
a. RHR Cires > " Nom. Wall Thickness 8.8.4.1 UT, PT C-F, C-G 24 6 1 2 3 ISI-0003-C a
b. RHR Long. >k" Nom. Wall Thickness 8.8.4.1 UT PT C-F, C-G 4 1 1 0 0 ISI-0003-C

SQNP. SI-114.2 Page 8 of 10 Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS B COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. D. Piping (Continued)

c. RIIR Cires 5 " Nom. Wall Thickness 8.8.4.1 PT C-F, C-G 105 26 8 9 9 ISI-0003-C
d. RHR Long. 5 " Nom. Wall Thickness 8.8.4.1 PT C-F, C-G 28 7 2 2 3 ISI-0003-C i B. Safety Injection System
a. SIS Circs > " Nom. Wall Thickness 8.8.4.2 UT, PT C-F, C-G 35 9 3 3 3 ISI-0002-C
b. SIS Cires 1 " Nom. Wall Thickness 8.8.4.2 PT C-F, C-G 40 10 2 4 4 ISI-0002-C ISI-0074-A
c. SIS Long. 5 " Nom. Wall Thickness 8.8.4.2 PT C-F, C-G 15 5 0 2 3 ISI-0002-C C. Main Steam System
a. MS Cires >\" Nom. Wall Thickness 8.8.4.3 UT, MT C-F, C-G 24 6 1 2 3 ISI-0015-C
b. MS Long. > " Nom. Wall Thickness 8.8.4.3 UT, MT C-G, C-G 5 1 0 1 0 ISI-0015-C SI-114.2

SQNP SI-114.2 Page 9 of 10 Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS B COMPONENTS ! Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference i Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. 1 D. Piping (Continued) ' D. Feedwater System

a. FW Cires >\" Nom. Wall Thickness 8.8.4.4 UT, MT C-F, C-G 17 4 0 2 2 CHM-2403-C

.i b. FW Long. >\" Nom. Wall Thickness 3 8.8.4.4 UT, MT C-F, C-G ' 1 1 1 0 0 CIIM-2403-C E. Containment Spray System -

a. CS Cires $ " Nom. Wall Thickness 8.8.4.5 PT C-F, C-G 6 1 1 0 0 ISI-0007-C
b. CS Long. $ " Nom. Wall Thickness 8.8.4.5 PT C-F, C-G 2 1 0 1 0 ISI-0007-C F. Upperhead Injection System 8.8.4.6 UT, PT C-F, C-G 26 7 2 2 3 ISI-0001-C E. Pumps
1. Residual lleat Removal Pumps (2) RilRP 4
a. RJIRP Support Components 8.9.1.2 VT-3 C-C, C-E 2 2 1 0 1 J

SI-114.2 ]

SQNP SI-114.2 Page 10 of 10 Rev. 7 APPENDIX A TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS B COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Exam No. Length No. Length Inspection Periods Reference Component Section Method Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. , F. Exempted ' Components 8.11 VT-2 C-H See Program Section 8.12 ? 1 , I i l i T I SI-11//.2

SQNP-SI-114.2 Page-1 of 2 Rev. 7 APPENDIX A TABLE C SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS C COMPONENTS Program Method Section XI 40 Yr. Sample 1st Insp. Interval Reference of Exam No. Length No. Length Inspection Periods Reference Component Section Insp. Category Welds /of Weld Welds /of Weld 3 yrs. 7 yrs. 10 yrs. Dwg. No. A. Piping

1. All Classes C 9.0, 9.1 VT-2 D-A, D-B N/A N/A 100% 100% 100% N/A and D D-C B. Component Supports
1. Auxiliary 9.0.1.1 VT-3 D-A 45 45 45 45 45 ISI-01'46-C j3 feedwater VT-4 j' System
2. Chemical and 9.0.1.2 VT-3 D-A 7 7 7 7 7 ISI-0149-C Volume Control VT-4 System
3. Component 9.0.1.3 VT-3 D-A, D-B 208 208 208 208 208 ISI-0154-C Cooling VT-4 System
4. Containment 9.0.1.4 VT-3 D-B 26 26 26 26 26 ISI-0153-C Spray System VT-4
5. Essential Raw 9.0.1.5 VT-3 D-A, D-B 222 222 222 222 222 ISI-0153-C Cooling Water VT-4 Sys, tem
6. Fuel Pool 9.0.1.6 VT-3 D-C N/A N/A See Program Section 9.0.1.6 Cooling VT-4 System SI-114.2

SQNP SI-114.2 Page 2 of 2 Rev. 7 APPENDIX-A TABLE C (Continued) SEQUOYAH' INSERVICE INSPECTION PROGRAM CLASS C COMPONENTS Program Method Section XI 40 Yr. Sample 1st Insp. Interval Reference of Exam No. Length No. Length Inspection Periods Reference-Component Section Insp. Category Welds /of Weld Welds /of -id 3 yrs. 7 yrs. 10 yrs. Dwg. No. 11 . Component Supports (Continued)

7. Residual lleat 9.0.1.7 VT-3 D-B 7 7 7 7 7. ISI-0150-C Removal System VT-4
8. Sa fe ty 9.0.1.8 VT-3 D-B 28 28 28 28 28 ISI-0151-C Injection VT-4 System l

SI-114.2,

SQNP SI-114.2 Page 1 of 2 Rev. 7 APPENDIX A TABLE D Valves Subject to the Requirements of Examination Category B-M-2 of Table IWB-2500-1 of Section XI Code Valve Piping Valve Valve Valve Group TVA Dwg No. Vendor Material Valve Forging / Valve No. Class Cat. System Size Type Act No. (Weld Map) Dwg No. Vendor Spec. Function Casting FCV-63-67 A B-PAS SIS 10' Cate MO 1 CHM-2333-C 88926 Velan ASTM A182 Forging FCV-63-80 A B-PAS SIS 10" Cate NO 1 CHM-2333-C 88926 Velan ASTM'A182 Forging FCV-63-98 A B-PAS SIS 10" Gate M0 l' CHM-2333-C 88926 Velan ASTM A182 Forging FCV-63-118 A B-PAS SIS 10" Cate MO 1 CHM-2333-C 88926 Velan ASTM A182 Forging 63-560 A AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A5161 psyy 63-561_ A AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A5161 PSIV 63-562 A AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A5161 PSIV 1 63-563 A AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A5161 PSIV g 63-622 A AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A5161 PSIV e 63-623 A AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-1289 Darling ASTM A5161 PSIV 63-624 A AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A5161 PSIV 63-625 A AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A5161 psyy 63-640 A AC-Act SIS /RHR 8" Ck SA 2 CHM-2336-C 94-12892 Darling ASTM A5161 p3yy 63-663 A AC-Act SIS /RHR 8" Ck SA 2 CHM-2336-C 94-12892 Darling ASTM A5161 PSIV 63-558 A AC-Act SIS 6" Ck SA 3 CHM-2333-C 78704 Velan ASTM A182 PSIV Forging 63-559 A AC-Act SIS 6" Ck SA 3 CHM-2333-C 78704 Velan ASTM A182 PSIV Forging 63-632 A AC-Act SIS 6" Ck SA 3 CHM-2333-C 78704 Velan ASTM A182 PSIV Forging 63-633 A AC-Act SIS 6" Ck SA 3 CHM-2333-C 78704 Velan ASTM A182 PSIV Forging 63-634 A AC-Act SIS 6" Ck SA 3 CHH-2333-C 78704 Velan ASTM A182 PSIV Forging l 63-635 A AC-Act SIS 6" Ck SA 3 CHM-2333-C 78704 Velan ASTM A182 PSIV Forging 63-641 A AC-Act SIS /RHR 6" Ck SA 3 Clel-2336-C 78704 Velan ASTM A182 PSIV Forging 63-644 A AC-Act SIS /RHR 6" Ck SA 3 CHM-2336-C 78704 Velan ASTM A182 PSIV Forging 68-563 A C RCS 6" Rel SA 4 CHM-2334-C H51688 Crosby See ASTM A182/ A3512- yote2 SI-114.2

SQNP. SI-114.2 . Page 2 of 2 Rev. 7 APPENDIX A TABLE D Valves Subject to the Requirements of Examination Category B-M-2 of Table IWB-2500-1 of Section XI Code Valve Piping Valve Valve Valve Group TVA Dwg No. Vendor laaterial Valve Forging / Valve No. Class Cat. System Size Type Act No. (Weld Map) Dwg No. Vendor Spec. Function Casting 68-564 A C RCS 6" Rel SA 4 CHM-2334-C H51688 . Crosby ASTM A182/ See. A3512 Note 2 68-565 A C RCS 6" Rel SA 4 CHH-2334-C H51688 Crosby ASTM A182/ See A3512 Note 2 FCV 74-1 A A-Act RIIR 14" Gate MO 5 CHM-2336-C E-1-144831 Copes-Vulcan ASTM A182 PSIV Forging FCV-74-2 A A-Act RHR 14" Cate MO 5 CHM-2336-C E-1-144831 Copes-Vulcan ASTM A182 PSIV Forging a 87-558 A AC-Act UllI 8" Ck SA 6 CHM-2337-C B-148885 Copes-Vulcan ASTM A182 PSIV Forging. 25 87-559 A AC-Act UllI 8" Ck SA 6 CHM-2337-C B-148885 Copes-Vulcan ASTM A182 PSIV Forging l# 87-560 A AC-Act UllI 8" Ck SA 6 CHM-2337-C B-148885 Copes-Vulcan ASTM A182 PSIV Forging 87-561 A AC-Act UllI 8" Ck SA 6 CHM-2337-C B-148885 Copes-Vulcan ASTM A182 PSIV Forging 87-562 A AC-Act Ulil 12" Ck SA 6 CHM-2337-C B-148885 Copes-Vulcan ASTM A182 PSIV 87-563 Forging A AC-Act UllI 12" Ck SA 6 CHM-2337-C B-148284 Copes-Vulcan ASTM A182 PSIV Forging j NOTES: 8 Seal plate manufactured to ASTM A240 F304. ! 2 i Nozzle manufactured to ASTM A182 F316 - Forging Body manufactured to ASTM A351 CR8M - Casting SI-114.2 . \

SQNP SI-114.2 Page 1 of 2 Rev. 7 APPENDIX A Valves Subject to the Examination Requirements of Examination Category B-G-2 TABLE E Valve ID Bolt Size Bolt Length Bolt Material System 87-559 1 1/4" 7 3/8" SA-453 GR 660 UllI 87-558 1 1/4" 7 3/8" SA-453 GR 660 UHI 87-560 1 1/4" 7 3/8" SA-453 GR 660 UHI-87-561 1 1/4" 7 3/8" SA-453 GR 660 UllI 87-562 1 1/2" 9 1/4" SA-453 GR 660 UHI 87-563 1 1/2" 9 1/4" SA-453 GR 660 UllI FCV 87-7 1 1/8" 5" SA-453 GR 660 UHI FCV 87-8 1 1/8" 5" SA-453 GR 660 UHI j, 63-560 1 3/8" Unknown A-193 GR B7 Safety Inj. c3 63-563 1 3/8" Unknown A-193 GR B7 Safety Inj. i 63-622 1 3/8" Unknown A-193 GR B7 Safety Inj . 63-625 1 3/8" Unknown A-193 GR B7 Safety Inj.

63-624 1 3/8" Unknown A-193 GR B7 Safety Inj.

63-562 1 3/8" Unknown A-193 GR B7 Safety Inj. i 63-561 1 3/8" Unknown A-193 GR B7 Safety Inj. l 63-623 1 3/8" Unknown A-193 GR B7 Safety Inj. 63-635 1 1/4" 6 1/2" A-193 Safety Inj. i 63-633 1 1/4" 6 1/2" A-193 Safety Inj. 63-632 1 1/4" 6 1/2" A-193 Safety Inj. 63-634 1 1/4" 6 1/2" A-193 Safety Inj. 63-558 1 1/4" 6 1/2" A-193 Safety Inj. 63-559 1 1/4" 6 1/2" A-193 Safety Inj. 63-581 3/4" 4 1/2" A-193 Safety Inj. 63-640 1 3/8" Unknown A-193 GR B7 RllR 63-643 1 3/8" Unknown A-193 GR B7 RllR 63-641 1 1/4" 6 1/2" A-193 RllR 63-644 1 1/4" 6 1/2" A-193 RilR Note: For Bolted Connection ID Add '-BC' to end of Valve ID. SI-114.2

SQNP SI-114.2 Page 2 of 2 Rev. 7 APPENDIX A Valves Subject to the Examination Requirements of Examination Category B-G-2 TABLE E (Continued) Valve ID Bolt Size Bolt Length Bolt Material System FCV 74-1 1 3/4" Unknown A-193 GR B7 RHR FCV 74-2 1 3/4" Unknown A-193 GR B7 RHR FCV 62-69 7/8" 3 3/8" A-193 GR B7 CVC FCV 62-70 7/8" 3 3/8" A-193 GR B7 CVC FCV 62-84 7/8" 3 3/8" A-193 GR B7 CVC PCV 68-340B 7/8" 3 3/ " A-193 GR B7 Reactor Coolant PCV 68-340D 7/8" 3 3/4" A-193 GR B7 Reactor Coolant i 68-530 3/4" 4 1/2" A-193 Reactor Coolant 2 68-536 3/4" 4 1/2" A-193 Reactor Coolant 

' 68-541                                     3/4"             4 1/2"                   A-193           Reactor Coolant 68-567                                    3/4"             4 1/2"                   A-193           Reactor Coolant 68-519                                    3/4"             4 1/2"                   A-193           Reactor Coolant 68-525                                    3/4"             4 1/2"                   A-193           Reactor Coolant 68-508                                    3/4"             4 1/2"                   A-193           Reactor Coolant 68-514                                    3/4"             4 1/2"                   A-193           Reactor Coolant.

FCV 68-332 3/4" 4 1/4" A-453 Reactor Coolant FCV 68-333 3/4" 4 1/4" A-453 Reactor Coolant 68-563 Unknown Unknown A-193 GR B7 Reactor Coolant 68-564 Unknown Unknown A-193 GR B7 Reactor Coolant 68-565 Unknown Unknown A-193 GR B7 Reactor Coolant FCV 63-67 1 3/8" 8 1/2" A-193 Safety Inj. FCV 63-118 1 3/8" 8 1/2" A-193 Safety Inj. FCV 63-98 1 3/8" 8 1/2" A-193 Safety Inj. FCV 63-80 1 3/8" 8 1/2" A-193 Safety Inj. SI-ll4.2

l SQNP , SI-114.2 l Page 1 of 3 Rev. 7 APPENDIX A . . , TABLE F LIST 0F DRAWINGS - UNIT 2 Reactor Vessel Appendix A Drawing No. Title Page No. ISI-0008-B Reactor Coolant Piping 64-65 ISI-0001-C Upper Head Injection System 39-41 CH-M-2341-B Reactor Vessel Stud Locations and Details 1-2 CH-M-2343-B Reactor Vessel Seam Welds 3 CH-M-2358-A Reactor Vessel Closure H ad 4 CH-M-2359-A Control Rod Drive Housin. 8-9 CH-M-2360-A Reartor Vessel Inlet Nozzles 10 CH-M-2361-A Reactor Vessel Outlet Nozzles 11 ISI-0014-A Auxiliary Head Adapter 7 ISI-0016-A Reactor Vessel Clad Patches (PSI Only) 12 MSG-0001-B Closure Head Cladding Patches (PSI Only) 13 MSG-0004-C Reactor Vessel Bottom Head Penetrations 14 ISI-0097-C Closure Head Penetrations 5-6 Pressurizer Appendix A Drawing No. Title Page No. CH-M-2362-A Pressurizer Support Skirt Weld 19 CH-M-2363-A Pressurizer Seam Welds- 20 MSG-0002-B Pressurizer and Steam Generator Cladding Patches 17 MSG-0006-A Pressurizer Heater Penetations 21 Steam Generators Appendix A Drawing No. Title Page No. ISI-0008-B Reactor Coolant Piping 64-65 CH-M-2345-B Steam Generator 16 76M1 Vertical Steam Generators (Tube Sheet Arrangement) 15 MSG-0002-B Pressurizer and Steam Generators Cladding Patches 17 MSG-0005-A Steam Generator /Feedwater Transition Spool Piece 18 

                                                             ~
                              -105-                             ~

SQNP SI-114.2 Page 2 of 3 Rev. 7 APPENDIX A _. TABLE F LIST OF DRAWINGS - UNIT 2 Heat Exchangers Appendix A Drawing No. Title Page No. CH-M-2404-A Residual Heat Removal Heat Exchanger 27 ISI-0066-A Regenerative Heat Exchanger 28-30 ISI-0067-A Excess Letdown Heat Exchanger 31 ISI-0068-!. Letdown Heat Exchanger 32 Piping and Valve Weld Maps Appendix A Drawing No. Title Page No. ISI-0008-B Reactor Coolant Piping (Main Loops) 64-65 ISI-0002-C Safety Injection System 42-53 ISI-0013-C Reactor Coolant System 68-78 ISI-0009-C Chemical and Volume Control System 66-67 ISI-0003-C Residual Heat Removal System 54-62 ISI-0001-C Upper Head Injection System 39-41 MSG-0008-C Seal Water Injection (Chemical and Volume Control System) 81-85 CH-M-2403-C Feedwater System 37-38 ISI-0015-C Main Steam System 79-80 ISI-0007-C Containment Spray System 63 Class A and B Piping and Valve Support Drawings Appendix A Drawing No. Title Page No. I MSG-0013-C Reactor Coolant System 108-119 MSG-0012-C Chemical and Volume Control System 106-107 MSG-0015-C Seal Water Injection (Chemical and Volume Control System) 124-128 MSG-0010-C Residual Heat Removal System 98-104 MSG-0009-C Safety Injection System 86-97 MSG-0014-C Upper Head Injection System 120-123 MSG-0017-C Main Steam System 131-132 MSG-0016-C Feedwater System' 129-130 MSG-0011-C Containment Spray System 105 

                                   -106-                 SI-114.2

SQNP SI-114.2 Page 3 of 3 Rev. 7 APPENDIX A TABLE F LIST OF DRAWINGS - UNIT 2 Class C and D Piping and Valve Support Drawings Appendix A Drawing No. Title Page No. ISI-0146-C Auxiliary Feedwater System 136-137 ISI-0149-C Chemical and Volume Control System 138 ISI-0150-C Residual Heat Removal System . 139 ISI-0151-C Safety Injection System 140-141 ISI-0153-C Containment Spray System 142-143 ISI-0154-C Component Cooling System 144-152 ISI-0158-C Essential Raw Cooling Water System 153-164 Pumps Appendix A Drawing No. Title Page No. CH-M-2675-B Reactor Coolant Pump Main Flange and Lower Seal House Bolt Pattern 22 ISI-0098-A Reactor Coolant Pump Support Feet. 23 ISI-0099-A Residual Heat Removal Pump Supports 25 ISI-0146-A Centrifugal Charging Pump Supports 24 ISI-0147-B Safety Injection Pump Supports 26 Tanks Appendix A Drawing No. Title Page No. ISI-0070-A Upperhead Injection Water Accumulator 33-34 ISI-0071-A Accumulator Surge Tank 35 ISI-0074-A Boron Injection Tank (Unit 2) 36 ( 

                                  -107-                    SI-114.2

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e TENNESSEE VALLEY AUTHORITY DIVl500N Of NUCLEAR POWER SEQUOYAH NUCLEAR PLANT UNITS I&2 AUX. HEAD ADAPTER xsuis --,,, o y 'e s-ndo n_e a_=t @_---- ~sme I cws I smens 

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                                                                                                        /            REFERENCE DRAWINGS

( 30616-1041 

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8 - IElit!CL5EE VALLEY Atraliti. liY 

                                                                                                            'SEQUOYAH NUCLEAR PLANT UNITS #18 #2 CONTROL ROD DRIVE HOUSING a 8A SCALES NTS       SUBMITTio               APP 'alvf fa        .1 ATc J             ADD DIMEhSlahS4REEDW6No..TAA } MC- 1)R o n n _pue. ..                      [~- - - }g ~                                       (,- 2 s
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[-fi[{[Eo7ppf-CK'O API! 

      -_                 . .. -   . .O. DATE N                       REVISIONS CH.-M f359 A g,

LIST OFCONTROL ROD DRIVE HOUSINGS C.R.D. NO. NUM8ER 8 , I-9 9 9.05 10 -13 4 9.57 14 -17 4 12.20 18-21 4 13.0 7 l 22-29 8 14.0 2 30-37 8 16.81 38-41 4 19.6 9 I 42-49 8 20.67 l 50-53 4 21.69 1 54-61 8 23.74 E 3$v l f 62-65 4 27,17  ? M'j ! 66-73 8 2 8.31 s ep

74-7 8 5 31.5 0 S, N TOTAL
78 -

FOR LOCATIONS SEE DRAWINGS: $ CHM-2651-C(UNIT #1) ISI-OO97-C (UNIT # 21 b 

                                ~        ~

l 5-1l 83 ADO UNtlW2 LOCRTIDnf DWC, til g&f NO. DATE REVISIONS CK"O APR TENNESSEE VALLEY AUTHOR 11Y ceVt580N OF NUCLEAR FOWER

SEQUO(AH NUCLEAR PLANT l UNITS #l 8 #2 CONTROL ROD DRIVE HOUSING j^4'.. [$_. eta 9 ____ ,,, dM[ ,,,,

3g,;;,ypg__ *="'94-____ CHM-2359-A 81

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                                                                             /            \\                          /   NOTES
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O l. UPPER g SHALLCLAD PATCH EXAMINATIONS i i 14 BE DONE THROUGH THE i RADIATION SPECIMEN ACCESS Ora PORTS. ZIMUTH O* 8 300 2. AZIMUTHS ARE TAKgOFF OF 

                                                                                           /             ,

REACTOR CENTERL , l 6" TENNESSEE VALLEY AUTHORITY I DIVISION OF NUCLEAR POWER l LOWER - - - (CLAD PATCH SEOUOYAH NUCLEAR PLANT CENTERLINE OF CORE UNIT #1 a #2 ADS REACTOR VESSEL CLAD PATCHES g[d__ 59% n_______ eta ______ y'[g g,_g - g 3 IsidOOl6-A

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2. PUMP SUPPORT NUMBERS CCPH-IA-A CCPH-lB-B CCPH-2A-A CCP.H-28-8
3. THE PUMP FEET ARE INTERGALLY WELDED TO THE CASING. l m ,,emc,r,,,

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SQNP SI-114.2 Page 1 of 1 Rev. 7 APPENDIX C DATA SHEET 1 SEQUOYAH NUCLEAR PLANT UNIT 2, CYCLE INSERVICE INSPECTION FINAL REPORT e Reviewed by: ISI Group Supervisor Plant Manager S1-114.2 1, 7 I

SQNP SI-114.2 Page 1 of 1 Rev. 7 

  .                                  APPENDIX D NOTIFICATION OF INDICATION PART I - FINDINGS NOI No.                   Plant / Unit Examination Report No.                     Component ID Drawing No.

Description of Indication: (Attach Sketch / Photograph if needed) Signature of Examiner / Certification Level Date Signature of Field Supervisor (Contractor) Date NDE Section Representative Date PART II - DISPOSITION Disposition Prepared By Date Disposition Approved By Date PART III - VERIFICATION Verification of Completed Corrective Action and/or Examinaton by NDE Section Representative. Signature Date 

                                          -272-                         SI-114.2

SQNP SI-114.2 Page 1 of 26 Rev. 7 O APPENDIX E l REQUEST FOR RELIEF 4: t 

                                                    -273-      SI-114.2

SQNP SI-114.2. Page 2 of 26 Rev. 7 S REQUEST FOR RELIEF ISI-1 Components: Reactor coolant pumps (four per unit) Class: TVA Safety Class A Function: -Circulates reactor coolant Inspection Requirement: ASME Section XI, Table IWB-2500-1, examination category B-L-2, item No. B12.20, visual exami-nation of pump internal pressure boundary surface. Basis for Relief: In absence of required maintenance, dis-assembly of a reactor coolant pump solely to ~ perform a visual examination of internal surfaces is impractical. This would represent an unnecessary employee exposure to high radiation and contamination areas and an excessive expense to TVA. Time required for this major task of dis-asembly, examination, and reassembly would consume at least three weeks of 24-hours-per-day work._ Radiation dose rates of the pump exterior will average 100 to 300 mres/ hour, and pump internal dose rates will average 10 to 20 res/ hour. The benefit received from this major effort is minimal considering employee exposure, potential damage to safety-related equipment, and cost in dollars. In addition, the two units at Sequoyah Nuclear Plant will operate under similar conditions. Therefore, we feel that if a pump from one of the units is disassembled for maintenance during a ten-year interval, the visual exami-nation performed will be representative of the pump condition for each unit. This would avod unnecessary employee exposure to the high radiation dose rates noted above. We conclude that if one pump is disassembled for mainte-nance during the ten-year interval, the visual examination performed eatisfies examination category B-L-2 requirements for both units. Disassembly of the pump solely for visual examination is impractical. 

                                          -274-                  31 114.2

SQNP SI-114.2 Page 3 of 26 Rev. 7 REQUEST FOR RELIEF ISI-1 (Continued) Alternate Inspection: The internal surface of'the reactor coolant pump casing will be visually examined whenever the surfaces are made accessible when a pump is disassembled for maintenance purposes. If during the ten-year interval a pump from either unit is not disassembled for mainte-nance, a pump from one unit shall be examined from the exterior. This shall be accomplished by ultrasonic thickness measurements of the pump casing. l i i I f 6 6 i i 1 

                                                                                                     -275-                                                                  SI-114.2

SQNP , SI-114.2 Page 4 of 26 Rev. 7 REQUEST FOR RELIEF ISI-2 Components: Valves exceeding four-inch nominal pipe size Class: TVA Safety Class A Function: Various functions Inspection Requirement: ASME Section XI, Table IWB-2500-1, examination category B-M-2, item No. B12.40, visual exami-nation of valve internal pressure boundary surface. Basis for Relief: During routine maintenance, visual exami-nations of valve body internal pressure boundary surfaces are performed and documented under existing plant administrative pro-cedures. Most Class A valves, particularly containment isolation valves, are disassembled frequently for maintenance. In addition, the two units at Sequoyah Nuclear Plant will operate under similar conditions. If a valve from one of the units is disassembled for maintenance within a ten-year interval, we feel that the visual examination performed would be representat'ive of both units and would be sufficient to satisfy the examination requirements for both units for that partic-ular valve classification as defined in exami-nation category B-M-2. We conclude that if one valve in each group of valves of the same constructional design and manufacturer that perform similar functions is , disassembled from either unit during the ten-year interval, the visual examination performed satisfies examination cagegory B-H-2 requirements of both units. Alternate Inspection: If a valve from a particular classification has not been disassembled as the end of the inspection interval approaches, a case-by-case study will be made to determine the practi-cality of disassembling a valve from one of the units solely for visual examination (determine if draining the vessel would be required, etc.). If necessary, a request for relief will be issued at that time. 

                                        -276-                    SI-114.2

3 SQNP SI-114.2 Page 5 of 26 Rev. 7 REQUEST FOR RELIEF ISI-3 Components: Pressure-retaining welds in piping Class: TVA Safety Classes A and B Function: Pressure-retaining component Inspection Requirement: ASME Section XI, Table IWB-2500-1, examination categories B-F (item No. B5.50), B-J (item Nos. B9.10, B9.20, and B9.30), and C-F (item Nos. C5.10, C5.20, and C5.30), volumetric examination of longitudinal, circumferential, and pipe branch connection welds. Basis for Relief: In some cases it will be impractical to inspect all welds from both sides, i.e., nonremovable hanger interference or valve and pump casingsadjoining the welds. These welds will be noted on the ultrasonic examination data sheets and on attachment A of this request for relief. 

 - Alternate Inspection:    In addition to the visual examination performed during system leakage and hydro-static pressure tests, a "best effort" ultra-sonic examination and a surface examination will be performed on accessible areas of the weld (s).
                                           -277-                  33 114.2

SQNP ATTACllMENT A SI 114.2 Page 6 of 26 REQUEST FOR RELIEF ISI-3 Rev. 7 (Continued) WELD PIIYSICAL  % CODE nut!BER SIZE CAT. HATL DRAWING NUMBER CONFIGURATION SCAN / LIMITATIONS SCAN REHARKS R.IIRil- 125 6" B-J SS ISI-0003 (SHT 5) Nozzle / Elbow 4/No scan 83% No scan 4 due to nozzle 3/No scan 5:00-7:00 geometry No scan 3 5:00-7:00 due to inner radius RCF-23 4" B-J SS ISI-0013 (SHT 1) Elbow / Safe-end 4/No scan 75% No scan 4 due to safe-end 3/ Limited scan geometry Scan 3 limited by inner radius of elbow RCW-29 SE 14" B-F SS/CS CHM-2363 (SHT 1) Nozzle / Safe-end 3/ Limited at 90% Scan 3 limited by 1" WGS 12:00, 3:00, at 12:00, 3:00, 6:00 6:00 and 9:00 and 9:00 ti 4/No scan 

  ?                                                                                                               No scan 4 due to nozzle geometry SIF-128             10"     B-J   SS            ISI-0002 (SHT 4)   Valve / Tee         3 and 4/No scan        0%   No scan 3 and 4 due to valve to tee geometry RCW-24 SE           4"      B-F   SS/CS         CIIM-2363 (SHT 1)  Nozzle / Safe-end   4/No scan             40%   No scan 4 due to 3/ Limited                     safe-end geometry Scan 3 limited by
                                                                                ,                                   nozzle curvature RC-3                31"     B-J   SS            ISI-0008-B         Safe-end/ Elbow     3/No scan             50%   No scan 3 due to 4/\ node                      nozzle geometry RC-1 S2             29"     B-J   SS            ISI-0008-r         Pipe / Elbow        3/ Limited 9:30       98%   Scan 3 limited by and 10:30                  one inch nozzles at 9:30 and 10:30
                                                                                                                                  $I-114.2

SQNP SI-114.2 Page 7 of 26 Rev. 7 REQUEST FOR RELIEF ISI-4 Component: Steam generator (four per unit) Class: TVA Safety Class B Inspection Requirement: ASME Section XI, Table IWB-2500-l', examination category C-A, item No. C1.10, volumetric examination of circumferential shell welds. Basis for Relief: One circumferential shell weld on each generator is inaccessible due to the upper steam generator support brackets (weld Nos. SGW-D1, -D2, -D3 and -D4). See attached drawing CH-M-2345-B for weld location. Also attached drawing CH-M-2345-B for weld location. Also attached are drawings showing arrangements of the support brackets. One weld on one generator will be examined on a "best effort" basis for the baseline inspection intervals in accordance with IWC-2411 and Table IWC-2500-1. Alternate Inspection: None 4 

                                         -279-SI-114.2
                             =          .. -    _

3 SQNP SI-114.2 Page 8 of 26 Rev. 7 REQUEST FOR RELIEF ISI-5 4 Component: Reactor Pressure Vessel Class: TVA Safety Class A Inspection Requirement: ASME Section XI, Table IWB-2500-1, examination category B-A, item No. Bl.20, 100-percent preservice baseline volumetric examination of lower head dollar weld, under conditions and with equipment and techniques equivalent to those expected to be employed during inservice inspection. Basis for Relief: TVA will employ automated remote inspection devices to examine most of the reactor vessel welds. These examinations will be conducted from the vessel inside diameter. However, the lower head weld on each reactor pressure vessel is partically inaccessible for exami-nation from the vessel inside diameter due to instrumentation tubes which penetrate the lower head (weld No. W01 see attached drawings). Portions of the weld can be examined from one side (as permitted by T-441.4, Article 4 of Section XI) and will 

   ,                                            include 100 percent of the examination volume in accordance with IWB-3511.1 of Section V.

1 These portions of the weld will be reexamined during the inservice intervals in accordance-with the examination category B-A of Table IWB-2500-1. , Alternate Inspection: A 100 percent baseline examination of the weld will be conducted from the vessel outside diameter. This will be accomplished by performance of a manual ultrasonic examination. A remote ultrasonic examination will be conducted from the vessel inside diameter on all accessible areas of the weld. 

                                                                 -280-                        SI-114.2

SQNP SI-114.2 Page 9 of 26 Rev. 7 REQUEST FOR RELIEF ISI-6 Component: Steam Generator (four per unit) Class: TVA Safety Class A (ASME Code Class 1) Inspection Requirement: ASME Section XI, Table IWB-2500-l', examination category B-D, item no. B3.140, volumetric examination of nozzle inside radius section on the primary side. Basis for Relief: Each steam generator consists of two integrally cast nozzles and two integrally cast manways. Relief from the inspection requirement above is based on EPRI report NP-4242, "Long-Term Inspection Requirements for Nuclear Power Plants", dated March 1986. This report presents a linear fracture mechanics analysis which predicts that cracks of size .025 inch (which is greater than the allowable reference flow size) will propagate to only slightly greater than one sixteenth of the nozzle wall thickness during the entire life of the plant. The report proposes that the nozzle inner radius be examined at least at half the plant life, and subsequently, at the regular code inspection intervals. The primary chamber radiation exposure dose rate is generally on the order of 30, rem /hr. As a result, individual " stay-time in the chamber would be limited to a degree where meaningful results from alternative surface and visual examinations could not be achieved. In addition, the presence of the interior surface austenitic stainless steel cladding which has a higher ductility than the base ASME-SA-216 grade WCC casting material raises the possibility of under cladding cracking which would not be visible with a surface examination. Alternate Inspection: TVA will initiate examination of the steam generator nozzle inner radius sections in accordance with the applicable Section XI Code during the second inspection interval. This will provide for examination of all the steam generator nozzle inner radii by the period ending at half the plant life. 

                                       -281-                   SI-114.2

SQNP SI-114.2 Page 10 of 26 Rev. 7 REQUEST FOR RELIEF ISI-7 Component: Reactor Coolant Loop Piping Welds (2) Class: TVA Safety Class A Inspection Requirement: ASME Section XI, IWB-2500-1, examination category B-J, item No. B9.10, volumetric examination of circumferential welds. Basis for Relief: Two circumferential shell welds in the reactor coolant loop piping (RC-23S1 and 

                                        -31S1, loops 3 ond 4) are located inside the reactor vessel shield wall and are inacces-sible for baseline and inservice examination (see attached drawings). Both welds have undergone shop radiographic examinations.

Since the baseline inspection serves as a reference to future inservice inspections and bot welds will be inaccessible for inservice inspections, the shop radiographic exami-nations coupled with the Section III hydrostatic test will provide adequate proof of integrity of the system welds. Inservice system leakage and hydrostatic testing will prove weld integrity during the life of the plant. Alternate Inspection: None e M l 

                                                       -282-                   SI-114.2

SQNP SI-114.2 Page 11 of 26 Rev. 7 REQUEST FOR RELIEF ISI-8 Component: Reactor coolant pumps (four per unit) Class: TVA Safety Class A Inspection Requirement: ASME Section XI, IWB-2500-1, examination category B-L-1, item No. B12.10, volumetric examination of pressure-retaining welds in pump casing. Basis for Relief: Each reactor coolant pump casing consists of a two piece welded type 304 SST casting. The present capability of ultrasonic testing is not sufficient to examinate cast material of this thickness and achieve meaningful results. Alternate Inspection: All four welds will be surface examined for the preservice baseline, and one weld will be surface examined during each inspection interval. I i 4 6 

                                       -283-                  SI-114.2

SQNP SI-114.2 Page 12 of 26 Rev. 7 REQUEST FOR RELIEF ISI-9 Component: Uncladded vessel welds in ferritic material less than two inches in thickness. Class: TVA Safety Classes A and B Inspection Requirement: Ultrasonic examination of welds, paragraph T-530 of ASME Section V, Article 5, 1977 Edition, Summer 1978 Addenda as referenced in paragraph IWA-2232 (c) of ASME Section XI 1977 Edition Summer 1978 Addenda. Basis for Relief: Paragraph T-533.2(a) of Article 5 of ASME Section V requires that the basic calibration block include a basic calibration hole drilled parallel to the contact surface. However, paragraph T-533.2(1-) permits the use of other calibration reflec; ors provided equivalent responses to that from the basic calibration hole are demonstrated. TVA currently uses five percent notches in lieu of side drilled holes. Although the use of the five percent notch cannot be shown to be equivalent in all cases to the applicable side-drilled holes, TVA considers that examinations are technically acceptable based on the calibration requirements of paragraph III-3430 of Appendix III to the 1977 Edition, Summery 1978 Addenda of ASME Section XI. The calibration notches for ferritic material are 10%t when t is less than .312" and , 

                          .104t .009t2 for material .312"-6" thick.

TVA's use of five percent notches is considered equivalent to the latest approved code examination techniques. Alternate Inspection: TVA proposes to continue the use of notches located on the I.D. and 0.D. surfaces at a nominal depth of 5%t as reference reflectors. l l l l l l l t -284- SI-114.2

SQNP SI-114.2 Page 13 of 26 Rev. 7 REQUEST FOR RELIEF ISI-10 Components: Reactor vessel flange to upper shell weld Class: TVA Safety Class A Inspection Requirement: ASME Section XI, Table IWB-2500-1~, examination category B-A, item No. Bl.30, volumetric from flange face Basis for Relief: The reactor vessel flange-to-upper shell weld is located behind the core barrel and is therefore inaccessible until the core barrel is removed. The vessel flange-to-upper shell weld is 41.9 inches below the flange face. Due to the location of the vessel flange-to-upper shell weld, TVA intends to address the weld as a reactor vessel shell weld. We have reviewed the Sequoyah Reactor Vessel Stress Report entitled Analysis of the Main Closure Including Core Support Ledge (Document No. 30616-1105) purposely to determine a fatigue usage factor for the vessel flange to shell weld. This analysis does not provide a usage factor specifically for the weld because the analysis considers weld and base material to be homogeneous and equal in elasticity, strength, and fatigue properties. Instead, the analysis provides usage factors at critical locations. The maximum fatigue usage factor in the vessel in the vacinity of the flange to shell weld as found in the above anlaysis is 0.00662 and this value can be conservatively used for the weld. We consider the valuve of 0.00662 to be extremely low compared to the code allowed fatigue usage factor of 1.0. We conclude that the distance ( ") from the flange face to the flange-to-upper shell weld coupled with present ultrasonic techniques and the very low fatigue usage factor that the flange-to-upper shell weld should be treated as a reactor vessel shell weld. Alternate Inspection: A remote ultrasonic examination of the weld will be conducted from the vessel inside diameter near the end of the inspection interval. 

                                        -285-SI-114.2

SQNP SI-114.2 Page 14 of 26 Rev. 7 n REQUEST FOR RELIEF ISI-11 (Withdrawn) 

                    -286-     SI-114.2

                                  ._ ._                       - ._.       . _ _ . . _ . _ _ _       . . . ~ _        ._.

SQNP SI-114.~2 Page 15 of 26 l Rev. 7 ' REQUEST FOR RELIEF ISI-12 Components: 1. Excess Letdown Heat Exchanger - Chemical and Volume Control System (CVCS)

2. Regenerative Heat Exchanger - CVCS Class: ASME Class 2 (TVA Safety Class B)'

Inspection Requirement: ASME Section XI, Table IWC-2500-1, Examination Category C-A, item Nos. C1.10, C1.20, and C1.30, volumetric examination of essentially 100 percent of each circumferential weld at gross structural discontinuities (head-to-shell and tubesheet-to shell weld). Examination Category C-C and C-E, Item No. C.3.10, surface examination of integrally welded support attachments. Basis for Relief: The excess letdown heat exchanger (ELHX) and the regenerative heat exchanger (RHX) were l scheduled for examination during the first inspection period in accordance with the In-service Inspection (ISI) Programs SI-114.1 and SI-114.2. The ELHX circumferential head weld ) was scheduled for ultrasonic (UT) examination in the first three-year inspection period. For the RHX there are six circumferential tubesheet- . to-shell welds were to be examined in the first 2 period by UT 1978 Addenda, Table IWC-2500-1 j Examination Category C-A requires a volumetric examination of 100 percent of the required welds. j The ELHX weld was examined ultrasonically from one - side for almost the entire length, except where the head's flanged nozzle-inlet and outlet welds interferred with the examination (see attached drawing). This allowed for an UT examination of 90 percent of the weld from the one side. From the opposite side, the head taper and head closure studs and nuts severly restricted access to the weld area and as a result no meaningful results could be obtained. The UT was performed on a best-effort basis and supplemented with a liquid-penetrant test (PT) over 100 percent of the weld 9 area. 1 In the case of the RHX when examinations were performed, the state-of-the-art UT examination l capabilities did not allow the achievement of meaningful results because of the component i fabrication processes involved.

-287- SI-114.2 1

y = s--,--r +mer+ - - - - , er--w-ne.-e-w,s--- - - , -

SQNP SI-114.2 Page 16 of 26 Rev. 7 REQUEST FOR RELIEF ISI-12 (Continued) The RHX is a centrifugally cast stainless steel, SA-351, CF8 vess'e1. In addition, the examinations.were hindered by supports which were essentially nonremovable from the area of two of the four welds because of the location in the heat exchanger room and their position on the vessel (see attached drawings). As a result, a PT was performed in place of the required UT. On the two restricted welds examined, only 75 percent of the weld lengths were surface examined because of supports covering part of the weld areas. In accordance with 10 CFR 50.2(v) of the Code of Federal Regulations, the RHX and the ELHX are defined to be within.the reactor coolant pressure boundary (RCPB) (ASME Class 1). Secondly, 10 CFR 50.55.2(c) further states: 

     "(2) Components which are connected to the reactor coolant system and are part of the reactor coolant pressure boundary defined in 50.2(v) need not meet these requirements (Class I requirements), provided: (ii) The component is or can be isolated from the reactor coolant system by two valves (both closed, both open, or one closed and the other open)._ Each open valve must be capable of automatic actuation and, assuming the other valve is v en, its closure time must be such that, in the event of postulated failure of the component during normal reactor operation, each valve remains operable and the' reactor can be shutdown and cooled down in an orderly manner, assuming makeup is provided by the reactor coolant makeup system only." As a result of this paragraph, the R7X, ELHX, and
the connecting piping to the Reactor Coolant System (RCS) and piping out to the containment isolation valves would be exempt from ASME Class 1 examination requirements.

Sequoyah Nuclear Plant units 1 and 2 ISI programs, SI-114.1 and SI-114.2, classify components for examination in accordance with Regulatory Guide 1.26, Revision 3. The guidelines of Regulatory Guide 1.26, paragraph C.1, classify components which are exempted by 10 CFR 50.55A(c) (2)ii from ASME Class 1 

                     -288-                  SI-114.2

SQNP SI-114.2 Page 17 of 26 Rev. 7 REQUEST FOR RELIEF ISI-12 (Continued) , examination requirements (such as the RHX,~ ELHX, and associated piping) as ASME Class 2 equivalent. The Sequoyah Final Safety Analysis Report (FSAR), Section 9.3.4.1.7, further describes the RHX, ELHX, and associated piping as "not required to function during a loss-of-coolant accident." Additional system design considerations are the following:

1. The ELHX is not used during normal plant operations and is isolated from the RCS by three valves, two normally closed gate valves and a check valve.
2. The RHX is isolated from the RCS by two check valves. Leakage from the RCS is prevented by the two check valves in series which were leak-tested during t he
 .             preoperational test program. Leakage also can be detected by monitoring for signs of system incoming leakage and by monitoring the RCS for signs of outgoing leakage (FSAR 6.3-26).
3. There are no leakage problems into the CVCS from the RCS because of the higher pressure at which the CVCS is generally a maintained (FSAR 6.3-27).

In addition, the inlet and outlet piping (one inlet and one outlet) associated with the ELHX is 1-inch nominal pipe size (NPS) and 3-inch NPS for the RHX. Both of these are less than the 4-inch NPS which, in accordance with IWC-1220(c), is exempt from the examination requirements in Table IWC-2500-1 (Class 2) of ASME Section XI. Also note.that the Winter 1980 Addenda, paragraph IWB-1220(b) (2) exempts from examination components and their connections in piping of 1-inch nominal pipe size and smaller. (Having one inlet and one outlet pipe, each 1-NPS or smaller). TVA also feels that the ALARA considerations to perform the liquid penetrant (PT) examina-tiont- on the ELJDC and RHX are excessive for 

                        -289-                           SI-114.2

SQNP SI-114.2 Page 18 of 26 Rev. 7 REQUEST FOR RELIEF ISI-12 (Continued) the benefits received from the inspections. The actual radiation exposures to perform the first. inspection period examinations alone were 2,200 MREM and 6,600 MREM respectively. Note that, in addition to the requirements in Examination Category C-A, Table IWC-2500-1, Examination Category C-H requires that all pressure retaining components be pressure tested in accordance with IWC-5000. This results in a system pressure test conducted each 10-year interval during a system func-tional test for the ELHX and a system hydro-static test performed each inspection interval for the RHX. Based on the component classifications as defined in 10 CFR 50.55, the nonsafety related function as stated in Sequcyah FSAR, the design of the heat exchangers and their supports preventing 100-percent examination coverage, and the ALARA considerations in view of the small benefit realized, TVA requests relief from the ASME Section XI examination requirements as shown in Table IWC-2500-1, Examination Category C-A, C-C, and C-E. Alternate Inspection: None. 

                                             -290-                       SI-114.2

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SQNP SI-114.2 Page 23 of 26 Rev. 7 REQUEST FOR RELIEF ISI-13 Components: Residual Heat Removal Heat Exchanger (two per unit) Class: TVA Safety Class B (ASME Code Class 2) Inspection Requirement: ASME Section XI, Table IWC-2500-1, examination category C-B, item no. C2.20, nozzles in vessels with over -inch in nominal wall thickness; surface and volumetric examination. Basis for Relief: Each heat exchanger consists of an inlet-outlet head chamber with one inlet and one outlet nozzle and two integrally attached support brackets. Volumetric examination of the nozzle-to-vessel welds and the nozzle inner radii is inhibited by the shell-to-tubesheet weld, shell-to-head weld, and the integral supports as shown in the attached sketches. Proximity of the welds and inner radius sections do not allow for the achievement of meaning results from a volumetric examinatiou. Alternate Examination: The nozzle-to-vessel welds will be examined utilizing a surface only examination. s i C l -295- SI-114.2

p O O NOTES i

f. REPLACE THE X IN THE WELD NUMBER WITH THE APPROPRIATE HEAT EXCHANGER NUMBER.

AC I' k IPLET ' RHRW-14-X INLET -RHRW-f6-X RHRW-19-Xq e , RHRW pw-18-X f x -. A g l; _J'_~ I _*.- 1 I O [ O [ 4 , ,,, g__ 2 1 79 op 

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 ;                                                                             SEQUOfAH NUCLEAR PLANT UNIT #1 & #2                            '
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                                         -298-

SQNP SI-114.2 Page 1 of 1 Rev. 7 T e APPENDIX H SUPPORT LOAD CRITERIA 

           -299-       SI-114.2

Typ.e . SQNP VS-Varitble Spring I-114.2 RS-Rigid Support Page 1 of 4 MS-Mechanical Snubber Rev. 7 Model RS-Rigid Strut Ril-Rigid Hanger Plant: SQNP Unit: 2 Page 1 of AFDH IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-AFDil-200 3 RS RH 2-AFDH-243 3 VS BE 401 760# 760# 0 1/4"-1" Type F Size 8 2-AFDii-244 3 RH BE 415 RS d Size 1 2-AFDif-245 3 VS BE 401 668# 687# 1/16".Up 5/16"-1" Type A Size 8 2-AFDil-246 3 VS BD 401 311# 319# 3/32" Up 11/32"-1" Type G Size 5 2-AFDil-247 3 RS BE 415 , RS Size 1 2-AFDil-248 3 RS RH 2-AFDil-249 3 RS Ril - 2-AFDil-250 3 RS Ril 2-AFDil-251 3 RS RH SI-114.2 SNP SUPPORT LOAD

SQNP.' Plant: SQNP Unit: 2 SI-114.2 Pzge 2 of AFDH Page 2.of 4 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING TiiERMAL ACCEPTABLE-TVA'S ISI'S CLASS TYPE HODEL STROKE liOT COLD HOVEMENT RANGE 2-AFDil-252 3 VS BE 401 531# 595# 3/32" Up 11/32"-1" Type G Size 7 2-AFDil-295 3 RS RH 2-AFDII-305 3 VS BE 401 1559# 1/16" Up 1594# 5/16"-1" Type B Size 11 2-AFDll-306 3 RS RH 2-AFDif-307 3 RS Rii 8 2-AFDil-308 3 RS RH w 2-AFDil-309 3 VS BE 401 144# 148# 1/32" Up 9/32"-1" Type B Size 2 2-AFDH-310 3 RS RH 2-AFDII-311 3 RS RH 2-AFDil-312 3 VS BE 402 1058# 1058# Slight

  • 1/4"-2 1/4"**

Type F Size 9 2-AFDil-313 3 RS BE 415 RS 1 Size 1 2-AFDil-331 3 RS RH

  • Thermal movement as stated by EN DES on BE 4180-2AFD sheet il3-31E as constructed.
 **No thermal movement accounted for.

SI-114.2 SNP SUPPORT LOAD

SQNP-Plant: SQNP Un i t.: 2 and 1 SI-114.2 Pagm 3 of AFDH Page 3 of 4 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT- RANGE 2-AFDil-342 3 VS BE 401 1222# 1255# 1/16" Up 5/16"-1" Type B Size 10 2-AFDil-343 3 RS Rif 2-AFDil-344 3 RS BE 415 RS j Size 2 2-AFDH-345 3 RS RH 2-AFDif-346 3 RS BE 415 RS s Size 1 t>> 2-AFDil-347 3 RS RH , 2-AFDil-348 3 RS RH 2-AFDH-349 3 VS BE 401 1055# 1055# Slight *- 1/4"-1"** Type F 4 Size 9 - 2-AFDil-350 3 RS BE 415 RS Size 1 , A l-AFDil-227 3 RS RH i 2-AFDil-229 3 MS BE 417 5" l'-5 5/8" l'-5 7/8" 1/4" 1/2"-4 3/4" PSA-3 

                                                                                                                                   ^

1-AFDil-229 3 RS RH 1 1-AFDil-242 3 RS RH

  • Thermal movement stated by EN DES.
      **No thermal movement accounted for.

SI-114.2 SNP SUPPORT LOAD 

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SQNP Plant: SQNP Unit: 2 SI-ll4.2 Pcge 4 of AFDH Page 4 of 4 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING TiiERNAL ACCEPTABLE 

         -TVA'S                      ISI'S    CLASS     TYPE   HODEL     STROKE   Il0T        COLD        MOVEMENT        RANGE l- AFDil-250      3          VS      GR SPRG         350#          350#         0            1/4"-1" Fig. 82 Type F Size 5 1 -AFDil-251      3          VS      GR SPRG         129#          129#         0            1/4"-1" Fig. 82 Type F Size 3 1-AFDil-252        3          RS      BE 415 Size 2 RS
1-AFDil-253 3 VS GR SPRG 293# 293# 0 1/4"-1" w Fig. 82 O Type F (N Size 5 I

l-AFDil-254 3 RS BE 415 Size 2 RS i SI-ll4.2SNPSUPPURTLOAD -

SQNP Plant: SQNP Unit: 2 SI-114.2 Paga 1 of CVCMH Page 1 of 1 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE Il0T COLD MOVEMENT RANGE ICVCMH-439 3 RS RH I ICVCMll-440 3 RS RH ICVCMH-441 3 RS RH 

                                                       ~

ICVCMH-442 3 RS RH ICVCMil-455 3 RS RH ICVCMH-457 3 RS RH I VJ O f-s 4 SI-114.2 SNP SUPPORT LOAD

Type SQNP RS-Rigid Support 

                                          'SI-114.2                                VS-Vcritble Spring Page 1 of 2                             HS-Mechanical Snubber Rev. 7                                  IA-Integrally-Welded Attachment Model RS-Rigid Strut RH-Rigid Hanger Plant: SQNP      Unit:  2 Page 1 of CSH IDENTIFIER         SAFETY         SUPPORT            DESIGN SETTING       THERMAL       ACCEPTABLE TVA'S           ISI'S    CLASS   TYPE MODEL      STROKE   HOT        COLD      HOVEMENT         RANGE 2-CSH-416    3      MS      BE 417     5"   2'-7 7/8"    2'-7 3/4"  1/8"          1/4"-4 5/8" PSA 3 2-CSH-417   3       RS      RS BE 415 Size 1 2-CSH-418   3       RS     RS BE 415 i                                          Size 4 W

O 2-CSil-419 3 RS RH U'1 2-CSil-420 3 RS RH 2-CSil-421 3 RS RH - 2-CSH-422 3 RS RH 2-CSii-423 3 RS RH 2-CSil-424 3 RS RH 2-CSH-425 3 RS RH 2-CSH-426 3 RS RH SI-114.2 SNP SUPPORT LOAD

SQNP Plant: S_QNP Unit: 2 SI-114.2 Pzga 2 of CSH Page 2 of 2 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS . TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-CSH-427 3 RS Ril 2-CSII-428 3 RS RH 2-CSil-429 3 RS RH 2-CSil-430 3 RS Ril 2-CSil-431 3 RS RH 2-CSil-432 - 3 R RH 2-CSil-433 3 RS Ril 2-CSil-434 3 RS Rif [ 2-CSll-435 3 RS RH O O 2-CSil-436 3 RS RH i 2-CSii-437 3 RS RH 2-CSil-438 3 RS RH 2-CSH-439 3 RS Size 1 RS BE 415 A 2-CSii-451 3 RS RH 2-CSil-452 3 RS BE 415 RS Size 1 A b SI-114.2 SNP SUPPORT LOAD i i Y 

                                                                                     '! J

_ r 

                                      ~
                                *7 ^           .05 e                                                                                                    I
                            ~
                                              >/*                                                Type SQNP                                        RS-Rigid Support j                    SI-114.2                                    VS-Veritble Spring
                                    ,                Page 1 of 15-                ,              MS-Mechanical Snubber Rev. 7
                                                 '                              ~

IA-Integrally Welded

Attachment:

HS-Hydraulic Snubber Model RS-Rigid Strut RH-Rigid Hanger Plant: SQNP Unit: 2 

                                                                                                                'Page 1 of CCH IDENTIFIER            SAFETY            SUPPORT                DESIGN SETTING        THERMAL         ACCEPTABLE TVA'S           IS1'S       CLASS    TYPE    MODEL       STROKE     HOT        COLD MOVEMENT           RANGE 2-CCll-4-158    3       RS        RH 1-CCll-400      3       VS        BE -Sp rg.         5604#         5745#       1/16" Up        1/4"-15/16"
Fig. 401 Type B.

Size 15 1-CCll-401 3 RS Rif i ' to kl-CCll-402 3 IIS BE 411 5" l'-8 1/2" 5/10" Size 1 l'-8.19" 2 1/16" - 6 1/4"- [h ' ' 1-CCll-403 3 HS BE 417 6" 4'-9 7/8" 4'-9 3/4" 1/8" 1/4"-5 5/8" PSA 10 1-CCII-404 3 VS Grinnell 1994# 1882# 1/8" Down 1/4"-7/8" Sprg. Fig 82 "F" Size 12 1-CCH-405 3 VS BE 3943# 3837# 1/16" Down 1/4"-15/16" Sprg. Fig 401 Type B Size 14 Support identifiers 1-CCll-400 through 1-CCH-769 are supports to be examined with the Unit 2 ISI sample. SI-114.2 SNP SUPPORT LOAD

i SQNP , Plant: SQt;P Unit: 2 SI-114.2 Page 2 of CCH Page 2 of.15. Rev. 7 l' LIEN 51F1' Elk SAFETY SUPPORT DESIGN SETTING TilERMAL ACCEPTABLE. TVA'S I.91'S CLASS TYPE MODEL STROKE ' 110T COLD MOVEMENT RANCE 1-CCil-413 3 VS Gr. Sprg. 3000# 2925# 1/16" Down 1/4"-15/16" Fig 82 Type B Size 13 1-CCH-414 3 VS Gr. Sprg. 2571# 2421# 1/8" Down 1/4"-7/8" Fig 82 Type B Size 13 1-CCil-415 3 IIS BE 411 5" 3 7/16" 3 1/2" 1/16" 1 5/16"-5 3/4" Size 2's 1-CCll-416 3 VS Gr. Sprg. 8327# 8139# 1/16" Down 1/4"-15/16" Fig 82 Type B Size 16

d O

1-CCll-420 3 RS RH CD 1-CCll-421 BE 411 5" 3 HS 3 5/16" 3 9/16" 1/4" 1 5/8"-5 7/8" Size 3k" 1-CCH-422 3 RS RH 1-CCil-423 3 RS RH a 1-CCli-424 3 RS R'I 

                        *1-CCll-425   3      RS    RH 1-CCll-426  3      RS    RH 1-CCH-428   3      RS    RH
  • 1 -CCII-454 3 RS RH 1-CCil-455 3 RS Ril l <

SI-114.2 SNP SUPPORT LOAD i

SQNP Plant: SQNP . Unit: 2  ; SI-114.2 ,P ge 3 of CCH. Page 3 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 1-CCII-458 3 RS RH 1-CCil-459 3 RS RH 

             *1-CCil-476     3      RS 1-CCll-482    3      RS     Rif 1-CCil-483   3       RS     RS 1-CCll-489   3       RS     RH 1-CCll-490   3       RS     RH 1 -CCII-491  3       RS     RH 1-CCH-492   -3       RS     RH 8

gg 1-CCil-492A 3 RS RH i 1-CCll-493 3 RS RH 1-CCH-494 3 VS BE Sprg. 5124# 4983# 1/16" Down 1/4"-15/16" Fig 401 Type B Size 15 1-CC11-495 3 RS RH 1-CCH-496 3 RS RH 1-CCil-545 3 RS RH 1-CCH-545A 3 RS RH 1-CCH-546 3 RS RH SI-114.2 SNP SUPPbRT LOAD

a 

                                                                     'SQNP Plant: SQNP      Unit: 2                                          SI-114.2                    Pagn 4 of CCH' Page 4 of 15                      ,

Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING TIIERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE Il0T COLD HOVEMENT RANGE l-C011-547 3 RS Ril 1-CCll-548 3 RS RH 1-CCll-549 3 RS RH 1-CCll-550 3 RS RH 1-CCil-551 3 RS RH 1-CCll-552 3 RS Ril 1-CCll-553 3 RS Ril 1-CCll-554 3 RS RH 1-CCll-555 3 RS Ril I E 1-CCll-556 3 RS RH O 1-CCll-557 3 RS RH 1-CCil-557A 3 RS BE 415 RS Size 1 1-CCil-558 3 RS RH 1-CCll-574 3 RS Ril 1-CC11-576 3 RS Rii 1-CCll-577 3 RS Ril 1-CCll-578 3 RS Fig 415 RS Size 4 SI-114.2 SNP SUPPORT LOAD l l

SQNP Plant: SQNP Un i t. : _2 SI-114'.2 - Pzgr 5 cf CCli Page 5 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING - TilERMAL ACCEPTABLE _TVA'S ISI'S CLASS TYPE MODEL STROKE 110T COLD MOVEMENT RANGE I-CCll-5 79 3 RS BE 415 RS Size 7 1-CCll-580 3 RS Ril 1-CCil-581 3 RS Rif 1-CCil-582 3 RS RH 1-CCll-583 3 VS Gr. Sprg. 2017# 1/8" Up Fig 82 2130# 3/8"-1" Type F Size 12 1-CCH-584 3 RS RH E ca 1-CCll-585 3 RS RH 

 '              1-CCH-586        3        RS    BE 415 RS Size 1 1-CCil-587       3        RS    RH 1-CCH-588        3        RS    RH 1-CCH-589        3        RS    RH                                                               -

1-C011-590 3 RS RH 1-CCH-591 3 RS RH 1-CCil-592 3 RS RH 1-CCil-593 3 RS Ril SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2- Pag 2'6 cf CCil Page 6 of 15 Rev. 7. IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERHAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE Il0T COLD HOVEMENT RANGE l-CCil-594 3 RS RH i 1-CCil-595 3 RS BE 415 I RS Size 3 } 1-CCil-596 3 RS Ril i 1-CCll-597 3 RS RH i 1 1-C011-598 3 RS RH i ! l-CCll-599 3 RS RH i , La 1-CC11-600 3 RS Gr. Sprg 2144# 2234# 3/32" Down 1/4" - 29/32" ! pJ . Fig 82 e Type F f Size 12 I l-CCll-601 3 RS BE 415 RS j Size 3 1-CCll-602 3 RS Ril 1 1-CCH-603 3 RS Ril i l 1-CCll-604 3 RS BE 415 j P.S - Size 1 ] l-CCII-605 3 RS Ril , 1-CCil-606 3 RS Ril i j 1-CCII-607 3 RS Rif 4 SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 :P g2 7 cf CCH Pag 2 7 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE l-CCH-608 3 RS RH 1-CCH-609 3 RS RH 1-CCH-609A 3 VS Gr. Sprg. 587# 601# 1/16" Up 5/16"-1" Fig 82 Type F Size 7 1-CCil-648 3 RS RH 1-CCll-649 3 RS RH 1-CCH-650 3 RS RH 1-CCil-651 3 RS RH 1-CCH-652 3 RS _h_ RH T l-CCH-653 3 RS RH 1-CCil-653A 3 RS RH 1-CCH-654 3 RS BE 415 RS Size 2 1-CCil-655 3 RS RH 1-CCil-656 3 RS RH 1-CCll-657 3 RS RH 1-CCII-658 3 RS BE 415 RS Size 1 SI-114.2 SNP SUPPORT LOAD 

                                                                                            ~SQNP                       .

Plant: SQNP Unit: 2 SI-114.2 P ga 8 cf CCH - Page 8 of 15. Rev 7 

    ~~~

IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL- ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE s 1-CCH-663 3 RS Ril 1-CCH-664 3 RS RH 1-CCil-665 3 RS RH 1-CCll-677 3 RS BE 415 RS

Size 3 1-CCH-678 3 VS Gr. Sprg. 4153# 4253# 1/16" Up 5/16"-1" Fig 82

] Type B Size 14 1 ! 1-CCil-679 3 RS RH N 1-CCH-700 3 RS RH 

 +'

1-CCH-701 3 RS RH i 1-CgH-702 3 RS RH 4 1-CCH-703 3 RS RH l 1-CCII-707 3 RS RH l l-CCH-711 3 RS RH ! l-CCH-712 3 RS BE 415 , 1 RS J Size 1 1-CCH-713 3 RS BE 415 RS Size 2 SI-114.2 SNP SUPPORT LOAD

SQNP P1 ant: SQNP Unit: 2 Page 9 of.CCH SI-114.2 . Page'9 of 15 Rev. 7-IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL 

  ~ TV
    'A'S                    ISI'S    CLASS   TYPE MODEL     STROKE    HOT        COLD       MOVEMENT ACCEPTABLE RANGE 1-CCH-714          3       RS    RH 1-CCH-715          3      RS     RH 1-CCH-716         3       RS     RH                                                                     '

1-CCll-717 3 RS RH 1-CCH-718 3 RS RH 1-CCH-719 3 VS Gr. Sprg. 2007# 2106# .1/9" Up 11/32"-1" Fig 82 Type F Size 12 1 u l-CCH-720 3 MS BE 416 6" l'-11 7/16" l'-11 3/8" 1/16" 1/4"-5 11/16" @9 PAS 10 1-CCil-721 3 RS RH 1-CCH-722 3 RS BE 415 RS Size 1 1-CCH-723 3 RS RH 1-CCH-724 3 RS RH

  • 1-CCH-725 3 VS Gr. Sprg. 2076# 2189# 1/8" Up' 3/8"-1" Fig 82 Type F Size 12 1-CCH-726 3 RS RH SI-114.2 SNP SUPPORT LOAD

SQNP _ Plant: SQNP Unit: 2 SI-114.2 Pege 10 cf CCH. P g2 10 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD HOVEMENT RANGE 1-CCil-727 3 RS BE 415 RS - Size 1 1-CCil-728 3 MS BE 416 5" 1/16" 5/16"-4 3/4" PSA 3 Compression 1-CCil-729 3 RS RH 1-CCil-730 3 RS RH 1-CCll-731 3 RS BE 415 , RS Size 3 i g 1-CCil-732 3 RS Ril

00

! p- 1-CCil-733 3 MS BE 416 4" l'-3 5/8" l'-3 5/8" .06 1/4"-3 3/4" !  : PSA 1 l i 1-CCil-734 3 VS Gr. Sprg. 781# 799# 1/16" Up 5/16"-1" l Fig 82 j Type B Size 8 i 1-CCil-735 3 RS RH 1-CCH-736 3 RS BE 415 RS i Size 2 1-CCil-737 3 RS BE 415 RS l Size 2 1-CCil-738 3 RS BE 415 Size 1 4 ! SI-114.2 SNP SUPPORT LOAD 

          .. .          -.- .       . . _  . _    ~                      .

SQNP Plant: SQNP Unit: 2 SI-114.2 Pega 11 cf CCH Page 11 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAI ACCEPTABLE TVA'S ISI'S CLASS TYPE- MODEL STROKE HOT COLD MOVEMENT RANGE l-CCll-739 3 RS BE 415 RS Size I l-CCH-740 3 RS RH 

,                     1-CC11-741            3        RS     RH 1-CCH-742             3         RS     Ril                                                            ^

1-CCII-743 3 RS Rif 1-CCil-744 3 RS RH i 

   ,                 1-CCH-745            3         RS      RH
\ Lu
  ]                  l-CCII-746           3         RS      RH l   t j                     1-CCII-747           3         RS      RH 1-CCH-748            3         RS      RH      ,

1-CCH-749 3 RS RH j 1-CCH-750 3 RS RH i 1-CCil-751 3 RS RH j 1-CCll-752 3 RS RH 1-CCH-753 3 MS BE 416 6" 2'-0 7/16" i 2'-0 5/8" 3/16" 7/16"-5 3/4" PSA 10 ! l-CCH-754 3 RS Rif 1-CCH-755 3 RS RH SI-114.2 SNP SUPPORT LOAD i

SQNP . Plant: _SQNP Unit: 2 SI-114.2 Pcge 12_of'CCH Page 12 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE NODEL STROKE - HOT COLD HOVEMENT RANGE 1-CCII-756 3 RS RH 1-CCH-757 3 RS RH 1-CCH-758 3 RS RH 1-CCll-760 3 MS BE 416 5" l'-4 7/8" l'-5 3/16" 5/16" 9/16"-4 3/4" Size PSA 3 1-CCH-761 3 RS BE 415 RS Size 1 1-CCH-762 3 MS BE 417 6" l'-7 13/16" l'-8 8/3" 9/16" 13/16"-5 3/4" PSA 10 LA . 65 1-CCil-763 3 VS BE 402 - 924# 1016# 1/4" Up 1/2"-2 1/4" 5 Tne A Size 9 1-CCil-764 3 MS BE 417 4" 3'-0 1/8" 3'-0 1/16" -1/16" 1/4"-3 11/16" PSA 1 1-CCH-765 3 VS Gr. Sprg. 701# 767# 1/4" Up 1/2"-1" Fig 82 Type C Size 8 1-CCil-766 3 VS Gr. Sprg. 314# '361# 3/8" Up 5/8"-1" Fig 82 Type B Size 5 1-CCH-767 3 VS Gr. Sprg. 955# 1047# 1/4" Up 1/2"-1" Fig 82 Type B Size 9 d 

                                                                                                   , SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 .SI-114.2 Peg 2 13 ef CCH-Pzge 13 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 1-CCH-768 3 MS BE 417 5" 7'-1 3/4" 7 '. .? " 1/4" 1/2"-4 3/4" PSA 3 1-CCII-769 3 MS PSA 1 4" l'-7/8" l'-1" 1/8" 3/8"-3 3/4" 2-CCH-60 3 VS Gr. Sprg. 271# 283# 1/4" Up -1/2"-2 1/4" Fig 268 Type ~F Size 5 2-CCII-61 3 RS RH 2-CCH-62 3 MS PSA 1 4" 13 1/2" 13" 1/2" 1/4"-3 1/4" 2-CCH-63 3 RS RH 2-CCII-64 3 RS RH .D 2-CCH-65 3 RS RH 2-CCH-66 3 RS RH 2-CCil-67 3 RS RH , 2-CC11-68 3 RS RH 2-CCH-69 3 RS Rif 2-CCII-70 3 RS RH 2-CC11-71 3 RS RH . 2-CCH-72 3 RS RH 2-CCH-73 3 RS RH 2-CCH-74 3 RS RH 

                                     .                                               SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Peg 2 14 cf CCN Pcge 14 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE ' HOT COLD MOVEMENT RANGE 2-CCH-75 3 RS RH 2-CCH-76 3 RS. RH 2-CCH-77 3 RS RH 2-CCH-78 3 RS RH 

   .             2-CCH-800    3      RS    RH 2-CCH-801    3      RS    RH 2-CCH-802    3      RS    RH 2-CCH-803    3      RS   .RH 1

(*) 2-CCH-805 3 RS RH N 9 2-CCll-806 3 RS -RH 2-CCH-807 3 RS RH 2-CCH-808 3 RS RH 

                                                   ~

2-CCil-809 3 RS RH 2-CCII-810 3 RS RH 2-CCH-811 3 RS RH 2-CCH-812 3 RS RH 2-CCH-813 3 RS RH 2-CCH-814 3 RS RM 2-CCil-815 3 RS RH 4 f SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pag 2 15 of CCH Page 15 of 15 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA*S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-CCH-816 3 RS RH 2-CCH-817 3 RS RH 2-CCH-844 MS BE 416 5" 20 1/2" 20 7/8" 3/8" 5/8"-4 3/4" PSA 3 2-CCH-845 MS BE 416 5" l'-9 5/16" l'-8 7/8" 7/16" 1/4"-4 5/16" PSA 3 2-CCH-4-158 3 RS RH t La N 7 ' 4 3 e F 4 SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 .SI-114.2 Pcg2 1' ef ERCW Page 1 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT' RANGE 2-ERCMI 1 3 RS RH 2-ERCMI-5-2 3 RS RH 2-ERCWH-5-3 3 RS RH 2-ERCMI-5-4 3 RS RH 2-ERCMI-5-18 3 RS RH 2-ERCMI-5-20 3 RS RH 2-ERCMI-5-20A 3 RS RH 2-ERCMI-5-20B 3 RS RH I 2-ERCMI-5-20C 3 RS RH V 2-ERCMI-5-25A 3 RS RH 2-ERCMi-5-25B 3 RS RH 2-ERCMI-5-26 3 RS RH 2-ERCMI-5-27 3 RS Ril 2-ERCMI-5-28 3 RS RH 2-ERCMI-5-29 3 RS RH 2-ERCMi-5-30 3 RS RH 2-ERCMI-5-31 3 RS Rif 2-ERCMI-5-32 3 RS RH 2-ERCMI-5-33 3 RS RH a SI-114.2 SNP SUPPORT LOAD

SQNP-Plant: SQNP Unit: 2 SI-114.2 Pcg2 2 of ERCh' Page 2 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-ERCMI-5-34 3 RS RH 2-ERCW-5-39 3 RS RH ' 2-ERCMI-5-40 3 RS RH 2-ERCMI-2-64 3 RS RH 2-ERCMI-2-65A 3 RS RH 2-ERCW-2-65B 3 RS RH 2-ERCMi-2-66 3 RS RH 

,               2-ERCMi-2-67  3       RS    RH G3 N                2-ERCMI-3-39  3       RS    RH W

2-ERCMI-3-40A 3 RS RH 2-ERCMI-3-40B 3 RS RH 2-ERCMI-3-41 3 RS RH 2-ERCMI-3-42A 3 RS RH 2-ERCMI-3-42B 3 RS Rif ' 2-ERCMI-3-43 3 RS RH 2-ERCMI-3-44 3 RS Ril 2-ERCMI-3-46A 3 RS RH 2-ERCMI-3-46B 3 RS Rif 2-ERCMI-3-46C 3 RS Rif SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit.: 2 SI-114.2 Peg;s 3 cf ERCW Paga 3 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE-TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-ERCMI-3-57 3 RS RH 2-ERCMI-3-58 3 RS RH 2-ERCMi-3-59A 3 RS RH 2-ERCMI-3-59B 3 RS RH 2-ERCMI-3-59C 3 RS RH 2-ERCMI-3-59D 3 RS RH 2-ERCMi-3-68 3 RS RH 2-ERCMi-3-70 3 RS RH t g 2-ERCMi-3-76 3 RS RH P 1 2-ERCMI-3-77 3 RS RH 2-ERCMI-4-50 3 RS RH 2-ERCMI-4-51 3 RS RH 2-ERCMI-4-52 3 RS RH 2-ERCMi-5-2A 3 RS RH 2-ERCMi-5-2B 3 RS RH - 2-ERCMI-5-3A 3 RS RH 2-ERCMI-5-3B 3 RS RH 2-ERCMI-25-312 3 Hor. MS PSA 3 5" NA 17" .17C .42"-4.71" 

                                                                                         .04T Ver. MS PSA 3      5"   NA            17"          .02C           .27"-4 3/4" SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pag 2 4'ef ERCW-Page 4 of 16 i Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE - TVA'S ISI's CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-ERCWil-25-340 3 llor. MS PSA 3 5" NA 17" .02C .27"-4.59" 

                                                                                                               .16T Ver. MS PSA 3            5"   NA            17"           .02C          .27"-4 3/4" l

2-ERCWlf-25-368 3 Hor. MS PSA 1 4" 12 29/32 13" .02C .27"-3.75" Ver. MS PSA 3 5" NA 17" .16T . 25"-4.59" 

                                  ,                                                                           .02C-          .27"-4.75" 2-ERCWH-25-396 3          Hor. MS PSA 3             5"                 17 5/8" NA                         1/16C         5/16"-4 3/4" Ver. MS PSA 3             5"   NA            16 3/4"      1/16C          5/16"-4 3/4" 2-ERCWit-25-441 3         MS             PSA 3      5"   NA            17"
5/8C 7/8"-4 3/4" 2-ERCWH-25-442 3 MS PSA 3 5" NA 17" 5/16T 1/4"-4 7/16"

), , 2-ERCWH-25-445 3 MS PSA 3 5" NA 17" .23T .25"-4.52" ) o j y' 2-ERCWit-25-446 3 MS PSA 3 5" NA 17" 5/16T 1/4"-4 7/16" }

  • 2-ERCWH-2 2 RS RH 2-ERCWii-3 2 RS RH t

l 2-ERCWH-4 2 RS RH l $ 2-ERCWH-5 2 RS RH I 4 l 2-ERCWH-6 2 RS RH l 2-ERCWil-7 2 RS RH l 2-ERCWH-8 2 RS RH i {, 2-ERCWH-9 2 RS RH 4 2-ERCWH-10 2 RS .RH i A 1 SI-114.2 SNP SUPPORT LOAD 4

_. .. ._..-- _. _ ~ _ _ _._ SQNP Plant: SQNP Unit: 2 SI-114.2 Peg 2 5 cf ERCW L Page 5 of 16 

 ;                                                                                           Rev. 7 i

j IDENTIFIER SAFETY SUPPORT DESIGN SETTING . THERMAL - ACCEPTABLE j TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-ERCW-11 2 RS RH 2-ERCW-12 2 RS RH-1 

 !                                   2-ERCW-13  2      RS    RH j                                     2-ERCMi-14 2      RS    RH j                                     2-ERCMI-15 2      VS    Gr.               408#          429#          1/8 Up          3/8"-1" j                                                             Fig 82 i                                                             Type B j                                                             Size 6                                                    -

j 2-ERCMI-18 3 RS RS BE 415 Size 1 j i 2-ERCMI-19 3 RS RH te h 2-ERCW-20 3 VS Gr. 623# 665# 3/16'Up 7/16"-1" j Fig 82 Type A h ( Size 7 ! 2-ERCMI-21 3 RS RH j 2-ERCMI-22 3 RS RH , i i l 2-ERCMI-23 3 RS RH t a i 1-ERCW-52 3 VS Gr. 2288# 2276# .01" Up & Dn .26" .99" l Fig 82 2264# l Type B Size 13 . 1-ERCWH-53 3 RS RH l SI-114.2 SNP SUPPORT LOAD

i SQNP . , Plant: SQNP Unit: 2 SI-114.2 . Pag:e 6 ef ERCW-- j Page 6 of 16 Rev. 7 i IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE I 1-ERCW-54 3 RS RH

1-ERCW-55 3 RS RH 1-ERCW-56 3 RS RS BE 415 Size 3 1-ERCW-57 3 RS RH I

1-ERCW-58 3 MS PSA 10 6" l'-0 1/2" 2'-0 3/8" 1/8T 1/4"-5 5/8" PSA 10 6" 2'-0 1/2" 2'-0 3/8" 1/8T 1/4"-5 5/8" l ) 1-ERCW-59 3 RS RH 1-ERCW-60 3 RS RS j BE 415 l j Size 1 N f 1-ERCW-61 3 RS RH j 1-ERCW-62 3 RS RH ~ 1-ERCW-63 3 RS RH 1-ERCW-64 3 RS RH 1-ERCW-65 RS RH 1 1 1-ERCW-66 3 RS RH 

;                              1-ERCW-67            3          RS     RS BE 415 Size 2 l                              1-ERCWH-68           3          RS     RH l

i SI-114.2 SNP SUPPORT LOAD

SQNP-Plant: SQNP Unit: 2 SI-114.2 Peg 2 7 ef ERCW Page 7 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE l-ERCWH-69 3 RS RS BE 415 Size 4' l-ERCW-70 3 RS Ril l-ERCW-71 3 RS RH 1 -ERCW-72 3 RS RH 1-ERCWH-73 3 RS RH 1-ERCWil-74 3 VS Gr. 8247# 8153# 1/32" Dn 1/4"-31/32" Fig 82 Type B Size 16 to 1-ERCW-75 3 RS RH 1-ERCW-76 3 RS RH 1-ERCWH-77 3 RS RH 1-ERCWH-79 3 RS RH 1-ERCW-80 3 RS RH 1-ERCWH-81 3 RS RH 1-ERCWH-82 3 RS RH 1-ERCW-83 3 RS RH 1-ERCWH-84 3 RS RH 1-ERCWH-121 3 RS RH l SI-114.2 SNP SUPPORT LOAD

y SQNP Plant: SQNP Unit: 2 -SI-114.2 Pcge 8 ef ERCW Page 8 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE l-ERCMI-122 3 RS RH 1-ERCMI-123 3 RS RH 1-ERCWH-124 3 RS RH 1-ERCWil-125 3 RS RH 1-ERCWH-126 3 RS RH 1-ERCWil-127 3 RS RH - 1-ERCMI-128 3 RS RS BE 415 Size 6 i 1-ERCWil-129 3 RS Rif .D 

'               l-ERCWil-130 3      RS    RS BE 415, Size 3 1-ERCMI-131  3      RS    RH 1-ERCWH-132  3      RS    Rll 1-ERCWH-133  3      RS    RH 1-ERCMI-134  3      RS    RH 1-ERCWH-135  3      RS    RH 1-ERCWif-136 3      VS    Gr.            3224#        3272#         .04 Up        .29" .97" Fig 82         3308#                      .03 Dn Type B.

Size 13 1-ERCWH-137 3 RS RH ' SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Peg 2 9 cf.ERCW Page 9 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT

  • DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD H0VEMENT RANGE
l-ERCMi-137A 3 RS RH i

1-ERCVH-138 RS RH I l-ERCMI-139 3 RS RH 1-ERCWH-140 3 RS RH

1-ERCMi-142 3 RS RH i

1-ERCMi-143 3 RS RS l BE 415 Size 4 1 1-ERCMI-144 3 RS RH 1-ERCMi-145 3 RS RH

  • i O 1-ERCWH-146 3 RS RH j

j 1-ERCMI-147 3 RS RH i 1-ERCMi-160 3 RS RH , 1-ERCMi-161 3 RS RH 1-ERCMi- 162 3 RS RH j 1-ERCMi-163 3 RS RH ] l-ERCMI-164 3 RS RH I i 1-ERCWii-165 3 RS RH 1-ERCMI-166 3 RS RH I l-ERCMI-167 3 RS Rif J 

,                                                                                                                                       SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Paga 10 of ERCW: Page 10 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE l-ERCWil-168 3 RS RH 1-ERCWH-190 3 RS RH 1-ERCW-191 3 RS -RH 1-ERCW-193 3 RS RH 1-ERCWH-194 3 RS RH 1-ERCWH-195 3 RS RH 1-ERCWH-196 3 RS RH 1 -ERCW-197 3 RS RH 1-ERCW-198 3 RS RH r 1-ERCWH-204 3 RS RH 1-ERCW-205 3 RS RH 1-ERCW-206 3 RS Rif 1-ERCWH-207 3 RS RH 1-ERCWH-208 3 RS RH 1-ERCWH-209 3 RS RS BE 415 Size I l-ERCWH-210 3 RS RS BE 415 Size I l-ERCW-211 3 RS RH SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Peg 2 11 ef ERCW Peg 2 11 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE l-ERCWH-212 .3 RS RH 1-ERCWH-213 3 RS RH 1-ERCWH-214 3 RS RH 1-ERCk11-215 3 RS RH 1--ERCh11-216 3 RS RH 1-ERChil-217 3 RS RH 1-ERCh11-218 3 RS RH 1-ERChil-219 3 RS RH j 1-ERCWH-220 3 RS RH e 00, 1-ERCh11-221 ,_ . 3- RS RH 1-ERCWH-222 3 RS RH 1-ERCh11-223 3 RS RS BE 415 Size 6 1-ERCh11-224 3 RS RH 1-ERCWH-224A 3 RS RH 1-ERChil-225 3 RS RS BE 415 Size 3 1-ERCWH-226 3 RS RH a SI-114.2 SNP SUPPORT LOAD 

                                                                                                         ,m_

SQNP Plznt: SQNP Uai t.: 2 .SI-114.2 Peg 2.12 cf ERCW Page 12 of 16 Rev. 7 ~ IDENTIFIER SAFETY SUPPORT DESIGN SETTING - THbkHAL, TVA*S ISI'S CLASS TYPE 

                                                                                                                                                                                  ' ACCEPTABLE MODEL      STROKE                            HOT                       COLD             MOVENINT RANGE l-ERCW-227           3           RS             RS                                                                                                                                         '

BE 415 Size 7 " ' a 

                                                                                                                             '                                  y                                    <

s 1 - 1-ERCW-227A 3 RS RS-s ' 

                                                                                                                                                                               .t       i         .v:

i' EE 415 \ , Size 7 _ , 

                                                                                                 '                                                                                % .* r I-ERCW-228           3           RS             RH             '
                                                                                             ;- t                     ,
                                                                                                                                                                                  /          '

( , ..s 3, w_, , 1-ERCW-229 3 RS ' RH N_ s 

                                                                                                                                               }s. ".

s_\s .? 

                                                                                                                                                     ~
                                                                                                     ~'                                     '

1-ERCW-233A 3 RS RH ' * '

  • s n '

s , a s (fN/ 1-ERCW-233B ' 3 - _ RS ' , , RS J, 

                                                                                                                                                                    -J,-

a.BE 415 . Size 3 - ' 

                                                                                        ,                                                            .t         .

1./-/ o .. .. d _ 1-ERCW-234 3 ' RS 

                                              ,                 RH                                                                ,

(A

  • s Y 1-ERCW-235 3 RS, RN s
                                                                                                                                       ~
                                                                                                                                           't 1-ERCW-235A          3          $4 '            RH                                                                             ',

1-ERCW-236 3 RS RH 

                                                                  !                                                                     ~

1-ERCW-237 3 RS RS . , BE 415 Size 4 1-ERCW-238 -3 RS RH 1-ERCW-239 ' 3 RS RS BE 415 Size 2 1-ERCW-240 3 RS RH J SI-114.2 SNP SUPPORT LOAD

SQNP ., Plant: SQNP Unit: 2 SI-114.2- Pcge 13 ef ERCW Page 13 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE 

 ~iVA15            ISI'S    CLASS   TYPE HODEL    STROKE  HOT        COLD       HOVEMENT          RANGE l-ERCMI-241  3      .RS    RS BE 415 Size 2 1-ERCWit-242 3       RS    RH 1-ERCMI-243  3       RS    RH 1-ERCMI-262  3       RS    R!!

l-ERCMI-263 3 RS RH 1 -ERCMI-264 3 RS RS BE 415 Size 1 e W 1-ERCMI-265 3 RS RH W f 1-ERCMI-266 3 RS RH 1-ERCMi-267 3 RS RH 1-ERCMI-268 3 RS RH 1-ERCW-269 3 RS RH = l-ERCMi-270 3 RS RH 1-ERCWH-271 3 RS RH l-ERCMI-272 3 RS RH 1-ERCMI-273 3 RS RH 1-ERCMI-274 3 RS PH , 1-ERCMI-275 3 RS RH a SI-114.2 SNP SUPPORT LOAD

SQEP Plant: SQNP Unit: 2 SI-114.2 Pcge 14 cf ERCW Page 14 of 16 

                                                                                        ~

Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL- ACCEPTABLE TVA'S ISI'S CLASS TYPE HODEL STROKE HOT COLD MOVEMENT RANGE 1-ERCMI-276 3 RS RH 1-ERCMI-277 3 RS RH 1-ERCMi-300 3 RS RH 1-ERCMI-301 3 RS RH 1-ERCMI-302 3 RS RH 1-ERCWH-342 3 RS RH 1-ERCWi-343 3 RS RH 1-ERCMi-344 3 RS RH 1-ERCWH-350 3 RS RH vu 

  '                   1-ERCMI-351  3       RS     RH 1-ERCWil-352 3       RS     RH 1-ERCWil-357 3       RS     RH 1-ERCWil-358 3       RS     RS BE 415                                                      -

Size 1 1-ERCWil-359 3 RS RS BE 415 Size 1 1-ERCWil-360 3 RS RH 1-ERCWil-361 3 RS RS BE 415 j Size 1 4 SI-114.2 SNP SUPPORT LOAD i

SQNP Plant: SQNP Unit: 2 SI-114.2 Pcg2 15 cf ERCW. Page 15 of 16 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE 

     , TVA'S           ISI'S    CLASS  TYPE MODEL    STROKE HOT        COLD        MOVEMENT          RANGE l-ERCWil-362 3      RS    Rll 1-ERCMI-363  3      RS    Rii 1-ERCMI-364  3      RS    R!!

1-ERCWit-365 3 RS RH 1-ERCWil-366 3 RS RS BE 415 Size 1 1-ERCMI-367 3 RS RH 1-ERCWil-368 3 RS RH 1 1-ERCMI-370 3 RS RH CA) 1-ERCWil-371 3 RS RH 1-ERCWH-372 3 RS RS BE 415 Size 1 1-ERCWil-373 3 RS RH 1-ERCWil-374 3 RS RH 1-ERCWil-375 3 RS RH 1-ERCWii-376 3 RS RH 1-ERCWil-377 3 RS RS BE 415 Size 1 1-ERCWil-378 3 RS Rif 4 SI-114.2 SNP SUPPORT LOAD i l

SQNP. Plant: SQNP 1]ng: 2 SI-114.2 Peg 2 16 ef ERCW. Page 16 of 16 Rev 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE-1-ERCMI-379 3 RS RS BE 415 Size 1 , 1-ERCMI-380 3 RS RH 1-ERCMI-381 3 RS RS BE 415 Size 1 1-ERCMI-382 3 RS RH 1-ERCMI-500 3 RS RH 

  ,               1-ERCMI-505  3      RS    RH W

1-ERCWH-511 3 RS RH 1-ERCMI-512 3 RS RH i 1-ERCWH-513 3 RS RH 1-ERCWil-514 3 RS RH - 

,                 1-ERCMI-515  3      RS    RH i

1-ERCWil-520 3 RS RH ERCMI-3-06 3 RS RH ERCWil-3-08 3 RS Rif 4 SI-114.2 SNP SUPPORT LOAD

Type ._ SQNP RS-Rigid Support-SI-114.2 MS-Mechanical Snubber Page 1 of 2 Model Rev. 7 RS-Rigid Strut RH-Rigid Hanger Plant: SQNP Unit: 2 Page 1 of SIH IDENTIFIER SAFETY SUPPORT DESIGN SETTlNG THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE Il0T COLD MOVEMENT RANGE 2-SIH-72 3 MS BE 416 6" 24 1/2" 24 3/8" 1/8" 1/4"-5 5/8" PSA 10 2-SIH-73 3 MS BE 416 5" l'-9 9/16" l'-9" 9/16" 1/4"-4 3/16" PSA 3 2-S Ill-74 3 RS RH 2-SIH-112 3 RS RH 2-Sill-400 3 RS Ril us 2-Sill-401 3 RS Rif 2-Sill-402 3 RS RH 2-Sill-403 3 RS RH 2-Sill-404 3 RS RH 2-Sill-405 3 RS RH 2-Sill-406 3 RS Rif 2-Sill-407 3 RS RH 2-Sill-408 3 RS Rif 2-Sill-409 3 RS RH 4' SI-114.2 SNP SUPPORT LOAD

SQNP Pla n t. : SQNP Unit: 2 SI-114.2 Prge 2 ef SIH Page 2 of 2 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-SIH-410 3 RS BE 415 RS Size 5 2-SIH-411 3 RS Rif 2-SIH-412 3 RS BE 415 RS Size 2 i 2-Sill-413 3 RS RH 2-Sill-414 3 RS RH 2-Sill-415 3 VS Gr. Sprg 2236# 2264# 1/8" Up 3/8"-1" 

   ,                                             Fig 82 g                                              Type B W                                              Size 12 2-Sill-416    3      RS    RH 2-Sill-417    3      RS    RH 2-Sill-418    3      RS    RH 2-Sill-419   .3      RS    RH 2-SIII-420    3      RS    RH 2-Sill-438    3      RS    RH l

fl SI-114.2 SNP SUPPORT LOAD

T_yp.e SQNP VS-Varitblo Spri:g SI-114.2 RS-Rigid Support Page 1 of 1 Model Rev. 7 RS-Rigid Strut RH-Rigid Hanger Plant: SQNP Unit: 2 Page 1 of RHRH IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERHAL ACCEPTABLE TVA'S ISI'S CLASS TYPE HODEL STROKE HOT COLD HOVEMENT RANGE 2-RifRH-431 3 VS BE 401 1273; 1495# 5/16" Up 9/16"-1" Type F Size 11 2-RilRil-432 3 RS RH 2-RilRH-433 3 RS BE 415 RS Size 1 2-RIIRil-434 3 RS RH I .p:. 2-RilRH-435 3 RS RH O 

 '                 2-RilRil-436    3      RS    RH 2-RllRil-437    3      VS    BE 401          1175#        1234#  1/8" Up        3/8"-1" Type B Size 10 i

SI-114.2 SNP SUPPORT LOAD

SQNP Type SI-114.2 HS-Hydraulic S ubber Page 1 of 7 IA-Integrally Welded Attachment Rev. 7 MS-Mechanical Snubber RS-Rigid Support VS-Variable Spring Model RS-Rigid Strut RH-Rigid Hanger Plant: ,SQNP Unit: 2 Page 1 of MSH IDENTIFIER 

                                                                                                 ~

SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-MSii-300 2 HS BE 411 5" 4 1/4" 3 3/8" 7/8"T 1 1/2"-5 1/8" Size 8" X=1 1/4" 2-MSil-301 2 IIS BE 411 5" 3 7/16" 4 1/16" 5/8"C 2 1/8"-6" Size 8" 2-MSil-302 2 VS Gr. Sprg. 10,065# 12,725# 2" Up 2 1/4"-4 3/4" 3 Fig. C-98 op Type B 4 Size 18 7 2-MSil-303 2 IIS BE 411 5" 2 7/8" 4 3/8" 1 1/2"C 2 7/8"-5 7/8" Size 4 2-MSil-304 2 VS Gr. Sprg 11,420# 13,016# .6 Up .85"-2 1/4" Fig 268 Type B Size 18 2-MSil-305 2 RS Rif 2-MSil-306 2 IIS BE 410 5" 3 1/2" 2 3/4" 3/4" 1 3/8"-5 1/8" Size 4 2-MSil-307 2 VS Gr. Sprg. 37,210# 30,542# .8" Down .25"-1.45" Fig C-268 Type A Size 22 SI-114.2 SNP SUPPORT LOAD

Plant: SQNP Unit: 2 SQNP Pcg2 2 ef HSH-SI-114.2 Page 2 of 7 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-MSil-308 2 VS Gr. Sprg. 33,840# 20,762f .82 Down .25"-1.43" Fig C-268 Type F Size 21 2-MSil-309 2 MS BE 416 6" 2'-0 1/16" 2'-0 13/16" .75"C 1.00"-5.75" Size PSA 10 , *2-MSil-310 2 IIS BE 410 5" 2.875" 3 1/4" .375"C 1.75"-5.875" Size 3k" 

                                                                                         *2-MSil-310        2      IIS   BE 410     5"          3.125"       3 1/2"       .375"C         1.75"-5.875" Size 3k" d                                                                                       2-MSil-311       2      RS    BE 415 f                                                                                                                   RS 7                                                                                                                     Size #4 2-MSil-312       2      IA 2-MSil-312       2      RS    Rif 2-MSil-313       2      RS    RH 2-MSil-314       2      IIS   BE 410     5"          3 7/8"       3 3/8"       1/2"           1.375"-5.375" Size 3k" X=1 1/8" 2-MSil-315       2      IIS   BE 411     5"          4 1/16"      2 9/16"      1.5"T          1.375"-4.375" Size 3k" X=1 1/8" 2-MSil-316       2      RS    Ril 2-MSil-317       2      RS    Ril
                            *Snul>l>ers to operate simultaneously.                                                                                                                          s SI-114.2 SNP SUPPORT LOAD

Plant: SQNP Unit: 2 SQNP Pcg3 3 ef MSN SI-114.2 Pagn 3 of 7 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE 

 ~ VA'S           ISI'S       CLASS   TYPE MODEL     STROKE          Il0T        COLD    MOVEMENT         RANGE 2-MSH-340      2       HS    BE 411     5"          4 1/4"        3 5/16"  .938T         1.50"-5.062" Size 8" X=1 1/4" 2-MSH-341      2       HS    BE 411     5"          3 3/8"        4 1/8"   3/4"C         2.25"-6" Size 8" X=1k" 2-MSil-342     2      VS     Gr. Sprg.              10,885#       13,412#  1 15/16" Up   2.19"-4.75" F-C-98 Type B Size 18 2-MSil-343     2      IIS    BE 411     5"          2 7/8"        4 3/8"   1 1/2"C       2.875"-5.875" Size 4 X=1 1/8" 8

2-MSil-344 2 VS Gr. Sprg. 10,380# 11,604# 7/16" Up .75"-2.25" h W Fig. C-268 Type B Size 18 2-MSH-345 2 RS RH 2-MSil-346 2 VS Gr. Sprg. 16,925# 14,093# 13/16" Down .25"-1.44" Fig C-268 Type C Size 19 2-MSil-347 2 MS BE 416 6" 2'-6 13/16" 2'-6" 13/16"T .25"-3.937" PSA 35 2-MSil-348 2 IIS BE 410 5" 4.5" 3.69" .81"T 1.375"-5.065" Size 4 X=1.125 2-MSil-349 2 IA SI-114.2 SNP SUITORT LOAD

Plant: SQNP Unit: 2 SQNP P.:ge 4 cf MSH SQ-114.2 Page 4 of 7 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING ~ THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD N0'KMENT RANGE 2-MSH-349 2 RS RH 2-MSH-350 2 MS BE 416 6" l'-6 7/16" l'-7 1/8" 11/16"C 15/16"-5.75" PSA 10 2-MSH-351 2 VS Gr. Sprg. 18,600# 16,167# 11/16" Down .25"-1.562" Fig C-268 Type C Size 19 2-MSH-352 2 IIS BE 410 5" 3 11/16" 3 1/2" 3/16"T 1.375"-5.69" Size 4" 2-MSil-353 2 MS BE 417 6" 4'-1 5/16" 4'-0 5/16" 1"T .25"-4.75" PSA 10 2-MSH-354 2 RS Rif f 2-MSH-355 2 RS RH 2-MSil-380 2 IIS BE 411 5" 4 3/16" 3.5/16" 7/8"T 1.5"-5.125" Size 8" X=1.25" 2-MSil-381 2 HS BE 411 5" 3 7/16" 4 1/16" 5/8"C 2.125"-6" Size 8" X=1.25" 2-MSil-382 2 VS Gr. Speg. 11,380# 14,040# 2" Up 2.25"-4.75" Fig C-98 Type B Size 18 2-MSii-383 2 IIS BE 411 5" 3 7/8" 4 3/8" 1.5"C 3.0"-6.0" Size 4 X=1.25" e SI-114.2 SNP SUPPORT LOAD

Plant: SQNP Unit: 2 SQNP Pcga 5 ef MSN SI-114.2 Pcgn 5 cf 7 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE 

    ~TVA'S            ISI'S       CLASS   TYPE  MODEL     STROKE          HOT         COLD    MOVEMENT          RANGE 2-MSH-384       2       VS     Gr. Sprg.              4,565#        5,105#   1/2" Up        .75"-2.25" Fig C-268 Type D Size 15 2-MSil-385     2        RS     RH 2-MSH-386      2        VS     Gr. Sprg.              26,050#       22,760#  .7"  Down      .25"-1.55" C-268 Type C Size 20 2-MSil-387     2       MS      BE 416     6"         23 1/16"       22 1/4"  13/16"T        .25"-4.94" PSA 10 t-MSil-388     2       VS      Gr. Sprg.             6,370#         5,506#   13/16" Down    .25"-1.44" y                                               Fig C-268 Type D Size 15 2-MSil-389     2        IA 2-MSil-389     2       RS    'RH 2-MSil-390     2       VS      Gr. Speg.              18,705#       16,935#  1/2" Down      .25"-1.75" Fig C-268 Type B Size 19 2-MSil-391     2       MS 2-MSH-392      2       IIS     BE 410     5"         3.75"          3.56"    .188T          1.38"-5.69" Size 3k" X=1.125 2-MSil-393      2       MS      BE 417     6"'       3'-10 15/16" 4'-0 5/16"  1.4"c          1.65"-5.75" PSA 10 SI-114.2 SNP SUPPORT LOAD

Plant: SQNP Unit: 2 SQNP . Pa g2 6 ef MSN SI-114.2 Page 6 of 7 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD NOVEMENT RANGE 2-MSH-394 2 RS RH 2-MSH-395 2 RS RH 2-MSil-420 2 HS BE 411 5" 4.1875" 3.1875" 1"T 1.5"-5" Size 8" X=1.25" 2-MSil-421 2 IIS BE 411 5" 2.56" 3.25" .69"C 2.19"-6" Size 8" X=1.25" 2-MSH-422 2 VS Gr. Sprg. 10,735# 13,528# 2 1/8" Up 2.375"-4.75" Fig C-98 Type B 8 g, Size 18 2-MSil-423 2 IIS BE 411 5" 2.875" 4.375" 1.5"C 2.875"-5.875" 8 Size 4" X=1.125" 

,                   2-MSH-424        2      RS    BE 415 RS
                                                 ' Size 11 2-MSil-425       2      VS    Gr. Sprg.              4,480#       5,128#     .625" Up       .875"-2.25" Fig C-268           ,

Type D Size 15 2-MSil-426 2 RS RH 2-MSil-427 2 VS Gr. Sprg. 23,930# 20,640# .7 Down .25"-1.55"

Fig C-268 Type F Size 20 i

2-MSil-428 2 RS Ril e j SI-114.2 SNP SUPPORT LOAD 2

P1anL: SQNP Unit: 2 SQNP P;g; 7 ef MSN : SI-114.2 Peg 2 7 cf 7 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-MSH-429 2 VS Gr. Sprg. 17,150# 15,734# .375" Down .25"-1.875" Fig C-268 Type D Size 19 2-MSil-430 2 MS BE 417 6" 20" 20 3/8" 3/8"C .625"-5.75" PSA 10 2-MSil-431 2 RS BE 415 RS . Size 6 2-MSil-432 2 HS BE 410 5" 3.57" 3.69" .12"C 1.5"-5.875" Size 4" X=1.125" 2-MSil-433 2 MS BE 417 6" l'-8" l'-9 1/8" 1.125"C 1.375"-5.75" d PSA 10 - 

;3             2-MSil-434   2      RS    RH 2-MSil-435   2      RS    RH 2-MSil-438   2      Ril   RH 2-MSil-439   2      RS    BE 415 RS Size 1 2-MSii-440   2      MS    BE 416     2 1/2        10 1/2        11 13/16   1 5/16C       1 9/16"-2 1/4" PSA 1/2 I

SI-114.2 SNP SUlPORT LOAD

T_gte SQNP CF-Constert Fcrc2 SI-114.2 HS-Hydraulic Snubber Page 1 of 12 MS-Mechanical Snubber Rev. 7 RS-Rigid Support 

                                                                                .VS-Variable Spring IA-Integrally Welded Att.

Model RS-Rigid Strut RH-Rigid Hanger T-Tension C-Compression Plant: SQNP Unit: 2 Page 1 of RCH IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCH-011 1 MS BE 416 4" 12-7/16" 12" 7/16" T .25"-3.3125" PSA1 . 2-RCll-012 1 RS RH-G d 2-RCil-013 1 RS RH-G -e y 2-RCll-014 1 RS RH-G 2-RCII-015 1 CF BE Const. 2.5" up 2-3/4"-3-1/4" Spring Type V No. 23 . Total Travel 3.5" Actual " 2.5" up. 2-RCll-016 1 RS BE 415 RS. Size 1 2-RCll-017 1 RS Ril e SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pcg2 2 ef RCH P2g2 2 cf 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCH-018 1 MS BE '416 4" 17-1/4" 16-1/2" 3/4"T 2.75"-3.00"* PSA-1 14" 16-1/2" 2-1/2"C 2-RCll-019 1 RS RH 2-RCil-020 1 MS BE 416 2.5" 10-7/8" 12" 1-1/8"C 1.375"-2.25" PSA-1/2 2-RCll-021 1 VS Grin. 130# 145# 1-1/8" up. 1.375"-4.75" Sprg Fig. C-98 - Type B Size #2 2-RCll-022 1 VS Grin. 120# 130@ 3/8" up .625"-2.25" Sprg. 

 $                                              Fig.

g C-268 2-RCll-023 1 RS BE 415 RS Size 1 __ 2-RCH-024 1 MS BE 416 5" 17-3/4" 17-1/2" 1/4"_T .875"-4.5"* PSA-3 16-7/8" 17-1/2" 5/8" C 2-RCH-025 1 VS Grin C-98 710# 832# 1-5/8" up 1.875"-4.75" Size 8 Type "B" 2-RCH-026 1 MS BE 417 5" l'-6-1/2" l'-4-7/8" 1-5/8" T .25"-4.125" PSA-3 2-RCll-027 1 RS Ril 

    *tios t Conservative Calculation Used SI-114.2 SN1* SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pcg3 3 cf RCH Page 3 of 12 Rev. 7 

    ~

IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCH-028 1 MS BE 416 5" 22-11/16" 21-13/16" 7/8" T 2.75"-3.875"* PSA-3 19-5/16" 21-13/16" 2.5" C 2-RCII-029 1 RS RH 2-RCII-030 1 MS BE-417 5" 18-1/2" 16-3/16" 2-5/16" T 1.19"-2.43"* PLA-3 15-1/4" 16-3/16" 15/16" C 1 2-RCll-031 1 MS BE 416 5" 21-3/8" 21" 3/8" T 1.19"-4.37"* PSA-3 20-1/16" 21" 15/16"C 2-RCll-032 1 CF 15/16" down 25/8"-2 13/16"* 2-3/8" up 2-RCil-033 1 RS Ril-G 2-RCil-034 1 RS RH g 2-RCil-035 1 MS BE 417 6" 4'-5-11/16" 4'-7-3/16" 1.5"C 1.75"-5.75" o PSA-10 s 2-RCil-036 1 RS RH 2-RCll-037 1 RS RH 2-RCli-038 1 RS Ril 2-RCil-039 1 RS Ril-G 2-RCll-065 1 RS RS 2-RCil-066 1 MS BE 416 6" 19-1/2" 19-3/4" .25" C .50-5.75" i PSA-10 2-RCll-071 1 RS BE 415 RS Size #4 

      *Most Conservative Calculation Used                                                                  a SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Prga 4 cf RCH Page.4 of 12 Rev. 7 , IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S -CLASS TYPE MODEL STROKE HOT COLD HOVEMENT RANGE 2-RCH-082 1 RS RH 2-RCH-083 1 RS RH 2-RCH-086 1 MS BE 416 5" 23-1/16" 19-1/2" 3-9/16" T .25"-1.18" , PSA-3 2-RCH-088 1 RS RH 2-RCH-089 1 CF BE 3-5/8"-3-7/8" Counter-

poise l Type B l Size 14 i

e 6'

  • 2-RCil-090 1 MS BE, 416 4" 17-7/16" 13-13/16" 3.625 T .125" .25"*

_M_ PSA 1 2-RCH-091 1 MS BE 417 4" 12.5" 13" 1/2" C .75"-3.75" PSA 1 2-RCil-093 1 RS RH i 2-RCil-094 1 RS RH 2-RCll-095 1 VS Size 20 1043# 1043# 3.56" up 3.81"-4.75" BE 403 Sprg "B" HGR 2-RCll-096 1 MS BE 417 5" 3'-10-1/2" 3'-10-3/8" .125 T .25"-4.625" PSA-3 l 2-RCll-125 1 MS BE 417 5" 3'-10-1/2 3'-10-3/8" .125T .25"-4.625" PSA-3 i SI-114.2 SNP SUPPORT LOAD

SQNP. Plant: SQNP s Unit: 2 SI-114.2 . Pcga 5 cf RCH - Page 5 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCH-126 1 CF BE 5" 3.56" up 3.81"-4.75" i Counter-poise Type S Size 11 j ' 

                     '2-RCH-131                         BE 417       4" 1        MS                         12"            10-5/16"     1-11/16" T.     .25"-2.06" PSA 1/4" 2-RCH-132       1       RS        RH 2-RCH-133       1       MS        BE 416       2.5" 12-1/8" -     9-15/16"     2.19"T           .125" .185"*

PSA 1/2 2-RCil-134 1 MS BE 416 4" 15-3/8" 15-1/2" .125 C .375"-3.75" 8 la PSA 1 Ul Ni 2-RCil-135 1 RS RH 2-RCH-136 1 RS RH 2-RCil-137 1 RS RH 2-RCll-138 1 RS RH 2-RCH-139 1 RS RH 2-RCH-140 1 MS BE 416 5" 15-3/16" 16-3/16" 1-5/8" C 1.875"-4.75" PSA 3 2-RCll-141 1 MS BE 416 5" l'-7" l'-5-3/8" 1-5/8" T .25"-3.125" PSA 3 j 2-RCH-142 1 RS Rif ! 2-RCil-143 1 MS BE 416 2.5" 9-9/16" 8" 1-9/16" T .25" .687" PSA 1/2 SI-114.2 SNP SUPFORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pag; 6 ef RCH Page 6 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE _ TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCH-144 1 RS RH 2-RCH-145 1 RS RH 2-RCil-146 1 RS RH 2-RCil-147 1 MS BE 416 2.5"

  • 9" 7-3/4" 1.25" T .25"-1.000"*

PSA 1/2" BE 416 4"

  • 12-1/8" 13-1/8" 1.00" C 1.25"-3.75"*

PSA 1 2-RCH-148 1 MS BE 417 5"

  • 3'-5-1/4" 3'-4-13/16" .44" T .25"-4.31"
  • PSA-3 BE-416 5"
  • 21-9/16" 20-3/8" 1.19" T .25"-3.56" *
                                  ,                                                                                       PSA-3 (38 W                               2-RCH-150                              1      RS               RH tr>

2-RCll-165 1 VS Grinnell 460# 486# 1/8" up .375"-1" Sprg Hgr Fig. C82 Type D Size 7 2-RCH-166 1 VS Grinnell 110# 116# 1/8 up .375"-1" Sprg ligt Fig-C82 Type B Size 1 2-RCH-181 1 MS BE 416 2.5" 10-1/4" 11-15/16" 1.69" C 1.94"-2.25"

  • PSA-1/2" 2-RCil-182 , 1 RS Ril 2-RCil-183 1 MS BE 416 4" 16-7/16" 14-3/4" 1.69" T .25"-2.06"
  • PSA-1 SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P:g2 7 cf RCH Page 7 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE N0 DEL STROKE HOT COLD HOVEMENT RANGE 2-RCH-184 1 MS BE 416' 4" 15-3/4" 15-1/2" .25" T .32"-3.5"* PSA-1 15-7/16" 15-1/2" 1/16" C 2-RCH-185 1 RS RH 2-RCII-186 1 RS RH 2-RCII-187 1 RS RH-G 2-RCil-188 1 MS BE 416 5" l'-8-1/4" l'-9-13/16" 1.56 C 1.81"-4.75" PSA-3 2-RCH-189 1 RS Rif 

,                2-RCH-190      1       MS    BE 416     5"    l'-8-1/4"     l'-9-13/16" 1.56 C          1.81"-4.75" (p                                             PSA-3 tn f                2-RCH-191       1       RS    RH 2-RCil-192      1       MS    BE 416     4"    16-5/8"       14-13/16"     .82" T        .25"-2.93" PSA-1 2-RCH-193       1       RS    RH-G 2-RCil-194      1       RS    Ril-G 2-RCll-196      1       MS    BE 417     2,.5" 7-7/8"        9-1/4"        1.375" C      1.625"-2.25"*

PSA 1/2" 2-RCH-197 1 MS BE 417 2.5" l'- l'9-1/2" 1.19" T .25"-1.06"* PSA 1/2" 10-11/16" 2-RCll-198 1 MS BE 417 4" 2'-2-1/16" 2'-1-1/4" .82" T .25"-2.93"* PSA-1

  • Host Conservative Calculation Used SI-114.2 SNP SUPPORT LOAD
                                                                                                                     .c SQNP Plant: SQNP      Unit:   2                                             SI-114.2-                   Pcg2 8 cf RCH Page 8 of 12                            ,

Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL- ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCH-199 1 MS BE 416 4" 15-1/2" 16-3/4" 1.25" C 1.5"-3.75"* PSA-1 2-RCil-200 1 RS RH 2-RCil-216 1 RS RH 2-RCll-231 1 MS BE 416 5" l'-4-1/4" l'-5-3/4" 1.5" C 1.75"-4.75" PSA-3 2-RCil-232 1 MS BE 416 5" l'-4-1/4" 1'-5-3/4" 1.5" C 1.75"-4.75" PSA-3 2-RCH-233 1 RS RH 2-RCil-234 1 RS RH e W 2-RCil-235 1 RS RH-G g 2-RCll-236 1 RS RH 2-RClf-237 1 RS RH 2-RCll-238 1 MS BE 416 4" 15-7/16" l'-3-5/8" 3/16" C .44"-3.75" PSA-1 2-RCil-239 1 MS BE 416 4" 15-3/8 14-5/8"- .75" T .25"-3.0" PSA-1 2-RCil-240 1 RS RH 2-RCll-241 1 MS BE 416 2.5" 10-3/16" 11" .82 C" 1.07"-2.25" PSA 1/2 2-RCil-242 1 MS BE 416 4" 16-3/8" 14-7/8" 1.5" T .25"-2.25" PSA-1 e SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P g2 9 cf RCH Peg 2 9 of 12 Rev. 7-IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCil-243 1 RS Rll 2-RCll-244 1 RS RH , 2-RCII-246 1 MS BE 416 4" l'-3-3/8" l'-3-5/8" .25" C .50" - 3.75" PSA-1

2-RCil-247 1 MS BE 416 4" 16-1/8" 17" 7/8" C 1.13"-3.75" PSA-1 2-RCll-248 1 MS BE 417 4" 13-3/8" 12" 1.375" T .25"-2.375" PSA-1 2-RCll-249 1 MS BE 417 4" l'-1" l'-1-7/16" .44" C .69"-3.75" PSA-1 b 2-RCII-250 1 MS BE 417 5" 4'-10-3/8" 4'-10-1/4" 1/8" T .25"-4.625" W PSA-3 6'

2-RCil-251 3 1 VS Grinnel 179# 168# 1/8" down .25 .875" Fig C-82 Type B Size #4 4 2-RCll-267 1 RS Ril , 2-RCil-268 1 VS BE 401 488# 507# 1/8" up .375"-1" Type B

Size 7

) 2-RCll-281 1 MS BE-416 4" l'-2-3/16" l'-0-1/2" 1.69" T .25"-2.06" { PSA-1/4" 2-RCil-282 1 RS Ril 2-RCll-283 1 MS BE 416 2.5" 11-15/16" 10-5/16" 1.625" T .25" .625" PSA 1/2 SI-114.2 SNP SUP' ORT P LOAD

SQNP Plant: SQNP Unit: 2 S0-114.2 Paga 10 cf RCH Page 10 of.12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCH-284 1 MS BE 416 4" l'-3-7/16" l'-3-1/2" 1/16" C .32"-3.68"* PSA-1 l'-3-9/16" 1/16 T 2-RCH-285 1 RS RH 

                ,   2-RCH-286       1      RS    RH 2-RCH-287       1      RS    RH-G 2-RCil-288      1      MS    BE 416    5"     l'-10-13/16" l'-7-1/8"    3.68" T        .25"-1,07" PSA-3 i

2-RCH-289 1 RS RH i , 2-RCII-290 1 MS BE 416 5" 19-3/16" 20-7/8" 1.68" C 1.94"-4.75" PSA-3 9 

  $                 2-RCll-291      1      RS    BE 415
  -J RS Size 1 2-RCll-292      1      MS    BE 416    4"     l'-2-7/8"     l'-4-3/8"   1.5" C         1.75"-3.75" PSA 1 i

2-RCil-293 1 RS RH 2-RCH-294 1 RS Rll 2-RCil-295 1 RS RH 2-RCll-296 1 MS BE 416 2.5" 10-5/8" 11-5/8" 1" C 1.25"-2.25" PSA 1/2 2-RCil-297 1 MS BE 416 2.5" 11-11/16" 10-5/8" 1-1/16" T .25"-1.18" PSA 1/2 

     *tlost Conservative Calculation Used SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Peg 2 11 cf RCH-Page 11 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RCH-298 1 MS BE 417 4" l'-0-7/16" 11-5/8" .82" T .25"-2.93" PSA 1 2-RCH-299 1 MS BE 416 4" 17-1/4" 16-1/8" 1.125" T .25"-2.75" PSA 1 2-RCll-300 1 MS BE 416 4" 11-5/8" 11-1/2" .125 T .25"-3.62" PSA-1 2-RCH-301 1 VS Grinnel 242# 233# .1" down .25" .90" F. C82 Type B Size 4 2-RCil-832 1 VS Grinnel 64# 52# .8" down .25"-1.45" Fig C-268 Type "D" t ui 2-RCH-833 1 MS BE 416 2.5" 11-7/8" 10-3/8" 1.5" T .25" .75" y PSA 1/2

2-RCH-834 1 VS Gr. Sprg 170# 142# .79 down .25"-1.46" FIG. 268 Type B Size 3 2-RCII-835 1 MS BE 416 4" 16-1/16" 15-1/4" .82" T .25"-2.93"
PSA-1 2-RCH-862 1 VS BE Sprg. 64# 52# .8" down .25" .75" BE 402 Type A 2-RCll-863 1 MS BE 416 2.5" 11-7/8" 10-3/8" 1.5" T .25" .75" PSA 1/2" SI-114.2 SNP SUPPORT LOAD
                                &                                                   f

SQNP Plant: SQNP Unit: 2 . SI-114.2 P;;g2 12 cf RCH Page 12 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE HODEL STROKE HOT COLD HOVEMENT RANGE 2-RCil-864 1 VS Grin Sprg 160# 132# .8 down .25"-1.45" Fig. C-268 Type B Size 3

, 2-RCll-865 1 MS BE 416 4" 16" 15-1/4" .75" T .25"-3.0" PSA 1 2-RCII-892 1 VS Gr. Sprg 70# 59# .75" down .25"-1.5"

, FC-268 Type D - Size: 0 2-RCil-893 1 MS BE 416 4" 16-7/16" 14-7/8" 1.57" T .25"-2.18" PSA: I h 2-RCil-894 1 VS Grin. Sprg 150# 122# .8" down .25"-1.45" U1 FIG C-268 f Type B Size 3 2-RCll-895 1 MS BE 416 4" 16" 15-1/4" .75" T .25"-3.0" PSA-1 2-RCll-920 1 VS Grin Sprg 72# 62# .69" down .25"-1.56" FIG 268

Type B Size 0 2-RCil-921 1 MS BE 416 2.5" 10" 10-5/8" .625" C .875"-2.25" l PSA-1/4 l

2-RCil-922 1 VS Grin. IIgr 158# 141# 5/16" down .25" .68" I FC-82 i 2-RCll-923 1 MS BE 416 4" 15" 16" 1" C 1.25"-3.75" PSA 1 SI-114.2 SNP SUPPORT LOAD

SQNP Type SI-114.2 HS-Hydrculic Snubber Pzge 1 of 8 MS-Mechanical Snubber Rev. 7 RS-Rigid Support VS-Variable Spring RESIDUAL HEAT REMOVAL IA-Integrally Welded Attch-Model CLASS 1 & 2 COMPONENTS RS-Rigid Strut RH-Rigid Hanger Plant: SQNP Unit: 2 Page 1 of RHRH I D"T1 FI ER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA's

  • ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RIIRII-001 1 RS RH 2-RilRH-002 1 RS RH 2-RHRil-003 1 RS RH 2-RIIRil-004 1 RS Ril .

2-RIIRil-005 1 RS RH I h O 2-Ri!Ril-006 1 HS BE 410 5" 3-5/8" 3-11/16" 1/16" C 1.44"-5.87" 3-1/4" Cyl. x = 1.125" 2-RIIRil-007 1 HS BE 411 5" 2-5/8" 4-3/8" 7/4" C 3.0"-5.75" 2-1/2" Cyl. x = 1.0" , 2-RIIRll-400 2 VS Sprg. Hgr 3165# 3007# .25" .875" 1/8" down BE 401 Type G Size 13 2-RIIRil-401 2 MS BE 417 5" 4'-3-5/8" 4'-3-1/2" 1/8" T .25"-4.63" PSA 3 2-RilRil-402 2 RS BE 415 RS Size 4 SI-114.2 SNP SUPPORT LOAD 9

  • SQNP . 7 Plant: SQNP Unit: 2 SI-114.2 Pzg2 2 cf RHRH Page 2 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE HODEL STROKE HOT COLD HOVEMENT RANGE 2-RilRil-403 2 RS RH 2-RIIRH-404 2 RS BE 415 RS Size 2 2-RilRil-405 2 RS RH 2-RilRil-407 2 VS Sprg Fig 4437# 4226# 1/8" down .25" .875"-

BE 401 Type G Size 14 2-RHRH-408 2 MS BE 417 5" 4'-3-5/8" 4'-3-1/2" 1/8" T .25"-4.62" PSA-3 2-RHRil-409 2 RS BE 415 d RS Size 4 _s._- 2-RIIRil-410 2 RS RH 2-RifRH-411 2 RS Rif - 2-RilRil-412 2 RS RH

2-Ri!Ril-414 2 VS Sprg f lig. 1174# 1124# 1/8" down .25" .875" 401 BE
Type F _

Size 9 a

2-RIIRil-415 2 RS BE 41's RS Size 1 2-RIIRil-416 2 RS Ril 2-RilRil-417 2 RS Ril ,

SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P;ga 3 cf RHRH Page 3 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RIIRil-418 2 RS BE 415 RS Size 1 2-Ri!Ril-419 2 RS BE 415 RS Size 2 2-RIIRil-420 2 VS Sprg Fig. 1891# 1802# 1/8" down .25" .875" BE 401 Type A Size 11 2-RIIRII-421 2 RS Rif 2-RIIRil-422 2 RS BE 415 RS d e Size 2 N 2-RifRil-423 2 RS BE 415 i RS Size 1 2-RifRil-424 2 VS Sprg Fig. 1748# 2164# 7/16" Up .69" - 1" BE 401 - Type G Size 12 2-RilRil-425 2 MS BE 416 2-1/2" 11-5/8" 11-1/8" 1/2" T .25"-1.75" PSA 1/2" - 2-RIIRil-426 2 RS Rif , , I 2-RIIRil-427 2 RS Ril . 2-RilRil-428 2 RS BE 415 j RS + Size 1 e f SI-114.2 SNP SUPPORT LOAD j

4 SQNP Plant: SQNP Unit: 2 SI-114.2 Pcge 4 cf RHRH Page 4 of 8 . Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN S[fTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE H0 DEL STROKE HOT COLD MOVEMENT RANGE 2-RIIRil-429 2 VS Sprg. FIG 2309# 2665# 3/8" Up .625"-1" BE 401 Type F Size 12 2-RllRil-430 2 MS BE 417 5" l'-4-3/4" l'-5-1/8" 3/8" C .625"-4.75# PSA-3 2-R11Ril-438 2 RS BE 415 RS Size 2 2-RHRil-439 2 RS BE 415 RS 

                                         '    Size 1 3  ,

va 2-RIIRil-440 2 RS Ril 2-RilRil-441 2 RS RH 2-RilRil-442 2 RS BE 415 RS Size 1 i 2-RIIRil-443 2 RS Ril 2-RilRII-444 2 RS Ril 2-RIIRil-445 2 VS Sprg Fig 1700# 1700# 0" Up .25"-1.00" BE 401 Type B Size 11 2-RilRil-446 2 RS BE 415 RS Size 2 s SI-114.2 SNP SUPPORT LOAD

SQNP . Plant: SQNP Unit: 2 SI-114.2 P g2 5 cf RHRH Pcge 5 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING TIIERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE' 2-RHRil-447 2 RS BE 415 RS Size 1 2-RIIRil-448 2 RS BE 415 RS Size 2 2-RIIRil-449 2 RS BE 415 RS Size 2 2-RHRil-450 2 RS RH 2-RilRil-451 2 VS Sprg Fig 652# 765# 3/8" Up .63"-1" 

,                                             BE 401 o                                              Type G Size 8 i

2-RIIRa-452 2 MS BE 417 4" 2'-10-1/16" 2'-9-11/16" 3/8" T .25"-3.375" PSA 1/4" 2-RilRil-453 2 RS BE 415 RS Size 2 2-RIIRil-454 2 RS Ril 2-RiiRil-455 2 RS BE 415 RS Size 3 2-RifRil-456 2 RS Rll 2-RIIRil-457 2 MS BE 416 6" 23-15/16" 2'-0-3/4" 13/16" C 1.06"-5.75" PSA-10 SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P:ge 6 cf RHRH Page 6 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE-2-RHRil-458 2 VS BE 402 2296# 1999# 5/8" down .25"-1.62" Type B 2-RIIRH-459 2 RS BE 415 

         ,                                     RS Size 1 2-RIIRif-460     2      RS    Ril 2-RifRil-461     2      VS    BE 401         1167#         1301#        1/4" Up        .5"-1" Type F Size 10 2-RllRIl-462     2      RS    Rif 6'

2-RIIRll-463 2 MS BE 417 4" 4'-7-7/16" 4'-8-1/8" 11/16" C .94"-3.75" PSA-1 UI 2-RIIRil-464 2 RS RH 2-RilRil-465 2 RS BE 415 RS Size 3 2-RilRll-466 2 RS Rif 2-RilRil-467 2 MS BE 416 5" l'-8-13/16" l'-8-1/16" 3/4" T .25"-4" PSA-3 2-RIIRil-468 2 VS Grinnel 2355# l'963# 7/16" Down .25" .56" Fig 82 Type F Size 12 2-RIIRll-469 , 2 RS BE 415 RS Size 1 

              'q                                                                         SI-114.2 SNP SUPPORT LOAD-

SQNP Plant: SQNP Unit: 2 SI-114.2 Pcg2 7 cf RHRH Page 7 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-RifRil-470 2 RS RH 2-RilRH-471 2 MS BE 416 6" l'-7-1/2" l'-7-3/4" .5"-5.75" 1/4" C Size PSA-10 2-RiiRil-472 2 MS BE 416 5" l'-4" l'-4-1/4" 1/4" C .5"-4.75" Size PSA-3 2-SIH-380 2 RS RH 2-SIH-381 2 RS RH 2-Sill-382 2 RS RH 2-Sill-383 2 RS RH d c 2-SIH-384 2 RS RH ( 2-SIH-385 2 RS RH 2-Sill-386 2 RS Rif 2-SIH-387 2 RS RH 2-Sill-388 2 RS Rll 2-SIH-389 2 RS RH 2-Sill-390 2 RS Ril 2-S Ill-391 2 RS Ril 2-Sill-392 2 RS Ril 2-Sill-393 2 RS Ril G SI-114.2 SNP SUPPORT LOAD

SQNP . Plant: SQNP Unit: 2 SI-114.2 P;g1 8 ef RHRH Page 8 of 8 Rev. 7 IDENTIFIER . SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE 

   , TVA'S           ISI'S       CLASS  TYPE MODEL     STROKE HOT        COLD        MOVEMENT          JtANGE 2-SIH-394       2      RS     RH 2-SIH-395       2      RS     RH 2-SIH-396       2      RS     RH 2-Sill-397      2      RS     RH 2-S Ill-398     2      RS     RH 2-SIH-399       1      RS     Rll 2-Sill-800      1      RS   - RH 2-Sill-801      1      RS     RII
,                2-SIH-802       1      RS     RH t>>

2-Sill-803 1 RS RH 2-Sill-805 1 RS BE 415 RS Size 2 2-Sill-806 1 RS Rll 2-SIH-807 1 RS BE 415 RS Size 5 2-Sill-808 1 RS Rif 2-SIH-809 1 RS Rif f SI-114.2 SNP SUPPORT LOAD

SQNP ' Type. SI-114.2 HS-Hydrculic Snubber. Pege 1 ef 12 MS-Mechanical Snubber. Rev. 7 RS-Rigid Support VS-Variable Spring SAFETY INJECTION CLASS 1 & 2 COMPONENTS IA-Integrally Welded Attch Model RS-Rigid Strut RH-Rigid Hanger Plant: SQNP Unit: 2 Page 1 of SIH T-Tension C-Compression DENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE 

  , TVA'S          ISI'S     CLASS   TYPE   MODEL     STROKE           HOT        COLD       MOVEMENT          RANGE 2-RHRH-008   1      MS       BE 416     4"              .325" l'             l'-1.125"   .8" C         1.05"-3.75" PSA 1 2-RHRil-009   1      RS       RH           .

2-RIIRil-010 1 RS RH 2-Ri!RH-011 1 RS RH I 2-Sill-001 1 RS RH w 2-SIH-002 1 RS RH 2-SIH-003 1 VS Grinnell 5720# 5750# .01" Up .26"-1" Fig C-82 Type B Size 16 2-Sill-004 1 RS RH 2-Sill-005 1 VS Grinnell 2510# 2870# 5/16" Up 9/16"-1" Fig C-82 Size 13 Type B 2-Sill-006 1 MS BE 416 6" 2'-1-7/16" 2'-2-1/8" 11/16" C 15/16"-5.75" PSA 35 SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-14.2 Pcg2 2 cf SIH Page 2 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT- DESIGN SETTING THERMAL ACCEPTABLE 

, TVA'S            ISI'S    CLASS  TYPE MODEL     STROKE         HOT        COLD       MOVEMENT           RANGE 2-SIH-007    1      RS    RH 2-SIH-008    1      RS    RH 2-SIH-009    1      RS    Ril 2-Sill-010   2      RS    RH 2-Sill-011   2      MS    BE 417     5"         15-5/8"      18-7/16"     2-13/16" C     3.06"-4.75" PSA 3 2-SIH-012    2      RS    RH 2-Sill-013   2      MS    BE 417     5"         2'-7-11/16" 2'-10-5/8" 2-15/16" C        3.19"-4.75" PSA 3 2-Sill-014   2      RS    RH D             2-Sill-015   2      MS    BE 417     5"         16-1/16"     17"          15/16" C       1.19"-4.75"

' PSA 3 2-Sill-016 2 RS RH 2-Sill-017 2 RS RH 2-Sill-018 2 RS RH 2-Sill-019 2 RS RH 2-Sill-020 1 RS Rll 2-SIlf-021 1 RS Ril 2-Sill-022 1 RS BE 415 RS Size 6 SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pcge 3 cf SIH Page 3 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-Sill-023 1 MS BE 416 6" 2'-1-1/2" 2'-1-5/8" 1/8" C .375"-5.75" PSA 10 2-Sill-024 1 RS RH 2-Sill-025 1 RS RH 2-Sill-026 1 RS Rif 2-SIH-027 1 HS BE 411 5"- 3-7/8" 3-3/8" 1/2" T 1.4"-5.37" 4" CYL. X=1-1/8" 1 te 2-SIH-031 1 VS GRINNELL 180# 182# 1/16" Up .32"-2.25" 1 4 Fig C-268 f Type C Size 3 2-SIH-032 1 MS BE 416 4" 12-15/16" 13" 1/16" C .32"-3.75" PSA 1 2-Sill-038 1 VS BE 401 90# 87# 1/16" Down .25" .93" Type B Size 1 

;                   2-SIH-039    1      MS    BE 416     4"     13-15/16"     13-3/8"      9/16" T        .25"-3.18" PSA 1/4"        ,

2-Sill-040 2 MS BE 416 2.5" 10-15/16" 11-3/8" 7/16" C .69"-2.25" PSA 1/2" j 2-S111-041 2 RS Rif 5 SI-114.2 SNP SUPPORT LOAD 4 ___ s

SQNP . Plant: SQNP Unit: 2 SI-114.2 P;g2 4 cf SIM 

                                                                           -                Page 4 of 12 Rev. 7 IDENTIFIER                    SAFETY           SUPPORT               DESIGN SETTING         THERMAL       ACCEPTABLE TVA'S                     ISI'S     CLASS- TYPE   MODEL      STROKE       HOT        COLD       MOVEMENT          RANGE J

2-SIH-042 2 RS RH 2-SIH-043 2 RS RH

2-Sill-044 2 MS BE 416 6" l'-7-1/2" l'-8-3/4" 1-1/4" .1.5"-5.75"

.; PSA-10 2-SIH-045 2 RS RH 2-SIH-047 2 RS RH 2-Sill-048 2 RS RH

  • 2-Sill-049 2 RS Rif I

4 D> 2-Sill-050 2 RS RH 7 2-Sill-051 2 RS RH 2-Sill-052 2 RS RH 2-SIH-053 2 RS RH 2-SIH-054 2 RS RH 2-SIH-055 2 RS Ril 2-Sill-056 2 RS RH 2-SIH-057 2 MS BE 416 5" 19-1/4" 21-5/8" 2-3/8"C 2.63"-4.75" PSA-3 2-Sill-058 2 RS Ril - i SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2~ Pcg2 5 cf SIM Page 5 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-SIH-059 2 MS BE 416 6" 23-1/8" 23-3/8" 1/4" C .5"-5.75" PSA-10 2-SIH-060 2 VS GRINNEL 1960# 2130# 1/4" Up .5"-1.00" Fig C-82 Type B Size 12 2-SIH-061 1 MS BE 416 5" 15-1/8" 16-3/8" 1-1/4" C 1.5"-4.75" PSA-3 2-SIH-064 1 RS RH 2-Sill-065 1 MS BE 416 6" 2'-0-5/8" 2'-0-1/8" 1/2" T .25"-5.25" PSA-10

  • s

$ 2-SIH-066 1 VS GRINNEL 2178# 1764# 7/16" down .25" .5625" G FIG C-82 Type B Size 12 2-SIH-067 1 MS BE 416 6" 2'-0-1/16" 2'-0-1/8" 1/16" C .32"-5.75" PSA-10 2-Sill-068 1 VS GRINNEL 4500# 5040# 1/4" Up .5"-1" FIG C-82 . Type B Size 15 2-SIH-069 1 HS BE 410 5" 3-7/8" 3-7/16" 7/16" T 1.38"-5.5" Size #4 X = 1.125" 2-Sill-070 1 IIS BE 410 5" 3-1/4" 2-5/8" 5/8" T 1.38"-5.25" Size #4 X = 1.125 s SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2

  • SI-114.2 Page 6 ef SIH Page 6 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE

___TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-SIH-071 1 RS RH 2-SIH-075 2 RS RH 2-Sill-076 2 RS Rll 2-SIH-077 2 MS BE 416 4" 17-1/8" 14-1/4" 2-7/8" T .25" .875" PSA-1 2-Sill-078 1 RS RH 2-Sill-079 1 RS Rii 2-SIH-104 1 VS Grin Sprg 2346# 2489# 3/8" up .625"-2.25" 2 FC.268 W Type F -g Size 12 e 2-SIH-105 1 MS BE 416 6" 23-1/8" 23-3/8" 1/4" C .5" -5.75" PSA-10 2-Sill-106 1 MS BE 417 6" 21-1/8" 20-3/8" 3/4" T .25"-5" PSA-10 2-Sill-107 1 VS Grin Sprg 1,570# 1655# 1/8" up .375"-1" Fig C-82 Type B Size #11 2-SIH-108 1 RS RH 2-Sill-109 1 MS BE 416 6" 22-7/8" 23" 1/8" C .375"-5.75" PSA-10 2-SlH-110 1 MS BE 416 6" 2'-0-15/16" 2'-0" 15/16" T .25"'4.81" PSA-10 SI-114.2 SNP SUPPORT LOAD

SQNP. Plt.nt : SQNP Unit: 2 SI-114.2 Pega 7 cf SIN Page 7 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-SIH-111 1 MS BE 417 6" l'-6-15/16" l'-7-1/8" 3/16"C .44"-5.75" PSA-10 2-SIH-113 1 RS RH 2-SIH-118 1 RS RH 2-SIH-119 1 MS BE 416 PSA-10 2-SIH-150 1 RS RH 2-SIH-151 1 RS RH 2-SIH-152 1 RS RH E (>> 2-Sill-153 1 RS RH -3 2-SIII- 154 1 RS RH 2-Sill-155 1 RS RH 2-SIH-156 1 RS RH 2-Sill-157 1 RS RH 2-SIH-158 1 RS RH 2-SIH-159 1 RS RH 2-Sill-160 1 RS RH , 2-SIH-161 1 RS RH 2-Sill-162 1 RS Ril' o SI-114.2 SNP SUPPORT LOAD

SQNP-Plant: SQNP Uni t.: 2 SI-114.2 Pcge 8 df SIM Page 8 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE IIOT COLD

  • MOVEMENT RANGE 2-Sill-163 1 RS RH 2-Sill-164 1 RS RH 2-Sill- 165 1 RS Rif 2-Sill-166 I RS RH
                                                                                                       ^

2-Sill-167 1 RS RH 2-Sill-168 1 RS RH 2-Sill-169 1 RS RH 2-SIH-170 1 RS RH a-J ' 2-SIH-171 1 RS BE 415 

@                                           RS Size #1 2-Sill-172    1      RS    RH 2-SIH-173     1      RS    RH 2-Sill-174    1      RS    RH 2-Sill- 175   1      RS    Ril e

SI-114.2 SNP SUPPORT LOAD

_ - - . - _ . _ . . . - - - . ~ . _ _. -- SQNP l Plat: SQNP Unit: 2 SI-114.2 P;ge 9 cf SIM 

 !                                                                                            Page 9 of 12 Rev. 7 IDENTIFIER             SAFETY               SUPPORT                  DESIGN SETTING         THERMAL       ACCEPTABLE
;        TVA'S               ISI'S     CLASS         TYPE MODEL          STROKE    NOT        COLD       MOVEMENT          RANGE 2-SIH-176        1             RS    RH i                     2-SIH-204        1             RS    RH 2-SIH-205        1             RS    RH l                   *
!                     2-SIH-206        1             RS    RH l

2-SIH-207 1 RS RH 2-SIH-208 1 RS RH

2-SIH-209 1 RS RH 2-SIH-210 1 RS RH i I (A8 2-SIH-211 1 RS RH
   -J                                                                                                .

C

. i 2-SIH-212 1 RS RH 2-SIH-213 1 RS RH

) 2-SIH-214 1 RS RH i 2-SIH-215 1 RS RH ] 2-SIH-216 I RS RH 2-SIH-217 1 RS RH 2-SIH-218 1 RS RH ] 2-SIH-219 1 RS RH ! 2-SIH-220 1 RS RH 2-SIH-221 1 RS RH J - SI-114.2 SNP SUPPORT LOAD i

SQNP Plant: SQNP Unit: 2 SI-114.2 P ge 10 cf SIM Page 10 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA*S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-SIH-222 I RS RH , 2-SIH-223 1 RS RH 2-SIH-224 1 RS RH 

        ~   .

2-SIH-225 1 RS RH 2-SIH-226 1 RS RH 2-Sill-227 1 RS RH 2-SIH-228 1 RS RH 2-S1H-229 1 RS RH 2-SIH-318 1 RS RH 2-SIH-319 1 RS BE 415 s RS Size #1 2-SIH-320 I RS RH 2-SIH-363 1 RS RH 2-SIH-365 1 RS RH 2-SIH-364 1 RS RH 2-SIH-366 1 RS RH 2-Sill-415 2 VS Grin Sprg 2236# 2264# 1/8" up .375"-1" Fig 82 Type B Size 12 e SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P;ga 11 cf SI] . Page 11 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA*S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-SlH-416 2 RS RH 2-SIH-421 2 RS RH 2-SIH-422 2 RS RH 2-SIH-423 2 RS RH 2-SIH-424 2 RS RH 2-SIH-425 2 RS RH 2-SIH-426 2 RS RH 2-SIH-427 2 RS BE 415 RS 

,                                               Size #1 La J               2-Sill-428       2       RS     BE 415 T                                                RS Size #1 2-SIH-429         2       RS     RH 2-Sill-430        2       RS     RH 2-Sill-431        2       HS     BE 417     6"   3'-10-7/16" 3'-10-7/8" 7/16" C                          .69"-5.75" PSA-10 2-Sill-446        2       RS     RH 2-SIH-450         2       RS     BE 417     6"   l'-8-1/2"                     l'-8"       1/2" T        .25"-5.25"          l PSA-10                                                                                    -1 l

2-Sill-451 2 RS RJI ' 2-Sill-452 2 RS Rll SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pcge 12 ef S1H Page 12 of 12 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-Sill-453 2 VS BE 401 627# 608# 1/16" down .25" .93" Type B Size 8 2-SIH-454 2 VS BE 401 375# 407# 3/16" up .44"-1" 

             ,                             Tne B Size 6 2-SIH-455    2      RS    RH 2-S1H-456    2      RS    RH 2-SIlf-457   2      MS    BE 417    5"   l'-5-11/16"   l'-5"        11/16" T      .25"-4.06" PSA-3 2-SIH-458    2      RS    BE 415 d

4 RS Size 1 -.D I 2-Sill-459 2 RS BE 413 RS Size 1 2-Sill-460 2 RS Rif 4 SI-114.2 SNP SUPPORT LOAD

SQNP Type SI-114.2 HS-Hydrmlic Snubber Page 1 of 8 MS-Mechanical Snubber Rev. 7 RS-Rigid Support VS-Variable Spring CHEMICAL VOLUME CONTROL CLASS 1 IA-Integrally Welded Attch Model COMPONENT SUPPORTS RS-Rigid Strut RH-Rigid Hanger G-Guide AR-Axial Restraint Plant: SQNP Unit: 2 Page 1 of CVCH IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-CVCll-001 1 RS RH-G 2-CVCll-002 1 RS RH-G - 2-CVCll-003 1 RS RH-G 2-CVCII-004 1 RS RH-G i 

 $O                2-CVCil-005    1      RS    RH-G 2-CVCll-006    1      RS    Guide RH Axial-Res 2-CVCII-007    1      RS    RH-G 2-CVCll-008    1      RS    RH-G 2-CVCil-009    1      RS    Ril-G 2-CVCil-010    1      RS    Ril-G 2-CVCII-011    1      RS    Ril-G 2-CVCll-012    1      RS    Ril-G f      .

SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P;.g2 2 cf CVCH Page 2 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERNAL ACCEPTABLE TVA'S IS1'S CLASS TYPE MODEL STROKE HOT COLD HOVEMENT RANGE 2-CVCH-013 1 RS RH-G 2-CVCH-016 1 RS RH-G 2-CVCH-017 1 RS RH-G 2-CVCH-018 1 RS RH 2-CVCll-019 1 RS RH 2-CVCil-020 1 MS BE 417 4" 2'-5-1/4" 2'-4" 1.25" T .25"-2.5" PSA-1/4 2-CVCll-021 1 RS RH 2-CVCll-030 1 RS RH-G i W 2-CVCll-031 1 RS RH-G c_D 

'                2-CVCH-032    1      RS    Ril-G 2-CVCil-033   1      RS    Ril-G 2-CVCll-034   1      RS    Ril-G 2-CVCH-035    1      RS    RH-G 2-CVCH-036    1      RS    RH-G 2-CVCH-037    1      RS    RH-G 2-CVCll-038   1      RS    RH-G 2-CVCll-039   1      RS    Ril-G 2-CVCil-040   1      RS    Ril-G f

SI-114.2 SNP SUPPORT LOAD-

SQNP Plant.: SQNP Unit: 2 SI-114.2 P :ge 3 cf CVCH Page 3 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE-TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-CVCH-041 1 RS RH-G 2-CVCH-042 1 RS RH-G 2-CVCH-043 1 RS RH 2-CVCll-044 1 RS RH-G 2-CVCil-045 1 RS RH-G 2-CVCH-046 1 RS RH-G 2-CVCH-047 1 RS RH-G 2-CVCH-048 1 RS RH-G s 2-CVCll-049 1 RS RH-G La 2-CVCll-050 1 RS RH-G 2-CVCH-051 1 RS RH-G 2-CVCll-052 1 RS RH 2-CVCll-053 1 RS RH-G 2-CVCll-054 1 RS RH 2-CVCil-055 1 RS RH 2-CVCil-056 1 RS RH-G 2-CVCil-057 1 RS Ril-G 2-CVCll-071 1 RS Ril-G SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P;g2 4 cf CVCH Page 4 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-CVCH-072 1 RS RH-G 2-CVCil-073 1 RS RH-G 2-CVCII-074 1 RS RH-G 2-CVCII-075 1 RS RH 2-CVCH-076 1 RS RH-G 2-CVCH-077 1 RS RH-G 2-CVCH-078 1 RS RH-G 

                            ~

2-CVCII-079 1 RS RH-G d 2-CVCil-080 1 RS RH-G co T 2-CVCil-081 1 RS Ril-G 2-CVCll-082 1 RS RH 2-CVCH-083 1 RS RH-G 2-CVCH-084 1 RS RH-G 2-CVCll-085 1 RS RH 2-CVCil-086 1 RS RH 2-CVCll-087 1 MS BE 416 2.5" 11-7/8" 10-3/8" 1.5" T .25" .75" Size 1/2 2-CVCll-088 1 RS RH 2-CVCil-089 1 RS Ril-G 2-CVCH-090 1 RS Ril-G t SI-114.2 SNP SUPPORT LOAD

SQNP Plent: SQNP Ur.it: 2 SI-114.2 Pcge 5 cf CVCH Page 5 of 8 - Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL TVA'S ACCEPTABLE ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-CVCH-101 1 RS RH-G 2-CVCH-102 1 RS RH-G 2-CVCH-103 1 RS RH-G 2-CVCH-104 1 RS RH-G 2-CVCH-105 1 RS RH-G 2-CVCH-106 1 RS RH-G 2-CVCH-107 1 RS RH 2-CVCH-108 1 RS RH

2-CVCll-119 1 RS RH-G -

to 2-CVCH-120 1 RS RH-G 2-CVCH-121 1 RS RH 2-CVCII-122 1 RS RH-G 2-CVCH-123 1 RS RH-G 2-CVCH-124 1 RS RH-G . 2-CVCH-125 1 RS RH-G 2-CVCH-126 1 RS RH-G 2-CVCH-127 I RS RH-G 2-CVCil-128 1 RS RH-G, 2-CVCil-129 1 RS RH-G ' SI-Il4.2 SNP SUPPORT LOAD

4 SQNP Plant: SQNP Unit: 2 SI-114.2 Page 6 cf CVCH Page 6 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-CVCH-130 1 RS RH-G 2-CVCH-131 1 RS RH-G 2-CVCll-132 1 RS RH-G 2-CVCII-133 1 RS RH 2-CVCH-134 1 RS RH-G , 2-CVCH-135 1 RS RH-G 2-CVCil-136 1 RS ANCHOR RH 2-CVCH-291 1 RS RH-G 8 5, v 2-CVCH-292 1 RS RH-G 2-CVCH-293 1 RS RH-G 2-CVCH-294 1 RS RH-G 2-CVCII-295 1 RS RH-G 

                                                            ~

2-CVCH-296 1 RS GUIDE RH AXIAL. RES 2-CVCil-297 1 RS RH-G 2-CVCil-298 1 RS Ril-G 2-CVCll-299 1 RS Ril-G a SI-114.2 SNP SUPPORT LOAD 

                                                                                                                   ~2 SQNP Plant: -SQNP      Unit: 2                                              SI-114.2    .               P;32 7 af CVCR Page 7 of 8 Rev.-7 IDENTIFIER        SAFETY        SUPPORT             DESIGN SETTING          THERMAL      ACCEPTABLE-TVA'S            ISI'S   CLASS   TYPE MODEL    STROKE     HOT        COLD        MOVEENT           RANGE 2-CVCH-300  1      RS     RH-G 2-CVCH-301  1      RS     BE 415 RS Size il 2-CVCH-302  1      RS     RH-G 2-CVCH-303                BE 416 1      MS               5"   l'-8"          l'-7-1/2"     1/2" T        .25"-4.25" PSA-3 2-CVCH-327  1      RS     RH-G 2-CVCH-342 1       RS     RH-G 2-CVCH-343  1       RS     RH-G E               2-CVCH-344  1       RS     RH-G m

$ 2-CVCH-345 1 RS RH-G 2-CVCH-346 1 RS BE 415 RS Size #1 2-CVCH-347 1 MS BE 416 5" l'-7-1/8 l'-9-1/2" 2-3/4" C 2.63"-4.75" PSA 3 2-CVCH-348 1 RS BE 415 RS Size #1 

                                                                                  ~

2-CVCH-349 MS BE 416 9-1/8" 8-1/4" 1 2.5" 7/8" T .25"-1.375" PSA 1/2 2-CVCH-360 1 MS RH-G e SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pcge 8 cf CVCH Page 8 of 8 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-CVCH-361 1 RS RH-G 2-CVCH-362 1 RS RH 2-CVCH-363 1 MS BE 417 5" 17-3/8" 16-5/8" 3/4" T .25"-4" PSA-3 2-CVCH-364 1 MS BE 416 6" l'-11-5/8" 2'-0-1/4" 5/8" C .875"-5.75" PSA 10 t l I i e 1 , w Y I, SI-114.2 SNP SUPPORT LOAD

SQNP Type SI-114.2 HS-Hydrculic Szubber Page 1 of 1 MS-Mechanical Snubber Rev. 7 RS-Rigid Support VS-Variable Spring CONTAINMENT SPRAY CLASS 2 SUPPORTS IA-Integrally Welded Attch Model RS-Rigid Strut RH-Rigid Hanger G-Guide AR-Axial Restraint Plant: SQNP Unit: 2 Page 1 of CSH IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE l TVA'S ISI'S _ CLASS TYPE MODEL STROKE HOT COLD HOVEMENT RANGE 1 2-CSH-440 2 RS BE 415 RS j Size #2 j 2-CSil-441 2 RS BE 415 '; RS 4 8 Size #1 j ad

0) 2-CSil-442 2 RS Rii (D

2-CSH-445 2 VS SPRING 3518# 3835# 3/16" up .44"-1" l BE 401 Type F Size 14 i 1 2-CSH-450 2 RS BE 415 i RS Size #1 1 j , SI-114.2 SNP SUPPORT LOAD

SQNP SI-114.2 m T RS-Rigid Support Page 1 of 9 VS-Variable Spring , Rev. 7 MS-Mechanical Snubber IA-Integrally Welded Attch UPPER HEAD INJECTION HS-Hydraulic Snubber Model CLASS 1 & 2 COMPONENT SUPPORTS RS-Rigid Strut RH-Rigid Hanger Plant: SQNP Unit: 2 Page 1 of UHIH IDENTIFIER SAFETY SUPPORT DESIGJ SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-UHIH-1 1 RES- RH TRAINT RS 2-UilIH-2 1 RS 2-UllIII-3 1 RES- Size 7 TRAINT RS i RS BE 415 05 

 -[               2-UllIII-4   1      RES-    BE 415 TRAINT  RS Size 3 2-UllIII-5   1      RES-    RH TRAINT RS 2-U11111-6   1      VS      G Fig.                1742#        1803#  .09" up        .34"-1.00" l                                              C-82 "E"
Size 11 l

l 2-U11111-7 1 MS BE 416 ~5 " 20-29/32" 21" 3/32" 11/32-4.75" 2-U11111-8 1 RES- Ril TRAINT RS SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pcge 2 cf UNIH Page 2 of 9 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING ' THERMAL ACCEPTABLE TVA'S- ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-UllIH-9 1 MS BE 416 6" 2'-2-1/2" 2'-2-1/4" .25" .25"-5.50" Size PSA-10 2-UHIH-10 , 1 MS BE 417 6" 20-3/4" 19-3/4" 1" .25"-4.75" Size PSA-10 1 2-UllIll-11 1 MS BE 417 5" 4'-9-3/8" 4'-7-7/8" 1.5" .25"-3.25" Size PSA-3 2-UllIH-12 1 VS G FIG 3221# 3461# .31" up .56"-2.25" C-268 TYPE 'F' 

   ,                                             Size 14 g               2-UllIII-13    1       MS     BE 416     6"    24-1/2"       24-1/4"       .25"          .25"-5.50" i                                            Size PSA 10 2-UllIll-14    1       MS     BE 417     5"    40"           40-1/4"      .25"           .50"-4.75" Size PSA 3 2-UllIII-15    1       MS     BE 416     5"    20-5/16"      21-3/4"      1-7/16"        1.69"-4.75" Size PSA 3 2-U11111-16    1       MS     BE 416     5 ',' 16-3/4"       17-1/4"      1/2"           .25"-4.25" Size PSA 3 2-U11111- 17           VS     GRINNEL          1514#                      1-1/2" Up 1                                             1771#                       1-3/4"-4-4/34" Fig C-98 Type G Size 11 SI-114.2 SNP SUPPORT LOAD

SQNP.. Plant: SQNP Unit: 2 SI-114.2 Pcg2 3 cf IElIN Page 3 of 9 Rev. 7 IDENTIFIER SAFETY SUPPORT - DESIGN SETTING THERNAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT- RANGE 2-UllIH-18 I MS Size 6" 4'-9.377" 4'-9.75" .373" .25"-5.377" PSA 10 2-UHIH-19 1 MS Size- 6" 7' .15" 7' .5" .350" .603"-5.75" PSA 35 2-UHIH-22 1 MS Size 5" 18.53" 18.75"- .224" .474"-4.75" PSA 3 2-UllIH-23 1 MS Size 6" 22.728" 22.875" .147" .397"-5.75" PSA.10 2-UHIll-24 1 RS RH t 2-UllIH-25 1 RS RH (A S' 2-UHIll-26 1 VS GRINNEL 804# 925# 0.6"Up 0.85"-2.25" Fig C-268 Type A Size 9 2-UllIII-27 1 MS BE 417 2-1/2" l'-11-9/16" 2'-3/16" .6" 0.85"-2.25" Size PSA 1/2 2-UHIll-28 1 RS 2-UHIll-29 1 VS GRINNEL 865#- 1000# 1-3/8" 1-5/8"-4-3/4"- FIG C-98 Type B Size 9 2-U11111-30 1 MS BE 417 5" 2'-5-7/8" 2'-7-1/4" 1-3/8 up 1-5/8"-4-3/4" PSA 3 2-U11111-31 1 RS Ril P SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2- SI-114.2 Pcge 4 cf UNIH Peg 2 4 cf 9 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-UllIH-32 1 MS BE 416 6" 2'-0-5/16" 23-7/8" 7/16" 1/4"-5-5/16" PSA 10 2-UllIH-33 1 MS BE 417 5" 17-3/8" 16-1/2" 7/8" 1/4"-3-7/8" PSA 3 2-UllIII-34 1 IA 2-UllIII-34 1 VS GRINNEL 1346# 1606# 1.53" up .25"-3.22" FIG-C98 Type E Size 11 2-UllIII-35 1 MS BE 417 6" 3'-3-1/8" 3'-1-5/8" 1/2" 3/4"-5.75" PSA 10 d .D 2-UllUll-36 1 MS BE 417 5" 4'-1" 3'- 1-1/16" 1/4"-3-11/16" PSA 3 11-15/16" Y 2-UllIII-37 1 MS BE 417 5" 16" 17-1/8" 1-1/8" 1-3/8"-4.75" PSA 3 2-UllIII-38 1 MS BE-416 6" 25-3/16" 23-5/8" 1-9/16" 1-13/16"-5.75" Size PSA 10 2-UllIII-39 1 MS BE 416 6" 24-13/16" 24" 13/16" 1/4"-4-15/16" Size PSA 10 2-UllIll-40 1 VS GRINNEL 1657# 1954# 1-3/4" up 2"-4-3/4" Fig C-98 Type "B'? Size 11 2-UllIII-41 1 MS PSA 35 6" 2'-4.902" 2'-5-1/4" .348" .25"-5.402" SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P;;g2 5 cf. UNIH Page 5 of 9-Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-UllIll-42 1 MS PSA 35 6" 2'-4.9" 2'-5-1/4" .345" .595"-5.75" 2-UllIli-45 1 MS PSA 3 5" 18.91" 19-1/4" .343" .6"-4.75" 2-UllIll-46 1 MS PSA 10 6" 22.53" 22-7/8" .343" .593"-5.75" 2-UllIII-47 1 RS BE 415 - I SWAY STRUT Size 2 a 2-UllIll-60 1 RS RH 2-U11111-61 1 RS Rif I 2-U11111-62 1 RS Rif w 

; -D wi 2-UllIII-63    1      RS      Rif 2-UllIll-64    1      RS      Rii 2-UllIII-65    1      RS      RH

, 2-U11111-66 1 RS RH 4 2-UllIll-67 1 MS BE 416 5" l'-8-3/8" l'-8" 3/8" 1/4"-4-3/8" PSA-3

2-UllIll-68 1 MS BE 417 5" 17-1/16" 16" 1-1/16" 1/4"-3-11/16" PSA 3 4

2-U11111-69 1 MS BE 416 4" 17-1/4" 15-3/8" 1-7/8" 1/4"-1-7/8" PSA-1 4 SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pag 2 6 cf UNIH Peg 2 6 cf 9 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-UHIll-70 1 VS GRINNEL 3524# 3724# 1/4" up Fig C-268 1/2"-2-1/4" Type "F" Size 14 2-UHIll-71 1 MS BE 416 5" 2'-8-7/8" 2'-8-1/4" 5/8" Size 1/4"-4-1/8" PSA 3 2-UllIll-72 1 MS BE 417 5" 4'-0" 4'-0-3/16" 3/16" 7/16"-4-3/4" PSA 3 2-U11111-73 1 VS GRINNEL 774# 909# 1-7/16" up 1-11/16"-4-3/4" Fig C-98 Type G Size 9 bD 2-UllIll-74 1 MS BE 417 5" 16-11/16" 17-5/16" 5/8" 7/8"-4-3/4" PSA 3 2-U11111-75 1 MS BE 416 5" 20-5/16" 21-3/4" 1-7/16" 1-11/16"-4-3/4" PSA 3 2-UllIll-76 1 MS PSA-35 6" 2'-3.97" 2'-5-1/4" 1.28" 1.53"-5.75" 2-UllIII-77 1 MS PSA-35 6" 2'-4.743" 2'-5-1/4" .507 .757"-5.75" 2-U11111-80 MS PSA-10 6" 22.408 i 1 22-7/8" .467 .717"-5.75" 2-UllIII-92 1 RS Rif 2-U11111-94 1 RS Rif 2-U11111-95 1 RS Ril 2-Ulilli-96 1 RS Ril SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 P gi 7 ef UNIH. Page 7 of 9 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD- MOVEMENT RANGE 

                                                                                        ~

2-U11111-100 2 RS RH 2-UllIH- 101 2 IA 2-UllIll-101 2 MS BE 416 6" 2'-0-7/16" 2'-0-3/8" 1/16" 1/4"-5-11/16"- PSA 10 2-Ulilli-102 2 IA 2-UHIII-102 2 RS RH 2-UllIH-103 2 VS GRINNEL 4575# 4564# .01" down .25"-1.99" Fig C-268 Type D - Size #15 u, 2-UllIll-104 2 IA 

'               2-U11111-104  2      RS    RH 2-UllIII-105  2      IA 2-UllIll-105  2      MS    BE 416     6"     2'-0-5/16"    2'-0-3/8"    1/16"          5/16"-5.75" PSA 10 2-U11111-106  2      RS    RH 2-UllIll-130  1      MS    PSA 35     6"     2'-4.784"     2'-5-1/4"    .466"          .716"-5.75" 2-UllIII-131  1      RS    Ril 2-U11111-132  1      RS    Ril 2-UllIll-133  1      MS    BE 416     4"     15-3/8"       15-7/8"      1/2"           .75-3.75" PSA 1 4

SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pig 2 8 cf UNIH Page 8 of 9 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-U11111-134 1 VS GRINNEL 729# 807# 1/2" up 3/4"-2-1/4" Fig C-268 Type B Size 8 2-UllIII-135 1 RS RH 2-UllIII-136 1 RS RH 2-UllIll- 137 1 VS GRINNEL 586# 649# 1-1/8"Up 1-3/8"-4-3/4" Fig C-98 Type G Size #7 e 2-U11111- 138 1 MS BE 416 4" 16-1/2" 15-3/8" 1-1/8" 1/4"-2-5/8" , y PSA 1 s' . 3 2-UllIll-139 1 MS BE 416 4" 15-7/8" 15-1/8" 3/4" 1/4"-3" < . PSA 1 ! 2-U11111- 140 1 IIS BE 417 5" 17-1/2" 16-1/2" 1" 1/4"-3-3/4" PSA 3 2-UllIII-141 1 VS GRINNEL 1279# 1471# 1.13" up 1.38"-4.75" Fig C-98

Tge F Size 11 2-U11111- 142 1 MS BE 416 4" 16" 14-7/8" 1-1/8" 1/4"-2-5/8" PSA 1 2-UllIll-143 1 MS 2-U11111-144 1 MS BE 416 6" 23-3/4" 24-3/4" 1" 1-1/4"-5-3/4" PSA 10 4

SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 SI-114.2 Pag 2 9 cf UHIH. Page 9 of 9 Rev. 7 IDENTIFIER , SAFETY SUPPORT DESIGN SETTING TliERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-UHIH-145 1 MS BE 417 5" 16-1/2" 17-1/2" 1" 1-1/4"-4-3/4" PSA 3 2-UllIll-146 1 VS GRINNEL 1645# 2038# 1-3/4" up 2"-4.75" Fig C-98 Type '6' Size 12 2-UllIII-147 1 MS BE 416 5" 20-1/8" 21-7/8" 3/4" 1"-4. 7.5" PSA 3 i 2-UllIII-148 1 MS PSA 35 6" 2'-4.43" 2'-5-1/4" .816" ' 1.066"-5.75" 2-UHIll-149 2 MS PSA 10 6" 22.48" 22-7/8" .395" .645"-5.75" d a 2-UllIII-152 1 MS PSA 10 6" 22.463" 22-7/8" .412" .662"-5.75" Y 2-U11111- 153 2 MS PSA 3 5" l'-6.84 l'-7-1/4" .412" .662"-4.75" 4 SI-114.2 SNP SUPPORT LOAD

SQNP Plant: SQNP Unit: 2 -- SI-114.2 P;ga 2 ef FDH-Page 2 of 4 Rev. 7 l IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S ISI'S CLASS TYPE MODEL STROKE HOT ' COLD MOVEMENT RANGE 2-FDil-205 2 RS RH 2-FDH-206 2 IIS BE 410 5" 4-1/8" 3-5/8" .5" T 1-1/2"-5-1/2"  : CYL:6" I X=1.25" 2-FDil-207 2 RS RH-G 2-FDil-208 2 RS RH-G 2-FDil-240 2 RS BE 415 RS Size 6 a 2-FDil-241 2 RS RH-G te; j 2-FDil-242 2 VS BE COUNTER-POISE l Type 9 Size 38 l 2-FDil-243 2 MS BE 417 6" 19-9/16" 20-3/4" 1-3/16" C 1-7/16"-5-3/4" PSA 10 2-FDil-243 2 VS GRINNEL 1865# 2007# 5/8" up 7/8"-4-3/4" SPRING FIG C-98 Type B S2.12 2-FDif-244 2 IIS BE 411 5" 3-5/16" 3-5/16" 5/8" C 2"-5.875" Size 3-1/4" X=1-1/8" 

                                                                                          =1.125 4

SI-114.2 SNP SUPPORT LOAD

/. SQNP T_ype . SI-114.2 HS-Hydrculic Snubber P:ge 1 of 4 MS-Mechanical Snubber Rev. 7 RS-Rigid Support VS-Variable Spring FEEDWATER IA-Integrally Welded Attch-CF-Constant Force CLASS 2 COMPONENT SUPPORTS Model RS-Rigid Strut RH-Rigid Hanger; Plant: SQNP Unit: 2 Page 1 of FDH IDENTIFIER SAFETY SUPPORT TVA'S DESIGN SETTING THERMAL ACCEPTABLE ISI'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-FDII-200 2 RS RH 2-FDH-201 2 RS BE 415 - RS Size 7 2-FDil-202 2 VS BE 

    ,                                             COUNTER-1-13/16" up 2-1/16"-2-3/4" w                                              POISE
   -4                                        ,

Type 'S' Total Travel =3" 2-FDil-203 2 MS BE 417 6" 19-5/16" 20-1/2" 1-13/16" C 2-1/16"-5-3/4" PSA 10 2-FDif-203 2 VS GRINNEL 2152# 2298# .65" up .90"-4.75" SPRING FC-C98 Type B Size 12 2-FDif-204 2 MS BE 416 6" 19-3/4" 19-7/8" 1/8" C .375"-5.75" PSA 10 4 SI-114.2 SNP SUPPORT LOAD

SQNP .  % Plant: SQNP Unit: 2 SI-114.2 P g2 4 d'FDH = - Page 4 of 4 Rev. 7 IDENTIFIER SAFETY SUPPORT DESIGN SETTING THERMAL ACCEPTABLE TVA'S IS1'S CLASS TYPE MODEL STROKE HOT COLD MOVEMENT RANGE 2-FDil-321 2 RS RH 2-FDif-322 2 VS BE 1-13/16" up 2-1/16"-2-3/4" COUNTER-POINT Type S Size 38 T.T=3" 2-FDH-323 2 MS BE 417 6" 19-1/2" 20-3/4" 1-1/4" T 1/4"-4-1/2" PSA 10 2-FDil-323 2 VS FIG C268 3572# 4122# .67" up 9/10"-2-1/4" GRINNEL SPRING f f 2-FDil-324 2 IIS BE 410 5" 3-15/16" 3-5/16" 5/8" T 1-3/8"-3" 2 Size #4

X=1.125 2-FDil-325 2 RS Ril 2-FDH-326 2 RS BE 415 RS Size 7 2-FDll-327 2 RS RIl 2-FDll-328 2 RS RH 2-FDil-329 2 RS BE 415 RS Size 6 SI-114.2 SNP SUPPORT LOAD
                                ,}}
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