ML17130A313
| ML17130A313 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/06/2017 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17130A259 | List:
|
| References | |
| Download: ML17130A313 (189) | |
Text
{{#Wiki_filter:EXHIBIT I REACTOR PRESSURE VESSEL PURCHASE SPECIFICATION 21A1111 APPENDIX K K.I-1 REV. 25, APRIL 2015
EXHIBIT I - REACTOR PRESSURE VESSEL PURCHASE SPECIFICATION 21A1111 The power rerate design requirements are unchanged from the original design requirements specified in Exhibit I, Section 5 (i.e., design pressure of 1250 psig at bottom of the reactor vessel, design temperature of 575°F). The power rerate normal operating pressure is increased from 1005 psig to 1035 psig at top of reactor vessel. The normal operating temperature is increased from 547°F to 551°F. The operating shroud support pressure differentials provided in Appendix K, Exhibit I, Section 7.5.1 are increased from 34.0 and 21.85 to 35.68 and 26.32 psid for power rerate. Estimates for reactor vessel irradiation at the end of 60 years have been recalculated based on actual data obtained from the reactor vessel surveillance specimens which were removed and analyzed. The updated information presented in Sections 4.2.4 and 4.2.5 supersede the information contained in Exhibit I Section 5.1.11. Expected operating cycles for which fatigue has been evaluated are listed in UFSAR. The Unit 2 and 3 TPO power rerate did not change the normal operating pressure or temperature for the reactor vessel. The extended power uprate (EPU) did not change the normal operating pressure or temperature for the reactor vessel. The design pressure differentials across the shroud support and shroud provided in Appendix K, Exhibit I, Section 7.5.12 are not exceeded for EPU. APPENDIX K K.I-1A REV. 25, APRIL 2015
PBAPS ern ERAL 0 ELECTR re SPECIAL l'~JEC1 ATOMIC POWER EQUIPMENT Dr'ARTMENT
'~.C.HO. 21Allll, MCV.NO. 9 PURCHASE SPECIFICATION - t.\T:. SH!ET ... 110. 2 CON" 0*' .--ca r 3 REACTOR PRESSURE VESSEL SECTtON TITLE 1 SCOPE 2 RESPONSIBILITY 3 GENERAL DESCRIPnON 4 CODES 5 DESICH lEQUItwmHts 6 _ DESIGN ANALYSIS 7 CONST1UCTIOH 8 MAnuALS 9 FABRICATION l~ INSPECTION Ale TEST 11 PJEPARATION FOR SUIPMEHT 12 SUBKITTALS AtTACHMENT A - IHSTRUcrION MANUAL.
DIWlING AND D.\TA REQUIIt.!M!HTS ATtACHMENT B - TEST SAMPLES
------~----------~--~---.------~----------
- 1. SCOPE 1.1. This specification d.fines the enlineeriDI requirements of the equipment specified herein.
1.2. The work dODe by*the Saller in accordance with this specification*.hall include all necessary desi6ft. development, analysis. drav1nss, evalu3tion of mat~ria1s and fabrication methods, fabrication, shop testina. inapection and preparatieD for 8hipment. K.I-2
GErJERALtj) ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT
....e. NO. 2WlIl, ... v. No.9 PURCHASE SPECIFICATION 1M NO. 3 CONY ON 'H*
- y 4
- 2. RESPONSIBILITY 2.1. Th_ Seller shall accept full responsib~lity for his York and for compliance with this specification. Review or approVal of drawinss,procedur.es, data or speci-fications by the Buyer with regard to general design and controlling dimensioDs does not constitute acceptance of any designs, materials or equipment ~hich will not fulfill the functional or performance 'requirements established by the purchas.
contract. *
- 3. GENERAL DESCRIPTION 3.i. The reactor vessel will be used as a pressure. container s~pport1ns the ste..
senerating core. 3.2. The equipment to be furnished in accordance with this specification shall be one reactor pressure vessel assembly with a removable head and nozzles and certain internal support structures, arranged as shown on Draying 886D499 complete with: 3.2.1. Attachments for thermal insulation, vessel and,core supports, brackets or legs for lift:f.ng and h<<ndlins of VI;llAIlIP.l hP.Ild, and mounts for outside surface thermo-couples. 3.2.2. One set of necessary special tools re,uired to remove and replac~ the reactor vessel head. The set of tools shall ~nclude: four hydraulic stud ten-sioners,stud elongation measuring device, stud and nut wrenches, one set of stud thread pr~tectors, three head suide caps, one bushing wrench, one stud slinS. Stud tensioners shall be in accordance with Specification 21A9821 and shall 1n-~ clude a lifting device that properly spaces ~he tensioners over the 'volt circle. 3.2.3. One set of necessary special tools required to install and remove the re-actor Ve~8p.~ head seals with manual contact. This set of tools shall include a protective cover for the reactor vessel 'shell flange seal surface. 3.2.4. MCt~1 boxes for the hand tools. Boxes shall be suitable for handling with a crane and/or fork lift truck. 3.2.5. One lot of reactor vessel material test plate and m3terial test specimens
'in accordance with Attachment B.
3.2.6. Deleted
'SSUED, AUG 2 6 1970 K.I-3 .
GENERAL 0 ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT I~EC. NO. 2lAllll. REV. No.9 PURCHASE SPECIFICATION IH NO. 4 CONT ON SHEE r 5
- 4. CODES 4.1. ~e reactor vessel shall be designed, fabricated, inspected, tested and stamped in accordance with the American Society of Mechanical Engineers (AsHE),.
Boiler and Pressure Vessel Code, Section III, applicable requirements for Class A Vessels as defined therein, interpretations of the AsHE Boiler and Pressure Vessel Code, and all laws, rules and regulations of the state in which the reactor plant will be locatea which are in effect on the date of the contract. 4.2. Deviations from the applicable codes or regulations shall be avoided. Where a conflict exists among the codes or regulations', the Seller shall bring this to the Buyer's attention. It shall be the responsibility of the Seller to obtain resolution and disposition of deviation with the Buyer and other appropriate parties and authorities. 4.3. The intent of this specification is to supplement the req~irements of the codes specified herein and to encompas& the means whereby the design ~bjective is satisfied. 4.4. All standards and materials specifications shall be per latest revision in effect on the date of the contract.
- 5. DESIGN REQUIREl-mNTS 5.1. Operating Conditions 5.1.1. .Internal pressure. Design pressure: 1250 psig at bottom of the reactor vessel. Normal Operating Pressure: 1005 psig at top of reactor vessel.
5.1.2. Temperature. Design temperature: 575°F Normal Operating Temperature: 547°F 5.1.3. ~eactor core and internal weight. 1be weight of the reactor core and in-ternal structure, centers of gravity and distribution of loadings are shown on Drawing 886D499. 5.1.4. Water weight. The weight of water contained in the vessel for various conditions of operation are presented on Drawing 886D499. 5.1.5. Pipe reactions. The Buyer shall provide the Seller with the pipe reactions which the connecting piping will apply to all nozzles with a nominal size larger than the reactor vessel wall thickness and those nozzles which in addition are sub-jected to significant thermal cycling. The reactions will be limited by the Buyer such that the combined stress 3S due to pipe reactions and design pressure in the vessel shell.at the nozzle attachment will not exceed the design stress allowed by the AS~m Code, Section III. These pipe reactions shall be used in the detailed stress analysis require~ by the Code and performed by the Seller. This analysis shall include the thin section of the nozzle in the vicinity of the weld prepara-tion fpr connecting piping, any bi-metal weld and shall- take into account the nozzle el:adding. ISIUEDI AUG 2 6 1970 K.I-4
GEtJ ERA L( ) ELEe TRIC ATOMIC POWER EQUIPMENT DEPARTMENT S.ECoNO. 21Allll ~EV.NO. 9 PURCHASE SPECIFICATION SH NO. 5 CONT ON SHeET 6 5.1.6. Control rod drive weight and reaction. *The momentary reactions which are suddenly applied to each control rod driue housing in the vessel, bottom head are presented on Drawing 886D499. 5.1.7. Steady state thermal conditions. Steady state metal temperatures will be computed by the Seller for no more than twelve locations on the reactor vessel. The locations will include the head and ,shell closure flanges, the sfiell adjacent to the reactor core, the bottom head and major nozzles including the control rod drive nozzles. Temperature gradients through the shell wall' adjacent to the por-tion of the reactor core peak flux zone will be co~puted by the Buyer and furnished to the Seller. Data will be presented on Drawings 729E762 and l35B9990. S.1.8. Cyclic loading. Reactor coolant temperature, pressure and flow changes at the above twelve locations, together with the expected number of cycles, will be furnished to the Seller by the Buyer. The total number of different cyclic changes whieh must be analyzed at anyone location will be limited to six. Data will be presented on Drawings 729E762 and l35B9S90. 5.1.9. Earthquake loads. Earthquake loads shall be taken into account in accord-ance with the criteria and load presented on Drawing 8860499. 5.l.JO. Internal Heat Generation. The maximum internal heat generation due to 8 Amm.Q hE!l!t~_ng 1.8 S.-S'x 10 3 BTU/ft3 hr at the inside of the reactor pressure vessel .- opposite the active fuel zone
- 5.1.11. Neutr~n Irradiation. The maxim~ neu~ron irradiation for fast (~l Mev) neutrons is 3.8 x 10 17 nvt for 40 years at the inside of the reactor pressure vessel wall opposite the active fuel zone.
5.2. Design Considerations 5.2.1. Design*ob1ective. The objective shall be to design and fabricate this reactor vessel to have a useful life of forty years under operating conditions sp-ecified by the auyer. 5.2.2. Reactor vessel supports. Reactor vessel supports, internal supports, their attachments and adjacent shell shall be designed to take maximum combined loads in-cluding control rod drive reactions, earthquake loads, and jet reaction thr~sts as defined on Drawing ~86D499. There shall be no gross yielding of the reactor vessel
~upports causing permanent displacement under these conditions.
5.2.3. Stress concentrations. Care shall be taken in design and fabrication to minimize stress concentrations at changes in sections or penetrations. Fillet radii shall be equal to at least half the thickness of the thinner of the two sections being joined. If reinforcement for openings (except the control rod drive and in-core flux monitor nozzles) requires local vessel shell added thickness, such reinforcement shall extend at least 1-1/2 times the diameter of the opening from the c.enter of the opening. These requirementR are not to be construed as a waiver for evaluating the stresses for use in the analysis for cyclic operation.
' **UEO:
AUG 2 61970 K.I GENERAL 0 ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT
,PEC. NO. 2lAllli "EY. No.9 PURCHASE SPECIFICATION SH NO.* 6 CONT ON SHEET 7 5.2.4. Corrosion allowance. Exterior exposed ferritic surfaces of pressure-con-taining parts including heads, shell, flanges and nozzles shall have a minimum corrosion allowance of 1/16 inch. The interior surface of. carbon or low alloy steel nozzles exposed to the reactor coalant shall also have a minimum corrosion allowance of 1/16 inch. If the main closure head is left unclad. its interior .
surface shall also have a minimum corrosion allowance >of 1/16 inch. 5.2.5. Main closure seal. The reactor pressure vessel main closure seal shall be a double seal designed to have no detectable leakage thro~gh ~he inner or outer member at all operating conditions. These conditions inclUde, but are not limited to: (a) cold hydrostatic pressure test.at*the design pressure. (b) heating to design pressure and temperature at a rate of lOO*F/hr ** maximum, (c) operating for extended periods of several months duration at operating conditions. and (d) cooling at a rate of lOO*F/hr., maximum. 5.2.6. Design stress. Design stress values used in the calculations shall be as contained in ASME Section III and applicable interpretations of ASHE Boiler and Pressure Vessel Code for materials covered therein. The design stress values for ASME, Section III calculations for other materials approved by the Buyer in accord-ance with Paragraph 8.1. of this specification. shall be determined per APpendix II. ASHE Code, Section III. 5.2.7. Dimensional control. Seller shall show the method of controlling measuring and maintaining alignment and location ~f control rod drive penet~ation8 wfth the vessel and core supporta. 5.2.8. The reactor shall be designed to minimize retention pockets and crevices. 5.2.9. The jurisdiction of Section III of the Code shall include all attachments to pressure boundary parts. wt,~re weld buildup pads are used to attach inte~a!_ or external brackets. the vessel support skirt, the shroud sppport or the refvel-ing bellows support skirt. the weld buildup pad shall be considered the attachment to the pressure boundary part. Section III shall be used as a guide in the design. fabrication and inspec.tion of parts attached to the attachments to pressure boundary parts.
- 6. DESIGN ANALYSIS 6.1. Requirements The Seller shall perform the design. calculations and analyses as required by the
>applicable Standards and Codes indicated in Section 4. The requirements of Article
- 4. ASME Code, Section III, shall be fulfilled. The analysis required shall be performed in two divisions as follows:
6.1.1. Stress annlysis. A stress analysis shall be performed in accordance with Section N-430. ASME Code Section III. CalculatIons shall be performed in accord-ance with Paragraph N-43l to verify that the minimum wall thickness is provided. A detailed stress analysis shall be performed in accordance with Paragraph N-432. This analysis shall take into account all combinations of loads in conjunction with metal temperatures, as indicated in Section 5. above, and Drawings 729E762 and l3SB9990, within the nesign Stress Criteria of As~m Code Section III, Article 4. IAuf2 61970 K.I-6
GEr. ERA L~ ELEeTRIC ATOMIC POWER EQUIPMENT DEPARTMENT PURCHASE SPECIFICATION 21Allll "EV. No.9 7 CONTONt" E E T 8 6.1.2. Analysis for cXclic oper~. The Selle~ shall perfor. an analysis in accordance with Section N-4IS'of the ASHE Code, Section III,. to determine that the vessel i. suitable for the cyclic loading conditions of Paragraph 5.1.8. above. This analysis shall also be performed wiUhin" the desian stress criteria of' Section III, Article 4, to establish whether the design objective in Paragraph 5.2.1. above is reached. The analysis will be used to determine the adequacy of any required thermal baffling used to control or limit*thermal stresses and to place safe opera-ting limits on the cyclic conditions imposed on the vessel where it is reasonable to control them, as in the startup heating rate and shutdown cooling rate. 6.2. Calculation of Stresses 6.2.1. The detailed structural analysis required to meet the requirement. of 6.1. shall be made for the stresses resulting from internal pressure, external and internal loadings, and the effects of steady and fluctuation teaperature8 and loads for regions given in 6.3. which involve changes of shape, structural discontinuities, and points of concentrated loadings. 6.2.2. Where dimensions and loading conditions permit, the adequacy of struc-tural elements will be verified by comparison with completely analyzed elements. The calculations shall include a complete analysis of stresses under 8teady state and transient conditions to d~termine suitability of the design with respect to the allowable stress given in AS~ Code, Seetloft III, .ad to detetaiBa ~he 0p.~. tionai l1mitations with respect to fatigue of the reactor vessel materials over the life of the reactor vessel (Design Objective) using the loading conditions supplied by the Buyer. 6.3. Parts of the Reactor Vessel Ass~mbly to be Analyzed 6.3.1. The parts of the reacto~ vessel to be analyzed shall include: head closure, bottom head, shell adjacent to reactor core, reactor vessel supports and stabilizers, supports for reactor vessel internals, control rod drive penetration, feedwater nozzle, poison, nozzle, emergency core cooling nozzles, drive system return nozzle, and all nozzles 10 inches or larger in size. 6.4. Closure Head Seal Calculation 6.4.1. To assure meeting sealing requirements of the main closure seal as speci-fied in Paragraph 5.2.5. above, the relative rotations of the flanges shall be calculated. These totations shall be used to demonstrate analytically satisfactory seal performance using the following assumptions: 6.4.1.1. The mating surfaces of the flanges shall be assumed rigid. 6.4.1.2. The rotation shall be assumed to cause contact over the minimum area which will sustain the loading between the faces when stressed to the yield strength at the metal temperature. 6.4.1.3. The flange faces shall be assumed to diverge from the contact a~ea, speci-fied in Paragraph 6.4.2., throub~ the angle of calculated relative rotation les8 any radial -~per machined on the ce(s) to accommodate the flange rotations. I'~'tltr'2 6 1970 I IS. 1-7
GENERAL" ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT PURCHASE SPECIFICATION I"EC. NO. 21 Alill IItE¥. NO. 9 1M NO. 8 co.n ON .... EET 9 6.4.1.4. It may be assumed that the seal will be maintained if, at both O-ring seal locations, the separation between flange8 i8 1e88 than the minimum elastic spring-back of the O-ring. 6.5. Calculations 6.5.1. The calculations shall be clear and in sufficient detail to permit in-dep~ndent checking. Specific references shall be given for all formulas and methods used or the formulas and methods shall be derived independent.1y. Cal-culation shall be submitted to the Buyer for apprOval. 6.6~ Descriptions of Computer.Programs 6.6.1. If computer programs are used to obtain solutions to design ~roblems, the Seller shall furnish the Buyer the description of each different computer program used. These descriptions shall be furnished with the first issue of the design calculations incorporating such programs. The computer program desc~iption shall include computer type, program capabilities, assump~ions, limitations and statement of availability. . 6.1. Measurement Report9 6.7.1. Measured values of strain, deflections or stresses resulting from tests on models or actual reactor vessels shall be supplied to the Buyer by the Seller. These reports ~ha1l include all information necessary to duplicate the conditions required to obtain the results repotted. 6.8. Summary Report 6.8.1. After completion of the reactor vessel design, the Seller shall furnish the Buyer addi~ional copies of all calculations plus a summary report of results of all computations. Each copy shall be bound in a suitable paper binding and indexed.
- 7. CONSTRUCTION The reactor vessel body including all components which contain pressure including the she~l, lower and upper heads shall be made of rolled plate and/or forgings welded witft full penetration welds throughout except as noted in 7.3.5. The shell and head flange and nozzles shall be forged.
7.1., Shell and Heads 7.1.1. Longitudinal and circumferential weld joints in the reactor vessel shall be oriented so as not to intersect openings or penetrations, wherever practical. Circumferential weld seams should avoid regions of highest neutron flux in the core region, if practical. The region of highest neutron flux occurs between the mid-plane and top of the *core. ISSUED: AUG 2 6 1970 K.I-a
GENERAL G ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT
."EC. NO. \lAllll REY. NO. 9 PURCHASE SPECIFICATION .H NO. CONT ON .MEIET10 7.1.2. Bottom head. The section of the bottom head which encompasses the pene-trations for the control rod drives and in-core flux monitors shall be either a single forging or dished plate, if practical. If this is not practical and a weldment'is used, the orientation of the weld sections shall as far as practical, minimize the number of intersections of weld seams with penetrations.
7.1.3. Top tiead. The top head shall be either a single forging or dished plate or shall be fabricated of sections welded together, with the orientation of the weld seams such that no seams intersect openings or penetrations. 7.1.4. Weld 10ints. Weld joints shall be designed to facilitate a maximum of radiographic examination per the ASHE Boiler and Pressure Vessel Code, Section III, Paragraph N-624. 7.2. Head Closure 7.2.1. Assembly and disassembly 7.2.1.1. The head closure shall be designed for removal and reassembly, using 4 or more hydraulic stud tensioners. 7.2.1.2. *It shall be the desi!R objective to replace and remove the head within 16 hours elapsed ti.e. Specifically, the cycle shall include placing the head oyer the studs, tightening the studs to operating bolt-up loads, unbolting and removal of the head over the studs. It is expected that 120 such cycles will be performed during the life of the reactor vessel. 7.2.2. ~ 7.2.2.1. The head seal shall be a double seal with a vent between the se~18 ~hrough which leakage of the inner ring can be detected. The seal vent shall be designed for full desi~ pressure of the reactor vessel. 7.2.2.2. The seal shall be metal a-ring type with pressure equalizing vents on I.D.
,7*.2.2.3. The grooves for the a-rings shall be placed in the reactor head flange.
Suitable fasteners shall be provided to hold the a-rings in the grooves during head removal and assembLy operations. 7.2.2.4. ~rovisions shall be made for installation of a low pressure leak detec-tion system outside of the second seal, and may be outside of the bolt circle. The provisions shall include a vent through the vessel flange with extended linch nipple and socket weld fitting and either a shallow groove or other suitable back-ing to retain a soft asbestos braided packing. There shall be no protruding parts of this low pressure seal beyond the O.D. of the head and vessel flange. ISSUED: AUG 2 61970 K.1-9
GENERAL ~~ ELECTRIC ATOMIC POWER EQUIPMENT OEPARTMENT SPEC. NO. 2lAIIIl "EY. No.9 PURCHASE SP ECIFICA nON aH NO. 10 CONTON aHEET 11 7.2.3. Bolting 7.2.3.1. Studs shall be used to secure the reactor vessel 'head. Stud, nut and bushing 'threads shall be in accordance with 'Drawing 885D91l. 7.2.3.2. The stud bolt holes in the reactor vessel flange shall be bushed with removable bushings. Keys shall be provided for each bushing to prevent rotation of the bushings when removing studs. 7.2.3.3. Spherical washers shall be used with the $tuds to minimize bending of the studs. 7"2.3.4. It shall be possible to remove and replace the head with the studs in-stalled. To facilitate head removal and replacement, three special guide caps shall be provided to couple onto three studs. The lengths of the guiding surfaces of the guide caps shall be staggered so that the shorter of the three Guide caps shall ex-tend above the top of the installed studs for a minimum distance of 4 inches. The length of the three guide caps shall be staggered in 3 inch minimum increments. The internal threads of the guide caps shall be similar to the stud nuts threads. The upper end of the guide caps shall be provided with a conical leak-in taper and a horizontal through-hole bored to accommodate a round bar for wrenching. 7.'.1.5. Flange ho le , bushing) and stud d~'signs shall be such that the studs st~d perpendicular to the flange surface when the studs and bushings are bottomed in the holes to facilitate removal and replacement of vessel head over studs as called for in Paragraph 7.2.3.4. 7.2.3.6. The surface of all threads in the studs, nuts and bushings shall be given a phosphate coating to act as a rust inhibitor and to assist in'retaining lubricant on the surfaces. An approved lubricant should be applied to the stn~ threads as soon as possible after coating. 7.~.3.7. A stud sling for the main closure' studs shall be provided. The stud sling shall include & swivel and counter-weight spring to support the weight of the, stud during turning of stud into vessel flange. Studs are to be provided with a wrenching surface accessible when suspended on sling. 7.2.3.8. All main load-carrying threads and spherical washers shall be assembled only after cleaningi gaging, and lubricating. In no case during fabrication or t.esting shall these parts be assembl,ed without lubricant. Only thread lubricant approved by the Buyer shall be used. R.I-IO
GEr~ ERAL C) ELECTRIC ATOMIC POWER EQUIPMENT OEPARTMENT
CC. NO. 21A1lll RCV. NO. 9 PURCHASE SPECIFICATION 1M NO. 11 CONY ON IHECT12 7.2.4. Flanges 7.2.4.1. The top head flange surface shall.be machined or the area around each stud hole spot faced. Spot facings shall be complete and extend beyond washer O.D. to accommodate maximum eccentricity of stud in head flange bolt hQle.
7.3. Nozzle Ends 7.3.1. The ends of all nozzles other than flanged nozzles shall be prepared for welding in accordance with Drawing l07CS30S. Nozzle safe ends are considered to be part of the vessel, not part of the connecting piping but in no case shall the s.fe end wall thickness be less than the wall thickness of the connecting pipe. 7.3.2. Where thermal sleeve nozzles are specified to a nominal size, the size of the pipe through the nozzle as well as the nozzle external end shall be the nominal size specified for the nozzle. Thermal sleeves shall be supplied by the Seller. 7.3.3. The Buyer will furnish information on the wall thickness. t p* of all piping connections and will set the inner bore diameter including tolerances and allow-ances of the connecting piping will follow ASA Standards. The Buyer will use the formulas and allowable stresses of B3l.l for establishing the required piping wall
~hi~~nPRRp.R. ~ozzle safe end wall th1c~ness shall be governed by Drawingl07CS305 and will in general be &r~ater than required by Sectiun.III.
7.3.4. Details of the transition weld preparation shall be submitted to the Buyer for approval. 7.3.S. Nozzles of 3 inches nominal size or larger shall be full penetration welded to the ve~sel. Nozzles less than 3 inches nom1nal size may be.partial penetratio~ '-._._- welded if permitted by ASHE Code, Section III. 7.4. The vessel top head nozzles shall be .provided with flanges with small groove facing. Match marked mating flanges with small tongue facing gaskets and a com-plete set o£ studs &~d nuts shall also be provided. The loose flanges for the 6 inch instrument nozzles shall be blind. the Temainder shall be weld neck. The flanges and gaskets shall be in accordance with ABA Standards 816.5. The threads on studs and nuts shall be 8-pitch series in accordance with ASA Standard Bl.l. 7.5. Reactor Vess&l Support~ 7.5.1. External and internal supports shall be provided as an integral part of the reactor vessel. The location and design of the supports shall be such that stresses in the reactor vessel and supports will be within ASHE Code limits due to reactions at these supports. The pressure differentials across the shroud support and shroud shall be as tabulated below (higher pressure under the support). The design of the core shroud support shall take into account the restraining effect of the components attached to the supports and the weight and earthquake and jet loadings as shown on Drawing 886D499, Sheet 7. The design parameters given in Notes 1-8 of the above Drawing apply to components other than the shroud ,.- support. legs. The design parameters tabulated below shall be applied to the shroud support legs only. K.I-II
GEr~ ERJ~ J. ,r:~)
......;.J ELEe Tn I C ATOMIC POWER EQUIP"~ENT OEPARTMENT PURCHASE SP ECI FICA TlON SPf:C. NO. 2lAllll MEv. NO. 9 12 7.5.1. (Continued)
SHROUD SUPPORT DIFFERENTIAL PRESSURE Pressure (psid) Pressur-e Area Design Operating 57.0 34.0 >
=
98.375"R 39.0 21.85 < 98.375"R SHROUD SUPPORT LEG DESIGN PARA~TERS
- a. S max < Sm for tensile stresses at design pressure and temperature without seismic loads.
- b. S max < Sm for tensile stresses at operating pressure and temperature with s~ismic loads.
- c. S max < 1.5 Sm for tensile stresses at o~erating pressure and temperature with m~. seismic + jet loads.
- u. S max, 2.0 s~ for tensile stresses at design pressure anrl temperature with ma.". sei.smic + jet loads.
- e. S max ~ 0.4 Sy for compressive stresses at zero pressure and room temperature with seismic loads.
- f. S max ~ 0.6 Sy for compressive stresses at operating pressure and temperature with m~~. seismic + jet loads.
- g. S max ~ 0.8 Sy for compressive atresses at zero pressure and room tecp~rature with max. seismic + jet loads.
K.I-12
GENERAL ~ ELECTRIC ATOMIC POWER EQUIPMENT OEPARTMENT SPEC. NO. 2lAlll1 REV. No.9 PURCHASE SPECIFICA nON ON S"F.F.:~ll. SH NO. 13 CONT 7.5.2. The anchor bolts and the sole plate on which the reactor vessel rests will be furnished by the Buyer. 7.5.3. The drain nozzle shall extend 16 inches vertically below the bottom out-side surface of the reactor vessel and shall be of the full penetration design. 7.6. External Attachments 7.6.1. Brackets to support insulation shall be provided on the exterior of the reactor vessel in accordance with Drawing 886D499. 7.6.2. Provisions shall be made for the attachment of at least 36 thermocouples in mounts on the reactor vessel exterior as specified on Drawing 886D499. Exact location and number will be specified by the Buyer. The thermocouples shall not be furnished by the Seller.
- 8. MATERIALS 8.1. All materials to be used shall be indicated on the Seller's drawings. The Seller 9hal1 9ubmit for the Buyer's approval, all material selections ~nd mzterial purchatsing tsp~cification8.
8.2. Records 8.2.1. The Seller shall maintain complete records showing use o£ all materials so that it will be possible to relate every component of the finished reactor vessel to the original certification of the material and the fabrication history of the component. The Seller shall prepare a summary of the heat number, chc~ical composition and mechanical properties for each reactor vessel component. 8.3. Forgings 8.3.1. Low alloy steel forgings for pressur~ parts shall be made in accordance with ASTM A-508, in accordance with ASME Code Case 1332-2, Paragraph 5. Nozzles which are partial penetration welded as specified in 7.3.5. may be nickel-chroc-ium-iron forgings made in accordance with ASHE SB-166 modified in accordance with Code Case 1336 or &A-182, Grade F304. Forging ingots shall be produced by vacuum degassed pouring. 8.4. Plate 8.4.1. Plate for pressure parts shall be in accordance with AS}ffi SA-302, Grade B, Firebox Quality, or as modified in accordance with ASME Code Case 1339, Para. 1. K.I-13
GENERAL~ ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 2lAllll REV. NO. 9 PURCHASE SPECIFICATION SH NO. 14 CONT ON SHEE T 15 8.5. Castings 8.5.1. The use of castings will be considered by the Buyer but specific Buyer approval shall be required. Castings for pressure parts shall be made in accord-ance with ASME SA-356. Grade 10. Code Case 1333. Paragraph 1. 8.6. Material for pressure parts shall be selected and worked to produce as fine a grain size as practical. It shall be an objective of the fabrication technique to retain a grain size of 5 or finer in all material. Grain size shall be deter-mined by the method in ASME El12. 8.7. Heat Treatment 8.7.1. Heat treatment of carbon and low alloy steel pressure parts shall consist of normalizing and then tempering at not less than l200°F. For section thickness over 3 inches nominal. heat treatment shall consist of accelerated cooling from the austenitizing temperature to below the martensite finish temperature followed by tempering at not less than 1200°F to obtain tensile and impact properties com-parable to those developed by normalizing and temp~ring section thickness of less than 3 inches nominal.
~.~. ~echanical Properties 8.8.1. The low alloy steel forging, plate and castings for pressure parts shall be tested in accordance with Paragraph 10.3. and shall have the mechanieal pro-perties requi~ed therein in addition to thos~ required by the applicable ASME Specification.
8.9. Studs, Nuts, Bushings, aud Washers for Main Vessel Closure 8.9.1. Studs shall conform to ASTM A540. Grade B23 or B24 and ASME Code Case l335-2~ Paragraph 4, Class. 3. 4 or 5. 8.9.2. NutS. bushings and washers shall conform to AST~l A540. Grade B23 or B24 and Code Case 1335-2. Paragraph 4. Class 3. 4 or 5 but to suit the stud material used and to have a minimum difference in hardness of Rockwell C points from the stud material. 8.9.3. Hardness and impact properties shall meet the requirements of Paragraph
'10.3.2.5.
"AUG: 2 6 1970 K.I-14
GENERAL Q ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 2lAllll REV. NO. 9 PURCHASE SPECI FICA TION S .. NO. 15 CON T 0"4 'HEE T 16 8.10. Cladding Material 8.10.1. All internal carbon and low alloy steel surfaces of the reactor vessel, including the shell, bottom head, vessel flange (but not including top head and flange), nozzles for connecting stainless steel piping, and internal attachments, shall be clad with weld overlay meeting the following requirements: 8.10.1.1. Weld overlay cladding shall be a minimum of 0.125 inches total thick-ness. The finished surface shall have a composition equivalent to ASTM A371, Type ER308 or A240 - Type 304 except the carbon content shall not exceed 0.08 per-cent. (Exception - the lower head may be clad with Inconel 82 or 182). 8.10.1.2. Cladding in the "as-clad" condition is acceptable, provided the result-ing surface finish does not interfere with the ultrasonic and liquid penetrant test. requirements. 8.10.1.3. The sealing surfaces of the reactor vessel head and shell flanges shall be weld overlay clad with austenitic stainless steel which consists of a minimum of two layers and a minimum of 0.25 inch total thickness. The first layer shall be deposited with an analysis equivalent to ASTM A371, Type ER309. The second and subsequent layers shall have a composition equivalent to ASTM A37l, Type ER308, except the carbon content shall not exceed 0.08 percent. ~~nimum thickness of 1/4 lnch shall apply after all machining including area under groove. 8.10.1.4. Six cladding examination patches shall be prepared to meet the examination requirements of Paragraph I-I of t~e ASME Code for Inservice Inspection of Nuclear Reactor Coolant Systems. 8.10.2. Nozzles for con~ecting carbon steel piping (except for the top head nozzles which shall be unclad) shall be clad through at least the thickness of the vessel wall or' one-half the diameter of the nozzle bore, whichever is less. 8.11. Attachments 8.11.1. Internal attachments other than the weld clad ferritic attachments (and the steam dryer hold-down brackets which may be carbon steel) shall be annealed stainless steel, Tyge 304 per ASTM A240 or ASTM A276, or Type F304 per ASTM AI82. The core support structure shall be stainless steel clad low alloy or carbon steel or solid nickel-chromium-iron alloy per ASHE SB166, SB161 or SB168. 8.11.2. External attachments to the reactor vessel shall be of the same material as the reactor vessel base material, or shall be of a material which has mechanical and impact properties compatible with the base material. Where welds must be made to the attachments in the field, the material selected shall not require preheat or post-weld heat treatment. K.I-1S
GEUERA L ~C) ELEe TAI C ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 21Al11l REV. NO. 9 PURCHASE SPECIFICATION SH NO. 16 CONT ON SHEET 17 8.12. Nozzle Safe Ends and Flanges 8.12.1. Nozzle ends for austenitic pipe shall be ASTM A336, Class F8 or F8M; A240, Type 304, or Type 316; or A376, Type 304 or Type 316 solution heat treated stain-less steel, depending upon the mating pipe material selected by the Buyer. Nozzle ends for carbon steel pipe shall be ASTM AlOS, Grade II, forgings except phosphorous content shall be 0.03S percent maximum and sulphur 0.040 percent maximum. Propor-tions shall be as shown on Drawing l07CS30S. 8.12.2. Standard flanges for flanged nozzles shall be ASTM AIOS, Grade II, except 0.035 percent maximum phosphorus and 0.040 percent maximum sulphur. 8.12.3. Studs for standard flanges shall be SAl93, Grade B7. Nuts for standard flanges shall be SAl94, Grade ~H. 8.13. Pipes and tubes shall be ASTM A213, A249, A312, A376, solution heat treated, Grade TP304 or TP3l6; or A240, Type 304 plate welded and radiographed in accordance with ASME Code, Section III, Paragraph N624. 8.14. Miscellaneous bolting material shall be subject to the Buyer's approval. 8.15. W~ld Electrodes and Rods 8.15.1~ Material for weld electrot!es and rods shall be selected from ASTl1 A2"33, A298, A316, A371 or equivalent for other processes and reported to the Buyer for approval. 8.15.2. All austenitic stainless steel welds and weld cladding shall contain con-trolled amounts of ferrite, confi~ed by quantitative tests. The procedures for control of, and testing for the ferrite content of welds and weld cladding sh~ll be submitted to the Buyer for approval. The acceptance standard for quantitative tests ~hall b~ either % Cr = 1.9 x % Ni, or S percent ferrite minimum. 8.16. Alternate Materials The Seller shall be free to suggest alternate materials during preparatiou of de-tailed drawings and shall bring such alternates to the attention of the Buyer, but shall not make substitutions without approval of the Buyer. Request shall include:
-8.16.1. Reason r substitution 8.16.2. Identification of the component or parts involved.
ISSUED: AUG 2 6 1970 K.I-16
GEN ERAL 0 ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 2lAllll REV. N0.9 PURCHASE SPECIFICATION S~I NO. O~' SHEET 18 17 CONT 8.16.3. Either the complete material specification similar to ASTM for. each type and form of proposed material, or the information as follows:
- a. Type of Service (structural, high/low pressure, temperature, weldable)
- b. Manufactured Form (pipe, plate, tube, bar, bolting)
- c. Size, thickness limits
- d. Alloy Grades (C-steel, Alloy Steel, Stainless Steel Designations)
- e. Steel-Making Process (Open hearth, basic electric)
- f. Forming Process (Hot forged, hot/cold rolled, drawn, seamless welded, cast)
- g. Heat Treatment, Stress Relief Parameters
- h. Type, Location and Number of Mechanical Tests (Tensile, Bend Homogeniety, Hydrostatic)
- L, l-Iechanical Property Acceptance Limits
- j. Chemical Composition Acceptance Llmit~
- k. Inspection Requirements such as: Radiography, Liquid Pene-tlant, Magnetic Particl~, Ultrasonic including acceptance limits
- 1. Surface Finish ac~eptance limits 8.16.4. .\llowable Stresses (if not an ASME material) 8.16.5. For major pressure parts, additional information will be required re-garding details of previous applications of the material, impact strength, NDT temperature, micro-structure variations, creep, stress rupture, hardness, radia-tion damage, welding, forming, corrosion and temperature effects as applicable for
~ngineering evaluation of the application and as required for code purposes.
I$5\1EO: AUG 2 6 1970 K.I-I7
GENERALO ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 2lAl111 REV. No.9 PURCHASE SPECIFICATION SMNO. 18 CONT ON SHEET 19 8.17. S:msiti2ationof Stainless steel.. All furnace sensitized wrought stainless steel base metal shall be eliminated by either of the following:
- a. Schedule the manufacturing sequences such that wrought stainless steel is not subjected to furnace heat treat-ment above 800°F after final solution heat treatment.
- b. If any wrought stainless steel base metals have been furnace sensitized after they have been fabricated and installed in the reactor pressure vessel, they shall be removed and replaced per a. above or overlayed with.
308L stainless steel cladding.
- 9. FABRICATION 9.1. Procedures 9.1.1. The Seller shall submit for the Buyer's apploval, all of the following procedures and procedure specification.
9.1.1.1. Heat traatmant pro~eaureo foe all thermal pruc~~~~s exceeding 800°F after the mill rolling or forging or foundry casting operation. 9.1.1.2. Forming and bending procedures for all forming during fabrication sub-sequent to mil: forging or rolling or foundry forming and cladding. 9.1.1.3. Welding and weld repair procedures including temporary welds as required in accordance with the AS~m Cede, Section IX, Paragraphs Q-lO and 11, and QN-lO and 11, Section III, Paragraph N-540. 9.1.1.4; Method of qualifying welding procedures and performance, if other than ASME Code, Section IX and III. 9.1.1.5. Repair procedures for major and minor defects as defined in Paragraph 9.4. 9.1.1.6. Drawings showing location and preparation of test specimens, including specimens required in Attachment B.
~.1.1.1. Fabrication schedule including the detailed sequence to be followed in fabrication of the vessel.
9.1.2. All work by the Seller or his sub-suppliers shall be performed in accord-ance'with Buyer approved drawing, and fabrication and test procedures. 9.2. ~.ateri.al Cutting 9.2.1. Stainless steel and carbon steel shall be cut to size or shaped by machin-ing, shearing or thermal cutting. K.I-18
GENERAL G ELECTRIC ATOMIC POWER EQUIPMENT OEPARTMENT ,- PURCHASE SPECIFICATION SPEC. NO. SH NO. 21Allll 19 REV. NO. CONT 0'"' SHEET 9 20 9.2.2. Thermal cutting of stainless steel shall be followed by the removal of approximately 1/32 inch depth .from the cut surface. Thermal cutting of,carbon steel shall be followed by the removal of oxides. 9.3. Welding 9.3.1. The reactor vessel base material pre-heat and interpass temperature shall be as specified in the welding procedures, but in no case less than 300°F, except weld overlay pre-heat which shall be no less than 20QoF. Pre-heat temperature shall be maintained after welding until start of post-weld heat treatment. Pre-heating techniques shall be such as to ensure that the full thickness :of the weld joint preparation and adjacent base material is at the specified te~perature for the distance of "T" or two inches, whichever is greater, where liT" is the material thickness. 9.3.2. When stainl~ss steel or nickel-chromium-iron alloy is welded to itself or to each other, no pre-heat is required, except when the heat-affected zone reaches ferritic base material as in the cases of welding to buttered nozzle ends or cladding. When the buttering or cladding is less than 1/4 inch thick, pre-heat to at least 200°F is required, followed by post-weld heat treatment ex-cept that subsequent welding to cladding greater than 1/8 inch thick may be done without pre-heat if the specific welding procedure is qualified to show that the heat affected zone does not reach the base metal. 9.3.3. All surfaces (to be welded) shall be free of cavities or protrusions which may interfere with the welding procedure. 9.3.4. Pre-heat, welding and post-weld treat~ent shall be planned and conducted to minimize undue distortion or warpi~g of the parts and preclude cracking. 9.3.5. Machined surfaces and tnreads shall be protected against weld splatter. 9.3.6. Stainless steel welds shall be cleaned with stainless steel wool or stain-let9s steel brushes before'adding the next bead and following the final bC:ld to facilitate inspection. The light oxide discoloration which forms on the weld sur-face need not be removed. 9.3.7. Welds shall be cleaned of slag and flux between passes and following the final deposit. 9.3.8. Any cracks, blow holes, or other defects which appear on the surface of weld beads shall be removed by machining, chipping, grinding, or arc gouging. Austenitic~weld repairs, if arc gouged shall be followed by grinding. Austenitic welds shall not be peened; ferritic welds may be peened under controlled condi-tions with the approval of the Buyer. 9.3.9. Wide welds to overcome poor fj.t are not permissible. Poor fits shall be remedied by. suitable meatis such as regrooving, and approved by the Buyer. Except for small cavities, the Seller shall not correct a plate edge deficiency unless approved by the Buyer. The Buyer may require radiography or other methods of ex-amination of welds used to correct* plate edge deficiencies. ISSUEO: AUG 2.6 1970 K.I-19
GENERAL ( ) ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 2lAIIII REV. No.9 PURCHASE SP ECI FICA nON SH NO. 20 CONT ON SHEET 21 9.3.10. Post-weld heat treatment temperature shall be 1100°F-1150°F. Interstage post-weld heat treatment holding time. shall be 15 minutes minimum. Final post-weld heat treatment holding time shall be one hour per inch of thickness, minimum. 9.4. Repair of Defects 9.4.1. Repair procedures shall be prepared for the repair of all defects. Major defects shall require prior approval by the Buyer and may require witnessing by the Buyer's representative. Major repair is defined as (1) a repair to material other than weld metal which requires an excavatiDn greater than 3/8 inch deep or 10 percent of the wall thickness, whichever is less; (2) the repair of any cracks, other than crater cracks, in any material or weld metal; and (3) the repair of any defect which is indicative of either a fundamental material problem or a process out of control. A minor repair is defined as all other repairs.
- 10. INSPECTION AND TEST 10.1. General
'The Seller shall submit for the Buyer's approval, the following inspection and test proce'.iures:
10.1.1. Ultrasonic Examination Procedure for the following:
- a. Forginlts
- b. Plate
- c. Welds
- d. Weld build-ups
- e. Cladding
- f. Tubular Products 10.1.2. Magnetic Particle Examination Procedures for the following:
10.1.2.1. Carbon steel and low alloy steel forgings 10.1.2.2. Carbon steel and low alloy steel welds 10.1.2.3. Weld Build-ups 10.1.2.4. Bolting 10.1.2.5. Carbon steel and low alloy steel tubular products 10.1.2.6. Carbon steel and low alloy steel castings 10.1.2.7. Edge preparations of carbon steel and low alloy steel materials 10.1.*3. Liquid Penetrant Examination Procedures for the following: 10.1.3.1. Austenitic Forgings ISSUED: AUG 2 6 1970 K.I-20
GENERAL Q ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 21A111l REV. NO. ? PURCHASE SPECIFICATION SH NO. 21 CONT ON SHEF:' 22 10.1.3.2. Austenitic Welds 10.1.3.3. Austenitic Weld Buildup 10.1.3.4. Cladding 10.1.3.5. Austenitic Tubular Products 10.1.3.6. Austenitic Castings 10.1.3.7. Edge Preparations of Austenitic Materials 10.1.4. Radiographic examination procedures for welds, castings, for each type of radiographic source above and below 2 MEV. 10.1.5. Hydrostatic Examination Procedures 10.1.6. Leak Check Procedures 10.1.7. Methods, processes and equipment to be used in establishing "as-built" dimensions and alignment checks which are not normally used in the shop. 10.2. Definitions 10.2.1. "As-Fabricated" Specimens. "As-fabricated" specimens are mechanical test specimens taken from carbon and low alloi st~~l forgings and plates llsed in the vessel fabrication from each heat and heat treatment lot and from welds between base material made by each welding procedure used and in a thickness equal to or greater than the thickest weld made with each procedure. Coupons for "as-fabri-cated" specimens shall be taken from the forgings or plates following all hot work-ing or forming and all heat treatment except post-weld heat treatment. These coupons shall then be subj~cted to a post-weld heat treatment equivalent to the treatments which the parts it represents will receive in the completed vessel. Thi- shall consist cf holding the coupon at the post-weld heat treatment tempera-ture for a time equal to or greater than the longest accumulated time any part it represents shall be at the post-weld heat Creatment temperature. 10.2.2. "1/4T x T" Locati.on. The "1/4T x T" location of specimens is defined as a location within the material no closer than "1/4T" from one quenched surface, and jro closer than "T" from any other quenched edge, where "T" is the nominal thickness of the material. ISSUED: AUG 2 6 1970 K.I-21
GEt~ERAL ( ) ELECTRIC ATOMIC POWER EQUIPMENT OEPARTMENT SPEC. NO. 21Allll REV. NO. 9 PURCHASE SPECIFICATION SH NO. 22 CONT ON SHEET23 10.2.3. NIL-ductility transition (NDT) temperature. The nil-ductility;transi-tion (NDT) temperature is defined as the temperature at which a specimen is broken in a series of tests in which duplicate no-break performance occurs at a temperature 10°F higher, when tested in accordance with ASTM E208. 10.2.4. Impact transition curve. A curve representing breaking energy vs tem-perature from at least twelve Type A Charpy-V specimens, tested in accordance with ASTM A370, except each specimen tested at a different temperature. The temperature ranSe of testing shall establish the upper plateau, the transition region, and the lower plateau. ~ach plateau shall' be determined by at least one, but not more than two points. The remaining specimens shall be used to develop the transition region. The lower plateau need not be developed if it occurs below -BO°F. 10.2.5. A "lot of Material" consists of all material from one heat (one melt) in one heat treatment furnace charge. 10.3. Material Mechanical Tests 10.3.1. Mechanical properties 10.3.1.1. Impact properties of all as-fabricated carbon and low alloy steel used in the main c:loeu'[e flatlcee and the shell and h~ad materials connecting to these rlCi1i~t:~ $hall Wet:L the reliulreU1t:uL~ UL the ASi*lF; Code, Sec t Lon III, Pat.. agr aph N-J,JO at a temperature no higher than 10°f. In addition, this material shall have an NDT temperature no higher 10°F as determined per ASTM E208. 10.3.1.2. Impact properties of all other "as-fa~ricatedn carbon and low alloy steel pressure containing material and the vessel support skirt material shall meet the requirements of the ASME Code, Section III, N-330 at a temperature no higher than 40°F. In addition, this material shall have an NDT temperature no higher than 40°F as determined per ASTM E203. The actual NDT temperature of all material opposite the center of ~he active fuel of the core as indicated on Drawing 886D499 shall be determined. 10.3.1.3. Tensile te~t properties of all ma~erials shall be inspected and tested to meet the requirement of the applicable A~~m Code or ASTM specification. 10.3.1.4. Test data shall be reported to the Buyer. 10.3.2. Required number and specimen location. The number and location of tensile and impact'test specimens required shall be per ASME Code, Section III, N-3l3.2 and the following depending on the form of the material. The following tests may be integrated with the tests required by the ASME Code and ASTM Specification wherever possible. ISSUED: AUG 2 6 1970 K.I-22
GEt~ERAL ,? ELECTRIC ATOMIC POWER EQUIPMENT OEPARTMENT SPEC. NO. 2lAllll REV. No.9 PURCHASE SPECIFICATION SH NO. 23 CONT ON SHEET24 10.3.2.1. Vessel flange and head flange forgings. Tangential specimens, as-fabri-cated, shall be taken from locations per ASME Code, Section III, N-313.2 (d) (2). A total of at least 2 tensile, 6 Charpy-V impact and 4 drop weight specimens shall be tested for each flange from which 1 tensile, 3 Charpy-V impact and 2 drop weight specimens shall De located approximately 180 0 from the other specimens. The material shall meet the requirements of Paragraph 10.3.1. 10.3.2.2. Low-alloy steel nozzle forgings. Specimens, as-fabricated, shall be taken from locations per ASME Code, Section III, N-3l3.2 (d) for forged nozzles. At least 2 tensile, 3 Charpy-V and 2 drop weight specimens shall be tested for each heat and heat treatment charge. The material shall meet the r~quirements of Paragraph 10.3.1. 10.3.2.3. In addition to the tests required by the ASME Boiler and Pressure Vessel Code, longitudinal specimens (parallel to the primary rolling direction), as-fabri-cated, shall be taken from the 1/4T x T location. At least 2 drop weight specimens shall be tested from the top end (top as determined by ingot pouring) of each mill rolled plate and each heat treatment charge. The material shall meet the require-ments of Paragraph 10.3.1. Additional drop weight specimens shall be required for NDT temperature determination per Paragraph 10.3.1.2. for plates located opposite the center of the core. 10.3.2.4. Castings. Tangential specimens, as-fabricated, shall be taken from lo-cations per f~~m Code, Section lIt, N-3l3.2 (d). Castings 1000 1b w~ight and under 3hall have a total of 1 tensile specimen, I metallographic specimen, and 3 Charpy-V and 2 drop weight specimens, te~ted :f5or each heat and heat treatment charge. Castings over 1000 lb weight shall have a tot~l of 2 tensile specimens, 2 metallo-graphic specimens, 6 Charpy-V and 4 drop weight specimens tested from which 1 tensile specimen, 1 meta1lographic specimen, 3 Charpy-V and 2 drop weight speci-mens shall be taken 180 0 apart and/or diagonally opposite. The metallographic speci-mens shall be for reference only. Additional drop weight specimens shall be required in accordance with Paragraph 10.3.1.1. if the casting is located in the core area. The material shall meet the requirements of Paragraph 10.3.1. 10.3.2.5. Studs, nuts, bushings and washers for main vessel closure. Hardness tests shall be made on all main vessel closure bolting to demonstrate that heat treatment has been performed. Studs, nuts and bHshings shall be hardness tested individually. One sample from each lot of washers shall be hardness tested. Im-pact tests required. by ASrlli Code, Section III, Paragraph N-330 shall meet the Code
~equirements at a temperature no higher than 10°F. In addition the the magnetic particle aT liquid penetrant acceptance standards specified in AS}ffi Code, Section III, Paragraph N-325, axial defects of less than thread depth shall be investigated to determine their nature. Any cracks or sharply defined linear indications are unacceptable.
ISSUCO:
~*.L;Li 2 6 1970 K.I-23
GEt' ERAL (0 ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPH. NO. 2lAIli1 REV. NO. 9 PURCHASE SP ECI FICA TlON
$H NO. 24 CONT ON ''loE?)
10.4. Welded Base Material - Mechanical Tests 10.4.1. AS}m code weld test plates. The Seller shall prepare and test weld coupons of Category A and B joints in accordance with ASME Code, Section III N-7l3. The impact test temperatures shall be determined in accordance ,~ith Paragraph 10.3.1. of this specification. In addition to the tests required by the Code, 6 drop weight specimens shall be taken from the 1/4T x T location from these plates and, if different welding procedures are used, from plates for base material to base material welds of Category D joints as defined in ASME Code, Section III, N-46l. Two each of the drop weight specimens shall represent the base metal, heat affected zone and weld metal. The specimens shall meet the re-quirements of Paragraph 10.3.1.2. Additional drop weight specimens shall be required in accordance with Paragraph 10.3.1.2. if the welding procedure is to be applied in the area opposite the core. 10.4.2. One of the test plates of Category A or B required in 10.4.1. above shall be selected by the Buyer for the fabrication tests required in Attachment B, Para-graph 2. The Seller shall perform all required tests and reports. These tests are for information only, but time is of the essence and the tests should be per-formed and the results reported as early as practical. 10.4.3. The Seller shall pr~p~re and ship) but not test, Surveillance Test Pro-gram material and specimens in accordance with Attachment H, Paragraph 3. 10.4.4. [lange forging weld test plate. In the event the vessel and head flanges are made by weJding two or more forged segments, the Seller shall prepare a weld test plate from the forging material. Impact anc tensile specimens shall be pre-pared and tested. The specimens shall be prepared from material in the weld-heat-affected zone and from the weld metal. Test results shall meet the requirements of Paragraph 10.3.1. 10.5. Ult~nic Inspection 10.5.1. Ultrasonic inspection of plate and forged material shall be performed in accordance with ASHE Code, Section III, except that ASME Case Interpretation 1338-2, Alternate 2 shall not be acceptable, and the plate material testing shall Le a 100 percent volumetric inspection and shall be perforrr.ed after forming and heat treat-ment. The following acceptance criteria shall apply in addition to Code require-ments. A defect which causes any echo indication that exceeds 50 percent of the ipdication from the calibration standard and that is continuous during movement of the transducer more than 3 inches in any direction shall be unacceptable, A chart shall be maintained of defects with 50 percent or greater loss of back reflection. K.I-24
GEN ERAL Q ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 2L\llll REV. NO. 9 PURCHASE SP ECI FICA TION Sit ~IO. 2S CONT ON S'H:ET26 10.5.2. Prior to connecting any attachment, support or bracket, except insulation and thermocouple brackets, to the interior or exterior of plate portions of the vessel by means other than groove welds below the plate, the plate shall be ultra-sonically inspected. The plate shall be inspected to a depth at least equal to the thickness of the part being joined, and over the entire area of the subsequent connection plus a band all around this area of width equal to half the thickness of the part being joined. The inspection shall be in accordance vrLth ASNE Code, Section III, Paragraph N-32l, using longitudinal wave technique. The surface shall be 100 percent inspected with the transverse interval being no greater than 90 per-cent of the crystal diameter. 10.5.2.1. Reference standard. The Seller shall prepare a reference standard which consists of a flat bottom hole having a diameter equal to one-quarter of the thick-ness of the part befng joined or 1/4 inch diameter whichever is greater. The bottom of the hole shall be one thickness of the part being joined below the plate surface. This reference stacdard shall be used for calibration purposes. 10.5.2.2. Acceptance standards. Any defect which produces a trace line pattern equal to or in excess of the appropriate reference 5tandard shall be unacceptable. 10.5.3. The main closure stud, nut, bushing and washer material shall be ultra-sonically tested follQ,-ring heat treatment and rough machf rrtng to 250 rms 0'[ be r t er r Luisi! using both Lcu gLt udLn a L awl ~l1t~a( WdV~ t echn Lque s . Loug.I tuJ1nal wave exam-ination shall be performed on 100 percent of the cylindrical surface, and in addi-tion on stud material from both ends of each stnd. The longitudinal/wave trans-ducer shall ha~Je a maximum diameter of 1/2 inc~. Shear wave examination shall be performed on 100 percent of the outer cy1indrica~ surface in both axial and cir-cumferential directions. 10.5.3.1. Reference standards. The Seller shall prepare a reference standard of the same material thickness and curvature as the part being examined. The refer-ence standard shall contain calibration features as follows:
- a. L~ngitudinal Wave-Radial Scan: 1/2 inch diameter flat-bottom hole*
having a depth equal to 10 percent of the material thickness.
- b. Longitudinal Wave-End Scan: Flat-bottom hole uith area equal to 1 percent of stud cross-section or 1/4 inch diameter, ~i\ichever is smaller, ha7ing a depth of 1/2 inch.
- c. Sh~ar Wave: Square bottomed notches 1 inch long anrl 1 percent of the part thickness in depth, both axial and circumfere.ntial.
ISSUED: AUG 2 6 1970 K.I-25
GEN ERAL G ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 2lAllll "EV. NO. 9 PURCHASE SPECIFICATION SM NO. 26 CONT ON UiEET27 10.5.3.2. Acceptance standards. Any defect which produces a trace line pattern (echo indication) greater than the indication from the applicable calibration feature shall be unacceptable. A ~istance-amplitude curve may be used for the longitudinal wave examination. The curve may be a line established by plugging the hole and examining it from both sides of the material. For end examination of studs the curve may be established for half the stud length and applied to an examination from each end to the center. 10.6. Cladding 10.6.1. Ultrasonic inspection - cladding general. 10.6.1.1. The cladding bond shall be tested with the transducer on the clad side using a suitable covplant. The entire clad surface shall be inspected at inter-vals 1.4 times the base material thickness, but not greater than 12 inches, trans-verse to the direction of welding. 10.6.1.2. Reference standard. The Seller shall prepare a reference standard which consists of a flat bottom groove in typical clad pl~te. The groove shall be 0.35 inch maximum width by at least one crystal diameter long, parallel to the direction of welding. The groove shall be formed by machining the base metal within 1/32 inch
~f th~ ~l?~~~~e in~~~f~~~ ~n~ ~~chpo wi.~h ni~ri~ A~irl to TP-movp- excess ferritic material from the Interfac~. Thl~ c~[~r~nce staildard shall be used for calibration pur1>,",ses.
10.6.1.3. Acceptance standards. Cladding whi:h produces a trace line pattern equal to or in excess of the appropriate Reference Standard shall be unacceptable if a continuous pattern occurs during movement of the transducer more than three inches in any direction or if oce cr more patterns occur during movement of the transducer less than one inch in anyone pattern. 10.6.2. Liquid penetrant 'inspection - cladding general. 10.6.2.1. All clad areas and clad repairs shall be liquid penetrant inspected per ASME Code, Section III, N-627. The followinp, indications shall constitute unaccept-able defects and shall be repaired. 10.6.2.2. Any crack-like indications or incomplete fusion. 10.6.2.3. Linearly-disposed spot indications of 4 or more spots spaced 1/4 inch or less from edge to edge of the indications. 10.6.2.4. Spot indications which are indicative of defects greater than 1/32 inch deep as rev~aled by bleed-out. K.I-26
GENERAL Q ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 2lAllll REV. No.9 PURCHASE SPECIFICA TlON SH NO. 27 CONT ON 5HEET28 10.6.3. Ultrasonic inspection - cladding special areas. 10.6.3.1. The flange seal surfac~s shall be inspected for bond to the flanges as per 10.6.1. except that the inspection shall be over 100 percent of the area. Prior to final machining the volume 1/8 inch above and below the surfaces on which the double seals will seat shall be 100 percent inspected for defect using longi-tudinal wave technique. The acceptance criteria shall be that any defect which produces a trace line pattern equal to or in excess of a 1/16 inch flat bottom hole may be unacceptable. 10.6.3.2. The final machined surfaces on which the double seals seat shall be inspected by surface wave technique. Any defect producing a signal greater than the signal produced by the 0.002 inch deep by 1/8 inch long spark machined groove in a reference standard which the Seller shall furnish may be cause for rejection. 10.6.4. Liquid penetrant inspection - cladding special areas. 10.6.4.1. The area of the flange seal surfaces on which the double seals seat shall be liquid penetrant inspected per As~m Code, Section III, N-627, except that any indication of any type shall be unacceptable. 10.6.5. 10.6.5.1. Both internal and external surfaces of all low alloy steel plate material shall be magnetic particle inspected per ASME Code, Section III, Paragraph N-626 following for~ing and heat treatment. TIle ac~eptance standard of AS~ffi Code, Section III, Paragraph' N-62S.5 shall apply. 10.6.6. Openings in pressurp. parts. 10.6.6.1. The entire surface of all openings for partial penetration nozzles, re-gardle~s of size, except for the seal leak detection connection, shall be examined 1n accordance with AS}ffi Code, Section III, N-S13. 10.6.6.2. The entire surface of the finish~d stud holes in the head flange and the holes in the vessel flange prior to tapping shall be examined by the ~ethods of AS}m Code, Section III, N-S13. Any indication of cracks or linear indications shall be reported to the Buyer for information. Any crack or linear indication may be subject to ?emoval and repair if required. 10.7. Welds 10.7.1. Radiographs. 10.7.1.1. Gamma rays shall ~ot be used unless approved by the Buyer.
"'AUG 2 6 1970 J K.I-27
GE~JERAL ~ ELECTRIC A TOMle POWER EOUIPMENT DE PARTM(t~ r
!r r r , ~':" 21Allll REV. NO. 9 PURCHASE SP Eel FICA TlON s ** '.; 2R CO"".,. ON SHEET29 10.7.1.2. Films shall be suitably marked to identify the weld. Film identifica-tion markings shall coincide with the detail drawing markings for each weld.
10.7.2. Ultrasonic Testing. All full-penetration pressure carrying welds shall be 100 percent ultrasonically tested as described in Paragraph N-625 of Section III of the Code. Both shear wave and longitudinal wave techniques shall be used. 10.7.2.1. Indications with 50 percent or greater loss of back reflection or 50 percent of indication from the calibration standard shall be recorded on charts "to scale" so that they can be used as a basis for comparison with subsequent "in-service" ultrasonic tests. 10.7.2.2. Any work (additional investigation and testing or repair of welds) which is requested by the Buyer as a result of the ultrasoni~ testing shall be subject to mutual Buyer-Seller agreement. 10.8. Hydrostatic Tests 10.8.1. After completion of fabrication but prior to shipment, while the vessel is supported on its normal supports, the reactor ~ssel shall be pressure tested in accordance with the AS~m Boiler and Pressure Vessel Code, Section III, Para-graph N-7l2. (Paragraph numbering as per Winter 1966 Addenda.) Reactor vessel material temperature shail be at least lUU~F. In no caGe, however: shall the water temperature be higher than 180°F. Suitable gasket material instead of metal O-rings may be used for this test. Hydrotest water shall be d the r potable tap water "lith addition of TSP, or demineralized wat e r , Hater may be heated with steam provided that the source of feedwater i~ potable or deminer~lized water. 10.8.2. Following the Code test, the vessel shall be hydrostatically tested at design pressure with new O-rings. This test shall demonstrcte that the head seal meets the sealing requirements. 10.8.3. Altetnative Procedures. As an alternative to 10.8.1 and 10.8.2, the second hy~atic test may be combined 't"ith the Code test if metal O-rings are used and the'stud tension-used, is normal operating bolt-up tennion. A perQiss-ible variation on the above would be to perform the Code hydrostatic test of 10.8.1 using metal O-rings and hydrostatic test bolt-up tension. After this test has been completed, the pressure is to be dropped to zero psi and stud tension. decreased ~o normal bolt-up tension. The leak testing of 10.8.2 is
.then to be performed.
10.9. The placing of the head, tightening the studs to operating bolt-up loads, unbolting and removal of the head over the studs shall be demonstrated. The elapsed times for each step shall be recorded. 10.10. Final inspection after hydrostatic test per ASME Code, Section III, N-6l8 shall include seal surfaces and the nozzle weld preps. ISS~ot 2 6 1970 K.1-28
GENERAL fD ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT S~EC ..... 0. 22All11 REV. NO. 9 PURCHASE SPECIFICATION SH NO. 29 CONT 0 ... SHEET 30 10.11. Immediately prior to hydrostatic testing of the reactor vessel, all in-terior surfaces that will contact w~ter during the hydrostatic test, all nozzle fixtures, all piping which will be wed to fill the reactor vessel, and all surfaces of stainless steel and Ni-Cr-Fe components shall be cleaned to remove all halide-bearing soils, grease, oil, penetrant materials, inks, chalk or crayon marks, and all dirt and debris. All loose dirt and other foreign materials shall be removed by sweeping or vacuuming. Deposits of grease and oil shall be removed with an appropriate solvent. Tightly adhering soils may be removed with the aid of stainless steel brushes which have not been previously used on carbon steel, or by grinding. The vessel shall then be cleaned with high-pressure water con-taining a minimum of 500 ppm of phosphate added as TSP. The vessel and water temperature shall be less than 180°F during the TSP cleaning step. The water pressure shall be a minimum of 5,000 psi. The trisodium phosphate shall be reagent grade per American Chemical Society standards. Water shall be potable water con-taining less than 50 ppm chlorides, 10 ppm fluorides, and 1 ppm sulfides, or de-mineralized water containing not more than I ppm chlorides, 1 ppm fluorides and 1 ppm sulfides. The TSP solution may be left on the surface of the vessel. However, the vessel must be completely drained so that no puddles of TSP solution remain. The cleanliness of the vessel shall be checked visually and with the aid of an ultraviolet light to assure that the vessel is clean. The ultraviolet examination shall be conducted under darkened conditions with a lamp having a minimum brilliance of lOO~foot c~ndJp.~. A ~ermissible var~ation on the abo~e ulLraviol~L lIght cl~un* liness e~amination will be to wipe the vessel with clean rags as an tnspp-ction method for determining cleanliness. 10.11.1. It is intended that hydrostatic tectin~ follow immediately after clean-ing and that all plumbing, welding, or testing work be performed orior ro clean-ing. During any entry of personnel into the vessel after cleaning has been com-pleted shoe covers shall be worn and clean-room conditions maintained in the re-actor vessel. 10.12. The water used to fill the vessels for the hydrostatic test may be either tap water or demineralized water. For vessels filled with tap ,~ater plus a mini-mum phosphate addition of five times the crloride content of the test water in the vessel (but not less than 100 ppm phosphate), TSP shall be added as reagent-grade
'trisodium phosphate (TSP). The water used to fill the vessel shall meet the following requirements:
)
pH = 5.8 to 8.0 Cl less than 50 ppm Fl = less than 10 ppm S = less than I ppm K.I-29
GENERAL G ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT
~~*(c. t.o. 21Alill REV. No.9 PUQCHASE SPECIFICA TlON SH "'0. 30 CONT 0 ... 'HEEl 31 10.12.1. For vessels filled with demineralized water, the water in the vessel shall meet the following requirements:
pH
- 5.8 to 8.0 Cl = not more than 1 ppm F1 = not more than 1 ppm S = not more than 1 ppm 10.2.2. The conductivity of the fill water shall be 3 micro mho/cm maximum. TIle vessel shall be dried as soon as practical after hydro. TSP shall ~e washed, using demineralized water, from any surface which is heated to above 500°F.
- 11. PREPARATION FOR SHIPMENT 11.1. ~ning Procedures 11.1.1. The Seller shall submit for the Buyer's approval, all cleaning procedures, preserving procedures and a list of cleaning agenta and preservatives together with their chemical content which shall be used during fabrication and in prepar~tion for shipment. In lieu of a complete chemical analysis, the Buyer shall accept a repor~ whicil ~lalt:~ Un: \;1.1vL i~es, fluvi"i~;::~ .:l~~ ~~lf~:- c~~t~~t::. 0t h Q !, htt1'"Tl'lfl11 elements should also be reported.
11.2. lnlerior Surfaces 11.2.1. Interior surfaces of the re~ctor vessel shall be thoroughly cleaned to be visibly free of lubricant, weld spatter, chips, imbedded iron particles and other foreign materials. The vess~l shall then be cleaned in accordance with Paragraph 10.11 except that demineralized water with 500 ppm phosphate shall be us~d. After the vessel and head interior surfaces are cleaned, they shall be dried with hot a~r or other suitable means and the vessel and head sealed to prevent entry of moisture, dirt, and other harmful materials. The coating of TSP from the final wash may be left on the surface. 11.3. Exterior Surfaces 11.3.1. Where vessels are to be shipped over salt water (i.e., Peachbottom 2 & 3 and Browns Ferry 2 & 3) the fo l l.cwf.ng requirements apply: Exterior carbon steel surfaces sh be clean~d of oil and grease after which mill scale, rust, rust scale, paint and other foreig'l matter shall be thoroughly removed by such means as sandblasting. All surfaces shall be brushed or air cleaned to r~move all traces of sand or grit and shall then be dried and painted. Sufficient coats of an approved paint (ap-proved by the Buyer - Superior Primary Lead 01746 is not approved) shall be applied to all exterior carbon steel surfaces (stainless steel and Ni~Cr-Fe sur-faces shall ~ot be painted) to assure complete coverage and sufficient protection f~om the we~ther. Exterior stainless steel and Ni-Cr-Fe surf~ces shall be coated witl\ a juitable'm~terial to prev~nt moisture contact with the surfaces. The vessel and
.~ :
R.I-30
GErJERAL 0 ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT S~CC. NO. 2lAlll1 "lEV. No.9 PURCHASE SP ECIFICATION 31 1M NO. COHT ON 'H,nT 32 11.3.1. (Continuted) closure head shall be purged with dry nitrogen until the gas within the vessel and closure head has attained a dew point of 32°F. The vessel and closure head shall be fitted with a suitable nitrogen pressure system to maintain a positive pressure of nitrogen within the vessel and closure head. In lieu of the nitrogen purge re-quirements for the vessel and closure head, it will be acceptable to coat the in-terior surfaces with tectyl (or other Buyer approved preservatives) provided the Seller assumes this additional cleanup responsibility once the vessel and closure head are received at the site. Where vessels are to be shipped over inland routes (i.e *., Brown Ferry 1) no painting, nitrogen purge or nitrogen pressure system will be required. Protection of exterior stainless steel surfaces will be required, as above. 11.4. Small Parts 11.4.1. Small, loose pieces, including bolting, tools, gaskets, etc., shall be adequately crated or boxed for protection during shipment. Parts subject to rusting shall be suitably protected. All boxes, crates and shipments shall be marked with the equipment piece number. 11.5. Shipping Weight and Dimensions .- 11.5.1. Estimated sh1ppiTlg weights and overall clearance dLmens Lons bhdii lit: Sa,owl1 on the drawings when submitted to the Buyer for approval
- 11.6. Shipping Skids 11.6.1. The reactor vessel body shall be shipped on a skid which supports the reactor vessel in a horizontal position. The top head shall likewise be shipped on a skid. The skids shall be designed to support the reactor vessel adequately and securely during shipment to the site and to permit movement on rollers (not supplied by Seller) at the p.rection site.
- 12. SUBMITTALS
~2.1. Tabulation (for Information Only) 12.1.1. Fabrication, qualification and inspection procedures, reports processes, and calculations are tabulat~d below (all of which require submittal to the Buyer in quanti~ies as shown on Attachment A). This tabulation shall in no way be con-strued as being complete or limiting the documents necessary to meet the require-ments of this specification.
- a. Heat treatment procedure
- b. Forming and bending procedure
- c. Welding and weld repair procedure specification
- d. Repair procedures
- e. Cleaning and preserving procedures
- f. Ferrite content or Ni/Cr ratio control procedure
- g. Ultrasonic exa~ination procedure
- h. }fugnetic particle examination procedure *
'liVED, AUG 2 6 1970 K.I-31
GEN ERAL (~) ELECTRIC ATOMIC POWER EQUIPMENT DEPART.vENT
!.~CC. NO.
21All11 REV. NO. 9 PUQCHASE SPECIFICATION ~ ... "",0. 32 CONT 0 ... ""'CF;T 33 12.1.1. (continued)
- i. Liquid penetrant examination procedure
- j. Radiographic examination procedure
- k. Hydrostatic examination procedure
- 1. Leak check procedure
- m. Measurement reports
- n. Summary reports
- o. liAs-built" dimensions and alignment checks procedures
- p. Design analysis calculations
- q. Material purchase specifications
- r. Material selections 12.2. The following shall be submitted in accordance with Attachment A:
12.2.1. Drawings 12.2.1.1. Outline Drawings - A drawing depicting the outline of the reactor vessel indicating overall dimensions, location and size of nozzles, location of supports, shipping and operating weights. 1'..'.1.2. Assembly Draw1"gs - A section drawln~ depict1ng the 3rran8emen~ of the functional parta, parts list and material designations. 12.2.1.3. Detail Drawings - Drawings for details of construction such as ~~cld preparations, surface finishes, finished dfmet.s Lons , noaz Le s , lifting attachments, insulation attachments, thermocouple pads, flanges and supports. 12.2.1.4. Drawings for Approval - Outline, assembly and detail drawings shall be submitted for approval. TIle detail drawings submitted shall be for design details enumernted in 12.2.1.3. which are required for coordination with piping and struc-ture and design details which are at variance with the code or the requirements of this specification. 12.2.1.5. Controlling location arrangement drawings. One or more drawings shall be devoted exclusively to outl:f.ne dimensions such that mating components designed and supplied by others such as piping, anchor bolts, instruments, etc., may be pro-cured fOT an exact jit with the reactor vessel assembly. These drawings shall show reference to the controlling detail drawings and show overall dimensions and loca-tions on r.eactor vessel. 12.2.1.6. Drawings to be Certified - Outlines assembly and detail drawings for design coordination shall, upon completion of the design, be certified to be correct with no further changcs required. No alterations may be madc to the de-sign after certification without the ~pproval of the Buycr.
'SSUEO:
AUG 2 6 1970 K.I-32
GENE RA L~' ELE ern I C ATO~IC POWER EQUIPMENT DEPART ..... ENl
'jPf.C. NO.
2lAllll RE\(. NO. ~ PuqCHA SE SP ECI FICA TlON ~II "10. 33 CONT 0 .... SHF:ET 34 12.2.1.7. As-Built Drawings - Prior to shipment of the reactor vessel, the Seller shall provide an outline drawing with the previously designated actual measured significant dimensions. The accuracy of as-built measurements shall be at least 25 percent of the tolerance of the dimensions measure. If the final construction differs from the previously submitted assembly and detail drawings, corrected drawings shall be provided by the Seller. 12.2.2. Instruction Manuals. 12.2.2.1. Instruction manuals shall present the following basic categories of in-formation in a practical, complete and comprehensive manner, prepared for use by operating and/or maintenance personnel:
- a. Instructions for making up the head closure seal for:
- 1. Normal operation and,
- 2. Hydrostatic tests
- b. Instructions for opening up the head closure
- c. Instructions for operation, maintenance and repair of all tools provided
- d. Recommendeci maximum heating and couling rates with ~aximum allowable temperature differences between the various thermo-couple locations.
- e. Reco~ended inspection points and per40d of inspection
- f. Ordering instructions for all replaceable parts, gaskets, etc.
12.2.2.2. The information shall be organized in a logical and orderly sequence. A general description of the equipment including significant technical character-istics shall be included to familiarize operating and maintenance personnel with the equipment. 12.2.2.3. Necessary drawings and/or other illustrations shall be included or copies of appropriate certified drawings may be bound into the manual. Test, adjustment and calibration information, as appropriate, shall be specified and identified to the specific equipment. Safety and other warning notices and installation, main-tenance and operating cautions shall be emphasized.
~2.2.2.4. ' A parts list shall be included showing part nomenclature, manufacturer's part number and/or other inform2tion necessary for accurate identification and or-dering of replacement parts. Common hardware items or other parts to be locally procured shall be adequately identified by Technical description.
IS'UEO: AUG 2 6 1970 K. 1-33
GENERAL 0 ELECTRIC ATOMIC POWER EQUIPMENT OEPARTMENT SPEC. NO. 21Allll REV. N0.9 PURCHASE SPECIFICATION SH NO. 3/. CONT ON S .... EET F 12.2.2.5. Instructions and parts list shall be clearly legible and prepared on good quality paper; carbon copies and tissue copies of other flimsy material are not acceptable. }iultiple page instructions shall be securely bound. 12.2.2.6. In a standard manual is furnished covering more than the specific equip-ment purchased, the applicable model (or other identification) parts and other in-formation for the specific equipment purchased shall he clearly identified. 12.2.3. Photographs. The Seller shall provide the Buyer with sets of progress photographs of the vessel at each significant stage of fabrication. One set shall consist of one negative and three glossy 8" x 10" prints. 12.2.4. Engineering schedule 12.2.5. Fabrication schedule 12.3. Records The Seller shall maintain records of all material qualifications, all w~ld and weldor qualifications and all process qualifications required by this specifica-tion and the material specifications. In addition, the Seller shall maintain records of all tests and inspections (e.g., ultrasonic, radiography and hydro-static). A list of the records shall be submitted to the Buyer on completion of the j~b. The Buver shall be able to obtain certified copies of such records for a five year period. Wh~rc the Seller considers th~ actual test recorrlR to h~ ~ro prietary, he shall submit certified reports containing all pertinent t~st data ex-cerpted from the actual test reports. Thes~ certified test reports shall ~lso be available for? 5 year period. At the en~ of the 5 year period, both the vessel user and the Buyer shall be notified at least 120 days prior to disposal of the records, so that a request can be made (if either the vessel user or the Buyer so desires) to have these records 3ent to either the vessel user or the Buyer.
~
"AUG 2 6 19~
h_ K.I-34
GENERAL;tD ELECTRIC ATOMIC POWER EQUIPMENT OEPARTMENT PURCHASE SP ECI FICA TlON SPEC. NO. 2lAllll REV. No.9 SH NO I CONT 0"1 SHEET2 ATTAClmENT B - }~TERIAL TESTS AND TEST SPECIMENS
- 1. SCOPE The Seller shall retain selected portions of the material used to fabricate the reactor vessel of this contract. He shall process some of this material into finished mechanical specimens which shall be in metallurgical conditions repre-sentative of the following as-fabricated reactor vessel material: Base-plate, welds and heat-affected zone. The Seller shall test some of these specimens for "Fabrication Tests" to determine the effect of thickness on the mechanical pro-perties of the material. The remainder of the specimens and the remainder of the selected test material shall be prepared for shipment. These latter specimens will be used for "Surveillance Tests" to monitor the effect of neutron irradiation on the mechanical properties of the reactor vessel steel.
- 2. FABRICATION TEST PROGRAM (DELETE)
- 3. SURVEILLANCE TEST PROGRAM 3.1. Bas~ Met~l - 'Fienre 1 3.1.1. The Seller shall furnish two plates, as shm.;n in Figure 1, from the plate used to make the reactor vessel in the reactor core region, or from a similar plate from the same heat.
3.1.2. Th2 Seller shall heat t't'eat these plates with the reactor vessel, or in similar fashion, to insure that they represent the metallurg~cal condition of the vessel steel, in the core region of the completed reactor vessel including all post weld heat treat cycles seen by that region. 3.1.3. The ~eller shall furnish documents to the Buyer, showing the location of the test plates and detailing all metallurgical data concerning the test plates. 3,1.4. The Seller shall make mechanical test specimens, as outlined belo\v, from one of these plates and send the other to the Buyer.
~.2. Welded Plate - Figure 2 3.2.1. The Seller shall furnish a welded plate representative of a reactor vessel longitudinal weld, in the base of reactor vess~ls formed from plate or representative of a reactor vessel girth weld in the case of reactor vessels forml~d from forged rings, as shown in Figure 2, from the plate used to make the reactor vessel in the reactor core region, or from a similar plate from the same heat.
ISSUE 0:
!-\UG 2 G 1970 K.I-35
GEr~ERAL 0 ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. No.2lAllll "KY. No.9 PURCHASE SP ECIFICA TION h~ .... o. 2 CONT ON IHCCT 3 3.2.2. TIle Seller shall heat treat the plate with the reactor vessel, or in similar fashion, to insure that it an~ the weld represent the metallurgical condition of a vessel weld, in the core region of the completed reactor vessel including all post weld heat treatment cycles seen by that weld. 3.2.3. The Seller shall furnish documents to the Buyer showing the location of the test plates, detailing all metallurgical data and demonstrating that the weld was made in a manner similar to a reactor vessel weld. X-rays of the weld ahall be furnished. 3.2.4. The Seller shall make mechanical test specimens, as outlined below, from half of 'the plate and shall supply the other half to the Buyer. 3.3. Surveillance Specimen Fabrication 3.3.1. The Seller ~hall provide a detailed plan of specimen preparation for the Buyer's approval prior to the start of any work required by this attachment. The Buyer can furnish a plan which the Seller may use as a guide. He shall be specific in indicating how the notch location of the Heat-Affected Zone Charpy specimens will be determined. 3.3.2. All specimen cutting shall be done by machi~ing. 3.3.3. Specimen M2rking 2n~ m,rk orientation are of upmo~t importAnce. Each speci-
.men shall be marked seria:Lly Vlith Lhe FAil CoJt:: series provided.
3.3.4. The Seller shall apply rust preventative to all specimens, shall arrange them in serial groups of like materials, and sh a Ll, wrap them to prevent mechanical damage. 3.3.5. The Seller shall provide drawings showing all specimen locations with respect to the plate. 3.4. Preparation of Base Metal Charpy Test Specimens (Refer to Figure 3 and Drawing l17B1549) The Seller shall prepare 53 standard Charpy V-Notch impact specimens (ASTH E23, Type A, G.E. Drawing l17B1549) from the base plate material described in pre-vious paragraphs. The specimens shall ~e taken from 1/4 thickness positions in the plate and at least IT from any asquenched edge. The long axes of the specimens shall be parallel to the plate rolling direction, or principal forg-ing direction~ The specimen notches shrtll be perpendicular to the original plate surface and shall be controlled by the orientation of the end marking on the 'Specimen blanks. 3.5. Presparation of Base }tetal Tcnsil~eci~ens (Refer to Figure 3 and G.E. Drawing ll7B1550) TIle Seller shall prepare 14 1/4-inch gage diameter tensile specimens as per G.E. Drawing l17B1550, froQ the base plate material previollsly uescribed. The specimens shall be taken from 1/4 thickness positions in the plate and at least IT from any as-quenched edge. The long axes of the specimens shall
~e parallel to the plate rolling direction or principal forging direction.
IIIU£OI
,\lJG '2 G 1~~ 7.,
......_~--'...-_,1 i
K.I-36
GErJfnAL 0 ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT S~[C. NO. 2lAllll KY. NO. 9 PURCHASE SP ECIFICATION JHNO. 3 CONTONIHI:CT 4 3.6. Preparation of Weld Charpy Specimens (Refer to Figure 4 and G.E. Drawing l17B1549) The Seller shall prepare 53 Qlarpy impact specimens, per G.E. Drawing l17B1549 and Figure 4, from the weld deposit material of the furnished plate. The long axes of the specimens shall be perpendicular to the weld direction and parallel to the plate surface, with the middle of the specimen at the mid-plane of the weld, as shown in Figure 4. The specimen location in the stock material shall be recorded, approximately, by the numbering system. The notch shall be parallel to the plate sur-face and its orientation shall be controlled by the orientation of the marking symbols. 3.7. Preparation of Weld Tensile Specimens (Refer to Figure 5 and G.E. Drawing l17B1550) The Seller shall prepare_ 13 tensi:e specimens, per G.E. Drawing !17B1550 from the weld deposit material of the furnished plate. The long axes of the specimens ahall be parallel to the length of the we!d and parallel to the top surface of the plate (See Figure 5). The gage length of the speci-mens shall be of weld-deposit metal only. The treaded ends of the specimens may include Heat-Affected Zone or base metal. The approximate location of the Gpecimens in the stock materi~l shRll. he recorded by the marking system. 3.8. Preparation of Heat-Affected Zone Tensile Speci~ (Refer to Figure 6 and G. E. Draw.Lng l17B1550) The Seller shall prepare 13 tensile specimens, per G.E. Drawing l17B1550, f rom the weLded material of the furnished plate. The long axes of the speci-mens shall be perpendicular to the length of the weld and parallel to the top surface of the plate (See Figure 6). The center of the specimen shall be in the Heat-Affected Zone adjacent to the edge of the weld metal. TIle approximate location of* the specimens in the stock material shall be recorded by the, marking system. 3.9. Preparation of Heat-Affected Zone Charpy Specimens (Refer to Figure 7 and G.E. Drawing ll7B1549) The Seller shall prepare 53 Charpy specimens, per G.E. Drawing 117B1549, from the welded material of the furnished plate. The long axes of the specimens sh a lL be perpendicular to the length of the Held and parallel to the top sur-face of the plate (See Figure 7). The radius of the notch of the specimen shall be at one outer edge of the we Ld , The axis of the notch shall be par-allel to the original plate surface. The notch orientation shall be controlled by the marking orientation. The location of the speciT:1en in the stock material shal~ be recorded, appioximately, by the marking system.
,....-_._----_... ~ ..
K.r-37
GEN EAAL 0 ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT PURCHASE SPECIFICATION IPEc.No.2LAllll ~CV. NO.9 1 llot NO.4 CONT ON IHEe T 5 FLAMECUT OR WELD EDGES
~~CHINE CUT EDG~S t ."""., PI? ESS f/i'(E Ll.ESS c L
~/I'1L.L. T///CI(IV£"SS (CL) - 71//5 OII1ENS/Of\/
1'111 y' BE ;:tI~tV/SI/i
.11.5 2. Of? 3 SI1ALLE/
PieCES.
"Al1~ 2 6 1970
_ _ _ _ _ _ <0:;)
~
K.I-38
GENERAL 0 ELECTRIC ATOMIC POWER eQUIPMENT DEPARTMENT SPEC. NO. 2lAllll REV. No.9 PURCHASE SP Eel FICA TlON SH NO. 5 CONT ON SHEET 6 ORIGINAl- PL-ATE ECJ&,G MUST 8E
,4J1YAY ,.t::RC)/'r? /YeLD t- PRe-SSU.RE . VESS~~
*W,4I.t. rHICKIV4SS.~ (I.-
(cr,) - SEVERAL 'P/ec~s
~AN'&f v'o//ve.o. TtJ N,w$' .7Ii/..1 £)/MAI/.51011 NiJw6yir~) h/ez,O Ma;r es Ctj7lT//(VOVS.
~.MINI~tlH H/N!N~V1 3t
- 3t
~ W£LD ceNTEP"oLAN£ r/G. 2 t TE5T WELD FOR )'V£~LD ;I #EAT AFFECTED ZONE 5PEC//y/EN
'Autf2 6 1970 K.I-39
GEtl ERAL ~ ELECTRIC ATOMIC POWER EQUIPMENT DEPARTMENT SPEC. NO. 21All11 REV. NO. 9 HI NO. 6 CONT ON SHEET 7 PL.-ATE. SURFA'c.E. t t - \;, P\.J\"~ -r~\CJ~NaS~ (\. \~ Cl4.~RP,( e.,LAN~ \'\!.!~~"H FIG. 3 CHARPY & ENSILE SPECIMEN LOCATION b .. \~ T~~1r:J\'-~ i~\..A~lK Le.~<!l"H K.I-40
GENERAl e ELECTRIC ATOMIC POWE R EQUIPME NT DE PART MENT
!>p£c. NO. 2V.llll R£V. No.9
!>H NO 7 CONT ON SH[n 8 a - FJl3fiV; /2".
~-J:eS$ct. WAL.I. TN./'.
~ -C/l~SI $UJNK nq.
~ ~...bItCtfIIIP '?EM fl/lT~~/JL
- WELD FIGURE 4 WELD CHARP\'
['AUG' 2 6 1970 K.I-41
GENERAl(jJp ELECTRIC ATOMIC PowER [QUIPI,I.(NT DEPARTMENT sp[e No.21Allll 11:'. "'0. 9 s .. 'JO 8 co~r ON SHEEr 9 ~ -~UT /2(/(30(111/) 5 213 e -l'4SSS. JfI/IU 11(~ IN---':'_;iI q-hlfU; M'/)~ .p./. 3f -1)JSCIJe~ 7//.IS N~/I1.L fi~~
~./cL{) TEAl4S'/LE ISSuED.
AUG 2 6 1970 K.I-42
GENERAL@ ELECTRIC ATOMIC PowE R E OUIPME NT DE PAR TMEN T SPEe ... o , 2lA 1111 REV. No.9 SH NO. 9 CONT ox SHFET 1:'
~ - - VESSEL. f'II1LL T/IICj(NESS
. - - - O/SCARD TillS I1/jTc;'(I/!L t
ISSUED' AUG 2 6 1970 K.I-43
GENERAL (J) ELECTRIC ATOMIC powER EOUIPMENT OEPARTMENT SPEC. NO. 21Allll ~EV. No.9 h .... 0. 10 COST ON SHEEr NOTES:-* fr.I~1 t,.V&:SS~L WALL THICJ{NES3 Ihl~ ~ 11"= Ol5CARO 'rHI~ M"Tt:RIAL. ., J\~V 1'.P;.r-:------ d -,J~2" - - -
)~£~;..t _
.L t=:======:.:: ---
~1'cIJ!j1~
T l=========:..::=:::=========~=====:V t*
"~VEO AUG 2 6 1970 K.I-44
PBAPS 22 October 1970 Project: 1V,\ 1 t. 2 Project: TVA 3 Pro i cc t : PB 2 (( 3 Con trac t: C,lO-0127 Contract: 610-0145 Contrac t : 610-0139 P. 0: 20S-S5577 P. 0: 205-H0397 P. 0: 205-Cl15G Date: 10/23/70 CLr\RIFICATln;~s OF Sr[CIFICATIOi~ 211\1111, PE\ITSIOj! 9 8.7.1 J cmpcr i nq at 1175°F meets the intent of tile specification nrovided the post \'/elo heat treatment maximum temperatures do not exceed 1150°F. 9.3.1 The provisions for preheat and maintenance of preheat in [32'~'1 Spcc i t t ca t i on tWS-129, Rev. 4, dated 3/31/69, are acceptable alternate requirements. 10.5.3.1 The V-notch calibration s tandard described in [3&~'1 Specifioation f!UT-82, Rcv. 0, da tcd 4/19/67, is an accep tab l e alternate standard- to the square bottomed notch. 10.6.2 The acccpt.ance standard of 8&\*J Specification {IS-102C, Rev. 5, Par aqraph 8.2.2 - 1\11 rounded indications with dimensions nreater than 3/16 inch, is an acceptable ulternute standurd to srot indicutions which arc indic-ative of defects greater than 1/32 inch deep as r~veu1ed by bleed-out. 10.6.3.2 The O.OOG inch deer cu l ibre t ion crcove described in ~&\'1 Spac i f i ca t i nn OUT-GU, Rev. 0, dated ~/19/G7, is un accertab1e ulternute stundilrd when used for testing Nic~el-Chroilliurn-Iron clad flange seu1 surfaces. iO.6.6.1 The fo l l ow i nr; alternate acceptance s tandard may be app l i ed to the orrcn inqs for purtia1 penetration nozzles not requlreu to be examined by Paragraph rl-513 of the Sect icn III Code: Cracks and l i ncar indications wh i ch are non-Lami nar shall be repaired. K.I-45
PBAPS GENERAL" ELECTRIC NUCLEAR ENERGY DIVISION COMPANY 175 CURTNER AVE., SAN JOSE, CALIF. 95125 * *
- AREA CODE 408, TEL. 297*3000 ATOMIC POWER EQUIPMENT DEPARTMENT TWX NO. 910*338*0116 Au gus t 6 t 1970 TO WHOM IT MAY CONCERN:
This letter of certification lists the specification and draw-ings which comprise the Design Specification for the reactor pressure vessels for Units 2 & 3 of the Philadelphia Electric Company's Peach Bottom Atomic Power Station as required by Paragraph N-14l of the ASME Boiler and Pressure Vessel Code t Section lIlt Nuclear Vessels. The specification and drawings are: 21Al1ll,Rev. 9 - Reactor Pressure Vessel 8860499 - Reactor Vessel Purchased Part Sheet No. Rev. No. Sheet No. Rev. No. 1 11 5 3 2 8 6 4 3 3 7 6 4 6 8 0 729E762, Rev. o- Reactor Thermal Cyc 1es 13589990 - Nozzle Thermal Cycles Sheet No. Rev. No. Sheet No. Rev. No. 1 1 5 0 2 0 6 0 3 0 7 0 4 0 8 0 8850911, Rev. 2 - Vessel Flange Bolting 107C5305, Rev. 2 - Nozzle End Preparation K.I-46
PBAPS GENERAL 0 ELECTRIC Page 2 This certification is issued in order that design and fabrica-tion of the reactor pressure vessels identified by General Electric Company Purchase Orders No. 205-Bl156, No. 205-H4641 and No. 205-H4642, may proceed in accordance with the require-ments of Section III of the ASME B&PV Code. The certification is issued solely for the purpose of complying with the require-ments of Paragraph N-141 of Section III and is not to be con-strued as involving, modifying, or changing contractual rela-tions or legal liabilities. The Design Specification is certified to be in compliance with the requirements of Paragraph N-14l of Section III of the ASME B&PV Code and is correct and complete with respect to functions and operating conditions in accordance with Section III, 1965 Edition with addenda to and including Winter 1965 Addenda. CERTIFIED BY: ~ t tP~ ReglSered Professional Engineer DATE: ~~
~).
&70 STATE: California
--~-------
BRANCH: Mechanical NO: 13540 RLC/jf' K.I-47
EXHIBIT II MANUFACTURE'S DATA REPORT AND VESSEL CERTIFICATION APPENDIX K K.II-1 REV. 25, APRIL 2015
EXHIBIT II - MANUFACTURERS' DATA REPORT AND VESSEL CERTIFICATION The power rerate design requirements are unchanged from the original design requirements (i.e., design pressure of 1250 psig at bottom of the reactor vessel, design temperature of 575°F). The power rerate normal operating pressure is increased from 1005 psig to 1035 psig at top of reactor vessel. The normal operating temperature is increased from 547°F to 551°F. The Unit 2 and 3 TPO power rerate did not change the normal operating pressure or temperature for the reactor vessel. The extended power uprate (EPU) design requirements for the reactor vessel are unchanged from the original design requirements. The EPU did not change the normal operating pressure or temperature for the RPV. APPENDIX K K.II-1A REV. 25, APRIL 2015
rOR~1 N*I,\ 11,\:'\UF,\LiL'nEnS' I),\T.\ nl~POnT FOn NUCI.F.,\n \*F.SSEI..s Aller.le F... (or Sin;:lo CIm**ber Complclely Sho,l*ful.rienled \lraaels Only A. required L~ 'he P,**"iRlonl .. rille ~\5\1.: C...Ir.llull:!Il CS,I Cont.69-4962 Z Chicaqo Bridge , Iron Company<< Mempbi $, Tennesspe o I ......'.c** 'd.,
~~~~~~
- 1. ......'acl.'.. ,** General Electric Co. for PhilAdelphia Electric peach Bottom,
~ > ...... ~ ,. Co Pennsylvania 4~ ;.Js. T", Vert.
Z * ....... v...., V....I ** (J- 2 J g;;:..,....
)(
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)
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.......g r
... AU. . _la. bi":~F...!! Ia. L....I'-lLFI.~...
'l6i:Mo N1 Steel
~
Z i'~ So S1f......... DblButtWldILT.* XCI GW DblButtWldll.T.* Ye, x.I-Complete E,racleaq x.**Complete N*** fC..... _s...... iii b..*. S SA 302 Gr B to ee1339
~
18 ~.~~ a(.U rl.1 Mn.Mo.Nl.* ToSlO,ooo ~)"".,ial "D.Mo.Ni.
- T.sIO,OOO 0 .........' ....... * ,.... 'Fa.. *..... P......
-:=..... . cr-. ., -..... .-....... * ~. tc-**, c_****
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t~ 5~ ~~) Top
,..." ~: .,....ft.,*.
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.J ~ matpx:ial "III **..... !.!1J5
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I
- e-....~ (at top) aa",
1fi.......
"an---l~I..a.. ~=~.:.}~:.a~olottom AI. . . . i ........
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- tII .~!: l1/itle,
~~. ~7~~a~~PY 0
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c~o.ur. %~g ** 'laJacen£ SI. ahell Lee ............,;;U5oln!Oz,k~n.9'_m~r--_ _...._~__
, hd. ~l.tes only at +lO-F*
...... c.......
............ ..~ D..... ,... ..'.. 1 A I ** pwg "' ]8 l-tp36- 0 '0'/'3 55IDteqral Welded
,I. Up_I.,1: 1 laapeal 1... Ne.
1*** ~. II.. SI. a..c , _ n He. II. Lec ~~~~-~.....- - - - - II * ......UI Slrlr, It** v.... _~.j
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....,..1 ** .c'.' Welded l~ilIIH
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- 12. __,..:Shell end Bottom Head thickness , h**" aboYe 're for ha.e !ret.,
and 1 do not include 1/8- min. oyerlay cl,""1ng Tap hea" th" cknps, 1 ncltu!e. 1/8 total corrosion allowaDce aDd no cladding . I LIe if ......
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Cft.mcM.~h ...ri.M~E.,h"~O~c~t~o~b~e~r~~2~1~,~1~'~7~2~_~ ~_~_~~~~~ __~_~ CERTIFICATIO~ OF DESIC~ De......., . _. . _ rue ** Chicago "ridge , IrQn Co.. Hempbi". Tenn
..........,...*,....'i Chicpgo Bridg. , IrQn cO. ,Memphi, Tenn
................, "' ~R.L. CIll (G.E. Cp.) a.*. "ech C.,it 13540
..........,.. ~ J. P. Butt! fR,.,,..,,,,.., , Ca** MACh. .. nh10 *2'810 U.l. ...... UA \"D.
CERr....*zc,\T": Ot' SIIOI' 1~~rECTIO~
,.,**!tL MADt,.y ChicaGO Br 4";e , IrOn Co .. Memgb!$<< Tenn L ~ ***14 ~ ._1 w4 ~ '- _ " _ * ** ,*
- h. * ***
- P ., , Hartford SteAm Doi 1 erI't.. Hartford Conn
.............................1 , ***, c III .hl. _.~***_ , _ I A... 3. _1t...ls2- .*_
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K.11-2
PBAPS Revision 1 Rat'l Bd.13903 August 26, 1970 610-0139-1 A 'art 01
- FORM H-2 afANtJFACTUREOS' PARTIAL DATA REPORT NlIClear Vessel Fabricaled by One 'tanultlcturer (or Another Manufacturer As required by the Pr\lvisions or the ASME Code Rules 1.(->>...-....... .., The Babcock & lolilcox Company., Mt. Vernon, Indiana (N . . . oiJ"iGiJ,.. . ."r Ilin'at.ctui. or port)
N ........... ,., The Chicago Brid2e & Iron CompanY Memphis 2 Tennessee
-.;:;.;;,;;;,,;;.....;;.,;;,,;.;;.;;..-..~h'=~o=
. .r ~ ., iI_\ilu'....r ot eorrapl.,eJ Duel* ., "e..1)
A48-139-1 (.)C_tructecl Ace.clift<< to ~W111C N..... l~3~~~~..;;;~;...-._ _-:Dta.... PN. .,.d ~e Babcock & Wilcox Co.
,,)DHcrlpt'ooolP.-tIn.p.eted Shell Course, MK. 60 welded to Flange MK. 48 ':a*..,b: This Shell .~~?_':l~E~e is comprised of segments as follows:
SERIAL NUMBER HEAT NUMBER MIC. 48 48-139-1 124-V-20l ASB-87 6-139-4 C2796-2 MK 60 6-139-5 C2863-2 6-139-6 C2773-1 Shell CmlTSe for C] ass A Reactor Vessel
........117 that the .t.t. . . DI. _d.
1 coni*
- to th. ASI.lE Cod. I . Hucle.r V I.. //) ?
In 11lI. ,.pon 'N cowect" that .U "etoU. of_t.rIoJ.d...... conalrucuonf!~. z . o n
~ .. pol D... September 16 u 69 licftOciThe Babcock & Wilcox C6~ ///(t"Yl., / / ./,../
- - Apr~,na;;W-7;) .. ~ j,.
e:-unee**., Autb.l&etloe Ibp.... .;...----~----::------ 17 CERTIFICATION OF DESIGN Dee ... w ...u_ ot m. e. XXXXXXXXXXXXXXXXXXXXXX}OJXXXXXXXXXXXXXXXXXXXXXXY..xXXXXXXXX ........_1,.1. ,.port _ fU. _. XXXXXXXxxxx,'{XXXXXXXXXXXXXXXXXXXXXXXXXX'Q{XXXXXXXXXXXXX De'1ea .p.cUlcatlon. cerlUlod bF XXXXXXXXXXXXXXXXxxxx.'{XX Prol. £nl* .xxx St.le --XX:i. c* Ho. X XXXXX atro*** n.I,..,. report unifIed' b,. XX~XXX~XX)QCX.xXXXXXXX2<X.~ Prof. En£X:KX- Stale ---.:XX ReC. No. X<XX'{XXX CERTIFICATE OF SHOP INSPECTION
.. Ut. uncI.rellned. holdlnc _ .. aUd com......on IUUltd b,. Ihe Nat'OftII' Bootd of O;>>Uer and Pre.aun V. . . . I mapeclan and/or the Sl.te -1iiIaI:lD 01 ud emplo,..d b,. HartforJLSJiI & I Company at Ha rt ford, Con n . ha.a tnapecled the part of a pr.a.ur. ".. ** el deacr'bed In thl ..... nul.ch"..er*. pertlal data
..port on September 16 19--.2L. end at.le that 10 the bell 01 "', knowled.e .nd bellet.lh. lIIanulaC:lur.~ he. co".ll\lcte. W. put In .ccordance with the ASME Cod. for Nuel.ar Ve *** le. 8" ellnlnl 'hi. c.rtll'ca, ** n.Uhu Ihe m.peetor nor hi. amplo,..r makee en, _rTltnr)'***pr **** d or 'IIIpll.d. cone.mln. the part de. ocrlbad In thle _n~aCCluer*. parUal dala report. Furthermore. n.IU.ar the anapector nor hi. emplo,.r ahan b. lI.bl, In .", ""naer lor any penoftallnJurJ' or propert,. da",a.e or a 10** of .ny kind arl.ln. Ir_ or connf'cted with thl. tn.pectlon. D.te September 16 19~
/2./1 ~d.d:._<'2<Y~ /(. (4', 'n.p.cI~16O'\ ..ture
_ NB-3864 Naclon.l no.rel or S181. e"d No. K.II-3
PBAPS Nat'l Bd. '3903
,FOR~I N*2 (back) . . . . . . . . Incl. '0 ~.co",ple **d I .. * Ili. _II ***** 1** teek... 0' t.ek**ed ***** 1. . . . .".u. 0' h.o, ** eho" er**
o e ase M~n. 1/8" 7/8'"
. . . . .U, Ma,.,lal SA- 302B T.'. 80, 000 ~.. _6__... ~u':~"ol/ 16... 0 .... 20 ,.11 IA. Loa"h 14 ,*._3__ lA *
(ItW
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Flanee 251 3/8" I.D. X 279~" O.D., A508, CL. 2, Code Case 1332-2, Clad with 1/8"
- J**k** ca.....: w***,,, ***1" ,ad ** 13, &ii. ote. Ii ii, _1***.,."**0 . . . 11'oh.a. a.. c,G 0' ok.tch). Min. chicknes s Matin~ p surface clad with 1/4 ft Incone1 ~ ..,.. stainless ,t*UJ stee:
I. c peell lne " . 1 _ **1 ** _ 0,. ........, 0,.
***** _d .0 ** b. cOlllpl.t.d , .. 'ub. . . ctlon.
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&.-e.... n.......
c.... ItIIucki.
&11I,,".1 Cwe.'
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C_.... )
~)T Mt'.......
- lC .
. . . . . . .b bolt...... c.) ,(b) (e) OtM' , **** DlAe Cl)eoe,lb....."DCh .1eo'Ch)
C. ., _ee. ,*. a. I ** =~=~'::;:'_C_II_I._d P.I , 0,. 01 °,.
. . . . . . .ow .... compl.,.d lor all v. . . . ,. wh.,. opplic.b'**
II. I.'**, Y.I** 0\111.' ** N. . .' **** .....u- ..... _
.t. II .
. . . . . . (1n **,.
ChIt'.'. Owelft) Ole . .....rI**
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...' 1
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17......cU_ . . . . .1*** N.. 11** .......- _ Leeo.'" o.~.. ...ftCIho***, No. TIlr**d .... II.. It.. .....tI... __
.1..........: Ilrlr' (Yeo or N.) L~. b."...,) L.I*--r.:=~~- Otho'_=~":,:,,,,::~_ At ..eh.d UkoerlbO)
-=~~~~ .....----
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NDTon O.D. Build-up on Flange has not been performed since build-up has not been machined by final configuration. K.II-4
PBAPS Nat'l Bd.'3903 Revision 1 August 26, 1970 FORM N-2 MANUFACTURERS' PARTIAL DATA REPORT A: Part or a Nuclear Vessel Fohricaled by One ManuCacturer for Another Manufacturer 610-0139 . As required by the Provisions or the A~\1E Code Rules I. (a) ......,eeture. II, The Babcock & ~~2~aaS~~2J;a'ct!~J~?rfton, Ohio
. ) ..._eet.... IN--:Th:;.;.;;.e~..;;:;C..:.:h:..:i;:.;c;:.;a;;;"g~o~B;.,;:r:...;i;:..;-dg O(a_
e & ar I ron Comp V Memp h i s;....;,"--'T~e:;;.,n;.:..::.;;n...;;;;e.:::.s-=s;..;:e;;..;e~_ _
.na addii** Of ".n\Ja.c:tur., oreoll'lp .r.J Ducl* ., " . . . .l) 1.liIeatJIac..._ .....8I.t.-r*. I .... No *
- 1 Pert _..:..;=--==.;.:.:.;:=.;.;;.;:::;.-.
See Remarks ~_ e-) c.-trIIet** Accordlnc t. Orawlftl No. 129384E Orawiftl Prep..... '" The Babcock & Hi lcox Co (fll)De.crlptloo.,Partrn.poeted 2" .Instrumentation Nozzle (MK. A-12)
..: ........ NOZZLE SElL NO. HEAT NO. SAFE END SER. xo. HEAT t\f >...
A12-139-9 8601 9-139-1 26083 A12-139-10 8601 9-139-2 26083 2" lost. Nozzle for Class A Reactor Vessel
- w. eortll, that the .t.t.lD.nte _d. In thl. "IIort . . correct .ad that aI. d.t.U. 01 _ t . ,.... d ** lID. cOMtrue1Ion, .nd workm.n.hlp 01
.... , . . conlor. to the ASWE Cod. fo, Nucl.ar V****l**
January 26 Certlfleeto .1 Aate.orla.tloo Esp"'. April
...... 10,....... 1972
'--~:.....:..=_ _
CERTIFICATION OF DESIGN De .... W _ _ tlon ot 1110 ot XXXXXXXXXXXXXXXXXXXX'<XXXXXXXXXXXXXXXXXXXXXXXXXXXXXVXX_
...... eftalpl. ,.port _IU. et XXXXXXXXXXXXXXXXXX}OOG{xXXXXXXXXXXXXXXXXXXXXXx..~xxxx _
xxxxxxxxxxxxxxxxxxxxxxx xx XXXX Itro ** ono.y.I."port c.rtUI.d b,. xxxXXXXX XXXXXXXX XXXXXXX P,of. Enl ~.t. XX R.II. No. XXXxx.XX I CERTIFICATE OF SHOP INSPECTION LIM . . . .,.llaed. holdlne * "elld co. . . . . loa I....d by tho National So.ret of S"U., ."d Pre"u,. V**** IIn.p.ctor. U1d/o, 0.. Stat *
* - - - 01 Hartford, Conn.
.nd .laplo,..d by h
Hart ford SET & T Company In.p.ct.d the p.rt of. p, 1 duc,le,.d In thh lII.nut.etur.,*. p.rtl.l d.t. of I Nport en January 27 .9--1..0-..* nd at.t. that to the be.t of.J' Imowl.dll* *ad b.Uef.th. . . .nul.et ....' he. co".tnac: **d ew. pert ... accordanc. with tho AS WE Cod. for Nucl** , V**** I** a,. el.-Inc thl. c.,tUac *** , ... Uh., th. In.peetor _, hi* * ~Io,.., _b ** n,. _".nI,..** pr **** d 0' 'lftpll.d, conc.mlnll 0.. part d **
- rlNd .. tltl. _aul.c'"",,'. p.,U.1 d *** ,.port. FunhenD_. n.Uh., the lnep.ct. no' hi*
- lIIplo,.., .... n be lIabl. In ."y lila""., 10' an,.
. .,.. . .1 ....., .r prop.rt,. d._co or. 10* *
- f .a,. kind .,I.lnl "Olft or conn.ct.d -!th thl. lnapectJoa.
Ohio 1143
"'.Uon.1 B_,a 0' Sl.t ** nd No.
K.II-S
PBAPS Hat'l ade '3903 FORM N-2 (back)
=.
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Ea_... ewc.1 H** l.pIs.rlc.1 ..... ,. Pre***
....1. . A. ._A. .I. ".la* (C . . . . .r C_.)
Ca)
,,)-----
* ..- . . 1** Mit***** (ii.'.rlol. Sp.c. N*** T .S.* lla** N\Db.r) Other ' ** '.e&ac ----r.:=~~-:::-::_::':~~==":'":'-------
(i)** c,.... Of' .u.ch .ketch) Y. J.ck.' C.....: ----(I)_ee,S ** 0 . . . .id w.ld. bi,. etc. D iii .1 ... a~nal_** 11 bolt.d. a"c,n;; .r .k.,cbS.
~ ..,., 't-Ib .. C ,.cll'" ope pro a _ p.1 ** __* t * ..,. OF .t t * ..,.*' OF
- ad 10 '0 be completed 'or tub. uction.
- t. or : 1t.'lour)'. "".rlol D.... TNc ID. AIt.c _--:~~-:--:'-:-~~ _
ex-..
- S,.c. No.) (SubJ.c, ,. ,....... 0) (Woldod. Bol,.d)
_ _ _ _ _ _ _ O.D. _
'0b. compl.,.d 'or Inner cMmbO,. 0' Jock.,.d ...... 1** or chann.l. of h.o' .achoneer**
=.
. . . . 11-14 Incl. II. " U I ... ipec. No.) 12 . . . . . . 1 Lon. H.T.' X.R. alflclo.c, -'WJ,..",~~:or---" (II ci". B) Olrtll _ H.T.1 X.R. IC** of C...... _ II. He". C.) Mo'.,101 _ _ _ _ _. T.I. ,{tt) ..a'.,..I T.I. _ ew._ Knuckl. E11IpUc.1 Conical H.1D1.phorlcal "I., Sid. ,. Pro ** ur. Lee.,... TIaIc ..... Radlu. aodlu. aa'lo Ape. Alllio a.dllla DIo_,.r (Con.... or Conc.... ) (e) Top **",,,, otld. Ot)CIla..-1
., ,......bl***olt. ~.d C.) Cb) Cc) Oth.r ' ** t.nine (,D**crib. 01 .ttach .ketch) e..., flapact It-Ib I ** =:.'t'~~'~f::;:f_c_U_l._d p.l .t _0. t.lIIP. 0. at ,."" ., 0 ..
- bol_ '0 b. COlllpleted for .11 " **** 1. whore .pplic.bl*.
- 15. ,.,." V.I... Outlot.: NuIlIbor Sl ** Location _
1** II.a.a.a: Purpou (InI.'. Outl.,. Drain) NUlllbor DIo",. or Sl ** SB-166 M.,.rlol Thlckne ** R.Worcelll.nt Materi.1 Ho. Attach.d Inst.MK. 12 2 2" CC1336-1 .401" Integral Safe End MK 9 2 ?" SA336_ .401" Integral Welded CT~- FB Type 304 Monhol** Ho. 51** Location _ n ..... poctlon r Openln**: Handhol*** Ho. _ !sa.. Locl'lon _ T ....d.d. Ho. 51.. Locollon _ I'. 'upport.: Skirt --:=-:---:=:-:- LUC' ~.,--...,-....,._ _ L*** _'"':":":.---:---:-_ Oth.r _-..,.--,._ Allechld -:::;;:-_-:--:-:-_:-- _ (Yea or No) (D**crlb.) (Wh . . . at How) lit P **twold H.at.Troat.d. I lola, oth.r IIlt.rn.1 or **ternal pr .....r. with colne ld.nt t.",poro'..,.. whell .ppllcabl. KeII-6
PBAPS Hat'l Bd** 3903 Revision 1 August 26, 1970 FORM N-2 MANUFACTURERS* PARTIAL DATA REPORT A' Part of a Nuclear Vessel Fabricated by One Manufacturer for Anotber ManufactW'er 610-0139-1 As required by the Provistons of the AS~tE Code Rules I * .., .....,...... b~ The Ba be oc k &(N~ ~~~r.~.o;r~~lt'ur.~.f ;'rtyern on, I':ld iana
~) .....,.c.'lN The Chicaci.~~J!~.~Ol~.lfac~~,~,~~,R~~:r,;'&lCI~;~r.~rfs, Tennessee I ......,Ic.U_.....,. . . . .*. . . . . . No. 01 P .... See Remarks
_.;..;;;..;;;;.....;;,;===~ _ Ca)C... trv~'.d Acc.-cllac 10 0,..,1... No. 129381E Dr * .,Iq .....pareCSby The Babcock & Wilcox Co. ftt) D...,lptll>D 01 P .... Ia.peet.d Fou~. 26" St~am Outlet Nozzles NOZZLE St;f{. SAFE END SER. NO. HEAT NO. A14-139-1 32-139-1 214795 AI4-139-2 32-139-2 214795 A14-139-3 32-139-6 214795 A14-139-4 32-139-5 214795 Four (4 ) Steam Outlet Nozzles with Safe End for Class A Reactor Vessel Certification of Design shall be furnished by others (Briel a**crIpUOn 0' ** ",acelor which .....1 p.rt w** a**I***a) w II~
".****contor. to'he ASHE Ced.for Nucl**r y .... I.. &(1
..... the .tet...... _ ** In .hl...port .re co,"** and tho** U **t.U.of mo** rlaJ*****ln. __truc*
D... September 4 It 69 liIDe. The Babcock & Wilcox Cg).
--- (UiaiIJ.cturer)
,if
.......----.........-.,;.........=.o.~...-..__:.t~--
Certuae. . . .1 Authar....... Eaplre._-..:=-- April 10, 1972 ~ _ CERTIFICATION OF DESIGN De.... W . . .Uon of IU. at XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX . . . . . . . .al,.l. report _ f ... at XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX CERTIFICATE OF SHOP INSPECTION
.. tho uncI.rellned. holdlne *** Ud commt**lon 1** \IOd by tho N.tlonol R_rd of B~llor ond Preuure y **** 1 In.p.ctor**nd/or dI. St.t.
IN _ _ lSrrr~ . * .... lIIplo,.d b, Hartford S8l & I Company of Hartford, Conn ha ** tn.p.c'.d tho p.rt of. pr 1 d**crlbed In .hl nlll.ct r*. p.rtl.1 d.t* ..port Oft Se p tember 2 .9 69 ** nd .t****hol to the beu of ..,.knowl.d** and b.Uef**he * *nlll.c r con.true**d tW. p.rt In .ccordonc. with .h. ASME Cod. for Nuel**r V**** I*. a** llnlnl .ht. c.rtlflc***.".Ithor .h. In.pectOf' nor hi.....Io,.r _Ire *
- ny _rr.nc,.**pr****dor 'mpll.d. cone.mlne tho part d**
..,I..d 1ft thl. _nuf.ct_r*. p......1 d *** report. Fwthenn_. ".lth.r the Inap.ctOl' nor hi**lIIplo,.r .hall be lI.bl. In .n" _nIl.rlor .n" ,.r.o_II",,,,, or propert, d.m****r
- 10** of .ny Irlnd .rl.lnC fr_ or conn.c**d with thla tnapacUoa.
D*** ~.p.tember 4 .,~ It? ,T. /~/]~2'~~r-~
"a;\itor*. SI&n.tur.
_ C.-I****** NB-3864 N.Uon.1 D"O'.rG .r S.ol. and No. K.II-7
PBAPS Hat'l Bd. 13903 FORM N*2 (back)
. . . . . . . Incl.'o ,.co.-pl***d fOf' .I"c'. -II *****1** JIKIr*** 0' ,.ck.ted or .h.n. of h*****cha"s.r**
I ....... L-. *.T. 1 a.T*. _ UIc .. DC'__..... ~~:'r""' _ _ " (II e.... i)
*** . , C-.a.
Kaaekla Conical Ha.laphftlcel Ild*** .-,.*** Radili* Apas Anel. R.dlu. CC_** 01' Conc.)
..l _
.l _
.............a 41 (ii***rlal. sp.c.No ** T3.* ita** Numb.r) Other f ---.,.,~~~-~~":":""'~~"":":'-------
,. J.acko. C. . . . . : - - -...(bi.r.:~.~cr='libC~-::.~. .... iu .nd weld, b.r**se, It ba, c,;'7f:.\T,,7enaaOfta. U ilolt.a. a.acrabe or ak.tch).
~ ..,.ct ,,*at
.. C . . InIet" f. . . .clf&ed . . . _an. pre . . . . . _ pal ** _s. t.lIP. Or ** t. . . . .f Or
. . . . t **4110 to "co.pl.,.d fOf' tab. a.ctio".
t * .,... ....t.: * *tlo. .".. ",t.,I.1 Ole.. Thlc..... _ _ Ia. AItaC . . . . . _--::=-':":"'~"='~~:-- _ (JUDd. Spec. No.) (Subj.ct to pr . . . III'.) ew.ld.d. Bolt.d) _ _ _ _ _ _ _ 0.0. _ (S". or OJ
. . . . 11-14 lneL compl.t.d for '"".r chamb.r. of j.ek.t.d v or ch.nn.l. of beat ..~chan**r**
11."_.: ..... H.T.* 1.R., _ we.... D) II. "ada (0) .........1 R.T.* T.I.
,X.R.
(b) Watftla1 Ko* ., c__.. T.I. _ er... ~kte EllIpUcel C-.leal H...'.pherlcal rl.t SWoto Pre.. lII'. nk..... Rocfbaa R.cUIi. R.'10 Apes Aacl. Raclau. O. . . . t., (Conv.s .r Conc. . .)
..IT ocf*
** C I
. . . . . . . . . . . Mit* * *41 C.) (b) (c) Other f** t ...... (i).IIC. Of' .ttach ak.tela)
CIIarp, Intp.ct ft-.
- 14. =~~~f::.;:f_c_If_I._d p.1 at _ ** t. . . . 0,. .t . . . . . .f o ,.
a*****1_ to ... comp,et.d fOl' .U ***** 1. wh.re .pplic.bl*. II. Safet, V.lv. Oatl.n: "'""be'~~_~ 51.. Locatl_ ~-------------:___::_--_---_::_- Nozzles clad internally with 1/8" min. thickness stainless steel 1I.1f***I..: ( OuII.t. Dwwln) Ola",. or Si** Type AS08 .CL- Ilhlckn... a.Wore.M.1lI Mat.rlal Ho. An.ch.d Steam Outlet 26" Forg.CC1332-1&2 9.437"Integral Safe End 4 Pipe SAl-OS Gr.II 1.312" Integral Welded CC1332-1 _ (D **crlb.) (Wh.r*
- HoW)
'. P H**t*Treat.d *
...... ..her ,..1 Of' . . . . r. .1 pre** ur* * "h c.&ncld**t t. . . . r.tur. . . . .n .ppllc.bl**
K.II-8
PBAPS Nat'l Bd. 13903 FORM N-2 (back)
. . . . .UIU.t.'..,
CC1339 SA-302B T.I. SO,OOO_ 3/S"
~~1.:: .._6__ ~:::=~".1/1~*.
1n. Dl *** 21 "...Q..la.....C'"lS ft . siS"
.l.1.-ln.
("W'1.~ (WI". of Ranko S",cU'.d
. . . . . . . . Leeputt Weld H.T.' Yes RoT.* Yes Efficiency _... ~---- ,..
Ul eLi.. s) See Note lolrtla B u t t We1c:\c.T.' Yes R.T. Yes .0. efC__. . (2) Two
- t. HeM.: (.) Kate,LaI TA. (It) U.terlal T.5.
....u_ c..... ICftueIr'e ElIlpUnl CenJnl He.l.ph_lc.1 r"t Sido to Pre...
('rep***t - . elld.) TWcbe ** Rad** aedlu. a *** Ape. A"-Ie Rad.u. D......, (C..,". cw C_e.) (a) _ (b) _
* .._ _blo. bolt. u. .cI (M.t.rlal. speC'. No** T .S.* lizo. Numb.,) Ot"', ' **tealae -----~--::~-~--::-.,.--......,......-------
(boacrJbe 01' .tt.ch .ketch)
- 7. Jaellet Clo.ure: .
(bncribi .0 oc ***"ClWi'Iir.liir** re , II ber cavo almenoaono. at bolted. a.ocnbe or
- ketch).
Shell Sub-Assy. clad on I.D. woth 11-8 11 min. thickness stainless steel CIIarpy Impact It-Ib I. c. .truete. lor ap.cll". oporetinl .,........1____ pal.t __**elllp. 0p .t t.... ol Or
..... 9 and 10 to b. eotllpl ..ted 'or tube .celion.
- t. T .... Sheeto: It.UOlallry. Materl.1 Dia... ThIelEn". _ _ In. A<<.ebnlenl (K.lad
- Spec. No.) (Subj.ct to pre .....) (W.ld *** Bolted)
_ _ _ _ _ _ _ O.D. _
..... 11-14 in:l. to be compl"ted 'or inncr chamb'r. 0' j.cketed "e... I., or ch.nn." 0' "".t .lI:e".ncero.
NOIDin.1 Cerro. ion II.....UJ ..~ .. Spec. Ho.) Tr:~;.. 01 Ra"C .pe:Jt::;w" In. AUowaftCe _ _ In. Dla*._ _ 't.---lta. Len.th:"- ft. _ _ Ie. e U ......: &.-1 R.T.' x.a. Elfle'one)' _~.....,.----=~ __ " weli.. B) Olrtll _ H.T.1 x.a. No. 01 Cow... _ U. He.d. (a) "at.rllli T.S. (b) Uat.rial T.S. _ C,o_ Knuckle Elliptical Conll:.1 Hem i.pherlca I Fl.t Side to Pre ** \I!'. Loc.tlon Tblcllne** a .*dlua Radiu. aallo Ape_ A"Ile Radlu. DI.meter (Convell: or C_e.".) (a) T.,. bott_** nd. (b) ChaftftOl U ,e.o".ble. bolt. u.ed C.) (b) (c) Other fa.'enin. (D**cribe or .ttach .kelch) Charp)' Impact 't-III
- 14. ~:::.~':'n~t~~e'::;~I_c_U_le_d P.I.t rna** t * .,.p. Or at temp. o, Or It.ID. brlow '0 be con.tll'led Cor 1111 vess,l. where .l'l'licAble.
l-IK. lSOS.c"r f AIV
,&OU'l "1*: Number Size Loc.tlo"
- 16. ~ouI,.:'Nozzles clad i.nternally wi t h 1 / 8 " min. thickness stainless steel PurPOU (Inlet. See Note if1 Rr-inlotcr-ment Safe Ends Outlet. Drain) Number Di.m. o,Si,. Type ASOR Thlckn... llalerl.1 How AIIGch ..d MK.lO ~('~_c!~~_t~r_ 6 12" Foq;.... c~J)31- 2 .?.~l_?.-Off j ; n t e g r a ~ SA 105 II ,CC1)32-]
MK. 11.fQX£-S.J~~:..0y -rO-rr- """A~58g1:~ljj2_~.. 9201l Intc~r.1l S t n . S t t . s!\376 T3 MK.13 -e-;R-:O-:-- - t - - ---4..t.L.- FOTg:CL~--'\'j08 Y;6-25 U -Intc-g-r<rl-St:n:"St-l--;---SkY36 CT. ~uc 12 Ins t r , . . 2 - - . 2'.!* -Bar-.-~~~ 1()t' -.401~n_t:_g*Fii-1:-&~lh-St:-h--&AJ..36CL Op .. n.n ... : .Lon.lhol.... No. $1... cc 1336 . _ _ _ _ _ $Ue Loc.ll"n _ TIv.aded. No. U. Surportt: Skirl _ _--,._ Allochrd
~~hrr .. &. How)
'II Po.' ..... ld U....'*Tr... I .. d.
1 Lltt uth,r "",."".1 or ** I"rnal rt"l.ur. wllh e .. l"cIJrnl 'Pr.lur* .,h..n arrll('.bl *. K.II-9
PBAPS Revision 2 Itat'l Bd. 13903 October 7. 1970 Fon~1 N*2 MANtIFACTURl-:ns' PARTIAL DATA REPORT A* Part or a Nuc'lenr Vessel Fabricated by O~" Manurncturcr lor Anodaor ~18nuracturer As renuired Lv the Provi!dons
.: or the AS~,!t: Code Rules
===
*. w....,***..*.., The Babcock & Wilcox Company, Mt. Vernon, Indiana CJfijM-'-J"7I4miilorllaiallictur.,-.'-pnJ
~)....., ,_ The Cbicaca.J~~YS'£".£cnn~-£~Xrr!\~a~.~ Tennessee I ......., .,....., ** S. . . I No. of P.rt CS9-13.9.,;;;,-....1..... _
129376E
<<-) C . . .nacl~d Ac* *dln. '0 Dra wl"eMo. 129377E 15-139-1 C-2789-3 6-139-1 C-3042-2 15-139-2 C-2775-3 6-139-2 C-2796-l 15-139-3 B-6776-1 6-139-3 .C-2859-2 (1) Shell Sub-Assembly for Class A Reactor Vessel Note 1 - Status of fabrication shown on B&~ ~Yg. ~MTV-QC-71555, Contract w 1" .u**
". ***1 cool*
- he a'a'***** _d. In
'0
'hi. report .... corree' aacl
.h. ASMS Cod. lor Mucl**, V**** I.. 'ha' .11 de'aU. of m.'.rlal,cI** ac.. coraatrueliOft,
.if::! /
.~d worlaD.n.hlp of
_ October 21 ..~._.The llil~c;-ll-S.~, /;, 'Hlcox co,.~£k.-t'-~ e.tIlllc.t* *f A... h. . . . . . . Itapln. April 10, 1972 CERTIFICATION OF DESIGN DeaacaW. . . U_" IU. . . XXXXXXXXXXXXXXXXXXXXXXXXXXXXX'{}OeXXXXXXXXXXXXXXXXXXXXXXX ......._Ipla r.port . . IU. a' XXXXXXXXXXXXXXXXXXXXXXX~XXXXXXXXXXXXXXXXXXXXXXXXXXXXX De.lla .pectrlcaUOft. cer,lIl.d bl' xxxxxxxxxxxxxxxxxx.xxxxxx Pro'. En~XXX s,.,. XX]{ RCI. No. XXXXXX'<.tX I.,. . . . nal,..I.,.port ce"lfled b, ~XXXXXX.~?i~~~Xx.'{XX~X~~P'ol. Ena XXX Sta'. XXX Rlrl. N~X'{ArxXX'{X CErtTIFICATE OF SHOP INSPECTION I, the under.llned, holdlnc .... Ud comml** lon I.. ""d by Ih. M,IIIC1nol O"a,d of O"U", and Pr~"u,. V..... In.p.ctar**nd/or lh~ Slot.
-.8SC£d=-' arode.Plo,.dby _ _llartf..~rd SBl.§c I Company of
--H.EtLt;Jord
- COlln. h* .,e In.pectf'd the r,ar' of
- p,~ ** W'. ve ***1 de.c,Ibed In 'hi. ",.nulac,..,.,'. r8,tlol doO'a rep.,t on October 15 19~_. and .'at. ,Ua, 10 tl.. be., 01 Illy "nowl* .1K. and bellef,th. ",anulactwe, hac enn.l,\lct.d thla pa,. In .. ccord.ne. wllh Ih. ASU£ Coda 10. Nud... , V**** I**
B, ****\lnC I"'. c."Ulc.'e. n.ith", Ih. In.p.MN roor hi. _11I('101 ft.k** aroy wanant" ** lfr'**** d or Implied, coneemlnl the p." d~* oc,lbeet In thl. ft.. nutacI,.,"". p",tu.1 d,,'n ,.po.t. Footlh..""o,***",Il"(', 'h. In.p** lor no, hla emrlo,., .hall b. U.bl~ In any ",a""e, fo, any ..non"l InJOA')" O' swope"y d.",.,,, or a 10** 0' an)' kind arl.I". f,om N connflc,.d ... hlt thl. In.".c,lon. Da,. _ _Q.<;toh(~-2.L-_'9~ R. rhd!/~!.!:*; n.,.,..*.,.",.., '-'*."'"..1 -l:2 *LJ UI. COlNllla.lo". NB-3869 n;;i1,;n..Tl1':;;;;.s-o~~ ... K.II-IO
PBAPS Revision 2 Nat'l Bd. 13903 October 7, 1970 FORM N*2 MANtJFACTlJltEns' PAnTIAL nATA REPORT A Part or a ~uclc8r Vessel Fabricered by OI1t" Manufacturer Cor Another Manufacturer As rotyu_rC'f1 hy the Prnvistons nf tlto AS.:a~ Code Rules __-=-==-===:lI_-======z': . -
.)II_III.c'... '., The Chicag~".~;!a~5~e.~ort~n~1k-5.9JPP'~~h !"!r~p!:!.~l)' Tennessee I. Weat1lac.U_M.lII.e,**,'. I.,lal No.*f P.rt _~_......E;:..1.L'=-~1L.3~.;;o9r.:-:..l.L- ~~ _
129376E (8)C.ut,ue ,.4Ace.dina: lo Drawlll' N(J. 129372J;; ..__D, ** ",- Prep...d aJ.:!!e Babcock & t-lilcox Co.
. ) D..erlptloa of Par' Inepeeted Lower Hc?d Asscmbl~y~ _ ';a._rk.l El-139- Lower Head AS.::'.f;ml:>..1y ... i~.compriscd of parts as shown on Babcock & l-1ilcox Drall1ing /1MTV-QC- 7l5.;;;..5.;;;..5~, _N;.;..o_t_e_:~~ Sheets /11 &2 _
One (1) Lower Head Assembly for Class A Reactor Vessel Certification of Des i~~I.f2:~~IOIIbof7i!~i=r~r~~~ ..eY~e.~i:art0.~!ta~!i.~.a) ..
-p ./
w* * "'tI~ that ,he .Ial...nt. _4. In thb .. port ON correet.nd 'ut all detoU. of _terlal.d** te... con.'nactlOll, ar.l worlan .Jalp or .... "....... _ **** conlor", to the A.ME Code lor Hucl.ar V****1.. CfYr./.t:~-'k~.;,!-I2./t'1 Dat. February 17 Certlflcat* *1 A8IIMlra..lloa Eaplro. It 70 Itcn. 4 The Babcock & Wilcox
--APr il ~O :a-D1Ui9ae7ilUre2-rJ
--"_'--__ -'-_.... ~ .........'-- _
if CERTU".CATION OF DESIGN XXXXXXXXXXXXXXXXXXXXXXXX}O(XXXXXXXXXXXXXXXXXXXXXXXXXXXXXX ",.......Iys ** roport _ ru. a' XXXXXXXX~"{XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX}L'{XXXXXXXXX Do." **pecillcoll_. cerllfl.d by XXXXXXXXXXXXXXXXXXXXXXX Pro'. En.i'XX 5'.1. XXX Re*. NO. X 'rxxxxx XXXX~XXXXX~~,{XXXXXXX 1"0'. EnK_XXXStote XXX ReI[. No. XXXXX.XX CERTIFICATE OF SHOll INSPECTION I. the und.ralr_,j, holdlne * .,alld cOlDml**lo" I.. ~d by Ih. N.HoMI Oo,,,d 0' O"Uer .nef Pre ..",. V..... In.p.Clor**nd/or th. St.t. or ............ etf .nd employed by ----lL1I:..tf.ars::J SB J & T C.O~y 01 ---llnJ:t.f.Q.r..~. Q.no
- h*** 1... "acl.d thO' p." 0' a pr ....... ~o .... 1 d.ec,ibed in thie m.l\wacturer'e ".,tleld.t.
"p.'1 on ~Q.r.u:1 r~.lL- 19--1.-0_, .nd.tato that to tha bcU 0' Ifty "nowl.dc.. and beU.',lt,e 1II."ul.ct",., h** cOII.uuct..d W. p.,t III .ec ....one. with the ASME Cod. 'IIr Huel.a, V.e."o. Sf .I,,,lnr th.o ce,tlflcate, ftellt,e, the lnepeC1" nor hi. aMploy.., _kee .fty _" ** Y*** ",...... 0' I"'t'Jlod, eonc."'..... tho pert d..* .c,lbed In thle _aut.elu,.,*. r",l1.1 d.t. r.porl. F",th..,mo,., n..Uh.., Iha Inopertor no, tll.....,,10'.' .h.1I "0 lIabl. In any ",a"" e r '0' any peraonal Injury Of ,..opt>rt, dam.,e 0'
- looe 0' afty kind .,Iainll Iroon 0' C'"nnfOcted wllh Ihle In.pactlon.
D.,. ---Erl~ruar~J] 19-.:1lL.. R. ,L;I;1;:(..;:.{;:£.~....;.(....., -------- K.rr-II
PBAPS Nat'l Bd. 13903 FORM N-2 (huck) Ite_ **1 l..el. 10 b.~o"'rlfled fo, .1" .. le "".11 ..... el ** '.o:k<<'. of J.ck.ted ..e ** el ** or .hell. of hen' esche","". CCT339 . 1D' L'I
- 4. IMII: "'te,I.1 SA- 3O (t:lnd~V.c. N~ (:.n".
R T.S.
80 ' 000 0' T:'lo::'ne"~In. 1"0.,.1".1 R*"lI e Sre~lfled 6 VI Con-o.lon Allowaaco _ _ I** Dl * .m-_H-__
"0 ' 1 3 .8 Lenl'h _ 11_ n. 3 Shell Clad with ln.
. . . . . . .1 L~Utt '*7eldn.T.1 Yes R.T.. Yes Eakl.oc, N~A ~/8" min. thick-
--'tiFIAUB) ness Stn. Steel Yes Ifo. 01 Cow...
Crown Knuckle Conical H...I.pherlc.1 Side to Pr<t*** Radlu. Rodlu. Ape- Anel. Redlu. (Co.",.o,C-e.) tal Bottom 125 11/16" 251 3/....8_" _ 0.) _
* ,.-.IIIe. boln **** OLI**,lol. Si'e~. No ** T .5.* Siz ** Nunlb.,) Othe, ,.uteniRi (D **c,ibe or .tt.ch ....tch)
Bottom Clad with 1/8" Min. thickness Stainless Steel
- t. J.ck.' Clo.ure: ---(b"".~.""c,'"'ibir=-"':".-:.""'o"':","':"e-:e"':".'O:"na:r:~-CIC.it bar elye JinlCnuon***, boh.a. a** cllbe 0' .kelch).
CIaupJ Impact 't*1Il
** C.elnlCtocl '0' .peclfle* .,...Une ,...uure'____ p.l.t __
- te*
- 0p .t ,e*
- 01 OF It*** 9 .nd to '0 be comple*** 'or tub* *ectlon.
- 9. Tee .....t.: St.tloaa". Ilat.,I.1 Dle.... Thlcb. . . _ _ In. Att.chm** _--::~-:-:--:::.-..---::-:- _
(JCirad. Spec. No.) (SUbject to ..... w.) (W.lded. Bolt.d) _ _ _ _ _ _ _ _ O.D. _ It*** 11-14 lL£1. to be cO:Dpleted '0' Inner chambe,. of jacketed ye ... I** or chann.l. oC he.t u:chanll:er** II..... U, ...~ , Spt'c. No.)
- 12. k ***: L-e H.T.' X.R. E"leI.ftc, -"7i7:;Ilr~:-:::--Yo iu ciU. B)
GIrth H.T.' ,X.R. No. 0' Co,..*** _ I ** Head. (a) ..., .. lel T.I. (b) .... t.'I.1 T.S. _ Cro_ Knuckle Elliptical Conlc.1 H.ml.phe.lcal Flat Iide to plf' ** ure Lee_'. TIde...... R.dlu. R.dius a.tio Ape_ Anet. Radlu. Dl ....eter (Conv.s or Conc.ve) (e) Top. ~CIII'-' end *
* )C".eel If ,..ov.ble. boll. u.'. Co) tb) (c) Oth.r 'a.U'nine (De.cribe or .ttach .ketch)
C.....p, Impact 1t.1b
, ** ~:.\in~t~:::;~r_C_II_I._d_ ....... P.I.1 _x. te.,p. OF .l'emp.o' Op
- 15. S.'trl, V.I... Oullen: f\umll.' Sh'. _ Locallon ~----------------_
- 16. Nonl** : r-tK. 7, 8, 17, 19, clad internally ,-lith 1/8" Nin. thickness stn. stl.
Purpo..* (1nle,. AS 08, CL. 2 Re Wo,cement Oull.... Dt.ln) Numlle, Dh..... or 512. Type ...... ri.1 'nIlckn... M"le",.1 Ho"" Attnch.d Rec Lr c . Inlet 10 _Jl~ F9.!"~~ _C..Q13..32..-2 6. 716" Intc$ral \-1/S ,End SA376 T.: Rec [!:~c~*Q.iJ~.Jct -2 28" For~ CC1332-2
---- - i\SOS.CL.*.....2~1. .3r- . *..,.5S0'r-intcgl*al w7s End sA376 ~
~~~£}:~~p JUMole::-;;!- --4-;;;; Forg-:- x~633l:~-z-91j211-r(11:c~rr.:I1-V1S-U1ilSrl:336 LiquiJ Cont; Vc,.ss<< 1 1 - --IJ.--CC*11*j)**l_'L--Q*1-5l' :x t:~~lIS E"d c1I336
~ ~ 1r.~b"'~-;/n .",
ASO~**Gwl......,c.------------ I " ** ,- Sb roud Sllrr)~")~'~: No. Siu 1....uOlro".*s .... __ i.!--:..J:'_ _ Luc.==-=--=_- _ _ L.c. _ _ 6 OlhO', Attached Butt \olcl<.1ing l'*.....,. No) lS.. nlb.. ,I ("' ..n.bO',) ,D ...cribe) lW.h.,e .. t1ow'-,~--- I., rC'.I... ld U.."t.T,...I ..... a LI.t ..1M. Inlr, 1 f1< * *1.,,,.1 wllh COIMI"""1 'r.I,. whO'n .r.r" hl *. Drain Nozzle No.1, Din. 2" Type Bar) Hatl. SAlOS-II, CCl332-1, Integral nO\~ Attached - \.1<*]<led CC1336 WeI CI~D l\o7.:t..lc 185 6" Sn166-63 .750" Intcgrnl K.II-12
PBAPS Revision 1 Nat'l Bd. 13903 August 26, 1970 FORM N..2 MANUFACTURERS' PARTIAL DATA REPORT A' Part or
- Nuclear \'essel Fabricated by One Maraufacturer lor Anotber MaBufacturer
.!10-0139-1 . A. reQuired by the Provisions or the AS\IE Code Rules
** N ........... ~ The Babcock & Wilcox COTPfnv,- Mt. Vernon, Indiana
\N. . . . . ..cr.r,. ** Mi1\llf** tur.;-**,.rn
~ .......... ,... The Chicago BridM.& Iron Com.;ea2X-' Memphis, Tennessee CR... ... ia'irlI."Ulac'wer co.. *,.1 "ucl.........1 I * ......, ....., , No** r Port _A 5~8w,;;;--..11w3.....,.;9.;:-~11o.- _
~>>C Mearet'nclcd.ln.Ia.No. 142117E Dn.In. . . .,.".~e Babcock & \-1ilcox Co *
* >>Do**'.......r Put ...,.ct** -S.be 11--C.Q.y~r....s'-le~ _
This Shell Course comnrised of segments as f01101"$' SERtAL IDJ11]tER 6-139-17 C-276l-2 6-139-18 C-2873-l 6-139-23 C-2894-2 Shell Course for Class A Reactor Vessel w** mU, ..... the .'.'."Id. _d. in thi. raport .,. COrNct ond that .11 d.taU. of _t.'..I.d.... A. con.tructlo '-:.za.wor.
.... ,... . . . _ ***1 eoal** tothe ASME Cod. for NIleI.., v....... .-7~
Ian IGhlp 01 Dee. September 16 I9--2LSi,n.cr.Ihe Rqbc'p~k & Wilcox COl{, /h..~J~?r M"I CwtUlce***r A. . . . . .Uon Eaptr** _ . AP
--=-
~*~<<, Wi)9 7 2
~____
~. ~.
(/ CERTIFICATION OF DESIGN Do.lea W_Uoa 01 IUe .t XXXXXXXXYXXXXXXXX~XXXXXXXXXXXXXXXXXXXXXXXXX
,,".....17-** "port on tu. 0' XXXXXXXXXXXXXXXXXXX.xxxx.xxxxxXXXXXXo.\AXXXXXXXXXXXXXXXXXX De. . . . . . .clllcott.... .,tilt.d by XXXXXXXXXXXXXXXXXXXXXXXX,X Prol. Ene. xxx. 51.le ..xxx R.c. N~ XXXXX
.......na.,..lu.port certill.d b,. XXXXXXXX'S~95~XXX'~"{XXXVXProt. Ene XXX Stet. XX~ee. No. }O{XXXX CERTIFICATE OF SHOP INSPECTION
"'M vnd.,.I,nod. holdlne * ""lid coromillion I.. ued by the National Bo.rd of Boller .nd Pre'.ur. V.... lln.p.ctor. and/or the SI.le w~of oncr employ.d by Hartford SBI & I Company of Hartford, Conn. h.". Inlpected the pert ole prcuun "e.. et de.crtbed In thh ....nul.ctur.r*. p.rll.1 d.l.
"port _ September 16 19~. ond .t.t. ,hat to th. beat of my bowledc. end b.llef.th. rn.nufecl"" he. con.lrucled Ihl. , .... In .ce.cronce with Ihe "SWE Cod. for Nucl**, V.... I**
B, .I,nln, 'hi. cerUfic.te, n.lther 'h. In.,.etor nor hi**cnploye, _ire. ony ...."anl,..**rr.... d 0' impll.d. cone.mlnc the p.rt de. ocr ..... In thi. _n~.ctw.,*. pOI"" deta "port. .....h.rmON. nellher the In.pector no' hil .mployer Ihall be lI.bl. In .ny mann'r for .ny
,.,._1 InJWF 0' propertJ' dam.ca 0'0 101. of any kind .rllinc Irora or connected with thl. Inlp.ctton.
- September 16 C - I** lon. -u-= NB - 38__6':::-4-:.-o-1....,.."...,~-:-r'r.~---- K,rr-I3
PBAPS Nat'l Bd.13903 FOR~I N-2 (back)
. . . . .01 .........
CC1339 SA-302B CKW
- I ** c. R** )
. . . . . . .I . . . .Jlutt Weld K.T.*
T.I. 80, 000 =.. . . M1.n. (Mift *
- t I ..... apecUIe..
Yes ReT.. 1/8
~_ ~:r,:~:.1/16ill. Dia*. 20 f ,!.!:*. Lencth 11 ".__
Yes Ukl* *, ------ 3/8 1_... Sbell Course clad I with l/8"min. thickness stai;r~~s':)teel One
..... "T. ReT. II** of C. . . . .
T... .) .....d.1 T". t ....... 1 Ca) "'('rlal (a)
....t..
CI'eP. ~t .......) TWclra... C....
""18.
aa-Id. IUUptIc.1 C"'c.l Ape. A,.I. H** laph** ac.l
..cU**
ria' D".... lid. '0 Pr **** (Con.... Cone.)
.)------
. . . . . . .bl** Mil' ..... (ii.,.rlal. sPoe. No ** t:s.*IUl** Huab.r) 0tM. '."'Blnc - - -.... (I)~-~-~~-:-~~-:-:--------
** crAbe . . .'tach 'ke,ch)
CD** crib*** oc***na ....e ld. iiir** ie. If 6.u -Ilayo aimeD.i_** it 'ou.a. a**crl5i or 'ke,c h). CIlupf "'oct ft-. I. c.....,.. 'or **ocUIe. operatln& ......... 1 _ pal., ma or ** t . . . . .' or
**** t .nd 10 '0...co.pl.,.d lor tub***cUon.
- t. T __ lha*** : I,.tlo..ry .....' .... 1 Die.. Thleiln. . . I.. Att.c. . . . .
(K.tocI
- Spec. No.) (SubJ'ct '0 pr. . . . .o) 0.0. _
(S'r. or 0)
. . . . 11-14 incl. '0'" compllpt.d lor inner chamb.,. of Jack.,.d " .... I_._._or_c_h_._n_n_._I._of_h_ **_'_.s_c_ha_n..;'_._r._. _
II .....11: 1Ia~~
- SpIc. No.)
It......: Leoc H.T.I X *** Efflcl.oc, -"7n....,..,..-"..........- - '" we.... s) Olrdl _ H.T.' .X.It. 1'0. of C ...... _ U ....... (.) M.'.rlal T.S. (b,) ""'rlal T.I. _ e-kle Elliptic. I Conlc.1 H'lDi.pherlc.1 FI.t Sid. to P"" .. I T .. kkno ** Itedlu. a.,io Ape. Anele a.dtu. Dlam.'.. (Con** s or Conc... ) Ca)Tep. " **_ **Dd*
* )C ""..
If b ... bolt. _ ** Ca) ,{b) (c) Ot".r 1**' **lnc (b. ,crib. or .'tach .ketch) C ...., Inap.ct 't-a,
- 14. =:.'tb.~t~f::;:f_c_U_Ie_d P.l.' _S. "lDp. Or .t '.mp. of Or De ** b.lo" to be complet.d for aU " .. ssel ..... h.'. applicabl*.
- 15. I.'et, V.I** Outl.ta: Num~r SI ** Loc:.tl- _
- 16. No ..... :
. . .po ** (Inle,. a.Wcwcem.nt Outl.,. Oweln) Numb.r 01 *** 01' Si ** TJP' M.,erl.l, 11alckft'" Materl.1 How Allached Inst4Umentation 2 2" B.ar- SB-166 .601" Integral '01/5 . End SA336 CC1336 U. lft'pIctiOft Manhole** No. SI.e Location Openln,.: Haftdhol*** No. _ !tIn Loc.Uon Thre.ded. No. Sl ** LocaUon II. lupportl: Skirt Luc' LIII Oth.r AU.ched (yea 01' No) (Numbu) (Nurnbu) (Oe.crabe) (Wher. Ii How)
I If Pou....d 1I**,.T,.al.d.
'Ll" other inlun.1 _ e.le,n,1 1W'.'ure wllh COincident temp.ra,woe wh'n ,ppllcabl**
K.II-14
PBAPS Revision 1 Nat'l Bd.13903 August 26, 1970 FORM N*2 MANUFACTURERS' PARTIAL DATA REPORT A' Part or a Nuclear Vessel ."BbricBled by One Manufacturer lor Another Manufacturer 610-0139-1 'As reguired by the Provisions of thoAS~tE Code Rules I, (.) "'aeI**,... bJ' The Babcock & Wilcox (N... .Nf""ilCDi".'"i'i-or-r.r.nuf.ctuiiloTPiiO ComDany~ Mt. Vernon, Indiana The Chicago Bridge & Iron Company, Memphis, Tennessee Ui- .Dd aieti'ii'Or'R.luJactw.r of cOlllpl.t.d Ducleu "....1) I. ~.U.,,"',,"aetarer*. aerial Ho.*f Port A202-139-1 _..;..;..;~.;;;;......;;;;..;;....;._~ _ e-)COft.truel** Accardin.. Dr....a Ho. I.... 129394E a Prep.red ~The Babcock & Wilcox Co. Dra"'....
~) De.crlptlo**f Part In.p.ct.d __-=-.::.- =- ~ _
a:*.o_,k.;fhis Her1d Segment Assembly is comprised of segments as follows: SERIAL NUMBER HEAT NUMBER 202-146-3 C-3262-1 202-146-5 C-3262-3 202-145-5 C-3042-3 202-145-1 C-313l-3 202-145-6 C-3042-3 202-146-6 C-3262-3 Head Segment Assembly For Class A Reactor Vessel Certification of Derl~~9.criP9r!lJ,.£~.~tW_"~p.!l~.nb.x.a%,*~q~5'!Ff .....s'-ll.'------- _ Wo e.,.U, that ,he .t.t._nt. _d. ID thl. N1Ion .,. CotT*
- t.nd thet .U d'I.U. of _teri.l.d...... c_tnactlon. a
............. ".***1 . - ' _ to Iho ASUE Cod. lor Nucle.r V**** I.. , } ,. DMo September 16 It 69 IlpeXhe Babcock & Wilcox CO By --.........~~'.
--ua'DUtacliii'f,) ~;,;..t:.~~"':;';O'....~.,..:...,;,Q,.....,~-
April 10, 1972 CERTIFICATION OF DESIGN XXXXXXXXXXXXXXXXXXXXX}L"{XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX ......._1,.1. report OD mo.1 XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX}(){)L"{XXXXXXXXXXXXX De..... poclflc.tlOD~ certlflod by XXXXXXXXXXXXXXXXXXXXXXX P,ol. Ena. x"'OC S** I* x""{X R'a. No. XXXXXXX CERTIFICATE OF SHOP INSPECTION I dor.I,_d, holdlne
- y.lld c_IIII**lon t..ued by the N.tionel 8_rd 0'8,)11., .nd Pru,. V. . . . IIn.p.clor**Dd/or tIIo Slato orO e and _plo,eer b, Hartford SB I & I Cgrnpany 01 Hartford, Conn. ha"o tn.poct.d the p.rt 01 a pre**wo "****1da.c,lbed In IhJ. m.nul.c:turu', p.rtlol d.t*
....... OD September. 16 19~, and ***to lhat to the be" 0' "'y Iulowledao .nd b.Il",lh. lII.nul.clur" hat con.lrueted tW. part In occord.nco wfth the ASWE Codo 1o, Nucl.ar V**** I*. B, .I,nl"a thl**orllflcalo, n.llho, the In.pe~o, no, hi**anplo,.r _k***ny -".11II" .lrpr. . . . dor Impllod, cone.mlnl til. part de-
- ,IMd In thl. __utoct.....,'. pallial d.ta ,.port. Further.ore, n.lth.r the In.p.ctor nor hi. employ.r 'hall b. lI.bl. In .ny _nno, fo, an,
....0_1 InJur, .r proparty d...... 0' a 10** of any kind .,I.ln. ,,_ or conn.cted with thl. Ia.p.ctlon. >>.,. kptcmber 16 I'J.L I?*~*~l~~g~~~o------- NB-3864 R.i1on::-:.~1~br-::o~'rG~o~r"S~t.":":t.:-.~"~aMN~*-=o:-.- - - - K.II-IS
PBAPS Nat'l Bd.f3903 FORM N-2 (back)
........ c_.....
lM~ .*f Ronc. i~~:r**---"'* AUO"lleK. .... D&aa. __ f'-..,III. LotIctIt_ft. la. Head 1.10_.: ..... Butt Wel4..T.'-.-..;~~ Yes .. '1'*. Yes _ &ftlc **_ '_ _.....~__...-_ _
- die.....)
Q - . 80 ~TO"'O-
.... oIC. . . . .
0-' SA-302B.cc H.T.' 1337... ~
........:(.) ........1 Leeo'
CT.....t ........) T ..clr.... c,...
* ...w.
Xaac Id. aedl.o (1)>) M***r .. 1
& IIlllC1c.1 a....
Conic.1 A,.. Allel.
......p".rlc.I a.dlu.
'1'. ..
Plot D. . . . .r lid. t.Pre *** (c.... or C_.) Top
~)_...;:;,.;:;.a;;; _ _ _125 11/16"-IR Concave
.)------
* .._ _.Ie. Mit****d 6iA**r1ai. sPec. N*** t .S.* 51&e. RiIIDb.r) Otller I**.*1llaa -----~~~-~~~~~":"":"-------
(I) **cr. . . . . . .ch ***ch) USe.cr" ****e***a ** id~ liir. liC. It W .1". al_ ** lone. U 'olt.a. auerabi or .ke.eb). a.u". ..,act It*a. I. C ......... for .poclfle* .,.retlna ........1 _ p.1 . . . . . . , .... Or at 'O..:.f Op
**** t a.d 10 '0 be co.p.e**d few 'ub* *ec.lon.
- t. '1' .....t.: It.UOUf7. Ma,.ra.1 0tIDd .Ipoc. N**)
D.... (Iubject .......ur.) TWcllD*** _ _ Ia. Att.c ...... _--::=~~""':'~~:-- (W.ld.cS. Bol'.d) _ _ _ _ _ _ _ 0.0. _ Ito. . 11-14 _I. ,. b. coaple**d lor inner chall\b.r. of jaek***d or channel. 01 h**' eachanCer** II......: LooI H.T.' X.R. &fflc....,_"7ft~~~~ Ul e.... a) __ "Ao 0IrtIl _ H.T.1 ,X.R. .... 01 C....... _ II. lleod. (0) ".t.r..1 '1'.1. .-(1)>) ""ar181 T.I. _ Crow. Knuckl. ElUpelul C_lcal 1I.lIlispherlc.1 Pia, lid. ,. Pre ** ur. Leee . ftIc ..... Rod.o aadlu. aa,lo Ape. Aaal. aadlu. Dla_'.r (Con..ea or Conc. . . )
..)T '- .
Ot)C 1
- re__ ~.IIl ***** Ca) (1)>) Cc) OIlier I**'.aJnc OS** erib* *
- tt.ch .ketch)
C--., lIIlpact ft.a.
- 14. ~:.\':i'~.'::;:1_C_lf_I._cl P.I.t __.,**p. Op .t , * ..,. of Or
****** Iow to be comple,.d lor .11 wh.,. eppllc.bl*.
IS. I.'." V.l". Outl.'.: Numbor llaa Loc.Uon _ I'. ".aal** : Pwpo** (lnl.,. 0uI1.,. Drain) D.... 01' SI.. ...,.ri.1 Thlelm...
..w.ce.. .
Materl.1 at lIow An.ch.d U .....paell_ ...""01***. .... II.. Locatl_ Op...." **: .......hol*** N**
,...,.odotl. N**
-'la*
II** Loc.' &on Locallon II. luppor'l: Stalrt LUI* L*** Other An.eh.d (Y** 01' No) (Hllmb.r) (Numb.r) (De.cr'b.) (Wh.,e
- How)
'., P ***** ld H*** *Tre.t.d.
1 LI., r lMer.. a. or **'e,., utO .lIh eoanc Ide t**p.r.'ur. w.e**pplle.bl** K.II-16
PBAPS Revision 1 Nat'l Bd.IJ90J August 26, 1970 FORK N-2 T.fANtJFACTURERS* PARTIAL DATA REPORT A' Part or. Nuclear Vessel FaLricaled by One Ma.luCacturer Cor Another ManuCacturer 610-0139-1 As required by the Provisions or the AS~tE Code Rules
- a. (II) .....,. .,. . . ~J' The Babcock &(NaW~J~~x r.Qmoanv M~~~~DOO, d _
** aiiiladfrrii'i ir&r.nuf"'cnar-.:-;'i panl Indiana I * ......,............t**..,** . .... No. or Part _.:..;:;..:;.....:::=.-=--= 209-139-1 _
W C .....uc*** Aocdlne '0 ~a"lnl Ifo. 1;..;;2;;..9;;..;;.3~9..;;2;;.;E;:;_. Dra.,.... PNpa.. cI .., The Babcock & Wile ox CO.
- 6) "'.cr-".o. or P** In.pecte' ~1osur~_. He_~:..::d=-:.F...::1:.::a:.n:.:.c;gL:e:._. _
SERIAL NUMBER HEAT NUMBER 209-139-1 SP-2744 ABU 134 Closure Head Flange for Class A Reactor Vessel Certification of Design shall be furnished by othersr (atr'** de.cr!pUon ori""n'lcelor which vene! pan wa. CJma==,,==.:2a ) - - - - - - - - - - -
** . ....11' tet._nt. _do 10 thl. ~port _ Co,"ct
. . . . . . . . . . . . . .a.1 cont.18 to tha ASUE Code for Huclear V**** I.. J.. --4 eftcl that all detaUa of _terlal.de * *". coaetructlon. a"d .,or_a"",.p 01 I'
hie September 16 19 69 Blpad The Babcock & Wilcox CPr- /1. (?,J1.- .'" A {l/'
--APril 10 ,(lI&iw;;;erJ /f Cftttncet. _rAutlMr ..otloa ItXpIr . . ----~-----.;;..-.------ '1 CERTIFICATION OF DESIGN O'.... w_tl_ 01 rua at XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX _
""-......1,- ** report _ fn. at XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX De.... Ip.clflcatlonl certlfl.d b,. XXXXXXXXXXXXXXXXXXXXXXXX P rof
- EnelOQ{ Stlt. XXX R e a
- No, XXXXXXX
~ee. No. XXXXXXX CERTIFICATE OF SHOP INSPECTION L .... und......DOcI. holdlne a ** lId cOI1l",I.8Ion .I. . ued b" the Nallonll DOlrd of O"iler Ind Preuure Ve . . . 1 In.pecton and/or the State or
- 4$4 and employed by Hartford SB I & I Compa ny of Hartford. Conn. "'"e In.pected the part of a prenura v.nel de.crlbed In thi. menwecturer'. pertlal dete
..port... September 16 19~, and etate that to the beat of lDy knowledee and bellef,the In.nul.cturer .... con.'Ncted thla pewt In Iccordanc. with the 105.. £ Cod. fM Nuclear Ve **el **
BJ' 111"lnl thll c.rllUclte. neUh.r the Inapeeto, "or " Dlploy.r INIk** any warTeRty, .apre *** d or Impll.d, coneemlne the pI'" de-IcrlMd In thla _n~acturcr*. pulill ".'a ,eport. Furth.nno , nellh.r the Inapeetor nt'r hie employer .... 11 be lIabl. In any .... nn.' for any
, . , . __ 1 Injury or prop.,ty damace 0' I loe. of anv kind Ir'.ln" f,om or connected with this "".paeUon.
Data September 16 19 69
.L? h"J ~.~'/cz~c..I~
X. In.p;;l~*. SI ... ,.twe _ CO_*** l o n e - . N J 1 - 3864
. rr.i'lOftii'nroa:::-::MS:::-::o~r'!!"S:-::le~le:-e::-:n:::dr"'NIU*o:-.----
K.rr-I7
PBAPS Nat'l Bd.13903 FORM N-2 (back)
. . . . 4-' IMI***** c_pl***, fer ."'11. _II *****1** jIlek..... ,.ekete' ***** a****h.lI* *f he.t .-eh.n.....
- 4. "'UI Malil:J
- SSlec. R**)
.. ......, Ca) ..., **Ia' _
T"* 1' lid*** .,.... CT ) D....... (Con** Of' C_.) Ca) _
.)------
........... Mit****d (ii.'.rl.i.Sp.c. No .* T.s..si... Md.,) oe..., Ia *** Dln. CC13jbi~~. ..,..~-~-~~_:_~~~-------
oc:,s,ach .lret~h) Closure Head Flange 245 3/4
- t. J.c**' CI. . . . : ** e, *******a 11 I.D. x 279~" O.D. A508 CL 2 lr
.cc d wl.th 3/8" Hin:
c:; CIlun ..,.. mating,.... surface.
*** *,_a. ,.... 01' ., ......, 01' **** t .Ild .0 to bll comple**d lor tube neUoa.
I. T'" .... ,il: St.Uo_ry. ""11,1.. (KIDd .. Spec. No.) D....(Subj.ct to "".ur.) TWcllne.. _ _ Ie. Alt.c...... (W.Id.d. 80h.d) _ _ _ _ _ _--:. OeD. _ (Stt.or 0)
**** 11-14 incl. '0 bll compl.,.d lor Innllr chamber. 01 I.cke,.d " ***el .... ch.nnel. 01 h**' **ch.n. ., **
II.....U....~, Spec. No.) It. . . . . . 1 1._. H.T.' X.R. _ Of e.... 8) IS. Head. (.) Ma'.rlal H.T.' T.I. X.R. (b) Ma.ar".
.... ., C__..
T.I. Cro_ Knuckle Elllptica. Conlc.l H** '.phllric.. 1'** , lid. to p,.nur. LeceU_ Ta.&c line ** Radlue R.dlu. R.Uo Apea Anel. Redlu. DIe.e,., (Conye. or Cone. . . ) Ca) Top. bott-. cad*
* )Che ......
If ...o.able. bolt. und C.) . (b) (c) Othe, f **'lIala. (i).Krlbe or .Uach .ke'ch) C1aarp~ hpact ft*nt
- 14. ~r~\'1n~'~'.O:;~f_C_U_IIl_d p.l at _It. leap. ______ Or ** leap. 0' °1' Il*** "elow '0 be tomple,ed ror .U ......el ..... her. applicable.
Loc.U _ II.SalelF V.I.... Outlen: Numbll' SI ** _ I" Noade.: PUlpo. . (1ftle,. ReWorce** na Out.e** Dr.in) N_be, Dlom. Of 11** Ma,er.al Thlckne ** """rlal How Attach.d
- 17. lnap.cUon .... ""01*** No. 'be Location Op.nln,.; Hondhole ** No. _ 111.. Location Threaded. No. 51** Loc.tlon 1** IUPPOfU: Skll' LUC' LII,a Other Att.c".d (Yea 01 No) (Number) (Numb.,) (Deacribe) (Whllre
- How)
'If p **,weld 1I**,*Tre.,.d.
- Lltl other Internal or e.lernal pr ** aur. -Ilh coinclden' te",perature ."en applicabl**
K.rr-IS
PBAPS Revision 2 Nat'l Bd.'J90J October 7, 1970 FORr" N*2 MANIJlc",\C1'URERS' PARTIAL nATA REPORT It: Pari or a Nuclear Vessel ....obricated hy One M,luuCucturer for Another Manufacturer 610-0139 As reftuirr.d by the Provisions of the AS~Jr; (:0<10 Rules
==:~-::::=e - - -
I. C.).,* ...,.ct. . . b, The Babcock & Wilcox Company, Barberton, u:...."&ricrdi'iiiOrU.il..,.ctui.,-.7-p.m Ohio The Chicago Bridge & Iron Companx, Memphis, Tennessee "tl....aa .aiiiiii"'irni'iNr.c,~c, o'ITompT.,.d Iluclur v. . . . n I .....tUSC.U.... ".atal.ch....** I.rlal No **f Part -=.S..;;e:;,;e~.:.R:..:e:;.m~~n:.:r~k:.;:.:s~ _ C.) c .."lt\ICt" Accordlnt '0 Drawtnc No. 129393E. ,Dra.. anc Prep..... b, The Babcock & Wilcox Co. _ O')De.nlptloft.,P.... Ift.paet.d 6" Instrument Nozzle (MK. A-206) NOZZLE SER. NO. HEAT NO. SAFE END ~ER~ NO. A206-139-3 207-139-3 6 11 Instrument Nozzle for Class A Reactor Vessel Certification of Design Shall be furnished by others (Ii, *** descrlptlon 01 ** ",lce lor wEIC'Ji"Yei'i"iT p.rt wa. am=::.n:-:::.:":lIdT) - - - - - - - - - - -
- w. cortlr, t"at.he ata,**on" _d. . . thl. report .re COlNct and UYt a.1I d.t.U. 01 _t.rt.l.d...... coaatructlon**nd worb'l***hlp or w ............ " ***1 conlor. to tho ASI.(E Code lor Nucl.ar V****I**
Dat. October 16 It 69 .,cna1he Babcock & '~i1cox COB,
--- (iI.nUliicTUiirl CfttUlcote 01 Aatlaarlaetloo Eltplro. April 10, 1972
~.A.-_";"-;;;;;-oL-~~~ _
CERTIFIC;\TION OF IJESIGN D** 'CD Inlot_tlon 01111. at XXXXXXXXXXXXXXXXX~XXXXX~~XXXXXXXXXXXXXX~XXXXXXXXXX .t..... anaJ,.I. report on me al XXXXXXXXXXXXXXXXXXXXXXXXX~'OOL~!{XXXXXXXXXXXXYXXXXXXX.'(XX De."n .paclflcatlon. cettill.d II, XXXXXXXXXXXXXXXX,(X~XXXXX Prol. E".XXX Slat. XXXX R.a. No. XXXXXX ..,. .. anal,.I. repon unllied b, ){XXX~X~;<X~.~~X~~X.~~~.~:K~ Pro'. E"~~~_S'ale .XXXX Rec. No. XXXX~~X CERTIFICATE Ol" SHOP I~SPECTION I. Ille uncIerolcnad. holdln, ....aU' comllll,.lon leave-d b, the N.,lonal no.rd 01 0,,11., .nd Pr ***ur. V..... I In.p.ctor. aad/or the St.t* or ~;"ei..... c:.~
- ftd .mplo,.d by _!Jllr..tf_oJ.:~L.s..ltT._&.I Conmnoy 01
__1!'!!"t ford..t--f~n.n* ....". In.pecl.d , .... pe,' 01
- rr .... ~a v**** 1 .... .:rl~d In tt.l. ",anUla~'Uter*. pe,tlal da,a ropo,' on Oc tQbcr .16__ 19 ~.9_ .*nd .'.le t1... , 10 'he be" 01 "')I' ,""owl.dc. and belief, th * *anufaclur.r ha. ~o".'ruet.d thl. r.r' 1ft .ccord.nca Wllh the ASalE Co.l. lot Nuclrar V**** I**
Dr ,11"ln. lhle crrtUlcal., neither the In.pe~or nnt hi. "Plo,., _k** an, _".lIIly*** rw.... cr or Impll.ca, COftC.",InC lha rert d.* .~,Ibed In lhl* *
- nularl",e,'...orll.1 ".'11 r.po.,'. FW.. 'IIaO,., "c-II"., lI** In .. p. C'lfW aCtr hi ** mplo,e, .haU b. lI.bl. In a", lftannO, '0' an, par.onal I"jur, or pr~&Wrt, oI*
- ac_ or
- 10** 01 an)' kino! a,I.I""I""" or "'"nroc, ..d "'lh 'hi. tnap.rUon.
Do,. October 16~'.~ _~L 2z2~-~ ~.{_~1--' t
=G Co_I .. lo"* ~~~~t1~6(141~.
....... . ~:.;.:. ~.t:.t **,"".
-./"/ iii. on_ "erG vr h"- "n e, K.II-19
PBAPS Nat'l Bd.f3903 FOR\I N-2 (back) e..,...." 4 .....U: lie.,::
- iPi'c. No.)
II_1M I
'ta:;..*r i ..... iiJctt,~~"---"* Allo_oc. Ia. Dl***_ _ ft-.Jn. a.-et"__ ft. lft.
I ...... , L-c H.T.' R.T., _ Ui e.... h) 0IflIt H.T.1 1LT. _
*** ofC. . . . .
_ _ _ _ _ _ _ _ _ _ T.s. (It) Ma **,lal T.I.
- a. H**** : Co) MIIt.,1e1 CT.......t . . . . . . .)
ita_ide Racllu. ElUptleel R.Uo H'.I'phHlcol R.dluo
.,let DIe.cUr Side to Pt-****
(Con** or Cone.) Ie)
.)------
* . . ._bl** bob' ueed *.rlal. sp.c. No** TOS**Sio... Nuaab.,) OU,., ' **t.NIle ---~~~~-~~-:-~~-:-:'------- (b** crJbe or .u.ch .ketch)
CM," ..,_t 0., ft.lb
.. C * *tnIft.d for ,p'cll"cI opereUft& pr......' _ p.1 .t _s. t . . . . 0 .. .t t.... of
. . . . t _d 10 to be completed 'or tube ncti"n*
** Twill. .....,.: 5tl'IIII17. llet'rill 0.... TlUc ...... _ _ In. Attee...... _--:=:-~-;-'"'='""':':'--:":-- _
(lUnd. Spec. No.) (Subj.ct '0 pr. . .ur.) (Weld.d. Bolted) _ _ _ _ _ _ _ _ 0.0. _
**** 11-14 incl*** be completed '0' lnne, chOlftbe,.. 0' j.l.:ke,cd v ***ell, or ch.nn." 01 he.t ouho",.r**
- 11. "U, KatOl:J * &Pic. No.)
- 12. " **1: .....e H.T.' X.R. E"lcleocJ' - ' 7 n.....r-=~~--~
we.... B)
, d. (a)
...._------- 1 H.T,'
T.S. X.R, (b) Ma,erlol Ho* ., Cow-** T.'. lCnuckJe Ellipticll COft1c.1 H.... i.pbe'le.1 F.l.' Side to P ..... ur. Thlckn'.1 R.diu. R.Uo AplE Allli. R.dlul DIa**ter (Convell or Conc. . . ) Ie) Top. Nt.... ead. Ot)C ........1
. . . ..".Ie. "oil.....d Co) ,(b) (c) _ _,..- Olher ' ** telll". (b **crib. or .ttach .ketch) cta-p, Imp.ct fl*1tt
'4. ~-::.\7:,t~:::;:r_c_lf_I._cl - - - p.l.t ..... temp. 0., .t .e~. 0. °..
**** below I;>> be ('omple"d 'or .11 v.. a.eb where .. ""lieoble.
15*. Ia'et, V.I.. e Outlo,.: Num~r II.. Location _
- 16. N***I** :
.""0" (1nl".
Outlet,D,ain) Di.",. . . Si.. Trp, AS aBeL. 2 Thlek"e.. R. inlorcem.nt Wa,e,lal How Att.ched Inst. NK. 206 1 6" For& CC l:t3_2- 2 2.609"l Integra 1 Flangc-~n,C 207 1 --6-"-- F.9~ SA-IDS --:-BliZi ' lnt(~grar ~ 17.1"*** cllon Ma"ol. ., No. li.I' ~Ei~~;l --rh1cKilcssofrl-anf!c-=-4~~ Looe.'i"n n _ Openl"c*: '1a".I".I*** No. _ !Un LC'C'.tion _
,......cI.d. No, Sile Looc.lion _
II. SUltp"".: Skirt -,...,y~.-.-or-.,N=""o-)
... Lu.. 'l\i~'u-ma..-:--,"")_ _ Le ** _~_""""T-_ Olhu ~__~-:-_ ...".C'h.d ~::':':""-_:_~_.,~----
(DeaC',... o)
' .. ro .... 1tt n,.t.T,. .. ed,
- Lol*
- other In, .. ,,,.t "" to,,,ol "i'h cowld,,,, t""'~r.'ur' wht'ft .Mllte.bl.,
K.II-20
PBAPS Revision 1 Nat'l Bd. '3903 August 26, 1970 FOIUI N-2 AIANtJFACTURERS' PARTIAL DATA REPORT A" Part of
- Nucloar Vessel Fabricated by One Manufacturer for Another ManufactW'er
.~10-0139 . As required by the Pro\'isions of the~IE Code Rules The Babcock & Wilcox Company, Barberton, Ohio
."w~..*..*~ IN_ .iITi-cmii'i"inl.ia4tlictw. . .Tjad)
The Chicago Bridge & Iron Company, Memphis, Tennessee CR- .Da .Clan.. Of Q.lUitacl_r 01 compl***a .ucl.... "_. . . 1) I .......ae.daII-.....,aclww*. . . . . . N***f P." _ ... Sue.e ........,;Bl.le
....mM.u.a.r
...k-.s~ _
131874E Ca)C__. , .... locc Dra . . . . N** 122877E Dr_Inc ....., .... ~ The Babcock & lo1ilcox Co *
- J~~.fP pect** 6" Instrument Nozzle (MK. A-206)
NOZZLE SER. NO. HEAT NO. S_AFE END SER. NO. HEAT NO. A206-127-4 ZT-3043 207-146-2 QlQlvto148lN 6" Instrument Nozzle for Class A Reactor Vessel W. c J,)" lbal I" .gt._nt. mocl Ihl ,ort
. . . . . . . . . . _ ***J coni*
- to the ASME Cod. I . Nucl** r V**** l..
COrNet that aU d.t.l.I*
- 1 _te,lal c.nallvc:llOft. end wo,* *n.hJp 01
~
DOl. December 2 It 69 sl cnol1le Babcock & lo1ilcox
---~Aiiiir.cl..... r)
COli;, ~~---r~""'~- ea.tJlJc****f Aatbc.-Jutl... Eaplr" April
..L. 10, 1972
-'-~..;:;...;-= _
CERTIFICATION OF DESIGN De.ll. Int._110ft .IIUe aeXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX
......._I;rou report Oft m*** XXXXXXXXXXXXXXXXXXX'O{XXXXXXXXXXXX~XXXXXXXXXX~,{XXXXXXX~X De.... 'peclfJeaUon.;certlll.d by XXXXXXXXXXXXXXXXXX..I'(XXXXXX:¥xXXn e* XX'{Slate XXXX R'e. No. XXXXXXXX CERTIFICATE OF SHOP INSPECTION
...... undICIllOd. holcUnc **oUd ~olllmh.lon I** urd by th. N.tlonal Bo.rd of 0,,11., and Pro ** ur. V.... I In.p.c.ora Uld/or tho Sl ***
... p. I .. ( ODchlDplol'.d II,. Hart ford 58 I & I Company 01 Hartford, Conn. ha ** In.p.c'.d lhe part of. puny,. .....1 d** c:rlb.d In th.. manw.c:turer'. part'l.1 d.t.
"PO" Oft October 16 19--6.2-.** nd .t.t. that.o lh' be.t 01 Ill, luto-I.de. and bellef.th. lII.nul.c.-yrer ha. cOlu'nac.ed W. p." In .c~c.-danc. with tho ASME Code lor Nuel.ar V**** I**
8;, .Ienln. thl. c.rUlic **** nelth.r .h. In.pector nor hJ. '1IIp10l'.r ... k*** ny w.".... , *** pr.... d or Impll.d. cone.mlnl the port d**
- crlbod In .hl. _nuractur.,*. pwU.1 d.l. r.port. Furth e rmo.... n.Uh., .h. lnap,clor lDor hi*
- lnplo,.r .h.ll b. liable In any m.nn., lor .n,.
. .nolYll InIUl;' 0' pooperty dam*** or. 10** ol.ny kind a,.alnll Ir_ or connecud .,lIh lhl. In.p.cl1on.
-- D*** w 111* November 7
-r:-: ~
~:-:-----?~--
19.
- 69
_ Ohio 1143
~ In.peflY* Slcn* 1ur * *-'"7 Retlonal Boaf'd 0' Sle,. end No.
K.II-21
PBAPS Hat'l Bd.f3903 FORM N-2 (back) p IMI. ,. MC...,Ie'M , * . ... 'a. _II " ******* jecll ., tec-.ed u UM"S.,. *
. . . . . .1 Thlcll.....
c Cs. AU
... _ ... D&ea_ft-.Ja. 1.eIIct._ft. ... .....a' lfalK'.!:J ...... ii*. j .f ..... i ..cU"~
(MIa; I .......' ..) ......... _ T". cr-.
........ )
D......r
'Id***
(c..,.* c Pre .
)
..1 -
.,----- &a**
. . . . . . . .1 r1ai.tP.c.R*** t ili** R-.;ir) oaber ,. ---"'710=~~~~~~=~~-------
us**c.& ** 0'.0 ."a ",~la. w ** te, U iii .1.. i _** I0*** 11 '.it.i. iuna;; or .il**c'S: I. C. ..,..od ,* *pocll......,.....1 .......1 _ **'a..... ,.... 0,. .,, CIIupr 0,. ae....Dd.O '0.. co,,'.t.d , . 'ub*** etlona t ........... te: ... tl6na17. Mo'. ria' 0tW. Spec. No.) D.... (SubJec' '0 .......)ThIem... lao AU......... -----:=-':'T-:-""'='~--:':__--- (W.iii....ol.od) 0.0. _
. . . . 11-14 lad. '0 bo compl.,.d f . i"" challlb.,* *f j.ck**o. " 01' cM""ol. of h *** oach co,*.
II......: Lonl H.T.1 x.a. Eftlele. .,. -_",,"=:.-Il~-- Yo Ul t .....) 0IrtIa _ H.T.1 x.a. .... ., C..... _ II....... (.) Ma.o.'" T *** lb) Ma'.rla' T.'. _ nae.....
~Id.
aodlu. Itlllptle.. a.'10 C_c.. Ape. AIIC'. H. .i.phO,ico' a.dlu. DIa .... r lid**o CC__ a Preo .ur. 0" CODe."} te) Top .
* )C .
- b bolle u..d C.) (b) (c) Othe .. , .... DJ.I (Ducrib. 01' .tt.cb .kltcb)
CIlarn ct ft*.
- 14. =~~~.~.'::;:r_C_U_i._d p.' ** _ 0,. .t 0' 0,.
..... bel... '0 b. COftlpl~t.d fo, oU vessels where .pplic.ble.
IS. I.'**, V.lve Outlot.: NUIDbe' Si ** Loc.U _
- 16. N..... e:
pgopo** (lnl.t. A508CL.2 a.w.....", Out'e** Dr.in) N_.... 01 .... or Si** ..... ri.1 Thick..... ....t.ri.1 How Att.chM lnst .MK. 206 1 6" c.cJ.J..12.:: 2 2. 6 09" In t: e gra 1 MK. 207 Flange 1 6" SAlaS ,GR. II .844" Integral Welded CCl332 Thickness of Flange, 4.594" 17..... poeU_ ".Mole.. No. 51.. Loc.Uon _
'a.a. Loc.U _
Oponl"**: Thr ** d... Handhole ** No. No. SI.. Loe.U _ I I**..,.*** : Sklr' --:("'y"'.-.-.-'N:"l'o-):- Luc e -Cl"::N"'Y-IIIb"":-.-')-- L*I._",=:---:-~ __ Other _-:':'--:'_ AUlched -:::",..._...-..,.,..--:~---- CNlilllb.,) cv.'he, *
- How)
- U Poe.weld H..t*T,. ... d.
11..1** o.he, inter"al .. '.'011 pro .. ur. "'a'h colnCldeftC t**pe'ltur. whe" .,plle.ble. K.II-22
PBAPS
~C'vision 2 Nat'l Bd. 13903 October 7, 1970 FO~UI N-2 MA~lJFACTUnEns' PARTIAl. DATA REPORT A' Pori or a Nt!cI~Br \'essel Fabricated hy Oile M.ulIICacturer for Anot!l('lf ',Ianu(actluer 610- 01.19 Ap. re~ufred ~Y the Provlsjons or tho AS::tE Code Rules The Babcock &a}t1~.~~~70~forrR~Xluiir~o~f.~e_r~t....;o;..;n~,_O;.,.h-i_o ----
.) .....r........ ,. The Chica&2a. ~n~a1¥~.of1~.1J..g-e.rS~~~r.~~ucJ:f~VJ:,ts, Tennessee See Remarks Ca)CenltrllCt** Aceorcllnl[ lo D,.wlftc No. 129393E Drawine P,.p..... ~e 6f~
Babcock & Wilcox Co.
~) o..erlptloa 01 Put In'p.ct.d 4" Vent Noz z Le (HK. A-204) ~_~ ~ _
I~ **_ b : NOZZLE SER. NO. HEAT
=_. NO. SAFE END SER. NO. HEAT NO.
A204-139-1 ZT-3043 205-139-1 4 II Vent Nozzle for Class A Reactor Vessel Certification of D~sign Shall be furnished by others (&,TeTireim:>tIOn-on-.rvlU for-.o::li1ch vn. .rp:-:.-:::;"~w::'::a:-:.~ar=.:"l.Ir=C~IlD:':Ia"')----------- Wa **rtll,. th.t tho .'at. . .nt. _ ** In th** report .r. nrnct .nd that all **t.u*
- t _t.rlal.cI** I,.. cor.. true...... and weND.nlhlp of W ........,. _ .... contorlD to the ASUE Cod. 'or N~lear Vea.el**
Date February 19 19 70 SII".:rhe Babcock & Wilcox Co.,
----u::-llw."T.ii-i"iT CenJtJcat. al "ut.. I**Uon Eaplre. April 10, 1972
~ -.t.. _
CERTIFICATION OF DESIGN D.elea Wormatl_ 01 IU. at XXXXXXXXXXXXXXXXArxXXXXXX..'O{XXXXXXXx,'{XXXXXXXXXX~'{XXXx,'{XXX ....... ana.,..I. ,.port on Ii'. at XXXXXXXXXXXXXx,~XXXXXXXXXXXXXXXVXXXXXXXXXXXXXXXXXXx.'{XX CERTIFIC,.\ TE OF SHOP INSPECTION
** , ** u..... "I'ne** holdl.... VIlId COflIft1I.llon 11.~d by the Netlon.1 DOlIi'd 0' O;>>Il"r .. nd f'reuure V.... I InlpeCtor* *nel/or the State or ~:.~., .nd e.nplo)'f'd b, _ _HaT_~.tord_~_L..§.:_LCl9mp[\I1Y 0' llnrt ford, Conry. ha". In.peeted tI.e re,l 01. pre'l"e " . . .el de.crlbf'd In lid. ma"ullctur.. ** rl,t1d da.a r.pon on S <'P t l'mb" r 18 19_ 69 . and a**t. tMt tal lh. b ... t or my "nowlttdCc and 1..11.'. the l!\lnuflec".r .... c:nn.eructed
'h** ,..rt In aeeor.s_cI With the ASIalr:: Cool. I", N..d ** r V ....... 0, .lenln. thl. c.,tU.c.... "toU"., the .... C-.ctOl' noto hi. '!bPlo,.r II_Ire. an, _r,,,nt,. ,wl"e ** ed or .mplled. conc.rnlnl th- rArt d.- .c-rUM .. In 'hla It... nutaClu,er*1 ra,h.1 d.tll Illport. Furtherlnore. nellhu lh. In.p.ctor no, hll "mr.oy.r .hall be lI.bl. in "'y ",anner 'or any , ...onal .nJ"", 01 llIopert)' "a""cl or. lOll 0' .. ny klnJ .,llln" "0"' 01' cvnnC'cl.d Wlrtl 'hi. In,p'ellon. K.II-23
PBAPS Nat'l Bd.13903 FORM N-2 (bock) I . . . . . . a ....1 H.T. 1 LT*. _ Utel... U) G.... H.T.1 L T. _ No." C. . . . . I ....... t (e) Material
......._ _ _ _ _ _ _ _ _ _ _1'...
CT... ~t... a * *) Tlalclr. . . . Cr__ JCnuclrla Redlu. (b) M.t~r.1 EUlptlc.1 R.Uo COft1cal Apea Afte,. Heml.ph.rj~.1 R.dlv. 1' ***
.. lat Da..der lid. to ..,.***
(e-. or COftC.) Ca) _ t-) _
* ,._ _ble. bolt* *"d (ii**,rl". sp.c. No** T .S**SU'. Number) Olller ' . '**nlne -r.:=~~~~~_:_-:-:-=:_:~-------
(D.. cdb' or ** tacJs ......ch)
- 7. J_cket Cloeur.a
---.,,(b~.:::.:-::c:::!t&be*.. Oil" and weld. blir, a.:. II 1)0' caye all_ndoni. 1160lted, de,c,abe 0' .il** ch).
et.arn eet .l-Ib I. C ... tructacl 'or .pacUiod oparatlnc pre ** ura l _ _ _ _ p.l.t _a. talllP. 0 .. .t t of 0 ..
**** t .nd 10 to be cO!l"plc-ced ,., tub* *actlon.
- t. Tube lhaa'.; S'_tlona",. "fat~,l.t_
(KiAd. Spec. No.) D.... (SlibJ'ct to prea....) Thlckne. . _ _ Ia. AU.c. . . . . (11->>..... Boh.d) 0.0. _
. . . . JJ-14 l1li:1. to be compl** ed lor jnner c:h:amb.,. 0' Ja.It't~d y*** el ** or rhAran.l. of h,a** icbo:acera.
Nominal Corro.lo" T .1. Thic Irna** ---In. Al1ow.nc:. la. Da.a-ft.--J!a. Lhlcth:"-' ft. - II .....U: ...~::
- Sp.c. No.) (Min. 01 Rall6;' .p.citl.d)
II....... : LoaC H.T.* X.R., _ (Qe.... s) Gbt. _ H.T.* X.R. No* ., Coura** _ II........ (a) "'t".1 1'.1. (1)>) "'t.,.1 1'.'. _ Crown ~Id. Elliptical Conlc.1 Reml.p.,leal rlat Sid. to Pr***ur. Tldrlm, ** Red.... Radlu. RaUo Apea A. .lo Radlu. DI*** t., (Cony** or Coneayo) Ca) Top. bOlt_****
* )C",.....I
.,,._a"Io, boll. us.d (a) (b) (e) - - - - - - - Other 'a"'nlne (D ** cribe << attach .ketch)
Claorn Impact It*...
- 14. ~::,~a:~~t~'.o:.::r_c:_i'_if'_d pal at _a. t...p. 0,. .t .'IIIP. o, Or
..... ".10'" to tI. c:_pl,."d 10' aU " *** eh wh,.,. _ppll**.,I**
IS. I.'etr Valv. Outleu: Nucntler SI** Loc:.Uon _
- 16. N*** I** :
Pwpo** (1It1*** Outl.t. Praln) Number DI.... or Si ** Vent J:tl(_,-lQ..~_ 1 i." MK. 2 Q.5_Ela ng£.. 1 4" No. SI** Location _
- 17. Jnopf'rU_ ...""01....
Ha".lhole ** No. _ '1** LocaU- _ Op.. nln..:.: T .... ad... No. SI"e Lor.tlon _ I', "'rport.: Sku. (y ** or NoJ LUll' (Nu ....,.') L'C*-_(;'umb.,) Other ('A'h.,. .lIow) Ilf Po.,..... 1I**,*T,... ,.d.
- Llat oth** """"'01 ,. **t.,,,.1 ......u,. with rolneld.nt '."'p.. r....... whe" appllr."I**
K.II-24
EXHIBIT III
SUMMARY
STRESS REPORT APPENDIX K K.III-1 REV. 25, APRIL 2015
PBAPS UFSAR EXHIBIT III -
SUMMARY
STRESS REPORT The power rerate design requirements are unchanged from the original design requirements specified on page K.III-7 of Exhibit III (i.e., design pressure of 1250 psig at bottom of the reactor vessel, design temperature of 575°F). The operating pressure is increased from 1005 psig to 1035 psig. The operating temperature is increased from 546°F to 551°F. GE report NEDC-32166, "Reactor Pressure Vessel, Power Rerate, Stress Report Reconciliation for the Peach Bottom Nuclear Power Plant Units 2 and 3," January 1993, documents the ASME Boiler and Pressure Vessel Code, Section III, analysis of limiting reactor pressure vessel components for PBAPS. This analysis constitutes the stress report reconciliation for validating the use of existing reactor pressure vessel components for the power rerate conditions. GE report GE-NE-523-61-0493 "Fatigue Evaluation of the Peach Bottom II and III Reactor Vessels," May 1993, GE letter GENE B13-01805-73, October 18, 1996, GE letter WFW 9607, November 13, 1996, and Calculation PM-1164 document the re-evaluation of reactor vessel fatigue in accordance with UFSAR Table 4.2.4. Closure stresses and usage factors have been re-evaluated in M-1-A-411 based on a reduced number of tensioning and detensioning passes for RPV assembly and disassembly. The Unit 2 and 3 TPO power rerate did not change the normal operating pressure or temperature for the reactor vessel. The extended power uprate (EPU) design requirements for the reactor vessel are unchanged from the original design requirements specified on page K.III-7 of Exhibit III. The EPU did not change the normal operating pressure or temperature for the RPV. GEH Report 0000-0100-9064-R1, Reactor Vessel Integrity - Stress and Fatigue Evaluation for PBAPS Units 2 and 3 Extended Power Uprate, June 2012 (G-080-VC-411) documents the stress and fatigue evaluation of limiting RPV components in accordance with the ASME B&PV Code, Section III. This analysis constitutes the stress report reconciliation and validates the use of the existing RPV components for the EPU conditions. This analysis is primarily based on the design requirements specified in GEH APPENDIX K K.III-1A REV. 25, APRIL 2015
PBAPS UFSAR certified design specification 26A8258 R2, Reactor Pressure Vessel - Extended Power Uprate (120% OLTP) (G-080-VC-412). Additionally, supplementary analysis was performed by Structural Integrity Associates for the feedwater nozzle and other limiting RPV components, as documented in report PEAM-EPU-128, Environmentally Assisted Fatigue Analysis. This analysis addresses fatigue evaluation and incorporates environmental fatigue effects due to reactor coolant environment in determining the cumulative usage factors for a plant life of 60 years. The existing steam dryer support brackets and the attachment points within the RPV have been evaluated for the replacement steam dryer (RSD) by Westinghouse as documented in Report LTR-BWR-ENG-14-001, Revision 1, February 27, 2014. There is no adverse impact on the original bracket design or structural integrity of the RPV due to increased weight of the RSD. GEH Report 0000-0148-0814-R1, December 2013 (PEAM-EPU-130), documents the evaluation performed for the RSD interface with the RPV, with the conclusion that there is no impact on the stress and fatigue reconciliation performed by GEH as documented in report 0000-0100-9064-R1 (G-080-VC-411). APPENDIX K K.III-1B REV. 25, APRIL 2015
PBAPS S.-aJ")' stress Report For Geaeral Eleetr1e - RED PElCRmTlUl II Genenl Eleetric Onler 10. 205-m56
. . , Coatrac't 110. 610-0139-51 Prepare4 By:
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Jfucl ear Power Gmention D1n.~10D Tbe Babcock & Wllcox Ccapur lit. VenoD, I~aD& Sept_bert 1970 K.III-2
PBAPS STRESS RL!lORTS C~{TIPICATION DOCl~~T Babcock & Wilcox Co. Contrac£ No. 610-0139-51 User: General Electric User Contra.ct No. ?05-RJ.156 All of the stress reports identified on Sheet I, dated 11-2-70 are complete and have \leen prepal:'ed in accorda.t1ce wi tIl the design specifications given on Sheet II, dated 11-2-70 The Babcock & Wilcox Ca. p~essure boundary drawings identified on Sheet III, dated 11-2-70 , and the 1965 Edition of the ASME Section !II Boiler & Pressure Vessel Code for Nuclear Vessels including addenda through hTT7oTT. -(,5._and Attested to this date 11-.3 . .70 By: ~ P, &Jt:: License No. E-298l0 J.P. Butti Ohio State Board Mechanical. Design Section of Profession91 Nucleal:' Con~onents Engineering Engineers The Babcock & l-lilcox Company , r " . -....... K.III-3
PBAPS SHEET I STRESS REPORTS November 2, 1970 HUMBER TITLE REVISION NUMBER 1 Sizing Calculations 0 2 Weight & Center of r,ravity Calculations 0 3 Closure Analysis 0 4 Feedwater Nozzle Analysis 0 5 Control Rod Drive Nozzle Analysis 0 6 Miscellaneous Nozzles Analysis 0 7 Piping Reactions 0 8 Support Skirt Analysis 0 9 Refueling Bellows An'l1ysis 0 , 10 Brackets 0 11 Shroud Support System Analysis '2 12 Recirculation Outlet Nozzle Analysis 0 13 Recirculation Inlet Nozzle Analysis 0 14 Does Not Apply 15 CRD Hydraulic Return Nozzle Analysis 0 16 Nozzle Ends 0 17 Core Spray Nozzle Analysis 0 16 Does not apply 19 Does not apply 20 Shell Analysis 0 21 2" Instrwnentatj,on Nozzle Analysis 0 Summary Report 2 Note: The r~vision numb~r~ arc given in the first colwnn are those in effect at the d~~' shown on the f:i.r:;t pa2~ of this certi ficat:lc.n document and are certified provici r.-: by the first page is signed. Additional r(;vi~;ions must be initio.l(;d by c.utho~*i::r* B&W Co. Professional Eneineers. K.III-4
PBAPS II. USER SPECIFICATIONS November 2, 1970 NillffiER TITLJ<~ REVISION J';'Tj}.ffi~R 211\1111 Reactor Pressure Ves~el l~rchase 9 Specificati.on with Clarification Document dated 10-22-70. Note: The reV1S10n numbers given are those in effect at the date sho~,~ on the first page of this certification document and are certified provided the first page is signed. Additional revisions must be initialed by authori7.l';:d IX,\'/ Co. Professional EnGi.neers. K.III-5
PBAPS III. BABCOCK & WILCOX CO. PRESSURE BOUNDARY DRAl'lINGS November 2, 1970 NUMBER TITLE R ~ISION NUt>ffiFR 81745D Shell Forming Details 0 25466F General Outline 8 25467F Outline Sections 9 2546& Vessel Sub-As:;cmbly 7 12937lE List of Material 12 "129372E Lower Head Assembly 9 129373E Lower Head Bottom Segment Assembly 8 129374E Lower Head Upper Segment Assembly 8 129376E Shell Segment I\ssembly Course Hl & #4 8 129377E Shell Segment Assembly Course #3 1+ 129378E Shell Segment \;;sembly ('ourse #5 3 129379E Shell Flange Detail 3 129380E Recirculation Nozzles 1+ 129381E Steam Outlet Nozzle 5 129382E Feedwater Nozzle 2 129383E Cor~ Spray N07.71e 3 129384F. 2" Inst. & 4" C.R.D. Hyd. System Return Nozzle 6 129385E 4" Jet Pump Nozzle 1+ 129386E Shroud Support 6
.129387E Ve:;sel Attac1li'" .nt l'~h ils 5 129388E Support Skirt 7 129389E Vessel Insulation Supports 1 129390E Vessel Thermocouple Pads 2 12939lE Refueling Containment Skirt 2 129392E Closure Head ~ssembly 7 129393E Closure Head dazzles 129394E Closure Head Fonning Z 4
129395E Stud Assembly & Misc. Details 129396E Stud, Nut & Washer Details 6 129397E. Vessel Sub-A~,,~mbly Details 7 129399E controi Rod Nozzles Unit #1 5 142117E Shell Segment Assembly Course #2 1 142119E Lower Head Forming Details 1 151877E Modification of 12" Recirculation Inlet Nozzle 0 151878E ModH'ication of 28" Re.circulation Outle .
'Nozzle 0 151879E Modification of 4" Jet Pump Nozzles 0 15l88oE Modification of 2" Liquid Control Nozzl 0 9 4982C 7" Bushing 2 lO5291C 7" Tapped Hole Detail a
... --- -_._-----~---_._- Note: The rev~non numbers gi,,-en in the first column are those in effect at the date shown on the first paGe of this certification document and are certified provided the first pa~e is signed. Acditioncl revizions must be initialed by e.\!:l.horizcd 'B~lV Professional Ent;inecrs. K.III-6
PBAPS Design Data B.&W. Contract 610-0139-51 General Electric N.E.D. COl1tract #205-Bl156 Engineering Specification - 2lAllll Discussion of Unit: Peachbottom II Reactor Vessel and head with special tools, test j'lc.teriaJ., vessel shipping skid and head sling. Data Pressure Temperature Design 1250 psi Operation 1005* psi Hydrotest 1565 psi Temperature of water cannot be above 2000 F Inside Radius (to clad} Thickness Top Head 125.5" 4.0" Shell 125.5" 6.125" Bottom Head 125.5" 6.125"/8.0" Cladding 3/16" nom./l/B" min. Corrosion Allowance 1/16" outside surface 1/16" nonclad inside surface K.III-7
PBAPS MATERIALS sm lOPER/DESIGN) PAM' Carl'lOn Steel 19,600/19,200 Sate end, Ba.ckins strip, Drain nozzle SA-508 CL2 26,700/26,700 External nozzles, Stab, Bracket Code Case 1332-2 SA-5404GR 23 or GR2 Code Case 1335-2 Inconel SB-166, 6 A..'1 6 steel K. III- 8
PBAPS Pipe Size Nozz 1es Req. MK. No. Dwg. Mat'l. Location (Dia. ) Nl - Recirc. Outlet 2 8 129380E MN-MO Shell 13' 5-1/2" 28" N2 - Recirc. Inlet 10 7 l29380E MN-MO Shell 1;" 1" 12" N3 - Steam Outlet 4 14 l29381E MN-l-10 Shell 54' 10-1/2" 26" N4 - Feedwater 6 10 l29382E MN-MO Shell 41' 6-1/2" 12" N5 - Core S1)ray 2 11 12~~J~~ M!"J 10 Shell 40' 4-1/2" 10" SA-I05 N15- Drain 1 22 129373E GR. II Bottom Head 2" lJ7 _ Vpnt. 1 204 l2q~q'~E ~1N-MO Top Head 4" 'NQ - e'Rn Hvn 'Ret. 1 l~ l2g184E MN-MO Shell 37' 4-1/2" 4" N10-Core Diff. Press. 1', T.; n P();~()n 1 17 12q17)IE MH-MO Bottom Head 2" Control Rod Drive 185 101-128 12g1gqE INCONEL Bottom Head 6" NR - .1F>t "Pmnn Tnstr 2 19 12q,:\8csE MN-MO Shell 11' 3" 4" Jh _h H Tn.:::." ~*,.-(~~t.ilt.*i"r. 2 ?O6 l?O~q**n*; ~'1N-Ml) 'iou BeaU ___.J 6" l'Jll _?" Tns . lInt: ::ILion ? 12 12q~84E INCONEL Shell l~ 3' 1" 2" 1\110 _0" T ""t;()n ? l? 12q~84E INCONEL Shell 49' 11" 2" 1\T1h. _0" T"' ... ~-*-~..,t.!1t;("\n ? 12 12q~84E INCONEL Shell ~O' 6" 2" K.III-9
PBAPS Support Brackets and Misc. Attachments A~tachrnent Beq. MJ<. No. Drawing ~aterial pemark Support Ski rt _.1 . ----- '11-
- ".:...4.
)10, '41 l2938~E Hull Steel BottoI:'l Head Shroud Sunnort 1 1:), - 1:)4 '2Q~86E Inconel Internal
'Ref'lJel Carlt ~ldrt , 72 '2Q~qlE Hull Steel Vessel FlanQ:e Stabj]jze.r e"'~c*1t.e:L ___8 _.-~ .l9.L-.... 12q~_6'7..j ~l:N-H() ExternaJ S+,erm n-rye-r SllPPO-rt_ 4 - I , ~l '2q~87E st. stL TnT.ernal I eOl"e Snralr B~pcket h 1~2 '2Q-~fh~ :3t. StL Internal ~l1ine 'Pan ~r~('kpt 2 ,~4 12Q~87E st. Stl. Internal F. \-1. Snar;:c!' Bracke.t .J? -., 135 129387E st. St1. Internal Drver Ho1ddmm Brack ~t 4 rn 129187E ?-iN-Me Internal , Surveillance ~necJ-mer. 6 199-200 129187E st. stl. Internal In~;ulo.";ion ~:2.ckei-.c:: ?4 81- 8~.._ . 12q-;~qE Carbo stl. ~~t~!"!!!'.:l Hearl Ljftj,rg LuS ._-" 4 210 12q~q2E MN-MO Ton Head K.III-IO
PBAPS z____ _
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K.III-Il
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PBAPS Sizing Calculations The vessel shell, upper and lower heads, and all nozzles satisfy the thickness formulae of 1-110 and 1-120 of Section III of the A.8.M.E. Code. The compensation requirement of N-450 has been met for all nozzle openings in the vessel shell, closure head, and lower head. (Ref. Report* #1 - Rev. 0). (A-3) K.III-13
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t~\-\6\..L') 2.7 \~.a 0.57 £':'.0 (A-S) K. III-IS
PBAPS T\'\'C- \V\A.~\MUM '-O~O\~~ O~ ~E- \lE-~~E-'- Rt-~u\..\s FR~'~ """'E- ~\~CO\L\7.~\~ ~R~~V"....e -\. Loc...~\.. ME:-M'ORJl....\'\t;.- : 2 G. b 7 (\~c..\... ~'Cs.';,. ~\RI::-o;::;~
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PBAPS C~OBure I.R. O.R. B.C. Height Head Flan&e 122.875" 139.625" 133.625" ;U" Vossel Flanee 125.6875" 139.625" 133.625" "36" No. Dinm. Stud Hole Length Studs 92- 6" 1" 5'-5-3/16" Washers 92 8-5/8" O.D. 2.125"/.875" Stud Shank Dia. Length S.83" 2-7-;/8 11 Interface Sui"i"acc O.D. = 260.625" I.D. = 251.25" Inner Gasket Groove
.tean Radius 126.6115
- Outer Gasket Groove
)of.ean Radius 128.2365 Gaske~ Groove Yidth .59 Gaskets Location (top or bott~m flange) Top Flange Dopth of Cladding 1/4" Botto:n & Top Flange 5/g n Top Flange at Gaskets Clo&ure Sealing Jot!lt'l Diameter 2 O-Rings Incone1 253.25"/256.5" Fiber seal outside of O-Ring
".lsc. 2 Spherical t.:ashers Per Stud nrawinc~ 1~9392Kc Closure li~!ld Ass{;:!':bly 1~9379E~~ Shell !o')anec DoJtnils (A-7)
K.III-l7
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K.III-18
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#~ c:"E"yS h-~~r ~LC: 7-?3c C.z:-/T.-eA?'/r,,?
O~ -;?;:V6 -q:. ~. c:§;i"P6c/ r-/ C,.,.v -;??o"v.. SHROUD SUPPORT LEGS (A-15B) K.III-27
PBAPS Nozzlo Rec1rc. Outlet No. Req 2 .n:. 110. 8 1)',18. No. °12938oE toeation Shell 13' 5-1/2" fro::l vessel zero JI.at '1 ).~-}.:O Inside D1wr ~ Shell 35.9" Tapor I.D. Yes Internal Lip No Inside Diem 0 First Wold 25.90" ~tsido Diam or Nozzle 53 ft Outside l>iaJU at First. Ycld 29.375" ClAdding Nom. ThY.. 3/16" Distnnco FrOl:l Vessel I.D. To bimetal weld Mat'l ASTI-t 371 ER30~ Bimetp.l Weld Distance fr.o:n Shell 26.125" Hat '1 psn*1 371 ER308 Connecting Pipe Thickness 1.181" Min.
}~tll Stainless~Steel Type 316 Thermal Sleeve No Welded Rolled Attached ~ipe Reactions Yes Tranaicnt~ Per GE Dr?win[; 729B762 Rev. 0 & 135B9990 Sheet 1, Rev. 1 (A-16 )
K.III-28
PBAPS ,-,. ....: 1 - 1.,375 " a"% R rt. WELD
---'---, 7.375
\ --:.-.1__I I--
\\ II .
I
....,,. r:-
="""'.
\,,;
"' L 7
1" 1~
"3 " R
/
I
,:__.-.- lo.SS h - L......
i
* .. }'
1~5 /::. RECIRCULATION OUTLET NOZZLE (A-I? ) K.III-29
PBAPS FT~.I. -r ~ l:::.c..... ~,-~C::"-~ os lNTE...NSIY,,/ Kl\ l--!('.:;>E, wI p, P\~~ "R~p...c-nC)~ F'o~ ~A. ~((.~ ty\:t:. ~\<o ~J\ Pi::. E.H~
\6,0 -
1"1.0 ___~~.~ ... 39.:?_ 51*3" . 64:5 f I I I
\6 .C>/-.--- --.,;..:J,. 29.0 I
1.1. 0 . . 21.0
'L Q[
31.6 2.4.0 rriII I* I 21.0, . I I RECIRCULATION OUTLET NOZZLE (A-18) K.III-30
PBAPS
~\~E:.~<;' E.~ ~\- "\L ~AF E:
g, M \::) A:r~ : TO ~E:. COM.\>A.~E..~ ,C> \.<;~m -=- 2G.' I I
\1.34 I
MA."f... ~G. +r--'aE.~~. ~-re.E..~"::.. I "l"n::'Ws. 'TV OS \\ O""'N N 0 IoJ. ~ ~ 't:."'\ c.. \0{ cs. "-'-'\...0-...1../ -= '=:>.0 ~l), -=. 8 0.. <:;) ""A'I.... Il'\E1A':n~.J\\.)E: T pe.l::S~ ~T~e.~"~ U...JT'C:.l-l ~ n-Y "
=27.09 'SALLOW ~ I C;-~m -== 4*0..*0 ~-------------,;"-}
i rI
~.o:20 ' "- .. - " J - - - - - - -
L-C...eqh- :Cc;co;:::'7'""'""" 7 ;eel/* 0') N 0,- i:: ~ 1-" L L <:;;*r'f.~c. os.~, '2..";,> A \::.E:
\ ).l -,;;: $. \
RECIRCULATION OUTLET NOZZLE (A-19) K.III-31
PBAPS Nozzle Recirc. Inlet No. Req 10 Mk. No. 7 Dwg. No. 129380E Location Shell 1S' 1" from vessel zero Ma't'l.. MN-ID Inside Diam.@ Shell li.568" Taper I.D. *No Internal Lip No Inside Diem @ First '*leld 1l.507" Outside Diem of Nozz1e" 25" Outside Diem at First Weld 13.875" Cladding Nom. Thk. 3/16" nistance From Vessel I.D. To bimetal we1.d J.1at'1. ASTM A371 ER308. Bimetal. ~!eld. Distance from Shell 22.875" J.lat'l.. .ASTM A371 ER30E Connecting Pipe Thickness .817" Min. Mat'l stainless Steel Type 316 Thermal Sleeve Yes Welded Rolled Attached by others Pipe Reactions Yes Transients Per GE dra~~ng 729E762 Rev. 0 and 135B9990 Rev. 1 (A- 20") K.III-32
PBAPS 5.lo/!£; "R --.B?/S I
.. -- 1;;. ViE.LD
---r-cr-I I
S.,*:S*65 r<¢.. 1.loq." 4-t R II f 4.."A.'OI:tS
- 4. '1?> 7S
_____i_ _; II It _a -.;,::.. . . ~_ I~ II t II ,.
._!>- b.71/~S--~ ~~ R 5.1,,15
, U
. 1-. 1= R
*-1-I II ~~
II
/
-------.---==========-
----.--.----. ---------- --1--
.l_._J__1 RECIRCULATION INLET NOZZLE I I .,
Kr) (A-21) I ',....) C-.> -_.* If., K.III-33
PBAPS
--J~"\. 1 (\u'S\c,=-}--- <73
- k.,. "'5 (O,n"S\t--:.;) .. 17*f. L Jc.,. 1 (01)\'$\0;;::.) _0' 107
~,.z. (\\{'S\O~'")-" II*-;! >:.:(.-:s (\\-1S\Os\ -0 ,~I )c."-T. ~- (Ou$\O'<:.") --- 8a
)c.,. "'l. _(OU\-s \o~) -_.' 76
>:-""1. eo. (hJ-:'\~~\o, e:J EL. \, "Z., if "S-- S,. c:;-n.... \9. ~\L:;~- ~A'" ~7..
\:~. ~ ~ 0,_ -_" 00;5""'(. "'5-T\..,. \?"".> o"\- - - 5", ... ~-,
t.L.v - '0 - 0 ~A.-Sos Cl. ~ ~ -_" "'S A. ~ caD S\~'=. 'Pg,. -\- -S'C--<:.. 12'ii;;?Ql.J\ecl...;~u-rs A~f;;;;
~OT Mc.:\ e. ~G\:**~. "2..3.~.cor e 'B,O\\\
53 - c.. - 62 ~uer-kc..cs.-S If @ ~\,)'-,)c...,.vv_t:: S e
\\-\\::" Ov\S\C~ -SUQ_~AC.l;.. Au ~'-l~,,!;\\~--'
?\.k.s*n<: Aub"\,,......o;; \"$ W"..I... PEj:c?"POI2.MC"_I,;)
\"\\":-'.J:::. C~CA-r\C,.J~. ~e ~\.J,"",-rlFIC.l~\\OI..'
~---13
/9 -
~\. ~ (>>\-s\oec.) ..,.-- "2.\
~c:.-r. ~ ~o~\-;;\'V~')--- S3
\
\0 48 (A-22)
PRIMARY AND SECONDARY STRESS INTENSITY RANGES - FINAL TOTAL VALUES K.III-34
PBAPS
~T~t:-- 'SS J"t"y E...~-S (*C\ ~ ~ AT" -rHc.
~AF E:. E.ND A t:E "TC:> ~C COlv\..P;.~.. ~£'b -\0 \ ..<:;"' -~rt\ -=::. ZG.'
\7.Cfl
--tl- 'V:r-L~-~- I I
,J
}/\J.\'1... .. ~Ec... i- ~t:"E.:~...~ ~\\~t::.~~ 'l-r-E)~-:-::. \\-y \~
'5 H o~v :-.\ Ok) ~_~ Eo\""c H
~ALt.o'.../ =.. "3.C>S >n -00:::::. BO~C>
'S,-"Co\;-:.<:.~ '"oS u-' -\E. ~-..\ "S. \ TY ~::'"2 6.5 :3
~ I, L Loy,/ -:::. -\ e- C;; <2... . ('f\ -::::'.40 .. C>
\
"~--_. ----
27*77 ">. ("-ee,c.o-7?£?C>I'2'r# 7 ~£vr:--O') l -'o-r'C'
"\ -- I... ' I
" ' - ' " - '": ...... r.. r.:::--..:.~~....
\ to>> _~ __"") .;;') ~ ;::. r, -..,.-..
A't0r.- RECIRC INLET. NOZZLE PIPING REACTION STRES&ES (A-23) K.III-35
PBAPS Nozzle . Steam Outl.et No. Req. 4 MIt. No. 14 Dwg. No. 12938lE Location Shell 54'~10!" Mat'l. MN-MO Inside Diam.@ Shell 23.75" iraper I. D. No Internal Lip No Inside Diam @ First Weld 24.326" . Outside Diam of Nozzle 42.625" Outside Diem a.t First Weld 26.374" Cladding Bom. Thk. 3/16" Distance From VC:;.3cl Mat'l. ASTM A371 ER308 Bimetal \oleld No Distance from Shell Mat'l. Connecting Pipe Thickness 1.019 Mat'l SA-105 Gr. II Thennal Sleeve No Weided Rolled Attached Pipe Reactions Yes Transients Per GE Drawing 729E762 Rev'. 0 and 135B9990 Hev. 1 (A-24) K.III-36
PBAPS l I, rz..I~~
-'5A- \ oS ~:II:
REF. ecpole.T #"~
,eev: o.
A -t---- ---II--A
--1;---------b'- .-1-----------~
\ \-Va" C) '!Jc..
c.. I "Sc>\- ~\
- s\\-
e::..u-.c 0\ ~~ ,
~
_. I I
~.
~~
STEAM OUTLET NOZZLE 14 ~~GIO~:=)-== ==(=A=-:'::;S=)===~--~ 1~ NOZZLE JUSTIFIED BY N41S.1 & N4S0 OF SECTION III Ie.. /2C;/. / K.III-37
PBAPS D E~\<::'\\~ ME-<.\4.?\ 9\ 1'\~ <S,~. .\?-~S~~ 18.0'" II IS.8'Z. (;ee,&;'~epO;er~/<:' ~eY.O)
--:JJL .---t "",£\...l:>
~Tt:.E..~*~ 1"'\E\.tS\T\c;:.~ A\ Tt\\..:.* ~~\-"c EI.1\":) A~: To ~e: c:'OM...~~t~~~ ,-0 I*'t ~ r" = ? '(. 0
. h\A..'I..... -SE..G. 1-?R.Ss'$. ~T~E_~-;'
\).\Te.t-.\"S fl"~ \~ ~\-\o").,l 0 l-.,)
\"t\E:. ~\<:t::.\"Gl-t
~A..'-'-~w -~.
- "::lo. 0"-
rl'\ ~- r~,._ ,..,..
~,;,'-J .........
M~":l.. . A\ '2'. ~A 'i?:>R. F\ N t:.: +- t>k ~'"~4. 'S Of" e ::-Z":>'";. n.,rn:. N -
~ l"Y = 2C;.7t:;}
*~J,LLo-N - l ..'So ~rl'\ -::: 40.0 1
2G.47 2'7.01 J.,'O,,\E. ~ A L\._ r...... ~T'~' ~-'.~"'s.t:::....~\ I' r-..I ~'"
' " .., \
STEAM OUTLET NOZZLE PIPE REACTION STRESSES (A-26) K.III-38
PBAPS Nozzle Feedwater No. Req. 6 I*ik. No. 10 Dwg. No. 129382E Location Shell 41' -6tn from vessel zero Mat'l. MIHMO Inside Diam.@ Sht.:ll 11, r{o2" Taper J D. No Internal Lip No Inside Diam @ First l-le1d 11.7" Outside Diam of Nozzle 26" Outside Dia'D at First Held 14.125" Cladding Nom. Thk. 3/16" Distance From Vessel I.D. 17.0625" Mat'l. ASTM A371 ER30e Bimetal Weld No Distance from Shell Mat'l*. Connecting Pipe Thickness .953" Min. Mat'l SA-105 GR. II Thenl1al Sleeve Yes Welded Rolled Attached Not attached in nozzle Pipe Reactions Yes Transients Per GE DraT,*;inE; 729£762 Rev. 0 arid 13539990 Rev. 1 (A-27) K.III-39
PBAPS _.c;5<6 .' t I.~ I2.S--:'-:-' 4 - - - - -
~VE l.D A-I If 3.0025 5.9375 I-D
~
Ib Bs'n r--~5"':"*~_ _-~----1.1~ - - - - - . I It
.1' 5-3" 1
3+ R I
-----..- II "3.0 R 12" FEEDWATER NOZZLE (A-28 )
K.III-40
PBAPS p~\ ."\- ~EC. ~il:.t::'$~ 1~1... t!.t.J~\l*Y (r6~.' ?=,po£.,...t,~4 lC,c;/,O)
~f..,)..\C:.. E:: \V/ P/PINe- REJ~G7IoN STREsSES F"o J::. Tn r:: "SAF' t!. "E.N t) ~"'LLo'N 0;:, ~.o ~"" :: S'"?.<+
tO~ Tl\e. NOr.CoLE:
~ ,.. ::::. "=t r"'l ~ -:::: <7'>,'-" - . .
~ .. ,l,..L~V" _.".. t", ~ ......... --...J 2.6 '2.8
~s '25 39 '35'
~\~ 't\.~CS\\c.... - ~\..~ST\~ 5'2 - ~4-I\~~\."\~\'S \s ~e:~\.)\\'>~~\) 0)5
~O~ ~c..T "l\ S ~ ~G\ ts ~
O\),..~ \t?So- I
, *~5r---------1 *45
'3' t
..I
'------------1.$<;
86 S3
'-!OTE:: /-'Ll- 'S..~\k C. ~.':::, C~
\~ \:::0.:::..\
12" FEEDWATER NOZZLE (A-29 ) K.III-41
PBAPS
'C';'-V:..t:': '::;.<;.. , I'J Y CJ.-l'-;' \ ' \ t t::: "$. AT" Tl\C
~A.~ Eo E"-1 '\:S A . .*?. c:. ,0 'B '2: <:.D/t" 'f> ~1<..e ~
,0 10:<5 ~ M. -;::. 1-"{.?
I Io\A.'f... ~E.c.. + y~,~*s~ ~ *rl"-\::."S<;' IN'TE1'\"S\"TY \~ ~\-\O'\llV 0\0 ,nt:: "S. l::: E:Tc }-{
~''LLO'N -==: ~,O<;t"t\ = eo, 0 1 Mf:\Y-.. */AE.;\ '& l~_I-\ w c. T'\::>l::.C~. ~\-1:l;;:.:'::::'s. 'tV\~\...l~\\Y '::= 2~ .4t "s, ALLO'N "=.' \
- S' ~ r..... -=- 4*<:;> * (:) \6.\B
-~
~
J WcL.D---":"
~~ -~*.e~po-e.r~:1J:/(p~t!:1/. 0 ) J-~
I fI 2"5.e~" L.~_..__._ 2?:_3~.~ _~ . . C;:CL.-:'~.' Z/~7"b/.::*;_ . :.r*?" 7':-~Y": 0') HO\-~ ~ AL.L c::,*n~l::.~-s.E_<::' A~C. I~ ~s \.
-12" FEEDWATER NOZZLE PIPING REACTION STRESSES (A-30)
K.III-42
PBAPS Nozzlo Core Spray No. Req. 2 )oDe. Uo. 11 I>Jg. 110. n.29383E Location. Shell 40' ':4l" above vessel zero Mat '1 l-1N-MO Inside DiaJ" ~ Shell .8.18.5" Taper I.D. No Internal Lip No Inside Diem C First Veld 8.785" Outside Dia.'i1 or l:ozzle 21:' Outside Diam at First Weld 11.5" CJ.eddine Nom. Thk. 1/4" Distance* From Vessel I.D. To bimeta~ w.eld
)O~t 11 ASTM A311 ER308 Bimetal Wald Distance from Shell 15.3125" list 11 ASTM A371 ER308:
Connecting Pipe Thick~ess .55" Min. l~tfl Stainless Steel Type*316 Thermal Sleeve Yes ~olded Rolled Attached *interference fit by "cld ~hrinkage Pipe Reactions Yes
. Tran81ents Per GE Drawing 729E762-0 and 135B9990-0 (A-31 )
K.III-43
PBAPS II
.555
-------
- r~7S-
,f G.1075" N
~
jY' ~
~=================================d _f,--l--_.'
CORE SPRAY NOZZLE (A-32)
'1:$.67/
K.III-44
PBAPS _EC?~'*~~~!~V .:'!:..._S£ca~/.c/l..s...y.
~--;::~S,.$ ..b/ TE//..S / ;~y ,81/6 E" FOR '\H E:. NO c. C.l- t::
~A\..\"'O'N -= ""3 ..o~rl'\ 7.:. 'i->>o. <.::> ~\
_ -\_~54- .l::'SI /N.
~ B ~S.l 0(,17. A" .E\..~~i\c... '~,-/:l.,.~\ \c-
~~~\..'1s.\~ \s ~e,<\) \~~~
A.T. ~c..". ~ \ ,..f TI '27 KSI
/7 /CSI
/.Y, 0'..J7:
I
. f3z KS1 /,y.
l:?z .<SI o:lT 26 Ksr. IN *
"37 K5I Of.JT.
-_. . . _... ._-----------_._._--I
~~==:====-------
~
_--~--------------- CORE SPRAY NOZZLE (A-33) K.III-45
PBAPS
\l\8:.\\. 'B \'\ \~ ~ S~~~<;:,E-S ~
e:,;\~(7.'" ::'~. 1"lrt::H~ \1\ E.'-~ AT '\He
'SA-FE. ~t-.\D A?..E"_ ,0 cc.. ~ t'v\.i-,;,\~t.i)
,0* I.e:; ~ 11\ = 2G.1 Fo \? T t\ c. ~ 0 -:c. 7_ L ~ "TO c;:; \\ E. L'- .k.\".
,y..!\'J...... J".EI-t\BEf\\j~. "\- ?~~;:...: .. ~T~.~";;'
U*rrE".N S \ '\,V '- 2.G."33
\1.3\ \C<:..L .." <::'A,LI,0V./ -=:. \.<;:" c:;, ..,"\ =- 40.0
\ ( / (;eG,c': 7?dPc>,cr#/&> ;eev: 0)
--~~_':_'1::-_W£L~ 11\1\"!... c;. EG .. -to "p';~.E.~S. ~\t:.E.S"'S
\~-rt::.l-.!~'\\c."S A~E:. ~Hov .... ).J OJ...) Tac..
.-;;. y.;:: t::."\ C. \-\
~27.o5
_. ,P
- ---7;,....~ ;;..-;:-~,:::~~
L ,-~'.
;;'--:_~*:-~*7*-:"
,.",-~_,r- :.~",,-..
- ,.:'-/ :;:---'1"--"--'"
'-"'" )
No",-C I. ALL "~*\\:'.C,'):':*"C."':'. "'\.\"-C". 1"'-> \C~\ CORE SPRAY NOZZLE PIPING REACTION STRESSES (A-34) K.III-46
PBAPS Nozzle Dra.in No. *Req. 1 }1k. No. 22 1)'",g. No. 129373E Location Bottom Head. Mat'l. SA-105 Gr. II Inside Diam.@ Shell 1.939" Taper Ie D. No Internal Lip No Inside DiaT&l @ First lo!eld 1.993" Outside Di.~ of' Nozzle 3.0" Outside Dia.~ at First \veld 2.50" Cladding No Nom. Thk. D"lstanct: Fl'oJU V:sSE:l I. D. Mat'l. Bimetal Weld No Distance ~rom Shell Mat'l. Connectinc Pipe Yes Thi.ckness .253" J.lat'l SA-106 Gr. B Thermal Sleeve No \tlelded Rolled Attached Pipe Reactions Yes Transients Per GE Drawing 729E762 Rev. 0 (A-35 ) K.III-47
PBAPS rI
--\---- - -4: WElO
,~
~
l::.. c,... . . -e..~o'-' 51t::r,~,- 2" DRAIN NOZZLE 22 (REGION C) (A-36) NOZZLE JUSTIFIED BY N415.1 & N450 OF SECTION III K.III-4B
PBAPS STRE-'5~ \~\E~S\\\E-b 1\, T\-\E:- S~~E- 't~t:> ~~~ To CO-e.- c..oV\~~~~o To \. 5 St~ ': 'Z7. ~ M~'(. S~(". + \>~~~~. ~\\:le-c:s
\\\T~~~\\,( \~ CS\o\ow~ ~ 'S,,~,(t+
<s ~\.OW :: 3.0 Sm ':- ~O. 0 M~')(. ~\;:M~~~\\C' -\- \'il:C:~~\JR~
~\R'CS<::' \~\~",s.\\"( :. C).COZ5 S,,\\OW = \.5' CS~ ':. 40.0
, 1'l.17
~ ~\o.o
('rc~." ;<::'"G;'!70,er #" 7 ;:::6 t/. 0 ') N o,e--: ~\.'- CS\~~"::~~'e--:' h\ ~~ \ 2" DRAIN NOZZLE MK 22 PIPING REACTION STRESSES (A-37 ) K.III-49
PBAPS Nozzle Vent No. Req. 1. t-1k. No. 204 D'~g. No. 129393E Location Top Head Mat'l. t-m-}oiO Inside Diom.@ Shell 4 250" c Taper I.D. Uo Internal. Lip No Inside Dia:il @ First \-leld 3.875" Outside DiaJll of Nozzle 7" Outside Diem at First Held 5.5" Cladding Nom. Thk. 1/4" Distance From Vessel I.D. To bimetal weld Mat' 1.. ASTI-1 A37l ER308 Bimetal. Weld Distance from Shell 7.218" l-la t ' 1.
- ASTt*1 A371 ER308.
Connecting Pipe Thickness Flange Connections Mat'1. Stainless Steel Thenna1. Sleeve No Welded Rolled Attached Pipe Reactions Yes* Transients Per GE Dra".*rinG 7291':762 Rev. 0 (A-38 ) K.III-SO
PBAPS -+ \~ .
\ . ,<...
It 2"3~
, tl 2.~
-SY;z.
_1 _ t-.I\ '-J - WI. () Sb.-~l. Gf':. ~ (A-39) VENT NOZZLE 204 (REGION A) NOZZLE JUSTIFIED BY N41S.1 & N4S0 OF SECTION III K.III-SI
PBAPS DES\~~ MEC.\-t ?\~\~<;. S\RE-~~~ STR&~~ \"\\£=-~~\\\'C:~ ~\ ,\\e-
~A.PC:- 't:~tl t>..\'_":- \0 ~~
c.otJ\('~~£O To \.s- ~~ ':'.27.3 MA.'#.. ~E'<... + PRG-~~. ~~&cs.'S
\~\e.N~\\'( \~ ~~ow~ O~ CS't\c.\"\
S~\.\.ow =- 3.0 SW\ ':I 80.0 M~,')!. Me\J\s~. .~~cc.+ ~R~~,SIJ\L~ 5T~c-~~ \\-\\~~~\\'( -::. \9.65
~M\.C>W ::. I. S ~"" :.. 40,0 I
c:ee~.- ;;t?~.Pt.?"e-r"#7' ~t/. 0)
\~.~5" (A-40)
VENT NOZZLE MK 204 PIPING REACTION STRESSES K.III-52
PBAPS Nozzlo CRD Hyd. ReOturn No. Req. 1.- l-D<. No. 13 INg. No. 129384E Location Shell 37' -4t" from vessel zero Hat 11 . j.:N-MO Inside DieJr tJ Shell 3.870" Taper I.D. No Internal Lip Yes Inside Die~ C First Weld 3.870" Outside Diem.or Nozzle 11.495" Outside Di~~ at First Weld 2.,625" Cladding Nom. Thk. 3/16" Distenc~OFrnm Vehsel 1.0. To bimetal weld
}lASt '1 .P.s1-i-*t A3 /l ER308 r
Bimetal lo:eld Distance trOI!1 Shell 4.25" Mat '1 AS'I)1 A371 ER308 Connecting Pipe Thickness .278"
)~t'l stainless Steel Type*304 Thermal Sleeve No \1elded Rolled Attached Inside Vessel Pipo R~actions Yes Transients Per GE Drawing 729E762 Rev. 0 and 135B9990 Rev. 0 (A-41 )
K.III-53
PBAPS 5.5208 I V f-a:? ~ ?..I2.ZS * --------..,~----t-lD'I; I
. _-----==:::...-======-~ -+--_..
3/,,, CRD HYD. RET. NOZZLE (A-42 ) K.III-54
PBAPS
?~\V\~~'( -+ 'S~C.O\~\)~\~Y ~\;~c::. \~\G~~\"'< ~~~~~
"U/ P\P\Nt"\ ~~<:'1'\O'~ ~\""?....5~:S Fo~ Tt\e ~~~E ~\)
S1\u,()u.) : 30 ~l11 : 4e ,,~\
\
tO~ "'H~ ~~:r..LE' 'SPM.Ol.c) :: 3.0 ~ =- eo.o \<.'2,\ 3 f - - - - - - - - l 2SK~' 4
~---""'55K~\
~ 60..:...:--.:Y.":,:~;,,!,,,\~------I6& K~'
7 eRD HYD. RET. NOZZLE (A-43) K.III-55
PBAPS DE-~\c..-,~ -_.
~'\::c.\-\. -p, ~'\~.~ ~'\~_~C::>l;S-S S\~'C-~rs \\4Te~~\\\'CS ~\ \\\TC-S~~\::- \::~~ ~~~ To B~
COM~~S-£:-"'O To \.55"" = 2.~.7 foR. ~OZ:LLE- \0 ~\t-\..\.. \~l\,)~\c...\0~~ M~~. Mt=M'O~A.~,=--\- ~~E-~. ~~~s~ lNTe~~\"\'( =- 26.7.9 SA,\.\.Ow ::: \.S Sb1 "; 4-c~O M p..)C. CS'i::-C. -\- ?~~~~. ~\\(..~':;.~.
,~\~~ ~\T\~ ~~~ ~\-\O"""'\~
ON T\-\&- ~"e-TC...\-\ CSf;\\.\.W-/ ~ 3. 0 ~~ -::..80. D ~\.\. ~""R~~\:-~ \H \(S\ CRD HYD. RETURN NOZZLE (A-44) PIPING REACTION STRESSES K.III-56
PBAPS Nozzle Core Diff. Press. & Liquid Control No. Req. 1 Mk. No. 17 Dwg. No. l29374E Location Bottom Head Mat'l. ~lN-~~O Inside lJ';a.-n.@ SheJ_l 1.90625" Taper I.D. Internal Lip Inside Diam @ First 1-reid .l.90625" Outside Diam of Nozz1e 5.937" Outside Diam at First Weld 3.126" Cladding Nom. Thk. 3/16" Dist.ance From Vessel I. D. To bimetal we1d
).~at*l. ASTI~ A3'!l ER308 Bimetal Weld Distance from Shell 3.875" Mat' 1. ASTl-1 A37l ER308 Connecting Pipe Thickness .206" Mat'l Stainless Steel Type 304 Thcnnal Sleeve No Welded Rolled Attached Pipe Reactions Yes Transients Per G.E. DrawInG 729E162 Rev. 0 and l35B9990 - Rev. 0 (A-45 )
K.III-57
PBAPS A -+I--A V'\u- t-"\ I) I
'$C:. :-~o"- <:;; C. 'T3. ~~
(A-46) LIQUID CONTROL NOZZLE 17 (REGION C) NOZZLE JUSTIFIED BY N415.1 & N450 OF SECTION III K.III-58
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PBAPS Nozzle Control Rod Drive No. Req. 185 .1k. no. 101-12B Dwg. Ito. - 129399E Location Bottom Head Mat'l Inconel Inside DiElI11. @ Shell 6.0" Taper I. D. No Internal Lip No Inside Diem. @ First l~eld 6.0" outside Diam. or Uozzle 7.5" Outside Di~. at First Weld 7.75" Cladding rro Nom. Thk. Distance From Vessel lAD. Ma.t'! Bimeta.l '-leld IIo Distance from Shell Mat'l Connecting Pipe No Thickness J.lat'l Thermal Sleeve No Welded Rolled Attached Pipe Reactions Yes Transients Per GE Dra~in~: 886n499 Rev. 5, Sheet 2 1.35B9990 Rev. 0 729E162 *Rev. 0 886n~99 Sheet 7 (A-48) K.III-60
PBAPS
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CONTROL ROD DRIVE NOZZLE (A-50 ) K.III-62
PBAPS Nozzle Jet Pump Inst. No. Req. 2 MIt. No. 19 Dwg. No. l29385E Location Shell n* 3" above vessel zero Mat'l. MN-MO Inside piam.@ Shell_ 3.8125" Taper I.D. No Internal Lip No Inside Diam.. @ First \*!eld J 8125" c. Outside Diam of Nozzle 8" Outside Dia-n at First Weld 5.375" Cladding Nom. Thk
- 1/4"
,- Distance From Vessel I.D. To bimetal weld Kat
- J.. AST1-1 371 ER308 Bimetal Weld Di stance r~om Shell 3.875"
}.{at-I.l. ASTM 371 ER308 Connecting Pipe Thickness 0.311" Mat'l Stainless Steel Type 304 Thermal Sleeve No Welded Rolled Attached Pipe Reactions Yes Transients Per GE Drawing 729E762 Rev. 0 (A-51 )
K.III-63
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\0.10 2.5.15 4" JET PUMP NOZZLE MK 19 (A-53) PIPING REACTION STRESSES K.III-65
PBAPS Nozzle 2" InstruInentation No. Req. Nl'.* No. 12 Location Shel13CP -;-6" ,4.3' -1" ,and 49' ,..l?--tf above vessel zero l-tat'l. Inconel Inside Dic:n.@ Shel,L 1.9~) . )" Taper I.D. No Internal Lip No Inside Di8.:'1l @ First \*leld 1.953" Outside* Dia:n o~ Nozzle 2.755" Outside Diaro at l"irst Weld 2.755" Cladding No Nom. Thk. Distance F:ro!!l V~ssel !. D. Mat'l. Bimetal l-:e ld No Distance from Shell Mat'1. Connecting Pipe Thickness .2422" stainless Steel Type 304 Thennal Sleeve No Welded Rolled Attached 1'5 }'C Reacti.ons Yes Pc r CS Dz";;.',: inc 729E7G2 and 13)B9~90 Rev. 0 (A-54 ) K.III-66
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f() -\D. N 2" INSTRUMENT NOZZLE (A-55) K.III-67
PBAPS PR\\,,\f:\RY + Sc-c..o~,\>~~Y S"'Rr-~~ \N"~~~\\'( \<.f>-..~~': CSA.\....o~ = 3~", '::. 70.0 ,,~\ 51,'2. ~\ (A-56) 2 11 INSTRUMENT NOZZLE K.III-68
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(A-57) MK 2 INSTRUMENTATION NOZZLE PIPING REACTION STRESSES K.III-69
PBAPS Nozzle 6" InstruJ'aents.tion (Head Spray) No. Rcq. 2 D'Ng. No:. 129393 Location Top Head Mat'i. MN-MO Inside Dia.-n.@ 8"lH.:11 6.218'{) Teper I.D. No Internal Lip No Inside Diam @ First \~eld 5.8125" Outside Diam of Nozzle 11.4375" Outside Dianl at first Welt! '1.5" Cladding Nom. Thk. 1/4" Distance From Vessel I.D. To bU(letal weld 1-1at 'I. ASTl'-1 A37l ER308 Bimetal Held Yes Distance from Shell 9.125" Mat'l. ASTI~ A37l ER308 Connecting Pipe Thickness Flange Connection Mat'1 Stainless Steel ThCl~al Sleeve Yes Welded Rolled For use as Head Spray Attached Clamped between flanges Pipe Reactions Yes Transients Per GE Dra*.....i ng 729=;762 Rev. 0 & l35B9990 Rev*. 0 (A-58 ) K.III-70
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I _ _ _ _I I I (A-59 ) 6" INSTRUMENTATION NOZZLE 206 (REGION A) NOZZLE JUSTIFIED BY N415.1 & N450 OF SECTION III K.III-71
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PBAPS
','AXIl*1Ur*1 US.~GE FAC'roRS Recirculation Outlet Nozzle stainJ.ess Steel .10 Mn Moly .30 SA-376 Type 316 .233 SA- 312 Type 304 .147 Mn Moly .027 l"eea.watcr Mn Moly .70 Core Spray Noz zle stainless Stce1 .01 Mn Moly .02 CRD Hyd. Ret. lk>z,zle Stain1ess Steel No uSRge *ractor Mn I~oly .363 Control Rod Drive Nozzle Inconel .005
?" JY)~t.rumentat:ion Nozzl e Inconel .06 Support Skirt Mn Moly .55 Refueling Cont~.inment Skirt Mn Moly .328 Shroud Support Mn Moly .17 Closure ~1n Moly .000 Stud .762 Vessel Shells Water Level Area .009 Lower Head Area .032 (A-61 ) K.III-73
PBAPS This section of tlle report contains a tabulation of all deviations that affect the struct.u~.~al integrity of t'he reactor vessel and closure head.
!he deviations are listed by CV numbers; also, the corresponding VN numbers are shown. A description of the variation is given along loTi. th a summary of the engil'leertng justif.l.catio~1 .~)f' that variation.
K.III-74
PBAPS cv# Description 139-6A 50472 A dimensional inspection of the 26" steam Outlet Nozzle revealed that the 5-7/8" radius was machined 1/4" too deep into the 45° angle. Conclusion In keeping t.he originu configuration, 1/4" of the reinfol Cl;Iaent area was machined off of the 45° slope. This was justified from Article 1-6 of the A.S.M.E Code, Section III. 139-19A 70207 Description Th~ minimum shank diameter of one of the studs is 5.8195" which is 0.0105" too small.
Conclusion:
The maximum primary + secondary stress in-tensity is 100 ksi. The allowable is 110 ksi; therefore, the stud as machined meets the stress requirements of the AS~m Code, Section III. 139-22 75028
Description:
Flux Monitor Penetrations exceeded the radial tolerance of 0.060" with the maximum off center of 0.164" on penetration #22-C. (B-2) K.III-75
PBAPS
Conclusion:
~le resulting reinforcement area is still in excess of the required area.
139-23B 75019
Description:
A maximum mismatch of 1-3!i6" between MK-2 (Lower Head Upper Segment) and MK-57 (Shell Course
#1 Assembly).
Conelusi.on: The maximum primary plus secondary stress is 37 ksi. The allowable is 80 ksi; therefore, the as built assembly meets the stress require: ments of the A.S.M.E. Code, Section III. 127-23B A dimensional inspection of the Lower Head Dome to Torus Assembly showed a maximum mismatch of 1/2" on th e 0 .D.
Conclusion:
Engineering calculations show the maximum primary local membrane stress intensity to be 26.8 ksi. Sallow = 1.5 Sm = 40 ksi. The maximun primary + secondary stress intensity is 35.7 ksi. Sallow = 3.0 Sm = 80 ksi. (B-3 ) K.III-76
PBAPS cv# VNI! Description l27-24B 50655 A dimensional inspection of the torus to the lower head assembly showed a mismatch of 7/8" maximum I. D. and 1/4" maximum o. D. Conclusion Engineering calculations show the primary local membrane stress intensity for mismatch geometry to be 26.8 ksi. Sedlow. = 1.5 Sm = 40.0 ksi. The maximum primary + secondary stress intensity is 19.6 ksi. Sallow. = 3.0 Sm = 80.0 ksi. Therefore engineering recommends acceptance "as is". 127-36 51403
Description:
CRD and Flux l-1onitor "J" groove deviations.
Conclusion:
The reported weld groove variations are satisfactory from the standpoint of base metal reinforcement and ligament efficiency. K.III-77
PBAPS CB&I Deviation
Description:
Repo rt IfJ I C)( '?-1 A maximum mismatch of 1- 3/8" between MK-202 (closure head segment) and MK-209 (closure head fl<i.nge) .
Conclusion:
The maxlmum primary + seconda.ry stress intensity is 75.7 ksi. The allowable is 80.0 ksi; therefore, the as built assembly meets the stress ~equirements of the AS~ffi Code, ~ection III. CB&I Deviation Description Report #4962-2 Three of the tapped stud bushing holes (#14,32,66) had defective threads. Also, the bottom 2-1/2 inches of thread of one side of hole #31 were incomplete or missing.
Conclusion:
Special overzize bushings were used for the thread holes (14,32,66) that hn.d defective threads. The minim\UTI effecti.ve thr(:.:-Jl lenGth that (B-5 ) K.III-78
PBAPS cv# VNI Conclusion - (Cont'd.) is required in the flange is 4.07 in. Therefore, the 8 inches of good thread'in hole #31 is acceptable. CB&I Deviation Description-Report #4962-8 Two thin areas in the lower head vnth the minimum thickness of 7.99 in. which includes the cladding thickness.
Conclusion:
These two thin areas are outside the eRD and in-core penetration region. Since the required thickness in this region is 3.0751", the 7.99 in. thickness is acceptable. (B-6) K.III-79
PBAPS UFSAR EXHIBIT IV - VESSEL FABRICATION AND ASSEMBLY IV.1 DIVISION OF WORK A significant portion of the vessel fabrication was performed by B&W in their shop facilities at Mt. Vernon, Indiana. This work was in accordance with the ASME code and GE fabrication and quality control requirements. The balance of the fabrication and assembly was performed by CB&I in their shop facilities at Memphis, Tennessee. IV.2 B&W to CB&I Transfer of Vessel Parts The condition of the parts and equipment of the Peach Bottom vessel at the time of transfer to CB&I was as described below. IV.2.1 Condition and Stage of Fabrication for Peach Bottom Unit 2 Reactor Vessel IV.2.1.1 Piecemark 57 and C1 consisting of the bottom head assembly and No. 1 ring. The entire assembly was complete with nozzles installed, flux monitor penetrations machined, CRD penetrations and sleeves completed and machined, shroud support installed and top machined, jet pump adapter weld preparations machined, skirt and skirt flange welded complete with flange holes drilled, all overlay welding complete, and all non-destructive testing complete. In addition, all furnace sensitized stainless steel safe ends were removed, the nozzle to safe end weld prep machined, re-buttered, and re-machined. The weld preparation for the seam between the No. 1 and No. 2 shell ring was not made. IV.2.1.2 Piecemark 58 consisting of the No. 2 shell ring complete in one piece, overlay cladding applied, and all non-destructive testing complete. The weld peparation for the seams to both the No. 1 and No. 3 shell rings was not made. IV.2.1.3 Piecemark 59 and 16 consisting of the No. 3 ring and the "dutchman" were complete with all nozzles installed, safe ends installed, all overlay cladding applied, and all non-destructive testing complete. The weld preparations for the seams to both the No. 2 and No. 4 shell rings were not prepared. IV.2.1.4 Piecemark 60 and 48 consisting of a complete assembly of the No. 4 shell ring with the vessel flange. All cladding and back cladding of welds was complete, the weld buildup for the refueling containment skirt was complete, and all non-destructive testing complete. The flange was clad, the ninety-two 6 ft 3/4-in diameter holes pre-bored, the seal surface rough machined, and all non-destructive testing complete. The APPENDIX K K.IV-1 REV. 21, APRIL 2007
PBAPS UFSAR final machining of the stud holes and seal surface, and the installation of all nozzles were not performed. All nozzles to be installed were included and were fabricated, clad, safe ends installed, machined, all non-destructive testing complete, and ready for installation. The weld preparation for attachment of the No. 4 shell ring to the No. 3 shell ring was not made. IV.2.1.5 Piecemark 201 consisting of the closure-head dome. This item was shaped, quenched, and tempered with non-destructive testing complete. All nozzles were complete and included, but not installed. IV.2.1.6 Piecemark 202 consisting of the closure head torus. All long seams were welded and all non-destructive testing complete. IV.2.1.7 Piecemark 209 consisting of the closure head flange. The flange seal surface was clad, the stud holes rough bored and all non-destructive testing complete. IV.2.1.8 Equipment and Tools (not piecemark items)
- 1. Ninety-two studs, nuts, bushings, washer sets, and taper pins.
- 2. Ninety-two bottom inserts, top inserts, and bottoming sleeves.
- 3. Top head nozzle gaskets, one 4-in weld neck flange, one 4-in blind flange, and two 6-in blind flanges.
- 4. Thermal sleeves as required for recirculation inlet and feedwater nozzles.
- 5. Refueling containment skirt, fabricated and machined, ready for welding to the vessel.
- 6. All brackets and attachments, both internal and external.
- 7. Two sets of new Inconel "O" rings together with a minimum of fifty "O" ring retainer clips and fasteners.
APPENDIX K K.IV-2 REV. 21, APRIL 2007
PBAPS UFSAR IV.2.2 Condition and Stage of Fabrication for Peach Bottom Unit 3 Reactor Vessel IV.2.2.1 Piecemark C1 IV.2.2.1.1 MK1, dome, formed to contour, material certified after quench and temper, and all non-destructive testing complete. IV.2.2.1.2 MK4, lower torus, segments formed and welded, seams blended, and all non-destructive testing complete. IV.2.2.1.3 MK2, upper torus, segments formed and welded, seams blended, and all non-destructive testing complete. IV.2.2.1.4 MK24, support skirt transition ring. The ring was shipped as 4 segments, formed, and all non-destructive testing complete. IV.2.2.1.5 Sufficient material for fabrication of MK40 support skirt, MK41 base ring. IV.2.2.1.6 MK17, nozzles with safe ends attached, clad, machined, and all non-destructive testing complete. IV.2.2.1.7 MK101 through 128, CRD stub tube material in sufficient quantity for socket type installation. IV.2.2.1.8 Shroud support assembly consisting of legs MK51 and 52, ring MK54, baffle plate MK53 all fabricated and welded. All non-destructive testing and machining complete except for machining of final leg length. IV.2.2.2 Piecemark 57, No. 1 ring formed and welded and all non-destructive testing complete, no cladding or nozzle installation. Safe ends attached to nozzles MK7, 8, and 19. Nozzles clad, machined, and all non-destructive testing complete. IV.2.2.3 Piecemark 58, No. 2 ring formed and welded and all non-destructive testing complete. Not clad. IV.2.2.4 Piecemark 59, No. 3 ring, formed and welded and all non-destructive testing complete. No cladding or nozzle installation. Safe ends attached to nozzles MK12 and 13. Nozzles clad, machined, and all non-destructive testing complete. IV.2.2.5 Piecemark 16, No. 4 ring formed and welded and all non-destructive testing complete. No cladding or nozzle installation. APPENDIX K K.IV-3 REV. 21, APRIL 2007
PBAPS UFSAR Safe ends attached to nozzles MK10, 11, and 12. Nozzles clad, machined, and all non-destructive testing complete. IV.2.2.6 Piecemark 60, No. 5 ring formed and welded and all non-destructive testing complete. No cladding or nozzle installation. Safe ends attached to nozzles MK12 and 14. Nozzles clad, machined, and all non-destructive testing complete. IV.2.2.7 Piecemark 48 vessel flange. Ninety-two stud holes rough bored and all non-destructive testing complete. Not clad. IV.2.2.8 Piecemark 201 IV.2.2.8.1 Closure head flange MK209 IV.2.2.8.2 Closure head torus segments MK202, formed and all non-destructive testing complete. IV.2.2.8.3 Closure head dome MK201, formed, O.D. turned, and material certified after quench and temper. IV.2.2.8.4 Piecemarks 201, 204, 205, 206, and 207. Nozzles with safe ends, machined, and non-destructive testing complete. Lifting lugs, flanges, and gaskets. IV.2.2.9 Equipment and Tools (not piecemark items)
- 1. Ninety-two studs, nuts, bushings, washer sets, and taper pins.
- 2. Ninety-two bottom inserts, top inserts, and bottoming sleeves.
- 3. Thermal sleeves as required for recirculation inlet and feedwater nozzles.
- 4. Refueling bellows lower ring segments, upper ring segments, and base ring, formed and all non-destructive testing complete.
- 5. Nozzle shipping covers for 2296, all brackets and attachments both internal and external for 2297, two sets of new Inconel "O" rings with minimum of 50 "O" ring seal retainer clips and fasteners.
IV.3 Records and Documentation The following is a list of records and documents delivered by B&W to CB&I. APPENDIX K K.IV-4 REV. 21, APRIL 2007
PBAPS UFSAR IV.3.1 Quality Control Records
- 1. ASME Partial Data Reports (signed by the appropriate Code Inspector).
- 2. "As-built" drawings of the vessel components.
- 3. Chemistry of the cladding.
- 4. Maps of "recordable" ultrasonic indications as detected in shell plates after hot forming.
- 5. Contract Variation Notices.
- 6. Chemical and physical properties of materials as shown on Material Test Reports.
- 7. Thermal history of materials, including certified graphic depiction of furnace charts.
IV.3.2 B&W Reactor Vessel Design Drawings IV.3.3 B&W Welding Procedures and Specifications IV.3.4 B&W Non-Destructive Testing Procedures APPENDIX K K.IV-5 REV. 21, APRIL 2007
PBAPS UFSAR EXHIBIT V - SEISMIC ANALYSIS OF REACTOR VESSEL V.1 ABSTRACT AND RESULTS The maximum seismic shears and moments in the Peach Bottom reactor pressure vessel and vessel internals due to the maximum credible earthquake (MCE) have been determined. The maximum credible earthquake response spectra used in this analysis is shown in Figure C.3.2. The results for those components that develop significant seismic loads are given in the following table: SIGNIFICANT SEISMIC SHEARS AND MOMENTS MCE RPV Support Skirt Moment 6,320 kip-ft RPV Support Skirt Shear 205 kips Fuel Assy. Moment 0.89 kip-ft/assy CRD Housing Moment 2.97 kip-ft each Total Fuel Shear on Top Guide 133 kips Shroud Support Moment 6,219 kip-ft Shroud Support Shear 287 kips RPV Stabilizer Force 267 kips V.2 ANALYSIS V.2.1 Mathematical Model The Peach Bottom system was modeled with 40 discrete lumped masses connected by massless springs. Relatively lightweight components such as the jet pumps, steam dryer, in-core housing, in-core guide tube, and spargers were not modeled separately; only their mass effects being accounted for. This simplification is made to limit the complexity of the analysis and is valid since the dynamic effects of these components on the rest of the system is slight. Should the seismic response of these components be of interest, the response of the reactor vessel at their points of attachment to the vessel would then be used as input forcing functions. Because of the solidity of the site foundation, the reactor building was modeled as fixed at its base. V.2.2 Mass and Elastic Properties To develop equivalent lumped masses, the system components are visualized as consisting of vertical segments. The lumped mass, located in general at the center of mass of each segment, represents the sum of: (1) the segment mass, (2) components in the segment not modeled separately (such as the dryer mass being lumped into a vessel mass), (3) the enclosed water mass effects discussed in detail in paragraph V.2.3. APPENDIX K K.V-1 REV. 21, APRIL 2007
PBAPS UFSAR The system flexibility matrix is determined by using the elastic properties of cross-sectional moment of inertia, shear area, length, Young's Modulus, and Poisson's ratio for each component segment between lumped masses to derive individual segment matrices which are then combined as discussed in paragraph V.2.6. Shearing deformations are accounted for in the derivation of the segment flexibility coefficients. V.2.3 Hydrodynamic Mass In order to account for the effects of the core cooling water on the dynamic characteristics of the system, hydrodynamic mass (or apparent mass) terms have been included in the system mass matrix. The hydrodynamic mass manifests itself as a dynamic coupling between the real masses and therefore appears in the mass matrix at diagonal as well as off-diagonal locations. These hydrodynamic masses are added algebraically to the lumped metal masses to form the total mass matrix. V.2.4 Natural Frequencies and Mode Shapes The overall system flexibility matrix is derived by using the matrix force method which is described in detail in reference 1. Given the flexibility matrix, f, the stiffness matrix, K, of the system can be found by inversion. From the mass matrix, (non-diagonal in this case), and the stiffness matrix, the undamped natural frequencies and normalized mode shapes are computed. V.2.5 Equivalent Modal Damping Damping coefficients for individual component elements are given as follows: MCE Coefficient Component (% Critical Damping) Reactor Vessel 2.0 Vessel Support Skirt 2.0 Shroud 2.0 Shroud Head and Separators 2.0 Fuel 7.0 Control Rod Guide Tubes 2.0 CRD Housings 3.5 Shield and Pedestal 5.0 Reactor Building 5.0 Modal damping values are then computed for each mode on the basis of modal-displacement and mass. APPENDIX K K.V-2 REV. 21, APRIL 2007
PBAPS UFSAR V.2.6 Earthquake Response The equation of motion of the system in matrix form is as follows: M X + Y + C X + K X = O (V.1) where: M = mass matrix, n x n (this includes the hydro-dynamic mass) X = column vector of displacement relative to ground (n x 1) C = damping matrix (n x n) K = stiffness matrix (n x n) Y = column vector of ground accelerations (n x 1) ( ) = second derivative with respect to time (*) = first derivative with respect to time Upon removing the ground acceleration vector to the right side of Equation (V.1), the equation reduces to the classical form: M X + CX + K X = M Y (V.2) To uncouple equation (V.2) set X = q, = modal matrix (V.3) Equation (V.2) then becomes M q + C q + K q = M Y (V.4) Pre-multiplying by the transpose of and using the orthogonality conditions: T M q + T C q + T K q = T M Y (V.5) q + T C q + T Kq = T M Y (V.6) This procedure for uncoupling the equation of motion by using the modal matrix of the undamped system requires that damping in the system be small. It is further assumed that the damping matrix C is such that TC is a diagonal matrix. The elements of this diagonal matrix are the modal damping values. With these assumptions, Equation (V.6) may be written as: APPENDIX K K.V-3 REV. 21, APRIL 2007
PBAPS UFSAR qi + 2ii qi + i 2qi = S Ug (+) (V.7) i = 1, 2, -----N where: th i = damping ratio for the i mode expressed as percent of critical damping th i = i natural angular frequencies of the system th TMI Si = modal participation factor for the i mode = i u Ug = earthquake ground acceleration time history T= th i transpose of the i mode shape Iu = (n x 1) column vector whose elements are all unity The system of one degree of freedom equation represented by Equation (V.7) subjected to the initial conditions qi (0) = 0 qi (0) = 0 determines the modal response qi (+). Using Equation (V.7), the maximum seismic modal response (displacement, acceleration, or load response) can be determined for each natural frequency of interest from the response spectrum curve. Response spectrum curves are essentially plots of the maximum responses of single-degrees-of-freedom systems described by Equation (V.7) with Si = 1.0 against various natural periods or frequencies. Having found the maximum modal responses, qi, i = l, ...m, the maximum physical th displacement for the i mode is given by: X = Si q (V.8) i i i where: APPENDIX K K.V-4 REV. 21, APRIL 2007
PBAPS UFSAR X i = X 1i i = 1i X 2i 2i O O X ni Ni As shown in reference 2, the maximum physical response for each mass can be taken to be the square root of the sums of the squares of each of the maximum responses for each mode; i.e., 1/2 m _ 2 (xi ) max X ij j = 1 i = 1,. . . , N th Similarly, the maximum load response for the i mode if found from: L = S X i i where: L 1i Li = L 2i Where n is the number of rows in the S matrix O L ni S = Stress or load matrix APPENDIX K K.V-5 REV. 21, APRIL 2007
PBAPS UFSAR The maximum load response is again taken to be the square root of the sums of the squares of each of the maximum responses for each mode; i.e., m _ 2 1/ 2 (Li ) max = L ij j = 1 i = 1, . . . n APPENDIX K K.V-6 REV. 21, APRIL 2007
PBAPS UFSAR K.V SEISMIC ANALYSIS OF REACTOR VESSEL REFERENCES
- 1. Leckie, F. A. and Pestel, E. C., Matrix Methods in Elasto-Mechanics, McGraw-Hill, 1963.
- 2. Clough, R. W. "Earthquake Analysis by Response Spectrum Superposition," Bull, Seismological Society of America, Vol 52, No. 3, July, 1962.
APPENDIX K K.V-7 REV. 21, APRIL 2007
PBAPS UFSAR PBAPS PEACH BOT7OM UNITS 2 EXHIBIT VI
SUMMARY
TECHNICAL REPORT REACTOR VESSEL OVERPRESSURE PROTECTION FOR EXTENDED POWER UPRATE OCTOBER 2011 GE HITACHI NUCLEAR ENERGY APPENDIX K K.VI-1 REV. 26, APRIL 2017
PBAPS UFSAR Reactor Vessel Overpressure Protection for Extended Power Uprate The overpressure protection analysis for reactor vessel was performed for EPU to show compliance with the requirements of Article 9 of ASME Boiler and Pressure Vessel Code, Section Ill. The analysis is documented in GEH Report 26A8321 (G-080-VC-413), and it is included in Appendix K as Exhibit VI. The EPU analysis is based on the following operating conditions (Ref. NEDC-33566P, Figure 1-3): Power - 4030 MWt (102% of rated thermal power) Vessel dome pressure - 1053 psig Steam flow-16.55 x 106 lbm/hr (102.34% of rated steam flow rate) The analysis credits 10 of 11 safety relief valves, and 3 of 3 spring safety valves (including a new safety valve added for EPU), all with a set pressure tolerance of +/- 3%. The worst-case peak pressure at the bottom of the RPV is 1335 psig which is below the ASME Code limit of 1375 psig (RPV design pressure of 1250 psig X 1.10). See Exhibit VI for additional details. APPENDIX K K.VI-2 REV. 26, APRIL 2017
PBAPS UFSAR APPENDIX K K.VI-3 REV. 26, APRIL 2017
PBAPS UFSAR APPENDIX K K.VI-4 REV. 26, APRIL 2017
PBAPS UFSAR ABSTRACT This report provides sufficient information and documentation to show compliance with all requirements of Article 9 of ASME Boiler and Pressure Vessel Code - Section III, Nuclear Vessels, 1965 Edition with Addenda to and including Winter 1965, in the area of the reactor vessel overpressure protection design of the Peach Bottom Units 2 nuclear pressure vessels for the Extended Power Uprate (EPU) condition. APPENDIX K K.VI-5 REV. 26, APRIL 2017
PBAPS UFSAR TABLE OF CONTENTS
1.0 INTRODUCTION
2.0 DESIGN BASIS 3.0 METHOD OF ANALYSIS 4.0 SYSTEM DESIGN 5.0 OVERPRESSURE PROTECTION EVALUATION 6.0 SAFETY/RELIEF AND SPRING SAFETY VALVE CHARACTERISTICS
7.0 CONCLUSION
8.0 REFERENCES
LIST OF ILLUSTRATIONS Figure 1 Typical Dual Safety/Relief Valve Capacity Characteristics Figure 2 Typical Spring Safety Valve Capacity Characteristics Figure 3 RPV Bottom Head Pressure versus Time for MSIV Closure with Flux SCRAM Overpressure Protection Transient Figure 4 Safety Valve Location Schematic Plan View APPENDIX K K.VI-6 REV. 26, APRIL 2017
PBAPS UFSAR
1.0 INTRODUCTION
1.1 The vessel overpressure protection system is designed to satisfy the requirements of Section III, Nuclear Vessels, of the ASME Boiler and Pressure Vessel Code (Reference 8.1). The general requirements for protection against overpressure as given in Article 9 of Section III of the Code recognize that reactor vessel overpressure protection is one function of the reactor protective systems and allows the integration of pressure relief devices with the protective systems of the nuclear reactor. Hence, the SCRAM protective system is a complimentary pressure protection device. GEH, however, provides analyses, which take credit only for reactor protective signals, which are indirectly derived (high neutron flux signal). The NRC has also adopted the ASME codes as part of their requirements in the Code of Federal Regulations (10CFR50.55a). This Design Report demonstrates code compliance for the EPU condition. 2.0 DESIGN BASIS 2.1 Safety Valve Capacity The capacity of the Safety/Relief Valves (SRVs) and Spring Safety Valves (SSV) are sized to limit the primary system pressure, including transients, to the requirements of the ASME Boiler and Pressure Vessel Code, Section Ill, Nuclear Vessels. The essential ASME requirements, which are all met by this analysis, are: 2.1.1 It is recognized that the protection of vessels in a nuclear power plant is dependent upon many protective systems to relieve or terminate pressure transients. Installation of pressure relieving devices may not independently provide complete protection. 2.1.2 The safety/relief valve and spring safety valve sizing evaluation considers operation of the SCRAM protective system which may be tripped by any one of the three sources; i.e., a direct, flux, or pressure signal. The direct SCRAM signal is derived from position switches mounted on the main steam line isolation valves or the turbine stop valves. The position switches are actuated when the respective valves are closing and following 15% travel of full stroke. The pressure signal SCRAM is derived from pressure switches mounted on the turbine control valve hydraulic actuation system. The pressure switches are actuated when a fast closure of the control valves is initiated. However, for the design basis, the safety/relief valve and spring safety valve evaluation does not assume credit for the APPENDIX K K.VI-7 REV. 26, APRIL 2017
PBAPS UFSAR direct or low turbine control valve hydraulic pressure SCRAM, only for the indirect high neutron flux SCRAM. Credit is taken for the 10 of 11 available dual purpose SRVs in their ASME code qualified mode of safety operation and 3 of 3 available SSVs (Reference 8.3). 2.1.3 The rated capacity of the pressure relieving devices shall be sufficient to prevent a rise in pressure within the protected vessel of more than 110% of the design pressure (1.10 x 1250 psig). Full account is taken of the pressure drop on both the inlet and discharge sides of the valves. The spring safety valves discharge directly into the drywell and have no restrictions. The safety/relief valves discharge into the suppression pool through a discharge pipe from each valve which is designed to achieve sonic flow conditions through the valve, thus providing flow independence to discharge piping losses. 2.1.4 The nominal pressure setting of at least one safety valve connected to any vessel or system shall not be greater than a pressure at the safety valves corresponding to the design pressure (1250 psig) anywhere in the protected vessel. 3.0 METHOD OF ANALYSIS 3.1 To design the overpressure protection for the nuclear boiler system, extensive analytical models representing all essential dynamic characteristics of the associated systems are simulated with an approved model. These models include the hydrodynamics of the flow loops, the reactor kinetics, the thermal characteristics of the fuel and its transfer of heat to the coolant, and all the principal controller features (such as, feedwater flow, recirculation flow, reactor water level, pressure, and load demand). These are represented with all their principal non-linear features in models that have evolved through extensive experience and favorable comparison of analysis with actual BWR test data. 3.2 A detailed description of the model referenced in Paragraph 8.2 is documented as a licensing topical report. Included within this model, then, are components of the reactor vessel pressure protection system, the system which is the subject of this report. Both dual safety/relief valves and spring safety valves are simulated in the non-linear representation, and the model thereby allows full investigation of the various valve response time, valve capacity, and actuation set points that are available in applicable hardware systems. APPENDIX K K.VI-8 REV. 26, APRIL 2017
PBAPS UFSAR 3.3 The capacity characteristics as modeled are represented in Figures 1 and 2 for both the safety/relief valve and the spring safety valve types. 4.0 SYSTEM DESIGN 4.1 The overpressure protection analysis is based upon the operating conditions, plant configuration and design parameters in Paragraphs 4.2 thru 4.7. 4.2 Operating Conditions Operating Power - 4030 MWt (102 percent of reactor rated power) Vessel Dome Pressure - 1053 psig Steamflow - 16.550 x 106 lb/hr (102.34 percent of reactor rated steam flow) The specified operating conditions are the most severe with respect to overpressure transient response because the maximum stored energy exists at these conditions. At the lower power conditions the transient would be less severe. 4.3 Transients. The overpressure protection system must accommodate the most severe pressurization transient. There are two major transients, the closure of all main steam line isolation valves and a turbine/generator trip (with a failure of the turbine steam bypass system valves to open) that represent the most severe abnormal operational transients resulting in a nuclear system pressure rise. The evaluation of transient behavior with final plant configuration has shown that the main steam line isolation valve closure is slightly more severe when credit is taken only for indirect derived SCRAMS, therefore, it is used as the overpressure protection basis event. 4.4 Scram
- a. Scram reactivity curve for each transient analyzed is calculated within the ODYN computer program. (Reference 8.2)
- b. Control rod drive scram motion APPENDIX K K.VI-9 REV. 26, APRIL 2017
PBAPS UFSAR Rod Position (% insertion) Time (seconds) 0 0.050 + 0.200 = 0.250 5 0.050 + 0.490 = 0.540 20 0.050 + 0.900 = 0.950 50 0.050 + 2.000 = 2.050 90 0.050 + 3.500 = 3.550 100 0.050 + 3.875 = 3.925 4.5 Safety/Relief Valve Transient Analysis Specifications 4.5.1 SRV opening spring set pressures Quantity Opening spring set pressure (psig) 4 1135 4 1145 3 1155 4.5.2 SRV opening spring set pressure tolerance: +/-3% (Reference 8.4) 4.5.3 SRVs assumed out of service: 1 (10 of 11 operable) (Reference 8.3) 4.6 Spring Safety Valve Transient Analysis Specifications 4.6.l SSV opening spring set pressure Quantity Opening spring set pressure (psig) 3 1260 4.6.2 SSV opening spring set pressure tolerance: +/-3% (Reference 8.4) 4.6.3 SSVs assumed out of service: 0 (3 of 3 operable) (Reference 8.3) 4.7 Safety/Relief Valve and Spring Safety Valve Capacity Sizing of the safety/relief valve and spring safety valve is based on establishing an adequate margin from the peak vessel pressure to the vessel code limit (1375 psig) in response to the reference transient. 5.0 OVERPRESSURE PROTECTION EVALUATION 5.1 Basis APPENDIX K K.VI-10 REV. 26, APRIL 2017
PBAPS UFSAR 5.1.1 The safety/relief valve and spring safety valve capacity required for overpressure protection is determined from the minimum capacity which will provide an adequate margin between the peak vessel pressure and the vessel code limit (1375 psig) in response to the MSIV closure-flux SCRAM event. The combination of safety/relief valves and spring safety valves, which provide a total capacity equal to or greater than the minimum required capacity, constitutes the minimum safety/relief valve and spring safety valve requirement for overpressure protection. 5.1.2 The MSIV closure-flux SCRAM event is evaluated with respect to the ASME vessel code limit (1375 psig) to demonstrate the overpressure protection capability of the safety/relief valve system at the highest level of indirect SCRAM. The MSIV closure-flux SCRAM is the limiting event for the overpressure protection evaluation. 5.2 Evaluation of Analysis Results 5.2.1 ASME Code Requirements 5.2.1.l The design basis transient with respect to ASME code requirements is the MSIV closure where credit is not taken for direct SCRAM, only for the indirect high neutron flux SCRAM. The time response of the reactor pressure vessel (RPV) pressure to the MSIV closure with flux SCRAM transient is illustrated in Figure 3. This shows that the pressure at the bottom of the RPV exceeds 1250 psig for about 5 seconds with a peak pressure of 1335 psig (Reference 8.3). The change in temperature due to the pressure rise is not long enough to transfer any appreciable amount of heat into the RPV metal that was at a temperature well below 575°F at the start of the transient. 6.0 SAFETY/RELIEF AND SPRING SAFETY VALVE CHARACTERISTICS 6.1 Safety/Relief Valve Description 6.l.l The safety/relief valves were manufactured by Target Rock Corporation. They comply with ASME III, 1968 Edition, Paragraph N-91l.4(a) of Article 9 as safety relief valves operated by pilot devices.
- 6.1.2 Quantities, setpoints and associated capacities are as follows:
APPENDIX K K.VI-11 REV. 26, APRIL 2017
PBAPS UFSAR Opening Minimum Reclosing ASME Rated Capacity at 103 Setpoint Pressure percent of Set Pressure Quantity psig psig (lbm/hr minimum)* 4 1135 1101 840,209 4 1145 1111 847,520 3 1155 1120 854,830
- Based on ASME certified capacity of 800,000 lbm/hr at a reference set pressure of 1080 psig.
6.2 Spring Safety Valve Description 6.2.1 The SSVs are spring-loaded safety valves. These valves were manufactured by Dresser. They comply with ASME Ill, 1968 Edition, Section N-911 of Article 9 for spring-loaded safety valves. 6.2.2 Quantities, setpoints and associated capacities are as follows: Opening Minimum Reclosing ASME Rated Capacity at 103 Setpoint Pressure percent of Set Pressure Quantity psig psig (lbm/hr minimum)* 3 1260 1222 948,020
- Based on ASME certified capacity of 925,700 lbm/hr at a reference set pressure of 1230 psig.
6.3 Schematic Arrangement The schematic arrangement of the SRVs and SSVs is shown in Figure 4.
7.0 CONCLUSION
Safety requirements have long demanded very high reliability in the reactor SCRAM functions. Recognition of this reliability as being completely adequate justification for these functions to contribute to vessel pressure protection is reflected in the new Section III Code provisions. Actual design practice very conservatively applies the new code provisions that results in margins even beyond those necessary to satisfy code limits, which further enhances the reliability of vessel pressure protection. The design basis for sizing safety/relief valves and spring safety valves with indirect SCRAM credit is technically sound APPENDIX K K.VI.A-12 REV. 26, APRIL 2017
PBAPS UFSAR and a most realistic approach. It is allowed under Section III of the ASME Boiler and Pressure Vessel Code, which has been adopted by GEH in the design of the Peach Bottom Units 2 and 3 Boiling Water Reactor.
8.0 REFERENCES
8.1 American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code; Section III, Nuclear Vessels 8.2 Licensing Topical Report, "Qualification of the One-Dimensional Core Transient Model (ODYN) for Boiling Water Reactors," NED0-24154-A, Vols. 1 - 3, February 1986, NEDC-24154P-A Supplement 1, Volume 4, February 2000 8.3 0000-0100-9751-RO, "Peach Bottom Units 2 & 3, Extended Power Uprate, Task T0900: Transient Analysis", February 201l 8.4 Design Input Request, Peach Bottom Units 2 & 3, EPU T0900, OPL-3 Transient Analysis, Tracking Number EPU-T0900-3-0, 05/14/2010 (DRF 0000-0100-9744) APPENDIX K K.VI.A-13 REV. 26, APRIL 2017
PBAPS UFSAR APPENDIX K K.VI.A-14 REV. 26, APRIL 2017
PBAPS UFSAR APPENDIX K K.VI-15 REV. 26, APRIL 2017
PBAPS UFSAR APPENDIX K K.VI-16 REV. 26, APRIL 2017
PBAPS UFSAR APPENDIX K K.VI-17 REV. 26, APRIL 2017
PBAPS UFSAR EXHIBIT VI.B Deleted APPENDIX K K.VI.B-1 REV. 26, APRIL 2017
EXHIBIT VII - REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM The surveillance program for Peach Bottom Units 2 and 3 is the standard surveillance program described in the GE-APED Topical Report, NEDO-10115, "Mechanical Property Surveillance of General Electric BWR Vessels." This surveillance program does not conform to ASTM E-185-66, "Recommended Practice for Surveillance Tests on Structural Materials in Nuclear Reactors," or its revision ASTM E-185-70, "Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels." The following is a comparison of the surveillance program to the applicable portions of ASTM E-185-70 (paragraph numbers correspond to paragraph numbers in ASTM E-185-70): 3.1 Test Material The test specimens are taken from a plate sample of the same heat as the wall plates in the reactor core region. The sample plate is welded with the same material and by the same procedure as a butt weld in the core region. 3.1.1 Fabrication History The test panel represents all of the fabrication processes to which the vessel plate is subjected except for forming. Since the vessel plate was quenched and tempered after forming, the forming operation has no effect on the part properties. 3.1.2 Test Specimens Test specimens are taken from the test plate to represent the base metal, heat-affected zone (HAZ), and weld material. The plate material is not tested before selection since this pretesting would impose a large material and test cost on the surveillance program. The weld procedures and materials duplicate actual fabrication. The specimens are located vertically in the highest fluence area. Circumferentially, the specimens are located where access dictates, not necessarily at the highest fluence. One extra base line set of specimens has been retained as spares. All specimens are identified and complete documentation is available.
3.1.3 Chemical Composition Since specimens are taken from each heat of actual plate material, chemical analysis of this material is on record. 3.2 Type of Specimens The surveillance test specimens conform to ASTM E-185-70 requirements, except that the HAZ impacts have the notch at the fusion line instead of 1/32 in away. The weld material tensile specimen is oriented parallel to the weld. All other specimens are oriented parallel to the plate rolling direction, transverse to the weld. The impact notch is perpendicular to the plate surface. 3.3 Number of Specimens The following sets of test specimens have been retained. There are equal numbers of base metal, HAZ's and weld specimens: Impact Tensile Base Line 36 9 Irradiated Sets 1 36 6 2 24 6 3 24 6 Spares 36 9 TOTAL 156 36 The program is based on 12 impacts per test set since experience indicates that this quantity is adequate. 3.4 Correlation Monitors Correlation monitors are not used since this is a surveillance program, not a research and development program. 4.1 Location of Specimens The specimens are located as close as possible to the zone of highest fluence. The test plate duplicates the vessel material, and the specimens are placed as close
as practical to the vessel wall to best duplicate the vessel wall conditions. 4.2 Accelerated or Reduced Irradiation Accelerated exposures are not used. 4.3 Thermal Control Specimens Themal controls were part of earlier test programs and have discontinued. 4.4 Test Capsules The BWR is a constant temperature system, so no monitoring is employed. The specimens are hermetically sealed in an inert gas environment in a thin wall stainless steel capsule which is not buoyant and does not present any problems in removing the irradiated capsules. All specimens are encapsulated in tight containers, and tensile specimens have aluminum spacers to keep gamma heating as close as possible to vessel wall conditions. The vessel design does not have provision for later insertion of surveillance material. Sample containers can be withdrawn but not replaced. 4.5 Corrosion-Resistant Reactor Vessel Materials The vessel wall and all test specimens are low alloy ferritic steel. 4.6 Specimen Withdrawal The radiation levels in a BWR are expected to have no significant effect on the vessel wall, even for 40 yr of service. The specimens can be removed during any plant shutdown if required. The specimen withdraw included three capsules of irradiated specimens as listed in paragraph 3.3. A flux capsule installed in the vessel belt line region was removed at the end of 1 yr of commercial power operation and a plot established of integrated neutron flux as determined by the flux wires versus megawatts thermal. Using a linear interpolation, the year that the vessel reaches the threshold of 1017 nvt is estimated and the removal of the first capsule established (expected at approximately one-fourth of design service life). The withdrawn specimens are tested and compared with original material properties to ensure that no
unexpected changes have occurred. The remaining withdraw schedule will be to remove the second capsule for specimen testing and comparison at three-fourths of design service life while retaining the third capsule for standby. Note: This is a comparison of GE NEDO-10115 and ASTM E 185-70 only. See UFSAR Section 4.2.6 for the current approved specimen withdrawal schedule. The base material for the reactor pressure vessel forging, beltline and plate, were drop weight and Charpy V-notch tested. Typical data obtained are as follows (original data available at vendor's plant): Specimen Test Identification Test Temperature Requirement Data No breaks PB-2 top head Drop weight 20°F No break -4 specimens Flange (ABU-134) charpy 10°F 20 ft-lb avg. 58 57 78 6 96 speci-86 mens 82 No break PB-3 feedwater Drop weight 50°F No break -2 specimens noxxles (AV-1909, charpy 10°F 20 ft-lb avg. 47 7K-6126A) 86 90 6 116 speci-91 mens 84 No break PB-3 belt line Drop weight 20°F No break -4 specimens material charpy 10°F 30 ft-lb vg. 44 (C2773-2) 44 84 6 70 speci-50 mens 46 No break PB-3 bottom head Drop weight 50° F No break -2 specimens dollar plat charpy 40°F 30 ft-lb avg. 55 (C3354-2) 66 70 6 74 speci-65 mens 62 5.1 Significance Dosimeters are a part of the specimens to measure flux. Irradiation induced temperature is of no consequence and not measured. Evaluation of the radiation spectrum is a development, not a surveillance function.
5.2 Neutron Flux Dosimeters Iron, nickel with known cobalt content, and copper are used as flux monitors. One of each is included in each impact specimen capsule. 6.7 Method 7.1 The General Electric recommended test methods are not in complete conformance with ASTM E-184. 7.2.1 The surveillance program and test interpretation are based on 30 ft-lb Charpy impact. This data will indicate significant changes in NDT temperature, if any should occur.}}