ML19344E554
| ML19344E554 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 07/31/1980 |
| From: | Anderson W, Atteridge D, Olson N Battelle Memorial Institute, PACIFIC NORTHWEST NATION |
| To: | |
| References | |
| NUDOCS 8009020219 | |
| Download: ML19344E554 (60) | |
Text
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Initial Draft SAFETY EVALUATION REPORT ON METALLURGY REVIEW COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1, 2 TEXAS UTILITIES GENERATING COMPANY Dockets Nos 50 J45 and 50 J46 d
W. E. Anderson D. G. Atteridge N. J. Olson Project Leader C. Pavloff - Task Leader 1
July, 1980 SATTELLE Pacific Northwest Laboratories Richland, Wasnington 99352 THIS DOCUMENT CONTAINS 8~009020 '1.\\$
POOR QUAUTY PAGES
- w--
Initial Draft SAFETY EVALUATION REPORT ON METALLURGY REVIEW CCMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 TEXAS UTILITIES GENERATING COMPANY Docket = 50-445 and 50-446 Battelle Pacific Northwest Laboratories
SUMMARY
The Safety Evaluation Report on the Metallurgy Review has been prepared along tne guidelines defined in the Introduction, and the najor issues from Appendix A were incorporated into the text. A summary of the major issues (along with the referenced Appendix A ouestion numbers) is as follows:
Possible use of austenitic staialess steel with yield strength greater than 90,000 psi in the control rod mechanism.
[1]
Lack of materials definition such as ASME Code specification and heat treatment.
[1,2,3,4,5,6,9,15,19]
Prevent deminerali:er resins from entering cooling stream.
[7]
Post weld hea treatment of clad ferritic steels could not be evaluated.
[8]
Comoliance af some Westinghouse specification with Regulatory guides could not be evaluated [10,11,12]
i
Evaluation of cold work on Inconel 600 and austenitic stainless steel tubing for the steam generators are not addressed [13,16]
Lack of references in steam generator denting.
[14]
Concern about low temper on SA-194 Grade 2H nuts.
[17]
Effect of borated water on ESF materials could not be evaluated.
[18]
Errors in material listing.
[20,21,22]
ii
CONTENTS
SUMMARY
i INTRODUCTION iii REACTOR...............................
1 Control Rod System Structural Materials 1
Reactor Internals Materials 3
REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 4
Material Specifications and Compatibility with Reactor Coolant.
4 Fabrication and Processing of Ferritic Materials.........
6 Fabrication and Processing of Austenitic Stainless Steels 7
STEAM GENERATOR MATERIALS.....................
8 ENGINEERED SAFETY FEATURES 9
Enginee red Safety Features....................
9 STEAM AND POWER CONVERSION SYSTEM 11 Steam and Feedwater System Materials...............
11 REFERENCES 13 APPENDIX A - Comanche Peak Metallurgy Review Issues......... A-1 APPENDIX 3 - Check Lists for Standard Review Plans B-1 APPENDIX C - List of Materials / Components Reviewed C-1 iii
INTRODUCTION The philosophy employed in the review of the Comanche Peak FSAR was that of a design audit rather than a design review. This approach was im-piemented after the meeting with NRC Staff in December,1979.
Our initial draft submittal employs the recommended phrases from the applicable Standard Review Procedures that were used as references to indicate conformance, except for qualifications due to major issues.
These qualifications are underlined and referenced in brackets to Appen-dix A for exolanations. All major issues are listed in the Summary.
It is assumed that NRC Staff will review these issues and determine their applicability to Ccmanche Peak.
Those issues that may be deleted, due to information not at our disposal, misunderstandings, or established pre-cedents, will be deleted by NRC Staff, since we have employed the SRP's "to the letter." For those issues which can not be resolved in this manner, it is expected that technical interaction with the applicant will be re-quired.
The standard, final, no issue, SER is the text with all underlined words re-moved or changed to be positive rather than to qualify in a negative sense.
Standard Review Plan conformance is noted, where possible, in Appendix B and the. list of materials and components reviewed is in Appendix C.
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Initial Draft SAFETY EVALUATION REPORT ON METALLURGY REVIEW CCMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 TEXAS UTILITIES GENERATING COMPANY
. Docket Nos. 50-445 and 50-446 REACTOR Control Rod System Structural Materials The mecnanical properties of structural materials selected for the con-trol-rod system components exposed to the reactor coolant satisfy Appendix I of Section III of the ASME Boiler and Pressure Vessel Code, or Part A of Section II of the ASME Code, but may not satisfy the NRC Position that the
[1]
yield strength 'of cold worked austenitic stainless should not exceed 90,000 psi.
Some materials have not been identified by the ASME Code.
[2,4]
The requirements and controls on welding processes provide reasonable assurance that no deleterious microfissuring or hot cracking will be present during welding of austenitic stainless steel components. All weld filler metal will be of selected composition to produce welds with at least SP, delta ' ferrite. Tests and examinations, in accordance with Sec-tion III of the ASME Code and the recommendaticqs of Regulatory Guide 1.31
" Control of Ferrite Content in Stainless Steel Weld Metal" will be requirec to assure delta ferrite levels are met.
r.
I The centrol imposed on compositions, heat treatments, welding processes and cooling rates of stainless steels are in conformance with the recom-mendations of Regulatory _ Guide 1.44 " Control of the Use of Sensitized Stainless Steel."
_ Fabrication of structures and components performed in accordance with these recommendations provide added assurance that stress corrosion cracking will not occur and that the probability of loss of structural integrity is minimized.
The compatibility of all materials used in the control rod system in con-tact with the. reactor coolant satisfies the criteria for Articles NB-2160 and NB-3120 of Section III of the ASME Code.
It can not be determined
[3]
if both martensitic and precipitation-hardening stainless steels have been given tempering or aging treatment in accordance with NRC positions.
Conformance with the Codes and Regulatory Guides indicated above, and with the NRC Positions on the allowable maximum yield strength of cold worked austenitic stainless steel and minimum tempering or aging temperatures of martensitic and precipitation-hardened stainless steels, constitues an acceptable basis for meeting the requirements of NRC General Design Cri-terion 26, Appendix A of 10 CFR Part 50.
L-
Reactor Internals Materials The, materials for construction of components of the reactor internals have been identified by specification and found to be in conformance with the requirements of Section III of the ASME Code.
The materials for reactor internals exposed to the reactor coolant have been identified anc all of the materials are compatible with the expected environment, as proven by extensive testing and satisfactory performance.
General corrosion on all materials is expected to be negligible.
The controls imposed on reactor coolant chemistry provide reasonable assurance that the reactor will. be adequately protected during operation from conditions which could lead to stress corrosion of the materials and loss of component structural integrity.
The welding controls imposed upon components constructed of austenitic stainless steel as used in the reactor internals satisfy the requirements of the ASME Code,Section III, and the recommendations of Regulatory Guide 1.31, " Control of Ferrite Content in Stainless Steel Weld Metal" and Regu-latory Guide 1.44, " Control of the Use of Sensitized Stainless Steel," ex-ceot for the ootional use of ASTM A-393 instead of ASTM A-262 for the verification of non-sensitization of stainless steel (R. G.1.ta-C.3).
[11]
Material selection, fabrication practices, examination procedures, and pro-tection procedures performed as stated above provide reasonable assurance that the austenitic stainless steel used for reactor internals will be in a metallurgical condition which precludes susceptibility to stress corrosion cracking during service.
.The use of materials proven to be satisfactory by actual service ex-perience ano conformance with the requirements of the ASME Code consti-tutes an acceptable basis for meeting in part the requirements of NRC General Design Criteria 1 and 14, Appendix A of 10 CFR Part 50. i
)
REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS Material Suecifications and Comoatibility with Reactor Coolant Most of the materials used.for constru: tion of components of the reactor coolant pressure boundary (RCPB) have been identified by specification and found to'be._in conformance with the requirements of Section III 'of the ASME Code.
Some materials have 'not been identified by the ASME Code.
[5,6]
The RCP3 materials of construction'that will be exposed to the reactor coolant have been identified and all of the materials are compatible with the expected environment, as proven by extensive: testing and satisfactory performance.
General carrosion except for carbon and low alloy steel will be negligible.
For these materials, conservative corrosion allowances
-have been provided for all exposed surfaces of carbon and low alloy steel in accordance with the requirements of the ASME Code,Section III. Only reflective metallic insulation is used on the RCPB.
Regulatory ' Guide 1.36
" Nonmetallic Thermal Insulation for Austenitic Stainless Steels" does not
- apply.
Further protection against corrosion problems will be provided by control of the chemical environment. The composition of the reactor coolant will-be controlled, and_the proposed maximum contaminants levels, as well as the proposed pH,- hydrogen' overpressure and boric acid concentrations, have~ been shown by tests and service experience to be adequate to protect against corrosion and stress corrosion problems.
The controls imposed on reactor coolant chemistry are in conformance with the recommendations of Regulatory Guide 1.44 " Control of Sensiti::ed Stainless Steel," and provide' reasonable assurance that the RCPB com-ponents will be adequately protected during operation from conditions that could lead to stress corrosion of the materials and loss of. structu-ral. integrity of a' component.
I
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The instrumentation and sampling provisions for minitoring reactor coolant water chemistry provide adequate capability to detect significant changes on a timely basis. The use of materials of proven performance and the conformance with the recommendations of the regulatory guides constitutes an acceptable basis for satisfying the requirements of NRC General Design Criterion 14, Appendix A of 10 CFR Part 50.
5-
Fabrication and Processino of Ferritic Materials The, controls imposed on welding preheat temperatures and weld cladding satisfy the recommendations lof Regulatory Guide 1.50 " Control of Preheat.
Temperature for Welding of Low-Alloy Steel," and Regulatory Guide 1.43
" Control of Stainless Steel Weld Cladding of Low-Alloy Steels." These recommendations provide reasonable assurance that cracking of components made from low-alloy steels will not occur during fabrication, and will minimize the possibility of subsequent cracking due to residual stress
~
being reta1ned in the weldment.
Conformance with Regulatory Guides and Codes mentioned constitutes an j
acceptable basis for meeting the requirements of NRC General Design Criteria 1 and la, Appendix A of 10 CFR Part 50.
t 4
5-i k.
Fabrication and Processino of Austenitic Stainless Steels Within the reactor coolant pressure boundary, no components of auste-nitic stainless steel have a yield strength exceeding 90,000' psi in accordance with the NRC Position.
The controls imposed upon components constructed of austenitic stain-less. steel used in the reactor coolant pressure boundary satisfy the rec-ommendations of the. ASME Code,Section III, Regulatory Guide 1.4a
" Control of the Use of Sensitized Stainless Steel" and Regulatory Guide 1.27
" Quality Assurance Requirements for Cleaning of Fluid Systems and Associatec Components of Water Cooled Nuclear Power Plants," if Westinchouse scecifi-cations are in comoliance with the accrooriate Reculatorv Guides.
[10,12]
The requirements and controls on welding processes provide reasonable assurance that no~ deleterious not cracking will be present during the
-assembly of austenitic stainless steel comconents. All weld filier metal will be of selected composition to produce welds with at least 55 delta fe rri te.
Material selection, fabrication practices, examination procedures, and pro-tection procedures performed in accordance with the reccmmendations men-tiened above, provide reasonable assurance that the austenitic stainless steel in the reactor coolant pressure boundary will be free from hot cracking (microfissures) and in a metallurgical condition wnich precluces susceptibility to-stress corrosion cracking during service. Confo rmance with the ASME Code, Regulatory Guides and NRC Positions mentioned consti-tutes an acceptable basis for meeting the recuirements of NRC General Ce-sign Criteria 1 and-14, Acpenoix A of 10 CFR Part 50.
.J.-
STEAM GENERATOR MATERIALS The materials used in Class l and Class 2 components of the steam generators were-selected and fabricated according to applicable ASME Codes, Standards.and Regulatory' Guides, constituting an acceptable basis for meeting the requirements'of General Design Criterion 1, Appendix A of 10 CFR Part 50.
The steam generator pressure retaining parts are designed and manufactured to meet the ASME Code,Section III. The on-site cleaning and cleanliness controls during t ibrication conform to the recommendation of Regulatory Guide 1.37 " Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled. Nuclear Power Plants". The con-trols placed on secondary coolant chemistry combined with conformance with approved ASME Codes and applicable Standards, Staff Positions, and Regula-tory Guides constitute an acceptable-basis for meeting in part the require-ments of General Design Criteria 14.,15 and 31, Appendix A of 10 CFR Part 50.
Discussion of ootential oroblems associated with steam cenerator tube wall dentina does not include any references.
[14] _s
.2 EMGINEERED SAFETY FEATURES Encineered Safety Features Materials-The mechanical properties of materials selected for the engineering safety features are believed to satisfy Appendix I of Section III of the ASME
[15]
Code, or Parts A, B and C of Section II of the ASME. Code, and the NRC
- Position that the yield strength of cold worked stainless steel shall be less than 90,000 psi.
The controls on the pH of the reactor containment sprays and the emer-z gency core cooling water following a postulated loss-of-coolant accident l
are adequate to ensure freedom from stress corrosion cracking of the austenitic stainless steel components and welds of the containment spray and emergency core cooling systems throughout the duration of the costu-lated accident to completion of cleanup.
The requirements and controls on welding processes provide reasonable -
. assurance that no deleterious hot cracking will be present during the assembly of austenitic stainless steel components. All weld filler metal will be of selected composition to produce welds with at least 5% delta ferri te.
Tests'and examinations will be made in accordance with the ASME Code,Section III to assure that adequate delta ferrite levels are present.
Controls imposed in the application and processing of austenitic stain-less steels for components of the engineered safety features, to avoid sensitization, satisfy recommendations of Regulatory G;:de i.44" Control of the Use of Sensitized Stainless Steel."
. Fabrication and heat-treatment practices performed in accordance with these requirements provide added assurance that stress corrosion cracking
~
will not occur during the postulated accident time interval. The control of the pH.of the sprays anc. cooling water will not give rise to unaccept-able corrosion of containment metal or:cause serious ceterioration of the
-g.
~
n containment. The controls placed on concentrations of leachable
- impurities in nonmetallic thermal insulation used on austenitic stainless steel components of the engineered safety. features are in accordance with i
Regulatory Guide 1.36 ' Nonmetallic Thermal Insulation for Austenitic Stain-less Steel."
Conformance with the Codes and Regulatory Guides mentioned above, and with the NRC Positions on the allowable maximum yield strength of cold worked austenitic stainless steel, and the minimum level of pH of can-tainment-sprays and' emergency core cooling water constitute an acceptable.
basis for meeting applicable requirements of MRC General Design Criteria 35, 38 and 41,' Appendix A of 10 CFR Part 50.
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STEAM AND POWER CCNVERSICM SYSTEM Steam-and Feedwater System Materials
.The mechanical properties of materials selected for Class 2 and Class 3.
components of the steam and feedwater systems satisfy-Appendix I of Section III of the ASME Soiler' and Pressure. Vessel Code, or Parts A, B and C of Section II of the Code.
The requirements and controls on weiding processes provide reasonable assurance that no deleterious hot cracking will be present during the assembly of austenitic stainless steel comoanents. All aeld filler metal will be of selected composition to produce welds with at least 55 delta ferrite. -Tests-and examinations in accordance with Section III of the ASME Code will be made to assure-that adequate delta ferrite levels are met.
Controls imposed in the application and processing of austenitic stainless steels satisfy the recommencations of Regulatory Guide 1.44 " Control of the Use of. Sensitized Stainless Steel."
Fabrication and heat treatment practices that will be performed in accor-dance with these requirements provide reasonable assurance that stress corrosion cracking will not occur during the design life of the plant.
The controls placed upon concentrations of leachable impurities in nonmetallic thermal insulation used on -austenitic stainless steel components of the steam and feedwater systems are in accordance with Regulatory Guide 1.35
" Nonmetallic Thermal: Insulation for Austenitic Stainless Steel."
The on-site cleaning and cleanliness controls during fabrication satisfy
^
the positions given in Regulatory Guide 1.37 " Quality Assurance Require--
ments for Cleaning of Fluid Systems and Associated Components of Water-Cooler Nuclear Power Plants."
.- L.
The precautions taken in controlling and monitoring the preheat and
-interpass temperatures during welding of carbon and low alloy steel components conform to Regulatory Guide 1.50 " Control of Preheat Tempera-ture for Welding Low-Alloy Steel."
Conformance.with the Codes, Standards, Regulatory Guides, and NRC Posi-
'tions mentioned constitutes an acceptable basis for assuring the integrity of steam and feedwater system materials, and for meeting the requirements of NRC General Design Criterion 1, Appendix A of 10 CFR Part 50..-.
REFERENCES General Federal Register'10 CFR Part 50, Appendix A " General Design Criteria for Nuclear Power Plants," September 1,1973.
Material Soecifications ASME Boiler and Pressure Vessel Code,Section III,1974 Edition:
a) - Paragrapn NS-2121: Permitted Material Specifications b) Paragraph NB-2122:.Specia' Requirements Conflicting with Permi c'd Material Specifications ASME Soiler and Pressure Vessel Code, Caction II, 1974 Edition.
Chemistry of Reactor Coolant
.NRC Regulatory Guide 1.44 " Control of the Use of Sensitized Stainless Steel," May 1973.
Ferritic Stael ASME Boiler and Pressure Vessel Code,Section III, 1974 Edition.
J NRC Regulatory Guide 1.50 " Control of Preheat Temperature for Welding of Low-Alloy Steel, May 1973.
i NRC Regulatory Guide 1.37 " Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants,
5 March 16,.1973.
1
)
,-n
-r y
REFERENCES t.
Austenitic Stainless Steel NRC Regulatory Guide 1.31- " Control of Ferrite Content in -Stainless Steel Weld Metal," Revision 3, April 1978.
NRC Regulatory Guide 1.36 " Nonmetallic Thermal Insulation for Austenitic Stainless Steel," February 23, 1973.
NRC Regulatory Guide 1.37 " Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants," March 16, 1973.
NRC -Regulatory Guide 1.43
" Control of Stainless Steel Neld Cladding of Low-Alloy Steel Components," May 1973.
" Welder Qualification for Areas of Limited Acces-sibili ty," Decemcer 1973.
ASTM A 262-77a, practice E " Copper-Copper Sulfate-Sulfuric Acid Test for Detecting Intergranular Attack in Austenitic Stainless Steels," Annual Book of ASTM Standards, Part'3,.1978.
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,. 1
APPEilDIX A Comanche Peak Metallurgy Review Issues 4.5.1 Control Rod Syste.a Strr;tural-Materials
- 1) On p. 4.2-10 it is stated "The controi rod cladding which is cold drawn Type 304 stainless steel tubing is the only non-code material used in l
the control rod assembly." Also, en p. 4.2-23 "The clad in the rod assemolies is slightly cold-worked Type 304 stainless steel."
It is necessary to know wnat specifications were used to purchase this Type 304 stainless steel and the yield strength of the finished product, which should be less than 90,000 psi to comply with Regulatory Guide 1.70 and Standard Review Plan 4.5.1.
Perhaps QA covers this area of concern.
- 2) The material for components of the control rod system are not'specified j
by ASME Code (Appendix C).
- 3) The heat treatment and tempering conditions of martensitic and precipi-tation hardening stainless steels used in the control rod system should be listed (p. 4.5-1).
4.5.2 Reactor Internal Materials
'4) ~ The. heat treatment of. the X750 supcort pins for the guide tube assemoly should be given.
It has been found that X750 is susceptible to stress corrosion cracking unless a solution heat treatment > 1800*F/1 hr. is emoloyed.
If support pins fail in the Uoper Head Injection (UHI) plant, there is the possibility for misalignment between the control rod drive assemoiy and the guide tube.
Support pins with proper heat treatment A-1
.i
and modified design to improve safety features (prevent misalign-ment in case of pin failure) have been required in domestic UHI A
plants (e.g., Sequoyah).
The specification of SA-461 GR 688 in the List of Materials appears to be in error. We assume the applicant means A-461 or SA-637 Grade 688 for the Inconel X750. However, this error may be irrelevent since the support pins are to be changed anyway and a re-definition of materials and design is required.
5.2.3 Reactor Coolant Pressure Boundary Materials
- 5) On p. 5.2-12, "In some cases, Table 5.2-3 may not be totally inclusive of the material specifications used in the listed applications." A list of all materials and their use condition is needed for metallurgi-cal review.
- 6) On p. 5.2-13, the statement "The welding materials.... conform to of are eouivalent to ASME..." is not acceptable for an FSAR. -Any equi-valent material should be specified. Also in the material list (see Appendix C), "og" appears c.ite frequently, leaving the reviewers in doubt as to what material has actually been specified.
- 7) Specify steps to be taken to assure demineralizer resins do not enter into the main coolant stream (p. 5.2-14).
- 8) State post-weld heat treatment of clad ferritic low alloy and carbon steels and verification of corrosion resistance after treatment (p. 5.2-15).
- 9) State fabrication sequence and heat treatments used for safe ends, also materials used for safe end applications, weld consumables and resultant corrosion compatibility of dissimilar materials (p. 5.2-15).
- 10) Are the Westinghouse -process specifications listed on p. 5.2-19 and -20 in compliance with RG 1.37?
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A-2
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- 11) ~Have the amendments to ASTM A-262-70 by Westinghouse process specifica--
tion 84201 MW been approved by NRC (p. 5.2-21)? Also why is the option of using ASTM A-393 given (p. 5.2-25), since ASTM discontinued its use in 1973?
- 12) Electroslag welds made for:the bridge industry and NOT inspected to ASME code requirements before installment are being found to exhibit gross internal flaws by sophisticated post-installation inspection. This same situation was found to be the case in a reactor under construction on the Hanford Reservation (No. 2). Are the inspection techniques used
. for electroslag welds sufficient to assure no repetition of the apparent presence of gross flaws after Regulatory Guide 1.34 inspection require-ments have been met in the Comanche Peak Units?
- 5. 4. 2.1 - Steam Generator Materials
- 13) Do the reference tests as to the suitability of Inconel 600 for steam generator tubing (p. 5.4-15) include favorable evaluation of cold-worked
-tubing as wtuld occur in the hairpin bend and at the tube sheet jcints?
- 14) _ In 5.4.2.5 (p. 5.4-32), the discussion about steam generator denting does not include any references.
6.1 Enaineered Safety Feature Materials
- 15) On p. 6.1 N-1 it is stated: "In some cases, this list of materials may not be totally inclusive. However, the listed specifications are representative of those materials used." Please clarify, a review of comoliance can not be completed without definitive statement of mate-rials usage.
16). What is tne condition of the spray tubing / piping of the ECCS (austenitic stainless steel) wnen cold bent on site without stress relief?
i A-3
- 17) There is some concern about the call-out Table 6.
1N-1, Sheet 2, for closure bolting with SA-194, Grade 2H nuts. These have 0.40 C, minimum, (no maximum limit), and may be tempered as low as 850 F.
Are these located anywhere such that a nut failure could compromise safety?
- 18) The integrity of the materials of construction for ESF equipment when exposed to borated water in event of a LOCA (p. 6. IN-2) are discussed in references WCAP-7803 (non-proprietary) and WCAP-7798-L (proprietary).
Have these references been approved by NRC Staff?
- 19) To review these materials (Table 6.1N-1), their metallurgical condition and their expected normal, off-normal, and upset conditions should be described.
10.3.6 Steam and Feed Water System Material
- 20) In Table 10.3-6, Sheet 2, 26 in. to 32 in fittings are listed as SA-234, WPPW: ASME Specification SA-234 does not list WPPW.
- 21) In Table 10.3-7 the guide and guide rings are listed as "ACI CF8M nicology (solution annealed)." What is the equivalent ASME specification?
22)
In Table 10.3-8, the bonnet nuts are listed as SA-194 Grade 37.
Should they be Grade 7?
A-a
APPENDIX B Check Lists for Standard Review Plans 6-1
u/ 6 E S - U N r - 3 C:iECX LIST FOR S ANCARD RE7IE'i FLAN 4.5.1, C::NTRCL RCD SYui GUC""dRAL MA ERIALS l fl r i
- a iu
>4 5,13
.&l t.%
=
1.
.veenanical P Ocerties
,$ 3 a.
ASME Code,Section III, Appencix I (ecuivalent techanical i i properties),cr
- p. +. N Id i
e b.
ASME C ce, Secticn III, Part A (ecuivalent mecnanical i
Precerties).
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Cold-worked austanitic stainless stasis yield streng:n I
u per limit of 30,000 psi.
I l' 45_3 r
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2.
Austanitic Stsinless Steel 00mecnents t
a.
Regulat:ry Guide 1.3 (preventing intergnnular c:r-esien of p.45-3
<{
suinless stael c:m:ccen:1). (exezy use a: Asrn A 293)
C.1 Cleaning and ;retacticn against c:ntaminant:
,4g_g C.2 Solutien hea: trea:=ent.
I,
- p. 4 c_4,4,y.9 v
C.3 Verifiestien Of ncn-sansiti:2 tion.
y.
.f.4 g.r-e d
C.4 Ma:arial heated := 3CC-15CO*F sucsacuent : saturien i
heat treating.
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,eA S-/o u'
C.5 Material heated t: 3CO-1500*F during hea: treating er I
precassing c ner than welding subsecuen: : sciutien I
heat trenting.
P ^ r-'O o -ly C.5 Intargranular c:r esien test fer eacn 'welcing precacurs.p.dr-a b.
Branch Techniczi Positien.YTE3 5-1 (Regu' ::ry Guide 1.31 i,
!ntarim Petition). (Delta fer ita intar m accartanca i
cri' aria).
P A T- *> " r-!!
. v (;
3.1 Ac:actanca tas:s for weld filler =etals.
par-/> l v I, 3.2 Cartified matarials :as recor.
a A r-'i 3.3 Examina:icn Of pr: duction,elas.
c^ r-'/
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-[
3.4 Ac:sctability critaria fer ncn-c:nf:rming precuction g
.r-4 e(
)
4 welcs.
I e
1 I
1 w ariais 3.
Other a
{
e a.
ASME C de, Secti:n III, partgra hs N5-2150 an N3-3100 (:: mea:i-
{
l bility wi t.
sac :r ::cian:)
r s
5.
Martansitic ::ael =ini=um :scering treentre (f:r Tyce 113 I
s: sinless, ICSC*F 1: ac:ac:2:;e).
3-2
w.s E s - U N iT - 3
-2 8
d5
?C B.lW
,e Precipitation-hardening stainless steels minimum aging T
c.
r
- amperature (for Type 17-4 FH steel, llCO*F is acceptable).
J,t P
4 Cleanina and Cleanfiness Cantml f
P p, q,_g p [
a.
Regulatory Guids 1.37 (cnsita cleaning and cleanliness f
h centrol).
5; C.1 Occ=ent: incluced in ANSI N45.2.1-1973.
C.2 Requirement: and rec::zendations apolicable to plan: c eration also.
E C.3 Water cuality for final flushes of fluid systems and
[
f as:::ciatad c:mconents.
C.A Avoidacca of chemical :=councs that cause corrosien I
cracking of c:r esien-esistant alloys.
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C.5 C:ntrol of ccerations efch generata particulata matter that causes c;rrosicn cracking of cor sion-resistant alicys.
f g
C.5 Intergranular precipita:icn testing of :crmsion-resistant alloys.
l b.
ANSI N45.2.1-1973 (onsi a cleaning and cleanliness c:ntr:1).
,f 3-3
W b E b - U N ' T ~h CSECX LIST FOR STANDARD RS7:EW PL%N 4.5.2, REACER INTERNALS MAGIALS ou
=
5,.2
.3 E-a y
v 1.
MataMal Scecificattens a.
ASME Ccde,Section III, i NG-21211 and Accendix I, Tables 1-1.1 3
and 1,1.2 (; emit ad :nataMais.dentified),
b.
ASME Ccde,Section II, Parte A, 3, and C (pernitted =aterials descMbed).
2.
Centmis on Veldine a.
ASME Ccde, Section II: 1 NG 4400 (fabrication recuirements).
5.
ASME Ccce,Section III, i NG-ECCO (accaptanca cM taria). p.4.5-7 3.
Nondest" active Examination of Wrcugnt Seamless Tubular F'ccucu anc ?11:1ngs a.
Reculaterv Guide 1.55 (accactanca cM tem a for eddy-current ana uitrasenic examina:1cn].
C.1 Recuired examinations.
C.2 Ultrasenic examina icn.
C.3 Reference sceci=en.
i b.
ASME Ccce, Secticn III,1 NG-5220 (accaotance critaMa for radiogra::nic examination).
p.4.5-7 4.
Austanitic Stainless Steels a.
CritaM a for Testine. Alicy Cc=cesitiens. and Heat Traa*=ent c Avc1a sens1:::stien.
(1) hgulatory Guide 1.M, Pcsitiens C.2 to C.S.
PAS-B C.2 Solution heat treat =ent.
PA f-9 r
C.3 Venfic1:icn of ncn-sensizi:1:icn. (Asm 'sn) ?'T*8 v
C.4 Material heatad to 500-15CC'F sucsecuen: ?
solution heat treating.
FM-'c C.S Ma:arial heated.c SCO-15CC*F during !::e m :q cr precessing ett:er t. tan weiding s: he~
-l!
sciution heat t eating,
- p. 4.r 'c C.5 Intargranular cor csion ast for eaca wei-.
?
- 4 7,,
peccacure.
5.
Centrais en Cieanine. Contaminant 3m tacticn. and Yield S rang n :: Avetc 5 mss ccc-csten Cm cx1na i
(1) Requia: cry Guide 1 u, Position C.1.
Sa
W.S ES - U N l'r -h =v x
e s
res C
=-
.E.'
r 00 C.1 Clean-ing and protacting :natarials against c:ntaminan:s.
P 45~0 (2) Regula. cry 3 aide 1.37, ?csiticn C.3.
PA 5-2 v
C.3 Watar cuality fer final flushes of flutd systams and associated c:mconents cuMng installaticn.p 45-8 7
(3) Cold weri:ed austanitic stainless staels yield strength u:per limit of 90,CC0 psi.
P. M-6 v
c.
Ac:setacle ~Ter-ai Insulation (1) 'leflective metal insulaticn, er (2) Nonmetallic insulation per Regula::ry Guide 1.26 (ncn=etallic themal insulatien).
C.1 Limiting chicride and flucride centamination prior
- = anc duMng installaticn.
C.2 Cualifica: ten tast.
C.3 Precuc:icn tas:.
C.4 Recualifica:icn.
d.
Austanitic Stainless Stael '4eldine s
(1) 3 ranch Technical Position MTE3 5-1 (delta ferMta intarim acceptanca cM tad a).
p 4 5-//
3.1 Ac:a :ance tasts of weld filler =etals.
P "
3.2 Cartified mataMais test re crt.
PA T-"
3.3 Examina:icn ci pr:duc:icn welds.
P M~
3.4 Ac:::: ability critada for ncn-c:nforming precucticn welcs.
par.n
/
(2) Regulaterf Guide 1.21 (electreslag welds ac:actanca). o.+.5 n.
C.1 Precadure cua11 fica:1cn rt:uiremen(ts - r:cass ~No electrc$leta'we/ abo variables and macro-eten tas:.
C.2 Car-ified cualifica:1cn tas repert.
C.3 Testing icngitudinal produe:1cn wids of icw-alicy
- ael vessels. (Nata: Nc: acclica:1e *4 austanitic staels.)
C.a Menit:Mng ;recuction welcs cf austanitic stainless stael ex.cenen a.
C.5 Ad iticnal recuirement: for 'mac:2 table weids.
3-3
'WS Es -U N IT.3 8 t
5
- 8. ;
3 iii-00 (3) Regula:crj Guide 1.71 (welder qualificatien for areas of limitad accassibility).
p. 4. r-/1 C.1 Per#cenance qualification requirsena.
~
C.2 Recualification requirements.
C.3 Production welding :nenitoring and cartificaticn of welding qualification requirements.
e.
Ncndesetive Examinatien ef Austanitic Stsiniese Steel iucuiar.M aucis (1) Regula:crf Guide 1.56.
. w-7 C.1 Recuired examinations.
C.2 Ultrasenic examina:icn.
C.3 Reference s::ecimen.
1 1
3-6 s
W S ES - U N l'r -3 s
CHECX LIST FCR STANDARD RE'/IEW PLAN 5.2.3.,
REACTOR CCCLANT PRES 3URE 3CUNDARY MATERIALS 8
t i
a3 ?
O d 1.
Material scecifications a.
ASME Code,Section III, Appendix I (pe nitted materials s:ecifica-icns identified).
b.
ASME Code,Section II, Parts.L. 3, and C (permittad materials s;:ecifics:1cns described).
Ta.6/e S2-3
/
2.
C:=catibility of Materials with the React:r C:oiant a.
In Boiline Water Reactors (BWRs)
(1) Resulatory Guide 1.55 (reacter c:alant purity '
c uctivity and chloride centent).
C.1 Limits en c:ndensate cc::cesitionand electrical c:n'ductivi ty.
~
/
Esablishnent of minimu/m.~sidual deminerali:e C.2 capacity.N C.3 Anion and cat.
demineralizer resin capacity measurement.
C.4 Verification of ma ntenance of minimum residual f
deminerali:er eslacit4 C.5 Conductivitf meter to trig (er c:ntr:1 rocm alar n.
C.5 Limits,fo'r c nductivity and enlcrides in the reacter vessel.
N Table Recresentative conductivity Nits at the Recresentative limits for c:nduc\\
deminerali:er cutlet.
T le 2 tiitty and chiarides in the reacter vessel wateg l
b.
In ?Nssurized Vater React:rs (PVRs1 l
(1) Regulat:ry Guide 1.44 (reacter c:alant chemistry),
t l
Chicride and fluoride less than 0.15 p;m at all times.
l Dissolved oxycen belcw 0.10 ppm wnen above 250*F.p.5.2-M
/
Table q,3-7 c.
In !cth ?VRs and M s l
(1) ASME Code, Secticn III, I NS-3120 (ccr osien l
alicwance f:r unciac car cn and icw alicy steeis).
i 3-7
WS 6.5 - Li N i T-3 8 c
w 8
. v v
(2) Regulator / Gr'de 1.44 (non-sensiti:stion of RCFB c::mponents of austanitic stainless steel).
C.1 Cleaning and protection agains c:ntamina :". v.E.2-/1 C.2 Solution heat treat:nent.
C.3 VeMfication of non-sensiti:stion.
p.32-n C.4 MataMal heated to SCO-1500*F subsequent to F S, _,,
solution hea: treating.
>.S.:. '3,
C.5 Matarial heatad tm 800-15CO*F during heat
}
treating cr processing otner than weicing i
subsequent to solution heat treating.
p.50-'3 v
C.5 Intargranular cor esion tas for eacn welding prCCacurt.
3.
Fabrication and Pmcassine'cf'Fer-itic Matartals a.
inctir= ~ouchness (Thtandard Review Plan 5.3.1 (react:r vessel ma:ard s).
(2) AIMCCode %Section III,1 NB-2330 and N
'3 4 and Acpendix 7,'54-3100 (pipin g and valves mataMais).
l (3) ASME Code, Sect 4 II,T W 2330 and N8-2333, and
" AcpanetCB, I G-4100 (boitiniwMals).
i (4 4'E Ccde, Secticn III,1 NS-2350 (clM tion of j
instm ments and ecui: ment).
b.
Fer itic Stael '4eldino -
i (la) ASME Code Section III, Accendix 0, 1 0-1200 (preheat 1
tamcerature amount).
(lb) Regulatcry Guide 1.50 (preheat tamcerature c:ntrol)p.I2 'I
. p.52-y e
i C.1 'delding precadurs qualification recuirements regarcing mini:::um prehea: and :naximum in:arcass temceratures.
p.t2-9 C.2 Maintaining prehea tamcerature.
C.3 Mcnit:Hng preouction welds.
p.g.g - g y
- p. S.2 -9 C.A VeMfying weld soundness when Positiens C.1, C.2 and C.3 are not met.
p.5:-?
/
(2) Regula:Or/ Guide 1.34 (eiect eslac weids ac:actanca procacure cualifica:4cn recuiremena.s/a., w,wm).t,.c: es dvo e/ectro ai I
C.1
$recass ~'
)
variaoles, macro-et: tast, anc imcac: :ss:ing.
l 3-3
w a ss -u n !r-2.
' 1 8
x
=
5 2
?
~
I yv C.2 Cartified qualification test report.
C.3 Testing longitudinal production weids of icw-alley 4
steel vessals.
C.4 Mcnitoring production welds of austanitic stainless.
steel ccmcenents. (Nota: Not apolicable 3 ferritic steel.)
C.5 Additional recuirements for unac:actacle welds.
l (3) Regulatory Guide 1.71 (welder qualificaticn for areas of a
limited accassibility).
pil-lo C.1 Perfor.anca qualification requirements.
C.2 Requalification requirements.
C.3 Procuction welding :nonitcHng and cartification of welding qualification requirements.
- c. L
..metive Examination of FerMtic Steel Tubular Pmduc s (1) Regulatory Guide 1.56.
I C.1 Recuired examinations.
C.2 Ultrasonic examination.
C.3 Reference specimen.
4 FacMeation and Pmcassine of Austanitic Stainless Steel a.
CHtaMa for Testinc,' Alicy Camecsitiens, and Heat Treatent to Avcia sens1ti:stlen.
(1) Regula cry Guide 1.44, Positions C.2 to C.5.
I C.2 Solution heat treatment.
A EN' C.3 Verification of non-sensiti:stien.(Asm At93) # Il-"
C.4 MataMal heated to 800-15CO*F subsequent to solution heat treating.
- p. 0 2-/2 y
C.5 Material heatad to SCO-1ECO*F during heat treating or precassing other than welding subsecuent ts saluticn heat treating.
- a. s.1-t2.
y C.S Intergranular cornsien test for each welding prcCadure.
- p. f a -oz
/
b.
Cantm is en Cleaninc. Cantaminant P'etection and Yield 3CNnC*n
".3 AVo10 3 0"*ss Car"esien CraCX* NC r
(1) Regulat:ry Guice 1.44, Position C.I.
- s. E 2-li, Et-i3
/
3-9
w sss-cSr-3 1.-
l 8
=
k
.2 a
3 I
0a C.1 Cleaning and protacting materials agains:
c:ntaminan c.
(2) Regulaurf Guide 1.37, Pesitien C.3.
C.3 Watar quality for final flusnes of fluid systams and asscciatad c:mconents duMng insu11atien.p.r.2-z (3) Celd werked austanitic suiniess staels yield streng:n uccer limit cf 90,000 psi.
,,5 2.,a c.
Accactacie T*nemal Insulatien (1) Reflective metal insulation, er P 52 '1 (2) Ncnmetalife insulation :er Regulat:ry Guide 1.35 (nonmetallic themal insulatien).
- o. 5 2 -d C.1 Limiting enicMde and flucride cenumina:1cn price to and taring instsilatien.
C.2 Qualifica:^:n tast.
C.3 Prcduction test.
C.4 Recualification.
d.
Austanitic Stauids3 Steel Weldinc (1) 3rsnch Technical Position.WE3 5-1 (delta feMta intarim ac:aptanca critaria).
3.1 Ac:actanca tasts of weld filler metals.
PS 2-'r 3.2 Car:1fied ma.arials tast report.
3.3 Examination of pr cuction welds.
- p. 3,
-,7 r
- o. n -is 3.4 Ac:anubility critaria for non-cenferning precuction welds.
a. r.1-!r (2)
Regulator / Guide 1.3a (electicslag(Nc <!+e*rcsta, ~t&%e.c2-io welds ac:actanca).
r C.1 Precadure cualifica:1cn recuiremenu - precass variaoles and macro-et:n ast.
C.2 Cartifiec cualification test re:cr.
C.3 Testing longitucinal procuction welds :f icw-alley stael vessels. (Noa: Not acplicaole to austanitic staels.)
C.4 Mcnitoring or:cucticn welcs of aus.anitic stainless stael ex enenu.
C.5 Acditianal recuiremenza for unac:sotacle elas.
l 3 - 1C
W 5 ES - U N IT-3 5-8 b
=
s.
8 u _u (3) Regulatory Guide 1.71 (welder qualification 'for areas of limitad accassibility).
- p. 5.2 -to C.1 Performanca qualification requirements.
C.2 Requalifiestion requirements.
C.3 Production welding monit: ring and cartification of welding qualification requirements.
e.
ficedestreadve Ese=4 nation ef' Austenitte Stainless Steel Tucuiar Precuc.s
(
(1) Regulat ry Guide 1.66.
- g. 3,2.f o C.1 Recuired e.xaminations.
C.2 Ult.ascnic examination.
C.3 Referenca 3;:ecimen.
I i
3 - 11 4
4
m 6 5 - U N I T"-3 CHECX f.!ST FOR STANDARD REVIE4 P! AN 5.4.2.1, STEAM GENERATCR MATERIALS 8
b e,l P ! s.
u 5
u 1.
Selection and Fabrication of Materials a.
MataMais Meenanical ?meerties.
(1) ASNE Code Section III, Accendix I, or Tab /e.r.2 s (2) ASME Code,Section II, Paru A, B, and C.
raA/e E;-3 b.
Tube Sheet Weld-Cecesited Claddine Recuirwenn (1) ASME Ccde, Sec:fcn IX, Article QW-214 (weld depositten and inspection),
c.
Rc111ne or Excandine Tubes in U-Tuced Steam Genenters fer.cuii t.ene.a et Tuce shee:
l (1) Branch Tecnnical Pcsition MTE3 5-3, Position 1.
3.1 Minimi:ing crevices between tubing and tuce sheets er tubing supper:s.
p y a.i, d.
Cnsita Cleanine and Clean 11aess Contml (1) Regulatcry Guide 1.37 P E 4 'J-C.1 Cccuments included in ANSI N45.2.1-1973.
P # d-
C.2 Recuirsmen u and reccanendations acplicable
.c plant coerstion also.
C.3 Watar cuality for final flushes of fluid systams and assceiated ecmconen u.
C.4 Avoidanca of chemical ecmconents t. Mat cause cer esica crtexing of cerMsion-resisun; alleys.
C.5 Control of ccerstions wnich genersta cart-icula.a mattar ::a: causas cernsion cracking of cernsion-essistant alleys.
C.5 Intargranular preciciution tasting cf r
cer ccien-nsis un: alleys.
l l
l t
i 3 - 12 1
I
W.5 E S - U N I T-3 3 D
2
& =
v$
0 (2) ANSIN45[2.1-1973, e.
Tubes to Tube Sheet Velds Recuir=ments (1) ASME Code Sectica III.
F ' *
(2) ASNE Code Section IX.
g.54 -//
v f.
MataMais Cesicned t: Code 4ase Recuir=ments (1) Regulater/ Guide 1.35'(Cece Case accaptabili*y for ASME Section III matarials).
C.1 Code Cases ac:aptable t: NRC stsff in construction of water-c:oled nuclear power pc-3:.
r_
plant c:mocnents.
g.
Fracture Touenness of Ferritic Materials of Class 1 A0 h.
Fractura Teugnness of Ferritic MataMais of Class 2 M moenants-
/
w (1) ASME CodeAtWtane o 2 Addenda, 7!ifsg'rapn NC-2310.
2.
Steam Senerater Cesien a.
Desienino to Avoid Extensive C.7vica Areas (1) 3rsnch Technical Position MTE3 5-3, Positien 1.
3.1 Minimi:ing crevicas betwen tubing and tube sneet: or tubing succcrts.
- p. s. '-!!
/
3.
Cemeatibili*y of de Steam Genern:r Tubine wi'h the 2H= arf ano Secencarf C oiant s.
Accactanca C.+aMa for Mmarf C:oiant Chemismi (1) Regulatory Guide 1.c (react:r c:olant chemistry)Ja#e/0.3d v
Chiar de and flucMde less than 0.15 ;pm at all
{
a t mes.
l Jissolved oxygen belcw 0.10 ;cm wnen above 250'F.
S - 13
W.sg.s-UNor-3 3
t i I
O v
b.
Nnit:Mnc of See:ndary Coolant PuMty (1) 3rsnch Technical Position MTE3 5-3, Positien 2.
3.2 Menitoring requirenants for plant: utili:ing volatile chemist:/ or pheschata treat:nent. p./0.3-6
/
a 4
3-N i
w.5 ers - U N o r-3 CHECX !.IST FOR STANDARD REVIEW PLAN 6.1.1, ENGINE..'4ED SAFETY FEATURES METALLIC MATERIALS 0
t' 5
3
!?
ae 1.
MataMais Selection and Fabrication a.
MataMais Selection (1) ASNE Code Section III, Paragraphs N8-2160 and NS-3120 (c meatibility with core and containment scray solutions).
p.d./- 8.
l (2) ASME Code, Secticn III, Appendix I (mechanical l
precerties), or (3) ASME Code, Secticn II, Parts A, 3, and C (mechanical properties).
- p. g,, f <
g.
(4)
Cald-woried austanitic stainless steels yield t
strengtn upper limit of 90,000 psi.
p.6./-f v
b.
MataMais F3bMestien (1) Regulatory Guide 1.44 (preventing intargranular cor-resten of austanitic stainless steel ccmcenents),at./+
C.1 Cleaning and protaction against c:ntaminants. W C.2 Solution heat treatment.
/
C.3 Verification of non-sensitiution.
p 4 /-#-
C.4 MataMal heated to 8C0-1500'? subsequent to solutien haat treating.
j C.5 MataMal heated to 800-1500*F during heat l
treating or precassing other than welding l
subsequent to solution heat treating.
i C.6 Intergranular c:rresion tast for each welding l
proct-dure.
(2) 3ranen Technical Position. TI3 5-1 (Requiatory V
Guide 1.31 IntaMm ?csitien). (Celu ferrita intaMm accaptance t-itaMe for weldino sustanitic suinTess stael c:mconents.)
P 6 /~C l
3.1 Accaotance tasts fur weld filler metsis.
p.6J-F
<l l
3.2 Car.ified :nataMais tast recort.
p.4./-o-
-i 3.3 Examinatien of production welds.
4 4 /'C Wl l
3.4 Ac:actability cMtaMa fer non-c:nfor ting l
procuction welds.
- p. 4J-$f iv 3 - 15 1
W o e s - u N er-a l 8 D
a s
T 3
v v
(3) Regulat:ry Guide 1.26 (centroling c:zncasition of nonmedilic thermal insulation for austenitic suinless steel ccmconents).
? 4./-E C.1 Limiting chloHde and flucHde contamination pHor to and during installation.
C.2 Qualifiestion tast.
i C.3 Production tast.
C.4 Requalification.
2.
Cemcositten and Cemeatibility of Cantsinment and Care Scray CCCiants a.
Inhibitine Initiatien of Stress-Carmsion Crackine of Austantric stainiess Steel C:meonents foiiew1ne a t.CCA.
(1) 3 ranch Tecnnical Position MTE3 6-1 (pH for emergency
- alant water).
3.1 Minimum pH of 7.0.
p.4./
.2.
3.2 High pH and stress-c rresien cracking.
3.3 Higner cH and hycrogen generation frem aluminum carresien.
i b.
Centm ilina Hvdrecen Release frem Carresion of Centainment Matar7ais foiicwino a LOCA.
(1) Ragulat ry Guide 1.7 (centrol of c:moustible gas concentrations in c:ntainment follcwing a LCCA).
C.1 Availability of c:mcustible gas centrol equipment.
C.2 Egineered safety feature recuirements for c:mous:1ble gas c:ntrol sys ams.
C.3 Cacability far c:ntralled purge of c:nuinment.
C4 Calculating hydregen and oxygen c:ncantra:icn in c:nuinment:.
C.5 Identifying anc limiting c:nuinment =ataMal:
(i.e., aluminum) taa yield hydrogen gas due t cartesien from emergency c:oling or c:nt-ainment s: ray solutions.
B - 16
W.S E.5 - U N I'r-3 8 b :
a ::
3 +
0 8 c.
Storing Containment and Core Sor3v Soluttens (1) Avoidance of deterioration of containment and care scray solutions (containing boren for reactivity c:ntrol, thiosulfates for reacting with gasecus fission ;r ducts, and other addit 1Yts) by enemical stability or corrosive attack on the s'arage vessel.
- p. 4.1-9 3 - 17
w 5 fE S - O N I M CMECX LIS FCR STANCARD RE7IEW Pt.AN 10.3.5, STEM AND FEEDWATER SYSTEi MATERIALS 8
t i
$7 3
iib dd 1.
Fracture Touchness of Class 2 and 3 Comconents ASME Cede Section III, Paragrach NB-2200 (farMtk terials for all Class 1 ccmconenc).
5.
ASME bce Section III, Paragrach NS-22
ferM tic u tam al" cr Class 1 vessels).
c.
ASME Code, Sec': ton III, Paragrap NS-2332 (feraitic s
ma:arial for ClassSJioing, :umes, and valves),
d.
ASME Code, Section IIr, Sunner 1972 Addenda, Paragra:n NC Te3TO (ferritic matarials for Class 2
. ccmcone N
e.
ASME Cetfe Section III, Sunner 1972 A'ddenda, Firagracn NO-2310 (ferMtic matarials forTass 3 comoonents).
N 2.
MataMals Selection and FabMestion for Class 2 and 3 Cemconents a.
MataM ais Mechanical Pncer-ies (1) ASME Code,Section III Accendix I, or
- 3. fo.39 v
(2) ASME Cace.Section II, Parts A, 3, and C.
b.
CH:aMa Aeolicable to All Austanit'c Stainless Steel Ccmoonents l
(1) Regulatory Guide 1.44 (preventing stress c:r esion).
l C.1 Cleaning and protaction against c:nt:minants.6.2.3-9 C.2 Solution heat treacent.
'c. /c. 3-a C.3 Mazarial neazad to 800-15C0*? subsecuent to ~~"c' 'l VeMfication of non-sensiti:stion.
..a C.a solution heat treating.
C.5 MataMal neatad to 200-1500*? duM ng heat treating or processing Ocer.t:an welding l
subsecuen: to sciution hea: - eating.
C.5 Intargranular c:r esion heat for eacn welcing ;recacurs.
A 'C* U l *' 3 3 - 13
W6 E.S - U u er-s l 8 b
&3 O b (2) Regulatory Guide 1.36 (centraling ecmcositicn of nonmetallic themal insulation).
WO 3+
v C.1 Limiting chicride and flucride contamination prior to and during insullation.
C.2 Qualification test.
C.3 Production ast.
C.4 Reccalification.
(3) 3 ranch Technical Position MTE3 5-1 (Regulat:ry Guide 1.31 intaMm position). (Celta fer-ita interim acceptance cMtaMa for weiding.)
3.1 Ac:aptance tests for weld filler metals.
p./o 3-/c 3.2 Cartified mataMais test recort.
- p. /c.3 -/c 3.3 E.xamination of production welds.
- p. /c.3 -/c v
3.4 Acceptability cMtaMa for non-confor-ring production welds.
r /c 3 -/c v
c.
CritaHa Acclicable to All Cemconents.
(1) Regulatory Guide 1.71 (welder qualification for areas of limited accessibility).
p fo, g.g C.1 Perfennanca qualification requirment:.
C.2 Requalification requirements.
C.3 Procuction welding monitaMng and certification of welding qualification requirements.
(2) Regulatory Guide 1.37 (ac:ap uble precadures for cleaningandhandling).
p/o. 3 -//
Col Cocuments included in ANSI N45.2.1-1973.
C.2 Recuirements and rec:mmendations acplicable
- a plant oceration also.
I C.3 Watar quality for final flushes of fluid systams and asscciated c::mcenents.
C.4 Avaicance of chemical c:mconents that cause ccmsion c acking of c:r esien-resisunt alloys.
C.5 Centrol of ocerations wnich generata par.1culata mattar that causes c:r esien c acting of c:r osion-resisunt alicys.
B - 19
wSE5 -u N : 7-3 3
8 t
5 3
?
O3 C.5 Intargranular precipitation tasting of cernsicn-resistant alloys.
(3) ANSI N45.2.1-1973 (ac:aotscle precadures for cleaning and handling).
s te.3 -a d.
Critaria Aco11caele to All Careen or Lew Alloy S'ael ccmcenent:
(1) Fracture t=ugnness critaria of Itam 1 of this check list.
(2) Regulatory Guide 1.50 (;; reheat 'amcerature c:ntrol).
ino tou-alica stee s C.1 'delding precadure qualificatlen re:qu)irements p.ic.3-1) v regarding minimum preheat and maximum intar-pass tamcerstures.
C.2 Maintaining preneat ta!=:erature.
C.3 Monitoring precuction velds.
C.
Verifying weld souncness wnen Posittens C.1, C.2, and C.3 are not ::et.
3 - 20
APPENDIX C List of ffaterials/ Components Reviewed O
C-1
7 REACIOR C0llP0litflTS REf[ItEliCE MATERIALS 4.S.1 Control Rod Systeni Pressure llousing Table 5.2-2 SA-182 Grade F304 or SA-351 Grade CF8 Pressure forgings Table.,.2-2 SA-182 Grade F304 or SA-3Sl Grade F8 Dar Material Table s.2-2 SA-479 Type 304 Welding Materials Table 5.2 SFA-5.4 and 5.9 Type 308 or 308L Control Rod
- p. 4.2-10 Cold Drawn Type 304 S.S.
Absorber Rod End Plug
- p. 4.2-21 Type 308 S.S.
Spiiler Assendily
- p. 4.2-22 Type 304 and 308 S.S.
Spider Assendily Retainer
- p. 4.2-22 17-4 Pil g,
Spider Assendily Springs
- p. 4.2-22 Inconel 718 i
Thiinble Plug Assenibly
- p. 4.2-25 Type 304 S.S.
Thiinble Plug Springs
- p. 4.2-25 Inconel 718 Control Rod Drive:
flagnetic Pole Pieces
- p. 4.5-2 Type 410 S.S.
All rion-magnetic Parts
- p. 4.5-2 lype 304 S.S.
Link Pins
- p. 4.5-2 Ilaynes 25 Springs
- p. 4.5-2 flickel-Chrome-t ron Alloy latch Ana lips
- p. 4.5-2 Clad witti Stellite-6 llearing and Wear Surfaces
- p. 4.5-2 liard Chrome Plate and Stellite-6 4
a
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REACTOR COMP 0NElliS REICREllCE MATERIALS 4.5.2 Reactor Vessel Internals forgings Table 5.2-4 SA-182 Type l'304 Plates Table 5.2-4 SA-240 Type 304 Tubes Table 5.2-4 SA-213 Type 304 liars Table 5.2-4 SA-479 Type 304 and 410 Castings Table 5.2-4 SA-351 Grade Cf8 or Cf8A Bolting Table 5.2-4 SA-193 Grade B8M (65MYS/90MTS)
Code Case 1618 Inconel-750 (needs heat treatment) o SA-461 Grade 688 (?) 'Can not find SA-461 description - also need to know heat treatment)
Nuts Table 5.2-4 SA-193 Grade B8 Iocking Devices Table 5.2-4 SA-479 Type 304 Weld Buttering Table 5.2-4 S.S. Held Metal Analysis A-7 Reactor Core Components:
Lower Core Support Structure
- p. 3.9ft-99 Type 304 S.S.
Core Barrel (need better materials description)
Core Baffle Lower Core Plate & Support Columns fleutron Pads
- p. 3.9N-100 Type 304 S.S.
Core Support (welded to Core Barrel)
(need better materials description)
ill AC10lt COMP 0flEllTS IllTl itEllCE IIAIEltiALS t
lipper Core Structure
- p. 3.9N-100 Type 301 S.S.
lipper Support Asseinbly (need better niaterials description)
Upper _ Core Plate Uill* Support Coluinn Guide Tulse Assemblies in-Core lustrianentation Support Structure llolddown Springs
- llote: till! ' Upper llead injection
,.-. ~.- - _
S.2.3 fleactor Coolant Pressure Boundary n
lleactor Coolant Pump Pressure forgings Table S.2-2 SA-182 Type F304, F316, F347 or f 348 Pressure Casting Table S.2-2 SA-3SI Grade i -
Tube and Pipe Table S.2-2 SA-213, SA-376 or SA-312 Seamless Type 304 or 316 Pressure Plates Table 5.2-2 SA-240 Type 304 or 316 liar itaterial Table S.2-2 SA-479 Type 304 or 316 Closure Bolting Table S.2-2 SA-193, SA-320, SA-540 or SA-453 Grade 660 flywheel Table 5.2-2 SA-533 Grade II, Class 1 l
1.
1 1
i llEAC10R COMPONENTS REFEREllCE flATERI Al.S 4
Reactor Coolant Piping Reactor Coolant Pipe Table 5.2-2 SA-376 Grade 30-1N or SA-3SI Grade Cf8A Centrifugal Casting
- Reactor Coolant fittings Branch Nozzles' Table 5.2-2 SA-351 Grade Cf8A and SA-182 Code Case 1423-2 Grade 304N 4
. Surge Line and I.onp Bypass Table 5.2-2 SA-376 Grade 304, 316 or F304N S.4.2.1 Steam Generator
.n tr' Pressure Plates Table 5.2-2 SA-533 Grade A, B or C, Class 1 or 2-Pressure forgings (including Nozzles and Tubesbeet)
Table 5.2-2 SA-508 Class 2 or 3 Nozzles. Safe Ends Table 5.2-2 S.S. Weld Metal Analysis A-7 Channel lleads Table 5.2-2 SA-533 Grade A, B or C, Class 1 or 2 or SA-216 Grade WCC Inbes Table 5.2-2 58-163 Ni-Cr-fe Annealed Cladding and Buttering Table 5.2-2 S.S. Weld Metal Analysis A-7 and i.
Ni-Cr-fe Weld Metal F-finmber 43 Closure Bolting Table 5.2-2 SA-193 Grade 87
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ItEACTOR COMP 0flEllTS ltEFEREilCE MATERIALS flanges 4 in. to 8 in.
Table 10.3-6 SA-350 Grade LF2 34 in.
Table 10.3-6 A-105 Main Steam Safety Valves Valve !!ody Table 10.3-7 SA-105 Inlet flozzle Table 10.3-7 SA-182 Grade F316 Disc Insert Table 10.3-7 SA-182 Grade F316 Guide and Guide Iting Table 10.3-7 "ACI Cf8M tlicology" (solution annealed?)
Studs (Inlet flan 9e)
Table 10.3-7 SA-193 Grade B7 fluts (Inlet flange)
Table 10.3-7
^'.-194 Grade 211
[6 Main Steam itelief Valves Valve Body Table 10.3-8 SA-216 Grade WCB Disc insert Table 10.3-8 SA-479 Type 316
'llonne t Table 10.3-8 SA-216 Grade WCB Bonnet Studs or Bol ts Table 10.3-8 SA-193 Grade B7 Bonnet Nuts Table 10.3-8 SA-194 Grade 87 (Grade 7?)
Main Steam Isolation Valves Valve Body Table 10.3-9 SA-216 Grade WCC Bonnet Table 10.3-9 SA-105 Bonnet Studs Table 10.3-9 SA-540 Grade B23C4 Bonnet luts Table 10.3-9 SA-194 Grade 7 Gland Studs Table 10.3-9 SA-193 Grade 7 Gland fluts Table 10.3-9 SA-194 Grade 2ll llisc Table 10.3-9 SA-182 Grade Fil k
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