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MIVTSUBISHI HEAVY INDUSTRIES, LTD. 16-5, KONAN 2-CHOME, MINATO-KU TOKYO, JAPAN April 21, 2010 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco Docket No. 52-021 MHI Ref: UAP-HF-10114 Subject: MHI's Responses to US-APWR DCD RAI No.544-4267 Revision 0 Reference: 1) "Request for Additional Information 544-4267 REVISION 0, SRP Section: 06.01.01 -Engineered Safety Features Materials Application Section: 6.1.1, QUESTIONS for Component Integrity, Performance, and Testing Branch 1 (AP10OO/EPR Projects)" dated March 2, 2010. With this letter, Mitsubishi Heavy Industries, Ltd. ("MHI") transmits to the U.S. Nuclear Regulatory Commission ("NRC") a document entitled "Responses to Request for Additional Information No.544-4267 Revision 0." Enclosed are the responses to Questions 06.01.01-13 through 06.01.01-19 that are contained within Reference 1. Please contact Dr. C. Keith Paulson, Senior Technical Manager, Mitsubishi Nuclear Energy Systems, Inc. if the NRC has questions concerning any aspect of the submittals. His contact information is below. Sincerely, Yoshiki Ogata, General Manager- APWR Promoting Department Mitsubishi Heavy Industries, LTD. Enclosure: 1. Responses to Request forAdditional Information No.544 Revision 0 CC: J. A. Ciocco C. K. Paulson

MIVTSUBISHI HEAVY INDUSTRIES, LTD. · SFA-5.22 E309LT1-1/4, E308LT1-1/4 SFA-5.28 ER90S-B3 Impact on COLA There is no impact on the COLA. Impact on PRA There is no impact on the PRA

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Page 1: MIVTSUBISHI HEAVY INDUSTRIES, LTD. · SFA-5.22 E309LT1-1/4, E308LT1-1/4 SFA-5.28 ER90S-B3 Impact on COLA There is no impact on the COLA. Impact on PRA There is no impact on the PRA

MIVTSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KU

TOKYO, JAPAN

April 21, 2010

Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001

Attention: Mr. Jeffrey A. Ciocco

Docket No. 52-021MHI Ref: UAP-HF-10114

Subject: MHI's Responses to US-APWR DCD RAI No.544-4267 Revision 0

Reference: 1) "Request for Additional Information 544-4267 REVISION 0, SRP Section:06.01.01 -Engineered Safety Features Materials Application Section: 6.1.1,QUESTIONS for Component Integrity, Performance, and Testing Branch 1(AP10OO/EPR Projects)" dated March 2, 2010.

With this letter, Mitsubishi Heavy Industries, Ltd. ("MHI") transmits to the U.S. NuclearRegulatory Commission ("NRC") a document entitled "Responses to Request for AdditionalInformation No.544-4267 Revision 0."

Enclosed are the responses to Questions 06.01.01-13 through 06.01.01-19 that are containedwithin Reference 1.

Please contact Dr. C. Keith Paulson, Senior Technical Manager, Mitsubishi Nuclear EnergySystems, Inc. if the NRC has questions concerning any aspect of the submittals. His contactinformation is below.

Sincerely,

Yoshiki Ogata,General Manager- APWR Promoting DepartmentMitsubishi Heavy Industries, LTD.

Enclosure:

1. Responses to Request forAdditional Information No.544 Revision 0

CC: J. A. CioccoC. K. Paulson

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Contact InformationC. Keith Paulson, Senior Technical ManagerMitsubishi Nuclear Energy Systems, Inc.300 Oxford Drive, Suite 301Monroeville, PA 15146E-mail: ck [email protected]: (412) 373-6466

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Docket No. 52-021MHt Ref: UAP-HF-10114

Enclosure 1

UAP-HF-10114Docket No. 52-021

Responses to Request for Additional Information No.544-4267Revision 0

April 2010

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

4/21/2009

US-APWR Design Certification

Mitsubishi Heavy Industries

Docket No. 52-021

RAI NO.: NO. 544-4267 REVISION 0

SRP SECTION: 06.01.01 - ENGINEERED SAFETY FEATURES MATERIALS

APPLICATION SECTION: 6.1.1

DATE OF RAI ISSUE: 3/2/2010

QUESTION NO.: 06.01.01-13

In response to RAI 06.01.01-1, the applicant modified DCD Tables 6.1-1 "Principle EngineeredSafety Feature Pressure Retaining Material Specifications" and 6.1-2 "Principle Engineered SafetyFeatures Materials Exposed to Core Coolant and Containment Spray." The staff reviewed therevised Table and requests that the applicant address the following.

1. There appears to be several typographical errors in Tables 6.1-1 and 6.1-2 which include butare not limited to the following:

a. Material grades listed under SA-182 use the prefix "TP" which is inconsistent with SA-182 andASME Code, Section I1, Part D, Table 1A.

b. Materials specification SA-1 55 is not listed in ASME Code Section II or ASME Code, Section II,Part D, Table 1A.

c. Table 6.1-1 lists SA-181 Grade 70 material. The applicant's reference to Grade 70 isinconsistent with material specification SA-181. SA-181 does list a Class 70 material.

The staff requests that the applicant perform a complete review of Tables 6.1-1 and 6.1-2 to verifytheir consistency with ASME Section II materials specifications and modify the DCD as necessary.

2. In RAI 06.01.01-2 the staff stated that each ESF system should be identified and broken downby components, such as valves, piping, fittings, accumulators, pumps, heat exchanges etc., so thestaff can identify the application of each material. The applicant lists plate, casting, and shapematerials but does not identify what components will be fabricated from these materials. The staffrequests that the applicant modify Tables 6.1-1 and 6.1-2, to be more specific and provide detailsrelated to components that will be fabricated from the materials listed in the Tables.

3. Tables 6.1-1 and 6.1-2 do not identify materials that will be used to fabricate the RWSP,containment liner or containment liner penetrations. The staff requests that the applicant includethese materials and the welding filler materials that will be used to fabricate these components.

4. DCD Section 6.0 identifies the containment systems, emergency core cooling systems,habitability systems and fission product removal systems as ESF systems but it is unclear fromTables 6.1-1 and 6.1-2 which materials will be used in these systems as well as the subsystems

6.1.1-1

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within each of these systems. The staff requests that the applicant provide the materialsspecifications and grades for all ESF systems and subsystems, by component type, in Tables6.1-1 or 6.1-2, including weld filler materials, or provide a reference to the section of the DCDwhere this information is located.

5. DCD Subsection 6.1.1.1 states that all ESF components in contact with core coolants andcontainment spray solutions are either fabricated from austenitic stainless steel or ferritic materialsclad with austenitic stainless steel. Tables 6.1-1 and 6.1-2 identify materials other that austeniticstainless steels. For example; Alloy 690 is listed in both Tables as well as low-alloy steels andcarbon steels. If the applicant intended to state that all pressure retaining ESF components incontact with core coolants and containment spray solutions are either fabricated from Alloy 690,fabricated from stainless steel or clad with austenitic stainless steel, the staff requests that theapplicant modify the DCD accordingly. If this is not the case the staff requests that the applicantmodifies the DCD to appropriately address this inconsistency.

ANSWER:

Table 6.1-1 and 6.1-2 will be revised to respond these NRC's questions.

Impact on DCD

Table 6.1-1 and 6.1-2 will be revised as follows:

Table 6.1-1 Principle Engineered Safety Feature Pressure Retaining MaterialSpecifications

ESF Component Material Class, Grade or TypeContainmentContainment Vessel Liner SA-516 Gr. 60, 70Penetrations

Plate SA-516 Gr. 60, 70SA-537 Cl. 1SA-240 Type 304

Pipe SA-106 Gr. A, BSA-312 Gr. TP304, TP304LSA-358 Gr. 304, 304L

Flued Head SA-266 Gr. 3SA-336 Gr. F22SA-182 Gr. F22, F304, F304L

Containment Spray SystemCS/RHR Pump

Pressure casting SA-351 Gr. CF-3 or CF-3MGr. CF-8 or CF-8M

Pressure forgings SA-182 Gr. F304 or F304L/LNGr. F316 or F316L/LN

Tubes and pipes SA-213 Type. 304 or 304LSA-312 Type. 316 or 316L

Closure Stud Bolts SA-193 Gr. B7 or B8SA 638 G660

Closure Stud Nuts SA-194 Gr. 7 or 8SA 638 G660

CS/RHR Heat ExchangerPressure plates SA-240 Type 304, 304L, 316,

6.1.1-2

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316LSA-516 Gr. 60, 70

Pressure forgings SA-105SA-182 Gr. F304, F304L, F316,

F316LSA-350 Gr. LF1, LF2

Tubes and pipes SA-213 Gr. TP304, TP304L,SA-312 TP316, TP316L

Closure bolts SA-193 Gr. B6, B7, B8, B16Closure nuts SA-194 Gr. 2, 2H, 4, 8, 8M, 16

PipingClass 1 Piping See Table 5.2.3-1Class 2 Piping SA-312 Gr. TP304, TP304L

SA-358 Gr. 304, 304LValve

Class 1 Valves See Table 5.2.3-1Class 2 Valves The material for Class 2

valves are the same asClass 1. See Table5.2.3-1

Fitting /.Flange SA-312 Gr. TP304, TP304LSA-358 Gr. 304, 304LSA-182 Gr. F304, F304LSA-479 Type 304, 304L

Emergency Core CoolingSystemSafety Injection PumpPressure casting SA-351 Gr. CF-3 or CF-3M

Gr. CF-8 or CF-8MPressure forgings SA-1 82 Gr. F304 or F304L/LN

ASTM A965 Gr. F316 or F316 L/LNSA-508 Gr. 3 CI.1

Tubes and pipes SA-213 Type 304 or 304LSA-312 Type 316 or 316L

Closure Stud Bolts SA-193 Gr. B6 or B7SA 638 G660

Closure Stud Nuts SA-194 Gr. 6 or 7SA 638 G660

Cladding, Buttering Type 308L/309LStainless Steel StripElectrode

AccumulatorPressure plates SA-516 Gr. 60 or 70Pressure forgings SA-105

SA-182 Gr. F304, F304L, F316or F316L

SA-350 Gr. LF1 or LF2Pipes SA-312 Gr. TP304, TP304L,

TP316 and TP316LClosure bolts SA-193 Gr. B6, B7, B8, B16,Closure nuts SA-194 Gr. 2, 2H, 4, 8, 8M or 16

Piping

6.1.1-3

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Class 1 Piping See Table 5.2.3-1Class 2 Piping SA-312 Gr. TP304, TP304L

SA-358 Gr. 304, 304LValvesClass 1 Valves See Table 5.2.3-1Class 2 Valves The material for Class 2

valves are the same asClass 1. See Table5.2.3-1

RWSP ASTM A 572 Grade 60ASTM A 240 Gr. TP304L

Fitting / Flange SA-312 Gr. TP304, TP304LSA-358 Gr. 304, 304LSA-182 Gr. F304, F304LSA-479 Type 304, 304L

ESF Filter SystemSee Subsection 6.5.1.7

Weld Filler Material

SFA-5.1 E6018, E7018, E6016,E7016

SFA-5.4 E308-16, E309-16,E308L-16, E309L-16

SFA-5.5 E9018-B3, E9016-B3SFA-5.9 ER308, ER309,

ER308LSFA-5.18 ER70S-2, ER70S-3,

ER70S-4, ER70S-6,ER70S-G

SFA-5.22 E309LT1-1/4,E308LT1-1/4

SFA-5.28 ER90S-B3

6.1 .1-4

Page 8: MIVTSUBISHI HEAVY INDUSTRIES, LTD. · SFA-5.22 E309LT1-1/4, E308LT1-1/4 SFA-5.28 ER90S-B3 Impact on COLA There is no impact on the COLA. Impact on PRA There is no impact on the PRA

Table 6.1-2 Principle Engineered Safety Features Materials Exposed to CoreCoolant and Containment Spray

ESF Component Material Class, Grade or TypeContainmentContainment Vessel Liner SA-516 Gr. 60, 70Penetrations

Plate SA-516 Gr. 60, 70SA-537 CI. 1SA-240 Type 304

Pipe SA-106 Gr. A, BSA-312 Gr. TP304, TP304LSA-358 Gr. 304, 304L

Flued Head SA-266 Gr. 3SA-336 Gr. F22SA-182 Gr. F22, F304, F304L

Containment Spray SystemPiping

Class 1 Piping See Table 5.2.3-1Class 2 Piping SA-312 Gr. TP304, TP304L

SA-358 Gr. 304, 304LValve

Class 1 Valves See Table 5.2.3-1Class 2 Valves The material for Class 2

valves are the same asClass 1. See Table5.2.3-1

Fitting / Flange SA-312 Gr. TP304, TP304LSA-358 Gr. 304, 304LSA-182 Gr. F304, F304LSA-479 Type 304, 304L

Emergency Core CoolingSystemAccumulatorPressure plates SA-516 Gr. 60, 70Pressure forgings SA-105

SA-182 Gr. F304, F304L, F316,F316L

SA-350 Gr. LF1, LF2Internal parts SA-240 Type 304, 304L, 316,

316LSA-182 Gr. F304, F304L, F316,

F316LPipes SA-312 Gr. TP304, TP304L,

TP316, TP316LClosure bolts SA-193 Gr. B6, B7, B8, B16Closure nuts SA-194 Gr. 2, 2H, 4, 8, 8M, 16

PipingClass 1 Piping See Table 5.2.3-1Class 2 Piping SA-312 Gr. TP304, TP304L

SA-358 Gr. 304, 304L

6.1.1-5

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ValvesClass 1 Valves See Table 5.2.3-1Class 2 Valves The material for Class 2

valves are the same asClass 1. See Table5.2.3-1

RWSP ASTM A 572 Gr. 60ASTM A 240 Gr. TP304L

Fitting / Flange SA-312 Gr. TP304, TP304LSA-358 Gr. 304, 304LSA-182 Gr. F304, F304LSA-479 Type 304, 304L

ESF Filter SystemSee Subsection 6.5.1.7

Weld Filler MaterialSFA-5.1 E6018, E7018, E6016,

E7016SFA-5.4 E308-16, E309-16,

E308L-16, E309L-16SFA-5.5 E9018-B3, E9016-B3SFA-5.9 ER308, ER309,

ER308LSFA-5.18 ER70S-2, ER70S-3,

ER70S-4, ER70S-6,ER70S-G

SFA-5.22 E309LT1-1/4,E308LT1-1/4

SFA-5.28 ER90S-B3

Impact on COLA

There is no impact on the COLA.

Impact on PRA

There is no impact on the PRA.

6.1.1-6

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

4/21/2009

US-APWR Design Certification

Mitsubishi Heavy Industries

Docket No. 52-021

RAI NO.: NO. 544-4267 REVISION 0

SRP SECTION: 06.01.01 - ENGINEERED SAFETY FEATURES MATERIALS

APPLICATION SECTION: 6.1.1

DATE OF RAI ISSUE: 3/2/2010

QUESTION NO.: 06.01.01-14

(a) In response to RAI 06.01.01-3, the applicant added Table 10.4.9-7 "Principle EmergencyFeedwater Materials" to the DCD. In addition, the applicant stated in its response that the EFWSwelding filler materials are located in Table 10.3.2-5. The staff reviewed Table 10.4.9-7 anddetermined that the applicant did not provide enough detail for the staff to complete its reviewbecause the applicant lists component types such as plate, shapes, casings, forgings and bars.The applicant did not identify the actual components that will be fabricated from theaforementioned product forms. The staff also reviewed Table 10.3.2-5 and could not find areference to Table 10.4.9-7 or Section 10.4.9 in Table 10.3.2-5. In addition, Table 10.4.9-7 listsstainless steel materials but Table 10.3.2-5 does not specify stainless steel welding filler materials.The staff requests that the applicant address the above and modify the DCD accordingly.

(b) In the applicant's response to RAI 06.01.01-3 the applicant verified, but did not include in theDCD, that the recommendations of RGs 1.31, 1.37, 1.44, and 1.50 are applied during fabricationof the EFWS. In addition, the applicant stated that preheat guidelines in ASME Code Section III,Appendix D, Article D-1000 for carbon steel and low alloy steel are applied to EFWS components.Although the staff finds the applicant's use of the above referenced RGs and ASME Code SectionIII preheat guidelines acceptable, the above information should be included in the DCD Section10.4.9. The applicant should also discuss its use of RG 1.36. The staff requests that the applicantaddress the above and modify the DCD accordingly.

(c) In the applicant's response to RAI 06.01.01-3, the applicant states that the main materials usedin the EFWS are ferritic materials. The staff notes that carbon and low alloy steels are susceptibleto general corrosion. Therefore, the staff requests that that the applicant modify FSAR Section10.4.7 to identify the corrosion allowance for low-alloy and carbon steel materials and state thetechnical basis for the corrosion allowance for low-alloy and carbon steels used in the EFWSsystems to ensure that it is sufficient for the design life of the plant.

ANSWER:

Answer to question (a)

Table 10.4.9-7 will be revised to incorporate the NRC comment as follows:

6.1.1-7

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Table 10.4.9-7 Principle Emergency Feedwater System Materials

ESF Component Material Class, Grade or TypeEmergency Feedwater PumpPressure casting SA-351 Gr. CF-3 or CF-3M

Gr. CF-8 or CF-8MPressure forgings SA-182 Gr. F304 or F304L/LN

Gr. F316 or F316L/LN

SA-266 Gr.2

Tubes and pipes SA-213 Gr. TP 304 or TP304LSA-312 Gr. TP316 or TP316L

Closure Stud Bolts SA-193 Gr. B6 or B7SA 638 G660

Closure Stud Nuts SA-1 94 Gr. 6 or 7SA-564 630

Cladding, Buttering Type 308L/309L StainlessSteel Strip Electrode

Piping SA-106 Gr. B

Valves SA-105SA-266 Gr. 2SA-216 Gr. WCB

Fitting / Flange SA-105SA-266 Gr. 2

Weld Filler Material SFA-5.1 E6018, E7018, E6016,E7016

SFA-5.18 ER70S-2, ER70S-3,ER70S-4, ER70S-6

Answer to question (b)

RG 1.50 is not applied to the EFWS since low-alloy steel is not used in the EFWS. RG 1.31 is notapplicable to the EFWS because the regulatory is applied for class 1 and 2 components not class3 such as EFWS. And also, RG1.44 is not applicable to EFWS since this requirement is foravoiding severe sensitization for systems which have reactor coolant with over 90 deg F such asRCS, CVCS, RHRS and CSS.

Subsection 10.4.9 will be revised to include that the recommendation of RGs 1.36 and 1.37 areapplied during fabrication of the EFWS and preheat guidelines in ASME Code Section III,Appendix D, Article D-1000 for carbon steel are applied to the EFWS component.

Answer to question (c)

Piping of the systems potentially susceptible to FAC are made from FAC resistant alloy or aredesigned to have sufficient FAC allowance as mentioned in the response to RAI 10.03.06-12.For other systems which are not susceptible to FAC like the EFWS, carbon steel piping is used,however, the piping have the minimum wall thickness which takes into account additionalthickness to the minus tolerances of pipe thickness, therefore, it is larger than the required wallthickness calculated based on the pressure design ofASME Sec. III NX-3641 orASME B31.1.And also, water chemistry condition of the EFWS is controlled to be low temperature ensuring littleturbidity which is not over 1 ppm as mentioned in DCD 10.4.9.2, D. Emergency Feedwater Pits.Under these conditions, effects of general corrosion are quite negligible compared to that of FAC.Therefore, margin for carbon steels used in the EFWS is sufficient for the design life of the plant.

6.1.1-8

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Impact on DCD

Table 10.4.9-7 will be revised to incorporate the NRC comment as shown above.The following sentence will be added to the last bullet of the DCD Subsection 10.4.9.1.

The recommendations of RGs 1.36 and 1.37 are applied during fabrication of the EFWSand preheat guidelines in ASME Code Section III, Appendix D, Article D-1000 for carbonsteel are applied to the EFS component.

Impact on COLA

There is no impact on the COLA.

Impact on PRA

There is no impact on the PRA.

6.1.1-9

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

4/21/2009

US-APWR Design Certification

Mitsubishi Heavy Industries

Docket No. 52-021

RAI NO.: NO. 544-4267 REVISION 0

SRP SECTION: 06.01.01 - ENGINEERED SAFETY FEATURES MATERIALS

APPLICATION SECTION: 6.1.1

DATE OF RAI ISSUE: 312/2010

QUESTION NO.: 06.01.01-15

In RAI 06.01.01-4, the staff requested that the applicant modify DCD Section 6.1.1 to identify thecorrosion allowance for ferritic materials. The applicant stated in its response to RAI 06.01.01-4that the failure of ferritic materials due to corrosion does not occur because their environmentalconditions are not severe. The staff notes that DCD Section 6.1.1.2.1 states that general corrosionis negligible with the exception of low alloy and carbon steels. If general corrosion is not negligiblefor low-alloy and carbon steels, there must be a corrosion allowance and a basis for the corrosionallowance for these materials. Therefore, the staff requests that the applicant modify FSARSection 6.1.1 to identify the corrosion allowance for low-alloy and carbon steel materials and statethe technical basis for the corrosion allowance for low-alloy and carbon steels used in ESFsystems to ensure that it is sufficient for the design life of the plant.

ANSWER:

The materials of ESF components, except the containment vessel liner, in contact with coolantsare either fabricated from or clad with austenitic stainless steel. The carbon steels used for suchas containment vessel liner are coated. So, general corrosion for ESF components is negligible.

Impact on DCD

There is no impact on the DCD

Impact on COLA

There is no impact on the COLA.

Impact on PRA

There is no impact on the PRA.

6.1.1-10

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

4/21/2009

US-APWR Design Certification

Mitsubishi Heavy Industries

Docket No. 52-021

RAI NO.: NO. 544-4267 REVISION 0

SRP SECTION: 06.01.01 - ENGINEERED SAFETY FEATURES MATERIALS

APPLICATION SECTION: 6.1.1

DATE OF RAI ISSUE: 3/2/2010

QUESTION NO.: 06.01.01-16

In RAI 06.01.01-9, the staff requested that the applicant modify FSAR Section 6.1.1 and Table6.1-1 to limit the carbon content of austenitic stainless steel to 0.03% maximum or provide atechnical basis for why this is not necessary. In response to the above RAI, the applicant revisedDCD section 6.1.1.1 to limit the carbon content of pressure retaining austenitic stainless steelcomponents to 0.03% maximum, however, the applicant did not provide a note to Table 6.1-1 thatstates that all pressure retaining austenitic stainless steel components have a maximum carboncontent of 0.03%. The staff requests that the applicant provide a note to Table 6.1-1 to address theabove.

ANSWER:A note to limit the carbon content of pressure retaining austenitic stainless steel will be added toTable 6.1-1. Please see the response for RAI 06.01.01-13.

Note: The response for RAI 06.01.01-9, UAP-HF-09370, dated July 10, 2009 has been amendedby letter UAP-HF-10085, dated March 30, 2010. Carbon content of austenitic stainless steel islimited to 0.05%. Therefore, note for Table 6.1-1 is based on this latest information.

Impact on DCD

Please see the response for RAI 06.01.1-13

Impact on COLA

There is no impact on the COLA.

Impact on PRA

There is no impact on the PRA.

6.1.1-11

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

4/21/2009

US-APWR Design Certification

Mitsubishi Heavy Industries

Docket No. 52-021

RAI NO.: NO. 544-4267 REVISION 0

SRP SECTION: 06.01.01 - ENGINEERED SAFETY FEATURES MATERIALS

APPLICATION SECTION: 6.1.1

DATE OF RAI ISSUE: 3/2/2010

QUESTION NO.: 06.01.01-17

In response to RAI 06.01.01-7, the applicant modified DCD Subsection 6.1.1.2.2 to state that itfollows the recommendations of RG 1.50. The staff notes that the applicant has placed the abovestatement in its application Subsection which specifies controls for austenitic stainless steels.Given that RG 1.50 applies to low alloy steels, the staff requests that the applicant modify the DCDto place this information in the appropriate DCD Subsection which is Subsection 6.1.1.1. Inaddition, the staff requests that the applicant modify Subsection 6.1.1.1 to include the applicantspreheat requirements for carbon steel and low-alloy steel components. Staff guidancerecommends the preheat guidelines in ASME Code Section III, Appendix D, Article D-1000 forcarbon steel and low alloy steel components.

ANSWER:

Low alloy steels are not applied to ESF components. Therefore, a description with regard to RG1.50 application to low alloy steels will not be added in the DCD.

Preheating for carbon steel and low alloy steel is applied in accordance with qualified weldingprocedure specification. So this description will be added in the DCD.

Impact on DCD

The 8t" paragraph of Subsection 6.1.1.1 will be revised as follows:

The control of welding, heat treatment, welder qualification, and contamination protection forESF ferritic and austenitic stainless steel material fabrication are described in Chapter 5,Subsection 5.2.3. Preheatinq for carbon steel and low alloy steel is applied in accordancewith qualified welding procedure specification.

Impact on COLA

There is no impact on the COLA.

Impact on PRA

There is no impact on the PRA.

6.1.1-12

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

4/14/2009

US-APWR Design Certification

Mitsubishi Heavy Industries

Docket No. 52-021

RAI NO.: NO. 544-4267 REVISION 0

SRP SECTION: 06.01.01 - ENGINEERED SAFETY FEATURES MATERIALS

APPLICATION SECTION: 6.1.1

DATE OF RAI ISSUE: 3/2/2010

QUESTION NO.: 06.01.01-18

In RAI 06.01.01-5, the staff requested that the applicant provide additional information regardingdissimilar metal welds in ESF systems. In the applicant's response, it discussed process controlsto minimize weld metal dilution and welding flaws. The applicant also identified the accumulator asa component that has dissimilar metal welds between carbon steel and austenitic stainless steelusing Alloy 52/152 weld filler material. In order to provide clarity as to the use of dissimilar metalwelds in ESF systems, the staff requests that the applicant address the following in the DCD.

(a) Provide a lists of ESF components, in the DCD, that utilize dissimilar metal welds, In addition,discuss how these welds are performed and verify that austenitic stainless steels are notsubjected to post weld heat treatment as part of the process.

(b) Specify the maximum amount of weld metal dilution (min amount of Chromium in completedweld) and state how maximum dilution is verified when performing weld procedure qualifications.

(c) State process controls used to minimize welding defects in DMWs. In the applicant's responseto RAI 06.01.01-5, the applicant stated that interpass treatment is performed but it is not clear tothe staff what the interpass treatment entails.

(d) State the maximum normal operating temperature of DMWs

ANSWER:

(a) Dissimilar metal welds in the ESF systems are utilized to only the section between theaccumulator and outlet piping. Carbon steel are buttered by Alloy 52/152 weld filler materialand subjected to post weld heat treatment in accordance with qualified WPS.The dissimilar metal weld between austenitic stainless steel and Alloy 52 are performed byAlloy 52/152 weld filler material without post weld heat treatment in accordance with qualifiedWPS.

(b) Minimum amount of Chromium in completed weld between austenitic stainless steel and Alloy52 was more than 12% in weld test coupon. Maximum dilution of dissimilar metal weldsbetween austenitic stainless steel and Alloy 52 was not verified in weld procedurequalification.

(c) The interpass treatment means the brushing or grinding the weld bead for removing the scaleon weld bead which may cause welding defects.

6.1.1-13

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(d) The maximum normal operating temperature of DMWs on the accumulator is 120 deg F. Thistemperature is the same as the maximum normal operation temperature inside thecontainment. The accumulator is located inside the containment and in standby condition atnormal operation. Therefore, the temperature of the accumulator and associated piping issimilar to the ambient temperature inside the containment.

Impact on DCD

There is no impact on the DCD.

Impact on COLA

There is no impact on the COLA.

Impact on PRA

There is no impact on the PRA.

6.1.1-14

Page 18: MIVTSUBISHI HEAVY INDUSTRIES, LTD. · SFA-5.22 E309LT1-1/4, E308LT1-1/4 SFA-5.28 ER90S-B3 Impact on COLA There is no impact on the COLA. Impact on PRA There is no impact on the PRA

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

4/21/2009

US-APWR Design Certification

Mitsubishi Heavy Industries

Docket No. 52-021

RAI NO.: NO. 544-4267 REVISION 0

SRP SECTION: 06.01.01 - ENGINEERED SAFETY FEATURES MATERIALS

APPLICATION SECTION: 6.1.1

DATE OF RAI ISSUE: 312/2010

QUESTION NO.: 06.01.01-19

The staff was unable to locate ITAAC for the containment liner system relative to verifyingcompliance with ASME Codes for fabrication, welding and nondestructive examination. The staffrequested, in RAI 06.01.01- that the applicant identify where the aforementioned information isaddressed in FSAR Tier 1 or modify the FSAR accordingly. The applicant responded to the aboveRAI and stated that the information is located in Tier 1, Table 2.11.1-2 which references Tier 1,Table 2.2-4. The staff reviewed the aforementioned Tier 1 Tables and finds them to be unclear andvague. Therefore, the staff requests that the applicant modify Tier 1 ITAAC for the pre-stressedconcrete containment vessel (PCCV) to provide clear ITAAC requirements for verifying that thePCCV liner meets ASME Code, Section III for materials, fabrication, welding and non-destructiveexamination of welds.

ANSWER:

As stated in the DCD Tier 1 Revision 2, Subsection 2.11.1.1 Design Description (page 2.11-2), thePCCV is designed and constructed in accordance with ASME Code Section II1. Design andanalysis procedures for the PCCV, including the steel liner, are subject to ASME III Division 2,Subarticle CC-3300. The liner is in the scope of the ASME design report referenced in ITAACItem 5 in DCD Tier 1 Table 2.2-4. ITAAC Item 1 in DCD Tier 1 Table 2.11.1-1 is revised tospecifically address conformance of the PCCV liner to ASME III with respect to materials,fabrication, installation (which includes welding per ASME III Subarticle NCA-9200) andnon-destructive examination of welds.

6.1.1-15

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Impact on DCD

Revise Tier 1 Table 2.11.1-2 as follows:

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

1.a The PCCV pressure l.a Refer to Table 2.2-4 ITAAC l.a Refer to Table 2.2-4 ITAACboundary is designed to Item 5. Item 5.meet ASME Code, SectionIII requirements.

i.b. The PCCV liner materials 1.b Inspection of the as-built 1.b ASME Code Data Report(s)of construction, PCCV and ASME Code (certified, when required byfabrication, and Data Report(s) will be the ASME Code) exist andinstallation meet ASME performed, conclude that the as-builtCode, Section III PCCV liner materials ofrequirements, construction, fabrication

and installation meet ASMECode, Section IIIrequirements.

1.c. The PCCV liner welds 1.c. Inspection of the as-built 1.c. ASME Code, Section IIImeet ASME Code, Section PCCV liner welds will be code reports exist andIII requirements for performed in accordance conclude that the ASMEnon-destructive with ASME Code, Section Code, Section IIIexamination. Ill. requirements are met for

non-destructiveexamination of the as-builtPCCV liner welds.

Impact on COLA

There is no impact on the COLA.

Impact on PRA

There is no impact on the PRA.

6.1.1-16