48
MITSUBISHI HEAVY INDUSTRIES, LTD. 16-5, KONAN 2-CHOME, MINATO-KU TOKYO, JAPAN, February 15, 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-10043 Subject: Transmittal of US-APWR DCD Tier I Revision 2 Update Reference: 1) Letter MHI Ref: UAP-HF-09490 from Y Ogata (MHI) to U.S. NRC, "Submittal of US-APWR Design Control Document Revision 2 in Support of Mitsubishi Heavy Industries, Ltd.'s Application for Design Certification of the US-APWR Standard Plant Design" dated on October 27, 2009. On December 14, 2009 Mitsubishi Heavy Industries, LTD ("MHI") and the U.S. Nuclear Regulatory Commission ("NRC") held a conference call to clarify and discuss the NRC's concerns related to the proposed resolution of the following former RAI responses. MHI's response to RAI 452, MHI's response to RAI 452, MHI's response to RAI 181, MHI's response to RAI 195, MHI's response to RAI 184, MHI's response to RAI 192, 14.03.02-12 (MHI ref. UAP-HF-09466, dated on 10/01/2009) 14.03.02-13 (MHI ref. UAP-HF-09485, dated on 10/08/2009) 14.03.05-04 (MHI ref. UAP-HF-09155, dated on 04/06/2009) 14.03.10-02 (MHI ref. UAP-HF-09076, dated on 03/05/2009) 14.03.07-27 (MHI ref. UAP-HF-09166, dated on 04/09/2009) 14.03.04-15 (MHI ref. UAP-HF-09167, dated on 04/10/2009) During the conference call, MHI agreed to revise the applicable portions of US-APWR DCD Tier 1 revision 2 (Reference 1). With this letter, MHI transmits to the NRC the proposed marked-up to be made to revision 2 of the DCD (Reference 1) based on the discussion during the conference call. This update will be incorporated into a future DCD revision. 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, 1/1 y1cc, Yoshiki Ogata, General Manager- APWR Promoting Department Mitsubishi Heavy Industries, LTD.

Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

  • Upload
    others

  • View
    4

  • Download
    0

Embed Size (px)

Citation preview

Page 1: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

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

TOKYO, JAPAN,

February 15, 2010

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

Attention: Mr. Jeffrey A. Ciocco,

Docket No. 52-021MHI Ref: UAP-HF-10043

Subject: Transmittal of US-APWR DCD Tier I Revision 2 Update

Reference: 1) Letter MHI Ref: UAP-HF-09490 from Y Ogata (MHI) to U.S. NRC, "Submittalof US-APWR Design Control Document Revision 2 in Support of MitsubishiHeavy Industries, Ltd.'s Application for Design Certification of the US-APWRStandard Plant Design" dated on October 27, 2009.

On December 14, 2009 Mitsubishi Heavy Industries, LTD ("MHI") and the U.S. NuclearRegulatory Commission ("NRC") held a conference call to clarify and discuss the NRC'sconcerns related to the proposed resolution of the following former RAI responses.

MHI's response to RAI 452,MHI's response to RAI 452,MHI's response to RAI 181,MHI's response to RAI 195,MHI's response to RAI 184,MHI's response to RAI 192,

14.03.02-12 (MHI ref. UAP-HF-09466, dated on 10/01/2009)14.03.02-13 (MHI ref. UAP-HF-09485, dated on 10/08/2009)14.03.05-04 (MHI ref. UAP-HF-09155, dated on 04/06/2009)14.03.10-02 (MHI ref. UAP-HF-09076, dated on 03/05/2009)14.03.07-27 (MHI ref. UAP-HF-09166, dated on 04/09/2009)14.03.04-15 (MHI ref. UAP-HF-09167, dated on 04/10/2009)

During the conference call, MHI agreed to revise the applicable portions of US-APWR DCDTier 1 revision 2 (Reference 1).

With this letter, MHI transmits to the NRC the proposed marked-up to be made to revision 2of the DCD (Reference 1) based on the discussion during the conference call. This updatewill be incorporated into a future DCD revision.

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,

1/1 y1cc,Yoshiki Ogata,General Manager- APWR Promoting DepartmentMitsubishi Heavy Industries, LTD.

Page 2: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

Enclosure:

1. US-APWR DCD Tier 1 Revision 2 Update

CC: J. A. Ciocco-C. K. Paulson

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

Page 3: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

Docket No.52-021MHI Ref: UAP-HF-10043

Enclosure I

UAP-HF-09510Docket No. 52-021

US-APWR DCD Tier I Revision 2 Update

February 2010

Attachment 1:

Attachment 2:

Attachment 3:

Attachment 4:

Attachment 5:

Attachment 6:

Proposed mark-up of the resolution of 2 nd round comments onMHI's response to RAI 452, 14.03.02-12

Proposed mark-up of the resolution of 2 nd round comments onMHI's response to RAI 452, 14.03.02-13

Proposed mark-up of the resolution of 2nd round comments onMHI's response to RAI 181, 14.03.05-04

Proposed mark-up of the resolution of 2 nd round comments onMHI's response to RAI 195, 14.03.10-02

Proposed mark-up of the resolution of 2nd round comments onMHI's response to RAI 184, 14.03.07-27

Proposed mark-up of the resolution of 2nd round comments onMHI's response to RAI 192, 14.03.04-15

Page 4: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

I Attachment 1-1 (Chapter 14) I14. VERIFICATION PROGRAMS US-APWR Design Control Document

Table 14.3-2 Example of ITAAC Table

(Sheet 3of 4)

Design Commitment Inspections, Tests, Acceptance CriteriaAnalyses

5.b Each of the seismic category 5.b.i Inspections will be 5.b.i Reports(s) document thatpiping, including supports, performed to verify that each of the as-builtidentified in Table _is the as-built seismic seismic Category I piping,designed to withstand Category I piping, including supports,combined normal and seismic including supports, identified in Table isdesign basis loads without a identified in Table _ supported by a seismicloss of its safety function, are supported by a Category I structure(s).

seismic Category Istructure(s).

5.b.ii Inspections and 5.b.ii A report exists andanalyses will be concludes that each of theperformed to verifyfer-the as-built seismic Category I

ofarepr piping, including supports,verifying that the as-built identified in Table canseismic Category I withstand combinedpiping, including normal and seismic designsupports, identified in basis loads without a lossTable _ can withstand of its safety function.combined normal andseismic design basisloads without a loss of itssafety function.

6.a The Class 1E equipment 6.a.i Type tests and/or 6.a.i The results of the typeidentified in Table as analyses will be tests and/or analysesbeing qualified for a harsh performed on Class 1 E conclude that the Class 1 Eenvironment is designed to equipment located in a equipment identified inwithstand the environmental harsh environment. Table as beingconditions that would exist qualified for a harshbefore, during, and following environment can withstanda design basis event without the environmentalloss of safety function for the conditions that would existtime required to perform the before, during, andsafety function. following a design basis

event without loss ofsafety function for the timerequired to perform thesafety function.

Tier 2 14.3-61

Revision 23

Tier 2 14.3-61 Revision 2_31

Page 5: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

I Attachment 1-2 (Tier 1)2.4 REACTOR SYSTEMS US-APWR Design Control Document

8.ii Inspections and analyses 8.ii A report exists andwill be performed to concludes that each of theverifyfor the-existencee.f.a as-built seismic Category Irepeot veFifying that the as- piping, including supports,built seismic Category I identified in Table 2.4.2-3piping, including supports, can withstand combinedidentified in Table 2.4.2-3 normal and seismic designcan withstand combined basis loads without a lossnormal and seismic design of its safety function.basis loads without a lossof its safety function.

Tier I 2.4-25

Revision 32

Tier I 2.4-25 Revision 32-1

Page 6: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.4 REACTOR SYSTEMS US-APWR Design Control Document

Table 2.4.4-5 Emergency Core Cooling System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 4 of 10)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b Each of the seismic Category 5.b.i Inspections will be 5.b.i Reports(s) document thatI piping, including supports, performed to verify that each of the as-built seismicidentified in Table 2.4.4-3 is the as-built seismic Category I piping, includingdesigned to withstand Category I piping, supports, identified in Tablecombined normal and seismic . including supports, 2.4.4-3 is supported by adesign basis loads without a identified in Table 2.4.4-3 seismic Category Iloss of its safety function. are supported by a structure(s).

seismic Category Istructure(s).

5.b.ii Inspections and analyses 5.b.ii A report exists andwill be performed to concludes that each of theverifdf-4he-exis - A as-built seismic Category Ia-report•.verify.ing that the piping, including supports,as-built seismic Category identified in Table 2.4.4-3I piping, including can withstand combinedsupports, identified in normal and seismic designTable 2.4.4-3.can basis loads without a loss ofwithstand combined its safety function.normal and seismicdesign basis loadswithout a loss of its safetyfunction.

6.a The Class 1 E equipment 6.a.i Type tests and/or 6.a.i The results of the type testsidentified in Table 2.4.4-2 as analyses will be and/or analyses concludebeing qualified for a harsh performed on the Class that the Class 1E Eenvironment is designed to 1 E equipment located in equipment identified inwithstand the environmental a harsh environment. Table 2.4.4-2 as beingconditions that would exist qualified for a harshbefore, duringl and following a environment can withstanddesign basis event without the environmentalloss of safety function for the conditions that would existtime required to perform the before, during, andsafety function. following a design basis

event without loss of safetyfunction for the timerequired to perform thesafety function.

6.a.ii Inspections will be 6.a.ii The as-built Class 1Eperformed on the as-built equipment and theClass I E equipment and associated wiring, cables,the associated wiring, -and terminations identifiedcables, and terminations in Table 2.4.4-2 as beinglocated in a harsh qualified for a harshenvironment, environment are bounded

by type tests and/oranalyses.

Tier 1 .2.4-50 Revision 32 1

Page 7: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.4 REACTOR SYSTEMS US-APWR Design Control Document

Table 2.4.5-5 Residual Heat Removal System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 4 of 8)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b.ii Inspections and 5.b.ii A report exists andanalyses will be concludes that each of theperformed to verifyfe& as-built seismic Category Ithe-ex-ist~ee-f-a-repe4 piping, including supports,verifying that the as-built identified in Table 2.4.5-3seismic Category I can withstand combinedpiping, including normal and seismic designsupports, identified in basis loads without a lossTable 2.4.5-3 can of its safety function.withstand combinednormal and seismicdesign basis loadswithout a loss of itssafety function.

6.a The Class 1E equipment 6.a.i Type tests and/or 6.a.i The results of the typeidentified in Table 2.4.5-2 as analyses will be tests and/or analysesbeing qualified for a harsh performed on the Class conclude that the Class 1 Eenvironment is designed to 1 E equipment located in equipment identified inwithstand the environmental a harsh environment. Table 2.4.5-2 as beingconditions that would exist qualified for a harshbefore, during, and following a environment can withstanddesign basis event without the environmentalloss of safety function for the conditions that would existtime required to perform the before, during, andsafety function. following a design basis

event without loss of safetyfunction for the timerequired to perform thesafety function.

6.a.ii Inspections will be 6.a.ii The as-built Class 1 Eperformed on the as- equipment and thebuilt Class I E equipment associated wiring, cables,and the associated and terminations identifiedwiring, cables, and in Table 2.4.5-2 as beingterminations located in a qualified for a harshharsh environment. environment are bounded

by type tests and/oranalyses.

6.b The Class 1 E equipment, 6.b A test will be performed 6.b The simulated test signalidentified in Table 2.4.5-2, is on each division of the exists at the as-built Classpowered from their respective as-built equipment by 1 E equipment identified inClass IE division, providing a simulated Table 2.4.5-2 under test.

test signal only in theClass 1 E division undertest.

Tier I 2.4-74

Revision 32Tier I 2.4674 Revision 321

Page 8: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.4 REACTOR SYSTEMS US-APWR Design Control Document

Table 2.4.6-5 Chemical and Volume Control System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 3 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.a The seismic Category I 5.a.i Inspections will be 5.a.i The as-built seismicequipment, identified in Table performed to verify that Category I as-built2.4.6-2, is designed to the seismic Category I as- equipment identified inwithstand seismic design built equipment and Table 2.4.6-2 is located inbasis loads without loss of valves identified in Table the containment or reactorsafety function. 2.4.6-2 are located in the building.

containment or reactorbuilding.

5.a.ii Type tests and/or 5.a.ii The results of the type testsanalyses of the seismic and/or analyses concludeCategory I equipment will that the seismic Category Ibe performed. equipment can withstand

seismic design basis loadswithout loss of safetyfunction.

5.a.iiiAn inspection will be 5.a.iiiThe as-built equipmentperformed on the as-built including anchorage isequipment including seismically bounded by theanchorage. tested or analyzed

conditions.

5.b Each of the seismic Category 5.b.i Inspections will be 5.b.i Reports(s) document thatI piping, including supports, performed to verify that each of the as-built seismicidentified in Table 2.4.6-3 is the as-built seismic Category I piping, includingdesigned to withstand Category I piping, supports, identified in Tablecombined normal and seismic including supports, 2.4.6-3 is supported by adesign basis loads without a identified in Table 2.4.6-3 seismic Category Iloss of its safety function. are supported by a structure(s).

seismic Category Istructure(s).

5.b.ii Inspections and analyses 5.b.ii A report exists andwill be performed to concludes that each ofverifyfor thee of the as-built seismicarepe~ify4Rg that the Category I piping,as-built seismic Category including supports,I piping, including identified in Table 2.4.6-3supports, identified in can withstand combinedTable 2.4.6-3 can normal and seismicwithstand combined design basis loadsnormal and seismic without a loss of its safetydesign basis loads function.without a loss of itssafety function.

Tier I 2.4-99

Revision 32

Tier I 2.4-99 Revision 32

Page 9: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.2-5 Main Steam Supply System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 4 of 7)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b.ii Inspections and analyses 5.b.ii A report exists andwill be performed to verifdfw concludes that each of thethe existence of a report as-built seismic Category Iverifying that the as-built piping, including supports,seismic Category I piping, identified in Table 2.7.1.2-including supports, identified 3 can withstand combinedin Table 2.7.1.2-3 can normal and seismic designwithstand combined normal basis loads without a lossand seismic design basis of its safety function.loads without a loss of itssafety function.

6.a The Class 1 E equipment 6.a.i Type tests and/or analyses 6.a.i The results of the typeidentified in Table 2.7.1.2- will be performed on the tests and/or analyses2 as being qualified for a Class 1 E equipment located conclude that the Class 1 Eharsh environment is in a harsh environment, equipment identified indesigned to withstand the Table 2.7.1.2-2 as beingenvironmental conditions qualified for a harshthat would exist before, environment can withstandduring, and following a the environmentaldesign basis event without conditions that would existloss of safety function for before, during, andthe time required to following a design basisperform the safety event without loss offunction, safety function for the time

required to perform thesafety function.

6.a.ii Inspections will be 6.a.ii The as-built Class 1 Eperformed on the as-built equipment and theClass 1 E equipment and the associated wiring, cables,associated wiring, cables, and terminations identifiedand terminations located in in Table 2.7.1.2-2 as beinga harsh environment, qualified for a harsh

environment are boundedby type tests and/oranalyses.

6.b The Class 1 E equipment, 6.b A test will be performed on 6.b The simulated test signalidentified in Table 2.7.1.2- each division of the as-built exists at the as-built Class2, is powered from their equipment by providing a 1 E equipment identified inrespective Class IE simulated test signal only in Table 2.7.1.2-2 under test.division. the Class 1E division under

test.

6.c Separation is provided 6.c Inspections of the as-built 6.c Physical separation or.between Class 1E Class 1 E divisional cables electrical isolation isdivisions, and between will be performed. provided between the as-Class 1 E divisions and built cables of Class 1 Enon-Class 1E cable. divisions and between

Class 1 E divisions andnon-Class 1 E cables.

7. Deleted. 7. Deleted. 7. Deleted.

Tier-1 2.7-15Revision 3_2

Page 10: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.9-5 Condensate and Feedwater System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 4 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b Each of the seismic Category I 5.b.i Inspections will be 5.b.i Reports(s) document thatpiping, including supports, performed to verify that the each of the as-built seismicidentified in Table 2.7.1.9-3 is as-built seismic Category I Category I piping, includingdesigned to withstand piping, including supports, supports, identified in Tablecombined normal and seismic identified in Table 2.7.1.9-3 2.7.1.9-3 is supported by adesign basis loads without a are supported by a seismic seismic Category Iloss of its safety function. Category I structure(s). structure(s).

5.b.ii Inspections and analyses 5.b.ii A report exists and concludeswill be performed for-the that each of the as-builtexistence of a Fcport seismic Category I piping,verifYiagLo verify that the including supports, identifiedas-built seismic Category I in Table 2.7.1.9-3 canpiping, including supports, withstand combined normalidentified in Table 2.7.1.9-3 and seismic design basiscan withstand combined loads without a loss of itsnormal and seismic design safety function.basis loads without a lossof its safety function.

6.a The Class 1 E equipment 6.a.i Type tests and/or analyses 6.a.i The results of the type testsidentified in Table 2.7.1.9-2 as will be performed on the and/or analyses concludebeing qualified for a harsh Class 1 E equipment that the Class 1 E equipmentenvironment is designed to located in a harsh identified in Table 2.7.1.9-2withstand the environmental environment, as being qualified for a harshconditions that would exist environment can withstandbefore, during, and following a the environmental conditionsdesign basis event without loss that would exist before,of safety function for the time during, and following arequired to perform the safety design basis event withoutfunction. loss of safety function for the

time required to perform thesafety function.

6.a.ii Inspections will be 6.a.ii The as-built Class 1 Eperformed on the as-built equipment and theClass 1 E equipment and associated wiring, cables,the associated wiring, and terminations identified incables, and terminations Table 2.7.1.9-2 as beinglocated in a harsh qualified for a harshenvironment, environment are bounded by

type tests and/or analyses.

Tier I 2.7-42

Revision 32Tier I 2.7-42

Revision 3_2 1

Page 11: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.10-4 Steam Generator Blowdown System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 4 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b Each of the seismic Category 5.b.i Inspections will be performed to 5.b.i Reports(s) document thatI piping, including supports, verify that the as-built seismic each of the as-built seismicidentified in Table 2.7.1.10-2 Category I piping, including Category I piping, includingis designed to withstand supports, identified in Table supports, identified in Tablecombined normal and seismic 2.7.1.10-2 are supported by a 2.7.1.10-2 is supported by adesign basis loads without a seismic Category I structure(s). seismic Category Iloss of its safety function. structure(s).

5.b.ii Inspections and analyses will 5.b.ii A report exists and.be performed to verifyfGF4he concludes that each of theexistenee.-of -a-repG4.ver.lfy-ing as-built seismic Category Ithat the as-built seismic piping, including supports,Category I piping, including identified in Table 2.7.1.10-2supports, identified in Table can withstand combined2.7.1.10-2 can withstand normal and seismic designcombined normal and seismic basis loads without a loss ofdesign basis loads without a its safety function.loss of its safety function.

6. The Class 1 E equipment, 6. A test will be performed on each 6. The simulated test signalidentified in Table 2.7.1.10-1, division of the as-built equipment exists at the as-built Class 1 Eis powered from their by providing a simulated test equipment identified in Tablerespective Class 1E division, signal only in the Class 1E 2.7.1.10-1 under test.

division under test.7. Separation is provided .7. Inspections of the as-built Class 7. Physical separation or

between Class 1E divisions, 1E divisional cables will be electrical isolationis. providedand between Class 1 E performed. between the as-built cables ofdivisions and non-Class 1 E Class 1 E divisions andequipment. between Class 1 E divisions

and non-Class 1 E cables.8. After loss of motive power, the 8. Tests of the as-built valves will 8. Upon loss of motive power,

air-operated valves, identified be performed under the each as-built remotelyin Table 2.7.1.10-1, assume conditions of loss of motive operated valves identified inthe indicated loss of motive power. Table 2.7.1.10-1 assumes thepower position. indicatedloss of motive power

position.9. Each mechanical division of 9. Inspections of the as-built 9. Each mechanical division of

the SGBDS except for piping SGBDS will be performed, the as-built SGBDS except for(Division A&B and C&D pairs) piping is physically separatedis physically separated from from other mechanicalthe other divisions with the divisions of the as-builtexception of reactor building SGBDS by structural barriersexterior and inside the with the exception of reactorcontainment. building exterior and inside

the containment.10. MCR alarms and displays of 10. Inspections will be performed for 10. The MCR alarms and displays

the parameters identified in retrievability of the SGBDS' identified in Table 2.7.1.10-3Table 2.7.1.10-3 can be - parameters in the as-built MCR. can be retrieved in the as-builtretrieved in the MCR. MCR.

11. RSC alarms, displays and 11.i Inspections of the as-built RSC 11.J Alarms, displays and controlscontrols are identified in Table alarms, displays and controls will exist on the as-built RSC as2.7.1.10-3. be performed. identified in Table 2.7.1.10-3.

Tier I 2.7-54

Revision 32

Tier I 2.7-54 Revision 32.

Page 12: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.11-5 Emergency Feedwater System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 4 of 7)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.a.iii Inspections will be 5.a.iii The as-built equipmentperformed on the as-built including anchorage isequipment including seismically bounded by theanchorage. tested or analyzed

conditions.

5.b Each of the seismic Category I 5.b.i Inspections will be 5.b.i Reports(s) document thatpiping, including supports, performed to verify that the each of the as-built seismicidentified in Table 2.7.1.11-3 is as-built seismic Category I Category I piping, includingdesigned to withstand piping, including supports, supports, identified in Tablecombined normal and seismic identified in Table 2.7.1.11- 2.7.1.11-3 is supported by adesign basis loads without a 3 are supported by a seismic Category Iloss of its safety function. seismic Category I structure(s).

structure(s).

5.b.ii Inspections and analyses 5.b.ii A report exists and concludeswill be performed to that each of the as-builtveriifFr-the-exizsterie-Gf-a seismic Category I piping,report erify..ng that the as- including supports, identifiedbuilt seismic Category I in Table-2.7.1.11-3 canpiping, including supports, withstand combined normalidentified in Table 2.7.1.11- and seismic design basis3 can withstand combined loads without a loss of itsnormal and seismic design safety function.basis loads without a lossof its safety function.

6.a The Class 1E equipment 6.a.i Type tests and/or analyses 6.a.i The results of the type testsidentified in Table 2.7.1.11-2 as will be performed on the and/or analyses concludebeing qualified for a harsh Class 1 E equipment that the Class 1 E equipmentenvironment is designed to located in a harsh identified in Table 2.7.1.11-2withstand the environmental environment, as being qualified for a harshconditions that would exist environment can Withstandbefore, during, and following a the environmental conditionsdesign basis event without loss that would exist before,of safety function for the time during, and following arequired to perform the safety design basis event withoutfunction. loss of safety function for the

time required to perform thesafety function.

6.a.ii Inspections will be 6.a.ii The as-built Class 1 Eperformed on the as-built equipment and theClass 1 E equipment and associated wiring, cables,the associated wiring, and terminations identified incables, and terminations Table 2.7.1.11-2 as beinglocated in a harsh qualified for a harshenvironment, environment are bounded by

type tests and/or analyses.

Tier I 2.7-81

Revision 32

Tier I 2.7-81 Revision .32 1

Page 13: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.3.1-5 Essential Service Water System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 3 of 5)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria4.b The ASME Code Section III 4.b. A hydrostatic test will be 4.b The results of the

piping, identified in Table performed on the as-built hydrostatic test of the as-2.7.3.1-3, retains its piping required by the ASME built piping identified inpressure boundary integrity Code Section III to be Table2.7.3.1-2 as ASMEat its design pressure. hydrostatically tested: Code Section III conform to

the requirements of theASME Code Section II1.

5.a The seismic Category I 5.a.i Inspections will be 5.a.i. The seismic Category I as-equipment identified in performed to verify that the built equipment identifiedTable 2.7.3.1-2 is designed seismic Category I as-built in Table 2.7.3.1-2 isto withstand seismic equipment identified in installed in the locationdesign basis loads without Table 2.7.3.1-2 is installed identified in Table 2.7.3.1-loss of safety function. in the location identified in 1.

Table 2.7.3.1-1.5.a.ii Type tests and/or analyses 5.a.ii The results of the type

of the seismic Category I tests and/or analysesequipment will be conclude that the seismicperformed. Category I equipment can

withstand seismic designbasis loads without loss ofsafety function.

5.a.iii Inspections will be 5.a.iii The as-built equipmentperformed on the as-built including anchorage isequipment including seismically bounded by theanchorage. tested or analyzed

conditions.5.b Each of the seismic 5.bi Inspections will be 5.b.i Reports(s) document that

Category I piping, including performed to verify that the each of the as-built seismicsupports, identified in as-built seismic Category I Category I piping, includingTable 2.7.3.1-3 is designed piping, including supports, supports, identified into withstand combined identified in Table 2.7.3.1-3 Table 2.7.3.1-3 isnormal and seismic design are supported by a seismic supported by a seismicbasis loads without a loss Category I structure(s). Category I structure(s).of its safety function.

5.b.ii Inspections and analyses 5.b.ii A report exists andwill be performed to concludes that each of theverifyfrtho t f as-built seismic Category Irepe4tefi that the as- piping, including supports,built seismic Category I identified in Table 2.7.3.1-3piping, including supports, can withstand combinedidentified in Table 2.7.3.1-3 normal and seismic designcan withstand combined basis loads without a lossnormal and seismic design of its safety function.basis loads without a lossof its safety function.

6.a The Class I E equipment 6.a A test will be performed on 6.a The simulated test signalidentified in Table 2.7.3.1-2 each division of the as-built exists at the as-built Classis powered from their equipment by providing a 1 E equipment identified inrespective Class 1 E division. simulated test signal only Table 2.7.3.1-2 under test.

in the Class 1 E divisionunder test.

Tier I 2.7-101

Revision 32

Tier I 2.7-101 Revision 32

Page 14: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.3.3-5 Component ICooling Water System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 4 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria5.b.ii Inspections and analyses 5.b.ii A report exists and

will be performed to concludes that each of theverifIfor the cxiztenp of a as-built seismic Category IePert VeFi that the as- piping, including supports,

built seismic Category I identified in Table 2.7.3.3-3piping, including supports, can withstand combinedidentified in Table 2.7.3.3-3 normal and seismic designcan withstand combined basis loads without a lossnormal and seismic design of its safety function.

,basis loads without a lossof its safety function.

6.a The applicable Class 1 E 6.a.i Type tests and/or analyses 6.a.i The results of the type testsequipment identified in will be performed on the and/or analyses concludeTable 2.7.3.3-2 as being Class 1 E equipment that the Class 1 Equalified for a harsh located in a harsh equipment identified inenvironment is designed to environment. Table 2.7.3.3-2 as beingwithstand the qualified for a harshenvironmental conditions environment can withstandthat would exist before, the environmentalduring, and following a conditions that would existdesign basis event without before, during, andloss of safety function for following a design basisthe time required to event without loss of safetyperform the safety function, function for the time

required to perform thesafety function.

6.a.ii An inspection will be 6.a.ii The as-built Class 1Eperformed on the as-built equipment and theClass 1 E equipment and associated wiring, cables,the associated wiring, and terminations identifiedcables, and terminations in Table 2.7.3.3-2, as beinglocated in a harsh qualified for a harshenvironment, environment are bounded

by type tests and/oranalyses.

6.b The Class 1 E equipment 6.b A test will be performed on 6.b The simulated test signalidentified in Table 2.7.3.3-2 each division of the as-built exists at the as-built Classis powered from their equipment by providing a 1 E equipment identified inrespective Class 1 E simulated test signal only in Table 2.7.3.3-2 under test.division, the Class 1 E division under

test.6.c Separation is provided 6.c Inspections of the as-built 6.c Physical separation or

between Class 1 E Class 1 E divisional cables electrical isolation isdivisions, and between will be performed. provided between the as-Class 1 E divisions and built cables of Class 1 Enon-Class 1 E cable. divisions and between

Class 1 E divisions andnon-Class 1 E cables.

Tier I 2.7-125

Revision 32

Tier1I 2.7-125 Revision 3-21

Page 15: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.3.5-5 Essential Chilled Water System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 4 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b.ii Inspections and analyses 5.b.ii A report exists andwill be performed to concludes that each of theveri ffr-the existeRnc of a as-built seismic Category Irepo-veifyýn that the as- piping, including supports,built seismic Category I identified in Table 2.7.3.5-piping, including supports, 3 can withstand combinedidentified in Table 2.7.3.5- normal and seismic design3 can withstand combined basis loads without a lossnormal and seismic design of its safety function.basis loads without a lossof its safety function.

6.a The Class 1 E equipment, 6.a A test will be performed on 6.a The simulated test signalidentified in Table 2.7.3.5- each division of the as- exists at the as-built Class2, is powered from their built equipment by 1 E equipment identified inrespective Class 1 E providing a simulated test Table 2.7.3.5-2 under test.division, signal only in the Class 1E

division under test.

6.b Separation is provided 6.b Inspections of the as-built 6.b Physical separation orbetween Class 1 E Class 1 E divisional cables electrical isolation isdivisions, and between will be performed. provided between the as-Class 1 E divisions and built cables of Class 1 Enon-Class 1 E cable. divisions and between

Class 1 E divisions andnon-Class 1 E cables.

7. The ECWS components 7.i An inspection for the 7.i A report exists andidentified in Table 2.7.3.5- existence of a report that concludes that the heat2 remove heat from determines the heat removal capability of thevarious cooling coils during removal capability of the as-built ECWS is greaterall plant operating as-built ECWS will be than or equal to the designconditions, including performed. values for all plantnormal plant operating, operating conditions,abnormal and accident including normal plantconditions. operating, abnormal and

accident conditions.

7.ii Tests will be performed to 7.ii The as-built ECWS pumpsconfirm that the as-built identified in Table 2.7.3.5-ECWS pumps identified in 2 are capable of achievingTable 2.7.3.5-2 provide their design flow rate.flow to the ECWS coolingunit.

8. The remotely operated 8. Test will be performed on 8. The as-built remotelyvalves identified in Table the as-built remotely operated valves identified2.7.3.5-2 as having PSMS operated valves listed in in Table 2.7.3.5-2 ascontrol perform an active Table 2.7.3.5-2 using having PSMS controlsafety function after simulated signals. perform the active functionreceiving a signal from identified in the table afterPSMS. receiving a simulated

signal.

Tier I 2.7-144 Revision _32 1

Page 16: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.6.3-5 Spent Fuel Pit Cooling and Purification System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 3 of 4)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria5. The seismic Category I 5.i Inspections will be 5.i The seismic Category I as-

equipment, identified in Table performed to verify that built equipment identified in2.7.6.3-1 is designed to the seismic Category I as- Table 2.7.6.3-1 is located inwithstand seismic design basis built equipment identified the containment and reactorloads without loss of safety in Table 2.7.6.3-1 is building.function. located in the containment

and reactor building.5.ii Type tests and/or 5.ii The results of the type tests

analyses of seismic and/or analyses concludeCategory I equipment will that the seismic Category Ibe performed. equipment can withstand

seismic design basis loadswithout loss of safetyfunction.

5.iii Inspections will be 5.iii The as-built equipmentperformed on the as-built including anchorage isequipment including seismically bounded by theanchorage. tested or analyzed

conditions.6. Each of the seismic Category I 6.i Inspections will be 6.i Reports(s) document that

piping, including supports, performed to verify that each of the as-built seismicidentified in Table 2.7.6.3-2 is the as-built seismic Category I piping, includingdesigned to withstand Category I piping, supports, identified in Tablecombined normal and seismic including supports, 2.7.6.3-2 is supported by adesign basis loads without a identified in Table 2.7.6.3- seismic Category Iloss of its safety function. 2 are supported by a structure(s).

seismic Category Istructure(s).

6.ii Inspections and analyses 6.ii A report exists andwill be performed to concludes that each of theverifFr-the-existenr -of-a as-built seismic Category IrepoWt.-verifying that the piping, including supports,as-built seismic Category I identified in Table 2.7.6.3-2piping, including supports, can withstand combinedidentified in Table 2.7.6.3- - normal and seismic design2 can withstand combined basis loads without a loss ofnormal and seismic design its safety function.basis loads without a lossof its safety function.

7.a The Class 1 E equipment 7.a A test will be performed on 7.a The simulated test signalidentified in Table 2.7.6.3-1 is each division of the as- exists at the as-built Classpowered from their respective built equipment by 1 E equipment identified inClass 1 E division, providing a simulated test Table 2.7.6.3-1, under test.

signal only in the Class 1Edivision under test.

7.b Separation is provided 7.b Inspections of the as-built 7.b Physical separation orbetween Class 1 E divisions, Class 1 E divisional cables . electrical isolation isand between Class 1 E will be performed. provided between the as-divisions and non-Class 1 E built cables of Class 1 Ecable. divisions and between

Class 1 E divisions and non-Class 1 E cables.

Tier I 2.7-247

Revision 32

Tier I 2.7-247 Revision 32

Page 17: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.6.7-6 Process and Post-accident Sampling System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 4 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b Each of the seismic Category I 5.b.i Inspections will be 5.b.i Reports(s) document thatpiping, including supports, performed to verify that each of the as-built seismicidentified in Table 2.7.6.7-3 is the as-built seismic Category I piping, including

'designed to withstand Category I piping, supports, identified in Tablecombined normal and seismic including supports, 2.7.6.7-3 is supported by adesign basis loads without a identified in Table 2.7.6.7- seismic Category Iloss of its safety function. 3 are supported by a structure(s).

seismic Category Istructure(s).

5.b.ii Inspections and analyses 5.b.ii A report exists andwill be performed to concludes that each of theverify f a as-built seismic Category Ireport verify.•ng that the piping, including supports,as-built seismic Category I identified in Table 2.7.6.7-3piping, including supports, can withstand combinedidentified in Table 2.7.6.7- normal and seismic design3 can withstand combined basis loads without a loss ofnormal and seismic design its safety function.basis loads without a lossof its safety function.

6.a The Class 1 E equipment 6.a.i Type tests and/or - 6.a.i The results of the type testsidentified in Tables 2.7.6.7-1 as analyses will be performed and/or analyses concludebeing qualified for a harsh on the Class 1 E that the Class 1 Eenvironment is designed to equipment located in a equipment identified inwithstand the environmental harsh environment. Table 2.7.6.7-1 as beingconditions that would exist qualified for a harshbefore, during, and following a environment withstands thedesign basis event without loss environmental conditionsof safety function for the time that would exist before,.required to perform the safety during, and following afunction, design basis event without

loss of their safety function,for the time required toperform the safety function.

6.a.ii An inspection will be 6.a.ii The as-built Class 1 Eperformed on the as-built equipment and theClass 1 E equipment and associated wiring, cables,the associated wiring, and terminations identifiedcables, and terminations in Table 2.7.6.7-1 as beinglocated in a harsh qualified for a harshenvironment, environment are bounded

by type tests, and/oranalyses.

6.b The Class 1 E equipment 6.b A test will be performed on 6.b The simulated test signalidentified in Table 2.7.6.7-1 is each division of the as- exists at the as-built Classpowered from their respective built equipment by 1 E equipment, identified inClass 1 E division, providing a simulated test Table 2.7.6.7-1, under test.

signal only in the Class 1 Edivision under test.

Tier 1 2.7-276 Revision 3,.2

Page 18: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.11 CONTAINMENT SYSTEMS US-APWR Design Control Document

Table 2.11.2-2 Containment Isolation System Inspections, Tests, Analyses,

and Acceptance Criteria (Sheet 3 of 8)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.a The seismic Category I 5.a.i Inspections will be 5.a.i The seismic Category I as-equipment is designed to performed to verify that built equipment is located inwithstand seismic design the seismic Category I as- the containment and thebasis loads without loss of built equipment are reactor building.safety function. located in the

containment and thereactor building.

5.a.ii Type tests and/or 5.a.ii The results of the type testsanalyses of seismic and/or analyses concludesCategory I equipment will that the seismic Category Ibe performed. equipment can withstand

seismic design basis loadswithout loss of safetyfunction.

5.a.iii Inspections will be 5.a.iii The as-built equipmentperformed the as-built including anchorage isequipment including seismically bounded by theanchorage. tested or analyzed

conditions.

5.b Each of the seismic 5.b.i Inspections will be 5.b.i Reports(s) document thatCategory I piping, including performed to verify that each of the as-built seismicsupports, is designed to the as-built seismic Category I piping, includingwithstand combined normal Category I piping, supports, is supported by aand seismic design basis including supports, are seismic Category Iloads without loss of its supported by a seismic structure(s).safety function. Category I structure(s).

5.b.ii Inspections and analyses 5.b.ii A report exists andwill be performed to verify concludes that each of thef4r the Bxisten¢e f a as-built seismic Category Irepotverifying that the piping, including supports,as-built seismic Category can withstand combinedI piping, including normaland seismic designsupports, can withstand basis loads without a loss ofcombined normal and its safety function.seismic design basisloads without a loss of itssafety function.

6.a The Class 1E equipment 6.a.i Type tests and/or 6.a.i The results of the type testsidentified in Table 2.11.2-1 as analyses will be and/or analyses concludebeing qualified for a harsh performed on the Class that the Class 1 E equipmentenvironment is designed to 1E equipment located in a identified in Table 2.11.2-1withstand the environmental harsh environment, as being qualified for aconditions that would exist harsh environment canbefore, during, and following withstand the environmentala design basis event without conditions that would existloss of safety function for the before, during, and followingtime required to perform the a design basis event withoutsafety function. loss of safety function for

the time required to performthe safety function.

Tier 1 2.11-23 Revision 32

Page 19: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.11 CONTAINMENT SYSTEMS US-APWR Design Control Document

Table 2.11.3-5 Containment Spray System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 4 of 7)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b.ii Inspections and analyse 5.b.ii A report exists andwill be performed to verify concludes that each of thefor the exi6t9RGe Gf a as-built seismic Category I

ing that the piping, including supports,as-built seismic Category identified in Table 2.11.3-31 piping, including can withstand combinedsupports, identified in normal and seismic designTable 2.11.3-3 can basis loads without a loss ofwithstand combined its safety function.normal and seismicdesign basis loadswithout a loss of its safetyfunction.

6.a The Class 1 E equipment 6.a.i Type tests and/or 6.a.i The results of the type testsidentified in Table 2.11.3-2 analyses will be and/or analyses concludesas being qualified for a performed on the Class that the Class 1 E equipmentharsh environment is 1 E equipment located in a identified in Table 2.11.3-2designed to withstand the harsh environment. as being qualified for aenvironmental conditions harsh environment canthat would exist before, withstand the environmentalduring, and following a conditions that would existdesign basis event without before, during, and followingloss of safety function for a design basis event withoutthe time required to perform loss of safety function forthe safety function. the time required to perform

the safety function.

6.a.ii Inspections will be 6.a.ii The as-built Class 1 Eperformed on the as-built equipment and theClass 1 E equipment and associated wiring, cables,-the associated wiring, and terminations identifiedcables, and terminations. in Table 2.113 -2 as beinglocated in a harsh qualified for a harshenvironment. environment are bounded

by type tests and/oranalyses.

6.b The Class I E equipment, 6.b A test will be performed 6.b The simulated test signalidentified in Table 2.11.3-2, on each division of the as- exists at the as-built Classis powered from their built equipment by 1 E equipment identified inrespective Class 1 E providing a simulated test Table 2.11.3-2 under test.division. signal only in the Class

1 E division under test.

6.c Separation is provided 6.c Inspections of the as-built 6.c Physical separation orbetween Class 1 E divisions, Class 1 E divisional cables electrical isolation isand between Class I E will be conducted. provided between the as-divisions and non-Class 1 E built cables of Class 1 Ecable. divisions and between

Class 1 E divisions and non-Class 1 E cables.

117.a Deleted. 7.a Deleted, Ta Deleted.

Tier 1 2.11-41 Revision 32

Page 20: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

I Attachment 2

2.4 REACTOR SYSTEMS US-APWR Design Control Document

Table 2.4.2-5 Reactor Coolant System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 7 of 7)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

15. RSC alarms displays and 15.i Inspections of the as-built 15.i Alarms, displays andcontrols are identified in RSC alarms, displays and controls exist on the as-Table 2.4.2-4. controls will be performed. built RSC as identified in

Table 2.4.2-4.

15.ii Tests of the as-built RSC 15.ii Controls exist to operatecontrols will be performed. each as-built RSC control

function identified in Table2.4.2-4.

16. Each of the as-built piping 16. Inspections of the as-built 16. The LBB acceptanceidentified in Table 2.4.2-3 piping will be performed criteria are met by the as-as designed for LBB meets based on the evaluation built piping and pipingthe LBB criteria, or an report for LBB or the materials, or the protectionevaluation is performed of protection from dynamic is.provided for the dynamicthe protection from the effects of a pipe break, as effects of the piping break.dynamic effects of a rupture specified in Section 2.3.of the piping. _

17. Controls exist in the MCR to 17. Tests will be performed on 17. Controls exist in the as-builtstart and stop the the as-built pressurizer MCR to start and stop thepressurizer heaters heaters listed in Table as-built pressurizer heatersidentified in Table 2.4.2-4. 2.4.2-4 using controls in the identified in Table 2.4.2-4.

as-built MCR.

Tier I 2.4-29

Revision 32

Tier I 2.4-29Revision 32 1

Page 21: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.4 REACTOR SYSTEMS US-APWR Design Control Document

Table 2.4.4-5 Emergency Core Cooling System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 10 of 10)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

11. MCR alarms and displays of 11. Inspections will be 11. MCR alarms and displaysthe parameters identified in performed for identified in Table 2.4.4-4Table 2.4.4-4 can be retrieved retrievability of the ECCS can be retrieved in the as-in the MCR. parameters in the as-built built MCR.

MCR.

12. RSC alarms, displays and 12.J Inspections of the as-built 12.i Alarms, displays andcontrols are identified in Table RSC alarms, displays controls exist on the as-built2.4.44. and controls will be RSC as identified in Table

performed. 2.4.4-4.

12.ii Tests of the as-built RSC 12.ii Controls exist to operatecontrols will be each as-built RSC controlperformed. function identified in Table

2.4.4-4.

13. Each of the as-built piping 13. Inspections of the as-built 13. The LBB acceptanceidentified in Table 2.4.4-3 as piping will be performed criteria are met by the as-designed for LBB meets the based on the evaluation - built piping and pipeLBB criteria, or an evaluation report for LBB or the materials, or the protectionis performed of the protection protection from dynamic is provided for the dynamicfrom the dynamic effects of a effects of a pipe break, as effects of the piping break.rupture of the line. specified in Section 2.3.

14.a The materials of construction 14.a Inspection of the certified 14.a The materials ofof the ASME Code Section ill, material test reports will construction of the ASMEClass I components, be performed. Code Section III, Class 1identified in Table 2.4.4-2, are components identified inin accordance with ASME Table 2.4.4-2 conform toCode requirements. the requirements of the

ASME Code.

14.b The materials of construction 14.b Inspection of the certified 14.b The materials ofof the ASME Code Section III, material test reports will construction of the ASMEClass 1 piping, identified in be performed. Code Section III, 'Class 1Table 2.4.4-3, are in piping identified in Tableaccordance with ASME Code 2.4.4-3 conform to therequirements. requirements of the ASME

Code.

Tier I 2.4-56

Revision 32

Tier I 2.4-56 Revision 3 .2 1

Page 22: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.4 REACTOR SYSTEMS US-APWR Design Control Document

Table 2.4.5-5 Residual Heat Removal System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 8 of 8)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

13. RSC alarms, displays and 13.i Inspections of the as 13.i Alarms, displays andcontrols are identified in Table built RSC alarms, controls exist on the as-2.4.5-4. displays and controls will built RSC as identified in

be performed. Table 2.4.5-4.

13.ii Tests of the as-built 13.ii Controls exist to operateRSC controls will be each as-built RSC controlperformed. function identified in Table

24.5-4.

14. Each of the as-built piping 14. Inspections of the as- 14. The LBB acceptanceidentified in Table 2.4.5-3 as built piping will be criteria are met by the as-designed for LBB meets the performed based on the built piping and pipeLBB criteria, or an evaluation evaluation report for the materials, or protection isis performed of the protection LBB or the protection provided for the dynamicfrom the dynamic effects of a from dynamic effects of effects of the piping break.rupture of the line. a pipe break, as

specified in Section 2.3.

15.a The materials of construction 15.a Inspection of the 15.a The materials ofof the ASME Code Section III, certified material test construction of the ASMEClass 1 components, identified reports will be Code Section III, Class 1in Table 2.4.5-2, are in performed. components identified inaccordance with ASME Code Table2.4.5-2 conform torequirements. the requirements of the

ASME Code.

15.b The materials of construction 15.b Inspection of the 15.b The materials ofof the ASME Code Section III, certified material test construction of the ASMEClass 1 piping, identified in reports will be Code Section III, Class 1Table 2.4.5-3, are in performed. piping identified in Tableaccordance with ASME Code 2.4.5-3 conform to therequirements. requirements of the ASME

Code.

Tier I 2.4-79

Revision 32

Tier I 2.4-79 Revision 321

Page 23: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.4 REACTOR SYSTEMS US-APWR Design Control Document

Table 2.4.6-5 Chemical and Volume Control System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 6 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

12. MCR alarms and displays of 12. Inspections will be 12. MCR alarms and displaysthe parameters identified in performed for retrievability identified in Table 2.4.6-4Table 2.4.6-4 can be of the CVCS parameters can be retrieved in the as-retrieved in the MCR. in the as-built MCR. built MCR.

13. RSC alarms, displays and 13.i Inspections of the as-built 13.i Alarms, displays andcontrols are identified in RSC alarms, displays and controls exist on the as-Table 2.4.6-4. controls will be performed. built RSC as identified in

Table 2.4.6-4.

13.ii Tests of the as-built RSC 13.ii Controls exist to operatecontrols will be performed, each as-built RSC control

function identified in Table2.4.6-4.

14.a The materials of construction 14.a Inspection of the certified 14.a The materials ofof the ASME Code Section III, material test reports will construction of the ASMEClass 1 components, be performed. Code Section III, Class 1identified in Table 2.4.6-2, are components identified inin accordance with ASME Table 2.4.6-2 conform toCode requirements. the requirements of the

ASME Code.

14.b The materials of construction 14.b Inspection of the certified 14.b The materials ofof the ASME Code Section III, material test reports will construction of the ASMEClass 1 piping, identified in be performed. Code Section III, Class 1Table 2.4.6-3, are in piping identified in Tableaccordance with ASME Code 2.4.6-3 conform to therequirements. requirements of the ASME

Code.

Tier I 2.4-102

Revision 32Tier I 2.4-102 Revision 32

Page 24: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.2-5 Main Steam Supply System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 6 of 7)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

9.d After loss of motive power, 9.d Tests of the as-built valves 9.d Upon loss of motivethe remotely operated will be performed under the power, each as-builtvalves, identified in Table conditions of loss of motive remotely operated valve2.7.1.2-2, assume the power. identified in Table 2.7.1.2-indicated loss of motive 2 assumes the indicatedpower position. loss of motive power

position.

9.e The MSIVs identified in 9.e.i Tests or type tests of'the 9.e.i Each MSIV changesTable 2.7.1.2-2 perform an MSIVs will be performed to position as indicated inactive safety function to demonstrate the capability Table 2.7.1.2-2 underchangeposition as of the valve to operate under design conditions.indicated in the table. its design conditions.

9.e.ii Tests of the as-built MSIVs 9.e.ii Each as-built MSIVwill be performed under pre- changes position asoperational flow, differential indicated in Table 2.7.1.2-pressure, and temperature 2 under pre-operationalconditions. test conditions.

10. MCR alarms and displays 10. Inspections will be 10. The MCR alarms andof the parameters performed for retrievability of displays identified in Tableidentified in Table 2.7.1.2- the MSS parameters in the 2.7.1.2-4 can be retrieved4 can be retrieved in the as-built MCR. in the as-built MCR.MCR.

11. RSC alarms, displays, and 1 1.i Inspections of the as-built 1 1.i Alarms, displays andcontrols are identified in RSC alarms; displays and controls exist on the as-Table 2.7.1.2-4. controls will be performed. built RSC as identified in

Table 2.7.1.2-4.

1i1.ii Tests of the as-built RSC 1 l.ii Controls exist to operatecontrols will be performed.- each as-built RSC control

function identified in Table2.7.1.2-4.

12. Each of the as-built piping 12. Inspections of the as-built 12. The LBB acceptanceidentified in Table 2.7.1.2- piping will be performed criteria are met by the as-3 as designed for leak based on the evaluation built piping and pipebefore break (LBB) meets report for LBB or the materials, or the protectionthe LBB criteria, or an protection from dynamic is provided for theevaluation is performed of effects of a pipe break, as dynamic effects of thethe protection from the specified in Section 2.3. piping break.dynamic effects of arupture of the line.

Tier I 2.7-17

Revision 32Tier 1 2.7-17 Revision 32

Page 25: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.9-5 Condensate and Feedwater System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 6 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

9.a The valves, identified in 9.a.i Tests or type tests of air 9.a.i Each air operated valveTable 2.7.1.9-2 perform an operated valves and and each MFIV changesactive safety function to MFIVs will be performed position as indicated inchange position as indicated that demonstrate the Table 2.7.1.9-2 underin the table, capability of the valve to design condition.

operate under its designconditions.

9.a.ii Tests of the as-built air 9.a.ii Each as-built air operatedoperated valves and valve and each as-builtMFIVs will be performed MFIV changes position asunder pre-operational indicated in Table 2.7.1.9-2flow, differential under the pre-operationalpressure, and test conditions.temperature conditions.

9.a.iii Tests of the as-built 9.a.iii Each as-built check valvecheck valves with active changes position assafety functions indicated in Table 2.7.1.9-identified in Table 2.2.7.1.9-2 will beperformed underpreoperational testpressure, temperature,and fluid flow conditions.

9.b After loss of motive power, 9.b Tests of the as-built 9.b Upon loss of motive power,the remotely operated valves, valves will be performed each as-built remotelyidentified in Table 2.7.1.9-2, under the conditions of operatedvalves identifiedassume the indicated loss of loss of motive power. in Table 2.7.1.9-2 assumesmotive power position, the indicated loss of motive

power position.

10. MCR alarms and displays of 10. Inspections will be 10. MCR alarms and displaysthe parameters identified in performed for identified in Table 2.7.1.9-4Table 2:7.1.9-4 can be retrievability of the CFS can be retrieved in the as-retrieved in the MCR. parameters in the as- built MCR.

built MCR.

11. RSC alarms, displays and 11.j Inspections of the as- 11.i Alarms, displays andcontrols are identified in built RSC alarms controls exist on the as-Table 2.7.1.9-4. displays and controls will built RSC as identified in

be performed. Table 2.7.1.9-4.

11.ii Tests of the as-built RSC 11.ii Controls exist to operatecontrols will be each as-built RSC controlperformed. function identified in Table

2.7.1.9-4.

Tier I 2.7-44

Revision 32Tier I 2.7-44 Revision 32

Page 26: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.10-4 Steam Generator Blowdown System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 4 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

5.b Each of the seismic Category 5.b.i Inspections will be performed to 5.b.i Reports(s) document thatI piping, including supports, verify that the as-built seismic each of the as-built seismicidentified in Table 2.7.1.10-2 Category I piping, including Category I piping, includingis designed to withstand supports, identified in Table supports, identified in Tablecombined normal and seismic 2.7.1.10-2 are supported by a 2.7.1.10-2 is supported by adesign basis loads without a seismic Category I structure(s). seismic Category Iloss of its safety function. structure(s).

5.b.ii Inspections and analyses will 5.b.ii A report exists andbe performed to verif -the concludes that each of theexistence-of..a report verifying as-built seismic Category Ithat the as-built seismic piping, including supports,Category I piping, including identified in Table 2.7.1.10-2supports, identified in Table can withstand combined2.7.1.10-2 can withstand normal and seismic designcombined normal and seismic basis loads without a loss ofdesign basis loads without a its safety function.loss of its safety function.

6. The Class 1 E equipment, 6. A test will be performed on each 6. The simulated test signalidentified in Table 2.7.1.10-1, division of the as-built equipment exists at the as-built Class 1 Eis powered from their by providing a simulated test equipment identified in Tablerespective Class 1E division, signal only in the Class 1E 2.7.1.10-1 under test.

division under test.7. Separation is provided 7. Inspections of the as-built Class 7. Physical separation or

between Class 1 E divisions, 1 E divisional cables will be electrical isolation is providedand between Class 1 E performed. between the as-built cables ofdivisions and non-Class 1 E Class 1 E divisions andequipment. between Class- 1 E divisions

and non-Class 1 E cables.8. After loss of motive power, the 8. Tests of the as-built valves will 8. Upon loss of motive power,

air-operated valves, identified be performed under the each as-built remotelyin Table 2.7.1.10-1, assume conditions of loss of motive operated valves identified inthe indicated loss of motive power. Table 2.7.1.10-1 assumes thepower position. indicated loss of motive power

position.9. Each mechanical division of 9. Inspections of the as-built 9. Each mechanical division of

the SGBDS except for piping SGBDS will be performed. the as-built SGBDS except for(Division A&B and C&D pairs) piping is physically separatedis physically separated from from other mechanicalthe other divisions with the divisions of the as-builtexception of reactor building SGBDS by structural barriersexterior and inside the with the exception of reactorcontainment. building exterior and inside

the containment.10. MCR alarms and displays of 10. Inspections will be performed for 10. The MCR alarms and displays

the parameters identified in retrievability of the SGBDS identified in Table 2.7.1.10-3Table 2.7.1.10-3 canbe parameters in the as-built MCR. can be retrieved in the as-builtretrieved in the MCR. MCR.

11. RSC alarms, displays and 11.i Inspections of the as-built RSC. 11.i Alarms, displays and controlscontrols are identified in Table alarms, displays and controls will exist on the as-built RSC as2.7.1.10-3. be performed. identified in Table 2.7.1.10-3.

Tier I 2.7-54

Revision 32

Tier I 2.7-54 Revision 32

Page 27: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.10-4 Steam Generator Blowdown System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 5 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

11.ii Tests of the as-built RSC 11 .ii Controls exist to operatecontrols will be performed, each as-built RSC control

function identified in Table27.110-3.

12. The Class 1E equipment 12;i Type tests and/or analyses 12.i The results of the typeidentified in Table 2.7.1.10-1 will be performed on the tests and/or analysesas being qualified for a harsh Class 1 E equipment located conclude that the Class 1 Eenvironment are designed to in a harsh environment, equipment identified inwithstand the environmental Table 2.7.1.10-1 as beingconditions that would exist qualified for a harshbefore, during, and following a environment can withstanddesign basis event without loss the environmentalof safety function for the time conditions that would existrequired to perform the safety before, during, andfunction. following a design basis

event without loss of safetyfunction for the timerequired to perform thesafety function.,

12.ii Inspections will be performed 12.ii The as-built Class 1Eon the as-built Class 1 E equipment and theequipment and the associated associated wiring, cables,wiring, cables, and and terminations identifiedterminations located in a in Table 2.7.1.10-1 asharsh environment, being qualified for a harsh

environment are boundedby type tests and/oranalyses.

13.a Controls exist in the MCR to 13.a Tests will be performed on 13.a Controls exist in the as-"open and close the remotely the as-built remotely operated built MCR to open andoperated valves identified in valves listed in Table close the as-built remotelyTable 2.7.1.10-3. 2.7.1.10-3 using controls in operated valves listed in

the as-built MCR. Table 2.7.1.10-3.

13.b The valves identified in 13.b Test will be performed on the 13b The as-built remotelyTable 2.7.1.10-1 as having as-built remotely operated operated valves identifiedPSMS control perform an valves listed in Table in Table 2.7.1.10-1 asactive safety function after 2.7.1.10-1 using simulated having PSMS controlreceiving a signal from signals. perform the active safetyPSMS. function identified in the

table after receiving asimulated signal.

Tier I 2.7-55

Revision 32

Tier I 2.7-55 Revision 3.2

Page 28: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.1.11-5 Emergency Feedwater System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 6 of 7)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

9.a The motor-operated valves and 9.a.i Tests or type tests of 9.a.i Each motor-operated valvecheck valves, identified in Table motor-operated valves will changes position as indicated2.7.1.11-2, perform an active be performed that in Table 2.7.1.11-2 undersafety function to change demonstrate the capability design conditions.position as indicated in the of the valve to operatetable. under its design conditions.

9.a.ii Tests of the as-built motor- 9.a.ii Each as-built motor-operatedoperated valves will be valve changes position asperformed under pre- indicated in Table 2.7.1.11-2operational flow, differential under pre-operational testpressure, and temperature conditions.conditions.

9.a.iii Tests of the as-built check 9.a.iii Each as-built check valvevalves with active safety. changes position as indicatedfunctions identified in Table in Table 2.7.1.11-2.2.7.1.2-2 will be performedunder pre-operational testpressure, temperature, andfluid flow conditions.

9.b After loss of motive power, the 9.b. Tests of the as-built valves 9.b Upon loss of motive power,remotely operated valves, will be performed under the each as-built remotelyidentified in Table 2.7.1.11-2, conditions of loss of motive operated valve identified inassume the indicated loss of power. Table 2.7.1.11-2 assumesmotive power position. the indicated loss of motive

power position.

10. MCR alarms and displays of the 10. Inspections will be 10. MCR alarms and displaysparameters identified in Table performed for retrievability identified in Table 2.7.1.11-42.7.1.11-4 can be retrieved in of the EFWS parameters in can be retrieved in the as-the MCR. the as-built MCR. built MCR.

11. RSC alarms, displays and 11.J Inspections of the as-built 11.i_ Alarms, displays and controlscontrols are identified in Table . RSC alarms, displays and exist on the as-built RSC as2.7.1.11-4. controls will be performed. identified in Table 2.7.1.11-4.

1 1ii Tests of the as-built RSC 11.ii Controls exist to operatecontrols will be performed. each as-built RSC control

function identified in Table2.7.1.11-4.

12. Each EFW pump delivers at 12 A test of each as-built EFW 12 From the result of analyses,least the minimum flow required pump will be performed to any two of the as-built EFWfor removal of core decay heat determine system flow vs. pumps deliver at least 705using the SGs against a SG SG pressure under gpm to the-any two of thepressure up to the set pressure preoperational condition. fourtwe SGs against a SGof the first stage of main steam Analyses will be performed pressure up to the setsafety valve plus 3 percent. to convert the test results pressure of the first stage of

to the design conditions, main steam safety valve plus3 percent.

Tier I 2.7-83

Revision 32Tier I 2.7-83 Revision 321

Page 29: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.3.1-5 Essential Service Water System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 5 of 5)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria9.a.iii Tests of the as-built check 9.a.iii Each as-built check valve

valves will be performed changes position asunder preoperational flow, indicated in Table 2.7.3.1-differential pressure, and 2.temperature conditions.

9.b Upon the receipt of an 9.b A test of each as-built 9.b The ESW discharge valveESWP start signal, the interlock for the essential closes when its respectiveessential service water service water discharge pump is not running. Upondischarge valve opens valve will be performed. the receipt of a simulatedautomatically. Each pump's using a simulated test ESWP start signal, the as-discharge valve is signal. built discharge valve for theinterlocked to close when respective pump starts tothe pump is not running or is open automatically after thetripped. The valve starts to pump starts.open after the respective The valve closes when thepump starts. pump is tripped.

9.c After loss of motive power, 9.c Tests of the as-built valves 9.c Upon loss of motive power,the remotely operated will be performed under the each as-built remotelyvalves, identified in Table conditions of loss of motive operated valve identified in2.7.3.1-2, assume the power. Table 2.7.3.1-2 assumes theindicated loss of motive indicated loss of motivepower position. power position.

10.a Controls exist in the MCR to 1O.a Tests will be performed on 10.a Controls exist in the as-builtstart and stop the pumps the as-built pumps listed in MCR to start and stop theidentified in Table 2.7.3.1-4. Table 2.7.3.1-4 using as-built pumps listed in

controls in the as-built MCR. Table 2.7.3.1-4.10.b The pumps identified in 10.b Tests will be performed on 1O.b The as-built pumps

Table 2.7.3.1-2 as having the as-built pumps listed in identified in Table 2.7.3.1-2PSMS control perform an Table 2.7.3.1-2 using as having PSMS controlactive safety function after simulated signals. perform the active safetyreceiving a signal from function identified in thePSMS. table after receiving a

simulated signal.11. MCR alarms and displays of 11. Inspections will be 11. The MCR alarms and

the parameters identified in performed for retrievability of displays identified in TableTable 2.7.3.1-4 can be the ESWS parameters in the 2.7.3.1-4 can be retrieved inretrieved in the MCR. as-built MCR. the as-built MCR.

12. RSC alarms, displays, and 12.i Inspections of the as-built 12.i Alarms, displays andcontrols are identified in RSC alarms, displays and controls exist on the as-builtTable 2.7.3.1-4. controls will be performed. RSC as identified in Table

2.7.3.1-4.12.ii Tests of the as-built RSC 12ii Controls exist to operate

controls will be performed. each as-built RSC controlfunction identified in Table2.7.3.1-4.

Tier I 2.7-103

Revision 32Tier I 2.7-103 Revision 32

Page 30: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.3.3-5 Component Cooling Water System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 6 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria9.b After loss of motive power, 9.b Tests of the as-built valves 9.b Upon loss of motive power,

the remotely operated will be performed under the - each as-built remotelyvalves, identified in Table conditions of loss of motive operated valve identified in2.7.3.3-2, assume the power. Table 2.7.3.3-2 assumesindicated loss of motive the indicated loss of motivepower. position. power position.

10.a Controls exist in the MCR 10.a Tests will be performed on 10.a Controls exist in the as-builtto start and stop the pumps the as-built pumps listed in MCR to start and stop theidentified in Table 2.7.3.3- Table 2.7.3.3-4 using as-built pumps listed in4. controls in the as-built Table 2.7.3.3-4.

MCR.10.b The pumps identified in 10.b Test will be performed on 10.b The as-built pumps

Table 2.7.3.3-2 as having the as-built pumps listed in identified in Table 2.7.3.3-2PSMS control perform an Table 2.7.3.3-2 using as having PSMS controlactive safety function after simulated signals. perform the active safety

- receiving a signal from function identified in thePSMS. table after receiving a

simulated signal.11. MCR alarms and displays 11. Inspections will be 11. The MCR alarms and

of the parameters identified performed for retrievability displays identified in Tablein Table 2.7.3.3-4 can be of the CCWS parameters in 2.7.3.3-4 can be retrievedretrieved in the MCR. the as-built MCR. in the as-built MCR.

12. RSC alarms, displays and 12.i Inspections of the as-built 12.i Alarms, displays andcontrols are identified in RSC alarms, displays and controls exist on the as-Table 2.7.3.3-4. controls will be performed. built RSC as identified in

Table 2.7.3.3-4.12.ii Tests of the as-built RSC 12.ii Controls exist to operate

controls will be performed. each as-built RSC contr6lfunction identified in Table2.7.3.3-4.

13. The CCW pumps have 13. Tests to measure the as- 13. The as-built system meetssufficient net positive built CCW pump suction the design, and thesuction head (NPSH). pressure will be performed. analysis confirms that the

Inspections and analyses NPSH available exceedsto determine NPSH the required NPSH.available to each pump willbe performed.

Tier I 2.7-127

Revision 32Tier I 2.7-127 Revision. 3-2

Page 31: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.3.5-5 Essential Chilled Water System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 6 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

11. MCR alarms and displays 11. Inspections will be 11. The MCR alarms andof the parameters performed for retrievability displays identified in Tableidentified in Table 2.7.3.5- of the ECWS parameters 2.7.3.5-4 can be retrieved4 can be retrieved in the in the as-built MCR. in the as-built MCR.MCR.

12. RSC alarms displays and 12.i Inspections of the as-built 12.i Alarms, displays andcontrols are identified in RSC alarms, displays and controls exist on the as-Table 2.7.3.5-4. controls will be performed built RSC as identified in

Table 2.7.3.5-4.

12,ii Tests of the as-built RSC 12,ii Controls exist to operatecontrols will be performed, each as-built RSC control

function identified in Table2,73,5-4

.13. The ECWS pumps have 13. Tests to measure the as- 13. The as-built system meetssufficient net positive built ECWS pump suction the design, and thesuction head (NPSH). pressure will be analysis confirms that the

performed. Inspections NPSH available exceedsand analysis to determine the required NPSH.NPSH available to eachpump will be performed.

Tier I 2.7-146

Revision 32

Tier I 2.7-146 •Revision 32 1

Page 32: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.5.1-3 Main Control Room HVAC System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 4 of 4)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

7. MCR alarms and displays of 7. Inspections will be performed 7. MCR alarms and displays,the MCR HVAC system for retrievability of the MCR identified in Table 2.7.5.1-2,parameters identified in HVAC system parameters in can be retrieved in the as-Table 2.7.5.1-2 can be the as-built MCR. built MCR.retrieved in the MCR.

8. RSC alarms, displays and 81i Inspections of the as-built 8.i Alarms, displays and controlscontrols are identified in RSC alarms, displays and, exist on the as-built RSC asTable 2.7.5.1-2. controls will be performed. identified in Table 2.7.5.1-2.

8,ii Tests of the as-built RSC 8.ii Controls exist to operatecontrols will be performed, each as-built RSC control

function identified in Table2.7.5.1-2.

Tier I 2.7-176

Revision 32

Tier I 2.7-176Revision 3_2 1

Page 33: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.5.2-3 Engineered Safety Features Ventilation System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 6 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

6.d The safeguard component 6.d Tests of the as-built 6.d The as-built safeguardarea HVAC system, safeguard component area component area HVACemergency feedwater pump HVAC system, emergency system, emergencyarea HVAC system, and the feedwater pump area feedwater pump area HVACsafety related component area HVAC system, and the system, and the safetyHVAC system air handling unit safety related component related component areafans identified in Table 2.7.5.2- area HVAC system air HVAC system air handling1 start after receiving a high handling unit fans will be unit fans identified in Tabletemperature signal. performed using a 2.7.5.2-1 start after

simulated signal. receiving a high temperaturesignal.

7. MCR alarms and displays of 7. Inspections will be 7. MCR alarms and displaysthe ESFVS parameters performed for retrievability identified in Table 2.7.5.2-2identified in Table 2.7.5.2-2 of the ESFVS parameters can be retrieved in the as-can be retrieved in the MCR. in the as-built MCR. built MCR.

8. RSC alarms, displays and 8.i Inspections of the as-built 8.i Alarms, displays andcontrols are identified in Table RSC alarms, displays and controls exist on the as-built2.7.5.2-2. controls will be performed. RSC as identified in Table

2.7.5.2-2.

8.ii Tests of the as-built RSC 8.ii Controls exist to operatecontrols will be performed. each as-built RSC control

function identified in Table2.7.5.2-2.

Tier I 2.7-206Revision 2.3

Page 34: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.5.4-3 Auxiliary Building Ventilation System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 2 of 3)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

4.a The isolation dampers 4.a Tests will be performed on 4.a Each as-built isolationidentified in Table 2.7.5.4-1 as the as-built isolation dampers identified in Tablehaving PSMS control, perform dampers in Table 2.7.5.4-1 2.7.5.4-1 as having PSMSan active safety function after using a simulated signal. control, perform the activereceiving a signal from PSMS. function identified in the

table after receiving asimulated signal.

4.b After loss of motive power, the 4.b Tests of the as-built 4.b Upon loss of motive power,isolation .dampers identified in isolation dampers will be each as-built isolationTable 2.7.5.4-1, assume the performed under the damper identified in Tableclosed position, conditions of loss of 2.7.5.4-1 assumes the

motive power. closed position.

4.c The fire dampers in ductwork 4.c Tests of the as-built fire 4.c Each as-built fire damper inthat penetrates fire barrier that dampers will be ductwork that penetrates fireare required to protect safe- performed. barrier that are required toshutdown capability close fully protect safe-shutdownwhen called upon to do so. capability close under

design air flow conditions.

5. Controls exist in the MCR to 5. Tests will be performed on 5. Controls exist in the as-builtclose the remotely operated the as-built remotely MCR to open and close theisolation dampers identified in operated isolation as-built remotely operatedTable 2.7.5.4-2. dampers listed in Table valves listed in Table

2.7.5.4-2 using controls in 2.7.5.4-2.the MCR.

6. MCR alarms and displays of 6. Inspections will be 6. MCRalarms and displaysthe parameters identified in performed for retrievability identified in Table 2.7.5.4-2Table 2.7.5.4-2 can be of the as-built ABVS can be retrieved in the as-retrieved in the MCR. parameters in the as-built built MCR.

MCR.

7. RSC alarms, displays and 7.J Inspections of the as-built 7.i Alarms, displays andcontrols are identified in Table RSC alarms, displays and controls exist on the as-built2.7.5.4-2. controls will be performed. -RSC as identified in Table

2.7.5.4-2.

7.ii Tests of the as-built RSC 7.ii Controls exist to operatecontrols will be performed. each as-built RSC control

function identified in Table2.7.5.4-2.

Tier I 2.7-228

Revision 32Tier I 2.7-228 Revision 3 .2 1

Page 35: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.6.3-5 Spent Fuel Pit Cooling and Purification System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 4 of 4)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria8. The SFPCS components 8.a An inspection for the 8.a A report exists and

identified in Table 2.7.6.3-1 existence of a report that concludes that the productremove the decay heat determines heat removal of the overall heat transfergenerated by the spent fuel capacity of the as-built coefficient and heatassemblies in the SFP during heat exchangers will be exchanger area of the SFPall plant operating conditions, performed. heat exchangers identifiedincluding normal plant in Table 2.7.6.3-1 is greateroperating, abnormal and than or equal to the designaccident conditions. values for all plant operating

conditions, including normalplant operating, abnormaland accident conditions.

8.b Tests will be performed to 8.b The as-built SFP pumpsconfirm that the as-built identified in Table 2.7.6.3-1SFP pumps can provide are capable of achievingflow to the SFP heat their design flow rate.exchangers.

9. MCR displays of the 9. Inspections will be 9. MCR displays identified inparameters identified in Table performed for the Table 2.7.6.3-3 can be2.7.6.3-3 can be retrieved in retrievability of the SFPCS retrieved in the as-builtthe MCR. parameters in the as-built MCR.

MCR.10. RSC displays and controls are 10.i Inspections of the as-built 10.J Displays and controls exist

identified in Table 2.7.6.3-3. RSC displays and controls on the as-built RSC aswill be performed. identified in Table 2.7.6.3-3.

10.ii Tests of the as-built RSC 10.ii Controls exist to operatecontrols will be performed. each as-built RSC control

function identified in Table2.76.3-3.

11. Controls exist in the MCR to 11. Tests will be performed on 11. Controls exist in the as-builtstart and stop the pumps the as-built pumps in MCR to start and stop theidentified in Table 2.7.6.3-3. Table 2.7.6.3-3 using as-built pumps listed in

controls in the as-built Table 2.7.6.3-3.MCR.

12. The check valves, identified in 12. Tests of the as-built check 12. Each as-built check valveTable 2.7.6.3-1, perform an valves will be performed changes position asactive safety function to under pre-operational indicated in Table 2.7.6.3-1change position as indicated in flow, differential pressure, under pre-operational testthe table. and temperature conditions.

conditions. II

Tier I 2.7-248

Revision 32

Tier I 2.7-248 Revision 32

Page 36: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

Table 2.7.6.7-5 Process and Post-accident Sampling System Inspections, Tests,Analyses, and Acceptance Criteria (Sheet 6 of 6)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

1O.a Controls exist in the MCR to' 1O.a Tests will be performed 10.a Controls exist in the as-close remotely operated on the as-built remotely built MCR to open andvalves identified in Table operated valves identified close the as-built remotely2.7.6.7-1. in Table 2.7.6.7-1 using operated valves identified

the controls in the MCR. in Table 2.7.6.7-1.

10.b The valves identified in Table 10.b Tests will be performed. 10.b The as-built remotely2.7.6.7-1 as having PSMS on the as-built remotely operated valves identifiedcontrol perform an active operated valves listed in in Table 2.7.6.7-1 assafety function after receiving Table 2.7.6.7-1 using having PSMS control,a signal from PSMS. simulated signals. perform the active function

identified in the table after-receiving a simulatedsignal.

11. After loss of motive power, 11. Tests of the as-built 11. After loss of motive power,the remotely operated valves valves will be performed each as-built remotelyidentified in Table 2.7.6.7-1 under the conditions of operated valve identified inassume the indicated loss of loss of motive power. Table 2.7.6.7-1 assumesmotive power position. the indicated loss of motive

power position.

12. MCR alarms and displays of 12. Inspections will be 12. MCR alarms and displaystheparameters identified in performed for identified in Table 2.7.6.7-4Table 2.7.6.7-4 can be retrievability of the PSS can be retrieved in the as-retrieved in the MCR. parameters in the as-built built MCR.

MCR.

13. RSC alarms, displays and 13.i Inspections of the as-built 13.i Alarms, displays andcontrols are identified in Table RSC alarms, displays controls exist on the as-2.7.6.7-4.. and controls will be built RSC as identified in

performed. Table 2.7.6.7-4.

13,ii Tests of the as-built RSC 13.ii Controls exist to operatecontrols will be each as-built RSC controlperformed. function identified in Table

2.7.6.7-4.

Tier I 2.7-278

Revision 32

Tier 1 2.7-278 Revision 3 -2-1

Page 37: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.11 CONTAINMENT SYSTEMS US-APWR Design Control Document

Table 2A11.2-2 Containment Isolation System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 7 of 8)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

8.xiv The CCWS CIVs close within 8.xiv Tests will be performed to 8.xiv The following as-built CCWSthe containment isolation verify as-built CCWS CIVs CIVs close within the requiredresponse time. close within the isolation times:

response times. 20 seconds

NCS-MOV-51 1,NCS-MOV-517

< 40 secondsNCS-MOV-402 A, B,NCS-MOV-436 A,B,NCS-MOV-438 A,B,NCS-MOV-531,NCS-MOV-537.

8.xv The PSS CIVs close within 8.xv Tests will be performed to 8.xv The following as-built PSSthe containment isolation verify as-built PSS CIVs CIVs close within the requiredresponse time. close within the isolation times:

response times. < 15 seconds

PSS-AOV-003,PSS-MOV-006,PSS-MOV-013,PSS-MOV-023,PSS-MOV-031 A,BPSS-AOV-062 A,B,C,D,PSS-AOV-063

9. The systems penetrating 9. Tests will be performed to 9. The as-built containmentcontainment retain their verify the as-built isolation valve leakage iscontainment inventory during containment isolation valve within design limits and iscontainment isolation, leakage in accordance with less than the allowable

10 CFR 50, Appendix J, leakage rate specified in 10Type C tests. CFR 50,.Appendix J.

10. Controls exist in the MCR to 10. Tests will be performed on 10. Controls exist in the as-builtopen and close the remotely the as-built remotely MCR operate to open andoperated valves identified in operated valves listed in close the as-built remotelyTable 2.11.2-3. Table 2.11.2-3 using operated valves listed in

controls in the as-built Table 2.11.2-3.MCR.

11 .a MCR alarms and displays of 11 .a Inspections will be 1 1.a The as-built MCR alarms andthe parameters identified in performed for retrievability displays identified in TableTable 2.11.2-3 can be of the CIS parameters in 2.11.2-3 can be retrieved inretrieved in the MCR. the as-built MCR. the as-built MCR.

11 .b RSC alarms, displays and 11.b_ Inspections of the as-built 1 l.b.i Alarms, displays and controlscontrols are identified in RSC alarms, displays and exist on the as-built RSC asTable 2.11.2-3. controls will be performed. identified in Table 2.11.2-3.

11.b.ii Tests of the as-built RSC 11.b.ii Controls exist to operatecontrols will be performed. each as-built RSC control

.function identified in Table2.11.2-3. -

Tier I 2.11-27 Revision _3-2

Page 38: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.11 CONTAINMENT SYSTEMS US-APWR Design Control Document

Table 2.11.3-5 Containment Spray System Inspections, Tests, Analyses,and Acceptance Criteria (Sheet 7 of 7)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

10.c An interlock is provided for 10.c Tests will be performed 10.c Each as-built interlock foreach division of CS/RHR to on each as-built interlock the RHR discharge linepreclude the simultaneous for the RHR discharge containment isolation valvesopening of both the RHR line containment isolation and the correspondingdischarge line containment valves and the containment spray headerisolation valves and the containment spray header containment isolation valvecorresponding containment containment isolation preclude the simultaneousspray header containment valve, opening of both the RHRisolation valve. discharge line containment

isolation valves and thecorresponding containmentspray header containmentisolation valve.

10.d An interlock is provided for 1O.d Tests will be performed 1O.d Each as-built interlock foreach division of CS/RHR to on each as-built interlock the containment sprayallow opening of the for the containment spray header containmentcontainment spray header header containment isolation valve andcontainment isolation valve isolation valves and corresponding two in-seriesonly if either or both of the CS/RHR pump hot leg CS/RHR pump hot legcorresponding two in-series isolation valves, isolation valves will allowCS/RHR pump hot leg opening of the containmentisolation valves are closed. spray header containment

isolation valve only if eitheror both of the cor respondingtwo in-series CS/RHR pumphot leg isolation valves areclosed.

11. MCR alarms and displays of 11. Inspections will be 11. MCR alarms and displaysthe parameters identified in performed for retrievability identified in Table 2.11.3-4Table 2.11.3-4 can be of the CSS parameters in can be retrieved in the as-retrieved in the MCR. the as-built MCR. built MCR.

12. RSC alarms, displays and 12.i Inspections of the as-built 12.J Alarms, displays andcontrols are identified in RSC alarms, displays and controls exist on the as-builtTable 2.11.3-4. controls will be RSC as identified in Table

performed. 2.11.3 -4.

12.ii 'Tests of the as-built RSC 12.ii Controls exist to operatecontrols will be each as-built RSC controlperformed. function identified in Table

2.11.3-4.

Tier I 2.11-44

Revision 32

Tier 1 2.11-44Revision 3_21

Page 39: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

Attachment 32.5 INSTRUMENTATION AND CONTROLS US-APWR Design Control Document

Table 2.5.1-6 RT System and ESF System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 2 of 8)

Design Commitment Inspections, Tests, Acceptance CriteriaAnalyses

6. The Class 1 E equipment 6J Type tests and/or 6J The results of the type testsidentified in Table 2.5.1-1 as analyses will be and/or analyses conclude thatbeing qualified for a harsh performed on Class the Class 1 E equipmentenvironment is designed to 1 E equipment identified in Table 2.5. 1 -1 aswithstand the environmental located in a harsh being qualified for a harshconditions that would exist environment. environment can withstand thebefore, during, and following a environmental conditions.design. basis event without lossof safety function for the time 6.ii Inspections will be 6.ii The as-built Class 1 Erequired to perform the safety performed on the equipment and the associatedfunction. as-built Class 1 E wiring, cables, and terminations

equipment and the identified in Table 2.5. 1 -1 asassociated wiring, being qualified for a harshcables, and environment are bounded byterminations located type tests and/or analyses.in a harshenvironment.

7. The RPS, ESFAS, SLS, safety 7. Type tests and/or 7. A report exists and concludesVDU processor, and safety VDU analyses will be that the RPS, ESFAS, SLS,are qualified to meet the performed on the safety VDU processor, andelectromagnetic conditions that equipment. safety VDU are qualified towould exist before, during, and meet the electromagneticfollowing a design basis conditions that would existaccident, with respect to its before, during, and following alocation in the facility, without design basis accident, withloss of safety function for the respect to its location in thetime required to perform the facility, without loss of safetysafety function. function for the time required to

perform the safety function.

8. The Class 1 E equipment listed in 8. An inspection of the 8. The as-built equipment listed inTable 2.5. 1 -1 is located in a as-built equipment Table 2.5. 1 -1 is located in afacility Area that provides location will be plant area that providesprotection from natural performed. protection from naturalphenomena hazards such as phenomena hazards such astornadoes, and accident related tornadoes, and accident relatedhazards such as missiles, pipe hazards such as missiles, pipebreaks and flooding. breaks and flooding.

9. The Class 1 E equipment listed in 9. Inspection of the as- 9. The Class 1 E equipment listedTable 2.5. 1 -1 is powered from built equipment will in Table 2.5. 1 -1 is poweredtwo safety related power be performed. from two safety related powersources: the first source is its sources: the first source is itsrespective- Class 1 E division and respective Class 1 E divisionthe second source is from and the second source is fromanother division to ensure another division to ensurereliable power to each division of reliable power to each divisionLhe PSIVIS. of the PSIVIS.

Tier I 2.6-11 Revision 32 1

Page 40: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.5 INSTRUMENTATION AND CONTROLS US-APWR Design Control Document

Table 2.5.1-6 RT System and ESF System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 5 of 8)

Design Commitment Inspections, Tests, Acceptance CriteriaAnalyses

17.a The PSMS is designed to 17.a An inspection of the 17a. The as-built PSMS is designedfacilitate the timely recognition, as-built PSMS will to facilitate the timelylocation, replacement, repair and be performed. recognition, location,adjustment of malfunctioning replacement, repair andcomponents or modules. adjustment of malfunctioning

components or modules.

17. b A single channel or division of 17. b Tests will be 17. b Asingle channel or divisionthe PSMS can be bypassed to performed to of the as-built PSMS can beallow on-line testing, confirm the as-built bypassed to allow on-linemaintenance or repair without channel or division testing, maintenance orimpeding the safety function, bypass capabilities repair without impeding the

and to confirm the safety function.function of thebypass interlocklogic.

18. The PSMS automatically 18. A test of the as-built 18. The as-built PSMSremoves operating bypasses PSMS will be automatically removeswhen permissive conditions are performed. operating bypasses whennot met. permissive conditions are not

met.

19. The PSMS setpoints are 19. An inspection will be 19. The as-built PSMS setpointsdetermined using a methodology performed to define are determined using thebased on proven nuclear the as-built PSMS acceptable methodology, whichindustry standards. This setpoints in provides allowance formethodology provides accordance with the uncertainties between analyticalallowance for uncertainties acceptable limits and device setpointsbetween analytical limits and methodology., based on proven nucleardevice setpoints. industry standards.

20. Each d-ivsion of the PSMS and 20. A test f the as W4il 20. Each dvision- of the as builfield equipment listed in Table equipment will be PSMS and field equipment2.5.1 1 is supplied from Meo perfeFmeDeleted. listed in Table 2.5.9 1 issafety-related-~s4-oe epled #rom t.AAD safety relatedSO~We Either poWer 69ource is Glees-I -qw&-efý*Fee&Eithersuffici8nt to power each divisio power source is 6uffieint tonf 4he-P-SMISDeleted. power each d'ivision of the as

built PSMS. Deleted.

21. The PSMS logic is designed to 21. A test will be 21. Each division of the as-builtfail to a safe state such that loss performed by PSMS will fail to a safe stateof electrical power to a division disconnecting the upon loss of electrical power toof PSMS results in a reactor trip electrical power to the division (i.e., results in acondition for that division. Loss each division of the reactor trip condition for thatof electrical power does not as-built PSMS. division), and loss of electricresult in ESF actuation. power does not result in ESF

actuation.

Tier I 2.5-14

Revision 32

Tier I -2.6-14Revision 3_2

Page 41: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.5 INSTRUMENTATION AND CONTROLS US-APWR Design Control Document

Table 2.5.1-6 RT System and ESF System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 7 of 8)

Design Commitment Inspections, Tests, Acceptance CriteriaAnalyses

26. A signal selector algorithm (SSA) 26. An inspection of the 26. The as-built PSMS and PCMSis provided in the PCMS for the as-built SSA conform to the functionalmonitoring variables as listed in functional arrangement of the SSATable 2.5.1-5 to ensure the arrangement will be functions as described in thePCMS does not take an performed. design description and Tableerroneous control action that 2.5.1-5.results in a condition whichrequires RT or ESF action toconsider a single instrumentchannel failure or a single RPStrain failure.

27. Input sensors from each division 27. An inspection of the 27. The input sensors from eachof the PSMS are compared as-built PSMS and division of the as-built PSMScontinuously in the PCMS to PCMS functions will are compared continuously indetect abnormal deviations for be performed. the as-built PCMS to detectchecking the operational abnormal deviations.availability of each division of thePSMS input sensor that may berequired for a safety functionduring reactor operation.

28. The spatially dependent sensors 28. An inspection of the 28. The as-built PSMS includes thethat are required for protective as-built spatially minimum number and locationsactions are identified in Table dependent sensors of spatially dependent sensors2.5.1-2 and Table 2.5.1-3. required for that are required for protective

protective actions actions as identified in Tablewill be performed. 2.5.1-2 and Table 2.5.1-3.

29a. ESF systems are automatically 29a.A test of the as-built 29a. As-built ESF systems areinitiated from signals that PSMS will be automatically initiated fromoriginate in the RPS. performed. signals that originate in the as-

built RPS.

29b. Manual actuation of ESF 29b.A test of the as-built 29b. Manual actuation of the as-builtsystems is carried out through a PSMS will be ESF systems is carried outdiverse signal path that performed. through a diverse signal pathbypasses the RPS. that bypasses the as-built RPS.

Tier 1 2.5-16 Revision 32

'3

Page 42: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

Attachment 4

US-APWR Design Control Document2.7 PLANT SYSTEMS

Table 2.7.6.4-2 Light Load Handling System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 3 of 3)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

6. The fuel handling machine 6. Test of the as-built 6. The as-built fuel handlingutilizes electrical interlocks, electrical interlocks, limit machine utilizes electricallimit switches, and switches, and interlocks, limit switches,mechanical stops to: mechanical stops of the and mechanical stops to:

a) prevent damage to a fuel as-built fuel handling a) prevent damage to a fuelassembly, machine will be assembly,

b) assure appropriate performed, including: b) assure appropriateradiation shielding depth a) Operating the open radiation shielding depthbelow the water level in the controls of the gripper below the water level inreactor cavity, while suspending a the reactor cavity.dummy fuel assembly. teratrcvW

c) monitor the fuel assembly c) monitor the fuel assemblyload for imparted loads b) Attempting to raise a load for imparted loadsgreater than the nominal dummy fuel assembly greater than the nominalweight of the fuel above a preset height. weight of the fuelassembly. c) Attempting to lift a assembly.

dummy assembly that isheavier than the nominalfuel assembly.

7. The fuel transfer tube is 7J Inspections will be 7.i Design documentationdesigned and constructed conducted of the exists and concludes thatin accordance with ASME fabrication and the as-built fuel transferCode Section III installation of as-built fuel tube is fabricated,requirements. transfer tube. installed, and inspected

in accordance with ASMECode Section Illrequirements.

7.ii Analysis will be 7,ii The analysis concludesconducted to reconcile that the as-built fuelthe as-designed and as- transfer tube isbuilt information with the reconciled with theASME design design documents.documentation.

8. Pressure boundary welds 8, Inspections of the as- 8, The ASME Code Sectionof the fuel transfer tube built pressure boundary III code reports exist andmeet ASME Code Section welds will be performed conclude that the ASMEIII requirements for non- in accordance with the Code Section IIIdestructive examination of ASME Code Section III. requirements are met forwelds. non-destructive

examination of the as-built p~ressure boundarywelds.

9. The fuel transfer tube 9, A pressure test will be 9. The results of theretains the pressure performed on'the as-built pressure test of the as-boundary integrity at the fuel transfer tube built fuel transfer tubedesign pressure, required to be conform with the

hydrostatically examined requirements in theby applicable ASME applicable ASME Code.code.

Tier I 2.7-255 Revision 32-

Page 43: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

7. IAAC or uel transfer tube: Refpr to DGCD Tier I Table, 2.11.2 2, IT.AAC items 1, 2b, 3b, and lb.

Tier I 2.7-256

Revision 32

Tier I 2.7-266 Revision 32

Page 44: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.10 EMERGENCY. PLANNING' US-APWR Design Control Document

2.10.2 Inspections, Tests, Analyses, and Acceptance Criteria

Table 2.10-1 describes ITAAC for emergency planning.

Table 2.10-1 Emergency Planning Inspections, Tests, Analyses,and Acceptance Criteria

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

1. The TSC floor space is at 1. An inspection of the as-built 1. The as-built TSC has at leastleast 1875 ft2 (75 ft2 for each TSC floor area will be 1875 ft2 of floor space.of at least 25 persons). performed.

2. The TSC is located close to 2. An inspection will be performed 2. Walking between the as-builtthe MCR. for the location of the as-built TSC and MCR takes no more

TSC relative to the as-built than 2 minutes.MCR. -

3: The TSC provides a habitable 3. See Table 2:7.5.4-3, ITAAC 3. See Table 2.7.5.4-3, ITAACworkspace environment. Item 8. Item 8.

4. Adequate emergency 4. See Table 2.7.6.10-1. ITAAC 4. See Table 2.7.6.10-1, IjAACcommunications systems are Items 2, 3, and 4 and Table Items 2. 3. and 4 and Tablein place. 2.9-1, ITAAC Items 7.k and 7.1. 2.9-1, ITAAC Items 7.k and 7.1.

Tier I 2.10-2

Revision 32

Tier I 2.10-2Revision 3.2_ 1

Page 45: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.8 RADIATION PROTECTION US-APWR Design Control Document

Table 2.8-1 Radiation ProtectionInspections, Tests, Analyses, and Acceptance Criteria

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

1.a Shielding walls and floors l.a Inspections of the as-built 1-.a The as-built shieldinglisted in Table 2.2-2 are shielding walls and floors walls and floors listed inprovided to maintain the thicknesses will be performed. Table 2.2-2 are consistentmaximum radiation levels Refer to Table 2.2 4 !TAAC with the designedspecified in Table 2.8-2. lte,_ý concrete wall and floor

thicknesses.

Refer to Table 2.2 4

1.b Shielding walls and floors in 1.b Inspections of the as-built 1 .b The as-built shieldingthe auxiliary building are shielding walls and floors walls and floors in theprovided to maintain the thicknesses will be performed. auxiliary building aremaximum radiation levels consistent with thespecified in Table 2.8-2. designed concrete wall

and floor thicknesses.

2. Area radiation and airborne 2. Refer to Table 2.7.6.13-3 2. Refer to Table 2.7.6.13-3radioactivity monitoring ITAAC Item 1. ITAAC Item 1.systems are provided tomonitor radioactivityconcentrations.

3. Ventilation flow for the 3. Tests of the as-built 3. The as-built containmentradioactive controlled area is containment purge system purge system andprovided to control the and auxiliary building HVAC auxiliary building HVACconcentrations of airborne system will be performed. provide ventilation flow toradioactivity specified in 10 control the concentrationsCFR 20 Appendix B. of airborne radioactivity

specified in 10 CFR 20Appendix B.

Table 2.8-2 Radiation Zone Designations

Zone Dose RateI <50.25 mrem/hII <1.0 mrem/hIII <2.5 mrem/hIV 515.0 mrem/hV <100.0 mrem/h

VI <1.0 rem/hVII 510.0 rem/hVill <100.0 rem/hIX <5500.0 rad/hX >500.0 rad/h

Tier I 2.8-2Revision -2_31

Page 46: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

Attachment 5US-APWR Design Control Document2.7 PLANT SYSTEMS

Table 2.7.5.3-1 Containment Ventilation System Inspections, Tests, Analyses, andAcceptance Criteria

Design Commitment Inspections, Tests, Analyses Acceptance Criteria

1. The functional arrangement of 1. Inspections of the as-built 1. The as-built CVVS conformsthe CWS is as described in CVVS will be performed. with the functionalthe Design Description of this arrangement as described inSubsection 2.7.5.3.1. Design Description of this

Subsection 2.7.5.3.1.

2. Deleted. 2. Deleted. 2. Deleted.-

Tier I 2.7-217

Revision 32

Tier 1 2.7-217 Revision 3 .2 1

Page 47: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

2.7 PLANT SYSTEMS US-APWR Design Control Document

There is no important system operation.

Alarms, Displays, and Controls

There are no important alarms, displays, and controls.

Logic

There is no logic needed for direct safety functions related to the reactor cavity coolingsystem.

Interlocks

There are no interlocks needed for direct safety functions related to the reactor cavity

cooling system.

Class IE Electrical Power Sources and Divisions

Not applicable.

Equipment to be Qualified for Harsh Environments

Not applicable.,

Interface Requirements

There are no safety-related interfaces with systems outside of the certified design.

Numeric Performance Values

Not applicable.

2.7.5.3.2 Inspections, Tests, Analyses, and Acceptance Criteria

Table 2.7.5.3-1 specifies the inspections, tests, analyses, and associated acceptancecriteria for the CWS. Table-2.-1.22--speGifies the ITAAC f9r the non E^WS pipin•gsystem and comnponentS that are part Af t e CIS that ,uple ,coling water tot-hecontainR.ent fan coo.er unit and ,RDM cooling unit cGOolig coil The ITAAC associatedwith the GVVS-equipment, components and piping of the CWS and non-ECWS-arnd thatalso comprise a portion of the CIS, are described in Table 2.11.2-2.

Tier 1 2.7-216 Revision 32

Page 48: Transmittal of US-APWR DCD Tier 1 Revision 2 Update.Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Mr. Jeffrey A. Ciocco, Docket No

Attachment 6US-APWR Design Control Document2.7 PLANT SYSTEMS

Table 2.7.3.1-5 Essential Service Water System Inspections, Tests, Analyses, andAcceptance Criteria (Sheet 4 of 5)

Design Commitment Inspections, Tests, Analyses Acceptance Criteria6.b Separation is provided 6.b Inspections of the as-built 6.b Physical separation or

between Class 1 E divisions, Class 1 E divisional cables electrical isolation isand between Class 1 E will be performed. provided between the as-divisions and non-Class 1 E built cables of Class 1Ecable. divisions and between Class

1 E divisions and non-Class1 E cables.

7. The ESWS components 7.i An inspection for the 7.i A reportexists andidentified in Table 2.7.3.1-2 existence of a report that concludes that the heatprovide adequate cooling determines the heat removal removal capabili of the as-water to the CCW heat capability of the as-built built ESWS providesexchangers and the ESWS will be performed. adequate oG&g .iwater-teessential chiller units of the the-CCW heat exchangersECWS during all plant and the essential chilleroperating conditions, units of the ECWS is greaterincluding normal plant than or equal to the desiqnoperating, abnormal and value fordu4ni all plantaccident conditions. operating conditions,

including normal plantoperating, abnormal andaccident conditions.

7.ii Tests will be performed to 7.ii The as-built ESWS pumps•confirm that the as-built identified in Table 2.7.3.1-2ESWS pumps can provide are capable of achievingflow to the CCW heat their design flow rate.exchangers and theessential chiller units of theECWS.

8. Controls exist in the MCR to 8. Tests will be performed on 8. Controls exist in the as-builtopen and close the remotely the as-built remotely MCR to open and close theoperated valves identified in operated valves listed in as-built remotely operatedTable 2.7.3.1-2. Table 2.7.3.1-2 using valves listed in Table

controls in the as-built MCR. 2.7.3.1-2.9.a The remotely operated and 9.a.i Tests or type tests of the 9.a.i Each remotely operated

check valves, identified in remotely operated valves valve changes position asTable 2.7.3.1-2, perform an will be performed that indicated in Table 2.7.3.1-2active safety function to demonstrate the capability under design conditions.change position as indicated of the valve to operate underin the table. its design conditions.

9.a.ii Tests of the as-built 9.a.ii Each as-built remotelyremotely operated valves operated valve changeswill be performed under pre- position as indicated inoperational flow, differential Table 2.7.3.1-2 under pre-pressure, and temperature operational test conditions.conditions.

Tier I 2.7-102

Revision 32

Tier I 2.7-102 Revision 32