ML20245K928

Forwards Amended Response to QA Branch 890516 Request for Addl Info Re Resolution of Outstanding Advanced BWR Ssar Issues,Including Compliance w/quality-related Reg Guides & Reg Guides Applicable to Advanced BWR

ML20245K928
Person / Time
Site:	05000605
Issue date:	06/28/1989
From:	Marriott P GENERAL ELECTRIC CO.
To:	Chris Miller NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
046-89, 46-89, NUDOCS 8907050305
Download: ML20245K928 (11)

Text

_

' ' GE Nuclear Energy

.___3 GP'itihI EMIG: $0m.%

175 C.:n e? A,'ers San .cn CA 95125 June 28,1989 MFN No. 046-89 Docket No. STN 50-605

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Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Charles L. Miller, Director Standardization and Non-Power Reactor Project Directorate

Subject:

Response to Quality Assurance Branch RAI

Reference:

Letter, P.W. Marriott (GE) to Charles L. Miller (NRC),

" Resolution of Outstanding ABWR SSAR Issues and Response to RAl", June 23,1989 Enclosed is an amended response to the Quality Assurance Branch Request for Additional Information (RAI) dated May 16,1989. Specifically, the attached tables replace those provided in the referenced letter.

It is intended that GE will amend the SSAR accordingly in a future amendment.

I Sincerely, P. W hiarriott, Manager Licensing and Consulting Services cc: D. C. Scaletti (NRC)

J. G. Spraul (NRC)

P. E. Novak (GE)

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8907050305 890628 k PDR ADOCK 05000603 O PDC

. ASWR Standard Plant nuia.ao Kn' A TABLE 17.0-1 ABWR COMPLIANCE M1TH QUALITY RELATED REGULATORY GUIDES Regulatory Guide Rev. Comments I.e i ble excerh. o"*

I,4 3 A/, exey s .s 1.28 3 Except for NRC accepted alternate positions docu-mented in Table 2-1 of Reference 1.

l.M 3 #eexcerHeas 130 0 No exceptions.

137 0 Except for NRC accepted alternate positions docu-mented in Table 21 of Reference 1.

138 2 Except for NttC accepted alternate positions docu-  !

mente m Tabl in Table 2-1 of Reference 1. I 139 2 No Exceptions. i 1.58 Je -- Superseded by Reg. Guide 1.2S, Rev. 3 except for NRC accepted alternate positions documented in l Table 2-1 of Reference 1. '

1/4 & Superseded by Reg. Guide 1.28, Rev. 3 except for NRC accepted alternate positions documented in Table 21 of Reference 1.

1.74 @ Superseded by Reg. Guide 1.28, Rev. 3.

1.88 -iH': Superseded by Reg. Guide 1.28, Rev. 3 except for

- NRC accepted alternate positions documented in Table 21 of Reference 1.

1.94 1 A pph'A ;; ".""'" C:=frf ":x: _ni;.- Me rxcja##*'s 1.116 0-R Except for NRC accepted alternate positions docu-

=ented ir. Table 2-1 of Reference 1.

1.123 - Superseded by Reg. Guide 1.28, Rev. 3 except for NRC accepted alternate positions documented in Table 21 of Reference 1.

1.144 44 - Superseded by Reg. Guide 1.28, Rev. 3.

1.146 & Superseded by Reg. Guide 1.28, Rev. 3 except for l

NRC accepted alternate positions documented in Table 21 of Reference 1.

l i

Amendment 2 17.04

a ABM 234amac Standard Plant RFV B TABLE 1.8 20 I

NRC Regulatory Guides Applicable to ABWR ABWR Appl. Issued Appli-RG No. Rerulatory Guide 'Htle Bgn Dmit cabic? Comments 1.1 Net Positive Suction Head for Emergency 0 11/70 Yes Core Cooling and Containment Heat Removal System Pumps.

1.2 Thermal Shock to Reactor Pressure Vessels. 0 11/70 Yes 13 Assumptions Used for Evaluating the Poten- 2 6/74 Yes tial Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors.

No PWR only .  !

1.4 Assumptions Used for Evaluating the Poten- 2 6/74 tial Radiological Consequences c,f a 1.oss-of-Coolant Accident for Pressurized Water Reactors.

1.5 Assumptions Used for Evaluating the Poten- 0 3/71 Yes tial Radiological consequences of a Steam Line Break Accident for Boiling Water Re-( actors.

1.6 Independence Between Redundant Standby (On- 0 3/71 Yes site) Power Sources and Between Their Distribution Systems.

1.7 Control of Combustible Gas Concentrations 2 11/78 Yes in Containment Following a Loss of Coolant Accident.

1.8 Oualifi:ation and Training of Personnel for  : ^/?! L 3 384Ib E I ~I ' O ~ I Nuclear Power Plants.

1.9 Selection, Design, and Qualification of 2 12/79 Yes Diesel Generator Units Used As Standby (Onsite) Electric Power Systems at Nuclear Plants.

1.11 Instrument Lines Penetrating Primary Reac- 0 3/71 Yes for Containment.

1.12 Instrumentation for Earthquakes. 1 4/74 Yes 1.13 Spent Fuel Storage Facility Design Basis. I 12/75 Yes l

l li Amendment 2 1A36

BWR mme andard Plant nrv a TABLE L8 20 RGs Applicable to ABWR (Continued)

ABWR Appl. Issued Appil-RG No. Esanlatorv Guide 7 hie En, Date cabic? Comments k.14 Reador Coolant Pump FlywheelIntegrity.

1 8/75 No PWR only B.16 Reporting of Operating Information-Appendix 4 8/75 -

NA to design A Technical Specifications.

B.17 Protection of Nuclear Power Plants Against 1 6/73 Yes Industrial Sabotage.

p Comprehensive Vibration Assessment Program 2 5/76 Yes l for Reactor Internals During Preoperational and Initial Startup Testing.

L21 Measuring, Evaluating anu Reporting Radio- 1 6/74 Yes activity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water Nuclear Power Plants.

.22 Periodic Testir.g of Protection System Actu- 0 2/72 Yes ation Functions.

L23 On-site Meteorological Programs.

0 2/72 Yes l

@ Assumptions Used for Evaluating the Poten. 0 3/72 No PWR only tial Radiological Consequences of a Pressu-rized Water Reactor Gas Storage Tank Fail-ute.

p Ar,sumptions Used for Evaluating the Poten. 0 3/72 Yes tital Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressu-rized Water Reactors.

% Ouality Group Classifications and Standards 3 2/% L e See.To d c n.0-I for Water , Steam , and Radioactive-Waste-Containing Components of Nuclear Power Plants 97 Ultimate Heat Sink for Nuclear Power 2 1/76 Yes Plants.

B Quality Assurance Program Requirements  : Sjes m; (Design and Construction).

$ e e "Te W l'i.0- 1 I

pnt 2 1 S 39

. A.B M ms3.sc Standard Plant nrv n TABLE 1.8 20 RGs Applicable to ABWR (Continued)

ABWR Appl. Issued Appli-RG No. _Rerulatorv Guide

• Hilt h Dalg cable? Comments 1.14 Reactor Coolant Pump FlywheelIntegrity. 1 8/75 No PWR only 1.16 Reportingof OperatingInformation Appendix 4 8/75 -

NA to design A Technical Specifications.

1.17 Procedion of Nudear Power Plants Against 1 6/73 Yes Industrial Sabotage.

1.20 Comprebecsive Vibration Assesment Program 2 5/76 Yes for Reactor Internals During Preoperational and Initial Startup Testing.

1.21 Measurmg. Evaluating and Reporting Radio- 1 6/74 Yes activity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from 1.ight Water Nudear Power Plants.

1.22 Periodic Testing of Protection System Actu- 0 2/72 Yes ation Functions.

1.23 On-site Meteorological Programs. 0 2/72 Yes 1.24 Assumptions Used for Evaluating the Poten- 0 3/72 No PWR only tial Radiological Consequences of a Pressu-rized Water Reactor Gas Storage Tank Fail-ure.

1.2.5 Assumptions Used for Evaluating the Poten- 0 3/72 Yes tial Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressu-rized Water Reactors.

1.26 Quality Group Classifications and Standards

2/70 L4 5 e e.Tckdc 17.0-I for Water , Steam , and Radioactive-Waste-Contaming Components of Nudear Power Plants 1.27 Ultimate Heat Sink for Nudear Power 2 1/76 Yes Plants.

1.28 Quality Assurance Program Requirements 3 S/fi ho S e4"Te W l'1.0-1 (Design and Construction).

I Amendment 2 1 6-39

ABWR zwiooxc prv n Standard Plant 2

TABLE 1.8 20 RGs Applicable to ABWR (Continued)

ABWR Appl. Irsued Appli-RG No, Regulatory Guide Thit h Dalg able? Comments 1.29 Seismic Design Classification. 2 0,"S Yx* Se.A. % 9 e M . J -1 3

0 S/'2 Yess 6 e e. T o N C. 1 1, O - l -

130 Quality Assurance Requirements for the In-stallation, Inspection, and Testing of Instrumentation and Electric Equipment.

Control et Ferrite Content in Stainless 3 4/78 Yes 131 Steel Weld Metal.

132 Criteria for Safety Related Electric Power 2 2/77 Yes a Systems for Nuclear Power Plants.

Ouality Assurance Program Requirements 2 2/78 -- NA to design 133 (Operations).

134- Control of Electroslag Weld Properties. 0 12/72 Yes 135 In service of Ungrouted Tendons in Pre- 2 1/76 Yes stressed Concrete Containment Structures.

136 Non MetallicInsulation fc. '.ustenitic 0 2/73 Yes

.. Stainless Steel.

137 Quality Assurance Requirements for Cleaning 0  ?/7 hu S4_c. g bb n.0-t of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants.

138 Ouality Assurance Requirements for Pack- 2 5/T Y n :' sec % W 11.O-I aging, Shipping, Receiving. Storage, and Handling of items for Water Cooled Nuclear Power Plants.

S e e Table t ~1. 0 - 1

. ;; he:g;a e 139 Housekeeping Requirements for Water Cooled 2 !O/T Nuclear Power Plants.

1.40 Qualification Tests of Continuous-Duty 0 3/73 Yes Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants.

1.41 Preoperational Testing of Redundant On-site -0 3/73 Yes Electric Power Systems to Verify Proper Load Group Assignments. l l

IS40 Amendment 2

i!

, ABR 23AMAC -

arv a Ses.ndard Plant ,

1

- TABLE 1.8 20 j l

RGs Applicable to ABWR (Continued) i ABWR .]

Appl. Issued Appli '

RG No. Ranulatorv Guide 11tle Egy,, Ilsig galdg2 Comments 1.43 Control of Stainless Steel Weld Cladding 0 5/73 Yes of Low Alloy Steel Weld Cladding of low  ;

Alloy Steel Components.

1.44 Control of Use of Sensitized Stainless 0 5/73 Yes j

Steel.

1.45 Reactor Coolant Pressure Boundary Leakage 0 5/73 Yes Detection Systems.

1.47 Bypassed and Inoperable Status Indication 0 5/73 Yes .

for Nuclear Power Plant Safety Systems. -l 1.49 Power levels of Nuclear Power Plants. I 12/73 Yes

'l 1.50 Control of Preheat Temperature Welding of 0 5/73 Yes 5 Low Alloy Steel.

1.52 Design, Testing. Maintenance Criteria for 2 3/78 Yes Post Accident Engineered-Safety Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled  ;

- Nuclear Power Plants.  !

1.53 Application of the Single Failure Criterion 0 6/73 Yes to Nuclear Power Plant Protection Systems.

1.54 Ouality Assurance Requirements for Protee. 0 6/73 Yes tive Coatings Applied to Water-Cooled Nuclear Power Plants.

1.56 Maintenance of Water Purity in Boiling 1 7/78 Yes Water Reactors.

1.57 Design Limits and Loading Combinations for 0 6/73 Yes Metal Primary Reactor Containment System Components.

l smpar,a L l See."Todel"7.0-l 1.58 Qualification of Nuclear Power Plant in- s  : 7/0^ C ~ 1 '.; 7 spection, Fumination, and Testing Person-nel.

1.59 Design Basis Floods for Nuclear Power 2 8/77 Yes Plants I l 1 8-41 Amendment 2

i

'. ABM UA6100AC RFV B Standard Plant TABLE 1.8 20 RGs Applicable to ABWR (Continued) j AB%R Appl. Issued Appli-Ranulatory Guide Title En, Dale cable? Comments l RG No.  ;

Design Response Spectra for Seismic Design 1 12/73 Yes 1.60 of Nudear Power Plants.

Damping Values for Seismic Design of Nu- 0 15/73 Yes 1.61 j clear Power Plants. l 0 10.73 Yes 1.62 ManualInitiation of Protective Actions.

Electric Penetration Assemblies in Contain- 3 2/87 Yes 1.63 ,

ment Structures of Nuclear Power Plants.

s p4vM S e4 TeW 0 -I 1 64 Quality Assurance Requirements for the De- 2 f/75 h 4" sign of Nuclear Power Plants.

Materials and Inspections for Reactor Ves. 0 10/73 Yes 1.65 sel Closure Studs.

Initial Test Programs for Water-Cooled 2 8/78 Yes 1.68 Reactor Power Plants.

(

1.68.1 Freoperational and Initial Startup Testing 1 1/77 Yes of Feedwater and Condensate Systems for

~

Boiling Water Reactor Power Plants.

1.68.2 Initial Startup Test Program to Demonstrate 1 7/78 Yes Reinote Shutdown Capability for Water Cooled Nuclear Power Plants. l 1.68.3 Preoperational Testing of Instrument and 1 7/78 Yes Contiof Air Systems.

Concrete Radiation Shields for Nuclear Po- 0 12/73 Yes 1.69 wer Plants.

Standard Format and Content of Safety Ana- 3 11/78 Yes 1.70 lysis Reports for Nuclear Power Plants.

0 12/73 -- NA to design 1.71 Welder Qualifications for Areas of Limited Accessibility.

Spray Fond Piping Made From Fiberglass. 2 11/78 Yes i 1.72 Reinforced Thermosetting Resin.

i Amendment 2

1

~

Mk .

- 23A6100AC arv n Standard Plant j

TABLE 1.8 20 RGs Applicable to ABWR (Continued)

ABWR Appl. lasued- Appli-ma=ulatory Guide Title b Dalt 33hk1 Comments RG No.

I j

Qualification Tests of Elearic Valve Ope- 0 1/74 Yes 1.73 j retors Installed laside the Containment of Nudcar Power Plants.

1.74 Quality Assurance Terms and Definitions. c09 < 2/?' '.'.. S4 e hNt M.O-L i

i 2 9/78 Yes 1.75 PhysicalIndependence of Electric Systems.

0 4/74 Yes 1.76 Design Basis Tornado for Nudear Power Plants Assumptions Used for Evaluating a Contro! O 5/74 Yes 1.77 Rod Ejection Accident for Pressurized Water 1

Reactors.  !'

1.78 Assumptions for Evaluating the Habitability 0 6/74 Yes j 4

of a Nudear Power Plant Control Room Dur- 1 ing a Postulated Hazardous Chemical Re. i lease.

1 9/75 No PWR only 1.79 Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reac-tors.

Shared Emergency and Shutdown Electric Sys- 1 1/75 Yes i 1.81 tems for Multi Unit Power Plants. l Water Sources for long-Term Recirculation 1 /85 Yes l 1.82 Coolir.g Fo!!owing loss of-Coolant Accident. ~l In Service Inspection of Pressurized Water 1 7/75 No PWR only 1.83 Reactor Steam Generator Tubes.

Design and Fabrication Code Case Acceptabi- 24 6/86 Yes 1.84 lity, ASME Senion III, Division 1.

l 1 Materials Code Case Acceptability, ASf4E 24 6/86 Yes 1.85 '

Section Ul, Division 1.

Termination of Operating licenses for Nu- 0 6/74 -- NA to design 1.86 dear Reactors.

i l

I 1.843 Amendment 2

)

l

ABM Standard Plant uxoooxc nrv n TABLE 1.8 20 RGs Applicable to ABWR (Continued) j l

ABWR Appl. Issued Appil-RG No, n.-ulatory Guide Title EtL Dalt cable? Comments 1.87 Guidance for Construction of Class 1 Compo- 1 6/75 Yes ments in Elevated-Temperature Reactors j

(Supplement to ASME Section III Code Cases i 1592,1593,1594,1595, and 15%).

S4 pen" b M See%Q4 W .O 1 1.88 Collect:sn, Storage, and Maintenance of 7 2 10/% 'W Nuclear Power Plant Quality Assurance Re-cords Environmental Qualification of Certain 1 7/64 Yes -

1.89 Electric Equipment Important to Safety {

i for Nuclear Power Plants.

1 8/77 - NA to design j 1.90 Inservice Inspection of Prestressed Con-i crete Containment Structures with Grouted Tendons. )

1.91 Evaluations of Explosions Postulated to 2 2/78 Yes Occur on Transportation Routes Near Nuclear

( Power Plants.

l 1.92 Combining Model Responses and Sp ual Com- 1 2/76 Yes l

_ l ponents in Seismic Response Analysis.

Yes j 1.93 Availability of Electric Power Sources. 0 12/74 1.94 Ouality Assurance Requirements for Instal- I/% 5 S ae. T a N \7. o -I lation, Inspection, and Testing of Structu-ral Stect During the Construction Phase of Nucicar Power Plants.

1.95 Protection of Nuclear Power Plant Control 1 1/77 Yes Room Operators Against an Accidental Chlo-rine Release.

1.96 Design of Main S*.eam Isolation Valve Leak- 1 6/76 Yes age Control Systems for Boiling Water Reac-tor Nuclear Power Plants.

1.97 Instrumentation for light Water-Cooled 3 5/83 Yes Nuclear Power Plants to Assess f%nt and Environs Conditions During and Following an Accident.

1.6-M Amendment 2

i s.

MM 23A6tmAc nv n ,

Standard Plant ,

~

TABLE 1.8 20 RGs Applicable to ABWR (Continued)  ;

ABWR Appl. Issued Appil-EEL Dalt sahltl Comments RG No. *-ulatorv Guide T1tle 0 Yes l 1.112 Calculation for Releases of Radioactive Ma- 5/77 terials in Gaseous and Liquid Effluents from Light. Water-Cooled Power Reactors. )

i Estimating Aquatic Dispersion of Effluents 1 4/77 Yes 1.113 from Accidental and Routine Reactor Re- i leases for the Purpose ofImplementing Appendix 1.

l Guidance On Being Operator At the Controls 1 11/76 - NA to design 1.114 of a Nuclear Power Plant.

Protection Against Low-Trajectory Turbine 1 7/77 Yes 1.115 Missiles.

1.116 Quality Assurance Requirements for Instal- p 0' 5/'f Y= S 44 Table M 0- l l i

lation, inspection, and Testing of Mechani-i cal Equipment and Systems.

f Tornado Design Classification. 1 4/78 Yes 1.117 Periodic Testing of Eier'.ric Power and Pro- 2 6/78 Yes  ;

- 1.118 I tection Systems.

Fire Protection Guidelines for Nucicar Po- 1 11/87 Yes 1.120 wer Plants.

Bases for Plugging Degraded PWR Steam Gene- 0 8/76 No PWR only 1.121 rator Tubes.

Development of floor Design Response Sper- 1 2/78 Yes 1.122 tra for Seismic Design of Floor.Supponed Equipment or Components.

ss <Y '" Ya S e e Tm bl c 17 0 -I i

1.123 Ouality Assurance Requirements for Control g ? ,

of Procurement of items and Services for Nuclear Power Plants.  ;

Service Limits and Loading Combinations for 1 1/78 Yes 1.124 Class 1 Linear Type Component Supports.

15.a6 Asnenemem 2 i

j 1

~

IBWR zuumc  !

Erandard Plant REV B l i .  ;

TABLE I.8 20 i RGs Applicable to ABWR (Continued)  ;

ABWR Appl. lassed Appli-M Ragulatorv Guide Title BEL Dalt sahlt2 Comments  !

1.137 Fuel-Oil Systems for Standby Diesel Genera. I 10/79 Yes j tors.

1.138 laboratory Investigations of Sous for En- 0 4/78 Yes gineering Analpis and Design of Nudear .

Pos.tr Plants.

I 1.139 Guidance for Residual Heat Removal. 0 $/78 Yes 1.140 Design, Testing, and Maintenance Criteria 1 10/79 Yes For Normal Ventilation Exhaust System Air .

Piltration and Absorption Units of Light- 1

. Water Cooled Nudcar Power Plants.

1.141 Containment Isolation Provisions for Fluid 0 4/78 Yes Systems.

1.142 Safety-Related Concrete Structures for Nu- 1 11/81 Yes dear Power Plants (Oth:r Than Reactor Ves-( sets and Containmer.ts).

1

. 1.143 Guidance for Radioactive Waste Management 1 10/79 Yes j Systems, Structures, and Components lastal- i led in Light Water Cooled Nudcar Power )

Plants.

J s 44Takb V7.0-l '

1.144 Auditing of Quality Assurance Progruns Nu- , _

p g /SO 30 P/. n '-t t clear Power Plants.

1.145 Atmospheric Dispersion Models for Potential 1 12/82 Yes j Accident Consequences Assessments at Nude-

]

ar Power Plants. <

g u p .v M"} 5'e s. T* W t 7 . 0 - 1 1.146 Qualification of Quality Assurance Program g- S S/ . , . . . . . , . i Audit Personnel for Nudear Power Plants. I l

1.147 Inservice Inspection Code Case Acceptabi- $ 8/86 - NA to design lity ASME Scaion XI, Division 1. 1 1.148 Functional Spedfication for Active Valve 0 4/81 Yes i Assemblics in Systems important to Safety  ;

in Nuclear Power Plants.  !

I I

i Amendment 2 1MF I

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