ML19274E520

App A,Amend 9 to Sar,Extension Review Matter for Preliminary Design Approvals.

ML19274E520
Person / Time
Site:	05000532
Issue date:	03/09/1979
From:	C.F. BRAUN & CO.
To:
Shared Package
ML19274E517	List: ML19274E516 ML19274E520
References
NUDOCS 7903290168
Download: ML19274E520 (130)

Text

GUIDE PAGE This Amendment 9, in its entirity, is added to the end'of BPAUN SAR.

There are no deletions or additions inside the document.

q q 03'M M hm VW&1M%% vin

BRAUN SAR APPENDIX A EXTENSION REVIEW MATTER FOR PRELIMINARY DESIGN APPROVALS Amn 9 March 14, 1979 3_1

A ,

Ak JNDIX A TABLE OF CONTENTS

• PARAGRAPH A.1 Introduction A.2 Assessments A.2.1 Part I Category I Matters Approved by RRRC and Issued from May 1975 through August 1978 A.2.1.1 Regulatory Gui de 1.7 Control of Combustible Gas Concentration Revision 2 in Containment rollowing a Loss-of-Collant Accident A.2.1.2 Regulatory Guide 1.9 Selection, Design, and Qualification for p Revision 1 Diesel-Generator Units Used as Onsite b Electric Power Systems at Nuclear Power Plants A.2.1.3 Regulatory Guide 1.20 Comprehensive Vibration Assessment Program Revision 2 for Reactor Internals During Preoperational and Initial Startup Testing A.2.1.4 Regulatory Guide 1.28 Quality Assurance Program Requirements Revision 1 (Design and Construction) a

@ A.2.1.5 Regulatory Guide 1.29 Seismic Design Classification 9- Revision 3 A.2.1.6 Regulatory Guide 1.31 Control of Ferrite Content in Stainless

[l Revision 2 Steel Weld Metal

A.2.1.7 Regulatory Guide 1.32 Criteria for Safety-Related Electric Revision 2 Power Systems for Nuclear Power Plants

• A.2.1.8 Regulatory Guide 1.33 Quality Assurance Program Requirements Revision 1 (Ope ration)

A.2.1.9 Regulatory Guide 1.35 Inservice Inspection of Ungrouted Tendons Revision 2 in Pre-stressed Concrete Containment Structures A.2.1.10 Regulatory Guide 1.38 Quality Assurance Requirements for Packaging, Revision 2 Shipping, Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants A.2.1.ll Regulatory Guide 1.39 Housekeeping Requirements for Water-Cooled Revision 2 Nuclear Power Plants

> A.2.1.12 hegulatory Guide 1.52 Design, Testir.g, and Maintenance for b Revision 2 Engineered Safety Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light Water Cooled Nuclear Power Plants A.2.1.13 Regulatory Guide 1,63 Electric Penetration Assemblies in Revision 1 Containment Structures for Light-Water-Cooled Nuclear Power Plants g A.2.1.14 Regulatory Guide 1.64 Quality Assurance Requirements for the

@ Revision 2 Design of Nuclear Power Plants O

g A.2.1.15 Regulatory Guide 1.68 Initial Test Programs for Water-Cooled

' Revision 2 Reactor Power Plants 5

3

A.2.1.16 Regulatory Guide 1.68.1 Preoperational and Initial Startup Testing Revision O of Feedwater and Condensate Systems for g

b Boiling Water Reactor Power Plants e

A.2.1.17 Regulatory Guide 1.72 Spray Pond Plastic Piping Revision 1 A.2.1.18 Regulatory Guide 1.84 Code Case Acceptability - ASME Section III nevision 12 Design and Fabrication A.2.1.19 Regulatory Guide 1.85 Code Case Acceptability - ASME Section III Revision 12 Materials A.2.1.20 Regulator" Guide 1.90 Inservice Inspection of Pre-stressed Revision 1 Concrete Containment Structures with Grouted Tendons y A.2.1.21 Regulatory Guide 1.92 Combining Modal Responses and Spatial t- Revision 1 Coniponents in Seismic Response Analysis A.2.1.22 Regulatory Guide 1.94 Quality Assurance Requirements for Installation, Revision 1 Inspection, and Testing of Structural Concrete and Structural Steel during the Construction Phase of Nuclear Power Plants A.2.1.23 Regulatory Guide 1.95 Protection of Nuclear Power Plant Control Revision 1 Room Operators Against an Accidental g

Chlorine Release O- A.2.1.24 Regulatory Guide 1.99 Effects of Residual Elements on Predicted Revision 1 Radiation Damage to Reactor Vessel Materials

[

[$ A.2.1.25 Regulatory Guide 1.100 Seismic Qualification of Electric Equipment 2! Revision 1 for Nuclear Povar Plants

A.2.1.26 Regulatory Guide 1.103 Post-Tensioned Pre-stressing Systems for Revision 1 Concrete Reactor Vessels and Containments e A.2.1.27 Regulatory Guide 1.106 Thermal Overload Protection for Electric Revision 1 Motors on Motor-Operated Valves A.2.1.28 Regulatory Guide 1.107 Qualifications for Cement Grouting for Revision 1 Pre-stressing Tendons in Containment S tructures A.2.1.29 Regulatory Guide 1.116 Quality Assurance Requirements for Revision 0-R Installation, Inspection, and Testing of Mechanical Equipment and Systems A.2.1.30 Regulatory Guide 1.118 Periodic Testing of Electric Power and Revision 1 Protection Systems p A.2.1.31 Regulatory Guide 1.120 Fire Protection Guidelines for Nuclear b Revision 1 Power Plants A.2.1.32 Regulatory Guide 1.122 Development of Floor Design Response Spectra Revision 1 for Seismic Design of Floor-Supported Equipment or Components A.2.1.33 Regulatory Guide 1.123 Quality Assurance Requirements for Control Revision 1 of Procurement of Items and Services for Nuclear Power Plants g A.2.1.34 Regulatory Guide 1.126 An Acceptable Model and Related Statistical

!} Revision 0 Methods for the Analysis of Fuel Densification A.2.1.35 Regulatory Guide 1.128 Installation Design and Installation of g Revision 1 Large Lead Storage Batteries for Nuclear j Power Plants

A.2.1.36 Regulatory Guide 1.129 Maintenance, Testing and Replacement of Revision 0 Large Lead Storage Batteries for Nuclear Power Plants e

A.2.1.37 Regulatory Guide 1.131 Qualification Tests of Electric Cables, Revision O Field Splices and Connection for Light Water Cooled Nuclear Power Plants s

A.2.1.38 Regulatory Guide 1.132 Site Investigations for Foundations of Revision O Nuclear Power Plants A.2.1.39 Regulatory Guide 1.134 Medical Certification and Monitoring of Revision 0 Personnel Requiring Operator Licel.ses A.2.1.40 Regulatory Guide 1.135 Normal Water Level and Discharge at Revision 0 Nuclear Power Plants y A.2.1.41 Regulatory Guide 1.136 Material for Concrete Containments S Revision O A.2.1.42 Regulatory Guide 1.137 Fuel Oil Systems for Standby Diesel Revision 0 Generators A.2.1.43 NUREG-0102 (SRP 1.8) Interfaces for Standard Designs Revision 0 A.2.1.44 Regulatory Guide 1.138 Laboratory Investigation of Soils for Revision O Engineering Analysis and Design of Nuclear y Power Plants h

p. A.2.1.45 Regulatory Guide 1.XXX Permanent Dewatering Systems Revision 0 d A.2.1.46 Regulatory Guide 1.140 Design, Testing, and Maintenance Criteria Revision 0 for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of LWR's

A,2.1.47 Regulatory Guide 1.142 Safety-Related Concrete Structures Revision 0 b

u) A.2.1.48 Regulatory Guide 8.19 Occupational Radiation Dose Assessment Revision 0 at LWR's - Design Stage Man-Rem Estimates A.2.1.49 RSB 5-2 Reactor Coolant System Overpressure Revision 0 Protection A.2.2 Part II Category II Matters Approved by RRRC from March 1974 through August 1978 A.2.2.1 Regulatory Guide 1.27 Ultimate Heat Sink for Nuclear Power Plants Revision 2 A.2.2.2 Reguletory Guide 1.52 Design, Testing, and Maintenance Criteria p Revision 1 for Engineered-Safety-Feature Atmosphere b Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants A.2.2.3 Regulatory Guide 1.59 Design Basis Floods for Nuclear Power Plants Revision 2 A.2.2.4 Regulatory Guide 1.63 Electric Penetration Assemblies in Revision 1 Containment Structures for Light-Water-x Cooled Nuclear Power Plants 9 A.2.2.5 Regulatory Guide 1.68.2 Initial Startup Test Program to Demonstrate e Revision 1 Remote Shutdown Capability for Water-Cooled Nuclear Power Plants 1

A.2.2.6 Regulatory Guide 1.91 Evaluation of Explosions Postulated to Revision 1 Occur on Transportation Routes Near Nuclear Power Plant Sites e

A.2.2.7 Regulatory Guide 1.97 Instrumentation for Light-Water-Cooled Revision 1 Nuclear Power Plants to Assess Plart Conditions During and Following an Accident A.2.2.8 Regulatory Guide 1.102 Flood Protection for Nuclear Power Plants Revision 1 A.2.2.9 Regulatory Guide 1.105 Instrument Setpoints Revision 1 A.2.2.10 Regulatory Guide 1.108 Periodic Testing of Diesel Generator Units Revision 1 Used as Onsite Electric Power Systems at p Nuclear Power Plants E

A.2.2.ll Regulatory Guide 1.115 Protection Against Low-Trajectory Revision 1 Turbine Missiles A.2.2.12 Regulatory Guide 1.117 Tornado Design Classification Revision 1 A.2.2.13 Regulatory Guide 1.124 Service Limits and Loading Combinations Revision 1 for Class 1 Linear Type Component Support

! A.2.2.14 Regulatory Guide 1.130 Design Limits and Loading Combinations N

P.

, Revision O for Class 1 Plate- and Shell-Type

r. Component Supports

?

r. A.2.2.15 Regulatory Guide 1.137 Fuel Oil Systems for Standby Diesel e

y Revision 0 Generators

A.2.2.16 Regulatory Guide 8.8 Information Relevant to Ensuring that g Revision 2 Occupational Radiation Exposures at Nuclear b Power Stations will be as Low As is Reasonably Achievable (Nuclear Power Reactors)

A.2.2.17 Branch Technical Position Guidelines for Fire Portection for Nuclear ASB 9.5-1 Power Plants Under Review and Construction A.2.2.18 Branch Technical Position Material Selection and Processing Guidelines MTEB 5-7 for BWR Coolant Pressure Boundary Piping A.2.2.19 SRP 5. 4. 7 Residual Heat Removal System Revision 1 A.2.2.20 Regulatory Guide 1.141 Containment Isolation Provisions for Revision O Fluid Systems Y

e A.2.3 Part III Category III Matters Approved by RRRC from March 1974 through August 1978 A.2.3.1 Regulatory Guide 1,56 Maintenance of Water Purity in Boiling Revision 1 Water Reactors A.2.3.2 Regulatory Guide 1.68.2 Initial Startup Test Program to Demonstrate Revision 1 Remote Shutdown Capability for Water-Cooled Nuclear Power Plants a

g A.2.3.3 Regulatory Guide 1.99 Effects of Residual Elements on Predicted P

y Revision 1 Radiation Damage to Reactor Vessel Materials A.2.3.4 Regulatory Guide 1.101 Emergency Planning for Nuclear Power Plants g Revision 1

A.2.3.5 Regulatory Guide 1.114 Guidance on Being Operator at the Revision 1 Controls of a Nuclear Power Plant

• A.2.3.6 Regulatory Guide 1.121 Bases for Plugging Degraded PWR Steam Revision G Generator Tubes A.2.3,7 Regulatory Guide 1.127 Inspection of Water-Control Structures Revision 1 Associated with Nuclear Power Plants A.2.2.8 Regulatory Guide 1.137 Fuel Oil Systems for Standby Diesel Revision 0 Generators A.2.3.9 SRP 5.4.7 Residual Heat Removal System Revision 1 A.2.3.10 Regulatory Guide 1.141 Containment Isolation Provisions for Revision 0 Fluid Systems h A.2.3.ll RSB 5-2 Reactor Coolant System Overpressurization Revision 0 Protection A.2.4 Part IV NRR Category IV Matters A.2.4.1 Regulatory Guide 1.13 Spent Fuel Storage Facility Design Basis Revision 1 A.2.4.2 Regulatory Guide 1.14 Reactor Coolant Pump Flywheel Integrity

@ Revision 1 0

e. A.2.4.3 Regulatory Guide 1.79 Preoperational Testing of Emergency Core u

Revision 1 Cooling Systems for Pressurized Water G Reactors e

T. 2.4.4 Regulatory Guide 1.83 Inservice Inspection of Pressurized Revision 1 Water Reactor Steam Generator Tubes o A.2.4.5 Res.latory Guide 1.104 Overhead Crane Handling Systems for Revision O Nuclear Power Plants A.2.4.6 Standard Review Plan BTP MTEB-5-3, Monitoring of Secondary SRP 5.4.2.1 Side Water Chemistry in PWR Steam Generators A.2.4.7 Standard Review Plan BTP CSB-6-1, Minimum Containment SRP 6.2.1, 6.2.lA, 6.2.lB, Pressure Model for PWR ECCS Performance 6.2.1.2, 6.2.1.3, 6.2.1.4, Evaluation 6.2.1.5 A.2.4.8 Standard Review Plan BTP-6-2, Control of Combustible Gas SRP 6.2.5 Concentrations in Containment Following p a Loss-of-Coolant Accident i

U A.2.4.9 Standard Review Plan BTP CSB-6-3, Determination of Bypass ,

SRP 6.2.3 Leakage Path in Dual Containment Plants A.2.4.10 Standard Review Plan BTP CSB-6-4, Containment Purging During S RP 6.2.4 Normal Plant Operations A.2.4.ll Standard Review Plan S RP 9.1.4 BTP ASB-9.1, Overhead Handling Systems 3 for Nuclear Power Plants S A.2.4.12 Standard Review Plan BTP ASB-10.1, Design Guidelines for e S RP 10.4.9 Auxiliary Feedwater System Pump Drive and Power Supply Diversity for PWR's 5

Q! A.2.4.13 Standard Review Plan Procedures for Composite Section Local SRP 3.5.3 Damage Prediction (SRP Section 3. 5. 3, par. II.l.C)

A.2.4.14 Standard Review Plan Development of Design Time History for SRP 3.7.1 Soil-Structure Interaction Analysis (SRP S Section 3.7.1, par. II.2) e A.2.4.15 Standard Review Plan Procedures for Seismic System Analysis S RP 3.7.2 (SRP Section 3.7.2, par. II)

A.2.4.16 Standard Review Plan Procedures for Seismic Subsystem Analysis S RP 3.7.3 (SRP Secticn 3.7. 3, par. II)

A.2.4.17 Standard Review Plan Design and Construction of Concrete SRP 3.8.1 Containments (SRP Section 3.8.1, par. II)

A.2.4.18 Standard Review Plan Design and Construction of Steel SpP 3.8.2 Containments (SRP Section 3.8.2, par. II)

A.2.4.19 Standard Review Plan Structural Design Criteria for Category y SRP 3.8.3 I Structures Inside Containment (SRP b

tJ Section 3.8.3, par. II)

A.2.4.20 Standard Review Plan Structural Design Criteria for Other S RP 3.8.4 Seismic Category I Structures (SRP Section 3.8.4, par. II)

A.2.4.21 Standard Review Plan Structural Design Criteria for Foundations S RP 3.8.5 (SRP Section 3.8.5, par. II)

A.2.4.22 Standard Review Plan Seismic Design Requirements for Radwaste 3

g SRP 3.7, 11.2, 11.3, 11.4 Systems and Their Housing Structures

@ (SRP Section 11.2, BTP ETSB 11-1, par. B.v)

A.2.4.23 Standard Review Plan Tornado Load Effect Combinations (SRP y SRP 3.3.2 Section 3.3.2, par. II.2.d)

A.2.4.24 Standard Review Plan Dynamic Effects of Wave Action (SRP SRP 3.4.2 Section 3.4.2, par. II) e A.2.4.25 Standard Review Plan Water Hammer for Steam Generators with SRP 10.4.7 Preheaters (SRP Section 10.4.7, par.

I.2.b)

A.2.4.26 Standard Review Plan Thermal-Hydraulic Stability (SRP SRP 4.4 Section 4.4, par. II.5)

A.2.4.27 Standard Review Plan Intersystem Leakage Detection (SRP S RP 5.2.5 Section 5.2.5, par. II.4, and Regulatory Guide 1.45)

A.2.4.28 Standard Review Plan Main Steam Isolation Valve Leakage Control SRP 3.2.2 System (SRP Section 10.3, par. III.3 and BTP RSB-3.2)

J. A.2.4.29 Standard Review Plan Ductility of Reinforced Concrete and S RP 3. 5. 3 Steel Structural Elements Subjected to Impactive or Impulsive Loads A.2.4.30 Standard Review Plan Response Spectra in Vertical Direction SRP 3.7.1 A.2.4.31 Standard Review Plan BWR Mark III Containment Pool Dynamics S RP 3. 8.1, 3. 8. 2 A.2.4.32 Standard Review Plan Air Blast Loads Q. S RP 3. 8. 4

- A.2.4.33 Standard Review Plan Tornado Missile Impact g S RP 3. 5. 3 3

A.2.4.34 Standard Review Plan Passive Failures During Long-Term SR1- 6. 3 Cooling Following LOCA

t A.2.4.35 Standard Review Plan Control Room Position Indication of p S RP 6. 3 Manual (Handwheel) Valves in the ECCS N

$ A.2.4.36 long-Term Recovery from Steamline Break -

Standard Review Plan SRP 15.1.5 Operator Action to Prevent Overpressurization A.2.4.37 Standard Review Plan Pump Operability Requirements S RP 5.4.6, 5.4.7, 6.3 A.2.4.38 Standard Review Plan Gravity Missiles, Vessel Seal Ring S RP 3.5.1 f.'issiles Inside containment A.2.4.39 Standard Review Plan Cc>re Thermal-Hydraulic Analysis SRP 4.4 A.2.4.40 Standard Review Plan Degraded Grid Voltage Conditions SRP 8. 3

d. A.2.4.41 Standard Review Plan Asymmetric Loads on Components Located S RP 6. 2.1. 2 Within Containment Subcompartments A.2.4.42 Standard Review Plan Containment Leak Testing Program S RP 6.2.6 A.2.4.43 Standard Review Plan Containment Response Due to Main Steam S RP 6. 2.1. 4 Line Break and Failure of MSLIV to Close

, A.2.4.44 Standard Review Plan Main Steam and Feeduater Pipe Failures

@ SRP 3.6.1, 3.6.2 5

r. A.2.4.45 Standard Review Plan Decign Requirements for Cooling Water u

SRP 9.2.2 to Reactor Coolant Pumps 5

d A.2.4.46 Standard Review Plan Design Guidelines for Water Hammer in SRP 10.4.7 Steam Generators with Top Feedring Design (BTP ASB-10.2)

A.2.4.47 Standard Review Plan Environmental Control Systams for SRP 3.11 Safety Related Equipment P

d e

G a

k 3

BRAUN SAR A.1 INTRODUCTION The Con =tission's August 22, 1978 policy statement en standardization provides for a two year extension of Preliminary Design Approvals originally issued for a three year term.

The application for a PDA extension requires an assessment of the design with respect to the Category I, II, III and IV matters approved for implementation since the regulatory requirements cuteff date for the PDA.

This Appendix provides the required assessments for an extension of PDA-5 issued for BRAUN SAR Turbine Island design. The regulatory requirement cutoff date for BRAUN SAR was May 30, 1975.

Amn 9 A-16 March 14, 1979

BRAUN SAR A.2 ASSESSMENTS C F Braun & Co has assessed the BRAUN SAR Turbine Island design with respect to the Regulatory Guides and other matters listed in R S Boyd's letter to H A Baird dated January 24, 1979, titled " Extension Review Matters for Preliminary Design Approvals."

The following sections centain the individual assessmants of the listed matters. Since the Turbine Island contains no safety class structures, systems, or components, the majority of the regulatory matters have been assessed as not applicable to the scope of the Turbine Island. For applicable regulatory matters full compliance or alternate positions are provided. Reference to the BRAUN SAR text is used to the maxi =um extent possible.

A-17 March 14, 1979 Amn 9

BRAUN SAR REGULAIORY GUIDANCE ASSESSMENT

>JA EXTENSION A.2.1.1 PEGULATORY GUIDE 1.7 REVISION 2 DATED Issued in 1978 TITLE Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident REGULATORY GUIDE This guide describes methods that are acceptable to the NRC staff for implementing the provisions of Criterion 41, " Containment Atmosphere Cleanup," which requires that systems to control hydrogen, oxygen and other substances that may be released into the reactor containment be provided as necessary to control the concentrations of such substances following postulated accidents and ensure that containment integrity is maintained.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-18 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.2 REGULATORY GUIDE 1.9 REVISION 1 DATED March 10, 1971 TITLE Selection, Design, and Qualification for Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants REGULATORY GUIDE This safety guide describes an acceptable basis for the selection of diesel generator sets of sufficient capacity and margin to implement General Design Criterion 17.

A diesel generator set selected for use as a standby power supply should have the capability to (1) start and accelerate a number of large motor loads in rapid succession, and be able to sustain the loss of any such load, and (2) supply continuously the sum of the loads needed to be powered at any one time.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-19 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.3 REGUIATORY GUIDE 1.20 REVISION 2 DATED May 1976 TITLE Comprehensive Vibration Assessment Program for Reactor Internals During Pre-Operational and Initial Startup Testing REGULATORY GUIDE Regulatory Guide 1.20 describes a comprehensive vibration assessment program for reactor internals during preoperational and initial startup testing. The vibration assessment program meets the requirements of Criterion 1, " Quality Standards and Records," of Appendix A to 10CFR Part 50 and Section 50.34, " Contents of Applications, Technical Information," of 10CFR Part 50.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH REE;ECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-20 March 14, 1979

BRAUN SAR REGULATORY GUID MCE ASSESSMENT PDA EXTENSION A.2.1.4 REGULATORY GUIDE 1.28 REVISION 1 DATED March, 1978 TITLE Quality Assurance Program Requirements (Design and Construction)

REGULATORY GUIDE Regulatory Guide 1.28 endorses ANSI N45.2-1977 as an adequate basis for complying with quality assurance program requirements for Appendix B to 10CFR50 (subject to certain 1:emized considerations) , for the design and construction phases of nuclear power plants.

EVALUATION OF BRAUN SAR (BWR TUFBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The QA program for BRAUN SAR references the topical report Braun TR-21 Quality Assurance Program. This report is updated and approved by the NRC annually and provides degrees of compliance to Quality Assurance Regulatory Guides and ANSI N45.2 series standards.

C F Braun & Co is committed to use of the QA program described in TR-21 for any nuclear project utilizing BRAUN SAR.

Amn 9 A-21 March 14, 1979

BRAUN SAR REGULATORY GUIDMICE ASSESSMENTS PDA EXTENSION A.2.1.5 REGULATORY GUIDE 1.29 REVISION 2 DATED February 1976 TITLE Seismic Design Classification REGULATORY GUIDE INTENT Regulatory Guide 1.29 describes an acceptable method of identifying and classifying those features of light-water cooled nuclear power plants that should be deisgned to withstand the effects of SSE.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The main steam and feedwater lines located in the Turbine Island are not classified Seismic Category I as required by C.l.e of Regulatory Guide 1.29. GESSAR Docket STN 50-447 uses the alternate position as presented in FIG 3.2-1 of SRP 3.2.1 which sets the criteria for the Turbine Island that the main steam and feedwater lines seismic classification is non seismic Category I.

Amn 9 A-22 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.6 REGULATORY GUIDE 1.31 REVISION 2 DATED May 1977 TITLE Control of Ferrite Content in Stainless Steel Weld 5.. 1 REGULATORY GUIDE Regulatory Guide 1.31 describes an acceptable method of implementing requirements with regard to the control of ferrite content in stainless steel weld metal.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-23 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.7 REGULATORY GUIDE 1.32 REVISION 2 DATED February 1977 TITLE Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants REGULATORY GUIDE Regulatory Guide 1.32 identifies disparity between GDC 17, IEEE-308 R.G. 1.6, IEEE-450 and provides an acceptable supplement to these criteria for offsite power supply, and standby power supply systems.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE For electrical instrumentation and control systems or components in the Turbine Island which interface with safety related systems in the NI (GESSAR Docket STN 50-447) , BRAUN SAR commits for such systers to use the same criteria as is used .n the NI with the exception of the Seismic Category I classificatien.

Amn 9 A-24 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.8 REGULATORY GUIDE 1.33 REVISION 1 DATED January 1977 TITLE Quality Assurance Program Requirements (Operation)

REGULATORY GUIDE Regulatory Guide 1.33 endorses ANSI N18.7-1976/ANS 3.2 which defines the overall quality assurance program requirements for the operation phase of nuclear power plants. The NRC finds this document to be an adequate basin for the nuclear power plant owner to comply with the quality assurance program requirements of Appendix B to 10CFR50, subject to certain itemized considerations.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The Regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

O Amn 9 A-25 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.9 REGULATORY GUIDE 1.35 REVISION 2 DATED January 1976 TITLE Inservice Inspection of Ungrouted Tendens in Pre-stressed Concrete Containment Structures EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND)

WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-26 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.10 REGULATORY GUIDE 1.38 REVISION 2 DATED May 1977 TITLE Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items for Water-Cooled Nuclear Power Plants REGULATORY GUIDE Regulatory Guide 1.38 endorses NASI N45.2.2-1972 which defines requirements for packaging, shipping, receiving, storage, and handling of safety-related items for nuclear power plants. These requirements deal with the protection and control necessary to assure that the requisite quality of those important parts of the plant are preserved from the time items are fabricated until they are incorporatad in the plant.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The QA program for BRAUN SAR references the topical report Braun TR-21 Quality Assurance Program. This report is updated and approved by the NRC annually and provides degrees of compliance to Quality Assurance Regulatory Guides and ANSI N45.2 series standards.

C F Braun & Co is committed to use of the QA program described in TR-21 for any nuclear project utilizing BRAUN SAR.

Amn 9 A-27 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.11 REGULATORY GUIDE 1.39 REVISION 2 DATED September 1977 TITLE Housekeeping Requirements for Water-Cooled Nuclear Power Plants REGULATORY GUIDE This guide describes an acceptable method of complying with the Commission's regulations with regard to housekeeping requirements for the control of work activities, conditions, and environments at water-cooled nuclear power plant sites.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLANr' WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-28 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESS}ENT PDA EXTENSICN A.2.1.12 REGULATORY GUIDE 1.52 REVISION 2 DATED April 1978 TITLE Design, Testing, and Maintenance for Engineered Safety Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light Water Cooled Nuclear Power Plants REGULATORY GUIDE This guide describes criteria to be used in the design, maintenance and testing of atmosphere cleanup systems, filtration units and adsorption units.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-29 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMINT PDA EXTENSION A.2.1.13 PEGULATORY GUIDE 1.63 REVISION 1 DATED May 1977 TITLE Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants REGULATORY GUIDE Regulatory guide 1.63 describes acceptable methods of design and qualification of containment electrical penetrations. It endorses IEEE-317 - 1976 with specific exceptions.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) NITH PESPECT TO THE PIGULATORY GUIDE The regulatory position does not address any structures, syster s, or components within the scope of the Turbine Island.

A:m 9 A-30 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A,2.1.14 REGULATORY GUIDE 1.64 REVISION 2 DATED Jtma 1976 TITLE Quality Assurance Requirements for the Design of Nuclear Power Plants REGULATORY GUIDE Regulatory Guide 1.64 endorses ANSI N45.2.ll-1974, subject to the comments in section C, " Regulatory Position." The purpose of the standard is to provide requirements and guidance for a quality assurance program for the design of nuclear power plant structures, systems, and components whose satisfactory and reliable performance is required to (1) prevent accidents that could cause undue risk to the health and safety of the public, or (2) to mitigate the consequences of such accidents if they were to occur.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The QA program for BRAUN SAR references the topical report Braun TR-21 Quality Assurance Program. This report is updated and approved by the NRC annually and provides degrees of compliance to Quality Assurance Regulatory Guides and ANSI N45.2 series standards.

C F Braun & Co is committed to use of the QA program described in TR-21 for any nuclear project utilizing BRAUN SAR.

Amn 9 A-31 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.15 REGULATORY GUIDE 1.68 REVISION 2 DATED .Tanuary 1978 TITLE Initial Test Programs for Water-Cooled Reactor Power Plants REGULATORY GUIDE This guide describes the general scope and depth of initial test programs acceptable to the NRC staff.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE BRAUN SAR Section 14.1 lists the systems included in the initial test program in accordance with Regulatory Guide 1.68. The appropriate revision of Regulatory Guide 1.68 will be used when the details of initial test program are develcped.

Amn 9 A-32 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSME!;T PDA EXTENSION A.2.1.16 REGULATORY GUIDE 1.68.1 REVISION O DATED December 1975 TITLE Preoperational and Initial Startup Testing of Feedwater and Condensate Systems for Boiling Water Reactor Power Plants REGULATORY GUIDE This guide describes in detail the type and nature of BWR feedwater and condensate system tests that are acceptable to the staff.

EVALUATION OF BRAUN SAR (BWR TURBINE ISIRID) WITH RESPECT TO THE REGULATORY GUIDE The appropriate revision of Regulatory Guide 1.68.1 will be used when the details of the initial test program are developed.

Amn 9 A-33 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.17 REGULATORY GUIDE 1.72 REVISION 1 DATED January 1978 TITLE Spray Pond Plastic Piping REGULATORY GUIDE This guide describes a method for implementing these requirements with regard to the design, fabrication, and testing of figerglass-reinforced thermosetting resin (RTR) piping for spray pond applications. This guide applies to plants using spray ponds es an ultimate heat sink as opposed to rivers, cooling towers, etc.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-34 March 14, 1979

' BRAUN SAR REGULATORY GUIDANCE ASSESSMENTS PDA EXTENSION A.2.1.18 REGULA"GRY GUIDE 1.84 REVISION 12 DATED March 1978 TITLE Code Case Acceptability - ASME Section III Design and Fabrication REGULATORY GUIDE INTENT This guide provides a list of ASME Design and Fabrication Code Cases that have been generically approved by the Regulatory Staff. Code Cases on this list may, for design purposes, be used until appropriately annulled.

Annulled cases are considered " active" for equipment that has been contractually committed to fabrication prior to the annulment.

The guide, Revision 6 and later revisions, requires specific approval by the NRC on all ASME Section III, Class 1 Code Cases not listed.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-35 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENTS A.2.1.19 REGULATORY GUIDE 1.85 REVISION 12 DATED March 1978 TITLE Code Case Acceptability - ASME Section III Materials REGULATORY GUIDE This guide provides a list of ASME Materials Code Cases that have been generically approved by the Regulatory Staff.

Code Cases on this list may, for design purposes, be u::cd until appropriately annulled. Annulled cases are considered " active" for equipment that has been contractually committed to fabrication prior to the annulment.

The guide, Revision 6 and later revisions, requires specific approval by the NRC on all ASME Section III, Class 1 Code Cases not listed.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-36 March 14, 1979

BFAUN SAR REGULATORY GUIDANCE ASSESSME!Tr PDA EXTENSION A.2.1.20 REGULATORY GUIDE 1.90 REVISION 1 DATED August 1977 TITLE Inservice Inspection of Pre-stressed Concrete Centainment Structures with Grouted Tendons EVALUATION OF BRAUN SAR (BWR TURBINE ISLAIC)

WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the secpe of the Turbine Island.

Amn 9 A-37 March 14, 1979

BRAUN SAR REGULATCRY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.21 REGULATORY GUIDE 1.92 REVISION 1 DATED Februa 1976 TITLE Combining Modal Responses and Spatial Components in Seismic Response Analysis REGULATORY GUIDE This guide describes metnods for corbining the individual modal responses from a seismic response dynamic analysis and in combining maximum values (in case of time history dynamic analysis) or the representative maximum values (in case of spectrum dynamic analysis) due to multi-directional seismic impact motions.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-38 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.22 REGULATORY GUIDE 1.94 REVISION 1 DATED April 1976 TITLE Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel during the Construction Phase of Nuclear Power Plants REGULATORY GUIDE This guide describes the quality assurance requirements for installatien, inspection and testing of structural concrete and structural steel during the constructicn phase of nuclear power plants.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The QA program for BRAUN SAR references the topical report Braun TR-21 Quality Assurance Program. This report is updated and approved by the NRC annually and provides degrees of compliance to Quality Assurance Regulatory Guides and ANSI N45.2 series standards.

C F Brat.n & Co is committed to use of the QA program described in TR-21 for any nuclear project utilizing BRAUN SAR.

Amn 9 A-39 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSME.NT PDA EXTENSION A.2.1.23 REGULATORY GUIDE 1.95 REVISION 1 DATED JanuTry 1977 TITLE Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release REGULATORY GUIDE This guide describes assumptions acceptable to the Regulatory Staff to be used in assessing the habitability of the control room during and after a postulated external release of chlorine. It also describes requirements for control room isolation and emergency procedures.

EVALUATION OF BRAUN SAR (BWR TURSINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Acn 9 A-40 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENTS PDA EXTENSION A.2.1.24 REGULATORY GUIDE 1.99 REVISION 1 DATED April 1977 TITLE Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials REGULATORY GUIDE Regulatory Guide 1.99 describes an acceptable procedure for prediction of radiation damage to the beltline of reactor vessels of light water reactors.

EVALUATION OF BRAUN SAR (BWR TURBIN'E ISLAND) WITH RESPECT TO TPE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Ann 9 A-41 March 14, 1979

BRAUN SAR REGULATORY GUIDA!'CE ASSESSMENTS PDA EXTENSION A.2.1.25 REGULATORY GUIDE 1.100 REVISION 1 DATED August 1977 TITLE Seismic Qualification of Electric Equipment for Nuclear Power Plants REGULATORY GUIDE This regulatory guide describes guidelines for complying with the Commission's regulations with respect to verifying the adequacy of the seismic design of electrical equipment. This guide requires that IEEE Standard 344-1975 with supplemental regulatory requirements be used.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATOTY CUIDE The regulatory position does not address any structures, systems, or components within the scope of the Tarbine Isl4 .d.

O Amn 9 A-42 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.26 REGULATORY GUIDE 1.103 REVISION 1 DATED October 1976 TITLE Post-Tensioned Pre-stressing Systems for Concrete Reactor Vessels and Containments EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

A-43 March 14, 1979 g9

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.27 REGULATORY GUIDE 1.106 REVISION 1 DATED March 1977 TITLE Thermal Overload Protection for Electric Motors on Motor-Operated Valves REGULATORY GUIDE The regulatory guide describes acceptable methods of disabling the thermal protection on motor operated valve motors during emergency operation in order to enhance their availability for safety functions.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-44 March 14, 1979

BRAUN SAR REGUIATORY GUIDANCE ASSESSMENT -

PDA EXTENSION A.2.1.28 REGULATORY GUIDE 1.107 REVISION 1 DATED February 1977 TITLE Qualifications for Cement Grouting for Pre-stressing Tendons in Containment Structures EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

A=n 9 A-45 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.29 REGULATORY GUIDE 1.116 REVISION 0-R DATED May 1977 TITLE Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems REGULATORY GUIDE Regulatory Guide 1.116 endorses ANSI N45.2.8-1975, subject to the comments in section C, " Regulatory Position." The purpose of the standard is to provide requirements and guidelines to assure that important items of nuclear power plants, including structures, systems, and components, are installed, inspected, and tested in a manner that will provide adequate confidence that they will perform satisfactorily in service.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the secpe of the Turbine Island.

Amn 9 A-46 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.30 REGULATORY GUIDE 1.118 REVISION 1 DATED November 1977 TITLE Periodic Testing of Electric Power and Protection Systems REGULATORY GUIDE Regulatory Guide 1.118 describes acceptable methods of periodically testing the functional performance and responses of electric power and protection systems.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-47 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.31 REGULATORY GUIDE 1.120 REVISION 1 DATED November 1977 TITLE Fire Protection Guidelines for Nuclear Power Plants REGULATORY GUIDE The purpose of the Fire Protection program is to ensure the capabilities to shutdown the reactor and maintain it in a safe shutdown condition and to minimize radioactive releases to the environment in the event of a fire.

The guide addresses fire protection programs for safety-related systems and equipment and for other plant areas centaining fire hazards that could adversely affect safety-related systems and supplements Regulatory Guide 1.75, " Physical Separation of Electrical Systems".

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-48 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.32 REGULATORY GUIDE 1.122 REVISION 1 DATED February 1978 TITLE Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components REGULATORY GUIDE This guide describes methods for developing design response spectra at various floors or other equipment support locations of interest from the time-history motions resulting from the dynamic analyses of the supporting structures.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-49 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.33 REGULATORY GUIDE 1.123 REVISION 1 DATED July 1977 TITLE Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants REGULATORY GUIDE Regulatory Guide 1.123 endorses NASI N45.2.13-1976, subject to the comments in Section C, " Regulatory Postion." The purpose of the standard is to describe requirements and provide guidelines for the control of activities to be exercised during procurement of items and services which affect the quality of nuclear pcwer plants.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-50 March 14, 1979

BRALU SAR REGULATORY GUIDANCE ASSESSMENTS PDA EXTENSION A.2.1.34 REGULATORY GUIDE 1.126 REVISION O DATED March 1978 TITLE An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification REGULATORY GUIDE This guide provides an analytical model and related assumptions and procedures that are acceptable to the NRC staff for predicting the effects of fuel densification in light-water-cooled nuclear power reactors. The guide also describes statistical methods related to product sampling that will provide assurance that this and other approved analytical models will adequately describe the effects of densification for each initial core and reload fuel quantity produced.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-51 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSICN A.2.1.35 REGULATORY GUIDE 1.128 REVISION 1 DATED April 1977 TITLE Installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants REGULATORY GUIDE This Regulatory Guide describes an installation design for Class lE batteries that is in general agreement with IEEE-484-1975.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-52 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.36 REGULATORY GUIDE 1.129 REVISION O DATED April 1977 TITLE Mair.tenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants REGULATORY GUIDE This regulatory guide describes a method acceptable to the NRC staff for performing the maintenance, testing and replacement of large lead storage batteries for all types of nuclear power plants. The guide requires the use of IEEE Standard 450-1975 and additional regulatory requirements. The guide does not include design requirements.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-53 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.37 REGULATORY GUIDE 1.131 REVISIOP O DATED August 1977 TITLE Qualification Tests of Electric Cables, Field Splices and Connection for Light Water Cooled Nuclear Power Plants REGULATORY GUIDE This regulatory guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification testing of electric cables, field splices, and connections for service in light-water-cooled nuclear power plants to ensure that the cables, field splices, and connections can perform their safety-related functions.

This guide states that the procedures described in IEEE Standard 383-1974 are acceptable with the additional requirements stated in the guide.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE For electrical instrumentation and control systems or components in the Turbine Island which interface with safety related systems in the NI (GESSAR Docket STN 40-447) , BRAUN SAR commits for such systems to use the same criteria as is used in the NI with the exception of the seismic Category I classificatien.

Amn 9 A-54 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.38 REGULATORY GUIDE 1.132 REVISION O DATED September 1977 TITLE Site Investigations for Foundations of Nuclear Power Plants REGULATORY GUIDE This guide describes programs of site investigations that would normally meet the needs for evaluating the safety of the site from the standpoint of the performance of foundations and earthworks under most anticipated loading conditions, including earthquakes.

EVALUATION OF BRAUN SAR (BWR TURBINE ISI AND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-55 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.39 REGULATORY GUIDE 1.134 REVISION O DATED September 1977 TITLE Medical Certification and Monitoring of Personnel Requiring Operator Licenses REGULATORY GUIDE This guide descrites a method for complying with the Comnission's regulations for evaluation of the medical qualifications of applicants for initial or renewal operator or senior operator licenses.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-56 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.40 REGULATORY GUIDE 1.135 REVISION O DATED September 1977 TITLE Normal Water Level and Discharge at Nuclear Power Plants REGULATORY GUIDE This guide states requirements for the analysis of the capability of structures to resist the forces of normal ground water, or from lakes, streams, oceans, etc.

EVALUATION 01' BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATOiY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-57 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.41 REGULATORY GUIDE 1.136 REVISION O DATED November 1977 TITLE Material for Concrete Containments REGULATORY GUIDE This guide provides information regarding the NRC staff's position on the acceptability for NRC licensing actions of Article CC-2000 of the "ASME B&PVC,Section III, Division 2 (Concrete Reactor Vessels and Containments)" relative to material requirements. In those areas where the provisions of the above code are considered insufficient for licensing purposes, the staff has provided supplementary guidelines it considers to be acceptable.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-58 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.42 REGULATORY GUIDE 1.137 REVISION 0 DATED Januarj .378 ,

TITLE Fuel Oil Systems for Standby Diesel Generators REGULATORY GUIDE This regulatory guide describes a method that is acceptalbe to the NRC staff for complying with the Commission's regulations regarding fuel-oil systems for standby diesel generators. This guide requires the use of ANSI N-195-1976 and additional regulatory requirements.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-59 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.43 NUREG-0102 (SRP 1. 8) REVISICN 0 TITLE Interfaces for Standard Designs The staff report describes safety-related interfaces, for light water reactors, at the preliminary design stage of review, that should be presented by the reactor vendor in a Nuclear Steam Supply SSAR.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NUREG Section 1.10 of BRAUN SAR provides the interface matrix and physical location of the interface between the Turbine Island and Reactor Island, and between the Turbine Island and Applicant's BOP. Specifics of the interface are described in the appropriate section of the SAR as cross referenced in the matrix. Therefore, BFAUN SAR meets the requirements of NUREG-0102 (SRP 1. 8) .

Ann 9 A-60 March 14, 1979

BRAUN SAR REGULATOR'I GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.44 REGULATORY GUIDE 1.138 REVISION O DATED April 1978 TITLE Laboratory Investigation of Soils for Engineering Analysis and Design of Nuclear Power Plants REGULATORY GUIDE This guide describes laboratory investigations and testing practices for determining soil and rock properties and characteristics needed for engineering analysis and design for foundations and earthworks for nuclear power plants. Criteria for planning and performing laboratory tests are also given in the regulatory position.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND' WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address. any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-61 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.45 REGULATORY GUIDE 1.XXX REVISION O DATED Not Dated TITLE Permanent Dewatering Systems REGULATORY GUIDE The intent of this guide is to describe methods acceptable to the NRC staff for designing a permanent dewatering system.

EVALUATION OF BRAUN SAR (BWR TUFBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

A=n 9 A-62 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.46 REGULATORY GUIDE 1.140 REVISION O DATED March 1978 TITLE Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of LWR's REGULATORY GUIDE This guide presents methods acceptable to the NRC staff for implementing the Commission's regulations in 10 CFR Part 50 and in Appendices A and 1 to 10 CFR 50 with regard to the design, testing, and maintenance criteria for air filtration and adsorption units installed in the normal ventilation exhaust systems of light-water-cooled nuclear power plants. This guide applies only to atmosphere cleanup systems designed to collect airborne radioactive materials during normal plant operation, including anticipated operational occurrences, and addresses the atmosphere cleanup systems, including various components and ductwork in the normal operating environment.

This guide does not apply to post-accident engineered-safety-feature atmosphere cleanup systems that are designed to mitigate the consequences of postulated accidents. Regulatory Guide 1.52, " Design, Testing, and Maintenance Criteria for Post-accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants,"

provides guidance for these systems.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turibne Island.

Amn 9 A-63 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.47 REGULATORY GUIDE 1.142 REVISION O DATED April 1978 TITLE Safety-Related Concrete Structures REGULATORY GUIDE This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with reagrd to safety-related concrete structures (other than reactor vessels and containments) for nuclear power plants.

ACI Standard 349-76, " Code Requirements for Nuclear Safety-Related Structures" is incorporated in this guide by reference.

ACI Standard 349-76 delineates requirements for the sizing of concrete structural systems and elements, requirements for construction details, and specifications and tests for materials.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-64 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.48 REGULATORY GUIDE 8.19 REVISION O DATED May 1978 TITLE Occupational Radiation Dose Assessment at LWR's - Design Stage Man-Rem Estimates REGULATORY GUIDE The objective of this guide is to describe a method acceptable to the NRC Staff for perfoming an assessment of collective occupational radiation dose as part of the process of designing a ligh-water-cooled power reactor (LWR) .

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE Although not divided in comparable detail as indicated in this Guide, the format of the radiological assessment contained in Section 12.1.6 and specifically Tables 12.1-4 and 12.1-5 conform to the intent of Regulatory Guide 8.19. These data are Braun's estimate of the activities performed in the Turbine Island and are consistent with the Task 5 Report of AIF, " Compilation and Analysis of Data on Occupational Radiation Exposure Experienced at Operational Nuclear Power Pl&nts." These data are of a preliminary nature r.c.d are, of course, dependent on the operational philosophies of the applicant.

As specific operational and maintenance requirements of the applicant become available, a more detailed radiological assessment will be made possible and the principle of this Guide will be used to continue Braun's design approach of maintaining radiation exposure in the Turbine Island ALARA.

Amn 9 A-65 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.1.49 BRANCH TECHNICAL POSITION RSB 5-2 REVISION O DATED April 1978 TITLE Reactor Coolant System Overpressure Protection BRANCH TECHNICAL POSITION This BTP describes methods acceptable to the NRC staff for avoiding inadvertent overpressurization cf a Pressurized Water Reactor primary system at low temperatures.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-66 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.1 REGULATORY GUIDE 1.27 REVISION 2 DATED January 1976 TITLE Ultimate Heat Sink for Nuclear Power Plants REGULATORY GUIDE This guide applies to all types of nuclear power plants that use water primarily as the ultimate heat sink. The guide describes a bcais that may be used to implement General Design Criteria 44 and 2.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-67 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.2 REGULATORY GUIDE 1.52 REVISION 1 DATED July 1976 TITLE Design, Testing, and Maintenance Criteria for Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cocled Nuclear Power Plants EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Ann 9 ' Gd March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.3 REGULATORY GUIDE 1.59 REVISION 2 DATED August 1977 TITLE Design Basis Floods for Nuclear Power Plants REGULATORY GUIDE In cases where site flooding is postulated this guide states requirements for flood protection for safety-related structures, systems and components.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-69 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.4 REGULATORY GUIDE 1.63 REVISION 1 DATED TITLE Electric Penetratien Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-70 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.5 REGULATORY GUIDE 1.68.2 REVISION 1 DATED July 1978 TI"LE Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants REGULATORY GUIDE This guide describes an initial startup test program, acceptable to the NRC staff, for demonstrating the capability to shut down the hot operating and cold reactor from outside the control room by fulfilling three objectives.

1 verification that the nuclear power plant can be safely shut down from outside the control room.

2 Verification that the nuclear power plant can be maintained in the hot shutdown condition from outside the control room.

3 Verification that the nuclear power plant has the potential for being safely cooled from hot and cold shutdown conditions from outside the control room.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-71 March 14, 1979

BRAUN SAR REGULATCRY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.6 REGULATORY GUIDE 1.91 REVISION 1 CATED February 1978 TITLE Evaluation of Explosions Postulated to Occur on Transportation Routes Necr Nuclear Power Plant Sites REGULATORY GUIDE This guide describes a method for determining distances from the power plant to a railway, highway, or navigable waterway beyond which any explosion that mtcht occur en these transportation routes is not likely to have an adverce effect on plant operation or prevent a safe shutdown.

EVALUATION OF BRAUN SAR (BWR TURSINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Ann 9 A-72 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.7 REGULATORY GUIDE 1.97 REVISION 1 DATED August 1977 TITLE Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident REGULATORY GUIDE This guide describes a method acceptable to the NRC staff to provide instrumentation to monitor plant variables and systems during and following an accident.

EVALUATICN OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-73 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.8 REGULATORY GUIDE 1.102 REVISICN 1 DATED September 1976 TITLE Flood Protection for Nuclear Power Plants REGULATORY GUIDE This guide describes types of flood protection guidelines for the safety-related structures, systems, and cceponents identified in Regulatory Guide 1.29 that must be designed to withstand the Safe Shutdown Earthquake and remain functicnal.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine I91and.

Amn 9 A-74 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.9 REGULATORY GUIDE 1.105 REVISION 1 DATED Noverber 1976 TITLE Instrument Setpoints REGULATORY GUIDE This guide describes guidelines for ensuring that the instrument setpoints in systems important to safety initially are within and remain within the specified limits.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE For electrical instrumentation and control systems or components in the Turbine Island which interface with safety related systems in the NI (GESSAR Docket STN 50-447) , BRAUN SAR commits for such systers to use the same criteria as is used in the NI with the exception of the Seismic Category I classification.

Amn 9 A-75 March 14, 1979

BRAUN SAR BEGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.10 REGULATORY GUIDE 1.108 REVISION 1 DATED August 1977 TITLE Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants REGULATORY GUIDE This Regulatory Guide describes Diesel Generator Design features and testing provisions which are acceptable for verification of availability and reliability of Standby Power Sources.

EVALUATION OF BRAUN SAR (BWR TURDINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-76 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.ll REGULATORY GUIDE 1.115 REVISION 1 DATED J 21y 1977 TITLE Protection Against Low-Trajectory Turbine Missiles REGULATORY GUIDE This guide describes guidelines for protecting safety-related structures, systems, and components against low-trajectory missiles resulting from turbine failure by appropriate orinetation and placement of the trubine-generator set.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE BRAUN SAR meets the Regulatory Guide requirements by orientation of the Turbine Generator axis inline with the Reactor Island safety related structures and by the fact that BRAUN SAR is a single unit plant.

Other safety related structures and multi-unit plants must be evaluated by an owner-applicant.

Amn 9 A-77 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.12 REGULATORY GUIDE 1.117 REVISION 1 DATED April 1978 TITLE Tornado Design Classification REGULATORY GUIDE This guida describes a method for identifying those structures, systems, and components of light-water-cooled reactors that should be designed to withstand the effects of the Design Basis Tornado (see Regulatory Guide 1.76, " Design Basis Tornado for Nuclear Power Plants") including tornado missiles, and remain functional.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-78 March 14, 1979

BRAUN SAR REGULATORY GUILidCE ASSESSMENT PDA EXTENSION A.2.2.13 REGULATORY GUIDE 1.124 REVISION 1 DATED January 1978 TITLE Service Limits and Loading Combinations for Class 1 Linear Type Component Support REGULATORY GUIDE This guide delineates acceptable levels of service limits and combinations of loadings associated with normal operation, postulated accidents, and specified seismic events for the design of Class 1 linear-type component supports as defined in Subsection NF of Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAID) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-79 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.14 REGULATORY GUIDE 1.130 REVISION O DATED July 1977 TITLE Design Limits and Loading Combinations for Class 1 Plate- and Shell-Type Ccmponent Supports REGULATORY GUIDE This guide delineates design limits and combinations of loadings associated with normal operation, postulated accidents, and specified seismic events for the design of Class 1 plate-and-shell type component supports as defined in Subsection NF of Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-80 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA Er"ENSICN A.2.2.15 REGULATORY GUIDE 1.137 REVISION O DATED January 1978 TITLE Fuel Oil Systems for Standby Diesel Generators REGULATORY GUIDE INTENT This regulatory guide describes a method that is acceptable to the NRC staff for complying with the Commission's regulations regarding fuel-oil systems for standby diesel generators. This guide requires the use of ANSI N-195-1976 and additional regulatory requirements.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulstory position does not address any structures, systems, or components within the scope of the Turbine Island.

A=n 9 A-81 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.16 REGULATORY GUIDE 8.8 REVISION 2 DATED August 1976 TITLE Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be as Low As is Reasonable Achievable (Nuclear Power Reactors)

REGULATORY GUIDE This guide primarily is addressed to assuring that the plant operator carries out his activities so operational radiation exposure is ALARA.

However, the system / equipment suppliers are also responsible for design / arranging so as to achieve ALARA conditions per pertinent parts of Section C.2.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The Turbine Island design meets the intent of Regulatory Guide 8.8 as it applies to the design of the facility, exclusive of those sections of this Guide concerning health physics programs and operational philosophies of the applicant, which currently have not been determined. Section 12.1 contains specific features of the Turbine Island design which incorporate the basic principles contained in Regulatory Guide 8.8.

Amn 9 A-82 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.17 BRANCH TECHNICAL POSITION ASB 9.5-1 DATED May 1, 1976 TITLE Guidelines for Fire Protection for Nuclear Power Plants Under Review and Construction BRANCH TECHNICAL POSITION The assessment for this item was written with the assessment on Regulatory Guide 1.120, Section A.2.1.31 of this document. c EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE BRANCH TECHNICAL POSITION The Turbine Island design meets the requirements of Regulatory Guide 1.120 Revision 1 where applicable.as described in Section 9.5.1. The Turbine Island contains no safety class systems or systems necessary for safe shutdown of the reactor. As such, no fire hazard analysis is required.

Amn 9 A-83 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.18 BRANCH TECHNICAL POSITION MTEB 5-7 DATED July 1977 TITLE Material Selection and Processing Guidelines for BWR Coolat Pressure Boundary Piping BRANCH TECHNICAL POSITION Branch Technical Position MTED 5-7 provides material selection and processing guidelines, and identifies acceptable methods to minimize susceptibility to stress corrosion in BWR pressure boundary piping.

EVALUATION OF BRAUN SkR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-84 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.19 SRP 5.4.7 REVISION 1 DATED January 1978 TITLE Residual Heat Removal System EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-85 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.2.20 REGULATORY GUIDE 1.141 REVISION O DATED April 1978 TITLE Containment Isolation Provisions for Fluid Systems REGULATORY GUIDE This guide describes a method acceptable to the NRC staff for complying with the Commission's requirement with respect to containment isolation of fluid systems. This guide incorporates ANSI N271-1976, " Containment Isolation Provisions for Fluid Systems".

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH FISPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-86 March 14,1979

BR%N SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.1 REGULATORY GUIDE 1.56 REVISION 1 DATED July 1978 TITLE Maintenance of Water Purity in Boiling Water Reactors REGULATORY GUIDE This guide describes a method acceptable to the NRC staff for implementing the general design criteria with regard to minimizing the probability of corrcsion-induced failure of the reactor coolant pressure boundary in boiling water reactors (BWRs) by maintaining acceptable purity levels in the reactor coolant. It further describes instrumentation acceptable to the NRC staff for determining the condition of the reactor coolant and coolant purification systems in BWRs.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The condensate cleanup system is a part of the Turbine Island and is described in BRAUN SAR Section 10.4.6. It is designed to maintain acceptable reactor coolant purity levels in accordance with Regulatory Guide 1.56.

Amn 9 A-87 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.2 REGULATORY GUIDE 1.68.2 REVISION 1 DATED July 1978 TITLE Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants REGULATORY GUIDE This guide describes an initial startup test program, acceptable to the NRC staff, for demonstrating the capability to shut dewn the hot operating and cold reactor from outside the control room by fulfilling three objectives.

1 verification that the nuclear power plant can be safely shut down from outside the control room.

2 Verification that the nuclear power plant can be maintained in the het shutdown condition from outside the control room.

3 Verification that the nuclear power plant has the potential for being safely cooled from hot and cold shutdown conditions from outside the control room.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-88 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENTS PDA EXTENSION A.2.3.3 REGULATORY GUIDE 1.99 REVISION 1 DATED April 1977 TITLE Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials REGULATORY GUIDE Regulatory Guide 1.99 describes an acceptable procedure for prediction of radiation damage to the beltline of reactor vessels of light water reactors.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-89 March 14, 1979

~

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.4 REGULATORY GUIDE 1.101 REVISION 1 DATED March 1977 TITLE Emergency Planning for Nuclear Power Plants REGULATORY GUIDE This guide provides more complete guidance in developing the emergency plans required in the FSAR.

EVALUATION OF BRAUN SAR (BWR TUP 3INE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-90 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.5 REGULATORY GUIDE 1.114 REVISION 1 DATED Nove:rber 1976 TITLE Guidance on Being Operator at the Controls of a Nuclear Power Plant REGULATORY GUIDE This guide ciescribes a method acceptable to the NRC scaff for complying with the Commission's regulations that require an operator to be present at the controls of a nuclear power plant.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-91 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.6 REGULATORY GUIDE 1.121 REVISION O DATED May 1976 TITLE Bases for Plugging Degraded PWR Steam Generator Tubes EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-92 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.7 REGULATORY GUIDE 1.127 REVISICN 1 DATED March 1978 TITLE Inspection of Water-Control Structures Associated w4.th Nuclear Power Plants REGULATORY GUIDE This guide describes a basis for developing an appropriate in-service inspection and surveillance program for dams, slopes, canals, and other water-control structures associated with emergency cooling water systems as flood protection of nuclear power plants.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH PISPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-93 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.8 REGULATORY GUIDE 1.137 REVISION O DATED September 1977 TITLE Fuel Oil Systems for Standby Diesel Generators EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-94 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSPI!Tr PDA EXTENSION A.2.3.9 SRP 5.4.7 REVISION 1 DATED January 1978 TITLE Residual Heat Removal System EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-95 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.10 REGULATORY GUIDE 1.141 REVISION G DATED April 1978 TITLE Containment Isolation Provisions for Fluid Systems REGULATORY GUIDE This guide describes a method acceptable to the NRC staff for complying with the Commission's requirement with respect to centainment isolation of fluid systems. This guide incorporates ANS1 N271-1976, " Containment Isolation Provisions for Fluid Systems".

EVALUATION OF BRAUN SAR (BWR TUPBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-96 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.3.ll RSB 5-2 REVISION O DATED March 1978 TITLE Reactor Coolant System Overpressurization Protection EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or compcnents within the scope of the Turbine Island.

Amn 9 A-97 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.4.1 REGULATORY GUIDE 1.13 REVISION 1 DATED December 1975 TITLE Spent Fuel Storage Facility Design Basis REGULATORY GUIDE This guide delineates the design criteria that are appropriately applied to the fuel storage facility.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not addresa any structures, systems, or components within the scope of the Turbine Is.'.and.

Amn 9 A-98 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.4.2 REGULATORY GUIDE 1.14 REVISICN 1 DATED August 1975 TITLE Reactor Coolant Pump Flywheel Integrity REGULATORY GUIDE This guide describes a method acceptable to the NRC staff of implementing requirements with regard to minimizing the potential for failures of the flywheels of reacotr coolant pump motors.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

4 Amn 9 A-99 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.4.3 REGULATORY GUIDE 1.79 REVISION 1 DATED September 1975 TITLE Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors REGULATORY GUIDE This guide describes a preoperational test program acceptable to the staff specifically for emergency core cooling systems (ECCS) in pressurized water reactor power plants.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-100 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.4.4 REGULATORY GUIDE 1.83 REVISION 1 DATED July 1975 TITLE Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The regulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-101 March 14, 1979

BRAUN SAR REGULATORY GUIDANCE ASSESSMENT PDA EXTENSION A.2.4.5 REGULATORY GUIDE 1.104 REVISION O DATED February 1976 IITLE Overhead Crane Handling Systems for Nuclear Power Plants REGULATORY GUIDE This guide includes requirements, acceptable to the NRC, to be placed on overhead cranes which handle critical loads such as spent fuel casks or loads which if dropped could damage safety related systems.

EVALUATICN OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE REGULATORY GUIDE The segulatory position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-102 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.6 EP SECTION 5.4.2.1 DATED November 24, 1978 TITLE BTP MTEB-5-3, Monitoring of Secondary Side Water Chemistry in PWR Steam Generators EVALUATION OF BRAUN SAR (BRR TURBINE ISLAND) WITH RESPECT TO THE STANDARD REVIEW PLAN The Branch Technical Position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-103 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.7 SRP SECTION 6.2.1, 6.2.lA, 6.2.lB, DATED November 24, 1975 6.2.1.2, 6.2.1.3, 6.2.1.4, 6.2.1.5 TITLE BTP CSB-6-1, Minimum Containment Pressure Model for PWR ECCS Performance Evaluation EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE STANDARD REVIEW PLAN The Branch Technical Position does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-104 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.8 SRP SECTION 6.2.5 REVISION 0 DATED November 24, 1975 TITLE BTP-6-2, Control of Combustible Gas Cr.tcentrations in Containment Following a Loss-of-Coolant Accident BRANCH TECHNICAL POSITION CSB 6-2 describes an acceptable method of implementing control of combustible gas concentrations in BWR/6 Mark III Containment.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO BTP The Branch Technical Position does not address any structure, system, or components within the scope of the Turbine Island.

A=n 9 A-105 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.9 SRP SECTICN 6.2.3 REVISION 0 DATED November 24, 1975 TITLE BTP CSB-6-3, Determination of Bypass Leakage Path in Dual Containment Plants BRANCH TECHNICAL POSITION The basis for determining bypass leakage paths can have an impact on site dose (10CFR100). This BTP sets criteria which systems that will contribute / mitigate site dose have to address in order to provide some assurance that there will not be a safety related concern in regards to bypass leakage.

EVAI4'ATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO BTP The Branch Technical Position does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-106 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.10 SRP SECTION 6.2.4 DATED November 24, 1975 TITLE BTP CSB-6-4, Containment Purging During Normal Plant Operations BRANCH TECHNICAL POSITION This branch technical position pertains to system lines which can provide an open path from the containment to the environs during normal plant operation, eg, the purge and vent 14.nes of the containment purge system.

It supplements the position taken in SRP Section 6.2.4.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO BTP The Branch Technical Position does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-107 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.ll SRP SECTION 9.1.4 REVISION O DATED November 24, 1975 TITLE BTP ASB-9.1, Overhead Handling Systems for Nuclear Power Plants BRANCH TECHNICAL POSITION This Branch Technical Position describes an acceptable method for designing overhead handling systems when failure could cause damage to spent fuel or safety related systems.

EVALUATION CT BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO BTP The Branch Technical Position does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-108 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSIGN A.2.4.12 SRP SECTION 10.4.9 TITLE BTP ASB-10.1, Design Guidelines for Auxiliary Feedwater System Pump Drive and Power Supply Diversity for PWR's The Branch Technical Position addresses PWR's and as such was not assessed for BRAUN SAR.

Amn 9 A-109 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.13 SRP SECTION 3.5.3 REVISION O DATED November 24, 1975 TITLE Procedure for Composite Section Local Damage Predictions (SRP Section 3.5. 3, par. II.l.C)

STANDARD REVIEW PLAN DESCRIPTION This SRP states that NRC staff's position relating to the procedures to be utilized in the design of seismic Category I structures to withstand the effects of missile impact on composite missile barriers.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-110 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.14 SRP SECTION 3.7.1 REVISION O DATED November 24, 1975 TITLE Development of Design Time History for Soil-Structure Interaction Analysis (SRP Section 3. 7.1, par. II. 2)

STANDARD REVIEW PLAN DESCRIPTION This SRP paragraph describes NRC Staff Acceptance Criteria for developing the time history to be used at the base of the soil structure interaction system.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or ccxponents within the scope of the Turbine Island.

Amn 9 A-lli March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.15 SRP SECTION 3.7.2 REVISION O DATED November 24, 1975 TITLE Procedures for Seismic System Analysis (SRP Section 3. 7. 2, par. II)

STANDARD REVIEW PLAN DESCRIPTION This SRP paragraph describes criteria acceptable to the NRC staff for seismic analysis methods including natural frequencies and response loads and procedures for analytical modeling.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-ll2 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.16 SRP SECTION 3.7.3 REVISION O DATED November 24, 1975 TITLE Procedure for Seismic Subsystem Analysis (SRP Section 3.7.3, par. II)

STANDARD REVIEW PLAN DESCRIPTION This SRP paragraph describes criteria acceptable to the NRC staff for seismic subsystem analysis such as determination of the number of earthquake cycles and analytical procedures for piping systems.

EVALUATION OF BRAUN SAR (BdR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-ll3 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.17 SRP SECTION 3.8.1 REVISION O DATED November 24, 1975 TITLE Design and Construction of Concrete Containments (SRP Section 3.8.1, par. II)

STANDARD REVIEW PLAN DESCRIPTION This SRP provides the NRC staff's position on design of concrete containments.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-114 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.18 SRP SECTION 3.8.2 REVISION 0 DATED November 24, 1975 TITLE Design and Construction of Steel Containments (SRP Section 3.8.2, par. II)

STANDARD REVIEW PLAN DESCRIPTION This SRP states the NRC staff's position on steel containments and other Class MC steel portions of steel containments.

EVALUATION OF bRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-115 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.19 SRP SECTION 3.8.3 REVISION O DATED November 24, 1975 TITLE Structural Design Criteria for Category I Structures Inside Containment (SRP Section 3. 8. 3, par. II)

STANDARD REVIEW PLAN DESCRIPTION This guideline states the requirements for the design of structures inside containment such as the drywell, the weir wall, containment pool walls, reactor pedestal, shield wall and pipe support structure, and other internal structures.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-ll6 March 14, 1979

ERAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.20 SRP SECTION 3.8.4 REVISION O DATED November 24, 1975 TITLE Structural Design Criteria for Other Seismic Category I Structures (SRP Section 3.8.4, par. II)

STANDARD REVIEW PLAN DESCRIPTION This SRP states the NRC staff's position on the design of Category I structures other than the containment and its interior structures.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-117 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.21 SEP SECTION 3.8.5 REVISION O DATED November 24, 1975 TITLE Structural Design Criteria for Foundations (SRP Section 3.8.5, par. II)

STANDARD REVIEW PLAN DESCRIPTION This section of the SRP defines the internal branches of the NRC responsible for the review responsibilities of this SRP section and the applicable review areas, acceptance criteria, review procedures, and evaluation findings statement.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-ll8 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.22 SRP SECTION 3.7, 11.3, REVISION O DATED November 24, 1975 11.2, 11.4 TITLE Seismic Design Requirements for Radwaste Systems and Their Housing Structures (SRP Section 11.2, BTP ETSB 11-1, par. B.v)

STANDARD REVIEW PLAN DESCRIPTION This position paper sets forth design guidance for radwaste systems and recommendations are given for provisions to preclude the inadvertent release of radioactive materials and sets criteria for seismic design requirement of the radwaste system and structures.

EVALUATICN OF BRAUN SAR (BWR TURSINE ISLAND) WITH RESPECT TO SRP The main condenser off-gas system is housed in the Turbine Island.

The protective structure for the major radwaste containing components of the off-gas system is described in Section 3.2.6.3.4.1 of BRAUN SAR.

This structure is designed to the requirements of BTP ETSB 11-1, paragraph B.v.

Amn 9 A-119 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.23 SRP SECTION 3.3.2 REVISION O DATED November 14, 1975 TITLE Tornado Load Effect Cembinations (SRP Section 3.3.2, par.

II.2.d)

STANDARD REVIEW PLAN DESCRIPTION This section of the SRP defines the internal branches of the NRC responsible for the review responsibilities of this SRP section, the applicable review areas relating to the design of structures that must withstand the effects of the design basis tornado (DBT) specified for the plant, the design parameters and procedures relative to structural loads from pressure and missiles, the NRC acceptance criteria and review procedures, and the NRC acceptable evaluation findings statement.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

L Amn 9 A-120 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.24 SRP SECTION 3.4.2 REVISION O DATED November 24, 1975 TITLE Dynamic Effects of Wave Action (SRP Section 3.4.2, par. II)

STANDARD REVIEW PLAN DESCRIPTIC..

For plants where the flood level is higher than the proposed grade around the plant structures, the dynamic phenomena associated with such a flooding, such as currents, wind waves, and their hydrological effects, are to be considered.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-121 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSEMENT PDA EXTENSION A.2.4.25 SRP SECTION 10.4.7 DATED October 1, 1975 TITLE Water Hammer for Steam Generators with Preheaters (SRP Section 10.4.7, par. I.2.b)

This item is applicable to the steam generator for a PWR and therefore was not assessed against the BRAUN SAR design.

Amn 9 A-122 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSFENT PDA EXTENSION A.2.4.26 SRP SECTION 4.4 REVISION O DATED November 24, 1975 TITLE Thermal-Hydraulic Stability (SRP SECTION 4.4, par. II . 5)

STANDARD REVIEW PLAN DESCRIPTION This standard review plan defines typical methods to demonstrate that the reactor is free or undamped oscillations or other hydraulic instabilities for all conditions of steady-state operation, for all operational transients, for all load following maneuvers, and for partial loop operation.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-123 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.27 SRP SECTION 5.2.5 REVISION O DATED November 24, 1975 TITLE Intersystem Leakage Detection (SRP Section 5.2.5, par. II.4, and Regulatory Guide 1.45)

STANDARD REVIEW PLAN DESCRIPTICN Provisions should be made to monitor systems connected to the RCPB for signs of intersystem leakage. Detection methods include radioactivity monitoring and indicators to show abnormal water levels or flow in the potentially affected systems and unaccountable increases in reactor coolant make-up flow.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO SRP The Standard Review Plan does not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-124 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.28 SRP 3.2.2 REVISION O DATED November 24, 1975 TITLE Main Steam Isolation Valve Leakage Control System (SRP Section 10.3, par. III.3, and BTP RSB-3.2)

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE SRP The Standard Review Plan does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-125 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION to2.4.29 SRP SECTION 3.5.3 REVISION O DATED December 1, 1976 TITLE Ductility of Reinforced Concrete and Steel Structural Elements Subjected to Impactive or impulsive Loads STANDARD REVIEW PLAN. DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979 - subject - Extension Review Matter for PDA's.

In the evaluation of overall response of reinforced concrete structural elements (eg, missile barriers , columns , slabs , etc) subjected to impactive or impulsive loads, such as impacts due to missiles, assumption on non-linear response (ie, ductility ratios greater than unity) of the structural elements is generally acceptable provided that the safety functions of the structural elements and those of safety-related systems and components supported or protected by the elements are maintained.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-126 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.30 SRP SECTION 3.7.1 REVISION N/A DATED August 1, 1976 TITLE Response Spectra in Vertical Direction STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird - dated January 24, 1979 - subject - Extension Review Matter for PDA's.

Subsequent to the issucnce of Regulatory Guide 1.60, the report " Statistical Studies of Vertical and Horizontal Earthquake Spectra" was issued in January 1976 by FRC as NUREG-0003. One of the important conclusions of this report is that the response spectrum for vertical motion can be taken as 2/3 the response spectrum for horizontal motion over the antire range of frequencies in the Western United States. According to Regulatory Guide 1.60, the vertical response spectrum is equal to the horizontal response spectrum between 3.5 cps and 33 cps. For the Western United States only, consistent with the latest available data in NUREG-0003, the option of taking the vertical design response spectrum as 2/3 the horizontal response spectrum over the entire range of frequencies will be accepted. For other locctions, the vertical response spectrum will be the same as that given in Regulatory Guide 1.60.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESP Cf TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-127 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSIOti A.2.4.31 SRP SECTION 3.8.1, 3.8.2 DATED April 1, 1976 TITLE BWR Mark III Containment Pool Dynamics STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E of NRC letter, R S Boyd to H A Baird - dated January 24, 1979 - subject - Extension Review Mat *er for PDA's.

EVALUATION OF BRALN SAR (BWR TURIIINE ISLAND) WITH PISPECT TO SPP The Standard Review Plan does not address any structure, system, or component within the scope of the Turbine Island.

Amn 9 A-128 March 14, 1979

9 BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.32 SRP SECTION 3.8.4 REVISION O DATED September 1, 1976 TITLE Air Blast Loads STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird - dated January 24, 1979 - subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELIIES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-129 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.33 SRP SECTION 3.5.3 REVISION O DATED November 24, 1975 TITLE Tornado Missile Impact STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird - dated January 24, 1979 - subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBIIG ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-130 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.34 SRP SECTION 6.3 REVISION N/A DATED October 13, 1978 TITLE Passive Failures During Long-Tem Cooling Following LOCA STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird - dated January 24, 1979 - subject - Extension Review Matters for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or corponents within the scope of the Turbine Island.

Amn 9 A-131 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.35 SRP SECTION 6.3 REVISION 2 DATED September 1, 1977 TITLE Control Room Position Indication of Manual (Handwheel) Valves in the ECCS STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird - dated January 24, 1979 - subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINEC The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-132 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.3G SRP SECTION 15.1.5 REVISION O DATED April 1, 1977 TITLE Long-Tem Recovery from Steamline Break - Operator Action to Prevent Overpressurization This is a PWR item and is not applicable to the BRAUN SAR design.

A::n 9 A-133 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.37 SRP SECTIONS 5.4.6 REVISION N/A DATED December 1, 1977 5.4.7 6.3 TITLE Pump Operability Requirements STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statment of NRC letter, R S Boyd to H A Baird - dated January 24, 1979 - subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-134 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.38 SRP SECTION 3.5.1 REVISION O DATED March 28, 1978 TITLE Gravity Missiles, Vessel Seal Ring Missiles Inside Containment STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures , systems , or components within the scope of the Turbine Island.

Amn 9 A-135 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSTION A.2.4.39 SRP SECTION 4.4 REVISION O DATED January 1, 1977 TITLE Core Thermal-Hydraulic Analysis STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-136 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.40 SRP SECTION 8.3 REVISION O DATED January 1, 1978 TITLE Degraded Grid Voltage Conditions STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE SRP The Standard Review Plan does not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-137 March 14, 1979

BRAUN SAR STANDARD REVIEW PIRJ ASSESSMENT PDA EXTENSION A.2.4.41 SRP SECTICN 6.2.1.2 REVISION O DATED June 1, 1976 TITLE Asymmetric Loads en Components Located Within Containment Subcompartments STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structure, system, or components within the scope of the Turbine Island.

Amn 9 A-138 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.42 SRP SECTION 6.2.6 REVISION N/A DATED September 1, 1977 TITLE Containment Leak Testing Program STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in EnclJsure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

un 9 A-139 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.43 SRP SECTION 6.2.1.4 REVISION 0 DATED January 1, 1977 TITLE Containment Response Due to Main Steam Line Break and Failure of MSLIV to Close STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA s.

EVALUATICN OF BRAUNSAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-140 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.44 SRP SECTION 3.6.1, 3.6.2 REVISION O DATED November 1, 1977 TITLE Main Steam and Feedwater Pipe Failures STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURSINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Ann 9 A-141 March 14, 1979

BRAUN SAR STANDARD REIIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.45 SRP SECTIONS 5.4.1, 9.2.2 DATED January 1, 1976 TITLE Design Requirements for Cooling Water to Reactor Coolant Pumps STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA's.

EVALUAi!ON OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-142 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSFINT PDA EXTENSION A.2.4.46 SRP SECTION 10.4.7 DATED August 1, 1976 TITLE Design Guidelines for Water Hammer in Steam Generators with Top Feeding Design (BTP ASB-10.2)

This item is applicable to the steam generator for a PWR and therefore was not assessed against the BRAUN SAR design.

Arn 9 A-143 March 14, 1979

BRAUN SAR STANDARD REVIEW PLAN ASSESSMENT PDA EXTENSION A.2.4.47 SRP SECTION 3.11 REVISION O DATED January 1, 1976 TITLE Environmental Control Systems for Safety Related Equipment STANDARD REVIEW PLAN DESCRIPTION NRC guidelines provided in Enclosure E statement of NRC letter, R S Boyd to H A Baird, dated January 24, 1979, subject - Extension Review Matter for PDA's.

EVALUATION OF BRAUN SAR (BWR TURBINE ISLAND) WITH RESPECT TO THE NRC GUIDELINES The NRC guidelines do not address any structures, systems, or components within the scope of the Turbine Island.

Amn 9 A-144 March 14, 1979