ML20066J517

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Amend 9 to GESSAR-II
ML20066J517
Person / Time
Site: 05000447
Issue date: 11/08/1982
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML20066J510 List:
References
NUDOCS 8211240358
Download: ML20066J517 (38)
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Text

F GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 b(~%

INSTRUCTIONS FOR FILING AMENDMENT NO. 9 Pages 12.2-2 is reprinted one-sided to correct a page assembly error in Amendment 4. Pages 19.3.3.32-1/19.3.3.32-2 and 19.3.3.33-1/19.3.3.33-2 are included because they were omitted from Revision 8. Tabs are also included for Appendices 18A and 18B.

  • Remove and insert the pages listed below. Dashes (----) in the remove or insert column indicate no action required.

REMOVE INSERT Summary Table of Contents xxxvi xxxvi Chapter 10 10.3-2 10.3-2 Chapter 18 New Chapter 18

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'v' Chapter 18 title page Appendix 18A

New Appendix 18A Appendix 18B

New Appendix 18B

  • Place these tabs, the tabs previously supplied for Chapter 18 and the contents of Chapter 18 at the end of Volume 24.

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l 9211240358 821109 PDR ADOCK 05000447 D PDR Amendment 9 November 8, 1982

GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 4  %

SUMMARY

TABLE OF CONTENTS (Continued)

}

Chapter /

Section Title Volume 17 QUALITY ASSURANCE _

17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION 24

-17.1.1 Organization 17.1.2 Quality Assurance Program 17.1.3 Design Control 17.1.4 Procurement Document Control 17.1.5 Instructions, Procedures, and Drawings 17.1.6 Document Control 17.1.7 Control of Purchased Material, Equipment,,and Services 17.1.8 Identification and Control of Materials, Parts, and Components 17.1.9 Control of Special Processes 17.1.10 Inspection

() 17.1.11 17.1.12 Test Control Control of Measuring and Test Equipment 17.3.13 Handling, Storage, and Shipping 17.1.14 Inspection, Test, and Operating Status 17.1.15 Nonconforming Materials, Parts, or Components 17.1.16 Corrective Action 17.1.17 Quality Assurance Records 17.1.18 Audits 17.1.19 References 17.2 QUALITY ASSURANCE DURING THE OPERATING PHASE 24 O

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GESSAR II 22A7007 238 NUCLEAR ISLAND R v. 9

SUMMARY

TABLE OF CONTENTS (Continued)

Chapter /

Section Title Volume

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18 HUMAN FACTORS 18.1 HUMAN FACTORS ENGINEERING TEAM 24 18.1.1 Review Team Methodology 18.1.2 Survey Team 18.2 SYSTEMS ANALYSIS 24 18.2.1 Event Selection 18.2.2 Emergency Procedures 18.2.3 Event Description 18.2.4 Systems Analyses Results 18.3 TASK ANALYSIS 24 18.3.1 Methodology 18.3.2 Significant Walkthrough Results 18.4 CONTROL ROOM REVIEW 24 18.4.1 Methodology 18.4.2 Significant Control Room Review Results 18.5 CONTROL CENTERS OUTSIDE OF THE MAIN CONTROL PCOM 24 18.5.1 Introduction 18.5.2 Remote Shutdown System Panel - NSSS Comparisons APPENDIX 18A 24 APPENDIX 18B 24 ,

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1 GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 4 10.3 MAIN STEAM SUPPLY 10.3.1 Design Bases Applicant to provide.

10.3.2 Description The main steam lines between the reactor pressure vessel and the shutoff valves are described in Section 5.4. Section 5.2 discus-ses in-service inspection, materials, and environmental condi-tions for the safety-related portions of the system piping. A discussion of the measures provided to limit blowdown of the system in the event of a steam line break is presented in Subsection 5.4.4.

The remainder of the description for the main steam supply will g j

() be supplied by the Applicant.

10.3.3 System Evaluation The portion of the main steam supply deteribed in this section has no safety-related function as discussed in Section 3.2, and therefore is not classified as Seismic Category I.

10.3.4 Tests and Inspections Inspection and testing will be carried out in accordance with the requirements of Table 3.2-1. The main steam line will be hydro-statically tested to confirm leak tightness. Visual inspection of the pipe weld joints in the main steam line will confirm the exterior condition of the weld.

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10.3-1

GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 10.3.5 Water Chemistry (PWR)

Not applicable to BWR. _

10.3.6 Steam and Feedwater System Materials Section 5.4 discusses the Class 2 and 3 portion of the main steam and feedwater piping and contains a discussion of materials. .

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10.3-2

GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. O n

k ,) 12.2.1.2 Reactor Building 12.2.1.2.1 Reactor Vessel Sources 12.2.1.2.1.1 Radiation from the Reactor Core 12.2.1.2.1.1.1 General The information in this section defines a reactor vessel model and the associated gamma and neutron radiation sources. This section is designed to provide the data required for calculations beyond the vessel. The data selected were not chosen for any given pro-gram, but were chosen to provide information for any of several shield program types. In addition to the source data, calculated radiation dose levels are provided et locations surrounding the vessel. These data are given as a potential check point for cal-

~ culations by shield designers.

12.2.1.2.1.1.2 Physical Data Table 12.2-1 presents the physical data required to form the model in Figure 12.2-1. This model was selected to contain as few separate regions as possible to adequately portray the reactor.

Table 12.2-1 provides nominal dimensions and material volume frac-tions for each boundary and region in the reactor model. To describe the reactor core, Table 12.2-1 provides thermal power, power density, core dimensions, core average material volume fractions and reactor power distributions. The reactor power dis-tributions are given for both radial and axial distributions.

These data contain uncertainties in the volume regions near the edge of the core. The level of uncertainties for these regions is estimated at 20%.

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6 18.1 IlUMAN FACTORS ENGINEERING TEAM 18.1-1 l 18.1.1 Review Team Methodology 18.1-1 (

18.1.2 Survey Team 18.1-2 l

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 l

SECTION 18.2 CONTENTS Page 18.2 SYSTEMS ANALYSIS 18.2-1 18.2.1 Event Selection 18.2-1 18.2.2 Emergency Procedures 18.2-2 18.2.3 Event Description 18.2-3 18.2.4 Systems Analyses Results 18.2-4 i

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9

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b SECTION 18.2 TABLES Table Page 18.2-1 Major Contributions to BWR Risk 18.2-5 18.2-2 Events Selected for Human Factors Review 18.2-6 18.2-3a Summary Event Description for Human Factors Evaluation 18.2-7 18.2-3b Emergency Procedure Guideline Application to Human Factors Evaluation 18.2-8 18.2-4a Summary Event Description for Human Pactors Evaluation 18.2-9 18.2-4b Emergency Procedure Guideline Application to Human Factors Evaluation 18.2-10 18.2-5a Summary Event Description for Human Factors Evaluation 18.2-11

(~N 18.2-5b Emergency Procedure Guideline Application to Human Fa' tors Evaluation 18.2-12 18.2-6a Summary Event Description for Human Factors Evaluation 18.2-13 18.2-6b Emergency Procedure Guideline Application to Human Factors Evaluation 18.2-14 18.2-7a Summary Event Description for Human Factors Evaluation 18.2-15 18.2-7b Emergency Procedure Guideline Application to Human Factors Evaluation 18.2-16 18.2-8 Notes to Tables 18.2-3 Through 18.2-7 18.2-17 O

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SECTION 18.3 CONTENTS Page 18.3 TASK ANALYSIS 18.3-1 18.3.1 . Methodology 18.3-1 4 18.3.2 Significant Walkthrough Results 18.3-2 a

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TABLES Table Title e Page

18.3-1 Summary of Event Walkthrough Failpres 18.3-5 i

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 (p,)

SECTION 18.4 CONTENTS Page 18.4 CONTROL ROOM REVIEW 18.4-1 18.4.1 Methodology 18.4-1 18.4.2 Significant Control Room Review Results 18.4-3 ry TABLES Table Title Page I 18.4-1 Control Room Review Checklist Subject Areas 18.4-5 18.4-2 Differences Between the Black Fox Simulator and the 238 Nuclear Island Control Room Design 18.4-6 18.4-3a Summary of Checklist Findings - Panel Layout and Design 18.4-7 18.4-3b Summary of Checklist Findings - Instrumentation and Hardware 18.4-12 18.4-3c Summary of Checklist Findings - Annunciators 18.4-13 18.4-3d Summary of Checklist Findings - Computers 18.4-16 l 0 LJ 18.4-i/18.4-ii

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l GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 SECTION 18.5 CONTENTS Page 18.5 CONTROL CENTERS OUTSIDE OF THE MAIN CONTROL ROOM 18.5-1 l 18.5.1 Introduction 18.5-1

. 18.5.2 Remote Shutdown System Panel - NSSS I

Comparisons 18.5-1 1

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TABLES

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Table Title Page 18.5-1 Remote Shutdown System Panel - NSSS Comparison Survey 18.5-3 ILLUSTRATIONS Figure Title Page 18.5-1 Perry RSS Panel 18.5-5 18.5-2 GESSAR II RSS Panel 18.5-7 l

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GESSAR 11 22A7007 238 NUCLEAR ISLAND Rev. 9

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APPENDIX 18A CONTENTS Section Title Page

  • 18A.1-1 18A EMERGENCY PROCEDURES 18A.1 General Operator Precautions 18A.1-1 18A.2 EP-1 RPV Control 18A.2-1 18A.2.1 RC/L Monitor and Control RPV Water Level 18A.2-2 18A.2.2 RC/P Monitor and Control RPV Pressure 18A.2-13 18A.2.3 RC/O Monitor and Control Reactor Power 18A.2-20 18A.2.4 RPV Flooding 18A.2-22 18A.3 EP-2 Containment Control 18A.3-1 18A.3.1 SP/T Monitor and Control Suppression Pool Temperature 18A.3-1 18A.3.2 DW/T Monitor and Control Drywell Temperature 18A.3-2 18A.3.3 CN/T Monitor and Control Containment Temperature 18A.3-3 18A.3.4 PC/P Monitor and Control Primary Containment Pressure 18A.3-3 18A.3.5 SP/L Monitor and Control Suppression Pool Water Level 18A.3-5 O

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GESSAR II 22A7007 l 238 NUCLEAR ISLAND Rev. 9 i

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ILLUSTRATIONS j Figure Title Page 1

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. 18A-3 Maximum Core Uncovery Limit 18A.3-10 l 18A-4 RPV Saturation Temperature 18A.3-ll 18A-5 Heat Capacity Level Limit 18A.3-12 l

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 O

APPENDIX 18B EMERGENCY RESPONSE INFORMATION SYSTEM i

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SUMMARY

18B-1 18B.2 GENERAL DESCRIPTION 18B-1 18B.3 FUNCTIONAL DESCRIPTION 18B-2 18B.3.1 Introduction 18B-2 18B.3.2 System Operation 18B-3 18B.4 GRAPHIC DISPLAYS 18B-3 18B.4.1 Introduction 18B-3 188.4.2 Critical Plant Variables Display 18B-4 188.4.3 Emergency Procedure Guidelines Displays 18B-4 188.4.3.1 Reactor Pressure Vessel (RPV) Control Display 18B-5 188.4.3.2 Containment Control Display 18B-6 18B.4.4 Two-Dimensional Plots 18B-7 18B.4.5 Trend Plots 18B-8 (x' 18B.5 CONCLUSION 18B-9 C)

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 O APPENDIX 18B ILLUSTRATIONS Figure Title Page 18B-1 Critical Plant Variables Display 18B-ll 18B-2 RPV Control Display 18B-12 18B-3 Containment Control Display 18B-13 O

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SUMMARY

PROPRIETARY INFORMATION - provided under separate cover O

18B.2 GENERAL DESCRIPTION PROPRIETARY INFORMATION provided under separate cover O

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t GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 O

18B.2 GENERAL DESCRIPTION (continued)

PROPRIETARY INFORMATION - provided under separate cover 9

18B.3 FUNCTIONAL DESCRIPTION PROPRIETARY INFORMATION - provided under separate cover O

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 3 e

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18B.4 GRAPHIC DISPLAYS (continued)

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 9 O:

i 18B.5 CONCLUSION (continued)

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, .e GESSAR II 22A7007 l 238 NUCLEAR ISLAND Rev. 8 1

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, 19.3.3.32 QUESTION / RESPONSE 3.32 (241.23)

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/ QUEST 7.ON 3.32 1

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GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 8

() 19.3.3.33 QUESTION / RESPONSE 3.33 (241.24)

QUESTION 3.33 For vertical SSI analysis, the depth of the water table governs

the compressional wave velocity in the medium. Reevaluate your l results for vertical analysis taking into account the effect of the depth of the water table. (3.A 5.2)

. RESPONSE 3.33 f

r The effect of the depth of the water t able on response was accounted for by a variation in the modulus values for both PDA GESSAR and GESSAR II. .

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19.3.3.33-1/19.3.3.33-2

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