ML19329E019

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App 5A of Rancho Seco PSAR, Design Bases for Structures, Sys & Equipment. Includes Revisions 1-4
ML19329E019
Person / Time
Site: Rancho Seco
Issue date: 10/31/1967
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
References
NUDOCS 8004090607
Download: ML19329E019 (13)
v • d • e


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SACRAMENTO MUNICIPAL UTILITY DISTRICT I

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Q__.,.,'d' PRELIMINARY SAFETY ANALYSIS REPORT Volume V

60077-aggg3 TORY JOCIET FILE Cd 01.81 8004090 NOVEMBER 1967

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Docket No. 50-312

-m p-April 15,1968 AMENDMENT NO. 2 SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 Amendment No. 2 to the Sacramento Municipal Utility District's Preliminary Safety Analysis Report includes both replacement pages and new pages and tabs.

All pages to be inserted are identified as Amendment 2, except the reprinted appendices.

Any technical text material changed by this amend-ment is coded in the outside margin by a black bar and the numeral two.

Before inserting the Amendment 2 material in the different volumes, it is suggested that Appendices 2A, 2C, 2D and 2E be removed from Volume IV, discarded and replaced with.the new reprinted appendices 2A, 2C, 2D, and 2E.

Additionally, remove Appendices 3 and 4 (including tabs) from Volume V and place at the back of Volume IV.

The list of Effective Pages should be checked to verify the completeness of Volumes I thru V.

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It should be noted that three new additional pages, 10, 11 and 12 are to be added to the License Application.

The response to letter from Peter A. Morris, Director, Division of Reactor Licensing to E. K. Davis, General Counsel, Sacramento Municipal Utility District, dated March 21, 1968, is arranged in the question order of the above letter.

For convenience a cross reference of the AEC DRL question number and SMUD response number is presented below.

Response to questions

., *nre to be inserted into the volumes according to the assigned SMUD number.

4 N

/

Q v

9 A

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AEC AEC AEC

- 1 DRL SMUD.

DRL SMUD DRL SMUD QUESTION RESPONSE QUESTION RESPONSE QUESTION RESPONSE NO.

NO.

50.

NO.

NO.

NO.

1.1 1A.4 6.1 6A.7 12.1 12A.2 1.2 1A.5 6.2 6A.8 12.2 12A.3 1.3 1A.6 6.3 6A.9 12.3 12A.4 1.4 1A.7 6.4 6A.10 12.4 12A.5 1.5 1A.8 6.5 6A.11 12,5 12A.6 1.6 1A.9 6.6 6A.12 12.6 12A.7 1.7 1A.10 6.7 6A.13 6.8 6A.14 13.1 13A.1 2.1 14A.14 6.9 6A.15 13.2 13A.2 2.2 14A.15 6.10 6A.16 13.3 13A.3 2.3 14A.16 13.4 12A.8 2.4 14A.17 7.1 7A.2 1.5 14A.18,.

7.2 7A.3 14.1 14A.20 2.6 14A.19 7.3 7A.4 14.2 14A.21 2.7 2H.1 7.4 7A.5 14.3 14A.22 2.8 2H.2

'7. 5 7A.6 14.4 14A.23 7.6 7A.7 14.5 14A.24 3.1 3A.6 7.7 7A.S 14.6 14A.25 3.2 3A.7 7.8 7A.9 14.7 14A.26 3.3 3A.8 7.9 7A.10 14.8 14A.27 3.4 3A.9 14.9 14A.28 3.5 3A.10 8.1 8A.1 3.6 3A.11 8.2 SA.2 15.1 15A.1 3.7 3A.12 8.3 6A.3 3.8 3A.13 8.4 SA.4 16.1 7A.ll 3.9 3A.14 8.5 8A.5 16.2 14A.29 3.10 3A.15 16.3 14A.30

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  • 9.1 9A.2 16.4 3A.16 4.1 4A.12 9.2 9A.3 16.5 5J.5 4.2 53.4 9.3 9A 4 16.6 1A.11 4.3 4A.13 9.4 9A.5 4.4 4A.14 9.5 9A.6 4.5 4A.15 9.6 9A.7 9.7 9A.8

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R Amendrae nt 2 i

Docket No* 50-312 g

L1ST OF A ril 15' 1968 s-P

..t E F F ECTIV E' P AG ES 2

d Amendment.o.

6 The active pages in this report are as follpws:

Page or Fig. No.

Issue Page or Fig. No.

Issue

' Title Page.

. Original' Fig. 2.2-1 thru 2.2-10.

. original A thru H

...... A me ndme n t 2 2.3-1 thru 2.3-2.

.. Amendment 2 i.

. Original 2.3-3 thru 2.3-4.

. Original 11.

Amendment 2 2.3-5 thru 2.3-8.

Amendment 2 iii

. Original Fig. 2.3-1 thru 2.3-6.

. Original iv r'.

Amendment 2 2.4-1.

. Original v thru vii.

Amendment 1 2.4-2.

Amendment 2 viii.

Amendment 2 2.4-3.

. Original ix.

Amendment 1 Fig. 2.4-1 thru 2.4-2.

. Original

. Original 2.5-1

. Original x

xi.

Amendment 1 2.6-1.

. Original xii thru xiv.

Amendment 2 2.7-1

. Original 1-1.

. Original 2.8-1 thru 2.8-4.

Amendment 1 1-1i.

Amendment 2 2.9-1

. original 1-tii.

. original 3-i thru 3-iii.

Amendment 2 1-iv.

Amendment 2 3-iv thru 3-vi.

. Original

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1.1-1 thru 1.1-2.

. original 3.1-1.

. Original Fig. 1.1-1.

. Original 3.1-2 thru 3.1-4.

Ame ndment ' 2 Amendment 2

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Fig. 1.1-2 thru 1.1-8.

Amendment 2 3.1-5.

Amendment 2 1,2-1.

. Original 3.1-6..........

1.2-2 thru 1.2-4.

Amendment 2 3.2-1 thru 3.2-2.

. Original 1.3-1 thru 1.3-3.

. Original 3.2-3.

Amendment 2 1.3-4.

Amendment 1 3.2-4 thru 3.2-10.

. Original

. Original 3.2-11.

Amendment 2 L.3-5.

1.3-6 thru 1.3-7.

Amendment 2

3. 2-12 thru 3. 2-69.

. Original 1.3-8.

. Original 3.2-70 thru 3.2-101.

. Amendment 2 y 1. 3-9.

Amendment 2 Fig. 3. 2-1 thru 3. 2-59.

. Original 1.4-1

. Original Fig. 3.2-59 thru 3.2-61. Auendment 2 1.4-2.

Amendment 2 Fig. 3.2-62 thru 3.2-63.

. original 1.4-3.

Amendment 1 Fig. 3.2-64.

Amendment 2 1.4-4 thru 1.4-6.

. Original Fig. 3.2-63.

. Amendment 1 1.4-7 thru 1.4-8.

Amendment 2 Fig. 3.2-60 Original 1.4-9 thru 1.4-37 Amendment 2 Fig. 3.2-67.

. Amendment 2 1.5-1 thru 1.5-2.

Amendment 2 Fig. 3.2-68.

. Amendment 1 1.6-1

. Original Fig. 3.2-69..

Original 1.6-2 thru 1.6-3.

Amendment 2 3.3-1.

. Original

)

Fig. 1.6-1 thru 1.6-2.

. Original 3.3-2.

. Amendment 2 1.7-1

. Original 3.3-3 thru 3.3-5.

Original 1.8-1 thru 1.8-2.

. Original 3.3-6 thru 3.3-7.

. Amendment 2 1.9-1.

. Original 3.3-8 thru 3.3-10.

Original

.,,s.,

2-i thru 2-ii.

Amendment 1 3.3-11 thru 3.3-12..

. Amendment 2

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2-111.

.Origina l 3.4-1 thru 3.4-5.

..... Original 2.1-1

. Original 4-1 thru 4-il.

Original

. i 2.2-1 thru 2.2-5.

. original 4.1-1 thru 4.1-15.

Original x _.,

Amendment 2 C

Docket No. 50-312 LIST OF April 15, 1960 EFFECTIVE PAGES Alendment No. 2

(/ l Page or Fig. No.

Issue Page or Fig. No.

Issue Fig. 4.1 '.

Original Fig. 5.7-1.

. Amendment 2 Fig. 4.1-2.

. Amendment 2

5. 8-1.

Original Fig. 4.1-3 thru 4.1-4.

Original 5.9,1.

Original 4.2-1.

... Amendment 2 6-1.

. Amendment 1 4.2-2 thru 4.2-6.

Original 6-ii.

. Amendment 2 4.2-7 thru 4.2-8.

. Amendment 2 6.0-1.

. Amendment 2 4.2-9.

. Original Fig. 6.0-1.

. Amendment 2

4. 2-10 ti ru 4. 2.11.

. Amendment 2 6.1-1 thru l-7.

. Amendment 2 l

4.2-12.

. Original 6.1-8.

Original Fig. 4.2-1.

. Amendment 2 6.1-9 thru 6.1-10.

. Amendment 2 Fig. 4.2-2 thru 4.2-8.

. Original 6.1-11.

. Amendment 1 4.3-1.

. Amendment 2 6.1-12 thru 6.1-14.

. Amendment 2 4.3-2 thru 4.3-7.

. Original 6.1-15.

. Amendment 1 4.3-8 thru 4.3-10.

. Amendment 2 6.1-16.

. Amendment 2 4.3-11.

. Amendment 1 Fig. 6.1-1 thru 6.1-2

. Amendment 2 4.4-1 thru 4.4-3.

. Orfginal Fig. 6.1-3.

Original 4.4-4.

. Amendment 2 Fig. 6.1-4.

. Amendment 2 4.4-5.

. Original 6.2-1 thru 6.2-8.

. Amendment 2 4.5-1.

. Original Fig. 6.2-1.

. Amendment 2 3-1 thru 5-iii.

. Amendment 1 6.3-1 thru 6.3 '

Original 3.1-1.

. Amendment 1 6.3-3.

. Amendment 2 e

5.1-2

. Original 7-i.

. Amendment 2 h1

'~'

5.1-3.

. Amendment 1 7-ii.

. Amendment 1 5.1-4 thru 5.1-9.

. Original 7-iii.

Original 5.1-10.

. Amendment 1 7.1-1 thru 7.1-20.

. Amendment 2 5.1-11 thru 5.1-24.

Original Fig.

7.1-1.

Original 3.1-25 thru 5.1-26.

. Amendment 1 Fig. 7.1-2 thru 7.1-3

. Amendment 2 5.1-37 thru 5.1-29.

. Original Fig. 7.1-4.

Original 177-3D........... Amendment 1 7.2-1 thru 7.2-5.

Original 5.'l-)l.

........... Original 7.2-6.

. Amendment 2 5.1-32 thru 5.1-33.

. Amendment 1 7.2-7 thru 7.2-8.

. Amendment 1 Fig. 5.1-1 thru 5.1-3.

. Original 7.2-9 thru 7.2-11.

Original Fig. 5.1-4.

...... Amendment 1 Fig. 7.2-1 thru 7.2-4 Original 5.2-1 thru 5.2-5.

. Original 7.3-1 thru 7.3-3.

Original 5.3-1.

. Original 7.3-4 thru 7.3-7.

. Amendment 2 5.4-1.

. Amendment 1 Fig. 7.3-1.

. Amendment 2 5.4-2 thru 5.4-5.

. Original Fig. 7.3-2.

Original 5.4-6.

. Amendment 1 Fig. 7.3-3.

. Amendment 1 5.4-7.

. Original Fig. 7.3-4 thru 7.3-5.

. Amendment 2 5.4-8 thru 5.4-9.

. Amendment 1 7.4-1.

Original 5.5-1 thru 5.5-3.

. Original 7.4-2 thru 7.4-5.

. Amendment 1 5.6-1 thru 5.6-2.

. Original Fig.

7.4-1.

Original 5.6-3 thru 5.6-6.

. Amendment 2 8-i thru 8-11

. Amendment 2 s

Fig.

5.6-1.

.\\.

. Amendment 2 8.1-1.

Original 5.7-1.

. Amendment 2 8.2-1 thru 8.2-18

_\\mendment 2 5.7-2.

. Original Fig. 8.2-1 thru 8.2-3 a cn3 wnt 2 d

9 D

Amendment 2

Docket No. 50-312

  • <r^

LIST OF April 15'..o1968 1

2 EFFECTIVE PAGES Amendment s.

2 s

Page or Fig. No.

Issue Page or Fig. No.

Issue e

8.3-1 thru 8.3-3.

. Amendment 2 12-i...........

. Amendment 1 8.3-4.

. Amendment 1 12.1-1.

Original 8.4-1.

Original' 12.2-1 thru 12.2-2.

. Amendment 2 9-1.

. Original Fig. 12.2-1.

. Amendment 2 9-11 thru 9-iii.

. Amendment 2 12.3-1 thru 12.3-2.

. Amendment 2 9.0-1 thru 9.0-2.

. Original 12.3-3 thru 12.3-5.

. Amendment 1

... Amendment 2 Fig. 9.0-1.

. Original Fig. 12.3-1 Original 9.1-r thru 9.1-2.

. Amendment 2 12.4-1.

9.1-3

. Original 12.5-1.

Original 9.1-4 thru 9.1-7.

. Amendment 2 12.6-1.

Original 9.1-8 Original 12.7-1.

Original Fig. 9.1 1

. Amendment 2 13-1.

. Original 9.2-1.

. Original 13.1-1 thru 13.1-2.

. Original 9.2-2 thru 9.2-7.

. Amendment 2 13.1-3.

Amendment 2 9.2-8.

Original 13.2-1.

. original 9.2-9....

. Amendment 2 13.3-1

. original Fig. 9.2-1.

. Original 14-1.

. original 9.3-1 thru 9.3-6.

. Amendment 2 14-ii thru 14-iii.

Amendment 1 Fig. 9.3-1 thru 9.3-3.

. Amendment 2 14-iv thru 14-viii

. Original

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9.4-1 thru 9.4-4.

. Original 14.1-1 thru 14.1-7.

. Original

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Fig. 9.4-1.

. Amendment 1 14.1-8 thru 14.1-10.

Amendment 2 9.5-1 thru 9.5-3.

. Amendment 2 14.1-11 thru 14.1-15.

. Original 9.5-4.

. Original 14.1-16.

Amendment 2 Fig. 9.5-1 thru 9.5-2

. Amendment 2 14.1-17 thru 14.2-19.

. original 9.6-1.

. Amendment 2 14.1-20.

. Amendment 2 9.6-2 thru 9.6-7.

. Original Fig. 14.1-1 thru 14.1-21.

. original Fig. 9.6-1.

. Original 14.2-1.

. original s',9.7-1 thru 9.7-2.

. Original 14.2-2.

Amendment 2 a

yig. 9.7-1.

. Amendment 2 14.2-3.

Amendment 1 10-i.

. Original 14.2-4.

. original 10.1-1.

. Original 14.2-5 thru 14.2-6.... Amendment 1 10.2-1.

. Amendment 2 14.2-7 thru 14.2-9.

. Original 10.2-2.

. Original 14.2-10.

Amendment 2 Fig. 10.2-1.

. Original 14.2-11 thru 14.2-23.

. Original 10.3-1 thru 10.3-2.

. Original 14.2-24.

Amendment 2 10.4-1.

. Original 14.2-25.

. Original ll-i thru 11-11

. Amendment 1 14.2-26 thru 14.2-30.

Amendment 2 11.1-1 thru 11.1-4.

... Amendment 1 14.2-31 thru 14.2-32.

. Original 11.1-5..

. Amendment 2 14.2-33.

Amendment 2 11.1-6 thru 11.1-8..

. Amendment i 14.2-34.

. original Fig. 11.1-1, 11.1-2.

. Original 14.2-35 thru 14.2-37 Amendment 1 11.2-1.

,,A=qndme n t 1 14.2-38.

Amendment 2 11.2-2 thru 11.\\2-5..

. Original 14.2-39.

. original 11.2-6.

. Amendment 1 Fig. 14.2-1 thru 14.2-18.

. Original

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11.2-7 thru 11.2-11.

. Original Fig. 14.2-19 thru 14.2-20. Amendment 2

)

11.3-1.

. Original Fig. 14.2-21 thru 14.2-28.

. Original s

y Amendment 2 E

f03 LIST OF Docket No. 50-312

. w E F F ECTIV E PAGES April la 1968 Amendment No. 2 Page or Fig. No Issue Page or F,ig. No.

Issue Fig. 14.2-29.

Amendment 2 Preliminary Projections to Fig. 14.2-30 thru 14.2-31.

. original 1985-1 thru 4 Original Fig. 14.2-32 Amendment 2 2C' Geology and Seis:nology-Fig. 14.2-33.

. Original 2C-1 thru 2C-13.

Original Fig. 14.2-34.

Amendment 2 Fig. 2C-1 thru 2C-11.

Original Fig. 14.2-35.

. original Geophysical Report-Fig. 14.2-36.

Amendment 1 1 thru 6.

Original Fig. 14.2-37 thru 14.2-47.

. Original Additional Seismic Exploration-Fig. 14.2-48 thru 14.2-50. Amendment 1 1 thru 2, Plate 1 thru 14.3-1 thru 14.3-2

. Original Plate 3.

Original 14.3-3 thru 14.3-8 Amendment 1 Geological Log of Drill 14.3-9 thru 14.3-10.

Amendment 2 Holes-91 Sheets.

Original 14.3-11 thru 14.3-13.,..

Amendment 1 2D Seismic Report 14.3-14.

Amendment 2 Seismic Hazard at the Fig. 14.3-1 thru 14.3-3.

. Original Clay Site, 1 thru 14.

Original Fig. 14.3-4 thru 14.3-5.

Amendment 1 Addendum to Seismic Hazard Fig. 14.3-6.

. Original at the Clay Site-1 sheet Original Fig. 14.3-7.

Amendment 1 Seismic Hazard at the 14.4-1 thru 14.4-2

. Original Sierran Sites Area 15-1 thru 15-5.

. Original 1 thru 10.

. Amendment 1 Appendix 1 Table of 2E Soil and Foundations 1'. i Contents Amendmen t 2

' Investigation Report 1A Answers to Questions.

Amendment 1 2E-1 thru 2E-11, 1A-1 thru 1A-14.

Amendment 1 Fig. C-119-E thru Fig. 1A.2-1.

Amendment 1 Cl22-E.

Original lA-15 thru 1A-16.

... Amendment 1 Report of Laboratory 1 A-17 th ru 1A-23.

Amendment 2 Testing-1 thru 9, 3 Tables, 13,qpality Assurance Fig. I thru 2 and 9, curves

"*0p g ra t ion s Amendment 1 1 thru 7 Original 13-1Y...........

. Original 2F Meteorological Station 13-2 thru 13-4 Amendment 1 2F-1 thru 2F-2

. Amendment 1 16-5.

Amendment 2 2G Storage Reservoir Criteria Fig. IB-1.

Amendment 2 2G-1 thru 2G-3.

. Amendment 1 1C Rancho Seco Project 2GA-1.

. Amendment 1 Engineering Staff.

Amendment 2 2H Answers to Questions IC-1 thru 1C-4 Amendment 2 2H-1 thru 2H-2

.Am'ndment 2 e

Fig. IC-1.

Amendment 2 Letter pg. I and 2

. Amendment 2 Appendix 2 Table of Fig. 2H.2-1 thru 23.2-2. Amendment 2 Contents.

Amendment 2 Appendix 3 Table of 2A Final Report Contents

. Amendment 1 i thru vi.

. Original 3A Answers to Questions 1 thru 63.

. Original 3A-1 thru 3A-14.

. Amendment t Supplement Fig. 3A.2-1 thru,.3A.2-3.. Amendment i ym s

1 thru 18.

.i.

Amendment 2 Fig. 3A.4-1.

. Amendment 1 23 Southeast Area Plan 3A-15 thru 3A-23.

. Amendment 2 (Bound)-14 pages.

. Original Fig. 3A.14-1.

. Amendment 2 D

F Amendment 2 17

r-(f.

Docket No. 50-312 LIST OF i

I E F F ECTIV E PAGES April 15, 1968 N_ '

Amendment No. 2 Page or Fig. No.

Issue Page or Fig. No.

Issue 3A-24 thru.3A-26.

. Amendment 2 Figure SG-1.

Original Appendix 4 Table of 5H Quality Control Procedure Contents

. Amendment 1 for Field Welding 4A Answers to Questions 5H-1 thru 5H-5.

Original 4A-1 thru 4A-6 51 Containment Structure Fig. 4A.1-1 thru 4A.1-15. Amendment 1 Instrumentation Appendix A 51-1.

Original The Properties and Micro-SJ Answers to Questions structure of Spray-Quenched 5J-l thru 5J-2.

. Amendment 1 Thick-Section Steels Fig. 5J2-1

. Amendment i 15 pages Original 5J-3 thru 5J-14.

. Amendment 2 4A-l Original Appendix 6 Table of

.S 4A-2 thru 4A-8.

. Amendment 1 Contents

.. Amendment i Appendix B, B & W Data 6A Answers to Questions (2 pgs.)

.Ame'ndment t 6A-l.

. Amendment 1 4A-9 thru 4A-12

. Amendment 1 6A-2.

. Amendment 2 4A-l3 thru 4A-18.

. Amendment 2 6A-3 thru 6A-5.

. Amendment 1 Appendix 5 Table of 6A-6 thru 6A-7

. Amendment 2 J_s Contents.

. Amendment 1 Fig. 6A.8-1.

. Amendment 2

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5A Structural Design Bases 6A-8 thru 6A-18.

. Amendment 2

-N' 5A-1 thru 5A-5.

. Amendment 2 Fig. 6A.16-1 thru Fig. 5A-6 thru 5A-7.

.. Amendment 1 6A.16-2

. Amendment 2 Fig. 5A-1 thru 5A-2.

. Amendment 1 Appendix 7 Table of SB Justification of Contents

. Amendment 1 Structural Proof Test -

7A Answers to Questions Pressures 7A-1.

.knendment 1 y,.PB-1 thru SB-3.

Original 7A-2 thru 7A-9

. Amendment 2

, Sc Specification for Splicing Appendix 8 Table of

' Reinforcing Bar Using the Contents

. Amendment 2 Coldwell Process 8A Answers to Questions SC-1 thru SC-3.

.... Original 8A-1 thru 8A-4

. Amendment 2 SD Turbine Generator Missiles Appendix 9 Table of 1 thru 10.

Original Contents

. Amendment 2 4 sheets of Parts Drawings 9A Answers to Questions SE Justification for Load 9A-1.

. Amendment 2 Factors 9A-2.

. Amendment t 5E-1 thru SE-2.

Original 9A-3 thru 9A-6.

. Amendment 2 SF Justification for Yield Appendix 10 Contains nothing Reduction Factors.

Appendix 11 Table of SF-1 thru SF-2.

Original Contents.

. Amendment 1 5G Description of the Finite llA Answers to Questions Element Technique Used in'"

llA-1 thru 31A-2.

. Amendment 1 Containment St'ructural Fig. 11A.1-L.

. Amendment 1 Analysis Fig, llA.1-2.

. Amendment 2 L

i 5G-1 thru 5G-2 Original llA-3 thru 11A-6.

. Amendment i Amendment 2 G

LIST OF Docket No.30-312

'"c

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H E F F ECTIV E PAGES April 15, 1968 Amendment No. 2 Page or Fig. No.

Issue Page or Fig.

?.'o.

Issue Appendix 12 Table of Appendix 15 Table of Contents.

. Amendment 1 Contents.

. Amendment 2 12A Answers to Questions 15'A Answers to Questions 12A-1 thru 12A-4

. Amendment i 15A-1 thru 15A-2.

. Amendment 2 12A-5 thru 12A-10.

. Amendment 2 Fig. 12A.5-1

. Amendment 2 12A-11

. Amendment 2 Fig. L2 A.6-1 thru 12A.6-3.

. Amendment 2 12A-12 thru 12A-17.

. Amendment 2 Appendix 13 Table of Contents

... Amendment 2 13A Answers to Ques ~tions 13A-L thru 13A-3.

. Amendment 2 Appendix 14 Table of Contents

. Amendment 1 14A Answers to Questions 14A-1.

. Amendment 1 14A-2.

. Amendment 2 14A-3 thru 14A-6.

. Amendment 1 14A-7 thru 14A-9.

. Amendment 2 Fig. 14A.6-1 thru m

14A.6-3.

. Amendment 1 Fig. 14A.6-4 thru 14A.6-5.

. Amendment 2 14A-11 thru 14A-13.

. Amendment 1 14A-14.

. Amendment 2 F4 g. 14A.8-1

. Amendment 2

' 14,\\-15 thru 14A-20.

. Amendment i FDs. 14A.ll-1 thru 14A.11-2

. Amendment 1 14A-21 thru 14A-22

. Amendment 1 14A-23 thru 14A-29.

. Amendment 2 Fig. 14A.18-l.

. Amendment 2 14A-30.

. Amendment 2 Fig. 14A.19-l.

. Amendment 2 14A-31 thru 14A-32.

. Amendment 2 Fig. 14A.21-L thru 14A.21-4

. Amendment 2 14A-33 thru 14A-34.

. Amendment 2

)

Fig. L4A.22-l.

. Amendment 2 14A-35 thru 14A-36

. Amendment 2 Fig. 14A.25-1.

. Amendment 2 Fig. 14A.26-1..\\.

. Amendment 2 J{(

14A-37 th ru 14A-41.

. Amendment 2 I

O 1

H A wndment 2

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TABLE OF CONTENTS 7

VOLUME I 1.

INTRODUCTION AND SU> DIARY Section Page

1.1 INTRODUCTION

1.1-1 1.2 DESIGN HIGHLIGHTS 1.2-1 1.2.1 SITE CHARACTERISTICS 1.2-1 1.2.2 POWER LEVEL 1,2-1 1.2.3 PEAK SPECIFIC POWER LEVEL 1.2-1 1.2.4 REACTOR BUILDING 1.2-1 1.2.5 ENGINEERED SAFEGUARDS 1.2-2 1.2.6 ELECTRICAL SYSTDIS AND DIERGENCY POWER 1.2-3 1.2.7 ONCE-THROUGH STEAM GENERATORS 1.2-4 1.3 TABULAR CHARACTERISTICS 1.3-1 1.3.1 ITDI L - HYDRAULIC AND THERMAL DESIGN PARAMETERS 1.3-1 1.3.2 ITEM 2 - CORE MECHANICAL DESIGN PARAMETERS 1.3-1 1.3.3 ITRI 3 - PRELIMINARY NUCLEAR DESIGN DATA 1.3-8 1.3.4 ITD14 - PRINCIPAL DESIGN PARAMETERS OF THE REACTOR COOIANT SYSTDI 1.3-8 1.3.5 ITEM 5 - REACTOR C001 ANT SYSTEM - CODE REQUIRDENTS 1.3-8

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1.3.6 ITDI 6 - PRINCIPAL DESIGN PARAMETERS OF THE REACTOR VESSEL 1.3-9 1.3.7 ITDI 7 - PRINCIPAL DESIGN FEATURES OF THE STEAM GENERATORS 1.3-9 1.3.8 ITDI 8 - PRINCIPAL DESIGN PARAMETERS OF THE REACTOR COOLANT PUMPS 1.3-9 1.3.9 ITEM 9 - PRINCIPAL DESIGN PARAMETERS OF THE REACTOR C001 ANT PIPING 1.3-9 1.3.10 ITDI 10 - REACTOR BUILDING PARAMETERS 1.3-9 1.3.11 ITDI 11 - ENGINEERED SAFEGUARDS 1.3-9 1.4 PRINCIPAL DESIGN CRITERIA 1.4-1 1.4.1 CRITERION 1

. QUALITY STANDARDS (CATEGORY A) 1.4-1 1.4.2 CRITERION 2 - PERFORMANCE STANDARDS (CATEGORY A) 1.4-2 1.4.3 CRITERION 3 - FIRE PROTECTION (CATEGORY A) 1.4-3 1.4.4 CRITERION 4 - SHARING OF SYSTDIS (CATEGORY A) 1.4-5 1.4.5 CRITERION 5 - RECORDS REQUIRDIENTS (CATEGORY A) 1.4-5 1.4.6 CRITERION 6 - REACTOR CORE DESIGN (CATEGORY A) 1.4-5

.1.4.7 CRITERION 7 - SUPPRESSION OF POWER OSCILIATIONS (CATEGORY B) 1,4-6 1.4.8 CRITERION 8 - OVERALL POWER COEFFICIENT (CATEGORY B) 1.4-7 1.4.9 CRITERION 9 - REACTOR COOLANT PRESSURE BOUNDARY (CATEGORY A) 1.4-7 1.4.10 CRITERION 10 - CONTAINMENT (CATEGORY A) 1.4-8 1.4.11 CRITERION 11 - CONTROL ROOM (CATEGORY B) 1.4-8 (D

%J 1

I

-Amendment 3 i

Section Page 1.4.12 CRITERION 12 - INSTRUMENTATION AND CONTROL SYSTEMS (CATEGORY B) 1.4-10 1.4.13 CRITERION 13 - FISSION PROCESS MONITORS AND CONTROLS (CATEGORY B) 1.4-11 1.4.14 CRITERION 14 - CORE PROTECTION SYSTEMS (CATEGORY B) 1.4-12 1.4.15 CRITERION 15 - ENGINEERED SAFETY FEATURES PROTECTION SYSTEMS (CATEGORY B) 1.4-12 1.4.16 CRITERION 16 - MONITORING REACTOR COOLANT PRESSURE BOUNDARY (CATEGORY B) 1.4-12 1.4.17 CRITERION 17 - MONITORING RADI0 ACTIVITY RELEASES (CATEGORY B) 1.4-13 1.4.18 CRITERION 18 - MONITORING FUEL AND WASTE STORAGE (CATEGORY B) 1 4-15 1.4.19 CRITERION 19 - PROTECTION SYSTEMS RELIABILITY (CATEGORY B) 1.4-15 1.4.20 CRITERION 20 - PROTECTION SYSTEMS REDUNDANCY AND INDEPENDENCE (CATEGORY B) 1.4-16 1.4.21 CRITERION 21 - SINGLE FAILURE DEFINITION (CATEGORY B) 1.4-16 1.4.22 CRITERION 22 - SEPARATION OF PROTECTION AND CONTROL INSTRUMENTATION SYSTEMS (CATEGORY B) 1.4-16 1.4.23 CRITERION 23 - PROTECTION AGAINST MULTIPLE DISABILITY FOR PROTECTION SYSTEMS (CATEGORY B) 1.4-17 1.4.24 CRITERION 24 - EMERGENCY POWER FOR PROTECTION SYSTEMS (CATEGORY B) 1.4-17 1.4.25 CRITERION 25 - DEMONSTRATION OF FUNCTIONAL OPERABILITY OF PROTECTION SYSTEMS (CATEGORY B) 1.4-17 1.4.26 CRITERION 26 - PROTECTION SYSTEMS FAIL-SAFE DESIGN (CATEGORY B) 1.4-18 1.4.27 CRITERION 27 - REDUNDANCY OF REACTIVITY CONTROL (CATEGORY A) 1,4-19 1.4.28 CRITERION 28 - REACTIVITY HOT SHUTDOWN CAPABILITY (CATEGORY A) 1,4-19 1.4.29 CRITERION 29 - REACTIVITI SHUIDOWN CAPABILITY (CATEGORY A) 1.4-19 1.4.30 CRITERION 30 - REACTIVITV HOLDDOWN CAPABILITY (CATEGORY B) 1,4-20 1.4.31 CRITERION 31 - REACTIVITY CONTROL SYSTEMS MALFUNCTION (CATEGORY B) 1.4-20 1.4.32 CRITERION 32 - MAXIMUM REACTIVITY WORTH OF CONTROL RODS (CATEGORY A) 1.4-20 1.4.33 CRITERION 33 - REACTOR COOLANT PRESSURE BOUNDARY CAPABILITY (CATEGORY A) 1.4-21 1.4.34 CRITERION 34 - REACTOR COOLANT PRESSURE BOUNDARY RAPID PROPAGATION FAILURE PREVENTION (CATEGORY A) 1.4-21 1.4.35 CRITERION 35 - REACTOR COOLANT PRESSURE BOUNDARY BRITTLE FRACTURE PREVENTION (CATEGORY A) 1.4-22 1.4.36 CRITERION 36 - REACTOR COOLANT PRESSURE BOUNDARY SURVEILLANCE (CATEGORY A) 1.4-22

}

11 Amendment 3

r fN 5

Sec tion Page 1.4.37 CRITERION 37 - ENGINEERED SAFETY FEATURES BASIS FOR DESIGN (CATEGORY A) 1.4-22 1.4.38 CRITERION 38 - RELIABILITY AND TESIABILITY OF ENGINEERED SAFETY FEATURES (CATEGORY A) 1.4-23 1.4.39 CRITERION 39 - EMERGENCY POWER FOR ENGINEERED SAFETY

' FEATURES (CATEGORY A) 1.4-24 1.4.40 CRITERION 40 - MISSILE PROTECTION (CATEGORY A) 1,4-24 1.4.41 CRITERION 41 - ENGINEERED SAFETY FEATURES PERFORMANCE CAPABILITY (CATEGORY A) 1.4-25 1.4.42 CRITERION 42 - ENGINEERED SAFETY FEATURES COMPONENTS CAPABILITY (CATEGORY A) 1.4-25 1.4.43 CRITERION 43 - ACCIDENT AGGRAVATION PREVENTION (CATEGORY A) 1.4-26 1.4.44 CRITERION 44 - EMERGENCY CORE COOLING SYSTEMS CAPABILITY (CATEGORY A) 1.4-26 l

1.4.45 CRITERION 45 - INSPECTION OF EMERGENCY CORE COOLING SYSTEMS (CATEGORY A) 1.4-27 E

1.4.46 CRITERION 46

. TESTING OF EMERGENCY CORE COOLING SYSTEMS COMPONENTS (CATEGORY A) 1.4-27 3

1.4.47 CRITERION 47 - TESTING OF EMERGENCY CORE COOLING j

SYSTEMS (CATEGORY A) 1.4-28 1.4.48 CRITERION 48 - TESTING OF OPERATIONAL SEQUENCE OF EMERGENCY CORE COOLING SYSTEMS (CATEGORY A) 1.4-28

]

1.4.49 CRITERION 49 - CONTAINMENT DESIGN BASIS (CATEGORY A) 1.4-28 1.4.50 CRITERION 50 - NDT REQUIREMEhT FOR CONTAINMENT MATERIAL l

(

CATEGORY A) 1.4-29 1

1.4.51 CRITERION 51 - REACTOR COOLANT PRESSURE BOUNDARY OUTSIDE CONIAINMFNT (CATEGORY A) 1.4-29 1.4.52~ CRITERION 52 - CONTAINMENT HEAT REMOVAL SYSTEMS i

(CATEGORY A) 1.4-30 j

1.4.53 CRITERION 53 - CONTAIN>ENT ISOLATION VALVES (CATEGORY A) 1.4-31

{

l.4.54 _ CRITERION 54 - CONTAINMENT LEAKAGE RATE TESTING (CATEGORY A) 1.4-31

}

1.4.55 CRITERION 55 - CONTAINMENT PERIODIC LEAKAGE RATE TESTING (CATEGORY A) 1,4-32 1.4.56 CRITERION 56 - PROVISIONS FOR TESTING OF PENETRATIONS (CATEGORY A) 1.4-32 1.4.57 CRITERION 57 - PROVISIONS FOR TESTING OF ISOLATIONS VALVES (CATEGORY A) 1.4-32 1.4.58 CRITERION 58 - INSPECTION OF CONTAINMENT PRESSURE-REDUCING SYSTEMS _(CATEGORY A) 1.4-33 1.4.59 CRITERION 59 - TESTING OF CONTAINMENT PRESSURE-REDUCING SYSTEMS COMPONENTS (CATEGORY A) 1.4-33 1.4.60 CRITERION 60 - TESTING OF CONTAINMENT SPRAY SYSTEMS (CATEGORY A) 1.4-34 1.4.61 CRITERION 61 - TESTING OF OPERATIONAL SEQUENCE OF 1

p CONTAINMENT PRESSURE-REDUCING SYSTEMS (CATEGORY A) 1.4-34 r

f dJte ndQO UC 5 iii

~*

Section Pace 3

1.4.62 CRITERION 62 - INSPECTION OF AIR CLEANUP SYSTEMS (CATEGORY A) 1.4-35 1.4.63 CRITERION 63 - TESTING OF AIR CLEANUP SYSTEMS COMPONENTS (CATEGORY A) 1.4-35 1.4.64 CRITERION 64 - TESTING OF AIR CLEANUP SYSTEMS (CATEGORY A) 1.4-35 1.4.65 CRITERION 65 - TESTING OF OPERATIONAL SEQUENCE OF AIR CLEANUP SYSTEMS (CATEGORY A) 1.4-36 1.4.66 CRITERION 66 - PREVENTION OF FUEL STORAGE CRITICALITY (CATEGORY B) 1.4-36 1.4.67 CRITERION 67 - FUEL AND WASTE STORAGE DECAY HEAT (CATEGORY B) 1.4-36 1.4.68 CRITERION 68 - FUEL AND WASTE STORAGE RADIATION SHIELDING (CATEGORY B) 1.4-37 1.4.69 CRITERION 69 - PROTECTION AGAINST RADI0 ACTIVITY RELEASE FROM SPENT FUEL AND WASTE STORAGE (CATEGORY B) 1.4-37 1.4.70 CRITERION 70 - CONTROL OF RELEASES OF RADIOACTIVITY TO THE ENVIRONMENT (CA'icGORY B) 1,4-38 1.5 RESEARCH AND DEVELOPMENT REQUIREMENTS 1.5-1

1. 5.1 XENON OSCILLATIONS 1.5-1 1.5.2 THERMAL AND HYDRAULIC PROGRAMS 1.5-1 1.5.3 FUEL ROD CLAD FAILURE 1.5-2 1.5.4 HIGH BURNUP FUEL TESTS 1.5-3 1.5.5 INTERNALS VENT VALVES 1.5-3 1.5.6 CONTROL ROD DRIVE TEST 1.5-4 1.5.7 ONCE-THROUGH STEAM GENERATOR TEST 1.5-4 1.5.8 SELF POWERED DETECTOR TESTS 1.5-5 1.5.9 BLOWDOWN FORCES ON INTERNALS 1.5-5 1.5.10 RADIO IODINE SPRAY REMOVAL SYSTEM 1.5-6 1.6 SMUD'S COMPETENCE TO BUILD AND OPERATE NUCLEAR PLANT 1.6-1 1.7 IDENTIFICATION OF CONTRACTORS AND AGENTS 1.7-1

1.8 CONCLUSION

S 1.8-1 1.9 hfTERENCES 1.9-1 2.

SITE AND ENVIRONMENT 2.1 SLBDmin-2.1-1 2.2 SITE AND ADJACENT AREAS 2.2-1 2.2.1 SITE LOCATION 2.2-1 2.2.2 SITE OWNERSHIP 2.2-1 2.2-1 2.2.3 SITE ACTIVITIES

~

2.2-1 2.2.4 POPULATION 2.2.5 LAND USE

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2.2-3 2.2.6 ACCESS AND EGRESS 2.2-3 2.2.7 BMKE-UP WATER SUPPLY 2.2-5 vff

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iv Amendment 4

r~f"'y Section

( j Page 2.3 METEOROLOGY 2.3-1 2'

3.1 INTRODUCTION

2.3-1 2.3.2 DESCRIPTIVE METEOROLOGY 2.3-1 2.3.3 METEOROLOGICAL DATA 2.3-2 2.3.4 PROGRAM OF METEOROLOGICAL INVESTIGATION-2.3-5 1

2.3.5 PRELIMINARY ESTIMATES OF DIFFUSION 2.3-5 2.4 HYDROLOGY 2.4-1 2.4.1 CHARACTERISTICS OF STREAMS AND LARES IN VICINITY 2.4-1 2.4.2 TOPOGRAPHY 2.4-1 2.4.3 TERMINAL DISPOSAL OF' STORM RUNOFF 2.4-1 2.4.4 HISTORICAL FLOODING 2.4-1 2.4.5 PREDICTION OF LAND URBANIZATION 2.4-1 a

2.4.6 GROUNDWATER 2.4-3 2.5 GEOLOGY 2.5-1 2.6 SEISMOLOGY 2.6-1 2.7 SOILS 2.7-1 2.8

' SITE ENVIRONMENTAL RADIOACTIVITY PROGRAM-2.8-1 f\\

2.8.1 GENERAL 2.8-1 2.8.2 LAND ENVIRONMENT 2.8-I 2.8.3 WATER ENVIRONMENT 2.8-2 2.8.4 SAMPLING 2.8-2

2.9 REFERENCES

2.9-1 i

3.

REACTOR 3.1 DESIGN BASES 3.1-L 3.1.1 PERFORMANCE 0BJECTIVES 3.1-1 2

3.1.2 LIMITS 3.1-1 3.2

~ REACTOR DESIGN 3.2-1 3.2.1 GENERAL

SUMMARY

3.2-1 l

3.2.2 NUCLEAR DESIGN AND EVALUAIION 3.2-2 3.2.3 THERMAL AND HYDRAULIC DESIGN AND EVALUATION 3.2-29 3.2.4 MECHANICAL DESIGN LAYOUT 3.2-70 l

3.3

-TESTS AND INSPECTIONS 3.3-l i

3.3.1 NUCLEAR TESTS AND INSPECTION 3.3-5 l

3.3.2 DIERMAL AND HYDRAULIC TESTS AND INSPECTION 3.3-2 3.3.3 FUEL ASSEMBLY, CONTROL ROD ASSEMBLY, AND CONTROL ROD DRIVE MECllANICAL TESTS AND INSPECTION 3.3-3 j

-[-~3 3.3.4 l

x, /.

INTERNALS TESTS AND INSPECTIONS 3.3-19

3.4 REFERENCES

3.4-1

Amendment 3-v i

.1. _,_._.. _

VOLUME II s

Section Page 4.

REACTOR COOLANT SYSTEM 4.1 DESIGN BASES 4.1-1 4.1.1 PERFORMANCE OBJECTIVES 4.1-1 4.1.2 DESIGN CHARACTERISTICS 4.1-2 4.1.3 EXPECTED OPERATING CONDITIONS 4.1-7 4.1. 4 SERVICE LIFE 4.1-8 4.1.5 CODES AND CLASSIFICATIONS 4.1-15 4.2 SYSTEM DESCRIPTION AND OPERATION 4.2-1 4.2-1 4.2.1 GENERAL DESCRIPTION 4.2.2 MAJOR COMPONENTS 4.2-1 4.2.3 PRESSURE-RELIEVING DEVICES 4.2-7 4.2.4 ENVIRONMENTAL PROTECTION 4.2-7 4.2.5 MATERIALS OF CONSTRUCTION 4.2-7 4.2.6 MAXIMUM HEATING AND COOLING RATES 4.2-11 4.2.7 LEAK DETECTION 4.2-11 4.3 SYSTEM DESIGN EVALUATION 4,3-1 4.3.1 SAFETY FACTORS 4.3-1 4.3.2 RELIANCE ON INTERCONNECTED SYSTEMS 4.3-8 4.3.3 SYSTEM INTEGRITY 4.3-9 4.3.4 PRESSURE RELIEF 4.3-9 4.3.5 REDUNDANCY 4.3-10 4.3.6 SAFETY ANALYSIS 4.3-10 4.3.7 OPERATIONAL LI1 HTS 4.3-10 4.4 TESTS AND INSPECTIONS 4.4-1 4.4.1 COMPONENT IN-SERVICE INSPECTION 4.4-1 4.4.2 REACTOR COOLANT SYSTEM TESTS AND INSPECTIONS 4.4-3 4.4.3 MATERIAL IRRADIATION SURVEILLA::CE 4.4-4

4.5 REFERENCES

4.5-1 5.

CONTAINMENT SYSTEM 5.1 STRUCTURAL DESIGN 5.1-1 5.1.1 GENERAL DESCRIPTION OF CONTAINMENT STRUCTURE 5.1-1 5.1.2 BASIS FOR DESIGN LOADS 3.1-1 5.1. 3 CONSTRUCTION MATERIALS 5.1 4 5.1.4 CONTAINMENT STRUCTURE DESIGN CRITERIA 5.1-11 5.1.5 STRUCTURAL DESIGN ANALYSIS 5.1-27 5.2 DESIGN, CONSTRUCTION, AND TESTING OF PENETRATIONS 5.2-1 5.2-1 5.2.1 TYPES OF PENETRATIONS 5.2.2 DESIGN OF PENETRATIONS 5.2-3 5.2.3 INSTALLATION OF PENETRATIONS 5.2-5 5.2.4 TESTABILITY OF PENETRATIONS AND WELD SEAMS 5.2-5 lb vi Amendment 4

(

)

Section Page v

5.3 CONTAINMENT ACCESSIBILITY CRITERIA 5.3-1 5.4 CONSTRUCTION PRACTICES AND QUALITY ASSURANCE 5.4-1 5.4.1 ORGANIZATION OF QUALITY ASSURANCE PROGRAM 5.4-1 5.4.2 APPLICABLE CONSTRUCTION CODES 5.4-1 5.4.3 CONSTRUCTION MATERIALS INSPECTION AND INSTALLATION 5.4-2 5.4.4 SPECIFIC CONSTRUCTION TOPICS 5.4-7 5.5 CONTAINMENT SYSTDI INSPECTION, TESTING, AND SURVEILIANCE 5.5-1 5.5.1 TESTS TO ENSURE LINER INTEGRITY 5.5-1 5.5.2 STRENGTH TEST 5.5-3 5.6 ISOLATION SYSTEM 5.6-1 5.6.1 DESIGN BASES 5.6-1 5.6.2 SYSTEM DESIGN 5.6-1 5.7 VENTILATION SYSTEM 5.7-1 5.7.1 DESIGN BASES 5.7-1 5.7.2 SYSTEM DESIGN 5.7-1 5.8 LEAKAGE MONITORING SYSTEM 5.8-1 5.9 SYSTEM DESIGN EVALUATION 5.9-1

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6.

ENGINEERED SAFEGUARDS 6.1 EMERGENCY INJECTION 6.1-1 6.1.1 DESIGN BASES 6.1-1 6.

1.2 DESCRIPTION

6.1-1 6.1.3 DESIGN EVALUATION 6.1-5 6.1.4 TEST AND INSPECTIONS 6.1-15 6.2 REACTOR BUILDING ATMOSPHERE COOLING AND WASHING 6.2-1 6.2.1 DESIGN BASES 6.2-1 6.

2.2 DESCRIPTION

6.2-1 6.2.3 DESIGN EVALUATION 6.2-2 6.2.4 TESTS AND INSPECTIONS 6.2-7 6.3 ENGINEERED SAFEGUARDS LEAKAGE AND RADIATION CONSIDERATIONS 6.3-1 6.

3.1 INTRODUCTION

6.3-1 6.3.2

SUMMARY

OF POSTACCIDENT RECIRCULATION AND LEAKAGE CONSIDERATION 6.3-1 6.3.3 LEAKAGE ASSUMPTIONS 6.3-2 6.3.4 DESIGN BASIS LEAKAGE 6.3-2 6.3.5 LEAKAGE ANALYSIS CONCLUSIONS 6.3-2

!u) h4 ent 3 vii

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6 l

Section Page 7.

INSTRUMENTATION AND CONTh0L 7.1 PROTECTION SYSTEMS 7.1-1 7.1.1 DE9IGN BASEE 7.1-1 7.1.2 SYSTEM DESIGN 7.1-6 7.1.3 SYSTEMS EVALUATION 1.1-17 7.2 REGULATING SYSTEMS 7.2-1 7.2.1 DESIGN BASES 7.2-1 7.2.2 SYSTEM DESIGN 7.2-3 7.2.3 SYSTEM EVALUATION 7.2-9 7.3 INSTRUMENTATION 7.3-1 7.3.1 NUCLEAR INSTRUMENTATION 7.3-1 7.3.2 NONNUCLEAR PROCESS INSTRUMENTATION 7.3-3 7.3.3 INCORE MONITORING SYSTEM 7.3-5 7.4 OPERATING CONTROL STATIONS 7.4-1 7.4.1 GENERAL LAYOUT 7.4-1 7.4.2 INFORMATION DISPLAY AND CONTROL FUNCTION 7.4-1 7.4.3

SUMMARY

OF ALARMS 7.4-2 7.4.4 COMMUNICATION 7.4-2 7.4.5 OCCUPANCY 7.4-2 7.4.6 AUZILIARY CONTROL STATIONS 7.4-3 7.4.7 SAFETY FEATURES 7.4-4 7.4.8 SYSTEM EVALUATION 7.4-4 8.

ELECTRICAL SYSTEMS 8.1 DESIGN BASIS 8.1-1 8.2 ELECTRICAL SYSTEM DESIGN 8.2-1 8.2.1 ELECTRICAL SYSTEM DESIGN NETWORK INTERCONNECTIONS 8.2-1 8.2.2 SIATION DISTRIBUTION SYSTEM 8.2-2 8.2.3 EMERGENCY PORER SYSTEM 8.2-9 8.3 DESIGN EVALUATION 8.3-1 8.3.1 EVALUATION OF THE PHYSICAL LAYOUT 8.3-1 8.3-2 ACCIDENTAL PHASE REVERSAL 8.3-2 8.4 TESTS AND INSPECTIONS 8.4-1 9.

AUXILIARY AND EMERGENCY SYSTEMS 9.1 MAKEUP AND PURIFICATION SYSTEM 9.1-1 9.1.1 DESIGN BASES 9.1-1 9.1.2 SYSTEM DESCRIPTION AND EVALUATION 9.1-2 9.2 CHEMICAL ADDITION AND SAMPLING SYSTEM 9.2-1 9.2-1 9.2.1 DESIGN BASES Q 9-- -

9.2.2 SYSTEM DESCRIPTION AND EVALUATION

/y 9.2-1 viii Amendment 3

Section Page 9.3 COOLING WATER SYSTEMS 9.3-1 9.3.1 DESIGN BASES 9.3-1 9.3.2 SYSTEM DESCRIPTION AND EVALUATION 9.3-1 9.4 SPENT FUEL COOLING SYSTEM 9.4-1 9.4.1 DESIGN BASES 9.4-1 9.4.2 SYSTEM DESCRIPTION AND EVALUATION 9.4-1 9.5 DECAY HEAT REMOVAL SYSTEM 9.5-1 9.5.1 DESIGN BASES 9.5-1 9.5.2 SYSTEM DESCRIPTION AND EVALUATION 9.5-1 9.6 FUEL HANDLING SYSTEM 9.6-1 9.6.1 DESIGN BASES 9.6-1 9.6.2 SYSTEM DESCRIPTION AND EVALUATION 9.6-2 9.7 STATION VENTILATION SYSTEMS 9.7-1 9.7.1 DESIGN BASES 9.7-1 9.7.2 SYSTEM DESCRIPTION AND EVALUATION 9.7-1 VOLUME III 10.

STEAM AND POWER CONVERSION SYSTEM l

10.1 DESIGN BASES 10.1-1 10.1.1 OPERATING AND PERFORMANCE REQUIREMENTS 10.1-1 10.1.2 ELECTRICAL SYSTEM CHARACTERISTICS 10.1-1 10.1.3 FUNCTIONAL LIMITATIONS 10.1-1 10.1.4 SECONDARY FUNCTIONS 10.1-1 10.2 SYSTEM DESIGN AND OPERATION 10.2-1 10.2.1 SCHEMATIC FLOW DIAGRAM 10.2-1 10.2.2 CODES AND STANDARDS 10.2-1 10.2.3 DESIGN FEATURES 10.2-2 10.2.4 SHIELDING 10.2-2 l

10.2.5 CORROSION PROTECTION 10.2-2 L

10.2.6 IMPURITIES CONTROL 10.2-2 10.2.7 RADI0 ACTIVITY 10.2-2 10.3 SYSTEM ANALYSIS 10.3-1 10.3.l TRIPS, AUTOMATIC CONTROL ACTIONS, AND ALARMS 10.3-1 10.3.2 TRANSIENT CONDITIONS 10.3-2 10.3.3 MALFUNCTIONS 10.3-2 10.3.4 OVERPRESSURE PROTECTION 10.3-2

.10.3.5 INTERACTIONS 10.3-2

'~N 10.3. 6 '0PERATIONAL LIMITS 10.3-2 10.4 TESTS AND INSPECTIONS i

10.4-1 Amendment 3 ix

,.~.

Section Page 11.

RADI0 ACTIVE WASTES AND RADIATION PROTECTION 11.1 RADIOACTIVE WASTE ILANDLING 11.1-1 11.1.1 DESIGN BASES 11.1-1 11.1.2 SYSTEM DESIGN AND EVALUATION 11.1-6 11.1.3 TESTS AND INSPECTIONS 11.1-8 11.1.4 TRITIUM MANAGEMENT FOR NORMAL OPERATION 11.1-8 11.2 RADIATION SilIELDING 11.2-1 11.2.1 PRIMARY, SECONDARY, REACTOR BUILDING, AND AUXILIARY 11.2-1 S11IELDING 11.2.2 AREA RADIATION MONITORING SYSTEM 11.2-0 11.2.3 HEALTil PHYSICS 11.2-8 11.3 REFE RENCES 11.3-1 12.

CONDUCT OF OPERATIONS 12.1 T NTRODUCTION 12.1-1 12.2 ORGANIZATION AND RESPONSIBILITY 12.2-1 12.3 PERSONNEL TRAINING 12.3-1 12.3.1 TRAINING INITIAL PLANT STAFF 12.3-1 12.3.2 REPLACEMENT AND REFRESHER TRAINING 12.3-4 12.3.3 EMERGENCY DRILLS 12.3-5 12.4 WRITTEN PROCEDURE 12.4-1 12.5 RECORD 12.5-1 12.6 ADMINISTRATIVE CONTROLS 12.6-1 12.7 INDEPENDENT AUDIT OF PLANT OPERATIONS 12.7-1 13.

INITIAL TESTS AND OPERATION 13.1-1 13.1 TESTS PRIOR TO REACTOR FUELING 13.2 INITIAL CRITICALIIY 13.2-1 13.3 POSTCRITICALITY TESTS 13.3-1 M9 O

Amendment 4 x

Q Section Page 14.

SAFETY ANALYSIS 14.1 CORE AND C001 ANT BOUNDARY PROTECTION ANALYSIS 14.1-1 14.1.1 ABNORMALITIES 14.1-1 14.1.2 ANALYSIS OF EFFECTS AND CONSEQUENCES 14.1-2 14.2 STANDBY SAFECUARDS ANALYSIS 14.2-1 14.2.1 SITUATIONS ANALYZED AND CAUSES 14.2-1 14.2.2 ACCIDENT ANALYSES 14.2-1 14.3 ENVIRONMENTAL CONSEQUENCES OF HYPOTHETICAL ACCIDENTS 14.3-1 14.3.1 GENERAL APPROACH 14.3-1 14.3.2 STEAM CENERATOR TUBE FAILURE 14.3-1 14.3.3 LOSS OF ELECTRIC POWER 14.3-1 14.3.4 STEAM LINE FAILURE 14.3-3 14.3.5 FUEL HANDLING ACCIDENT 14.3-4 14.3.6 R0D EJECTION ACCIDENT 14.3-4 14.3.7 WASTE CAS TANK RUPIURE 14.3-4 14.3.8 LOSS-OF-COOIANT ACCIDENT 14,3-5 14.3.9 MAXIMUM HYFOTHETICAL ACCIDENT 14.3-6 p

14.3.10 IODINE REMOVAL SENSITIVITY ANALYSIS 14.3-10 t

14.3.11 POPULATION DENSITY CONSIDERATIONS 14.3-12

14.4 REFERENCES

14.4-1 15.

TECHNICAL SPECIFICATIONS 2 60 O>

>\\.)

Amendment 3 xi

VOLUME IV APPENDIX 1 1A ANSWERS TO QUESTIONS 1B QUALITY ASSURANCE OPERATIONS 1C RANCHO SECO PROJECT ENGINEERING STAFF APPENDIX 2 2A METEOROLOGY 2B LAND USAGE AND POPULATION 2C GEOLOGY AND SEISMOLOGY 2D SEISMIC REPORT 2E SOIL AND FOUNDATIONS INVESTIGATION REPORT 2F METEOROLOGICAL STATION 2G STORAGE RESERVOIR 2H ANSWERS TO QUESTIONS APPE" DIX 3 3A ANSWERS TO QUESTIONS APPENDIX 4

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4A ANSWERS TO QUESTIONS l

l l

I Sol O

xii Amendment 3

'~

VOLUME V APPENDIX 5

~

SA STRUCTURAL DESIGN BASES SB JUSTIFICATION OF STRUCTURAL PROOF TEST - PRESSURES 1

SC SPECIFICATION FOR SPLICING REINFORCING BAR USING THE CADWELD PROCESS 4

~5D TURBINE GENERATOR MISSILES

{

SE JUSTIFICATION FOR LOAD FACTORS i

SF JUSTIFICATION FOR YIELD REDUCTION FACTORS 5G DESCRIPTION OF THE FINITE ELEMENT TECHNIQUE USED IN CONTAINMENT STRUCTURAL ANALYSIS SH QUALITY CONTROL PROCEDURE FOR FIELD WELDING SI CONTAINMENT STRUCTURE INSTRUMENTATION SJ ANSWERS TO QUESTIONS APPENDIX 6 6A ANSWERS TO QUESTIONS i

j 1

APPENDIX 7 l

7A ANSUERS TO QUESTIONS i

l APPENDIX 8 8A ANSWERS TO QUESTIONS n

v a

2

-Amendment 3 xiii-

~

_ _ _ ~..

APPENDIX 9 9A ANSWERS TO QUESTIONS APPENDIX 11 llA NiSWERS TO QUESTIONS APPENDIX 12 12A ANSWERS TO QUESTIONS APPENDIX 13 13A ANSWERS TO QUESTIONS APPENDIX 14 14A ANSWERS TO QUESTIONS APPENDIX 15 15A ANSWERS TO QUESTIONS 9 03 O

xiv Amendment 3

CONTENTS-APPENDIX 5 5A DESIGN BASES FOR STRUCTURES, SYSTEMS AND EQUIPMENT

-5B JUSTIFICATION OF STRUCTURAL PROOF TEST - PRESSURES SC SPECIFICATION FOR SPLICING REINFORCING BAR USING THE CADWELD PROCESS SD CONSIDERATION OF THE CONSEQUENCES OF A TURBINE GENERATOR FAILURE IN WHICH MISSILES ARE GENERATED SE JUSTIFICATION FOR LOAD FACTORS AND LOAD COMBINATIONS USED IN DESIGN EQUATIONS 5F JUSTIFICATION FOR YIELD REDUCTION FACTORS (9 - FACTORS) USED IN DETERMINING YIELD STRENGTH OF CONTAINMENT STRUCTURE SG DESCRIPTION OF THE FINITE ELEMENT TECHNIQUE USED IN CONTAINMENT STRUCTURAL ANALYSIS 5H QUALITY CONTROL PROCEDURE FOR FIELD WELDING SI CONTAINMENT STRUCTURE INSTRUMENTATION SJ ANSWERS TO QUESTIONS

~'AOY O

.'mendment 3 A5-1 A

7 APPENDIX SA DESIGN BASES FOR STRUCTURES, SYSTEMS AND EQUIPMENT 1.0 GENERAL The design bases for structures for normal operating conditions are governed by the applicable building design codes.

The design bases for specific systems and equipment are stated in the appropriate PSAR Section.

The basic design criterion for the maximum hypothetical accident and seismic conditions is that there be no loss of function if that function is related to public safety.

2.0 CLASSES OF STRUCTURES, SYSTEMS AND EQUIPMENT 2.1 CLASS 1 Class 1 structures, systems and equipment are those whose failure could cause uncontrolled release of radioactivity or those essential for irnediate and long-term operation following a loss-of-coolant accident.

They are designed to withstand the appropriate seismic loads and other applicable loads without loss of function. When a system as a whole is referred to as Class 1, portions of the system not associated with the loss of function 2

g criteria, may. be designated as Class 2.

Class 1 structures will be

/,

i sufficiently isoldted or protected from Class 2 structures.to ensure that their integrity is maintained at all times.

The fol'1owing are Class 1 structures.

l2 e Containment structure shell Nuclear service spray ponds and pipe lines e

2 The auxiliary building that houses engineered safeguards systems, e

control room, and radioactive materL 's e Fuel storage facilities l2 Supports for Class 1 system components e

e Storage Reservoir 3

Class 1 equipment and systems are as follows l2 Reactor vessel and internals including control rods and control e

rod drives Primary coolant system components (steam generators, pressurizer, e

pumps, etc.) and piping, including vent and drain piping inside the p)

(V

. containment f

0205 onsai

~

. Amendment 3 5A-1

e Containment penetrations up to and including the first isolation valve outside containment Main steam and main feedwater piping up to the code limit of ASME e

3 Boiler and Pressure Vessel Code Section I.

(Stop Valves)

Atmospheric dump and main steam safety valves and associated piping e

from main steam headers e New and spent fuel storage racks and fuel handling equipment Motor-driven and steam-driven auxiliary feedwater pump, condensate e

storage tank and associated piping Emergency diesel generators including fuel supply 2l e

Containment building crane (unloaded condition) e 2l e Control boards, switchgear, load centers, batteries, transformers and cable runs serving Class 1 equipment Nuclear service raw water system e

3 Nuclear service cooling water system e

o Containment spray system o Containment air recirculation 2l Low pressure injection and decay heat removal e

Core flooding injection tanks and piping e

2l High pressure injection, make-up and purification e

3 e Borated water storage tank 2l e Radioactive waste treatment Spent fuel cooling and clean-up e

1l

  • Plant Vent 2.2 CLASS 2 Class 2 structures, systems, and equipment are those whose failure would not result in the release of radioactivity and would not prevent reactor shutdown.

3.0 DESIGN BASES 3.1 CLASS 1 STRUCTURES DESIGN 3.1.1 Containment Structure a""-

UUiLc The design of the containment structure for all credible conditions of loading including normal loads, accident loads, thermal loads and environmental loads (including seismic) is found in Section 5, Containment System.

0206 5A-2 Amendment 3

3.1.2 Storage Reservoir

. fm

, ().

The design of the storage reservoir is found in Appendix 2G, Storage Reservoir Criteria.

1 3.1.3 Structures Other Than Containment and Reservoir a.

Normal Operations Loads encountered during nomal plant operation including design earthquake loads are resisted by the structure using design methods of appropriate standards and codes insofar as they are applicable. Nomal allowable stresses are used for this load condition.

b.

Accident, Wind and/or Seismic Conditions Class 1 structures are, in general, proportioned to maintain elastic behavior when subjected to various combinations of dead loads, accident loads, thermal loads, wind loads and/or earthquake loads.

Concrete structures are designed for ductile behavior wherever possible; that is, with steel stress control-ling the design.

The final design of Class 1 structures other than the contain-ment structure satisfies the following load combinations and factors.

A = 1.0D + 1.0L + 1.0H A = 1.0D + 1.0H + 1.0E/W Y = 1/0 (1.0D + 1.0H + 1.0E ')

Y = 1/

(1.0D + 1.0R)

Y = 1.0D + 1.0R + 1.0E' l3 In areas where dead load subtracts from critical stress 0.90 D will be used.

A = capacity of the structure based upon allowabic code stresses with no stress increase.

Y = required yield capacity of the structures.

D = dead. load of structure and equipment plus any other pemanent loads contributing stress, such as so'1 or hydrostatic loads.

In addition, a portion of " live load" is added when such load is expected to be present when the plant is operating.

An allowance is also made for future pemanent loads.

L = appropriate live load R = load on structure from reaction or pressure due to rupture of any one pipe.

l2 H = load on structure due to thermal expansion of pipes under operating conditions.

E = " design earthquche" load resulting from (Figure SA-1)

- V)

'('!'

ground surface acceleration of 0.13g.

l3 E' =v" maximum hypothetical earthquake" load resulting from (Figure TA-2) seismic ground surface acceleration of I

W'= win koad 0207 l

Amendment 3 5A-3

0 = 0.90 for reinforced concrete in flexure.

0 = 0.85 for tension, shear, bond, and anchorage in rein-forced concrete.

= 0.75 for spirally-reinforced concrete compression members.

0 = 0.70 for tied compression members.

0 = 0.90 for fabricated structural steel.

= 0.90 for mild reinforcing steel (not prestressed) in direct tension.

0 = 0.95 for prestressed tendons in direct tension.

The containment structure and engineered safeguards systems components are protected by barriers from all credibic missiles which might be generated from the primary system.

Local yielding or erosion of barriers is permissible due to jet or missile impact, 1

provided there is no general failure. Missile barriers are de-signed on the basis of absorbing energy by plastic yielding.

The final design of the missile barrier and equipment support structures inside the containment will be reviewed to assure that they can withstand applicable pressure loads, jet forces, pipe reactions and earthquake loads without loss of function.

The deflections or deformations of structures and supports will be checked to assure that the functions of the containment and engineered safeguards equipment are not impaired, The maximum displacement of structures, systems and equipment y*

will be considered so the design and major components will have structural separation (with the exception of the fuel transfer i

tube) which will allow for differential movement.

The found-ation material is uniform and of such a nature that no perma-nent settlement or tilting will result from seismic loads.

3.2 CLASS 1 SYSTEMS AND EQUIPMENT DESIGN Components and systems classified as Class 1 will be designed in accordance with the following criteria a.

For Case I stress intensities shall be maintained within the allowable working stress limits accepted as good practice, and where applicable, as set forth in the appropriate design stan-

dards, e.g., ASME Boiler and Pressure Vessel Code and USASI B31.1 Code for Pressure Piping.

3 b.

For Cases II, III, and IV stress intensities and the correspond-ing strains shall be limited so that the function of the com-ponent or system shall not be impaired as to prevent a safe and orderly shutdown of the plant.

0208 SA-4 Amendment 3

f~~

~

Case Loading Combination Stress Limits I

Design loads + design earthquake loads P,s 1.0 S,

  1. l3S Pg+Pb m

II Design loads + maximum hypothetical P,s 1.2 S, earthquake loads Pg+Pb s 1.2 (1.5 S,)

III Design loads + pipe rupture loads P,s 1.2 S, Pg+Pb 1.2 (1.5 S,)

5 IV Design loads + maximum hypothetical P s 2/3 S m

u 3

earthquake loads + pipe rupture loads Pj+Pb ' 2/3 Su

  • where P, = Primary general membrane stress intensity Sm = Allowable membrane stress intensity Pg = Primary local membrane stress intensity Pb = Primary bending stress intensity S = Ultimate stress for unirradiated material at u

operating temperature

  • (1) All symbols have the same definition or connotation as those in ASME B&PV Code Section III, Nuclear Vessels.
  • (2)

Portions of systems or components not covered by ASME B&PV Code Section III will be designed in accordance with applicable codes using the stress limits stated above.

  • (3) The limits given above are for primary stresses; general mem-brane, local membrane, and bending.

Based on available stress-strain curves, the corresponding strains will be about 20% of

'the uniform strain or less. This applies to all pertinent material, in the unirradiated condition.

4

  • (4) Maximum local strains, due to Pg+Pb" 37 for carbon steel and 107. for type 18-8 stainless steel for cases I and II in unirradiated material.

For Cases III and IV the piping will be restrained to prevent secondary damage.

O)

All components will be designed to insure against structural instabilities 3

(

regardless of stress levels.

0209

([$ Amendment 4 5A-5

Adequate ficxibility will be provided in piping and other interconnecting elements to allow for differential movement during an carthquake. 3.3 CLASS 2 STRUCTURES, SYSTEMS AND EQUIPMENT DESIGN All Class 2 structures, systems and equipment are designed in accordance with the applicant's standard practice. However, in no case will the design criteria in this classification be less restrictive than that required by standard applicable codes and standards or the requirements of the Uniform Building Code. 4.0 EARTHQUAKE LOADS FOR CLASS 1 STRUCTURES, SYSIDiS AND EQUIPMENT Seismic Forces (E and E') -- AEC publication TID 7024, " Nuclear Reactors and Earthquakes," is used as the basic design guide for seismic analysis. The " design earthquake" to be used for this plant has a ground acceleration of 0.13 g horizontally and 0.07g vertically, acting simultaneously. The 3 " maximum hypothetical earthquake" has a ground acceleration of 0.25g horizontally and 0.13g vertically, acting simultaneously. Seismic loads on structures, systems and equipment are determined by realistic evaluation of dynamic properties and the accelerations from the attached acceleration spectrum curves (Figures 5A-1, 5A-2). 0210 fnfof h v v i u gr-5A-6 Amendment 4

l3 5.0 DAMPING * % Critical Damping Stress Level Type and Condition Percentage of of Structure Critical Damping 1. Low, well below a. Vital piping 0.5 proportional limit, b. Steel, reinforced or stresses below 1/4 prestressed concrete, 0.5 to 1.0 yield point no cracking, no joint slip 2. Working stress, no a. Vital piping 0.5 to 1.0 more than about 1/2 b. Welded steel, pre-yield point stressed concrete, 2 well reinforced concrete (only slight cracking) c. Reinforced concrete with considerable 3 to 5 cracking ( s' d. Bolted and/or riveted s steel 5 to 7 3. At or just below a. Vital piping 2 yield point b. Welded steel, prestressed concrete (without complete 5 loss in prestress) c. Prestressed concrete with no prestress left 7 d. Reinforced concrete 7 to 10 e. Bolted and/or riveted 10 to 15 steel 4 All-rangas Rocking of Entire Structure 5 to 9 ** Translation'of Entire Struc-30% ** ture

  • Reference 8 3
    • Reference 5, 6, 7 0211

.f)% M ( . Amendment'3 5A-7

6. 0 LOADINGS COMMON TO ALL STRUCTURES Ice or Snow Loading - A uniform distributed live load of 20 pounds per square foot on all roofs provides for any anticipated snow and/or ice loading.

7.0 REFERENCES

1. " Nuclear Reactors and Earthquakes" AEC Publication TID-7024. 2 Housner, G.W., Design of Nuclear Power Reactors Against Earthquakes, Proceedings of the Second World Conference on Earthquake Engineering, Page 133, Japan (1960). 3. Housner, G.W., Behavior of Structures During Earthquakes, Journal of the Engineering Mechanics Division, Proceedings of the American Society of Civil Engineers, Page 109, October 1959, 4 Task Committee on Wind Forces, " Wind Forces on Structures," ASCE Paper No. 3269. 5. Arnold, R. N., Bycroft, G. N., Warburton, G. B., Forced Vibrations of a Body on an Infinite Elastic Solid, Journal of Applied Mechanics, American Society of Mechanical Engineers, Vol. 22, No. 3 (1955). l 6. Whitman, R. V., Richart, F. E., Desien Procedures for Dynamically Loaded Foundations, Journal of the Soil Mechanics and Foundations Division, American Society of Civil Engineers, SM6 (Nov. 1967). 3 7. Parmelee, R. A., Building-Foundation Interaction Effects, Journal of the Engineering Mechanics Division, American Society of Civil Engineers, EM2 (April 1967). 8. Newmark, N. M., Design Criteria for Nuclear Reactors Subjected to Earthquake Motions, Presented at the International Atomic Energy Agency g Meeting in Tokyo, (June 1967). 0212 .n n, e n _ vv.LV SA-8 Amendment 3

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  1. O PERIOD (secs) i FIGURE 5A-2 l

MAXIMUM HYPOTHETICAL EARTHQUAKE OMd_c RESPONSE SPECTRUM GROUND ACCELERATION 0.25g $suun m SACRAMENTO MUNICIPAL UTILITY DISTRICT Amendment 3 1}}

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