ML19329D992
| ML19329D992 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/31/1967 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| References | |
| NUDOCS 8004090515 | |
| Download: ML19329D992 (13) | |
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@ SOUZ SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SEC0 NUCLEAR GENERATING STATION O
UNIT NO.1
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x PRELIMINARY SAFETY ANALYSIS REPORT Volume 111
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NOVEMBER 1967 8004090 3
37;'e
~ d' Docket No. 50-312 February 2, 1968 AMENDMENT NO. 1 SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 Amendment No. 1 to the Sacramento Municipal Utility Distric t's Prelimi-nary Safety Analysis Report includes both replacement pages and new pages and tabs.
All pages to be inserted are identified as Amendment 1.
Any technical text material changed by this amendment is coded in the outside margin by a black bar and the numeral one.
Before inserting the Amendment 1 material (contained in this new Volume V) in the different volumes, it is suggested that the Appendix 5 material be removed from Volume IV to provide space. After the Amendment 1 material
[^N has been inserted, Appendix 3 should be the first amendment in the new
(_,'
Volume V.
The List of Effective Pages should be checked to verify the completeness of Volumes I thru V.
It should be noted that License Application page 4 is replaced with a new page 4 plus two new additional pages, 8 and 9.
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SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 LIST OF Docket No. 50-289 E F F ECTIV E PAGES February 2, 1968 Amendment No. 1 The active pages in this report are as follows:
Page or Fig. No.
Issue Page or Fig. No.
Issue Title...................... 0riginal
- 3. 3-1 thru 3. 4-5............. Or iginal A........................ Amendment 1 4-1 thru 4-iv................ Original B th ru E.................. Amendmen t 1 4.1-1 thru 4.3-10............ Original i........................... Original 4.3-11.................... Amendment 1 ii........................ Amendment 1 4.4-1 thru 4.5-1............. Original lii.........................
0riginal 5.1-1..................... Amendment 1 iv thru ix............... Amendment 1 5.1-2........................ Original x.......................... 0riginal 5.1-3..................... Amendment 1 xi thru xiv.............. Amendment 1 5.1-4 thru 5.1-9............. Original 1-i.......................... Original 5.1-10.................... Amendment 1 1-ii...................... Amendment 1 5.1-11 thru 5.1-24........... Original 1-111 thru iv................ Original 5.1-25 thru 5.1-26........ Amendment 1 1-v.......................... Original 5.1-27 thru 5.1-29........... Original 1.1-1 thru 1.1-2............. Original 5.1-30.................... Amendment 1 Fig. 1.1-4 thru 1.1-8..... Amendment 1 5.1-31....................... Or igin a l 1.2-1 thru 1.2-4............. Original 5.1-32 thru 5.1-33........ Amendment 1 1.3-1 thru 1.3-3............. original Fig.
5.1-4................ Amendment 1 1.3-4..................... Amendment 1 5.2-1 thru 5.3-1............. Original 1.3-5 thru 1.3-9............. Original 5.4-1..................... Amendment 1 1.4-1........................ Original 5.4-2 thru 5.4-5............. Original 1.4-2 thru 1.4-3.......... Amendment 1 5.4-6..................... Amendment 1 1.4-4 thru 1.9-1............. Original 5.4-7........................ original 2-1 thru 2-ii............. Amendment 1 5.4-8 thru 5.4-9.......... Amendment 1 2 - iii........................ Or igina l 5.5-1 thru 5.9-1............. Original 2.1-1 thru 2. 3-5............. Original 6-1 thru 6-ii............. Amendment 1
- 2. 3-6 thru 2. 3-8.......... Amendment 1 6.0-1........................ Original 2.4-1 thru 2.5-1............. original 6.1-1........................ original 2.6-1..................... Amendment 1 6.1-2 thru 6.1-16......... Amendment 1 2.7-1........................ Original Fig.
6.1-1................ Amendment 1 2.8-1 thru 2.8-4.......... Amendment 1 6.2-1..................... Amendment 1 2.9-1........................ Original
- 6. 2-2 thru 6. 2-8............. Original 3-1 thru 3-vi................ Original Fig.
6.2-1................ Amendment 1 3.1-1 thru 3.1-6............. Original 6.3-1 thru 6.3-3............. Original Fig. 3.2 -6 5............... Amendmen t 1 7 -i.......................... Or i gin a l FiE. 3.2-68............... Amendment 1 7-ii...................... Amendment 1 0
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SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 LIST OF Docket No. 50-289 E F F ECTIV E PAGES February 2, 1968 Amendment No. 1 Page or Fig. No.
Issue Fage or Fig. No.
Issue 7.1-1 thru 7.1-5............. Original
- 11. 2-2 thru 11. 2-5........... Original 7.1-6 thru 7.1-7.......... Amendment 1 11.2-6.................... Amendment 1 7.1-9........................ Original 11.2-7 thru 11.3-1....
....... Original 7.1-10 thru 7.1-11........ Amendment 1 12-1..
......... Original 7.1-12 thru 7.1-13........... Original 12.1-1.....
...... original 7.1-14 thru 7.1-15........ Amendment 1 12.2-1 thru 12.2-2......... Amendment 1 7.1-16 thru 7.1-19........... Original Fig. 12.2-1................ Amendment 1 Fig.
7.1-2................ Amendment 1
- 12. 3 - 1 t hru 12. 3-5......... Amen dmen t 1 7.2-1 thru 7.2-6............. Original 12.4-1 thru 12.7-1............ Original 7.2-7 thru 7.2-8.......... Amendment 1 13-i....
.................... 0riginal f-~x
- 7. 2-9 thru 7. 2-11............ original 13.1-1 thru 13.3-1............ Original
)
7.3-1 thru 7.3-7............. Original i........................... 0riginal Fig.
7.3-3................ Amendment 1 11 thru 111............... Amendment 1 7.4-1........................ Original 14.1-1 thru 14.1-8............ Original 7.4-2 thru 7.4-5.......... Amendment 1 14.1-9..
...... Amendment 1 8-1 thru 8-ii............. Amendment 1 14.1-10 thru 14.1-19......... Original 8.1-1 thru 8.2-1............. Original 14.1-20.................... Amendment 1 8.2-2 thru 8.2-17......... Amendment 1 14.2-1 thru 14.2-2..
.. Original Fig. 8.2-1 thru 8.2-3..... Amendment 1 14.2-3..................... Amendment 1 8.3-1........................ original 14.2-4.....................
. Original 8.3-2 thru 8.3-4.......... Amendment 1 14.2-5 thru 14.2-6......... Amendment 1 8.4-1........................ Original 14.2-7 thru 14.2-32....
...... original 9-1 thru iii................. Original 14.2-33...............
.... Amendment 1 9.0-1 thru 9.2-9............. Original 14.2-34....................... original 9.3-1..................... Amendment 1 14.2-35 thru 14.2-37....... Amendment 1 9.3-2 thru 9.4-4............. Original
- 14. 2-38 thru 14. 2-39.......... original F i g. 9. 4 - 1................ Ame nd me n t 1 Fig. 14.2-36............... Amendment 1 9.5-1 thru 9.5-2............. Original Fig. 14.2-48 thru 14.2-50.. Amendment 1 9.5-3..................... Amendment 1 14.3-1 thru 14.3-2............ Original 9.5-4........................Original 14.3-3 thru 14.3-14........ Amendment 1 Fig.
9.5-1................ Amendment 1 Fig. 14.3-4 thru 14.3-5.... Amendment 1 9.6-1 thru 9.6-7............. Original Fig. 14.3-7..
............. Amendment 1 10-1......................... Original 14.4-1 thru 14.4-2............ Original 10.1-1 thru 10.4-1........... Original 15-1 thru 15-5.....
.......... Original 11-i......................... Original Appendix 1 11-li..................... Amendment 1 Table of Contents....... Amendment 1 11.1-1 thru 11.2-1........ Amendment 1 1A 1A-1 thru 1A-17....... Amendment 1
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SACRAMENTO MUNICIPAL UTILITY DISIRICT RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 LIST OF D cket No. 50-289 E F F ECTIV E PAGES February 2, 1968 Amendment No. 1 Page or Fig. No.
Issue Page or Fig. No.
Issue 1B 1B-1 thru 1B-5........ Amendment 1 2GA-1................
.. Amendment 1 Appendix 2 Appendix 3 Table of Contents....... Amendment 1 Table of Contents....... Amendment 1 2A Title Page................ Original 3A 3A-1 thru 3A-14....... Amendment 1 i thru vi.................
0riginal 4A Questions-4A-1 1 thu 63.................. Original thru 4A-8............... Amendment 1 2B Southeast Area Plan Appendix A to Question (Bound)-17 pages........... Original 4A.2-1 thru 15.......... Amendment 1 Preliminary Projections...
Appendix B to Question to 1985-1 thru 4........... Original 4A.2-1 thru 2........... Amendment 1 2C Geology and Seismology-Questions-4A-9 thru 2C-1 thru 2C-13, Fig 2C-1 4A-12...................Ameacment 1
thru 2C-11................. Original Appendix 5 Geophysical Report-Table of Contents....... Amendment 1 i
l 1 thru 6....
.............. Original 5A 5A-1..................... Original l
Additional Seismic Exploration-SA-2 thru SA-6.......... Amendment 1 1 thru 2, Plate 1 thru Fig SA-1 thru 5A-2...... Amendment 1 Plate 3.................
.. Original SB SB-1 thru 5B-3........... Original l
Geological Log of Drill 5C SC-1 thru 3C-3........... Original Holes-91 Sheets.......
.... Original SD 1 thru 10................ Original 2D Seismic Hazard at the SE SE-1 thru SE-2........... Original l
Clay Site 1 thru 14........ Original 5F SF-1 thru 5F-2........... Original i
Addendum to Seismic Hazard SG SG-1 thru SG-2........... Original at the Clay Site-1 sheet... Original 5H 5H-1 thru 5H-5........... Original Seismic Hazard at the SI SI-1..................... Original Sierran Sites Area 5J SJ-1 thru SJ-2........ Amendment 1 1 thru 10............... Amendment 1 Appendix 6 2E Soil and Foundations Table of Contents....... Amendment 1 Investigation Report 6A-1 thru 6A-6......... Amendment 1 2E-1 thru 2E-11, Fig C-119-E Appendix 7 thru C122-E................ Original Table of Contents....... Amendment 1 Report-of Laboratory 7A-1.................... Amendment 1 Testing-1 thru 9, 3 Tables, Appendix 9 Fig 1 thru 2 and 9, curves Table of Contents....... Amendment 1 1 thru 7................... Original 9A-1 thru 9A-2.......... Amendment 1 2F 2F-1 thru 2F-2........ Amendment 1 Appendix 11 2G 2G-1 thru 2G-3........ Amendment 1 Table of Contents....... Amendment 1 O
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O SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION UNIT NO. 1 LIST OF Docket No. 50-289 E F F ECTIV E PAGES February 2, 1968 Amendment No. 1 Page or Fig. No.
Issue llA-1 thru llA-6........ Amendment 1 Appendix 12 Table o f Contents....... Amendment 1
)
12A-1 thru 12A-4........ Amendment 1 Appendix 14 Table of Contents....... Amendment 1 14A-1 thru 14A-22...... Amendment 1 O
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(q Docket.No. 50-312 n
April 15, 1968
.a y, AMENDMENT NO. 2 i '
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 ciargin by a black bar and the numeral two.
.Before insertin'g ttie 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 i
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.
3 should be noted that-three new additional pages, 10, 11 and 12 are to-It
)
.be added.to the License Application.
%J, n.
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
.*are to be inserted-into the volumes according to the assigned SMUD number.
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- SMUD, DRL SMUD DRL SMUD QUESTION RESPONSE QUESTION RESPONSE QUESTION RESPONSE NO.
50.
NO.
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 12 A. 3 1.3 1A.6 6.3 6A.9
- 12. 3 12A.4 1.4 1A.7 6.4 6A.10 12.4 12 A. 5 1.5 1A.8 6.5 6A.11 12.5 12A.6 1.6 1A.9 6.6 6 A.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 6 A.16 13.3 13A.3 13.4 12 A.- 8 2.3 14A.16 2.4 14A.17 7.1 7A.2
)
2.5 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.8 14.6 14A.25 3.2 3A.7 7.8 7A.9 14.7 14A.26 3.3 JA.S 7.9 7A.10 14.8 14A.27 14.9 14A.28 3.4 3A.9 i-3.5 3A.10 8.1 6A.1 3.6 3A.ll 8.2 8A.2 15.1 15A.1 3.7 3A.12 9.3 8A.3 3.8 3A.13
.4 SA.4 16.1 7A.11 3.9 3A.14 S.5 SA.5 16.2 14A.29 16.3 14A.30 3.10 3A.15 9.1 9A.2 16.4 3A.16 g4.1 4A.12 9.2 9A.3 16.5 5J.5
" 4. 2 5J.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.S
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Amendment 2 B
Docket No. 50-312
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LIST OF April 15, 1968 E F F ECTIV E PAGES Amendment No.,
t The active pages in this report are as follpws:
Issue Pege or F2.g. No.
Issue Page or Fig. No.
' Title Page.
. Original' Fig. 2.2-1 thru 2.2-10.... original A thru H Amendment 2 2.3-1 thru 2.3-2.
Amendment 2
- i.............. Original 2.3-3 thru 2.3-4.
. Original li.
Amendment 2 2.3-5 thru 2.3-8.
Amendment 2 111.
. Original Fig. 2.3-1 thru 2.3-6.
. Original Amendment 2 2.4-1.
. Original iv;'.
v thru vii.
Amendment 1 2.4-2.
Amendment 2 viii.
Amendment 2 2.4-3.
. Original ix.
Amendment 1 Fig. 2.4-1 thr'u 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 1-11.
. Amendment 2 2.9-1
. Original 1-111.
. Original 3-i thru 3-tii.
Amendment 2 1-iv.
. Amendment 2 3-iv thru 3-vi.
. Original (3
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1.1-1 thru 1.1-2..
. Original 3.1-1.
. Original A
F ig. 1.1-1.
. Original 3.1-2 thru 3.1-4 Ame ndment ' 2 Amendment 2 I
Fig. 1.1-2 thru 1.1-8.. Amendment'2 3.1-5.
Amendment. 2 1.2-1.
.......... Original 3.1-6 s
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 1.3-5.
. Original 3.2-11.
Amendment 2 1.3-6 thru 1.3-7.
Amendment 2 3.2-12 thru 3.2-69.
. Original
. original 3.2-70 thru 3.2-101.
Amendment 2 1,3-8.
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. Amendment 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. 3.2-65.
Amendment 1 1.4-7 thru 1.4-8.
. Amendment 2 Fig. 3.2-66.
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.
.Originat Fig. 1.6-1 thru 1.6-2.
. Original 3.3-2.
Amendment 2 i
1.7-1
...... Original 3.3-3 thru 3.3-5.
Original l.8-1 thru 1.8-2.
. Original 3.3-6 thru 3.3-7.
Amendment 2
. Original 3.3-8 thru 3.3-10.
Original l.9-1.
.p.
2-1 thru 2-11.
. Amendment 1
- 3. 3-11 thru 3. 3-12.... Amendment 2 2-111.
. Original 3.4-1 thru'3.4-5...... Original 9
2.1-1.
. original 4-1 thru 4-ii.
Original
]$
2.2-1 thru 2.2-5.
. Original 4.1-1 thru 4.1-15.
Original Amendment 2 C
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LIST OF P
.e-as A rH b, 1966 g-
.v EFFECTIVE PAGES Amendment No. ?
%d Page or Fig. No.
Issue Page or Fig.'No.
Issue e
Fig. 4.1-1.
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 6-11.
. 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 thru 4.2.11.
. Amendment 2 6.1-1 thru l-7.
. Amendment 2 4.2-12.
Original 6.1-8.
. Original Fig. 4.2-1.
. Amendment 2 6.1-9 thru 6.1-10.
. Ame n d.ne n t 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
,-~s 5-1 thru 5-111....... Amendment 1 6.3-1 thru 6.3-2.
Original (x')
3.1-1.
. Amendment 1 6.3-3.
. Amendment 2 (7%
5.1-2.
. Original 7-i.
. Amendment 2
({g) 5.1-3.
. Amendment 1 7-11.
. Amendment 1 5.1-4 thru 5.1-9.
. Original 7-111.
. 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 5.1-25 thru 5.1-26.
. Amendment 1 Fig. 7.1-2 thru 7.1-3.
. Amendment 2 5.1-47 thru 5.1-29.
. Original Fig. 7.1-4.
. Original f7R-3p........... Amendment 1 7.2-1 thru 7.2-5.
Original 5.'1-11............ 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 Original 7.3-1 thru 7.3-3.
Original 5.2-1 thru 5.2-5.
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 i
5.4-6.
. Amendment 1 Fig. 7.3-3.
. Amendment 1 5.4-7.
Original Fig. 7.3-4 thru 7.3-5.
./mendment 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 3.6-2.
Original Fig. 7.4-1.
Original 5.6-3 thru 5.6-6.
.Amensceqt 2 8-i thru 8-11
. Amendment 2 Fig. 5.6-1.
.\\.
. Amendment 2 8.1-1.
Origina L
- 5. 7-1.
. Amendment 2 8.2-1 thru 8.2-18.
. Amendment 2 5.7-2.
Original Fig. 8.2-1 thru 8.2-3.
.Auendacnt 2 l
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D haendment 2 l
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l LIST OF 1
April 15* 1968
~
s E F F ECTIV E PAGES Amendment No. 2 Page or Fig. No.
Issue Page or Fig. No.
Issue r
8.3-1 thru 8.3-3.
... Amendment 2 12-i.
. Amendment 1 8.?-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 9-111.
. 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 9.1 '1' thru 9.1-2.
. Amendment 2 12.4-1.
.. Original 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 Amendment 2 9.2-2 thru 9.2-7.
. Amendment 2 13.1-3.
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 I Fig. 9.3-1 thru 9.3-3.
. Amendment 2 14-iv thru 14-viii
. Original
[a) 9.4-1 thru 9.4-4.
. Original 14.1-1 thru 14.1-7.
. Original
'~y 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
% 9.7-1 thr-9.7-2.
. Original 14.2-2 Amendment 2 ig. 9.7-1.
. Amendment 2 14.2-3.
Amendment 1 10-1.
. 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 11-1 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 1 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=qndment 1 14.2-38.
Amendment 2 11.2-2 thru 1122-5.
. Original 14.2-39.
. Original 11.2-6.
. Amendment 1 Fig. 14.2-1 thru 14.2-18.
. Original 11.2-7 thru 11.2-11.
. Original Fig. 14.2-19 thru 14.2-20. Amendment 2 p) 11.3-1.
. Original Fig. 14.2-21 thru 14.2-28.
. Original 77 Amendment 2 E
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LIST OF D ket No. 50-312 A ril 15, 1966
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s~~j EFFECTIVE PAGES P
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 Seismology-Fig. 14.2-33.
. Original Fig. 14.2-34.
. Amendment 2 Fig. 2C-1 thru 2C-Il.
. 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, I 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 I
([F,
r g-~3 Appendix 1 Table of 2E Soil and Foundations
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Contents.
... Amendment 2 Investigation Report lA Answers to Questions.
Amendment 1 2E-1 thru 2E-11, IA-1 thru 1A-14.
Amendment 1 Fig. C-Il9-E thru Fig. IA.2-1.
Amendment 1 Cl22-E.
Amendment 1 Report of Laboratory 1A-17 thru 1A-23 Amendment 2 Testing-1 thru 9, 3 Tables, 1B,qpality Assurance Fig. I thru 2 and 9, curves
"'Qpgrations Amendment 1 1 thru 7.
Original 13-lY..........
Original 2F Meteorological Station IB-2 thru 1B-4.
. Amendment 1 1B-5...
Amendment 2 2G Storage Reservoir Criteria Fig. IB-1.
. Amendment l IC Rancho Seco Project 2CA-l.
. Amendment 1 Engineering Staff.
Amendment 2 2H Answers to Questions
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LC-1 thru 1C-4 Amendment 2 2H-1 thru 2H-2
.Ame'ndment 2 Fig. IC-l.
Amendment 2 Letter pg. I and 2.
. Amendment 2 Appendix 2 Table of Fig. 2H.2-1 thru 2H.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.
. Amendment 1 Supplement Fig. 3A.2-1 thru,3A.2-3.. Amendment i 1 thru 18.
kmendment 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
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LIST OF Docket No. 50-312 EFFECTIVE PAGES April l5, 1968 Amendment No. 2 Page or Fig. No.
Issue Page or Fig. No.
. Amendment 2 Figure SG-1.
Original Appendix 4 Table of 5H Quality Control Procedure Contents.
. Amendment i for Field Welding 4A Answers to Questions 5H-l thru SH-5.
Original 4A-1 thru 4A-6 SI Containment Structure Fig. 4A.1-1 thru 4A.1-15. Amendment i Instrumentation Appendix A SI-1.
Original The Properties and Micro-SJ Answers to Questions structure of Spray-Quenched 5J-1 thru 5J-2.
. Amendment 1 Thick-Section Steels Fig. 5J2-1.
. Amendment 1 15 pages Original SJ-3 thru SJ-14.
. Amendment 2 4A-l.
Original Appendix 6 Table of
. Amendment 1 Contents
. Amendment 1 Appendix B, B & W Data 6A Answers to Questions (2 pgs.)
..Ame*ndment 1 6A-1
. Amendment 1 4A-9 thru 4A-12.
. Amendment 1 6A-2.
. Amendment 2 4A-13 thru 4A-18.
. Amendment 1 Appendix 5 Table of 6A-6 thru 6A-7
. Amendment 2
,f 3)
Contents
. Amendment 1 Fig. 6A 8-1.
. Amendment 2
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5A Structural Design Bases 6A-8 thru 6A-18.
. Amendment 2 Fig. 6A.16-1 thru Fig. 5A-6 thru SA-7.
... Amendment 1 6A.16-2.
. Amendment 2 Fig. SA-1 thru SA-2.
. Amendment 1 Appendix 7 Table of 5B Justification of Contents
. Amendment i Structural Proof Test -
7A Answers to Questions Pressures 7A-1.
. Amendment 1
,g53-1 thru 53-3.
. Amendment 2 5@ Specification for Splicing Appendix 8 Table of
' Reinforcing Bar Usiag the Contents
. Amendment 2 Coldwell Process 8A Answers to Questions SC-1 thru SC-3.
Original SA-1 thru 8A-4
. Amendment 2 5D Turbine Generator :lissiles Appendix 9 Table of 1 thru 10......... Original Contents
. Amendment 2 4 sheets of Parts Drawings 9A Answers to Questions 5E Justification for Load 9A-1.
. '.. Amendment 2 Factors 9A-2.
. Amendment 2 SF Justification for Yield Appendix 10 Contains nothing Reduction Factors.
Appendix ll Table of 5F-l thru 5F-2.
Original Contents
. Amendment 1 SC Description of the Finite llA Answers to Ouestions C
Element Technique Used in 11A-1 thru.llA-2
. Amendment 1 Containment S t'ru c tu ral Fig. IlA.1-1.
. Amendment i Analysis Fig. 11A.1-2
. Amendment 2 f<
SG-1 thru SG-2 Original llA-3 tnru llA-6.
. Amendment I Amendment 2 G
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Docket :lo. 30 - j l.l LIST OF April 15, 196a E F F ECTIV E PAGES amendment No.
Page or Fig. No.
Issue Page or Fig. No.
Issue Appendix 12 Table of Appendix 15 Table of Contents.
... Amendment 1 Contents Amandment 2 12A Answers to Questions 15'A Answers to Questions 12A-1 thru 12A-4.
. Amendment i 15A-L thru 15A-2.
. Amendment 2 12A-5 thru 12A-10.
. Amendment 2 Fig. 12A.5-1
. Amendment 2 12A-11.
. Amendment 2 Fig. L2A.6-1 thru L2A.6-3.
. Amendment 2 12A-12 thru 12A-17.
. Amendment 2 Appendix 13 Table of Contents.
. Amendment 2 13A Answers to Questions 13A-1 thru 13A-3.
. Amendment 2 Appendix 14 Table of Contents.
. Amendment i 14A Answers to Questions 14A-1.
. Amendment l 14A-2.
. Amendment 2 p)
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. Amendment 1 14A-7 thru 14A-9.
. Amendment 2 Fig. 14A.6-1 thru 14A.6-3.
. Amendment 1 Fig. 14A.6-4 thru 14A.6-5.
. Amendment 2 14A-ll thru 14A-13.
. Amendment 1 14A-14.
. Amendment 2 F4 g. 14A.8-1
. Amendment 2
' 14,\\-15 thru 14A-20.
. Amendment 1 F E 14A. ll-1 thru 14A.ll-2.
. Amendment i 14A-21 thru 14A-22.
. Amendment 1 14A-23 thru 14A-29.
. Amendment 2 Fig. 14A.18-1.
. Amendment 2 14A-30.
. Amendment 2 Fig. 14A.19-1.
. Amendment 2 14A-31 thru 14A-32.
. Amendment 2 Fig. 14A.21-1 thru 14A.21-4
. Amendment 2 14A-33 thru 14A-34.
. Amendment 2 FLg. 14A.22-1.
. Amendment 2 14A-35 thru 14A-36.
. Amendment 2 Fig. 14A.25-1.
. Amendment 2 Fig. 14A.26-1.
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. Amendment 2 14A.37 thru 14A-41.
. Amendment 2 o)
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TABLE OF CONTENTS VOLUME I 1.
INTRODUCTION AND
SUMMARY
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-l' 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 I'IDI 1 - HYDRAULIC AND THERMAL DESIGN PARAMETERS 1.3-1 1.3.2 ITDI 2 - CORE MECHANICAL DESIGN PARAMETERS 1.3-1 1.3.3 ITDI 3 - PRELDIINARY NUCLEAR DESIGN DATA 1.3-8 1.3.4 ITDI 4 - PRINCIPAL DESIGN PARAMETERS OF THE REACTOR C001 ANT SYSTDI 1.3-8 m.
1.3.5 ITDI 5 - REACTOR C001 ANT SYSTEM - CODE REQUIRDIENTS 1.3-8 1.3.6 ITEM 6 - PRINCIPAL DESIGN PARAMETERS OF THE REACTOR VESSEL 1.3-9 1.3.7 ITEM 7 - PRINCIPAL DESIGN FEATURES OF THE STEMI 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 COOLANT PIPING 1.3-9 1.3.10 ITEM 10 - REACTOR BUILDING PARAMETERS 1.3-9 1.3.11' ITD1 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 (CATECORY 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 (3
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Amendment ~3 i
000 008)
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Section Page 1.4.12 CRITERION 12 - INSTRUMENTATION AND CONTROL SYSTDIS (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 SYSTDIS (CATEGORY B) 1,4-12 1.4.15 CRITERION 15 - ENGINEERED SAFETY FEATURES PROTECTION SYSTDiS (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 RADIOACTIVITY 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 SYSTDIS 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 - DIERGENCY POWER FOR PROTECTION SYSTEMS (CATEGORY B) 1,4-17 1.4.25 CRITERION 25 - DEMONSTRATION OF FUNCTIONAL OPERABILITY OF PROTECTION SYSTDIS (CATEGORY B) 1.4-17 1.4.26 CRITERION 26 - PROTECTION SYSTDiS FAIL-SAFE DESIGN (CATEGORY B) 1,4-18 1.4.27 CRITERION '?7 - 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 - REACTIVITY SHUTDOWN CAPABILITY (CATEGORY A) 1.4-19 1.4.30 CRITERION 30 - REACTIVITY 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 COO 1 ANT PRESSURE BOUNDARY SURVEILIANCE (CATEGORY A) 1.4-22 0082 11 Amendment 3
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b Sec t' ion Page i
1.4.37. CRITERION 37 - ENGINEERED SAFETY FEATURES BASIS FOR DESIGN (CATEGORY A) 1.4-22 1.4.38 CRITERION 38 - RELIABILITY AND TESTABILITY OF ENGINEERED SAFETY. FEATURES. (CATECORY A) 1.4-23 1.4.39 CRITERION 39 - EdERGENCY 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 4
l CAPABILITY (CATEGORY A) 1,4-25 1.4.43 CRITERION 43 - ACCIDENT AGGRAVATION PREVENTION l
(CATEGORY A) 1.4-26 1.4.44 CRITERION 44 - EMERGENCY CORE COOLING SYSTEMS CAPABILITY ' (CATEGORY A) 1.4-26
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1.4.45 ' CRITERION 45 - INSPECTION OF EMERGENCY CORE COOLING
. SYSTEMS (CATEGORY A) 1.4-27 1.4.46 CRITERION 46 - TESTING OF EMERGENCY CORE COOLING SYSTEMS COMPONENTS (CATEGORY A) 1,4-27 1.4.47 CRITERION 47 - TESTING OF EMERGENCY CORE COOLING 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
,l 1.4.50. CRITERION 50 - NDT REQUIRDENT FOR CONTAINMENT MATERIAL (CATEGORY A) 1.4-29
. 1.4.51 CRITERION 51 - REACTOR COOLANT PRESSURE BOUNDARY OUTSIDE CONTAINMENT '(CATEGORY A) 1.4-29 1.4.52 CRITERION 52 - CONTAIN>ENT HEAT REMOVAL SYSTEMS (CATEGORY A).
1.4-30 1.4.53 CRITERION 53 - CONTAINMENT ISOLATION VALVES (CATEGORY A) 1.4-31 1.4.54 CRITERION 54 - CONTAINMENT LEAKAGE RATE TESTING (CATEGORY A) l.4-31 1.4.55 CRITERION 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 SYSTDIS
.(CATEGORY A) 1.4-34
- 1. 4. 6 L ' CRITERION 61 - TESTING OF OPERATIONAL SEQUENCE OF CONTAINMENT PRESSURE-REDUCING ' SYSTEMS (CATEGORY A) 1.4-34 N
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Section Pace 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 RADIOACTIVITY 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 (CATEGORY 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 1.54 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 IDESTIFICATION OF CONIRACTORS AND AGENTS 1.7-1
1.8 CONCLUSION
S 1.8-1
1.9 REFERENCES
1.9-1 2.
SITE AND ENVIRONMENT 2.1
SUMMARY
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 2.2.3 SITE ACTIVITIES 2.2-1 2.2.4 POPULATION 2.2-1 2.2.5 LAND USE 2.2-3 2.2.6 ACCESS AND EGRESS 2.2-3 2.2.7 MARE-UP WATEA SUPPLY 2.2-5 iv Amendment 4 00J 0084 0
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I Section Pace x-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 2.3-3 2.3.5 PRELIMINARY ESTIMATES OF DIFFUSION 2.3-5 2.4 HYDROLOGY 2.4-1 2.4.1 CHARACTERISTICS OF STREAMS AND LAKES IN VICINITY 2.4-1 2.4.2 TOP 0 GRAPHY 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 2.4.6 GROUNDRATEk 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
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2.8.1 CENERAL 2.3-1 2.8.2 LAND ENVIRONMENT 2.3-1 2.8.3 h'ATER E:iVIRON 'ENT 2.8-2 2.S.4 S AMPLI :G 2.8-2
2.9 REFERENCES
2.9-1 3.
REACTOR 3.1 DESIGN BASES 3.1-1 3.1.1 PERFORMANCE OBJECTIVES 3.1-1 3.1.2 LIMITS 3.1-1 3.2 REACTOR DESIGN 3.2-1 3.2.1 GENERAL
SUMMARY
3.2-1 3.2.2 NUCLEAR DESIGN AND EVALUATION 3.2-2 3.2.3 THERMAL AND HYDRAULIC DESIGN AND EVALUATION 3.2-29 3.2.4 MECHANICAL DESIGN LAYOUT 3.2-70 3.3 TESYS AND INSPECTIONS 3.3-1 3.3.1 NUCLEAR IESTS AND INSPECTION 3.3-5 3.3.2 THERMAL AND HYDRAULIC TESTS AND INSPECTION 3.3-2 3.3.3 FUEL ASSEMBLY, CONTROL ROD ASSEMBLY, AND CONTROL ROD DRIVE MECHANICAL TESTS AND INSPECTION 3.3-5 3.3.4 INTERNALS TESTS AND INSPECTIONS 3.3-19 I
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3.4 REFERENCES
3.4-1 hhhh A.cendment 3
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VOLUME II 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 GENERAL DESCRIPTION 4.2-1 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 MAXIMDI HEATING AND COOLING RATES 4.2-11 4.2.7 LEAR DETECTION 4.2-11 9
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 LIMITS 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 SURVEILLANCE 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 5.1-1 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 PENETRATIOS'S 5.2-1 5.2.1 TYPES OF PENETRATIONS 5.2-1 5.2.2 DESIGN OF PENETRATIONS 5.2-3 5.2.3 INSTALL \\ TION OF PENETRATIONS 5.2-5 5.2.4 TESTABILITY OF PENETRATIONS AND WELD SEAMS 5.2-5 00] 0086 vi Amendment 4
O Seetion Page
- 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 SURVEILLANCE 5.5-1 5.5.1 TESTS TO ENSURE LINER INTEGRITY 5.5-1 5.5.2 STRENGTH TEST 5.5-3 5.6 ISOIATION SYSTEM 5.6-1 5.6.1 DESIGN BASES 5.6-1 5.6.2 SYSTDI DESIGN 5.6-1 5.7 VENTILATION SYSTDI 5.7-1 5.7.1 DESIGN BASES 5.7-1 5.7.2 SYSTEM DESIGN 5.7-1 5.8 LEAKAGE MONITORING SYSTDI 5.8-1 5.9 SYSTDI DESIGN EVALUATION 5.9-1 p
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 SU> DIARY 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 i
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000 0087 OL, Amendment 3 vii
Section Page 7.
INSTRUBENTATION AND CONTROL 7.1 PROTECTION SYSTEMS 7.1-1 7.1.1 DESIGN BASES 7.1-1 7.1. 2 SYSTEM DESIGN 7.1-6 7.1.3 SYSTEMS EVALUATION 7.1-17 7.2 REGULATING SYSTEMS 7.2-1 7.2.1 DESIGN BASES 7.2-1 7.2.2 SYSTEM DESIGD; 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 SIATIONS 7.4-1 7.4.1 GENERAL LAYOUT 7.4-1 7.4.2 IhTORMATION 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 AUXILIARY CONTROL SIATIONS 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 NEIWORK INTERCONNECTIONS 8.2-1 8.2.2 STATION DISTRIBUTION SYSTEM 8.2-2 8.2.3 EMERGENCY POWER 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 DESIGN BASES 9.2-1 9.2.2 SYSTEM DESCRIPTION AND EVALUATION 9.2-1 viii Amendment 3 9
Section Page t
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
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9.6 FUEL RANDLING 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 VEYrILATION 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
.i 10.1.1 OPERATING AND PERFORMANCE REQUIREMENTS
- 10. 1-1 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 10.2.5 CORROSION PROTECTION 10.2-2 10.2.6 IMPURITIES CONTROL 10.2-2 10.2.7 RADIOACTIVITY 10.2-2 10.3 SYSTEM ANALYSIS 10.3-1
-10.3.1 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 10.3.6 OPERATIONAL LIMITS 10.3-2
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.10.4 TESTS AND INSPECTIONS 10.4-1
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Section page 11.
RADIOACTIVE WASTES AND RADIATION PROTECTION 11.1 RADIOACTIVE WASTE HANDLING 11.1-1 11.1.1 DESIGN EASES 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 TRITIDI MANAGEMENT FOR NORMAL OPERATION 11.1-8 11.2 RADIATION SHIELDING 11.2-1 11.2.1 PRIMARY, SECONDARY, REACTOR BUILDING, AND AUXILIARY 11.2-1 SHIELDING 11.2.2 AREA RADIATION MONITORING SYSTEM 11.2-6 11.2.3 HEALTH PHYSICS 11.2-8 11.3 REFE RENCES 11.3-1 12.
CONDUCT OF OPERATIONS 12.1 TNTRODUCTION 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 TESTS PRIOR TO REACTOR FUELING 13.1-1 13.2-1 13.2 INITIAL CRITICALITY 13.3-1 13.3 POSTCRITICALITY TESTS oouuJ 0090 lll>
Amendment 4 x
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Section Page 14.
SAFETY ANALYSIS 14.1 CORE AND COOLANT 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 SAFEGUARDS ANALYSIS 14.2-1 14.2.1 SITUATIONS ANALYZED AND CAUSES 14.2-1 14 ^_ 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 GENERATOR TUBE FAILURE 14.3-1 14.3.3 LOSS OF ELECTRIC POWER 14.3-i 14.3.4 STEAM LINE FAILURE 14.3-3 14.3.5 FUEL HANDLING ACCIDENT 14.3-4 14.3.6 ROD EJECTION ACCIDENT 14.3-4 14.3.7 WASTE GAS TANK RUPTURE 14.3-4 14.3.8 LOSS-OF-COOLANT ACCIDENT 14.3-5 14.3.9 MAXIMUM HYPOTHETICAL ACCIDENT 14.3-6 14.3.10 IODINE REMOVAL SENSITIVITY ANALYSIS 14.3-10
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14.3.11 POPULATION DENSITY CONSIDERATIONS 14.3-12
14.4 REFERENCES
14.4-1 15.
TECHNICAL SPECIFICATIONS 1
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VOLUME IV APPENDIX 1 1A ANSWERS TO QUESTIONS 1B QUALITY ASSURANCE OPERATIONS IC RANCHO SECO PROJECT ENGINEERING STAFF APPENDIX 2 2A FITEOROLOGY 2B LAND USAGE AND POPULATION 2C GEOLOGY A'iD SEISMOLOGY 2D SEISMIC REPORT 2E SOIL AND FOUNDATIONS INVESTIGATION RE? ORT 2F METEOROLOGICAL STATION 2G STORAGE RESERVOIR 2H ANSWERS TO QUESTIONS APPENDIX 3 3A ANSWERS TO QUESTIONS APPENDIX 4 4A AJSWERS TO QUESTIONS
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VOLUME V APPENDIX 5 SA STRUCTURAL DESIGN BASES i
5B JUSTIFICATION OF STRUCTURAL PROOF TEST - PRESSURES SC SPECIFICATION FOR SPLICING REINFORCING BAR USING THE CADWELD PROCESS SD TURBINE GENERATOR MISSILES j.
SE JUSTIFICATION FOR LOAD FACTORS SF JUSTIFICATION FOR YIELD REDUCTION FACTORS 5G DESCRIPTION OF THE FINITE ELEMENT TECHNIQUE USED IN CONTAINMENT STRUCTURAL ANALYSIS i
5H. QUALITY CONTROL PROCEDURE FOR FIELD WELDING SI CONTAINMENT STRUCTURE INSTRUMC4TATION l
O 5J ANSWERS TO QUESTIONS 1
APPENDIX 6 i
6A ANSWERS TO QUESTIONS api)ENDIX 7 1-7A ANSWERS TO QUESTIONS APPENDIX 8 O_.
8A ANSWERS TO QUESTIONS I
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APPENDIX 9 9A ANSWERS TO QUESTIONS APPENDIX 11 llA ANSWERS TO QUESTIONS APPENDIX 12 12A ANSWERS TO QUESTIONS APPENDIX 13 O
13A ANSWERS TO QUESTIONS 1
APPENDIX 14 14A ANSWERS TO QUESTIONS APPENDIX 15 15A ANSWERS TO QUESTIONS 003 0094 g
xiv Amendment 3 1
i
TABLE OF CONIENTS 10.
STEAM AND POWER CONVERSION SYSTEM Section Page 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 10.2.5 CORROSION PROTECTION 10.2-2 10.2.6 IMPURITIES CONTROL 10.2-2 10.2.7 RADIOACTIVITY 10.2-2 10.3 SYSTEM ANALYSIS 10.3-1 10.3.1 TRIPS, AUTOMATIC CONTROL ACTIONS, AND ALARMS 10.3-1 m
10.3.2 TRANSIENT CONDITIONS 10.3-2 I
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10.3.3 MALFUNCTIONS 10.3.2 10.3.4 OVERPRESSURE PROTECTION 10.3-2 10.3.5 INTERACTIONS 10.3-2 10.3.6 OPERAT10NAL LIMITS 10.3-2 10.4 TESTS AND INSPECTIONS 10.4-1 LIST OF FIGLRES Figure Number Title 10.2-1 Steam and Power Conversion System Amendment 3_
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STEAM AND POWER CONVERSION SYSTEM 10.1 DESIGN BASES 10.1.1 OPERATING AND PERFORMANCE REQUIREMEhTS The steam and power conversion system for the unit will be designed to remove heat energy from the reac' tor coolant in the two steam generators and convert it to electrical energy. The closed feedwater cycle will con-dense the steam, and the heated feedwater will be returned to the steam generators. The entire system will be designed for the maximum expected energy (2584 Mwt) from the nuclear steam supply system.
Upon loss of full load, the system will dissipate all the energy existent or produced in the reactor coolant system through steam relief to the con-denser and the atmosphere. The unit will be designed to maintain station auxiliaty load without a reactor trip on loss of full load. The steam bypass to the condenser and atmospheric relief valves will be utilized as necessary to achieve this load reduction.
10.1.2 ELECTRICAL SYSTEM CHARACTERISTICS The station will be designed for load following operation. The maximum
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rate of change of load is noted in 10.1.3.
O 10.1.3 FUNCTIONAL LIMITATIONS The rate of change of reactor power will be limited to values consistent with the characteristics of the reactor coolant system and its control systems. These limitations in the reactor coolant system will be reflected as functional limitations in the steam and power conversion system.
Increasing reactor power transients between 20 and 90 percent of full load will be limited to ramp changes of 10 percent per minute and step increases of 10 percent. Power variations above 90 percent will be limited to 3 per-cent per minute.
Decreasing reactor power transients between 90 and 20 percent of full load will be limited to ramp changes of 10 percent per minute and step decreases of 10 peccent.
10.1.4 SECONDARY FUNCTIONS The steam and power conversion system will provide steam for driving the two one-half capacity feedwater pumps.
Steam will also be used for the condenser air removal equipment, gland steam seal system, the radwaste process equipment, and the 5 percent emergency feedwater pump when required.
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000 0096 OL 10.1-1 b
10.2 SYSTEM DESIGN AND OPERATION 10.2.1 SCHEMATIC FLOW DIAGRAM The steam and power conversion system is shown in Figure 10.2-1.
The closed cycle feeduater heaters will be half-size units (two parallel strings).
De-aeration will be accomplished in the condenser hotwell.
A bypass of 15 percent of full load main steam flow to the condenser will be provided.
Three one-half capacity condensate pumps will be in normal use at all times to avoid tripping of the unit if one condensate pump is lost.
Each of the two feedwater pumps will be at least one-half capacity.
There will be a total of five minutes condensate storage at full load in the condenser hotwells.
There will also be two 5 percent capacity, emergency feedwater pumps, one turbine driven and one motor driven, which take suction from the conden-sate train or condensate storage tank and pump to the steam generators.
Steam for the turbine drive will come from the main steam line and from the hot reheat line.
The main steam lines and the feedwater lines will be the only lines of 7'
the steam and power conversion system which penetrate the reactor building.
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These lines can be isolated by the main stop valves and the feedwater line valving.
Each of the lines or common header leaving the main steam line 3
before the main stop valves has valves to complete the isolation of a steam generator. These lines are:
a.
Steam bypass b.
Steam relief valves to atmosphere c.
Supply to steam reheaters d.
Supply header to ccndenser, feed pump turbines, air ejectors, emergency feed pump turbine, gland steam seal system, and radwaste system 10.2.2 CODES AND STANDARDS The turbine-generator equipment will conform to the applicable USASI, ASME and IEEE standards.
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Amendment 2 10.2-1
System Design and Operation The design, materials and details of construction of the feedwcter heaters will be in accordance with both the ASME Code, Section \\ III, "Unfired Pressure \\ cssels," and the Standards of Feedwater Heater Manufacturers' Association, Inc.
The condenser equipment will be in accordance with the Standards for Steam Surface Condensers as published by the Heat Exchange Institute.
10.2.3 DESIGN FEATURES The condenser air ejector off-gas will be continuously monitored with an alarm to indicate high radiation levels. The air ejector off-gas will be released through the plant vent, as will the feedwater heater relief valve line.
10.2.4 SHIELDING No radiation shielding will be required for the components of the steam and power conversion sys tem.
Continuous access to the components of this system will be possible during normal conditions.
10.2.5 CORROSION PROTECTION Hydrazine will be added to the feedwater for oxygen control, and ammonia will be used to maintain the pH at the optimum value for the materials of construction for the systru.
No other additives are contemplated.
10.2.6 IMPURITIES CONTROL Impurities in the steam and power conversion system will be controlled by a polishing demineralizer sized for at least one-half flow. The makeup water to the steam and power conversion system will be treated by a sep-arate demineralizer.
10.2.7 RADIOACTIVITY Under normal operating conditions, there will be no radioactive contamin-ants present in the steam and power conversion system.
It is possible for this system to become contaminated only through steam generator tube leaks.
In this event, monitoring of the steam generator shell side sample points and the air ejector off-gas will detect any contamination.
Leakage of radioactivity from the condensate system into the cooling water system cannot occur. The circulating water pressure will be greater than 20 psig because of the head developed for the cooling towers.
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10.3 SYSTEM ANALYSIS 10.3.1 TRIPS, AtTIOMATIC CONTROL ACTIONS, AND ALARMS Trips, autcmatic control actions, and alarms will be initiated by devia-tions of system variables within the steam and power conversion system.
In the case of automatic corrective action in the steam and power conver-sion system, appropriate corrective action will be taken to protect the reactor coolant system.
The more significant malfunctions or faults which cause trips, automatic actions or alarms in the steam and power conversion system are:
a.
Turbine Trips (1) Generator / electrical faults (2) Loss of condenser vacuum (3) Thrust bearing wear (4) Loss of both feedwater pumps (5) Turbine overspeed (6) Reactor trip b.
Automatic Control Actions (1) Feedwater flow lagging feedwater demand results in a reduction in power output.
(2) Low feedwater temperature results in a reduction in power output.
(3) High level in steam generator results in a reduction in feedwater flow.
( 4) Low level in steam generator results in an increase in feedwater flow.
c.
Principal Alarms (1) Low pressure at feedwater pump suction (2) Low vacuum in condenser (3) Low water level in condenser hotwell (4) High water level in ecndenser hotwell (5) High water level in steam generator (6) Low water level in steam generator (7) High pressure in steam generator Rno Ql01 l-10.3-1
System Analysis (g) 1.ow pressure in steam generaur (9) Lou feedwater temperature 10.3.2 TRANSIENT CONDITIONS The analysis of the effects of loss of full load on the reactor coolant system is discussed in 14.1.2.8.
Analysis of the ef fects of partial loss of ad on the reactor coolant system is discussed in 7.2.3.4.
10.3.3 MALFUNCTIONS The effects of inadvertent steam relief or steam bypass are covered by the analysis of the steam line failure given in 14.1.2.9.
The effects of an inadvertent rapid throttle valve closure are covered by the loss of full load discussion in 14.1.2.8.
10.3.4 OVERPRESSURE PROTECTION Pressure relief is required at the system design pressure of 1050 psig, and the first safety valve bank will be set to relieve at this pressure.
The design pressure is based on the operating pressure of 925 psia plus a ten percent allowar.cc for transients and a four percent allowance for blowdown. Additional safety valve banks will be set at pressures up to 1104 psig, as allowed by the ASME Code.
The pressure relief capacity will be such that the energy generated at the reactor high power level trip setting can be dis,sipated through this system.
10.3.5 IhTERACTIONS Following a turbine trip, the control system will reduce reactor power output immediately.
The safety valves will relieve excess steam until the output is reduced to the point at which the steam bypass to the con-denser can handle all the steam generated.
In the event of failure of a single feedwater pump, there will be an auto-matic runback of the power output. The one feedwater pump remaining in service will carry approximately 60 percent of full load feedwater flow with feedwater to individual steam generators proportioned by control valves.
If both feedwater pumps fail, the turbine will be tripped, and the emergency feedwater pump started.
If reactor coolant system conditions reach trip limits, the reactor will trip.
10.3.6 OPERATIONAL LIMITS The air ejector off-gas will be monitored for radioactivity, and safe operating limits will be established for the station.
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10.4 TESTS AND INSPECTIONS As is essential in successful operation of any modern power station, fre-quent functional operational checks will be made on vital valves, control systems and protective equipme'nt.
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