ML20198G746
| ML20198G746 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Diablo Canyon |
| Issue date: | 12/20/1985 |
| From: | Knight J Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML082840462 | List:
|
| References | |
| FOIA-86-197 TAC-60065, NUDOCS 8601060490 | |
| Download: ML20198G746 (2) | |
Text
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%b UNITED STATES E
NUCLEAR REGULATORY COMMISSION o
g c
WASHINGTON, D. C. 20555 t
/
December 20, 1985 MEMORANCUM FOR: Steven A. Varga, Director PWR Project Directorate #3 Division of PWR Licensing-A FROM:
James P. Knight, Assistant Director for PWR-A Division of PWR Licensing-A
SUBJECT:
SUPPLEMENTAL SAFETY EVALUATION REPORT INPUT DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATION - STARTUP TEST REPORTING CLARIFICATIONS Enclosed is our Supplemental Safety Evaluation Report (SSER) input related to clarification of Technical Specification requirements for startup test reporting, Section 6.9.
This task was assigned to the pre-reorganization, Procedures and Systems Review Branch, under TAC No. 60065 and is now completed.
The DBL:F0B reviewer is Richard Becker (X29689).
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,g James P. Knight, Assistant Director for PkR-A '
Division of PWR Licensing-A
Enclosure:
SSER Input cc:
H. Schierling T. Speis h
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t SUPPLEMENTAL SAFETY EVALUATION REPORT INPUT DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS SECTION 6.9 -
REPORTING REQUIREMENTS CLARIFICATION Technical Specifications Subsection 6.9.1.1 reouires the insertion of the word " initial" between the words "The" and "Startup" and "startup" between the words "the" and " tests" and " chapter 14 of" between the words "in" and "the," in the first sentence of the paragraph.
In addition, the sentence,
" Subsequent Startup Reports shall address startup tests that are necessary to demonstrate acceptability of the change and/or modification." is to be added to the paragraph.
These clarifications are necessary to clearly stipulate that the subject matter of the initial startup report need only cover the power ascension phase of testing. There are preoperational, acceptance and other tests, described in Section 14 and other sections of the Final Safety Analysis Report, the results of which are not required to be reported. The added sentence clarifies the content of subsequent startup test reports after the initial power ascension is completed.
Principal Contributor:
R. A. Becker Dated:
December 20, 1985
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
I wAsHWGTON, D. C. 20066 e,
f
,,,,,l JAN 6 1986 Docket Nos.: 50-275 and 50-323 LICENSEE: Pacific Gas and Electric Company (PG&E)
FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2
SUBJECT:
MEETING
SUMMARY
- SPENT FUEL POOL RERACKING arctrteMN)98 bers of the NRC Staff and its consultants (Franklin cember 5 1 On met with representatives from Pacific Gas and Electric Company R
(PG&E) and its contractors and consultants (Bechtel, Joseph Oat Corporation (rack vendor) and Southern Sciences) to discuss the PG8E proposed spent fuel pool re. eking for Diablo Canyon Units 1 and 2 as described in the PG&E Reracking Report (PG&E letter DCL 85-306, dated September 19,1985) and the associated License Amendment Request LAR-85-13 (PG&E letter DCL-85-333, dated October 30,1985). The meeting announcement, acenda and list of attendees are provided in Enclosures 1, 2 and 3 respectively.
(Note: A television company was present for approximately 15 minutes at the beginnina to film the meeting).
Fol10 wino a brief overview of the existing fu'el handlina building and fuel storaae facility PG8E and Joseph Oat Corporation described the proposed spent fuel pool rerackino layout, design fabricatinn and assnciated safety analyses perfomed for the existing spent fuel pool structures and the new racks. The following specific subjects were discussed and view graphs provided as indicated:
1.
Rack design and arranaement details; Oat experience with rack design (Enclosure 4) 2.
Criticality analysis and results (Enclosure 5) 3.
Seismic analysis and results (Enclosure 6) 4.
Thermal-hyraulic analysis and results (Enclosure 7) 5.
Fuel pool makeup water sources (Enclosure 8 6.
Fuel pool structure evaluation (Enclosure 9.
During the discussions the NRC Staff raised the following questions and requests for further information:
1.
Identify proposed changes to mechanical, cleanup, HVAC and radiation monitoring systems as resulting from the reracking.
2.
Identify the sources of makeup water and flow capacity. Consider the need for changes to the Technical Specifications if the. condensate storage tank is relied on as a source for makeup water.
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3.
Discuss the spent fuel. pool cooling system with respect to the requirements of General Design Criterion 44 of 10 CFR 50, Appendix A.
4.
Clarify if the allowable stress limits for Level A and Level B Service are identical (see pace 6-16 of the Reracking Report).
5.
Specify the water level above the top of the new fuel racks for various conditions.
6.
Discuss the compatibility of the new fuel racks with the fuel pool material and environment.
7.
Describe in detail how ALARA commitments were considered in the spent fuel pool layout and design.
8.
The change in offsite doses for postulated accidents should be addressed.
9.
What is the incremental radioloaical dose due to the increased spent fuel storage capacity to plant operations personnel during the life of the plant from routine fuel handling operation?
- 10. Clearly indicate that fuel from other facilities will not be stored in the Diablo Canyon fuel pools and that PG&E does not intend to ship fuel offsite in the near future.
- 11. Address the consequences of thermal expansion of the fuel racks under maximum fuel temperature, e.g., with respect to the gap between modules.
The staff stated that the above questions and concerns are the result of its review thus far of the Reracking Report and the presentation at this meeting.
The staff finds that further information is required in general with respect of the spent fuel pool cooling system capability and radioloaical consequences of postulated accidents. The staff will provide PG&E with a written reouest for additional information in the near future.
l PG&E stated that the design of the reracks has essentially been completed.
l Delivery at the site is expected by the end of February 1986. The installation i
is expected to commence in early April 1986. PG&E stated that installation of the new racks in a wet condition would complicate and prolong the process. The staff indicated that, based on its review thus far, it appears that the technical issues can be resolved in a timely manner.
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- , The staff stated that the required prenoticina of the proposed spent fuel pool reracking and associated changes of the Technical Specifications is in process.
Hans Schierling, Pro.iect Manager PWR Pro.iect Directorate No. 3 Division of PWR Licensing-A
Enclosures:
As stated cc: See next page Distribution:
Docket File / Central File W. Brooks NRC PDR L. Chandler L PDR R. Fell PAD #3 Rdg H. Gilpin ORAS S. B. Kim H. Denton T. Quay S. Varga F. Rinaldi H. Schierling R. Serbu OELD J. Shapker E. L. Jordan A. Singh B. Grimes J. Wing J. Martin R. Herrick (Franklin Research Center M. Mendonca ACRS (10)
C. Parrish f
D AD3 CParrish-HSchi$
ing/yt )
S 1/g/86 1/h/86 1/ /86
- t Mr. J. D. Shiffer Pacific Gas and Electric Company Diablo Canyon cc:
Philip A. Crane, Jr., Esq.
Resident Inspector /Diablo Canyon NPS Pacific Gas & Electric Company c/o US Nuclear Regulatory Commission Post Office Box 7442 P. O. Box 369 San Francisco, California 94120 Avila Beach, California 93424 Mr. Malcolm H. Furbush Ms. Raye Fleming Vice President - General Counsel 1920 Mattie Road Pacific Gas & Electric Company Shell Beach, California 93440 Post Office Box 7442 San Francisco, California 94120 Joel Reynolds, Esq.
John R. Phillips Esq.
Janice E. Kerr, Esq.
Center for Law in the Public Interest '
California Public Utilities Commission 10951 West Pico Boulevard 350 McAllister Street Third Floor San Francisco, California 94102 Los Angeles, California 90064 Mr. Frederick Eissler, President Mr. Dick Blankenburg Scenic Shoreline Preservation Editor & Co-Publisher Conference, Inc.
South County Publishing Company 4623 More Mesa Drive P. O. Box 460 Santa Barbara, California 93105 Arroyo Grande, California 93420 Ms. Elizabeth Apfelberg Bruce Norton, Esq.
1415 Cozadero Norton, Burke, Berry & French, P.C.
San Luis Obispo, California 93401 202 E. Osborn Road P. O. Box 10569 Mr. Gordon A. Silver Phoenix, Arizona 85064 Ms. Sandra A. Silver 1760 Alisal Street Mr. W. C. Gangloff San Luis Obispo, California 93401 Westinghouse Electric Corporation P. O. Box 355 Harry M. Willis, Esq.
Pittsburgh, Pennsylvania 15230 Seymour & Willis 601 California Street Suite 2100 David F. Fleischaker, Esq.
San Francisco, California 94108 P. O. Box 1178 Oklahoma City, Oklahoma 73101 Mr. Richard Hubbard MHB Technical Associates Suite K 1725 Hamilton Avenue San Jose, California 95125 l
Mr. John Marrs, Managing Editor l
San Luis Obispo County Telegram Tribune 1321 Johnson Avenue P. O. Box 112 San Luis Obispo, California 93406 l
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't Pacific Gas & Electric Company Diablo Canyon cc:
Arthur C. Gehr, Esq.
Mr. Thomas Devine Snell & Wilmer Government Accountability 3100 Valley Center Project Phoenix, Arizona 85073 Institute for Policy Studies 1901 Que Street, NW Mr. Leland M. Gustafson, Manager Washington, DC 20009 Federal Relations Pacific Gas & Electric Company 1726 M Street, N.W.
Suite 1100 Washington, DC 20036-4502 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Michael J. Strumwasser, Esq.
Special Counsel to the Attorney General State of California 3580 Wilshire Boulevard, Suite 800 Los Angeles, California 90010 Mr. Tom Harris Sacramento Bee 21st and 0 Streets Sacramento, Califarnia 95814 Mr. H. Daniel Nix California Energy Commission l
1516.9th Street, MS 18 l
Sacramento, California 95814 i
Lewis Shollenberger, Esq.
US Nuclear Regulatory Commission Region V 1450 Maria Lane Suite 210 l
Walnut Creek, California 94596
Pacific Gas & Electric Company Diablo Canyon ec:
Chairman San Luis Obispo County Board of Supervisors Room 220 County Courthouse Annex San Luis Obispo, California 93401 Director Energy Facilities Siting Division Energy Resources Conservation and Development Commission 1516 9th Street Sacramento, California 95814 President California Public Utilities Commission California State Building 350 McAllister Street San Francisco, California 94102 Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 O
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UNITED STATES P
NUCLEAR REGULATORY COMMISSION o
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.,1 WASHING TON, D. C. 20555
- ...../
s, NOV 181985 Docket Nos.: 50-275 and 50-323 MEMORANDUM FOR: George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing FROM:
Hans Schierling, Project Manager Licensing Branch No. 3 Division of Licensing
SUBJECT:
DIABLO CANYON POWER PLANT - SPENT FUEL POOL RERACKING DATE & TIME:
December 5, 1985 9:00 am LOCATION:
Room 6507 Maryland National Bank Building Old Georgetown Road Bethesda, Maryland PURPOSE:
PG&E will discuss its proposed spent fuel pool reracking for Units 1 and 2 and provide additional information as requested by the staff.
PARTICIPAm'S:
NRC LICENSEE H. Schierling B. Lew W. Brooks E. Connell F. Witt S. Johnson S. Kim B. Giffin H. Gilpin Consultants R. Serbu A. Singh R. Fell E. Pentecost G. Knighton t
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ns Schierling, Project M ager Licensing Branch No. 3 Division of Licensing cc: See next page 1,. n s
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PROPOSED MEETING AGENDA NRC 1.
NRC Opening Remarks PGandL 2.
PGandE Opening Remarks PGandE 3.
Current Configuration PGandE/
4.
Proposed Rerack Design Joseph Oat General design and layout a.
Similarity to other previously approved design and b.
Joseph Oat's experience on rack design Criticality analysis and results c.
d.
Seismic design and load sembin,tions Thermchydraulic Design e.
Makeup capability during a Pool Boiling Event f.
Fuel pool structural analysis for the new storage racks g.
PGendE 5.
Schedule PGandE/
6.
Discussion NRC NRC 7.
Summary Remarks L
9 1125M
'J.
Attendees NRC/PG8E Meeting December S, 1985 NRC and Consultants PGAE and Consultants W. Brooks R. Anderson (Bechtel)
L. Chandler S. Bhattacharya R. Fell G. Blanc H. Gilpin E. Connell, III R. Herrick*
B. Giffin S. B. Kim J. Hinds T. Quay R. Johnson F. Rinaldi S. Johnson (Bechtel)
H. Schierling T. P. Lee R. Serbu B. Lew J. Shapker R. Locke A. Singh D. Ogden J. Wina G. Sarkisian K. Sinah (Oat)
M. Tressler S. Turner
- L. Womack News Media (part-time)
J. Henreux - W Newsfeed H. Hinds
- n Newsfeed
- Consultants i
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Q Cut wrCan ikG'% tins & I Arnalon kJCig an 90*In Cou*ONI Nts s,
Ed. sue 4
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l DIABLO CANYON POWER PLANT l
UNITS 1 AND 2 I
l UNIT 1: 1084 MW.
l 3338 MWe t
UNIT 2: 1106 MW, CURRENT CAPACITY 270 PROPOSED EXPANSION:
1324 NO. OF MODULES 16
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BURN-UP 34500 MWD /MTU ENRICHMENT 4.5 % WEIGHT
l Table 2.1 DESIGN DATA t
1 (Cell Pitch)
Flux Trap Nominal Min. B-10 Gap (Nominal)
Region in.
Loading in.
s 1
10.93 0.012 ga/ca 1.786 i
1 2
10.93 unpoisoned 1.9
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Table 2.2 MODULE DATA Approximate Module Ouantity cells per Array Weight Region Type Per Unit Module Size (lb/ module) 1 A
2 100 10 x 10 21,500 1
B 1
90 9 x 10 19,500 2
C 1
100 10 x 10 25,500 2
D 3
90 9 x 10 23,000 2
E 1
66 11 x 6 17,000 2
F 1
72 9x8 18,500 2
G 1
80 10 x 8 20,500 15,000 2
H 1
24 + 10 2
J 1
96 9 x 10 + 6 24,500 2
K 1
54 6x9 14,000 l
2 L
1 81 9x9 21,000 2
M 1
110 11 x 10 28,000 2
N 1
81 9x9 21,000 l
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e WESTINGHOUSE FUEL ASSEMBLY
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OAT FUEL RACKS BASIC ATTRIBUTES 4
ALL 304L S.S. CONSTRUCTION 4
FREE STANDING G
VENTED POISON CONSTRUCTION 4
REDUNDANT FLOW PATHS 4
ACCOMMODATES POOL FL005 WAVINESS 4
CELLilLAR CONSTRUCTION 4
CAN EASILY CONFORM TO NON-RECTANGULAR STORAGE AREAS c a p 4 & e.
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Table 3.1 BORAFLEX EXPERIENCE FOR HIGH DENSITY RACKS i
Plant NRC Licensing Site Type Docket No.
Status Point Beach 1 and 2 PWR 50-226 & 301 Licensed Nine Mile Point 1
BWR 50-220 Licensed i
1 and 2 PWR 50-269 6 270 Licensed I
Oconee Prairie Island 1 and 2 PWR 50-282 & 306 Licensed Calvert Cliffs 2
PWR 50-318 Licensed Quad Cities
PWR 50-382 Pending Fermi
- 2 BWR 50-341 Licensed H. B. Robinson 2
PWR 50-261 Licensed River Bend 1
BWR 50-458 Licensed Rancho Seco
- 1 PWR 50-312 Licensed Nine Mile Point 2
BWR 50-410 To be ap-plied for Shearon Harris 1
PWR 50-400 To be ap-plied for Millstone 3
PWR 50-423 To be ap-plied for 1
BWR 50-416 Pending Grand Gulf BWR 50-219 Licensed Oyster Creek
- V. C. Summer
- PWR 50-395 Licensed
- Joseph Oat Corporation-fabricated racks
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3.49 am Deseemed hip htty Juneph est tresus-3) apues suma amene
- eery, asraassa sarte seems Seteest Sesana Gumpey Fanashad 3439 tashnesten peh11e pts 3.300 8000 patasmad tagh emnetty WS Corporettes Power sepply system egens fant resha (Ub'P-Omit 1)
(IAIP4mst 3)
(UtP 4mit 3)
(up-east 4)
(WEp=Ghit 3) tartnuma anstaasten pah11s poner supply systan la Process $443 enumsmaalth Ediana M
S.W0 1980 pmaammme hip emmesty Jameph est to a1yt (6.ed C3 ties a Saat 1) spent fun! remha P&atehse (Dead C1stee
- Snit 3)
REFtat.sct : Seed tattee t 6 3 e -.ith Estase te Process 3452 Secremsets amnistpal pts 3.12 8901 petammad hip emastty Joaoph est Beeign De118eles Statetat spues Smal samha Fle&ahad (Reshe Some4 mat 1)
EFERENCE: Banske Sean Saaremsete tuntespal St116taas Baattist Is Preesse 3454 assetestypt puner &
M 3.Ill Ital totammad high emastty Joseph Ost Desigs L&#ht Campany spans Smal sneks Fansehad (Grand Swif % 1=ar Statten = tatt #1)
RETlaES2: W &;.
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M 3.tec
$941 potees tag essetty Josert est ad light spent emot uneke (opster Cremk) martats:t r seeeras petits statattaa
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4-29
_ _ _ -. - ~ _
Figure 4-1 SPENT FUEL RACK CRITICALITY ANALYSIS FEL ELDOff DESIGN STORAGE RACK OESIGN and ed PERFORNANCE SPECIFICATION ECHANICAL TOLERANCES UTILITY /VDCOR JOSEPH DAT CORPORATION GE(MTRIC ICOEL and
=
FEL SPECIFICATI(MS I
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I PRINCIPAL FML M U.
ENSITIVITY ANALYSES CALCLLATIONS ANALYSES 4
CASND E CASPC E pgAIF and e
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t REFERDKE REACTIVITY REACTIVITIES LMCERTAINITIES COMPUTER CODES CASMO 2E - NitigrouP TranePort, IELIF - Nltigeme Cross-Section Theory
~Ceneration MX (NITAWU - 27 Crog SCALE CNR00 - Slackness Therg Liberg KDC - Nltigene Mnte-Crlo FD W D Diffusion Theorg o
SUMMARY
OF CRITICALITY SAFETY ANALYSES l
Region 1-Region 2 Minimum acceptable burnup 0
34.5 mwd /kgU f 4.5% initial enrichment Temperature assumed 0*C 65*C for analysis Reference k, (nominal) 0.9104 0.9119 Calculational bias 0.0013 0.0013 Uncertainties Bias 10.0018 10.0018 B-10 concentration 70.0013 NA Boraflex thickness 70.0064 NA Boraflex width 30.0006 NA Inner box dimension 10.0008 70.0002 Water gap thickness 70.0029 70.0041 SS thickness 10.0018 30.0028 Fuel enrichment 10.0011 10.0011 Fuel density to.0029 10.0029 i
Eccentric assembly
+0.0010
+0.0020 position Statistical 10.0083 10.0064 combination Allowance for NA
+0.0183 burnup uncertainty c
Total 0.9117,* 0.0083 0.9315 1 0.0054 Maximum reactivity 0.920 0.938 Maximum k, Analytical Method Bias-corrected k_
(954/954)
CASMO-2E 0.9117 i 0.0018 0.9135 27-gap AMPX-KENO 0.9011 i 0.0075 0.9086 1
I'23-gap AMPX-KENO 0.9059 i 0.0071 0.9130 Diffusion-blackness 0.9078 0.9078 Theory
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4 Table 4.2 t
REACTIVITY EFFECTS OF ABNORMAL AND ACCIDElff CONDITIONS i
Accident / Abnormal Conditions Reactivity Effect i
Temperature increase Wegative in Region 1 Positive in Region 2 Void (boiling)
Negative in both regions Assembly dropped on top of rack Wegligible j
Lateral rack module movement Weg11gible Misplacement of a fuel assembly Positive l
- Double contingency principle of ANSI N16.1-1975, as specified in the April 14, 1978 NRC letter (Section 1.2) and implied in the proposed revision (draft) to Reg. Guide 1.13 (Sec. 1.4, Appendit A).
I i
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i Table 4.7 EFFECT OF TEMPERATURE AND VOID ON CALCULATED REACTIVITY OF STORAGE RACK Case Incremental Reactivity Change, Ak Region 1 Region 2 0*C Reference 20*C
-0.0028
-0.0114 40*C
-0.0074
-0.0069 65'C Reference 80*C
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~ ANALYSIS STEPS I 1. DEVELOP DYNAMIC M DEL II. -WRITE EQUATION OF MOTION INCLUDING INERTI L COUPLING EFFECTS 111. SOLVE EQUATION OF MOTION IV. COMPUTE THE STRESS FIELD
s COMPUTER CODE DYNAHIS ... A Three dimensional non-linear l Time History Program with mass coupling effects...
o a J2SEPH CAT C2CPC~'ATIOA; y c-ruce r$c.wara: 4 suacaron: nsetrea ronta coueosa urs MODEL OUTLINE (i) SIx D.O.F. RACK PLUS 2 D.O.F. FUEL ASSEMBLY ASSEMBLAGE. (II) ALL FUEL ASSEMBLIES VIBRATE IN UNISON. (III) RACK LEGS MAY LIFT OFF THE BASE OR SLIDE. (Iv) FLUID COUPLING BETWEEN FUEL ASSEMBLAGE & CELL; RACK TO RACK INCLUDED. (v) POTENTIAL' IMPACTS MODELLED BY COMPRESSION ONLY SPRINGS. (vi) FLUID DAMPING NEGLECTED. (VII) FORM DRAG BETWEEN EUEL ASSEMBLY & CELL RELATIVE MOTION NEGLECTED. j (Ix) RACK MOTION FORM DRAG NEGLECTED. (X) EFFECT OF NON-LINEAR COUPLING NEGLECTED - VERY CONSERVATIVE. 1
M.(BODY 1) FLUID COUPLING 1 / 2 (soDy 2) ( M (My + Myy) M - f'12 E2=Fy y 21 1 + (M2 I'22) Y
- F2
~ -M 2 WHERE Mjj VIRTUAL MASS,B0DY d = Mjj COUPLANT MASS (i Y 3) = Mjj = FUNCTION OF THE' SHAPE OF BODIES, INTER-BODY GAP R.J. FRITZ, "THE EFFECT OF LIQUIDS ON THE DYNAMIC MOTIONS OF IMMERSED SOLIDS", (1972) SOLER AND SINGH, " DYNAMIC COUPLING IN A CLOSELY SPACED TWO-BODY SYSTEM VIBRATING IN A LIQUID MEDIUM: THE CASE OF FUEL RACKS" (1981) 9
Coupling Elements 2 l -- 7 i i i 4-qs /, 2, l 47 .l l bs'l H I Ay = = h I i S3 [p S4 l p l' 44lB-1,' X B vbr N= y - - 42 AX i rhr / 1 1 45 e [i Support h S1 ._1. X ,[ XB, YB - Location of fuel rod q, group mass centroid - relative to centerline of fuel rack ClGURE C.2.1 Dynamic Model (-:
cr i a Typ. Top impact Element v~ m I i W M Rack-Structure Typ. Bottom impact Element w a e av mr l i l i FIGURE 6.2.2 Gap Elements To Simulate Inter-rack Impacts ('.
s' y impact Springs l i e n ~ M~ Mass -=:-; y* my ~ +.. 1 i l \\ / \\ Fluid 4 Dampers (not used in this analysis) Rigid Frame l 1 =X FIGURE 6.2.3 Impact Springs And Fluid Dampers (-4: .-,u
Ky 2 L K, / K w lM 2 HM ~ g 2 iLGap Elements To Simulate inter-Rack Impacts -(4 for 2-D Motion Rack Centroid 16 for 3-D Motion) (Assumed At H/2) ( H [ Rigid Rack l Baseplate U { K K h g g K. ^ f K K o r:w R,w f f FIGURE 6.3.1 Spring Mass Simulation For Two-DimensionalMotion y
o J35EPH CAT CSRPC2ATEN C =f.* l A. I h "**% t l *b i f af R :610*S p,., cts f 5 pop f A COWO4f A75 COMPARIS0N 8 DOF VS, 32 DOF MAX DISP AT'IOP X DIR Y'DIR 32 D0F 2.71" 2.213" 8 DOF 2.79" 2.27" hx "R" FACTOR R = ACTUAL ALLOWABLE 32 DOF .279 8 DOF .280 ) LOAD CASE 10 x 11 RACK C0F =.2 NO IMPACTS WITH ADJACENT RACKS BUILT INTO MODELJ H.E. QUAKE 37.5% OF FULL ASSUMED RATTLING AT TOP 0F RACK IN 8 DOC MODEL.
T;ble 6.8.1
SUMMARY
OF RESULTS RACK TYPE 6x11 Impact Loads (1b) Between Load Factors Ri for Rack Base * ) Rack / Storace Between and for Supports i run Rack Cell / Fuel Rack to Remarks Impact Assembly Rack R 1 R2 R 3 Rg R5 Rs .091 .114 .185 .126 .25R .291 l "a91 Hosari quike Yes 1.360x1g*5
- 0. 565x1g,5 j
COF = .8, full 1.75x10 5.30x10 .198 .233- .640 .342 .R44 .962 a 5 5 con 2 Hosari quake Yes 0.991x10 0.619x10 .053 .023 .092 .064 .146 .164 COP = .2, full .092 .033* .094 .ORO .184 .199 non3 Hosari quake Yes 1.66x10" 3.77x10" .084 .035 .173 .110 .212 .238 COF = .2, 11 cells .146 .052 .143 .124 .271 .293 (simulates near 2 empty rack) ) non4 Hoscri quake Yes 2.300x10" 3.950x10" .057 .059- .064 .076 .212 .239 COF = .8, 11 cells ,343 ,353- .415 .244 .705 .800 i (simulates near I empty rack) / Upper set of values in each column are load factors for rack base f(1.0 allowable) lower set of values are similar maximum load factors for support feet (2.0 allowable). (The upper part nC the nupport feet have the more critical load levels the lower support feet locations have i much lower load factors which meet the required 1.67 HE level limit with significant margin.) Al l owa bl a impact value with a factor of safety of 2 over the load.which would initiate plastic { action.
s i Table 6.6.1 RACE MATEFIAL DATA Young's Yield Ultimate Modulus Strength Strength ~ E (psi) 5, (psi) S, (psi) Property Value ,27.S.x,10,6 .23150 6810,0 Section III Table Table Table Reference I-6.0 1-2.2 1-3.2 Table 6.6.2 SUFFORT MATERIAL DATA j Young's Yield Ultimate Material Modulus Strength Strength 1 ASTM 479-521800 27.9 x 106 44,900 psi 94,350 psi (top part of support) 2 SA564-630 (hardened 27.9 x 106 101.040 poi 145,000 psi at 1075'F) (bottom part of support) Section III Reference 1-6.0 I-2.2 I-3.1 h! l I )
o J35EPH OAT CORPORATION CnfV Co.I%:%Etnb$9nrn.:A10RL kvCLt is 90.'i A cow *ONEk'15 s. COMPARIS0N 8 DOF vS. 32 DOF MAX. DISP AT TOP ~ X DIR Y DIR 32 DOF 2.71" 2.213" 8 DOF 2.79" 2.27" FIAx "R" FACTOR R = ACTUAL ALLOWABLE 32 D0F .279 8 DOF .280 LOAD CASE 10 x 11 RACK C0F =.2 NO IMPACTS WITH ADJACENT RACKS DUILT INTO MODEL; H.E. QUAKE 37.5% OF FULL ASSUMED RATTLING AT TOP 0F RACK IN 8 DOF MODEL.
4 Tabic 6.E.1
SUMMARY
OF RESULTS RACK TYPE 6x11 4 l Impact Loads (1b) a Between Load Factors R[ for Rack Base
- i Rack /
Storage Between and for Supports i t'u n Rack Cell / Fuel Rack to I Ma. Remarks Impact Assembly Rack Rg R2 'R 3 Rg' R 5 R6 I 5 .091 .114 ..185 .126 .258 .291
- 5. 30x10g**
1.7Bx10(5 ca91 Honori quake Yes 1.360x1 0.565x1 I COF = .R, full .198 .233 .640 .342 .R44 .962 i i 5 5 an02 Hoscri quake Yes 0.991x10 0.619x10 .053 .023 .092 .064 .146 .164 COF = .2, full .092 .033 .094 .080 .1R4 .199 i can3 Hoscri quake Yes 1.66x10" 3.77x10" .084 .035 .173 .110 .212 .238 COF =. 2, 11 cells .146 .052 .143 .124 .271 .293 ) (simulates near j empty rack) j con 4 Hosari quake Yes 2.300x10" 3.950x10" .057 .059 .064 .076 .212 .239 ) COF = .8, 11 cells .143 .151 '415 .244 .705 .800 (simulates near j, empty rack) \\ I i ~ Upper net of values in each column are load factors for rack base,(1.0 allowable) lower set of valuas are similar maximum load factors for support fee t (2.0 allowable). (The upper part of the nupport feet have the more critical load levels the lower support feet locations have much lower load factors which meet the required 1.67 HE level limit with significant margin.) l Allowabla impact value with a factor of safety of 2 over the load which would initiate plastic 4 j action. /
s Table 6.6.1 RACK MATEFIAL DATA Young's Yield Ultimate ~ Modulus Strength Strength E (psi) S, (psi) S, (psi) Property 6' 2315'O 68100 .Value 27.3 z.10 Section III Table Table Table Reference 1-6.0 1-2.2 1-3.2 Table 6.6.2 SUPPORT MATERIAL DATA Young's Yield Ultimate Material Modulus Strength Strength 1 ASTM 479-521800 27.9 x 106 44,900 psi 94.350 psi (top part of support) 2 SA564-630 (hardened 27.9 x 106 101.040 poi 145,000 psi at 1075'F) ~ (bottom part of support) Section III Reference 1-6.0 1-2.2 1-3.1 f b
i l a Table 6.8.1 (continued) RACK TYPE 6x11-
SUMMARY
OF RESULTS t Impact Loads (Ib) t for Rack Base
- Between Load Factors Rt Rack /
Storage Between and for Supports l Pun Rack Cell / Fuel Raqk to l Ho. Remarks Impact Assembly Rack Rt R2 R3 R s. R5 Rs aa05 Hongri quake Yes 6.0x10" 5.210x10" .069 .097 .167 .087 .243 .273 COF =.8 .163 .229,.524 .629 .876 1.00 half full in po'titive Y half e o= i i e 4 / 3 1 l j i l i
Tcblo 6.8.2 i
SUMMARY
OF RESULTS RACK TYPE 10x11 Impact Loads (Ib) l Between Load Factors Rt for Rack' Base
- Rack /
Storage Between and for Supports Pun Rack Cell / Fuel Rack to j Ho. Remarks Impact Assembly Rack Rt R 2-R3 R4 R3 R6 i l aa001 Hosarl EO Yes 2.494x10 ,7g4,g .119 .092 .146 .136 .232 .263 5 5 l 5 COF =.R 8.830x10 ** 1.75x10 ** Full fuel .262 .277 .659 6R7 1.30 1.4R j load aann2 Hosari EO Yes 2.426x10 5 6.770x10" .053 .022 .072 .057 .14R .164 l COF =.2 Full fuel .140 .051 .141 .112 .300 .327 i load 5 acorn 10 Hosqri EO Yes 2.497x10 7.630x10" .122 .156 - .231 .134 .323 .364 ) k CO .342 .389,1.07 .731 1.47 1.66 Full fuel load 5 acorn 12 Hongri EO Yes 2.127x10 2.737x10" .051 .023 .081 .065 .147 .164 I .149 .051 .141 .120 .314 .343 OF =. 2 max. movement l Full fuel 2.79 in. i-load toward wall i b 4 ) Upper set of values in each row are load factors for rack base (1.0 allowable); lower set of i values are similar maximum load factors for support feet (2.0 allowable). (Tha upper part of I the nupport feet have the more critical load levelst the lower Mupport feet locations have much lower load factors which meet the limiting HE load factor of.1.67 with significant margin.) f
- Allowable impact value with a factor of safety of 2 over the load which would initiate plastic action.
l
~ 1 Table 6.8.2 (continued) 2
SUMMARY
OF RESULTS RACK TYPE 10x11 a s Impact Loads (Ib) Between Load Factors Rt for Rack Base
- Rack /
Storage Between and for Supports Run Rack Cell / Fuel Rack.to No. Remarks Impact Assembly Rack Rt R2 R3 Rt R5 Rs ) aa003 interior rack Yes 2.36x10" 4.6x10" .037 .055 .093 .052 .151 .172 COF =.8 .171 .184 .484 .503 .766 .870 an004 interior rack Yes 2.317x10" 4.6x10' .063 .023- .170 .111 .210 .235 !5 ???;ei',fu11) 222 Daa iva 143 492 saa ,1 4 l Floor Loading 5 Rack A = Sum of 4 feet (max. value) 6.77 x 10 j Maximum value of 1 foot 1.89 x 10 5 (interior rack) Rack E = Maximum value of 1 foot 1.68 x 10 5 (interior rack) r The maximum possible in-plane liner forces are C.8 times the maximum values for one foot. gg -l i I
ACCEPTANCE CRITERIA to N0 li TER-RACK IMPACT e KENEMATIC 1.5 AGAINST TILTING e STRESS LIMITS LINEAR TYPE STRUCTURE SRP DESIGNATION ASME DESIGNATION (i) D+L LEVEL A (ii) D+L+E LEVEL B (iii) D + L + To PRIMARY MEf8ERS + BENDING <2S y AND Su 1 (iv) D + L + To + E SAME AS AB0VE (v) D-+ L + To + E LEVEL D 2E
EudoSkrz l-f THERMAL-HYDRAULIC ANALYSIS TASKS: A. COMPUTE POOL WATER BULK TEMPERATURE dOMPUTE MAXIMUM LOCAL WATER TEMPERATURE B. C. COMPUTE MAXIMUM FUEL CLADDING TEMPERATURE Dsee. lop ( ole foronino ) Pith VN $.,g;9 AV O en etshen & w*'t[ $toggsis Y& Q go'ft 0% 9* O E < l e /
0 a n er a,,s ar m,
- i. v u,.' a n,
x,y,,.' ar y, t e e s*
- 7,'.
- i r e* p f'
to s' F 1 i (T;) g f O. 3 L MP * 'M' A'#**',rTg (t ) (2(T ) 2 _L -1 r i J =- ~ ', Ms (M,) ._.._Tt ~ o (M l ~ s j 0 L t-T (f2) 2 FIG.l: SCHEMATIC FLOW AND TEMPERATURE DATA FOR A HEAT EXCHANGE e / ~. l d e
3 C
- . (./ 9 6 vo #
POOL f W OL IE E ( COOLINGWATER NHRHEAT 47 95* F(Maxy EXCHANGER iI) N 4 I i i ? T f .y y } } __Z Z:: gh,I TO Hggy I I )I I ] SINK g w g fL y SECONDARY Cf;OLERf-COOLANT g t r ATIOSoy I I TO I b REACTOR CAVITY f N.C:- NORM ALLY -FROM REACTOR CAVITY j CLOSED FI G 5.1.1 IDEALIZED POOL' COOLING SYSTEM y l l I
s ASSUMPTIONS: - NO AfD FROM RHR HEAT EXCHANGEFkS MAXIMUM INVENTORY OF FUEL IN THE POOL - HEAT EXCHANGERS FOULED TO'THEIR DESIGN MAXIMUM t - NO LOSS THROUGH EVAPORATION IN YHE POOL e e / e i l l e
ft fr y rd P TI C N r ~ c.. tk.q.c c V fr./cr rc.<u f 90-f g, p.it f u e t. A rr EM
- c. t. i t.,
$-P. Vt M ( M A x of HFAn-C:w? t t r u c N A M TE) C-M s o) FY S Lt d A. PL AW D. Poou S usn Tov P CM - .nv n.r acue c w ec u.s. 1 l s/ ~ j t
Actual Outline Of Pool Actual Outline Of Assumed Added Rack Assembly Fuel Assemblies m S+Y l ++& / Rack Assembly \\ //// ) A / N
- . Idealized Outline idealized Outiine Of Pool Boundary Of Rack Assembly
/ t FIGURE 6./ f r.'c : li: t ' ion Of Rt c : As s e mt ly
l dt i C-0 -O 2 3 dr = nP Q3 e n: LINEAR IN TIME, (r-r) p: EXPONENTIAL IN TIME, Q2= HEAT REMOVED BY THE FUEL POOL CCOLERS { Q2=M t (T '-T ) 2 i or Q2=M t-S(t-T ) 1 l S: TEMPERATURE EFFECTIVENESS 7 I n ncs) y c, c w= W W Q. ",i s .,,. q,,,
- % e ( < - T)
I ,..g-----P"**** k F** - $ ! i. ' '.. f t ( L' j l
l 1 i Table 5.1 LIST OF CASES ANALYZED - No. of Total Time i Fuel to Transfer Assemblien Fuel Into Dacay Time Discharged, the Fool Before Transfer l Cane No. Condition N th, hra Baging, hra 1 76 fuel discharge
- 76 19 100
~ 2 Half core discharge ** 96 24 100 4 3 Full core
- 193 48 100 i
j discharge \\ Discharge in assumed to be into a pool containing fuel from 15 previoun dischargen of 76 annemblien each at 18-month intervale.
- Discharge in assumed to be into a pool containing fuel from 12 previous discharges
,I of 96 annemblien each at 24-month intervale. %l I l
s o d-Peak Value = 140 F At 36 Hours e O-m C-E w *. we i U S' i w Eo *. Em Case 1 4$- E E Number Of Assemblies = 76 xW. Time Of Discharge = 19 Hours Spent Fuel Pool Heat Exchanger 1 = m 0-E- T.000 io.0 2'0.0 3'0.0 40.0 5'0.0 6'0. 0 TIME (HOURS) FIGURE 5.1a Pool Bulk Temperature / I-27 - -.,. = - - - .,---c _--.,,,,,-.----,,,,n.,--,-,,.-,_._,-n----,,-.---- - - - - - - - - - - - - - ~
l 1 o 'E. Peak Value = 147.3 F At 40 Hours 1 l 9 E. I a. I w. i E .o tod wn. C# w Case 2 w cco $N ' Number Of Assemblies = 96 4.- Time Of Discharge 24 Hour So Spent Fuel Pool Heat Exchanger 1 W-w*2-N*- o 1.000 lb.0 2b.0 3b.0 db.0 5b.0 6b.0 TIME (HOURS) ) FIGURE 5.2a Pool Bulk Temperature /'
E. Peak Value = 174.3 F At 61 Hours E,. E.. E c.o. wo g!- case 3 l W e f. Number Of Assemblies 103 = < cv. m ** Time Of Discharge 48 Hours w E Spent Fuel Pool Heat Exchanger = 1 W. I Ho 3" E" .000 2'0.0 40.0 6'0. 0 B'0.0 1'00.0 1'20.0 TIME (HOURS) FIGURE 5.3a Pool Bulk Temperature; Full Core Discharge / 9
Table 5.2 MAXIMUM POOL BULK TEMPERATURE t. COINCIDENT TOTAL POWER Qg, ann COINCIDENT SPECIFIC POWER FOR THE HOTTEST ASSEMBLY CoinciWent Time to Time (After Coincident Transfer Maximum Initiation Specific Cane No. of Fuel into Pool Bulk of Fuel Power, q, Qgx10-6 No. Agnemblien Pool, hre Temp.*F Transfer),hre Btu /see Mta/ hour Noten
- =
~ l 76 19 140.0 36 55.339 21.8905 Normal condition
- 2 96 24 147.3 40 54.498 24.9604 Normal condition **
3 193 48 174.3 61 51.572 42.5824 Full core offlond* 1 l l l nischarge in annumed to be into a pool containing fuel from 15 previous discharren of 76 ansamblien each at 18-month intervals. 1 nincharge in annumed to be into a pool containing fuel from 12 previous dischargan of 96 naacmblien each at 24-month interents.
s Table 5.3 TIME (HRS) TO BOILING AND BOILING VAPORI2ATION RATE FROM THE INSTANT ALL COOLING IS LOST CONDITION 1 CONDITION 2 Loss of Cooling at Loss of Cooling at Maximum Maximum Power Discharge Pool Bulk Temperature Rate Case Time (Hrs) Vap. Rate Time (Hrs) Vap. Rate l No. Ib/hr Ib/hr 1 9 22145 10 22915 2 7' 25329 8 26216 3 2.5 43676 2.75 44905 5-9
T .N Table 5.4 MAXIMUM LOCAL POOL WATER TEMPERATURE AND LOCAL FUEL CLADDING TEMPERATURE AT INSTANT OF MAXIMUM POOL BULK TEMPERATURE Maximum Coincident Case Maximum Local Pool Cladding 'F Case Identified No. Water Temperature, F Temperature, 1 188.0 225.0 76 assemblies 2 194.0 230.5 96 assemblies 3 219'.5 254.3 193 assemblies / 9 ) ,,-m -y-,_.-_,,e,._, c. ,,,__y_#
T l d p A l l Table 5.5 i POOL AND MAXIMUM CLADDING TEMPERATURE AT THE INSTANT FUEL ASSEMBLY TRANSFER BEGINS j 1 CoinckdentPool Cladding Temperature, *F Case No. Temperature, 'F Bulk Local -l 1 202.0 109.2 160.5 2 200.5 107.9 159.1 3 191.9 99.2 150.4 e ? ,---,------__4
EnetoureE MAKE-UP WATER SOURCES TO SPENT FUEL POOL
- 1) Condensate Storage Tank (178,000 gal.)
~200 gpm
- 2) Fire Water Tank (300,000 gal. )
>250 gpm - 3) Fire Water Transfer Tank (150,000 gal. ) ~200 gpm s s ,' b *
- b.4*
v. 9 t__9 r p 1 E l = 'A 4- . m.. .4 4.' +y
- ,
- f,*,N*
i i l Maximum Boiloff Rate 2"90 gpm. Path (1) is Design Class I. Path (2) is Seismic Design Class I, with Class I hosereels nearby. Path (3) Tank is Desigr. Class I, part of piping is Design Class II. Raw Water Peservoir is available for additional capacity.
.--,--,----------,,-,,---,----,,,,----e-,
l N4' 1 EL 65' A l 4 f_ f-EL 100 50A' I / / EL 85' K f m i EL SST unit 2 T 147' DI A N uwiri 60' EL l EL m 90' 90' - EL 85, il 8' 89' L89 TURBINE BU LDlNG o 746 i NOTE : ALL ELEVATIONS l s ARE AT TOP OF M AT. BUILDINGS: A I I CONTAINMENTS PACi FI C OCEAN 4 l l AuxlLIARY c I I TURSINE. o' w i F { i l t
t T U t 'O' 32'0" M& KEY PLAN = cow 7AtHMENT STguct' ($Q \\ y-Q~f e \\ d .. :.p;.. n _ / g
- ~
- e
,y*o 4 O ~
- , t
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j g . (.-
- ,C S
4 9 EL. IIS '0" \\ j , ~. ,g i ^ :.0 ' s 1, Cf e ',' l ?.re
- b..
e ce 4.7, O,, N Q PL AN - FUE L P O O L. 6 ..-,-,v
T n ..e< 'w-t 7 to-12 - b,*h k $*i,, $,* h,, a e e
- 1 EL. /40 0 l
(...
- -=.-==.--.-.--.---m i
-.,., g F c 'd . e.'.,=; 'e9. b Q 6, __g A e? a e. O'
- ., a
- /.' '.
- [ "e,.* ' i
- }
,e ' M,M*,$ p ~ >r~ e r;.',. v
- 9, 6
g e :s e VW y ) pg ;,7 ' W u'Yl" U/nV/rygr-SEC TION 8 \\c:/
r 't I 25'O'
- to ' o " s i
i i i l M j 2l /w i / M. TRa sitW ML A N a ) Pt.)-(SS)TYM y j' MMIMING TWACY, \\ l 3,y,a i~ waw as>vum(p-.. a- - d, - A__---#y/,4/5fA ) ( ...a Lt. s i u \\ {,=
==xe yza.=caravy p.s 1A _., '$33 fllM t 3A. w7. is,sq es u a ar.._ _ _ _ _ _ _, ' _ _ _ _ _ _ $6 TWOS 4,L6. L lI D CA4 SON 7tEl. E Ib:z I .:rs BEC 7/ON gn-ny =-,y w wai.o u su ) n.rsxjxte'o' DETAIL O w TYR DETAllS OF FUEL POOL UNERS
i SIGNIFICANT DESIGN FEATURES POOL STRUCTURE IS SUPPORTED ON BED ROCK FOUNDATION SLAB 5' THICK WALLS, IN GENERAL, 6' THICK STAINLESS STEEL LINER IS PROVIDED FOR LEAKTHIGHTNESS EACH WELD SEAM IS PROVIDED WITH A LEAK CHASE. ALL LEAK CHASE LEAD TO A COLLECTION POINT. I e ,n..
r I DESIGN INFORMATION LOADS AND LOAD C0fSINATIONS FSAR SECTION 3.8.2.3 ACCEPTANCE CRITERIA FSAR SECTION 3.8.2.5 DESIGN AND ANALYSIS PROCEDURE FSAR SECTION 3. 8. 2. 11 e
l ( e f SEISMIC ANALYSIS
b ij 1 I j LEGEND: j I 2 - NODE NUMBER ll @ - ELEMENT NUMBER f - ROTATIONAL DEGREE OF FREEDOM -TRANSLATIONAL DEGREE OF FREEDOM / J t $ -MASS POINT i. @E W4 ~ i f i t.4' 05.8* S1.5' i i h ? M i 15.% J 3 / 9( ) k EL.163* 1 p h 34.{, j p D L 2m 2 l EL 140* RfGID / 2 LINK TYP. RIGID LINK TYP. 3 d I TORSIONAL / E' EL.115' h > 2 3' SOIL SPRING' d g 4 4s p Y f EL 10 _-OJ TRANS - ,y LATIONAL / g SOf L SPRING n s ./ 4 s 17.7'. a" sL.e5 g,=me =,OTe N t Org. _ ' VERTICAL MODEL E-W MODEL N-S MODEL (HOSGRI ONLY )
s 90!TACHUO1 TUDNT!W 3PUT3Unt2 3R!Tv3 p ;330, o.E DHIOJIUS YMAIJIXUR I _y i, aTi l 4 l 1 i l \\ I l l t' I i .CH 32 A.' JMPJ9 t> . e i>,t, e'. 3 i s.s i h, i 3.gn gity n i l l l l j l l 1 I I a 1
's bbbbbb b .o. j g i f-m g ,.dums. l 4 g;tyyr,"T H, [5 '.) -'f ig ' E ' g @R. 171 . e jf.( "}.. m t _. = 3 ftFLOfR (' 00NCRt Q S.E 'l r,. 4W) a @g G) O '.' b Jtacoon R-51, l e m 51 -O i
- n I g i,
stTwstN UpstTS FI6unt 2.1.t*I0 StASLO CANT 001 P08ttR PLANT neitT l AUXILIARY BUILDING FLOOR PLAN AT EL 600'.0" 10/1893
.+ Scro Setts i a a tsat Isentt te0Lt 3.813 AOtttl4ST 00ftelet SLAGS $10f1$ Stile 5III 10-Ptest LOAg$ (IE) sheer (cl. ness.t{dl. tte t-ft tievetten. sa tten 'H 'I I stress ft gester emetod e-1tw *I ^ tagetitv *I Getje I I les 1-e 170 4.390 3.698 N.108 310.0 100 1-6 $10 4.900 13.005 65.000 5.8 let 7-e 930 5.900 10.105 100.000 6.0 100 7-t 290 1.038 1.148 13.300 6.3 100 2-t 20 300 let 1.790 >10.0 115 3 170 3.730 29.000 08.500 3.5 115 F.e 110 1.700 18.300 239.000 310.0 115 2-4 400 1.t M 0.090 16.000 F.0 111 3-e 400 2.330 3.100 14.900 4.7 115 3-6 DN 2.500 3.300 40.908 3.0 115 4 3.940 15.500 117.000 1.170.000 3.9 140 1 1.170 3.070 9.200 30.000 3.5 tot 7-e 1.170 0.010 7.303 P40.000 6.0 let F-t 900 4.150 7.750 43.100 4.6 tot 3.e 44 030 3.290 13.000 1.0 840 36 970 3.C10 11.300 90.700 3.1 tot 4 5.710 14.900 157.000 1.150.000 2.0 (a) Sheer tapettty is cetteleted for the settlee subjected te deuend sement and estal forte. (b) nement teoetity is talte14ted for the settlen setjected to demand estal force. (t) Sheer resorttles and demends are rounded to the nearest le tips or 3 signifteent dittts. (d) neurat teostttles and demeads are rounded to the meerest 50 f t-tips or 3 signtf tteet Olgtts. (e) Settlen 1stetten is theim en flgeres 3.0-60 through 3.0-62. (f) Stress rette. E M 3 for sheer er moment,whichever ts smelter, temead (gt Cemeeneet to entt 2 ts steller. 6 n. I e
F N e ss SCPP UnllS 16 2 ISAR UPSAtt 1AtLi 3.0-16 AURILI Asi tu1L9tnG C0steg edALLS Sletss eAll05 (ut) tasil Shear, pil moment 10! t.f t II". fanaettu(b) temaq tanaette(t) Stress batte Latattaa ft sammad On 11ae n (11.1 20.3) _100 400 483 176 404 1.7 660 630 270 642 1.2 On Inne J (11.116.1)IIIC 90 100 107 113 1.3 OS e?O 500 14) 113 1.3 On Itne 1 (6.415.1)I'I 100 190 110 438 the 1.6 OS 230 320 493 979 5.4 > line 1 (16.019.2) 100(8) 150 360 42 160 2.3 I en Itne 0.5 (10.312.9h'Il00 'I 130 190 to 191 1.5 en Itne V (15.1 20.3) too 1 40 200 to est 1.4 05 ble 470 102 405 l.11 I8I D 11ae V (6.4 11.1)III 100 220 640 291 900 1.1 On itse 6.4 (V.$)I8I 100 140 460 101 434 f.7 05 390 450 63 04 1.15 en line 10.3 (1.V)I'I 1003 330 400 220 339 1.4 I83 en line 12.9 (1.V)III 100 270 460 199 324 1.6 en Itne 11,1 (N.1,6)(t) 100 130 120 664 1494 " i.8 SS 320 450 S$9 1426 3.4 On Itne 15.1 (0.V)(t) 100 140 480 19 Se 1.4 el 160 300 30.6 32.6 l.01 (4) $ tress tatte e for theer er aument, tetthever 13 ses11er (6) Astal gemend ef fect is lettooed to the tapetitles. (t) Counterpart in mit 2 ts tieller. (0) taalt Sees not estead Delow elevatten 100 ft
f., t OTHER LOADS CONSIDERED HYDROSTATIC OUT OF PLANE SEISMIC DUE TO POOL WATER SELF WEIGHT SEISMIC THERMAL EFFECT l i l
I.. f t LINER DESIGN LINER DETAILS ARE SIMILAR TO OTHER PLANTS LICENSED TEMPERATURE EFFECT ON LINER IS EVALUATED. IT MEETS THE ACCEPTANCE CRITERIA 0F ASME SEC Ill DIVISION 2. l l 4
f J. " ~% UNITED STATES .e o } B I NUCLEAR REGULATORY COMMISSION WASHI AGTON, D.C. 20555 O, . January 8.1986 DOCKET NO(S).50-275 and 50-323 Mr. James D. Shiffer Vice President of Nuclear Power Generation Pacific Gas and Electric Company 77 Beale Street - Room 1451 San Francisco, California 94106
SUBJECT:
DIABLO CANYON NUCLEAR POWER PLANT UNITS 1 AND 2 /V /C t' o - hwi Wh% C&Y^ The following documents concerning our review of the subject facility are transmitted for your information. O Notice of Receipt of Application, dated O Draf t/ Final Environmental Statment, dated O Notice of Availability of Draft / Final Environmental Statement, dated O Safety Evaluation Report, or Supplement No. , dated O Notice of Hearing on Application for Construction Permit, dated O Notice of Consideration of issuance of Facility Operating License, dated C Monthly Notice; Applications and Amendments to Operating Licenses involving no Significant Hazards Considerations, dated O Application and Safety Analysis Report, Volume O Amendment No. to Application /SAR dated O Construction Permit No. CPPR- , Amendment No. dated O Facility Operating License No. , Amendment No. , dated O Order Extending Construction Completion Date, dated 00 Other (Speci/y)_ Dated January 6,1986 RE: Spent Fuel Storage Reracking. Division of PWR Licensi g-A Office of Nuclear Reactor Re ulation
Enclosures:
As stated cc: /Q' o
d J Mr. J. D. Shiffer Pacific Gas and Electric Company Diablo Canyon CC* Philip A. Crane, Jr., Esq. Resident Inspector /Diablo Canyon NPS Pacific Gas & Electric Company c/o US Nuclear Regulatory Commission Post Office Box 7442 P. O. Box 369 San Francisco, California 94120 Avila Beach, California 93424 Mr. Malcolm H. Furbush Ms. Raye Fleming Vice President - General Counsel 1920 Mattie Road Pacific Gas & Electric Company Shell Beach, California 93440 Post Office Box 7442 San Francisco, California 94120 Joel Reynolds. Esq. John R. Phillips Esq. Janice E. Kerr, Esq. Center for Law in the Public Interest California Public Utilities Commission 10951 West Pico Boulevard 350 McAllister Street Third Floor San Francisco, California 94102 Los Angeles, California 90064 Mr. Frederick Eissler, President Mr. Dick Blankenburg Scenic Shoreline Preservation Editor & Co-Publisher Conference, Inc. South County Publishing Company 4623 More Mesa Drive P. O. Box 460 Santa Earbara, California 93105 Arroyo Grande, California 93470 Ms. Elizabeth Apfelberg Bruce Norton, Esq. 1415 Cozadero Norton, Burke, Berry & French, P.C. San Luis Obispo, California 93401 202 E. Osborn Road P. O. Box 10569 Mr. Gordon A. Silver Phoenix, Arizona 85064 Ms. Sandra A. Silver 1760 Alisal Street Mr. W. C. Gangloff San Luis Obispo, California 93401 Westinghouse Electric Corporation P. O. Box 355 Harry M. Willis, Esq. Pittsburgh, Pennsylvania 15230 Seymour & Willis 601 California Street,' Suite 2100 David F. Fleischaker, Esq. San Francisco, California 94108 P. O. Box 1178 Oklahoma City, Oklahoma 73101 Mr. Richard Hubbard MHB Technical Associates Suite K 1725 Hamilton Avenue San Jose, California 95125 Mr. John Marrs, Managing Editor San Luis Obispo County Teleoram Tribune 1321 Johnson Avenue P. O. Box 112 San Luis Obispo, California 93406 i l
Pacific Gas & Electric Company Diablo Canyon cc: Arthur C. Gehr Esq. Mr. Thomas Devine Snell & Wilmer Government Accountability 3100 Valley Center Pro.iect Phoenix, Arizona 85073 Institute for Policy Studies 1901 Oue Street, NW Mr. Leland M. Gustafson, Manager Washington, DC 20009 Federal Relations Pacific Gas & Electric Cmnpany 1726 M Street, N.W. Suite 1100 Washington, DC 20036-4502 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Michael J. Strumwasser, Esq. Special Counsel to the Attorney General State of California 3580 Wilshire Boulevard, Suite 800 Los Angeles, California 90010 Mr. Tom Harris Sacramento Bee 21st and 0 Streets Sacramento, California 95814 Mr. H. Daniel Nix California Energy Commission 1516 9th Street, MS 18 Sacramento, California, 95814 Lewis Shollenberger, Esq. US Nuclear Regulatory Commission Region V 1450 Maria Lane Suite 210 Walnut Creek, California 94596 )
J l Pacific Gas & Electric Company Diablo Can. von
- cc:
Chairman San Luis Obispo County Board of Supervisors Room 220 County Courthouse Annex San Luis Obispo, California 93401 Director Energy Facilities Siting Division Energy Resources Conservation and Development Comission 1516 9th Street Sacramento, California 95814 President California Public Utilities Commission California State Building 350 McA11 ester Street San Francisco, California 94102 Mr. Joseph 0. Ward, Chief Radiological Health Branch 4 State Department of Health t Services 714 P Street Office Building #8 Sacramento, California 95814 i 1 - -,,~.,...-,-_-,-.}}