ML17083B727
| ML17083B727 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/11/1986 |
| From: | Rinaldi F Office of Nuclear Reactor Regulation |
| To: | Ballard R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16342C169 | List: |
| References | |
| NUDOCS 8604180375 | |
| Download: ML17083B727 (34) | |
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UNITEDSTATES NUCLEAR REGULATORY COMNllSSION WASHINGTON, D. C. 20555 APR 11586 MEMORANDUM FOP:
IIonald L. Ballard, Chief Enqineerinq
- Branch, PWP.-A THRU:
FROM:
David C. Jeng, Section Leader Structural and Civil Enqineering Section Engineering
- Branch, PWR-A Frank Rinaldi, Structural Enofneer Engineering
- Branch, PWR-A
SUBJECT:
AUDIT OF JOSEPH OAT FUEL RACKS FOR DIABLO CANYON NPP On March ?4 and 25, 1986, I have audited with the support of our consultarrts at Franklin Research Center the computations performed by Joseph Oat Corporation for the re-racking of the spent fuel pool for the PGAE Diablo Canyon plants.
Also, I visited the fabrication plant to observe the construction process for the fuel racks.
Enclosure I identifies the oersnns present during the audit and plant visit.
The documents audited include formulations for seismic/structural evaluation of the fuel racks, user manuals for computer programs and numerical results that demonstrate the adequacy of the racks in complyina with the requirements of nationally recognized desiqn codes and staff technical positions.
Enclosure 2 identifies the material reviewed during the audit.
The fuel racks have been designed to meet the desiqn conditions outlined in the applicant report and follow the requirement of ASME (Section NFl design code and the staff requirements nutlined in the OT Position and SRP 3.8.4, Appendix D.
The seismic loads considered in the design consist of the design basis earthquake, the safe shut-down earthquake (double the values of the design basis earthquake) and the Hosori earthquake.
Other loads considered include dead loads, live loads, and thermal effects.
The results are presented in terms o< stress ratios (R) of actual stress over allowable stress.
There are six stress ratios cateqories, as follnws R>
= Ratio of direct tensile or compressive stress on a net section to its allowable value R>
Ratio of gross shear on a net section to its allowable value R3
= Ratio of maximum bending stress due to bending about the x-axis to its allowable value for the section R
Ratio nf maximum bending stress due tn bendinq about the v-axix to its allowable value CONTACT:
F. Rinaldi X24708
1L r j$('
APR 11 lggg Ronald L. Sallard R5
= Combined flexure and compressive factor R6 Combined flexure and tension (or compression) factor" The results were reviewed to determine that they meet the acceptance requirements of less than one for normal condition and less than two for severe accident conditions.
The results were found to meet the acceptance requirements.
However, they were slightly lower than reported in the report submitted to the staff.
This condftfon is considered acceptable, because it indicates additional margin of safety incorporated in the design.
This condition results frnm the combined change in the area of the four supports for the rack assemblies and from the reduction of the material allowable stress.
The fuel rack supports were enlarged to provide a diameter of 9.inches.
The material stress aHowables were reduced to 23,150 psi to account for the reduction factor related to the postulated temperature effects.
The results were validated by checking the change between the final and original results.
The change in size of supports would reduce the applicable stress level ratios while the reduction in the value of allowable stress would increase the applicable stress level ratios.
These conditions were verified by checking the results at specific locations in the fuel
- racks, and were found acceptable.
In addition the applicant considered at our request the localized stress level at the base of the fuel rack for one can compartment.
The results fndicated that the stress level is below the allowable stress value of the material and was considered acceptable to the staff.
The documents listed in Enclosure 2 are considered proprietary information by the fuel rack manufacturer.
However, they provided the staff with an index of the four reports applicable to PGKE's Diablo Canyon fuel racks (Items 3 through 6 in Enclosure 2).
These documents are attached to this report as Enclosures 3 and 4.
This information fs enclosed for future reference.
In conclusion, the staff and fts consultants found the documentation of the design of the fuel racks for Diablo Canyon NPP, performed hy Joseph Oat Corporation, acceptable.
The staff raised two concerns related to the slight varfatfon between the results provided in the original submittal and those included in the final computations of record.
However', the detailed verification nf the results indicated that the applicant and their
APR;; rv Ronald L. Ballard a 3 manufacturer have considered in their desiqn the actual supports provided for the racks, and the most applicable allowable material stress level, ider tified during previous meetings with the staff.
The staff acceptance rests on the verification of the adequacy of the desiqn assumptions, structural modelling methods of analvses, acceptance
- criteria, and resulting stress ratios.
Enclosures:
As stated Frank Rinaldi, Structural Engineer Structural and Civil Engineering Section Engineering Branch Division of PWR Licensinq-A cc:
C. Rbssi S. Varga H. Scbierling D. geng C. Herrick, FRC A. OKaily, FRC F. Rinaldi DISTRIBUTION:
PAEB Reading Files PAEB Plant Files
FNCLASURE 1
Audit Oat Corp. 3/24/86 A 3/25/86 lame Frank Rinaldi Aly A. Okaily P.. Clyde Herrick Scott Johnson*
N. R. Tresler Charles
- 0. Coffer H. P. Singh Alan Soler*
Jay McGurren**
H. Schierlinq**
Not at 3/25/86 meeting
- Part time only P>ant Ins ection F. Rinaldi H. Schierling J. McGurren H. Tresler C. Coffer J. Hurphy J.
Reader R. Coquet S. Johnson Or anizatinn USNRC, Engineering Branch FRC, Engineering Department FRC, Engineering Department Bechtel, Diablo Canyon Project PGKE$
PGKE PE PGKE, Nuclear Regulatory Affairs Joseph Oat Corp.
(JOC), Engineering VP U. of PA, Consultant, JOC USNRC$
OELD USNRC, Project Manager 3/'25/86 NRC NPC NRC PGEE PGKE JOC JOC Rechtel Bechtel
ENCLOSURE 2
Documents Audited at
)ose h Oat Cor oration Information manual
+or Dynahis (Version for 8 Det Analysis STD-28)
Rev
~
3/1/86 A. I. Solar User's Manual for Joseph Oat Time History Analysis Problem "DYNAH:S" (32 D.O.F.)
Version FDYNA984. Fuel Rack (HP 3000)
Version FDYMAHIS (HP 9000)
Document ¹STD-P6 A. I. Soler October 1981 manual Revised Dec.
1985 3.
Seismic Analysis of High Penisty Fuel Racks for Pacific Gas E Electric Diablo Canyon Nuclear Pnwer Station, Oat lob J2473 PO QS-5679-AA4 and ZS-5679-AB4 by A. Solar TN Report ¹779 4.
Folder ¹1 PGIIE Rack Analyses Preliminary, Superceded, Test Puns, A. Solar 3/85 5.
Folder ¹2 PGIIE Final Analysis - Runs as Reported in Seismic Report November 11, 1985 Comparison of 800'F vs 3200'F 6.
Folder ¹3 PGINE Jan 1986 Additional Conv.
Rigid Rack Yodel Welding Effects Runs 7.
User Manual for Pre-Processor FGGLAST (for 32DOF DYNAHIS Model), Version FRAKNF10-HP3000; Version FRACKNF-9000> - Document No. 27, A. I. Snler, Rev. 1, Dec.
1985
~ ~
je ENCLOSURE 3
r INDEX FOR ITEM 3 OF ENCLOSURE 2
(6 PAGES)
TABLE OF CONTENTS PART I SECTION CONTENTS PAGE Introduction to Stress Calculations Axial Stress Torsional Stresses lateral Shear Stress Shear Deformation (Timoshenko Shear Correction)
Combined Stresses and Corner Displacements A.
Within Fuel Rack B.
Stresses Within Supporting Legs Lifting and Impact Safety Z-1.1 I-2.1 I-3.1 I-4.1 I-5.1 I-6. 1 I-6.2 I-6.5 I-7.1 APPENDIX 1:
TORSIONAL STRESS IN RECTANGULAR SECTIONS
~
APPENDIX 2:
SECTIONAL PROPERTIES OF RACK SAHPLE CALCULATION A.
Area B.
Homent of Inertia (for distributed area):
C.
Homent of Inertia for Lumped Area Hodel D.
First Static Homents REFERENCES
~ A1-1 A2-1 A2-1 A2-1 A2-4 A2-8 Sht 1 of 6
TABLE OF CONTENTS PART II SECTION 'ONTENTS PAGE 2
F 1 2.2 2.3 2 ~ 4 2.5 2.6 2.7 2.8 2.9 3.1.1 Introduction Analysis Outline Fuel Rack -'uel Assembly Hodel Outline of Hodel Hodel Description (8
DOF Hodel)
Development of Hodel Equations of Hotion Coupling Between Fuel Rack and Fuel Rod Group Coupling Between Fuel Rack being Hodelled and Adjacent Structures Fluid Hass Effects in Vertical Direction Calculation of Rack Inertia Properties Force and Homent Resultants at Rack Base Damping Detailed Remarks on Non-I inear Spring Rates and Coupling Coefficients Impact Elements between Rack and Rattling Fuel Assemblies II-1 II-1 II-4 II-6 II-16 II-17 II-20 II-21 II-24 II-25 Sht2of 6
TABLE OF CONTENTS PART II SECTION CONTENTS PAGE 3.1 '
3.1.3 3.2 3.3 3 ~ 4 3.5 4 ~
4.1 5.
5.2 5 '
5.3.1 5.3.2 6.
6.1 Fuel Rack Base Support Elements at z
= -h to Simulate Sliding of Supports Initial Deformation of Rack A Remark on Computation of Input Data Effective Rattling Hass for Dynamic Analysis Fluid Sloshing Within an Empty Rack Time Integration of the Equation of Hotion Time History Analysis Using 8
DOF Rack Hodel Design Criteria Structural Acceptance Criteria Haterial Properties Stress Limits for Various Conditions Normal and Upset Conditions (Level A or Level B)
Level D Service Limits Results Remarks II-36 II-39 II-40 II-41 II-41 II-43 II-46 II-46 II-47 II-47 II-49 II-50 II-5O II-52 II-53 II-53 Sht3of 6
TABLE OF CONTENTS PART II SECTION CONTENTS PAGE 6.2 6.3 6.4 6.4.1 6.4.2 6.5 6.6 6.7 Support Leg Properties Tabular Results for Hosgri Earthquake (HE) and for Design Earthquake (DE)
Impact Loadings Impact Loading Between Fuel Assembly and Cell Wall Impact Loading Between Ad)acent Racks Weld Stresses Local Buckling of Fuel Cell Walls Analysis of Welded 3oints in Rack due to Thermal Load II-55 II-57 II-64 II-64 II-66 II-7O I!-72 II-74 6.8 Definition of Terms Used in'art II II of the Seismic Report REFERENCES APPENDIX I:
PRELIHINARY COHPUTATIONS FOR DYNAHICS DATA FILES PG&E Preliminary Calculations for PREDYNA Check of Inertia Properties in FR1 Input Data for DYNAHIS II-75 II-77 Sht4of 6
TABLE OF CONTENTS PART II SECTION CONTENTS APPENDIX II:
OUTPUTS FROH DYNAHICS RUNS (UNCORRECTED) 10x11 df=dpge.acorn10 cof=.8, using v1.2.3 imp springs corner
'0x11 df=dpge.aa003,
- hosgri, cof=.8 empty rack 10x11 df=dpge.aa000, dmp=.001 cof=.2 empty rack 6x11 df=dpge.,
- ee01, cof =. 8 hosgri, full rack 10x11 df=dpge.,
- aa001, hosgri, cof=.8, ext.sp.
dmp=.001 10x11 df=dpge.aa002, dmp=.001 cof=.2, hosgri, extspr.
6x11 df=dpge.,
aaOO,hosgri, cof=.8, empty rack 6x11 df=dpge.aa05, hosgri cof=.8, half rack, pos y
6x11 df=dpge.ee00,
- hosgri, cof=.8, empty rack 6x11 df=dpge.ee05, hosgri dof =. 8, half rack, pos y
10x11 df=dpge.ac13aa1, cof=.8, corn 11, f.a. fluid damp.,
wall sp 10x11 df=dpge.ac33b, cof=.8 corner 110 f. a. fluid damp.,
obe Sht5of 6
t I
TABLE OF CONTENTS PART II SECTION CONTENTS APPENDIX II:
OUTPUTS FROM DYNAMICS RUNS (UNCORRECTED) 10x11 df=dpge.ac33aa cof=.8, corner 11 f.a. fluid damp.,
obe 10x11 df=dpge.ac13ab, cof=.2 corner 11 f.a. fluid damp.
10x11 df=dpge.ac33ab, cof=.2 corner 11, f. a. fluid damping, obe APPENDIX III: ANALYSIS OF THERMAL STRESSES IN A RACK CELL Sht6of 6
ENCLOSURE 4 INDEX FOR ITEMS 4, 5 AND 6 OF ENCLOSURE 2 (5
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