ML20043E806
| ML20043E806 | |
| Person / Time | |
|---|---|
| Issue date: | 06/08/1990 |
| From: | Roberts J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Massey J PACIFIC SIERRA NUCLEAR ASSOCIATES |
| References | |
| REF-PROJ-M-53 NUDOCS 9006130406 | |
| Download: ML20043E806 (4) | |
Text
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JUN 0 81990 Project No. M-53 Pacific Sierra Nuclear Associates ATTN: Dr. John V. Massey General Manager 5619 Scotts Valley Drive Scotts Valley, CA 95066
Dear Dr. Massey:
Nuclear Regulatory Commission (NRC) staff has uncovered an additional issue regarding the adequacy of shear reinforcement in the Ventilated Concrete Cask (VCC) for Pacific Sierra Nuclear Associates (PSN) topical report (TR).
The discussion of the shear reinforcement problem, the related references, and the suggested format for load combinations for critical sections are provided in the Enclosure.
It is expected that PSN will provide documentation of the resolution of concerns discussed in the Enclosure, if the documentation shows that the VCC design is deficient in shear reinforcement, PSN should add the necessary additional steel.
PSN should satisfactorily incorporate the requested further analyses and possible redesign in the TR docketed documentation.
Resolution of this matter is needed to allow the current review of Palisades ISFSI license application to be completed.
If you have any questions please call K. C. Leu at (301) 492-0696.
SI"#6"[glkl Signed by John P. Roberu Joh'n P. Roberts Irradiated fuel Section fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety L
Enclosure:
As stated Distribution:
Project M-53 PDR NRC File Center IMIF R/F IMSB R/F JRoberts FSturz JSchneider SRuffin KCleu FBrown DKasun, SG RGramman,5G JSpraul, NRR CJHaughney bec: JStokley, SAIC
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NAME :KCleu dc krown
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M-53 FDC
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i ENCLOSURE Project No. M-53
Subject:
Adequacy of VCC Shear Reinforcement
References:
a.
PSN TR on the VSC System for Irradiated Fuel, Rev 1.
b.
J.P. Roberts Memo, 20 April 1990, Project No. M-53 c.
NRC-PSN Meeting 3-4 May 1990.
d.
ACI 349-85, Code Requirements for Nuclear Safety Related Structures.
I.-
This issue addresses an additional concern of the NRC staff on the design and validation of the design of the PSN Ventilated Concrete Cask (VCC) of the VSC System, as presented in Reference a and additional docketed docu-mentation. submitted for the case by PSN.
The concern relates to the adequacy of the reinforcing steel of the VCC in satisfying Reference d, Chapter 11, requirements for shear reinforcement.
This is in addition to the concerns expressed (References b and c) regarding meeting Section 7.12, Minimum Reinforcement, of the Code.
2.
Reference a'and the additional docketed submittals do not adequately address shear stresses and capacities for the VCC.
Design calculations and combination of load expression analyses (e.g., Table 3.4-6) are not included for shear stresses and capacities.
No analyses regarding strengths, stresses, and shear reinforcement requirements (or evidence that such reinforcement is not needed) related to the ACI Code Chapter 11, Shear and Torsion, are provided.
The limited discussion of shear stresses, as at TR paragraph 3.4.3.1 l
does not satisfy the requirement.
Even that calculation, for example, does not compare the calculated stress with shear strength.
Allowable shear stress in that example would be.859 x2(4000)D 6 = 107 psi (per ACI Code, Formulas 11-1, 11-2, and 11-3), while the calculated stress is 200 psi.
i 3.
It is considered probable that shear reinforcement perpendicular to the l
faces of the VCC will be required either to provide the necessary shear strength or to satisfy minimum shear reinforcement requirements.
- Further, combination of load expression results should be provided to demonstrate the adequacy of sections of the VCC in shear.
A presentation in 'the TR (and in l
SARs) similar to the attached illustration is suggested.
Design analyses should be submitted in sufficient detail to provide an " audit trail" for the calculated stresses and capacities leading to the combination of load analyses.
Information not provided in such tables and the documentation supporting them must still eventually be developed in the course of the review prior to_ positive action on the application.
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GLOSSARY T
U = AVAILABLE STRENGTH, AFTER APPLICATION OF STRENGTH REDUCDON FACTOR.
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i D = DEAD LOAD. MAY INCLUDE FUEL STORAGE CASK AND CONTENT IN MON-DYNAMIC IDADING SITUATIONS. VARIED BY!
ESTIMATETO ACHIEVE WORST CASE DEAD LOAD.
L= LIVE LOAD. VARIED BETWEEN 0% TO 1005 OF ESTIMA'IE10 ACHEVE WORST CASE LIVE LOAD. INCLUDES MMtCES ASS "IRANSFER AND PIPING AND EQUIPMENT REACDONS WHICH OOCUR UNDER NORMAL AND OFF NORMAL CONDfnONS.
NUCLEAR MATERIAL PRESENT IS NOT OFCONCERN]
H = LATERAL SOB. PRESSURE. IF NO H "IMEN NO LOAD COMBINATION 3.
"T = THERMAL LOADS DUR94G OPERATION-DIRECTLY ON STRUCTURE BECAUSE OF RESTRAINT CONDITION AND REA SIRUCIURE fROM BQUIPDENT, PIPING, AND ENVBtONS FROM NORMAL AND OFF NORMAL CONDITIONS.
W= LOADS GENERATED BY NORMAL AND OFF NORMAL WINDS (PER ANSI 58.1). DOES NOT INCLUDE LOADS DUE TORN MISSILES.
i E = EARTHQUAKE LOADS, COhFARABLE 1D SAFE SHUIDOWN EARTHQUAKE OF PLANT FSAR.
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A = ACCIDENT IDADS. MCLUDES DROPS, IMPACTS, ODIER LOADS ONLY OCCURRMG IN
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T LOADS.
T, = THERMAL LOADS UNDER " ACCIDENT
- TEDWERATURE RISE CONDrDONS, INCLUDING THOSE RESULTING RtOM LOSS OF COOLING AIR FOR AN EXTENDED PEltlOD OF TIME, MAXIMUM ANTICFATED *ACCE)ENT* TEnWERATURE OR HEAT IDAD, AND T IDADS.
i W = LOADS GENERATED BY TORNADO OR RELATED INTERNAL MOMENTS AND MMtCES. INCLUDES LOADS DUE TO TORN g
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PRESSURE,TOItNADO CREATED DBTERENHAL PRESSURE, AND TORNADO OENERATED MISSR.ES.
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NOTES:
t 1.
LOAD COMBINATIONS ARE BASED ON ANSI 57.9. LOAD COMBINATION NO. 8 TREATS TORNADO d.OADS AS OTHER A
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AND DISTINGUISHES TORNADO RtOM
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2.
RETAIN 1ME LOAD COMSMATION-NUMBER CORRESPONDENG EVEN IF LOAD COMBINATIONS ARE OMTTIED. IDENH!
i BASIS FOR OMISSION OR "DE TEXT OR TABLE REFERENCE WEEltE SUCH OMISSION IS EXPLAMED.
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3.
CRTnCAL SECDONS ARE THOSE OF EACH STRUCTURE, SYSTEM, AND MA3Olt COMPONENT TIEltEOF IMPOItTANT TO SAFETY (10CRt7!
winch HAVE THE LOWEST MARGIN OF SARETY. SECDONS MAY BE DIFR3 TENT IUR MOST CItITICAL SIEAR AND MOIENT.
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4.
IDENHFY PRECEDING LOCATION (S) IN TR/SAR TEXT OR TABER(S) WHEltE DATA ARE DEltiVED, PERMITTING AN AUDTT BACK TO TIE DESIGN ANALYSIS IN DOCKETED DOCUMENTATION OF THE CRTTICAL SECHON VALUES AND VALIDATION THAT I MOSTCRTnCAL SECDONS.
i 5.
USE CONSISTENT UNTTS THROUGH THE TABLE AND EXPLAIN BASIS BY NOTE, e.g., PER 12" WIDE SECTION. PSI MAY BE USED IUR MOhENTS IF COMBINED FACTORED STRESSES (f0It " LOADS") AND ALIDWABLE STRESSES WITH APPItOPRIATE S j
FACTOR APPLIED (70It "CAPACTTY*) FOR BOTH STEEL AND CONC 3 TETE ARE PRESENTED AND IDENTIRED.
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