ML19211C028
| ML19211C028 | |
| Person / Time | |
|---|---|
| Issue date: | 06/26/1979 |
| From: | Bagchi G NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Hanauer S NRC - TMI-2 UNRESOLVED SAFETY ISSUES TASK FORCE |
| References | |
| REF-GTECI-A-40, REF-GTECI-SC, TASK-A-40, TASK-OR NUDOCS 8001090071 | |
| Download: ML19211C028 (14) | |
Text
'
UNITED STATES
/
pa mfCoq'o NUCLEAR REGULATORY COMMisslON
~
g WASHINGTON, D. C. 20555
=l 2
)
/
JUH 2 6 879 D,y MEMORANDUM FOR:
S. H. Hanauer, Director Unresolved Safety Issu'es Program FROM:
Goutam Bagchi, Chief Structural Engineering Research Branch THRU:
L. C. Shao, Assistant Director for General Reactor Safety Research y
SUBJECT:
TASK ACTION PLAN (TAP) A-40, SEISMIC DESIGN CRITERIA -
SHORT TERM INFORMATION FOR ACRS Enclosed is the relevant information you requested in your memorandum dated June 15,1979.
Also enclosed is a copy of a table summarizing RES support of Unresolved Safety Issues in FY1979 and FY1980.
7 l
Goutam Bagchi, Chief Structural Engineering Research Branch Division of Reactor Safety Research
Enclosures:
as stated cc:
T. E. Murley, RSR L. C. Shao, RSR J. E. Richardson, RSR J. Harbour, RSR C. W. Burger, RSR 8 0 010 90 o7l 1737 051
Enclosure 1.
Following is a list of Industry /NRC studies:
Nelson, T. A., Murray, R. C., " Elastic-Plastic Seismic Analysis of Power Plant Braced Frames," Dec. 4, 1978.
Bumpus, S., Smith, P.
S., "The Role of the Operating Basis Earthquake in Controlling Design," May 21, 1979.
URS/ John A. Blume, & Associates, Engineers, " Nonlinear Structural Dynamic Analysis Procedures for Category I Structures," Sept.1978.
Smith, P. D., " Structural Damping," Part IV, UCID-18111.
Maslenikov, O. R., Smith, P.
D., " Soil-Structure Interaction at the Humboldt Bay Power Plant," Part V, UCID-18105.
Smith, P. D., Bumpus, S., Maslenikov, O. R., " Response to Three Input Components," Part VI, UCID-17959.
Smith, P.
D., Bumpus, S., Maslenikov, 0.
R., " Broadening of Floor Response Spectra," Part VII, UCID-18104.
Bumpus, S., " Structural and Mechanical Resistance," Part VIII, UCID-17965.
- Bumpus, S., " Nonlinear Structural Response," Part IX, UCID-18100.
Maslenikov, 0. R., Smith, P. D., " Calculation of Subsystem Response," Part X, UCID-18110.
Nelson, T. A., " Seismic Analysis Methods for the Systematic Evaluation Program," UCRL-52528, July 1978.
Berkowitz, L., " Seismic Analysis of Primary Piping Systems for Nuclear Generating Systems," Reactor and Fuel Processing Technology, Argonne National Laboratory, Fall 1969.
Cloud, R.
L., " Structural Mechanics Applied to Pressurized Water Reactor Systems," Nuclear Engineering and Design, Vol. 46, No. 2, April 1978.
American Society of Mechanica.1 Engineers, " Criteria of the ASME Boiler and Pressure Vessel Code for Design by Analysis," Sections III and VIII, Division 2 NY, NY, 1972.
Prepared by Weidlinger Assoc., Electric Power Research Institute, " Nonlinear Soil-Structure Interaction," Palo Alto, CA, EPRI NP-945,1978.
Prepared by Science Applications Inc., Electric Power Research Institute,
" Study of Nonlinear Effects on One-Dimensional Earthquake Response,"
Palo Alto, CA, EPRI NP-865,1978.
1737 0512
Enclosure 2
Prepared by URS/ John Blune, & Associates, E'ectric Power Research Institute, " Applications in Soil-Structure Interaction," Palo Alto, CA, EPRI NP-1091, 1979.
Bohm, George, J., "Darping for Dynamic Analysis of Reactor Coolant Loop Systems," Topical Meeting on Reactor Safety, Salt Lake City, UT, Conf-730304 Avail, NTIS. March 1973.
Cloud, R. L. " Seismic Capability of Nuclear Piping," Unpublished,1979.
Prepared by URS/ John Blume, & Associates, for USNRC, " Nonlinear Struct"ral Analysis Procedures for Category I Structures," Sept.1978.
Prepared by D' Appolonia Consulting Engineers for USNRC, " Seismic Input and Soil-Structure Interaction," NUREG/CR-0693 Feb.1979.
2.
A listing of NRC Consultants:
N. M. Newmark, University of Illinois W. J. Hall, University of Illinois R. P. Ker.nedy, EDAC J. C. Stepp, FUGR0 R. L. Cloud, R. L. Cloud Consultants J. M. Roesset, University of Texas -
3.
The table provided in Enclosure 2 addresses this point.
4.
The following table provides the necessary information.
1737 053
Enclosure Amount Lead Task No.
Division Contractor FY1978 FY1979 FY1980 Task Objective 1.0 D0R LLL 304,000 0
Quantify seismic conservatisms 2.0 00R LLL 80,000 0
Develop and evaluate elasto-plastic analysis techniques 3.0 D0R LLL 70,000 0
Develop methods to determine site-specific response spectra 2
4.Cf D0R LLL 5.0 DSS URS/ John 62,000 0
Develop nonlinear Bl ume seismic analysis methods 6.0 DSS D'Appolonia 142,000 29,000 Evaluate soil-structure interaction analysn 7.0 DSE Sys tems,
0 65,000 101.000 Develop earthquake Science and source modeling methods Software 8.0 & 9.0 DSE LLL 57,000 58,000 Develop methods to determine strong-nution near-field spectra 10.0 RES LLL 279,000**
Review results of program, modify SRP TOTALS 658,000 430,000 159,000
- Project was deleted.
- An additional $75K has been requested for Task #3.
- Total funding includes amounts associated with Task #3.
1737 054
Enclosure (f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEARCH (g)
(h)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY1979 FY198')
SUPPORTING THE GENERIC FY1979 FY1980 CATEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUN 0 LNG SUBJECT NO.
ISSUES MFETY ISSUES FOR (c)
FOR (c) listed in NUREG-0371)
. FOR (f)
FOR (f)
- A-1 Water Hausner Although it is not
$170K
$50K An additional research
$150K mentioned in NUREG-0371, program on " Steam Conden*
sation Induced Water research manpower and Hanener" will support prograni funds were pro-research needs in this vided in FY1979 and will area.
be provided in FY1980.
i
- A-2 Asysunetric Blowdown None Hone O
Research program to de -
0
$ 300K.
velop load conbination Loads on the Reactor criteria will support this Vessel area.
- A-3 Westinghouse Steam PNL: Steam Generator
$430K
$985K(A-3,4,5)
None O
Generator Tube Tube Integrity Integrity BNL: Inconel 600 Steam
$210K
$225K (A-3,4,5)
Generator Tube Corroston ORNL: Eddy Current
$58K
$145K (A-3,4,5)
Nondestructive Examination Ncne O
- A-4 Cosbustion Engineering Sane as A-3 Steam Generator Tube Ir.tegrity None O
- A-5 Babcock & Wilcox Same as A-3 Steam Generator Tube m
Integrity y
OJ N
C"3 CJ1
( T1 i
r
~
(f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEARCH (g)
(h)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY fY1979 FY1980 SUPPORTING THE GENERIC FY1979 FY1980 CATEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUNDING SUBJECT NO.
ISSUES SAFETY ISSUES FOR (c)
FOR (c)
Ifsted in NUREG-0371)
. FOR (f)
FOR (f)
- A-6 Mark I short Ters 1.1/5 scale test series
$100K 0
LLL prograssto develop,
$500K
$200K Program at LLL to obtain compter program to confirmatory pool analyze fluid-structure interaction effects.
dynamic load data (FIN No. A0118)
(FIN No. A0116)
- 2. MIT program to in-
$130K 0
vestigate scaling relationships for hyd.mdynamic phenomer a, I
fluid-structure inter-action effects, and steam chugging phenomena (FIN No.
B6167)
- 3. UCLA program to
$115K 0
investigate air and steam venting into water pools.
(FIN NO. B5875)
- A-7 Mark I Long Tenn Same as A-6 Program
- A-8 Mark !! Progren 1.
MIT program to in-0 LLL program to develop
($500K,A-6)
($200K,A-6]
vestigate scaling computer program to an-y relationships for alyze fluid-structure interaction effects.
g hydrodynamic phenom-ena, fluid-structure (FIN NO. A0116) interaction effects f
C and steam chugging W
phenomena. (FIN No.
O B6167).
2.
UCLA program to in-vestigate air and steam venting into water, pools (FIN No.
(f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEADCH (g)
(h)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY1979 FY1980 SUPPORTING THE GENERIC FY1979 FY1990 CATEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING.
SAFETY ISSUES (not FUNDING FUNDING SUBJECT NO.
ISSUES SAFETY ISSUES FOR (c)
FOR (c) listedinNUREG-0371)
. FOR ( f)
FOR (f)
- A-9 ATWS Research staff assist-
$36K 0
Research staf f sponsors -
O
~
a program which estimated ance is provided to failure rates for control review ATWS documentati( n and estimate risk from rod drive mechanism systens by evaluating ATWS LEMs.
The Engineering Technology Engineering Center did a literature search on pressurizer safety / relief valve dis-charge under ATWS con-ditions. This was at the request of ;iRR.
si,
- A-10 BWR Nozzle Cracking ORML: HSST Program
$2087K(A-11,26 i $1890K (A-11,2f ) SWRl: Ultrasonic Testing ($160K.A-14)
($)50KTA-14) in Field App 11-cations Univ. Mich: Fast Reliable $237K,A-14)
($100K,A-14)
Ultrasonic Testing Detection
- A-1T Reactor Vessel Mater-ORNL: HSST Program
($2087K, A-10,26)($1890K,A-10,26l NRL: Irradiation Fffects $700K
$800r in LWRs tal Toughness NSRDC: Elastic Plastic
$100K
$100K Specimen Shape Wash. Univ: Tearing In-
$108K
$175K stability
%a BCL: Crack Arrest
$305K
$325K U
N CD L.71 N
(f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEARCH (9)
(h)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY19ts FY1980 SUPPORTING THE GENERIC FY1979 FY1990 CATEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUNDING SUBJECT NO.
ISSUES SAFETY ISSUES FOR (c)
FOR (c) listedinNUREG-0371)
. FOR (f)
FOR (f)
- A-12 Fracture Toughness 0
0 ORNL: Pressure Vessel
$790K
$750K (A-11,12)
Simulation of Steam Generator and Reactor Coolant Experiment HEDL: Surveillance
$540K
$500K (A-11,12)
Pung Supports Dostmetry NBS: Dostmetry Data Base
$72K
$ 90K (A-11.12)
A-13 Snubbers 0
0 Research program on
$90K
$150K snubbers and restraint devices will support this issue A-14 Flaw Detection PNL: Acoustic Emission
$350K
$400K ORKL: Eddy Current Non-($5BK A-3)
($145K, A-3)
Material destructive Univ. Mich: Fast
$237K
$100K Examination Reliable Ultra-PNL: Integration of Non-
$274K
$645K sonic Detection destructive SWRI: Ultrasonic Test-
$160K
$150K Examination and ing in Field Fracture Mech.
Daedalean: Incipient 0
$200K flaw Detection A-15 Primary Coolant No direct research 0
0 BNL: Inconel 600 Steam
($210K,A-3)
($225K,A-3)
Generator Tube System Decontaminatio,
Corrosion A-16 Steam Effects on 0
0 This physical phenomenon
$600K
$1,5M (estimate BWR Core Spray will be investigated in the NRC/GE/EPRI program in Lynn, Massachusetts facilltv in FY1980-1982 N
tra N
O CO
(f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEARCH (g)
(h)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY1979 FY1980 SUPPORTING THE GENERIC FY1979 FY1980 TEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUN 3ING BJECT NO.
ISSUES SAFETY ISSUES FOR (c)
FOR (c) listedinNUREG-0371)
.FOR(f)
FOR (f)
- A-17 Systems Interaction Research provides staff 0
0 None O
O assistance to formulate and review the NRR technical assistance program A-18 Pipe Rupture Design None 0
0 BCL: Cold Leg Break
$200K
$200K Criteria Criteria Sandia: Two-Phase Jet 0
$350K Loads LLL: Pipe Whip Evaluation 0
5150K NSRDC: Elastic Plastic
$100K L5100K, A-11)
Specimen Shape NRL: Irradiation Effects
($700K,A-11)
($800K,A-11) in LWRs Wash. Univ: Tearing
($108K, A-11)
($175K, A-11)
Instability PNL: Integration of Non-($274K,A-14)
(16450,A-14) destructive Examination and Fracture Mech.
A-19 Digital Computer Hone 0
0 0
0 A-20 Ispacts of Coal Fuel Research manpower and 0
0 The program supportive
$160K
$100K of this issue is entitled Cycle funds were provided
" Health Effects of in FY1978, 1979 and 198(
Radiological and y
Nonradiological Pollutant <
u N
O LT1 W
(f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEARCH (g)
(h)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY1979 FY1980 SUPPORTING THE GENERIC FY1979 FY1980 CATEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUNDING SUBJECT NO.
ISSUES SAFETY ISSUES FOR (c)
FOR (c) listed in NUREG-0371)
, FOR (f)
FOR (f)
A-21 Main Steamline Bmak None 0
0 0
0 Inside Containment A-22 Main Steamline Break No'ne 0
0 0
0 Outside Containment A-23 Containment Load Test None 0
0 Mone 0
0
- A-24 Qualification of Sandia Laboratories is
$775K
$600K None 0
0 Class IE Safety working to develop Related Equipment methodology for:
- aging
- radiation source term
- testing A-25 NonSafety Loads on None 0
0 None 0
0 Class IE Power Sources
- A-26 Reactor Vessel None 0
0 Heavy Section Steel
($2087K,A-10
($18Ffl-10 A
Pressure Transient Technology Research 11)
MSRDC: Elastic Plastic
($100K,A-11)
($100K,A-11)
Protection (over, pressure)
Specimen Shape NRL: Irradiation Effects ($700K,A-11)
($800K A-11) in LWRs Wash. Univ: Tearing
($108K, A-11)
($175K. A-11)
Instability BCL: Crack Arrest
($305K,A-11)
($325K, A-11) s N
Ltd N
CD T-CD
(f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEARCH (g)
(h)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY1979 FY1980 SUPPORTING THE GENERIC FY1979 FY1990 CATEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUNDING SUBJECT NO.
ISSUES SAFETY ISSUES FOR (c)
FOR (c) listed in NUREG-0371)
. FOR (f )
FOR (f )
A-27 Reload Application None 0
0 Most of the LWR fuel 0
0 research provides generic Guide information on evaluation of reload applications.
However, A-27 is the development of a Regulatory Guide giving guidelines for reload core applications.
A-28 Increase in Spent Althou9h not directly 0
0 This issue involves 0
0 Fuel Stora9e Capacity mentioned in NUREG 0371, development of licensing research manpower was positions and generic provided in FY197n and criteria for storage additional manpower may of spent fuel at reactor be necessary in FY1980.
facilities. No research need has been identified in support of this issue.
A-29 Design Features to Research effort to
$600K (total funds Additional research effort 0 0
Control Sabotage directly support the through FY1979 indirectly supportive of need in this area will
$1600K) this issue is on be concluded at the
" Development of Evaluation end of FY1979.
Methods for Physical Protection. "
A-30 Adequacy of DC Research administers
$ 60K
$100K None 0
0 Power Supplies (for NRR) and provides staff assistance to a program evaluating the adequacy of
~~a current design criteria tja for DC power supplies.
-,3 CD Ch
(f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEARCH (g)
(h)
ASPECTS OF RESEARCH PROGRAMS IMOIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY1979 FY1980 SUPPORTING THE GENERIC FY1979 FY1980 CATEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUNDING SUBJECT NO.
ISSUES SAFETY ISSUES FOR (c)
FOR (c) listedinNUkEG-0371)
. FOR (f )
FOR (f )
- A-31 RHR Shutdown None 0
0 Research supports a
$100K
$200K program to provide an Requirements integrated technical basis for future regulatory actions regard-ing shutdown heat removal systems. This includes a review of current design i
criteria and practices and identification of the potential threats to and vulnerabilities of these systems.
A-32 Evaluation of Overall No research need has 0
0 Hone 0
0 Effects of Missiles been identified for this issue yet.
A-33 NEPA Reviews Research sponsors a
$180K
$100K None 0
0 program to evaluate the e
risk from Class 3-8 accidents as required by NEPA reviews.
~
A-34 Instruments for None 0
0 tione 0
0 Monitoring Radiation and Pmcess Variable during Accidents y
A-35 Adequacy of offsite None 0
0 Hone O
O N
Power Systems C *A-36 Heavy Loads Near Hone 0
0 None 0
0 Spent Fuel
1 (f)
(a)
(b)
(c)
(d)
(e)
ASPECTS OF RESEARCH (9)
(h)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY1979 FY1980 SUPPORTING THE GENERIC FY1979 FY1980 CATEGORY A
- GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUNDING SUBJECT NO.
uliUtS SAFETY ISSUES FOR (c)
FOR (c)
Itsted in NUREG-0371)
, FOR f )
FOR F )
A-37 Turbine Missiles Research support needed 0
0 None 0
0 for this issue relates to damage probability.
Research manpower was provided in FY1979.
No additional need is anticipated.
i A-38 Tornado Missiles Research manpower and
$ 41K 0
Additional funds are 0
$100K being bud 9eted for funds were provided in FY1979. Additional research program on
" Aircraft impact support is not Effects." The results anticipated in FY1980.
will be useful for this iss ue.
- A-39 Determination of Mone 0
0 MIT program is evaluating 0 0
scaling relationships Safety Relief Valve for SRV discharge.
(SRV) Pool Dynamic FIN No. B6167 Loads and Temperaturo Limits for BWR Containments
- A-40 Seismic Design Research manpower and
$170K 0
The primary program in 0
$150K FY1980 on effective Criteria - Short funds were provided seismic input addresses Term in FY1979 for program the research need in this renagement and support area.
of research efforts.
'd Additional research L/4 manpower and funds
d ray be necessary in
.I C:)
Ch U4
~ ~
(f)
(a)
(b)
(c)
(d)
(e)
. h)
(
ASPECTS OF RESEARCH (9)
ASPECTS OF RESEARCH PROGRAMS INDIRECTLY TITLE OF CATEGORY PROGRAMS DIRECTLY FY1979 FY1990 SUPPORTING THE GENERIC FY1979 FY1980 CATEGORY A A GENERIC SAFETY SUPPORTING THE GENERIC FUNDING FUNDING SAFETY ISSUES (not FUNDING FUNDING SU6 JECT NO.
ISSUES SAFETY ISSUES FOR (c)
FOR (c) listedinNUREG-0371)
.FOR(f)
FOR (f)
A-41 Seismic Design A program entitled,
$2303K
$2450K Many seismic research
$275K
$4330K, Criteria - Long
" Seismic Safety programs underway and Term (This generic Margins Program" was planned w111 support task has been initiated in FY1979 the research need in deleted. The long and will continue this area. The major term research through FY1980. This programs are on regional program entitled is a major research seismic studies, geotech-nical studies, dynamic
" Seismic Safety effort directed to the s
Margins Program" Itcensing need in this testing, earthquake hazard assessments and discussed in a rea.
Colum (e) will qualification tests of supply much of the equipinent.
information originally en-visioned as part of this task.)
- A-42 Pipe Cracks in None 0
0 None 0
0 Boiling Water Reactors
- A-43 Emergency Susp None 0
0 None 0
0 Reliability N
- A-44 Station Blackout None 0
0 None 0
0 TOTAL
$8212K
$7195K
$4914K
$11.465K g
} 1.
Some of the research prograns are useful for several generic issues.
Those funds, shown in parentheses, are ass ociated with ouer l'ssues, and A
are not counted in the total research funds.
2.
The otal sum of direct and indirect support for FY1979 is $13,126K which is approxi mately 9% of FY1979 research budget.
($14J,480K)
\\
3.
The.otal sum of direct and indirect suppcrt for FY1980 is $18,660K which is approxi mately 11% of FY1980 research budget. ($163.000K) 1