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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20005G4211989-02-28028 February 1989 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. ML20206C7451988-11-30030 November 1988 ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5 ML20205T7501988-11-0404 November 1988 Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20154N6081988-09-30030 September 1988 Rev 1 to Identification of Unisolable Piping & Determination of Insp Locations ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML17347A7981988-06-16016 June 1988 Radiological Data Prepared for Resolution of USI A-46. ML17347A7971988-06-16016 June 1988 Seismic Hazard Data Prepared for Resolution of USI A-46. ML20150F2941988-05-31031 May 1988 Rev 4 to, ATWS Mitigation Sys Specific Design for Byron/ Braidwood Stations ML20196L6281988-05-20020 May 1988 Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac) ML20196L6421988-05-0606 May 1988 ATWS Mitigation Sys Actuation Circuitry Response to Unit Transients ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness ML20148G5431988-01-15015 January 1988 Nonproprietary Mods to Critical Flow Model in RELAP5YA ML20155K1391987-12-30030 December 1987 Final Rept MSIV 3-Way Dual Solenoid Valve Failures ML20235F0881987-12-17017 December 1987 Marked-up Draft Seismological Analysis of Bodega Head,Ca ML20236Y0941987-10-21021 October 1987 Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Final Rept ML20235G3041987-09-29029 September 1987 Partially Withheld, Preliminary Investigation of Enrico Fermi II Nuclear Power Plant ML20235B3121987-08-31031 August 1987 Comparison of Monticello & Brunswick Recirculation Pump Trip ML18151A1351987-08-28028 August 1987 Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. ML20237K8201987-08-26026 August 1987 TVA Employee Concerns Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-2, Review of Nuclear Safety Review Staff Non-Startup Items at Bellefonte ML20237K7691987-08-0606 August 1987 Rev 3 to TVA Employee Concern Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-1, Review of Nuclear Safety Review Staff Restart Items at Browns Ferry ML20236N2591987-07-31031 July 1987 Final Summary Rept of Human Factors Engineering Review for Byron & Braidwood Stations Spds ML20237K7981987-07-28028 July 1987 Rev 1 to TVA Employee Concerns Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-2, Review of Nuclear Safety Review Staff Non-Restart Items at Browns Ferry ML20237K8081987-07-23023 July 1987 Rev 0 to TVA Employee Concern Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-1, Review of Nuclear Safety Review Staff Startup Items at Bellefonte ML18093A1791987-06-19019 June 1987 Installation of Trip-A-Unit Protection Scheme Suppl Info Salem & Hope Creek Generating Stations. ML20214S3081987-05-28028 May 1987 Weekly Status Rept,Assessment of Embedment Plates Status as of 870528 ML20214T2941987-05-27027 May 1987 Comm Ed Final Summary Rept on Human Factors Review for Byron/Braidwood Stations Emergency Response Facilities ML20215K2441987-04-30030 April 1987 Assessment of Embedment Plates Status as of 870430, Weekly Status Rept ML20214E0581987-04-16016 April 1987 Rev 2 to ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations ML17279A1911987-04-0707 April 1987 Comparision of Electrical Design of Wye Pattern Globe Valve Actuator W/Ball Valve,Hanford 2 & River Bend Design. Five Oversize Drawings Encl ML18092B4971987-04-0303 April 1987 S-C-E500-NSE-0675-R-1, Justification for Operation of All Three Units at Artificial Island at Increased Power During Hope Creek-Keeney Line Outage. ML20204J7431987-03-12012 March 1987 Assessment of Embedment Plates Status as of 870308, Weekly Status Rept ML20212K1201987-01-23023 January 1987 Final Design Description,Atws Mitigation Sys Actuation Circuitry ML20210U3761987-01-16016 January 1987 Rev 1 to ATWS Mitigation Sys Specific Design for Byron/ Braidwood Stations 1989-08-14
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18094B3211990-02-28028 February 1990 Annual Operating Repts for 1989 for Salem & Hope Creek Generating Stations ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML18094B1471989-10-25025 October 1989 Emergency Plan Annual Exercise 1989 for Artificial Island on 891025. W/One Oversize Drawing ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML20248G8291989-10-0202 October 1989 Rev 19 to YOQAP-I-A, Operational QA Program ML17347B3821989-09-30030 September 1989 Monthly Operating Repts for Sept 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/891016 Ltr ML19327C0681989-09-30030 September 1989 Nuclear Safety & Compliance Semiannual Rept Number 11,Apr- Sept 1989. W/891027 Ltr ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20248D1571989-09-13013 September 1989 Rev 56 to QA Program ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML17347B3341989-08-31031 August 1989 Monthly Operating Repts for Aug 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/890913 Ltr ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML17347B2731989-07-31031 July 1989 Monthly Operating Repts for Jul 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2 ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML17347B2741989-06-30030 June 1989 Corrected Monthly Operating Repts for June 1989 for Turkey Point Units 3 & 4 ML17347B1851989-06-30030 June 1989 Monthly Operating Repts for June 1989 for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4.W/890717 Ltr ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML18151A5411989-06-21021 June 1989 Updated Operational QA Program Topical Rept. ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML18101A4931989-06-13013 June 1989 Radiological Emergency Preparedness Exercise Evaluation Rept. ML17345A7241989-06-0909 June 1989 Rev 15 to Topical QA Rept. ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML17345A7501989-05-31031 May 1989 Monthly Operating Repts for May 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2 ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML17345A6851989-04-30030 April 1989 Monthly Operating Repts for Apr 1989 for Turkey Point Units 1 & 2 & St Lucie Units 1 & 2.W/890515 Ltr ML17345A7531989-04-30030 April 1989 Corrected Monthly Operating Rept for Apr 1989 for St Lucie Unit 2 ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing 1990-02-28
[Table view] |
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e STATEMENT By DR. GEORGE W. HOUSNER PROFESSOR OF CIVIL ENGINEERING AND APPLIED MECHANICS CALIFORNIA INSTITUTE OF TECHNOLOGY i
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f My name is George W. Housner and my business address is 1201 East California Boulevard,' Pasadena, California. I am 3
Professor of Civil Engineering and Applied Mechanics at the.
[ California Institute of Technology. I received'a Bachelor of l Science degree froan the University of Michigan in 1933, a Master h of Science degree from the California Institute of Technology in 1934, and the Doctor'of Philosophy degree from the California Institute of Technology in 1941. I have been on the staff of the j California Institute of Technology since 1945 1 i I am a member of the following scientific and professional
! l I organizations: Seismological Society of America, American Geophysical Union,; Earthquake Engineering Research Institute, f International Association of Earthquake Engineering, Mexican f Association of Earthquake Engineering, Structural Engineers ,
i Association of California, American Society of Civil Engineers, and others.
i I hold the following positions of responsibility relating h to earthquake engineering:. President of the Earthquake Engineering .
! Research Institute; Member of Board of Directors of the Interna-tional Association of Earthquake Engineering; Member of Board of Directors of the International Institute of Seismology and Earthquake Engineering in Tokyo; Member of the Consulting Board j
for Earthquake Problems for the California State Department'of Water Resources. I was formerly a member of the Advisory Panel on i
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Safety Against Groundshock for the U. S. Atomic Energy Commission and a member of the Scientific Council of the Seismological Society of America.
I am, or have been, a consultant on the following projects I
concerned with earthquakes, bombshock, or other vibratory excita-tions: preparation of handbook " Nuclear Reactors and Earthquakes" for the Atomic Energy Commission; earthquake design of nine nuclear i
- power plants in different parts of the' United States; design of
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- nuclear power plant for Japan Atomic Power Company; earthquake I f design of suspension bridge over the Tagus River in Lisbon, Portugal; l
design of the San Francisco Bay Area Rapid Transit System; design ,
of Titan missile bases for Space Technology Laboratory; design of j i Saturn Missile Test Facilities, and others. I have also served as consultant to the following organizations: General Electric Company, Westinghouse Corporation, Allis-Chalmers Corporation, !
. I Rocketdyne; Bechtel Corporation, Ralph M. Parsons Company, <
Sverdrup & Parcel and Associates, Los Angeles Department of Water and Power, Humble Oil Company, Standard Oil of California, i Aerojet-General Corporation, General Telephone Company, Hancock 011 Company, and others. 1 I am the author of forty technical papers and books, most of which deal with problems of earthquakes.
I have been asked by the Pacific Gas and Electric Company to present my opinion as to the earthquake resistant design of t}ie
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( 8 proposed nuclear reactor power plant to be located en Bodega Head.
Northern California is in an active seismic region, as is most of the western United States. Strong earthquakes have also occurred in the midwestern and eastern United States but with
- less frequency than in the western parts of the country. That
, California is subject to earthquakes has long been recognized by seismologists and engineers, and much research has been done on the I priblems posed by their occurrence. The frequency of occurrence i f
of earthquakes of various Magnitudes have been analyzed the
- locations of epicenters have been determined , the potentially i
i damaging ground motions during earthquakes have been recorded W;
I
! spectral analyses of these ground motions have been made 3/ ,
t studies have been made of the behavior of structures during 1 Y l ; earthquakes ; the motions of buildings have been measured during j l
4 I 1. B. Outenberg and C. F. Richter, Seismicity of the Earth, Princeton University Press, 1954. !
- 2. "U. S. Earthquakes 1928-63," U. S. Department of Commerce, j W'ashington, D. C. l i
- 3. G. W. Housner, J. L. Alford and R. R. Martel, " Spectrum ;
Analyses of Strong-Motion Earthquakes", Bull. Seismological '
i Soc. Am., Vol. 43, No. 2, 1953.
- 4. " Proceedings of the World Conference on Earthquake Engineering",
Earthquake Engineering Research Institute, Berkeley, 1956; and." Proceedings of the Second World Conference on Earthquake Engineering", Tokyo, 1960. ,
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earthquakes W , and methods of analysis and design of structures to resist earthquakes have been developed 9/ . The results of these
, studies are reflected in the bui,1 ding codes that govern the earthquake-resistant design of buildings and schools in our f communities. The forces induced by earthquakes can be taken into account in the design of a structure in the same way that wind forces and other types of forces are taken into account, and any
[
I desired degree of safety can be incorporated.in the structure.
No movement on faults is expected to occur on the site ;
I 2 of the plant, but the design will be such that fault movement f
I could be accommodated without damage to the functional integrity i of the plant.
I s The motion of the ground during strong earthquakes in California is recorded by a network of special accelerographs that !
- are maintained by the Seismological Field Survey of the U. S. !
O Coast and Geodetic Survey / The characteristics of strong earth- f,
. quake ground motion and the behavior of structures subjected to f
- 5. C. M. Duke and R. A. Brisbane, " Earthquake Strain Measurements ,
in a Reinforced Concrete Building", Bull. Seism. Soc. Am.,
Vol. 45, 1955
- 6. G. W. Housner and D. E. Hudson, " Vibrations of Structures Induced by Seismic Waves", Chapter 50, Shock and Vibration Handbook, McGraw-Hill, 1961.
7 " Report of the State Earthquake Investigation Commission",
Carnegie Institution of Washington, Vol.1,1908; Vol. 2,1910.
- 8. The data are published in the series of booklets, "U. S.
Earthquakes 1928-63, "U. S. Dept. of Commerce, Washington, D.C.
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f this ground motion have bee'n analyzed V . Methods of design of ordinary structures to resist earthquakes have been presented in 1M detail. . The design of nuclear reactors to resist earthquakes jl1 has also been described . An extensive discussion of the design of nuclear reactors to resist ear akes is presented in an Atomic Energy Commission Handbook .
l The design of the Bodega Bay power plant is based on 1 ,
the expectation that there will be a repetition of the 1906 (
f
[ earthquake. There is a very complete report on this earthquake (
i that describes the slip on the fault and the damage to buildings V j r .
r In particular, there are photographs and descriptions of structures close to the surface trace of the fault which give a good indica-tion of the severity of ground shaking. The design of the plant l :
l is such that in the event of a repetition of the 1906 shock the '
' stresses induced will be less than the allowable working stresses 1 <
i
) for the materials. This means that the buildings and equipment 1
(
, could withstand a repetition of the 1906 shock every week without )
l
- 9. G. W. Housner, "The Behavior of Structures During Earthquakes",
Proc. Amer. Soc. Civ. Engnrs. , Vol. 85, EM4, October,1959
- 10. J. A. Blume, L. H. Corning, N. M. Newmark, " Design of Multistory Reinforced Concrete Buildings for Earthquake Motions", Portland Cement Assn. ,1961,
- 11. G. W. Housner, " Design of Nuclear Reactors to Resist Earth-quakes", Proc. Seco nd World Conference on Earthquake Engineer-ing, Tokyo, 1960.
- 12. U. S. Atomic Energy Commission, " Nuclear Reactors and Earth-quakes", 1963
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3 ill effect, he design will incorporate a large factor of safety
.! so that the reactor structure could withstand, without damage, E .
ground motion twice as severe as that during the 1906 shock. The earthquake forces used in the design of the reactor' building are ,
more than five times the values required by the Building Codes of.
San Francisco and Los Angeles. he plant will be able to withstand
[ the maximum credible ground shaking as estimated by seismologists
'f i with ample factor of safety, t
r In summary, the plant can be designed to withstand.1 M -
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ground shaking and to accomr.odate fault movement without . jeopardizing; its integrity.
- i. ;
i 13 P. Byerly, " Seismicity of the Western United States", ,
L' Proc. World Conference on Earthquake Engineering Earthquake En {'
- Icuderback, "gineering Faults Research Institute, and Earthquakes", Bull. Seism. 1956;,G.
Soc. D. ;
Am., Vol. 32, No. 4, 1942; W. K. Cloud, " Maximum 1
! Accelerations During Earthquakes, "First Chilean 1
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Conference on Seismology and Earthquake Engineering, (
Santiago, Chile, July, 1963. 4 Y
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