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Category:NRC TECHNICAL REPORT
MONTHYEARML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept ML20204J6141988-08-31031 August 1988 AEOD/E807, Pump Damage Due to Low Flow Cavitation ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20196G5251988-06-15015 June 1988 Technical Review Rept T809, Blocked Thimble Tubes/Stuck Incore Detector ML20245H9601988-04-15015 April 1988 BWR Overfill Events Resulting in Steam Line Flooding, AEOD Engineering Evaluation Rept ML20148D0671988-03-17017 March 1988 Headquarters Daily Rept for 880317 ML20148B3291988-03-14014 March 1988 Headquarters Daily Rept for 880314 ML20196H6351988-03-0808 March 1988 Headquarters Daily Rept for 880308 ML20196G8881988-03-0303 March 1988 Headquarters Daily Rept for 880303 ML20147E3961988-01-0606 January 1988 Rept of Interview W/Rg Lagrange on 841206 & 14 to Discuss Info Contained in B Hayes 841017 Memo Identifying Series of Submittals Received from Util Between 1980 & 1984 ML20147E3211988-01-0606 January 1988 Rept of Interview W/Rg Lagrange to Discuss Gpu 830520 & s Re Environ Qualification equipment.Marked-up 850409 Statement from H Hukill Also Encl ML20237L3001987-08-24024 August 1987 AEOD/E709 Engineering Evaluation Rept Re Auxiliary Feedwater Trips Caused by Low Suction Pressure.Draft Info Notice Encl ML20235C9311987-06-23023 June 1987 Rept to ACRS Re Humboldt Bay Unit 3 - Core II ML20212F6581986-12-31031 December 1986 Technical Review Rept, Degradation of Safety Sys Due to Component Misalignment &/Or Mispositioned Control/Selector Switches ML20212D9091986-12-23023 December 1986 Localized Rod Cluster Control Assembly (Rcca) Wear at PWR Plants, Engineering Evaluation Rept ML20212B0321986-12-17017 December 1986 Emergency Diesel Generator Component Failures Due to Vibration, Engineering Evaluation Rept ML20214R4851986-10-0909 October 1986 Initial OL Review Rept for Seabrook Station Unit 1 ML20212K6641986-08-0707 August 1986 Inadvertent Recirculation Actuation Signals at C-E Plants, Technical Review Rept ML20206H0871986-03-0303 March 1986 Allegation Review Data Sheet for Case 4-85-A-013 Re Const Activities.Addl Info Requested from Alleger.Case Closed Due to Lack of Response.Related Info Encl ML20206H0761986-01-21021 January 1986 Allegation Review Data Sheet for Case 4-84-A-085 Re Alteration of Personnel Records.Based on Resolution of Allegation 4-84-A-094,case Closed ML20137X6151986-01-0909 January 1986 Engineering Evaluation of Deficient Operator Actions Following Dual Function Valve Failures ML20234F5601985-12-17017 December 1985 Draft Hazards Analysis ML20234F4751985-12-17017 December 1985 Licensing of Power Reactors by Aec ML20214T2211985-11-25025 November 1985 Initial OL Review Rept:Millstone Point Unit 3 ML20206H0621985-10-15015 October 1985 Allegation Review Data Sheet for Case 4-85-A-045 Re Inadequate Handling/Installation Procedures for Equipment, Vendor Control Programs & Spare Parts.Based on Insp Rept 50-482/85-22,case Closed ML20206H0371985-10-0202 October 1985 Allegation Review Data Sheet for Case 4-85-A-044 Re Lack of Effective QA Programs & QC Insps.Based on Insp Rept 50-482/85-22,allegation Closed IR 05000482/19850191985-09-30030 September 1985 Allegation Review Data Sheet for Case 4-85-A-050 Re Mishandling of Document Control Program.Concerns Addressed in Insp Rept 50-482/85-19.Dept of Labor & Allegation Cases Closed ML20206H0131985-09-27027 September 1985 Allegation Review Data Sheet for Case 4-84-A-076 Re Vague Administrative Procedures,Calibr Program Not Working,Test Engineer Authority & Harassment.Based on Insp Rept 50-482/85-03,case Closed ML20137B1231985-09-16016 September 1985 HPCS Sys Relief Valve Failures, Engineering Evaluation Rept ML20206G8431985-09-0303 September 1985 Allegation Review Data Sheet for Case 4-84-A-013 Re Improper Termination of Employee Due to Refusal to Weld Laminated Pipe.Welding non-safety Related.Case Closed on 850827.W/ 840315 Telcon Record & Addl Info IR 05000482/19850311985-08-28028 August 1985 Allegation Review Data Sheet for Case 4-85-A-077 Re 6 Rem Exposure in Containment Bldg Due to Pipe Break.Allegation Investigated During Insp 50-482/85-31 on 850715-19 & Found Unsubstantiated ML20206G8051985-08-27027 August 1985 Allegation Review Data Sheet for Case 4-84-A-114 Re Drugs Planted at Plant.Evidence Destroyed in Testing.Based on Insp Rept 50-482/85-03 & Mullikin 850429 Memo,Case Closed ML20206G7781985-08-27027 August 1985 Allegation Review Data Sheet for Case 4-84-A-195 Re Quality First.Fuel Load Issue Resolved in Insp Rept 50-482/85-10. Technical Issues to Be Resolved Prior to Full Power Licensing.Case Closed w/850815 Memo to File ML20209G3051985-08-0909 August 1985 Closure of ECCS Min Flow Valves, Engineering Evaluation Rept.Recommends IE Issue Info Notice to Remind Licensees of Importance of Min Flow Bypass Capability as Essential Pump Protection Feature ML20206H1021985-07-30030 July 1985 Allegation Review Data Sheet for Case 4-84-A-008 Re Improper Const Practices.Insp Rept 50-482/84-12 Issued on 841012 & Closeout Ltr Sent on 850405 ML20206H0801985-07-30030 July 1985 Allegation Review Data Sheet for Case 4-84-A-007 Re Intimidation of QC Inspector.Forwards Documents Closing Allegation.W/O Encls ML20147E4401985-06-20020 June 1985 Rept of Interview W/Cw Smyth on 850510.Smyth Advised of Unfamiliarity W/Environ Qualification Program in Technical Sense & W/Documentation Needed to Qualify Individual components.Marked-up Lw Harding Statement Encl ML20199G0701985-05-0303 May 1985 Partially Withheld Statement of Decision Re Allegation AQ-38 Concerning Alleged Harassment of QC Inspectors Upon Observation of Weld Defects on vendor-inspected Restraints. Allegation Substantiated.Addl Allegation Repts Encl ML20147H0101985-04-16016 April 1985 Draft Summary Rept for Regional Evaluation of Texas Utils Electric Co,Comanche Peak Steam Electric Station ML20206G9151985-03-12012 March 1985 Allegation Review Data Sheet for Case 4-84-A-015 Re Harassment of Mechanical/Welding QC Inspector for Writing Nonconformance Rept Re Improper Welding Amperage by Superintendent.Util Rept Issued & Case Closed ML20147G9901985-01-31031 January 1985 Summary Rept for Regional Evaluation of Texas Utils Electric Co,Comanche Peak Steam Electric Station ML20205Q7691985-01-18018 January 1985 Status Rept Mechanical/Piping Area. Related Info Encl ML20206G8861985-01-0909 January 1985 Allegation Review Data Sheet for Case 4-85-A-004 Re Electrical Installations.Insp Required.Related Info Encl ML20214R5681984-12-31031 December 1984 Shoreham Nuclear Power Station Initial OL Readiness Assessment ML20214T7251984-11-30030 November 1984 Summary Rept for Regional Evaluation of Diablo Canyon Unit 2 ML20206G8131984-10-0303 October 1984 Allegation Review Data Sheet for Case 4-84-A-102 Re Visual Insp Through Paint,Unfair Intimidation to Produce Results, Rejection of Previous Inspected Welds,Defective Welds & Missing Beams.Addl Info Encl ML20206G7731984-10-0101 October 1984 Allegation Review Data Sheet for Case 4-84-A-098 Re Qa/Qc Program Allegations Re Matl Verification, post-ok Reviews by Engineers & Improper Verification of Snubber Transaction Assemblies ML20206H2431984-09-13013 September 1984 Allegation Review Data Sheet for Case 4-84-A-89 Re Kickbacks & Coverups in QA Dept.State of Ks Interested.No Federal Regulations Violated If Kickback Allegations true.W/840912 Telcon Record.Related Info Encl ML20205Q7591984-08-31031 August 1984 Preliminary Summary of Allegations for Comanche Peak Steam Electric Station,Units 1 & 2 ML20206H2321984-08-17017 August 1984 Allegation Review Data Sheet for Case 4-84-A-80 Re False Resume Submitted to Louisiana Power & Light Co W/Plant Listed as Former Place of Employment 1989-09-29
[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 ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML19327C0681989-09-30030 September 1989 Nuclear Safety & Compliance Semiannual Rept Number 11,Apr- Sept 1989. W/891027 Ltr 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 ML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept 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 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 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 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 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 ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. 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] |
Text
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U. S. ATDMIC ENERGY Cole (ISSION REGION Y DIVISION OF COMPLIANCE-By: G. S. Spencer, Reactor Inspector '
October 29, 1963 Region V, Division of Compliance Title . PACIFIC GAS & ELECTRIC COMPANY (BODEGA BAY)
' DOCKET NO. 50-205
SUMMARY
The proposed site of the Pacific Gas and Electric Company's Bodega Bay Reactor, Bodega, California, was visited on October 7,l1963. Three repre-sentatives of the U. S. Coast and Geodetic Survey, San Francisco, California accompanied the AEC inspectors on the visit. . Since the U. S. Geological.
Survey geologists who have been making a detailed study of the- site were not present during the visit, a later visit was made to their offices in Menlo Park, California on October 22,.1963 to discuss the current status of their st'udies. '
Excavation to the -73 ft. elevation was completed by October 16.' A final determination regarding the nature, probable origin, and. significance of the fault observed in the reactor excavation, will not'be made by the-U.S.G.S. geologists until they have completed mapping the contours of the bedrock surface.
The U.S.G.S. final report on the geological investigation of the site will not be submitted to Washington D.C. until late November or early December.
The granitic rock found at the bottom depths of the reactor excavation is not competent, according to the U. S. geologists. The Dames & Moore compression tests.of the rock taken from borings at -35 to -65 ft, elevations showed " ultimate compressive strengths" ranging from 1000 '4000 psi. In contrast to this, references in other geology literature list typical granitic foundation rock as ranging from 10,000 - 40,000 psi.
The U.S.G.S. appears to have available at its Menlo Park facility, consid-erable resources in trained manpower and equipment for the study and evaluation of the data and samples obtained during their examination of-the Bodega site. Techniques being utilized in the study in:1ude: Xaray diffraction. studies,-microscopic studies of granitic bedrock samples including the use"of oil immersion ~t'achniques, differential. staining techniques for studies of bedrock samples and statistical analyses of the (continued) 4
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Summa ry (continued) i distribution and orientation of the observed faults for determination of the nature of the stresses.
DETAILS I. Scope of Visit:
On October 7,1963 G. S. Spencer and R. H. Engelken,' Region V, Division of Compliance, accompanied Messrs. W. K. Cloud, C. F. Knudson, and V. A.
Moore of the U. S. Coast and Geodetic Survey, San Francisco, California, on -
l a visit to the proposed. site of the Pacific Gas and Electric Company's ,
Bodega Bay Reactor, Bodegn Bey, California. ' The visit ' included:
i 1. A briefing by Don Tocher, PG&E's seismology consultant, summarizing
.the' geological studies and findings made to-date at the site.
- 2. A tour of the entire site to acquaint the U. S. Coast & Geodetic I Survey representatives with the overall project layout.
- 3. Observation of the fault tracing exposed in'the walls and along
'the floor of the proposed reactor building excavation, including.
examination of an apparently related fault' indication in the sediments outside of the excavation at the +5 to +25. foot eleva-tion.
Principal contacts during the visit were:
(
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W. K. Cloud'- Geophysicist, U. S. Coast & Geodetic Survey i C. F. Knudson - Geologist, " " " '" "
V. A. Moore - Geologist, " "~ " " "
D. Tocher - Seismologist, Consultant to PG&E -
E. Marliove' - Geological Engineer,' Consultant to PG&E '
F. Lee - Geologist, U. S. Geological Survey, Denver,' Colorado F. Mautz - Project Engineer, PG&E
')
Since Messrs. Schlocker and Bonilla, the U.S.G.S. geologists who. '
have been making a detailed study of the excavated areas of the site,,were not present on the day of the visit, a later visit was made to their offices in Menlo Park, California, on October 22, 1963 for the purpose of discussing their findings.
II. Results of Visit A. Status of Site Preparation The floor of the reactor building -excavation had progressed down . -;
(continued) ,
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l Results of Visit (continued) to the -61 foot elevation, with the I-beam ring girder and gunite shoring installation completed down to the -59 foot elevation. According to Mr. ;
Mautz, the schedule called for the excavation to be completed (-73 ft. I elev.) by the 18th of October. All on-site construction activities which {
bad taken place up to the date of the visit appeared to be in accord with: )
(1) the letter from N. R. %;.herland to Robert Lowenstein, dated June 27, i 1963, setting forth PG&E's plans for preparation of the proposed ~ reactor ]
excavation and requesting confirmation of PG&E's views concerning the j application of the Consnission's regulation 10 CFR 50.10, to such work, '
(2) the letter of reply from the General Counsel dated July 23, 1963; and (3) the conditions set forth in Section 50.10(b) of 10 CFR Part 50. j i
B. Status of Fault Tracing As reported previously in our TWX dated September 16, 1963, a ;
fault indication was discovered in the (proposed) reactor building exca- '
vation on September 12, 1963 by Schlocker and Tocher. In our subsequent TWX's dated September 28 and October 2,1963, it was reported that the fault had been traced from the -11 ft. elevation in the southwest quadrant j of the hole, down into and across the bedrcck floor in a southwest to, north- .]
east direction, then vertically in the opposite wall at a point slightly 1 south of due east where it was lost within 3'(eet.from the top of the bedrock at elevation -21 feet. )
i buring the. visit covered by this report, it was noted that PG&E I was attempting to determine the age of the fault in the' reactor excavation by searching for an extension of the fault in the younger upper level ' !
sediments located outside of the reactor excavation. Later discussions l with Schlocker and Bonilla on October 22, 1963 established that a fault indication had been picked up just outsideof the excavation and traced for a distance of 165 feet in a southwesterly direction where it was lost at the +55 foot elevation. Ilowever, the relationship between this long l fault trace observed in the upper level sediments and the fault trace found in the reactor excavation has not been established as yet, according to Schlocker, due to their echeloned orientation relative to one another 1 (i.e., the trace end of one is parallel to and staggered relative to the trace beginning of the other). Schlocker explained that " echelon folding" of sediments overlying rock formations sometimes occurs as a result of horizontal displacement of the rock, and could be the explanation for this particular fault pattern. -
III. Results of Visit to U.S.G.S. , Menlo Park Since Messrs. Schlocker'and Bonilla, the U.S.G.S. geologists who have been making a detailed study of the excavated areas pf th'e site, were not present at the site on the day of the visit (October 7), a later (continued) 8
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i Results of Visit to U.S.G.S. . Menlo Park (continued) ,
- visit was made to their offices in Menlo Park, California on detober 22, 1963 to discuss the current status of their studies. The following pertinent information was obtained:
- 1. Excavation to the -73 ft. elevation was completed by October 16.
Schlocker stated that a final determination regarding the nature, probable origin, and significance of the fault observed in the reactor excavation will not be made until: contour mapping of .the
' bedrock surface is completed.
- 2. The U.S.G.S. final report on the geological investigation of the site will not be submitted to Washington, D. C, until late ;
November or early December, according to Schlocker. He also '
mentioaed that the report from PG&E's seismology consultant, Mr.
Don Tocher, was not yet available.
- 3. Mr. Bonilla stated that he and Schlocker were surprised to find l that the quartz diorite granite rock found at the bottom depths '
of the excavation was not competent. The excavating contractor apparently was surprised at this too, according to Bonilla, and had not anticipated a need' for shoring the bottom (bedrock) levels :
with I-beam ring girders. . However, the rock proved to be so '
deteriorated and sand-like, that shoring was required. . Schlocker stated that this indicated the rock has been subjected to tremen-dous stresses in the past. .
The Dames and Moore compression tests .of the rock taken frce borings at levels of -35 feet to -65 feet elevations, showed ultimate compressive strengths ranging from 1,000 - 4,000 psi, as shown below:
- a. Boring No.14 (rock encountered at -40 ft. elev.)
Ultimate Compression Strengths Level of Sample 2108 psi -40 ft. elev.
1861 pai -62 ft, elev.
2448 psi -65 ft. elev.
- b. Boring No.16 '(Center of reactor hole)
(rock encountered at -28 ft. elev.)
Ultimate Compression Strengths Level of Sample 1037 psi -35 ft. elev.
3673 psi -41 ft. ele'v.
3953 psi -43 ft. elev.
(continued)
.-- - . _ . . -m=-- -_yua w 7 g m yn, yecules of mic to U.5,c.5. , Menlo Park (continued)-
In contrast.to this, the inspectors were shown data in'other geology literature which indicated compressive strengths for typical granitic
. foundation rock as ranging'from 10,000 - 40,000* psi _.For example,.
theAmerican'GeologicalInstitute,DataSheet.24,glistedthefollowing values: .,
Avg. Compr'ession Strength
. . . . h Granite - slightly altered - 9400 ps'i- -
Granite - " " -
, 10,460 psi Granite - medium grain - '21_,580 psi Another reference indicated that the average ' ompressive c strength of three specimens of typical foundationiuarta! diorite taken from the Garden Valley das site, Mountain ~' Rome, Idaho, was 12,670 psi. The. samples were described as coarse grained,' massive and !
.very slightly fractured. 'Other references,- such as Physical {
Properties of Mine Rock, dated March 1949 '(R.I. 4459) . show compre- ~i salve strengths of up to '35,000 and 40,000_ psi 'for granite.
- 4. In the course of touring the laboratory . facilities o'f the U.S.G.S.
at Menlo Park, it became readily apparent co'the inspectors' that Schlocker and Bonills' appear to have available to them' considerable j,. Jl resources in trained manpower and equipment forithe" study and evaluation of the extensive. data and mineral' samples obtained during their examination of the Bodega site.- It was noted that techniques.being utilized ~in this study' included the following: I
- a. X-ray diffraction studies.
- b. Microscopic studies of thin sections -(~ 30 microns) of granitic bedrock samples, including the use of oil immersion techniques..
- c. Differential staining techniques for mineral' analysis of sawed pieces of bedrock samples.
1
- d. Statistical analyses of the distribution and orientation of all 'l faults observed and aspped in the reactor excavation, for deter-mination of the nature of the stresses.
-)
The inspectors viewed .several slides under the microscope which contained specimens of granitic rock taken from the Bodega site excavation and other regions for' comparison purposes. As pointed out by Schlocker, the fracturing of the Bodega rock was so exten-sive that it could even be discerned in-the individual crystals of l the quartz material in the rock.
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