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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 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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4 3-7 U. S. ATOMIC ENERGY CO MISSION REGION V DIVISION OF COMPLIANCE By: G. S. Spencer, Reactor Inspector July 24, 1963 Region V, Division of Compliance a7q
Title:
PACIFIC CAS AND ELECTRIC COMPANY - BODEGA BAY REACTOR DOCKET NO. 50-205 4
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6 '
The proposed site of the Pacific Gas and Electric Company's Bodega Bay Reactor,
- 7. Bodega, California, was visited on July 17, 1963. The purpose of the visit 4- was to accompany and observe the activities of the U. S. Geological Survey
"(1 ,
team assigned to study and evaluate the excavated areas of the site for J -
evidence of seismic faulting.
t
- A 180-ft, square by 20-ft, deep excavation around the proposed reactor center line had progressed to 5 feet above mean low water level. Examination of
[. the west and east faces of the excavation indicated that the relationship F~ between the weathered quartz diorite observed in the north face and the Lf; well-bedded clay-sand sediment in the south face was one of gradual tran-y' sition rather than a distinct demarcation due to faulting.
g 4 Abundant faults were observed in the weathered quartz diorite exposed on L the north face of the excavation from elevation +5 to the top of the face F
'l' (clevation +25). The faults had offsets from approximately 2 inches to 2 feet as revealed by the offset and displacement of pegmatite dikes and b, clay containing gouges. The age of the quartz diorite is considered to r be on the order of several millions of years in contrast to the considerably
'f younger age (tens to possibly hundreds of thousands of years) of the over-lying sediment. Examination of the overlying sediment from elevation +5 ft.
in the reactor hole area to the top of the face of the main yard excavation
-(- $
at elevation +50 ft. revealed no evidence of high angle faulting in the vicinity of the reactor hole. The sediments observed during this visit were approximately 45 feet lower than the sedimentary layers examined on a previous visit by the U. S. Geological Survey team, and which had been age dated (by Carbon-14 method) at 38,000 years.
In the opinion of the U. S. Geological Survey team, there was no evidence of nearly vertical or steep faults occurring in the past 38,000 or possibly 50,000 years. However, since the existence of low angle faults cannot be determined *mtil the reactor hole is dug deeper, the U. S.
', geologists plan to examine the e avation as it progresses down to the
-73 foot level.
8709230347 851217 I PDR FOIA FIRESTOBS-665 PDR
2 IbasMLry (continued)
Dye tests to evaluate the mixing action of the ocean in the proposed vicinity of the affluent outfall were started in March 1963. One hundred hour dye runs are conducted once a month and water samples collected at 10 different locations. Analyses of the samples are performed in PG&E's locally established laboratory.
- DETAILS f I. Scone of Visit E
[ On July 17, 1963, G. S. Spencer and R. R. Engelkan, Region V, Division
- - of Compliance, accompanied two geologists from the U. S. Geological Survey,
. Engineering Geology Branch, Menlo Park, California on a visit to the
{i ~ proposed site of the Pacific Gas and Electric Company's Bodega Bay Reactor, L,
f Eodega Bay, California. The U. S. Geological Survey team was assigned to study and evaluate the excavated areas of the site for evidence of seismic faulting. The visit included:
[ a. Observation of the activities and methods employed by the U. S.
p geologists in conducting their study.
- b. Discussion concerning the seismic and geological history as well r as. the current observations and findings relative to the seismic
{-
activity of the site with both Federal and several State geologists also present at the site.
- c. Observation of dye tests in progress at the proposed location of the effluent outfall.
- d. A visit to PG&E's locally established laboratory where the dye samples are analyzed.
e kJ Principal contacts during the visit were:
Mr. J. Schlocker - Geologist, U. S. Geological Survey Mr. M. G. Bonilla - Geologist, U. S. Geological Survey Mr. J. B. Koenig - Geologist, Calif. State Div. of Mines & Geology Mr. S. J. Rice - Geologist, Calif. State Div. of Mines & Geology Mr. F. Mautz - Chief Engineer, PG&E Mr. C. Joslin - Construction Supt., PG&E (continued)
, l b .
II. Results of Visit A. Status of Site Preparation _.
Mr. Schlocker stated that the north, west and south faces of the ;
site excavation were essentially completed, and that the floor of the ex-cavation was approximately 25 feet above mean low water level. A 180 ft.
square ho!, around the proposed reactor center line had been excavated
"~1 from the floor level (elevation +25') down to elevation +5 ft. The north, west, and east faces of the reactor hole were sloping and the south face 1 nearly vertical. Mr. Schlocker said that his objective during this visit I was to examine the exposed well-bedded sediment and weathered quarts j diorite overlying the solid granite formation more thoroughly, by having i the faces of the reactor hole excavation washed off. He explained that during L
his previous visit he had observed stratified sediment in the south face s exposure, whereas the north face had the appearance of weathered decomposed k- diorite. He said that by washing off the west and east faces of the l p_ excavation, he hoped to be able to see the relationship between the i r, materials in the north and south faces and to determine whether the j F
transition was gradual or a distinct demarcation due to faulting.
B. Examination of the Excavation Following washdown of the reactor hole excavation faces, the inspectors accompanied Messrs. Schlocker and Bonilla down to the +5 ft.
h elevation where the following observations were made, as pointed out by the U. S. geologists.
k 7"
Weathered quarts diorite was exposed from the bottom to the top of the north face of the reactor hole. At the bottom of the excavation ;
(elevation +5 ft.) it appeared 6 ft. east of the proposed center line of l
V" g" the reactor, rose to the top of the face (elevation +25 ft.) and continued
' over to the east end of the north face. Abundant faults were observed in
! the quartz diorite. The faults were marked by clay souge sones - 2 inches thick, although some appeared to be clean breaks with no gouge at all. The faults had offsets from approximately 2 inches to 2 feet as revealed by the displacement of pegmatite' dikes and the clay containing gouges Or unta-tion of the faults varied from due east-west to due north-south, dipping
_.J east and south. The weathered quarts diorite appeared to be moderately sound incompressible material, according to Schlocker. At the west half of the north face the quartz diorite graded into residual soil (green-gray sandy clay), 4 - 6 ft. thick lying of the quarts diorite. This appeared to grade into washed soil on the west end, gradually losing its weathered rock characteristics with sediment interbedded with fairly clean sand.
(continued)
~4- l Results of Visit (continued)
The south face consisted of well-bedded reddish-brown clay sand sediment. Examination of the west face of the excavation, indicated that the reddish-brown clay sand observed on the south face was interbedded with the more massive greenish-gray clay sands exposed on the north face. On the east face of the excavation, the reddish-brown clay sand from the south face appeared to be interbedded with gray material exposed at the north and of the east face. There was no evidence of faulting on the east face, acc.ording to Schlocker.
C. Tentative Findings Tentative conclusions reached by Schlocker and Bonilla following their examination of the site appeared to be as follows:
- 1. Examination of the west and east faces of the excavation indicated that the relationship between the weathered quartz diorite observed in the north face and the well-bedded clay 6and sediment in the south face, was one of gradual transition rather than a distinct debarkation due to faulting.
- 2. Examination of the overlying sediment from elevation +5
- . ft. in the reactor hole area to the top of the face of the d main yard excavation at elevation +50 ft., revealed no evidence of high angle faulting in the vicinity of the
- rasctor hole. The sediments observed during this visit y
were approximately 45 feet lower than the sedimentary layers examined on a previous visit by Schlocker and Bonilla.
A The sediments examined during the previous visit were '
' radiometrically dated (by Carbon-14 method) to be 38,000 years old.
- 3. There was no evidence of nearly vertical or steep faults occurring in the past 38,000 or possibly 50,000 years.
However, since the existence of low angle faults cannot J be determined until the reactor hole is dug deeper, Schlocker and Bonilla plan to examine the excavation as it progresses down to the -73 ft. level. The U. S. geologists also expressed the opinion that high angle faulting cannot be entirely ruled out yet until the excavation progresses deeper into older sediment. However, the older sediments will not be older than the quarte diorite.
(continued)
- . . + ,
y Results of Visit (continued)
D. Discussion With State Geolonists -
f Mr. J. B. Koenig and Mr. S. J. Rice, geologists with the California State Division of Mines and Geology, were also present at the site during the time of the visit. Judging from discussions between the Federsi and State geologists present, and independent discussions the inspectors had y , with the State geologists, there appeared to be substantial agreement between the geologists from both governmental agencies regarding their findings. ,
l E. Oceanorrschic Studies g- The inspectors accompanied Mr. Fred Mautz, Chief Engineer for E PG&E, to the proposed location of the reactor effluent discharge on the P ocean side of Bodega Head, to observe a dye test in progrees. The dye (Rhodamine B) was being pumped into the~ ocean at a point where the water b enters a cove in which the effluent outfall will be located. hr. Mautz stated that 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> runs are conducted once a month, and that the'first l
' run had been initiated during Mn ch 1963. He said that PG&E had hired several boats for the purpose of collecting water samples at 10 different ,i locations. Some of the sampling stations are located out in the ocean y area and some within Bodoga Harbor, according to Hautz. The inspectors were also shown through a laboratory which PG&E has established near the !
f-b town of Bodega, in which fluorometric analyses for dye concentration and )
r salinity tests are performed on the collected samples. A cursory exam- )
ination of the analytical data sheets indicated that fluorometric detection sensitivities in the range of 0.1 part per billion were being obtained. .
,j Also observed in the laboratory storeroom were drif t poles, which Mr. Mautz !
said were used to study the ocean currents in the vicinity of Bodega Head, g Mr. Hautz stated that in addition to the oceanographic studies, a continuing L survey of the ecology of Bodega Head, Bodega Harbor, and vicinity is a being conducted under the direction of Dr. Ernest Salo, of Humboldt State College, the Company's consultant on Oceanography and Marine Biology.
According to Mautz, these studies will be continued for a period of two years as required by the State Public Utilities Commission. Dr. Salo d was present at the site during the visit by the inspectors.
F. Construction Activities It was observed that construction activities vera confined to those described in the previous report dated March 26, 1963 and that these activities were consistent with provisions of 10 CFR 50.10(b).
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