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Category:Drawing
MONTHYEARNMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML22292A1382022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 18, Figures ML22292A0812022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 4, Figures 4.3-1 Through 4.6-9 ML22292A1022022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 6, Appendix 6D, Figures 6.2.1 Through 6C-1 ML22292A1362022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 13, Figure 13.5-1, at the Controls Main Control Room El. 306'-0 ML22292A1082022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 3, Figures 3.2-1 Thru 3C.3-3 ML22292A0772022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 8, Figures ML22292A1182022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 15, Figures ML22292A0662022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 9, Figures ML22292A1272022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 14, Figures ML22292A0932022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 10, Figures ML22292A0892022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 5, Figures ML22292A1102022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 1, Figures 1.2-33 Through End ML22292A1302022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 17, Figures ML22292A1372022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 12, Figures ML22292A1172022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 2, Figures ML22292A1012022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 2, Figures 2H.43 Through 2K-27F ML22292A1092022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 2, Figures 2K.28A Through End ML22292A0632022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 7, Figures ML22292A0922022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 11, Figures ML22292A0992022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 9, Figures 9.4-2e Thru End ML22292A0652022-10-0505 October 2022 5 to Updated Final Safety Analysis Report, Chapter 1, Figures ML18018B3202018-01-18018 January 2018 Undersized Documents - Transformer 2MTX-XM1B - Oil Cooler Piping, Failed Windings, Tank Bulging, Preparation for Removal, HV Tap Changer, and Lv Leads and Bracing ML18018B1942018-01-18018 January 2018 Undersized Documents, Drawings and Photographs ML17037C5622017-02-0606 February 2017 Plate 4-9 - Geologic Plan View of Fault Cooling Tower Piping Trench ML17037C6602017-02-0606 February 2017 Figure 5.4-3; Steam Concentration Following a LOCA with CAD Operation ML17037B4552017-02-0606 February 2017 Drawing 12177-EE-1AR-3, 600V One Line Diagram 2EHS*MCC102 Auxiliary Building North - Nine Mile Point Nuclear Station - Unit 2. ML17037C7252017-02-0606 February 2017 Drawing; Figure 7.15-1, Rod Worth Minimizer Functional Control Diagram ML17037A7102017-02-0606 February 2017 Figure 12.7-1a Radiation Zones - Reactor Building. ML17037C6592017-02-0606 February 2017 Figure 5.4-2; Hydrogen and Oxygen Concentration in Primary Containment Following a LOCA ML17037C6582017-02-0606 February 2017 Figure 5.3-2; Stand-by Gas Treatment System ML17037C5692017-02-0606 February 2017 Plate 5-10A - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-4-8 Through T-4-10 ML17037C5672017-02-0606 February 2017 Plate 5-10 - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-4-1 Through T-4-7 ML17037C5662017-02-0606 February 2017 Plate 5-9A - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-3-9 and T-3-10 ML17037C5652017-02-0606 February 2017 Plate 5-9 - Diagram Showing Relationship Between Dip of Bedding and Depth Borings T-3-1 Through T-3-8 ML17037C5642017-02-0606 February 2017 Plate 5-1 - Composite Site Stratigraphic Column ML17037C5632017-02-0606 February 2017 Plate 4-10 - Cross Section CT-2 West Wall Cooling Tower Piping Trench ML17037A8162017-02-0606 February 2017 Drawing No. 12177-ESK-4CEC25A ML17037A8182017-02-0606 February 2017 Drawing No. 12177-ESK-4CEC24 ML17037A6892017-02-0606 February 2017 Figure 12.1-1, General Arrangement Reactor Building - Plans ML17037A6902017-02-0606 February 2017 Figure 7.9 - 1A, Feedwater Control System. ML17037A6922017-02-0606 February 2017 Figure 7.6-7, Rod Block Interlocks from Neutron Monitoring System ML17037A8382017-02-0606 February 2017 Drawing - (Drawing No. Not Available) ML17037A7142017-02-0606 February 2017 Drawing No. 12241-GSK-31, Over Excavated Area - Reactor Containment - Locations. ML17037A4622017-02-0606 February 2017 Drawing 807E154TY, Revision 3, Leak Detection System Elementary Diagram. Sheet 4 ML17037A8272017-02-0606 February 2017 Drawing No. 12177-ESK-4CEC15 ML17037A7122017-02-0606 February 2017 Figure 12.7-2a, Radiation Zones-Turbine Building, Radwaste Building, and Screenwell. ML17037B4562017-02-0606 February 2017 Drawing 12177-EE-1AQ-3, 600V One Line Diagram 2EHS*MCC101 & 2EHS*MCC301 Screenwell Building - Nine Mile Point Nuclear Station - Unit 2. ML17037A6942017-02-0606 February 2017 Figure 7.4-10, Power Range Neutron Monitoring System Instrument Electrical Diagram ML17037A7052017-02-0606 February 2017 Figure 2.7-16, Screenwell Building Plan and Sections 2024-09-20
[Table view] Category:Letter
MONTHYEARNMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) 2024-09-04
[Table view] Category:Program Review
MONTHYEARML17037B9311977-05-0606 May 1977 Letter Regarding an Enclosed Progress Review of Program for Evaluation of Geologic Structural Discontinuities as of April 30, 1977 - Cooling Tower Unit ML17037B9381977-01-24024 January 1977 Letter Regarding the Safety Significance of Geologic Features and an Enclosed Evaluation of Geologic Structural Discontinuities at Nine Mile Point ML17037C4431976-07-0909 July 1976 Letter Regarding the Requalification Program for Licensed Operators and Senior Operators Submitted on June 22, 1976 and Advising That the Revised Program Meets Requirements 1977-05-06
[Table view] |
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FILE NUMOER NRC DISTRIBUTION Fon P. 50 DOCI(ET MATERIAL TO I ROM: NIAGARA MOHAWK PWR CORP. DATE OF DOCUMENT E.G. CASE SYRACUSE, N Y. 5 6/77 ~
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/LETTER QORIGINAL gf UN C LASS I F I E D SCOPY DESCRIPTION FNCLOSURE ltr. trans the following....... APPENDIX SUMMARIZING TPE WORK AND THE 'INTHRPRE-TATIONS OF. APPLICANTS INVESTICATXVE PROGRAM..
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Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Re: Nine Mile Point Unit 2 Docket No. 50-410
Dear Mr. Case:
We have previously informed members of your staff and the Office of Inspection and Enforcement of certain geologic features at our Nine Mile Point Unit 2 construction site. On April 11 and 12, 1977, we discussed additional discontinuities observed in the cooling water intake-discharge shaft and on 'April 29 and May 2, 1977 we discussed a discontinuity observed in the a drainage ditch constructed adjacent to and parallel to our walls'f east property line.
Observations of these discontinuities and comparison with other on-site features lead to the conclusion that these newly discovered features are also inactive and of no seismo-tectonic significance. These new observations are entirely consistent with the earlier interpretation of other on-site features.
Evaluation of these new observations will be considered in the context of the investigative program described in my letter of January 24, 1977. The program is expected to continue for several more months and to address the combination of geologic features noted at the site to date, including the discontinuity found in the walls of the drainage ditch.
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Mr. Edson G. Case Page Two
.U. S. Nuclear Regulatory Commission May 6, 1977 During our meeting with members of your staff on April 14, 1977, Dames and Moore provided additional information to support earlier interpretations of the cooling tower features. We have attached hereto an Appendix which summarizes to date the work and the interpretations of our investigative program. As indi-cated in the Appendix, Dames and Moore continues to interpret the evidence as supporting the position that the cooling tower fault has no seismo-tectonic significance and does not represent a hazard to the operating units at the site.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION Ge aid K. ode Vice President - ngineering
/sjz Attachment Xc: Mr. T. K. DeBoer, Director Technical Development Programs New York State Energy Office
APPENDXX Progress Review of Program for Evaluation of Geologic Struc-tural Discontinuities at Nine Mile Point as of April 30, 1977 Cooling Tower Fault Excavation -of Trenches To date a series of five trenches and an exploratroy pat have been excavated across the trace of the fault exposing the offsets in the bedrock for a distance of approximately 2500 feet (Figure 1).
Trenches No. 1 and 2 to the northwest of the cooling tower area were excavated to bedrock and the fault zone was not present at either of these locations. Pit No. 1 was excavated over the fault to bedrock. Trenches No.
3 and 4 have been excavated to bedrock and a slot approx-imately 3'x10'x8'eep has been cut into the bedrock across the fault zone at each location. Trench No. 5 has been excavated to bedrock and a similar rock slot is presently being cut.
The last significant episode of faulting appears to have occurred during the Cretaceous Period with no tectonic movements within the last 70 to 100 million years. The most recent surficial movements involving sediments have been placed"within the last 13,000 years. We believe, at the 'present time, that sufficient evidence can be obtained at the existing exploratory sites for an evaluation of the possible mechanisms of
'surficial deformation and the probability of reactivating this zone.
- 2. 'rill'ing A drilling program to explore the nature and the faulting has been in progress since orrentation of late February. To date ten NX boreholes have been drilled to an average depth of approximately 200 feet.
These holes are positioned at two separate locations and are patterned to profile the rock strata across the fault zone. Rock cores and downhole gamma ray logs are being combined to produce stratigraphic logs for each boring to aid in the detailed correlation of bed-rock units across the fault.
- 3. M~a pin Geologic mapping and structural analysis of the bedrock and overlying materials has been completed for the walls and floors of Trenches No. 3, 4, and Slots5.
The mapping in Pit No. 1 is to commence shortly.
cut into the bedrock to expose the fault in cross section have been mapped in Trenches No. 3 and 4; Similar mapping in Trench No. 5 will be performed when that rock slot is completed.
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4 ~ Samplin and Analysis Rock cores have been extracted from both the. sandstone and shale units and laboratory tested for a determination of the strength characteris-tics of these rocks.
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Trenches No. 3 and 4 and a pollen analysis has been initiated for correlation purposes and to ascertain the relative ages of deposition of the sediments over-lying the'edrock fault. Samples from the overlying peat bog have been taken and are being dated by radio-carbon methods.
Rock cores have been collected and analyzed for mineral-ogical content. Geochemical analyses have been performed on mineral crystals sampled from the fault zone. These data aid in evaluating the depth of burial, temperature of formation and age of the materials.
- 6. Geomorphology 'and Strati'aohy of Gl'acial and Post Glacial
'epos'z'ts Regional geology.c and geomorphic literature searches have been conducted. These studies investigated the possibility of similar geologic structures in the area and the relationship'of the structures at the site to the geologic history. Emphasis has been placed on the geologic history of the area for the last 15,000 years. lake and land levels for this period have been plotted and studied to evaluate the rebound characteris-tics resulting from unloading the glacial ice and water that covered the area. The possible relevance of pop-ups during this time of unloading is also under investigation.
7~ Stre'ss'ea'surement Stress conditions in the region have been evaluated and a program is underway to measure in situ stress conditions at the site. The measurement of stresses in the bedrock utilizes the overcore and the overcore/undercore techniques. One overcore borehole has been completed to a depth of 95 feet and drilling at a second location is in progress.
- 8. Sei'smi'ci'ty A review of seismic events in the region 1
tectonic events in the area and its relationship to the site.
'INTERPRETATION AND CONCLUSIONS Dames & Moore began its pre-lrmrnary rnvestrgatron of ttto cooling tower fault soon after its September 29, 1976 discovery. On December 13, 1976 a detailed geologic investigation was initiated. This inves-tigation is ongoing and is scheduled to continue for several more months. A great many of the planned tasks have been
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completed. A ma jor part of the incompleted work, as of this date, is related to the boring program. NX core borings across the fault zones are approximately 80 percent complete.
The overcore stress measurements are 15 percent complete and the surface overcore/undercore program is just getting under-way. The completion of these tasks will provide an under-standing of the in situ stress field and its relationship to past and any possible future recurrence of movement at the fault zone.
An analysis and evaluation of the evidence to date continues to support major portions of our earlier interpretation.
There appear to be three distinct movements associated with the fault zone. The first movement was the formation of the strike slip fault during the Paleozoic Era, more than 200 million years ago. This fault experienced about, 3 feet of left lateral strike-slip movement. A second movement produced the monoclinal flexuring. Analysis of minerals that coat dip slip slickensides suggest this movement. may have occurred during the Cretaceous Period, 70 to 100 million years ago. The third and last move-ment was previously judged as a pop-up along a pre-existing fault. It is characterized by smooth folding in the bedrock close to the fault zone, folded brecciated zones, bedding plane slip, and small high-angle reverse faults in the glacial and post-glacial deposits. Although these features were probably produced by the same conditions that are thought to produce pop-ups (glacial ice and lake unloading and horizontal stresses),
the rate of release is considered to be distinctly different from that commonly associated with pop-ups. We interpret this Qifference to be a slow energy release that could not produce a perceptable seismic event instead of the almost instantaneous stress release generally associated with the formation of pop-ups.
Dames a Moore continues to interpret the evidence as supporting the position that the fault has no seismo-tectonic significance to the site and we feel, at this time, that there is no reason to suggest that the fault represents a hazard to the operating units at the site.
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