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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999 Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217N2111999-10-19019 October 1999 Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings ML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls ML20217C6251999-10-0505 October 1999 Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives ML20212J6921999-09-29029 September 1999 Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified ML20216G2441999-09-27027 September 1999 Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form IR 05000382/19993011999-09-21021 September 1999 Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14 ML20212D8761999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C5881999-09-14014 September 1999 Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted ML20211Q4421999-09-0909 September 1999 Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld ML20211K9741999-09-0101 September 1999 Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211G5751999-08-27027 August 1999 Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4 ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F4611999-08-24024 August 1999 Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements ML20211G1731999-08-23023 August 1999 Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210T9791999-08-18018 August 1999 Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator ML20210R9231999-08-11011 August 1999 Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20210D8701999-07-23023 July 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3 ML20210B1521999-07-15015 July 1999 Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 IR 05000382/19990081999-07-12012 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503 ML20209E5231999-07-0909 July 1999 Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode 1999-09-09
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20006D5481989-10-20020 October 1989 Discusses Insp of Ebasco Procurement Activities at Facility. Involved Ebasco Personnel Will Be Trained on Requirements Prior to Initiation of Any New safety-related Purchase Orders as Required by Quality Program Manual ML20245K5951989-06-19019 June 1989 Discusses Nonconformances Noted Re 35 Purchase Orders Placed W/Gismo Co Prior to June 1980 W/O Supplier on Approved List. Ebasco Maintains High Confidence Level That Procurement of Subj Matl Does Not Represent Safety Consideration ML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20236U5221987-10-19019 October 1987 FOIA Request for LERs for Listed Plants,Including All Attachments & Encls from Original Documents ML20235L7971987-06-25025 June 1987 Forwards Final EGG-NTA-7668, Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components:Waterford 3, Informal Rept. Licensee Should Describe Interface Program W/Nsss Vendor ML20214Q9141987-04-21021 April 1987 Forwards EGG-NTA-7446, Conformance to Generic Ltr 83-28, Item 2.2.1 - Equipment Classification for All Other Safety- Related Components:Waterford-3 ML20214R1361987-03-26026 March 1987 Forwards Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Maine Yankee, St Lucie 1 &-2 & Waterford 3, Final Rept.Plants Conform to Generic Ltr ML20235P2631985-06-0505 June 1985 Informs That Retyped Version of 850530 Appeal Board Hearing Delivered to Appeal Board.Original Transcripts Rejected Due to Typeface on Printer ML20095A1921984-08-15015 August 1984 Forwards NUS Project Plan for Prelicensing Issues Task Force Support Group ML20094J6311984-08-0909 August 1984 Forwards Resumes for NUS Personnel Involved W/Preliminary Issues Task Force Support Group.Inspector & Auditor Certificates Also Encl ML20101E2841984-06-15015 June 1984 FOIA Request That Exercise Repts for Waterford 3 & Comanche Peak Re Emergency Preparedness Exercises Held in 1983 & 1984 Be Placed in PDR ML20128G8731984-05-0707 May 1984 Forwards Evaluation of Concrete in Basemat,Waterford Unit Number 3, Based on Observation of Record During 840430-0504 ML20112H8101984-04-0505 April 1984 FOIA Request for Repts Resulting from Listed Environ Qualification of Equipment Site Audits to Be Placed in Pdr. Access to Any Repts Resulting from Audits Held Since Oct 1982 Also Requested ML20076E1411983-08-17017 August 1983 Responds to NRC Inquiry Re Classification of Stresses by C-E in Potential Finding Rept 2448-011.Misclassification of Stresses Is Isolated Case,Based on Specific Method.No Generic Problem Indicated ML20072K8951983-03-29029 March 1983 Forwards Util Transmitting Vols 1-3, Independent Design Review of Waterford Steam Electric Station Unit 3 Emergency Feedwater Sys.Sys Design Adequate ML20039C6751981-08-17017 August 1981 Forwards Revised FSAR Subsection 2.4.2.3 Re Effects of Local Intense Precipitation to Assist in Review.Flood Study of Cooling Towers & Potential for Blockage of Reactor Bldg Roof Drains as Suppl Info Also Encl ML20009H2731981-08-0606 August 1981 Forwards Revised Sections & Table of Contents Discussed in NRC 810610 Ltr for ETR-1001,Ebasco Nuclear QA Program Manual.Revisions,Which Are Dtd 810731 Will Be Included in Change 10 to ETR-1001 ML19254F8991979-11-12012 November 1979 Forwards Reply to Concern Re Effect of Cloud Expansion Upon Burning.Deflagration of Worst Cloud Ensuing from Catastrophic Break in Pipelines Poses No Hazard to Plant ML19209C8771979-10-12012 October 1979 Responds to 791011 Telcon.Forwards AP Van Ulden Article, Loss Prevention & Safety Promotion in Process Industries. Article Used in FSAR to Determine Area of Fluid Flowing Under Force of Gravity ML19208D1881979-09-24024 September 1979 Forwards Updated Electrical Instrumentation & Control Drawings Noted in FSAR Table 1.7-1.Drawings Available in Central Files ML19208B7581979-09-19019 September 1979 Forwards Errata Sheet for Environ Rept,Amend 1 ML20204B9521978-11-0909 November 1978 Ack Receipt of 781005 NRC Ltr Accepting Recently Proposed Rev to Topical Rept ETR-1001,Ebasco Quality Assurance. Manual.Forwards Rev Pages Which Will Affect Subj Facils 1989-06-19
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 05000382/LER-1999-005, Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits1999-06-24024 June 1999 Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits ML20196G5731999-06-24024 June 1999 Forwards Operator Licensing Exam Outlines Associated with Exam Scheduled for Wk of 991004.Exam Development Is Being Performed in Accordance with NUREG-1021,Rev 8 ML20212J4121999-06-23023 June 1999 Responds to NRC Re Reconsideration of EA 98-022. Details Provided on Actions Util Has Taken or Plans to Take to Address NRC Concerns with Ability to Demonstrate Adequate Flow Availability to Meet Design Requirements ML20196E9371999-06-22022 June 1999 Forwards Revs Made to EP Training Procedures.Procedures NTC-217 & NTC-217 Have Been Deleted.Procedure NTP-203 Was Revised to Combine Requirement Previously Included in Procedures NRC-216 & NTC-217 ML20196A1021999-06-17017 June 1999 Provides Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Per 990513 Request of NRC Project Manager ML20195F3671999-06-0909 June 1999 Forwards Rev 21,Change 0 to EP-001-010, Unusual Event. Rev Reviewed in Accordance with 10CFR50.54(q) Requirements & Determined Not to Decrease Effectiveness of Emergency Plan ML20195C7801999-06-0303 June 1999 Submits Response to Violations Noted in Insp Rept 50-382/99-08.Corrective Actions:All Licensee Access Authorization Personnel Were Retrained Prior to Completion of Insp ML20195C2951999-05-28028 May 1999 Forwards Annual Evaluation of Changes & Errors Identified in Abb CE ECCS Performance Evaluation Models Used for LOCA Analyses.Results of Annual Evaluation for CY98 Detailed in Attached Rept,Based Upon Suppl 10 to Abb CE Rept ML20195C0241999-05-28028 May 1999 Notifies NRC of Operator Medical Condition for Waterford 3 Opertaor Sp Wolfe,License SOP-43723.Attached NRC Form & Memo Contain Info Concerning Condition.Without Encls ML20196L3281999-05-24024 May 1999 Informs That Entergy Is Withdrawing TS Change Request NPF-38-205 Re TS 3.3.3.7.1, Chlorine Detection Sys & TS 3.3.3.7.3, Broad Range Gas Detection Submitted on 980629 ML20206S4691999-05-17017 May 1999 Requests Waiver of Exam for SRO Licenses for an Vest & Hj Lewis,Iaw 10CFR55.47.Both Individuals Have Held Licenses at Plant within Past Two Year Period,But Licenses Expired Upon Leaving Util Employment.Encl Withheld 05000382/LER-1999-004, Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.31999-05-14014 May 1999 Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.3 ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J1471999-05-0606 May 1999 Requests That Implementation Date for TS Change Request NPF-38-211 Be within 90 Days of Approval to Allow for Installation of New Monitoring Sys for Broad Range Gas Detection Sys ML20206J1721999-05-0606 May 1999 Notifies That Proposed Schedule for Plant 1999 Annual Exercise Is Wk of 991013.Exercise Objective Meeting Scheduled for 990513 at St John Baptist Parish Emergency Operations Ctr ML20206G8021999-05-0404 May 1999 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-382/99-01.Licensee Denies Violation as Stated.Change Made Is Denoted by Rev Bar & Does Not Materially Impact Original Ltr ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20205T2531999-04-22022 April 1999 Forwards LER 99-S02-00,describing Occurrence of Contract Employee Inappropriately Being Granted Unescorted Access to Plant Protected Area ML20205R2611999-04-20020 April 1999 Forwards Rev 19 to Physical Security Plan,Submitted in Accordance with 10CFR50.54(p).Plan Rev Was Approved & Implemented on 990407.Rev Withheld,Per 10CFR73.21 ML20205Q3241999-04-16016 April 1999 Submits Addl Info Re TS Change Request NPF-38-215 for Administrative Controls TS Changes.Appropriate Pages from New Entergy Common QA Program Manual Provided as Attachment to Ltr 1999-09-07
[Table view] |
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. EBASCO SERVICES INCORPORATED EKO Two World Trade Center. New York. N Y 10048 f/
August 17, 1981 L-LOU-81-220 TO: R Gonzales (NRC)
FROM: W Wittich
SUBJECT:
LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT NO 3 LOCAL INTENSE PRECIPITATION Please find attached a copy of revised Subsection 2.4.2.3 Effects of Local Intense Precipitation to assist you in your review. Also attached are Flood Study of Cooling Towers and Potential for Blockage of Reactor Building Roof Drains as supplementary information.
If I can be of assistance, please call me (212) 839-3804.
C W:eco \ g, Attachments '/
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J J Castello 2 Og 7 J K To=. peck g- 4,7 4 Og -
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" $*'8 G Hofer \A "ON D Palmer O- i N M P Horrell IA5 R Vidal R M Foley R Prados (LPL)
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Daybook E Olizon (C.2.4.2)
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2.4.2.3 Effects of Local Intense Precipitation 2.4.2.3.1 Design Criteria for Probable Maximum Precipitation (PMP)
The probable maximum precipitation (PMP) is calculated by a method which uses a combination of a physical model and several estimated neteorological parameters to yield the theoretically greatest depth of precipitation for a given duration which is physically possible over a particular area. The value is estimated by maximizing all the physical parameters responsible for extreme precipitation in previously observed heavy storms and transposing the storm orientations and trajectories to produce the greatest possible precipitation over the area of concern. Consequently, the calculated PMP is a hypothetical indication of the extreme upper limit of precipitation events.
As deternined from Reference 16, the 10 square mile PMP d.pths for 6, 12 and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are 30.7, 34.6 and 39.4 inches respectively. The one hour rain fall increments in the critical six hour period were then arranged according to the criteria in Reference 17 such that 10 percent of the six-hour value occurred in the first hour, 12 percent in the second hour, 15 percent in the third hour, 38 percent in the fourth hour, 14 percent in the fifth hour, and 11 percent in the sixth hour.
2.4.2.3.2 Effects of PMP on the Plant Site The plant site is located such that runoff produced flooding from local intense precipitation will not affect the safety of Waterford-3. The site is drained externally by drainage ditches around the plant. The exterior walls of the plant are flood protected up to El +30 f t MSL (12.5' to 15.5' above grade) which is far above any ponding that could be expected due to a severe rainfall up to and including the PMP and assuming blocked culverts.
2.4.2.3.3 Effects of PMP on Roofs of Structures (Refer to Figure 2.4-8 Roof Drainage)
- a. Fuel Handling Building The Fuel Handling Building is provided with six 4 inch roof drains which exceeds the normal code design requirements by 100%. Assuming one-third of the roof drains are blocked, the remaining functional drains and storage capacity of the roof can accommodate the PMP for its duration.
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- b. Reactor Auxiliary Building The Reactor Auxiliary Building is provided with six 4 inch,
, four 5 inch, and two 6 inch roof drains which exceeds the normal code design requirements by 100%. Assuming one-third of the drainage capacity is blocked, the remaining functional drains and storage capacity of the roofs can accommodate the PMP for its duration.
- c. Reactor Building The Reactor Building dome and its surrounding walk-way is provided with'3 six inch roof drains which exceed the normal code requirements by 50%. The parapet surrounding the walk-way rises to a height of 21 inches. An analysis revealed that clogging of the drains was . improbable, but a 33% blockage was considered to be conservative. Assuming t one-third of the walk-way roof drains are blocked, the remaining functional drains and storage capacity of the walk-way can accommodate the PMP with the exception of the 4th hour. A portion of the water will spill on to the 1 Reactor Auxiliary Building roof and a portion of the water
} will spill into each of the Cooling Tower "A" and "B" areas. The contribution to each Cooling Tower area is presented in Table 2.4-6a.
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- d. Cooling Tower Areas "A" and "B" i '
! Both Cooling Tower areas were considered as being one large I roof with regard to rain water contribution from open areas, projected wall areas .(50% of external walls and 100% of internal walls), wet cooling tower overflow, and partial spill-over from the Reactor Building parapet. The water I
storage capability of the Cooling Tower areas took into account the open areas less the internal walls and wet cooling tower basins. The lowest elevation of the Fuel Handling Building (EL-35MSL) was also considered as water storage capability for the Cooling Tower areas with equalization of water level between the two areas'cccurring
! through exit doors located on each side of the structure.
- There is no safety related equipment on this elevation of the Fuel Handling Building that would be effected by this
Each dry cooling tower cell and open area adjacent to the '
cells are provided with area drains. The wet cooling towers are provided with overflows at their high water
. level elevations, which spill onto the open areas adjacent to them. .All area drains in each Cooling. Tower area are
~ interconnected by a network of drainage piping which terminates at the area drain sump no. 1 for Cooling Tower i ~ area "A" and area drain sump no. 2 for Cooling Tower area i "B". Each drain area sump is provided with a set of r
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duplex sump pumps at a capacity of 325 gpm per pump.
Loss of offsite power coincident with the PMP storm was considered and provisions were made to power the sump pumps from the emergency diesel generators via a manual switch. The sump pumps have also been designed for seismic considerations (Refer to Table 3.2-1).
Assuming one sump pump in each cooling tower is out of service and the remaining sump pump in each cooling towet area is not operating for the first half-hour of :he PMP, a resulting build-up of 1.60 feet of water after six hours occur evenly over.the available water-storage area. This' buildup for the critical six hour
, duration of the PMP is presented in Table 2.4-6.
The safety related equipment in cooling tower areas "A" and "B" are Motor Control Centers 3A315-S and 3B315-S, and Transformers A and B. The maximum height to which rainwater can rise before flooding of essential portions of this equipment can occur is 1.71'. Therefore, local intense rainfall on the Cooling Tower areas up to and including the PMP, will not result in the flooding of safety related equipment.
To further preclude the possibility of flooding the MCCs and the transformers, openings' are provided for their respective dry cooling tower cubicles. These openings wi11 drain water from the cubicle in the event of localized drain clogging in the dry cooling tower cells. These openings will prevent water from rising above the critical 1.71'.
2.4.2.3.4 Effects of Ice Accumulation on Site Facilities Ice Accumulation effects at the Waterford-3 site are considered to be negligible because of the climate of the region as discussed in Section 2.3. Therefore, ice induced flooding and structural damage is not considered as design bases.
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TABLE 2.4-6a PMP STORM WATER CONTRIBUTION TO COOLING TOWER AREAS FROM REACTOR BUILDING DOME 4
EMP PMP DEPTH CODE DESIGN REACTOR BUILDING DRAINACE PARAPETi. 60% CONTR 50% CONTR 50% CONTR HOUR '
44/i:R IN/liR (2) ROOF AREA-FT2 EXCEEDANCE . STORAGE TO TOWER AREAS "A" TO T0JER "B" 1 FT3 FT3 FT (1) 3 k . TO FTTokt:'R 3 (I) %FT 3 (') 't'
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e TABLE 2.4-6 r
PMP RUNOFF ACCW LATION IN COOLING TOWER AREAS
- s PMP PMP DEPTH OPEN AREA REACTOR BUILDING ROOF CUMULATIVE WATERPUgPED INCREASE OF TOTAL TOTAL HOUR INCHES CogTRIBUTION' CONTRIBUTION TOTAL CON- OUT - FT STgRAGE- STORACE ACCUML* LATED
_ FT (1)(3) 3 FT (2) TRIBUTION-FT 3 FT WATER-FT3 WATER-FT(4) i 1/2 1.54 lJ E 7 'L2 A '4 3132 ' O 3132 0 3132 3132 .14 i P 1 1.54 3132 0 3132 2608 524 3656 .16 2 3.69 '
7504 0 7504 5214 2290 5946 .26 3 4.61 9375 0 9375 5214 4161 10107 44 4 11.67 23731 3262 26993 5214 21779 31886 1.38 5 4.30 t 8744 0 8744 -
5214 3530 35416 1.53 6 3.38 6873 0 6873 5214 1659 37075 1.60 7 1,48 3010 0 3010 5214 -2204 34871 1.51 (1) See Figure 2.4-8 (2) See Figurd 2.4-6a 7~ I(- h,,','{f[,;$ M },M 1,u-(A (3) Cooling Tower Area "A" - 11958 ft 2 Cooling Tower Area "B" - 12444 ft ~QQ f
(4) Cooling Tower Area "A" - 9300 ft2 of storage area Cooling Tower Area "B" - 8259 ft2 of storage area Fuel Handling Building - 5572 ft2 of storage area
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e POTENTIAL FOR BLOCKAGE OF REACTOR BUILDING ROOF DRAINS An evaluation of the actual potential for the Reactor ouilding roof drains to partially or completely block, resulting in uncontrolled overflow of storm water, should consider two factors. First is the potential for a suf ficient amount of wind blown leaves to reach the roof, accnmulate, and block one or more of the drains. Secondly, an analysis is needed of the likelihood of drain clogging from nests constructed on the roof by birds known to occur in the area.
A comparison of the-6-hour probable maximum precipitation (PMP) (refer to revised Subsection 2.4.2.3 of the FSAR) for the Waterford-3 site with other extreme rainfall estimates and observations will reveal the conservatism contained in the roof drain design criteria. The 6-hour PMP is 30.7 inches, while the greatest observed 6-hour precipitation, as well as the precipitation with a calculated 100 year return period, are both only between 8 and 9 inches. Thus the 6-hour PMP is more than a factor of 3 greater than any 6-hour rainfall event which has been observed or can reasonably be expected to occur at the c
Waterford-3 site. Substantial drain clogging, occurring concurrently with a precipitation event exceeding those known or likely to be expected, would be required to tax the roof drain capacity.
Drain clogging from leaf litter cannot be considered as likely to occur under reasonably expected conditions. The nearest stand of trees to the Reactor Building is a thin band of riparian hardwoods , approximately 500 feet to the northeast. Larger wooded tracts occur approximately 1400 feet to the northwes t, 3000 feet to the northeast, and more than a mile to the southwest. Other than the riparian hardwoods, the area within 1600 feet of the Reactor Building is devoid of trees. Average leaf canopy height in any of the wooded tracts is not likely to be more s than 65 feet. The height of the Reactor Building roof is therefore almost 3 times the leaf canopy height. Leaf senescecce commences in late October to early November, and extends throughout the winter. In this area, there is no sudden advent of leaf fall, such as occurs in most northern states, and consequently no rapid seasonal accumulation of leaf s
litter on the ground. Given the scarcity of trees in the immediate vicinity of the Containment Building and its considerable elevation above
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the leaf canopy, as well as the extended period of leaf fall and slower litter accumulation, it is very unlikely that leaf transport to the building roof could occur under reasonably foreseeable conditions.
When evaluating the potential for drain blockage by birds nests, it should be noted that relatively few species of birds will attempt to nest on man made structures. In addition, species which typically nest in crevices, holes, or on vertical walls (ie, rock doves, starlings, house sparrows, chimney swifts, barn swallows and cliff swallows) would not utilize the Containment Building roof because of its size and configuration. Species which are known to nest on rooftops (ie, 4 c rn 5 <
least-turns, killdeer, and nighthawks) prefer flat, bare s2rfaces, but build no nest and so pose no threat to drain blockage. Also these species are unlikely to nest on top of a building the height of the Reactor Building or on its domed roof. Finally, the configuration of the roof drains make it extremely unlikely any species of bird will attempt to nest in the drains.
Therefore, for these reasons, it must be concluded that clogging of the roof drains is extremely unlikely.
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