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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
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EBASCO SERVICES INC0RPQRATED UTILITY CONSULTANTS - E N GINE E R S - CONSTRUCTORS TWO RECTOR STREET NEW YO RK, N.Y.10006 c .oo.. .. . ...co.-
, November 12, 1979 TO: Bob Benedict FROM: J Costello/R Prados
SUBJECT:
WATERFORD SES UNIT NO. 3 REPLY TO NRC CONCERN OVER THE EFFECT OF CLOUD EXPANSION UPON BUILNING Attached herein is a report addressing the concerns raised by Jack Reed of the Accident Analysis Branch in a telephone conversation with R Iotti of Ebasco. If you have any questions pertaining to the enclosed material please contact us.
JC:RP:ku cc: R Iotti J Reed
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1343 191 7911190 3 74-
REPLY TO NRC CONCERN OVER THE EFFECT OF CLOUD EXPANSION UPON BURNING In order to best address the concern raised, it is necessary to examine the modes in which the cloud can ignite and explode.
A vapor cloud of flammable concentration may burn (deflagrate) or detonate (if within the detonable limits) or both types of combustion may occur in case of transition from deflagration to detonatic.i. Volumetric explosions may also occur, particularly, if partial confinement of the cloud exists.
More likely pockets of gas in a cloud may explode volumetrically if heated to the autoignition limit by radiated heat or shock waves.
In general, therefore, one should consider deflagration, detonation, and volumetric explosion to be the comon modes of combustion. In our case due to the unconfined nature of the cloud the latter mode cannot occur, and it is only necessary to address detonations and deflagrations.
For detonations all of the thermodynamic properties, detonation velocities and flow properties behind the detonation front are calculable from standard thermodynamic equilibrium calculations.
If one defines as Uyand U2the velocity of the unburned gas and burned gas with respect to the stationary detonation wave, then with respect to a stationary observer, Uy is the detonation velocity and W= Uy-U2 is the velocity of the gas behind the detonation wave front.
Further the thermodynamic states behind the detonation front are described by the Hugoniot equation.
DE= E -E ={(p2 P 1) (# ~V 2 1 2) (1) wherein, p and v are the pressure and specific volume and E the energy and 1 and 2 denote the unburned and burned states respectively.
1343 192
2-The actual detonation involves a passage through a family of Hugoniot curves.
These proceed from the curve corresponding to no chemical reaction, AE= E2 -E -= C (T2-T) g is the average specific heat at constant volume between temperaturesy T and2T before and after the passage of the wave front) to the curve corresponding to complete chemical reactor in which case E -E 2 = g (T2 -T)-AE ,
irherein AE is the energy released in the combustion process.
Figure 1 shows both Hugoniot curves. The Hugoniot curve for the complete reaction is distinguished by two branches. The branch from A to V is the
" detonation" branch and the one from B to C is the " deflagration" branch.
It has been shown that the only possible stable detonation is the detonation proceeding at the minimum detonation velocity (see reference 1). This is the Chapman-Jouguet detonation and the resulting detonation overpressure can be found by running a tangent line to the detonation branch from the original condition. The resulting C-J overpressure for stoichiometric propane air mixture has been determined to be p2/P 1 = 17.8 from an initial state of 14.7 psi and 460 F.
That value is closely correspondent to that reported by J. H. Lee and others (reference 2 and 3). Point A corresponds to the overpressure resulting from an adiabatic constant volume explosion. The value obtained of P /P =8.7 differs 2 i slightly from that quoted in various references including reference 2, which reports 8.34. The difference is due essentially to the initial state assumed for these calculations which was O C, whereas others generally used 25 C.
Reference 1- Courant & Fredericks " Supersonic Flow and Shock Waves" Interscience Publishers, New York, N. Y.
Reference 2- J. H. Lee, at al " Blast Effects from Vapor Cloud Explosions" McGill University, Montreal, Canada 1343 193
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W The intersection of the tangent line with the Hugoniot curve for no reaction is the Von Neumann spike which precedes the C-J detonation pressure. Its computed value is approximately p2/Py =28, again in close agreement with values reported in the literature.
The detonation velocity which is given by U=Dv y p2-P i v y-v 2
is computed to be D= 5330 fps or 1610 mps, which is in reasonable agreement with literature data.
In the detonation branch the flow velocity of burned gas , W, is in the same direction as the detonation wave. In fact it can be shown that (reference 3)
D= W + C where C is the velocity of sound in the burned medium.
Since the detonation wave travels supersonically with respect to the un-burned medium, no disturbance precedes it, hence the cloud size remains at its initial size as the detonation propagates, i.e. the gas expansion occurs afterwards and has the effect of a rarefaction wave which tries to overtake the detonation wave at sonic velocity in the burned medium. This observation has been made by others (reference 2, page 12). Further discussion of the subsequent expansion is given later on.
Thus the effects of the detonation blast of the wave of the propane gas clouds has already been properly addressed in the FSAR sect 2.2.3.
Reference 3- Lewis & Von Elbe " Combustion Flames and Explosions of Gases" Academic Press, New York, N. Y.
1343 195
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4 The portion of the curve between A and B corresponds to no real physical state. The portion of the Hugoniot curve between B and C represents a decrease in pressure and increase in volume, corresponding to a rarefaction.
The burned gas flow velocity W therefore is always negative, i.e. the burned gas no longer moves in the same direction as the wave, but away from it.
The consequence of this is that in this deflagrative process a pre-com-pression wave is sent out into the explosive mixture to push that unburned gas with a velocity just sufficient to ensure that tha gas may come to rest when it is swept over and burned-by the deflagration front.
Physically no deflagration occurs past the point C (reference 1) which is known as a Chapman-Jouguet deflagration point. In fact weak deflagrations (essentially constant pressure explosions) are those to be considered for vapor clouds explosions, and are the ones that have been observed in experiments.
Whereas the C-J detonation velocity represents the minimum of all detonation velocities, the C-J deflagration velocity is in fact the largest possible deflagration velocity which is calculable from eqn (3).
For the propane-air mixture studied (stoichiometric) the C-J deflagration velocity was computed to be 168 fps.
For weak detonations however the deflagration velocity is the same as the laminar burning velocity 1.5-2.0 fps, hence a thousand times less than detonation velocities.
However the spatial deflagration velocity, which would be that seen by a stationary observer,.is higher than the deflagration velocity computed by egn. (3). This ic Jae to the displacement of the unburned gases ahead of the propagating flame caused by the specific vo? .me increase across the flame front. Since this increase is about eight fold,the spatial defla-gration velocity is roughly eight times that computed by eqn (3).
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Hence for a C-J deflagration, spatial velocities of the order of 1300-1400 fps could occur. In actual tests however (reference 5 and 6) the spatial flame velocity has been measured to be of the order of 30-l<0 fps. for
, mixtures difficult to detonate (like propane-air) and ten times larger for mixtures rivs in oxygen.
The effect of oxygen richness is not surprising since lack of inerts such as nitrogen has the effect of raising the Hugoniot curve for complete reaction to higher values. For instance the C-J detonation point for a stoichiometric propane oxygen mixture would correspond ta overpressure almost exactly double that occurring for the detonation of propane-air mixtures, with detonation velocities thirty percent higher. Similarly the C-J deflagration velocities for oxygen rich mixtures is expected to be higher than that for propane-air mixtures.
Hence C-J deflagrations of any kind exhibit velocities in excess of 1300 fps.
The fact that no such spatial burning velocity has been observed confirms that C-J deflagrations do not occur, but that only weak deflagrations, i.e.
basically constant pressure burning, occur.
For these kinds of deflagrations, the precompression sent into the unburned medium and surrounding air is in the nature of basically an acoustic wave, which does not steepen into an air shock unless spatial flame velocities of 300 fps or more are achieved, as shown in the attached figure taken from reference 1.
Reference 6- NUREG/CR -0075 " Accidental Vapor Phase Explosions on Transportation Routes Near Nuclear Power Plants", April 1977.
Reference 5- Lind, C. D. and R. A. Strehlew, 4th, International Symposium on Transport of Hazardous Cargoes by Sea and Inland Water-vays, Jacks 9nville, Florida (1975) 1343 197
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Likewise there is no overpressure of great significance within the defla-grating cloud. For typical spatial burning velocities of 30 fps or less, overpressures of about 1 psi vill occur just ahead of the flame front.
Hence it is concluded that blast damages are insignificant for deflagrative
. burning of propane air clouds either near or far from the cloud. Hence for a deflagration the possible damage is limited to temperature.
In a detonationevent after pasrege of the initial detonation blast, the com-pressed products expand. Under the assumption that this expansion is isentropic, the final volume will be approximately 9.7 times initial volume (assuming K= 1.25),(for an oxygen rich detonation these rates would be more than double). This expansion in turn can generate a second shode in the air ahead of the expanding products of the detonation, which follows the initial shock caused by the hydrodynamic coupling of the detonation wave and the air.
This second shock is one order of magnitude smaller than the first air shock (see reference 7) and exhibits the same decay with distance from the center of detonation as the first and much stronger shock.
Since the Waterford plant has been shown to withstand the first shock over-pressures, it is also safe against the weaker second shock caused by the expanding detonation products.
During the preceding it has been tacitly assumed that the flammabic cloud is entirely formed of a stoichiometric mixture of propane and air (or oxygen).
This was of course the case for all experiments conducted (see references 2,3,6,7). In fact the computed propane air clouds as shown in figures 2.2-8 and 2.2-9 exhibit a range of mixtures which are only stoichiometric in a region which at ground level is centered from 1300 ft to 3500 ft from the origin of the cloud. At closer distances to the origin of the cloud ground level concentrations are overrich, farther away they are leaner than stoichiometric 1343 199
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Since the propane plume downwind of the 1000 ft /see source is shown to present the greatest hazard to the plant, Figure 2.2-9 has been modified to reficct the larger span of mixture concentrations within which a defla-gration can occur. Whereas the detonable limits for propane air mixtures are 7.0 and 2.8 percent by volume of propane, the limits of deflagrations are 9.5 and 2.2 percent.
In addition an overconservatism was discovered in the values of ay and a y used in assembling the information of Figure 2.2-9. Smaller values of
'y has been used than published in the literature for distances downwind exceeding 2500 ft.
With the corrected Table 2.2-21 and Figure 2.2-9, the lower limits of flam-mability and detonability are reached at 5020 and 4298 ft respectively.
Similarly the upper and lower detonability limits are reached at 2178 ft and 2575 ft from the break.
The volume of fla=mabic nixture contained within the vapor cloud is computed 7 3 to be 1.95 x 107 ft ,3 whereas the detonable volume is only 1.15 x 10 ft .
Hence 407. of the total flammable volume has concentrations below 2.87., or below 0.67 times the stoichiometric concentration of 4.127..
The expansion of a mixture of less than 677. stoichiometric concentration (as well as that of concentrations above 120-130% of stoichiometric mixtures is at least 307. less than the expansion of stoichiometric mixtures. This results basically from the icwar flame temperature. The expansion given in Figure 1 at point B is thus applicable only to stoichiometric concen-trations. Therefore the final volume of the deflagrated vapor cloud can be conservatively estimated by expanding the volume of 2.8% or larger propane concentration to a final volume 8 times larger, and the volume of lower concentration to a volume 5.5 times larger. The resultant final volume 8 3 would be 1.35 x 10 ft ,
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Assuming that the original cloud can be represented as a hemi-cilipsoid of 4564 ft, 143 ft, and 28.6 ft dimensions in the downwind, crossvind and vertical direction, centered at 2734 ft from the break, and that the deflagration is either centered at that point or the final dLmension of the product cloud downward will be 6717 ft from the break.
The closest distance from the 8" pipeline to a safety structure in Waterford 3 is 7350 ft. Hence it is concluded that the deflagration of the " worst" cloud ensuing from a catastrophic break in such line poses no hazard to the plant.
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